JAFP-06-0127, CFR 50.46 Annual Report - Errors in Emergency Core Cooling System (ECCS) Evaluation Models

CFR 50.46 Annual Report - Errors in Emergency Core Cooling System (ECCS) Evaluation Models

ML062340339
Person / Time
Site:	FitzPatrick
Issue date:	08/14/2006
From:	Jim Costedio Entergy Nuclear Northeast, Entergy Nuclear Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
JAFP-06-0127
Download: ML062340339 (7)

Text

Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.

James A. Fitzpatrick NPP P.O. Box 110 SEntergy Lycoming, NY 13093 Tel 315 342 3840 August 14,2006 JAFP-06-0127 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-05-0126), dated August 17, 2005, 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, 2005 to June 30, 2006 for Entergy's James A. FitzPatrick Nuclear Power Plant.

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

This letter contains no new commitments. If you have any questions, please contact Mr. Jim Costedio at (315) 349-6358.

Very iurs Jim Costedio Regulatory Compliance Manager

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, 2005 to June 30, 2006

-r, cc:

Mr. Samuel J. Collins Regional Administrator, Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 Resident Inspector's Office U.S. Nuclear Regulatory Commission James A. FitzPatrick Nuclear Power Plant P.O. Box 136 Lycoming, NY 13093-0136 Mr. John P. Boska, 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

Attachment to JAFP-06-0127 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, 2005 to June 30, 2006 for Entergy's James A. FitzPatrick Nuclear Power Plant.

No changes or errors to the FitzPatrick models have been identified since the last annual report (Reference 19). Therefore, a 30 day report for errors that qualify as significant changes is not required.

Table I summarizes the current FitzPatrick ECCS evaluation models.

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Attachment to JAFP-06-0 127 TABLE 1 - ACCOUNTING OF LICENSING BASIS PEAK CLAD TEMPERATURES FOR FITZPATRICK Report Estimated Updated Period PCT Change PCT ECCS Evaluation GEl GEl2 GE14 GEll GE12 GEl4 Fuel(') Fuel Fuel(2 ) Fuel Fuel Fuel Baseline 1993 FitzPatrick LOCA Baseline N/A N/A 1570OF N/A N/A Evals. Analysis (Ref. 2)

FitzPatrick Reload 12 N/A Base- N/A N/A 1370OF N/A Supplemental Report line (Ref. 3)

FitzPatrick Reload 13 N/A 1570OF 1370OF N/A Supplemental Report Baseline (Ref. 4)

Prior to 10 CFR 50.46 +50°F N/A 1620OF 1420OF N/A July 1, Notification Regarding 2000 Sensitivity To Small Input Parameter Changes (Ref. 5) 10 CFR 50.46 +50F N/A 1625 0F 1425 0 F N/A Notification Regarding Minor Code Corrections (Ref. 5) 10 CFR 50.46 +100 F N/A 1635 0F 1435 0F N/A Notification Regarding Bottom Head Drain (Ref. 6)

July 1, 10 CFR 50.46 -5F N/A 1630°F 1430°F N/A 2000- Notification Regarding June 30, Time Step Size (Ref. 1) 2001 Estimated Effect Of +90°F N/A 1720WF 1520OF N/A Condensation Error On PCT (Ref. 7)

Estimated Effect Of +10WF N/A 1730OF 1530F N/A Pressure Rate Inconsistency Error On PCT (Ref. 8)

Estimated Effect Of N/A -5WF N/A 1730WF 1525 0 F N/A Accounting Error On PCT (Ref. 9)

July 1, SAFER Core Spray +50 F N/A 1735WF 1530WF N/A 2001 - Injection Elevation Error June30, (Ref. 10) 2002 Impact of SAFER Bulk +100F N/A 1745WF 1540WF N/A Water Level Error on PCT (Ref. 11)

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Attachment to JAFP-06-0127 TABLE 1 - ACCOUNTING OF LICENSING BASIS PEAK CLAD TEMPERATURES FOR FITZPATRICK (Continued)

Report Estimated Updated Period PCT Change PCT ECCS Evaluation GEll GE12 GE14 GElI GE12 GE14 Fuel(') Fuel Fuel(2 ) Fuel Fuel Fuel July 1, Cycle 16 Core Load N/A N/A 1700OF N/A N/A 1700OF 2002 - Using GE 14 Type Fuel June 30, (Ref. 12) 2003 Impact of SAFER N/A 00 F 00 F N/A 1540OF 1700OF Level/Volume Table Error on the PCT (Ref. 13)

Impact of SAFER Initial N/A 00 F N/A N/A 1540°F 1700OF Separator Pressure Drop Error on the PCT (Ref. 14)

July 1, Impact of GESTR Input N/A 0°F N/A N/A 1540OF 1700OF 2003 - File Interpolation Error June 30, on the PCT (Ref. 15) 2004 Impact of SAFER04 N/A 0°F N/A N/A 1540OF 1700OF Computer Platform Change on the PCT (Ref. 16)

Impact of WEVOL S1 N/A 0°F N/A N/A 1540OF 1700OF Volume Error on the PCT (Ref. 17)

Impact of Postulated N/A 0°F 0°F N/A 1540OF 1700OF Hydrogen-Oxygen Recombination (Ref. 18)

July 1, No Changes orErrors N/A N/A N/A N/A 1540OF 1700OF 2004-June 30, 2006 (1) GEl 1 fuel was removed from the core at conclusion of Cycle 15, 10/2002 (2) GE14 fuel was first installed during RF15, 10/2002 Page 3 of 5

Attachment to JAFP-06-0127 REFERENCES

1. Global Nuclear Fuel letter, A. Alzaben (GNF) to C. Franklin (NYPA), (AFA 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, J1 1-02914SRL, Revision 0, August 1996, "Supplemental Reload Licensing Report for James A. FitzPatrick, Reload 12, Cycle 13."

4. 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."

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)

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Attachment to JAFP-06-0127

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."

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 CRF 50.46 Annual Report - Errors in Emergency Core Cooling System (ECCS) Evaluation Models."

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