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Category:Letter type:DCL
MONTHYEARDCL-24-010, Nuclear Material Transaction Report for New Fuel2024-01-29029 January 2024 Nuclear Material Transaction Report for New Fuel DCL-24-009, Nuclear Material Transaction Report for New Fuel2024-01-17017 January 2024 Nuclear Material Transaction Report for New Fuel DCL-24-008, Schedule Considerations for Review of the DCPP License Renewal Application2024-01-17017 January 2024 Schedule Considerations for Review of the DCPP License Renewal Application DCL-24-004, Supplement to License Amendment Request 23-01 Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2024-01-15015 January 2024 Supplement to License Amendment Request 23-01 Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b DCL-23-129, Nuclear Material Transaction Report for New Fuel2023-12-27027 December 2023 Nuclear Material Transaction Report for New Fuel DCL-23-122, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-14014 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation DCL-23-128, Emergency Plan Update2023-12-13013 December 2023 Emergency Plan Update DCL-23-125, Core Operating Limits Report for Unit 1 Cycle 252023-12-0606 December 2023 Core Operating Limits Report for Unit 1 Cycle 25 DCL-23-121, Supplement to License Amendment Request 23-03, Revision to Technical Specification3.7.8, Auxiliary Saltwater System2023-11-16016 November 2023 Supplement to License Amendment Request 23-03, Revision to Technical Specification3.7.8, Auxiliary Saltwater System DCL-23-120, License Amendment Request 23-03 Revision to Technical Specification 3.7.8, Auxiliary Saltwater (Asw) System2023-11-14014 November 2023 License Amendment Request 23-03 Revision to Technical Specification 3.7.8, Auxiliary Saltwater (Asw) System DCL-23-118, License Renewal Application2023-11-0707 November 2023 License Renewal Application DCL-2023-520, Discharge Self-Monitoring at Diablo Canyon Power Plant (DCPP)2023-10-19019 October 2023 Discharge Self-Monitoring at Diablo Canyon Power Plant (DCPP) DCL-23-103, Independent Spent Fuel Storage Installation - Withdrawal of License Amendment Request 22-01, Request for Approval of Alternative Security Measures for Early Warning System2023-10-13013 October 2023 Independent Spent Fuel Storage Installation - Withdrawal of License Amendment Request 22-01, Request for Approval of Alternative Security Measures for Early Warning System DCL-23-092, Material Status Report for the Period Ending August 31, 20232023-09-28028 September 2023 Material Status Report for the Period Ending August 31, 2023 DCL-23-077, License Amendment Request 23-02 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-27027 September 2023 License Amendment Request 23-02 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors DCL-23-083, Upcoming Meeting with Nuclear Security and Incident Response Staff2023-09-13013 September 2023 Upcoming Meeting with Nuclear Security and Incident Response Staff DCL-23-078, Nuclear Material Transaction Report for New Fuel2023-09-0606 September 2023 Nuclear Material Transaction Report for New Fuel DCL-23-070, Withdrawal of Request Regarding Senior Reactor Operator License Application2023-08-16016 August 2023 Withdrawal of Request Regarding Senior Reactor Operator License Application DCL-23-068, Nuclear Material Transaction Report for New Fuel2023-08-0909 August 2023 Nuclear Material Transaction Report for New Fuel DCL-23-066, Nuclear Material Transaction Report for New Fuel2023-08-0303 August 2023 Nuclear Material Transaction Report for New Fuel DCL-23-065, Letter DCL-23-065 Request That Exam Material Be Withheld from Public Disclosure2023-07-27027 July 2023 Letter DCL-23-065 Request That Exam Material Be Withheld from Public Disclosure DCL-23-064, Nuclear Material Transaction Report for New Fuel2023-07-26026 July 2023 Nuclear Material Transaction Report for New Fuel DCL-23-054, License Amendment Request 23-01 Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2023-07-13013 July 2023 License Amendment Request 23-01 Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b DCL-23-055, Nuclear Material Transaction Report for New Fuel2023-07-0606 July 2023 Nuclear Material Transaction Report for New Fuel DCL-23-042, Independent Spent Fuel Storage Installation, Submittal of Quality Assurance Program Description, Revision 02023-05-24024 May 2023 Independent Spent Fuel Storage Installation, Submittal of Quality Assurance Program Description, Revision 0 DCL-23-032, Independent Spent Fuel Storage Installation Docket No. 72-27, Materials License Number SNM-2514 Humboldt Bay Independent Spent Fuel Storage Installation - NRC Requested Notification of Withdrawal from Voluntary Program2023-05-22022 May 2023 Independent Spent Fuel Storage Installation Docket No. 72-27, Materials License Number SNM-2514 Humboldt Bay Independent Spent Fuel Storage Installation - NRC Requested Notification of Withdrawal from Voluntary Program DCL-23-041, 10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for Peak Cladding Temperature for 20222023-05-22022 May 2023 10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for Peak Cladding Temperature for 2022 DCL-23-038, Revision to the Unit 1 Reactor Vessel Material Surveillance Program Withdrawal Schedule2023-05-15015 May 2023 Revision to the Unit 1 Reactor Vessel Material Surveillance Program Withdrawal Schedule DCL-23-034, 2022 Annual Nonradiological Environmental Operating Report2023-05-0101 May 2023 2022 Annual Nonradiological Environmental Operating Report DCL-23-036, 2022 Annual Radiological Environmental Operating Report2023-05-0101 May 2023 2022 Annual Radiological Environmental Operating Report DCL-23-025, 2022 Annual Radioactive Effluent Release Report2023-05-0101 May 2023 2022 Annual Radioactive Effluent Release Report DCL-2023-512, Submittal of Receiving Water Monitoring Program 2022 Annual Report2023-04-27027 April 2023 Submittal of Receiving Water Monitoring Program 2022 Annual Report DCL-23-035, Response to Request for Additional Information on Request Regarding Senior Reactor Operator License Application2023-04-24024 April 2023 Response to Request for Additional Information on Request Regarding Senior Reactor Operator License Application DCL-23-028, Technical Specification Bases, Revision 142023-04-24024 April 2023 Technical Specification Bases, Revision 14 DCL-2023-511, Report on Discharge Monitoring for the First Quarter of 20232023-04-20020 April 2023 Report on Discharge Monitoring for the First Quarter of 2023 DCL-23-031, Submittal of Annual Report of Occupational Radiation Exposure for 20222023-04-19019 April 2023 Submittal of Annual Report of Occupational Radiation Exposure for 2022 DCL-23-024, Independent Spent Fuel Storage Installation, Response to Nrg Request for Additional Information for Revision to License Amendment Request 22-01 Request for Approval of Alternative Security Measures for Early Warning System2023-04-0404 April 2023 Independent Spent Fuel Storage Installation, Response to Nrg Request for Additional Information for Revision to License Amendment Request 22-01 Request for Approval of Alternative Security Measures for Early Warning System DCL-23-022, 2023 Annual Statement of Insurance for Pacific Gas and Electric Companys Diablo Canyon Power Plant2023-03-29029 March 2023 2023 Annual Statement of Insurance for Pacific Gas and Electric Companys Diablo Canyon Power Plant DCL-23-023, Decommissioning Funding Report for Diablo Canyon Power Plant, Units 1 and 22023-03-28028 March 2023 Decommissioning Funding Report for Diablo Canyon Power Plant, Units 1 and 2 DCL-23-021, Independent Spent Fuel Storage Installation, Emergency Plan Update2023-03-23023 March 2023 Independent Spent Fuel Storage Installation, Emergency Plan Update DCL-23-020, Responses to NRC Questions Regarding License Renewal Efforts2023-03-17017 March 2023 Responses to NRC Questions Regarding License Renewal Efforts DCL-23-009, Owner'S Activity Report for Unit 2 Twenty-Third Refueling Outage2023-02-22022 February 2023 Owner'S Activity Report for Unit 2 Twenty-Third Refueling Outage DCL-23-008, Request Regarding Senior Reactor Operator License Application2023-02-22022 February 2023 Request Regarding Senior Reactor Operator License Application DCL-2023-503, Annual Sea Turtle Report2023-01-26026 January 2023 Annual Sea Turtle Report DCL-2023-502, (DCPP) 4th Quarter 2022 Report on Discharge Self-Monitoring2023-01-18018 January 2023 (DCPP) 4th Quarter 2022 Report on Discharge Self-Monitoring DCL-22-091, Revised Steam Generator Tube Inspection Report for Twenty-First Refueling Outage2022-12-20020 December 2022 Revised Steam Generator Tube Inspection Report for Twenty-First Refueling Outage DCL-22-089, Core Operating Limits Report for Unit 2 Cycle 242022-12-20020 December 2022 Core Operating Limits Report for Unit 2 Cycle 24 DCL-22-085, Request to Resume Review of the License Renewal Application or, Alternatively, for an Exemption from 10 CFR 2.109(b), Concerning a Timely Renewal Application2022-10-31031 October 2022 Request to Resume Review of the License Renewal Application or, Alternatively, for an Exemption from 10 CFR 2.109(b), Concerning a Timely Renewal Application DCL-22-041, Site-Specific Decommissioning Cost Estimate, Revision 12022-10-12012 October 2022 Site-Specific Decommissioning Cost Estimate, Revision 1 DCL-22-042, Post-Shutdown Decommissioning Activities Report, Revision 12022-10-12012 October 2022 Post-Shutdown Decommissioning Activities Report, Revision 1 2024-01-29
[Table view] Category:Operating Report
MONTHYEARDCL-20-043, Thirty-Day Notification Report of Significant Emergency Core Cooling System Evaluation Model Changes That Affect Peak Cladding Temperature and 10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Mode2020-05-20020 May 2020 Thirty-Day Notification Report of Significant Emergency Core Cooling System Evaluation Model Changes That Affect Peak Cladding Temperature and 10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Mode DCL-18-071, 10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for Peak Cladding Temperature for 20172018-09-25025 September 2018 10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for Peak Cladding Temperature for 2017 DCL-14-101, Core Operating Limits Report for Unit 2 Cycle 192014-11-10010 November 2014 Core Operating Limits Report for Unit 2 Cycle 19 DCL-13-030, Core Operating Limits Report for Unit 2 Cycle 182013-03-27027 March 2013 Core Operating Limits Report for Unit 2 Cycle 18 DCL-07-049, Annual Nonradiological Environmental Operating Report2007-04-26026 April 2007 Annual Nonradiological Environmental Operating Report DCL-05-047, Pressure and Temperature Limits Report (PTLR-1), Revision 52005-04-22022 April 2005 Pressure and Temperature Limits Report (PTLR-1), Revision 5 DCL-05-001, Pressure and Temperature Limits Report (Ptlr). Revision 32005-01-0707 January 2005 Pressure and Temperature Limits Report (Ptlr). Revision 3 DCL-02-062, Core Operating Limits Report, Cycle 122002-05-17017 May 2002 Core Operating Limits Report, Cycle 12 2020-05-20
[Table view] |
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Pacific Gas and Electric Company" James M. Welsch Diablo Canyon Power Plant Vice President P.O. Box 56 Nuclear Generation and Avila Beach, CA 93424 Chief Nuclear Officer 805.545.3242 E-Mail: James.Welsch@pge.com September 25, 2018 PG&E Letter DCL-18-071 U.S. Nuclear Regulatory Commission 10 CFR 50.46 ATTN: 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 2017
Dear Commissioners and Staff:
Pursuant to 10 CFR 50.46, Pacific Gas and Electric Company (PG&E) hereby submits the annual report of changes in the Westinghouse emergency core cooling system evaluation models that affect peak cladding temperature (PCT) calculations for Diablo Canyon Power Plant, Units 1 and 2.
The enclosure and its attachments provide a summary of the PCT margin allocations and their bases.
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 remains within the 2200°F limit specified in 10 CFR 50.46.
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.
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Document Control Desk PG&E Letter DCL-18-071 September 25, 2018 Page2 dqmg/6192/50871345 Enclosure cc: Diablo Distribution cc/enc: Kriss M. Kennedy, NRC Region IV Administrator Christopher W. Newport, NRC Senior Resident Inspector Balwant K. Singal, NRC Senior Project Manager A member of the STARS Alliance Calla w ay
Enclosure PG&E Letter DCL-18-071 ANNUAL REPORT OF EMERGENCY CORE COOLING SYSTEM EVALUATION MODEL CHANGES FOR PEAK CLADDING TEMPERATURE
Enclosure PG&E Letter DCL-18-071 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 evaluation models that affect peak cladding temperature (PCT) calculations for Pacific Gas and Electric Company's Diablo Canyon Power Plant, Units 1 and 2. This report is based on changes described in Westinghouse Letter LTR-LIS-18-17, "Diablo Canyon Units 1 and 2 10 CFR 50.46 Annual Notification and Reporting for 2017," dated February 15, 2018.
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 B 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 previous annual update.
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.
Unit SBLOCA BELOCA Unit 1 1391 °F (no change) Reflood 1 Reflood 2 2049°F (no change) 2124°F (no change)
Unit 2 1288°F (no change) 2125°F (no change)
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 remains within the 2200°F limit specified in 10 CFR 50.46.
1
Enclosure Attachment A PG&E Letter DCL-18-071 DIABLO CANYON POWER PLANT, UNIT 1 PEAK CLADDING TEMPERATURE MARGIN UTILIZATION SMALL-BREAK PG&E Letter1 LOSS-OF-COOLANT-ACCIDENT (LOCA}
Peak Cladding A. ANALYSIS OF RECORD 1391 °F DCL-09-057 Temperature (PCT)=
B. PRIOR 10 CFR 50.46 EMERGENCY CORE COOLING SYSTEM (ECCS)
MODEL ASSESSMENTS
- 1. None .".\PCT= 0°F C. 10 CFR 50.46 ECCS MODEL ASSESSMENTS THIS YEAR
- 1. None .".\PCT= 0°F D. SUM OF 10 CFR 50.46 CHANGES
- 1. Net Sum of 10 CFR 50.46 PCT Changes .".\PCT= 0°F
- 2. Absolute Sum of 10 CFR 50.46 PCT
.".\PCT= 0°F Changes E. Analysis of Record PCT (Line A) + Line D.1 Net Sum 1391 °F of 10 CFR 50.46 PCT Changes For those issues that have been previously reported under 10 CFR 50.46, a PG&E letter number is listed .
A-1
Enclosure Attachment A PG&E Letter DCL-18-071 DIABLO CANYON POWER PLANT, UNIT 1 PEAK CLADDING TEMPERATURE MARGIN UTILIZATION BEST-ESTIMATE, LARGE-BREAK LOCA PG&E Letter1 Reflood 1 Reflood 2 A. ANALYSIS OF RECORD 1900°F 1860°F DCL-05-146
~PCT ~PCT B. PRIOR 10 CFR 50.46 ECCS MODEL ASSESSMENTS
- 1. Revised blowdown heatup 5°F 5°F DCL-05-086 uncertainty distribution.
- 2. HOTSPOT Fuel Relocation 10°F 0°F DCL-07-071 Error.
- 3. Replacement Steam 75°F 71°F DCL-09-057 Generators
- 4. 230 kV Degraded Voltage Event 0°F 39°F DCL-11-082
- 5. Performance and Design 4.0 -118°F -118°F DCL-12-102 Implementation
- 6. Fuel Thermal Conductivity 133°F 238°F DCL-12-102 Degradation 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 0°F 0°F 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 For those issues that have been previously reported under 10 CFR 50.46, a PG&E letter number is listed.
A-2
Enclosure Attachment B PG&E Letter DCL-18-071 DCPP UNIT 2 PEAK CLADDING TEMPERATURE MARGIN UTILIZATION SMALL-BREAK LOSS-OF-COOLANT ACCIDENT (LOCA) PG&E Letter1 Peak Cladding A. ANALYSIS OF RECORD 1288°F DCL-08-061 Temperature (PCT)=
B. PRIOR 10 CFR 50.46 EMERGENCY CORE COOLING SYSTEM(ECCS)MODEL ASSESSMENTS
- 1. None LiPCT = 0°F C. 10 CFR 50.46 ECCS MODEL ASSESSMENTS THIS YEAR
- 1. None LiPCT = 0°F D. SUM OF 10 CFR 50.46 CHANGES
- 1. Net Sum of 10 CFR 50.46 PCT Changes LiPCT = 0°F
- 2. Absolute Sum of 10 CFR 50.46 PCT Changes LiPCT = 0°F E. Analysis of Record PCT (Line A) +
Line D.1 Net Sum of 10 CFR 50.46 1288°F PCT Changes For those issues that have been previously reported under 10 CFR 50.46, a PG&E Letter number is listed.
B-1
Enclosure Attachment B PG&E Letter DCL-18-071 DCPP UNIT 2 PEAK CLADDING TEMPERATURE MARGIN UTILIZATION BEST-ESTIMATE, LARGE BREAK LOCA PG&E Letter1 A. ANALYSIS OF RECORD PCT= 1872°F DCL-07-071 B. PRIOR 10 CFR 50.46 ECCS MODEL ASSESSMENTS
- 1. HOTSPOT Fuel Relocation Error. ~PCT= 0°F DCL-07-071
- 2. 230 kV Degraded Voltage Event. ~PCT= 16F DCL-11-082
- 3. Fuel Thermal Conductivity Degradation and Peaking Factor ~PCT= 209°F DCL-12-102 Burndown
- 4. Revised Heat Transfer Multiplier
~PCT= -17°F DCL-13-111 Distribution
- 5. Changes to Grid Blockage and
~PCT= 24°F DCL-13-111 Porosity
- 6. Error in Burst Strain Application ~PCT= 21 °F DCL-14-070 C. 10 CFR 50.46 ECCS MODEL ASSESSMENTS THIS YEAR
- 1. None ~PCT= 0°F 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= 287°F PCT Changes E. Analysis of Record PCT (Line A) +
Line 0.1 Net Sum of 10 CFR 50.46 2125°F PCT Changes For those issues that have been previously reported under 10 CFR 50.46, a PG&E letter number is listed.
8 -2