IR 05000298/2023003
| ML23305A144 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 11/02/2023 |
| From: | William Schaup NRC/RGN-IV/DORS/PBC |
| To: | Dia K Nebraska Public Power District (NPPD) |
| References | |
| IR 2023003 | |
| Download: ML23305A144 (24) | |
Text
November 02, 2023
SUBJECT:
COOPER NUCLEAR STATION - INTEGRATED INSPECTION REPORT 05000298/2023003
Dear Khalil Dia:
On September 30, 2023, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Cooper Nuclear Station. On October 5, 2023, the NRC inspectors discussed the results of this inspection with John Dent, Executive Vice President and CNO, 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, William T. Schaup, Jr., Acting Branch 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-2023-003-0010
Licensee:
Nebraska Public Power District
Facility:
Cooper Nuclear Station
Location:
Brownville, NE
Inspection Dates:
July 1, 2023, to September 30, 2023
Inspectors:
G. Birkemeier, Resident Inspector
K. Chambliss, Senior Resident Inspector
R. Kopriva, Senior Project Engineer
J. O'Donnell, Senior Health Physicist
W. Schaup, Acting Branch Chief
S. Veunephachan, Health Physicist
Approved By:
William T. Schaup, Jr., Acting Branch 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
Type Issue Number Title Report Section Status LER 05000298/2022-002-01 Manual Core Spray Injection to Restore Skimmer Surge Tank Level 71153 Closed
PLANT STATUS
Cooper Nuclear Station began the inspection period at rated thermal power. On August 18, 2023, power was lowered to approximately 65 percent for a planned rod pattern adjustment. The plant returned to rated thermal power on August 19, 2023. On September 30, 2023, power was lowered to approximately 80 percent for flexible power operations. The plant returned to rated thermal power on October 1,
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 hot temperatures for the following systems:
- emergency diesel generators on July 24, 2023
- heating, ventilation, and air conditioning on July 24, 2023
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
(1)reactor core isolation cooling system on July 14, 2023 (2)emergency diesel generator division 2 on July 24, 2023 (3)125 Vdc battery system division 1 on August 15, 2023 (4)core spray subsystem B on August 15, 2023 (5)core spray subsystem A on September 27, 2023
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations during a complete walkdown of the high pressure coolant injection system on August 18, 2023.
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (7 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 standby liquid control area, 976-foot 0-inch elevation, on July 12, 2023 (2)reactor building northeast quadrant, 881-foot 0-inch and 859-foot 0-inch elevations, on July 14, 2023 (3)reactor building southeast quadrant, 881-foot 0-inch and 859-foot 0-inch elevations, on July 14, 2023 (4)reactor building northwest quadrant, 881-foot 0-inches and 859 foot 0-inches, on July 25, 2023 (5)control building battery and switchgear rooms, 903-foot 6-inch elevation, on July 25, 2023 (6)reactor building southwest quadrant, 881-foot 0-inch and 859-foot 0-inch elevations, on July 27, 2023 (7)control building critical switchgear rooms, elevation 932-foot 6-inch elevation, on July 27, 2023
Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the onsite fire brigade training and performance during an announced fire drill on August 16, 2023.
71111.07A - Heat Exchanger/Sink Performance
Annual Review (IP Section 03.01) (1 Sample)
The inspectors evaluated readiness and performance of:
- (1) emergency diesel generator 2 lube oil and jacket water heat exchanger on August 14, 2023
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 quarterly downpower for rod sequence exchange on August 21, 2023.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated simulator licensed operator training on July 12, 2023.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (3 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)radiation monitoring function RMP-F03 near (a)(1) on August 24, 2023 (2)core spray function CS-PF01A potentially at (a)(1) due to relay failing to fully drop out on August 24, 2023 (3)failure to properly scope in several components within the fuel pool cooling system into function FPC-F01 on September 29, 2023
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)control of quality parts and verification of quality control process for relay replacement and maintenance in various safety-related systems on September 29, 2023
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (4 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)planned Yellow online risk during residual heat removal service water booster division 1 maintenance window on July 12, 2023 (2)planned Yellow online risk during high pressure coolant injection relay maintenance on July 31, 2023 (3)emergent assessment of risk due to through wall piping leakage near discharge flange of residual heat removal service water booster pump C on August 31, 2023 (4)planned Yellow online risk during reactor core isolation cooling maintenance window on September 6, 2023
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (3 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
(1)reactor core isolation cooling lube oil cooler auxiliary cooling water supply relief valve experiencing degradation of seat leakage on July 14, 2023 (2)service water check valve to emergency diesel generator inservice test missed due to operator misinterpreting test setting value on July 24, 2023 (3)potential loss of secondary containment due to path from secondary containment to atmosphere not being identified prior to maintenance activities on August 31, 2023
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)reactor core isolation cooling system temporary modification of trip and throttle valve closing time and sequence on September 8, 2023
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) (7 Samples)
(1)high pressure coolant injection relay replacement operational testing on July 31, 2023 (2)division 1 residual heat removal service water booster maintenance window post work testing on August 1, 2023 (3)standby liquid control pump post work testing for pump and metering on August 25, 2023 (4)service water pump B maintenance window post maintenance testing on August 25, 2023 (5)service water booster pump C post work testing after through wall piping leak repairs on August 31, 2023 (6)system operability testing of core spray subsystem B following maintenance window activities on September 7, 2023 (7)reactor core isolation cooling maintenance window post maintenance and modification testing on September 29, 2023
Surveillance Testing (IP Section 03.01) (4 Samples)
(1)division 1 high pressure coolant injection steam line high flow channel functional test on July 13, 2023 (2)division 2 main steam isolation valve logic system functional test on July 31, 2023 (3)biennial residual heat removal division 2 pumps comprehensive testing on August 25, 2023 (4)high pressure coolant injection overspeed hydraulic reset timing functional test on September 20, 2023
71114.06 - Drill Evaluation
Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)
The inspectors evaluated:
- (1) full scale emergency preparedness drill on August 31,
RADIATION SAFETY
71124.05 - Radiation Monitoring Instrumentation
Walkdowns and Observations (IP Section 03.01) (9 Samples)
The inspectors evaluated the following radiation detection instrumentation during plant walkdowns:
(1)portable survey instruments "ready for use" at the exit to the radiologically controlled area (2)portable survey instruments in storage, but "available for use" in the instrument lab (3)personnel contamination monitors at the exit to the radiologically controlled area (4)portal monitors at the exit to the protected area (5)chemistry count room instruments (gamma spectroscopy and liquid scintillation)
(6)process radiation monitors in the reactor building (7)area radiation monitors in the reactor building (8)elevated release point gaseous effluent monitor in the augmented radwaste building (9)turbine building gaseous effluent monitor
Calibration and Testing Program (IP Section 03.02) (14 Samples)
The inspectors evaluated the calibration and testing of the following radiation detection instruments:
- (1) Ludlum Model 177, RP-11281, frisker
- (2) Ludlum Model 3, RP-11330, count rate meter - alpha
- (3) Ludlum Model 2401P, RP-11292, dose rate meter
- (4) Mirion Wide Range TelePole II, RP-11967, dose rate meter
- (5) Mirion TelePole, RP-11246, dose rate meter
- (6) Eberline RO-20, RP-10749, dose rate meter
- (7) HPI REM-500, RP-100516, neutron survey meter
- (8) Thermo Eberline SAM, RP-11152, contamination (small article) monitor
- (9) Canberra GEM-5, RP-11996, gamma exit monitor
- (10) Canberra ARGOS -5AB, RP-11983, personnel contamination monitor
- (11) Eberline E-140, RP-10063, dose rate meter
- (12) Victoreen Model 875, RMA-RM-40A/B, containment high range radiation monitors
- (13) Canberra High Purity Germanium Detector 01, gamma spectroscopy system
- (14) General Electric RMA-RM-1 through RMS-RM-30, area radiation monitors Effluent Monitoring Calibration and Testing Program Sample (IP Section 03.03) (3 Samples)
The inspectors evaluated the calibration and maintenance of the following radioactive effluent monitoring and measurement instrumentation:
(1)liquid radwaste effluent monitor RMP-RM-354 (2)reactor building vent monitor RMV-RM-40 (3)turbine building vent monitor RMV-RM20A
71124.08 - Radioactive Solid Waste Processing & Radioactive Material Handling, Storage, and
Transportation
Radioactive Material Storage (IP Section 03.01)
The inspectors evaluated the licensees performance in controlling, labeling and securing the following radioactive materials:
- (1) Part 37 radioactive materials and selected sealed sources (2)radioactive material storage containers stored within the radiological controlled boundary and storage site
Radioactive Waste System Walkdown (IP Section 03.02) (2 Samples)
The inspectors walked down the following accessible portions of the solid radioactive waste systems and evaluated system configuration and functionality:
(1)radioactive liquid processing system (2)solid radioactive processing system
Waste Characterization and Classification (IP Section 03.03) (2 Samples)
The inspectors evaluated the following characterization and classification of radioactive waste:
(1)2022 Part 61 spent bead resin waste stream analysis and characterization (2)2022 Part 61 dry active waste stream analysis and characterization
Shipping Records (IP Section 03.05) (4 Samples)
The inspectors evaluated the following non-excepted radioactive material shipments through a record review:
- (2) Shipment number 22-05, UN2916, Yellow-III, Type B(U), Class AU mixed bead resin
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
IE01: Unplanned Scrams per 7000 Critical Hours Sample (IP Section 02.01)===
- (1) July 1, 2022, through June 30, 2023 IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02) (1 Sample)
- (1) July 1, 2022, through June 30, 2023
MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04) (1 Sample)
- (1) July 1, 2022, through June 30, 2023
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)review of follow-up actions regarding relays subject to 10 CFR Part 21 notification on September 29, 2023
71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02)
(1)human performance trend resulting in configuration management, configuration control, and in-service testing issues on September 1, 2023
71153 - Follow Up of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)
The inspectors evaluated the following licensee event reports (LERs):
- (1) LER 05000298/2022-002-01, Manual Core Spray Injection to Restore Skimmer Surge Tank Level (ADAMS Accession No. ML23180A170). The circumstances surrounding this LER and a Green, non-cited violation are documented in the Cooper Nuclear Station - Biennial Problem Identification and Resolution Inspection Report 05000298/2023010 (ML23135A107). This LER is closed.
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On August 24, 2023, the inspectors presented the public radiation safety inspection results to Bill Chapin, General Manager of Plant Operations, and other members of the licensee staff.
- On October 5, 2023, the inspectors presented the integrated inspection results to John Dent, Executive Vice President and CNO, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
CR-CNS-
22-01568, 2022-01692, 2022-02600, 2022-03646, 2023-
01821, 2023-01825, 2023-02721, 2023-03807, 2023-03882
0-CNS_FAP-WM-
016
Seasonal Reliability
2.1.12
Control Room Data
144
2.2.38
HVAC Control Building
2.2.39
HVAC Diesel Generator Building
2.2.47
HVAC Reactor Building
2.2.84
HVAC Main Control Room and Cable Spreading Room
Procedures
2.2.93
Sewage Lagoon
Work Orders
WO 5393272, 5444141, 5444142, 5444177, 5444227, 5450139
Corrective Action
Documents
CR-CNS-
2018-08353, 2018-08576, 2021-04964, 2021-05277, 2022-
00698, 2022-01774, 2022-03120, 2022-04401, 2022-04507,
22-04797, 2022-04925, 2022-05599, 2022-05695, 2022-
06035, 2022-06037, 2022-06070, 2022-06072, 2022-06316,
23-00400, 2023-00423, 2023-00665, 2023-00975, 2023-
01149, 2023-01828, 2023-01977, 2023-01978, 2023-02401,
23-02881, 2023-02896, 2023-03347, 2023-03558, 2023-
06139, 2022-06143
DWG 2043
Reactor Core Isolation Coolant and Reactor Feed Systems
DWG 2044
High Pressure Coolant Injection and Reactor Feed Systems
DWG 2045,
Sheet 1
Flow Diagram Core Spray System
DWG 2077
Flow Diagram - Diesel Generator Building Service Water,
Starting Air, Fuel Oil, Sump System & Roof Drains
DWG 3058
DC One Line Diagram
Drawings
DWG 69-4
Valve Needle Model 500F
Clearance Order
ASB-1-2023
Summer ASB Work
Miscellaneous
Clearance Order
HPCI-1
Replace Relay K10 And K36
Procedures
0.36.8
Electrical Safety Rule Book, Revision 230.36.8, Electrical
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Safety Rule Book
2.2.20
Standby AC Power System (Diesel Generator)
116
2.2.20.1
Diesel Generator Operations
2.2.20.2
Operation of Diesel Generators from Diesel Generator Rooms
2.2.33.1
High Pressure Coolant Injection System Operations
2.2.33A
High Pressure Coolant Injection System Component Checklist
2.2.33B
High Pressure Coolant Injection System Instrument Valve
Checklist
2.2.67A
Reactor Core Isolation Cooling System Component Checklist
2.2.9
CS Subsystem A Standby Status
2.2A.CS.DIV2
Core Spray Component Checklist (DIV 2)
2.2A.DG.DIV2
Standby AC Power System (Diesel Generator) Component
Checklist (DIV 2)
2.2A.DGDO.DIV1
Diesel Fuel Oil Transfer System Component Checklist (DIV 2)
2.2A_125DC.DIV1
25 VDC Power Checklist (DIV 1)
2.2B.DG.DIV2
Standby AC Power System (Diesel Generator) Instrument
Valve Checklist (DIV 2)
2.2B.DGDO.DIV2
Diesel Fuel Oil Transfer System Instrument Valve Checklist
(DIV 2)
2.3_DG2
Panel DG-2 - Annunciator DG-2
6.HPCI.311
HPCI Turbine Trip and Initiation
6.HPCI.311
HPCI Turbine Trip and Initiation Logic Functional Test
6.HPCI.313
HPCI (</= 165 PSIG) Beginning of Cycle Test
6.HPCI.318
HPCI Simulated Actuation Test (IST)
Corrective Action
Documents
CR-CNS-
2018-02084, 2018-02385, 2018-06275, 2019-00903, 2019-
01368, 2019-02575, 2019-06278, 2020-00766, 2020-00874,
20-05971, 2021-00495, 2021-02855, 2021-03030, 2021-
03150, 2021-03189, 2021-03981, 2022-00209, 2022-04525,
22-05579, 2023-00550, 2023-01031, 2023-01108, 2023-
01109, 2023-01725, 2023-03496
CNS-FP-211
Reactor Building Northeast Quadrant Elevations 881-9" and
859-9
Fire Plans
CNS-FP-212
Reactor Building Southeast Quadrant Elevations 881-9" and
859-9
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
CNS-FP-213
Reactor Building Northwest Quadrant Elevations 881-9 and
859-9
CNS-FP-214
Reactor Building Southwest Quadrant Elevations 881-9 and
859-9
CNS-FP-216
Reactor Building Critical Switchgear Room 1F Elevation 932-
CNS-FP-217
Reactor Building Critical Switchgear Room 1G Elevation 932-
CNS-FP-220
Reactor Building SBLC Area Elevation 976-0
CNS-FP-227
Control Building Corridor Battery/Switchgear/RPS Rooms 1A
Elevation 903-6
CNS-FP-228
Control Building Corridor Battery/Switchgear/RPS Rooms 1B
Elevation 903-6
CNS-FP-245
Turbine Generator Building North - Condensate Pump Area
Elevation 882-6
0-BARRIER
Barrier Control Process
0-BARRIER-
CONTROL
Control Building
0-BARRIER-
MAPS
Barrier Maps
0-BARRIER-MISC
Miscellaneous Buildings
0-BARRIER-
REACTOR
Reactor Building
0-BARRIER-
TURBINE
Turbine Building
0.23
CNS Fire Protection Plan
0.7.1
Control of Combustibles
2.2.30
Fire Protection System
5.1INCIDENT
Site Emergency Incident
5.4POST-FIRE-
TURBINE
Turbine Building/Outside Areas Post-Fire Operational
Information
Procedures
EPIPEALHOT
Corrective Action
Documents
CR-CNS-
23-01843, 2023-01849, 2023-01965, 2023-01976, 2023-
01977, 2023-02019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Drawings
DWG KSV-47-9-
NP
Jacket Water Schematic
Miscellaneous
VM-1778
ITT/American Heat Exchangers Composite Manual
Work Orders
Corrective Action
Documents
CR-CNS-
21-01581, 2021-01938, 2022-03751, 2023-03791, 2023-
03792, 2023-03793, 2023-03794
10.13
Control Rod Sequence and Movement Control
10.14
Reactivity Maneuver Plan
15.TG.301
Main Turbine Lube Oil Pumps Functional Test
2.0.3
Conduct of Operations
106
2.1.10
Station Power Changes
23
2.3_C-2
Panel C - Annunciator C-2
2.4EX-STM
Extraction Steam Abnormal
2.4PC
Primary Containment Control
2.4RR
Reactor Recirculation Abnormal
RPV Control (1-3)
Primary Containment Control (1-3)
Procedures
EPIPEALHOT
Corrective Action
Documents
CR-CNS-
2019-01609, 2019-01613, 2019-01672, 2019-01673, 2019-
01674, 2019-01675, 2019-01676, 2020-01995, 2020-02930,
20-04733, 2020-05244, 2021-03316, 2021-05792, 2022-
201, 2022-00225, 2022-00452, 2022-04449, 2022-05293,
22-05296, 2022-05574, 2023-01010, 2023-01055, 2023-
252, 2023-02263, 2023-02274, 2023-02298, 2023-02545,
23-03260, 2023-03421
DWG 3752,
Sheet 3
Annunciator Loop Diagram ANN-MUX-2
DWG 791E265,
Sheet 2
Elementary Diagram Core Spray System
DWG 791E265,
Sheet 3
Elementary Diagram Core Spray System
Drawings
DWG 791E269,
Sheet 1
Elementary Drawing Fuel Pool Cooling and Cleanup System
Miscellaneous
Maintenance Rule Function FPC-F01 Performance Criteria
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Basis Document
Maintenance Rule Function RMP-F03 Performance Criteria
Basis Document
Maintenance Rule Function CS-PF01A Performance Criteria
Basis Document
Maintenance Rule (a)(1) Evaluation, CR 2023-02298
07/25/2003
VM-0469
Rad Monitoring
VM-1025
Operations & Maintenance Instructions
0-CNS-FAP-QV-
400
Quality Control Hold Point Independent Review
0.50.5
Outage Shutdown Safety
2.1
2.5
2.4FPC
Fuel Pool Cooling Trouble
3-CNS-DC-112
Engineering Change Request and Project Initiation Process
3-CNS-DC-213
Engineering Quality Review
4.15
Elevated Release Point and Building Kaman Radiation
Monitoring Systems
5.8.17
Primary Containment Venting
5.8.18
Primary Containment Venting for PCPL, PSP, Primary
Containment Flooding, or Early Containment Venting
5.8.21
PC Venting and Hydrogen Control (Less Than Combustible
Limits)
5.8.21
PC Venting and Hydrogen Control (Greater Than Combustible
Limits)
5.8.23
Decay Heat Removal Methods
Primary Containment Control (1-3)
RPV Control (4)
Procedures
Decay Heat Removal (5,D)
Work Orders
WO 5300313, 5386055, 5430830, 5463574, 5503728, 5504618,
5504641
Corrective Action
Documents
CR-CNS-
20-00907, 2023-01453, 2023-03091, 2023-03136, 2023-
03909, 2023-03911, 2023-03947
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Protected Equipment Tagout RHWA-1-SW-P-BPA WEEK
27
Protected Equipment Tagout RHWA-1-SW-P-BPCLEAK
Protected Equipment Tagout RCIC-1-RCIC TCC WEEK 2336
Miscellaneous
Protected Equipment Tagout HPCI-1-HPCI WK 2330
0-CNS-FAP-OM-
031
Emergent Issue Response, Risk Classification, and Oversight
Determination
0-CNS-WM-104
On-Line Risk Assessment
0-PROTECT-EQP
Protected Equipment Program
2, 63
2.0.2
Operation Logs and Reports
23
Procedures
7.0.8.1
System Leakage Testing
Work Orders
Corrective Action
Documents
CR-CNS-
23-01325, 2023-03253, 2023-03296, 2023-03561, 2023-
03580
DWG 2012,
Sheet 1
Flow Diagram Building Heating and Auxiliary Steam Systems
DWG 2012,
Sheet 2
Flow Diagram Building Heating and Auxiliary Steam Systems
DWG 2012,
Sheet 3
Flow Diagram Building Heating and Auxiliary Steam Systems
DWG 2012,
Sheet 4
Flow Diagram Building Heating and Auxiliary Steam Systems
DWG 2012,
Sheet 5
Flow Diagram Building Heating and Auxiliary Steam Systems
Drawings
DWG 2041
Flow Diagram Reactor Building Main Steam System
VM-0005
Consolidated Safety & Relief Valve Composite Manual
NEDC 07-082
Radiological Dose Analysis for a Loss of Coolant Accident
(LOCA) at Cooper Nuclear Station
Miscellaneous
VM-0227
Cast Steel Valves
0-CNS-31
CNS Clearance Order and Lockout Standards
13.1
ECCS Leakage Evaluation
Procedures
6.1SW.401
Diesel Generator Service Water Check Valve and Sump Test
(IST)(DIV 1)
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
6.MISC.501
ECCS Leakage Walkdown
6.SC.501
Secondary Containment Leak Test
6.SC.502
Secondary Containment Penetration Examination
Work Orders
WO 5401965, 5453354
BWR Owners Group Report on the Operational Design Basis
of Safety-Related Motor Operated Valves
NEDC 87-131C
25 VDC Division 1 Load and Voltage Study
CCN 19C8
NEDC 91-079
System Level Design Basis Review for Reactor Core Isolation
Cooling System MOVs
Calculations
NEDC 96-039
RC-Powered Motor Operated Valve Stroke Time and
Capability Calculation
Corrective Action
Documents
CR-CNS-
23-02885
Drawings
DWG
29E517BC,
Sheet 3
Reactor Core Isolation Cooling System Functional Control
Drawing
Temporary Configuration TCC-5503748, RCIC Jumpers For
RCIC Turbine Trip on High Water Level
Miscellaneous
VM-0075
RCIC Pump Drive
0.31MOV
Motor Operated Valves
0.4LSFT
Logic System Functional Test (LSFT) Guidelines
2.2.67
Reactor Core Isolation Cooling System
2.2.67.1
Reactor Core Isolation Cooling System Operations
3-CNS-DC-354
Risk Assessment of Surveillance Test Interval Changes
4.6.1
Reactor Vessel Water Level Indication
Procedures
6.RCIC.102
Work Orders
Corrective Action
Documents
CR-CNS-
20-00181, 2020-00677, 2020-01524, 2020-01990, 2020-
2944, 2021-03591, 2023-02252, 2023-03381, 2023-03436,
23-03909, 2023-03911, 2023-03947
DWG 2006,
Sheet 1
Flow Diagram Circulating, Screen Wash, & Service Water
Systems
Drawings
DWG 2006,
Sheet 4
Flow Diagram Control Building Service Water System
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
DWG 2026,
Sheet 1
Flow Diagram Reactor Vessel Instrumentation
DWG 2040,
Sheet 2
Flow Diagram Residual Heat Removal System Loop B
DWG 2045,
Sheet 1
Flow Diagram Core Spray System
DWG 2045,
Sheet 1
Flow Diagram Core Spray System
DWG 2C4747
28KXL1STGVCT Service Water Pump
DWG-2044
Flow Diagram - High Pressure Coolant Injection and Reactor
Feed Systems
DWG-791E271,
Sheet 4
Elementary Diagram HPCI System
Protected Equipment Tagout RHWA-1-SW-BPA WEEK 2327
Miscellaneous
VM-1824
Allen Bradley Composite Manual
6.1HPCI.701
HPCI Steam Line High Flow Channel Functional Test (DIV 1)
6.1SWBP.101
RHR Service Water Booster Pump Flow Test and Valve
Operability Test (DIV 1)
6.2RHR.101
RHR Test Mode Surveillance Operation (IST) (DIV2)
6.2RPS.305
MSIV Channel Logic Test (DIV 2)
6.2SC.101
Core Spray Test Mode Surveillance Operation (IST) (DIV 2)
6.2SC.501
ASME Section XI Periodic Pressure Test of Class 2 Core
Spray System Loop B
6.2SW.101
Service Water Surveillance Operation (DIV 2) (IST)
6.HPCI.312
HPCI Pump Low Discharge Flow Channel Calibration
6.HPCI.317
HPCI Overspeed Hydraulic Reset Timing Calibration and
Functional Test
6.HPCI.709
HPCI Gland Seal Condenser Hotwell Level Channel
Functional Test
6.RCIC.102
6.RCIC.201
RCIC Power Operated Valve Operability Test (IST)
6.SLC.101
SLC Pump Operability Test
Procedures
7.0.14.2.2
Oil Sampling
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
7.0.8.1
System Leakage Testing
Work Orders
WO 5356822, 5389891, 5399151, 5405058, 5405064, 5407274,
5407315, 5407316, 5407322, 5412210, 5412228, 5414706,
5455461, 5455551, 5455622, 5455635, 5503746, 5504618,
5504641, 5512675,
Corrective Action
Documents
CR-CNS-
23-03934, 2023-03936, 2023-03943, 2023-03944, 2023-
03946, 2023-03954
2.1.5
Reactor Scram
2.4FPC
Fuel Pool Cooling Trouble
2.4PC
Primary Containment Control
2.4TURB
Main Turbine Abnormal
5.1QUAKE
5.3ALT-
STRATEGY
Alternate Core Cooling Mitigating Strategies
5.3DC125
Loss of 125 VDC
5.3EMPWR
Emergency Power During Modes 1,2, or 3
5.3SBO
Station Blackout
5.7.2
Emergency Director EPIP
5.7.6
Notification
5.8.1
RPV Pressure Control Systems
RPV Control (1-3)
Alternate Level/Pressure Control
Primary Containment Control (1-3)
Procedures
EPIPEALHOT
CNS Wall Chart Hot
5166228 /
5166232 /
5398873
14.8.16 KAMAN System Flow Indication Calibration
2/17/2021
and
03/03/2021
and
06/02/2021
5166232
6.PRM.315 Turbine Building KAMAN Channel Calibration
03/05/2021
5166732
6.PRM.329 Containment High Range Monitors A/R/H
Determination
10/03/2018
Calibration
Records
238323 /
248168
15.ARM.302 Area Radiation Monitors Calibration and
Functional Test - 2020
03/06/2020
and
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
06/01/2020
282475
6.PRM.323 High Range Containment Monitor Victoreen
Model 875 Source Calibration Check
10/04/2020
5315880 /
5413628 /
5340429
15.ARM.302 Area Radiation Monitors Calibration and
Functional Test - 2021
10/14/2021
and
2/30/2021
5358399
6.PRM.313 Reactor Building KAMAN Monitor Channel
Calibration
08/17/2022
5362794
6.PRM.308 Liquid Radwaste Effluent System Channel
Calibration
08/31/2022
5384952
6.PRM.322 Containment High Range Area Monitor Channel
Calibration
10/27/2022
5399148
6.PRM.322 SW Radiation Monitor B Calibration Check and
Instrument Channel Test
05/16/2023
Detector 1 - 2
Liter Marinelli
Efficiency Confirmation Check Report
07/25/2022
Detector 1 -
Charcoal Canister
Efficiency Confirmation Check Report
08/12/2022
Detector 1 -
Particulate Filter
Efficiency Confirmation Check Report
05/20/2023
RP-100516
Certificate of Calibration
HPI REM-500
06/08/2022
RP-10063
Instrument Calibration Data Sheet
Eberline E-140
08/08/2022
RP-10749
Instrument Calibration Data Sheet
Eberline RO-20
03/14/2023
RP-11152
Instrument Calibration Sheet
Thermo Eberline SAM
05/01/2023
RP-11246
Instrument Calibration Data Sheet
Mirion WR TelePole
03/20/2023
RP-11281
Instrument Calibration Data Sheet
Ludlum Model 177
2/02/2023
RP-11292
Instrument Calibration Data Sheet
Ludlum Model 2401P
06/06/2023
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
RP-11330
Instrument Calibration Data Sheet
Ludlum Model 3
05/10/2023
RP-11967
Instrument Calibration Data Sheet
Mirion Wide Range TelePole II
03/15/2023
RP-11983
Instrument Calibration Data Sheet
Canberra ARGOS-5AB
08/29/2022
RP-11996
Instrument Calibration Sheet
Canberra GEM-5
08/22/2022
Corrective Action
Documents
CR-CNS-
21-04133, 2021-04226, 2021-04298, 2021-04381, 2021-
04793, 2021-05062, 2022-02044, 2022-02050, 2022-02334,
22-03074, 2022-03078, 2022-04111, 2022-04318, 2022-
04646, 2022-05514, 2023-00188, 2023-01040, 2023-01967,
23-02439, 2023-02606, 2023-02725, 2023-02908, 2023-
2909, 2023-02946
Corrective Action
Documents
Resulting from
Inspection
CR-CNS-
23-03848
Miscellaneous
2Q2023
System Health Report:
Radiation Monitors
07/19/2023
3.26
Instrument Setpoint Control
07/25/2018
6.PRM.308
Liquid Radwaste Effluent System Channel Calibration
2/19/2020
6.PRM.313
Reactor Building KAMAN Monitor Channel Calibration
03/17/2021
6.PRM.315
Turbine Building KAMAN Channel Calibration
03/08/2023
6.PRM.322
Containment High Range Area Monitor Channel Calibration
2/21/2022
6.PRM.323
High Range Containment Monitor Victoreen Model 875
Source Calibration Check
2/08/2023
9.INST.50
Geiger-Mueller (GM) Survey Meters
01/12/02022
9.INST.53
Ion Chamber Survey Instrument - Eberline Model RO-20
09/08/2021
9.INST.68
WR TelePole GM Survey Instrument
07/19/2023
9.INST.70
TelePole II Telescopic Meter
10/23/2019
9.INST.71
CRONOS Gamma Object/Tool Monitor
06/15/2022
Procedures
Offsite Dose Assessment Manual
04/01/2020
Self-Assessments
LO-2022-0100
Radiological Monitoring Instrumentation and Radioactive Solid
01/19/2023
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Waste Processing and Radioactive Material Handling,
Storage, and Transport
577786003
Spent Bead Resin Waste Stream Analysis
2/03/2022
Miscellaneous
8-J Cond-WST
23 condensate waste storage tank waste stream analysis
2/27/2023
Self-Assessments
8-C 2022
71124.05-08 Pre-NRC Assessment Report
2/16/2022
2-02
Shipping record 22-02 UN 2912, LSA-I Class 7 AU
04/15/2022
Shipping Records
23-04
Shipping record UN2912 LSA-I, Dry active waste, AU
03/27/2023
Miscellaneous
Performance Indicator Documentation and Data Review
Package
0-EN-LI-114
Regulatory Performance Indicator Process
6.1SW.401
Diesel Generator Service Water Check Valve and Sump Test
(IST)(DIV 1)
71151
Procedures
6.HPCI.314
HPCI Pump Discharge Flow Indication Calibration
DWG 3071
Control Elementary Diagram
DWG 3257,
Sheet 66
Alternate Shutdown HPCI Panel Internal Connections
DWG 791E261,
Sheet 18
Elementary Drawing Residual Heat Removal System
DWG 791E261,
Sheet 21
Elementary Drawing Residual Heat Removal System
DWG 791E261,
Sheet 22
Elementary Drawing Residual Heat Removal System
DWG 791E261,
Sheet 3
Elementary Drawing Residual Heat Removal System
DWG 791E261,
Sheet 7
Elementary Drawing Residual Heat Removal System
DWG 791E271,
Sheet 6
HPCI System Elementary Diagram
DWG 791E562,
Sheet 2
Panel 9-3 Connection Diagram
DWG 791E562,
Sheet 6
Panel 9-3 Connection Diagram
Drawings
DWG CNSEE89
HPCI Flow Control and Indication Loop Diagram DC 86-21
Miscellaneous
Clearance Orders
SDG-1-5451827 SDG-VI-PSYNC 02
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
0.31.1
Configuration Control During Maintenance Activities
0.9
Tagout
113
2.2.99
Supplemental Diesel Generator System
Procedures
7.3.24.2
HFA DC and AC Relay Pick-Up Test
Corrective Action
Documents
CR-CNS-
20-05244, 2022-02778, 2022-04176, 2022-06139, 2022-
06878, 2023-00085, 2023-00400, 2023-00454, 2023-00487,
23-00492, 2023-00528, 2023-00960, 2023-01170, 2023-
01171, 2023-01317, 2023-01340, 2023-01385, 2023-01415,
23-01421, 2023-01423, 2023-01453, 2023-01956, 2023-
252, 2023-02274, 2023-02322, 2023-02357, 2023-02468,
23-02823, 2023-03026, 2023-03091, 2023-03238, 2023-
296
Work Orders
WO 5075843, 5401965, 5451827, 5503746
Corrective Action
Documents
CR-CNS-
22-05293, 2022-05296, 2023-01743, 2023-01750, 2023-
01757, 2023-01786, 2023-01842, 2023-01868
2.5FPC.F/DA
Fuel Pool Cooling Filter Demineralizer A
Procedures
2.5FPC.F/DB
Fuel Pool Cooling Filter Demineralizer A
3