IR 05000397/2019003
| ML19303C894 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 10/30/2019 |
| From: | Jeffrey Josey NRC/RGN-IV/DRP/RPB-A |
| To: | Sawatzke B Energy Northwest |
| References | |
| IR 2019003 | |
| Download: ML19303C894 (21) | |
Text
October 30, 2019
SUBJECT:
COLUMBIA GENERATING STATION - INTEGRATED INSPECTION REPORT 05000397/2019003
Dear Mr. Sawatzke:
On September 30, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Columbia Generating Station. On October 10, 2019, the NRC inspectors discussed the results of this inspection with Mr. David Brown, Plant General Manager, 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. One Severity Level IV violation without an associated finding is documented in this report. We are treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2 of the Enforcement Policy.
If you contest the violation or significance or severity of the violation documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN:
Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region IV; the Director, Office of Enforcement; and the NRC Resident Inspector at Columbia Generating Station.
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 10 CFR 2.390, Public Inspections, Exe mptions, Requests for Withholding.
Sincerely,
/RA/
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-2019-003-0010
Licensee:
Energy Northwest
Facility:
Columbia Generating Station
Location:
Richland, WA
Inspection Dates:
July 1, 2019 to September 30, 2019
Inspectors:
G. Kolcum, Senior Resident Inspector
L. Merker, Resident Inspector
R. Alexander, Senior Project Engineer
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 Procedure Results in Open Current Transformer Cornerstone Significance Cross-Cutting Aspect Report Section Initiating Events Green FIN 05000397/2019003-01 Open/Closed None (NPP)71111.18 The inspectors reviewed a self-revealed, Green finding for the licensee's failure to follow plant Procedure 10.25.19, "Termination and Splicing Instruction," that ensures wire and cable terminations, splices, and insulation are properly controlled. Specifically, on February 16, 2015, the licensee did not re-terminate the current transformer wires for the low voltage winding temperature circuit in main transformer 3 per the panel wiring termination instructions. This resulted in the current transformer operating in an open circuit, arcing, overheating the terminals, and damaging the feed through, which allowed transformer oil to leak outside the transformer.
Announcement of an NRC Inspector's Presence by Station Personnel Cornerstone Significance Cross-Cutting Aspect Report Section Not Applicable NCV 05000397/2019003-02 Open/Closed Not Applicable 71152 The inspectors identified a Severity Level IV, non-cited violation (NCV) of 10 CFR 50.70(b)(4), associated with the licensees failure to ensure the arrival and presence of an NRC inspector, who had been properly authorized facility access, was not announced or otherwise communicated by its employees or contractors to other persons at the facility unless specifically requested by the NRC inspector. Specifically, a licensee employee entered the protected area search train ahead of the NRC resident inspector and informed the nearby security officers that the NRC resident inspector was about to enter the area without being requested to do so by the inspector; this impacted the NRCs ability to perform its regulatory oversight function to perform unannounced inspections.
Additional Tracking Items
Type Issue Number Title Report Section Status LER 05000397/2017007-00 Valve Closure Results in Momentary Increase in Secondary Containment Pressure 71153 Closed
PLANT STATUS
The reactor unit began the inspection period at rated thermal power. On July 7, 2019, plant power was reduced to 72 percent due to high level trip of feedwater heater 1C with subsequent trips of feedwater heaters 2A, 2B, 2C, and 3C. On July 9, 2019, the reactor was returned to 100 percent power. On September 13, 2019, plant power was reduced to 95 percent and then returned to 100 percent due to condensate pump minimum flow maintenance. On September 21, 2019, plant power was reduced to 73 percent to perform control rod sequence exchange and bypass valve testing. Reactor power returned to 100 percent rated power on the same day and stayed there 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 plant status activities described in IMC 2515, Appendix D, Plant Status, and conducted routine reviews using IP 71152, Problem Identification and Resolution. 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 03.02) (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 August 2, 2019:
- Standby service water A
- Standby service water B
- Division 1 switchgear
- Division 2 switchgear
71111.04Q - 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)high pressure core spray system standby lineup following system maintenance on July 26, 2019 (2)ac power panel 7AF lineup on August 7, 2019 (3)ac power panel 7A lineup on August 7, 2019 (4)high pressure core spray system standby lineup during planned reactor core isolation cooling maintenance on September 10, 2019
71111.04S - Equipment Alignment
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations during a complete walkdown of the standby service water system A on August 16, 2019.
71111.05Q - Fire Protection
Quarterly Inspection (IP Section 03.01) (5 Samples)
The inspectors evaluated fire protection program implementation in the following selected areas:
- (1) Fire Area DG-4/1, diesel generator 1 diesel fuel oil storage tank access room, on July 17, 2019
- (2) Fire Area DG-5/2, diesel generator 2 diesel fuel oil storage tank access room, on July 17, 2019
- (3) Fire Area DG-6/#, high pressure core spray diesel fuel oil storage tank access room, on July 17, 2019
- (4) Fire Area SW-1/1, standby service water pump house 1A, on July 18, 2019
- (5) Fire Area SW-2/2, standby service water pump house 1B, on July 18, 2019
71111.06 - Flood Protection Measures
Inspection Activities - Internal Flooding (IP Section 02.02a.) (1 Sample)
The inspectors evaluated internal flooding mitigation protections in the:
- (1) emergency core cooling system pump rooms on August 16, 2019
71111.07A - Heat Sink Performance
Annual Review (IP Section 02.01) (1 Sample)
The inspectors evaluated readiness and performance of:
(1)reactor building closed cooling water system heat exchangers, RCC-HX-1A and RCC-HX-1B, on August 23, 2019
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (2 Samples)
- (1) The inspectors observed and evaluated licensed operator performance in the control room during main turbine vibration changes on August 14, 2019.
- (2) The inspectors observed and evaluated licensed operator performance in the control room during the opening of the turbine miscellaneous drain valves on high differential temperature on August 30, 2019.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated the licensed operator requalification evaluated scenario (Crew B) on August 5, 2019.
71111.12 - Maintenance Effectiveness
Routine Maintenance Effectiveness Inspection (IP Section 02.01) (1 Sample)
The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:
(1)high pressure core spray system on August 9, 2019
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated the risk assessments for the following planned and emergent work activities:
(1)yellow risk for high pressure core spray system maintenance on July 25, 2019 (2)yellow risk for diesel generator 1 barover on August 7, 2019 (3)yellow risk for reactor core isolation cooling system maintenance on September 10, 2019 (4)yellow risk for standby service water system B maintenance on September 17, 2019
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 02.02) (3 Samples)
The inspectors evaluated the following operability determinations and functionality assessments:
(1)electrical power panel E-PP-7AF low voltage on A phase on August 26, 2019 (2)diesel generator 3 mixed air fan failure on August 28, 2019 (3)diesel generator 3 starting air on September 25, 2019
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (2 Samples)
The inspectors evaluated the following temporary or permanent modifications:
(1)main condenser air removal suction valve permanently left in the open position on August 1, 2019 (2)jumper installation across main transformer 3 low voltage winding temperature circuit on August 29, 2019
71111.19 - Post-Maintenance Testing
Post Maintenance Test Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated the following post maintenance tests:
(1)standby liquid control regulator on July 4, 2019 (2)diesel generator 3 standby service water pump on July 23, 2019 (3)high pressure core spray system on July 26, 2019 (4)diesel generator 4 annual and biannual preventative maintenance on August 14, 2019 (5)electrical power panel E-PP-7AF following transformer replacement on August 27, 2019
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
- (1) ISP-HPCS-X302, high pressure core spray minimum flow instrument calibration, on July 30, 2019
- (2) OSP-ELEC-W102, electrical distribution subsystem breaker alignment and power, on August 2, 2019
- (3) OSP-SW/IST-Q701, standby service water loop A operability, on August 6, 2019
- (4) OSP-LPCS-M101, low pressure core spray fill verification, on August 7, 2019
- (5) TSP-DG2-B502, diesel generator 2 load testing, on August 26, 2019
Inservice Testing (IP Section 03.01) (1 Sample)
- (1) OSP-LPCS/IST-Q702, low pressure core spray system quarterly operability, on August 7, 2019
FLEX Testing (IP Section 03.02) (1 Sample)
- (1) OSP-FLEX-Q705, diesel generator 5 quarterly operability, on July 10, 2019
71114.06 - Drill Evaluation
Drill/Training Evolution Observation (IP Section 03.02) (2 Samples)
The inspectors evaluated:
- (1) Team B Emergency Response Organization (ERO) drill on July 16, 2019.
Specifically, the inspectors evaluated the ERO's drill performance in the control room simulator, emergency operations facility, alternate emergency operations facility, and joint information center and assessed the overall drill critique results.
- (2) Team A Emergency Response Organization (ERO) drill on September 10, 2019.
Specifically, the inspectors evaluated the ERO's drill performance in the control room simulator and emergency operations facility and assessed the overall drill critique results.
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
MS06: Emergency AC Power Systems (IP Section 02.05)===
(1)
(07/01/2018 - 06/30/2019)
MS07: High Pressure Injection Systems (IP Section 02.06) (1 Sample)
(1) (07/01/2018 - 06/30/2019)
MS08: Heat Removal Systems (IP Section 02.07) (1 Sample)
(1) (07/01/2018 - 06/30/2019)
MS09: Residual Heat Removal Systems (IP Section 02.08) (1 Sample)
(1) (07/01/2018 - 06/30/2019)
MS10: Cooling Water Support Systems (IP Section 02.09) (1 Sample)
(1) (07/01/2018 - 06/30/2019)
71152 - Problem Identification and Resolution
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)announcement of an NRC inspector's presence by station personnel on August 28, 2019 (2)evaluation of the March 22, 2019, standby service water system B pump discharge valve failure to open, on September 6, 2019
71153 - Followup of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)
The inspectors evaluated the following licensee event reports (LERs):
- (1) LER 05000397/2017-007-00, Valve Closure Results in Momentary Increase in Secondary Containment Pressure (ADAMS accession: ML17334B440)
The inspectors determined that the cause of the condition described in the LER was not reasonably within the licensees ability to foresee and correct. No performance deficiency or violation of NRC requirements was identified.
Personnel Performance (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated the high level trip of feedwater heater 1C with subsequent trips of feedwater heaters 2A, 2B, 2C, and 3C; resultant reactor downpower to 72 percent; and the licensees response on July 7,
INSPECTION RESULTS
Failure to Follow Procedure Results in Open Current Transformer Cornerstone Significance Cross-Cutting Aspect Report Section Initiating Events
Green FIN 05000397/2019003-01 Open/Closed
None (NPP)71111.18 The inspectors reviewed a self-revealed, Green finding for the licensee's failure to follow plant Procedure 10.25.19, "Termination and Splicing Instruction," that ensures wire and cable terminations, splices, and insulation are properly controlled. Specifically, on February 16, 2015, the licensee did not re-terminate the current transformer wires for the low voltage winding temperature circuit in main transformer 3 per the panel wiring termination instructions. This resulted in the current transformer operating in an open circuit, arcing, overheating the terminals, and damaging the feed through, which allowed transformer oil to leak outside the transformer.
Description:
On May 14, 2019, during a transformer inspection, the licensee discovered evidence of arcing inside the current transformer well of main transformer 3 and oil leaking to the ground. Upon further inspection, the licensee discovered the low voltage winding temperature current transformer wires were not connected to the current transformer terminal block, resulting in an open current transformer. The current transformer provides an input signal to the control logic for starting the main transformer 3 cooling fans to reduce the temperature of the transformer during normal operation.
Plant Procedure 10.25.19, "Termination and Splicing Instruction," ensures that wire and cable terminations, splices, and insulation are properly controlled. Step 7.11.2 states, in part, to ensure all determ/re-term(s) [sic], splice installations, panel wiring terminations, and cable terminations are properly completed. Attachment 9.10, "Determ/Reterm Data Sheet," of Procedure 10.25.19 provides further guidance regarding determination and re-termination data sheets. Steps 2.6 and 2.6.1 of Attachment 9.10 state, in part, that the performer lands all required leads using Determ/Reterm Data Sheet, and after leads are landed, the verifier checks the leads.
The licensee last determinated the current transformer wires on February 10, 2015. Work Order 02051297 provided instructions to terminate the wires to reassemble main transformer 3. Step 4.4 of Work Order 02051297 states, in part, to terminate cables per attached panel wiring termination instructions. This step was completed on February 18, 2015; however, contrary to Step 7.11.2 of Procedure 10.25.19, not all determ/reterm(s) were properly completed. Specifically, on February 16, 2015, the licensee did not re-terminate the current transformer wires for the low voltage winding temperature circuit in main transformer 3 per the panel wiring termination instructions. This resulted in the current transformer operating in an open circuit, arcing, overheating the terminals, and damaging the feed through, which allowed transformer oil to leak outside the transformer.
Corrective Actions: The licensee performed an extent of condition evaluation and verified all other terminations on main transformers 1, 2, and 3 were configured as expected. The licensee reconfigured the low voltage winding temperature circuit to put the transformer in a safe condition, modified the winding temperature alarm, and put the transformer cooling in manual until the low voltage winding temperature circuit can be repaired in the next Refueling Outage R25.
Corrective Action References: Action Request 393438
Performance Assessment:
Performance Deficiency: The failure to follow plant Procedure 10.25.19, "Termination and Splicing Instruction," that ensures wire and cable terminations, splices, and insulation are properly controlled, was a performance deficiency.
Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the configuration control 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, on February 16, 2015, the licensee did not re-terminate the current transformer wires for the low voltage winding temperature circuit in main transformer 3 per the panel wiring termination instructions. This resulted in the current transformer operating in an open circuit, arcing, overheating the terminals, and damaging the feed through, which allowed transformer oil to leak outside the transformer.
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 the 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.
Announcement of an NRC Inspector's Presence by Station Personnel Cornerstone Severity Cross-Cutting Aspect Report Section Not Applicable Severity Level IV NCV 05000397/2019003-02 Open/Closed
Not Applicable 71152 The inspectors identified a Severity Level IV, non-cited violation (NCV)of 10 CFR 50.70(b)(4), associated with the licensees failure to ensure the arrival and presence of an NRC inspector, who had been properly authorized facility access, was not announced or otherwise communicated by its employees or contractors to other persons at the facility unless specifically requested by the NRC inspector. Specifically, a licensee employee entered the protected area search train ahead of the NRC resident inspector and informed the nearby security officers that the NRC resident inspector was about to enter the area without being requested to do so by the inspector; this impacted the NRCs ability to perform its regulatory oversight function to perform unannounced inspections.
Description:
On July 30, 2019, the resident inspector was walking towards the protected area search train when the inspector was passed by a licensee employee. The resident inspector observed the individual enter the search train and overheard the individual inform the nearby security officers that the NRC resident inspector was on the way and about to enter the area.
The resident inspector had not asked the individual to announce their presence to the security officers.
Procedure SWP-SEC-04, "Access of NRC Personnel," describes the methods used by the licensee to control access of NRC personnel. Step 2.1.6 of Procedure SWP-SEC-04 states that a licensee shall ensure that the arrival and presence of an NRC inspector, who has been properly granted authorized facility access, is not announced or otherwise communicated by its employees or contractors to other persons at the facility unless specifically requested by an NRC inspector. The inspector noted that this encounter was in violation of Procedure SWP-SEC-04 and constituted a minor performance deficiency.
Corrective Actions: The licensee entered this issue into the corrective action program and provided coaching to the employee. The licensee also issued a site announcement regarding the incident explaining that announcing the presence of an NRC inspector is highly inappropriate and contrary to the requirements of 10 CFR 50.70.
Corrective Action References: Action Request 397451
Performance Assessment:
The inspectors determined this violation was associated with a minor performance deficiency.
Enforcement:
The ROPs significance determination process does not specifically consider the regulatory process impact in its assessment of licensee performance. Therefore, it is necessary to address this violation which impedes the NRCs ability to regulate using traditional enforcement to adequately deter non-compliance.
Severity: The inspectors evaluated the finding and determined the violation was of very low safety significance, was not repetitive or willful, and was entered into the corrective action program. Therefore, this violation is being treated as a Severity Level IV NCV, consistent with the NRC Enforcement Policy.
Violation: Title 10 CFR 50.70(b)(4), requires, in part, that the licensee shall ensure that the arrival and presence of an NRC inspector, who has been properly authorized facility access, is not announced or otherwise communicated by its employees or contractors to other persons at the facility unless specifically requested by the NRC inspector.
Contrary to the above, on July 30, 2019, the licensee failed to ensure that the arrival and presence of an NRC inspector, who had been properly authorized facility access, was not announced or otherwise communicated by its employees or contractors to other persons at the facility unless specifically requested by the NRC inspector. Specifically, a licensee employee entered the protected area search train ahead of the NRC resident inspector and informed the nearby security officers that the NRC resident inspector was about to enter the area without being requested to do so by the inspector; this impacted the NRCs ability to perform its regulatory oversight function to perform unannounced inspections.
Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On October 10, 2019, the inspectors presented the integrated inspection results to Mr. David Brown, Plant General Manager, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Calculations
ME-02-92-41
Calculation for Ultimate Heat Sink Analysis
007
Calculations
ME-02-92-43
Room Temperature Calculation for DG Building, Reactor
Building, Radwaste Building and Service Water
013
Corrective Action
Documents
Action Requests
(ARs)
381176, 382754, 385692, 391357, 392706, 393813,
397509, 397579, 397587, 397588
Procedures
SOP-
HOTWEATHER-
Hot Weather Operations
006
Procedures
SOP-SW-SPRAY
Standby Service Water Spray Header Operations
000
Procedures
SOP-
WARMWEATHER-
Warm Weather Operations
016
Work Orders
2114379, 02109629/02109631
71111.04Q Drawings
M520
HPCS and LPCS Systems Reactor Building Flow Diagram
105
71111.04Q Procedures
HPCS Flow Rate Low (Minimum Flow) - CC
008
71111.04Q Procedures
Electrical Distribution Subsystem Breaker Alignment and
Power Availability Verification
031
71111.04Q Procedures
HPCS Valve Lineup
005
71111.04Q Procedures
SOP-ELEC-AC-LU
AC Electrical Distribution System Breaker Lineup
074
71111.04Q Procedures
SOP-HPCS-LU
HPCS Valve and Breaker Lineup
004
71111.04Q Procedures
SOP-HPCS-STBY
Placing HPCS in Standby Status
004
Miscellaneous
FSAR Chapter 9.2
Procedures
SOP-
HOTWEATHER-
Hot Weather Operations
006
Procedures
SOP-SW-DRAIN
Standby Service Water Drain
008
Procedures
SOP-SW-FILL
Standby Service Water System Fill
2, 007
Procedures
SOP-SW-LU
Standby Service Water System Valve & Breaker Lineup
010
Procedures
SOP-SW-OPS
Standby Service Water Operations
2, 009
Procedures
SOP-SW-
SHUTDOWN
Standby Service Water System Shutdown
2
Procedures
SOP-SW-SPRAY
Standby Service Water Spray Header Operations
000, 003
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
SOP-SW-START
Standby Service Water System Start
008
Procedures
SOP-SW-STBY
Placing Standby Service Water in Standby Status
2, 003
Procedures
SOP-SWCF-LU
Service Water Chemical Addition System Valve Line-up
000
71111.05Q Corrective Action
Documents
Resulting from
Inspection
Action Requests
(ARs)
397011, 397014, 397016
71111.05Q Fire Plans
PFP-DG-
BUILDING
Power Block Pre-Fire Plan: Diesel Generator Building
004
71111.05Q Fire Plans
PFP-MN-XFMR-
YD-MISC
Pre-Fire Plan: Standby Service Water Pumphouses 1A &
1B
006
71111.05Q Procedures
PPM 15.1.2
Fire Door Operability Surveillance
27
71111.05Q Procedures
PPM 15.3.17
Fire Door Operability - Semiannual, Annual, Biennial
010
Procedures
10.2.251
Installation of Temporary Flood Barriers
000, 001
Procedures
15.4.6
Essential Fire Rated Penetration Seal and Essential Fire
and Flood Barrier Operability Inspection
010
Procedures
ABN-FLOODING
Flooding
2, 020
Procedures
ECCS Pump Room Flood Level - Calibration
003
Corrective Action
Documents
Action Requests
(ARs)
338360, 364270, 364288
Drawings
M508-1
Plant Service Water System All Buildings Flow Diagram
29
Miscellaneous
10.07.70
Calculation for TSW and RCC Heat Exchanger Steady Flow 000
Miscellaneous
ME-02-18-09
Tube Plugging Limits for RCC Heat Exchangers
000
Miscellaneous
ME-02-91-28
Calculation for Heat Exchanger Effectiveness Evaluation
000
Miscellaneous
SD000196
Reactor Closed Cooling Water
011
Miscellaneous
SPC 350
Plant Service Water (TSW) System Design Basis Document 006
Procedures
ABN-RCC
Loss of RCC
006
Procedures
SOP-RCC-OPS
RCC System Operations
007
Procedures
SYS-4-22
014
Work Orders
2074046, 02019119, 02031264, 01165204
71111.11Q Corrective Action
Documents
Action Requests
(ARs)
397827, 398564, 398613, 398624, 398786
71111.11Q Engineering
17964
Temporary Modification to Keep MD-V-87 Open and
000, 001
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Changes
Jumper Relay TG-RLY-TR/SMT Closed
71111.11Q Miscellaneous
Crew B Evaluated
Scenario Cycle 19-
4.0 Critique Summary
000
71111.11Q Miscellaneous
LR002465
Cycle 19-3 Evaluated Scenario
000
71111.11Q Procedures
1.19.3A
Vibration Monitoring
003
71111.11Q Procedures
13.1.1
Classifying the Emergency
049
71111.11Q Procedures
13.1.1A
Classifying the Emergency Technical Bases
034
71111.11Q Procedures
5.1.1
RPV Control
2
71111.11Q Procedures
5.1.2
26
71111.11Q Procedures
5.1.3
Emergency RPV Depressurization
2
71111.11Q Procedures
5.2.1
Primary Containment Control
28
71111.11Q Procedures
5.5.1
Overriding ECCS Valve Logic to Allow Throttling RPV
Injection
006
71111.11Q Procedures
5.5.25
Alternate Injection Using the SLC System
006
71111.11Q Procedures
ABN-
Earthquake
015
71111.11Q Procedures
ABN-FLOODING
Flooding
20
71111.11Q Procedures
ABN-LEAKAGE
Reactor Coolant Leakage
007
71111.11Q Procedures
OI-69
Time Critical Operator Actions
013
71111.11Q Procedures
SOP-MT-START
Main Turbine Start
29
71111.11Q Work Orders
2149788
Corrective Action
Documents
Action Requests
(ARs)
249204, 374239, 368837, 376172, 389755, 397093,
397124, 397167, 397179, 397181, 397223, 397279
Work Orders
2116085, 02116951, 02116991, 02118186, 02118456,
2131311, 02136227
Corrective Action
Documents
Action Requests
(ARs)
397227, 397294
Miscellaneous
19-0020
Fire Prevention Evaluation for RB 471 SW General Floor
Area
07/22/2019
Miscellaneous
19-0021
Fire Prevention Evaluation for RB 522 General Floor Area;
RMS 410-412; E-IR-P027
07/22/2019
Miscellaneous
19-0022
Fire Prevention Evaluation for R548; RM 512; RM 516
07/22/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
19-0023
Fire Prevention Evaluation for RW437 C106; Behind SHLD
Wall; C130/131
07/22/2019
Miscellaneous
19-0024
Fire Prevention Evaluation for Division 2 RM C213; Division
RM C224
07/22/2019
Miscellaneous
19-0025
Fire Prevention Evaluation for RW 525 RM 502; RM C503,
RM C510
07/22/2019
Miscellaneous
19-0026
Fire Prevention Evaluation for SM-7 SWGR RM C208
07/22/2019
Procedures
1.3.10
Plant Fire Protection Program Implementation
034
Procedures
1.3.76
Integrated Risk Management
055, 056
Procedures
1.3.83
Protected Equipment Program
030
Procedures
1.3.85
On-line Fire Risk Management
005
Procedures
ABN-SW
Service Water Trouble
015
Procedures
SOP-RCIC-
STANDBY
Placing RCIC in Standby Status
2
Work Orders
2147259, 02111466, 02118499
Corrective Action
Documents
Action Requests
(ARs)
397437, 397507, 397548, 397608, 395246, 398540,
393270, 360595, 399533, 399463, 369316, 369318
Drawings
EWD-46E-240
AC Electrical Distribution System Power Panel E-PP-7AF
Electrical Wiring Diagram
019
Procedures
Electrical Distribution Subsystem Breaker Alignment and
Power Availability Verification
031
Procedures
SOP-ELEC-AC-LU
AC Electrical Distribution System Breaker Lineup
074
Work Orders
2136940, 02137174, 02137381, 02137558, 02147724
Corrective Action
Documents
Action Requests
(ARs)
370326, 371242, 397439, 397553, 397557, 393438,
395744
Drawings
CVI 215-09, 7
Wafer Valve 24 in General Arrangement with Cylinder
2
Drawings
D-ARV1GAG-488
Mechanical Gag for AR-V-1
000
Drawings
EWD-46E-283
AC Electrical Distribution System Main Transformer E-TR-
M3 Power Supply and Auxiliary CKTS
015
Drawings
M511
Gas & Air Removal System Flow Diagram
058
Engineering
Changes
16670
Bypass AR-SPV-1/1 to Open AR-V-1 and Keep It Open
2
Engineering
Changes
17007
AR-V-1 Permanent Gag Open
001
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Engineering
Changes
17761
Install Jumper Across M3 LV Temperature CT
000
Procedures
10.25.19
Termination and Splicing Instruction
26
Procedures
3.1.6C
Instrument Rack Valve Lineup Turbine Generator Building
441' Elevation
010
Work Orders
2118726, 02125129, 02051297, 02115677, 02115678,
2115679, 02144461
Corrective Action
Documents
Action Requests
(ARs)
397093, 397165, 397279, 381813, 397437
Drawings
EWD-46E-240
AC Electrical Distribution System Power Panel E-PP-7AF
Electrical Wiring Diagram
019
Procedures
Electrical Distribution Subsystem Breaker Alignment and
Power Availability Verification
031
Procedures
Procedures
OSP-HPCS/IST-
Q701
HPCS System Operability Test
058
Procedures
Procedures
OSP-SW/IST-
Q703
Procedures
SOP-ELEC-AC-LU
AC Electrical Distribution System Breaker Lineup
074
Work Orders
2116085, 02116951, 02118186, 02118456, 02136227,
2138600, 02117111, 02117108, 02117109, 02126089,
2115248, 02147724
Corrective Action
Documents
Action Requests
(ARs)
2512, 325768, 368884, 388014, 391335, 398380,
398388, 398402, 398403, 398405, 398408, 398410
Drawings
M520
HPCS and LPCS Systems Flow Diagram
105
Miscellaneous
18-0428
E-IR-P024 Barrier Impairment Permit
07/22/2019
Miscellaneous
E/I-02-91-1060
Calculation for Setpoint Range and Allowable Value
Determination for Instrument Loop HPCS Flow Indicating
Switch 6
001
Miscellaneous
E/I-02-92-04
Calculation for Flow Calibration Curve Verification for HPCS
Flow Element 7 and Flow Transmitter 5 and Flow Indicating
Switch 6
000
Miscellaneous
EC QMR 13763
HELB Barrier Impairment for P001, P005, P018, P021,
004
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
P026, and P027
Miscellaneous
HPCS-FIS-6
Instrument Master Data Sheet
2
Procedures
1.5.1
Surveillance Testing Program
040
Procedures
1.5.19
Surveillance Frequency Control Program
000
Procedures
HPCS Flow Rate Low (Minimum Flow) -- CC
008
Procedures
Electrical Distribution Subsystem Breaker Alignment and
Power Availability Verification
031
Procedures
Diesel Generator 5 Quarterly Surveillance
000
Procedures
LPCS Fill Verification
015
Procedures
OSP-LPCS/IST-
Q702
LPCS System Operability Test
044
Procedures
OSP-SW/IST-
Q701
Standby Service Water Loop A Operability
2
Procedures
SOP-LPCS-STBY
Placing LPCS in Standby Status
2
Procedures
TSP-DG2-B502
Standby Diesel Generator DG2 Load Testing
24
Work Orders
2136320, 02106811, 02118313, 02113216, 021137715,
213659901
Corrective Action
Documents
Action Requests
(ARs)
395491, 396909, 396911, 397283
Miscellaneous
Columbia Generating Station Classification Notification
Forms for July 2019 ERO Drill
07/16/2019
Miscellaneous
Team B - ERO Drill July 2019: Drill Scenario Timeline
07/16/2019
Miscellaneous
After Action Report
/ Improvement
Plan
Columbia Generating Station ERO Team B Drill Report
(July 16, 2019)
08/06/2019
Procedures
PPM 13.1.1
Classifying the Emergency
049
71151
Miscellaneous
MSPI Indicator Margin Remaining In Green Report
07/18/2019
71151
Miscellaneous
MSPI Derivation Report: Emergency AC Power System
07/18/2019
71151
Miscellaneous
MSPI Derivation Report: High Pressure Injection System
07/18/2019
71151
Miscellaneous
MSPI Derivation Report: Heat Removal System
07/18/2019
71151
Miscellaneous
MSPI Derivation Report: Residual Heat Removal System
07/18/2019
71151
Miscellaneous
MSPI Derivation Report: Cooling Water System
07/18/2019
71151
Miscellaneous
MSPI-01-BD-0001
Mitigating System Performance Index (MSPI) Basis
21
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Document
71151
Procedures
1.10.10
Consolidated Data Entry Process Description
008
71151
Procedures
SYS-4-34
PSA Configuration Control
007
Corrective Action
Documents
Action Requests
(ARs)
391347, 391334, 391352, 397451, 391337, 391347,
391352, 398152
Miscellaneous
ACEMAN Thumbs Down Submission
08/01/2019
Procedures
10.25.105
Motor Control Center and Switchgear Maintenance
036
Procedures
10.25.13A
4.16KV Vacuum Breaker Maintenance with Stored Energy
Mechanism
20
Procedures
ABN-BKR-FAULT
Failure of MOC Switch Activation for Safety Related
Breakers
2
Procedures
ABN-SW
Service Water Trouble
015
Procedures
GBP-LIC-08
Preparation and Conduct of NRC Inspections
004
Procedures
SWP-SEC-04
Access of
NRC Personnel
006
Work Orders
2140678
Corrective Action
Documents
Action Requests
(ARs)
2103, 372134, 396522
Miscellaneous
Operations Log: July 6 - July 7, 2019
07/07/2019
Procedures
ABN-FWH-
HILEVEL/TRIP
Feedwater Heater High Level Trip
007
Procedures
ABN-POWER
Unplanned Reactor Power Change
016
Procedures
Electrical Distribution Subsystem Breaker Alignment and
Power Availability Verification
031
Work Orders
2119476, 02010762, 29150355