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| | issue date = 05/27/2016 | | | issue date = 05/27/2016 |
| | title = Design Bases Inspection (Programs) (Inspection Report 05000397/2016008) | | | title = Design Bases Inspection (Programs) (Inspection Report 05000397/2016008) |
| | author name = Farnholtz T R | | | author name = Farnholtz T |
| | author affiliation = NRC/RGN-IV/DRS/EB-1 | | | author affiliation = NRC/RGN-IV/DRS/EB-1 |
| | addressee name = Reddemann M E | | | addressee name = Reddemann M |
| | addressee affiliation = Energy Northwest | | | addressee affiliation = Energy Northwest |
| | docket = 05000397 | | | docket = 05000397 |
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| =Text= | | =Text= |
| {{#Wiki_filter: | | {{#Wiki_filter:==SUBJECT:== |
| [[Issue date::May 27, 2016]]
| | COLUMBIA GENERATING STATION - DESIGN BASES INSPECTION (PROGRAMS) (INSPECTION REPORT 05000397/2016008) |
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| Mr. Mark Chief Executive Officer Energy Northwest P.O. Box 968 (Mail Drop 1023)
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| Richland, WA 99352-0968
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| SUBJECT: COLUMBIA GENERATING STATION - DESIGN BASES INSPECTION (PROGRAMS) (INSPE CTION REPORT 05000397/2016008)
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| ==Dear Mr. Reddemann:== | | ==Dear Mr. Reddemann:== |
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| The NRC inspectors did not identify any findings or violations of more than minor significance. | | The NRC inspectors did not identify any findings or violations of more than minor significance. |
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| In accordance with Title 10 of the Code of Federal Regulations 2.390, "Public Inspections, Exemptions, Requests for Withholding," of the NRC's "Rules of Practice and Procedure," a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRC's Public Document Room or from the Publicly Available Records (PARS) | | In accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding, of the NRC's "Rules of Practice and Procedure," a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRCs Public Document Room or from the Publicly Available Records (PARS) |
| component of the NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). | | component of the NRC's Agencywide Documents Access and Management System (ADAMS). |
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| Sincerely,/RA/
| | ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). |
| Thomas R. Farnholtz, Chief Engineering Branch 1 Division of Reactor Safety
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| Docket No. 50-397 License No. NPF-21 | | Sincerely, |
| | /RA/ |
| | Thomas R. Farnholtz, Chief Engineering Branch 1 Division of Reactor Safety Docket No. 50-397 License No. NPF-21 |
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| ===Enclosure:=== | | ===Enclosure:=== |
| Inspection Report 05000397/2016008 | | Inspection Report 05000397/2016008 w/Attachment: Supplemental Information |
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| ===w/Attachment:=== | | REGION IV== |
| Supplemental Information
| | Docket: 05000397 License: NPF-21 Report: 05000397/2016008 Licensee: Energy Northwest Facility: Columbia Generating Station Location: North Power Plant Loop Richland, WA 99354 Dates: May 9 through May 12, 2016 Inspectors: R. Kopriva, Senior Reactor Inspector, Team Lead J. Braisted, PhD, Reactor Inspector N. Okonkwo, Reactor Inspector Approved By: Thomas R. Farnholtz Chief, Engineering Branch 1 Division of Reactor Safety Enclosure |
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| cc: Electronic Distribution for Columbia Generating Station May 27, 2016 Mr. Mark
| | =SUMMARY= |
| | IR 05000397/2016008, 05/09/2016 - 05/12/2016; Columbia Generating Station; Baseline |
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| =SUMMARY=
| | Inspection, NRC Inspection Procedure 71111.21N, Design Bases Inspection (Programs). |
| IR 05000397/2016008, 05/09/2016 - 05/12/2016; Columbia Generating Station; Baseline Inspection, NRC Inspection Procedure 71111.21N, "Design Bases Inspection (Programs)."
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| The inspection activities described in this report were performed between May 9, 2016, and May 12, 2016, by three inspectors from the NRC's Region IV office. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process." | | The inspection activities described in this report were performed between May 9, 2016, and May 12, 2016, by three inspectors from the NRCs Region IV office. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process. |
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| No findings were identified. | | No findings were identified. |
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| ==REACTOR SAFETY== | | ==REACTOR SAFETY== |
| Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity | | Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity {{a|1R21}} |
| {{a|1R21}} | |
| ==1R21 Component Design Basis Inspection== | | ==1R21 Component Design Basis Inspection== |
| {{IP sample|IP=IP 71111.21}} | | {{IP sample|IP=IP 71111.21}} |
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| ====a. Inspection Scope==== | | ====a. Inspection Scope==== |
| The inspection team performed a pilot inspection conducted as outlined in NRC Inspection Procedure (IP) 71111.21N, Attachment 1, "Environmental Qualification under 10 CFR 50.49, Programs, Processes, and Procedures." The team assessed Columbia Generating Station's implementation of the environmental qualification program as required by 10 CFR 50.49, "Environmental qualification of electric equipment important to safety for nuclear power plants." The team evaluated whether Columbia Generating Station staff properly maintained the environmental qualification of electrical equipment important to safety throughout plant life, established and maintained required environmental qualification documentation records, and implemented an effective corrective action program to identify and correct environmental qualification-related deficiencies. | | The inspection team performed a pilot inspection conducted as outlined in NRC Inspection Procedure (IP) 71111.21N, Attachment 1, Environmental Qualification under 10 CFR 50.49, Programs, Processes, and Procedures. The team assessed Columbia Generating Stations implementation of the environmental qualification program as required by 10 CFR 50.49, Environmental qualification of electric equipment important to safety for nuclear power plants. The team evaluated whether Columbia Generating Station staff properly maintained the environmental qualification of electrical equipment important to safety throughout plant life, established and maintained required environmental qualification documentation records, and implemented an effective corrective action program to identify and correct environmental qualification-related deficiencies. |
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| The inspection included review of environmental qualification program procedures, component environmental qualification files, environmental qualification test records, equipment maintenance and operating history, maintenance and operating procedures, vendor documents, design documents, and calculations. The team interviewed program owners, engineers, maintenance staff, and warehouse staff. The team performed | | The inspection included review of environmental qualification program procedures, component environmental qualification files, environmental qualification test records, equipment maintenance and operating history, maintenance and operating procedures, vendor documents, design documents, and calculations. The team interviewed program owners, engineers, maintenance staff, and warehouse staff. The team performed in-plant walkdowns (where accessible) to verify equipment was installed as described in Columbia Generating Stations environmental qualification component documentation files and that the components were installed in their tested configuration. Additionally, the team performed in-plant walkdowns to determine whether equipment surrounding the components could fail in a manner that could prevent the safety functions of the components and to verify that components located in areas susceptible to a high energy line break were properly evaluated for operation in a harsh environment. The team reviewed and inspected the storage of replacement parts and associated procurement records to verify environmental qualification parts approved for installation in the plant were properly identified and controlled, and that storage and environmental conditions did not adversely affect the components qualified lives. Documents reviewed for this inspection are listed in the attachment. |
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| in-plant walkdowns (where accessible) to verify equipment was installed as described in Columbia Generating Station's environmental qualification component documentation files and that the components were installed in their tested configuration. Additionally, the team performed in-plant walkdowns to determine whether equipment surrounding the components could fail in a manner that could prevent the safety functions of the components and to verify that components located in areas susceptible to a high energy line break were properly evaluated for operation in a harsh environment. The team reviewed and inspected the storage of replacement parts and associated procurement records to verify environmental qualification parts approved for installation in the plant were properly identified and controlled, and that storage and environmental conditions did not adversely affect the components' qualified lives. Documents reviewed for this inspection are listed in the attachment. | |
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| The inspection procedure requires the team to select 6 to 10 components to assess the adequacy of the environmental qualification program. The team selected 9 components for this inspection. Component samples selected for this inspection are listed below: | | The inspection procedure requires the team to select 6 to 10 components to assess the adequacy of the environmental qualification program. The team selected 9 components for this inspection. Component samples selected for this inspection are listed below: |
| * CEP-SPV-1A, Containment Exhaust Pur ge Solenoid Pilot Valve CEP-SPV-1A. | | * CEP-SPV-1A, Containment Exhaust Purge Solenoid Pilot Valve CEP-SPV-1A. |
| * E-CONN X102A, SOLISTRAND #34130 Parallel Splice Connectors, for Thermocouple and RTD Penetrations. Off of Mid-Plane in Drywell, Within Primary Containment. | | * E-CONN X102A, SOLISTRAND #34130 Parallel Splice Connectors, for Thermocouple and RTD Penetrations. Off of Mid-Plane in Drywell, Within Primary Containment. |
| * HPCS-MO-1, Motor Operator for the High Pressure Core Spray Motor Operated Valve 1. | | * HPCS-MO-1, Motor Operator for the High Pressure Core Spray Motor Operated Valve 1. |
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| ==OTHER ACTIVITIES== | | ==OTHER ACTIVITIES== |
| Cornerstones: Initiating Events, Mitigating Systems, Barrier Integrity | | Cornerstones: Initiating Events, Mitigating Systems, Barrier Integrity {{a|4OA2}} |
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| {{a|4OA2}} | |
| ==4OA2 Problem Identification and Resolution== | | ==4OA2 Problem Identification and Resolution== |
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| ====a. Inspection Scope==== | | ====a. Inspection Scope==== |
| The team reviewed a sample of issues which were previously identified and entered into the corrective action program. The team reviewed these issues to verify an appropriate threshold for identifying issues and to evaluate the effectiveness of corrective actions. In addition, condition reports written on issues identified during the inspection were reviewed to verify adequate problem identification and incorporation of the problem into the corrective action program. The specific condition reports that were sampled and reviewed by the team are listed in the attachment. | | The team reviewed a sample of issues which were previously identified and entered into the corrective action program. The team reviewed these issues to verify an appropriate threshold for identifying issues and to evaluate the effectiveness of corrective actions. |
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| | In addition, condition reports written on issues identified during the inspection were reviewed to verify adequate problem identification and incorporation of the problem into the corrective action program. The specific condition reports that were sampled and reviewed by the team are listed in the attachment. |
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| ====b. Findings==== | | ====b. Findings==== |
| No findings were identified. | | No findings were identified. |
| | | {{a|4OA6}} |
| {{a|4OA6}} | |
| ==4OA6 Meetings, Including Exit== | | ==4OA6 Meetings, Including Exit== |
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| ===Licensee Personnel=== | | ===Licensee Personnel=== |
| : [[contact::B. Abney]], Manager, Operations | | : [[contact::B. Abney]], Manager, Operations |
| : [[contact::V. Bhardwaj]], Manager, Planning/Scheduling/Outage | | : [[contact::V. Bhardwaj]], Manager, Planning/Scheduling/Outage |
| : [[contact::A. Black]], General Manager, Emergency Services | | : [[contact::A. Black]], General Manager, Emergency Services |
| : [[contact::D. Brandon]], Plant Support Engineering Manager, Engineering | | : [[contact::D. Brandon]], Plant Support Engineering Manager, Engineering |
| : [[contact::D. Brown]], Manager, System Engineering | | : [[contact::D. Brown]], Manager, System Engineering |
| : [[contact::A. Elsey]], EQ Program Owner, Technical Services Engineering | | : [[contact::A. Elsey]], EQ Program Owner, Technical Services Engineering |
| : [[contact::E. Gilmour]], Manager, Computer Engineering | | : [[contact::E. Gilmour]], Manager, Computer Engineering |
| : [[contact::K. Gosney]], Manager, Security Operations | | : [[contact::K. Gosney]], Manager, Security Operations |
| : [[contact::D. Gregoire]], Manager, Regulatory Affairs and Performance Improvement | | : [[contact::D. Gregoire]], Manager, Regulatory Affairs and Performance Improvement |
| : [[contact::R. Hammons]], Manager, Employee Concerns Program | | : [[contact::R. Hammons]], Manager, Employee Concerns Program |
| : [[contact::W. Jaleel]], Engineer, Technical Services Engineering | | : [[contact::W. Jaleel]], Engineer, Technical Services Engineering |
| : [[contact::A. Javorik]], Vice President, Engineering | | : [[contact::A. Javorik]], Vice President, Engineering |
| : [[contact::D. Kettering]], Manager, Design Engineering | | : [[contact::D. Kettering]], Manager, Design Engineering |
| : [[contact::R. Meyers]], Manager, Operations Training | | : [[contact::R. Meyers]], Manager, Operations Training |
| : [[contact::C. Moon]], Manager, Quality | | : [[contact::C. Moon]], Manager, Quality |
| : [[contact::T. Parmelee]], Compliance Engineer, Regulatory Affairs | | : [[contact::T. Parmelee]], Compliance Engineer, Regulatory Affairs |
| : [[contact::J. Pierce]], Recovery Manager, Vice President-Operations | | : [[contact::J. Pierce]], Recovery Manager, Vice President-Operations |
| : [[contact::M. Reddemann]], Chief Executive Officer | | : [[contact::M. Reddemann]], Chief Executive Officer |
| : [[contact::G. Silvan]], NSSS Engineer, System Engineering | | : [[contact::G. Silvan]], NSSS Engineer, System Engineering |
| : [[contact::D. Scott]], Engineer, Design Engineering | | : [[contact::D. Scott]], Engineer, Design Engineering |
| : [[contact::B. Strecker]], Information Services/Telecom | | : [[contact::B. Strecker]], Information Services/Telecom |
| : [[contact::J. Trautvetter]], Manager, Maintenance Services | | : [[contact::J. Trautvetter]], Manager, Maintenance Services |
| : [[contact::D. Wolfgramm]], Compliance Supervisor, Regulatory Affairs | | : [[contact::D. Wolfgramm]], Compliance Supervisor, Regulatory Affairs |
| : [[contact::R. Wolfgramm]], Supervisor, Technical Services Engineering | | : [[contact::R. Wolfgramm]], Supervisor, Technical Services Engineering |
| : [[contact::J. Zielinski]], Engineer, Technical Services Engineering | | : [[contact::J. Zielinski]], Engineer, Technical Services Engineering |
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| ===NRC Personnel=== | | ===NRC Personnel=== |
| : [[contact::G. Kolcum]], Senior Resident Inspector | | : [[contact::G. Kolcum]], Senior Resident Inspector |
| : [[contact::D. Bradley]], Resident Inspector | | : [[contact::D. Bradley]], Resident Inspector |
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| ==LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED== | | ==LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED== |
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| Open and | | Open and |
| ===Closed=== | | ===Closed=== |
| : None
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| | None |
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| ==LIST OF DOCUMENTS REVIEWED== | | ==LIST OF DOCUMENTS REVIEWED== |
| ===Calculations===
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| : Number Title Revision
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| : TM-2019 Summary of Equipment Qualification Environmental Profiles 12
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| : EQ-02-86-01 Calculation for Scheduled Maintenance Interval Flexibility Based on Conservative Assumptions Previously Used in Establishing Qualified Life
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| ===Drawings===
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| : Number Title Revision 624 WPPSS Primary Containment Vessel Penetration
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| : PX 102 thru
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| : PX 105
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| : E3 992C349BC Outline (Induction Motor) 12
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| : CRC-628-1817M554 From Hydrogen Recombiner Skid
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| : CAC-HI-1A to Penetration X-102 and X-98
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| : D114 WPPSS Primary Containment Vessel Penetration X102 thru X105
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| : E7 D-220-031.1 Tube Erection and Support Isometric IR67 R.B.
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| : EL 548'-0''
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| : E-2698 Modular Design Penet. Type 1 through 5 & 7 0 E-2722 Canister Cable Support A
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| : E-2735 Outboard Enclosure Box, Penet. Type 1, 3 4
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| : E-2736 Inboard Enclosure Box, Penet. Type 1, 3 5
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| : E507-4 Main Three Line Diagram E-SM-4 HPCS Bus 27
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| : E536-2K Connection Wiring Diagram, Terminal Boxes & Misc. Devices 22 E-539, Sh. 42 Connection Wiring Diagram Reactor Instrumentation &
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| : Control Sheet No. 42
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| : E-539, Sh. 43 Connection Wiring Diagram Reactor Instrumentation &
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| : Control Sheet No. 43
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| ===Drawings===
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| : Number Title Revision E-539-1 Connection Wiring Diagram Reactor Instrumentation &
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| : Control Sheet No. 1
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| : E694 Instrument and Control Conduit & Tray Plan 15
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| : EWD-3E-148 Electrical Wiring Diagram, Reactor Recirculation System, Adjustable Speed Drive Loop A and B RTD
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| : Inputs 1
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| : EWD-46E-233 Electrical Wiring Diagram, AC Electrical Distribution System Power Panel E-PP-4A
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| : EWD-7E-022 Electrical Wiring diagram, High pressure Core Spray System Pump,
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| : HPCS-P-1 (E22-C001) Breaker
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| : HPCS-CB-P1 20
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| : EWD-7E-023 Electrical Wiring diagram, High pressure Core Spray System Pump,
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| : HPCS-P-1 (E22-C001) Breaker HPCS-
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| : CB-P1 22
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| : EWD-7E-025B Electrical Wiring diagram, High pressure Core Spray System, Initiation and Trip Logic
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| : EWD-7E-025D Electrical Wiring diagram, High pressure Core Spray System, Initiation and Trip Logic
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| : EWD-7E-025F Electrical Wiring diagram, High pressure Core Spray System, Initiation and Trip Logic
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| : EWD-7E-028 Electrical Wiring diagram, High pressure Core Spray System Pump, HPCS Bus, Relay and metering
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| : M 568 General Arrangement Plan El 471'-0" and EL. 501'-0", Reactor Building
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| : M519 Flow Diagram Reactor Core Isolation Cooling System 98 M520 Flow diagram, HPCS and LPCS systems, Reactor Building 103 M543-3 Flow Diagram Reactor Building Primary Containment Cooling And Purging System
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| : M695 Main and Aux. Steam, SV Vent, and Misc. Drain Piping 32 M711 RFW, RCIC, HPCS, SW, RWCU, RRC and TSW
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| : Reactor Building
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| : EL 422'-3''
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| ===Drawings===
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| : Number Title Revision M712 RFW, RCIC, HPSC, SW, RWCU, RRC and TSW
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| : Reactor Bldg.
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| : EL.
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| : 441'-0''
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| : M806 HVAC Plan and Sections at
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| : EL 471'-0'' 33 M937 Qualification Scheduled Maintenance List for Safety-
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| : Related Equipment
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| : M944 Special Maintenance Practices Based on Equipment Qualification
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| : P2-3311-N-4 6" Bolted Bonnet Gate Valve 0
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| ===Procedures===
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| : Number Title Revision/Date 1.19.3 Component Condition Monitoring Program 4 1.5.13 Preventive Maintenance Optimization Living Program 34
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| : 10.1.21 Maintenance of Environmentally Qualified Equipment 11
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| : 10.25.19 Termination and Splicing Instruction 26
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| : 10.25.4 Lubrication and Inspection of Limitorque MOV(s) 27
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| : 5.5.5 Overriding RCIC Low RPV Pressure Isolation and High Exhaust Pressure Isolation
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| : DES-2-1 Plant Design Changes 55
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| : DES-2-18 Replacement Item Equivalency 7
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| : DES-4-7 Classification of Systems, Structures, and Components
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| : DES-5-3 Safety Classification Determination 3
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| : EQES-12 Engineering Standard for Special Maintenance Practices on EQ Database Page: 1 of 9 Management Standard for Drawings M944
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| ===Procedures===
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| : Number Title Revision/Date
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| : EQES-2 Technical Requirements for Electrical Equipment Environmental Qualification
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| : EQES-2 Technical Requirements for Electrical Equipment Environmental Qualification
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| : MI-1.22A Maintenance Planner's Guide 6
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| : MOT-Motor-1-3 EQ Requirements 7
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| : PPM 10.1.21 Maintenance of Environmentally Qualified Equipment 11
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| : SCSI-3.6 Use Shelf Life Control and Preventive Maintenance of Warehoused Material
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| : SPES-1.6.2 Spare Parts Engineering Standard 48
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| : SPES-1.6.4 SAFETY FUNCTION / QUALITY CLASSIFICATION 44
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| : SPES-1.6.5 Commercial Grade Dedication 47
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| : SPES-1.6.8 Vendor Inspection Plans 44
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| : SPES-1.7.11 EQ Testing/Inspection May 8, 2006
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| : SPES-1.7.13 Required Test And Inspections By Vendor 44
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| : SPES-1.7.18 Storage Maintenance 46
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| : SPES-1.7.19 Shelf Life May 8, 2006
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| : SPES-1.7.57 Post-Maintenance Testing May 8, 2006
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| : SPES-1.7.87 Columbia Generating Station Design Specification 44
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| : SWP-DES-02 Q-list Control/Classifications of Structures, Systems and Component
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| : SWP-MMP-02 Warehousing 11
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| : SWP-PUR-04 Material, Equipment, Parts and Supplies Procurement 15
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| : Audits and Self-Assessments Number Title Date
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| : AR-SA
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| : 195397 Equipment Qualification Program Environmental QID Files Self-Assessment January 18, 2011
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| : AR-SA
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| : 297748 Equipment Qualification - Seismic and Environmental March 15, 2014
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| : AR-SA
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| : 335435 Component Design Basis Inspection (CBDI) and Equipment Qualification (EQ) Program Inspection September 29, 2015AU-EN-16 Quality Services Audit Report - Engineering Program February 25, 2016
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| ===Miscellaneous===
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| : Number Title Revision/Date
| |
| : Operations Training Systems Study Guide 4
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| : Limitorque Maintenance Update 92-1
| |
| : 15608 Motor, Induction, Medium Voltage, High Pressure Core Spray, Safety Related.
| |
| : 9A-CR3-580A-39 Justification for Use of Inconel 625 Bellows in Model
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| : 24
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| : DPU-Based Products December 3, 2008 CER NO. C93-
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| : 246 Component Classification Evaluation Record 1 CER NO. C93-
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| : 247 Component Classification Evaluation Record 2 CER NO. C93-
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| : 250 Component Classification Evaluation Record 1
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| : Division 300 Section 210
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| : Design Basis Document:
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| : Environmental Qualification
| |
| : EV-556 Procurement Engineering Evaluation 16
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| : GLH-85-011 Barksdale Pressure Switch Qualification Audit March 28, 1985
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| : IEEE Std. 323-
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| : 1974 IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations
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| : 1974
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| ===Miscellaneous===
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| : Number Title Revision/Date IEEE Std. 334-
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| : 1994 IEEE Standard for Qualifying continuous Duty Class 1E Motors for Nuclear Power Generating Station June 9, 1994
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| : PSA-1-SM-0001 Probabilistic Safety Assessment - CGS PSA Internal Event Summary
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| : R3-288-1
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| : IEE 344-1975 Seismic and Radiation Qualification Tests for ITT Barton Differential Pressure Indicating Switches, Models 288A and 289A
| |
| : Section 315 Reactor Core Isolation Cooling System Design Bases Document
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| : SER
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| : Design Criteria For Structures, Systems, And Components, Section 3
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| : SSER 3 Design Criteria For Structures, Systems, And Components Section 3.5 - 3.11 and Appendix 3D: Safety-Related Systems In The Environmental Qualification Program
| |
| : SSER 4 Design Criteria For Structures, Systems, And Components Section 3.5 - 3.11
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| : SSER 5 Design Criteria For Structures, Systems, And Components Section 3.9 - 3.11
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| : WPC875-84-58 Contract
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| : C-0875,
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| : WRO 85-05, Buna-N Elastomer Qualified Age Life in Safety-Related C1E Equipment August 31, 1984
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| : Environmental Qualification Test Reports Number Title Revision/Date 22A3008 BWR Equipment Environmental Interface Data 6 22A4722 ECCS Motor Qualification Program 0
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| : 600376A BWR Containment Qualification - Nuclear Power Station Qualification Type Test Report Limitorque Valve Actuators for BWR Service August 30, 1972
| |
| : AQR-67368 Test Report On Qualification Of Automatic Switch Co. (ASCO) Catalog
| |
| : NP-1 Solenoid Valves For Safety-Related Applications In Nuclear Power Generating Stations
| |
| : Environmental Qualification Test Reports Number Title Revision/Date B0003 Qualification Type Test Report, Limitorque Valve Actuators for Class 1E Service, Outside Primary Containment January 23, 1975 B0058 Limitorque Valve Actuator Qualification For Nuclear Power Station Service, Tests Conducted Per IEEE 382-1972, 323-1974, 344-1975
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| : January 11, 1980
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| : B0119
| |
| : Qualification Type Test Report Of Multi-Point Terminal Strips For Use In Limitorque Valve Actuators For PWR Service April 28, 1982 B0212 Nuclear Power Station Qualification Type Test Report Limitorque Valve Actuators With Type LR Motor For Westinghouse PWR. November 30, 1984 B0373 Limitorque Environmental Qualification Report for
| |
| : SMB-000 "C Style" Torque Switch August 22, 2014 DD213A8812CK Motor Vertical (3000 HP) 0
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| : ELR 221-11 Qualification Retention Test of A-MP* SOLISTRAND* Terminals per
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| : MIL-T-7928F: Type
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| : 1, Class 2 May 24, 1970
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| : NEDM-10672 Environmental Qualification Test for Vertical Induction Motor for ECCS Service on Nuclear
| |
| : Power Plants August 1992
| |
| : Qualification Information Documents Number Title Revision/Date 049005EL Environmental Qualification Tyco/Raychem Heat Shrink Tubing, Tape, & Splice Kits (LV/reformulated
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|
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|
| compounds)
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| : 049006EL Environmental Qualification Amp SOLISTRAND Parallel Splice Connector
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| : 049006EL-01 Environmental Qualification, Subject: Amp
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| : SOLISTRAND Parallel Splice Connector
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| : 049007EL Environmental Qualification Raychem Heat Shrink Tubing, Tape, and Splice Kits (LV, Original
| |
| : Compound)
| |
| : Qualification Information Documents Number Title Revision/Date 086001EL Environmental Qualification ITT Barton Differential Pressure Indicating Switches
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| : 086001EL-01 ITT Barton Differential Pressure Indicating Switches 2 21001EL-01C Limitorque Valve Operators with DC Motors (Insulation Classes RH and H)
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| : 21001EL-01D Fiberite Limit Switch and Torque Switch for Limitorque Valve Operators
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| : 213032EL Environmental Qualification General Electric ECCS Pump Motors
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| : 221001EL-01B Environmental Qualification, Subject: Limitorque Valve Operators with AC Motors (Insulation Classes
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| : H and B) 2 221001EL-01D Environmental Qualification, Subject: Fiberite Limit Switch and Torque Switch for Limitorque Valve Operators
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| : 221001EL-01E Environmental Qualification, Subject: Terminal Blocks for Limitorque Valve Operators.
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| : 256002EL-01 Barksdale Pressure Switches, Models B1T and P1H 1 315006EL Environmental Qualification, Subject: ASCO
| |
| : Solenoid Pilot Valves (N P8316 Series)
| |
| : 03A
| |
| : 339004-01 PYCO Temperature Element 17
| |
| : 800030 QID Work Sheet 0
| |
| : W01981 Extend PMQR 7506-05 on
| |
| : HPCS-M-P/1 from 5 to years January 7, 2013
| |
| : Vendor Manuals Number Title Revision/Date 15808 Specification for Motor, Induction, medium voltage, High pressure core spray, Safety related
| |
| : 531-00,1,1 Differential Pressure Indicating Switches, Unit, Calibration And Parts List
| |
| : Vendor Manuals Number Title Revision/Date 999-00,12,1 Limitorque Valve Control and Hazardous Brake 4 999-00,86 ASCO Solenoid Valve Catalogs 2
| |
| : NEDO-32937
| |
| (02E-12-12,8) Custom 8000 Vertical Indication Motor Weather Protected Type 1 Solid and Hollow Shaft December 19, 2006
| |
| ===Action Requests===
| |
| : 00246503
| |
| : 00275750
| |
| : 00333165
| |
| : 00348164
| |
| : 00349369
| |
| : 00248580
| |
| : 00287143
| |
| : 00338239
| |
| : 00348494
| |
| : 00349388
| |
| : 255999
| |
| : 00302169
| |
| : 00343392
| |
| : 00348583
| |
| : 00349392
| |
| : 270927
| |
| : 00323762
| |
| : 00343393
| |
| : 00349304
| |
| : 00349412
| |
| : 00270931
| |
| : 00324946
| |
| : 00346992
| |
| : 00349348
| |
| ===Action Requests===
| |
| : Generated During Inspection
| |
| : 346992
| |
| : 349164
| |
| : 349369
| |
| : 349392
| |
| : 349424
| |
| : 348494
| |
| : 349304
| |
| : 349388
| |
| : 349412
| |
| : 349457
| |
| : 348583
| |
| : 349348
| |
| ===Work Orders===
| |
| : A64692 AR6810
| |
| : 02011451
| |
| : 02045314
| |
| : 02048837 01 AP3457
| |
| : 02008915 01
| |
| }} | | }} |
|
|---|
Category:Inspection Report
MONTHYEARML24290A1142024-10-17017 October 2024
CGS FPTI 2024011
IR 05000397/20244032024-10-0101 October 2024
Cybersecurity Inspection Report 05000397/2024403 Public
IR 05000397/20240052024-08-22022 August 2024
Updated Inspection Plan for Columbia Generating Station (Report 05000397/2024005)
IR 07200035/20244012024-08-19019 August 2024
Security Baseline Inspection Report 07200035/2024401
IR 05000397/20244022024-08-13013 August 2024
Security Baseline Inspection Report 05000397/2024402
IR 05000397/20240022024-08-0909 August 2024
Integrated Inspection Report 05000397/2024002
IR 05000397/20240122024-07-10010 July 2024
– Safety Conscious Work Environment Issue of Concern Follow-up Inspection 05000397/2024012
IR 05000397/20244202024-06-27027 June 2024
– Security Baseline Inspection Report 05000397 2024420 Cover Letter
IR 05000397/20240012024-04-24024 April 2024
Integrated Inspection Report 05000397/2024001
IR 05000397/20244012024-04-0202 April 2024
– Security Baseline Inspection Report 05000397/2024401 (Cover Letter Only)
IR 05000397/20230062024-02-28028 February 2024
Annual Assessment Letter for Columbia Generating Station (Report 05000397/2023006)
IR 05000397/20253012024-02-14014 February 2024
Notification of NRC Initial Operator Licensing Examination 05000397/2025301
IR 05000397/20230042024-01-29029 January 2024
Integrated Inspection and Independent Spent Fuel Storage Installation Report 05000397/2023004 and 07200035/2023001
IR 05000397/20230122023-11-20020 November 2023
Commercial Grade Dedication Inspection Report 05000397/2023012
IR 05000397/20230102023-11-0909 November 2023
Biennial Problem Identification and Resolution Inspection Report 05000397/2023010
IR 05000397/20230932023-11-0101 November 2023
Final Significance Determination of a White Finding, Notice of Violation and Follow-Up Assessment Letter; NRC Inspection Report 05000397/2023093
ML23299A2072023-10-26026 October 2023
Biennial Requalification Inspection Request for Information
IR 05000397/20230032023-10-25025 October 2023
Integrated Inspection Report 05000397/2023003
IR 05000397/20230112023-10-0404 October 2023
License Renewal Phase 2 Report 05000397/2023011
IR 05000397/20234012023-09-11011 September 2023
Security Baseline Inspection Report 05000397/2023401
IR 05000397/20230052023-08-22022 August 2023
Updated Inspection Plan for Columbia Generating Station (Report 05000397/2023005) - Mid Year Letter
IR 05000397/20230022023-08-0101 August 2023
Integrated Inspection Report 05000397/2023002
IR 05000397/20230922023-06-0101 June 2023
NRC Inspection Report 05000397/2023092 and Preliminary White Finding
IR 05000397/20230902023-06-0101 June 2023
Final Significance Determination of a White Finding, Notice of Violation and Follow-Up Assessment Letter; NRC Inspection Report 05000397/2023090
IR 05000397/20230012023-05-0505 May 2023
Integrated Inspection Report 05000397/2023001 - April 26, 2023
IR 05000397/20233012023-05-0101 May 2023
NRC Examination Report 05000397/2023301
IR 05000397/20220062023-03-0101 March 2023
Annual Assessment Letter for Columbia Generating Station (Report 05000397/2022006)
IR 05000397/20234022023-02-23023 February 2023
NRC Security Baseline Inspection Report 050003972023402 (Full Report)
IR 05000397/20220042023-01-23023 January 2023
Integrated Inspection Report 05000397/2022004- 4th Quarter
IR 05000397/20224062023-01-18018 January 2023
NRC Security Baseline Inspection Report 05000397/2022406 (Cover Letter)
IR 05000397/20224042023-01-17017 January 2023
Amended - Columbia Generating Station - Security Baseline Inspection Report 05000397/2022404 (Public)
IR 05000397/20224012022-11-12012 November 2022
Cyber Security Inspection Report 05000397/2022401 (Cover Letter Only)
IR 05000397/20220032022-10-31031 October 2022
Integrated Inspection Report 05000397/2022003
IR 05000397/20224052022-09-15015 September 2022
Material Control and Accounting Program Inspection Report 05000397 2022405 Cover Ltr Only
IR 05000397/20224032022-09-0101 September 2022
NRC Security Inspection Report 05000397/2022403 (Full Report)
IR 05000397/20220022022-07-28028 July 2022
and Independent Spent Fuel Storage Installation - Integrated Inspection Report 05000397/2022002 and 07200035/2022001
IR 05000397/20220102022-06-30030 June 2022
Design Basis Assurance Inspection (Team) Inspection Report 05000397/2022010
IR 05000397/20224022022-06-23023 June 2022
Security Baseline Inspection Report 05000397/2022402
IR 05000397/20220012022-04-29029 April 2022
Integrated Inspection Report 05000397/2022001
IR 05000397/20210062022-03-0202 March 2022
Annual Assessment Letter for Columbia Generating Station (Report 05000397/2021006)
IR 05000397/20210042022-01-20020 January 2022
Integrated Inspection Report 05000397/2021004
IR 05000397/20214012022-01-19019 January 2022
Security Baseline Inspection Report 05000397/2021401
IR 05000397/20210902022-01-13013 January 2022
NRC Inspection Report 05000397/2021090 and Preliminary White Finding
IR 05000397/20214202021-11-0404 November 2021
Security Baseline Inspection Report-Cover Letter - 05000397/2021420
IR 05000397/20210122021-11-0303 November 2021
Design Basis Assurance Inspection (Programs) Inspection Report 05000397/2021012
IR 05000397/20210032021-11-0202 November 2021
Integrated Inspection Report 05000397/2021003
IR 05000397/20210112021-09-21021 September 2021
Triennial Fire Protection Inspection Report 05000397/2021011
IR 05000397/20214022021-09-0909 September 2021
Security Baseline Inspection Report 05000397/2021402
IR 05000397/20210102021-08-29029 August 2021
Biennial Problem Identification and Resolution Inspection Report 05000397/2021010
IR 05000397/20210022021-08-0202 August 2021
Integrated Inspection Report 05000397/2021002
2024-08-09
[Table view]
Category:Letter
MONTHYEARML24290A1142024-10-17017 October 2024
CGS FPTI 2024011
IR 05000397/20244032024-10-0101 October 2024
Cybersecurity Inspection Report 05000397/2024403 Public
GO2-24-088, Supplement to Response to Request for Additional Information Regarding License Amendment Request to Revise Columbia Emergency Plan2024-09-24024 September 2024
Supplement to Response to Request for Additional Information Regarding License Amendment Request to Revise Columbia Emergency Plan
GO2-24-051, Application to Revise Technical Specifications to Adopt TSTF-592, Revise Automatic Depressurization System (ADS) Instrumentation Requirements2024-09-23023 September 2024
Application to Revise Technical Specifications to Adopt TSTF-592, Revise Automatic Depressurization System (ADS) Instrumentation Requirements
ML24247A1572024-09-12012 September 2024
Withholding Determination Letter for Presentation Materials for Energy Northwest Pre-application Meeting 8-9-2024
ML24255A1012024-09-12012 September 2024
Request for Withholding Information from Public Disclosure Energy Northwest Regulatory Engagement Plan, Revision 0
GO2-24-082, Response to Request for Additional Information Regarding License Amendment Request to Revise Columbia Emergency Plan2024-09-10010 September 2024
Response to Request for Additional Information Regarding License Amendment Request to Revise Columbia Emergency Plan
IR 05000397/20240052024-08-22022 August 2024
Updated Inspection Plan for Columbia Generating Station (Report 05000397/2024005)
IR 07200035/20244012024-08-19019 August 2024
Security Baseline Inspection Report 07200035/2024401
IR 05000397/20244022024-08-13013 August 2024
Security Baseline Inspection Report 05000397/2024402
IR 05000397/20240022024-08-0909 August 2024
Integrated Inspection Report 05000397/2024002
GO2-24-060, Reply to a Notice of Violation, EA-21-170 and EA-23-0542024-07-30030 July 2024
Reply to a Notice of Violation, EA-21-170 and EA-23-054
GO2-24-070, Response to Request for Additional Information Regarding Fifth Interval Inservice Testing Program2024-07-29029 July 2024
Response to Request for Additional Information Regarding Fifth Interval Inservice Testing Program
GO2-24-063, Notification of Extension to Columbias Fourth 10-Year Interval Inservice Testing Program Plan2024-07-15015 July 2024
Notification of Extension to Columbias Fourth 10-Year Interval Inservice Testing Program Plan
IR 05000397/20240122024-07-10010 July 2024
– Safety Conscious Work Environment Issue of Concern Follow-up Inspection 05000397/2024012
ML24180A1482024-06-28028 June 2024
Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report 05000397/2024011) and Request for Information
IR 05000397/20244202024-06-27027 June 2024
– Security Baseline Inspection Report 05000397 2024420 Cover Letter
GO2-24-057, Notice of Readiness for Supplemental Inspection2024-06-19019 June 2024
Notice of Readiness for Supplemental Inspection
ML24099A2232024-06-12012 June 2024
Issuance of Amendment No. 275 to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling
GO2-24-056, Relief Request for the Columbia Generating Station Fourth Ten-Year Interval Inservice Testing2024-06-11011 June 2024
Relief Request for the Columbia Generating Station Fourth Ten-Year Interval Inservice Testing
ML24128A2242024-05-31031 May 2024
Issuance of Amendment No. 274 to Revise Technical Specifications to Adopt TSTF-584, Eliminate Automatic RWCU System Isolation on SLC Initiation
GO2-24-049, 2023 Annual Radiological Environmental Operating Report2024-05-13013 May 2024
2023 Annual Radiological Environmental Operating Report
GO2-24-050, Annual Environmental Operating Report2024-04-30030 April 2024
Annual Environmental Operating Report
IR 05000397/20240012024-04-24024 April 2024
Integrated Inspection Report 05000397/2024001
GO2-24-042, 2023 Annual Radioactive Effluent Release Report2024-04-22022 April 2024
2023 Annual Radioactive Effluent Release Report
ML24089A2282024-04-15015 April 2024
– Acceptance of Requested Licensing Action License Amendment Request to Revise Columbia Generating Station Emergency Plan
ML24074A4532024-04-11011 April 2024
Request for Withholding Information from Public Disclosure
GO2-24-044, Voluntary Response to Regulatory Issue Summary 2024-012024-04-11011 April 2024
Voluntary Response to Regulatory Issue Summary 2024-01
IR 05000397/20244012024-04-0202 April 2024
– Security Baseline Inspection Report 05000397/2024401 (Cover Letter Only)
GO2-24-034, Supplement to License Amendment Request to Revise Columbia Generating Station Emergency Plan2024-03-20020 March 2024
Supplement to License Amendment Request to Revise Columbia Generating Station Emergency Plan
ML24058A0692024-03-14014 March 2024
Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request for Emergency Plan
ML24044A0492024-03-12012 March 2024
Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0064 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting))
GO2-24-041, Level of Financial Protection - Annual Reporting Requirement2024-03-12012 March 2024
Level of Financial Protection - Annual Reporting Requirement
GO2-24-036, Presentation Information for Pre-Application Meeting Regarding Columbia’S Replacement Steam Dryer Evaluation Approach for Extended Power Uprate2024-03-11011 March 2024
Presentation Information for Pre-Application Meeting Regarding Columbia’S Replacement Steam Dryer Evaluation Approach for Extended Power Uprate
GO2-24-039, Report of Changes or Errors in Emergency Core Cooling System Loss of Coolant Accident Analysis Models Pursuant to 10 CFR 50.462024-03-11011 March 2024
Report of Changes or Errors in Emergency Core Cooling System Loss of Coolant Accident Analysis Models Pursuant to 10 CFR 50.46
ML24047A0422024-03-0707 March 2024
Issuance of Amendment No. 273 Renewed Facility Operating License and Technical Specification Clean Up
IR 05000397/20230062024-02-28028 February 2024
Annual Assessment Letter for Columbia Generating Station (Report 05000397/2023006)
IR 05000397/20253012024-02-14014 February 2024
Notification of NRC Initial Operator Licensing Examination 05000397/2025301
GO2-24-004, License Amendment Request to Revise Emergency Plan2024-01-30030 January 2024
License Amendment Request to Revise Emergency Plan
IR 05000397/20230042024-01-29029 January 2024
Integrated Inspection and Independent Spent Fuel Storage Installation Report 05000397/2023004 and 07200035/2023001
GO2-24-003, Relief Requests for the Columbia Generating Station Fifth Ten-Year Interval Inservice Testing2024-01-29029 January 2024
Relief Requests for the Columbia Generating Station Fifth Ten-Year Interval Inservice Testing
GO2-24-014, Independent Spent Fuel Storage Installation, Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2024-01-15015 January 2024
Independent Spent Fuel Storage Installation, Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
ML24011A1522024-01-10010 January 2024
March 2024 Emergency Preparedness Exercise Inspection-Request for Information
GO2-24-005, Docket No. 50-397 Supplement to Reply to a Notice of Violation; EA-21-1702024-01-0808 January 2024
Docket No. 50-397 Supplement to Reply to a Notice of Violation; EA-21-170
GO2-23-136, Guarantee of Payment of Deferred Premium2023-12-20020 December 2023
Guarantee of Payment of Deferred Premium
GO2-23-135, Notice of Readiness for Supplemental Inspection2023-12-14014 December 2023
Notice of Readiness for Supplemental Inspection
GO2-23-130, Reply to a Notice of Violation; EA-23-0542023-12-14014 December 2023
Reply to a Notice of Violation; EA-23-054
GO2-23-105, Licensing Basis Document Update and Biennial Commitment Change Report2023-12-12012 December 2023
Licensing Basis Document Update and Biennial Commitment Change Report
ML23288A0002023-12-0707 December 2023
Issuance of Amendment No. 272 to Adopt TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position
GO2-23-107, Application to Revise Technical Specifications to Adopt TSTS-584, Eliminate Automatic RWCU System Isolation on SLC Initiation2023-12-0505 December 2023
Application to Revise Technical Specifications to Adopt TSTS-584, Eliminate Automatic RWCU System Isolation on SLC Initiation
2024-09-24
[Table view] |
Text
SUBJECT:
COLUMBIA GENERATING STATION - DESIGN BASES INSPECTION (PROGRAMS) (INSPECTION REPORT 05000397/2016008)
Dear Mr. Reddemann:
On May 12, 2016, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Columbia Generating Station. The NRC inspectors discussed the results of this inspection with you and other members of your staff. The inspectors documented the results of this inspection in the enclosed inspection report.
The NRC inspectors did not identify any findings or violations of more than minor significance.
In accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding, of the NRC's "Rules of Practice and Procedure," a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRCs Public Document Room or from the Publicly Available Records (PARS)
component of the NRC's Agencywide Documents Access and Management System (ADAMS).
ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
Thomas R. Farnholtz, Chief Engineering Branch 1 Division of Reactor Safety Docket No. 50-397 License No. NPF-21
Enclosure:
Inspection Report 05000397/2016008 w/Attachment: Supplemental Information
REGION IV==
Docket: 05000397 License: NPF-21 Report: 05000397/2016008 Licensee: Energy Northwest Facility: Columbia Generating Station Location: North Power Plant Loop Richland, WA 99354 Dates: May 9 through May 12, 2016 Inspectors: R. Kopriva, Senior Reactor Inspector, Team Lead J. Braisted, PhD, Reactor Inspector N. Okonkwo, Reactor Inspector Approved By: Thomas R. Farnholtz Chief, Engineering Branch 1 Division of Reactor Safety Enclosure
SUMMARY
IR 05000397/2016008, 05/09/2016 - 05/12/2016; Columbia Generating Station; Baseline
Inspection, NRC Inspection Procedure 71111.21N, Design Bases Inspection (Programs).
The inspection activities described in this report were performed between May 9, 2016, and May 12, 2016, by three inspectors from the NRCs Region IV office. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process.
No findings were identified.
REPORT DETAILS
REACTOR SAFETY
Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity
1R21 Component Design Basis Inspection
Main article: IP 71111.21
a. Inspection Scope
The inspection team performed a pilot inspection conducted as outlined in NRC Inspection Procedure (IP) 71111.21N, Attachment 1, Environmental Qualification under 10 CFR 50.49, Programs, Processes, and Procedures. The team assessed Columbia Generating Stations implementation of the environmental qualification program as required by 10 CFR 50.49, Environmental qualification of electric equipment important to safety for nuclear power plants. The team evaluated whether Columbia Generating Station staff properly maintained the environmental qualification of electrical equipment important to safety throughout plant life, established and maintained required environmental qualification documentation records, and implemented an effective corrective action program to identify and correct environmental qualification-related deficiencies.
The inspection included review of environmental qualification program procedures, component environmental qualification files, environmental qualification test records, equipment maintenance and operating history, maintenance and operating procedures, vendor documents, design documents, and calculations. The team interviewed program owners, engineers, maintenance staff, and warehouse staff. The team performed in-plant walkdowns (where accessible) to verify equipment was installed as described in Columbia Generating Stations environmental qualification component documentation files and that the components were installed in their tested configuration. Additionally, the team performed in-plant walkdowns to determine whether equipment surrounding the components could fail in a manner that could prevent the safety functions of the components and to verify that components located in areas susceptible to a high energy line break were properly evaluated for operation in a harsh environment. The team reviewed and inspected the storage of replacement parts and associated procurement records to verify environmental qualification parts approved for installation in the plant were properly identified and controlled, and that storage and environmental conditions did not adversely affect the components qualified lives. Documents reviewed for this inspection are listed in the attachment.
The inspection procedure requires the team to select 6 to 10 components to assess the adequacy of the environmental qualification program. The team selected 9 components for this inspection. Component samples selected for this inspection are listed below:
- CEP-SPV-1A, Containment Exhaust Purge Solenoid Pilot Valve CEP-SPV-1A.
b. Findings
No findings were identified.
OTHER ACTIVITIES
Cornerstones: Initiating Events, Mitigating Systems, Barrier Integrity
4OA2 Problem Identification and Resolution
a. Inspection Scope
The team reviewed a sample of issues which were previously identified and entered into the corrective action program. The team reviewed these issues to verify an appropriate threshold for identifying issues and to evaluate the effectiveness of corrective actions.
In addition, condition reports written on issues identified during the inspection were reviewed to verify adequate problem identification and incorporation of the problem into the corrective action program. The specific condition reports that were sampled and reviewed by the team are listed in the attachment.
b. Findings
No findings were identified.
4OA6 Meetings, Including Exit
Exit Meeting Summary
On May 12, 2016, the inspectors presented the final inspection results to Mr. M. Reddemann, Chief Executive Officer, and other members of the licensee staff. The licensee acknowledged the issues presented. The licensee confirmed that any proprietary information reviewed by the inspectors had been returned or destroyed.
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee Personnel
- B. Abney, Manager, Operations
- V. Bhardwaj, Manager, Planning/Scheduling/Outage
- A. Black, General Manager, Emergency Services
- D. Brandon, Plant Support Engineering Manager, Engineering
- D. Brown, Manager, System Engineering
- A. Elsey, EQ Program Owner, Technical Services Engineering
- E. Gilmour, Manager, Computer Engineering
- K. Gosney, Manager, Security Operations
- D. Gregoire, Manager, Regulatory Affairs and Performance Improvement
- R. Hammons, Manager, Employee Concerns Program
- W. Jaleel, Engineer, Technical Services Engineering
- A. Javorik, Vice President, Engineering
- D. Kettering, Manager, Design Engineering
- R. Meyers, Manager, Operations Training
- C. Moon, Manager, Quality
- T. Parmelee, Compliance Engineer, Regulatory Affairs
- J. Pierce, Recovery Manager, Vice President-Operations
- M. Reddemann, Chief Executive Officer
- G. Silvan, NSSS Engineer, System Engineering
- D. Scott, Engineer, Design Engineering
- B. Strecker, Information Services/Telecom
- J. Trautvetter, Manager, Maintenance Services
- D. Wolfgramm, Compliance Supervisor, Regulatory Affairs
- R. Wolfgramm, Supervisor, Technical Services Engineering
- J. Zielinski, Engineer, Technical Services Engineering
NRC Personnel
- G. Kolcum, Senior Resident Inspector
- D. Bradley, Resident Inspector
LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED
Open and
Closed
None
LIST OF DOCUMENTS REVIEWED
