LR-N09-0221, 10 CFR 50.46 Report

10 CFR 50.46 Report

ML092820459
Person / Time
Site:	Hope Creek
Issue date:	09/23/2009
From:	Wagner L Public Service Electric & Gas Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LR-N09-0221
Download: ML092820459 (6)

Text

PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 O PSEG Nuclear LLC SEP 2 3 2009 10 CFR 50.46 LR-N09-0221 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NO. NPF-57 DOCKET NO. 50-354

Subject:

10CFR50.46 REPORT Pursuant to the requirements of 10 CFR 50.46, PSEG Nuclear LLC (PSEG) hereby reports changes in the application of the Emergency Core Cooling System (ECCS) evaluation models for the Hope Creek Generating Station. 10 CFR 50.46(a)(3)(ii) requires licensees to report at least annually each change to or error discovered in evaluation models used for calculating ECCS performance and the estimated effect on the limiting ECCS analysis. For significant changes or errors, licensees are required to submit a 30 day report and include a proposed schedule for providing a reanalysis or taking other action necessary to show compliance with 10 CFR 50.46 requirements.

This letter and its attachments satisfy the annual reporting requirement.

For the current operating cycle, the Hope Creek core consists entirely of GE 14 fuel.

There are no regulatory commitments contained in this correspondence.

If you have any questions regarding this submittal, please contact Mr. Philip J. Duca at (856) 339-1640.

Sincerely, Lawrence M. anr Plant Manager - Hope Creek Attachment 1 - 10 CFR 50.46 Report Attachment 2 - 10 CFR 50.46 Report Assessment Notes 95-2168 REV. 7/99

2 LR-N09-0221 Document Control Desk C Mr. S. Collins, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. R. Ennis, Project Manager - Hope Creek U. S. Nuclear Regulatory Commission Mail Stop 08B3 Washington, DC 20555-0001 USNRC Senior Resident Inspector - Hope Creek (X24)

Mr. P. Mulligan, Manager IV Bureau of Nuclear Engineering PO Box 415 Trenton, New Jersey 08625 Hope Creek Commitment Coordinator (H02)

Corporate Commitment Coordinator (N21)

LR-N09-0221 Document Control Desk Attachment 1 10 CFR 50.46 Report Page 1

LR-N09-0221 Document Control Desk Attachment 1 (Page 2)

Hope Creek Generating Station 10 CFR 50.46 Report Peak Cladding Temperature Rack-up Sheet PLANT NAME: Hope Creek Generating Station ECCS EVALUATION MODEL: SAFER/GESTR-LOCA REPORT REVISION DATE: 9/15/2009 CURRENT OPERATING CYCLE: 16 ANALYSIS OF RECORD Evaluation Model: The GESTR-LOCA and SAFER Models for the Evaluation of the Loss-of-Coolant Accident, Volume III, SAFER/GESTR Application Methodology, NEDE-23785-1-PA, General Electric Company, Revision 1, October 1984.

Calculations: "SAFER/GESTR-LOCA Loss-of-Coolant Accident Analysis for Hope Creek Generating Station at Power Uprate," NEDC-33172P, GE Energy, Nuclear, March 2005.

Fuel: GE 14 (see note 1)

Limiting Fuel Type - Licensing Basis PCT: GE 14 Limiting Single Failure: Battery Limiting Break Size and Location: Double-Ended Guillotine in a Recirculation Suction Pipe Fuel Type: GE 14 Reference PCT 1380 OF MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS Impact of Top Peaked Power Shape on Small Break LOCA APCT = 00 F Analysis (see note 2) _ PCT = 0°F Total PCT change from prior assessments Y-APCT = 0°F Cumulative PCT change from prior assessments Y IAPCT I= 0°F Net PCT 1380 OF B. CURRENT LOCA MODEL ASSESSMENTS None (see note 3) APCT = 0°F Net PCT 1380 °F

LR-N09-0221 Document Control Desk Attachment 2 10 CFR 50.46 Report Assessment Notes Page 1

LR-N09-0221 Document Control Desk Attachment 2 (Page 2)

Hope Creek Generating Station 10 CFR 50.46 Report Assessment Notes

1. Hope Creek has discharged all the SVEA-96+ fuel that was reported on in the last annual 10 CFR 50.46 Report (Letter LR-N08-0221). No SVEA-96+ fuel is in reactor operation at Hope Creek.

[Letter (LR-N08-0221) from John F. Perry (Plant Manager - Hope Creek) to U.S. NRC, "10 CFR 50.46 Report."]

2. Prior LOCA Model Assessments Letter, LR-N08-0221, reported the impact of the top peak axial power shape on the small break LOCA. The impact of the top peak axial power shape on the licensing basis PCT was zero degrees for GE 14 fuel for Hope Creek.

3. Current LOCA Model Assessments No new assessments since the last 10 CFR 50.46 Report transmitted in Letter, LR-N08-0221.