IR 05000346/2022002

Integrated Inspection Report 05000346/2022002

ML22221A255
Person / Time
Site:	Davis Besse
Issue date:	08/11/2022
From:	Eve E NRC/RGN-III/DRP/B2
To:	Brown T Energy Harbor Nuclear Corp
References
IR 2022002
Download: ML22221A255 (29)

Text

August 11, 2022

SUBJECT:

DAVIS-BESSE NUCLEAR POWER STATION - INTEGRATED INSPECTION REPORT 05000346/2022002

Dear Mr. Brown:

On June 30, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Davis-Besse Nuclear Power Station. On July 27, 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.

Two findings of very low safety significance (Green) are documented in this report. One of these findings 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.

A licensee-identified violation which was determined to be Severity Level IV is documented in this report. 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 violations or the significance or severity of the violations 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 or a finding not associated with a regulatory requirement 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, Signed by Burket, Elise on 08/11/22 Elise C. Eve, Acting Branch Chief Branch 2 Division of Reactor Projects Docket No. 05000346 License No. NPF-3

Enclosure:

As stated

Inspection Report

Docket Number: 05000346 License Number: NPF-3 Report Number: 05000346/2022002 Enterprise Identifier: I-2022-002-0043 Licensee: Energy Harbor Nuclear Corp.

Facility: Davis-Besse Nuclear Power Station Location: Oak Harbor, OH Inspection Dates: April 01, 2022 to June 30, 2022 Inspectors: D. Mills, Senior Resident Inspector K. Barclay, Reactor Inspector R. Cassara, Resident Inspector J. Cassidy, Senior Health Physicist E. Fernandez, Reactor Inspector M. Garza, Emergency Preparedness Inspector T. Ospino, Resident Inspector J. Reed, Health Physicist Approved By: Elise C. Eve, Acting Branch Chief Branch 2 Division of Reactor Projects Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Davis-Besse Nuclear Power Station, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information. A licensee-identified non-cited violation is documented in report section: 71114.0

List of Findings and Violations

Failure to Use Procedure during Loss of Letdown Event Cornerstone Significance Cross-Cutting Report Aspect Section Initiating Event Green [H.8] - 71152A FIN 05000346/2022002-01 Procedure Open/Closed Adherence A self-revealed finding of very low safety significance (Green) was identified when the licensee failed to use procedures when responding to a loss of letdown. Specifically, the licensee failed to enter the annunciator response procedure, and isolated letdown with valve MU2B instead of valves MU6 and MU4 per procedure. The licensee also failed to utilize procedures while attempting to restore letdown during the initial response to the loss of letdown.

Failure to Provide Adequate Procedural Instructions when Swapping Purification Demineralizer Trains Cornerstone Significance Cross-Cutting Report Aspect Section Initiating Events Green [H.2] - Field 71152A NCV 05000346/2022002-02 Presence Open/Closed A self-revealed finding of very low safety significance (Green) and an associated non-cited violation (NCV) of Technical Specification (TS) 5.4.1(a) were identified for the licensees failure to establish and implement procedural guidance for performing a change of the on-service purification demineralizer. Specifically, the guidance in licensee procedure DB-OP-6006, "Makeup and Purification System," revision 53, for switching purification demineralizers did not provide instructions to ensure that the purification demineralizer being placed on-service was not manually isolated. This lack of procedural guidance resulted in control room operators inadvertently isolating letdown because they failed to un-isolate the manually closed outlet valve of purification demineralizer 1 prior to putting it on-service.

This resulted in high pressure in the letdown system, lifting of the relief valve MU-1890, and subsequent increase of pressurizer level to over 228 inches. This required the licensee to enter TS LCO 3.4.9 conditions A and B, resulting in a rapid reduction in power to roughly 15 percent.

Additional Tracking Items

Type Issue Number Title Report Section Status URI 05000346/2021050-06 Potential Adverse 93812 Discussed Changes During 2006 Emergency Diesel Generator Modifications

PLANT STATUS

The unit began the inspection period shut down for refueling outage. On April 18, the unit entered startup, and on April 21 the unit reached full power. On May 17, the unit was down powered to 64 percent to allow repair of a cracked small diameter instrument line on the secondary side. On May 19, the unit was returned to rated thermal power, 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://ww.w.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors performed activities described in IMC 2515, Appendix D, Plant Status, observed risk significant activities, and completed on-site portions of IPs. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance, and compliance with Commission rules and regulations, license conditions, site procedures, and standards.

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (3 Samples)

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

(1) Decay heat train 2 during the week ending April 30, 2022

(2) Containment spray train 1 during train 2 scheduled maintenance during the week ending June 30, 2022

Complete Walkdown Sample (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated system configurations during a complete walkdown of the control room emergency ventilation system through the week ending June 11, 2022.

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (4 Samples)

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

(1) Containment closeout walkdown, fire areas D, AB, and A, during the week ending April 9, 2022

(2) Emergency core cooling system train 2 room 115, fire area A-04, during the week ending April 16, 2022

(3) Low voltage switchgear rooms E and F, fire areas X and Y, during the week ending May 7, 2022

(4) Radioactive waste exhaust equipment and main station exhaust fan room, fire area EE, during the week ending June 30, 2022

71111.08P - Inservice Inspection Activities (PWR) PWR Inservice Inspection Activities Sample (IP Section 03.01)

(1) The inspectors verified that the reactor coolant system boundary, steam generator tubes, reactor vessel internals, risk-significant piping system boundaries, and containment boundary are appropriately monitored for degradation, and that repairs and replacements were appropriately fabricated, examined and accepted by reviewing the following activities from March 7, 2022 to March 18, 2022:

03.01.a - Nondestructive Examination and Welding Activities Ultrasonic examination (UT) of cold leg inlet nozzle to pipe weld, component ID RC-MK-B-59-1-FW-113B Ultrasonic examination (UT) of hot leg outlet nozzle to shell weld, component ID RC-RPV-WR-13/14/72-Z Liquid penetrant (PT) examination of fillet weld on RCTC CLNT 1-2-1 seal return line component ID DB-FTMU60A Liquid penetrant (PT) examination of fillet weld on RCTC CLNT 1-2-1 seal return line component ID DB-FTMU60B Visual examination (VT) of reactor vessel interior keyways Visual examination (VT) of control rod guide tubes per MRP-227 Welding of 2 to 1 fillet weld on RCTC CLNT 1-2-1 seal return line component ID DB-FTMU60B (WO 200747521)03.01.b - Pressurized-Water Reactor Vessel Upper Head Penetration Examination Activities Visual examinations of 69 penetrations on the reactor vessel closure head 03.01.c - Pressurized-Water Reactor Boric Acid Corrosion Control Activities Condition Report (CR)-2020-05467 containment spray pump 1 pipe cap at CS32 CR-2021-07323 BWST SFAS channel 2 level transmitter CR-2021-07401 decay heat pump casing vent CR-2021-02688 makeup pump 2 outlet isolation 03.01.d - Pressurized-Water Reactor Steam Generator Tube Examination Activities Eddy current (ET) testing of 15502 steam generator tubes in SG 2A Eddy current (ET) testing of 15538 steam generator tubes in SG 1B

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 ascension, including syncing main generator to grid, delta cold leg temperature adjustments, and starting of second main feed pump during the week ending April 23, 2022.

71111.12 - Maintenance Effectiveness

Maintenance Effectiveness (IP Section 03.01) (3 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) Replacement of station battery 2 during the week ending March 12, 2022

(2) Decay heat pump 2 bearing and oil seal replacement due to oil leak during the week ending April 16, 2022

(3) 10-year overhaul of the YVB inverter static transfer switch channel 'B' during the week ending May 7, 2022

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (1 Sample)

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) Reactor power reduction and emergent work related to instrument line steam leak repairs from May 17 - 19, 2022

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) Main steam isolation valve 2 inoperable due to scaffold pole in path of MS100, CR 2022-01484, during the week ending April 9, 2022

(2) Decay heat pump 2 pump outboard constant level oiler empty, CR 2022-02550, during the week ending April 16, 2022

(3) Decay heat pump 1 inboard/outboard bearings constant level oilers were found empty, CR 2022-03669, during the week ending April 30, 2022

(4) RCP 1-2 seal leak / lower differential pressure, CR 2022-03463, and CR 2022-03482, during the week ending June 30, 2022

71111.19 - Post-Maintenance Testing

Post-Maintenance Test Sample (IP Section 03.01) (1 Sample)

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

(1) Containment air cooler 2 outlet temperature control valve SW1357 during the week ending May 14, 2022

71111.20 - Refueling and Other Outage Activities

Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated refueling outage 1R22 activities from March 4, 2022 through April 19, 2022

71111.22 - Surveillance Testing

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

Surveillance Tests (other) (IP Section 03.01) (5 Samples)

(1) Steam feed rupture control system channel 2 integrated testing during the week ending April 9, 2022

(2) Physics testing during power ascension during the week ending April 23, 2022

(3) Emergency diesel generator 1 monthly test during the week ending April 30, 2022

(4) Steam feed rupture control system channel 1 differential pressure inputs surveillance on May 16, 2022

(5) Low pressure injection quarterly test during the week ending June 11, 2022

FLEX Testing (IP Section 03.02) (1 Sample)

(1) Annual run of FX-P1A alternate low pressure flex emergency feed water pump and FX-P2A flex emergency feed water storage tank replenishment and spent fuel pool spray N+1 pump during the week ending 30 June, 2022

71114.02 - Alert and Notification System Testing

Inspection Review (IP Section 02.01-02.04) (1 Sample)

(1) The inspectors evaluated the following maintenance and testing of the alert and notification system:

2020 annual siren preventive maintenance (PM) results 2021 annual siren PM results

71114.03 - Emergency Response Organization Staffing and Augmentation System

Inspection Review (IP Section 02.01-02.02) (1 Sample)

(1) The inspectors evaluated the readiness of the emergency preparedness organization

71114.05 - Maintenance of Emergency Preparedness

Inspection Review (IP Section 02.01 - 02.11) (1 Sample)

(1) The inspectors evaluated the maintenance of the emergency preparedness program

71114.06 - Drill Evaluation

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

The inspectors evaluated:

(1) Integrated drill on May 24,

71124.05 - Radiation Monitoring Instrumentation

Walkdowns and Observations (IP Section 03.01) (8 Samples)

The inspectors evaluated the following radiation detection instrumentation during plant walkdowns:

(1) ARGOS-5 number Li 2.12.112 at the main exit of the radiologically controlled area

(2) SAM-11 number Li 2.12.54 at the main exit of the radiologically controlled area

(3) GEM-5 number Li 2.12.115 at the main exit of the radiologically controlled area

(4) AMP-100 number Li 2.7.502 in the calibration facility

(5) Chronos-4 number Li 2.12.113 in the rad waste truck bay

(6) Telepole Li.2.7.337 ready for issuance in radiation protection counting room

(7) Area radiation monitor RE-8426 in the fuel handling building

(8) Area radiation monitor RE-1998 in the auxiliary building

Calibration and Testing Program (IP Section 03.02) (13 Samples)

The inspectors evaluated the calibration and testing of the following radiation detection instruments:

(1) ARGOS 5-AB number Li 2.12.112

(2) GEM-5 number Li 2.12.115

(3) SAM-11 number Li 2.12.54

(4) FUJI neutron detector number Li 2.7.682

(5) AMP-100 number Li 2.7.502

(6) Chronos-4 number Li 2.12.113

(7) Whole body counter number Li 2.12.42

(8) TopTrak air flow calibration standard number 65775

(9) Benchtop counter model L-177 number Li 2.7.545

(10) Benchtop counter model L-177 number Li 2.7.558

(11) Failed fuel monitor number RE-1998

(12) Control room normal air supply monitor number RE-4597

(13) Containment air normal monitor number RE-4597 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) Batch tank liquid effluent monitor, RE-1878A

(2) Station vent accident range noble gas monitor, RE-4598AB

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:

EP01: Drill/Exercise Performance (DEP) Sample (IP Section 02.12) ===

(1) January 1, 2021 through March 31, 2022 EP02: Emergency Response Organization (ERO) Drill Participation (IP Section 02.13)

(1 Sample)

(1) January 1, 2021 through March 31, 2022 EP03: Alert And Notification System (ANS) Reliability Sample (IP Section 02.14) (1 Sample)

(1) January 1, 2021 through March 31, 2022

71152A - Annual Follow-Up Problem Identification and Resolution Annual Follow-Up of Selected Issues (Section 03.03)

The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:

(1) February 5, 2022, forced downpower due to loss of letdown

71153 - Follow-Up of Events and Notices of Enforcement Discretion Event Follow-Up (IP Section 03.01)

(1) The inspectors evaluated forced downpower and licensees response on February 5,

INSPECTION RESULTS

Licensee-Identified Non-Cited Violation 71114.02 This violation of very low safety significance was identified by the licensee and has been entered into the licensee corrective action program and is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.

Violation:

On July 19, 2020, Ottawa County, Ohio notified the licensee that a single emergency siren sounded spuriously. On July 20, 2020, the licensee notified the Ottawa County Dispatch that the affected siren was out of service for repair. Title 10 CFR 50.72(b)(2)(xi) requires the licensee to report within four hours, any event related to the health and safety of the public for which notification to other government agencies has been made. Initially on July 19, the licensee concluded that the siren actuation was not reportable because less than 25 percent of the local population was affected. On July 20, the licensee reviewed the circumstances surrounding the siren, and concluded that 10 CFR 50.72(b)(2)(xi) applied and a four-hour report should have been made. NUREG-1022 includes as an example that an emergency notification is needed if county governments are informed of an actuation by concerned members of the public. The licensee made the notification at 1636 on July 20, 2020. The inspectors concluded that the failure to make the required four-hour notification in timely fashion was a performance deficiency. Because the violation impacted the regulatory process, in that the licensee failed to make a required report on time, the inspectors assessed the performance deficiency using traditional enforcement. The licensee entered the condition into the corrective action process as Condition Report 2020-05859. Corrective actions included clarifications to licensee procedures to prevent similar occurrences.

Significance/Severity: Severity Level IV. The inspectors concluded that the finding was a Severity Level IV violation in accordance with the Enforcement Policy, which includes a failure to make a report required by 10 CFR 50.72 as an example of a SL IV violation.

Because the licensee self-identified the condition, entered the condition in the corrective action program, and took action to address the causes, the inspectors concluded that the issue could be addressed as a licensee-identified non-cited violation.

Corrective Action References: CR 2020-05859 Failure to Use Procedure during Loss of Letdown Event Cornerstone Significance Cross-Cutting Report Aspect Section Initiating Event Green [H.8] - 71152A FIN 05000346/2022002-01 Procedure Open/Closed Adherence A self-revealed finding of very low safety significance (Green) was identified when the licensee failed to use procedures when responding to a loss of letdown. Specifically, the licensee failed to enter the annunciator response procedure and isolated letdown with valve MU2B instead of valves MU6 and MU4 per procedure. The licensee also failed to utilize procedures while attempting to restore letdown during the initial response to the loss of letdown.

Description:

On February 5, 2022, a switching of on-service purification demineralizers was performed.

During operator performance of this evolution, letdown was inadvertently isolated. Letdown pressure raised above 150psig, sounding annunciator alarm 2-2-A, "Letdown Pressure High,"

and letdown system pressure relief valve MU-1890 lifted. The annunciator response procedure corresponding to annunciator 2-2-A, "Letdown Pressure High," was not entered.

Entering the correct annunciator response procedure is required by NOP-OP-1002 "Conduct of Operations" revision 16. The annunciator response procedure, DB-OP-02002, 2-2-A, step 3.1 states, verify MU-4, pressure reducing valve closed, and step 3.2 states verify MU-6 letdown flow control valve closed. Operators did not reference a procedure but instead used their system knowledge and isolated letdown by closing letdown isolation valve MU-2B.

Operators attempted to restore letdown by closing MU10A (1 purification demineralizer inlet),opening MU10B (2 purification demineralizer inlet), and then opened MU-2B. Makeup system pressure increased to 145psig, and indications of rising reactor coolant drain tank (RCDT)level again caused operators to isolate letdown with MU2B again. Operators then entered abnormal procedure DB-OP-02512 Makeup and Purification System Malfunctions, section 4.3 Loss of letdown flow path." Following the loss of letdown, the level in the pressurizer increased. When pressurizer level reached 228 inches, operators entered LCO 3.4.9 condition A restore level to within limit within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Operators attempted to restore letdown again by opening MU104 purification demineralizer bypass and closing MU10B before opening MU2A and slowly raising letdown flow through MU6. Operators correctly diagnosed that letdown relief valve MU1890 failed to reseat based on indications of increasing RCDT level, and operators isolated letdown by closing MU6 and MU4. Operators again attempted to restore letdown through MU104 to allow mechanical agitation of MU1890 to seat the relief valve, but continuing indications of increasing RCDT level indicated MU1890 did not reseat.

Operators then entered DB-OP-02504, "Rapid Shutdown," and commenced a power reduction at 10 percent per minute. Operators did not restore pressurizer level to within limit and entered LCO 3.4.9. condition B be in mode 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and be in mode 4 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Letdown was isolated by closing MU4 and MU6, and MU1890 was manually cycled and reseated. Letdown was then restored with a stable level in the RCDT. Pressurizer level was restored to within limits and LCO 3.4.9 was exited with reactor power at approximately 15 percent.

Corrective Actions: Corrective actions included the removal of operators from duty for training remediation including simulator training specific to alarm response and procedural adherence, revisions to operating procedures, and improved control board markings.

Corrective Action References: CR 2022-00879, Abnormal procedure entries for loss of letdown flow path

Performance Assessment:

Performance Deficiency: The inspectors reviewed this finding using the guidance contained in IMC 0612, "Issue Screening," Appendix B, "Issue Screening Directions," dated July 23, 2021.

The inspectors determined that the licensees failure to use procedures during the initial response to the loss of letdown constituted a performance deficiency that was reasonably within the licensees ability to foresee and correct and should have been prevented.

Specifically, the licensee failed to enter the annunciator response procedure for letdown pressure high requiring isolation with valve MU6 and valve MU4 but operators isolated letdown with valve MU2B by memory without procedural guidance.

Screening: The performance deficiency was more than minor in accordance with IMC 0612, "Issue Screening," Appendix B, "Issue Screening Directions," dated July 23, 2021, because, if left uncorrected the performance deficiency had the potential to lead to a more significant safety concern. Specifically, by not performing activities affecting quality in accordance with a procedure, the operators could improperly manipulate plant equipment and challenge plant safety by causing unexpected transients or impact safety-related equipment.

Significance: The inspectors assessed the significance of the finding using IMC 0609 Appendix A, The Significance Determination Process (SDP) for Findings At-Power. The inspectors determined the finding to be of very low safety significance (Green) since it did not cause a reactor trip and the loss of mitigation equipment relied upon to transition the plant from the onset of the trip to a stable shutdown condition.

Cross-Cutting Aspect: H.8 - Procedure Adherence: Individuals follow processes, procedures, and work instructions. Specifically, the licensee failed to enter the annunciator response procedure for letdown pressure high during the initial response to loss of letdown.

Enforcement:

Inspectors did not identify a violation of regulatory requirements associated with this finding.

Failure to Provide Adequate Procedural Instructions when Swapping Purification Demineralizer Trains Cornerstone Significance Cross-Cutting Report Aspect Section Initiating Events Green [H.2] - Field 71152A NCV 05000346/2022002-02 Presence Open/Closed A self-revealed finding of very low safety significance (Green) and an associated non-cited violation (NCV) of Technical Specification (TS) 5.4.1(a) were identified for the licensees failure to establish and implement procedural guidance for performing a change of the on-service purification demineralizer. Specifically, the guidance in licensee procedure DB-OP-6006, "Makeup and Purification System," revision 53, for switching purification demineralizers did not provide instructions to ensure that the purification demineralizer being placed on-service was not manually isolated. This lack of procedural guidance resulted in control room operators inadvertently isolating letdown because they failed to un-isolate the manually closed outlet valve of purification demineralizer 1 prior to putting it on-service. This resulted in high pressure in the letdown system, lifting of the relief valve MU-1890, and subsequent increase of pressurizer level to over 228 inches. This required the licensee to enter TS LCO 3.4.9 conditions A and B, resulting in a rapid reduction in power to roughly 15 percent.

Description:

On February 5, 2022, a switching of on-service purification demineralizers was performed. A turnover for the command senior reactor operator and the balance of plant reactor operator was conducted so they could participate in a concurrent fire brigade drill. A pre-job brief for swapping to purification demineralizer 1 was conducted in the control room. The brief did not include a discussion of the caution tagged purification demineralizer outlet isolation valve MU139 that was closed due to leak-by of purification demineralizer 1 inlet isolation valve MU10A. A pre-job brief form was not used as required by procedure. The demineralizer swap was performed per DB-OP-6006, "Makeup and Purification System," revision 53.

DB-OP-6006 does not have a step to address the plant conditions encountered, namely that MU139 purification demineralizer 1 outlet had been manually isolated for an extended period due to leak-by of purification demineralizer 1 inlet, MU10A. The procedure does have such a step applying to purification demineralizer 3 outlet, for similar leak-by conditions. Operators inadvertently isolated letdown when taking purification demineralizer 2 off service because the purification demineralizer 1 lineup was not complete due to MU139 being closed. Letdown pressure increased above 150 psig, resulting in annunciator alarm 2-2-A, "letdown pressure high." Operators attempted to restore letdown but were unsuccessful. Following the loss of letdown, the level in the pressurizer rose. When pressurizer level reached 228 inches, the operators appropriately entered LCO 3.4.9 condition A restore level to within limit within one hour. Operators did not restore pressurizer level to within limit and entered LCO 3.4.9 condition B, be in mode 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and be in mode 4 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Operators entered DB-OP-02504, "Rapid Shutdown," and commenced a power reduction at 10 percent per minute. During the rapid shutdown, letdown was reestablished, and pressurizer level was restored to within limits, allowing operators to exit LCO 3.4.9 conditions A and B. Reactor power was reduced to approximately 15 percent before the restoration of letdown and proper pressurizer level.

Corrective Actions: Corrective actions included the removal of operators from duty for training remediation, issuance of standing order 22-001 for crew engagement in briefs and observations of evolutions, revision of the system procedure (DB-OP-6006, "Makeup and Purification System," revision 55) to address manipulation of each purification demineralizer outlet valve as required if there is known leak-by of the inlet valve, control room crew reorganization and assessment, and senior crew mentor implementation.

Corrective Action References: CR 2022-00879, "Abnormal procedure entries for loss of letdown flow path"

Performance Assessment:

Performance Deficiency: The inspectors reviewed this finding using the guidance contained in IMC 0612, "Issue Screening," Appendix B, "Issue Screening Directions," dated July 23, 2021.

The inspectors determined that the licensees failure to provide adequate procedural instructions to plant operators for performing a change of the on-service purification demineralizer constituted a performance deficiency that was reasonably within the licensees ability to foresee and correct and should have been prevented. Specifically, the licensee failed to provide procedural instructions to open purification demineralizer 1 outlet, MU 139, if it had been isolated due to leak-by of the purification demineralizer 1 inlet, MU 10A. However, the procedure has a step for purification demineralizer 3.

Screening: The inspectors determined the performance deficiency was more than minor in accordance with IMC 0612, "Issue Screening," Appendix B, "Issue Screening Directions,"

dated July 23, 2021, because it was associated with the configuration control (or human performance) attribute of the Initiating Events cornerstone and adversely affected the cornerstone objective to limit the likelihood of events that upset plant stability and challenge critical safety functions during shutdown as well as power operations. This issue is similar to example 4.b from IMC 0612 Appendix E, "Examples of Minor Issues."

Significance: The inspectors assessed the significance of the finding using IMC 0609 Appendix A, The Significance Determination Process (SDP) for Findings At-Power. The inspectors determined the finding had resulted in a transient initiator for the Initiating Events cornerstone and using, "Exhibit 1 - Initiating Events Screening Questions," determined that the finding was of very low safety significance (Green). Specifically, because the finding did result in a turbine trip, and not a reactor trip, the finding screened directly to Green without the need for a detailed risk evaluation.

Cross-Cutting Aspect: H.2 - Field Presence: Leaders are commonly seen in the work areas of the plant observing, coaching, and reinforcing standards and expectations. Deviations from standards and expectations are corrected promptly. Senior managers ensure supervisory and management oversight of work activities, including contractors and supplemental personnel.

Specifically:

A procedural change order was in progress to address procedural inadequacies in DB-OP-6006 but was not yet implemented at the time of the event.

The reactivity manipulation pre-job brief that occurred in the control room prior to the evolution did not accurately review the activity, or potential consequences, and supervision did not identify or correct the deviation from the standards and expectations.

Concurrent fire drill and relief turnover distractions occurred that impacted the brief, peer checks, and supervisory oversight of the reactivity manipulation for changing purification demineralizers with no intervention of supervision to mitigate the distractions.

Enforcement:

Violation: Technical Specification Section 5.4.1.a 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, February 1978. NRC Regulatory Guide 1.33, Revision 2, Appendix A, Section 3 addresses Procedures for Startup, Operation, and Shutdown of Safety-Related PWR Systems, Instructions for energizing, filling, venting, draining, startup, shutdown, and changing modes of operation should be prepared, as appropriate, for the following systems, Section 3.n, addresses Chemical and Volume Control System (including Letdown/Purification System). The licensee established procedure DB-OP-6006, Makeup and Purification System, revision 53, to provide instructions for operating the makeup and purification system.

Contrary to the above, between September 2, 2020 and February 7, 2022, the licensee failed to maintain a written procedure for the chemical and volume control system (including letdown/purification system). Specifically, the licensee failed to maintain procedure DB-OP-6006, Makeup and Purification System, such that it accurately directed operations personnel to un-isolate purification demineralizer 1 if it was manually isolated by MU-139 outlet for purification demineralizer 1.

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

URI Potential Adverse Changes During 2006 Emergency 93812 (Discussed) Diesel Generator Modifications URI 05000346/2021050-06

Description:

The NRC continues to evaluate an unresolved item documented in inspection report 2021050-06 (ADAMS Accession Number ML21348A767). Generally, the staff is assessing the adequacy of the sites modification associated with the installation of the emergency diesel generator field flash selector switches.

EXIT MEETINGS AND DEBRIEFS

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

On July 27, 2022, the inspectors presented the integrated inspection results to Mr. T. Brown, Site Vice President, and other members of the licensee staff.

On March 18, 2022, the inspectors presented the ISI Exit Meeting inspection results to Mr. T. Brown, Site Vice President, and other members of the licensee staff.

On May 16, 2022, the inspectors presented the radiation protection baseline inspection results to Mr. T. Brown, Site Vice President, and other members of the licensee staff.

On July 1, 2022, the inspectors presented the emergency preparedness program inspection results to Mr. T. Brown, Site Vice President, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.04 Corrective Action 2022-03619 BACC: Boric Acid Leak from DH154 Pipe Cap 04/26/2022

Documents

71111.04 Corrective Action 2022-03714 Maintenance Rule Reviews for CREVS System 04/29/2022

Documents

71111.04 Corrective Action 2022-03879 CREVS Refrigerant Line Insulation and Support Degradation 05/05/2022

Documents

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

Procedure

71111.04 Procedures DB-OP-06013 Containment Spray System 28

71111.04 Procedures DB-OP-06505 Control Room Emergency Ventilation System Procedure 22

71111.05 Fire Plans PFP-AB-115 ECCS Pump Room 1-2, Rooms 115, Fire Area A-04 06

71111.05 Fire Plans PFP-AB-428 Low Voltage Switchgear Room F - Bus, Room 428, 05

Fire Area X

71111.05 Fire Plans PFP-AB-429 Low Voltage Switchgear Room E - Bus, Room 429, 05

Fire Area Y

71111.05 Fire Plans PFP-AB-500 Radwaste and Fuel Handling Areas Air Supply Equipment 05

Area, Room 500, Fire Area EE

71111.05 Fire Plans PFP-AB-501 Radwaste Exhaust Equipment and Main Station Exhaust Fan 06

Room, Rooms 501 and 501DC, Fire Area EE

71111.05 Fire Plans PFP-AB-515 Purge Exhaust Equipment Room, Room 515, Fire Area EE 05

71111.05 Fire Plans PFP-CB-214 Core Flooding Tank Area, Room 214, Fire Area D 06

71111.05 Fire Plans PFP-CB-215 Let Down Coolers Area, Room 215, Fire Area D 06

71111.05 Fire Plans PFP-CB-216 Steam Generator West D Ring Area, Room 216, Fire Area D 06

71111.05 Fire Plans PFP-CB-218 Steam Generator East D Ring Area, Room 218, Fire Area D 06

71111.05 Fire Plans PFP-CB-317 Containment Air Cooler Area, Room 317 and 317A, 08

Fire Area D

71111.05 Fire Plans PFP-CB-410 East Elevation 603' and Valve Room Elevation 636', Rooms 05

410 and 508, Fire Area D

71111.05 Fire Plans PFP-CB-A208 Southwest Penetration Area of Annulus Space Elevations 08

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

71111.05 Fire Plans PFP-CB-A236H East and Southwest Penetration Areas at Elevations 585' 08

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

Inspection Type Designation Description or Title Revision or

Procedure Date

AB

71111.05 Fire Plans PFP-CB-A236L East Penetration Area of Annulus Space Elevations 585' and 05

603', Partial Room 127E, Fire Area A

71111.05 Fire Plans PFP-CB-EL565 North Area 565' Elevation, Rooms 213, 217 and Normal 08

Sump Area, Fire Area D

71111.05 Fire Plans PFP-CB-EL603 Fuel Transfer Pool and North and West 603' Elevation, 05

Rooms 219, 407 and 410A, Fire Area D

71111.08P Corrective Action 2022-02047 Foreign Material Found During Control Rod Guide Tube 04/08/2022

Documents MRP-227-A Exam

71111.08P Engineering INR-DB1R22-001 Reactor Vessel - RPV Interior - Keys Examination 03/14/2022

Evaluations

71111.08P Procedures 54-IISI-400-024 Multi-Frequency Eddy Current Examination of Tubing 12/07/2020

71111.08P Procedures 54-ISI-808-000 Automated Phased Array Ultrasonic Examination of PPWR 03/24/2020

Vessel Shell Welds

71111.08P Procedures 54-ISI-809-000 Automated Phased Array Ultrasonic Examination of PWR 03/24/2020

Vessel Nozzle to Shell Welds from Nozzle Bore

71111.08P Procedures NA-QC-00191 Liquid Penetrant Examination 9

71111.08P Procedures NOP-CC-5763 Appendix VIII Procedure for Ultrasonic Examination of 5

Austenitic Pipe Welds

71111.08P Procedures NOP-CC-5765 Appendix VIII Procedure for Straight Beam Ultrasonic 6

Examination of Bolts and Studs

71111.08P Procedures NOP-ET-2001 Boric Acid Corrosion Control Program 19

71111.08P Procedures WPS A8-2-1 Gas Tungsten (GTAW) of Stainless Steel (P8), Groove with 03

or Without Backing

71111.12 Corrective Action 2015-15566 Document NA of Step in DB-ME-09205 During YVA PM 11/15/2015

Documents

71111.12 Corrective Action 2022-03731 Decay Heat Pump Problem Solving 04/29/2022

Documents

71111.12 Corrective Action 2022-03860 X2 Replacement Board for YVB Found Bad 05/05/2022

Documents

71111.12 Corrective Action 2022-03869 Document NA of Step in DB-ME-09205 During YVB PM 05/05/2022

Documents

71111.12 Corrective Action 2022-04131 P42-2, 2 Decay Heat Oil Pump 2, Pump O/B Bearing Level 05/15/2022

Documents Low

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.12 Corrective Action 2022-04174 Turbine Building Ventilation Concerns 05/17/2022

Documents

71111.12 Corrective Action 2022-04175 Annunciator 5-1-B Delayed During SFAS CH 1 Monthly 05/17/2022

Documents Functional

71111.12 Corrective Action 2022-04452 YVB Normal Operations Light is Out 05/26/2022

Documents

71111.12 Corrective Action 2022-04722 DH Pump 2 Pump O/B Oil Leak 06/09/2022

Documents

71111.12 Miscellaneous 80-9230400-90 Oscillator Board Technical Description

71111.12 Procedures DB-ME-09202 Maintenance of Essential SC1 UPS 10

71111.12 Procedures DB-ME-09205 Maintenance of Inverters YVA and YVB 11

71111.13 Corrective Action 2022 -04032 Main Feed Pump 2 Recirculation Valve FW438 Packing Leak 05/12/2022

Documents

71111.13 Drawings OS-012A SH 1 Main Feedwater System 26

71111.13 Miscellaneous IR22 Shutdown Defense In-Depth Report 00

71111.13 Procedures NOP-OP-1007 Risk Management 36

71111.15 Corrective Action 2020-01652 1R21 BACC: Boric Acid Crystals and Oil Underneath West 03/01/2020

Documents Fuel Transfer Tube Flange

71111.15 Corrective Action 2020-01664 1R21 BACC: Fuel Transfer Tube 1-2 Flange 03/02/2020

Documents

71111.15 Corrective Action 2022-03169 1R22 BACC: Active Leak in Refueling Canal/ Deep End 04/11/2022

Documents

71111.15 Corrective Action 2022-03435 Main Feed Pump 2 Recirculation Valve FW438 Packing Leak 05/19/2022

Documents

71111.15 Corrective Action 2022-03566 Minor Cooling Water Leak on Decay Heat Pump 2 04/24/2022

Documents

71111.15 Corrective Action 2022-03570 AFPT 1 Steam Admission Valve Leak-By 04/24/2022

Documents

71111.15 Corrective Action 2022-03614 Periodic Verification Testing of MS106, MS107 and MS107A 04/26/2022

Documents Missed Frequency

71111.15 Corrective Action 2022-03669 Decay Heat Pump 1 IB/OB Bearings Constant Level Oilers 04/28/2022

Documents Were Found Empty

71111.15 Corrective Action 2022-03704 RCP 1-2 Motor Lower Bearing High Oil Level Alarm 04/29/2022

Documents

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.15 Corrective Action 2022-03879 CREVS Refrigerant Line Insulation and Support Degradation 05/05/2022

Documents

71111.15 Corrective Action 2022-04128 RCP 1-2 Seal Leakage Increased Following CAC Swap/CAC 05/15/2022

Documents 2 Monthly Testing

71111.15 Corrective Action 2022-04380 RCP 2-2 Seal Return TIRC17A2 Failed to Mid-Scale 05/24/2022

Documents (Approx. 214 F)

71111.15 Corrective Action 2022-04523 Reactor Coolant Pump 1-2 Leakage Missed 1R22 Learning 05/31/2022

Documents Opportunity

71111.15 Corrective Action 2022-04535 Main Steam Line 1 MS131 Leaks by the Closed Seat 06/01/2022

Documents

71111.15 Corrective Action 2022-04574 Found CCW Train 1 Ventilation Damper Open with Fan Off 06/01/2022

Documents

71111.15 Corrective Action 2022-04651 Component Cooling Water Pump 1 Outboard Bearing Oil 06/06/2022

Documents Leak

71111.15 Corrective Action 2022-04668 Potentiometer Dead Spots Found While Cycling SBODG 06/07/2022

Documents MOC

71111.15 Corrective Action 2022-04688 SBODG Overfilled with Lube Oil 06/07/2022

Documents

71111.15 Corrective Action 2022-04691 DH Pump 2 Outboard Bearing Oil Leak 06/07/2022

Documents

71111.15 Corrective Action 2022-04695 Foreign Material Identified in New Hoses for Replacement on 06/08/2022

Documents SBODG

71111.15 Corrective Action 2022-04722 DH Pump 2 Pump O/B Oil Leak 06/09/2022

Documents

71111.15 Corrective Action 2022-04759 Potential FME Falling into Cooling Tower Basin 06/09/2022

Documents

71111.15 Corrective Action 2022-04788 Station Blackout Diesel Generator Water Jacket Specific 06/10/2022

Documents Gravity High Out of Specification

71111.15 Corrective Action 2022-04789 Unexpected Alarm Received for Control Valve 4 Output 06/10/2022

Documents Current Voting Mismatch

71111.15 Corrective Action 2022-04807 Entered DB-OP-02515 Reactor Coolant Pump And Motor 06/12/2022

Documents Abnormal Operation Due to RCP 1-2 Third Stage Seal

Pressure Lowering and Bringing in Computer Point P814

71111.15 Miscellaneous ODMI 22-02 Operation with Reactor Coolant Pump 1-2 Indications of 00

Inspection Type Designation Description or Title Revision or

Procedure Date

Degraded Seal Performance

71111.19 Corrective Action 2022-03912 Service Water SW1357 Failed to Stroke Open 05/07/2022

Documents

71111.19 Corrective Action 2022-04063 SW1357 Open Stroke Time Exceeded Maximum Time 05/13/2022

Documents

71111.19 Corrective Action 2022-04101 Service Water SW1357 Nitrogen Supply Box Shield has 05/13/2022

Documents Stripped, Broken Fasteners

71111.19 Procedures DB-PF-03027 Service Water Train 2 Valve Test 40

71111.20 Procedures DB-MI-05253 Nuclear Instrumentation NI 06 (RPS Channel 1) Power 15

Range Adjustment

71111.20 Procedures DB-MI-05254 Nuclear Instrumentation NI 05 (RPS Channel 2) Power 15

Range Adjustment

71111.20 Procedures DB-MI-05255 Nuclear Instrumentation NI 08 (RPS Channel 3) Power 15

Range Adjustment

71111.20 Procedures DB-MI-05256 Nuclear Instrumentation NI 07 (RPS Channel 4) Power 15

Range Adjustment

71111.20 Procedures DB-NE-03212 Zero Power Physics Testing 13

71111.22 Corrective Action 2022-04169 PDS-2686B Preconditioned During Performance of 05/16/2022

Documents DB-MI-03203

71111.22 Corrective Action 2022-04169 PDS-2686B Preconditioned During Performance of 05/16/2022

Documents DB-MI-03203

71111.22 Procedures DB-MI-03203 Channel Functional Test and Calibration of SFRCS Actuation 18

Channel 1, Steam Generator Differential Pressure Inputs

PDS-2686A, PDS-2686B, PDS-2685C AND PDS-2685D

71111.22 Procedures DB-PF-03001 Main Steam Safety Valve Setpoint Test 10

71111.22 Work Orders 200821891 RT 11915 DB-FX-P1A Operational Inspection 05/04/2020

71111.22 Work Orders 200821891 RT 11915 DB-FX-P1A Operational Inspection 05/04/2020

71111.22 Work Orders 200822483 SFRCS Channel 2 Integrated Test 03/06/2022

71111.22 Work Orders 200825784 Decay Heat Train 2 Pump and Valve Test (Mode 1-3) 06/06/2022

71111.22 Work Orders 200842476 MI3203-001 08.000 CH1 SFRCS ACH1 05/16/2022

71111.22 Work Orders 200842476 MI3203-001 08.000 Channel 1 SFRCS ACH1 05/16/2022

71111.22 Work Orders 200860045 PM 5554 SP17A1 Test MSSVs 02/27/2022

71114.02 Corrective Action 2020-03003 Communication Failure on Siren 803 and Battery Failures on 04/08/2020

Documents Sirens 402&507

Inspection Type Designation Description or Title Revision or

Procedure Date

71114.02 Corrective Action 2020-05101 Siren Computer Remote Access Phone Lines Issues 06/16/2020

Documents

71114.02 Corrective Action 2020-05859 Late 10 CFR 50.72 Notification of Siren Activation 08/20/2020

Documents

71114.02 Corrective Action 2020-06246 DB Sirens 309 and 504 Reported False Failures 09/04/2020

Documents

71114.02 Corrective Action 2021-00752 4 DB EPZ Sirens Indicated Chopper Motor Current Fail After 02/05/2021

Documents the 02/05/2021 One Minute Audible Siren

71114.02 Corrective Action 2021-03470 Trending of Alert and Notification System (Sirens) 04/29/2021

Documents

71114.02 Corrective Action 2021-04458 Trending of Alert and Notification System Sirens - Siren 504 06/04/2021

Documents

71114.02 Corrective Action 2022-04213 DB Siren 2 Failure 05/18/2022

Documents

71114.03 Corrective Action 2020-06204 Missed ERO 3rd Quarter Tabletop Drill 07/30/2020

Documents

71114.03 Corrective Action 2020-06317 On Duty ERO Member Did Not Respond Appropriately 08/10/2020

Documents

71114.03 Corrective Action 2021-03367 Emergency Response Organization Not Notified When 04/27/2021

Documents Individual Assigned to On-Call Position Went on Short Term

Leave

71114.03 Corrective Action 2021-03667 CANS Weekly Test Phone Call Issue 05/05/2021

Documents

71114.03 Corrective Action 2021-03929 Individual Did Not Complete All Required Requalification 05/13/2021

Documents Training to Support SCBA Quals

71114.03 Corrective Action 2021-04224 Strategic Engineer Call-Tree Individual Did Not Respond to 05/25/2021

Documents Augmented Call-In Drill in a Timely Manner

71114.03 Corrective Action 2021-04233 RP Call-Tree Individual Did Not Respond to the Augmented 05/25/2021

Documents Call-In Drill in a Timely Manner

71114.03 Corrective Action 2021-04271 Chemistry Call-Tree Individual Failed to Respond to 05/26/2021

Documents Augmented Call-In Drill

71114.03 Corrective Action 2021-06935 Ops Advisor Call-Tree Position Individual Did Not Respond 09/15/2021

Documents to the ERO Call-In Drill

71114.03 Corrective Action 2021-09314 ERO Call-Tree Position Individual Did Not Respond to CANS 12/08/2021

Inspection Type Designation Description or Title Revision or

Procedure Date

Documents Call-In Drill

71114.03 Corrective Action 2022-01665 Effective Review for ERO Call-In Response Did Not Meet 03/03/2022

Documents Success Metrics

71114.03 Corrective Action ATA-2021-13077 4th Quarter 2021 Unannounced Call-In Drill 10/14/2021

Documents

71114.03 Miscellaneous ATA-2020-12191 3rd Quarter 2020 Unannounced Call-In Drill 11/06/2020

71114.03 Miscellaneous ATA-2020-15528 4th Quarter 2020 Unannounced Call-In Drill 12/19/2020

71114.03 Miscellaneous ATA-2021-13075 2nd Quarter 2021 Unannounced Call-In Drill 04/12/2021

71114.03 Miscellaneous ATA-2021-13076 3rd Quarter 2021 Unannounced Call-In Drill 07/01/2021

71114.03 Miscellaneous ATA-2021-4521 1st Quarter 2021 Unannounced Call-In Drill 03/26/2021

71114.05 Corrective Action 2021-01242 EP Drill: Drill Objective C.7 Not Met Due to Failing to 02/24/2021

Documents Communicate Entire PAR

71114.05 Corrective Action 2021-01253 EP Drill: EOF Controller Interject For State and County 02/24/2021

Documents Communication

71114.05 Corrective Action 2021-06491 EP Drill: CTRM Simulate Initial Notification Objective C.1 Met 08/27/2021

Documents with Comments

71114.05 Corrective Action 2021-06496 EP Drill: Drill Objective F.6 Not Met for DA due to Controller 08/27/2021

Documents Inject

71114.05 Miscellaneous DBNPS Emergency Plan 35

71114.05 Miscellaneous ATA-2020-13695 2020 Medical Emergency Drill 11/06/2020

71114.05 Miscellaneous ATA-2021-5276 EP Integrated Drill Evaluation 04/07/2021

71114.05 Miscellaneous ATA-2021-5372 Evaluate 1st Quarter 2021 ERO Proficiency Table Top Drills 04/09/2021

71114.05 Miscellaneous ATA-2022-10418 Evaluation the Performance of the ERO During the 06/07/2022

August 24, 2021 EP Integrated Drill

71114.05 Miscellaneous ATA-2022-10737 3rd Quarter 2021 ERO Proficiency Tabletop Drill Summary 06/11/2022

71114.05 Miscellaneous ATA-2022-9175 Assess the Performance During the 2021 Post-Accident 05/15/2022

Sample Drills

71114.05 Miscellaneous ATA-2022-9176 Evaluated Performance During October 15, 2021, Ops DA 05/15/2022

Focus Area Drill

71114.05 Miscellaneous CA-SA-DB-2020- 2020 RMT Environmental Sample Drill Results 10/13/2020

0005

71114.05 Miscellaneous DBRM-EMER- Davis-Besse Emergency Action Level Basis Document 09

1500A

71114.05 Miscellaneous RA-EP-01500 Davis-Besse Nuclear Power Station Emergency Plan 16

Inspection Type Designation Description or Title Revision or

Procedure Date

Implementing Procedure

71114.06 Corrective Action 2022-04375 Simulator Malfunction Could Not be Removed During an 05/24/2022

Documents Evaluated Scenario

71114.06 Corrective Action 2022-04396 EP Drill 5/24/22 Integrated Drill UE Classification 06/24/2022

Documents

71114.06 Corrective Action 2022-04403 EP Drill Simulator Computer Point Did Not Display Correctly 06/24/2022

Documents

71114.06 Corrective Action 2022-04413 05/24/22 EP Integrated Drill Started 1 Hour Late Due to 05/25/2022

Documents Phone Issues in Simulator

71114.06 Corrective Action 2022-04415 EP Drill - Incorrect Release Path Analyzed Caused Missed 05/25/2022

Documents Drill Objective F.13

71114.06 Miscellaneous Davis-Besse Nuclear Power Station Drill/Exercise 05/24/2022

May 24, 2022

71124.05 Calculations Library 105 Gamma Spectroscopy Nuclide Library 01

71124.05 Calibration LI 2.12.112 ARGOS-5 Calibration Record 12/31/2020

Records

71124.05 Calibration LI 2.12.112 ARGOS-5 Calibration Record - Partial Calibration 03/05/2021

Records Completed for Detector Replacement

71124.05 Calibration LI 2.12.112 ARGOS-5 Calibration Record 01/19/2022

Records

71124.05 Calibration LI 2.12.113 Chronos-4 Calibration Record 10/08/2020

Records

71124.05 Calibration LI 2.12.113 Chronos-4 Calibration Record 10/19/2021

Records

71124.05 Calibration LI 2.12.115 GEM-5 Calibration Record 02/04/2021

Records

71124.05 Calibration LI 2.12.115 GEM-5 Calibration Record 02/11/2022

Records

71124.05 Calibration LI 2.12.42 Whole Body Counter Calibration Record 11/03/2021

Records

71124.05 Calibration LI 2.12.42 Whole Body Counter Calibration Record 02/28/2022

Records

71124.05 Calibration LI 2.12.54 SAM-11 Calibration Record 07/21/2021

Records

Inspection Type Designation Description or Title Revision or

Procedure Date

71124.05 Calibration LI 2.7.233 ASP-1 with Neutron Radiation Detector Calibration Record 04/14/2021

Records

71124.05 Calibration LI 2.7.233 ASP-1 with Neutron Radiation Detector Calibration Record 07/08/2021

Records

71124.05 Calibration LI 2.7.502 Amp-100 Calibration Record 03/01/2022

Records

71124.05 Calibration LI 2.7.502 AMP-100 Calibration Record 03/01/2021

Records

71124.05 Calibration LI 2.7.545 Model L-177 Stationary Frisker Calibration Record 01/04/2021

Records

71124.05 Calibration LI 2.7.545 Model L-177 Stationary Frisker Calibration Record 01/03/2022

Records

71124.05 Calibration LI 2.7.558 Model L-177 Stationary Frisker Calibration Record 02/22/2021

Records

71124.05 Calibration LI 2.7.558 Model L-177 Stationary Frisker Calibration Record 02/11/2022

Records

71124.05 Calibration LI 2.7.682 FUJI Electric Model NSN3 Calibration Record 11/08/2021

Records

71124.05 Calibration M&TE FAF0047 Calibration of Mass Thermal Flowmeter 09/21/2022

Records

71124.05 Corrective Action 2020-07352 RE5328A Will Not Calibrate 09/21/2020

Documents

71124.05 Corrective Action 2020-07798 Station Vent Flow Computer Point F885 Step Change 10/08/2020

Documents

71124.05 Corrective Action 2020-07980 2020 D-B Mid-Cycle Assessment Observation - Radiation 10/14/2020

Documents Element Belt Guards

71124.05 Corrective Action 2020-08509 RE4597A Flow Reg Valve is >60 Percent Open 11/02/2020

Documents

71124.05 Corrective Action 2020-09062 RP Section Gamma-Spec Failed Daily QC Check 11/25/2020

Documents

71124.05 Corrective Action 2020-09113 Gamma-Spec Failed Daily QC Check 11/29/2020

Documents

71124.05 Corrective Action 2020-09482 451B 2.7.525 Failed Source Check 12/15/2020

Documents

Inspection Type Designation Description or Title Revision or

Procedure Date

71124.05 Corrective Action 2020-09645 HPGe 3 (Radiation Protection) Failed Daily Source Check 12/22/2020

Documents

71124.05 Corrective Action 2021-00174 Gamma-Spec Failed Daily Quality Control Check 01/10/2021

Documents

71124.05 Corrective Action 2021-00727 J.L. Shepherd Model 89 Gamma Irradiator Safety Lock 02/04/2021

Documents Failure

71124.05 Corrective Action 2021-01230 RE4597BA Flow Regulating Valve is >60 Percent Open 02/24/2021

Documents

71124.05 Corrective Action 2021-08786 IPA Quarterly Trending - Radiation Monitoring Equipment 11/17/2021

Documents

71124.05 Corrective Action 2022-04055 NRC Identified: Full Standardization of the Model 89 05/12/2022

Documents Calibrator

Resulting from

Inspection

71124.05 Corrective Action 2022-04146 NRC Identified: DB-HP-04029 Inconsistencies 05/16/2022

Documents

Resulting from

Inspection

71124.05 Corrective Action 2022-04147 NRC Identified: Documentation of Dose Study for Measuring 05/16/2022

Documents RE4598 Grab Samples

Resulting from

Inspection

71124.05 Miscellaneous DB-0395-2 Model 89 Standardization Check 01/13/2022

71124.05 Miscellaneous DB-0395-2 Model 89 Standardization Check 01/15/2021

71124.05 Miscellaneous Interlab Cross Results of Radiochemistry Cross Check Program 01/01/2020 -

Check Program 12/31/2021

71124.05 Miscellaneous NOP-OP-3201-06 2020 and 2021 Interlaboratory Testing Program Results 01/01/2020 -

2/31/2021

71124.05 Procedures DB-0500-0 Instrument Evaluation Form 00

71124.05 Procedures DB-HP-00010 Radiation Measuring and Test Equipment Calibration and 12

Control Program

71124.05 Procedures DB-HP-01103 Use of Portable Radiation, Contamination, and Airborne 07

Survey Equipment

71124.05 Procedures DB-HP-01407 Calibration and Use of the J.L. Shepherd Model 89 09

Inspection Type Designation Description or Title Revision or

Procedure Date

71124.05 Procedures DB-HP-01458 Ludlum Model 2000 Portable Scaler Operation and 02

Calibration

71124.05 Procedures DB-HP-1407 Calibration and Use of the J.L. Shepherd Model 89 09

71124.05 Procedures DB-MI-04559 Channel Calibration if RE-1998 (Failed Fuel) 19

71124.05 Procedures DBBP-RP-1007 Meter Source and Response Testing 48

71124.05 Procedures NOP-OP-4416 ARGOS-5 Personnel Contamination Monitor Calibration and 00

Use

71124.05 Work Orders 200761572 DB-HP4029-001 Review Rad Monitor Setpoints 12/30/2020

71151 Miscellaneous NRC Performance Indicator Data; Emergency Preparedness 01/01/2021 -

Drill/Exercise Performance 03/30/2022

71151 Miscellaneous NRC Performance Indicator Data; Emergency Preparedness: 01/01/2021 -

ERO Participation Drill 03/30/2022

71151 Miscellaneous NRC Performance Indicator Data; Emergency Preparedness: 01/01/2021 -

Alert and Notification System 03/30/2022

71152A Corrective Action 2022-00879 Abnormal Procedure Entries for Loss of Letdown Flow Path 02/05/2022

Documents

71152A Corrective Action 2022-00879 Abnormal Procedure Entries for Loss of Letdown Flow Path 02/05/2022

Documents

71152A Procedures DB-OP-01003 Operations Procedure Use Instructions 16

71152A Procedures DB-OP-02002 Letdown/Makeup Alarm Panel 2 Annunciators 15

71152A Procedures DB-OP-02512 Makeup and Purification System Malfunctions 19

71152A Procedures DB-OP-06006 Makeup and Purification System 56

71152A Procedures DBBP-DCU-0109 Processing Engineering Change Packages 33

71152A Procedures NOBP-OP-0012 Operator Work-Arounds, Burdens, Control Room 09

Deficiencies and Operations Aggregate Assessment

71152A Procedures NOBP-SS-4001 Change Management 04

71152A Procedures NOP-LP-2601 Procedure/Work Instruction Use and Adherence 08

71152A Procedures NOP-OP-1001 Clearance/Tagging Program 34

71152A Procedures NOP-OP-1002 Conduct of Operations 16 & 17

71152A Procedures NOP-OP-1014 Plant Status Control 08

26