ML18101A780
| ML18101A780 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 06/12/1995 |
| From: | Tosch K NEW JERSEY, STATE OF |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9506200210 | |
| Download: ML18101A780 (2) | |
Text
Christine Todd Whitman Governor
- ~tau of ~efn Werse~
Department of Environmental Protec~ion Division of Environmental Safety, Health, and Analytical Programs.
. Radiation Protection Programs Bureau of Nuclear Engineering CN 415 Trenton, New Jersey 08625-0415 June 12, 1994 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 To Whom It May Concern:.
Subject:
Salem Generating Station Docket Nos. *50-272 * & 50-311 Amendment* to *Facility Operating License License Change Request 94-45 Robert C. Shinn, Jr.
Commissioner The subject*reqliest was submitted to the NRC by PSE&G letter dated March 30, 1995.
The request proposes t:o modify Se<?tions 3/4.5.4, 3.*4.6.2, 4.4.6.2, 3/4.4.6.2, 3.4.7.2 of the Salem Units 1 and 2 Technical Specifications to eliminate the defined term Controlled Leakage to remove Controlled Leakage flow from the Reactor Coolant System Operational Leakage Limiting Condition for*
Operation *(LCO), and to establish a new Seal Injection Flow LCO.
The New Jersey Department of Environmental Protection's Bureau of Nuclear Engineering (BNE) has reviewed the request in acco~dance with the requirements of 10 CFR 50.91 (b).
NRC Inspection Report Nos. 50-272/94-19 and 50-311/94-19, Regulatory Guide 1.45, NRC Information Notice 94-46, and.NUREG-1431 were reviewed and compared to this License Change Request~
Plant specific procedures and installed.flow instrumentation were discussed with PSE&G personnel.
The intent of R G 1. 45, *for early Reactor Coolant System leak detection before the leak becomes a LOCA, is not impacted by.this amendment.
The safety significance of this issue is that by not having appropriate techn'ical specification surveillance requirements, the license~ could operate in a c~ndition that is beyond the plant design basis JECCS assumptions and not detect it during the surveillance test.
Based on the review of. the above *documents, requirements of *the Salem procedures and instrumentation, and discussions with.. PSE&G personnel, the. State* of New Jersey has determined that this change has a positive. impact to plant safety.
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9506200210 950612
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PDR ADOCK 05000272 P
PDR New Jersey is an Equal Opportunity Employer Recycled Paper
The RCP seal leak-off flow is a normal function of the plant systems and should not be classified -as leakage since the term is generally intended to indicate unwanted or abnormal loss of reactor coolant which is a precursor to a Loss 9f Coolant Accident.
It is clear that this amendment will contribute to ensuring that maximum flow from the charging pump will be available in the event of a LOCA arid the ECCS injectio.n function is initiated.
If you have any questions, please contact Dave Vann.at (.609) 987-2033 or Rich Pinney at (609) 987-2086.
c:
Jill Lipoti N.J. DEP D. Zannoni N.J. DEP D. Chawaga sincerely,
~~d--
Kent W. Tosch, Manager
_Bureau of Nuclear Engiheeririg NRC Region I State Liaison Officer
- c. Marschall NRC Sr. Resident Inspector_
L. Olshan NRC Project Manager F. Thomson PSE&G