IR 05000298/2022002
| ML22207A043 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 07/28/2022 |
| From: | Jeffrey Josey NRC/RGN-IV/DORS |
| To: | Dent J Nebraska Public Power District (NPPD) |
| Josey J | |
| References | |
| IR 2022002 | |
| Download: ML22207A043 (25) | |
Text
July 28, 2022
SUBJECT:
COOPER NUCLEAR STATION - INTEGRATED INSPECTION REPORT 05000298/2022002
Dear Mr. Dent:
On June 30, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Cooper Nuclear Station. On July 18, 2022, the NRC inspectors discussed the results of this inspection with Mr. K. Dia, General Manager of Plant Operations, and other members of your staff. The results of this inspection are documented in the enclosed report.
One Severity Level IV violation without an associated finding is documented in this report. We are treating this violation as a non-cited violation (NCV) consistent with section 2.3.2 of the Enforcement Policy.
No NRC-identified or self-revealing findings were identified during this inspection.
If you contest the violation or the significance or severity of the violation documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN:
Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region IV; the Director, Office of Enforcement; and the NRC resident inspector at Cooper Nuclear Station.
J. Dent, Jr.
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, Jeffrey E. Josey, Chief 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-2022-002-0010
Licensee:
Nebraska Public Power District
Facility:
Cooper Nuclear Station
Location:
Brownville, NE
Inspection Dates:
April 1 to June 30, 2022
Inspectors:
K. Chambliss, Resident Inspector
D. Dodson, Senior Reactor Inspector
M. Doyle, Acting Senior Resident Inspector
H. Freeman, Senior Project Engineer
S. Hedger, Senior Emergency Preparedness Inspector
C. Henderson, Senior Resident Inspector
W. Sifre, Senior Reactor Inspector
M. Stafford, Acting Senior Resident Inspector
H. Strittmatter, Emergency Preparedness Inspector
W. Tejada, Physical Security Inspector
F. Thomas, Reactor Inspector
Approved By:
Jeffrey E. Josey, Chief
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
Safety Relief Valve Lift Settings Outside of Technical Specifications Required Setpoints Cornerstone Severity Cross-Cutting Aspect Report Section Not Applicable Severity Level IV NCV 05000298/2022002-01 Open/Closed Not Applicable 71153 A self-revealed, Severity Level IV non-cited violation of Technical Specification 3.4.3,
Safety/Relief Valves and Safety Valves, was identified when the licensee discovered through as-found test results that two of the eight Target Rock safety relief valve pilot assemblies failed to lift within the technical specifications lift setpoint requirements.
Additional Tracking Items
Type Issue Number Title Report Section Status LER 05000298/2021-002-00 Valve Test Failures Result in Condition Prohibited by Technical Specifications 71153 Closed
PLANT STATUS
Cooper Nuclear Station began the inspection period at rated thermal power. On April 29, 2022, power was lowered to approximately 60 percent for core management. The plant was returned to rated thermal power on May 3, 2022. On May 21, 2022, power was lowered to approximately 70 percent for core management. The plant was returned to rated thermal power on May 24, 2022. On June 3, 2022, power was lowered to approximately 85 percent for core management. The plant was returned to rated thermal power on June 4, 2022. On June 17, 2022, power was lowered to approximately 70 percent for core management. The plant was returned to rated thermal power on June 20, 2022. On June 24, 2022, power was lowered to approximately 70 percent for core management. The plant was returned to rated thermal power on June 25, 2022. 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 high temperatures for the following systems:
reactor building heating, ventilation, and air conditioning
control room air conditioning
External Flooding Sample (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated that flood protection barriers, mitigation plans, procedures, and equipment are consistent with the licensees design requirements and risk analysis assumptions for coping with external flooding on April 28, 2022.
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
(1)division 1 emergency diesel generator on April 14, 2022 (2)division 1 residual heat removal on April 29, 2022 (3)standby gas treatment A on April 29, 2022 (4)core spray train A on June 17, 2022
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations during a complete walkdown of the division 2 residual heat removal service water system on June 21, 2022.
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (5 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 northeast quadrant, 881-foot 9-inch and 859-foot 9-inch elevations, on April 12, 2022 (2)reactor building standby liquid control area, 976-foot elevation, on April 28, 2022 (3)flex support building 1, 903-foot 6-inch elevation, on May 13, 2022 (4)reactor building general area, 903-foot 6-inch elevation, on May 24, 2022 (5)control building cable spreading room, 918-foot elevation, on May 25, 2022
71111.06 - Flood Protection Measures
Inspection Activities - Internal Flooding (IP Section 03.01) (1 Sample)
The inspectors evaluated internal flooding mitigation protections in the:
- (1) reactor building southwest quadrant on May 3, 2022
71111.07A - Heat Exchanger/Sink Performance
Annual Review (IP Section 03.01) (1 Sample)
The inspectors evaluated readiness and performance of:
- (1) reactor equipment cooling heat exchanger B evaluation on May 12, 2022
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 downpower to 65 percent for core management on April 30, 2022.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated a simulator training scenario on April 20, 2022.
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 remain capable of performing their intended function:
(1)service water function F04 near (a)(1) on June 2, 2022 (2)fire protection function F03 near (a)(1) on June 15, 2022 (3)reactor water cleanup function F03 at (a)(1) on June 15, 2022
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (6 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)emergency diesel generator isolation switch operability test on April 12, 2022 (2)planned Yellow risk for valve SW-MO-89B failure on April 18, 2022 (3)startup transformer maintenance window on May 10, 2022 (4)week 2220 emergent issues risk management on May 19, 2022 (5)4160 V, bus 1G, relay test on May 23, 2022 (6)high-pressure coolant injection drip leg drain test on June 27, 2022
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (6 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
(1)water leaking from REC-269 on April 14, 2022 (2)valve SW-MO-89A minimum flow setting incorrect on April 21, 2022 (3)valve SW-MO-89B failure to open on May 4, 2022 (4)wetted residual heat removal conduit on May 13, 2022 (5)reactor equipment cooling pump B breaker high-temperature delta on June 15, 2022 (6)division 2 H2/O2 analyzer failed surveillance on June 27, 2022
71111.17T - Evaluations of Changes, Tests, and Experiments Sample Selection (IP Section 02.01)
The inspectors reviewed the following evaluations, screenings, and/or applicability determinations for 10 CFR 50.59 from June 13 to June 16, 2022.
(1)performance analysis and design (PAD) 162270, engineering evaluation EE-19-030, RCIC Minimum Flow Bypass Valve Closure Requirement Evaluation (50.59 Screening)
- (2) PAD 172302, licensing basis document change request 2020-017, Modification of Technical Specification Basis Action B.3.1 and B.3.2 (50.59 Screening)
(3)procedure change request emergency procedure 5.1FLOOD, "FLOOD," revision 29 (50.59 Screening)
- (4) PAD 202349, condition report CR-CNS-2020-02917, Compensatory Measure for Reactor Equipment Cooling Leakage (50.59 Screening)
- (5) PAD 172276, design engineering change (DEC) 5329608, HV-DPIC-835A and/or B Replacement (50.59 Screening)
- (6) PAD 172274, temporary configuration change (TCC) 5328958, Diesel Generator Cooling Water Alternate Discharge Flow Path (50.59 Screening)
- (7) PAD 202422, compensatory measure for condition report CR-CNS-2021-02034 (50.59 Screening)
(8)evaluation 2021-1/TCC-5395350, MS-AOV-790AV Packing Leak Repair (50.59 Evaluation)
- (9) PAD 192336, Cooper Nuclear Station vessel internals program, revision 30.0 (50.59 Screening)
- (10) PAD 202385, engineering evaluation 05-001, Core Shroud Weld Flaw Analysis for Core Shroud Circumferential Welds performed by Structural Integrity Associates per NEI 96-07, revision 1 (50.59 Screening)
- (11) PAD 202405, engineering evaluation 21-001, RCIC-LS-74 Evaluation of Setpoint and Tolerances (50.59 Screening)
- (12) PAD 202410, Cooper Nuclear Station vessel internals program, revision 30.1 (50.59 Screening)
- (13) PAD 2O2411, engineering evaluation 2L-OO7, Use-As-ls Engineering Evaluation for MS-V-205 (50.59 Screening)
(50.59 Screening)
- (15) PAD 202480, Revise Limiting Component Analysis for Containment Spray Motor-Operated Valves (50.59 Screening)
- (16) PAD 202494, Cooper Nuclear Station vessel internals program, revision 31 (50.59 Screening)
(17)procedure change request (PCR) 2.2.20, system operating procedure 2.2.20, Standby AC Power System (Diesel Generator), revision 110
- (18) PCR 2.2.69.3, system operating procedure 2.2.69.3, Residual Heat Removal Suppression Pool Cooling and Containment Spray, revision 52
- (23) PAD 202395, HPCI [High-Pressure Coolant Injection] Nutherm Loss of Voltage Relay Removal (50.59 Screening)
- (24) PAD 202425, Cooper 345 KV Switchyard Reactor 3401 Hydran Removal (50.59 Screening)
- (25) PAD 202470, Update of NEDC 87-131D (50.59 Screening)
- (26) PAD 202483, 345 KV Switchyard Replace PCB 3310 (50.59 Screening)
- (27) PAD 202487, OG-MOT-OGVP (VPA) Motor Change Evaluation (50.59 Screening)
- (28) PAD 202464, TSTF-554, Revise Reactor Coolant Leakage Requirements (50.59 Applicability Determination)
- (29) PAD 202408, Alternate Recorder for RWCU-FR--97A/B (50.59 Screening)
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)standby gas treatment system change in drawdown to negative pressure interval and control room dose during a postulated loss of coolant accident on April 27, 2022
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated the following post-maintenance testing activities to verify system operability and/or functionality:
(1)traversing in-core probe ball valve repair on April 14, 2022 (2)residual heat removal B maintenance window on May 16, 2022 (3)valve SW-V-538 replacement on May 19, 2022 (4)control room air conditioning compressor and dryer filter replacement on May 25, 2022
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance testing activities to verify system operability and/or functionality:
Surveillance Tests (other) (IP Section 03.01) (4 Samples)
(1)standby liquid control pumps operability test on April 14, 2022 (2)reactor high-pressure channel functional test on June 17, 2022 (3)torus air and water temperature calibration on June 28, 2022 (4)high-pressure coolant injection system operability test on June 29, 2022
Inservice Testing (IP Section 03.01) (1 Sample)
(1)closure testing of diesel generator starting air receiver inlet check valves on April 16, 2022
FLEX Testing (IP Section 03.02) (1 Sample)
- (1) FLEX 175 kW emergency diesel generator 1 on June 16, 2022
71114.01 - Exercise Evaluation
Inspection Review (IP Section 02.01-02.11) (1 Sample)
- (1) The inspectors evaluated the biennial emergency plan exercise conducted on May 24, 2022. The exercise scenario simulated a security event; a jet pump failure causing fuel clad damage; an anticipated transient without scram; and a steam leak from the reactor core isolation cooling (RCIC) system. The last part of the scenario resulted in a failure of both primary and secondary containment leading to an unmonitored release to the environment.
71114.04 - Emergency Action Level and Emergency Plan Changes
Inspection Review (IP Section 02.01-02.03) (1 Sample)
- (1) The inspectors evaluated the following Emergency Plan changes and risk significant implementing procedure changes:
emergency plan implementing procedure (EPIP) 5.7.1, "Emergency Classification," revision 72 (NRC notified 3/8/2022, effective 2/16/2022)
Emergency Action Level Technical Basis Document, revision 0 The inspectors also evaluated the 10 CFR 50.54(q) emergency plan change process and practices between March 1, 2021, and March 20, 2022. This involved review of a selection of additional licensee screening and evaluation documentation. These evaluations and reviews do not constitute NRC approval.
71114.06 - Drill Evaluation
Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)
(1)emergency preparedness dress rehearsal drill on April 5, 2022
71114.08 - Exercise Evaluation - Scenario Review
Inspection Review (IP Section 02.01 - 02.04) (1 Sample)
- (1) The inspectors reviewed the licensee's preliminary exercise scenario that was submitted to the NRC on March 22, 2022 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML22083A153) for the exercise scheduled to occur on May 24, 2022. The inspectors discussed the preliminary scenario with Mr. P. Martin, Manager, Emergency Preparedness, and other members of the emergency preparedness staff on April 20, 2022. The inspectors' review does not constitute NRC approval of the scenario.
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10)===
- (1) April 1, 2021, through March 31, 2022
BI02: RCS Leak Rate Sample (IP Section 02.11) (1 Sample)
- (1) April 1, 2021, through March 31, 2022
EP01: Drill/Exercise Performance (DEP) Sample (IP Section 02.12) (1 Sample)
- (1) April 1, 2021, through March 31, 2022 EP02: Emergency Response Organization (ERO) Drill Participation (IP Section 02.13) (1 Sample)
- (1) April 1, 2021, through March 31, 2022 EP03: Alert and Notification System (ANS) Reliability Sample (IP Section 02.14) (1 Sample)
- (1) April 1, 2021, through March 31, 2022
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)control and tracking of long-term scaffolding in the reactor building on June 1, 2022 (2)an unqualified shift technical engineer standing watch 25 times on June 9, 2022
71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02)
- (1) The inspectors reviewed the licensees corrective action program for quality issues relating to the content, control, and promptness that might be indicative of a more significant issue with the corrective action program.
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 05000298/2021-002-00, Valve Test Failures Result in Condition Prohibited by Technical Specifications, (ML21137A329). The circumstances surrounding this LER and a Severity Level IV non-cited violation is documented in the Inspection Results section of this report.
INSPECTION RESULTS
Safety Relief Valve Lift Settings Outside of Technical Specifications Required Setpoints Cornerstone Severity Cross-Cutting Aspect Report Section Not Applicable Severity Level IV NCV 05000298/2022002-01 Open/Closed Not Applicable 71153 A self-revealed, Severity Level IV non-cited violation of Technical Specification 3.4.3, Safety/Relief Valves and Safety Valves, was identified when the licensee discovered through as-found test results that two of the eight Target Rock safety relief valve pilot assemblies failed to lift within the technical specifications lift setpoint requirements.
Description:
Licensee Event Report 05000298/2021-002-00, Valve Test Failures Result in Condition Prohibited by Technical Specifications, (ML21137A329), was associated with two of the eight Target Rock safety relief valve (SRV) pilot assemblies as-found setpoints being outside of the +/-3 percent setpoint band required for their operability. This was discovered between March 18 and March 20, 2021, during as-found testing on all eight SRV pilot assemblies that were removed during the fall 2020 refueling outage. The licensee discovered that the two SRV pilot valves stuck due to corrosion bonding. The licensee determined that these two SRVs were inoperable for an indeterminate period of time from November 14, 2018, when the unit entered mode 2 (beginning of operating cycle) to September 26, 2020, when the unit entered mode 4 (beginning of refueling outage). The inspectors reviewed the licensee event report and determined that the report adequately documented the summary of the event including the cause and potential safety consequences. The inspectors also reviewed other documents that indicate that this type of failure is a known industry issue associated with this type of valve.
Corrective Actions: The licensee replaced all eight of the SRV pilot valve assemblies with refurbished valves during the fall 2020 refueling outage. The currently installed valves were certified, tested, and as-left values were verified to be within +/-1 percent of their setpoints. The licensee is tracking industry initiatives to address the known corrosion bonding phenomenon and is working on a technical specification amendment to address this issue.
Corrective Action References: condition reports CR-CNS-2019-01277, CR-CNS-2021-01483, and CR-CNS-2021-01511
Performance Assessment:
The NRC determined this violation was not reasonably foreseeable and preventable by the licensee and therefore is not a performance deficiency.
Enforcement:
Enforcement Policy, section 2.2.4, states that violations with no associated performance deficiency will be dispositioned using traditional enforcement. Therefore, operating reactor violations with no associated performance deficiencies should be assigned a severity level and are, thus, not described as findings or assigned a color (e.g., Green).
Severity: This violation is characterized as a Severity Level IV non-cited violation based on its similarity to Severity Level IV, example 6.1.d.1, in the Enforcement Policy. The inspectors also reviewed the Enforcement Policy, section 3.10, Reactor Violations with no Performance Deficiencies.
Violation: Cooper Nuclear Station Technical Specification 3.4.3, Safety/Relief Valves (SRVs)and Safety Valves (SVs), condition A, requires that with one or more required SRVs or SVs inoperable, that the unit be in mode 3 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and mode 4 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. Contrary to the above, two required SRVs were inoperable from November 14, 2018, to September 26, 2020, and the unit did not enter mode 3 and mode 4 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> respectively.
Enforcement Action: This violation is being treated as a non-cited violation, consistent with section 2.3.2 of the Enforcement Policy.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On April 20, 2022, the inspectors presented the emergency preparedness exercise scenario review inspection results to Mr. P. Martin, Manager, Emergency Preparedness, and other members of the licensee staff.
On June 16, 2022, the inspectors presented the Cooper Nuclear Station 10 CFR 50.59 inspection results to Mr. K. Dia, General Manager of Plant Operations, and other members of the licensee staff.
On June 30, 2022, the inspectors presented the emergency preparedness exercise inspection results to Mr. K. Dia, Acting Vice President and Chief Nuclear Officer, and other members of the licensee staff.
On July 18, 2022, the inspectors presented the integrated inspection results to Mr. K. Dia, General Manager of Plant Operations, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
0-BARRIER-
REACTOR
Reactor Building
0-CNS-FAP-WM-06
OPS Department Warm Weather Checklist
14.27.4
Reactor Building Floor Drain Sump Level Calibration
2.2.39
HVAC Diesel Generator Building
2.2.47
HVAC Reactor Building
2.2.84
HVAC Main Control Room and Cable Spreading Room
5.10FLEX
Flex Support Guidelines (FSGs)
5.10FLEX.32
Dam Accident Mitigation System (DAMS)
5.1Flood
Flood
Procedures
7.0.11
Flood Control Barriers
Work Orders
Corrective Action
Documents
CR-CNS-
22-02063
DWG 2006,
Sheet 1
Circulating, Screen Wash & Service Water System
DWG 2006,
Sheet 4
Service Water System Flow Diagram
DWG 2036,
Sheet 1
Reactor Building Service Water System
DWG 2037
Flow Diagram H&V Standby Gas Treatment & Off Gas
Filters
DWG 2040
Flow Diagram Residual Heat Removal System
Drawings
DWG 2045
Flow Diagram Core Spray System
2.2.69
Residual Heat Removal System
104
2.2.70
RHR Service Water Booster Pump System
2.2.71
Service Water System
135
2.2.73
2.2A.CS.DIV1
Core Spray Component Checklist (DIV 1)
2.2A.DG.DIV1
Standby AC Power System (Diesel Generator) Component
Checklist (DIV 1)
Procedures
2.2A.RHR.DIV1
Residual Heat Removal System Component Checklist
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
(DIV 1)
2.2A.RHR.DIV2
Residual Heat Removal System Component Checklist
2.2A.RHR.DIV2
Residual Heat Removal System Component Checklist
(DIV 2)
2.2A.RHRSW.DIV2
RHR Service Water Booster Pump System Component
Checklist (DIV 2)
2.2A.SGT.DIV1
Standby Gas Treatment System Component Checklist
(DIV 1)
2.2A.SW.DIV0
Service Water System Non-Divisional Component
Checklist
2.2A.SW.DIV0
Service Water System Non-Divisional Component
Checklist
2.2A.SW.DIV2
Service Water System Component Checklist (DIV 2)
2.2B.RHR.DIV1
Residual Heat Removal System Instrument Valve Checklist
(DIV 1)
2.2B.RHR.DIV2
Residual Heat Removal System Instrument Valve Checklist
(DIV 2)
2.2B.RHR.DIV2
Residual Heat Removal System Instrument Valve Checklist
(DIV 2)
2.2B.RHRSW.DIV2
RHR Service Water Booster Pump System Instrument
Valve Checklist (DIV 2)
2.2B.SGT.DIV1
Standby Gas Treatment System Instrument Valve
Checklist (DIV 1)
2.2B.SW.DIV0
Service Water System Non-Divisional Instrument Valve
Checklist
2.2B.SW.DIV2
Service Water System Instrument Valve Checklist (DIV 2)
2.2B.SW.DIV2
Service Water System Instrument Valve Checklist (DIV 2)
Work Orders
WO 5343188, 5343240
Corrective Action
Documents
CR-CNS-
22-02221, 2022-02233
CNS-FP-211
Reactor Building Northeast Quadrant Elevations 881-9
and 859-9
CNS-FP-215
Reactor Building First Floor Elevation 903-6
Fire Plans
CNS-FP-220
Reactor Building SBLC Area Elevation 976-0
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
CNS-FP-229
Control Building Cable Spreading Room Elevation 918-0
CNS-FP-397
FLEX Equipment Storage Facility Bldg. #1
0-BARRIER-MAPS
Barrier Maps
Procedures
0-BARRIER-
REACTOR
Reactor Building
Corrective Action
Documents
CR-CNS-
2013-04701, 2022-01138
Miscellaneous
NEDC 09-102
Internal Flooding - HELB, MELB, and Feedwater Line
Break
0-BARRIER-
REACTOR
Reactor Building
14.27.4
Reactor Building Floor Drain Sump Level Calibration
5.1FLOOD
Flood
Procedures
7.0.11
Flood Control Barriers
Work Orders
13.15.1
Reactor Equipment Cooling Heat Exchanger Performance
Analysis
3.34
Heat Exchanger Program Implementation
Procedures
7.2.42.3
Heat Exchanger Tube Plugging
Work Orders
Corrective Action
Documents
CR-CNS-
22-01836
RPV Control (1-3)
Miscellaneous
Primary Containment Control (1-3)
2.1.10
Station Power Changes
21
2.1.9
Low Power Operation for Maintenance Activities
Procedures
2.2.14
2kV Electrical System
Work Orders
Corrective Action
Documents
CR-CNS-
2019-05496, 2019-06302, 2020-06131, 2022-01143, 2022-
01643, 2022-01672
DWG 2006,
Sheet 1
Flow Diagram Circulating, Screen Wash & Service Water
Systems
Drawings
DWG 2006,
Flow Diagram Circulating, Screen Wash & Service Water
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Sheet 4
Systems
DWG 2016,
Sheet 2
Flow Diagram for Pumphouse and Storage Tanks
DWG 2036,
Sheet 1
Flow Diagram Reactor Building Service Water System
Maintenance Rule Function FP-F03 Performance Criteria
Basis
RWCU-F03
Maintenance Rule Function RWCU-F03 Performance
Criteria Basis
SW-F04
Maintenance Rule Function SW-F04 Performance Criteria
Basis
Miscellaneous
VM-0725
Moore Products Composite Manual
15.2SW.601
SW Bay Emergency Sparger Functional Test
15.SWBP.201
Emergency Core Flooding Supply Valves Flushing
3-EN-DC-205
Maintenance Rule Monitoring
7C0
Procedures
5.8.8
Alternate Boron Injection and Preparation
Work Orders
Corrective Action
Documents
CR-CNS-
22-02074, 2022-02084, 2022-02685
Protected Equipment Tagout, RHRB-1-SW-MOV-89B
INOP
04/18/2022
Protected Equipment Tagout, EE-1-WK 2219 EE-SSST
05/10/2022
Protected Equipment Tagout, DGB-1-DG2 Week 2220
05/16/2022
0-BARRIER-MISC
Miscellaneous Buildings
0-CNS-06
Site Risk Significance Standards
0-CNS-WM-104
On-Line Schedule Risk Assessment
Miscellaneous
0-PROTECT-EQP
Protected Equipment Program
0-CNS-FAP-OM-
031
Emergent Issue Response, Risk Classification, and
Oversight Determination
6.1DG.104
Diesel Operability Test with Isolation Switches in Isolate
(DIV 1)
Procedures
6.HPCI.204
HPCI-SOV-SSV64 and HPCI-SOV-SSV87 IST Closure
Test
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Work Orders
WO 5343188, 5357684, 5414295
Corrective Action
Documents
CR-CNS-
2019-02761, 2021-00343, 2021-01450, 2021-02271, 2021-
03035, 2021-03273, 2021-03646, 2021-04054, 2022-
01607, 2022-01631, 2022-01643, 2022-01667, 2022-
01671, 2022-01672, 2022-01777, 2022-01778, 2022-
01789, 2022-02084, 2022-02158, 2022-02688, 2022-
2705, 2022-02726, 2022-02729, 2022-02745
CNS-EQ-129
EQ Configuration Detail - Limitorque Valve Actuator
N05
DWG 2031
Flow Diagram Reactor Building - Closed Cooling Water
System
N65
Drawings
DWG 2036
Flow Diagram Reactor Building - Service Water System
A6
ECR Number - CR-CNS-2022-01672
04/21/2022
ECR Number - CR-CNS-2022-01643-CA-006
04/21/2022
Overthrust/Overtorque Evaluation Sign-Off and Review
Sheet, SW-MOV-MO89B
04/18/2022
ODM - MCC-K(4D)
Operational Decision Making Review for MCC-K(4D)
VM-0217
5800 Horizontal Split Case Pumps
VM-0986
Limitorque Composite Manual
VM-1183
Hydrogen/Oxygen Monitoring System
Miscellaneous
VM-1369
Peneberthy Composite Manual
0.9
Tagout
108
2.2.70
RHR Service Water Booster Pump System
6.1SWBP.101
RHR Service Water Booster Pump Flow Test and Valve
Operability Test (DIV1)
Procedures
7.5.3
MOV Diagnostics
Work Orders
NEDC 00-041
Limiting Component Analysis for Containment Spray Motor
Operated Valves
Calculations
NEDC 96-018
Design Specification for Valve Limiting Component
Analysis
1C1
Corrective Action
Documents
CR-CNS-
2016-02281, 2018-07146, 2019-02583, 2021-01653, 2021-
2034, 2021-02943
Corrective Action
Documents
CR-CNS-
22-02530, 2022-02555, 2022-02570
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Resulting from
Inspection
2041
Cooper Nuclear Station Isometric Key Reactor Building
Main Steam System
AF/29
3038, Sheet 7
Control Elementary Diagrams
3058
Cooper Nuclear Station, DC One-Line Diagram
3059, Sheet 5
Cooper Nuclear Station, EE-Panel-BB2 125VDC Load And
Fuse Schedule
3062, Sheet 3
Cooper Nuclear Station, DC Control Elementary Diagram
3063, Sheet 4
Cooper Nuclear Station, DC Control Elementary Diagrams
45003608
Flow Diagram, Reactor Building Heating and Ventilating
791E260, Sheet 2
Elem [Elementary] Diag [Diagram] - Traversing Incore
Probe Calibration Sys [System] Cooper
N03
791E266, Sheet 5
Elementary Diagram Primary Containment Isolation
System
791E266, Sheet 6
Elementary Diagram Primary Containment Isolation
System
791E266, Sheet 8
Elementary Diagram, Primary Containment Isolation
System
791E271, Sheet 1
Cooper Nuclear Station, HPCI [High-Pressure Coolant
Injection] System Elementary Diagram
791E271, Sheet 10
Elementary Diagram HPCI System, Cooper Nuclear
Station
791E271, Sheet 11
Cooper Nuclear Station, HP Coolant Injection System
Elementary Diagrams
791E271, Sheet 7
Cooper Nuclear Station, Elementary Diagram HPCI
System
791E271, Sheet 8
Cooper Nuclear Station, HPCI System Elementary
Diagram
N20
NC66688
Cooper 345KV Substation One-Line Switching Diagram
NF89767
Cooper 345KV Substation Connection Diagram Reactor
No. 3401
Drawings
X2629-204
MS-1 Main Steam
Engineering
CED 6013561
Reactor Building Ventilation Exhaust System Upgrade
03/23/2005
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
DC 5319938
HPCI LOV [Loss of Voltage] Relay Removal
DEC 5314933
TIP Drive Control Unit Replacement
DEC 5329608
HV-DPIC-835A&B Replacement
DEC 5345657
Alternate Recorder for RWCU-FR-97A/B
DEC 5404656
HPCI-FIS-78 SCR 202I-003 for Switch 1
EE 19-030
RCIC Minimum Flow Bypass Valve Closure Requirements
Evaluation
EE 21-001
RCIC-LS-74 Evaluation of Setpoint and Tolerances
15C15
EE 21-007
Use-As-ls Engineering Evaluation for MS-V-205
03/24/2021
EE 21-018
Update of NEDC 87-131D
2/20/2021
EE 22-004
OG-MOT-OGVP (VPA) Motor Change Evaluation
TCC 5328958
Diesel Generator Cooling Water Alternate Discharge Flow
Path
Changes
TCC 5395350
MS-AOV-790AV Packing Leak Repair
CNS Inservice Testing Program Basis Document
2336
CNS Vessel lnternals Program
Cooper 345kV -
930096
NPPD Relay Setting Request
05/14/2020
2019
Regulatory Performance Indicator Process for MSPI EAC
01/18/2020
Miscellaneous
VM 1869
Vendor Manual for Siemens Model 353 Process
Automation Controller
2/00/2011
0-CNS-LI-100
Process Applicability Determination
0-CNS-LI-101
10CFR50.59 Evaluations
0.4
Procedure Change Process
2.0.1
Conduct of Operations Procedure - Plant Operations Policy
2.0.1.2
Conduct of Operations Procedure - Operations Procedure
Policy
2.0.1.3
Conduct of Operations Procedure - Time Critical Operator
Action Control and Maintenance
2.0.3
Conduct of Operations
105
2.3_9-3-1
Alarm Procedure - Panel 9-3 - Annunciator 9-3-1
Procedures
3-EN-DC-115
Engineering Change Process
15C16
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
3.4.4
Temporary Configuration Change
IP-ENG-001
Standard Design Process
1C0
Miscellaneous
VM-0248
Crane Valve Composite Manual
Procedures
7.7.10.2
P1-B Welding Procedure Specification
Work Orders
WO 27024, 5345882, 5346891, 5373673, 5383074,
5406580, 5412710, 5412711, 5423432, 5442690
Corrective Action
Documents
CR-CNS-
22-02108, 2022-02780, 2022-02785, 2022-02807
Drawings
DWG 2036
Flow Diagram Reactor Building - Service Water System
A6
0-CNS-WM-104
On-Line Schedule Risk Assessment
2.3.1
General Alarm Procedure
6.1DG.402
IST Closure Testing of DGSA Receiver Inlet Check Valves
(DIV 1)
6.1PC.303
PCIS Main Steam Line High Flow Channel Calibration
(DIV 1)
6.HPCI.103
6.LOG.601
Daily Surveillance Log - Modes 1, 2, and 3
2
6.RHR.706
Reactor High-Pressure Channel Functional Test
6.SLC.101
SLC Pump Operability Test
Primary Containment Control (1-3)
Procedures
Secondary Containment Control (1-3)
Work Orders
WO 5344852, 5353642, 5354557, 5356861, 5437883
Corrective Action
Documents
CR-CNS-
20-00227, 2020-00349, 2020-00526, 2020-00670, 2020-
01442, 2021-00892, 2021-02452, 2021-02749, 2021-
2769, 2021-02957, 2021-03197, 2021-03560, 2021-
03792, 2021-05452, 2022-00028, 2022-02226, 2022-
229, 2022-02234
February 25, 2020, Full Team Dress Rehearsal Exercise
03/16/2020
21 NRC/FEMA Biennial Exercise - ERO Team "D"
06/24/2021
February 2, 2021, Full Team B Drill
03/01/2021
21 Biennial Exercise Dress Rehearsal
05/05/2021
April 5, 2022, Full Team 2 & B Dress Rehearsal Drill
04/15/2022
Miscellaneous
22 Emergency Management Performance Evaluation
2/09/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Dress Rehearsal Drill
22 Emergency Management Performance Evaluation
Drill
2/16/2022
July 31, 2018, Biennial NRC-Graded Exercise Summary
Report
08/10/2018
Updated Final Safety Analysis
Emergency Plan for Cooper Nuclear Station
EAL Technical Basis Document
Controller/Evaluator
Log
05/24/2022
Controller/Evaluator
Log
TSC, Engineering Mechanical
05/24/2022
Controller/Evaluator
Log
05/24/2022
Controller/Evaluator
Log
TSC, Security Coordinator
05/24/2022
Emergency Action
Log
Ops/EOP Adviser
05/24/2022
Emergency Action
Log
TSC Communicator
05/24/2022
Notification Report
Number 3
Drill SA6.1 Alert Declaration, 10:03 a.m.
05/24/2022
Notification Report
Number 4
Drill FS1.1 Site Area Emergency Declaration, 10:23 a.m.
05/24/2022
Notification Report
Number 5
Drill AG1.2 General Emergency Declaration, 10:41 a.m.
05/24/2022
Notification Report
Number 6
Drill AG1.2 General Emergency Follow-Up, 11:03 a.m.
05/24/2022
Notification Report
Number 7
Drill AG1.2 General Emergency Follow-Up, 12:02 p.m.
05/24/2022
TSC Log
May 24th Biennial Exercise, CNS TSC Log Keeper
TSC09
Position Instruction Manual
Procedures
5.7.1
4, EAL Classification Matrix
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
5.7.1
Emergency Classification
5.7.11
Early Dismissal/Evacuation of Site Personnel
5.7.12
Emergency Radiation Exposure Control
5.7.16
Release Rate Determination
5.7.17
CNS-DOSE Assessment
5.7.20
Protective Action Recommendations
5.7.7
Activation of TSC
5.7.9
Activation of EOF
5.7ENS
ENS Communicator
Engineering
Changes
DEC-5416038
TSC/OSC Upgrades
Emergency Plan for Cooper Nuclear Station
Updated Final Safety Analysis
EAL Technical Basis Document
21-37
Emergency Preparedness Regulatory Review (50.54(q))
21-63
Emergency Preparedness Regulatory Review (50.54(q))
5.7.1
Emergency Classification
5.7.1, Attachment 4
EAL Classification Matrix
5.7.1, Attachment 4
EAL Classification Matrix
50.54(q) Evaluation
Number: 2021-94
Activity/Document Number: TSC/OSC Upgrade, Title:
"Digital Upgrade and Remodel of TSC/OSC"
01/10/2022
50.54(q) Evaluation
Number: 2022-06
Activity/Document Number: DEC 5338473, Title: EPN
Component Replacement
2/03/2022
50.54(q) Screen
Number: 2021-092
Activity/Document Number: 5.7.1, Revision Number: 72,
Title: Emergency Classification
01/04/2022
50.54(q) Screen
Number: 2021-94
Activity/Document Number: DEC-5416038, Revision
Number: 0, Title: TSC/OSC Upgrades
01/07/2022
50.54(q) Screen
Number: 2022-06
Activity/Document Number: DEC-5338473, Title: EPN
Component Replacement
2/03/2022
83307
Intranet Document Control System
05/24/2021
Miscellaneous
NLS2022006
Emergency Plan Implementing Procedure, Cooper Nuclear
Station, Docket No. 50-298, DPR-46
03/08/2022
Procedures
0.29.1
License Basis Document Changes
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
0.29.4
Other Regulatory Reviews
5.7.1, Attachment 4
EAL Classification Matrix
Miscellaneous
NLS2022013
Emergency Plan Full Participation Exercise Drill Scenario,
Cooper Nuclear Station, Docket No. 50-298, DPR-46
03/22/2022
2.1.5
Reactor Scram
5.2FUEL
Fuel Failure
5.7.1
Emergency Classification
Procedures
5.7.20
Protective Action Recommendations
Corrective Action
Documents
CR-CNS-
21-02749, 2021-03221
A Prompt Alert and Notification System Design Report for
the Cooper Nuclear Station
Miscellaneous
Performance Indicator Documentation and Data Review
Forms from April 2021 through March 2022
0-EN-LI-114
Regulatory Performance Indicator Process
17C0
8.8.1.14
Radiochemical Iodines Analysis
EPDG No. 2,
C-1
Semi-Monthly Alert and Notification System Siren Testing
71151
Procedures
EPDG No. 2,
C-5
Annual Full-Cycle Sounding of Alert and Notification
System Sirens
Corrective Action
Documents
CR-CNS-
21-05061, 2022-01643, 2022-01646, 2022-01647, 2022-
01777, 2022-01778, 2022-01789, 2022-01869, 2022-
01870, 2022-01871, 2022-01896, 2022-01912, 2022-
2737, 2022-02821
Miscellaneous
USA M-1
CFR 50.59 Resource Manual
0-CNS-LI-100
Process Applicability Determination
0-CNS-LI-102
Corrective Action Process
0.5.OPS
Operations Review of Condition Reports/Operability
Determinations
Procedures
7.0.7
Scaffolding Construction and Control
Work Orders
Corrective Action
Documents
CR-CNS-
2019-01277, 2021-01483, 2021-01511