IR 05000346/2020001
| ML20139A017 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 05/15/2020 |
| From: | Billy Dickson NRC/RGN-III |
| To: | Bezilla M Energy Harbor Nuclear Corp |
| References | |
| IR 2020001 | |
| Download: ML20139A017 (23) | |
Text
May 15, 2020
SUBJECT:
DAVIS-BESSE NUCLEAR POWER STATION - INTEGRATED INSPECTION REPORT 05000346/2020001
Dear Mr. Bezilla:
On March 31, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Davis-Besse Nuclear Power Station. On April 20, 2020, the NRC inspectors discussed the results of this inspection with you and other members of your staff. The results of this inspection are documented in the enclosed report.
No findings or violations of more than minor significance were identified during this inspection.
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,
/RA/
Billy C. Dickson, Jr., Chief Branch 2 Division of Reactor Projects
Docket No. 05000346 License No. NPF-3
Enclosure:
As stated
Inspection Report
Docket Number:
05000346
License Number:
Report Number:
Enterprise Identifier: I-2020-001-0044
Licensee:
Energy Harbor Nuclear Corp.
Facility:
Davis-Besse Nuclear Power Station
Location:
Oak Harbor, OH
Inspection Dates:
January 01, 2020 to March 31, 2020
Inspectors:
S. Bell, Health Physicist
E. Fernandez, Reactor Inspector
J. Harvey, Resident Inspector
D. Mills, Senior Resident Inspector
C. Norton, Senior Resident Inspector
J. Park, Reactor Inspector
J. Rutkowski, Project Engineer
Approved By:
Billy C. Dickson, Jr., Chief
Branch 2
Division of Reactor Projects
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Davis-Besse Nuclear Power 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
No findings or violations of more than minor significance were identified.
Additional Tracking Items
None.
PLANT STATUS
The plant began the inspection period at rated thermal power. On January 16, 2020, the plant started coasting down with periodic power reductions. The licensee shut down the plant for the refueling outage on February 29, 2020. The plant remained shut down for 25 days. On March 24, 2020, the licensee started up the plant, but operators tripped the plant at very low power on March 25, 2020, due to a failed transformer fuse. The licensee restarted the plant on March 26, 2020, and the plant reached rated thermal power on March 30, 2020. The plant remained at or near full power for the rest of the inspection period.
On February 27, 2020, the licensees parent company successfully completed its Chapter 11 restructuring process and emerged from bankruptcy as Energy Harbor Nuclear Corp. The NRC Region III inspectors used flexibility in the baseline inspection program to assess the potential impact of the financial conditions on licensee performance. Through February 27, 2020, the inspectors applied additional focus to the following areas:
- (1) impact on regulatory required plant staffing,
- (2) corrective maintenance backlog,
- (3) changes to the planned maintenance schedule,
- (4) corrective action program implementation, and
- (5) reduction in outage scope, including risk-significant modifications. No concerns were identified.
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/readingrm/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. From January 1 - March 19, 2020, 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 portion of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In 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
71111.04 - 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) Decay heat/low pressure injection (DH/LPI) train 2 while DH/LPI train 1 was out of service for planned emergency core cooling system room cooler maintenance during the week ending January 11, 2020
- (2) Emergency diesel generator (EDG) train 2 while component cooling water train 1 was out of service for planned testing during the week ending February 1, 2020
- (3) High pressure injection train 1 while DH/LPI train 2 was out of service for planned maintenance and EDG 2 was out of service for planned testing during the week ending February 22, 2020
- (4) Decay heat/low pressure injection train 1 while DH/LPI train 2 was in operation during the planned reactor drain down during the week ending March 7, 2020
- (5) Decay heat/low pressure injection train 2 while defueled and credited as an alternate means of spent fuel pool cooling during the week ending March 14, 2020
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (3 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) Electrical penetration room 2, fire area DF, during the week ending February 8, 2020
- (2) East and southwest penetration areas of the annulus, fire areas A and AB, during the week ending March 21, 2020
- (3) High voltage switchgear room A, fire area S, during the week ending April 4, 2020
71111.08P - Inservice Inspection Activities (PWR) PWR Inservice Inspection Activities Sample (IP Section 03.01)
- (1) The inspectors verified the reactor coolant system boundary, steam generator tubes, reactor vessel internals, risk-significant piping system boundaries, and containment boundary were appropriately monitored for degradation and repairs and replacements were appropriately fabricated, examined and accepted by reviewing the following activities from March 2nd, 2020 to March 13th, 2020:
03.01.a - Nondestructive Examination and Welding Activities.
- Ultrasonic Examination (UT) of 2.5 Elbow to Pipe Weld for High Pressure Injection Emergency Core Cooling, Component ID HP-33C-CCB-2-35-SWE
- Liquid Penetrant Examination (PT) of the 8.25 SG 1 Upper Primary Head Nozzle Head Vent Safe-End Weld Component ID RC-SG-1-2-W253
- Inservice Inspection (ISI) Report 21-PT-030 Non-Relevant Indication (<1/16")
on Upper Primary Head Nozzle Head Vent Safe-End Weld Component ID RC-SG-1-2-W253
- Work Order (WO) 200744645-01 2 1/2" HP2A Valve Replacement
03.01.b - Pressurized-Water Reactor Vessel Upper Head Penetration Examination Activities.
- UT of 69 penetrations on the Reactor Vessel Closure Head (RVCH)
03.01.c - Pressurized-Water Reactor Boric Acid Corrosion Control Activities.
- CR-2019-02550 Decay Heat and Low-Pressure Injection DH Pumps Test Line Relief DH2761
- CR-2020-00129 Emergency Sump, Borated Water Storage Tank Isolation Valve DH7A
- CR-2019-06622 Containment Spray Discharge CS26
03.01.d - Pressurized-Water Reactor Steam Generator Tube Examination Activities.
- Eddy current testing of 15604 Tubes in steam generator (SG 1B) and 15580 Tubes in SG 2A
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 the shutdown for the planned refueling outage during the week ending February 29, 2020, and the plant trip recovery during the week ending March 28, 2020
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) Licensed operator requalification simulator scenario on February 11, 2020
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (1 Sample)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
- (1) Structures monitoring and aging management associated with pipe supports
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) Component cooling water pump 1 pump bearing replacement, constant level oiler installation, and new pump bearing oil seal installation
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (10 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) Planned replacement of integrated control system modules and delta Tcold adjustment during the week ending January 11, 2020
- (2) Emergent issue during nuclear instrument calibration resulting in unplanned power change during the week ending January 18, 2020
- (3) Planned maintenance on component cooling water train 1 during the week ending January 25, 2020
- (4) Emergent work on the seal oil vacuum pump and planned orange risk to personal safety (confined space activity) during the week ending February 8, 2020
- (5) Planned maintenance on decay heat/low pressure injection 2 pump resulting in an orange risk to nuclear generation window during the week ending February 22, 2020
- (6) Emergent conflict between high pressure injection system maintenance work and the reactor coolant system drain down contingency plan during the week ending March 7, 2020
- (7) Yellow shutdown defense-in-depth risk window for reactor coolant system reduced inventory and steam generator nozzle dam installation during the week ending March 7, 2020
- (8) Heavy lift associated with the reactor head removal and movement to head stand during the week ending March 7, 2020
- (9) Planned fuel movement and defueled activities during the week ending March 14, 2020
- (10) Yellow shutdown defense-in-depth risk window for planned reactor coolant drain following core reload during the week ending March 21, 2020
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (5 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Condition Report (CR) 2019-10096: Bolt found missing in diesel fuel oil pressure relief valve DO3672
- (2) CR 2020-01984: 1R21 Framatome - Potentially incorrect CRDM [control rod drive mechanism] o-ring lubricant supplied as equivalent
- (3) CR 2020-01840: Transverse crack in peripheral weld AFPT [auxiliary feedwater pump turbine] #2 governor
[maximum allowable leakage rate]
- (5) CR 2020-01702: Rust and staining on reactor vessel closure head flange
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (2 Samples)
The inspectors evaluated the following temporary or permanent modifications:
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (7 Samples)
The inspectors evaluated the following post maintenance test activities to verify system operability and functionality:
- (1) Auxiliary feedwater pump 1 after planned maintenance during the week ending January 4, 2020
- (2) Component cooling water pump 1 following planned maintenance during the week ending February 1, 2020
- (3) Decay heat/low pressure injection train 2 following planned maintenance during the week ending February 22, 2020
- (4) Startup transformer X02 following tap changes during the week ending March 7, 2020
- (5) High pressure injection 2A following planned maintenance during the week ending March 7, 2020
- (6) Emergency diesel generator 1 governor testing and tuning following planned governor replacement during the week ending March 14, 2020
- (7) Zero power physics testing during the week ending March 28, 2020
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Partial)
(1)
(Partial)
The inspectors evaluated licensee activities during refueling outage 21 from February 28, 2020 to March 30, 2020
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
- (1) Auxiliary feedwater pump 2 quarterly surveillance during the week ending February 15, 2020
- (2) Spent fuel pool ventilation system refueling interval test during the week ending March 7, 2020
- (3) Safety features actuation system train 2 integrated test during the week ending March 7, 2020
- (4) Off-Site AC sources train B bus transfer test during the week ending March 14, 2020
- (5) Emergency diesel generator 2 monthly surveillance run during the week ending March 14,
RADIATION SAFETY
71124.01 - Radiological Hazard Assessment and Exposure Controls
Radiological Hazard Assessment (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated how the licensee identifies the magnitude and extent of radiation levels and the concentrations and quantities of radioactive materials and how the licensee assesses radiological hazards
Instructions to Workers (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated radiological protection-related instructions to plant workers
Contamination and Radioactive Material Control (IP Section 03.03) (2 Samples)
The inspectors evaluated licensee processes for monitoring and controlling contamination and radioactive material:
- (1) Observed licensee surveys of potentially contaminated material leaving the radiologically controlled area (RCA)
- (2) Observed licensee contamination surveys during steam generator work activities
Radiological Hazards Control and Work Coverage (IP Section 03.04) (3 Samples)
The inspectors evaluated in-plant radiological conditions during facility walkdowns and observation of radiological work activities:
- (1) Steam Generation Nozzle Dam Installation under RWP 120-5301
- (2) Auxiliary Building Radiological Controls for Radiography under RWP 120-6052
- (3) HP2A (high pressure injection line 2-1 isolation) Valve Replacement under RWP 120-6053
High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (2 Samples)
The inspectors evaluated licensee controls of the following High Radiation Areas and Very High Radiation Areas:
- (1) Auxiliary Building for Radiography
- (2) Containment 603' Elevation Refueling Floor Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 03.06) (1 Sample)
- (1) The inspectors evaluated radiation worker and radiation protection technician performance as it pertains to radiation protection requirements
71124.02 - Occupational ALARA Planning and Controls
Implementation of ALARA and Radiological Work Controls (IP Section 03.03) (2 Samples)
The inspectors evaluated the licensees communication of as low as is reasonably achievable ALARA and radiological work controls for the following work activities:
- (1) Steam Generation Nozzle Dam Installation under RWP120-5301
- (2) HP2A (high pressure injection line 2-1 isolation). Valve Replacement under RWP 120-6053
Radiation Worker Performance (IP Section 03.04) (1 Sample)
The inspectors evaluated radiation worker and radiation protection technician performance during:
- (1) The inspectors evaluated the implementation of as low as is reasonably achievable techniques for work activities during the 1R21 refueling outage
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) Unit 1 (January 2019 - December 2019)
IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02) (1 Sample)
- (1) Unit 1 ( January 2019 - December 2019)
IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (1 Sample)
- (1) Unit 1 (January 2019 - December 2019)
71152 - Problem Identification and Resolution
Semiannual Trend Review (IP Section 02.02) (1 Sample)
Trend of Work Planning and Work Management issues
- (1) The inspectors reviewed the licensees corrective action program for potential adverse trends in work management that might be indicative of a more significant safety issue
71153 - Follow-up of Events and Notices of Enforcement Discretion Personnel Performance (IP Section 03.03)
- (1) The inspectors evaluated the plant trip during start-up due to a failed Potential Transformer (PT) fuse and licensees performance on March 25,
INSPECTION RESULTS
Observation: Trend of Work Planning and Work Management issues 71152 The inspectors reviewed the licensees corrective action program for potential adverse trends in work planning and work management that might be indicative of a more significant safety issue. During the review period for this inspection sample, the inspectors noted that a significant number of low-level performance issues and errors had challenged the licensee.
The inspectors determined that though some of these issues were directly attributable to human performance and/or procedural compliance, there were several that could be attributed to work planning and work management deficiencies. Specific examples associated with this trend included, but were not limited to:
- During the third quarter of 2019, the licensee commenced work to replace the control room emergency air temperature control system train 2 compressor. The plant risk due to the work was modeled as green but when maintenance personnel went out into the field, they identified the lift path for the train 2 compressor required lifting it over the train 1 equipment.
The personnel correctly identified that this situation significantly increased the nuclear safety and generation risk (to yellow) and stopped work. The inspectors noted that the work planning process could have identified this issue prior to work starting. (CR 2019-06415)
- While performing a field walkdown for motor driven feedwater pump target rock cable replacement, the licensee recognized that the conduit intended for use had other safety-related cables running through it that had not been identified during preparation of the engineering change package and work order. The licensee halted the work and developed an alternate approach. The inspectors determined that if this condition had not been recognized and work had proceeded as originally planned, the risk could have been higher than expected. Additionally, the inspectors noted this issue could have been identified during the engineering change process or the work planning process. (CR 2019-06418)
- During a post maintenance run of the emergency feedwater pump, the work order mistakenly directed operators to run the emergency feedwater pump with valves aligned for steam generator injection and not recirculation as intended. The error resulted in an unintended emergency feedwater pump injection into Steam Generator 1 (SG1) for one minute and seventeen seconds. The inspectors noted this event could have been avoided at multiple points during the work planning process and execution of the work order. The inspectors documented this issue in inspection report 2019004 (section 71152).
(CR 2019-07705)
- During a scheduled functional test of the train 2 containment normal range radiation monitor (RE4597BA), the operator performing the test was provided the procedure written for the train 1 containment normal range radiation monitor (RE4597AA). The operator followed the procedure he was given and initiated work on the wrong train component rendering both trains inoperable. The inspectors documented this issue in inspection report 2019002 (section 71152). (CR 2019-03346)
Individually, none of these examples may suggest an ongoing problem but when viewed in the aggregate, the inspectors determined they may indicate a programmatic weakness.
Specifically, for these and other work planning deficiencies the station may be missing the opportunity to identify and resolve deficiencies prior to the work being started, potentially resulting in an adverse impact to the plant. The inspectors provided these observations to the licensee and the licensee agreed that additional focus may be necessary to evaluate the trend. The NRC inspectors plan to continue monitoring the licensees actions to address work planning and work management issues.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On April 20, 2020, the inspectors presented the integrated inspection results to Mr. M. Bezilla, Site Vice President, and other members of the licensee staff.
- On March 6, 2020, the inspectors presented the radiation protection baseline inspection results to Mr. G. Norlund, Radiation Protection Manager, and other members of the licensee staff.
- On March 25, 2020, the inspectors presented the Davis-Besse ISI Inspection results to Mr. P. McCloskey, Performance Improvement Director, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
CR-2019-02774
DHP#2 Suction Pressure Gauge Out of Cal
03/25/2019
CR-2019-07307
Oil Drop Found on LPI Pump 2 Inboard Bearing
09/03/2019
Drawings
M-033A
High Pressure Injection
M-033B
Decay Heat Train 1
M-033C
Decay Heat Train 2
M-035
Spent Fuel Pool Cooling System
Procedures
DB-OP-06011
High Pressure Injection System
DB-OP-06012
Decay Heat and Low-Pressure Injection Operating
Procedure
DB-OP-06316
Diesel Generator Operating Procedure
Work Orders
200728759
DB-SP3447-001 - Decay Heat Train 2 Pump and Valve Test
09/24/2019
Fire Plans
High Voltage Switchgear Room A
Annulus Space Except East and Southwest Penetration
Areas at Elevations 585 and 603
East Penetration Area of Annulus Space Elevations 585 and
603
Miscellaneous
Fire Hazards Analysis Report
Procedures
DB-FP-04014
Fire Hose Station Inspections
Corrective Action
Documents
Resulting from
Inspection
CR-2020-01702
Rust Deposits and Staining Noted on RVCH Fange
03/20/2020
CR-2020-01798
New Indication Type Identified During SG Tube Examination
03/04/2020
CR-2020-02164
Non-Relevant Indications Observed on Nine Nozzles During
03/12/2020
Procedures
280-TECR-
104262
EPRI Appendix H/N Eddy Current Technique Validation
54-ISI-240-048
Visible Solvent Removable Liquid Penetrant Examination
Procedure
05/24/2019
54-ISI-603-011
Automated Ultrasonic Examination of RPV Closure Head
Penetrations Containing Thermal Sleeves
2/24/2020
54-ISI-829-014
PDI Generic Procedure for the Ultrasonic Examination of
Dissimilar Metal Welds PDI-UT-10
01/22/2020
54-ISI-836-018
PDI Generic Procedure for Ultrasonic Examination of
Austenitic Piping Welds PDI-UT-2
01/22/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Work Orders
200744645-01
Davis-Besse 2 1/2 HPA Valve Replacement
2/17/2019
71111.11Q Miscellaneous
Simulator Guide CYC 2020-01
Procedures
DB-OP-02528
Instrument Air System Malfunctions
NOP-OP-1002
Conduct of Operations
Corrective Action
Documents
CR-2019-10259
CCW Pump Outboard Bearing Design
2/09/2019
CR-2020-00174
Component Cooling Water Pump #1 Mechanical Seal Leak
01/10/2020
CR-2020-00362
Design Engineering Review/Evaluation of Data for any
Impact on Design Basis of CCW Pump 1
01/17/2020
CR-2020-00365
Abnormal Color in Oil Sample from CCW Pump 1 Outboard
Bearing
01/18/2020
CR-2020-00642
Design Engineering Evaluation of CCW Pump 1
Performance per DB-PF-03572, Step 4.41
01/27/2020
CR-2020-00651
CC1 (CCW Pump 1 Suction Valve) Stem Lock Handle is
Missing
01/27/2020
CR-2020-01257
CCW Pump #1 Lessons Learned
2/18/2020
CR-2020-02239
Change oil in P43-1 as Soon as Practical Due to High Iron
and Silicon
03/15/2020
CR-2020-10256
CCW Pump Inboard and Outboard Bearing Reservoir
Coatings are Deteriorating
2/09/2019
Corrective Action
Documents
Resulting from
Inspection
CR-2020-02858
Rust Identified on Spring Can Pipe Support 33-GCB-1-H3
04/01/2020
Miscellaneous
Structures Monitoring Inspection ECCS Pump Rm 1
03/31/2017
Structures Monitoring Inspection ECCS Pump Rm 1
08/16/2019
Structures Monitoring Inspection ECCS Pump Rm 2
03/13/2017
LRPD-05
3.7
Aging Management Program Evaluation Results - Structures
Monitoring Program
MRPM
Maintenance Rule Program Manual
NDE Reports
20-VT-101
Section XI Variable Spring Hanger Support Aux/Rm 500
03/10/2018
20-VT-108
Section XI Variable Spring Support AFP #1 Rm
03/13/2018
Procedures
DB-PF-03572
Component Cooling Water Pump 1 Baseline Test
DBBP-OPS-0011
Protected Equipment Posting
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
EN-DP-01511
Structures Monitoring
NA-QC-05560
Visual Examination Procedure for VT-1, VT-3, and General
Visual Examinations
Work Orders
200708089
Repair Inboard Bearing Oil Leak
03/19/2020
200736805
CCW Pump 1 Clean/Lubricate/Inspect
03/18/2020
200739481
CCW Pump1 Oil Level Validation
03/23/2020
200763444
CCW Pump 1 Constant Level Oilers
01/29/2020
Corrective Action
Documents
CR 2017-10941
Pipe Spring Identified on the Separator Tank for the Seal Oil
Vacuum Pump (P76_H)
10/31/2017
CR 2020-00607
Main Gen Seal Oil Vacuum Pump Degraded
01/25/2020
CR-2020-00230
Power Excursion While Placing ICS Back in Auto
01/13/2020
CR-2020-01255
As Found Condition Identified with the New Seal Cartridge
for the Decay Heat Pump
2/17/2020
CR-2020-01257
CCW Pump #1 Lessons Learned
2/18/2020
CR-2020-01363
Decay Heat Pump 2 Inboard Seal Package Leakage ~2 dpm
2/21/2020
CR-2020-01622
ICS11A Failed to Operate from Control Room During Plant
Shutdown
03/01/2020
CR-2020-01848
1R21 Framatome - Nuclear Instrument (NI) Well Covers
Leaking
03/05/2020
Drawings
M-035
Spent Fuel Pool Cooling System
OS-025
Main Generator Seal Oil System
Miscellaneous
Response to Generic Letter Number 88-17, Loss of Decay
Heat Removal
01/03/1989
Acuren Radiography Shot Plan for HP2A at DBNPS
1R21 Shutdown
Defense In Depth
Report
Contingency Plan for RCS Drain Below Flange Level and
Operation Below 80 Inches Above the RCS Hot Leg
Centerline
Lesson Plan G-
OPS-FHT
G-OPS-FHT Operations and Operation Contract Support
Personnel Fuel Handling Equipment
NOBP-OP-0007-
Worksheet
1R21 Reactor Head Lifts From and to the Reactor Vessel
2/10/2020
NOP-CC-5703-05 Repair/Replacement Certification Record
NOP-OP-1007-01 Risk Management Plan
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
DB-MM-09088
Reactor Vessel Head Removal
DB-MM-09089
Reactor Vessel Closure Head Stud Removal
DB-MM-09388
Reactor Vessel Head CRDM Service Structure Disconnects
DB-MN-00006
Control of Lifting and Handling of Heavy Loads
DB-OP-02016
Generator Alarm Panel 16 Annunciators
DB-OP-02527
Loss of Decay Heat Removal
DB-OP-06002
RCS Draining and Nitrogen Blanketing
DB-OP-06902
Power Operations
DBBP-OPS-0011
Protected Equipment Posting
NOBP-OP-0007
Conduct of Infrequently Performed Tests or Evolutions
NOP-OP-2018-02 Report of Repair/Replacement Activities for Nuclear
Facilities
Work Orders
200755711
Decay Heat and Low Pressure Injection Install Cartridge
Seals
03/12/2020
Corrective Action
Documents
2019-00351
Info Only Test on Relief Valve DO3671. Valve did not Lift
01/14/2019
2019-10096
Bolt Found Missing in Diesel Relief Valve DO3672
2/03/2019
20-01840
Transverse Crack in Peripheral Weld AFPT #2 Governor
03/05/2020
20-02064
CF1544 LLRT Exceeded Its MALR
03/10/2020
CR 2020-01984
1R21 Framatome - Potentially Incorrect CRDM [Control Rod
Drive Mechanism] O-Ring Lubricant Supplied as Equivalent
03/09/2020
CR-2020-01257
CCW Pump #1 Lessons Learned
2/18/2020
CR-2020-01702
Rust and Staining on Reactor Vessel Closure Head Flange
03/02/2020
CR-2020-01798
New Indication Type Identified during SG Tube Examination
03/04/2020
CR-2020-01840
Transverse Crack in Peripheral Weld AFPT #2 Governor
03/05/2020
CR-2020-01925
Nuclear Fuel - DB1R21: Fuel Inspection - Fuel to Baffle
Interaction Fuel Rod Wear Observed on Fuel Assembly
03/07/2020
CR-2020-01936
DB-ZS-ICS-11B-B1 Position Switch for PV-ICS11B Not
Charging
03/08/2020
CR-2020-01992
White Fibrous Material Identified on the Top Side of RVCH
CRDM Nozzle 23
03/09/2020
Drawings
DB-MM-09190
Control Rod Drive Mechanism Quick Vent and Hydraulic
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Closure Maintenance
OS-041C
Emergency Diesel Generator Diesel Oil System
Engineering
Evaluations
601154925
Evaluate ICS38A Seat Seal Weld Crack
03/11/2018
Miscellaneous
ISTB4
Pump and Valve Basis Document, Volume IV - Maximum
Allowable Leakage Rate (MALR) Basis
Procedures
DB-MM-09344
Emergency and Station Blackout Diesel Engine 4-Year
Maintenance
DB-OP-06012
Decay Heat and Low Pressure Injection System Operating
Procedure
DB-OP-06234
NOP-LP-2018-02
Report of Repair/Replacement Activities for Nuclear
Facilities
NOP-OP-1009
Operability Determinations and Functionality Assessments
Shipping Records Purchase Order
45382204/0
Quality Control Receiving Inspection Report for DC Fuel Oil
Pump
05/08/2012
Purchase Order
45463301/1
Quality Control Receiving Inspection Report for Valve -
Relief from Supplier Engine Systems Incorporated
06/12/2015
Engineering
Changes
16-0332
Emergency Feedwater (EFW) NFPA Manual Initiation Circuit
19-0011-004
Replacement of RCP Seal Return Flow Instrumentation -
FEMU60D/FTMU60D (and Installation of Relief Valve to
Address Potential Overpressurization of Penetration 56
Piping)
Corrective Action
Documents
CR 2020-02613
ZPPT: Cycle 22 Control Rod Worth Greater than Predicted
03/25/2020
CR 2020-02682
Cycle 22 Hot Zero Power (HZP) Reactivity Anomaly Larger
than Expected
03/27/2020
CR-2020-01245
Voided Pipe Upstream of DH200
2/17/2020
CR-2020-01257
CCW Pump #1 Lessons Learned
2/18/2020
CR-2020-01363
Decay Heat Pump 2 Inboard Seal Package Leakage ~2 dpm
2/21/2020
CR-2020-01891
HP2A Stroke Times are Less Than Expected Stroke Times
03/06/2020
CR-2020-01895
HPI Pump 2-D Horizontal Vibe Reading in the Alert Range
03/07/2020
DB-SP-03151
AFP 1 Quarterly Test
Miscellaneous
NOP-CC-5703-05 Repair/Replacement Certification Record
Procedures
DB-ME-09700
Woodward 2301A Electronic Load Sharing and Speed
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Control Setup and Adjustment
DB-MM-09098
AFPT Governor Maintenance
DB-MM-09150
AFPT Maintenance
DB-OP-06314
13.8 KV Switching
DB-OP-06316
Diesel Generator Operating Procedure
DB-PF-03207
HPI Pump Comprehensive and Check Valve Forward Flow
Test Train 1
DB-PF-03208
HPI Pump Comprehensive and Check Valve Forward Flow
Test Train 2
DB-PF-03572
Component Cooling Water Pump 1 Baseline Test
DB-PF-09302
Testing Motor Operated Valves
NOP-LP-2018-02
Report of Repair/Replacement Activities for Nuclear
Facilities
Work Orders
200738187
AFP 1 Quarterly Test
01/02/2020
200746960
Auxiliary Feedwater Pump Turbine 1-1 Preventive
Maintenance
01/02/2020
200755827
NE3212-001 Zero Power Physics Test RFL
03/25/2020
200755962
HPI Pump Comprehensive Test
03/07/2020
Corrective Action
Documents
20-02269
TYTRC7A [Reactor Coolant Loop 2 Temperature Difference
Indicator] Found Out of Tolerance
03/16/2020
CR-2020-00683
Procedure Non-compliance: NOP-LP-4011 - Work Hour
Controls
01/29/2020
CR-2020-00984
Cycle 22 Fuel Receipt - Marking Identified on Fuel Cladding
of Assembly UDDG65 During Receipt Inspection
2/08/2020
CR-2020-01190
Pipe Supports Removed During MFPT #2 Pre-Outage Work
2/14/2020
CR-2020-01617
DB-PF-03180 Leakage Observed from RC 51
2/29/2020
CR-2020-01758
1R21 Framatome Spring Scale Not Used for CRDM
Leadscrew Uncoupling Parking
03/04/2020
CR-2020-01863
Cooling Tower Column Degradation
03/06/2020
CR-2020-01880
HP2A Critical Path Re-Assembly Delays
03/06/2020
CR-2020-01886
Rust Buildup Found on Internals of New Aux Feed Trip
Throttle Valve
03/06/2020
CR-2020-01897
Ground on Bus E1
03/07/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
CR-2020-01904
Corrosion Found on Shield Building Wall
03/07/2020
CR-2020-02009
1R21 - Incidental Duties Performed Off-site Result in Fatigue
Rule Violations
03/09/2020
CR-2020-02112
DB 1R21 Trend in Work Hour Rule Compliance
03/11/2020
CR-2020-02112
DB 1R21 Trend in Work Hour Control Compliance
03/11/2020
CR-2020-02164
Non-Relevant Indications Observed on Nine Nozzles During
03/12/2020
CR-2020-02203
Emergency Diesel Generator 1 Emergency Shutdown
03/13/2020
CR-2020-02217
SP7A 3-way Valve Vent Hole is Leaking
03/14/2020
CR-2020-02222
Diode for K2 Relay Shorted
03/14/2020
CR-2020-02238
Issue Noted During Performance of DB-MI-03743
03/15/2020
CR-2020-02248
ICS11A Did Not Operate Smoothly
03/15/2020
CR-2020-02448
1R21 CTMT Closeout Inspection Results
03/20/2020
CR-2020-02524
1R21 - Unapproved Material Found in CTMT During Mode 3
03/23/2020
CR-2020-02557
Foreign Material Identified During Mode 3 Inspection of
Integrated Head Assembly
03/24/2020
CR-2020-02562
1R21 BACC: A Packing and Pipe Cap Leak Was Found on
CF60
03/24/2020
CR-2020-02576
1R21 Final CTMT Closeout Inspection Results
03/24/2020
Corrective Action
Documents
Resulting from
Inspection
CR-2020-01376
Fuel Handling JFG Documentation Issue
2/21/2020
CR-2020-01650
Material Control Within a Posted Protected Equipment Area
03/01/2020
CR-2020-02063
1R21 Framatome - Spent Fuel Building FME Area Sign
03/10/2020
Miscellaneous
NOBP-OP-1004-
Evolution Specific Reactivity Plan
1/7/2020
Procedures
Cycle 22 COLR
Cycle 22 Core Operating Limits Report
DB-MM-09234
Equipment Hatch Removal and Reinstallation
DB-NE-06303
Fuel Handling in the Auxiliary Building
DB-NE-06307
Fuel Storage Handling Bridge Operating Procedure
DB-NE-06308
Main Fuel Handling Bridge Operating Procedure
DB-OP-02547
Spent Fuel Pool Cooling Malfunctions
DB-OP-06021
Spent Fuel Pool Operating Procedure
GEN-MNT- 0004
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
NG-DB-0017
Shutdown Defense in Depth Assessment
NOBP-OP-1004-
Cycle 21 End of Cycle Shutdown While Restoring Tave to
2F
2/24/2020
Radiation
Surveys
CR-2020-02258
CF-4A1A Found Leaking (CF-LT3A1)
03/15/2020
Corrective Action
Documents
CR 2020-01837
DB-SS-03708 Spent Fuel Pool Ventilation System Refueling
Interval Test Acceptance Criteria 5.3 Not Met
03/05/2020
CR-2020-02423
Field Copy of DB-SC-03121 Lost Before Transferring Data to
Master
03/19/2020
Drawings
E-1043 Sh 1
Emergency Diesel Generator 1-2 Loading Table
E-1043 Sh 2
Emer. Diesel Generator 1-2 Loading Table
Miscellaneous
Recommended Enhanced Monitoring of the AFPT 2
Governor and Governor Valve Linkage Prior/During the
Performance of DB-SP-03160 AFP 2 Quarterly Testing
2/14/2020
Technical Requirements Manual
Procedures
DB-SC-03022
Off-Site AC Sources Bus Transfer Test
DB-SC-03071
Emergency Diesel Generator 2 Monthly Test
DB-SP-03160
AFP 2 Quarterly Test
Work Orders
200756129
SFAS Train 2 Integrated Response Time Test
03/19/2020
200756227
SS3708-001 SFP Ventilation Test
03/05/2020
200817786
SFAS Component Test CV5075
03/17/2020
Calculations
DB-HP4344-01
Source Term Determination
08/02/2019
Calibration
Records
Containment Access Facility Exit Radiological Monitor
Calibration and Setpoint Data
Various
Corrective Action
Documents
CR-2019-05009
Elevated Contamination Levels Found in Clean Areas of
Auxiliary Building
06/07/2019
CR-2019-08502
Continuous Noble Gas Monitor, AMS-4, Failed Due to Water
Intrusion
10/16/2019
CR-2019-08763
Individual Received a Dose Rate Alarm
10/22/2019
CR-2019-10082
Individual Alarmed Passive Monitoring
2/02/2019
CR-2019-10166
Elevated Dose Rates Identified in Dry Shielded Container
Drain Port Hole
2/05/2019
Procedures
NOP-OP-4101
Access Controls for Radiologically Controlled Areas
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
NOP-OP-4102
Radiological Posting and Labeling
NOP-OP-4104
Job Coverage
NOP-OP-4701
Radiation and Contamination Surveys
Radiation
Surveys
Steam Generator Lower Bowl and Platform Radiological
Surveys and Air Sample Data
Various
Radiation Work
Permits (RWPs)
20-5302
Once-Through Steam Generator Activities
ALARA Plans
1R21 Refuel Outage Dose Estimate Trend
03/06/2020
Miscellaneous
Shutdown Chemistry and Source Term Reduction Plan 1R21 0
RWP 120-5019
Alara Plan Waiver Form
11/16/2019
RWP 120-5405
Alara Work in Progress Review
03/04/2020
Procedures
NOP-OP-4107
Radiation Work Permit (RWP)
Radiation Work
Permits (RWPs)
20-5104
Reactor Head Disassembly and Reassembly Work Activities
20-5304
Rotate Orifice Plate Inside Steam Generator 1-1 and 1-2
71151
Corrective Action
Documents
CR 2019-00201
Steam Leak on MS100-1 Piping
01/08/2019
Miscellaneous
Licensee Logs
Various
Regulatory Assessment Performance Indicator Guideline
Corrective Action
Documents
CR-2019-06415
CREATCS Train 2 Compressor Replacement Under Order
200582815 was Not Identified as Yellow Nuclear Safety and
Generation Risk
07/30/2019
CR-2019-06418
Critical Order ECP15-0138-004 Target Rock Work Order
Dropped at T+1
07/30/2019
CR-2019-06544
Chemistry Step in the WIS was Incorrectly Scheduled for the
Auxiliary Boiler Outage
08/04/2019
CR-2019-07192
On-line Preparation Milestones not Followed IAW NOP-WM-
0001 Work Management Process
08/28/2019
CR-2019-07763
System Leakage Test of CCW Pump #3 as #1 - Schedule
Change at T-0
09/20/2019
CR-2019-07864
Field Problem Resolution was not Processed Correctly
09/25/2019
CR-2019-09876
Unexpected Loss of Power on Security MUX6 Primary
Communication AdTran
11/22/2019
CR-2019-09925
AD110 HFA Relay Testing concerns
11/25/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
CR-2019-09949
Poor Planning for #2 Circ Pump Maintenance
11/26/2019
CR-2019-10670
AFW Train 1 Lube PM Removed from Schedule at T5 and
Placed Back into Schedule at NWW Without Crew
Acknowledgement
2/30/2019
CR-2019-10674
LPI 1 Post-Quarterly Run Oil Sample Requires a Clearance
and Determination to Defer the Sample not Completed at T2
2/30/2019
CR-2020-00037
Switchyard Breaker 34560 Project Schedule Impacts
01/02/2020
CR-2020-01036
1R21 Orders Changing from RDEX to APLN for Additional
Information
2/11/2020