RS-20-059, 10 CFR 50.46 Annual Report
| ML20125A088 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 05/04/2020 |
| From: | Simpson P Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RS-20-059 | |
| Download: ML20125A088 (12) | |
Text
4300 Winfield Road Warrenville, IL 60555 Exelon Generation 630 65 7 2000 Office RS-20-059 10 CFR 50.46 May 4, 2020 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 RS-19-049 from P.R. Simpson (Exelon Generation Company, LLC) to U.S . NRC, "10 CFR 50.46 Annual Report," dated May 2, 2019 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.
Based on the referenced letter, the annual submittal due date is May 2. In accordance with 10 CFR 50.4(a) if a submission due date falls on a Saturday, Sunday, or Federal holiday, the next Federal working day becomes the official due date. As a result, the annual report is being submitted on May 4, 2020.
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.
Respectfully, P~rz ~
Patrick R. Simpson Sr. Manager Licensing
May 4, 2020 U.S . Nuclear Regulatory Commission Page 2 Attachments:
- 1. Quad Cities Nuclear Power Station Unit 1, 10 CFR 50.46 Report (Westinghouse Fuel) - USA6
- 2. Quad Cities Nuclear Power Station Unit 1, 10 CFR 50.46 Report (Framatome Fuel)
- 3. Quad Cities Nuclear Power Station Unit 2, 10 CFR 50.46 Report (Westinghouse Fuel) - USA5
- 4. Quad Cities Nuclear Power Station Unit 2, 10 CFR 50.46 Report (Westinghouse Fuel) - USA6
- 5. Quad Cities Nuclear Power Station Unit 2, 10 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 1, 10 CFR 50.46 Report (Westinghouse Fuel) - USA6 PLANT NAME: Quad Cities Unit 1 ECCS EVALUATION MODEL: USA6 REPORT REVISION DATE: 05/04/2020 CURRENT OPERATING CYCLE: 26 ANALYSIS OF RECORD 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: SVEA-96 Optima2 Limiting Fuel Type: SVEA-96 Optima2 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): PCT= 2150°F MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS 10 CFR 50.46 Report dated Mav 2, 2017 (See Note 8) ~PCT= 0°F 10 CFR 50.46 Report dated May 2, 2018 (See Note 9) ~PCT= 0°F 10 CFR 50.46 Report dated May 2, 2019 (See Note 11) ~PCT= 0°F Net PCT 2150°F B. CURRENT LOCA MODEL ASSESSMENTS None (See Note 12) ~PCT= 0°F Total PCT change from current assessments I~PCT = 0°F Cumulative PCT change from current assessments I l~PCT I = 0°F Net PCT 2150°F
ATTACHMENT 2 Quad Cities Nuclear Power Station Unit 1, 10 CFR 50.46 Report (Framatome Fuel)
PLANT NAME: Quad Cities Unit 1 ECCS EVALUATION MODEL: EXEM BWR-2000 REPORT REVISION DATE: 05/04/2020 CURRENT OPERATING CYCLE: 26 ANALYSIS OF RECORD 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 10XM 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 : ATRIUM 10XM Limiting Fuel Type : ATRIUM 10XM Limiting Single Failure: High Pressure Coolant Injection system Limiting Break Size and Location: 0.13 ft 2 split break recirculation discharge pipe Reference Peak Cladding Temperature (PCT): PCT= 2138°F MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS 10 CFR 50.46 Report dated May 2, 2017 (See Note 8) L1PCT = 0°F 10 CFR 50.46 Report dated May 2, 2018 (See Note 9) L1PCT = 0°F 10 CFR 50.46 Report dated January 9, 2019 (See Note 10) L1PCT = -40°F 10 CFR 50.46 Report dated May 2, 2019 (See Note 11) L1PCT = 0°F Net PCT 2098°F B. CURRENT LOCA MODEL ASSESSMENTS New Lattice Introduction (See Note 12) L1PCT = +1°F RODEX4 PMCI coding issue (See Note 12) L1PCT = +1°F AUTOHUP preparation of RODEX2-2a inputs (See Note 12) L1PCT = -1°F Total PCT change from current assessments IL1PCT = +1°F Cumulative PCT change from current assessments I I L1PCT I = 3°F Net PCT 2099°F
ATTACHMENT 3 Quad Cities Nuclear Power Station Unit 2, 10 CFR 50.46 Report (Westinghouse Fuel) - USAS PLANT NAME: Quad Cities Unit 2 ECCS EVALUATION MODEL: USA5 REPORT REVISION DATE: 0510412020 CURRENT OPERATING CYCLE: 26 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: 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 : SVEA-96 Optima2 Limiting Fuel Type: SVEA-96 Optima2 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): PCT= 2150°F MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS 10 CFR 50.46 Report dated May 7, 2010 (See Note 1) L1PCT = 0°F 10 CFR 50.46 Report dated May 6, 2011 (See Note 2) L1PCT = 0°F 10 CFR 50.46 Report dated May 4, 2012 (See Note 3) L1PCT = 0°F 10 CFR 50.46 Report dated May 3, 2013 (See Note 4) L1PCT = 0°F 10 CFR 50.46 Report dated May 2, 2014 (See Note 5) L1PCT = 0°F 10 CFR 50.46 Report dated May 1, 2015 (See Note 6) L1PCT = 0°F 10 CFR 50.46 Report dated May 2, 2016 (See Note 7) L1PCT = 0°F 10 CFR 50.46 Report dated May 2, 2017 (See Note 8) L1PCT = 0°F 10 CFR 50.46 Report dated May 2, 2018 (See Note 9) L1PCT = 0°F 10 CFR 50.46 Report dated May 2, 2019 (See Note 11) L1PCT = 0°F Net PCT 2150°F B. CURRENT LOCA MODEL ASSESSMENTS None (See Note 12) 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 4 Quad Cities Nuclear Power Station Unit 2, 10 CFR 50.46 Report (Westinghouse Fuel) - USA6 PLANT NAME: Quad Cities Unit 2 ECCS EVALUATION MODEL: USA6 REPORT REVISION DATE: 0510412020 CURRENT OPERATING CYCLE: 26 ANALYSIS OF RECORD 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 : SVEA-96 Optima2 Limiting Fuel Type: SVEA-96 Optima2 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): PCT= 2150°F MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS 10 CFR 50.46 Report dated May 2, 2016 (See Note 7) L1PCT = 0°F 10 CFR 50.46 Report dated May 2, 2017 (See Note 8) L1PCT = 0°F 10 CFR 50.46 Report dated May 2, 2018 (See Note 9) L1PCT = 0°F 10 CFR 50.46 Report dated May 2, 2019 (See Note 11) L1PCT = 0°F Net PCT 2150°F B. CURRENT LOCA MODEL ASSESSMENTS None (See Note 12) 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 5 Quad Cities Nuclear Power Station Unit 2, 10 CFR 50.46 Report (Framatome Fuel)
PLANT NAME: Quad Cities Unit 2 ECCS EVALUATION MODEL: EXEM BWR-2000 REPORT REVISION DATE: 0510412020 CURRENT OPERATING CYCLE: 26 ANALYSIS OF RECORD Evaluation Model: "EXEM BWR-2000 ECCS Evaluation Model ," EMF-2361(P)(A),
Revision 0, May 2001 Calculations: 1. "Quad Cities Units 1 and 2 ATRIUM 10XM Break Spectrum with Increased ADS Flow," ANP-3794P, Revision 0, September 2019
- 2. "Quad Cities Units 1 and 2 ATRIUM 10XM LOCA-ECCS Analysis MAPLHGR Limits with Increased ADS Flow," ANP-3795P, Revision 0, October 2019
- 3. "Quad Cities Unit 2 Cycle 26 Reload Safety Analysis ,"
ANP-3820P, Revision 0, January 2020 Fuel Analyzed in Calculation : ATRIUM 10XM Limiting Fuel Type : ATRIUM 10XM Limiting Single Failure: High Pressure Coolant Injection system Limiting Break Size and Location: 0.12 ft 2 split break recirculation discharge pipe Reference Peak Cladding Temperature (PCT): PCT= 2139°F MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS I None L1PCT = 0°F I Net PCT 2139°F B. CURRENT LOCA MODEL ASSESSMENTS New LOCA Calculation (See Note 12) L1PCT = 0°F RODEX4 PMCI coding issue (See Note 12) L1PCT = +1°F AUTOHUP preparation of RODEX2-2a inputs (See Note 12) L1PCT = -1°F Total PCT change from current assessments IL1PCT = 0°F Cumulative PCT change from current assessments I I L1PCT I = 2°F Net PCT 2139°F
ATTACHMENT 6 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 (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 Q2C25 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, "10 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, "10 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 10 CFR 50.46 report for Unit 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 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 Q2C25 were evaluated for this change and this penalty no longer apply.
[
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]
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ATTACHMENT 6 Quad Cities Nuclear Power Station Units 1 and 2, 10 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, "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, "10 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, "10 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, "10 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, 10 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 EGGS-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 10XM 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 3 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 EGGS-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, 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 1OXM 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, 10 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 - 10 CFR 50.46 30-Day Report," dated January 9, 2019)
- 11. Prior LOCA Assessment There were no new changes, error corrections or enhancements in the USA5 or USA6 Westinghouse LOCA analyses for QCNPS Units 1 & 2. There were no new changes, error corrections or enhancements in the Framatome EXEM BWR-2000 Evaluation Model for QCNPS units 1 & 2 . Also, no ECCS-related changes or modifications occurred at QCNPS Units 1 & 2 that affected the assumptions to any of the LOCA AO Rs .
[Reference : Letter from P. R. Simpson (Exelon Generation Company, LLC) to U.S. NRC, "10 CFR 50.46 Annual Report," dated May 2, 2019)
- 12. Current LOCA Assessment There are no new changes , error corrections or enhancements in the USA5 or USA6 Westinghouse LOCA analyses for QCNPS Units 1 & 2. A new calculation of the Framatome EXEM BWR-2000 Evaluation Model has been performed for QCNPS Unit 2 with a limiting PCT of 2139°F.
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ATTACHMENT 6 Quad Cities Nuclear Power Station Units 1 and 2, 10 CFR 50.46 Report Assessment Notes There were two assessments to the Framatome EXEM BWR-2000 Evaluation Model that apply to both the QCNPS Unit 1 and Unit 2 analyses . The first assessment was a coding issue in the RODEX4 thermal-mechanical code interpolation process of the RODEX4 Pellet-Cladding Mechanical Interaction routine. This assessment showed an estimated impact on PCT of +1°F. The second assessment was that some of the RODEX2-2a inputs associated with the fuel rod geometry were not being appropriately prepared. This assessment showed an estimated impact on PCT of -1°F. The combined impact of these two assessments was 0°F There was one assessment to the Framatome EXEM BWR-2000 Evaluation Model for QCNPS Unit 1 where a new lattice type was utilized. This new lattice type assessment resulted in a penalty of +1°F to the Unit 1 Framatome model resulting in a limiting PCT of 2099°F.
Also, no ECCS-related changes or modifications occurred at QCNPS Units 1 & 2 that affected the assumptions to any of the LOCA AORs.
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