ML19257B940

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Forwards Request for Addl Info Re Containment Purge Sys & Containment Venting Sys.Review of Responses to NRC 790927 & 1022 Ltrs Will Determine Acceptability of Continued Interim Operation
ML19257B940
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 01/02/1980
From: Ippolito T
Office of Nuclear Reactor Regulation
To: Bayer E
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
References
NUDOCS 8001210291
Download: ML19257B940 (4)


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UNITED STATES

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NUCLEAR REGULATORY COMMISSION

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,E WASMNGTON, D. C. 20555 JANUARY I E Docket Nos. 50-277 and 50-278 Mr. Edward G. Bauer, Jr., Esquire Vice President and General Counsel Philadelphia Electric Company 2301 Market Street Philadelphia, Pennsylvania 19101

Dear Mr. Bauer:

By letter dated November 28, 1978 the staff requested all licensees of operating reactors to respond to generic concerns about containment purging and venting during nomal plant operation.

In response you submitted letters dated January 2, July 31 and October 25, 1979 which discussed the design and operation of the containment purging and venting systems at the Peach Bottom Atomic Station, Units Nos. 2 and 3.

This was also the subject of a meeting we held with you in Bethesda, Maryland on August 24, 1979.

Since our initial correspondence, problem resolution has been divided into short term interim activities and a long term effort. Our short tem requirements were forwarded by letters in September and October of this year. By letter dated September 27, 1979 the staff forwarded guidelines for valve operability and requested your commitment to a valve qualifica-tion program within 30 days. By letter dated October 22, 1979 we forwarded the NRC containment purge interim position and requested your comitment within 45 days to operate in confomance with this position. The staff's review of your response to these letters will determine the acceptability of continued interim operation of the Peach Bottom facilities.

The enclosed request for additional information is forwarded as part of the long term review of the Peach Bottom facilities. Your response within 60 days of receipt of this letter would be appreciated.

Please note that additional written questions as well as a meeting in Bethesda are very likely.

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1774 206 8001210ZH

Mr. Edward G. Bauer, Jr., Esquire Please advise if we can be of further assistance.

Sincerely, u

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Thomas Af Ippolito, Chief Operating Reactors Branch #3 Division of Operating Reactors

Enclosure:

Request for Additional Information cc w/ enclosure:

see next page 1774 207

Mr. Edward G. Bauer, Jr.

Philadelphia Electric Company

-3 cc:

Eugene J. Bradley Philadelphia Electric Company Assistant General Counsel 2301 Market Street Philadelphia, Pennsylvania 19101 Troy B. Conner, Jr.

1747 Pennsylvania Avenue, N. W.

Washington, D. C.

20006 Raymond L. Hovis, Esquire 35 South Duke Street York, Pennsylvania 17401 Warren K. Rich, Esquire Assistant Attorney General Department of Natural Resources Annapolis, Maryland 21401 Government Publications Section State Library of Pennsylvania Education Building Commonwealth and Walnut Streets Harrisburg, Pennsylvania 17126 M. J. Cooney, Superintendent Generation Division - Nuclear Philadelphia Electric Company 2301 Market Street Philadelphia, Pennsylvania 19101 Edward Greenman U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement Peach Bottom Atomic Power Station P. O. Box 399 Delta, Pennsylvania 17314 Philadelphia Electric Company ATTN: Mr. W. T. Ullrich Peach Bottom Atomic Power Station Delta, Pennsylvania 17314

REQUEST FOR ADDITIONAL INFORMATION FOR

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CONTAINMENT PURGE SYSTEM AND CONTAINMENT VENTING SYSTEM FOR PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3 DOCKET NOS.56-277 AND 50-278 With regard to'the containment purge and venting system, provide the following infonnation:

a.

Discuss the provisions made to ensure that isolation valve closure will not be prevented by debris which could potentially become entrained in the escaping air ~

and steam.

b.

Discuss the provisions made for testing the availability of the isolation function and the leakage rate of the isolation valves, individually, during reactor operation.

c.

Provide an analysis to demonstrate the acceptabi-lity of the pmvisions made to pmtect structures and safety-related equipment, e.g., fans, filters and ductwork, located beyond the purge system isolation valves against loss of function from the environment created by the escaping air and steam.

d.

For the containment purge isolation valves, specify the differential pressure across the valve for which the maximum leak rate occurs.

Provide test results (e.g.,

from vendor tests of leakage rate versus valve differential pressure) which support your conclusion.

1774 209 O