IEC 62118 pdf download – Nuclear reactor instrumentation – Pressurized water reactor (PWR) of VVER design – Monitoring adequate cooling within the core during shutdown
1scope and object
This International Standard applies to pressurized water reactors (PWRs) of VVER designwith configurations similar to those shown in figures 1 and 2,and presents the requirementsfor monitoring adequate cooling within the core during hot and cold shutdown conditions.Annex B provides more information on vVER operating states.
Good international practices to be used when designing new or upgrading existing corecooling monitors for VVER systems are summarized in this standard.This standard does notconsider the design details of the different VVER technological systems designs, except to theextent that the design affects the monitoring of core cooling.
Requirements are given for core cooling monitoring instrumentation to ensure the safeoperation of VVERs during abnormal operation and during and after design basis accidents(DBA). Requirements for core cooling monitoring during conditions beyond a DBA, whichcould be a specific national requirement or consideration, are not covered here.
The core cooling monitoring instrumentation has to function under widely different conditions.The circumstances under which this instrumentation needs to function are described.Descriptions of diverse measuring principles and suitable devices are given along withrequirements for the following:
operational conditions;installation;
operator displays;
testing, calibration and maintenance;equipment qualification;
documentation;
redundancy.
2 Normative references
The following normative documents contain provisions which，through reference in this text,constitute provisions of this International Standard. For dated references，subsequentamendments to,or revisions of,any of these publications do not apply.However，parties toagreements based on this International Standard are encouraged to investigate the possibilityof applying the most recent editions of the normative documents indicated below. For undatedreferences,the latest edition of the normative document referred to applies. Members ofIEC and lso maintain registers of currently valid lnternational Standards
IEC 60050(393):1996,International Electrotechnical Vocabulary (IEV) – Chapter 393:Nuclearlnstrumentation – Physical phenomena and basic concepts
IEC 60737:1982，In-core temperature or primary envelope temperature measurements innuclear power reactors – Characteristics and test methods
CEl 60780:1998,Centrales nucléaires – Equipements électriques de sureté – QualificationCEI 60880:1986，Logiciel pour les calculateurs utilises dans les systemes de surete descentrales nucleaires
CEI 60911:1987,Mesures pour surveiller la bonne réfrigeration du coeur des reacteurs a eaulegere pressurisee
CEl 60964:1989,Conception des salles de commande des centrales nucleaires de puissanceCEI 60980:1989，Pratiques recommandées pour la qualification sismique du materiel électriquedu systeme de surete des centrales électronucléaires
CEl 60987:1989,Calculateurs programmes importants pour la surete des centrales nucleairesCEl 61225:1993,Centrales nucleaires – Systemes d’instrumentation et de controle-commandeimportants pour la sureté – Prescriptions pour les alimentations électriques
CEl 61226:1993,Centrales nucleaires – Systemes d’instrumentation et de contrble-commandeimportants pour la srete – Classification
CEl 61227:1993,Centrales nucleaires de puissance – Salles de commande – Commandesoperateurs
CEI 61343:1996,Instrumentation des réacteurs nucléaires – Reacteurs a eau bouillante (BWR)-Mesures dans la cuve pour la surveillance adequate du refroidissement du caeur
IAEA Guide de surete 50-SG-D8:1984，Systemes d’instrumentation et de commande lies a lasarete dans les centrales nucleaires
3Definitions et abreviations
Pour les besoins de la présente Norme internationale, les definitions suivantes s’appliquent. Sides termes sont definis dans une autre norme, leur source est indiquee entre crochets.
3.1
ALARA
aussi bas que raisonnablement possible
3.2
fluide de refroidissement
eau et/ou vapeur destinée a éliminer la puissance produite dans le caeur
3.3
ADR
accident de reference
3.4
diversite
existence de composants ou de systemes redondants pour ‘accomplissement dune fonction deter-minee, lorsque ces composants ou systemes ont collectivement un ou plusieurs attributs différents[IAEA 50-SG-D8]
3.5
espace annulaire
volume annulaire entre la paroi de la cuve du reacteur et les composants internes, qui dirige lefluide de refroidissement vers la partie inferieure du coeur
IEC 62118 pdf download – Nuclear reactor instrumentation – Pressurized water reactor (PWR) of VVER design – Monitoring adequate cooling within the core during shutdown
