ML18092A269
| ML18092A269 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 08/31/1984 |
| From: | Liden E Public Service Enterprise Group |
| To: | Varga A Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8409110189 | |
| Download: ML18092A269 (2) | |
Text
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Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Nuclear Department August 31, 1984 Director of Nuclear Reactor Regulation u.s. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20014 Attention:
Mr. Steven A. Varga, Chief Operating Reactors Branch, No. 1
Dear Mr. Varga:
REQUEST FOR ADDITIONAL INFORMATION RELATED TO ASYMMETRIC LOCA LOADS SUBMITTAL SALEM GENERATING STATION UNIT NO. l DOCKET NO. 50-272 In your letter dated May 21, 1984, you requested additional information regarding the plant-specific asymmetric LOCA loads analysis for Salem Unit 1.
The PSE&G report, "Evaluation of the Reactor Coolant System Considering Subcompartment Pressurization Following a LOCA for Salem Units 1 and 2," was submitted to the staff on March 6, 1979 and revised on March 29, 1979.
The results of this analysis were approved in Supplement No. 4 to the Safety Evaluation Report (Section 3.9.1) dated April 18, 1980.
Although the approval contained in Supplement No. 4 to the SER applied specifically to Salem Unit 2, the analysis submitted was common to both Units 1 and 2.
Clarification is therefore requested regarding the reason for the request for additional information on the Unit 1 analysis since this issue has previously been resolved for Unit 2.
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The Energy People 95-2168 (25M) 6-84
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Mr. Steven 8/31/84 PSE&G has contacted Westinghouse regarding the Unit 1 information requested in your letter.
Preliminary indications from Westinghouse are that this information is not readily available and would require several man-months of work on their part.
The alternate approach contained in Generic Letter 84-04, dated February 1, 1984, "Safety Evaluation of Westinghouse Topical Reports Dealing with Eliminating of Postulated Pipe Breaks in PWR Primary Main Loops" has also been discussed with Westinghouse.
This alternative, which would eliminate postulation of asymmetric loads from design basis LOCA's, would require six months after a decision is made.
PSE&G is currently awaiting further information from Westinghouse regarding these alternate approaches and will keep you informed of future developments.
Should you have any questions, please do not hesitate to contact us.
C Mr. Donald c. Fischer Licensing Project Manager Mr. James Linville Senior Resident Inspector Sincerely, E. A. Liden Manager -
Nuclear Licensing and Regulation
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