IR 05000346/2021004
| ML22038A130 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse (NPF-003) |
| Issue date: | 02/09/2022 |
| From: | Billy Dickson NRC/RGN-III/DRP/B2 |
| To: | Tony Brown Energy Harbor Nuclear Corp |
| References | |
| EA-21-172 IR 2021004 | |
| Download: ML22038A130 (24) | |
Text
SUBJECT:
DAVIS-BESSE NUCLEAR POWER STATION - INTEGRATED INSPECTION REPORT 05000346/2021004 AND EXERCISE OF ENFORCEMENT DISCRETION
Dear Mr. Brown:
On December 31, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Davis-Besse Nuclear Power Station. On January 28, 2022, the NRC inspectors discussed the results of this inspection with you and other members of your staff. The results of this inspection are documented in the enclosed report.
No findings or violations of more than minor significance were identified during this inspection.
This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, Billy C. Dickson, Jr., Chief Branch 2 Division of Reactor Projects Docket No. 05000346 License No. NPF-3
Enclosure:
As stated
Inspection Report
Docket Number:
05000346
License Number:
Report Number:
Enterprise Identifier:
I-2021-004-0080
Licensee:
Energy Harbor Nuclear Corp.
Facility:
Davis-Besse Nuclear Power Station
Location:
Oak Harbor, OH
Inspection Dates:
October 01, 2021 to December 31, 2021
Inspectors:
D. Mills, Senior Resident Inspector
R. Baker, Senior Operations Engineer
S. Bell, Health Physicist
R. Cassara, Resident Inspector
J. Cassidy, Senior Health Physicist
M. Garza, Emergency Preparedness Inspector
G. Hansen, Sr. Emergency Preparedness Inspector
T. Ospino, Resident Inspector
G. Roach, Senior Operations Engineer
R. Ruiz, Project Engineer
J. Steffes, Senior Resident Inspector
Approved By:
Billy C. Dickson, Jr., Chief
Branch 2
Division of Reactor Projects
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Davis-Besse Nuclear Power Station, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.
List of Findings and Violations
No findings or violations of more than minor significance were identified.
Additional Tracking Items
Type Issue Number Title Report Section Status EDG EA-21-172 Failure to Comply with 10 CFR Part 37 71124.08 Closed
PLANT STATUS
The unit began the inspection period at rated thermal power. On December 1, 2021, the unit was down powered to 50 percent to allow condenser inspection and plugging of leaking condenser tubes. The unit was returned to rated thermal power on December 7, 2021 and remained at or near rated thermal power for the remainder of the inspection period.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors performed activities described in IMC 2515, Appendix D, Plant Status, conducted routine reviews using IP 71152, Problem Identification and Resolution, 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
External Flooding Sample (IP Section 03.03) (1 Sample)
- (1) The inspectors completed evaluations that flood protection barriers, mitigation plans, procedures, and equipment were consistent with the licensees design requirements and risk analysis assumptions for coping with external flooding during the week ending December 31, 2021.
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) Containment spray train 2 during the week ending December 25, 2021
- (2) Emergency diesel generator 1 during the week ending November 27, 2021
- (3) Station blackout diesel generator while emergency diesel generator 2 was out of service for monthly surveillance run during the week ending December 25, 2021
- (4) Emergency feedwater pump while emergency diesel generator was out of service for monthly surveillance run during the week ending December 25, 2021
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations during a complete walkdown of the high-pressure injection system during the week ending December 18, 2021.
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) No. 2 Mechanical penetration room, fire area A during the week ending October 16, 2021
- (2) No. 1 Mechanical penetration room and pipeway area, fire area AB during the week ending October 23,2021
- (3) High voltage switchgear room A and B, fire area S and Q during the week ending November 27, 2021
- (4) Component cooling water heat exchanger and pump room rooms, fire area T, with component cooling water pump 1 out of service for maintenance during the week ending December 4, 2021
Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the onsite fire brigade training and performance during three fire drills during November 8 - 10, 2021.
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) Emergency core cooling system pump room 1
71111.07A - Heat Sink Performance
Annual Review (IP Section 03.01) (1 Sample)
The inspectors evaluated readiness and performance of:
- (1) Emergency core cooling room 2 cooler during the week ending October 30, 2021
71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance
Requalification Examination Results (IP Section 03.03) (1 Sample)
- (1) The inspectors reviewed and evaluated the licensed operator examination failure rates for the requalification annual operating tests administered from October 18, 2021 through December 10, 2021.
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)
- (1) The inspectors observed and evaluated licensed operator performance in the control room during reactor power escalation from 50 percent to 100 percent after condenser work on December 7, 2021.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (2 Samples)
- (1) The inspectors observed and evaluated a simulator-based requalification examination on October 20, 2021.
- (2) The inspectors observed and evaluated the NRC annual operating test examination for crew 1 on November 17-18, 2021.
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) Service water pump 3 replacement
- (2) Train 1 component cooling water pump rotor replacement
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) Operation at reduced power (~50 percent) for condenser tube leak repairs during the week ending December 11, 2021
- (2) Post maintenance testing of component cooling water pump 1 following rotor replacement during the week ending December 11, 2021
- (3) Inspection and repairs of spent fuel pool fuel handling equipment including bridge and fuel assembly up-enders during the week ending December 18, 2021
- (4) Scheduled testing of safety related D1 4160-volt bus during the week ending December 25, 2021
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (2 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Service water pump 3 excessive packing leak off, CR-2021-08266
- (2) Emergency diesel generator 1 room ventilation recirculation damper failure, CR-2021- 07222
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (2 Samples)
The inspectors evaluated the following temporary or permanent modifications:
- (1) Train 1 component cooling water pump rotor replacement
- (2) Emergency diesel generator 1 room ventilation recirculation damper temporary repair
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (8 Samples)
The inspectors evaluated the following post-maintenance test activities to verify system operability and functionality:
- (1) Service water pump 3 following replacement of stuffing box bearing during the week ending October 30, 2021
- (2) Service water pump 3 following shaft bearing replacement and repacking during the week ending November 27, 2021
- (3) Component cooling water pump 1 following replacement of pump rotor during the week ending December 11, 2021
- (4) Reactor protection system channel 2 reactor trip breaker 'A' following trip breaker replacement during the week ending December 18, 2021
- (5) Decay heat / low pressure injection pump 2 following inspection and cleaning of pump borated water storage tank suction during the week ending December 25, 2021
- (6) Safety features actuation system channel 2 following replacement of channel 2 borated water storage tank level sensor power supply and bistable during the week ending December 18, 2021
- (7) Auxiliary feedwater pump 2 following replacement of turbine governor relays during the week ending December 18, 2021
- (8) Safety features actuation system channel 1 following replacement of channel 1 containment pressure sensor power supply and bistables during the week ending December 4, 2021
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
- (1) Emergency diesel generator 2 monthly surveillance run during the week ending December 25, 2021
Inservice Testing (IP Section 03.01) (1 Sample)
- (1) Turbine marine diesel FLEX generator quarterly run during the week ending November 20, 2021
71114.04 - Emergency Action Level and Emergency Plan Changes
Inspection Review (IP Section 02.01-02.03) (1 Sample)
- (1) The inspectors evaluated the following submitted Emergency Action Level and Emergency Plan changes.
The licensee did not make any changes to the site's Emergency Action Level procedures or Emergency Plan during the period of this inspection (July 1, 2020 through June 30, 2021). The NRC inspectors independently reviewed the revisions of the site's Emergency Action Level procedures and Emergency Plan that were current for the inspection period to verify no changes were made.
This evaluation does not constitute NRC approval.
71114.06 - Drill Evaluation
Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01) (1 Sample)
- (1) Emergency preparedness integrated drill on October 5,
RADIATION SAFETY
71124.08 - Radioactive Solid Waste Processing & Radioactive Material Handling, Storage, &
Transportation
Radioactive Material Storage (IP Section 03.01)
The inspectors evaluated the licensees performance in controlling, labeling, and securing the following radioactive materials:
- (1) This included activities within the auxiliary, radioactive waste, and steam generator storage buildings
Radioactive Waste System Walkdown (IP Section 03.02) (1 Sample)
The inspectors walked down the accessible portions of the solid radioactive waste systems and evaluated system configuration and functionality:
- (1) This included the components located with the auxiliary and radioactive waste buildings
Waste Characterization and Classification (IP Section 03.03) (3 Samples)
The inspectors evaluated the following characterization and classification of radioactive waste:
(1)10 CFR Part 61 Data for Primary Resin Sampled July 16, 2020 (2)10 CFR Part 61 Data for Primary Resin Sampled June 17, 2019 (3)10 CFR Part 61 Data for Dry Active Waste Sampled December 20, 2018
Shipping Records (IP Section 03.05) (4 Samples)
The inspectors evaluated the following non-excepted radioactive material shipments through a record review:
- (1) Radioactive Waste Shipment 2021-1005 of Dewatered Resin Transported in a Type A Package
- (2) Radioactive Waste Shipment 2021-1001 of Dewatered Resin Transported in a Type A Package
- (3) Radioactive Waste Shipment 2020-1002 of Dry Active Waste Transported in a General Design Package
- (4) Radioactive Waste Shipment 2021-1003 of Dewatered Resin Transported in a Type A Package
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04)===
- (1) April 1, 2020 through March 31, 2021
MS06: Emergency AC Power Systems (IP Section 02.05) (1 Sample)
- (1) July 1, 2020 through June 30, 2021
MS07: High Pressure Injection Systems (IP Section 02.06) (1 Sample)
- (1) July 1, 2020 through June 30, 2021
MS08: Heat Removal Systems (IP Section 02.07) (1 Sample)
- (1) July 1, 2020 through June 30, 2021
MS09: Residual Heat Removal Systems (IP Section 02.08) (1 Sample)
- (1) October 1, 2020 through September 30, 2021
MS10: Cooling Water Support Systems (IP Section 02.09) (1 Sample)
- (1) October 1, 2020 through September 30, 2021 BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10) (1 Sample)
- (1) July 1, 2020 through September 30, 2021
BI02: RCS Leak Rate Sample (IP Section 02.11) (1 Sample)
- (1) October 1, 2020 through September 30, 2021
OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)
- (1) July 1, 2020 through September 30, 2021 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, 2020 through September 30, 2021
71152 - Problem Identification and Resolution (PI&R)
Semiannual Trend Review (IP Section 02.02) (2 Samples)
- (1) The inspectors reviewed the licensees corrective action program for potential adverse trends related to missed surveillances that might be indicative of a more significant safety issue.
- (2) The inspectors reviewed the licensees corrective action program for inconsistencies in condition reports that might be indicative of a more significant safety issue.
Annual Follow-Up of Selected Issues (IP Section 02.03) (3 Samples)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) Failure of reactor coolant system boron trending to detect a diverging boron concentration trend caused by failed boron measurement equipment
- (2) Service water valve 1429, component cooling water heat exchanger 3 service water outlet isolation valve failed air drop test (CR 2021-06913)
- (3) Service water pump 3 rework due to bearing modification
OTHER ACTIVITIES
- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL
92709 - Licensee Strike Contingency Plans Licensee Strike Contingency Plans
- (1) On November 15, 2021, at midnight, the contract extension between the International Brotherhood of Electrical Workers Local 245 and Energy Harbor expired. In preparation for a potential strike, the NRC inspectors evaluated the adequacy of the licensees contingency plan. The inspectors assessed the adequacy of the plan's post strike staffing levels, staff qualifications, safety conscious working environment, and site access in meeting operational and security requirements. No issues were identified. A new contract was agreed upon on January 14,
INSPECTION RESULTS
Enforcement Discretion Enforcement Action EA-21-172: Failure to Comply with 10 CFR Part 37 71124.08
Description:
On November 29, 2016, the licensee was issued NRC Inspection Report No.
05000346/2016403, which documented a licensee identified violation of 10 CFR Part 37, Physical Protection of Category 1 and Category 2, Quantities of Radioactive Material at Facilities with a 10 CFR Part 73, Physical Protection Program. The violation met the criteria for Enforcement Discretion as described in Enforcement Guidance Memorandum (EGM)14-001, "Interim Guidance for Dispositioning 10 CFR Part 37 Violations with Respect to Large Components or Robust Structures Containing Category 1 or Category 2 Quantities of Material at Power Reactor Facilities Licensed Under 10 CFR Parts 50 and 52."
Subsequently, the inspectors re-evaluated this activity and found that while a violation of regulatory requirements continues to exist, the conditions remain within the criteria for enforcement discretion established within EGM 14-001.
Corrective Actions: As specified in EGM 14-001, the application of discretion is authorized until the underlying technical issue is dispositioned through rulemaking or other regulatory action. Additional corrective actions are not required.
Corrective Action References: Not applicable.
Enforcement:
Violation: On November 29, 2016, a violation of 10 CFR Part 37 was documented in Davis-Besse Inspection Report No. 05000346/2016403. The inspectors determined that the previously identified violation remains.
Basis for Discretion: This violation met the criteria for Enforcement Discretion as described in Enforcement Guidance Memorandum (EGM) 14-001, "Interim Guidance for Dispositioning 10 CFR Part 37 Violations with Respect to Large Components or Robust Structures Containing Category 1 or Category 2 Quantities of Material at Power Reactor Facilities Licensed Under 10 CFR Parts 50 and 52."
Minor Violation 71152 Minor Violation: The inspectors performed an in-depth inspection sample of unexpected boron sample results as detailed in condition report 2021-03645. On May 4, 2021, a daily reactor coolant boron sample, which indicated 26 parts per million (ppm) less than the previous days sample, occurred. An expected change in reactor coolant system (RCS)boron concentration is 1-4 ppm daily. Further analysis determined that the May 4 sample was valid and that samples between March 27 and May 3, 2021, had discrepancies in their results of 20 to 30 ppm higher than what was indicated by other reactivity parameters. Due to the inaccurate boron measurements, the licensee invoked technical specification surveillance requirement 3.0.3 and reperformed surveillances with updated procedures and chemistry equipment. The licensee determined that boron concentration in the RCS, borated water storage tank, core flood tanks, and waste receiver tanks was within technical specification required limits. The licensee performed an apparent cause analysis, which determined that instrument error was the most attributing cause. Licensee corrective actions include revised titrator procedure documents, newly purchased instrumentation, and improved training.
Screening: The inspectors determined the performance deficiency was minor. The licensees failure to provide adequate procedures for the sampling, analysis, and trending was a minor performance deficiency because during the period between March 27, 2021 and May 4, 2021, results from chemistry sampling diverged from actual and predicted trend values.
Enforcement:
Technical Specification Section 5.4.1 requires, in part, that written procedures shall be established, implemented, and maintained covering the applicable procedures recommended in Regulatory Guide 1.33, Revision 2, Appendix A, February1978.
NRC Regulatory Guide 1.33, Revision 2, Appendix A, Section 8 addresses Procedures for Control of Measuring and Test Equipment and for Surveillance Tests, Procedures and Calibrations and Section 8.a addresses Procedures of a type appropriate to the circumstances should be provided to ensure that tools, gauges, instruments, controls, and other measuring and testing devices are properly controlled, calibrated, and adjusted at specified periods to maintain accuracy. Specific examples of such equipment to be calibrated and tested are readout instruments, interlock permissive and prohibit circuits, alarm devices, sensors. signal conditioners, controls, protective circuits, and laboratory equipment. The failure to comply with Technical Specification Section 5.4.1 constitutes a minor violation that is not subject to enforcement action in accordance with the NRCs Enforcement Policy.
Minor Violation 71152 Minor Violation: The inspectors reviewed the licensees corrective action program for potential adverse trends related to missed surveillances that might indicate of a more significant safety issue.
CR 2020-04007, DB-SC-04200 overdue, describes the miscellaneous diesel generator and security uninterruptible power supply test unable to be performed before going overdue because of a maintenance condition on an inverter. This test is not a technical specification-required surveillance test, and the licensee was discovered the issue on its overdue date.
CR 2020-05248, Portions of monthly surveillance DB-ME-04009 for June 2020 incorrectly marked N/A, describes several portions of the surveillance test marked N/A and skipped.
CR 2021-08458, DB-MI-04014 not completed prior to overdue date, describes the failure to perform the surveillance test before the due date clean waste receiver tank hydrogen and oxygen sensor surveillance going overdue by more than a week and was discovered past the overdue date.
CR 2021-08760, Battery room B door 427A not inspected on correct frequency, describes the failure to inspect the normally open fire door on the required weekly frequency.
CR 2021-09697, DB-FP-04017 Acceptance criteria 5.1.2 went overdue on December 23, 2021 for #4 MPR water curtain spray system, describes the failure to perform the surveillance test before the overdue date and was discovered several shifts after the overdue date had passed.
CR 2021-01104, SR 3.3.1.3 Function 7 for RCP running not performed within 23 days, describes the failure to perform the technical specification surveillance high flux/number of reactor coolant pumps on within the required 23-day interval. This issue is documented below as a minor violation of technical specifications.
Though the inspectors did not identify any issue of greater than minor significance, the fact that the licensee missed multiple surveillances tests during the reviewed period could indicate a more significant underlying issue. The trend, if not arrested, may lead to a more significant safety issue.
Regarding the condition report 2021-01104, SR 3.3.1.3 Function 7 for RCP running not performed within 23 days, the license implemented a surveillance test risk-informed documented evaluation (STRIDE) to include the requirement for each of the four channels to be tested on a 92-day interval. Still, it failed to include the requirement for testing on a staggered 23-day frequency. This means that each channel is required to be tested every 92 days and that one channel is required to be tested at least once every 23 days. In this case, an engineering review of the STRIDES implementation discovered that the licensee had missed the 23-day requirement. Two channels were overdue for testing per the 23-day frequency but were not overdue per the 92-day frequency requirement.
Screening: The inspectors determined the performance deficiency was minor. The licensees failure to perform surveillance requirement 3.3.1.3 according to the interval required by technical specifications was a performance deficiency. The significance of this performance deficiency was minor because it did not negatively affect plant safety.
Enforcement:
The failure to comply with technical specification surveillance requirement 3.3.1.3 constitutes a minor violation that is not subject to enforcement action in accordance with the NRCs Enforcement Policy.
Observation: Potential Trend Regarding Inconsistent Use of the Corrective Action Program 71152 The inspectors reviewed the licensees corrective action program for condition reports that might indicate a more significant safety issue. The inspectors noted multiple examples indicating that the threshold for writing a condition report may not be consistent among plant employees.
On July 30, 2021, during work on the fire protection system, the mechanical penetration room 4 water curtain was spuriously activated which caused a significant amount of water to run from the room into the passage outside. Following this condition, the inspectors observed standing water. The licensee determined that this standing water was caused by partially and completely blocked floor drains. A plant employee cleared the blockage and water drained as designed. Following discovery of this issue, the inspectors noted several additional floor drains that appeared to contain significant buildup of debris. The licensee did not generate a condition report until the inspectors intervened (CR 2021-07350).
A contributing cause of the July 8, 2021 reactor trip was the failure of the digital electrohydraulic control (DEHC) uninterruptible power supply (UPS) battery due to a degraded cell. The licensee replaced this cell, and the battery was thought to be restored. However, the inspectors noted that another cell appeared to show similar signs of degradation and brought the concern to the licensee over several months.
The licensee wrote no condition report until the inspectors brought their concern to the Plant Manager (CR 2021-07316). The licensee has since replaced the entire battery bank.
On several instances, the inspectors noted charging error messages on battery backup emergency lighting and brought these to the licensee's attention. Though the licensee fixed the issue every instance, the licensee wrote no condition report. This result was in contrast to multiple CRs written for similar conditions over the same period.
Individually, none of these examples may suggest an ongoing problem, but the inspectors determined that they may indicate a potential weakness when viewed in the aggregate.
Specifically, station personnel may not have a consistent standard for documenting condition reports for these and other issues. Because of this, some conditions may be tracked through the corrective action program and the station may be missing the opportunity to identify and trend deficiencies potentially resulting in an adverse impact on the plant. The inspectors provided these observations to the licensee and identified no findings or violations.
Observation: Service Water Valve 1429 Failed Air Drop Test 71152 The inspectors performed an in-depth inspection sample of service water valve 1429, component cooling water (CCW) heat exchanger 3 service water outlet isolation valve, which failed a scheduled air drop test as documented in condition report 2021-06913. This fail-open pneumatically actuated valve controls service water flow through CCW heat exchanger 3.
The licensee overhauls the valve on a 12-year preventive maintenance frequency. The licensee performed this air drop test to assess the condition of the valve and determine a maintenance strategy. This scheduled interval for the air drop test changed from 18 months to 24 months in 2006. The failed air drop test indicated reduced seal performance, but the licensee determined that the valve would fulfill its safety function until scheduled preventive maintenance. The inspectors identified no findings or violations.
Observation: Service Water Pump 3 Repetitive Failure of Packing Due to Bearing Design Change 71152 The inspectors performed an in-depth inspection sample of service water pump 3 (SWP3)rework following the scheduled pump replacement in July 2021. The initial post-maintenance testing of the new pump failed due to a lack of packing leak-by resulting in overheated packing. Plant operators tripped the pump manually as soon as the observed the condition, and maintenance personnel repacked the pump following troubleshooting. Once the licensee repacked SWP3, it passed post-maintenance testing with less than expected packing leak-by, and was declared operable on August 3, 2021, but maintained in spare status.
SWP3 was again declared inoperable for unrelated maintenance from August 26, 2021, until September 21, 2021, when it was declared operable but maintained in spare status. On September 30, 2021, SWP3 was declared inoperable pending completion of the quarterly test performed on 10/14/2021. During the quarterly test on October 14, 2021, the packing leak-by issue persisted, and the packing began to overheat. Troubleshooting identified that a change in the bushing type, from smooth bronze to axially grooved polymer, had led to the packing issues. The licensee replaced the axially grooved polymer bearings with conventional smooth bronze, and operators restored the pump to an operable condition with adequate packing leak-by. The inspectors identified no findings or violations.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On January 28, 2022, the inspectors presented the integrated inspection results to Mr. T. Brown, Site Vice President, and other members of the licensee staff.
On December 13, 2021, the inspectors presented the radiation protection baseline inspection results to Mr. T. Brown, Site Vice President, and other members of the licensee staff.
On December 13, 2021, the inspectors presented the Review of Licensed Operator Annual Examination summary results inspection results to Mr. D. Witt, Operations Training Superintendent, and other members of the licensee staff.
On December 14, 2021, the inspectors presented the EP Inspection Exit Meeting inspection results to Mr. R.W. Oesterle, Manager, Regulatory Compliance and Emergency Response, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
CR-2021-08640
DFP Room Watertight Door 217 Hinges Degraded, and
Latch Pins are at Maximum Adjustment
11/11/2021
Corrective Action
Documents
CR-2021-09473
Door 217 Upper Latch Found Degraded
2/14/2021
NORM-LP-7221
Davis Besse Flooding Mitigating Strategy Assessment
Support Document
2/19/2016
NORM-LP-7222
Davis Besse Nuclear Power Station Flooding Focused
Evaluation
10/13/2017
Procedures
RA-EP-02830
Emergency Plan Off Normal Occurrence Procedure
CR-2021-01043
EDG RM 1 Heater E48-1 Not Maintaining Desired
Temperature
2/17/2021
Corrective Action
Documents
CR-2021-09576
SBODG DC Ground Meter Swinging During Monthly Run
Miscellaneous
Notification
601304770
Emergency Diesel Generator Room 1 Ambient
Temperature 68-69 Degrees F
2/17/2021
DB-OP-06011
High Pressure Injection System
DB-OP-06013
Containment Spray System
DB-OP-06234
DB-OP-06316
Diesel Generator Operating Procedure
Procedures
DB-OP-06334
Station Blackout Diesel Generator Operating Procedure
No 1 Mechanical Penetration Room and Pipeway Area
Rooms 202, 208 and 209 DC Fire Area AB
Fire Plans
No 2 Mechanical Penetration Room, Room 236 Fire Area A
Miscellaneous
Requalification
Program Annual
Testing Summary
Results
Licensed Operator Annual Performance Records for 2021
2/13/2021
OPS-JPM-042
In Plant Job Performance Measure
OPS-JPM-238
Simulator Job Performance Measure
OPS-JPM-257
In Plant Job Performance Measure
OPS-JPM-284
Simulator Job Performance Measure
OPS-JPM-293
Administrative Job Performance Measure
ORQ-EPE-S103
Simulator Scenario Guide
Miscellaneous
ORQ-EPE-S114
Simulator Scenario Guide
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
ORQ-EPE-S129
Simulator Scenario Guide
200817776
Auxiliary Feedwater Pump Turbines
11/08/2021
Work Orders
200866466
Service Water Pumps, Strainers, and PIPI
10/22/2021
Corrective Action
Documents
CR-2021-07736
Service Water Pump 3 Manually Tripped
10/14/2021
200866466
Service Water Pump 1-3 Minor Maintenance
10/22/2021
Work Orders
200866740
Service Water Pump 1-3 Install Leak Collection and
Drainage Equipment
10/20/2021
CR-2021-07222
HV5329B EDG Room 1 Recirc Damper Not Modulating
10/26/2021
CR-2021-07257
EDG 1 Ventilation Recirc Damper has a Crack in the Shaft
10/27/2021
Corrective Action
Documents
CR-2021-08257
EDG Room 2 Vent Fan Recirc Supply Damper HV5336B
Not Fully Open with Hydromotor De-Energized
11/24/2021
Procedures
DB-PF-03572
Component Cooling Water Pump 1 Baseline Test
Work Orders
200817776
Auxiliary Feed Pump Turbine 1-2 Replace Agastat Relay
10/19/2021
200809037
SFAS Channel 1 Functional Test
11/30/2021
200809710
SFAS Channel 2 Functional Test
2/14/2021
200810139
Channel Functional Test of Reactor Trip Breaker A, RPS
Channel 2 Reactor Trip Module Logic and Arts Channel 2
Output Logic
2/15/2021
Work Orders
200816776
Determination of MTC - Rod Swap
10/12/2021
DBRM-EMER-
1500A
Davis Besse Emergency Action Level Basis Document
Miscellaneous
RA-EP-01500
Emergency Classification
Miscellaneous
Davis-Besse
Nuclear Power
Station Emergency
Preparedness
Integrated Dill
Drill Guide
10/05/2021
Calibration
Records
Tennelec Proportional Counter Model S5XLR Serial
Number 2.12.56 Calibration
11/18/2019
CR-2020-00306
Periodic Low PH Conditions in Liquid Radwaste System
01/16/2020
CR-021-03087
Waste Oil Drum
04/19/2021
Corrective Action
Documents
CR-2021-04312
Source Paperwork
05/28/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
CR-2021-06693
MS-C-08-03: Gaps in Shipping Package Checklists
09/03/2021
Davis-Besse Nuclear Power Station Part 37 Radioactive
Materials Security Plan
467716004
CFR Part 61 Analysis for Dry Active Waste
2/20/2018
483034001
CFR Part 61 Analysis for Primary Resin
06/17/2019
23959001
CFR Part 61 Analysis for Primary Resin
07/16/2020
DBBP-LP-1601
Davis-Besse Nuclear Power Station Part 37 Radioactive
Materials Security Plan Guidance
G-RP-
10CFR37_FEN_00
10CFR37 Control of Cat 1 and Cat 2 RAM
Miscellaneous
SE-
PART37WKR_FEN
Radioactive Materials Part 37 Plan Worker Training-DB
Security
DB-HP-01511
Low Level Radioactive Waste Storage Facility (LLRWSF)
DB-HP-01702
Transfer, Handling and Storage of Radioactive Material
Procedures
NOP-OP-5201
Shipment of Radioactive Material-Waste
Radiation
Surveys
Licensed Sources Leak Testing and Inventory
05/27/2021
20-1002
Radioactive Waste Shipment of Dry Active Waste
03/19/2020
21-1001
Radioactive Waste Shipment of Dewatered Resin
08/14/2021
21-1003
Radioactive Waste Shipment of Dewatered Resin
08/28/2021
Shipping Records
21-1005
Radioactive Waste Shipment of Dewatered Resin
11/20/2021
Reactor Coolant System Activity Dose Equivalent Iodine
Data (07/01/2020 - 09/30/2021)
Various
Reactor Coolant System Dose Equivalent Analysis
11/03/2021
Miscellaneous
Gaseous and Liquid Radioactive Effluent Radiological Dose
Summary Reports, July 2020 through September 2021
Various
DB-CH-01815
Dose Equivalent I-131 Determination
DB-HP-01116
Canberra Genie 2000Counting System with Apex Gamma
Software
71151
Procedures
NOBP-LP-4012
Industry Reporting and Information System (IRIS)
Corrective Action
CR-2020-00200
DB-FP-04017 Not Able to be Completed by Overdue Date
01/11/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
CR-2020-02157
PRA Analysis Assessment Not Performed in Support of
STRIDE 2019-0001
03/12/2020
CR-2020-04007
DB-SC-04200 Overdue
05/05/2020
CR-2020-05248
Portions of Monthly Surveillance DB-MI-04009 for June
20 Incorrectly Marked N/A
06/24/2020
CR-2021-01104
SR 3.3.1.3 Function 7 for RCP Running Not Performed
Within 23 Days
2/18/2021
CR-2021-01506
TRM TVR 8.8.1.2 Not Met for EDG 1 and EDG 2 Due to
PM Frequency From 6 Years to 18 Years Not Being
Evaluated by an Acceptable 50.59
03/04/2021
CR-2021-02729
Surveillance and Periodic Test Program Change Form Not
Submitted as Required
04/09/2021
CR-2021-03645
Unexpected Boron Results for the Daily Reactor Coolant
System
05/04/2021
CR-2021-03693
Unexpected Boron Results - Investigation in Progress
05/05/2021
CR-2021-03709
Reactivity Anomaly Surveillance Missed due to
Performance with Potentially Erroneous RCS Boron
Concentration
05/06/2021
CR-2021-05633
SW Pump 3 Full Flow Testing Stopped Due to Loss of
Pump Packing Gland Leak Off
07/24/2021
CR-2021-05658
Entry into Abnormal Procedure for Loss of Service Water
Secondaries
07/26/2021
Cr-2021-05760
Lantern Ring Dimensions per Vendor Recommended
Clearances Not in Tolerances
07/29/2021
CR-2021-05789
Water curtain Activation
07/30/2021
CR-2021-05793
HPI Pump 2 Sprayed with Fire Protection Water
07/30/2021
CR-2021-05795
Low Pressure Injection Pump 2 Sprayed with Fire
Protection Water
07/30/2021
CR-2021-06913
SW1429 (Component Cooling Water Heat Exchanger 3
Service Water Outlet Isolation Valve) Air Drop Test
09/14/2021
Documents
CR-2021-07350
Backed Up Floor Drain Encountered During Water Curtain
Actuation
10/01/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
CR-2021-07511
Untimely Initiation of Condition Report 2021-07350 (Backed
Up Floor Drain Encountered During Water Curtain
Actuation)
10/08/2021
CR-2021-07736
Service Water Pump 3 Manually Tripped
10/14/2021
CR-2021-08458
DB-MI-04014 Not Completed Prior to Overdue Date
11/05/2021
CR-2021-08760
Battery Room B Door 427A Not Inspected on Correct
Frequency
11/16/2021
CR-2021-09054
Low Oil Level SW Pump 3 Thrust Bearing
11/29/2021
CR-2021-09697
DB-FP-04017 Acceptance Criteria 5.1.2 went Overdue on
2/23/21 for '4' MPR Water Curtain Spray System
2/25/2021
CR-2021-01334
Degraded Cabinet Ground Strap Lug
03/26/2021
Cr-2021-01488
Conduit Elbow Cover Top Cover Bolt Missing
04/02/2021
CR-2021-01490
Flexible Conduit Has Ground Lugs on Each End but no
Ground Cable
04/02/2021
CR-2021-01573
NRC Identified Concern Regarding Potentially Inadequate
Part 21s Leading to EDG Failures
09/17/2021
CR-2021-02204
NRC NCV: Failure to Maintain the Effectiveness of the
Emergency Plan due to Telephone Issues
05/21/2021
CR-2021-02440
Containment Spray 1 Pump Outboard Bearing Oil Level
Below Sightglass Band
04/30/2021
CR-2021-02969
21 Cyber Inspection: Instruments for Reg Guide 1.97,
Post Accident Monitor, are Categorized as Indirect when
they Should be Direct CDAs
05/14/2021
CR-2021-03462
NRC Observation: Rust Discovered on Self-Contained
Breathing Apparatus Pack
05/26/2021
CR-2021-04641
NRC Question Regarding Functionality of Fire Suppression
Sprinkler in SW Valve Room
07/13/2021
CR-2021-04717
DFP Alternator Lower Mounting Nut is Loose
07/16/2021
CR-2021-04718
DFP Cooling Hoses Have Small Cracks Developing
07/16/2021
CR-2021-04720
DFP Alternator Positive Lug Questions
07/16/2021
CR-2021-04894
Service Water Tunnel Ceiling Leak Impacting Conduits
Below
07/23/2021
Corrective Action
Documents
Resulting from
Inspection
CR-2021-05395
NRC Identified: Vegetation Growth Around Radiological
Environmental Monitoring Program Air Sampling Stations
08/13/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
CR-2021-05419
NRC Identified: DB-HP-01702: Procedure Confusion on
Environmental Air Sampler Calibration
08/13/2021
CR-2021-05729
21 NRC SIT: Operational Impact for Not Replacing
ZS01B
09/15/2021
CR-2021-05919
21 NRC SIT: Maintenance Rule Evaluation for
CR-2021-05262 Required
09/03/2021
CR-2021-06024
NRC SIT: Maintenance Rule Failure Review for
CR-2021-05319 Defective Battery Cell Identified at D3201B
During Troubleshooting of DEHC UPS
09/08/2021
CR-2021-06134
21 NRC SIT: Incorrect AP-913 Classification for C3621
09/10/2021
CR-2021-06146
Switch DST for MUP time Delay Relay 2Y1 Isolation
Potentially Exposed to Similar Degradation Mechanisms as
EDG FFSS
09/10/2021
CR-2021-06212
Incorrect Value Recorded in Operator Rounds for
August 2020 DC MCC 2 Ground Indication
09/16/2021
CR-2021-06279
MPR 4 Housekeeping Issues
09/17/2021
CR-2021-06500
21 PI&R NRC Inspection: Observation for Appropriate
CR Category Assignments
09/24/2021
CR-2021-06582
21 NRC SIT: Calculation Contains Incorrect Value in
Table
09/30/2021
CR-2021-06845
BACC: Leak from Instrument Housing on PD16589
10/08/2021
CR-2021-07350
Backed up Floor Drain Encountered During Water Curtain
Actuation
10/29/2021
CR-2021-07458
NRC DBAI 2021 - Clarification of Result and Conclusions
Summary in C-EE-002.01-010
11/05/2021
CR-2021-07511
Untimely Initiation of condition Report 2021-07350 (Backed
Up Floor Drain Encountered During Water Curtain
Actuation)
11/05/2021
CR-2021-07512
NRC DBAI 2021 - Excessive Grease Identified on 1P
Battery Connector
11/05/2021
CR-2021-07515
NRC DBAI 2021 - Clarification of Output Documents to
Calculation C-EE-004.01-049 (4.16 kV Bus C1/D1
Degraded Voltage, Loss of Voltage, and 27X-6
11/05/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
CR-2021-07904
NRC DBAI 2021 - Error in Previous Revision of 30 of
C-EE-002.01-010
11/19/2021
CR-2021-07914
Unable to Identify CRs Related to WO 200751566 and
WO 200679064 Regarding Instrument As-Found Out of
Tolerance
10/19/2021
CR-2021-09166
Failure to Appropriately Classify the DEHC UPS Supply
Battery Bank
11/19/2021
CR-2021-09167
Failure to Provide Procedural Instructions for Transferring
Gland Sealing Steam from Main to Auxiliary Steam
Following a Reactor Trip
11/19/2021
CR-2021-09278
NRC TI Inspection: Resources Not Established for
Performance of Calibration/Alarm Testing for Open Phase
Systems
2/09/2021
CR-2021-09282
NRC TI Inspection: DB-OP-06313 Procedure Enhancement
Observation for Open Phase Condition
2/09/2021
CR-2021-09636
Wasp Nest Identified on the SBODG Building
2/29/2021
CR-2021-09637
Bird Nest Identified on SBODG Radiator
01/03/2022
CR-2021-7464
NRC DBAI 2021 - HV5336B (EDG 2 Room HVAC Recirc
Damper Hydramotor Position Indicator Labels Incorrectly
Depict 'Open' and 'Shut'
11/05/2021
Drawings
N300214401
Model VITx-50 2G/28BHC - 2 STG
Engineering
Changes
EC 19-0041-001
Service Water Pump 3 Refurbishment
08/02/2019
Maintenance Plan
DB-TV1429 CCW Heat Exchanger
Maintenance Plan
DB-TV1429 CCW Heat Exchanger (Service Water Side
Various)
Miscellaneous
Maintenance Plan
Db-TV1429 SW Outlet Isolation Valve Op
Labor Contingency Plan - Energy Harbor
Labor Contingency Plan - Energy Harbor
Davis Besse Chemistry Department Management
Personnel Training Qualification Records
Various
2709
Miscellaneous
Davis Besse Chemistry Department Management
Personnel Training Exemption and Equivalent Qualification
Forms
11/05/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Selection and Training of Nuclear Power Plant Personnel
03/08/1971
Command SRO
Proficiency
Records
3rd Quarter 2021
11/16/2021
Command SRO
Proficiency
Records
4th Quarter 2021
11/16/2021
EMERGENCY PLAN
ORQ-EPE-S111
Simulator Scenario Guide
ORQ-EPE-S112
Simulator Scenario Guide
ORQ-EPE-S149
Simulator Scenario Guide
Shift Manager
Proficiency
Records
3rd Quarter 2021
11/16/2021
Shift Manager
Proficiency
Records
4th Quarter 2021
11/16/2021
TPD-CRP
Training Program Description - Fleet Radiation Protection
Common Training Program
01/27/2021
TPD-DBCH
Davis Besse Chemistry Training Program Descrption
TPD-DBRP
Davis-Besse Radiation Protection Training Program
Description
NOBP-TR-1112
Conduct of Simulator Training and Evaluation - Crew and
Individual Evaluation Forms
10/29/2021
Procedures
NOBP-TR-1271
Inactive License Retraining Program
13