ML20206B325
| ML20206B325 | |
| Person / Time | |
|---|---|
| Issue date: | 10/25/1988 |
| From: | Kerr W Advisory Committee on Reactor Safeguards |
| To: | Zech L NRC COMMISSION (OCM) |
| References | |
| ACRS-SL-0351, ACRS-SL-351, NUDOCS 8811150412 | |
| Download: ML20206B325 (4) | |
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UNITED STAT ES
- I NUCLEAR REGULATORY COMMIS$10N ADVISORY COMANTTit ON RE ACTOR SAFEQUARD$
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w AsHIneoY04. O. C. N4a4 I
October PS, 1988 1
l The Honorable Lando W. Zech, Jr.
(
Chaiman U.S. Nuclear Regulatory Comission d'
i Washington, D.C.
20555 i
Dear Chairman Zech:
SUBJECT:
THREE HUNDRED FCRTY-SECOND MEETING OF THE ADVISORY COMMITTEE i
ON REACTOR SAFEGUARDS, OCTOBER 6-7, 1988 The Advisory Comittee on Reactor Safeguards held its 342nd meeting, in l
J Behesda, Md., on Octcber 6-7, 1988, t
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ACRS REPORTS / ACTIONS The Comittee ccepleted its report on the Preapplication Safety Evalua.
f tion Report for the Modular High Temperature Ga Cooled Reactor. (i.etter t
to Chairran Zech dated October 13, 1988)
The Cornittee was briefed by representatives of the Staff, the Depart-d l
nent of Energy, and All Chemical isotope Enrichment, Inc. on the Licens-i ing of All Chemical Isotope Enrichment Facilities and prepared a~ report 4
(Letter t3 Chairman Zech dated October 13, to y)ou on this subject.
1988 Peports on the subjects noted above have been sent to you.
l t
OTHER ACTIONS. AGRECHENts, ASS!GNMENTS, AND REQUESTS i
4 1
1 Dr. Siess reported to the Comittee on the nature of the proposed
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anendment of 10 CFR 50, Appendix J, "Prinary Containnent Leakage Testing i
for Water-Cooled Power Reactors."
The Comittee decided that it had no CNection to the issuance of this amendment.
Mr. Fraley infom.d Mr.
a I
b
.w of the Cemittee's decision in a remorandum dated Octcber 11, f
'P.
f A o d ttee discussed the actions which should be taken on a number of i
l issu., which had been identified as irportant safety-related issues by i,
ACRS members. The Comittee's decisions included the following:
i t
l (a) The ACRS Subcomittee on Occupational and Environmental Protec*. ion I
Systems will hold a tutorial session with the NRC Staff. FEMA, and j
i Industry groucs as appropr' ate to become better informed regarding f
i Emergency Planning at nu', tear power plants and will develop rec-
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orrendations for future ACRS actions.
The tutorial session tas s
been tentatively scheduled for March 2, 1989.
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i The Honorable'Lando W. Zech, Jr. October 25, 1988 (b) The Subcomittee on Systematic Assessment of Experience 'will develop recommendations regarding the Comi ttee's approach to reviewing reactor operating experience.
(c) The Subcomittee on AC/DC Power Systems Reliability will discuss the adequacy of lightning and electrical power surge protection and develop recomendations as necessary, for ACRS consideration, for improvements in existing plants and for establishing requirements for future plants.
(d) The Subcommittee on Instrumentation and Control Systems will discuss the need for improved quality of instrumentation and control systems in t.Jclear power plants and develop recomendations av appropriate.
p The Committee did not complete its discussions of Hierarchical Structure for Important Safety-Related Issues. Time will be scheduled to continue these discussions during the November 17-19, 1988 ACRS meeting.
Mr. Michelson briefed the. Comittee on the status of the Mechanical Con,ponents Subcomittee review of the NRC Staff's proposed expended testing and surveillance requirements for motor-operated valves.
further discussion of this subject has been scheduled during the October 26-27, 1988 meeting of this Subcommittee.
Industry representatives are expected to attend and give presentations on the impact of the Staff's proposed new requirements.
The Cemittee's discussion of and action on this matter will be scheduled during the November 17-19, 1988 ACRS meeting.
Mr. Ward briefed the Comittee on the status of planning for the Inter-
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national Conference on Quality. This conference is scheduled to be held on May 14-18, 1989, in San Diego, Calif.
Mr. Ward recomended that the Comittee review the matters discussed and the conclusions arrived at after the conference, s
The Comittee was briefed by representatives of the NRC Staff and BNL on i
the design features of the PRISH reactor.
Time will be scheduled to continue these discussions and to develop a report on the PRISM design during the November 17-19, 1988 ACRS meeting.
The Comittee was briefed by the Staff on the proposed inplementation plan for the NRC's Safety Goal Pelicy.
The Comittee decided not to report on this matter until the NRC Staff has completed their develop-m,nt of the proposed implementation plan.
The Comittee plans to discuss and report un the proposed implementation plan during the November 17-19, 1988 meeting.
4 Mr. Ward asked that a briefing on the lessons learned from the NRC Staff's Diagnostic Evaluation Program be requested from the appropriate industry representatives.
The chairman of the Systematic Assessment of
6 The Honorable Lando W. Zech, Jr. October 25, 1988 Experience Subcomittee agreed to make the necessary arrangements for such a briefing.
The Comittee's briefing on misrepresented equipment was postponed to the Novembv 17-19, 1980 ACRS meeting.
The Committee decided not to schedule matters for discussion at an ACRS l
neeting unless the documents to be reviewed are made available to the i
Comittee during the ACRS meeting held one month before the meeting at which these matters are to be discussed.
Mr. Fraley is to advise the Staff regarding the Comittee's decision.
Exceptions would be made only r
in special cases such as specific Comission requests and when the j
restart cf a plant would be unnecessarily delayed.
Since the last report of ACRS activities, the foi;owing subcommittee meetings have been held:
Mechanical Components, October 4,1988 - The Subcomittee reviewed the hRC Staff's proposed new requirements for in-situ testing and surveillance of safety-related motor-operated valves.
r The Subcomittee Advanced Reactor Designs. October 5,
1988 reviewed the NRC Stt,5f draft Safety Evaluation Report for the PRISM i
t
- design, FUTURE AGENDA The following items have been scheduled for consideration during the ACRS meeting on November 17-19, 1988:
Briefing regarding lessons learned from Operator Requalifica tion implementation of revised operator requalification methodology (Draf t l
Examiner Standard 601).
j Liquid Metal Cooled Reactor - ACRS review and comment regataing proposed design features of the liquid metal cooled Power Reactor Inherently Safe 4
Module (PRISM).
l
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Quantitative Safety Goals - Review and coment on the proposed NRC Staff i
plan for implementation of the NRC's Safety Goal Policy.
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Nuclear Power Plant Valve Testing - Review and coment regarding pro-posed changes in NRC requireitents for in-situ testing of motor-uperated j
valves in nuclear power plants.
Hierarchical Structure f or Safety-Relat.ed Issues - Discuss proposed Eierarchical structure for certain issues identiffed by ACRS members in the areas of ACRS procedures and practices and NRC regulatory practices.
The Honorable Lando W. Zech, Jr. October 25, 1988 Misrepresented Equipment in Nuclear Power Plants _ - Briefing regarding hRC staff activities related to the supply and use of hisrepresented equipment in nuclear power plants.
Sincerely, William Kerr Chairman