ML20042D117
| ML20042D117 | |
| Person / Time | |
|---|---|
| Issue date: | 04/27/1989 |
| From: | Fraley R Advisory Committee on Reactor Safeguards |
| To: | Stello V NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| References | |
| ACRS-GENERAL, NUDOCS 8905100172 | |
| Download: ML20042D117 (5) | |
Text
{{#Wiki_filter:PbK /'+.,%, C'; UNITED 8TATES ~ / NUCLEAR REGULATORY COMMISSION n {
- )
AnnsoRY COMMITTEE ON REACTOR SAFEQUARD8 .g w m uwetow,o.c. sones April 27,1989 MEMORANDUM FOR: Victor Stello, Jr. Executive Director for Operations ATTN: J. Blaha FROM: Ra non . Fraley, E ive Director, ACRS
SUBJECT:
348TH 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, Agree-ments, Assignments, and Requests made during each ACRS meeting will be sent to your office following each meeting. Attached per this agreement is a list of the requests made at the 348th ACRS meeting, April 6-8, 1989. Those items in the-list " Actions Agreements, Assignments, and Requests" that do not deal with requests made of the NRC Staff or that are not pertinent to NRC Staff activities have not been included in this follow-up list.
Attachment:
As stated cc: E. L. Jordan, AEOD H. L. Thompson, EDO S. J. Chilk, SECY R. M. Bernero, NMSS T. E. Murley, NRR E. S. Beckjord, RES A. Vietti-Cook, OCM/L2 C. Ader, OCM/TR T. Elsasser, OCM/KC G. Marcus, OCM/KR K.-Connaughton,OCM/JC DESIC nTED ORIGINAL ~ Gertified By O $90$l00l'1% g f
- t
~ ACTIONS, AGREEMENTS, ASSIGNMENTS, AND REQUESTS 34BTH-ACRS MEETING - APRIL 6-8, 1989 s REPORTS AND LETTERS
- 1.. Proposed Final Rulemaking Related to Maintenance of Nuclear Power Plants (Report-to Chairman Zech dated April 11,1989)
- 2. -Integrated Approach on Regulatory Matters (Report to Chairman Zech dated April 17, 1939) 3.
Letter From Janes R. Sutton Dated March 23, 1989 Regarding Three Mile ~ Island Warning Siren (Letter to V. Stello dated April 13,1989) 4. Proposed Amendment to 10 CFR 50.61, " Fracture Toughness Requirements for Trotection Against Pressurized Thernal Shock Events" (Letter to V. Stello dated April 11,1989) 5. Proposed Resolution of Generic Issue 82, "Beyond Design Basis Accidents in Spent Fuel Pools" (Letter to V. Stello dated April 11,1989) 6. Proposed Resolution of Generic Issue 115. " Enhancement of Reliability of Westinghouse Solid State Protection Systems" (Letter to V. 5tello dated April 11, 1989) 7. Proposed Resolution of Generic Issue 101, "BWR Water Level Redundancy" (Letter to V. Stello dated April 11,1989) 8. Proposed Final Resolution of Generic -Issue 103, " Design for Probable Maximum Precipitation" (Letter to V. Stello dated April 11,1989) 9. Final Draft Generic Letter - Safety-Related Motor Operated Valve Testing and Surveillance The Committee discussed a proposed ACRS report on the NRC staff's proposed program for testing and surveillance safety-related motor-operated valves in nuclear power plants. The Connittee did not agree on a final report and will continue its discussions during the May 3-6, 1989 ACRS meeting. OTHER ACTIONS, AGREEMENTS, ASSIGNMENTS, AND REQUESTS
- 10. A meeting with the Commissioners has been scheduled between 2:00 p.m.
and 3:30 p.m. on May 3, 1989.
'I.
- t 348TH - ACTIONS & AGREEMENTS,
- 11. The Comittee discussed possible ACRS action on the proposed EPA Standard (40 CFR Part 61) regarding national emission standards for hazardous air pollutants. The Comittee decided not to coment on this matter at this time. Mr. Carroll, Chaiman of the Subcomittee on Occupational and Environmental Protection Systems, will follow the NRC and EPA actions and keep the ACRS infonned, as necessary.
(Mr. Igne has thefollow-upactiononthisitem.)
- 12. The AEOD was not able to complete its presentation on the Performance Indicator program during the April 6-8, 1989 meeting. The Comittee asked to hear the remainder of this presentation at a future ACRS meeting.
(Mr. Fraley has scheduled this topic for the May 3-6. 1989 ACRS meeting. Mr. Boehnert has the follow-up action on this item.)
- 13. The Comittee discussed the issues associated with NUREG/CR-5320,
" Impact of Radiation Embrittlement on Integrity of Pressure Vessel Supports for PWR Plants," dated January 1989, and decided to take no action at this time. -Dr. Shewmon, Chairman of the Subcomittee on Materials and Metallurgy, and Dr. Siess, Chairman of the Subcomittee on Structural Engineering, will continue to follow the NRC staff actions and refer the matter to the ACRS, as appropriate. (Mr. Igne has the follow-upactiononthisitem.)
- 14. The Comittee discussed the proposed NRC/ industry-program to study thermal-hydraulic phenomena associated with the B&W once-through steam generator (OTSG) and decided to take no action at this time. Mr. Ward, Chairman of the Thermal-Hydraulic Phenomena Subcomittee, will continue to follow this work and refer the matter to the ACRS, as appropriate.
Dr. Catton recommended that the NRC staff carefully consider the OTSG modeling deficiencies in the TRAC and RELAP codes and evaluate existing nonnuclear thermal-hydraulic research data. He also recomended that this work should be performed on a schedule that would allow input in the planning stage of the NRC/ industry program. Dr. Sheron, RES, agreed to follow up on Dr. Catton's recomendations. (Mr. Boehnert has follow-up action on this item.)
- 15. Mr. Wylie stated that he was concerned about the low priority (Priority
- 3) assigned by the staff to the implementation of the resolution of USI A-46, " Seismic Qualification of Equipment in Operating Plants." He will discuss this matter during a future meeting of the Reliability Assurance Subcomittee and will refer it to the ACRS, as appropriate.
(Mr. Duraiswamy has the follow-up action on this item.) v y A ^ '^
O.- (; 348TH - ACTIONS & AGREEMENTS ! FUTURE ACTIVITIES The Comittee agreed to a tentative schedule for the May 3-6, 1989 ACRS meeting as shown in Appendix A. I l (' a >r ^--'
. _. _ = h 1. APPENDIX A FUTURE ACTIVITIES Schedule for May 3-6, 1989 ACRS Meeting i Preparation for Meeting with NRC Comissioners - Discuss recent ACRS reports on the following topics: implementation of the NRC Safety Goal Policy Proposed NRC Maintenance Rule NUREG-1150, " Severe Accident Risk: An Assessment for Five U.S. Nuclear Plants" Containment Design Requirements Meeting with the NRC Comissioners - Discuss the reports and topics noted above. NUREG-1150, Reactor Risk Reference Document - Review and comment on the proposed uses and content of NUREG-1150, " Severe Accident Risk: An Assessment for Five U.S. Nuclear Power Plants" (Second Draft). Limerick Nuclear Power Station Unit 2 - Review and report on the application of the Philadelphia Electric Company for a license to operate this plant. Human Factors - Review and comment regarding the proposed NRC research plan on human factors'and human factors related NRC initiatives. Radiological Exposure-Criteria - Review and report on the proposed NRC. generic letter on evaluation of radiation. exposure / doses from " hot parti-cles " Evaluation of Operating Experience - Briefing and discussion of AE0D reports on several aspects of nuclear power plant operations, including loss of decay heat removal capability, inadequate NPSH in high pressure safety systems, and deficiencies in control room ventilation systems in nuclear power plants. Safety-Related Valve Testing and Surveillance - Discuss draft ACRS report to the NRC regarding proposed generic letter on testing and surveillance of safety-related motor operated valves .in nuclear power plants. Emergency Planning - Briefing and discussion regarding the status of emergen-cy planning and preparedness for nuclear power plants. f Performance Indicator Program - Briefing by representatives of the NRC staff regarding development and use of the perfonnance indicators at nuclear power
- plants, l
e - =..}}