ML20217A080
| ML20217A080 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 09/07/1997 |
| From: | Tosch K NEW JERSEY, STATE OF |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9709190064 | |
| Download: ML20217A080 (2) | |
Text
_ _ _ _. _
t w.
i f*inte of hiriu 3crecu Christine Todd Whitman Department of Environmental Protection Robert C. Shinn, Jr.
Governor Commissiones Division of Environmental Safety, Health, and Analytical Programs Radiation Protection Programs Bureau of Nuclear Engineering P. O. Box 415 Trenton, NJ 08625-0415 Tel: (609) 987-2032 Fax: (609) 987-6354 September 7, 1997 U.S. Naclear Regulatory Commission Document Control Desk Washington, D.C.
20555 Ladies & Gentlemen:
s
SUBJECT:
Hope Creek Generating Station (HC)
Facility Operating Licenses NPF-57, Docket No. 50-354 Technical Specification (TS) Change Request (LCR H97-02)
Ultimate Heat Sink and River Wat6r Level Limits On May 19, 1997, Public Service Electric & Gas Company (PSE&G) submitted to the U.S.
Nuclear Regulatory Commission (NRC) the subject request for a change to the HC operating license.
Specifically, via LCR H97-02, PSE&G seeks revisions to the TSs, Bases, and the Updated Final Safety Analysis Report (UFSAR) tor HC.
According to the licensee, the proposed changes resulted from various evaluations, spanning over several years, of the SSWS, its sub-systems, and their interfaces and are intended to: (1) more clearly define the licensing basis for the HC Ultimate Heat Sink (UHS) and its supported systems, (2) improve the consistency between the TS requirements and plant design changes, and (3) allow for required corrective actions.
Among the proposed additions to the TSs, are appropriate Limiting Condition of Operation (LCO) and ACTION Statements for UHS.
Also calculated, were new limits for river water level and temperature to maintain the capability of the UHS to mitigate the consequences of combinations of design basis accidents.
The New Jersey Department of Environmental Protection (NJ DEP)
Bureau of Nuclear Engineering (BNE) has reviewed the change request hCO{jO in accordance with the requirements of 10 CFR 50.91(b) and has the following comment:
PDR ADOCK 050003S4 bjkkk1j. g}(({i((I((}l\\\\{
9709190064 970907
?
P PDR 9
Nmimey a an Equa!opporturuer Eznetoyer 3p3paat,vA~
secyant r.per
.s,
' In the proposed revisions, PSE&G removed a discussion in the Bases (3/4.7.1 Paragraph 2 Page B 3/4 7-1), on the function and actions relating to the heat removal capabilities of the SSWS and its safety-related sub-systems.
By contrast, NUREG 1433-Rev. 1 (4/7/95) " Standard Technical Specifications, General Electric Plants, BWR/4" in Section B.3.7, covers the background, applicable safety analyses, and other issues for this plant cooling water system.
The 9?oposed Bases in LCR H97-02 do not adequately describe the med or the content of the technical specifications for ultimate heat sink and river water levels.
If you have any questions, please contact Richard Pinney at (609) 984-7550.
Sincerely, YQ
/w Kent Tosch, Manager Bureau of Nuclear Engineering c:
H. Miller, Administrator - Region I U.S. NRC D. Jaffe, Licensing Project Manager - HC U.S. NRC S. Morris, Senior Resident Inspector - HC U.S. NRC J.
Lipoti, PhD., Assistant Director - RPP NJ DEP D. Powell, Manager Licensing and Regulation PSE&G
_ - _ -