IR 05000298/2022003
| ML22300A063 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 10/27/2022 |
| From: | Jeffrey Josey, William Schaup NRC/RGN-IV/DORS/PBC |
| To: | Dent J Nebraska Public Power District (NPPD) |
| Josey J | |
| References | |
| IR 2022003 | |
| Download: ML22300A063 (19) | |
Text
October 27, 2022
SUBJECT:
COOPER NUCLEAR STATION - INTEGRATED INSPECTION REPORT 05000298/2022003
Dear John Dent:
On September 30, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Cooper Nuclear Station. On October 6, 2022, 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.
One finding of very low safety significance (Green) is documented in this report. This finding involved a violation of NRC requirements. We are treating this violation as a non-cited violation (NCV) consistent with section 2.3.2 of the Enforcement Policy.
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.
If you disagree with a cross-cutting aspect assignment in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region IV; and the NRC Resident Inspector at Cooper Nuclear Station. 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-2022-003-0010
Licensee:
Nebraska Public Power District
Facility:
Cooper Nuclear Station
Location:
Brownville, NE
Inspection Dates:
July 1 to September 30, 2022
Inspectors:
D. Antonangeli, Health Physicist
B. Bergeon, Senior Operations Engineer
K. Chambliss, Resident Inspector
N. Greene, Senior Health Physicist
A. Siwy, Senior Resident 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
Failure to Maintain in Effect all Provisions of the Fire Protection Program Cornerstone Significance Cross-Cutting Aspect Report Section Initiating Events Green NCV 05000298/2022003-01 Open/Closed
[P.1] -
Identification 71111.05 The inspectors identified a Green finding and associated non-cited violation of Facility Operating License 2.C(4), Fire Protection, for the failure to implement in effect all provisions of the approved fire protection program. Specifically, prior to May 24, 2022, the licensee failed to promptly clean up combustible liquids that had come in contact with insulation and replace insulation as needed in accordance with the licensees committed National Fire Protection Association (NFPA) 805 standard, element 3.3.10.
Additional Tracking Items
None.
PLANT STATUS
Cooper Nuclear Station began the inspection period at rated thermal power. On July 3, 2022, the plant commenced power coastdown. On August 26, 2022, power was lowered to approximately 70 percent for core management. On August 27, 2022, the plant was returned to approximately 81 percent for continued power coastdown. The plant continued power coastdown for the remainder of the inspection period. The unit was approximately 70 percent power at the end 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
71111.04 - 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 residual heat removal service water on July 21, 2022 (2)division 1 service water on July 28, 2022 (3)reactor core isolation cooling on August 2, 2022 (4)division 1 125 Vdc system on September 28, 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)control building basement floor, residual heat removal service water booster pump room, 882-foot 6-inch elevation, on July 21, 2022 (2)control building battery/switchgear rooms, 903-foot 6-inch elevation, on August 29, 2022 (3)reactor building southwest quadrant, 881-foot 9-inch and 859-foot 9-inch elevations, on August 29, 2022 (4)control building cable spreading room, 918-foot elevation, on September 16, 2022 (5)reactor building northwest quadrant, 881-foot 9-inch and 859-foot 9-inch elevations, on September 26, 2022
71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance
Requalification Examination Results (IP Section 03.03) (1 Sample)
- (1) The inspectors reviewed and evaluated the licensed operator examination failure rates for the requalification annual operating exam administered June 7 through July 15, 2022.
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (2 Samples)
- (1) The inspectors observed and evaluated a simulator scenario on July 26, 2022.
- (2) The inspectors observed and evaluated a simulator scenario on September 2, 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 (SSCs) remain capable of performing their intended function:
(1)circulating water function CW-SD1 near (a)(1) on August 5, 2022 (2)heating and ventilation function HV-F03 exceeded number of functional failures on August 11, 2022 (3)condensate makeup function CM-F01 approved to remain in a(2) on September 19, 2022
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:
(1)standby liquid control A relief valve maintenance on July 8, 2022 (2)planned Yellow online risk with high pressure coolant injection inoperable on July 11, 2022 (3)planned Yellow online risk for emergency diesel generator 2 maintenance window on July 21, 2022 (4)planned Yellow online risk during core spray A logic testing on August 2, 2022 (5)planned Yellow online risk during division 1 service water chemical injection on September 26, 2022
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (4 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
(1)high pressure coolant injection condensate drain valve HPCI-MO-40 failed to open on August 4, 2022 (2)residual heat removal heat exchanger B sample valve leak degradation on August 9, 2022 (3)residual heat removal pump C motor test data out of range on August 10, 2022 (4)southeast quad fan coil unit reduced air flow on August 19, 2022
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated the following post-maintenance testing activities to verify system operability and/or functionality:
(1)replace SGT-SOV-SPV543B2 on July 1, 2022 (2)post replacement leak rate test for REC-V-217 on July 5, 2022 (3)replace vent pipe for service water booster pump A on July 20, 2022 (4)emergency diesel generator 2 overvoltage relay replacement on August 9, 2022 (5)service water booster pump D gland water line replacement on September 6, 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) (1 Sample)
(1)reactor protection system electrical protection assembly 1B1 calibration on September 29, 2022
71114.06 - Drill Evaluation
Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01) (1 Sample)
(1)emergency preparedness drill on September 13,
RADIATION SAFETY
71124.06 - Radioactive Gaseous and Liquid Effluent Treatment
Walkdowns and Observations (IP Section 03.01) (5 Samples)
The inspectors evaluated the following radioactive effluent systems during walkdowns:
(1)liquid radwaste radiation monitor RMP-RE-354 (2)elevated release point high range radiation monitor RMP-RM-3B (3)turbine building normal range radiation monitor RMV-RM-20A (4)radwaste and augmented radwaste building high range radiation monitor RMV-RM-30B (5)reactor building normal range radiation monitor RMV-RM-40
Sampling and Analysis (IP Section 03.02) (4 Samples)
Inspectors evaluated the following effluent samples, sampling processes and compensatory samples:
(1)liquid effluent discharge - gamma analysis - May 11, 2020 (2)reactor building vent - particulate sample - September 1, 2020 (3)radwaste building vent - charcoal sample - June 1, 2021 (4)elevated release point - noble gas sample - December 5, 2021
Dose Calculations (IP Section 03.03) (3 Samples)
The inspectors evaluated the following dose calculations:
(1)elevated release point dose analysis for the 4th quarter of 2021 (2)radwaste and augmented radwaste building dose analysis for February 2022 (3)liquid effluent dose analysis for August 2020 Abnormal Discharges (IP Section 03.04)
The inspectors evaluated the inspection period and identified no abnormal discharges to review.
71124.07 - Radiological Environmental Monitoring Program
Environmental Monitoring Equipment and Sampling (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated environmental monitoring equipment and observed collection of environmental samples.
Radiological Environmental Monitoring Program (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the implementation of the licensees radiological environmental monitoring program.
GPI Implementation (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated the licensees implementation of the Groundwater Protection Initiative program to identify incomplete or discontinued program elements.
There were no incomplete or discontinued program elements identified.
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, 2021, through June 30, 2022 IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02) (1 Sample)
- (1) July 1, 2021, through June 30, 2022
IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (1 Sample)
- (1) July 1, 2021, through June 30, 2022
MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04) (1 Sample)
- (1) January 1 through June 30, 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)safety function determination program review on August 19, 2022
71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02)
- (1) The inspectors reviewed the licensees corrective action program for potential adverse trends in procedure adherence that might be indicative of a more significant safety issue.
INSPECTION RESULTS
Failure to Maintain in Effect all Provisions of the Fire Protection Program Cornerstone Significance Cross-Cutting Aspect Report Section Initiating Events Green NCV 05000298/2022003-01 Open/Closed
[P.1] -
Identification 71111.05 The inspectors identified a Green finding and associated non-cited violation of Facility Operating License 2.C(4), Fire Protection, for the failure to implement in effect all provisions of the approved fire protection program. Specifically, prior to May 24, 2022, the licensee failed to promptly clean up combustible liquids that had come in contact with insulation and replace insulation as needed in accordance with the licensees committed National Fire Protection Association (NFPA) 805 standard, element 3.3.10.
Description:
On May 24, 2022, while maintenance technicians were brazing a replacement filter for the control room air conditioning unit in the cable spreading room, a fire occurred during brazing on insulation resulting in the fire watch having to suppress the flame. The flame was extinguished in approximately 10 seconds. Engineering analysis later determined the insulation had been impregnated with petroleum.
The licensees NFPA 805 commitment, element 3.3.10 states, Combustible liquids, including high flashpoint lubricating oils, shall be kept from coming into contact with hot pipes and surfaces, including insulated pipes and surfaces. Administrative controls shall require the prompt cleanup of oil on insulation. The licensee did not identify nor perform prompt cleanup for the oil-impregnated insulation.
Cooper Nuclear Station Procedure 0.7.1, Control of Combustibles, revision 42, section 4.2.12.1 states, Immediately clean up any combustible liquids that come in contact with insulation and replace insulation as needed. The licensee failed to either clean up the combustible liquids on the insulation or replace or remove the insulation to prevent the insulation from becoming flammable.
The licensees NFPA 805 commitment, element 3.3.1.3.1, requires a hot work procedure in accordance with NFPA standard 51B, 1999 edition. NFPA standard 51B, 1999 edition, section 3-3.2, provides guidance for mitigating hazards for performing hot work near combustible material. It states, in part, all combustible materials shall be relocated at least 35 feet horizontally from the work site. If relocation is impractical, combustibles shall be protected with fire-retardant covers or otherwise shielded with metal or fire-retardant guards or curtains. The licensee did not perform a thorough pre-job walkdown to identify all risk hazards prior to performing hot work. As a result, the licensee failed to recognize the insulation as combustible material since the insulation had been impregnated with petroleum; and the licensee failed to either relocate or shield the impregnated insulation to mitigate the fire hazard.
Corrective Actions: Immediately following the fire event, the licensee paused all hot work on site to conduct a review of the licensees hot work procedures, policies, and training. The licensee removed all insulation for the control room air conditioning unit. Additionally, the licensee initiated a condition report and revised the hot work procedure to better indicate the risk of performing hot work in sensitive areas, established a seminar to communicate the risk of performing work in sensitive areas, and revised fire watch training to increase recognition of hazards.
Corrective Action References: condition report CR-CNS-2022-02221
Performance Assessment:
Performance Deficiency: The inspectors determined that failure to implement all provisions of the fire protection program was a performance deficiency that was within the licensees ability to foresee and prevent. Specifically, the licensee did not promptly cleanup combustible liquids which came in contact with hot pipes and surfaces nor replaced insulation as needed resulting in a fire during hot work activities in the cable spreading room.
Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Protection Against External Factors attribute of the Initiating Events cornerstone and adversely affected the cornerstone objective to limit the likelihood of events that upset plant stability and challenge critical safety functions during shutdown as well as power operations. Specifically, while performing hot-work maintenance, a fire occurred inside the cable spreading room that could have upset plant stability or challenged critical safety functions during power operations.
Significance: The inspectors assessed the significance of the finding using IMC 0609, appendix F, Fire Protection Significance Determination Process. The finding was determined to be within the Fire Prevention and Administrative Controls using attachment 1 and screened under attachment 2 as having a High Degradation rating for failing to ensure the location was free of combustibles or that combustibles that cannot be moved were shielded against ignition. The inspectors assessed the significance of the finding using IMC 0609.04, Initial Characterization of Findings, and IMC 0609, appendix F, attachment 1, and determined the finding to be of very low safety significance (Green) because the fire adversely affected an area with adequate automatic detection and suppression.
Cross-Cutting Aspect: P.1 - Identification: The organization implements a corrective action program with a low threshold for identifying issues. Individuals identify issues completely, accurately, and in a timely manner in accordance with the program. Specifically, the licensee did not accurately and completely identify the insulation in the area where the hot work was impregnated with combustible liquid. Cooper Nuclear Station Procedure 0.39, "Hot Work,"
section 2.2, provides guidance for performing hot work in a restricted area which includes the cable spreading room. It states, in part, a hot work area inspection is required by Fire Protection (FP) or a Licensed Operator (LO) prior to initiating hot work in the hot work restricted areas. The individual performing the inspection will sign the applicable step on the hot work permit. The technician filling out the hot work permit failed to recognize the cable spreading room as a restricted area and the required signature was missing. This resulted in a failure of the defense-in-depth to prevent a fire by failing to confirm a thorough inspection of the hot work area and identifying all combustible materials in the hot work area.
Enforcement:
Violation: License condition 2.C(4) requires, in part, that, NPPD shall implement and maintain in effect all provisions of the approved fire protection program. As per the licensees NFPA 805 commitment, element 3.3.10, requires in part, that, administrative controls shall require the prompt cleanup of oil on insulation. Cooper Nuclear Station Procedure 0.7.1, Control of Combustibles, revision 42, section 4.2.12.1 states, Immediately clean up any combustible liquids that come in contact with insulation and replace insulation as needed.
Contrary to the above, prior to May 24, 2022, the licensee failed to implement and maintain in effect all provisions of the approved fire protection program. Specifically, the licensee failed to promptly clean up combustible liquids that had come into contact with insulation and replace insulation as needed. Additionally, the licensee failed to remove insulation prior to performing hot work activities near the oil-impregnated insulation in the cable spreading room.
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 July 14, 2022, the inspectors presented the radiation safety inspection results to Khalil Dia, Site Vice President, and other members of the licensee staff.
On August 10, 2022, the inspectors presented the IP 71111.11A inspection results to Matthew Bohannon, Operations Training Supervisor - Requalification, and other members of the licensee staff.
On October 6, 2022, the inspectors presented the integrated inspection results to John 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
Drawings
DWG-3058
DC One Line Diagram
2.2.25.1
25 VDC Electrical System (Div 1)
2.2.67A
Reactor Core Isolation Cooling System Component Checklist
2.2A.RHRSW.DIV1
RHR Service Water Booster Pump System Component
Checklist (Div 1)
2.2A.SW.DIV1
Service Water System Component Checklist (Div 1)
Procedures
2.2A_125DC.DIV1
25 VDC Power Checklist (Div 1)
Corrective Action
Documents
CR-CNS-
22-02221, 2022-03667
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-224
Control Building Basement Floor Elevation 882-6
CNS-FP-228
Control Building Battery/Switchgear Rooms Elevation 9036
Fire Plans
CNS-FP-229
Control Building Cable Spreading Room Elevation 918-0
0.23
CNS Fire Protection Plan
Procedures
0.39
Hot Work
54, 55
2.4RXLVL
RPV Water Level Control Trouble
5.7.1
Emergency Classification
5.7.1.1
Emergency Classification Process
RPV Control (1-3)
RPV Flooding
Primary Containment Control (1-3)
Procedures
EPIPEALHOT
Corrective Action
Documents
CR-CNS-
20-03402, 2020-05668, 2020-05933, 2021-00573, 2022-
00053, 2022-01851, 2022-02184, 2022-02307, 2022-02466,
22-02912, 2022-03472, 2022-03788
Maintenance Rule Function Basis for HV-F03
VM-0308
Exhaust Fans and Accessories
VM-0491
Raychem Auto Trace Composite Manual
Miscellaneous
VM-1408
Honeywell Operators and Actuators
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
0-CNS-LI-102
Corrective Action Process
2.1
2.5
7.3.21.6
Fire Seal Installation - Permanent Ceramic Fiber
Procedures
Secondary Containment Control (1-3)
Work Orders
WO 5316815, 5317501, 5352211, 5397932, 5403127, 5408577
Miscellaneous
Protected Equipment Tagout, SW-1-FALL 2022 CHM INJ DIV
Work Orders
WO 210245, 5211335, 5439652, 5454160
Corrective Action
Documents
CR-CNS-
22-03239, 2022-03406, 2022-03479, 2022-03501, 2022-
03504,
Drawings
DWG 2036,
Sheet 2
Flow Diagram Reactor Building Service Water System
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
VM-1490
LRP - RACK - SREC Condensate FD Sample Rack
Miscellaneous
VM-1801
MCEMAX Data Interpretation
Procedures
7.3.20.3
Motor Analysis
Work Orders
Corrective Action
Documents
CR-CNS-
22-03120, 2022-03475
DWG 2006,
Sheet 4
Flow Diagram Control Building Service Water
Drawings
DWG 3012,
Sheet 6
Main Three Line Diagram
VM-0248
Crane Valve Composite Manual
VM-0633
Reactor Protection Electrical Protection Assembly
VM-1023
Vogt Valve Composite Manual
Miscellaneous
VM-1750
GE Relay Composite Manual
Procedures
6.2SGT.301
SGT Operability Test/Off Gas Flow Monitor Channel
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Functional Test IST (Div 2)
6.MISC.401
Position Indicator Inservice Testing (IST)
7.2.26.8
Bolted or Screwed Bonnet Globe Valve Maintenance
7.2.49.1
Environmental Qualified NP ASCO Solenoid Valve
Replacement
7.2.57.1
Pipe Support Removal and Reinstallation
7.2.71.1
Bolting and Torquing Implementation
7.3.13
Motor Control Center and Local Auxiliary Shutdown Panels
Examination and Maintenance
7.3.28.1
Lead Removal/Installation and Lug Installation
7.7.10.80
P8-A Welding Procedure Specification
Work Orders
WO 5393872, 5397664, 5406184, 5410691, 5432546, 5457083
Corrective Action
Documents
CR-CNS-
22-04154
Drawings
DWG 3010, Sheet
Vital One Line Diagram
Procedures
6.2RPS.313
RPS Electrical Protection Assemblies Calibration and
Functional Test (Div 2)
Work Orders
Corrective Action
Documents
CR-CNS-
2019-05466, 2019-05596, 2020-02642, 2020-03084,2020-
06191, 2020-06357, 2021-00019, 2021-00813, 2021-01679,
21-04902, 2022-02042, 2022-02044,
Corrective Action
Documents
Resulting from
Inspection
CR-CNS-
22-03033
Liquid Radioactive Waste Discharge Package 20-33
05/11/2020
Elevated Release Point Dose Analysis for the 4th Quarter of
21
Radwaste and Augmented Building Sample Analysis for
February 2022
Radwaste and Augmented Building Sample Analysis for
June 2021
Miscellaneous
Elevated Release Point Sample Analysis for January 2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Elevated Release Point Sample Analysis for December 2021
2/05/2021
Results of Radiochemistry Cross Check Program for 2021
8.11.1
Effects Program
8.4.1.2
Gaseous Releases Emergency Sampling
8.8.1.19
Effluent Composite Sample Preparation and Analysis
8.8.1.31
Radiochemical Analysis of Tritium
8.8.11
Liquid Radioactive Waste Discharge Authorization
8.8.15
Noble Gas and Tritium Sampling from Effluent Release
Pathways
8.8ERP
Particulate and Iodine Sample Collection for ERP Effluent
8.8RW
Particulate and Iodine Sample Collection for Radwaste
Building Effluent
8.8RX
Particulate and Iodine Sample Collection for Reactor Building
Effluent
8.8TB
Particulate and Iodine Sample Collection for Turbine Building
Effluent
Procedures
CNS-CY-110
Canberra Apex Gamma Spectroscopy System Operation
Self-Assessments
LO-2020-0204-005
Effluent Focused Self-Assessment
06/02/2022
Corrective Action
Documents
CR-CNS-
2019-04570, 2019-04579, 2019-04691, 2019-04836, 2019-
04950, 2019-04960, 2019-04982, 2019-05746, 2019-05763,
2019-05866, 2019-06111, 2020-02666, 2020-03115, 2020-
211, 2020-05678, 2020-06124, 2021-00779, 2021-01059,
21-01751, 2021-01923, 2021-03032, 2021-03854, 2021-
04137, 2022-00460
Corrective Action
Documents
Resulting from
Inspection
CR-CNS-
22-02978, 2022-03015
REMP Training Records
07/07/2022
Training Records for Meteorological Instrumentation
07/07/2022
XOQOD Maps 2021
06/13/2022
Cooper Nuclear Station Offsite Dose Calculation Manual
(ODAM)
04/01/2020
Miscellaneous
Cooper Nuclear Station Radioactive Effluent Release Report
2019, 2020,
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
21
Cooper Nuclear Station Radiological Environmental
Monitoring Program Annual Report
2019, 2020,
21
20-018
License Basis Document Change Request - ODAM
Appendix C
03/29/2020
CR-CNS-2020-
2666
50.75(g) Leak/Spill Record
06/24/2020
14.MET.304
Meteorological Maintenance Procedure for New 100-Meter
Tower - System A
14.MET.305
Meteorological Maintenance Procedure for New 100-Meter
Tower - System B
8.CNS-CY-102
Quality Control for Analytical Laboratory Interlab and Intralab
Cross-Check Programs
8.ENV.1
REMP Administration
8.ENV.2
REMP Sampling
8.ENV.3
Action Levels for Environmental Samples
8.ENV.4
8.ENV.5
Annual Review of Broadleaf Vegetation Sample Locations
Procedure
8.ENV.6
Annual CNS Land Use Census
8.ENV.7
CNS Temporary LLRW Storage Facility Sampling Program
8.ENV.8
Administering the CNS Meteorological Program (CNS MET)
8.ENV.9
Ground Water Monitoring Program Sampling, Monitoring, and
Administrative Requirements
Procedures
Response to Contaminated Spills/Leaks
Radiation
Surveys
903-foot OCA - Leak/Spill Survey
06/24/2020
LO-2020-0204-004
REMP Focused Self-Assessment
03/30/2022
Self-Assessments
LO-HQNLO-2021-
00024
Groundwater Protection Program
10/27/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
CR-CNS-
22-02724
2.0.11
Entering and Exiting Technical Specification/TRM/ODAM
LCO Condition(s)
Procedures
2.0.11.1
Safety Function Determination Program
Corrective Action
Documents
CR-CNS-
22-05067