ML20138G976
| ML20138G976 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 04/30/1997 |
| From: | Eric Simpson Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LR-N97276, NUDOCS 9705070028 | |
| Download: ML20138G976 (2) | |
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I Public Service APR 3 01997 Electric and Gas Cornpany E. C. Simpson Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1700 SenicVice President Nuclear Engineering LR-N97276
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United States Nuclear Regulatory Commission Document Control Desk l
Washington, DC 20555 STATUS OF ULTIMATE HEAT SINK ISSUES HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NPF-57 DOCKET NO. 50-354 Gentlemen:
On July 18, 1996, Public Service Electric & Gas (PSE&G) met with NRC representatives at a public meeting to discuss issues related to the Hope Creek ultimate heat sink (UHS) and its interfacing systems.
At that meeting, PSE&G provided plans for resolution of the UHS issues known at that time.
On March 17, 1997, via letter j
LR-N97135, PSE&G provided an update on the status of Hope Creek's resolution of these UHS issues.
This letter revises the status of those activities.
Since March 17, 1997, PSE&G has continued reviewing Station Service Water System (SSWS) and Safety Auxiliaries Cooling Systeitt (SACS) design basis information to validate UHS temperature calculations that will be used to support a change to the Technical Specifications.
However, validation of the SSWS and SACS design basis information has impacted the schedule for submittal of the UHS Technical Specification change described in PSE&G's March 17th letter.
PSE&G anticipates that validation of SSWS and SACS design basis information and submittal of the required UHS Technical Specification change will be completed on or before May 31, 1997.
To maintain operability of the UHS, SSWS, and SACS, PSE&G has implemented appropriately conservative compensatory measures (including limits on UHS temperature and river water level) in accordance with Hope Creek's Corrective Action Program.
These actions ensure that the safety related functions of these systems can be fulfilled and that the consequences of design basis accidents are mitigated.
These compensatory measures will remain in place until NRC approval of the required Technical Specification changes is obtained.
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9705070028 970430 l
PDR ADOCK 05000354 s
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APR 3 01997 Document Control Desk..R-N97 2 7 6 Should you have any questions regarding this request, we will be pleased to discuss them with you.
Sincerely,
\\J C
Mr. H. Miller, Administrator - Region I U.
S.
Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr.
D.
Jaffe, Licensing Project Manager - HC U.
S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 14E21 Rockville, MD 20852 Mr.
R.
Summers (X24)
USNRC Senior Resident Inspector - HC Mr.
K.
Tosch, Manager IV Bureau of Nuclear Engineering 33 Arctic Parkway CN 415 Trenton, NJ 08625 95-4033