IR 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:
Report Number:
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,
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
ANO-1 Flow Accelerated Corrosion (FAC) Program
System Susceptibility Evaluation
11/30/2009
Engineering
Changes
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
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
Inaccessible or Underground Power Cable Failures
That Disable Accident Mitigation Systems or Cause
Plant Transients
2/7/2007
Miscellaneous
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
Self-Assessment: Flow Accelerated Corrosion
Program
5/16/2017
Miscellaneous
Pre-INPO MRV Self-Assessment
2/28/2019
Miscellaneous
Focused Self-Assessment for Upcoming Phase 4
License Renewal NRC Inspection
8/3/2021
Miscellaneous
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
Determine Wall Thinning Inspections Required in
1R24
2/6/2012
Miscellaneous
Implement Actions From CALC-ANO1-ME-11-00027
9/18/2013
Miscellaneous
Implement and Maintain New Wall Thinning
Inspection Program IAW NRC commitment A-17855
11/7/2013
Miscellaneous
Implementation of the NRC commitments
associated with the ANO-1 Reactor Vessel Internals
Aging Management Program Plan.
1/19/2016
Miscellaneous
Materials Reliability Program: PWR Internals
Material Aging Degradation Mechanism Screening
and Threshold Values
Miscellaneous
Materials Reliability Program: Screening,
Categorization, and Ranking of B&W-Designed
PWR Internals Component Items
Miscellaneous
Materials Reliability Program: Failure Modes,
Effects, and Criticality Analysis of B&W-Designed
PWR Internals
Miscellaneous
Materials Reliability Program: Pressurized Water
Reactor Internals Inspection and Evaluation
Guidelines
Miscellaneous
Materials Reliability Program: Inspection Standard
for PWR Internals
Miscellaneous
Materials Reliability Program: AREVA Functionality
Evaluation Report for B&W-Designed PWR Internals
Component Items
Miscellaneous
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
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
Miscellaneous
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
PWR Vessel Internals Program
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
Condition Monitoring of Maintenance Rule
Structures
Procedures
NRC Generic Letter 89-13 Service Water Program
Procedures
Lubrication Program
Procedures
Predictive Maintenance Program
Procedures
Flow Accelerated Corrosion Program
Procedures
Heat Exchanger Performance and Condition
Monitoring
Procedures
Microbiologically Influenced Corrosion (MIC)
Monitoring Program
Procedures
Underground Piping and Tanks Inspection and
Monitoring Program
Procedures
Cable Reliability Program
Procedures
Non-Environmentally Qualified Insulated Cables and
Connections Inspection
Procedures
EN-FAP-LR-027
License Renewal Sensitive Instrumentation Circuits
Review Aging Management Program
Procedures
Commitment Management Program
Procedures
Conduct of Maintenance
Procedures
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
Underground Piping & Tanks Inspection &
Monitoring Program Snapshot
9/12/2016
Self-Assessments
Flow Accelerated Corrosion Program
5/16/2017
Self-Assessments
Underground Piping & Tanks Inspection &
Monitoring Program Snapshot Assessment
Self-Assessments
Pre-NRC Full Scope Assessment: Triennial Heat
Sink Assessment
Self-Assessments
Pre-NRC Fire Protection Triennial
9/26/2018
Self-Assessments
Pre-INPO Material Review Assessment
2/28/2019
Self-Assessments
Focused Self-Assessment for Upcoming Phase 4
License Renewal NRC Inspection
8/3/2021
Self-Assessments
Fleet Engineering Programs Assessment
2/28/2018
Self-Assessments
Engineering Programs Assessment
Self-Assessments
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