ML20205K205
| ML20205K205 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse, Hope Creek, Rancho Seco, 05000000 |
| Issue date: | 07/21/1986 |
| From: | Ward D Advisory Committee on Reactor Safeguards |
| To: | Zech L NRC COMMISSION (OCM) |
| References | |
| ACRS-SL-0324, ACRS-SL-324, NUDOCS 8704010533 | |
| Download: ML20205K205 (5) | |
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8 NUCLEAR REGULATORY COMMISSION o
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,I ADVISORY COMMITTEE ON REACTOR SAFEGUARDS g
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%4 July 21, 1986 Honorable Lando W. Zech, Jr.
Chairman U.S. Nuclear Regulatory Comission Washington, D.C. 20555
Dear Mr. Zech:
SUBJECT:
THREE HUNDRED AND FIFTEENTH MEETING OF THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS, JULY 10-12, 1986 The Advisory Comittee on Reactor Safeguards held its 315th meeting in Washington, D.C. on July 10-12, 1986.
Items considered during this meeting are summarized below:
315TH ACRS MEETING The Committee met with representatives of the Toledo Edison Company (Licens-ee) and of the NRC Staff to review actions taken to resolve concerns raised as a result of the loss of feedwater event at the Davis Besse Nuclear Power Station, Unit 1.
The Comittee met with representatives of the NRC Staff to review the pro-posed Comission Policy Statement on Technical Specifications (second draft) as transmitted by memorandum dated June 30, 1986.
The Committee discussed continuing NRC support of activities provided by the ICRP, the NCRP, and the NAS concerning the effects of exposures to various types of radiation, The Comittee met with representatives of the NRC Staff to consider various activities associated with nuclear power plant fire protection provisions including 10 CFR Part 50.48, the Appendix R modification process, and fire-related portions of the NRC safety research program.
The Comittee considered procedures that might be used in the development of a g minimis radiation dore value for regulatory use, Reports on the subjects noted above have been sent to you.
The Comittee discussed its recomendations that a structured test program for evaluating overspeed protection of the turbine be prepared and submitted to the NRC Stafi for review and approval before full power operation of the l
Hope Creek Generating Station which appeared in its letter to Chairman Palladino on December 18, 1984, and new information bearing on that recomen-dation.
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t Honorable Lando W. Zech, Jr.
2 July 21, 1986 The Committee discussed proposed revisions to the Standard Review Plan Sections 9.2.1, " Station Service Water System," and 9.2.2, " Reactor Auxiliary Cooling Water Systems."
The Committee discussed the B&W Owners Group Safety and Performance Improve-ment Program and NRC staff plans to reassess the long-term safety of B&W reactors.
The Committee proposed that the NRC should consider the use of the screening model recently published by the National Council on Radiation Protection and Measurements to certain nonnuclear power plant licensees who must either develop plans for coping with accidental radionuclide releases or justify the reasons that the development of such plans is not needed (emergency planning requirements).
The Committee's comments on these subjects have been provided to the Execu-tive Director for Operations. Copies have been sent to you.
The Committee met with representatives of the NRC Staff and the Tennessee Valley Authority (TVA) to review the issues related to the shutdown of the TVA nuclear power plants and the reorganization of the TVA management struc-ture. Additional consideration of this matter is planned for the 316th ACRS meeting to be held on August 7-9, 1986.
The Committee met with representatives of the NRC Staff, the Atomic Indus-trial Forum, and EPRI to review the NRC Standardization Policy Statement and the EPRI Advanced LWR Utility Recuirements program. Additional consideration of this matter is planned for t1e 316th ACRS meeting to be held on August 7-9, 1986.
The Committee met with representatives of the NRC Staff to discuss issues NRR considers important to the reactivation of deferred, terminated, or cancelled nuclear power plants.
The Committee was briefed by a representative of the NRC Staff regarding the IIT's findings applicable to the December 26, 1985 incident at the Rancho Seco nuclear plant.
Since the last report of ACRS activities, the following subcommittee meetings have been held:
Ad Hoc Subcommittee on TVA, in Chattanooga, TN on June 12-13, 1986 to discuss TVA reorganization and related technical and management issues
i Honorable Lando W. Zech, Jr.
3 July 21, 1986 Babcock and Wilcox (B&W) Reactor Plants, in Washington, D.C. on June 25, 1986 to consider the B&W Owners Group's plans to reassess the long-tem safety of B&W reactors, including the implications of operating experi-ence on the adequacy of B&W plant designs.
The Subcommittee was also briefed on the NRC Staff's Incident Investigation Team's findings related to the 12/26/85 loss of integrated control system power and overcooling transient at the Rancho Sec nuclear power plant Metal Components, in Churchill, PA on June 25, 1986 to review the status of nondestructive examination of cast stainless steel components and changes in steel-making practice Auxiliary Systems, in Washington, D.C. on June 26, 1986 to discuss: (1) among the Staff, (3)ppendix R compliance, (2) differing technical views the status of the A i
proposed research and associated budget for FY 1988 i
and 1989 in the fire protection area, (4) updates on the progress being made in the Sandia experimental program on fire protection, (5) inspec-tion activities to determine compliance with the Fire Protection Re-l quirements, and (6) recent experiences associated with inadvertent actuation of fire protection systems i
Gas Cooled Reactor Plants, in Washington, D.C. on June 26, 1986 to review the applicability of NRC requirements for equipment qualification and cable testing and other topics related to the Fort St. Vrain gas cooled reactor.
Regulatory Policies and Practices, in Washington, D.C. on June 26, 1986 to review the regulatory process as it relates to the June 9,1985 Davis-Besse event using the Davis-Besse Ad Hoc Group Report as the basis for the meeting Joint Occupational and Environmental Protection Systems and Auxiliary Systems, in Washington, D.C. on June 27, 1986 to: (1) be briefed by NRR and Region Staffs on the status of various control room HVAC systems problems and the control room habitability improvement effort, (2) be briefed by the AE0D Staff on the effects of ambient temperature on I&C systems, (3) discuss with the Staff their procedures and criteria for reviewing Chilled Water Systems, their " walk-down" of the Chilled Water Systems at Shearon Harris, and the contribution to risk from Chilled Water System failures based on PRA studies, and (4) discuss with the i
Staff de minimis environmental radiation levels Davis-Besse, in Washington, D.C. on June 27, 1986 to review start-up activities for Davis-Besse Plant Operating Procedures, in Washington, D.C.
on July 1, 1986 to review " Proposed Comission Policy Statement on Technical Specifica-tions" 1
1 Honorable Lando W. Zech, Jr.
4 July 21, 1986 Metal Components, in Columbus, OH on July 1 and 2,1986 to review the degraded piping program of RES and NRR and visit the Battelle-Columbus primary testing facility Improved LWR Designs, in Washington, D.C. on July 9,1986 to be briefed and discuss the following topics:
(1) the proposed NRC Standardization Policy Statement, (2) proposed changes to 10 CFR 50, and (3) the EPRI Advanced Light Water Utility Requirements documents Lonc Range Plan for NRC, in Washington, D.C. on July 9,1986 to discuss guicelines for the development of a long range plan Future Agenda The following items are tentatively scheduled for consideration during the 316th ACRS meeting, August 7-9, 1986:
Meeting with Director, NMSS -- Discuss items of mutual interest San Onofre Nuclear Generating Station, Unit 1 -- Discuss corrective measures following loss of feedwater event on November 21, 1985 Human Factors Issues -- ACRS comments on (1) Proposed NRC policy state ment on fitness for duty; (2) proposed NRC Advanced Notice of Rulemakin on Educational Requirements for Senior Reactor Operators; and (3 proposed revision of Regulatory Guide 1.114, Guidance to Operators at the Controls and to SR0s in the Control Room USI A-46, Seismic Qualification of Equipment in Operating Plants -- ACRS comments on proposed final USI resolution package Recent Events at Operating Nuclear Power Plants -- Report of ACRS Subcommittee and representatives of the NRC Staff regarding recent incidents and accidents at nuclear power plants Continue discussion of ACRS coments on Advanced LWR Designs -- Discuss proposed ACRS coments regarding design requirements for advanced LWRs Lons-Range Plan -- Report of ACRS Subcommittee regarding proposed guicelines for a long range plan for NRC Standardized Nuclear Plants - Continue review of proposed NRC Policy Statement TVA Reorganization - Discuss proposed ACRS coments regarding the pro-posed TVA reorganization to address design, construction, and opera-tional problems in TVA's nuclear power plants
1 Honorable Lando W. Zech, Jr.
5 July 21, 1986 i
Radioactive Waste Management and Disposal - Discuss proposed ACRS com-ments on matters related to residual radiation levels in the disposition of land, buildings, equipment, and metal Sincerely, QA)
David A. Ward Chairman 4
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