RS-19-049, Submittal of 10 CFR 50.46 Annual Report

Submittal of 10 CFR 50.46 Annual Report

ML19122A127
Person / Time
Site:	Quad Cities   (DPR-029, DPR-030)
Issue date:	05/02/2019
From:	Simpson P Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RS-19-049
Download: ML19122A127 (10)

Text

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• Exelon Generation RS-19-049 May 2, 2019 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Quad Cities Nuclear Power Station, Units 1 and 2 630 657 2000 Office Renewed Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265

Subject:

1 O CFR 50.46 Annual Report 1 O CFR 50.46

Reference:

Letter RS-18-048 from P. R. Simpson (Exelon Generation Company, LLC) to U.S. NRC, "1 O CFR 50.46 Annual Report," dated May 2, 2018 This letter provides the annual report required by 1 O 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 Ms. Rebecca L. Steinman at (630) 657-2831.

mpson Manager - Licensing Attachments:

1. Quad Cities Nuclear Power Station Unit 2, 1 O CFR 50.46 Report (Westinghouse Fuel) - USA5

2. Quad Cities Nuclear Power Station Unit 1, 1 O CFR 50.46 Report (Westinghouse Fuel) - USA6

3. Quad Cities Nuclear Power Station Unit 2, 1 O CFR 50.46 Report (Westinghouse Fuel) - USA6

4. Quad Cities Nuclear Power Station Unit 1, 10 CFR 50.46 Report (Framatome Fuel)

5. Quad Cities Nuclear Power Station Unit 2, 1 O CFR 50.46 Report (Framatome Fuel)

6. Quad Cities Nuclear Power Station Units 1 and 2, 10 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 2, 10 CFR 50.46 Report (Westinghouse Fuel) - USA5 PLANT NAME:

ECCS EVALUATION MODEL:

REPORT REVISION DATE:

CURRENT OPERATING CYCLE:

ANALYSIS OF RECORD Quad Cities Unit 2 USA5 05/02/2019 25 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:

1. "Quad Cities 1 & 2 LOCA Analysis for SVEA-96 Optima2 Fuel,"

OPTIMA2-TR021QC-LOCA, Revision 5, September 2009

2. "Quad Cities Nuclear Power Station Unit 2 Cycle 23 MAPLHGR Report," NF-BEX-13-168-NP, Revision 0, January 2014 Fuel Analyzed in Calculation:

Limiting Fuel Type:

SVEA-96 Optima2 SVEA-96 Optima2 Limiting Single Failure:

Limiting Break Size and Location:

Low Pressure Coolant Injection system injection valve 1.0 double-ended guillotine break in the recirculation pump suction line Reference Peak Cladding Temperature (PCT):

PCT= 2150°F MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS 1 O CFR 50.46 Report dated May 7, 2010 (See Note 1) flPCT = 0°F 1 O CFR 50.46 Report dated May 6, 2011 (See Note 2) flPCT = 0°F 1 O CFR 50.46 Report dated May 4, 2012 (See Note 3) flPCT = 0°F 1 O CFR 50.46 Report dated May 3, 2013 (See Note 4) flPCT = 0°F 1 O CFR 50.46 Report dated May 2, 2014 (See Note 5) flPCT = 0°F 1 O CFR 50.46 Report dated May 1, 2015 (See Note 6) flPCT = 0°F 1 O CFR 50.46 Report dated May 2, 2016 (See Note 7) flPCT = 0°F 1 O CFR 50.46 Report dated May 2, 2017 (See Note 8) flPCT = 0°F 1 O CFR 50.46 Report dated May 2, 2018 (See Note 9) flPCT = 0°F Net PCT 2150°F B. CURRENT LOCA MODEL ASSESSMENTS None (See Note 11) flPCT = 0°F Total PCT change from current assessments L:L1PCT = 0°F Cumulative PCT change from current assessments L: I flPCT I = 0°F Net PCT 2150°F

ATTACHMENT 2 Quad Cities Nuclear Power Station Unit 1, 10 CFR 50.46 Report (Westinghouse Fuel)- USA6 PLANT NAME:

ECCS EVALUATION MODEL:

REPORT REVISION DATE:

CURRENT OPERATING CYCLE:

ANALYSIS OF RECORD Quad Cities Unit 1 USA6 05/02/2019 26 Evaluation Model:

"Westinghouse BWR ECCS Evaluation Model Updates:

Supplement 4 to Code Description, Qualification and Application,"

WCAP-16865-P-A, Revision 1, October 2011 Calculations:

1. "Quad Cities 1 & 2 LOCA Analysis for SVEA-96 Optima2 Fuel,"

NF-BEX-13-143-P, Revision 3, April 2016

2. "Quad Cities Nuclear Power Station Unit 1 Cycle 24 Supplemental MAPLHGR Report," NF-BEX-14-135-NP, Revision 1, October 2015 Fuel Analyzed in Calculation:

Limiting Fuel Type:

SVEA-96 Optima2 SVEA-96 Optima2 Limiting Single Failure:

Limiting Break Size and Location:

Low Pressure Coolant Injection system injection valve 1.0 double-ended guillotine break in the recirculation pump suction line Reference Peak Cladding Temperature (PCT):

PCT= 2150°F MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS 1 O CFR 50.46 Report dated May 2, 2017 (See Note 8)

L1PCT = 0°F 1 O CFR 50.46 Report dated May 2, 2018 (See Note 9)

L1PCT = 0°F Net PCT 2150°F

8. CURRENT LOCA MODEL ASSESSMENTS None (See Note 11)

L1PCT = 0°F Total PCT change from current assessments IL1PCT = 0°F Cumulative PCT change from current assessments I I L1PCT I = 0°F Net PCT 2150°F

ATTACHMENT 3 Quad Cities Nuclear Power Station Unit 2, 1 O CFR 50.46 Report (Westinghouse Fuel) - USA6 PLANT NAME:

ECCS EVALUATION MODEL:

REPORT REVISION DATE:

CURRENT OPERATING CYCLE:

ANALYSIS OF RECORD Quad Cities Unit 2 USA6 05/02/2019 25 Evaluation Model:

"Westinghouse BWR ECCS Evaluation Model Updates:

Supplement 4 to Code Description, Qualification and Application,"

WCAP-16865-P-A, Revision 1, October 2011 Calculations:

1. "Quad Cities 1 & 2 LOCA Analysis for SVEA-96 Optima2 Fuel,"

NF-BEX-13-143-P, Revision 3, April 2016

2. "Quad Cities Nuclear Power Station Unit 2 Cycle 24 MAPLHGR Report," NF-BEX-15-174-NP, Revision 0, January 2016 Fuel Analyzed in Calculation:

Limiting Fuel Type:

SVEA-96 Optima2 SVEA-96 Optima2 Limiting Single Failure:

Limiting Break Size and Location:

Low Pressure Coolant Injection system injection valve 1.0 double-ended guillotine break in the recirculation pump suction line Reference Peak Cladding Temperature (PCT):

PCT= 2150°F MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS 1 O CFR 50.46 Report dated May 2, 2016 (See Note 7)

~PCT= 0°F 1 O CFR 50.46 Report dated May 2, 2017 (See Note 8)

~PCT= 0°F 1 O CFR 50.46 Report dated May 2, 2018 (See Note 9)

~PCT= 0°F Net PCT 2150°F B. CURRENT LOCA MODEL ASSESSMENTS None (See Note 11)

~PCT= 0°F Total PCT change from current assessments I~PCT = 0°F Cumulative PCT change from current assessments I I ~PCT I = 0°F Net PCT 2150°F

ATTACHMENT 4 Quad Cities Nuclear Power Station Unit 1, 1 O CFR 50.46 Report (Framatome Fuel)

PLANT NAME:

ECCS EVALUATION MODEL:

REPORT REVISION DATE:

CURRENT OPERATING CYCLE:

ANALYSIS OF RECORD Quad Cities Unit 1 EXEM BWR-2000 05/02/2019 26 Evaluation Model:

"EXEM BWR-2000 ECCS Evaluation Model," EMF-2361 (P)(A),

Revision 0, May 2001 Calculations:

1. "Quad Cities Units 1 and 2 LOCA Break Spectrum Analysis for ATRIUM 10XM Fuel," ANP-3328P, Revision 2, December 2016

2. "Quad Cities Units 1 and 2 LOCA-ECCS Analysis MAPLHGR Limits for ATRIUM 1 OXM Fuel," ANP-3356P, Revision 2, February 2017

3. "Quad Cities Unit 1 Cycle 26 Reload Safety Analysis,"

ANP-3744P, Revision 0, January 2019 Fuel Analyzed in Calculation:

Limiting Fuel Type:

ATRIUM 10XM ATRIUM 10XM Limiting Single Failure:

High Pressure Coolant Injection system Limiting Break Size and Location:

0.13 ft2 split break recirculation discharge pipe Reference Peak Cladding Temperature (PCT):

PCT= 2138°F MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS 1 O CFR 50.46 Report dated May 2, 2017 (See Note 8)

L'lPCT = 0°F 1 O CFR 50.46 Report dated May 2, 2018 (See Note 9)

L'lPCT = 0°F 1 O CFR 50.46 Report dated January 9, 2019 (See Note 10)

L'lPCT = -40°F Net PCT 2098°F B. CURRENT LOCA MODEL ASSESSMENTS None (See Note 11)

L'lPCT = 0°F Total PCT change from current assessments IL'lPCT = 0°F Cumulative PCT change from current assessments I I L'lPCT I = 0°F Net PCT 2098°F

ATTACHMENT 5 Quad Cities Nuclear Power Station Unit 2, 1 O CFR 50.46 Report (Framatome Fuel)

PLANT NAME:

ECCS EVALUATION MODEL:

REPORT REVISION DATE:

CURRENT OPERATING CYCLE:

ANALYSIS OF RECORD Quad Cities Unit 2 EXEM BWR-2000 05/02/2019 25 Evaluation Model:

"EXEM BWR-2000 ECCS Evaluation Model," EMF-2361 (P)(A),

Revision 0, May 2001 Calculations:

1. "Quad Cities Units 1 and 2 LOCA Break Spectrum Analysis for ATRIUM 1 OXM Fuel," ANP-3328P, Revision 2, December 2016

2. "Quad Cities Units 1 and 2 LOCA-ECCS Analysis MAPLHGR Limits for ATRIUM 10XM Fuel," ANP-3356P, Revision 3, January 2018

3. "Quad Cities Unit 2 Cycle 25 Reload Safety Analysis,"

ANP-3642P, Revision 1, February 2018 Fuel Analyzed in Calculation:

ATRIUM 10XM ATRIUM 10XM Limiting Fuel Type:

Limiting Single Failure:

High Pressure Coolant Injection system Limiting Break Size and Location:

0.13 ft2 split break recirculation discharge pipe Reference Peak Cladding Temperature (PCT):

PCT= 2150°F MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS 1 O CFR 50.46 Report dated May 2, 2018 (See Note 9) t.PCT = 0°F 1 O CFR 50.46 Report dated January 9, 2019 (See Note 10) t.PCT = -13°F Net PCT 2137°F B. CURRENT LOCA MODEL ASSESSMENTS None (See Note 11) t.PCT = 0°F Total PCT change from current assessments It.PCT= 0°F Cumulative PCT change from current assessments I It.PCT I = 0°F Net PCT 2137°F

ATTACHMENT 6 Quad Cities Nuclear Power Station Units 1 and 2, 1 O 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. These PCT impacts will remain in effect only until the MAPLHGR limits for all bundles in future QCNPS Unit 2 cores are evaluated for this change. The MAPLHGR limits for all bundles in the QCNPS Unit 2 cores starting with 02C25 were evaluated for these changes and these penalties no longer apply.

[

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 7, 201 O]

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 1 O CFR 50.46 report for Unit 2. The letter reported errors in the current Westinghouse OCNPS LOCA analysis associated with the use of incorrect Fl-factors. The impact due to this change was determined to be 18°F increase in PCT. This PCT will remain in effect only until the MAPLHGR limits for all bundles in future QCNPS Unit 2 cores are evaluated for this change. The MAPLHGR limits for all bundles in the QCNPS Unit 2 cores starting with 02C25 were evaluated for this change and this penalty no longer apply.

[

Reference:

Letter from D. M. Gullott (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 4, 2012]

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ATTACHMENT 6 Quad Cities Nuclear Power Station Units 1 and 2, 1 O 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. Gullatt (Exelon Generation Company, LLC) to U.S. NRC, "1 O 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, "1 O CFR 50.46 Annual Report," dated May 2, 2014]

6.

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, "1 O CFR 50.46 Annual Report," dated May 1, 2015]

7.

Prior LOCA Assessment The new USA6 LOCA Evaluation Model and calculation was implemented for QCNPS Unit 2 for all fresh fuel starting with Cycle 24. This evaluation model and calculation supplement the existing Evaluation Model and calculation. This model reports a limiting PCT of 2150°F and has no additional PCT impacts or estimates.

Additionally, there are no new changes, error corrections, or enhancements in the current QCNPS LOCA analysis based on the USA5 LOCA Evaluation Model. Also, no ECCS-related changes or modifications occurred at QCNPS that affected the assumptions in the ECCS analyses.

[

Reference:

Letter from P. R. Simpson (Exelon Generation Company, LLC) to U.S.

NRC, "1 O CFR 50.46 Annual Report," dated May 2, 2016]

8.

Prior LOCA Assessment The new USA6 LOCA Evaluation Model and calculation was implemented for QCNPS Unit 1 during Cycle 24 for the Optima2 fuel loaded fresh into the Cycle 24 core. This evaluation model and calculation supplement the existing Evaluation Model and calculation. This model reports a limiting PCT of 2150°F and has no additional PCT impacts or estimates.

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ATTACHMENT 6 Quad Cities Nuclear Power Station Units 1 and 2, 1 O CFR 50.46 Report Assessment Notes The new AREVA/Framatome EXEM BWR-2000 Evaluation Model and calculation has been implemented for QCNPS Unit 1 for the fresh fuel of ATRIUM 10XM loaded into the Cycle 25 core. This model reports a limiting PCT of 2138°F and has no additional PCT impacts or estimates.

Additionally, there are no new changes, error corrections, or enhancements in the current QCNPS LOCA analysis based on the USA5 LOCA Evaluation model, USA6 LOCA Evaluation model or EXEM BWR-2000 LOCA Evaluation model. Also, no ECCS-related changes or modifications occurred at QCNPS that affected the assumptions in the ECCS analyses.

[

Reference:

Letter from P. R. Simpson (Exelon Generation Company, LLC) to U.S. NRC, "10 CFR 50.46 Annual Report," dated May 2, 2017]

9.

Prior LOCA Assessment The new AREVA/Framatome EXEM BWR-2000 Evaluation Model and calculation has been implemented for QCNPS Unit 2 for the fresh fuel of ATRIUM 1 OXM loaded into the Cycle 25 core. This model reports a limiting PCT of 2150°F and has no additional PCT impacts or estimates.

Additionally, updated LOCA/MAPLHGR analyses were performed for QCNPS Unit 2 for the Westinghouse fuel first introduced in the Cycle 23 reload. These analyses for QCNPS Unit 2 maintained the calculated PCT at 2150°F and accounted for the incorrect vessel leakage and bypass hole coefficient outlined in Note 1 and the incorrect R-factors outlined in Note 3.

All other Westinghouse fuel from before Cycle 23 that was impacted by these errors within Unit 1 and 2 has been discharged. Therefore, the previous penalty of 11 °F in Note 1 and 18°F in Note 3 no longer apply for QCNPS Unit 2. The penalty in Attachment 1 listed for Notes 1 and 3 have all been changed to 0°F.

Additionally, there are no new changes, error corrections, or enhancements in the current QCNPS LOCA analysis based on the USA5 LOCA Evaluation model, USA6 LOCA Evaluation model or EXEM BWR-2000 LOCA Evaluation model. Also, no ECCS-related changes or modifications occurred at QCNPS that affected the assumptions in the ECCS analyses.

[

Reference:

Letter from P. R. Simpson (Exelon Generation Company, LLC) to U.S. NRC, "1 O CFR 50.46 Annual Report," dated May 2, 2018]

10.

Prior LOCA Assessment This report issued several error corrections and one input change to the current QCNPS LOCA analysis based on the Framatome EXEM BWR-2000 Evaluation Model.

The first LOCA error determined that the QCNPS Unit 1 ATRIUM 1 OXM licensing basis used an incorrect cladding axial growth factor. The value used in the input, 0.0006 is for PWR fuel whereas the appropriate value for BWR fuel is 0.0007. This issue had a +0°F impact on the licensing PCT for QCNPS Unit 1. QCNPS Unit 2 was not impacted by this error.

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ATTACHMENT 6 Quad Cities Nuclear Power Station Units 1 and 2, 1 O CFR 50.46 Report Assessment Notes The second LOCA error determined that an updated QCNPS free volume input for the steam dryer region was needed within the LOCA model. The impact of this steam dryer parameter change on PCT was evaluated. Based on the assessment, the impact on the licensing PCT is estimated to be +5°F for both QCNPS Unit 1 and Unit 2.

The third LOCA error determined an incorrect value for reactor power was used in the HUXY runs of the QCNPS break spectrum analysis. This update resulted in no impact to the limiting break. As such, the bounding condition input used in the analysis to confirm the MAPLHGR limits were unaffected and thus had a 0°F impact on the licensing basis PCT for both QCNPS Unit 1 and Unit 2.

The fourth LOCA error determined that the AUTOHUP LOCA automation code calculated an incorrect power level approximately 1 % lower when building the HUXY input decks. The impact of this error on the QCNPS Unit 1 licensing basis PCT is estimated to be +5°F and on the QCNPS Unit 2 licensing basis PCT is estimated to be +45°F.

The one LOCA analysis input change was the updated automatic depressurization system (ADS) flow capacity. The effect of this change on the QCNPS Unit 1 licensing basis PCT is estimated to be -50°F and on the QCNPS Unit 2 licensing basis PCT is estimated to be -63°F.

The overall net change due to the above errors and input change was a decrease of -40°F and an absolute value impact of 60°F for QCNPS Unit 1. The overall net change due to the above errors and input change was a decrease of -13°F and an absolute value impact of 113°F for QCNPS Unit 2. The current licensing basis PCT for Unit 1 is 2098°F and for Unit 2 is 2137°F.

[

Reference:

Letter from P. R. Simpson (Exelon Generation Company, LLC) to U.S. NRC, "ECCS Evaluation Model Error - 1 O CFR 50.46 30-Day Report," dated January 9, 2019]

11.

Current LOCA Assessment There are no new changes, error corrections or enhancements in the USAS or USA6 Westinghouse LOCA analyses for QCNPS Units 1 and 2. There are no new changes, error corrections or enhancements in the Framatome EXEM BWR-2000 Evaluation Model for QCNPS Units 1 and 2. Also, no ECCS-related changes or modifications occurred at QCNPS Units 1 and 2 that affected the assumptions to any of the LOCA AORs.

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