ML20058L500
| ML20058L500 | |
| Person / Time | |
|---|---|
| Issue date: | 07/06/1990 |
| From: | Fraley R Advisory Committee on Reactor Safeguards |
| To: | Taylor J NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| References | |
| ACRS-GENERAL, NUDOCS 9008070258 | |
| Download: ML20058L500 (7) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION n
d ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, D. C. 20666 '
July 6, 1990
. MEMORANDUM FOR:
James M. Taylor Executive Director for Operations ATT Blaha FROM:
R. F.
Fraley, E ecutive Director, ACRS
SUBJECT:
362ND 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, and Requests made t
during each full Committee meeting will be sent to your office following each meeting.
Attached per this agreement is a list of the requests made during the 362nd ACRS Meeting, June 7-9, 1990.
Attachment:
As stated cc w/ attachment:
E. L. Jordan, AEOD 1
R. M. Bernero, 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 J.-Guttmann, OCM/FR AG l
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GENERhif,$69007p4 PI DESIONATE ORIGIRAL
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4 ACTIONS, AGREEMENTS, ASSIGNMENTS, AND REQUESTS AND
SUMMARY
OF FOL*.4W-UP MATTERS 362ND ACRS MEETING JUNE 7-9, 1990 Reports to the Commission The Committee provided the following reports to the Commission.
Copies of these reports are attachedt e
Proposed Rule to Imolement an Emeraency Resoonse Data System (Report to Chairman Carr, dated June 12, 1990).
e Modified Enforcement Policy for Hot Particle Exposures Incorooratina the Recommendations of the NCRP Reoort No. 106 (Report to Chairman Carr, dated June 12, 1990).
o Generic Issue-84 Combustion Enaineerina Plants Without Power Qp_ grated Relief Valves (Report to Chairman Carr, dated June 12, 1990).
e Draft Study on Source Term Uodate and Decouclina Sitina from Desian (Report to Chairman Carr, dated June 13, 1990).
ligmorandaum to the EDO e
Schedulina of ACRS Reviews (Memorandum from R.
F.
Summary of Matters Considered by the Committee o
Proposed Resolution of Generic Issue-84. "CE Plants Without PORVs" The Committee heard presentations by and held discussions with representatives from the Office of Nuclear Regulatory Research (RES) and Combustion Engineering (CE) with regard to the NRC staff's proposed resolution of Generic Issue-84.
The Committee provided a report to the Commission on this
- matter, e
Sitina of Nuclear Power Plants I
Representatives of RES briefed the Committee on the status of j
a study being conducted by them to examine an alternate approach for decoupling siting from reactor design and the proposed schedule for completing this task that are delineated
]
in a draft Commission paper,
" Staff Study on Source Term Update and Decoupling Siting from Design."
The Committee provided a report to the Commission on this i
matter.
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362ND ACRS MEETING - ACTIONS, AGREEMENTS, ASSIGNMENTS AND REQUESTS 2
e Interin Standard for Hot Particles The Committee heard presentations by and held discuasions with representatives from the Office of Nuclear Reactor Regulation (NRR), RES, and Region V regarding the modified enforcement policy for hot particle exposure that is based on the recommendations of the NCRP report No.106, Limit for Exposure to Hot Particles to the Skin, dated December 31, 1989.
The Committee discussed also the " technical issues" raised in Mr.
Beckjord's letter to Dr. Murley, dated April 20, 1990.
The Committee provided a report to the Commission on this matter.
e Emeraency Response Data System The Committee met with representatives of the Office for Analysis and Evaluation of Operational Data (AEOD), RES, and the Nuclear tianagement and Resources Council (NUMARC) and discussed the proposed rule to implement an Emergency Response Data System (ERDS) program.
The Committee provided a report to the Commission on this matter.
e Accident Secuence Precursor Procram Representatives of AEOD and NRR provided an information briefing to the Committee regarding the status and application of the Accident Sequence Precursor (ASP) program.
The primary objective of this program is to review licensee event reports and to identify and characterize precursors to potential severe core damage accidents.
Dr. Murley requested ACRS comments on the ASP program as well as on the application of the results of this program in the regulatory process, e
Risk-Based Technical Snecifications Representatives of RES and NRR provided an information briefing to the Committee. on the program related to the development of risk-based technical specifications.
The primary goal of this program is to improve operational safety.
An Industry /NRC working group was formed in 1988 to perform necessary work on this matter.
The committee plans to discuss this program with the staff after it has been developed further
362ND ACRS MEETING - ACTIONS, AGREEMENTS, ASSIGNMENTS AND REQUESTS 3
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Additional Evolutionary Licht Water Reactor (ELWR) Certifi-cation Issues i
The Committee discussed " additional" issues other than those identified by the staff in SECY-90-016 that may be appropriate for consideration in the ELWR certification process.
The following issues were considered by the Committee Extension of PRAs for those Modes of plant operation other than Mode 1 operation.
Verification and validation of computer sof tware used in control ar.d protection systems.
Adoption of the general principle of N+2 trains for active, safety-related functions.
Quality assurance requirements for design, construction, and operation of ELWRs.
Security and protection requirements against sabotage.
Systems Interactions.
After deliberations, the Committee decided not to make any recommendations regarding the above issues pending detailed review of these issues by cognizant ACRS Subcommittees.
Summarv/ List of Follow-Un Matters e
The Committee decided not to recommend " additional" issues that may be appropriate for consideration in the ELWR certification process, pending detailed review of these issues.
by cognizant ACRS Subcommittees. The Committee assigned these issues to various Subcommittees as shown below.
Plant Onerations (Mr. Carroll) - Extension of PRAs for tnose Modes of operation other than Mode 1 operation.
Computers in Nuclear Power Plant Operations (Dr. Lewis)
- Verification and validation of computer software used in control and protection systems.
Imoroved LWRs (Mr. Wylie)
Adoption of the general principle of N+2 trains for active, safety-related functions.
Safeauards and Security (Dr.
Lewis)
Security and protection requirements against sabotage.
362ND ACRS MEETING - ACTIONS, AGREEMENTS, ASSIGNMENTS AND REQUESTS 4
The Committee stated that after review of these issues, designated Subcommittees could prepare individual reports on these items and submit them for consideration by the full Committee.
(Mr. Boehnert, Mr. Alderman, and Dr. El-Zeftawy have the follow-up action on this matter).
The Committee suggested that the Improved LWRs Subcommittee e
hold a meeting with the staff and discuss "what constitutes an essentially complete design for standard plants" and recommend a course of action to the full Committee for consideration.
(NOTE:
A meeting of the Improved LWRs Subcommittee has been scheduled for July 10, 1990 to discuss this matter).
(Dr. El-Zeftawy has the follow-up action on this matter),
The Committee agreed not to provide comments to the Commission o
on SECY-90-080, Draft Regulatory Impact Survey Report, until it has been reviewed by the Regulatory Policies and Practices Subcommittee and a course of action has been recommended for the full Committee consideration.
(Mr. Quittschreiber has the follow-up action on this matter).
The Committee agreed with the recommendation by Mr. Carroll, e
Chairman of the Maintenance Practices and Procedures r
Subcommittee, that there is no need to review at this time the proposed criteria (delineated in SECY-90-137) to be used by the staff in determining when the industry progress in the area of maintenance would be sufficient to obviate a need for rulemaking; he plans to hold a Subcommittee meeting, probably during the fall of 1990, to discuss this matter after the staff has progressed further.
(Mr. Alderman has the follow-up action on this matter),
e The Committee agreed with the recommendation by Dr. Lewis, Chairman of the Regulatory Policies and Practices Subcommittee, that there is no need to review the NRC proposal, delineated in SECY-90-022, to amend regulations to make unlicensed individuals subject to enforcement actions.
(Mr. Quittschreiber has the follow-up action on this matter, if any).
The Committee agreed that the staff brief the ACRS on the e
following operating events during the July 12-14, 1990 meeting:
Status of the reactor vessel head cracking at Quad Cities and Fitzpatrick plants.
Cracking of pressurizer vessel cladding at the Haddrm Neck plant.
U 362ND ACRS MEETING - ACTIONS, AGREEMENTS, ASSIGNMENTS AND REQUESTS 5
Malfunction of molded case GE circuit breakers.
Failure of operators to pass requalification tests at the J
Brunswick plant.
l NRC review of the Westinghouse Owners' Group study justifying suppert of reduction of turbine stop valve testing frequency.
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(Mr.
Boehnert has the responsibility to make necessary arrangements).
Mr. Carroll requested that the staff provide another briefing e
to the Committee after the Risk-Based Technical Specifications Program has been developed further.
The RES staff agreed to do so.
(Mr.
Boehnert has the follow-up action on this matter).
The Committee requested that the staff use " legible" slides e
during the ACRS meetings and also include the names and telephone numbers of the presenters.
gMr. Fraley has the follow-up action on this matter).
During the discussion of the Accident Sequence Precursor program, Mr. Wylie asked whether the staff has looked at the layout to ensure that alternate AC power supply used during station blackout conditions is located such that transformer i
explosion or fire would not render it inoperable. Mr. Congel, i
NRR, stated that he would provide the information later.
(Mr.
Alderman has the follow-up action on this matter).
e Dr. Murley, NRR, requested ACRS comments on the Accident Sequence Precursor Program as well'as on the applicatio", of the results of this program in the regulatory process.
(Mr.
i Alderman has the follow-up action on this matter).
Schedule for the 363rd Meetina The Committee agreed to the following tentative schedule
.'or the 363rd ACRS meeting, July 12-14, 1990:
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e Nuclear Power Plant Operatina Experience (Open/ Closed)
Briefing and discussion of nuclear power plant operating experience, including:
Status of the reactor vessel head cracking at Quad Cities and Fitzpatrick plants.
Cracking of pressurizer vessel cladding at the Haddam j
Neck plant.
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362ND ACRS MEETING - ACTIONS, AGREEMENTS, ASSIGNMENTS AND REQUESTS 6
Malfunction of molded case GE circuit breakers.
Failure of operators to pass requalification tests at tla Brunswick plant.
NRC review of th-3 Westinghouse Owners' Group study justifying support of reduction of turbine stop valve testing frequency.
Briefing by e
Emeraency Ooeratina Procedures (Ocen) representatives of the NRC staff and the nuclear industry as appropriate regarding NRC efforts related to the development
<# emergency operating procedures and performance of PRAs for
'{
th shutdown modes of operation.
e systematic Assessment of Licensee Performance Evaluation (Ocen). - Briefing by and discussion with members of the NRC staff regarding their evaluation of the SALP program, o
EPRI Advanced LWR Recuirements Document (Ocen)_ - Review and report on the NRC staff's draft SER on Chapters 1-5 of the EPRI ALWR Requirements Document.
Representatives of the NRC staff and EPRI will participate, as appropriate.
e Recuirements for Essentially Complete Desian (Ocen) - Briefing by and discussion with representatives of the NRC staff and' the nuclear-industry regarding-status of the development of requirements for an essentially complete design.
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