JAFP-11-0097, James a FitzPatrick - 10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System (ECCS) Evaluation Models

James a FitzPatrick - 10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System (ECCS) Evaluation Models

ML112130314
Person / Time
Site:	FitzPatrick
Issue date:	08/01/2011
From:	Eugene Dorman Entergy Nuclear Northeast, Entergy Nuclear Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
JAFP-11-0097
Download: ML112130314 (10)

Text

• -=-Entergy Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.

James A. FitzPatrick NPP P.O. Box 110 Lycoming, NY 13093 Tel 315-342-3840 Eugene Dorman Acting Licensing Manager JAFP-11-0097 August 1, 2011 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

SUBJECT:

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

REFERENCE:

1. Entergy Nuclear Operations, Inc. to USNRC, JAFP-1 0-0084, dated July 31,2010, 10 CFR 50.46 Annual Report - Errors in Emergency Core Cooling System (ECCS) Evaluation Models.

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, 2010 to July 31, 2011 for Entergy's James A. FitzPatrick Nuclear Power Plant (JAF). There have been two errors identified in the Loss of Coolant Accident (LOCA) Peak Cladding Temperatures (PCT) analysis since the publication of Reference 1. Those errors are summarized in 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, 2010, to July 31,2011.

This letter contains no new commitments. Should you have any questions, please contact Mr.

Eugene Dorman at (315) 349-6810.

Sincerely, I:UJ~

Eugene W. Dorman Acting Licensing Manager ED/ed cc: next page

JAFP-11-0097 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, 2010, to July 31, 2011 cc:

Mr. William Dean Regional Administrator, Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 Resident Inspectors Office U.S. Nuclear Regulatory Commission James A. FitzPatrick Nuclear Power Plant P.O. Box 136 Lycoming, NY 13093-0136 Mr. Bhalchandra Vaidya, Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop O-8-C2 Washington, DC 20555-0001

JAFP-11-0097 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, 2010, to July 31, 2011 (7 Pages)

JAFP-11-0097 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, 2010 to July 31, 2011 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, 2010 to July 31, 2011 for Entergys James A. FitzPatrick Nuclear Power Plant.

Two errors in the FitzPatrick models have been identified since the last annual report (Reference 24). FitzPatrick has been operating with the same models and analysis as reported in the last update, see Reference 24.

Table 1 summarizes the current FitzPatrick ECCS evaluation models.

Page 1 of 7

JAFP-11-0097 Attachment 1 TABLE 1 - ACCOUNTING OF LICENSING BASIS PEAK CLAD TEMPERATURES FOR FITZPATRICK Estimated Updated Report ECCS PCT Change PCT Period Evaluation GE11 GE12 GE14 GE11 GE12 GE14 Fuel(1) Fuel(2) Fuel(3) Fuel Fuel Fuel 1993 FitzPatrick LOCA 1570° Baseline N/A N/A N/A N/A Analysis (Ref. 2) F FitzPatrick Reload 12 Base- 1370° Baseline Supplemental Report N/A N/A N/A N/A line F Evals. (Ref. 3)

FitzPatrick Reload 13 1570° 1370° Supplemental Report N/A N/A Baseline F F (Ref. 4) 10 CFR 50.46 Notification Regarding 1620° 1420° Sensitivity To Small Input +50°F N/A N/A F F Parameter Changes (Ref. 5)

Prior to 10 CFR 50.46 July 1, Notification Regarding 1625° 1425°

+5°F N/A N/A 2000 Minor Code Corrections F F (Ref. 5) 10 CFR 50.46 Notification Regarding 1635° 1435°

+10°F N/A N/A Bottom Head Drain F F (Ref. 6) 10 CFR 50.46 1630° 1430° Notification Regarding -5F N/A N/A F F Time Step Size (Ref. 1)

Estimated Effect Of 1720° 1520° Condensation Error On +90°F N/A N/A July 1, F F PCT (Ref. 7) 2000 -

Estimated Effect Of June 30, Pressure Rate 1730° 2001 +10°F N/A 1530F N/A Inconsistency Error On F PCT (Ref. 8)

Estimated Effect Of 1730° 1525° Accounting Error On N/A -5°F N/A N/A F F PCT (Ref. 9)

SAFER Core Spray 1735° 1530° July 1, Injection Elevation Error +5°F N/A N/A F F 2001 - (Ref. 10)

June 30, Impact of SAFER Bulk 1745° 1540° 2002 Water Level Error on +10°F N/A N/A F F PCT (Ref. 11)

Page 2 of 7

JAFP-11-0097 Attachment 1 TABLE 1 - ACCOUNTING OF LICENSING BASIS PEAK CLAD TEMPERATURES FOR FITZPATRICK (Continued)

Estimated Updated PCT Change PCT Report ECCS Period GE12 GE14 GNF2 GE12 GE14 GNF2 Evaluation Fuel(2) Fuel(3) Fuel(4) Fuel Fuel Fuel Cycle 16 Core Load Using GE 14 Type Fuel 1700° N/A 1700°F N/A N/A N/A (Ref. 12) F Impact of SAFER July 1, Level/Volume Table Error 2002 - 1540° 1700° N/A on the PCT 0°F 0°F N/A June 30, F F (Ref. 13) 2003 Impact of SAFER Initial Separator Pressure Drop N/A N/A 1540° 1700° N/A Error on the PCT 0°F F F (Ref. 14)

Impact of GESTR Input File Interpolation Error on 1540° 1700° N/A 0oF N/A N/A the PCT (Ref. 15) F F Impact of SAFER04 Computer Platform July 1, 1540° 1700° N/A Change on the PCT 0oF N/A N/A 2003 - F F (Ref. 16)

June 30, Impact of WEVOL S1 2004 Volume Error on the PCT 1540° 1700° N/A 0oF N/A N/A (Ref. 17) F F Impact of Postulated Hydrogen-Oxygen 1540° 1700° N/A 0oF 0oF N/A Recombination (Ref. 18) F F July 1, 2004 - No Changes or Errors 1540° 1700° N/A June 30, (Ref. 19, Ref. 21) N/A N/A N/A F F 2006 July 1, Impact of Top Peaked 2006 - Power Shape for Small 1540° 1700° N/A June 30, Break LOCA Analysis (Ref. N/A N/A N/A F F 2008 20)

July 1, Cycle 19 Core Load Using 2008 - 1800° GNF2 Type Fuel 1700° December N/A N/A N/A N/A F (Ref. 20, Ref 22) F 30, 2008 December 30, 2008 - No changes or errors 1800° 1700° July 31, (Ref. 23) N/A N/A N/A N/A F F

2009 Page 3 of 7

JAFP-11-0097 Attachment 1 TABLE 1 - ACCOUNTING OF LICENSING BASIS PEAK CLAD TEMPERATURES FOR FITZPATRICK (Continued)

Estimated Updated PCT Change PCT Report ECCS Period GE14 GE14 Evaluation GNF2 Fuel(4) GNF2 Fuel Fuel(3) Fuel August 1, 2009 - No changes or errors July 31 (Ref. 24) N/A N/A 1700°F 1800°F 2010 Impact of Database Error for Heat Deposition on the Peak 45°F 45°F 1745°F 1845°F Cladding Temperature (PCT) for 10 X 10 Fuel August 1, Bundles (Ref. 25) 2010 -

Impact of Updated July 31, Formulation for 2011 Gamma Heat Deposition to Channel 5°F 5°F 1750°F 1850°F Wall for 9 X 9 and 10 X 10 Fuel Bundles (Ref. 26)

(1) GE11 fuel was removed from the core at conclusion of Cycle 15, 10/2002 (2) GE12 fuel was removed from the core at conclusion of Cycle 17, 10/2006 (3) GE14 fuel was first installed during RF15, 10/2002 (4) GNF2 fuel was first installed during RF18, 10/2008 Page 4 of 7

JAFP-11-0097 Attachment 1

REFERENCES:

1. Global Nuclear Fuel letter, A. Alzaben (GNF) to C. Franklin (NYPA), (AFA-00-N061 dated November 20, 2000) regarding 10 CFR 50.46 error report - impact of SAFER time step size on the peak clad temperature (PCT) for jet pump plant analyses. Includes General Electric/Global Nuclear Fuel 10 CFR 50.46 Notification Letter 2000-04 dated November 8, 2000 regarding "Impact of SAFER Time Step Size on the Peak Clad Temperature (PCT) for Jet Pump Plant Analyses." (Proprietary)

2. General Electric Nuclear Energy, "James A. FitzPatrick Nuclear Power Plant SAFER/GESTER-LOCA, Loss-of-Coolant Analysis," Licensing Topical Report NEDC-31317P, Class III (proprietary), Revision 2, April 1993.

3. General Electric Nuclear Energy Report, J11-02914SRL, Revision 0, August 1996, "Supplemental Reload Licensing Report for James A. FitzPatrick, Reload 12, Cycle 13."

4. General Electric Nuclear Energy Report, J11-03359SRL, Revision 1, Class I, October 1998, "Supplemental Reload Licensing Report for James A. FitzPatrick, Reload 13, Cycle 14."

5. General Electric Nuclear Energy, MFN-090-93, June 30, 1993, "Reporting of Changes and Errors in ECCS Evaluation Models."

6. General Electric Nuclear Energy, MFN-020-96, February 20, 1996, "Reporting of Changes and Errors in ECCS Evaluation Models."

7. General Electric/Global Nuclear Fuel 10 CFR 50.46 Notification Letter 2001-01 dated May 8, 2001 (via E-mail) regarding "Impact of SAFER Condensation Error on the Peak Clad Temperature (PCT)." (Proprietary)

8. General Electric/Global Nuclear Fuel 10 CFR 50.46 Notification Letter 2001-02 dated May 10, 2001 (via E-mail) regarding "Impact of SAFER Pressure Rate I inconsistency Error on the Peak Clad Temperature (PCT)." (Proprietary)

9. Global Nuclear Fuel letter, A. Alzaben (GNF) to J. Head (Entergy Nuclear Operations, Inc.), (AFA-01-E004, June 29, 2001) regarding GE12 Upper Bound PCT for FitzPatrick, (Proprietary).

10. General Electric/Global Nuclear Fuel 10 CFR 50.46 Notification Letter 2002-01 regarding "SAFER Core Spray Injection Elevation Error." (Proprietary)

11. General Electric/Global Nuclear Fuel 10 CFR 50.46 Notification Letter 2002-02 regarding "Impact of SAFER Bulk Water Level Error on the Peak Clad Temperature (PCT)."

(Proprietary)

12. Entergy letter, T.A. Sullivan to USNRC, dated November 12, 2002 (JAFP-02-0210) regarding 10 CFR 50.46 Reporting of Changes In Emergency Core Cooling System (ECCS) Evaluation Model.

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JAFP-11-0097 Attachment 1

13. General Electric 10 CFR 50.46 Notification Letter 2003-01, dated May 6, 2003 regarding Impact of SAFER Level/Volume Table Error on the Peak Cladding Temperature (PCT).

(Proprietary)

14. General Electric 10 CFR 50.46 Notification Letter 2003-03, dated May 6, 2003 regarding Impact of SAFER Initial Separator Pressure Drop Error on the Peak Cladding Temperature (PCT). (Proprietary)

15. General Electric 10 CFR 50.46 Notification Letter 2002-03, dated August 26, 2002 regarding Impact of GESTR Input File Interpolation Error on the Peak Clad Temperature (PCT). (Proprietary)

16. General Electric 10 CFR 50.46 Notification Letter 2002-04, dated August 26, 2002 regarding Impact of SAFER04 Computer Platform Change on the Peak Clad Temperature (PCT). (Proprietary)

17. General Electric 10 CFR 50.46 Notification Letter 2002-05, dated August 26, 2002 regarding Impact of WEVOL S1 Volume Error on the Peak Clad Temperature (PCT).

(Proprietary)

18. General Electric 10 CFR 50.46 Notification Letter 2003-05, dated May 13, 2004 regarding Impact of Postulated Hydrogen-Oxygen Recombination. (Proprietary)

19. Entergy letter, T.A. Sullivan to USNRC, dated August 17, 2005 (JAFP-05-0126) regarding 10 CFR 50.46 Annual Report - Errors in Emergency Core Cooling System (ECCS)

Evaluation Models.

20. GE Report, Supplemental Reload Licensing Report for James A. FitzPatrick Reload 18 Cycle 19, 0000-0078-7492-SRLR Rev.0, September 2008.

21. Entergy letter, J. J. Costedio to USNRC, dated August 14, 2006 (JAFP-06-0127) regarding 10 CFR 50.46 Annual Report - Errors in Emergency Core Cooling System (ECCS)

Evaluation Models.

22. Entergy Nuclear Operations, Inc. letter E. Dorman to USNRC, JAFP-08-0133, dated December 22, 2008, 10 CFR 50.46 Annual Report - Errors in Emergency Core Cooling System (ECCS) Evaluation Models.

23. Entergy Nuclear Operations, Inc. letter E. Dorman to USNRC, JAFP-09-0091, dated July 31, 2009, 10 CFR 50.46 Annual Report - Errors in Emergency Core Cooling System (ECCS) Evaluation Models.

24. Entergy Nuclear Operations, Inc. letter J. Pechacek to USNRC, JAFP-10-0084, dated July 31, 2010, 10 CFR 50.46 Annual Report - Errors in Emergency Core Cooling System (ECCS) Evaluation Models.

25. 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 10 X 10 Fuel Bundles. (Proprietary)

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JAFP-11-0097 Attachment 1

26. 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 9 X 9 and 10 X 10 Fuel Bundles. (Proprietary)

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