ML18096B164

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Forwards Rev 1 to Rept NFU-060, Fracture Toughness Analysis for Salem Units 1 & 2 Reactor Pressure Vessels to Protect Against Pressurized Thermal Shock Events 10CFR50.61.
ML18096B164
Person / Time
Site: Salem  PSEG icon.png
Issue date: 12/15/1992
From: Labruna S
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18096B165 List:
References
NLR-N92177, NUDOCS 9212220325
Download: ML18096B164 (2)


Text

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Public Service Electric and Gas Company Stanley LaBruna Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1200 Vice President - Nuclear Operations DEC 1 5 1992 NLR-N92177 United States Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Gentlemen:

EVALUATION OF PRESSURIZED THERMAL SHOCK (PTS)

SALEM GENERATING STATION UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311

. Public Service Electric and Gas (PSE&G) originally responded to the PTS Rule (10CFR50.61) in a letter dated January 20, 1986.

10CFR50.61 (b) (1) requires an Adjusted Reference Temperature for Pressurized Thermal Shock (ART t ) update whenever changes in core loading, surveillance mea~u~ement or other information indicates a significant change in the .projected values. The attached report (NFU-060, Revision 1) updates the information previously submitted.

The ART t for both Salem Reactor Vessels remains below the PTS screeniHgscriteria at the current Operating License expiration date. The low leakage loading pattern employed at Salem has significantly reduced the Reactor Vessel flux at the critical vessel location. Flux reductions of approximately 50%, compared to the conventional out-in designs, have been achieved for both Salem Units.

Please note that results from the most recent capsule removal on Unit 2 (Capsule X) were not available when our report was prepared. We will forward Capsule X results when the DOT analysis is complete, if there is a significant impact.

Should you have any questions on this submittal, please contact us.

Sincerely, Attachment 9212220325 921215 PDR ADDCK 05000272 p PDR

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Document Control Desk 2 NLR-N92177 DEC 15 1992 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 - Salem

u. s. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. T. P. Johnson (S09)

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