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Category:Annual Report
MONTHYEARDCL-24-032, 2024 Annual Statement of Insurance for Pacific Gas and Electric Company’S Diablo Canyon Power Plant2024-03-27027 March 2024 2024 Annual Statement of Insurance for Pacific Gas and Electric Company’S Diablo Canyon Power Plant DCL-2024-502, 2023 Annual Sea Turtle Report for Diablo Canyon Power Plant (DCPP)2024-01-25025 January 2024 2023 Annual Sea Turtle Report for Diablo Canyon Power Plant (DCPP) DCL-20-021, Submittal of 2020 Annual Statement of Insurance for Pacific Gas and Electric Company'S Diablo Canyon Power Plant and Humboldt Bay Power Plant2020-04-0101 April 2020 Submittal of 2020 Annual Statement of Insurance for Pacific Gas and Electric Company'S Diablo Canyon Power Plant and Humboldt Bay Power Plant DCL-19-024, and Humboldt Bay Power Plant 2019 Annual Statement of Insurance2019-03-28028 March 2019 and Humboldt Bay Power Plant 2019 Annual Statement of Insurance ML16154A1652016-04-27027 April 2016 Submittal of Copies of Receiving Water Monitoring Program 2015 Annual Report L-2016-518, Diablo Canyon Power Plant, Submittal of Copies of Receiving Water Monitoring Program 2015 Annual Report2016-04-27027 April 2016 Diablo Canyon Power Plant, Submittal of Copies of Receiving Water Monitoring Program 2015 Annual Report DCL-16-052, Submittal of Annual Report of Occupational Radiation Exposure for 20152016-04-26026 April 2016 Submittal of Annual Report of Occupational Radiation Exposure for 2015 DCL-15-093, 10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for Peak Cladding Temperature for 20142015-08-0606 August 2015 10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for Peak Cladding Temperature for 2014 DCL-2014-517, Letter from Kenneth W. Cortese Report on Discharge Monitoring at Diablo Canyon Power Plant2014-04-17017 April 2014 Letter from Kenneth W. Cortese Report on Discharge Monitoring at Diablo Canyon Power Plant DCL-14-025, Annual Report of Occupational Radiation Exposure for 20132014-04-10010 April 2014 Annual Report of Occupational Radiation Exposure for 2013 DCL-2014-509, Annual Report on Discharge Monitoring2014-02-28028 February 2014 Annual Report on Discharge Monitoring DCL-07-047, Annual Radioactive Effluent Release Report2007-04-27027 April 2007 Annual Radioactive Effluent Release Report DCL-06-088, CFR 50.46 Annual Report for 2005 of Emergency Core Cooling System Evaluation Model Changes2006-07-24024 July 2006 CFR 50.46 Annual Report for 2005 of Emergency Core Cooling System Evaluation Model Changes DCL-2006-522, PG&E Diablo Canyon Power Plant (DCPP) Submittal - Receiving Water Monitoring Program 2005 Annual Report2006-04-28028 April 2006 PG&E Diablo Canyon Power Plant (DCPP) Submittal - Receiving Water Monitoring Program 2005 Annual Report DCL-06-048, 2005 Annual Radioactive Effluent Release Report.2005-12-31031 December 2005 2005 Annual Radioactive Effluent Release Report. DCL-05-050, 2004 Annual Radiological Environmental Operating Report2005-04-29029 April 2005 2004 Annual Radiological Environmental Operating Report DCL-05-027, PG&E Corporation 2004 Annual Report2005-03-22022 March 2005 PG&E Corporation 2004 Annual Report DCL-04-051, Units I and 2, 2003 Annual Radiological Environmental Operating Report2004-04-30030 April 2004 Units I and 2, 2003 Annual Radiological Environmental Operating Report DCL-04-053, Annual Nonradiological Environmental Operating Report2004-04-28028 April 2004 Annual Nonradiological Environmental Operating Report DCL-04-038, Annual Technical Specification 5.6.1 Report2004-04-16016 April 2004 Annual Technical Specification 5.6.1 Report DCL-03-040, Annual Technical Specification 5.6.1 Report2003-04-16016 April 2003 Annual Technical Specification 5.6.1 Report DCL-02-114, Commitment Change Summary Report, January - December 20012002-09-24024 September 2002 Commitment Change Summary Report, January - December 2001 DCL-02-089, CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes2002-07-26026 July 2002 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes 2024-03-27
[Table view] Category:Letter type:DCL
MONTHYEARDCL-24-103, Pg&Es Voluntary Submittal of Information Related to 10 CFR 2.206 Petition Regarding Seismic Core Damage Frequency for DCPP, Units 1 and 22024-10-24024 October 2024 Pg&Es Voluntary Submittal of Information Related to 10 CFR 2.206 Petition Regarding Seismic Core Damage Frequency for DCPP, Units 1 and 2 DCL-24-092, Supplement and Annual Update License Renewal Application, Amendment 12024-10-14014 October 2024 Supplement and Annual Update License Renewal Application, Amendment 1 DCL-24-098, Material Status Report for the Period Ending August 31, 20242024-10-0909 October 2024 Material Status Report for the Period Ending August 31, 2024 DCL-24-091, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation2024-10-0303 October 2024 Response to Request for Additional Information by the Office of Nuclear Reactor Regulation DCL-24-087, License Renewal - Historic and Cultural Resources Reference Documents (Redacted)2024-09-12012 September 2024 License Renewal - Historic and Cultural Resources Reference Documents (Redacted) DCL-24-083, CFR Part 21 Notification: Commercially Dedicated Snubber Valve Not Properly Heat Treated2024-09-0909 September 2024 CFR Part 21 Notification: Commercially Dedicated Snubber Valve Not Properly Heat Treated DCL-24-078, Pre-Notice of Disbursement from Decommissioning Trust2024-09-0303 September 2024 Pre-Notice of Disbursement from Decommissioning Trust DCL-24-082, Decommissioning Draft Biological Assessment and Draft Essential Fish Habitat Assessment2024-08-28028 August 2024 Decommissioning Draft Biological Assessment and Draft Essential Fish Habitat Assessment DCL-24-077, Responses to NRC Requests for Additional Information on Diablo Canyon Power License Renewal Application Severe Accident2024-08-15015 August 2024 Responses to NRC Requests for Additional Information on Diablo Canyon Power License Renewal Application Severe Accident DCL-24-075, Response to Request for Additional Information for 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 React2024-08-0808 August 2024 Response to Request for Additional Information for 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 React DCL-24-079, DC-2024-07 Post Exam Comments Analysis2024-08-0202 August 2024 DC-2024-07 Post Exam Comments Analysis DCL-24-070, License Amendment Request 24-03 Revision to Technical Specification 5.5.16 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2024-07-31031 July 2024 License Amendment Request 24-03 Revision to Technical Specification 5.5.16 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies DCL-24-071, Core Operating Limits Report for Unit 2 Cycle 252024-07-22022 July 2024 Core Operating Limits Report for Unit 2 Cycle 25 DCL-2024-523, Submittal of Report on Discharge Self-Monitoring2024-07-18018 July 2024 Submittal of Report on Discharge Self-Monitoring DCL-2024-527, Sea Turtle Stranding Report (Loggerhead Sea Turtle) Diablo Canyon Power Plant2024-07-0101 July 2024 Sea Turtle Stranding Report (Loggerhead Sea Turtle) Diablo Canyon Power Plant DCL-24-066, Request to Extend the Nrg Approval of Alternative for Use of Full Structural Weld Overlay, REP-RHR-SWOL2024-06-27027 June 2024 Request to Extend the Nrg Approval of Alternative for Use of Full Structural Weld Overlay, REP-RHR-SWOL DCL-24-052, Responses to NRC Requests for Additional Information on the Diablo Canyon Power Plant License Renewal Application Environmental Report2024-05-16016 May 2024 Responses to NRC Requests for Additional Information on the Diablo Canyon Power Plant License Renewal Application Environmental Report DCL-24-051, One Hundred Eighty Day Steam Generator Report for Twenty-Fourth Refueling Outage2024-05-0808 May 2024 One Hundred Eighty Day Steam Generator Report for Twenty-Fourth Refueling Outage DCL-24-049, 2023 Annual Radiological Environmental Operating Report2024-05-0101 May 2024 2023 Annual Radiological Environmental Operating Report DCL-24-047, 2023 Annual Non-radiological Environmental Operating Report2024-05-0101 May 2024 2023 Annual Non-radiological Environmental Operating Report DCL-24-048, O CFR 50.59 and 1 O CFR 72.48 Summary Report for the Period of January 1, 2022, Through December 31, 20232024-04-30030 April 2024 O CFR 50.59 and 1 O CFR 72.48 Summary Report for the Period of January 1, 2022, Through December 31, 2023 DCL-24-027, 2023 Annual Radioactive Effluent Release Report2024-04-28028 April 2024 2023 Annual Radioactive Effluent Release Report DCL-24-045, Annual Report of Occupational Radiation Exposure for 20232024-04-24024 April 2024 Annual Report of Occupational Radiation Exposure for 2023 DCL-24-042, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-04-17017 April 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations DCL-24-022, Notification of Changes to Decommissioning Schedule2024-04-0202 April 2024 Notification of Changes to Decommissioning Schedule DCL-24-023, Revised Certification of Permanent Cessation of Power Operations2024-04-0202 April 2024 Revised Certification of Permanent Cessation of Power Operations DCL-24-031, Decommissioning Funding Report2024-03-27027 March 2024 Decommissioning Funding Report DCL-24-032, 2024 Annual Statement of Insurance for Pacific Gas and Electric Company’S Diablo Canyon Power Plant2024-03-27027 March 2024 2024 Annual Statement of Insurance for Pacific Gas and Electric Company’S Diablo Canyon Power Plant DCL-24-028, Request for Enforcement Discretion Regarding Compliance with Technical Specification 3.0.3, Limiting Condition for Operation Applicability2024-03-21021 March 2024 Request for Enforcement Discretion Regarding Compliance with Technical Specification 3.0.3, Limiting Condition for Operation Applicability DCL-24-018, License Amendment Request 24-01 Revision to Technical Specification 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)2024-02-28028 February 2024 License Amendment Request 24-01 Revision to Technical Specification 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) DCL-2024-507, 2023 Annual Report on Discharge Self-Monitoring2024-02-27027 February 2024 2023 Annual Report on Discharge Self-Monitoring DCL-24-020, Nuclear Material Transaction Report for New Fuel2024-02-21021 February 2024 Nuclear Material Transaction Report for New Fuel DCL-24-014, Owners Activity Report for Unit 1 Twenty-Fourth Refueling Outage2024-02-12012 February 2024 Owners Activity Report for Unit 1 Twenty-Fourth Refueling Outage DCL-24-013, Nuclear Material Transaction Report for New Fuel2024-02-0707 February 2024 Nuclear Material Transaction Report for New Fuel DCL-24-010, Nuclear Material Transaction Report for New Fuel2024-01-29029 January 2024 Nuclear Material Transaction Report for New Fuel DCL-2024-502, 2023 Annual Sea Turtle Report for Diablo Canyon Power Plant (DCPP)2024-01-25025 January 2024 2023 Annual Sea Turtle Report for Diablo Canyon Power Plant (DCPP) DCL-2024-501, Sea Turtle Stranding Report (Green Sea Turtle)2024-01-24024 January 2024 Sea Turtle Stranding Report (Green Sea Turtle) DCL-2024-500, Transmittal of the 4th Quarter of 2023 Report on Discharge Self-Monitoring2024-01-18018 January 2024 Transmittal of the 4th Quarter of 2023 Report on Discharge Self-Monitoring 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-24-009, Nuclear Material Transaction Report for New Fuel2024-01-17017 January 2024 Nuclear Material Transaction Report for New Fuel 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 2024-09-09
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Pacific Gas and Electric Company Barry S. Allen Diablo Canyon Power Plant Vice President, Nuclear Services Mail Code 104/6 P. 0. Box 56 August 6, 2015 Avila Beach, CA 93424 805.545.4888 Internal: 691.4888 PG&E Letter DCL-15-093 Fax: 805.545 .6445 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 2014
Dear Commissioners and Staff:
Pursuant to 10 CFR 50.46, "Acceptance criteria for emergency core systems for light-water nuclear power reactors," 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 provide a summary of the PCT margin allocations and their bases.
PG&E will complete a reanalysis for both Units 1 and 2 using the Westinghouse FULL SPECTRUMTM loss-of-coolant accident (FSLOCA') methodology and provide the updated PCT results to the NRC by December 2018. This is a change to a previous regulatory commitment (as defined in NEI 99-04) made in PG&E Letter DCL-13-111, "Thirty-Day Notification Report of Significant Emergency Core Cooling System Evaluation Model Changes That Affect Peak Cladding Temperature," dated November 14, 2013, in which PG&E committed to complete the best estimate large break loss-of-coolant accident reanalysis for Units 1 and 2 and provide the updated PCT results to the NRC by December 2016. The reason for the change in commitment date is the current schedule for NRC approval of the methodology required to address fuel thermal conductivity degradation.
If you have questions regarding this submittal please contact Mr. Mark Sharp at 805-545-3031.
Sincerely, Jf7_5. AP--.
Barry S. Allen A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway
Document Control Desk PG&E Letter DCL-15-093 August 6, 2015 Page2 dqmg/6192/50795995 Enclosure cc/enc: Marc L. Dapas, NRC Region IV Administrator Siva P. Lingam, NRR Project Manager John P. Reynoso, Acting NRC Senior Resident Inspector Diablo Distribution A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway
Enclosure PG&E Letter DCL-15-093 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's (PG&E's) Diablo Canyon Power Plant (DCPP), Units 1 and 2. This report is based on changes described in Westinghouse Letter LTR-LIS-15-42, "Diablo Canyon Units 1 and 2 10 CFR 50.46 Annual Notification and Reporting for 2014," dated February 19, 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 or BELOCA PCT results for either Units 1 or 2 since the last annual update. The last annual update was provided in PG&E Letter DCL-14-070, "10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for Peak Cladding Temperature for 2013," dated August 7, 2014.
The 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)
Unit 2: 1288°F (no change) 2125°F (no change)
The PCT values remain within the 2200°F limit specified in 10 CFR 50.46.
However, because Units 1 and 2 BELOCA have a total PCT margin allocation that is currently greater than 50°F, PG&E had proposed to complete a BELOCA reanalysis and provide the updated PCT results for both Units 1 and 2 to the NRC by December 2016, as stated in PG&E Letter DCL-13-111, "Thirty-Day Notification Report of Significant Emergency Core Cooling System Evaluation Model Changes That Affect Peak Cladding Temperature," dated November 14, 2013. However, in order to schedule compliance with methodology changes to address fuel Thermal Conductivity Degradation, PG&E will complete a reanalysis of both Units 1 and 2 using the Westinghouse FULL SPECTRUM' loss-of-coolant accident (FSLOCA') methodology and provide the updated PCT results to the NRC by December 2018.
1
Attachment A PG&E Letter DCL-15-093 DCPP UNIT 1 PEAK CLADDING TEMPERATURE MARGIN UTILIZATION SMALL-BREAK LOCA PG&E Letter1 A. ANALYSIS OF RECORD PCT= 1391 OF DCL-09-057 B. PRIOR 10 CFR 50.46 ECCS MODEL ASSESSMENTS 2
- 1. None ooF
~Per=
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 Changes ~PCT= ooF E. Analysis of Record PCT (Line A)
+ Line 0.1 Net Sum of 1391 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-15-093 DCPP UNIT 1 PEAK CLADDING TEMPERATURE MARGIN UTILIZATION BELOCA 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 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 71°F DCL-09-057 Generators
- 4. 230 kV Degraded Voltage Event ooF 39°F DCL-11-082
- 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 C. 10 CFR 50.46 ECCS MODEL ASSESSMENTS THIS YEAR
- 1. Error in Burst Strain Application 15°F 40°F DCL-14-070 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 0.1 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.
A-2
Attachment A PG&E Letter DCL-15-093 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-3
Attachment 8 PG&E Letter DCL-15-093 DCPP UNIT 2 PEAK CLADDING TEMPERATURE MARGIN UTILIZATION SBLOCA PG&E Letter1 A." ANALYSIS OF RECORD PCT= 1288°F DCL-08-061 B. PRIOR 10 CFR 50.46 ECCS MODEL ASSESSMENTS 2
- 1. None LlPCT = OoF C. 10 CFR 50.46 ECCS MODEL ASSESSMENTS THIS YEAR
- 1. None ooF LlPCT =
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 = ooF 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.
8-1
Attachment B PG&E Letter DCL-15-093 DCPP UNIT 2 PEAK CLADDING TEMPERATURE MARGIN UTILIZATION BELOCA PG&E Letter1 A. ANALYSIS OF RECORD PCT= 1872oF 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 TCD and Peaking factor ~PCT= 209°F DCL-12-102 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 C. 10 CFR 50.46 ECCS MODEL ASSESSMENTS THIS YEAR
- 1. Error in Burst Strain Application ~PCT= 21oF DCL-14-070 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)+ 2125°F 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.
8-2
Attachment B PG&E Letter DCL-15-093 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-3