LR-N05-0328, Submittal of Supplement No. 1 to Request for License Amendment Extended Power Uprate Loss of Coolant Analysis

Submittal of Supplement No. 1 to Request for License Amendment Extended Power Uprate Loss of Coolant Analysis

ML053250465
Person / Time
Site:	Hope Creek
Issue date:	11/07/2005
From:	Barnes G Public Service Enterprise Group
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LCR H05-01, LR-N05-0328
Download: ML053250465 (3)

Text

PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 NOV 0 7 2005 n

PSEG Nutclear LLC LR-N05-0328 LCR H05-01 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 SUPPLEMENT NO. I TO REQUEST FOR LICENSE AMENDMENT EXTENDED POWER UPRATE LOSS OF COOLANT ANALYSIS HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NPF-57 DOCKET NO. 50-354

References:

1) PSEG letter LR-N05-0258, Request for License Amendment: Extended Power Uprate, November 7, 2005

2) NRC Letter to GE Nuclear Energy, Review of Extended Power Uprates for Boiling Water Reactors, June 25, 2003

3) PSEG letter LR-N04-0378, SAFER/GESTR-LOCA Loss of Coolant Analysis Report, September 3, 2004 By the Reference 1 letter, PSEG Nuclear LLC (PSEG) requested an amendment to Facility Operating License NPF-57 and the Technical Specifications (TS) for the Hope Creek Generating Station to increase the maximum authorized power level to 3840 megawatts thermal (MWt).

In the Reference 2 letter, the NRC described additional plant-specific information to be submitted by licensees applying for extended power uprate (EPU) with a mixed core.

PSEG plans to implement the extended power uprate (EPU) with a mixed core. In accordance with the guidance in Reference 2, PSEG is providing the attached report in support of the NRC's review of the proposed amendment.

In the Reference 3 letter, PSEG provided a report of the results of the Loss of Coolant Accident (LOCA) analysis for the SVEA 96+ and GE14 fuel types at the Current

/

This letter forwards proprietary information in accordance with 10 CFR 2.390. The balance of this letter may be considered non-proprietary upon removal of Attachment 1.

95-2168 REV. 7W99

Document Control Desk

-2 20 LR-N05-0328 NOV 0 7 2005 Licensed Thermal Power. The report in Attachment 1 provides the same results for analysis applicable to the Constant Pressure Power Uprate rated thermal power. contains proprietary information as defined by 10 CFR 2.390. GE, as the owner of the proprietary information, has executed the affidavit included in, which identifies that the attached proprietary information has been handled and classified as proprietary, is customarily held in confidence, and has been withheld from public disclosure. GE requests that the proprietary information be withheld from public disclosure in accordance with the provisions of 10 CFR 2.390 and 9.17. A non-proprietary version suitable for public disclosure is provided in.

PSEG has determined that the information contained in this letter and attachments does not alter the conclusions reached in the 1 OCFR50.92 no significant hazards analysis previously submitted.

If you have any questions or require additional information, please contact Mr. Paul Duke at (856) 339-1466.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on

° (date)

George P. Barnes Site Vice President Hope Creek Generating Station Attachments (2)

Document Control Desk NOV 0 7 2005 LR-N05-0328 C

Mr. S. Collins, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. S. Bailey, Project Manager - Hope Creek U. S. Nuclear Regulatory Commission Mail Stop 0861 Washington, DC 20555-0001 USNRC Senior Resident Inspector - Hope Creek (X24)

Mr. K. Tosch, Manager IV (without Attachment 1)

Bureau of Nuclear Engineering PO Box 415 Trenton, NJ 08625