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[[Issue date::May 27, 2016]] | [[Issue date::May 27, 2016]] | ||
Mr. Mark Chief Executive Officer Energy Northwest P.O. Box 968 (Mail Drop 1023) | Mr. Mark Chief Executive Officer Energy Northwest P.O. Box 968 (Mail Drop 1023) | ||
Richland, WA 99352-0968 | Richland, WA 99352-0968 | ||
SUBJECT: COLUMBIA GENERATING STATION - DESIGN BASES INSPECTION (PROGRAMS) ( | SUBJECT: COLUMBIA GENERATING STATION - DESIGN BASES INSPECTION (PROGRAMS) (INSPE CTION REPORT 05000397/2016008) | ||
==Dear Mr. Reddemann:== | ==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. | 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 NRC's Public Document Room or from the Publicly Available Records (PARS) component of the NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). | 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 NRC's Public Document Room or from the Publicly Available Records (PARS) | |||
component of the NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). | |||
Sincerely,/RA/ | Sincerely,/RA/ | ||
Thomas R. Farnholtz, Chief Engineering Branch 1 Division of Reactor Safety Docket No. 50-397 License No. NPF-21 | Thomas R. Farnholtz, Chief Engineering Branch 1 Division of Reactor Safety | ||
Docket No. 50-397 License No. NPF-21 | |||
===Enclosure:=== | ===Enclosure:=== | ||
| Line 40: | Line 46: | ||
Supplemental Information | Supplemental Information | ||
cc: Electronic Distribution for Columbia Generating Station | cc: Electronic Distribution for Columbia Generating Station May 27, 2016 Mr. Mark | ||
=SUMMARY= | =SUMMARY= | ||
| Line 80: | Line 66: | ||
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 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 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 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. | 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 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. | |||
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 | * CEP-SPV-1A, Containment Exhaust Pur ge 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. | ||
| Line 97: | Line 85: | ||
==OTHER ACTIVITIES== | ==OTHER ACTIVITIES== | ||
Cornerstones: Initiating Events, Mitigating Systems, Barrier Integrity | Cornerstones: Initiating Events, Mitigating Systems, Barrier Integrity | ||
{{a|4OA2}} | {{a|4OA2}} | ||
==4OA2 Problem Identification and Resolution== | ==4OA2 Problem Identification and Resolution== | ||
| Line 110: | Line 99: | ||
==4OA6 Meetings, Including Exit== | ==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. | 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. | ||
| Line 147: | Line 136: | ||
===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 | ||
==LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED== | ==LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED== | ||
| Line 157: | Line 147: | ||
===Calculations=== | ===Calculations=== | ||
: Number Title Revision | : Number Title Revision | ||
: TM-2019 Summary of Equipment Qualification Environmental Profiles | : TM-2019 Summary of Equipment Qualification Environmental Profiles | ||
: EQ-02-86-01 Calculation for Scheduled Maintenance Interval Flexibility Based on Conservative Assumptions Previously Used in Establishing Qualified Life | : EQ-02-86-01 Calculation for Scheduled Maintenance Interval Flexibility Based on Conservative Assumptions Previously Used in Establishing Qualified Life | ||
===Drawings=== | ===Drawings=== | ||
: Number Title Revision 624 WPPSS Primary Containment Vessel Penetration | : Number Title Revision 624 WPPSS Primary Containment Vessel Penetration | ||
: PX 102 thru | : PX 102 thru | ||
: PX 105 E3 992C349BC Outline (Induction Motor) 12 | : PX 105 | ||
: E3 992C349BC | |||
: Outline (Induction Motor) 12 | |||
: CRC-628-1817M554 From Hydrogen Recombiner Skid | : CRC-628-1817M554 From Hydrogen Recombiner Skid | ||
: CAC-HI-1A to Penetration X-102 and X-98 | : CAC-HI-1A to Penetration X-102 and X-98 | ||
: | : D114 WPPSS Primary Containment Vessel Penetration X102 thru X105 | ||
: EL 548'-0'' | : E7 D-220-031.1 Tube Erection and Support Isometric IR67 R.B. | ||
: EL 548'-0'' | |||
: E-2698 Modular Design Penet. Type 1 through 5 & 7 0 E-2722 Canister Cable Support A | |||
: E-2735 Outboard Enclosure Box, Penet. Type 1, 3 4 | : E-2735 Outboard Enclosure Box, Penet. Type 1, 3 4 | ||
: E-2736 Inboard Enclosure Box, Penet. Type 1, 3 5 | : E-2736 Inboard Enclosure Box, Penet. Type 1, 3 5 | ||
: E507-4 Main Three Line Diagram E-SM-4 HPCS Bus 27 | : E507-4 Main Three Line Diagram E-SM-4 HPCS Bus 27 | ||
: E536-2K Connection Wiring Diagram, Terminal Boxes & Misc. Devices 22 E-539, Sh. 42 Connection Wiring Diagram Reactor Instrumentation & Control Sheet No. 42 | : E536-2K Connection Wiring Diagram, Terminal Boxes & Misc. Devices 22 E-539, Sh. 42 Connection Wiring Diagram Reactor Instrumentation & | ||
: Control Sheet No. 42 | |||
: E-539, Sh. 43 Connection Wiring Diagram Reactor Instrumentation & | |||
: Control Sheet No. 43 | |||
===Drawings=== | ===Drawings=== | ||
: Number Title Revision E-539-1 Connection Wiring Diagram Reactor Instrumentation & Control Sheet No. 1 | : Number Title Revision E-539-1 Connection Wiring Diagram Reactor Instrumentation & | ||
: Control Sheet No. 1 | |||
: E694 Instrument and Control Conduit & Tray Plan 15 | |||
: EWD-3E-148 Electrical Wiring Diagram, Reactor Recirculation System, Adjustable Speed Drive Loop A and B RTD | : EWD-3E-148 Electrical Wiring Diagram, Reactor Recirculation System, Adjustable Speed Drive Loop A and B RTD | ||
: Inputs 1 | : Inputs 1 | ||
: EWD-46E-233 Electrical Wiring Diagram, AC Electrical Distribution System Power Panel E-PP-4A | : EWD-46E-233 Electrical Wiring Diagram, AC Electrical Distribution System Power Panel E-PP-4A | ||
: EWD-7E-022 Electrical Wiring diagram, High pressure Core Spray System Pump, | : EWD-7E-022 Electrical Wiring diagram, High pressure Core Spray System Pump, | ||
: HPCS-P-1 (E22-C001) Breaker | : HPCS-P-1 (E22-C001) Breaker | ||
| Line 182: | Line 181: | ||
: HPCS-P-1 (E22-C001) Breaker HPCS- | : HPCS-P-1 (E22-C001) Breaker HPCS- | ||
: CB-P1 22 | : CB-P1 22 | ||
: EWD-7E-025B Electrical Wiring diagram, High pressure Core Spray System, Initiation and Trip Logic | : EWD-7E-025B Electrical Wiring diagram, High pressure Core Spray System, Initiation and Trip Logic | ||
: EWD-7E-025D Electrical Wiring diagram, High pressure Core Spray System, Initiation and Trip Logic | : EWD-7E-025D Electrical Wiring diagram, High pressure Core Spray System, Initiation and Trip Logic | ||
: EWD-7E-025F Electrical Wiring diagram, High pressure Core Spray System, Initiation and Trip Logic | : EWD-7E-025F Electrical Wiring diagram, High pressure Core Spray System, Initiation and Trip Logic | ||
: EWD-7E-028 Electrical Wiring diagram, High pressure Core Spray System Pump, HPCS Bus, Relay and metering | : EWD-7E-028 Electrical Wiring diagram, High pressure Core Spray System Pump, HPCS Bus, Relay and metering | ||
: EL 422'-3'' | : M 568 General Arrangement Plan El 471'-0" and EL. 501'-0", Reactor Building | ||
: 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 | |||
: M695 Main and Aux. Steam, SV Vent, and Misc. Drain Piping 32 M711 RFW, RCIC, HPCS, SW, RWCU, RRC and TSW | |||
: Reactor Building | |||
: EL 422'-3'' | |||
===Drawings=== | ===Drawings=== | ||
: Number Title Revision M712 RFW, RCIC, HPSC, SW, RWCU, RRC and TSW Reactor Bldg. | : Number Title Revision M712 RFW, RCIC, HPSC, SW, RWCU, RRC and TSW | ||
: Reactor Bldg. | |||
: EL. | : EL. | ||
: 441'-0'' | : 441'-0'' | ||
: EL 471'-0'' 33 M937 Qualification Scheduled Maintenance List for Safety-Related Equipment | : M806 HVAC Plan and Sections at | ||
: | : EL 471'-0'' 33 M937 Qualification Scheduled Maintenance List for Safety- | ||
: Related Equipment | |||
: M944 Special Maintenance Practices Based on Equipment Qualification | |||
: P2-3311-N-4 6" Bolted Bonnet Gate Valve 0 | |||
===Procedures=== | ===Procedures=== | ||
: Number Title Revision/Date 1.19.3 Component Condition Monitoring Program 4 1.5.13 Preventive Maintenance Optimization Living Program 34 | : Number Title Revision/Date 1.19.3 Component Condition Monitoring Program 4 1.5.13 Preventive Maintenance Optimization Living Program 34 | ||
| Line 198: | Line 206: | ||
: 10.25.19 Termination and Splicing Instruction 26 | : 10.25.19 Termination and Splicing Instruction 26 | ||
: 10.25.4 Lubrication and Inspection of Limitorque MOV(s) 27 | : 10.25.4 Lubrication and Inspection of Limitorque MOV(s) 27 | ||
: 5.5.5 Overriding RCIC Low RPV Pressure Isolation and High Exhaust Pressure Isolation | : 5.5.5 Overriding RCIC Low RPV Pressure Isolation and High Exhaust Pressure Isolation | ||
: DES-2-1 Plant Design Changes 55 | : DES-2-1 Plant Design Changes 55 | ||
: DES-2-18 Replacement Item Equivalency 7 | : DES-2-18 Replacement Item Equivalency 7 | ||
: DES-4-7 Classification of Systems, Structures, and Components | : DES-4-7 Classification of Systems, Structures, and Components | ||
: DES-5-3 Safety Classification Determination 3 | : DES-5-3 Safety Classification Determination 3 | ||
: EQES-12 Engineering Standard for Special Maintenance Practices on EQ Database Page: 1 of 9 Management Standard for Drawings M944 | : EQES-12 Engineering Standard for Special Maintenance Practices on EQ Database Page: 1 of 9 Management Standard for Drawings M944 | ||
===Procedures=== | ===Procedures=== | ||
: Number Title Revision/Date | : Number Title Revision/Date | ||
: EQES-2 Technical Requirements for Electrical Equipment Environmental Qualification | : EQES-2 Technical Requirements for Electrical Equipment Environmental Qualification | ||
: EQES-2 Technical Requirements for Electrical Equipment Environmental Qualification | : EQES-2 Technical Requirements for Electrical Equipment Environmental Qualification | ||
: MI-1.22A Maintenance Planner's Guide 6 | : MI-1.22A Maintenance Planner's Guide 6 | ||
: MOT-Motor-1-3 EQ Requirements 7 | : MOT-Motor-1-3 EQ Requirements 7 | ||
: PPM 10.1.21 Maintenance of Environmentally Qualified Equipment 11 | : PPM 10.1.21 Maintenance of Environmentally Qualified Equipment 11 | ||
: SCSI-3.6 Use Shelf Life Control and Preventive Maintenance of Warehoused Material | : SCSI-3.6 Use Shelf Life Control and Preventive Maintenance of Warehoused Material | ||
: SPES-1.6.2 Spare Parts Engineering Standard 48 | : SPES-1.6.2 Spare Parts Engineering Standard 48 | ||
: SPES-1.6.4 SAFETY FUNCTION / QUALITY CLASSIFICATION 44 | : SPES-1.6.4 SAFETY FUNCTION / QUALITY CLASSIFICATION 44 | ||
| Line 222: | Line 230: | ||
: SPES-1.7.57 Post-Maintenance Testing May 8, 2006 | : SPES-1.7.57 Post-Maintenance Testing May 8, 2006 | ||
: SPES-1.7.87 Columbia Generating Station Design Specification 44 | : SPES-1.7.87 Columbia Generating Station Design Specification 44 | ||
: SWP-DES-02 Q-list Control/Classifications of Structures, Systems and Component | : SWP-DES-02 Q-list Control/Classifications of Structures, Systems and Component | ||
: SWP-MMP-02 Warehousing 11 | : SWP-MMP-02 Warehousing 11 | ||
: SWP-PUR-04 Material, Equipment, Parts and Supplies Procurement 15 | : SWP-PUR-04 Material, Equipment, Parts and Supplies Procurement 15 | ||
| Line 231: | Line 239: | ||
: 297748 Equipment Qualification - Seismic and Environmental March 15, 2014 | : 297748 Equipment Qualification - Seismic and Environmental March 15, 2014 | ||
: AR-SA | : AR-SA | ||
: 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 | : 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 | ||
===Miscellaneous=== | ===Miscellaneous=== | ||
: Number Title Revision/Date | : Number Title Revision/Date | ||
: Operations Training Systems Study Guide 4 | : Operations Training Systems Study Guide 4 | ||
: Limitorque Maintenance Update 92-1 | : Limitorque Maintenance Update 92-1 | ||
: 15608 Motor, Induction, Medium Voltage, High Pressure Core Spray, Safety Related. | : 15608 Motor, Induction, Medium Voltage, High Pressure Core Spray, Safety Related. | ||
: DPU-Based Products December 3, 2008 CER NO. C93- | : 9A-CR3-580A-39 Justification for Use of Inconel 625 Bellows in Model | ||
: Environmental Qualification | : 24 | ||
: DPU-Based Products December 3, 2008 CER NO. C93- | |||
: 246 Component Classification Evaluation Record 1 CER NO. C93- | |||
: 247 Component Classification Evaluation Record 2 CER NO. C93- | |||
: 250 Component Classification Evaluation Record 1 | |||
: Division 300 Section 210 | |||
: Design Basis Document: | |||
: Environmental Qualification | |||
: EV-556 Procurement Engineering Evaluation 16 | : EV-556 Procurement Engineering Evaluation 16 | ||
: GLH-85-011 Barksdale Pressure Switch Qualification Audit March 28, 1985 | : GLH-85-011 Barksdale Pressure Switch Qualification Audit March 28, 1985 | ||
: IEEE Std. 323-1974 IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations 1974 | : IEEE Std. 323- | ||
: 1974 IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations | |||
: 1974 | |||
===Miscellaneous=== | ===Miscellaneous=== | ||
: Number Title Revision/Date IEEE Std. 334-1994 IEEE Standard for Qualifying continuous Duty Class 1E Motors for Nuclear Power Generating Station June 9, 1994 | : Number Title Revision/Date IEEE Std. 334- | ||
: PSA-1-SM-0001 Probabilistic Safety Assessment - CGS PSA Internal Event Summary | : 1994 IEEE Standard for Qualifying continuous Duty Class 1E Motors for Nuclear Power Generating Station June 9, 1994 | ||
: IEE 344-1975 Seismic and Radiation Qualification Tests for ITT Barton Differential Pressure Indicating Switches, Models 288A and 289A | : PSA-1-SM-0001 Probabilistic Safety Assessment - CGS PSA Internal Event Summary | ||
: | : R3-288-1 | ||
: Design Criteria For Structures, Systems, And Components, Section 3 | : IEE 344-1975 Seismic and Radiation Qualification Tests for ITT Barton Differential Pressure Indicating Switches, Models 288A and 289A | ||
: 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 | : Section 315 Reactor Core Isolation Cooling System Design Bases Document | ||
: SSER 4 Design Criteria For Structures, Systems, And Components Section 3.5 - 3.11 | : SER | ||
: SSER 5 Design Criteria For Structures, Systems, And Components Section 3.9 - 3.11 | : Design Criteria For Structures, Systems, And Components, Section 3 | ||
: 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 | |||
: SSER 5 Design Criteria For Structures, Systems, And Components Section 3.9 - 3.11 | |||
: WPC875-84-58 Contract | : WPC875-84-58 Contract | ||
: C-0875, | : C-0875, | ||
: WRO 85-05, Buna-N Elastomer Qualified Age Life in Safety-Related C1E Equipment August 31, 1984 | : WRO 85-05, Buna-N Elastomer Qualified Age Life in Safety-Related C1E Equipment August 31, 1984 | ||
: Environmental Qualification Test Reports Number Title Revision/Date 22A3008 BWR Equipment Environmental Interface Data 6 22A4722 ECCS Motor Qualification Program 0 | : Environmental Qualification Test Reports Number Title Revision/Date 22A3008 BWR Equipment Environmental Interface Data 6 22A4722 ECCS Motor Qualification Program 0 | ||
: 600376A BWR Containment Qualification - Nuclear Power Station Qualification Type Test Report Limitorque Valve Actuators for BWR Service August 30, 1972 | : 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 | : 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 | : 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 January 11, 1980 B0119 | : 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 | ||
: January 11, 1980 | |||
: 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 | : 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 | : SMB-000 "C Style" Torque Switch August 22, 2014 DD213A8812CK Motor Vertical (3000 HP) 0 | ||
| Line 264: | Line 286: | ||
: MIL-T-7928F: Type | : MIL-T-7928F: Type | ||
: 1, Class 2 May 24, 1970 | : 1, Class 2 May 24, 1970 | ||
: NEDM-10672 Environmental Qualification Test for Vertical Induction Motor for ECCS Service on Nuclear Power Plants August 1992 | : NEDM-10672 Environmental Qualification Test for Vertical Induction Motor for ECCS Service on Nuclear | ||
: Qualification Information Documents Number Title Revision/Date 049005EL Environmental Qualification Tyco/Raychem Heat Shrink Tubing, Tape, & Splice Kits (LV/reformulated compounds) | : Power Plants August 1992 | ||
: | : Qualification Information Documents Number Title Revision/Date 049005EL Environmental Qualification Tyco/Raychem Heat Shrink Tubing, Tape, & Splice Kits (LV/reformulated | ||
: | |||
: Qualification Information Documents Number Title Revision/Date 086001EL Environmental Qualification ITT Barton Differential Pressure Indicating Switches | compounds) | ||
: | : 049006EL Environmental Qualification Amp SOLISTRAND Parallel Splice Connector | ||
: H and B) | : 049006EL-01 Environmental Qualification, Subject: Amp | ||
: SOLISTRAND Parallel Splice Connector | |||
: 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 | |||
: 086001EL-01 ITT Barton Differential Pressure Indicating Switches 2 21001EL-01C Limitorque Valve Operators with DC Motors (Insulation Classes RH and H) | |||
: 21001EL-01D Fiberite Limit Switch and Torque Switch for Limitorque Valve Operators | |||
: 213032EL Environmental Qualification General Electric ECCS Pump Motors | |||
: 221001EL-01B Environmental Qualification, Subject: Limitorque Valve Operators with AC Motors (Insulation Classes | |||
: H and B) | |||
: 221001EL-01D Environmental Qualification, Subject: Fiberite Limit Switch and Torque Switch for Limitorque Valve Operators | |||
: 221001EL-01E Environmental Qualification, Subject: Terminal Blocks for Limitorque Valve Operators. | |||
: 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 | : 339004-01 PYCO Temperature Element 17 | ||
: 800030 QID Work Sheet 0 | : 800030 QID Work Sheet 0 | ||
: W01981 Extend PMQR 7506-05 on | : W01981 Extend PMQR 7506-05 on | ||
: HPCS-M-P/1 from 5 to | : 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 | |||
: 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 | : 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 | : NEDO-32937 | ||
(02E-12-12,8) Custom 8000 Vertical Indication Motor Weather Protected Type 1 Solid and Hollow Shaft December 19, 2006 | |||
===Action Requests=== | ===Action Requests=== | ||
: 00246503 | : 00246503 | ||
Revision as of 08:02, 30 June 2018
| ML16148A445 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 05/27/2016 |
| From: | Thomas Farnholtz Region 4 Engineering Branch 1 |
| To: | Reddemann M E Energy Northwest |
| References | |
| IR 2016008 | |
| Download: ML16148A445 (18) | |
Text
May 27, 2016
Mr. Mark Chief Executive Officer Energy Northwest P.O. Box 968 (Mail Drop 1023)
Richland, WA 99352-0968
SUBJECT: COLUMBIA GENERATING STATION - DESIGN BASES INSPECTION (PROGRAMS) (INSPE CTION 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 NRC's Public Document Room or from the Publicly Available Records (PARS)
component of the NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,/RA/
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
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 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 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."
No findings were identified.
REPORT DETAILS
REACTOR SAFETY
Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity
1R21 Component Design Basis Inspection
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 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 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.
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.
- 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-FIS-6, High Pressure Core Spray Discharge Header Minimum Flow Indicator Switch for High Pressure Core Spray Pump HPCS-P-1.
- HPCS-M-P/1, 3000HP/373A Drive Motor for High Pressure Core Spray Pump HPCS-P-1.
- LD-TE-4A, Reactor Core Isolation Cooling Equipment Area Leak Detection Temperature Element.
- RCIC-DPIS-13A, Reactor Core Isolation Cooling Steam Supply High Flow Indicator Switch.
- RCIC-M-V/13, Reactor Core Isolation Cooling Injection Valve Motor for the Valve Operator.
- RCIC-PS-9A, Reactor Core Isolation Cooling Exhaust Pressure High Trip Switch.
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
- 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
- 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
Calculations
- Number Title Revision
- TM-2019 Summary of Equipment Qualification Environmental Profiles
- EQ-02-86-01 Calculation for Scheduled Maintenance Interval Flexibility Based on Conservative Assumptions Previously Used in Establishing Qualified Life
Drawings
- Number Title Revision 624 WPPSS Primary Containment Vessel Penetration
- PX 102 thru
- PX 105
- E3 992C349BC
- Outline (Induction Motor) 12
- CAC-HI-1A to Penetration X-102 and X-98
- D114 WPPSS Primary Containment Vessel Penetration X102 thru X105
- E7 D-220-031.1 Tube Erection and Support Isometric IR67 R.B.
- EL 548'-0
- E-2698 Modular Design Penet. Type 1 through 5 & 7 0 E-2722 Canister Cable Support A
- E-2735 Outboard Enclosure Box, Penet. Type 1, 3 4
- E-2736 Inboard Enclosure Box, Penet. Type 1, 3 5
- E507-4 Main Three Line Diagram E-SM-4 HPCS Bus 27
- E536-2K Connection Wiring Diagram, Terminal Boxes & Misc. Devices 22 E-539, Sh. 42 Connection Wiring Diagram Reactor Instrumentation &
- Control Sheet No. 42
- E-539, Sh. 43 Connection Wiring Diagram Reactor Instrumentation &
- Control Sheet No. 43
Drawings
- Number Title Revision E-539-1 Connection Wiring Diagram Reactor Instrumentation &
- Control Sheet No. 1
- E694 Instrument and Control Conduit & Tray Plan 15
- EWD-3E-148 Electrical Wiring Diagram, Reactor Recirculation System, Adjustable Speed Drive Loop A and B RTD
- Inputs 1
- EWD-46E-233 Electrical Wiring Diagram, AC Electrical Distribution System Power Panel E-PP-4A
- EWD-7E-022 Electrical Wiring diagram, High pressure Core Spray System Pump,
- HPCS-P-1 (E22-C001) Breaker
- HPCS-CB-P1 20
- EWD-7E-023 Electrical Wiring diagram, High pressure Core Spray System Pump,
- HPCS-P-1 (E22-C001) Breaker HPCS-
- CB-P1 22
- EWD-7E-025B Electrical Wiring diagram, High pressure Core Spray System, Initiation and Trip Logic
- EWD-7E-025D Electrical Wiring diagram, High pressure Core Spray System, Initiation and Trip Logic
- EWD-7E-025F Electrical Wiring diagram, High pressure Core Spray System, Initiation and Trip Logic
- EWD-7E-028 Electrical Wiring diagram, High pressure Core Spray System Pump, HPCS Bus, Relay and metering
- M 568 General Arrangement Plan El 471'-0" and EL. 501'-0", Reactor Building
- 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
- M695 Main and Aux. Steam, SV Vent, and Misc. Drain Piping 32 M711 RFW, RCIC, HPCS, SW, RWCU, RRC and TSW
- Reactor Building
- EL 422'-3
Drawings
- Reactor Bldg.
- EL.
- 441'-0
- M806 HVAC Plan and Sections at
- EL 471'-0 33 M937 Qualification Scheduled Maintenance List for Safety-
- Related Equipment
- M944 Special Maintenance Practices Based on Equipment Qualification
- P2-3311-N-4 6" Bolted Bonnet Gate Valve 0
Procedures
- Number Title Revision/Date 1.19.3 Component Condition Monitoring Program 4 1.5.13 Preventive Maintenance Optimization Living Program 34
- 10.1.21 Maintenance of Environmentally Qualified Equipment 11
- 10.25.19 Termination and Splicing Instruction 26
- 10.25.4 Lubrication and Inspection of Limitorque MOV(s) 27
- DES-2-1 Plant Design Changes 55
- DES-2-18 Replacement Item Equivalency 7
- DES-4-7 Classification of Systems, Structures, and Components
- DES-5-3 Safety Classification Determination 3
- EQES-12 Engineering Standard for Special Maintenance Practices on EQ Database Page: 1 of 9 Management Standard for Drawings M944
Procedures
- Number Title Revision/Date
- EQES-2 Technical Requirements for Electrical Equipment Environmental Qualification
- EQES-2 Technical Requirements for Electrical Equipment Environmental Qualification
- MI-1.22A Maintenance Planner's Guide 6
- MOT-Motor-1-3 EQ Requirements 7
- PPM 10.1.21 Maintenance of Environmentally Qualified Equipment 11
- SCSI-3.6 Use Shelf Life Control and Preventive Maintenance of Warehoused Material
- SPES-1.6.2 Spare Parts Engineering Standard 48
- SPES-1.6.4 SAFETY FUNCTION / QUALITY CLASSIFICATION 44
- SPES-1.6.5 Commercial Grade Dedication 47
- SPES-1.6.8 Vendor Inspection Plans 44
- SPES-1.7.11 EQ Testing/Inspection May 8, 2006
- SPES-1.7.13 Required Test And Inspections By Vendor 44
- SPES-1.7.18 Storage Maintenance 46
- SPES-1.7.19 Shelf Life May 8, 2006
- SPES-1.7.57 Post-Maintenance Testing May 8, 2006
- SPES-1.7.87 Columbia Generating Station Design Specification 44
- SWP-DES-02 Q-list Control/Classifications of Structures, Systems and Component
- SWP-MMP-02 Warehousing 11
- SWP-PUR-04 Material, Equipment, Parts and Supplies Procurement 15
- Audits and Self-Assessments Number Title Date
- AR-SA
- 195397 Equipment Qualification Program Environmental QID Files Self-Assessment January 18, 2011
- AR-SA
- 297748 Equipment Qualification - Seismic and Environmental March 15, 2014
- AR-SA
- 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
Miscellaneous
- Number Title Revision/Date
- Operations Training Systems Study Guide 4
- 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
- 24
- DPU-Based Products December 3, 2008 CER NO. C93-
- 246 Component Classification Evaluation Record 1 CER NO. C93-
- 247 Component Classification Evaluation Record 2 CER NO. C93-
- 250 Component Classification Evaluation Record 1
- Division 300 Section 210
- Design Basis Document:
- Environmental Qualification
- EV-556 Procurement Engineering Evaluation 16
- GLH-85-011 Barksdale Pressure Switch Qualification Audit March 28, 1985
- IEEE Std. 323-
- 1974 IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations
- 1974
Miscellaneous
- Number Title Revision/Date IEEE Std. 334-
- 1994 IEEE Standard for Qualifying continuous Duty Class 1E Motors for Nuclear Power Generating Station June 9, 1994
- R3-288-1
- 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
- Design Criteria For Structures, Systems, And Components, Section 3
- 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
- SSER 5 Design Criteria For Structures, Systems, And Components Section 3.9 - 3.11
- WPC875-84-58 Contract
- C-0875,
- WRO 85-05, Buna-N Elastomer Qualified Age Life in Safety-Related C1E Equipment August 31, 1984
- Environmental Qualification Test Reports Number Title Revision/Date 22A3008 BWR Equipment Environmental Interface Data 6 22A4722 ECCS Motor Qualification Program 0
- 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
- January 11, 1980
- 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
- ELR 221-11 Qualification Retention Test of A-MP* SOLISTRAND* Terminals per
- MIL-T-7928F: Type
- 1, Class 2 May 24, 1970
- 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
compounds)
- 049006EL Environmental Qualification Amp SOLISTRAND Parallel Splice Connector
- 049006EL-01 Environmental Qualification, Subject: Amp
- SOLISTRAND Parallel Splice Connector
- 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
- 086001EL-01 ITT Barton Differential Pressure Indicating Switches 2 21001EL-01C Limitorque Valve Operators with DC Motors (Insulation Classes RH and H)
- 21001EL-01D Fiberite Limit Switch and Torque Switch for Limitorque Valve Operators
- 213032EL Environmental Qualification General Electric ECCS Pump Motors
- 221001EL-01B Environmental Qualification, Subject: Limitorque Valve Operators with AC Motors (Insulation Classes
- H and B)
- 221001EL-01D Environmental Qualification, Subject: Fiberite Limit Switch and Torque Switch for Limitorque Valve Operators
- 221001EL-01E Environmental Qualification, Subject: Terminal Blocks for Limitorque Valve Operators.
- 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
(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