ML20198H804
| ML20198H804 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 12/18/1997 |
| From: | Jaffe D NRC (Affiliation Not Assigned) |
| To: | Eliason L Public Service Enterprise Group |
| Shared Package | |
| ML20198H809 | List: |
| References | |
| TAC-MA0088, TAC-MA88, NUDOCS 9801130400 | |
| Download: ML20198H804 (3) | |
Text
'
,m (Mr. Leon R. Eliason December 18, 1997 Chief Nuclear Officer & President-Nuclear Business Unit i
Public Service Electric & Gas Company Post Office Box 236 Hancocks Bridge, NJ 08038 s
SUBJECT:
CORRECTION OF THE NRC STAFF SAFETY EVALUATION ISSUED IN-SUPPORT 0F' AMENDMENT N0. 63 - HOPE CREEK GENERATING STATION (TAC NO. MA0088)
Dear Mr. E11ason:
By letter dated October 24, 1997, you provided comments concerning an error that appears in an NRC staff s'afety evaluation (SE).
The subject SE was prepared by the NRC staff in support of issuance of Amendment No. 63 to facility Operating License No NPF-57, for Hope Creek Generating Station, and dated January 25, 1994. The error relates to the description of minimum core thermal power and flow conditions that must be achieved under single recirculation loop operating conditions to avoid thermal stratification.
While the NRC staff SE describes these conditions as ".. 38 percent thermal power and 50 percent of rated 12rg flow" (emphasis added), your letter dated October 24, 1997, correctly identifies these conditions as relating to recirculation 1000 flow rather than Istte flow. While the associated Technical Specifications (TS) 3.4.1.1.a.l.g and 4.4.1.1.2 correctly identify the subject condition:, as relating to recirculation 1000 flow, the SE was incorrect.
Based upon the above, the NRC staff concludes that, while the SE issued in support of Amendment No. 63 contained the above described error, the error did not affect the subject TS. Accordingly, with the correction noted above, the NRC staff SE is acceptable and na additional changes to the TS are needed.
Revised SE pages, with the subject change noted by a marginal change indicator, are enclosed herein.
Sincerely,
/S/
David H. Jaffe, Senior Project Manager Project Directorate I-2 Division of Reactor Projects - I/II Docket No. 50-354
Enclosure:
Revised Safety Evaluation Pages cc w/ enc 1:
See next page pg DISTRIBUTION:
TLC 1 ark GHil's (2)
Docket File DJaffe rT T { 3 PUBLIC OGC
-P01-2 r/f ACRS
\\
BBoger JLinville, RI i
- JStolz TCollins
- SEE PREVIOUS CONCURRENCE 0FFICE POI-2/PMs PDI-3/thi SRXB/BC*
OGC*
PDI-2/2[
NAME DJaffeic'wI TLC M D TCollins RBachmann JStolz k
~
DATE b/li97 (h/h/97 12/03/97 12/8/97 it /l7/97
/
0FFICIAL RECORD COPY DOCUMENT NAME: MA0088.00R ll lll lllll 'IlIlll l l lel H F Hlh II I 9801130400 971218 PDR ADOCK 05000354
.P PDR
i pant
.k UNITED STATES y*
}
NUCLEAR REGULATORY COMMISSION t
WASHINGTON, D.C. 30666-4001 December 18, 1997 Mr. Leon R. E11ason Chief Nuclear Officer & President-Nuclear Business Unit Public Service Electric & Gas Company Post Office Box 236 Hancocks Bridge, NJ 08038
SUBJECT:
CORRECTION OF INE NRC STAFF SAFETY EVALUATION ISSUED IN SUPPORT OF AMEN 0 MENT NO. 63 - HOPE CREEK GENERATING STATION (TAC NO. MA0088)
Dear Mr. Elisson:
By letter dated October 24, 1997, you provided comments concerning an error that appears in an NRC staff safety evaluation (SE). The subject SE was
)repared by the NRC staff in support of issuance of Amendment No. 63 to acility Operating License No. NPF-57, for Hope Creek Generating Station, and r
dated January 25, 1994.
The error relates to the description of minimum core thermal power and flow conditions that must be achieved under single recirculation loop operating conditions to avoid thermal stratification.
While the NRC staff SE describes these conditions as ".. 38 percent thermal power and 50 percent of rated rang flow" (emphasis added), your letter dated October 24, 1997, correctly identifies these conditions as relating to recirculation 1000 flow rather than rang flow. While the associated Technical Specifications (TS) 3.4.1.1.a.l.g and 4.4.1.1.2 correctly identify the subject conditions as relating to recirculation lqan flow, the SE was incorrect.
Based upon the above, the NRC staff concludes that, while the SE issued in support of Amendment No. 63 contained the above described error, the error did not affect the subject TS, Accordingly, with the correction noted above, the NRC staff SE is acceptable and no additional changes to the TS are needed.
Revised SE pages, with the subject change noted by a marginal change indicator, are enclosed herein.
Sincerely, h
\\
k k\\
Daiid'H. Jaffe, Serlior Project Manager Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket No. 50-354
Enclosure:
Revised Safety Evaluation Pages cc w/ encl: See next page l
j
Mr. Leon R. Eliason Hope Creek Generating Station Public Service Electric & Gas Company cc:
Jeffrie J. Keenan, Esquire Manager - Joint Generation Nuclear Business Unit - N21 Atlantic Energy P.O. Box 236 6801 Black Horse Pike Hancocks Bridge, NJ 08038 Egg Harbor Twp., NJ 08234-4130 Hope Creek Resident Inspector Richard Hartung U.S. Nuclear Regulatory Commission Electric Service Evaluation Drawer 0509 Board of Regulatory Commissioners Hancocks Bridge, NJ 08038 2' Gateway Center, Tenth Floor Newark, NJ 07102 Mr. Louis Storz Sr. Vice President - Nuclear Operations Lower Alloways Creek Township Nuclear Department c/o Mary O. Henderson, Clerk P.O. Box 236 Municipal Building, P.O. Box 157 Hancocks Bridge, NJ 08030 Hancocks Bridge, NJ 08038 General Manager - Hope Cree Operations Mr. Elbert Simpson Hope Creek Generating Statioc Senior Vice President-P.O. Box 236 Nuclear Engineering Hancocks Bridge, NJ 08038 Nuclear Department P.O. Box 236 Manager - Licensing and Regulation Hancocks Bridge, NJ 08038 Nuclear Business Unit - N21 P.O. Box 236 Hancocks Bridge, NJ 08038 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Dr. Jill Lipoti, Asst. Director Radiation Protection Programs NJ Department of Environmental Protection and Energy CN 415 Trenton, NJ 08625-0415 L
T
- v