ML19210C547

Forwards Request for Addl Info to Complete Review of Unlimited Purging at Facility

ML19210C547
Person / Time
Site:	Maine Yankee
Issue date:	10/30/1979
From:	Lainas G Office of Nuclear Reactor Regulation
To:	Reid R Office of Nuclear Reactor Regulation
References
NUDOCS 7911190071
Download: ML19210C547 (3)

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VVASHINGTON, D. C. 20555 a\\v,/

OCT 3 01979 MEMDRANDUM FOR:

R. Reid, Chief Operating Reactors Branch #3 Division of Operating Reactors FROM:

G. Lainas, Chief Plant Systems Branch Division of Operating Reactors

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION - CONTAINMENT PUP.GE SYSTEM - MAINE YANKEE ATOMIC POWER PtANT (TAC 10215)

REFERENCE:

1.

Letter to R. Reid from W. Johnson, " Containment Purging During Nomal P1 ant Operation," dated Decerrber 29, 1978 2.

Letter to A. Schwencer from E. Wood, dated May 14, 1979 Plant Name: Maine Yankee Atomic Power Plant Docket No. : 50-309 Project Manager:

M. Fairtile Review Status: Awaiting Infomation With regard to the containment purge and vent system at Maine Yankee Atomic Pcwer Plant, the licensee plans to justify unlimited purging (Reference 1). The Plant Systems Branch, Section B, after di::cussions with the licensee (telecon J. Kerrigan and R. Turcott, October 19, 1979), has prepared the enclosed request for additional information.

Section A is continuing their review and will provide questions regarding the electrical and instrurrentation aspects of containment purging in January 1980.

1. G. Lainas, Chief Plant Systems Branch Division of Operating Reactors

Enclosure:

As stated Contacts:

1351 052 J. Kerrigan, X28129 cc: See next page 7911190 0 7 /

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9 00I O0 073 R. Reid cc w/ enclosure:

D. Eisenhut B. Grimes W. Gamill L. Nichols G. Lainas E. Reeves E. Adensam M. Fairtile D. Tondi D. Shum J. Kerrigan J. T. Beard G. Knighton V. Noonas.

F. Yitt J. Zudans R. Scholl 1354 053

ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION FOR CONTAINMENT PURGE SYSTEM AND CONTAINMENT VENTING SYSTEM FOR MAINE YANKEE ATOMIC POWER PLAaT DOCKET NO. 50-309 1.

Provide a schematic drawing of your containment purge and vent system.

2.

With regard to the containment purge and venting system, provide the following information:

a.

Discuss the provisions made to ensure that isolation valve closure will not be prevented by debris which could poten-tially 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 acceptability of the provisions made to protection structures and safety-related equipment; e.g., fans, filters, and duct'vork, located beyond the purge system isolation valve 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 the above data.

3.

As discussed with your staff (telecon J. Kerrigan and R. Turcott, 10/19/79), the following information should also be provided:

a.

Provide an analysis of the reduction in the containment pressure resulting from the partial loss of containment atmosphere during the accident for ECCS backpressure deter-mination.

b.

Quantify the amount of containment atmosphere released through the purge and vent isolation valves during the maximum closure tme allowed in your Technical Specifications.

1354 054

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