ML20137C371
| ML20137C371 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 03/17/1997 |
| From: | Eric Simpson Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LR-N97135, NUDOCS 9703240234 | |
| Download: ML20137C371 (2) | |
Text
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4 Pubhc Service Electric and Gas Capany E. C. Simpson Public Service Electric and Gas Company P.O. Box 236. Hancocks Bridge, NJ 08038 603-339-1700 l
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MAR 171997 LR-N97135 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 STATUS OF ULTIMATE HEAT SINK ISSUES HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE 11PF-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.
The following information is provided to update the NRC concerning our current plans to resolve these UHS issues.
Since July, 1996, PSE&G has continued the Configuration Baseline Document (CBD) validation of the Station Service Water System
)
(SSWS) and Safety Auxiliaries Cooling System (SACS).
In j
addition, a Service Water System Operational Performance 1
Inspection (SWSOPI) is being conducted as described in PSE&G's letters LR-N96276, dated September 5, 1996, and LR-N96327, dated October 16, 1996.
During these reviews, PSE&G identified various discrepancies, including additional design basis issues that impacted the Technical Specification:
- 1) UHS temperature limits;
- 2) UHS river water level limits; and 3) SSWS and SACS operating configurations.
PSE&G notified the NRC of these issues in Licensee Event Reports 96-015-00 and 96-022-00 (and its supplements).
To address these issues and maintain operability of the UHS, SSWS, and SACS, PSE&G has implemented appropriate 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 5
g functions of these systems can be fulfilled and that the I
consequences of design basis accidents are mitigated.
At this time, PSE&G is continuing to assess these compensatory I
measures to:
- 1) ensure that the associated systems remain capable of performing their safety functions; 2) determine the optimal configurations and limits to support plant operations; 9703240234 970317 PDR ADOCK 05000354-P PDR Printed on AmdM Pgw
MAR 171997 Document Control Desk LR-N97135 and 3) provide suitable justification to support or revise the Hope Creek licensing documents, including a potential amendment to the Technical Specifications.
Resolution of these issues is scheduled to be accomplished by April 30, 1997, including the submittal of license change requests if required.
In addition, PSE&G is scheduled to complete the SWSOPI activities, including a review of SACS, by the end of the second quarter of 1997.
Should you have any questions regarding this request, we will be pleased to discuss them with you.
Sincerely,
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Mr. H. Miller, Administrator - Region I U.
S. Nuclear Regulato7:y 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 l
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