IR 05000346/2022004
| ML23038A204 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 02/09/2023 |
| From: | Billy Dickson NRC/RGN-III/DORS/RPB2 |
| To: | Tony Brown Energy Harbor Nuclear Corp |
| References | |
| EA-22-137 IR 2022001, IR 2022004 | |
| Download: ML23038A204 (1) | |
Text
SUBJECT:
DAVIS-BESSE NUCLEAR POWER STATION - INTEGRATED INSPECTION REPORT 05000346/2022004 AND 07200014/2022001
Dear Terry Brown:
On December 31, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Davis-Besse Nuclear Power Station. On January 24, 2023, 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, Billy C. Dickson, Jr., Chief Reactor Projects Branch 2 Division of Operating Reactor Safety Docket Nos. 05000346 and 07200014 License No. NPF-3
Enclosure:
As stated
Inspection Report
Docket Number:
05000346 and 07200014
License Number:
Report Number:
05000346/2022004 and 07200014/2022001
Enterprise Identifier:
I-2022-004-0043 and I-2022-001-0113
Licensee:
Energy Harbor Nuclear Corp.
Facility:
Davis-Besse Nuclear Power Station
Location:
Oak Harbor, OH
Inspection Dates:
October 01, 2022 to December 31, 2022
Inspectors:
B. Bergeon, Senior Operations Engineer
R. Cassara, Resident Inspector
J. Cassidy, Senior Health Physicist
R. Edwards, Branch Chief
G. Hansen, Senior Emergency Preparedness Inspector
T. Henning, Operations Engineer
J. Kutlesa, Emergency Preparedness Inspector
D. Mills, Senior Resident Inspector
J. Nance, Senior Operations Engineer
J. Robbins, Senior Resident Inspector
Approved By:
Billy C. Dickson, Jr., Chief
Reactor Projects Branch 2
Division of Operating Reactor Safety
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
Unit 1 began the inspection period at rated thermal power. On December 5, 2022, the unit was shut down to replace the reactor coolant pump 1-2 seal. The unit was returned to rated thermal power on December 19, 2022. At 1412 ET on December 23, 2022, operators commenced a technical specification required reactor shutdown due to a lowering level in the intake forebay caused by severe weather. The shutdown was halted at 87.5 percent power and the unit was returned to full rated power later on December 23 after NRC granted verbal approval of a notice of enforcement discretion to allow continued operation with reduced intake forebay level. The unit remained at or near rated thermal power for the remainder of the inspection period.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors performed activities described in IMC 2515, appendix D, Plant Status, observed risk significant activities, and completed on-site portions of IPs. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
REACTOR SAFETY
71111.01 - Adverse Weather Protection
Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of seasonal cold temperatures for the following systems:
ultimate heat sink, service water, and component cooling water.
External Flooding Sample (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated that flood protection barriers, mitigation plans, procedures, and equipment are consistent with the licensees design requirements and risk analysis assumptions for coping with external flooding.
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) Emergency diesel generator 2 following emergency diesel generator 1 surveillance run during the week ending October 15, 2022
- (2) Fire protection system after repair during the week ending November 19, 2022
- (3) Emergency diesel generator 1 following emergency diesel generator 2 surveillance run during the week ending November 26, 2022
- (4) Decay heat during reduced reactor coolant system inventory during the week ending December 10, 2022
- (5) Emergency feedwater system following outage during the week ending December 24, 2022
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations during a complete walkdown of the service water system during the week ending October 22, 2022.
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) Protected area yard while main and auxiliary transformer deluge systems were out of service for repairs, fire areas MA, MB, MC, ME, MF, MH, and OS during the week ending November 12, 2022
- (2) Emergency core cooling system train 1 room 105, fire area AB during the week ending December 17, 2022
- (3) Containment closeout walkdown, fire areas D, AB, and A during the week ending December 17, 2022
Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the onsite fire brigade training and performance during a live fire drill during the week ending October 8, 2022.
71111.06 - Flood Protection Measures
Inspection Activities - Internal Flooding (IP Section 03.01) (1 Sample)
The inspectors evaluated internal flooding mitigation protections in the:
- (1) Manholes MH 3045 and MH 3001 following sump pump replacement during the week ending December 3, 2022
71111.07A - Heat Exchanger/Sink Performance
Annual Review (IP Section 03.01) (1 Sample)
The inspectors evaluated readiness and performance of:
- (1) Ultimate heat sink during the week ending December 24, 2022
71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance
Requalification Examination Results (IP Section 03.03) (1 Sample)
- (1) The inspectors reviewed and evaluated the licensed operator examination failure rates for the requalification biennial written examinations and the annual operating tests administered from October 17, 2022 through December 2, 2022.
71111.11B - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Requalification Program (IP Section 03.04) (1 Sample)
- (1) Biennial Requalification Written Examinations The inspectors evaluated the quality of the licensed operator biennial requalification written examination administered on December 2, 2022.
Annual Requalification Operating Tests The inspectors evaluated the adequacy of the facility licensees annual requalification operating test.
Administration of an Annual Requalification Operating Test The inspectors evaluated the effectiveness of the facility licensee in administering requalification operating tests required by 10 CFR 55.59(a)(2) and that the facility licensee is effectively evaluating their licensed operators for mastery of training objectives.
Requalification Examination Security The inspectors evaluated the ability of the facility licensee to safeguard examination material, such that the examination is not compromised.
Remedial Training and Re-examinations The inspectors evaluated the effectiveness of remedial training conducted by the licensee and reviewed the adequacy of re-examinations for licensed operators who did not pass a required requalification examination.
Operator License Conditions The inspectors evaluated the licensees program for ensuring that licensed operators meet the conditions of their licenses.
The inspectors identified one potential violation associated with this review. This issue is documented in NRC Inspection Report 2022091.
Control Room Simulator The inspectors evaluated the adequacy of the facility licensees control room simulator in modeling the actual plant, and for meeting the requirements contained in 10 CFR 55.46.
Problem Identification and Resolution The inspectors evaluated the licensees ability to identify and resolve problems associated with licensed operator performance.
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (2 Samples)
- (1) The inspectors observed and evaluated requalification annual simulator evaluation drills on October 19, 2022.
- (2) The inspectors observed and evaluated annual simulator evaluation drills on October 26, 2022.
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) AFW train 1 agastat relay replacement during the week ending November 12, 2022
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) RCP seal replacement during the week ending December 17, 2022
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (6 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) Risk management during emergent fire protection system maintenance during the week ending November 26, 2022
- (2) AFW sticking agastat during the week ending November 12, 2022
- (3) Yellow risk for reduced inventory to remove handholes in preparation for reactor coolant pump seal replacement during the week ending December 10, 2022
- (4) Yellow risk for reduced inventory below flange level for reactor coolant pump seal replacement during the week ending December 10, 2022
- (5) Yellow risk to fill and vent the RCS after reactor coolant pump seal replacement during the week ending December 17, 2022
- (6) Source range nuclear instrumentation replacement and calibration during the week ending December 24, 2022
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) TC computer point during the week ending October 22, 2022
- (2) Annunciator panel 4 after power failure during the week ending December 3, 2022
- (3) Decay heat valves DH11, DH12, DH48, DH48A during the week ending December 17, 2022
- (4) Electrical penetration 2 using excessive nitrogen to maintain pressure during the week ending December 17, 2022
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (1 Sample)
The inspectors evaluated the following temporary or permanent modifications:
- (1) Control room door 509 frame reinforcement during the week ending December 24, 2022
Severe Accident Management Guidelines (SAMG) Update (IP Section 03.03) (1 Sample)
- (1) The inspectors verified the site SAMG were updated in accordance with the PWR generic severe accident technical guidelines and validated in accordance with NEI 14-01, Emergency Response Procedures and Guidelines for Beyond Design Basis Events and Severe Accidents, Revision 1.
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (6 Samples)
The inspectors evaluated the following post-maintenance testing activities to verify system operability and/or functionality:
- (1) Service water pump 3 after scheduled maintenance during the week ending October 29, 2022
- (2) Auxiliary feedwater train 1 quarterly test following agastat relay replacement during the week ending November 12, 2022
- (3) Emergency diesel generator 1 monthly test after replacement of pressure control and regulating pilot valves during the week ending November 12, 2022
- (4) Component cooling water pump 1 after scheduled maintenance during the week ending December 3, 2022
- (5) Source range nuclear instrument 1 following replacement during the week ending December 17, 2022
- (6) Personnel hatch local leak rate test during the week ending December 17, 2022
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated maintenance outage activities related to reactor coolant pump 1-2 seal replacement from December 5 to December 19.
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance testing activities to verify system operability and/or functionality:
Inservice Testing (IP Section 03.01) (2 Samples)
- (1) High pressure injection quarterly test during the week ending October 29, 2022
- (2) Auxiliary feedwater pump 2 during the week ending November 12, 2022
RCS Leakage Detection Testing (IP Section 03.01) (1 Sample)
- (1) Reactor coolant system leak rate testing during the week ending November 26, 2022
71114.04 - Emergency Action Level and Emergency Plan Changes
Inspection Review (IP Section 02.01-02.03) (1 Sample)
- (1) The inspectors evaluated the following submitted Emergency Action Level and Emergency Plan changes:
10 CFR 50.54(q)3 Screen/Evaluation: DB-2020-015-00, 09/08/2020 This evaluation does not constitute NRC approval.
71114.06 - Drill Evaluation
Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01) (1 Sample)
- (1) Emergency response organization training and tabletop exercise on November 8,
RADIATION SAFETY
71124.06 - Radioactive Gaseous and Liquid Effluent Treatment
Sampling and Analysis (IP Section 03.02) (2 Samples)
Inspectors evaluated the following effluent samples, sampling processes and compensatory samples:
- (1) Station vent - weekly grab sample
- (2) Radiative waste storage building - compensatory action
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04)===
- (1) April 1, 2021 through September 30, 2022
MS06: Emergency AC Power Systems (IP Section 02.05) (1 Sample)
- (1) July 1, 2021 through September 30, 2022
MS07: High Pressure Injection Systems (IP Section 02.06) (1 Sample)
- (1) July 1, 2021 through September 30, 2022
MS08: Heat Removal Systems (IP Section 02.07) (1 Sample)
- (1) July 1, 2021 through September 30, 2022
MS09: Residual Heat Removal Systems (IP Section 02.08) (1 Sample)
- (1) October 1, 2021 through September 30, 2022
MS10: Cooling Water Support Systems (IP Section 02.09) (1 Sample)
- (1) October 1, 2021 through September 30, 2022
71152A - Annual Follow-up Problem Identification and Resolution Annual Follow-up of Selected Issues (Section 03.03)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (2) Reactor coolant system unidentified leakage trend
71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02)
- (1) The inspectors reviewed the licensees corrective action program for potential adverse trends related to ground settling and sink holes that might be indicative of a more significant safety issue.
71153 - Follow-Up of Events and Notices of Enforcement Discretion Notice of Enforcement Discretion (NOED) (IP Section 03.04)
- (1) The inspectors evaluated licensee actions related to severe weather conditions on December 23-25, including a seiche on Lake Erie, that decreased the plant intake canal level to below the technical specification required 562 feet above sea level. At 1412 ET on December 23, the licensee petitioned the NRC for enforcement discretion. At 1640 ET NRC granted verbal approval for a notice of enforcement discretion [EPID: I-2022-004-0043] to allow continued plant operation during the period of reduced intake canal level. The events are discussed in greater detail in the licensees written request (ADAMS Accession number ML22362A109) and the NRC response (ADAMS Accession number ML22363A561). The NOED can be accessed at http://www.nrc.gov/reading-rm/doc-collections/enforcement/notices/noedreactor.html.
OTHER ACTIVITIES
- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL
60855 - Operation of an ISFSI Operation of an ISFSI
- (1) The inspectors evaluated the licensees activities related to the long-term operation and monitoring of its Independent Spent Fuel Storage Installation (ISFSI). The inspectors reviewed relevant documentation remotely during the weeks of October 10 and October 17, 2022, and were onsite on October 18, 2022. During the onsite walkdown, the inspector toured the ISFSI and evaluated the material and radiological conditions of the ISFSI pad and loaded TN NUHOMS 24P, 32PTH, and EOS 37PTH systems. The inspectors verified that radiological conditions on the ISFSI pad were as expected during the walkdown.
Since the last inspection, the inspectors evaluated corrective action documents and changes performed in accordance with 10 CFR 72.48, "Changes, Tests, and Experiments." The inspectors also reviewed the surveillance procedure and interviewed operations staff regarding daily checks of the loaded horizontal storage modules.
INSPECTION RESULTS
Observation: ICS11A (Atmospheric Vent Valve 2) Carbon Bushing Wrong Size 71152A The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
In March 2022, during the performance of atmospheric vent valve #2 scheduled maintenance, the licensee found a stem-packing carbon bushing broken. Licensee personnel determined the installed bushing to be incorrect and that the supplied replacement part was also wrong.
The licensee determined that the incorrect part was supplied for the previous maintenance and the scheduled maintenance due to errors in the licensees supply software. The licensee corrected the supply software's mistakes and installed the correct carbon bushing. The inspectors reviewed the circumstances leading to this incident, the licensee's corrective actions, and extent of condition. The inspectors also reviewed surveillance test procedures, drawings, and work orders for both atmospheric vent valves. No findings were identified.
Observation: Reactor Coolant System Unidentified Leakage Trending Higher 71152A The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
The licensee detected an increasing trend in reactor coolant system unidentified leakage following reactor coolant pump 1-2 seal replacement during the refueling outage in April 2022. Residents verified that the licensee followed their process to investigate the elevated unidentified leakage. The licensee did not identify the source of the leakage, but it was suspected to be an unmeasured flow past the seal leak-off measuring device. Due to this indication and other indications pointing to a damaged or degrading seal third stage, the licensee replaced the seal during a maintenance outage in December 2022. Following this seal replacement, the unidentified leakage returned to the expected range. The resident inspectors verified that licensee actions were in accordance with their procedures and observed inspections of infrequently accessed locations, including containment. Resident inspectors continue to monitor unidentified leakage independent of the licensee monitoring program. No findings were identified.
Observation: Ground Settling/Sinkholes 71152S The inspectors reviewed the licensees corrective action program for potential adverse trends related to ground settling and sinkholes that might indicate of a more significant safety issue.
During the review period for this inspection sample, the inspectors noted several issues related to ground settling. The licensee previously identified similar problems over the previous several years. The inspectors determined that the licensee identified these issues and that the licensee implemented corrective actions. Specific examples associated with this trend included but were not limited to:
- Sinkhole near Security Warehouse (2021-01278)
- Sinkhole under sidewalk (2021-08529)
- Sinkhole training center contractor lot (2022-06310)
- Cooling Tower Bypass Pipe Support Settlement/Sinkhole (2022-02401)
- Potential Sink Hole Identified in Personnel Walkway between PSF and South PAC (2022-09856)
- Potential sinkhole near Water Treatment Plant (2022-04366)
- Potential Sinkhole Near AC Transformer (2022-07790)
- North Underground Fire Protection Loop Pipe Rupture (2022-07575)
- Small Sinkhole Identified South of Wellness Center (2022-04199)
- Sinkhole Identified in security isolation zone (2022-04728)
- Potential Sinkhole North of Circulating Water Pump House (2022-05651)
- Sink Holes In The Protected Area (2021-05696)
Individually, none of these examples suggested an ongoing problem, but the inspectors determined that they may indicate a potential weakness when viewed in the aggregate.
Specifically, for these and other issues, the station may be missing the opportunity to identify and resolve deficiencies before a failure manifests and adversely impacts the plant. The inspectors provided these observations to the licensee and the inspectors will continue monitoring the licensees actions to identify and correct similar issues.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On November 4, 2022, the inspectors presented the ISFSI Interim Exit inspection results to T. Brown, Site Vice President, and other members of the licensee staff.
On December 2, 2022, the inspectors presented the emergency action level and emergency plan changes inspection results to G. Wolf and other members of the licensee staff.
On December 8, 2022, the inspectors presented the radiation protection inspection results to C Jackson, General Plant Manager, and other members of the licensee staff.
On January 5, 2023, the inspectors presented the Licensed Operator Requalification Program Annual Testing Summary Results inspection results to C. Jackson, General Plant Manager, and other members of the licensee staff.
On January 18, 2023, the inspectors presented the Biennial Licensed Operator Requalification Program Exit inspection results to T. Brown, Site Vice President, and other members of the licensee staff.
On January 24, 2023, the inspectors presented the integrated inspection results to T. Brown, Site Vice President, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
20-07214
Aging Management Inspections
09/16/2020
20-07215
DSC 24P-R01 Was Not Rotated 180-Degrees
09/16/2020
20-07216
Foreign Material Identified on the Rail During AMP
Inspections
09/10/2020
20-08358
Exceeding Groundwater Chemistry Limits
11/18/2020
Corrective Action
Documents
21-05199
NCV From Davis-Besse 2019 EOS Campaign
08/06/2021
Corrective Action
Documents
Resulting from
Inspection
22-08332
Missing FME Plugs on DB-HSM1 to DB-HSM4
11/02/2022
CFR 72.212 Evaluation Report
CFR 72.212 Evaluation Report for the NUHOMS EOS
System
HSM Basemat Survey Results
09/01/2021
2.48 Screen No.
20-00443
HSM-80 Door Plate Helicoil Inserts
2.48 Screen No.
20-01045
ISFSI Aging Management Program
Miscellaneous
2.48 Screen No.
20-01271
Shielding Request for HSM Aging Management Inspections
Procedures
DB-NE-03400
Horizontal Storage Monitoring
DB-M-20200624-3
Dry Fuel Storage Pad
06/24/2020
DB-M-20210610-1
Dry Fuel Storage Pad
06/10/2021
Radiation
Surveys
DB-M-20220615-2
Dry Fuel Storage Pad
06/15/2022
60855
Self-Assessments QFO-2021-0001
ISFSI Audit
04/02/2021
DB-ME-09521
Preventive Maintenance and Circuit Testing of Freeze
Protection and Heat Tracing
DB-OP-06331
Freeze Protection and Electrical Heat Trace
DB-OP-06913
Seasonal Plant Preparation Checklist
Procedures
RA-EP-02830
Flooding
Corrective Action
Documents
22-06915
EDG Air Compressor 1 Air Leak
09/10/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
DB-FP-04031
Quarterly Fire Valve Alignment Verification
DB-OP-06012
Decay Heat and Low-Pressure Injection System Operating
Procedure
DB-OP-06234
DB-OP-06261
Service Water System Operating Procedure
DB-OP-06316
Diesel Generator Operating Procedure
Procedures
DB-OP-06316
Diesel Generator Operating Procedure
ECCS Pump Room 1-1, Rooms 105, Fire Area AB-01
ECCS Pump Room 1-1, Rooms 105, Fire Area AB-01
Core Flooding Tank Area, Room 214, Fire Area D
Let Down Coolers Area, Room 215, Fire Area D
Steam Generator West D Ring Area, Room 216, Fire Area
D
Steam Generator East D Ring Area, Room 218, Fire Area D
Containment Air Cooler Area, Room 317 and Room 317A,
Fire Area D
Fuel Transfer Pool and North and West 603' Elevation,
Rooms 219, 407, and 410A, Fire Area D
North Area 565' Elevation, Rooms 213, 217, and Normal
Sump Area, Fire Area D
Protected Area Yard, General, Manholes, Junction Box,
Transformers, and Auxiliary Feedwater Exhaust Enclosure,
Fire Areas MA, MB, MC, ME, MF, MH, and OS
Fire Plans
Protected Area Yard Strategy, Explosion and/or Large
Accelerant Fed Fire Involving Large Areas of the Plant
22-08207
Standing Water in Electrical Manhole MH 3001
10/28/2022
Corrective Action
Documents
22-09251
Aux Boiler Deaerator Level Control Valve CD1666B Failed
Open
2/05/2022
Procedures
RA-EP-02880
200605395
Replace Sump Pump - MH3045
11/04/2022
Work Orders
200898057
Replace Motor CNDS PIT West Sump 1-1 Pump B
2/05/2022
C-69
Construction Water Intake
Drawings
TECW-201-BI
Intake Canal Water Intake and Discharge
2/20/1972
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
System
Description
Service Water System for Energy Harbor Nuclear Davis-
Besse Nuclear Power Station, Unit 1
DB-ME-09521
Preventive Maintenance and Circuit Testing of Freeze
Protection and Heat Tracing
DB-OP-06331
Freeze Protection and Electrical Heat Trace
Procedures
DB-OP-06913
Seasonal Plant Preparation Checklist
Miscellaneous
22 Annual
Licensed Operator
Requal Test
Results
Davis-Besse 2022 Annual LORT Exam Summary Results
2/02/2022
Corrective Action
Documents
Resulting from
Inspection
22-09503
22 NRC 71111.11 Inspection: Continuous Training
Participation
2/15/2022
Engineering
Evaluations
NOBP-TR-1112
Davis-Besse Crew 2 Evaluation Annual Exam Form
11/30/2022
Operating Crew 2 Watch Standing Hours 2021-2022
22 Biennial Exam 1
DB-0779-1
Crew / Individual Performance Improvement Plan(s)
2/09/2020
None
Attendance Sheets Licensed Operator Continuing Training
Cycle
20
None
Attendance Sheets Licensed Operator Continuing Training
Cycle
21
None
Attendance Sheets Licensed Operator Continuing Training
Cycle
22
ORQ-EPE-S101
Crew 2 Requalification Scenario
ORQ-EPE-S105
Crew 2 Requalification Scenario
ORQ-EPE-S137
Crew 2 Requalification Scenario
ORQ-EPE-S139
Crew 2 Requalification Scenario
ORQ-EPE-S153
22 Annual Exam SBT
07/12/2022
OTL1POS106
Approach to Criticality
2/22/2020
OTL1POS107
Raise Power Above Low Level Limits
2/22/2020
OTLAOPDBS104
Rapid Shutdown
2/26/2021
Miscellaneous
Post-Event
Overcooling Plant Trip
07/08/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Testing
Simulator Based
Testing
Cycle 23 Steady State Comparison 100% Reactor Power
Simulator
Scenario Based
Testing
Cycle 23 Steady State Comparison 40% Reactor Power
Simulator
Scenario Based
Testing
Cycle 23 Steady State Comparison 75% Reactor Power
Simulator
Scenario Based
Testing Form
22 ILT Scenario 4
11/3/2021
Simulator Training
Certification Test
N2a
SHUTDOWN - FPSS to 500 Degrees
Simulator Training
Certification Test
N6
Sixty Minute Drift Test
Simulator Training
Certification Test
RTT
Computer Real Time Test
Simulator Training
Certification Test
Tab 03
Simultaneous Closure of All Main Steam Isolation Valves
Simulator Training
Certification Test
Tab 05
Trip of One Reactor Coolant Pump
Simulator Training
Certification Test
Tab 08
Double Ended Hot Leg Shear with a Coincident Loss of All
Off-Site Power
Simulator Training
Certification Test
Tab 10
The PORV Fails Fully Open and HPI Does Not Actuate
Procedures
DBBP-TRAN-0021
Simulator Configuration Control
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
DBBP-TRAN-01
NRC Initial Operator License Exam Security
DBBP-TRAN-0552
Continuing Training Simulator Evaluations
NOBP-TR-1112
Conduct of Simulator Training and Evaluation
NOBR-TR-1271
Operator License Administration
NOP-TR-1010
Licensed Operator Requalification Exam Development and
Administration
NOP-TR-1280
Simulator Configuration Management
Self-Assessments Assessment ATA-
22-0659
NRC 71111.11 Inspections Preparations
21-00083
Training Simulator Phone System Stopped Working
01/06/2021
22-04375
Simulator Malfunction Could Not be Removed During an
Evaluated Scenario
05/24/2022
Corrective Action
Documents
22-04403
EP Drill: Simulator Computer Point Did Not Display
Correctly
05/25/2022
ALARA Plans
2-2010
Troubleshoot/Repair/Replace Nuclear Instrumentation 1
Detector
Corrective Action
Documents
22-09351
RCP1-2 Shaft Alignment As-Found Data Out of Tolerance
2/08/2022
264
Schematic Diagram Source Range Channel Sub Assembly
'A'
Drawings
C-149
Containment Internal Structures Reactor Seal Ring Details
Sheet 2
Engineering
Evaluations
601383951
Evaluate RCP 1-2 Shaft Alignment Data
2/09/2022
End of Day Shift Package
2/10/2022
601384078
Request to Store Old NI Detector in Containment on 603'
Elevation
String Work Package
CA9900131
Degradation and Life Expectancy Tests for BF3 Detectors
Miscellaneous
ODMI 22-06
Operation with Reactor Coolant Pump 1-2 Indications of
Degraded Seal Performance
DB-MI-03452
Channel Calibration of 78A-ISN101 Source Range Neutron
Flux and Rate to RPS Channel 2
Procedures
DB-MI-09023
RCP 1-1
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
DB-MM-03006
Examination of Safety Related Hydraulic Snubbers
DB-MM-09012
RCP Seal Removal and Replacement
DB-MM-09108
Removal and Installation of Snubbers
DB-MM-09117
Reactor Coolant Pump Maintenance
DB-MM-09266
Torquing
200833803
AFW Train 1 Level Control, Interlock and Flow Transmitter
Test
10/09/2022
200835994
AFW Train 1 Level Control, Interlock and Flow Transmitter
Test
11/05/2022
200835995
AFPT 1 Inlet Isolation
11/06/2022
200881008
RCP 1-2 Seal Replacement
2/05/2022
200895775
Low Suction Pressure Switch 1 AFP
11/22/2022
Work Orders
200898520
Contingent Detector Replacement, Troubleshooting
2/12/2022
ALARA Plans
2-2010
Troubleshoot/Repair/Replace Nuclear Instrumentation 1
Detector
Corrective Action
Documents
22-09383
RCP 1-2 Schedule Logic Omission
2/09/2022
264
Schematic Diagram Source Range Channel Sub Assembly
'A'
Drawings
C-149
Containment Internal Structures Reactor Seal Ring Details
Sheet 2
End of Day Shift Package
2/10/2022
Contingency Plan for RCS Drain Below Flange Level and
Operation Below 80 Inches Above the RCS Hot Leg
Centerline
11/14/2022
Shutdown Defense In-Depth Review Sheet, Forced Outage
11/14/2022
601384078
Request to Store Old NI Detector in Containment on 603'
Elevation
String Work Package
Miscellaneous
CA9900131
Degradation and Life Expectancy Tests for BF3 Detectors
DB-MI-03452
Channel Calibration of 78A-ISN101 Source Range Neutron
Flux and Rate to RPS Channel 2
Procedures
DB-OP-06904
Shutdown Operations
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
DBBP-OPS-0003
On-Line Risk Management Process
01/27/2021
NG-DB-00001
On-Line Risk Management
NOP-OP-1007
Risk Management
200833803
AFW Train 1 Level Control, Interlock and Flow Transmitter
Test
10/09/2022
200835994
AFW Train 1 Level Control, Interlock and Flow Transmitter
Test
11/05/2022
Work Orders
200835995
AFPT 1 Inlet Isolation
11/06/2022
22-02170
Electrical Penetration 101 Exceeds Maximum Allowable
Total Leakage Rate
03/14/2022
22-02902
Electrical Penetration Room 1 Nitrogen Flow High
04/01/2022
22-02950
FI6443, Nitrogen Flow to Electrical Penetration Room 2,
Reading Greater Than 550 CC/M
04/03/2022
22-07811
Shift in RCS Delta Tcold
10/16/2022
22-07891
SASS Tcold Instrument String Could Not be Returned to
Auto
10/18/2022
22-08004
10/21/2022
22-08234
Reactor Coolant Loop 1 Cold Leg Narrow Range T780 Step
Change
10/30/2022
22-09292
1M23 - BACC: Leak on Pipe Cap of DH48A
2/07/2022
22-09324
1M23 - BACC: Boric Acid Deposits Identified on DH12
2/08/2022
Corrective Action
Documents
22-09351
RCP1-2 Shaft Alignment As-Found Data Out of Tolerance
2/08/2022
Engineering
Evaluations
601383951
Evaluate RCP 1-2 Shaft Alignment Data
2/09/2022
ISTB4
Pump and Valve Basis Document
Miscellaneous
ODMI 22-06
Operation with Reactor Coolant Pump 1-2 Indications of
Degraded Seal Performance
DB-MM-03006
Examination of Safety Related Hydraulic Snubbers
DB-MM-09012
RCP Seal Removal and Replacement
DB-MM-09108
Removal and Installation of Snubbers
DB-MM-09117
Reactor Coolant Pump Maintenance
DB-MM-09266
Torquing
Procedures
DB-OP-06411
Station Annunciator Operating Procedure
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
NOPB-WM-4004
Critical Maintenance Identification and Execution
200881008
Align Right 11424 RCP 1-2 Seal Rebuild with PM 2415 RCP
1-2 Seal
2/05/2022
200895721
Request Forced Outage
11/18/2022
Work Orders
200897623
Annunciator and Miscellaneous Power Supply
11/30/2022
Calculations
VBW07/B001-043
Evaluation of Auxiliary Building Masonry Wall 5337 at
Elevation 623'0"
10/10/2017
Corrective Action
Documents
2019-01345
New SAMG Input Will Not be Corrected in Initial Revision
2/13/2019
14-0629
Reinforcement of Block Wall 5337
Engineering
Changes
14-0629-001
Reinforcement of Door 509 Frame and Associated Analysis
of Block Wall 5337
Miscellaneous
Maintenance Rule
2016-08324/2016-13970
2/09/2016
DB SAMG-BASES
SAMG Bases
DPG
Diagnostic Process Guideline
NG-EN-00550
Severe Accident Management
PWROG-15015-P
PWR Owners Group Severe Accident Management
Guidelines
SAG-1
Technical Support Center Severe Accident Guideline - Initial
Response
SAG-10
Technical Support Center Severe Accident Guideline
Control SFP Level
SAG-2
Technical Support Center Severe Accident Guideline - TSC
Recommending Strategies
SAG-3
Technical Support Center Severe Accident Guideline -
Injection into Steam Generators
SAG-4
Technical Support Center Severe Accident Guideline -
Depressurize RCS
SAG-5
Technical Support Center Severe Accident Guideline - Inject
into RCS
SAG-6
Technical Support Center Severe Accident Guideline - Inject
into Containment
Procedures
SAG-7
Technical Support Center Severe Accident Guideline -
Reduce Containment Hydrogen
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
SAG-8
Technical Support Center Severe Accident Guideline -
Control Containment Pressure
SAG-9
Technical Support Center Severe Accident Guideline -
Mitigate Fission Product Release
Technical Support Guideline - Instrumentation
Technical Support Guideline - SAMG Ultimate
Decisionmaker
Technical Support Guideline - Site Capabilities Technical
Support Information
Technical Support Guideline - Benefit Consequence
Technical Support Guideline - Computational Aids
ALARA Plans
2-2010
Troubleshoot/Repair/Replace Nuclear Instrumentation 1
Detector
Corrective Action
Documents
22-09351
RCP1-2 Shaft Alignment As-Found Data Out of Tolerance
2/08/2022
264
Schematic Diagram Source Range Channel Sub Assembly
'A'
Drawings
C-149
Containment Internal Structures Reactor Seal Ring Details
Sheet 2
End of Day Shift Package
2/10/2022
601384078
Request to Store Old NI Detector in Containment on 603'
Elevation
String Work Package
CA9900131
Degradation and Life Expectancy Tests for BF3 Detectors
Miscellaneous
ODMI 22-06
Operation with Reactor Coolant Pump 1-2 Indications of
Degraded Seal Performance
DB-MI-03452
Channel Calibration of 78A-ISN101 Source Range Neutron
Flux and Rate to RPS Channel 2
DB-MI-05145
Source Range Detector High Voltage and Discriminator
Setting Procedure
DB-MM-03006
Examination of Safety Related Hydraulic Snubbers
DB-MM-09012
RCP Seal Removal and Replacement
DB-MM-09108
Removal and Installation of Snubbers
Procedures
DB-MM-09117
Reactor Coolant Pump Maintenance
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
DB-MM-09266
Torquing
DB-PF-03030
Service Water Pump 3 Testing
NOPB-WM-4004
Critical Maintenance Identification and Execution
200748084
PM 6636 Replace PCV2988 and PCV2988A
10/13/2022
200767904
PM 6142 MP43-1, Motor Testing, CCW 101 P
10/10/2022
200804006
PM 2907 Calculation EDG 1 Air Receiver
09/19/2022
200833294
AFP 1 Quarterly Test
10/04/2022
200835995
AFPT 1 Inlet Isolation
11/06/2022
200836400
AFP 2 Quarterly Test
11/15/2022
200840426
CCW Pump 1 Quarterly Test
11/29/2022
Work Orders
200881008
Align Right 11424 RCP 1-2 Seal Rebuild with PM 2415 RCP
1-2 Seal
2/05/2022
Miscellaneous
Restart readiness Package
DB-SP-03357
RCS Water Inventory Balance
DB-SP-03357
RCS Water Inventory Balance
Procedures
DB-SP-03357
RCS Water Inventory Balance
Work Orders
200836400
AFP 2 Quarterly Test
11/15/2022
Davis-Besse Nuclear Power Station Emergency Plan
Miscellaneous
Davis-Besse Nuclear Power Station Emergency Plan
Procedures
CFR 50.54(q)3
Screen/Evaluation:
DB-2020-015-00
DBNPS Emergency Plan Revision 35
09/08/2020
NOP-LP-5501
Accident Assessment
NOP-LP-5502
Event Classification
NOP-LP-5503
Emergency Notifications
NOP-LP-5504
Protective Measures
NOP-LP-5505
Facility Activation, Operation and De-Activation
Procedures
NOP-LP-5506
Termination and Recovery
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
Resulting from
Inspection
22-09428
NRC Observation of Alpha Survey on RCP 1-2 Seal
2/13/2022
Miscellaneous
Standing Order
22-001
Alpha Contamination Risk Level Assignments
01/04/2022
Procedures
NOP-OP-4903
Determination of Alpha Monitoring Levels
Radiation
Surveys
DB-I-20220328-10
RCP 1-2 Seal Replacement
03/28/2022
Radiation Work
Permits (RWPs)
2-2005
Reactor Coolant Pump 1-2 Seal
11/23/2022
CR-2022-09426
NRC identified Tritium Sampling Basis Methodology Was
Not Determined
2/13/2022
Corrective Action
Documents
Resulting from
Inspection
CR-2022-09427
NRC Observation Low Level Radwaste Storage Facility
Effluent Release Point
2/13/2022
White Paper - DBNPS Tritium Sampler Flow Rate Inquiry
Date Not
Provided
Miscellaneous
Davis-Besse Low-Level Radiation Waste Storage Facility
Position
Date Not
Provided
Corrective Action
Documents
22-02351
1R22 Repack of AVV DB-ICS11A Identified Incorrect
03/17/2022
Drawings
645141-1
Drag Valve
D
ASME 2008a
Section XI,
Division 1
Article IWA-4000 Repair/Replacement Activities
04/14/2010
Miscellaneous
Vendor Certificate
Certificate of conformance, Control Components Inc.
06/30/1994
Procedures
DB-PF-03440
Atmospheric Vent Valves, ICS11A and ICS11B, Operability
Test
200817842
Repack ICS11A during IR11
03/14/2022
Work Orders
200822911
Main Steam Line 1 Atmospheric Vent Valve
03/29/2022
21-01278
Sinkhole Near Security Warehouse
2/25/2021
21-02075
Sinkhole in Zone 9 Degrading Stone Near Perifield
03/21/2021
21-02350
Sink Hole in Owner Controlled Area
03/29/2021
Corrective Action
Documents
21-04199
Small Sinkhole Identified South of Wellness Center
05/24/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
21-04366
Potential Sinkhole Near Water Treatment Plant
06/01/2021
21-04728
Sinkhole Identified in Security Isolation Zone
06/16/2021
21-05651
Potential Sinkhole North of Circ Pump House
07/25/2021
21-05696
Sinkholes in the Protected Area
07/27/2021
21-08529
Sinkhole Under Sidewalk
11/08/2021
22-01260
Degraded Storm Drain and Sinkhole Identified in ROCA
2/18/2022
22-02401
Cooling Tower Bypass Pipe Support Settlement/Sinkhole
03/19/2022
22-02401
Cooling Tower Bypass Pipe Support Settlement/Sinkhole
03/19/2022
22-03985
Duct Bank Not on Site Drawings Discovered During
Sinkhole Excavation
05/10/2022
22-06310
Sinkhole Training Center Contractor Lot
08/16/2022
22-06310
Sinkhole Training Center Contractor Lot
08/16/2022
22-06365
Assessment Identified Temporary Configuration Change
Process Non-Compliance Issues
08/17/2022
22-06519
ECCS Sump Pump Discharge Piping Temporary Leak
Repairs to Remain in Place for additional Cycle
08/24/2022
22-06639
Temporary Leak Repairs that Remained in Place Past 1R22
08/29/2022
22-07031
Possible Sinkhole/Trip Hazard Along Safe Walkway
Southwest of the Primary Access Facility
09/15/2022
22-07575
North Underground Fire Protection Loop Pipe Rupture
1010/2022
22-07790
Potential Sinkhole Near AC Transformer
10/15/2022
22-07790
Potential Sinkhole Near AC Transformer
10/15/2022
22-09856
Potential Sinkhole Identified in Personnel Walkway Between
PSF and South PAC
2/29/2022
22-09879
Potential Water Leak Near Fire Protection Valve 43
2/31/2022
Corrective Action
Documents
Resulting from
Inspection
22-07735
NRC Questions/Concerns Concerning CR 2022-03195
Investigation
10/13/2022
118817
Seal Leak Meter Assembly
Drawings
Pump Sectional, Reactor Coolant Pump
H
M-530-00452-02
Vendor Manual, RCP Seal Leak Meter
05/03/2005
Miscellaneous
2013-14401, Recommendations for Operating with
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Recommendation
Summary Sheet
Degraded RCP 1-1 Third Stage Seal Performance
Procedures
NG-EN-00327
RCS Integrated Leakage Program
2