ML18100A863
| ML18100A863 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 02/01/1994 |
| From: | Hagan J Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML18100A864 | List: |
| References | |
| LCR-92-14, NLR-N94006, NUDOCS 9402150268 | |
| Download: ML18100A863 (2) | |
Text
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Public Service Electric and Gas Company Joseph J. Hagan Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1200 Vice President - Nuclear Operations FEBO 11994 NLR-N94006 LCR 92-14 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
REQUEST FOR AMENDMENT SUPPLEMENTAL INFORMATION SALEM GENERATING STATION UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 By letter dated December 2, 1993, the NRC provided Public Service Electric & Gas Company (PSE&G) with a draft safety evaluation for the approval to delete the steamflow/feedflow mismatch and low steam generator water level reactor trip.
Because the license change request submittal contained Westinghouse proprietary information, PSE&G was requested to review and to have Westinghouse review the draft safety evaluation to identify any proprietary information.
PSE&G has reviewed the draft safety evaluation and identified no Westinghouse proprietary information.
By letter dated January 12, 1994 (ref PSE-ADFCS-94-001), Westinghouse notified PSE&G that the draft safety evaluation contained no proprietary information.
Two minor comments on page 4 of the draft safety evaluation have been identified.
First, in the first paragraph, first sentence, the Westinghouse Model 131-110 isolation amplifiers are being replaced with NUS Model FCA801 isolation amplifiers.
- Also, approximately in the middle of the page, in third paragraph, the third sentence states, "In case both primary and backup computer fail, the FW valve-control demand signal will be reduced to zero."
The sentence should read, "In case both primary and backup computer fail, the FW valve-control-demand indication signal will be reduced to zero."
r--9402150268 940201
. PDR ADOCK 05000272 P
c.. Doctiiilent Control Desk
~LR-N94006 2
FEB 0 11994 In the event of a loss of both the primary and backup computers, the FW valve-control-demand indication will go to zero and not the demand to the valve itself.
This information was provided to Mr. R. Skokowski, NRC Region I by telecon during discussion of the loss of f eedwater control computers event that occurred at the Catawba Nuclear Station. contains a marked up page 4 from the draft safety evaluation with the previously described changes in pen and ink.
Should there be any questions with regard to this submittal, please do not hesitate to contact us.
c Mr. J. c. stone Licensing Project Manager Mr. c. Marschall Senior Resident Inspector Sincerely, Mr. T. Martin, Administrator Region I Mr. Kent Tosch, Manager IV New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625