DCL-16-105, 10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for Peak Cladding Temperature for 2015: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(StriderTol Bot change)
 
Line 16: Line 16:


=Text=
=Text=
{{#Wiki_filter:m     Pacific Gas and
{{#Wiki_filter:m Pacific Gas and  
~ ~*. Electric Company                                       James M. Welsch                   Diablo Canyon Power Plant Vice President, Nuclear Generation Mail Code 104/6 P. 0. Box 56 Avila Beach, CA 93424 805.545.3242 Internal: 691.3242 October 18, 2016                                                                              Fax: 805.545.4884 PG&E Letter DCL-16-1 05 U.S. Nuclear Regulatory Commission                                           10 CFR 50.46 ATIN: Document Control Desk Washington, DC 20555-0001 Docket No. 50-275, OL-DPR-80 Docket No. 50-323, OL-DPR-82 Diablo Canyon Units 1 and 2 10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for Peak Cladding Temperature for 2015
~  
~ *. Electric Company October 18, 2016 PG&E Letter DCL 1 05 James M. Welsch Vice President, Nuclear Generation Diablo Canyon Power Plant Mail Code 104/6 P. 0. Box 56 Avila Beach, CA 93424 805.545.3242 Internal: 691.3242 Fax: 805.545.4884 U.S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, DC 20555-0001 10 CFR 50.46 Docket No. 50-275, OL-DPR-80 Docket No. 50-323, OL-DPR-82 Diablo Canyon Units 1 and 2 1 0 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for Peak Cladding Temperature for 2015  


==Reference:==
==Reference:==
: 1. PG&E Letter DCL-15-093, "1 0 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for Peak Cladding Temperature for 2014," dated August 6, 2015.
: 1. PG&E Letter DCL-15-093, "1 0 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for Peak Cladding Temperature for 2014," dated August 6, 2015.
(ADAMS Accession No. ML15218A626)
(ADAMS Accession No. ML15218A626)  


==Dear Commissioners and Staff:==
==Dear Commissioners and Staff:==
Pursuant to 10 CFR 50.46, the enclosure to this letter is the annual report of changes in the Westinghouse emergency core cooling system evaluation models that affect peak cladding temperature (PCT) calculations for Pacific Gas and Electric Company's (PG&E's) Diablo Canyon Power Plant, Units 1 and 2. The attachments to the enclosure prov~de a summary of the PCT margin allocations and their bases.
Pursuant to 10 CFR 50.46, the enclosure to this letter is the annual report of changes in the Westinghouse emergency core cooling system evaluation models that affect peak cladding temperature (PCT) calculations for Pacific Gas and Electric Company's (PG&E's) Diablo Canyon Power Plant, Units 1 and 2. The attachments to the enclosure prov~de a summary of the PCT margin allocations and their bases.
The PCT values remain within the 2200°F limit specified in 10 CFR 50.46. Because the Unit 1 and Unit 2 best-estimate, large-break loss-of-coolant accident analyses each have a total PCT margin allocation that is currently greater than 50°F, PG&E has already proposed to complete a reanalysis of both units using the Westinghouse FULL SPECTRUM' LOCA (FSLOCA') methodology and will provide the updated PCT results to the NRC by December 2018, per PG&E Letter DCL-15-093 (Reference 1). The FSLOCA' will include code methodology changes that address fuel thermal conductivity degradation.
The PCT values remain within the 2200°F limit specified in 10 CFR 50.46. Because the Unit 1 and Unit 2 best-estimate, large-break loss-of-coolant accident analyses each have a total PCT margin allocation that is currently greater than 50°F, PG&E has already proposed to complete a reanalysis of both units using the Westinghouse FULL SPECTRUM' LOCA (FSLOCA') methodology and will provide the updated PCT results to the NRC by December 2018, per PG&E Letter DCL-15-093 (Reference 1 ). The FSLOCA ' will include code methodology changes that address fuel thermal conductivity degradation.
PG&E makes no new or revised regulatory commitments (as defined by NEI 99-04) in this letter.
PG&E makes no new or revised regulatory commitments (as defined by NEI 99-04) in this letter.
If you have questions regarding this submittal please contact Mr. Mark Sharp at 805-545-3031.
If you have questions regarding this submittal please contact Mr. Mark Sharp at 805-545-3031.
Line 32: Line 32:
* Diablo Canyon
* Diablo Canyon
* Palo Verde
* Palo Verde
* Wolf Creek
* Wolf Creek  


Document Control Desk                                           PG&E Letter DCL-16-105 October 18, 2016 Page 2
Document Control Desk October 18, 2016 Page 2
: S72ely, Jam~~w~6~
: S72ely, Jam~~w~6~
Vice President, Nuclear Generation bnsm/4540 Enclosure cc/enc: Kriss M. Kennedy, NRC Region IV Administrator Christopher W. Newport, NRC Senior Resident Inspector Balwant K. Singal, NRC Senior Project Manager Diablo Distribution A member of the STARS Alliance Callaway
Vice President, Nuclear Generation bnsm/4540 Enclosure PG&E Letter DCL-16-105 cc/enc: Kriss M. Kennedy, NRC Region IV Administrator Christopher W. Newport, NRC Senior Resident Inspector Balwant K. Singal, NRC Senior Project Manager Diablo Distribution A member of the STARS Alliance Callaway
* Diablo Canyon
* Diablo Canyon
* Palo Verde
* Palo Verde
* Wolf Creek
* Wolf Creek  


Enclosure PG&E Letter DCL-16-1 05 10 CFR 50.46 ANNUAL REPORT OF EMERGENCY CORE COOLING SYSTEM EVALUATION MODEL CHANGES FOR PEAK CLADDING TEMPERATURE FOR 2015 Pursuant to 10 CFR 50.46, this enclosure provides an annual report of changes in the Westinghouse emergency core cooling system evaluation models that affect peak cladding temperature (PCT) calculations for Pacific Gas and Electric Company's (PG&E's) Diablo Canyon Power Plant, Units 1 and 2. This report is based on changes described in Westinghouse Letter LTR-LIS-16-29, "Diablo Canyon Units 1 and 2 10 CFR 50.46 Annual Notification and Reporting for 2015,"
Enclosure PG&E Letter DCL-16-1 05 10 CFR 50.46 ANNUAL REPORT OF EMERGENCY CORE COOLING SYSTEM EVALUATION MODEL CHANGES FOR PEAK CLADDING TEMPERATURE FOR 2015 Pursuant to 10 CFR 50.46, this enclosure provides an annual report of changes in the Westinghouse emergency core cooling system evaluation models that affect peak cladding temperature (PCT) calculations for Pacific Gas and Electric Company's (PG&E's) Diablo Canyon Power Plant, Units 1 and 2. This report is based on changes described in Westinghouse Letter L TR-LIS-16-29, "Diablo Canyon Units 1 and 2 10 CFR 50.46 Annual Notification and Reporting for 2015,"
dated February 18, 2016.
dated February 18, 2016.
Attachment A contains Unit 1 small-break loss-of-coolant accident (SBLOCA) and best-estimate, large-break loss-of-coolant accident (BELOCA) PCT Margin Utilization sheets. Attachment 8 contains the corresponding Unit 2 data. There have been no changes in the SBLOCA PCT results or BELOCA PCT results for either Unit 1 or Unit 2 since the last annual update. The last annual update was provided in PG&E Letter DCL-15-093, "10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for Peak Cladding Temperature for 2014," dated August 6, 2015.
Attachment A contains Unit 1 small-break loss-of-coolant accident (SBLOCA) and best-estimate, large-break loss-of-coolant accident (BELOCA) PCT Margin Utilization sheets. Attachment 8 contains the corresponding Unit 2 data. There have been no changes in the SBLOCA PCT results or BELOCA PCT results for either Unit 1 or Unit 2 since the last annual update. The last annual update was provided in PG&E Letter DCL-15-093, "10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for Peak Cladding Temperature for 2014," dated August 6, 2015.
The final net PCT values are listed below for each unit. Two PCT values are reported for the Unit 1 BELOCA results. The two BELOCA PCT values are labeled Reflood 1 and Reflood 2, as they represent the two distinctive PCT peaks that occur during the reflood phase for the Unit 1 BELOCA Code Qualification Document methodology. The Unit 2 BELOCA reports only one PCT value consistent with the BELOCA ASTRUM methodology.
The final net PCT values are listed below for each unit. Two PCT values are reported for the Unit 1 BELOCA results. The two BELOCA PCT values are labeled Reflood 1 and Reflood 2, as they represent the two distinctive PCT peaks that occur during the reflood phase for the Unit 1 BELOCA Code Qualification Document methodology. The Unit 2 BELOCA reports only one PCT value consistent with the BELOCA ASTRUM methodology.
SBLOCA                                             BELOCA Reflood 1            Reflood 2 Unit 1:   1391 oF (no change)           2049°F (no change)     2124°F (no change)
SBLOCA BELOCA Unit 1: 1391 oF (no change)
Unit 2:  1288°F (no change)                         2125°F (no change)
Unit 2:
1288°F (no change)
Reflood 1 Reflood 2 2049°F (no change) 2124°F (no change) 2125°F (no change)
The PCT values remain within the 2200°F limit specified in 10 CFR 50.46.
The PCT values remain within the 2200°F limit specified in 10 CFR 50.46.
However, because the Unit 1 and Unit 2 BELOCA analyses each have a total PCT margin allocation that is currently greater than 50°F, PG&E has already proposed to complete a reanalysis of both Units using the Westinghouse FULL SPECTRUMTM LOCA (FSLOCA') methodology and provide the updated PCT results to the NRC by December 2018, per PG&E Letter DCL-15-093. The FSLOCATM will include code methodology changes that address fuel thermal conductivity degradation.
However, because the Unit 1 and Unit 2 BELOCA analyses each have a total PCT margin allocation that is currently greater than 50°F, PG&E has already proposed to complete a reanalysis of both Units using the Westinghouse FULL SPECTRUMTM LOCA (FSLOCA') methodology and provide the updated PCT results to the NRC by December 2018, per PG&E Letter DCL-15-093. The FSLOCATM will include code methodology changes that address fuel thermal conductivity degradation.
1
1  


Attachment A PG&E Letter DCL-16-105 DCPP UNIT 1 PEAK CLADDING TEMPERATURE MARGIN UTILIZATION SMALL-BREAK Loss-of-Coolant Accident                                     PG&E Letter1 Peak Cladding A. ANALYSIS OF RECORD                                       1391°F       DCL-09-057 Temperature (PCT) =
A.
B. PRIOR 10 CFR 50.46 EMERGENCY CORE COOLING SYSTEM(ECCS)MODEL ASSESSMENTS 2
B.
: 1. None
C.
                                              ~PCT=               ooF C. 10 CFR 50.46 ECCS MODEL ASSESSMENTS THIS YEAR
D.
: 1. None                                                   OoF
E.
                                              ~PCT=
Attachment A PG&E Letter DCL-16-105 DCPP UNIT 1 PEAK CLADDING TEMPERATURE MARGIN UTILIZATION SMALL-BREAK Loss-of-Coolant Accident PG&E Letter 1 Peak ANALYSIS OF RECORD Cladding 1391°F Temperature DCL-09-057 (PCT) =
D. SUM OF 10 CFR 50.46 CHANGES
PRIOR 10 CFR 50.46 EMERGENCY CORE COOLING SYSTEM(ECCS)MODEL ASSESSMENTS2
      ,/
: 1.
: 1. Net Sum of 10 CFR 50.46 PCT Changes                       ~PCT=               OoF
None  
: 2. Absolute Sum of 10 CFR 50.46 PCT Changes           ~PCT=               ooF E. Analysis of Record PCT (Line A) +
~PCT=
Line D.1 Net Sum of                                         1391 °F 10 CFR 50.46 PCT Changes The sum of the PCT from the most recent analysis of record using an acceptable evaluation model and the estimates of the net PCT effect for changes and errors identified since this analysis remains less than 2200°F.
ooF 10 CFR 50.46 ECCS MODEL ASSESSMENTS THIS YEAR
For those issues that have been previously reported under 10 CFR 50.46, a PG&E letter number is listed .
: 1.
2 Only permanent assessments of PCT margin are included. Temporary PCT allocations that address current LOCA model issues are not considered with respect to 10 CFR 50.46 reporting requirements.
None  
A-1
~PCT=
OoF SUM OF 10 CFR 50.46 CHANGES  
,/
: 1.
Net Sum of 10 CFR 50.46 PCT Changes  
~PCT=
OoF
: 2.
Absolute Sum of 1 0 CFR 50.46 PCT Changes  
~PCT=
ooF Analysis of Record PCT (Line A) +
Line D.1 Net Sum of 1391 °F 1 0 CFR 50.46 PCT Changes The sum of the PCT from the most recent analysis of record using an acceptable evaluation model and the estimates of the net PCT effect for changes and errors identified since this analysis remains less than 2200°F.
2 For those issues that have been previously reported under 1 0 CFR 50.46, a PG&E letter number is listed.
Only permanent assessments of PCT margin are included. Temporary PCT allocations that address current LOCA model issues are not considered with respect to 10 CFR 50.46 reporting requirements.
A-1  


Attachment A PG&E Letter DCL-16-105 DCPP UNIT 1 PEAK CLADDING TEMPERATURE MARGIN UTILIZATION Best Estimate, Large Break Loss-of-Coolant Accident                               PG&E Letter1 Reflood 1     Reflood 2 A. ANALYSIS OF RECORD                           1900°F         1860°F         DCL-05-146 ilPCT         ilPCT B. PRIOR 10 CFR 50.46 EMERGENCY CORE COOLING SYSTEM (ECCS)
Attachment A PG&E Letter DCL-16-105 DCPP UNIT 1 PEAK CLADDING TEMPERATURE MARGIN UTILIZATION Best Estimate, Large Break Loss-of-Coolant Accident PG&E Letter 1 Reflood 1 Reflood 2 A.
ANALYSIS OF RECORD 1900°F 1860°F DCL-05-146 ilPCT ilPCT B.
PRIOR 10 CFR 50.46 EMERGENCY CORE COOLING SYSTEM (ECCS)
MODELASSESSMENTS 2
MODELASSESSMENTS 2
: 1. Revised blowdown heatup                       5°F           5°F         DCL-05-086 uncertainty distribution.
: 1. Revised blowdown heatup 5°F 5°F DCL-05-086 uncertainty distribution.
: 2. HOTSPOT Fuel Relocation                       10°F           OoF         DCL-07-071 Error.
: 2. HOTSPOT Fuel Relocation 10°F OoF DCL-07-071 Error.
: 3. Replacement Steam                           75°F           71oF         DCL-09-057 Generators
: 3. Replacement Steam 75°F 71oF DCL-09-057 Generators
: 4. 230 kV Degraded Voltage Event                 ooF
: 4. 230 kV Degraded Voltage Event ooF
* 39°F         DCL-11-082
* 39°F DCL-11-082
: 5. Performance and Design (PAD)               -118°F         -118°F         DCL-12-102 4.0 Implementation
: 5. Performance and Design (PAD)  
: 6. Fuel Thermal Conductivity                   133°F         238°F         DCL-12-102 Degradation (TCD) and Peaking Factor Burndown
-118°F  
: 7. Revised Heat Transfer Multiplier             5°F           -35°F         DCL-13-111 Distributions
-118°F DCL-12-102 4.0 Implementation
: 8. Changes to Grid Blockage and                 24°F           24°F         DCL-13-111 Porosity
: 6. Fuel Thermal Conductivity 133°F 238°F DCL-12-102 Degradation (TCD) and Peaking Factor Burndown
: 9. Error in Burst Strain Application             15°F         40°F         DCL-14-070 C. 10 CFR 50.46 ECCS MODEL ASSESSMENTS THIS YEAR
: 7. Revised Heat Transfer Multiplier 5°F  
: 1. None D. SUM OF 10 CFR 50.46 CHANGES
-35°F DCL-13-111 Distributions
: 1. Net Sum of PCT Changes                     149°F         264°F
: 8. Changes to Grid Blockage and 24°F 24°F DCL-13-111 Porosity
: 2. Absolute Sum of PCT Changes                 385°F         570°F E. Analysis of Record PCT (Line A) +
: 9. Error in Burst Strain Application 15°F 40°F DCL-14-070 C.
Line D.1 Net Sum of 10 CFR 50.46             2049°F         2124°F PCT Changes The sum of the PCT from the most recent analysis of record using an acceptable evaluation model and the estimates of the net PCT effect for changes and errors identified since this analysis remains less than 2200°F.
10 CFR 50.46 ECCS MODEL ASSESSMENTS THIS YEAR
For those issues that have been previously reported under 10 CFR 50.46, a PG&E letter number is listed.                                                 '
: 1. None D.
2 Only permanent assessments of PCT margin are included. Temporary PCT allocations that address current LOCA model issues are not considered with respect to 10 CFR 50.46 reporting requirements.
SUM OF 10 CFR 50.46 CHANGES
A-2
: 1. Net Sum of PCT Changes 149°F 264°F
 
: 2. Absolute Sum of PCT Changes 385°F 570°F E.
Attachment B PG&E Letter DCL-16-105 DCPP UNIT 2 PEAK CLADDING TEMPERATURE MARGIN UTILIZATION Small Break Loss-of-Coolant Accident                                      PG&E Letter1 Peak Cladding A. ANALYSIS OF RECORD Temperature (PCT) =          1288°F    DCL-08-061 B. PRIOR 10 CFR 50.46 EMERGENCY CORE COOLING SYSTEM (ECCS)
Analysis of Record PCT (Line A) +
MODEL ASSESSMENTS 2
Line D.1 Net Sum of 10 CFR 50.46 2049°F 2124°F PCT Changes The sum of the PCT from the most recent analysis of record using an acceptable evaluation model and the estimates of the net PCT effect for changes and errors identified since this analysis remains less than 2200°F.
: 1. None                                  LlPCT =            ooF C. 10 CFR 50.46 ECCS MODEL ASSESSMENTS THIS YEAR
2 For those issues that have been previously reported under 10 CFR 50.46, a PG&E letter number is listed.
: 1. None                                                      ooF LlPCT =
Only permanent assessments of PCT margin are included. Temporary PCT allocations that address current LOCA model issues are not considered with respect to 10 CFR 50.46 reporting requirements.
D. SUM OF 10 CFR 50.46 CHANGES
A-2  
: 1. Net Sum of 10 CFR 50.46 PCT Changes                              LlPCT =            ooF
: 2. Absolute Sum of 10 CFR 50.46 PCT Changes                          LlPCT =            0°F E. Analysis of Record PCT (Line A)
      + Line 0.1 Net Sum of                                      1288°F 10 CFR 50.46 PCT Changes The sum of the PCT from the most recent analysis of record using an acceptable evaluation model and the estimates of the net PCT effect for changes and errors identified since this analysis remains less than 2200°F.
For those issues that have been previously reported under 10 CFR 50.46, a PG&E Letter number is listed.
2 Only permanent assessments of PCT margin are included. Temporary PCT allocations that address current LOCA model issues are not considered with respect to 10 CFR 50.46 reporting requirements.
B-1


Attachment 8 PG&E Letter DCL-16-105 DCPP UNIT 2 PEAK CLADDING TEMPERATURE MARGIN UTILIZATION BELOCA                                                                         PG&E Letter1 A. ANALYSIS OF RECORD                               PCT=         1872°F     DCL-07-071 B. PRIOR 10 CFR 50.46 ECCS MODEL ASSESSMENTS 2
Attachment B PG&E Letter DCL-16-105 DCPP UNIT 2 PEAK CLADDING TEMPERATURE MARGIN UTILIZATION Small Break Loss-of-Coolant Accident PG&E Letter 1 Peak A.
: 1. HOTSPOT Fuel Relocation Error.             ~PCT=             ooF     DCL-07-071
ANALYSIS OF RECORD Cladding Temperature (PCT) =
: 2. 230 kV Degraded Voltage Event.               ~PCT=           16°F     DCL-11-082
1288°F DCL-08-061 B.
: 3. Fuel Thermal Conductivity                   ~PCT=         209°F       DCL-12-102 Degradation (TCD) and Peaking Factor Burndown
PRIOR 10 CFR 50.46 EMERGENCY CORE COOLING SYSTEM (ECCS)
: 4. Revised Heat Transfer Multiplier             ~PCT=           -17oF     DCL-13-111 Distribution
MODEL ASSESSMENTS2
: 5. Changes to Grid Blockage and               ~PCT=           24°F     DCL-13-111 Porosity
: 1. None LlPCT =
: 6. Error in Burst Strain Application           i\PCT=           21oF     DCL-14-070 C. 10 CFR 50.46 ECCS MODEL ASSESSMENTS THIS YEAR
ooF C.
: 1. None                                       ~PCT=
10 CFR 50.46 ECCS MODEL ASSESSMENTS THIS YEAR
D. SUM OF 10 CFR 50.46 CHANGES
: 1. None LlPCT =
: 1. Net Sum of 10 CFR 50.46 PCT                 ~PCT=         253°F Changes
ooF D.
: 2. Absolute Sum of 10 CFR 50.46               ~PCT=         287oF PCT Changes E. Analysis of Record PCT (Line A) +                             2125°F Line D.1 Net Sum of 10 CFR 50.46 PCT Changes The sum of the PCT from the most recent analysis of record using an acceptable evaluation model and the estimates of the net PCT effect for changes and errors identified since this analysis remains less than 2200°F.
SUM OF 10 CFR 50.46 CHANGES
For those issues that have been previously reported under 10 CFR 50.46, a PG&E letter number is listed.
: 1. Net Sum of 10 CFR 50.46 PCT Changes LlPCT =
2 Only permanent assessments of PCT margin are included. Temporary PCT allocations that address current LOCA model issues are not considered with respect to 10 CFR 50.46 reporting requirements.
ooF
* 8-2}}
: 2. Absolute Sum of 10 CFR 50.46 PCT Changes LlPCT =
0°F E.
Analysis of Record PCT (Line A)
+ Line 0.1 Net Sum of 1288°F 10 CFR 50.46 PCT Changes The sum of the PCT from the most recent analysis of record using an acceptable evaluation model and the estimates of the net PCT effect for changes and errors identified since this analysis remains less than 2200°F.
2 For those issues that have been previously reported under 10 CFR 50.46, a PG&E Letter number is listed.
Only permanent assessments of PCT margin are included. Temporary PCT allocations that address current LOCA model issues are not considered with respect to 10 CFR 50.46 reporting requirements.
B-1 PG&E Letter DCL-16-105 DCPP UNIT 2 PEAK CLADDING TEMPERATURE MARGIN UTILIZATION BELOCA PG&E Letter 1 A.
ANALYSIS OF RECORD PCT=
1872°F DCL-07-071 B.
PRIOR 10 CFR 50.46 ECCS MODEL ASSESSMENTS 2 1. HOTSPOT Fuel Relocation Error.  
~PCT=
ooF DCL-07-071
: 2. 230 kV Degraded Voltage Event.  
~PCT=
16°F DCL-11-082
: 3. Fuel Thermal Conductivity  
~PCT=
209°F DCL-12-102 Degradation (TCD) and Peaking Factor Burndown
: 4. Revised Heat Transfer Multiplier  
~PCT=  
-17oF DCL-13-111 Distribution
: 5. Changes to Grid Blockage and  
~PCT=
24°F DCL-13-111 Porosity
: 6. Error in Burst Strain Application i\\PCT=
21oF DCL-14-070 C.
10 CFR 50.46 ECCS MODEL ASSESSMENTS THIS YEAR
: 1. None  
~PCT=
D.
SUM OF 10 CFR 50.46 CHANGES
: 1. Net Sum of 10 CFR 50.46 PCT  
~PCT=
253°F Changes
: 2. Absolute Sum of 10 CFR 50.46  
~PCT=
287oF PCT Changes E.
Analysis of Record PCT (Line A) +
2125°F Line D.1 Net Sum of 10 CFR 50.46 PCT Changes The sum of the PCT from the most recent analysis of record using an acceptable evaluation model and the estimates of the net PCT effect for changes and errors identified since this analysis remains less than 2200°F.
2 For those issues that have been previously reported under 10 CFR 50.46, a PG&E letter number is listed.
Only permanent assessments of PCT margin are included. Temporary PCT allocations that address current LOCA model issues are not considered with respect to 10 CFR 50.46 reporting requirements.
8-2}}

Latest revision as of 19:47, 9 January 2025

10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for Peak Cladding Temperature for 2015
ML16292A889
Person / Time
Site: Diablo Canyon  Pacific Gas & Electric icon.png
Issue date: 10/18/2016
From: Welsch J
Pacific Gas & Electric Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
DCL-16-105
Download: ML16292A889 (7)
v • d • e


Text

m Pacific Gas and

~

~ *. Electric Company October 18, 2016 PG&E Letter DCL 1 05 James M. Welsch Vice President, Nuclear Generation Diablo Canyon Power Plant Mail Code 104/6 P. 0. Box 56 Avila Beach, CA 93424 805.545.3242 Internal: 691.3242 Fax: 805.545.4884 U.S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, DC 20555-0001 10 CFR 50.46 Docket No. 50-275, OL-DPR-80 Docket No. 50-323, OL-DPR-82 Diablo Canyon Units 1 and 2 1 0 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for Peak Cladding Temperature for 2015

Reference:

1. PG&E Letter DCL-15-093, "1 0 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for Peak Cladding Temperature for 2014," dated August 6, 2015.

(ADAMS Accession No. ML15218A626)

Dear Commissioners and Staff:

Pursuant to 10 CFR 50.46, the enclosure to this letter is the annual report of changes in the Westinghouse emergency core cooling system evaluation models that affect peak cladding temperature (PCT) calculations for Pacific Gas and Electric Company's (PG&E's) Diablo Canyon Power Plant, Units 1 and 2. The attachments to the enclosure prov~de a summary of the PCT margin allocations and their bases.

The PCT values remain within the 2200°F limit specified in 10 CFR 50.46. Because the Unit 1 and Unit 2 best-estimate, large-break loss-of-coolant accident analyses each have a total PCT margin allocation that is currently greater than 50°F, PG&E has already proposed to complete a reanalysis of both units using the Westinghouse FULL SPECTRUM' LOCA (FSLOCA') methodology and will provide the updated PCT results to the NRC by December 2018, per PG&E Letter DCL-15-093 (Reference 1 ). The FSLOCA ' will include code methodology changes that address fuel thermal conductivity degradation.

PG&E makes no new or revised regulatory commitments (as defined by NEI 99-04) in this letter.

If you have questions regarding this submittal please contact Mr. Mark Sharp at 805-545-3031.

A member of the STARS Alliance Callaway

  • Diablo Canyon
  • Palo Verde
  • Wolf Creek

Document Control Desk October 18, 2016 Page 2

S72ely, Jam~~w~6~

Vice President, Nuclear Generation bnsm/4540 Enclosure PG&E Letter DCL-16-105 cc/enc: Kriss M. Kennedy, NRC Region IV Administrator Christopher W. Newport, NRC Senior Resident Inspector Balwant K. Singal, NRC Senior Project Manager Diablo Distribution A member of the STARS Alliance Callaway

  • Diablo Canyon
  • Palo Verde
  • Wolf Creek

Enclosure PG&E Letter DCL-16-1 05 10 CFR 50.46 ANNUAL REPORT OF EMERGENCY CORE COOLING SYSTEM EVALUATION MODEL CHANGES FOR PEAK CLADDING TEMPERATURE FOR 2015 Pursuant to 10 CFR 50.46, this enclosure provides an annual report of changes in the Westinghouse emergency core cooling system evaluation models that affect peak cladding temperature (PCT) calculations for Pacific Gas and Electric Company's (PG&E's) Diablo Canyon Power Plant, Units 1 and 2. This report is based on changes described in Westinghouse Letter L TR-LIS-16-29, "Diablo Canyon Units 1 and 2 10 CFR 50.46 Annual Notification and Reporting for 2015,"

dated February 18, 2016.

Attachment A contains Unit 1 small-break loss-of-coolant accident (SBLOCA) and best-estimate, large-break loss-of-coolant accident (BELOCA) PCT Margin Utilization sheets. Attachment 8 contains the corresponding Unit 2 data. There have been no changes in the SBLOCA PCT results or BELOCA PCT results for either Unit 1 or Unit 2 since the last annual update. The last annual update was provided in PG&E Letter DCL-15-093, "10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for Peak Cladding Temperature for 2014," dated August 6, 2015.

The final net PCT values are listed below for each unit. Two PCT values are reported for the Unit 1 BELOCA results. The two BELOCA PCT values are labeled Reflood 1 and Reflood 2, as they represent the two distinctive PCT peaks that occur during the reflood phase for the Unit 1 BELOCA Code Qualification Document methodology. The Unit 2 BELOCA reports only one PCT value consistent with the BELOCA ASTRUM methodology.

SBLOCA BELOCA Unit 1: 1391 oF (no change)

Unit 2:

1288°F (no change)

Reflood 1 Reflood 2 2049°F (no change) 2124°F (no change) 2125°F (no change)

The PCT values remain within the 2200°F limit specified in 10 CFR 50.46.

However, because the Unit 1 and Unit 2 BELOCA analyses each have a total PCT margin allocation that is currently greater than 50°F, PG&E has already proposed to complete a reanalysis of both Units using the Westinghouse FULL SPECTRUMTM LOCA (FSLOCA') methodology and provide the updated PCT results to the NRC by December 2018, per PG&E Letter DCL-15-093. The FSLOCATM will include code methodology changes that address fuel thermal conductivity degradation.

1

A.

B.

C.

D.

E.

Attachment A PG&E Letter DCL-16-105 DCPP UNIT 1 PEAK CLADDING TEMPERATURE MARGIN UTILIZATION SMALL-BREAK Loss-of-Coolant Accident PG&E Letter 1 Peak ANALYSIS OF RECORD Cladding 1391°F Temperature DCL-09-057 (PCT) =

PRIOR 10 CFR 50.46 EMERGENCY CORE COOLING SYSTEM(ECCS)MODEL ASSESSMENTS2

1.

None

~PCT=

ooF 10 CFR 50.46 ECCS MODEL ASSESSMENTS THIS YEAR

1.

None

~PCT=

OoF SUM OF 10 CFR 50.46 CHANGES

,/

1.

Net Sum of 10 CFR 50.46 PCT Changes

~PCT=

OoF

2.

Absolute Sum of 1 0 CFR 50.46 PCT Changes

~PCT=

ooF Analysis of Record PCT (Line A) +

Line D.1 Net Sum of 1391 °F 1 0 CFR 50.46 PCT Changes The sum of the PCT from the most recent analysis of record using an acceptable evaluation model and the estimates of the net PCT effect for changes and errors identified since this analysis remains less than 2200°F.

2 For those issues that have been previously reported under 1 0 CFR 50.46, a PG&E letter number is listed.

Only permanent assessments of PCT margin are included. Temporary PCT allocations that address current LOCA model issues are not considered with respect to 10 CFR 50.46 reporting requirements.

A-1

Attachment A PG&E Letter DCL-16-105 DCPP UNIT 1 PEAK CLADDING TEMPERATURE MARGIN UTILIZATION Best Estimate, Large Break Loss-of-Coolant Accident PG&E Letter 1 Reflood 1 Reflood 2 A.

ANALYSIS OF RECORD 1900°F 1860°F DCL-05-146 ilPCT ilPCT B.

PRIOR 10 CFR 50.46 EMERGENCY CORE COOLING SYSTEM (ECCS)

MODELASSESSMENTS 2

1. Revised blowdown heatup 5°F 5°F DCL-05-086 uncertainty distribution.
2. HOTSPOT Fuel Relocation 10°F OoF DCL-07-071 Error.
3. Replacement Steam 75°F 71oF DCL-09-057 Generators
4. 230 kV Degraded Voltage Event ooF
5. Performance and Design (PAD)

-118°F

-118°F DCL-12-102 4.0 Implementation

6. Fuel Thermal Conductivity 133°F 238°F DCL-12-102 Degradation (TCD) and Peaking Factor Burndown
7. Revised Heat Transfer Multiplier 5°F

-35°F DCL-13-111 Distributions

8. Changes to Grid Blockage and 24°F 24°F DCL-13-111 Porosity
9. Error in Burst Strain Application 15°F 40°F DCL-14-070 C.

10 CFR 50.46 ECCS MODEL ASSESSMENTS THIS YEAR

1. None D.

SUM OF 10 CFR 50.46 CHANGES

1. Net Sum of PCT Changes 149°F 264°F
2. Absolute Sum of PCT Changes 385°F 570°F E.

Analysis of Record PCT (Line A) +

Line D.1 Net Sum of 10 CFR 50.46 2049°F 2124°F PCT Changes The sum of the PCT from the most recent analysis of record using an acceptable evaluation model and the estimates of the net PCT effect for changes and errors identified since this analysis remains less than 2200°F.

2 For those issues that have been previously reported under 10 CFR 50.46, a PG&E letter number is listed.

Only permanent assessments of PCT margin are included. Temporary PCT allocations that address current LOCA model issues are not considered with respect to 10 CFR 50.46 reporting requirements.

A-2

Attachment B PG&E Letter DCL-16-105 DCPP UNIT 2 PEAK CLADDING TEMPERATURE MARGIN UTILIZATION Small Break Loss-of-Coolant Accident PG&E Letter 1 Peak A.

ANALYSIS OF RECORD Cladding Temperature (PCT) =

1288°F DCL-08-061 B.

PRIOR 10 CFR 50.46 EMERGENCY CORE COOLING SYSTEM (ECCS)

MODEL ASSESSMENTS2

1. None LlPCT =

ooF C.

10 CFR 50.46 ECCS MODEL ASSESSMENTS THIS YEAR

1. None LlPCT =

ooF D.

SUM OF 10 CFR 50.46 CHANGES

1. Net Sum of 10 CFR 50.46 PCT Changes LlPCT =

ooF

2. Absolute Sum of 10 CFR 50.46 PCT Changes LlPCT =

0°F E.

Analysis of Record PCT (Line A)

+ Line 0.1 Net Sum of 1288°F 10 CFR 50.46 PCT Changes The sum of the PCT from the most recent analysis of record using an acceptable evaluation model and the estimates of the net PCT effect for changes and errors identified since this analysis remains less than 2200°F.

2 For those issues that have been previously reported under 10 CFR 50.46, a PG&E Letter number is listed.

Only permanent assessments of PCT margin are included. Temporary PCT allocations that address current LOCA model issues are not considered with respect to 10 CFR 50.46 reporting requirements.

B-1 PG&E Letter DCL-16-105 DCPP UNIT 2 PEAK CLADDING TEMPERATURE MARGIN UTILIZATION BELOCA PG&E Letter 1 A.

ANALYSIS OF RECORD PCT=

1872°F DCL-07-071 B.

PRIOR 10 CFR 50.46 ECCS MODEL ASSESSMENTS 2 1. HOTSPOT Fuel Relocation Error.

~PCT=

ooF DCL-07-071

2. 230 kV Degraded Voltage Event.

~PCT=

16°F DCL-11-082

3. Fuel Thermal Conductivity

~PCT=

209°F DCL-12-102 Degradation (TCD) and Peaking Factor Burndown

4. Revised Heat Transfer Multiplier

~PCT=

-17oF DCL-13-111 Distribution

5. Changes to Grid Blockage and

~PCT=

24°F DCL-13-111 Porosity

6. Error in Burst Strain Application i\\PCT=

21oF DCL-14-070 C.

10 CFR 50.46 ECCS MODEL ASSESSMENTS THIS YEAR

1. None

~PCT=

D.

SUM OF 10 CFR 50.46 CHANGES

1. Net Sum of 10 CFR 50.46 PCT

~PCT=

253°F Changes

2. Absolute Sum of 10 CFR 50.46

~PCT=

287oF PCT Changes E.

Analysis of Record PCT (Line A) +

2125°F Line D.1 Net Sum of 10 CFR 50.46 PCT Changes The sum of the PCT from the most recent analysis of record using an acceptable evaluation model and the estimates of the net PCT effect for changes and errors identified since this analysis remains less than 2200°F.

2 For those issues that have been previously reported under 10 CFR 50.46, a PG&E letter number is listed.

Only permanent assessments of PCT margin are included. Temporary PCT allocations that address current LOCA model issues are not considered with respect to 10 CFR 50.46 reporting requirements.

8-2

Retrieved from "https://kanterella.com/w/index.php?title=DCL-16-105,_10_CFR_50.46_Annual_Report_of_Emergency_Core_Cooling_System_Evaluation_Model_Changes_for_Peak_Cladding_Temperature_for_2015&oldid=5162780"