ML20198C186
| ML20198C186 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 06/20/1991 |
| From: | Beck G PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9106280168 | |
| Download: ML20198C186 (2) | |
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PIIILADELPIIIA ELECTRIC COMPANY NUCLEAR GROUP HEADQUARTERS 955-65 CHESTERBROOK BLVD.
WAYNE, PA 19087 5691 (215) 640-6000 NUCLEAR ENGINEERINO & $ERYlCES DEPARTMENT June 20, 1991 Docket Nos.
50-277 50-278 License Nos. DIR-44 DIR-56 U.S. Nuclear Ngulatory Chanission Attn: Docunent Cbntrol Deck Washington, DC 20555 SU1Dirr: Ibach Bottan Avomic Power Station, Units 2 and 3 Response to Rerpest for Acilitional Information Concerning the Containment Isakage 'Ibsting Program Technical Specifications R12Mt1NCE:
1) letter fran E. J. Bradley (IECo) to H. R. Denton (th), dated October 10, 1986 2)
Intter frun G. J. Deck (PEOo) to U.S. Nuclear Regulatory Cm mission, dated May 17, 1991
Dear Sir:
As roguested by the interim leadt Dottan Atanic Ibwer Station Project Manager (Pat Milano), attached is a revised "Information Supportirq a Finding of No Significant Hazards Consideration" to supercede the Reference 1 Technical Specification Anendment Application and the Reference 2 response to the request for additional information.
g If you have any questions or require aMitional information, please do not basitate to contact us.
Very truly yours, sb[ L G. J. Beck, Manager Licensing Section Nuclear Dgineerity & Services Attachnent cc:
T. T. !brtin, Administrator, Region I, USNRC J. J. Lyash, USNI<C Senior Msident Inspector, PB T. M. Gerusky, Camonwealth of Ibnnsylvania 9106280169 910620 PDR ADOCK 05000277 jf0/7 P-PDR
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k Attachment Page 1 Information Suonortina a Findina of No Sianificant Hazards consideration The p: sposed changes to the Peach Bottom Operating License do not constitute a significant hazards consideration for the following reasons:
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The proposed revisions do not involve a sianificant increase in the orobability or consecuences of an accident previously evaluated since these revisions incorporate into the Technical Specifications requirements of 10CFR50, Appendix J and NRC approved exemptions. Additionally, these changes do not affect primary containment leakage rates as assessed in the-safety design analyses.
Also, the frequency of conducting local leak rate tests and the primary containment integrated leak rate test conform to the requirements of 10CFR50, Appendix J and the previously approved NRC exemptions.
The proposed changes provide more complete and detailed isolation valve tables and text changes which conform to the testing and leak rate requirements of 10CFR50, Appendix J and the previously approved NRC exemptions, 11)
The proposed revisions do not create the oo.gsibility of a new or different kind of accident from any accblent previously evaluated because the periodic verification of the leak-tight integrity of the penetrations, valves and piping subject to these periodic tests as discussed in this proposed Technical Specification Amendment Application conform to the requirements of 10CFR50, Appendix J and the NRC approved exemptions.
Additionally, the acceptance criteria for the leakage rates conform to the requirements of 10CFR50, Appendix J and the NRC approved exemptions.
iii) The proposed revisions do not involve a sianificant reduction in a margin of safety because the proposed changes meet the requirement of 10CFR50 Appendix J and the previously NRC approved exemptions.
The proposed changes will ensure that the period verification and leak-tight integrity of the reactor containment is maintained and will not reduce the margin of safety.
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