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Category:Emergency Preparedness-Emergency Plan
MONTHYEARDCL-23-128, Emergency Plan Update2023-12-13013 December 2023 Emergency Plan Update DCL-23-021, Independent Spent Fuel Storage Installation, Emergency Plan Update2023-03-23023 March 2023 Independent Spent Fuel Storage Installation, Emergency Plan Update DCL-22-052, Emergency Plan Update2022-07-0606 July 2022 Emergency Plan Update DCL-22-018, Independent Spent Fuel Storage Installation Responses to NRC Requests for Additional Information on License Amendment Request 21-04, Proposed Changes to the Emergency Plan for Post-Shutdown and Permanently.2022-03-23023 March 2022 Independent Spent Fuel Storage Installation Responses to NRC Requests for Additional Information on License Amendment Request 21-04, Proposed Changes to the Emergency Plan for Post-Shutdown and Permanently. DCL-22-015, Independent Spent Fuel Storage Installation - Emergency Plan Implementing Procedure Update2022-03-16016 March 2022 Independent Spent Fuel Storage Installation - Emergency Plan Implementing Procedure Update DCL-21-012, Spent Fuel Storage Installation, Emergency Plan Update2021-02-0303 February 2021 Spent Fuel Storage Installation, Emergency Plan Update DCL-20-053, Independent Spent Fuel Storage Installation Emergency Plan Update2020-07-0101 July 2020 Independent Spent Fuel Storage Installation Emergency Plan Update DCL-19-025, Independent Spent Fuel Storage Installation - Emergency Plan Update2019-04-0404 April 2019 Independent Spent Fuel Storage Installation - Emergency Plan Update DCL-18-064, Request to Revise Emergency Plan Response Organization Staffing and Augmentation2018-09-12012 September 2018 Request to Revise Emergency Plan Response Organization Staffing and Augmentation ML18340A0432018-08-31031 August 2018 San Luis Obispo County/Cities - Nuclear Power Plant Emergency Response Plan DCL-18-044, Independent Spent Fuel Storage Installation - Emergency Plan Update2018-06-13013 June 2018 Independent Spent Fuel Storage Installation - Emergency Plan Update DCL-17-080, Emergency Plan Update for Appendix D Bases. Introduction. Category C. and Category s and Sections 10, 8, 4, and 22017-09-20020 September 2017 Emergency Plan Update for Appendix D Bases. Introduction. Category C. and Category s and Sections 10, 8, 4, and 2 DCL-17-044, ISFSI - Emergency Plan Update for Appendix D Category H, Appendix F, Section 5 and Coversheet2017-05-12012 May 2017 ISFSI - Emergency Plan Update for Appendix D Category H, Appendix F, Section 5 and Coversheet DCL-16-103, Independent Spent Fuel Storage Installation Emergency Plan Section 8 Update2016-10-12012 October 2016 Independent Spent Fuel Storage Installation Emergency Plan Section 8 Update DCL-16-004, Diablo Canyon, Units 1 and 2 - Revisions to Emergency Plan (Enclosures 4, 5, 6, 7, 8, 9 & 10)2016-01-0606 January 2016 Diablo Canyon, Units 1 and 2 - Revisions to Emergency Plan (Enclosures 4, 5, 6, 7, 8, 9 & 10) ML16021A2802016-01-0606 January 2016 Revisions to Emergency Plan (Enclosures 4, 5, 6, 7, 8, 9 & 10) DCL-09-044, Emergency Plan Update2009-06-22022 June 2009 Emergency Plan Update DCL-04-033, Emergency Plan, Revision 4, Section 5, Change 5: Sections 4 and 7, Change 4: Section 6, Change 3: Sections 1. 2 and 8, Change 2: and Appendix A. Change 12004-03-29029 March 2004 Emergency Plan, Revision 4, Section 5, Change 5: Sections 4 and 7, Change 4: Section 6, Change 3: Sections 1. 2 and 8, Change 2: and Appendix A. Change 1 2023-03-23
[Table view] 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
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Pacific Gas and Electric Company James M. Welsch Oiablo 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 April 4, 2019 PG&E Letter DCL-19-025 PG&E Letter DIL-19-007 U.S. Nuclear Regulatory Commission 10 CFR 50.54 ATTN: Document Control Desk 10 CFR 72.32 Washington, DC 20555-0001 10 CFR 72.44(f)
Director, Division of Spent Fuel Management Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Washington, DC 20555-001 Docket No. 50-275, OL-DPR-80 Docket No. 50-323, OL-DPR-82 Diablo Canyon Units 1 and 2 Docket No. 72-26, Materials License No. SNM-2511 Diablo Canyon Independent Spent Fuel Storage Installation Emergency Plan Update
Dear Commissioners and Staff:
In accordance with the requirements of 10 CFR 50.54, 10 CFR 72.32, and 10 CFR 72.44(f), Pacific Gas and Electric Company (PG&E) is providing a summary of the analysis of changes to the Emergency Plan (E-Plan) in the associated enclosures listed below:
- Enclosure 1 - Diablo Canyon Power Plant Emergency Plan Table of Contents
- Enclosure 2 - Summary of the Analysis of Changes in Emergency Plan Appendix F, Revision 4.07, "ERO On-Shift Staffing Analysis Report" PG&E evaluated the changes for a reduction in effectiveness, as described in 10 CFR 50.54(q), and concluded that the changes do not reduce the effectiveness of the E-Plan. The E-Plan continues to meet the requirements in Appendix E of 10 CFR 50 and the standards of 10 CFR 50.47(b). Therefore, PG&E concluded that prior NRC approval of the associated changes was not required.
This update does not contain any privacy or proprietary information in accordance with NRC Generic Letter 81-27, "Privacy and Proprietary Material in Emergency Plans."
A member of the STARS Alliance Callaway
Document Control Desk PG&E Letter DCL-19-025 April 4, 2019 PG&E Letter DIL-19-007 Page 2 PG&E makes no new or revised regulatory commitments (as defined by NEI 99-04) in this letter.
If there are questions regarding this update, please contact Mr. Michael Ginn, Manager, Nuclear Emergency Planning at (805) 545-3446.
Sincerely, J~-~~
Vice President Nuclear Generation and Chief Nuclear Officer armb/4743/51022205 Enclosures cc/enc: William C. Allen, P.E., NMSS Project Manager Scott A. Morris, NRC Region IV Administrator Christopher W. Newport, NRC Senior Resident Inspector Balwant K. Singal, NRC Senior Project Manager Senior Emergency Preparedness Inspector (RGN-IV/DR)
A member of the STARS Alliance Callaway
Enclosure 1 PG&E Letter DCL-19-025 PG&E Letter DIL-19-007 DIABLO CANYON POWER PLANT EMERGENCY PLAN Table of Contents
Enclosure 1 PG&E Letter DCL-19-025 PG&E LetterDIL-19-007 Diablo Canyon Power Plant Emergency Plan Table of Contents
- Section 1 - Definitions & Abbreviations
- Section 2 - Scope and Applicability
- Section 4 - Emergency Conditions
- Section 5 - Organizational Control of Emergencies
- Section 6 - Emergency Measures
- Section 7 - Emergency Facilities and Equipment
- Appendix B - Offsite Agency Support Documentation
- Appendix D - Emergency Action Level Technical Basis Manual
- Appendix E - Evacuation Time Estimates
- Appendix F* - ERO On-Shift Staffing Analysis Report
- Appendix G - Protective Action Recommendation (PAR) Strategy Bases
- Revised Document Page 1 of 1
Enclosure 2 PG&E Letter DCL-19-025 PG&E Letter DIL-19-007 Summary of the Analysis of Changes in Emergency Plan Appendix F, Revision 4.07 "ERO On-Shift Staffing Analysis Report"
Enclosure 2 PG&E Letter DCL-19-025 PG&E Letter DIL-19-007 Summar~ of the Anal~sis of Changes in Emergenc~ Plan AQQendix Fz Revision 4.07 Change Original Content (Revision 4.06) Revised Content (Revision 4.07) Description of Change 1 3.2.15 3.2.15 Modified content.
Task 274961, implement transition from Task 274961, implement transition from Editorial change to update the procedure the EOP's to SACRG-1 and SAMG the EOP's to SAG 01 and SAMG training title of the Control Room's entry point into training (which includes classroom and (which includes classroom and simulator Severe Accident Mitigation Guidelines simulator training) is given in licensed training) is given in licensed operator (SAMGs) from SACRG-01 to SAG 01.
operator continuing training on a four continuing training on a four year year frequency. None of the UFSAR frequency. None of the UFSAR limiting Diablo Canyon Power Plant (DCPP) limiting fault events result in entry fault events result in entry conditions into rewrote all of the SAMGs to align with the conditions into SAMG procedures prior SAMG procedures prior to the ERO latest pressurized water reactor (PWR) to the ERO augmentation. Entry augmentation. Entry conditions into owner's group guidance. This resulted in conditions into SAMG procedures for all SAMG procedures for all of the other a reorganization of the content of the of the other events analyzed, with the events analyzed, with the exception of SAMGs and changes in the titles of the exception of the event established to the event established to artificially guidelines.
artificially exceed PAGs, are not exceed PAGs, are not expected to occur expected to occur until after the until after the augmenting ERO has The overall changes to the SAMGs were augmenting ERO has responded. DCPP responded. DCPP SAG 01 entry fully evaluated under 50.54(q) 2018-97.
SACRG-1 entry conditions are as conditions are as follows:
follows: This change does not affect how the current Emergency Plan (E-Plan) meets any planning standard functions, elements, or site-specific commitments. No additional evaluation required.
2 Table 3-1 : Analysis #15 - SAMG Table 3-1: Analysis #15 - SAMG Modified content.
Reference Document(s) Reference Document(s) Editorial change to update the procedure title of the Control Room's entry point into SACRG-1 SAG 01 SAMGs from SACRG-01 to SAG 01.
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Enclosure 2 PG&E Letter DCL-19-025 PG&E Letter DIL-19-007 Summarv of the Anal~sis of Changes in Emergenc~ Plan A~~endix F 2 Revision 4.07 Change Original Content (Revision 4.06) Revised Content (Revision 4.07) Description of Change DCPP rewrote all of the SAMGs to align with the latest PWR owner's group guidance. This resulted in a reorganization of the content of the SAMGs and changes in the titles of the guidelines.
The overall changes to the SAMGs were fully evaluated under 50.54(q) 2018-97.
This change does not affect how the current E-Plan meets any planning standard functions, elements, or site-specific commitments. No additional evaluation required.
3 3.5.1 - Procedures Used 3.5.1 - Procedures Used Modified content.
RCP D-220 RCP NISP-RP.05 The decision to transition to the Nuclear RCP D-240 RCP NISP-RP.04 Industry Standard Process (NISP) format resulted in the need to update procedure 3.5.3 - Procedures Used 3.5.3 - Procedures Used titles in Appendix F to replace the old DCPP procedure titles with the new NISP RCP D-220 RCP NISP-RP.05 title.
RCP D-240 RCP NISP-RP.04 The scopes of the NISPs are the same 3.5.6 - Procedures Used 3.5.6 - Procedures Used as the scopes of RCP D-220, RCP D-240, and RCP D-500 which they replace.
RCP D-500 RCP NISP-RP.02 The procedures describe the processes for personnel contamination monitoring 3.5.7 - Procedures Used 3.5.7 - Procedures Used and decontamination, radiation and contamination surveys, radiological RCP D-500 RCP NISP-RP.02 Page 2 of 5
Enclosure 2 PG&E Letter DCL-19-025 PG&E Letter DIL-19-007 Summarl of the Anal~sis of Changes in Emergenc~ Plan AQQendix Fz Revision 4.07 Change Original Content (Revision 4.06) Revised Content (Revision 4.07) Description of Change posting and labeling, and access control for high radiation areas.
The NISPs also include all DCPP site 3.5.8 - Procedures Used 3.5.8- Procedures Used specific instructions to ensure that all unique processes at DCPP are RCP D-500 RCP NISP-RP.02 adequately described.
Table 3-2: Event Procedures Table 3-2: Event Procedures The E-Plan generically describes the methods and processes used for RCP D-220 RCP NISP-RP.05 personnel monitoring and RCP D-240 RCP NISP-RP.04 decontamination, authorizing emergency RCP D-500 RCP NISP-RP.02 exposure limits and posting and labeling radiological areas, and controlling access 6.56 6.53 to high radiation areas. The E-Plan states that radiation control standards RCP D-500, Routine and Job Coverage RCP NISP-RP.02, Radiation and used during normal operations would be Surveys Contamination Surveys used during an emergency as well.
6.53 6.54 The proposed activity updates these radiation control standards to the current RCP D-240, Radiological Posting RCP NISP-RP.04, Radiological Posting industry acceptable methods and and Labeling processes.
6.52 6.55 The title changes have no impact on the assignment of on-shift staff resources or RCP D-220, Control of Access to High, RCP NISP-RP.05, Access Controls for capabilities as described in Appendix F.
Locked High, and Very High Radiation High Radiation Areas Areas This change does not affect how the 6.57 6.56 current E-Plan meets any planning standard functions, elements, or site-RCP NISP RP.06, Personnel RCP NISP-RP.06, Personnel Decontamination and Evaluation Contamination Monitoring Page 3 of 5
Enclosure 2 PG&E Letter DCL-19-025 PG&E Letter DIL-19-007 Summary of the Analysis of Changes in Emergency Plan Appendix F, Revision 4.07 Change Original Content (Revision 4.06) Revised Content (Revision 4.07) Description of Change specific commitments. No additional evaluation required.
4 3.5.12: Procedures Used N/A- Content removed Removed content.
CP M-10 Removed reference to Casualty Procedure CP M-10, "Fire Protection of Table 3-2: Event Procedures Safe Shutdown Equipment," as it was rescinded as part of the National Fire CP M-10 Protection Association (NFPA) 805 implementation at DCPP under License 6.14 Amendments 225 and 227.
CP M-10, Fire Protection of Safe CP M-10 was used in the station Shutdown Equipment blackout (SBO) scenario in Appendix F.
The applicable action in CP M-10 for the SBO event was to control heat buildup in vital areas. Guidance for this task was added to Emergency Operating Procedure EOP ECA-0.0, "Loss of Vital AC Power," in Attachment 1. ECA-0.0 is already identified in Appendix Funder the SBO event as an applicable procedure.
50.54(q) 2017-12 evaluated the impacts on the E-Plan of transitioning to NFPA 805 including a revalidation of the shift staffing analysis (Revision 4.05 of Appendix F). At the time 50.54(q) 2017-12 was performed CP M-10 had not yet been rescinded, which is why Revision Page 4 of 5
Enclosure 2 PG&E Letter DCL-19-025 PG&E Letter DIL-19-007 SummarY of the Anal~sis of Changes in Emergenc~ Plan A~~endix F 1 Revision 4.07
,Change Original Content (Revision 4.06)
- Revised Content (Revision 4.07) Description of Change 4.05 of Appendix F did not include the removal of CP M-10.
The updated staffing analysis that was done as part of the Revision 4.05 change to Appendix F included the use of the updated EOP ECA-0.0 and concluded that no new task overlaps were created for applicable scenarios evaluated under Appendix F.
This change does not affect how the current E-Plan meets any planning standard functions, elements, or site-specific commitments. No additional evaluation required.
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