LR-N20-0063, 2020 Annual 10 CFR 50.46 Report
| ML20268C286 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 09/25/2020 |
| From: | Poorman S Public Service Enterprise Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LR-N20-0063 | |
| Download: ML20268C286 (6) | |
Text
PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 0 PSEG Nuclear LLC 10 CFR 50.46 LR-N20-0063 September 25, 2020 U.S. Nuclear Regulatory Commission ATTN : Document Control Desk Washington , DC 20555-0001 Hope Creek Generating Station Renewed Facility Operating License No. NPF-57 Docket No. 50-354
Subject:
2020 Annual 10 CFR 50.46 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. 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 GE14 fuel assemblies and GNF2 fuel assemblies (there are 618 GNF2 fuel assemblies and 146 GE14 fuel assemblies) in the Cycle 23 core .
There are no regulatory commitments in this correspondence.
If you have any questions regarding this submittal, please contact Frank Safin at (856) 339-1937.
Sine~ ~
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Steven R. Poorman Plant Manager, Hope Creek Generating Station : 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
LR-N20-0063 Document Control Desk Page 2 cc: Regional Administrator - USNRC Region I USNRC Project Manager - Hope Creek USNRC Senior Resident Inspector - Hope Creek (X24)
Mr. Patrick Mulligan, Manager IV, NJ Bureau of Nuclear Engineering Hope Creek Commitment Coordinator (N21)
Corporate Commitment Coordinator (N21)
LR-N20-0063 Attachment 1 Hope Creek Generating Station 10 CFR 50.46 Report Peak Cladding Temperature Rack-up Sheet Page 1 of 2 PLANT NAME: Hope Creek Generating Station ECCS EVALUATION MODEL: SAFER/GESTR-LOCA (GE14)
SAFER/GESTR-PRIME (GNF2)
REPORT REVISION DATE: 9/15/2020 CURRENT OPERATING CYCLE: 23 ANALYSIS OF RECORD Evaluation Model: 1. 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.
- 2. Licensing Topical Report, The PRIME Model for Analysis of Fuel Rod Thermal-Mechanical Performance, Part 1 - Technical Bases, NEDC-33256P-A, Revision 1, Part 2 - Qualification, NEDC-33257P-A, Revision 1, and Part 3 - Application Methodology, NEDC-33257P-A, Revision 1, September 2010. (See Assessment Note 1)
Calculations: 1. GE14: "SAFER/GESTR-LOCA Loss-of-Coolant Accident Analysis for Hope Creek Generating Station at Power Uprate, NEDC-33172P, GE Energy, Nuclear, March 2005.
- 2. GNF2: Hope Creek Generating Station GNF2 ECCS-LOCA Evaluation, 002N5176-R0, Revision 0, August 2016.
Fuel: GE14 and GNF2 Limiting Fuel Type - Licensing Basis PCT: GNF2 Limiting Single Failure: Battery Limiting Break Size and Location: Double-Ended Guillotine in a Recirculation Suction Pipe Fuel Type: GE14 GNF2 Reference PCT 1380 ºF 1610 ºF
LR-N20-0063 Attachment 1 Hope Creek Generating Station 10 CFR 50.46 Report Peak Cladding Temperature Rack-up Sheet Page 2 of 2 MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS GE14 GNF2 2006-01 Impact of Top Peaked Power Shape on Small PCT = 0°F NA Break LOCA Analysis (see Assessment Note 2) 2011-02: Impact of database error for heat deposition on the Peak Cladding Temperature (PCT) for 10 x 10 PCT = 45°F NA fuel bundles (see Assessment Note 2) 2011-03: Impact of updated formulation for gamma heat deposition to channel wall for 9 x 9 and 10 x 10 PCT = 5°F NA fuel bundles (see Assessment Note 2) 2012-01: PRIME Fuel Properties Implementation for Fuel Rod T/M Performance, replacing GESTR Fuel PCT = 45°F NA Properties (see Assessment Note 2) 2014-01: SAFER04A E4-Maintenance Update PCT = 0°F NA Changes. (see Assessment Note 2) 2014-02: SAFER04A E4-Mass Non-Conservatism.
PCT = 10°F NA (see Assessment Note 2) 2014-03: SAFER04A E4-Minimum Core DP Model.
PCT = 20°F NA (see Assessment Note 2) 2014-04: SAFER04A E4-Bundle/Lower Plenum CCFL PCT = -20°F NA Head. (see Assessment Note 2) 2017-01: GNF2 Lower Tie Plate Leakage (see NA PCT = -20°F Assessment Note 2) 2017-02: Fuel Rod Plenum Temperature Update (see PCT = 0°F PCT = 0°F Assessment Note 2) 004N1122-R0: Summary of GEH AOO Transient and LOCA Analyses with Respect to ASD Modification in PCT = 20°F PCT = 20°F HCGS (see Assessment Note 2)
Net PCT 1505 ºF 1610 ºF B. CURRENT LOCA MODEL ASSESSMENTS GE14 GNF2 2019-05: SAFER Lower Limit on Differential Pressure for Bypass Leakage (see Assessment Note PCT = 0°F PCT = 0°F 3) 2020-01: PRIME Coding Errors for Zircaloy Irradiation Growth and Zr Barrier Thermal PCT = 0°F PCT = 0°F Conductivity as input to ECCS LOCA Analyses (see Assessment Note 4)
Total PCT change from current assessments PCT = 0°F PCT = 0°F Cumulative PCT change for current assessments PCT= 0°F PCT= 0°F Net PCT 1505 ºF 1610 ºF
LR-N20-0063 Attachment 2 Hope Creek Generating Station 10 CFR 50.46 Report Assessment Notes Page 1 of 2
- 1. Evaluation Model The GESTR fuel rod thermal mechanical models described in Evaluation Model Reference 1 were replaced by the PRIME fuel rod thermal mechanical models described in Evaluation Model Reference 2.
- 2. 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 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 fuel.
Letter LR-N13-0210 reported the impact of PRIME Fuel Properties Implementation for Fuel Rod T/M Performance, replacing GESTR Fuel Properties.
Letter LR-N14-0211 reported the impact of Evaluation Model changes or errors associated with SAFER04A E4-Maintenance Update Changes, E4-Mass Non-Conservatism, E4-Minimum Core DP Model, and E4-Bundle/Lower Plenum CCFL Head.
Letter LR-N16-0234 reported the implementation of GNF2 and associated evaluation. All prior LOCA model assessments were incorporated, as applicable, in the licensing basis GNF2 evaluation.
Letter LR-N17-0141 reported the impact of Evaluation Model changes or errors associated with the modeling of GNF2 lower tie plate leakage and use of modern fuel rod design input for fuel rod plenum modeling.
Letter LR-N18-0099 reported the impact of the replacement of the recirculation system motor-generator sets with adjustable speed drives (ASD).
- 3. Current LOCA Model Assessments - 2019-05: SAFER Lower Limit on Differential Pressure for Bypass Leakage GE Hitachi (GEH) Notification Letter 2019-05 reported an error in the implementation of the lower limit applied to the differential pressure modeled for backward leakage between the control rod guide tubes and the control rod drive housing within the SAFER model. The effect of the error on Hope Creek Generating Stations licensing basis PCT values for both fuel types is 0 degrees F. Both resulting PCT values therefore remain within compliance of the 50.46(b)(1) criterion that peak cladding temperature shall not exceed 2200 degrees F.
LR-N20-0063 Attachment 2 Hope Creek Generating Station 10 CFR 50.46 Report Assessment Notes Page 2 of 2
- 4. Current LOCA Model Assessments - 2020-01: PRIME Coding Errors for Zircaloy Irradiation Growth and Zr Barrier Thermal Conductivity as input to ECCS LOCA Analyses GE Hitachi (GEH) Notification Letter 2020-01 reported errors in the PRIME code used for input to the ECCS LOCA evaluation models. The errors were in the areas of Zircaloy irradiation growth after breakaway neutron fluence, the thermal conductivity applied to the Zr barrier for cladding temperature drop, and gap conductance during pellet-cladding gap closure. The effect of the errors on Hope Creek Generating Stations licensing basis PCT values for both fuel types is 0 degrees F. Both resulting PCT values therefore remain within compliance of the 50.46(b)(1) criterion that peak cladding temperature shall not exceed 2200 degrees F.