ML20063A878

Confirms Info Previously Provided by Util During 931208 Telcon Re LCR 93-05 Concerning Ultimate Heat Sink Temp Changes

ML20063A878
Person / Time
Site:	Hope Creek
Issue date:	01/13/1994
From:	Hagan J Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NLR-N93202, NUDOCS 9401270123
Download: ML20063A878 (4)

Text

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• i Pubhc Service Dectric and Gas Company Joseph J. Hagan Pubhc Service Electnc and Gas Company P.O. Box 236 Hancocks Bndge, NJ 08038 609 339-1200 Vice Presg1ent - Nuclear Operations

'JANIS 1994 NLR-N93202 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

DECEMBER 8, 1993 TELECONFERENCE LICENSE CHANGE REQUEST 93-05 ULTIMATE HEAT SINK TEMPERATURE CHANGES l HOPE CREEK GENERATING STATION i

FACILITY OPERATING LICENSE NPF-57 DOCKET NO. 50-354 l The purpose of this letter is to confirm the information previously provided by PSE&G during a December 8,.1993 teleconference concerning License Change Request (LCR) 93-05, Ultimate Heat Sink Temperature Changes. Attachment 1 of this l letter provides a list of those NRC questions and PSE&G responses i requiring confirmation via this letter. Please note that this 4 l

submittal does not change LCR 93-05 nor modify any of the conclusions stated in the Significant Hazards Consideration Evaluation previously submitted.

A copy of the this letter has been sent to the State of New Jersey.

' l Should you have any questions or comments on this transmittal, do not hesitate to contact us.

l Sincere y,- )

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'JAN131994 Document Control Desk NLR-N93202 Affidavit Attachment C Mr. T. T. Martin, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. J. C. Stone, Licensing Project Manager U. S. Nuclear Regulatory Commission one White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. C. S. Marschall (SO9)

USNRC Senior Resident Inspector Mr. K. Tosch, Manager IV NJ Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 1

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JAN 131994 REF: NLR-N93202 STATE OF NEW JERSEY )

) SS.

COUNTY OF SALEM )

J. J. Hagan, being duly sworn according to law deposes and says:

I am Vice President - Nuclear Operations of Public Service Electric and Gas Company, and as such, I find the matters set forth in the above referenced letter, concerning the Hope Creek Generating Station, are true to the best of my knowledge, information and belief.

Subscribed and Sworn to before me this /3 db day of violl/nt< ,

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botaryPubli of New Jersey KIMBERLY JO BROWN NOTARY PUBUC 0F NEW JERSEY My Commission expires on u, cnm,,a,,;nn rrnhes April 21,1998

ATTACIIMENT 1 DECEMBER 8, 1993 TELECONFERENCE QUESTIONS CONCERNING LICENSE CIIANGE REQUEST 93-05, ULTIMATE HEAT SINK TEMPERATURE CHANGES HOPE CREEK GENERATING STATION NLR-N93202 FACILITY OPERATING LICENSE NPF-57 DOCKET NO. 50-354 NRC OUESTION 1:

What is the basis for the 88.6*F and 89.9'F temperature limits established in PSE&G's letter NLR-N93169, dated November 10, 1993?

PSE&G RESPONSE:

As stated in letter NLR-N93169, the 88.6*F and 89.9'F are the ultimate heat sink temperature limits that would enable the plant to safely complete normal shutdown procedures with two or three Station Service Water System (SSWS) and Safety Auxiliaries Cooling System (SACS) pumps operating respectively. The basis, and limiting factor, used for the calculation of these temperature limits was the maintaining of SACS temperature below l 95'F throughout the normal shutdown period. Since failure analysis of individual pieces of equipment due to elevated SACS temperature was not being conducted, the more conservative 95'F  :

design temperature of the SALS was used to calculate the ultimate l heat sink temperature limits.

NRC OUESTION 2:

The PSE&G letter, NLR-N92065, dated August 4, 1992, provided a technical basis for the 88.1*F administrative limit in effect at that time. As part of that technical basis, PSE&G stated that operator actions would be taken if, in the event of a loss of offsite power, there were only one SSWS/ SACS loop available and river water temperature was between 85'F and 88.1*F. One of these operator actions was the isolation of SACS loop flow to the  !

l Fuel Pool Heat Exchangers. In establishing the new Technical Specification ultimate heat sink temperature limits, is SACS loop flow to the Fuel Pool Heat Exchangers isolated under similar conditions?

PSE&G RESPONSE:

The new ultimate heat sink temperature limits proposed in the LCR do not require, nor take credit for, plant operator actions to isolate SACS flow to the Fuel Pool Heat Exchangers under these conditions. PSE&G concluded that reducing the amount of required operator actions in the post loss of offsite power scenario, as well as maintaining fuel pool cooling in this situation, provides greater operational benefit with minimal impact on SACS operation.

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