LR-N15-0203, Transmittal of 2015 Annual 10 CFR 50.46 Report

Transmittal of 2015 Annual 10 CFR 50.46 Report

ML15272A113
Person / Time
Site:	Hope Creek
Issue date:	09/28/2015
From:	Carr E Public Service Enterprise Group
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LR-N15-0203
Download: ML15272A113 (5)

Text

PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 10 CFR 50.46 LR-N15-0203 SEP 2 8 2015 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:

2015 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 GE14i fuel assemblies (there are 12 GE14i Isotope Test Assemblies in the Cycle 20 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, Eric S. Carr Plant Manager - Hope Creek pjd : 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-N15-0203 Document Control Desk Page 2 of 2 cc: Mr. Daniel H. Dorman, Regional Administrator - USNRC Region I Mr. Thomas J. Wengert, 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-N15-0203 Document Control Desk Page 1 of 2 Attachment 1 Hope Creek Generating Station 10 CFR 50.46 Report Peak Cladding Temperature Rack-up Sheet PLANT NAME: Hope Creek Generating Station ECCS EVALUATION MODEL: SAFERIGESTR-LOCA REPORT REVISION DATE: 9/22/2015 CURRENT OPERATING CYCLE: 20 ANALYSIS OF RECORD Evaluation Model: The GESTR-LOCA and SAFER Models for the Evaluation of the Loss-of Coolant Accident, Volume Ill, SAFERIGESTR Application Methodology, NEDE-23785-1-PA, General Electric Company, Revision 1, October 1984.

Calculations: "SAFERIGESTR-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

LR-N15-0203 Document Control Desk Page 2 of 2 Attachment 1 MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS GE14 GE14i Impact of Top Peaked Power Shape on Small Break LOCA Analysis (see Assessment Note 1) ilPCT = ooF ilPCT = ooF 2011-02: Impact of database error for heat deposition on the Peak Cladding Temperature (PCT) for 10 x 10 ilPCT = 45°F ilPCT = 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 ilPCT = 5°F ilPCT = 5°F fuel bundles (see Assessment Note 1_)

2012-01: PRIME Fuel Properties Implementation for Fuel Rod T/M Performance, replacing GESTR Fuel ilPCT = 45°F ilPCT = 45°F Properties (see Assessment Note 1) 2014-01: SAFER04A E4-Maintenance Update Changes. (see Assessment Note 1) ilPCT = 0°F ilPCT = ooF 2014-02: SAFER04A E4-Mass Non-Conservatism.

(see Assessment Note 1) ilPCT = 10°F ilPCT = 10°F 2014-03: SAFER04A E4-Minimum Core DP Model.

(see Assessment Note 1) ilPCT = 20oF ilPCT = 20°F 2014-04: SAFER04A E4-Bundle/Lower Plenum CCFL Head. (see Assessment Note 1) ilPCT = -20°F ilPCT = -20°F Net PCT 1485 °F 1485 °F B. CURRENT LOCA MODEL ASSESSMENTS GE14 GE14i None. (see Assessment Note 2)

Total PCT change from current assessments L: ilPCT = ooF L: ilPCT = ooF Cumulative PCT change for current assessments L I ilPCT l= ooF L:_lilPCT I= ooF Net PCT 1485 °F 1485 °F

LR-N15-0203 Document Control Desk Page 1 of 1 Attachment 2 Hope Creek Generating Station 10 CFR 50.46 Report Assessment Notes

1. Prior LOCA Model Assessments Letters, LR-NOB-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.

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.

2. Current LOCA Model Assessments No new assessments since the last 10 CFR 50.46 Report transmitted in Letter, LR-N14-0211.