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| | issue date = 05/13/2013 | | | issue date = 05/13/2013 |
| | title = IR 05000269-13-008, 05000270-13-008 & 05000287/2013-008, 4/1-5/2013 - 4/15-18/2013, Oconee Nuclear Station, Units 1, 2 and 3, Biennial Inspection of the Problem Identification and Resolution Program | | | title = IR 05000269-13-008, 05000270-13-008 & 05000287/2013-008, 4/1-5/2013 - 4/15-18/2013, Oconee Nuclear Station, Units 1, 2 and 3, Biennial Inspection of the Problem Identification and Resolution Program |
| | author name = Rapp C W | | | author name = Rapp C |
| | author affiliation = NRC/RGN-II/DRP/RPB7 | | | author affiliation = NRC/RGN-II/DRP/RPB7 |
| | addressee name = Batson S | | | addressee name = Batson S |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303-1257 May 13, 2013 Mr. Scott Batson Site Vice President | | {{#Wiki_filter:May 13, 2013 |
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| Duke Energy Carolinas, LLC Oconee Nuclear Station 7800 Rochester Highway Seneca, SC 29672
| | ==SUBJECT:== |
| | | OCONEE NUCLEAR STATION - NRC PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT 05000269/2013008, 05000270/2013008, 05000287/2013008 |
| SUBJECT: OCONEE NUCLEAR STATION - NRC PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT 05000269/2013008, 05000270/2013008, 05000287/2013008 | |
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| ==Dear Mr. Batson:== | | ==Dear Mr. Batson:== |
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| The inspection was an examination of activities conducted under your license as they relate to the identification and resolution of problems, and 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 representative records, observations of plant equipment and activities, and interviews with personnel. | | The inspection was an examination of activities conducted under your license as they relate to the identification and resolution of problems, and 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 representative records, observations of plant equipment and activities, and interviews with personnel. |
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| 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 Oconee Nuclear Station Units 1, 2, and 3 was adequate. Licensee identified problems were entered into the corrective action program at a low threshold. Problems were generally prioritized and evaluated commensurate with the safety significance of the problems. Corrective actions were generally implemented in a timely manner commensurate with their importance to safety and addressed the identified causes of problems. Lessons learned from the industry operat ing experience were generally reviewed and applied when appropriate. Audits and self-assessments were effectively used to identify problems and appropriate actions. In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be available electr onically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of the NRC's document system (ADAMS). Adams is accessible from the NRC Web site at http://www.nrc.gov/reading- rm/adams.html (the Public Electronic Reading Room). | | 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 Oconee Nuclear Station Units 1, 2, and 3 was adequate. Licensee identified problems were entered into the corrective action program at a low threshold. Problems were generally prioritized and evaluated commensurate with the safety significance of the problems. Corrective actions were generally implemented in a timely manner commensurate with their importance to safety and addressed the identified causes of problems. Lessons learned from the industry operat ing experience were generally reviewed and applied when appropriate. Audits and self-assessments were effectively used to identify problems and appropriate actions. In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be available electr onically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of the NRC's document system (ADAMS). Adams is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). |
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| Sincerely, | | Sincerely, |
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| Docket Nos.: 50-269, 50-270, 50-287 License Nos.: DPR-38, DPR-47, DPR-55 | | Docket Nos.: 50-269, 50-270, 50-287 License Nos.: DPR-38, DPR-47, DPR-55 |
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| Enclosure: INSPECTION REPORT 05000269/2013008, 05000270/2013008, and 05000287/2013008 w/Attachment: Supplemental Information | | ===Enclosure:=== |
| | | INSPECTION REPORT 05000269/2013008, 05000270/2013008, and 05000287/2013008 w/Attachment: Supplemental Information |
| cc w/encl. (see page 3)
| |
| | |
| ML13133A087________ X SUNSI REVIEW COMPLETE X FORM 665 ATTACHED OFFICE RII:DRP RII:DRP RII:DRP RII:DRP RII:DRP SIGNATURE Via telecom Via email Via email Via email CWR:/RA/ NAME LSuggs RPatterson NPitoniak NStaples CRapp DATE 5/13/2013 5/8/2013 5/1/2013 5/3/2013 5/13/2013 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO cc w/encl:
| |
| Kent Alter Regulatory Compliance Manager Oconee Nuclear Station
| |
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| Duke Energy Carolinas, LLC Electronic Mail Distribution
| |
| | |
| Lara S. Nichols Vice President-Legal Duke Energy Corporation Electronic Mail Distribution
| |
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| Luellen B. Jones Fleet Licensing Engineer
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| Duke Energy Carolinas, LLC Electronic Mail Distribution
| |
| | |
| M. Christopher Nolan Fleet Safety Assurance Manager
| |
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| Duke Energy Carolinas, LLC Electronic Mail Distribution
| |
| | |
| Sandra Threatt, Manager Nuclear Response and Emergency Environmental Surveillance
| |
| | |
| Bureau of Land and Waste Management Department of Health and Environmental
| |
| | |
| Control Electronic Mail Distribution
| |
| | |
| Senior Resident Inspector U.S. Nuclear Regulatory Commission Oconee Nuclear Station
| |
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| 7812B Rochester Hwy Seneca, SC 29672
| |
| | |
| Terry L. Patterson
| |
| | |
| Safety Assurance Manager
| |
|
| |
|
| Duke Energy Carolinas, LLC Electronic Mail Distribution
| | REGION II== |
| | |
| Charles Brinkman
| |
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| Director Washington Operations Westinghouse Electric Company, LLC Electronic Mail Distribution
| |
| | |
| Tom D. Ray Engineering Manager Oconee Nuclear Station Duke Energy Carolinas, LLC Electronic Mail Distribution
| |
| | |
| County Supervisor of Oconee County 415 S. Pine Street Walhalla, SC 29691-2145
| |
| | |
| W. Lee Cox, III Section Chief Radiation Protection Section N.C. Department of Environmental
| |
| | |
| Commerce & Natural Resources Electronic Mail Distribution Letter to Scott Batson from Curtis W. Rapp dated May 13, 2013.
| |
| | |
| SUBJECT: OCONEE NUCLEAR STATION - NRC PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT 05000269/2013008, 05000270/2013008, 05000287/2013008
| |
| | |
| Distribution w/encl:
| |
| C. Evans, RII EICS L. Douglas, RII EICS OE Mail RIDSNRRDIRS PUBLIC RidsNrrPMOconee Resource Enclosure U.S. NUCLEAR REGULATORY COMMISSION
| |
| | |
| ==REGION II==
| |
|
| |
|
| Docket Nos.: 50-269, 50-270, 50-287 | | Docket Nos.: 50-269, 50-270, 50-287 |
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| ==LIST OF DOCUMENTS REVIEWED== | | ==LIST OF DOCUMENTS REVIEWED== |
| ===Procedures===
| | |
| : SOMP 02-01, Safety Tagging and Configuration Control, Rev. 16
| |
| : IMP-ON-2012-00531, Mulsifyre's Isolated for HPSW Strainer PM OP/0/A/1104/011, High Pressure Service Water, Rev. 90 OP/0/A/1104/048, TB Sump Operation
| |
| : NSD 316, Fire Protection and Impairment and Surveillance, Rev. 10
| |
| : NSD 316, Fire Protection and Impairment and Surveillance, Rev. 13
| |
| : NSD 506 Appendix C Workaround Aggregate Assessment completed 2/4/13, Rev. 5
| |
| : NSD 506, Operator Workarounds and Control Room Deficiencies, Rev. 5
| |
| : NSD 208, Problem Investigation Program, Rev. 32
| |
| : NSD-212, Cause Analysis, Rev. 27
| |
| : NSD-602, Employee Concerns Program, Rev. 6
| |
| : NSD-203, Operability/Functionality Determination, Rev. 26
| |
| : NSD-204, Operating Experience Program, Rev. 15
| |
| : NSD-208, Problem Investigation Program, Rev. 38
| |
| : NSD-607, Self Assessments and Benchmarking, Rev. 17
| |
| : NSD-125, Performance Improvement, Rev. 5
| |
| : NSD-120, Equipment Reliability Process, Rev. 6
| |
| : NSD-331, Insulated Cables Aging Management Program, Rev. 0 OMP 1-32, Configuration Control for Components Prone to Mispositioning, Re.v 3
| |
| : OMP 2-16 Attachment C, Unit Shift Turnover Sheet from 4/4/2013
| |
| : IP-0-A-2001-003A, Inspection and Maintenance of 4.16KV and 6.9KV ACB, Rev. 50
| |
| : IP-0-A-2001-003-H, Refurbishing 5HK and 7.5HK Air Circuit Breakers, Rev. 43
| |
| : Problem Investigation Program (PIPs)
| |
| : O-12-07940
| |
| : O-11-11449
| |
| : O-12-04008
| |
| : O-12-01269
| |
| : O-08-06525
| |
| : O-12-04368
| |
| : O-12-08202
| |
| : O-12-11235
| |
| : O-10-01685
| |
| : O-10-01674
| |
| : O-12-06827
| |
| : O-12-11522
| |
| : O-12-10338
| |
| : O-12-01876
| |
| : O-11-00218
| |
| : O-11-11449
| |
| : O-12-01906
| |
| : O-09-08779
| |
| : M-10-00655
| |
| : O-10-01565
| |
| : O-10-09834
| |
| : O-10-09847
| |
| : O-11-00016
| |
| : O-11-00387
| |
| : O-11-00388
| |
| : O-11-00660
| |
| : O-11-00751
| |
| : O-11-01215
| |
| : O-11-01321
| |
| : O-11-05143
| |
| : O-11-06162
| |
| : O-11-06292
| |
| : O-11-06984
| |
| : O-11-08215
| |
| : O-11-08999
| |
| : O-11-10036
| |
| : O-11-10039
| |
| : O-11-10040
| |
| : O-11-10473
| |
| : O-11-11635
| |
| : O-11-13667
| |
| : O-11-14680
| |
| : O-11-14686
| |
| : O-11-14975
| |
| : O-11-15134
| |
| : O-11-15285
| |
| : O-11-15459
| |
| : O-12-00120
| |
| : O-12-00123
| |
| : O-12-00175
| |
| : O-12-00224
| |
| : O-12-00252
| |
| : O-12-00281
| |
| : O-12-00370
| |
| : O-12-00384
| |
| : O-12-01412
| |
| : O-12-01537
| |
| : O-12-01546
| |
| : O-12-01581
| |
| : O-12-01590
| |
| : O-12-02285
| |
| : O-12-02685
| |
| : O-12-02732
| |
| : O-12-02754
| |
| : O-12-03028
| |
| : O-12-03237
| |
| : O-12-03406
| |
| : O-12-03409
| |
| : O-12-03565
| |
| : O-12-03614
| |
| : O-12-03726
| |
| : O-12-03856
| |
| : O-12-04017
| |
| : O-12-04036
| |
| : O-12-04318
| |
| : O-12-04580
| |
| : O-12-04654
| |
| : O-12-05151
| |
| : O-12-05508
| |
| : O-12-05541
| |
| : O-12-05680
| |
| : O-12-05988
| |
| : O-12-07937
| |
| : O-12-07994
| |
| : O-12-08011
| |
| : O-12-08295
| |
| : O-12-08650
| |
| : O-12-09197
| |
| : O-12-09985
| |
| : O-12-10000
| |
| : O-12-10212
| |
| : O-12-10268
| |
| : O-12-10449
| |
| : O-12-10969
| |
| : O-12-11115
| |
| : O-12-11313
| |
| : O-12-11509
| |
| : O-12-11556
| |
| : O-12-11623
| |
| : O-12-11964
| |
| : O-12-12236
| |
| : O-12-12281
| |
| : O-12-12480
| |
| : O-12-12499
| |
| : O-12-12807
| |
| : O-12-12979
| |
| : O-12-13121
| |
| : O-12-13133
| |
| : O-12-13169
| |
| : O-12-13589
| |
| : O-12-13772
| |
| : O-12-13822
| |
| : O-12-13846
| |
| : O-12-13923
| |
| : O-12-14051
| |
| : O-12-14345
| |
| : O-12-14850
| |
| : O-13-00175
| |
| : O-13-00719
| |
| : O-13-01935
| |
| : O-13-02043
| |
| : O-13-03267
| |
| : G-12-01740
| |
| : G-12-01754
| |
| : G-12-00264
| |
| : G-13-00507
| |
| : O-10-01680
| |
| : O-11-10962
| |
| : O-11-11438
| |
| : O-11-11015
| |
| : O-11-11510
| |
| : O-11-10907
| |
| : O-11-15323
| |
| : O-11-11800
| |
| : O-12-13700
| |
| : Attachment
| |
| : O-12-00831
| |
| : O-12-01156
| |
| : O-12-10874
| |
| : O-12-11938
| |
| : O-12-01340
| |
| : O-12-01551
| |
| : O-12-01399
| |
| : O-12-06062
| |
| : O-12-01399
| |
| : O-12-01346
| |
| : O-12-01340
| |
| : O-12-03790
| |
| : O-12-00577
| |
| : O-12-03273
| |
| : O-12-10817
| |
| : O-13-03647
| |
| : O-13-03462
| |
| : O-12-02037
| |
| : O-12-13014
| |
| : O-12-13121
| |
| : O-10-08395
| |
| : O-11-15172
| |
| : G-12-01901
| |
| : O-11-15055
| |
| : G-12-00693
| |
| : O-12-07940
| |
| : O-12-03457
| |
| : O-12-01998
| |
| : O-12-03114
| |
| ===Operating Experience===
| |
| : Documents
| |
| : O-11-59916
| |
| : O-11-59955
| |
| : O-11-59917
| |
| : O-11-59919
| |
| : G-12-60451
| |
| : O-12-61027
| |
| : O-12-61801
| |
| : O-12-09000
| |
| : O-12-62064
| |
| : O-11-59977
| |
| : O-12-60095
| |
| : G-12-1416
| |
| : G-12-60208
| |
| : O-12-61612
| |
| : PIPs Generated as a Result of Inspection
| |
| : O-13-03567
| |
| : O-13-03616
| |
| : O-13-03662
| |
| : O-13-03679
| |
| : O-13-03727
| |
| : O-13-03746
| |
| : O-13-04158
| |
| : O-13-04162
| |
| : O-13-04167
| |
| : O-13-04213
| |
| : O-13-04216
| |
| : O-13-04262
| |
| : Self-Assessments Independent Nuclear Oversight-Audit Oconee Corrective Action Program Audit 12-6, 3/7/2012
| |
| : Independent Nuclear Oversight-Audit Oconee Corrective Action Program Audit 10-3, 3/18/2010 Corrective Action Program Assessment, O-12-03114
| |
| ===Other Documents===
| |
| : LER 270/2008-02, Several MSSVs Slightly Out of Tolerance, Rev. 1
| |
| : TS-OC-SSS-LPW/HPW, High Pressure Service Water System Description Summary, Rev. 7 Quick Cause Evaluation (QCE) User's Guide, Rev. 3 Apparent Cause (ACE) User's Guide, Rev. 6 Root Cause Analysis User's Guide, Rev. 15
| |
| : Cause Analysis Certification List Scaffold Inspection Correspondence (Email), 4/2/13
| |
| : PT/1/A/0600/010, Reactor Coolant Leakage, Rev. 94,
| |
| : PT/0/A/0230/001, Radiation Monitor Check, Rev. 165 HP/0/A/1008/005, RIA Setpoints, Rev. 9
| |
| : PIP 12-3409 and
| |
| : PIP 3614 Root Cause Team Charter Duke Energy Carolinas Topical Report Quality Assurance Program, Duke-1-A, Amendment 39
| |
| : Duke Energy,
| |
| : LER 269/2011-04, Rev. 0, 6/1/2011
| |
| : ETQS 2200.0, Employee Training and Qualification System Standard Training Committee Administration, Rev. 10, 2/27/13 ETQS 5300.0, Employee Training and Qualification System Standard On-the-Job Training and Task Performance Evaluation, Rev. 6, 12/17/12
| |
| : Attachment
| |
| : OTP 5405.0, Development, Administration, and Security of Exams, Rev. 31, 2/8/13
| |
| : OTP 5701.0, Simulator training and Evaluation, Rev. 30a, 2/25/13 Curriculum Review Committee Agenda, 2/7/12
| |
| : Curriculum Review Committee draft minutes, 6/12/12
| |
| : Curriculum Review Committee minutes, 8/7/12
| |
| : Curriculum Review Committee minutes, 9/25/12
| |
| : Reactor Coolant System health reports, for 2012
| |
| : AD-EG-ALL-1202, Preventative Maintenance Administrative Guidance, Rev. 0
| |
| : AM-0-A-1300-059, Pump-Submersible-Emergency SSF Water Supply-Installation and Removal,
| |
| : Rev. 11
| |
| : OSC-2790, HVAC Calculations for Chillers A&B, Rev.2
| |
| : OSC-5930, Unit 1 Motor Starter Circuit Voltage and Fuse Adequacy Calculation, Rev. 13
| |
| : OSS-0254.00-00-2020, Standby Shutdown Facility 125VDC Essential Power System, Rev. 9
| |
| : OFD-099A-1.1, Symbols for Flow Diagrams, Rev. 14
| |
| : OCFD-OPS-HPSW-1, Composite Diagram HPSW System, Rev. 0
| |
| : OSC-10791, Documentation of ONS Turbine Building Flood Assessment, Rev. 0
| |
| : ECP Independent Survey Letter to from T. Preston Gillespie, Vice President ONS to U.S. NRC Reply to Notice of
| |
| : Violation, 2/27/12
| |
| : ONS PIOC Certification Completion Status
| |
| : ONS Central Screening Team Certification Completion Status
| |
| : ONS Root Cause Evaluation Core Team Certification Completion Status
| |
| : ONS Apparent Cause Evaluation Core Team Certification Completion Status
| |
| }} | | }} |
|
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Category:Inspection Report
MONTHYEARIR 05000269/20243012024-08-0808 August 2024 – Operator Licensing Examination Approval 05000269/2024301, 05000270/2024301, and 05000287/2024301 IR 05000269/20240022024-07-25025 July 2024 Integrated Inspection Report 05000269/2024002 and 05000270/2024002 and 05000287/2024002 IR 05000269/20240012024-05-0303 May 2024 Integrated Inspection Report 05000269/2024001, 05000270/2024001 and 05000287/2024001 IR 05000269/20244022024-04-24024 April 2024 Security Baseline Inspection Report 05000269/2024402 and 05000270/2024402 and 05000287/2024402 IR 05000269/20244012024-03-28028 March 2024 – Security Baseline Inspection Report 05000269-2024401 and 05000270-2024401 and 05000287-2024401 IR 05000269/20230062024-02-28028 February 2024 Annual Assessment Letter for Oconee Nuclear Station Units 1, 2 and 3 - (NRC Inspection Report 05000269/2023006, 05000270/2023006, and 05000287/2023006) IR 05000269/20240102024-02-21021 February 2024 Information Request- Oconee Nuclear Station, Age Related Degradation Inspection 05000269/2024010, 05000270/2024010 and 05000287/2024010 IR 05000269/20230042024-02-13013 February 2024 Integrated Inspection Report 05000269/2023004, 05000270/2023004, and 05000287/2023004; and Inspection Report 07200040/2023001 ML23331A7982023-12-14014 December 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report (01R32) IR 05000269/20230032023-11-14014 November 2023 Integrated Inspection Report 05000269/2023003, 05000270/2023003, and 05000287/2023003; and IR 07200040/2023001; and Exercise of Enforcement Discretion IR 05000269/20230112023-08-25025 August 2023 Comprehensive Engineering Team Inspection Report 05000269/2023011 and 05000270/2023011 and 05000287/2023011 IR 05000269/20230052023-08-25025 August 2023 Updated Inspection Plan for Oconee Nuclear Station Units 1, 2 and 3 (Report 05000269/2023005, 05000270/2023005, and 05000287/2023005) IR 05000269/20230022023-07-28028 July 2023 Integrated Inspection Report 05000269/2023002, 05000270/2023002 and 05000287/2023002 IR 05000269/20230102023-07-19019 July 2023 Biennial Problem Identification and Resolution Inspection Report 05000269/2023010 and 05000270/2023010 and 05000287/2023010 and Notice of Violation RA-23-0128, Refuel 32 (O1R32) Steam Generator Tube Inspection Report2023-05-18018 May 2023 Refuel 32 (O1R32) Steam Generator Tube Inspection Report IR 05000269/20230012023-05-12012 May 2023 Integrated Inspection Report 05000269/2023001 and 05000270/2023001 and 05000287/2023001 IR 05000269/20234012023-04-14014 April 2023 Security Baseline Inspection Report 05000269 2023401 and 05000270 2023401 and 05000287 2023401 IR 05000269/20220062023-03-0101 March 2023 Annual Assessment Letter for Oconee Nuclear Nuclear Station, Units 1, 2 and 3 (NRC Inspection Report 05000269/2022006, 05000270/2022006, and 05000287/2022006) ML23037A0772023-02-0606 February 2023 402 Cyber Notification and RFI Letter Final IR 05000269/20220042023-02-0202 February 2023 Integrated Inspection Report 05000269 2022004 and 05000270/2022004 and 05000287/2022004 IR 05000269/20220032022-11-0707 November 2022 Integrated Inspection Station 05000269/2022003 and 05000270/2022003 and 05000287/2022003 IR 05000269/20220112022-09-26026 September 2022 NRC Inspection Report 05000269/2022011 and 05000270/2022011 and 05000287/2022011 IR 05000269/20224012022-08-26026 August 2022 Material Control and Accounting Program Inspection Report 05000269/2022401 and 05000270/2022401 and 05000287/2022401 (OUO Removed) IR 05000269/20220052022-08-26026 August 2022 Updated Inspection Plan for Oconee Nuclear Station, Units 1, 2 and 3 - NRC Inspection Report 05000269/2022005, 05000270/2022005, and 05000287/2022005 IR 05000270/20220022022-07-29029 July 2022 Integrated Inspection Report 05000269/ 2022002 and 05000270/2022002 and 05000287/2022002 IR 05000269/20220102022-06-30030 June 2022 Triennial Fire Protection Inspection Report 05000269/2022010 and 05000270/2022010 and 05000287/2022010 IR 05000269/20224032022-05-0404 May 2022 Security Baseline Target Set Inspection Report 05000269/2022403 and 05000270/2022403 and 05000287/2022403 IR 05000269/20220012022-05-0404 May 2022 Integrated Inspection Report 05000269/2022001, 05000270/2022001 and 05000287/2022001 IR 05000269/20224042022-04-27027 April 2022 Security Baseline Inspection Report 05000269/2022404 and 05000270/2022404 and 05000287/2022404 IR 05000269/20223012022-03-0707 March 2022 Notification of Licensed Operator Initial Examination 05000269/2022301, 05000270/2022301 and 05000287/2022301 IR 05000269/20210062022-03-0202 March 2022 Annual Assessment Letter for Oconee Nuclear Station, Units 1, 2, and 3 (Report 05000269/2021006, 05000270/2021006, and 05000287/2021006) IR 05000269/20220122022-02-24024 February 2022 Safety Conscious Work Environment Issue of Concern Followup Report 05000269/2022012 and 05000270/2022012 and 05000287/2022012 IR 05000269/20224022022-02-16016 February 2022 Security Baseline Inspection Report 05000269/2022402 and 05000270/2022402 and 05000287/2022402 IR 05000269/20210042022-02-14014 February 2022 Integrated Inspection Report 05000269/2021004 and 05000270/2021004 and 05000287/2021004 and Apparent Violation IR 05000269/20210032021-10-28028 October 2021 Integrated Inspection Report 05000269/2021003 and 05000270/2021003 and 05000287/2021003 IR 05000269/20210102021-09-17017 September 2021 Design Basis Assurance Inspection (Programs) Inspection Report 05000269/2021010 and 05000270/2021010 and 05000287/2021010 IR 05000269/20210052021-08-26026 August 2021 Updated Inspection Plan for Oconee Nuclear Station Units 1, 2, and 3 (NRC Inspection Report 05000269/2021005, 05000270/2021005, and 05000287/2021005) IR 07200004/20210012021-08-26026 August 2021 Operation of an Independent Spent Fuel Storage Installation Report 07200004/2021001 IR 05000269/20210022021-08-0404 August 2021 Integrated Inspection Report 05000269/2021002 and 05000270/2021002 and 05000287/2021002 IR 05000269/20213012021-07-0606 July 2021 NRC Operator License Examination Report 05000269/2021301, 05000270/2021301, and 05000287/2021301 IR 05000269/20210112021-06-0202 June 2021 Biennial Problem Identification and Resolution Inspection Report 05000269/2021011 and 05000270/2021011 and 05000287/2021011 IR 05000269/20210012021-04-23023 April 2021 Integrated Inspection Report 05000269/2021001 and 05000270/2021001 and 05000287/2021001 IR 05000269/20214012021-04-22022 April 2021 Security Baseline Inspection Report 05000269/2021401, 05000270/2021401 and 05000287/2021401 (U) IR 05000269/20200062021-03-0303 March 2021 Annual Assessment Letter for Oconee Nuclear Station Units 1, 2, & 3 NRC Inspection Report 05000269/2020006, 05000270/2020006, & 05000287/2020006 IR 05000269/20200042021-02-22022 February 2021 Reissue- Oconee Nuclear Station Integrated Inspection Report 05000269/2020004, 05000270/2020004, 05000287/2020004 ML21036A0012021-02-0404 February 2021 Integrated Inspection Report 05000269/2020004 and 05000270/2020004 and 05000287/2020004 IR 05000269/20200102021-01-22022 January 2021 NRC Design Bases Assurance Inspection (Team) Report 05000269/2020010 and 05000270/2020010 and 05000287/2020010 and Notice of Violation IR 05000269/20204012020-11-13013 November 2020 Security Baseline Inspection Report 05000269/2020401 and 05000270/2020401 and 05000287/2020401 IR 05000269/20200032020-11-0404 November 2020 Integrated Inspection Report 05000269/2020003, 05000270/2020003, 05000287/2020003, and 07200004/2020002 IR 05000269/20204202020-10-15015 October 2020 Security Inspection Report 05000269/2020420, 05000270/2020420 and 05000287/2020420 2024-08-08
[Table view] Category:Letter
MONTHYEARIR 05000269/20243012024-08-0808 August 2024 – Operator Licensing Examination Approval 05000269/2024301, 05000270/2024301, and 05000287/2024301 IR 05000269/20240022024-07-25025 July 2024 Integrated Inspection Report 05000269/2024002 and 05000270/2024002 and 05000287/2024002 ML24192A1312024-07-15015 July 2024 Licensed Operator Positive Fitness-For-Duty Test ML24183A0972024-07-12012 July 2024 ISFSI; Catawba 1, 2 & ISFSI; McGuire 1, 2 & ISFSI; Oconee 1, 2, 3 & ISFSI; Shearon Harris 1; H. B. Robinson 2 & ISFSI; and Radioactive Package Shipping Under 10 CFR 71 (71-266 & 71-345) – Review of QA Program Changes EPID L-2024-LLQ-0002 ML24183A2352024-06-29029 June 2024 Update 3 to Interim Report Regarding a Potential Defect with Schneider Electric Medium Voltage Vr Type Circuit Breaker Part Number V5D4133Y000 ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc IR 05000269/20240012024-05-0303 May 2024 Integrated Inspection Report 05000269/2024001, 05000270/2024001 and 05000287/2024001 IR 05000269/20244022024-04-24024 April 2024 Security Baseline Inspection Report 05000269/2024402 and 05000270/2024402 and 05000287/2024402 ML24108A0792024-04-16016 April 2024 EN 57079 Paragon Energy Solutions Email Forwarding Part 21 Interim Report Re Potential Defect with Schneider Electric Medium Voltage Vr Type Circuit Breaker Part Number V5D4133Y000 IR 05000269/20244012024-03-28028 March 2024 – Security Baseline Inspection Report 05000269-2024401 and 05000270-2024401 and 05000287-2024401 ML24088A3052024-03-25025 March 2024 Fws to NRC, Agreement with Nlaa Determination for Tricolored Bat for Oconee Lr IR 05000269/20230062024-02-28028 February 2024 Annual Assessment Letter for Oconee Nuclear Station Units 1, 2 and 3 - (NRC Inspection Report 05000269/2023006, 05000270/2023006, and 05000287/2023006) ML24045A2942024-02-16016 February 2024 Ltr. to Carolyn Chavis Bolton Chief Pee Dee Indian Nation of Upper Sc Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A3082024-02-16016 February 2024 Ltr. to Ralph Oxendine Chief Sumter Tribe of Cheraw Indians Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A2962024-02-16016 February 2024 Ltr. to David Hill Principal Chief Muscogee Creek Nation Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A3072024-02-16016 February 2024 Ltr. to Pete Parr Chief Pee Dee Indian Tribe Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A2972024-02-16016 February 2024 Ltr. to Dexter Sharp Chief Piedmont American Indian Assoc Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A2992024-02-16016 February 2024 Ltr. to Eric Pratt Chief the Santee Indian Organization Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A2952024-02-16016 February 2024 Ltr. to Chuck Hoskin, Jr, Principal Chief Cherokee Nation Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A3062024-02-16016 February 2024 Ltr. to Michell Hicks, Principal Chief Eastern Band of Cherokee Re Oconee Nuclear Station Units 1,2, and 3 Section 106 ML24030A0052024-02-16016 February 2024 Ltr. to Brian Harris, Chief, Catawba Indian Nation; Re., Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A3032024-02-16016 February 2024 Ltr. to John Creel Chief Edisto Natchez-Kusso Tribe of Sc Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A3012024-02-16016 February 2024 Ltr. to Harold Hatcher Chief the Waccamaw Indian People Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A3022024-02-16016 February 2024 Ltr. to Joe Bunch United Keetoowah Band of Cherokee Indians in Ok Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A3042024-02-16016 February 2024 Ltr. to Lisa M. Collins Chief the Wassamasaw Tribe of Varnertown Indians Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A3052024-02-16016 February 2024 Ltr. to Louis Chavis Chief Beaver Creek Indians Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 IR 05000269/20230042024-02-13013 February 2024 Integrated Inspection Report 05000269/2023004, 05000270/2023004, and 05000287/2023004; and Inspection Report 07200040/2023001 ML24030A5212024-02-13013 February 2024 Letter to Elizabeth Johnson, Director, Shpo; Re Oconee Nuclear Stations Units 1, 2, and 3 Section 106 ML23304A1422024-02-0101 February 2024 Issuance of Environmental Scoping Summary Report Associated with the U.S. Nuclear Regulatory Commission Staffs Review of the Oconee Nuclear Station, Units 1, 2, & 3, Subsequent License Renewal Application ML24005A2492024-01-24024 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) ML23331A7982023-12-14014 December 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report (01R32) ML23262A9672023-12-13013 December 2023 Alternative to Use RR-22-0174, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section XI, Division 1 IR 05000269/20230032023-11-14014 November 2023 Integrated Inspection Report 05000269/2023003, 05000270/2023003, and 05000287/2023003; and IR 07200040/2023001; and Exercise of Enforcement Discretion ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 ML23219A1402023-10-10010 October 2023 Audit Report Proposed Alternative to Use ASME Code Case N-752, Risk Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems XI, Division 1 ML23269A1102023-10-0606 October 2023 Letter to Steven Snider-Revised Schedule for the Environmental Review of the Oconee Nuclear Station, Unit 1, 2, and 3, Subsequent License Renewal Application ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000269/20230052023-08-25025 August 2023 Updated Inspection Plan for Oconee Nuclear Station Units 1, 2 and 3 (Report 05000269/2023005, 05000270/2023005, and 05000287/2023005) IR 05000269/20230112023-08-25025 August 2023 Comprehensive Engineering Team Inspection Report 05000269/2023011 and 05000270/2023011 and 05000287/2023011 IR 05000269/20230022023-07-28028 July 2023 Integrated Inspection Report 05000269/2023002, 05000270/2023002 and 05000287/2023002 ML23208A0972023-07-27027 July 2023 Subsequent License Renewal List of Threatened and Endangered Species That May Occur in Your Proposed Project Location or May Be Affected IR 05000269/20230102023-07-19019 July 2023 Biennial Problem Identification and Resolution Inspection Report 05000269/2023010 and 05000270/2023010 and 05000287/2023010 and Notice of Violation ML23178A0682023-07-0303 July 2023 Audit Plan Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 & 3 Systems Section XI, Division 1 ML23132A2392023-06-0101 June 2023 Summary of the April 2023 Remote Environmental Audit Related to the Review of the Subsequent License Renewal Application ML23144A0192023-05-25025 May 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report (O3R31) IR 05000269/20230012023-05-12012 May 2023 Integrated Inspection Report 05000269/2023001 and 05000270/2023001 and 05000287/2023001 ML23121A0552023-05-0303 May 2023 Acknowledgement of Withdrawal Request to Revise TS 5.5.2 Containment Leakage Rate Testing Program ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML23117A0432023-04-20020 April 2023 Framatome, Inc., Part 21 Notification of Existence of a Defect 2024-08-08
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Inspection Report - Oconee - 2013008 |
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May 13, 2013
SUBJECT:
OCONEE NUCLEAR STATION - NRC PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT 05000269/2013008, 05000270/2013008, 05000287/2013008
Dear Mr. Batson:
On April 18, 2013, the U. S. Nuclear Regulator y Commission (NRC) completed an inspection at your Oconee Nuclear Station Units 1, 2, and 3. The enclosed report documents the inspection findings, which were discussed on April 18, 2013, with you and other members of your staff.
The inspection was an examination of activities conducted under your license as they relate to the identification and resolution of problems, and 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 representative records, observations of plant equipment and activities, and interviews with personnel.
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 Oconee Nuclear Station Units 1, 2, and 3 was adequate. Licensee identified problems were entered into the corrective action program at a low threshold. Problems were generally prioritized and evaluated commensurate with the safety significance of the problems. Corrective actions were generally implemented in a timely manner commensurate with their importance to safety and addressed the identified causes of problems. Lessons learned from the industry operat ing experience were generally reviewed and applied when appropriate. Audits and self-assessments were effectively used to identify problems and appropriate actions. In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be available electr onically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of the NRC's document 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/ Curtis W. Rapp, Chief Reactor Projects Branch 7 Division of Reactor Projects
Docket Nos.: 50-269, 50-270, 50-287 License Nos.: DPR-38, DPR-47, DPR-55
Enclosure:
INSPECTION REPORT 05000269/2013008, 05000270/2013008, and 05000287/2013008 w/Attachment: Supplemental Information
REGION II==
Docket Nos.: 50-269, 50-270, 50-287
License Nos.: DPR-38, DPR-47, DPR-55
Report Nos.: 05000269/2013008, 05000270/2013008, 05000287/2013008
Licensee: Duke Energy Carolinas, LLC
Facility: Oconee Nuclear Station, Units 1, 2 and 3
Location: Seneca, SC 29672
Dates: April 1 - 5, 2013 April 15 - 18, 2013
Inspectors: L. Suggs, Senior Construction Projects Inspector, Team Leader R. Patterson, Reactor Inspector N. Pitoniak, Fuel Facility Inspector N. Staples, Senior Project Inspector
Approved by: C. Rapp, Chief Reactor Projects Branch 7
Division of Reactor Projects
Enclosure
SUMMARY OF FINDINGS
IR 05000269/2013-008, 05000270/2013-008, 05000287/2013-008; April 1, 2013 - April 18, 2013; Oconee Nuclear Station Units 1, 2 and 3; Biennial Inspection of the Problem Identification and Resolution Program.
The inspection was conducted by a senior construction project inspector, a senior project inspector, a reactor inspector, and a fuel facility inspector. No findings were identified. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process," Rev. 4.
Identification and Resolution of Problems The inspectors concluded that, in general, problems were properly identified, evaluated, prioritized, and corrected. The licensee was effective at identifying problems and entering them into the corrective action program (CAP) for resolution, as evidenced by the relatively few number of deficiencies identified by external organizations (including the NRC) that had not been previously identified by the licensee, during the review period. Generally, prioritization and evaluation of issues were adequate, formal root cause evaluations for significant problems were adequate, and corrective actions specified for problems were acceptable. Overall, corrective actions developed and implemented for issues were generally effective and implemented in a timely manner. However, two minor examples associated with failure to take adequate corrective actions were identified.
The inspectors determined that overall, audits and self-assessments were adequate in identifying deficiencies and areas for improvement in the CAP, and appropriate corrective actions were developed to address the issues identified. Operating experience usage was found to be generally acceptable and integrated into the licensee's processes for performing and managing work, and plant operations.
Based on discussions and interviews conducted with plant employees from various departments, the inspectors determined that personnel at the site felt free to raise safety concerns to management and use the CAP to resolve those concerns.
REPORT DETAILS
OTHER ACTIVITIES
4OA2 Problem Identification and Resolution
.1 Assessment of the Corrective Action Program
a. Inspection Scope
The inspectors reviewed the licensee's CAP procedures which described the administrative process for initiating and res olving problems primarily through the use of the Problem Investigation Program (PIPs).
To verify that problems were properly identified, appropriately characterized and entered into the CAP, the inspectors reviewed PIPs that were issued between December 2011 and February 2013, including a detailed review of selected PIPs associated with the following risk-significant systems: Reactor Coolant (NC), 4160VAC Auxiliary Power (AC) and High Pressure Service Water (HPSW). Where possible, the inspectors independently verified that the corrective actions were implemented. The inspectors also reviewed selected common causes and generic concerns associated with root cause evaluations to determine if they had been appropriately addressed. To help ensure that samples were reviewed across all cornerstones of safety identified in the NRC's Reactor Oversight Process (ROP), the inspectors selected a representative number of PIPs that were identified and assigned to the major plant departments, including operations, maintenance, engineering, health physics, chemistry, and security. The inspectors reviewed selected PIPs, verified corrective actions were implemented, and attended meetings where PIPs were screened for significance to determine whether the licensee was identifying, accurately characterizing, and entering problems into the CAP at an appropriate threshold.
The inspectors conducted plant walkdowns of equipment to assess the material condition and to identify any deficiencies that had not been previously entered into the CAP. The inspectors reviewed PIPs, maintenance history, completed work orders (WOs) for the systems, and reviewed associated system health reports. These reviews were performed to verify that problems were being properly identified, appropriately characterized, and entered into the CAP. Items reviewed generally covered a two-year period; however, in accordance with the inspection procedure, a five-year review was performed for selected systems for age-dependent issues.
Control room walkdowns were also performed to assess the Main Control Room (MCR) deficiency list and to ascertain if deficiencies were entered into the CAP. Operator Workarounds and Operator Burden screenings were reviewed and the inspectors verified compensatory measures for deficient equipment which were being implemented.
The inspectors conducted a detailed review of selected PIPs to assess the adequacy of the root-cause and apparent-cause evaluations of the problems identified. The inspectors reviewed these evaluations against the descriptions of the problem described in the PIPs and the guidance in licensee procedure NSD 212, "Cause Analysis," Rev. 27 and NSD 208 "Problem Investigation Program," Rev. 38. The inspectors assessed if the licensee had adequately determined the cause(s) of identified problems, and had adequately addressed operability, reportability, common cause, generic concerns, extent-of-condition, and extent-of-cause. The review also assessed if the licensee had appropriately identified and prioritized corrective actions to prevent recurrence for significant conditions adverse to quality.
The inspectors attended various plant meetings to observe management oversight functions of the corrective action process. These included PIP screening meetings and Performance Improvement and Oversight Committee (PIOC) meetings.
Documents reviewed are listed in the Attachment.
b. Assessment Identification of Issues
The inspectors determined that the licensee was generally effective in identifying problems and entering them into the CAP and there was a low threshold for entering issues into the CAP. Trending was generally effective in monitoring equipment performance. Site management was ac tively involved in the CAP and focused appropriate attention on significant plant issues.
Prioritization and Evaluation of Issues Based on the review of PIPs sampled by the inspection team during the onsite period, the inspectors concluded that problems were generally prioritized and evaluated in accordance with the licensee's CAP procedures. Each PIP was assigned a significance level by certified members during the Central Screening Team (CST) meeting.
The inspectors determined that station personnel had conducted root cause and apparent cause analyses in compliance with the licensee's CAP procedures. The assigned cause determinations were appropriate and considered the significance of the issues being evaluated. A variety of formal causal-analysis techniques were used depending on the type and complexity of the issue consistent with NSD 212.
Effectiveness of Corrective Actions
The inspectors determined that, overall, corrective actions were timely, commensurate with the safety significance of the issues, and effective in that conditions adverse to quality were. For significant conditions adverse to quality, the corrective actions directly addressed the cause and effectively prevented recurrence.
Effectiveness reviews for corrective actions to prevent recurrence (CAPRs) were sufficient to ensure corrective actions were properly implemented and were effective.
The inspectors identified the following two examples of a minor performance deficiency (PD) associated with the licensee's failure to take adequate corrective action. These two examples involved a violation of regulatory requirements, but are not subject to regulatory enforcement.
- PIP O-12-7940 - The intent of proposed corrective action was not accomplished by the actual corrective action, which was contrary to procedure NSD 208, rev. 38, section 208.9.3.2. The licensee initiated PIP O-13-3662 to address this issue.
- PIP O-12-1269 - The actual corrective action was closed, however the action to update the associated documentation had not been completed. Additionally, the corrective actions did not address the identified cause of the condition. The licensee initiated PIP O-13-04158 to address this issue.
c. Findings
No findings were identified.
.2 Assessment of the Use of Operating Experience (OE)
a. Inspection Scope
The inspectors examined licensee program for reviewing industry OE, reviewed licensee procedure NSD 204, "Operating Experience Program," Rev. 15 and reviewed the licensee's OE database to assess the effectiveness of how external and internal OE data was handled at the plant. In addition, the inspectors selected operating experience documents (e.g., NRC generic communications, 10 CFR Part 21 reports, licensee event reports, vendor notifications, and plant internal OE items, etc.) issued since December 2011, to verify if the licensee had appropriately evaluated each notification for applicability and if issues identified through these reviews were entered into the CAP.
Documents reviewed are listed in the Attachment.
b. Assessment
The inspectors determined that the licensee was generally effective in screening operating experience for applicability to the plant. Industry OE was evaluated by plant OE Coordinators and relevant information was then forwarded to the applicable department for further action or informational purposes. OE issues requiring action were entered into the CAP for tracking and closure. In addition, OE was included in all root cause evaluations in accordance with licensee procedures.
c. Findings
No findings were identified.
.3 Assessment of Self-Assessments and Audits
a. Inspection Scope
The inspectors reviewed audit reports and self-assessment reports, including those which focused on problem identification and resolution, to assess the thoroughness and self-criticism of the licensee's audits and self assessments, and to verify that problems identified through those activities were appropriately prioritized and entered into the CAP for resolution in accordance with licensee procedure NSD 607, "Self Assessments and Benchmarking."
b. Assessment The inspectors determined that the scopes of assessments and audits were adequate.
Self-assessments were generally detailed and critical. The inspectors verified that PIPs were created to document all areas for improvement and findings resulting from the self-assessments, and verified that actions had been completed consistent with those recommendations. Generally, the licensee performed evaluations that were technically accurate. Site trend reports were thorough and a low threshold was established for evaluation of potential trends as evidenced by the PIPs reviewed that were initiated as a result of adverse trends.
c. Findings
No findings were identified.
.4 Assessment of Safety-Conscious Work Environment
a. Inspection Scope
The inspectors randomly interviewed several on-site workers regarding their knowledge of the CAP and their willingness to write PIPs or raise safety concerns. During technical discussions with members of the plant staff, the inspectors also conducted interviews to develop a general perspective of the safety-conscious work environment. The interviews were also conducted to determine if any conditions existed that would cause employees to be reluctant to raise safety concerns. The inspectors reviewed the licensee's Employee Concerns Program (ECP) and interviewed the ECP manager. Additionally, the inspectors reviewed a sample of ECP issues to verify that concerns were being properly reviewed and identified deficiencies were resolved and entered into the CAP when appropriate.
b. Assessment The inspectors determined that licensee management emphasized the need for all employees to identify and report problems using the appropriate methods established within the administrative programs, including the CAP and ECP. These methods were readily accessible to all employees. The inspecto rs determined that employees felt free to raise issues, and that management encouraged employees to place issues into the CAP for resolution.
The inspectors did not identify any reluctance on the part of the licensee staff to report
safety concerns.
c. Findings
No findings were identified.
4OA6 Exit
Exit Meeting Summary
On April 18, 2013, the inspectors presented the inspection results to Mr. Batson and other members of the site staff. The inspectors confirmed that all proprietary information examined during the inspection had been returned to the licensee.
ATTACHMENT:
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee personnel
Judy Smith - Regulatory Affairs
Susan Perry - Regulatory Affairs
Pam Metler - PI INPO Coordinator
Amanda Stevenson - RP Technical Support
Lesley Smith - Performance Improvement
Gail Joyner - Regulatory Affairs
Jimmy Looper - Operations Support
Tommy Young - Operations Support
Matt Ginn - Systems Engineer
Edgar Scott - Operations Support Robert Meixell II - Licensing Specialist
Trevor Turner - System Engineer
Tracy Roland - Senior Operations Specialist
Jeff Hyrnda - Operations Shift Manager Mark Carroll - Control Room Supervisor Thomas Wehrman - Operations Support
NRC personnel
- G. Hopper, Chief, Branch 7, Division of Reactor Projects
LIST OF DOCUMENTS REVIEWED