ML19308C860
| ML19308C860 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/01/1977 |
| From: | Case E Office of Nuclear Reactor Regulation |
| To: | Gossick L NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| References | |
| RTR-REGGD-01.032, RTR-REGGD-01.099, RTR-REGGD-1.099, TASK-TF, TASK-TMR NUDOCS 8002070610 | |
| Download: ML19308C860 (2) | |
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4,*g UNITE 3 STATES NUCLEAR REGUt.ATORY COMMISSION
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February 1,1977 MEMORANDUM FOR:
Lee V. Gossick, Executive Director for Operations FROM:
E. G. Case, Chairman, Regulatory Requirements Review Committee
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SUBJECT:
SUMMARY
OF REGULATORY REQUIREMENTS REVIEW COMMITTEE MEETING NO. 57, JANUARY 14, 1977 The Committee reviewed:
1.
PROPOSED REGULATORY GUIDE 1.99, REVISION 1, " EFFECTS OF RESIDUAL ELEMENTS ON PREDICTED RADIATION DAMAGE TO REACTOR VESSEL MATERIALS,"
and recommended appraval subject to the following-commentsd a.
The footnote on research and construction ' experience on page 1 of the proposed revision should be expanded to include the wording concerning the limitations of the guide suggested by the Office of Nuclear Regulatory Research.
b.
The Committee characterized paragraphs C.1, C.2, and C.4 of the proposed Regulatory Position as C,ategory 3 - backfit required; and paragraph C.3 as C tegory 1 - no backfiY-x PROPOSEDREGULATORYGUIDE1.XX,"ACCEPTABbl0DELANDRELATED 2.
STATISTICAL METHODS FOR ANALYSIS OF FUEL DENSIFICATION," and found that the proposed Regulatory Guide represented an acceptable model and appropriate methods for analysis of fuel densification effects. Utilization of such models and methods in the licensing process should be implemented in accordance with 10 CFR 50.46 and the related Appendix K to 10 CFR 50.46, 3.
DRAFT REGULATORY GUIDE 1.XXX, " INSPECTION OF WATER CONTROL STRUCTURES ASSOCIATED WITH NUCLEAR PLANT FACILITIES" (DRAFT "A",
DATED SEPTEMBER 17, 1976) and recommended approval subject to the following comments:2 1 Committee comments refer to the draft distributed at the meeting dated January 1977, rather than the draft distributed with the agenda dated September 1976.
2The Committee comments refer to the draft guide distributed at the meeting dated December 16, 1976, rather than the draft distributed with the agenda dated September 17, 1976.
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. a.
The Committee review of this proposed guide was limited to its applicability and acceptability with regard to water control structures which could affect radiological safety. The proposed guide should be amended throughout (including the title) to set forth this limitation.
b.
The Committee leaves to the staff the development of appropriate methods and procedures to be utilized for assuring that the inspection, surveillance, and/or test requirements set forth in the guide are met by licensees.
The Committee characterized this guide as Category 3 - backfit required.
PROPOSED REVISION 2 M REGULATORY GUIDE 1.32, " CRITERIA FOR SAFhiY 4.
RELATED ELECTRIC POWER SYSTEMS FOR NUCLEAR POWER PLANTS," and recommended approval.
The Committee characterized this guide as Category 1 - no backfit.
S.
PROPOSED REGULATORY GUIDE 10.XX, " GUIDANCE ON IMPLEMENTATION OF REGULATORY GUIDES % STANDARDIZED NUCLEAR POWER PLANTS," and concluded the following:
a..
Guidance on the implementation of regulatory guides for standardized nuclear power plants should be included in a revision to WASH-1341, rather than in a regulatory guide.
b.
The present system for Committee characterization of the backfit potential of proposed guides for operating plants can and s hould be applied to standardized plants; i.e., Category 1 - need not be applied to standardized plants; Category 2 - applicability to standardized plants must be decided by NRR on a case-by-case basis; Category 3 - must be applied to standardized plants.
The Executive Secretary should develop and circulate for Committee -
comments within 2 weeks a proposed revision to the definitions of backfit categories previously established by the Committee i
in Meeting No. 31 (see memorandum to L. V. Gossick dated September 24,197S) that includes these additions concerning standardized plants, and clarifies, as necessary, the applicability of Committee-considered guides to custom plants with cps.
4 NRR (DPM) should develop a grogram and procedures for implementing j
c.
the Committee's recommendations concerning bacErit potYHtial of'-
changes in regulatory requirements to those specific plants not i'
- having an operating license whi are affe ted.
W E. G. Case, Chairman Regulatory Requirements Review Committee f
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