JAFP-14-0094, 10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System Evaluation Models
| ML14213A056 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 08/01/2014 |
| From: | Chris Adner Entergy Nuclear Northeast, Entergy Nuclear Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| JAFP-14-0094 | |
| Download: ML14213A056 (6) | |
Text
~ Entergy JAFP-14-0094 August 1, 2014 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP P.O. Box 110 Lycoming, NY 13093 Tel 315-342-3840 Chris M. Adner Licensing 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 Nuclear Operations, Inc. to USNRC, JAFP-13-0096, dated August 1, 2013, 1 O CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System Evaluation Models.
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, 2013 to July 31, 2014 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.
Sincerely, Chris M. Adner Regulatory Assurance Manager CMA/db/ds cc: next page
JAFP-14-0094 Page 2 of 2
- 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, 2013 to July 31, 2014 cc:
Regional Administrator, Region I U. S. Nuclear Regulatory Commission 2100 Renaissance Boulevard, Suite 100 King of Prussia, PA 19406-2713 Resident Inspectors Office U.S. Nuclear Regulatory Commission James A. FitzPatrick Nuclear Power Plant P.O. Box 136 Lycoming, NY 13093-0136 Mr. Douglas Pickett Senior Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
JAFP-14-0094 ATTACHMENT 1 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, 2013 to July 31, 2014 (3 Pages)
JAFP-14-0094 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, 2013 to July 31, 2014 Page 1 of 3 INTRODUCTION Table 1 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, 2013 to July 31, 2014 for Entergys James A. FitzPatrick Nuclear Power Plant.
Since the last reporting update (Reference 1), FitzPatrick has been subject to four notifications of changes and errors in the Evaluation Model used for ECCS-LOCA calculation (Reference 2).
Notification Letter 2014-01 reported Evaluation Model changes regarded as code maintenance items having very minimal influence on the hot node heat-up calculation. Sensitivity calculations demonstrated that these items individually and collectively have insignificant effect on calculated peak cladding temperature (PCT).
Notification Letter 2014-02 reported an Evaluation Model error related to mass non-conservatism that results in a small (non-significant) change in PCT.
Notification Letter 2014-03 reported an Evaluation Model error related to the minimum core differential pressure model that results in a small (non-significant) change in PCT.
Notification Letter 2014-04 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.
The JAF core is uniformly loaded with the GNF2 fuel type. The GNF2 fuel type, with the Licensing Basis PCT 1925F is well below the 2200F peak cladding temperature acceptance criterion of 10 CFR 50.46.
JAFP-14-0094 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, 2013 to July 31, 2014 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, 3 & 9)
Cycle 19 Core Load Using GNF2 Type Fuel (Ref. 4, 5) n/a 1800F 2011-02, Impact of Database Error for Heat Deposition on the Peak Cladding Temperature (PCT) for 10x10 Fuel Bundles (Ref. 6) 45F 1845F 2011-03, Impact of Updated Formulation for Gamma Heat Deposition to Channel Wall for 9x9 and 10x10 Fuel Bundles (Ref. 7) 5F 1850F 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. 8) 40F 1890F Base PCT (adjusted Licensing Basis PCT on July 31, 2013) 1890F August 1, 2013 -
July 31, 1014 2014-01, Maintenance Update Changes (Ref. 2) 0F 1890F 2014-02, Mass Non-conservatism (Ref. 2) 10F 1900F 2014-03, Minimum Core Differential Pressure Model (Ref. 2) 20F 1920F 2014-04, Bundle/Lower Plenum Counter Current Flow Limited Head (Ref. 2) 5F 1925F Cumulative sum of absolute magnitude of changes and errors in this reporting period 35F NOTE: (1) GNF2 fuel was first installed during Refueling Outage 18, October 2008
JAFP-14-0094 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, 2013 to July 31, 2014 Page 3 of 3 REFERENCES
- 1.
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
- 2.
Entergy Nuclear Operations, Inc. Memorandum to File, CEXI-2014-00002, Entergy Plant 10 CFR 50.46 Notification Letters 2014-01, 2014-02, 2014-03, and 2014-04
- 3.
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
- 4.
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
- 5.
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)
- 6.
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)
- 7.
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)
- 8.
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)
- 9.
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