ML17331A962

Discusses Util Response to Suppl 1 to GL-87-02, Seismic Qualifications of Mechanical & Electrical Equipment in Operating Plants

ML17331A962
Person / Time
Site:	Cook
Issue date:	08/17/1993
From:	Wetzel B Office of Nuclear Reactor Regulation
To:	Fitzpatrick E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
References
GL-87-02, GL-87-2, TAC-M69437, TAC-M69438, NUDOCS 9309020306
Download: ML17331A962 (5)

Text

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50-315 and 50-316 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 17, 1993 0~5M Hr. E.

E. Fitzpatrick, Vice President Indiana Michigan Power Company c/o American Electric Power Service Corporation 1 Riverside Plaza

Columbus, Ohio 43216

SUBJECT:

DONALD C.

COOK NUCLEAR PLANT, UNITS 1

AND 2 RESPONSE TO SUPPLEMENT NO.

1 TO GENERIC LETTER 87-02, "SEISMIC QUALIFICATION OF MECHANICAL AND ELECTRICAL EQUIPHENT IN OPERATING PLANTS" (TAC NOS.

H69437 AND H69438)

On Hay 22, 1992, the NRC staff issued Supplement No.

1 to Generic Letter (GL) 87-02, which transmitted Supplemental Safety Evaluation Report No.

2 (SSER No. 2) on the Seismic Qualification Utility Group's (SQUG) Generic Implementation Procedure, Revision 2 (GIP-2), dated February 14, 1992, for the resolution of Unresolved Safety Issue (USI) A-46.

By letter dated September 21,

1992, you submitted your 120-day response to Supplement No.

1 to GL 87-02.

The staff reviewed your response, and, in a letter dated December 23, 1992, provided a safety evaluation and a request for additional information related to your submittal.

In your September 21,

1992, response it was unclear as to whether you intended to implement the entire GIP-2, including both the SQUG commitments and the implementation guidance.

By letter dated April 1,

1993, and in a conference call on April 22,

1993, you clarified your commitment to the entire GIP-2, including both the SQUG commitments and the implementation

guidance, and confirmed that any deviation from the implementation guidance would be performed in accordance with the provisions of Part I, Section 1.3 of GIP-2.

The staff finds that the commitment to the entire GIP-2 is an acceptable method for resolving USI A-46.

The staff also reviewed your April 1,

1993, response to our request for additional information regarding the development of the in-structure response spectra (IRS).

Based on our review of your response and the staff positions delineated in the SSER No. 2, we conclude that the procedure used to generate the IRS is adequate and acceptable with the following conditions.

The IRS discussed in the submittal should be treated as median-centered response spectra due to the lack of considerations in the dynamic analyses of:

(1) the extent of conformance regarding whether the average ground response spectra obtained from the two sets of the time histories envelop the licensing basis ground response spectra (GRS),

(2) the impact of use of soil springs in lieu of a comprehensive soil-structure interaction analysis, (3) square root of the sum of the squares approach in calculation of the combined multi-directional responses, and (4) the effect of insufficient peak broadening.

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Mr. E.

E. Fitzpatri ck August 17, 1993 Additionally, in response to your request not to inspect a few isolated areas of the plant, where inspection of the raceway supports may not be possible due to congestion, the staff emphasizes that the walkdown should cover all areas I'th pl

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although the staff does not anticipate such cases, then we request that you prepare a document that provides comprehensive justification for not inspecting the area including the field condition, potential radiological

hazards, bases for judging raceway support adequacy without direct inspection, and pertinent design and construction drawings for staff review and acceptance.

This document should be available for audit onsite.

If you have any questions regarding these

items, please contact me on 301-504-1355.

Sincerely, cc:

See next page DISTRIBUTION:

NRC 8 Local PDRs PDI-I-I-I-Reading-Fil e J.

Roe J. Zwolinksi W. Dean B. Wetzel C. Jamerson J. Norberg G. Bagchi OGC ACRS (10)

W. Shafer, RIII Original signed by Beth A. Wetzel, Acting Project Manager Project Directorate III-1 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation LA:PDIII-1 OFFICE NAME CJamerson DATE 93 COPY YES NO G:)WPDOCSIt OOK)C069438.L A PM:PDIII-1 BC GB BWetzel &

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Mr. E.

E. Fitzpatrick Indiana Michigan Power Company CCJ Regional Administrator, Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137 Attorney General Department of Attorney General 525 West Ottawa Street

Lansing, Michigan 48913 Township Supervisor Lake Township Hall Post Office Box 818 Bridgman, Michigan 49106 Al Blind, Plant Manager Donald C.

Cook Nuclear Plant Post Office Box 458 Bridgman, Michigan 49106 U.S. Nuclear Regulatory Commission Resident Inspector Office 7700 Red Arrow Highway Stevensville, Michigan 49127 Gerald Charnoff, Esquire

Shaw, Pittman, Potts and Trowbridge 2300 N Street, N.

W.

Washington, DC 20037 Mayor, City of Bridgman Post Office Box 366 Bridgman, Michigan 49106 Special Assistant to the Governor Room 1

State Capitol

Lansing, Michigan 48909 Nuclear Facilities and Environmental Monitoring Section Office Division of Radiological Health Department of Public Health 3423 N. Logan Street P. 0.

Box 30195

Lansing, Michigan 48909 Donald C.

Cook Nuclear Plant Mr. S. Brewer American Electric Power Service Corporation 1 Riverside Plaza

Columbus, Ohio 43216 July 1%6