IR 05000346/2022003

Integrated Inspection Report 05000346/2022003

ML22314A166
Person / Time
Site:	Davis Besse
Issue date:	11/10/2022
From:	Billy Dickson NRC/RGN-III/DORS/RPB2
To:	Tony Brown Energy Harbor Nuclear Corp
References
IR 2022003
Download: ML22314A166 (21)

Text

SUBJECT:

DAVIS-BESSE NUCLEAR POWER STATION - INTEGRATED INSPECTION REPORT 05000346/2022003

Dear Terry Brown:

On September 30, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Davis-Besse Nuclear Power Station. On October 25, 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.

One finding of very low safety significance (Green) is documented in this report. This finding involved a violation of NRC requirements. We are treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2 of the Enforcement Policy.

If you contest the violation or the significance or severity of the violation documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN:

Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region III; the Director, Office of Enforcement; and the NRC Resident Inspector at Davis-Besse Nuclear Power Station.

If you disagree with a cross-cutting aspect assignment in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region III; and the NRC Resident Inspector at Davis-Besse Nuclear Power Station.November 10, 2022 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 No. 05000346 License No. NPF-3

Enclosure:

As stated

Inspection Report

Docket Number: 05000346

License Number: NPF-3

Report Number: 05000346/2022003

Licensee: Energy Harbor Nuclear Corp.

Facility: Davis-Besse Nuclear Power Station

Location: Oak Harbor, OH

Inspection Dates: July 01, 2022 to September 30, 2022

Inspectors: R. Cassara, Resident Inspector J. Cassidy, Senior Health Physicist D. Mills, Senior Resident Inspector J. Reed, Health Physicist

Approved By: Billy C. Dickson, Jr., Chief Reactor Projects Branch 2 Division of Operating Reactor Safety

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

Failure to Develop Appropriate Local Leak Rate Testing for Fuel Transfer Tubes Cornerstone Significance Cross-Cutting Report Aspect Section Barrier Integrity Green [H.6] - Design 71152S NCV 05000346/2022003-01 Margins Open/Closed The inspectors identified a Green finding and associated non-cited violation of Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix B, Criterion XI, Test Control.

Specifically, the licensee did not establish testing requirements and acceptance limits to provide reasonable assurance of containment integrity by detecting fuel transfer tube flange seal degradation as required by 10 CFR Part 50, Appendix B, Criterion XI. Failure to detect degradation of the fuel transfer tube flange seals could result in a loss of containment integrity. The licensee entered this issue into their corrective action program as condition reports 2022-03195.

Additional Tracking Items

Type Issue Number Title Report Section Status LER 05000346/2021-002-00 LER 2021-002-00 for 71153 Closed Davis-Besse Nuclear Power Station, Unit 1, Failure of Auxiliary Feedwater Rooms Interconnecting Door to Latch due to Worn Interlock LER 05000346/2021-003-00 LER 2021-003-00 for 71153 Closed Davis-Besse Nuclear Power Station, Unit 1, Reactor Trip due to Failed Uninterruptible Power Supply and Steam Feedwater Rupture Control System Actuations

PLANT STATUS

The unit operated at or near rated thermal power for the entire 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 weather of forecasted severe thunderstorms and high winds during the week ending July 23, 2022

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (4 Samples)

The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:

(1) Component cooling water (CCW) train 2 following pump maintenance during the week ending August 13, 2022

(2) Spent fuel pool cooling system during the week ending August 27, 2022

(3) Auxiliary feedwater train 1 while auxiliary feedwater train 2 out of service for scheduled maintenance during the week ending August 27, 2022

(4) Motor driven feed pump while emergency feedwater out of service for scheduled maintenance during the week ending September 24, 2022

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (5 Samples)

The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:

(1) Security data management system locations for the CAS/SAS (Central Alarm Station/Secondary Alarm Station) and security computer rooms during the week ending July 9, 2022

(2) Number 4 mechanical penetration room, rooms 115CC, 314 and 314CC, and fire area A, during water curtain outage the week ending August 13, 2022

(3) Emergency feedwater facility during the week ending September 10, 2022

(4) Auxiliary feed pump 1 and 2 rooms, room 237 and 238, fire area E and F during the week ending August 27, 2022

(5) Cable spreading room, room 422A, fire area DD during the week ending September 3, 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) High water in manholes 3009 and 3010, and inspection of manholes 3040, 3045, 3046, and 3005

71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance

Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)

(1) The inspectors observed and evaluated requalification simulator during drill on August 30, 2022

71111.12 - Maintenance Effectiveness

Maintenance Effectiveness (IP Section 03.01) (2 Samples)

The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:

(1) Control rod drive absolute position indicating power supply replacement after failure

(2) Integrated control system feedwater module replacement and calibration

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (3 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) Integrated control system feedwater module calibration causing delta cold leg temperature difference during the week ending August 27, 2022

(2) Risk management during scheduled emergency feedwater outage during the week ending September 24, 2022

(3) Containment entry at power to inspect for reactor coolant system leakage during the week ending September 17, 2022

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (1 Sample)

The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:

(1) Anticipatory reactor trip system channel 4 due to unexpected trip of control rod drive breaker C after opening the cabinet door during the week ending August 6, 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) CCW pump 2 rotor and seal package replacement during the week ending August 6, 2022

71111.19 - Post-Maintenance Testing

Post-Maintenance Test Sample (IP Section 03.01) (8 Samples)

The inspectors evaluated the following post-maintenance testing activities to verify system operability and/or functionality:

(1) Makeup pump 2 maintenance and PMT during the week ending July 30, 2022

(2) CCW pump 2 after rotor and seal package replacement during the week ending August 6, 2022

(3) Motor driven feed pump after scheduled maintenance during the week ending August 6, 2022

(4) Safety features actuation signal channel integrated testing following scheduled component replacement during the week ending August 20, 2022

(5) Auxiliary feedwater pump 2 quarterly test after scheduled maintenance during the week ending August 27, 2022

(6) High pressure injection pump 1 after flow transmitter calibration during the week ending September 17, 2022

(7) Emergency feedwater pump quarterly after planned maintenance during the week ending September 24, 2022

(8) Near full-power testing of turbine stop and control valves following installation of p-port orifices during the week ending September 24, 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) (1 Sample)

(1) Low pressure injection pump 1 quarterly during the week ending July 23, 2022

Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)

(1) Personnel hatch local leak rate testing during the week ending September 17, 2022

71114.06 - Drill Evaluation

Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)

The inspectors evaluated:

(1) Integrated drill on August 30,

71124.06 - Radioactive Gaseous and Liquid Effluent Treatment

Walkdowns and Observations (IP Section 03.01) (4 Samples)

The inspectors evaluated the following radioactive effluent systems during walkdowns:

(1) Station vent system

(2) Borated water storage tank

(3) North basin

(4) Training center pond to Toussaint River

Sampling and Analysis (IP Section 03.02) (2 Samples)

Inspectors evaluated the following effluent samples, sampling processes and compensatory samples:

(1) Borated water storage tank - weekly gamma emitter

(2) Training center pond to Toussaint River - compensatory action

Dose Calculations (IP Section 03.03) (2 Samples)

The inspectors evaluated the following dose calculations:

(1) Containment purge pre-release permit - 22-B0003G

(2) Liquid discharge pre-release permit - 21-B0008L

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) January 1, 2021 through June 30, 2022

IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02) (1 Sample)

(1) January 1, 2021 through June 30, 2022

IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (1 Sample)

(1) January 1, 2021 through June 30, 2022

BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10) (1 Sample)

(1) July 1, 2021 through June 30, 2022

BI02: RCS Leak Rate Sample (IP Section 02.11) (1 Sample)

(1) October 1, 2021 through September 30, 2022

OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)

(1) July 1, 2021 through June 30, 2022

PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample (IP Section 02.16) (1 Sample)

(1) July 1, 2021 through June 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:

(1) Condition report 2022-00382, "Door 300 Damaged During Fuel Delivery." In January 2022, during new fuel delivery, a truck impacted the fuel handling building train bay door (door 300) and damaged the door frame. The inspectors reviewed the circumstances leading to this incident and licensee corrective actions, including repairs. The inspectors also reviewed licensee analyses related to fuel handling building and fuel handling weather enclosure air leakage. No deficiencies were identified.

71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02)

Transfer tube flange leaks following acceptable local leak rate tests

(1) The inspectors reviewed the licensees corrective action program for potential adverse trends related to transfer tube flange leaks that might be indicative of a more significant safety issue. The plant has two fuel transfer tubes connecting the spent fuel pool with the refueling canal in containment. The transfer tubes are isolated from containment using gate valves and bolted blind flanges. The bolted blind flanges are sealed to the pipe flanges using two concentric rubber O-rings. In 2018, the licensee implemented an engineering change that reduced the number of flange bolts from 28 to 14. This reduction of bolts was supported by an engineering evaluation. Since this change, the licensee has experienced multiple issues related to the positive sealing of the east and west transfer tubes.

In 2020, following shutdown for refueling outage, a walkdown of the containment revealed a significant amount of wet and dry boric acid in the refueling canal. This boric acid was traced to a leak of approximately 60 drops per minute from the west transfer tube flange. Condition report 2020-01652 In 2022, during a walkdown of containment prior to startup a leak of more than 1 gallon per minute was found coming from the east transfer tube flange. The flange bolts were found to be only slightly more than hand-tight.

Inspectors identified a Green non-cited violation and a minor violation of NRC regulations related to these issues.

71153 - Follow-Up of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)

The inspectors evaluated Davis-Besse licensee event reports (LERs) 05000346/202100300, "Reactor Trip due to Failed Uninterruptible Power Supply and Steam Feedwater Rupture Control System Actuations," and 05000346/2021002 "Failure of Auxiliary Feedwater Rooms Interconnecting Door to Latch due to Worn Interlock."

(1) LER 05000346/2021002, "Failure of Auxiliary Feedwater Rooms Interconnecting Door to Latch due to Worn Interlock," (ADAMS Accession No. ML21235A413). The inspectors determined that it was not reasonable to foresee or correct the cause discussed in the LER therefore no performance deficiency was identified. The inspectors did not identify a violation of NRC requirements. This LER is closed.

(2) LER 05000346/2021003, "Reactor Trip due to Failed Uninterruptible Power Supply and Steam Feedwater Rupture Control System Actuations," (ADAMS Accession No. ML21250A131). The inspection conclusions associated with this LER are documented in Inspection Report 05000346/2021050. This LER is closed.

INSPECTION RESULTS

Failure to Develop Appropriate Local Leak Rate Testing for Fuel Transfer Tubes Cornerstone Significance Cross-Cutting Report Aspect Section Barrier Integrity Green [H.6] - Design 71152S NCV 05000346/2022003-01 Margins Open/Closed The inspectors identified a Green finding and associated non-cited violation of Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix B, Criterion XI, Test Control.

Specifically, the licensee did not establish testing requirements and acceptance limits to provide reasonable assurance of containment integrity by detecting fuel transfer tube flange seal degradation as required by 10 CFR Part 50, Appendix B, Criterion XI. Failure to detect degradation of the fuel transfer tube flange seals could result in a loss of containment integrity. The licensee entered this issue into their corrective action program as condition reports 2022-03195.

Description:

In 2018, the licensee performed a local leak rate test on the east and west fuel transfer tube blind flanges. Both fuel transfer tubes satisfactorily passed these local leak rate tests. In 2020, the licensee determined that the west transfer tube flange was leaking and had leaked for a significant amount of time. In 2022, during containment walkdowns before reactor startup, the licensee found the east transfer tube flange leaking at the flange. The east and west flanges had previously passed local leak rate testing (LLRT). The licensee determined the bolts holding the flanges in place to be only hand-tight, and upon disassembly, the licensee found the LLRT test port filled with grease. With grease blocking the test point port, the results of the LLRTs conducted gave invalid results.

Based on a review of licensee procedures for assembling the transfer tube seals and for performing local leak rate testing, the inspectors determined that the LLRT procedure is unsuitable for detecting transfer tube sealing with excess grease on the O-rings as is current licensee practice.

Corrective Actions: The licensee revised the transfer tube flange assembly procedure, reperformed the local leak rate test, and performed an extent of condition considering the west transfer tube.

Corrective Action References: CR 2020-01652, CR 2022-03169, CR 2022-03195, CR 2022-07735

Performance Assessment:

Performance Deficiency: In 2020, at the beginning of a refueling outage, it was discovered that the west transfer tube flange leaked. In 2022, prior to startup, it was discovered that the west transfer tube leaked. In both cases the leaks developed following successful local leak rate tests. The licensee's failure to adequately test the flange seals to provide reasonable assurance that they were reasonably leak tight is a performance deficiency.

Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the structures, systems, and component (SSC) and Barrier Performance attribute of the Barrier Integrity cornerstone and adversely affected the cornerstone objective to provide reasonable assurance that physical design barriers protect the public from radionuclide releases caused by accidents or events. Specifically, the failure of the LLRT as currently performed with seals coated in grease may result in a failure to detect an improperly sealed transfer tube flange.

Significance: The inspectors assessed the significance of the finding using Inspection Manual Chapter (IMC) 0609 Appendix A, The Significance Determination Process (SDP) for Findings At-Power. Inspectors referenced IMC 0609 Appendix A, Exhibit 3 - "Barrier Integrity Screening" Question C.1 which refers the user to IMC 0609, Appendix H, because the flange leaks represented an actual open pathway in the physical integrity of reactor containment.

Inspectors referenced IMC 0609 Appendix H, Table 7.2 "Phase 2 Risk Significance - Type B Findings at Power" for large dry containments, which resulted in the finding screening to Green because there was no actual leakage from containment to environment and the volume of leakage under postulated accident conditions would have been much less than 100 percent of containment volume per day.

Cross-Cutting Aspect: H.6 - Design Margins: The organization operates and maintains equipment within design margins. Margins are carefully guarded and changed only through a systematic and rigorous process. Special attention is placed on maintaining fission product barriers, defense-in-depth, and safety related equipment. Specifically, the flange leaks discovered in 2020 and 2022 coupled with the discovery of the local leak rate test port packed with grease should have resulted in a more robust organizational response and recognition of a potentially deficient local leak rate test.

Enforcement:

Violation: 10 CFR 50 Appendix B Criterion XI "Test Control," requires, in part, "A test program shall be established to assure that all testing required to demonstrate that structures, systems, and components will perform satisfactorily in service is identified and performed in accordance with written test procedures which incorporate the requirements and acceptance limits contained in applicable design documents." Contrary to the above, the licensee failed to develop a testing program for the fuel transfer tube flange seals to ensure they remained capable of performing their functions satisfactorily in service.

Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.

Minor Violation 71152S Minor Violation: In 2018, the licensee implemented a design change to reduce the number of transfer tube blind flange bolts from 28 to 14 per tube. The licensee performed an engineering analysis but failed to consider all factors. Specifically, the licensee failed to analyze the adequacy of the reduced bolting for the maximum allowed planar warpage/misalignment of the tube flange and blind flange. The design drawing states, "check seal surface of the tube flange for flatness

(a) At 45-degree intervals (8 places);

(b) To be within 0.015" which was specified for the original design using 28 flange bolts. The licensee failed to validate that this specification is adequate to ensure proper sealing with the use of 14 flange bolts. Since the licensee made this change, the licensee has, on multiple occasions, detected fuel transfer tube leakage following reassembly.

Screening: The inspectors determined the performance deficiency was minor. The licensee's failure to perform a thorough engineering review constituted a minor performance deficiency.

Enforcement:

Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Title 10 CFR Part 50, Appendix B, Criterion III, Design Control, requires, in part, that, "measures shall be established to assure that applicable regulatory requirements and the design basis are correctly translated into specifications, drawings, procedures and instructions." Contrary to the above requirement, the licensee failed to evaluate and/or document that the design specification for the seal flange was adequate to ensure proper sealing with reduced bolting.

This failure to comply with 10 CFR 50 Appendix B, Criteria III constitutes a minor violation that is not subject to enforcement action in accordance with the NRCs Enforcement Policy.

EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

On October 25, 2022, the inspectors presented the integrated inspection results to Mr. T. Brown, Site Vice President, and other members of the licensee staff.

On August 26, 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

71111.04 Corrective Action 2021-04816 Handwheel Nut and Handwheel Fell Off of Valve FW126 06/21/2021

Documents 2022-06530 BACC on SF16268 08/24/2022

Procedures DB-OP-06021 Spent Fuel Pool Operating Procedure 40

DB-OP-06233 Auxiliary Feedwater System 45

DB-OP-06262 Component Cooling Water System Procedure 46

DB-SS-03090 Motor Driven Feed Pump Monthly Valve Verification 11

71111.05 Corrective Action 2022-05878 Fire Piping Flange Leak in Cable Spread Room Near West 07/29/2022

Documents Wall

Fire Plans PFP-AB-237 Auxiliary Feed Pump 1 Room 237 05

PFP-AB-238 Auxiliary Feed Pump 2 Room 238, Fire Area F 05

PFP-AB-314 No 4 Mechanical Penetration Rooms 115CC, 314, and 09

314CC, Fire Area A

PFP-AB-422A Cable Spreading Room 422A, Fire Area DD 04

PFP-AB-422A Cable Spreading Room, Room 422A, Fire Area DD 04

71111.06 Corrective Action 2022-05891 High Water in Manhole MH3009 07/29/2022

Documents 2022-05892 High Water in Manhole MH3010 07/29/2022

22-06114 Paved Area East of the Plant is Underwater 08/09/2022

Miscellaneous Emergency Preparedness Integrated Drill 08/30/2022

Visual Exam of DB-SUB49-01 Emergency Sump, Borated Water Storage 09/13/2022

Equipment and Tank

Components

(VT-3)

Work Orders 200832523 Check Manhole Water Levels in MH3040, MH3044, 09/28/2020

MH3045, and MH3048

71111.07A Corrective Action 2019-05879 CCW Heat Exchanger 3 Outage at Risk 07/11/2019

Documents 2020-03251 E22-2, CCW 2 Heat Exchanger, Endbell Leak 04/15/2020

22-04541 CCW HX 3 Eddy Current Test Results 06/01/2022

Corrective Action 2020-07564 NRC Identified: Error in EER 600724048, CCW HX Tube 09/29/2020

Documents Evaluation

Resulting from

Inspection

71111.11Q Miscellaneous Emergency Preparedness Integrated Drill 08/30/2022

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.12 Corrective Action 2019-10760 Q233, CRD 5 VDC Power Supply 'B' Fault, Indicates NTNM 09/11/2016

Documents 2020-02452 The CRD API Power Supply 'B' in C4801X Did Not Turn on 03/20/2020

When the DCRDCS Was Energized

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

22-01894 System Monitoring Identified Anomalies with Rod 2-1 03/09/2022

Absolute Position Indication

22-02312 Set Screw Missing From HIC-ICS20 03/17/2022

22-03271-1 Maintenance Rule Review ICS/NNI System 04/29/2022

22-03275 Plant Computer Lost OPC Connection to ICS-ULD 04/14/2022

22-03441 Main Feed Pump 1 ICS Controller HICICS36B Will Not 04/19/2022

Transfer from Manual to Auto

22-04263 Received Unexpected Annunciator Alarm 14-2-F ICS ULD 05/20/2022

Trouble

22-05606 CRD Absolute Position Indicator 5-Vold Power Supply 'B' 07/18/2022

Failed High

22-06464 Secondary HBP Unexpectedly Non-Functional During 08/22/2022

Testing

22-06474 T983 Feedwater Temperature Incorrectly Feeding Through 08/23/2022

to FDMIS

22-06499 String Check Found Out of Tolerance 08/23/2022

22-06500 Temperature Sensitivity for FYSP02A1 (X) Calibration 08/23/2022

22-06734 Unit Load Demand Transferred to Manual on Feedwater 09/01/2022

Flow Deviation

Miscellaneous NOBP-LP-2601-Pre-Job Brief 0

Procedures DB-OP-06401 Transferring Rod Control Panel 32

Work Orders 200889122 DB-SUB055-01 SUB055-01 CRD System Power Supply B 07/18/2022

Fault

71111.13 Corrective Action 2022-06909 Unexpected Change in Delta T Cold During Adjustments 09/10/2022

Documents 2022-06935 Boric Acid Identified During Containment Walkdown 09/12/2022

22-07181 Diesel Oil Leak coming from EFW Day Tank 09/22/2022

22-07345 Containment Entry, Higher Dose Rates than Expected in Not 09/29/2022

Normally Accessed Area

22-07349 Untimely Documentation of a Condition Report 09/29/2022

Inspection Type Designation Description or Title Revision or

Procedure Date

Procedures DBBP-OPS-0003 On-Line Risk Management Process 17

DBBP-OPS-0011 Protected Equipment Posting 16

NG-DB-00001 On-Line Risk Management 18

NOP-OP-1007 Risk Management 36

Work Orders 200724732 PM 12055 EFW Diesel, Gear and Pump Drain/Fill T-89 09/19/2019

200820648 PM 12055 EFW Diesel, Gear and Pump 09/12/2022

71111.15 Corrective Action 2022-05932 ARTS Channel 4 Trip During Testing 08/01/2022

Documents

Work Orders 200829575 Train 2 Staggered Test, Breaker C 08/02/2022

200842248 Channel Functional Test of SFRCS Actuation Channel 2 08/01/2022

Logic for Mode 1

71111.18 Corrective Action 2020-01257 CCW Pump 1 Lessons Learned 02/18/2020

Documents 2022-05826 Potential Leakage Identified from Degraded Hose 07/27/2022

22-07345 Containment Entry, Higher Dose Rates Than Expected in 09/29/2022

Not Normally Accessed Area

Engineering 22-1032-001 Temporary Modification to Replace a Braided Hose with SS 0

Changes Tubing on RE4598BA

2-1032-002 Temporary Modification to Replace a Braided Hose with SS 0

Tubing on RE4598BA, Restoration

Procedures NOP-CC-2003 Engineering Changes 27

Work Orders 200763445 Add Constant Level Oilers to CCW Pump 2 Inboard and 08/23/2018

Outboard Bearing

200765344 Replace CCW Pump 2 Inboard and Outboard Slinger Rings 07/26/2022

with 8.5" ID Slinger Rings

200889938 CCW Pump 2 Baseline Test 08/05/2022

71111.19 Corrective Action 2021-01355 Main Turbine Stop Valve 4 Closed While Testing Main 02/28/2021

Documents Turbine Stop Valve 2

21-04152 Turbine Stop Valve 2 Testing Issues 05/22/2021

22-03993 Elevated Vibration Readings on MDFP 05/11/2022

22-06031 Motor Driven Feedwater Pump P241 High Vibration Level 08/05/2022

22-06049 Engineering Review DB-PF-03573 CCW Pump 2 Baseline 08/05/2022

Data

22-06060 CCW Pump 2 Outboard Oil Discoloration 08/06/2022

Inspection Type Designation Description or Title Revision or

Procedure Date

22-06066 CCW Pump 2 Abnormal Noise 08/06/2022

22-06070 High Pressure Injection Pumps Recirculation Line Drain 08/07/2022

Valve HP157A Handwheel is Loose

22-06950 BACC: Water Drop Formed on Bottom of HPI Pump 1 09/12/2022

Casing Flange

Miscellaneous SD-038 System Description for High Pressure Injection System for 07

Energy Harbor Nuclear Davis Besse Nuclear Power Station

Unit 1

Procedures DB-SS-04201 Emergency Feedwater Pump Quarterly Test 08

Work Orders 200627177 PM 5190 BF1201 Test MCC Breakers 08/25/2022

200724732 PM 12055 EFW Diesel, Gear and Pump Drain/Fill T-89 09/19/2019

200804014 Makeup Pump 1-2 PM 0171 07/27/2022

200820648 PM 12055 EFW Diesel, Gear and Pump 09/12/2022

200821069 Repair Oil Leak on the Pump Inboard Bearing Cap 07/05/2022

200822815 PM 2522 Lubricate MDFP Motor MP241 08/04/2022

200825460 CRD Exercise Test 09/12/2022

200829614 Motor Driven Feed Pump Quarterly Test 08/03/2022

200831602 PM 1702K3-2 Lube/Check TTV 08/22/2022

200831943 P3218-001 05.001 BW26 Forward Flow BW26 Forward Flow 09/12/2022

FA Norm

200847339 Installation of P-Port Orifices on All Fast-Acting Solenoid 04/20/2021

Valves for All Main Stop, Control, Intercept, and Intermediate

Stop Valves

200859897 Install P-Port Orifice in the FASVs for Turbine Generator 08/06/2021

Control Valves and Reheat Stop Valves

200889938 CCW Pump 2 Baseline Test 08/05/2022

71111.22 Procedures DB-OP-03291 Containment Personnel and Emergency Airlocks Seal 14

Leakage Test

DB-OP-06012 Decay Heat and Low Pressure Injection System Operation 84

Procedure

DB-PF-03291 Containment Personnel and Emergency airlocks Seal 14

Leakage Test

DB-SP-03446 Decay Heat Train 1 Pump and Valve Test (Mode 1-3) 12

71114.06 Corrective Action 2022-06710 EP Drill: Trend Identified in Lack of Overall Knowledge of 08/31/2022

Inspection Type Designation Description or Title Revision or

Procedure Date

Documents Security Events or Threats Procedures

22-06726 EP Drill: August 30, 2022, Integrated Drill Objectives Not Met09/01/2022

71124.06 Corrective Action 2022-06404 Storm Sewer RE 4686 Indication Flashing 08/19/2022

Documents

Corrective Action 2022-0658 Lack of Clarity in DB-CN-12005 Could Result in Required 08/24/2022

Documents Compensatory Sampling Interval Being Exceeded

Resulting from

Inspection

Miscellaneous Offsite Dose Calculation Manual 38

Offsite Dose Calculation Manual 39

21-B0008L Liquid Batch Release Package 03/08/2021

2-B0003G Containment Purge Release Package 03/03/2022

L-21-107 Combined Annual Radiological Environmental Operating 05/15/2021

Report and Radiological Effluent Release Report for the

Davis-Besse Nuclear Power Station - 2020

L-22-092 Annual Radiological Environmental Operating Report, 05/16/2022

including the Radiological Effluent Release Report for the

Davis-Besse Nuclear Power Station - 2021

Procedures DB-CH-04005 Weekly Condenser Air Activity Sampling and Analysis 22

DB-CN-03008 Station Vent Release, Weekly Radiological Monitoring, 18

Sampling, and Analysis of RE4598AA

DB-CN-03013 Liquid Releases, Quarterly Monitoring Analysis 10

DB-CN-04039 North Settling Basin Weekly Sampling and Analysis 05

DB-CN-04040 North Settling Basin Quarterly Analysis 09

DB-CN-12005 Storm Sewer Monitor (RE4686) Inoperable / In Alarm 06

DB-OP-03011 Radioactive Liquid Batch Release 30

DB-OP-03012 Radioactive Gaseous Batch Release 29

71151 Miscellaneous 2021 DOSE_ST.xlsx Various

22 DOSE_ST.xlsx Various

Cycle 22 DEI.xlsx Various

Cycle 23 DEI.xlsx Various

Procedures NOBP-LP-4012 Industry Reporting and Information System (IRIS) 08

71152A Corrective Action 2022-00382 Door 300 Damaged During Fuel Delivery 01/18/2022

Inspection Type Designation Description or Title Revision or

Procedure Date

Documents

71152S Calculations 32-9279098-000 Davis-Besse Fuel Transfer Tube Cover Plate Bolt Reduction 01/24/2018

[Proprietary]

Corrective Action 2008-32482 Fuel Transfer Tube Blank Flanges Improperly Sealed 01/02/2008

Documents 2008-33846 DB-PA-08-01: DB-MM-09186 Procedural 01/19/2008

Quality/Compliance Issues

2008-34027 DB-PA-08-01: Transfer Tube Blank Flanges Were Installed 01/02/2008

with 2 O-Rings

2008-34209 Rework Fuel Transfer Tube Blank Flanges 01/23/2008

2009-67480 2009 CDBI: Inadequate Equivalency Justification Provided in 11/09/2009

ERR 60-0003-070

20-01652 1R21 BACC: Boric Acid Crystals and Oil Underneath West 03/01/2020

Fuel Transfer Tube Flange

20-01655 ESM: Oil Under Fuel Transfer Tube in Refueling Canal 03/01/2020

20-01664 1R21 BACC: Fuel Transfer Tube 1-2 Flange 03/02/2020

22-03169 1R22 BACC: Active Leak in Refueling Canal/ Deep End 04/11/2022

22-03195 As Found Condition of the East Transfer Tube Flange 04/12/2022

Drawings M-519-00050 Drawing/Diagram 8, 15, 17, 18

Engineering ECP 2018-0022 Fuel Transfer Tube Bolting Reduction 0

Changes

Engineering EER 60-0003-070 Gasket Equivalent Replacement Flexitalic gasket, O-ring, 11/05/1999

Evaluations EPDM gasket

Miscellaneous Document M-519-00050 5, 6

Change Request

Procedures DB-MM-09186 Fuel Transfer Tube Removal and Installation 1

DB-PF-03008 Containment Local Leak Rate Tests 21, 22, 23,

24, 25

Work Orders 200686523 Fuel Transfer Tube 1-1 Local Rate Testing 03/19/2018

200686524 Fuel Transfer Tube 1-2 Local Leak Rate Testing 03/19/2018

200688164 Fuel Transfer Tube 1-1 03/20/2018

200755857 200755857 - Fuel Transfer Tube 1-1 Local Leak Rate 03/18/2020

Testing

200755858 Fuel Transfer Tube 1-2 Local Leak Rate Testing 03/18/2020

Inspection Type Designation Description or Title Revision or

Procedure Date

200768446 Fuel Transfer Tube 1-1 03/19/2020

200822015 Fuel Transfer Tube 1-1 03/29/2022

200822140 Fuel Transfer Tube 1-2 Local Leak Rate Testing 03/29/2022

200822141 Fuel Transfer Tube 1-1 Local Leak Rate Testing 03/29/2022

200880334 Fuel Transfer Tube 1-1 04/20/2022

200880454 Fuel Transfer Tube 1-2 Local Leak Rate Testing 04/12/2022

MWO 1747 Fuel Transfer Tube Blind Flanges 06/22/1977

18