LR-N11-0275, 10CFR50.46 Reports Changes in the Application of the Emergency Core Cooling System Evaluation Models
| ML11264A035 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 09/13/2011 |
| From: | Doris Lewis Public Service Enterprise Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LR-N11-0275 | |
| Download: ML11264A035 (6) | |
Text
PSEG Nuclear LLC P. 0. Box 236, Hancocks Bridge, NJ 08038 0 PSEG SEP 13 2011 Nuclear LLC 10 CFR 50.46 LR-N1 1-0275 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 10CFR46(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 GEl4 fuel assemblies and GE14i fuel assemblies (there are 12 GE14i Isotope Test Assemblies in the Cycle 17 core; the remainder are GEl4).
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,
- Davi P.Lwis Plant Manager - Hope Creek - 10 CFR 50.46 Report (2 pages) - 10 CFR 50.46 Report Assessment Notes (2 pages)
2 LR-N11-0275 Document Control Desk cc:
Mr. W. Dean, 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 08 BIA 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-N11-00275 Document Control Desk Page 1 of 2 10 CFR 50.46 Report Page 1 of 2
LR-N1 1-0275 Document Control Desk 10 CFR 50.46 Report Page 2 of 2 PLANT NAME:
ECCS EVALUATION MODEL:
REPORT REVISION DATE:
CURRENT OPERATING CYCLE:
Hope Creek Generating Station SAFER/GESTR-LOCA 8/31/2011 17 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.
"SAFER/GESTR-LOCA Loss-of-Coolant Accident Analysis for Hope Creek Generating Station at Power Uprate," NEDC-33172P, GE Energy, Nuclear, March 2005.
Calculations:
Fuel: GE14 and GE14i Limiting Fuel Type - Licensing Basis PCT: GE1 4/GE14i Limiting Single Failure: Battery Limiting Break Size and Location: Double-Ended Guillotine in a Recirculation Suction Pipe Fuel Type:
GE14 GE14i Reference PCT 1380 'F 1380 -F MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS GE14 GE14i Impact of Top Peaked Power Shape on Small Break APCT = 00F APCT = 00F LOCA Analysis (see Assessment Note 1)
Cumulative PCT change from prior assessments Z APCT
= 0°F Z APCT = 0°F B. CURRENT LOCA MODEL ASSESSMENTS GE14 GE14i 2011-02: Impact of database error for heat deposition APCT = 450F APCT = 45°F on the Peak Cladding Temperature (PCT) for 10 x 10 fuel bundles (see Assessment Note 2) 2011-03: Impact of updated formulation for gamma APCT = 5"F APCT = 50F heat deposition to channel wall for 9 x 9 and 10 x 10 fuel bundles (see Assessment Note 2)
Total PCT change from current assessments Z APCT = 50°F Z APCT = 50°F Cumulative PCT change from prior and current Z APCT = 50°F Z APCT = 50°F assessments Net PCT 1430 OF 1430 OF
LR-N11-0275 Document Control Desk Page 1 of 2 10 CFR 50.46 Report Assessment Notes Page 1 of 2
LR-N 10-0275 Document Control Desk Page 2 of 2 Hope Creek Generating Station 10 CFR 50.46 Report Assessment Notes
- 1. 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 GEl 4 fuel for Hope Creek. See Note 3 for applicability to GE14i Isotope Test Assemblies.
- 2. Current LOCA Model Assessments Two new assessments have been issued since the last Hope Creek Generating Station 10 CFR 50.46 Report transmitted in letter, LR-N10-0353. See Note 3 for applicability to GE14i Isotope Test Assemblies.
Notification letter 2011-02 reported a discovery made regarding input coefficients used to direct the deposition of gamma radiation energy produced by the fuel, determining whether it would heat the fuel rod, cladding, channel, or control rod structural materials. The input caused the heat deposited in the fuel channel (post-scram) to be over-predicted, and the corresponding heat deposited in the fuel to be under-predicted. The error only applies to 10 x 10 fuel, and the bounding effect on peak cladding temperature was determined to be 45 degrees Fahrenheit.
Notification letter 2011-03 reported a discovery made during investigation of the input coefficients referenced in 2011-02.
The contribution of heat from gamma ray absorption by the channel was minimized. The formulation had been simplified such that all energy was assumed to be deposited in the fuel rods prior to the LOCA, and after the scram, it was adjusted such that the correct heat deposition was applied.
Energy distribution during the pre-scram phase of LOCA was updated with the appropriate energy distribution, and the bounding effect on peak cladding temperature was determined to be 5 degrees Fahrenheit.
- 3. Applicability to GE14i Isotope Test Assemblies GE14i fuel is not listed in the LOCA analysis of record. In Section 4.5.6 of the "Safety Analysis Report to Support Introduction of GE14i Isotope Test Assemblies (ITAs) in Hope Creek Generating Station," NEDC-33529P, Rev. 0, December 2009, the five acceptance criteria established by 10 CFR 50.46 were determined to be satisfied with the introduction of the GE14i ITAs. NEDC-33529P also provided documentation that the licensing basis PCT, including reported errors, for GE14 is applicable for GE14i ITAs. Therefore, the errors identified in Notes 1 and 2 above are applicable to GE14i.