LR-N24-0059, 2024 Annual 10 CFR 50.46 Report

2024 Annual 10 CFR 50.46 Report

ML24275A113
Person / Time
Site:	Hope Creek
Issue date:	09/30/2024
From:	Mclaughlin R Public Service Enterprise Group
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LR-N24-0059
Download: ML24275A113 (1)

Text

Robert McLaughlin Plant Manager-Hope Cree k, PSEG Nuclear

PO Box 236 o PSEG I NUCLEAR Hancoc ks Bridge, New Jersey 08038-0221 856-339-1873 Robert.mclaughlin@pseg.com

10 CFR 50.46

LR-N24-0059 30 September 2024

U.S. Nuclear Regulatory Commission ATTN : Document Control Desk Washington DC 20555-0001

Hope Creek Generating Station Renewed Facility Operating License No. NPF-57 NRC Docket No. 50-354

Subject:

2024 Annual 1 O CFR 50.46 Report

PSEG Nuclear LLC (PSEG) submits the attached documents for Hope Creek Generating Station in accordance with 10 CFR 50.46(a)(3)(ii). This letter and its attachments satisfy the annual reporting requirement.

For the current operating cycle, Cycle 26, the Hope Creek core consists only of GNF2 fuel assemblies.

There are no regulatory commitments in this correspondence.

Should you have any quest ions regarding this submittal, please contact Mr. Eric Scott at (856) 339 -2046.

Sincerely,

Robert McLaughlin Plant Manager, Hope Creek Generating Station 30 September 10 CFR 50.46 2024 Page 2 LR-N24-0059

Hope Creek Generating Station 1 0 CFR 50.46 Report - Peak Cladding Temperature Rack-up Sheet

Hope Creek Generating Station 1 0 CFR 50.46 Report - Assessment Notes

cc: USN RC Regional Administrator - Region 1 USNRC Project Manager - Hope Creek USN RC Senior Resident Inspector - Hope Creek NJ Bureau of Nuclear Engineering Corporate Commitment Coordinator, PSEG Nuclear, LLC LR-N24-0059

Attachment 1 Hope Creek Generating Station 10 CFR 50.46 Report Peak Cladding Temperature Rack-up Sheet (2 pages)

LR-N24-0059 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-PRIME REPORT REVISION DATE: 9/09/2024 CURRENT OPERATING CYCLE: 26

ANALYSIS OF RECORD

Evaluation Model: 1. The GESTR-LOCA and SAFER Models for the Evaluation of the Loss-of-Coolant Accident, Volume Ill, 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-33258P-A, Revision 1, September 2010. (See Assessment Note 1)

Calculations: Hope Creek Generating Station GNF2 ECCS-LOCA Evaluation, 002N5176-R0, Revision 0, August 2016.

Fuel: 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 I Fuel Type: GNF2 Reference PCT 1610 °F LR-N24-0059 Page 2 of 2

MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS

GNF2 2017-01: GNF2 Lower Tie Plate Leakage (see t.PCT = -20°F Assessment Note 2) 2017-02: Fuel Rod Plenum Temperature Update (see L'iPCT = 0°F Assessment Note 2) 004N1122-R0: Summary of GEH AOO Transient and LOCA Analyses with Respect to ASD Modification in L'1PCT = 20°F HCGS (see Assessment Note 2) 2019-05: SAFER Lower Limit on Differential Pressure L'1PCT = 0°F for Bvoass Leakaae (see Assessment Note 2) 2020-01: PRIME Coding Errors for Zircaloy Irradiation Growth and Zr Barrier Thermal Conductivity as input to L'1PCT = 0°F ECCS LOCA Analyses (see Assessment Note 2) 2021-01: Error in Fuel Pellet to Plenum Spring L'iPCT = 0°F Conductance (see Assessment Note 2) 2021-02: Discrepancy in Inner Cladding Surface L'1PCT = 0°F Rouahness (see Assessment Note 2)

Net PCT 1610 °F

B. CURRENT LOCA MODEL ASSESSMENTS

GNF2 None (See Assessment Note 3)

Total PCT change from current assessments I L'iPCT = 0°F Cumulative PCT change for current assessments I I t.PCT I = 0°F Net PCT 1610 °F LR-N24-0059

Attachment 2 Hope Creek Generating Station 10 CFR 50.46 Report Assessment Notes (1 page)

LR-N24-0059

Attachment 2

Hope Creek Generating Station 10 CFR 50.46 Report Assessment Notes

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

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).

Letter LR-N20-0063 reported the impact of errors associated with the differential pressure lower limit for bypass leakage, Zircaloy irradiation growth, thermal conductivity of the Zr barrier, and gap conductance during pellet-cladding gap closure.

Letter LR-N21-0071 reported the impact of errors associated with the fuel pellet to plenum spring conductance value applied to calculations for the plenum region of the fuel rods, and an inconsistency in the inner cladding surface roughness used by the PRIME and SAFER models.

3. Current LOCA Model Assessments

No new assessments since last 1 O CFR 50.46 Report transmitted in LR-N23-0065. Therefore, the GNF2 fuel type remains in compliance with the 50.46(b)(1) criterion that peak cladding temperature shall not exceed 2200 degrees F.