JAFP-03-0124, 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

ML032530238
Person / Time
Site:	FitzPatrick
Issue date:	08/28/2003
From:	Ted Sullivan Entergy Nuclear Northeast, Entergy Nuclear Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
JAFP-03-0124
Download: ML032530238 (8)

Text

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 28, 2003 Site Vice President - JAF JAFP-03-0124 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station O-P1-17 Washington, DC 20555-0001

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

REFERENCES:

1. Entergy Nuclear Operations, Inc. letter T.A. Sullivan to USNRC (JAFP-02-0210) dated November 12, 2002 regarding same subject.

2. Entergy Nuclear Operations, Inc. letter M. Kansler to USNRC (JPN-02-023) dated August 14, 2002 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(aX3)(ii) for the period July 1, 2002 to June 30, 2003 for Entergy's James A. FitzPatrick Nuclear Power Plant.

A total of one change and two errors to the FitzPatrick model have been identified since the last report (Reference 2). Reference 1 document was submitted by FitzPatrick to the NRC in November 2002, following the completion of the plant's Refueling Outage 15 to inform the Commission that operations (commencing with Cycle 16) would be utilizing both General Electric 14 type fuel (GE 14) and General Electric 12 type fuel (GE 12).

This change and the calculated peak clad temperature (PCT) for GE 14 are reflected on the attached summary sheets. For the remaining two errors, thirty day reports were not submitted because they did not qualify as a significant change (a peak clad temperature change of greater than 500 F) according to 10 CFR 50.46(a)(3)(i).

Corrected for these errors, estimated peak clad temperatures (PCTs) are unchanged from the previous reports and remain below the 22000 F requirement of 10 CFR 50.46(b)(1).

This letter contains no new commitments. If you have any questions, please contact Mr. Andrew Halliday at (315) 349-6055 (eW 't 1.ict T. A. SULLIVAN cc: 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 P.O. Box 136 Lycoming, NY 13093 Mr. Guy Vissing, Project Manager Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop: 8C2 Washington, DC 20555

Attachment:

Annual 10 CFR 50.46(a)(3)(ii) Report on Changes and Errors in Emergency Core Cooling System (ECCS) Evaluation Models for the period from July 1, 2002 to June 30, 2003.

Attachment to JAFP-03-0124 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, 2002 to June 30, 2003 for Entergy's James A. FitzPatrick Nuclear Power Plant.

A total of one (1) change and two (2) errors to the FitzPatrick model have been identified since the last annual report (Reference 18). The change was reported to the Commission (Reference 19) following completion of the plant's fall 2002 Refuel Outage 15. Thirty-day reports were not submitted for the two errors because they do not qualify as a significant changes (a peak clad temperature [PCT] change of greater than 500 F) according to 10 CFR 50.46(a)(3)(i).

Table 1 summarizes the changes and errors to the current FitzPatrick ECCS evaluation models. The last three entries represent ECCS evaluation changes or errors identified during the period July 1, 2002 to June 30, 2003.

Additional information on the change and errors identified during the reporting period is provided below.

DISCUSSION OF CHANGES OR ERRORS IDENTIFIED DURING REPORTING PERIOD USE OF GENERAL ELECTRIC 14 TYPE FUEL The plant completed Refueling Outage 15 (October 2002), and began Cycle 16 operations utilizing both General Electric 14 type fuel (GE14) and General Electric 12 type fuel (GE12). GE12 has been use during the previous three operating cycles. The Licensing Basis peak clad temperature (PCT) calculated for GE14 is 1700° Fahrenheit (F), increasing the previous calculated PCT value by 160'F. PCT calculations for GE12/GE14 are based on the same NRC approved GE methods. The PCT increase is a result of: (1) higher Linear Heat Generation Rate (LHGR) for GE14; (2) lower assumed Core Spray System flow rate; and (3) a wider band of operating conditions including Maximum Extended Loadline Limit Analysis and Final Feedwater Temperature reduction.

SAFER Level/Volume Table Error In 10 CFR 50.46 Notification Letter 2003-01, dated May 6,2003 (Ref 19), General Electric reported an error in the process for constructing the initial level/volume table in the SAFER. It was assumed that the value of initial water level was the same as the volume break point in the original RPV level/volume calculation. However, the level/volume tables were generated with revised initial water levels, which did not consider this assumption. This error resulted in an incorrect volume split in the nodes above and below the water surface, and incorrect initial liquid mass. The total volume in the mass was correct.

I

Attachment to JAFP-03-0124 This error did not result in a change in PCT. Therefore, this error did not qualify as a significant change according to 10 CFR 50.46(a)(3)(i), and no 30-day report was submitted.

SAFER Initial Separator Pressure Drop Error In 10 CFR 50.46 Notification Letter 2003-03, dated May 6, 2003 (Ref. 20), General Electric reported calculation errors in determining the initial steam separator pressure drop value. These errors resulted in a higher initial steam separator pressure drop and overly restricted the flow through the separator during the LOCA event.

These errors did not result in any changes to PCT. Therefore, these errors did not qualify as a significant change according to 10 CFR 50.46(a)(3)(i) and no 30-day report was submitted.

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Attachment to JAFP-03-0124 TABLE I - ACCOUNTING OF LICENSING BASIS PEAK CLAD TEMPERATURES FOR FITZPATRICK (NOTE: GE11 FUEL REMOVED FROM CORE DURING JAF's REFUEL 15 OUTAGE)

Report Estimated Updated Period PCT Change PCT ECCS Evaluation GE11 GE12 GE14 GE11 GE12 GE14 Fuel Fuel Fuel Fuel Fuel Fuel (Removed at (Installed conclusion of during Cycle 15, RFIS, 10/2002) 10/2002)

Baseline 1993 FitzPatrick LOCA Baseline N/A N/A 1570°F N/A N/A Evals. Analysis (Ref. 7)

FitzPatrick Reload 12 N/A Base- N/A N/A 1370°F N/A Supplemental Report line (Ref. 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 Smal Input Parameter Changes (Ref. 10) 10 CFR 5OA6 +5 0 F N/A 1625°F 1425°F N/A Notification Regarding Minor Code Corrections (Ref. 10) 10 CFR 50A6 +10°F N/A 1635°F 1435°F N/A Notification Regarding Bottom Head Drain (Ref. 11) _

July 1, 10 CFR 50.46 -SF N/A 1630°F 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 -5 0 F N/A 1730°F 1525°F N/A Accounting Error On PCT (Ref. 14) 3

I Attachment to JAFP-03-0124 TABLE I - ACCOUNTING OF LICENSING BASIS PEAK CLAD TEMPERATURES FOR FITZPATRICK (Continued)

Report Estimated Updated Period PCT Change PCT ECCS Evaluation GEll GE12 GE14 GEll GE12 GE14 Fuel Fuel Fuel Fuel Fuel Fuel (Removed at (Installed conclusion of during Cycle 15, RF1S, 10/2002) 10/2002)

July 1, SAFER Core Spray +5 0 F N/A 1735 0 F 15300 F N/A 2001 - Injection Elevation Error June 30, (Ref. 16) 2002 Impact of SAFER Bulk +10 0 F N/A 1745 0 F 15400 F N/A Water Level Error on the Peak Clad Temperature (Ref. 17)

July 1, Cycle 16 Core Load N/A N/A 17000 F N/A N/A 1700OF 2003- Using GE 14 Type Fuel (Fuel type June 30, (Ref. 19) no longer 2003 in use)

Impact of SAFER N/A 0 0F0 F N/A 15400 F 17000 F LevelVolume Table Error on the Peak Clad Temperature (PCT)

(Ref. 20)

Impact of SAFER Initial N/A OOF N/A N/A 15400 F 17000 F Separator Pressure Drop (ECCS-Error on the Peak Clad LOCA Temperature (PCT) analyses (Ref. 21) not affected by error) 4

-> - t Attachment to JAFP-03-0124 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-0O-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)

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, J1 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 IlIl (proprietary), Revision 2, April 1993.

8. General Electric Nuclear Energy Report, JI 1-02914SRL, Revision 0, August 1996, "Supplemental Reload Licensing Report for James A. FitzPatrick, Reload 12, Cycle 13."

9. General Electric Nuclear Energy Report, J1 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) 5

^ - w; Attachment to JAFP-03-0124 REFERENCES (CONT.)

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)

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, (Proprietary).

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. Kanslerto 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 LeveWolume 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) 6