ML050770441

Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 Report

ML050770441
Person / Time
Site:	LaSalle
Issue date:	03/09/2005
From:	Enright D Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML050770441 (6)

Text

.7 ExekepnM Exelon Generation Company, LLC LaSalle County Station 2601 North 21'Road Marseilles, IL 61341-9757 www.exelonCoTp.Com1 Nuclear March 9, 2005 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

Reference:

Plant Specific ECCS Evaluation Changes-10 CFR 50.46 Report Letter from S. R. Landahl (Exelon Generation Company, LLC) to U. S. NRC, uPlant Specific ECCS Evaluation Changes -

10 CFR 50.46 Report," dated March 9, 2004.

In accordance with 10 CFR 50.46, 'Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors," Exelon Generation Company (EGC), LLC, submits the enclosed attachments to fulfill the 30-day and annual reporting requirements for LaSalle County Station, Units 1 and 2. In the referenced letter, EGC reported the fuel peak cladding temperatures (PCTs) calculated based on an acceptable model to be 1380 0F for General Electric (GE) fuel. The referenced letter also provided the PCT of 1807 0F for the FANP fuel based on an acceptable model. Additionally, the referenced letter estimated the effects of changes that occurred since the PCT values had been calculated using an acceptable model. These changes resulted in an increase of 25 0F to 1832 0F for FANP fuel. Since the last evaluation, GE14 fuel has also been introduced into Unit

2. As a result, a new analysis was performed to bound both LaSalle units. Based on the new analysis, the PCT for GE fuel increased to a value of 1400 0F. This is a change of 20'F from the last evaluation using an acceptable model. There were no changes for the FANP fuel and the PCT remains at 18320F.

Unit 1 and Unit 2 employ a mixed core design containing co-resident GE and FANP fuel. The Loss of Coolant Accident (LOCA) analyses of record for both GE and FANP fuel are within all of the acceptance criteria set forth in 10 CFR 50.46.

Attachments 1 and 2 provide PCT information for the limiting LOCA evaluations for LaSalle County Station, Units 1 and 2, including all assessments as of February 1, 2005. The assessment notes are contained in Attachment 3 and provide a detailed description for each change or error reported.

U. S. Nuclear Regulatory Commission March 9, 2005 Page 2 Should you have any questions concerning this letter, please contact Mr. Terrence W. Simpkin, Regulatory Assurance Manager, at (815) 415-2800.

Respectfully, Daniel J. Enright Plant Manager LaSalle County Station Attachments cc:

Regional Administrator - NRC Region IlIl NRC Senior Resident Inspector - LaSalle County Station

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

PLANT NAME:

ECCS EVALUATION MODEL:

REPORT REVISION DATE:

CURRENT OPERATING CYCLES:

LaSalle Units 1 and 2 SAFER/GESTR LOCA February 1, 2005 LICI I and L2C1I

• 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:

"Project Task Report, Exelon LaSalle Unit I and 2 SAFER/GESTR Loss-of-Coolant Accident Analysis for GE 14 Fuel," GE report number GE-NE-0000-0022-8684-RI, dated December 2004.

Fuel:

GE14 Limiting Single Failure:

Limiting Break Size and Location:

Reference PCT:

HPCS Diesel Generator Double Ended Guillotine of Recirculation Pump Suction Piping 14000F MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS A GE LOCA analysis was performed in December 2004 to support the introduction APCT =0 0 F of GE 14 for L2C1 1. This analysis bounds both LaSalle Units and addressed all errors and issues.

Net PCT 1400 OF B. CURRENT LOCA MODEL ASSESSMENTS None N/A Net PCT 1400 'F

• Currently Unit 2 in refueling. Expected startup - March 12, 2005 LaSalle Units I and 2 10 CFR 50.46 Report (FANP Fuel)

PLANT NAME:

ECCS EVALUATION MODEL:

REPORT REVISION DATE:

CURRENT OPERATING CYCLE:

LaSalle Units I and 2 EXEM BWR Evaluation Model February 1, 2005 LICI I and L2CI I

• ANALYSIS OF RECORD Evaluation Model Methodology:

Advanced Nuclear Fuels Corporation Methodology for Boiling Water Reactors EXEM BWR Evaluation Model, ANF 048(P)(A), January 1993.

BWVR Jet Pump Model Revision for RELAX, ANF-91-048(P)(A),

Supplement I and Supplement 2, Siemens Power Corporation, October 1997.

Calculation:

1.

LaSalle LOCA-ECCS Analysis MAPLHGR Limits for ATRIUMTNI-9B Fuel, EMF-2175(P), March 1999.

2.

LOCA Break Spectrum Analysis for LaSalle Units I and 2, EMF-2174(P), March 1999.

3.

LaSalle Units I and 2 LOCA-ECCS Analysis MAPLHGR Limit for ATRIUMTM-1 0 Fuel, EMF-2641 (P), November 2001.

4.

LaSalle Units I and 2 LOCA Break Spectrum Analysis for ATRIUMT^'-I 0 Fuel, EMF-2639(P), November 2001.

Fuel:

Limiting Fuel Limiting Single Failure:

Limiting Break Size and Location:

Reference PCT:

MARGIN ALLOCATION ATRIUMTN.-9B and ATRIUMTNI-10 ATRIUMTN.-9B HPCS Diesel Generator 1.1 ft2 Recirculation Pump Discharge Side Line Break 1807 OF A. PRIOR LOCA MODEL ASSESSMENTS 10 CFR 50.46 report dated May 7, 999 (See Note 2)

APCT= 00 F 10 CFR 50.46 report dated February 9,2000 (See Note 3)

APCT =18 IF 10 CFR 50.46 report dated June 12, 2000 (See Note 4)

APCT = 0 IF 10 CFR 50.46 report dated June 8, 2001 (See Note 5)

APCT = 0 IF 10 CFR 50.46 report dated June 8, 2002 (See Note 6)

APCT = 2 IF 10 CFR 50.46 report dated June 9, 2003 (See Note 7)

APCT = 5 IF 10 CFR 50.46 report dated March 9, 2004 (See Note I)

APCT = 0 IF Net PCT 1832 OF B. CURRENT LOCA MODEL ASSESSMENTS No errors/issues for this reporting period APCT = 0 0 F Net PCT 1832 OF

• Currently Unit 2 in refueling. Expected startup - March 12, 2005 LaSalle Units I and 2 10 CFR 50.46 Report (FANP Fuel)

1. Prior LOCA model assessment for FANP fuel During the startup of LaSalle Unit I Cycle 11 several evaluations were performed for FANP LOCA analysis as reported in the Reference. The net results of these evaluations were that there was a zero degree PCT impact.

Additionally a problem was also identified by FANP pertaining with the transfer of RELAX coolant temperature data from PREHUXY to HUXY at the time of core spray. FANP determined that the impact this problem on the limiting break spectrums results was zero degree. This was also reported in the Reference.

[

Reference:

Letter from Susan R Landahl (Exelon) to U.S. NRC, "Plant Specific ECCS Evaluation Changes -

10 CFR 50.46 Report," dated March 9, 2004.]

2.

Prior LOCA Model Assessment for FANP fuel The May 1999 LOCA model assessment was a new analysis of record for Framatome (Formerly Siemens) due to the introduction of ATRIUM-9B fuel into the Unit 2 Cycle 8 core. Therefore, there is no PCT change.

Analysis was performed for a core power of 3722 MWt that bounds the current uprated power of 3489 MWt.

[

Reference:

Letter from J. A. Benjamin (ComEd) to U.S. NRC, "Report of Significant Change in Calculated Peak Cladding Temperature (PCT) - IOCFR 50.46 Report," dated May 7, 1999.]

3.

Prior LOCA Model Assessment for FANP fuel The February 2000 50.46 report assessed the impact of errors in the LOCA evaluation model.

[

Reference:

Letter from J. A. Benjamin (ComEd) to U.S. NRC, "Plant Specific ECCS Evaluation Changes -

I OCFR 50.46 Report," dated February 9,2000.]

4.

Prior LOCA Model Assessment for FANP fuel The June 2000 10 CFR 50.46 report does not have any PCT assessment for ATRIUM-9B fuel.

[

Reference:

Letter from C. G. Pardee (ComEd) to U.S. NRC, "Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 Report," dated June 12,2000.]

5.

Prior LOCA model assessment for FANP fuel The reference letter assessed impact of Unit 2 LPCS riser leakage, errors in FANP LOCA analysis model and Unit 2 Cycle 9 reload fuel.

[

Reference:

Letter from M. A Schiavoni (Exelon) to U.S. NRC, "Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 Report," dated June 8,2001.]

6.

Prior LOCA model assessment for FANP fuel The referenced letter assessed impact of errors in FANP LOCA analysis model, Unit I Cycle 10 reload fuel and ATRIUM-9B exposure extension.

[

Reference:

Letter from M. A Schiavoni (Exelon) to U.S. NRC, "Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 Report," dated June 8, 2002.]

LaSalle Units I and 2 10 CFR 50.46 Report (FANP Fuel)

7. Prior LOCA model assessment for FANP fuel The June 2003 50.46 report assessed the impact of errors in the LOCA evaluation, Unit 2 jet pump leakage, Unit 2 Cycle 10 reload Fuel and the Unit I mid-cycle reload.

[

Reference:

Letter from Susan R Landahl (Exelon) to U.S. NRC, "Plant Specific ECCS Evaluation Changes -

10 CFR 50.46 Report," dated June 9, 2003.]