ML18102A334
| ML18102A334 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 08/19/1996 |
| From: | Dawn Powell Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LR-N96248, NUDOCS 9608270237 | |
| Download: ML18102A334 (2) | |
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PS~G P'i'.iblic.S~vice~Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit AUG 191996 LR-N96248 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 REQUEST FOR ADDITIONAL INFORMATION CONTAINMENT DESIGN TEMPERATURE SALEM GENERATING STATION NOS. 1 AND 2 FACILITY OPERATING LICENSES DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 Gentlemen:
By letter LR-N96126, dated June 18, 1996, Public Service Electric
& Gas Company (PSE&G) submitted a request to amend Technical Specification (TS) Section 5.2.2 pertaining to Salem Generating Station's design air temperature for the containment structure.
This letter provides a clarification to that request.
Specifically, the requested change added the peak temperature resulting from a Main steamline Break (MSLB) into the TS along with the currently specified temperature resulting from a Loss of Coolant Accident.
Pertinent descriptions in the Updated Final Safety Analysis Report (UFSAR) of the containment liner design and MSLB parameters are contained in Sections 3.8.1, Containment Structure, and 15.4.8.2, Mass and Energy Release to Containment Following a Steamline Rupture, including Figure 15.4~100.
In the June 18, 1996 submittal, PSE&G stated that the increase of approximately one degree (350°F to 351.3°F) in the calculated maximum temperature during a MSLB is not considered to have a significant impact on the environmental qualification of equipment.
In the review of the requested change, it was unclear to the Staff if the components within the containment had been reviewed against the higher temperature, albeit small in magnitude.
PSE&G had reviewed and documented the revised MSLB containment temperature and pressure profiles for impact on the environmental qualification of safety related equipment inside containment.
The review.of the revised temperature profiles against vendor equipment qualification data supported the qualified status of the equipment and demonstrated that the operability of the 9608270237 960819 ----------,
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Document Control Desk L"R-NfJ~24'B.
AUG 1 9 1996 2
equipment would not be jeopardized by the increase in containment temperatures.
Should you have any questions regarding the evaluation performed or any other part of the requested change, we will be pleased to discuss them with you.
Sincerely, D. R. Powell Manager -
Licensing & Regulation C
Mr. Hubert J. Miller, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. L. Olshan, Licensing Project Manager -
Salem
- u. s. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 14E21 Rockville, MD 20852 Mr. c. Marschall (X24)
USNRC Senior Resident Inspector Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering 33 Arctic Parkway CN 415 Trenton, NJ 08625