LR-N13-0210, Annual 10 CFR 50.46 Report
| ML13253A389 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 09/10/2013 |
| From: | Carr E Public Service Enterprise Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LR-N13-0210 | |
| Download: ML13253A389 (6) | |
Text
PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 SEP 1 0 2013 LR-N 13-0210 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Subject:
Hope Creek Generating Station Renewed Facility Operating License No. NPF-57 Docket No. 50-354 2013 Annual 10 CFR 50.46 Report I)SEG Nuclear LLC 10 CFR 50.46 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. In accordance with 10 CFR 50.46(a)(3)(ii), licensees are required 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. This letter and its attachments satisfy the annual reporting requirement.
For the current operating cycle, the Hope Creek core consists of GE 14 fuel assemblies and GE14i fuel assemblies (there are 12 GE 14i Isotope Test Assemblies in the Cycle 18 core; the remainder are GE 14).
There are no regulatory commitments in this correspondence.
If you have any questions regarding this submittal, please contact Mr. Paul Bonnett at (856) 339-1923.
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Eric S. Carr Plant Manager - Hope Creek : Hope Creek Generating Station 10 CFR 50.46 Report - Peak Cladding Temperature Rack-up Sheet : Hope Creek Generating Station 10 CFR 50.46 Report Assessment Notes -
Assessment Notes
LR-N13-0210 Page 2 of 2 cc:
Mr. W. Dean, Regional Administrator - Region I U.S. Nuclear Regulatory Commission 2100 Renaissance Blvd, Suite 100 King of Prussia, PA 19406-2713 Mr. J. Hughey, Project Manager - Hope Creek U.S. Nuclear Regulatory Commission One White Flint North Mail Stop 08B1A 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, NJ 08625 Hope Creek Commitment Coordinator (H02)
Corporate Commitment Coordinator (N21)
LR-N13-0210 Page 1 of 2 Hope Creek Generating Station 10 CFR 50.46 Report Peak Cladding Temperature Rack-up Sheet
LR-N13-0210 Page 2 of 2 Hope Creek Generating Station 10 CFR 50.46 Report Peak Cladding Temperature Rack-up Sheet PLANT NAME:
ECCS EVALUATION MODEL:
REPORT REVISION DATE:
CURRENT OPERATING CYCLE:
ANALYSIS OF RECORD Hope Creek Generating Station SAFER/GESTR-LOCA 8/2912013 18 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: GE14/GE14i Limiting Single Failure: Battery Limiting Break Size and Location: Double-Ended Guillotine in a Recirculation Suction Pipe GE14 GE14i MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS GE14 GE14i Impact of Top Peaked Power Shape on Small Break flPCT = OaF LlPCT = OaF 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 flPCT = 45°F flPCT = 45°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 flPCT = 5°F flPCT = 5°F fuel bundles (see Assessment Note 1)
NetPCT 1430 OF 1430 OF B. CURRENT LOCA MODEL ASSESSMENTS GE14 GE14i 2012-01: PRIME Fuel Properties Implementation for Fuel Rod TIM Performance, replacing GESTR Fuel flPCT = 45°F flPCT = 45°F Properties (see Assessment Note 2)
Total PCT change from current assessments I flPCT = 45°F I flPCT = 45°F Cumulative PCT change for current assessments I I flPCT I = 45°F II flPCT I = 45°F NetPCT 1475 OF 1475 OF
LR-N 13-021 0 Page 1 of 2 Hope Creek Generating Station 10 CFR 50.46 Report Assessment Notes
LR-N13-0210 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-N11-0275, reported the impact of the top peaked axial power shape on the small break LOCA for GE14 and GE14i fuel for Hope Creek.
Letter LR-N11-0275 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 One new assessment has been issued since the last Hope Creek Generating Station 10 CFR 50.46 Report transmitted in letter, LR-N12-0301.
GE Hitachi Notification letter 2012-01 reported that implementation of the PRIME fuel rod thermal mechanical performance bases, specifically PRIME fuel properties, addresses inaccuracies in fuel pellet thermal conductivity as a function of exposure that were identified in NRC Information Notice 2011-21. The effect of applying PRIME fuel properties on the Hope Creek Generating Station licensing basis PCT is an increase in the PCT of 45 of. The resulting PCT is in compliance with the 50.46(b)(1) criterion that peak cladding temperature shall not exceed 2200 ° F.