ML20029E513

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Submits Requested Info Re Rev 1 to GL 92-01, Reactor Vessel Structural Integrity,10CFR50,54(f), in Response to Ltr Dtd 940406
ML20029E513
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 05/12/1994
From: Labruna S
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-92-01, GL-92-1, NLR-N94085, NUDOCS 9405180438
Download: ML20029E513 (4)


Text

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  • Pubhc SeMee Dcctnc and Gm Company Stanley La3runa Pubhc Service Drsctnc ar a r' a ,P.O Box 236, Hancocks Bndge, NJ 08038 609 339-1700

- v.c. e sa o Ne w re m m NLR-N94085 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

GENERIC LETTER 92-01, REVISION 1 REACTOR VESSEL STRUCTURAL INTEGRITY, 10CFR50.54(f)

HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NO. NPF-57 DOCKET NO. 50-354 In response to NRC Letter dated April 6, 1994, Public Service Electric & Gas Company (PSE&G) submits to the NRC as requested the following information:

1. PSE&G commits to the BWR Owners Group effort to validate the methodology for determining the initial RT er values identified in Enclosure 1 to the above referenced-NRC Letter,
2. PSE&G confirms the plant-specific applicability of BWR Owners Group Topical Report NEDO-32205, Rev. 1 for Hope Creek for 1/4T Upper Shelf Energy (USE) at End of~ Life (EOL) and Unirradiated USE values identified in Enclosure 2 to the NRC Letter. PSE&G has committed to incorporate NEDO-32205 as part of the Hope Creek licensing basis as stated in our letter dated July 20, 1993 (NLR-N93110). PSE&G requests approval of the topical report as the basis for demonstrating compliance with 10CFR50, Appendix G, Paragraph IV.A.1.
3. PSE&G has verified the information contained in Enclosures 1 and 2 of the above referenced letter.

With regard to the information contained in Enclosure 1, the following corrections and clarifications are provided:

Enclosure 1

a. Initial RTer for Intermediate Shell Plate heat No. SK2608-1 should be 19'F.
b. Weld material heat No. 510-01205 data has been omitted and should be added for the Axial welds for the Lower Shell, l l

1 94051bO438 40512 .

I PDR ADOCK 05000354 P PDR

l M AY 121994-l Document Control Desk 2 l

NLF-N94085 Intermediate Shell, and the Circumferential weld between the Lower-Intermediate and Lower Shell plates. (See Tables 2 and 4 of PSE&G Letters NLR-N92080 dated June 30, 1992 and NLR-N92120 dated September 3, 1992.)

c. Weld material heat Nos. 519-01205, 504-01205 and D53040 should be included for the Circumferential weld between the Lower-Intermediate and Intermediate Shell Plates.
d. The reference indicates that fluence levels were provided in PSE&G Letter dated June 30, 1992. However, PSE&G provided the 1/4T fluence levels in this letter, and not the ID fluence levels at End-of-life / Effective Full Power Years contained in the Enclosure. The reference description should be revised.

PSE&G has confirmed only the columns in Enclosure 1 for Heat No.

Identification, Initial RT gg , %Cu and %Ni as previously submitted to the NRC in PSE&G Letters NLR-N92080 dated June 30, 1992 and NLR-N92120 dated September 3, 1992.

With regard to the information contained in Enclosure 2, the following corrections and clarifications are provided:

Enclosure 2

a. PSE&G Letter NLR-N92120 dated September 3, 1992 provided updated 1/4T fluence levels that should be included in the Enclosure. It is understood that rounded off values are being used. The existing Reference for Hope Creek should be revised to delete the word " Fluence". An additional Reference should be added as follows: " Fluence data are from September 3, 1992 Letter from S. Miltenberger (PSEG) to USNRC Document Control Desk, subject: Response to Generic Letter 92-01, Revision 1, Reactor Vessel Structural Integrity, 10CFR50. 54 ( f) " .
b. Weld material heat No. 510-01205 data has been omitted and should be added for the Axial welds for the Lower Shell, Intermediate Shell, and the Circumferential weld between the Lower-Intermediate and Lower Shell plates. (See Tables 2 and 4 of PSE&G Letters NLR-N92080 dated June 30, 1992 and NLR-N92120 dated September 3, 1992.)
c. Weld material heat Nos. 519-01205, 504-01205 and D53040 should be included for the Circumferential weld between the Lower-Intermediate and Intermediate Shell Plates,
d. LPCI Nozzle Weld Heat No. 529-01205 should be 519-01205.

Document Control Desk 3 NLR-N94085

c. Even though the flux type of weld materials are unknown as far as comparison to known American flux types, the chemical compositions of all welds are known and illustrated in Table 9 of PSE&G Letter dated June 30, 1992.

PSE&G has confirmed only the columns in Enclosure 2 for Heat No.

Identification, Material Type, and 1/4T fluence levels as previously submitted to the NRC in PSE&G Letters NLR-N92080 dated June 30, 1992 and NLR-N92120 dated September 3, 1992.

Please contact us should you have any questions regarding this submittal.

Sincerely, sWD cne Affidavit C Mr. T. T. Martin, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. J. Stone, Licensing Project Manager U. S. Nuclear Regulatory Commission One White Flint North 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 Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625

i REF: NLR-N94085 l

STATE OF NEW JERSEY )

) SS.

COUNTY OF SALEM ) l l

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

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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.

/

// -

t%rf w Subscribed and Sworn to before me this [N day of D7'7dd

, 1994 U

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}_473b1Ab Notary Public hf New Jersey KlMBERLY JO BROWN My Commission expires on NPTARY PUBllC OF NFW JEREFY My cornmission hpires April 21,1998 l

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