RS-15-124, 10 CFR50.46 Annual Report: Difference between revisions
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{{#Wiki_filter:Exelon Generation RS-15-124 May 1, 2015 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Quad Cities Nuclear Power Station, Units 1 and 2 | {{#Wiki_filter:4300 Winfield Road Warrenville, IL 60555 Exelon Generation 630 657 2000 Office RS-15-124 10 CFR 50.46 May 1, 2015 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:== | ==Subject:== | ||
1O CFR 50.46 Annual Report | |||
==Reference:== | ==Reference:== | ||
Letter from P. R. Simpson (Exelon Generation Company, LLC) to U.S. NRC, "10 CFR 50.46 Annual Report," dated May 2, 2014 This letter provides the annual report required by 1O 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. | |||
RPk Patrick R. Simpson ((_ | |||
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, 1O CFR 50.46 Report Assessment Notes cc: NRC Regional Administrator, Region Ill NRC Senior Resident Inspector, Quad Cities Nuclear Power Station | |||
ATTACHMENT 1 Quad Cities Nuclear Power Station Unit 1, 1O CFR 50.46 Report (Westinghouse Fuel) | |||
PLANT NAME: Quad Cities Unit 1 ECCS EVALUATION MODEL: USA5 REPORT REVISION DATE: 05/01/2015 CURRENT OPERATING CYCLE: 24 ANALYSIS OF RECORD 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*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 and 1.o double-ended guillotine break in the recirculation pump Location: suction line Reference Peak Cladding PCT = 2150°F Temperature (PCT): | |||
SVEA-96 Optima2 Limiting Fuel Type: SVEA-96 Optima2 Limiting Single Failure: Low Pressure Coolant Injection System injection valve Limiting Break Size and 1 .o double-ended guillotine break in the recirculation pump Location: | MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS 10 CFR 50.46 Report dated Mav 7, 2010 See Note 1 APCT = 11°F 10 CFR 50.46 Report dated Mav 6, 2011 See Note 2 A.PCT= 0°F 1O CFR 50.46 Report dated May 4, 2012 See Note 31 A.PCT= 18°F 10 CFR 50.46 Report dated Mav 3, 2013 See Note 4 APCT= 0°F 10 CFR 50.46 Report dated Mav 2, 2014 See Note 5 APCT=0°F Net PCT 2179°F B. CURRENT LOCA MODEL ASSESSMENTS None (See Note 6) A.PCT= 0°F Total PCT change from current assessments 2:APCT=0°F Cumulative PCT change from current assessments 2: IAPCT I = ~-$-4 Net PCT 2179 | ||
suction line Reference Peak Cladding PCT = 2150°F Temperature (PCT): MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS 10 CFR 50.46 Report dated Mav 7, 2010 See Note 1 APCT = 11°F 10 CFR 50.46 Report dated Mav 6, 2011 See Note 2 A.PCT= 0°F | |||
Net PCT 2179 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 | ATTACHMENT 2 Quad Cities Nuclear Power Station Unit 2, 10 CFR 50.46 Report (Westinghouse Fuel) | ||
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: | PLANT NAME: Quad Cities Unit 2 ECCS EVALUATION MODEL: USA5 REPORT REVISION DATE: 05/01/2015 CURRENT OPERATING CYCLE: 23 ANALYSIS OF RECORD Evaluation Model: "Westinghouse BWR ECCS Evaluation Model: | ||
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 1 See Note 1 APCT = 11°F | 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-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 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 1 See Note 1 APCT = 11°F 1o CFR 50.46 Report dated May 6, 2011 1 See Note 2 APCT=0°F 10 CFR 50.46 Report dated May 4, 2012 See Note 3 APCT = 18°F 10 CFR 50.46 Report dated May 3, 2013 See Note 4 APCT=0°F 10 CFR 50.46 Report dated May 2, 2014 See Note 5 APCT=0°F Net PCT 2179°F B. CURRENT LOCA MODEL ASSESSMENTS None (See Note 6) APCT=0°F Total PCT change from current assessments L:APCT=0°F Cumulative PCT change from current assessments I: IAPCT I = 0°F Net PCT 2179°F | |||
ATTACHMENT 3 Quad Cities Nuclear Power Station Units 1 and 2, 1O 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 (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:== | ==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] | |||
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,' | : 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 Quad Cities Nuclear Power Station (QCNPS) that affected the assumptions of the ECCS analyses. | ||
Annual Report," 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 Quad Cities Nuclear Power Station (QCNPS) that affected the assumptions of the ECCS analyses. | |||
[ | [ | ||
==Reference:== | ==Reference:== | ||
Letter from J. L. Hansen (Exelon Generation Company, LLC) to U.S. NRC, "1 o CFR 50.46, 'Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors,' Annual Report," dated May 6, 2011] | |||
Letter from J. L. Hansen (Exelon Generation Company, LLC) to U.S. NRC, "1 o CFR 50.46, 'Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors,' | : 3. Prior LOCA Assessment The referenced letter provided the annual 1O 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 A-factors. The impact due to this change was determined to be an 18°F increase in PCT. For 1O 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 A-factors. | ||
Annual Report," dated May 6, 2011] 3. Prior LOCA Assessment The referenced letter provided the annual | |||
The impact due to this change was determined to be an 18°F increase in PCT. For | |||
[ | [ | ||
==Reference:== | ==Reference:== | ||
Letter from D. M. Gullatt (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] | |||
ATTACHMENT3 Quad Cities Nuclear Power Station Units 1 and 2, 1O CFR 50.46 Report Assessment Notes | |||
: 4. Prior LOCA Assessment The referenced letter reported no new PCT assessment for the Westinghouse LOCA analysis. Also, no ECCS-related changes or modifications occurred at QCNPS that affected the assumptions of the ECCS analyses. | |||
ATTACHMENT3 Quad Cities Nuclear Power Station Units 1 and 2, | |||
Also, no ECCS-related changes or modifications occurred at QCNPS that affected the assumptions of the ECCS analyses. | |||
[ | [ | ||
==Reference:== | ==Reference:== | ||
Letter from D. M. Gullett (Exelon Generation Company, LLC) to U.S. NRC, 11 10 CFR 50.46 Annual Report," dated May 3, 2013] | |||
Letter from D. M. Gullett (Exelon Generation Company, LLC) to U.S. NRC, 11 10 CFR 50.46 Annual Report," dated May 3, 2013] 5. Prior LOCA Assessment The referenced letter reported no new PCT assessment for the Westinghouse LOCA analysis. | : 5. Prior LOCA Assessment The referenced letter reported no new PCT assessment for the Westinghouse LOCA analysis. Also, no ECCS-related changes or modifications occurred at QCNPS that affected the assumptions of the ECCS analyses. | ||
Also, no ECCS-related changes or modifications occurred at QCNPS that affected the assumptions of the ECCS analyses. | |||
[ | [ | ||
==Reference:== | ==Reference:== | ||
Letter from P. R. Simpson (Exelon Generation Company, LLC) to U.S. | |||
Letter from P. R. Simpson (Exelon Generation Company, LLC) to U.S. NRC, 11 10 CFR 50.46 Annual Report," dated May 2, 2014] 6. Current Assessment There are no new changes, error corrections, or enhancements in the current QCNPS LOCA analysis. | NRC, 11 10 CFR 50.46 Annual Report," dated May 2, 2014] | ||
Also, no ECCS-related changes or modifications occurred at QCNPS that affected the assumptions in the LOCA AOR.}} | : 6. Current Assessment There are no new changes, error corrections, or enhancements in the current QCNPS LOCA analysis. Also, no ECCS-related changes or modifications occurred at QCNPS that affected the assumptions in the LOCA AOR.}} |
Revision as of 13:08, 31 October 2019
ML15121A174 | |
Person / Time | |
---|---|
Site: | Quad Cities |
Issue date: | 05/01/2015 |
From: | Simpson P Exelon Generation Co |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
RS-15-124 | |
Download: ML15121A174 (5) | |
Text
4300 Winfield Road Warrenville, IL 60555 Exelon Generation 630 657 2000 Office RS-15-124 10 CFR 50.46 May 1, 2015 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:
1O CFR 50.46 Annual Report
Reference:
Letter from P. R. Simpson (Exelon Generation Company, LLC) to U.S. NRC, "10 CFR 50.46 Annual Report," dated May 2, 2014 This letter provides the annual report required by 1O 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.
RPk Patrick R. Simpson ((_
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, 1O CFR 50.46 Report Assessment Notes cc: NRC Regional Administrator, Region Ill NRC Senior Resident Inspector, Quad Cities Nuclear Power Station
ATTACHMENT 1 Quad Cities Nuclear Power Station Unit 1, 1O CFR 50.46 Report (Westinghouse Fuel)
PLANT NAME: Quad Cities Unit 1 ECCS EVALUATION MODEL: USA5 REPORT REVISION DATE: 05/01/2015 CURRENT OPERATING CYCLE: 24 ANALYSIS OF RECORD 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*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 and 1.o 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 Mav 7, 2010 See Note 1 APCT = 11°F 10 CFR 50.46 Report dated Mav 6, 2011 See Note 2 A.PCT= 0°F 1O CFR 50.46 Report dated May 4, 2012 See Note 31 A.PCT= 18°F 10 CFR 50.46 Report dated Mav 3, 2013 See Note 4 APCT= 0°F 10 CFR 50.46 Report dated Mav 2, 2014 See Note 5 APCT=0°F Net PCT 2179°F B. CURRENT LOCA MODEL ASSESSMENTS None (See Note 6) A.PCT= 0°F Total PCT change from current assessments 2:APCT=0°F Cumulative PCT change from current assessments 2: IAPCT I = ~-$-4 Net PCT 2179
ATTACHMENT 2 Quad Cities Nuclear Power Station Unit 2, 10 CFR 50.46 Report (Westinghouse Fuel)
PLANT NAME: Quad Cities Unit 2 ECCS EVALUATION MODEL: USA5 REPORT REVISION DATE: 05/01/2015 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-16078-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 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 1 See Note 1 APCT = 11°F 1o CFR 50.46 Report dated May 6, 2011 1 See Note 2 APCT=0°F 10 CFR 50.46 Report dated May 4, 2012 See Note 3 APCT = 18°F 10 CFR 50.46 Report dated May 3, 2013 See Note 4 APCT=0°F 10 CFR 50.46 Report dated May 2, 2014 See Note 5 APCT=0°F Net PCT 2179°F B. CURRENT LOCA MODEL ASSESSMENTS None (See Note 6) APCT=0°F Total PCT change from current assessments L:APCT=0°F Cumulative PCT change from current assessments I: IAPCT I = 0°F Net PCT 2179°F
ATTACHMENT 3 Quad Cities Nuclear Power Station Units 1 and 2, 1O 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 (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]
- 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 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, "1 o CFR 50.46, 'Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors,' Annual Report," dated May 6, 2011]
- 3. Prior LOCA Assessment The referenced letter provided the annual 1O 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 A-factors. The impact due to this change was determined to be an 18°F increase in PCT. For 1O 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 A-factors.
[
Reference:
Letter from D. M. Gullatt (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]
ATTACHMENT3 Quad Cities Nuclear Power Station Units 1 and 2, 1O CFR 50.46 Report Assessment Notes
- 4. Prior LOCA Assessment The referenced letter reported no new PCT assessment for the Westinghouse LOCA analysis. Also, no ECCS-related changes or modifications occurred at QCNPS that affected the assumptions of the ECCS analyses.
[
Reference:
Letter from D. M. Gullett (Exelon Generation Company, LLC) to U.S. NRC, 11 10 CFR 50.46 Annual Report," dated May 3, 2013]
- 5. Prior LOCA Assessment The referenced letter reported no new PCT assessment for the Westinghouse LOCA analysis. Also, no ECCS-related changes or modifications occurred at QCNPS that affected the assumptions of the ECCS analyses.
[
Reference:
Letter from P. R. Simpson (Exelon Generation Company, LLC) to U.S.
NRC, 11 10 CFR 50.46 Annual Report," dated May 2, 2014]