IR 05000397/2022004
| ML23019A345 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 01/23/2023 |
| From: | Patricia Vossmar NRC/RGN-IV/DORS/PBA |
| To: | Schuetz R Energy Northwest |
| Freeman H | |
| References | |
| IR 2022004 | |
| Download: ML23019A345 (25) | |
Text
January 23, 2023
SUBJECT:
COLUMBIA GENERATING STATION - INTEGRATED INSPECTION REPORT 05000397/2022004
Dear Robert Schuetz:
On December 31, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Columbia Generating Station. On January 12, 2023, 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 NRC-identified or self-revealing findings were identified during this inspection.
Licensee-identified violations which were determined to be of very low safety significance are documented in this report. We are treating these violations as non-cited violations (NCVs)
consistent with Section 2.3.2 of the Enforcement Policy.
If you contest the violations or the significance or severity of the violations 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 Columbia Generating 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, Patricia J. Vossmar, Chief 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-2022-004-0004
Licensee:
Energy Northwest
Facility:
Columbia Generating Station
Location:
Richland, WA
Inspection Dates:
October 01, 2022, to December 31, 2022
Inspectors:
P. Niebaum, Senior Resident Inspector
A. Donley, Resident Inspector
N. Hernandez, Operations Engineer
J. Drake, Senior Reactor Inspector
S. Hedger, Senior Emergency Preparedness Inspector
H. Strittmatter, Emergency Preparedness Inspector
J. Walker, Emergency Response Inspector
Approved By:
Patricia J. Vossmar, Chief
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. Licensee-identified non-cited violations are documented in report sections: 71111.15 and 71152
List of Findings and Violations
No findings or violations of more than minor significance were identified.
Additional Tracking Items
None.
PLANT STATUS
Columbia Generating Station began the inspection period at rated thermal power (RTP). On December 10, 2022, the station reduced power to approximately 60 percent RTP for a control rod sequence exchange and surveillance testing. The station returned to 100 percent RTP later that day and remained at or near that power level 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 and during seasonal cold temperatures for the following systems:
diesel generator ventilation on November 8, 2022
standby service water on November 10, 2022
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
(1)residual heat removal system (RHR) A when RHR B was out of service for maintenance on October 17, 2022 (2)high pressure core spray system (HPCS) when the reactor core isolation cooling (RCIC) system was out of service for corrective maintenance on November 29, 2022
- (3) RHR B when the RHR A system was out of service for maintenance on December 6, 2022 (4)control room air conditioning system B when aligned to standby service water while emergency control room chiller B was out of service for maintenance on December 16, 2022
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations during a complete walkdown of the emergency diesel generator division 2 system on October 10, 2022.
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (8 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)fire areas DG-3, 9, 5; diesel generator 2 (DG-2), DG-2 day tank, and DG-2 diesel fuel oil storage tank access rooms; on October 4, 2022 (2)fire area R-5, RHR pump room 2A, on October 17, 2022 (3)fire area RC-3/1, vertical electrical cable chase, on November 15, 2022 (4)fire area R-4, RHR pump room 2B, on December 6, 2022 (5)fire areas RC-9, 6, 7; remote shutdown and division 2 battery rooms, electrical equipment, and reactor protection system (RPS) rooms; on December 16, 2022 (6)fire areas RC-4, 5; division 1 electrical equipment, RPS, and battery rooms; on December 16, 2022 (7)fire area R-1, reactor building elevation 471-foot general equipment area, on December 27, 2022 (8)fire area DG-10, deluge valve equipment room, on December 27, 2022
71111.06 - Flood Protection Measures
Inspection Activities - Internal Flooding (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated internal flooding mitigation protections in the reactor building 422-foot elevation, emergency core cooling pump room watertight doors, on December 23, 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 October 31, 2022, to December 8, 2022.
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)
- (1) The inspectors observed and evaluated licensed operator performance in the control room during a load reduction, control rod sequence exchange, and scram time testing on December 10, 2022.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated an annual simulator exam scenario on November 21, 2021.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (2 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)high energy line break (HELB) structures, enclosures, and panels on October 7, 2022 (2)adjustable speed drive system for the reactor recirculation pumps on December 22, 2022
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 for inoperability of the backup transformer due to Bonneville Power Administration maintenance on the 115 kV line on October 28, 2022
- (2) Yellow risk for corrective maintenance on the reactor core isolation cooling keep fill pump on November 29 and 30, 2022
- (3) Yellow risk and increased on-line fire risk for residual heat removal system A planned maintenance outage on December 6, 2022
- (4) Yellow risk for a high-risk evolution due to increased plant transient probability associated with emergent Bonneville Power Administration work on 500kV output line breaker on December 21, 2022
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (5 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
(1)condition report (CR) 437368, control room chiller 1B (CCH-CR-1B) lower sight glass low oil level, completed on October 20, 2022
- (2) CR 438074, alternate power supply for 2A and 2B inverters impacted due to degraded capacitors associated with transformer E-TR-IN/2, completed on October 31, 2022
- (3) CR 438395, evaluation of barrier impairment process for tornado missile barrier B-DOOR-G200 associated with the 'B' service water pump house planned for November 1, 2022
- (4) CR 436766, service water flow to control room emergency chiller 1B below minimum flow for operability, on November 17, 2022
- (5) CR 439030, watertight door R10A found open and door R10 not fully dogged, on December 23, 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)work order 02167219 for control room division A emergency filtration system following planned system outage on October 12, 2022 (2)work order 02200819, corrective maintenance for replacement of the capacitors in E-TR-IN/2 on October 27, 2022 (3)work order 02164578 for FLEX diesel generator (DG4) following maintenance on November 16, 2022 (4)work order 02201855, replacement of RCIC-P-3, reactor core isolation cooling keep fill pump power frame on November 30, 2022
- (5) OSP-RHR/IST-Q702, RHR Loop A Operability Test, following planned maintenance on RHR system A on December 7, 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) (3 Samples)
- (1) WO 02189057, channel calibration/functional test of RHR system B (low pressure coolant injection mode) pump start time delay relay, RHR-RLY-K70B, on October 20, 2022
- (2) SR 3.6.4.1.1 secondary containment drawdown time determination per OSP-INST-H101 on November 9, 2022
- (3) WO 02195088, monthly operability test of DG-2, on December 22, 2022
Inservice Testing (IP Section 03.01) (1 Sample)
- (1) OSP-SW/IST-Q701, Standby Service Water Loop A Operability, in accordance with WO 02189201 on November 7, 2022
71114.01 - Exercise Evaluation
Inspection Review (IP Section 02.01-02.11) (1 Sample)
- (1) The inspectors evaluated the biennial emergency plan exercise conducted on October 25, 2022. The exercise scenario simulated a reactor coolant system leak in the drywell, an anticipated transient without scram, losses of feedwater and condensate pumps; a break in the reactor core isolation cooling system steam line with failed isolation; emergency depressurization with loss of most low-pressure emergency core cooling systems, and a loss of reactor vessel water level below the top of active fuel.
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10)===
- (1) October 1, 2021, through September 30, 2022
BI02: RCS Leak Rate Sample (IP Section 02.11) (1 Sample)
- (1) October 1, 2021, through September 30, 2022
EP01: Drill/Exercise Performance (DEP) Sample (IP Section 02.12) (1 Sample)
- (1) October 1, 2021, through September 30, 2022 EP02: Emergency Response Organization (ERO) Drill Participation (IP Section 02.13) (1 Sample)
- (1) October 1, 2021, through September 30, 2022 EP03: Alert And Notification System (ANS) Reliability Sample (IP Section 02.14) (1 Sample)
- (1) October 1, 2021, through September 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) CR 437979, missed limiting condition for operation 3.0.9 and flood tour, on November 17, 2022
- (2) CR 433720, RRC-P-1A (1A reactor recirculation pump) manually tripped following restart on adjustable speed drive channel 1A/2 on June 11, 2022
71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02)
- (1) The inspectors reviewed the licensees corrective action program for an identified adverse trend in procedure use and adherence that might be indicative of a more significant safety issue, CR 00433595, gap in procedure use and adherence. One observation was documented in the results section of this report.
INSPECTION RESULTS
Licensee-Identified Non-Cited Violation 71111.15 This violation of very low safety significance was identified by the licensee and has been entered into the licensees corrective action program and is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
Violation: Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix B, criterion V, Instructions, Procedures, and Drawings requires in part, activities affecting qualityshall be accomplished in accordance with these instructions, procedures, or drawings. More specifically, licensee procedure 1.3.57, Barrier Impairment, step 4.11.1 states that flood barriers shall be operable in Modes 1/2/3, and step 4.11.2.1.a.3 provides the required compensatory measures to be taken when the reactor building 422-foot water-resistant doors are propped open for more than 15 minutes. Contrary to this requirement, on November 24, 2022, with two flood barriers inoperable in Mode 1, the licensee failed to implement the required compensatory measures. Specifically, the licensee identified door R10A was left open and door R10 was not fully latched in the closed position, rendering both doors inoperable and no compensatory measures had been implemented. These are the two water-resistant doors leading into the high-pressure core spray pump room from the control rod drive pump room and are both credited flood barriers. Upon discovery, the licensee closed and latched the two doors restoring operability of the flood barriers and documented the issue in a condition report.
Significance/Severity: Green. The inspectors determined the finding was very low safety significance, Green, when screened in accordance with NRCs Inspection Manual Chapter (IMC) 0609, Appendix A, The Significance Determination Process For Findings At-Power.
Specifically, using the exhibit 2 mitigating systems screening questions, the finding did not involve the loss of degradation of equipment specifically designed to mitigate a flooding initiating event (e.g., flooding barriers) for greater than 14 days.
Corrective Action References: The issue was captured in the licensees corrective action program under CR 439030.
Licensee-Identified Non-Cited Violation 71152A This violation of very low safety significance was identified by the licensee and has been entered into the licensees corrective action program and is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
Violation: 10 CFR 50, Appendix B, criterion V, Instructions, Procedures, and Drawings requires in part Activities affecting quality shall be prescribed by documented instructions, procedures, or drawings, of a type appropriate to the circumstances and shall be accomplished in accordance with these instructions, procedures, or drawings. More specifically, licensee procedure 1.3.57, Barrier Impairment, step 4.11.1 states that flood barriers shall be operable in Modes 1/2/3, and step 4.14.1 states in part that HELB barriers in primary and secondary containment are required to be operable in Modes 1/2/3.
Compensatory measures are required for when those barriers are inoperable, depending on the function of the barrier that is impacted (e.g., HELB and flood), as defined in license procedure 1.3.57. Contrary to this requirement, on October 24, 2022, with a flood and HELB barrier inoperable in Mode 1, the licensee failed to implement the required compensatory measures. Specifically, the licensee failed to enact the compensatory measures listed in procedure 1.3.57 while maintenance was performed on reactor building door R211 that rendered the flood and HELB barrier functions of the door inoperable.
Significance/Severity: Green. The inspectors determined the finding was very low safety significance, Green, when screened in accordance with NRCs Inspection Manual Chapter (IMC) 0609, Appendix A, The Significance Determination Process For Findings At-Power.
Specifically, all of the screening questions in exhibit 2 mitigating systems screening questions, section A, mitigating SSCs and PRA functionality (except reactivity control systems) were answered no as the door was fixed and the barrier restored within 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.
Corrective Action References: The issue was captured in the licensees corrective action program as CR 437979.
Observation - Adverse Trend in Procedure Use and Adherence 71152S The inspectors reviewed the licensee's corrective action program (CAP) for licensee-identified adverse trends during a six-month period ending November 28, 2022. CR 433595 documented an adverse trend in NRC violations that reflect human performance issues in procedure use and adherence. The gap, drivers, actions, results worksheet and associated corrective actions for this negative trend have been completed. The licensee is continuing to monitor for any additional NRC violations that reflect issues in procedure use and adherence and if performance degrades further, another CR will be written to address the continued negative trend. While the licensee continues to trend performance, the station has begun implementing corrective actions including manager in the field observations and specific pre-job brief templates.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On November 21, 2022, the inspectors presented the emergency preparedness exercise inspection results to Robert Schuetz, Chief Executive Officer, and other members of the licensee staff.
On December 9, 2022, the inspectors presented the annual requalification examination inspection results to Kelly Robertson, Examination Group Supervisor, and other members of the licensee staff.
On January 12, 2023, the inspectors presented the integrated inspection results to Robert Schuetz, Chief Executive Officer, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
Action Requests
26293, 429685, 413893, 423107, 433925
Procedures
SOP-
COLDWEATHER-
Cold Weather Operations
039, 040
Corrective Action
Documents
Action Requests
437345, 434126, 431146, 417435, 416161, 384618, 360196,
437802, 439746
Corrective Action
Documents
Resulting from
Inspection
Action Requests
439747
M512-3
Flow Diagram Diesel Oil & Miscellaneous Systems Diesel
Generator Building
2
M520
Flow Diagram HPCS and LPCS Systems Reactor Building
105
M521-1
Flow Diagram Residual Heat Removal System Loop A
117
M521-2
Flow Diagram Residual Heat Removal Loop B
117
M524-2
Flow Diagram Standby Service Water System Reactor,
Radwaste, D.G. Bldgs and Yard
24
M551
Flow Diagram HVAC Circ water, Make-up water & Service
Water Pump Houses & Diesel Generator Bldg
071
Drawings
M775
Flow Diagram Emergency Chilled Water Piping System
Control Room
030, 031
HPCS Valve Lineup
006
Residual Heat Removal System B Valve Position Verification
004
Standby Service Water Loop B Valve Position Verification
053
SOP-DG2-LU
Emergency Diesel Generator (DIV 2) Valve & Power Supply
Lineup
010
SOP-DG2-STBY
Emergency Diesel Generator (DIV 2) Standby Lineup
25
Procedures
SOP-HVAC/CR-
LU
Control, Cable, and Critical Switchgear Rooms HVAC Lineup
003
SOP-HVAC/CR-
Control, Cable, and Critical Switchgear Rooms HVAC
Operations
030
SOP-HVAC/CR-
STBY
Control, Cable, and Critical Switchgear Rooms HVAC in
Standby Status
2
SOP-RHR-LU
RHR System Valve and Breaker Lineup
009
SOP-RHR-STBY
Placing RHR in Standby Status
006
Procedures
SOP-SW-LU
Standby Service Water System Valve & Breaker Lineup
016
2134916, 02106765, 02175583, 02184395
Work Orders
Work Requests
29104562, 29119495, 29166453, 29144635, 29133029
Calculations
FP-02-85-03
Combustible Loading Calculation
011
Corrective Action
Documents
Action Requests
434082
Corrective Action
Documents
Resulting from
Inspection
Action Requests
437869, 438816, 440032, 439936, 439941
PFP-DG-
BUILDING
Diesel Generator Building
004, 005
Reactor 471
007
PFP-RB-
BUILDING
Reactor 422
007
Fire Plans
Radwaste 467 (Fire Area RC-3/1)
006, 007
15.2.14
Function Check, Sensitivity Check and Cleaning of
Photoelectric Detectors
015
15.2.16
Thermal Detector - Channel Function Test
009
15.2.2
Function and Sensitivity Check of Ionization Detectors
21
15.4.6
Essential Fire Rated Penetration Seal and Essential Fire and
Flood Barrier Operability Inspection
014
Procedures
ABN-FIRE
Fire
045
Work Orders
2166895
5.44.20
Calculation of Allowable Leakage Past Doors on RB Pump
Rooms Elevation 422
001
Calculations
ME-02-02-02
Calculation for Reactor Building Flooding Analysis
001
Calculations
ME-02-93-57 and
calculation
modifications
CMR-98-0167,
CMR-94-0507
Effects of Stairwell Flooding on Adjacent Pump Rooms
(422 ft 3 in Elevation)
000
Corrective Action
Documents
Action Requests
435749, 435704, 437438, 408253
Corrective Action
Documents
Resulting from
Inspection
Action Requests
439802
2-0472
Barrier Impairment Permit
A553
Door Schedule Sheet 1
045
Spec Section 8H Watertight Doors R4 through R13
010
SPC 08H
Design Specification for Division 8 Section 8H Interior Water-
Resistant Doors and Frames
003
Miscellaneous
STL-S748
Structural Reactor Building Interior Walls
25
Procedures
15.3.17
Fire Door Operability Inspections
011
Work Orders
2168010, 02141746
Miscellaneous
22 Annual Licensed Operator Requalification Examination
Results
Reactivity Control Plan, Sequence Exchange and Surveillance
Testing
December
22
Miscellaneous
LE000047
LORQ Annual Exam Scenario
000
3.3.1
Reactor Scram
069
Control Rod Scram Accumulator Verification
009
000
SOP-DEH-OPS
Main Turbine DEH Operations
23
SWP-TQS-01
Training, Qualifications and Simulators
21
TDI-23
LORQ Annual Exam Development and Administration
018
Procedures
TSP-CRD-C101
CRD Scram Timing with Auto Scram Timer System
030
Corrective Action
Documents
Action Requests
23489, 390934, 390844, 3908733, 389937, 400637, 401022,
416184, 411721, 431110, 431123, 431209, 424522, 430304,
431015, 432146, 418481, 424626, 390934, 435704, 410248,
408826, 433588, 424399, 433720, 273087
Corrective Action
Documents
Resulting from
Inspection
Action Requests
435131, 434361, 434359, 438062
M545-1
Flow Diagram Heating Ventilation and Air conditioning Reactor
Building
073
M545-2
Flow Diagram Heating Ventilation and Air conditioning Reactor
Building
014
Drawings
M545-3
Flow Diagram Heating Ventilation and Air conditioning Reactor
Building
26
Engineering
Changes
Evaluation of Open Enclosures
004
Life Cycle Management Plan Adjustable Speed Drives
004, 005
2B35-20,13,16
GE FANUC Automation Series 90 30 PLC Installation &
Hardware Manual
WO 02112343, 02112340,
AR 433720433720 AR 273087273087 AR 433720433720001
TM-2004
Evaluation of Safety-Significant Equipment for Moisture
Intrusion Potential
001
Miscellaneous
TM-2019
Summary of Equipment Qualification Environmental Profiles
013
1.3.56
Conduct of Maintenance
015
1.3.57
Barrier Impairment
043
1.5.11
016
10.25.60
Reactor Recirc Inverter Maintenance
000
ABN-ASD-INV
Failure
2
SOP-ELEC-ASD-
Adjustable Speed Drive UPS System Operation
004
SOP-ELEC-ASD-
START
Adjustable Speed Drive UPS System Startup
003
SOP-HVAC-ASD
Shutdown ASD Building Ventilation System Shutdown
000
Procedures
SOP-RRC-FLOW-
Reactor Power Change With RRC Flow Controllers - Quick
Card
005
SOP-RRC-
SHUTDOWN
Reactor Recirculation System Shutdown
005
SYS-4-22
015
Procedures
SYS-4-23
Maintenance Rule Structural Baseline Inspections
001
2198308, 0217913, 02117345
2112343, 02112340
Work Orders
Work Requests
29162338, 29147552, 29167052, 29147084, 29165557,
29152335, 29162244
Corrective Action
Documents
Action Requests
439372, 439864, 439875
Fire Prevention Evaluation Permits: 22-0062, 22-0063,
2-0064, 22-0065, 22-0066, 22-0067, 22-0068, 22-0069,
2-0070, 22-0071, 22-0072, 22-0073
Operator Log Entry
2/21/2022
P-500kV-003
eSOMS protection scheme
P-E-TR-B-02
eSOMS protection scheme
P-RHR-SYS-A-
001
eSOMS protection scheme
T22-E-TR-B-006
eSOMS tracker
Miscellaneous
T22-RHR-SYS-A-
001
eSOMS tracker
1.3.83
Protected Equipment Program
037
1.3.85
On-line Fire Risk Management
006
1.5.14
Risk Assessment and Management for
Maintenance/Surveillance Activities
044
Response
Procedure
4.800.C4
800.C4 Annunciator Panel Alarms
Procedures
OI-41
Operations Work Control Expectations
073
5.44.20
Calculation of Allowable Leakage Past Doors on RB Pump
Rooms Elevation 422
001
Calculations
ME-02-02-02
Calculation for Reactor Building Flooding Analysis
001
Corrective Action
Documents
Action Requests
27687, 438205, 436881, 323811, 422237, 409203
Corrective Action
Documents
Resulting from
Inspection
Action Requests
437600, 437632, 438708
Drawings
E504-1
Vital One Line Diagram
007
Engineering
Changes
Service Water Pump House Door B-DOOR-G200 with gear
box internal shear pins broken
000
BIP 19-0146
Barrier Impairment Permit for B-DOOR-G200
10/31/2022
BIP 21-0269
Barrier Impairment Process for B-DOOR-G200
06/06/2021
CVI 339-00,1,5
York Centrifugal Turbopak R-11, Installation, Operation and
Maintenance Instructions
001
Miscellaneous
TM-2150
Mission Time of Emergency Safety Features
2
8.4.81
SW System Performance with FPC HX Valved In
008
ABN-FLOODING
Flooding
2
ECCS Pump Room Flood Level - Calibration
003
Electrical Distribution Subsystem Breaker Alignment and
Power Availability Verification
037
Standby Service Water Loop B Valve Position Verification
046, 051
Procedures
SPS-9-5
Fuji Ultrasonic Flowmeter Operation
001
20167155, 02187303, 02188838, 02085979, 02145627,
2085979, 02177755
Work Orders
Work Requests
29167528
Corrective Action
Documents
Action Requests
437433, 437322, 437340, 439058
Drawings
M521-1
Flow Diagram - Residual Heat Removal System Loop A
119
10.2.10
Fastener Torque and Tensioning
030
MSP-WMA-B101
Control Room Div A Emergency Filtration System HEPA Filter
Test
010
MSP-WMA-B103
Control Room Div A Filtration System - Carbon Adsorber Test
014
Diesel Generator 4 Quarterly Surveillance
2
Procedures
RCIC Fill, Flow Controllers, and Valve Lineup Verification
019
Work Orders
2167220, 02178890
Corrective Action
Documents
Action Requests
307452, 321177, 035374, 438611, 438649, 439867, 439868
EWD-9E-004B
Electrical Wiring Diagram RHR System, Pump RHR-P-2B
Breaker RHR-CB-P2B
003
Drawings
EWD-9E-097
Electrical Wiring Diagram Residual Heat Removal System
Miscellaneous Relay Circuits (Div 2)
013
Engineering
Evaluations
TE 12862
Technical Evaluation of Secondary Containment Loss of
Safety Function
03/06/2014
E/I-02-91-1076
Setting Range Determination For RHR-RLY-K70A(B)
003
RHR Pump B Time Delay (LPCI Mode) - CFT/CC
014
IST-4
Inservice Testing Program Plan, Fourth Ten-Year Inspection
Interval
6.0
Procedures
Diesel Generator 2 - Monthly Operability Test
Work Orders
Corrective Action
Documents
Action Requests
(ARs)
2865, 415391, 416842, 416863, 420927, 424824, 432417,
434636, 434926, 434964, 435001, 435004, 435460, 435759,
435785, 435858, 436644, 426115, 427035, 427770, 427887,
430259, 432157, 433111, 433278, 434040, 412056, 420879,
23847, 424448, 424705, 425035, 438082, 438358, 438359
Corrective Action
Documents
Resulting from
Inspection
Action Requests
438193
Columbia Generating Station, ERO Team A ERO Drill, Dress
Rehearsal, September 13, 2022, After Action
Report/Improvement Plan
000
Columbia Generating Station ERO Team A Drill Report,
October 27, 2020 - After Action Report/Improvement Plan
000
Columbia Generating Station ERO Team D Dress Rehearsal
Drill Report, February 25, 2020 - After Action
Report/Improvement Plan
03/19/2020
Miscellaneous
Columbia Generating Station ERO Team B Drill Report, April
6, 2021 - After Action Report/Improvement Plan
04/29/2021
Columbia Generating Station ERO Team D Dress Rehearsal
Drill Report, August 31, 2021 - After Action
Report/Improvement Plan
10/7/2021
Columbia Generating Station ERO Team D Exercise Report,
October 26, 2021 - After Action Report/Improvement Plan
2/6/2021
Columbia Generating Station ERO EDMG Demonstration
Exercise Report, November 30, 2021 - After Action
Report/Improvement Plan
000
Columbia Generating Station ERO Team A Drill Report,
February 22, 2022 - After Action Report/Improvement Plan
000
Columbia Generating Station ERO Team C Drill Report,
June 21, 2022 - After Action Report/Improvement Plan
000
Columbia Generating Station ERO Team A Dress Rehearsal
Drill Report, September 13, 2022 - After Action
Report/Improvement Plan
000
Form 26522
Operations Support Center (OSC) Manager Checklist
005
Form 26523
OSC Repair Team Coordinator Checklist
004
Form 26525
OSC Health Physics Lead Checklist
008
Form 26526
005
Form 26527
OSC Chemistry Technician Checklist
001
Miscellaneous
Form 26528
004
13.1.1A
Classifying the Emergency - Technical Bases
034 (Minor
2)
13.10.9
Operations Support Center Manager and Staff Duties
050
13.11.7
Radiological Emergency Manager Duties
037 (Minor
004)
13.14.11
EP Equipment
014 (Minor
001)
13.14.8
Drill and Exercise Program
018 (Minor
2)
13.2.2
Determining Protective Action Recommendations
20 (Minor
2)
13.4.1
Emergency Notifications
044 (Minor
001)
13.8.1
Emergency Dose Projection System Operations
040
Procedures
EPI-21
Drill and Exercise Development and Implementation
019
71151
Corrective Action
Documents
Resulting from
Inspection
Action Requests
438201
Consolidated Data Entry (CDE) Desktop Guide
ANS Test Report Data 2021Q4 - 2022Q3
Key ERO Member Drill Participation Data 2021Q4 - 2022Q3
Report
Alert and Notification System (ANS) Design Report
2
Miscellaneous
Regulatory Assessment Performance Indicator Guideline
007
13.14.4
Emergency Equipment Maintenance and Testing
054 (Minor
005)
CI-10.17
014
CSP-I131-W101
Reactor Coolant Isotopic Analysis for I-131 Dose Equivalent
009
EPI-18
Emergency Preparedness Performance Indicators
27 (Minor
N/A)
TSI-6.2.22
EP Annual Emergency Response Siren System Activation
Test
004 (Minor
2)
71151
Procedures
TSI-6.2.32
003 (Minor
2)
Action Requests
2145
Corrective Action
Documents
Action Requests
(ARs)
430745, 435013, 424814, 435320, 435050, 420746, 433451,
433450, 433448, 419954
Operations Logs
10/24/2022
BI 22-0192
Barrier Impairment Permit
Miscellaneous
Root Cause
Evaluation
RRC-P-1A Manually Tripped Following Restart on ASD 1A/2
Channel
08/16/2022
SOP-HVAC-ASD
Startup ASD Building Ventilation System Startup
000
1.3.57
Barrier Impairment
046
1.3.83
Protected Equipment Program
037
Procedures
10.25.103
ASD Cooling System Cartridge Filter Replacement
003, 004,
005
10.25.66
Reactor Recirc Inverter, RRC-IN-ASD/1A (1B), Battery
Replacement
000
10.25.68
RRC Induction Motor Drive Software Settings and Self-Test
001
Procedures
SOP-ELEC-ASD-
SHUTDOWN
Adjustable Speed Drive UPS System Shutdown
003
SOP-RRC-ASD
Reactor Recirculation ASD Operation
018, 019
Procedures
SOP-RRC-
START
Reactor Recirculation System Start
21
2194321
Work Orders
Work Requests
29165556
GBP-CAP-03
Trending Program
2
Procedures
TM-01
Trending Manual
004