ML20044A087
| ML20044A087 | |
| Person / Time | |
|---|---|
| Issue date: | 05/29/1990 |
| From: | Fraley R Advisory Committee on Reactor Safeguards |
| To: | Taylor J NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| References | |
| ACRS-GENERAL, NUDOCS 9006280052 | |
| Download: ML20044A087 (8) | |
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- ' sacuavg'o, UNITED STATES e
NUCLEAR REGULATORY COMMISSION o
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<r ADVISORY OOMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, D, C. 20555
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May 29, 1990-
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MEMORANDUM FOR:
James M. Taylor Executive Director for Operations 1
ATTN:
J. Blaha FROM:
R.
ra ey, Exec tive Director, ACRS
SUBJECT:
361ST-ACRS MEETING
SUMMARY
/ 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-
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during each full Committee meeting will be sent to your_ office following each meeting.
Attached pnr this agreement is a list of the requests made at-the 361st ACRS Meeting, May 10-11, 1990.
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Attachment:
As-stated cc w/ attachment:
'E.
L.-Jordan, AEOD R. M.
Bernero,.NMSS T. E. Murley, NRR E.
S.
Beckjord, RES S. Chilk, SECY
.A. Vietti-Cook, OCM/KC C. Ader, OCM/TR G. Marcus, OCM/KR D. Trimble, OCM/JC J.,Guttmann, OCM/FR DESIG HTED ORIGINAL i
9006280032 900529
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GENERAL PDC Certified By
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ACTIONS, AGREEMENTS, ASSIGNMENTS, AND REQUESTS AND
SUMMARY
OF FOI. LOW-UP MATTERS 361ST ACRS MEETING MAY 10-11, 1990 J
REPORT TO THE COMMISSION e
Proposed _. Generic Letter Sucolement on Individual Plant Examination' for Severe Accident Vulnerabilities Due to External Events (Report to Chairman Carr, dated May 15, 1990).
SUMMARY
OF MATTERS Cold,10ERED BY THE COMMITTEE HEC Research Proaram on Planh Acina 1
e The Committee heard presentations by and held discussions with j
representatives of the Office of Nuclear Regulatory Research (RES) and their contractors regarding the status of activities associated with the Nuclear Plant Aging Research (NPAR) 1 program.
In addition, the Committee heard a presentation from NUMARC with respect to industry initiatives for handling j
aging-related issues, q
e Reactor ODeratina Events Representatives of the Office of Nuclear Reactor Regulation (NRR) briefed the Committee on the following operating events and certain regulatory actions:
480v circuit breaker problem at the Pilgrim nuclear plant.
-Recent problems with Essential Service Water Systems.
Reactor vessel head cracks at Quad Cities Unit 2 and Fitzpatrick nuclear plants.
Regulatory actions _in response to fuel failures caused by BWR channel box bowing - Bulletin 90-02, " Loss-of Thermal Margin caused by Channel Box Bow," March 20, 1990.
The committee requested that.the NRR staff keep the Committee informed of the results of the investigations associated with the reactor vessel head cracks, especially those related to the Fitzpatrick plant.
e Individual Plant Examination for External Events The Committee heard presentations by and held discussions with representatives of RES and NRR regarding their activities in implementing the Commission's Severe Accident Policy -for hazards due to external events.
The Committee discussed a.
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l 361ST ACRS MEETING - ACTIONS, AGREEMENTS, ASSIGNMENTS AND REQUESTS 2
proposed Supplement to Generic Letter 88-20, Individual Plant Examination for Severe Accident Vulnerabilities, and a draft NUREG ' document that is intended to provide guidance and recommendations to the industry regarding the scope and i
acceptable methodologies for performing the IPEEE.
Also, the Committee heard presentations from the Yankee Atomic Electric Company and its consultant regarding their approach for seismic margins assessment for use in the IPEEE program.
The Committee provided a report to the Commission on-this matter.
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BWR Core Power Stability Dr.
- Catton, Chairman of the Thermal Hydraulic Phenomena
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Subcommittee, provided a report of the April 27, 1990 combined meeting of the Thermal Hydraulic Phenomena and Core Performance Subcommittees at which the status of the staff's efforts in resolving the BWR core power stability issue were discussed.
The Subcommittee plans to discuss this matter further. prior to recommending it to the full Committee for consideration, e-Sitina of Nuclear Power Plants Representatives of RES briefed the Committee on the str.tus of a
study being conducted by. them, as directed by the Commission, to examine an alternate approach of decoupling siting from reactor design.
The RES staff stated that a Commission paper, including the results of the study and-proposing a plan of action and schedule will be submitted to the Commission on June 30, 1990.
A draft of'this Commission paper is expected to.be made available to the ACRS as soon as possible. The Committee plans to discuss the staff's proposed plan of action and. schedule during the June 7-9, 1990 meeting.
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Maintenance Performance Indicators l
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. Representatives of the Office for Analysis and Evaluation of Operational Data (AEOD) 'provided an information briefing to the Committee on the status of a demonstration project for
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i the development of maintenance performance indicators that was i.
' initiated in response to the Commission's direction. The AEOD L
staff stated that through the coordination of NUMARC and the Institute of Nuclear Power Operations-(INPO), six utilities volunteered' to participate in this project.
The staff presented the findings and accomplishments of this project and stated that it plans to develop a Commission paper, including its recommendations on this matter.
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-l 361ST ACRS' MEETING - ACTIONS, 1
AGREEMENTS, ASSIGNMENTS AND REQUESTS' 3
i e
Decommissionina of the Shoreham Nuclear Power Station The NRR staff provided an information briefing to the Committee on the current status of activities related to the 1
decommissioning of the Shoreham Nuclear Power Station.
Proposed-NRC Staff's Schedule for Review of the Evolutionary e
Licht Water Reactors (ELWRs) and Passive Advanced Licht Water Reactors (ALWRs)
The NRR staff briefed the Committee regarding the process, schedule, and resources for the review of ELWRs and passive ALWRs that are delineated in SECY-90-146.
Some-members of the Committee stated that the scheddle
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proposed initially in SECY-90-065 for ACRS review of ABWRs was tight. but reasonable.
They expressed concern - that the proposed schedule in SECY-90-146 is too~ compressed..
They expressed similar concern about the proposed schedule for the ACRS review of the EPRI ALWR Requirements Document.
Dr. - Miller, NRR, stated that if the Committee prefers. to review the staff's SERs on each module of the ABWR and provide
-interim reports to the EDO, the staff will try to accommodate such reviews..He proposed a similar approach for review of the'EPRI ALWR Requirements Document.
e Additional ELWR Certification Issues The Committee meabers discussed additional. issues, other than those proposed by the staff in L SECY-90-016, that may be appropriate for consideration in the certification' process of ELWRs. The Com'aittee plans to continue the discussion of this matter during the June 7-9, 1990 meeting, e -
ProDosed Resolution of Generic Issue 84. "CE Plants Without PORVs" Mr.
- Ward, Chairman of the Decay Heat Removal Systems Subcommittee, briefed the Committee on the staff's proposed resolution of Generic Issue 84.
There are six plants with CE l
reactors'(Palo Verde Units 1-3, San Onofre Units 2 and 3, and Waterford) operating without PORVs or any other primary system manual high capacity venting. capability, Generic Issue 84 was
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established to determine whether such provisions should be required for these plants.
Based on the results of its evaluation, the staff plans to resolve Generic. Issue 84 without _ recommending installation of
- PORVs, or other l
r 361ST ACRS MEETING - ACTIONS, AGREEMENTS, ASSIGNMENTS AND REQUESTS 4
equivalent features on the above mentioned plants.
The Committee plans to discuss this matter with the staff during the June 7-9, 1990 ACRS meeting.
I
SUMMARY
/ LIST OF FOLLOW-UP MATTERS e
Mr. Michelson suggested that the Maintenance Practices and Procedures Subcommittee look at 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, and recommend a course of action to the full Committee during the June 7-9, 1990 ACRS meeting.
Mr.
Carroll, Chairman of the Maintenance Practices and Procedures Subcommittee agreed to do so.
(Mr. Alderman has the follow-up action on this matter).
Mr'.
Michelson suggested that the - Regulatory Policies and Practices Subcommittee look at the NRC proposal, delineated in SECY-90-022, to amend regulations to make unlicensed individuals subject to enforcement actions, and recommend a course of action to the full Committee during the June 7-9, 1990 ACRS meeting.
Dr. Lewis, Chairman of the Regulatory 1
Policies'and Practices Subcommittee agreed to do so.
(Mr.
Quittschreiber has the follow-up action on this matter).
The Committee agreed to discuss the following elements of the e
Nuclear Plant Aging Research Program, that were deferred owing to lack of time, during future Subcommittee and/or full Committee meetings, as appropriate.
(Mr-Igne has the follow-up action on this matter):
Evaluation methodology for the risk effects of aging.
. Structural Engineering aging research.
The Committee agreed with the proposal by Dr. Catton, Thermal-e Hydraulic Phenomena Subcommittee Chairman, that the Thermal Hydraulic Phenomena Subcommittee-discuss further the BWR core power stability issue prior to referring -it to the full Committee for consideration.
(Mr.-Boehnert has the follow-up action on this matter).
The Committee agreed.to discuss the staff's proposed plan of
,o action-and schedule associated with decoupling nuclear plant siting. from source term during the June 7-9, 1990 ACRS meeting.
(Mr. Quittschreiber has the follw-up action on this matter).
y 361ST'ACkS MEETING - ACTIONS, AGREEMENTS, ASSIGNMENTS AND REQUESTS 5
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e The Committee agreed with the recommendation by Mr. Ward,
-Decay Heat Removal Systems Subcommittee Chairman, that there is no need to hold a Subcommittee meeting to discuss the staff's proposed resolution of Generic Issue 84, "CE plants without PORVs," and that the full Committee consider this-matter during the June 7-9, 1990 ACRS meeting.
(Mr. Boehnert 1
has the follow-up action on this matter).
The Committee members agreed to consider Vfeparing a report e-to the Commission on " additional" issues other than those identified by the staff in SECY-90-016 that may be appropriate for consideration in the certification process of ELWRs.
(Dr.
El-Zeftawy has the follow-up action on this matter).
The Committee requested that the NRC staff keep the Committee.
e informed of the results of the investigations associated with-the reactor vessel head cracks, especially those related to the Fitzpatrick plant.
(Mr. Igne has the follow-up cctic." on this mattor).
The Committee agreed that senior NRR management personnel be e
invited to discuss the following during the June 7-9, 1990 ACRS meeting.. (Mr. Boehnert has-the follow-up action on this matter):
NRC's opinion on the need to develop additional emergency operating procedures to address incidents that occur during non-power modes (Modes 3-6) of operation.
Potential use of PRA to analyze the risks associated with L
l non-power operation.
The status of industry efforts in this area.
(NOTE:
This item has been subsequently deferred to the L
July 12-14, 1990 ACRS meeting).
L e
The Committee. expressed an interest in reviewing the L
_ Commission paper, when available, that will address ALWR issues such as the level of design details, inspection, test, analysis,-acceptance criteria, and environmental review of design alternatives.
(Dr. El-Zef tawy has the follow-up action on this matter).
The Committee decided to perform separate reviews of staff's 4
e SERs associated with each module of the ABWR design as they became available, and provide interim comments to the EDO.
l After the staff has issued the final (consolidated) SER, the
' Committee is rvoected to issue a
final report to the
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E. (i_,ga 361ST ACRS MEETING - ACTIONS, AGREEMENTS, ASSIGNMENTS AND REQUESTS 6
Commission. The Committee agreed to follow a similar approach I
for reviewing the staff's SERs related to the EPRI ALWR Requirements Document.
l Dr. Miller, NRR, agreed to provide appropriate support to accommodate such reviews.
(Dr. El-Zeftawy has the follow-up action on this matter).
Stating that through a staff Requirements Memorandum dated e
December 15, 1989 related to SECY-89-311, the Commission i
requested that the ACRS provide a comparison of the Licensing Review Basis (LRB) document for GE ABWR with that for CE System 80+, Mr. Michelson asked when the staff _would be able to provide necessary documents to the Committee to perform l
such a comparison.
He suggested that the staff point out the differences between these two LRB documents so as to facilitate the Committee's review.
l Dr. Miller, NRR, stated that he will inform the Committee H
later as '~ to when the staff will be able to provide the required documents.. (Dr. El-Zeftawy has the follow-up action on this matter).
During-the discussion of-the activities associated with the e
L decommissioning of. the Shoreham Nuclear Power Station, Dr.
l Siess asked whether there is a list that identifies the plants that have been decommissioned as well--as the nature of the-decommissioning process.
Mr. Partlow, NRR, agreed to provide I
such information.
(Mr. Alderman has the_ follow-up action on p
this matter).
V 1:
. FUTURE ACTIVITIES' The Committee agreed to the following tentative schedule for the 362nd:ACRS meeting, June 7-9, 1990.
Discussion of e
Certification of Evolutionary LWRs (ODen) issues other than those identified in SECY-90-016 for consid-eration in evcelutionary light-water reactor certification.
e Interim Standerd for Hot Particles (ODen) - Briefing regarding l'-
the status of proposed revisions to the standard for exposure of the skin from radioactive particles.
.(ODen) l o=
Accident Seauence Precursor Procram Briefing l
regarding the Accident Sequence Precursor Program at the ORNL
-Nuclear Operations Analysis Center.
p e.
Status of Imolementation of the Safety Goal Policy (Ocen)
L Discussion of the status of implementation of the NRC's Safety Goal Policy.
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361ST'ACRS MEETING - ACTIONS,
. AGREEMENTS, ASSIGNMENTS AND REQUESTS 7
e Systematic' Assessment of Licensee Performance (Ocen)
Briefing and discussion regarding proposed revisions to the NRC Manual Chapter on Systematic Assessment of Licensee Performance.
1 e
NRC Research Procram (Ocen) - Discussion of proposed' nature of the-annual'ACRS report to the U.S.
Congress.
.e ACRS Subcommittee Activities (Ocen) - Hear and discuss reports 3
of ACRS subcommittees -regarding the status of assigned activities such as the low charpy upper. shelf energy matters relating to the integrity of reactor pressure vessels, results of the MOV tests performed in FRG, and the reliability of dampers.
A report of the ACRS Subcommittee on Planning and Procedures will also be discussed.-
e Sitina of Nuclear Power Plants (Ocen)
Briefing and diccussion regarding NRC staff activities to decouple nuclear plant. citing from source term.
e Nuclear Po.t?" Plant Technical Soecifications (Onen) - Briefing regarding the status of NRC staff activities regarding the -
development of risk-based technical specifications, o
Generic Issue 84: CE Plants Without'PORVs (Ocen) - Briefing and discussion.of proposed resolution of this generic issue.
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