ML20070D982

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Safety Evaluation Supporting Amend 86 to License DPR-56
ML20070D982
Person / Time
Site: Peach Bottom 
Issue date: 12/07/1982
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20070D977 List:
References
NUDOCS 8212160551
Download: ML20070D982 (2)


Text

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NUCLEAR REGULATORY COMMISSION r,

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 86 TO FACILITY OPERATING LICENSE NO. DPR-56 PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY

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PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 3 DOCKET NO. 50-278 INTRODUCTION By letters dated October 19, 1982 and December 3,1982, the Philadelphia Electric Company (PECo or the licensee) made application to amend the Technical Specifications (TSs) for the Peach Bottom Unit 3 to temporarily extend the inspection interval applicable to two inaccessible hydraulic snubbers.

EVALUATION On April 8,1982, as a result of a determination that two inaccessible pipe support hydraulic snubbers were found inoperable by the licensee, the next required inspection interval, based on the provisions of section 4.11.D.1 of the Peach Bottom Technical Specifications, would require Peach Bottom Unit 3 to be removed from service to accommodate inspection of snubbers on or before December 7,1982 PECo estimates that Unit 3 would be out of service for approximately four days to accommodate the inspection of the snubbers which were previously declared inoperable on April 8,1982, which are located in the drywell.

However, Peach Bottom Unit 3 is presently scheduled to be removed from service for a refueling outage 67 days later, on February 12, 1983.

Thus, performing the inspection of the inaccessible snubbers within the present required interval would add one shutdown, startup transient to the operating history of the unit despite the availability of a scheduled outage a short time later.

We have detertnined through a review of the last six complete inspections on all 158 safety related snubbers that only four snubbers have been found inoperable, including the two detected on April 8,1982. The four snubbers were inoperable due to loss of oil. - All four have been 8212160551 821207 PDR ADOCK 05000278 P

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- repaired and returned to service, As stated in the bases, on page 235a, Section 3.11.D, of the Technical Specifications, the snubber protection is required only during low probability events.

We conclude, based on the favorable past failure history, the need for snubber protection only during low probability events, and the additional cooldcun - heatup transient required to conduct the inspection, that the extension of the inspection interval as requested is acceptable.

ENVIR0tNENTAL CONSIDERATIONS We have determined that the amendrent does 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 amendment involves 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, or negative declaration and environ-mental impact appraisal need not be prepared in connection witn the issuance of this amendment.

CONCL'JS. ION We have concluded, based on the considerations discussed above, that:

(1) because the amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated, does not create the possibility of an accident of a type different from any evaluated previously, and does not involve a significant reduction in a margin of safety, the amendment does 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 this amendment will not be inimical to the common defense and security or to the health and safety of the public.

Dated: December 7,1982

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The following NRC personnel have contributed to this Safety Evaluation:

Gerry Gears, Morton Fairtile, Horace Shaw.

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