ML20071D425
| ML20071D425 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 03/01/1983 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20071D416 | List: |
| References | |
| NUDOCS 8303110157 | |
| Download: ML20071D425 (2) | |
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SAFETY EVALUATION BY THE OFFICE OF HUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NOS. 9 0 AND 9 0 TO FACILITY LICE'NSE' NOS. DPR-44 AND PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS NOS. 2 AND 3 DOCKETS NOS. 50-277 AND 50-278 Introduction By letter dated December 15,1982 (Reference 1), the Philadelphia Electric Company (PECo or the licensee) made application to amend the Technical Specifications (TSs) for the Peach Bottom Atomic Power Station, Units Nos. 2 and 3, to provide operability and surveillance requirements for the scram discharge volume (SDV) vent and drain isolation valves. As indicated in their December 16, 1900 letter (Reference 2), the licensee, as a result of an HRC requested reevalua-tion of their SDV system, outlined modifications which would provide redundant isolation valves on the SDV system vent and drain lines in series with the existing valves.
These new valves would protect against loss of reactor coolant from the discharge volume, given a
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single active failure of one of the valves.
Eval uation The licensee committed by letter (Reference 2) to provide redundant isolation valves on the SDV system vent and drain lines in series with the existing valves.
These valves were installed in conformance with cr.iteria developed by the BHR Owners' Group as reque.sted by the NRC staff.
The proposed revisions to the TSs are intended to provide operability and surveillance requirenents for these redundant isolation valves in accordance with the existing TSs on Primary Containment Isolation Valves.' He have reviewed the requested TS changes to determine whether they are in confomance with the licensee's existing s0rveillance TSs for Containment Isolation Valves. Our review indicates that the proposed TSs do conform with the licensee's existing TS surveillance requimments and are, therefore, acceptable. The licensee has alsa requested the deletion of obso.lete footnotes pertaining to Ameridment No. 73 for Peach Bottom Unit No. 2 and Arendment No. 72 for Peach Bottom Unit No. 3 since the modifications authorized by these amend-ments have been completed.
8303110157 830301 PDR ADOCK 05000277 P
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e We have reviewed the above deletion requests and concur that the modifications have been completed. Therefore, these TS changes are acceptable.
Envirenrental Consideration We have determined that the amendments do not authorize a change in effluent types or total amounts nor an increase in power level and will not result in any significant environmental impact. Having made this determination, we have further concluded that the amendments involve an action which is insignificant from the standpoint of environmental impact and, pursuant to 10 CFR 551.5(d)(4), that an environmental impact statement, ~ r negative declaration and environ-o mental impact appraisal need not be prepared in connection with the issuance of'these amendments.
Conclusion We have concluded, based on the considerations discussed above, that:
(1) because the amendments-do not involve a significant increase in the probability or consequences of an accident previously evaluated, do not create the possibility of an accident of a type different from any evaluated previously, and do not involve a significant reduction in a margin of safety, the amendments do not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by-operation'in the proposed manner, and (3) such activities will be conducted in compliance with the Commission's regulations and the issuance of these amendments will not be inimical to the common defense and security or to the health and safety of the public.
Dated: MAR 011983 The following NRC personnel have contributed to this Safety Evaluation:
Gerry Gears and "en Eccleston.
References:
1.
Letter to H. R. Denton (NRR) from E. J. Bradley (PECo), Application for Amendment of Facility Operating Licenses DPR-44 and DPR-56,
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December 15, 1982.
2.
Letter to D. G. Eisenhut (NRR) from S. L. Daltroff (PECo),
Responses to October 1,1980 letter Requesting Results of SDV System Reevaluation, December 16, 1980.
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