RS-18-039, Stations - Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors

From kanterella
Jump to navigation Jump to search
Stations - Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors
ML18099A278
Person / Time
Site: Byron, Braidwood  Constellation icon.png
Issue date: 04/09/2018
From: Gullott D
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
RS-18-039
Download: ML18099A278 (20)
v • d • e


Text

4300 Winfield Road Warrenville, IL 60555 Exelon Generation 630 657 2000 Office RS-18-039 10 CFR 50.46 April 9, 2018 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-72 and NPF-77 N RC Docket Nos. STN 50-456 and 50-457 Byron Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-37 and NPF-66 NRC Docket Nos. STN 50-454 and 50-455

Subject:

Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors

Reference:

Letter from David M. Gullett (Exelon Generation Company, LLC) to U.S. NRC, "Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors," dated April 7, 2017 In accordance with 10 CFR 50.46, 11 Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors, 11 paragraph (a)(3)(ii), Exelon Generation Company, LLC, (EGC) is submitting the attached information to fulfill the annual reporting requirements for Braidwood and Byron Stations, Units 1 and 2. The attachments describe the changes in the evaluations associated with the accumulated peak cladding temperature (PCT) since the previous annual report submitted in the referenced letter.

There are no regulatory commitments contained in this submittal.

Should you have any questions concerning this letter, please contact Ryan Sprengel at (630) 657-2814.

Respectfully, David M. Gullett Manager - Licensing Exelon Generation Company, LLC

April 9, 2018 U.S. Nuclear Regulatory Commission Page 2 Attachments: 1) Braidwood and Byron Stations, Units 1 and 2 - 10 CFR 50.46 Report

2) Braidwood and Byron Stations, Units 1 and 2 - 10 CFR 50.46 Report Assessment Notes cc: NRC Regional Administrator, Region Ill NRC Senior Resident Inspector, Braidwood Station NRC Senior Resident Inspector, Byron Station NRR Project Manager, Braidwood and Byron Stations Illinois Emergency Management Agency - Division of Nuclear Safety

Attachment 1 Braidwood and Byron Stations, Units 1 and 2 10 CFR 50.46 Report PLANT NAME: Braidwood Station Unit 1 ECCS EVALUATION MODEL: Small Break Loss of Coolant Accident (SBLOCA)

REPORT REVISION DATE: 4/9/18 CURRENT OPERATING CYCLE: 20 ANALYSIS OF RECORD (AOR)

Evaluation Model: NOTRUMP Calculation: Westinghouse CN-LIS-00-208, December 2000 Fuel: VANTAGE+ 17 x 17 Limiting Fuel Type: VANTAGE+ 17 x 17 Limiting Single Failure: Loss of one train of ECCS flow Limiting Break Size and Location: 2-inch Break in the Bottom of the Cold Leg Reference Peak Cladding Temperature (PCT) PCT= 1624.0°F MARGIN ALLOCATION A. PRIOR LOSS OF COOLANT ACCIDENT (LOCA) MODEL ASSESSMENTS 10 CFR 50.46 report dated June 11, 2001 (Note 1) ~PCT= 0 °F 10 CFR 50.46 report dated April 18, 2002 (Note 2) ~PCT= 0 °F 10 CFR 50.46 report dated April 14, 2003 (Note 3) ~PCT= 0 °F 10 CFR 50.46 report dated April 14, 2004 (Note 4) ~PCT= +35 °F 10 CFR 50.46 report dated April 14, 2005 (Note 5) ~PCT= 0 °F 10 CFR 50.46 report dated April 14, 2006 (Note 6) ~PCT= 0 °F 10 CFR 50.46 report dated April 13, 2007 (Note 7) ~PCT= 0 °F 30-Day 10 CFR 50.46 report dated June 22, 2007 (Note 9) ~PCT= 0 °F 30-Day 10 CFR 50.46 report dated November 19, 2007 (Note 10) ~PCT= +90 °F 10 CFR 50.46 report dated April 11, 2008 (Note 11) ~PCT= 0 °F 10 CFR 50.46 report dated April 9, 2009 (Note 12) ~PCT= 0 °F 10 CFR 50.46 report dated April 8, 201 O (Note 13) ~PCT= 0 °F 10 CFR 50.46 report dated April 6, 2011 (Note 15) ~PCT= 0 °F 10 CFR 50.46 report dated April 6, 2012 (Note 17) ~PCT= 0 °F 10 CFR 50.46 report dated April 5, 2013 (Note 19) ~PCT= 0 °F 10 CFR 50.46 report dated April 7, 2014 (Note 21) ~PCT= 0 °F 10 CFR 50.46 report dated April 7, 2015 (Note 22) ~PCT= 0 °F 10 CFR 50.46 report dated April 7, 2016 (Note 23) ~PCT= 0 °F 10 CFR 50.46 report dated April 7, 2017 (Note 24) ~PCT= 0 °F NET PCT PCT= 1749.0°F Page 1 of 12

Attachment 1 Braidwood and Byron Stations, Units 1 and 2 10 CFR 50.46 Report B. CURRENT LOCA MODEL ASSESSMENTS General Code Maintenance (Note 25) ~PCT= 0 °F Error in the Upper Plenum Fluid Volume Calculation (Note 25) ~PCT= 0 °F Total PCT change from current assessments L ~PCT= 0 °F Cumulative PCT change from current assessments L I ~PCT I= 0 °F NET PCT PCT= 1749.0°F Page 2 of 12

Attachment 1 Braidwood and Byron Stations, Units 1 and 2 10 CFR 50.46 Report PLANT NAME: Braidwood Station Unit 1 ECCS EVALUATION MODEL: Large Break Loss of Coolant Accident (LBLOCA)

REPORT REVISION DATE: 4/9/18 CURRENT OPERATING CYCLE: 20 AOR Evaluation Model: ASTRUM (2004)

Calculation: Westinghouse WCAP-16841-P, November 2007 Fuel: VANTAGE+ 17x17 Limiting Fuel Type: VANTAGE+ 17 x 17 Limiting Single Failure: Loss of one train of ECCS flow Limiting Break Size and Location: Guillotine break in the Cold Leg Reference PCT PCT= 1913.0°F MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS 30-Day 10 CFR 50.46 report dated March 15, 2011 (Note 14) i\PCT = 0 °F 10 CFR 50.46 report dated April 6, 2011 (Note 15) i\PCT = 0 °F 10 CFR 50.46 report dated April 6, 2012 (Note 17) i\PCT = 0 °F 30-Day 10 CFR 50.46 report dated May 21, 2012 (Note 18) i\PCT = +44 °F 10 CFR 50.46 report dated April 5, 2013 (Note 19) i\PCT = 0 °F 30-Day 10 CFR 50.46 report dated February 27, 2014 (Note 20) i\PCT = +66 °F 10 CFR 50.46 report dated April 7, 2014 (Note 21) i\PCT = 0 °F 10 CFR 50.46 report dated April 7, 2015 (Note 22) i\PCT = +2 °F 10 CFR 50.46 report dated April 7, 2016 (Note 23) i\PCT = 0 °F 10 CFR 50.46 report dated April 7, 2017 (Note 24) i\PCT = 0 °F NET PCT PCT = 2025.0°F B. CURRENT LOCA MODEL ASSESSMENTS General Code Maintenance (Note 25) i\PCT = 0 °F Evaluation of Inconsistent Application of Numerical Ramp Applied to i\PCT = 0 °F the Entrained Liquid I Vapor lnterfacial Drao Coefficient (Note 25)

Evaluation of Inappropriate Resetting of Transverse Liquid Mass i\PCT = 0 °F Flow (Note 25)

Evaluation of Steady-State Fuel Temperature Calibration Method i\PCT = 0 °F (Note 25)

Total PCT change from current assessments L i\PCT = 0 °F Cumulative PCT change from current assessments L Ii\PCT I= 0 °F NET PCT PCT = 2025.0°F Page 3 of 12

Attachment 1 Braidwood and Byron Stations, Units 1 and 2 10 CFR 50.46 Report PLANT NAME: Braidwood Station Unit 2 ECCS EVALUATION MODEL: Small Break Loss of Coolant Accident (SBLOCA)

REPORT REVISION DATE: 4/9/18 CURRENT OPERATING CYCLE: 20 AOR Evaluation Model: NOTRUMP Calculation: Westinghouse CN-LIS-00-208, December 2000 Fuel: VANTAGE+ 17 x 17 Limiting Fuel Type: VANTAGE+ 17 x 17 Limiting Single Failure: Loss of one train of ECCS flow Limiting Break Size and Location: 2-inch Break in the Bottom of the Cold Leg Reference PCT PCT= 1627.0°F MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS 10 CFR 50.46 report dated June 11, 2001 (Note 1) i\PCT = +3 °F 10 CFR 50.46 report dated April 18, 2002 (Note 2) i\PCT = 0 °F 10 CFR 50.46 report dated April 14, 2003 (Note 3) i\PCT = 0 °F 10 CFR 50.46 report dated April 14, 2004 (Note 4) i\PCT = +35 ° F 10 CFR 50.46 report dated April 14, 2005 (Note 5) i\PCT = 0 °F 10 CFR 50.46 report dated April 14, 2006 (Note 6) i\PCT = 0 °F 10 CFR 50.46 report dated April 13, 2007 (Note 7) i\PCT = 0 °F 30-Day 10 CFR 50.46 report dated June 22, 2007 (Note 9) i\PCT = 0 °F 10 CFR 50.46 report dated April 11, 2008 (Note 11) i\PCT = +90 °F 10 CFR 50.46 report dated April 9, 2009 (Note 12) i\PCT = 0 °F 10 CFR 50.46 report dated April 8, 2010 (Note 13) i\PCT = 0 °F 10 CFR 50.46 report dated April 6, 2011 (Note 15) i\PCT = 0 °F 10 CFR 50.46 report dated April 6, 2012 (Note 17) i\PCT = 0 °F 10 CFR 50.46 report dated April 5, 2013 (Note 19) i\PCT = 0 °F 10 CFR 50.46 report dated April 7, 2014 (Note 21) i\PCT = 0 °F 10 CFR 50.46 report dated April 7, 2015 (Note 22) i\PCT = 0 °F 1o CFR 50.46 report dated April 7, 2016 (Note 23) i\PCT = 0 °F 10 CFR 50.46 report dated April 7, 2017 (Note 24) i\PCT = 0 °F NET PCT PCT= 1755.0°F Page 4 of 12

Attachment 1 Braidwood and Byron Stations, Units 1 and 2 10 CFR 50.46 Report B. CURRENT LOCA MODEL ASSESSMENTS General Code Maintenance (Note 25) ~PCT= 0 °F Error in the Upper Plenum Fluid Volume Calculation (Note 25) ~PCT= 0 °F Total PCT change from current assessments L ~PCT= 0 °F Cumulative PCT change from current assessments L I~PCT I= 0 °F NET PCT PCT= 1755.0°F Page 5 of 12

Attachment 1 Braidwood and Byron Stations, Units 1 and 2 10 CFR 50.46 Report PLANT NAME: Braidwood Station Unit 2 ECCS EVALUATION MODEL: Large Break Loss of Coolant Accident (LBLOCA)

REPORT REVISION DATE: 4/9/18 CURRENT OPERATING CYCLE: 20 AOR Evaluation Model: ASTRUM (2004)

Calculation: Westinghouse WCAP-16841-P, November 2007 Fuel: VANTAGE+ 17 x 17 Limiting Fuel Type: VANTAGE+ 17 x 17 Limiting Single Failure: Loss of one train of ECCS flow Limiting Break Size and Location: Guillotine break in the Cold Leg Reference PCT PCT = 2041.0°F MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS 30-Day 10 CFR 50.46 report dated March 15, 2011 (Note 14) ~PCT= 0 °F 10 CFR 50.46 report dated April 6, 2011 (Note 15) ~PCT= 0 °F 30-Day 10 CFR 50.46 report dated March 19, 2012 (Note 16) ~PCT= -42 °F 10 CFR 50.46 report dated April 6, 2012 (Note 17) ~PCT= 0 °F 10 CFR 50.46 report dated April 5, 2013 (Note 19) ~PCT= 0 °F 10 CFR 50.46 report dated April 7, 2014 (Note 21) ~PCT= +46 °F 10 CFR 50.46 report dated April 7, 2015 (Note 22) ~PCT= +2 °F 10 CFR 50.46 report dated April 7, 2016 (Note 23) ~PCT= 0 °F 10 CFR 50.46 report dated April 7, 2017 (Note 24) ~PCT= 0 °F NET PCT PCT= 2047.0°F B. CURRENT LOCA MODEL ASSESSMENTS General Code Maintenance (Note 25) ~PCT= 0 °F Evaluation of Inconsistent Application of Numerical Ramp Applied to ~PCT= 0 °F the Entrained Liquid I Vapor lnterfacial Draq Coefficient (Note 25)

Evaluation of Inappropriate Resetting of Transverse Liquid Mass ~PCT= 0 °F Flow (Note 25)

Evaluation of Steady-State Fuel Temperature Calibration Method ~PCT= 0 °F (Note 25)

Total PCT change from current assessments L ~PCT= 0 °F Cumulative PCT change from current assessments L I ~PCT I= 0 °F NET PCT PCT= 2047.0°F Page 6 of 12

Attachment 1 Braidwood and Byron Stations, Units 1 and 2 10 CFR 50.46 Report PLANT NAME: Byron Station Unit 1 ECCS EVALUATION MODEL: Small Break Loss of Coolant Accident (SBLOCA)

REPORT REVISION DATE: 4/9/18 CURRENT OPERATING CYCLE: 22 ANALYSIS OF RECORD (AOR)

Evaluation Model: NOTRUMP Calculation: Westinghouse CN-LIS-00-208, December 2000 Fuel: VANTAGE+ 17 x 17 Limiting Fuel Type: VANTAGE+ 17 x 17 Limiting Single Failure: Loss of one train of ECCS flow Limiting Break Size and Location: 2-inch Break in the Bottom of the Cold Leg Reference Peak Cladding Temperature (PCT) PCT= 1624.0°F MARGIN ALLOCATION A. PRIOR LOSS OF COOLANT ACCIDENT (LOCA) MODEL ASSESSMENTS 10 CFR 50.46 report dated June 11, 2001 (Note 1) dPCT = 0 °F 10 CFR 50.46 report dated April 18, 2002 (Note 2) dPCT = 0 °F 1o CFR 50.46 report dated April 14, 2003 (Note 3) dPCT = 0 °F 10 CFR 50.46 report dated April 14, 2004 (Note 4) dPCT = +35 °F 10 CFR 50.46 report dated April 14, 2005 (Note 5) dPCT = 0 °F 10 CFR 50.46 report dated April 14, 2006 (Note 6) dPCT = 0 °F 10 CFR 50.46 report dated April 13, 2007 (Note 7) dPCT = 0 °F 30-Day 10 CFR 50.46 report dated June 22, 2007 (Note 9) dPCT = 0 °F 10 CFR 50.46 report dated April 11, 2008 (Note 11) dPCT = +90 °F 10 CFR 50.46 report dated April 9, 2009 (Note 12) dPCT = 0 °F 10 CFR 50.46 report dated April 8, 201 O (Note 13) dPCT = 0 °F 10 CFR 50.46 report dated April 6, 2011 (Note 15) dPCT = 0 °F 10 CFR 50.46 report dated April 6, 2012 (Note 17) dPCT = 0 °F 10 CFR 50.46 report dated April 5, 2013(Note19) dPCT = 0 °F 10 CFR 50.46 report dated April 7, 2014 (Note 21) dPCT = 0 °F 10 CFR 50.46 report dated April 7, 2015 (Note 22) dPCT = 0 °F 10 CFR 50.46 report dated April 7, 2016 (Note 23) dPCT = 0 °F 10 CFR 50.46 report dated April 7, 2017 (Note 24) dPCT = 0 °F NET PCT PCT= 1749.0°F Page 7 of 12

Attachment 1 Braidwood and Byron Stations, Units 1 and 2 10 CFR 50.46 Report B. CURRENT LOCA MODEL ASSESSMENTS General Code Maintenance (Note 25) ~PCT= 0 °F Error in the Upper Plenum Fluid Volume Calculation (Note 25) ~PCT= 0 °F Total PCT change from current assessments L ~PCT= 0 °F Cumulative PCT change from current assessments L I ~PCT I= 0 °F NET PCT PCT= 1749.0°F Page 8 of 12

Attachment 1 Braidwood and Byron Stations, Units 1 and 2 10 CFR 50.46 Report PLANT NAME: Byron Station Unit 1 ECCS EVALUATION MODEL: Large Break Loss of Coolant Accident (LBLOCA)

REPORT REVISION DATE: 4/9/18 CURRENT OPERATING CYCLE: 22 AOR Evaluation Model: ASTRUM (2004)

Calculation: Westinghouse WCAP-16841-P, November 2007 Fuel: VANTAGE+ 17x17 Limiting Fuel Type: VANTAGE+ 17 x 17 Limiting Single Failure: Loss of one train of ECCS flow Limiting Break Size and Location: Guillotine break in the Cold Leg Reference PCT PCT= 1913.0°F MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS 30-Day 10 CFR 50.46 report dated March 15, 2011 (Note 14) L'.\PCT = 0 °F 10 CFR 50.46 report dated April 6, 2011 (Note 15) L'.\PCT = 0 °F 10 CFR 50.46 report dated April 6, 2012 (Note 17) L'.\PCT = 0 °F 30-Day 10 CFR 50.46 report dated May 21, 2012 (Note 18) L'.\PCT = +44 °F 10 CFR 50.46 report dated April 5, 2013 (Note 19) L'.\PCT = 0 °F 30-Day 10 CFR 50.46 report dated February 27, 2014 (Note 20) L'.\PCT = +66 °F 10 CFR 50.46 report dated April 7, 2014 (Note 21) L'.\PCT = 0 °F 10 CFR 50.46 report dated April 7, 2015 (Note 22) L'.\PCT = +2 °F 10 CFR 50.46 report dated April 7, 2016 (Note 23) L'.\PCT = 0 °F 10 CFR 50.46 report dated April 7, 2017 (Note 24) L'.\PCT = 0 °F NET PCT PCT= 2025.0°F B. CURRENT LOCA MODEL ASSESSMENTS General Code Maintenance (Note 25) L'.\PCT = 0 °F Evaluation of Inconsistent Application of Numerical Ramp Applied to L'.\PCT = 0 °F the Entrained Liquid I Vapor lnterfacial Draq Coefficient (Note 25)

Evaluation of Inappropriate Resetting of Transverse Liquid Mass L'.\PCT = 0 °F Flow (Note 25)

Evaluation of Steady-State Fuel Temperature Calibration Method L'.\PCT = 0 °F (Note 25)

Total PCT change from current assessments L L'.\PCT = 0 °F Cumulative PCT change from current assessments L IL'.\PCT I= 0 °F NET PCT PCT= 2025.0°F Page 9 of 12

Attachment 1 Braidwood and Byron Stations, Units 1 and 2 10 CFR 50.46 Report PLANT NAME: Byron Station Unit 2 ECCS EVALUATION MODEL: Small Break Loss of Coolant Accident (SBLOCA)

REPORT REVISION DATE: 4/9/18 CURRENT OPERATING CYCLE: gj_

AOR Evaluation Model: NOTRUMP Calculation: Westinghouse CN-LIS-00-208, December 2000 Fuel: VANTAGE+ 17 x 17 Limiting Fuel Type: VANTAGE+ 17 x 17 Limiting Single Failure: Loss of one train of ECCS flow Limiting Break Size and Location: 2-inch Break in the Bottom of the Cold Leg Reference PCT PCT= 1627.0°F MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS 10 CFR 50.46 report dated June 11, 2001 (Note 1) APCT = +3 °F 10 CFR 50.46 report dated April 18, 2002 (Note 2) APCT = 0 °F 10 CFR 50.46 report dated April 14, 2003 (Note 3) APCT = 0 °F 10 CFR 50.46 report dated April 14, 2004 (Note 4) APCT = +35 °F 10 CFR 50.46 report dated April 14, 2005 (Note 5) APCT = 0 °F 10 CFR 50.46 report dated April 14, 2006 (Note 6} APCT = 0 °F 10 CFR 50.46 report dated April 13, 2007 (Note 7) APCT = 0 °F 30-Day 10 CFR 50.46 report dated May 10, 2007 (Note 8) APCT = +90 °F 30-Day 10 CFR 50.46 report dated June 22, 2007 (Note 9) APCT = 0 °F 10 CFR 50.46 report dated April 11, 2008 (Note 11) APCT = 0 °F 10 CFR 50.46 report dated April 9, 2009 (Note 12} APCT = 0 °F 10 CFR 50.46 report dated April 8, 201 O (Note 13} APCT = 0 °F 10 CFR 50.46 report dated April 6, 2011 (Note 15} APCT = 0 °F 10 CFR 50.46 report dated April 6, 2012 (Note 17) APCT = 0 °F 10 CFR 50.46 report dated April 5, 2013 (Note 19) APCT = 0 °F 10 CFR 50.46 report dated April 7, 2014 (Note 21) APCT = 0 °F 10 CFR 50.46 report dated April 7, 2015 (Note 22} APCT = 0 °F 10 CFR 50.46 report dated April 7, 2016 (Note 23) APCT = 0 °F 10 CFR 50.46 report dated April 7, 2017 (Note 24) APCT = 0 °F NET PCT PCT = 1755.0°F Page 10 of 12

Attachment 1 Braidwood and Byron Stations, Units 1 and 2 10 CFR 50.46 Report B. CURRENT LOCA MODEL ASSESSMENTS General Code Maintenance (Note 25) t1PCT = 0 °F Error in the Upper Plenum Fluid Volume Calculation (Note 25) t1PCT = 0 °F Total PCT change from current assessments L t1PCT = 0 °F Cumulative PCT change from current assessments L It1PCT I= 0 °F NET PCT PCT= 1755.0°F Page 11 of 12

Attachment 1 Braidwood and Byron Stations, Units 1 and 2 10 CFR 50.46 Report PLANT NAME: Byron Station Unit 2 ECCS EVALUATION MODEL: Large Break Loss of Coolant Accident (LBLOCA)

REPORT REVISION DATE: 4/9/18 CURRENT OPERATING CYCLE: gj_

AOR Evaluation Model: ASTRUM (2004)

Calculation: Westinghouse WCAP-16841-P, November 2007 Fuel: VANTAGE+ 17 x 17 Limiting Fuel Type: VANTAGE+ 17 x 17 Limiting Single Failure: Loss of one train of ECCS flow Limiting Break Size and Location: Guillotine break in the Cold Leg Reference PCT PCT= 2041.0°F MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS 30-Day 10 CFR 50.46 report dated March 15, 2011 (Note 14) ~PCT= 0 °F 10 CFR 50.46 report dated April 6, 2011 (Note 15) ~PCT= 0 °F 30-Day 10 CFR 50.46 report dated March 19, 2012 (Note 16) ~PCT= -42 °F 10 CFR 50.46 report dated April 6, 2012 (Note 17) ~PCT= 0 °F 10 CFR 50.46 report dated April 5, 2013 (Note 19) ~PCT= 0 °F 10 CFR 50.46 report dated April 7, 2014 (Note 21) ~PCT= +46 °F 10 CFR 50.46 report dated April 7, 2015 (Note 22) ~PCT= +2 °F 10 CFR 50.46 report dated April 7, 2016 (Note 23) ~PCT= 0 °F 10 CFR 50A6 report dated April 7, 2017 (Note 24) ~PCT= 0 °F NET PCT PCT= 2047.0°F B. CURRENT LOCA MODEL ASSESSMENTS General Code Maintenance (Note 25) ~PCT= 0 °F Evaluation of Inconsistent Application of Numerical Ramp Applied to ~PCT= 0 °F the Entrained Liquid I Vapor lnterfacial Drag Coefficient (Note 25)

Evaluation of Inappropriate Resetting of Transverse Liquid Mass ~PCT= 0 °F Flow (Note 25)

Evaluation of Steady-State Fuel Temperature Calibration Method ~PCT= 0 °F (Note 25)

Total PCT change from current assessments L ~PCT= 0 °F Cumulative PCT change from current assessments L I ~PCT I= 0 °F NET PCT PCT = 2047 .0°F Page 12 of 12

Attachment 2 Braidwood and Byron Stations, Units 1 and 2 10 CFR 50.46 Report Assessment Notes 1 . Prior LOCA Model Assessment The 10 CFR 50.46 report dated June 11, 2001 reported new small break loss of coolant accident (SBLOCA) analyses to support operations at uprated power conditions. The same report assessed the impact from annular axial blankets on SBLOCA analysis, which determined a 0°F PCT penalty for Units 1 and a 3°F PCT penalty for Units 2. Evaluations for plant conditions and SBLOCA model changes which resulted in 0°F PCT change were reported.

2. Prior LOCA Model Assessment The 10 CFR 50.46 report dated April 18, 2002 reported evaluations for SBLOCA model changes which resulted in 0°F PCT change.
3. Prior LOCA Model Assessment The 10 CFR 50.46 report dated April 14, 2003 reported evaluations for SBLOCA model changes which resulted in 0°F PCT change.
4. Prior LOCA Model Assessment The 10 CFR 50.46 report dated April 14, 2004 reported evaluations for a SBLOCA assessment related to NOTRUMP bubble rise/drift flux model inconsistency corrections, which resulted in 35°F PCT assessment.
5. Prior LOCA Model Assessment The 10 CFR 50.46 report dated April 14, 2005 reported evaluations for SBLOCA model changes which resulted in O °F PCT change for Byron and Braidwood Unit 1 and Unit 2.

The Braidwood Station, Unit 1 assembly N1 OS was reconstituted with two stainless steel filler rods during Braidwood Unit 1 Refueling Outage 11 . This assembly is reloaded into the core and is in use during Braidwood Unit 1 Cycle 12 operation. The introduction of up to five stainless steel filler rods has been evaluated and shown to have no impact on SBLOCA analysis. The estimated PCT effect is 0°F for Braidwood Unit 1. This assembly was discharged during Reload 12.

6. Prior LOCA Model Assessment The 10 CFR 50.46 report dated April 14, 2006 reported evaluations for SBLOCA NOTRUMP General Code Maintenance which resulted in 0°F change.
7. Prior LOCA Model Assessment The 10 CFR 50.46 report dated April 13, 2007 reported evaluations for SBLOCA model changes and errors. The report documented general code maintenance for NOTRUMP, AXIOM lead test assembly evaluation and NOTRUMP refined break spectrum, which resulted in 0°F PCT impact.

Page 1 of 6

Attachment 2 Braidwood and Byron Stations, Units 1 and 2 10 CFR 50.46 Report Assessment Notes

8. Prior LOCA Model Assessment The 30-day 10 CFR 50.46 report dated May 10, 2007 applicable to Byron Station Unit 2 reported an assessment of the Emergency Core Cooling System (ECCS), which evaluated changes in ECCS flow during the recirculation phase due to Generic Safety Issue (GSI) -

191 related safety injection (SI) throttle valve replacements. The evaluation of recirculation phase ECCS flow changes relative to impact on the current Analysis of Record (AOR) was performed for the SBLOCA. Based on the NOTRUMP and SBLOCTA calculations performed for Byron Station Unit 2, a conservative, bounding PCT assessment of +90°F was applied to the current Byron Station Unit 2 SBLOCA PCT.

9. Prior LOCA Model Assessment The 30-day 10 CFR 50.46 report dated June 22, 2007 applicable to Byron Station Units 1 and 2 and Braidwood Station Units 1 and 2 reported an error in the HOT SPOT Code which did not impact the SBLOCA analysis. The 30-day report also reported minor errors with the reactor vessel data collections that potentially affected the vessel inlet and outlet fluid volume, metal mass and surface area. The corrected values were evaluated for impact, and a 0°F penalty was assessed for Byron Station Units 1 and 2 and Braidwood Station Units 1 and 2, SBLOCA analysis.
10. Prior LOCA Model Assessment The 30-day 10 CFR 50.46 report dated November 19, 2007 applicable to Braidwood Station Unit 1 reported an assessment of the Emergency Core Cooling System (ECCS), which evaluated changes in ECCS flow during the recirculation phase due to GSl-191 related SI throttle valve replacements. The evaluation of recirculation phase ECCS flow changes relative to impact on the current Analysis of Record (AOR) was performed for the SBLOCA.

Based on the NOTRUMP and SBLOCA calculations performed for Braidwood Station Unit 1, a conservative, bounding PCT assessment of +90°F was applied to the Braidwood Station Unit 1 SBLOCA PCT.

11 . Prior LOCA Model Assessment The 10 CFR 50.46 report dated April 11, 2008 reported evaluations for LOCA model changes and errors. Applicable to Braidwood Station Unit 2 and Byron Station Unit 1, the ECCS assessment evaluated changes in ECCS flow during the recirculation phase due to GSl-191 related safety injection SI throttle valve replacements. A conservative, bounding PCT assessment of +90°F was applied to the Braidwood Station Unit 2 and Byron Station Unit 1 SBLOCA PCTs. The report also documented general code maintenance for SBLOCA and evaluation for pump weir resistance modeling for SBLOCA analyses, which resulted in 0°F PCT impact.

12. Prior LOCA Model Assessment The 10 CFR 50.46 report dated April 9, 2009 reported evaluations for LOCA model changes and errors. The report documents general code maintenance for SBLOCA, errors in reactor vessel lower plenum surface area calculations, discrepancies in metal mass from drawings, Page 2 of 6

Attachment 2 Braidwood and Byron Stations, Units 1 and 2 10 CFR 50.46 Report Assessment Notes and an evaluation of Areva Lead Use Assemblies. All of which have a 0°F PCT penalty associated with them.

13. Prior LOCA Model Assessment The 10 CFR 50.46 report dated April 8, 201 O reported no evaluations for SBLOCA model changes which resulted in 0°F PCT change.
14. Prior LOCA Model Assessment The 30-day 10 CFR 50.46 report dated March 15, 2011 reported a new large break BELOCA (ASTRUM) analysis to support operations for Byron and Braidwood Stations, Units 1 and 2. The same report assessed the impact from several errors, issues, and code enhancements. Each of these errors/issues/code enhancements had a 0°F PCT impact with a net 0°F PCT impact.
15. Prior LOCA Model Assessment The 10 CFR 50.46 report dated April 6, 2011 reported no evaluations for the Large Break LOCA model. For the SBLOCA model, the following errors, changes, corrections or enhancements were reported. Two errors relating to urania-gadolinia pellet thennal conductivity calculation, two errors relating to pellet crack and dish volume calculation, a discrepancy involving the treatment of vessel average temperature uncertainty, and general code maintenance were reported for the SBLOCA model. All of these issues were determined to have an estimated impact of 0°F.
16. Prior LOCA Model Assessment The 30-day 10 CFR 50.46 report dated March 19, 2012 applicable to Braidwood Station Unit 2 and Byron Station Unit 2 reported an assessment of Thermal Conductivity Degradation (TCD) with an associated peaking factor burndown and a design input change consisting of a reduction in upper bound steam generator tube plugging, a reduction in nominal upper bound nominal vessel average temperature, and an increase in the assumed containment pressure boundary condition. As a result, the estimated effect of the TCD with burndown was determined to be +148°F and the estimated effect of the design input changes was determined to be -190°F. These two assessments are coupled together via their evaluations of burnup effects which include thermal conductivity degradation, peaking factor burndown and design input changes. Therefore, the combined affect of these two changes results in a net change in the reported LBLOCA PCT for Braidwood Station Unit 2 and Byron Station Unit 2 of -42°F.
17. Prior LOCA Model Assessment The 10 CFR 50.46 report dated April 6, 2012 reported evaluations for LOCA model changes and errors. The report documents general code maintenance for both SBLOCA and LBLOCA, errors in Radiation Heat Transfer Logic for SBLOCA, and an error in the Maximum Fuel Rod Time Step Logic for SBLOCA. All of which have a 0°F PCT penalty associated with them.

Page 3 of 6

Attachment 2 Braidwood and Byron Stations, Units 1 and 2 10 CFR 50.46 Report Assessment Notes

18. Prior LOCA Model Assessment The 30-day 10 CFR 50.46 report dated May 21, 2012 applicable to Braidwood Station Unit 1 and Byron Station Unit 1 reported an* assessment of TCD with an associated peaking factor burndown an analysis input change consisting of a reduction in conservatism in analyzed FQ values and an increase in the assumed containment pressure boundary condition. As a result, the estimated effect of the TCD with burndown was determined to be + 110°F and the estimated effect of the analysis input changes was determined to be -66°F. These two assessments are coupled together via their evaluations of burnup effects which include thermal conductivity degradation, peaking factor burndown and analysis input changes.

Therefore, the combined affect of these two changes results in a net change in the reported LBLOCA PCT for Braidwood Station Unit 1 and Byron Station Unit 1 of +44°F.

19. Prior LOCA Model Assessment The 10 CFR 50.46 report dated April 5, 2013 reported evaluations for LBLOCA model changes, and HOTSPOT and WCOBRA!fRAC code corrections. For SBLOCA, TCD was evaluated with NOTRUMP to estimate the effect on the limiting cladding temperature model.

All evaluations led to PCT impact of 0°F.

20. Prior LOCA Model Assessment The 30-day 10 CFR 50.46 report dated February 27, 2014 applicable to Braidwood Station Unit 1 and Byron Station Unit 1 reported evaluations for LBLOCA model changes and code corrections. For Braidwood Station Unit 2 and Byron Station Unit 2 a net change of 46°F PCT impact did not require inclusion in the 30-day report and is reported herein. Revised heat transfer multiplier distributions, changes to grid blockage ratio and porosity and HOTSPOT burst strain error corrections was determined to be 5°F, 24°F, and 37°F PCT impact, respectively for Braidwood Station Unit 1 and Byron Station Unit 1. Other model changes and code corrections sum to 0°F PCT impact. Therefore, the combined effect of the changes resulted in a net change of 66°F PCT impact for Braidwood Station Unit 1 and Byron Station Unit 1.
21. Prior LOCA Model Assessment The 10 CFR 50.46 report dated April 7, 2014 applicable to Braidwood Station Unit 2 and Byron Station Unit 2 reported evaluations for LBLOCA model changes and code corrections.

For Braidwood Station Unit 1 and Byron Station Unit 1 a net change of 66°F PCT impact required a 30-day report sent on February 27, 2014 (Note 20). Revised heat transfer multiplier distributions, changes to grid blockage ratio and porosity and HOTSPOT burst strain error corrections was determined to be 7°F, 24°F, and 15°F PCT impact, respectively for Braidwood Station Unit 2 and Byron Station Unit 2. Other model changes and code corrections sum to 0°F PCT impact. Therefore, the combined effect of the changes resulted in a net change of 46°F PCT impact for Braidwood Station Unit 2 and Byron Station Unit 2 LBLOCA. SBLOCTA cladding strain requirement for fuel rod burst resulted in a 0°F PCT impact to Byron and Braidwood Stations, Units 1 and 2 SBLOCA.

Page 4 of 6

Attachment 2 Braidwood and Byron Stations, Units 1 and 2 10 CFR 50.46 Report Assessment Notes

22. Prior LOCA Model Assessment The 10 CFR 50.46 report dated April 7, 2015 reported General Code Maintenance and a change to Safety Injection and Core Spray flow rates for LBLOCA & SBLOCA. The report also reported an error in the decay group uncertainty factor for LBLOCA, errors in the fuel rod gap conductance, radiation heat transfer model and pre-DNB cladding surface heat transfer coefficient and an evaluation to increased Auxiliary feedwater switchover delay for SBLOCA. With the exception of 2°F PCT impact to LBLOCA due to the change to Safety Injection and Core Spray flows, all other changes reported an impact of 0°F PCT.
23. Prior LOCA Model Assessment The 10 CFR 50.46 report dated April 7, 2016 reported General Code Maintenance for the SBLOCA which led to a PCT impact of 0°F. There were no impacts to LBLOCA.
24. Prior LOCA Model Assessment The 10 CFR 50.46 report dated April 7, 2017 reported General Code Maintenance for the LBLOCA to enhance the usability of codes and to streamline future analyses which led to a PCT impact of 0°F. There were two errors assessed to the LBLOCA analysis related to the calculation of high temperature oxidation within a realistic LBLOCA calculation and to the use of the American Society of Mechanical Engineers (ASME) steam tables to calculate the steady-state upper head liquid temperature as a function of the pressure and specific enthalpy in the ASTRUM software program. Both errors each resulted in an estimated PCT impact of 0°F for 10 CFR 50.46. Lastly there was one evaluation to the LBLOCA analysis where non-conservative methods here used in modeling the effect of containment purge on the containment pressure response. This evaluation using a more appropriate/conservative method was estimated to have an impact of 0°F for 10 CFR 50.46. There were no impacts to SBLOCA.
25. Current LOCA Model Assessment For the current LBLOCA and SBLOCA analysis, various changes have been made to enhance the usability of codes and to streamline future analyses. Examples of these changes include modifying input variable definitions, units and defaults; improving the input diagnostic checks; enhancing the code output; optimizing active coding; and eliminating inactive coding. These changes resulted in an estimated PCT impact of 0°F.

There was one error assessed to the SBLOCA analysis. An error was found in the fluid volume calculation in the upper plenum where the support column outer diameter was being used instead of the inner diameter. The correction of this error lead to a reduction in the upper plenum fluid volume used in the Appendix K Small Break LOCA analyses. The corrected values represent a less than 1% change in the total RCS fluid volume and will be incorporated on a forward-fit basis, based on the evaluated impact on the current licensing basis analysis results and is to have a negligible effect on small break LOCA analysis results, leading to an estimated PCT impact of 0°F.

There were three evaluations assessed to the LBLOCA analysis. The first evaluation involved a numerical ramp which was used to account for the disappearance of the Page 5 of 6

Attachment 2 Braidwood and Byron Stations, Units 1 and 2 10 CFR 50.46 Report Assessment Notes entrained liquid phase was applied to the entrained liquid I vapor interfacial drag coefficient.

The numerical ramp was applied such that the interfacial drag coefficient used in the solution of the entrained liquid and vapor momentum equations was not consistent.

WCOBRA/TRAC was updated to apply the numerical ramp prior to usage of the interfacial drag coefficient in the momentum equations, such that a consistent 'interfacial drag coefficient was used in the entrained liquid and vapor momentum equations. It was determined based on the code validation results, the impact of correcting the error is estimated to have a 0°F impact on PCT.

The second evaluation involved the WCOBRA/TRAC routine which evaluates the mass and energy residual error of the time step solution, the transverse liquid mass flow is reset as the liquid phase disappears. The routine is updated to remove the resetting of the transverse liquid mass flow since the routine is to only evaluate the residual error based on the time step solution values. Based on the code validation results and limited applicability of the logic removed, correcting the error is estimated to have a 0°F impact on PCT.

The third evaluation concerned how the ASTRUM steady-state fuel pellet temperature calibration method involves solving for the hot gap width (AGFACT} to calibrate the fuel temperature for each fuel rod. In some infrequent situations, small non-conservatisms can occur in the calibration process such that the resulting fuel pellet temperature will be slightly lower than intended and outside the acceptable range defined by Table 12-6 of WCAP-16009-P/NP-A. A review of licensing basis analyses concluded that the potential non-conservatisms in the fuel pellet temperature calibration did not occur for the limiting analysis cases. Therefore, an estimated PCT impact of 0°F is assigned for 10 CFR 50.46 reporting purposes.

Therefore, there is no PCT impact to the LBLOCA analysis from the evaluations and there is no PCT impact to the SBLOCA analysis from the errors.

Page 6 of 6

Retrieved from "https://kanterella.com/w/index.php?title=RS-18-039,_Stations_-_Annual_10_CFR_50.46_Report_of_Emergency_Core_Cooling_System_Evaluation_Model_Changes_and_Errors&oldid=2073266"