CP-201500263, Annual Report of Changes in Peak Cladding Temperature

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Annual Report of Changes in Peak Cladding Temperature
ML15118A535
Person / Time
Site: Comanche Peak  Luminant icon.png
Issue date: 04/13/2015
From: Flores R, Madden F
Luminant Generation Co, Luminant Power
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
CP-201500263, TXX-15038
Download: ML15118A535 (15)
v • d • e


Text

Rafael Flores Luminant Power Senior Vice President P 0 Box 1002 011% & Chief Nuclear Officer 6322 North FM 56 rafael.tlores@Luminant.com Glen Rose, TX 76043 Lum inant T 254 897 5590 C 817 559 0403 F 254 897 6652 CP-201500263 Ref. # 10CFR50.46 Log # TXX-15038 April 13, 2015 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001

SUBJECT:

COMANCHE PEAK NUCLEAR POWER PLANT (CPNPP)

DOCKET NOS. 50-445 AND 50-446 ANNUAL REPORT OF CHANGES IN PEAK CLADDING TEMPERATURE REF: 1. Letter logged TXX-12146, dated October 18, 2012, from Rafael Flores of Luminant Power to the NRC regarding "30-Day Report for Significant Change in Peak Clad Temperature"

2. Letter logged TXX-14058; dated April 22, 2014, from Rafael Flores of Luminant Power to the NRC regarding "30-Day Report for Significant Change in Peak Clad Temperature"

Dear Sir or Madam:

Pursuant to 10CFR50.46(a)(3)(ii)-, Luminant Generation Company LLC (Luminant Power) hereby submits the attached peak cladding temperatures (PCT) for Comanche Peak Nuclear Power Plant (CPNPP), Units 1 and 2. The Large-Break Loss-of-Coolant-Accident (LBLOCA) and Small-Break Loss-of-Coolant Accident analysis for Units 1 and 2 were performed for Luminant Power with the approved Westinghouse methodologies listed in Technical Specification 5.6.5. Per Reference 1, Luminant Power previously submitted information regarding fuel pellet thermal conductivity with fuel burnup in the Westinghouse Best Estimate LBLOCA analysis methodology for CPNPP Units 1 and 2. Also, per Reference 2, Luminant Power submitted information regarding an evaluation of revised Heat Transfer Multiplier Distributions, changes to Grid Blockage Ratio and Porosity, and application of a corrected Burst Strain in the Westinghouse Best Estimate LBLOCA analysis methodology for CPNPP Unit 2 and its effect on Peak Cladding Temperature (PCT).

Luminant Power has reviewed the notification of 10CFR50.46 reporting information pertaining to the Emergency Core Cooling System (ECCS) Evaluation Model changes that were implemented by Westinghouse for 2014. The review concludes that the effect of additional changes to, or errors in, the Evaluation Models on the limiting transient PCT were not significant for 2014.

This report of the ECCS Evaluation Model changes provides an update on an annual basis. Attachment 1 provides an assessment of the specific changes and enhancements to the Westinghouse Evaluation Models for 2014.

U. S. Nuclear Regulatory Commission TXX-15038 Page 2 April 13, 2015 provides the calculated LBLOCA and Small Break Loss-of-Coolant Accident PCT margin allocations in effect for the 2014 Comanche Peak Units I and 2 Evaluation Models. There were no changes, error corrections, or enhancements to the 1985 Westinghouse Small Break Loss-of-Coolant Accident Evaluation Model with NOTRUMP. The PCT values determined in the LBLOCA analysis of record, combined with all of the PCT allocations, remain well below the 10CFR50.46 regulatory limit of 2200 degrees Fahrenheit. Therefore, CPNPP Units 1 and 2 are in compliance with 10CFR50.46 requirements and no other action is required.

This communication contains no new licensing basis commitments regarding CPNPP Units 1 and 2.

Should you have any questions, please contact Mr. J. D. Seawright at (254) 897-0140.

Sincerely, Luminant Generation Company LLC Rafael Flores

  • By: v ý

/Fred W Madden Director, External Affairs Attachments - 1. Assessment of Specific Changes and Enhancements to the Westinghouse Evaluation Models for 2014

2. CPNPP Units 1 and 2 Peak Cladding Temperatures c- Marc L. Dapas, Region IV Balwant K. Singal, NRR Resident Inspectors, Comanche Peak

Attachment I to TXX-15038 Page 1 of 5 Assessment of Specific Changes and Enhancements to the Westinghouse Evaluation Models for 2014 GENERAL CODE MAINTENANCE

Background

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 represent Discretionary Changes that will be implemented on a forward-fit basis in accordance with Section 4.1.1 of WCAP-13451, "Westinghouse Methodology for Implementation of 10 CFR 50.46 Reporting."

Affected Evaluation Model(s) 1996 Westinghouse Best Estimate Large Break LOCA Evaluation Model 2004 Westinghouse Realistic Large Break LOCA Evaluation Model Using Automated Statistical Treatment of Uncertainty Method (ASTRUM) 1985 Westinghouse Small Break LOCA Evaluation Model with NOTRUMP Estimated Effect The nature of these changes leads to an estimated Peak Cladding Temperature (PCT) impact of 0 degrees Fahrenheit (OF).

Attachment I to TXX-15038 Page 2 of 5 ERRORS IN DECAY GROUP UNCERTAINTY FACTORS

Background

Errors in the calculation of decay heat were discovered in the WCOBRA/TRAC code. The decay group uncertainty factors for each fissile isotope are provided in Table 8-14 of WCAP-16009-P-A. The uncertainty factors for 239 Pu were applied to 238U, and those for 238U were applied to 239Pu. This error causes an over-prediction of the uncertainty in decay power from 239 Pu and an under-prediction of the uncertainty in decay power from 238U. Further, the decay group uncertainty factor for Decay Group 6 of 235U was erroneously coded as 2.5% instead of 2.25%. Correction of these errors impacts the application of the sampled decay heat uncertainty, which may result in small changes to the decay heat power. These issues have been evaluated to estimate the impact on Automated Statistical Treatment of Uncertainty Method (ASTRUM) Best-Estimate (BE)

Large-Break Loss-of-Coolant Accident (LBLOCA) analysis results. The resolution of these issues represents a closely-related group of Non-Discretionary Changes in accordance with Section 4.1.2 of WCAP-13451.

Affected Evaluation Model 2004 Westinghouse Realistic Large Break LOCA Evaluation Model Using ASTRUM Estimated Effect The issues described above are judged to have either no effect or a negligible effect on the LBLOCA analysis results, leading to an estimated Peak Cladding Temperature (PCT) impact of 0°F for Comanche Peak Units I and 2.

Attachment I to TXX-1 5038 Page 3 of 5 FUEL ROD GAP CONDUCTANCE ERROR

Background

An error was identified in the fuel rod gap conductance model in the NOTRUMP computer code (reactor coolant system response model). The error is associated with the use of an incorrect temperature in the calculation of the cladding emissivity term. This error corresponds to a Non-Discretionary Change as described in Section 4.1.2 of WCAP-13451.

Affected Evaluation Model(s) 1985 Westinghouse Small Break LOCA Evaluation Model with NOTRUMP Estimated Effect The estimated effect was determined based on a combination of engineering judgment of the phenomena and physics of a small break LOCA and sensitivity calculations performed with the advanced plant version of NOTRUMP. It was concluded that this error has a negligible effect on small break LOCA analysis results, leading to an estimated Peak Cladding Temperature (PCT) impact of 0°F.

to TXX-1 5038 Page 4 of 5 RADIATION HEAT TRANSFER MODEL ERROR

Background

Two errors were discovered in the calculation of the radiation heat transfer coefficient within the fuel rod model of the NOTRUMP computer code (reactor coolant system response model). First, existing logic did not preclude non-physical negative or large (negative or positive) radiation heat transfer coefficients from being calculated.

These erroneous calculations occurred when the vapor temperature exceeded the cladding surface temperature or when the predicted temperature difference was less than 10 F. Second, a temperature term incorrectly used degrees Fahrenheit instead of Rankine. These errors represent a closely related group of Non-Discretionary problems in accordance with Section 4.1.2 of WCAP-13451.

Affected Evaluation Model(s) 1985 Westinghouse Small Break LOCA Evaluation Model with NOTRUMP Estimated Effect The estimated effect was determined based on a combination of engineering judgment of the phenomena and physics of a small break LOCA and sensitivity calculations performed with the advanced plant version of NOTRUMP. It was concluded that this error has a negligible effect on small break LOCA analysis results, leading to an estimated Peak Cladding Temperature (PCT) impact of 0°F.

to TXX-1 5038 Page 5 of 5 SBLOCTA PRE-DNB CLADDING SURFACE HEAT TRANSFER COEFFICIENT CALCULATION

Background

Two errors were discovered in the pre-departure from nucleate boiling (pre-DNB) cladding surface heat transfer coefficient calculation in the SBLOCTA code (cladding heat-up calculations). The first error is a result of inconsistent time units (hours vs. seconds) in the parameters used for the calculation of the Reynolds and Prandtl numbers, and the second error relates to an incorrect diameter used to develop the area term in the cladding surface heat flux calculation. Both of these issues impact the calculation of the pre-DNB convective heat transfer coefficient, representing a closely related group of Non-Discretionary Changes to the Evaluation Model as described in Section 4.1.2 of WCAP-13451.

Affected Evaluation Model(s) 1985 Westinghouse Small Break LOCA Evaluation Model with NOTRUMP Estimated Effect These errors have been corrected in the SBLOCTA code. Because this condition occurred prior to DNB, it was judged that these errors had no direct impact on the cladding heat-up related to the core uncovery period. A series of validation tests were performed and confirmed that these errors have a negligible effect on SBLOCA analysis results, leading to an estimated Peak Cladding Temperature (PCT) impact of 0°F.

to TXX-15038 Page 1 of 8 CPNPP Units I and 2 Peak Cladding Temperatures Westinghouse LOCA Peak Clad Temperature Summary for ASTRUM Best Estimate Large Break Plant Name: Comanche Peak Unit 1 Utility Name: Luminant Revision Date: 2/5/2015 Analysis Information EM: ASTRUM (2004) Analysis Date: 7/27/2007 Limiting Break Size: Guillotine FQ: 2.5 FdH: 1.6 Fuel: OFA SGTP (%): 10 Notes:

Clad Temp (OF) Ref. Notes LICENSIS BASIS Analysis-Of-Record PCT 1492 1 PCT Assessments (Delta PCT)

A. PRIOR ECCS MODEL ASSESSMENTS

1. Evaluation of Fuel Pellet Thermal Conductivity 122 2 (a)

Degradation and Peaking Factor Bumdown

2. Revised Heat Transfer Multiplier Distributions -6 3
3. Error in Burst Strain Application 21 4 B. PLANNED PLANT MODIFICATION EVALUATIONS
1. None 0 C. 2014 ECCS MODEL ASSESSMENTS
1. None 0 D. OTHER
1. None 0 LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 1629

References:

1. WCAP-16762-P, Revision I, "Best-Estimate Analysis of the Large-Break Loss-of-Coolant Accident for the Comanche Peak Nuclear Power Plant Unit 1 Using the ASTRUM Methodology," March 2009.
2. LTR-LIS-12-410, "Comanche Peak Units I and 2, 10 CFR 50.46 Notification and Reporting for Fuel Pellet Thermal Conductivity Degradation and Peaking Factor Buradown," September 20, 2012.
3. LTR-LIS-I 3-359,"Comanche Peak Units I and 2 10CFR50.46 Report for Revised Heat Transfer Multiplier Distributions," July 2013.
4. LTR-LIS-14-43,"Comanche Peak Units 1 and 2 10CFR50.46 Report for the HOTSPOT Burst Strain Error Correction." January 2014.

Notes:

(a) This evaluation credits peaking factor bumdown, see Reference 2.

to TXX-15038 Page 2 of 8 CPNPP Units 1 and 2 Peak Cladding Temperatures Westinghouse LOCA Peak Clad Temperature Summary for ASTRUM Best Estimate Large Break Plant Name: Comanche Peak Unit I Utility Name:

Revision Date:

Luminant 2/5/2015 Cycle 18 Analysis Information EM: ASTRUM (2004) Analysis Date: 7/27/2007 Limiting Break Size: Guillotine FQ: 2.5 FdH: 1.6 Fuel: OFA SGTP (%): 10 Notes:

Clad Temp (OF) Ref. Notes LICENSIS BASIS Analysis-Of-Record PCT 1492 1 PCT Assessments (Delta PCT)

A. PRIOR ECCS MODEL ASSESSMENTS

1. Evaluation of Fuel Pellet Thermal Conductivity 122 3 (a)

Degradation and Peaking Factor Bumdown

2. Revised Heat Transfer Multiplier Distributions -6 4
3. Error in Burst Strain Application 21 5 B. PLANNED PLANT MODIFICATION EVALUATIONS
1. PBOT/PMID Violation 0 2 C. 2014 ECCS MODEL ASSESSMENTS
1. None 0 D. OTHER
1. None 0 LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 1629

References:

I. WCAP-16762-P, Revision 1, "Best-Estimate Analysis of the Large-Break Loss-of-Coolant Accident for the Comanche Peak Nuclear Power Plant Unit I Using the ASTRUM Methodology," March 2009.

2. LTR-LIS-14-414, "LBLOCA PCT Rackup Sheet Update for the Evaluation of the Comanche Peak Unit I Cycle 18 PBOT/PMID Violations," September 2014.
3. LTR-LIS-12-410, "Comanche Peak Units I and 2, 10 CFR 50.46 Notification and Reporting for Fuel Pellet Thermal Conductivity Degradation and Peaking Factor Bumdown," September 20, 2012.
4. LTR-LIS-I 3-359,"Comanche Peak Units I and 2 10CFR50.46 Report for Revised Heat Transfer Multiplier Distributions," July 2013.
5. LTR-LIS-14-43,"Comanche Peak Units I and 2 10CFR50.46 Report for the HOTSPOT Burst Strain Error Correction," January 2014.

Notes:

(a) This evaluation credits peaking factor bumdown, see Reference 3.

to TXX- 15038 Page 3 of 8 CPNPP Units 1 and 2 Peak Cladding Temperatures Westinghouse LOCA Peak Clad Temperature Summary for ASTRUM Best Estimate Large Break Plant Name: Comanche Peak Unit 1 Utility Name: Luminant C ycle 17 Revision Date: 2/5/2015 Retired Analysis Information EM: ASTRUM (2004) Analysis Date: 7/27/2007 Limiting Break Size: Guillotine FQ: 2.5 FdH: 1.6 Fuel: OFA SGTP (%): 10 Notes:

Clad Temp (OF) Ref. Notes LICENSIS BASIS Analysis-Of-Record PCT 1492 1 PCT Assessments (Delta PCT)

A. PRIOR ECCS MODEL ASSESSMENTS

1. Evaluation of Fuel Pellet Thermal Conductivity 122 3 (a)

Degradation and Peaking Factor Burndown

2. Revised Heat Transfer Multiplier Distributions -6 4
3. Error in Burst Strain Application 21 5 B. PLANNED PLANT MODIFICATION EVALUATIONS
1. PBOT/PMID Violation 0 2 C. 2014 ECCS MODEL ASSESSMENTS
1. None 0 D. OTHER
1. None 0 LICENSING BASIS PCT + PCT ASSESSMENTS PCT 1629

References:

1. WCAP-16762-P, Revision 1, "Best-Estimate Analysis of the Large-Break Loss-of-Coolant Accident for the Comanche Peak Nuclear Power Plant Unit 1 Using the ASTRUM Methodology," March 2009.
2. LTR-LIS-13-160, "LBLOCA PCT Rackup Sheet Update for the Evaluation of the Comanche Peak Unit I Cycle 17 PBOT/PMID Violations," March 2013.
3. LTR-LIS-12-410, "Comanche Peak Units I and 2, 10 CFR 50.46 Notification and Reporting for Fuel Pellet Thermal Conductivity Degradation and Peaking Factor Bumdown," September 20, 2012.
4. LTR-LIS-1 3-359,"Comanche Peak Units I and 2 10CFR50.46 Report for Revised Heat Transfer Multiplier Distributions," July 2013.
5. LTR-LIS-14-43,"Comanche Peak Units I and 2 10CFR50.46 Report for the HOTSPOT Burst Strain Error Correction," January 2014.

Notes:

(a) This evaluation credits peaking factor bumdown, see Reference 3.

to TXX-15038 Page 4 of 8 CPNPP Units 1 and 2 Peak Cladding Temperatures Westinghouse LOCA Peak Clad Temperature Summary for Appendix K Small Break Plant Name: Comanche Peak Unit I Utility Name: Luminant Revision Date: 2/5/2015 Analysis Information EM: NOTRUMP Analysis Date: 6/8/2007 Limiting Break Size: 4 inch FQ: 2.5 FdH: 1.6 Fuel: OFA SGTP (%): 10 Notes:

Clad Temp (OF) Ref. Notes LICENSIS BASIS Analysis-Of-Record PCT 1013 1 PCT Assessments (Delta PCT)

A. PRIOR ECCS MODEL ASSESSMENTS

1. None 0 B. PLANNED PLANT MODIFICATION EVALUATIONS
1. None 0 C. 2014 ECCS MODEL ASSESSMENTS
1. None 0 D. OTHER
1. None 0 LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 1013

References:

I. WCAP-I 6840-P, "Comanche Peak Nuclear Power Plant Stretch Power Uprate Licensing Report," August 2007. (Results are included in TXX-07107., "Comanche Peak Steam Electric Station (CPSES), Docket Nos. 50-445 and 50-446, Submittal of the CPSES Units I and 2 Large and Small Break LOCA Analyses." July 31, 2007.)

Notes:

None to TXX-15038 Page 5 of 8 CPNPP Units 1 and 2 Peak Cladding Temperatures Westinghouse LOCA Peak Clad Temperature Summary for ASTRUM Best Estimate Large Break Plant Name: Comanche Peak Unit 2 Utility Name: Luminant Revision Date: 2/5/2015 Analysis Information EM: ASTRUM (2004) Analysis Date: 7/27/2007 Limiting Break Size: Guillotine FQ: 2.5 FdH: 1.6 Fuel: OFA SGTP (%): 10 Notes:

Clad Temp (OF) Ref. Notes LICENSIS BASIS Analysis-Of-Record PCT 1632 I PCT Assessments (Delta PCT)

A. PRIOR ECCS MODEL ASSESSMENTS

1. Evaluation of Fuel Pellet Thermal Conductivity 190 2 (a)

Degradation and Peaking Factor Burndown

2. Revised Heat Transfer Multiplier Distributions -17 3
3. Changes to Grid Blockage Ratio and Porosity 24 4
4. Error in Burst Strain Application 21 5 B. PLANNED PLANT MODIFICATION EVALUATIONS
1. None 0 C. 2014 ECCS MODEL ASSESSMENTS
1. None 0 D. OTHER
1. None 0 LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 1850

References:

I. WCAP-16763-P, Revision 1, "Best-Estimate Analysis of the Large-Break Loss-of-Coolant Accident for the Comanche Peak Nuclear Power Plant Unit 2 Using the ASTRUM Methodology," March 2009.

2. LTR-LIS-12-4 10, "Comanche Peak Units I and 2, 10 CFR 50.46 Notification and Reporting for Fuel Pellet Thermal Conductivity Degradation and Peaking Factor Bumdown," September 20, 2012.
3. LTR-LIS-13-359,"Comanche Peak Units I and 2 10CFR50.46 Report for Revised Heat Transfer Multiplier Distributions," July 2013.
4. LTR-LIS-13-472,"Comanche Peak Units I and 2 10CFR50.46 Reports for Changes to Grid Blockage Ratio and Porosity," October 2013.
5. LTR-LIS-14-43,"Comanche Peak Units I and 2 10CFR50.46 Report for the HOTSPOT Burst Strain Error Correction," January 2014.

Notes:

(a) This evaluation credits peaking factor bumdown, see Reference 2.

to TXX-15038 Page 6 of 8 CPNPP Units 1 and 2 Peak Cladding Temperatures Westinghouse LOCA Peak Clad Temperature Summary for ASTRUM Best Estimate Large Break Plant Name: Comanche Peak Unit 2 Utility Name: Luminant C ycle 15 Revision Date: 2/5/2015 Analysis Information EM: ASTRUM (2004) Analysis Date: 7/27/2007 Limiting Break Size: Guillotine FQ: 2.5 FdH: 1.6 Fuel: OFA SGTP (%): 10 Notes:

Clad Temp (OF) Ref. Notes LICENSIS BASIS Analysis-Of-Record PCT 1632 1 PCT Assessments (Delta PCT)

A. PRIOR ECCS MODEL ASSESSMENTS

1. Evaluation of Fuel Pellet Thermal Conductivity 190 3 (a)

Degradation and Peaking Factor Bumdown

2. Revised Heat Transfer Multiplier Distributions -17 4
3. Changes to Grid Blockage Ratio and Porosity 24 5
4. Error in Burst Strain Application 21 6 B. PLANNED PLANT MODIFICATION EVALUATIONS
1. PBOT/PMID Evaluation 0 2 C. 2014 ECCS MODEL ASSESSMENTS
1. None 0 D. OTHER
1. None 0 LICENSING BASIS PCT + PCT ASSESSMENTS PCT= 1850

References:

1. WCAP-16763-P, Revision I, "Best-Estimate Analysis of the Large-Break Loss-of-Coolant Accident for the Comanche Peak Nuclear Power Plant Unit 2 Using the ASTRUM Methodology," March 2009.
2. LTR-LIS-14-173, "LBLOCA PCT Rackup Sheet Update for the Evaluation of the Comanche Peak Unit 2 Cycle 15 PBOT/PMID Violations" March 2014.
3. LTR-LIS-12-410, "Comanche Peak Units I and 2, 10 CFR 50.46 Notification and Reporting for Fuel Pellet Thermal Conductivity Degradation and Peaking Factor Bumdown," September 20, 2012.
4. LTR-LIS-13-359,"Comanche Peak Units I and 2 10CFR50.46 Report for Revised Heat Transfer Multiplier Distributions," July 2013.
5. LTR-LIS-13-472,"Comanche Peak Units I and 2 10CFR50.46 Reports for Changes to Grid Blockage Ratio and Porosity," October 2013.
6. LTR-LIS-14-43,"Comanche Peak Units I and 2 10CFR50.46 Report for the HOTSPOT Burst Strain Error Correction," January 2014.

Notes:

(a) This evaluation credits peaking factor burmdown, see Reference 3.

to TXX-15038 Page 7 of 8 CPNPP Units 1 and 2 Peak Cladding Temperatures Westinghouse LOCA Peak Clad Temperature Summary for ASTRUM Best Estimate Large Break Plant Name: Comanche Peak Unit 2 Utility Name:

Revision Date:

Luminant 2/5/2015 Cycle 14 Retired Analysis Information EM: ASTRUM (2004) Analysis Date: 7/27/2007 Limiting Break Size: Guillotine FQ: 2.5 FdH: 1.6 Fuel: OFA SGTP (%): 10 Notes:

Clad Temp (OF) Ref. Notes LICENSIS BASIS Analysis-Of-Record PCT 1632 1 PCT Assessments (Delta PCT)

A. PRIOR ECCS MODEL ASSESSMENTS

1. Evaluation of Fuel Pellet Thermal Conductivity 190 3 (a)

Degradation and Peaking Factor Burndown

2. Revised Heat Transfer Multiplier Distributions -17 4
3. Changes to Grid Blockage Ratio and Porosity 24 5
4. Error in Burst Strain Application 21 6 B. PLANNED PLANT MODIFICATION EVALUATIONS
1. PBOT/PMID Evaluation 0 2 C. 2014 ECCS MODEL ASSESSMENTS
1. None 0 D. OTHER
1. None 0 LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 1850

References:

1. WCAP-16763-P, Revision 1, "Best-Estimate Analysis of the Large-Break Loss-of-Coolant Accident for the Comanche Peak Nuclear Power Plant Unit 2 Using the ASTRUM Methodology," March 2009.
2. LTR-LIS-l 2-498, "LBLOCA PCT Rackup Sheet Update for the Evaluation of the Comanche Peak Unit 2 Cycle 14 PBOT/PMID Violations" September 2012.
3. LTR-LIS-12-410, "Comanche Peak Units I and 2, 10 CFR 50.46 Notification and Reporting for Fuel Pellet Thermal Conductivity Degradation and Peaking Factor Bumdown," September 20, 2012.
4. LTR-LIS-I 3-359,"Comanche Peak Units I and 2 10CFR50.46 Report for Revised Heat Transfer Multiplier Distributions," July 2013.
5. LTR-LIS-13-472,"Comanche Peak Units I and 2 10CFR50.46 Reports for Changes to Grid Blockage Ratio and Porosity," October 2013.
6. LTR-LIS-14-43,"Comanche Peak Units I and 2 10CFR50.46 Report for the HOTSPOT Burst Strain Error Correction," January 2014.

Notes:

(a) This evaluation credits peaking factor bumdown, see Reference 3.

to TXX-15038 Page 8 of 8 CPNPP Units 1 and 2 Peak Cladding Temperatures Westinghouse LOCA Peak Clad Temperature Summary for Appendix K Small Break Plant Name: Comanche Peak Unit 2 Utility Name: Luminant Revision Date: 2/5/2015 Analysis Information EM: NOTRUMP Analysis Date: 6/8/2007 Limiting Break Size: 4 inch FQ: 2.5 FdH: 1.6 Fuel: OFA SGTP (%): 10 Notes:

Clad Temp (OF) Ref. Notes LICENSIS BASIS Analysis-Of-Record PCT 1210 1 PCT Assessments (Delta PCT)

A. PRIOR ECCS MODEL ASSESSMENTS

1. None 0 B. PLANNED PLANT MODIFICATION EVALUATIONS
1. None 0 C. 2014 ECCS MODEL ASSESSMENTS
1. None 0 D. OTHER
1. None 0 LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 1210

References:

I. WCAP-16840-P, "Comanche Peak Nuclear Power Plant Stretch Power Uprate Licensing Report," August 2007. (Results are included in TXX-07107, "Comanche Peak Steam Electric Station (CPSES), Docket Nos. 50-445 and 50.446, Submittal of the CPSES Units I and 2 Large and Small Break LOCA Analyses," July 31, 2007.)

Notes:

None

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