LR-N18-0099, 2018 Annual 10 CFR 50.46 Report

2018 Annual 10 CFR 50.46 Report

ML18270A162
Person / Time
Site:	Hope Creek
Issue date:	09/27/2018
From:	Casulli E Public Service Enterprise Group
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LR-N18-0099
Download: ML18270A162 (5)

Text

PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 0 PSEG Nuclear LLC 10 CFR 50.46 LR-N18-0099 StP 27 2018 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:

2018 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 412 GNF2 assemblies in the Cycle 22 core ; the remainder are GE14).

There are no regulatory commitments in this correspondence.

If you have any questions regarding this submittal, please contact Frank Safin at (856) 339-1937.

Sincerely, Edward T Casulli Plant Manager - Hope Creek ttm : 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- N18-0099 Document Control Desk Page 2 cc: Mr. David Lew, Regional Administrator - USNRC Region I Mr. James Kim, USNRC Project Manager - Hope Creek Mr. Justin Hawkins, USNRC Senior Resident Inspector - Hope Creek (X24)

Mr. Patrick Mulligan, Manager IV, NJ Bureau of Nuclear Engineering Mr. Thomas MacEwen, Hope Creek Commitment Coordinator (H02)

Mr. Lee Marabella, Corporate Commitment Coordinator (N21)

LR-N 18-0099 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: 9/17/2018 CURRENT OPERATING CYCLE: 22 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-33257P-A, Revision 1, September 2010. (See Assessment Note 1)

Calculations: 1. GE 14: "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-RO, 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 T e: GE14 GNF2 Reference PCT 1380 Of 1610 °F

LR-N 18-0099 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 Break LOCA Analysis (see Assessment Note 2)

LiPCT =0°F NA 2011-02: Impact of database error for heat deposition on the Peak Cladding Temperature (PCT) for 10 x 10 LiPCT =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 1O x 10 LiPCT =5°F NA fuel bundles (see Assessment Note 2) 2012-01: PRIME Fuel Properties Implementation for Fuel Rod T/M Performance, replacing GESTR Fuel LiPCT =45°F NA Properties (see Assessment Note 2) 2014-01: SAFER04A E4-Maintenance Update ChanQes. (see Assessment Note 2)

LiPCT =0°F NA 2014-02: SAFER04A E4-Mass Non-Conservatism.

(see Assessment Note 2)

LiPCT = 10°F NA 2014-03: SAFER04A E4-Minimum Core DP Model.

(see Assessment Note 2)

LiPCT =20°F NA 2014-04: SAFER04A E4-Bundle/Lower Plenum CCFL Head. (see Assessment Note 2)

LiPCT =-20°F NA 2017-01: GNF2 Lower Tie Plate Leakage (see Assessment Note 2)

NA LiPCT =-20°F 2017-02: Fuel Rod Plenum Temperature Update (see Assessment Note 2)

LiPCT =0°F LiPCT =0°F Net PCT 1485 °F 1590 °F B. CURRENT LOCA MODEL ASSESSMENTS GE14 GNF2 004N 1122-RO: Summary of GEH AOO Transient and LOCA Analyses with Respect to ASD Modification in LiPCT =20°F LiPCT =20°F HCGS (see Assessment Note 3)

Total PCT change from current assessments I LiPCT =20°F I LiPCT =20°F Cumulative PCT change for current assessments I ILiPCT I=20°F LI LiPCT I= 20°F Net PCT 1505 °F 1610 °F

LR-N18-0099 Attachment 2 Hope Creek Generating Station 10 CFR 50.46 Report Assessment Notes Page 1 of 1

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-N13-021 O 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.

3. Current LOCA Model Assessments - 004N1122-RO: Summary of GEH AOO Transient and LOCA Analyses with Respect to ASD Modification in HCGS GE Hitachi (GEH) Letter Report 004N1122-RO evaluated the impact to the Hope Creek Generating Station licensing basis ECCS-LOCA evaluations due to the replacement of the recirculation system motor-generator sets with adjustable speed drives (ASD). ASD implementation occurred during the Hope Creek 2018 refueling outage. ASD use reduces the inertia of the tripped recirculation pumps, causing faster pump coast down during a LOCA.

The effect of ASD implementation on Hope Creek Generating Station's licensing basis PCT, for both GNF2 and GE14 fuel types, is an increase of 20 degrees F. The resulting PCT for both fuel types is in compliance with the 50.46(b)(1) criterion that peak cladding temperature shall not exceed 2200 degrees F.