JAFP-05-0126, Annual Report - Errors in Emergency Core Cooling System (ECCS) Evaluation Models

Annual Report - Errors in Emergency Core Cooling System (ECCS) Evaluation Models

ML052430230
Person / Time
Site:	FitzPatrick
Issue date:	08/17/2005
From:	Ted Sullivan Entergy Nuclear Northeast, Entergy Nuclear Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
JAFP-05-0126
Download: ML052430230 (8)

Text

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Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.

James A. Fitzpatrick NPP Entergy P.O. Box 110 Lycoming, NY 13093 Tel 315 349 6024 Fax 315 349 6480 T.A. Sullivan August 17, 2005 Site Vice President - JAF JAFP-05-0126 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

SUBJECT:

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

REFERENCE:

1. Entergy Nuclear Operations, Inc. letter T.A. Sullivan to USNRC (JAFP-04-0135) dated August 23, 2004 regarding same subject.

Dear Sir:

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 July 1, 2004 to June 30, 2005 for Entergy's James A. FitzPatrick Nuclear Power Plant.

There were no changes or errors identified to the FitzPatrick model since the last report (Reference 1).

This letter contains no new commitments. If you have any questions, please contact Mr. Richard Plasse at (315) 349-6793.

Very truly yours, T. A. SULLIVAN

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 July 1, 2004 to June 30, 2005.

,Sao I.

cc: Mr. Samuel J. Collins Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Office of the Resident Inspector U.S. Nuclear Regulatory Commission James A. FitzPatrick Nuclear Power Plant P.O. Box 136 Lycoming, NY 13093 Mr. John P. Boska, Project Manager Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop: O-8B-1 Washington, DC 20555

Attachment to JAFP-05-0126 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 July 1, 2004 to June 30, 2005 for Entergy's James A. FitzPatrick Nuclear Power Plant.

No changes or errors to the FitzPatrick model have been identified since the last annual report (Reference 27). The fact that there were no reporting errors resulted in no thirty-day report submittals (errors that qualify as significant changes) in accordance with 10 CFR 50.46(a)(3)(i).

Table 1 summarizes the current FitzPatrick ECCS evaluation models.

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Attachment to JAFP-05-0126 TABLE I - ACCOUNTING OF LICENSING BASIS PEAK CLAD TEMPERATURES FOR FITZPATRICK Report Estimated Updated Period PCT Change PCT ECCS Evaluation GE11 GE12 GE14 GE11 GE12 GE14 Fuel"') Fuel Fuel( 2 ) Fuel Fuel Fuel Baseline 1993 FitzPatrick LOCA Baseline N/A N/A 1570°F N/A N/A Evals. Analysis (Ref. 7) I FitzPatrick Reload 12 N/A Base- N/A N/A 1370°F N/A Supplemental Report line Rcf. 8)

FitzPatrick Reload 13 N/A 1570°F 1370°F N/A Supplemental Report Baseline (Ref. 9)

Prior to 10 CFR 50.46 +50°F N/A 1620°F 1420°F N/A July 1, Notification Regarding 2000 Sensitivity To Small Input Parameter Changes (Ref. 10) 10 CFR 50.46 +5°F N/A 1625°F 1425°F N/A Notification Regarding Minor Code Corrections (Ref. 10) 10 CFR 50.46 +10°F N/A 1635°F 1435°F N/A Notification Regarding Bottom Head Drain (Ref. 11)

July 1, 10 CFR 50.46 -5F N/A 1630QF 1430°F N/A 2000 - Notification Regarding June 30, Time Step Size (Ref. 3) 2001 Estimated Effect Of +90°F N/A 1720°F 1520°F N/A Condensation Error On PCT (Ref. 12)

Estimated Effect Of +10°F N/A 1730°F 1530F N/A Pressure Rate Inconsistency Error On PCT (Ref. 13)

Estimated Effect Of N/A -50F N/A 1730°F 1525°F N/A Accounting Error On PCT (Ref. 14)

July 1, SAFER Core Spray +5°F N/A 1735°F 1530°F N/A 2001 - Injection Elevation Error June30, (Ref. 16) 2002 Impact of SAFER Bulk +100F N/A 1745WF 1540WF N/A U'ater Level Error on PCT (Ref. 17)

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t- 2 Attachment to JAFP-05-0126 TABLE I - ACCOUNTING OF LICENSING BASIS PEAK CLAD TEMPERATURES FOR FITZPATRICK (Continued)

Report Estimated Updated Period PCT Change PCT ECCS Evaluation GE11 GE12 GE14 GE11 GE12 GE14 Fuel Fuel Fuel Fuel Fuel Fuel July 1, Cycle 16 Core Load N/A N/A 1700OF N/A N/A 1700°F 2002 - Using GE 14 Type Fuel June 30, (Ref. 19) 2003 Impact of SAFER N/A 0°F 0°F N/A 1540°F 1700OF Level/Volume Table Error on the PCT (Ref. 20)

Impact of SAFER Initial N/A 0°F N/A N/A 1540°F 1700OF Separator Pressure Drop Error on the PCT (Ref. 21)

July 1, Impact of GESTR Input N/A 0°F N/A N/A 1540°F 1700OF 2003 - File Interpolation Error June 30, on the PCT (Ref. 22)(_)

2004 Impact of SAFER04 N/A 0°F N/A N/A 1540°F 1700OF Computer Platform Change on the PCT (Ref. 23) (3)

Impact of WEVOL S1 N/A 0°F N/A N/A 1540°F 1700OF Volume Error on the PCT (Ref. 24) (3)

Impact of Postulated N/A 0°F 0°F N/A 1540°F 1700OF Hydrogen-Oxygen Recombination (Ref. 25)

July 1, No Changes or Errors N/A N/A N/A N/A 1540°F 1700OF 2004 -

June 30, 2005 (1) GE1 I fuel was removed from the core at conclusion of Cycle 15, 10/2002 (2) GE14 fuel was first installed during RF15, 10/2002 (3) This item was inadvertently omitted from the 2002-2003 report Page 3 of 6

Attachrm ent to JAFP-05-0126 REFERENCES

1. NYPA letter, M. J. Colomb to USNRC (JAFP-00-0164), dated July 21, 2000, regarding reporting of changes and errors in ECCS evaluation models.

2. Entergy Nuclear Operations, Inc. letter, M. Kansler to USNRC, (JPN-01-010) dated June 4, 2001, regarding 10 CFR 50.46(a)(3)(ii) 30-day report, two errors in ECCS evaluation models.

3. Global Nuclear Fuel letter, A. Alzaben (GNF) to C. Franklin (NYPA), (AFA-00-NO61 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)

4. NEDC-23785-1-PA Rev. 1, "The GESTR-LOCA and SAFER Models for the Evaluation of the Loss-Of-Coolant Accident Volume II, SAFER - Long Term Inventory Model for BWR Loss-Of-Coolant Analysis," October 1984.

5. NEDC-23785-1 -PA Rev. 1, "The GESTR-LOCA and SAFER Models for the Evaluation of the Loss-Of-Coolant Accident Volume IlIl, SAFER/GESTR Application Methodology," October 1984.

6. General Electric Nuclear Energy Report, JI 1-03757SRL, August 2000, "Supplemental Reload Licensing Report for James A. FitzPatrick, Reload 14, Cycle 15."

7. 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.

8. General Electric Nuclear Energy Report, JI1-02914SRL, Revision 0, August 1996, "Supplemental Reload Licensing Report for James A. FitzPatrick, Reload 12, Cycle 13."

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

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

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

12. 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)

13. 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)

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Attachment to JAFP-05-0126

14. 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, (Propritary). r

15. Entergy letter, M. Kansler to USNRC, dated August 15, 2001 (JPN-01-0014) regarding "10 CFR 50.46 Annual Report - Errors in Emergency Core Cooling System (ECCS) Evaluation Models."

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

17. 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)

18. Entergy letter, M. Kansler to USNRC, dated August 14, 2002 (JPN-02-023) regarding "10 CFR 50.46 Annual Report - Errors in Emergency Core Cooling System (ECCS) Evaluation Models."

19. 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."

20. General Electric 10 CFR 50.46 Notification Letter 2003-01, dated May 6, 2003 regarding "Impact of SAFER LevelNolume Table Error on the Peak Cladding Temperature (PCT)." (Proprietary)

21. 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)

22. 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)

23. 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)

24. 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)

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

26. Entergy letter, T.A. Sullivan to USNRC, dated August 28, 2003 (JAFP-03-0124) regarding "10 CFR 50.46 Annual Report - Errors in Emergency Core Cooling System (ECCS) Evaluation Models."

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Attachment to JAFP-05-0126

27. Entergy letter, T.A. Sullivan to USNRC, dated August 23, 2004 (JAFP-04-0135) regarding "10 CRF 50.46 Annual Report - Errors in Emergency Core Cooling System (ECCS) Evaluation Models."

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