IR 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:
Report Number:
Enterprise Identifier:
I-2022-003-0043
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
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 Aspect Report Section Barrier Integrity Green NCV 05000346/2022003-01 Open/Closed
[H.6] - Design Margins 71152S 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 Davis-Besse Nuclear Power Station, Unit 1, Failure of Auxiliary Feedwater Rooms Interconnecting Door to Latch due to Worn Interlock 71153 Closed LER 05000346/2021-003-00 LER 2021-003-00 for Davis-Besse Nuclear Power Station, Unit 1, Reactor Trip due to Failed Uninterruptible Power Supply and Steam Feedwater Rupture Control System Actuations 71153 Closed
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.
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 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,
RADIATION SAFETY
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 Aspect Report Section Barrier Integrity Green NCV 05000346/2022003-01 Open/Closed
[H.6] - Design Margins 71152S 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
Procedure
Type
Designation
Description or Title
Revision or
Date
21-04816
Handwheel Nut and Handwheel Fell Off of Valve FW126
06/21/2021
Corrective Action
Documents
22-06530
BACC on SF16268
08/24/2022
DB-OP-06021
Spent Fuel Pool Operating Procedure
DB-OP-06233
Auxiliary Feedwater System
DB-OP-06262
Component Cooling Water System Procedure
Procedures
DB-SS-03090
Motor Driven Feed Pump Monthly Valve Verification
Corrective Action
Documents
22-05878
Fire Piping Flange Leak in Cable Spread Room Near West
Wall
07/29/2022
Auxiliary Feed Pump 1 Room 237
Auxiliary Feed Pump 2 Room 238, Fire Area F
No 4 Mechanical Penetration Rooms 115CC, 314, and
314CC, Fire Area A
Cable Spreading Room 422A, Fire Area DD
Fire Plans
Cable Spreading Room, Room 422A, Fire Area DD
22-05891
High Water in Manhole MH3009
07/29/2022
22-05892
High Water in Manhole MH3010
07/29/2022
Corrective Action
Documents
22-06114
Paved Area East of the Plant is Underwater
08/09/2022
Emergency Preparedness Integrated Drill
08/30/2022
Miscellaneous
Visual Exam of
Equipment and
Components
(VT-3)
DB-SUB49-01 Emergency Sump, Borated Water Storage
Tank
09/13/2022
Work Orders
200832523
Check Manhole Water Levels in MH3040, MH3044,
MH3045, and MH3048
09/28/2020
2019-05879
CCW Heat Exchanger 3 Outage at Risk
07/11/2019
20-03251
E22-2, CCW 2 Heat Exchanger, Endbell Leak
04/15/2020
Corrective Action
Documents
22-04541
CCW HX 3 Eddy Current Test Results
06/01/2022
Corrective Action
Documents
Resulting from
Inspection
20-07564
NRC Identified: Error in EER 600724048, CCW HX Tube
Evaluation
09/29/2020
Miscellaneous
Emergency Preparedness Integrated Drill
08/30/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2019-10760
Q233, CRD 5 VDC Power Supply 'B' Fault, Indicates NTNM
09/11/2016
20-02452
The CRD API Power Supply 'B' in C4801X Did Not Turn on
When the DCRDCS Was Energized
03/20/2020
22-00893
MFP 1 Did Not Transfer from ICS to MDT-20 Control
2/06/2022
22-01894
System Monitoring Identified Anomalies with Rod 2-1
Absolute Position Indication
03/09/2022
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
Transfer from Manual to Auto
04/19/2022
22-04263
Received Unexpected Annunciator Alarm 14-2-F ICS ULD
Trouble
05/20/2022
22-05606
CRD Absolute Position Indicator 5-Vold Power Supply 'B'
Failed High
07/18/2022
22-06464
Secondary HBP Unexpectedly Non-Functional During
Testing
08/22/2022
22-06474
T983 Feedwater Temperature Incorrectly Feeding Through
to FDMIS
08/23/2022
22-06499
String Check Found Out of Tolerance
08/23/2022
22-06500
Temperature Sensitivity for FYSP02A1 (X) Calibration
08/23/2022
Corrective Action
Documents
22-06734
Unit Load Demand Transferred to Manual on Feedwater
Flow Deviation
09/01/2022
Miscellaneous
NOBP-LP-2601-
Pre-Job Brief
Procedures
DB-OP-06401
Transferring Rod Control Panel
Work Orders
200889122
DB-SUB055-01 SUB055-01 CRD System Power Supply B
Fault
07/18/2022
22-06909
Unexpected Change in Delta T Cold During Adjustments
09/10/2022
22-06935
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
Normally Accessed Area
09/29/2022
Corrective Action
Documents
22-07349
Untimely Documentation of a Condition Report
09/29/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
DBBP-OPS-0003
On-Line Risk Management Process
DBBP-OPS-0011
Protected Equipment Posting
NG-DB-00001
On-Line Risk Management
Procedures
NOP-OP-1007
Risk Management
200724732
PM 12055 EFW Diesel, Gear and Pump Drain/Fill T-89
09/19/2019
Work Orders
200820648
PM 12055 EFW Diesel, Gear and Pump
09/12/2022
Corrective Action
Documents
22-05932
ARTS Channel 4 Trip During Testing
08/01/2022
200829575
Train 2 Staggered Test, Breaker C
08/02/2022
Work Orders
200842248
Channel Functional Test of SFRCS Actuation Channel 2
Logic for Mode 1
08/01/2022
20-01257
CCW Pump 1 Lessons Learned
2/18/2020
22-05826
Potential Leakage Identified from Degraded Hose
07/27/2022
Corrective Action
Documents
22-07345
Containment Entry, Higher Dose Rates Than Expected in
Not Normally Accessed Area
09/29/2022
2-1032-001
Temporary Modification to Replace a Braided Hose with SS
Tubing on RE4598BA
Engineering
Changes
2-1032-002
Temporary Modification to Replace a Braided Hose with SS
Tubing on RE4598BA, Restoration
Procedures
NOP-CC-2003
Add Constant Level Oilers to CCW Pump 2 Inboard and
Outboard Bearing
08/23/2018
200765344
Replace CCW Pump 2 Inboard and Outboard Slinger Rings
with 8.5" ID Slinger Rings
07/26/2022
Work Orders
200889938
CCW Pump 2 Baseline Test
08/05/2022
21-01355
Main Turbine Stop Valve 4 Closed While Testing Main
Turbine Stop Valve 2
2/28/2021
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
Data
08/05/2022
Corrective Action
Documents
22-06060
CCW Pump 2 Outboard Oil Discoloration
08/06/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
22-06066
CCW Pump 2 Abnormal Noise
08/06/2022
22-06070
High Pressure Injection Pumps Recirculation Line Drain
Valve HP157A Handwheel is Loose
08/07/2022
22-06950
BACC: Water Drop Formed on Bottom of HPI Pump 1
Casing Flange
09/12/2022
Miscellaneous
SD-038
System Description for High Pressure Injection System for
Energy Harbor Nuclear Davis Besse Nuclear Power Station
Unit 1
Procedures
DB-SS-04201
Emergency Feedwater Pump Quarterly Test
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
08/22/2022
200831943
P3218-001 05.001 BW26 Forward Flow BW26 Forward Flow
FA Norm
09/12/2022
200847339
Installation of P-Port Orifices on All Fast-Acting Solenoid
Valves for All Main Stop, Control, Intercept, and Intermediate
Stop Valves
04/20/2021
200859897
Install P-Port Orifice in the FASVs for Turbine Generator
Control Valves and Reheat Stop Valves
08/06/2021
Work Orders
200889938
CCW Pump 2 Baseline Test
08/05/2022
DB-OP-03291
Containment Personnel and Emergency Airlocks Seal
Leakage Test
DB-OP-06012
Decay Heat and Low Pressure Injection System Operation
Procedure
DB-PF-03291
Containment Personnel and Emergency airlocks Seal
Leakage Test
Procedures
DB-SP-03446
Decay Heat Train 1 Pump and Valve Test (Mode 1-3)
Corrective Action
22-06710
EP Drill: Trend Identified in Lack of Overall Knowledge of
08/31/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Security Events or Threats Procedures
Documents
22-06726
EP Drill: August 30, 2022, Integrated Drill Objectives Not Met
09/01/2022
Corrective Action
Documents
22-06404
Storm Sewer RE 4686 Indication Flashing
08/19/2022
Corrective Action
Documents
Resulting from
Inspection
22-0658
Lack of Clarity in DB-CN-12005 Could Result in Required
Compensatory Sampling Interval Being Exceeded
08/24/2022
Offsite Dose Calculation Manual
Offsite Dose Calculation Manual
21-B0008L
Liquid Batch Release Package
03/08/2021
2-B0003G
Containment Purge Release Package
03/03/2022
Combined Annual Radiological Environmental Operating
Report and Radiological Effluent Release Report for the
Davis-Besse Nuclear Power Station - 2020
05/15/2021
Miscellaneous
Annual Radiological Environmental Operating Report,
including the Radiological Effluent Release Report for the
Davis-Besse Nuclear Power Station - 2021
05/16/2022
DB-CH-04005
Weekly Condenser Air Activity Sampling and Analysis
DB-CN-03008
Station Vent Release, Weekly Radiological Monitoring,
Sampling, and Analysis of RE4598AA
DB-CN-03013
Liquid Releases, Quarterly Monitoring Analysis
DB-CN-04039
North Settling Basin Weekly Sampling and Analysis
DB-CN-04040
North Settling Basin Quarterly Analysis
DB-CN-12005
Storm Sewer Monitor (RE4686) Inoperable / In Alarm
DB-OP-03011
Radioactive Liquid Batch Release
Procedures
DB-OP-03012
Radioactive Gaseous Batch Release
21 DOSE_ST.xlsx
Various
22 DOSE_ST.xlsx
Various
Cycle 22 DEI.xlsx
Various
Miscellaneous
Cycle 23 DEI.xlsx
Various
71151
Procedures
NOBP-LP-4012
Industry Reporting and Information System (IRIS)
Corrective Action
22-00382
Door 300 Damaged During Fuel Delivery
01/18/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Documents
Calculations
2-9279098-000
Davis-Besse Fuel Transfer Tube Cover Plate Bolt Reduction
[Proprietary]
01/24/2018
2008-32482
Fuel Transfer Tube Blank Flanges Improperly Sealed
01/02/2008
2008-33846
DB-PA-08-01: DB-MM-09186 Procedural
Quality/Compliance Issues
01/19/2008
2008-34027
DB-PA-08-01: Transfer Tube Blank Flanges Were Installed
with 2 O-Rings
01/02/2008
2008-34209
Rework Fuel Transfer Tube Blank Flanges
01/23/2008
2009-67480
2009 CDBI: Inadequate Equivalency Justification Provided in
ERR 60-0003-070
11/09/2009
20-01652
1R21 BACC: Boric Acid Crystals and Oil Underneath West
Fuel Transfer Tube Flange
03/01/2020
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
Corrective Action
Documents
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
Changes
ECP 2018-0022
Fuel Transfer Tube Bolting Reduction
Engineering
Evaluations
EER 60-0003-070
Gasket Equivalent Replacement Flexitalic gasket, O-ring,
EPDM gasket
11/05/1999
Miscellaneous
Document
Change Request
M-519-00050
5, 6
DB-MM-09186
Fuel Transfer Tube Removal and Installation
Procedures
DB-PF-03008
Containment Local Leak Rate Tests
21, 22, 23,
24, 25
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
Testing
03/18/2020
Work Orders
200755858
Fuel Transfer Tube 1-2 Local Leak Rate Testing
03/18/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
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