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

{{Adams
| number = ML20057F249
| issue date = 10/06/1993
| title = Provides Response to Request for Addl Info Re Floor Spectra for Resolution of USI A-46
| author name = Beard P
| author affiliation = FLORIDA POWER CORP.
| addressee name = 
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05000302
| license number = 
| contact person = 
| case reference number = REF-GTECI-A-46, REF-GTECI-SC, TASK-A-46, TASK-OR
| document report number = 3F1093-04, 3F1093-4, GL-87-02, GL-87-2, TAC-M69440, NUDOCS 9310140338
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE
| page count = 4
| project = TAC:M69440
| stage = Request
}}

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

 . - .           ~._           _   _. _-        - - - _ _ _ , _ _ _ _ _ . .. _ . . _  ._. .
U. S. Nuclear Regulatory Commission                                                 i 3fl093-04                                                                           i
       . Page 2                                                                              ?
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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.                                                                          I i
Sincerely,                                                                          ;
M[
           .M Beard, Jr.
Senior Vice President Nuclear Operations                                                                  ,
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Attachment
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