IR 05000313/2021013

From kanterella
Jump to navigation Jump to search
License Renewal Phase 4 Inspection Report 05000313/2021013
ML22130A693
Person / Time
Site: Arkansas Nuclear 
Issue date: 05/17/2022
From: Nick Taylor
NRC/RGN-IV/DORS/EB2
To: Sullivan J
Entergy Operations
References
IR 2021013
Download: ML22130A693 (28)


Text

May 17, 2022

SUBJECT:

ARKANSAS NUCLEAR ONE - NRC UNIT 1 LICENSE RENEWAL PHASE 4 INSPECTION REPORT 05000313/2021013

Dear Mr. Sullivan:

On April 11, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Arkansas Nuclear One and discussed the results of this inspection with Mr. Grant Flynn, Acting Site Vice President, and other members of your staff. The results of this inspection are documented in the enclosed report.

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

If you contest the violation or the significance or severity of the violation documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN:

Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region 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, Nicholas H. Taylor, Chief Engineering Branch 2 Division of Operating Reactor Safety Docket No. 05000313 License No. DPR-51

Enclosure:

As stated

Inspection Report

Docket Number:

05000313

License Number:

DPR-51

Report Number:

05000313/2021013

Enterprise Identifier:

I-2021-013-0014

Licensee:

Entergy Operations, Inc

Facility:

Arkansas Nuclear One

Location:

Russellville, Arkansas

Inspection Dates:

January 23 to April 11, 2022

Inspectors:

G. Pick, Senior Reactor Inspector, Team Lead

J. Drake, Senior Reactor Inspector

J. Lee, Reactor Inspector

Accompanying

M. Chisolm, Reactor Inspector

Personnel

J. Mejia, Reactor Inspector

Approved By:

Nicholas H. Taylor, Chief

Engineering Branch 2

Division of Operating Reactor Safety

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a NRC 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 maintain in-scope medium voltage cables dry Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV NCV 05000313/2021013-01 Open/Closed

[H.14] -

Conservative Bias 71003 The team identified a Green noncited violation of License Condition 2.c.3 and regulatory requirements because the licensee failed to effectively implement aging management activities. Specifically, the licensee failed to keep inaccessible non-environmentally qualified medium voltage cables dry.

Additional Tracking Items

Type Issue Number Title Report Section Status URI 05000313/2021013-02 Condition of Emergency Cooling Pond Buried Piping 71003 Open

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 team 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.

OTHER ACTIVITIES

- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL

71003 - Post-Approval Site Inspection for License Renewal Post-Approval Site Inspection for License Renewal

(1)71003 Phase 4 Inspection Activities NRC conducted this Phase 4 Inspection 8 years after the licensee entered the period of extended operation for Unit 1. The inspection confirmed that the licensee continued to meet their commitments, processed any commitment changes in accordance with their commitment management procedure, and evaluated implementation of aging management activities. The period of extended operation included the additional 20 years beyond the original 40-year licensed term. Arkansas Nuclear One, Unit 1, began the period of extended operation after midnight on May 20, 2014. The team determined that the licensee had not processed any commitment changes that impacted the programs selected for detailed review.

As part of the license extension, licensees placed a description of their aging management programs in an Updated Final Safety Analysis Report (UFSAR)supplement. Arkansas Nuclear One, Unit 1 included their aging management program descriptions and commitments in Chapter 16. The licensee developed program implementing procedures or modified existing program procedures that described implementation of their aging management activities.

The team performed detailed reviews of the aging management programs listed in Table 1, Detailed Program Evaluations. The team reviewed license renewal program assessments, commitment changes, engineering evaluations, procedures, program documents, completed tests, completed maintenance activities, nondestructive examination reports, technical reports, correspondence, and drawings. The team did not identify any concerns with the aging management activities for the programs listed in Table 1:

Table 1 Detailed Program Evaluations UFSAR Section Description 16.1.5 Reactor Vessel Internals 16.1.7 Wall Thinning Inspections 16.2.3.6 IWL (Tendon Inspections)16.2.9 Flow Accelerated Corrosion 16.2.13 Structures Monitoring The team reviewed recently completed implementing activities related to the aging management programs listed in Table 2, Verification of Implementing Activities. The team reviewed correspondence, completed surveillance tests, implementing procedures, completed maintenance activities, and engineering evaluations. The team did not identify any concerns with the aging management activities for the programs listed in Table 2.

Table 2 Verification of Implementing Activities UFSAR Section Description 16.1.3 Heat Exchanger Monitoring 16.2.2 Alternate AC Diesel Generator Testing and Inspection 16.2.10 Inspection and Preventive Maintenance of the Polar Crane 16.2.11 Instrument Air Quality 16.2.14 Oil Analysis 16.2.16 Reactor Building Leak Rate Testing 16.2.17 Reactor Building Sump Closeout 16.2.18 Reactor Vessel Integrity 16.2.21.1 Annual Emergency Cooling Pond Sounding 16.2.21.3 Control Room Ventilation Testing 16.2.21.5 Emergency Diesel Generator Testing and Inspections During review of implementing activities related to managing the aging effects for the aging management programs listed in Table 3, Detailed Program Evaluations with Comments, the team identified insights into licensee performance that are discussed in detail in the results section of this report.

Table 3 Detailed Program Evaluations with Comments UFSAR Section Description 16.1.1 Buried Piping 16.1.2 Electrical Components Inspection

Sensitive Instrumentation Circuits

Inaccessible Non-Environmentally Qualified Medium Voltage Cables

Metal Enclosed Buses 16.2.6.5 Service Water Chemistry Control 16.2.8.

Fire Suppression Sprinkler Surveillance 16.2.19 Service Water Integrity Selective Leaching 16.1.1 Buried Piping This program applied to both Unit 1 and Unit 2 and included the buried piping for the fire water and service water systems. The buried service water piping included the return piping from the plant to the emergency cooling pond and the supply piping from the emergency cooling pond to the intake structure. The emergency cooling pond provided the ultimate heat sink supply in the event of a loss of Lake Dardanelle.

From interviews and a review of Procedure SEP-UIP-ANO, Underground Components Inspection Plan Non-Rad and Rad Piping, Revision 7, the team determined that the licensee had completed an evaluation of a buried pipe section prior to entering the period of extended operation on the Unit 1 emergency cooling water return line (1HBD-13-18). The program required the licensee to inspect for external corrosion any time maintenance activities provided an opportunity. The licensee used the guidelines in NEI 09-14, Guideline for the Management of Buried Piping Integrity, Revision 4, for implementing a risk-informed buried piping program. Procedure EN-DC-343, Underground Piping and Tanks Inspection and Monitoring Program, Revision 13, implemented the buried pipe program high level requirements, including those for license renewal. The program monitored for external corrosion and coordinated with the microbiologically influenced and flow-accelerated corrosion programs that monitor and evaluate internal corrosion.

Procedure CEP-UPT-0100, Underground Piping and Tanks Inspection and Monitoring, Revision 6, contained additional implementing guidance related Procedure EN-DC-343. The procedure

(1) described the component identification and sampling methodology, inspection methodologies, leak detection and monitoring, preventive actions, repair strategies, and mitigation strategies;
(2) recommended grouping components and specified at least one direct examination for each high-risk piping group; and
(3) established guidelines for risk ranking each component based on both an impact assessment and corrosion risk assessment.

The team identified the following observations and potential performance deficiencies, which are described more fully in the Results section of this report:

unresolved item related to the aging management of the internal and external emergency cooling pond piping

observation related to the condition of the cathodic protection system 16.1.2 Electrical Components Aging Management Programs The team reviewed three areas related to aging management of electrical components: sensitive instrumentation circuits, inaccessible nonenvironmentally qualified medium voltage (medium voltage) cables, and metal-enclosed bus ducts, as described below.

Sensitive Instrumentation Circuits Review Procedure EN-FAP-LR-027, License Renewal Sensitive Instrumentation Circuits Review AMP, Revision 3, described the requirements for managing the effects of aging for high voltage, low signal level (5 - 1000 nanoamperes) instrumentation cables. The sensitive instrumentation circuits included the reactor protection system and emergency feedwater initiation circuits. The team confirmed that the licensee had evaluated their circuits prior to entering the period of extended operation.

While questioning whether the licensee had scheduled the required 10-year review, the team identified that personnel were not familiar with the requirement to perform the review. Consequently, the team questioned whether a preventive maintenance task existed to ensure completion of the task.

Since Unit 1 had been in the period of extended operation for 8 years, the team concluded that, although the licensee had not missed performing this task, personnel had a high likelihood of failing to perform this this aging management activity. The team noted that the engineers reviewed the completed calibration results for sensitive instrumentation circuits following each 18-month calibration looking for circuit anomalies. Personnel have sufficient time to complete the evaluation over the next 2 years. In response to this observation, the licensee wrote Condition Report 1-2022-00136. In addition, the team determined that the licensee had established Recurring Commitment R-19368 related to performing the 10-year review. The team determined that this may have identified an action in May 2022 to verify that the licensee had implemented actions to complete the aging management review of sensitive instrumentation circuits.

Nonenvironmentally Qualified Inaccessible Medium Voltage Cable Program Procedure EN-DC-346, Cable Reliability Program, Revision 8, prescribed the requirements for implementing the program in response to both maintenance rule and license renewal requirements. The licensee included cables related to powering safety -related pumps and cables that support offsite power supply that would be lost in the event of a station blackout. For the cables included because of license renewal, the licensee had installed sump pumps prior to entering the period of extended operation. Engineering Evaluation CALC-ANO1-EE-13-00005, Non-Environmentally Qualified Inaccessible Medium-Voltage Cable and Manhole Review, Revision 0, provided the basis for the licensee-specific program and included the results of the initial tan-delta test results.

Overall, the team determined that the licensee had implemented an aging management program that prescribed appropriate activities for monitoring the effects of aging. The licensee installed sump pumps to keep in-scope cables dry with one exception. The program requires the licensee to maintain the cables dry to prevent degradation of the cables caused by a wet environment. The licensee established a cable program engineer to monitor and evaluate work activities. The licensee performed tan-delta and withstand testing every 6 years as committed, which exceeded the 10-year recommended frequency. However, the team describes in detail in the Results section a Green non-cited violation for the failure to maintain the 22kV cables from the startup transformer to the voltage regulator dry.

Metal-Enclosed Bus Maintenance The team determined that the licensee had processed industry operating experience related to managing the effects of aging of their metal-enclosed busses, as required.

However, because of their license basis, the licensee was not required to formally establish an aging management program for metal-enclosed busses.

Engineering Evaluation CALC-ANO1-EE-11-00001, ANO-1 Screening and Aging Management Review of Electrical Components for RIS 2007-016, Revision 0 processed the industry operating experience associated with electrical components as described in Regulatory Information Summary 2007-016, Implementation of the Requirements of 10 CFR 54.37(b) for Holders of Renewed Licenses, Revision 1.

Engineering Evaluation CALC-ANO1-EE-11-00001 performed aging management reviews of the passive, long-lived components that supported the nonsegregated metal-enclosed-buses.

The team determined that the licensees aging management review confirmed several passive long-lived components that required aging management. However, the licensee did not establish a formal aging management program for metal-enclosed busses. The licensee performed maintenance on a 10-year frequency on the nonsegregated metal-enclosed bus ducts. The team reviewed the completed maintenance activities and compared the maintenance against the requirements listed in NUREG-1801, Generic Aging Lessons Learned (GALL) Report, Revision 2. The team identified no issues with the maintenance performed.

16.2.8.4 Fire Suppression Sprinkler Surveillance The team confirmed that NRC baseline inspections reviewed fire protection activities credited for managing the effects of aging. These activities included fire barrier inspections, halon system inspections, fire water system surveillances, and fire sprinkler system surveillances. The licensee elected to change out their sprinkler heads at 50 years as specified in the National Fire Protection Association code. The team reviewed the controls established for replacing the sprinkler heads by review of several work orders.

As a result of reviewing the completed work orders before providing them to the team, the licensee identified discrepancies because the number of sprinkler heads listed on the drawing and listed in the work orders differed from the number of sprinkler heads installed. The licensee documented this deficiency in Condition Report ANO-1-2022-00025. The team verified that the licensee had installed like-for-like sprinkler heads based on temperature and type (pendant or upright). The team identified that the deficiencies resulted in a minor violation and that the licensee initiated corrective actions to reinforce expectations related to stopping work to get work packages corrected.

Selective Leaching The team evaluated the selective leaching program to confirm that the licensee had implemented the required actions to evaluate for the presence of selective leaching in their buried piping systems. The team could not evaluate implementation because the licensee had not completed any aging management review activities related to selective leaching. The licensee had developed a program as described in LR-LAR-2015-00081, Corrective Action 5 and as described in Inspection Report 05000313/2015009. The licensee had identified the systems that would be subject to selective leaching and the population of components that could be sampled. The Unit 2 systems that would be representative of Unit 1 included fire water, service water, and emergency feedwater. A self-assessment, performed to prepare for the inspection, identified that no actions had been taken to ensure that the program activities would be implemented.

The licensee wrote Condition Report ANO-C-2021-2622 to track the corrective actions needed to address this deficiency and implement their selective leaching program. The team determined that the licensee had 6 years remaining until the end of the first 10-year period for Unit

INSPECTION RESULTS

Failure to maintain in-scope medium voltage cables dry Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000313/2021013-01 Open

[H.14] -

Conservative Bias 71003 The team identified a Green noncited violation of License Condition 2.c.3 and regulatory requirements because the licensee failed to effectively implement aging management activities. Specifically, the licensee failed to keep inaccessible non-environmentally qualified medium voltage cables dry.

Description:

The team reviewed implementation of the non-environmentally qualified inaccessible medium voltage cable program. Procedure EN-DC-346, Cable Reliability Program, Revision 8, specified requirements to maintain cables dry. The licensee had installed solar powered sump pumps in the manholes to maintain in-scope safety-related cables dry based on their original license renewal application. For all other manholes the licensee used the program option to periodically drain down the manholes.

Engineering Evaluation CALC-ANO1-EE-11-00001, ANO-1 Screening and Aging Management Review of Electrical Components for RIS 2007-016, dated February 16, 2011, identified that the licensee would include 22kV cables that ran from a switchyard voltage regulator to Startup Transformer #1 (X-03) through manholes 24 and 25. The licensee included these cables because they connected the first offsite breaker from the switchyard to the normal offsite power supply components. The team determined that that the licensee had not provided solar powered sump pumps for the manholes that included this in-scope cable.

The team determined that the licensee had not appropriately established manual inspections and pumping frequencies to maintain the cables dry. From review of surveillance trends associated with manholes MH-11, MH-13, MH-24, MH-25, MH-26, and MH1VR1, the team determined that the licensee pumped down the manholes each time they performed the monthly surveillance. The team confirmed that the licensee had brown ethylene propylene and red ethylene propylene cables installed for the 22kV circuits, which were not qualified to be continuously wet or submerged. The cables of interest were located on the floor of the manholes and continued to sit in 1 inch of water even when dewatered. The team determined that the licensee had replaced their cables in the mid-nineties. The red ethylene propylene cable jackets are manufactured to be more resistant to moisture intrusion. The cables are continuously energized. The last set of testing confirmed no degradation of the cable insulation.

Procedure EN-DC-346, Section 8.6 provides the requirements to perform manhole inspections in accordance with the preventive maintenance template and to prevent cable submergence, if possible, to increase the longevity of the insulation system. Step 8.6.2.a specifies, Install sump pumps wherever practical in manholes, vaults, and duct systems which contain Medium Voltage In-scope Cable List (MVICL) or Low Voltage In-scope Cable List (LVICL) cables that have the potential for submergence. The team determined that the licensee included safety related, nonsafety-related, maintenance rule scoped, and license renewal scoped cables. Step 8.6.2.b specifies, if manual inspections and pumping are used to maintain a cable system dry, then

(1) ensure the intervals are sufficient to keep the cables dry;
(2) adjust the intervals as necessary, based on inspection results; and
(3) if cable rewetting occurs, use the corrective action process for trending the occurrence and as found water levels; perform an evaluation of the submerged cable. The team confirmed that the same requirements existed since the beginning of the period of extended operation (i.e.,

Procedure EN-DC-346, Revision 6, step 5.6.2.b and Revision 7, Step 8.6.2.b).

Corrective Actions: The licensee placed the issue in their corrective action program to ensure that actions would be taken to stop water from entering the manholes or to install sump pumps.

Corrective Action References: Condition Report ANO-C-2022-00553

Performance Assessment:

Performance Deficiency: The team determined that the failure to implement the aging management requirements for the in-scope inaccessible medium voltage cables was a performance deficiency. Specifically, the licensee failed to maintain the cables dry.

Screening: The team determined the performance deficiency was more than minor because it was associated with the equipment performance 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 licensee could not assure that electrical cables designed to be dry or wetted would continue to function when called upon because they had been submerged.

Significance: The team assessed the significance of the finding using Inspection Manual Chapter 0609, Appendix A, The Significance Determination Process (SDP) for Findings At-Power. The team determined that the finding screened to green because the deficiency potentially affected the qualification of cables that facilitate power to the safety-related offsite power feed. The team consulted with the senior reactor analyst who confirmed that any risk associated with this deficiency would be dominated by the at-power conditions. Because the cables had been replaced with material more resistant to degradation caused by moisture, were continuously energized, and the last test performed confirmed the integrity of the cable insulation.

Cross-Cutting Aspect: H.14 - Conservative Bias: Individuals use decision-making practices that emphasize prudent choices over those that are simply allowable. A proposed action is determined to be safe to proceed, rather than unsafe in order to stop. Specifically, personnel with the knowledge that the cables continued to be continuously wet did not question or take action to meet the aging management program requirements.

Enforcement:

Violation: Operating License No. DPR-51, License Condition 2.c.(3) states, in part, that the safety analysis report supplement submitted pursuant to 10 CFR 54.21(d), as revised on March 14, 2001, describes certain future inspection activities to be completed before the period of extended operation. The licensee shall complete these activities no later than May 20, 2014.

Updated Final Safety Analysis Report Section 16.1.2, Electrical Component Inspection, states, in part, that the scope of the inspection program includes cables exposed to wet environments and that inaccessible medium-voltage cables exposed to significant moisture and voltage will either be tested for the presence of aging effects or a replacement program for these cables will be developed.

Procedure EN-DC-346, Cable Reliability Program, used to implement Updated Final Safety Analysis Report, Section 16.1.2, Revisions 6, 7, and 8, Steps 5.7[2](b), 8.6.2.b, and 8.6.2.b, respectively, require, in part, that if manual inspections and pumping are used to maintain a cable system dry, then ensure the intervals are sufficient to keep the cables dry and adjust the intervals as necessary based on inspection results. If cable rewetting occurs, use the corrective action process for trending the occurrence and as found water levels and perform an evaluation of the submerged cables.

Contrary to the above, from May 20, 2014, to April 11, 2022, for manual inspections and pumping used to maintain a cable system dry, the licensee failed to ensure the pumping intervals were sufficient to keep the cables dry and to adjust the intervals as necessary based on inspection results. Specifically, the licensee failed to ensure that electrical cables identified for aging management inspection activities were maintained dry as designed and specified in Procedure EN DC 346.

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

Unresolved Item (Open)

Condition of Emergency Cooling Pond Buried Piping URI 05000313/2021013-02 71003

Description:

During review of the buried emergency cooling pond service water piping, the team identified several programs that the licensee had identified as managing the effects of aging on both the exterior and interior of the piping. Procedure EN-DC-343, Buried Pipe Program, Revision 13, specified requirements to manage the effects of aging caused by exterior corrosion and specified that the program owner would coordinate with the flow-accelerated corrosion and microbiologically influenced corrosion program engineers when an opportunistic excavation occurred. Procedure CEP-UPT-0100, Underground Piping and Tanks Inspection and Monitoring, Revision 6, contained additional guidance related to implementing the buried piping program requirements. The team determined that Condition Report CR-C-2021-00987 documented that volumetric examinations to support a fitness for service evaluation required by Procedure EN-DC-343 had not been performed.

Similarly, Procedure EN-DC-184, NRC Generic Letter 89-13 Service Water Program, Revision 6, implemented requirements for managing the effects of aging on the interior surfaces of the safety-related service water piping. The licensee implemented the site-specific aspects of this program using Procedure SEP-SW-ANO-001, Arkansas Nuclear One (ANO)

NRC Generic Letter 89-13 Service Water Program, Revision 1. Procedure EN-DC-184 identified that nondestructive examination requirements are implemented by Procedure EN-DC-340, Microbiologically Influenced Corrosion (MIC)

Program. Procedure EN-DC-340 states that inadequately treated water sources, open-cycle, once through water sources, and long vertical runs are conducive to the occurrence of microbiologically influenced corrosion. Procedure SEP-MIC-ANO-001, Microbiological Influenced Corrosion (MIC) Program, utilizes risk ranking from other site programs such as buried piping and describes that it supplements the service water integrity program, including meeting license renewal commitments for the service water integrity program, and includes portions of the buried pipe program but monitors for internal pipe corrosion.

The team determined that the application of these procedures has not resulted in the ultimate objective of the procedures to manage the effects of aging of the interior and exterior of the emergency cooling pond buried service water piping to maintain structural and leakage integrity through the end of licensed operations of the facility.

Planned Closure Actions: During a follow-up inspection, NRC inspectors, with the assistance of program experts in buried piping and service water programs from the Office of Nuclear Reactor Regulation, will confirm the following items:

The licensing requirements related to the buried piping, service water, and microbiologically influenced corrosion programs

Whether the licensee has properly implemented the interface requirements among the buried piping, service water, and microbiologically influenced corrosion programs

Whether the licensee has implemented their required external and internal inspections and program requirements

Action plans for inspecting the buried emergency cooling pond supply and return lines

Plans for using carbon fiber reinforced polymer wrap, including interim actions to ensure health of the lines until installation of the repair Licensee Actions: The licensee documented operational data for the buried emergency cooling pond service water piping and documented operability determinations for the system CR-ANO-1-2021-02429, CR-ANO-2-2021-01204, and CR-ANO-C-2021-03142. Additional condition reports related to identified issues included: CR-ANO-C-2019-1633, CR-ANO-C-2021-00987, CR-ANO-C-2022-00804, CR-ANO-1-2022-00171, and CR-ANO-1-2022-00533. The team did not identify any current concerns with operability of the service water system.

Corrective Action References: Condition Report C-2022-00955

EXIT MEETINGS AND DEBRIEFS

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

On April 11, 2022, the team presented the NRC inspection results to Mr. Grant Flynn, Acting Site Vice President, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71003

Calculations

CALC-19-E-0013-02

Minimum Thickness Calculation for HBD-12-36,

HBD-14-18, HBD-20-18, 2 HBD-33-20,

HBC-34-20, 2HBC-83-30, 2HBC-88-42 Buried

Pipe

Calculations

CALC-ANO1-EP-20-00002

Fitness For Service - 1JBD-26-6"

Calculations

CALC-ANO2-EP-21-00001,

EC90989

Risk-informed Repair Replacement Activities

(RI-RRA) - ANO Unit 2 Service Water

Corrective Action

Documents

CR-ANO-1-

2005-00344, 2013-02793, 2015-04232,

2016-02835, 2016-03004, 2016-03262,

2016-03855, 2016-03856, 2016-03857,

2016-03858, 2016-03870, 2016-05582,

2017-00704, 2017-00818, 2017-03289,

2017-03290, 2017-03780, 2019-00141,

2019-00160, 2019-00277, 2019-02302,

2019-03060, 2019-03613, 2020-01039,

20-01051, 2021-00492, 2021-00741,

21-00888, 2021-00918, 2021-01188,

21-01204, 2021-01326, 2021-01841,

21-01891, 2021-02021, 2021-02429,

21-02824, 2021-02868, 2022-00088

Corrective Action

Documents

CR-ANO-2-

2018-03333, 2020-02431, 2021-01204, 2022-00099

Corrective Action

Documents

CR-ANO-C-

2013-00820, 2015-01357, 2019-00756,

2019-01633, 2019-02302, 2020-00624,

20-00373, 2020-02049, 2021-00987,

21-01360, 2021-02620, 2021-02703,

21-02893, 2021-03142, 2021-03247, 2022-00178

Corrective Action

Documents

CR-HQN-

2019-00645, 2021-01930

Corrective Action

Documents

Resulting from

CR-ANO-1-

22-00025, 2022-00129, 2022-00130,

22-00134, 2022-00135, 2022-00136,

22-00148, 2022-00150, 2022-00151,

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Inspection

22-00152, 2022-00153, 2022-00154,

22-00155, 2022-00156, 2022-00157,

22-00158, 2022-00161, 2022-00162,

22-00163, 2022-00164, 2022-00165,

22-00166, 2022-00167, 2022-00169,

22-00163, 2022-00171, 2022-00230

Corrective Action

Documents

Resulting from

Inspection

CR-ANO-2-

22-00161, 2022-00269, 2022-00271, 2022-00272

Corrective Action

Documents

Resulting from

Inspection

CR-ANO-C-

21-02622, 2022-00199, 2022-00220,

22-00248, 2022-00249, 2022-00252,

22-00264, 2022-00368, 2022-00464,

22-00553, 2022-00604, 2022-00804, 2022-00955

Drawings

6600-M67-40-10

Diesel Generator Rooms 86 and 87 Sprinkler

Arrangement

11/11/1971

Drawings

E-2005, Sheet 2

Single Line Meter & Relay Diagram - AAC

Generator System 4.16 KV Generator & Switchgear

Drawings

E-2042, Sheet 2

Logic Diagram - AAC Generator System 4.16 KV

Tie Breakers

Drawings

E-2042, Sheet 3

Logic Diagram - AAC Generator System 4.16 KV

Tie Breakers

Drawings

M-219, sheet 1

Arkansas Nuclear One, Unit 1 - Piping and

Instrument Diagram Fire Water

Drawings

M-2219, sheet 1

Arkansas Nuclear One, Unit 2 - Piping and

Instrument Diagram Fire Water

Drawings

MT21018

Emergency Cooling Pond Hydrographic Map - 2021

Model Hydrographic Mapping of Emergency Cooling

Pond, Arkansas Nuclear One Facility

7/1/2021

Engineering

Changes

EC-17938

ANO-1 Flow Accelerated Corrosion (FAC) Program

System Susceptibility Evaluation

11/30/2009

Engineering

Changes

EC-46763

ANO-1 Wall Thinning Inspection Aging Management

Program Scope

9/17/2013

Engineering

2-9097174-000

Assessment of November 2008 Core Barrel Bolts

11/12/2008

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Evaluations

Inspection Results at Arkansas Unit 1

Engineering

Evaluations

A-EP-2005-001

ANO Microbiological Influenced Corrosion (MIC)

Program

Engineering

Evaluations

ANO1ILRT.19-R191110B

Integrated Leakage Rate Test Report

11/10/2019

Engineering

Evaluations

CALC-08-E-0013-05

Assessment of November 2008 Core Barrel Bolts

Inspection Results at Arkansas Nuclear One, Unit 1

Engineering

Evaluations

CALC-ANO1-CS-11-00010

Maintenance Rule Structural Program Review

Engineering

Evaluations

CALC-ANO1-CS-13-00006

Engineering Evaluation Report per IWL-3300 for the

40th Year ANO Unit 1 Containment Building Tendon

Surveillance and Concrete Inspection

Engineering

Evaluations

CALC-ANO1-CS-18-00005

Engineering Evaluation Report per IWL-3300 for the

45th Year ANO Unit 1 Containment Building Tendon

Surveillance and Concrete Inspection

Engineering

Evaluations

CALC-ANO1-EE-11-00001

ANO-1 Screening and Aging Management Review

of Electrical Components for RIS 2007-016

Engineering

Evaluations

CALC-ANO1-EE-11-00002

Review of the Electrical Component Inspection

Aging Management Program for License Renewal

Implementation

Engineering

Evaluations

CALC-ANO1-EE-13-00004

Non-Environmentally Qualified Sensitive

Instrumentation Circuits Test Review

Engineering

Evaluations

CALC-ANO1-EE-13-00005

Non-Environmentally Qualified Inaccessible Medium

Voltage Cable and Manhole Review

Engineering

Evaluations

CALC-ANO1-ME-11-00002

Review of the Buried Pipe Inspection Aging

Management Program for License Renewal

Implementation

Engineering

Evaluations

CALC-ANO1-ME-11-00004

Review of the Service Water Integrity Aging

Management Program for License Renewal

Implementation

Engineering

Evaluations

CALC-ANO1-ME-11-00007

Review of the Heat Exchanger Monitoring Aging

Management Program for License Renewal

Implementation

Engineering

CALC-ANO1-ME-11-00009

Review of the Reactor Building Leak Rate Testing

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Evaluations

(RBLRT) Aging Management Program for License

Renewal Implementation

Engineering

Evaluations

CALC-ANO1-ME-11-00012

Review of the Pressurizer Examinations Aging

Management Program for License Renewal

Implementation

Engineering

Evaluations

CALC-ANO1-ME-11-00026

Review of the Reactor Vessel Internals Aging

Management Program for License Renewal

Implementation

Engineering

Evaluations

CALC-ANO1-ME-11-00027

Review of the Wall Thinning Inspection Aging

Management Program for License Renewal

Implementation

Engineering

Evaluations

CALC-ANO1-ME-11-00028

Review of the Fire Protection Aging Management

Program for License Renewal Implementation

Engineering

Evaluations

CALC-ANO1-ME-12-00003

Review of the Oil Analysis Aging Management

Program for License Renewal Implementation

Engineering

Evaluations

CALC-ANO1-ME-12-00004

Review of the Chemistry Control Aging

Management Program for License Renewal

Implementation

Engineering

Evaluations

CALC-ANO1-ME-13-00002

Review of the Emergency Diesel Generator Testing

and Inspections Aging Management Program for

License Renewal Implementation

Engineering

Evaluations

CALC-ANO1-ME-13-00010

Review of the Control Room Ventilation Testing

Aging Management Program for License Renewal

Implementation

Engineering

Evaluations

CALC-ANO1-ME-13-00011

Review of the Flow Accelerated Corrosion Aging

Management Program for License Renewal

Implementation

Engineering

Evaluations

CALC-ANO1-ME-15-00004

MRP-227-A Applicant/Licensee Action Item #7

Analysis of IMl Guide Tube Spider Castings at

ANO-1

Engineering

Evaluations

CALC-ANO1-ME-16-00004

Assessment of Fall 2016 Upper Core Barrel (UCB)

and Lower Core Barrel (LCB) Bolts Inspection

Results - ANO-1 (1R26)

Engineering

CALC-ANO1-ME-16-00005

ANO-1 Reactor Vessel Vent Valve Examination

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Evaluations

Indication Resolution

Engineering

Evaluations

CALC-ANOC-CS-15-00001

2015 Maintenance Rule Structural Monitoring 5

Year Walkdown of High Risk Structures

Engineering

Evaluations

CALC-ANOC-CS-21-00002

20 Maintenance Rule Structural Monitoring

Inspection Report for High and Low Risk Structures

Engineering

Evaluations

Report-ECS-17-0002

ANO-2 LRI Project: Selective Leaching Material

Composition and Sample Population

Miscellaneous

Q3-2021 - Program Health Report - Cathodic

Protection

Miscellaneous

Units 1 and 2 Cable List by Manhole

Miscellaneous

Q3-2021 Program Health Report - Buried Piping and

Tanks Program

Miscellaneous

EN-DC-346 Low and Medium Voltage Cable Lists

Miscellaneous

Q2-2021 System Health Report Alternate AC Diesel

Generator

Miscellaneous

05000313/2005003 and

05000368/2005003

Arkansas Nuclear One - NRC Integrated Inspection

Report

8/5/2005

Miscellaneous

200459.401

SI Report: PWR Internals Aging Management

Program Plan for Arkansas Nuclear One, Unit 1

1/03/2013

Miscellaneous

1700534.01

ANO 2019/2020 Area Potential Earth Current

(APEC)

4/2020

Miscellaneous

1901127.01

ANO InTellusAS' 2020 Annual Survey Report

Miscellaneous

1CANO10003

License Renewal Application, App. B, section 3.2

(Ref. 2)

1/31/2000

Miscellaneous

1CANO40107

Safety Evaluation Report (NUREG-1743),

4/12/2001

Miscellaneous

2100141.021

ANO InTellusAS' 2021 Annual Survey Report

Miscellaneous

2100141.021

21 Annual Survey Report

8/4/2021

Miscellaneous

93-R-1011-01

Review of the Programs Credited in the License

Renewal Evaluations

Miscellaneous

93-R-1013-08

Demonstration of the Management of Aging Effects

for the ANO-1 Reactor Vessel Internals

Miscellaneous

93-R-1016-11

Aging Management Review of the Emergency

Feedwater System

PC-1

Miscellaneous

93-R-1016-12

Aging Management Review of the Sodium

001-03-0

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Hydroxide System

Miscellaneous

93-R-1016-14

Aging Management Review of the Main Steam

System

PC-1

Miscellaneous

93-R-1016-19

Aging Management Review of the Condensate

Storage System

001-03-0

Miscellaneous

93-R-1016-20

Aging Management Review of the Control Room

Ventilation System

Miscellaneous

93-R-1016-23

Aging Management Review of the Containment

Isolation Mechanical Components

001-03-0

Miscellaneous

93-R-1016-24

Aging Management Review of the Chilled Water

System

001-03-0

Miscellaneous

Arkansas Nuclear One,

Unit 1

Updated Final Safety Analysis Report, Chapter 16

Miscellaneous

EPRI 1020805

Plant Support Engineering: Aging Management

Program Guidance for Medium-Voltage Cable

Systems for Nuclear Power Plants

6/2010

Miscellaneous

EPRI TR-3002010594

CHECWORKS Steam/Feedwater Application

Guidelines for Plant Modeling and Evaluation of

Component Inspection Data

Miscellaneous

Generic Letter 2007-01

Inaccessible or Underground Power Cable Failures

That Disable Accident Mitigation Systems or Cause

Plant Transients

2/7/2007

Miscellaneous

Information Notice 2013-06

Corrosion in Fire Protection Piping Due to Air and

Water Interaction

3/25/2013

Miscellaneous

Job Orders

00926007, 00927858, 00933415

Miscellaneous

LAR-2015-00081, CA-05:

ANO Unit 1 and Unit 2 Selective Leaching

10-Element Summary Evaluation and History

Miscellaneous

Letter 0CAN011002

Clarification of Response to Generic Letter 2007-01

- Arkansas Nuclear One, Units 1 and 2

1/11/2010

Miscellaneous

Letter 0CAN029304

Station Blackout Commitment for One-Time

Confirmatory Load Test

2/26/1993

Miscellaneous

Letter 0CAN049512

Notification Of Completion Of the Station Blackout,

NUMARC Part B. 12 Test

4/18/1995

Miscellaneous

Letter 0CAN050701

Response to Generic Letter 2007-01, Arkansas

5/7/2007

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Nuclear One - Units 1 and 2

Miscellaneous

Letter 0CAN069302

Additional Information Regarding the Proposed SBO

Diesel Generator Testing

6/29/1993

Miscellaneous

Letter 0CAN089203

Conceptual Design for Station Blackout Modification

(TAC Nos. M68508 and M68509)

8/14/1992

Miscellaneous

Letter 0CAN109205

Revised Approach for Compliance to NRC Generic Letter 89-13; Service Water

10/30/1992

Miscellaneous

Letter 0CAN119507

Notification of Completion of Station Blackout Diesel

Testing Commitments

11/17/1995

Miscellaneous

Letter 0CAN129406

Notification of Compliance with the Station Blackout

Rule

2/30/1994

Miscellaneous

Letter 0CNA129208

Conceptual design for station blackout (SBO)

modification - Arkansas Nuclear One, Units 1 and 2

(TAC NOS. M84338 and 84339)

2/18/1992

Miscellaneous

Letter 1CAN011405

Notification of Revised License Renewal

Commitments Arkansas Nuclear One - Unit 1

1/30/2014

Miscellaneous

Letter 1CAN051403

Reactor Vessel Internals Aging Management

Program Plan

5/14/2014

Miscellaneous

Letter 1CAN111401

License Amendment Request Update the Reactor

Coolant System Pressure and Temperature and the

Low Temperature Overpressure Protection System

Limits

11/21/2014

Miscellaneous

Letter 1CNA041504

Arkansas Nuclear One, Unit No. 1 - Issuance of

Amendment Re: Update The Reactor Coolant

System Pressure and Temperature Limits and The

Low Temperature Overpressure Protection System

Limits

4/24/2015

Miscellaneous

LO-ALO-2016-0082

Self-Assessment: Flow Accelerated Corrosion

Program

5/16/2017

Miscellaneous

LO-ALO-2019-00021 CA-00008

Pre-INPO MRV Self-Assessment

2/28/2019

Miscellaneous

LO-ALO-2021-00038

Focused Self-Assessment for Upcoming Phase 4

License Renewal NRC Inspection

8/3/2021

Miscellaneous

LO-HQNLO-2017-0047

Gap assessment for the Engineering Programs

2/28/2018

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

being transferred to the Central Engineering

Organization

Miscellaneous

LR-LAR-2010-00176 CA-175

Determine Wall Thinning Inspections Required in

1R24

2/6/2012

Miscellaneous

LR-LAR-2010-00176 CA-209

Implement Actions From CALC-ANO1-ME-11-00027

9/18/2013

Miscellaneous

LR-LAR-2010-00176 CA-33

Implement and Maintain New Wall Thinning

Inspection Program IAW NRC commitment A-17855

11/7/2013

Miscellaneous

LR-LAR-2016-00032

Implementation of the NRC commitments

associated with the ANO-1 Reactor Vessel Internals

Aging Management Program Plan.

1/19/2016

Miscellaneous

MRP-175

Materials Reliability Program: PWR Internals

Material Aging Degradation Mechanism Screening

and Threshold Values

Miscellaneous

MRP-189

Materials Reliability Program: Screening,

Categorization, and Ranking of B&W-Designed

PWR Internals Component Items

Miscellaneous

MRP-190

Materials Reliability Program: Failure Modes,

Effects, and Criticality Analysis of B&W-Designed

PWR Internals

Miscellaneous

MRP-227-A

Materials Reliability Program: Pressurized Water

Reactor Internals Inspection and Evaluation

Guidelines

Miscellaneous

MRP-228

Materials Reliability Program: Inspection Standard

for PWR Internals

Miscellaneous

MRP-229

Materials Reliability Program: AREVA Functionality

Evaluation Report for B&W-Designed PWR Internals

Component Items

Miscellaneous

MRP-231

Materials Reliability Program: Aging Management

Strategies for B&W PWR Internals

Miscellaneous

Plant Health Committee

Cathodic Protection System Deficiencies

Miscellaneous

PM Basis Template

EN-Cable-Medium Voltage

Miscellaneous

Presentation

Chemistry Lab Pre-Action System Clogging

9/12/2011

Miscellaneous

Regulatory Guide 1.155

Station Blackout

August

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

1988

Miscellaneous

Regulatory Issue Summary 2007-16

Implementation of the Requirements of 10 CFR 54.37(b) for Holders of Renewed Licenses

8/23/2007

Miscellaneous

Regulatory Issue Summary 2007-16, Revision 1

Implementation of the Requirements of 10 CFR 54.37(b) for Holders of Renewed Licenses

4/28/2010

Miscellaneous

ULD-0-SYS-19

Upper Level Document - Alternate AC Generator

System (AAC)

Miscellaneous

Vendor Manual

ESI - EMD Owners Group Recommended

Maintenance Program - Electrical for Nuclear

Standby Emergency Diesel Generators

Miscellaneous

Vendor Manual

ESI -EMD Owners Group Recommended

Maintenance Program -Mechanical Nuclear Standby

Emergency Diesel Generators

Miscellaneous

WCAP-17096-NP

Reactor Internals Acceptance Criteria Methodology

and Data Requirements

NDE Reports

1-BOP-UT-18-032

UT Thickness Examination of T-39A - AR 9808

Instrument Air Tank

2/10/2018

NDE Reports

1-FAC-19-072

1R28-203 WT-DBD001E001 Wall Thinning

Examination

10/17/2019

NDE Reports

1-FAC-19-076

1R28-204 WT-DBD001P012 Wall Thinning

Examination

10/17/2019

NDE Reports

1-FAC-19-084

1R28-208 WT-EBB002BE001 Wall Thinning

Examination

10/17/2019

NDE Reports

1-FAC-19-093

1R28-205 WT-DBD002P003 Wall Thinning

Examination

10/19/2019

NDE Reports

1-FAC-19-096

1R28-206 WT-DBD002P015 Wall Thinning

Examination

10/19/2019

NDE Reports

1-FAC-19-103

1R28-207 WT-EBB002AP003 Wall Thinning

Examination

10/22/2019

NDE Reports

1-FAC-19-105

1R28-220 WT-HBD024P010 Wall Thinning

Examination

10/21/2019

NDE Reports

1-FAC-19-106

1R28-221 WT-HBD024P013 Wall Thinning

Examination

10/21/2019

NDE Reports

1-FAC-19-107

1R28-223 WT-HBD024P016 Wall Thinning

10/23/2019

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Examination

NDE Reports

1-FAC-19-108

1R28-222 WT-HBD024P015 Wall Thinning

Examination

10/22/2019

NDE Reports

1-FAC-19-111

1R28-215 WT-HBB002P54-AUX Wall Thinning

Examination

10/22/2019

NDE Reports

1-FAC-19-112

1R28-214 WT-HBB001P43 Wall Thinning

Examination

10/22/2019

NDE Reports

1-FAC-19-113

1R28-214 WT-HBB001P43-AUX Wall Thinning

Examination

10/22/2019

NDE Reports

1-FAC-19-124

1R28-224 WT-JBD001R001 Wall Thinning

Examination

10/24/2019

NDE Reports

1-FAC-19-129

1R28-215 WT-HBB002P54 Wall Thinning

Examination

10/25/2019

NDE Reports

1-FAC-19-130

1R28-218 WT-HBB005P51 Wall Thinning

Examination

10/24/2019

NDE Reports

1-FAC-19-131

1R28-216 WT-HBB002P60 Wall Thinning

Examination

10/24/2019

NDE Reports

1-FAC-19-132

1R28-217 WT-HBB002P62 Thinning Examination

10/25/2019

NDE Reports

1-FAC-19-133

1R28-213 WT-HBB005P59 Wall Thinning

Examination

10/25/2019

NDE Reports

1-FAC-19-134

1R28-212 WT-EBD006T001 Wall Thinning

Examination

10/25/2019

NDE Reports

1-FAC-19-135

1R28-213 WT-HBB005P59-AUX Wall Thinning

Examination

10/25/2019

NDE Reports

1-FAC-19-136

1R28-216 WT-HBB002P60-AUX Wall Thinning

Examination

10/25/2019

NDE Reports

1-FAC-19-143

1R28-209 WT-EBD006E004 Wall Thinning

Examination

10/25/2019

NDE Reports

1-FAC-19-144

1R28-211 WT-EBD006BE003 Wall Thinning

Examination

10/25/2019

NDE Reports

1-FAC-19-145

1R28-219 WT-HBB007P42 Wall Thinning

Examination

10/25/2019

NDE Reports

1-FAC-19-148

1R28-210 WT-EBD006P022 Wall Thinning

Examination

10/25/2019

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

NDE Reports

REP-1086-510

Final Report for the 40TH Year (10th Period)

Tendon Surveillance at Arkansas Nuclear One

Unit 1

10/24/2013

NDE Reports

REP-1137-510

Final Report for the 2018 Tendon Cap Replacement

Project at Arkansas Nuclear One Unit 1

10/25/2018

Procedures

1015.036

Containment Building Closeout

Procedures

1104.032, Supplement 10

Fire Protection Systems - 3-year Fire Water System

Flow Test

Procedures

1104.032, Supplement 2

Fire Protection System - Surveillance Test of Diesel

Fire Pump (P-6B)

Procedures

1104.032, Supplement 7

Fire Protection Systems - Annual Manual Valves

Surveillance Test of Unit 1 and Common Fire Water

System

Procedures

1104.036

Emergency Diesel Generator Operation,

Supplement 1

Procedures

1306.014

Unit 1 Control Room & Auxiliary Control Room

Halon Fire System Inspection

Procedures

1306.019

Annual Emergency Cooling Pond Sounding

Procedures

1307.026

Unit 1 K4A and K4B Emergency Diesel Generator

Month Surveillance

Procedures

1309.016

Decay Heat Cooler Thermal Test

Procedures

1402.066

Month Inspection on Unit 1 Emergency Diesel

Generator Engine

Procedures

1416.045

Unit 1 K4A/K4B Periodic Maintenance

Procedures

2104.037

Alternate AC Diesel Generator Operations

Procedures

CEP-CII-004

General and Detailed Visual Examinations of

Concrete Containments

311

Procedures

CEP-FAC-001

Flow Accelerated Corrosion Program Component

Scanning and Gridding Standard

Procedures

CEP-NDE-0505

Ultrasonic Thickness Examination

Procedures

CEP-NDE-0505

Ultrasonic Thickness Examination

Procedures

CEP-UPT-0100

Underground Piping And Tanks Inspection And

Monitoring

Procedures

EN-DC-133

PWR Vessel Internals Program

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Procedures

EN-DC-150

Condition Monitoring of Maintenance Rule

Structures

Procedures

EN-DC-184

NRC Generic Letter 89-13 Service Water Program

Procedures

EN-DC-303

Lubrication Program

Procedures

EN-DC-310

Predictive Maintenance Program

Procedures

EN-DC-315

Flow Accelerated Corrosion Program

Procedures

EN-DC-316

Heat Exchanger Performance and Condition

Monitoring

Procedures

EN-DC-340

Microbiologically Influenced Corrosion (MIC)

Monitoring Program

Procedures

EN-DC-343

Underground Piping and Tanks Inspection and

Monitoring Program

Procedures

EN-DC-346

Cable Reliability Program

Procedures

EN-DC-348

Non-Environmentally Qualified Insulated Cables and

Connections Inspection

Procedures

EN-FAP-LR-027

License Renewal Sensitive Instrumentation Circuits

Review Aging Management Program

Procedures

EN-LI-110

Commitment Management Program

Procedures

EN-MA-101

Conduct of Maintenance

Procedures

EN-OP-104

Operability Determination Process

Procedures

SEP-APJ-002

Arkansas Nuclear One Primary Containment

Leakage Rate Testing (Appendix J) Program

Section

Procedures

SEP-CISI-ANO-101

Program Section for ASME Section XI, Division 1

ANO-1 Containment Inservice Inspection Program

Procedures

SEP-HX-ANO-001

Arkansas Nuclear One Heat Exchanger Program

Procedures

SEP-ISI-ANO1-101

ASME SECTION XI, DIVISION 1,ANO 1

INSERVICE INSPECTION PROGRAM

Procedures

SEP-LR-ANO-001

Aging Management Review and TLAA Evaluation of

Newly Identified Structures, Systems, or

Components

and 1

Procedures

SEP-LUB-ANO-002

ANO Oil Analysis Program

Procedures

SEP-MIC-ANO-001

Arkansas Nuclear One (ANO) Microbiological

Influenced Corrosion (MIC) Program

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Procedures

SEP-PVI-ANO-1-001

ANO-1 PWR Vessel Internals Program

Procedures

SEP-SLP-ANO

Arkansas Nuclear One (ANO) Selective Leaching

Program

Procedures

SEP-SW-ANO-001

Arkansas Nuclear One (ANO) NRC Generic Letter 89-13 Service Water Program

Procedures

SEP-UIP-ANO

Underground Components Inspection Plan Non-Rad

And Rad Piping

Procedures

SEP-WTI-ANO-001

Arkansas Nuclear One (ANO) Wall Thinning

Inspection (WTI) Program

and 4

Self-Assessments

LO-ALO-2016-0016

Underground Piping & Tanks Inspection &

Monitoring Program Snapshot

9/12/2016

Self-Assessments

LO-ALO-2016-0082

Flow Accelerated Corrosion Program

5/16/2017

Self-Assessments

LO-ALO-2016-16

Underground Piping & Tanks Inspection &

Monitoring Program Snapshot Assessment

Self-Assessments

LO-ALO-2017-00071

Pre-NRC Full Scope Assessment: Triennial Heat

Sink Assessment

Self-Assessments

LO-ALO-2018-00064

Pre-NRC Fire Protection Triennial

9/26/2018

Self-Assessments

LO-ALO-2019-00021, CA-00008

Pre-INPO Material Review Assessment

2/28/2019

Self-Assessments

LO-ALO-2021-00038

Focused Self-Assessment for Upcoming Phase 4

License Renewal NRC Inspection

8/3/2021

Self-Assessments

LO-HQNLO-2017-0047

Fleet Engineering Programs Assessment

2/28/2018

Self-Assessments

LO-HQNLO-2017-47

Engineering Programs Assessment

Self-Assessments

LO-HQNLO-2019-77

Self-Assessment on the Buried Pipe and Tank

Program

Work Orders

00181327, 00313266, 00413802, 00415785,

00417880, 00431634, 00466281, 00466305,

00476087, 00510329, 00512386, 00522015,

00522878, 00556678, 00557269, 00557272,

00557273, 50234712, 50234894, 50239454,

239455, 50239692, 52396269, 52399594,

2517938, 52640734, 52695570, 52713610,

2758769, 52799321, 52803138, 52803139,

2804233, 52804234, 52814408, 52836524,

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

2844772, 52874481, 52878110, 52878111,

2903447, 52908026, 52908679, 52910286,

2917821, 52919501, 52919826, 52923102,

2923103, 52925767, 52925845, 52927684,

2928754, 52933200, 52934878, 52934878,

2937553, 52941266, 52947678, 52954470,

2971739, 52990570, 52991934