IR 05000346/2022001
| ML22131A379 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 05/12/2022 |
| From: | Billy Dickson NRC/RGN-III/DRP/B2 |
| To: | Tony Brown Energy Harbor Nuclear Corp |
| References | |
| IR 2022001 | |
| Download: ML22131A379 (15) | |
Text
SUBJECT:
DAVIS-BESSE NUCLEAR POWER STATION - INTEGRATED INSPECTION REPORT 05000346/2022001
Dear Mr. Brown:
On March 31, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Davis-Besse Nuclear Power Station. On April 28, 2022, 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 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-2022-001-0061
Licensee:
Energy Harbor Nuclear Corporation
Facility:
Davis-Besse Nuclear Power Station
Location:
Oak Harbor, OH
Inspection Dates:
January 01, 2022 to March 31, 2022
Inspectors:
D. Mills, Senior Resident Inspector
R. Cassara, Resident Inspector
J. Cassidy, Senior Health Physicist
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
Unit 1 began the inspection period at rated thermal power. On February 5, 2022, plant operators reduced reactor power to approximately 15 percent following an inadvertent isolation of the reactor coolant system letdown during a planned letdown demineralizer swap. The plant operators increased reactor power to 93 percent between February 7 and February 17, 2022.
Shortly after that, the unit entered coast-down operations and began a scheduled refueling outage on March 4, 2022. The unit remained shut down in the refueling outage 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
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 winter storms during the week ending February 5, 2022.
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (2 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Decay heat removal train 1 during the week ending March 12, 2022
- (2) Service water system during the week ending March 19, 2022
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (4 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) Shield building annulus, fire areas A and AB, during the week ending March 19, 2022
- (2) Containment building 565', 585', 603' elevations, fire area D, during the week ending April 2, 2022
- (3) Diesel generator 1-2 room, fire area J, during the week ending March 19, 2022
- (4) Containment under vessel area, east-west tunnel, East and West D-rings, fire area D, during the week ending April 2, 2022
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (3 Samples)
- (1) The inspectors observed and evaluated licensed operator performance in the control room following a forced power reduction during the week ending February 5, 2022, and power ascension including main feedwater pump operations during the week ending February 12, 2022
- (2) The inspectors observed and evaluated licensed operator performance in the control room during power reduction for refueling outage 1R22, including main feedwater pump operations, turbine trip, and low power operation during the week ending March 5, 2022
- (3) The inspectors observed and evaluated licensed operator performance in the control room during yellow risk while the reactor coolant system inventory was reduced for refueling operations during the week ending April 2, 2022
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated licensed operator requalification simulator scenarios during the week ending February 19, 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) Replacement of containment pressure power supply and bistables BA409 and BA410 for safety features actuation system channel 4 during the week ending February 19, 2022
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (4 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) Refueling outage risk plan during the week ending March 5, 2022
- (2) Risk management during yellow risk due to reactor coolant system reduced inventory for handhole removal and nozzle dam installation during the week ending March 12, 2022
- (3) Risk management during reactor vessel head detention and lift during the week ending March 12, 2022
- (4) Risk management during reactor vessel head installation during the week ending April 2, 2022
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (6 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Decay Heat Pump 2 - oil leak at outboard pump bearing (regarding the use of the pump in decay heat mode), CR 2022-03165, during the week ending March 26, 2022
- (2) Foreign material found in reactor vessel integrated head assembly, CR 2022-02851, during the week ending March 26, 2022
- (3) Cooling tower foundation settlement, CR 2022-02411, during the week ending March 26, 2022
- (4) Snubber SNC283 discovered with no oil in reservoir, CR 2022-01703, during the week ending April 2, 2022
- (5) MS100 limit switch issue, CR 2022-01780, during the week ending April 2, 2022 (6)
1R22 Main transformer X1 identification of broken B phase winding shield ground,
CR 2022-02186, during the week ending March 19, 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) Emergency diesel generator 2 speed switch replacement during the week ending January 22, 2022
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated the following post-maintenance testing activities to verify system operability and/or functionality:
- (1) Emergency diesel generator 2 post maintenance test following installation of new speed switch during the week ending January 22, 2022
- (2) Safety features actuation system post maintenance test following installation of containment pressure power supply and bistables BA409 and BA410 during the week ending February 19, 2022
- (3) Auxiliary feedwater pump 1 functional test following scheduled maintenance during the week ending February 26, 2022
- (4) Local leak rate testing of penetration 34, containment vessel purge outlet line, following maintenance during the week ending April 2, 2022
- (5) Decay heat pump 2 following outboard bearing and seal replacement during the week ending March 26, 2022
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated refueling outage 1R22 activities from March 4, 2022 through April 19, 2022
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance testing activities to verify system operability and/or functionality:
Surveillance Tests (other) (IP Section 03.01) (6 Samples)
- (1) Containment spray pump 2 quarterly test during the week ending January 15, 2022
- (2) Demineralizer filter 1-1 change during the week ending February 12, 2022
- (3) Auxiliary feedwater pump 1 quarterly test during the week ending February 26, 2022
- (4) Turbine overspeed trip test during the week ending March 5, 2022
- (5) Safety features actuation system integrated testing during the week ending March 26, 2022
- (6) Local leak rate testing of penetration 102, electrical penetration PCC5V during the week ending March 12, 2022
Inservice Testing (IP Section 03.01) (1 Sample)
- (1) Main steam safety valve testing during the week ending March 5, 2022
Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)
- (1) Local leak rate testing of penetration 34, containment vessel purge outlet line during the week ending April 2,
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 how the licensee instructs workers on plant-related radiological hazards and the radiation protection requirements intended to protect workers from those hazards
Contamination and Radioactive Material Control (IP Section 03.03) (2 Samples)
The inspectors observed/evaluated the following licensee processes for monitoring and controlling contamination and radioactive material:
- (1) Licensee surveys of workers and potentially contaminated material leaving the radiologically controlled area (RCA) at the contractors access facility control point during the Unit 1 refueling outage
- (2) Licensee surveys of workers and potentially contaminated material leaving the RCA at the main control point during the Unit 1 refueling outage
Radiological Hazards Control and Work Coverage (IP Section 03.04) (3 Samples)
The inspectors evaluated the licensee's control of radiological hazards for the following radiological work:
- (1) Movement of reactor head / plenum / core barrel and associated preparation
- (2) Incore cutting / cask transfer / post incore cutting tank decontamination
- (3) Installation / removal of once through steam generator nozzle dams and foreign material covers 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) Locked high radiation area barricade surrounding the Unit 1 incore tank
- (2) Locked high radiation area postings and locks on the steam generator manway shield door 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.
71124.03 - In-Plant Airborne Radioactivity Control and Mitigation
Temporary Ventilation Systems (IP Section 03.02) (1 Sample)
The inspectors evaluated the configuration of the following temporary ventilation systems:
- (1) Temporary high efficiency particulate air [filter] (HEPA) unit supporting the stud cleaning tent
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On April 28, 2022, the inspectors presented the integrated inspection results to Mr. T. Brown, Site Vice President, and other members of the licensee staff.
On March 18, 2022, the inspectors presented the radiation protection inspection results to Mr. T. Brown, Site Vice President, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
DB-OP-06331
Freeze Protection and Electrical Heat Trace
DB-OP-06913
Seasonal Plant Preparation Checklist
DB-OPS-0011
Protected Equipment Posting
NOP-WM-2002
Seasonal Readiness Process
Procedures
RA-EP-02870
Emergency Plan Off-Normal Occurrence
DB-OP-06012
Decay Heat and Low-Pressure Injection System Operating
Procedure
Procedures
DB-OP-06261
Service Water System Operating Procedure
2019-05984
PI 20436 Over Ranged
Corrective Action
Documents
21-08257
EDG Room 2 Vent Fan Recirc Supply Damper Not Fully
Open with Hydro-Motor De-Energized
Diesel Generator 1-2 Room, Rooms 319 and 318A,
Fire Area J
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 317A, Fire Area
D
East Elevation 603' and Valve Room Elevation 636', Rooms
410 and 508, Fire Area D
Southwest Penetration Area of Annulus Space Elevations
585' and 603', Partial Room 127W, Fire Area AB
East and Southwest Penetration Areas at Elevations 585' and
603', Partial Rooms 127W and 127W, Fire Area A and AB
East Penetration Area of Annulus Space Elevations 585' and
603', Partial room 127E, Fire Area A
North Area 565' Elevation, Rooms 213, 217 and Normal
Sump Area, Fire Area D
Fire Plans
Fuel Transfer Pool and North and West 603' Elevation
Rooms 219, 407 and 410A, Fire Area D
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
DB-M-20220305-
Annulus Down-Post from lHRA to RA
03/05/2022
2019-04383
Multiple SFAS Channel 4 Bistables Tripped High Out of Band
Corrective Action
Documents
22-01148
SFAS Bistable Difficult to Remove
2/15/2022
DB-MI-03118
Response Time Test of 59AISP2003 Containment Pressure
SFAS Channel 4
Procedures
DB-MI-05032
Performance/Post Maintenance Test of
LAMBDA/PENTAS/ACOPIAN/NJE Power Supplies
Work Orders
200762599
Containment Pressure High SFAS Channel 4
2/15/2022
Corrective Action
Documents
22-02550
Begin RCS Drain to Lowered Inventory
03/23/2022
Miscellaneous
IR22 Shutdown Defense In-Depth Report
Procedures
NOP-OP-1007
Risk Management
22-01703
Snubber SNC283 Discovered with no Oil in the Reservoir
03/05/2022
22-01780
MS100 Limit Switch Issue
03/07/2022
22-01936
1R22 Main Transformer Winding Shield Ground Accessibility
03/09/2022
22-02186
1R22 Main Transformer X1 Identification of Broken B Phase
Winding Shield Ground
04/13/2022
22-02585
DH Pump 2 Gland Plate Nut Found Loose
04/22/2022
Corrective Action
Documents
22-03165
Decay Heat Pump 2 - Oil Leak at Outboard Pump Bearing
04/10/2022
Drawings
Section A-A Typical Section Across Cooling Tower Ring
Footing
04/03/1984
20-01384
SFAS Channel 4 Reactor Coolant Pressure Bistables
Tripping Early
Corrective Action
Documents
20-07535
SFAS RC Pressure Lo Trip BA 404 Bistable Tripped Early
Miscellaneous
DB-PF-03008
PMT 200822941
03/31/2022
DB-MI-03114
Channel Functional Test/Calibration of 59A-ISP2003
Containment Pressure Input to SFAS Channel 4
DB-MI-05032
Performance/Post Maintenance Test of
LAMBDA/PENTAS/ACOPIAN/NJE Power Supplies
DB-MI-09072
SFAS Documentation for Module Testing
DB-PF-03007
Procedures
DB-SP-03444
SFRCS Channel 1 Trip of MS100 and MS101
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
DB-SP-03445
SFRCS Channel 2 Trip of MS100 and MS101
200809036
EDG 2 184-Day Test
01/18/2022
Work Orders
200809831
EDG 2 Monthly Test
2/19/2021
ATL-2022-0311-
ATA-02
Provide Copy of Reactor Undervessel Inspection
04/08/2022
Corrective Action
Documents
ATL-2022-0311-
ATA-03
Provide Copy of Reactor Head Inspection
04/06/2022
Miscellaneous
DB-PF-03008
PMT 200822941
03/31/2022
DB-PF-03001
Main Steam Safety Valve Setpoint Test
DB-PF-03007
DB-SC-03121
SFAS Train 2 Integrated Response Time Test
Procedures
DB-SP-03338
Containment Spray Train 2 Quarterly Pump and Valve Test
200756129
Integrated SFAS Act Channel 2 Test
03/03/2020
200761833
CAC Unit 2 Monthly Test
06/07/2021
200762597
Containment Pressure High SFAS Channel 2 Test
01/25/2022
200789025
Main Turbine Stop Valves
09/17/2021
200789026
09/17/2021
200789027
Main Turbine CIV Test
09/17/2021
200798159
CTMT Press SFAS Chanel 3 R/T Test
2/09/2021
200800405
Emergency Feedwater Pump Quarterly Test
09/03/2021
200804747
Emergency Ventilation System Train 2 Refueling Interval
SFAS Drawdown
11/26/2021
200809663
CS9 Forward Flow Test
01/12/2022
200809664
200809665
Containment Spray Pump 2 Quarterly
200809985
CC1338 Stroke Test
2/10/2022
200810110
Train 2 Stroke Valve Strokes Test
2/15/2021
200811153
RC LP 1 PR SFAS Channel 3 R/T Test
2/02/2019
200822233
Stroke Time Refuel Coast Down Test
03/08/2022
200822470
Integrated SFAS ACT Channel 2 Test
03/16/2022
200822471
Integrated SFAS Act Channel 2 Test
03/16/2022
200822473
HP2A/2B Discharge Valve Test
03/17/2022
Work Orders
200822572
03/04/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
200828471
SFAS O/ALL R/T Calculation Maintenance Test
05/13/2021
200844948
MB8630 SP17B3 MSSV Test
03/02/2022
200844949
BM8644 SP17A9 MSSV Test
03/02/2022
200844951
BM8053 SP17B7 MSSV Test
03/02/2022
200844952
BM8632 SP17B1 MSSV Test
03/02/2022
200844953
BM8635 SP17B8 MSSV Test
03/02/2022
200844954
BM8640 SP17A6 MSSV Test
03/02/2022
200844955
BM8643 SP17B2 MSSV Test
03/02/2022
200844956
BM8645 SP17A1 MSSV Test
03/02/2022
200856618
SFAS O/ALL R/T Calculation Maintenance Test
2/10/2021
200860045
Main Steam Line 2 Code Safety
2/21/2022
200871109
SFAS Channel 3 BWST Level LO Output Module
01/05/2022
CR-2022-01874
Personnel Contamination Event (Action Level 2)
03/08/2022
CR-2022-01929
Personal Contamination Event - Level 3 PCE
03/09/2022
Corrective Action
Documents
CR-2022-02060
Positive Whole-Body Count on S/G Platform Worker
03/12/2022
CR-2022-02249
RWP 122-5114 Task 1 Needs Hold Point Revision
03/15/2022
Corrective Action
Documents
Resulting from
Inspection
CR-2022-02294
Vendor Sealand Containers Were Not Locked
03/16/2022
DB-HP-01702
Transfer, Handling, and Storage of Radioactive Material
Procedures
NOP-OP-4702
Air Sampling and Analysis
Radiation
Surveys
DB-M-20220315-
Core Barrel Lift for 10 Year ISI
03/15/2022
2-5105
Movement of Reactor Head / Plenum / Core Barrel and
Associated Preparation
2-5114
Incore Cutting / Cask Transfer / Post Incore Cutting Tank
Decontamination
2-5114
Incore Cutting / Cask Transfer / Post Incore Cutting Tank
Decontamination
Radiation Work
Permits (RWPs)
2-5301
Installation / Removal of Once Through Steam Generator
Nozzle Dams and Foreign Material Covers
Corrective Action
Documents
22-00382
Fuel Handling Rollup Door - West Damage from Truck
01/18/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
22-00880
Main Feed Pump 1 Integrated Control System Controller
Abnormal Indication
2/05/2022
22-00881
Auxiliary Boiler Failed to Fire
2/05/2022
22-00883
Heater Drain Pump 1 Tripped during Downpower and was
Found Rotating Backward
2/05/2022
22-00893
MPF 1 did Not Transfer from ICS to MDT-20 Control
2/06/2022
22-00900
Feedwater Transient during Rapid Shutdown
2/06/2022
22-00903
Letdown Pressure Spike After Initial Restoration
2/06/2022
Corrective Action
Documents
22-00908
Unable to Match Incoming and Running Volts to Sync Main
Generator to the Grid
2/06/2022