디지털계측제어분야 iec 표준규제동향 · ieee-std 603 10 cfr 50 부록/ gdc ... ieee...

제13회 원자력안전기술정보회의

2007.4.10~11

디지털계측제어 분야

IEC 표준 규제동향

디지털계측제어 분야

IEC 표준 규제동향

고정수

1/35

목 차

1. 원자력기술표준 (공식적표준 대 사실상표준) 이해

2. 현행 원자력 안전규제 체계도

3. 계측제어 규제요건 개략도

4. KEPIC I&C분야 구성체계

5. 국제표준의 국내 원자력규제기준 적용방안 연구1) 사업의 필요성 및 목표

2) 국내도입 평가대상 국제표준 현황

3) IEC SC-45A Working Group 활동 현황

6. 향후 추진계획

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1. 원자력기술표준 (공식적표준 대 사실상표준) 이해

IEEE/ASME 등(미국단체 표준기반)

현재 원자력에 적용

IEC/ISO 국제표준 기반(IAEA 안전표준과 연계)

장기적 국가 추진방향(원자력 상품교역에 중점)

원자력

국제표준화사업

( 5년간 )

국제표준의

국내원자력기준

적용방안 연구

KINS

국가 표준 개발

KOPEC

국가표준(KS) 단체표준(KEPIC 등)

중 장 기 비 전중 장 기 비 전원자력기술표준

일반요건중심

세부사항중심

공식적 표준 사실상 표준

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원자력법/시행령/시행규칙

(법 12조, 22조)

원자로시설등의 기술기준에 관한규칙(’06.07.19 부령 제 92호)

IEEE 기준

Reg. Guide.

안전심사지침(SRG/SRP); 기술적인사항

(안전규제업무 세부처분기준)

전력산업기술기준의 원자로 시설 기술

기준 적용에 관한 지침(’05.03.22, 고시 2005-4)

IEC 기준

표1,2

- 적용범위/방법

- 기준의 해석

- 제한사항

- 상충시 처리방법

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원자력법 10CFR 50

IEEE-Std 603

10 CFR 50 부록 / GDC

10 CFR 50.55a(h)IEEE-Std-603

KINS-SRG / SRP IEEE-Std 7.4.3.2

Regulatory Guide 1.153 Regulatory Guide 1.152

Reg. Guidelines,IEEE Stds

Reg. Guidelines,IEEE Stds

원자로시설등의 기술기준에 관한 규칙

전력산업기술기준의원자로 시설 기술기준적용에 관한 지침

10 CFR 50 부록QA / GDC50.62 ATWSSRP(NUREG-0800)

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3. 계측제어 규제요건 개략도 - 1

계측제어계통규제요건

10CFR50 APP.A

10CFR50 APP.B

10CFR50.34 (f)

10CFR50.55a(h) BTP

일반설계기준 품질보증기준 TMI 요건 보호계통기준

SRG 참조

계략도 2 참조 계략도 3 참조

RG 1.30 RG 1.68 RG 1.47 RG 1.53 RG 1.62 RG 1.75 RG 1.118

계측/전기기기품질요건

시운전시험우회/작동불능상태지시

단일고장기준 수동보호조치전력계통물리적분리

전력/보호계통주기시험

IEEE 336 IEEE 379 IEEE 603 IEEE 384 IEEE 338

계측/전기기기설치,검사,시험

단일고장기준 보호계통기준등급 1E 장비회로독립성

주기시험기준

Reference Reference Reference

IEEE 603 IEEE 603 IEEE 308

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IEEE 497RG 1.97

10CFR50.49(b)

IEEE 603IEEE 279IEEE 467

ASME NQA-1

RG 1.100RG 1.89RG1.28외다수

ReferenceReferenceReferenceReferenceReference

안전계통기준

컴퓨터계통적용기준

주기시험안전관련계기관 기준

안전관련계기 설정치

사고감시기능

IEEE 603-1980

IEEE 7.4.3.2

IEEE 338-1977ISA-S67.02ISA-S67.04ANS-4.5-

1980

RCPB 누설감지계통

안전계통전력,계측,제어기준

컴퓨터계통S/W 기준

전력/보호계통 주기시험

보호계통작동기능주기시험

계기 감지관Loose Part탐지계측

계측 설정치

PAM 계측설비

원격정지반시운전시험

RG 1.45RG 1.153RG 1.152RG 1.118RG 1.22RG 1.151RG 1.133RG 1.105RG 1.97RG 1.68.2

GDC 29GDC4: 환경기준

RCPB품질GDC 24GDC 24GDC19: 제어실GDC2: 자연재해

GDC 30GDC 23GDC 22GDC13: I&CGDC1: 품질기준

GDC 21GDC 20

10CFR50 APP. A일반설계기준(GDC)

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10CFR50.34(f)I&C 관련 TMI 요건

II.D.3 II.E.1.2 II.E.4.2 II.F.1 II.F.3 II.K.1.23 II.K.2.9 II.K.2.10 II.K.3

NUREG - NUREG - NUREG - NUREG - NUREG - NUREG - NUREG - NUREG -

718737694

718737694

718737694

718737694

718 694718737694

718737694

.1 .9 .10 .12 .13 .15 .18 .21 .22 .23

자동 PORV 격리

PID 제어기예상트립변경

예상원자로트립

HPCI&RCIC수준

HPCI&RCIC격리

ADS 작동LPCS&LCPI기동

RCIC 자동전환

중앙 수위기록

NUREG - NUREG - NUREG - NUREG - NUREG - NUREG - NUREG - NUREG - NUREG - NUREG -

073707370694

07370694

07370694

07180737

073707180737

07180737

0737 0718

RV/SV위치 지시

AFS자동개시유량지시

격납격리위치

(4),(6),(7)

사고감시계측 위치(4),(5),(6)

PAM(RG1.97)

BWRRV

수위지시

BWRI&CS FMEA

BWR안전등급예상트립

최종 권고사항

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요 건 준용기준 참조기준

8. 동력원

7. 실행설비

6. 감지/명령 설비

5.

안

전

계

통

기

준

5.15 신뢰도5.16 공통원인고장

5.14 인적요소

5.13 복수호기

5.12 보조설비

5.11 식별

5.10 수리

5.9 출입관리

5.8 정보 표시기

5.7 시험/교정 능력

5.6 독립성

5.5 계통의 건전성

5.4 기기검증

5.3 품질

5.2 보호조치의 완결

5.1 단일고장기준

IEEE 384IEEE 420IEEE 494

IEEE 497

IEEE 338

IEEE 384

IEEE 379

IEEE 323IEEE 627

ANSI/ASME NQA 1-1989

IEEE 379

IEEE 500IEEE 577

IEEE 323 IEEE 344IEEE 379 IEEE 384IEEE 494 IEEE 603

ASTM E136-92NEMA VE 1-1991

IEEE 383 IEEE 494IEEE 628 IEEE 690

IEEE 352IEEE 279IEEE 308IEEE 338IEEE 379

NUREG 0700

IEEE 308IEEE 379

R.G 1.97ANSI/ANS-4.5-1980

IEEE 577

IEEE 308

IEEE 577

IEEE 352

IEEE 1023

안전계통 기준

IEEE 603

IEEE 344

IEEE 384

IEEE 352IEEE 577

IEEE 7-4.3.2

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Codes

RegulatoryGuide

IndustrialCode & Std.

Guidance

reg. guide

EPRI TR-106439-1988(Digital COTS evaluation)

Planning

830-1993(Req. spec.)

1016-1998 (Design Spec.)

Design(Coding)

1008-1987(Unit test)

V&V

577-1976(Reliability

anal.)

1028-1998(Review&Audit)

982.1&2-1988 (SW Measures)

1044-1993 (Anomalies class)

Etc.RG 1.169

(CMP) RG 1.168 (V&V, audit)RG 1.170 (Test docum.)RG 1.171 (Unit test)

Req. spec.RG 1.172

(Req. spec.)

EPRI NP-5652(COTS

Guideline)

IEEE 603 (Safety sys.)5.3절(품질) ; 소프트웨어품질,

V/V 등 ---RG 1.153

RG 1.173(Development

of LCP)

LCP

829-1998 (Test doc.)

Installation

ANSI/IEEE 7-4.3.2-2003RG 1.152

Standard Review Plan – NUREG-0800 (Ch. 7 & BTP-14)

IEEE

1046-1991(Application

guide)

1042-1987 (CM

guideline)

1074-1997(Life cycleProcess)

1012-1998(V&V plan)

1058-1998(Manag. plan)

828-2005(CM plan)

1228-1994(Safety plan)

730-2002(QA plan)

1219-1998 (Maintenance)

1061-1998 (Quality metrics)

1540-2001 (Risk

management)

1012-1998(V&V plan)

10/35

4. KEPIC I&C분야 구성체계

KEPIC-E

EC 전선 및 전로용품

EE 전기기기

EM 계측 및 제어기기

ET 송변배전

EN 원자력 전기

일반(ENA)

설계(ENB)

검증(END)

설치(ENE)

시험 및 검사(ENF)

일반(EMA)

계측기기(EMB)

신호변환 및 제어기기(EMC)

지시 및 기록기기(EMD)

공정컴퓨터(EME)

공정변수(EMF)

.

.

.

.

.

11/35

KEPIC I&C 기술기준

KEPIC 제목 참조기준

ENA 일반요건 ASME Sec.III NCA

ENB1100 안전계통 설계 IEEE 603

ENB2000 전기1급 기기 및 회로 독립성 IEEE 384

ENB2100 전기1급 기기 및 회로 격리기준 IEEE 384

ENB3000 안전계통 단일고장기준 ANSI/IEEE 379

ENB4100 안전계통 신뢰도 분석 일반지침 ANSI/IEEE 352

ENB4200 안전계통 설계 및 운전신뢰도 분석요건 ANSI/IEEE 577

ENB6100 보호계통 설계 IEEE 279

ENB6310 제어실 설계 IEEE 567

ENB6360 인간공학 적용지침 IEEE 1023

ENB6370 안전계통 디지털 컴퓨터 IEEE 7-4.3.2

END1100 전기1급 기기검증 IEEE 323

ENB6330 사고 감시용 계측설비 설계 IEEE 497

ENB6380 방사성 유출물 감시용 계측설비 ANSI/IEEE N42.18

12/35

KEPIC I&C 기술기준

KEPIC 제목 참조기준

ENE1100 전력, 계측 및 제어기기 설치요건 IEEE 336

ENF1100 전력, 계측제어기기 시험과 검사요건 IEEE 336

ENF3100 안전계통 주기시험 ANSI/IEEE 338

ENF3610 계측 및 시험기기 교정 및 관리 IEEE 498

EMC5000 계측 및 제어기기 접지 설계지침 IEEE 1050

ENE1000 분산 디지털 제어 및 감시 설비 IEEE 1046

ENE3100 컴퓨터 소프트웨어 확인 및 검증 IEEE 1012

ENE3200 소프트웨어 시방서 요건 IEEE 830

ENE3300 소프트웨어 형상관리계획서 IEEE 828

ENE3400 소프트웨어 생명주기공정 IEEE 1074

ENE3500 소프트웨어 단위시험 ANSI/IEEE 1008

END2000 전기1급 기기 내진검증 IEEE 344

END3100 안전계통 기기 설계검증 IEEE 627

END1200 안전계통 기기검증시험 수행조직 IEEE 600

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5. 국제표준의 국내 원자력규제기준 적용방안 연구

과제명

국제표준의 국내 원자력규제기준 적용방안연구개발

사업주관 및 참여기관사업주관 : 대한전기협회참여기관 : KINS 및 KOPEC

사업기간2006.12.1 – 2011.11.30 (5년, 60개월)

14/35

사업의 필요성 및 목표

□ 사업의 필요성원자력안전규제의 국제 규범화 동참• 초창기, 원전 도입국 (美,加,佛) 기술기준 도입• 이후, IAEA 및 ICRP 등 국제 기술기준 도입• WTO 대응, ISO 및 IEC 표준의 국내도입의 필요

□ 사업의 목표최종 목표• 원자력법 규제기준과 국가표준의 연계 운영체제 구축• 국제표준의 국내 원자력규제기준 적용방안 개발

15/35

사업의 수행체계

□ 사업책임자 : 원자력안전기술원, 법제기준실장

□ 세부분야 및 참여자 : 4개 분야 (311표준), 9명

일반분야 (35 표준 • KS • IAEA) : 2명

계측제어 및 전기분야 (128 표준) : 3명

방사선방호 및 계측분야 (102 표준) : 2명

핵연료 분야 (46 표준) : 2명

□ 분야별 운영체계

분야별 운영책임자 지정

표준별 담당자 지정

분야별 및 전체 기술회의를 통한 도입여부 평가

16/35

국내도입 평가대상 국제표준 현황

□ ISO (국제표준화 기구, International Organization for Standardization)

설립 : 1947. 2. 23

회원국 : 158개국 (스위스 제네바)

목적 : 제품 및 서비스의 국제교역 증진을 위한 국제표준 제정

한국 가입 : 1963년

□ IEC (국제전기표준회의, International Electro-technical Commission)

설립 : 1906

목적 : 전기 및 전자 관련기술의 국제표준 제정

회원국 : 65개국 (스위스 제네바)

한국 가입 : 1963년

17/35

국내도입 평가대상 국제표준 현황

□ IEC/TC-45 Nuclear Instrumentation

위원회 명칭 표준수

TC Nuclear Instrumentation

(원자력계측 일반표준)

64

SC-A Instrumentation and Control of Nuclear Facilities

(원전제어표준)

64

SC-B Radiation Protection Instrumentation(방사선 계측표준)

39

합계 - 167

18/35

사업추진 주요내용

□ 국제표준의 체계 및 개발현황 분석

ISO 및 IEC 표준체계 및 개발현황 분석

• ISO 144 표준에 대한 평가 및 요약서 작성

– 1등급: 46, 2등급: 18, 3등급: 37

– 4등급: 3, 5등급: 28, 기타: 12

• IEC 167 표준에 대한 평가 및 요약서 작성

– 1등급: 77, 2등급: 20, 3등급: 32

– 4등급: 18, 5등급: 10, 기타: 10

19/35

Working Group in SC-45A

WGA2 : Sensors and measurement techniques

• IEC 60515 Ed. 2.0 publication, Nuclear power plants -Instrumentation important to safety - Radiation detectors:Characteristics and test methods

• IEC 60737 Ed. 2.0 publication, Nuclear Power Plants - 45A/644/FDISInstrumentation important to safety – Temperature sensors (In-core andprimary envelope); Characteristics and test methods

• IEC 60988 Ed. 2.0 publication, Nuclear Power Plants -Instrumentation important to safety - Accoustic monitoring systems forloose part detection : Characteristics, design criteria and operational procedure

• IEC 62397 Ed. 1.0 publication, Nuclear Power Plants -Instrumentation and control important to safety - ResistanceTemperature Detectors

20/35


WGA3 : Application of digital processors to safety in nuclear power plants

• IEC 60987 - Ed 2.0 publication, Nuclear Power PlantsInstrumentation and Control Important to Safety - Hardware DesignRequirements for Computer Based Systems

• IEC 61500 - Ed 2.0 publication, Nuclear Power Plants -Instrumentation and control systems important to safety - Functionalrequirements for multiplexed data transmission

• IEC 61513 Ed 2.0 publication, Nuclear power plants -Instrumentation and control important to safety - General requirements for systems

• IEC 62566 Ed 1.0 publication, Nuclear power plants -Instrumentation and control systems important to safety – Guidance onselection and use of complex electronic components in design ofinstrumentation and control systems performing category A functions

21/35


WGA5 : Special process measurements and radiation monitoring

• IEC 60768 Ed. 2.0 publication, Nuclear power plants - Instrumentation and control systems important to safety - Process radiation monitoring equipment in light water nuclear reactors for normal operating and incident conditions

• IEC 60951 Parts 1 to 4 Ed. 2.0 publications, Nuclear power plants - Instrumentation and control systems important to safety - Radiation monitoring equipment for accident and post-accident conditions in nuclear power plants

WGA7 : Reliability of electrical equipment in reactor safety systems

• IEC 60671 Ed. 2.0 publication, Nuclear Power Plants - Instrumentation and control important to safety - Surveillance testing

• IEC 61226 Ed 2.0 publication, Nuclear power plants - Instrumentation and control systems important to safety – Classification of instrumentation and control functions

• IEC 61838 TR Ed 2.0 publication, Nuclear power plants - Instrumentation and control functions important for safety - Use of probabilistic safety assessment for the classification

• IEC 62340 Ed 1.0 publication, Nuclear power plants - Instrumentation and control systems important to safety – Requirements for coping with common cause failure (CCF)

22/35


WGA8 : Control rooms

• IEC 60964 Ed. 2.0 publication, Nuclear power plants -Control rooms - Design

• IEC 60965 Ed. 2.0 publication, Nuclear power plants - Control rooms - Supplementary control points for reactor shutdown without access to the main control room

• IEC 61227 Ed. 2.0 publication, Nuclear power plants - Control rooms – Operator controls

• IEC 61772 Ed. 2.0 publication, Nuclear Power Plants - Control Rooms – Application of Visual Display Unit (VDU)

WGA9 : Instrumentation systems

• IEC 62003 Ed. 1.0 publication, Nuclear Power Plants -Instrumentation and control systems important to safety - Requirementsfor electromagnetic compatibility testing To discuss next stage

• IEC 62385 Ed. 1.0 publication, Nuclear power plants – Instrumentation and control systems important to safety –

23/35


WGA10 : Upgrading and Modernisation of I&C systems in NPP

• IEC 62096 TR Ed. 2.0 publication, Nuclear PowerPlants – Instrumentation and control systems – Guidance for thedecision on modernization

• IEC 62342 Ed. 1.0 publication, Nuclear power plants -Instrumentation and control systems important to safety - Managementof ageing

• IEC 62465 Ed. 1.0 publication, Nuclear power plants –Instrumentation and control important to safety – Management of agingof electrical cable systems

• IEC 625XX Ed. 1.0 publication, Nuclear power plants –Instrumentation and control important to safety – Methods for conditionmonitoring of electrical equipment of safety systems

24/35

IEEE 기준과 IEC 기준의 비교

Software management planSoftware aspect of system validation planSystem validation plan

Software maintenance planSystem maintenance plan

Software operation planSystem operation plan

Software installation planSystem installation plan

Software safety plan (IEEE 1228)No software safety planNo system safety plan

Software integration planSoftware aspect of system integration planSystem integration plan

Software development planSystem security plan

Software configuration management planSystem configuration management plan

Software verification and validation planSoftware verification planSystem verification plan

Software quality assurance planSoftware quality assurance planSystem quality assurance programs

Software PlanningSoftware PlanningSystem planning

NUREG 0800IEC 60880 software safety lifecycleIEC 61513 I&C system safety lifecycle

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국내도입 평가결과

□ IEC TC-45 표준도입 시급성 평가

1순위 : 당장 도입 및 현장적용 가능

2순위 : 5년 이내에 도입가능

3순위 : 미래의 여건변화에 따라 도입가능

4순위 : 미래의 여건변화에 따라 재검토

5순위 : 도입 불필요

순위 1 2 3 4 5 기타 합계

TC45 4 18 20 16 0 6 64

SCA 52 0 1 1 8 2 64

SCB 21 2 11 1 2 2 39

합계 77 20 32 18 10 10 167

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6. 향후 추진계획

□ 국제표준의 주요 내용 분석 및 국내 적용성 분석

• ISO 및 IEC 표준의 심층분석(Working Group)

• 활용대상, 적용분야 및 현장 적용성 검토

• 현장적용 타당성 확인 및 문제점 도출

□ 국제표준의 국내규제기준 적용방안수립

• 국내도입 국제표준의 확정

• 문제점 해결방안 수립 (장/단기)

• 분야별 고시(안) 개발

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Publications issued by TC 45


• IEC 60248 (1984-11) Dimensions of planchets used in nuclear electronic instruments• IEC 60313 (2002-04) Coaxial connectors used in nuclear laboratory instrumentation • IEC 60333 (1993-07) Nuclear instrumentation - Semiconductor charged-particle detectors -Test procedures

• IEC 60405 (2003-10) Nuclear instrumentation - Constructional requirements and classification of radiometric gauges

• IEC 60412 (2007-06) Nuclear instrumentation - Scintillation detectors - Nomenclature (identification)

• IEC 60462 (1974-01) Standard test procedures for photomultiplier tubes for scintillation counting

• IEC 60476 (1993-07) Nuclear instrumentation - Electrical measuring systems and instruments utilizing ionizing radiation sources - General aspects

• IEC 60482 (1975-01) Dimensions of electronic instrument modules (for nuclear electronic instruments)

• IEC 60498 (1975-01) High-voltage coaxial connectors used in nuclear instrumentation• IEC 60516 (1975-01) A modular instrumentation system for data handling; CAMAC system • IEC 60516-am1 (1984-01) Amendment 1 - A modular instrumentation system for data handling; CAMAC system

• IEC 60527 (1975-01) Direct current amplifiers; characteristics and test methods

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• IEC 60547 (1976-01) Modular plug-in unit and standard 19-inch rack mounting unit based on NIM standard (for electronic nuclear instruments)

• IEC 60547-am1 (1985-01) Amendment 1 - Modular plug-in unit and standard 19-inch rack mounting unit based on NIM standard (for electronic nuclear instruments)

• IEC 60552 (1977-01) CAMAC - Organization of multi-crate systems. Specification of the Branch-highway and CAMAC crate controller Type A1

• IEC 60552-am1 (1984-01) Amendment 1 - CAMAC - Organization of multi-crate systems. Specification of the Branch-highway and CAMAC crate controller Type A1

• IEC 60600 (1979-01) Equipment for minehead assay and sorting radioactive ores in containers

• IEC 60640 (1979-01) CAMAC - Serial Highway Interface System• IEC 60640-am1 (1984-01) Amendment 1 - CAMAC - Serial Highway Interface System• IEC 60650 (1979-01) Analogue counting ratemeters. Characteristics and test methods• IEC 60677 (1980-01) Block transfers in CAMAC systems• IEC 60692 (1999-11) Nuclear instrumentation - Density gauges utilizing ionizing radiation -Definitions and test methods

• IEC 60713 (1981-01) Subroutines for CAMAC• IEC 60729 (1982-01) Multiple controllers in a CAMAC crate• IEC 60739 (1983-01) Digital counting ratemeters - Characteristics and test methods• IEC 60741 (1982-01) Multichannel amplitude analyzers: Standards for time-to-amplitude converters

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• IEC 60759 (1983-01) Standard test procedures for semiconductor X-ray energy spectrometers

• IEC 60759-am1 (1991-11) Amendment 1 - Standard test procedures for semiconductor X-ray energy spectrometers

• IEC 60775 (1983-01) Real-time BASIC for CAMAC• IEC 60808 (1985-09) Complementary instrumentation for counting ratemeters -Characteristics and test methods

• IEC 60912 (1996-06) Nuclear instrumentation - ECL (emitter coupled logic) front panel interconnections in counter logic (Revision of IEC 912)

• IEC 60935 (1996-07) Nuclear instrumentation - Modular high speed data acquisition system - FASTBUS

• IEC 60973 (1989-06) Test procedures for germanium gamma-ray detectors• IEC 60982 (1989-12) Level measuring systems utilizing ionizing radiation with continuous or switching output

• IEC 61052 (1991-03) IEC 1052 FASTBUS standard routines. Standard routines for use with FASTBUS data acquisition system

• IEC 61134 (1992-06) Airborne instrumentation for measurement of terrestrial gamma radiation

• IEC 61145 (1992-05) Calibration and usage of ionization chamber systems for assay of radionuclides

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Publications issued by SC 45A

• IEC 60231 (1967-01) General principles of nuclear reactor instrumentation• IEC 60231A (1969-01) First supplement• IEC 60231B (1972-01) Second supplement: Principles of instrumentation of direct cycle boiling water power reactors

• IEC 60231C (1974-01) Third supplement: Instrumentation of gas-cooled graphite-moderated reactors

• IEC 60231D (1975-01) Fourth supplement: Principles of instrumentation for pressurized water reactors

• IEC 60231E (1977-01) Fifth supplement: Principles of instrumentation of high temperature indirect cycle gas-cooled power reactors (HTGR)

• IEC 60231F (1977-01) Sixth supplement: Steam generating, direct cycle, heavy-water moderated reactors

• IEC 60231G (1977-01) Seventh supplement: Liquid-metal cooled fast reactors• IEC 60515 (2007-02) Nuclear power plants - Instrumentation important to safety -Radiation detectors - Characteristics and test methods

• IEC 60557 (1982-01) IEC terminology in the nuclear reactor field• IEC 60568 (2006-01) Nuclear power plants - Instrumentation important to safety - In-core instrumentation for neutron fluence rate (flux) measurements in power reactors

• IEC 60671 (2007-05) Nuclear power plants - Instrumentation and control systems important to safety - Surveillance testing

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• IEC 60709 (2004-11) Nuclear power plants - Instrumentation and control systems important to safety - Separation

• IEC 60737 (1982-01) In-core temperature or primary envelope temperature measurements in nuclear power reactors. Characteristics and test methods

• IEC 60744 (1983-01) Safety logic assemblies of nuclear power plants - Characteristics and test methods

• IEC 60768 (1983-01) Process stream radiation monitoring equipment in light water nuclear reactors for normal operating and incident conditions

• IEC 60772 (1983-01) Electrical penetration assemblies in containment structures for nuclear power generating stations

• IEC 60780 (1998-10) Nuclear power plants - Electrical equipment of the safety system -Qualification

• IEC 60880 (2006-05) Nuclear power plants - Instrumentation and control systems important to safety - Software aspects for computer-based systems performing category A functions

• IEC 60910 (1988-03) Containment monitoring instrumentation for early detection of developing deviations from normal operation in light water reactors

• IEC 60911 (1987-03) Measurements for monitoring adequate cooling within the core of pressurized light water reactors

• IEC 60951-1 (1988-08) Radiation monitoring equipment for accident and post-accident conditions in nuclear power plants. Part 1: General requirements

• IEC 60951-2 (1988-08) Radiation monitoring equipment for accident and post-accident conditions in nuclear power plants. Part 2: Equipment for continuously monitoring radioactive noble gases in gaseous effluents

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• IEC 60951-3 (1989-12) Radiation monitoring equipment for accident and post-accident conditions in nuclear power plants. Part 3: High range area gamma radiation dose rate monitoring equipment

• IEC 60951-4 (1991-12) Radiation monitoring equipment for accident and post-accident conditions in nuclear power plants - Part 4: Process stream in light water nuclear power plants

• IEC 60951-5 (1994-02) Nuclear power plants - Radiation monitoring equipment for accident and post-accident conditions - Part 5: Radioactivity of air in light water nuclear power plants

• IEC 60960 (1988-08) Functional design criteria for a safety parameter display system for nuclear power stations

• IEC 60964 (1989-03) Design for control rooms of nuclear power plants• IEC 60965 (1989-01) Supplementary control points for reactor shutdown without access to the main control room

• IEC 60980 (1989-06) Recommended practices for seismic qualification of electrical equipment of the safety system for nuclear generating stations

• IEC 60987 (2007-08) Nuclear power plants - Instrumentation and control important to safety - Hardware design requirements for computer-based systems

• IEC 60988 (1990-10) Acoustic monitoring systems for loose parts detection -Characteristics, design criteria and operational procedures

• IEC 61031 (1990-07) Design, location and application criteria for installed area gamma radiation dose rate monitoring equipment for use in nuclear power plants during normal operation and anticipated operational occurences

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• IEC 61224 (1993-05) Nuclear reactors - Response time in resistance temperature detectors (RTD) - In situ measurements

• IEC 61225 (2005-12) Nuclear power plants - Instrumentation and control systems important to safety - Requirements for electrical supplies

• IEC 61226 (2005-02) Nuclear power plants - Instrumentation and control systems important to safety - Classification of instrumentation and control functions

• IEC 61227 (1993-06) Nuclear power plants - Control rooms - Operator controls• IEC 61250 (1994-01) Nuclear reactors - Instrumentation and control systems important for safety - Detection of leakage in coolant systems

• IEC 61343 (1996-03) Nuclear reactor instrumentation - Boiling light water reactors (BWR) -Measurements in the reactor vessel for monitoring adequate cooling within the core

• IEC 61468 (2000-03) Nuclear power plants - In-core instrumentation - Characteristics and test methods of self-powered neutron detectors

• IEC 61468-am1 (2003-06) Amendment 1 - Nuclear power plants - In-core instrumentation -Characteristics and test methods of self-powered neutron detectors

• IEC 61497 (1998-10) Nuclear power plants - Electrical interlocks for functions important to safety - Recommendations for design and implementation

• IEC 61500 (1996-03) Nuclear power plants - Instrumentation and control systems important to safety - Functional requirements for multiplexed data transmission

• IEC 61501 (1998-11) Nuclear reactor instrumentation - Wide range neutron fluence rate meter - Mean square voltage method

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• IEC 61502 (1999-11) Nuclear power plants - Pressurized water reactors - Vibration monitoring of internal structures

• IEC 61504 (2000-05) Nuclear power plants - Instrumentation and control systems important to safety - Plant-wide radiation monitoring

• IEC 61505 (1998-11) Nuclear reactor instrumentation - Boiling water reactors (BWR) -Stability monitoring

• IEC/TR 61510 (1996-08) RBMK nuclear reactors - Proposals for instrumentation and control improvements

• IEC 61513 (2001-03) Nuclear power plants - Instrumentation and control for systems important to safety - General requirements for systems

• IEC 61771 (1995-12) Nuclear power plants - Main control-room - Verification and validation of design

• IEC 61772 (1995-08) Nuclear power plants - Main control room - Application of visual display units (VDU)

• IEC/TR 61838 (2001-02) Nuclear power plants - Instrumentation and control functions important for safety - Use of probabilistic safety assessment for the classification

• IEC 61839 (2000-07) Nuclear power plants - Design of control rooms - Functional analysis and assignment

• IEC 61888 (2002-08) Nuclear power plants - Instrumentation important to safety -Determination and maintenance of trip setpoints

• IEC/TR 61940 (1998-06) Nuclear instrumentation - A review of the application of IEC 60880(1986)

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Publications issued by TC 45• IEC/TR 61963 (2005-02) Nuclear power plants - Main control room - Comparison of IEC

60964 to similar standards on control room design• IEC/TR 62096 (2002-09) Nuclear power plants - Instrumentation and control - Guidance for

the decision on modernization• IEC 62117 (1999-12) Nuclear reactor instrumentation - Pressurized light water reactors (PWR)

- Monitoring adequate cooling within the core during cold shutdown • IEC 62118 (2000-11) Nuclear reactor instrumentation - Pressurized water reactor (PWR) of

VVER design - Monitoring adequate cooling within the core during shutdown• IEC 62138 (2004-01) Nuclear power plants - Instrumentation and control important for safety

- Software aspects for computer-based systems performing category B or C functions • IEC/TR 62235 (2005-03) Nuclear facilities - Instrumentation and control systems important to

safety - Systems of interim storage and final repository of nuclear fuel and waste• IEC 62241 (2004-11) Nuclear power plants - Main control room - Alarm functions and

presentation• IEC/TR 62247 (2003-09) Nuclear power plants - Main control room design - A review of the

application of IEC 60964 (1989)• IEC 62342 (2007-08) Nuclear power plants - Instrumentation and control systems important to

safety - Management of ageing• IEC 62385 (2007-06) Nuclear power plants - Instrumentation and control important to safety -

Methods for assessing the performance of safety system instrument channels• IEC 62397 (2007-05) Nuclear power plants - Instrumentation and control important to safety -

Resistance temperature detectors

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