ML16347A428

30-Day, 10 CFR 50.46 Report, ECCS Evaluation Model Change

ML16347A428
Person / Time
Site:	Hope Creek
Issue date:	12/12/2016
From:	Casulli E T Public Service Enterprise Group
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LR-N16-0234
Download: ML16347A428 (4)

Text

PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 LR-N16-0234 DEC 1 2 2016 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 1 1 SEG Nuclear LLC 10 CFR 50.46

Subject:

30-Day, 10 CFR 50.46 Report, ECCS Evaluation Model Change Pursuant to the requirements of 10 CFR 50.46, PSEG Nuclear LLC (PSEG) hereby reports a change in the application of the Emergency Core Cooling System (ECCS) evaluation models for the Hope Creek Generating Station (HCGS). In accordance with 10 CFR 50.46(a)(3)(ii), licensees are required to provide a 30 day report when a change to evaluation models used for calculating ECCS performance results in a significant Peak Cladding Temperature (PCT) change. This letter and its attachments satisfy the 30 day reporting requirement.

HCGS has started to transition to the GNF2 fuel design. The introduction of the GNF2 fuel design was a planned activity implemented during the fall 2016 refueling outage. The Licensing Basis Peak Cladding Temperature (PCT) for the GNF2 fuel design is more than 50 °F greater than the GE14 Licensing Basis PCT including consideration of previously reported 10 CFR 50.46 Notifications (GNF2 Licensing Basis PCT = 1610 °F, GE14 Licensing Basis PCT plus all previously reported 10 CFR 50.46 Notifications

= 1485 °F). HCGS will complete transition from a full core of the GE14 fuel design to full cores of GNF2 over the next several operating cycles. For the current operating cycle, the HCGS core consists of 212 GNF2 fuel assemblies and 552 GE14 fuel assemblies.

There are no regulatory commitments in this correspondence.

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

Sincerely,

.. Edward T Casulli Plant Manager -Hope Creek ttm Attachment 1: Hope Creek Generating Station 10 CFR 50.46 Report-Peak Cladding Temperature Rack-up Sheet Attachment 2: Hope Creek Generating Station 10 CFR 50.46 Report-Assessment Notes LR-N16-0234 Document Control Desk Page 2 cc: Mr. Daniel H. Dorman, Regional Administrator-US NRC Region I Ms. Carleen Parker, 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-N16-0234 Attachment 1 Hope Creek Generating Station 10 CFR 50.46 Report Peak Cladding Temperature Rack-up Sheet Page 1 of 1 PLANT NAME: ECCS EVALUATION MODEL: REPORT REVISION DATE: Hope Creek Generating Station SAFER/GESTR-PRIME 12/08/2016 CURRENT OPERATING CYCLE: 21 ANALYSIS OF RECORD Evaluation Model: 1. The GESTR-LOCA and SAFER Models for the Evaluation of the 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-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-RO, 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 MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS GNF2 None (see Assessment Note 2)

= 0°F Net PCT 1610 °F B. CURRENT LOCA MODEL ASSESSMENTS GNF2 None. (see Assessment Note 2) Total PCT change from current assessments 2::

= ooF Cumulative PCT change for current assessments L I I = oo F Net PCT 1610 °F LR-N16-0234

1. Evaluation Model Attachment 2 Hope Creek Generating Station 10 CFR 50.46 Report Assessment Notes Page 1 of 1 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 and Current LOCA Model Assessments There are no prior or current LOCA Model Assessments.

This report is being provide to document the Peak Cladding Temperature (PCT) resulting from the planned introduction of the GNF2 fuel design for Hope Creek Cycle 21 operation in accordance with 10 CFR 50.46. Hope Creek will transition from a full core of the GE14 fuel design to full cores of GNF2 over the next several operating cycles. All information reported to the NRC in accordance with 10 CFR 50.46 for the GE14 fuel design remains unchanged at the time of this report (Reference PSEG Transmittal Letter to NRC: LR-N16-0180 from Edward T Casulli, Plant Manager-Hope Creek, to U.S. NRC, "2016 Annual10 CFR 50.46 Report", Dated September 30, 2016). This report is being submitted as a 30 day report as a result of the GNF2 fuel design PCT (1610 °F) increasing more than 50 °F from the GE14 fuel design PCT (1485 °F). No proposed schedule for providing a reanalysis or taking other action as may be needed to show compliance with 10 CFR 50.46 requirements is provided with this report. All previous 10 CFR 50.46 notifications that are applicable to GNF2 have been analyzed and incorporated in the determination of the GNF2 Licensing Basis PCT. No new notifications of errors or changes have been identified at this time.