ML20059D179
| ML20059D179 | |
| Person / Time | |
|---|---|
| Issue date: | 08/28/1990 |
| From: | Fraley R Advisory Committee on Reactor Safeguards |
| To: | Taylor J NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| References | |
| ACRS-GENERAL, NUDOCS 9009060131 | |
| Download: ML20059D179 (4) | |
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'8 NUCLEAR REGULATORY COMMISSION 7
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ADV180MY COMhWTTEE ON REACTOR SAFEGUARDS g
wAsHusetom, p. c. asses August 28, 1990 MEMORANDUM FOR:
James M. Taylor Executive Director for Operations
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FROM:
- raley, ecutive Director, ACRS l
SUBJECT:
364th ACRS MEETING FOLLOW-UP ITEMS Based on discussions regarding methods for improved implementation 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 the actions, requests, and commitments made during the 364th ACRS meeting, August 9-11, 1990.
Attachment:
As stated t
cc w/ attachment:
l E.
L. Jordan, AEOD R. M.
Bornero, NMSS T.
E. Murley, NRR E.
S.
Beckjord, RES S.
Chilk, SECY' A. Vietti-Cook, OCM/KC G.
Marcus, OCM/KR D.
Trimble, OCM/JC l.-
J.
Guttman, OCM/FR l
l l-l 0 033 ATED ORIGIIIAL 9009060131 900828 RS led Dy j
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4 ACTIONS, AGREEMENTS, ASSIGNMENTS, AND REQUESTS 364TH ACRS MEETING AUGUST 9-11,.1990 REPORTS TO THE COMMISSION
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The Committee provided the following reports to the Commission.
Copies of these reports are attached:
Level of Detail Recuired for Desian Certification Under Part 52 (Report to Chairman Carr, dated August 14, 1990) e ProDosed Resolution of Generic Safety Issue B-56,
" Diesel Generator Reliability". (Report to Chairman Carr, dated August 14., 1990) e NRC Research Procram on Orcanizational Factors (Report to Chairman Carr, dated August 16, 1990)
LIST OF FOLLOW-UP MATTERS e
In its repart to ' the commission related to-level of. detail l
required for design certification under 10 CFR Part 52, the Committee suggested that some form of the two-tier approach I
proposed by NUMARC is essential and that the NRC staff and L
industry develop criteria to define'the division between the two tiers.
The Committee expressed its willingness to review such criteria, as progress is made in this effort, and report to the Commission if the Commission wishes that this be done.
(Dr. El-Zeftawy has the follow-up action on this matter.)
e In its report to the Commission on the NRC organizational.
I Factors research program, the Committee-stated that it would follow the progress of this research program with1 interest.
(Mr. Alderman has the follow-up action on this matter.)
In view of'the fact-that extensive changes ~have been.made to-e the EPRI-ALWR Requirements Document, the Committee decided not' to comment on this matter until after completing its review of the revised version of this document that is expected.to be made available by the end of August 1990.
(Dr. El-Zeftawy
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l has the follow-up. action on this matter.)
1 During the discussion of the IIT report related to the loss of vital AC power / loss of decay heat removal event at Vogtle Unit 1,
Mr. Jordan, AEOD, committed to the following:
(Mr.
l Boehnert has the follow-up action on this matter):
Provide the ACRS with a copy of the proposed staff actions, that have been submitted to the Commission by the EDO, for dealing with the ITT recommendations.,
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i 364TH ACRS MEETING --ACTIONS AGREEMENTS, ASSIGFMENTS AND REQUESTS 2
Provide a briefing to the - Committee, at an appropriate time in the future on the status of the' staff actions on this matter.
During the discussion of the Solenoid Valve case Study, Mr.
Novak, AEOD, committed to provide - another briefing to the Committee on this matter after the industry comments have been received and resolved.
(Mr. Alderman has the follow-up action -
on this matter.)-
Dr. Kerr requested, and the Committee endorsed, that the staff provide information on the following.
(Mr. Boehnert has the follow-up action on this matter):
Temporarf instructions on inspection activities associated. with plant-specific emergency operating.
procedures.
Details of the " Engineering' Managers' Forum" initiated l
during 1988 by licensees :in NRC Region V that is l
mentioned _in the August 6, 1990 letter from Mr. Thomas T.
- Martin, Regional Administrator, Region I,
tol Mr.
Feigenbaum, Seabrook nuclear power plant.
EUTURE ACTIVITIES The Committee agreed to the following tentative schedule for'the i
l 365th, September 6-8, 1990, ACRS meeting:
Reactor Operatina Exnerience (Open) - Briefing and discussion on information and experience gained from nuclear power plant operations, including Westinghouse owners Group study justifying reduction in turbine-stop valve testing frequency.
Members of the NRC staff-will participate, as appropriate.
NRC Ouantitative Safety Goals (Open) - Discussion regarding-the status of-NRC plans for implementation of Quantitative Safety Goals for nuclear power plants.
Reactor Coolant Pumo Seal Failures (Generic Issue 23) (Open)
Review and ce r/ent' on - proposed resolution of this; generic issue.
Members of the NRC staf f and the nuclear industry will participate, as appropriate.
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364TH ACRS MEETING - ACTIONS AGREEMENTS, ASSIGNMENTS AND REQUESTS 3
l e
Nine Mile Point Nuclear Plant, Unit 1 (Ocen)
Briefing and discussion of the status of Nine Mile Point, Unit i restart by representatives of the NRC staff and.the licensee, as appropriate.
I e
Performance-Based Ouality Assurance (Ocen)
Information briefing and discussion regarding use of performance-based quality assurance requirements and the associated revision.of the NRC Standard Review Plan.
(
e Foreion Activities (Open/ Closed)' - Report and discussion of NRC-USSR meeting on aspects of nuclear power plant safety related to radiation embrittlement and annealing, severe i
accidents, erosion / corrosion attack'of piping and components, and fire protection for nuclear facilities.
l e
Generic Safety Issues (Ocen)
Discussion and comment regarding proposed priority rankings for' a group: of new generic safety issues.
Members of the NRC staff will' participate, as appropriate.
~
e Yankee-Rowe Nuclear Power Plant (Ocen)_ - Discussion and report regarding the status of the Yankee Rowe ' _ reactor pressure vessel radiation embrittlement.
Representatives of the NRC-staff and the licensee will participate, as appropriate..
l Systematic Assessq3nt of Licensee Performance (Ocen) - Discuss e
l_
proposed ACRS comments on the NRC SALP. program.
e Reactor Risk Assessment Document (NUREG-1150) ' (Ocen) - Discuss proposed ACRS comments on the NRC report, NUREG-1150, Severe Accident Risks:
An Assessment for Five U.S.
Nuclear Power Plants.
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