ML18101A924
| ML18101A924 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 08/18/1995 |
| From: | Jamie Benjamin Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LR-N95128, NUDOCS 9508280092 | |
| Download: ML18101A924 (3) | |
Text
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- ps~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit AUG 181995 LR-N95128 LCR 94-45 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
REQUEST FOR ADDITIONAL INFORMATION SALEM GENERATING STATION UNIT NOS. 1 AND 2 FACILITY OPERATING LICENSE NOS. DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 This letter transmits our response to your request for additional information regarding License Change Request (LCR) 94-45.
In our original submittal (our ref. LR-N94216 dated March 30, 1995),
Public Service Electric and Gas (PSE&G) submitted a proposed change to the Salem Unit 1 and 2 Technical Specifications (TS).
This proposed change eliminated the term CONTROLLED LEAKAGE, created a new Seal Injection Limiting Condition for Operation (LCO), and modified the definition for IDENTIFIED and UNIDENTIFIED LEAKAGE.
The proposed LCO contained an Action Statement (AS) that read:
"With seal injection flow not within the limit, adjust manual seal injection throttle valves to give a flow within the charging pump discharge pressure 2430 psig and the charging flow control valve fully open within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />."
The proposed AS should be changed to read:
"With seal injection flow not within the limit, adjust manual seal injection throttle valves to give a flow within the charging pump discharge pressure 2430 psig and the' charging flow control valve fully open within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />."
9508280092 950818
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PDR ADDCK 05000272 P
PDR The power is in your hands.
95-2168 REV. 6/94
t Document Control Desk LR-N95128 AUG 181995 Because of misinterpretation of the Westinghouse Standard Technical Specification (NUREG 1431, Rev O), we originally requested 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to HOT SHUTDOWN (an additional 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />),
instead of the suggested 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
Additionally, from the proposed definitions of IDENTIFIED LEAKAGE and UNIDENTIFIED LEAKAGE, as shown in marked-up pages, the phrase 11 *** or seal leak off" should be deleted.
The revised definitions should read as follows:
IDENTIFIED LEAKAGE shall be:
- a. Leakage (except Reactor Coolant Pump Seal Water Injection) into closed systems, such as pump seal or valve packing leaks that are captured and conducted to a sump or collecting tank, or
- b. Leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be PRESSURE BOUNDARY LEAKAGE, OR
- c. Reactor coolant system leakage through a steam generator to the secondary system.
UNIDENTIFIED LEAKAGE UNIDENTIFIED LEAKAGE shall be all leakage (except Reactor Coolant Pump Seal Water Injection) which is not IDENTIFIED LEAKAGE.
These changes will make PSE&G's proposed Technical Specification change consistent with the Westinghouse Standard Technical Specification (NUREG 1431, Rev O and Rev 1).
Should you have any additional questions, please do not hesitate to contact me.
Sincerely, Review
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Document Control Desk LR-N95128 C Mr. L. Olshan, Licensing Project Manager U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 14E21 Rockville, MD 20852 Mr. c. s. Marschall (S09)
USNRC Senior Resident Inspector Mr. T. T. Martin, Administrator - Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. Kent Tosch, Manager, VI AUG 18 1995 New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625