RS-12-080, CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors, Annual Report

CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors, Annual Report

ML12125A280
Person / Time
Site:	Quad Cities
Issue date:	05/04/2012
From:	Gullott D M Exelon Nuclear, Exelon Nuclear Security
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RS-12-080
Download: ML12125A280 (4)

Text

Exelon Nuclear Security, LLC 4300 Winfield Road Warrenville, IL 60555 RS-12-0BO www.exeloncorp.com Nuclear 10 CFR 50.46(a)(3)(ii)

May 4,2012 u.s. Nuclear Regulatory Commission A TIN: 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, "Acceptance criteria for emergency core cooling systems for water nuclear power reactors," Annual Report

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 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, Units 1 and 2. The attachments describe the changes in accumulated peak cladding temperature since the previous annual report submitted in the referenced letter. This report covers the period from May 6, 2011, through May 4, 2012. There are no regulatory commitments contained in this letter. Should you have any questions concerning this letter, please contact Mr. Joseph A. Bauer at (630) 657-2B04.

Respectfully, 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 ATTACHMENT 1 Quad Cities Nuclear Power Station, Unit 1 10 CFR 50.46 Report (Westinghouse Fuel) Page 1 of 1 PLANT NAME: ECCS EVALUATION MODEL: REPORT REVISION DATE: CURRENT OPERATING CYCLE: ANALYSIS OF RECORD Quad Cities Unit 1 USA5 04/13/2012 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-960ptima2 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 Temperature (PCT): PCT = 2150°F 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 Net PCT 2161°F B. CURRENT LOCA MODEL ASSESSMENTS Incorrect R-factors (See Note 3)

= 18°F Total PCT change from current assessments

= 18°F Cumulative PCT change from current assessments L I I = 18° F Net PCT 2179°F ATTACHMENT 2 Quad Cities Nuclear Power Station, Unit 2 10 CFR 50.46 Report (Westinghouse Fuel) Page 1 of 1 PLANT NAME: Quad Cities Unit 2 ECCS EVALUATION MODEL: USA5 REPORT REVISION DATE: 04/13/2012 CURRENT OPERATING CYCLE: 22 ANALYSIS OF RECORD Evaluation Model: 'Westinghouse BWR ECCS Evaluation Model: Calculations:

Supplement 3 to Code Description, Qualification and Application to SVEA-96 Optima2 Fuel," WCAP-16078-P-A, November 2004. "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-960ptima2 Limiting Single Failure: Low Pressure Coolant Injection System injection valve Limiting Break Size and Location:

1.0 double-ended guillotine break in the recirculation pump suction line Reference Peak Cladding Temperature (PCT) MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS 10 CF10 CFR 50.46 Report dated May 7,2010 (See Note 1) 10 CFR 50.46 Report dated May 6, 2011 (See Note 2) NetPCT B. CURRENT LOCA MODEL ASSESSMENTS Incorrect R-factors (See Note 3) Total PCT change from current assessments Cumulative PCT change from current assessments Net PCT

=11°F

= OaF 2161°F

= 18°F

= 18°F L

= 18°F 2179°F ATTACHMENT 3 Quad Cities Nuclear Power Station, Units 1 and 2, 10 CFR 50.46 Report Assessment Notes Page 1 of 1 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 (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 of. 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 of and 2 of, respectively.

[

Reference:

Letter from Jeffery 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 Reporf' for Quad Cities Nuclear Power Station (QCNPS), Units 1 and 2, dated May 7,2010] 2. Prior LOCA Assessment The referenced letter reported no new PCT assessment for the Westinghouse LOCA analysiS.

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

[

Reference:

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

Annual Reporf' for QCNPS, Units 1 and 2, dated May 6, 2011] 3. Current Assessment In the referenced letter, Westinghouse reported errors in the current QCNPS LOCA analysis associated with the use of incorrect R-factors.

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

[

Reference:

Westinghouse letter L TR-LAM-11-63, Revision 0, "Dresden Units 2 & 3 and Quad Cities Units 1 & 2, 10 CFR 50.46 Notification and Report for R-Factor Error Evaluation," September 14,2011]