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| | issue date = 05/04/2012 | | | issue date = 05/04/2012 |
| | title = IR 05000275-12-007, 05000323-12-007; 03/05/2012 - 03/22/2012; Diablo Canyon Power Plant Biennial Baseline Inspection of the Identification and Resolution of Problems | | | title = IR 05000275-12-007, 05000323-12-007; 03/05/2012 - 03/22/2012; Diablo Canyon Power Plant Biennial Baseline Inspection of the Identification and Resolution of Problems |
| | author name = Alexander R D | | | author name = Alexander R |
| | author affiliation = NRC/RGN-IV/DRS | | | author affiliation = NRC/RGN-IV/DRS |
| | addressee name = Conway J T | | | addressee name = Conway 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 = Alexander R D | | | contact person = Alexander R |
| | document report number = IR-12-007 | | | document report number = IR-12-007 |
| | document type = Inspection Report, Letter | | | document type = Inspection Report, Letter |
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| =Text= | | =Text= |
| {{#Wiki_filter: | | {{#Wiki_filter:May 4, 2012 |
| [[Issue date::May 4, 2012]]
| |
|
| |
|
| John Conway Senior Vice President and Chief Nuclear Officer Pacific Gas and Electric Company 77 Beale Street, B32 San Francisco, CA 94105
| | ==SUBJECT:== |
| | DIABLO CANYON POWER PLANT - NRC PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT 05000275/2012007 AND 05000323/2012007 |
|
| |
|
| SUBJECT: DIABLO CANYON POWER PLANT - NRC PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT 05000275/2012007 AND 05000323/2012007 Dear Mr. Conway
| | Dear Mr. Conway |
| : On March 22, 2012, the U.S. Nuclear Regulatory Commission (NRC) completed a Problem Identification and Resolution biennial inspection at your Diablo Canyon Power Plant Units 1 and The enclosed inspection report documents the inspection results, which were discussed on March 22, 2012, with Mr. J. Becker and other members of your staf This inspection was an examination of activities conducted under your license as they relate to problem identification and resolution and compliance with the Commission's rules and regulations and the conditions of your licens Within these areas, the inspection involved examination of selected procedures and representative records, observations of activities, and interviews with personne Based on the inspection sample, the inspection team concluded that the implementation of the corrective action program and overall performance related to identifying, evaluating, and resolving problems at Diablo Canyon was generally effectiv Licensee identified problems were entered into the corrective action program at an appropriately low threshol Problems were effectively prioritized and evaluated commensurate with the safety significance of the problem Corrective actions were effectively implemented in a timely manner commensurate with their importance to safety and addressed the identified causes of problem Lessons learned from industry operating experience were effectively reviewed and applied when appropriat Audits and self-assessments were effectively used to identify problems and appropriate action Finally, Diablo Canyon effectively established and maintained a Safety Conscious Work Environmen No findings were identified during this inspectio In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of J. Conway - 2 - | | : On March 22, 2012, the U.S. Nuclear Regulatory Commission (NRC) completed a Problem Identification and Resolution biennial inspection at your Diablo Canyon Power Plant Units 1 and The enclosed inspection report documents the inspection results, which were discussed on March 22, 2012, with Mr. J. Becker and other members of your staf This inspection was an examination of activities conducted under your license as they relate to problem identification and resolution and compliance with the Commission's rules and regulations and the conditions of your licens Within these areas, the inspection involved examination of selected procedures and representative records, observations of activities, and interviews with personne Based on the inspection sample, the inspection team concluded that the implementation of the corrective action program and overall performance related to identifying, evaluating, and resolving problems at Diablo Canyon was generally effectiv Licensee identified problems were entered into the corrective action program at an appropriately low threshol Problems were effectively prioritized and evaluated commensurate with the safety significance of the problem Corrective actions were effectively implemented in a timely manner commensurate with their importance to safety and addressed the identified causes of problem Lessons learned from industry operating experience were effectively reviewed and applied when appropriat Audits and self-assessments were effectively used to identify problems and appropriate action Finally, Diablo Canyon effectively established and maintained a Safety Conscious Work Environmen No findings were identified during this inspectio In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of UNITED STATESNUCLEAR REGULATORY COMMISSIONREGION IV1600 EAST LAMAR BLVDARLINGTON, TEXAS 76011-4511 J. Conway - 2 - |
| NRC's Agencywide Document 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). | | NRC's Agencywide Document 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/ Ryan Alexander, Branch Chief (Acting), Technical Support Branch Division of Reactor Safety Docket Nos.: 05000275, 05000323 License Nos: DPR-80, DPR-82 | | Sincerely, |
| | /RA/ Ryan Alexander, Branch Chief (Acting), Technical Support Branch Division of Reactor Safety Docket Nos.: 05000275, 05000323 License Nos: DPR-80, DPR-82 |
|
| |
|
| ===Enclosure:=== | | ===Enclosure:=== |
| Inspection Report 05000275/2012007 and 05000323/2012007 | | Inspection Report 05000275/2012007 and 05000323/2012007 w/Attachment: Supplemental Information |
|
| |
|
| ===w/Attachment:===
| | REGION IV Docket: 05000275, 05000323 License: DPR-80, DPR-82 Report: 05000275/2012007, 05000323/2012007 Licensee: Pacific Gas and Electric Company Facility: Diablo Canyon Power Plant Location: 71/2 Miles NW of Avila Beach, CA Dates: March 5 - 22, 2012 Team Leader: Charles Peabody, Resident Inspector, Wolf Creek Inspectors: |
| Supplemental Information cc w/Enclosure Electronic Distribution
| |
| | |
| ML12115A130 SUNSI Rev Compl. Yes No ADAMS Yes No Reviewer Initials RDA Publicly Avail. Yes No Sensitive Yes No Sens. Type Initials RDA RI:DRP/B SPE:DRP/C SRI:DRP/B PE: DRP/B C:DRS/TSB C:DRP/B CPeabody BHagar MPeck NMakris NOKeefe RAlexander CP (preparer)/RA/ BH (email)/RA/ MP (email)/RA/ NM (email)/RA/CFO /RA/ RDA/RA 04/02/2012 04/02/2012 03/29/2012 03/29/2012 04/27/2012 05/04/2012 1 Enclosure U.S. NUCLEAR REGULATORY COMMISSION REGION IV Docket: 05000275, 05000323 License: DPR-80, DPR-82 Report: 05000275/2012007, 05000323/2012007 Licensee: Pacific Gas and Electric Company Facility: Diablo Canyon Power Plant Location: 71/2 Miles NW of Avila Beach, CA Dates: March 5 - 22, 2012 Team Leader: Charles Peabody, Resident Inspector, Wolf Creek Inspectors:
| |
| Bob Hagar, Senior Project Engineer Michael Peck, Senior Resident Inspector Nestor Makris, Project Engineer Approved By: Ryan Alexander, Branch Chief (Acting) Technical Support Branch Division of Reactor Safety | | Bob Hagar, Senior Project Engineer Michael Peck, Senior Resident Inspector Nestor Makris, Project Engineer Approved By: Ryan Alexander, Branch Chief (Acting) Technical Support Branch Division of Reactor Safety |
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| ==LIST OF DOCUMENTS REVIEWED== | | ==LIST OF DOCUMENTS REVIEWED== |
| PROCEDURES
| |
| : NUMBER TITLE REVISION / DATE
| |
| : WCAP-16638-P Diablo Canyon Units 1 and 2 Replacement Steam Generator Program NSSS Licensing Report
| |
| : TFB 11-036 Training Feedback Form April 26, 2011
| |
| : STA-213 Use of RETRAN to Assess DCPP Plant Simulator Operability Testing Performance Calculation
| |
| : SCR-08-017 Simulator Deficiency March 13, 2008
| |
| : SCR 10-061 Simulator Deficiency December 13, 2010
| |
| : SCR 10-013 Simulator Deficiency March 3, 2010 Plant Drawing
| |
| : 108003 Unit 2 Feedwater System Sheet 3 75 Plant Drawing
| |
| : 108003 Unit 2 Feedwater System Sheet 4 61
| |
| : Attachment 1 PROCEDURES
| |
| : NUMBER TITLE REVISION / DATE Plant Drawing
| |
| : 2003 Unit 1 Feedwater System Sheet 3 81 Plant Drawing
| |
| : 2003 Unit 1 Feedwater System Sheet 3A 69 Plant Drawing
| |
| : 2003 Unit 1 Feedwater System Sheet 4 76
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| : OP1.DC10 Conduct of Operations 30 OP
| |
| : AP-15 Loss of Feedwater Flow, Unit 1 24 OP
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| : AP-15 Loss of Feedwater Flow, Unit 2 3
| |
| : OM7.ID4 Apparent Cause Evaluation 22
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| : OM7.ID3 Root Cause Evaluations 27
| |
| : OM7.ID1 Problem Identification and Resolution 40A
| |
| : OM4.ID14 Notification Review Team (NRT) 15
| |
| : DCM No. S-3B Auxiliary Feedwater System 20
| |
| : AD1.ID2 Procedure Process Control 34 A0681337 Simulator Study March 6, 2012
| |
| : 2011 Emergency Preparedness Program Audit May 23, 2011
| |
| : 2011 Professional Assessment and Consultation, Inc Audit November 21, 2011
| |
| : 2011 Special Processes & Inservice Inspection (ISI) / Inservice Testing (IST) Programs Audit November 30, 2011
| |
| : Equipment Reliability Self Assessment January 7, 2010
| |
| : Self-Assessment of Licensed Operator Requalification Program and Simulator February 28, 2011
| |
| : Emergency Planning Program Assessment April 15, 2010
| |
| : Human Performance Self-Assessment July 26, 2010
| |
| : Attachment 1 PROCEDURES
| |
| : NUMBER TITLE REVISION / DATE
| |
| : 2R15 Organizational Effectiveness Self-Assessment January 29, 2010
| |
| : Nuclear Industry Evaluation Program Diablo Canyon
| |
| : Quality Program Implementation Assessment March 26, 2010
| |
| : Ops Services Department Quarterly Performance Improvement Report November 3, 2011
| |
| : Outage Management Quarterly Performance Improvement Report 1 st
| |
| : Quarter 2011 April 1, 2011
| |
| : Unit 1 63A and B 4kV Vital & Non-Vital System Health Report February 2, 2012
| |
| : Unit 1 65A &B 120V Vital & Non Vital System Health Report February 2, 2012
| |
| : Unit 1 O3B Auxiliary Feedwater System Health Report January 25, 2012
| |
| : Unit 2 46 Loose Parts Monitoring System Health Report February 2, 2012
| |
| : Unit 2 64A and B 480V Vital & Non-Vital System Health Report February 2, 2012
| |
| : Unit 2 69 230kV System Health ReportFebruary 2, 2012
| |
| : Diablo Canyon Power Plant Nuclear Safety Culture Improvement Plan July 7, 2011
| |
| : PG&E Premier Survey (Site Vice President, DCPP) December
| |
| : 2011
| |
| : PG&E Premier Survey (Vice President Engineering & Projects, DCPP) December 2011
| |
| : 3Q11 Nuclear Safety Culture Monitoring Panel Report
| |
| : OP
| |
| : AP-15 Licensing Basis Impact Evaluation Screen January 3, 2012
| |
| : OP
| |
| : AP-15, Unit 1 History Summary details July 28, 2011 OP
| |
| : AP-15, Units 1 & 2 History Summary details March 6, 2008
| |
| : Attachment 1 PROCEDURES
| |
| : NUMBER TITLE REVISION / DATE
| |
| : OP
| |
| : AP-15, Units 1 & 2 History Summary details August 26, 2008
| |
| : OP
| |
| : AP-15, Unit 2 History Summary details July 28, 2011OM7.ID4 Apparent Cause Evaluation 22
| |
| : OM7.ID3 Root Cause Evaluation 27
| |
| : OM4-ID14 Notification Review Team 15
| |
| : TS3.ID2 Licensing Basis Impact Evaluations 31
| |
| : 3Q11 Nuclear Safety Culture Monitoring Panel Report
| |
| : MISCELLANEOUS DOCUMENTS
| |
| : NUMBER TITLE REVISION / DATE
| |
| : Apparent Cause Evaluation Manual (DCPP ACE Manual for Web.doc)
| |
| : DCPP Event Investigation Manual (DCPP Event Investigation Team Manual)
| |
| : Engineering 3
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| rd Quarter 2010 Performance Improvement Report Engineering 3
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| rd Quarter 2011 Performance Improvement Report Strategic Projects 3
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| rd Quarter 2010 Performance Improvement Report Strategic Projects 3
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| rd Quarter 2011 Performance Improvement Report
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| : PG&E Memo from Supervisor, Quality Verification regarding 2011 Technical Specification Audit
| |
| : October 5, 2011
| |
| : Diablo Canyon Nuclear Safety Culture Improvement Plan July 7, 2011
| |
| : Site Security Logs Attachment 1 AUDITS REPORTS
| |
| : TITLE
| |
| : 1R16 Design Changes
| |
| : 2010 Engineering Programs
| |
| : 2010 Fire Protection
| |
| : Learning Services Quarterly Performance Improvement Report Fourth Period - 09/28/11 - 12/06/11
| |
| : Learning Services Quarterly Performance Improvement Report Third Period - 07/01/11 - 09/27/11
| |
| : Learning Services 3
| |
| rd Quarter 2010 Performance Improvement Report Security Services Performance Improvement Report 07/01/11 - 10/18/11
| |
| : Security Services Quarterly Performance Improvement Report Period 2010 April 1, 2010 to September 30, 2010
| |
| : SYSTEM HEALTH REPORTS
| |
| : NUMBER TITLE
| |
| : U1 03A Feedwater
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| : U1 03B Auxiliary Feedwater
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| : U1 03E Digital Feedwater Control System
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| : U1 09 Safety Injection
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| : U1 10 Residual Heat Removal
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| : U1 14 Component Cooling Water
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| : U2 03B Auxiliary Feedwater
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| : U2 09 Safety Injection
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| : U2 14 Component Cooling Water
| |
| ===Notifications===
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| : 50043531
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| : Attachment 1
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| : Attachment 1
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| : 60024659
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| : 60026910
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| : Attachment 2 Information Request January 17, 2012 Biennial Problem Identification and Resolution Inspection -
| |
| : Diablo Canyon Power Plant Inspection Report Number 05000275/2012007 and 05000323/2012007
| |
| : This inspection will cover the period from January 1, 2010
| |
| to January 1, 2012.
| |
| : All requested information should be limited to this period unless otherwise specified.
| |
| : To the extent possible, the requested information should be provided electronically in Adobe PDF or Microsoft Office format.
| |
| : Lists of documents should be provided in Microsoft Excel or a similar sortable format.
| |
| : A supplemental information request will likely be sent during the week of February 20, 2012.
| |
| : Please provide the following no later than February 10, 2012:
| |
| : 1. Document Lists Note: for these summary lists, please include the document/reference number, the document title or a description of the issue, initiation date, and current status.
| |
| a. Summary list of all corrective action documents related to significant conditions adverse to quality that were opened, closed, or evaluated during the period
| |
| b. Summary list of all corrective action documents related to conditions adverse to quality that were opened or closed during the period
| |
| c. Summary lists of all corrective action documents which were upgraded or downgraded in priority/significance during the period
| |
| d. Summary list of all corrective action documents that subsume or "roll up" one or more smaller issues for the period
| |
| e. Summary lists of operator workarounds, engineering review requests and/or operability evaluations, temporary modifications, and control room and safety system deficiencies opened, closed, or evaluated during the period
| |
| f. Summary list of plant safety issues raised or addressed by the Employee Concerns Program (or equivalent)
| |
| g. Summary list of all Apparent Cause Evaluations completed during the period
| |
| h. Summary list of all Root Cause Evaluations planned or in progress but not complete at the end of the period.
| |
| : 2. Full Documents, with Attachments
| |
| a. Root Cause Evaluations completed during the period b. Quality assurance audits performed during the period Attachment 2
| |
| c. All audits/surveillances performed during the period of the Corrective Action Program, of individual corrective actions, and of cause evaluations
| |
| d. Corrective action activity reports, functional area self-assessments, and non-NRC third party assessments completed during the period (do not include INPO assessments)
| |
| e. Corrective action documents generated during the period for the following:
| |
| i. NCV's and Violations issued ii. LER's submitted
| |
| f. Corrective action documents generated for the following (for those that were evaluated but determined not to be applicable, provide a summary list):
| |
| i. NRC Information Notices, Bulletins, and Generic Letters issued or evaluated during the period ii. Part 21 reports issued or evaluated during the period iii. Vendor safety information letters (or equivalent) issued or evaluated during the period iv. Other external events and/or Operating Experience evaluated for applicability during the period
| |
| g. Corrective action documents generated for the following:
| |
| i. Emergency planning drills and tabletop exercises performed during the period ii. Maintenance preventable functional failures which occurred or were evaluated during the period iii. Adverse trends in equipment, processes, procedures, or programs which were evaluated during the period iv. Action items generated or addressed by plant safety review committees during the period
| |
| : Attachment 2 3. Logs and Reports
| |
| a. Corrective action performance trending/tracking information generated during the period and broken down by functional organization
| |
| b. Corrective action effectiveness review reports generated during the period
| |
| c. Current system health reports or similar information
| |
| d. Radiation protection event logs during the period
| |
| e. Security event logs and security incidents during the period (sensitive information can be provided by hard copy during first week on site)
| |
| f. Employee Concern Program (or equivalent) logs (sensitive information can be provided by hard copy during first week on site)
| |
| g. List of Training deficiencies, requests for training improvements, and simulator deficiencies for the period
| |
| : 4. Procedures
| |
| a. Corrective action program procedures, to include initiation and evaluation procedures, operability determination procedures, apparent and root cause evaluation/determination procedures, and any other procedures which implement the corrective action program.
| |
| b. Quality Assurance program procedures
| |
| c. Employee Concerns Program (or equivalent) procedures
| |
| d. Procedures which implement/maintain a Safety Conscious Work Environment
| |
| : 5. Other a. List of risk significant components and systems
| |
|
| |
|
| b. Organization charts for plant staff and long-term/permanent contractors Note: "Corrective action documents" refers to condition reports, notifications, action requests, cause evaluations, and/or other similar documents, as applicable.
| |
| : Attachment 2 This information should be uploaded on the Certrec IMS website no later than February 10, 2012.
| |
| : Please note that the NRC is not currently able to accept electronic documents on thumb drives or other similar digital media.
| |
| }} | | }} |
|
---|
Category:Inspection Report
MONTHYEARIR 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 05000275/20243012023-08-24024 August 2023 Notification of NRC Initial Operator Licensing Examination 05000275/2024301; 05000323/2024301 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) IR 05000275/20200042021-01-26026 January 2021 Integrated Inspection Report 05000275/2020004 and 05000323/2020004 IR 05000275/20204112020-12-22022 December 2020 Security Baseline Inspection Report 05000275/2020411 and 05000323/2020411 IR 05000275/20204102020-12-15015 December 2020 NRC Security Inspection Report 05000275/2020410 and 05000323/2020410 IR 05000275/20200102020-10-30030 October 2020 Biennial Problem Identification and Resolution Inspection Report 05000275/2020010 and 05000323/2020010 IR 05000275/20200032020-10-29029 October 2020 Integrated Inspection Report 05000275/2020003 and 05000323/2020003 IR 05000275/20200052020-09-0101 September 2020 Updated Inspection Plan for Diablo Canyon Power Plant, Units 1 and 2 (Report 05000275/2020005 and 05000323/2020005) IR 05000275/20200022020-07-22022 July 2020 Integrated Inspection Report 05000275/2020002 and 05000323/2020002 IR 05000275/20200012020-04-16016 April 2020 Integrated Inspection Report 05000275/2020001 and 05000323/2020001 2024-02-09
[Table view] Category:Letter
MONTHYEARIR 05000275/20230042024-02-0909 February 2024 Integrated Inspection Report 05000275/2023004 and 05000323/2023004 ML24002B1802024-01-29029 January 2024 LRA Audit Plan DCL-24-010, Nuclear Material Transaction Report for New Fuel2024-01-29029 January 2024 Nuclear Material Transaction Report for New Fuel ML24018A0152024-01-29029 January 2024 License Renewal Application Review Schedule Letter ML24017A2492024-01-24024 January 2024 Letter to Neil Peyron, Chairman, Tule River Tribe, Re. Diablo Canyon ML24024A1752024-01-24024 January 2024 Letter to Tribal Council San Luis Obispo County Chumash Indians on Section 106 Consultation and Scoping Process for the Environmental Review of Diablo Canyon Nuclear Plant, Unit 1 and 2 License Renewal Application ML24003A8902024-01-24024 January 2024 Letter to P. Gerfen - Diablo Canyon Notice of Intent to Conduct Scoping and Prepare an Environmental Impact Statement ML24012A1582024-01-24024 January 2024 Letter to Hon. Violet Sage Walker, Chairwoman Northern Chumash Tribal Council on Section 106 Consultation and Scoping Process for the Environmental Review of Diablo Canyon Nuclear Plant, Unit 1 and 2 License Renewal Application ML24012A0062024-01-24024 January 2024 Achp Scoping Letter for Diablo Canyon License Renewal ML24012A0552024-01-24024 January 2024 Letter to J. Polanco, Shpo, on Request to Initiate Section 106 Consultation and Scooping Process for the Environmental Review of Diablo Canyon Nuclear Plant, Unit 1 and 2 License Renewal Application ML24024A1562024-01-24024 January 2024 Letter to Hon. Gabe Frausto, Coastal Band of Chumash Indians on Section 106 Consultation and Scoping Process for the Environmental Review of Diablo Canyon Nuclear Plant, Unit 1 and 2 License Renewal Application ML24024A1652024-01-24024 January 2024 Letter to Hon. Mona Olivas Tucker, Yak Tityu Tityu Yak Tilhini Northern Chumas Indians on Section 106 Consultation and Scoping Process for the Environmental Review of Diablo Canyon Nuclear Plant, Unit 1 and 2 License Renewal Application ML24024A1612024-01-24024 January 2024 Letter Hon. Gary Pierce, Salian Tribe of Monterey and San Luis Obispo Counties on Section 106 Consultation and Scoping Process for the Environmental Review of Diablo Canyon Nuclear Plant, Unit 1 and 2 License Renewal Application ML24012A0362024-01-24024 January 2024 Request to Initiate Section 106 Consultation and Scoping Process for the Environmental Review License Renewal Application DCL-24-009, Nuclear Material Transaction Report for New Fuel2024-01-17017 January 2024 Nuclear Material Transaction Report for New Fuel DCL-24-008, 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 IR 05000275/20230112024-01-12012 January 2024 NRC License Renewal Phase 1 Inspection Report 05000275/2023011 DCL-23-129, Nuclear Material Transaction Report for New Fuel2023-12-27027 December 2023 Nuclear Material Transaction Report for New Fuel ML23326A0122023-12-21021 December 2023 12-21-23 Letter to the Honorable Byron Donalds from Chair Hanson Responds to Letter Regarding 2.206 Petition to Close Diablo Canyon Nuclear Power Plant, Unit 1 ML23341A0042023-12-19019 December 2023 LRA Acceptance Letter ML23352A2342023-12-18018 December 2023 Notification of Age-Related Degradation Inspection (05000275/2024014 and 05000323/2024014) and Request for Information 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 ML23355A0952023-12-0808 December 2023 License Renewal Application Online Reference Portal 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 ML23291A2702023-11-28028 November 2023 Letter to Nakia Zavalla, Shpo, the Santa Ynez Band of Chumash Indians; Re., Diablo Canyon ISFSI Initiating Section 106 Consultation ML23320A2442023-11-28028 November 2023 Letter to Kerri Vera, Director of Department of Environmental Protection, Tule River Tribe; Re., Diablo Canyon ISFSI Initiating Section 106 Consultation ML23325A1382023-11-27027 November 2023 ISFSI Tribal Letter to San Luis Obispo County Chumash Indians ML23325A1322023-11-27027 November 2023 ISFSI Tribal Letter to Salian Tribe of Montgomery, San Luis Obispo ML23325A1332023-11-27027 November 2023 ISFSI Tribal Letter to Yak Tityu Tityu Northern Chumash Indians ML23307A0062023-11-27027 November 2023 ISFSI Tribal Letter to Northern Chumash Tribal Council ML24003A7242023-11-27027 November 2023 Independent Safety Committee; Diab Lo Canyon Nuclear Power Plant Operations, Thirty-Third Annual Report on the Safety ML23325A1292023-11-27027 November 2023 ISFSI Tribal Letter to Coastal Band of Chumash ML23320A1502023-11-17017 November 2023 Individual Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, & Opportunity for Hearing (Exigent Circumstances) (EPID L-2023-LLA-0155) - LTR 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 ML23296A0982023-11-15015 November 2023 Notification and Request for Consultation Regarding Pacific Gas and Electric Diablo Canyon Independent Spent Fuel Storage Installation Material License Renewal Request (Docket Number: 72-26) 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 ML23293A1052023-11-14014 November 2023 Receipt and Availability of License Renewal Application IR 05000275/20230032023-11-13013 November 2023 Integrated Inspection Report 05000275/2023003 and 05000323/2023003 ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV DCL-23-118, License Renewal Application2023-11-0707 November 2023 License Renewal Application ML23318A2102023-10-31031 October 2023 Independent Safety Committee; Thirty-Third Annual Report on the Safety of Diablo Canyon Nuclear Power Plant Operations 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 IR 05000275/20240152023-10-10010 October 2023 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection (050002752024015 and 050003232024015) 2024-02-09
[Table view] |
Text
May 4, 2012
SUBJECT:
DIABLO CANYON POWER PLANT - NRC PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT 05000275/2012007 AND 05000323/2012007
Dear Mr. Conway
- On March 22, 2012, the U.S. Nuclear Regulatory Commission (NRC) completed a Problem Identification and Resolution biennial inspection at your Diablo Canyon Power Plant Units 1 and The enclosed inspection report documents the inspection results, which were discussed on March 22, 2012, with Mr. J. Becker and other members of your staf This inspection was an examination of activities conducted under your license as they relate to problem identification and resolution and compliance with the Commission's rules and regulations and the conditions of your licens Within these areas, the inspection involved examination of selected procedures and representative records, observations of activities, and interviews with personne Based on the inspection sample, the inspection team concluded that the implementation of the corrective action program and overall performance related to identifying, evaluating, and resolving problems at Diablo Canyon was generally effectiv Licensee identified problems were entered into the corrective action program at an appropriately low threshol Problems were effectively prioritized and evaluated commensurate with the safety significance of the problem Corrective actions were effectively implemented in a timely manner commensurate with their importance to safety and addressed the identified causes of problem Lessons learned from industry operating experience were effectively reviewed and applied when appropriat Audits and self-assessments were effectively used to identify problems and appropriate action Finally, Diablo Canyon effectively established and maintained a Safety Conscious Work Environmen No findings were identified during this inspectio In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of UNITED STATESNUCLEAR REGULATORY COMMISSIONREGION IV1600 EAST LAMAR BLVDARLINGTON, TEXAS 76011-4511 J. Conway - 2 -
NRC's Agencywide Document 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/ Ryan Alexander, Branch Chief (Acting), Technical Support Branch Division of Reactor Safety Docket Nos.: 05000275, 05000323 License Nos: DPR-80, DPR-82
Enclosure:
Inspection Report 05000275/2012007 and 05000323/2012007 w/Attachment: Supplemental Information
REGION IV Docket: 05000275, 05000323 License: DPR-80, DPR-82 Report: 05000275/2012007, 05000323/2012007 Licensee: Pacific Gas and Electric Company Facility: Diablo Canyon Power Plant Location: 71/2 Miles NW of Avila Beach, CA Dates: March 5 - 22, 2012 Team Leader: Charles Peabody, Resident Inspector, Wolf Creek Inspectors:
Bob Hagar, Senior Project Engineer Michael Peck, Senior Resident Inspector Nestor Makris, Project Engineer Approved By: Ryan Alexander, Branch Chief (Acting) Technical Support Branch Division of Reactor Safety
2 Enclosure
SUMMARY OF FINDINGS
IR 05000275/2012007 & 05000323/2012007; 3/05/2012 - 3/22/2012; Diablo Canyon Power Plant Biennial Baseline Inspection of the Identification and Resolution of Problems.
The team inspection was performed by the resident inspector at Wolf Creek (team lead), the senior resident inspector at Diablo Canyon, a Region IV based senior project engineer, and a Region IV based project engineer. The significance of most findings is indicated by their color (Green, White, Yellow, or Red) using Inspection Manual Chapter 0609, "Significance Determination Process." Findings for which the significance determination process does not apply may be Green or be assigned a severity level after NRC management review. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG 1649, "Reactor Oversight Process," Revision 4, dated December 2006.
Identification and Resolution of Problems
The team reviewed approximately 350 condition reports, work orders, engineering evaluations, root and apparent cause evaluations, and other supporting documentation to determine if problems were being properly identified, characterized, and entered into the corrective action program for evaluation and resolution. The team reviewed a sample of system health reports, self-assessments, trending reports and metrics, and various other documents related to the corrective action program.
Based on this sample, the team concluded the Diablo Canyon corrective action program implementation was generally effective. Diablo Canyon staff consistently identified problems and entered those problems into the corrective action program at an appropriately low threshold. Problems were prioritized and evaluated commensurate with the safety significance of the problems. Corrective actions were implemented in a timely manner and addressed the identified causes of problems.
The licensee appropriately evaluated industry-operating experience for relevance to the facility and entered applicable items in the corrective action program. The licensee used industry-operating experience when performing root cause and apparent cause evaluations. The licensee performed effective quality assurance audits and self-assessments which were self-critical, of an appropriate level of detail, and that identified issues and causes appropriate to the circumstances. The team determined that the licensee had established and maintained a safety-conscious work environment.
A. NRC-Identified and Self-Revealing Findings
No findings were identified.
B. Licensee-Identified Violations
None
REPORT DETAILS
OTHER ACTIVITIES (OA)
4OA2 Problem Identification and Resolution
The team based the following conclusions on the sample of corrective action documents that were initiated in the assessment period, which ranged from January 1, 2010, to the end of the onsite portion of the inspection on March 22, 2012.
.1 Assessment of the Corrective Action Program Effectiveness
a. Inspection Scope
The team reviewed approximately 350 condition reports and notifications, including associated root cause, apparent cause, and working group evaluations (low level), from approximately 35,000 that had been issued between January 1, 2010, and March 23, 2012, to determine if problems were being properly identified, characterized, and entered into the corrective action program for evaluation and resolution. The team reviewed a sample of system health reports, operability determinations, self-assessments, trending reports and metrics, and various other documents related to the corrective action program. The team evaluated the licensee's efforts in establishing the scope of problems by reviewing selected logs, work requests, self-assessment results, audits, system health reports, action plans, and results from surveillance tests and preventive maintenance tasks. The team reviewed work requests and attended the licensee's daily notification review team and the corrective action review board meetings to assess the reporting threshold, prioritization efforts, and significance determination process, as well as observing the interfaces with the operability assessment and work control processes when applicable. The team's review included verifying the licensee considered the full extent of cause and extent of condition for problems, as well as how the licensee assessed generic implications and previous occurrences. The team assessed the timeliness and effectiveness of corrective actions, completed or planned, and looked for additional examples of similar problems. The team conducted interviews with plant personnel to identify other processes that may exist where problems may be identified and addressed outside the corrective action program.
The team also reviewed corrective action documents that addressed past NRC-identified violations to ensure that the corrective actions addressed the issues as described in the inspection reports. The inspectors reviewed a sample of corrective actions closed to other corrective action documents to ensure that corrective actions were still appropriate and timely.
The team considered risk insights from both the NRC's and Diablo Canyon risk assessments to focus the sample selection and plant tours on risk significant systems and components. The team selected the significant areas/systems of seismic hazards and the intake structure. The samples reviewed by the team focused on, but were not limited to, these systems.
b. Assessments 1. Assessment - Effectiveness of Problem Identification The team determined that the licensee was effectively identifying problems at a low threshold and entering them into the corrective action program. The team also concluded that, in accordance with the licensee's corrective action program guidance and NRC requirements, the licensee properly identified those deficiencies that met the definition of a condition adverse to quality, and entered them into the corrective action program. The team did not identify any conditions adverse to quality that were not placed in the corrective action program.
The team identified five instances in which the licensee identified that a weakness in the corrective action program had prevented the licensee from successfully addressing a technical issue. In these examples, the licensee developed corrective actions to address the technical issue, but did not address the identified weakness in their corrective action program. Those instances were:
- SAPN 50428905 documents that after the licensee had identified a corrective action to revise a procedure to provide guidance on the potential impact of NRC Information Notices on the current licensing basis, the licensee had failed to fully implement that action. In that notification, the licensee developed corrective actions to complete the subject revision, but did not address why the licensee had failed to implement it fully.
- In the licensee's quality assurance audit of 1R16 Design Changes, the audit team concluded that the extent-of-condition evaluations had not adequately addressed the impact of the ineffective owner acceptance review process on other temporary design changes. The audit report also stated that the impact of the ineffective owner acceptance review process on the other design changes would be addressed in SAPN 50365188. In that notification, the auditor concluded that appropriate corrective actions had been taken (and would continue to be taken) to prevent or mitigate errors in vendor performed design work and strengthen the owner acceptance review process. However, SAPN 50365188 did not address why the earlier extent-of-condition evaluations had not adequately addressed the impact of the ineffective owner acceptance review process on the other design changes.
- The licensee's quality assurance audit of 2010 engineering programs identified that human performance problems had not been evaluated for impact on the post-maintenance testing program. To address that deficiency, the licensee initiated and completed SAPN 50306153. However, SAPN 50306153 did not address why human performance 5 Enclosure problems had not been evaluated for impact on the post-maintenance testing program.
- The licensee initiated SAPN 50353903 after receiving a non-cited violation associated with high-use fire doors. SAPN 50353903 notes that over the previous 3 years, the corrective action program had not been effective in identifying issues associated with high-use fire doors. It also stated that the corrective action program had not been effective in implementing corrective actions to address door-related issues. SAPN 50353903 indicated that evaluation of those issues was documented in SAPN 50357845. SAPN 50357845 was subsequently closed to SAPN 50358672. The team observed that SAPN 50358672 addressed the technical issues associated with high-use fire doors, but did not address the failures of the corrective action program that had been identified in SAPN 50353903.
- The licensee initiated SAPN 50367580 after receiving a different non-cited violation associated with high-use fire doors. The SAPN 50367580 record included a notation that action should be taken to complete an apparent-cause evaluation and to "determine why corrective actions conducted previously were not successful in preventing door failure." The SAPN 50367580 record documents that this SAPN was subsequently downgraded such that instead of an apparent cause evaluation, a work group evaluation would be completed. The resulting work group evaluation did not address the action quoted above.
The team concluded that these collective examples (an issue of concern), was not a finding, because it did not meet the more than minor screening criteria detailed on Manual Chapter 0612, Appendix B. However, the licensee entered this item into its corrective action program as SAPN 50464362 for resolution.
2. Assessment - Effectiveness of Prioritization and Evaluation of Issues The team determined that, in general, the licensee appropriately prioritized and evaluated issues commensurate with the safety significance of the identified problems during this assessment period. The team screened a number of condition reports that involved immediate operability and/or reportability issues, and including six condition reports that involved prompt operability reviews, to assess the quality, timeliness, and prioritization of operability assessments. The team noted that the immediate and prompt operability assessments reviewed were of appropriate thoroughness and were completed in a timely manner. Extent of cause and extent of condition evaluations were also appropriate to the circumstances.
3. Assessment - Effectiveness of Corrective Action Program Based on a sample of 99 condition report notifications, the team concluded that the licensee developed appropriate corrective actions to address problems. The 6 Enclosure team identified no corrective actions associated with conditions adverse to quality that were not completed in a timely manner.
Every team member noted instances in which the licensee's efforts to evaluate and correct identified problems were documented in several notifications that in many cases were not referenced to each other. Examples include:
- The licensee's response to a non-cited violation for a failure to follow a procedure included SAPN 50299740, Order 60023821, and related SAPNs 50259493, 50215872-30, 50087077, and 50181167.
- The licensee's response to a non-cited violation for a failure to appropriately evaluate and correct a condition adverse to quality included SAPN 50311167, Order 60025142, related SAPNs 50309610, 50310081, 50308225, 50307757, and 50311719, and related order 60025167.
The team considered that the practice of compiling corrective action program records in this way might result in the unintended consequence of reducing the accessibility and usefulness of those records as resources that could provide insights to assist future efforts at problem resolution.
.2 Assessment of the Use of Operating Experience
a. Inspection Scope
The team examined the licensee's program for reviewing industry operating experience, including reviewing the governing procedure and self assessments. A sample of 23 operating experience notifications that were issued during the assessment period were reviewed to assess whether the licensee had appropriately evaluated the notification for relevance to the facility. The team then examined whether the licensee had entered those items into the corrective action program and assigned actions to address the issues. The team reviewed a sample of root cause evaluations and corrective action documents to verify if the licensee had appropriately included industry-operating experience.
b. Assessment Overall, the team determined that the licensee was adequately evaluating industry-operating experience for relevance to the facility, based on the sample size noted. The licensee entered the 23 applicable items into the corrective action program and evaluated them in accordance with station procedures.
.3 Assessment of Self-Assessments and Audits
a. Inspection Scope
The team reviewed a sample of 45 licensee self-assessments, surveillances, and audits to assess whether the licensee was regularly identifying performance trends and 7 Enclosure effectively addressing them. The team reviewed audit reports to assess the effectiveness of assessments in specific areas. The team evaluated the use of self- and third party assessments, the role of the quality assurance department, and the role of the performance improvement group. The specific self-assessment documents reviewed are listed in the Attachment.
b. Assessment The team concluded that the licensee had an effective self-assessment process. Diablo Canyon self-assessments were timely, self-critical, of an appropriate level of detail, identified issues, and causes appropriate to the circumstance. The Diablo Canyon Quality Assurance internal audits of various station departments were also timely, self critical, of an appropriate level of detail, and identified issues and causes appropriate to the circumstances. The Diablo Canyon Performance Improvement Group organized the assessments within the corrective action program, accurately tracked, and trended information and themes across station departments. The inspection team review of various third party assessments determined that Diablo Canyon regularly incorporated feedback from external sources and takes related corrective action as appropriate.
.4 Assessment of Safety-Conscious Work Environment
a. Inspection Scope
The inspection team conducted individual interviews with 37 licensee personnel. The interviewees represented various functional organizations and ranged across contractor, staff, and supervisor levels. These interviews were designed to elicit a qualitative assessment of the degree to which the participants believed the licensee had established and maintained a safety-conscious work environment at Diablo Canyon and were based upon the NRC's definition of a safety-conscious work environment:
An environment in which employees feel free to raise safety concerns, both to their management and to the NRC, without fear of retaliation and where such concerns are promptly reviewed, given the proper priority based on their potential safety significance, and appropriately resolved with timely feedback to employees.
b. Assessment The team determined that the licensee had established and maintained a safety-conscious work environment. Based upon the responses received during the licensee personnel interviews, the team concluded that Diablo Canyon had established and was maintaining an environment where workers felt free to raise safety concerns, both to their management and to the NRC, without fear of retaliation. Licensee staff interviewed generally thought highly of their work environment. All groups understood the primary importance of safety; although schedule and budget concerns existed, none of the interviewed licensee personnel indicated that they felt these factors overshadowed nuclear safety concerns. Most of the Diablo Canyon personnel interviewed desired to participate personally in continuous improvement in the areas of safety, plant performance, and knowledge management.
8 Enclosure
4OA6 Meetings
Exit Meeting Summary
On March 22, 2012, the team presented the inspection results to Mr. J. Becker, Site Vice President, and other members of the licensee staff. The licensee acknowledged the issues presented. The inspector asked the licensee whether any materials examined during the inspection should be considered proprietary. No proprietary information was retained.
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SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee Personnel
- T. Baldwin, Regulatory Services Manager
- J. Becker, Site Vice President
- G. Close, Problem Prevention and Resolution Manager
- S. David, Site Services Director
- T. Garrity, Corrective Action Program Supervisor
- P. Gerfen, Operations Manager
- R. Simmons, Engineering Manager
- J. Welsh, Station Director
NRC personnel
- R. Alexander, Branch Chief (Acting)
LIST OF DOCUMENTS REVIEWED