Regulatory Guide 1.28
| ML13350A384 | |
| Person / Time | |
|---|---|
| Issue date: | 03/31/1978 |
| From: | NRC/OSD |
| To: | |
| References | |
| RG-1.028, Rev 1 | |
| Download: ML13350A384 (2) | |
U.S. NUCLEAR REGULATORY
COMMISSION
Revision i March 1978 REGULATORY
GUIDE OFFICE OF STANDARDS
DEVELOPMENT
REGULATORY
GUIDE 1.28 QUALITY ASSURANCE
PROGRAM REQUIREMENTS (DESIGN AND CONSTRUCTION)
A. INTRODUCTION
National Standards Institute olt A '1 7, 1977.'Some uncertainty has arise ith regard !o the Appendix B. "Quality Assurance Criteria for Nu- NRC staff's position when e R tory guide cn-clear Power Plants and Fuel Reprocessing Plants," dorses, as an acceptabIe rd od, "i'guidelines- to 10 CFR Part 50. "Licensing of Production and as well as the "requir It. nclu ed in a stand-Utilization Facilities," establishes overall quality ard. The NRC staf d the guidelines assurance requirements for the design, construction, contained in N45 97 'th r spect ,o importance and operation of safety-related structures, systems, to safety. Thi., to guide is interded (o and components.
This guide describes a method ac- clarify the , C f'sosition on the "reqtsie.ceptable to the NRC staff for complying with the ments.. a u ,nes included in ANSI Commission's regulations with regard to overall N45.2. 7. conformance to the recommen-quality assurance program requirements during de- datio rc ulatory guide is indicated in an sign and construction of nuclear power plants. cat out further qualification, this indi-c at e applicant will comply with the "re-B.DSUSINts" of ANSI N45.2-1977, as supplemented Subcommittee N45-2.7 (formerly N45-3.7) of the di ied by the regulatory position of this guide.American National Standards Committee Reactor Plants and Their Maintenance, dev ope C. REGULATORY
POSITION ANSI N45.2-1971 that included general r 're- The overall quality assurance program require-ments for establishing and executing a y a ments for the design and construction phas.s that are ante program during the design an const tion included in ANSI N45.2-1977 provide an adequate phases of nuclear power plants. This nd was basis for complying with the quality assurance pro.endorsed by Regulatory Guide 1.28 ( Guide gram requirements of Appendix B to 10 CFR Part 28). To update the requirements of the standard and 50, as supplemented or modified by the following:
to make it applicable toft nuclear facilities sub-ject to 10 CFR Part AI dix B, the standard Section 2 of N45.2-1977 requires.
in part. that was revised by the N4 A iGroup in coopera- "A documented Quality Assurance Program which tion with the N 4,Groupc ioittee. complies with the applicable sections and elements The revised rna wapproved by Subcom- of this standard shall be established at the earliest mittee ear ality Assurance Standards, practical time consistent with the schedule for ac-of the A Ci I~p l Standards Committee N45 complishing the activities for the nuclear facility." and the 1 45 committee and by Subcommittee The following information should be used to clarify N46-2, the fIN46 committee, and the N18 commit- the requirement of Section 2 of ANSI N45.2-1977.
tee. It was s sequently approved and designated Copies may be obtained from the American Society (if N45.2-1977, "Quality Assurance Program Re- Mechanical Engineers, United Engineering Center. 345 East quirements fur Nuclear Facilities," by the American 47th Street. New York, N.Y. 1001
7. USNi C REGULATORY
GUIDES Comments should be iint to the Semetary of the coniuon. US NutrWhe' squ RMgtalory GU.deware iNRCd toRdescbe " GUa&"AabiDtoIthe Publicmethods wre, Commission.
Washflgton, D C 2055S. Attiteon Docha,. ,*n #'d S.*. r, socettable it the NRC staff of #empteetirigl V ietc Pan& of the Comm'suon't Branch.irgulations.
tO delineteitt tCthn-Cl'
r used by the itaff in *valuating problemt The h uidiesa I the foltott ,ng It, dwsvont or Pomlulatsc oat tn to rovidte uid¢nce to Reutatony Guid" are Mot subaulate for regultitons, and complianet wieth thorn ts not required.
1. Power Reaido., 6 Produ~cts lethodo and sul'or diff erent from thos, let o ut i'n the gsacde wtlt l be e et 2. Researca Teo Rectors
7. Rtonapotrifro
't Ae it they hOitds a belt, for the finditp rmielete to the isance or ocontInuance
3. Fuels and f Facities a. Occuiaoluo nat t th o fa parmth or license by the Comttlion
- r. 4. E s i'ieontni ,tat v ietdSiting
9. Antitust Rle..no , S. end Plant Protection.
10. An Ue t Comments end wemiorn for impeoment.
in those guds ae encourage at .11 timtet. end guidem will be revised. &I appropriate.
to semmmottdarte coni"Wents and Rettueti for single copisi t o ttsted queJes teet,dt m~ay be ,eiyduca1t or to, Ptace to teflBect ltow information o, e.perttence.
I4o~vw. coerton'v as on tttrt guhde~it mnwt on an automattc dirttr*utoon tilt to, Single cove" ot tutwje 2.4% ' UC.n SKih d within about two montht SOtWr .s rusuhtie.
Will be OsltiCutetl useful in dftvtons houtld be made in writng to the US. Nuclo& Rglatory C",nmn ,n.ef= uitg the need lot an aaly sewiton. Waahngtort.
O.C. M 55. Allet ton Onector. ODnsuon ot Ootument Contro//
Il -- .- .For those safety-related activities that are initiated by the applicant prior to submitting its application for a construction permit, the requirements set forth in ANSI N45.2-1977 and amplified in the applicable N45.2 series standards should be in effect prior to accomplishing the activities.
The following are examples of such activities that are or may be ini-tiated prior to submitting the application:
a. Activities performed in the establishment of the information required to he included in the Prelimi-nary Safety Analysis Report.h. Activities pertaining to the preparation of de-sign and procurement documents affecting safety-related structures, systems. and components, 2. The guidelines (indicated by the verb "should")of ANSI N45.2-1977 contained in the following sec-tions have sufficient safety importance to be treated the same as the requirements (indicated by the verb"shall") of the standard: a. Section 14. second paragraph-The guidelines on procedures for critical, sensitive, periihable.
oi'high-value articles and on use and control of special handling tools.b. Section 19. second paragraph-The guideline on when to perform audits.c. Section 19. third paragraph-The guideline in the first sentence of the paragraph that indicates the three general areas of evaluation to include in an audit.d. Section 19. fifth paragraph-The guideline on developing an audit plan, e. Section 19. sixth paragraph-The guideline on scheduling of audits and the guideline that specifies the conditions that require conducting audits.3. The Foreword and Section 1.2. "Applicability." of ANSI N45.2-1977 state: "The ASME Boiler and Pressure Vessel Code, as well as other American National Standards, have been considered in the de-velopment of this standard, and this standard is in-tended to be compatible with their requirements.
However. this standard does not apply to Ihe at'.tivities covered hy Section III mid t'clioti XIl otf li Code." It is important to consider the relationship of the quality assurance requirements included in Section III of the Code with those included in ANSI N45.2. Code-covered activities are primarily in-tended to ensure the integrity of the pressure bound-ary of an item.Section III of the Code does not ad-dress activities necessary io ensure fuactional operability of sonic Code-covered items such as pumps or values. Therefore.
to ensure functional operability of these items, the quality assurance program for design and construction should hb ex-tended to these other activities, and the guidance in N45.2 should be used, as appropriate.
D. IMPLEMENTATION
The purpose of this section is to provide informa-tion to applicants and licensees regarding the NRC staff's plans for using this regulatory guide. Except in those cases in which the applicant proposes an alternative method for complying with specified por-tions of the Commission's regulations.
the method described herein will be used in the evaluation of submittals for construction permit applications dock-eted after November 30. 1978. If an applicant whose application for a construction permit is docketed on or before November 30, 1978. wishes to use this reg-ulatory guide in developing submittals for applica-tions, the pertinent portions of the application will be evaluated on the basis of this guide.1.28-2