IR 05000346/2020004
| ML21043A444 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse |
| Issue date: | 02/12/2021 |
| From: | Billy Dickson Division Reactor Projects III |
| To: | Tony Brown Energy Harbor Nuclear Corp |
| References | |
| IR 2020004 | |
| Download: ML21043A444 (27) | |
Text
February 12, 2021
SUBJECT:
DAVIS-BESSE NUCLEAR POWER STATION - INTEGRATED INSPECTION REPORT 05000346/2020004
Dear Mr. Brown:
On December 31, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Davis-Besse Nuclear Power Station. On January 28, 2021, 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. 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,
/RA/
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-2020-004-0028
Licensee:
Energy Harbor Nuclear Corporation
Facility:
Davis-Besse Nuclear Power Station
Location:
Oak Harbor, OH
Inspection Dates:
October 1, 2020 to December 31, 2020
Inspectors:
S. Bell, Health Physicist
J. Cassidy, Senior Health Physicist
M. Garza, Emergency Preparedness Inspector
J. Harvey, Resident Inspector
D. Mills, Senior Resident Inspector
J. Neurauter, Senior Reactor 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
Failure to Maintain the Effectiveness of the Emergency Plan Cornerstone Significance Cross-Cutting Aspect Report Section Emergency Preparedness Green NCV 05000346/2020004-01 Open/Closed
[H.11] -
Challenge the Unknown 71114.04 The inspectors identified a Green finding and associated Non-cited Violation (NCV) of 10 CFR 50.54(q)(2) for the licensees failure to follow and maintain the effectiveness of an emergency plan that meets the planning standards of 10 CFR 50.47(b)(4). Specifically, on August 11, 2020, the Davis-Besse Nuclear Power Station experienced a phone outage that affected the licensees ability to receive calls from offsite. Since they could not receive calls and an alternate notification method was not available, they could not receive notifications per Emergency Action Level (EAL) HA 1.2. During the communications outage, the licensee did not maintain the emergency plan due to EAL HA 1.2 being rendered ineffective. The licensee did not establish compensatory actions until after inquiry from the Senior Resident Inspector.
The licensees corrective actions included:
- establishing compensatory measures
- updating their procedures to incorporate these actions
- entering this issue into their CAP as CR 2020-06343
Additional Tracking Items
None.
PLANT STATUS
The plant 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 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.
Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the Coronavirus Disease 2019 (COVID-19), resident inspectors were directed to begin telework and to remotely access licensee information using available technology. During this time, the resident inspectors performed periodic site visits each week; conducted plant status activities as described in IMC 2515, Appendix D, Plant Status; observed risk-significant activities; and completed on-site portions of IPs. In addition, resident and regional baseline inspections were evaluated to determine if all or portions of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In some cases, portions of an IP were completed remotely and on-site. The inspections documented below met the objectives and requirements for completion of the IP.
REACTOR SAFETY
71111.01 - Adverse Weather Protection
Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of winter for the following systems:
- Borated water storage tank
External Flooding Sample (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated that flood protection barriers, mitigation plans, procedures, and equipment are consistent with the licensees design requirements and risk analysis assumptions for coping with external flooding during the week ending December 5, 2020.
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (2 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Core spray train 2 during the week ending December 19, 2020
- (2) High pressure injection train 2 after planned testing during the week ending December 26, 2020
Complete Walkdown Sample (IP Section 03.02) (2 Samples)
- (1) The inspectors evaluated system configurations during a complete walkdown of the emergency feedwater system during the week ending January 2, 2021.
- (2) The inspectors evaluated system configurations during a complete walkdown of the emergency diesel generator system during the week ending December 19, 2020.
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) Mechanical penetration room 1 (room 208), fire area AB, during the week ending November 7, 2020
- (2) Control room and control room support rooms (rooms 502-513), fire area FF, during the week ending December 12, 2020
- (3) Service water pump room (room 52), fire area BF, during the week ending December 19, 2020
- (4) Emergency core cooling system pump room 2 (room 115), fire area A-04, during the week ending December 19, 2020
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 2 (room 115)
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 program biennial written examination and annual operating test administered between October 19 and December 11, 2020.
71111.11B - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Requalification Program (IP Section 03.04) (1 Partial)
(1)
(Partial)
Biennial Requalification Written Examinations
The inspectors evaluated the quality of the licensed operator biennial requalification written examination administered on 12/4/2020.
Annual Requalification Operating Tests
The inspectors evaluated the adequacy of the facility licensees annual requalification operating test.
Administration of an Annual Requalification Operating Test
Due to the COVID-19 PHE, the inspectors could not by direct observation, evaluate the effectiveness of the facility licensee in administering requalification operating tests required by 10 CFR 55.59(a)(2) and that the facility licensee is effectively evaluating their licensed operators for mastery of training objectives. Specifically, the inspectors did not observe the administration of simulator scenarios and JPMs during the conduct of an annual requalification operating test required by 10 CFR 55.59(a)(2).
Requalification Examination Security
The inspectors evaluated the ability of the facility licensee to safeguard examination material, such that the examination is not compromised.
Remedial Training and Re-examinations
The inspectors evaluated the effectiveness of remedial training conducted by the licensee, and reviewed the adequacy of re-examinations for licensed operators who did not pass a required requalification examination.
Operator License Conditions
The inspectors evaluated the licensees program for ensuring that licensed operators meet the conditions of their licenses.
Control Room Simulator
The inspectors evaluated the adequacy of the facility licensees control room simulator in modeling the actual plant, and for meeting the requirements contained in 10 CFR 55.46.
Problem Identification and Resolution
The inspectors evaluated the licensees ability to identify and resolve problems associated with licensed operator performance.
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 power changes, turbine valve testing, and control rod drive exercise during the week ending December 12, 2020.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated operator license requalification simulator scenarios on December 9, 2020 and December 10, 2020.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (5 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) Repeat failure of containment air cooler 2 service water outlet, SW1357 during the week ending September 5, 2020
- (2) Borated water storage tank level transmitter replacement due to water intrusion during the week ending June 27, 2020
- (3) Programmatic review of the periodic maintenance effectiveness assessment report for May 9, 2018, to March 3, 2020
- (4) Emergency diesel generator 1 scheduled 2-year preventive maintenance during the week ending November 14, 2020
- (5) Low pressure injection/decay heat pump 2 bearing replacement and constant level oiler installation during the week ending October 31, 2020
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (4 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) CR 2020-05932: Incorrect comparison of borated water storage tank concentration to upper technical specification limit
- (2) CR 2020-04688: Reactor coolant pump 2-2 seal return flow high
- (3) CR 2020-09055: Storm damage to shield building scaffold
- (4) CR 2020-05473: AF6451 close mVdc does not meet the minimum value specified in test procedure during minimal time period of power being applied
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (7 Samples)
The inspectors evaluated the following post-maintenance test activities to verify system operability and functionality:
- (1) Emergency feedwater testing following installation of automatic start function during the week ending November 21, 2020
- (2) Component cooling water pump 1 following overhaul during the week ending October 31, 2020
- (3) Emergency diesel generator 1 following planned maintenance during the week ending November 14, 2020
- (4) Low pressure injection/decay heat pump 1 following planned maintenance during the week ending December 12, 2020
- (5) Emergency core cooling system room cooler 4 following planned maintenance during the week ending December 12, 2020
- (6) Auxiliary feedwater pump 1 following planned maintenance during the week ending September 12, 2020
- (7) Low pressure injection/decay heat pump 2 following bearing replacement and constant level oiler installation during the week ending October 31, 2020
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
- (1) Emergency diesel generator 1 184-day run during the week ending November 28, 2020
Inservice Testing (IP Section 03.01) (3 Samples)
- (1) Emergency core cooling system train 1 quarterly valve testing during the week ending December 5, 2020
- (2) Turbine valve testing during the week ending December 12, 2020
- (3) Control rod drive exercise during the week ending December 12, 2020
FLEX Testing (IP Section 03.02) (1 Sample)
- (1) Emergency feedwater pump quarterly testing during the week ending November 28, 2020
71114.04 - Emergency Action Level and Emergency Plan Changes
Inspection Review (IP Section 02.01-02.03) (1 Sample)
- (1) The inspectors completed an evaluation of submitted emergency action level and emergency plan changes on December 31, 2020. This evaluation does not constitute NRC approval.
71114.06 - Drill Evaluation
Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)
The inspectors evaluated:
- (1) Integrated emergency preparedness/emergency response drill held on October 6,
RADIATION SAFETY
71124.01 - Radiological Hazard Assessment and Exposure Controls
Radiological Hazards Control and Work Coverage (IP Section 03.04) (1 Sample)
The inspectors evaluated in-plant radiological conditions during facility walkdowns and observation of radiological work activities.
- (1) Shepherd Model 89 calibrator repair under RWP 120-1048. This work involved high activity sources and significant dose gradients.
71124.05 - Radiation Monitoring Instrumentation
Calibration and Testing Program (IP Section 03.02) (11 Samples)
The inspectors evaluated the calibration and testing of the following radiation detection instruments:
- (1) MG Telepole, SN 2.7.338, calibrated on March 22, 2020
- (2) Fluke 451B, SN 2.7.526, calibrated on April 3, 2020
- (3) Canberra Cronos-4, SN 2.12.99, calibrated on November 4, 2019
- (4) Tennelec S5XLB, SN 2.12.56, calibrated on November 17, 2019
- (6) Eberline AMS-4, SN 2.8.183, calibrated on August 3, 2020
- (7) Apex High Purity Germanium Gamma Spectroscopy Detector, SN 3, calibrated on September 11, 2019
- (8) Ludlum Model 12, SN 2.7.667, calibrated on August 19, 2020
- (9) Canberra Fastscan Whole Body Counter, calibrated on August 8, 2019
- (10) Ludlum Model L177, SN 2.7.541, calibrated on April 23, 2020
- (11) Hi Range Containment Radiation Monitor, RE4596B, calibrated on March 24, 2020
Effluent Monitoring Calibration and Testing Program Sample (IP Sample 03.03) (2 Samples)
The inspectors evaluated the calibration and maintenance of the following radioactive effluent monitoring and measurement instrumentation:
- (1) Radioactive Liquid Discharge Monitor, RE1770A
- (2) Radioactive Gaseous Vent Stack Discharge Monitor, RE4598BA
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
MS09: Residual Heat Removal Systems (IP Section 02.08)===
- (1) July 1, 2019 through September 30, 2020
MS10: Cooling Water Support Systems (IP Section 02.09) (1 Sample)
- (1) October 1, 2019 through September 30, 2020
BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10) (1 Sample)
- (1) July 1, 2019 through June 30, 2020
BI02: RCS Leak Rate Sample (IP Section 02.11) (1 Sample)
- (1) October 1, 2019 through September 30, 2020
OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)
- (1) January 1, 2019 through September 30, 2020
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, 2019 through June 30, 2020
71152 - Problem Identification and Resolution
Semiannual Trend Review (IP Section 02.02) (1 Sample)
- (1) The inspectors reviewed the licensees corrective action program for potential adverse trends in communications systems 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)2020 Inspection campaign as part of long-term monitoring for the shield building laminar cracking condition, EN-DP-01511
- (2) Licensee effectiveness in maintaining minimum staffing levels
- (3) Unintended power change during feedwater flow transmitter calibration
INSPECTION RESULTS
Failure to Maintain the Effectiveness of the Emergency Plan Cornerstone Significance Cross-Cutting Aspect Report Section Emergency Preparedness
Green NCV 05000346/2020004-01 Open/Closed
[H.11] -
Challenge the Unknown 71114.04 The inspectors identified a Green finding and associated Non-cited Violation (NCV) of 10 CFR 50.54(q)(2) for the licensees failure to follow and maintain the effectiveness of an emergency plan that meets the planning standards of 10 CFR 50.47(b)(4). Specifically, on August 11, 2020, the Davis-Besse Nuclear Power Station experienced a phone outage that affected the licensees ability to receive calls from offsite. Since they could not receive calls and an alternate notification method was not available, they could not receive notifications per Emergency Action Level (EAL) HA 1.2. During the communications outage, the licensee did not maintain the emergency plan due to EAL HA 1.2 being rendered ineffective. The licensee did not establish compensatory actions until after inquiry from the Senior Resident Inspector.
The licensees corrective actions included:
- establishing compensatory measures
- updating their procedures to incorporate these actions
- entering this issue into their CAP as CR 2020-06343
Description:
On August 11, 2020, security staff at the Davis-Besse Nuclear Power Station discovered that offsite phone calls were not being received to onsite phone lines, including the NRC and Emergency Notification System phone lines. The unexpected outage began at approximately 1315 EDT and affected the inbound calling capability of all hardwired phones onsite. The outbound calling ability was not affected. The shift manager contacted the senior resident inspector (SRI) as a courtesy notification regarding the outage and provided a personal cell phone number. Upon receipt of the call, the SRI inquired about compensatory actions to allow the station to receive notifications from offsite entities, including the NRC Operations Center. The SRI noted that cell phone reception is deficient in the control room, making it an unreliable communication method for receiving notifications. Following this discussion, the licensee established compensatory measures to allow offsite communications with control room operators. The licensee informed the NRC Operations Center of the compensatory measures.
Corrective Actions: The licensee entered this issue into their corrective action program. The corrective actions included a revision to plant procedures governing equipment important to EP, and include appropriate compensatory actions in the event of a loss of phone lines.
Corrective Action References: CR-2020-06343; Site Phones Experiencing Issues Receiving Outside Calls
Performance Assessment:
Performance Deficiency: The inspectors determined that the licensee failed to maintain the effectiveness of the Davis-Besse emergency plan due to an ineffective EAL because plant operators were unable to receive timely notifications from offsite entities including the NRC Operations Center. The inspectors also determined that this was a performance deficiency within the licensees ability to foresee and correct.
Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Procedure Quality attribute of the Emergency Preparedness cornerstone and adversely affected the cornerstone objective to ensure that the licensee is capable of implementing adequate measures to protect the health and safety of the public in the event of a radiological emergency. In this case the licensee may not have received a notification of a hostile threat with enough time to implement the required procedures and declare an Alert prior to the event. Inspection manual chapter 0612 Appendix E example 4.i is similar to this issue.
Significance: The inspectors assessed the significance of the finding using Manual chapter 0609 Appendix B, Emergency Preparedness Significance Determination Process.
Appendix B table 5.4-1 and figure 5.4-1 provide significance determination examples for an ineffective EAL. Since the licensee would not have received notifications and thus, would not have been able to be declare an Alert under HA1.2 during the time that the phone lines were out, this finding screens as GREEN.
Cross-Cutting Aspect: H.11 - Challenge the Unknown: Individuals stop when faced with uncertain conditions. Risks are evaluated and managed before proceeding. This finding has a cross-cutting aspect in Human Performance, Challenge the Unknown, because the licensee did not stop and assess all vulnerabilities when presented with the unexpected loss of inbound communications capabilities. Specifically, the licensee failed to fully evaluate and manage the risk presented by the inability to declare an emergency under HA1.2 and enter the proper response procedures due to the loss of inbound communications capability.
Enforcement:
Violation: Title 10 of the Code of Federal Regulations, Part 50.54(q)(2) requires that a holder of a nuclear power reactor operating license under this part, shall follow and maintain the effectiveness of an emergency plan that meets the requirements in Appendix E to this part and the planning standards of 10 CFR 50.47(b). Title 10 CFR 50.47(b)(4) requires a standard emergency classification and action level scheme, the bases of which include facility system and effluent parameters, is in use by the nuclear facility licensee, and State and local response plans call for reliance on information provided by facility licensees for determinations of minimum initial offsite response measures.
Contrary to the above, the licensee failed to maintain the effectiveness of the emergency plan. Specifically, on August 11, 2020, the licensee failed to maintain a standard emergency classification and action level scheme as the site could not receive incoming phone calls and there were no compensatory actions in place to receive notifications that would meet the initiating condition of the sites emergency action level, HA 1.2.
Enforcement Action: This violation is being treated as an non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
Observation: 2020 Inspection Campaign as Part of Long-Term Monitoring for the Shield Building Laminar Cracking Condition 71152 As part of the continued long-term monitoring of the shield building laminar cracking condition, the licensee subjected a sample of existing shield building core bores to visual examination as prescribed by licensee procedure EN-DP-01511, "Structures Monitoring."
One purpose of the core bore visual examinations conducted under this procedure was to determine if any growth or change in the nature of the cracks had occurred by measurement of crack width and comparison to historical values. In areas of identified laminar crack planar propagation, the licensee performed additional impulse response mapping to provide a relative indication of the extent of propagation.
During this in-depth review, the inspectors verified the status of the licensee's core bore visual examinations and their evaluations and corrective actions resulting from shield building laminar cracking not identified by previous visual examinations. The inspectors reviewed the licensee's plans for follow-on examinations and corrective actions that they had established to verify that the classification, prioritization, focus, and timeliness of these actions were commensurate with the safety significance of the issue.
During the 2020 periodic examination, the licensee identified additional growth in laminar crack width. In some instances, the measured laminar crack width exceeded the crack widths induced during testing previously performed at selected universities referenced in IR 05000346/2014008 to credit full reinforcement capacity in those areas. The licensee documented measured laminar crack widths that exceeded the testing limit in the corrective action program. The licensee observed laminar crack propagation at some locations based on visual examination. The inspectors verified that the licensee determined the extent of laminar crack growth by a combination of additional impulse response mapping and confirmatory concrete cores. As a result of the increased crack widths, the licensee performed operability evaluations of the shield building and determined that the shield building remained operable because the increased crack widths were localized in nature.
The inspectors reviewed the licensee's operability determinations, engineering analyses, and assessment that the shield building remained capable of performing its intended safety functions and identified no concerns. The inspectors identified no findings.
Observation: Trend of Communication System Issues 71152 The inspectors reviewed the licensees corrective action program for potential adverse trends involving communication systems that might be indicative of a more significant safety issue.
During the review period for this inspection sample, the inspectors noted several phone system problems challenged the licensee. The inspectors determined that though these issues were identified and corrected by the licensee, several could have negatively impacted plant safety. Specific examples associated with this trend included but were not limited to:
- During the third quarter of 2020, the licensee was notified by an offsite employee that he could not reach anyone onsite by landline. The licensee identified that incoming calls could not reach any onsite phones even though they maintained the ability to call out and to call numbers onsite. Operators notified the NRC Resident Inspectors of the condition and provided personal cell phone number of an operator. The inspectors requested an alternate method of communication. The licensee provided an acceptable alternate communication method for the NRC emergency operations center to reach the unit control room in response to inspector requests. This issue is discussed in more detail in section 71114.04 of this report (ineffective EAL HA1.2).
(CR 2020-06343 - August 11, 2020)
- While performing a monthly walkdown of the Joint Information Center, the licensee discovered three phone lines and two fax lines were nonfunctional.
(CR 2020-06399 - August 13, 2020)
- The licensee discovered that five plant cell phones were not able to receive incoming phone calls. (CR 2020-08623 - November 3, 2020)
- The licensee discovered that hardwired phone lines were once again not able to receive incoming phone calls. (CR 2020-08623 - November 7, 2020)
- The licensee discovered that several security cell phones were not working.
(CR 2020-09147 - November 30, 2020)
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, for these and other issues, the station may be missing the opportunity to identify and resolve deficiencies before the failure manifests, potentially resulting in an adverse impact on the plant. The inspectors provided these observations to the licensee. The inspectors will continue monitoring the licensees actions to identify and correct similar issues.
Observation: Inspector verification of licensee minimum staffing levels 71152 The inspectors reviewed the licensee's pandemic response plan, condition reports, staffing plans, and licensee use of NRC exemption from certain portions of part 26 and part 73.
The inspectors verified that the licensee maintained sufficient staffing levels in key positions (e.g., operations, emergency response organization, security). Additionally, the inspectors evaluated for deferred maintenance and other activities, use of overtime, and the use of NRC enforcement discretion.
The inspectors also assessed licensee preparations and planning for potential staffing challenges at the facility or in the conduct of activities related to operations, emergency response organization, and security.
No issues were identified.
Observation: Unintended Power Change during Feedwater Flow Transmitter Calibration 71152 On March 29, 2020, as operators were starting up the reactor following the refueling outage, the control room received feedwater flow deviation alarms, and the operators halted the power ascension. The licensee determined that the issue was caused by the loop 1 feedwater flow instrument channel being out of calibration. The licensee commenced a calibration of the instrument channel using the approved calibration procedure. While performing the calibration, a plant transient resulted, during which the control rods automatically inserted and resulted in a 2.5 percent power reduction. The operators halted the transient by placing rod control and reactor demand hand/auto stations in hand (manual operation), and the calibration was completed. The licensee conducted an apparent cause evaluation that identified the apparent cause: the procedure failed to include steps to direct the operators to place the rod control and reactor demand hand/auto stations in hand before conducting the calibration. The licensee also identified that contributing causes included failures to identify the procedural deficiency. The licensee previously performed the procedure during plant conditions when control rod movement was not possible.
Inspectors reviewed procedures, logs, and the apparent cause evaluation. The inspectors identified no findings, but the licensee's failure to identify this issue before the performance of this work activity may indicate a weakness related to work planning and job preparation. The licensee had multiple opportunities to identify the issue during work planning, pre-job brief, and other work preparation activities. The inspectors will continue to monitor the licensee's focus on addressing work planning and work management issues.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On January 28, 2021, the inspectors presented the integrated inspection results to Mr. T. Brown, Site Vice President, and other members of the licensee staff.
- On November 4, 2020, 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 9, 2020, the inspectors presented the radiation protection inspection results to Mr. M. Sidoti, Radiation Protection Support Manager, and other members of the licensee staff.
- On December 17, 2020, the inspectors presented the Davis-Besse Biennial Licensed Operator Requalification Program Inspection Results inspection results to Mr. D. Huey, Operations Plant Manager, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
DB-OP-06913
Seasonal Plant Preparation Checklist
RA-EP-02870
Station Isolation
Corrective Action
Documents
20-07572
Relay Failed as Found Testing for BF1141TD
10/29/2020
Drawings
M-017A
Diesel Generators
M-017B
Diesel Generators Air Start
M-017C
Fuel Oil
OS-003
High Pressure Injection System
Procedures
DB-OP-06011
High Pressure Injection Operating Procedure
DB-OP-06013
Containment Spray System
DB-OP-06234
DB-OP-06316
Diesel Generator Operating Procedure
Fire Plans
ECCS Pump Room 1-2 Room 115
No. 1 Mechanical Penetration Room and Pipe Way Area
Rooms 202, 208, and 208DC
Control Room and Adjacent Support Rooms
Service Water Pump Room
Drawings
A-2111
Barrier Penetration Drawing Intake Structure
Procedures
NORM-ER-3208
Penetrations and Barriers
Work Orders
200720548
08/25/2020
71111.11A Miscellaneous
Davis-Besse Annual Licensed Operator Requalification
Program Results Information
2/14/2020
71111.11B Corrective Action
Documents
2018-10895
Ops Training-Potential Exam Security Event, Cell Phone
2/12/2018
2019-03972
Negative Performance Trend with Respect to EAL
Classification
04/30/2019
20-02741
Unexpected Rod Insertion During FW Flow Calibration
03/29/2020
20-08032
Senior Reactor Operator May Have Not Have Met the
Minimum Watch Standing Requirements
10/16/2020
20-08446
ILT Exam Security - SCANNER
10/26/2020
ATL-2019-0015-
ATA-1 l
Effectiveness Evaluation for EAL Performance Gap
10/19/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
Resulting from
Inspection
20-09464
20 NRC IP 71111.11 Issue of Concern; the Amount of
Overlap Between the 2018 and 2020 Written Exams.
2/15/2020
Miscellaneous
20 CT List
Davis-Besse Licensed Operator Critical Task List
2/03/2020
20 DB Biennial
Written Exam 1
20 Davis-Besse Biennial Written Exam 1
09/29/2020
20 DB Sample
Plan
20 Davis-Besse Examination Sample Plan and Outlines
Various
20 JPM Crew 1
20 Davis-Besse Annual Operating Test Job Performance
Measures Crew1 (001, 045, 227, 285, 308)
11/30/2020
20 JPM Crew 2
20 Davis-Besse Annual Operating Test Job Performance
Measures Crew 2 (027, 166, 120, 283, 193)
10/19/2020
20 Scn Crew 1
20 Davis-Besse Annual Operating Test Crew 1 Scenarios
(S109R14, S132R8, S137R5)
11/30/2020
20 Scn Crew 5
20 Davis-Besse Annual Operating Test Crew 5 Scenario
(S134R12)
11/09/2020
CREW
EVALUATION
ANNUAL EXAM
FORM (from
NOBP-TR-1112)
Scenarios #1 - #3: for Crew 1
2/02/2020
CYCLE 22 TAB
Simulator Transient Test
11/23/2020
DB 2020 Biennial
Exam 2
LORT Biennial Written Exam Failed by an Applicant
08/27/2020
DB 2020 Biennial
Exam 3
LORT Remedial Biennial Written Exam Passed by an
Applicant
11/18/2020
DBBP-TRAN-
21 for Scenario
ORQ EPE S101
Simulator Scenario Based Testing Documentation
07/13/2020
Procedures
DBBP-OPS-1013
Control of Time Critical Actions
DBBP-TRAN-
Conduct and Development of Job Performance Measures
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
0501
NOP-TR-1010
Requal Exam Development and Administration
Corrective Action
Documents
2017-10018
SW1357 Failed to Close During Air Drop Test due to
SV1357B Continuously Venting
10/01/2017
2018-02603
SW1357, CAC 2 Service Water Outlet, Would Not Stroke
Closed during Test
03/18/2018
20-01255
Difficulty Installing Split Ring on New Cartridge Style Seals
for the Decay Heat Pump
2/17/2020
20-01305
P42-2, Decay Heat Pump 2, Seal Leakage
2/19/2020
20-01363
BACC: Decay Heat Pump 2 Inboard Seal Package Leakage
2/21/2020
20-01382
Oil Sample on Decay Heat Pump 2 O.B. Pump Bearing
Grayish in Color
2/21/2020
20-01458
Decay Heat Pump 2 Mechanical Seal Replacement Post Job
Comments
2/25/2020
20-01909
1R21 BACC Boric Acid Build Up on 2 Decay Heat Pump
Inboard Pump Seal
03/07/2020
20-02616
Minor Oil Leakage from Decay Heat/Low Pressure Injection
Pump 2 Outboard Bearing Inside Cover
03/25/2020
20-02856
Vibration Point on Decay Heat Pump 1 is in the Alert Range
04/01/2020
20-03031
Required Actions Not Completed for HPI Pump 2 D-H
Vibrations in Alert Range from 1R21 Comprehensive Test
04/09/2020
20-05230
SFAS Channel 4 BWST Level Erratic
06/24/2020
20-06179
Suction Pressure Spike Following LPI Pump 2 Jog
08/05/2020
20-06619
SW1357 Would Not Stroke Closed
08/23/2020
20-07101
Alpha Level 3 Contamination Found Inside RCS Piping
09/11/2020
20-07724
EDG FOST 1 Internal Oxidation at Top of Tank
10/06/2020
20-07821
EDG Week Tank 1 Refill Delayed Retest and Operability
Determination
10/08/2020
20-07826
EDG 1 FOST Fuel Found with Water/Sediment Post
Maintenance
10/08/2020
20-07844
High Pressure at P12987 (1 Emergency Diesel Generator
South Air Start)
10/09/2020
20-08296
As Found Thrust on P42-2 Found Outside the Procedural
10/26/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Specifications in DB-MM-09174
20-08671
Pitting Noted n EDG 1-1 HX E10-1 Tubing
11/09/2020
20-08678
As-Found Visual Inspection for Piston Oil Piping was
Discovered Out Alignment
11/10/2020
20-08705
EDG 1 Jacket Water Hose Replacement Parts Not Correct
Size
11/11/2020
20-08740
EDG 1 Exhaust Temp Thermocouples Read Outside of
Required Value
11/11/2020
20-08742
EDG 1 Outage Critical Path Delay
11/11/2020
20-08743
EDG 1 Failed the Overspeed Trip Test
11/11/2020
20-08826
Control Room Annunciator 1-1-K EDG 2 Trouble Failed to
Alarm
11/15/2020
20-09073
Old Removed EDG 1 Speed Switch Signs of Overheating
11/25/2020
Corrective Action
Documents
Resulting from
Inspection
20-09755
Maintenance Rule Program Missed Condition Monitoring
Failure CR in Periodic Assessment Cycle 21
2/30/2020
Miscellaneous
MRPM
Maintenance Rule Program Manual
Procedures
NOBP-LP-2001
Self-Assessment and Benchmarking
NOP-ER-3004
Self-Assessments ATA-2020-9407
Cycle 21 Periodic Maintenance Effectiveness Assessment
Report (PMEAR)
Cycle 21
SA-BN-2018-
1138
Cycle 20 Periodic Maintenance Effectiveness Assessment
Report (PMEAR)
Cycle 20
Work Orders
200700254
PM 8878 GK5-1 Check Slip Ring Runout
11/09/2020
200709265
Decay Heat Pump Outboard Bearing Housing Interior
Coating
10/26/2020
200755711
Replace Decay Heat Pump Seals with Cartridge Type Seals
2/16/2020
200759589
PM 10851 Engine Analysis on EDG 1
11/09/2020
200766360
PM 0723 K5-1 24-Month Check EDG 1
11/08/2020
200767926
Emergency Diesel Generator 1 Static Exercise
11/09/2020
200771879
Diesel Generator and Auxiliary
11/08/2020
200772284
EDG 1 Overspeed Trip Test
11/08/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
200772284
Emergency Diesel Generator 1 Overspeed Trip Test
11/08/2002
200784743
Recommendations from EDG 1 Engine Analysis
11/09/2020
200784759
Borated Water Storage Tank Level SFAS Channel 4 Level
TA
06/24/2020
200826241
Borated Water Storage Tank Level SFAS Channel 4 Level
TA
06/24/2020
Corrective Action
Documents
2012-18810
DB-SP-03161 AF6451 Closed Voltage Out of Spec
2/02/2012
20-04688
RCP 2-2 Seal Return Flow High
05/31/2020
20-05473
AF6451 Close mVdc Does Not Meet the Minimum Value
Specified in Test Procedure During Minimal Time Period of
Power Being Applied
07/05/2020
20-05932
Incorrect Comparison of BWST Concentration to Upper Tech
Spec Limit
07/24/2020
20-09055
Storm Damage to Shield Building Scaffold
11/24/2020
G201-2008-
36648
Boron Concentrations Do Not Include Sample Accuracy
03/11/2008
Procedures
DBBP-OPS-0011
Protected Equipment Posting
Work Orders
200683357
Auxiliary Feedpumps and Piping
09/09/2020
200684824
Auxiliary Feedpump 1 to Steam Generator
09/09/2020
200714135
Auxiliary Feedwater Pump Turbines
09/09/2020
200765006
AFW Train 1 Valve Testing
09/09/2020
Procedures
DB-MM-09180
Component Cooling Water Pump Maintenance
DB-PF-03572
Component Cooling Water Pump 1 Baseline Test
DB-PF-03572
Component Cooling Water Pump 1 Baseline Test
Work Orders
200683357
Motor for AFP 1 Discharge to SG 1
09/09/2020
200684824
Auxiliary Feed Pump 1-1 to SG 1-2 Stop Valve
09/09/2020
200714135
Main Steam Line 1 to AFPT 1 Isolation Valve Motor
09/09/2020
200765030
AFP 1 Quarterly Test
09/08/2020
200770852
Decay Heat Train 2 Pump and Valve Test
2/26/2020
200770857
Emergency Feedwater Pump Monthly Test
10/29/2020
200772760
Monthly PMT Order
11/18/2020
200775489
Emergency CR RM CLR FAN 4
2/03/2020
200776052
ECCS Room 105 Cooler Fan 4 Motor Refurbish
2/04/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
200837784
CCW Pump 1 Quarterly Test
11/23/2020
Procedures
DB-SS-04201
Emergency Feedwater Pump Quarterly Test
Work Orders
200764576
MTSV Main Turbine Stop Valves Test
2/05/2020
200764577
2/05/2020
200764578
Main Turbine CIV Test
2/05/2020
200772722
EDG 2 184 Day Test
11/25/2020
200773169
CRD Exercise Test
2/05/2020
200774425
DH14B Mech Stop POS Test
11/30/2020
200840154
Quarterly PMT Test
11/18/2020
Corrective Action
Documents
2019-08756
Need to Perform 50.54(q) Reviews on Three Procedures
That Were Revised and Made Effective Without These
Reviews
10/22/2019
20-06343
Site Phones Experiencing Issues Receiving Outside Calls
08/11/2020
Miscellaneous
DB-2019-022-01
CFR 50.54(q)(2) Analysis
11/15/2019
DB-2019-026-00
CFR 50.54(q)(3) Screen/Evaluation
10/22/2019
DBRM-EMER-
5003
Equipment Important to Emergency Response
DBRM-EMER-
5003
Equipment Important to Emergency Response
NOBP-OP-1015
ALARA Plans
20-1048
Repair of Gamma Irradiator Shepherd Model 89
Radiation Work
Permits (RWPs)
20-1048
Repair and Maintenance of the Shepherd Model 89
Work Orders
200833345
Source Rod of JL Shepherd Model 89 Calibrator has
Become Detached
11/17/2020
Calibration
Records
Canberra Fastscan Whole Body Counter Calibration
08/08/2019
DB-MI3401-001
Radioactive Liquid Discharge Monitor, RE1770A, Calibration
06/17/2019
DB-MI3408-001
Hi Range Containment Radiation Monitor, RE4596B,
Calibration
03/14/2020
DB-MI3413-001
Radioactive Gaseous Vent Stack Discharge Monitor,
RE4598BA, Calibration
05/14/2019
RE4596B
Hi Range Containment Radiation Monitor Calibration
03/24/2020
SN 2.12.56
Tennelec S5XLB Calibration
11/17/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
SN 2.12.99
Canberra Cronos-4 Calibration
11/04/2019
SN 2.7.338
MG Telepole Calibration
03/22/2020
SN 2.7.501
09/09/2020
SN 2.7.526
Fluke 451B Calibration
04/03/2020
SN 2.7.541
Ludlum Model 177 Calibration
04/23/2020
SN 2.7.667
Ludlum Model 12 Calibration
08/19/2020
SN 2.8.183
Eberline AMS-4 Calibration
08/03/2020
SN Number 3
Apex High Purity Germanium Gamma Spectroscopy
Detector Calibration
09/11/2019
Corrective Action
Documents
2018-08094
JL Shepherd Model 89 Requires Repair
10/12/2020
2019-09708
Shepherd Model 89 Gamma Irradiator Failure
11/16/2019
2019-09708
Shepherd Model 89 Gamma Irradiator Failure
11/16/2019
20-00942
Incorrect Alarm Setpoints in RE8406, Miscellaneous Waste
Evaporator Room Area Monitor
2/07/2020
20-01010
Initial Part 21 Notification from Fluke Regarding to
Compliance Gap on Nickel Seal Rings for Victoreen CTMT
High Range (Model 977) Ion Chamber Area Radiation
Monitors
2/10/2020
20-01025
Telepole 2.7.343 Taken Out of Service
2/20/2020
20-04503
JL Shepherd 89 Gamma Irradiator Failure
05/24/2020
20-05419
CFR 21 Notice of Deviation for Victoreen Model 876A-1,
P/N 3649559, Radiation Monitor
07/01/2020
20-06066
Stop Work Criteria for Shepherd was Met
07/30/2020
20-06730
Telepole 2.7.339 Failed Daily Check
08/26/2020
71151
Corrective Action
Documents
2019-10166
Elevated Dose Rates Identified in Dry Shielded Container
Drain Port
2/05/2019
Miscellaneous
Cycle 21 Chemistry Dose Equivalent Iodine Data
Undated
Cycle 22 Chemistry Dose Equivalent Iodine Data
Undated
Radiological Effluent Dose Summary Information from
07/01/2019 through 06/30/2020.
Various
Corrective Action
Documents
2016-07491
Unit Load Demand Transferred to Manual Due to Feedwater
Flow Divergence
06/07/2016
2018-09568
Integrated Control System Unit Load Demand in Alarm Due
10/30/2018
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
to Loop 2 Feedwater Flow Deviation
20-02414
Re-Evaluate Medical Screening of Ill Personnel for
Departments and Health Services
03/19/2020
20-02733
Unit Load Demand Transferred to Manual Due to Feedwater
Flow Divergence
03/29/2020
20-02741
Unexpected Rod Insertion During FW Flow Calibration
03/29/2020
20-02818
Hospital Inventories not Completed for 1st Quarter 2020 per
RA-EP-00600 due to Covid-19
03/31/2020
20-02854
Monthly JIC Walkdown/RA-EP-04010 Quarterly
Communication Test
04/01/2020
20-03386
Concern with How Range Masks are Cleaned/Disinfected
04/18/2020
20-03473
Recommendation for Hand Search PPE Requirements
04/21/2020
20-05090
Shield Building Inspection Results - Shoulders 3, 4, 5, 6, 8,
and 11
06/16/2020
20-05091
Shield Building Inspection Results - Shoulder 16
06/16/2020
20-05388
Telephone Lines Out of Service at Lindsey Emergency
Response Facility
06/30/2020
20-05400
New Alternate Davis-Besse 4-Way Phone Number Did Dot
Work
07/01/2020
20-05524
Telephone Lines Out of Service at Lindsey Emergency
Response Facility
07/07/2020
20-05546
Unsafe Mandatory Wearing of Face Masks
07/08/2020
20-05926
Knowledge and Ownership of Equipment Previously
Supported by FirstEnergy IT
07/24/2020
20-06004
Shield Building Inspection Results - Shoulder 1
07/28/2020
20-06019
Shield Building Inspection Results - Shoulder 2
07/29/2020
20-06055
Shield Building Inspection Results - Shoulder 15
07/30/2020
20-06224
First Half 2020 IPA Site Gap Identified for Equipment
Reliability
08/06/2020
20-06280
Evaluate the Effectiveness of Curtain on PSF Rooftop
08/09/2020
20-06343
Site Phones Experiencing Issues Receiving Outside Calls
08/11/2020
20-06399
Phones/Fax Lines Not Working at Joint Information Center
During Monthly Walkdown
08/13/2020
20-06481
Safety Condition Report Social Distancing Separation Not
08/17/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
being Maintained
20-06552
Covid-19 PHE Related Violation of 10 CFR 73 Appendix B,
VI.C.3.(I)(1) Subject to NRC Enforcement Guidance
Memorandum 20-002
08/20/2020
20-07727
Failure Analysis Report - 4 Control Valve Intermittently
Changes Position During Transfers of ICS SG/RX Demand
Station from Manual to Auto
10/06/2020
20-07764
EP Drill: Network and Miscellaneous Technical Issues
During 10/06/2020 ERO Drill
10/07/2020
20-07776
Post 1R21 Code Safety Valve RC13A As-Found Setpoint
Tested High
10/07/2020
20-07779
EP Drill: EOF Fax Did Not Receive Messages During
10/06/2020 Drill
10/07/2020
20-07834
Sprinkler Guard Hanging Improperly
10/08/2020
20-07840
Revised Reactor Vessel P-T Curves Limited to 43 EPY
10/09/2020
20-07851
Shield Building Inspection Results - Shoulder 13
10/09/2020
20-07929
Shield Building Inspection Results - Shoulder 14
10/13/2020
20-08032
Potential Licensed Operator Watch Standing Requirements
Not Met
10/16/2020
20-08039
Foreign Material/Obstruction Identified at the Bottom of the
West-Most Drainpipe of EDG 1 FOST (FME Unrecovered)
10/17/2020
20-08070
Post 4 Floor Degradation
10/19/2020
20-08076
Contraband Identified at Entrance
10/19/2020
20-08088
Hydrogen Orbisphere Will Not Communicate with Computer
Preventing Instrument Calibration
10/19/2020
20-08096
Received Unexpected Annunciator Alarm 5-1A CRD System
Fault
10/19/2020
20-08135
MS107A Static Test Not Performed
10/20/2020
20-08152
Security Radio Degradation
10/21/2020
20-08169
RPS Channel 2 Scaled Difference Amplifier Found Out of
Tolerance
10/21/2020
20-08211
Conduit to MS100-1 is Separated
10/23/2020
20-08215
Electrical Manhole Inspection Sump Pump Failures
10/23/2020
20-08222
Startup Transformer 01 Trouble
10/23/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
20-08300
DB-FP-04035 Fire Suppression System 5-Year Test Not
Completed as Required
10/26/2020
20-08443
Emergency Plan Drills Not Conducted Due to Pandemic
10/30/2020
20-08519
Security B5b Phones Not Working as Designed
11/03/2020
20-08623
Site Phones Experiencing Issues Receiving Outside Calls
11/07/2020
20-09012
Inadequate Covid-19 prevention and Planning
11/21/2020
20-09036
Non-CDC Approved Disinfectant
11/23/2020
20-09147
CAS/SAS/SSS Cell Phone Failure Noted During
Computerized Automated Notification System Weekly Test
(CANS)
11/30/2020
Miscellaneous
Energy Harbor Pandemic Health Emergency Response Plan
Nuclear Generation Pandemic Health Emergency Response
Plan
DBRM-EMER-
1500A
Davis-Besse Emergency Action Level Basis Document
NDE Reports
Construction
Technology
Laboratories
(CTLGroup)
Project 263453
20 Shield Building Inspections
05/26/2020 -
10/09/2020
Procedures
EN-DP-01511
Structures Monitoring
Work Orders
200743529
Steam Room Work Online
05/26/2020
200743529
Shield Building Long Term Monitoring for the Laminar
Cracking Condition Under EN-DP-01511, Structures
Monitoring - 2020 Inspection Campaign
10/27/2020