Letter Sequence Supplement |
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TAC:ME6360, Allow 7 Day Completion Time for a TURBINE-DRIVEN AFW Pump Inoperable, Provide Actions for One Steam Supply to Turbine Driven Afw/Efw Pump Inoperable, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO (Approved, Closed) |
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MONTHYEARML1120300652011-07-21021 July 2011 Acceptance Review Email, Request to Revise Technical Specifications Related to Auxiliary Feedwater System to Adopt TSTF-245, Rev. 1, TSTF-340, Rev. 3, TSTF-412, Rev. 3, and TSTF-439, Rev. 2 Project stage: Acceptance Review ML1200504882012-01-0505 January 2012 Request for Additional Information, Round 2, Revise Technical Specifications Related to Auxiliary Feedwater System to Adopt TSTF-245, Rev. 1, TSTF 340, Rev. 3, TSTF-412, Rev. 3, and TSTF-439, Rev. 2 (TAC ME6360-ME6361) Project stage: RAI DCL-11-059, Response to NRC Request for Additional Information Regarding PG&E Letter DCL-11-059, License Amendment Request 11-04, Revision to Technical Specification 3.6.6, 'Containment Spray and Cooling Systems,' ...2012-02-0606 February 2012 Response to NRC Request for Additional Information Regarding PG&E Letter DCL-11-059, License Amendment Request 11-04, Revision to Technical Specification 3.6.6, 'Containment Spray and Cooling Systems,' ... Project stage: Response to RAI ML1213607062012-05-21021 May 2012 Memo to File, Summary of 5/11/12 Telephone Conference Issues Associated TSTF-412, Rev. 3 and Effect on Staff Review of Request to Revise Technical Specifications Related to Auxiliary Feedwater System (TAC ME6360-ME6361) Project stage: Approval DCL-12-057, Supplement to PG&E Letter DCL-12-017, Response to NRC Request for Additional Information: NRC Question 12012-05-31031 May 2012 Supplement to PG&E Letter DCL-12-017, Response to NRC Request for Additional Information: NRC Question 1 Project stage: Supplement DCL-12-076, Response to NRC Second Request for Additional Information Regarding PG&E Letter DCL-11-059, License Amendment Request 11-04, Revision to Technical Specification (TS) 3.6.6, 'Containment Spray and Cooling Systems,' Ts..2012-08-0606 August 2012 Response to NRC Second Request for Additional Information Regarding PG&E Letter DCL-11-059, License Amendment Request 11-04, Revision to Technical Specification (TS) 3.6.6, 'Containment Spray and Cooling Systems,' Ts.. Project stage: Request DCL-12-107, Supplement to PG&E Letter DCL-11-059, License Amendment Request 11-04, Revision to Technical Specification (TS) 3.6.6, 'Containment Spray and Cooling Systems,' TS 3.7.5, 'Auxiliary Feedwater (AFW) System,' TS 3.8.1, 'Ac.....2012-11-0101 November 2012 Supplement to PG&E Letter DCL-11-059, License Amendment Request 11-04, Revision to Technical Specification (TS) 3.6.6, 'Containment Spray and Cooling Systems,' TS 3.7.5, 'Auxiliary Feedwater (AFW) System,' TS 3.8.1, 'Ac..... Project stage: Supplement ML12352A0672013-01-31031 January 2013 Issuance of Amendment Nos. 215 and 217, Revise Technical Specifications Related to Auxilary Feedwater System to Adopt TSTF-245, Rev. 1, TSTF-340, Rev. 3, TSTF-412, Rev. 3, and TSTF-439, Rev. 2 Project stage: Approval 2012-02-06
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Category:Letter type:DCL
MONTHYEARDCL-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-24-070, 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-24-010, 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-23-041, 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-23-032, 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-23-038, 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-23-036, 2022 Annual Radiological Environmental Operating Report2023-05-0101 May 2023 2022 Annual Radiological Environmental Operating Report DCL-23-034, 2022 Annual Nonradiological Environmental Operating Report2023-05-0101 May 2023 2022 Annual Nonradiological Environmental Operating Report DCL-23-025, 2022 Annual Radioactive Effluent Release Report2023-05-0101 May 2023 2022 Annual Radioactive Effluent Release Report 2024-08-08
[Table view] Category:Technical Specifications
MONTHYEARML23012A2172023-02-0909 February 2023 Issuance of Amendment Nos. 244 and 245 Revision to Technical Specifications to Adopt TSTF-569, Revision 2, Revise Response Time Testing Definition ML21242A2162022-12-21021 December 2022 Issuance of Amendment Nos. 243 and 244 Technical Specifications and Revised License Conditions for the Permanently Defueled Condition (EPID: L-2020-LLA-0261 DCL-22-059, License Amendment Request 22-03 Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions2022-07-26026 July 2022 License Amendment Request 22-03 Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions ML21188A3452021-07-0808 July 2021 Issuance of Amendment No. 238 Revision to TS 3.7.8, Auxiliary Saltwater (Asw) System (Emergency Circumstances) ML21188A0372021-07-0707 July 2021 Attachment 1 TS_3_7_8 (Marked Up Pages) ML21188A0352021-07-0707 July 2021 Attachment 2 TS_3_7_8 (Retype Pages) ML21188A0342021-07-0707 July 2021 Attachment 3-TS Bases Section 3_7_8 (Marked-up Pages) DCL-19-094, License Amendment Request 19-02 to Relocate Technical Specification 5.3, Unit Staff Qualifications, to the Updated Final Safety Analysis Report2019-12-0505 December 2019 License Amendment Request 19-02 to Relocate Technical Specification 5.3, Unit Staff Qualifications, to the Updated Final Safety Analysis Report DCL-18-100, License Amendment Request 18-02 - License Amendment Request to Revise Technical Specification 5.6.5b1 Core Operating Limits Report (COLR) for Full Spectrum Loss-of-Coolant Accident Methodology2018-12-26026 December 2018 License Amendment Request 18-02 - License Amendment Request to Revise Technical Specification 5.6.5b1 Core Operating Limits Report (COLR) for Full Spectrum Loss-of-Coolant Accident Methodology ML16330A6722017-01-0505 January 2017 Issuance of Amendment Nos. 228 and 230, Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation ML16139A0082016-12-21021 December 2016 Issuance of Amendment Nos. 227 and 229, Digital Replacement of the Process Protection System Portion of the Reactor Protection System and Engineered Safety Features Actuation System ML16035A4412016-04-14014 April 2016 Issuance of Amendment Nos. 225 and 227, Adopt National Fire Protection Association NFPA 805, Performance-Based Standard for Fire Protection for LWR Generating Plants (2001 Edition) ML16083A5642016-03-23023 March 2016 License Amendment Request 16-02, License Amendment Request to Revise Technical Specification 3.4.12., Low Temperature Overpressure Protection (Ltop) System. DCL-16-028, Technical Specifications B.4.17., Steam Generator (SG) Tube Integrity, LTOP Orifice-Key Design Features, and Additional Information2016-03-23023 March 2016 Technical Specifications B.4.17., Steam Generator (SG) Tube Integrity, LTOP Orifice-Key Design Features, and Additional Information ML16055A3592016-03-0909 March 2016 Issuance of Amendment Nos. 224 and 226, Revise Updated Final Safety Analysis Report for Beacon Power Distribution Monitoring System Methodology and TS 5.6.5 (COLR) Paragon and Nexus Methodologies ML16032A0062016-02-19019 February 2016 Redacted, Issuance of Amendment Nos. 223 and 225, Revise UFSAR Section 15.4.2.2 to Incorporate Pressurizer Filling Analysis for Major Rupture of a Main Feedwater Pipe Accident Into Licensing Basis ML15245A5422015-09-30030 September 2015 Issuance of Amendment Nos. 220 and 222, Request to Revise Operating License Condition Related to Cyber Security Plan Milestone H Full Implementation Date ML15204A2222015-08-27027 August 2015 Issuance of Amendment Nos. 219 and 221, Adopt Technical Specifications Task Force Traveler TSTF-432, Revision 1, Change in Technical Specification End States (WCAP-16294) ML15162A8822015-07-0101 July 2015 Issuance of Amendment Nos. 218 and 220, Revise Surveillance Requirements in TS 3.8.1, AC Sources, Related to Diesel Generator Testing DCL-15-052, Response to NRC Request for Additional Information Regarding License Amendment Request 14-01, Revision to Technical Specification 3.8.1, AC Sources - Operating.2015-04-29029 April 2015 Response to NRC Request for Additional Information Regarding License Amendment Request 14-01, Revision to Technical Specification 3.8.1, AC Sources - Operating. ML14042A1932014-02-27027 February 2014 Issuance of Amendment Nos. 217 and 219, Editorial and Clarifying Changes to Technical Specification (TS) 3.7.10, Control Room Ventilation System (CRVS) and TS 5.6.5, Core Operating Limits Report (COLR) (TAC MF1959-MF1960) ML13130A2252013-05-10010 May 2013 Technical Specification 3.5.2 Safety Injection Pump 2-1 Issue Information ML13267A1352013-01-31031 January 2013 Attachment 6 to DCL-13-016, LTR-RAM-1-13-002 NP-Attachment, Revision 0, Justification for the Application of Technical Specifications Changes in WCAP-14333 and WCAP-15376 to the Tricon/Als Process Protection System at the Diablo Canyon Powe DCL-12-107, Supplement to PG&E Letter DCL-11-059, License Amendment Request 11-04, Revision to Technical Specification (TS) 3.6.6, 'Containment Spray and Cooling Systems,' TS 3.7.5, 'Auxiliary Feedwater (AFW) System,' TS 3.8.1, 'Ac.....2012-11-0101 November 2012 Supplement to PG&E Letter DCL-11-059, License Amendment Request 11-04, Revision to Technical Specification (TS) 3.6.6, 'Containment Spray and Cooling Systems,' TS 3.7.5, 'Auxiliary Feedwater (AFW) System,' TS 3.8.1, 'Ac..... DCL-12-057, Supplement to PG&E Letter DCL-12-017, Response to NRC Request for Additional Information: NRC Question 12012-05-31031 May 2012 Supplement to PG&E Letter DCL-12-017, Response to NRC Request for Additional Information: NRC Question 1 DCL-11-097, License Amendment Request 11-05, Evaluation Process for New Seismic Information and Clarifying the Diablo Canyon Power Plant Safe Shutdown Earthquake2011-10-20020 October 2011 License Amendment Request 11-05, Evaluation Process for New Seismic Information and Clarifying the Diablo Canyon Power Plant Safe Shutdown Earthquake DCL-11-059, Diablo Canyon Units 1 & 2, License Amendment Request 11-04, Revision to Technical Specification 3.6.6, Containment Spray and Cooling Systems, TS 3.7.5, Auxiliary Feedwater System, TS 3.8.1, AC Sources-Operating, TS 3.8.9, Distribution Sys2011-06-0101 June 2011 Diablo Canyon Units 1 & 2, License Amendment Request 11-04, Revision to Technical Specification 3.6.6, Containment Spray and Cooling Systems, TS 3.7.5, Auxiliary Feedwater System, TS 3.8.1, AC Sources-Operating, TS 3.8.9, Distribution Syste DCL-11-055, Supplement to License Amendment Request 11-02, Revision to Technical Specification 3.7.1, Main Steam Safety Valves (Mssvs).2011-04-21021 April 2011 Supplement to License Amendment Request 11-02, Revision to Technical Specification 3.7.1, Main Steam Safety Valves (Mssvs). DCL-11-018, License Amendment Request 11-02, Revision to Technical Specification 3.7.1, Main Steam Safety Valves (Mssvs)2011-02-17017 February 2011 License Amendment Request 11-02, Revision to Technical Specification 3.7.1, Main Steam Safety Valves (Mssvs) DCL-10-028, Diablo Canyon, Units 1 and 2, Emergency License Amendment Request 10-02, One Time Revision to Technical Specification 3.8.1, AC Sources - Operating.2010-03-11011 March 2010 Diablo Canyon, Units 1 and 2, Emergency License Amendment Request 10-02, One Time Revision to Technical Specification 3.8.1, AC Sources - Operating. DCL-10-028, Emergency License Amendment Request 10-02, One Time Revision to Technical Specification 3.8.1, AC Sources - Operating.2010-03-11011 March 2010 Emergency License Amendment Request 10-02, One Time Revision to Technical Specification 3.8.1, AC Sources - Operating. DCL-10-018, License Amendment Request 10-01, Revision to Technical Specification 3.8.1, AC Sources - Operating.2010-02-24024 February 2010 License Amendment Request 10-01, Revision to Technical Specification 3.8.1, AC Sources - Operating. DCL-09-062, Emergency License Amendment Request 09-04 Revision to Technical Specification 3.7.1, Main Steam Safety Valves (Mssvs) for Unit 2 Cycle 15.2009-09-0303 September 2009 Emergency License Amendment Request 09-04 Revision to Technical Specification 3.7.1, Main Steam Safety Valves (Mssvs) for Unit 2 Cycle 15. ML0919601772009-07-0303 July 2009 License Amendment Request 09-02, Revision to Technical Specification 3.4.15, RCS Leakage Detection Instrumentation, Operability Requirements and Actions for RCS Leakage Detection Instrumentation DCL-09-009, License Amendment Request 09-01 - Revision to Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation, Deletion of the High Negative Rate Trip Function2009-02-24024 February 2009 License Amendment Request 09-01 - Revision to Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation, Deletion of the High Negative Rate Trip Function DCL-08-100, Supplement to License Amendment Request 07-03, Revision to Technical Specification 3.7.10, Control Room Ventilation System (CRVS)2008-11-25025 November 2008 Supplement to License Amendment Request 07-03, Revision to Technical Specification 3.7.10, Control Room Ventilation System (CRVS) ML0824102622008-10-30030 October 2008 Issuance of Amendment Nos. 200 and 201, Technical Specifications Change to Relocate Surveillance Test Intervals to a Licensee-Controlled Program (Risk-Informed Initiative 5b) DCL-07-097, License Amendment Request 07-04, Proposed Technical Specifications Change to Relocate Surveillance Test Intervals to a Licensee-Controlled Program (Risk Informed Technical Specifications Initiative 5b)2007-10-15015 October 2007 License Amendment Request 07-04, Proposed Technical Specifications Change to Relocate Surveillance Test Intervals to a Licensee-Controlled Program (Risk Informed Technical Specifications Initiative 5b) DCL-07-075, Supplement to License Amendment Request 07-01, Revision to Technical Specifications to Support Steam Generator Replacement, and Response to Request for Additional Information2007-08-0909 August 2007 Supplement to License Amendment Request 07-01, Revision to Technical Specifications to Support Steam Generator Replacement, and Response to Request for Additional Information ML0713707332007-06-26026 June 2007 Tech Spec Pages for Amendment Nos. 197 and 198 TS 5.5.16, Containment Leakage Rate Testing Program, for Consistency with 10 CFR 50.55a(g)(4) ML0709900742007-06-25025 June 2007 Units, 1 and 2, Tech Spec Page for Amendments 196 and 197 Administrative Changes to the Technical Specification 5.5.8, Inservice Testing Program. ML0703500522007-04-17017 April 2007 Tech Spec Pages for Amendment Nos. 195 and 196 TS 3.4.1 Reactor Coolant System Pressure, Temperature, & Flow Departure from Nucleate Boiling Limits & TS 5.6.5 Core Operating Limits Report. ML0704404942007-03-21021 March 2007 Tech Spec Pages for Amendments 194 and 195 Regarding Steam Generator Tube Integrity Technical Specifications ML0701902142007-01-19019 January 2007 Units, 1 and 2 - Tech Spec Pages for Amendments 192 and 193 Technical Specification 1.1 Definitions and Technical Specification 3.4.16 Reactor Coolant System Specific Activity DCL-06-143, License Amendment Request 06-10 Revision to Technical Specification 5.5.8, Inservice Testing Program2006-12-29029 December 2006 License Amendment Request 06-10 Revision to Technical Specification 5.5.8, Inservice Testing Program DCL-06-136, License Amendment Request 06-05 Revision to Technical Specification 3.4.1, Reactor Coolant System Pressure, Temperature, and Flow Departure from Nucleate Boiling Limits, and Technical Specification 5.6.5, Core Operating....2006-12-29029 December 2006 License Amendment Request 06-05 Revision to Technical Specification 3.4.1, Reactor Coolant System Pressure, Temperature, and Flow Departure from Nucleate Boiling Limits, and Technical Specification 5.6.5, Core Operating.... DCL-06-142, License Amendment Request 06-09, Revision to Technical Specification 5.5.16, Containment Leakage Rate Testing Program (TSTF-343)2006-12-29029 December 2006 License Amendment Request 06-09, Revision to Technical Specification 5.5.16, Containment Leakage Rate Testing Program (TSTF-343) ML0635500312006-12-20020 December 2006 Tech Spec Pages for Amendment 192 Regarding TS 5.6.5, Core Operating Limits Report. DCL-06-129, Special Report 06-03 - 180 Day Report for Steam Generator Technical Specification Task Force 449, Thirteenth Refueling Outage2006-11-17017 November 2006 Special Report 06-03 - 180 Day Report for Steam Generator Technical Specification Task Force 449, Thirteenth Refueling Outage ML0631905402006-11-15015 November 2006 Technical Specifications, Issuance of Exigent Amendment No. 190 Revision to TS Section 3.8.4, DC Sources - Operating to Extend the Completion Time to Restore an Inoperable Station Battery 2023-02-09
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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 May 31,2012 Fax: 805.545.6445 PG&E Letter DCL-12-057 u.s. Nuclear Regulatory Commission 10 CFR 50.90 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 Supplement to PG&E Letter DCL-12-017. Response to NRC Request for Additional Information: NRC Question 1
References:
- 1. PG&E Letter DCL-11-059, "License Amendment Request 11-04, Revision to Technical Specification (TS) 3.6.6, 'Containment Spray and Cooling Systems,' TS 3.7.5, 'Auxiliary Feedwater (AFW)
System,' TS 3.8.1, 'AC Sources - Operating,' TS 3.8.9, 'Distribution Systems - Operating,' and TS Example 1.3-3," dated June 1, 2011
- 2. PG&E Letter DCL-12-017, Response to NRC Request for Additional Information Regarding PG&E Letter DCL-11-059, "License Amendment Request 11-04, Revision to Technical Specification (TS) 3.6.6, 'Containment Spray and Cooling Systems,' TS 3.7.5, 'Auxiliary Feedwater (AFW) System,' TS 3.8.1,
'AC Sources - Operating,' TS 3.8.9, 'Distribution Systems -
Operating,' and TS Example 1.3-3," dated February 6, 2012 In Reference 1, Pacific Gas and Electric Company (PG&E) submitted a license amendment request to revise Technical Specification (TS) 3.6.6, "Containment Spray and Cooling Systems," TS 3.7.5, "Auxiliary Feedwater (AFW) System," TS 3.8.1, "AC Sources - Operating," TS 3.8.9, "Distribution Systems - Operating," and TS Example 1.3-3.
The NRC staff provided a request for additional information (RAI) via e-mail, dated January 5, 2012. PG&E provided a response to the RAI in Reference 2. The Enclosure to this letter provides a supplement to the Reference 2 response to NRC RAI question 1.
PG&E makes no regulatory commitments (as defined by NEI 99-04) in this letter.
If you have any questions or require additional information, please contact Mr. Tom Baldwin at (805) 545-4720.
A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway. Comanche Peak. Diablo Canyon
- South Texas Project. Wolf Creek
__ Document Control Desk PG&E Letter DCL-12-057
~&~ May 31,2012 I & Page 2 I state under penalty of perjury that the foregoing is true and correct.
Executed on May 31,2012.
Si~CereIY, "
~> ~2--=------*~
Jam-e J:<.Becke~ -,.--
Site Vice President Mjrm/4557/50329767 Enclosure cc: Diablo Distribution cc/enc: Elmo E. Collins, NRC Region IV Michael S. Peck, NRC Senior Resident Inspector Joseph M. Sebrosky, NRR Project Manager A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway
Enclosure PG&E Letter DCL-12-057 Supplement to PG&E Letter DCL-12-017 Response to NRC Request for Additional Information: NRC Question 1
References:
- 1. PG&E Letter DCL-11-059, "License Amendment Request 11-04, Revision to Technical Specification (TS) 3.6.6, 'Containment Spray and Cooling Systems,' TS 3.7.5, 'Auxiliary Feedwater (AFW) System,'
TS 3.8.1, 'AC Sources - Operating,' TS 3.8.9, 'Distribution Systems -
Operating,' and TS Example 1.3-3," dated June 1, 2011
- 2. PG&E Letter DCL-12-017, Response to NRC Request for Additional Information Regarding PG&E Letter DCL-11-059, "License Amendment Request 11-04, Revision to Technical Specification (TS) 3.6.6, 'Containment Spray and Cooling Systems,' TS 3.7.5, 'Auxiliary Feedwater (AFW) System,' TS 3.8.1, 'AC Sources - Operating,' TS 3.8.9, 'Distribution Systems - Operating,' and TS Example 1.3-3,"
dated February 6,2012 In Reference 1, Pacific Gas and Electric Company (PG&E) submitted a license amendment request that proposed changes to several technical specifications (TSs) including changes to TS 3.7.5, "Auxiliary Feedwater (AFW) System." The license amendment request included changes to be consistent with TSTF traveler 412, Revision 3, "Allow 7 Day Completion Time for a Turbine-driven AFW Pump Inoperable."
During a public meeting on May 8, 2012, TSTF traveler 412 was discussed, including the NRC staff's issues associated with the portion of the TSTF traveler associated with a provision for 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> completion time for an inoperable motor-driven AFW pump coincident with one inoperable steam supply to the steam-driven AFW pump. The NRC staff's issues are documented in an April 12, 2012, memorandum from Greg Casto to Robert Elliot (ADAMS Accession No. ML121030032).
Because of the issues with TSTF traveler 412 identified during the May 8, 2012, meeting and in the April 12, 2012, letter, PG&E is proposing to amend the response provided to NRC question number 1 in Reference 2.
NRC Question 1:
On page 8 of the application letter dated June 1, 2011, the licensee, PG&E, states, "under the scenario with one steam supply for the turbine-driven auxiliary feedwater pump (TDAFWP) inoperable and one motor-driven auxiliary feedwater pump (MDAFWP) inoperable, a feed line or steam line rupture could challenge the capability of the auxiliary feedwater (AFW) system to provide feedwater." The staff is evaluating conditions of the plant during scenarios such as a feedwater line break (FWLB) or a main steamline break (MSLB) on steam generator (SG) 3 occurs when the MDAFWP 1-2 for SG1 and SG2 is inoperable and the steam supply from SG2 to the TDAFWP is inoperable. This scenario would leave only SG4 supplied by MDAFWP 1-3 available. In final safety analysis report (FSAR) Table 6.5-2, the licensee requires a minimum of 390 gpm auxiliary feedwater (AFW) flow to 2 of the 4 intact SGs to mitigate a main feed line 1
Enclosure PG&E Letter DCL-12-057 break. Therefore, in such scenarios the licensee would not meet the design requirement as stipulated in their design basis to mitigate an accident. Hence, the request to continue operations for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> with one steam supply inoperable coincident with an inoperable motor driven pump may result in such postulated scenario that is beyond the current analyzed design basis.
In its draft safety evaluation reporl (SER) for TSTF-412, dated April 14, 2006, the staff considered the possible credit for operators having the ability to remotely feed other SGs from the control room using the operable MDAFWP. Figure 1 in the letter dated June 1, 2011, does show a possible cross tie line between the discharge headers of MDAFWP's. However, in their application the licensee does not mention using the cross tie line to mitigate accidents when the plant is in a degraded condition.
The staff requests the licensee to justify their proposed TS that allows for continued operations for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in conditions that result in an unanalyzed condition. Note: the licensee can limit the proposed condition, where the inoperable steam supply could only exist on the SG that can be fed by the operable MDAFWP.
PG&E Revised Response:
The NRC staff had included the following note in question 1:
"the licensee can limit the proposed condition, where the inoperable steam supply could only exist on the SG that can be fed by the operable MDAFWP."
PG&E is proposing to remove the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> limiting condition for operation (LCO) in accordance with the above note and replace it with a 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> LCO when the conditions in the above note are met.
PG&E included the following in Reference 1.
INSERT 3 D. Turbine driven AFW tra in D.1 Restore the steam 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> inoperable due to one supply to the turbine inoperable steam supply. driven train to OPERABLE status.
AND OR One motor driven AFW 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> train inoperable. 0.2 Restore the motor driven AFW train to OPERABLE status.
PG&E is proposing the following revision to Reference 1 INSERT 3 as follows:
2
Enclosure PG&E Letter OCL-12-057 O. --------------~()lrE------------- 0.1 Restore the steam 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> supply to the turbine
()nly applicable when the driven train to remaining ()PERABLE
()PERABLE status.
motor driven AFW train provides feedwater to the steam generator with the 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> inoperable steam supply.
0.2 Restore the motor driven AFW train to ()PERABLE lrurbine driven AFW train status.
inoperable due to one inoperable steam supply.
()ne motor driven AFW train inoperable. to the enclosure provides retyped lrS pages (Condition E moved to page 3.7-11). Attachment 2 to the enclosure provides a revised markup to the lrS bases (included for information only).
lrhe revised lrS bases markup includes the following:
With one of the required motor-driven AFW trains (pump or flow path) inoperable and the turbine-driven AFW train inoperable due to one inoperable steam supply, action must be taken to restore the affected equipment to
()PERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. Assuming no single active failures when in this condition, the accident (a FWLB or MSLB) could result in the loss of the remaining steam supply to the turbine-driven AFW pump due to the faulted SG.
A note in Condition 0 limits applicability to only when the remaining ()PERABLE motor-driven AFW train provides feedwater to the SG with the inoperable steam supply. lrhis Condition will only apply during the following two scenarios:
- 1) Motor-driven AFW pump 2 ()PERABLE, motor-driven AFW pump 3 inoperable, and steam supply from SG 2 inoperable, or
- 2) Motor-driven AFW pump 2 inoperable, motor-driven AFW pump 3
()PERABLE, and steam supply from SG 3 inoperable.
lrhis ensures that if a FWLB were to occur affecting the ()PERABLE motor driven AFW pump, the turbine-driven AFW pump would still be capable of providing AFW to two intact SGs. If a MSLB were to occur on the SG feeding the remaining ()PERABLE steam supply to the turbine-driven AFW pump, the 3
Enclosure PG&E Letter DCL-12-057 OPERABLE motor-driven AFW pump would still be capable of providing AFW to two intact SGs.
If motor-driven AFW pump 2 and the steam supply from SG 3 are inoperable, or if motor-driven AFW pump 3 and the steam supply from SG 2 are inoperable, then Condition E for two inoperable AFW pumps applies.
The 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> Completion Time is reasonable based on the fact that the remaining motor-driven AFW train is capable of providing 100 percent of the AFW flow requirements, and the low probability of an event occurring that would challenge the AFW system.
The proposed changes do not affect the basis for or conclusions of the no significant hazards consideration determination of Reference 1.
4
Enclosure Attachment 1 PG&E Letter DCL-12-057 Revised TS Retype Pages (replace pages 3.7-1 Oa and 3.7-11 previously submitted in DCL-11-059) 1
AFW System 3.7.5 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME B. One or more motor driven B.1 -----------NOTE-------------
AFW trains with automatic No change in valve control of one motor driven demand is required if AFW level control valve per AFW is being relied train inoperable. upon for SG level control.
Place affected AFW Immediately level control valve(s) in manual control with valve demand full open.
OR B.2 Declare the associated Immediately AFW train inoperable.
C. One AFW train inoperable C.1 Restore AFW train to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> I in MODE 1, 2 or 3 for OPERABLE status.
reasons other than
-1 Condition A.
D. --------------NOTE-------------- 0.1 Restore the steam 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> Only applicable when the supply to the turbine remaining OPERABLE driven train to motor driven AFW train OPERABLE status.
provides feedwater to the OR steam generator with the inoperable steam supply. 0.2 Restore the motor driven 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />
AFW train to Turbine driven AFW train OPERABLE status.
inoperable due to one inoperable steam supply.
AND One motor driven AFW train inoperable.
(continued)
DIABLO CANYON - UNITS 1 & 2 3.7-10a Unit 1 - Amendment No. ~,4a9, Unit 2 - Amendment No. ~,4+Q,
AFW System 3.7.5 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME E. Required Action and E.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion AND Time of Condition A, C, or D not met. 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> E.2 Be in MODE 4.
OR Two AFW trains inoperable in MODE 1, 2 or 3 for reasons other than Condition D.
F. Three AFW trains F.1 -----------NOTE ---------------
inoperable in MODE 1, 2, or LCO 3.0.3 and all other
- 3. LCO Required Actions requiring MODE changes are suspended until one AFW train is restored to OPERABLE status.
Initiate action to restore Immediately one AFW train to OPERABLE status G. Required AFW train G.1 Initiate action to restore Immediately inoperable in MODE 4. AFW train to OPERABLE status.
DIABLO CANYON - UNITS 1 & 2 3.7-11 Unit 1 - Amendment No. ~,
Unit 2 - Amendment No. ~,
Enclosure Attachment 2 PG&E Letter DCL-12-057 Revised TS Bases Markup Page (for information only) 1
AFW System B 3.7.5 the more restrictive must be met.
0.1 and 0.2 With one of the required motor driven AFW trains (pump or flow path) inoperable and the turbine driven AFW train inoperable due to one inoperable steam supply, action must be taken to restore the affected equipment to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. Assuming no single active failures when in this condition, the accident (a FLB or MSLB) could result in the loss of the remaining steam supply to the turbine driven AFW pump due to the faulted SG.
A note in Condition 0 limits applicability to only when the remaining OPERABLE motor driven AFW train provides feedwater to the steam generator with the inoperable steam supply. This Condition will only apply during the following two scenarios:
- 1) Motor driven AFW pump 2 OPERABLE, motor driven AFW pump 3 inoperable, and steam supply from SG 2 inoperable, or
- 2) Motor driven AFW pump 2 inoperable, motor driven AFW pump 3 OPERABLE, and steam supply from SG 3 inoperable.
This ensures that if a FLB were to occur affecting the OPERABLE motor driven AFW pump, the turbine driven AFW pump would still be capable of providing AFW to two intact steam generators. If a MSLB were to occur on the SG feeding the remaining OPERABLE steam supply to the turbine driven AFW pump, the OPERABLE motor driven AFW pump would still be capable of providing AFW to two intact steam generators.
If motor driven AFW pump 2 and the steam supply from SG 2 are inoperable, or if motor driven AFW pump 3 and the steam supply from SG 3 are inoperable, then Condition E for two inoperable AFW pumps applies.
The 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> Completion Time is reasonable based on the fact that the remaining motor driven AFW train is capable of providing 100 % of the AFW flow requirements, and the low probability of an event occurring that would challenge the AFW system.
In MODE 4 with two AFW trains inoperable, operation is allowed to continue because only one motor driven pump AFW train is required in accordance with the Note that modifies the LCO. Although not required, the unit may continue to cool down and initiate RHR.
(continued)
DIABLO CANYON - UNITS 1 & 2 Revision 6