IR 05000313/2023002

Integrated Inspection Report 05000313/2023002 and 05000368/2023002 and Notice of Violation

ML23221A301
Person / Time
Site:	Arkansas Nuclear
Issue date:	08/11/2023
From:	John Dixon NRC/RGN-IV/DORS/PBD
To:	Pehrson D Entergy Operations
References
IR 2023002
Download: ML23221A301 (41)

Text

August 11, 2023

SUBJECT:

ARKANSAS NUCLEAR ONE - INTEGRATED INSPECTION REPORT 05000313/2023002 AND 05000368/2023002 AND NOTICE OF VIOLATION

Dear Doug Pehrson:

On June 30, 2023, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Arkansas Nuclear One. On July 13, 2023, 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.

The enclosed report discusses a violation associated with a finding of very low safety significance (Green), for the failure to ensure that conditions adverse to quality, involving failures of emergency feedwater steam supply check valves, were promptly identified and corrected. The NRC evaluated this violation in accordance section 2.3.2 of the NRC Enforcement Policy, which can be found at http://www.nrc.gov/about-nrc/regulatory/enforcement/enforce-pol.html. We determined that this violation did not meet the criteria to be treated as a non-cited violation because the violation had been previously identified in 2018, and failures continue to occur for Unit 2, indicating compliance has not been restored within a reasonable period of time.

You are required to respond to this letter and should follow the instructions specified in the Notice of Violation when preparing your response. If you have additional information that you believe the NRC should consider, you may provide it in your response. The NRCs review of your response will also determine whether further enforcement action is necessary to ensure your compliance with regulatory requirements.

Additionally, two findings of very low safety significance (Green) are documented in this report.

These findings involved violations of NRC requirements. We are treating these violations as non-cited violations (NCVs) 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 IV; the Director, Office of Enforcement; and the NRC Resident Inspector at Arkansas Nuclear One.

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 IV; and the NRC Resident Inspector at Arkansas Nuclear One.

This letter, its enclosure, and your response 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 Dixon, John on 08/11/23

John L. Dixon, Jr., Chief Reactor Projects Branch D Division of Operating Reactor Safety

Docket Nos. 05000313, 05000368 License Nos. DPR-51, NPF-6

Enclosure:

1. Notice of Violation 2. Inspection Report 05000313/2023002 and 05000368/2023002

Inspection Report

Docket Numbers:

05000313 and 05000368

License Numbers:

DPR-51 and NPF-6

Report Numbers:

05000313/2023002 and 05000368/2023002

Licensee:

Entergy Operations, Inc.

Facility:

Arkansas Nuclear One

Location:

Russellville, AR

Inspection Dates:

April 1, 2023, to June 30, 2023

Inspectors:

D. Antonangeli, Health Physicist

R. Azua, Senior Reactor Inspector

N. Brown, Resident Inspector

R. Bywater, Senior Resident Inspector

T. DeBey, Resident Inspector

N. Greene, Senior Health Physicist

J. O'Donnell, Senior Health Physicist

Approved By:

John L. Dixon, Jr., Chief

Reactor Projects Branch D

Division of Operating Reactor Safety

Enclosure 2

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SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Arkansas Nuclear One, 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 Properly Evaluate a Replacement Motor-Operated Valve Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000313/2023002-01 Open/Closed

[H.12] - Avoid Complacency 71111.18 The inspectors identified a Green finding and associated non-cited violation of 10 CFR Part 50, Appendix B, Criterion III, Design Control, for the licensees failure to evaluate all aspects of several service water boundary valve replacement motor-operated valves (MOVs). Specifically, modification engineering change 85805 installed a new, Unit 1, loop 2 service water-to-intermediate cooling water isolation valve CV-3811, which had a thicker actuator mounting plate than the original valve but reused the original fasteners in the final installation. Consequently, the installed actuator mounting fasteners did not meet thread engagement requirements.

Failure to Perform Air Sampling Analysis Resulting in Two Uptakes Cornerstone Significance Cross-Cutting Aspect Report Section Occupational Radiation Safety Green NCV 05000368/2023002-02 Open/Closed

[H.1] -

Resources 71124.04 The inspectors reviewed a self-revealed Green, non-cited violation of Technical Specification 6.4.1 for the licensee's failure to follow procedures to assess an air sample prior to a job activity. Specifically, the licensee failed to analyze an air sample prior to filter changeouts resulting in two workers receiving unintended exposure to airborne radioactivity (i.e., an uptake).

Failure to Establish Adequate Corrective Actions Resulting in Excessive Instances of Damaged and Broken Internals of the Emergency Feedwater Pump Turbine Steam Admission Check Valves Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NOV 05000368/2023002-03 Open

[H.6] - Design Margins 71152A The inspectors identified a Unit 2 Green finding and associated Notice of Violation of 10 CFR Part 50, Appendix B, Criterion XVI, Corrective Action, for the failure to promptly identify and correct a condition adverse to quality. Specifically, the licensee failed to correct in a timely manner the deficient system design of the check valves admitting steam to the emergency feedwater turbine.

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PLANT STATUS

Unit 1 began the inspection period at full power. On May 25, 2023, Unit 1 operators reduced power to 98.8 percent following a failure of circulating water pump B. Failure of circulating water pump B resulted in only 2 out of 4 circulating water pumps remaining functional, because circulating water pump D remained out of service for repairs following a failure it sustained on February 10, 2023. Operators returned power to 100 percent on May 26, 2023. Unit 1 continued operating at or near full power until June 30, 2023, when Unit 1 operators reduced power to approximately 96 percent because elevated lake temperatures exceeded the capability of the unit to operate at full power with only two circulating water pumps in operation.

Unit 2 began the inspection period operating at approximately 88 percent power in an end-of operating cycle power coast down. Unit 2 operators removed the unit from service on April 14, 2023, to begin refueling outage 2R29. Following the refueling outage, Unit 2 operators restarted the reactor on May 22, 2023, placed the unit online on May 23, 2023, and returned the unit to 100 percent power on May 26, 2023. On June 14, 2023, Unit 2 operators manually tripped the B main feedwater pump in response to an electrohydraulic control fluid leak on the pump turbine, which stopped the leak and initiated a turbine runback. Reactor power was reduced to approximately 79.2 percent and stabilized at approximately 80 percent power while repairs were made to an electrohydraulic control fluid fitting. After repairs were completed, Unit 2 operators raised power to 100 percent the same day. On June 14, 2023, Unit 2 operators identified symptoms of failure of the A main feedwater pump and initiated a rapid power reduction. The operators stabilized power at approximately 75 percent. The cause of the main feedwater pump A failure was failure of the turbine-to-pump coupling. Following completion of repairs, Unit 2 operators returned the unit to 100 percent power on June 17, 2023. Unit 2 remained at or near full power for the remainder of the inspection period.

INSPECTION SCOPES

Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors performed activities described in IMC 2515, Appendix D, Plant Status, 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.

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71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (1 Sample)

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

(1)alternate AC diesel generator after loss of London line (13.8 kV) and restoration activities on June 20, 2023

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

(1) The inspectors evaluated system configurations during a complete walkdown of the Unit 1 turbine-driven emergency feedwater system on June 28, 2023.

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (3 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) Unit 2 electrical class 1E cable spreading room, fire zone 2108-S, on May 23, 2023

(2) Unit 1 class 1E A3 4160 Vac switchgear, fire zone 100-N, on May 23, 2023

(3) Unit 1 turbine building, fire zone 197-X, on May 31, 2023

71111.07A - Heat Exchanger/Sink Performance

Annual Review (IP Section 03.01) (1 Sample)

The inspectors evaluated readiness and performance of:

(1) Unit 2 shutdown cooling heat exchangers 2E-35A and 2E-35B on April 25, 2023

===71111.08P - Inservice Inspection Activities (PWR) The inspectors verified that the reactor coolant system boundary, 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 April 16, 2023, to April 28, 2023.

PWR Inservice Inspection Activities Sample - Nondestructive Examination and Welding Activities (IP Section 03.01)===

The inspectors verified that the following nondestructive examination and welding activities were performed appropriately:

(1)

• Chemical Volume and Control System (Charging) 2CCA-26, ID 41-008, Pipe to Elbow Circumferential Weld (UT)

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• Low Pressure Safety Injection System 2CCA-22-1, ID 2-22-001A, Elbow to Pipe Circumferential Weld (UT)

• Low Pressure Safety Injection System 2CCA-22-1, ID 2-22-003, Pipe from Check Valve 2SI-15A to Elbow Circumferential Weld (UT)

• Chemical Volume and Control System (Charging) 2CCA-27-4, ID 40-059, One Way Small Pipe Restraint for Charging Inlet from Regenerative Heat Exchanger (VT-3)

• Service Water to Emergency Diesel Jacket Cooler 2E20B, ID 2-73-044W, Integrally Welded Pipe Support Attachment 2HBC-64-H9 (VT-1 & VT-3)

• Safety Injection and Shutdown Cooling to RCP C 2CCA-24, ID 23-069, Anchor for Pipe 2CCA-24-H22 (PT)o Weld package reviewed: Reviewed licensee historical weld package related to Safety Injection System Pipe Anchor 23-069 and reviewed licensee evaluation of indications identified in the dye penetrant testing, and actions taken by the licensee

• Service Water 2HBC-34, ID FW-016, Pipe Weld (MT)

PWR Inservice Inspection Activities Sample - Vessel Upper Head Penetration Inspection

Activities (IP Section 03.02) (1 Sample)

The inspectors verified that the licensee conducted the following vessel upper head penetration inspections and addressed any identified defects appropriately:

(1) The inspector observed the setup of visual, ultrasonic and eddy current examination equipment to be used for the inspection of the reactor vessel upper head and associated penetrations, and monitored the collection of data for the examination activities, which consisted of a bare metal visual examination of the reactor vessel head surface and penetrations, and subsequent ultrasonic and eddy current examination of selected CRDM nozzles.

PWR Inservice Inspection Activities Sample - Boric Acid Corrosion Control Inspection Activities (IP Section 03.03) (1 Sample)

The inspectors verified the licensee is managing the boric acid corrosion control program through a review of the following evaluations:

(1)

• CR-ANO-2-2022-00179; CR-ANO-2-2022-00383; CR-ANO-2-2022-00529; CR-ANO-2-2022-01378; CR-ANO-2-2023-00297

PWR Inservice Inspection Activities Sample - Steam Generator Tube Inspection Activities (Section 03.04) (1 Sample)

The inspectors verified that the licensee is monitoring the steam generator tube integrity appropriately through a review of the following examinations:

(1)

• no steam generator tube inspections were scheduled or performed during this refueling outage

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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 Unit 2 transition to shutdown cooling and mode change to cold shutdown on April 15, 2023.

Licensed Operator Requalification Training/Examinations (IP Section 03.02) (2 Samples)

(1) The inspectors observed and evaluated the Dynamic examination (steam generator fault, plant trip, overcooling event, main steam isolation) for Unit 2, crew E, on June 21, 2023.

(2) The inspectors observed and evaluated the security event requalification training for Unit 1, crew D, on June 27, 2023.

71111.12 - Maintenance Effectiveness

Maintenance Effectiveness (IP Section 03.01) (1 Sample)

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

(1) Unit 1 service water valve CV-3811 on April 7, 2023, after failure on February 11, 2023

Aging Management (IP Section 03.03) (1 Sample)

The inspectors evaluated the effectiveness of the aging management program for the following SSCs that did not meet their inspection or test acceptance criteria:

(1) Unit 2 thickness measurement of an excavated portion of buried service water piping from the emergency cooling pond completed on May 11, 2023

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (3 Samples)

The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:

(1) Unit 2 elevated risk due to failures of circulating water pumps P-3B and P-3D on May 31, 2023

(2) Unit 1 and Unit 2 elevated risk due to planned maintenance on startup transformer 2 on June 14, 2023

(3) Unit 1 and Unit 2 elevated risk due to planned maintenance on the alternate ac generator with Pleasant Hill 161 kV offsite transmission line unavailable on June 26, 2023

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71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (6 Samples)

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

(1) Unit 1 operability of service water pump P-4A after motor replacement and pump performance outside of expected band as documented in work orders 455328 and 52983646 on April 19, 2023 (2)functionality of fire barrier penetration FB-175-4-0098 after as found degraded condition on April 24, 2023 (3)functionality of fire barrier penetration FB-2048-05-0124 after as found degraded condition on April 26, 2023

(4) Unit 2 plant protection system response time test channel B after failed surveillance on May 21, 2023

(5) Unit 2 containment high range radiation monitor 2RE-8925-2 as-installed cable bending radius on May 24, 2023

(6) Unit 2 safety injection tank B operability determination due to inventory leakage on June 20, 2023

71111.18 - Plant Modifications

Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (4 Samples)

The inspectors evaluated the following temporary or permanent modifications:

(1)temporary modification to add alternate power source to Unit 2 spent fuel pool cooling pumps per work order 568997 on May 9, 2023 (2)temporary modification to provide a plate-type heat exchanger, spent fuel pool cooling system per work order 539568 on May 11, 2023 (3)temporary modification to add alternate startup channel to Unit 2 for fuel movements in reactor vessel per work order 574775 on May 16, 2023 (4)permanent modification to replace Unit 1 service water-to-intermediate cooling water isolation valve CV-3811, per engineering change 85805, on June 29, 2023

71111.20 - Refueling and Other Outage Activities

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

(1) The inspectors evaluated Unit 2 refueling outage 29 activities from April 14 to May 23, 2023.

71111.24 - Testing and Maintenance of Equipment Important to Risk

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

Post-Maintenance Testing (PMT) (IP Section 03.01) (5 Samples)

(1) Unit 1 service water valve CV-3811 following repair on April 4, 2023

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(2) Unit 2 containment high range rad monitor 2RITS-8925-1 after identification of errors in the calibration and site testing procedure on April 7, 2023

(3) Unit 2 high-pressure safety injection valve 2SI-27A following component replacement on May 24, 2023

(4) Unit 2 high-pressure safety injection valve 2SI-28A following component replacement on May 24, 2023

(5) Unit 2 plant protection system channel C variable trip module for steam generator level following replacement on June 2, 2023

Surveillance Testing (IP Section 03.01) (6 Samples)

(1)diesel fire water pump P-6B surveillance on May 4, 2023

(2) Unit 2 main steam safety valves surveillance on May 11, 2023

(3) FLEX Hale pump P-255 (Unit 1 steam generator/reactor coolant system makeup)surveillance on May 16, 2023

(4) Unit 2 main turbine speed detection module overspeed surveillance test on May 21, 2023

(5) Unit 2 main turbine diverse overspeed protection module surveillance test on May 21, 2023

(6) Unit 2 emergency-powered pressurizer heater capacity surveillance on May 25, 2023

Inservice Testing (IST) (IP Section 03.01) (1 Sample)

(1) Unit 2 testing of lower pressure safety injection valve 2CV-5037-1, per work order 52956635, on June 28, 2023

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

(1) Unit 2 testing of containment isolation valve 2CV-5650-2 per work order 52996885, on June 9, 2023

Diverse and Flexible Coping Strategies (FLEX) Testing (IP Section 03.02) (1 Sample)

(1) FLEX 800 kw diesel generator (K12) periodic testing on April 27,

71124.01 - Radiological Hazard Assessment and Exposure Controls

Radiological Hazard Assessment (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated how the licensee identifies the magnitude and extent of radiation levels and the concentrations and quantities of radioactive materials and how the licensee assesses radiological hazards.

Instructions to Workers (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated how the licensee instructs workers on plant-related radiological hazards and the radiation protection requirements intended to protect workers from those hazards.

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Contamination and Radioactive Material Control (IP Section 03.03) (2 Samples)

The inspectors observed/evaluated the following licensee processes for monitoring and controlling contamination and radioactive material:

(1)observed survey and control of potentially contaminated material leaving the radiologically controlled area, specifically the transport of a reactor coolant pump motor out of the Unit 2 equipment hatch (2)observed workers exiting the Unit 2 containment building during a refueling outage

Radiological Hazards Control and Work Coverage (IP Section 03.04) (3 Samples)

The inspectors evaluated the licensee's control of radiological hazards for the following radiological work:

(1)entries under the Unit 2 reactor vessel head for manual non-destructive examinations using radiation work permit (RWP) 2023-02471, revision 00 (2)removal of the 2P-32A reactor coolant pump seals using RWP 2023-02465, revision 00 (3)initial entry survey of the refueling water storage tank interior under RWP 2023-02474, revision 00

High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (5 Samples)

The inspectors evaluated licensee controls of the following high radiation areas (HRA) and very high radiation areas:

(1)

(HRA) the diversified skid and the 2T-20A/B tank rooms on the Unit 2 auxiliary building 317-foot elevation (2)

(HRA) 2T-5 and 2T-15 tank rooms and 2F-3A/B and 2F-4A/B rooms on the Unit 2 auxiliary building 335-foot elevation (3)

(HRA) radwaste crane ladder in the low-level radioactive waste building (4)

(HRA) reactor coolant piping hot leg penetration on the Unit 2 reactor building 369-foot elevation (5)

(HRA) reactor vessel head stand on the Unit 2 reactor building 404-foot elevation

Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 03.06) (1 Sample)

(1) The inspectors evaluated radiation worker and radiation protection technician performance as it pertains to radiation protection requirements.

71124.04 - Occupational Dose Assessment

Source Term Characterization (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated licensee performance as it pertains to radioactive source term characterization.

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External Dosimetry (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated how the licensee processes, stores, and uses external dosimetry.

Internal Dosimetry (IP Section 03.03) (3 Samples)

The inspectors evaluated the following internal dose assessments:

(1)personnel contamination event (PCE) 2022-009, and its associated whole body count assessment, October 21, 2022

(2) PCE 2022-011, and its associated whole body count assessment, December 24, 2022

(3) PCE whole body counts for filter changeouts 2F-3A/B, April 3, 2023

Special Dosimetric Situations (IP Section 03.04) (3 Samples)

The inspectors evaluated the following special dosimetric situations:

(1)effective dose equivalent (EDEX) multipack dosimetry assignment for radiation work permit (RWP) 2021-2430, RWP 2021-2471, RWP 2022-1502, and RWP 2023-2471

(2) NRC Form 5 for five workers using EDEX multipack dosimetry

(3) NRC Form 5 for three declared pregnant workers

71124.05 - Radiation Monitoring Instrumentation

Walkdowns and Observations (IP Section 03.01) (2 Samples)

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

(1) SPING-4 on the Unit 1 auxiliary building 354-foot elevation (2)area radiation monitor RE-8912 on the Unit 1 auxiliary building 354-foot elevation

71124.06 - Radioactive Gaseous and Liquid Effluent Treatment

Walkdowns and Observations (IP Section 03.01) (5 Samples)

The inspectors evaluated the following radioactive effluent systems during walkdowns:

(1) Unit 1 liquid radioactive waste system

(2) Unit 2 liquid radioactive waste system

(3) Unit 2 fuel handling area ventilation system

(4) Unit 2 reactor building purge system

(5) Unit 1 penetration room ventilation system

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Sampling and Analysis (IP Section 03.02) (4 Samples)

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

(1) June 13, 2023, gaseous effluent, tritium, charcoal and particulate sample for Unit 2 auxiliary building (2RX-9825 - SPING 6)

(2) June 13, 2023, gaseous effluent, tritium, charcoal and particulate sample for Unit 2 spent fuel pool area (2RX-9830 - SPING 7)

(3) June 13, 2023, charcoal and particulate sample for Unit 2 emergency penetration room (2RX-9835 - SPING 8)

(4) June 14, 2023, liquid effluent sample for Unit 1 neutralizing tank (T50)

Dose Calculations (IP Section 03.03) (2 Samples)

The inspectors evaluated the following dose calculations:

(1)dose calculations associated with liquid radioactive release permits: 1LR2020-0050, 1LR2021-0018, 1LR2022-0028, 1LR2023-0016, 2LR2020-0025, 2LR2021-0028, 2lR2022-0009, 2LR2023-0002 (2)dose calculations associated with gaseous radioactive release permits:

1GR2020-0092, 1GR2021-0029, 1GR2022-0049, 1GR2023-0002, 2GR2020-0030, 2GR2021-0097, 2GR2022-0028,2GR2023-0036

Abnormal Discharges (IP Section 03.04) (2 Samples)

The inspectors evaluated the following abnormal discharges:

(1) On March 28, 2020, air was unexpectedly released through an unmonitored pathway for 48 minutes. Air samples were obtained and a release permit (2GR2020-0030) was generated to document the abnormal release of tritium through the open roof hatch.

(2) On February 9, 2023, there was an unplanned release of air for 270 minutes through door 94 as workers changed out carbon filters for the Unit 1 fuel handling area exhaust ventilation system. Radiation protection personnel notified Chemistry and took air samples as directed. A release permit (1GR2023-0002) was generated to document the unplanned release.

71124.07 - Radiological Environmental Monitoring Program

Environmental Monitoring Equipment and Sampling (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated environmental monitoring equipment and observed collection of environmental samples.

Radiological Environmental Monitoring Program (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated the implementation of the licensees radiological environmental monitoring program.

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GPI Implementation (IP Section 03.03) (1 Sample)

(1) The inspectors evaluated the licensees implementation of the Groundwater Protection Initiative program to identify incomplete or discontinued program elements.

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification

The inspectors verified licensee performance indicators submittals listed below:

MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04)===

(1) Unit 1 (April 1, 2022, through March 31, 2023)

(2) Unit 2 (April 1, 2022, through March 31, 2023)

BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10) (2 Samples)

(1) Unit 1 (April 1, 2022, through March 31, 2023)

(2) Unit 2 (April 1, 2022, through March 31, 2023)

BI02: RCS Leak Rate Sample (IP Section 02.11) (2 Samples)

(1) Unit 1 (April 1, 2022, through March 31, 2023)

(2) Unit 2 (April 1, 2022, through March 31, 2023)

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

(1) Unit 1 and Unit 2 (October 1, 2022, through March 31, 2023)

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) Unit 1 and Unit 2 (October 1, 2022, through March 31, 2023)

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) The inspectors reviewed the licensees corrective action program for motor-operated valves (both Limitorque and Rotork) on both units. The review included problems identified with Unit 2 high pressure safety injection valve 2CV-5036-2, Unit 1 service water control valve CV-3811, and Unit 2 containment sump isolation valve 2CV-5650-2.

(2) The inspectors reviewed the licensees corrective action program for discrepancies in the fire hazards analysis related to actual plant configuration of fire dampers.

(3) The inspectors reviewed the licensees corrective action program for long term corrective actions associated with the failure of emergency feedwater steam supply

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check valve 2MS-39B.

(4) The inspectors reviewed the licensees corrective action program for the sites control of ladders and their materials of construction.

71153 - Follow Up of Events and Notices of Enforcement Discretion Personnel Performance (IP section 03.03)

(1) The inspectors evaluated the licensees performance in response to an electrohydraulic fluid leak at the Unit 2, main feedwater pump B, manual trip of the pump, turbine runback and rapid power reduction to approximately 79 percent power on June 14, 2023.

(2) The inspectors evaluated the licensees performance in response to a turbine-to-pump coupling failure on the Unit 2, main feedwater pump A, turbine runback and rapid power reduction to approximately 75 percent power on June 15,

INSPECTION RESULTS

Failure to Properly Evaluate a Replacement Motor-Operated Valve Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000313/2023002-01 Open/Closed

[H.12] - Avoid Complacency 71111.18 The inspectors identified a Green finding and associated non-cited violation of 10 CFR Part 50, Appendix B, Criterion III, Design Control, for the licensees failure to evaluate all aspects of several service water boundary valve replacement motor-operated valves (MOVs). Specifically, modification engineering change 85805 installed a new, Unit 1, loop 2 service water-to-intermediate cooling water isolation valve CV-3811, which had a thicker actuator mounting plate than the original valve but reused the original fasteners in the final installation. Consequently, the installed actuator mounting fasteners did not meet thread engagement requirements.

Description:

The ANO Unit 1 service water system provides shared cooling water flow to safety-related and non-safety-related heat loads. The system has boundary isolation valves that automatically close on an engineered safeguards actuation signal to isolate nonessential loads during an accident. Loop 2 service water-to-intermediate cooling water isolation valve CV-3811, is a 14 inch butterfly valve that has an active safety function to automatically close on an engineered safeguards actuation signal and provide the isolation boundary between the safety-related loop 2 service water loads required during an accident and the non-safety-related intermediate cooling water system. The licensee prepared modification engineering change (EC) 85805 to replace several service water boundary valves, including valve CV-3811, with an upgraded valve design with greater maximum allowable stem torque and lower minimum-required torque. The EC allowed the re-use of the original Limitorque SMB-000 actuator and HBC gearbox. The licensee replaced the valve in the plant during refueling outage 1R30 in 2022.

During the inspectors review of an unrelated maintenance issue with this valve, the inspectors noticed in the field that the actuator mounting bolts which fastened the CV-3811 valve body to its actuator, had significantly less thread engagement than valve CV-3820, redundant loop 1 service water-to-intermediate cooling water boundary valve. Valve CV-3820 was scheduled to be replaced in a future refueling outage. The actuator mounting fasteners

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for valve CV-3820 were flush with the top of its actuator gearbox flange whereas the fasteners for valve CV-3811 were not. The inspectors reviewed Procedure EN-MA-145, Maintenance Standard for Torque Applications, revision 11, which defined full thread engagement as follows: A fastener with the threads flush with the top of the nut. Note: 1-2 threads above the top of the nut is preferred. For studs installed in blind holes, a minimum of one stud diameter engagement in steel and two times stud diameter engagement for aluminum is required. Based on observations in the field, the inspectors noted the actuator mounting fasteners were not flush with the top of the steel actuator gearbox flange and did not appear to have at least one stud diameter of engagement with the gearbox flange. Based on the inspectors concern, the licensee entered this issue into their corrective action program as condition report CR-ANO-1-2023-00554. The licensee confirmed that the original 3/4 inch x 1 1/2 inch hex head cap screws were used in the installation of the new CV-3811 valve, and that the actuator mounting plate was approximately double the thickness of the original installation, resulting in approximately 1/2 inch fastener engagement to the actuator gearbox.

The licensee promptly initiated a work order and replaced the fasteners with ones of sufficient length to meet the procedure EN-MA-145 thread engagement requirements.

During the inspectors review of modification EC 85805, the inspectors noticed that the difference in actuator mounting plate thickness was not evaluated. Therefore, the licensee failed to identify that longer fasteners were required to meet the thread engagement requirements.

The licensee completed an engineering evaluation, including a thread engagement analysis of the as-found condition. The licensee was able to show that the required length of thread engagement to resist seismic design basis earthquake loads was 0.108 inch. Therefore, the licensees evaluation reasonably determined that the as-found thread engagement would not adversely affect operability of valve CV-3811.

Corrective Actions: The licensee promptly replaced valve CV-3811 fasteners with ones of sufficient length to meet the procedure EN-MA-145 thread engagement requirements and completed a thread engagement analysis to determine that valve CV-3811 was operable in the as-found condition. The licensee also completed an extent of condition review of other safety-related butterfly valves. The licensee identified five additional valves whose fasteners were not flush with the top of their actuator gearbox mounting flanges. However, in each case, the fasteners had greater than one stud diameter of engagement.

Corrective Action References: condition reports CR-ANO-1-2023-00554 and CR-ANO-1-2023-00960

Performance Assessment:

Performance Deficiency: The licensees failure to evaluate that a replacement valve, with a thicker actuator mounting plate, required longer actuator mounting fasteners to achieve full thread engagement, was a performance deficiency.

Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Design Control attribute of the Mitigating Systems cornerstone and adversely affected the cornerstone objective to ensure the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences. Specifically, the as-found thread engagement for loop 2 service water-to-intermediate cooling water isolation valve CV-3811, actuator mounting fasteners did not meet the licensees definition of full thread engagement contained in procedure EN-MA-145, which

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resulted in reasonable doubt about the modified valves seismic qualifications. The licensee corrected the condition and completed an engineering evaluation that determined the as-found condition did not adversely affect seismic qualification of the valve.

Significance: The inspectors assessed the significance of the finding using IMC 0609, Appendix A, The Significance Determination Process (SDP) for Findings At-Power. In accordance with IMC 0609, Appendix A, Exhibit 2, Mitigating Systems Screening Questions, issued November 30, 2020, the finding is of Green significance. The finding is a deficiency affecting the design or qualification of a mitigating structure, system, or component (valve CV-3811), but the valve maintained its operability and probabilistic risk assessment (PRA) functionality. Additionally, the finding did not involve external events mitigating systems, the reactor protection system, fire brigade, or flexible coping strategies.

Cross-Cutting Aspect: H.12 - Avoid Complacency: Individuals recognize and plan for the possibility of mistakes, latent issues, and inherent risk, even while expecting successful outcomes. Individuals implement appropriate error reduction tools. Specifically, during development of modification EC 85805, the licensee had determined the original actuator and gearbox were acceptable for use and assumed it was also acceptable to use the same fasteners.

Enforcement:

Violation: Title 10 CFR Part 50, Appendix B, Criterion III, Design Control, requires in part, measures shall be established for the selection and review for suitability of application of materials, parts, equipment, and processes that are essential to the safety-related functions of the structures, systems, and components.

Contrary to the above, from April 13, 2021 (the approval date of modification EC 85805)through April 3, 2023 (when the condition was corrected), measures were not established for the selection and review for suitability of application of materials, parts, equipment, and processes that are essential to the safety-related functions of the structures, systems, or components. Specifically, the licensee failed to establish measures for the selection and review for suitability of application of service water valve fasteners that are essential for Unit 1, loop 2 service water-to-intermediate cooling water isolation valve CV-3811, to close and ensure adequate service water system flow for completing the systems safety-related functions.

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

Failure to Perform Air Sampling Analysis Resulting in Two Uptakes Cornerstone Significance Cross-Cutting Aspect Report Section Occupational Radiation Safety Green NCV 05000368/2023002-02 Open/Closed

[H.1] -

Resources 71124.04 The inspectors reviewed a self-revealed Green, non-cited violation of Technical Specification 6.4.1 for the licensee's failure to follow procedures to assess an air sample prior to a job activity. Specifically, the licensee failed to analyze an air sample prior to filter changeouts resulting in two workers receiving unintended exposure to airborne radioactivity (i.e., an uptake).

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Description:

On April 3, 2023, radiation protection (RP) staff provided support to the maintenance staff during changeout of filters 2F-3A and 2F-3B (CVCS purification filters). The filters had been isolated since February 9, 2023, but were drained during the shift in preparation for the changeout. The greatest potential for creating airborne contamination is when the filter is within the drying process. During the changeout of filter 2F-3A, RP completed an air sample, but failed to analyze or count the sample, in a timely fashion, prior to the maintenance crew proceeding with the replacement of the second filter. The maintenance crew swapped out the worker and moved directly into the changeout of filter 2F-3B, as the worker from the prior filter changeout of filter 2F-3A stood by for support.

At this time, a second air sample was completed for the 2F-3B filter changeout. After the filter changeouts were completed and the work area was secured, RP proceeded to analyze and count both air samples.

During this period, two of the maintenance workers proceeded to the radiologically controlled area (RCA) exit and alarmed the personnel radiation monitors (i.e., Gamma Exit Monitor, GEM-5). The worker who changed out the 2F-3A filter was decontaminated and cleared the GEM-5 at the RCA exit. The worker who changed out the 2F-3B filter could not clear the GEM-5 and was escorted by RP to dosimetry for whole-body counting (WBC). A review of the WBC data identified the individual did have an uptake of radioactive material during the filter changeout.

The worker who changed out the 2F-3A filter initially cleared the GEM-5, but did not receive a WBC at the time of his co-worker. However, this individual alarmed a GEM-5 at the primary access point 3 days later, on April 6, 2023. At this time, the worker who changed out the 2F-3A filter received a WBC, which confirmed an uptake of radioactive material. The licensee determined the uptake was due to the filter changeout work.

The licensees review of this issue determined that the filters were dry, which increased the potential for airborne radioactivity in the work area and created unknown radiological conditions. This may have been prevented if RP would have completed an assessment of the air sample for filter changeout 2F-3A in a timely fashion, as instructed by licensee procedure.

Licensee Procedure EN-RP-131, "Air Sampling," revision 18, section 5.1.6 stated, in part,

"EVALUATE grab samples as quickly as practicable to determine the need for adjusting engineering controls. The failure to evaluate the air samples as quickly as possible resulted in not adjusting engineering controls and two confirmed uptakes of radioactive materials.

The assessment of the air samples (ANO-AS-040323-0095), dated April 3, 2023, indicated a derived air concentration (DAC) fraction of 1.54. These results indicated an airborne radioactivity area and the need for additional radiological and engineering controls to prevent unintended exposures. The additional radiological and engineering controls would have been required prior to work starting on the second filter changeout. However, the maintenance workers were allowed to continue working without additional controls being implemented, and they were not aware of the actual radiological conditions in their work area.

When the inspectors inquired about why the worker that changed out filter 2F-3A was able to pass the GEM-5 monitors at the RCA exit, the licensee stated that video footage showed both individuals monitored appropriately at the RCA exit. The licensee added that difference in body mass may have impacted the shielding of internal radionuclides, resulting in one worker being able to pass the GEM-5 monitor based on positioning. The inspectors did confirm that the satisfactory calibrations for these GEM-5 monitors were current and the alarming levels were appropriately set.

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In the licensee's Condition Analysis Template, dated May 15, 2023, the licensee identified gaps in their procedural guidance relative to the verification of the filter housing configuration that attributed to this issue. In an operations procedure, there were steps that instruct workers to validate the housing configuration of the filter and evaluate and implement engineering controls prior to opening the housing when utilizing the filter transfer assembly tool. This procedure was not tied to the radiation work permit (RWP) that was used. As part of their corrective actions, the licensee plans to update the RWP with these steps and enhance procedures. Additionally, the licensee concluded the small work area in which the filters were stationed challenged RP's ability to support the work, and there should have been additional instructions to use remote monitoring to help address the risk associated with system breaches for filter changeouts.

Corrective Actions: As immediate corrective actions, the licensee performed whole body counts on the two workers and entered this issue into their corrective action program. As a follow-up, the licensee performed a dose assessment, coached all individuals involved, and made changes to their procedures in order to prevent recurrence of these failures during filter changeouts.

Corrective Action References: condition report CR-ANO-2-2023-00521

Performance Assessment:

Performance Deficiency: The licensees failure to follow procedures to assess airborne radiological conditions was a performance deficiency. This failure resulted in not implementing appropriate engineering controls and two confirmed uptakes by maintenance workers.

Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Program & Process attribute of the Occupational Radiation Safety cornerstone and adversely affected the cornerstone objective to ensure the adequate protection of the worker health and safety from exposure to radiation from radioactive material during routine civilian nuclear reactor operation. Specifically, this failure resulted in not implementing appropriate engineering controls and two confirmed uptakes by maintenance workers. Additionally, the performance deficiency was similar to example

(6h) in Inspection Manual Chapter (IMC) 0612, Appendix E, "Examples of Minor Issues," in which a more than minor performance deficiency occurred when the licensee failed to establish appropriate radiological controls such that an unplanned internal exposure occurred resulting in greater than 10 mrem committed effective dose equivalent (CEDE). In this case, the two maintenance workers received 14.37 millirem CEDE and 0.4 millirem CEDE, respectively.

Significance: The inspectors assessed the significance of the finding using IMC 0609, Appendix C, Occupational Radiation Safety SDP. Using IMC 0609, appendix C, the inspectors determined the finding to be of very low safety significance (Green) because:

(1) it was not a finding in ALARA Planning or Work Controls;

(2) it was not an overexposure;

(3) there was no substantial potential for overexposure;

(3) it was not a shallow dose exposure or discrete radiation particle exposure; and

(4) it was not a whole-body exposure within a very high radiation area.

Cross-Cutting Aspect: H.1 - Resources: Leaders ensure that personnel, equipment, procedures, and other resources are available and adequate to support nuclear safety.

Specifically, the licensee failed to ensure that the workers had complete and adequate

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Failure to Establish Adequate Corrective Actions Resulting in Excessive Instances of Damaged and Broken Internals of the Emergency Feedwater Pump Turbine Steam Admission Check Valves Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NOV 05000368/2023002-03 Open

[H.6] - Design Margins 71152A The inspectors identified a Unit 2 Green finding and associated Notice of Violation of 10 CFR Part 50, Appendix B, Criterion XVI, Corrective Action, for the failure to promptly identify and correct a condition adverse to quality. Specifically, the licensee failed to correct in a timely manner the deficient system design of the check valves admitting steam to the emergency feedwater turbine.

Description:

In 2018, the NRC issued Green, non-cited violations05000313/2018011-02 and 05000368/2018011-02, of 10 CFR Part 50, Appendix B, Criterion XVI, Corrective Action, for both ANO units, for failure to establish an adequate corrective action program and the resulting inability to correct a deficient system design which resulted in damaged and broken internals of the check valves admitting steam to the emergency feedwater turbine.

The Unit 1, Babcock and Wilcox reactor design, safety-related function of check valve MS-271 is to open and admit steam from its steam generator to the emergency feedwater pump turbine and to close to prevent excessive loss of steam flow from the opposite steam generator such that sufficient flow of steam will pass through the sister check valve MS-272 (and vice versa). The same arrangement applies to the Unit 2, Combustion Engineering reactor design, design with check valves 2MS-39A and 2MS-39B.

Enforcement:

Violation: Technical Specifications 6.4.1.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. Section 7.e of appendix A of Regulatory Guide 1.33 requires procedures for radiation protection. Section 5.1.6 of Procedure EN-RP-131, "Air Sampling," revision 18, section 5.1.6, requires grab samples to be evaluated as quickly as practicable to determine the need for adjusting engineering controls.

Contrary to these requirements, on April 3, 2023, the licensee failed to follow procedure EN-RP-131 when they failed to evaluate an air sample as quickly as practicable to determine the need for adjusting engineering controls. Specifically, the licensee completed an air sample for the changeout of CVCS purification filter 2F-3A but did not evaluate the sample quickly or prior to the next filter changeout job for filter 2F-3B in the same area, which resulted in not adjusting engineering controls and confirmed uptakes of radioactive materials for two maintenance workers.

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

instructions available to them, as associated with their RWP, to conduct the filter changeouts of 2F-3A and 2F-3B. The licensee also failed to ensure the workers were properly trained on the risks associated with system breaches for filter changeouts.

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As part of the licensees response to the above listed NCVs, the licensee entered the deficient condition into the corrective action program and expressed a commitment to correct the condition and avoid future failures of these check valves, condition report CR-ANO-C-2018-04349. Subsequently, a new check valve design was developed under engineering change (EC) documents EC-81851 and EC-82061 and installed in each unit during refueling outages 1R28 and 2R27, work orders (WO) WO 517493, WO 517494, WO 520975, and WO 520976. Corrective actions were also implemented to replace each of the check valves every refueling outage for each unit. Additionally, the licensee implemented a modification in Unit 1 to maintain one of the steam-supply motor-operated valves (MOV)

(CV-2617) in a normally closed position to eliminate abnormal wear due to differential pressure oscillations. The Unit 1 steam admission MOVs each receive an automatic open signal on an emergency feedwater actuation signal. A similar modification was not completed for Unit 2 because the Unit 2 steam admission valves do not receive an automatic open signal on an emergency feedwater actuation signal. There have been no additional failures of Unit 1 check valves MS-271 or MS-272 since implementation of the modification in Unit 1 to keep valve CV-2617 normally closed.

On October 13, 2021, during Unit 2 refueling outage 2R28, the licensee performed an inspection of 2MS-39B and found that the check valve had failed, and its internals were missing. The licensee wrote condition report CR-ANO-2-2021-02496 to document the as found condition and developed a parts retrieval plan. The missing parts were retrieved and a new check valve of the same design as well as an acoustic monitoring device were installed.

On May 4, 2023, during Unit 2 refueling outage 2R29, the licensee performed another inspection of 2MS-39B. Again, the licensee found that the check valve had failed, and its internals were missing. The licensee wrote condition report CR-ANO-2-2023-01282 to document the as found condition and develop a parts retrieval plan. The missing parts were retrieved and a new check valve of the same design as well as an acoustic monitoring device were once again installed.

During these failures the broken internals were found to be heavily worn from excessive cycling. Check valve failures prior to the issuance of NCV 05000313/2018011-02 and NCV 05000368/2018011-02 exhibited damage also caused by excessive cycling. Operability evaluations performed for each failure always determined that the valves were operable despite their broken internals. Supporting justifications included that the check valves sufficiently passed forward steam flow as demonstrated by successfully completed surveillance tests of the turbine-driven emergency feedwater pump, loose parts evaluations that concluded any loose parts in the system would not adversely affect system operability, and engineering evaluations that concluded the as-found valve damage would not have prevented the valve from performing its closure function.

Since 2018 the licensee has not addressed the cyclic damage to the Unit 2 check valves and has not corrected the situation in a timely manner despite several refueling outages. No other compensatory measures have been established beyond the original valve replacement each cycle and the acoustic monitoring.

Corrective Actions: The licensee installed acoustic monitoring instrumentation to periodically monitor valve conditions and plans to replace the check valves again next outage.

Additionally, the licensee informed the inspectors that they would discuss operating experience with these valves with industry peers.

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Corrective Action References: The licensee entered these issues into the corrective action program with condition reports CR-ANO-2-2021-02496, CR-ANO-2-2023-01282, and CR-ANO-2-2023-02140.

Performance Assessment:

Performance Deficiency: The licensees failure to correct a condition adverse to quality related to the multiple failures of safety-related emergency feedwater pump turbine steam admission check valves is a performance deficiency.

Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Design Control attribute of the Mitigating Systems cornerstone and adversely affected the cornerstone objective to ensure the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences. Specifically, corrective actions taken since the NRC issued a non-cited violation in 2018 have not resolved the problem for Unit 2. The licensee continued to have failures of check valve 2MS-39B during the following two operating cycles, resulting in parts of the broken valve being found in other locations of the system, such that the overall performance of the system could not be considered as reliable as the original plant design.

Significance: The inspectors assessed the significance of the finding using IMC 0609, Appendix A, The Significance Determination Process (SDP) for Findings At-Power. In accordance with Section A, Exhibit 2, Mitigating Systems Screening Questions, issued November 30, 2020, the finding screened as Green because it was a deficiency affecting the design or qualification of the emergency feedwater system but did not cause a loss of system operability or PRA functionality.

Cross-Cutting Aspect: H.6 - Design Margins: The organization operates and maintains equipment within design margins. Margins are carefully guarded and changed only through a systematic and rigorous process. Special attention is placed on maintaining fission product barriers, defense-in-depth, and safety-related equipment. In the case of these check valves, the organization did not maintain the equipment within their design margins and the design changes did not reflect a rigorous change process.

Enforcement:

Violation: Title 10 CFR Part 50, Appendix B, Criterion XVI, "Corrective Action," requires, in part, "Measures shall be established to assure that conditions adverse to quality, such as failures, malfunctions, deficiencies, deviations, defective material and equipment, and nonconformances are promptly identified and corrected."

Contrary to the above, since 2018, when the NRC issued non-cited violations05000313/2018011-02 and 05000368/2018011-02 (ML18295A382), the licensee has continued to fail to assure that conditions adverse to quality such as failures, malfunctions, deficiencies, deviations, defective material and equipment, and nonconformances were promptly identified and corrected. Specifically, attempts to correct conditions adverse to quality for the Unit 2 safety-related emergency feedwater steam admission check valve, 2MS-39B, were unsuccessful because the internals of Unit 2 safety-related emergency feedwater steam admission check valve 2MS-39B were found damaged or broken during subsequent inspections in 2021 and 2023.

Enforcement Action: This violation is being cited because the licensee failed to restore compliance within a reasonable period of time after the violation was identified consistent with

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section 2.3.2 of the Enforcement Policy.

EXIT MEETINGS AND DEBRIEFS

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

• On April 28, 2023, the inspectors presented the occupational radiation safety inspection results to Doug Pehrson, General Manager, Plant Operations, and other members of the licensee staff.

• On June 15, 2023, the inspectors presented the public radiation safety inspection results to Joseph Sullivan, Site Vice President, and other members of the licensee staff.

• On July 13, 2023, the inspectors presented the integrated inspection results to Doug Pehrson, Site Vice President, and other members of the licensee staff.

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DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.04

Corrective Action

Documents

CR-ANO-

1-2023-00894, 1-2023-00895, 1-2023-00896,1-2023-00897,

C-2021-01676

71111.04

Drawings

M-204, Sheet 3

Emergency Feedwater

71111.04

Drawings

M-204, Sheet 4

Emergency Feedwater

71111.04

Drawings

M-204, Sheet 5

Emergency Feedwater Storage

71111.04

Drawings

M-206, Sheet 1

Steam Generator Secondary System

133

71111.04

Miscellaneous

STM 1-27

Emergency Feedwater System

71111.04

Miscellaneous

STM 1-66

Emergency Feedwater Initiation and Control

71111.04

Procedures

OP-1106.006

Emergency Feedwater Pump Operation

20

71111.04

Procedures

OP-1304.098

EFIC Channel A Calibration

71111.04

Procedures

OP-2104.037

Alternate AC Diesel Generator Operations

71111.04

Procedures

OP-3305.001

OPS System Alignment Tests

71111.05

Corrective Action

Documents

CR-ANO-

2-2022-01361, 2-2022-01376, 2-2022-01454, 2-2022-01486

71111.05

Engineering

Evaluations

ER-974313

Black and Green Cables Intermingled between Trays

PC-1

71111.05

Miscellaneous

PFP-U1

ANO Prefire Plan (Unit 1)

71111.05

Miscellaneous

PFP-U2

ANO Prefire Plan (Unit 2)

71111.07A

Calculations

CALC-95-R-0014-

Test Protocol Unit 2 Shutdown Cooling Heat Exchanger

Thermal Performance Test

71111.07A

Corrective Action

Documents

CR-ANO-

2-2021-03347, 2-2021-03664, C-2022-01391

71111.07A

Procedures

OP-2311.001

Shutdown Cooling Heat Exchanger Thermal Performance Test

71111.07A

Work Orders

WO

548828, 572642, 52939676

71111.08P

Corrective Action

Documents

Resulting from

Inspection

CR-ANO-2-2023-

01119

NRC Inspector Observation regarding a potential issue with

2SV-8344-1 "CBHVAC H2 Purge Manifold".

04/18/2023

71111.08P

Corrective Action

Documents

Resulting from

Inspection

CR-ANO-C-2023-

01187

During the NRC ISI Inspection, the NRC Inspector provided an

observation regarding equipment labeling in the plant.

04/25/2023

2-23

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.08P

NDE Reports

2-BOP-MT-23-

017

Magnetic Particle Examination: MT on 2HBC-34 Weld

04/27/2023

71111.08P

NDE Reports

2-ISI-PT-23-001

Liquid Penetrant Examination: Integrally Welded Attachment

2CCA-24-H22

05/02/2023

71111.08P

NDE Reports

2-ISI-UT-23-001

UT Calibration/Examination: Elbow to Safe End

Circumferential Weld

04/25/2023

71111.08P

NDE Reports

2-ISI-UT-23-002

UT Calibration/Examination: Pipe to Elbow Circumferential

Weld

04/25/2023

71111.08P

NDE Reports

2-ISI-VT-23-022

Visual Examination of Pipe Hanger, Support or Restraint (VT-

3): One Way Restraint 2HBC-64-H9

04/26/2023

71111.08P

NDE Reports

2-ISI-VT-23-023

Visual Examination of Welds (VT-1): Integrally Welded

2HBC-64-H9

04/26/2023

71111.08P

Procedures

CEP-BAC-001

Boric Acid Corrosion Control (BACC) Program Plan

71111.08P

Procedures

CEP-NDE-0400

Ultrasonic Examination

71111.08P

Procedures

CEP-NDE-0423

Manual Ultrasonic Examination of Austenitic Piping Welds

(ASME XI)

71111.08P

Procedures

CEP-NDE-0497

Manual Ultrasonic Examination of Welds in Vessels (Non-App.

VIII)

71111.08P

Procedures

CEP-NDE-0641

Liquid Penetrant Examination (PT) for ASME Section XI

71111.08P

Procedures

CEP-NDE-0901

VT-1

71111.08P

Procedures

CEP-NDE-0902

VT-2

71111.08P

Procedures

CEP-NDE-0903

VT-3

71111.08P

Procedures

CEP-NDE-0955

Visual Examination (VE) of Bare-Metal Surfaces

308

71111.08P

Procedures

EN-DC-319

Boric Acid Corrosion Control Program (BACCP)

71111.08P

Procedures

SEP-BAC-ANO-

001

Boric Acid Corrosion Control Program

Inspection and Identification of Boric Acid Leaks for

ANO-1 and ANO-2

71111.08P

Work Orders

00572367-01

ISI VT-1 on 73-044W Integrally Welded ATT 2HBC-64-H9

(2R29)

04/26/2023

71111.08P

Work Orders

00572398-01

2R29: ISI UT On 22-001A Elbow to Pipe Circ Weld 2SI-15D

04/20/2023

71111.08P

Work Orders

00572916-04

2R29: ISI VT-3 on 23-069 Anchor 2CCA-24-H22

Task: ISI #23-0069W: Perform at PT of the Integral

05/04/2023

71111.08P

Work Orders

00572925-01

2R29: ISI VT-3 ISI # 73-004 One Way Restraint 2HBC-64-H9

04/26/2023

2-24

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.08P

Work Orders

00572940-01

40-008: ISI UT On Pipe to Elbow Circ Weld

04/26/2023

71111.11Q Corrective Action

Documents

CR-ANO-

2-2023-00611, 2-2023-00615

71111.11Q Miscellaneous

A1LPOPSB5B

Security Event (B5b)

2305

71111.11Q Procedures

OP-1203.048

Security Event

71111.11Q Procedures

OP-2102.004

Power Operation

71111.11Q Procedures

OP-2102.010

Plant Cooldown

71111.11Q Procedures

OP-2103.015

Reactivity Balance Calculation

71111.11Q Procedures

OP-2104.004

Shutdown Cooling System

71111.11Q Procedures

OP-2203.011

RCS Overcooling

71111.11Q Procedures

OP-2203.013

Natural Circulation Operations

71111.12

Calculations

CALC-19-E-0013-

Minimum Thickness Calculation for HBD-12-36, HBD-14-18,

HBD-20-18, 2HBC-33-20, 2HBC-34-20, 2HBC-83-30, and

2HBC-88-42 Buried Pipe

71111.12

Corrective Action

Documents

CR-ANO-

1-2009-00041, 1-2023-00276, 1-2023-00277, 1-2023-00301,

1-2023-00393, 1-2023-00401, 1-2023-00554, C-2019-01633,

C-2021-03142, C-2022-03087, C-2023-00972

71111.12

Procedures

EN-DC-340

Microbiologically Influenced Corrosion (MIC) Monitoring

Program

71111.12

Procedures

EN-MA-125

Troubleshooting and Maintenance Activities

71111.12

Procedures

EN-MA-141

Limitorque Valve Operator Model SMB/B/SBD-000 Through 5

MOV and HBC Periodic Inspection

71111.12

Procedures

OP-1403.038

Maintenance of Limotorque SB and SMB Actuators

71111.12

Work Orders

WO

28327, 572224, 591642, 593693, 52920155, 52965589

71111.13

Corrective Action

Documents

CR-ANO-

1-2023-00304, 1-2023-00783, 1-2023-00961

71111.13

Miscellaneous

Maintaining Condenser Vacuum while P-3B and P-3D are

OOS

71111.13

Miscellaneous

Manually Initiated Condition Report, 6/25/2023 @ 2040

71111.13

Procedures

COPD-024

Risk Assessment Guidelines

71111.13

Procedures

EN-FAP-OM-029

Adverse Condition Monitoring and Contingency Planning

71111.13

Procedures

OP-1107.001

Electrical System Operations

135

71111.13

Procedures

OP-2107.001

Electrical System Operations

138

2-25

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.13

Procedures

OP-2203.019

Loss of Condenser Vacuum

71111.15

Calculations

CALC-ANO2-NE-

2-00001

ANO-2 Cycle 30 Groundrules

71111.15

Corrective Action

Documents

CR-ANO-

1-2022-01995, 1-2023-00202, 1-2023-00222, 1-2023-00230,

1-2023-00280,1-2023-00668, 2-2023-01013, 2-2023-01705, 2-

23-01961

71111.15

Drawings

M-2232, Sheet 1

Safety Injection System

23

71111.15

Miscellaneous

Plant Data Management System: RG59B/U Coax Cable

05/05/2023

71111.15

Miscellaneous

ULD-1-SYS-10

ANO-1 Service Water Systems

71111.15

Procedures

EN-OP-104

Operability Determination Process

71111.15

Procedures

OP-1104.029

Service Water and Auxiliary Cooling System

27

71111.15

Procedures

OP-2304.113

Plant Protection System Response Time Test Channel B

71111.15

Procedures

OP-3305.001

OPS System Alignment Tests

71111.15

Procedures

OP-6030.109

Installation of Electrical Cable & Wire

71111.15

Work Orders

WO

455328, 571414, 594717, 595779, 52983646

71111.18

Calculations

CALC-91-E-0016-

Valves CV-3811 & CV-3821

71111.18

Corrective Action

Documents

CR-ANO-

1-2020-00762, 1-2023-00275, 1-2023-00277, 1-2023-00554,

1-2023-00960, 2-2023-00327, 2-2023-00562, 2-2023-00575,

2-2023-00626, C-2023-00947, C-2023-01019

71111.18

Drawings

13-SW-119,

Sheet 1

Large Pipe Isometric Service Water Supply

71111.18

Drawings

M-210, Sheet 1

Service Water

155

71111.18

Engineering

Changes

EC-48418

Evaluate Temporary Modification to Provide Alternate Source

of Power to Spent Fuel Cooling Pump 2P-40A or 2P-40B

71111.18

Engineering

Changes

EC-65672

Evaluation of a Temporary Spent Fuel Pool (SFP) Cooling

System

71111.18

Engineering

Changes

EC-85563

Evaluate and Provide Guidance for Providing Temp Power to

Both U2 SFP Cooling Pumps 2P-40A and 2P-40B

71111.18

Engineering

Changes

EC-85805

U1 Service Water Butterfly Valve Replacements (Loop 2)

71111.18

Engineering

Changes

EC-95255

CV-3811 Thread Engagement Discussion

71111.18

Engineering

ER-ANO-2003-

Engineering Evaluation for ANO-2 SU Channel T-Alt

2-26

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Evaluations

0583-001

71111.18

Procedures

EN-MA-141

Limitorque Valve Operator Model SMB/B/SBD-000 Through 5

MOV and HBC Periodic Inspection

71111.18

Procedures

EN-MA-145

Maintenance Standard for Torque Applications

71111.18

Procedures

OP-1403.038

Maintenance of Limotorque SB and SMB Actuators

71111.18

Procedures

OP-2104.006

Fuel Pool Systems

71111.18

Procedures

OP-2203.002

Spent Fuel Pool Emergencies

71111.18

Procedures

OP-2303.145

Startup Channels 1 & 2 Test

71111.18

Procedures

OP-2311.001

Shutdown Cooling Heat Exchanger Performance Test

71111.18

Procedures

OP-2403.270

Alternate Startup Channel Using Excore Detector

71111.18

Work Orders

WO

539568, 568997, 574775

71111.20

Calculations

CALC-90-R-2006-

Fatigue Monitoring Program for AP&L at ANO-2

71111.20

Calculations

CALC-ANO2-ME-

1500009

Review of the Fatigue Monitoring Program for License

Renewal Implementation

71111.20

Corrective Action

Documents

CR-ANO-

2-2023-00137, 2-2023-00150, 2-2023-00615, 2-2023-00616,

2-2023-01569, 2-2023-01571, 2-2023-01598, 2-2023-01619,

2-2023-01647, 2-2023-01705, 2-2023-01760

71111.20

Miscellaneous

EN-RE-327

PWR Startup Critical Predictions and Evaluation Process

71111.20

Procedures

COLR-U2

Core Operating Limits Report for Cycle 30

71111.20

Procedures

EN-OM-123

Fatigue Management Program

71111.20

Procedures

OP-1010.002

Unit Two Transient Cycle Logging and Reporting

71111.20

Procedures

OP-1015.048

Shutdown Operations Protection Plan

and 34

71111.20

Procedures

OP-2102.001

Plant Pre-Heatup and Pre-Critical Checklist

71111.20

Procedures

OP-2102.002

Plant Heatup

71111.20

Procedures

OP-2102.004

Power Operation

71111.20

Procedures

OP-2102.010

Plant Cooldown

71111.20

Procedures

OP-2102.015

Filling and Draining the Refueling Canal

71111.20

Procedures

OP-2102.016

Reactor Startup

71111.20

Procedures

OP-2103.006

Reactor Coolant Pump Operations

71111.20

Procedures

OP-2103.011

Draining the Reactor Coolant System

71111.20

Procedures

OP-2106.009

Turbine Generator Operations

71111.20

Procedures

OP-2203.025

RCP Emergencies

2-27

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.20

Procedures

OP-2302.022

Initial Criticality Following Refueling

71111.24

Corrective Action

Documents

CR-ANO-

1-2020-01707, 1-2023-00276, 1-2023-00277, 1-2023-00393,

1-2023-00401, 2-2020-00661, 2-2022-00495, 2-2023-00032,

2-2023-00378, 2-2023-00525, 2-2023-00577, 2-2023-01598,

2-2023-01647, 2-2023-01702, 2-2023-01703, C-2021-02976,

C-2021-02985, C-2023-00628, C-2023-01232, C-2023-01280,

C-2023-01337,

71111.24

Drawings

M-2230, Sheet 1

Reactor Coolant System

71111.24

Drawings

M-2232, Sheet 1

Safety Injection System

23

71111.24

Miscellaneous

ULD-0-TOP-15

ANO Unit 1 & 2 FLEX Topical

71111.24

Procedures

CFSG-005

Initial Assessment and FLEX Equipment Staging

71111.24

Procedures

EN-MA-141

Limitorque Valve Operator Model SMB/SB/SBD-000 through 5

MOV an HBC Periodic Inspection

71111.24

Procedures

OP-1104.032

Fire Protection Systems

71111.24

Procedures

OP-2104.005

Containment Spray

71111.24

Procedures

OP-2104.039

HPSI System Operation

71111.24

Procedures

OP-2106.009

Turbine Generator Operations

71111.24

Procedures

OP-2304.039

Unit 2 Plant Protection System Channel C Test

71111.24

Procedures

OP-2304.133

Unit 2 High Range Containment Radiation Monitor Calibration

71111.24

Procedures

OP-2306.006

Unit 2 Main Steam Safety Valve Test

71111.24

Procedures

OP-2307.009

Pressurizer Proportional Heater Checkout

71111.24

Procedures

OP-2402.044

Disassembly, Inspection, & Reassembly of 2SI-26 A&B, 27

A&B, 28 A&B

71111.24

Work Orders

WO

573697, 593904, 594187, 595692, 595693, 52956635,

2965589, 52984752, 52984753, 52984754, 52984755,

2984756, 53021361, 53021367, 53026640, 53027917,

53033688,

71124.01

ALARA Plans

23-2904

Unit 2 Radiological Diving Operations for Repairs to Refuel

Equipment

04/28/2023

71124.01

Corrective Action

Documents

CR-ANO-

1-2022-02079, 1-2022-02084, 1-2022-02196, 1-2022-02254,

1-2022-02310, 1-2022-02445, 1-2022-02447, 1-2022-02505,

1-2022-03062, 2-2023-00521, 2-2023-00866, C-2022-01820,

C-2022-03025, C-2022-03090, C-2022-03552, C-2023-00261,

C-2023-00362, C-2023-00766, C-2023-00956, C-2023-01022

2-28

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71124.01

Corrective Action

Documents

Resulting from

Inspection

CR-ANO-

1-2023-00690, 2-2023-01057, 2-2023-01058

71124.01

Procedures

EN-RP-100

Radiation Worker Expectations

71124.01

Procedures

EN-RP-101

Access Control for Radiologically Controlled Areas

71124.01

Procedures

EN-RP-102

Radiological Control

71124.01

Procedures

EN-RP-105

Radiological Work Permits

71124.01

Procedures

EN-RP-108

Radiation Protection Posting

71124.01

Procedures

EN-RP-110

ALARA Program

71124.01

Procedures

EN-RP-121

Radioactive Material Control

71124.01

Procedures

EN-RP-131

Air Sampling

71124.01

Radiation Surveys

ANO-21-10-

00450

BWST Area 354' Elevation

10/07/2021

71124.01

Radiation Surveys

ANO-21-10-

00490

BWST Area 354'Elevation - Breach inside 2T3 RWT

10/08/2021

71124.01

Radiation Surveys

ANO-21-12-

00180

Unit 2 Spent Fuel Pool Items

2/13/2021

71124.01

Radiation Surveys

ANO-22-11-

00819

Unit 1 Spent Fuel Pool Items

11/30/2022

71124.01

Radiation Surveys

ANO-23-04-

00039

Unit 2 Auxiliary Building 335' Elevation - follow up survey after

2-F3 A/B filter change out

04/04/2023

71124.01

Radiation Surveys

ANO-23-04-

00611

Air Sample: Unit 2 Reactor Building 401' Elevation - under

head dose rate survey

04/19/2023

71124.01

Radiation Surveys

ANO-23-04-

00953

Air Sample: Unit 2 Reactor Building 405' Elevation - under

head entry

04/24/2023

71124.01

Radiation Surveys

ANO-AS-042323-

23

Air Sample: Unit 2 Reactor Building 404' Elevation - ICI

inspection

04/23/2023

71124.01

Radiation Surveys

ANO-AS-042323-

24

Air Sample: Unit 2 Reactor Building 404' Elevation - under

reactor head tool changeout

04/23/2023

71124.01

Radiation Surveys

ANO-AS-042323-

252

Air Sample: Unit 2 Reactor Building 404' Elevation - ROSA

04/23/2023

71124.01

Radiation Surveys

ANO-AS-042323-

265

Air Sample: Unit 2 Reactor Building 404' Elevation - RX head

stand inspect ROSA

04/23/2023

2-29

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71124.01

Radiation Surveys

ANO-AS-042323-

267

Air Sample: Unit 2 Reactor Building 404' Elevation - RX head

tool cleaning

04/23/2023

71124.01

Radiation Surveys

ANO-AS-042523-

0305

Air Sample: Unit 2 Reactor Building 404' Elevation - under

head inspection

04/25/2023

71124.01

Radiation Surveys

ANO-AS-102322-

0359

Air Sample: Unit 1 Reactor Building 335' Elevation - CF-1B

reassembly

10/22/2022

71124.01

Radiation Surveys

ANO-AS-102822-

0392

Air Sample: Unit 1 Reactor Building 426 Elevation - vacuum

change out

10/27/2022

71124.01

Radiation Surveys

ANO-AS-110622-

0458

Air Sample: Unit 1 Reactor Building 404' Elevation - Incore

tank

11/06/2022

71124.01

Radiation Surveys

ANO-AS-111522-

0493

Air Sample: Unit 1 Reactor Building 404' elevation - not

used/cross contaminated

11/15/2022

71124.01

Radiation Surveys

ANO-AS-122922-

0600

Air Sample: Unit 1 Reactor Building 386' Elevation - D-RCP

Startup

2/29/2022

71124.01

Radiation Surveys

RWP 2022-1430

Task 3

Lapel Air Sample - Alpha Level 2 Area

11/06/2022

71124.01

Radiation Surveys

RWP 2022-1433

Task 5

Lapel Air Sample - Alpha Level 2 Area

10/29/2022

71124.01

Radiation Surveys

RWP 2022-1433,

Task 2

Lapel Air Sample - Alpha Level 2 Area

11/06/2022

71124.01

Radiation Surveys

RWP 2022-1900

Task 5

Lapel Air Sample - Alpha Level 2 Area

2/22/2022

71124.01

Radiation Work

Permits (RWPs)

22-1420

1R30 Scaffold Activities

71124.01

Radiation Work

Permits (RWPs)

22-1430

1R30 Reactor Disassembly, Re-assembly and Support

Activities

71124.01

Radiation Work

Permits (RWPs)

22-1433

1R30 Remove and Replace (4) In-core detectors

71124.01

Radiation Work

Permits (RWPs)

22-1500

1R30 P-32B - RCP Motor and Rotating Assembly

Replacement

71124.01

Radiation Work

Permits (RWPs)

22-1502

1R30 Pressurizer Heater Bundle/Cable Replacement

71124.01

Radiation Work

Permits (RWPs)

22-1900

1R30 Emergent Maintenance

2-30

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71124.01

Radiation Work

Permits (RWPs)

23-2455

2SI-3B Disassemble, Inspect, and Repair

71124.01

Radiation Work

Permits (RWPs)

23-2465

2R29 - RCP Seal Replacement for 2P-32A, 2P-32B, and 2P-

2D

71124.01

Radiation Work

Permits (RWPs)

23-2471

2R29 Inspections on Unit 2 Reactor Head

71124.01

Radiation Work

Permits (RWPs)

23-2474

2R29 RWT Tank Maintenance and Inspections

71124.01

Self-Assessments

LO-ALO-2022-

00085

Focused Self-Assessment: Radiation Inspection -

Radiological Hazards and Exposure Controls, Occupational

Dose Assessment, and Performance Indicator Verification

IP-71124.01, IP-71124.04, IP-71151

2/19/2022

71124.04

Corrective Action

Documents

CR-ANO-

C-2021-02306, C-2021-02614, C-2021-02656, C-2021-02659,

C-2021-02732, C-2021-03209, C-2021-03268, 2-2021-02120,

C-2022-00715, C-2022-00716, C-2022-01167, 1-2022-01972,

1-2022-03043, 2-2023-00521, C-2023-00540

71124.04

Corrective Action

Documents

Resulting from

Inspection

CR-HQN-

23-00575

71124.04

Miscellaneous

21 Self-Reading Dosimeter (SRD) versus Dosimeter of

Legal Record (DLR) Discrepancies

21

71124.04

Miscellaneous

22 Self-Reading Dosimeter (SRD) versus Dosimeter of

Legal Record (DLR) Discrepancies

22

71124.04

Miscellaneous

NVLAP Certificate of Accreditation to ISO/IEC 17025:2017 for

Landauer, Inc., 1/1/2023 - 12/31/2023

01/01/2023

71124.04

Miscellaneous

Station 5-Year Exposure Reduction Plant Template: Arkansas

Nuclear One 5-Year Exposure Reduction Plan 2023-2027

2/12/2022

71124.04

Miscellaneous

2015 ANO Neutron Radiation Assessment Report

04/11/2016

71124.04

Miscellaneous

TEDE-ALARA Evaluation for RWP 2023-2471, Task 3, "Under

Head - All entries except CEDM Nozzle 71"

11/16/2022

71124.04

Miscellaneous

21 - 2023 List of Multipack TLD Assignment: EDEX work

activities and dose assigned

03/06/2023

71124.04

Miscellaneous

ANO-RPT-21-002

Site Radiological Characterization and Assessment

2/27/2021

2-31

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

RO

71124.04

Miscellaneous

PCE 2021-018

Personnel Contamination Event - Hair

11/24/2021

71124.04

Miscellaneous

PCE 2022-009

Personnel Contamination Event - Facial

10/21/2022

71124.04

Miscellaneous

PCE 2022-011

Personnel Contamination Event - Facial

2/24/2022

71124.04

Miscellaneous

Sample 22-07076

CFR Part 61 Waste Stream Sample Screening and

Evaluation: 2022 Dry Active Waste

01/11/2023

71124.04

Procedures

EN-RP-122

Alpha Monitoring

71124.04

Procedures

EN-RP-141

Job Coverage

71124.04

Procedures

EN-RP-141-02

Discrete Radioactive Particle Control

71124.04

Procedures

EN-RP-201

Dosimetry Administration

71124.04

Procedures

EN-RP-202

Personnel Monitoring

71124.04

Procedures

EN-RP-203

Dose Assessment

71124.04

Procedures

EN-RP-204

Special Monitoring Requirements

71124.04

Procedures

EN-RP-206

Dosimeter of Legal Record Quality Assurance

71124.04

Procedures

EN-RP-208

Whole Body Counting / In-Vitro Bioassay

71124.04

Procedures

EN-RW-104

Scaling Factors

71124.04

Radiation Surveys

ANO-21-09-

00317

PS5-01 Location CSB 1st Floor

09/21/2021

71124.04

Radiation Surveys

ANO-21-12-

00172

Radwaste-05 Sealand Storage

2/13/2021

71124.04

Radiation Surveys

ANO-22-07-

00087

PS5-01 Location CSB 1st Floor

07/07/2022

71124.04

Radiation Surveys

ANO-23-04-

00039

Unit 2 AUX 335 EL 2F3 A/B Room #20327

04/04/2023

71124.04

Radiation Surveys

ANO-AS-040323-

0094

Air Sample: Filter Changeout for 2F-3B Filter

04/03/2023

71124.04

Radiation Surveys

ANO-AS-040323-

0095

Air Sample: Filter Changeout for 2F-3A Filter

04/03/2023

71124.04

Radiation Work

Permits (RWPs)

21-2430

2R28 Reactor Disassembly / Reassembly

71124.04

Radiation Work

Permits (RWPs)

21-2471

2R28 Inspections and Laser Peening on Unit 2 Reactor Head

71124.04

Radiation Work

22-1061

Unit 1 Reactor Building Entry At Power

2-32

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Permits (RWPs)

71124.04

Radiation Work

Permits (RWPs)

23-2052

Unit 2 Change Spent Plant Process Filters

71124.04

Radiation Work

Permits (RWPs)

23-2471

2R29 Inspections on Unit 2 Reactor Head

71124.04

Self-Assessments

LO-ALO-2022-

00085

Radiation Inspection - Radiological Hazards and Exposure

Controls, Occupational Dose Assessment, and Performance

Indicator Verification IP 71124.01, IP 71124.04, IP 71151

2/19/2022

71124.05

Corrective Action

Documents

CR-ANO-

1-2023-00537

71124.05

Corrective Action

Documents

Resulting from

Inspection

CR-ANO-

2-2023-01054

71124.06

Corrective Action

Documents

CR-ANO-

1-2021-00341, 1-2021-03102, 1-2022-01118, 1-2022-01131,

1-2022-03171, 1-2023-00155, 1-2023-00160, 1-2023-00221,

1-2023-00282, 2-2020-01432, 2-2022-01916, 2-2022-01954,

2-2022-01991, 2-2023-01937, C-2022-02564, C-2022-03107,

C-2023-00222, C-2023-00541

71124.06

Corrective Action

Documents

Resulting from

Inspection

CR-ANO-

C-2023-01679

71124.06

Miscellaneous

0CAN042102

Radioactive Effluent Release Report for 2020

04/21/2021

71124.06

Miscellaneous

0CAN042202

Radioactive Effluent Release Report for 2021

04/14/2022

71124.06

Miscellaneous

0CAN042301

Radioactive Effluent Release Report for 2022

04/14/2023

71124.06

Miscellaneous

1Q2022

Results of Radiochemistry Cross Check Program - Entergy,

Arkansas Nuclear One

05/18/2022

71124.06

Miscellaneous

21

Land Use Census

08/12/2021

71124.06

Miscellaneous

22

CFR Part 61 waste stream analysis - dry active waste

01/11/2023

71124.06

Miscellaneous

2Q2022

Results of Radiochemistry Cross Check Program - Entergy,

Arkansas Nuclear One

08/30/2022

71124.06

Procedures

1607.010

Sampling of Unit Vents

71124.06

Procedures

1618.011

Sampling the Unit 1 Neutralizing Tank

2-33

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71124.06

Procedures

20.417

In-place Testing of the Unit 1 Penetration Room Filtration

Systems

71124.06

Procedures

EN-CY-131

Annual Radioactive Effluent Release Report

71124.06

Procedures

HES-06

Ventilation/Filtration Testing Program

71124.06

Procedures

ODCM

Offsite Dose Calculation Manual

71124.06

Radiation Surveys

Gaseous Release

Permits -

1GR20YY-ZZZZ

20-0061, 20-0092, 21-0018, 21-0026, 21-0029, 22-0012, 22-

0049, 22-0080, 22-0088, 23-0002

71124.06

Radiation Surveys

Gaseous Release

Permits -

2GR20YY-ZZZZ

20-0065, 20-0072, 20-0094, 20-0107, 21-0014, 21-0034, 21-

0068, 21-0097, 22-0017, 22-0028, 22-0063, 23-0023, 23-0036

71124.06

Radiation Surveys

Liquid Release

Permits -

1LR20YY-ZZZZ

20-0042, 20-0050, 21-0018, 21-0029, 21-0052, 21-0065, 21-

0089, 22-0015, 22-0028, 22-0041, 22-0054, 22-0073, 23-

0001, 23-0016

71124.06

Radiation Surveys

Liquid Release

Permits -

2LR20YY-ZZZZ

20-0025, 20-0044, 21-0009, 21-0020, 21-0028, 22-0005, 22-

0008, 22-0009, 23-0002, 23-0017

71124.06

Self-Assessments

LO-ALO-2022-

00075

Pre-NRC Inspection Assessment:

Radioactive Gaseous and Liquid Effluent Treatment,

Radiological Environmental

Monitoring Program

2/01/2023

71124.06

Self-Assessments

NAQA-20-0029

To evaluate the effectiveness of the Environmental Dosimetry

Company quality assurance program as implemented by their

quality assurance manual

08/19/2020

71124.06

Self-Assessments

NQ-2021-016

QA Audit Report QA-2/6-2021-ANO-01, 2021 QA Audit of

Chemistry,

Effluents & Environmental Monitoring Programs at Arkansas

Nuclear One (ANO)

09/16/2021

71124.06

Self-Assessments

WT-WTHQN-

21-

00564/NUPIC

To evaluate the adequacy and implementation of the Teledyne

Brown Engineering -Environment Services quality program for

the product/service

03/08/2022

71124.06

Work Orders

00572329 01

Repair Sagging Tubing Cause Water Intrusion on RX-9830

11/28/2022

71124.06

Work Orders

00583738 01

Replace VFC-1 charcoal filters

2/13/2023

71124.06

Work Orders

293635 01

Perform the Qtrly Channel Test of Sping 3, RX-9830

2/20/2021

2-34

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71124.06

Work Orders

2956781 01

Perform 18m test of VEF-38A (pent. room ventilation)

20.417, VEF-38A - mech obtain charcoal sample

03/28/2022

71124.06

Work Orders

2957597 01

Perform 18m test of VEF-38-B (pent room vent)

OP-5120.417, VEF-38B - mech to obtain charcoal sample

05/13/2022

71124.06

Work Orders

2972191

Charcoal filter testing results

07/25/2022

71124.06

Work Orders

2972191 01

20.413, 18m VEF-14 (fuel handling area) test

VEF-14 A/B - mech to obtain charcoal sample

07/13/2022

71124.07

Calibration

Records

Discharge canal composite sampler calibration

05/01/2023

71124.07

Calibration

Records

AS001

Air Station 1 Rotameter Calibration

04/28/2023

71124.07

Corrective Action

Documents

CR-ANO-

1-2021-03220, 2-2022-00471, 2-2023-00494, C-2021-01467,

C-2021-01612, C-2021-01887, C-2021-02292, C-2021-02354

71124.07

Corrective Action

Documents

Resulting from

Inspection

CR-ANO-

1-2023-00854, C-2023-01665, C-2023-01676, C-2023-01686,

C-2023-01687, C-2023-02950

71124.07

Miscellaneous

Annual Quality Assurance Status Report - January -

December 2022

03/24/2023

71124.07

Miscellaneous

First Quarter of 2023 Environmental Dosimetry Data

05/24/2023

71124.07

Miscellaneous

Quality control chart for chemistry count room gamma detector

1. 2 for 05/01/2023 to 06/13/2023

71124.07

Miscellaneous

Quality control chart for chemistry count room gamma detector

1. 3 for 05/01/2023 to 06/13/2023

71124.07

Miscellaneous

Liquid scintillation counting for gross beta and Tritium

measurements for Tri-Carb 4910 liquid scintillation counter #1

04/19/2023

71124.07

Procedures

EN-CY-102

Laboratory Analytical Quality Control

71124.07

Procedures

EN-CY-127

Land Use Census

71124.07

Procedures

EN-CY-130-01

Radiological Environmental Monitoring Program (REMP)

Arkansas Nuclear One

71124.07

Procedures

SOP 100

Standard Operating Procedures for Groundwater Monitoring

and Investigations

71124.07

Work Orders

WO# 53006838

Semi-annual meteorological monitoring calibration

2/02/2022

71124.07

Work Orders

WO# 00563242

Met tower elevator drive cable replacement

06/28/2021

2-35

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71124.07

Work Orders

WO# 00567157

Met tower investigation and repair inidcation

10/15/2021

71124.07

Work Orders

WO# 52906998

Met tower anchor inspection

07/27/2021

71124.07

Work Orders

WO# 52937302

Met tower guyed wire inspection

07/14/2021

71124.07

Work Orders

WO# 52990843

Semi-annual meteorological monitoring calibration

06/02/2022

71151

Miscellaneous

ANO-1 and ANO-2 NRC Performance Indicator

Technique/Data Sheets - Mitigating Systems

Q3-2022

71151

Miscellaneous

ANO-1 and ANO-2 NRC Performance Indicator

Technique/Data Sheets - Mitigating Systems

Q4-2022

71151

Miscellaneous

ANO-1 and ANO-2 NRC Performance Indicator

Technique/Data Sheets - Mitigating Systems

Q1-2023

71151

Miscellaneous

ANO-1 and ANO-2 NRC Performance Indicator

Technique/Data Sheets - Barrier Integrity

Q2-2022

71151

Miscellaneous

ANO-1 and ANO-2 NRC Performance Indicator

Technique/Data Sheets - Barrier Integrity

Q3-2022

71151

Miscellaneous

ANO-1 and ANO-2 NRC Performance Indicator

Technique/Data Sheets - Barrier Integrity

Q4-2022

71151

Miscellaneous

ANO-1 and ANO-2 NRC Performance Indicator

Technique/Data Sheets - Barrier Integrity

Q1-2023

71151

Miscellaneous

ANO-1 and ANO-2 NRC Performance Indicator

Technique/Data Sheets - Mitigating Systems

Q2-2022

71151

Miscellaneous

EN-LI-114, Att. 1

NRC Performance Indicator Technique / Data Sheet: 4th

Quarter of 2022 for RETS/ODCM Radiological Effluent

Occurrence

01/04/2023

71151

Miscellaneous

OR01

RCA entries >100 millirem

71151

Procedures

EN-LI-114

Regulatory Performance Indicator Process

19, 20

71152A

Corrective Action

Documents

1-1016-00327, 1-2018-03832, 1-2023-00214, 1-2023-00275,

1-2023-00276, 1-2023-00277, 1-2023-00393, 1-2023-00401,

1-2023-00554, 1-2023-00962, 2-2021-02496, 2-2023-00108,

2-2023-00387, 2-2023-00540, 2-2023-01057, 2-2023-01282,

2-2023-02140, C-2018-03178, C-2022-00147, C-2023-00912,

C-2023-00972, C-2023-01003, C-2023-01260, C-2023-03008

71152A

Engineering

Changes

EC-81851

MS-271 and MS-272 EFW Crosstie Replacement

71152A

Engineering

EC-82061

2MS-39A/B SIPD 9243

2-36

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Changes

71152A

Miscellaneous

FHA

Fire Hazards Analysis

71152A

Miscellaneous

PFP-U1

ANO Prefire Plan (Unit 1)

71152A

Procedures

EN-IS-111

General Industrial Safety Requirements

71152A

Procedures

EN-IS-114

Fall Protection

71152A

Procedures

EN-MA-133

Control Of Scaffolding

71152A

Procedures

EN-MA-141

Limitorque Valve Operator Model SMB/SB/SBD-000 through 5

MOV and HBC Periodic Inspection Procedures

71152A

Procedures

EN-MA-148

Motor Operated Valve Diagnostics

71152A

Work Orders

WO 517493, 517494, 520975, 593693, 52932138, 52996885

71153

Corrective Action

Documents 71153

CR-ANO-

1-2023-00252, 1-2023-00290, 1-2023-00325, 1-2023-00399,

1-2023-00611, 1-2023-00650,1-2023-00837, 2-2023-01929, 2-

23-01938, 2-2023-01939

71153

Miscellaneous

71153

Unit 2 Narrative Log

06/14/2023

71153

Miscellaneous

71153

Unit 2 Narrative Log

06/15/2023

71153

Procedures

71153

OP-1412.022

Protect, Relay Test & Insp of RCS Pump UndrwrRelay GE Mdl

CFW11E

71153

Procedures

71153

OP-2203.027

Loss of Main Feedwater Pump

19