ML20069H915

Provides Listed Addl Clarification Re Inside Diameter Fluence Levels at Eol & 1/4T Fluence Levels at Eol Contained in NRC Reactor Vessel Integrity Database,Per 940520 Telcon Concerning Generic Ltr 92-01,Rev 1

ML20069H915
Person / Time
Site:	Hope Creek
Issue date:	06/06/1994
From:	Labruna S Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-92-01, GL-92-1, NLR-N94098, NUDOCS 9406140091
Download: ML20069H915 (3)

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, e PutAC latwwKm n,- ne, Gturiptany St:nley LaDruna Pubhc Gorviw Doctric and Gas Company P O. Dox 230. Hanco< kn Dridge, NJ Oft 030 000 339 1700

.__,.m,,.,, JUN O 61994 N LR-N94 098 l

l United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gontlement GENERIC LETTER 92-01, REVISION 1 l REACTOR VESSEL STRUCTURAL INTEGRITY, 10CFR50.54(f) l IlOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NO. NPF-57 l DOCKET NO. 50-354 l

In responso to NRC Lotter dated April 6, 1994, Public Sorvico ]

Electric & Gas Company (PSE&G) submitted, as requested, corrections and clarifications to the NRC computorized databaso designated Roactor Vessel Integrity - Databaso. (RVID) for the Hope l Creek Conorating Station (Reference PSE&G Lottor NLR-N94085 dated May 12, 1994). Por tolocon with Mr. J. Stono, NRR Licensing Project Manegor, on May 20, 1994, PSE&G providos the following additional clarification regarding the Insido Diamotor (ID)

Fluence Imvola at End-Of-Life (EOL) and 1/4T Fluence Levels at EOL contained in the NRC RVID:

The ID Fluenco Levels at EOL provided in the Pressure-Temperaturo Limit Table of the NRC RVID should be updated to contain the levels previously provided in response to NRC Generic Letter 88-11, Radiation Embrittlement of Reactor Vessel Materials (PSE&G Lotter NLR-N90042 dated March 8, 1990). This reference should be added to the NRC Table.

The 1/4T Fluence Levels at EOL provided in the Upper Shelf Energy (USE) Table of the NRC RVID should be updated to l contain the lovels calculated in accordance with Regulatory '

Guido 1.99, Rev. 2 previously provided in response to NRC l

Generic Letter 88-11, Radiation Embrittlement of Reactor  ;

l Vessel Materials (PSE&G Lettor NLR-N90042 dated March 8, l 1990). This reference should be added to the NRC Table.

The clarifications provided above supersedo the previous comments regarding fluence lovels provided to the NRC in Lottor NLR-N94085.

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PDR ADOCK 05000354 I l P PDR l

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l JUN O 61994 l Document Control Desk 2 NLR-N94098 Please contact us should you have any questions regarding this submittal.

Sincerely, I

. / &y l

l Affidavit C Mr. T. T. Martin, Administrator - Region I i U. S. Nuclear Regulatory Commission

! 475 Allendale Road King of Prussia, PA 19406 l

Mr. J. Stone, Licensing Project Manager U. S. Nuclear Regulatory Commission l One White Flint North l 11555 Rockville Pike

! Rockville, MD 20852 Mr. C. S. Marschall (SO9)

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

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a-REF: NLR-N94098 STATE OF NEW JERSEY )

) SS.

COUNTY OF SALEM )

S. LaBruna, being duly sworn according to law deposes and says:

I am Vice President - Nuclear Engineering 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.

(66#1"w Subscribed and Swor ~to before me

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this[6 O ~

day of fMLA , 1994

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Notary Public \v of New Jersey WBERLY JO BROWN My Commission expires on ff0TARY PU8 tlc 0F NEW.frnery my conunission Empire: Apra 41998

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