IR 05000313/2021002

Integrated Inspection Report 05000313/2021002 and 05000368/2021002

ML21217A332
Person / Time
Site:	Arkansas Nuclear
Issue date:	08/09/2021
From:	John Dixon NRC/RGN-IV/DRP
To:	Dinelli J Entergy Operations
References
IR 2021002
Download: ML21217A332 (27)

Text

August 9, 2021

SUBJECT:

ARKANSAS NUCLEAR ONE - INTEGRATED INSPECTION REPORT 05000313/2021002 AND 05000368/2021002

Dear Mr. Dinelli:

On June 30, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Arkansas Nuclear One. On July 1, 2021, the NRC inspectors discussed the results of this inspection with Mr. J. Sullivan, General Manager Plant Operations, and other members of your staff. The results of this inspection are documented in the enclosed report.

One finding of very low safety significance (Green) is documented in this report. This finding involved a violation of NRC requirements. We are treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2 of the Enforcement Policy.

If you contest the violation or the significance of the violation documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region 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 (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 Dixon, John on 08/09/21 John L. Dixon, Jr., Chief Reactor Projects Branch D Division of Reactor Projects Docket Nos. 05000313 and 05000368 License Nos. DPR-51 and NPF-6

Enclosure:

As stated w/Attachment: Momentary Loss of Power to 4160 Vac bus A2 Event

Inspection Report

Docket Numbers: 05000313 and 05000368 License Numbers: DPR-51 and NPF-6 Report Numbers: 05000313/2021002 and 05000368/2021002 Enterprise Identifier: I-2021-002-0109 Licensee: Entergy Operations, Inc.

Facility: Arkansas Nuclear One Location: Russellville, AR Inspection Dates: April 1, 2021, to June 30, 2021 Inspectors: B. Baca, Health Physicist N. Brown, Resident Inspector R. Bywater, Senior Resident Inspector T. DeBey, Resident Inspector J. Drake, Senior Reactor Inspector J. O'Donnell, Senior Health Physicist A. Patz, Senior Resident Inspector Approved By: John L. Dixon, Jr., Chief Reactor Projects Branch D Division of Reactor Projects Enclosure

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 Provide Appropriate Procedures for 4160 Vac Switchgear Inspections Cornerstone Significance Cross-Cutting Report Aspect Section Initiating Events Green [H.9] - Training 71111.12 NCV 05000313/2021002-01 Open/Closed The inspectors identified a Green finding and associated non-cited violation of Arkansas Nuclear One, Unit 1, Technical Specifications 5.4.1.a, for the licensees failure to have an adequate maintenance procedure as required by Regulatory Guide 1.33, Quality Assurance Program Requirements, Revision 2, February 1978. Regulatory Guide 1.33, Appendix A,

Section 9, Procedures for Performing Maintenance, requires, in part, that maintenance should be properly preplanned and performed in accordance with written procedures, documented instructions, or drawings appropriate to the circumstances. Specifically,

Procedure OP-1416.002, U1 A2 Bus Switchgear Inspection, Revision 21, did not adequately provide the level of detail required, including qualitative or quantitative acceptance criteria, to ensure correct alignment of potential transformer contacts. A manual trip of Arkansas Nuclear One, Unit 1, from full power was caused by a bent potential transformer contact in the 4160 Vac A2 bus that was not identified during previous inspections.

Additional Tracking Items

Type Issue Number Title Report Section Status LER 05000313/2021-001-00 Reactor Manual Trip due to 71153 Closed Temporary Loss of Non-Vital 4160 Volt Bus

PLANT STATUS

Unit 1 entered the inspection period at 90 percent power and then shut down for a planned refueling outage between April 9 and May 11, 2021. Unit 1 operated at or near full power for the remainder of the inspection period.

Unit 2 operated at or near full power for the duration 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 reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.

Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the coronavirus (COVID-19), resident and regional inspectors were directed to begin telework and to remotely access licensee information using available technology. During this time, the resident inspectors performed periodic site visits each week, increasing the amount of time on site as local COVID-19 conditions permitted.

As part of their onsite activities, resident inspectors conducted plant status activities as described in IMC 2515, Appendix D; observed risk significant activities; and completed on site portions of IPs. In addition, resident and regional baseline inspections were evaluated to determine if all or a portion of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In some cases, portions of an IP were completed remotely and on site. The inspections documented below met the objectives and requirements for completion of the IP.

71111.01 - Adverse Weather Protection

Impending Severe Weather Sample (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated the adequacy of the overall preparations to protect risk- significant systems from a severe thunderstorm warning on June 21, 2021.

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) Unit 1 emergency diesel generator 1 during Unit 1 emergency diesel generator 2 outage on May 20, 2021

(2) Unit 1 service water loop 1 during Unit 1 emergency diesel generator 2 outage on June 9, 2021

(3) Unit 2 emergency diesel generator 2 during Unit 2 emergency diesel generator 1 outage on June 30, 2021

71111.05 - Fire Protection

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

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

(1) Unit 2 post-accident sampling building, Fire Zone PASS building, on April 1, 2021

(2) Unit 2 turbine-driven emergency feedwater pump A room, Fire Zone 2024, on May 21, 2021

(3) Unit 1 intake structure, Fire Area N, on June 21, 2021

(4) Unit 2 intake structure, Fire Area OO, on June 30, 2021

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

(1) The inspectors verified that the Unit 1 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 22 to May 4, 2021:

03.01.a - Nondestructive Examination and Welding Activities Ultrasonic Examination a. Containment Sump, P-66 IWE CS Sleeve to Flued Head b. Containment Sump, P-67 IWE CS Sleeve to Flued Head c. Containment Sump, P-68 IWE CS Sleeve to Flued Head d. Oily Waste Separator, OW-117-201, 6-inch Buried Pipe e. Service Water, MIC-I (HBD-2-18"), straight pipe Visual Examination a. Containment, P- 66, Reactor Building Sump Recirc Penetration Type VII b. Containment, P- 67, Reactor Building Sump Recirc Penetration Type VII c. Containment, P- 68, Reactor Building Sump Recirc Penetration Type VII The inspector reviewed the weld package for repairs on the main feedwater system for valve FW-2837, welds FW-1, FW-2, FW-3, FW-4, FW-5.

03.01.b - Pressurized-Water Reactor Vessel Upper Head Penetration Examination Activities The inspector reviewed the NDE report for the Reactor Vessel Upper Head Penetration examination activities which consisted of an ultrasonic examination of all CRDM nozzles and a demonstrated volumetric leak path assessment of all J-groove welds and supplemental eddy current examination of 35 CRDM nozzle inside surfaces.

03.01.c - Pressurized-Water Reactor Boric Acid Corrosion Control Activities The following boric acid evaluations and condition reports were reviewed:

a. CR-ANO-1-2018-01078, CR-ANO-1-2019-02272, CR-ANO-1-2020-01226, CR-ANO-1-2020-01229, CR-ANO-1-2020-01377 03.01.d - Pressurized-Water Reactor Steam Generator Tube Examination Activities 100 percent full length inspection of all tubes with bobbin coil probe X-Probe and bobbin probe inspection of the tubes surrounding each tie rod to evaluate tie rod bowing Problem Identification and Resolution review of Inservice items The inspector evaluated a sample of 34 condition reports associated with inservice inspection activities. No findings or violations of more than minor significance were identified.

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 Unit 1 control room during plant cooldown, depressurization, and transfer to shutdown cooling in preparation for Refueling Outage 29 on April 12, 2021.

Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)

(1) The inspectors observed and evaluated the Unit 2 licensed operator simulator evaluation scenario on June 15, 2021.

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) Alignment checks of potential transformer contacts in 4160 Vac switchgear on

June 7, 2021 Quality Control (IP Section 03.02) (1 Sample)

The inspectors evaluated the effectiveness of maintenance and quality control activities to ensure the following SSC remains capable of performing its intended function:

(1) Quality control for stored fuel oil/preventive maintenance strategy of diverse and flexible mitigation capability response equipment on June 29, 2021

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 1 Refueling Outage 29 plan on April 6, 2021

(2) Unit 1 planned entry into lowered reactor coolant system inventory on April 29, 2021

(3) Unit 1 and Unit 2 work controls for spurious opening of 161 kV switchyard breaker B1218 during alternate AC diesel generator maintenance outage on June 24, 2021

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (5 Samples)

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

(1) Unit 1 emergency feedwater initiation and control channel B steam generator B pressure transmitter containment isolation valve MS-6843 seat leakage operability determination on April 1, 2021

(2) Unit 2 Loop 2 service water pinhole leak operability determination on May 7, 2021

(3) Unit 1 high pressure injection system, all flow transmitters improper calibration/recalibration operability determination, on May 25, 2021

(4) Common unit meteorological tower functionality assessment and availability of alternate meteorological data on June 1, 2021

(5) Unit 1 borated water storage tank internal inspection operability determination on June 3, 2021

71111.18 - Plant Modifications

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

(1 Sample)

The inspectors evaluated the following temporary or permanent modifications:

(1) Unit 1 emergency diesel room exhaust fan replacements on May 24, 2021

71111.19 - Post-Maintenance Testing

Post-Maintenance Test Sample (IP Section 03.01) (2 Samples)

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

(1) Unit 1 service water pump P-4C post-maintenance testing after pump shaft replacement on June 29, 2021

(2) Common unit diesel-driven fire pump P-6B post-maintenance testing after semi-annual inspection and preventive maintenance on June 30, 2021

71111.20 - Refueling and Other Outage Activities

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

(1) The inspectors evaluated Unit 1 Refueling Outage 29 activities from April 9 to May 11, 2021.

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance tests:

Surveillance Tests (other) (IP Section 03.01)

(1) Unit 1 surveillance testing of five main steam safety valves on April 15, 2021

(2) Unit 2 surveillance testing of moderator temperature coefficient on April 22, 2021

(3) Unit 1 surveillance testing of emergency diesel generator 1 on May 3, 2021

(4) Unit 1 core power distribution surveillance testing after refueling outage on May 12, 2021

(5) Unit 1 service water system surveillance testing on May 17, 2021

(6) Unit 1 surveillance testing of boron concentration in primary coolant water on

May 19, 2021 Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)

(1) Unit 1 local leak rate testing of reactor building sump isolation valve CV-4400 on

April 29, 2021 FLEX Testing (IP Section 03.02) (1 Sample)

(1) Annual surveillance testing of FLEX portable pumps and generators on May 11,

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)

The inspectors evaluated instructions to workers including radiation work permits (RWP)used to access high radiation areas.

(1) The inspectors reviewed the following radiation work permit (RWP) packages, electronic alarming dosimeter condition reports, and labeling of containers:

RWP 2021-1471, "1R29 Reactor Pressure Vessel Closure Head - Volumetric and Surface Exams," Revision 0 RWP 2021-1442, "1R29 Steam Generator Primary Side Eddy Current Inspection and Repair Activities," Revision 0 RWP 2021-1406, "1R29 Radwaste Processing and Shipping," Revision 0 CR-ANO-1-2020-01134 - Worker received an unanticipated dose rate alarm and took appropriate actions CR-ANO-C-2020-01365 - Worker received a dose alarm during Unit 2 under vessel walk down; the alarm was determined to be instrument malfunction Yellow radioactive material trash bags [various areas in the Radiologically Controlled Area]

Two Intermodal containers of Dry Active Waste [ESUU300322 and ESUU300545]

Storage box (EQ-216) containing tensioner cables on the Reactor Building -

404-foot elevation

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

The inspectors evaluated licensee processes for monitoring and controlling contamination and radioactive material:

(1) Observed licensee surveys of potentially contaminated material leaving the radiologically controlled area

(2) Observed workers exiting the Unit 1 containment building during a refueling outage

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

The inspectors evaluated in-plant radiological conditions during facility walkdowns and observation of radiological work activities. The inspectors reviewed the following radiological work packages for activities within the Unit 1 containment building:

(1) RWP 2021-1442, "1R29 Steam Generator Primary Side Eddy Current Inspection and Repair Activities," Revision 0, specifically for installation of nozzle dams and eddy current equipment

(2) RWP 2021-1471, "1R29 Reactor Pressure Vessel Closure Head - Volumetric and Surface Exams," Revision 0, specifically for under head inspection activities

(3) The inspectors also reviewed the following radiological work package for activities associated with processing and handling of radioactive waste: RWP 2021-1406, "1R29 Radwaste Processing and Shipping," Revision 0, specifically for Shipment RSR-21-038 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 and Very High Radiation Areas:

(1) In-Core Tunnel was controlled as a Very High Radiation Area on the Unit 1 Containment Building - 335-foot elevation

(2) Access to the In-Core Tunnel was controlled as a Technical Specification (TS) High Radiation Area (HRA) on the Unit 1 Containment Building - 335-foot elevation

(3) Reactor Vessel Closure Head stand was controlled as a TS HRA using the flashing lights control option on the Unit 1 Containment Building - 404-foot elevation

(4) The T-11 Tank Room was controlled as a TS HRA in the Unit 1 Auxiliary Building -

317-foot elevation

(5) The F3A/B Filter Room was controlled as a TS HRA in the Unit 1 Auxiliary Building -

335-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.

71124.03 - In-Plant Airborne Radioactivity Control and Mitigation

Permanent Ventilation Systems (IP Section 03.01) (2 Samples)

The inspectors evaluated the configuration of the following permanently installed ventilation systems:

(1) Unit 1 control room emergency ventilation system

(2) Emergency operation facility ventilation system

Temporary Ventilation Systems (IP Section 03.02) (2 Samples)

The inspectors evaluated the configuration of the following temporary ventilation systems:

(1) Unit 1 Reactor Containment Building, 426-foot elevation - Reactor head ventilation and Alpha Level 2 decontamination tent ventilation

(2) Unit 1 Reactor Containment Building, 335-foot elevation - Steam Generator D-ring eddy current testing

Use of Respiratory Protection Devices (IP Section 03.03) (1 Sample)

(1) The inspectors evaluated the licensees use of respiratory protection devices during Unit 1 refueling outage work activities.

Self-Contained Breathing Apparatus for Emergency Use (IP Section 03.04) (1 Sample)

(1) The inspectors evaluated the licensees use and maintenance of self-contained breathing apparatuses.

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, 2020 through March 31, 2021)

(2) Unit 2 (April 1, 2020 through March 31, 2021)

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

(1) Unit 1 (April 1, 2020 through March 31, 2021)

(2) Unit 2 (April 1, 2020 through March 31, 2021)

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

(1) Unit 1 (April 1, 2020 through March 31, 2021)

(2) Unit 2 (April 1, 2020 through March 31, 2021)

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

(1) Unit 1 and Unit 2 (January 1, 2020 through December 31, 2020)

PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample (IP Section 02.16) (1 Sample)

(1) Unit 1 and Unit 2 (January 1, 2020 through December 31, 2020)

71153 - Follow Up of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)

The inspectors evaluated the following licensee event reports (LERs):

(1) LER 05000313/2021-001-00, Reactor Manual Trip due to Temporary Loss of Non-Vital 4160 Volt Bus (ADAMS Accession No. ML21133A020). The inspection conclusions associated with this LER are documented in this report as Non-Cited Violation 05000313/2021002-01.

INSPECTION RESULTS

Failure to Provide Appropriate Procedures for 4160 Vac Switchgear Inspections Cornerstone Significance Cross-Cutting Report Aspect Section Initiating Events Green [H.9] - Training 71111.12 NCV 05000313/2021002-01 Open/Closed The inspectors identified a Green finding and associated non-cited violation of Arkansas Nuclear One, Unit 1, Technical Specifications 5.4.1.a, for the licensees failure to have an adequate maintenance procedure as required by Regulatory Guide 1.33, Quality Assurance Program Requirements, Revision 2, February 1978. Regulatory Guide 1.33, Appendix A, Section 9, Procedures for Performing Maintenance, requires, in part, that maintenance should be properly preplanned and performed in accordance with written procedures, documented instructions, or drawings appropriate to the circumstances. Specifically, Procedure OP-1416.002, U1 A2 Bus Switchgear Inspection, Revision 21, did not adequately provide the level of detail required, including qualitative or quantitative acceptance criteria, to ensure correct alignment of potential transformer contacts. A manual trip of Arkansas Nuclear One, Unit 1, from full power was caused by a bent potential transformer contact in the 4160 Vac A2 bus that was not identified during previous inspections.

Description:

On March 14, 2021, while operating at full power, the Arkansas Nuclear One (ANO) Unit 1 reactor experienced a loss of power to the non-safety-related 4160 Vac bus A2, which feeds safety-related 4160 Vac bus A4. Reactor operators manually tripped the reactor as required by their procedures. Emergency diesel generator B automatically started and provided power to the A4 bus. The licensees adverse condition analysis determined that a bent contact in the A2 bus potential transformer drawer resulted in contact misalignment, loss of electrical continuity, and loss of power to the A2 bus. The licensee concluded the contact most likely became bent during refurbishment of the A2 bus in 2013. The inspectors reviewed the A2 bus maintenance records and found that the licensee performed A2 bus potential transformer drawer contact alignment inspections using Procedure OP-1416.002 in 2013, 2016, and 2019. Each of these inspections documented satisfactory alignment. The technique used in the procedure to check contact alignment was a contact wipe check using Mobil 28 grease. The inspectors determined that Procedure OP-1416.002 was inadequate because it did not provide instructions for how to perform the wipe check and did not contain quantitative or qualitative acceptance criteria for wipe check results. The procedure had a table with entries stating, Contact wiped using Mobil 28 grease, and, Ensure proper contact wipe using Mobil 28 grease. Acceptance criteria specified were: Sat and Unsat. The procedure was inadequate to identify the bent contact in the A2 bus potential transformer drawer.

The inspectors also examined the licensees procedures for inspecting potential transformer contact alignment in all the other seven Unit 1 and Unit 2 4160 Vac buses and found similar inadequate inspection acceptance criteria. Additionally, the inspectors identified several examples where the procedures were not written consistently using language required by Procedure CPG-001, ANO Procedure Writers Guide, Revision 2. For example, the procedures inconsistently used action words such as verify, check, and, ensure, which have different specific meanings. Also, although the potential transformer drawers for the eight ANO Unit 1 and Unit 2 4160 Vac buses are identical General Electric devices, the licensees inspection procedures varied considerably in format and content among them.

Corrective Actions: The licensee cleaned and realigned the potential transformer contacts and restored the A2 bus to normal operation. A condition report was written with corrective actions to perform an adverse condition analysis of the event, review and revise inspection procedures, and complete extent of condition inspections of potential transformer contacts in the other buses. The Unit 1 inspections were completed in the spring 2021 refueling outage and the Unit 2 inspections were scheduled to be performed in the fall 2021 refueling outage.

Corrective Action References: Condition Reports CR-ANO-1-2021-00457, CR-ANO-1-2021-00490, CR-ANO-1-2021-00491, and CR-ANO-2-2021-00709

Performance Assessment:

Performance Deficiency: The inspectors determined that the failure to have an adequate maintenance procedure to correctly perform inspection of potential transformer contact alignment in 4160 Vac bus A2 in accordance with Technical Specification 5.4.1.a and Regulatory Guide 1.33 was a performance deficiency.

Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the procedure quality 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. Specifically, Procedure OP-1416.002, U1 A2 Bus Switchgear Inspection, Revision 21, did not adequately provide the level of detail required, including qualitative or quantitative acceptance criteria, to ensure correct alignment of potential transformer contacts.

A manual trip of ANO Unit 1 from full power was caused by a bent potential transformer contact in the 4160 Vac A2 bus that was not identified during previous inspections.

Significance: The inspectors assessed the significance of the finding using Appendix A, The Significance Determination Process (SDP) for Findings At-Power. A detailed risk evaluation was required for this finding because it was a condition that caused a reactor trip and the loss of mitigation equipment (auxiliary feedwater pump P-75, powered from the A2 bus). A senior reactor analyst performed the detailed risk assessment and determined that the estimated increase in core damage frequency from internal events for this performance deficiency was 3.5E-7/year. The analyst determined the risk contribution due to external events was insignificant. There was no significant contribution to large early release frequency.

Therefore, the finding was of very low safety significance (Green). The full Detailed Risk Assessment is provided as an attachment to this report.

Cross-Cutting Aspect: H.9 - Training: The organization provides training and ensures knowledge transfer to maintain a knowledgeable, technically competent workforce and instill nuclear safety values. Specifically, knowledge transfer and knowledge retention strategies were not applied to ensure technicians were technically competent in the performance of wipe checks of potential transformer contacts while using inadequate inspection procedures.

Enforcement:

Violation: Technical Specification 5.4.1.a for Unit 1 requires, in part, that written procedures be established, implemented, and maintained covering the applicable procedures recommended in Appendix A to Regulatory Guide 1.33, Quality Assurance Program Requirements, Revision 2, February 1978. Regulatory Guide 1.33, Appendix A, Section 9, Procedures for Performing Maintenance, requires, in part, that maintenance should be properly preplanned and performed in accordance with written procedures, documented instructions, or drawings appropriate to the circumstances.

Contrary to the above, prior to March 14, 2021, the licensee failed to create written procedures, documented instructions, or drawings appropriate to the circumstances to perform inspection of potential transformer contact alignment in 4160 Vac buses.

Specifically, the licensee did not provide an adequate level of detail, including qualitative or quantitative acceptance criteria, in Procedure OP-1416.002, Unit 1 A2 Bus Inspection, Revision 21, to ensure correct alignment of potential transformer contacts. A manual reactor trip of ANO Unit 1 from full power was caused by a bent potential transformer contact in the 4160 Vac A2 bus that was not identified during previous inspections.

Enforcement Action: This violation is being treated as a non-cited violation, consistent with 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 22, 2021, the inspectors presented the occupational radiation safety inspection results to Mr. J. Dinelli, Site Vice President, and other members of the licensee staff.

On May 5, 2021, the inspectors presented the ANO Unit 1 inservice inspection results to Mr. J. Dinelli, Site Vice President, and other members of the licensee staff.

On July 1, 2021, the inspectors presented the integrated inspection results to Mr. J. Sullivan, General Manager Plant Operations, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.01 Procedures 1203.025 Natural Emergencies 77

71111.04 Corrective Action CR-ANO- 2-2021-00783, 2-2021-00785, 2-2021-00812, C-2021-01519

Documents

71111.04 Drawings M-217, Sheet 1 Emergency Diesel Generators Fuel Oil Storage 91

71111.04 Drawings M-217, Sheet 4 Emergency Diesel Generators K-4A/K-4B Starting Air 9

System

71111.04 Procedures OP-1104.029 Service Water and Auxiliary Cooling System 122

71111.04 Procedures OP-1104.036 Emergency Diesel Generator Operation Attachment A 86

71111.04 Procedures OP-2104.036 Emergency Diesel Generator Operations 99

71111.04 Work Orders WO 52933844, 52935896

71111.05 Corrective Action CR-ANO- 2-2021-1114, C-2021-0944, C-2021-0945, C-2021-0946

Documents

71111.05 Drawings FP-110, Sheet 1 Fire Zone Intake Structure 11

71111.05 Drawings FP-2104 Fire Zone Ground Floor Plan EL 354 40

71111.05 Drawings FP-2105, Sheet 1 Fire Zone Plan Below Grade EL 335-0 29

71111.05 Drawings FP-2112 Fire Zone Post Accident Sampling Facilities 8

71111.05 Miscellaneous Unit 2 Prefire Plans 17

71111.05 Miscellaneous Fire Hazards Analysis Arkansas Nuclear One - Unit 1 and 20

Unit 2

71111.05 Miscellaneous Unit 1 Prefire Plans 21

71111.05 Procedures EN-DC-161 Control of Combustibles 24

71111.08P Calculations CALC-20-E-0001- EVALUATION OF 14-INCH SERVICE WATER PIPE WALL 0

THINNING, LINE HBD-14-14, MIC LOCATION 9

71111.08P Calculations CALC-88-E-0100- Calculation for Unit 1 Intermediate Cooling Water 1

71111.08P Calculations CALC-ANO1-EP- ANO-1 Steam Generator Secondary Side Integrity Plan 3

71111.08P Corrective Action CR-ANO- 1-2004-01230, 1-2008-02183, 1-2016-03851, 1-2018-01775,

Documents 1-2019-03062, 1-2021-00871, 1-2021-01090, 1-2021-01135,

1-2021-01456, 1-2021-01767, 1-2021-01768, 1-2021-01769,

1-2021-01770

71111.08P Corrective Action CR-ANO- 1-2021-00704, 1-2021-00705, 1-2021-00708, 1-2021-00883,

Inspection Type Designation Description or Title Revision or

Procedure Date

Documents 1-2021-01031, 1-2021-01201, 1-2021-01263, 1-2021-01370,

Resulting from 1-2021-01468, 2-2021-00754

Inspection

71111.08P Miscellaneous R29 Reactor Vessel Head lnspection-BARK1 3

71111.08P Miscellaneous BARK1 Reactor Vessel Head lnspection Plan 3

71111.08P Miscellaneous WDI-PJF-344403- Examination Program Plan for the Arkansas Nuclear One 1

EPP-001 Unit 1

71111.08P Miscellaneous WDI-PJF-344403- Examination Program Plan for the Arkansas Nuclear One 29

EPP-001 Unit 1

71111.08P Procedures CEP-BAC-001 Boric Acid Corrosion Control (BACC) Program Plan 2

71111.08P Procedures CEP-CII- Visual Examinations of Class MC Components 308

003_308-1

71111.08P Procedures CEP-NDE-0121 Reactor Vessel Upper Head (RVUH) Nozzle Penetration 1

Non-Visual Examination Guidelines

71111.08P Procedures CEP-NDE-0400 Ultrasonic Examination 8

71111.08P Procedures CEP-NDE-0407 Straight Beam Ultrasonic Examination of Bolts and Studs 8

(ASME XI)

71111.08P Procedures CEP-NDE-0423 Manual Ultrasonic Examination of Austenitic Piping Welds 9

(ASME XI)

71111.08P Procedures CEP-NDE-0901 VT-1 Examination 6

71111.08P Procedures CEP-NDE-0902 VT-2 Examination 9

71111.08P Procedures CEP-NDE-0903 VT-3 Examination 6

71111.08P Procedures CEP-NDE-0955 Visual Examination (VE) of Bare-Metal Surfaces 308

71111.08P Procedures CEP-WP-GWS-1 General Welding Standard ASME/ANSI 5

71111.08P Procedures EN-DC-319 Boric Acid Corrosion Control (BACC) Program 12

71111.08P Procedures SEP-ISI-ANO1- Program Section For ASME Section XI, Division 1 ANO 1 8

101 Inservice Inspection Program

71111.08P Work Orders WO-ANO- 301122, 528933, 51511812, 52668905, 52914122

71111.11Q Corrective Action CR-ANO- C-2021-01182

Documents

71111.11Q Miscellaneous ORAT Outage Risk Assessment Team Report 03/29/2021

71111.11Q Miscellaneous SES-2-034 Unit 2 Dynamic Exam Scenario 7

71111.11Q Miscellaneous SES-2-063 Unit 2 Dynamic Exam Scenario 2

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.11Q Procedures OP-1102.010 Plant Shutdown and Cooldown 86

71111.11Q Procedures OP-1104.004 Decay Heat Removal Operating Procedure 133

71111.12 Corrective Action CR-ANO- 1-2021-00490, 1-2021-00491, C-2019-00471, HQN-2015-

Documents 01089

71111.12 Miscellaneous CPG-001 Procedure Writers Guide 2

71111.12 Miscellaneous EPRI 1003089 Maintenance of General Electric Magne-Blast M26 and M36 10/2001

Switchgear

71111.12 Miscellaneous IPH1250/175DJ- Installation and Operation Manual: High Performance 11/2014

TCL Industrial Pumping Module

71111.12 Miscellaneous OMRG36864 Operators Manual 9.0L OEM Diesel Engines 03/07/2013

71111.12 Miscellaneous TDG971 0010 FLEX Portable Diesel Generator 0

71111.12 Procedures OP-1416.001 Unit 1 A1 Bus Switchgear Inspection 20

71111.12 Procedures OP-1416.002 Unit 1 A2 Bus Switchgear Inspection 21

71111.12 Procedures OP-1416.004 Unit 1 A4 Bus Switchgear Inspection 18

71111.12 Procedures OP-1416.008 Unit 1 A3 Bus Switchgear Inspection 17

71111.12 Work Orders WO 52827304

71111.13 Corrective Action CR-ANO- 1-2021-00537, C-2021-01252

Documents

71111.13 Miscellaneous ANO Unit1 Operator Logs 04/29/2021

71111.13 Miscellaneous Outage Risk Assessment Team Review Comments 03/16/2021

71111.13 Miscellaneous ANO Unit 1 Outage Schedule 1

71111.13 Procedures 1015.048 Shutdown Operations Protection Plan 30

71111.13 Procedures EN-OU-108 Shutdown Safety Management Program (SSMP) 10

71111.15 Calculations CALC-21-E-0003- T-3 BWST Tank 1R29 NDE Review and Boric Acid 05/02/2021

Corrosion rate

71111.15 Calculations CALC-85-EQ-

0003-021

71111.15 Corrective Action CR-ANO- 1-2019-03062, 1-2021-00621, 1-2021-00641, 1-2021-01039,

Documents 1-2021-01090, 1-2021-01105, 1-2021-01106, 1-2021-01141,

1-2021-01150, 1-2021-01370, 2-2021-00739, C-2021-

01467, C-2021-01499, C-2021-01673

71111.15 Drawings M-206, Sheet 1 Steam Generator Secondary System 133

71111.15 Miscellaneous Arkansas Nuclear One Emergency Plan 46

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.15 Miscellaneous Unit 1 Narrative Log 06/01/2021

71111.15 Miscellaneous Unit 1 Shift Relief Sheet 04/01/2021

71111.15 Miscellaneous EC 89930 Engineering Review of NDE Prepared On T-3 05/02/2021

71111.15 Miscellaneous EC-83616 Unit 1 Online Rosemount EQ Transmitter Replacement 06/2020

71111.15 Procedures 1903.011 Emergency Response/Notifications 60

71111.15 Procedures 1904.002 Offsite Dose Projections 50

71111.15 Procedures EN-MA-107 Post-Maintenance Testing

71111.15 Procedures EN-OP-104 Operability Determination Process 16

71111.15 Procedures OP-1304.185 Unit 1 Green Channel High Pressure Injection Flow Inst Cal 11

71111.15 Procedures OP-1304.188 Unit 1 Red Channel High Pressure Injection Flow Inst Cal 10

71111.15 Work Orders WO 560988, 561566, 50235828, 52886069, 52914122

71111.18 Corrective Action CR-ANO- 1-2021-00679, 1-2021-00798, 1-2021-00892, 1-2021-01076,

Documents 1-2021-01118, 1-2021-01156, 1-2021-01283, 1-2021-01284,

1-2021-01340, 1-2021-01378, 1-2021-01386, 1-2021-01634,

1-2021-01647, 1-2021-01800, 1-2021-01818

71111.18

71111.18 Miscellaneous 12476506 Failure Mode Analysis for CR-ANO-1-2021-01818 0

71111.18 Miscellaneous EC-83454 Replace Unit 1 EDG Room Ventilation Fans (VEF- 0

24A/B/C/D) With New Fans

71111.18 Miscellaneous EC-85435 Replace Unit 1 EDG Room Ventilation Fan VEF-24A 0

71111.18 Miscellaneous FCR-89796 Field Change Request to Update TDC747 0030 Which 0

Incorrectly Identifies the Direction of Rotation as CCW

Installation, Operation, Maintenance and Handling

71111.18 Miscellaneous PAD for EC- 50.59 Screening for ANO EDG Replacement Fans 0

83454

71111.18 Miscellaneous TDC747 0030 Instructions for Curtiss Wright EDG Exhaust Fans 0

71111.18 Procedures OP-6030.210 Electrical Scheme Testing 4

71111.18 Procedures OP-6030.211 Motor Run Test

71111.18 Work Orders WO 527996, 527997, 527998, 527999, 562254, 552799

71111.19 Corrective Action CR-ANO- 1-2021-01523, 1-2021-01678

Documents

71111.19 Procedures 1104.032 Fire Protection Systems 94

71111.19 Procedures OP-1104.029 Service Water and Aux Cooling System Attachment C 122

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.19 Procedures OP-1306.027 Unit 1 K-5 Diesel Fire Pump Engine Surveillance Inspection 30

71111.19 Work Orders WO 488847, 527996, 527997, 527998, 527999

71111.20 Corrective Action CR-ANO- 1-2017-00198, 1-2021-02078, C-2021-01252

Documents

71111.20 Procedures 1015.036 Containment Building Closeout 59

71111.20 Procedures 1015.048 Shutdown Operations Protection Plan 30

71111.20 Procedures 1102.002 Plant Startup 115

71111.20 Procedures 1102.008 Approach to Criticality 34

71111.20 Procedures 1102.010 Plant Shutdown and Cooldown 87

71111.20 Procedures 1102.016 Power Reduction and Plant Shutdown 37

71111.20 Procedures EN-OM-123 Fatigue Management Program 18

71111.20 Procedures EN-OU-108 Shutdown Safety Management Program 10

71111.20 Procedures EN-RE-327 PWR Startup Critical Predictions and Evaluation Process 6

71111.22 Corrective Action CR-ANO- 1-2019-02484, 1-2020-00202, 1-2021-00677, 1-2021-00697,

Documents 1-2021-01780, 1-2021-01951, 2-2008-01469, 2-2009-03483,

2-2020-02492

71111.22 Drawings M-213 Laundry Waste and Containment and Aux. Building Sump 33

Drainage

71111.22 Miscellaneous CALC-ANO1-NE- ANO-1 Cycle 30 BMAC Summary Report 1

21-00005

71111.22 Procedures OP-1042.003 Radiochemistry Routine Surveillance Schedule and 43

Technical Specification Reporting

71111.22 Procedures OP-1104.036 Emergency Diesel Generator Operation 86

71111.22 Procedures OP-1302.005 Core Power Distribution for Physics Testing 23

71111.22 Procedures OP-1302.012 Periodic Core Power Distribution Testing 23

71111.22 Procedures OP-1305.018 Local Leak Rate Testing - Type C 37

71111.22 Procedures OP-1305.040 Service Water Full Flow Testing 4

71111.22 Procedures OP-1306.017 Unit 1 Main Steam Safety Valve Test 30

71111.22 Procedures OP-1607.001 Reactor Coolant System Sampling 4

71111.22 Procedures OP-2302.009 Moderator Temperature Coefficient at Power 32

71111.22 Work Orders WO 494948-04, 52901710-01, 52901711-01, 52901712-01,

2901831-01, 52902401-01, 52902483, 52931737-01

71124.01 Corrective Action CR-ANO- 1-2020-00776, 1-2020-00818, 1-2020-01134, 1-2021-00083,

Inspection Type Designation Description or Title Revision or

Procedure Date

Documents 1-2021-00095, 1-2021-00832, 1-2021-01151, 2-2020-01509,

2-2020-01511, 2-2020-01714, 2-2020-02481, 2-2020-02917,

2-2021-00627, C-2020-01365, C-2020-01882, C-2020-

267, C-2021-00935, C-2021-00937, C-2021-01139

71124.01 Miscellaneous ANO-2020-0035 Annual Inventory of the Miscellaneous Material in the ANO 08/18/2020

Spent Fuel Pools (SFPs)

71124.01 Procedures EN-RE-220 Control of Non-Fuel Materials 5

71124.01 Procedures EN-RP-100 Radiation Worker Expectations 13

71124.01 Procedures EN-RP-101 Access Control for Radiologically Controlled Areas 15

71124.01 Procedures EN-RP-102 Radiological Control 7

71124.01 Procedures EN-RP-106-1 Radiological Survey Guidelines 6

71124.01 Procedures EN-RP-108 Radiation Protection Posting 22

71124.01 Procedures EN-RP-121 Radioactive Material Control 17

71124.01 Procedures EN-RP-152 Conduct of Radiation Protection 6

71124.01 Radiation Air Samples 012821-0043, 041921-0242, 042021-0247, 042021-0248,

Surveys (ANO-AS-) 042021-0249, 042021-0250, 043020-0369

71124.01 Radiation ANO- 20-01-00178, 20-07-00342, 21-04-00202, 21-04-00225, 21-

Surveys 04-00226, 21-04-00228, 21-04-00786, 21-04-00826, 21-04-

00829, 21-04-00831, 21-04-00833, 21-04-00837, 21-04-

00856, 21-04-00865, 21-04-00868, 21-04-00870, 21-04-

00871, 21-04-00892, 21-04-00971

71124.01 Radiation Work 2020-2471 Perform Inspections on Unit 2 Reactor Head During 2R27 0

Permits (RWPs)

71124.01 Radiation Work 2020-2900 Emergent Minor Maintenance Activities During 2R27 2

Permits (RWPs)

71124.01 Radiation Work 2021-1054 Unit-1 Transfer Spent Resin to T-13 or 2T-13 Spent Resin 0

Permits (RWPs) Storage Tanks; to Include T-13 to Train Bay Activities

71124.01 Radiation Work 2021-1406 1R29 Radwaste Processing and Shipping 0

Permits (RWPs)

71124.01 Radiation Work 2021-1442 1R29 Steam Generator (SG) Primary Side Eddy Current 0

Permits (RWPs) Inspection and Repair Activities

71124.01 Radiation Work 2021-1454 1R29 Motor Operated Valves (MOV) and Air Operated 0

Permits (RWPs) Valves (AOV) Activities

71124.01 Radiation Work 2021-1471 1R29 Reactor Pressure Vessel Closure Head - Volumetric 0

Inspection Type Designation Description or Title Revision or

Procedure Date

Permits (RWPs) and Surface Exams

71124.01 Self-Assessments LO-ALO-2020- Radiation Safety - Hazard Assessment, Airborne Controls, 12/09/2020

00048 and Performance Indicators

71124.03 Calibration WO 52820087 Unit 1 RCS Radiation Leak Detection System 18 Month 12/12/2019

Records Calibration

71124.03 Calibration WO 52878423 Calibration of Fuel Handling Area 2RX-9830 (SPING 7) 04/01/2021

Records

71124.03 Corrective Action CR-ANO- 1-2019-04739, 2-2020-00573, C-2019-04031, C-2019-

Documents 04065, C-2019-04193, C-2020-01357, C-2020-01366

71124.03 Corrective Action CR-HQN- 2019-02415

Documents

71124.03 Miscellaneous TRI Air Testing Laboratory Report - Compressed Air/Gas

Quality Testing: Eagle Air (C-82A) on 08/01/2019;

01/28/2020; 07/28/2020; 01/27/2021; and 02/26/2021

71124.03 Miscellaneous TRI Air Testing Laboratory Report - Compressed Air/Gas

Quality Testing: BAUER (C-82C) on 01/28/2020;

07/28/2020; 01/28/2021

71124.03 Miscellaneous TRI Air Testing Laboratory Report - Compressed Air/Gas

Quality Testing: Unit 2 Breathing Air Compressor (2BA-

1009) on 10/21/2019 and 03/12/2020

71124.03 Miscellaneous Air Sample and Results Log from 03/27/2020 through

04/05/2021

71124.03 Miscellaneous 1601.406 Attachment 6.5 Breathing Air Analysis Sample Sheet - Dive

Compressor on: 11/06/2019; 02/25/2020; 03/15/2020;

06/01/2020; and 10/27/2020

71124.03 Miscellaneous 1601.406 Attachment 6.5 Breathing Air Analysis Sample Sheet - C-

2C (Burn Building) on: 11/08/2019; 12/26/2019;

01/16/2020; 03/28/2020; 04/30/2020; 05/21/2020;

06/04/2020; 08/13/2020; 09/22/2020; 10/27/2020; and

11/09/2020

71124.03 Miscellaneous 1601.406 Attachment 6.5 Breathing Air Analysis Sample Sheet - C-

2A (Warehouse 2) on: 12/26/2019; 02/11/2020; and

08/11/2020

71124.03 Miscellaneous 1601.406 Attachment 6.5 Breathing Air Analysis Sample Sheets -

Inspection Type Designation Description or Title Revision or

Procedure Date

Inline Air: (2BA-1009) 03/09/2020; (1IA-191) 03/16/2020;

and (2IA-1090) 03/04/2020

71124.03 Miscellaneous EN-RP-502 Inspection and Maintenance of Respiratory Protection

Equipment, Attachment 9.1, Face Piece Inspection Log from

11/29/2019 through 12/01/2020

71124.03 Miscellaneous EN-RP-502, Annual Respiratory Protection Equipment Inventory and 11/30/2020

9.5 Inspection

71124.03 Procedures 1001.008 Surveillance Frequency Control Program 4

71124.03 Procedures 1601.406 Setup and Operation of Breathing Air Sampling Kits 2

71124.03 Procedures EN-RP-131 Air Sampling 17

71124.03 Procedures EN-RP-402 DOP Challenge Testing of HEPA Vacuums and Portable 4

Ventilation Units

71124.03 Procedures EN-RP-404 Operation and Maintenance of HEPA Vacuum Cleaners and 9

HEPA Ventilation Units

71124.03 Procedures EN-RP-501 Respiratory Protection Program 7

71124.03 Procedures EN-RP-502 Inspection and Maintenance of Respiratory Protection 10

Equipment

71124.03 Procedures EN-RP-503 Selection, Issue and Use of Respiratory Protection 8

Equipment

71124.03 Procedures EN-RP-504 Breathing Air 4

71124.03 Self-Assessments LO-ALO-2020- Radiation Safety - Hazard Assessment, Airborne Controls 12/09/2020

00048 and Performance Indicators

71124.03 Work Orders WO 52762359 In-Place Testing of the Emergency Operations Facility 11/30/2018

Filtration System

71124.03 Work Orders WO 52785908 In-Place Testing of the Unit 1 Control Room Filtration 04/22/2019

System

71124.03 Work Orders WO 52855304 In-Place Testing of the Emergency Operations Facility 02/05/2020

Filtration System

71124.03 Work Orders WO 52873446 In-Place Testing of the Unit 1 Control Room Filtration 08/24/2020

System

71151 Calibration AMS-025 Calibration Data Ebeline Model AMS-4 Beta 10/08/2020

Records Particulate/Noble Gas Monitors

71151 Calibration AMS-031 Calibration Data Ebeline Model AMS-4 Beta 06/05/2019

Records Particulate/Noble Gas Monitors

Inspection Type Designation Description or Title Revision or

Procedure Date

71151 Calibration AMS-044 Calibration Data Ebeline Model AMS-4 Beta 10/08/2020

Records Particulate/Noble Gas Monitors

71151 Calibration AMS-045 Calibration Data Ebeline Model AMS-4 Beta 05/20/2020

Records Particulate/Noble Gas Monitors

71151 Miscellaneous Radiological Controlled Area Entries Greater than 100 03/22/2021

millirem Report: 03/26/20 - 01/28/2021

71151 Miscellaneous ANO-1 and ANO-2 NRC Performance Indicator Q2-2020

Technique/Data Sheets - RCS Leakage

71151 Miscellaneous ANO-1 and ANO-2 NRC Performance Indicator Q3-2020

Technique/Data Sheets - RCS Leakage

71151 Miscellaneous ANO-1 and ANO-2 NRC Performance Indicator Q4-2020

Technique/Data Sheets - RCS Leakage

71151 Miscellaneous ANO-1 and ANO-2 NRC Performance Indicator Q1-2021

Technique/Data Sheets - RCS Leakage

71151 Miscellaneous ANO-1 and ANO-2 NRC Performance Indicator Q2-2020

Technique/Data Sheets - RCS Specific Activity

71151 Miscellaneous ANO-1 and ANO-2 NRC Performance Indicator Q3-2020

Technique/Data Sheets - RCS Specific Activity

71151 Miscellaneous ANO-1 and ANO-2 NRC Performance Indicator Q4-2020

Technique/Data Sheets - RCS Specific Activity

71151 Miscellaneous ANO-1 and ANO-2 NRC Performance Indicator Q1-2021

Technique/Data Sheets - RCS Specific Activity

71151 Miscellaneous ANO-1 and ANO-2 NRC Performance Indicator Q2-2020

Technique/Data Sheets - SSFF

71151 Miscellaneous ANO-1 and ANO-2 NRC Performance Indicator Q3-2020

Technique/Data Sheets - SSFF

71151 Miscellaneous ANO-1 and ANO-2 NRC Performance Indicator Q4-2020

Technique/Data Sheets - SSFF

71151 Miscellaneous ANO-1 and ANO-2 NRC Performance Indicator Q1-2021

Technique/Data Sheets - SSFF

71151 Miscellaneous 0CAN042102 2020 Annual Radioactive Effluent Release Report 04/21/2021

71151 Procedures EN-LI-114 Regulatory Performance Indicator Process 17

71151 Procedures OP-1042.003 Radiochemistry Routine Surveillance Schedule and Tech 43

Spec Reporting

Inspection Type Designation Description or Title Revision or

Procedure Date

71153 Corrective Action CR-ANO- 1-2021-00457, 2-2017-02384

Documents

71153 Procedures EN-LI-108 Causal Analysis Process 34

Arkansas Nuclear One, Unit 1

Momentary Loss of Power to 4160 Vac bus A2 Event

Detailed Risk Evaluation

A regional senior reactor analyst performed a detailed risk evaluation and determined that the

finding associated with the momentary loss of power to 4160 Vac bus A2 event was of very low

safety significance (Green).

The analyst performed an initiating event analysis as called for in Section 8.0, Initiating Event

Analyses, of Volume 1, Internal Events, of the RASP Handbook. The analyst chose to run

this analysis as a transient (or reactor trip) with circuit breaker 1A-409 failed open (basic

event ACP-CRB-CO-1A409 set to TRUE). During the event, power was lost to bus A2, the

reactor was manually tripped, and power to bus A2 was subsequently restored within 1 minute.

When power was lost to bus A2, breaker 1A-409 (which supplies offsite power to bus A4)

opened and was not reclosed during the initial phases of the event. The resulting conditional

core damage probability was estimated to be 3.50E-7. This estimate equated to an increase in

core damage frequency from internal events of 3.5E-7/year.

The analyst assumed that external events would be an insignificant contributor to the increase

in core damage frequency because the probability of any external event coinciding with the

momentary loss of power to bus A2 event would be extremely low. As a result, only the

increase in core damage frequency from the initiating event was used in the final estimate,

making the total safety significance of the finding very low (Green).

After reviewing Manual Chapter 0609, Appendix H, Containment Integrity Significance

Determination Process, the analyst determined that transient sequences were not significant

contributors to large early release frequency and screened the finding to Green for large early

release frequency.

The analyst ran the Arkansas Nuclear One, Unit 1, SPAR model, Revision 8.60, on SAPHIRE,

Version 8.2.1, to calculate the conditional core damage probability using a cutset truncation of

1.0E-12.

Attachment