IR 05000298/2021003
| ML21299A198 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 11/04/2021 |
| From: | Jason Kozal NRC, NRC/RGN-IV/DRP |
| To: | Dent J Nebraska Public Power District (NPPD) |
| References | |
| IR 2021003 | |
| Download: ML21299A198 (21) | |
Text
SUBJECT:
COOPER NUCLEAR STATION - INTEGRATED INSPECTION REPORT 05000298/2021003
Dear Mr. Dent:
On September 30, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Cooper Nuclear Station. On October 4, 2021, the NRC inspectors discussed the results of this inspection with you 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, Jason W. Kozal, Chief Reactor Projects Branch C Division of Reactor Projects Docket No. 05000298 License No. DPR-46
Enclosure:
As stated
Inspection Report
Docket Number:
05000298
License Number:
Report Number:
Enterprise Identifier:
I-2021-003-0131
Licensee:
Nebraska Public Power District
Facility:
Cooper Nuclear Station
Location:
Brownville, NE
Inspection Dates:
July 1, 2021, to September 30, 2021
Inspectors:
D. Antonangeli, Health Physicist
D. Bryen, Project Engineer
K. Chambliss, Resident Inspector
J. O'Donnell, Senior Health Physicist
G. Pick, Senior Reactor Inspector
A. Siwy, Senior Resident Inspector
M. Stafford, Nuclear Systems Engineer
Approved By:
Jason W. Kozal, Chief
Reactor Projects Branch C
Division of Reactor Projects
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 05000298/2020-002-00 Secondary Containment Differential Pressure Perturbation Results in Potential Loss of Safety Function 71153 Closed LER 05000298/2021-001-00 Secondary Containment Differential Pressure Perturbation Exceeds Technical Specifications 71153 Closed LER 05000298/2020-004-00 Secondary Containment Differential Pressure Perturbation Could Have Prevented Fulfillment of a Safety Function 71153 Closed
PLANT STATUS
Cooper Nuclear Station began the inspection period at rated thermal power. On August 6, 2021, power was lowered to approximately 67 percent for a control rod sequence exchange. The plant was returned to rated thermal power on August 7, 2021. 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 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.
Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the coronavirus (COVID-19), resident and regional inspectors were directed to begin telework and to remotely access licensee information using available technology. During this time, the resident inspectors performed periodic site visits each week, increasing the amount of time on-site as local COVID-19 conditions permitted.
As part of their on-site activities, resident inspectors conducted plant status activities as described in IMC 2515, Appendix D; conducted routine reviews using IP 71152, Problem Identification and Resolution; observed risk significant activities; and completed on-site portions of IPs. In addition, resident and regional baseline inspections were evaluated to determine if all or a portion of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In some cases, portions of an IP were completed remotely and on-site. The inspections documented below met the objectives and requirements for completion of the IP.
REACTOR SAFETY
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (7 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Standby liquid control subsystem B on July 7, 2021
- (2) Reactor core isolation cooling on July 26, 2021
- (3) Core spray B on August 3, 2021
- (4) Division 2 reactor equipment cooling on August 10, 2021
- (5) Division 1 emergency diesel generator on August 18, 2021
- (6) Division 2 emergency diesel generator on September 16, 2021
- (7) High pressure coolant injection on September 22, 2021
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (9 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, 976-foot elevation, on July 6, 2021
- (2) Reactor building northeast quadrant, 881-foot 9-inch elevation and 859-foot 9-inch elevation, on July 28, 2021
- (3) Reactor building southeast quadrant, 881-foot 9-inch elevation and 859-foot 9-inch elevation, on August 3, 2021
- (4) Reactor building second floor, 931-foot 6-inch elevation, on August 10, 2021
- (5) Division 2 emergency diesel generator room, 917-foot 6-inch elevation and 903-foot 6-inch elevation, on August 16, 2021
- (6) Reactor building southwest quadrant, 881-foot 9-inch elevation and 859-foot 9-inch elevation, on August 24, 2021
- (7) Reactor building third floor, 958-foot 3-inch elevation, on August 28, 2021
- (8) Reactor building refuel floor, 1001-foot elevation, on September 2, 2021
- (9) Turbine building basement north condensate pump area, 882-foot 6-inch elevation, on September 14, 2021
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 and rod pattern adjustment on August 6, 2021.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated the licensed operator requalification scenario on July 13, 2021.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (4 Samples)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components remain capable of performing their intended function:
- (1) FLEX equipment operating experience smart sample 2020/01 (ADAMS Accession No. ML20220A261) on July 9, 2021
- (2) Open phase isolation system on September 1, 2021
- (3) Reactor core isolation cooling on September 28, 2021
- (4) Dry compressed air for instrument air near A(1) on September 29, 2021
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) Yellow risk during standby liquid control subsystem A maintenance on July 7, 2021
- (2) Yellow risk during high pressure coolant injection instrument repair on July 28, 2021
- (3) Yellow risk during Division 1 4160 volt bus undervoltage/underfrequency testing on August 2, 2021
- (4) Yellow risk during Division 2 4160 volt bus undervoltage testing on August 25, 2021
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) Standby liquid control pump A motor results on July 8, 2021
- (2) Limiting condition of operation not entered during maintenance on primary containment valves on July 23, 2021
- (3) Secondary containment operability in relation to a steam leak on August 19, 2021
- (4) Southeast quadrant heating, ventilation, and air conditioning flow rate on August 31, 2021
- (5) Reactor equipment cooling pump D motor inductance imbalance on September 13, 2021
- (6) Control rod drive mechanism high accumulator water level on September 14, 2021
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (3 Samples)
The inspectors evaluated the following temporary or permanent modifications:
- (1) Emergency service station transformer motor operated disconnect switch on July 14, 2021
- (2) Southeast quadrant fan coil unit replacement on August 26, 2021
- (3) Open phase isolation modifications on September 20, 2021
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (6 Samples)
The inspectors evaluated the following post-maintenance test activities to verify system operability and functionality:
- (1) Primary containment valve torus isolation on July 19, 2021
- (2) Division 2 emergency diesel generator starting air compressor operability test on July 23, 2021
- (3) Core spray pump A test line recirculation valve on August 4, 2021
- (4) Reactor equipment cooling pump B replaced on August 12, 2021
- (5) Core spray check valve on August 19, 2021
- (6) Fan coil unit FC-R-1E air flow test (newly installed fan coil) on August 19, 2021
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
- (1) Division 1 emergency diesel generator monthly surveillance on July 12, 2021
- (2) Reactor core isolation cooling pump low discharge flow calibration and steam supply pressure low channel functional test on July 16, 2021
- (3) Service water pump B in-service test on July 26, 2021
- (4) Reactor equipment cooling pumps C and D in-service tests on August 28, 2021
- (5) High pressure coolant injection quarterly surveillance on September 15, 2021
71114.06 - Drill Evaluation
Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01) (1 Sample)
- (1) Emergency preparedness drill on August 31,
RADIATION SAFETY
71124.05 - Radiation Monitoring Instrumentation
Walkdowns and Observations (IP Section 03.01) (7 Samples)
The inspectors evaluated the following radiation detection instrumentation during plant walkdowns:
- (1) Area radiation monitors and continuous air monitors in the reactor building, turbine building, and radwaste building
- (2) High purity germanium detectors and liquid scintillation counter in the chemistry lab
- (3) Friskers staged for use in the reactor building, radwaste building, and radiologically controlled area exits
- (4) SAM-12s staged for use at the exit of the radiologically controlled areas (5)iPCM-12 located at the radiologically controlled area exits
- (6) Telepoles and portable ion chambers staged for use within the radiological controlled area
- (7) Tennelec XLB alpha/beta counters located within the radiation protection count room
Calibration and Testing Program (IP Section 03.02) (14 Samples)
The inspectors evaluated the calibration and testing of the following radiation detection instruments:
- (1) G17 ion chamber, RMA-RA-1, 03/04/2020
- (2) G17 ion chamber, RMA-RA-2, 03/04/2020
- (3) G12 ion chamber, RMP-RM-452C, 03/04/2021
- (4) Victoreen Model 875 high range containment monitor, RMA-RM-40A, 04/14/2021
- (5) Victoreen Model 875 high range containment monitor, RMA-RM-40B, 04/14/2021
- (6) Eberline passive monitor (PM) -7, RP-10758, 11/09/2020
- (7) Eberline personnel contamination monitor (PCM) -2, RP-10788, 02/27/2020
- (8) Eberline small article contamination monitor (SAM) -12, RP-11152, 05/20/2020
- (9) Eberline SAM-12, RP-11150, 05/20/2020
- (10) Telepole II Geiger-Mueller survey meter, RP-11969, 10/10/2020
- (11) Ludlum Model 3 count rate meter, RP-11363, 04/22/2021
- (12) Frisker Model 177, RP-11276, 07/09/2020
- (13) Eberline AMS-4, RP-10872, 07/07/2021
- (14) Tennelec XLB alpha/beta counter, RP-10848, 03/02/2020 Effluent Monitoring Calibration and Testing Program Sample (IP Sample 03.03) (2 Samples)
The inspectors evaluated the calibration and maintenance of the following radioactive effluent monitoring and measurement instrumentation:
- (1) Elevated effluent release point monitor, RMP-RM-3A/3B
- (2) Reactor building vent effluent monitor, RMV-RM-40
71124.08 - Radioactive Solid Waste Processing & Radioactive Material Handling, Storage, &
Transportation
Radioactive Material Storage (IP Section 03.01)
Inspectors evaluated the licensees performance in controlling, labeling and securing radioactive materials. The following areas were observed by the inspectors:
- (1) Low level radioactive waste pad
- (2) Radioactive material storage building
- (3) East warehouse radioactive materials area
Radioactive Waste System Walkdown (IP Section 03.02) (2 Samples)
Inspectors walked down accessible portions of the solid radioactive waste systems and evaluated system configuration and functionality.
- (1) Condensate resin
- (2) Equipment drain/floor drain filter demineralizer
Waste Characterization and Classification (IP Section 03.03) (3 Samples)
The inspectors evaluated the licensees characterization and classification of radioactive waste.
- (1) Condensate and waste resin
- (2) Spent bead resin
- (3) Dry active waste
Shipment Preparation (IP Section 03.04) (1 Sample)
The inspectors observed that a shipment containing radioactive material is prepared according to requirements.
- (1) Shipment No. 21-05, low specific activity, LSA-II, dry active waste (trash) in a 20-foot sea/land container (ESUU200542), 07/20/2021
Shipping Records (IP Section 03.05) (5 Samples)
The inspectors evaluated the following nonexcepted radioactive material shipments through a record review:
- (1) Shipment No. 19-12, LSA-I, dry active waste (metal trash) in a 20-foot sea/land container (No. 209002), 09/16/2019
- (2) Shipment No. 19-13, Type A, high integrity container (PO690656-10), activated metal and contaminated, noncompactible metal trash, 10/22/2019
- (3) Shipment No. 20-02, LSA-II, condensate sludge and resin liner (PO690095-01),06/20/2020
- (4) Shipment No. 21-02, LSA-II, steel liner (No. 680262-3) filters and bulk dry active waste, 05/11/2021
- (5) Shipment No. 21-05, LSA-II, dry active waste (trash) in a 20-foot sea/land container (ESUU200542), 07/20/2021
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) January 1, 2020, through June 30, 2021 IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02) (1 Sample)
- (1) January 1, 2020, through June 30, 2021
IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (1 Sample)
- (1) April 1, 2020, through June 30, 2021
MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04) (1 Sample)
- (1) April 1, 2020, through June 30, 2021
71152 - Problem Identification and Resolution
Annual Follow-up of Selected Issues (IP Section 02.03) (3 Samples)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) Effectiveness of corrective actions related to the full implementation cyber security inspection findings as discussed in NRC Inspection Report 05000298/2019410 (ADAMS Accession No. ML19175A252)
- (2) Limiting condition of operation not entered during maintenance on primary containment valves on August 30, 2021
- (3) Failure to properly implement the fatigue management program on September 10, 2021
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 05000298/2020-002-00, Secondary Containment Differential Pressure Perturbation Results in Potential Loss of Safety Function (ADAMS Accession No. ML20304A209). The circumstances surrounding this LER and an associated minor performance deficiency are documented in the Inspection Results section of this report.
- (2) LER 05000298/2020-004-00, Secondary Containment Differential Pressure Perturbation Could Have Prevented Fulfillment of a Safety Function (ADAMS Accession No. ML21022A042). The inspectors determined that it was not reasonable to foresee or correct the cause discussed in the LER; therefore, no performance deficiency was identified. The inspectors did not identify a violation of NRC requirements.
- (3) LER 05000298/2021-001-00, Secondary Containment Differential Pressure Perturbation Exceeds Technical Specifications (ADAMS Accession No. ML21102A278). The circumstances surrounding this LER and an associated minor performance deficiency are documented in the Inspection Results section of this report.
INSPECTION RESULTS
Minor Performance Deficiency 71153 Minor Performance Deficiency: On August 6, 2020, secondary containment vacuum was reduced below the limit of 0.25 inches of vacuum water gauge, which is required by Technical Specification Surveillance Requirement 3.6.4.1.1. This condition existed for 3 minutes and was identified by operations personnel after it had occurred due to a computer alarm in the control room. This condition was initially concluded to be a momentary transient due to gusty wind conditions, which is considered acceptable and not a cause for failure to meet the surveillance requirement. An engineering review completed on August 13, 2021, concluded it was the result of an equipment issue rather than gusty wind conditions. This condition was a result of an air-line leak between the valve positioner and the lower diaphragm of a vortex damper due to contact with a support brace that was installed on November 7, 2007. At the time the support brace was installed, Attachment 15 of Procedure 3.4, Configuration Change Control, Revision 59, required an administrative engineering change to install the support brace. The guidance at the time of the causal evaluation was in Attachment 6 of Procedure 3-CNS-DC-112, Engineering Change Request and Project Initiation Process, Revision 0, which required an engineering change request. Contrary to the above, from November 7, 2007, to January 27, 2021, the licensee failed to properly evaluate the support brace as an engineering change in accordance with their procedures.
Screening: The inspectors determined the performance deficiency was minor. The performance deficiency associated with this violation was determined to be minor because: it could not be reasonably viewed as a precursor to a significant event; if left uncorrected, it would not have the potential to lead to a more significant safety concern; and it did not adversely affect the Barrier Integrity cornerstone objective to provide reasonable assurance that physical design barriers (containment) protect the public from radionuclide releases caused by accidents or events. Specifically, the performance deficiency did not affect the integrity of the secondary containment structure, nor did it affect the ability of the safety-related standby gas treatment system to perform its required safety function.
Minor Performance Deficiency 71153 Minor Performance Deficiency: On February 9, 2021, secondary containment vacuum was reduced below the limit of 0.25 inches of vacuum water gauge, which is required by Technical Specification Surveillance Requirement 3.6.4.1.1. This condition existed for less than 30 seconds and was identified by operations personnel after it had occurred due to a computer alarm in the control room. This condition was concluded to be a momentary transient due to barometric pressure changes. A similar issue occurred on November 3, 2020 and is documented in LER 05000298/2020-004-00 (ADAMS Accession No. ML21022A042). It was determined in both occurrences that the tuning parameters of the reactor building differential pressure controllers were not optimized to maintain the required pressure during changing conditions. After the first occurrence, the licensee decided not to implement interim actions on the basis that the condition was unlikely to repeat prior to full action implementation. Procedure 0-CNS-LI-118, Cause Evaluation Process, Section 8.2, requires interim corrective actions to address short term vulnerabilities. Contrary to the above, from November 3, 2020, through February 9, 2021, the licensee failed to develop interim actions to address short term vulnerabilities.
Screening: The inspectors determined the performance deficiency was minor. The performance deficiency associated with this violation was determined to be minor because: it could not be reasonably viewed as a precursor to a significant event; if left uncorrected, it would not have the potential to lead to a more significant safety concern; and it did not adversely affect the Barrier Integrity cornerstone objective to provide reasonable assurance that physical design barriers (containment) protect the public from radionuclide releases caused by accidents or events. Specifically, the performance deficiency did not affect the integrity of the secondary containment structure, nor did it affect the ability of the safety-related standby gas treatment system to perform its required safety function.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On July 22, 2021, the inspectors presented the public radiation safety inspection results to Mr. K. Dia, General Manager of Plant Operations, and other members of the licensee staff.
On September 22, 2021, the inspectors presented the cyber security full implementation problem identification and resolution inspection results to Mr. J. Wissler, Nuclear Information Technology Manager, and other members of the licensee staff.
On October 4, 2021, the inspectors presented the integrated inspection results to Mr. J. Dent, 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
2.2.20
Standby AC Power System (Diesel Generator)
2
2.2.20.1
Diesel Generator Operations
2.2.33A
High Pressure Coolant Injection System Component Checklist
2.2.33B
High Pressure Coolant Inject System Instrument Valve
Checklist
2.2.67A
Reactor Core Isolation Cooling System Instrument Valve
Checklist
2.2.74A
Standby Liquid Control System Component Checklist
2.2A
Reactor Equipment Cooling Water System Component
Checklist (Div 2)
2.2A.DG.DIV1
Standby AC Power System (Diesel Generator) Component
Checklist (Div 1)
2.2A.DG.DIV2
Standby AC Power System (Diesel Generator) Component
Checklist (Div 2)
Procedures
2.2B
Core Spray System Instrument Valve Checklist
CNS-FP-211
Reactor Building Northeast Quadrant Elevations 881-9 and
859-9
5, 6
CNS-FP-214
Reactor Building Southwest Quadrant Elevations 881-9 and
859-9
CNS-FP-218
Reactor Building Second Floor Elevation 931-6
CNS-FP-219
Reactor Building - Third Floor Elevation 958-3
CNS-FP-220
Reactor Building SBLC Area Elevation 976-0
CNS-FP-221
Reactor Building MG Set Area Elevation 976-0
CNS-FP-223
Reactor Building - Refuel Floor Elevation 1001-0
CNS-FP-237
Diesel Generator Building Diesel Generator #2 Elevations
917-6 and 903-6
Fire Plans
CNS-FP-245
Turbine Building Basement North - Condensate Pump Area
Elevation 882-6
Procedures
0-BARRIER-
MAPS
Barrier Maps
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
RMP 32-012
Procedures
2.0.3
Conduct of Operations
104
Corrective Action
Documents
CR-CNS-
2019-02127, 2021-02941
Maintenance Rule Unavailability Reports
09/24/2021
FLEX, HCVS, and DAMS Program Document
REC (Reactor Equipment Cooler) Pump Vibration and
Spectral Data
08/28/2021
VM-0143
Instrument Air System
Miscellaneous
VM-2912
Open Phase Protection (OPP) System Operating and
Maintenance Manual
15.AIR.501
Plant Air System Examination
15.EE.701
Open Phase Active System Functional Test
Procedures
7.2.21
Air Dryer Desiccant Removal and Replacement
Work Orders
WO 5305639, 5315637, 5349739, 5349740, 5361148, 5363543,
5363544, 5371520
Drawings
3019, Sheet 3
Miscellaneous
Clearance Order SLC-1-SLC-P-A Week 2127
6.1EE.302
4160V Bus 1F Undervoltage Relay and Relay Timer
Functional Test (Div 1)
6.2EE.302
4160V Bus 1F Undervoltage Relay and Relay Timer
Functional Test (Div 2)
Procedures
6.HPCI.312
HPCI Pump Low Discharge Flow Channel Calibration
Work Orders
Corrective Action
Documents
CR-CNS-
21-02285, 2021-03239, 2021-03644, 2021-03874, 2021-
04315
DEC-5347082
Replacement of HV-COIL-FC-R-1E, (FCR #2&3)
NEDC 90-388
HPCI Room and CS & RHR Quad Heat Load Tabulation for
3C2
NEDC 97-087
Acceptance Criteria for HPCI Room Cooler and Reactor
Building Quad Coolers
4C3
Miscellaneous
USAR, Section III-
Control Rod Drive Mechanism Design
03/08/2000
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
VM-1037
Control Rod Drive Model 7RDB144EG001
2.2.8
Control Rod Drive Hydraulic System
115
6.SC.502
Secondary Containment Penetration Examination
Procedures
7.3.20.3
Motor Analysis
Work Orders
WO 237983, 5339707, 5383218
Installation of PSStech OPP System on SSST and ESST
Engineering
Changes
Review of Zachary Calculation 16-101, ECN #1
Aerofin Calculation File, Aerofin Type W Coil, CA-529-2046-1
Aerofin Calculation File, Aerofin Type W Coil, CA-1811
DEC-5347082
Replacement of HV-COIL-FC-R-1E
Miscellaneous
NEDC 97-074
Thermal Performance of the HPCI Room Cooler and the CS &
RHR Quad Coolers
2C3
Procedures
Cooper Nuclear Station Cyber Security Plan
6.1CS.101
Core Spray Test Mode Surveillance Operation (IST) (Div 1)
6.1PC.204
PC Purge and Vent Valve 24 Month Test (Div 1) (IST)
6.1REC.101
REC Surveillance Operation (IST) (Div 1),
6.2CS.101
Core Spray Test Mode Surveillance Operation (IST) (Div 2)
6.2DG.105
Diesel Generator Starting Air Compressor Operability
(IST)(Div 2)
6.2HV.601
Air Flow Test of Fan Coil Unit FC-R-1E (Div 2)
Procedures
6.PC.522
Standby Nitrogen Injection and PC Purge and Vent System
Local Leak Rate Tests
Work Orders
WO 5304567, 5339707
Corrective Action
Documents
CR-CNS-
21-03381
6.1DG.101
Diesel Generator 31 Day Operability Test (IST) (Div 1)
6.1RCIC.703
RCIC Steam Supply Pressure Low Channel Functional Test
(Div 1)
6.1SW.101
Service Water Surveillance Operation (Div 2)(IST)
6.2REC.101
REC Surveillance Operation (IST) (Div 2)
6.HPCI.103
Procedures
6.RCIC.302
RCIC Pump Low Discharge Flow Channel Calibration
Work Orders
WO 5363759, 5385905
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
EPIPEALHOT
Calibrator Verification Exposure Rate Table
01/05/2021
Eberline Passive Monitor (PM)- 7, RP-10758
11/03/2020
Eberline Personnel Contamination Monitor (PCM)- 2,
RP-10788
2/27/2020
Eberline Small Article Contamination Monitor (SAM)-12,
RP-11152
05/20/2020
Eberline SAM-12, RP-11150
05/20/2020
Telepole II Geiger-Mueller Survey Meter, RP-11969
10/10/2020
Ludlum Model 3 Count Rate Meter, RP-11363
04/22/20201
Eberline Air Monitoring Station (AMS)-4
07/07/2021
Tennelec XLB Alpha/Beta Counter, RP-10848
03/02/2020
Frisker Model 177, RP-11276
07/09/2020
Reactor Building Ventilation Radiation Monitor, RMP-RM-452B
09/09/2019
Control Room Area Radiation Monitor, RMA-RA-20
03/06/2020
High Range Containment Monitor Victoreen Model 875,
RMA-RM-40A
10/04/2020
Main Steam Line Radiation Monitors (MSLRM),
RMP-RM-251D
10/08/2020
Containment High Range Monitor Victoreen Model 875,
RMA-RM-40B
03/02/2020
Calibration
Records
Reactor Building Ventilation Radiation Monitor, RMP-RM-452A
09/20/2020
Corrective Action
Documents
CR-CNS-
2019-04420, 2019-04713, 2019-06406, 2020-00717, 2020-
01052, 2020-01067, 2020-01080, 2020-01508, 2020-02009,
20-03028, 2020-03308, 2021-01539, 2021-02180
CNS System Health for Radiation Monitor Systems
06/01/2020
Effluent Radiation Monitors Out of Service Longer Specified in
the Offsite Dose Assessment Manual (ODAM)
07/19/2021
Miscellaneous
The Past Three Annual Trends of the Vent/Stack Effluent Flow
Rates Via Chart
06/17/2021
6.PRM.308
Liquid Radwaste Effluent System Channel Calibration
6.PRM.310
ERP Kaman Monitor Channel Calibration
Procedures
6.PRM.313
Reactor Building Kaman Monitor Channel Calibration
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
6.PRM.320
Radwaste Building Kaman Monitor Channel Calibration
6.PRM.322
Containment High Range Area Monitor Channel Calibration
6.PRM.323
High Range Containment Monitor Victoreen Model 875 Source
Calibration Check
6.PRM.328
Kaman Sample Flow System Channel Calibration
8-CNS-CY-102
Laboratory Analytical Quality Control
9.ALARA.3
Operation of the Canberra Fastscan Whole Body Counter with
Apex-Invivo
9.INST.14
Tennelec Eclipse LB Operation
9.INST.15
REM 500 Neutron Survey Meter
9.INST.53
Ion Chamber Survey Instrument Eberline Model RO-20
9.INST.57
Friskers
9.INST.64
Thermo Electron Corporation Small Articles Monitor SAM
9.INST.68
WR Telepole GM Survey Instrument
9.INST.70
Telepole II Telescopic Meter
Corrective Action
Documents
CR-CNS-
2019-05715, 2020-01085, 2020-02092, 2020-03042, 2020-
06381
CR-CNS-
21-03440, 2021-03464, 2021-03472
Corrective Action
Documents
Resulting from
Inspection
WT-
21-0001-249
Local Law Enforcement Agency Meeting Attendance
2/18/2020
Cooper Nuclear Station Part 37 Security Plan for the
Protection of Category 1 and Category 2 Quantities of
Radioactive Material
05/24/2016
Process Control Program (Uncontrolled)
11/10/2015
CNS RP-504
Radioactive Source Inventory and Leak Test Record
2/23/2020
RAD916-01-04
RP and Radioactive Transport Actions Regarding
CFR Part 37 "Protection of Category 1 and Category 2
Radioactive Material"
Sample No.
26708005
Waste Stream Analysis Review for Dry Active Waste
2/21/2020
Miscellaneous
Sample No.
530399001
Waste Stream Analysis Review for Condensate/Waste Resins
01/20/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Sample No.
2677001
Waste Stream Analysis Review for Spent Bead Resin
06/08/2021
0.PCP.1
59.RW.10
Physical Protection of Category 1 Quantities of Radioactive
Material
9.RADOP.1
Radiation Protection at CNS
9.RW.1
Radioactive Shipments
9.RW.7
Waste Stream Sampling
9.RW.9
Filling Containers with Waste/Radioactive Material
Procedures
Security
Procedure 2.16
Radioactive Materials Security
Horizontal Storage Module Pad
2/21/2021
Radioactive Material Storage Building
05/19/2021
Underwater Survey of Spent Fuel Pool and Items Stored
Within
06/15/2021
Radiation Surveys
Low Level Radioactive Waste Building, Perimeter Fencing and
General Area
07/14/2021
2019
Radiation Protection Program Annual Report
05/27/2020
LO-2019-0039-
001
CFR Part 37 - At Facilities with a 10 CFR Part 73 Physical
Protection Program
2/27/2020
LO-2020-0127
Radiological Monitoring Instrumentation and Radioactive Solid
Waste Processing and Radioactive Material Handling,
Storage, and Transport
04/19/2021
LO-2020-066-001
CFR Part 37 - At Facilities with a 10 CFR Part 73 Physical
Protection Program
2/22/2021
Self-Assessments
QAD 2020-0019
Quality Assurance Audit 20-04, "Radiological Controls"
08/19/2020
Shipment No.
19-12
LSA-I, Dry Active Waste (Metal Trash) in a 20-foot Sea/Land
(#209002)
09/16/2019
Shipment No.
19-13
Type A, High Integrity Container (PO690656-10), Activated
Metal and Contaminated, Non-Compactible Metal Trash
10/22/2019
Shipment No.
20-02
LSA-II, Condensate Sludge and Resin Liner (PO690095-01)
06/20/2020
Shipping Records
Shipment No.
21-02
LSA-II, Steel Liner (#680262-3) Filters and Bulk Dry Active
Waste
05/11/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Shipment No.
21-05
LSA-II, Dry Active Waste (Trash) in a 20-foot Sea/Land
(ESUU200542)
07/20/2021
Corrective Action
Documents
CR-CNS-
2019-00860, 2019-01161, 2019-01166, 2019-01167, 2019-
2947, 2019-02948, 2021-02439, 2021-03013, 2021-03257,
21-03313, 2021-03346, 2021-03767
Corrective Action
Documents
Resulting from
Inspection
CR-CNS-
21-04378, 2021-04379, 2021-04385
Drawings
High Level Connectivity Diagram - Cyber Security Architecture
Fire Plans
Assessment-
RFC-003
Reactor Feedwater Control Critical Digital Assets in the
Turbine Building Corridor
Cooper Nuclear Station Cyber Security Plan
Assessment
CDA-CPE-001-
CPU2
Computer Room Control Network Firewall
10/19/2019
Assessment
CDA-PDN-002-
NS
Network Switches
01/20/2021
Assessment-
CDA-CPE-001
Computer Process Equipment
Miscellaneous
Assessment-
CDA-TGC-002
Turbine Generator Control Critical Digital Assets (Computer
Room)
11.CYBER-
SECURITY
11.CYBER.01
Physical Security Guidance for Critical Digital Assets
11.CYBER.03
Cyber Security Scope
11.CYBER.07
Configuration Control of Critical Digital Assets
11.CYBER.08
Security Impact Analysis
11.CYBER.11
Cyber Security Vulnerability Management
11.CYBER.15
Cyber Security Access Control
11.CYBER.16
Audit and Accountability Procedure
11.CYBER.18
Identification and Authentication
Procedures
11.CYBER.19
Systems and Communications Protection
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
11.CYBER.20
Supply Chain for Critical Digital Assets
11.CYBER.21
Cyber Security Defense-in-Depth
Corrective Action
Documents
CR-CNS-
20-03402, 2020-03628, 2020-03728, 2020-05668, 2021-
00573