ML20205J741

Summary of ACRS 310th Meeting on 860213-15 in Washington,Dc Re Review Studies Done & Procedures Proposed by Gpu Nuclear to Protect Against Inadvertent Criticality During Defueling of TMI-2 Core

ML20205J741
Person / Time
Site:	Davis Besse, Mcguire, Perry, Arkansas Nuclear, Three Mile Island, Turkey Point, San Onofre, McGuire, 05000000
Issue date:	02/28/1986
From:	Ward D Advisory Committee on Reactor Safeguards
To:	Palladino N NRC COMMISSION (OCM)
References
ACRS-SL-0319, ACRS-SL-319, NUDOCS 8704010400
Download: ML20205J741 (5)

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UNITED STATES NUCLEAR REGULATORY COMMISSION hbf S W?

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$.. aE ADVlsORY COMMITTEE ON REACTOR SAFEGUARDS O WASHINGTON, D. C. 20555

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( February 28, 1986 Honorable Nunzio J. Palladino Chairman U. S. Nuclear Regulatory Comission Eashington, D. C. 20555 4

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Dear Dr. Palladino:

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SUBJECT:

THREE HUNDRED AND TENTH MEETING OF THE ADVISORY C0tNITTEE ON

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REACTOR SAFEGUARDS, FEBRUARY 13-15, 1986 s

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The Advisory Committee on Reactor Safeguards held its 310th meeting in Washington, D. C. on February 13-15, 1986. Items considered during this meeting are sumarized below:

310th ACRS MEETING The Committee met with representatives of GPU Nuclear and the NRC Staff to review studies done and procedures proposed by GPU Nuclear to protect x

against inadvertent criticality during the defueling of the Three Mile Island Nuclear Station, Unit 2 core.

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The Committee ret with representatives of the NRC and industry (NUMARC, 3

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, l in particular) to discuss the Insider Safeguards Rules proposed by the i, t NRC Staff and the so-called "NUMARC initiatives," a set of guidelines

- , 'for, achieving a similar purpose which utility licensees were said to prefer.

, g The Comittee completed its review of the NRC Safety Research Program and Budget for Fiscal Year 1987 and preparation of its related annual

. ACRS report to the U. S. Congress.

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Re' ports on the subjects noted above have been sent to you.

, The Comittee discussed a proposed Comittee report on the current D  ; status of nuclear power plant safety. This report was deferred indefi-

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The Comittee discussed comentt regarding the Proposed Revision of 10 CFR Part 20, " Standards for Protection Against Radiation." The Com-mittee forwarded coments to the Acting Executive Director for Opera-tions. A copy has been sent to you.

l s . The Comittee discussed how it intends to respond to several questions j i from Comissioner J. Asselstine associated with the loss of all feed- '

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m Honorable Nunzio J. Palladino February 28, 1986 water event at the Davis-Besse Nuclear Plant. The Committee has

- inquired of Comissioner Asselstine if he desires a separate ACRS review + ,

now that an ad hoc group and a Staff effort have been set up to review the' licensing aspects of the Davis-Besse 'feedwater systems and the long-ferm safety related aspects of Babcock and Wilcox nuclear power' plantsdesigns. Comissioner. Asselstine has indicated that ACRS comments s with rsspect to related Staff and ad hoc group. findings will be appro-priate in response to his request.

• The Committee met with representatives of the C eveland Electric Illum-inating Company, Weston Geophysical, Gilbert Comonwealth, and the NRC Staff to discuss the seismic event that occurred on January 31, 1986 near the site of thes Perry Nuclear Power Plant, Unit 1.

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Congressmen Dennis Eckart and John F. . Seiberling have requested ACRS' coments regarding review of the seismic data generated as a result of the earthquake near the Perry Nuclear Power Plant. An interim reply has been provided. The Comittee expects to respond to this request during its 311th (March 13-15, - 1986) or its 312th (April 10-12,1986) meeting depending in part on the availability of the NRC Staff Safety Evaluation j Report. .,

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The Committee was briefed by representatives of the Office of Inspection -

and Enforcement and the Office of Nuclear Reactor Regulation (NRR)

regarding recent operating occurrences at nuclear power plants,. in-

cluding a start-up with a degraded High Pressure Safety Injection System j at the McGuire Nuclear Station, Units 1 and 2, stop check valve failures at the Turkey Point Nuc! ear Generating Plant, Units 3 and 4, and a design deficiency in the steam supply to the steam-driven pumps in the i emergency feedwater system of Arkansas Nuclear One, Unit 1. The Com-i mittee was also' briefed by representatives of NRR on the MRR Technical Specification' Improvement Program.

The Committee, met with representatives of the NRC Staff to discuss the loss of AC power and feedwater water hammer event'which occurred on November 21,.1985 at the San Onof_re Nuclear Generating Station, Unit 1.

The Committee met with repreniitives of the NRC Staff, the U. S.

1 Federal Aviation Administ d4n, < td with NtMARC members to discuss the

! proposed use of the "cqr wc; 4 tor" concept for requalification of

nuclear power plant operat~rs.

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The Committee was briefed by members of the OIE Staff on the proposed

use of a Safety Systems Outage Modification Inspection Program.

The Committee was briefed by Mr. Benard C. Rusche, Director, High-Level Radioactive Waste Program of the U. S. Department of Energy on the status and implementation strategy for the Civilian Radioactive Waste Management Program.

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r Honorable Nunzio J. Palladino February 28, 1986 Since the last report of ACRS activities, the following subconinittee meetings. have been held:

. Qualification Program for Safety-Related Equipment, in Washington, D. C. on January 15, 1986, to discuss resolution and implementation of USI A-46, Seismic Qualification of Equipment in Operating Plants, and the SQUG/EQE evaluation of the Ma' ch 1985 Chilean earthquake

. Joint Waste Management and Reactor Radiological Effects, in Washington, D. C. on January 15-17, 1986 to review: (1) EPA's Low-Level Waste Standards (currently being developed), (2) Proposed Revision of 10 CFR 20, Standards for Protection Against Radiation, including the supporting AIF/NESP effort and SECY-85-147A, Regu-latory Exempt Radiation Levels (de minimis levels), (3) other topics in support of the NMSS/WM High-Level Waste Management Program, (4) the organization, role, and activities of the Com-mittee on Interagency Radiation Research and Policy Coordination (CIRRPC), and (5) MSS waste management and RES waste management and radiation protection research programs for FY 1987

. Emergency Core Cooling Systems, in Palo Alto, CA on January 23-24, 1986 to continue the review of the joint NRC/B&WOG/EPRI/B&W joint IST Program. The meeting included a visit to the EPRI-sponsored facilities supporting this Program at the Stanford Research Insti-tute and Science Applications, Inc.

. Core Performance, in Washington, D. C. on January 29, 1986 to review the potential for recriticality of TMI-2 during defueling operations

. Class 9 (Severe) Accidents, in Washington, D. C on January 29, 1986 to review the Staff's methodology and preliminary risk assess-ments for four reference plants to be reported in NUREG-1150

. Advanced Reactors, in Washington, D. C. on January 30, 1986 to review the GCR design description and the selection of design basis events

. Davis-Besse Nuclear Power Station, Unit 1 (restart), in Washington, D. C. on February 6, 1986 to review restart for Davis-Besse Nuclear Power Station, Unit 1 l

. Westinghouse Water Reactors, in Washington, D. C. on February 12, 1986 to review the November 21, 1985 loss of AC power and feedwater ,

water hammer event at San Onofre, Unit 1

. Reactor Operations, in Washington, D. C. on February 12,1986 to review recent operating events, and be briefed on the Technical Specification improvement program l

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Honorable Npzio J. Palladino February 28, 1986

. Long Range Plan for NRC, in Washington, D. C. on February 12, 1986 to continue discussion of a long range plan for the Comission and discuss future actions by the Subcomittee Future Agenda The following items are tentatively scheduled for consideration during the 311th ACRS meeting, March 13-15, 1986:

. Quantitative Safety Goals -- ACRS comments regarding review of two-year trial period for proposed NRC quantitative safety goals

. ACRS Effectiveness -- Proposed report to the Commissioners regard-ing implementation of the recomendations of the Panel on ACRS Effectiveness

. Proposed Revision of 10 CFR Part 72, Licensing Requirements for the Storage of Spent Fuel in an Inde )endent Spent Fuel Storage Installation (ISFSI) -- Status report )y subcommittee chairman

. Primary System Integrity -- ACRS coments on proposed revision of NRC GDC-4 to take credit for leak-before-break in all light water reactors for high energy piping systems; NUREG-0313, Pipe Crack Study Group Report, Rev. 2; and a proposed Regulatory Guide on implementation of the pressurized thermal shock program

. Advanced Reactor Design Review -- Review of conceptual design of DOE facilities

. Perry Nuclear Power Plant Seismic Design -- Request from Congress-men Dennis E. Eckart and John F. Seiberling and the NRC Staff for ACRS review of the seismic adequacy of the Perry Nuclear Power 1 Plant taking into account the recent earthquake near the plant I

. Safety Considerations in Future Reactors -- Discuss proposed ACRS coments regarding safety considerations in future reactors

. NRC Severe Accident Policy -- ACRS coments regarding the implemen-tation plan for the NRC Severe Accident Policy Statement

. Meeting with NRC Comissioners -- Discuss the following:

. ACRS resources / workload

. Proposal regarding the establishment of a Federal Academy for training of nuclear power plant operators

Honorable Nunzio February 28, 1986

. GESSAR II and safety considerations for future reactors Sincerely, 1

Y, David A. Ward Chairman l

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