IR 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:
Report Number:
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
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 Aspect Report Section Mitigating Systems Green NCV 05000397/2020001-01 Open/Closed
[H.11] -
Challenge the Unknown 71111.15 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.
REACTOR SAFETY
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 Aspect Report Section Mitigating Systems Green NCV 05000397/2020001-01 Open/Closed
[H.11] -
Challenge the Unknown 71111.15 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
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
ABN-WIND
Tornado/High Winds
2
SOP-
COLDWEATHER-
Cold Weather Operations
034
Drawings
M512-1
Flow Diagram: Diesel Oil and Miscellaneous Systems
Diesel Generator Building
047
M587
General Arrangement Plan & Section Diesel Generator
Building
040
M778
Composite Piping Sections & Details Diesel Generator Bldg
040
Procedures
OSP-SW/IST-
Q701
Standby Service Water Loop A Operability
2
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
Supply Lineup
007
SOP-DG2-START
Emergency Diesel Generator (DIV 2) Start
2
SOP-DG2-STBY
High Pressure Core Spray Diesel Generator Standby Lineup 019
SOP-DG3-LU
High Pressure Core Spray Diesel Generator Valve and
Power Supply Lineup
009
SOP-DG3-START
High Pressure Core Spray Diesel Generator Start
29
SOP-DG3-STBY
High Pressure Core Spray Diesel Generator Standby Lineup 019
SOP-RCC-
START
RCC System Startup
003
SOP-RCIC-
DRAIN
RCIC Drain
004
SOP-RCIC-FILL
RCIC Fill and Vent
019
SOP-RCIC-
INJECTION
010
SOP-RCIC-
INJECTION-QC
RCIC RPV Injection - Quick Card
008
SOP-RCIC-LU
RCIC Valve and Breaker Lineup
004
SOP-RCIC-OIL
RCIC Turbine or Pump Oil Fill and Prime
010
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
SOP-RCIC-
SHUTDOWN
RCIC Shutdown
010
SOP-RCIC-
START
RCIC Start in Test Return Mode
006
SOP-RCIC-STBY
Placing RCIC in Standby Status
2
SOP-RCIC-
SUCTION
RCIC Suction Transfer
001
SOP-RCIC-
TRANSFER-QC
RCIC Transfer to CST - CST Mode
001
SOP-RRC-ASD
Reactor Recirculation ASD Operation
013
SOP-RRC-FLOW-
Reactor Power Change with RRC Flow Controllers - Quick
Card
005
SOP-RRC-
RESTART-QC
Reactor Recirculation Pump Restart - QC
000
SOP-RRC-
SINGLELOOP
Reactor Recirculation Single Loop Operation
014
SOP-RRC-
START
Reactor Recirculation System Start
21
Work Orders
2182368, 02066997, 02087948, 02136139, 02137881,
2140403, 02128068, 02126087
Corrective Action
Documents
Action Requests
(ARs)
403399
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 -
H3/4.7
01/22/2020
Procedures
1.3.10C
Control of Combustibles
21
10.2.222
Seismic Storage Requirements for Transient Equipment
2
ISPM-2
Compressed Gases and Welding/Cutting
011
Reactor 422
006
Work Orders
2157539
Corrective Action
Documents
Action Requests
(ARs)
381023, 405330
Drawings
E-822-1
Electrical Manholes Development and Details
004
E823-1
Underground Duct Banks Plans and Profiles
27
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
E824-2
Underground Duct Banks Plans and Profiles
008
Engineering
Changes
13650
Calc 6.08.01-SII-6 Rev 0 - Modification to Tornado
Holddown Bolting for E-MH-E10, E-MH-E11, and E-MH-E15
Manhole Covers
000
Miscellaneous
19-0454
E-MH-E10 Manhole South of DG Building Barrier
Impairment Permit
03/24/2020
19-0455
E-MH-E11 30 East of Bldg 88 (north end) Building Barrier
Impairment Permit
03/24/2020
5059SCREEN-14-
0063
Temporary Concrete Deadmen will be Placed on Top of
Class 1 Electrical Manholes E10, E11, and E15
000
Procedures
1.3.57
Barrier Impairment
038
Work Orders
2124766
71111.11Q Miscellaneous
Crew D 4.0 Critique Summary LR002475
2/03/2020
LR002475
Operations Requalification Training Cycle 20-1 Evaluated
Scenario
000
Procedures
13.1.1
Classifying the Emergency
049
ABN-
Earthquake
015
ABN-ROD
Control Rod Faults
29
OSP-SW/IST-
Q701
Standby Service Water Loop A Operability
2
Corrective Action
Documents
Action Requests
(ARs)
373197, 403552, 403553, 403554, 403557, 403559,
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
Preventive Maintenance
007
10.25.68
RRC-IMD-ASD1A/1 and RRC-IMD-ASD1A/2 Induction
Motor Drive Software Settings and Self-test
000
MI-1.6
Peer Verification Program
010
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
Procedure
Type
Designation
Description or Title
Revision or
Date
SOP-RRC-FLOW-
Reactor Power Change with RRC Flow Controllers - Quick
Card
005
SOP-RRC-
RESTART-QC
Reactor Recirculation Pump Restart - QC
000
SOP-RRC-
SINGLELOOP
Reactor Recirculation Single Loop Operation
014
SOP-RRC-
START
Reactor Recirculation System Start
21
SWP-INS-01
Quality Control Inspection and Peer Verification
008
Work Orders
2123657, 02124798, 02126087, 02126091, 02126096,
2126105, 02136348, 02153813, 02126093, 02131506,
2158380, 02158476
Corrective Action
Documents
Action Requests
(ARs)
403631, 403667
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
Radwaste 467
005
SOP-DG2-START
Emergency Diesel Generator (DIV 2) Start
2
SOP-RFT-START
Reactor Feedwater Turbine System Start
2
Calculations
E/I-02-92-1063
Calculation for Setting Range Determination for Instrument
Loop MS Differential Pressure Indicating Switch 8A
001
Corrective Action
Documents
Action Requests
(ARs)
2942, 301084, 344042, 402397, 403325, 403084,
403090, 397067, 403302
Engineering
Changes
14942, 14973
Miscellaneous
2E22-13,15
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
Procedure
Type
Designation
Description or Title
Revision or
Date
Main Steam Line HI Flow Channel D - CFT/CC
013
Standby Service Water Loop A Valve Position Verification
041
Work Orders
2147076, 02156728, 02156735, 02157606, 29153247,
2107044, 02128633, 02157539,
Corrective Action
Documents
Action Requests
(ARs)
369318, 399463, 399557, 403249, 402490, 403302,
403465, 403668, 404607
Drawings
A990F07001
Schematic Diagram Air Start System
2
M512-1
Flow Diagram Diesel Oil & Miscellaneous Systems Diesel
Generator Building
047
M512-1
Flow Diagram Diesel Oil and Miscellaneous Systems Diesel
Generator Building
047
Engineering
Changes
2174
One DSA Air Receiver for All Four Air Start Motors of
HPCS-DG
000
15024
Replace Obsolete DG3 DSA-PCV-1C and DSA-PCV-2C
Pressure Regulating Assemblies with OEM Recommended
Replacement Assemblies
000
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;
SOP-DG-DSA
Rev. 5
This is an applicability determination review for procedure
SOP-DG-DSA change to Revision 5.
000
ME-02-94-44
Diesel Starting Air System Capabilities to Meet the Number
of Starts Requirement
2, 003
TM-2076
Design Basis for DSA Air Receiver 1C and 2C to Provide
Three Starts
000
Procedures
1.3.29
Locked Valve Checklist
085
10.27.63
PM/CAL Test - Pressure Control Valves with Integrated
011
8.3.290
DG3 Air Receiver Capacity Test
000
DES-2-10
Minor Alteration
2
DES-5-4
Design and Safety Assessment
003
SOP-DG-DSA
Diesel Starting Air Operations
016
Work Orders
2141293
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
Action Requests
(ARs)
403221, 403232, 403894, 403898, 403953, 403958,
2961, 403265
Procedures
10.2.10
Fastener Torque and Tensioning
28
Seismic System Channel Check
2
MI-1.8
Conduct of Maintenance
073
OSP-CCH/IST-
M701
Control Room Emergency Chiller System A Operability
046
HPCS Diesel Generator Semi-Annual Operability Test
064
Accident Monitoring Instrumentation Channel
015
OSP-SW/IST-
Q701
Standby Service Water Loop A Operability
2
Work Orders
2182368, 02066997, 02087948, 02136139, 02137881,
2140403, 02128068, 02110369, 02114830, 02131992,
2145234, 02126087, 02123665, 02153813, 02156676,
2120386, 02113572, 00402961
Calculations
2E12-03,6
Residual Heat Removal System Design Specification Data
Sheet
009
C106-92-03.01
Calculation for LPCS Motor Operated Valve Design Basis
Review
2
C106-92-03.03
Calculation for RHR Motor Operated Valve Design Basis
Review
005
Corrective Action
Documents
Action Requests
(ARs)
403669, 404026, 404079, 404030, 404031, 404062
Drawings
EWD-15E-010
Electrical Wiring Diagram Reactor Protection System Trip
System B Relays Sheet 1
019
M520
Flow Diagram: HPCS and LPCS Systems Reactor Building
105
Miscellaneous
IST-4
Inservice Testing Program Plan Fourth Ten-Year Inspection
Interval
003
Procedures
Main Steam Isolation Valve Closure Trip Channel B1 - RTT
006
Diesel Generator 1 - Monthly Operability Test
060
Diesel Generator 2 - Monthly Operability Test
065
B.5.B Pumper Truck Flex Functional Test
001
OSP-LPCS/IST-
Q702
LPCS System Operability Test
044
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
OSP-RHR/IST-
Q702
RHR Loop A Operability Test
2
SOP-
APRM/LPRM-
APRM/LPRM Operations
001
SOP-
APRM/LPRM-
APRM/LPRM Operations
001
TSP-LPCS/ISI-
G801
004
Work Orders
2124819, 02069917, 02123922, 02128884, 02146431,
2121561, 02123933, 02153138, 02120416, 02131553
Miscellaneous
LDCN-19-022
Licensing Document Change Notice: EP-01, Rev. 67
Emergency Plan (including 10 CFR 50.54(q) Screening and
Evaluation)
2/20/2020
Procedures
EPI-16
§50.54(Q) Change Evaluation
SWP-LIC-02
Licensing Basis Impact Determinations
71151
Corrective Action
Documents
Action Requests
(ARs)
380257, 387594, 389079, 396522
Miscellaneous
Operations Logs
01/01/2019-
2/31/2019
Procedures
1.10.10
Consolidated Data Entry Process Description
008
Corrective Action
Documents
Action Requests
(ARs)
009870, 280168, 394573, 394458, 394052, 393723,
2394, 402459, 402996, 403007, 403293, 403915,
403947, 405244
Procedures
1.5.13
Preventive Maintenance Optimization Living Program
2
SYS-4-22
014
Corrective Action
Documents
Action Requests
(ARs)
403173, 403256, 403257, 404225
Miscellaneous
Reactivity Control Plan January 2020 ASD Channel
Recovery
01/15/2020
Reactivity Control Plan February 2020 RRC-P-1A Recovery
and Ascension to 100% CTP
2/15/2020
Procedures
3.2.6
Power Maneuvering
013
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
ABN-CORE
Unplanned Core Operating Conditions
017
ABN-FWH-
HILEVEL/TRIP
Feedwater Heater High Level Trip
007
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