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| | issue date = 01/24/2018 | | | issue date = 01/24/2018 |
| | title = DCPP - Inspection of the Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communication/Staffing/ Multi Unit Dose Assessment Plans - Inspection Report (05000275/2017007 and 050003 | | | title = DCPP - Inspection of the Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communication/Staffing/ Multi Unit Dose Assessment Plans - Inspection Report (05000275/2017007 and 050003 |
| | author name = Haire M S | | | author name = Haire M |
| | author affiliation = NRC/RGN-IV/DRP/RPB-A | | | author affiliation = NRC/RGN-IV/DRP/RPB-A |
| | addressee name = Welsch J M | | | addressee name = Welsch J |
| | addressee affiliation = Pacific Gas & Electric Co | | | addressee affiliation = Pacific Gas & Electric Co |
| | docket = 05000275, 05000323 | | | docket = 05000275, 05000323 |
| | license number = DPR-080, DPR-082 | | | license number = DPR-080, DPR-082 |
| | contact person = Haire M S | | | contact person = Haire M |
| | document report number = IR 2017007 | | | document report number = IR 2017007 |
| | document type = Inspection Report, Letter | | | document type = Inspection Report, Letter |
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| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION IV 1600 E. LAMAR BLVD | | {{#Wiki_filter:January 24, 2018 |
| . ARLINGTON, TX 76011
| | |
| -4511 January 24, 2018 Mr. James M. Welsch, Vice President, Nuclear Generation and Chief Nuclear Officer Pacific Gas and Electric Company Diablo Canyon Power Plant P.O. Box 56, Mail Code 104/6 Avila Beach, CA 93424 SUBJECT: DIABLO CANYON POWER PLANT, UNITS 1 AND 2
| | ==SUBJECT:== |
| - INSPECTION OF THE IMPLEMENTATION OF MITIGATION STRATEGIES AND SPENT FUEL POOL INSTRUMENTATION ORDERS AND EMERGENCY PREPAREDNESS COMMUNICATION/STAFFING/ MULTI | | DIABLO CANYON POWER PLANT, UNITS 1 AND 2 |
| -UNIT DOSE ASSESSMENT PLANS | | - INSPECTION OF THE IMPLEMENTATION OF MITIGATION STRATEGIES AND SPENT FUEL POOL INSTRUMENTATION ORDERS AND EMERGENCY PREPAREDNESS COMMUNICATION/STAFFING/ MULTI-UNIT DOSE ASSESSMENT PLANS |
| - INSPECTION REPORT (05000275/2017007 AND 05000323/2017007 | | - INSPECTION REPORT (05000275/2017007 AND 05000323/2017007 |
| ) | | ) |
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| |
|
| In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, "Public Inspections, Exemptions, Requests for Withholding," | | In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, "Public Inspections, Exemptions, Requests for Withholding," |
| a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRC's Public Document Room or from the Publicly Available Records (PARS) component of the NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading | | a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRC's Public Document Room or from the Publicly Available Records (PARS) component of the NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). |
| -rm/adams.html (the Public Electronic Reading Room). | |
|
| |
|
| Sincerely, | | Sincerely, |
| /RA/ Mark S. Haire | | /RA/ Mark S. Haire |
| , Chief, Project Branch A Division of Reactor Projects Docket Nos. 50-275 and 50 | | , Chief, Project Branch A Division of Reactor Projects Docket Nos. 50-275 and 50-323 License Nos. DPR-80 and DPR-82 |
| -323 License Nos. DPR-80 and DPR-82 Enclosure: | | |
| | ===Enclosure:=== |
| Inspection Report 05000 275/201700 7 and 5000323/2017007 w/ Attachment: | | Inspection Report 05000 275/201700 7 and 5000323/2017007 w/ Attachment: |
| Supplemental Information cc w/encl: Electronic Distribution | | Supplemental Information |
|
| |
|
| Enclosure U.S. NUCLEAR REGULATORY COMMISSION REGION IV Docket: 50-275 and 50
| | REGION IV Docket: 50-275 and 50-323 License: DPR-80 and DPR-82 Report: 05000275/2017007 and 05000323/2017007 Licensee: Pacific Gas and Electric Company Facility: Diablo Canyon Power Plant, Units 1 and 2 Location: P.O. Box 56, Mail Code 104/6 Avila Beach, CA 93424 Dates: November 13 through December 27, 2017 Inspectors: |
| -323 License: DPR-80 and DPR | |
| -82 Report: 05000275/2017007 and 05000323/2017007 Licensee: Pacific Gas and Electric Company Facility: Diablo Canyon Power Plant, Units 1 and 2 Location: P.O. Box 56, Mail Code 104/6 Avila Beach, CA 93424 Dates: November 13 through December 27, 2017 Inspectors: | |
| J. Mateychick | | J. Mateychick |
| , Senior Reactor Inspector (Team Leader) C. Newport, Senior Resident Inspector R. Alexander, Senior Project Engineer E. Uribe, Project Engineer Approved By: Mark S. Haire Chief, Project Branch A Division of Reactor Projects 2 | | , Senior Reactor Inspector (Team Leader) C. Newport, Senior Resident Inspector R. Alexander, Senior Project Engineer E. Uribe, Project Engineer Approved By: Mark S. Haire Chief, Project Branch A Division of Reactor Projects 2 |
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|
| |
|
| ===Closed=== | | ===Closed=== |
| : 2515/191 TI Inspection of the Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communication/Staffing/ Multi-Unit Dose Assessment Plans
| | 2515/191 TI Inspection of the Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communication/Staffing/ Multi-Unit Dose Assessment Plans |
|
| |
|
| ==LIST OF DOCUMENTS REVIEWED== | | ==LIST OF DOCUMENTS REVIEWED== |
| ===Calculations===
| | |
| : Number Title Revision
| |
| : STA-294 Fukushima Emergency Pump Sizing
| |
| ===Drawings===
| |
| : Number Title Revision 8920 Model 500F Globe Valve Union Bonnet
| |
| : AA 347139 Emergency Operations Facility
| |
| : 900004146, Sheet
| |
| : FSG 99 Posting
| |
| : OP1.DC23 Control
| |
| : 6/29/2016
| |
| : 900004146, Sheet
| |
| : FSG 99 Posting
| |
| : OP1.DC23 Control
| |
| : 6/29/2016
| |
| ===Miscellaneous Documents===
| |
| : Number Title Revision DCM T-45 Diverse and Flexible Coping Strategies (FLEX) 1 DCM T-45, Appendix A
| |
| : Strategy S
| |
| -9, Communications Strategy
| |
| : DN 50813278
| |
| : FLEX PMCR: EAFW Pumps
| |
| : 10/21/2015
| |
| : EDT 4*1278
| |
| : Security Fence NMOD: FLEX RWR Strategy (NMOD
| |
| : 68038941) 7/24/2015 PG&E Letter
| |
| : DCL-15-117 Response to March 12, 2012,
| |
| : NRC 10 CFR
| |
| : 50.54(f) Request for Information Regarding Recommendation 9.3, Resubmittal of Phase 2 Staffing Assessment
| |
| : 10/28/2015
| |
| : PG&E Letter DCL
| |
| -16-003 Pacific Gas and Electric Company's Notification of Full Compliance with Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond
| |
| -Design-Basis External Events (Order Number
| |
| : EA-12-049) for Diablo Canyon Power Plant Unit 1
| |
| : 01/05/2016
| |
| : PG&E Letter DCL
| |
| -16-077 Pacific Gas and Electric Company's Notification of
| |
| : Full Compliance with Commission Order Modifying Licenses with Regard to Mitigation Strategies for Beyond-Design-Basis External Events (Order Number
| |
| : EA-12-049) for Diablo Canyon Power Plant Units 1 and 2
| |
| : 7/28/2016
| |
| ===Miscellaneous Documents===
| |
| : Number Title Revision
| |
| : NEI 12-06 Diverse and Flexible Coping Strategies (FLEX)
| |
| : Implementation Guide
| |
| : NRC Letter ML16349A386
| |
| : Diablo Canyon Power Plant, Unit Nos. 1 and 2
| |
| - Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA
| |
| -12-049 and EA
| |
| -12-051 (CAC Nos. MF0958, MF0959, MF0963, and
| |
| : MF0964) 12/28/2016
| |
| : Diablo Canyon Power Plant Beyond Design Basis Validation of the FLEX Time Sensitive Actions Units 1
| |
| and 2 4
| |
| : Diablo Canyon Power Plant Emergency Plan
| |
| - Section 5, Organizational Control of Emergencies
| |
| : 4.18
| |
| : FLEX Maintenance Plan Frequency Spreadsheet
| |
| {None}
| |
| : FLEX Equipment Status Board (per
| |
| : FS1.ID4), various dates 6/02/2016 10/05/2017
| |
| : 10/16/2017
| |
| : 10/19/2017
| |
| : 11/14/2017
| |
| : MIDAS Demonstration Report: Combined Accident Runs (DRILL)
| |
| : 11/16/2017
| |
| : SAFER Response Plan for Diablo Canyon Power Plant Operation and Maintenance Manual
| |
| - STARS Alliance PG&E Fukushima
| |
| - 150kW
| |
| : Operation and Maintenance Manual
| |
| - STARS Alliance PG&E Fukushima
| |
| - 275kW
| |
| : SIMPLEX Infinity 200kW Portable Load Bank
| |
| : EATON Doub le-Throw Safety Switch Spent Fuel Pool Instrumentation System Westinghouse Standard Product Technical Manual Spent Fuel Pool Instrumentation System Configuration
| |
| - Unit 1
| |
| : Installation Instructions for Westinghouse Spent Fuel Pool Instrumentation System Equipment Mounting & Termination Installation Instructions for Westinghouse Spent Fuel Pool Instrumentation System Power
| |
| -Up & Acceptance
| |
| ===Miscellaneous Documents===
| |
| : Number Title Revision Testing
| |
| : Spent Fuel Pool Instrumentation System Westinghouse Torque Specification Spent Fuel Pool Instrumentation System Westinghouse Specialty Tools List Spent Fuel Pool Instrumentation System Westinghouse Standard Product Integrated Function Test Procedure Spent Fuel Pool Instrumentation System Westinghouse Calibration Procedure
| |
| ===Notifications===
| |
| (Corrective Action Program Documents)
| |
| : 50950327*
| |
| : 50950367*
| |
| : 50950415*
| |
| : 50950417*
| |
| : 50950447*
| |
| : 50950592*
| |
| : 50950613*
| |
| : 50950615*
| |
| : 50950624*
| |
| : 50950628*
| |
| : 50950634*
| |
| : 50950673*
| |
| : 50950674*
| |
| : 50950536*
| |
| : 50950575*
| |
| : 50950576*
| |
| : 50950619*
| |
| : 50950675*
| |
| : 50950677*
| |
| : 50937019
| |
| : 50946852
| |
| : 50646319
| |
| : 50880784
| |
| : 50904294
| |
| : 50950628*
| |
| : Preventative Maintenance Activities Number Title Revision WO 64175685
| |
| -0010 Annual Inspection/Test of Emergency AFW Pump 1
| |
| : 10/13/2017
| |
| : WO 64175685
| |
| -0010 Annual Inspection/Test of Emergency AFW Pump 1 10/13/2017
| |
| : WO 64175685
| |
| -0020 Annual Inspection/Test of Emergency ASW Pump 1
| |
| : 10/13/2017
| |
| : WO 64175685
| |
| -0040 Annual Inspection/Test of Raw Water Pump 1
| |
| : 10/13/2017
| |
| : Preventative Maintenance Activities Number Title Revision WO 64175685
| |
| -0050 Annual Inspection/Test of FLEX 480V Safety Function Support (Distribution Panel) 1
| |
| : 10/12/2017
| |
| : WO 64175685
| |
| -0060 Annual Inspection/Test of FLEX 480V Safety Function Support (Distribution Panel) 4
| |
| : 10/12/2017
| |
| : WO 64175685
| |
| -0070 Annual Inspection/Test of 275KW FLEX 480V Diesel Generator 1
| |
| : 10/12/2017
| |
| : WO 64175685
| |
| -0080 Annual Inspection/Test of 20KW FLEX 120/240V Diesel Driven Generator FDEG5
| |
| : 10/12/2017
| |
| : WO 64177475
| |
| -0010 Quarterly Inspection/Test of 275KW FLEX 480V Diesel Generator 2
| |
| : 11/10/2017
| |
| : WO 64177475
| |
| -0020 Quarterly Inspection/Test of 150KW FLEX 480V Diesel Generator
| |
| : 11/10/2017
| |
| : WO 64177475
| |
| -0030 Quarterly Inspection/Test of 20KW FLEX 120/240V Diesel Driven Generator FDEG6
| |
| : 11/09/2017
| |
| : WO 64177475
| |
| -0050 Quarterly Inspection/Test of Emergency ASW Pump 2
| |
| : 11/10/2017
| |
| : WO 64177475
| |
| -0060 Quarterly Inspection/Test of Raw Water Reservoir Pump 0-2
| |
| : 11/09/2017
| |
| : WO 64177475
| |
| -0070 Quarterly Inspection/Test of Emergency AFW Pump
| |
| : 0-2
| |
| : 11/09/2017
| |
| : WO 64177475
| |
| -0090 Quarterly Inspection/Test of Portable Diesel Fuel Oil Caddy 0-2
| |
| : 11/06/2017
| |
| : WO 641810 91-0100 6 Month Inspection/Test of Emergency RCS Makeup Pump 0-1 4/20/2017 WO 64181091
| |
| -0200 6 Month Inspection/Test of Emergency RCS Makeup Pump 0-2 4/20/2017 WO 64181091
| |
| -0300 6 Month Inspection/Test of Emergency RCS Makeup Pump 0-3 3/13/2017
| |
| ===Procedures===
| |
| : Number Title Revision
| |
| : AD4.ID4 Temporary Storage Process
| |
| : EOP
| |
| : ECA-0.0 Loss of All Vital AC Power (Unit 1)
| |
| : EOP
| |
| : ECA-0.0 Loss of All Vital AC Power (Unit 2)
| |
| : EP R-2 Release of Airborne Radioactive Materials Initial Assessment
| |
| : EP
| |
| : RB-16 Operating Instructions for the EARS Computer Program 14 FS1 FLEX and SFP Instrumentation Program
| |
| : FS1.ID1 FLEX Strategy Management
| |
| ===Procedures===
| |
| : Number Title Revision
| |
| : FS1.ID2 Spent Fuel Pool Level Instrumentation Management
| |
| : FS1.ID4 FLEX Equipment Status and Availability
| |
| : FLEX Support Guideline 01
| |
| : Long Term RCS Inventory Control
| |
| : FLEX Support Guideline 02
| |
| : Alternate AFW Suction Source
| |
| : FLEX Support Guideline 03 (Unit 1)
| |
| : Alternate Low Pressure Feedwater
| |
| : FLEX Support Guideline 03 (Unit 2)
| |
| : Alternate Low Pressure Feedwater
| |
| : FLEX Support Guideline 04
| |
| (Unit 1) ELAP DC Bus Load Shed and Management
| |
| : FLEX Support Guideline 04
| |
| (Unit 2) ELAP DC Bus Load Shed and Management
| |
| : FLEX Support Guideline 05
| |
| : Initial Assessment and FLEX Equipment Staging
| |
| : 1A FLEX Support Guideline 08
| |
| : Alternate RCS Boration
| |
| : FLEX Support Guideline 09
| |
| : Low Decay Heat Temperature Control
| |
| : FLEX Support Guideline 10 (Unit 1)
| |
| : Accumulator Isolation
| |
| : FLEX Support Guideline 10 (Unit 2)
| |
| : Accumulator Isolation
| |
| : FLEX Support Guideline 11
| |
| : Alternate SFP Makeup and Cooling 1A FLEX Support Guideline 12
| |
| : Alternate Containment Cooling
| |
| : FLEX Support Guideline 14 (Unit 1)
| |
| : Shutdown RCS Makeup
| |
| ===Procedures===
| |
| : Number Title Revision FLEX Support Guideline 14 (Unit 2)
| |
| : Shutdown RCS Makeup
| |
| : FLEX Support Guideline 40
| |
| : Component Cooling Water Alignment for ELAP
| |
| : FLEX Support Guideline 41
| |
| : Refill Fire Water Storage Tank with FLEX Equipment
| |
| : FLEX Support Guideline 42
| |
| : Establishing the FLEX Suction Header Water Supply
| |
| : FLEX Support Guideline 43
| |
| : Staging FLEX Equipment
| |
| : FLEX Support Guideline 44
| |
| : Site Debris Removal 1 FLEX Support Guideline 45 (Unit 1)
| |
| : Supplying Power to SI Accumulator and RHR Valves
| |
| : FLEX Support Guideline 45 (Unit 2)
| |
| : Supplying Power to SI Accumulator and RHR Valves
| |
| : FLEX Support Guideline 47
| |
| : Operation of FLEX Communications Equipment
| |
| : FLEX Support Guideline 49 (Unit1)
| |
| : Align RCS Injection for Inventory / Boration
| |
| : FLEX Support Guideline 49 (Unit2)
| |
| : Align RCS Injection for Inventory / Boration
| |
| : FLEX Support Guideline 50 (Unit 1)
| |
| : Align Injection to Normal Charging During Reflux
| |
| : FLEX Support Guideline 50 (Unit 2)
| |
| : Align Injection to Normal Charging During Reflux
| |
| : FLEX Support Guideline 51
| |
| : Pacing Emergency ASW Pumps in Service
| |
| : FLEX Support Guideline 54
| |
| (Unit 1) Placing 480V Loads in Service
| |
| : FLEX Support Guideline 54
| |
| (Unit 2) Placing 480V Loads in Service
| |
| ===Procedures===
| |
| : Number Title Revision FLEX Support Guideline 56
| |
| : Supply FLEX 480V Power to Telecommunications Equipment 1 FLEX Support Guideline 57
| |
| : Fueling FLEX Equipment
| |
| : FLEX Support Guideline 58
| |
| (Unit 1) Preparing 4kV Bus for Service
| |
| : FLEX Support Guideline 58
| |
| (Unit 2) Preparing 4kV Bus for Service
| |
| : FLEX Support Guideline 59
| |
| (Unit 1) Placing 4kV Bus in Service
| |
| : FLEX Support Guideline 59
| |
| (Unit 2) Placing 4kV Bus in Service
| |
| : FLEX Support Guideline 60
| |
| : Local Manual Operation of 10% Steam Dumps
| |
| : FLEX Support Guideline 61
| |
| : Restarting Turbine Driven AFW Pump After Overspeed Trip 0 FLEX Support Guideline 62
| |
| : Local Closing of MSIVs
| |
| : FLEX Support Guideline 63
| |
| : Establishing Forced FLEX Guidelines
| |
| : FLEX Support Guideline 98
| |
| : FLEX ERO Guidance for BDB Event Response Draft - 0 FLEX Support Guideline 99
| |
| : FLEX Equipment Operating Guides
| |
| : MA1.ID27 Preventive Maintenance Program
| |
| : MP T-BDB-001 BDB Communications Equipment Inventory
| |
| : OP AP
| |
| : SD-1 Loss of AC Power
| |
| : TS3.ID2 Licensing Basis Impact Evaluations
| |
| : Training Documents Number Title Revision
| |
| : Enrollment and Completion Report for EQIP
| |
| -0022 November 13, 2017
| |
| : Fire Training FLEX Presentation
| |
| {None} ECTP 1702 ERO Requalification Training on FSGs for ERO
| |
| -TSC, EOF Leaders, ERO
| |
| -TSC Engineers, and Emergency Response Unit
| |
| : 2017
| |
| : EDP 912 FLEX Support Guidelines
| |
| {None}
| |
| : EQIP-0022 Wheel Loader Participant's Guide
| |
| {None} ESP 4Q2012
| |
| : 2012 ESP Continuing Training
| |
| - Fukushima Project 0 JITTOP 1608
| |
| : FLEX Equipment Status
| |
| : 0A MDCT 1502E
| |
| : Electrical Maintenance Continuing Training 2015
| |
| : 2015 MSCT 1401 Fukushima Design Changes Overview
| |
| : 2014 R151C3 FLEX - The First 24 Hours
| |
| : 0A R156C6 Licensed Operator Continuing Training
| |
| - In-Plant Walkdown Package (FLEX)
| |
| : 2015 R161C11 Oasis FLEX Dynamic Learning Activity
| |
| : TU 1443 2014 ESP Continuing Training
| |
| - Introduction to FLEX Systems
| |
| : 2014
| |
| : ML18025A000
| |
| : SUNSI Review:
| |
| : ADAMS:
| |
| : Non-Publicly Available
| |
| : Non-Sensitive
| |
| : Keyword:
| |
| : NRC-002 By:
| |
| : JMM/rdr
| |
| : Yes
| |
| : No
| |
| : Publicly Available
| |
| : Sensitive
| |
| : OFFICE SRI:EB2 S PE: PBA PE:IPAT SRI: PBA BC: PBA
| |
| : NAME JMateychick
| |
| : RAlexander
| |
| : EUribe CNewport MHaire
| |
| : SIGNATURE /RA/ /RA-E/ /RA/ /RA-E/ /RA/
| |
| : DATE 1/22/18 1/17/2018 1/24/18 1/22/18 1/24/18
| |
| }} | | }} |
|
---|
Category:Inspection Report
MONTHYEARIR 05000275/20240052024-08-22022 August 2024 Updated Inspection Plan for Diablo Canyon Power Plant, Units 1 and 2 (Report 05000275/2024005 and 05000323/2024005) IR 05000275/20240022024-08-0606 August 2024 Integrated Inspection Report 05000275/2024002 and 05000323/2024002 IR 05000275/20240142024-07-11011 July 2024 Age-Related Degradation Inspection Report 05000275/2024014 and 05000323/2024014 IR 05000275/20243012024-07-10010 July 2024 NRC Initial Operator Licensing Examination Approval 05000275/2024301; 05000323/2024301 IR 05000275/20244012024-07-0808 July 2024 Security Baseline Inspection Report 05000275/2024401 and 05000323/2024401 (Full Report) IR 05000323/20240112024-07-0303 July 2024 License Renewal Phase Report 05000323/2024011 IR 05000275/20240012024-04-23023 April 2024 Integrated Inspection Report 05000275/2024001 and 05000323/2024001 IR 05000275/20244032024-03-12012 March 2024 Cyber Security Inspection Report 05000275/2024403 and 05000323/2024403 (Cover Letter) IR 05000275/20230062024-02-28028 February 2024 Annual Assessment Letter for Diablo Canyon Power Plant, Units 1 and 2 (Report 05000275/2023006 and 05000323/2023006) IR 05000275/20230042024-02-0909 February 2024 Integrated Inspection Report 05000275/2023004 and 05000323/2023004 IR 05000275/20230112024-01-12012 January 2024 NRC License Renewal Phase 1 Inspection Report 05000275/2023011 IR 05000275/20230032023-11-13013 November 2023 Integrated Inspection Report 05000275/2023003 and 05000323/2023003 IR 05000275/20240152023-10-10010 October 2023 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection (050002752024015 and 050003232024015) IR 05000275/20230052023-08-22022 August 2023 Updated Inspection Plan for Diablo Canyon Power Plant, Units 1 and 2 (Report 05000275/2023005 and 05000323/2023005) - Mid Cycle Letter IR 05000275/20230022023-08-14014 August 2023 Quarterly Integrated Inspection Report 05000275/2023002 and 05000323/2023002- August 7, 2023 IR 05000275/20213012023-08-0909 August 2023 Errata for Diablo Canyon Power Plant, Units 1 and 2 - NRC Examination Report 050002752021301 and 050003232021301 IR 05000275/20234022023-08-0303 August 2023 NRC Security Inspection Report 05000275/2023402, and 05000323/2023402 IR 05000275/20233012023-07-25025 July 2023 NRC Initial Operator Licensing Examination Approval 05000275/2023301, 05000323/2023301 IR 05000275/20230102023-05-11011 May 2023 NRC Inspection Report 05000275 2023010 and 05000323 2023010 IR 05000275/20230012023-05-0909 May 2023 Integrated Inspection Report 05000275/2023001 and 05000323/2023001 IR 05000275/20234032023-03-10010 March 2023 NRC Security Baseline Inspection Report 05000275/2023403, 05000323/2023403 (Full Report) IR 05000275/20220062023-03-0101 March 2023 Annual Assessment Letter for Diablo Canyon Power Plant, Units 1 and 2 (Report 05000275/2022006 and 05000323/2022006) IR 05000275/20220042023-02-0202 February 2023 Integrated Inspection Report 05000275/2022004 and 05000323/2022004 IR 05000275/20220102023-01-27027 January 2023 Biennial Problem Identification and Resolution Inspection Report 05000275/2022010 and 05000323/2022010 IR 05000275/20224022022-10-26026 October 2022 Security Baseline Inspection Report 05000275/2022402 and 05000323/ 2022402 IR 05000275/20220032022-10-24024 October 2022 Integrated Inspection Report 05000275/2022003 and 05000323/2022003 and Exercise of Enforcement Discretion IR 05000275/20220052022-08-23023 August 2022 Updated Inspection Plan for Diablo Canyon Power Plant, Units 1 and 2 (Report 05000275/2022005 and 05000323/2022005) IR 05000275/20220022022-08-10010 August 2022 Integrated Inspection Report 05000275/2022002 and 05000323/2022002 IR 05000275/20220112022-08-0909 August 2022 Design Basis Assurance Inspection (Teams) Inspection Report 05000275/2022011 and 05000323/2022011 IR 05000275/20224012022-08-0303 August 2022 NRC Security Inspection Report 05000275/2022401, 05000323/2022401 ML22143A8812022-05-26026 May 2022 Revised Integrated Inspection Report 05000275/2022001 and 05000323/2022001 ML22118A9362022-05-0505 May 2022 Integrated Inspection Report 05000275/2022001 and 05000323/2022001 IR 05000275/20220012022-05-0505 May 2022 Integrated Inspection Report 05000275/2022001 and 05000323/2022001 IR 05000323/20214202022-03-31031 March 2022 Security Inspection Report 05000275 and 05000323/2021420 IR 05000275/20210062022-03-0202 March 2022 Annual Assessment Letter for Diablo Canyon Power Plant, Units 1 and 2 (Report 05000275/2021006 and 05000323/2021006) IR 05000275/20210042022-02-0303 February 2022 Integrated Inspection Report 05000275/2021004 and 05000323/2021004 IR 05000275/20214042022-01-13013 January 2022 Public - Security Baseline Inspection Report 05000275/2021404 and 05000323/2021404 IR 05000275/20210032021-11-0303 November 2021 Integrated Inspection Report 05000275/2021003 and 05000323/2021003 IR 05000275/20210112021-09-10010 September 2021 Design Basis Assurance Inspection (Programs) Report 05000275/2021011 and 05000323/2021011 IR 05000275/20214052021-08-0505 August 2021 Security Baseline Inspection Report 05000275/2021405 and 05000323/2021405 IR 07200026/20214012021-08-0303 August 2021 Diablo Canon Nuclear Power Plant, Security Baseline Inspection Report 07200026/2021401 IR 05000275/20210022021-08-0202 August 2021 Integrated Inspection Report 05000275/2021002 and 05000323/2021002 IR 05000275/20210122021-07-28028 July 2021 Temporary Instruction 2515/194 Report 05000275/2021012 and 05000323/2021012 IR 05000275/20214012021-07-0101 July 2021 Security Baseline Inspection Report 05000275/2021401 and 05000323/2021401 IR 05000275/20210012021-05-0707 May 2021 DC IR 2021-001-drk, Diablo Canyon Power Plant Units 1 & 2 - Integrated Inspection Report 05000275/2021001, 05000323/2021001, & Independent Spent Fuel Storage Installation Inspection Report 07200026/2021001 DCL-21-036, One Hundred Eighty Day Steam Generator Report for Diablo Canyon Power Plant Unit 1 Twenty-Second Refueling Outage2021-04-22022 April 2021 One Hundred Eighty Day Steam Generator Report for Diablo Canyon Power Plant Unit 1 Twenty-Second Refueling Outage ML21102A0702021-04-12012 April 2021 Notification of NRC Design Bases Assurance Inspection (Programs) (05000275/2021011 and 05000323/2021011) and Initial Request for Information IR 05000275/20214032021-03-31031 March 2021 Cyber Security Inspection Report 05000275/2021403 and 05000323/2021403 IR 05000275/20210102021-03-11011 March 2021 Triennial Fire Protection Inspection Report 05000275/2021010 and 05000323/2021010 IR 05000275/20200062021-03-0303 March 2021 DC 2020 Annual Assessment Letter for Diablo Canyon Power Plant, Units 1 & 2 (Report 05000275/2020006 & 05000323/2020006) 2024-08-06
[Table view] Category:Letter
MONTHYEARML24260A1222024-09-14014 September 2024 14 Sept 2024 Ltr - California Coastal Commission to Pg&E, Incomplete Consistency Certification for Requested Nuclear Regulatory Commission License Renewal for Diablo Canyon Power Plant 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) ML24262A2462024-09-11011 September 2024 10 CFR 2.206 - Diablo Canyon Units 1 and 2 Seismic - Petitioner Response to Acknowledgement Letter - 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 ML24205A0662024-08-27027 August 2024 OEDO-24-00083 - 10 CFR 2.206 - Ack Letter - Diablo Canyon Units 1 and 2 Seismic Core Damage Frequency - IR 05000275/20240052024-08-22022 August 2024 Updated Inspection Plan for Diablo Canyon Power Plant, Units 1 and 2 (Report 05000275/2024005 and 05000323/2024005) 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 IR 05000275/20240022024-08-0606 August 2024 Integrated Inspection Report 05000275/2024002 and 05000323/2024002 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 ML24187A1352024-07-16016 July 2024 Letter to Paula Gerfen - Diablo Canyon Units 1 and 2 - Summary of June 2024 Audit Related to the License Renewal Application Severe Accident Mitigation Alternatives Review IR 05000275/20240142024-07-11011 July 2024 Age-Related Degradation Inspection Report 05000275/2024014 and 05000323/2024014 IR 05000275/20243012024-07-10010 July 2024 NRC Initial Operator Licensing Examination Approval 05000275/2024301; 05000323/2024301 IR 05000275/20244012024-07-0808 July 2024 Security Baseline Inspection Report 05000275/2024401 and 05000323/2024401 (Full Report) IR 05000323/20240112024-07-0303 July 2024 License Renewal Phase Report 05000323/2024011 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 ML24155A2182024-06-18018 June 2024 OEDO-23-00350-NRR - (LTR-23-0228-1) - Closure Letter - 10 CFR 2.206 Petition from Mothers for Peace and Friends of the Earth Regarding Diablo Canyon ML24129A1762024-06-14014 June 2024 National Historic Preservation Act Section 106 Consultation – Results of Identification and Evaluation (Docket Number: 72-026) ML24200A2052024-06-0707 June 2024 Fws to NRC, List of Threatened and Endangered Species That May Occur in Your Proposed Project Location or May Be Affected by Your Proposed Project for Diablo Canyon License Renewal ML24099A2192024-05-29029 May 2024 Issuance of Amendment Nos. 245 and 247 Revision to TSs to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML24117A0132024-05-20020 May 2024 Letter to Paula Gerfen-Diablo Canyon Units 1 and 2-Regulatory Audit Regarding Severe Accident Mitigation Alternatives for the License Renewal Application 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 ML24127A2042024-05-0202 May 2024 02May2024 Ltr - California Coastal Commission to Pg&E, Coastal Development Permit Needed for Pg&E’S Proposed Relicensing of Diablo Canyon Nuclear Power Plant 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 L-24-004, Independent Spent Fuel Storage Installation - Responses to NRC Requests for Additional Information on the Diablo Canyon Independent Spent Fuel Storage Installation License Renewal Application (Cac/Epid 001028/L-2022-RNW-0007)2024-04-30030 April 2024 Independent Spent Fuel Storage Installation - Responses to NRC Requests for Additional Information on the Diablo Canyon Independent Spent Fuel Storage Installation License Renewal Application (Cac/Epid 001028/L-2022-RNW-0007) 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 IR 05000275/20240012024-04-23023 April 2024 Integrated Inspection Report 05000275/2024001 and 05000323/2024001 ML24114A2032024-04-22022 April 2024 Request for Information for EP Program and Performance Indicator Verification Inspection (Wolf Creek Nuclear Generating Station) Inspection Report 05000482/2024003 ML24106A2882024-04-18018 April 2024 License Renewal Application Environmental Review RCIs and RAIs ML24106A2892024-04-18018 April 2024 Letter to Paula Gerfen - Diablo Canyon Units 1 and 2 - Summary of March 2024 Audit Regarding the Environmental Review of the License Renewal Application 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 ML24108A1122024-04-15015 April 2024 License Amendment Request 24-02 Request for Approval of DCPP Early Warning System to Meet 10 CFR 73.55(i)(2) and 10 CFR 73.55(e)(9)(vi)(A) 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 ML24082A2592024-03-25025 March 2024 Notice of Enforcement Discretion for Diablo Canyon Power Plant, Unit 2 (EPID L-2024-LLD-0002) - March 25, 2024 ML24081A0462024-03-22022 March 2024 Audit Summary in Support of the License Amendment Request to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b 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 ML24081A4052024-03-21021 March 2024 Request for Enforcement Discretion Regarding Compliance with Technical Specification 3.0.3, Limiting Condition for Operation Applicability ML24065A1312024-03-20020 March 2024 ISFSI Renewal RAI Transmittal Letter 2024-09-09
[Table view] |
Text
January 24, 2018
SUBJECT:
DIABLO CANYON POWER PLANT, UNITS 1 AND 2
- INSPECTION OF THE IMPLEMENTATION OF MITIGATION STRATEGIES AND SPENT FUEL POOL INSTRUMENTATION ORDERS AND EMERGENCY PREPAREDNESS COMMUNICATION/STAFFING/ MULTI-UNIT DOSE ASSESSMENT PLANS
- INSPECTION REPORT (05000275/2017007 AND 05000323/2017007
)
Dear Mr. Welsch:
On December 27
, 2017, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Diablo Canyon Power Plant, Units 1 and 2.
On December 27, 2017 , t he NRC inspectors discussed the results of this inspection with Mr. C. Murry , Acting Station Director, and other members of your staff. Inspectors documented the results of this inspection in the enclosed inspection report. The inspection examined activities conducted under your license as they relate to the implementation of mitigation strategies and spent fuel pool instrumentation orders (EA-12-049 and EA-12-051) and Emergency Preparedness Communication, Staffing, and Multi-Unit Dose Assessment Plans, your compliance with the Commission's rules and regulations, and with the conditions of your operating license. Within these areas, the inspection involved examination of selected procedures and records, observation of activities, and interviews with station personnel.
Based on the results of this inspection, no findings of significance were identified.
In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, "Public Inspections, Exemptions, Requests for Withholding,"
a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRC's Public Document Room or from the Publicly Available Records (PARS) component of the NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/ Mark S. Haire
, Chief, Project Branch A Division of Reactor Projects Docket Nos. 50-275 and 50-323 License Nos. DPR-80 and DPR-82
Enclosure:
Inspection Report 05000 275/201700 7 and 5000323/2017007 w/ Attachment:
Supplemental Information
REGION IV Docket: 50-275 and 50-323 License: DPR-80 and DPR-82 Report: 05000275/2017007 and 05000323/2017007 Licensee: Pacific Gas and Electric Company Facility: Diablo Canyon Power Plant, Units 1 and 2 Location: P.O. Box 56, Mail Code 104/6 Avila Beach, CA 93424 Dates: November 13 through December 27, 2017 Inspectors:
J. Mateychick
, Senior Reactor Inspector (Team Leader) C. Newport, Senior Resident Inspector R. Alexander, Senior Project Engineer E. Uribe, Project Engineer Approved By: Mark S. Haire Chief, Project Branch A Division of Reactor Projects 2
SUMMARY
IR 05000275/2017007
- 05000323/2017007
- 11/13/2017 - 12/27/2017
- Diablo Canyon Power Plant, Units 1 and 2
- Temporary Instruction 2515/191, Inspection of the Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communication/Staffing/Multi-Unit Dose Assessment Plans , issued December 23, 2015. The inspection covered a one week inspection onsite by three inspectors from the Region IV office and one of the assigned resident inspectors.
No findings of significance were identified.
The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process," Revision 5.
A. NRC-Identified and Self-Revealing Findings
None
B. Licensee-Identified Violations
None 3
REPORT DETAILS
4. Other Activities
4OA5 Other Activities
(TI 2515/191) The objective of Temporary Instruction (TI) 2015/191 "Inspection of the Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communication/Staffing/Multi
-Unit Dose Assessment Plans" is to verify that licensees have adequately implemented the mitigation strategies as described in the licensee's Final Integrated Plan (ADAMS Accession No. ML16221A390
) and the NRC's plant safety evaluation (ADAMS Accession No. ML16349A386
) and to verify that the licensee installed reliable water-level measurement instrumentation in their spent fuel pools. The purpose of this TI is also to verify the licensees have implemented Emergency Preparedness (EP) enhancements as described in their site
-specific submittals and NRC safety assessments, including multi-unit dose assessment capability and enhancements t o ensure that staffing is sufficient and communications can be maintained during such an event. The inspection verifies that plans for complying with NRC Orders EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond- Design-Basis External Events (ADAMS Accession No. ML12229A174)and EA-12-051, Order Modifying Licenses With Regard to Reliable Spent Fuel Pool Instrumentation (ADAMS Accession No. ML12056A044)are in place and are being implemented by the licensee. Additionally, the inspection verifies implementation of staffing and communications information provided in response to the March 12, 2012 , request for information letter and multiunit dose assessment information provided per COMSECY-13-0010, Schedule and Plans for Tier 2 Order on Emergency Preparedness for Japan Lessons Learned, dated March 27, 2013 (ADAMS Accession No. ML12339A262).
The team discussed the plans and strategies with plant staff, reviewed documentation, and where appropriate, performed plant walkdowns to verify that the strategies could be implemented as stated in the licensee's submittals and the NRC staff prepared safety evaluation.
For most strategies, this included verification that the strategy was feasible, procedures and/or guidance had been developed, training had been provided to plant staff, and required equipment had been identified and staged. Specific details of the team's inspection activities are described in the following sections. 1. Mitigation Strategies for Beyond-Design-Basis External Events
a. Inspection Scope
The team examined the licensee's established guidelines and implementing procedures for the beyond-design-basis mitigation strategies.
The team assessed how the licensee coordinated and documented the interface/transition between existing off-normal and Emergency Operating Procedures with the newly developed mitigation strategies.
The team selected a number of mitigation strategies , conducted plant walkdowns with licensed operators and responsible plant staff , to assess the adequacy and completeness of the procedures; familiarity of operators with the procedure objectives and specific guidance; staging and compatibility of equipment ,
and the practicality of the operator actions prescribed by the procedures, consistent with the postulated scenarios.
The team verified that a preventive maintenance program had been established for the FLEX portable equipment and that periodic equipment inventories were in place and being conducted.
Additionally, the team examined the introductory and planned periodic/refresher training provided to the Operations and Fire Protection staffs most likely to be tasked with implementation of the FLEX mitigation strategies.
The team also reviewed the introductory and planned periodic training provided to the Emergency Response Organization personnel.
Documents reviewed are listed in the attachment.
b. Assessment Based on samples selected for review, the inspectors verified that the licensee satisfactorily implemented appropriate elements of the FLEX strategy as described in the plant specific submittals and the associated safety evaluation and determined that the licensee is generally in compliance with NRC Order EA-12-049. The inspectors verified that the licensee satisfactorily:
Developed and issued FLEX Support Guidelines (FSG s) to implement the FLEX strategies for postulated external events; Integrated their FSGs into their existing plant procedures such that entry into and departure from the FSGs are clear when using existing plant procedures; Protected FLEX equipment from site-specific hazards; Developed and implemented adequate testing and maintenance of FLEX equipment to ensure their availability and capability; Trained their staff to assure personnel proficiency in the mitigation of beyond-design-basis events; and Developed means to ensure that the necessary off-site FLEX equipment will be available from off-site locations.
The inspectors verified that non-compliances with current licensing requirements, and other issues identified during the inspection were entered into the licensee's corrective action program.
c. Findings
No findings identified.
2. Spent Fuel Pool (SFP) Instrumentation
a. Inspection Scope
The team examined the licensee's newly installed spent fuel pool instrumentation. Specifically, the inspectors verified the sensors were installed as described in the plant specific submittals and the associated safety evaluation and that the cabling for the power supplies and the indications for each channel are physically and electrically separated.
Additionally, environmental conditions and accessibility of the instruments were evaluated.
Documents reviewed are listed in the attachment.
b. Assessment Based on samples selected for review, the inspectors determined that the licensee satisfactorily installed and established control of the spent fuel pool instrumentation as described in the plant specific submittals and the associated safety evaluation and determined that the licensee is generally in compliance with NRC Order EA-12-051. The inspectors verified that the licensee satisfactorily:
Installed the SFP instrumentation sensors, cabling , and power supplies to provide physical and electrical separation as described in the plant specific submittal and safety evaluation; Installed the SFP instrumentation display in the location, environmental conditions
, and accessibility as described in the plant specific submittals; and Trained their staff to assure personnel proficiency with the maintenance, testing, and use of the SFP instrumentation.
The inspectors verified that non-compliances with current licensing requirements, and other issues identified during the inspection were entered into the licensee's corrective action program.
c. Findings
No findings identified.
3. Staffing and Communication Request for Information
a. Inspection Scope
Through discussions with plant staff, review of documentation
, and plant walkdowns the team verified that the licensee has implemented required changes to staffing, communications equipment , and facilities to support an Extended Loss of All AC Power (ELAP) scenario as described in the licensee's staffing assessment and the NRC safety assessment.
The team also verified that the licensee has implemented dose assessment (including releases from spent fuel pools) capability using the licensee's site-specific dose assessment software and approach as described in the licensee's dose assessment submittal.
Documents reviewed are listed in the attachment.
b. Assessment The inspectors reviewed information provided in the licensee's multi-unit dose submittal and in response to the NRC's March 12, 2012, request for information letter and verified that the licensee satisfactorily implemented enhancements pertaining to Near-Term Task Force Recommendation 9.3 response to a large scale natural emergency event that results in an extended loss of all ac power to the site and impedes access to the site. The inspectors verified the following:
Licensee satisfactorily implemented required staffing change(s)to support an ELAP scenario; Emergency preparedness communications equipment and facilities are sufficient for dealing with an ELAP scenario; and Implemented dose assessment capabilities (including releases from spent fuel pools) using the licensee's site-specific dose assessment software and approach. The inspectors verified that non-compliances with current licensing requirements, and other issues identified during the inspection were entered into the licensee's corrective action program.
c. Findings
No findings identified.
4OA6 Meetings, Including Exit
Exit Meeting Summary
On November 16
, 2017, the inspectors presented the on-site inspection results in a management debrief to Mr. H. Hamzehee, Manager Regulatory Services
, and other members of the site staff. The inspectors completed an exit meeting with Mr. C. Murry , Acting Station Director, and other members of the site staff, via telephone on December 27
, 201 7 , who acknowledged the final results of the inspection.
The inspectors confirmed that proprietary information was not provided or examined during the inspection.
=SUPPLEMENTAL
INFORMATION=
KEY POINTS OF CONTACT
Licensee Personnel
- B. Ashbrook, Security and Emergency Services Manager
- M. Baker, Engineering Supervisor
- T. Baldwin, Business Initiatives Chief
- R. B aradar an, Acting Manager, Regulatory Services
- J. Brancheau, Operations Shift Forman
- K. Bych, Manager, Engineering
- A. Chitwood, Operations
Shift Manager
- C. Christensen, Emergency Preparedness
- W. Conklin, FLEX Engineer
- D. Esminger, Chief, Fire Department
- M. Frauenheim, Process Improvement Manager
- F. Gaber, FLEX Program Owner, Arizona Public Service
- S. Guess, Manager, Operations
- H. Hamzehee, Manager, Regulatory Services
- J. Harker, Manager, Maintenance and Technical Training
- S. Kirvin, Manager, Security
- S. Leke, Nuclear Operator
- D. Madson, Acting Compliance Supervisor
- S. Maze, Fukushima Program Supervisor
- M. McCoy, NRC Interface, Regulatory Services
- J. Morris, Regulatory Services Supervisor
- C. Murry, Acting Station Director
- A. Peck, Engineering Director
- D. Phillips, Security Operations Support
- G. Reed, Beyond Design Basis Project Manager
- B. Simpson, Manager, Operations Training
- A. Sorensen, Regulatory Services Engineer
- D. Spaulding, Strategic Projects Contractor
- D. Ven tr es ca, Security Operations supervisor
- R. Waltos, Assistant engineering Director
- A. Warwick, Supervisor, Emergency Planning
- T. Wernet, Assistant Chief, Fire Department
- D. Yoder, FLEX Engineer
LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED
Closed
2515/191 TI Inspection of the Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communication/Staffing/ Multi-Unit Dose Assessment Plans
LIST OF DOCUMENTS REVIEWED