RA07-012, Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 Report

Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 Report

ML070950194
Person / Time
Site:	LaSalle
Issue date:	03/30/2007
From:	Enright D Exelon Generation Co, Exelon Nuclear
To:	Document Control Desk, NRC/NRR/ADRO
References
RA07-012
Download: ML070950194 (6)

Text

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Exelon Generation Company, LLC www.exeloncorp.com Nuclear LaSalle County Station 2601 North 21" Road Marseilles, IL61341-9757 RA07-012 March 30, 2007 10 CFR 50.46 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 LaSalle County Station, Units 1 and 2 Facility Operating License Nos. NPF-1 1 and NPF-1 8 NRC Docket Nos. 50-373 and 50-374

Subject:

Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 Report

Reference:

Letter from D. J. Enright (Exelon Generation Company, LLC) to U. S. NRC, "Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 Report," dated August 28, 2006 In accordance with 10 CFR 50.46, "Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors," Exelon Generation Company, LLC, (EGC) submits the enclosed attachments to fulfill the 30-day and annual reporting requirements for LaSalle County Station (LSCS), Units 1 and 2.

In the referenced letter, EGC reported the fuel peak cladding temperatures (PCTs) of 1460°F (including all assessments) for Units 1 and 2 for General Electric (GE) fuel, calculated based on an acceptable model. For the current reporting period there is no change in the PCT for the GE fuel.

The referenced letter also provided the Unit 2 PCT of 1832 0 F (including all assessments) for the AREVA NP (formerly Framatome Advanced Nuclear Power (FANP)) fuel based on an acceptable model for a mixed core of ATRIUM-9 and ATRIUM-10 with ATRIUM-9 being the limiting fuel type. Since the last evaluation, ATRIUM-9 fuel has been discharged from Unit 2 core making the ATRIUM-10 fuel the limiting fuel type. Because the PCT for the ATRIUM-10 fuel for Unit 2 is 1729 0 F, this is a change of over 50°F from the last evaluation using a NRC approved acceptable model. For Unit 1, there were no changes for the ATRIUM-10 fuel and the PCT remains at 1729 0 F.

Unit 1 and Unit 2 employ a mixed core design containing co-resident GE and AREVA NP fuel.

The Loss of Coolant Accident (LOCA) analyses of record for both GE and AREVA NP fuel are within all of the acceptance criteria set forth in 10 CFR 50.46.

/ OJ2Z

U. S. Nuclear Regulatory Commission March 30, 2007 Page 2 Attachments 1, and 2 provide PCT information for the limiting LOCA evaluations for LSCS, Units 1 and 2, including all assessments as of February 1, 2007. The assessment notes are contained in Attachment 3 and provide a detailed description for each change reported.

Should you have any questions concerning this letter, please contact Mr. Terrence W. Simpkin, Regulatory Assurance Manager, at (815) 415-2800.

Respectfully, Daniel J. Enrightj Plant Manager LaSalle County Station Attachments cc: Regional Administrator - NRC Region III NRC Senior Resident Inspector - LaSalle County Station

bcc: Norha Plumey Salauddin Ahmed (NFM)

NRC Project Manager - NRR (Stephen Sands)

Office of Nuclear Facility Safety - IEMA DCD Licensing (hard copy and electronic)

Correspondence file (P. Holland)

Attachment 1 LaSalle Units 1 and 2 10 CFR 50.46 Report (GE Fuel)

PLANT NAME: LaSalle Units I and 2 ECCS EVALUATION MODEL: SAFER/GESTR LOCA REPORT REVISION DATE: February 1, 2007 CURRENT OPERATING CYCLES: L1C12 and L2C12 ANALYSIS OF RECORD Evaluation Model Methodology: NEDE-23785-1-PA, Rev. 1, "GESTR-LOCA and SAFER Models for the Evaluation of the Loss-of-Coolant Accident (Volume III),

SAFER/GESTR Application Methodology", October 1984.

Calculation: GE-NE-0000-0022-8684-R2, "Exelon LaSalle Units I and 2 SAFER/GESTR Loss-of-Coolant Accident Analysis for GE 14 Fuel," November 2006.

Fuel: GEl4 Limiting Single Failure: HPCS Diesel Generator Limiting Break Size and 0.08 ft2 Recirculation Pump Suction Line Break Location:

Reference PCT: 1460OF MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS TF 10CFR50.46 report dated August 28, 2006 (Note 1) APCT = 0 Net PCT 1460 OF B. CURRENT LOCA MODEL ASSESSMENTS None N/A Total PCT change from current assessments XAPCT = 0°F Cumulative PCT change from current assessments YX I APCT I= 0°F Net PCT 1460 -F

Attachment 2 LaSalle Units 1 and 2 10 CFR 50.46 Report (AREVA NP Fuel Formerly FANP)

LaSalle Units I and 2 PLANT NAME:

ECCS EVALUATION MODEL: EXEM BWR-2000 Evaluation Model REPORT REVISION DATE: February 1, 2007 CURRENT OPERATING CYCLES: L1CI2 and L2C12 ANALYSIS OF RECORD Evaluation Model Methodology: EMF-2361 (P)(A) Revision 0, EXEM BWR-2000 ECCS Evaluation Model, Framatome ANP, May 2001.

Calculation: EMF-3230 (P) Revision 0, LaSalle Units 1 and 2 EXEM BWR-2000 LOCA Break Spectrum Analysis for ATRIUM - 10 Fuel, November 2005.

EMF-3231 (P) Revision 0, LaSalle Units 1 and 2 EXEM BWR-2000 LOCA-ECCS Analysis MAPLHGR Limit for ATRIUM - 10 Fuel, November 2005.

Fuel: ATRIUM- 10 Limiting Single Failure: Low-pressure coolant injection Diesel Generator Limiting Break Size and Double Ended Guillotine/0.8 discharge coefficient of Recirculation Location: Pump Suction Piping Reference PCT: 1729 OF MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS 10CFR50.46 report dated August 28, 2006 (Note 2) APCT = 0 °F Net PCT 1729 OF B. CURRENT LOCA MODEL ASSESSMENTS None N/A Total PCT change from current assessments TAPCT = 0°F Cumulative PCT change from current assessments Y IAPCT I=0F Net PCT 1729 OF

Attachment 3 LaSalle Units 1 and 2 10 CFR 50.46 Report (Assessment Notes)

1. Prior LOCA model assessment for GE Fuel To address the impact of axial power shape on the small break LOCA (SBLOCA) a complete SBLOCA break spectrum analysis was performed in November 2006. Additionally all reported 10CFR50.46 errors/issues that affect small break ECCS-LOCA analysis have been accounted for in this analysis. As reported in Reference 1, the large break LOCA (LBLOCA) is non-limiting.

There are no input errors, code errors, or modeling changes have been identified that would require adjustment to the LBLOCA results reported in Reference 1.

[

Reference:

1. Letter from Daniel J. Enright (Exelon) to U.S. NRC, "Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 Report," dated August 28, 2006.]

2. Prior LOCA Model Assessment for AREVA fuel An AREVA NP (formerly FANP) LOCA evaluation was performed in November 2005 due to the discharge of ATRIUM -9 fuel and the reanalysis of the ATRIUM-10 fuel for LIC 12. This analysis was reported to the NRC in Reference 1. The AREVA NP analysis for L2C 12 demonstrated that the LOCA analysis performed for L1C12 in November 2005 is applicable to L2C 12. Since the performance of November 2005 LOCA analysis, no input error, code errors, or modeling changes have been identified which would require adjustment to the results. The referenced letter also provided the Unit 2 PCT of 1832 'F (including all assessments) for the AREVA NP fuel based on an acceptable model for a mixed core of ATRIUM-9 and ATRIUM- 10 with ATRIUM-9 being the limiting fuel type. Since the last evaluation, ATRIUM-9 fuel has been discharged from Unit 2 core, making the ATRIUM-10 fuel the limiting fuel type. Because the PCT for the ATRIUM-10 fuel for Unit 2 is 1729 'F, this is a change of over 50 'F from the last evaluation using a NRC approved acceptable model. For Unit 1, there were no changes for the ATRIUM- 10 fuel and the PCT remains at 1729 'F.

[

Reference:

1. Letter from Daniel J. Enright (Exelon) to U.S. NRC, "Plant Specific ECCS Evaluation Changes - 10CFR 50.46 Report," dated August 28, 2006.]