View source for JAFP-15-0092, James a FitzPatrick, 10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System Evaluation Models

{{Adams
| number = ML15215A046
| issue date = 08/03/2015
| title = James a FitzPatrick, 10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System Evaluation Models
| author name = Adner C
| 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-15-0092
| document type = Annual Operating Report, Letter type:JAFP
| page count = 5
}}

=Text=
{{#Wiki_filter:* -=-Entergy JAFP-15-0092 August 3, 2015 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Entergy Nuclear Northeast Entergy Nuclear Operations, Inc. James A. FitzPatrick NPP P.0.Box110 Lycoming , NY 13093 Tel 315-342-3840 Chris M. Adner Regulatory Assurance Manager 

==Subject:==
1 O CFR 50.46 Annual Report -Changes and Errors in Emergency Core Cooling System Evaluation Models 

==Reference:==

==Dear Sir or Madam:==
James A FitzPatrick Nuclear Power Plant Docket No. 50-333 License No. DPR-059 Entergy letter, 1 O CFR 50.46 Annual Report -Changes and Errors in Emergency Core Cooling System Evaluation Models, JAFP-14-0094, dated August 1, 2014 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, 2014 to July 31, 2015 for Entergy's James A. FitzPatrick Nuclear Power Plant (JAF). This letter contains no new commitments.
Should you have any questions, please contact me at (315) 349-6766. Chris M. Adner Regulatory Assurance Manager CMA/mh cc: next page 

==Attachment:==

1 O 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, 2014 to July 31, 2015 cc: NRC Regional Administrator, Region I NRC Resident Inspector Senior Project Manager  

JAFP-15-0092 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, 2014 to July 31, 2015 (3 Pages)
JAFP-15-0092  0 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, 2014 to July 31, 2015 Page 1 of 3 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, 2014 to July 31, 2015 for Entergy's James A. FitzPatrick Nuclear Power Plant. Since the last reporting update (Reference 4), FitzPatrick has been subject to one notification of changes and errors in the Evaluation Model used for ECCS-LOCA calculation (Reference 9). Notification Letter 2014-04, Rev. 1 reported an Evaluation Model error related to bundle and reactor vessel lower plenum counter current flow limited (CCFL) head that results in a small (non-significant) change in PCT. Revision 1 replaces the change previously reported Notification Letter 2014-04, Rev. 0.
JAFP-15-0092  0 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, 2014 to July 31, 2015 Page 2 of 3 TABLE 1 - ACCOUNTING OF LICENSING BASIS PEAK CLAD TEMPERATURES FOR FITZPATRICK Report Period Notification Nature of PCT Change in ECCS Evaluation GNF2 Fuel (1) Estimated PCT Impact Licensing Basis PCT Prior Reporting Periods  (Ref. 1, 2, 3, & 4) Cycle 19 Core Load Using GNF2 Type Fuel (Ref. 10, 11) n/a 1800&deg;F 2011-02 , Impact of Database Error for Heat Deposition on the 

Peak Cladding Temperature (PCT) for 10x10 Fuel Bundles (Ref. 5) 45&deg;F 1845&deg;F 2011-03 , Impact of Updated Formulation for Gamma Heat Deposition to Channel Wall for 9x9 and 10x10 Fuel Bundles (Ref. 6) 5&deg;F 1850&deg;F 2012-01 , Change in an acceptable evaluation model or application of such model due to 

PRIME Fuel Properties Implementation for Fuel Rod T/M Performance, replacing GESTR Fuel Properties (Ref. 7) 40&deg;F 1890&deg;F 2014-01, Maintenance Update Changes (Ref. 8) 0&deg;F 1890 F 2014-02, Mass Non-conservatism (Ref. 8) 10&deg;F 1900&deg;F 2014-03, Minimum Core Differential Pressure Model (Ref. 8) 20&deg;F 1920&deg;F 2014-04 , Bundle/Lower Plenum Counter Current Flow Limited 

Head (Ref. 8) 5&deg;F 1925&deg;F Cumulative Licensing Basis PCT as of previous reporting period 1925&deg;F August 1, 2014 -
July 31, 2015 (Remove) 2014-04, Rev 0 -5&deg;F 1920&deg;F 2014-04, Rev. 1, Bundle/Lower Plenum Counter Current Flow 

Limited Head (Ref. 9) 
-20&deg;F 1900&deg;F Cumulative sum of absolute magnitude of changes and errors in this reporting period 25&deg;F   NOTE: (1) GNF2 fuel was first installed during Refueling Outage 18, October 2008 JAFP-15-0092  0 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, 2014 to July 31, 2015 Page 3 of 3 REFERENCES1. 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" 2. 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" 3. 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" 4. 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" 5. 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) 6. 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) 7. 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) 8. 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" 9. General Electric Hitachi 10 CFR 50.46 Notification Letter 2014-04, Rev. 1, dated December 5, 2014 (Proprietary) 10. 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 11. 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)}}