ML20205J984
| ML20205J984 | |
| Person / Time | |
|---|---|
| Issue date: | 05/16/1986 |
| From: | Ward D Advisory Committee on Reactor Safeguards |
| To: | Palladino N NRC COMMISSION (OCM) |
| References | |
| REF-GTECI-A-17, REF-GTECI-SY, TASK-A-17, TASK-OR ACRS-SL-0322, ACRS-SL-322, NUDOCS 8704010482 | |
| Download: ML20205J984 (3) | |
Text
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WASHINGTON, D. C. 20555 May 16, 1986 Honorable Nunzio J. Palladino Chairman U.S. Nuclear Regulatory Comission Washington, D. C.
20555
Dear Dr. Palladino:
SUBJECT:
THREE HUNDRED AND THIRTEENTH MEETING OF THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS, MAY 8-10, 1986 The Advisory Committee on Reactor Safeguards held its 313th meeting in Washington, D.C.
on May 8-10, 1986.
Items considered during this meeting are summarized below:
313th ACRS MEETING The Comittee met with representatives of the NRC Staff to review the recent Comission actions relative to the Department of Energy request for an exemption to permit salvaging of contaminated smelted alloys.
The Comittee discussed the need for the NRC to provide funds in support of the programs of certain key radiation protection organizations including the National Council on Radiation Protection and Measurements, the International Comission on Radiological Protection and the National Academy of Sciences Committee on the Biological Effects of Ionizing Radiation.
The Comittee met with representatives of the NRC Staff to discuss the Low-Level Radioactive Waste Policy Amendments Act of 1985 and the opportunity to expand the definition of low-level radioactive waste to include " Naturally Occurring and Accelerator Produced Radioactive Materials" or NARM wastes to bring this category of radioactive waste under regulatory control.
Reports on the subjects noted above have been sent to you.
The Committee met with representatives of the NRC Staff to review the draft proposed resolution of Unresolved Safety Issue A-17 (Systems Interactions in Nuclear Power Plants), as presented to the CRGR on April 10, 1986.
The Comittee's coments on this subject have been provided to the Executive Director for Operations. A copy has been sent to you.
The Comittee discussed with representatives of the NRC Staff the NRC Staff findings based on audits of the Department of Energy quality assurance program for the pre-licensing phase and construction of a g 40 g 2 860516 DESIONATED OEIGIEAL 4W WWW SL.03t.s PDR Certified By [
Honorable Nunzio J. Pa11adin) May 16, 1986 j
i high-level radioactive waste repository.
NRC research efforts in the area of high-level waste were also discussed.
The Committee met with you and the other Comissioners to discuss the proposed NRC Safety Goal Policy Statement using the ACRS report on this subject dated April 15, 1986 as the principal basis of the discussion.
The Comittee was briefed by representatives of the NRC Staff on the Staff's knowledge of the Chernobyl Nuclear Power Plant Event in the Ukraine, Soviet Union.
The Committee met with representatives of the RSK (Federal Republic of Germany) to discuss high-and low-level radwaste standards for radio-nuclide release limits (dose limits), plans for environmental monitoring of radwaste repositories, and modeling in connection with performance assessment of radwaste handling and disposal facilities to assure compliance with related standards and protection of the public health and safety.
The Committee was briefed by an ACRS member on the subject of decay heat removal from PWRs and a proposed system for primary blowdown (for enhanced core cooling) on the Westinghouse standardized PWR.
Since the last report of ACRS activities, the following subcomittee meetings have been held:
Waste Manacement, in Washington, D.C.
on April 24-25, 1986 to review the following topics:
(1) Modeling Strategy for HLW Performance Assessment, (2) Quality Assurance (addressing Safety Issues of Geologic Repositories), (3) the NRC LLW program (4) several research efforts, including International Programs and Cooperative Agreements, results of Modeling Workshop, and Setting Priorities for HLW Research, and (5) the Salvaging of Contaminated Smelted Alloys Thermal Hydraulic Phenomena, in Washington, D.C. on April 29-30, 1986 to continue review of the NRC's proposal to revise 10 CFR 50.46 and Appendix K and to continue discussions on defining important themal hydraulic safety issues Severe (Class 9) Accidents, in Albuquerque, NM on May 1-2, 1986 to review rebaselining studies for four or five reference plants, which are part of studies for NUREG-1150, " Nuclear Power Plant Risks and Regulatory Applications." On May 2,1986 a tour of the Sandia containment model was conducted Safety Philosophy, Technology, and Criteria, in Washington, D.C. on May 7, 1986 to review the NRC Staff's proposed resolution of USI A-17 " Systems Interactions in Nuclear Power Plants" l
Safety Research Program, in Washington, D.C. on May 7,1986 to gather information for use by the ACRS in its preparation of the j
Honorabic Nunzio J. Palladino May 16, 1986 8
annual report to the Commission on the proposed NRC Safety Research Program and Budget (for FY 1988-89)
Future Agenda Meeting with NRC Comissioners -- Discuss GESSAR II ACRS report dated January 14, 1986 Recent Events at Operating Nuclear Power Stations -- Report of ACRS Subcomittee and representatives of the NRC Staff regarding recent incidents and accidents at nuclear power plants South Texas Project, Units 1 and 2 -- OL review Davis-Besse Nuclear Plant, Unit 1 -- Subcommittee report on eval-uation of the review and approval process regarding the design of the auxiliary feedwater system and the operation / inspection of the Davis-Besse Plant per the request of Comissioner Asselstine as well as the IIT investigation process for the June 9,1985 incident at this plant Discuss proposed TVA reorganization to TVA Reorganization resolve QA, design, etc. problems at TVA nuclear plants Technical Integration Center -
ACRS Subcomittee Activities Subcomittee report regarding project status Reactor Safety Research Report -- Discuss proposed ACRS report to NRC regarding the proposed NRC safety research program for FY 1988-89 Reassessment of Source Term (NUREG-0956) -- ACRS coments regarding proposed revision of NUREG-0956 NRC Regulatory Guides -- ACRS coments regarding Regulatory Guide revisions regarding Reg. Guide 1.35, Rev. 3 ISI of Ungrouted Tendons in Prestressed Concrete Containments; and R.
G.
1.35, Determining Prestressing Forces for Inspection of Prestressed Concrete Containments - ACRS comments requested regarding minor changes since ACRS coments provided in 1984 Sincerely, e 1%
David A. Ward Chairman
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