ML19221A889
| ML19221A889 | |
| Person / Time | |
|---|---|
| Issue date: | 06/30/1976 |
| From: | NRC OFFICE OF STANDARDS DEVELOPMENT |
| To: | |
| References | |
| REGGD-01.064, REGGD-1.064, NUDOCS 7907100242 | |
| Download: ML19221A889 (2) | |
Text
Revision 2 U.S. NUCLEAR REGULATORY COMMISSION June 1976 g REGU' S TORYGCBDE OFFlCE OF STANDARDS DEVELOPMENT HEGULATORY GUIDE 1.64 QUALITY ASSURANCE REQUIREMFNTS FOR THE DESIGN OF N'JCLEAR POWER Pl ANTS A. INTRODUCTION C. REGULATORY POSITION Appenda b, Quahty Assurance Cntena for Nuclear The requirements ar.d recommendatiors for estabhsh-Power Plants and Fuel Reprocessing Plants," to 10 CFR ing and executmg a quahty asst.rance program during the Pa rt 50. "Ucensing of Production and Utthzation design phase of nuclear power plants that are included in Facthties," estabhshes overall quality assurance require-ANSI N45.2.11 1974' are acceptable to the NRC staff ments for the design, construction, and operation of and prmide an adequate basis for complying with the safety-related structures, systems, and components of pertment quahty assurance requirements of Appendix B nuclear power plants. This guide desenbes a method to 10 CFR Part SO, subject ro the following:
acceptab'e to *he NRC staff for complying with the Commission's regulations with regard to quahty assur-anse requaements for the design of all types of nuclear
- 1. Subdivision 1.5 of ANSI N45.2.11 1974 states p n er ; h ts.
he Advisory Committee on Reactor that other documents that are required to be included as Sate
.c h ha been consulted concernmg this guide and a pm of this standard adl be identified at thc point of hn wasuned in the regulatory position.
reference and described in Section 12 of the standa-d.
The specific acceptability of these lis*ed documents has B. DISCUSSION been or will be cosered separately in other regulatory
- E"'*
- EE' hking Group N45 2.11 of the American National Stand rds Committee N45, Reactor Plants and Their Mamtenance, has prepared a standard that delineates
- 2. hstead of the second sentence of the second requaements and recommendations for estabiishing and paragraph of Section 6.1 on design verification, the executmg a quahty assurance program for the design of following should be used: "The duties of a ' supervisor' nucler power plan 2. Tlus standard was approved by and the relationship with subordmates vary widely in dif-subcommittee N45-2. Nuc! car Quality Assurance Stan-ferent orjanizations. Regardless of their title, individuals dards, of the Amencan National Standards Institute performing design verification should not (1) have Committee N45 and the full committee and its secretar.
immediate supervisory responsibility for the individual ia t.
It was subsequently approved and designated performing the design, (2) have specified a singular N45. 2.1 1 19 74 t:y the American National Standards design approach, (3) have ruled out certain design Institute on June 6,1974.
considerations, or (4) have estabhshed the design inputs for the particular design aspect being verified. Whil:
Revision I to Regulatory Guide 1.64, which endorsed design verification by the designer's immediate supervi-
.NSI N45.2.11 1974, was published in February 1975.
sor is encouraged,it should not be construed that such As a result of comments received on the guide and verification constitutes the required independent design additional staff review, the staff has developed Revision
- 2. The only sigmficant change in the regulatory position mvuhes position C.2 concerning performance of design
- ANfl N45.2.11 1974. "Quahty Assurance Requirements for serification by supervisors.
the Design of Nutlear Power Plants," may be obtaincJ from the Amencan Society of Mechanical Engneers,l'nited Engneering
- Lines denMe wbstantae changes from previous issue.
Center,345 Last 47th Street, New York, NY 10017.
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- o. n t i c a ' m n n oi should the independent design serilisa-construed to mean "Noi ;onformance with pros Jmes
- n. n be construed to ddute or replace the clear responst-for the preparation and cointml of speciheationc a.J m N m,.! supenisors for the quality of work performed Section 4.5, item (7), "Nenconformance with Jewn ccr deir supenision."
document nquirements,' should be construed to n,can "Nonconformance with protewres for the prtpara'i In the first sen tence of Sec tion 8 of and control of design documents."
N34 111974, the word "effectmg" should t)e inserted
' design changes" ior clanfication. Further, the Nt re approved design Jocuments" should be construed D. IMPLEMENTATION
' m
'Jesign out put" (see Section 1.4) approved by
- m u i n.cn/atwn perf-mg the design.
The purpose of this section is to proside informanm to appbcants and beensees regardmg the NRC staf t's a sestions 4.3, and 4.5 of N45.2.11 197 4 plans for usmg tlus regulatory guide.
4.
s em the es bhshment of procedures for the prepara-s o
anJ : nuel of drawings, specifications, and other Except in tho e cases in which the appheant proposes t
u.. docurnents. These sections list typical subjects to an acceptable alternatise method f or cor"p!)ing with
- c arred by such pioccJures. One of the subjects to be specified pertions of the Commission's regulaimns. rhe metrJ is "nonconformances." The NRC staff considers method described herein wdl be used in the esa!uation rl.c 'nonson'urmances" liste i m these sections to be of subrruttals in connection with construction permit
. nanh,rmances with procedural requirements. Thus m appheations docketed after July I 5,1976.
l sccrim 4.3. item (11), "Nonconformance with Jrawing
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. ie n t s.'
should be construed to mean "Noncon.
11 an apphcant wishes to use this regulatory guide in mam with
- p. oce d ures for the preparation and deselopmg submittals for apphcations docketed on or at to! er dra wings," in Section 4.4, item (7), "Noncon-before July 15, 1976, the pertinent portions of the r r:ance w n b specification requirements," should be application wdl be evaluated on the basis of this guide.
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