JAFP-20-0063, Submittal of 10 CFR 50.46 Annual Report

Submittal of 10 CFR 50.46 Annual Report

ML20210L998
Person / Time
Site:	FitzPatrick
Issue date:	07/28/2020
From:	David Gudger Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
JAFP-20-0063
Download: ML20210L998 (8)

Text

200 Exelon Way 10 CFR 50.46 Annual Report Kennett Square, PA 19348 July 28, 2020 www.exeloncorp.com Page 2 10 CFR 50.46 JAFP-20-0063 July 28, 2020 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 James A. FitzPatrick Nuclear Power Plant Renewed Facility Operating License No. DPR-59 NRC Docket No. 50-333

Subject:

10 CFR 50.46 Annual Report The purpose of this letter is to submit the 10 CFR 50.46 reporting information for James A. FitzPatrick Nuclear Power Plant (JAF). The most recent 10 CFR 50.46 Annual Report for JAF was provided on August 1, 2019. (ML18213A011).

Two attachments are included in this letter that provide the current JAF 10 CFR 50.46 status. Attachment 1, "Peak Cladding Temperature (PCT) Rack-Up Sheets," provides updated information regarding the PCT for the limiting analysis and Attachment 2, "Assessment Notes," contains a detailed description of each change or error reported.

No new regulatory commitments are established in this submittal.

If any additional information is needed, please contact Enrique Villar at (610) 765- 5736.

Respectfully, David T. Gudger David T. Gudger Senior Manager, Licensing Exelon Generation Company, LLC Attachments: 1) Peak Cladding Temperature Rack-Up Sheets

2) Assessment Notes cc: USNRC Administrator, Region I USNRC Project Manager, JAF USNRC Senior Resident Inspector, JAF A. L. Peterson, NYSERDA

ATTACHMENT 1 Annual Report of the Emergency Core Cooling System Evaluation Model Changes and Errors Assessments Assessments as of July 15, 2020 Peak Cladding Temperature Rack-Up Sheets James A. FitzPatrick Nuclear Power Plant

James A. FitzPatrick 10 CFR 50.46 Annual Report Peak Cladding Temperature (PCT) Rack-Up Sheets Attachment 1 July 28, 2020 Page 1 of 2 PLANT NAME: James A. FitzPatrick ECCS EVALUATION MODEL: SAFER/GESTR(PRIME)-LOCA REPORT REVISION DATE: 07/15/2020 CURRENT OPERATING CYCLE: 24 ANALYSIS OF RECORD Evaluation Model:

1. B. S. Shiralkar et al, The GESTR-LOCA and SAFER Models for the Evaluation of the Loss-of-Coolant Accident: Volume III - SAFER/GESTR Application Methodology, February 1985 (NEDE-23785-1-P-A and NEDO-23785-1-A)

2. Compilation of Improvements to GENE's SAFER ECCS-LOCA Evaluation Model, NEDC-32950P, January 2000 as reviewed by letter from S. A. Richards (NRC) to J. F. Klapproth (GE), General Electric Nuclear Energy (GENE)

Topical Reports NEDC-32950P and NEDC-32084P Acceptability Review, May 24, 2000

3. GESTR-LOCA and SAFER Models for Evaluation of Loss-of-Coolant Accident Volume III, Supplement 1, Additional Information for Upper Bound PCT Calculation, NEDE-23785P-A, Supplement 1, Revision 1, March 2002

4. Implementation of PRIME Models and Data in Downstream Methods, NEDO-33173 Supplement 4-A, Revision 1, November 2012 Calculations:

1. 0000-0076-4111-R0 Rev 0, James A. Fitzpatrick Nuclear Power Plant GNF2 ECCS-LOCA Evaluation, August 2008 (JAF-RPT-08-00014 Rev 0)

Fuel: GNF2 Limiting Single Failure: Battery Failure Limiting Break Size and Location: Double-Ended Guillotine in a Recirculation Suction Pipe Reference Peak Cladding Temperature (PCT): GNF2 = 1800 °F MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS 10 CFR 50.46 Report dated December 22, 2008 (Note 1) GNF2: PCT = 0 10 CFR 50.46 Report dated July 31, 2009 (Note 2) GNF2: PCT = 0 10 CFR 50.46 Report dated July 31, 2010 (Note 3) GNF2: PCT = 0 10 CFR 50.46 Report dated August 1, 2011 (Note 4) GNF2: PCT = 50

James A. FitzPatrick 10 CFR 50.46 Annual Report Peak Cladding Temperature (PCT) Rack-Up Sheets Attachment 1 July 28, 2020 Page 2 of 2 10 CFR 50.46 Report dated August 1, 2012 (Note 5) GNF2: PCT = 0 10 CFR 50.46 Report dated August 1, 2013 (Note 6) GNF2: PCT = 40 10 CFR 50.46 Report dated August 1, 2014 (Note 7) GNF2: PCT = 35 10 CFR 50.46 Report dated August 3, 2015 (Note 8) GNF2: PCT = -25 10 CFR 50.46 Report dated August 1, 2016 (Note 9) GNF2: PCT = 0 10 CFR 50.46 Report dated August 1, 2017 (Note 10) GNF2: PCT = 0 10 CFR 50.46 Report dated August 1, 2018 (Note 11) GNF2: PCT = 0 10 CFR 50.46 Report dated August 1, 2019 (Note 12) GNF2: PCT = 0 NET PCT GNF2: 1900 °F B. CURRENT LOCA MODEL ASSESSMENTS Notification 2019-05 (Note 13) GNF2: PCT = 0 Notification 2020-01 (Note 13) GNF2: PCT = 0 Total PCT change from current assessments GNF2: PCT = 0 Cumulative PCT change from current assessments GNF2: lPCTl = 0 NET PCT GNF2: 1900 °F

ATTACHMENT 2 Annual Report of the Emergency Core Cooling System Evaluation Model Changes and Errors Assessments Assessments as of July 15, 2020 Assessment Notes for James A. FitzPatrick Nuclear Power Plant

James A. FitzPatrick 10 CFR 50.46 Annual Report Assessment Notes Attachment 2 July 28, 2020 Page 1 of 3

1) Prior LOCA Model Assessment GNF2 fuel was first installed during Refueling Outage 18, October 2008.

No changes or errors were reported against GNF2 during this reporting period.

[

Reference:

Letter from E. Dorman (Entergy Nuclear Operations) to the U.S. Nuclear Regulatory Commission, JAFP-08-0133, 10 CFR 50.46 Annual Report - Errors in Emergency Core Cooling System (ECCS) Evaluation Models, dated December 22, 2008.]

2) Prior LOCA Model Assessment No changes or errors were reported against GNF2 during this reporting period.

[

Reference:

Letter from J. Pechacek (Entergy Nuclear Operations) to the U.S. Nuclear Regulatory Commission, JAFP-09-0091, 10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System (ECCS) Evaluation Models, dated July 31, 2009.]

3) Prior LOCA Model Assessment No changes or errors were reported against GNF2 during this reporting period.

[

Reference:

Letter from J. Pechacek (Entergy Nuclear Operations) to the U.S. Nuclear Regulatory Commission, JAFP-10-0084, 10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System (ECCS) Evaluation Models, dated July 31, 2010.]

4) Prior LOCA Model Assessment Two errors were reported against GNF2 fuel during this reporting period.

Error 2011-02 described the database error for heat deposition on peak cladding temperature (PCT) for 10x10 fuel bundles. The error was estimated to increase the GNF2 PCT by +45 F.

Error 2011-03 described the updated formulation for gamma heat deposition to the channel wall for 10x10 fuel bundles. The error was estimated to increase the GNF2 PCT by +5 F.

[

Reference:

Letter from Eugene W. Dorman (Entergy Nuclear Operations) to the U.S. Nuclear Regulatory Commission, JAFP-11-0097, 10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System (ECCS) Evaluation Models, dated August 1, 2011.]

5) Prior LOCA Model Assessment No changes or errors were reported against GNF2 during this reporting period.

[

Reference:

Letter from Jorge OFarrill (Entergy Nuclear Operations) to the U.S. Nuclear Regulatory Commission, JAFP-12-0089, 10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System Evaluation Models, dated August 1, 2012.]

James A. FitzPatrick 10 CFR 50.46 Annual Report Assessment Notes Attachment 2 July 28, 2020 Page 2 of 3

6) Prior LOCA Model Assessment One change was reported against GNF2 during this reporting period.

Change 2012-01 described the impact from PRIME implementation to compute fuel properties.

The error was estimated to increase the GNF2 PCT by +40 F.

[

Reference:

Letter from Chris M. Adner (Entergy Nuclear Operations) to the U.S. Nuclear Regulatory Commission, JAFP-13-0096, 10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System Evaluation Models, dated August 1, 2013.]

7) Prior LOCA Model Assessment Four changes and errors were reported against GNF2 fuel during this reporting period.

Change 2014-01 described code maintenance changes. These changes were estimated to have no impact upon the GNF2 PCT.

Error 2014-02 described a mass non-conservatism. The error was estimated to increase the GNF2 PCT by +10 F.

Error 2014-03 described an error in the minimum core differential pressure model. The error was estimated to increase the GNF2 PCT by +20 F.

Error 2014-04 Rev 0 described an error in the bundle / lower plenum counter-current flow-limited head model. The error was estimated to increase the GNF2 PCT by +5 F.

[

Reference:

Letter from Chris M. Adner (Entergy Nuclear Operations) to the U.S. Nuclear Regulatory Commission, JAFP-14-0094, 10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System Evaluation Models, dated August 1, 2014.]

8) Prior LOCA Model Assessment One error was reported against GNF2 fuel during this reporting period.

Error 2014-04 Rev 1 was issued as a revision to error notification 2014-04 Rev 0 (Note 7). The revision identified a change to the hot bundle pressure head used as input to the counter-current flow-limited head model that resulted in a benefit (PCT reduction). With this revised notice, the prior PCT change of +5 F was replaced by a PCT change of -20 F. Consequently, the error was estimated to have a net change upon GNF2 PCT of -25 F.

[

Reference:

Letter from Chris M. Adner (Entergy Nuclear Operations) to the U.S. Nuclear Regulatory Commission, JAFP-15-0092, 10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System Evaluation Models, dated August 3, 2015.]

9) Prior LOCA Model Assessment No changes or errors were reported against GNF2 during this reporting period.

[

Reference:

Letter from William C. Drews (Entergy Nuclear Operations) to the U.S. Nuclear Regulatory Commission, JAFP-16-0121, 10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System Evaluation Models, dated August 1, 2016.]

James A. FitzPatrick 10 CFR 50.46 Annual Report Assessment Notes Attachment 2 July 28, 2020 Page 3 of 3

10) Prior LOCA Model Assessment One error was reported against GNF2 during this reporting period.

Error 2017-01 identifies that the GNF2 leakage paths between the bundle and the bypass (lower tie plate flow hole and channel to lower tie plate interface) were incorrectly modeled. The error was estimated to have no impact upon the GNF2 PCT.

[

Reference:

Letter from James Barstow (Exelon Generation) to the U.S. Nuclear Regulatory Commission, JAFP-17-0076, 10 CFR 50.46 Annual Report, dated August 1, 2017.]

11) Prior LOCA Model Assessment One error was reported against GNF2 during this reporting period.

Change 2017-02 describes a change in the GNF2 upper plenum model. The generic upper plenum model was changed to more explicitly model the GNF2 fuel design. The change was estimated to have no impact upon the GNF2 PCT.

[

Reference:

Letter from James Barstow (Exelon Generation) to the U.S. Nuclear Regulatory Commission, JAFP-18-0069, 10 CFR 50.46 Annual Report, dated August 1, 2018.]

12) Prior LOCA Model Assessment No changes or errors were reported against GNF2 during this reporting period.

[

Reference:

Letter from James Barstow (Exelon Generation) to the U.S. Nuclear Regulatory Commission, JAFP-19-0072, 10 CFR 50.46 Annual Report, dated August 1, 2019.]

13) Current LOCA Model Assessment Notification 2019-05 identifies that the upper and lower limits for the SAFER code forward and backward bypass leakage were coded incorrectly for the control rod guide tube to control rod drive housing interface backward leakage path. The error was estimated to have zero degree upon the GNF2 PCT.

Notification 2020-01 identifies that the PRIME code contained errors in irradiation growth after a breakaway neutron fluence, thermal conductivity applied to the zirconium barrier for cladding temperature drop, and gap conductance during pellet-cladding gap closure. The errors were estimated to have zero-degree impact upon the GNF2 PCT.