3F1093-04, Provides Response to Request for Addl Info Re Floor Spectra for Resolution of USI A-46

Provides Response to Request for Addl Info Re Floor Spectra for Resolution of USI A-46

ML20057F249
Person / Time
Site:	Crystal River
Issue date:	10/06/1993
From:	Beard P FLORIDA POWER CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
REF-GTECI-A-46, REF-GTECI-SC, TASK-A-46, TASK-OR 3F1093-04, 3F1093-4, GL-87-02, GL-87-2, TAC-M69440, NUDOCS 9310140338
Download: ML20057F249 (4)

Text

..

6 Florida Power CORPORATION 5%EN P

October 6, 1993 3F1093-04 U. S. Nuclear Regulatory Commission Attn:

Document Control Desk Washington, DC 20555

Subject:

Request for Additional Information on Floor Response Spectra for the 7

Resolution of USI A-46 (TAC No. M69440)

References:

1. NRC to FPC letter, 3N0793-07, dated July 9,1993

2. FPC to NRC letter, 3F0993-04, dated September 7, 1993

Dear Sir:

Reference 1 included 6 requests for additional information regarding the floor i

response spectra to be used for resolution of Unresolved Safety Issue (USI) A-46, Seismic Qualification of Equipment in Operating Nuclear Power Plants, for Crystal River 3 (CR-3).

The enclosure to Reference 2 provided Florida Power Corporation's (FPC's) response to 5 of the 6 requests.

The attachment to this letter provides the floor response spectra for elevations 160' and 180.5' of the reactor building.

This satisfies the request of item 5 of Reference 1.

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• i g CRYSTAL RIVER NUCLEAR PLANT: Powerline Road + P.O. Box 219 + Crystal River, Florida 34423-0219 + (904) 795fA86 9310140338 931006 PDR ADOCK 05000302 Ei P

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U. S. Nuclear Regulatory Commission i

3fl093-04 i

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These floor spectra are not bounded by the seismic capacity bounding spectrum l

based on earthquake experience data from the Generic Implementation Procedure

-i (GIP). Consequently, the generic seismic demand evaluation in Appendix A of the Technical Basis for the Crystal River Unit 3 Plant Specific Procedure to Resolve NRC Generic Letter 87-02 is not applicable to equipment at these elevations.

j Thus, all equipment at these elevations within the scope of USI A-46 will be evaluated as outliers for seismic capacity vs. demand in accordance with Section 5 of the Plant Specific Procedure for Seismic Verification of Nuclear Plant Equipment.

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Sincerely, M[

.M Beard, Jr.

Senior Vice President Nuclear Operations i

PMB/AEF:ff Attachment

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