IR 05000397/2024002
| ML24212A054 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 08/09/2024 |
| From: | Patricia Vossmar NRC/RGN-IV/DORS/PBA |
| To: | Schuetz R Energy Northwest |
| References | |
| IR 2024001 | |
| Download: ML24212A054 (18) | |
Text
August 09, 2024
SUBJECT:
COLUMBIA GENERATING STATION - INTEGRATED INSPECTION REPORT 05000397/2024002
Dear Robert Schuetz:
On June 30, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Columbia Generating Station. On July 25, 2024, the NRC inspectors discussed the results of this inspection with Dave Brown, Site Vice President, 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, Patricia J. Vossmar, Chief Reactor Projects Branch A Division of Operating Reactor Safety Docket No. 05000397 License No. NPF-21
Enclosure:
As stated
Inspection Report
Docket Number:
05000397
License Number:
Report Number:
Enterprise Identifier:
I-2024-002-0000
Licensee:
Energy Northwest
Facility:
Columbia Generating Station
Location:
Richland, WA
Inspection Dates:
April 1, 2024, to June 30, 2024
Inspectors:
J. Brodlowicz, Resident Inspector
L. Carson, Senior Health Physicist
D. Dodson, Senior Reactor Inspector
N. Greene, Senior Health Physicist
S. Hedger, Senior Emergency Preparedness Inspector
C. Highley, Senior Resident Inspector
C. Rosales-Cooper, Senior Emergency Preparedness Specialist
Approved By:
Patricia J. Vossmar, Chief
Reactor Projects Branch A
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Columbia Generating 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 05000397/2024-001-00 Failure to Track Operability Requirements of Transversing In-Core Probe Valves 71153 Closed
PLANT STATUS
The unit began the inspection period at rated thermal power. On May 1, 2024, the unit was down powered to 32 percent for repair of the adjustable speed drive system for reactor recirculation pump A. The unit was returned to rated thermal power on May 2, 2024. The unit was down powered on June 9, 2024, for preventive maintenance on the reactor recirculation pump adjustable speed drive system. The station was restored to rated thermal power on June 11, 2024, and remained at or near to 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 summer and seasonal high temperatures for the following systems:
- Ashe switchyard, reactor building heating, ventilation, and air conditioning (HVAC), service water, and vital switchgear HVAC on June 11, 2024
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)protected equipment lineup with emergency diesel generator 3 out of service on April 22, 2024 (2)high-pressure core spray on May 12, 2024 (3)
'A' residual heat removal system with 'C' out of service on May 20, 2024 (4)emergency diesel generator 3 lineup before the high-pressure core spray surveillance on June 24, 2024
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)radwaste building all floors, fire area RC-1, on April 18, 2024
- (2) HVAC equipment room 'A' and 'B', fire areas RC-11 and 12, on May 24, 2024 (3)reactor building residual heat removal train B heat exchanger rooms on 548-foot and 572-foot elevations, fire area R-4/2, on May 30, 2024 (4)cable chase room and reactor protection system (RPS) division 1, fire areas RC-3 and 4, on June 17, 2024 (5)422 equipment room and 'A' residual heat removal room, R-5 and R-15, on June 24, 2024
Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the onsite fire brigade training and performance during an unannounced fire drill on April 8, 2024.
71111.07A - Heat Exchanger/Sink Performance
Annual Review (IP Section 03.01) (1 Sample)
The inspectors evaluated readiness and performance of:
- (1) residual heat removal heat exchanger A, RHR-HX-1A1, on June 10, 2024
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 a reactor down power and entry into single loop operations in preparation for adjustable speed drive work on May 2, 2024.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated licensed operator performance in the simulator on loss of high-pressure core spray, loss of emergency bus, scram, loss-of-coolant accident (LOCA), and emergency depressurization, for operator requalification on May 13, 2024.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (1 Sample)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
(1)demineralized water system classification and basis on June 26, 2024
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)elevated Yellow risk for emergency diesel generator 3 outage on April 22, 2024 (2)elevated Yellow risk for the loss of the 115 kV off-site power for the backup transformer on May 3, 2024 (3)emergency diesel generator 2 emergent risk informed completion time (RICT) for maintenance window on June 10, 2024 (4)elevated Yellow risk for high-pressure core spray (HPCS) surveillances on June 24, 2024
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (3 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
(1)reactor core isolation cooling discharge check valve (RCIC-V-90) categorization in in-service testing subsection C (ISTC) of the ASME OM code, CR 00457692, on June 30, 2024 (2)unidentified reactor coolant system leakage instrumentation, CR 00458384, on June 30, 2024 (3)emergency diesel generator 2 fuel oil pipe leak, CR 00452873, on June 30, 2024
71111.24 - Testing and Maintenance of Equipment Important to Risk
The inspectors evaluated the following testing and maintenance activities to verify system operability and/or functionality:
Post-Maintenance Testing (PMT) (IP Section 03.01) (1 Sample)
(1)adjustable speed drive (ASD) 1A2 card replacement, Work Order 02206353-01, on June 30, 2024
Surveillance Testing (IP Section 03.01) (4 Samples)
- (1) SOP-FDR-OPS, floor drain system operation, manual determination of dry well unidentified leak rate on April 6, 2024
- (2) WO 02189187, plant procedures manual (PPM) 8.4.42, thermal performance of residual heat removal heat exchanger (RHR HX) 'A' on June 10, 2024
- (3) ISP-RCIC-Q907, RCIC isolation on low steam supply pressure channels B and D functional and channel calibration on June 18, 2024 (4)high-pressure core spray (HPCS) on June 30, 2024
Inservice Testing (IST) (IP Section 03.01) (1 Sample)
- (1) WO 02215182, standby liquid control (SLC) operability run on April 8, 2024
Diverse and Flexible Coping Strategies (FLEX) Testing (IP Section 03.02) (1 Sample)
- (1) OPS-FLEX-Q704, emergency diesel generator 4 quarterly surveillance on May 19, 2024
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 March 26, 2024. The exercise scenario simulated a partial loss of offsite power as a main turbine generator trip. Losses of emergency diesel generators resulted in only one source of alternating current power being available onsite. This was followed by a simulated steam line break in the reactor core isolation cooling system, which resulted in a simulated radiological release offsite. This was complicated further with the inability to restore reactor pressure vessel water level above the top of active fuel, coupled with filtration failures in the standby gas treatment system.
The licensee completed its critique process for the exercise on April 9, 2024, and the inspectors subsequently evaluated the effectiveness of the critique process to identify performance weaknesses and deficiencies to ensure they were entered into the corrective action program for resolution.
This documents completion of this inspection sample which was documented as a partial sample in Inspection Report 05000397/2024001 (Agencywide Documents Access and Management System [ADAMS] Accession No. ML24115A189).
71114.06 - Drill Evaluation
Additional Drill and/or Training Evolution (1 Sample)
The inspectors evaluated:
(1)simulator emergency action level (EAL) determination during the operator requalification scenario on May 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)reactor building effluent ventilation sampling system (2)turbine building effluent ventilation sampling system (3)radwaste building effluent ventilation sampling system (4)reactor building standby gas treatment system (5)off gas treatment system
Sampling and Analysis (IP Section 03.02) (5 Samples)
Inspectors evaluated the following effluent samples, sampling processes and compensatory samples:
- (1) WO 02213952-01, weekly iodine, particulate, and tritium sampling from the reactor building exhaust system (PRM-SR-2) using Procedure PPM 16.11.6, "Weekly Iodine, Particulate, and Tritium Analysis Results," revision 27, dated June 11, 2024
- (2) WO 02213952-01, weekly iodine and particulate sampling from the turbine building exhaust system (TEA-SR-26) using PPM 16.11.6, dated June 11, 2024
- (3) WO 02213952-01, weekly iodine and particulate sampling from the radwaste building exhaust system (WEA-SR-25) using PPM 16.11.6, dated June 11, 2024 (4)adjustment of flow rates for WEA-FT-14A, 14B, and 14C during weekly iodine and particulate sampling from the radwaste building system using CI-15-2, "Daily Monitor Data," revision 36, dated June 11, 2024
- (5) Log 024-WEA-FN-25-REPL-001, compensatory continuous/weekly effluent sampling system setup for the radwaste building effluent ventilation systems using PPM 12.5.37, "WEA Temporary Cart Sampling and Flow Monitoring," revision 12, dated June 12, 2024
Dose Calculations (IP Section 03.03) (3 Samples)
The inspectors evaluated the following dose calculations:
(1)continuous gaseous release permits dose evaluations for 2021 (June 2021 and December 2021)
(2)continuous gaseous release permits dose evaluations for 2022 (March 2022 and August 2022)
(3)continuous gaseous release permits dose evaluations for 2023 and 2024 (February 2023, November 2023, and May 2024)
Abnormal Discharges (IP Section 03.04) (3 Samples)
The inspectors evaluated the following abnormal discharges:
(1)turbine building roof hole effluent release, as documented in AR 427280427280 dated November 17, 2021 (2)turbine building roof hatch door opening effluent release, as documented in AR 431889431889 dated April 12, 2022 (3)turbine building roof hole effluent release, as documented in AR 444998444998 dated May 13, 2023
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 (GPI) program to identify incomplete or discontinued program elements.
OTHER ACTIVITIES - BASELINE
71153 - Follow Up of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)
The inspectors evaluated the following licensees event reporting determinations to ensure it complied with reporting requirements.
- (1) LER 2024-001-00, Failure to Track Operability Requirements of Transversing In-Core Probe Valves (ML24022A224). The inspection conclusions associated with this LER are documented in this report under Inspection Results Section 71111.15. This LER is Closed.
Reporting (IP Section 03.05) (1 Sample)
The inspectors evaluated the following licensee event reports (LERs):
- (1) Emergency notification, 10 CFR 50.72(b)(3)(ii)(B) and (v)(B), for residual heat removal degradation due to service water leak (Action Request (AR) 00454626). The event was reviewed to determine if reporting requirements were met and should have been reported by the licensee.
INSPECTION RESULTS
Minor Violation 71111.15 Failure to Isolate Primary Containment Isolation Valve Minor Violation: The inspectors identified a self-revealing, minor violation of TS 3.6.1.3 for primary containment isolation valves (PCIVs) TIP V-1 and V-2. Specifically, on November 16, 2023, clearance order D-TIP-V-7 and V-8 -001 was hung to support replacement of squib valves TIP-V-7 and TIP-V-8, which was an administrative control to close and de-activate TIP-V-1 and TIP-V-2 and provide means to satisfy TS Action Statements 3.6.1.3.A.1 and 2. At 10:43 a.m. on November 21, 2023, clearance orders D-TIP-V-7 and 8-001 were lifted prior to completing all of the post-maintenance testing (PMT) and caused TIP-V-1 and TIP-V-2 to be tracked as inoperable on an limiting condition of operability (LCO) Tracking Sheet T23-TIP-V-7 and no longer served as administrative means to satisfy TS action statements A.1 and A.2. On November 22, 2023, the on-coming shift control room supervisor (CRS) reviewed the LCO Tracking Sheet and identified that the PMT requirements were not completed and immediately directed crew to perform the remaining PMT to restore Operability. TS action statement was exited at 9:21 a.m. with TS A.1 and A.2 being ineffectively tracked for 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> and 38 minutes.
Screening: The inspectors determined the performance deficiency was minor. TIP-V-1 and 2 remained closed and de-activated despite not being administratively controlled by the clearance order D-TIP-V-7 and 8-001; therefore, although it is associated with the Barrier integrity cornerstone, this event did not represent a pathway out of containment. It also could not be viewed as a precursor to a significant event since TIP-V-1 and 2 remained closed and de-energized despite no longer being tagged out. Successful completion of the PMT demonstrated there was no potential to lead to a more significant safety concern and did not adversely affect an associated cornerstone objective outside of administrative tracking; therefore, this issue screens to minor.
Enforcement:
TS 3.6.1.3, "Primary Containment Isolation Valves (PCIVs)," requires, in part, that each PCIV shall be operable in Modes 1, 2, and 3. TS 3.6.1.3, condition A, states, in part, if one or more penetration flow paths with one PCIV inoperable, then isolate the affected penetration flow path by use of at least one closed and de-activated automatic valve in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. TS 3.6.1.3, condition E, states, in part, that if the required action and associated completion time of condition A is not met, then 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 />.
Contrary to the above, from November 21-22 (22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> and 3 minutes), with one PCIV inoperable, the affected penetration flow path did not use at least one de-activated automatic valve and action was not taken to place Columbia Generating Station in Mode 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> as required by TS 3.6.1.3.E.1. Specifically, the licensee lifted the clearance order D-TIP-V-7 and 8-001 prior to completing PMT and restoring TIP-V-1 and 2 to an operable condition. The licensee's immediate corrective actions to perform PMT OSP-TIP-M101 restored operability to TIP-V-1 & 2.
The disposition of this violation closes LER 05000397/2024-001-00, Failure to Track Operability Requirements of Transversing In-Core Probe Valves. This failure to comply with TS 3.6.1.3 constitutes a minor violation that is not subject to enforcement action in accordance with the NRC's Enforcement Policy.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On June 13, 2024, the inspectors presented the radiation protection program inspection results to Grover Hettel, Executive Vice President and Chief Nuclear Officer, and other members of the licensee staff.
- On June 13, 2024, the inspectors presented the emergency preparedness exercise inspection results to Grover Hettel, Executive Vice President/Chief Nuclear Officer, and other members of the licensee staff.
- On July 25, 2024, the inspectors presented the integrated inspection results to Dave Brown, Site Vice President, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
Resulting from
Inspection
Action Requests
458204, 458205, 458206
Procedures
1.3.83
Protected Equipment Program
Procedures
Residual Heat Removal System A Valve Position Verification
Procedures
SOP-DG3-STBY
High Pressure Core Spray Diesel Generator Standby Lineup
Corrective Action
Documents
Resulting from
Inspection
CR00458757, CR00458759, CR00458760, CR00458761,
CR00458770
Fire Plans
Reactor 422
Fire Plans
Radwaste 437-452
Fire Plans
Radwaste 467
Fire Plans
Radwaste 484-487
Fire Plans
Radwaste 501-507
Fire Plans
Radwaste 525
Miscellaneous
RW467-IN-5
Fire Drill Scenario for Radwaste Building 467 ft Level
04/08/2024
Procedures
1.3.1
Operating Policies, Programs, and Practices
141
Procedures
OI-09
Operations Standards and Expectation
Corrective Action
Documents
436095, 436380, 441376
Miscellaneous
Performance Criteria Basis Document
DW-SYS-1
Miscellaneous
Function Basis Document
DW-01, 02, and 03
Procedures
1.5.11
Work Orders
277731
Procedures
1.3.83
Protected Equipment Program
Corrective Action
Documents
Resulting from
457102, 457103, 459607
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Inspection
Procedures
RCIC Isolation on Low Steam Supply Pressure-Channels B
and D-CFT/CC
Procedures
Diesel Generator 4 Quarterly Surveillance
Procedures
OSP-SLC/IST-
Q701
Standby Liquid Control Pumps Operability Test
Work Orders
212945, 2206276
Corrective Action
Documents
Condition Reports
(AR)
2196, 452279, 456699, 456702, 456705, 456707, 456708,
456977, 456979, 456994, 457031, 457127, 457141
Corrective Action
Documents
Resulting from
Inspection
Condition Reports
(AR)
456734, 457699, 457701, 458472
Miscellaneous
March 2024 Columbia Generating Station and Off-site
Response Agency Ingestion Pathway (IPX) Evaluated
Exercise, Leadership Team Debrief
04/09/2024
Procedures
GEN-RPP-05
Respiratory Protection Program Description
Procedures
GEN-RPP-10
Use of Respiratory Protection Equipment
Procedures
OI-54
Operations Qualification Management
Procedures
SWP-CAP-01
Corrective Action Program
Corrective Action
Documents
Action Requests
2189, 422253, 427280, 430924, 431889, 432093, 435495,
437360, 440629, 441900, 442869, 444043, 444998, 445420,
446793, 446841, 457942
Corrective Action
Documents
Resulting from
Inspection
Action Requests
459163
Drawings
M544
Flow Diagram: HVAC - Standby Gas Treatment Reactor
Building
Drawings
M548-1
Flow Diagram: HVAC for Control and Switchgear Rooms -
Radwaste Building
103
Miscellaneous
Results of Radiochemistry Cross Check Program, 2nd
Quarter 2022
08/08/2022
Miscellaneous
Results of Radiochemistry Cross Check Program, 1st
06/10/2023
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Quarter 2023
Miscellaneous
Results of Radiochemistry Cross Check Program, 4th
Quarter 2023
2/14/2023
Miscellaneous
Results of Radiochemistry Cross Check Program, 3rd
Quarter 2021
08/13/2021
Miscellaneous
Columbia Generating Station Gaseous Release Permits from
06/28/2021 to 03/12/2024
06/11/2024
Miscellaneous
22 Part 61 Waste Stream Data
09/07/2023
Miscellaneous
Results of the 2023 Five-Mile Land Use Census
08/18/2023
Miscellaneous
Columbia Generating Station - Gaseous Effluent Period
Release Summary
07/14/2021
Miscellaneous
Columbia Generating Station - Gaseous Effluent Period
Release Summary
01/16/2022
Miscellaneous
Columbia Generating Station - Gaseous Effluent Period
Release Summary
04/11/2022
Miscellaneous
Columbia Generating Station - Gaseous Effluent Period
Release Summary
09/14/2022
Miscellaneous
Columbia Generating Station - Gaseous Effluent Period
Release Summary
03/23/2023
Miscellaneous
Columbia Generating Station - Gaseous Effluent Period
Release Summary
2/12/2023
Miscellaneous
Columbia Generating Station - Gaseous Effluent Period
Release Summary
06/10/2024
Miscellaneous
G02-22-048
Columbia Generating Station 2021 Annual Radioactive
Effluent Release Report
04/15/2022
Miscellaneous
G02-23-057
Columbia Generating Station 2022 Annual Radioactive
Effluent Release Report
04/25/2023
Miscellaneous
G02-24-042
Columbia Generating Station 2023 Annual Radioactive
Effluent Release Report
04/22/2024
Procedures
CI-15-2
Daily Monitor Data
Procedures
PPM 12.1.1
Laboratory Quality Assurance
Procedures
PPM 12.5.37
WEA Temporary Cart Sampling and Flow Monitoring
Procedures
PPM 16.10.1
Radioactive Liquid Waste Discharged to the River
Procedures
PPM 16.11.1
Monthly Grab Gas Samples
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
PPM 16.11.2
Grab Gas Samples Following Shutdown, Start-up and Power
Changes
Procedures
PPM 16.11.4
Monthly Composite Particulate Sample Analysis
Procedures
PPM 16.11.5
Quarterly Composite Particulate Sample Analysis
Procedures
PPM 16.11.6
Weekly Iodine, Particulate, and Tritium Analysis Results
Procedures
PPM 16.12.2
Monthly Gaseous Release Dose Assessment
Procedures
PPM 16.12.3
Annual Noble Gas, Iodine, and Particulates
Procedures
PPM 16.12.4
Total Cumulative Dose Contributions to the Public from
Liquid and Gaseous Effluent and Direct Radiation
Procedures
PPM 16.12.5
Annual Effluent Report
Procedures
PPM 16.14.1
Gaseous Monitor Setpoint Determinations
Self-Assessments AR-SA 427580
Performance Indicator (PI) Verification PR-01: Radiological
Effluent Technical Specifications/Offsite Dose Calculation
Manual Radiological Effluent Occurrences
2/15/2021
Self-Assessments AR-SA 438303
NRC IP 71124.06 - Radioactive Gaseous and Liquid Effluent
Treatment
01/11/2024
Self-Assessments AR-SA 439232
Performance Indicator (PI) Verification PR-01: Radiological
Effluent Technical Specifications/Offsite Dose Calculation
Manual Radiological Effluent Occurrences
01/17/2023
Self-Assessments AR-SA 453143
Performance Indicator (PI) Verification PR-01: Radiological
Effluent Technical Specifications/Offsite Dose Calculation
Manual Radiological Effluent Occurrences
01/30/2024
Self-Assessments AU-CH-22
Quality Services Audit Report: Chemistry and Environmental
Monitoring Programs
08/10/2022
Calibration
Records
ICP-MET-S302
04/01/2024
Calibration
Records
ICP-MET-S301
04/04/2024
Corrective Action
Documents
Action Requests
430924, 431889, 437162, 440574, 440576, 441900, 443715,
443967, 444080, 448529, 451961, 452578, 454324, 454889
Corrective Action
Documents
Resulting from
Inspection
Action Requests
437162, 459189, 459205, 459253
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
Columbia Generating Station 2021 Annual Radiological
Environmental Operating Report
04/11/2022
Miscellaneous
Columbia Generating Station 2022 Annual Radiological
Environmental Operating Report
05/09/2023
Miscellaneous
Columbia Generating Station 2023 Annual Radiological
Environmental Operating Report
04/09/2024
Miscellaneous
Land Use Census
08/03/2021
Miscellaneous
Land Use Census
08/29/2022
Miscellaneous
Land Use Census
08/13/2023
Procedures
Radiological Inter-Laboratory and Intra-Laboratory
Comparison Programs
Procedures
CI 6.0
Groundwater Protection Program - Risk Assessment
Procedures
PPM 16.13.2
Annual Environmental Operating Report
Procedures
PPM 1.11.1
Radiological Environmental Monitoring Program
Implementation Procedure
Procedures
PPM 10.24.74
Periodic Inspection of Meteorological System
Procedures
PPM 12.5.38
Cooling Tower Sludge Removal
Procedures
PPM 13.9.1
Environmental Field Monitoring Operations
Procedures
SOP 11.05
Garden Products Sampling
Procedures
SOP 11.06
Fish Collection and Preparation
Procedures
SWP-CHE-1
Groundwater Protection Program
Procedures
SWP-CHE-1
Groundwater Protection Program
Self-Assessments
CGS MET Review Report 2022: MET Data and XOQ/DOQ
05/23/2023
Self-Assessments
23 In-Light Dosimeter Audit
05/24/2023
Self-Assessments
Quality Audit of Landauer Inc Audit Report #25286
10/16/2021
Self-Assessments
Groundwater Protection Program as outlined in SWP-CHE-
(NEI 07-07 Revision 1)
09/20/2021
Self-Assessments AU-CH-22
QA Audit Chemistry and Environmental Monitoring Programs
08/10/2022