Documente online.
Username / Parola inexistente
  Zona de administrare documente. Fisierele tale  
Am uitat parola x Creaza cont nou
  Home Exploreaza
Upload




























POLITICI SI PRINCIPII DE OPERARE

Stiinte politice






PROCEDURA NR\

PROCEDURE NO:      82-01364-RD-L01







TITLU:           POLITICI sI PRINCIPII DE OPERARE

title:           OPERATING POLICIES AND PRINCIPLES






NUME

NAME


SEMNĂTURA

SIGNATURE


TITLU

TITLE


DATA

DATE

ELABORAT DE

PREPARED BY


R. Pageau



Safety and Licensing Manager



VERIFICAT DE

VERIFIED BY


D.M. Zaharia



Safety & Licensing

Deputy Manager




REVIZUIT DE

REVIEWED BY


J. McConnel




Comm. Execution Manager



VERIFICAT DE

VERIFIED BY


A. Mihai



Operating Senior Superintendant




REVIZUIT DE

REVIEWED BY


K. Verma



Comm. Tech. Support Manager



E. Moldoveanu




Comm. Tech. Senior Superintendent



VERIFICAT DE

VERIFIED BY


J. Thomson


Commissioning Operation General Manager



VERIFICAT AQ

VERIFIED QA


D. Balla-Boudreau



Quality Assurance Manager




APROBAT DE

APPROVED BY


I. Bucur



CNE Cernavoda Director








AVIZAT DE

ACCEPTED BY


T. Chirica



SNN Director




APROBAT DE CNCAN

APPROVED BY CNCAN


Dr. Ing. L. Biro




CNCAN Director





REVIZIA

REVISION


DATA

DATE


DESCRIEREA MODIFICĂRII

DESCRIPTION OF MODIFICATION





June, 2005


First issue for Unit 2/ Prima emitere pentru Unitatea 2




CERNAVODA NPP UNIT 2







TITLE:           OPERATING POLICIES AND PRINCIPLES


TITLU:           POLITICI SI PRINCIPII DE OPERARE



CONTENTS


BACKGROUND

PURPOSE

SCOPE

REFERENCES

RESPONSIBILITIES

DEFINITIONS


GENERAL: ORGANIZATION


Operating License Issued by CNCAN

Authorization of Operating Personnel

Delegation of Authority of Station Manager

Authority of Shift Supervisor

Station to be Adequately Staffed


Observance of National Regulations

Quality Assurance Program

Changes of Operating Policies and Principles



GENERAL: OPERATING SUBJECTS


Conditions Which Conflict With Operating Policies and Principles

Station Procedure Compliance

Authorization for Maintenance

Radiation Protection

Control of Radioactive Material

Gaseous and Liquid Emissions

Overpressure Protection

Chemistry Control

CNCAN Notification


GENERAL: REACTOR SAFETY OPERATING SUBJECTS


Modifications

Unavailability of Special Safety Systems


Maintenance

Safe State for Safety Related System Components

Frequency of Test on Systems

Independence of Channels and Systems




GENERAL: REPORTING


Reporting Modifications to CNCAN

Reporting of Incidents

Annual Report to CNCAN

Operating Records


SITE


Exclusion Area

Contingency Plans

Security


BUILDING & STRUCTURES


Containment System Availability

Containment System Leakage

Containment Testing

Reactor Building Access Control

Breaches of Containment


REACTOR, BOILERS & AUXILIARIES: GENERAL


Power Limits

Reactivity Control

Reactor State

Approach to Critical


REACTOR, BOILERS AND AUXILIARIES: MODERATOR


Moderator System

Cover Gas Deuterium Concentration

Moderator Purification

Moderator as the ultimate Heat Sink


REACTOR, BOILERS & AUXILIARIES: HEAT TRANSPORT



Primary Coolant

Heat Sink Availability

Failed Fuel Detection

Primary Heat Transport System

D2O Storage Tank Inventory

Heat Transport System Leakage

Heat Transport Iodine Limit



REACTOR, BOILER AND AUXILIARIES: AUXILIARIES


End Shield Cooling System

ECC System Availability


ECCS Testing

Annulus Gas System

Shutdown Cooling System

Liquid Zone Control System


REACTOR, BOILER AND AUXILIARIES: FUEL HANDLING



Fuelling Machines

Cooling and Shielding of Irradiated Fuel

Irradiated Fuel Storage Capacity


Reactor State During Fuelling



REACTOR, BOILERS AND AUXILIARIES: BOILERS



Auxiliary Feed Water

Boiler Make-up Water


Main Steam Safety Valves



TURBINE, GENERATOR AND AUXILIARIES


Turbine Protection Valve Testing

Control Valve Testing

Overspeed Trip Mechanism Testing


Turbine to be Shutdown if Turbine Trip System is Suspected to be failed


Turbine Loading Rate

Operating Limits of Turbine

Quality of Turbine Governor Oil

Generator Load

Generator Hydrogen Pressure and Purity


Turbine Control in Manual Mode


ELECTRICAL SYSTEMS: GENERAL


Electrical System Maintenance

Changes in Output Relay Settings

Protective Relaying to be Poised


ELECTRICAL SYSTEMS: STANDBY AND EMERGENCY SYSTEMS


Standby Diesel Generators Unavailability


Normal Status of Standby Diesel Generators


Standby Diesel Generator Maintenance

Standby Diesel Generator Fuel Inventory


Testing of Standby Diesel Generator Units

Testing of Transfer Logic

Normal Status of Emergency Diesl Generators

Availability of Emergency Diesel Generators

Emergency Diesel Generator Fuel Inventory

Testing of the Emergency Diesel Generators

Planned Maintenance of Emergency Diesel Generators


ELECTRICAL SYSTEM: NORMAL SUPPLIES


Class IV Power Supply


ELECTRICAL SYSTEMS: UNINTERRUPTABLE POWER SUPPLIES


Class I Power Supply

Class II Power Supply


INSTRUMENTATION AND CONTROL GENERAL


Control Room Operation

Secondary Control Room

Manual Control of Reactivity Mechanisms

Authorization for Increase in Power

Independence of Regulating and Protective Functions

Indication of Neutron Flux to be Available

Reactivity Device Replacement



INSTRUMENTATION AND CONTROL: REGULATING SYSTEM


Availability of the Regulating System

Sequence for Withdrawal of Absorber and Adjuster Rods

Reactor Regulating System Maintenance

Testing of Stepback and Setback


INSTRUMENTATION AND CONTROL: COMPUTERS


Control Computer Software Changes


Access to Computer Memory


INSTRUMENTATION AND CONTROL: SHUTDOWN SYSTEMS


Shutdown System Availability

Changes to Shutdown System Trip Setpoints


Neutron Overpower Trip Effectiveness


Maintenance of Shutdown Systems

Testing of Shutdown Systems

Guaranteed Shutdown State

Isotopic Concentration of Neutron Poisons



MISCELLANEOUS PLANT SYSTEMS


Raw Service Water, Recirculated Cooling Water and Chilled Water System

Fire Protection System

Ventilation System

Emergency Water System

Instrument Air System



CUPRINS


FUNDAMENTE

SCOP

DOMENIU DE APLICARE

REFERINTE

RESPONSABILITATI

DEFINITII


GENERAL: ORGANIZAREA


Autorizatia de functionare emisa de CNCAN

Autorizarea personalului de exploatare

Delegarea autoritatii Directorului de Centrala

Autoritatea Dispecerului Sef de Tura

Existenta unui Personal corespunzator īn Centrala

Respectarea Reglementarilor Nationale

Programul de Asigurare Calitatii

Modificarea Politicilor si Principiilor de Exploatare


GENERAL: ASPECTE DE EXPLOATARE


Situatii care sunt īn contradictie cu Politicile si Principiile de Exploatare

Conformitatea cu Procedurile Centralei

Autorizarea activitatilor de īntretinere

Protectia contra Radiatiilor

Controlul Materialelor Radioactive

Emisiile gazoase si lichide

Protectia la suprapresiune

Controlul Chimismului

Informarea CNCAN


GENERAL: ASPECTE DE SECURITATE NUCLEARA LEGATE DE EXPLOATARE


Modificari

Indisponibilitatea sistemelor speciale de securitate

Intretinere

"Stare sigura" pentru componente ale sistemelor cu functii de securitate

Frecventa de testare a sistemelor

Independenta canalelor si sistemelor




GENERAL: RAPORTARI


Raportarea modificarilor catre CNCAN

Raportarea incidentelor

Raportul anual catre CNCAN

Inregistrari īn exploatare


AMPLASAMENT


Zona de excludere

Planuri de urgenta

Protectia fizica


CLADIRI SI STRUCTURI


Disponibilitatea sistemului anvelopei

Scapari din sistemul anvelopei

Testarea sistemului anvelopei

Controlul accesului īn cladirea reactorului

Deschideri ale Anvelopei


REACTORUL, GENERATORII DE ABUR SI AUXILIARELE: GENERAL


Limite de putere

Controlul reactivitatii

Starea reactorului

Atingerea criticitatii


REACTORUL, GENERATORII DE ABUR SI AUXILIARELE: MODERATORUL


Sistemul moderatorului

Concentratia de deuteriu īn gazul de acoperire

Purificare moderator

Moderatorul ca ultima sursa de racire


REACTORUL, GENERATORII DE ABUR SI AUXILIARELE: TRANSPORTUL CALDURII


Agentul primar de racire

Disponibilitatea sursei de racire

Detectarea combustibilului defect

Sistemul primar de transport al caldurii

Inventarul rezervorului de stocare D2O

Scurgerile sistemului de transport al caldurii

Limita de iod īn sistemul de transport al caldurii


REACTORUL, GENERATORII DE ABUR SI AUXILIARELE: AUXILIARELE


Sistemul Protectii de Capat

Disponibilitatea Sistemul de racire la avarie a zonei active (SRAZA)

Testarea SRAZA

Sistemul de gaz inelar

Sistemul de racire la oprire

Sistemul de control zonal cu lichid


REACTORUL, GENERATORII DE ABUR SI AUXILIARELE: MANIPULAREA COMBUSTIBILULUI


Masina de īncarcat-descarcat combustibil

Racirea si ecranarea combustibilului iradiat

Capacitatea de stocare a combustibilului iradiat

Starea reactorului īn timpul īncarcarii combustibilului


REACTORUL, GENERATORII DE ABUR SI AUXILIARELE: GENERATORII DE ABUR


Sistemul auxiliar de apa de alimentare

Sistemul de apa de adaos la generatorii de abur

Vane de siguranta pentru evacuarea aburului viu


TURBINA, GENERATORUL SI AUXILIARELE


Testarea vanelor de protectie ale turbinei

Testarea vanelor de reglare

Testarea mecanismului de declansare la supraturatie

Oprirea turbinei īn cazul īn care dispozitivul de declansare la supraturatie este suspect a fi defect

Rata de īncarcare a turbinei

Limitele de exploatare ale turbinei

Calitatea uleiului de comanda al turbinei

Sarcina generatorului

Presiunea si puritatea hidrogenului de la generator

Controlul turbinei īn modul manual


SISTEME ELECTRICE: GENERALITATI


Intretinerea sistemelor electrice

Modificarea reglajelor prin relee

Releele de protectie sa fie armate


SISTEME ELECTRICE: SISTEMELE DE REZERVA SI DE URGENTA


Indisponibiltatea generatorilor Diesel de rezerva

Starea normala pentru generatorii Diesel electrici de rezerva

Intretinerea generatorilor Diesel de rezerva

Inventarul de combustibil al generatorilor Diesl de rezerva

Testarea generatorilor Diesel de rezerva

Testarea logicii de transfer

Starea normala a generatorilor Diesel de avarie

Disponibilitatea generatorilor Diesel de avarie

Inventarul de combustibil al generatorilor Diesel de avarie

Testarea generatorilor Diesel de urgenta

Intretinerea planificata a generatorilor Diesel de urgenta


SISTEME ELECTRICE: ALIMENTARI NORMALE


Alimentarea cu energie electrica de Clasa IV


SISTEME ELECTRICE: SURSE DE ALIMENTARE FARA INTRERUPERE


Alimentarea cu energie electrica de Clasa I

Alimentarea cu energie electrica de Clasa II


INSTRUMENTATIE SI CONTROL GENERALITATI


Activitati īn Camera de Comanda

Camera de Comanda secundara

Controlul manual al mecanismelor de control al reactivitatii

Autorizarea pentru cresterea puterii

Independenta functiilor de reglare si protectie

Indicatiile de flux neutronic sa fie disponibile

Īnlocuirea Dispozitivelor de Control Reactivitate


INSTRUMENTATIE SI CONTROL: SISTEMUL DE REGLARE


Disponibilitatea sistemului de reglare

Secventa de extragere a barelor absorbante si ajustoare

Intretinerea sistemului de reglare a reactorului

Testarea stepback si a setback


INSTRUMENTATIE SI CONTROL: CALCULATOARELE


Modificari īn programele de control ale calculatoarelor de proces

Accesul la memoria calculatorului


INSTRUMENTATIE SI CONTROL: SISTEME DE OPRIRE RAPIDA


Disponibilitatea sistemelor de oprire rapida

Modificari ale pragurilor de declansare ale sistemelor de oprire rapida

Eficacitatea declansarii la supraputere neutronica

Intretinerea sistemelor de oprire rapida

Testarea sistemelor de oprire rapida

Starea de oprire garantata

Concentratia izotopica a otravurilor de neutroni


SISTEME AUXILIARE ALE CENTRALEI


Sistemul de apa bruta de racire, sistemul de apa racire recirculata si sistemul de apa racita

Sistemul de Protectie la incendii

Sistemul de ventilatie

Sistemul de alimentare cu apa la avarie

Sistemul de aer instrumental


APPENDIX A


A.0      Applicability of Appendix

A.1      Containment System Initiation Setpoint


A.2      ECC System Initiation Setpoint

A.3      SDS#1 Trip Setpoint

A.4      SDS#2 Trip Setpoint

A.5      Containment System Limits


A.6      ECC System Limits

A.7      SDS#1 Limits

A.8      SDS#2 Limits

A.9      Reactivity Control Limits


A.10     Moderator System Limits


A.11     Heat Transport System Limits


A.12     End Shield Cooling Limits


A.13     Annulus Gas System Limits


A.14     MSSV Limits



A.15     Heat Sinks Availability

A.16     Electrical System Availability

A.17     Service Water System Availability


A.18      Guaranteed Shutdown State Limits

ANEXA A


A.0        Domeniul de aplicabilitate a anexei

A.1        Praguri De Initiere Pentru Sistemul Anvelopei

A.2        Praguri De Initiere Pentru SRAZA

A.3        Praguri De Declansare Pentru SOR #1

A.4        Praguri De Declansare Pentru SOR #2

A.5        Limite Aplicabile Pentru Sistemele Anvelopei

A.6        Limite Aplicabile Pentru SRAZA

A.7        Limite Aplicabile Pentru SOR #1

A.8        Limite Aplicabile Pentru SOR #2

A.9        Limite Aplicabile Pentru Sistemul de Control al Reactivitatii

A.10      Limite Aplicabile Pentru Sistemul Moderator

A.11      Limite Aplicabile Pentru Sistemul Primar De Transport al Caldurii

A.12      Limite Aplicabile Pentru Sistemul De Racire Protectii Biologice

A.13      Limite Aplicabile Pentru Sistemul Inelar De Gaz

A.14      Limite Aplicabile Pentru Vanele Principale De Descarcare Abur (MSSV)

A.15      Disponibilitatea Surselor Reci

A.16      Disponibilitatea Sistemelor Electrice

A.17      Disponibilitatea Sistemelor De Apa De Serviciu

A.18      Limite Aplicabile Starii De Oprire Garantata



BACKGROUND


The National Nuclear Control Board (CNCAN) is empowered to make and enforce regulations governing the construction and operation of nuclear facilities in Romania. Approval to operate a nuclear facility is granted by CNCAN through the issue of a Commissioning / Operating License.




In the process of acquiring an Commissioning / Operating License, the licensee is obliged to provide CNCAN with a comprehensive description of the plant design with particular emphasis on its safety-related features. The licensee must also demonstrate, by analysis or otherwise, that the safety features provided will adequately protect the general public from the consequences of certain postulated accidents, including accidents involving the concurrent failure of whichever system would otherwise provide the primary defence. The principal description of the plant design, the performance of its safety features is covered in the Final Safety Analysis Report (FSAR).




In addition, the licensee must demonstrate, using various analytical techniques including reliability evaluations, that emergencies of the type discussed in the Final Safety Analysis Report and elsewhere, have a probability of occurrence commensurate with the severity of the event under consideration, and consistent also with such mandatory targets as CNCAN may designate.



Further, the licensee must provide CNCAN with the operating procedures intended to prevent undesirable events and to control such events as may nevertheless occur. In granting a Commissioning / Operating License, CNCAN imposes that the station be operated and maintained in conformity with the documentary basis for the granting of a license. Design changes, and changes in operating procedures, are permissible, provided that the proposed change would have no appreciable impact on the validity of documents supporting the current license.





The documentary basis for the granting of the license may be changed with the CNCAN approval. In the latter case, the revised documentation then becomes the new basis for continued tenure of a current License.


FUNDAMENTE


Comisia Nationala pentru Controlul Activitatilor Nucleare (CNCAN) este īmputernicita prin lege sa elaboreze si sa aplice reglementarile ce guverneaza constructia si exploatarea instalatiilor nucleare īn Romānia. Aprobarea pentru functionarea unei instalatii nucleare se acorda numai de CNCAN prin emiterea unei Autorizatii de Punere īn functiune (PIF) / Functionare.


In procesul de obtinere a unei autorizatii de punere īn functiune / functionare , solicitantul este obligat sa prezinte la CNCAN o descriere comprehensiva a proiectului centralei subliniind īn mod explicit aspectele legate de securitate. De asemenea, solicitantul trebuie sa demonstreze prin analize sau prin alte mijloace ca masurile de securitate avute īn vedere, vor proteja adecvat publicul de consecintele accidentelor postulate pentru instalatia nucleara, acestea incluzīnd si evenimentele ce implica defectarea simultana a oricaror dintre sistemele centralei care asigura prima linie de protectie la accident. Descrierea proiectului centralei, ca si evaluarea performantelor sistemelor de securitate sunt acoperite īn Raportul Final de Securitate (RFS).


In plus, folosind diferite tehnici analitice, inclusiv metoda evaluarilor de fiabilitate, solicitantul de autorizatie trebuie sa demonstreze ca tipurile de evenimente analizate īn RFS si īn celelalte documente suport pentru autorizare, au o probabilitate de aparitie calculata corespunzator cu severitatea evenimentului luat īn consideratie si, de asemenea, este īn limitele obligatorii impuse de CNCAN.


Mai mult, solicitantul de autorizatie trebuie sa prezinte la CNCAN proceduri de exploatare elaborate atāt īn scopul prevenirii accidentelor nedorite cāt si pentru tinerea lor sub control īn cazul aparitiei, astfel īncāt consecintele aparitiei lor sa fie minime. La acordarea unei Autorizatii de punere īn functiune / functionare, CNCAN impune ca centrala sa fie exploatata si mentinuta īn conformitate cu cerintele specificate īn documentatiile suport ce stau la baza emiterii Autorizatiei. Modificari ale proiectului sau ale procedurilor de exploatare sunt permise asigurāndu-se ca nu vor afecta semnificativ validitatea documentatiei suport a autorizatiei īn vigoare.


Documentatia suport īn baza careia se elibereaza Autorizatia de Functionare poate fi modificata cu acordul CNCAN. Īn acest caz documentatia revizuita devine suport pentru mentinerea īn vigoare a autorizatiei curente.

Within the operating boundaries, clearly defined in Operating Policies and Principles detailed operating procedures are prepared for clearly defined operating requirements. Procedures are also written for abnormal or emergency conditions which may be precisely defined. It may from time to time be necessary to revise the detailed operating procedures. Such revisions may only be carried out within the boundaries established in the Operating Policies and Principles, and must be consistent with Chapter 15 of the FSAR.

In cadrul limitelor generale legate de securitatea nucleara, clar definite īn documentul Politici si Principii de Exploatare, se elaboreaza proceduri detaliate de exploatare īn care se definesc clar cerintele de exploatare. De asemenea, se elaboreaza proceduri clare pentru conditiile anormale si de accident. Īn timp, poate apare necesitatea ca procedurile de exploatare sa fie revizuite. Aceste revizii tre-buie facute cu respectarea limitelor generale stabilite īn documentul Politica si Principii de Exploatare si īn Capitolul 16 al RFS.


The Operating Policies and Principles also define the authorities of the station staff and thus act as an interface between the shift operating staff and the station management. This permits the operating staff to make decisions within the defined boundaries and indicates when a higher authority must be involved.


In order to prevent and/or mitigate any nuclear incident or accident, the following principles of reactor safety are considered to be important and should be complied with at all times as per Nuclear Safety Policy (79-RD-01364-L4).



a) Nuclear Safety has the utmost priority, overriding the demands of production. Decisions shall be made and reinforced consistent with this statement.


b) Defence in depth is to be maintained.


c) Personnel must be qualified.



d) Responsibilities for nuclear safety is to be defined.


e) Operating procedures must be followed.


f) Review of work must be done.



g) When unexpected occurs, expert advice must be obtained.



h) Operational limits must be defined.


i) Significant events shall be investigated and lessons learned implemented.


j) A questioning attitude is to be encouraged.


k) Operating Policies and Principles shall not be violated.


(l) A set of nuclear safety standards shall be established against which the safety performance of Cernavoda NPP shall be assessed.


PURPOSE


The principal function of this Reference Document is to document the safe envelope within which the plant is to be operated and also to define the authorities of the station staff.


SCOPE


This Reference Document is applied by all operating personnel in carrying out their responsibilities to operate and maintain Cernavoda NPP Unit 2 in safe manner.


Changes to this Reference Document will be submitted to CNCAN for approval prior to implementation.


REFERENCES


Cernavoda NPP Unit-2 Final Safety Analysis Report (FSAR, Chap 15 and Chap 16)

Integrated Management Manual (MMI-01.02

Norme Republicane de Securitate Nucleara, Reactori Nucleari si Centrale Nuclearoelectrice, 1975

Nuclear Safety Policy RD-01364-L4

List of Safety Related System, 82-RD-01364-C05


RESPONSIBILITIES


Responsibilities of Station Staff are defined throughout the document on a case-by-case basis.



DEFINITIONS


The defined terms of this section are applicable throughout these Operating Policies and Principles.


Politica si Principiile de Exploatare definesc deasemenea limitele de autoritate ale personalului centralei, stabilind astfel interfata īntre personalul operator si conducerea centralei. Aceasta permite personalului operator sa ia decizii īn limitele definite si sa indice cānd o autoritate superioara trebuie implicata.


Pentru a preveni si/sau limita orice incident sau accident nuclear urmatoarele principii de securitate nucleara sunt considerate importante si trebuie respectate īn orice moment, īn conformitate cu Documentul de Referinta al Centralei "Politici de Securitate Nucleara" (79-RD-01364-L4):


(a) Securitatea nucleara are prioritatea maxima, īn fata oricaror cerinte legate de productie. Toate deciziile vor fi luate si implementate īn conformitate cu aceasta declaratie.


(b) Principiul apararii īn adāncime va fi respectat.


(c) Personalul centralei trebuie sa aiba calificarea corespunzatoare.


(d) Responsabilitatile pentru securitatea nucleara a Centralei vor fi clar definite.


e) Procedurile de exploatare vor fi respectate.


f) Verificarea activitatilor trebuie sa fie facuta permanent.


g) La aparitia unor situatii neprevazute se impune consultarea specialistilor centralei īn domeniul respectiv.


h) Limitele operationale trebuie sa fie definite.


i) Evenimentele semnificative vor fi investigate iar concluziile intelese si implementate.


j) Atitudinea interogativa va fi īncurajata.


k) Politicile si Principiile de Exploatare nu vor fi violate.


(l) Se va stabili un set de standarde de securitate nucleara īn functie de care se vor evalua performantele de securitate ale Cernavoda U2.


SCOP


Scopul principal al acestui Document de Referinta este de a prezenta limitele īn cadrul carora Centrala trebuie mentinuta si operata astfel ca securitatea nucleara sa fie asigurata.


DOMENIU DE APLICARE


Acest document de referinta (RD) se aplica īntegului personal al centralei pe parcursul īndeplinirii responsabilitatilor ce le revin pentru mentinerea Unitatii 2 Cernavoda īn conditii de securitate nucleara.

Modificarile acestui Document de Referinta vor fi supuse aprobarii CNCAN īnainte de implementare.



REFERINTE


CNE Cernavoda Unit-2 Raport Final de Securitate (RFS Cap. 15 si 16)

Manual de Management Integrat (MMI-01.02)

Norme Republicane de Securitate Nucleara, Reactori Nucleari si Centrale Nuclearoelectrice, 1975

Politica de securitate Nucleara, RD-01364-L4

Lista Sistemelor cu Functii de Securitate, 82-01364-RD-C05


RESPONSABILITATI


Responsabilitatile personalului centralei sunt definite, de la caz la caz, pe parcursul acestui document.


DEFINITII


Termenii definiti īn aceasta sectiune sunt aplicabili peste tot īn cadrul acestor Politici si Principii de Exploatare.


6.1 AVAILABILITY - the fraction of a specified time period that a safety related system is able to satisfy the design intent for all accident conditions.




6.2 CONTAINMENT BOUNDARY - the pressure retaining portion of the containment up to the containment isolation device.


6.3 DERIVED EMISSION LIMIT (DEL) - that rate of discharge for the specific radionuclide in liquid or gaseous effluent, or group of nuclide, which if continued for one year exposes a member of the public to the regulatory limit (1 mSv at the exclusion boundary or condenser cooling water outfall).


6.4 GUARANTEED SHUTDOWN STATE - the specified subcritical state of a nuclear reactor which provides positive assurance that an inadvertent increase in nuclear reaction cannot occur.


6.5 IMMEDIATE SHUTDOWN - the reactor is shutdown at once using manual setback and normal shutdown operating procedures for other systems.



6.6 OPERABLE - a system, subsystem, train, component, or device shall be operable when it is capable of performing its specified function(s), and when all necessary attendant instrumentation, control, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, train, component or device to perform its function(s) are also capable of performing their related support function(s).


6.7 ORDERLY SHUTDOWN - the reactor is shutdown by successive load reductions after the specific defined time interval, using normal operating procedures.


6.8 TRIP - as used in this document 'reactor trip' means shutdown system action.



6.9 POISED - a term applied to a system that normally plays no part in the production process, but remains available to operate to minimize the consequences of a process system failure.


6.10 IMPAIRMENT - any fault that renders a special safety systems or safety related system less than fully capable of performing to its design intent or reduces redundacy or safety margin





6.11 SAFETY SYSTEM - a system which is intended to control, shutdown and cool the reactor core, or to limit the release of radioactivity.



6.12 SPECIAL SAFETY SYSTEM - Those systems specifically designed to limit or mitigate the consequences of plant process failures thereby ensuring that any resultant release of radioactivity to the environment and the public is kept within acceptable limits. (SDS#1, SDS#2, ECC, Containment).


6.13. PROCESS SYSTEM - a system used in the normal production process.


6.14. SAFE SHUTDOWN STATE - low power critical, or Xenon poisoned out or GSS with adequate fuel cooling maintained.



6.15 OPERATIONAL PARTS - refers to those components of Special Safety Systems which perform the associated safety function or indicate the availability of the associated safety functions, except for the test circuits.

6.1 DISPONIBILITATE - fractiunea de timp dintr-o perioada specificata de timp īn care un sistem cu functii de securitate este capabil sa-si īndeplineasca functia pentru care a fost proiectat pentru toate conditiile de accident.


6.2 LIMITA ANVELOPEI - acele portiuni ale sistemului de anvelopare care constituie incinta de izolare a cladirii reactorului.


6.3 LIMITE DERIVATE DE EMISIE - rate de eliberare pentru un radionuclid specific īn efluenti lichizi sau gazosi, sau pentru un grup de nuclizi care, daca sunt mentinute timp de 1 an, determina expunerea limita pentru un membru al populatiei (1 mSv la limita zonei de excludere sau la gura de deversare a apei de racire)


6.4 STARE DE OPRIRE GARANTATA - stare specificata de subcriticitate a unui reactor nuclear care furnizeaza asigurari ca nu este posibila aparitia unor cresteri intempestive ale numarului de reactii nucleare.


6.5 OPRIRE IMEDIATA - reactorul este oprit prin initierea manuala a functiei setback a RRS iar configuratia de oprire pentru celelalte sisteme se realizeaza prin utilizarea procedurilor normale de functionare.


6.6 FUNCTIONAL - un sistem, subsistem, traseu, componenta sau dispozitiv, este considerat functional daca este capabil sa-si īndeplineasca functia pentru care a fost proiectat si deasemenea daca toate cele necesare functionarii lui (instrumentatie si control, alimentare cu energie electrica, apa pentru racire sau pentru etansari, ungere si alte echipamente auxiliare) sunt capabile sa-si īndeplineasca functiile suport.


6.7 OPRIRE NORMALA - reactorul este oprit utilizānd procedurile normale de functionare prin reduceri succesive ale īncarcarilor īn perioade specificate de timp.


6.8 DECLANSARE- īn acest document prin "declansarea reactorului" se īntelege actiunea unuia sau ambelor sisteme de oprire.


6.9 ARMAT - termen care s 555r1717f e foloseste pentru un sistem care īn mod normal nu participa la procesul de productie, dar care este disponibil sa intervina pentru minimizarea consecintelor unei avarii de proces.


6.10 DISFUNCTIONALITATE - orice defectiune care face ca un sistem special de securitate sau un sistem cu functii de securitate nucleara sa nu mai fie capabil sa-si realizeze īntocmai functia pentru care a fost proiectat, reduce redundanta sau reduce marja de securitate.


6.11 SISTEM DE SECURITATE NUCLEARA - sistem care este implicat īn oprirea sau controlul reactorului, racirea zonei active sau īn limitarea eliberarilor de radioactivitate.


6.12 SISTEM SPECIAL DE SECURITATE - sisteme concepute in mod special pentru a limita sau atenua consecintele defectiunilor de proces mentinānd īn limite acceptabile orice eliberare de radioactivitate catre mediul īnconjurator sau catre public. (SOR#1, SOR#2, SRAZA, Anvelopa).



6.13. SISTEM DE PROCES - sistem care este folosit īn procesul normal de productie.


6.14. STARE SIGURA de OPRIRE - starea cu reactorul critic la putere joasa, otravit cu Xenon sau īn Stare de Oprire Garantata cu mentinerea racirii corespunzatoare a combustibilului.


6.15 COMPONENTE ACTIVE - acele componente ale sistemelor speciale de securitate, absolut necesare pentru īndeplinirea functiei de securitate nucleara asociate sau pentru indicarea disponibilitatii functiei de securitate nucleara asociate, cu exceptia circuitelor de testare.


CERNAVODA OPERATING POLICIES AND PRINCIPLES

POLITICA SI PRINCIPII DE OPERARE



GENERAL: ORGANIZATION


00.01 Commissioning / Operating License Issued by CNCAN


An up-to-date copy of the CERNAVODA Nuclear Power Plant Commissioning / Operating License is to be enclosed herewith. Any restriction specified shall be automatically incorporated as the policy of this station.


Authorization of Operating Personnel


Only persons authorized by CNCAN shall act as Station Manager, Production Manager, Technical Manager, Safety & Compliance Superintendent, Health Physics Superintendent


Only persons authorized by CNCAN shall act as Operating Superintendent, Shift Supervisor and Control Room Operator for Cernavoda Unit-2.



00.03 Delegation of Authority of Station Manager


In all sections of this document in which authorization by the Station Manager is prescribed, this shall be understood to mean the Station Manager or a designated alternate who shall be either the Production Manager or the Technical Manager, Operation Superintendent.



The Station Manager ensures that an alternate is designated all times to keep the plant in a safe state.


For some routine functions, the designated alternate is specified in Station Procedures .


Authority of Shift Supervisor


The Shift Supervisor has the responsibility and authority for the operation of the station, and the safety of all persons on site. The Station Manager can remove the Shift Supervisor from his position only if he is replaced by another authorized Shift Supervisor.



Station to be Adequately Staffed



There shall be sufficient qualified personnel present at all times to ensure the station safe operation.


The minimum complement is specified in Station Instruction SI-01365-P38. These shall include one Shift Supervisor and one Control Room Operator authorized by CNCAN. An authorized Shift Supervisor or Control Room Operator shall be in the control room at all times when there is fuel in the reactor unless, in the opinion of the Shift Supervisor, an unwarranted hazard exists. It is then the responsibility of the Shift Supervisor to authorize and supervise the immediate shutdown of the reactor if it is at power, and to ensure the orderly transfer of control to the Secondary Control Area.



Observance of National Regulations


Cernavoda NPP will be operated in accordance with all applicable National Regulations.



00.07 Operational Quality Assurance Program



All aspects of the operation of Cernavoda NPP U2 shall be in accordance with Operations Quality Assurance Manual - Integrated Management Manual (MMI-01.02)) and the associated reference documents.



00.08 Changes of Operating Policies and Principles


Changes to or temporary deviations from the Operating Policies and Principles shall be submitted to CNCAN for prior approval.


GENERAL: ORGANIZAREA


00.01 Autorizatia de Punere īn Functiune / de Functionare emisa de CNCAN


O copie a Autorizatiei de Punere īn Functiune / de Functionare īn vigoare va fi anexata la prezentul document. Orice restrictie mentionata īn aceasta autorizatie va fi incorporata automat ca un principiu de exploatare a centralei.


Autorizarea personalului de decizie


Numai persoanele care au fost autorizate de CNCAN vor putea actiona ca: Director de Centrala, Director de Productie, Director Tehnic si de Securitate Nucleara, Inginer Sef Securitate Nucleara, Inginer Sef de Radioprotectie.

Numai persoanele autorizate de catre CNCAN vor actiona ca Inginer Sef Exploatare, Dispecer Sef Tura si respectiv Operator Principal īn Camera de Comanda pentru Unitatea 2 Cernavoda.


00.03 Delegarea Autoritatii de catre Directorul de Centrala


In toate sectiunile acestui document īn care este prevazuta o activitate pentru care este necesara aprobarea din partea Directorului de Centrala se va īntelege ca aceasta aprobare poate fi facuta de catre Directorul de Centrala sau de catre loctiitorul acestuia care va fi Directorul de Productie sau Directorul Tehnic sau Inginerul Sef Exploatare.


Directorul de Centrala se asigura ca īn permanenta exista disponibila autoritatea necesara mentinerii centralei īn conditii de securitate nucleara.


Pentru anumite activitati specifice delegarea autoritatii este precizata īn procedurile centralei.


Autoritatea Dispecerului Sef de Tura


Dispecerul Sef de Tura are responsabilitatea si autoritatea de decizie pentru asigurarea operarii centralei, ca si pentru securitatea tuturor persoanelor din Centrala. Directorul de Centrala īl poate elibera pe Dispecerul Sef de Tura din aceasta pozitie daca īl īnlocuieste cu un alt Dispecer Sef de Tura autorizat.


00.05 Asigurarea personalului corespunzator īn Centrala


Tot timpul va fi prezent suficient personal calificat pentru asigurarea operarii Centralei īn conditii de securitate nuclera.


Structura minima specificata īn SI-01365-P38. Aceasta structura minima trebuie sa includa un Dispecer Sef de Tura si un Operator Principal autorizati de CNCAN. Dispecerul Sef de Tura sau Operatorul Principal trebuie sa fie īn camera de comanda tot timpul cāt este combustibil īn reactor, īn afara cazului īn care īn opinia Dispecerului Sef de Tura conditiile din camera de Comanda principala prezinta un pericol inacceptabil. Īn acest caz este responsabilitatea Dispecerului Sef de Tura sa autorizeze si sa supravegheze oprirea imediata a reactorului, daca acesta este la putere, si sa asigure transferul ordonat al controlului centralei catre camera de Comanda secundara.


Respectarea Reglementarilor Nationale


Activitatile de exploatare pentru CNE Cernavoda vor fi efectuate īn conformitate cu toate Reglementarile Nationale aplicabile.


00.07 Programul de asigurarea calitatii pentru exploatare


Toate aspectele referitoare la activitatile de Exploatare pentru CNE Cernavoda U2 vor fi īn conformitate cu Manualul de Asigurare a Calitatii pentru Exploatare - Manual de Management Integrat (MMI-01.02) si documentele de referinta asociate.


00.08 Modificari ale Politicilor si Principiilor de Exploatare


Modificarile, precum si deviatiile temporare de la prevederile Politicilor si Principiilor de Exploatare vor fi supuse aprobarii CNCAN īnainte de implementare.


GENERAL: OPERATING SUBJECTS


01.01 Conditions Which Conflict With Operating Polices and Principles


If conditions are found to exist which conflict with the stated Operating Policies and Principles, the affected system(s) shall promptly be put in the normal configuration or other known safe state, or the reactor shall be put in a safe shutdown state, as specified in the OP&P, within the time limits given in the Impairments Manual.




Station Procedure Compliance


The plant shall be operated and maintained according to approved station procedures, which shall be written to maintain the design intent.


Authorization for Maintenance


All maintenance of safety-related equipment as specified in List of Safety Related Systems (82-RD-01364-C05 ) must have prior approval of the Shift Supervisor or his delegate who shall be the Control Room Operator. In addition, the approval of the Station Manager or his designated alternate is also required whenever a change from a prescribed maintenance procedure or work plan is needed that could adversely affect nuclear safety.


GENERAL: ASPECTE DE EXPLOATARE


01.01 Situatii care sunt īn contradictie cu Politicile si Principiile de Operare


Daca se descopera situatii care sunt īn contradictie cu Politicile si Principiile de Operare din prezentul document, sistemul (sistemele) afectate vor fi plasate imediat īn configuratia normala sau īntr-o alta configuratie sigura cunoscuta, ori reactorul va fi adus īntr-o stare sigura de oprire dupa cum este specificat īn Politicile si Principiile de Operare, īn conformitate cu limitele de timp indicate īn Manualul de Disfunctionalitati.


Conformitatea cu procedurile centralei


Centrala va fi operata si mentinuta īn conformitate cu procedurile aprobate care vor fi īntocmite astfel īncāt sa se respecte intentia de proiectare.


Autorizarea activitatilor de īntretinere


Toate activitatile de īntretinere din Centrala care se efectueaza asupra echipamentelor cu functie de securitate nucleara specificate īn Lista Sistemelor cu Functii de Securitate (82-RD-01364-C05) vor fi aprobate in prealabil de catre Dispecerul Sef de Tura sau de loctiitorul acestuia, care va fi Operatorul principal. In plus, aprobarea Directorului Centralei sau a delegatului acestuia este de asemenea ceruta ori de cāte ori este necesara o abatere semnificativa de la o procedura de īntretinere aprobata sau de la un Plan de Lucru care ar putea influenta advers securitatea nucleara.


Radiation Protection


Protection of the public and operating personnel from radiation hazards shall be in accordance with the Radiation Protection Regulations (RD-01364-RP9), approved by the Station Manager and CNCAN.


Control of Radioactive Material


Handling and transportation of radioactive materials shall conform to the regulations specified in the Radiation Protection Regulations (RD-01364-RP9). Heavy water, sources containing radioactive material in excess of specified limits, and the fuel, are all substances prescribed by regulations. These substances shall be acquired, stored, used, and accounted for in accordance with the requirements of CNCAN.


Gaseous and Liquid Emissions


Radioactive emissions in airborne and liquid effluent shall be monitored and controlled such that the dose to the public due to the combined effects of all emissions is kept as low as practical and does not exceed the limits prescribed by CNCAN.


Derived emission limits (DELs) for each radionuclide are tabulated in Reference Document, RD-01364-RP4 "Derived Emission Limits for Radionuclides in Gaseous and Liquid Effluent", revisions to which are subject the approval of CNCAN.


It is a design and operating target that 5 percent of the annual DEL for each effluent pathway should not be exceeded. On any failure to comply with this target prompt corrective action shall be taken and the event shall be investigated.



Overpressure Protection


Overpressure relief devices shall be set at or below the respective system design pressure and shall be tested as per "Safety & Relief Valve Testing" (SI-01365-P8) in accordance with the requirements of ISCIR.




Vessels and pipe sections having no overpressure protection when isolated shall only be isolated if assurances exist that no source of energy input can arise during the period the vessel or pipe is not connected to a relief device.






Chemistry Control


Plant system chemistry shall be controlled to provide adequate chemical protection ensuring the integrity of plant systems/components over the design life of the plant as described in "Station Chemistry" (RD-01364-CH1).


Protectia contra radiatiilor


Protectia publicului si a personalului de exploatare īmpotriva radiatiilor va fi asigurata īn conformitate cu Regulamentul de Radioprotectie (RD-01364-RP9), aprobat de Directorul de Centrala si CNCAN.


Controlul materialelor radioactive


Manipularea si transportul materialelor radioactive se va face īn conformitate cu prevederile Regulamentului de Radioprotectie (RD-01364-RP9). Apa grea, sursele ce contin materiale radioactive peste limitele specificate si combustibilul sunt toate substante care se supun prevederilor reglementarilor CNCAN. Aceste substante se vor achizitiona, depozita, folosi si gestiona īn conformitate cu cerintele CNCAN.


Emisiile gazoase si lichide


Emisiile radioactive īn aerosoli si lichizi trebuie sa fie monitorate si controlate astfel īncāt doza catre public datorata efectelor combinate ale tututor emisiilor sa fie mentinuta la un nivel minim practic de realizat si sa nu depaseasca limitele stabilite de CNCAN.


Limitele derivate de emisie pentru fiecare radionuclid sunt tabelate īn Documentul de Referinta, RD-01364-RP4 "Limite de emisie derivate pentru radionuclizii din efluentii gazosi si lichizi". Reviziile acestui document sunt supuse aprobarii CNCAN.


Este stabilit ca obiectiv de operare sa nu fie depasita valoarea de 5% din Limita Derivata de Emisie considerānd fiecare cale posibila de emisie a efluentilor lichizi sau gazosi. La orice abatere de la acest obiectiv se vor īntreprinde actiuni corective imediate si evenimentul va fi investigat.


Protectia la suprapresiune


Dispozitivele de protectie la suprapresiune vor fi reglate sa actioneze la o presiune mai mica sau egala cu presiunea de proiectare a sistemului respectiv. Aceste dispozitive vor fi testate īn conformitate cu "Testarea Vanelor de Siguranta si de Protectie la Suprapresiune" (SI-01365-P8) si īn concordanta cu cerintele ISCIR.


Izolarea recipientelor si a portiunilor de conducte ce nu au protectie la suprapresiune se va face numai asigurāndu-se ca nici o sursa de energie nu poate apare īn timp ce recipientul sau conducta sunt deconectate de la dispozitivul de protectie la suprapresiune.





Controlul Chimismului


Chimismul īn sistemele centralei va fi controlat īn conformitate cu Documentul de Referinta "Chimismul Centralei" (RD-01364-CH1) pentru a se mentine o protectie chimica corespunzatoare care sa asigure integritatea sistemelor /componentelor pe parcursul perioadei de viata proiectate.


CNCAN Notification


CNCAN shall be notified as soon as reasonable when the Station Manager approves an activity which impacts on nuclear safety.


Informarea CNCAN


CNCAN va fi informat, īndata ce este posibil, ori de cāte ori Directorul de Centrala aproba o activitate cu impact asupra securitatii nucleare.



GENERAL: REACTOR SAFETY OPERATING SUBJECTS



Modifications


(a) Prior approval of Shift Supervisor shall be obtained for :


(i) all temporary changes to any station system;


(ii) all temporary changes to approved operating procedures.


(b) Prior approval of the Station Manager shall be obtained for:


(i) all permanent changes to any station system.


(ii) all temporary changes to the Special Safety Systems and the Reactor Regulating System.


(iii) all temporary changes to any safety system that could significantly and adversely affect nuclear safety.

(iv) all temporary or permanent changes to operating procedures that could significantly and adversely affect nuclear safety.

(v) All temporary or permanent modifications to the fuelling machines or to their controls.



(c) Prior approval of CNCAN shall be obtained for:


(i) all permanent changes to active parts Special Safety Systems and the Reactor Regulating System.

(ii) all temporary changes to the operational parts of the Special Safety Systems and the Reactor Regulating Systems.


Note: The trip parameters of the Shutdown Systems (SDS1, SDS2) included in the Appendix A.3, Note 3 and Appendix A.4, Note 3 can be temporary changed without CNCAN approval if the reactor power from the ion chambers is below 2x10-7FFP.


(iii) all permanent changes to any station system that could affect the current licensing documentation.

(iv) all temporary changes to any system that could significantly and adversely affect nuclear safety.


(v) all temporary or permanent changes to operating procedures that could significantly and adversely affect nuclear safety.


Replacement components shall preferably be identical to original component. Non identical replacement components can be used in accordance with procedures approved by Station Manager and CNCAN.



All operating personnel authorized by CNCAN shall be kept informed of modifications or changes to procedures which may affect the ability to control reactor power, cool the fuel or contain radioactivity.



Unavailability of Special Safety Systems



CNCAN prescribes a mandatory unavailability target of 10-3 year/year for each of the four Special Safety Systems.


The occurrence of random failures and the unavailability of components due to testing or maintenance, are anticipated in the design. Sufficient redundant components are provided such that each Special Safety System would still be capable of performing in accordance with the design intent even with significant component failures present.


The Special Safety System impairments assumed to be present for the purposes of ensuring adequate availability are summarized in the Appendix to this document and represent the limiting conditions which may be tolerated during normal operation. Any further degree of impairment, while not necessarily being unsafe, would not be tolerable since the adequacy of the special safety system, in that state of impairment, may not have been demonstrated.



The failure of a component in a Special Safety System does not contribute to the unavailability or impairment of the system, after the component is placed in a safe state, or if conditions are formally established under which the system is not required to be available.


If a Special Safety System is found to be impaired then action shall be taken as described in the Unit-2 Impairment Operating Manual.

GENERAL: ASPECTE DE SECURITATE NUCLEARA LEGATE DE OPERARE


Modificari


(a) Aprobarea prealabila a Sefului de Tura trebuie obtinuta pentru urmatoarele activitati :


(i) orice modificare temporara, pentru oricare sistem din Centrala;

(ii) orice modificare temporara a procedurilor de exploatare aprobate.


(b) aprobarea prealabila a Directorului de Centrala trebuie obtinuta pentru:


(i) orice modificare permanenta, pentru oricare sistem din Centrala;

(ii) orice modificare temporara pentru sistemele speciale de securitate si pentru sistemul de reglare a reactorului.

(iii) orice modificare temporara a unui sistem de securitate din Centrala care ar putea afecta semnificativ si advers securitatea nucleara.

(iv) orice modificare permanenta sau temporara a procedurilor de exploatare care ar putea afecta semnificativ si advers securitatea nucleara.

(v) orice modificare permanenta sau temporara a masinii de incarcat-descarcat sau a logicii de control a acesteia.


(c) aprobarea prealabila a CNCAN trebuie obtinuta pentru:


(i) orice modificare permanenta pentru partile active ale Sistemelor Speciale de Securitate sau Sistemului de Reglare a Reactorului.

(ii) orice modificare temporara a partilor active ale Sistemelor Speciale de Securitate si a Sistemului de Reglare a Reactorului.


Nota: Parametrii conditionati ai sistemelor de oprire rapida (SOR1, SOR2) descrisi in Anexa A.3, Nota 3 si Anexa A.4, Nota 3, pot fi modificati temporar fara aprobarea CNCAN numai in cazul in care puterea reactorului citita de camerele de ionizare este sub 2x10-7FFP.


(iii) orice modificare permanenta la oricare sistem din Centrala care ar putea afecta documentatia de autorizare in vigoare.

(iv) orice modificare temporara la oricare sistem din Centrala care ar putea afecta semnificativ si advers securitatea nucleara.

(v) orice modificare permanenta sau temporara a procedurilor de operare care ar putea afecta semnificativ si advers securitatea nucleara.


Componentele initiale vor fi, de preferinta, īnlocuite cu componente identice. Componentele care nu sunt identice cu cele ce urmeaza a fi īnlocuite pot fi folosite īn conformitate cu proceduri aprobate de Directorul de Centrala si CNCAN.


Tot personalul de operare autorizat de CNCAN va fi permanent informat īn legatura cu modificarile sau schimbarile procedurilor care ar putea afecta capacitatea de control a puterii reactorului, de racire a combustibilului sau de retinere a radioactivitatii.


03.02 Indisponibilitatea sistemelor speciale de securitate


CNCAN impune o limita obligatorie de indisponibilitate de 10-3 ani/an pentru fiecare din cele 4 sisteme speciale de securitate nucleara.


Aparitia unor defectiuni īntāmplatoare si indisponibilitatea componentelor datorata testelor sau lucrarilor de īntretinere sunt anticipate prin proiect. Sunt prevazute suficiente componente redundante astfel īncāt fiecare Sistem Special de Securitate sa fie capabil sa functioneze īn conformitate cu intentia de proiect chiar si īn cazul defectarii unor componente semnificative.


Disfunctionalitatile Sistemelor Speciale de Securitate care au fost considerate la definirea starii de disponibilitate acceptabila a acestor sisteme sunt sintetizate īn anexele acestui document si reprezinta conditiile limita care pot fi tolerate īn timpul functionarii normale. Orice alta afectare suplimentara a functionalitatii, chiar daca nu este neaparat īn sens negativ nu va fi tolerata, atāta timp cāt eficacitatea Sistemele Speciale de Securitate pentru aceasta configuratie nu a fost demonstrata.


Defectarea unui component al Sistemelor Speciale de Securitate nu contribuie la indisponibilitatea sau la afectarea functionalitatii sistemului, daca acel component este plasat īntr-o stare sigura, sau daca se stabilesc conditii īn Centrala pentru care disponibilitatea sistemului nu este necesara.


Īn cazul īn care pentru Sistemele Speciale de Securitate sunt descoperite disfunctionalitati se va actiona īn conformitate cu cele descrise de Manualul de Operare "Disfunctionalitati", pentru Unitatea 2.



Maintenance


Maintenance shall be performed to a high standard on all station systems with particular attention being paid to safety related systems following a defined maintenance program to ensure that system effectiveness is retained to meet the design intent.



Any maintenance that could significantly and adversely affect nuclear safety shall require prior approval of the Station Manager.



All failed equipment will be repaired based on a priority which recognizes the importance of the equipment in controlling reactor power, cooling the fuel, or containing radioactivity.



The following policies apply to maintenance of operational parts in any safety related system:

Īntretinerea


Lucrarile de īntretinere ale sistemelor centralei se vor executa la standarde ridicate, atentie speciala acordāndu-se sistemele cu functie de securitate urmarind un program de īntretinere menit sa asigure eficacitatea sistemelor la un grad adecvat, considerat īn intentia de proiectare.


Executarea oricarei lucrari de īntretinere care ar putea influenta semnificativ si advers securitatea nucleara se va face cu aprobarea prealabila a directorului centralei.


Echipamentele defecte vor fi reparate īn baza unor prioritati care tin cont de importanta echipamentelor respective īn realizarea functiilor de control al puterii reactorului, racire a combustibililui sau retinerea radioactivitatii.


Pentru lucrarile de īntretinere la componentele active ale sistemelor cu functie de securitate nucleara se aplica urmatoarele principii:


(a) Upon detection of failure or prior to performing maintenance, on any component, channel or system, the component, channel or system shall be placed in a safe state, if possible, based on system design.



(b) The availability of the remaining redundant system will be assessed before maintenance or repairs. Where there is no additional remaining redundancy, testing will be done, if appropriate and practicable, within one day of the start of the maintenance to confirm system availability during the maintenance period.




(c) Where practicable, maintenance shall be done on only one channel or redundant component at a time, and testing performed prior to returning it to service or before performing maintainance on another redundant component or channel.



Where this method is not practicable, procedures approved by the Station Manager shall be followed, unless conditions have been defined and established under which the system is not required to be available. For Special Safety Systems and the Reactor Regulating System CNCAN concurrence of procedures is required if maintenance is done on more than one channel or component prior to testing and return to service or if testing is not possible.




(d) All discretionary maintenance and modifications on safety related systems have been planned in sufficient detail to keep the equipment outage as short as possible consistent with station operation and maintenance strategy.



(e) Any planned maintenance on a non-redundant standby safety related component, channel or system shall be performed and executed consistent with assumptions claimed in the reliability study and in accordance with procedures approved by the Station Manager, unless it is not required to perform its safety related function.



(f) If a non-redundant standby safety component, channel or system becomes unavailable, necessary maintenance shall be expedited on a priority basis and Station Manager approval given for continued on power operation if the outage is likely to exceed 24 hours.



(g) Maintenance of the Special Safety Systems, the Reactor Regulating Systems and Control Computers shall have Shift Supervisor authorization.


(h) The Shift Supervisor shall be aware of maintenance activities to the extent necessary to ensure that the ability to control reactor power, cool the fuel, or contain radioactive material under all conditions is not impaired by the maintenance.




(a) La detectarea unei defectiuni sau īnainte de efectuarea de lucrari de īntretinere la o componenta, canal sau sistem, componenta, canalul sau sistemul vor fi plasate īntr-o stare sigura, unde acest lucru este posibil, īn baza proiectului sistemului.


(b) Disponibilitatea sistemului redundant se va evalua inaintea intretinerii sau reparatiilor. Īn cazul īn care plasarea componentei/sistemului īn starea sigura nu se poate realiza, se va verifica disponibilitatea elementelor/sistemelor redundante, pe cāt posibil cu o zi īnainte de īnceperea lucrarilor, pentru a confirma disponibilitatea functiei de securitate a sistemului pentru perioada de īntretinere.


(c) Acolo unde este posibil, lucrarile de īntretinere vor fi efectuate asupra unui singur canal sau component redundant, iar testarea acestora se va face īnainte de repunerea lor īn functiune sau de īnceperea unor lucrari de īntretinere la alt canal sau component redundant.


Acolo unde aceasta metoda nu este aplicabila, se vor folosi proceduri aprobate de Directorul Centralei exceptie facānd cazurile cānd au fost definite si stabilite conditii īn Centrala care nu necesita disponibilitatea sistemului afectat. Pentru Sistemele Speciale de Securitate si pentru Sistemul de Reglare al Reactorului este necesara acceptarea prealabila de CNCAN a procedurilor pentru cazurile īn care lucrarile de īntretinere se efectueaza pe mai mult de un canal sau componenta, īnainte de testare si punere īn functiune sau daca testarea nu este posibila.


(d) Toate lucrarile de īntretinere sau de modificare a sistemelor speciale de securitate vor fi organizate īn detaliu pentru a permite scoaterea din functiune a echipamentelor un timp cāt mai scurt posibil īn concordanta cu strategia de operare si īntretinere a centralei.


(e) Orice lucrare planificata de intretinere a unui component, canal sau sistem neredundant de securitate pregatit pentru interventie va fi executata īn concordanta cu ipotezele analizelor de fiabilitate si īn baza procedurilor aprobate de Directorul centralei, cu exceptia cazurilor īn care sistemul nu este solicitat sa-si īndeplineasca functia de securitate.


(f) Daca un component neredundant de securitate, desemnat pentru interventie, devine indisponibil, lucrarile necesare de īntretinere vor fi realizate cu prioritate maxima, iar īn situatia īn care se estimeaza ca reparatia va depasi 24 ore, continuarea operarii centralei la putere se va face numai cu aprobarea Directorului centralei.


(g) Lucrarile de īntretinere la Sistemele Speciale de Securitate, la Sistemul de Reglare al Reactorului si la Calculatoarele de Proces trebuie autorizate de Dispecerul Sef de Tura.


(h) Dispecerul Sef de Tura va avea cunostinta de desfasurarea activitatilor de īntretinere īn Centrala, īn masura care este necesara pentru a se asigura ca īn orice conditii aceste lucrari nu afecteaza capacitatea de a controla puterea reactorului, de a raci combustibilul, sau de a retine materialul radioactiv.


03.04 Safe State for Safety Related System Components


Safe state shall be understood to be the state or position that the component, channel or system would assume in performance of its safety function.


If placing a component, channel or system in the safe state would cause increased probability of personnel injury or a system upset, then it shall not be placed in the safe state but the reliability requirements of that system shall be maintained within acceptable limits.


Frequency of Tests on Systems


Special Safety System and other Safety-related systems shall be submitted to regular testing as specified in Station Documents "Surveillance Program (RD-01364-P05), and, "Operating Manuals Tests" (82-01364-SI-C14) where the reliability or effectiveness of equipment can not be inferred from normal operating experience.


The intervals between these tests will be consistent with reliability evaluations, explicitly or implicitly contained in current licensing submissions.


Test procedures should not make any Special Safety System or other safety related system unavailable if the unit is in a state where the system is required to be available.


Where this requirement cannot be satisfied, the system shall be put in safe state during the test or shall be ensured that the unavailability due to testing will not lead to an increase of the system unavailability over the target.



Idependence of Channels and Systems


The designed degree of independence of each channel in channelized systems and between systems shall be maintained at all times.

03.04 Starea sigura pentru componente ale sistemelor cu functii de securitate


Starea sigura va fi īnteleasa ca fiind acea stare sau pozitie pe care componentul, canalul sau sistemul ar avea-o īndeplinindu-si functia de securitate.


Daca plasarea unui component, canal sau sistem īn starea sigura ar determina o crestere a probabilitatii de ranire a personalului sau de defectare a sistemului, atunci acestea nu vor fi plasate īn starea sigura dar cerintele de fiabilitate pentru sistemul afectat vor trebui sa fie mentinute īn limite acceptabile.


Frecventa de testare a sistemelor


Sistemele Speciale de Securitate si alte sisteme cu functii de securitate nucleara vor fi testate regulat īn conformitate cu Documentul de Referinta "Programul de supraveghere a Centralei" (RD-01364-P05) si " Manualul Testelor de Operare" (82-01364-SI-C14) pentru cazurile īn care fiabilitatea sau eficacitatea echipamentelor nu pot fi determinate.

Intervalele dintre aceste teste vor fi īn conformitate cu evaluarile de fiabilitate continute implicit sau explicit īn documentatiile suport de autorizare īn vigoare.

Procedurile de testare nu trebuie sa faca indisponibile Sistemele Speciale de Securitate sau alte sisteme cu functie de securitate, daca centrala se afla īntr-o stare īn care sistemele respective trebuie sa fie disponibile.

In cazul in care aceasta cerinta nu poate fi respectata sistemele vor fi plasate intr-o stare sigura pe parcusul efectuarii testului sau se va asigura ca indisponibilitatea datorata testarii nu va conduce la depasirea indisponibilitatii impuse sistemului.


Independenta canalelor si sistemelor


Tot timpul va fi mentinut gradul proiectat de independenta pentru fiecare canal īn cadrul sistemelor ce contin canale logice ca si īntre sistemele Centralei.


GENERAL: REPORTING


Reporting Modifications to CNCAN


The following shall be reported to CNCAN quarterly regardless of whether prior approval has been granted in accordance with section 03.01:


a)       Any modification to:

i)   fuel

ii)  Special Safety Systems


b)       Any significant modification to:

i)   Safety Related Systems and operating procedures related to safety related systems

ii)  responsibilities of authorized operating personnel


Reporting of Incidents


CNCAN shall be informed promptly of incidents in accordance with Reportable Events Report (SI-01365-P13).



Annual Report to CNCAN


A review of station safety performance, including a summary of records and reports produced in accordance with sections 04.01 and 04.02, shall be sent to CNCAN at least annually.

GENERAL: RAPORTARI


Raportarea modificarilor catre CNCAN


Trimestrial se va raporta la CNCAN, chiar daca anterior au fost prezentate CNCAN-ului pentru aprobare conform sectiunii 03.01, urmatoarele:


a)      Orice modificare la:

i)   combustibilul nuclear

ii)  Sistemele Speciale de Securitate


b)      Orice modificare importanta la:

i)  sistemele cu functie de securitate si procedurile de exploatare pentru acestea

ii) responsabilitatile personalului de exploatare autorizat



Raportarea incidentelor


CNCAN va fi prompt informat despre incidentele care au loc īn Centrala īn conformitate cu Instructiunea de Centrala " Evenimente raportabile catre CNCAN" (SI-01365-P13).


Raportul anual catre CNCAN


Un raport al performantelor Centralei din punct de vedere al securitatii nucleare, incluzīnd un rezumat al informatiilor din sectiunile 04.01 si 04.02, va fi īnaintat la CNCAN, cel putin o data pe an.


Operating Records


Records shall be maintained of operation, maintenance, testing, and personnel radiation exposures, chemical and radioactivity releases and licensed material as required to meet regulatory requirements.

Inregistrari īn operare


Activitatile de operare, intretinere, testare, precum si expunerile personalului la radiatii, eliberarile de radioactivitate sau de materiale chimice ca si materialele speciale aflate sub control CNCAN vor fi tinute īn evidenta īn conformitate cu cerintele de reglementare aplicabile.


SITE


Exclusion Area


There shall be no permanent habitation within the Exclusion Zone. Use of the land within the Exclusion Zone for other than licensed activities shall require CNCAN approval.



The Exclusion Zone, which extends to a radius of 1000 meters from the reactor building, shall be posted in a manner acceptable to the CNCAN.



Contingency Plans


In order to ensure that no radiological or conventional contingency poses a threat to the general public or to operating personnel on site and off site, contingency plans will be maintained in cooperation with National jurisdictions in accordance with RD-01364-RP8 "On-site Radiation Emergency Plan".




Security


In order to ensure that the security of the Nuclear Power Plant is maintained, security activities as per Physical Security Plan (RD 01364-A1) shall be carried out.

AMPLASAREA


Zona de excludere


Īn zona de excludere nu vor exista asezari umane cu caracter permanent. Desfasurarea oricarei activitati īn interiorul zonei de excludere care nu a fost in prealabil autorizata, necesita aprobarea CNCAN.


Zona de excludere, care se īntinde pe o suprafata cu raza de 1000 metri de la cladirea reactorului, trebuie sa fie marcata īntr-un mod acceptat de CNCAN.


Planuri de urgenta


In conformitate cu Documentul de Referinta, "Plan de Urgenta Radiologica pe Amplasament" (RD-01364-RP8) planurile de urgenta pe amplasament si īn afara amplasamentului vor fi mentinute operationale īn cooperare cu organismele nationale abilitate pentru a se asigura ca nici o situatie de urgenta radiologica sau conventionala indusa de Centrala nu va pune īn primejdie populatia si personalul de exploatare.


Protectie fizica


Pentru asigurea securitatii CNE Cernavoda U2 vor fi mentinute masuri de securitate īn conformitate cu Documentul de Referinta "Protectia Fizica" (RD-01364-A1).



BUILDING & STRUCTURES


Containment System Availability


(See Appendix A.1, A.5)


The Containment System shall be operated and maintained to maximize availability.


(a) In the event that Containment becomes unavailable during normal operation, then action shall be taken as stipulated in Appendix A.5.


(b) Containment systems shall only be made unavailable when the requirements specified in Appendix 5 item 5.3, are met.


Containment System Leakage


(See Appendix A.5)


Operation of the Nuclear Power Plant shall be conducted so as to maintain the integrity of the containment structure and all other containment sub-systems.


The reactor shall remain in GSS if the measured leakage rate exceeds the licence limit of 0.5% of contained volume per day at 1.24 bar.


CLADIRI SI STRUCTURI


Disponibilitatea Sistemul Anvelopei


(Vezi Anexele A.1, A.5)


Sistemul Anvelopei va fi exploatat si īntretinut astfel īncāt disponibilitatea lui sa fie maxima.


(a) Daca īn timpul exploatarii normale a Centralei Sistemul Anvelopei devine indisponibil actiunile luate vor fi īn acord cu prevederile Anexei A.5.


(b) Sistemele anvelopei pot fi indisponibilizate numai atunci cānd conditiile specificate la punctul 5.3 al Anexei A.5 sunt indeplinite.


Scapari din Sistemul Anvelopei


(Vezi Anexa A.5)


Operarea centralei va fi realizata astfel īncāt sa se mentina integritatea structurii anvelopei ca si a tuturor subsistemelor componente ale

acesteia.


Reactorul va ramine in starea de oprire garantata daca rata de scurgeri masurata depaseste limita de autorizare de 0.5% din volumul cladirii reactorului pe zi la presiunea de 1.24 bari.


Containment Testing


The Containment systems shall be tested at regular intervals, in accordance with the reliability analysis approved by CNCAN.


Reactor Building Access Control


All regulations concerning access to specified areas of the Reactor Building shall be observed. No attempt shall be made to bypass or defeat the intent of any automatic interlock unless a greater hazard would be posed by failure to take such action, or an approved Safety Work Plan is in effect.



Normal entry to access-controlled area shall be in accordance with Radiation Protection Regulations, (RD-01364-RP9).



Breaches of Containment


The containment envelope shall not be deliberately breached unless the reactor is in a Guaranteed Shutdown State, the Primary Heat Transport System coolant temperature is below 90 C, and prior approval of the Station Manager and CNCAN has been obtained.

Testarea Anvelopei


Sistemele anvelopei vor fi testate la intervale regulate de timp īn conformitate cu cerintele analizelor de fiabilitate aprobate de CNCAN.


Controlul accesului īn cladirea reactorului


Toate reglementarile legate de accesul in diferite zone ale cladirii reactorului vor fi respectate. Se va evita orice īncercare de inhibare sau modificare a scopului interblocajelor automate pentru accesul īn cladirea reactorului īn afara cazurilor īn care neefectuarea acestui lucru ar conduce la un pericol mai mare sau cānd exista un Plan cu Masuri Speciale de Securitatea Muncii īn acest scop.


Īn mod normal intrarea īn zonele cu acces controlat se va face īn conformitate cu Documentul de Referinta "Regulamentul de Protectie contra Radiatiilor", (RD-01364-RP9).


Deschideri ale Anvelopei


Anvelopa nu va fi deschisa deliberat decāt īn cazul īn care reactorul este īn stare de oprire garantata, temperatura agentului primar de racire este sub 90 C si aprobarea prealabila a Directorului Centralei si a CNCAN-ului a fost obtinuta.



REACTOR, BOILERS & AUXILIARIES: GENERAL


Power Limits


(See Appendix A.9)


The reactor shall be operated so as to reduce the anticipated incidence of fuel sheath defects to an acceptable minimum. No fuel bundle shall be operated with centre-line melting of the fuel. In addition, no fuelling strategy shall be adopted which would tend to invalidate the Safety Analysis detailed in FSAR.




From these general requirements the specific limits for bundle, channel, and reactor core are stipulated in Appendix A.9.



REACTORUL, GENERATORII DE ABUR SI AUXILIARELE: GENERAL


Limite de putere


(Vezi Anexa A.9)


Reactorul va fi astfel exploatat īncāt aparitia unor defectari anticipate ale tecii combustibilului sa fie redusa la un minimum acceptabil. Nici unul din fascicolele de combustibil din zona activa nu va atinge temperatura de topire īn regiunea Centrala. Īn plus nu se va adopta o strategie de īncarcare/ descarcare cu combustibil care ar tinde sa invalideze rezultatele analizelor de securitate ce stau la baza RFS.


Īn baza acestor cerinte generale, īn Anexa A.9 sunt prezentate limitele specifice de putere pentru fascicolul de combustibil, canalul de combustibil si pentru zona activa a reactorului.

Reactivity Control


(See Appendix A.9)


Reactivity in the core shall be controlled to limit possible overpower transients.



(a) The reactor shall be operated such that the Reactor Regulating System, acting alone, is capable of introducing sufficient negative reactivity to shut it down.


(b) The rate of fuelling shall be limited such that the concentration of soluble poison in the moderator is restricted to the value given in Appendix A.9.


(c) The fuel shall consist of only natural or depleted uranium dioxide assembled in bundles of approved design. Prior approval of CNCAN shall be obtained for any specified change in composition or design.



(d) The void coefficient (void reactivity) shall not be modified by adding poison to the

primary coolant. The isotopic concentration of the coolant shall be limited as per Appendix A.9.


Reactor State


The reactor shall always be maintained either critical, or in a guaranteed shutdown state or in an active and monitored transition to one of these conditions.


Approach to Critical


Approach to critical shall be according to procedures approved by the Station Manager.


Controlul reactivitatii


(Vezi Anexa A.9)


Reactivitatea zonei active va fi controlata astfel incāt aparitia unor posibili tranzienti de supraputere sa fie limitata.


(a) Reactorul va fi astfel operat īncāt Sistemul de Reglare al Reactorului actionānd singur sa fie capabil sa introduca suficienta reactivitate negativa pentru oprirea reactorul.


(b) Rata de īncarcare cu combustibil trebuie sa fie astfel limitata īncāt concentratia otravurilor solubile īn moderator sa nu depaseasca valoarea limita data īn Anexa A.9.


(c) Combustibilul va consta numai din bioxid de uraniu natural sau saracit asamblat īn fascicule īn conformitate cu proiectul aprobat. Orice modificare īn compozitia sau īn proiectul combustibilului va trebui sa fie aprobata īn prealabil de CNCAN.


(d) Coeficientul de vid (reactivitatea de vid) nu va fi modificat prin adaugarea de otrava īn

circuitul primar. Concentratia izotopica a agentului de racire va respecta limitarea impusa īn Anexa A.9.


Starea Reactorului


Reactorul va fi tot timpul mentinut critic sau īn Stare de Oprire Garantata sau īntr-o stare monitorata de tranzitie activa spre una din aceste stari.


Apropierea de criticitate


Apropierea de criticitate se va face īn conformitate cu procedurile aprobate de Directorul Centralei.



REACTOR BOILERS AND AUXILIARIES: MODERATOR


(See Appendix A.10)


Moderator System


The moderator is required for the cooling, integrity and operational readiness of various reactor systems including a number of reactivity control devices.


The moderator temperature, level, and flow shall be maintained at values sufficient to ensure adequate cooling of calandria structures and reactivity control mechanisms.



Cover Gas Deuterium Concentration



In order to eliminate the possibility of an explosive cover gas mixture the reactor shall be shut down in an orderly manner if the concentration of deuterium plus hydrogen in cover gas system exceeds 4% by volume for more than 1 hour or should be immediately shutdown if the concentration is confirmed to exceed 6% by volume.


Moderator Purification


Except during a planned approach to criticality, the moderator purification system shall not be operated while the reactor is sub-critical.


REACTORUL, GENERATORII DE ABUR SI AUXILIARELE: MODERATORUL

(Vezi Anexa A.10)


Sistemul moderatorului


Moderatorul este necesar pentru racirea, mentinerea integritatii si a capacitatii functionale a diferitelor sisteme ale reactorului care includ si un numar de dispozitive de control a reactivitatii.


Temperatura, nivelul si debitul sistemului moderator vor fi mentinute la valori suficiente pentru a asigura o racire adecvata a structurilor calandriei si a mecanismelor de control reactivitate.


Concentratia de deuteriu īn gazul de acoperire


Pentru a elimina posibilitatea formarii unui amestec exploziv īn gazul de acoperire, reactorul va fi oprit īn mod controlat daca concentratia volumetrica de deuteriu si hidrogen īn sistemul de gaz de acoperire depseste 4% pentru o perioada mai mare de 1 ora, sau va fi oprit imediat cind este confirmata o concentratie volumetrica ce depaseste 6%.


Purificare moderator


Cu exceptia cazurilor cānd se efectueaza o apropiere planificata de criticitate, sistemul de purificare moderator nu va fi utilizat cānd reactorul este sub-critic.


Moderator as the ultimate Heat Sink


(See Appendix A.10)


To ensure an ultimate heat sink for fuel under certain accident conditions, the moderator shall be operated to maintain the operating configuration as defined in Appendix A.10.


Moderatorul ca ultima sursa de racire


(Vezi Anexa A.10)


Pentru asigurarea unei surse ultime de racire pentru combustibil īn anumite conditii de accident, sistemul moderator va fi exploatat astfel īncāt sa fie mentinuta configuratia definita īn Anexa A.10.







REACTOR, BOILERS & AUXILIARIES: HEAT TRANSPORT



Primary Coolant


Operating and maintenance procedures shall ensure that every fuel bundle in the reactor is adequately cooled at all times.


(a) The reactor power shall be limited to 2 percent of full power unless all four primary pumps are running. 


(b) An appropriate flow rate shall be maintained in each fuel channel at all times. During the startup following a prolonged outage or any outage when the heat transport system has been opened, a systematic check of channel exit temperatures is to be made at different power levels, starting at 10% FP and power shall not be raised further than 80% until adequate channel flows have been confirmed.




(c) At least quarterly the flowrate in each channel shall be verified to detect degradation in channel flow.



(d) During all on-power refuelling operations, the respective channel exit temperature or flow rate shall be monitored continuously.


If refuelling was performed at power less than 25% FP then channel flow verifications shall be performed during power increases.


(e) If indications of low flow arise, during refuelling or otherwise, the reactor power shall be reduced until all channel exit temperatures are sub-cooled by a margin of not less than 5 C, and power shall not be raised until it has been confirmed that all channel flows are normal.







Heat Sink Availability


(See Appendix A.15)


A heat sink capable of rejecting the heat liberated in the primary coolant is to be available at all times.


In addition, to ensure defence in depth for fuel cooling, at all times operation and maintenance must be planned and performed in such a way as to ensure that at least one credited alternate means of cooling the core is available. The credited alternate may be fully available, available within the required recall time or available with a power reduction as specified in the operating documents.



Failed Fuel Detection


When the reactor is operating at high power, then either the Gaseous Fission Product Monitor shall be available and in service, or alternatively manual sampling and analysis of the activity in each heat transport loop shall be conducted at least once per shift.


Primary Heat Transport System


(See Appendix A.11)


The plant is to be operated in such a manner as to minimize the risk of loss of primary inventory through equipment failure or through openings in the primary pressure boundary created during maintenance.


To comply with this:


(a) Chemical parameters in the primary and secondary coolant are to be maintained within the acceptable limits.


(b) Relief valve setpoints, reactor trip setpoints and operating procedures shall ensure that the primary coolant pressure is limited to 117.5 bar under upset conditions, as measured at the outlet headers.



(c) Maintenance procedures shall minimize the size and duration of unavoidable breaches of the primary pressure boundary.




(d) All repairs to, or modifications of, the primary pressure boundary shall be of a high quality and shall conform to all applicable codes and standards.


(e) Heating and cooling rates of primary and secondary components shall be controlled within limits in accordance with the design.


D2O Storage Tank Inventory


(See Appendix A.11)


The quantity of heavy water in the heat transport D2O storage tank shall normally be maintained above a minimum level.


Heat Transport System Leakage


(See Appendix A.11)


The integrity of the heat transport pressure boundary shall be monitored through surveillance. Any indication of an abnormal condition shall be promptly investigated and appropriate corrective action taken as necessary.


Upon indication of leak rates exceeding the limits stated in Appendix A.11 the reactor will be shutdown. Following the reactor shutdown the primary circuit shall be cooled below 90 C and depressurized as specified in the appropriate procedure.


Heat Transport Iodine Limit


(See Appendix A.11)


The plant is to be operated in such a manner as to minimize the release of radioactivity in the event of a loss of coolant accident. The quantity of radio-iodine in the heat transport system shall normally be maintained as low as reasonably achievable. The reactor shall be shut down if the limit in Appendix A.11 is exceeded.

REACTORUL, GENERATORII DE ABUR SI AUXILIARELE: TRANSPORTUL CALDURII


Agentul de racire primar


Procedurile de exploatare si īntretinere vor asigura o racire adecvata a fiecarui fascicul de combustibil din reactor pe tot parcursul operarii reactorului.


(a) Reactorul nu va fi operat la o putere mai mare de 2% din putere nominala decāt cu toate cele 4 pompe ale circuitului primar īn functiune.


(b) Debitul corespunzator de agent de racire va fi mentinut īn permanenta pentru fiecare canal de combustibil. In timpul pornirii dupa o oprire prelungita sau īn care sistemul de transport caldura a fost deschis, se va face o verificare sistematica a temperaturilor de iesire din canalele de combustibil la diferite nivele de putere cu īncepere de la 10% FP. Puterea reactorului nu va fi crescuta mai mult de 80%FP pana nu se confirma ca un debit corespunzator pentru fiecare nivel de putere, strabate fiecare canal de combustibil al reactorului.


(c) Pentru detectarea eventualelor degradari ale circulatiei agentului de racire prin canalele de combustibil se va efectua o verificare a debitelor pentru fiecare canal cel putin trimestrial.


(d) Īn timpul reīncarcarii cu combustibil cu reactorul la putere, temperatura de iesire sau debitul pe canalul afectat vor fi monitorate continuu.


Daca reīncarcarea cu combustibil a fost facuta la o putere mai mica de 25% PN atunci verificarile debitelor pe canal se vor face cu ocazia cresterilor de putere.

(e) Daca īn timpul reīncarcarii cu combustibil sau īn orice alta situatie īn timpul exploatarii reactorului, apar indicatii de debit scazut pe canal, puterea reactorului va fi redusa pāna cānd temperatura la iesirea din canale indica o subracire mai mare de 5 C. Puterea reactorului nu va fi crescuta decāt dupa ce se confirma ca debitele pe canale sunt cele normale.




Disponibilitatea sursei de racire


(Vezi Anexa A.15)


Tot timpul o sursa rece capabila sa īndeparteze caldura eliberata de combustibil īn agentul de racire primar va fi disponibila.


In plus, pentru a se respecta conceptul de aparare in adincime referitor la racirea combustibilului activitatile de operare si intretinere vor fi planificate si se vor desfasura astfel incit tot timpul sa se asigure ca cel putin o modalitate alternativa creditata de racire a zonei active este disponibila. Aceasta modalitate alternativa pentru racire poate fi disponibila imediat, sau intr-un interval de timp sau īn conditiile unei reduceri de putere a reactorului in conformitate cu documentele de exploatare.


Detectarea combustibilului defect


Cānd reactorul este la putere, sistemul de monitorare a produsilor de fisiune gazosi trebuie sa fie disponibil si īn functiune, sau daca nu, cel putin o data pe tura se vor lua probe din fiecare bucla a circuitului primar pentru determinarea activitatii acestora.


Sistemul primar de transport al caldurii


(Vezi Anexa A.11)


Centrala va fi operata, astfel īncāt riscul pierderii inventarului de agent primar ca urmare a defectarii unor echipamente sau prin deschiderile incintei sub presiune a circuitului primar practicate īn cursul activitatilor de īntretinere sa fie minim.


Īn vederea realizarii acestei prevederi:


(a) Parametrii chimici īn sistemul de racire primar si secundar se vor mentine īn limite acceptabile.



(b) Valorile fixate pentru deschiderea supapelor de siguranta, declansarea reactorului si procedurile de operare, vor asigura chiar si pentru conditii anormale ca presiunea īn colectorii de iesire ai circuitului primar nu depaseste valoarea de 117.5 bar.


(c) Īn timpul activitatilor de īntretinere care fac inevitabila deschiderea incintei sub presiune a circuitului primar, procedurile aplicate vor avea īn vedere reducerea la mimim a marimii si duratei acestora.


(d) Toate reparatiile si modificarile incintei sub presiune a circuitului primar vor fi de īnalta calitate si conforme cu toate codurile si standardele aplicabile.


(e) Rata de īncalzire si racire a componentelor circuitului primar si secundar va fi controlata īn limitele indicate prin proiect.


Inventarul rezervorului de stocare D2O


(Vezi Anexa A.11)


Cantitatea de apa grea din rezervorul de stocare D2O agent primar va fi īn mod normal mentinuta peste nivelul minim prestabilit.


Scurgerile sistemului de transport al caldurii


(Vezi Anexa A.11)


Integritatea incintei sub presiune a circuitului primar va fi monitorata prin supraveghere. Orice indicatie privind existena unor conditii anormale va fi prompt investigata si se vor lua masuri corective corespunzatoare.


Daca exista indicatii ca rata scurgerilor depaseste valorile limita mentionate īn Anexa A.11 reactorul va fi oprit. Dupa oprirea reactorului, circuitul primar va fi racit sub 90 C si depresurizat īn conformitate cu procedurile aplicabile.



Limita de iod īn sistemul de transport al caldurii

(Vezi Anexa A.11)


Centrala va fi astfel operata īncāt īn eventualitatea unui accident de pierdere a agentului de racire, eliberarea de radioactivitate sa fie minima. Cantitatea de iod radioactiv īn sistemul de transport al caldurii va fi limitata la un nivel cāt mai coborāt rezonabil de realizat. Reactorul va fi oprit, daca valoarea specificata īn Anexa A.11 este depasita.



REACTOR BOILER AND AUXILIARIES: AUXILIARIES


End Shield Cooling System


(See Appendix A.12)


The end shields and shield tank shall be maintained at levels and temperatures adequate to prevent thermal distortion of calandria components, and to ensure acceptable attenuation of radiation from the core.


ECC System Availability


(See Appendix A.2, A.6)


The Emergency Core Cooling (ECC) System shall be operated and maintained to maximize availability.


To comply with this requirement, the following actions shall be taken:


(a) In the event that ECC becomes unavailable when it is required then action shall be taken as stipulated in Appendix A.6.


(b) ECC shall only be blocked or made unavailable when the requirements specified in Appendix A.6, item 6.3 are met.


REACTORUL, GENERATORII DE ABUR SI AUXILIARELE: AUXILIARELE


Sistemul Protectii de Capat


(Vezi Anexa A.12)


Protectiile de capat si chesonul calandria vor fi mentinute cu apa la nivele si temperaturile adecvate pentru a preveni deformarile termice ale componentelor calandriei si pentru atenuarea la un nivel acceptabil a radiatiilor dinspre zona activa.


Disponibilitatea Sistemului de racire la avarie a zonei active (SRAZA)

(Vezi Anexele A.2, A.6)


Sistemul de racire la avarie a zonei active (SRAZA) va fi operat astfel īncāt disponibilitatea sa sa fie maxima.


Pentru a fi īn acord cu aceaste cerinte urmatoarele actiuni se impun a fi īndeplinite:


(a) Daca SRAZA devine indisponibil īn timpul exploatarii cīnd este necesar a fi disponibil actiunile care se vor intreprinde vor fi in acord cu Anexa A.6.


(b) SRAZA va fi blocat sau indisponibilizat numai cānd cerintele specificate īn articolul 6.3 al Anexei A.6 sunt īndeplinite.


ECCS Testing


The ECC system shall be tested at regular intervals in accordance with the reliability analysis approved by CNCAN.


Annulus Gas System


(See Appendix A.13)


The Annulus Gas System shall be operated as to maintain its capability to detect fuel channel leakage.




Shutdown Cooling System


(See Appendix A.15)


The Shutdown Cooling System shall normally be available as alternate heat sink. To comply to this requirements, the next actions should be done:


(a) If the system becomes unavailable action shall be taken as stipulated in Appendix A.15.



(b) Availability of the system, shall be demonstrated by routine testing, consistent with reliability claimed for the system.


(c) Any planned unavailability for maintenance or testing shall be consistent with the reliability claimed for the system and shall only be taken when the requirements of Appendix A.15 are met.


Liquid Zone Control System


In order to eliminate the possibility of an explosive cover gas mixture, the reactor shall be shutdown in an orderly manner if the concentration of hydrogen in the cover gas of the Liquid Zone Control System exceeds 4% by volume.



Testarea SRAZA


SRAZA va fi testat la intervale regulate īn conformitate cu analizele de fiabilitate aprobate de CNCAN.


Sistemul Inelar de Gaz


(Vezi Anexa A.13)


Sistemul Inelar de Gaz va fi astfel exploatat incat sa-si mentina capabilitatea de detectie a scaparilor de agent de racire din canalul de combustibil.




Sistemul de Racire la Oprire


(Vezi Anexa A.15)


Īn mod normal Sistemul de Racire la Oprire va fi disponibil ca sursa rece de rezerva. Pentru a fi īn acord cu aceaste cerinte urmatoarele actiuni se impun a fi īndeplinite :

(a) Daca Sistemul de Racire la Oprire devine indisponibil se va actiona īn conformitate cu cele precizate īn Anexa A.15.


(b) Disponibilitatea sistemului va fi demonstrata prin teste periodice īn conformitate cu cerintele de fiabilitate pentru sistem.


(c) Orice indisponibilitate planificata pentru efectuarea lucrarilor de intretinere sau testare va fi in conformitate cu fiabilitatea declarata pentru sistem si se va face numai cand cerintele din Anexa A.15 sunt indeplinite.


Sistemul de control zonal cu lichid


Īn scopul eliminarii pericolului de formare a unui amestec exploziv de gaze, reactorul va fi oprit īn mod controlat īn cazul īn care concentratia volumica a hidrogenului īn gazul de acoperire al sistemului de control zonal cu lichid depaseste 4%.



REACTOR BOILER AND AUXILIARIES: FUEL HANDLING



Fuelling Machines


The fuelling machine may contain radioactive material and also constitutes part of the primary pressure boundary during refuelling operation. The general considerations applicable to the heat transport system therefore apply, together with the following specific requirements:




(a) All refuelling operations must have the prior authorization of the Shift Supervisor or his delegate.


(b) The fuelling machine head shall only be unclamped from a fuel channel; and the closure plug shall only be removed from a fuel channel following confirmation that the appropriate pressure boundary is intact and the leak rate is within acceptable limits.


(c) There shall be no operations involving the transfer of irradiated fuel inside the reactor building while Containment is unavailable, except for those necessary to safely dispose of any irradiated fuel which is being transferred when a containment unavailability is discovered.




(d) In order to limit the number of irradiated fuel bundles at risk in the event of fueling machine failure while refuelling, irradiated fuel shall not be placed in adjacent chambers of a fuelling machine magazine, nor shall irradiated fuel be transferred from one channel to another in the course of routine fuelling. This does not apply in the event that a complete channel must be defuelled.


(e) The use of the fuelling machines on the reactor under any mode of control other than fully automatic must be specifically authorized by the Shift Supervisor except when prompt manual intervention is required in response to indications of an unsafe failure.


(f) The fuelling machine interlock bypass switches are to be left in the "not bypassed" position. The use of these switches must be authorized by the Shift Supervisor. Whenever practicable, the jumpering of one specific set of permissive contacts should be considered preferable.


(g) Following maintenance of a fuelling machine it is to be thoroughly tested and accepted by the Fuel Handling Superintendent or his delegate prior to use on the reactor.



Cooling and Shielding of Irradiated Fuel


Irradiated fuel shall be adequately cooled and shielded at all times.


Irradiated Fuel Storage Capacity



Sufficient spare capacity shall be maintained in the irradiated fuel storage bays to permit the removal of all fuel bundles from the reactor at any time.


Reactor State during Fuelling



Fuelling shall normally be performed with the reactor critical. Subcritical refuelling shall require procedures approved by Station Manager. If the reactor is refuelled while subcritical, a reactivity balance shall be performed before the reactor is next brought critical.


REACTORUL, GENERATORII DE ABUR SI AUXILIARELE: MANIPULAREA COMBUSTIBILULUI


Masinile de īncarcat-descarcat combustibil


Masina de īncarcat-descarcat combustibil poate contine material radioactiv si, de asemenea, constituie parte a incintei sub presiune a circuitului primar īn timpul operatiei de reīncarcare. Consideratiile generale aplicabile sistemului de transport al caldurii vor fi deci aplicabile si masinii de īncarcat-descarcat īmpreuna cu urmatoarele cerinte specifice:


(a) Toate operatiile de reīncarcare trebuie sa fie īn prealabil aprobate de Seful de Tura sau de delegatul acestuia.


(b) Capul masinii de īncarcat descarcat combustibil nu va fi decuplat de la canalul de combustibil si dopul de īnchidere nu va fi īndepartat din canalul de combustibil decāt dupa confirmarea integritatii corespunzatoare a incintei sub presiune si rata de scurgeri este in limitele acceptate.


(c) Īn timp ce anvelopa este indisponibila nu vor fi executate operatii ce implica transferul combustibilului iradiat īn cladirea reactorului. De la aceasta cerinta va face exceptie continuarea operatiilor de transfer necesare depozitarii īn siguranta a combustibilului iradiat care sunt īn curs de desfasurare la momentul īn care este descoperita indisponibilitatea anvelopei.


(d) In timpul reīncarcarii cu combustibil, pentru a limita numarul fasciculelor de combustibil iradiat expuse la risc, īn eventualitatea defectarii masinii de combustibil, nu este permisa plasarea combustibilului iradiat īn statii adiacente ale masinii de combustibil si nici transferul combustibilului iradiat de la un canal la altul. Conditia de mai sus nu se aplica īn cazul īn care un īntreg canal trebuie descarcat.


(e) Folosirea la īncarcarea combustibilului īn reactor a masinii de īncarcat-descarcat īn alt mod decāt cel complet automat se va face numai cu autorizarea Sefului de Tura, exceptānd cazul īn care interventia manuala prompta este necesara ca raspuns la o indicatie de defectare īn directie nesigura.


(f) Comutatoarele de anulare a interblocajelor masinii de īncarcat-descarcat vor fi lasate īn pozitia "not bypassed". Folosirea acestor comutatoare trebuie sa fie autorizata de Seful de Tura. Oricānd este posibil, actiunea de modificare temporara a unui īntreg set de contacte specifice este preferabila.



(g) Dupa o activitate de īntretinere a masinii de īncarcat-descarcat aceasta trebuie sa fie complet testata si acceptata de Seful Compartimentului Manipulare Combustibil sau delegatul acestuia īnainte de cuplarea ei la reactor.


Racirea si ecranarea combustibilului iradiat


Tot timpul combustibilul iradiat va fi racit si ecranat corespunzator.


Capacitatea de stocare a combustibilului iradiat


Īn bazinele de depozitare a combustibilului iradiat se va mentine īn permanenta o capacitate de rezerva, suficienta pentru transferarea tuturor fasciculelor de combustibil din reactor.


Starea reactorului īn timpul īncarcarii combustibilului


Īncarcarea cu combustibil se va realiza īn mod normal cu reactorul critic. Pentru īncarcarea cu combustibil cu reactorul subcritic, sunt necesare proceduri aprobate de Directorul Centralei. Daca reīncarcarea se face cu reactorul subcritic, un bilant al reactivitatii va fi facut īnainte de atingerea urmatoarei criticitati.




REACTOR, BOILERS AND AUXILIARIES: BOILERS



Auxiliary Feed Water


(See Appendix A.15)


The auxiliary feed water system shall normally be available as a back up heat sink.


(a) If the system becomes unavailable, action shall be taken as stipulated in Appendix A.15.



(b) Availability of the system, shall be demonstrated by routine testing.



(c) Any planned unavailability for maintenance or testing shall only be taken when the requirements of Appendix A.15 are met.



Boiler Make-up Water


(See Appendix A.15)


The boiler make-up water system (BMW) shall normally be available as a back up heat sink.



(a) If the boiler make-up system becomes unavailable, action shall be taken as stipulated in Appendix A.15.


(b) Availability of the system shall be demonstrated by routine testing.


(c) Any planned unavailability for maintenance or testing shall only be taken when the requirements of Appendix A.15 are met.


REACTORUL, GENERATORII DE ABUR SI AUXILIARELE: GENERATORII DE ABUR


Sistemul auxiliar de apa de alimentare


(Vezi Anexa A.15)


Īn mod normal sistemul auxiliar de apa de alimentare va fi disponibil ca sursa rece de rezerva.


(a) Daca Sistemul auxiliar de apa de alimentare devine indisponibil actiunile luate vor fi īn acord cu Anexa A.15.


(b) Disponibilitatea sistemului va fi demonstrata prin teste periodice īn conformitate cu cerintele de fiabilitate pentru sistem.


(c) Orice indisponibilitate planificata pentru efectuarea lucrarilor de intretinere sau testare se va face numai cind cerintele din Anexa A.15 sunt indeplinite.


Sistemul de apa de adaos la generatorii de abur

(Vezi Anexa A.15)


Īn mod normal sistemul de apa de adaos la generatorii de abur va fi disponibil ca sursa rece de rezerva.


(a) Daca Sistemul de apa de adaos la generatori de abur devine indisponibil actiunile luate vor fi īn acord cu Anexa A.15.


(b) Disponibilitatea sistemului va fi demonstrata prin teste periodice.


(c) Orice indisponibilitate planificata pentru efectuarea lucrarilor de īntretinere sau testare  se va face numai cind cerintele din Anexa A.15 sunt īndeplinite.






Main Steam Safety Valves


(See Appendix A.14)


(a) The main steam safety valves (MSSV's) shall be routinely tested in accordance with the requirements of the ISCIR.


(b) The MSSV's shall be capable of limiting boiler pressure during a postulated loss of regulation with no other steam discharge path credited.




(c) The ability to pneumatically open the MSSV's shall be demonstrated by routine testing of these valves and circuits at a frequency defined in accordance with the test frequency study approved by CNCAN.

Vane de siguranta pentru evacuarea a aburului viu

(Vezi Anexa A.14)


(a) Vanele de siguranta pentru evacuarea aburului viu (MSSV) trebuie sa fie testate periodic īn conformitate cu cerintele ISCIR.


(b) Vanele de siguranta pentru evacuarea aburului viu vor fi capabile sa limiteze presiunea īn generatorii de abur īn timpul unui accident postulat de pierdere a reglarii fara a credita o alta cale de evacuare a aburului.


(c) Capacitatea de deschidere pneumatica a vanelor de siguranta pentru evacuarea aburului viu va fi demonstrata prin teste periodice īn acord cu studiul de frecventa de testare aprobat de CNCAN.


TURBINE, GENERATOR AND AUXILIARIES


Turbine Protection Valve Testing


The Main Stop Valves, and Intermediate Stop Valves shall be trip tested periodically. These tests shall be performed in such a manner as to minimize the effect on reactor and turbine operation.


Control Valve Testing


The Main Control Valves and Intercept Valves shall be tested periodically for freedom of movement when the turbine generator is operating for prolonged periods at steady state conditions.


Overspeed Trip Mechanism Testing


During operation of the turbine generator, the overspeed bolts and electronic trip shall be tested periodically. Both overspeed trip mechanisms shall be tested periodically by actually overspeeding the turbine generator. Whenever the overspeed trip setting is adjusted, or maintenance work could have disturbed the overspeed trip mechanism, an overspeed test shall be performed on startup.




Turbine to be Shutdown if Turbine Trip System is Suspect to be failed



On any indication that the turbine tripping system is incapable of safely shutting down the unit on overspeed, the turbine generator shall be shut down. Unloading shall be controlled to reduce the risk of a load rejection.



Turbine Loading Rate


The loading rate should be limited in order not to exceed the prescribed thermal stress limits.




Operating Limits of Turbine


Heating and cooling of the turbine shall be controlled in order to maintain eccentricity, differential expansion and the difference between the internal and external temperature of the metal within prescribed limits.


Quality of Turbine Governor Oil


Operating and maintenance procedures shall maintain the quality of the regulating oil within prescribed limits.


Generator Load


The generator load shall be such that the temperature of the windings does not exceed the prescribed limits.


Generator Hydrogen Pressure and Purity



The purity and the pressure of the hydrogen used to cool the generator shall be maintained within prescribed limits during normal operation.


Turbine Control in Manual Mode


The control of the turbine generator in Manual Mode shall be authorized by the Shift Supervisor.


TURBINA, GENERATORUL SI AUXILIARELE


Testarea vanelor de protectie a turbinei


Vanele principale si intermediare de īnchidere rapida vor fi testate periodic. Testele vor fi facute astfel īncāt efectul asupra operarii reactorului si a turbinei sa fie minim.


Testarea vanelor de reglare


Ventilele principale si intermediare de reglaj vor fi testate periodic pentru a demonstra libertatea de miscare atunci cānd turbo-generatorul este exploatat perioade īndelungate īn regim stationar.


Testarea declansarii la supraturatie


In timpul operarii turbo-generatorului, bolturile mecanismului de declansare la supraturatie si declansarea electronica vor fi testate periodic. Ambele mecanisme de declansare la supraturatie vor fi testate periodic prin supraturarea efectiva a turbogeneratorului. Ori de cāte ori este modificat pragul de actionare al declansarii la supraturatie sau au fost executate lucrari de īntretinere care ar fi putut modifica mecanismul de declansare la supraturatie, īnainte de pornire se va face testarea declansarii la supraturatie.


Oprirea turbinei daca dispozitivul de declansare la supraturatie este suspect a fi defect


La orice indicatie ca sistemul de oprire a turbinei este incapabil sa opreasca agregatul īn conditii de siguranta īn cazul aparitiei unei supraturatii, turbogeneratorul va fi oprit. Descarcarea va trebui sa se faca īn mod controlat pentru a reduce riscul aruncarii sarcinii.


Rata de īncarcare a turbinei


Rata de īncarcare a turbinei va fi limitata pentru a nu se depasi eforturile termice prescrise.




Limitele de exploatare ale turbinei


Racirea si īncalzirea turbinei se va face īn mod controlat astfel īncāt excentricitatea, dilatarea axiala diferentiala si diferenta dintre temperatura la interiorul si la exteriorul carcasei (metalului) sa se mentina īn limitele prescrise.


Calitatea uleiului de Comanda al turbinei


Procedurile de operare si īntretinere vor asigura mentinerea calitatii uleiului de Comanda a turbinei īn limitele prescrise.


Sarcina generatorului


Īncarcarea generatorului va fi facuta astfel īncāt temperatura infasurarii generatorului sa nu depaseasca limitele prescrise.


Presiunea si puritatea hidrogenului din generator


Īn timpul functionarii normale presiunea si puritatea hidrogenului folosit pentru racirea generatorului vor fi mentinute īn limitele prescrise.


Controlul turbinei īn modul manual


Controlul turbinei īn modul manual trebuie sa fie autorizat de Dispecerul Sef de Tura.


ELECTRICAL SYSTEMS: GENERAL


Electrical System Maintenance


Any maintenance on electrical supplies to safety related systems should normally be confined to the odd or the even sections, where applicable, at a time. However, the Shift Supervisor has the authority to approve work on the odd and the even sections simultaneously at his discretion provided it does not adversly impact on the capability of any safety related system.


Changes in Output Relay Settings


Station output protection relay settings shall be done in conformity with the requirements of the "Dispecerului Energetic National".



Protective Relaying to be Poised


Normally both primary and backup protective systems shall be poised while the protected apparatus is energized. Either, but not both systems, may be removed from service for maintenance while the apparatus is energized.




If both protective schemes fail while the apparatus is energized, every effort shall be made to restore protection, or the apparatus shall be de-energized without delay.



SISTEME ELECRICE: GENERALITATI


Īntretinerea sistemelor electrice


Orice lucrare de īntretinere la sursele de alimentare cu energie electrica a sistemelor cu functie de securitate nucleara va fi īn mod normal restrānsa la numai una din sectiunile par sau impar. Dispecerul Sef de Tura are īnsa autoritatea de a aproba lucrari simultane pe ambele sectiuni de bare, cu conditia sa nu influenteze negativ eficienta nici unui sistem de securitate.


Modificarea reglajelor prin relee


Reglajele protectiilor prin relee ale instalatiilor electrice de legatura cu Sistemul Energetic National se stabilesc īn conformitate cu cerintele Dispecerului Energetic National.


Releele de protectie sa fie armate


Īn mod normal, cāt timp un echipament este energizat, sistemele sale de protectie, primar si de rezerva, trebuie sa fie amāndoua operationale. Cāt timp echipamentul este deenergizat, oricare dintre aceste doua sisteme de protectie, poate fi scos din functiune pentru īntretinere, dar nu amāndoua īn acelasi timp.


Daca ambele sisteme de protectie se defecteaza īn timp ce echipamentul este energizat, se vor depune toate eforturile pentru restabilirea protectiei sau daca acest lucru nu este posibil, echipamentul īn cauza va fi scos de sub tensiune fara īntārziere.


ELECTRICAL SYSTEMS: STANDBY AND EMERGENCY SYSTEMS


Standby Diesel Generator Unavailability


(See Appendix A.16)



The stand-by Class III power supply shall be operated and maintained to maximize availability.



If the Class III system become unavailable, action as stipulated in Appendix A.16 shall be taken.



Normal Status of Standby Diesel Generators


The normal status of the standby Diesel generators is the two generators available, shutdown and selected to start automatically in the event of a Class IV power failure or LOCA signal, to supply power to the respective 6kV Class III buses. Class III buses shall only be paralleled in accordance with procedures approved by the Station Manager.



Standby Diesel Generator Maintenance



(a) No planned maintenance shall be started on a standby Diesel generator if the other standby generator or the other 6kV Class III bus is unavailable for any reason.



(b) If one standby Diesel generators become unavailable, no operation or maintenance shall be carried out that would increase the probability of a loss of Class IV power, or that would impair the ability to provide for fuel cooling if a total loss of Class IV and III occur.








Standby Diesel Generator Fuel Inventory


(See Appendix A.16)


The standby generator fuel oil reserve shall be sufficient to permit continuous full load operation of either Diesel standby generators for at least 5 days.



Testing of Standby Diesel Generator Units


Standby Diesel generators and the associated starting logic shall be tested regularly.



Testing of Transfer Logic


Periodic testing shall be conducted in order to demonstrate the ability to retain Class IV power on 10 kV and 6 kV buses if either of the normal power supplies be lost, and to demonstrate also the capability for providing standby Class III power if a loss of Class IV power occur.



Normal Status of Emergency Generators



The normal state will be with both emergency power diesels available, shut down and ready to be started manually when necessary.


Availability of Emergency Generators


(See Appendix A.16)


The Emergency power system shall be operated and maintained to maximize availability.



Should the Emergency power system become unavailable, action as stipulated in Appendix A.16 shall be taken.







Emergency Generator Fuel Inventory


(See Appendix A.16)


The emergency power fuel oil reserve shall normally be sufficient to permit continuous operation of either diesel for at least 4 days at full load.


Testing of the Emergency Generators


Both emergency power units shall be tested regularly.


Planned Maintenance of Emergency Generators


Planned maintenance of an emergency power unit may be performed at any time, provided the other unit is available.




SISTEMELE ELECTRICE: SISTEME DE REZERVA SI DE AVARIE


Indisponibilitatea Generatorilor Diesel de Rezerva


(Vezi Anexa A.16)


Sistemul de alimentare cu energie electrica de Clasa III va fi mentinut si exploatat astfel īncāt sa fie maximizata disponibilitatea.


Daca sistemul de alimentare cu energie electrica de Clasa III devine indisponibil actiunile luate vor fi īn acord cu Anexa A.16.


Starea normala pentru generatorii Diesel de rezerva


Starea normala a generatorilor Diesel de rezerva este cu cei 2 generatori disponibili, opriti si selectati pentru pornire automata īn cazul pierderii alimentarii de Clasa IV sau īn cazul unui semnal de pierdere agent de racire, pentru a furniza putere la barele de Clasa III de 6 kV. Barele de Clasa III vor fi puse īn paralel numai īn conformitate cu procedurile aprobate de Directorul Centralei.


Intretinerea Generatorilor Diesel de rezerva


(a) Nu se vor efectua lucrari de īntretinere planificata la un generator Diesel de rezerva īn cazul īn care celalalt generator electric de rezerva sau cealalta bara de 6kV sunt indisponibile din orice motiv.


b) Daca un generator Diesel de rezerva devine indisponibil, nu se vor mai desfasura manevre sau activitati de īntretinere care ar putea sa creasca probabilitatea pierderii alimentarii cu energie electrica de Clasa IV sau care ar afecta negativ capacitatea de racire a combustibilului pentru cazul pierderii totale a alimentarii cu energie electrica de Clasa IV si III.






Inventarul de combustibil al generatorilor Diesel de rezerva

(Vezi Anexa A.16)


Rezerva de combustibil pentru generatorii electrici de rezerva va fi suficienta pentru a permite functionarea continua la sarcina nominala a oricarui din cei doi generatori de rezerva timp de cel putin 5 zile.


Testarea generatorilor Diesel de rezerva


Generatorii Diesel de rezerva si logica de pornire asociata vor fi testate periodic, īn conformitate cu cerintele de fiabilitate pentru sistem.


Testarea logicii de transfer


Se vor efectua teste periodice pentru a demonstra capabilitatea unitatii de a-si mentine alimentarea cu energie de Clasa IV pe barele de 10 KV si de 6 KV la pierderea oricarei dintre sursele de alimentare normala si de asemenea pentru a demonstra capabilitatea alimentarii cu energie electrica de rezerva de Clasa III īn cazul pierderii Clasei IV.


Starea normala pentru generatorii electrici de avarie


Starea normala va fi cu ambele generatoare disponibile, oprite si gata pentru a fi pornite manual cānd este necesar.


Disponibilitatea Generatorilor de Avarie


(Vezi Anexa A.16)


Sistemul de alimentare cu energie la avarie va fi mentinut si operat astfel īncāt disponibilitatea sa fie maxima.


Daca sistemul de alimentare cu energie electrica la avarie devine indisponibil actiunile luate vor fi īn acord cu Anexa A.16.






Inventarul de combustibil al generatorilor de avarie

(Vezi Anexa A.16)


Rezerva de combustibil pentru generatorii de avarie va fi suficienta pentru a permite operarea continua a oricarui generator cel putin 4 zile, la putere nominala.


Testarea generatorilor de avarie


Ambele unitati de alimentare cu energie electrica la avarie vor fi testate periodic.


Intretinerea planificata a generatorilor de avarie


Operatiile de īntretinere planificata a unei unitati de alimentare cu energie electrica de avarie pot fi efectuate īn orice moment, cu conditia ca cealalta unitate sa fie disponibila.


ELECTRICAL SYSTEMS: NORMAL SUPPLIES


Class IV Power Supply


With the unit on line, the preferred normal status of the Class IV 10kV and 6kV distribution buses is with both buses supplied by the Unit Transformer (UST), the Service Transformer (SST) being used as back-up supply. Any other configuration must be authorized by the Shift Supervisor.


SISTEME ELECTRICE: ALIMENTARI NORMALE


Alimentarea cu energie electrica Clasa IV


Starea normala a barelor de Clasa IV de 10 kV si de 6 kV, atunci cānd unitatea este cuplata la retea, este cu ambele bare alimentate din transformatorul unitatii (UST), transformatorul de servicii de sistem (SST) al centralei fiind folosit ca sursa de alimentare de rezerva. Orice alta configuratie va trebui sa fie aprobata de Dispecerul Sef de Tura.


ELECTRICAL SYSTEMS: UNINTERRUPTABLE POWER SUPPLIES


Class I Power Supply


(See Appendix A.16)


The full capability to supply class I power to non-interruptible station loads shall normally be maintained.



Class I batteries shall be kept fully charged.



Any maintenance which results in reduced capability or availability of the Class I supply system shall be carried out using procedures approved by the Station Manager.


If Class I is found to be unavailable then action shall be taken as stipulated in Appendix A.16.



Capability tests shall be done at least every five years to ensure that at least the minimum design capacity exists.


Class II Power Supply


During normal operation, power will normally be supplied to the 380V Class II buses through the two three-phase inverter and to the 220 V bus bars through the three mono-phase inverter.

SISTEME ELECTRICE: ALIMENTAREA NEĪNTRERUPTA CU ENERGIE ELECTRICA


Alimentarea cu energie electrica Clasa I


(Vezi Anexa A.16)


Īn mod normal va fi mentinuta intreaga capacitate de alimentare cu energie electrica Clasa I a consumatorilor centralei ce nu suporta īntreruperi īn alimentare.


Bateriile de Clasa I vor fi mentinute īncarcate la capacitatea maxima.


Toate activitatile de īntretinere care ar conduce la reducerea capacitatii sau disponibilitatii sistemului de furnizare a Clasei I vor fi desfasurate īn baza unor proceduri aprobate de Directorul de Centrala.


Daca alimentarea cu energie electrica Clasa I este indisponibila, actiunile luate vor fi īn conformitate cu Anexa A.16.


Se vor efectua teste de capacitate cel putin o data la 5 ani pentru a se asigura ca este mentinuta capacitatea minima de proiectare.


Alimentarea cu energie electrica Clasa II


Īn timpul operarii normale energia va fi furnizata īn mod normal prin intermediul a 2 invertoare trifazate la barele de Clasa II de 380V si prin intermediul a 3 invertoare monofazate la barele de Clasa II de 220 V.




INSTRUMENTATION AND CONTROL: GENERAL


Control Room Operation


Controls in the main and secondary control rooms, and the associated Control Equipment Rooms, shall only be operated by, or under the direction of, authorized personnel, in accordance with the approved station procedures.



Secondary Control Room


Maintenance and surveillance procedures shall ensure that the availability of the necessary monitoring and control of safety related systems provided in the Secondary Control Area is maximized.


Manual Control of Reactivity Mechanisms



In order to ensure that all safety features built into the automatic regulation are observed, manual control of any reactivity mechanism shall be conducted in accordance with procedures approved by the Station Manager.



Authorization for Increase in Power


Only the Shift Supervisor shall approve the startup or the power increase of the reactor.



Following Setback, Stepback or Reactor Trip, the cause of the transient must be fully understood and corrected as necessary before power is increased.





INSTRUMENTATIE SI CONTROL: GENERALITATI


Activitati īn Camera de Comanda


Activitatile din Camera de Comanda Principala, din Camera de Comanda Secundara si din camerele echipamentelor de control asociate vor fi efectuate numai de catre personalul autorizat sau numai sub directa īndrumare a acestuia, in acord cu procedurile aprobate.


Camera de Comanda secundara


Procedurile de īntretinere si supraveghere pentru camera de comanda secundara vor asigura ca disponibilitatea functiilor de monitorare si control ale sistemelor de securitate aferente acesteia este maxima.


Controlul manual al mecanismelor de control al reactivitatii


Pentru a se asigura ca toate caracteristicile de securitate īnglobate īn controlul automat al sistemului de reglare a reactorului sunt mentinute, controlul manual al oricarui mecanism de control reactivitate va fi efectuat īn conformitate cu proceduri aprobate de Directorul de Centrala.


Autorizarea pentru cresterea puterii


Pornirea reactorului precum si cresterea puterii, vor fi facute numai cu aprobarea Dispecerului Sef de Tura.


Īn urma unui setback, stepback sau a unei declansari de reactor, cauzele ce genereaza tranzientul trebuie sa fie intelese pe deplin si corectate dupa cum este necesar, īnainte de cresterea puterii.

Independence of Regulating and Protective Functions


Independence of both shutdown systems and the regulating system and of each channel of the shutdown systems shall always be maintained to meet the design intent.



Indication of Neutron Flux to be Available



A continuous indication of the neutron flux is required at all times when fuel is present in the reactor. Sufficient ion chambers for both shutdown systems and the Reactor Regulating System must be functioning or the reactor shall be placed in the Guaranteed Shutdown State.




Start-up Instrumentation shall be in service prior to the ion chambers going off-scale low.



Reactivity Device Replacement



The replacement of any reactivity device shall be done while in the Guaranteed Shutdown State.

The replaced reactivity devices shall be placed in a fixed position until they can be checked for reactivity worth at the first opportunity after achieving criticality.


Independenta functiilor de reglare si protectie


Gradul de independenta existent īntre sistemele de oprire rapida ca si dintre acestea si sistemul de reglare, precum si cel existent īntre canalele sistemelor de oprire rapida va fi mentinut tot timpul pentru a satisface intentia de proiectare.


Indicatiilor de flux neutronic sa fie disponibile


Pe tot parcursul operarii centralei indicarea fluxului neutronic este obligatorie cānd combustibilul se afla īn reactor. Un numar suficient de camere de ionizare trebuie sa fie īn stare de functionare pentru cele doua sisteme de oprire iar Sistemul de Reglare a Reactorului trebuie sa fie operational, īn caz contrar reactorul va fi plasat īn starea de oprire garantata.


Instrumentatia de pornire va fi īn functiune īnainte ca semnalul de la camerele de ionizare sa intre sub domeniul de masura.




Īnlocuirea Dispozitivelor de control Reactivitate


Īnlocuirea oricarui dispozitiv de control al reactivitatii se va face doar cu reactorul īn Starea de Oprire Garantata.

Dispozitivele de Control al Reactivitatii care au fost instalate vor fi plasate īntr-o pozitie fixa pāna la prima posibilitate de verificare a caracteristicilor de reactivitate ale acestora prin atingerea criticitatii.



INSTRUMENTATION AND CONTROL: REGULATING SYSTEM


Availability of the Regulating System


If the regulating system is impaired, such that it cannot control bulk power, the reactor shall promptly be placed in the Guaranteed Shutdown State (GSS).


If the regulating system is impaired, such that it cannot control spatial power distribution, the reactor power shall be reduced promptly to a power level less than 2% FP.


If the stepback and/or setback functions of the regulating system are impaired and repairs cannot be made promptly, the reactor shall be shutdown within 48 hours unless Station Manager approval is obtained for continued operation.


Sequence for Withdrawal of Absorber and Adjuster Rods


Rods shall normally be inserted and withdrawn in a sequence in accordance with the design intent.



Reactor Regulating System Maintenance for neutronic instrumentation



The method of performing maintenance, unless the Station Manager has approved an alternative method, shall be to isolate, repair, test, and return one channel to service prior to working on another channel.


Reactor power during such maintenance shall be sufficient to produce reliable neutronic signals from instrumentation, so that proper functioning may be demonstrated. A reactor power level of 10-5 full power or higher will be considered adequate for testing ion chambers; 5% full power or higher for in-core detectors.





When the reactor is critical, above 2% full power, liquid zone control, control absorbers, and liquid poison addition shall be available for insertion of negative reactivity under RRS control unless otherwise approved by the Station Manager.




When the reactor is critical, work shall be allowed on only one RRS reactivity control system at a time.


Testing of Stepback and Setback


The stepback and setback functions of RRS shall be tested regularly consistent with the approved test frequency. 


INSTRUMENTATIE SI CONTROL: SISTEMUL DE REGLARE


Disponibilitatea sistemului de reglare


Daca sistemul de reglare nu mai poate controla puterea globala a reactorului, atunci reactorul va fi imediat plasat īn Starea de Oprire Garantata.



Daca sistemul de reglare nu mai poate sa controleze distributia spatiala a puterii, atunci puterea reactorului va fi redusa prompt la un nivel mai scazut de 2% PN.


Daca functiile de stepback si/sau setback ale sistemului de reglare sunt afectate si reparatiile nu se pot face imediat, reactorul va fi oprit īn 48 ore īn afara de cazul īn care este obtinuta aprobarea Directorului Centralei pentru continuarea operarii.


Secventa de extragere a barelor absorbante si ajustoare


Īn mod normal, barele absorbante si ajustoare vor fi introduse si extrase īn secvente conforme cu intentia de proiectare.


Intretinerea instrumentatiei de masurare a fluxului neutronic a sistemului de reglare al reactorului


Īn afara de cazul īn care Directorul Centralei a aprobat o alternativa, modalitatea de efectuare a lucrarilor de īntretinere va consta din izolarea, repararea, testarea si repunerea īn functiune a unui canal īnainte de īnceperea lucrului la un alt canal.


Puterea reactorului īn timpul īntretinerii RRS va avea un nivel suficient pentru a produce semnale neutronice fiabile pentru instrumentatia de masura si pentru a confirma functionarea corespunzatoare a acesteia. Un nivel de putere de 10-5 putere nominala sau mai mare este considerat potrivit pentru testarea camerelor de ionizare; 5% putere nominala sau mai mare este considerat potrivit pentru testarea detectorilor din interiorul zonei active.


Cānd reactorul este critic la putere mai mare de 2% PN, sistemele de control zonal, barele absorbante de control si adaosul de otrava lichida trebuie sa fie disponibile pentru insertia de reactivitate negativa sub controlul RRS cu exceptia cazului cind Directorul de Centrala a aprobat o alta configuratie.


Cānd reactorul este critic nu se permite efectuarea de lucrari simultane la mai mult de un mecanism de control reactivitate.


Testarea stepback-ului si a setback-ului


Functiile stepback si setback ale sistemului de reglare a reactorului vor fi testate regulat īn conformitate cu frecventa de testare aprobata pentru sistem.




INSTRUMENTATION AND CONTROL COMPUTERS


Control Computer Software Changes



Digital Control computer software changes shall normally be done with systems in a state such that the intended effect is immediately apparent.




One digital control computer shall be worked on first, and put in control after verification and testing, and sufficient time allowed to confirm operation before changes are made to the second computer, in accordance with Commissioning Station Instruction "Control Computer Software Changes" (82-01365-SI-C23).




Access to Computer Memory


Access to core and to protected areas of disk memory of the control computers must be authorized by the Shift Supervisor. Any changes shall be made in accordance with section (66.01) and Commissioning Station Instruction "Control Computer Software Changes" (82-01365-SI-C23).


INSTRUMENTATIE SI CONTROL: CALCULATOARELE


Modificari īn programele de control ale calculatoarelor de proces


Modificarile programelor de control ale calculatoarelor de proces vor fi facute īn mod normal cu sistemele de proces deservite aflate īntr-o configuratie care sa permita constatarea imediata a efectelor urmarite.


Īn conformitate cu Instructiunea Centralei "Modificarile Programelor de Control ale Calculatoarelor Centralei" (82-01365-SI-C23) orice modificare va fi facuta la īnceput pe un singur calculator de proces dupa testare si verificare va fi lasat un timp suficient pentru a putea confirma functionarea īnainte de a face modificarea si īn cel de-al doilea calculator de proces.


Accesul la memoria calculatorului


Accesul la unitatea centrala si la zonele protejate de memorie de pe disc ale calculatoarelor de proces trebuie sa fie autori-zat de catre Seful de Tura. Orice modificari ale acestora se vor face īn conformitate cu clauza 66.01 si cu Instructiunea de Centrala pe durata Punerii īn Functiune "Modificarile Programelor de Control al Centralei" (82-01365-SI-C23).




INSTRUMENTATION AND CONTROL: SHUTDOWN SYSTEMS


Shutdown System Availability


(See Appendix A.3, A.4, A.7, A.8)


The Shutdown Systems (SDS) shall be operated and maintained to maximize availability.



In the event that a SDS becomes unavailable during normal operation, then action shall be taken as stipulated in Appendix A.7, A.8.


If, during normal operation, a trip occurs, the Shutdown system involved shall be re-poised as soon as possible consistent with overall plant safety. When SDS1 is re-poised after being tripped, reactivity shall be controlled so as to ensure the reactor does not go critical on withdrawal of the shut-off rods.



Completed reactor trips shall only be reset following Shift Supervisor approval which shall be given only after the cause of the reactor trip is fully understood, verifying that the condition which caused the trip no longer exists.


Changes to Shutdown System Trip Setpoints


Any changes to the trip set points of the shutdown systems must be authorized by the Station Manager and approved by CNCAN. This requirement is automatically fulfilled if the change is preselected by a handswitch or Programmable Digital Comparator (PDC) provided for this purpose.


The trip parameters of the Shutdown Systems (SDS1, SDS2) included in the Appendix A.3, Note 3 and Appendix A.4, Note 3 can be manually inhibited without CNCAN approval if the reactor power from the ion chambers is bellow 2x10-5FP. Trip parameters inhibition will be removed before disconecting SDS#1 start-up instrumentation (63760) and before power reaches 10-5FP.


Neutron Overpower Trip Effectiveness



The reactor power shall be limited, and overpower trip setpoints shall be set, such that the neutron overpower trips on SDS1 and SDS2 are as effective as is claimed in current licensing submissions, for all analyzed configurations of the mechanical reactivity control devices.


Maintenance of Shutdown Systems


(a) The reactor power during maintenance of the neutron power instrumentation, including linear and rate log power instruments (of either shutdown system) shall be sufficient to produce reliable signals from instrumentation, and to permit testing. 10-5 FP and 5% FP are adequate power levels for ion chamber and in-core detector maintenance respectively.





(b) Maintenance on shutdown systems should normally be arranged such that only one shutdown system is undergoing maintenance at any given time, however the Shift Supervisor has the authority to approve work on both shutdown systems simultaneously, at his discretion.



(c) Whenever practicable, different workers shall be employed on each of the two systems.


Testing of shutdown Systems


Testing of SDS1 and SDS2 shall be performed at regular intervals, in accordance with the reliability analysis approved by CNCAN.


Guaranteed Shutdown State


(See Appendix A.18)


The reactor shall be considered to be in a Guaranteed Shutdown State if there is sufficient negative reactivity to ensure subcriticality in the event of any process failure, and approved administrative safeguards are in place to prevent net removal of negative reactivity.



The guaranteed shutdown state procedures have been approved by the Station Manager and CNCAN, and their prior approval is required for deviation from these procedures.


The guaranteed shutdown state is defined in the Appendix A.18.


The preferred guaranteed shutdown state shall be overpoisoned with the heat transport system depressurized and at least one shutdown system poised. The authority to remove one shutdown system from service when the plant is in GSS belongs to Station Manager. Station Manager and CNCAN approval shall be obtained for entering alternate guaranteed shutdown states.



Station Manager approval is required for surrender of the Guaranteed Shutdown State.


Isotopic Concentration of Neutron Poisons



The isotopic concentration of Boron and Gadolinium salts intended for use as neutron poisons shall be verified prior to their introduction into any reactor system, to ensure that the isotopic concentration (B10 / Gd155-157) is at least as great as natural isotopic abundance.



INSTRUMENTATIE SI CONTROL: SISTEMELE DE OPRIRE RAPIDA


Disponibilitatea sistemelor de oprire rapida

(Vezi Anexele A.3, A.4, A.7, A.8)


Sistemele de Oprire Rapida (SOR) vor fi exploatate si īntretinute astfel īncāt disponibilitatea lor sa fie maxima.


Īn cazul īn care un SOR devine indisponibil īn timpul exploatarii normale, vor fi īntreprinse actiuni īn acord cu Anexele A.7, A.8.


Daca īn timpul operarii normale apare o declansare a unuia din sistemele de oprire rapida, sistemul implicat va fi rearmat cāt mai curīnd posibil, tinānd cont de securitatea nucleara globala a centralei. Cānd SOR1 este rearmat dupa o declansare, reactivitatea reactorului va fi tinuta sub control astfel īncāt sa se asigure ca reactorul nu va deveni critic īn momentul extragerii barelor de oprire. 


Declansarile de reactor vor fi resetate numai cu aprobarea Dispecerului Sef de Tura. Acesta va da aprobarea numai dupa ce a īnteles pe deplin cauza declansarii si a verificat ca acea conditie care a determinat declansarea nu mai exista.


Modificari ale pragurilor de declansare ale sistemelor de oprire rapida


Orice modificare a pragurilor de declansare ale sistemelor de oprire rapida trebuie sa fie autorizata de Directorul Centralei si aprobata de CNCAN. Aceasta cerinta este īndeplinita automat daca modificarea se preselecteaza prin intermediul comutatorului din camera de comanda principala sau Comparatoarelor Digitale Programabile prevazute īn acest scop.

Parametrii conditionati ai sistemelor de oprire rapida (SOR1, SOR2) descrisi in Anexa A.3, Note 3 si Anexa A.4, Note 3, pot fi inhibati manual fara aprobarea CNCAN numai in cazul in care puterea reactorului citita de camerele de ionizare este sub 2x10-5FP. Inhibarea va fi inlaturata inaintea deconectarii instrumentatiei de pornire (63760) de la SDS#1 si inainte ca puterea reactorului sa ajunga la 10-5FP.


Eficacitatea declansarii la supraputere neutronica


Puterea reactorului va fi limitata si pragurile de declansare la supraputere vor fi stabilite astfel īncāt eficacitatea declansarilor SOR1 si SOR2 sa fie īn acord cu documentatia suport de autorizare īn vigoare, pentru toate configuratiile analizate ale dispozitivelor mecanice de control al reactivitatii.


Intretinerea sistemelor de oprire rapida


(a) Īn timpul efectuarii lucrarilor de īntretinere la instrumentatia de masurare a puterii neutronice, inclusiv la instrumentele de determinare a puterii liniare si a ratei logaritmice (pentru ficare dintre sistemele de oprire), puterea reactorului va fi suficienta pentru a produce semnale semnificative pentru instrumentele aferente si pentru a permite testarea. Nivelele de putere 10-5 si 5% putere nominala, sunt adecvate pentru efectuarea activitatilor de īntretinere la camerele de ionizare si respectiv la detectorii de flux din zona activa.


(b) Īntretinerea sistemelor de oprire va fi planificata īn mod normal astfel īncāt la orice moment de timp numai un singur sistem de oprire rapida sa fie afectat de lucrarile de īntre-tinere, totusi Dispecerul Sef de Tura are autoritatea sa aprobe lucrul simultan la ambele sisteme de oprire dupa cum considera necesar.


(c) Pe cāt posibil, pentru fiecare din cele 2 sisteme de oprire rapida vor fi utilizati lucratori diferiti.


Testarea sistemelor de oprire rapida


Testarea lui SOR1 si SOR2 va fi efectuata la intervale regulate, īn conformitate cu analizele de fiabilitate aprobate de CNCAN.


Starea de oprire garantata


(Vezi Anexa A.18)


Se va considera ca reactorul se afla īntr-o stare de oprire garantata, daca exista suficienta reactivitate negativa inserata pentru a se asigura mentinerea subcriticitatii īn cazul producerii oricarei avarii de proces si daca au fost luate masuri administrative aprobate pentru a īmpiedica īndepartarea reactivitatii negative.


Procedurile pentru Starea de Oprire Garantata au fost aprobate de catre Directorul de Centrala si de catre CNCAN, deci orice deviere de la aceste proceduri trebuie sa aiba aprobarea prealabila a acestora.

Starea de oprire garantata este definita īn Anexa A.18.


Starea preferata de oprire garantata va fi cu moderatorul supraotravit, cu circuitul primar depresurizat si cu cel putin un sistem de oprire functional. Autoritatea scoaterii unui sistem special de oprire din functiune cānd centrala este īn starea de oprire garantata este a Directorului de Centrala. Pentru stabilirea unei alte stari de oprire garantata trebuie obtinuta aprobarea Directorului de Centrala si a CNCAN.


Pentru a iesi din Starea de Oprire Garantata este necesara aprobarea Directorului Centralei.


Concentratia izotopica a otravurilor de neutroni


Concentratia izotopica a sarurilor de Bor si Gadoliniu ce urmeaza a fi folosite ca absorbanti de neutroni va fi verificata īnainte de introducerea lor īn orice sistem din Centrala pentru a se asigura ca au o concentratie izotopica (īn B10 respectiv Gd155-157) cel putin la fel de mare ca si concentratia izotopica naturala.



MISCELLANEOUS PLANT SYSTEMS



Raw Service Water, Recirculated Cooling Water and Chilled Water System



The Raw Service Water (RSW), Recirculated Cooling Water System (RCW), and Chilled Water (CW) systems shall be operated and maintained in a manner which ensures their ability to provide a heat sink.


No system shall be taken out of service if such action would conflict with the requirements of alternative heat sink, Containment availability, or ECC availability.


Components of these systems shall be subject to routine testing where claims as to their availability cannot be supported by reference to routine operating experience.


Fire Protection System


The Fire protection system shall be operated and maintained in a manner which ensures its ability to provide fire protection on demand.


The availability of the firewater systems shall be demonstrated by routine testing of pumps and components.


The removal from service of the fire water supply system, the fire detection system, or of portions of these systems, shall be approved by the Shift Supervisor.


Ventilation System


The ventilation system and D2O vapor recovery system shall normally be operated and maintained so as to maintain the following:


a) Maintain the overall flow of air from radiological zones with a low probability of contamination toward zones with a higher probability of contamination.


b) Minimize radioactive releases to the environment.


Unavailability of ventilation systems shall be minimized and steps shall be taken to minimize any spread of contamination.


Emergency Water System


(See Appendix A.17)


The emergency water system shall normally be operated and maintained to maximize availability.



(a) The emergency water system shall be routinely tested.


(b) Any maintenance should be planned and executed consistent with OP&P 03.03.



(c) If the Emergency Water System becomes unavailable, action shall be taken as per

Appendix A.17

SISTEME AUXILIARE ALE CENTRALEI


Sistemul de apa bruta de racire, Sistemul de apa de racire recirculata si Sistemul de apa racita


Sistemele de apa bruta de racire, apa recirculata de racire si de apa racita vor fi operate si intretinute astfel īncāt sa se asigure capacitatea lor de a constitui sursa rece.



Nici unul din sistemele de mai sus nu va fi scos din functiune daca aceasta contravine cerintelor de sursa rece alternativa, disponibilitatea anvelopei, sau disponibilitatea SRAZA.


Componentele acestor sisteme vor fi subiectul testarilor periodice acolo unde cerintele de disponibilitate nu pot fi demonstrate de experienta de exploatare de rutina.


Sistemul de protectie la incendiu


Sistemul de protectie la incendiu va fi operat astfel īncāt, daca este cerut, sa fie asigurata capacitatea de protectie contra incendiilor.


Disponibilitatea sistemului de apa de incendiu va fi demonstrata prin testarea periodica a pompelor si componentelor.


Scoterea din functiune a sistemului de apa de incendiu, a sistemului de detectie a incendiilor sau a unor portiuni ale acestora se va face numai cu aprobarea Dispecerului Sef de Tura.


Sistemul de ventilatie


Sistemul de ventilatie si de recuperare vapori D2O vor fi operate īn mod normal astfel īncāt:



a) Mentinerea unei circulatii a aerului dinspre zonele radiologice cu probabilitate scazuta de contaminare spre zonele cu probabilitate mai mare de contaminare.


b) Minimizarea eliberarilor de radioactivitate īn mediul īnconjurator.


Indisponibilitatea sistemelor de ventilatie va fi minimizata si se vor lua masuri pentru a minimiza orice raspindire de contaminarii.


Sistemul de alimentare cu apa la avarie


(Vezi Anexa A.17)


Sistemul de alimentare cu apa la avarie va fi operat si īntretinut astfel īncāt disponibilitatea sa sa fie maxima.


(a) Testarea sistemului de alimentare cu apa la avarie va fi efectuata periodic.


(b) Orice activitate de īntretinere va fi planificata si executata īn conformitate cu prevederile aliniatului 03.03 al OP&P.


(c) Daca sistemul de alimentare cu apa la avarie devine indisponibil, actiunile īntreprinse vor fi īn acord cu Anexa A.17.


Instrument Air System


The Instrument Air System shall be operated and maintained in a manner which ensures its ability to support the safety related systems.



Instrument Air shall not be used for other purposes except as specified in Operating Manuals or when approved by the Station Manager.

Sistemul de Aer Instrumental


Sistemul de Aer Instrumental va fi operat si īntretinut astfel īncāt sa fie asigurata capacitatea de a sustine functionarea sistemelor cu functie de securitate nucleara.


Aerul Instrumental nu va fi folosit īn alte scopuri decīt cele destinate, exceptie fiind cazurile prevazute īn Manualele de Operare sau a cazurilor pentru care s-a obtinut aprobarea Directorului de Centrala.


APPENDIX A


CONTENTS


A.0       APPLICABILITY OF APPENDIX


A.1       CONTAINMENT SYSTEM INITIATION SETPOINTS


A.2       ECC SYSTEM INITIATION SETPOINTS


A.3       SDS #1 TRIP SETPOINTS


A.4       SDS #2 TRIP SETPOINTS


A.5       CONTAINMENT SYSTEM LIMITS


A.6       EMERGENCY CORE COOLING SYSTEM LIMITS


A.7       SHUTDOWN SYSTEM #1 LIMITS


A.8       SHUTDOWN SYSTEM #2 LIMITS


A.9       REACTIVITY CONTROL LIMITS


A.10 MODERATOR SYSTEM LIMITS


A.11 HEAT TRANSPORT SYSTEM LIMITS


A.12 END SHIELD COOLING LIMITS


A.13 ANNULUS GAS SYSTEM LIMITS


A.14 MAIN STEAM SAFETY VALVE LIMITS


A.15 HEAT SINKS LIMITS


A.16 ELECTRICAL SYSTEM LIMITS


A.17 SERVICE WATER SYSTEM LIMITS


A.18 GUARANTEED SHUTDOWN STATE LIMITS


A.0         APPLICABILITY OF APPENDIX



The limiting values specified in these appendices shall be applicable if the specific system is required to be poised or available as defined in the relevant section of the OP&P document or this Appendix.


A.1         CONTAINMENT SYSTEM INITIATION SETPOINTS



INITIATION PARAMETER

SETPOINT

CONDITIONING

PARAMETER

HAND SWITCHES


R/B High

Pressure



0.0345 bar (d)


N/A


N/A


High

Containment

Activity

(Iodine)



1.87x105 cps

[Vapour Recovery]

9.31x103 cps

[R/B Ventilation]



N/A


N/A


Dousing On


R/B Pressure

> 0.14 bar (g)



N/A


N/A


Dousing Off




R/B Pressure

< 0.07 bar (g)




N/A


N/A



A.2       ECC SYSTEM INITIATION SETPOINTS



INITIATION

PARAMETER

SETPOINT

CONDITIONING

PARAMETER

HAND SWITCHES


Heat Transport Low Pressure




59 +/-2 bar (g)


One of (a),(b), or (c) below


Note (1)


(a)



(b)



(c)




10.12 m



0.0345(d) bar



59 +/-2 (g) bar




High Moderator Level



Reactor Building High Pressure



Sustained low pressure for 5 minutes




N/A



N/A



N/A





Note:

Handswitch is used to block ECC initiation when Heat Transport System is depressurized and cooled below 100 C.



A.3         SDS#1 TRIP SETPOINTS


TRIP PARAMETER

SETPOINT

CONDITIONING PARAMETER

SWITCHES

Neutron Power High

122.1 %FP (normal)

111.8 %FP (adjusted)

88.7 %FP(2 pumps)

Setpoints adjusted by handswitches.

Note (1)

Rate Log Neutron Power High

10 %/sec



Gross Coolant Flow Low

a) 80 % Nominal Flow (4 pumps)



b) 50 % Nominal Flow

a) Trip is conditioned out for initial powers below 80 % FP, or if power drops below 80 % FP within 1 second of exceeding the trip setpoint;

b) Conditioned out when log power less than 0.1 %FP.

Note (3)

Steam Generator Level Low

-1.55 m at 0%FP

+1.74m >90% FP

linear ramp between 0% and 90% FP*

1) Setpoint determined by flux detector signals;

Conditioning out for log power < 1%FP, and lin power < 10%FP


Note (3)

Pressurizer Level Low

+ 2.0 m < 40% FP

2.0 m-4.0 m 40%-55% FP linear ramp

4.0 m 55%-75% FP

4.0 m to 7.26 m 75%-95%FP linear ramp

7.26m >95%FP

1) Setpoint determined by reactor power signal from in-core flux detectors;


Conditioning out for log power < 1%FP, and lin power < 10%FP

Note (2)

Note (3)

Moderator Temperature High

87oC

None.


Heat Transport Pressure High

a) 102.4bar (g)



b) 104.5bar (g)

a) Trip is conditioned out for initial powers below 70 % FP, or if power drops below 70 % FP within 3 seconds of exceeding the trip setpoint;

b) instantaneous

Note (2)

Heat Transport Pressure Low

61,5bar (g) at 0% FP

87 bar (g) >95% FP

linear ramp between 0% and 95% FP

1) Setpoint determined by ion chamber linear power signal;

2) Conditioned out if log power less than 0.1 %FP.

Note (2)

Note (3)

Boiler Feedline Pressure Low

39 bar (g)

Conditioned out for log power less than 9% FP.

Note (3)

Reactor Building Pressure High

0.0345 bar (d)



Manual




Start-Up Count Rate High**




Steam generator level setpoints are given relative to the narrow range taps.

For initial start-up after a prolonged shutdown only.


HANDSWITCHES

Note (1)                  Three positions for setpoint adjustment:

- NORMAL

- ADJUSTED OPERATION

- 2 PUMP

Note (2)                  Three positions for setpoint adjustment:

- 4 PUMP

- (P1 & P3)║ These positions are used only if reactor power < 2%FP.

- (P2 & P4)║

Note(3):Can be manually inhibited without CNCAN approval if the ion chambers reactor power is below 2x10-5FP.

A.4      SDS#2 TRIP SETPOINTS


TRIP PARAMETER

SETPOINT

CONDITIONING PARAMETER

SWITCHES

Neutron Power High

122.1 %FP (normal)

111.8 %FP (adjusted)

88.7 %FP (2 pumps)

Setpoints adjusted by handswitches.

Note (1)

Rate Log Neutron Power High

15 %/sec



Core Differential Pressure Low

a) 9.5bar (d)


b) 4.5 bar (d)

a) Trip is conditioned out if power drops below 70 %FP within 3 seconds of exceeding the trip setpoint;

b) Log power from ion chambers and conditioning level selected by handswitch; flux greater than 5.0 % (normal operation); flux greater than 0.3 % (handswitch when pumps stopped).

Note (2)

Note (3)

Steam Generator Level Low

-2.56m at 0%FP

+1.59m >90%FP

linear ramp between 0% and 90% FP*

1) Conditioned out when reactor log power less than 2 % FP and lin power less than 10%;

2) Setpoint determined by flux detector signals.

Note (2)

Note (3)

Pressurizer Level Low

+ 2.0m < 40%FP

2.0m-4.0m 40%-55%FP

linear ramp

4.0m 55%-75%FP

4.0m to 7.26m         75%-95%FP

linear ramp

7.26m >95%FP

1) Setpoint determined by reactor power signal from in-core flux detectors;

2) Conditioned out when reactor log power less than 1 %FP and lin power less than 10%FP.

Note (2)

Note (3)

Heat Transport Pressure High

a) 102.4 bar (g)



b) 116.2 bar (g)

a) Trip is conditioned out for initial powers below 70 %FP, or if power drops below 70 %FP within 5 seconds of exceeding the trip setpoint;

b) Instantaneous.

Note (2)

Boiler Feedline Pressure Low

39 bar (g)

Conditioned out for log power less than 9 %FP


Note (3)

Heat Transport Pressure Low

6.15 Mpa(g) at 0% FP

8.7 MPa (g) >95% FP

linear ramp between 0% and 95% FP

1) Setpoint determined by ion chamber linear power signal;

2) Conditioned out by log power less than 0.3 %FP.

Note (2)

Note (3)

Reactor Building Pressure High

0.0345 bar (d)



Manual

N/A



Steam generator level setpoints are given relative to the narrow range taps.


HANDSWITCHES

Note (1) Three positions for setpoint adjustment:

NORMAL

ADJUSTED OPERATION

2 PUMP

Note (2) Three positions for setpoint adjustment:

4 PUMPs

(P1 & P3)║ These positions are used only if reactor power < 2%FP.

(P2 & P4)║

Note (3): Can be manually inhibited without CNCAN approval if the ion chambers reactor power is below 2x10-5FP.

A.5      CONTAINMENT SYSTEM LIMITS.


LICENSING LIMITS





PARAMETER

ACCEPTABLE CONDITION


Dousing System

Dousing Water temperature

38oC

Dousing tank level

> 3.9 m and < 4.5 m

Dousing downcomers with initiating logic available

at least 4 downcomers

Dousing valve opening time

6s to fully open


Containment Isolation

Isolation damper closing time

2 s for PV1-PV16

10s for PV17-PV22, PV24-PV37

Isolation dampers available per pathway

at least 1 damper

Doors of each airlock shall be kept closed and seals inflated at all times

at least 1 door

Isolating valves

10 sec for PV 44-45, PV 54-55, PV 67-68, 63221 HCV17


Local Air Coolers

Reactor Building local air coolers (LAC)

at least 8 of the 16 class III LAC's and RCW available (4 in F/M vault and 4 in SG room)


Hydrogen Igniters

R/B Igniters

at least 1 out of 4 in each of the 11 locations

at least 4 of the 16 LAC"s for air circulation supplied by Class III/EPS



 


ACTION ON EXCEEDING LIMITS OR IMPAIRMENT


When Containment System conditions are tending to or outside the limits defined above, or if the system is found not to be poised as defined in Impairments Manual OM 01369 section 4.3, the operator shall take action as documented in OM 01369 section 4.4.


OPERATING STATES


i)          Dousing System and Reactor Building Local Air Coolers (LACs)


These systems shall not be removed from service unless all the following conditions are met:


The unit has been in the shutdown state with the HTS depressurized to less than 4 bar and at a temperature of less than 100 C.


The system can satisfy the specific recall requirements.


The proposed activities have been planned in sufficient detail to minimize the duration of the outage.


During a unit start-up, the Dousing System, Reactor Building Local Air Coolers, and Hydrogen Igniters must be available for service prior to the HTS temperature exceeding 100 C.


ii)         Containment Isolation System and Airlocks


These systems shall not be removed from service unless all the following conditions are met:


The unit is in the Guaranteed Shutdown State with the HTS depressurized to less than 4 bar and at a temperature of less than 100 C;


No irradiated fuel is presented in the fuelling machines;


The proposed activites have been planned in sufficient detail to minimize the duration of the outage.


Approval of the Station Manager and CNCAN has been obtained.


During a unit start-up, the Containment Isolation System and Airlocks must be available for service prior to the heat transport system temperature exceeding 100 C, and before removal of the Guaranteed Shutdown State.



A.6      EMERGENCY CORE COOLING SYSTEM LIMITS


LICENSING LIMITS


PARAMETER ACCEPTABLE CONDITION


i)          High Pressure Injection


One of two gas and water flowpaths available from High Pressure accumulators to unit injection valves.



Accumulator water level


Gas tank pressure


Gas tank valves opening

timing


Accumulator water tank

Pressure


Accumulator discharge

valve closing level


Accumulator discharge

valve closing time


Accumulator water

temperature


> 9.78 m


> 42 bar(g)


7.5 s



1.9 bar and 2.8 bar



> 1.35 m TK3

> 1.97 m TK1


20 s



47oC




ii)            Medium Pressure Injection


One of two flowpaths available from dousing tank to unit injection valves, via ECC pumps.



Dousing tank temperature


< 38 oC



iii)           Low Pressure Recovery


Flowpath available from recovery sump via one ECC pump and one heat exchanger to unit injection valves;


Flowpath of Cooling water to one heat exchanger from one of two sources; RCW from pumps through the heat exchanger to the outfall or EWS from the pumps through the heat exchanger to the outfall. RCW temperature should not exceed 35 C at inlet of the secondary side of the ECC-HX.


iv)           Loop Isolation


One of two loop isolation valves available to close in all levels connecting heat transport loops on initiation signal.


Loop Isolation valve closing time <20 s.


v)           Injection Valves


One flow path to each header available.


Injection valve opening time <20 s.


vi)           Boiler Crash Cool Capability


At least 10 out of 16 MSSV's available


MSSV opening time <1 s after 30 s time delay.


ACTION ON EXCEEDING LIMITS OR IMPAIRMENT


When Emergency Core Cooling System conditions are tending to or outside limits defined above, or if the system is found not to be poised as defined in Impairments Operating Manual OM 01369 sections 5.3, 5.4 and 5.5, the operator shall take action as documented in OM 01369 section 5.6.


OPERATING STATES


a) The ECCS shall not be removed from service unless the following conditions are met:


The unit has been in the shutdown state with the HTS depressurized to less than 4 bar and at a temperature of less than 100 oC;


The system can satisfy the specified recall requirements;


The proposed activities have been planned in sufficient detail to minimize the duration of the outage.


b) The ECCS can be blocked as per the provisions of the Operating Manual OM 34320, section 5.1.1.


During a unit start-up, the ECCS must be available for service prior to the HTS temperature exceeding 100 oC.


A.7         SHUTDOWN SYSTEM #1 LIMITS


LICENSING LIMITS



PARAMETER

ACCEPTABLE CONDITION


Shutoff rod insertion time

Distance Travelled from Top Electronic End Stop

Time (Individual rod)in seconds

Gate 1

1.83 m


Gate 2

3.96 m


Gate 3

6.10 m


Number of shutoff rods available

26 out of 28



ACTION ON EXCEEDING LIMITS OR IMPAIRMENT


When Shutdown System conditions are tending toward or are outside the limits defined above, or if the system is found not to be poised as defined in Impairments Manual OM 01369 section 6.3.1.1, the operator shall take action as documented in OM 01369 sections 6.3.1.2, 6.3.3 and 6.4.


OPERATING STATES


SDS #1 shall not be removed from service unless the reactor is in Guaranteed Shutdown State and Station Manager approval has been obtained.


During a unit start-up, SDS #1 must be poised and fully available before exiting the Guaranteed Shutdown State.



A.8         SHUTDOWN SYSTEM #2 LIMITS


LICENSING LIMITS


PARAMETER


Poison injection paths available


The available poison injection paths are based on:


- poison tank concentration


- helium injection pressure


- helium injection flowpath opening time (time from trip signal received to valve fully open)


ACCEPTABLE CONDITION


At least 5 of 6




> 8000 mg Gd/kg D2O


78.8 bar (g)


160 ms


ACTION ON EXCEEDING LIMITS OR IMPAIRMENT


When Shutdown System conditions are tending towards or are outside the limits defined above, or if the system is found not to be poised as defined in Impairments Manual OM 01369 section 6.3.2.1, the operator shall take action as documented in OM 01369 sections 6.3.2.2, 6.3.3 and 6.4.


OPERATING STATES


SDS #2 shall not be removed from service unless GSS and Station Manager approval has been obtained.


During a unit start-up, SDS #2 must be poised and fully available before exiting the Guaranteed Shutdown State.



A.9         REACTIVITY CONTROL


LICENSING LIMITS


In order to control reactivity to limit possible overpower transients, the following limits shall be respected:


a) The heat transport system void coefficient with the reactor at or above full power, shall be limited by maintaining the HTS isotopic purity not lower than 97.78 atom %;


b) The heat transport coolant D O isotopic purity shall be maintained at a level such that the moderator-to-HTS coolant isotopic purity is greater at all times;


c) The rate of fuelling shall be limited such that the concentration of soluble poison in the moderator is restricted to the equivalent of 5 mk excess reactivity when operating in steady state full power equilibrium fuel conditions;


d) The maximum thermal power transferred from the fuel to the coolant shall not exceed 2056 MW(t) averaged over 12 hours or 2071 MW(t) at any time under steady state conditions.


e) The maximum power generated in a fuel channel shall not exceed 7.3 MW(t) under steady state conditions;


f) The maximum power generated in a fuel bundle shall not exceed 935 kW(t) under steady state conditions.


g) The operation in the islanding mode at a power level greater than 2% FP is not allowed for a period of time greater than 2 h.


ACTION ON EXCEEDING LIMITS OR IMPAIRMENT


When conditions are tending to or outside the limits defined above, the operator shall take action as documented in the following manuals:


a) Plant Chemistry Control Operating Manual OM 78210 section 4.3.6; (not issued)

b) Plant Chemistry Control Operating Manual OM 78210 section 4.3.6; (not issued)

c) Reactor Physics Operating Manual OM 03310 section 5.5.1.2; (not issued)

d) Reactor Physics Operating Manual OM 03310 section 7.2.2.7; (not issued)

e) Reactor Physics Operating Manual OM 03310 sections 7.2.1.11 and 7.2.1.12; (not issued)

f) Reactor Physics Operating Manual OM 03310 sections 7.2.1.9 and 7.2.1.10. (not issued)



A.10 MODERATOR SYSTEM LIMITS


LICENSING LIMITS


The Moderator System is considered to be available as the ultimate heat sink (in the event of a LOCA & ECCS failure), if the following conditions are met:


a) Calandria outlet temperature does not exceed 77 oC;


b) LOCA crash cooling logic and secondary crash cooldown are available;


c)     At least one moderator pump and one heat exchanger flowpath is available;


d)     Calandria level is not less than 7550 mm when the reactor is at > 0.5 %FP and no less than 7300 mm on low power;


e)     Cooling water (RCW) and flow path available to the HX.


Other Limits:


f)      The hydrogen and deuterium concentration in the cover gas is less than 4 %.


g)     Nominal Moderator isotopic should be equal or above 99.81 atom


ACTION ON EXCEEDING LIMITS OR IMPAIRMENT


When conditions are tending towards or are outside the limits defined above, the operator shall take action as documented in the following manuals:


a) Moderator System Operating Manual OM 32110;


b) Moderator Cover Gas System Operating Manual (32310) section 6.1.


A.11 HEAT TRANSPORT SYSTEM LIMITS


LICENSING LIMITS


The heat transport system is considered to be within its licensing envelope if its operation conforms to the following limits:


a) Heat Transport D2O Inventory


Minimum D2O storage tank level (29.73m3): 1.81 m when the HTS is at or above "zero power hot" conditions and the unit is at steady state.


b) Heat Transport Heating and Cooling Rates


Rate of heat transport system warm-up or cooldown shall normally be set, so that the maximum selected rate does not exceed 2.8 oC/minute


c)     Heat Transport Isotopic Limit


Nominal Heat Transport isotopic should above 97.78 atom%.


d)     Heat Transport Iodine Limit


The concentration of I-131 in the HTS shall be no higher than 500 MBq/kg.


e)     Heat Transport Tritium Limit


Tritium in Heat transport D2O should be less than .0093 TBq/kg D2O


f)      Heat transport System Leakage


D2O leakage from a pressure tube shall not exceed 2 kg/h from the heat transport system;

General D2O leakage shall not exceed 20 kg/h;

D2O leakage from steam generator tubes shall not exceed 15 kg/h.


g)     Liquid Relief Valve Setpoints


One of two liquid relief valves per loop is available at its setpoint of 102.4 bar (g).


ACTION ON EXCEEDING LIMITS OR IMPAIRMENT


When heat transport system conditions are tending to or outside the limits defined above, the operator shall take action as documented in the following manuals:


a) HT D2O Storage and Transfer Operating Manual OM 33330-1


b) HT Pressure and Inventory Control Operating Manual OM 33320, and Shutdown Cooling System Operating Manual OM 33410;


c) Gross Activity Monitoring Operating Manual OM 63103;


d) Annulus Gas Operating Manual OM 34980;

HT D2O Storage and Transfer Operating Manual OM 33330-1;

D2O in H2O Leak Detection System Operating Manual OM 63862;


e) Heat Transport Liquid Relief Valves Open, Operating Manual Test OMT 68200.19.


A.12 END SHIELD COOLING SYSTEM LIMITS


LICENSING LIMITS


The end shield cooling system is considered to be within its licensing envelope if its operation conforms to the following limits when reactor power is >2 %FP:


a) End shield level greater than 18.8 m.

b) Calandria vault outlet temperature <66 oC;

c) End shield outlet temperature <80 oC.


ACTION ON EXCEEDING LIMITS OR IMPAIRMENT


When End Shield Cooling System conditions are tending towards or are outside the limits defined above, the operator shall take action as documented in End Shield Cooling System Operating Manual OM 34110.



A.13 ANNULUS GAS SYSTEM LIMITS


LICENSING LIMITS


The Annulus Gas System is considered to have adequate leak detection capability when:


a) The AGS is considered to have adequate detection capacity if the flow is > 1.63 l/s in either recirculation or purge mode (except the transition period);

b) There is continuous dewpoint monitoring in service;

c) At least one of the beetles is in service.


Station Manager and CNCAN approval is required to maintain reactor operation with annulus gas unavailable for more than 24 hours.


ACTION ON EXCEEDING LIMITS OR IMPAIRMENT


When Annulus Gas system conditions are tending towards or are outside the limits defined above, the operator shall take action as documented in the Annulus Gas System Operating Manual OM 34980:


a) for flow, section 6.4;

b) for dewpoint monitoring, section 6.1;

c) for beetles, section 6.6.



A.14 MAIN STEAM SAFETY VALVES


LICENSING LIMITS


The Main Steam Safety Valves must be in service and capable of limiting steam generator pressure to 51.4 bar(g) during a postulated loss of regulation. In order to achieve this, a decrement of 7 %FP shall be applied to the ROP trip setpoints for each MSSV removed from service.


ACTION ON EXCEEDING LIMITS OR IMPAIRMENT


When MSSV availability is tending towards or are outside the limits defined above, the operator shall take action as documented in Reactor Physics Operating Manual OM 03310 section 6.1.4.


A.15 HEAT SINK AVAILABILITY


CONDITIONS FOR HEAT SINK AVAILABILITY


AFW

Flowpath from deaerator to all boilers and auxiliary feedwater pump available, with 2 ASDV" or equivalent venting path available;

and

Condensate hotwell level >250 mm, Deaerator tank level >1007 mm and condensate auxiliary extraction pump available, or Condensate Storage tank (TK99) level >2350 mm and flowpath to AFWP available;


SDCS

Flowpath available via one heat exchanger and one SDCS pump (except if reactor has not been shut down for more than 6 hours, in which case both flowpaths, via exchanger and pumps, are to be available);

and

Recirculating Cooling Water available to heat exchanger.


BMW

auto depressurization logic available;

Dousing tank level > 3.9 m;

Flowpath from dousing tank to all available boilers;


EWS

Flowpath to all boilers available and with 2 MSSV's or equivalent venting path available.


ACTION ON EXCEEDING LIMITS OR IMPAIRMENT


Unless planned, if heat sinks are tending towards or are outside the limits defined above, the operator shall take action as documented in Impairments Manual OM 01369:


a) for AFW, section 7.1;

b) for SDCS, section 7.2;

c) for BMW and EWS, section 8.1;

d)     for combinations - Table 8-3


REMOVING HEAT SINK FROM SERVICE


Heat sinks can be made unavalailable for maintenance or/and testing with SS approval if the following conditions are met:


a)      AFW can be made unavailable if EWS/BMW and SDCS are available

b)      SDCS can be made unavailable if AFW and EWS/BMW are available.

c)      BMW can be blocked by selecting its handswitch to "override" according to Operating Manual procedures without further approvals or authorizations.

BMW can be made unavailable if SDCS, AFW and EWS are available and recall requirements for BMW have been specified.

EWS can be made unavailable if SDCS, AFW and BMW are available and a recall time for EWS has been specified.


The common elements of both BMW and EWS can be made unavailable if all the following conditions are met:

Shutdown Cooling System and Auxiliary FeedWater System are available.

The unit is in the shutdown state.

The system can satisfy the specified recall-time requirements.

The proposed activities have been planned in sufficient detail to minimize the duration of the outage.


Note:   "Available" means that the system could be made available within a specified recall-time.



A.16 ELECTRICAL SYSTEM LIMITS


LICENSING LIMITS


a)      Standby Class III Power is considered to be available if at least one standby diesel generators are capable of supplying 7.315 MW of Class III power to dedicated loads within 3 minutes of Loss of Class IV,


b)      Minimum combined fuel oil tank level to ensure the following,

Indoor fuel oil day tanks shall hold at least a 3-hour supply for each standby diesel generator.

Outdoor standby diesel generator fuel oil tanks shall hold a 7-day fuel oil supply minimum for each standby diesel generator.


c)      Class I power is considered to be available if the batteries are capable of supplying either even or odd Class I & II loads for at least 45 min.


d)      The Emergency Power Supply is considered to be available if at least one emergency generator is capable of supplying 890 kW of EPS power to dedicated loads within 30 minutes, with a minimum combined fuel oil tank level (corresponding to the inventory of both tanks) of not less than 95 % of the capacity of one tank.


ACTION ON EXCEEDING LIMITS OR IMPAIRMENT


When Electrical system conditions are tending to or outside the limits defined above, the operator shall take action as documented in the following manuals:


a) Impairments Manual OM 01369 section 7.3;

b) Class I Battery Discharge, call-up 55510/ 55610.X;

c) Impairments Manual OM 01369 section 8.2.


A.17 SERVICE WATER SYSTEM LIMITS


LICENSING LIMITS


a) The Emergency Water System is considered to be available if 1 of 2 pumps is available to operate from EPS with an intact flowpath to the ECCS HX, the PHT system, and the steam generators.


b) The Raw and Recirculating Water Systems are considered to be available if they are able to supply load as demanded and to limit RCW temperature to less than 35 oC.


ON EXCEEDING LIMITS OR IMPAIRMENT


When service water system conditions are tending to or outside the limits defined above, the operator shall take action as documented in Impairments Operating Manual OM 01369:


a) for EWS, section 8.1;

b) for RSW, RCW, section 7.4;





A.18 GUARANTEED SHUTDOWN STATE


The approved guaranteed shutdown state has the following limits:


a) Moderator level not less than 7300 mm;

b) Gd and/or B poison concentration greater than 42.9 mg/kg equivalent B;

c) Purification Moderator System isolated;

d) D2O addition isolated;

e) Poison concentration checked once a shift;

f) Moderator pH < 6.


The detailed isolation and procedure requirements are documented in SOS 32110.01.


ANEXA A



CONTINUT


A.0 DOMENIUL DE APLICABILITATE A ANEXEI


A.1 PRAGURI DE ACTIONARE PENTRU SISTEMUL ANVELOPEI


A.2 PRAGURI DE ACTIONARE PENTRU SRAZA


A.3 PRAGURI DE DECLANSARE PENTRU SOR #1


A.4 PRAGURI DE DECLANSARE PENTRU SOR #2


A.5 LIMITE APLICABILE PENTRU SISTEMELE ANVELOPEI


A.6 LIMITE APLICABILE PENTRU SRAZA


A.7 LIMITE APLICABILE PENTRU SOR #1


A.8 LIMITE APLICABILE PENTRU SOR #2


A.9 LIMITE APLICABILE PENTRU SISTEMUL DE CONTROL AL REACTIVITATII


A.10     LIMITE APLICABILE PENTRU SISTEMUL MODERATOR


A.11     LIMITE APLICABILE PENTRU SISTEMUL PRIMAR DE TRANSPORT AL CALDURII


A.12     LIMITE APLICABILE PENTRU SISTEMUL DE RACIRE PROTECTII BIOLOGICE


A.13     LIMITE APLICABILE PENTRU SISTEMUL INELAR DE GAZ


A.14     LIMITE APLICABILE PENTRU VANELE PRINCIPALE DE DESCARCARE ABUR (MSSV)


A.15     DISPONIBILITATEA SURSELOR RECI


A.16     DISPONIBILITATEA SISTEMELOR ELECTRICE


A.17     DISPONIBILITATEA SISTEMELOR DE APA DE SERVICIU


A.18     LIMITE APLICABILE STARII DE OPRIRE GARANTATA


A.0         DOMENIUL DE APLICABILITATE A ANEXEI


Valorile limita specificate īn aceste anexe sunt aplicabile daca sistemul respectiv este armat sa fie disponibil asa cum este definit īn sectiunea corespunzatoare a documentului OP&P sau īn aceasta Anexa.




A.1         PRAGURI DE ACTIONARE PENTRU SISTEMUL ANVELOPEI



PARAMETRU DE INITIERE

PRAG DE ACTIONARE

PARAMETRU DE CONDITIONARE

COMUTATOR

Presiune ridicata īn Cladire Reactor

0.0345 bar

N/A

N/A

Radioactivitate ridicata īn anvelopa (Iod)

1.87+105 cps

[Recuperare vapori]

9.31+103 cps

[Ventilare CR]

N/A

N/A

Initiere Stropire

Presiune īn cladire reactor

>0.14 bar (g)

N/A

N/A

Oprire Stropire


Presiune īn cladire reactor

<0.07 bar (g)

N/A

N\A




A.2         PRAGURI DE ACTIONARE PENTRU SRAZA


PARAMETRU DE INITIERE

PRAG DE ACTIONARE

PARAMETRU DE CONDITIONARE

COMUTATOR

Presiune coborāta īn sistemul primar

59 +/-2 bar (g)

Unul din parametrii (a), (b), or (c) de mai jos

Nota (1)

(a)


(b)



(c)




10.12 m


0.0345 bar (d)



59+/- 2 bar (g)



Nivel ridicat īn moderator


Presiune ridicata īn cladire reactor


Presiune scazuta sustinuta pentru 5 minute



N/A


N/A



N/A





Nota:      1. Comutatorul este utilizat pentru a bloca initierea SRAZA cānd sistemul primar este depresurizat si racit la <100 oC

A.3         PRAGURI DE DECLANSARE PENTRU SOR #1


PARAMETRU DE DECLANSARE

PRAG DE DECLANSARE

PARAMETRU DE CONDITIONARE

OBS

Putere neutronica ridicata

122.1% PN (normal)

111.8% PN (ajustat)

88.7% PN (2 pompe)

Pragurile de declansare ajustate prin comutator

Nota (1)

Rata ridicata a puterii neutronice logaritmice

10% /sec



Debit scazut īn circuitul primar

a) 80% Nivel nominal (patru pompe)

sau

b) 50% Nivel nominal

a) Declansarea este inhibata la puteri mai mici de 80% PN, sau cānd puterea scade mai jos de 80% PN īntr-o secunda de la depasirea pragului de declansare.

b) Inhibat cānd puterea logaritmica este <0.1%PN.

Nota (3)

Nivel scazut īn generatorul de abur

-1.55m                     at 0 % PN

+1.74m                    >90 % PN

crestere lineara de la 0 % la 90 % PN*

1) Pragul de declansare determinat de semnalele detectorilor de flux din zona activa.

2) Inhibat cānd puterea logaritmica <1%PN, iar puterea lineara <10%PN

Nota (3)

Nivel scazut īn presurizor

+2.0m                      <40% PN

2.0m-4.0m               40%-55%PN

crestere lineara

4.0m                        55%-75%PN

4.0m-7.26m             75%-95%PN

crestere lineara

7.26m                      >95 % PN

1) Prag de declansare determinat de semnalul de putere a rectorului de la detectorii de flux din zona activa.


2) Inhibat cānd puterea logaritmica <1%PN si puterea lineara <10%PN

Nota (2)

Nota (3)

Temperatura ridicata īn moderator

C

Neaplicabil


Presiune ridicata īn circuitul primar

a) 102.4 bar

sau


b) 104.5 bar

a) Declansarea este inhibata la puteri mai mici de 70% PN, sau cānd puterea scade mai jos de 70% PN īn 3 secunde de la depasirea pragului de declansare.

b) Instantaneu

Nota (2)

Presiune scazuta īn circuitul primar

61.5 bar (g)              0%PN

87 bar(g)                  >95% PN

crestere lineara de la 0% la 95%PN

1) Pragul de declansare determinat de semnalul de putere liniara de la camerele de ionizare.

2) Inhibat cānd puterea logaritmica este <10.1%PN

Nota (2)

Nota (3)

Presiune scazuta īn linia de alimentare cu apa a GA

39 bar (g)

Inhibat pentru puteri mai mici decāt 9% PN

Nota (3)

Presiune ridicata īn C/R

0.0345 bar (d)



Manual




Rata de numarare la pornire**




Pragul de declansare pe nivel īn generator este dat relativ la stuturile pentru domeniul īngust de masurare nivel.

Numai pentru pornirea initiala dupa o oprire īndelungata.

COMUTATOARE

Nota (1) Trei pozitii pentru ajustarea pragului de declansare:

NORMAL

ADJUSTED OPERATION

2 PUMP

Nota (2) Trei pozitii pentru ajustarea pragului de declansare:

4 PUMP

(P1 &P3)║ Aceste pozitii sunt utilizate doar daca puterea reactorului < 2%PN.

(P2 &P4)║

Nota (3) Pot fi inhibati fara a fi necesara aprobarea CNCAN numai in cazul in care puterea reactorului citita de camerele de ionizare este sub 2x10-5FP.

A.4         PRAGURI DE DECLANSARE PENTRU SOR #2


PARAMETRU DECLANSARE

PRAG DE DECLANSARE

PARAMETRU DE CONDITIONARE

OBS

Putere neutronica ridicata

122.1% PN (normal)

111.8% PN (ajustat)

88.7% PN  (2 pompe)

Pragurile de declansare ajustate prin comutator

Nota (1)

Rata ridicata a puterii logaritmice

15% /sec.



Presiune diferentiala scazuta īn zona activa.

a) 9.5 bar (d)

sau

b) 4.5 bar (d)

a) Declansarea este inhibata cānd puterea scade mai jos de 70%PN īn 3 secunde de la depasirea pragului de declansare.

b) Puterea logaritmica de la camerele de ionizare si nivel de conditionare selectat prin comutator. Fluxul>5.0% (functionare normala). Flux>0.3% (cānd pompele sunt oprite).

Nota (2)

Nota (3)

Nivel scazut īn generatorul de abur

-2.56m                     <0% PN

+1.59m                    >90% PN

crestere lineara de la 0% la 90% PN*

1) Inhibat cānd puterea logaritmica a reactorului este mai mica decāt 2% PN si puterea lineara mai mica decat 10%.

2) Pragul de declansare determinat de semnalele detectorilor de flux.

Nota (2)

Nota (3)

Nivel scazut īn presurizor

+2.0m              <40%PN

2.0m-4.0m       40%-55%PN crestere liniara

4.0m                 55%-75%PN

4.0m-7.26m     75%-95%PN crestere liniara

7.26m               >95%PN

1) Prag de declansare determinat de semnalul de putere al rectorului de la detectorii de flux din zona activa.

2) Inhibat cānd puterea log a reactorului este mai mica decāt 1% PN si puterea lineara mai mica decat 10%PN.

Nota (2)

Nota (3)

Presiune ridicata īn circuitul primar

a) 102.4 bar (g)

sau

b) 116.2 bar (g)

a) Declansarea este inhibata la puteri mai mici de 70% PN, sau cānd puterea scade mai jos de 70% PN īn 5 secunde de la depasirea pragului de declansare.

b) Instantaneu.

Nota (2)

Presiune scazuta īn circuitul primar

6.15 MPa (g) < 0%PN

8.7 MPa (g) >95% PN

crestere liniara de la 0% la 95%PN

1) Pragul de declansare determinat de semnalul de putere liniara de la camerele de ionizare.

2) Inhibat cānd puterea logaritmica mai mica decāt 0.3% PN

Nota (3)

Presiune scazuta īn linia de alimentare cu apa a GA

39 bar (g)

Inhibat pentru puteri mai mici decāt 9% PN


Nota (2)

Nota (3)

Presiune ridicata īn C/R

0.0345 bar (d)



Manual

N/A



Pragul de declansare pe nivel īn generator este dat pentru domeniul īngust de masurare nivel.

COMUTATOARE:

Nota (1) Trei pozitii pentru ajustarea pragului de declansare:

- NORMAL

- ADJUSTED OPERATION

- 2 PUMP

Nota (2) Trei pozitii pentru ajustarea pragului de declansare:

- 4 PUMP

- (P1 &P3)║ Aceste pozitii sunt utilizate doar daca puterea reactorului < 2%PN.

- (P2 &P4)║

Nota(3) Pot fi inhibati fara a fi necesara aprobarea CNCAN numai in cazul in care puterea reactorului citita de camerele de ionizare este sub 2x10-5FP.


A.5         LIMITE APLICABILE PENTRU SISTEMUL ANVELOPEI


LIMITE DE AUTORIZARE




PARAMETRI

PRAG DE ACTIONARE

SAU CONDITIE LIMITA

Sistemul de stropire


Temperatura apei de stropire

38oC

Nivelul īn rezervorul de stropire

> 3.9 m

< 4.5 m

Unitati de stropire cu logica de initiere disponibila

Cel putin 4 unitati de stopire

Timpul de deschidere al vanei de stropire

6s pāna la complet deschis


Izolare anvelopa


Timpul de īnchidere al vanelor de izolare

2s pentru PV1-PV16

10 s pentru PV17-PV22, PV24-PV37

Vane de izolare disponibile pe conducta

cel putin o vana

Usile fiecarei ecluze vor fi pastrate mereu īnchise si cu etansarile gonflate

cel putin o usa

Vane izolatoare

10 sec. pt PV 44-45, PV 54-55, PV 67-68, 63221 HCV 17

Racitorii locali de aer


Racitorii locali de aer (LAC)

cel putin 8 din 16 alimentati din Clasa III si Sistemul de Apa Recirculata disponibil (4 pe platforma MID si 4 in camera generatorilor de abur)

Arzatorii de hidrogen


Arzatorii de hidrogen din cladirea reactorului

Cel putin 1 din 4 in fiecare dintre cele 11 locatii

Cel putin 4 din cele 16 LAC-uri disponibile pentru circularea aerului, alimentati de Clasa III/EPS




ACTIUNI ĪN CAZ DE DISFUNCTIONALITATI


Īn cazul īn care starea anvelopei iese sau tinde sa iasa īn afara limitelor definite mai sus sau daca se constata ca sistemul nu este pregatit pentru actionare asa dupa cum este definit īn documentul Manual de Disfunctionalitati, OM 01369 sectiunea 4.3, operatorul va actiona īn conformitate cu OM 01369 sectiunea 4.4.


STARI DE EXPLOATARE


i)          Sistemul de stropire si racitori locali de aer din Cladirea Reactorului


Aceste sisteme nu vor fi scoase din functiune decāt daca fiecare din urmatoarele conditii sunt indeplinite simultan:


1. Centrala se afla in Stare Oprita cu circuitul primar depresurizat la mai putin de 4 bar si la o temperatura de mai putin de 100 C.


2. Sistemele pot fi repuse in functiune in perioade de timp precizate.


3. Activitatile propuse a se desfasura au fost planificate detaliat pentru a se minimiza durata opririi reactorului.


In timpul repornirii reactorului sistemul de stropire, racitorii locali de aer din cladirea reactorului si arzatorii de hidrogen trebuie sa fie disponibili inainte ca temperatura in circuitul primar sa depaseasca 100 C.


ii) Sistemul de izolare anvelopa si Ecluzele


Aceste sisteme nu vor fi scoase din functiune decāt daca fiecare din urmatoarele conditii sunt indeplinite simultan:


1. Reactorul este in Stare de Oprire Garantata cu circuitul primar depresurizat la mai putin de 4 bar si la o temperatura de mai putin de 100 C.


2. Nu exista combustibil iradiat īn masina de incarcat/descarcat combustibil nuclear.


Activitatile propuse a se desfasura au fost planificate detaliat pentru a se minimiza durata opririi reactorului.


Aprobarea Directorului Centralei si a CNCAN a fost obtinuta.


In timpul repornirii reactorului, sistemul de izolare anvelopa si ecluzele trebuie sa fie disponibile inainte ca temperatura in circuitul primar sa depasesca 100 C, si inainte de iesirea din starea de oprire garantata a reactorului.



A.6         LIMITE APLICABILE PENTRU ECCS


LIMITE DE AUTORIZARE


PARAMETRI PRAG DE ACTIONARE

SAU CONDITIE LIMITA


i)            Treapta de īnalta presiune


Trebuie sa fie disponibile una din doua cai pentru debitul de gaz si apa de la rezervoarele de īnalta presiune la vanele de injectie.


Nivelul apei īn rezervor


Presiunea īn rezervorul de gaz


Timpul de deschidere al vanelor rezervorului de gaz


Presiunea īn rezervorul de apa


Īnchiderea vanelor la nivel redus īn rezervoarele de apa


Timpul de īnchidere al vanelor de injectie


Temperatura apei īn rezervoare

> 9.78 m


> 42 bar(g)


7.5 s



1.9 bar si 2.8 bar


> 1.35 m  TK3

> 1.97 m  TK1


20s



47oC


ii)            Treapta de medie presiune


Trebuie sa fie disponibile una din doua cai ale debitului de la rezervorul de stropire la vanele de injectie prin pompele ECC.



Temperatura apei īn rezervorul de stropire



< 38oC



iii)           Treapta de joasa presiune


Traseul apei de la gurile de scurgere via pompele ECCS si schimbatorul de caldura pāna la vanele de injectie sa fie disponibil.


Apa de serviciu pentru schimbatorul de caldura sa fie disponibila de la una din cele doua surse: apa de racire recirculata de la pompe prin schimbatorul de caldura la evacuare sau apa de racire de urgenta de la pompe prin schimbatorul de caldura la evacuare. Temperatura RCW nu ar trebui sa depaseasca 35oC la intrarea in partea secundara a schimbatorilor de caldura ECC.


iv)           Izolarea buclelor


Una din cele doua vane de izolare sa fie disponibila sa se īnchida pentru fiecare din liniile ce conecteaza buclele circuitului primar.

Timpul de īnchidere al vanelor de izolare a buclelor < 20s.


v)           Vanele de injectie


Un traseu al apei la fiecare colector sa fie disponibil.

Timpul de deschidere al vanelor de injectie < 20s.


vi)           Capacitatea de racire rapida a generatorilor de abur


Cel putin 10 din 16 MSSV-uri sa fie disponibile.

Timpul de deschidere al MSSV-urilor < 1s dupa o īntārziere de 30s.


ACTIUNI ĪN CAZ DE DISFUNCTIONALITATI


Īn cazul īn care starea sistemului ECC iese sau tinde sa iasa īn afara limitelor definite mai sus, sau daca se constata ca sistemul nu este pregatit pentru actionare asa dupa cum este definit īn documentul Manual de Disfunctionalitati, OM 01369 sectiunile 5.3, 5.4 si 5.5, operatorul va actiona īn conformitate cu OM 01369 sectiunea 5.6.


STARI DE EXPLOATARE


a)           Sistemul ECC nu va fi scos din functiune decāt daca sunt īndeplinite urmatoarele conditii:


1. Centrala este oprita, cu sistemul primar depresurizat la o valoare mai mica de 4 bar si la o temperatura mai mica de 100oC.

2. Sistemul poate fi repus īn functiune īntr-o perioada de timp specificata.

3. Activitatile propuse au fost planificate suficient de detaliat pentru a minimiza durata opririi.


b)           ECCS poate fi blocat conform procedurii descrise īn Manualul de Operare OM 34320, sectiunea 5.1.1.


La pornirea centralei, ECCS trebuie sa fie disponibil īnainte ca temperatura sistemului primar sa depaseasca 100 oC.


A.7         LIMITE APLICABILE PENTRU SOR #1


LIMITE DE AUTORIZARE



PARAMETRI

CONDITIE ACCEPTABILA


Timpul de insertie al barelor de oprire

Distanta parcursa de la declansare la mecanismul de oprire

Timpul (bara individuala) in secunde

Poarta 1

1.83 m


Poarta 2

3.96 m


Poarta 3

6.10 m


Numarul de bare de oprire disponibile

26 din 28



ACTIUNI ĪN CAZ DE DISFUNCTIONALITATI


Īn cazul īn care starea SOR #1 iese sau tinde sa iasa īn afara limitelor definite mai sus sau, daca se constata ca sistemul nu este pregatit pentru actionare asa dupa cum este definit īn documentul Manual de Disfunctionalitati, OM 01369 sectiunea 6.3.1.1, operatorul va actiona īn conformitate cu OM 01369 sectiunile 6.3.1.2, 6.3.3 si 6.4.


STARI DE EXPLOATARE


SOR 1 nu va fi scos din functiune decāt daca reactorul se afla īn starea de Oprire Garantata si s-a obtinut aprobarea Directorului Centralei.


La pornirea centralei, SOR 1 trebuie sa fie complet disponibil si pregatit pentru actionare īnainte de iesirea centralei din starea de Oprire Garantata.



A.8         LIMITE APLICABILE PENTRU SOR #2


LIMITE DE AUTORIZARE


PARAMETRI



Minimul de cai disponibile pentru injectia otravii


Disponibilitatea cailor de injectie a otravii se bazeaza pe:


- concentratia otravii īn tanc


- presiunea de injectie a heliului


- timpul de deschidere a caii de injectie (timpul de la primirea semnalului pāna la

deschiderea completa a vanei)


CONDITIE ACCEPTABILA



Cel putin 5 din 6






> 8000 mgGd/kg D2O


78.8 bar (g)


160 ms


ACTIUNI ĪN CAZ DE DISFUNCTIONALITATI


Īn cazul īn care starea SOR #2 este sau tinde sa fie īn afara limitelor definite mai sus sau, daca se constata ca sistemul nu este pregatit pentru actionare asa dupa cum este definit īn documentul Manual de Disfunctionalitati, OM 01369 sectiunea 6.3.2.1, operatorul va actiona īn conformitate cu OM 01369 sectiunile 6.3.2.2, 6.3.3 si 6.4.


STARI DE EXPLOATARE


SOR 2 nu va fi scos din functiune decāt daca reactorul se afla īn Starea de Oprire Garantata si daca a fost obtinuta aprobarea Directorului Centralei.


La pornirea centralei, SOR 2 trebuie sa fie complet disponibil si pregatit pentru actionare īnainte de iesirea centralei din starea de Oprire Garantata.



A.9.      CONTROLUL REACTIVITATII


LIMITE DE AUTORIZARE


Pentru ca sistemul de control al reactivitatii sa limiteze posibilii tranzienti de supraputere, trebuie sa fie respectate urmatoarele limite:


a) Coeficientul de vid din sistemul primar, cānd reactorul este la o putere egala sau mai mare decāt puterea nominala trebuie sa fie limitat mentinānd īntotdeauna puritatea izotopica īn circuitul primar mai mare de 97.78 atom %.


b) Puritatea izotopica a deuteriului īn circuitului primar nu va fi mai mare decāt puritatea din sistemul moderator.


c) Rata de īncarcare a combustibilului va fi limitata astfel īncāt concentratia de otrava solubila din moderator sa fie limitata la un echivalent de 5 mk exces de reactivitate cānd se functioneaza la putere nominala īn regim stationar cu combustibilul la echilibru.


d) Puterea termica maxima transferata de la combustibil la agentul de racire nu va depasi 2056 MW(t) mediat pe parcursul a 12 ore sau 2071 MW(t) oricānd īn conditii de regim stationar.


e) Puterea maxima generata īntr-un canal de combustibil nu va depasi 7.3 MW(t) īn conditii de regim stationar.


f) Puterea maxima generata īntr-un fascicul de combustibil nu va depasi 935 kW(t) īn conditii de regim stationar.


g) Perioada maxima de timp permisa pentru functionarea centralei la o putere mai mare de 2% PN fara a fi conectata la retea (regim insularizat) este de 2 ore.


ACTIUNI ĪN CAZ DE DISFUNCTIONALITATI


Īn cazul īn care sistemul tinde sa iasa īn afara limitelor definite mai sus, operatorul va actiona īn conformitate cu urmatoarele manuale de operare:


a) Manualul de operare "Chimismul Centralei" OM 78210 sect. 4.3.6 (nu a fost emis);

b) Manualul de operare "Chimismul Centralei" OM 78210 sect. 4.3.6 (nu a fost emis);

c) Manualul de operare pentru Fizica Reactorului OM 03310 sect. 5.5.1.2 (nu a fost emis);

d) Manualul de operare pentru Fizica Reactorului OM 03310 sect. 7.2.2.7 (nu a fost emis);

e) Manualul de operare pentru Fizica Reactorului OM 03310 sect. 7.2.1.12 (nu a fost emis);

f) Manualul de operare pentru Fizica Reactorului OM 03310 sect. 7.2.1.9 si 7.2.1.10 (nu a fost emis).



A.10 LIMITE APLICABILE PENTRU SISTEMUL MODERATOR


LIMITE DE AUTORIZARE


Se considera ca sistemul moderator este disponibil ca ultima sursa de racire (exp. LOCA + indisponibilitate SRAZA), daca sunt īndeplinite urmatoarele conditii:


a)  Temperatura la iesirea din calandria nu depaseste 77oC.


b)    Logica de racire rapida pe semnal de LOCA si racirea rapida secundara (secondary crash cooldown) sunt disponibile.


c)    Cel putin o pompa si un schimbator de caldura din sistemul moderator sunt disponibile.


d)    Nivelul īn calandria nu este mai mic de 7550 mm cānd reactorul este la o putere > 0.5% din puterea nominala si nu mai mic de 7300 mm la putere scazuta.


e)  Concentratia de hidrogen si de deuteriu īn gazul de acoperire este mai mica de 4%.


Alte limite:


f)     Apa de racire (RCW) si traseul disponibil catre schimbatorul de caldura;


g)    Puritatea izotopica nominala a moderatorului trebuie sa fie egala sau mai mare decat 99.81 atom %.


Actiuni īn caz de disfunctionalitati


Īn cazul īn care sistemul are tendinta sau depaseste limitele definite mai sus, operatorul va actiona īn conformitate cu urmatoarele manuale de operare:


a) Manualul de operare al Sistemului Moderator OM;

b) Manualul de operare al Sistemului de Gaz de Acoperire a Moderatorului OM 32310 sectiunea 6.1.



A.11 LIMITE APLICABILE PENTRU SISTEMUL PRIMAR DE TRANSPORT AL CALDURII


LIMITE DE AUTORIZARE


Se considera ca sistemul primar de transport al caldurii este īn limitele sale de autorizare, daca functioneaza īn conformitate cu urmatoarele limite:


a) Inventarul de D2O din sistemul primar de transport al caldurii


Nivel minim īn rezervorul de stocare D2O (29.73 m3): 1.81 m cānd sistemul primar este la sau deasupra punctului de "0 cald" si reactorul se afla in regim stationar.


b) Rata de īncalzire si de racire a sistemului primar


Rata de īncalzire sau de racire a sistemului primar in mod normal va fi setata astfel īncāt rata maxima selectata sa nu depaseasca 2.8oC/minut1.


c) Limita aplicabila pentru puritatea izotopica in sistemului primar


Valoarea nominala a puritatii izotopice in sistemul primar trebuie sa fie peste 97.78 atom%.


d) Limita aplicabila pentru concentratia de iod din sistemul primar


Concentratia de I-131 din sistemul primar nu va fi mai mare de 500 MBq/kg.


e) Limita aplicabila pentru concentratia de tritiu din sistemul primar


Concentratia de tritiu in apa grea agent primar trebuie sa fie mai mica decat 0.0093 TBq/kg D2O.


f) Pierderi de agent din sistemul primar


Pierderile de D2O din sistemul primar provenite de la tuburile de presiune nu vor depasi 2 kg/h.

Pierderile generale de D2O nu vor depasi 20 kg/h.

Pierderile de D2O de la tuburile generatorilor de abur nu vor depasi 15 kg/h.


g) Praguri de actionare pentru vanele de protectie la suprapresiune


Una din cele doua vane de protectie la suprapresiune pe fiecare bucla este disponibila cu un prag de actionare de 102.4 bar (g).






Rata este reglata de programul de control a presiunii in generatorii de abur (BPC) cind temperatura circuitului primar este >150 C, sau de operator cind se opereaza cu pompele sistemului de racire la oprire. Aceasta rata poate fi depasita ca urmare a unor actiuni automate in timpul anumitor tranzienti.


ACTIUNI ĪN CAZUL ĪN CARE SUNT DEPASITE LIMITELE APLICABILE PENTRU SISTEMUL PRIMAR


Īn cazul īn care starea Sistemului primar tinde sa fie sau este īn afara limitelor definite mai sus, operatorul va actiona īn conformitate cu urmatoarele manuale de operare:


a) Stocare si transfer D2O, OM 33330-1;


b) Control presiune si inventar īn circuitul primar, OM 33320; Sistemul de Racire la Oprire, OM 33410;


c) Sistemul de monitorare radioactivitate, OM 63103;


d) Sistemul inelar de gaz OM 34980;

Stocare si transfer D2O, OM 33330-1;

Detectare scurgeri D2O īn H2O, OM 63862;


e) Deschiderea vanelor de descarcare ale circuitului primar, OMT 68200.19.

A.12 LIMITE APLICABILE PENTRU SISTEMUL DE RACIRE PROTECTII BIOLOGICE


LIMITELE DE AUTORIZARE


Sistemul de racire a protectiilor biologice este considerat a fi īn cadrul limitelor de autorizare daca functionarea sa este conforma cu urmatoarele limite (cānd puterea reactorului este > 2% din puterea nominala).


a) Nivelul apei īn protectiile de capat este mai mare de 18.8 m.


b) Temperatura la iesirea din vasul calandria < 66oC.


c) Temperatura la iesirea din protectiile de capat < 80oC.


ACTIUNI ĪN CAZ DE DISFUNCTIONALITATI


Īn cazul īn care starea Sistemului de protectii biologice este sau tinde sa fie īn afara limitelor definite mai sus, operatorul va actiona īn conformitate cu Manualul de operare pentru sistemul de racire protectii biologice, OM 34110.



A.13 LIMITE APLICABILE PENTRU SISTEMUL INELAR DE GAZ


LIMITE DE AUTORIZARE


Se considera ca sistemul inelar de gaz are o capacitate adecvata de detectie a pierderilor cānd:


a) Debitul sistemului inelar de gaz este > 1.63 l/s atāt īn regim de recirculare, cāt si īn regim de purja (cu exceptia perioadei de tranzitie).


b) Monitorarea punctului de roua este continua.


c) Cel putin un detector de umiditate este īn functionare.


Aprobarea Directorului centralei si a CNCAN este necesara pentru a mentine īn functiune reactorul atunci cānd sistemul inelar de gaz este indisponibil mai mult de 24 ore.


ACTIUNI ĪN CAZ DE DISFUNCTIONALITATI


Īn cazul īn care starea Sistemului inelar de gaz iese sau tinde sa iasa īn afara limitelor definite mai sus, operatorul va actiona īn conformitate cu Manualul de operare pentru sistemul inelar de gaz, OM 34980:


a)         pentru debit, sectiunea 6.4;

b)         pentru monitorarea punctului de roua, sectiunea 6.1;

c)         pentru detectori de umiditate, sectiunea 6.6.




A.14 LIMITE APLICABILE VANELOR PRINCIPALE DE DESCARCARE A ABURULUI (MSSV)


LIMITE DE AUTORIZARE


MSSV-urile trebuie sa functioneze si sa fie capabile sa limiteze presiunea īn generatorii de abur la 51.4 bar(g) īn timpul unui accident postulat de pierdere a reglarii.

Pentru a īndeplini aceasta cerinta, o descrestere de 7% din puterea reactorului va fi aplicata la pragurile de actionare la supraputere regionala pentru fiecare MSSV scos din functiune.


Actiuni īn caz de disfunctionalitati


Cānd disponibilitatea MSSV-urilor este sau tinde sa fie īn afara limitelor definite mai sus, operatorul va actiona īn conformitate cu Manualul de Operare pentru Fizica Reactorului, OM 03310, sectiunea 6.1.4.



A.15 DISPONIBILITATEA SURSELOR DE RACIRE


CONDITII PENTRU DISPONIBILITATEA SURSELOR DE RACIRE


Sistemul Auxiliar de Apa de Alimentare a Generatorilor de Abur


Calea de curgere de la degazor la toti generatorii de abur si pompa auxiliara de apa de alimentare disponibile, si 2 ASDV-uri sau o cale echivalenta de evacuare a aburului disponibila.


Nivelul in rezervorul de condensat >0,25m, nivelul in rezevorul degazorului >1007 mm si pompa auxiliara de extractie condensat disponibila sau (TK99)>2350 mm si cale de curgere catre pompa auxiliara de apa de alimentare disponibila.


Sistemul de racire la oprire


Cale de curgere disponibila printr-un schimbator de caldura si printr-o pompa a sistemului (cu exceptia cazului cind reactorul a fost in starea sigura de oprire mai putin de 6 ore, situatie in care ambele cai de curgere prin schimbatorii de caldura si pompele sistemului trebuie sa fie disponibile)


Sistemul de apa recirculata de racire sa fie disponibil la schimbatorul de caldura.


Sistemul de apa de adaos la generatorii de abur


logica de autodepresurizare disponibila

nivelul in rezervorul de stropire >3.9 m

cale de curgere de la rezervorul de stropire la toti generatorii de abur disponibila


Sistemul de apa de urgenta


Cale de curgere la toti generatorii de abur si 2 MSSV-uri disponibile sau, o alta cale echivalenta de evacuare a aburului disonibila.


ACTIUNI IN CAZ DE DEPASIRE A LIMITELOR SAU DISFUNCTIONALITATI


Cu exceptia cazurilor planificate, in cazul in care sursele de racire sunt sau tind sa fie in afara limitelor definite mai sus, operatorul va actiona in conformitate cu "Manualul de Disfunctionalitati" - OM-01369:

a) Pentru Sistemul auxiliar de apa de alimentare cu apa la GA, sectiunea 7.1;

b) Pentru Sistemul de racire la oprire, sectiunea 7.2;

c) Pentru Sistemul de apa de adaos la GA si Sistemul de apa de urgenta, sectiunea 8.1.

d) Pentru combinatii - Tabelul 8-3


SCOATEREA DIN FUNCTIONARE A SURSELOR DE RACIRE


Sursele reci pot fi indisponibilizate pentru lucrari de intretinere si/sau testare cu aprobarea Dispecerului Sef de Tura, daca urmatoarele conditii sunt indeplinite:


a)        Sistemul Auxiliar de Apa de Alimentare la GA poate fi facut indisponibil daca Sistemul de Apa de Urgenta/ Sistemul de Apa de Adaos la GA si Sistemul de Racire la Oprire sunt disponibile.


b)        Sistemul de Racire la Oprire poate fi facut indisponibil daca Sistemul Auxiliar de Apa de Alimentare la GA si Sistemul de Apa de Adaos la GA/ Sistemul de Apa de Urgenta sunt disponibile.


c)        Sistemul de Apa de Adaos la GA poate fi blocat prin selectarea comutatorului in pozitia "override" in conformitate cu Manualul de Operare fara ca alte aprobari sau autorizatii sa fie necesare.

Sistemul de Apa de Adaos la GA poate fi facut indisponibil daca Sistemul de Racire la Oprire, Sistemul Auxiliar de Apa de Alimentare la GA si Sistemul de Apa de Urgenta sunt disponibile si cerintele de repunere in serviciu pentru Sistemul de Apa de Adaos la GA au fost specificate.

Sistemul de Apa de Urgenta poate fi facut indisponibil daca Sistemul de Racire la Oprire, Sistemul Auxiliar de Apa de Alimentare la GA si Sistemul de Apa de Adaos la GA sunt disponibile si a fost specificat timpul de repunere in serviciu pentru Sistemul de Apa de Urgenta.

Elementele comune atat pentru Sistemul de Apa de Adaos la GA cat si pentru Sistemul de Apa de Urgenta pot fi facute indisponibile daca fiecare din urmatoarele conditii sunt indeplinite simultan:

Sistemul de Racire la Oprire si Sistemul Auxiliar de Apa de Alimentare la GA sunt disponibile.

Centrala este oprita.

Sistemul poate fi repus īn functiune īntr-o perioada de timp maxim admisa astfel incat sistemul sa-si realizeze functiile pentru care a fost proiectat (recall time).

Activitatile propuse au fost planificate suficient de detaliat pentru a minimiza durata opririi.


Nota:

"Disponibil" īnseamna ca sistemul poate fi facut disponibil īntr-o perioada de timp specificata.



A.16 DISPONIBILITATEA SISTEMELOR ELECTRICE


LIMITE DE AUTORIZARE


a)      Clasa III de alimentare cu energie electrica se considera a fi disponibila daca cel putin un generator de rezerva este capabii sa furnizeze 7.315 MW īn 3 minute de la pierderea clasei IV.


b)      Nivelul minim combinat īn rezervoarele de combustibil pentru a asigura urmatoarele:

Rezervoarele de combustibil de zi vor avea suficient inventar pentru a alimenta fiecare generator de rezerva pentru cel putin 3 ore;

Rezervoarele de combustibil externe ale generatoarelor Diesel vor avea suficient combustibil pentru a alimenta 7 zile minimum, fiecare generator diesel.

c)      Clasa I se considera a fi disponibila daca bateriile sunt capabile sa alimenteze sarcinile de clasa I si II par sau impar pentru cel putin 45 minute.


d)      Sistemul de alimentare cu energie electrica la avarie se considera a fi disponibil daca cel putin un generator de avarie este capabil sa furnizeze 890kW īn 30 minute, cu un nivel minim combinat īn rezervoarele de combustibil (corespunzator inventarului disponibil īn ambele rezervoare) de nu mai putin de 95% din capacitatea unui rezervor.


ACTIUNI ĪN CAZ DE DISFUNCTIONALITATI


Īn cazul īn care starea sistemelor electrice iese sau tinde sa iasa īn afara limitelor definite mai sus, operatorul va actiona īn conformitate cu urmatoarele manuale de operare:


a) Manualul de operare "Disfunctionalitati", OM 01369, sectiunea 7.3;

b) Call-up 55510/55610.X "Descarcarea bateriilor de clasa I";

c) Manualul de operare "Disfunctionalitati", OM 01369, sectiunea 8.2.



A.17 DISPONIBILITATEA SISTEMELOR DE APA DE SERVICIU


LIMITE DE AUTORIZARE


a) Sistemul de apa de racire la avarie se considera a fi disponibil daca una din doua pompe este disponibila sa functioneze din EPS, avānd un traseu intact la schimbatorul de caldura ECCS, la sistemul primar si la generatorii de abur.


b) Sistemele de apa bruta de racire si de apa recirculata se considera a fi disponibile daca sunt capabile sa alimenteze consumatorii la cerere si daca temperatura apei recirculate este limitata la o valoare mai mica de 35oC.


ACTIUNI ĪN CAZ DE DISFUNCTIONALITATI


Īn cazul īn care starea sistemelor de apa de serviciu iese sau tinde sa iasa īn afara limitelor definite mai sus, operatorul va actiona īn conformitate cu "Manualul de Disfunctionalitati" OM 01369:


a) pentru Sistemul de alimentare cu apa la avarie, sectiunea 8.1;

b) pentru apa bruta de racire, apa recirculata, sectiunea 7.4;



A.18 STAREA DE OPRIRE GARANTATA


Starea de oprire garantata aprobata are urmatoarele limite:


a) Nivelul īn moderator sa nu fie mai mic de 7300 mm;

b) concentratia de Gd si/sau B sa fie mai mare de 42.9 mg/kg B echivalent;

c) Sistemul Moderator de purificare izolat;

d) Adaosul de D2O izolat;

e) Concentratia de otrava sa fie controlata o data pe schimb;

f) pH moderator < 6.


Cerintele detaliate pentru izolare si procedura sunt prezentate īn Secventa Standard de Operare OM 32110.01.



The rate is controlled by BPC when HTS temperature is >150 C, and by the operator when in shutdown cooling mode. This rate may be exceded due to automatic actions during some transients.










Document Info


Accesari: 7979
Apreciat:

Comenteaza documentul:

Nu esti inregistrat
Trebuie sa fii utilizator inregistrat pentru a putea comenta


Creaza cont nou

A fost util?

Daca documentul a fost util si crezi ca merita
sa adaugi un link catre el la tine in site

Copiaza codul
in pagina web a site-ului tau.




eCoduri.com - coduri postale, contabile, CAEN sau bancare

Politica de confidentialitate




Copyright © Contact (SCRIGROUP Int. 2022 )