IR 05000298/2024004
| ML25035A012 | |
| Person / Time | |
|---|---|
| Site: | Cooper  (DPR-046) |
| Issue date: | 02/07/2025 |
| From: | Douglas Dodson NRC/RGN-IV/DORS/PBC |
| To: | Dia K Nebraska Public Power District (NPPD) |
| References | |
| IR 2024004 | |
| Download: ML25035A012 (1) | |
Text
February 07, 2025
SUBJECT:
COOPER NUCLEAR STATION - INTEGRATED INSPECTION REPORT 05000298/2024004
Dear Khalil Dia:
On December 31, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Cooper Nuclear Station. On January 07, 2025, the NRC inspectors discussed the results of this inspection with John Dent, Jr., Executive Vice President and Chief Nuclear Officer, and other members of your staff. The results of this inspection are documented in the enclosed report.
No findings or violations of more than minor significance 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 Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, Douglas E. Dodson II, Chief Reactor Projects Branch C Division of Operating Reactor Safety Docket No. 05000298 License No. DPR-46
Enclosure:
As stated
Inspection Report
Docket Number:
05000298
License Number:
Report Number:
Enterprise Identifier:
I-2024-004-0010
Licensee:
Nebraska Public Power District
Facility:
Cooper Nuclear Station
Location:
Brownville, NE
Inspection Dates:
October 1, 2024, to December 31, 2024
Inspectors:
G. Birkemeier, Resident Inspector
K. Chambliss, Senior Resident Inspector
J. Drake, Senior Reactor Inspector
G. Kolcum, Senior Resident Inspector
J. O'Donnell, Senior Health Physicist
E. Simpson, Nuclear Systems Scientist
Approved By:
Douglas E. Dodson II, Chief
Reactor Projects Branch C
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Cooper Nuclear Station, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.
List of Findings and Violations
No findings or violations of more than minor significance were identified.
Additional Tracking Items
None.
PLANT STATUS
Cooper Nuclear Station began the inspection period in a scheduled refueling outage. The station performed a reactor startup on November 2, 2024, ending the outage. The unit reached rated thermal power on November 7, 2024. On November 8, 2024, the operators lowered power to 65 percent for a control rod sequence exchange. The unit returned to rated thermal power on November 9, 2024. On November 22, 2024, the operators lowered power to 80 percent for a control rod sequence exchange. The unit returned to rated thermal power on November 23, 2024. On December 15, 2024, the operators lowered power to 98 percent due to a feedwater flow instrumentation malfunction. The unit returned to rated thermal power on December 19, 2024. The unit remained at rated thermal power for the remainder of the inspection period.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors performed activities described in IMC 2515, Appendix D, Plant Status, observed risk significant activities, and completed on-site portions of IPs. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
REACTOR SAFETY
71111.01 - Adverse Weather Protection
Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of seasonal cold temperatures for the following systems:
- emergency diesel generators, standby liquid control, and service water on November 15, 2024
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (1 Sample)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
(1)4160-volt alternating current (VAC) division 2 system on November 14, 2024
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations during a complete walkdown of the core spray division 1 system on December 12, 2024.
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:
(1)reactor building, 931-foot 6-inch elevation, on November 5, 2024 (2)refueling outage fire door impairments on November 13, 2024 (3)division 2 emergency diesel generator room, 917-foot 6-inch and 903-foot 6-inch elevations, on November 13, 2024 (4)cable spreading room, 918-foot elevation, on November 14, 2024
71111.08G - Inservice Inspection Activities (BWR)
BWR Inservice Inspection Activities Sample - Nondestructive Examination and Welding
Activities (IP Section 03.01)
The inspectors evaluated Cooper Nuclear Station boiling water reactor nondestructive testing during refueling outage RE 33 by reviewing the following examinations and records from October 6 - November 13, 2024:
(1)
Ultrasonic examination Feedwater, FWB-BJ-2, elbow to pipe, DW-953-135 DAZ-AFR Residual heat removal, RAD-BF-7, pipe to pipe DW-901-270 DA Reactor pressure vessel, NVE-BD-N8B, nozzle to shell weld, DW-921-285 DAZ Reactor pressure vessel, NVIR-BD-N8B, nozzle to inner radius section, DW-921-285 DAZ Reactor pressure vessel, NVIR-BD-N9, nozzle to inner radius section o
Visual examination Reactor pressure vessel, longitudinal weld, VLC-BB-3 Reactor pressure vessel, longitudinal weld, VLD-BB-1 Reactor pressure vessel, longitudinal weld, VLD-BB-2
- There were no relevant indications accepted for continued service
- Welding: Work Order 5492888, SW-Z3-2851-1, pipe to reducer
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)
- (1) The inspectors observed and evaluated licensed operator performance in the control room during reactor startup following the refueling outage on November 5, 2024.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated a simulator emergency preparedness scenario on November 29, 2024.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (2 Samples)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
(1)one-time deferral of 20-year diesel fuel oil tank inspection on November 5, 2024 (2)fuel pool cooling maintenance rule function FPC-F01 in monitoring and control of fuel pool cooling maintenance activities during fall 2024 refueling outage on November 13, 2024
Quality Control (IP Section 03.02) (1 Sample)
The inspectors evaluated the effectiveness of maintenance and quality control activities to ensure the following SSC remains capable of performing its intended function:
(1)motor control center K and motor control center Q contact replacement and torquing and 250-volt direct current (VDC) division 1 complete subsystem replacement activities on November 13, 2024
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:
(1)risk assessment and management of shut down cooling during reduced inventory on October 6, 2024 (2)planned Yellow offline risk window during emergency diesel generator division 1 sequential load testing on October 18, 2024 (3)planned Yellow offline risk window for 4160 VAC bus F outage and emergency station service transformer outage on October 21, 2024 (4)planned Yellow offline risk window due to unavailability of all four residual heat removal pumps during shutdown cooling supply valve maintenance on October 21, 2024 (5)planned Yellow offline risk window due to both trains of low-pressure coolant injection being unavailable during residual heat removal cross divisional surveillance testing on November 14, 2024
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (2 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
(1)intermediate range monitor B maintenance during outage activities on November 4, 2024 (2)source range instrument B inoperable during refuel movement activities on November 14, 2024
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (1 Sample)
The inspectors evaluated the following temporary or permanent modifications:
(1)main turbine stop valve limit switch configuration on November 13, 2024
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated refueling outage RE33 activities from September 28, 2024, to November 2, 2024.
71111.24 - Testing and Maintenance of Equipment Important to Risk
The inspectors evaluated the following testing and maintenance activities to verify system operability and/or functionality:
Post-Maintenance Testing (PMT) (IP Section 03.01) (8 Samples)
(1)off-line emergency core cooling system injection check valve operating in-service torque test following removal of temporary configuration change and complete replacement of terminal box due to suspected steam leak damage on November 14, 2024 (2)refurbishment and re-termination of residual heat removal heat exchanger division 1 service water outlet valve on November 14, 2024 (3)post work testing following maintenance on residual heat removal shut down cooling motor operated valves on November 14, 2024 (4)post work testing following complete replacement of 250 VDC division 1 batteries on November 15, 2024 (5)positioner replacement and packing adjustment for outboard main steam isolation valve A and refurbishment for all four outboard main steam isolation valves on November 15, 2024 (6)completion of modification of emergency station service transformer on November 15, 2024 (7)complete replacement of auxiliary contacts in safety-related motor control centers on November 15, 2024 (8)automatic depressurization system manual valve actuation following repair of instrument line to pressure switch low-low set function for MS-RV-71RV on December 3, 2024
Surveillance Testing (IP Section 03.01) (4 Samples)
(1)core standby cooling system initiation logic relay contact testing on October 23, 2024 (2)residual heat removal cross divisional surveillance testing on November 4, 2024 (3)emergency diesel generator division 1 load sequence test on November 14, 2024 (4)reactor protection system division 2 electrical protection assembly calibrations and functional tests on November 14, 2024
Containment Isolation Valve (CIV) Testing (IP Section 03.01) (1 Sample)
(1)local leak rate tests for various containment isolation valves located inside and outside containment on November 13,
RADIATION SAFETY
71124.01 - Radiological Hazard Assessment and Exposure Controls
Radiological Hazard Assessment (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated how the licensee identifies the magnitude and extent of radiation levels and the concentrations and quantities of radioactive materials and how the licensee assesses radiological hazards.
Instructions to Workers (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated how the licensee instructs workers on plant-related radiological hazards and the radiation protection requirements intended to protect workers from those hazards.
Contamination and Radioactive Material Control (IP Section 03.03) (2 Samples)
The inspectors observed/evaluated the following licensee processes for monitoring and controlling contamination and radioactive material:
(1)surveys of potentially contaminated material leaving the radiologically controlled area (2)workers exiting the drywell during a refueling outage
Radiological Hazards Control and Work Coverage (IP Section 03.04) (4 Samples)
The inspectors evaluated the licensee's control of radiological hazards for the following radiological work:
(1)desludging the torus, including diving using special work permit (SWP) 2024-508 (2)pulling and bending local power range monitors using SWP 2024-547 (3)under vessel and control rod drive mechanism exchange using SWP 2024-506 (4)valve work in the steam tunnel using SWP 2024-503 High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (5 Samples)
The inspectors evaluated licensee controls of the following high radiation areas (HRAs) and very high radiation areas (VHRAs):
(1)
(HRA) reactor water cleanup heat exchanger room on the 931-foot elevation of the reactor building (2)
(HRA) ladder lock in the hall on the 958-foot elevation of the reactor building (3)
(HRA) fuel pool cooling heat exchanger room gate on the 958-foot elevation of the reactor building (4)
(HRA) high integrity container storage pit (3 gates) on the 903-foot elevation of the augmented radwaste building (5)
(HRA) spent resin tank room in the radwaste building basement Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 03.06) (1 Sample)
- (1) The inspectors evaluated radiation worker and radiation protection technician performance as it pertains to radiation protection requirements.
71124.03 - In-Plant Airborne Radioactivity Control and Mitigation
Permanent Ventilation Systems (IP Section 03.01) (2 Samples)
The inspectors evaluated the configuration of the following permanently installed ventilation systems:
(1)control room emergency filter system (2)technical support center emergency filter system
Temporary Ventilation Systems (IP Section 03.02) (2 Samples)
The inspectors evaluated the configuration of the following temporary ventilation systems:
(1)high efficiency particulate air filtration (RPS-700-1 and RPS-700-2) utilized for turbine deck sandblasting operations for work tent operations, SWP-202-564, Task 1; Work Order 5483010-0830 (2)high efficiency particulate air filtration (DUST COLL-1) utilized for turbine deck sandblasting operations for work tent operations, SWP-202-564, Task 1; Work Order 5483010-0830
Use of Respiratory Protection Devices (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated the licensees use of respiratory protection devices.
Self-Contained Breathing Apparatus for Emergency Use (IP Section 03.04) (1 Sample)
- (1) The inspectors evaluated the licensees use and maintenance of self-contained breathing apparatuses.
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicator submittals listed below:
OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15)===
- (1) July 1, 2023, through June 30, 2024 PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample (IP Section 02.16) (1 Sample)
- (1) July 1, 2023, through June 30, 2024
71152A - Annual Follow-up Problem Identification and Resolution Annual Follow-up of Selected Issues (Section 03.03)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
(1)reactor recirculation A motor generator set voltage regulator tuning trip resulting in unplanned power change on October 24, 2024 (2)review of apparent cause analysis performed as a result of high vibrations observed during 2-year in-service test for residual heat removal service water booster pump B on December 16, 2024
71153 - Follow Up of Events and Notices of Enforcement Discretion Notice of Enforcement Discretion (IP Section 03.04)
- (1) On November 15, 2024, the inspectors evaluated the licensee actions surrounding Notice of Enforcement Discretion EA-24-036, which can be accessed at http://www.nrc.gov/reading-rm/doc-collections/enforcement/notices/noedreactor.html.
The inspectors previously documented NCV 05000298/2024002-05, Failure to Translate the Design Requirements into Plant Configuration, associated with the cause of the need to request a Notice of Enforcement Discretion.
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On October 11, 2024, the inspectors presented the occupational radiation safety inspection results to Khalil Dia, Site Vice President, and other members of the licensee staff.
- On October 11, 2024, the inspectors presented the inservice inspection results to Khalil Dia, Site Vice President, and other members of the licensee staff.
- On November 13, 2024, the inspectors presented the inservice inspection re-exit meeting inspection results to Matthew Nee, Acting Director of Nuclear Assurance, and other members of the licensee staff.
- On January 7, 2025, the inspectors presented the integrated inspection results to John Dent Jr., Executive Vice President and Chief Nuclear Officer, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
CR-CNS-
23-00556, 2023-00665, 2023-00666, 2023-00783, 2023-
01842, 2023-02262, 2023-02366
Procedures
2.2.15
Startup Transformer
Procedures
2.2.16
Normal Station Service Transformer
Procedures
2.2.17
Emergency Station Service Transformer
Procedures
2.2.18.1
4160V Auxiliary Power Distribution System
Procedures
2.2.18.3.DIV2
4160V Div 2 Distribution Support
Procedures
2.2.18.4
4160V Distribution Abnormal Power
2.2A.CS.DIV1
System Operating Procedure, Core Spray Component
Checklist (Div 1)
Procedures
2.2A 4160.Div0
4160 VAC Non-Divisional Auxiliary Power Checklist
Procedures
2.2A_4160.DIV2
4160 VAC Auxiliary Power Checklist (DIV 2)
Work Orders
CNS-FP-229
Cable spreading room, elevation 918'-0"
Fire Plans
CNS-FP-237
Division 2 emergency diesel generator room, elevations
917-foot 6-inches and 903-foot 6-inches
Procedures
2.2.30
Fire Protection System
Procedures
2.2.30A
Fire Protection System Component Checklist
Procedures
2.2.30B
Fire Protection System Instrument Valve Checklist
Procedures
2.3_FP-1
Fire Protection Annunciator 1
Procedures
2.3_FP-2
Fire Protection (Manual Pull Alarms) Annunciator 2
Procedures
2.3_FP-3
Fire Protection Annunciator 3
Procedures
2.3_FP-4
Fire Protection Annunciator 4
Procedures
2.3_FP-5
Fire Protection Annunciator 5
Corrective Action
Documents
CR-CNS-
22-04197, 2022-04218, 2022-04392, 2022-04405, 2022-
04491, 2022-04492, 2022-04560, 2022-04562, 2022-04735,
22-04869, 2022-04908, 2022-04931, 2022-04954, 2022-
05016, 2022-05017, 2022-06210, 2022-06231, 2022-06757,
22-06880, 2023-00149, 2023-00572, 2023-01001, 2023-
03700, 2023-04238, 2023-04346, 2023-04724, 2023-05269,
24-00353, 2024-00537, 2024-00556, 2024-00862, 2024-
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
01188, 2024-01273
Corrective Action
Documents
Resulting from
Inspection
CR-CNS-
24-04398, 2024-04405, 2024-04409
Procedures
Administrative
Procedure 0-
CNS-IS-109
Compressed Gas Cylinder Handling and Storage
Procedures
CNS Operations
Manual
Maintenance
Procedure 7.7.3.1
General Welding Standard for ASME and ANSI Code
Applications
Procedures
CNS Operations
Manual
Surveillance
Procedure
6.MISC. 504
ASME Class 1 10 Year System Leakage Test
Procedures
CNS Operations
Manual
Surveillance
Procedure
6.RCIC.502
ASME Section XI System Leakage Test of The Class 2
Reactor Core Isolation Cooling (RCIC) System in Steam
Tunnel
Procedures
Operations
Manual
Engineering -
Programs
Maintenance
Procedure
7.7.10.2
P1-B Welding Procedure Specification
Procedures
Operations
Manual
Engineering -
Programs
Maintenance
P1-G Welding Procedure Specification
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedure
7.7.10.4
Procedures
Operations
Manual
Engineering -
Programs
Maintenance
Procedure
7.7.10.6
P1-BG Welding Procedure Specification
Procedures
Wet or Dry Magnetic Particle Examination Procedure
Procedures
VT-1, VT-3
General and Detailed Visual Examinations
Procedures
ASME Section XI Flaw Characterization
Procedures
PDI Generic Procedure for the Ultrasonic Through-Wall and
Length Sizing of Planar Flaws in Reactor Pressure Vessel
Welds PDI-UT-7
Procedures
54-ISI-135-012
Conventional and Phased Array Ultrasonic Linearity
Measurements
Procedures
54-ISI-173
ASME Section XI Examination Coverage
Procedures
54-ISI-240-051
Visible Solvent Removable Liquid Penetrant Examination
Procedure
Procedures
54-ISI-805-012
PDI Generic Procedure for Ultrasonic Examination of
Reactor Pressure Vessel Welds PDI-UT-6
Procedures
54-ISI-829-014
PDI Generic Procedure for the Ultrasonic Examination of
Dissimilar Metal Welds PDI-UT-10
Procedures
54-ISI-835-020
Ultrasonic Examination of Ferritic Pipe Welds
Procedures
54-ISI-836-020
PDI Generic Procedure for the Ultrasonic Examination of
Austenitic Piping Welds PDI-UT-2
Procedures
54-ISl-363-010
Remote Visual Examination of Reactor Pressure Vessel
Internals Components, and Associated Repairs in Boiling
Water Reactors
Procedures
54-ISl-837-015
Ultrasonic Through-Wall Sizing in Piping Welds
Procedures
Administrative
Procedure 0.7.1
Control Of Combustibles
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
CNS Operations
Manual
Engineering
Procedure 3.10.1
UT (Ultrasonic Testing) Thickness Measurements and
Gridding Procedure
Procedures
CNS Operations
Manual
Engineering
Procedure
3.28.1.6
Visual Examination of Containment Bolting, VT-1
Procedures
CNS Operations
Manual
Surveillance
Procedure
6.1RHR.501
ASME Section XI Periodic Pressure Test of The Class 2
Residual Heat Removal System Loop A
Procedures
CNS Operations
Manual
Surveillance
Procedure
6.HPCI.502
ASME Section XI System Leakage Test of The Class 2 High
Pressure Coolant Injection (HPCI) System Pressure
Retaining Components in The Steam Tunnel
Work Orders
WO 242441, 5381126, 5381199, 5391483, 5391485, 5391487,
5391488, 5407844, 5465374, 5465451
Procedures
5.7.1
Emergency Classification
Procedures
5.7.1.1
Emergency Classification Process
Procedures
5.7.7
Activation of TSC
Procedures
5.7.8
Activation of OSC
Procedures
5.7.9
Activation of EOF
Procedures
5.8
Emergency Operation Procedures (EOPs)
Miscellaneous
0-CNS-LI-101
Evaluation 2024-2, Attachment 1 - 50.59 Evaluation Form
Miscellaneous
NEDC 88-233
Emergency Diesel Generator Fuel Requirements
Procedures
2.1
Procedures
2.5
Procedures
2.6
Procedures
2.2.32
Fuel Pool Cooling and Demineralizer System
117
Procedures
2.2.32A
Fuel Pool Cooling and Demineralizer System Component
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Checklist
2.2.32B
Fuel Pool Cooling and Demineralizer System Instrument
Valve Checklist
6.1REC.101
REC Surveillance Operation (IST) (DIV 1)
Revision 23
6.CSCS.402
Off-Line ECCS Injection Check Valve Operating IST Torque
Test and Position Indication Test
Revision 22
7.3.1.11
GE Type IAC Relay Testing and Maintenance
Revision 11
Procedures
6.MISC.401
Position Indicator Inservice Testing (IST)
Revision 22
Work Orders
WO 5483396, 5482639, 5483471, 5475486, 5475513, 5491663,
5375177, 4921470, 5475615
Miscellaneous
CS-1-RE33 SDC
WINDOW
Protected Equipment Clearance Order
Miscellaneous
EE-1-ESST-RE33
Protected Equipment Clearance Order
Miscellaneous
RHRB-1-RE33
Protected Equipment Clearance Order
Miscellaneous
TCC-5493954
Temp Power During 4160V F Bus Outage
Procedures
0-PROTECT-EQP
Protected Equipment Program
Procedures
3-CNS-DC-151
PSA Maintenance and Update
Procedures
3-CNS-DC-355
Technical Specification Surveillance Frequency Control
Program
Procedures
3-CNS-DC-355-
Surveillance Test Interval Change (STIC) Evaluations
Procedures
3-CNS-HU-104
Engineering Task Risk & Rigor
Procedures
CNS-LI-100
Administrative Procedure Process Applicability
Determination
Corrective Action
Documents
CR-CNS-
24-04177, 2024-03943, 2024-04049
Procedures
2.0.12
Operator Challenges
Procedures
2.0.3
Conduct of Operations
108
2.0.6
Operational Event Response and Review
Procedures
6.2SRM.302
SRM Channel Functional Test (Reactor Not In Run With
Shorting Link Switches Closed) (DIV 2)
Revision 20
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
6.IRM.301
IRM Channel Functional Test (Mode Switch Not In Run)
(DIV 1)
Revision 23
6.NMS.601
IRM and SRM Detector Travel Measurement
Revision 11
Work Orders
WO 5483320, 5475537, 5475554, 5531972
Engineering
Changes
DC-5547470
Turbine Stop Valve Limit Switches
Revision 0
Procedures
3-CNS-DC-112
Engineering Change Request and Project Initiation Process
Procedures
3-CNS-DC-128
Fire Protection Program Change Review
Procedures
3.4
Configuration Change Control
AH
Procedures
3.4.4
Temporary Configuration Change
3.4.5
Engineering Evaluations
Procedures
6.RPS.302
Main Turbine Stop Valve Closure and Steam Valve
Functional Test
Revision 67
Corrective Action
Documents
CR-CNS-
24-05071, 2024-03265
Miscellaneous
5.3AC-Outage
Restore SDC, Lesson SKL05151332
Procedures
2.1.1
Startup Procedure
207
Procedures
2.1.1.2
Technical Specifications Pre-Startup Checks
Procedures
2.1.20.1
Restoration form RPV Refueling
Procedures
2.1.20.2
Cycle Specific Fuel Transfer and Alternate Cooling
Guideline
Procedures
2.1.20.3
RPV Refueling Preparation (Wet Lift of Dryer and Separator)
Procedures
2.1.6
Primary Containment Access Preparation and Closeout
Activities
Procedures
2.2.31
Fuel Handling - Refueling Platform
Procedures
2.2.31A
Fuel Handling - Refueling Platform Component Checklist
2.4PC
Primary Containment Control
6.PC.522
Standby Nitrogen Injection and PC Purge and Vent System
Local Leak Rate Tests
Revision 22
6.REACT.603
Shutdown Margin Evaluation
Revision 14
Procedures
6.SC.603
Technical Specification Verification of Secondary
Containment Manual Valves and Blind Flanges
Revision 11
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
6.SC.701
Technical Specification Verification of Secondary
Containment Access Doors and Hatches
Revision 6
Work Orders
WO 5475605, 5467676, 5475576, 5475663, 5531972, 5475672,
5166168, 5497232, 5467146, 5474619, 5475720, 5475475,
5483286, 5475615, 5475486, 5465406, 5475513, 5482781,
5475605, 5475515, 5475570, 5484635, 5475695, 5475582,
5482689
Procedures
2. 7.2.42.2
RHR Heat Exchanger Maintenance
Procedures
2.6.1RHR.102
RHR Pump Operability Test (IST) (Div 1)
Procedures
3. 7.2.44.2
RHR-MOV-M027A and RHR-MOV-M027B Maintenance
Procedures
3.6.1DG.302
Undervoltage Logic Function, Load Shedding, and
Sequential Loading Test (Div 1)
101
4.7.3.31.6
Safety-related 125V/250V Battery Cell Replacement
6.1DG.302
Undervoltage Logic Functional Load Shedding, and
Sequential Load Test (DIV 1)
Revision 100
Procedures
6.1EE.301
Undervoltage Relay Testing of Model GE IAV-54E (DIV 1)
Revision 1
Procedures
5.7.2.24
Main Steam Isolation Valve Maintenance
Procedures
6.2.2.17
Emergency Station Service Transformer
Procedures
6.2RHR.102
RHR Pump Operability Test (IST) (Div 2)
Procedures
6.ADS.201
ADS Manual Valve Actuation (IST)
Procedures
6.CSCS.301
CSCS Initiation Logic Relay Contact Testing
6.CSCS.402
Off-Line ECCS Injection Check Valve Operating IST Torque
Test and Position Indication Test
Procedures
6.RHR.301
RHR Initiation and Containment Spray Logic System
Functional Test
Revision 29
Procedures
7.0.8.1
System Leakage Testing
Procedures
7.7.3.13
Motor Control Center and Local Auxiliary Shutdown Panels
Examination and Maintenance
Work Orders
WO 5482617, 5568290, 5481065, 5482639, 5483471, 5475493,
5483151, 5483199, 5483200, 5483205, 5483206, 5483207,
5475495, 5547958, 5483482, 5482639, 5483471, 5466382,
5481065, 5475486, 5474617, 5482689, 5482692, 5484635,
5512195, 5483386, 5375177, 5482617, 5568290
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
ALARA Plans
23-02
MS-V-1008 Repairs
05/16/2023
ALARA Plans
23-03
MS-V-70 Leak Repairs
05/16/2023
ALARA Plans
23-06
RWCU-P-B Power Frame Replacement
11/30/2023
ALARA Plans
24-05
Refuel
08/29/2024
ALARA Plans
24-35
Fuel Pool Cooling Maintenance
08/01/2024
ALARA Plans
24-36
RWCU Outage
07/18/2024
Corrective Action
Documents
CR-CNS-
23-04784, 2023-04881, 2023-05045, 2023-05081, 2023-
234, 2023-05290, 2024-00542, 2024-00656, 2024-00906,
24-00907, 2024-00937, 2024-00947, 2024-00992, 2024-
01097, 2024-01110, 2024-01409, 2024-01427, 2024-02856,
24-03047, 2024-04339, 2024-04365, 2024-04370
Corrective Action
Documents
LO-2024-
0077-015, 0077-016, 0077-017, 0077-018, 0134-001
Miscellaneous
NLS2024003
CFR 31.5(c)(5) Required 30 Day Report - Unauthorized
Disassembly of Liquid Scintillation Detector
01/15/2024
Procedures
0-CNS-LI-102
Corrective Action Process
Procedures
9.ALARA.1
Dosimetry Administration
Procedures
9.ALARA.4
Radiation Work Permits
Procedures
9.ALARA.5
ALARA Planning and Controls
Procedures
9.ALARA.6
ALARA Program
Procedures
9.NISP-RP-03
Radiological Air Sampling
Procedures
9.NISP-RP-04
Radiation Protection Posting and Labeling
Procedures
9.NISP-RP-05
Access Control for Radiologically Controlled Areas
Procedures
9.NISP-RP-07
Radioactive Material Control
Procedures
9.NISP-RP-10
Radiological Job Coverage
Procedures
9.RADOP.1
Radiation Protection at CNS
Procedures
9.RADOP.123
Radiological Controls for Highly Radioactive Objects
Procedures
9.RADOP.2
Radiation Safety Standards and Limits
Radiation
Surveys
Condenser Phase Separation Tanks
09/15/2023
Radiation
Surveys
RWCU Pump Room 1B
11/27/2023
Radiation
RWCU Pump 1B Impeller Removal
11/28/2023
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Surveys
Radiation
Surveys
Dryer/Separator Pit to Remove Main Steam Line Boxes
05/22/2024
Radiation
Surveys
Radwaste Building 877' Quarterly Survey
06/19/2024
Radiation
Surveys
RWCU Pump Room 1B
09/16/2024
Radiation
Surveys
Drywell - Under Vessel - Initial Survey
09/30/2024
Radiation
Surveys
SWP 2023-115
Air Sample for RWCU-P-B Impeller Removal
11/28/2023
Radiation
Surveys
SWP 2024-111
Air Sample for Removal/Repair of FPC-AO-A011B
01/25/2024
Radiation Work
RWCU Pump "B" Maintenance
Radiation Work
OPS and RP Activities - SWP for ALL Buildings
Radiation Work
Turbine Building - Locked HRA Activities
Radiation Work
Steam Leak Mitigation
Radiation Work
Torus Desludge SUPPORT
Radiation Work
Radiation Work
Refuel Floor Misc. - SWP
Self-Assessments 2023
Radiation Protection Program Annual Report
05/28/2024
Self-Assessments LO-2023-0211
Radiological Hazard Assessment and Exposure Controls
and In-Plant Airborne Radioactivity Control and Mitigation
and Performance Indicator Verification
07/31/2024
Self-Assessments QAD 2024-016
NIOS Audit 24-04, Radiological Controls
09/11/2024
Corrective Action
Documents
CR-CNS-
22-05204, 2022-06660, 2023-03848, 2024-01498, 2024-
2582, 2024-02713, 2024-02906
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
15.HV.102
TSC Emergency Ventilation Charcoal and HEPA Filter Leak
Test, Fan Capacity Test, and Charcoal Sampling
Procedures
15.HV.104
Training Center Emergency Ventilation Charcoal and HEPA
Filter Leak Test, Fan Flow and Pressurization Test, and
Charcoal Sampling
Procedures
9.INST.37
Constant Air Monitors
Procedures
9.RESP.1
Respiratory Protection Program
Procedures
9.RESP.2
Self-Contained Breathing Apparatus
Procedures
9.RESP.5
Air Quality Monitoring
Procedures
HSI-10
Respiratory Protection
Radiation Work
Undervessel CRDMs Changeout
09/27/2024
Radiation Work
TG Deck Sandblasting
09/27/2024
Self-Assessments QAD 2024-016
NIOS Audit 24-04, "Radiological Controls"
09/11/2024
Work Orders
5482799-0030
Remove Shoot Out Steel
09/27/2024
Work Orders
5483010-0830
Dust Blast LP1 Rotor
07/27/2024
Corrective Action
Documents
CR-CNS-
24-00260
Drawings
2008612
Cooper Nuclear Station Residual Heat Removal Service
Water Booster Pumps, Contract E-68-25
Procedures
0-CNS-LI-102
Corrective Action Process
Procedures
2.2.70
RHR Service Water Booster Pump System
Procedures
6.2SWBP.101
RHR Service Water Booster Pump Flow Test and Valve
Operability Test (Div 2)
Procedures
2.0.3
Conduct of Operations
108
Procedures
3.3SAFE
Safety Assessment
Procedures
3.4
Configuration Change Control
AH
Procedures
3.4.5
Engineering Evaluations
2