ML18093A933

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Forwards SER Accepting Util 860120 Projected Values of Matl Properties for Fracture Toughness Requirements for Protection Against PTS Events
ML18093A933
Person / Time
Site: Salem 
Issue date: 06/29/1988
From: Fischer D
Office of Nuclear Reactor Regulation
To: Miltenberger S
Public Service Enterprise Group
Shared Package
ML18093A934 List:
References
TAC-59979, NUDOCS 8807120478
Download: ML18093A933 (3)


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June 29, 1988

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Docket No. 50-311 Mr. Steven E. Miltenberger Vice President and Chief Nuclear Officer Public Service Electric & Gas Company Post Office Box 236 Hancocks Bridge, New Jersey 08038

Dear Mr. Miltenberger:

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SUBJECT:

PROJECTED VALUES OF MATERIAL PROPERTIES FOR FRACTURE TOUGHNESS REQUIREMENTS FOR PROTECTION AGAINST PRESSURIZED THERMAL SHOCK EVENTS (TAC NO. 59979)

RE:

SALEM NUCLEAR GENERATING STATION, UNIT 2 We have reviewed your letter dated January 20, 1986 which was submitted in response to the Pressurized Thermal Shock (PTS) Rule, 10 CFR 50.61, for Salem Nuclear Generating Station, Unit 2.

We have found the material properties of reactor vessel beltline materials, the projected fluence at the inner surface of the reactor vessel and the calculated RTPTS for the end of the current operating license and the 32 EFPY, the plant ~esign lifetime, to be acceptable.

The calculated RTPTS is below the screening criteria of 270°F at 32 EFPY and, therefore, meets tn~ requirements of the PTS Rule.

The PTS Rule requires that the projected assessment of the RT must be updated whenever changes in core loadings, surveillance measu~~~ents or other information (including changes in capacity factor) indicate a significant change in the projected values. This ensures that the licensees will track the accumulated fluence for the limiting beltline materials throughout the life of the plant to verify that their assumptions remain valid.

In this regard we request that you submit a re-evaluation of the RTPTS and comparison with of the predicted value in any future Pressure-Temperatur~ submittals which are submitted as required by 10 CFR 50, Appendix G.

Our associated Safety Evaluation is enclosed.

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Enclosure:

As stated cc w/enclosure:


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,fl Fischer: tr l,v/W/88 Sincerely,

~~jme ~t\\l &i!f Donald C. Fischer, Project Manager Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation PDI-2/D I ~

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 Docket No. 50-311 Mr. Steven E. Miltenberger Vice President and Chief Nuclear Officer Public Service Electric & Gas Company Post Office Box 236 Hancocks Bridge, New Jersey 08038

Dear Mr. Miltenberger:

June 29, 1988

SUBJECT:

PROJECTED VALUES OF MATERIAL PROPERTIES FOR FRACTURE TOUGHNESS REQUIREMENTS FOR PROTECTION AGAINST PRESSURIZED THERMAL SHOCK EVENTS (TAC NO. 59979)

RE:

SALEM NUCLEAR GENERATING STATION, UNIT 2 We have reviewed your letter dated January 20, 1986 which was submitted in response to the Pressurized Thermal Shock (PTS) Rule, 10 CFR 50.61, for Salem Nuclear Generating Station, Unit 2.

We have found the material properties of reactor vessel beltline materials, the projected fluence at the inner surface of the reactor vessel and the calculated RTPTS for the end of the current operating license and the 32 EFPY, the plant oesign lifetime, to be acceptable.

The calculated RTprs is below the screening criteria of 270°F at 32 EFPY and, therefore, meets tne requirements of the PTS Rule.

The PTS Rule requires that the projected assessment of the RT must be updated whenever changes in core loadings, surveillance measu~~~ents or other information (including changes in capacity factor) indicate a significant change in the projected values. This ensures that the licensees will track the accumulated fluence for the limiting beltline materials throughout the life of the plant to verify that their assumptions remain valid.

In this regard we request that you submit a re-evaluation of the RTPTS and comparison with of the predicted value in any future Pressure-Temperature submittals which are submitted as required by 10 CFR 50, Appendix G.

Our associated Safety Evaluation is enclosed.

Enclosure:

As stated cc w/enclosure:

See next page Sincerely, JJ~J l. 1-pOL Donald C. Fischer, Project Manager Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation

i Mr. Steven E. Miltenberger Public Service Electric & Gas Company cc:

Mark J. Wetterhahn, Esquire Conner and Wetterhahn Suite 1050 1747 Pennsylvania Avenue, NW Washington, DC 20006 Richard Fryling, Jr., Esquire Law Department - Tower SE 80 Park Place Newark, NJ 07101 Mr. John M. Zupko, Jr.

General Manager - Salem Operations Salem Generating Station P.O. Box E Hancocks Bridge, NJ 08038 Robert Traee, Mayor Lower Alloways Creek Township Muni ci pal Ha 11 Hancocks Bridge, NJ 08038 Richard W. Borchadt, Resident Inspector Salem Nuclear Generating Station U.S. Nuclear Regulatory Commission Drawer I Hancocks Bridge, NJ 08038 Richard F. Engel Deputy Attorney General Department of Law and Public Safety CN-112 State House Annex Trenton, NJ 08625 Mr. David M. Scott, Chief Bureau of Nuclear Engineering Department of Environmental Protection State of New Jersey CN 411 Trenton, NJ 08625 Salem Nuclear Generating Station Richard B. McGlynn, Commission Department of Public Utilities State of New Jersey 101 Commerce Street Newark, NJ 07102 Regional Administrator, Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Lower Alloways Creek Township c/o Mary 0. Henderson, Clerk Municipal Building, P.O. Box 157 Hancocks Bridge, NJ 08038 Mr. Bruce A. Preston, Manager Licensing and Regulation Nuclear Department P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. David Wersan Assistant Consumer Advocate Office of Consumer Advocate 1425 Strawberry Square Harrisburg, PA 17120 Morgan J. Morris, III General Manager - Operating License Atlantic Electric P.O. Box 1500 1199 Black Horse Pike Pleasantville, NJ 08232 Delmarva Power & Light Company c/o Jack Urban General Manager, Fuel Supply 800 King Street P.O. Box 231 Wilmington, DE 19899