ML20059N812
| ML20059N812 | |
| Person / Time | |
|---|---|
| Issue date: | 09/20/1990 |
| From: | Fraley R Advisory Committee on Reactor Safeguards |
| To: | Taylor J NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| References | |
| ACRS-GENERAL, NUDOCS 9010170319 | |
| Download: ML20059N812 (5) | |
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~ .8 UNITED STATES ! NUCLEAR REGULATORY COMMISSION.- ~'$ ' ADVISORY COMMITTEE ON REACTOR SAFEOUARDS wAsHmGTON, D. C. 20606 September 20, 1990-4 H MEMORANDUM FOR: James M. Taylor Executive-Director for Operations = ATTN: . Blaha' M M). f-FROM: R. F. Fraley,.Exocutive_ Director, ACRS.. -il Sulk 7ECT: 365th ACRS MEETING FOLLOW-UP ITEMS-j u Based on discussions regarding methodsL for. improved implementation 'a and follow-up of ACRS recommendations, the Committee agreed that a summary of Actions, Agreements,- Assignments, Requests and' Commitments made-during.each' full Committee meeting will be sent to your office following each meeting. Attached per this agreement is a" list of thetrequests;made;during-- the 365th ACRS Meeting,-September 6-7,-1990.- 4
Attachment:
~ As stated = 'l cc w/_ attachment: 4 E. L. Jordan, AEOD ( R.'M. Bernero,.NMSS T. E. Murley, NRR E. S. Beckjord, RES ] S._ Chilk, SECY A; Vietti-Cook, OCM/KC G'. Marcus, CCM/KR D. Trimble,.OCM/JC J. Guttmann,.OCM/FR 1 1 F,g 90101 h 9y$ 2 (
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I NACNJ LE POR PDC DESIGNATED ORIGINAL. L W121ed By_ ff/)f[ .l l
t -1 i L . ACTIONS, AGREEMENTS, ASSIGNMENTS,IAND-REQUESTS 365TH ACRS MEETING -{ l -September 6-7, 1990 g l t L REPORTS TO THE COMMISSION The Committee provided the following reporto to the' Commission.. .c Copies of these reports are attached: Implementation of the Safety Goal' Policy (Report'to Chairman [ L Carr, dat.ed September 11, 1990).- ' i Yankee Rowe-Reactor Pressure Vessel -Intecrity.(Report to Chairmars Carr, dated September 12, 1990). Reevaluation of the-SALP Proaram (Report < to : Chairman Carr, dated September 12, 1990). MEMORANDA TO THE EDO The following memoranda were provided to the EDO: .i Pronosed Priority Rankinas of Generic' Issues: Sixth Groun e (Memorandum.from C. Michelson, ACRS, for J. M.. Taylor,'EDO, dated September 11, 1990). Pronosed Resolution of Generic' Issues 23. " Reactor - Coolant-Pomm Seal Failures".(Memorandum from R. F. Fraley, ACRS, for-J. M. Taylor, EDO, dated-September.. 11,-1990).- LIST OF FOLIDW-UP MATTERS In its report to the commission on;the Implementation of.the 3 Safety Goal Policy, the Committee. noted, that 'it:looks forward to future interactions as the policy implementation develops.- (Mr. Houston has the follow-up action onLthiszmatter.) In.its report to the Commission on'the-Reevaluation of the SALP Program,- the Committee-noted that-it plans to meet with the staff in order to' evaluate the staff's proposed regulatory. reforms based on the Regulatory Impact: Survey, including. any reforms to'the SALP Program that may gotbeyond?SECY-90-189,; " Reevaluation .of. the Systematic-Assessment of; Li'censee Performance Program."~ ] 1 The Committee agreed with a proposal by Mr.; Ward, Chairman of .l the Advanced Reactor - Designs Subcommittee, - that represen-tatives of the NRC staff and DOE be? invited to the October 4 " 6, 1990'ACRS meeting:to' provide a briefing on the-short!and' j long-range plans of the NRCLand DOE in~allocatingcresources for ' review of the advanced reactor designs (e.g., CANDU-3, PIUS, etc.). (Dr. El-Zef tawy. has the' follow-up action on this : matter.) UL r
t tice .x g .li. s s .o J. 3'65TH ACRS-MEETING.- ACTIONS, AGREEMENTS, ASSIGNMENTS-AND REQUESTS 2 ' Stating 1 that l even -though, the probabilityiof the ; potential- . + a stress: corrosion. cracking 11n BWRm reactor > pressure vessel-s internals may be low the safety; consequences of such incidents may be very high,. Mr.- Minnick suggested that 1 thel -. ACRS f 1 determine ' the status of this matter as soon.as' possible.; The 'j Materials and Metallurgy' Subcommittee may, hold,a meeting lto review this matter. (Mr.cIgne has'thel follow-upTactionLon this-matter.) The Committee requested that the NRC. staff'beiinvited!to the. 1 October 4-6, 1990 ACRS meeting to provide-aLbriefing?on'the-status-of-' staff actions to accommodate the-commentssreceived-i from-various utilities..during the. staff's_regulatorylimpact: survey. -(Mr. Quittschreiber has the follow -up a'etion on this I matter. ): 1 The Committee decided that the' AC/DC Power'Sy' stems Reliability-y Subcommittee = invite Mr. ' C.. Morris,( ' NRR,: ; to, presenty ' his = R technical ~ concerns related to NRC staff ' actions: on-reactor - trip' breaker testing when discussing thel proposed Supplement: i to the Generic Letter related to reactor trip breaker testing. l The; committee agreed.that the subcommittee,could: discuss the l proposed - Supplement ; after CRGR ~ review l has - been J completed. (Dr. El-Zeftawy has the-follow-up action onttnisfmatter.)'
- q The Committee agreed with -the recommendatilon byt Dr.s Lewis, i
a chairman of the safeguards.andiSecurityiSubcommittee, thati q there is no need to review the' proposed 9 Rule ? on' Material l y Control" Requirements for Uranium Enrichment Facilities.. (Mr.- j Alderman has'the follow-up action on,this1 matter.) q The Committee agreed with the. suggestion by Mr. _Michelson that< the AC/DC Power Systems Reliability Subcommittee follow-up on the staff : activities ' related: to :: the: resolution ^ ofiGeneric~ Issue
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. " Leakage ' ' Through Electrical Isolators:.inL q Instrumentation Circuits."- (Dr. El Zeftawy:has;the' follow-up' action on this mattert) _i FUTURE ACTIVITIES y The committee. agreed to.the followingLtentative: schedule.for the-1 366th, October 4-6, 1990-ACRS: meeting:- Reactor-Ooeratina Exoerience (Ocen) -f ' Briefing f by-e representatives of the NRC' staff regarding reactor operating! experience'- and events, including the. ' status ' of activities: regarding the impact of non-condensable gases on' operation.of' safety-related systems and components. l p pp,
e e.; L I t g i. x s - 365TH ACRS MEETING - ACTIONS, AGREEMENTS, ASSIGNMENTS AND REQUESTS.; 3 s Quality Assurance (Ocen).- Briefing by representatives of the NRC staff on the status of activities-regarding' performance : based qualityfassurance:atLnuclear facilities and the-related proposed' revision of the NRC Standard Review-Plan.- +. International-Activities (Onen/ closed) - Briefing regarding-recent visit and; meetings of.the US-USSR Joint Coordinating-Committee on Civilian Nuclear Reactor Safety and visit of,U.S. representatives to the Loviisa Nuclear Power Plant in Finland. License Renewal Standard Review Plan'(Onen).. Review. 'and comment on proposed-revision to;the NRC Standard Review' Plan. and associated Regulatory Guide regarding guidance for license: renewal reviews of nuclear power plants.- Representatives'of. the NRC: staff and industry, as'appropriatelwill-participate ^. ? 'in the discussion. -Severe Accident' Risk Assessment 4for Five U.S. Nuclear'Pca r. Plants (NUREG-1150) (Onen) - The members will> hear and discuss -
- the report of the ACRS' joint subcommittee' meeting on Severe Accidents,. Extreme External. Phenomena, and Probabilistic Risk Assessment (fires and seismic events)' as they relate to NUREG-1150 ' evaluations.
The-members, will L discuss comments: and recommendations regarding the nature _and.use of-NUREG-1150 and. severe accident risk assessmentJin the : regulatory process.. Representatives 'of ' the :NRC-1 staff 'will. ' participateas-appropriate. 3 ~ i Reactor ~ Safety Research (Oneni ~ - The members will discuss.the ~ scope and content of the: annual' ACRS report to Congress on the NRCLSafety'Research Program. ACRS Subcommittee-Activitles (OnenL - The : membersi will: hear ~ l reports and discuss; activities of: cognizant ACRSJaubcommittee1 ' meetings regardingjsafety-relate 6 and' regulatory activities-~ l including.the status of the :NRCL ttaff review :of standardized nuclear plants such - as the CombustioniEngineering. CESSARf Systems 80+ nuclear power plar.c, and i use of.. bleed and feed, coolingLin nuclear power plants.. Representatives-ofithe NRC staff will participate as appropriate' i ( Westinchouse Standard Plant Desian (SP/901- (Onen) ? Review and-i report
- on the proposed _
preliminary. design - for 'this 1 -standardized nuclear' power plant. Representatives of-the.NRC' staff:.and the Westinghouse-Electric. Corporation-will-j participate as appropriate. j j + I t ._____._____l__._ ._i___----
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