DCL-12-070, 10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for Peak Cladding Temperature for 2011: Difference between revisions

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| issue date = 07/19/2012
| issue date = 07/19/2012
| title = 10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for Peak Cladding Temperature for 2011
| title = 10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for Peak Cladding Temperature for 2011
| author name = Becker J R
| author name = Becker J
| author affiliation = Pacific Gas & Electric Co
| author affiliation = Pacific Gas & Electric Co
| addressee name =  
| addressee name =  
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=Text=
=Text=
{{#Wiki_filter:Pacific Gas and Electric Company July 19, 2012 PG&E Letter DCL-12-070 James R. Becker Site Vice President Diablo Canyon Power Plant Mail Code 104/6 P. O. Box 56 Avila Beach, CA 93424 805.545.3462 Internal:
{{#Wiki_filter:Pacific Gas and Electric Company James R. Becker     Diablo Canyon Power Plant Site Vice President  Mail Code 104/6 P. O. Box 56 Avila Beach, CA 93424 805.545.3462 Internal: 691. 3462 July 19, 2012                                                                                    Fax: 805.545.6445 PG&E Letter DCL-12-070 U.S. Nuclear Regulatory Commission                                           10 CFR 50.46 ATTN: Document Control Desk Washington, DC 20555-0001 Docket No. 50-275, OL-DPR-BO Docket No. 50-323, OL-DPR-B2 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 2011
691. 3462 Fax: 805.545.6445 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 10 CFR 50.46 Docket No. 50-275, OL-DPR-BO Docket No. 50-323, OL-DPR-B2 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 2011 Dear Commissioners and Staff: Pursuant to 10 CFR 50.46, the enclosure to this letter 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 (PG&E) Diablo Canyon Power Plant, Units 1 and 2. There have been no changes in the small-break loss-of-coolant accident (SBLOCA) PCT results or the large-break, best-estimate loss-of-coolant accident (BELOCA) PCT results for either Unit 1 or Unit 2 since the last annual update. The last update was provided in PG&E Letter DCL-11-0B2, "10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for 2010," dated July 19, 2011. A summary of the PCT margin allocations and their bases are provided in the enclosed attachments.
 
The Unit 1 SBLOCA and BELOCA PCT Margin Utilization sheets are provided in Attachment A. The Unit 2 SBLOCA and BELOCA PCT Margin Utilization Sheets are provided in Attachment B. The PCT values remain within the 2200 degree Fahrenheit (F) limit specified in 10 CFR 50.46. However, because the Unit 1 BELOCA has a total PCT margin allocation that is currently greater than 50 degrees F, and in order to coordinate with the 24-month fuel cycle project schedule, PG&E expects to complete the . Unit 1 BELOCA reanalysis and provide the updated PCT results to the NRC by December 2016, as stated in PG&E Letter DCL-11-0B2, "10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for 2010," dated July 19, 2011. A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway
==Dear Commissioners and Staff:==
 
Pursuant to 10 CFR 50.46, the enclosure to this letter 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 (PG&E) Diablo Canyon Power Plant, Units 1 and 2.
There have been no changes in the small-break loss-of-coolant accident (SBLOCA) PCT results or the large-break, best-estimate loss-of-coolant accident (BELOCA) PCT results for either Unit 1 or Unit 2 since the last annual update. The last update was provided in PG&E Letter DCL-11-0B2, "10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for 2010,"
dated July 19, 2011.
A summary of the PCT margin allocations and their bases are provided in the enclosed attachments. The Unit 1 SBLOCA and BELOCA PCT Margin Utilization sheets are provided in Attachment A. The Unit 2 SBLOCA and BELOCA PCT Margin Utilization Sheets are provided in Attachment B.
The PCT values remain within the 2200 degree Fahrenheit (F) limit specified in 10 CFR 50.46. However, because the Unit 1 BELOCA has a total PCT margin allocation that is currently greater than 50 degrees F, and in order to coordinate with the 24-month fuel cycle project schedule, PG&E expects to complete the .
Unit 1 BELOCA reanalysis and provide the updated PCT results to the NRC by December 2016, as stated in PG&E Letter DCL-11-0B2, "10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for 2010,"
dated July 19, 2011.
A member of the STARS (Strategic Teaming and Resource Sharing)   Alliance Callaway
* Comanche Peak
* Comanche Peak
* Diablo Canyon
* Diablo Canyon
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* San Onofre
* San Onofre
* South Texas Project
* South Texas Project
* Wolf Creek Document Control Desk July 19, 2012 Page 2 PG&E Letter DCL-12-070 PG&E makes no new or revised regulatory commitments (as defined by NEI 99-04) in this report. If you have questions regarding this submittal please contact Mr. Steve Baker at 805-545-6742.
* Wolf Creek
Sincerely, Jame\lR. Becker Site Vice President wrl8/6980/64059110 Enclosure cc/enc: Elmo E. Collins, NRC Region IV Michael S. Peck, NRC Senior Resident Inspector Joseph M. Sebrosky, NRR Senior Project Manager Diablo Distribution A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway
 
Document Control Desk                                                 PG&E Letter DCL-12-070 July 19, 2012 Page 2 PG&E makes no new or revised regulatory commitments (as defined by NEI 99-04) in this report.
If you have questions regarding this submittal please contact Mr. Steve Baker at 805-545-6742.
Sincerely,
        ~~vJJr-I- ~
Jame\lR. Becker Site Vice President wrl8/6980/64059110 Enclosure cc/enc: Elmo E. Collins, NRC Region IV Michael S. Peck, NRC Senior Resident Inspector Joseph M. Sebrosky, NRR Senior Project Manager Diablo Distribution A member of the STARS (Strategic Teaming and Resource   Sharing) Alliance Callaway
* Comanche Peak
* Comanche Peak
* Diablo Canyon
* Diablo Canyon
Line 31: Line 45:
* San Onofre
* San Onofre
* South Texas Project
* South Texas Project
* Wolf Creek Enclosure PG&E Letter DCL-12-070 ANNUAL REPORT OF EMERGENCY CORE COOLING SYSTEM EVALUATION MODEL CHANGES FOR PEAK CLADDING TEMPERATURE Pursuant to 10 CFR 50.46, this enclosure provides an annual report of changes in the Westinghouse emergency core cooling system (ECCS) evaluation models that affect peak cladding temperature (PCT) calculations for Pacific Gas and Electric Company (PG&E) Diablo Canyon Power Plant (DCPP), Units 1 and 2. This report is based on changes described in the following Westinghouse 10 CFR 50.46 notification letter: Westinghouse Letter LTR-LlS-12-116, "Diablo Canyon Units 1 and 2 10 CFR 50.46 Annual Notification and Reporting for 2011 ," dated February 20,2012 Attachment A to this enclosure provides DCPP, Unit 1 small-break loss-of-coolant accident (SBLOCA) and best-estimate, large-break coolant accident (BELOCA) PCT Margin Utilization sheets. Attachment B to this enclosure provides DCPP Unit 2 SBLOCA and BELOCA PCT Margin Utilization sheets. There have been no changes in the SBLOCA PCT results or the BELOCA PCT results for either Unit 1 or Unit 2 since the last annual update. The last update was provided in PG&E Letter DCL-11-082, "10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for 2010," dated July 19, 2011. A summary of the PCT margin allocations and their bases are provided in the attachments.
* Wolf Creek
The final net PCT values are listed below for each unit. It should be noted that 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.
Enclosure PG&E Letter DCL-12-070 ANNUAL REPORT OF EMERGENCY CORE COOLING SYSTEM EVALUATION MODEL CHANGES FOR PEAK CLADDING TEMPERATURE Pursuant to 10 CFR 50.46, this enclosure provides an annual report of changes in the Westinghouse emergency core cooling system (ECCS) evaluation models that affect peak cladding temperature (PCT) calculations for Pacific Gas and Electric Company (PG&E) Diablo Canyon Power Plant (DCPP), Units 1 and 2.
Small-Break LOCA Large-Break, Best-Estimate LOCA Reflood 1 Reflood 2 Unit 1: 1391°F (no change) 1990°F (no change) 1975°F (no change) Unit 2: 1288°F (no change) 1888°F (no change) The PCT values remain within the 2200 degree Fahrenheit (F) limit specified in 10 CFR 50.46. However, because the Unit 1 BELOCA has a total PCT margin allocation that is currently greater than 50 degrees F, and in order to coordinate with the 24-month fuel cycle project schedule, PG&E expects to complete the 1 Enclosure PG&E Letter DCL-12-070 Unit 1 BELOCA reanalysis and provide the updated PCT results to the NRC by December 2016, as stated in PG&E Letter DCL-11-082, "10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for 2010," dated July 19, 2011. 2 A. B. C. Attachment A PG&E Letter DCL-12-070 DCPP UNIT 1 PEAK CLADDING TEMPERATURE MARGIN UTILIZATION SMALL*BREAK LOCA PG&E Letter 1 ANAL YSIS OF RECORD PCT= 1391°F DCL-09-057 PRIOR 10 CFR 50.46 ECCS
This report is based on changes described in the following Westinghouse 10 CFR 50.46 notification letter:
: 1. None L1PCT = O°F 10 CFR 50.46 ECCS MODEL ASSESSMENTS THIS YEAR 1. None L1PCT = O°F D. SUM OF 10 CFR 50.46 CHANGES 1. Net Sum of 10 CFR 50.46 PCT Changes L1PCT = O°F 2. Absolute Sum of 10 CFR 50.46 PCT Changes L1PCT = O°F E. Analysis of Record PCT -Line A + Line 0.1 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.
Westinghouse Letter LTR-LlS-12-116, "Diablo Canyon Units 1 and 2 10 CFR 50.46 Annual Notification and Reporting for 2011 ," dated February 20,2012 Attachment A to this enclosure provides DCPP, Unit 1 small-break loss-of-coolant accident (SBLOCA) and best-estimate, large-break loss-of-coolant accident (BELOCA) PCT Margin Utilization sheets. Attachment B to this enclosure provides DCPP Unit 2 SBLOCA and BELOCA PCT Margin Utilization sheets. There have been no changes in the SBLOCA PCT results or the BELOCA PCT results for either Unit 1 or Unit 2 since the last annual update.
Temporary PCT allocations that address current LOCA model issues are not considered with respect to 10 CFR 50.46 reporting requirements.
The last update was provided in PG&E Letter DCL-11-082, "10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for 2010," dated July 19, 2011.
A-1 Attachment A PG&E Letter DCL-12-070 DCPP UNIT 1 PEAK CLADDING TEMPERATURE MARGIN UTILIZATION BEST-ESTIMATE z LARGE-BREAK LOCA PG&E Letter 1 Reflood Reflood 1 2 A. ANAL YSIS OF RECORD 1900°F 1860°F DCL-05-146 L1PCT L1PCT B. PRIOR 10 CFR 50.46 ECCS MODEL ASSESSMENTS 2 1. Revised blowdown heatup 5°F 5°F DCL-05-086 uncertainty distribution.
A summary of the PCT margin allocations and their bases are provided in the attachments.
: 2. HOTSPOT Fuel Relocation 10°F OaF DCL-07-071 Error. 3. Replacement Steam 75°F 71°F DCL-09-057 Generators C. 10 CFR 50.46 ECCS MODEL ASSESSMENTS THIS YEAR 1. 230kV Degraded Voltage OaF 39°F DCL-11-082 Event Evaluation D. SUM OF 10 CFR 50.46 CHANGES 1. Net Sum of 10 CFR 50.46 PCT 90°F 115°F Changes 2. Absolute Sum of 10 CFR 50.46 90°F 1156°F PCT Changes E. Analysis of Record PCT -Line A + Line 0.1 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.
The final net PCT values are listed below for each unit. It should be noted that 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.
Temporary PCT allocations that address current LOCA model issues are not considered with respect to 10 CFR 50.46 reporting requirements.
Small-Break LOCA                     Large-Break, Best-Estimate LOCA Reflood 1               Reflood 2 Unit 1:   1391°F (no change)           1990°F (no change)     1975°F (no change)
A-2 Attachment B PG&E Letter DCL-12-070 DCPP UNIT 2 PEAK CLADDING TEMPERATURE MARGIN UTILIZATION SMALL-BREAK LOCA A. ANALYSIS OF RECORD B. PRIOR 10 CFR 50.46 ECCS MODEL ASSESSMENTS 2 1. None C. 10 CFR 50.46 ECCS MODEL ASSESSMENTS THIS YEAR 2. None D. SUM OF 10 CFR 50.46 CHANGES 3. Net Sum of 10 CFR 50.46 PCT PCT= ilPCT = ilPCT = Changes ilPCT = OaF 4. Absolute Sum of 10 CFR 50.46 PCT Changes ilPCT = OaF E. Analysis of Record PCT -Line A + Line 0.1 Net Sum of 10 CFR 50.46 PCT Changes PG&E Letter 1 DCL-08-061 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.
Unit 2:   1288°F (no change)                         1888°F (no change)
Temporary PCT allocations that address current LOCA model issues are not considered with respect to 10 CFR 50.46 reporting requirements.
The PCT values remain within the 2200 degree Fahrenheit (F) limit specified in 10 CFR 50.46. However, because the Unit 1 BELOCA has a total PCT margin allocation that is currently greater than 50 degrees F, and in order to coordinate with the 24-month fuel cycle project schedule, PG&E expects to complete the 1
B-1 Attachment 8 PG&E Letter DCL-12-070 DCPP UNIT 2 PEAK CLADDING TEMPERATURE MARGIN UTILIZATION BEST-ESTIMATE, LARGE-BREAK LOCA A. ANALYSIS OF RECORD PCT= 8. PRIOR 10 CFR 50.46 ECCS MODEL ASSESSMENTS 2 1. HOTSPOT Fuel Relocation Error. C. 10 CFR 50.46 ECCS MODEL ASSESSMENTS THIS YEAR 1. 230kV Degraded Voltage Event Evaluation D. SUM OF 10 CFR 50.46 CHANGES 1. Net Sum of 10 CFR 50.46 PCT Changes 2. Absolute Sum of 10 CFR 50.46 PCT Changes E. Analysis of Record PCT -Line A + Line 0.1 Net Sum of 10 CFR 50.46 PCT Changes llPCT= llPCT= llPCT= llPCT= PG&E Letter 1 DCL-07-071 DCL-07-071 DCL-11-082 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.
Enclosure PG&E Letter DCL-12-070 Unit 1 BELOCA reanalysis and provide the updated PCT results to the NRC by December 2016, as stated in PG&E Letter DCL-11-082, "10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for 2010,"
dated July 19, 2011.
2
 
Attachment A PG&E Letter DCL-12-070 DCPP UNIT 1 PEAK CLADDING TEMPERATURE MARGIN UTILIZATION SMALL*BREAK LOCA                                                     PG&E Letter1 A. ANAL YSIS OF RECORD                     PCT=         1391°F     DCL-09-057 B. PRIOR 10 CFR 50.46 ECCS MODELASSESSMENT~
: 1. None L1PCT =         O°F C. 10 CFR 50.46 ECCS MODEL ASSESSMENTS THIS YEAR
: 1. None L1PCT =         O°F D. SUM OF 10 CFR 50.46 CHANGES
: 1. Net Sum of 10 CFR 50.46 PCT Changes                       L1PCT =         O°F
: 2. Absolute Sum of 10 CFR 50.46 PCT Changes           L1PCT =         O°F E. Analysis of Record PCT - Line A
      + Line 0.1 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.
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.
A-1
 
Attachment A PG&E Letter DCL-12-070 DCPP UNIT 1 PEAK CLADDING TEMPERATURE MARGIN UTILIZATION BEST-ESTIMATE z LARGE-BREAK LOCA                                             PG&E Letter1 Reflood     Reflood 1           2 A. ANAL YSIS OF RECORD                           1900°F       1860°F         DCL-05-146 L1PCT         L1PCT B. PRIOR 10 CFR 50.46 ECCS MODEL ASSESSMENTS 2
: 1. Revised blowdown heatup                       5°F           5°F         DCL-05-086 uncertainty distribution.
: 2. HOTSPOT Fuel Relocation                     10°F           OaF         DCL-07-071 Error.
: 3. Replacement Steam                           75°F         71°F         DCL-09-057 Generators C. 10 CFR 50.46 ECCS MODEL ASSESSMENTS THIS YEAR
: 1. 230kV Degraded Voltage                       OaF         39°F         DCL-11-082 Event Evaluation D. SUM OF 10 CFR 50.46 CHANGES
: 1. Net Sum of 10 CFR 50.46 PCT                 90°F         115°F Changes
: 2. Absolute Sum of 10 CFR 50.46                 90°F       1156°F PCT Changes E. Analysis of Record PCT - Line A +
Line 0.1 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.
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.
A-2
 
Attachment B PG&E Letter DCL-12-070 DCPP UNIT 2 PEAK CLADDING TEMPERATURE MARGIN UTILIZATION SMALL-BREAK LOCA                                                     PG&E Letter1 A. ANALYSIS OF RECORD                       PCT=                    DCL-08-061 B. PRIOR 10 CFR 50.46 ECCS MODEL ASSESSMENTS 2
: 1. None                                   ilPCT =
C. 10 CFR 50.46 ECCS MODEL ASSESSMENTS THIS YEAR
: 2. None ilPCT =
D. SUM OF 10 CFR 50.46 CHANGES
: 3. Net Sum of 10 CFR 50.46 PCT Changes                             ilPCT =       OaF
: 4. Absolute Sum of 10 CFR 50.46 PCT Changes                         ilPCT =       OaF E. Analysis of Record PCT - Line A + Line 0.1 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.
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-12-070 DCPP UNIT 2 PEAK CLADDING TEMPERATURE MARGIN UTILIZATION BEST-ESTIMATE, LARGE-BREAK LOCA                                               PG&E Letter1 A. ANALYSIS OF RECORD                             PCT=                     DCL-07-071
: 8. PRIOR 10 CFR 50.46 ECCS MODEL ASSESSMENTS 2
: 1. HOTSPOT Fuel Relocation                   llPCT=                    DCL-07-071 Error.
C. 10 CFR 50.46 ECCS MODEL ASSESSMENTS THIS YEAR
: 1. 230kV Degraded Voltage                     llPCT=                    DCL-11-082 Event Evaluation D. SUM OF 10 CFR 50.46 CHANGES
: 1. Net Sum of 10 CFR 50.46 PCT               llPCT=
Changes
: 2. Absolute Sum of 10 CFR 50.46               llPCT=
PCT Changes E. Analysis of Record PCT - Line A +
Line 0.1 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.
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.
8-2}}
8-2}}

Latest revision as of 01:43, 12 November 2019

10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for Peak Cladding Temperature for 2011
ML12202A793
Person / Time
Site: Diablo Canyon  Pacific Gas & Electric icon.png
Issue date: 07/19/2012
From: Becker J
Pacific Gas & Electric Co
To:
Office of Nuclear Reactor Regulation, Document Control Desk
References
DCL-12-070
Download: ML12202A793 (8)


Text

Pacific Gas and Electric Company James R. Becker Diablo Canyon Power Plant Site Vice President Mail Code 104/6 P. O. Box 56 Avila Beach, CA 93424 805.545.3462 Internal: 691. 3462 July 19, 2012 Fax: 805.545.6445 PG&E Letter DCL-12-070 U.S. Nuclear Regulatory Commission 10 CFR 50.46 ATTN: Document Control Desk Washington, DC 20555-0001 Docket No. 50-275, OL-DPR-BO Docket No. 50-323, OL-DPR-B2 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 2011

Dear Commissioners and Staff:

Pursuant to 10 CFR 50.46, the enclosure to this letter 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 (PG&E) Diablo Canyon Power Plant, Units 1 and 2.

There have been no changes in the small-break loss-of-coolant accident (SBLOCA) PCT results or the large-break, best-estimate loss-of-coolant accident (BELOCA) PCT results for either Unit 1 or Unit 2 since the last annual update. The last update was provided in PG&E Letter DCL-11-0B2, "10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for 2010,"

dated July 19, 2011.

A summary of the PCT margin allocations and their bases are provided in the enclosed attachments. The Unit 1 SBLOCA and BELOCA PCT Margin Utilization sheets are provided in Attachment A. The Unit 2 SBLOCA and BELOCA PCT Margin Utilization Sheets are provided in Attachment B.

The PCT values remain within the 2200 degree Fahrenheit (F) limit specified in 10 CFR 50.46. However, because the Unit 1 BELOCA has a total PCT margin allocation that is currently greater than 50 degrees F, and in order to coordinate with the 24-month fuel cycle project schedule, PG&E expects to complete the .

Unit 1 BELOCA reanalysis and provide the updated PCT results to the NRC by December 2016, as stated in PG&E Letter DCL-11-0B2, "10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for 2010,"

dated July 19, 2011.

A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway

  • Comanche Peak
  • Diablo Canyon
  • Palo Verde
  • San Onofre
  • Wolf Creek

Document Control Desk PG&E Letter DCL-12-070 July 19, 2012 Page 2 PG&E makes no new or revised regulatory commitments (as defined by NEI 99-04) in this report.

If you have questions regarding this submittal please contact Mr. Steve Baker at 805-545-6742.

Sincerely,

~~vJJr-I- ~

Jame\lR. Becker Site Vice President wrl8/6980/64059110 Enclosure cc/enc: Elmo E. Collins, NRC Region IV Michael S. Peck, NRC Senior Resident Inspector Joseph M. Sebrosky, NRR Senior Project Manager Diablo Distribution A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway

  • Comanche Peak
  • Diablo Canyon
  • Palo Verde
  • San Onofre
  • Wolf Creek

Enclosure PG&E Letter DCL-12-070 ANNUAL REPORT OF EMERGENCY CORE COOLING SYSTEM EVALUATION MODEL CHANGES FOR PEAK CLADDING TEMPERATURE Pursuant to 10 CFR 50.46, this enclosure provides an annual report of changes in the Westinghouse emergency core cooling system (ECCS) evaluation models that affect peak cladding temperature (PCT) calculations for Pacific Gas and Electric Company (PG&E) Diablo Canyon Power Plant (DCPP), Units 1 and 2.

This report is based on changes described in the following Westinghouse 10 CFR 50.46 notification letter:

Westinghouse Letter LTR-LlS-12-116, "Diablo Canyon Units 1 and 2 10 CFR 50.46 Annual Notification and Reporting for 2011 ," dated February 20,2012 Attachment A to this enclosure provides DCPP, Unit 1 small-break loss-of-coolant accident (SBLOCA) and best-estimate, large-break loss-of-coolant accident (BELOCA) PCT Margin Utilization sheets. Attachment B to this enclosure provides DCPP Unit 2 SBLOCA and BELOCA PCT Margin Utilization sheets. There have been no changes in the SBLOCA PCT results or the BELOCA PCT results for either Unit 1 or Unit 2 since the last annual update.

The last update was provided in PG&E Letter DCL-11-082, "10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for 2010," dated July 19, 2011.

A summary of the PCT margin allocations and their bases are provided in the attachments.

The final net PCT values are listed below for each unit. It should be noted that 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.

Small-Break LOCA Large-Break, Best-Estimate LOCA Reflood 1 Reflood 2 Unit 1: 1391°F (no change) 1990°F (no change) 1975°F (no change)

Unit 2: 1288°F (no change) 1888°F (no change)

The PCT values remain within the 2200 degree Fahrenheit (F) limit specified in 10 CFR 50.46. However, because the Unit 1 BELOCA has a total PCT margin allocation that is currently greater than 50 degrees F, and in order to coordinate with the 24-month fuel cycle project schedule, PG&E expects to complete the 1

Enclosure PG&E Letter DCL-12-070 Unit 1 BELOCA reanalysis and provide the updated PCT results to the NRC by December 2016, as stated in PG&E Letter DCL-11-082, "10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for 2010,"

dated July 19, 2011.

2

Attachment A PG&E Letter DCL-12-070 DCPP UNIT 1 PEAK CLADDING TEMPERATURE MARGIN UTILIZATION SMALL*BREAK LOCA PG&E Letter1 A. ANAL YSIS OF RECORD PCT= 1391°F DCL-09-057 B. PRIOR 10 CFR 50.46 ECCS MODELASSESSMENT~

1. None L1PCT = O°F C. 10 CFR 50.46 ECCS MODEL ASSESSMENTS THIS YEAR
1. None L1PCT = O°F D. SUM OF 10 CFR 50.46 CHANGES
1. Net Sum of 10 CFR 50.46 PCT Changes L1PCT = O°F
2. Absolute Sum of 10 CFR 50.46 PCT Changes L1PCT = O°F E. Analysis of Record PCT - Line A

+ Line 0.1 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.

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.

A-1

Attachment A PG&E Letter DCL-12-070 DCPP UNIT 1 PEAK CLADDING TEMPERATURE MARGIN UTILIZATION BEST-ESTIMATE z LARGE-BREAK LOCA PG&E Letter1 Reflood Reflood 1 2 A. ANAL YSIS OF RECORD 1900°F 1860°F DCL-05-146 L1PCT L1PCT B. PRIOR 10 CFR 50.46 ECCS MODEL ASSESSMENTS 2

1. Revised blowdown heatup 5°F 5°F DCL-05-086 uncertainty distribution.
2. HOTSPOT Fuel Relocation 10°F OaF DCL-07-071 Error.
3. Replacement Steam 75°F 71°F DCL-09-057 Generators C. 10 CFR 50.46 ECCS MODEL ASSESSMENTS THIS YEAR
1. 230kV Degraded Voltage OaF 39°F DCL-11-082 Event Evaluation D. SUM OF 10 CFR 50.46 CHANGES
1. Net Sum of 10 CFR 50.46 PCT 90°F 115°F Changes
2. Absolute Sum of 10 CFR 50.46 90°F 1156°F PCT Changes E. Analysis of Record PCT - Line A +

Line 0.1 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.

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.

A-2

Attachment B PG&E Letter DCL-12-070 DCPP UNIT 2 PEAK CLADDING TEMPERATURE MARGIN UTILIZATION SMALL-BREAK LOCA PG&E Letter1 A. ANALYSIS OF RECORD PCT= DCL-08-061 B. PRIOR 10 CFR 50.46 ECCS MODEL ASSESSMENTS 2

1. None ilPCT =

C. 10 CFR 50.46 ECCS MODEL ASSESSMENTS THIS YEAR

2. None ilPCT =

D. SUM OF 10 CFR 50.46 CHANGES

3. Net Sum of 10 CFR 50.46 PCT Changes ilPCT = OaF
4. Absolute Sum of 10 CFR 50.46 PCT Changes ilPCT = OaF E. Analysis of Record PCT - Line A + Line 0.1 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.

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-12-070 DCPP UNIT 2 PEAK CLADDING TEMPERATURE MARGIN UTILIZATION BEST-ESTIMATE, LARGE-BREAK LOCA PG&E Letter1 A. ANALYSIS OF RECORD PCT= DCL-07-071

8. PRIOR 10 CFR 50.46 ECCS MODEL ASSESSMENTS 2
1. HOTSPOT Fuel Relocation llPCT= DCL-07-071 Error.

C. 10 CFR 50.46 ECCS MODEL ASSESSMENTS THIS YEAR

1. 230kV Degraded Voltage llPCT= DCL-11-082 Event Evaluation D. SUM OF 10 CFR 50.46 CHANGES
1. Net Sum of 10 CFR 50.46 PCT llPCT=

Changes

2. Absolute Sum of 10 CFR 50.46 llPCT=

PCT Changes E. Analysis of Record PCT - Line A +

Line 0.1 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.

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.

8-2