View source for JAFP-16-0121, James a FitzPatrick - Transmittal of 10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System Evaluation Models

{{Adams
| number = ML16214A290
| issue date = 08/01/2016
| title = James a FitzPatrick - Transmittal of 10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System Evaluation Models
| author name = Drews W
| author affiliation = Entergy Nuclear Northeast, Entergy Nuclear Operations, Inc
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000333
| license number = DPR-059
| contact person = 
| case reference number = JAFP-16-0121
| document type = Annual Operating Report, Letter type:JAFP
| page count = 5
}}

=Text=
{{#Wiki_filter:Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.
 -=*Entergy James A. FitzPatrick NPP P.O. Box 110 Lycoming, NY 13093 Tel 315-342-3840 William C. Drews Regulatory Assurance Manager JAFP-16-0121 August 1, 2016 U.S. Nuclear Regulatory Commission A TIN: Document Control Desk Washington, DC 20555

==Subject:==
10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System Evaluation Models James A FitzPatrick Nuclear Power Plant Docket No. 50-333 License No. DPR-059

==Reference:==
Entergy letter, 10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System Evaluation Models, JAFP-15-0092, dated August 3, 2015

==Dear Sir or Madam:==

The attached report summarizes changes and errors in emergency core cooling system (ECCS) evaluation models in accordance with 10 CFR 50.46(a)(3)(ii) for the period August 1, 2015 to July 31, 2016 for Entergy's James A. FitzPatrick Nuclear Power Plant (JAF).
This letter contains no new regulatory commitments. Should you have any questions, please contact me at (315) 349-6562.
Sincerely,
  '1v (_       9-William C. Drews Regulatory Assurance Manager WCD/mh

==Attachment:==
10 CFR 50.46(a)(3)(ii) Annual Report on Changes and Errors in Emergency Core Cooling System (ECCS) Evaluation Models for the period from August 1, 2015toJuly31, 2016 cc:     NRC Region I Administrator NRC Resident Inspector NRC Project Manager

JAFP-16-0121 Attachment 10 CFR 50.46(a)(3)(ii) Annual Report on Changes and Errors in Emergency Core Cooling System (ECCS) Evaluation Models for the period from August 1, 2015 to July 31, 2016 (3 Pages)

JAFP-16-0121 Attachment 10 CFR 50.46(a)(3)(ii) Annual Report on Changes and Errors in Emergency Core Cooling System (ECCS) Evaluation Models for the period from August 1, 2015 to July 31, 2016 INTRODUCTION This report summarizes changes and errors in emergency core cooling system (ECCS) evaluation models in accordance with 10 CFR 50.46(a)(3)(ii) for the period August 1, 2015 to July 31, 2016 for Entergys James A. FitzPatrick Nuclear Power Plant. There are no new changes or errors reported during this period.
FitzPatrick has been operating with the same models and analysis as reported in the last update, see Reference 7. The JAF core is comprised of GNF2 fuel. The base licensing basis Peak Cladding Temperature (PCT) is 1800&deg;F as reported in Reference 2. The PCT adjusted for changes and errors is 1900&deg;F as shown in Table 1, which remains below the 2200&deg;F acceptance criterion of 10 CFR 50.46.
Page 1 of 3

JAFP-16-0121 Attachment 10 CFR 50.46(a)(3)(ii) Annual Report on Changes and Errors in Emergency Core Cooling System (ECCS) Evaluation Models for the period from August 1, 2015 to July 31, 2016 TABLE 1 - ACCOUNTING OF LICENSING BASIS PEAK CLAD TEMPERATURES FOR FITZPATRICK GNF2 Fuel(1)
Notification Nature of PCT Report Period                                                      Estimated PCT       Licensing Basis Change in ECCS Evaluation Impact                PCT Cycle 19 Core Load Using GNF2 n/a               1800&deg;F Type Fuel (Ref. 1, 2) 2011-02, Impact of Database Error for Heat Deposition on the Peak Cladding Temperature                             45&deg;F               1845&deg;F (PCT) for 10x10 Fuel Bundles (Ref. 8) 2011-03, Impact of Updated Formulation for Gamma Heat Deposition to Channel Wall for                         5&deg;F               1850&deg;F 9x9 and 10x10 Fuel Bundles (Ref. 9) 2012-01, Change in an Prior Reporting acceptable evaluation model or Periods application of such model due to (Ref. 3, 4, 5, 6 &
PRIME Fuel Properties                                 40&deg;F               1890&deg;F 7)
Implementation for Fuel Rod T/M Performance, replacing GESTR Fuel Properties (Ref. 10) 2014-01, Maintenance Update 0&deg;F               1890F Changes (Ref. 11) 2014-02, Mass Non-conservatism 10&deg;F               1900&deg;F (Ref. 11) 2014-03, Minimum Core Differential Pressure Model                           20&deg;F               1920&deg;F (Ref. 11) 2014-04, Rev. 1, Bundle/Lower Plenum Counter Current Flow                          -20&deg;F               1900&deg;F Limited Head (Ref. 12)
Cumulative Licensing Basis PCT as of previous 1900&deg;F reporting period August 1, 2015 -
No changes or errors                                  n/a               1900&deg;F July 31, 2016 Cumulative sum of absolute magnitude of 0&deg;F changes and errors in this reporting period NOTE: (1) GNF2 fuel was first installed during Refueling Outage 18, October 2008 Page 2 of 3

JAFP-16-0121 Attachment 10 CFR 50.46(a)(3)(ii) Annual Report on Changes and Errors in Emergency Core Cooling System (ECCS) Evaluation Models for the period from August 1, 2015 to July 31, 2016 REFERENCES
: 1. General Electric Nuclear Energy, James A. FitzPatrick Nuclear Power Plant SAFER/GESTR-LOCA Loss-of-Coolant Accident Analysis, NEDC-31317P, Class III (Proprietary), Revision 2, April 1993
: 2. GE Report, James A. FitzPatrick Nuclear Power Plant GNF2 ECCS-LOCA Evaluation, 0000-0076-4111-R0, August 2008 (Proprietary) (Internal Report JAF-RPT-08-00014 R0)
: 3. Entergy Nuclear Operations, Inc. Letter to USNRC, JAFP-11-0097, dated August 1, 2011, 10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System Evaluation Models
: 4. Entergy Nuclear Operations, Inc. Letter to USNRC, JAFP-12-0089, dated August 1, 2012, 10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System Evaluation Models
: 5. Entergy Nuclear Operations, Inc. Letter to USNRC, JAFP-13-0096, dated August 1, 2013, 10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System Evaluation Models
: 6. Entergy Nuclear Operations, Inc. Letter to USNRC, JAFP-14-0094, dated August 1, 2014, 10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System Evaluation Models
: 7. Entergy Nuclear Operations, Inc. Letter to USNRC, JAFP-15-0092, dated August 3, 2015, 10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System Evaluation Models
: 8. General Electric 10 CFR 50.46 Notification Letter 2011-02, dated July 20, 2011 regarding Impact of Database Error for Heat Deposition on the Peak Cladding Temperature (PCT) for 10x10 Fuel Bundles (Proprietary)
: 9. General Electric 10 CFR 50.46 Notification Letter 2011-03, dated July 20, 2011 regarding Impact of Updated Formulation for Gamma Heat Deposition to Channel Wall for 9x9 and 10x10 Fuel Bundles (Proprietary)
: 10. General Electric 10 CFR 50.46 Notification Letter 2012-01, dated November 29, 2012 regarding PRIME Fuel Properties Implementation for Fuel Rod T/M Performance, replacing GESTR Fuel Properties (Proprietary) (Letter LRW-ENO-GEN-12-131)
: 11. Entergy Nuclear Operations, Inc. Memorandum to File, CEXI-2014-00002, dated May 23, 2014 regarding Entergy Plant 10 CFR 50.46 Notification Letters 2014-01, 2014-02, 2014-03, and 2014-04
: 12. General Electric Hitachi 10 CFR 50.46 Notification Letter 2014-04, Rev. 1, dated December 5, 2014 regarding SAFER04A E4-Bundle/Lower Plenum CCFL Head (Proprietary)
Page 3 of 3}}