ML20236U605
| ML20236U605 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 07/23/1998 |
| From: | Richard Ennis NRC (Affiliation Not Assigned) |
| To: | Keiser H Public Service Enterprise Group |
| References | |
| GL-88-20, TAC-M83630, NUDOCS 9807300340 | |
| Download: ML20236U605 (4) | |
Text
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July.23, 1998 Mr. Harold W. Kaiser Chief Nuclear Officer & President Nuclear Business Unit Public Service Electric & Gas Company Post Office Box 236 Hancocks Bridge, NJ 08038
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE INDIVIDUAL PLANT EXAMINATION OF EXTERNAL EVENTS (IPEEE) SUBMITTAL FOR HOPE CREEK GENERATING STATION (TAC NO. M83630)
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D.ar ur. Kais.r:
j Generic Letter (GL) 88 20, Supplement 4, " Individual Plant Examination of Extemal Events (IPEEE) for Severe Accident Vulnerabilities," issued by the NRC on June 28,1991, requested licensees to perform an IPEEE for plant-specific severs accident vulnerabilities and to submit the results to the NRC pursuant to 10 CFR 50.54(f). Public Service Electric and Gas Company (PSE&G) provided its response for Hope Creek Generating Station in letter LR-N970380, dated July 31,1997.
Based on our ongoing review of the Hope Creek IPEEE submittal, the NRC staff has developed the enclosed request for additional information (RAl) related to the seismic analysis in the IPEEE.
There are no RAls in the fire or high winds, flood, and other extemal events in the IPEEE. The RAls in the seismic area were developed by our contractor, Brookhaven National Laboratory and were reviewed by the " Senior Review Board"(SRB). The SRB is comprised of NRC Office of Nuclear Regulatory Research (RES) and Office of Nuclear Reactor Regulation (NRR) staff and RES consultants (Sandia National Laboratories) with probabilistic risk assessment expertise in extemai events.
We request that the additionalinformation be provided within 60 days of mceipt of this letter, if you have any questions, please contact me at (301) 415-1420.
f Sincerely,
/S/
Richard B. Ennis, Acting Project Manager
[O Project Directorate 1-2 Division of Reactor Projects-I/11 Office of Nuclear Reactor Regulation i
Docket No. 50-354
Enclosure:
Request for AdditionalInformation gy s
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July 23,1998 i
Mr. Harold W. Keiser t
Chief Nuclear Officer & President Nuclear Business tJnit Pi.blic Service Electric & Gas C>mpany Post Off,ce Box 236 Hancocks Bridge, NJ 08038
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REl.ATED TO THE INDIVIDUAL PLANT EXAMINATION OF EXTERNAL EVENTS (IPEEE) SUBMITTAL FOR HOPE CREEK GENERATING STATION (TAC NO. M83630)
Dear Mr. Keiser:
Generic Letter (GL) 88-20, Supplement 4, " Individual Plant Examination of Extemal Events (IPEEE) for Severe Accident Vulnerabilities," issued by the NRC on June 28,1991, requested licensees to perform an IPEEE for plant-specific severe accident vulnerabilities and to submit the results to the NRC pursuant to 10 CFR 50.54(f). Pub!ic Service Electric and Gas Company (PSE&G) provided its response for Hope Creek Generating Station in letter LR-N970380, dated July 31,1997.
Based on our ongoing review of the Hope Creek IPEEE submittal, the NRC staff has developed the enclosed request for additional information (RAl) related to the seismic analysis in the IPEEE.
There are no RAls in the fire or high winds, flood, and other extemal events in the IPEEE. The RAls in the seismic area were developed by our contractor, Brookhaven National Laboratory and were reviewed by the " Senior Review Board" (SRB). The SRB is comprised of NRC Office of Nuclear Regulatory Research (RES) and Office of Nuclear Reactor Regulation (NRR) staff and RES consultants (Sandia National Laboratories) with probabilistic risk assessment expertise in extemal events.
We request that the additional information be provided within 60 days of receipt of this letter, if you have any questions, please contact me at (301) 415-1420.
Sincerely, Richard B. Ennis, Acting Project Manager Project Directorate 1-2 Division of Reactor Projects - t/11 Office of Nuclear Reactor Regulation Docket No. 50-354 l
Enclosure:
Request for AdditionalInformation I
cc w/ encl: See next page
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Mr. Harold W. Keiser 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 l
Hope Creek Resident inspector Richard Hartung U.S. Nuclear Regulatory Commission Electric Service Evaluation l
Drawer 050g Board of Regulatory Commissioners Hancocks Bridge, NJ 08038 2 Gateway Center, Tenth Floor Newark, NJ 07102 Mr. Louis Storz i
Sr. Vice President - Nuclear Operations Lower Alloways Creek Township l
i Nuclear Department c/o Mary O. Henderson, Clerk P.O. Box 236 Municipal Building, P.O. Box 157 Hancocks Bridge, NJ 08038 Hancocks Bridge, NJ 08038 General Manager - Hope Creek Operations Mr. Elbert Simpson Hope Creek Generating Station Senior Vme 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 i
P.O. Box 236 i
Hancocks Bridge, NJ 08038 l
Regional Administrator, Region i U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 1g406 Dr. Jill Lipoti, Asst. Director Radiation Protection Programs NJ Department of Environmental Protection and Energy CN 415 Trenton, NJ 08625-0415 l
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.o l 4 REQUEST FOR ADDITIONAL INFORMATION HOPE CREEK IPEEE A.
Seismic 1.
According to Figure 3-10 of the subrnittal, the lateral spreading due to liquefaction of slopes becomes significantly large at a peak acceleration of about 0.35g. However, all the buried pipes, such as the service water (SW) piping, appear to be screened out.
Please explain why the lateral spreading did not affect the fragility of buriedpiping.
2.
In the submittal, detailed calculation procedures of component fragilities are not provided.
To allow completion of this twview, please provide the detailed calculations and results for the following components:
Relay GEPVD21 for4kV buses (HCLPP>0.56 1E 120V Dist. Panels 1AJ481 (median =1.086 and 1AJ482 (median =1.03g i
j 250VDC MCC 100251 (medianm0.73g).
Condensate Storage Tank (medianmC 956 3.
In Section 3.1.5.4.3 of the submittal, it is stated that "The LRR (low ruggedness relays]
have seismic capacity greater than the review level earthquake (HCLPF>0.3g)."
Please provide the detailed fragility calculation results confirming this conclusion.
4.
In Table 3-4 of the submittal, identification numbers are given for " notes" for components which were screened in as a result of seismic walkdowns. However, the " notes" themselves are not described in the submittal.
Please provide the notes assocInted with the identification numbers.
B.
Fire l
There are no RAls in this area.
C.
High winds, flood, and other external events There are no RAls in this area.
ENCLOSURE
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