LR-N12-0301, 10CFR50.46 Report

10CFR50.46 Report

ML12272A278
Person / Time
Site:	Hope Creek
Issue date:	09/07/2012
From:	Carr E Public Service Enterprise Group
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LR-N12-0301
Download: ML12272A278 (6)

Text

PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 0 PSEGNuclear LLC SEP 0 7 2012 10 CFR 50.46 LR-N 12-0301 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 [as defined in 1 OCFR46(a)(3)(i)], 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 of GE14 fuel assemblies and GE14i fuel assemblies (there are 12 GE14i Isotope Test Assemblies in the Cycle 18 core; the remainder are GE14).

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, Eric S. Carr Plant Manager - Hope Creek - 10 CFR 50.46 Report (2 pages) - 10 CFR 50.46 Report Assessment Notes (2 pages)

2 LR-N12-0301 Document Control Desk cc: Mr. W. Dean, Administrator - Region I U. S. Nuclear Regulatory Commission 2100 Renaissance Blvd, Suite 100 King of Prussia, PA 19406-2713 Mr. J. Hughey, Project Manager U.S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 BlA 11555 Rockville Pike Rockville, MD 20852 USNRC Senior Resident Inspector - Hope Creek (X24)

Mr. P. Mulligan, Manager IV Bureau of Nuclear Engineering PO Box 420 Trenton, New Jersey 08625 Hope Creek Commitment Coordinator (H02)

Corporate Commitment Coordinator (N21)

LR-N1 1-00275 Document Control Desk Attachment 1 Page 1 of 2 Attachment 1 10 CFR 50.46 Report Page 1 of 2

LR-N12-0301 Document Control Desk Attachment 1 10 CFR 50.46 Report Page 2 of 2 PLANT NAME: Hope Creek Generating Station ECCS EVALUATION MODEL: SAFER/GESTR-LOCA REPORT REVISION DATE: 9/05/2012 CURRENT OPERATING CYCLE: 18 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: GE14 and GE14i Limiting Fuel Type - Licensing Basis PCT: GE1 4/GE1 4i Limiting Single Failure: Battery Limiting Break Size and Location: Double-Ended Guillotine in a Recirculation Suction Pipe Fuel Type: GEl4 GE14i Reference PCT 1380 -F 1380 OF MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS GE14 GE14i Impact of Top Peaked Power Shape on Small Break APCT = 00 F APOT = 00 F LOCA Analysis (see Assessment Note 1) 2011-02: Impact of database error for heat deposition on the Peak Cladding Temperature (PCT) for 10 x 10 APCT = 45'F APCT = 45 0 F fuel bundles (see Assessment Note 1) 2011-03: Impact of updated formulation for gamma heat deposition to channel wall for 9 x 9 and 10 x 10 APCT = 5 0 F APCT = 5 0 F fuel bundles (see Assessment Note 1)

Net PCT 1430 OF 1430 OF B. CURRENT LOCA MODEL ASSESSMENTS GE14 GE14i None (see Assessment Note 2)

Total PCT change from current assessments Y APCT = 0°F Y_APCT = 0°F Cumulative PCT change for current assessments Z IAPCT = 0F Y IAPCT = 0°F Net PCT 1430 OF 1430 OF

LR-N12-0301 Document Control Desk Attachment 2 Page 1 of 2 Attachment 2 10 CFR 50.46 Report Assessment Notes Page 1 of 2

LR-N12-0301 Document Control Desk Attachment 2 Page 2 of 2 Hope Creek Generating Station 10 CFR 50.46 Report Assessment Notes

1. Prior LOCA Model Assessments Letters, LR-N08-0221 and LR-N1 1-0275, reported the impact of the top peaked axial power shape on the small break LOCA for GEl 4 and GE1 4i fuel for Hope Creek.

Letter LR-N1 1-0275 reported the impact of the database error for heat deposition on the Peak Cladding Temperature (PCT) for 10 x 10 fuel bundles and the impact of updated formulation for gamma heat deposition to channel wall for 9 x 9 and 10 x 10 fuel bundles as applicable to Hope Creek GE14 and GE14i fuel.

2. Current LOCA Model Assessments No new assessments since the last 10 CFR 50.46 Report transmitted in Letter, LR-N11-0275, dated September 13, 2011.