IR 05000397/2019003

Integrated Inspection Report 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

ber 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: NPF-21 Report Number: 05000397/2019003 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 Enclosure

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 Report Aspect Section Initiating Events Green None (NPP) 71111.18 FIN 05000397/2019003-01 Open/Closed 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 Report Aspect Section Not Applicable NCV 05000397/2019003-02 Not Applicable 71152 Open/Closed 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 71153 Closed Momentary Increase in Secondary Containment Pressure

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.

71111.01 - Adverse Weather Protection

Seasonal Extreme Weather Sample (IP Section 03.02)

(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)

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) 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)

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.)

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)

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)

=

(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)

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)

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)

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)

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)

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)

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)

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 Report Aspect Section Initiating Events Green None (NPP) 71111.18 FIN 05000397/2019003-01 Open/Closed 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 Report Aspect Section Not Severity Level IV Not 71152 Applicable NCV 05000397/2019003-02 Applicable Open/Closed 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 Type Designation Description or Title Revision or

Procedure Date

71111.01 Calculations ME-02-92-41 Calculation for Ultimate Heat Sink Analysis 007

71111.01 Calculations ME-02-92-43 Room Temperature Calculation for DG Building, Reactor 013

Building, Radwaste Building and Service Water

71111.01 Corrective Action Action Requests 381176, 382754, 385692, 391357, 392706, 393813,

Documents (ARs) 397509, 397579, 397587, 397588

71111.01 Procedures SOP- Hot Weather Operations 006

HOTWEATHER-

OPS

71111.01 Procedures SOP-SW-SPRAY Standby Service Water Spray Header Operations 000

71111.01 Procedures SOP- Warm Weather Operations 016

WARMWEATHER-

OPS

71111.01 Work Orders 02114379, 02109629/02109631

71111.04Q Drawings M520 HPCS and LPCS Systems Reactor Building Flow Diagram 105

71111.04Q Procedures ISP-HPCS-X302 HPCS Flow Rate Low (Minimum Flow) - CC 008

71111.04Q Procedures OSP-ELEC-W102 Electrical Distribution Subsystem Breaker Alignment and 031

Power Availability Verification

71111.04Q Procedures OSP-HPCS-M102 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

71111.04S Miscellaneous FSAR Chapter 9.2

71111.04S Procedures SOP- Hot Weather Operations 006

HOTWEATHER-

OPS

71111.04S Procedures SOP-SW-DRAIN Standby Service Water Drain 008

71111.04S Procedures SOP-SW-FILL Standby Service Water System Fill 002, 007

71111.04S Procedures SOP-SW-LU Standby Service Water System Valve & Breaker Lineup 010

71111.04S Procedures SOP-SW-OPS Standby Service Water Operations 002, 009

71111.04S Procedures SOP-SW- Standby Service Water System Shutdown 002

SHUTDOWN

71111.04S Procedures SOP-SW-SPRAY Standby Service Water Spray Header Operations 000, 003

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.04S Procedures SOP-SW-START Standby Service Water System Start 008

71111.04S Procedures SOP-SW-STBY Placing Standby Service Water in Standby Status 002, 003

71111.04S Procedures SOP-SWCF-LU Service Water Chemical Addition System Valve Line-up 000

71111.05Q Corrective Action Action Requests 397011, 397014, 397016

Documents (ARs)

Resulting from

Inspection

71111.05Q Fire Plans PFP-DG- Power Block Pre-Fire Plan: Diesel Generator Building 004

BUILDING

71111.05Q Fire Plans PFP-MN-XFMR- Pre-Fire Plan: Standby Service Water Pumphouses 1A & 006

YD-MISC 1B

71111.05Q Procedures PPM 15.1.2 Fire Door Operability Surveillance 027

71111.05Q Procedures PPM 15.3.17 Fire Door Operability - Semiannual, Annual, Biennial 010

71111.06 Procedures 10.2.251 Installation of Temporary Flood Barriers 000, 001

71111.06 Procedures 15.4.6 Essential Fire Rated Penetration Seal and Essential Fire 010

and Flood Barrier Operability Inspection

71111.06 Procedures ABN-FLOODING Flooding 002, 020

71111.06 Procedures ISP-FDR-X301 ECCS Pump Room Flood Level - Calibration 003

71111.07A Corrective Action Action Requests 338360, 364270, 364288

Documents (ARs)

71111.07A Drawings M508-1 Plant Service Water System All Buildings Flow Diagram 129

71111.07A Miscellaneous 10.07.70 Calculation for TSW and RCC Heat Exchanger Steady Flow 000

71111.07A Miscellaneous ME-02-18-09 Tube Plugging Limits for RCC Heat Exchangers 000

71111.07A Miscellaneous ME-02-91-28 Calculation for Heat Exchanger Effectiveness Evaluation 000

71111.07A Miscellaneous SD000196 Reactor Closed Cooling Water 011

71111.07A Miscellaneous SPC 350 Plant Service Water (TSW) System Design Basis Document 006

71111.07A Procedures ABN-RCC Loss of RCC 006

71111.07A Procedures SOP-RCC-OPS RCC System Operations 007

71111.07A Procedures SYS-4-22 Maintenance Rule Program 014

71111.07A Work Orders 02074046, 02019119, 02031264, 01165204

71111.11Q Corrective Action Action Requests 397827, 398564, 398613, 398624, 398786

Documents (ARs)

71111.11Q Engineering 17964 Temporary Modification to Keep MD-V-87 Open and 000, 001

Inspection Type Designation Description or Title Revision or

Procedure Date

Changes Jumper Relay TG-RLY-TR/SMT Closed

71111.11Q Miscellaneous Crew B Evaluated 4.0 Critique Summary 000

Scenario Cycle 19-

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 022

71111.11Q Procedures 5.1.2 RPV Control - ATWS 026

71111.11Q Procedures 5.1.3 Emergency RPV Depressurization 022

71111.11Q Procedures 5.2.1 Primary Containment Control 028

71111.11Q Procedures 5.5.1 Overriding ECCS Valve Logic to Allow Throttling RPV 006

Injection

71111.11Q Procedures 5.5.25 Alternate Injection Using the SLC System 006

71111.11Q Procedures ABN- Earthquake 015

EARTHQUAKE

71111.11Q Procedures ABN-FLOODING Flooding 020

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 029

71111.11Q Work Orders 02149788

71111.12 Corrective Action Action Requests 249204, 374239, 368837, 376172, 389755, 397093,

Documents (ARs) 397124, 397167, 397179, 397181, 397223, 397279

71111.12 Work Orders 02116085, 02116951, 02116991, 02118186, 02118456,

2131311, 02136227

71111.13 Corrective Action Action Requests 397227, 397294

Documents (ARs)

71111.13 Miscellaneous 19-0020 Fire Prevention Evaluation for RB 471 SW General Floor 07/22/2019

Area

71111.13 Miscellaneous 19-0021 Fire Prevention Evaluation for RB 522 General Floor Area; 07/22/2019

RMS 410-412; E-IR-P027

71111.13 Miscellaneous 19-0022 Fire Prevention Evaluation for R548; RM 512; RM 516 07/22/2019

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.13 Miscellaneous 19-0023 Fire Prevention Evaluation for RW437 C106; Behind SHLD 07/22/2019

Wall; C130/131

71111.13 Miscellaneous 19-0024 Fire Prevention Evaluation for Division 2 RM C213; Division 07/22/2019

RM C224

71111.13 Miscellaneous 19-0025 Fire Prevention Evaluation for RW 525 RM 502; RM C503, 07/22/2019

RM C510

71111.13 Miscellaneous 19-0026 Fire Prevention Evaluation for SM-7 SWGR RM C208 07/22/2019

71111.13 Procedures 1.3.10 Plant Fire Protection Program Implementation 034

71111.13 Procedures 1.3.76 Integrated Risk Management 055, 056

71111.13 Procedures 1.3.83 Protected Equipment Program 030

71111.13 Procedures 1.3.85 On-line Fire Risk Management 005

71111.13 Procedures ABN-SW Service Water Trouble 015

71111.13 Procedures SOP-RCIC- Placing RCIC in Standby Status 012

STANDBY

71111.13 Work Orders 02147259, 02111466, 02118499

71111.15 Corrective Action Action Requests 397437, 397507, 397548, 397608, 395246, 398540,

Documents (ARs) 393270, 360595, 399533, 399463, 369316, 369318

71111.15 Drawings EWD-46E-240 AC Electrical Distribution System Power Panel E-PP-7AF 019

Electrical Wiring Diagram

71111.15 Procedures OSP-ELEC-W102 Electrical Distribution Subsystem Breaker Alignment and 031

Power Availability Verification

71111.15 Procedures SOP-ELEC-AC-LU AC Electrical Distribution System Breaker Lineup 074

71111.15 Work Orders 02136940, 02137174, 02137381, 02137558, 02147724

71111.18 Corrective Action Action Requests 370326, 371242, 397439, 397553, 397557, 393438,

Documents (ARs) 395744

71111.18 Drawings CVI 215-09, 7 Wafer Valve 24 in General Arrangement with Cylinder 002

71111.18 Drawings D-ARV1GAG-488 Mechanical Gag for AR-V-1 000

71111.18 Drawings EWD-46E-283 AC Electrical Distribution System Main Transformer E-TR- 015

M3 Power Supply and Auxiliary CKTS

71111.18 Drawings M511 Gas & Air Removal System Flow Diagram 058

71111.18 Engineering 16670 Bypass AR-SPV-1/1 to Open AR-V-1 and Keep It Open 002

Changes

71111.18 Engineering 17007 AR-V-1 Permanent Gag Open 001

Changes

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.18 Engineering 17761 Install Jumper Across M3 LV Temperature CT 000

Changes

71111.18 Procedures 10.25.19 Termination and Splicing Instruction 026

71111.18 Procedures 3.1.6C Instrument Rack Valve Lineup Turbine Generator Building 010

441' Elevation

71111.18 Work Orders 02118726, 02125129, 02051297, 02115677, 02115678,

2115679, 02144461

71111.19 Corrective Action Action Requests 397093, 397165, 397279, 381813, 397437

Documents (ARs)

71111.19 Drawings EWD-46E-240 AC Electrical Distribution System Power Panel E-PP-7AF 019

Electrical Wiring Diagram

71111.19 Procedures OSP-ELEC-W102 Electrical Distribution Subsystem Breaker Alignment and 031

Power Availability Verification

71111.19 Procedures OSP-FLEX-M704

71111.19 Procedures OSP-HPCS/IST- HPCS System Operability Test 058

Q701

71111.19 Procedures OSP-INST-M101

71111.19 Procedures OSP-SW/IST-

Q703

71111.19 Procedures SOP-ELEC-AC-LU AC Electrical Distribution System Breaker Lineup 074

71111.19 Work Orders 02116085, 02116951, 02118186, 02118456, 02136227,

2138600, 02117111, 02117108, 02117109, 02126089,

2115248, 02147724

71111.22 Corrective Action Action Requests 322512, 325768, 368884, 388014, 391335, 398380,

Documents (ARs) 398388, 398402, 398403, 398405, 398408, 398410

71111.22 Drawings M520 HPCS and LPCS Systems Flow Diagram 105

71111.22 Miscellaneous 18-0428 E-IR-P024 Barrier Impairment Permit 07/22/2019

71111.22 Miscellaneous E/I-02-91-1060 Calculation for Setpoint Range and Allowable Value 001

Determination for Instrument Loop HPCS Flow Indicating

Switch 6

71111.22 Miscellaneous E/I-02-92-04 Calculation for Flow Calibration Curve Verification for HPCS 000

Flow Element 7 and Flow Transmitter 5 and Flow Indicating

Switch 6

71111.22 Miscellaneous EC QMR 13763 HELB Barrier Impairment for P001, P005, P018, P021, 004

Inspection Type Designation Description or Title Revision or

Procedure Date

P026, and P027

71111.22 Miscellaneous HPCS-FIS-6 Instrument Master Data Sheet 012

71111.22 Procedures 1.5.1 Surveillance Testing Program 040

71111.22 Procedures 1.5.19 Surveillance Frequency Control Program 000

71111.22 Procedures ISP-HPCS-X302 HPCS Flow Rate Low (Minimum Flow) -- CC 008

71111.22 Procedures OSP-ELEC-W102 Electrical Distribution Subsystem Breaker Alignment and 031

Power Availability Verification

71111.22 Procedures OSP-FLEX-Q705 Diesel Generator 5 Quarterly Surveillance 000

71111.22 Procedures OSP-LPCS-M101 LPCS Fill Verification 015

71111.22 Procedures OSP-LPCS/IST- LPCS System Operability Test 044

Q702

71111.22 Procedures OSP-SW/IST- Standby Service Water Loop A Operability 032

Q701

71111.22 Procedures SOP-LPCS-STBY Placing LPCS in Standby Status 002

71111.22 Procedures TSP-DG2-B502 Standby Diesel Generator DG2 Load Testing 024

71111.22 Work Orders 02136320, 02106811, 02118313, 02113216, 021137715,

213659901

71114.06 Corrective Action Action Requests 395491, 396909, 396911, 397283

Documents (ARs)

71114.06 Miscellaneous Columbia Generating Station Classification Notification 07/16/2019

Forms for July 2019 ERO Drill

71114.06 Miscellaneous Team B - ERO Drill July 2019: Drill Scenario Timeline 07/16/2019

71114.06 Miscellaneous After Action Report Columbia Generating Station ERO Team B Drill Report 08/06/2019

/ Improvement (July 16, 2019)

Plan

71114.06 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 021

Inspection Type Designation Description or Title Revision or

Procedure Date

Document

71151 Procedures 1.10.10 Consolidated Data Entry Process Description 008

71151 Procedures SYS-4-34 PSA Configuration Control 007

71152 Corrective Action Action Requests 391347, 391334, 391352, 397451, 391337, 391347,

Documents (ARs) 391352, 398152

71152 Miscellaneous ACEMAN Thumbs Down Submission 08/01/2019

71152 Procedures 10.25.105 Motor Control Center and Switchgear Maintenance 036

71152 Procedures 10.25.13A 4.16KV Vacuum Breaker Maintenance with Stored Energy 020

Mechanism

71152 Procedures ABN-BKR-FAULT Failure of MOC Switch Activation for Safety Related 002

Breakers

71152 Procedures ABN-SW Service Water Trouble 015

71152 Procedures GBP-LIC-08 Preparation and Conduct of NRC Inspections 004

71152 Procedures SWP-SEC-04 Access of

NRC Personnel

006

71152 Work Orders 02140678

71153 Corrective Action Action Requests 372103, 372134, 396522

Documents (ARs)

71153 Miscellaneous Operations Log: July 6 - July 7, 2019 07/07/2019

71153 Procedures ABN-FWH- Feedwater Heater High Level Trip 007

HILEVEL/TRIP

71153 Procedures ABN-POWER Unplanned Reactor Power Change 016

71153 Procedures OSP-ELEC-W102 Electrical Distribution Subsystem Breaker Alignment and 031

Power Availability Verification

71153 Work Orders 02119476, 02010762, 29150355

18