ML20035E045
| ML20035E045 | |
| Person / Time | |
|---|---|
| Issue date: | 12/15/1992 |
| From: | Fraley R Advisory Committee on Reactor Safeguards |
| To: | Taylor J NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| References | |
| ACRS-GENERAL, NUDOCS 9304140210 | |
| Download: ML20035E045 (6) | |
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UNITED STATES 8
NUCLEAR REGULATORY COMMISSION n-E ADVISORY COMMITTEE ON REACTOR SAFEGUARDS O,
g WASHINGTON, D. C. 20555 8
4 December 15, 1992 MEMORANDUM FOR:
James M.
Taylor Executive Director for Operations ATTN:
J.
Blaha L
FROM:
R.
ra ey, E'
utive Director, ACRS
SUBJECT:
391ST ACRS MEETING FOLLOW-UP ITEMS This memorandum is provided for follow-up action consistent with the Action, Agreements, Requests, and Commitments made during'the 391st ACRS Meeting, November 4-7, 1992.
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 J. Johnson, OCM/IS J. Scarborough, OCM/KR K. Connaughton, OCM/JC J. Guttmann, OCM/FR E. McKenna, OCM/GdeP 13014g DE^ACHLTED DRIGIRLL l
93 41 0 930409
' ctiflod 37 g
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QENERAL PDR
SUMMARY
OF ACTIONS, AGREEMENTS, REQUESTS, AND COMMITMENTS 391ST ACRS MEETING NOVEMBER 5-7, 1992 During its 391st meeting, November 5-7,
- 1992, the Advisory Committee on Reactor Safeguards discussed several matters and completed the Reports and Memoranda as noted.
REPORTS e
Risk-Based Reculation (Report to Chairman Selin, dated November 16, 1992)
Revised Guidelines for Prioritization of Generic Safety Issues e
(Report to Mr.
James M.
- Taylor, Executive Directer for Operations, dated November 12, 1992)
Revised Reculatory Analysis Guidelines (Report to Mr. James M.
e Taylor, Executive Director for Operations, dated November 12, 1992) e Environmental Oualification for Diaital Instrumentation and Control Systems (Report to Chairman Selin, dated November 12, 1992)
MEMORANDA e
Staff Response to the ACRS Report on the Severe Accident Research Procram Plan (Memorandum for James M.
- Taylor, Executive Director for Operations, from Raymond F.
- Fraley, Executive Director of the ACRS, dated November 13, 1992)
Proposed NRC Generic Letter on Auamented Inservice Inspection e
Recuirements for Mark I and Mark II Steel Containments, Refuelina
- Cavities, and Associated Drainace Systems (Memorandum for Jnmes E. Richardson, Director of the Division of Engineering, Office of Nuclear Reactor Regulation, from j
Raymond F.
Fraley, Executive Director of the ACRS, dated November 12, 1992)
Proposed Amendment to 3 0 CFR S50.55A that would Incorporate by Reference Subsection IWE and Subsection IWL,Section XI.
Division 1,
of the ASME Boiler and Pressure Vessel Code (Memorandum for Eric S.
Beckjord, Director of the Office of Nuclear Regulatory Research, from Faymond F. Fraley, Executive Director of the ACRS, dated November 13, 1992)
2 e
Appointment of ACRS Members (Memorandum for Chairman Selin from Raymond F.
Fraley, dated November 12, 1992)
ANTICIPATED ACRS ACTIVITIES i
The Committee agreed to discuss the following during its 392nd meeting, December 9-12, 1992:
A.
Systematic Assessment of Licensee Performance (SALP) - Review and comment on changes proposed to the SALP program by the NRC staff in SECY-92-290 as well as the issues and concerns associated with the overall SALP process.
Representatives of the nuclear industry will participace, as appropriate.
(Note:
This item has been deferred to a future meeting at the request of the staff.)
B.
Station Blackout Rule - Review and comment on the proposed final amendment to the station blackout rule (10 CFR 50.63) and the associated Regulatory Guide 1.9, Revision 3, regarding diesel-generator reliability.
Representatives of the nuclear industry will participate, as appropriate.
C.
Proteccion Acainst Lichtning and Electrical Transients for Nuclear Power Plants - Briefing by and discussion with representatives of the NRC staff regarding a petition to the NRC to amend its regulations to include lightning in the list of phenomena that a nuclear plant must safely accommodate.
Representatives of the nuclear industry will participate, as appropriate.
D.
River Bend Nuclear Plant - Briefing by and discussion with representatives of the licensee regarding the reliability monitoring program implemented at the River Bend Nuclear Plant.
Representatives of the NRC staff will participate, as appropriate.
E.
Technical Specifications Improvement Procram - Briefing by and discussion with representatives of the NRC staff on the status of the Technical Specifications Improvement Program.
F.
Generic Issue 120, "Online Testability of Protection Systems"
- Review and comment on the NRC staff's proposed resolution of this generic issue.
Representatives of the NRC staff and the nuclear industry will participate, as appropriate G.
Meetina with NRC Commissioners - Discuss topics of mutual
- interest, including use of digital control and protection systems, status of ACRS review of Advanced Reactor Design, implementation of the plant license renewal rule, and risk-based regulation.
H.
Meetina with the Director of the NRC Office of Nuclear Reculatory Research (RES) - Briefing by and discussion with the RES Director regarding the NRC safety research program and budget.
I.
Future Acenda - Discuss report of the ACRS Planning and Procedures Subconnittee regarding consideration of items proposed for review by the full Committee.
3 J.
Organizational Factors Research Report by cognizant Subcommittee Chairman regarding the November 12, 1992 NRC Workshop on organizational factors research.
K.
Miscellaneous - Discuss miscellerocus matters related to the conduct of Committee activities and complete discussion of topics that were not completed during previous meetings as time and availability of information permit.
Reconciliation of ACRS Comments and Recommendations (Open)
The Executive Director for Operations' (EDO's) responses to previous ACRS reports were discussed as follows:
EDO letter, dated October 23, 1992, responding to the ACRS report dated September 16,
- 1992, concerning the staff's proposed position on digital instrumentation and control system reliability.
The Committee will continue its deliberations on this matter.
A meeting of the Computer in Nuclear Power Plant Operations Subcommittee is scheduled to be held in the near future.
No specific member's comments on the EDO's response were made at this meeting.
e EDO letter, dated October 15, 1992, responding to the ACRS report dated September 15, 1992, concerning staff proposed resolution of issues found during its evaluation of shutdown and low-power operations.
The EDO letter was responsive to the Committee's comments, e
EDO letter, dated October 22, 1992, responding to the ACRS report dated September 16,
- 1992, concerning the staff's proposed positions on several of the issues discussed in the draft Commission paper, " Design Certification and Licensing Policy Issues Pertaining to Passive and Evolutionary Advanced Light Water Reactor Designs." The Committee's response to the staff's comments are as follows:
A.
Defense Against Common-Mode Failures in Digital Instrumentation and Control (I&C) Systems The Committee will continue its deliberations on this matter. A meeting of the Computer in Nuclear Power Plant Operations Subcommittee is scheduled to be held in the near future.
No specific member's comments on the EDO's response were made at this meeting.
B.
Multiple Steam Generator Tube Ruptures (MSGTRs)
Dr. Catton will report back to the Committee on this i
response at the December meeting.
)
l
4 E.
,(PRA)
Beyond Design Certification The EDO letter was responsive to the Committee's comments.
F.
Role of the Operator in a Passive Plant Control Room The EDO letter was responsive to the Committee's comments.
H.
Regulatory Treatment of Nonsafety Systems The EDO letter was responsive to the Committee's comments.
EDO letter, dated October 29, 1992, responding to the ACRS report dated August 17, 1992, concerning the Committee's comments and recommendations on the staff's positions for passive light water reactors issues. The Committee's response to the staff's comments are as follows:
G.
Hydrogen Control The response was not considered adequate.
It was noted that the Severe Accident Subcommittee will be looking at this matter in more detail during future meetings, as mentioned in the November 13, 1992 Memorandum for J.
l Taylor from R.
Fraley mentioned above.
I.
High Pressure Core Melt Ejection The response was not considered adequate.
It was noted that the Severe Accident Subcommittee will be looki:ag at this matter in more detail during future meetings, as mentioned in the November 13, 1992 Memorandum for J.
Taylor from R.
Fraley mentioned above.
J.
Containment Performance The EDO letter was responsive to the Committee's comments.
K.
Dedicated Containment Vent Penetration The EDO letter was responsive to the Committee's comments.
III.E Control Room Habitability The EDO letter was responsive to the Committee's comments.
5 e
EDO letter, dated November 2,
1992, responding to the ACRS report dated October 16, 1992, concerning the development of design acceptance criteria (DAC) for the U.S. Advanced Boiling Water Reactor (ABWR) design in the areas of instrumentation and controls (I&C) and control room design.
The members did not comment on the EDO's letter during this meeting.
SUMMARY
/ LIST OF FOLLOW-UP AND OTHER MATTERS Mr. Michelson requested a written response as to whether the e
PWR steam generator and the BWR reactor vessel overfill resolution to USI A-47, include assurance that the closure response time of feedwater isolation valves would preclude overfill with continuous feedwater flow, which did occur at the LaSalle plant (BWR).
(Mr. Coe is the cognizant engineer on this matter.)
Mr. Davis requested a copy of the results of the Accident Sequence Precursor study for the recent LaSalle reactor vessel overfill event.
(Mr. Coe is the cognizant engineer on this matter.)
Mr. Bernero requested the Committee to expedite its decision e
as to whether it would review the rulemaking packages that would amend 10 CFR Part 72 to include specific NRC approval of two dif ferent types of dry storage spent fuel systems, the TN-24, a conventional steel can design, and the VSC-24, a concrete design.
(Mr. Igne is the cognizant engineer on this matter.)
The Committee would like to hear the staff's final position on e
" point estimates" with regard to use in the NRC on stat istical matters.
A position was discussed in a staff memo by Dr.
Abramson and was sent to Drs. Kress and Lewis.
Dr. Cunningham should be asked to discuss this position at a future meeting.
(Mr. Houston is the cognizant engineer on this matter.)
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