IR 05000397/2020001

Integrated Inspection Report 05000397/2020001

ML20114E347
Person / Time
Site:	Columbia
Issue date:	04/23/2020
From:	Jeffrey Josey NRC/RGN-IV/DRP/RPB-A
To:	Sawatzke B Energy Northwest
References
IR 2020001
Download: ML20114E347 (22)

Text

April 23, 2020

SUBJECT:

COLUMBIA GENERATING STATION - INTEGRATED INSPECTION REPORT 05000397/2020001

Dear Mr. Sawatzke:

On March 31, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Columbia Generating Station. On April 9, 2020, the NRC inspectors discussed the results of this inspection with Mr. W. Grover 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 involved a violation of NRC requirements. 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 the 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 cross-cutting aspect assignment 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: NPF-21 Report Number: 05000397/2020001 Enterprise Identifier: I-2020-001-0011 Licensee: Energy Northwest Facility: Columbia Generating Station Location: Richland, WA Inspection Dates: January 1 to March 31, 2020 Inspectors: G. Kolcum, Senior Resident Inspector L. Merker, Resident Inspector R. Alexander, Senior Emergency Preparedness Inspector 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

Standby Service Water Low Flow for Room Cooler Cornerstone Significance Cross-Cutting Report Aspect Section Mitigating Green [H.11] - 71111.15 Systems NCV 05000397/2020001-01 Challenge the Open/Closed Unknown The inspectors reviewed a self-revealed, Green, non-cited violation of Technical Specification 5.4.1.a, for the licensees failure to perform maintenance in accordance with documented procedures. Specifically, on January 8, 2020, during the performance of required flushing and flow restoration following maintenance under Work Order 0213980 for a safety-related room cooler for a 480 V motor control center, the standby service water valve was positioned incorrectly, contrary to Procedure OSP-SW-M101, Standby Service Water Loop A Valve Position Verification, Revision 41, which states to not exceed seven turns closed. When standby service water pump A was started on January 12, 2020, a low flow alarm was received for the room cooler.

Additional Tracking Items

None.

PLANT STATUS

The reactor unit began the inspection period at rated thermal power. On January 14, 2020, plant power was reduced to 93 percent due to a failure on an adjustable speed drive. On January 16, 2020, plant power was reduced to 73 percent to recover the adjustable speed drive before returning to 100 percent.

On February 14, 2020, plant power was reduced to 39 percent due to a trip of reactor recirculation pump 1A. On February 15, 2020, the plant was stabilized at 48 percent power before reducing to 28 percent to attempt a restart of reactor recirculation pump 1A. On February 16, 2020, the plant was stabilized at 48 percent before reducing to 28 percent to attempt a second restart of reactor recirculation pump 1A. On February 17, 2020, the plant was stabilized at 48 percent. On February 18, 2020, the plant was reduced to 28 percent for a third attempt to restart reactor recirculation pump 1A before returning to 48 percent. On February 19, 2020, the plant was reduced to 29 percent to restart reactor recirculation pump 1A with modified control software settings before returning to 100 percent. On February 24, 2020, plant power was reduced to 98 percent due to a high level trip of feedwater heaters 4A and 4C. On February 25, 2020, plant power was lowered to 81 percent to recover feedwater heaters. Feedwater heaters 4A and C were recovered on February 26, 2020, and the unit returned to 100 percent power.

On March 6, 2020, plant power was reduced to 80 percent due to a high level trip of feedwater heater 1C with subsequent trips of feedwater heaters 2A, 2B, 2C, and 3C. On March 7, 2020, plant power was reduced to 75 percent for restoration of the feedwater heaters. On March 8, 2020, the reactor was returned to 100 percent power. On March 14, 2020, plant power was reduced to 78 percent to perform a control rod sequence exchange and bypass valve testing. Reactor power returned to 100 percent rated power on the same day where it remained at full power through 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.

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; and observed risk significant activities when warranted. In addition, resident and regional baseline inspections were evaluated to determine if all or portions 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 the cases where it was determined the objectives and requirements could not be performed remotely, management elected to postpone and reschedule the inspection to a later date.

71111.01 - Adverse Weather Protection

Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated the adequacy of the overall preparations to protect risk-significant systems from severe cold weather, snow, and wind advisory; week of January 13, 2020.

Impending Severe Weather Sample (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated the adequacy of the overall preparations to protect risk-significant systems from impending afternoon high wind warning on February 23, 2020.

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (5 Samples)

The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:

(1) standby service water system A on January 6, 2020

(2) diesel generator 3 following annual and 12-year system maintenance on February 6, 2020

(3) recirculation pump 1A startup on February 19, 2020

(4) reactor core isolation cooling system on March 11, 2020

(5) diesel generator 2 following maintenance on March 17, 2020

Complete Walkdown Sample (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated system configurations during a complete walkdown of the hardened containment vent system installed in accordance with NRC Order EA-13-109 on March 9, 2020. [Completion of this sample was in accordance with the guidance in Temporary Instruction 2515/193, with credit taken in IP

71111.04 - further

details are documented in Inspection Report 05000397/2020010, ADAMS Accession No. ML20085F489.]

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 R-7/1, residual heat removal pump 2C room, on January 23, 2020

(2) Fire Area RC-13/2, chiller room, on February 26, 2020

(3) Fire Area RC-11/1, heating, ventilation, and air conditioning equipment room A, on February 26, 2020

(4) Fire Area RC-12/2, heating, ventilation, and air conditioning equipment room B, on February 26, 2020

(5) Fire Area R-6/2, reactor core isolation cooling pump room, on March 11, 2020

71111.06 - Flood Protection Measures

Cable Degradation (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated cable submergence protection in the protected area, manholes E-MH-E10 and E-MH-E11, on March 26, 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 yellow risk for the standby service water system A pump run on January 8, 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 D) on February 27, 2020.

71111.12 - Maintenance Effectiveness

Maintenance Effectiveness (IP Section 03.01) (2 Samples)

The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:

(1) diesel generator 3 maintenance on January 31, 2020

(2) adjustable speed drive system following trip of reactor recirculation pump 1A on

February 19, 2020 Quality Control (IP Section 03.02) (1 Sample)

The inspectors evaluated the effectiveness of maintenance and quality control activities to ensure the following SSC remains capable of performing its intended function:

(1) diesel generator 3 maintenance on January 31, 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 standby service water system A maintenance, week of January 6, 2020

(2) yellow risk for diesel generator 3 maintenance on January 30, 2020

(3) yellow risk for a feedwater pump in idle during loss of recirculation pump 1A on February 19, 2020

(4) yellow risk for reactor core isolation cooling system maintenance on March 9, 2020

(5) yellow risk during diesel generator 2 pre-start checks (bar over) on March 19, 2020

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (4 Samples)

The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:

(1) valve issue in standby service water system A on January 8, 2020

(2) low standby service water system A flow on January 12, 2020

(3) main steam line D high flow switch found out of tolerance on February 21, 2020

(4) residual heat removal system B and C keepfill pump discovery of metal flakes in oil on March 18, 2020

71111.18 - Plant Modifications

Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02)

(3 Samples)

The inspectors evaluated the following temporary or permanent modifications:

(1) revision to correct Procedure SOP-DG-DSA, Diesel Starting Air Operations, to open diesel starting air cross connect valve during maintenance on February 26, 2020

(2) hardened containment vent system installed in accordance with NRC Order EA-13-109 on March 10, 2020. [Completion of this permanent modification sample was in accordance with the guidance in Temporary Instruction 2515/193, with credit taken in IP

71111.18 - further details are documented in Inspection

Report 05000397/2020010, ADAMS Accession No. ML20085F489.]

(3) replacement of obsolete pressure regulating assemblies in the diesel generator 3 starting air system on March 23, 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) standby service water system A pump on January 8, 2020

(2) control room emergency chiller A on January 22, 2020

(3) diesel generator 3 annual and 12-year preventive maintenance on February 6, 2020

(4) standby liquid control system flow controller on February 18, 2020

(5) seismic circuit diagnostics on February 27, 2020

(6) main control room cooler 52A on March 13, 2020

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance tests:

Surveillance Tests (other) (IP Section 03.01)

(1) OSP-ELEC-M701, diesel generator 1 monthly operability, on January 8, 2020

(2) ISP-MS-B608, response time testing of reactor protection system channel B1 trip on main steam isolation valve closure signal, on February 5, 2020

(3) OSP-LPCS/IST-Q702, low pressure core spray system operability, on February 11, 2020

(4) SOP-APRM/LPRM-OPS, average power range monitoring and local power range monitoring system operability, on February 19, 2020

(5) OSP-ELEC-M702, diesel generator 2 monthly operability, on March 19, 2020

Inservice Testing (IP Section 03.01) (1 Sample)

(1) OSP-RHR/IST-Q702, residual heat removal system A operability, on

February 14, 2020 FLEX Testing (IP Section 03.02) (1 Sample)

(1) OSP-FLEX-A102, B5B pumper truck functionality, on February 27, 2020

71114.04 - Emergency Action Level and Emergency Plan Changes

Inspection Review (IP Section 02.01-02.03) (1 Sample)

(1) The inspectors evaluated the Columbia Generating Station Emergency Plan, Revision 67, on March 22, 2020. The licensee implemented Revision 67 on March 12, 2020, and submitted the revised emergency plan to the NRC on the same date. This evaluation does not constitute NRC approval.

71114.06 - Drill Evaluation

Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)

The inspectors evaluated:

(1) general emergency preparedness drill, Team D, on February 25, 2020

71114.08 - Exercise Evaluation Scenario Review

Inspection Review (IP Section 02.01 - 02.04) (1 Sample)

(1) The inspectors reviewed the licensee's preliminary exercise scenario, which was submitted to the NRC on January 21, 2020, for the exercise which was scheduled to occur at the end of March 2020. The inspectors discussed the preliminary scenario with Mr. S.M. Sullivan, Manager, Emergency Preparedness, and other members of the EP staff on February 19, 2020. The inspectors' review does not constitute NRC approval of the scenario. [Subsequent to the scenario discussion, due to events surrounding the COVID-19 public health crisis, the licensee and offsite response organizations postponed the scheduled biennial exercise to a date later in 2020.

However, the scenario has been retained and securely controlled, such that it may be utilized when the exercise is conducted later in 2020.]

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:

IE01: Unplanned Scrams per 7000 Critical Hours Sample (IP Section 02.01) ===

(1) (01/01/2019-12/31/2019)

IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02) (1 Sample)

(1) (01/01/2019-12/31/2019)

IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (1 Sample)

(1) (01/01/2019-12/31/2019)

71152 - Problem Identification and Resolution

Annual Follow-up of Selected Issues (IP Section 02.03) (1 Sample)

The inspectors reviewed the licensees implementation of its corrective action program related to the following issue:

(1) classification of safety-related components coded as run to maintenance per the maintenance rule on March 24, 2020

71153 - Follow-up of Events and Notices of Enforcement Discretion Personnel Performance (IP Section 03.03)

(1) The inspectors evaluated a failure on an adjustable speed drive, resultant reactor downpower to 93 percent, and the licensee's response on January 16, 2020.

(2) The inspectors evaluated a trip of reactor recirculation pump 1A, resultant reactor downpower to 39 percent, and the licensee's response on February 15,

INSPECTION RESULTS

Standby Service Water Low Flow for Room Cooler Cornerstone Significance Cross-Cutting Report Aspect Section Mitigating Green [H.11] - 71111.15 Systems NCV 05000397/2020001-01 Challenge the Open/Closed Unknown The inspectors reviewed a self-revealed, Green, non-cited violation of Technical Specification 5.4.1.a, for the licensees failure to perform maintenance in accordance with documented procedures. Specifically, on January 8, 2020, during the performance of required flushing and flow restoration following maintenance under Work Order (WO) 0213980 for a safety-related room cooler for a 480 V motor control center, the standby service water valve was positioned incorrectly, contrary to Procedure OSP-SW-M101, Standby Service Water Loop A Valve Position Verification, Revision 41, which states to not exceed seven turns closed. When standby service water pump A was started on January 12, 2020, a low flow alarm was received for the room cooler.

Description:

On January 8, 2020, during the performance of required flushing and flow restoration following maintenance under WO 0213980 for a safety-related room cooler for a 480 V motor control center, standby service water valve SW-V-115 was positioned incorrectly. Procedure OSP-SW-M101, Standby Service Water Loop A Valve Position Verification, Revision 41, requires in step 7.2.21.c to not to exceed 7 TURNS CLOSED. Operators contacted the control room and the shift manager gave permission to throttle the valve beyond seven turns, without reviewing the notes in OSP-SW-M101. The procedure was not annotated by the crew to document the deviation from step 7.2.21.c, and an action request was not initiated for engineering to evaluate the new condition. On January 12, 2020, service water pump A was started and a low flow alarm was received at 4 gpm. Procedure OSP-SW-M101 required 12-15 gpm. Procedure OSP-SW-M101 required a minimum operability flow of 10 gpm. Engineering conducted a review of calculation ME-02-92-43, Room Temperature Calculation for DG Building, Reactor Building, Radwaste Building and Service Water, Revision 13, and the basis for the 10 gpm. Engineering re-performed the analysis and determined that the value of 4 gpm provided sufficient margin for operability. Operations reviewed the procedure and determined the operability limits stated in the procedure are administrative limits and should be changed.

Corrective Actions: The licensees corrective actions included immediately declaring the 480 V motor control center room inoperable in accordance with Technical Specification 3.8.7.A when the 480 V motor control center room cooler low flow alarm was received. The licensee entered Procedure OSP-SW-C101, Service Water Loop A Heat Exchanger Flushing, Revision 0, to adjust flow. In approximately one and a half hours, the adjusted flow was re-tested and the 480 V motor control center was declared operable.

Corrective Action References: Action Request 403084

Performance Assessment:

Performance Deficiency: The licensees failure to perform maintenance in accordance with documented procedures 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 Mitigating Systems Cornerstone and adversely affected the cornerstone objective to ensure the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences. Specifically, on January 8, 2020, during the performance of required flushing and flow restoration following maintenance under WO 0213980 for a safety-related room cooler for a 480 V motor control center, the standby service water valve was positioned incorrectly, contrary to Procedure OSP-SW-M101, Standby Service Water Loop A Valve Position Verification, Revision 41, which states to not exceed seven turns closed. When standby service water pump A was started on January 12, 2020, a low flow alarm was received for the room cooler.

Significance: The inspectors assessed the significance of the finding using Appendix A, The Significance Determination Process (SDP) for Findings At-Power. The inspectors determined the finding was of very low safety significance (Green) because all of the screening questions were answered in the negative.

Cross-Cutting Aspect: H.11 - Challenge the Unknown: Individuals stop when faced with uncertain conditions. Risks are evaluated and managed before proceeding. This finding had a cross-cutting aspect in the area of human performance, challenge the unknown, in that the licensee did not stop when faced with uncertain conditions and evaluate and manage risks before proceeding. Specifically, the licensee did not challenge the fact that the procedure did not allow them to close the valve more than seven turns.

Enforcement:

Violation: Technical Specification 5.4.1.a requires, in part, that written procedures shall be established, implemented, and maintained covering the applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2. Section 9.a of Appendix A of Regulatory Guide 1.33, Revision 2, requires, in part, that maintenance that can affect the performance of safety-related equipment should be performed in accordance with documented instructions appropriate to the circumstances. The licensee established WO 0213980016 to implement Procedure OSP-SW-M101, Standby Service Water Loop A Valve Position Verification, Revision 41, to meet the Regulatory Guide 1.33 requirement. The notes preceding step 7.2.21.c of Procedure OSP-SW-M101 state, "The recommended throttled position for SW-V-115 is 6.5 to 6.75 turns closed. The expected flow indication on SW-FI-60 will remain off scale high after performing the next step. Further, step 7.2.21.c states, in part, "Slowly throttle closed SW-V-115...not to exceed 7 TURNS CLOSED."

Contrary to the above, on January 8, 2020, the licensee failed to perform maintenance in accordance with documented instructions appropriate to the circumstances. Specifically, on January 8, 2020, during the performance of required flushing and flow restoration following maintenance under WO 0213980 for a safety-related room cooler for a 480 V motor control center, standby service water valve SW-V-115 was positioned incorrectly in that it exceeded greater than seven turns closed, contrary to Procedure OSP-SW-M101, Standby Service Water Loop A Valve Position Verification, Revision 41. When standby service water pump A was started on January 12, 2020, a low flow alarm was received for the room cooler.

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 February 19, 2020, the inspectors presented the Emergency Preparedness exit briefing for Emergency Plan revision in-office inspection results to Mr. S. M. Sullivan, Manager, Emergency Preparedness, and other members of the licensee staff.

• On April 9, 2020, the inspectors presented the integrated inspection results to Mr. W Grover Hettel, Chief Nuclear Officer/Vice President Nuclear Generation, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.01 Procedures ABN-WIND Tornado/High Winds 032

SOP- Cold Weather Operations 034

COLDWEATHER-

OPS

71111.04 Drawings M512-1 Flow Diagram: Diesel Oil and Miscellaneous Systems 047

Diesel Generator Building

M587 General Arrangement Plan & Section Diesel Generator 040

Building

M778 Composite Piping Sections & Details Diesel Generator Bldg 040

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

Q701

SOP-DG-DCW Emergency Diesel Generator Jacket Water Cooling 014

SOP-DG-DSA Diesel Starting Air Operations 016

SOP-DG2-LU Emergency Diesel Generator (DIV 2) Valve and Power 007

Supply Lineup

SOP-DG2-START Emergency Diesel Generator (DIV 2) Start 032

SOP-DG2-STBY High Pressure Core Spray Diesel Generator Standby Lineup 019

SOP-DG3-LU High Pressure Core Spray Diesel Generator Valve and 009

Power Supply Lineup

SOP-DG3-START High Pressure Core Spray Diesel Generator Start 029

SOP-DG3-STBY High Pressure Core Spray Diesel Generator Standby Lineup 019

SOP-RCC- RCC System Startup 003

START

SOP-RCIC- RCIC Drain 004

DRAIN

SOP-RCIC-FILL RCIC Fill and Vent 019

SOP-RCIC- RCIC RPV Injection 010

INJECTION

SOP-RCIC- RCIC RPV Injection - Quick Card 008

INJECTION-QC

SOP-RCIC-LU RCIC Valve and Breaker Lineup 004

SOP-RCIC-OIL RCIC Turbine or Pump Oil Fill and Prime 010

Inspection Type Designation Description or Title Revision or

Procedure Date

SOP-RCIC- RCIC Shutdown 010

SHUTDOWN

SOP-RCIC- RCIC Start in Test Return Mode 006

START

SOP-RCIC-STBY Placing RCIC in Standby Status 012

SOP-RCIC- RCIC Suction Transfer 001

SUCTION

SOP-RCIC- RCIC Transfer to CST - CST Mode 001

TRANSFER-QC

SOP-RRC-ASD Reactor Recirculation ASD Operation 013

SOP-RRC-FLOW- Reactor Power Change with RRC Flow Controllers - Quick 005

QC Card

SOP-RRC- Reactor Recirculation Pump Restart - QC 000

RESTART-QC

SOP-RRC- Reactor Recirculation Single Loop Operation 014

SINGLELOOP

SOP-RRC- Reactor Recirculation System Start 021

START

Work Orders 02182368, 02066997, 02087948, 02136139, 02137881,

2140403, 02128068, 02126087

71111.05 Corrective Action Action Requests 403399

Documents (ARs)

Miscellaneous ISP 20-0010 Plant Ignition Source Permit for RHR-P-3, H3/4.7 01/22/2020

TCP 20-001 Transient Combustible Permit for RHR-C inside door R13 - 01/22/2020

H3/4.7

Procedures 1.3.10C Control of Combustibles 021

10.2.222 Seismic Storage Requirements for Transient Equipment 002

ISPM-2 Compressed Gases and Welding/Cutting 011

PFP-RB-422 Reactor 422 006

Work Orders 02157539

71111.06 Corrective Action Action Requests 381023, 405330

Documents (ARs)

Drawings E-822-1 Electrical Manholes Development and Details 004

E823-1 Underground Duct Banks Plans and Profiles 027

Inspection Type Designation Description or Title Revision or

Procedure Date

E824-2 Underground Duct Banks Plans and Profiles 008

Engineering 13650 Calc 6.08.01-SII-6 Rev 0 - Modification to Tornado 000

Changes Holddown Bolting for E-MH-E10, E-MH-E11, and E-MH-E15

Manhole Covers

Miscellaneous 19-0454 E-MH-E10 Manhole South of DG Building Barrier 03/24/2020

Impairment Permit

19-0455 E-MH-E11 30 East of Bldg 88 (north end) Building Barrier 03/24/2020

Impairment Permit

5059SCREEN-14- Temporary Concrete Deadmen will be Placed on Top of 000

0063 Class 1 Electrical Manholes E10, E11, and E15

Procedures 1.3.57 Barrier Impairment 038

Work Orders 02124766

71111.11Q Miscellaneous Crew D 4.0 Critique Summary LR002475 02/03/2020

LR002475 Operations Requalification Training Cycle 20-1 Evaluated 000

Scenario

Procedures 13.1.1 Classifying the Emergency 049

ABN- Earthquake 015

EARTHQUAKE

ABN-ROD Control Rod Faults 029

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

Q701

71111.12 Corrective Action Action Requests 373197, 403552, 403553, 403554, 403557, 403559,

Documents (ARs) 403630, 403631, 403664, 403688, 403732, 404225,

404235, 404245, 404246, 404256, 404257, 404259,

404283, 404303, 404305, 404306

Procedures 10.20.18 Division 3 Diesel Generator Engine 2/4/6/12/18 Year 007

Preventive Maintenance

10.25.68 RRC-IMD-ASD1A/1 and RRC-IMD-ASD1A/2 Induction 000

Motor Drive Software Settings and Self-test

MI-1.6 Peer Verification Program 010

OSP-RRC-C103 RRC Pump Start Temperature and Loop Flow Verification 013

QAP-ASU-07 Peer Verification Program Planning 005

SOP-RRC-ASD Reactor Recirculation ASD Operation 013

Inspection Type Designation Description or Title Revision or

Procedure Date

SOP-RRC-FLOW- Reactor Power Change with RRC Flow Controllers - Quick 005

QC Card

SOP-RRC- Reactor Recirculation Pump Restart - QC 000

RESTART-QC

SOP-RRC- Reactor Recirculation Single Loop Operation 014

SINGLELOOP

SOP-RRC- Reactor Recirculation System Start 021

START

SWP-INS-01 Quality Control Inspection and Peer Verification 008

Work Orders 02123657, 02124798, 02126087, 02126091, 02126096,

2126105, 02136348, 02153813, 02126093, 02131506,

2158380, 02158476

71111.13 Corrective Action Action Requests 403631, 403667

Documents (ARs)

Miscellaneous Fire Tour Log Sheet 01/28/2020

Fire Tour Log Sheet 01/29/2020

Procedures 1.3.10 Plant Fire Protection Program Implementation 034

1.3.76 Integrated Risk Management 059

1.3.83 Protected Equipment Program 031

1.3.85 On-Line Fire Risk Management 005

1.3.86 Online Fire Risk Management 005

PFP-RW-467 Radwaste 467 005

SOP-DG2-START Emergency Diesel Generator (DIV 2) Start 032

SOP-RFT-START Reactor Feedwater Turbine System Start 022

71111.15 Calculations E/I-02-92-1063 Calculation for Setting Range Determination for Instrument 001

Loop MS Differential Pressure Indicating Switch 8A

Corrective Action Action Requests 402942, 301084, 344042, 402397, 403325, 403084,

Documents (ARs) 403090, 397067, 403302

Engineering 14942, 14973

Changes

Miscellaneous 02E22-13,15 Durco Mark 3 Sealed Metallic Pumps 000

AED-SPC-311 Design Basis Document Residual Heat Removal System 018

Procedures 1.3.66 Operability and Functionality Evaluation 034

Inspection Type Designation Description or Title Revision or

Procedure Date

ISP-MS-Q928 Main Steam Line HI Flow Channel D - CFT/CC 013

OSP-SW-M101 Standby Service Water Loop A Valve Position Verification 041

Work Orders 02147076, 02156728, 02156735, 02157606, 29153247,

2107044, 02128633, 02157539,

71111.18 Corrective Action Action Requests 369318, 399463, 399557, 403249, 402490, 403302,

Documents (ARs) 403465, 403668, 404607

Drawings A990F07001 Schematic Diagram Air Start System 002

M512-1 Flow Diagram Diesel Oil & Miscellaneous Systems Diesel 047

Generator Building

M512-1 Flow Diagram Diesel Oil and Miscellaneous Systems Diesel 047

Generator Building

Engineering 12174 One DSA Air Receiver for All Four Air Start Motors of 000

Changes HPCS-DG

15024 Replace Obsolete DG3 DSA-PCV-1C and DSA-PCV-2C 000

Pressure Regulating Assemblies with OEM Recommended

Replacement Assemblies

Miscellaneous DSA-PCV-2C Instrument Master Data Sheet 001, 004

DSA-PCV-1C Instrument Master Data Sheet 001, 004

2E22-07,54,1 HPCS Diesel Generator and Battery and Installation 010

AD-09-1584; This is an applicability determination review for procedure 000

SOP-DG-DSA SOP-DG-DSA change to Revision 5.

Rev. 5

ME-02-94-44 Diesel Starting Air System Capabilities to Meet the Number 002, 003

of Starts Requirement

TM-2076 Design Basis for DSA Air Receiver 1C and 2C to Provide 000

Three Starts

Procedures 1.3.29 Locked Valve Checklist 085

10.27.63 PM/CAL Test - Pressure Control Valves with Integrated 011

Pilot Regulators - HPCS DG

8.3.290 DG3 Air Receiver Capacity Test 000

DES-2-10 Minor Alteration 032

DES-5-4 Design and Safety Assessment 003

SOP-DG-DSA Diesel Starting Air Operations 016

Work Orders 02141293

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.19 Corrective Action Action Requests 403221, 403232, 403894, 403898, 403953, 403958,

Documents (ARs) 402961, 403265

Procedures 10.2.10 Fastener Torque and Tensioning 028

ISP-SEIS-M202 Seismic System Channel Check 002

MI-1.8 Conduct of Maintenance 073

OSP-CCH/IST- Control Room Emergency Chiller System A Operability 046

M701

OSP-ELEC-S703 HPCS Diesel Generator Semi-Annual Operability Test 064

OSP-INST-M201 Accident Monitoring Instrumentation Channel 015

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

Q701

Work Orders 02182368, 02066997, 02087948, 02136139, 02137881,

2140403, 02128068, 02110369, 02114830, 02131992,

2145234, 02126087, 02123665, 02153813, 02156676,

2120386, 02113572, 00402961

71111.22 Calculations 02E12-03,6 Residual Heat Removal System Design Specification Data 009

Sheet

C106-92-03.01 Calculation for LPCS Motor Operated Valve Design Basis 002

Review

C106-92-03.03 Calculation for RHR Motor Operated Valve Design Basis 005

Review

Corrective Action Action Requests 403669, 404026, 404079, 404030, 404031, 404062

Documents (ARs)

Drawings EWD-15E-010 Electrical Wiring Diagram Reactor Protection System Trip 019

System B Relays Sheet 1

M520 Flow Diagram: HPCS and LPCS Systems Reactor Building 105

Miscellaneous IST-4 Inservice Testing Program Plan Fourth Ten-Year Inspection 003

Interval

Procedures ISP-MS-B608 Main Steam Isolation Valve Closure Trip Channel B1 - RTT 006

OSP-ELEC-M701 Diesel Generator 1 - Monthly Operability Test 060

OSP-ELEC-M702 Diesel Generator 2 - Monthly Operability Test 065

OSP-FLEX-A102 B.5.B Pumper Truck Flex Functional Test 001

OSP-LPCS/IST- LPCS System Operability Test 044

Q702

Inspection Type Designation Description or Title Revision or

Procedure Date

OSP-RHR/IST- RHR Loop A Operability Test 052

Q702

SOP- APRM/LPRM Operations 001

APRM/LPRM-

OPS

SOP- APRM/LPRM Operations 001

APRM/LPRM-

OPS

TSP-LPCS/ISI- ASME LPCS System Leakage Test 004

G801

Work Orders 02124819, 02069917, 02123922, 02128884, 02146431,

2121561, 02123933, 02153138, 02120416, 02131553

71114.04 Miscellaneous LDCN-19-022 Licensing Document Change Notice: EP-01, Rev. 67 02/20/2020

Emergency Plan (including 10 CFR 50.54(q) Screening and

Evaluation)

Procedures EPI-16 §50.54(Q) Change Evaluation 16

SWP-LIC-02 Licensing Basis Impact Determinations 15

71151 Corrective Action Action Requests 380257, 387594, 389079, 396522

Documents (ARs)

Miscellaneous Operations Logs 01/01/2019-

2/31/2019

Procedures 1.10.10 Consolidated Data Entry Process Description 008

71152 Corrective Action Action Requests 009870, 280168, 394573, 394458, 394052, 393723,

Documents (ARs) 402394, 402459, 402996, 403007, 403293, 403915,

403947, 405244

Procedures 1.5.13 Preventive Maintenance Optimization Living Program 042

SYS-4-22 Maintenance Rule Program 014

71153 Corrective Action Action Requests 403173, 403256, 403257, 404225

Documents (ARs)

Miscellaneous Reactivity Control Plan January 2020 ASD Channel 01/15/2020

Recovery

Reactivity Control Plan February 2020 RRC-P-1A Recovery 02/15/2020

and Ascension to 100% CTP

Procedures 3.2.6 Power Maneuvering 013

Inspection Type Designation Description or Title Revision or

Procedure Date

ABN-CORE Unplanned Core Operating Conditions 017

ABN-FWH- Feedwater Heater High Level Trip 007

HILEVEL/TRIP

ABN-OG Off-Gas System Trouble 004

ABN-POWER Unplanned Reactor Power Change 016

ABN-RRC-LOSS Loss of Reactor Recirculation Flow 016

SOP-RRC-ASD Reactor Recirculation ASD Operation 013

Work Orders 29153498

19