ML19221A858

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For Comment Issue of Reg Guide 1.28,Revision 1, QA Program Requirements (Design & Const)
ML19221A858
Person / Time
Issue date: 03/31/1978
From:
NRC OFFICE OF STANDARDS DEVELOPMENT
To:
References
REGGD-01.028, REGGD-1.028, NUDOCS 7907100128
Download: ML19221A858 (2)


Text

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U.S. NUCLEAR REGULATORY COMMISSION March 1978 8 M REGMORYG TDDE M*

OFFICE OF STANDARDS DEVELO? MENT REGULATORY GUIDE 1.28 QUALITY ASSURANCE PROGRAM REQUIREMENTS (DESIGN AND CONSTRUCTION)

A. lNTRODUCTION National Standards Institute on A 'l7,1977

  • Some oncertainty has aris th regard to the Appendit II, " Quality Assurance Criteria for Nu NRC staff's position w hen ory guide en-clear Power Plants and Fuel Reprocessing Plants,"

dorses, as an acceptable i id,

'guidelinev to 10 CFR Part 50, " Licensing of Production and as well as the "requiry-nclu d in a stand-Utilitation Facilities,' establishes oserall qualit) ard. The NRC sta @

5cd the guidelines assurance requirements for the design, construction, contained in N4 977%th respect to importance and operation of safety-related structures, systems, to safety. Thi ' gdato?? guide is intended to and components. This guide describes a method ae-clarify the JWC fjf Mosition on the " require-certable to the NRC staf f for complying with the ments a D euIiffine v included in ANSI Co m mi s sio n 's regulations with regard to overall N45. ', J7. k conformance to the recommen-quality assurance program requirements during de-datior.$

Are)ulatory guide is indicated in an sign and construction of nuclear power plants.

p eat' Eithout further qualification, this indi-cht8 atDe applicant will comply with the "re-B. DISCUSSION A quych ts" of ANSI N45.21977, as supplemented Subcommittee N45-2.7 (formerly N45-3.7) of the

%' di ied by the regulatory poution of this guide.

American National Standards Committee )(K4 9 Reactor Plants and Their Maintenance, degopedQ 4 C. REGULATORY POSITION ANSI N45 21971 that included general ry ire-h The overall quality assurance program require-ments for establishing and esecuting ag8 Shy a%

ments for the design and construction phases that are ance program during the design anbconst tion included in ANSI N45 2-1977 provide an adequate phases of nuclear power plants. ThiWNnda i was basis for complyinF with the quality assurance pro-endorsed by Regulatory Guide 1.28 6

, 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 to nue' ear facilities sub-ject to 10 CFR Part A p dit B, the standard

1. Section 2 of N45.2-1977 requires, in part, that was resised by the N4 y

Group in coopera,

" A documented Quality Assurance Program which tion with the 'N-t McQittee.

c mplies with the applicable sections and elements The resised ndalpar approsed by Subcom.

f this standard shall be established at the earliest mittee N45 p. \\ lear. iality Assurance Standards, practical time consistent with the schedule f or ac-of the A wpi

' I Standards Committee N45 complishing the actisities for the nuclear facility.

and the 5 45 committee and by Subcommittee The following information should be used to clarify N46-2, the %N46 committee, and the NIH commit.

the requirement of Section 2 of ANSI N45.21977.

tee. It w as s sequently approved and designated

  • Copies may be obtained from the American Socien of N4 5. 2-19 7 7,

' Quality Assurance Program Re-Mechanical Engineers. United Engir eering center, us Eau quirements for Nuclear Facilities, ' by the American 47th sireci. New York. N.Y.10o17.

USNRC REGULATORY GUIDES com"*au hid te wat to t*e sa me, af ow c-~~~ i u s Nooes %,

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For those safety-related actisities that are initiated

3. The Foreword and Section 1.2,

' A pphc abiht y,

by the applicant prior to submitting its application of ANSI N45.2-1977 state: "The ASME Iloiler and fer a construction pernut, the requirements set forth Pressure Vessel Code, as well as other American in ANSI N45.21977 and amplified in the applicable National Standards, hase been wnsidered in the de-N45 2 series standards should be in ef fect prior to selopment of this standard, and this standard is in-accemplishing the activities. The following are tended :o be compatible with their requirements examples of such actisities that are or may be ini-lloweser, this standaid does not apply to the ac tiated prior to submitting the application:

tuities covered by Sestion lit and Nection XI of the Code.

It is important to consuler the relationship

a. Actisities performed in the establishment of the of the quality assurance requirements included m information required to be included in the Prelimi.

Section 111 of the Code with those included in ANSI nary Safety Analysis Report.

N45.2. Code-covered actisities are primarily in.

b. Actaities pertaining to the preparation of de.

tended to ensure the integrity of the pressu e bound-sign and procurement documents af fecting safety.

ary of an item. Section 111 of the Code does not ad-dress actisities necessary to ensure f unctionel related structures, sy stems, and components.

operability of some Code-cos cred items such as

2. The cuidelines tindicated bv the serb 'should")

purnps or s alues. "I'herefore, to ensure functional of ANS N45.2-1977 contained in the followine sec_

operabihty of these items, the quality assurance tions base sufficient safety importance to be treated program for design and construction should be ex-the same as Ibc requirements tindicated by the serb tended to these other actaitics..md the gmdance m N45.2 should be used, as appropriate.

' shat!") of the standard:

D. IMPLEMENTATION

a. Section 14, second paragraph-The guidelines on procedures for critical, sensitise, perishable, or T he purpose of this section is to provide informa-high-value articles and on use and control of special tion to applicants and licensees regarding the NRC handling tools.

s'aff's plans for using this regulatory guide. Euept

b. Section 19. second paragraph-The guideline in those cases in which the applicant proposes an on w hen to perforrr audits.

alternatise method for complying with specified por-

c. Section 19, third paragraph-The guideline in tions of the Commission's regulations, the method the first sentence of the paragraph that indicates the described herein will be used in the esaluation of three general areas of evaluation to include in an submittals for construction permit applications dock-audit.

eted after Nm ember 30, 1978. If an applicant whose

d. Section 19, fifth paragraph-The guideline on application for a construction permit is docketed on developing an audit plan.

or before November 30,1978, wishes to use this reg-

e. Section 19, sixth paragraph-The guideline on ulatory guide in deseloping submittals for applica-scheduling of audits and the guideline that specifies tions, the pertinent portions of the application will be the conditions that require conducting audits.

euluated on the basis of this guide.

O 125 142 1.28-2

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