ML13126A116

10 CFR 50.46 Annual Report

ML13126A116
Person / Time
Site:	Millstone, Quad Cities
Issue date:	05/03/2013
From:	Gullott D M Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RS-13-104
Download: ML13126A116 (4)

Text

4300 Winfield Road Warrenvi0le, IL 60555 630 657 2000 Office 10 CFR 50.46

^-- Exelon Generation:

RS-13-104 May 3, 2013 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265

Subject:

10 CFR 50.

46 Annual Report

Reference:

Letter from D. M. Gullott (Exelon Generation Company, LLC) to U.S. NRC,"10 CFR 50.46, 'Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors,' Annual Report," dated May 4, 2012 This letter provides the annual report required by 10 CFR 50.46, "Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors," for Quad Cities Nuclear Power Station (QCNPS), Units 1 and 2. The attachments describe the changes in accumulated peak cladding temperature (PCT) since the previous annual report submitted in the referenced letter.

There are no regulatory commitments contained in this letter. Should you have any questions concerning this letter, please contact Mr. Kenneth M. Nicely at (630) 657-2803.

David M. Gullott Manager -Licensing Attachments:

1.Quad Cities Nuclear Power Station Unit 1, 10 CFR 50.46 Report (Westinghouse Fuel) 2.Quad Cities Nuclear Power Station Unit 2, 10 CFR 50.46 Report (Westinghouse Fuel) 3.Quad Cities Nuclear Power Station Units 1 and 2, 10 CFR 50.46 Report Assessment Notes cc:NRC Regional Administrator, Region III NRC Senior Resident Inspector, Quad Cities Nuclear Power Station) 1 Exelon May 3,2013 U.S. Nuclear Regulatory Commission A TIN: Document Control Desk Washington, DC 20555-0001 Quad Cities Nuclear Power Station, Units 1 and 2 4300 Winfield Road Warrenville, IL 60555 630 657 2000 Office Renewed Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265

Subject:

10 CFR 50.46 Annual Report 10 CFR 50.46

Reference:

Letter from D. M. Gullott (Exelon Generation Company, LLC) to U.S. NRC, "10 CFR 50.46, 'Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors,'

Annual Report, II dated May 4, 2012 This letter provides the annual report required by 10 GFR 50.46, "Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors, II for Quad Cities Nuclear Power Station (QCNPS), Units 1 and 2. The attachments describe the changes in accumulated peak cladding temperature (PCT) since the previous annual report submitted in the referenced letter. There are no regulatory commitments contained in this letter. Should you have any questions concerning this letter, please contact Mr. Kenneth M. Nicely at (630) 657-2803.

David M. Gullott Manager -Licensing Attachments:

1. Quad Cities Nuclear Power Station Unit 1, 10 CFR 50.46 Report 0/'1 estinghouse Fuel) 2. Quad Cities Nuclear Power Station Unit 2, 10 CFR 50.46 Report 0/'Iestinghouse Fuel) 3. Quad Cities Nuclear Power Station Units 1 and 2, 10 CFR 50.46 Report Assessment Notes cc: NRC Regional Administrator, Region III NRC Senior Resident Inspector, Quad Cities Nuclear Power Station ATTACHMENT 1 Quad Cities Nuclear Power Station Unit 1, 10 CFR 50.46 Report (Westinghouse Fuel)

PLANT NAME:Quad Cities Unit 1 ECCS EVALUATION MODEL:USA5 REPORT REVISION DATE:05/03/2013 CURRENT OPERATING CYCLE:

23 ANALYSIS OF RECORD Evaluation Model:"Westinghouse BWR ECCS Evaluation Model:

Supplement 3 to Code Description, Qualification and Application to SVEA-96 Optima2 Fuel," WCAP-1 6078-P-A, November 2004 Calculations: "Quad Cities 1 & 2 LOCA Analysis for SVEA-96 Optima2 Fuel," OPTIMA2-TR021QC-LOCA, Revision 5, Westinghouse Electric Company, LLC, September 2009 Fuel Analyzed in Calculation:SVEA-96 Optima2 Limiting Fuel Type:SVEA-96 Optima2 Limiting Single Failure:Low Pressure Coolant Injection System injection valve Limiting Break Size and1.0 double-ended guillotine break in the recirculation pump Location:suction line Reference Peak CladdingPCT = 2150°F Temperature (PCT):

MARGIN ALLOCATION A.PRIOR LOCA MODEL ASSESSMENTS 10 CFR 50.46 Report dated May 7, 2010 See Note 1)

APCT = 11 °F 10 CFR 50.46 Report dated May 6, 2011 (See Note 2)

APCT = 0°F 10 CFR 50.46 Report dated May 4, 2012 (See Note 3)

APCT = 18°F Net PCT 2179°F B.CURRENT LOCA MODEL ASSESSMENTS None (See Note 4)

APCT = 0°F Total PCT change from current assessments Y_APCT = 0°F Cumulative PCT change from current assessments Y_11 APCT I= 0°F Net PCT 2179°F ATTACHMENT 1 Quad Cities Nuclear Power Station Unit 1, 10 CFR 50.46 Report (Westinghouse Fuel) PLANT NAME: ECCS EVALUATION MODEL: REPORT REVISION DATE: CURRENT OPERATING CYCLE: ANALYSIS OF RECORD Quad Cities Unit 1 USA5 05/03/2013 23 Evaluation Model: "Westinghouse BWR ECCS Evaluation Model: Supplement 3 to Code Description, Qualification and Application to SVEA-96 Optima2 Fuel, II WCAP-16078-P-A, November 2004 Calculations:

IIQuad Cities 1 & 2 LOCA Analysis for SVEA-96 Optima2 Fuel," OPTIMA2-TR021 QC-LOCA, Revision 5, Westinghouse Electric Company, LLC, September 2009 Fuel Analyzed in Calculation:

SVEA-96 Optima2 Limiting Fuel Type: SVEA-96 Optima2 Limiting Single Failure: Low Pressure Coolant Injection System injection valve Limiting Break Size and 1.0 double-ended guillotine break in the recirculation pump Location:

suction line Reference Peak Cladding PCT = 2150°F Temperature (PCT): MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS 10 CFR 50.46 Report dated May 7, 2010 (See Note 1)

= 11°F 10 CFR 50.46 Report dated May 6, 2011 (See Note 2)

= OaF 10 CFR 50.46 Report dated May 4, 2012 (See Note 3)

= 18°F Net PCT 2179°F B. CURRENT LOCA MODEL ASSESSMENTS None (See Note 4)

= OaF Total PCT change from current assessments

= OaF Cumulative PCT change from current assessments L I I = OaF Net PCT 2179°F ATTACHMENT 2 Quad Cities Nuclear Power Station Unit 2, 10 CFR 50.46 Report (Westinghouse Fuel)

Quad Cities Unit 2 USA5 05/03/2013 22"Westinghouse BWR ECCS Evaluation Model:

Supplement 3 to Code Description, Qualification and Application to SVEA-96 Optima2 Fuel," WCAP-1 6078-P-A, November 2004"Quad Cities 1 & 2 LOCA Analysis for SVEA-96 Optima2 Fuel," OPTIMA2-TR021QC-LOCA, Revision 5, Westinghouse Electric Company, LLC, September 2009 Fuel Analyzed in Calculation:SVEA-96 Optima2 Limiting Fuel Type:SVEA-96 Optima2 Limiting Single Failure:Low Pressure Coolant Injection System injection valve Limiting Break Size and1.0 double-ended guillotine break in the recirculation pump Location:suction line Reference Peak CladdingPCT = 2150°F Temperature (PCT):

MARGIN ALLOCATIONA.PRIOR LOCA MODEL ASSESSMENTS 10 CFR 50.46 Report dated May 7, 2010 (See Note 1)

APCT = 11 °F 10 CFR 50.46 Report dated May 6, 2011 (See Note 2)

APCT = 0°F 10 CFR 50.46 Report dated May 4, 2012 (See Note 3)

APCT = 18°F Net PCT 2179°F B.CURRENT LOCA MODEL ASSESSMENTS None (See Note 4)

APCT = 0°F Total PCT change from current assessments XAPCT = 0°F Cumulative PCT change from current assessments APCT = 0°F Net PCT 2179°F PLANT NAME:

ECCS EVALUATION MODEL:

REPORT REVISION DATE:

CURRENT OPERATING CYCLE:

ANALYSIS OF RECORD Evaluation Model:

Calculations:

ATTACHMENT 2 Quad Cities Nuclear Power Station Unit 2, 10 CFR 50.46 Report (Westinghouse Fuel) PLANT NAME: ECCS EVALUATION MODEL: REPORT REVISION DATE: CURRENT OPERATING CYCLE: ANALYSIS OF RECORD Quad Cities Unit 2 USA5 05/03/2013 22 Evaluation Model: "Westinghouse BWR ECCS Evaluation Model: Supplement 3 to Code Description, Qualification and Application to SVEA-96 Optima2 Fuel," WCAP-16078-P-A, November 2004 Calculations: "Quad Cities 1 & 2 LOCA Analysis for SVEA-96 Optima2 Fuel," OPTIMA2-TR021 QC-LOCA, Revision 5, Westinghouse Electric Company, LLC, September 2009 Fuel Analyzed in Calculation: SVEA-96 Optima2 Limiting Fuel Type: SVEA-96 Optima2 Limiting Single Failure: Low Pressure Coolant Injection System injection valve Limiting Break Size and 1.0 double-ended guillotine break in the recirculation pump Location:

suction line Reference Peak Cladding PCT = 2150°F Temperature (PCT): MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS 10 CFR 50.46 Report dated May 7, 2010 (See Note 1)

= 11°F 10 CFR 50.46 Report dated May 6,2011 (See Note 2)

= OaF 10 CFR 50.46 Report dated May 4, 2012 (See Note 3)

= 18°F Net PCT 2179°F B. CURRENT LOCA MODEL ASSESSMENTS None (See Note 4)

= OaF Total PCT change from current assessments

= OaF Cumulative PCT change from current assessments L

=O°F Net PCT 2179°F ATTACHMENT 3 Quad Cities Nuclear Power Station Units 1 and 1 10 CFR 50.46 Report Assessment Notes1.Prior Loss

-of-Coolant Accident (LOCA)Assessment The referenced letter reported a new Westinghouse LOCA analysis of record (AOR), which incorporated modifications for the newly added recirculation pump adjustable speed drives (ASD). The new AOR (Revision 5) updated the LOCA analysis to apply approved updated Westinghouse methods, incorporate previous corrections, and update plant specific inputs. The new Westinghouse LOCA analysis demonstrated that the limiting peak cladding temperature (PCT) was 2150

°F.The referenced letter also reported the impact of subsequent corrections for an incorrect bypass hole flow coefficient, and for updated vessel leakage values.

The PCT impact of these two corrections on the limiting PCT was 9°F and 2

°F, respectively.

[

Reference:

Letter from J. L. Hansen (Exelon Generation Company, LLC) to U.S. NRC,"10 CFR 50.46, 'Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors,' Annual Report," dated May 7, 2010]

Prior LOCA Assessment The referenced letter reported new no PCT assessment for the Westinghouse LOCA analysis.Also, no emergency core cooling system (ECCS)-related changes or modifications occurred at Quad Cities Nuclear Power Station (QCNPS) that affected the assumptions of the ECCS analyses.

[

Reference:

Letter from J. L. Hansen (Exelon Generation Company, LLC) to U.S. NRC," 10 CFR 50.46, 'Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors,' Annual Report," dated May 6, 2011]

3.

Assessment The referenced letter provided the annual 10 CFR 50.46 report for Units 1 and 2. The letter reported errors in the current Westinghouse QCNPS LOCA analysis associated with the use of incorrect R-factors. The impact due to this change was determined to be an 16°F increase in PCT.For 10 CFR 50.46 reporting purposes, the PCT update was conservatively applied to all bundle types including the fresh bundles. This PCT update will remain in effect only until the maximum average planar linear heat generation rate (MAPLHGR) limits for all bundles in future QCNPS Units 1 and 2 cores are evaluated with the correct R-factors.

[

Reference:

Letter from D. M. Gullott (Exelon Generation Company, LLC) to U.S. NRC,"10 CFR 50.46,'Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors,' Annual Report," dated May 4, 2012]

4.Current Assessment There are no new changes, error corrections, or enhancements in the current QCNPS LOCA analysis.No ECCS-related changes or modifications have occurred at QCNPS that affect the assumptions in the LOCA AOR.ATTACHMENT 3 Quad Cities Nuclear Power Station Units 1 and 2, 10 CFR 50.46 Report Assessment Notes 1. Prior Loss-of-Coolant Accident (LOCA) Assessment The referenced letter reported a new Westinghouse LOCA analysis of record (AOR), which incorporated modifications for the newly added recirculation pump adjustable speed drives (ASO). The new AOR (Revision

5) updated the LOCA analysis to apply approved updated Westinghouse methods, incorporate previous corrections, and update plant specific inputs. The new Westinghouse LOCA analysis demonstrated that the limiting peak cladding temperature (PCT) was 2150°F. The referenced letter also reported the impact of subsequent corrections for an incorrect bypass hole flow coefficient, and for updated vessel leakage values. The PCT impact of these two corrections on the limiting PCT was gOF and 2°F, respectively.

[

Reference:

Letter from J. L. Hansen (Exelon Generation Company, LLC) to U.S. NRC, "10 CFR 50.46, 'Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors,'

Annual Report," dated May 7,2010] 2. Prior LOCA Assessment The referenced letter reported new no PCT assessment for the Westinghouse LOCA analysis.

Also, no emergency core cooling system (ECCS)-related changes or modifications occurred at Quad Cities Nuclear Power Station (QCNPS) that affected the assumptions of the ECCS analyses.

[

Reference:

Letter from J. L. Hansen (Exelon Generation Company, LLC) to U.S. NRC, "10 CFR 50.46, 'Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors,'

Annual Report, II dated May 6, 2011] 3. Prior LOCA Assessment The referenced letter provided the annual 10 CFR 50.46 report for Units 1 and 2. The letter reported errors in the current Westinghouse QCNPS LOCA analysis associated with the use of incorrect R-factors.

The impact due to this change was determined to be an 18°F increase in PCT. For 10 CFR 50.46 reporting purposes, the PCT update was conservatively applied to all bundle types including the fresh bundles. This PCT update will remain in effect only until the maximum average planar linear heat generation rate (MAPLHGR) limits for all bundles in future QCNPS Units 1 and 2 cores are evaluated with the correct R-factors.

[

Reference:

Letter from O. M. Gullott (Exelon Generation Company, LLC) to U.S. NRC, "10 CFR 50.46, 'Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors, I Annual Report, II dated May 4, 2012] 4. Current Assessment There are no new changes, error corrections, or enhancements in the current QCNPS LOCA analysis.

No ECCS-related changes or modifications have occurred at QCNPS that affect the assumptions in the LOCA AOR.