IR 05000397/2020002
| ML20210M406 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 07/29/2020 |
| From: | Jeffrey Josey NRC/RGN-IV/DRP/RPB-A |
| To: | Sawatzke B Energy Northwest |
| References | |
| IR 2020002 | |
| Preceding documents: |
|
| Download: ML20210M406 (22) | |
Text
July 29, 2020
SUBJECT:
COLUMBIA GENERATING STATION - INTEGRATED INSPECTION REPORT 05000397/2020002
Dear Mr. Sawatzke:
On June 30, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Columbia Generating Station. On July 9, 2020, the NRC inspectors discussed the results of this inspection with Mr. W. Hettel, Chief Nuclear Officer/Vice President Nuclear Generation, 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 did not involve a violation of NRC requirements.
If you disagree with a finding not associated with a regulatory requirement 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 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, Jeffrey E. Josey, Chief Reactor Projects Branch A Division of Reactor Projects
Docket No. 05000397 License No. NPF-21
Enclosure:
As stated
Inspection Report
Docket Number:
05000397
License Number:
Report Number:
Enterprise Identifier: I-2020-002-0011
Licensee:
Energy Northwest
Facility:
Columbia Generating Station
Location:
Richland, WA
Inspection Dates:
April 1, 2020 to June 30, 2020
Inspectors:
G. Kolcum, Senior Resident Inspector
L. Merker, Acting Senior Resident Inspector
C. Roettgen, Senior Resident Inspector
J. Mateychick, Senior Reactor Inspector
W. Cullum, Reactor Inspector
N. Okonkwo, Reactor Inspector
Approved By:
Jeffrey E. Josey, Chief
Reactor Projects Branch A
Division of Reactor Projects
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
Failure to Follow Corrective Action Procedure in 2008 Leads to Recirculation Pump Trip Cornerstone Significance Cross-Cutting Aspect Report Section Initiating Events Green FIN 05000397/2020002-01 Open/Closed None (NPP)71152 The inspectors reviewed a self-revealed, Green, finding for the licensees failure to follow plant Procedure SWP-CAP-01, Corrective Action Program, Revision 16, that describes the corrective action process beginning with the identification of an issue or condition through implementing actions to correct the condition and/or preclude its recurrence. Specifically, in 2008, the licensee had a corrective action to perform a causal evaluation to understand the obsolescence of the adjustable speed drive (ASD) system gate turn-off thyristors (GTOs), but did not have a follow-on corrective action to address the noted increase in failure rates of the ASD system GTOs. This resulted in several ASD channel failures since 2008, and a recirculation pump trip and reactor transient on February 14, 2020.
Additional Tracking Items
None.
PLANT STATUS
The reactor unit began the inspection period at rated thermal power. On May 19, 2020, the reactor unit was down powered to 65 percent for economic dispatch from Bonneville Power Administration. On May 21, 2020, the reactor unit was down powered to 60 percent to recover an adjustable speed drive channel following maintenance and returned to 65 percent. The unit returned to rated thermal power on May 25, 2020. On May 30, 2020, the reactor unit was down powered to 65 percent for economic dispatch from Bonneville Power Administration. On June 1, 2020, the reactor unit returned to 85 percent and then down powered to 65 percent for economic dispatch from Bonneville Power Administration. On June 5, 2020, the reactor unit was down powered to 60 percent for control rod scram time testing and sequence exchange, and maintenance on circulating water valve 2C, and returned to 65 percent. On June 6, 2020, the reactor unit was down powered to 25 percent for economic dispatch from Bonneville Power Administration. On June 9, 2020, the reactor unit was down powered to 15 percent for the licensee to remove the main turbine generator from the grid and balance the turbine. On June 10, 2020, the main turbine generator was synchronized to the grid. On June 11, 2020, the reactor unit returned to 40 percent. On June 12, 2020, the reactor unit was down powered to 25 percent due to high vibrations on the turbine. On June 13, 2020, the reactor unit was down powered to 15 percent to remove the main turbine generator from the grid and to rebalance the turbine. On June 14, 2020, the main turbine generator was synchronized to the grid and the reactor unit returned to 40 percent. On June 15, 2020, the reactor unit down powered to 25 percent to close an open bleed steam valve and returned to 65 percent. On June 21, 2020, the reactor unit returned to 85 percent. The unit returned to rated thermal power on June 22, 2020. On June 26, 2020, the reactor unit was down powered to 40 percent for economic dispatch from Bonneville Power Administration, where it remained 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 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 and during that time conducted plant status activities as described in IMC 2515, Appendix D; 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 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
71111.01 - Adverse Weather Protection
Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of seasonal high temperatures for the following systems on June 26, 2020:
- standby service water system A
- standby service water system B
External Flooding Sample (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated readiness to cope with external flooding for the standby service water systems A and B pump rooms on May 28, 2020.
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (3 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
(1)low pressure core spray system following annual maintenance on May 7, 2020 (2)standby gas treatment system A following annual maintenance on May 21, 2020 (3)residual heat removal system C on June 19, 2020
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) Fire Area RC-19/2, vital island corridor, on April 17, 2020
- (2) Fire Area RC-2/1, cable spreading room, on April 23, 2020
- (3) Fire Area R-8/1, low pressure core spray system pump room, on May 5, 2020
- (4) Fire Areas RC-14/1 and RC-8/2, division 1 and 2 switchgear rooms, on June 5, 2020
- (5) Fire Areas RC-5/1 and RC-6/2, division 1 battery and security equipment room and division 2 battery room, on June 5, 2020
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 division 1 and 2 electrical switchgear rooms on June 16, 2020.
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 downpower for economic dispatch, May 19-20, 2020.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated a licensed operator requalification training drill (Crew C) on June 1, 2020.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated the effectiveness of low pressure core spray system maintenance to ensure the structures, systems, and components (SSCs) remained capable of performing their intended function on May 5, 2020.
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)yellow risk for reactor core isolation cooling planned maintenance on April 13, 2020 (2)high risk for recirculation pump A relay maintenance on breaker S5 on April 15, 2020 (3)high risk for adjustable speed drive system maintenance on May 21, 2020 (4)yellow risk for diesel generator 3 pre-start checks (bar over) and load testing on May 29, 2020 (5)emergent, high risk work on circulating water valve 2C during economic dispatch and station yellow risk on June 5, 2020
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated the licensee's justifications and actions associated with operability determinations and functionality assessments of degraded bolting on electrical manholes E-MH-E10, E-MH-E11, and E-MH-E15 on May 14, 2020.
71111.17T - Evaluations of Changes, Tests, and Experiments Sample Selection (IP Section 02.01)
The inspectors reviewed the following evaluations, screenings, and/or applicability determinations for 10 CFR 50.59 from April 13-17, 2020:
(1)5059EVAL-17-0003, Approve Use of GOTHIC for Analysis of Certain High Energy Line Breaks, Revision 0 (2)5059EVAL-18-0001, Changing Methodology to GOTHIC 8.1 for RWCU HELB Analysis, Revision 0 (3)5059SCREEN-16-0012, Main Steam Line Flow Restrictor Chocked Flow, Revision 0 (4)5059SCREEN-17-0034, RWCU-MO-1 & 4 Modifications (Actuator Replacements),
Revision 0 (5)5059SCREEN-19-0106, RHR-MO-4A Gear Change for RHR-V-4A, Revision 0 (6)5059SCREEN-19-0110, Major Leak from Turbine Building Oil System, Revision 0 (7)5059SCREEN-19-0118, ABN-FLOODING, Revision 0 (8)5059SCREEN-19-0130, EC 16816, Replace the Valve Wedge and Change the Gear Ratio in RHR-V-8, Revision 0 (9)5059SCREEN-19-0135, LDCN-19-045, Revision 0 (10)5059SCREEN-17-0145, Backseat HV-V-31B by its Electrical Motor, Revision 0 (11)5059SCREEN-17-0146, Installation of Protective Plate on Reactor Building ECCS Room Water Tight Doors, Revision 0 (12)5059SCREEN-17-0150, PPM ABN-FAZ Procedure Revision to Make the Procedure More Efficient, Revision 0 (13)5059SCREEN-17-0167, Temporary Modification EC 16899 Will Use Nitrogen to Maintain BS-RV-26A in the closed position, Revision 0 (14)5059SCREEN-18-0030, Keep Mechanical Gag on AR-AO-1 to Permanently Keep AR-V-1 Open, Revision 0 (15)5059SCREEN-19-0017, Add Sentence to FSAR Section 11.4.2.4 for the Radwaste Disposal System for Fuel Pool, Floor Drain, and Waste Collector Filter Resin, Revision 0 (16)5059SCREEN-16-0076, Replaces Existing GE NGV 125 VDC Battery Ground Detection Relays E-RLY-4PG/B5, and -64PG/B6 With an ABB 27B Model. EC
===15414, Revision 0 (17)5059SCREEN-16-0148, Replace Existing E-EF-IN4/ACIN With a New AC Filter, Revision 0 (18)5059SCREEN-17-0161, Level 8 Setpoint Setdown Software Changes, Revision 0 (19)5059SCREEN-18-0003, FSAR Revision For Use of GOTHIC in Safety Analysis (LDCN-18-002), Revision 0 (20)5059SCREEN-18-0014, Replace ITE Safety Related E-CB-8A4A MCCB With Fused Disconnect E-DISC-8A4A, Revision 0 (21)5059SCREEN-18-0015, Replace ITE Augmented Quality E-CB-8C1C MCCB With Fused Disconnect E-DISC-8C1C, Revision 0 (22)5059SCREEN-18-0015, Replace ITE Augmented Quality E-CB-8C4A MCCB With Fused Disconnect E-DISC-8C4A, Revision 0 (23)5059SCREEN-18-0016, Replace ITE Augmented Quality E-CB-8C4A MCCB With Fused Disconnect E-DISC-8C4A, Revision 0 (24)5059SCREEN-19-0064, Install CCTV for the Main Transformers, Revision 0 (25)5059SCREEN-19-0120, Replace Existing ITE Molded Case Circuit Breakers E-CB-8B2D, E-CB-2C1D, and WCH-CB-8E1E With Fused Disconnects, Revision 0
- (26) Applicability Determination LS-19-0233, Procedure 5.6.1, SBO/ELAP, Revision 030, Revision 0
- (27) Applicability Determination LS-20-0074, Procedure 5.6.2, Station Blackout (SBO)and Extended Loss of AC Power ELAP Attachments, Revision 015, Revision 0
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02)
=
- (1) The inspectors evaluated the temporary modification of concrete block placement on manhole covers E-MH-E11 and E-MH-E15 on April 30, 2020.
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)eight-hour report 54466, loss of seismic assessment instrumentation, on April 2, 2020 (2)replacement of fire pump 110 batteries, week of April 16, 2020 (3)reactor water cleanup system pump 3A maintenance on April 20, 2020 (4)low pressure core spray system annual maintenance on May 6, 2020 (5)standby gas treatment system A on May 20, 2020 (6)fire protection pump 2B on June 24, 2020
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
- (1) OSP-CRD-W101, control rod SCRAM accumulator verification, on April 15, 2020
- (2) OSP-CRD-M101, SCRAM discharge volume vent and drain valve monthly operability, on April 16, 2020
- (3) ESP-BAT-W101, weekly battery test, on April 14, 2020
Inservice Testing (IP Section 03.01) (1 Sample)
- (1) OSP-CCH/IST-M702, control room emergency chiller system B operability, on April 29,
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04)===
(1)
(April 1, 2019-April 30, 2020)
71152 - Problem Identification and Resolution
Semiannual Trend Review (IP Section 02.02) (1 Sample)
- (1) The inspectors reviewed the licensees corrective action program for potential adverse trends that might be indicative of a more significant safety issue. The inspectors performed an in-depth review of the licensee's ability to identify when prohibited items are brought onsite, evaluate each occurrence, and implement corrective actions; and documented one observation on June 30, 2020.
Annual Follow-up of Selected Issues (IP Section 02.03) (2 Samples)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
(1)evaluation of the February 14, 2020, trip of recirculation pump 1A on June 3, 2020 (2)evaluation of the January 15, 2020, loss of adjustable speed drive channel 1A/2 on June 15, 2020
71153 - Follow-up of Events and Notices of Enforcement Discretion Reporting (IP Section 03.05)
- (1) The inspectors evaluated a June 2, 2020, inadvertent emergency response organization callout and the licensee's response on June 4,
INSPECTION RESULTS
Failure to Follow Corrective Action Procedure in 2008 Leads to Recirculation Pump Trip Cornerstone Significance Cross-Cutting Aspect Report Section Initiating Events
Green FIN 05000397/2020002-01 Open/Closed
None (NPP)71152 The inspectors reviewed a self-revealed, Green, finding for the licensees failure to follow plant Procedure SWP-CAP-01, Corrective Action Program, Revision 16, that describes the corrective action process beginning with the identification of an issue or condition through implementing actions to correct the condition and/or preclude its recurrence. Specifically, in 2008, the licensee had a corrective action to perform a causal evaluation to understand the obsolescence of the adjustable speed drive (ASD) system gate turn-off thyristors (GTOs), but did not have a follow-on corrective action to address the noted increase in failure rates of the ASD system GTOs. This resulted in several ASD channel failures since 2008 and a recirculation pump trip and reactor transient on February 14, 2020.
Description:
On February 14, 2020, recirculation pump 1A tripped off when both ASD channels 1A/1 and 1A/2 tripped due to internal faults. The reactor recirculation system is designed to provide forced coolant flow through the reactor core and consists of two loops, each with a recirculation pump. The ASD system controls recirculation pump flow by varying the frequency of the electrical power supplied to the pump motor. Each recirculation pump is controlled by two ASD channels. Both channels are required for the recirculation pump to operate at full speed. A recirculation pump can be operated with only one ASD channel in service at a reduced speed.
In 2008, the licensee initiated action request (AR) 186054 that identified the ASD system GTOs failure rate was increasing. The AR also stated the cards were greater than 12 years old and may be nearing end of life. The licensee performed a causal evaluation that restated the GTO failure rate was increasing after 10-12 years of service. However, no corrective action assignment was initiated to address the increased failure rate of the GTO cards. This AR was cross referenced to engineering technical evaluation (AR-EVAL) 178017 that documented the obsolescence of the ASD system.
Engineering technical evaluation AR-EVAL 178017 had three assignments. The first assignment was to find a replacement part for the obsolete GTO; this assignment was closed out stating a replacement did not exist and that the ASD system would need to be replaced. The second assignment was to evaluate a new ASD system since the GTOs were obsolete with no repair or replacement available; this assignment was closed out with no action recommended as the licensee had enough spare GTOs available to last approximately 10 years. The third assignment was to review the evaluation and either take appropriate action or recommend AR closure; this assignment recommended the AR to be closed since the licensee had spare parts available for 10 years. Again, no corrective action assignment was initiated to address the increased failure rate of the GTO cards. The ASD obsolescence issue was then put on the licensee's 2009 long-range plan. In 2014, the ASD obsolescence issue was removed from the long-range plan and AR-EVAL 316044 was initiated to track resolution of the obsolescence of the ASD system.
The inspectors noted the purpose of Procedure SWP-CAP-01, Corrective Action Program, Revision 16, is to describe the corrective action process beginning with the identification of an issue or condition through implementing actions to correct the condition and/or preclude its recurrence. Step 4.11.1j states, in part, that corrective actions that require preliminary evaluation to understand the problem should have a separate corrective action for the preliminary activity and a follow on corrective action for implementation. In 2008, the licensee performed a causal evaluation that stated the GTO failure rate was increasing after 10-12 years of service. However, no corrective action assignment was initiated to address the increased failure rate of the GTO cards. This resulted in the GTO cards being replaced with spare parts after experiencing failure. The most recent GTO card failure resulted in the February 14, 2020, recirculation pump trip and reactor transient.
Corrective Actions: The licensee's corrective actions included replacing one GTO card in the 1A/1 channel and six GTO cards and a power supply in the 1A/2 channel, restoring both channels to service, and restarting the recirculation pump. The licensee also entered the issue into the corrective action program and completed an event investigation.
Corrective Action References: Action Request 404225
Performance Assessment:
Performance Deficiency: The failure to follow plant Procedure SWP-CAP-01, Corrective Action Program, Revision 16, that describes the corrective action process beginning with the identification of an issue or condition through implementing actions to correct the condition and/or preclude its recurrence was a performance deficiency.
Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the equipment performance 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, in 2008, the licensee had a corrective action to perform a causal evaluation to understand the obsolescence of the ASD system GTOs, but did not have a follow on corrective action to address the noted increase in failure rates. This resulted in several ASD channel failures since 2008 and a recirculation pump trip and reactor transient on February 14, 2020.
Significance: The inspectors assessed the significance of the finding using Appendix A, The Significance Determination Process (SDP) for Findings At-Power. Using the questions in Exhibit 1, initiating Events Screening Questions, the inspectors determined the finding was of very low safety significance (Green) because the finding did not cause a reactor trip and loss of mitigation equipment relied upon to transition the plant from the onset of the trip to a stable shutdown condition.
Cross-Cutting Aspect: Not Present Performance. No cross-cutting aspect was assigned to this finding because the inspectors determined the finding did not reflect present licensee performance.
Enforcement:
Inspectors did not identify a violation of regulatory requirements associated with this finding.
Observation: Increase in Prohibited Items Identified 71152 The inspectors performed an in-depth review of the licensee's evaluation and corrective actions related to a potential trend increase of prohibited items identified at the security checkpoint. From January 1, 2020, to June 30, 2020, the licensee initiated 12 action requests (ARs) related to prohibited items declared at the security checkpoint. The inspectors noted that 8 of the ARs were initiated in the second quarter, between April 1, 2020, to June 30, 2020, during the coronavirus (COVID-19) pandemic when less individuals than normal accessed the site. Conversely, from January 1, 2019, to June 30, 2019, the licensee initiated 9 similar ARs with 6 initiated in the second quarter, between April 1, 2019, to June 30, 2019, during a quarter that included Refueling Outage R24 when more individuals than normal accessed the site. The inspectors noted that the overwhelming majority of individuals with prohibited items in their possession were either contractors or delivery personnel and not licensee employees. The inspectors verified no prohibited items entered the protected area.
The inspectors assessed the licensee's problem identification threshold, evaluations, and corrective actions related to these ARs. In each instance, the licensee adequately followed site procedures to identify, evaluate, and correct the issue. The inspectors identified that the licensee was aware of the increasing trend of prohibited items identified at the security checkpoint and took corrective actions, but had not initiated an AR to document the trend. The inspectors also noted that the licensee's use of trend codes was inconsistently applied to ARs documenting prohibited items brought onsite. The licensee initiated AR 408442408442to document the concern.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On April 16, 2020, the inspectors presented the Evaluation of Changes, Tests, and Experiments Inspection exit meeting inspection results to Mr. W. Hettel, Chief Nuclear Officer/Vice President Nuclear Generation, and other members of the licensee staff.
- On July 9, 2020, the inspectors presented the integrated inspection results to Mr. W. Hettel, Chief Nuclear Officer/Vice President Nuclear Generation, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Calculations
CE-02-13-18
Probable Maximum Flood (PMF) Analysis for Columbia
Generating Station
000
CE-02-13-22
Effects of Local Intense Probable Maximum Precipitation
Analysis for Columbia Generating Station
000
ME-02-92-41
Calculation for Ultimate Heat Sink Analysis
007
ME-02-92-43
Room Temperature Calculation for DG Building, Reactor
Building, Radwaste Building and Service Water
013
Corrective Action
Documents
Action Requests
(ARs)
396990, 407275, 393438, 393813, 398976, 400018, 402976,
403992, 406096, 406680, 406733, 406737, 406949, 407290
Engineering
Changes
18010
Provide Power to E-TR-M2 Cooler Group 2 Cooler 2 Oil
Pump
001
Miscellaneous
Columbia Generating Station, Docket No. 50-397 Flooding
Hazard Reevaluation Report, Response to NRC Request for
Information Pursuant to 10 CFR 50.54(f) Regarding
Recommendation 2.1 of the Near-term Task Force Review of
Insights from the Fukushima Dai-ichi Accident
10/06/2016
Procedures
4.840.A5; 840.A5
Annunciator Panel Alarms
28
ABN-FLOODING
Flooding
2
SOP-
COLDWEATHER-
Cold Weather Operations
034
SOP-
HOTWEATHER-
Hot Weather Operations
006
SOP-
WARMWEATHER-
Warm Weather Operations
016
Work Orders
2126293, 02126294, 02129776, 29154662, 29154977
Corrective Action
Documents
Action Requests
(ARs)
2800, 396502, 407980, 407981
Drawings
M520
Flow Diagram HPCS and LPCS Systems
105
M521-3
Flow Diagram Residual Heat Removal Loop C
2
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
M544
Flow Diagram HVAC-Standby Gas Treatment
076
Miscellaneous
Instrument Master Data Sheet for SGT-FR-2A2
009
Instrument Master Data Sheet for SGT-FT-1A2
009
Procedures
1.3.29
Locked Valve Checklist
085
ABN-SGT-
TEMP/RAD
Standby Gas Treatment Charcoal High
Temperature/Radiation
006
SOP-LPCS-LU
LPCS Valve and Breaker Lineup
003
SOP-LPCS-STBY
Placing LPCS in Standby Status
2
SOP-RHR-LU
RHR System Valve and Breaker Lineup
008
SOP-RHR-STBY
Placing RHR in Standby Status
005
SOP-SGT-LU
Standby Gas Treatment System Lineup
000
SOP-SGT-STBY
Placing Standby Gas Treatment In Standby Status
2
Work Orders
29153347
Calculations
FP-02-85-03
Combustible Loading Calculation
010
Corrective Action
Documents
Action Requests
(ARs)
406072, 406195
Miscellaneous
BIP 20-0062
Transient Combustible Permit for Vital Island - General Area
04/08/2020
BIP 20-0160
Barrier Impairment Permit: Electrical Access Area, Door
C218
04/29/2020
BIP 20-0161
Barrier Impairment Permit: Electrical Access Area, Door
C218
06/01/2020
BIP 20-0178
Barrier Impairment Permit: Vital Island Door C216
04/27/2020
BIP 20-0244
Barrier Impairment Permit: Battery Room #1, Door C219
04/29/2020
BIP 20-0245
Barrier Impairment Permit: Battery Room #1, Door C219
06/01/2020
TCP 20-0014
Transient Combustible Permit: Cable Path TG501, TG471,
RW467, RW487
05/04/2020
TCP 20-0046
Transient Combustible Permit for Vital Island Div 1 Battery
Room C210, Inside Door
04/07/2020,
06/04/2020
TCP 20-0048
Transient Combustible Permit: Vital Island - General Area
05/26/2020
TCP 20-0053
Transient Combustible Permit for Vital Island - General Area
04/06/2020
TCP 20-0085
Transient Combustible Permit: RW 467 - In Front of Tool Crib
General Area
05/18/2020
Procedures
1.3.10C
Control of Combustibles
21
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
1.3.57
Barrier Impairment
038
ABN-FIRE
Fire
041
Reactor 422
006
Radwaste 467
005
Radwaste 484-487
005
Work Orders
2115649, 02128947
Calculations
ME-02-02-23
PFSS Flooding Analysis - Radwaste Building
001
ME-02-03-04
Radwaste Building Flooding Analysis
001
ME-02-11-12
Concrete Floor Flood Barrier Analysis
000
Corrective Action
Documents
Action Requests
(ARs)
398295, 400176, 400183, 403999, 404242, 407275
Miscellaneous
BIP 20-0124
Barrier Impairment Permit: R548 L7/8.3 at FPC Pump/HX
Room
03/18/2020
FPF 1.1-40
Fire Rated Penetration Seals
2
PSA-1-SM-0001
CGS PSA Internal Event Summary
008
PSA-2-FL-0002
Probabilistic Safety Assessment Model Notebook: Internal
Flooding Propagation, Screening, and Accident Scenario
Development Report
003
PSA-2-FL-0003
Probabilistic Safety Assessment Model Notebook: Internal
Flooding Initiating Events Frequency Development Report
2
Procedures
1.3.57
Barrier Impairment
038
15.4.6
Essential Fire Rated Penetration Seal and Essential Fire and
Flood Barrier Operability Inspection
011
4.FCP.3
FCP.3 Annunciator Panel Alarms
24
ABN-FLOODING
Flooding
2
SOP-
DOOR/HATCH-
Reactor Building, Turbine Building, Radwaste Building and
Containment, Personnel, Equipment Access Area Doors, and
Hatches
017
Work Orders
2138317, 02138318, 02138319, 02138320, 02138321
71111.11Q Corrective Action
Documents
Action Requests
(ARs)
389186, 402277, 406797, 407009, 407012, 407013, 404679,
407204
Miscellaneous
Reactivity Control Plan Economic Dispatch to 65% CTP May
20
05/19/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
LR002488
Columbia Generating Station Simulator Scenario 20-3
Evaluated Scenario
000
Procedures
3.3.1
REACTOR Scram
066
5.1.1
RPV Control
2
5.2.1
Primary Containment Control
28
ABN-CORE
Unplanned Core Operating Conditions
017
ABN-POWER
Unplanned Reactor Power Change
016
OI-07
Training Expectations
015
OI-09
Operations Standards and Expectations
077
SOP-CR-
MOVEMENT
Control Rod Movement
003
SOP-FWH-
SHUTDOWN
Extraction Steam and Heater Vents/Drains System Shutdown
004
SOP-RRC-FLOW-
Reactor Power Change with RRC Flow Controllers - Quick
Card
005
TDI-06
Simulator Management
21
Corrective Action
Documents
Action Requests
(ARs)
390944, 404026, 406546
Procedures
1.5.11
016
OSP-LPCS/IST-
Q702
LPCS System Operability Test
044
SYS-4-22
014
Work Orders
2117856, 02118311, 02118312, 02118313, 02117856,
2123922, 02131741, 02131742, 02131745, 02153301,
2153302
Corrective Action
Documents
Action Requests
(ARs)
406705, 406799, 407060, 393083, 398408, 407136, 407139,
407333, 407430, 407463, 407479, 407510, 407481
Drawings
M507-1
Flow Diagram Circulating Water System Turbine Generator
BLDG & Yard
178
Miscellaneous
High Risk Work Plan to Install Gag Device on CW-V-2C
000
High Risk Work Plan for Work Orders 02112977, 02158041,
and 02161630
05/19/2020
Procedures
1.3.76
Integrated Risk Management
060
1.3.76
Integrated Risk Management
059
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
1.3.83
Protected Equipment Program
031
1.3.86
Online Fire Risk Management
005
RCIC Isolation on Low Steam Supply Pressure - Channels B
& D - CFT/CC
005
TSP-DG3-B502
HPCS Diesel Generator DG3 Load Testing
25
Work Orders
2126770, 02121810, 02112977, 02158041, 02161630,
2085269, 02120123, 02163244
Calculations
6.08.01-SII-6
Calculation for Transformer Yard Electrical Manholes
001
Corrective Action
Documents
Action Requests
(ARs)
304266, 304289, 381023, 405330, 406119
Miscellaneous
5059SCREEN-14-
0063
Screening for Temporary Concrete Deadmen Will be Placed
on Top of Class 1 Electrical Manholes E10, E11, and E15
03/12/2014
AD-14-0339
Applicability Determination for Missing Bolts on Outer Covers
for Class 1 Electrical Manholes E10, E11, and E15
000
Columbia Generating Station, docket No. 50-397 Licensee
Event Report No. 2014003-0
05/12/2014
Procedures
SWP-CAP-01
Corrective Action Program
041
Work Orders
2124766
Calculations
ME-02-08-10
Flow Restrictor Chocked Flow Calculation
2
Engineering
Changes
RWCU-MO-1 & 4 Modifications (Actuator Replacements)
2
Perform Repairs to RHR-V-8 Based on EN inspections and
Results of EPRI MOV PPM Calculations Which Predicted a
TYPE 1 Error
000
RHR-MO-4A Gear Change for RHR-V-4A
000
LDCN-19045
Safety Relief Valve (SRV) Overpressure Analysis Basis at 25
%RTP
000
Miscellaneous
10.25.187A
Motor Control Center Starter Maintenance - NLI Starters
2
10.25.48
Testing Molded Case Circuit Breakers
016
50.59EVAL-18-
0001
Changing Methodology to GOTHIC 8.1 for RWCU HELB
Analysis
000
29SCREEN-19-
0106
RHR-MO-4A Gear Change for RHR-V-4A
000
5059EVAL-17-
Approve Use of GOTHIC for Analysis of Certain High Energy
000
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
0003
Line Breaks
5059SCREEN-16-
0012
Main Steam Line Flow Restrictor Chocked Flow
000
5059SCREEN-17-
0034
RWCU-MO-1 & 4 Modifications (Actuator Replacements)
000
5059SCREEN-19-
0110
Major Leak from Turbine Building Oil System
000
5059SCREEN-19-
0118
ABN-FLOODING
000
5059SCREEN-19-
0130
EC 16816, Replace the valve wedge and change the gear
ratio in RHR-V-8
000
5059SCREEN-19-
0135
LDCN-19-045
000
999-00,214
5600 Series Motor Control Center Cubicles Instruction
Manual
2
LS-19-0233
Procedure 5.6.1, SBO/ELAP, Revision 030
000
LS-20-0074
Procedure 5.6.2, Station Blackout (SBO) and Extended Loss
of AC Power ELAP Attachments, Revision 015
000
River Bend Station, Unit 1 - Issuance of Amendment RE: High
Energy Line Break Analysis
04/20/2004
Procedures
5.6.1
SBO/ELAP
030
5.6.2
Station Blackout (SBO) and Extended Loss of AC Power
ELAP Attachments
015
ABN-FLOODING
Flooding
2
ENG-DES-50
Interface Procedure for IP-ENG-001
2
IP-ENG-001
Standard Engineering Process
001
Major Leak from
Turbine Building
Oil Systems
000
PPM 1.3.76
Integrated Risk Management
049
PPM 3.2.1
Normal Plant Shutdown
088
SWP-LIC-02
Licensing Basis Impact Determinations
015
SWP-PRO-02
Preparation, Review, Approval and Distribution of Procedures 050
Engineering
266
Alternate Hold Down Detail for Manholes E-MH-E10, E-MH-
001
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Changes
E11, and E-MH-E15
13650
Calc 6.08.01-SII-6 Rev 0 - Modification to Tornado Holddown
Bolting for E-MH-E10, E-MH-E11, and E-MH-E15 Manhole
Covers
000
212
TMOD for Placing Concrete Blocks on Manhole Covers E-
MH-E11/E-MH-E15
000
Procedures
SWP-CM-02
Temporary Configuration Changes
003
Work Orders
2124766, 02153631
Corrective Action
Documents
Action Requests
(ARs)
406566, 406584, 406795, 406900, 406969, 407121, 407133,
407258, 407544, 407555, 407962
Engineering
Changes
17870
FP-P-2B Replacement
000
Procedures
15.1.3
FP-P-110 Operability Test
009
15.1.6
FP-P-2B Operability Test
014
15.4.8
Fire Protection System Functional Test
24
Seismic System Channel Check
2
Seismic System Channel Functional Test
001
Seismic System Channel Calibration
2
LPCS Fill Verification
015
OSP-LPCS/IST-
Q702
LPCS System Operability Test
044
Standby Gas Treatment System A Operability
018
OSP-SGT/IST-
Q701
SGT Valve Operability (System A)
010
SOP-OG-LU
Offgas System Lineup
001
SOP-RWCU-OPS
Reactor Water Cleanup System Operations
013
Work Orders
2159994, 02128013, 02128194, 02131742, 02131745,
2151690, 02153301, 02153302, 02131510, 02131511,
2131513, 02124025, 02146082, 02138843, 02107662,
2122123, 02046143, 02146952, 02160512
Corrective Action
Documents
Action Requests
(ARs)
403221, 405472, 406406
Miscellaneous
IST-4
Inservice Testing Program Plan Fourth Ten-year Inspection
Interval
003
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
1.5.1
Surveillance Testing Program
041
1.5.19
Surveillance Frequency Control Program
001
OSP-CCH/IST-
M702
Control Room Emergency Chiller System B Operability
044
Control Rod SCRAM Accumulator Verification
008
SWP-IST-01
ASME Inservice Testing
003
Work Orders
2150623, 02131655, 02150840
71151
Corrective Action
Documents
Action Requests
(ARs)
399463, 399557
Miscellaneous
Operations Logs April 1, 2019 - April 30, 2020
05/19/2020
Columbia Generating Station, Docket No. 50-397 Licensee
Event Report No. 2019-001-00
11/25/2019
Corrective Action
Documents
Action Requests
(ARs)
178017, 186054, 316044, 391432, 391991, 404225, 405176,
405183, 316044, 353763, 355428, 357897, 359747, 359748,
361492, 363946, 378928, 389577, 404225, 403173, 390327,
391189, 391430, 392724, 392965, 394214, 394942, 395529,
395904, 398063, 398301, 398350, 402101, 402572, 402886,
403574, 405059, 405297, 405723, 406670, 407030, 407276,
407805
Procedures
10.25.68
RRC-IMD-ASD1A/1 and RRC-IMD-ASD1A/2 Induction Motor
Drive Software Settings and Self-Test
000
DES-2-9
Technical Evaluations
039
GBP-CAP-03
Trending Program
001
SOP-RRC-START
Reactor Recirculation, System Start
21
SWP-CAP-01
Corrective Action Program
016, 041
SWP-SEC-03
Security Responsibilities of Site Personnel
030
SYS-2-18
Life Cycle Management
001, 005
TM-01
Trending Manual
003
Work Orders
2158380, 02158041, 02158042, 02161630, 29153498
Corrective Action
Documents
Action Requests
(ARs)
407465
Procedures
OI-34
Notifications
039
OI-36
NRC Notifications
009