IR 05000346/2022001

Integrated Inspection Report 05000346/2022001

ML22131A379
Person / Time
Site:	Davis Besse
Issue date:	05/12/2022
From:	Billy Dickson NRC/RGN-III/DRP/B2
To:	Brown T Energy Harbor Nuclear Corp
References
IR 2022001
Download: ML22131A379 (15)

Text

May 12, 2022

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, Signed by Dickson, Billy on 05/12/22 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: NPF-3 Report Number: 05000346/2022001 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 Enclosure

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.

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,

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 Type Designation Description or Title Revision or

Procedure Date

71111.01 Procedures DB-OP-06331 Freeze Protection and Electrical Heat Trace 33

DB-OP-06913 Seasonal Plant Preparation Checklist 41

DB-OPS-0011 Protected Equipment Posting 16

NOP-WM-2002 Seasonal Readiness Process 0

RA-EP-02870 Emergency Plan Off-Normal Occurrence 7

71111.04 Procedures DB-OP-06012 Decay Heat and Low-Pressure Injection System Operating 84

Procedure

DB-OP-06261 Service Water System Operating Procedure 74

71111.05 Corrective Action 2019-05984 PI 20436 Over Ranged 0

Documents 2021-08257 EDG Room 2 Vent Fan Recirc Supply Damper Not Fully 0

Open with Hydro-Motor De-Energized

Fire Plans PFP-AB-319 Diesel Generator 1-2 Room, Rooms 319 and 318A, 8

Fire Area J

PFP-CB-214 Core Flooding Tank Area, Room 214, Fire Area D 6

PFP-CB-215 Let Down Coolers Area, Room 215, Fire Area D 6

PFP-CB-216 Steam Generator West D Ring Area, Room 216, Fire Area D 6

PFP-CB-218 Steam Generator East D Ring Area, Room 218, Fire Area D 6

PFP-CB-317 Containment Air Cooler Area, Room 317 and 317A, Fire Area 8

D

PFP-CB-410 East Elevation 603' and Valve Room Elevation 636', Rooms 5

410 and 508, Fire Area D

PFP-CB-A208 Southwest Penetration Area of Annulus Space Elevations 8

585' and 603', Partial Room 127W, Fire Area AB

PFP-CB-A236H East and Southwest Penetration Areas at Elevations 585' and 8

603', Partial Rooms 127W and 127W, Fire Area A and AB

PFP-CB-A236L East Penetration Area of Annulus Space Elevations 585' and 5

603', Partial room 127E, Fire Area A

PFP-CB-EL565 North Area 565' Elevation, Rooms 213, 217 and Normal 8

Sump Area, Fire Area D

PFP-CB-EL603 Fuel Transfer Pool and North and West 603' Elevation 5

Rooms 219, 407 and 410A, Fire Area D

Inspection Type Designation Description or Title Revision or

Procedure Date

Miscellaneous DB-M-20220305- Annulus Down-Post from lHRA to RA 03/05/2022

71111.12 Corrective Action 2019-04383 Multiple SFAS Channel 4 Bistables Tripped High Out of Band 0

Documents 2022-01148 SFAS Bistable Difficult to Remove 02/15/2022

Procedures DB-MI-03118 Response Time Test of 59AISP2003 Containment Pressure 12

SFAS Channel 4

DB-MI-05032 Performance/Post Maintenance Test of 13

LAMBDA/PENTAS/ACOPIAN/NJE Power Supplies

Work Orders 200762599 Containment Pressure High SFAS Channel 4 02/15/2022

71111.13 Corrective Action 2022-02550 Begin RCS Drain to Lowered Inventory 03/23/2022

Documents

Miscellaneous IR22 Shutdown Defense In-Depth Report 0

Procedures NOP-OP-1007 Risk Management 36

71111.15 Corrective Action 2022-01703 Snubber SNC283 Discovered with no Oil in the Reservoir 03/05/2022

Documents 2022-01780 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 04/13/2022

Winding Shield Ground

22-02585 DH Pump 2 Gland Plate Nut Found Loose 04/22/2022

22-03165 Decay Heat Pump 2 - Oil Leak at Outboard Pump Bearing 04/10/2022

Drawings 80C435-C Section A-A Typical Section Across Cooling Tower Ring 04/03/1984

Footing

71111.19 Corrective Action 2020-01384 SFAS Channel 4 Reactor Coolant Pressure Bistables 0

Documents Tripping Early

20-07535 SFAS RC Pressure Lo Trip BA 404 Bistable Tripped Early 0

Miscellaneous DB-PF-03008 PMT 200822941 03/31/2022

Procedures DB-MI-03114 Channel Functional Test/Calibration of 59A-ISP2003 12

Containment Pressure Input to SFAS Channel 4

DB-MI-05032 Performance/Post Maintenance Test of 13

LAMBDA/PENTAS/ACOPIAN/NJE Power Supplies

DB-MI-09072 SFAS Documentation for Module Testing 5

DB-PF-03007 LLRT 1

DB-SP-03444 SFRCS Channel 1 Trip of MS100 and MS101 13

Inspection Type Designation Description or Title Revision or

Procedure Date

DB-SP-03445 SFRCS Channel 2 Trip of MS100 and MS101 15

Work Orders 200809036 EDG 2 184-Day Test 01/18/2022

200809831 EDG 2 Monthly Test 12/19/2021

71111.20 Corrective Action ATL-2022-0311- Provide Copy of Reactor Undervessel Inspection 04/08/2022

Documents ATA-02

ATL-2022-0311- Provide Copy of Reactor Head Inspection 04/06/2022

ATA-03

71111.22 Miscellaneous DB-PF-03008 PMT 200822941 03/31/2022

Procedures DB-PF-03001 Main Steam Safety Valve Setpoint Test 10

DB-PF-03007 LLRT 1

DB-SC-03121 SFAS Train 2 Integrated Response Time Test 11

DB-SP-03338 Containment Spray Train 2 Quarterly Pump and Valve Test 33

Work Orders 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 Main turbine Control Valves 09/17/2021

200789027 Main Turbine CIV Test 09/17/2021

200798159 CTMT Press SFAS Chanel 3 R/T Test 12/09/2021

200800405 Emergency Feedwater Pump Quarterly Test 09/03/2021

200804747 Emergency Ventilation System Train 2 Refueling Interval 11/26/2021

SFAS Drawdown

200809663 CS9 Forward Flow Test 01/12/2022

200809664 CS 1531 Stroke Test FA Norm 0

200809665 Containment Spray Pump 2 Quarterly 0

200809985 CC1338 Stroke Test 02/10/2022

200810110 Train 2 Stroke Valve Strokes Test 12/15/2021

200811153 RC LP 1 PR SFAS Channel 3 R/T Test 12/02/2019

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

200822572 Main Turbine Overspeed Trip 03/04/2022

Inspection Type Designation Description or Title Revision or

Procedure 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 12/10/2021

200860045 Main Steam Line 2 Code Safety 02/21/2022

200871109 SFAS Channel 3 BWST Level LO Output Module 01/05/2022

71124.01 Corrective Action CR-2022-01874 Personnel Contamination Event (Action Level 2) 03/08/2022

Documents CR-2022-01929 Personal Contamination Event - Level 3 PCE 03/09/2022

CR-2022-02060 Positive Whole-Body Count on S/G Platform Worker 03/12/2022

Corrective Action CR-2022-02249 RWP 122-5114 Task 1 Needs Hold Point Revision 03/15/2022

Documents CR-2022-02294 4 Vendor Sealand Containers Were Not Locked 03/16/2022

Resulting from

Inspection

Procedures DB-HP-01702 Transfer, Handling, and Storage of Radioactive Material 27

NOP-OP-4702 Air Sampling and Analysis 8

Radiation DB-M-20220315- Core Barrel Lift for 10 Year ISI 03/15/2022

Surveys 7

Radiation Work 122-5105 Movement of Reactor Head / Plenum / Core Barrel and 0

Permits (RWPs) Associated Preparation

2-5114 Incore Cutting / Cask Transfer / Post Incore Cutting Tank 1

Decontamination

2-5114 Incore Cutting / Cask Transfer / Post Incore Cutting Tank 2

Decontamination

2-5301 Installation / Removal of Once Through Steam Generator 0

Nozzle Dams and Foreign Material Covers

71152A Corrective Action 2022-00382 Fuel Handling Rollup Door - West Damage from Truck 01/18/2022

Documents

Inspection Type Designation Description or Title Revision or

Procedure Date

71152S Corrective Action 2022-00880 Main Feed Pump 1 Integrated Control System Controller 02/05/2022

Documents Abnormal Indication

22-00881 Auxiliary Boiler Failed to Fire 02/05/2022

22-00883 Heater Drain Pump 1 Tripped during Downpower and was 02/05/2022

Found Rotating Backward

22-00893 MPF 1 did Not Transfer from ICS to MDT-20 Control 02/06/2022

22-00900 Feedwater Transient during Rapid Shutdown 02/06/2022

22-00903 Letdown Pressure Spike After Initial Restoration 02/06/2022

22-00908 Unable to Match Incoming and Running Volts to Sync Main 02/06/2022

Generator to the Grid

13