1. International Trends in qa Activities for npPs

The importance of QA activities for ensuring safety and reliability at NPPs has been recognized in every country worldwide having NPPs. The IAEA is promoting its NUSS project to facilitate international harmonization of nuclear safety fundamentals and measures (standards, guides, manuals, etc.) and to provide its member states with the outcomes. In this connection, the IAEA is compiling relevant safety requirements to be observed and safety guides to be referred to.

The IAEA Safety Series No.50-C-QA “QA for Safety in NPPs and Other Nuclear Installations,” a set of implementation standards published in 1978, identified the basic requirements to observe in QA activities from NPP design, through manufacture to operation and maintenance. Then relevant safety guides have also been compiled which recommend detailed rules on design, procurement, and other activities. This IAEA Safety Series No.50-C-QA has been updated (through 2006) as follows (Figure 10.1.1).

1978: Publication of “QA for NPPs and Nuclear Installations”. It was developed based on the

⁽[Translator’s note] Hie term "Organization” in the original ISO publication is often cited in the present book. The term is translated differently, depending on the context example translations include electric utilities; and NPP suppliers. Further, electric utilities in Japan can be interpreted as: a license applicant; a licensee; a plant owner; a plant operator; a plant purchaser, etc. Readers should be careful in interpreting the text, based on their own national organizational structures.

US-NRC QA standards “10 CFR 50 Appendix. B”.

1988: Revised as “Safety Standard of NPPs - Quality Assurance -“(IAEA No.50-C-QA (Rev.l)).

1996: Revised as “QA for Safety in NPPs and Other Nuclear Installations” (IAEA No.50-C/SG-Q). In the revised version, mandatory items described by “shall” were limited to only fundamental ones in consideration of the results-oriented “Performance based QA”.

2006: Revised as the IAEA Safety Standards Series GS-R-3 “Management System for Facilities and Activities Safety Requirements”. It requires extensive application of the management system specified in ISO.

Countries specify their own QA concepts and implementation procedures with reference to the IAEA standards and safety guides. In reality these concepts and procedures are affected by many local factors such as the philosophy of the electric utilities, existing criteria, standards and practices in the nuclear industry, as well as contractual arrangements and NPP management policy.

3. Development of Commercial qa Standards in Japan

(l)JEAG4101“ QA guidance for NPPs”

The guidance was originally issued by the Japan Electricity Association (JEA) in 1972, based on the US-NRC QA standard “10 CFR 50 Appendix. B”. This was when QA became recognized in Japan as important for NPPs and as an issue to be tackled not only by the electric utilities but by the nuclear industry as a whole. Since then JEAC4101 has been revised according to the IAEA QA standards as follows.

JEAG4101-1990: Revised on the basis of IAEA No.50-C-QA1988.

JEAG4101-1993: Revised to include interaction with an independent audit organization.

JEAG4101-2000: Revised on the basis of IAEA NO.50-C/SG-Q 1996.

Figure 10.1.1 shows how the standards and codes on nuclear QA are mutually crossrelated.

JEAG4101-2000 had been used as the QA

NSRA, Japan

10-2

as of August 2006 (Notel) MlL-9858 1958 (Note2) 10CFR50 App.B 1967

<N

9 IL-9858A 1963

Notel.USDOD: QA Program-Requirements; applied to the suppliers to Army and Navy, Pentagon Note2.USCFR: QA Criteria for NPP and FRP Note3 ASME: Boiler & Pressure Vessel Code. Sec. HI Note4. ANCI: QA Requirements for Nuclear Facilities Note5.Japan Electric Association: QA Policy for NPP Note6.IAEA: QA for Safety in NPP and other Nuclear Installations Note7.USDOE interim standard: QA Program-A Management System: object to the sector except general commercial sector (national laboratory, experimental reactor, nuclear weapon facility and etc.) Note8.USDOE:10CFR PART 830.120(QuaIity Assurance Requirements):Order 5700.6C was modified to nuclear safety code and reduced from 18 control items to 10 control items by integration and abolishment. Note9.ANCI entrusted ASME with all the responsibility on QA criteria for NPP NSRA, Japan (Note3) ASME Sec. II App.JV 1968
ASME Sec.n NA 4000 1971
	£

ASHE Sec. IH NCA 4000 NCA 3800 NCA 3900 1974 every year Addenda published every three years Edition published ASJIE Sec. IN NCA 4000 1994 (maker obtaining ASME) 1OCFR5C for reference (Note 5) (Note4) ANSI N45.2 1977
(Note 9) ,
ANSI/ASME NOA-1 1979
	E
ANS I/ASME NQA-1.2 1983
ANS I/ASME NQA-1.2 1986
] ANSI/ASME : NQA-1.2,3 1989
-
ANSI/ASME NQA-1 1994

ANSI/ASME App.B 1970 in USA effective as of 2007 JEAG41C1 British standards BS5750 NOA-1 Firti, n.m.nr 1994 (maker obtaining ASME) determined on the basis of result I over [ (Note6) IAEA 50-C-QA 1978

for reference — reflected 1972 JEAG4T01 NIL-9858A out of use in October 1996 (replaced to ISO) 1981 NAQ-1:QA planning requirement, NAQ-2:QA requirement, NAQ-3. QA requirement for information collection for siting on high level radioactive Waste storage facility NQA-1,2 united and revised (Note?) DDE Order 5700.6C 1991 DOE Order 5700.6C 1992 (Note8) 10CFR830. 120 1994 i(inUSA) ASME NQAIwas published in2000 and also in 2004 but ASME NQA 1:1994 is endorsed by NRC. JEAG410I 1985 i IS09001 IAEA 50-C-0A 1988