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| | number = ML17277A291 | | | number = ML17277A291 |
| | issue date = 10/03/2017 | | | issue date = 10/03/2017 |
| | title = Cooper Nuclear Station - NRC Design Bases Assurance Inspection (Programs) Report 05000298/2017007 | | | title = NRC Design Bases Assurance Inspection (Programs) Report 05000298/2017007 |
| | 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 = Dent J | | | addressee name = Dent J |
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| =Text= | | =Text= |
| {{#Wiki_filter: | | {{#Wiki_filter:ber 3, 2017 |
| [[Issue date::October 3, 2017]]
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| Mr. John Dent, Jr., Vice President-Nuclear
| | ==SUBJECT:== |
| | | COOPER NUCLEAR STATION - NRC DESIGN BASES ASSURANCE INSPECTION (PROGRAMS) REPORT 05000298/2017007 |
| and Chief Nuclear Officer Nebraska Public Power District
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| Cooper Nuclear Station 72676 648A Avenue P.O. Box 98 Brownville, NE 68321
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| SUBJECT: COOPER NUCLEAR STATION - NRC DESIGN BASES ASSURANCE INSPECTION (PROGRAMS) REPORT 05000298/2017007 | |
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| ==Dear Mr. Dent:== | | ==Dear Mr. Dent:== |
| On August 31, 2017, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection | | On August 31, 2017, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Cooper Nuclear Station. NRC inspectors discussed the results of this inspection with Mr. J. |
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| at Cooper Nuclear Station. NRC inspectors discuss ed the results of this inspection with Mr. J. Kalamaja, General Manager-Plant Operations, and other members of your staff. The results of this inspection are documented in the enclosed report.
| | Kalamaja, General Manager-Plant Operations, and other members of your staff. The results of this inspection are documented in the enclosed report. |
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| No findings were identified during this inspection. | | No findings were identified during this inspection. |
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| This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with 10 CFR 2.390, "Public Inspections, Exemptions, Requests for Withholding. | | This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding. |
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| "
| | Sincerely, |
| | | /RA/ |
| Sincerely,/RA/ | | Thomas R. Farnholtz, Branch Chief Engineering Branch 1 Division of Reactor Safety Docket No. 50-298 License No. DPR-46 |
| Thomas R. Farnholtz, Branch Chief Engineering Branch 1 Division of Reactor Safety | |
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| Docket No. 50-298 | |
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| License No | |
| . DPR-46 | |
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| ===Enclosure:=== | | ===Enclosure:=== |
| Inspection Report 05000298/2017007 | | Inspection Report 05000298/2017007 w/Attachment: Supplemental Information |
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| ===w/Attachment:===
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| Supplemental Information | |
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| cc: Electronic Distribution Enclosure U.S. NUCLEAR REGULATORY COMMISSION REGION IV Docket: 05000298 License: DPR-46 Report Nos.: 05000298/2017007 Licensee: Nebraska Public Power District Facility: Cooper Nuclear Station Location: 72676 648A Ave Brownville, NE Dates: August 14 through August 31, 2017 Team Leader: G. George, Senior Reactor Inspector, Engineering Branch 1 Inspectors: R. Latta, Senior Reactor Inspector, Engineering Branch 1 W. Smith, Reactor Inspector, Engineering Branch 1 Approved By: Thomas R. Farnholtz, Branch Chief Engineering Branch 1 Division of Reactor Safety
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| | REGION IV== |
| | Docket: 05000298 License: DPR-46 Report Nos.: 05000298/2017007 Licensee: Nebraska Public Power District Facility: Cooper Nuclear Station Location: 72676 648A Ave Brownville, NE Dates: August 14 through August 31, 2017 Team Leader: G. George, Senior Reactor Inspector, Engineering Branch 1 Inspectors: R. Latta, Senior Reactor Inspector, Engineering Branch 1 W. Smith, Reactor Inspector, Engineering Branch 1 Approved By: Thomas R. Farnholtz, Branch Chief Engineering Branch 1 Division of Reactor Safety Enclosure |
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| =SUMMARY= | | =SUMMARY= |
| IR 05000298/2017007; 08/14/2017 - 08/31/2017; COOPER NUCLEAR STATION; Inspection | | IR 05000298/2017007; 08/14/2017 - 08/31/2017; COOPER NUCLEAR STATION; Inspection |
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| Procedure 7111121N, Design Bases Assurance (Programs)
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| This inspection was performed between August 14, 2017, and August 31, 2017, by three inspectors from the NRC's Region IV office. No findings were identified during this inspection. The significance of inspection findings is indicated by their color (Green, White, | | Procedure 7111121N, Design Bases Assurance (Programs) |
| Yellow, or Red), which is determined using Inspection Manual Chapter 0609, "Significance Determination Process." Their cross-cutting aspects are determined using Inspection Manual Chapter 0310, "Aspects Within the Cross-Cutting Areas." Violations of NRC requirements are dispositioned in accordance with the NRCs Enforcement Policy. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process." | | This inspection was performed between August 14, 2017, and August 31, 2017, by three inspectors from the NRCs Region IV office. No findings were identified during this inspection. The significance of inspection findings is indicated by their color (Green, White, |
| | Yellow, or Red), which is determined using Inspection Manual Chapter 0609, Significance Determination Process. Their cross-cutting aspects are determined using Inspection Manual Chapter 0310, Aspects Within the Cross-Cutting Areas. Violations of NRC requirements are dispositioned in accordance with the NRCs Enforcement Policy. 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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| =REPORT DETAILS= | | =REPORT DETAILS= |
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| ====a. Inspection Scope==== | | ====a. Inspection Scope==== |
| The inspection team performed an inspection as outlined in NRC Inspection | | The inspection team performed an inspection as outlined in NRC Inspection Procedure 71111.21N, Attachment 1, Environmental Qualification under 10 CFR 50.49 Programs, Processes, and Procedures. The team assessed Cooper Nuclear 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 Cooper Nuclear 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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| Procedure 71111.21N, Attachment 1, "Environmental Qualification under 10 CFR 50.49 Programs, Processes, and Procedures." The team assessed Cooper Nuclear Station's implementation of the environmental qualification program as required by 10 CFR 50.49, "Environmental qualification of electric equipm ent important to safety for nuclear power plants." The team evaluated whether Cooper Nuclear 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 in its qualified configuration as described in Cooper Nuclear Stations environmental qualification component documentation files. 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 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. |
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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
| | Documents reviewed for this inspection are listed in the attachment. |
| | |
| in-plant walkdowns (where accessible) to verify equipment was installed in its qualified configuration as described in Cooper Nuclear Station's environmental qualification component documentation files. 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 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 10 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 10 components for this inspection. Component samples selected for this inspection are listed below: |
| * CNS-0-PC-PENT-X101E, Electrical Cable Penetration, Imaging and Sensing Technology Type NY 10275 | | * CNS-0-PC-PENT-X101E, Electrical Cable Penetration, Imaging and Sensing Technology Type NY 10275 |
| * CNS-0-MS-TS-123D, Main Steam Leak Detection Temperature Switch, EGS/Fenwal Model 01-170020-090 | | * CNS-0-MS-TS-123D, Main Steam Leak Detection Temperature Switch, EGS/Fenwal Model 01-170020-090 |
| * CNS-1-EE-PNL-AA3, 125 V dc Electric Control Power Distribution Panel Board, General Electric Model QMR | | * CNS-1-EE-PNL-AA3, 125 V dc Electric Control Power Distribution Panel Board, General Electric Model QMR |
| | | * CNS-0-EE-PNL-CA, 125 V dc Electric Distribution Panel, Hatch Inc., |
| 4
| | Model V2B221LR |
| * CNS-0-EE-PNL-CA, 125 V dc Electric Distribution Panel, Hatch Inc., Model V2B221LR | |
| * CNS-1-SW-MO-MO89A, Service Water Discharge Valve Motor, Limitorque Model SMB-3 | | * CNS-1-SW-MO-MO89A, Service Water Discharge Valve Motor, Limitorque Model SMB-3 |
| * CNS-2-NBI-PIS-52B, Reactor Pressure Switch, Barton Model 288A | | * CNS-2-NBI-PIS-52B, Reactor Pressure Switch, Barton Model 288A |
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| ===Licensee Personnel=== | | ===Licensee Personnel=== |
| : [[contact::A. Able]], Supervisor, Design Engineering | | : [[contact::A. Able]], Supervisor, Design Engineering |
| : [[contact::V. Balanskas]], Director/Chief Engineer, Entergy Operations, Inc. | | : [[contact::V. Balanskas]], Director/Chief Engineer, Entergy Operations, Inc. |
| : [[contact::D. Buman]], Director, Nuclear Safety Assurance | | : [[contact::D. Buman]], Director, Nuclear Safety Assurance |
| : [[contact::L. Dewhirst]], Manager, Corrective Actions and Assessments | | : [[contact::L. Dewhirst]], Manager, Corrective Actions and Assessments |
| : [[contact::K. Dia]], Director, Engineering | | : [[contact::K. Dia]], Director, Engineering |
| : [[contact::R. Dia]], Supervisor, Design Engineering | | : [[contact::R. Dia]], Supervisor, Design Engineering |
| : [[contact::R. Estrada]], Program Manager, Nuclear Oversight | | : [[contact::R. Estrada]], Program Manager, Nuclear Oversight |
| : [[contact::M. Ferguson]], Supervisor, Materials Purchasing and Controls | | : [[contact::M. Ferguson]], Supervisor, Materials Purchasing and Controls |
| : [[contact::J. Grauerholz]], Administrative Assistant, Design Engineering | | : [[contact::J. Grauerholz]], Administrative Assistant, Design Engineering |
| : [[contact::J. Houston]], Manager, Production | | : [[contact::J. Houston]], Manager, Production |
| : [[contact::C. Johnson]], Engineer, Design Engineering | | : [[contact::C. Johnson]], Engineer, Design Engineering |
| : [[contact::J. Kalamaja]], General Manager, Plant Operations | | : [[contact::J. Kalamaja]], General Manager, Plant Operations |
| : [[contact::D. Kirkpatrick]], Leader, Performance Assessment, Quality Assurance | | : [[contact::D. Kirkpatrick]], Leader, Performance Assessment, Quality Assurance |
| : [[contact::C. Pelchat]], Manager, Nuclear Projects | | : [[contact::C. Pelchat]], Manager, Nuclear Projects |
| : [[contact::K. Porter]], Manager, Business Services | | : [[contact::K. Porter]], Manager, Business Services |
| : [[contact::J. Reimers]], Manager, System Engineering | | : [[contact::J. Reimers]], Manager, System Engineering |
| : [[contact::J. Shaw]], Manager, Licensing | | : [[contact::J. Shaw]], Manager, Licensing |
| : [[contact::P. Tetrick]], Manager, Operations | | : [[contact::P. Tetrick]], Manager, Operations |
| : [[contact::K. Tom]], Assistant to Director, Engineering | | : [[contact::K. Tom]], Assistant to Director, Engineering |
| : [[contact::M. Unruh]], Senior Engineer, Engineering Programs and Components | | : [[contact::M. Unruh]], Senior Engineer, Engineering Programs and Components |
| : [[contact::D. Van Der Kamp]], Technical Specialist, Licensing | | : [[contact::D. Van Der Kamp]], Technical Specialist, Licensing |
| : [[contact::M. Van Winkle]], Acting Manager, Design Engineering | | : [[contact::M. Van Winkle]], Acting Manager, Design Engineering |
| : [[contact::J. Wilson]], Engineer, Design Engineering | | : [[contact::J. Wilson]], Engineer, Design Engineering |
| : [[contact::R. Wise]], EQ Subject Matter Expert, Centech | | : [[contact::R. Wise]], EQ Subject Matter Expert, Centech |
| | |
| ===NRC Personnel=== | | ===NRC Personnel=== |
| : [[contact::C. Jewett]], Acting Resident Inspector | | : [[contact::C. Jewett]], Acting Resident Inspector |
| : [[contact::P. Voss]], Senior Resident Inspector | | : [[contact::P. Voss]], Senior Resident Inspector |
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| ==LIST OF DOCUMENTS REVIEWED== | | ==LIST OF DOCUMENTS REVIEWED== |
| ===Calculations===
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| : Number Title Revision
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| : EE-03-108 Basis for Environmental Conditions Used In The EQ Program Basis Document
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| : EE-13-44 Electrical Bus Maintenance Outage Plans 0
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| : NEDC-00-95C High Energy Line Break (HELB) / Loss of Coolant Accident (LOCA) Inside Containment
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| : NEDC-00-95D HELB
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| : EQ-RB Temperature/Pressure 1
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| : NEDC-03-12 Thermal Lag Analysis for EQ Equipment 2
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| : NEDC-03-26 Radiation Qualification of EQ Equipment 2
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| : NEDC-94-34C USAR Cases E & F Containment Analysis 4
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| : NEDC-94-34D Small Steam Line Break (SSLB) Analysis 3
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| : Design Change Packages Number Title Revision Date
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| : CED 2000-0194 Nutherm DC Starter Door Clip Replacement October 24, 2000EE 16-006 Reactor Building Sumps Acceptance Criteria an AO769 Operation
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| ===Procedures===
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| : Number Title Revision 0.19 Equipment Record and Functional Location File Program 31 14.15.5 Barton Differential Pressure Indicating Switch Calibration
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| : 1-EN-MP-112 Shelf Life Program 4C2 1-EN-MP-125 Control of Material 8C7
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| ===Procedures===
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| : Number Title Revision 1-EN-MP-131 Packaging and Labeling 3C4 3.12.1 Environmental Qualification Program Implementation 13
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| : 3.12.2 Environmental Qualification Data Package 23
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| : 3.12.3 Environmental Qualification Design Input File Control 12
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| : 3-EN-DC-115 Engineering Change Process 15C9
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| : 3-EN-DC-164 Environmental Qualification (EQ) Program 3C1
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| : 6.1RCIC.301 RCIC Steam Line High Flow Calibration Division 1 11
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| : 6.PCIS.601 Steam Line Break Detection Temperature Switch Calibration Test(Bath)
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| : 7.13.13 Motor Control Center Examination and Maintenance 23 7.3.25 NAMCO EA180 Series Limit Switch Installation and Removal 10 7.3.36 CNS Operations Manual - RHR And CS Motor Maintenance And Inspection
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| : 7.3.50.5 CNS Operations Manual - Limitorque MOV
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| : Maintenance
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| : 7.5.8 Limitorque Mechanical /Electrical Examination
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| : 17
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| ===Drawings===
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| : Number Title Revision 2024 SH 5 Radwaste Building HVAC Flow Diagram Chemistry Laboratories
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| : 2038 SH1 Flow Diagram Reactor Building Floor & Roof Drain Systems N54 3007 SH 7 Auxiliary One Line Diagram Motor Control Centers E, Q, R, RB & Y
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| : 3031 SH 3 Control Elementary Diagrams Switch Development 49
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| ===Drawings===
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| : Number Title Revision 3040 SH 9 Control Elementary Diagrams 38 4399-04 1 Inch - 150 lb. Gate Valve, Socket Weld End, Motor Operated (SMB-000)
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| : 2509-3A
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| : 454006581 Elementary Diagram RCIC System 36 829-3 10 Inch - 300 lb. Gate Valve, Bolted Bonnet, Cast Carbon Steel, Motor Operator
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| : NO 6
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| : CNS-EQ-116 SH
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| : EQ Configuration Detail NAMCO Limit Switch Series
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| : EA180 4
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| : CNS-EQ-116 SH
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| : EQ Configuration Detail Tabulation Sheet EA180
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| : Series 2
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| : CNS-EQ-122 SH
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| : EQ Configuration Terminal Boxes and Equipment Enclosures
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| : CNS-EQ-129 Cooper Nuclear Station, Limitorque - Valve Actuator, EQ Configuration Detail
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| : N0 2
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| : Vendor Technical Document Number Title Revision Date 1025-VOL8-P3B2 Instructions for Application, Installation, and Set Point Testing of Patel/EGS Temperature Switches August 10, 1994
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| : VM-0290
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| : ITE-Gould 480 Volt Motor Control Center 10
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| : VM-1726 Barton Model 288A/290A&B - 288C/290D Differential Pressure Indicating Switches
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| ===Condition Reports (CR-CNS-)===
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| : 2005-06142 2005-06143 2012-04809 2012-04978 2012-04985 2012-05365 2012-06467 2012-06760 2012-07114 2012-08163 2012-08223 2012-08637 2012-09630 2012-10044 2012-10160 2012-10616 2013-02427 2013-03442 2013-03454 2013-05313
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| : 2013-07463 2014-02432 2014-03024 2014-03246 2014-03380
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| : 2014-05601 2015-02051 2015-04871 2016-03999 2016-04219
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| ===Condition Reports (CR-CNS-)===
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| : 2016-05500 2016-05501 2016-08026 2016-08338
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| ===Condition Reports===
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| : Generated During the Inspection (CR-CNS-)
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| : 2017-04983 2017-04993 2017-05007 2017-05038 2017-05040 2017-05118 2017-05146 2017-05152 2017-05276 2017-05309
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| : 2017-05310
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| ===Work Orders===
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| (WO)
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| : 4410583
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| : 4470064
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| : 4655476
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| : 4816322
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| : 4816323
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| : 4905930
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| : 4919981
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| : 4921132
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| : 4921470
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| : 4922236
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| : 4949336
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| : 5075510
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| : 5090650
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| : 5147640
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| : 5156760
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| : 211132
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| ===Miscellaneous===
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| : Number Title Date LO 2017-0084-
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| : 003 2017 CNS EQ Self-Assessment Report April 27, 2017
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| : Equipment Classification System Work Package for Radwaste, Non-essential June 25, 1986
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| : Environmental Qualification Design Inputs Number Title Revision Date B0058 Limitorque Valve Actuator Qualification For Nuclear Power Station Service
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| : DI 0241 BWR Equipment Qualification - GE BWROG Reports
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| : QSR-111-A-05
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| : October 1980
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| : DI 1009 Letter to EDS Nuclear, Inc., Attn:
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| : Terry Bevers from Nebraska Public Power District September 9, 1982
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| : DI 1049 Record of Conversation GE Fusible Switch Non-Metallic Material Identification September 16, 1982
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| : DI 1050 Record of Conversation:
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| : GE QMR Panelboards September 14, 1982
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| : Environmental Qualification Design Inputs Number Title Revision Date
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| : DI 153 BWR Equipment Qualification Summary, Fenwal Temperature Switch October 11, 1980
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| : DI 2084 EDF Changes to THFP Disconnect Switch and
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| : QMR 221 Fused Disconnect Switch March 23, 1984
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| : DI 2142 GE Report
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| : NEDC-30294, Qualification Test Report
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| : October 1983
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| : DI 2221 Environmental Qualification Report for GE QMR
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| : Panelboards at Cooper Nuclear Station
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| : DI 244 ITT Barton Seismic and Radiation Qualification Test Report 3
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| : DI 2441 Evaluation of Isomedix Part 21 Notice RE: Dosimetry Accuracy August 4, 1989
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| : DI 2648 Test Report for Nuclear Environmental Qualification of Patel 1/2 Inch Electrical Connector March 24, 1989
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| : DI 2880
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| : ITE-Gould 5600 and 9600 Motor Control Center Qualification Report
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| : DI 2880 Walkdown Report for EQ Terminal Boxes and Condulets with Splices
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| : DI 2962 Similarity Analysis/Qualification Summary for Modified Patel Temperature Switches September 16, 1996
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| : DI 2963 Procedure for Assembly, Potting, and Testing of Modified Patel Temperature Switches September 16, 1996
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| : DI 3200 Electrical Containment Penetration Assembly 0
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| : DI 3203 Fax to NPPD - Cooper NPS from IST Conax Nuclear, Subject:
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| : IST-Conax Nuclear Electric Penetration Assembly, Ref. Drawing E-41468 Fax of 8-8-01 August 20, 2001
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| : DI 3358 EGS Products
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| : Memorandum No. 99-QDC-2, Use of Heat Shrink Tubing as a Strain Relief on EGS QDC
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| : October 7, 1999
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| : DI 3393 Aging Data Extracted from System 1000 for
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| : EQDP.4.142DOR, GE QMR Panelboards, Material # 383, 449, 1866, 829, 785, 578, and 808
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| : Engineering Order No.
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| : 600198 Test of Limitorque Valve Operator, Model
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| : SMB-0, to Meet Requirements of an Electric Valve Actuator in Nuclear Reactor Containment Environment January 2, 1996
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| : Material Specification Sheets Number Title
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| : 2022345 (EQ) Rotor, Limit Switch, Black Fiberite, For All Sizes of Limitorque Operators Environmental Qualification Data Packages Number Title Revision EQDP 2.129 DOR Environmental Qualification Data Package For SB and SMB Series Valve Actuators With Class H/RH 460V Reliance or Peerless Motors
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| : EQDP.1.128
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| : DOR 4000V RHR and CS Pump Motors, Model Number
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| : 5K6346XC74 (RHR) and 5K6346XC83A (CS)
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| : EQDP.1.154 125V DC, Hatch, Incorporated, 125 V DC ITE Panelboard (Siemens/ITE, Type V2B221LR
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| : Switches)
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| : EQDP.1.196DOR Environmental Qualification Data Package
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| : ITE-Gould Motor Control Center Model 5600
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| : EQDP.1.198 4000V RHR Pump Motor, General Electric, Model Number 5K6339XC185A
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| : EQDP.1.199 4000V RHR Pump Motor, General Electric, Model Number 5K6346XC74A
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| : EQDP.2.101DOR Environmental Qualification Data Package ITT Barton Pressure Switch Models 288
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| : EQDP.2.113 Steam Leak Detection Temperature Switch, EGS/Fenwal, 01-170020-090 and 01-170230-090 as modified by
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| : MP 91-114
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| : EQDP.2.116 Environmental Qualification Data Package NAMCO Limit Switch (Containment Applications) Model EA180
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| : EQDP.4.142DOR Panel Boards, General Electric, QMR Panel Boards 6
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| : EQDP.4.153DOR Electrical Termination for EGS/Patel SLD Temperature Switches, PVC Sleeved
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| : STA-KON 250 Series Disconnects, Alpha Wire Corp/NATVAR Corp/Thomas & Betts
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| : EQDP.4.163 Low Voltage Electrical Penetration Assembly, Imaging and Sensing Technology(IST), N/A, Serial No.
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| : 913501
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| : Material Specification Sheets Number Title
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| : 2035232 (EQ) Grease - Long Life, Grade 1
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| : 2047511 Kit, Gasket, and Seal, for
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| : SMB-00 Actuator
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| : 2059301 (EQ) Switch, Torque, Fiberite, For SMB, Limitorque Operators, with 1/8 In., Shear Proof Pins
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| : 2066556 (EQ) Actuator, Limitorque
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| : SMB-3, Without Motor
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| : 2098001 (EQ) Tubing - Heat Shrink, Range .11 IN to .23 IN (Raychem)
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| : 4003059 (EQ) Assembly, Fingerbase, Fiberite, For 2 Train Geared Limit Switch, Rotor Type
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| : 4003079 O-Ring, Viton, Limit Switch, Cartridge For
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| : SMB-000
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| : 4021672 (EQ) Motor, 200 Ft.-Lb., 460 Volt AC, 1800 RPM
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| : ML17277A291
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| : SUNSI Review
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| : ADAMS:
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| : Non-Publicly Available
| |
| : Non-Sensitive Keyword:
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| : By:
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| : GGeorge
| |
| : Yes
| |
| : No
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| : Publicly Available
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| : Sensitive
| |
| : NRC-002 OFFICE RI:EB1 SRI:EB1 SRI:EB1 C:PBC C:EB1
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| : NAME WCSmith RMLatta GAGeorge JKozal TFarnholtz
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| : SIGNATURE /RA/ /RA/ /RA/ /RA/ /RA/
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| : DATE 9/25/17 9/18/17 9/21/17 9/19/17 10/3/17
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| }} | | }} |
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Security Baseline Inspection Report 05000298/2023420
IR 05000298/20230102023-05-17017 May 2023
Biennial Problem Identification and Resolution Inspection Report 05000298/2023010
IR 05000298/20234032023-05-0404 May 2023
Security Baseline Inspection Report 05000298/2023403
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Integrated Inspection Report 05000298/2023001
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Design Basis Assurance Inspection (Programs) Inspection Report 05000298/2023001
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Annual Assessment Letter for Cooper Nuclear Station Report 05000298/2022006
IR 05000298/20220042023-01-30030 January 2023
Integrated Inspection Report 05000298/2022004
IR 05000298/20220112022-12-23023 December 2022
License Renewal Phase 4 Inspection Report 05000298/2022011
IR 05000298/20220032022-10-27027 October 2022
Integrated Inspection Report 05000298/2022003
IR 05000298/20223022022-10-20020 October 2022
NRC Initial Operator Licensing Examination Approval 05000298/2022302
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Notification of Commercial Grade Dedication Inspection 05000298/2023011 and Request for Information
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NRC Security Inspection Report 05000298/2022402 (Full Report)
IR 05000298/20220052022-08-18018 August 2022
Updated Inspection Plan for Cooper Nuclear Station (Report 05000298 2022005)
IR 05000298/20223012022-08-10010 August 2022
NRC Examination Report 05000298/2022301
IR 05000298/20220022022-07-28028 July 2022
Integrated Inspection Report 05000298/2022002
IR 05000298/20224012022-06-29029 June 2022
Security Baseline Inspection Report 05000298/2022401
IR 05000298/20224032022-06-28028 June 2022
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IR 05000298/20220102022-06-16016 June 2022
Triennial Fire Protection Inspection Report 05000298/2022010
IR 05000298/20220012022-04-28028 April 2022
Integrated Inspection Report 05000298/2022001
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Material Control and Accounting Program Inspection Report 05000298/2022404 - (Public)
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Notification of NRC Evaluations of Changes, Tests and Experiments Inspection 05000298/2022002 and Request for Information
IR 05000298/20210062022-03-0202 March 2022
Annual Assessment Letter for Cooper Nuclear Station (Report 05000298/2021006)
IR 05000298/20210042022-01-24024 January 2022
Integrated Inspection Report 05000298/2021004
IR 05000298/20210032021-11-0404 November 2021
Integrated Inspection Report 05000298/2021003
IR 05000298/20210112021-10-19019 October 2021
CNS2021011 TI194 RPT Jfd, Cooper Nuclear Station - Temporary Instruction 2515/194 Report 05000298/2021011
IR 05000298/20214022021-10-12012 October 2021
Security Baseline Inspection Report 05000298/2021402
IR 05000298/20210052021-09-0101 September 2021
CNS Mid-Cycle Inspection Plan Transmittal Letter for Cooper Nuclear Station (Report 05000298/2021005)
IR 05000298/20210022021-08-0909 August 2021
Integrated Inspection Report 05000298/2021002
IR 05000298/20213012021-07-29029 July 2021
NRC Retake Examination Report 05000298/2021301
IR 05000298/20210122021-07-27027 July 2021
Biennial Problem Identification and Resolution Inspection Report 05000298/2021012
IR 05000298/20210102021-06-0707 June 2021
Design Basis Assurance Inspection (Teams) Inspection Report 05000298/2021010
IR 05000298/20210012021-05-0505 May 2021
CNS2021001-IR-AS, Cooper Nuclear Station - Integrated Inspection Report 05000298/2021001
IR 05000298/20214012021-05-0404 May 2021
Security Baseline Inspection Report 05000298/2021401
IR 05000298/20200062021-03-0303 March 2021
Annual Assessment Letter for Cooper (Report 05000298/2020006)
IR 05000298/20200042021-02-0303 February 2021
Integrated Inspection Report 05000298/2020004
ML21026A3112021-01-27027 January 2021
Notification of NRC Design Bases Assurance Inspection (Team) (NRC Inspection Report 05000298/2021010) and Initial Request for Information
IR 05000298/20203022020-11-18018 November 2020
NRC Examination Report 05000298/2020302
IR 05000298/20200032020-11-0202 November 2020
Integrated Inspection Report 05000298/2020003 and Independent Spent Fuel Storage Installation Inspection Report 07200066/2020001
IR 05000298/20204202020-10-0505 October 2020
Cover Letter for Cooper Nuclear Station - Security Inspection Report 05000298/2020420 2020
IR 05000298/20204112020-09-17017 September 2020
Security Baseline Inspection Report 05000298/2020411
IR 05000298/20203012020-09-15015 September 2020
NRC Examination Report 05000298/2020301
IR 05000298/20200052020-09-0101 September 2020
Updated Inspection Plan for Cooper Nuclear Station (Report 05000298/2020005)
IR 05000298/20200022020-07-22022 July 2020
Integrated Inspection Report 05000298/2020002
IR 05000298/20204102020-07-21021 July 2020
Security Baseline Inspection Report 05000298/2020410
2023-09-01
[Table view]
Category:Letter
MONTHYEARML23334A2012024-01-0303 January 2024
Issuance of Amendment No. 274 Revision to Technical Specifications to Adopt TSTF-551, Revision 3, Revise Secondary Containment Surveillance Requirements
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Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV
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Integrated Inspection Report 05000298/2023003
IR 05000298/20234012023-11-0101 November 2023
Cyber Security Report 05000298/2023401 Public
ML23264A8052023-10-11011 October 2023
Issuance of Amendment No. 273 Revision to Technical Specifications to Adopt TSTF-580, Revision 1, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling
ML23233A1882023-09-0505 September 2023
Regulatory Audit Plan in Support of Relief Request RC3-02 Regarding Drywell Head Bolting
IR 05000298/20243012023-09-0101 September 2023
Notification of NRC Initial Operator Licensing Examination 05000298/2024301
IR 05000298/20230052023-08-21021 August 2023
Updated Inspection Plan for Cooper Nuclear Station (Report 05000298/2023005)- Mid Cycle Letter
IR 05000298/20230022023-08-0808 August 2023
Integrated Inspection Report 05000298/2023002
IR 05000298/20234022023-08-0303 August 2023
NRC Security Inspection Report 05000298/2023402
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Nuclear Station - Notification of Inspection (NRC Inspection Report 05000298/2023004) and Request for Information
IR 05000298/20234202023-08-0101 August 2023
Security Baseline Inspection Report 05000298/2023420
ML23173A0862023-06-26026 June 2023
Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000298/2023401
IR 05000298/20230102023-05-17017 May 2023
Biennial Problem Identification and Resolution Inspection Report 05000298/2023010
IR 05000298/20234032023-05-0404 May 2023
Security Baseline Inspection Report 05000298/2023403
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Submittal of Revision 31 to Updated Safety Analysis Report
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U.S. Nuclear Regulatory Commission Presentation at the May 8, 2023, Brownville Village Meeting
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Integrated Inspection Report 05000298/2023001
ML23060A1582023-03-0808 March 2023
Design Basis Assurance Inspection (Programs) Inspection Report 05000298/2023001
IR 05000298/20220062023-03-0101 March 2023
Annual Assessment Letter for Cooper Nuclear Station Report 05000298/2022006
ML23041A1622023-02-10010 February 2023
Licensed Operator Positive Fitness-for-Duty Test Request for Additional Information
IR 05000298/20220042023-01-30030 January 2023
Integrated Inspection Report 05000298/2022004
IR 05000298/20220112022-12-23023 December 2022
License Renewal Phase 4 Inspection Report 05000298/2022011
ML22286A2072022-11-30030 November 2022
Issuance of Amendment No. 272 Revision to Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements
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ML22304A0052022-10-26026 October 2022
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NRC Initial Operator Licensing Examination Approval 05000298/2022302
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Material Control and Accounting Program Inspection Report 05000298/2022404 - (Public)
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ML22045A0012022-03-31031 March 2022
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IR 05000298/20210042022-01-24024 January 2022
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2024-01-03
[Table view] |
Inspection Report - Cooper - 2017007 |
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Text
ber 3, 2017
SUBJECT:
COOPER NUCLEAR STATION - NRC DESIGN BASES ASSURANCE INSPECTION (PROGRAMS) REPORT 05000298/2017007
Dear Mr. Dent:
On August 31, 2017, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Cooper Nuclear Station. NRC inspectors discussed the results of this inspection with Mr. J.
Kalamaja, General Manager-Plant Operations, and other members of your staff. The results of this inspection are documented in the enclosed report.
No findings were identified during this inspection.
This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely,
/RA/
Thomas R. Farnholtz, Branch Chief Engineering Branch 1 Division of Reactor Safety Docket No. 50-298 License No. DPR-46
Enclosure:
Inspection Report 05000298/2017007 w/Attachment: Supplemental Information
REGION IV==
Docket: 05000298 License: DPR-46 Report Nos.: 05000298/2017007 Licensee: Nebraska Public Power District Facility: Cooper Nuclear Station Location: 72676 648A Ave Brownville, NE Dates: August 14 through August 31, 2017 Team Leader: G. George, Senior Reactor Inspector, Engineering Branch 1 Inspectors: R. Latta, Senior Reactor Inspector, Engineering Branch 1 W. Smith, Reactor Inspector, Engineering Branch 1 Approved By: Thomas R. Farnholtz, Branch Chief Engineering Branch 1 Division of Reactor Safety Enclosure
SUMMARY
IR 05000298/2017007; 08/14/2017 - 08/31/2017; COOPER NUCLEAR STATION; Inspection
Procedure 7111121N, Design Bases Assurance (Programs)
This inspection was performed between August 14, 2017, and August 31, 2017, by three inspectors from the NRCs Region IV office. No findings were identified during this inspection. The significance of inspection findings is indicated by their color (Green, White,
Yellow, or Red), which is determined using Inspection Manual Chapter 0609, Significance Determination Process. Their cross-cutting aspects are determined using Inspection Manual Chapter 0310, Aspects Within the Cross-Cutting Areas. Violations of NRC requirements are dispositioned in accordance with the NRCs Enforcement Policy. 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
1R21 N Design Basis Assurance Inspection (Programs)
Main article: IP 71111.21N
a. Inspection Scope
The inspection team performed an inspection as outlined in NRC Inspection Procedure 71111.21N, Attachment 1, Environmental Qualification under 10 CFR 50.49 Programs, Processes, and Procedures. The team assessed Cooper Nuclear 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 Cooper Nuclear 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 in its qualified configuration as described in Cooper Nuclear Stations environmental qualification component documentation files. 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 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 10 components for this inspection. Component samples selected for this inspection are listed below:
- CNS-0-PC-PENT-X101E, Electrical Cable Penetration, Imaging and Sensing Technology Type NY 10275
- CNS-0-MS-TS-123D, Main Steam Leak Detection Temperature Switch, EGS/Fenwal Model 01-170020-090
- CNS-1-EE-PNL-AA3, 125 V dc Electric Control Power Distribution Panel Board, General Electric Model QMR
- CNS-0-EE-PNL-CA, 125 V dc Electric Distribution Panel, Hatch Inc.,
Model V2B221LR
- CNS-1-SW-MO-MO89A, Service Water Discharge Valve Motor, Limitorque Model SMB-3
- CNS-2-NBI-PIS-52B, Reactor Pressure Switch, Barton Model 288A
- CNS-2-RHR-MOT-RHRP1D, Residual Heat Removal Pump D Motor, General Electric Model 5K6346XC74A/5K6339XXC185A
- CNS-1-RHR-MO-MO34A, Residual Heat Removal Torus Loop Inboard Throttle Valve Motor, Limitorque Model SMB-4
- CNS-2-EE-MCC-RB, 480 VAC Distribution Center, ITE Gould Model 9600
b. Findings
No findings were identified.
OTHER ACTIVITIES
4OA6 Meetings, Including Exit
Exit Meeting Summary
On August 31, 2017, the inspectors presented the inspection results to Mr. J. Kalamaja, General Manager, Plant Operations, 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
- A. Able, Supervisor, Design Engineering
- V. Balanskas, Director/Chief Engineer, Entergy Operations, Inc.
- D. Buman, Director, Nuclear Safety Assurance
- L. Dewhirst, Manager, Corrective Actions and Assessments
- K. Dia, Director, Engineering
- R. Dia, Supervisor, Design Engineering
- R. Estrada, Program Manager, Nuclear Oversight
- M. Ferguson, Supervisor, Materials Purchasing and Controls
- J. Grauerholz, Administrative Assistant, Design Engineering
- J. Houston, Manager, Production
- C. Johnson, Engineer, Design Engineering
- J. Kalamaja, General Manager, Plant Operations
- D. Kirkpatrick, Leader, Performance Assessment, Quality Assurance
- C. Pelchat, Manager, Nuclear Projects
- K. Porter, Manager, Business Services
- J. Reimers, Manager, System Engineering
- J. Shaw, Manager, Licensing
- P. Tetrick, Manager, Operations
- K. Tom, Assistant to Director, Engineering
- M. Unruh, Senior Engineer, Engineering Programs and Components
- D. Van Der Kamp, Technical Specialist, Licensing
- M. Van Winkle, Acting Manager, Design Engineering
- J. Wilson, Engineer, Design Engineering
- R. Wise, EQ Subject Matter Expert, Centech
NRC Personnel
- C. Jewett, Acting Resident Inspector
- P. Voss, Senior Resident Inspector
LIST OF DOCUMENTS REVIEWED
