DCL-19-025, Independent Spent Fuel Storage Installation - Emergency Plan Update

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Independent Spent Fuel Storage Installation - Emergency Plan Update
ML19094B868
Person / Time
Site: Diablo Canyon  Pacific Gas & Electric icon.png
Issue date: 04/04/2019
From: Welsch J
Pacific Gas & Electric Co
To:
Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
DCL-19-025, DIL-19-007
Download: ML19094B868 (10)
v • d • e


Text

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

  • Diablo Canyon
  • Palo Verde
  • Wolf Creek

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

  • Diablo Canyon
  • Palo Verde
  • Wolf Creek

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
  • Section 9 - Recovery
  • Section 10 - References
  • Appendix A - Procedures
  • 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.

Page 1 of 5

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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