View source for PY-CEI-NRR-0483, Forwards Design Control Procedure 2.10, Perry Power Plant Confirmatory Program of 860131 Ohio Earthquake Effect, Providing Final Results to Confirmatory Activity in Sser 9, Sections 3.7.2 & 3.10.1

{{Adams
| number = ML20199D088
| issue date = 06/17/1986
| title = Forwards Design Control Procedure 2.10, Perry Power Plant Confirmatory Program of 860131 Ohio Earthquake Effect, Providing Final Results to Confirmatory Activity in Sser 9, Sections 3.7.2 & 3.10.1
| author name = Edelman M
| author affiliation = CLEVELAND ELECTRIC ILLUMINATING CO.
| addressee name = Butler W
| addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| docket = 05000440, 05000441
| license number = 
| contact person = 
| document report number = 860617, PY-CEI-NRR-0483, PY-CEI-NRR-483, NUDOCS 8606190255
| package number = ML20199D092
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 1
}}

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t THE CLEVELAND ELECTR P.o. Box 0000
* CLavtLANo, oHlo 44101     .
TELEPHONE (210) 622 8600    ILLUMINATINo 8LDo.
Serving The Best Location in the Nation
                                                                                                                                                    =
                                                                                                                                                      $$ PusLtc$QUARE MURRAY R. EDELMAN June 17, 1986 VICE PPEElotNT                                                                 PY-CEI/NRR-0483 L NUCLEAR Dr. W. R. Butler, Director BWR Project Directorate No. 4 Division of BWR Licensing U.S. Nuclear Regulatory Commission Washington, D.C.                        20555 Perry Nuclear Power Plant Docket Nos. 50-440; 50-441 Engineering Evaluations to Resolve Seismic Confirmatory Items                              _

==Dear Dr. Butler:==

The purpose of this letter and its attachments is to provide the final results of the engineering studies to resolve the confirmatory items identifed in SSER No. 9 related to the January 31, 1986 earthquake. Included in the attached report are the results of our additional assessments of seismic qualification of equipment and the results of our generic evaluation of the energy content and the safety significance of high frequency, short duration earthquakes. The report reaffirmed the adequacy of the Perry Plant seismic design and demonstrates that plant structures and equipment seismic qualification have i         safety margins to accommodate the January 31, 1986 earthquake even though the design 20 Hz.
elastic response spectra was exceeded at isolated frequency range around In addition, the studies confirm the fact that the the Perry Nuclear Power Plant design has additional capability even when a high frequency content earthquake of somewhat higher amplitude and longer duration is assumed.
This submittal completes the confirmatory activity described in SSER No. 9 Sections next        supplement         3.7.2 and   3.10.1 to the  SSER. and should enable these issues to be resolved in the l
If you have any questions, pleasa let me know.
Very truly         ur ,
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John Stefano (2)                                                                                                                                   I    L J. Crobe                                                                                                                                                  .
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