JAFP-09-0091, 10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System (ECCS) Evaluation Models

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

ML092160402
Person / Time
Site:	FitzPatrick
Issue date:	07/31/2009
From:	Joseph Pechacek Entergy Nuclear Northeast, Entergy Nuclear Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
JAFP-09-0091
Download: ML092160402 (8)

Text

Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.

James A. Fitzpatrick NPP

-Entergy" P.O. Box 110 Lycoming, NY 13093 Tel 315-342-3840 Joseph Pechacek Licensing Manager July 31, 2009 JAFP-09-0091 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. 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.

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 December 31, 2008 to July 31, 2009 for Entergy's James A. FitzPatrick Nuclear Power Plant (JAF).

There have been no changes to the Loss of Coolant Accident (LOCA) Peak Cladding Temperatures (PCTs) since the publication of Reference 1.

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

Jose h Pechacek at (315) 349-6766.

l sV tr ly y urs, ose h A. echace Licen ing Manager JP:mh cc: next page ACXoV-

JAFP-09-0091 Attachment 1 JAFP-09-0091 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 December 31, 2008 to July 31, 2009 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. 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-09-0091 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 December 31, 2008 to July 31, 2009

JAFP-09-0091 Attachment 1 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 December 31, 2008 to July 31, 2009 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 22). FitzPatrick has been operating with the same models and analysis as reported in the last update, see Reference 22.

Table 1 summarizes the current FitzPatrick ECCS evaluation models.

Page 1 of 5

JAFP-09-0091 Attachment 1 TABLE 1 - ACCOUNTING OF LICENSING BASIS PEAK CLAD TEMPERATURES FOR FITZPATRICK Estimated Updated PCT Change PCT Report Period ECCS GEl1 GE12 GE14 GEl1 GE12 GE14 Evaluation Fuel(1 ) Fuel(2) Fuel()3 Fuel Fuel Fuel 1993 FitzPatrick LOCA Baseline N/A N/A 1570°F N/A N/A Analysis (Ref. 2)

FitzPatrick Reload 12 Baseline Supplemental Report N/A Base- N/A N/A 1370°F N/A Evals. (Ref. 3) line FitzPatrick Reload 13 Supplemental Report Baseline N/A 1570°F 1370°F N/A (Ref. 4) 10 CFR 50.46 Notification Regarding Sensitivity To Small Input Parameter +50'F N/A 1620°F 1420°F N/A Changes Prior to (Ref. 5)

July 1, 10 CFR 50.46 Notification 2000 Regarding Minor Code +5'F N/A 1625 0F 1425 0F Corrections N/A (Ref. 5) 10 CFR 50.46 Notification Regarding Bottom Head +10°F N/A 1635 0 F 1435 0 F N/A Drain (Ref. 6) 10 CFR 50.46 Notification Regarding Time Step -5F N/A 1630°F 1430°F N/A Size (Ref. 1)

Estimated Effect Of Condensation Error On +90'F N/A 1720°F 1520°F N/A July 1, PCT (Ref. 7) 200e 0, Estimated Effect Of 2001 Pressure Rate +10°F N/A 1730°F 1530F N/A Inconsistency Error On PCT (Ref. 8)

Estimated Effect Of Accounting Error On PCT N/A -50 F N/A 1730°F 1525 0 F N/A (Ref. 9)

SAFER Core Spray July 1, Injection Elevation Error +5°F N/A 1735 0 F 1530°F N/A 2001 - (Ref. 10)

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

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JAFP-09-0091 Attachment 1 TABLE 1 - ACCOUNTING OF LICENSING BASIS PEAK CLAD TEMPERATURES FOR FITZPATRICK (Continued)

Estimated Updated PCT Change PCT Report ECCS Period Evaluation GE12 GE14 GNF2 GE12 GE14 GNF2 3 4 Fuel(2) Fuel( ) Fuel( ) Fuel Fuel Fuel Cycle 16 Core Load Using GE 14 Type Fuel N/A 1700°F N/A N/A 1700OF N/A (Ref. 12)

July 1 Impact of SAFER July Level/Volume Table Error on the PCT 0°F 0°F N/A 1540°F 1700OF N/A June 30, 2003 (Ref. 13)

Impact of SAFER Initial Separator Pressure Drop Error on the PCT 0OF N/A N/A 1540°F 1700OF N/A (Ref. 14)

Impact of GESTR Input File Interpolation Error on 0OF N/A N/A 1540°F 1700OF N/A the PCT (Ref. 15)

Impact of SAFER04 July 1, Computer Platform 0°F N/A N/A 1540OF 1700OF N/A 2003- Change on the PCT June 30, (Ref. 16) 2004 Impact of WEVOL S1 Volume Error on the PCT 0OF N/A N/A 1540°F 1700OF N/A (Ref. 17)

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

July 1, 2004 - No Changes or Errors June 30, (Ref. 19, Ref. 21) N/A N/A .N/A 1540°F 1700OF N/A 2006 -

July 1, Impact of Top Peaked 2006 - Power Shape for Small June 30, Break LOCA Analysis N/A N/A N/A 1540°F 1700OF N/A 2008 (Ref. 20)

July 1, Cycle 19 Core Load 2008 - Cycle 19 CoreLoad December Using GNF2 Type Fuel N/A N/A N/A N/A 1700OF 1800°F 30, 2008 (Ref. 20, Ref 22)

December 30, 2008 - No changes or errors July 31, (Ref. 22) N/A N/A N/A N/A 1700OF 1800°F 2009

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t I) L* I I TUel was removed from Wne core at conciusion OT uycle 15, IU/20UU (2) GE12 fuel was removed from the core at conclusion of Cycle 17, 10/2006 (3) GE1 4 fuel was first installed during RF15, 10/2002 (4) GNF2 fuel was first installed during RF18, 10/2008 Page 3 of 5

JAFP-09-0091 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/G ESTER-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."

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)

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JAFP-09-0091 Attachment 1 REFERENCES (continued):

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."

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