IR 05000313/2021004
| ML22021B654 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 02/04/2022 |
| From: | Ami Agrawal NRC/RGN-IV/DRP/RPB-D |
| To: | Sullivan J Entergy Operations |
| References | |
| IR 2021004 | |
| Download: ML22021B654 (27) | |
Text
February 4, 2022
SUBJECT:
ARKANSAS NUCLEAR ONE - INTEGRATED INSPECTION REPORT 05000313/2021004 AND 05000368/2021004
Dear Mr. Sullivan:
On December 31, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Arkansas Nuclear One. On January 13, 2022, the NRC inspectors discussed the results of this inspection with you and other members of your staff. The results of this inspection are documented in the enclosed report.
One finding of very low safety significance (Green) is documented in this report. This finding involved a violation of NRC requirements. We are treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2 of the Enforcement Policy.
If you contest the violation or the significance of the violation documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region IV; the Director, Office of Enforcement; and the NRC Resident Inspector at Arkansas Nuclear One.
If you disagree with a cross-cutting aspect assignment in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region IV; and the NRC Resident Inspector at Arkansas Nuclear One. This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, Ami N. Agrawal, Acting Chief Reactor Projects Branch D Division of Reactor Projects Docket Nos. 05000313 and 05000368 License Nos. DPR-51 and NPF-6
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000313 and 05000368
License Numbers:
Report Numbers:
05000313/2021004 and 05000368/2021004
Enterprise Identifier:
I-2021-004-0122
Licensee:
Entergy Operations, Inc.
Facility:
Arkansas Nuclear One
Location:
Russellville, AR
Inspection Dates:
October 1, 2021, to December 31, 2021
Inspectors:
N. Brown, Resident Inspector
R. Bywater, Senior Resident Inspector
T. DeBey, Resident Inspector
J. Drake, Senior Reactor Inspector
J. Lee, Reactor Inspector
Approved By:
Ami N. Agrawal, Acting Chief
Reactor Projects Branch D
Division of Reactor Projects
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Arkansas Nuclear One, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.
List of Findings and Violations
Failure to Maintain a Source Range Neutron Flux Monitor Audible in the Control Room as Required by Technical Specifications Cornerstone Significance Cross-Cutting Aspect Report Section Barrier Integrity Green NCV 05000368/2021004-01 Open/Closed
[H.7] -
Documentation 71153 The inspectors identified a Green finding and associated non-cited violation of Arkansas Nuclear One, Unit 2, Technical Specification 3.9.2 for the licensees failure to have a source range neutron flux monitor with audible indication in the control room while in Mode 6.
Additional Tracking Items
Type Issue Number Title Report Section Status LER 05000368/2021-001-00 Non-Compliance with Technical Specifications Resulting in Lack of Nuclear Instrumentation Audible Indication 71153 Closed
PLANT STATUS
Unit 1 began the inspection period at full power. On November 29, 2021, Unit 1 automatically tripped from 100 percent power following a failure involving the main feedwater pump A control system. After repairs, the reactor was made critical on December 1, 2021, and the unit was returned to full power on December 3, 2021. Unit 1 remained at or near full power for the remainder of the inspection period.
Unit 2 began the inspection period shut down in a planned refueling outage and the reactor was made critical on November 26, 2021. Following completion of startup testing and equipment maintenance, the unit was returned to full power on December 5, 2021. Unit 2 remained at or near full power for the remainder of the inspection period.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors performed activities described in IMC 2515, Appendix D, Plant Status, conducted routine reviews using IP 71152, Problem Identification and Resolution, observed risk significant activities, and completed on-site portions of IPs. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
REACTOR SAFETY
71111.01 - Adverse Weather Protection
Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of the cold weather season:
Units 1 and 2 service water intake structure heaters on October 19, 2021
Common unit, alternate ac diesel generator building climate control on October 19, 2021
External Flooding Sample (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated that flood protection barriers, mitigation plans, procedures, and equipment are consistent with the licensees design requirements and risk analysis assumptions for coping with external flooding on October 13, 2021.
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (1 Sample)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Common feedwater system on November 22, 2021
Complete Walkdown Sample (IP Section 03.02) (2 Samples)
- (1) The inspectors evaluated system configurations during a complete walkdown of the Unit 2 train A emergency feedwater system on October 22, 2021.
- (2) The inspectors evaluated system configurations during a complete walkdown of the Unit 1 reactor building spray system on December 20, 2021.
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (3 Samples)
The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:
- (1) Unit 1 ammonia tank room (common feedwater pump room), Fire Zone 75-AA, on December 1, 2021
- (2) Unit 1 emergency diesel generator rooms, Fire Zones 86-G and 87-H, on December 15, 2021
- (3) Unit 1 emergency feedwater pump room, Fire Zone 38-Y, on December 16, 2021
71111.06 - Flood Protection Measures
Inspection Activities - Internal Flooding (IP Section 03.01) (1 Sample)
The inspectors evaluated internal flooding mitigation protections in the:
- (1) Unit 2 auxiliary building, 317-foot elevation, on October 20, 2021
Cable Degradation (IP Section 03.02) (1 Sample)
The inspectors evaluated cable submergence protection in:
- (1) Manhole 2MH-13 on October 1, 2021
71111.07A - Heat Sink Performance
Annual Review (IP Section 03.01) (2 Samples)
The inspectors evaluated readiness and performance of:
- (1) Unit 2 shutdown cooling heat exchanger A performance test on November 4, 2021
- (2) Unit 2 shutdown cooling heat exchanger B performance test on November 4, 2021
71111.08P - Inservice Inspection Activities (PWR) PWR Inservice Inspection Activities Sample (IP Section 03.01)
- (1) The inspectors verified that the reactor coolant system boundary, steam generator tubes, reactor vessel internals, risk-significant piping system boundaries, and containment boundary are appropriately monitored for degradation and that repairs and replacements were appropriately fabricated, examined, and accepted by reviewing the following activities from September 27, 2021, to December 13, 2021:
03.01.a - Nondestructive Examination and Welding Activities
Ultrasonic Examination o
Feed water, 17-001C1, pipe to pipe o
Feed water, 17-003C1, reducing elbow to pipe o
Feed water, 17-004C1, pipe to reducing elbow o
Reactor vessel closure head penetration 46
Eddy Current Examination o
Reactor vessel closure head penetration 46
Dye Penetrant Examination o
Component cooling water, 2CC-1113, FW-15C1 o
Component cooling water, 2CC-1113, FW-16C1 o
Reactor vessel closure head penetration 46
Visual 1 Examination o
Reactor vessel closure head penetration 46
Visual 3 Examination o
Main steam, 2EBB2-H2 pipe support o
Welding o
Component cooling water, 2CC-1113, FW-15C1
Component cooling water, 2CC-1113, FW-16C1
Reactor vessel closure head penetration 46 03.01.b - Pressurized-Water Reactor Vessel Upper Head Penetration Examination Activities
The following reactor vessel head penetrations eddy current and ultrasonic examination results were observed or reviewed: 49, 52, 70, 71
Penetration 46 had flaw identified and repaired, 50-9338579 Completed Traveler with weld package and NDE reports 03.01.c - Pressurized-Water Reactor Boric Acid Corrosion Control Activities ANO-2-2020-2674, ANO-2-2020-3024, ANO-2-2020-3025, ANO-2-2020-3951, ANO-2-2020-3258, ANO-2-2020-3575, ANO-2-2018-0695, ANO-2-2019-0125, ANO-2-2020-2199, ANO-2-2020-3801, ANO-2-2021-0926, ANO-2-2020-2309, ANO-2-2020-2320, ANO-2-2020-2479, ANO-2-2021-0863 Problem Identification and Resolution review of inservice items The inspector evaluated a sample of 92 condition reports associated with inservice inspection activities. No findings or violations of more than minor significance were identified.
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)
- (1) The inspectors observed and evaluated licensed operator performance in the control room during Unit 1 start up and power ascension on December 1 and 2, 2021.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated Unit 2 start up and ovation turbine control testing training on October 16, 2021.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (6 Samples)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
- (1) Unit 1 emergency feedwater initiation and control system on November 2, 2021
- (2) Unit 2 containment spray isolation valve 2CV-5612-1 on November 3, 2021
- (3) Unit 1 18-month reactor protection system surveillance/human performance error/out of tolerance test on November 4, 2021
- (4) Unit 2 motor-operated valve inspection program on November 5, 2021
- (5) Periodic (a)(3) assessment on November 10, 2021
- (6) Safety-related doors functional failures on December 15, 2021 Aging Management (IP Section 03.03)
The inspectors evaluated the effectiveness of the aging management program for the following SSCs that did not meet their inspection or test acceptance criteria:
- (1) There were no inspections or tests of passive long-lived SSCs that did not pass their acceptance criteria on Unit 1 or Unit 2.
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (3 Samples)
The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:
- (1) Unit 1 auto-transformer outage on October 7, 2021
- (2) Unit 1 during reduced power operations on December 2, 2021
- (3) Unit 2 during reduced power operations on December 2, 2021
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (6 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Unit 2 containment spray pump A suction pressure instrument overpressurization operability determination on November 3, 2021
- (2) Unit 1 door 78 flooding protection capability functionality determination on November 16, 2021
- (3) Unit 2 feedwater isolation valve 2CV-1023-2 to steam generator A magnesium motor rotor degradation operability determination on November 17, 2021
- (4) Unit 1 main feedwater valve bypass isolation valve FW-28 flange leakage operability determination on December 3, 2021
- (5) Unit 2 refueling water tank outlet valve 2CV-5630-1 control power fuse failure operability determination on December 6, 2021
- (6) Unit 2 emergency cooling pond service water supply piping identification of water in pipe during inspection operability determination on December 14, 2021
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (3 Samples)
The inspectors evaluated the following temporary or permanent modifications:
- (1) Unit 2 spent fuel pool cooling pumps temporary power modification on October 8, 2021
- (2) Unit 2 refueling machine modification on October 20, 2021
- (3) Unit 2 turbine control system upgrades for main turbine and main feed pump turbine electrohydraulic control on November 16, 2021
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (8 Samples)
The inspectors evaluated the following post-maintenance test activities to verify system operability and functionality:
- (1) Unit 2 refueling machine 2H-1 following console replacement on October 21, 2021
- (2) Unit 2 containment cooling fan 2VSF-1D following maintenance on November 5, 2021
- (3) Unit 2 turbine-driven emergency feedwater pump 2P-7A following governor upgrade on November 25, 2021
- (4) Unit 2 low-pressure safety injection motor-operated valve 2CV-5063-2 following maintenance on December 6, 2021
- (5) Unit 2 pressurizer safety valve 2PSV-4634 following maintenance on December 8, 2021
- (6) Unit 2 containment spray valve 2CV-5612-1 following maintenance on December 10, 2021
- (7) Unit 1 service water inlet to reactor building cooling coil valve CV-3813 following maintenance on December 15, 2021
- (8) Unit 2 pressurizer heaters following maintenance on December 29, 2021
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated Unit 2 Refueling Outage 28 activities from October 1 to December 5, 2021.
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
- (1) Unit 2 high pressure safety injection system full flow test on November 29, 2021
- (2) Unit 2 low pressure safety injection system full flow test on November 29, 2021
- (3) Unit 2 response time testing for low departure from nucleate boiling ratio trip from reactor coolant pump speed coastdown on December 7, 2021
Inservice Testing (IP Section 03.01) (2 Samples)
- (1) Unit 2 containment spray isolation valve 2CV-5612-1 on November 2, 2021
- (2) Unit 2 containment spray pump suction check valve 2BS-3A on November 4, 2021
Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)
- (1) Unit 2 main feedwater to steam generator A containment isolation valve 2CV-1023-2 test on November 12, 2021
71114.06 - Drill Evaluation
Drill/Training Evolution Observation (IP Section 03.02) (2 Samples)
The inspectors evaluated:
- (1) The Yellow emergency response organization team emergency operations facility drill on December 9, 2021.
- (2) The Green emergency response organization team emergency operations facility drill on December 16,
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
MS09: Residual Heat Removal Systems (IP Section 02.08)===
- (1) Unit 1 (October 1, 2020, through September 30, 2021)
- (2) Unit 2 (October 1, 2020, through September 30, 2021)
MS10: Cooling Water Support Systems (IP Section 02.09) (2 Samples)
- (1) Unit 1 (October 1, 2020, through September 30, 2021)
- (2) Unit 2 (October 1, 2020, through September 30, 2021)
71152 - Problem Identification and Resolution (PI&R)
Semiannual Trend Review (IP Section 02.02) (1 Sample)
- (1) The inspectors reviewed the licensees corrective action program for potential adverse trends in the resolution of problems that might be indicative of a more significant safety issue.
Annual Follow-up of Selected Issues (IP Section 02.03) (3 Samples)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) Common feedwater human-machine interface problems on December 9, 2021
- (2) Unit 2 magnesium rotor, motor-operated valve motor inspections and replacements on December 17, 2021
- (3) Emergency feedwater A pump steam supply check valve 2MS-39B on December 17, 2021
71153 - Follow Up of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)
The inspectors evaluated the following licensee event reports (LERs):
- (1) LER 05000368/2021-001-00, Non-Compliance with Technical Specifications Resulting in Lack of Nuclear Instrumentation Audible Indication (ADAMS Accession No. ML21323A180). The inspection conclusions associated with this LER and an associated non-cited violation are documented in the Inspection Results section of this report.
Personnel Performance (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated the trip of Unit 1 due to the loss of main feed pump B and the licensees performance on November 29,
INSPECTION RESULTS
Observation: Semiannual Trend 71152 Through a review of recent issues documented in the licensees corrective action program, the inspectors were concerned that there may exist a trend of inadequate resolution of problems at Arkansas Nuclear One. The inspectors were concerned that if problems were inadequately addressed then the safety performance of the plant could degrade. The following examples illustrate where inadequate or incomplete resolution of problems could result in vulnerabilities and potential challenges to plant operations.
Magnesium Rotor Motor-Operated Valves (MOVs)
Failures of magnesium motor rotors in motor-operated valves has been a long-known industry issue (NRC Information Notice 2006-26). However, the licensee had not aggressively addressed an inspection and replacement strategy for magnesium rotors in the plant until 2021. During the recent 2021 Unit 2 2R28 refueling outage, 7 out of 10 MOVs failed their inspections and the remaining 3 passed with degradation.
Emergency Feedwater Steam Supply Check Valves ANO has experienced repetitive failures of emergency feedwater steam supply check valves and these failures have been the subject of previous NRC enforcement (NRC Inspection Report 05000313/2018011 and 05000368/2018011; ADAMS Accession No. ML18295A382).
Unit 1 implemented a modification in 2020 (Engineering Change 84422) to maintain the steam supply isolation valve upstream of one of the affected check valves in the closed position during normal operation. This has appeared to have eliminated or reduced check valve damage due to chattering. Unit 2 identified a failed check valve during the recent 2R28 refueling outage and replaced the valve. However, the cause of check valve chattering has not been addressed on Unit 2 in a similar way as it was for Unit 1.
Watertight Door Degradation Unit 2 has had multiple problems with degrading door closure devices, incorrect placement of door closure devices after personnel ingress or egress, and degraded door closure alarms.
Incorrect Size Motor-Operated Valves Control Power Fuse After a fuse was found to have blown in the control power circuit for the train A refueling water tank outlet valve motor-operated valve 2CV-5630-1, the licensee identified that the incorrect size fuse had been installed. The licensee determined it was not necessary to perform an inspection of a sample of other motor-operated valve control circuits to determine if a similar condition existed elsewhere.
Secondary Plant Degraded or Nonconforming Conditions Unit 1 has had repetitive leaks of moisture separator reheater gland sealing steam supply check valves which has caused lifting of relief valves and steam leaks in the turbine building.
One of these, for example, is valve PSV-6805, whose relief tailpipe is near conduit containing reactor protection system cables. Although the cables were checked as currently functional, the conduits continue to be subjected to wet steam.
At the conclusion of the recent Unit 2 2R28 refueling outage, the licensee identified a seal water flange leak on the Unit 2 main feedwater pump B, which required repair before it could be placed in service during power escalation. The leak was attributed to incorrect bolting material and torque applied during maintenance during the outage. Through a review of maintenance records, the licensee identified the same incorrect bolting and torque condition existed on main feedwater pump A from maintenance performed during a previous outage.
Since the A pump was not experiencing leakage and repairing the pump would require swapping operating man feedwater pumps and breaking vacuum on the A pump, the license decided to continue with power escalation. The licensee added an action to repair the joint during the next outage. Failure of the joint in the interim would require downpowering the unit and removing the pump from service to complete the repair.
Failure to Maintain a Source Range Neutron Flux Monitor Audible in the Control Room as Required by Technical Specifications Cornerstone Significance Cross-Cutting Aspect Report Section Barrier Integrity Green NCV 05000368/2021004-01 Open/Closed
[H.7] -
Documentation 71153 The inspectors identified a Green finding and associated non-cited violation of Arkansas Nuclear One, Unit 2, Technical Specification 3.9.2 for the licensees failure to have a source range neutron flux monitor with audible indication in the control room while in Mode 6.
Description:
On October 1, 2021, while Arkansas Nuclear One (ANO), Unit 2, was operating in Mode 6 during a refueling outage and staff were performing control element assembly uncoupling, the inspectors noted there was no source range nuclear instrumentation audible in the control room. When the inspectors brought this to the attention of the shift manager, operators determined the volume setting of the instrument had been turned down to an inaudible level. The licensee then promptly increased its volume in the control room to an audible level and also confirmed it was audible inside the containment building. Technical Specification 3.9.2 requires two source range neutron flux monitors operating, each with continuous visual indication in the control room and one with audible indication in the containment and control room at all times during Mode 6.
The licensee completed a performance analysis of the event and determined that operability of both source range neutron flux monitors and their audible indication had been demonstrated on September 28, 2021, during completion of the Mode 6 entry checklist contained in Procedure OP-2103.011, Draining the Reactor Coolant System, Revision 62.
The performance analysis documented that operators turned down the volume of the audible indication in the control room because it was considered a distraction. Additionally, the operations checklist in effect, OPS-B40, Shutdown Cooling Log/Task Checklist, Revision 06/11/2021, identified that the mode of applicability for having audible counts in containment or the control room was only irradiated fuel moves or new fuel moves over irradiated fuel. Although the checklist referenced Technical Specification 3.9.2, operators did not recognize the checklist disagreed with the requirements of Technical Specification 3.9.2.
Corrective Actions: The licensee promptly restored the audible indication in the control room and revised checklist OPS-B40 to require checking operation of audible source range neutron flux indication each shift while in Mode 6. A condition report was written with corrective actions to complete a performance analysis of the event, to review other checklists to determine if there were similar discrepancies with technical specifications, to perform a training needs analysis, and to revise the process for making changes to operations logs and checklists to make it more formal and aligned with the procedure change process.
Corrective Action References: Condition Report CR-ANO-2-2021-01980
Performance Assessment:
Performance Deficiency: The inspectors determined the failure to have a source range neutron flux instrument with audible indication in the control room while in Mode 6, as required by Technical Specification 3.9.2, was a performance deficiency.
Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Procedure Quality attribute of the Barrier Integrity cornerstone and adversely affected the cornerstone objective to provide reasonable assurance that physical design barriers protect the public from radionuclide releases caused by accidents or events. Specifically, the licensee did not maintain operable audible indication of source range neutron flux in the control room as required by Technical Specification 3.9.2, to monitor the core reactivity condition.
Significance: The inspectors assessed the significance of the finding using Appendix G, Shutdown Safety SDP because the performance deficiency occurred when the plant was shut down in Mode 6. Using the Exhibit 4 Barrier Integrity screening questions of IMC 0609, Appendix G, Attachment 1, the finding:
- (1) did not involve protection of the reactor pressure vessel against fracture;
- (2) did not involve fuel bundle misplacement or misorientation;
- (3) did not involve low temperature over pressurization;
- (4) did not involve a freeze seal;
- (5) did not involve steam generator nozzle dams;
- (6) did not involve the potential for, or an actual, reactor coolant system boron dilution event;
- (7) did not involve a drain down or leakage path; and
- (8) did not involve the containment barrier. Therefore, the finding screened as very low safety significance (Green).
Cross-Cutting Aspect: H.7 - Documentation: The organization creates and maintains complete, accurate and up-to-date documentation. Specifically, the licensee did not maintain an accurate checklist for ensuring source range neutron flux instrumentation was audible in the control room and containment in Mode 6. The mode of applicability identified in the checklist for this requirement was incorrect.
Enforcement:
Violation: Technical Specification 3.9.2 for Unit 2 requires in Mode 6 that two source range neutron flux monitors shall be operating, each with continuous visual indication in the control room and one with audible indication in the containment and control room.
Contrary to the above, on October 1, 2021, while Unit 2 was in Mode 6, the licensee failed to have a neutron flux monitor operating with audible indication in the control room.
Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On October 7, 2021, the inspectors presented the Arkansas Nuclear One Unit 2 inservice inspection results to Mr. J. Dinelli, Site Vice President, and other members of the licensee staff.
On January 13, 2022, the inspectors presented the integrated inspection results to Mr. J. Sullivan, Site Vice President, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Calculations
CALC-ANOC-CS-15-
00003
ANO Flood Protection Design Basis
Calculations
CALC-ANOC-CS-15-
00012
ANO Flood Protection Room Evaluations - Units 1 and 2
Calculations
CALC-ANOC-CS-16-
00005
Arkansas Nuclear One Passive Barrier Features List
Corrective Action
Documents
CR-ANO-
1-2021-00335, 2-2021-00463, C-2021-00406, C-2021-
00470,
Miscellaneous
CES-02
ANO-1 General Structural Design Guide
Miscellaneous
CES-03
ANO-2 General Structural Design Guide
Miscellaneous
ULD-0-TOP-17
ANO Flooding
Procedures
OP-1104.039
Plant Heating and Cold Weather Operations
Procedures
OP-2106.032
Unit Two Freeze Protection Guide
Work Orders
Corrective Action
Documents
CR-ANO-
1-2021-00137, 1-2021-00201, 1-2021-00212, 1-2021-
263, 1-2021-03017, 1-2021-03302, C-2021-01942, C-
21-01996, C-2021-02842, C-2021-02877
Drawings
M-2204
Piping & Instrumentation Diagram Emergency Feedwater
Drawings
M-232, Sheet 1
Decay Heat Removal System
111
Drawings
M-236, Sheet 1
Reactor Building Spray and Core Flooding Systems
Engineering
Changes
ANO-2 EFW Pump Woodward Governor Controls
Upgrade 2R28
Miscellaneous
STM 1-08
Reactor Building Spray and Containment Building
Miscellaneous
STM 2-19-2
ANO Unit 2 System Training Manual, Emergency
Feedwater and Auxiliary Feedwater Systems
Procedures
OP-1104.005
Reactor Building Spray System Operation
85, 89
Procedures
OP-1106.007
Common Feedwater System
Procedures
OP-2106.006
Emergency Feedwater Pump Operation
104
Work Orders
WO 485548, 485557, 52940565
Corrective Action
Documents
CR-ANO-
1-2018-00004, 1-2021-03263, C-2021-03101
Drawings
FP-105, Sheet 1
Fire Zone Plan Below Grade Elev. 335-0
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Drawings
FZ-1032, Sheet 1
Fire Zone Detail No. & So. Diesel Gener. Room
Drawings
FZ-1072, Sheet 1
Fire Zone Detail Lower South Piping Penetration Area,
EFWP Area
Fire Plans
Unit 1 PreFire Plan
Fire Zone 75-AA Ammonia Tank Room & Main Steam
Lines
Miscellaneous
Unit 1 and 2 Fire Hazards Analysis
Miscellaneous
Unit 1 PreFire Plans
Miscellaneous
Fire Zones 86-G and 87-G North and South EDG Rooms
Procedures
OP-1203.009
Fire Protection System Annunciator Corrective Action
Procedures
OP-1203.049
Fires in Areas Affecting Safe Shutdown
Calculations
CALC-ANOC-CS-15-
00003
ANO Flood Protection Design Basis
Calculations
CALC-ANOC-CS-15-
00012
ANO Flood Protection Room Evaluations - Units 1 and 2
Miscellaneous
ULD-0-TOP-17
ANO Flooding
Corrective Action
Documents
CR-ANO-
2-2021-02893, 2-2021-02952, 2-2021-02953, 2-2021-
03344, 2-2021-03347, 2-2021-03664
Miscellaneous
CALC-91-R-2013-01
Service Water Performance Testing Methodology
Miscellaneous
CALC-95-R-0014-02
Test Protocol - Unit 2 Shutdown Cooling Heat Exchanger
Thermal Performance Test
Procedures
OP-2311.001
Shutdown Cooling Heat Exchanger Performance Test
Work Orders
WO 474776, 548828, 52358635, 52466000, 52674944,
2939676
Calculations
CALC-16-E-0300-01
ANO Unit 2 RVCH Nozzle Peening Stress Evaluation
Calculations
CALC-85-E-0053-50
Fire Area B-1 Combustible Loading Calculation
Corrective Action
Documents
CR-ANO-
2-2001-00467, 2-2005-01870, 2-2011-03653, 2-2016-
01065, 1-2021-01834, 1-2021-02816, 2-2016-01519, 2-
2018-00695, 2-2018-04153, 2-2019-00125, 2-2019-
00780, 2-2019-01025, 2-2019-01955, 2-2019-02417, 2-
20-00629, 2-2020-00720, 2-2020-00755, 2-2020-
00867, 2-2020-01076, 2-2020-01205, 2-2020-01258, 2-
20-01311, 2-2020-01328, 2-2020-01330, 2-2020-
01345, 2-2020-01346, 2-2020-01347, 2-2020-01348, 2-
20-01349, 2-2020-01373, 2-2020-01375, 2-2020-
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
01381, 2-2020-01409, 2-2020-01410, 2-2020-01589, 2-
20-01633, 2-2020-01651, 2-2020-01656, 2-2020-
01658, 2-2020-01660, 2-2020-01667, 2-2020-01675, 2-
20-01681, 2-2020-01702, 2-2020-01706, 2-2020-
01712, 2-2020-01738, 2-2020-01760, 2-2020-01761, 2-
20-01770, 2-2020-01775, 2-2020-01778, 2-2020-
01781, 2-2020-01788, 2-2020-01802, 2-2020-01837, 2-
20-01888, 2-2020-01962, 2-2020-01972, 2-2020-
2199, 2-2020-02309, 2-2020-02320, 2-2020-02479, 2-
20-02674, 2-2020-02709, 2-2020-03024, 2-2020-
03025, 2-2020-03258, 2-2020-03575, 2-2020-03801, 2-
20-03838, 2-2020-03951, 2-2021-00370, 2-2021-
00739, 2-2021-00863, 2-2021-00926, 2-2021-01597, 2-
21-01753, 2-2021-01758, 2-2021-01759, 2-2021-
01767, 2-2021-01769, 2-2021-01771, 2-2021-01800, 2-
21-01896, C-2021-02474, C-2021-02500, CR-GGN-
21-01236, CR-GGN-2021-02184
Drawings
Large Pipe Isometric Blowdown Line 2DBD-9
from 2CV-1016-1 to 2CV-1017
Drawings
P-32 D Seal Press
Drawings
E-234-763
Closure Head Assembly Arkansas Nuclear
Drawings
E6473E40
CEDM Cooling Shroud Upgrade Assembly
Drawings
M-2001-C2-111
As-Built: EC 80291, 80388
303
Engineering
Changes
ANO-2 EFPY Projection to 32 EFPY as of 8/1/17
000
Engineering
Changes
Reduce Scope EC80256 - CEDM Id. Surface
Improvement Only
Engineering
Evaluations
LEC-1485-R1
Seal Life Evaluation of Lisega Reactor Coolant Pump
Snubbers Arkansas Nuclear One, Unit 2
Miscellaneous
157-9338580-002
Repair of ANO-2 CEDM Penetration 46
Miscellaneous
Inservice Inspection Summary Report for the Twenty-
Seventh Refueling Outage (2R27)
07/08/2020
Miscellaneous
Relief Request ANO2-R&R-012 Support the Repair of the
Reactor Vessel Closure Head Penetration #46
10/10/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
50-9338579
Completed Repair Traveler with Weld Package and NDE
Reports
Miscellaneous
51-9287972-000
ANO Unit 2 Degradation Assessment for 2R26 - Fall
2018
000
Miscellaneous
51-9293037-000
ANO Unit 2 Condition Monitoring for 2R26 and Final
Operational - Assessment for Cycles 27, 28, and 29
000
Miscellaneous
CALC-ANO2-EP-20-
00003
ANO-2 Steam Generator Secondary Side Integrity Plan
Revision 2
01/25/2021
Miscellaneous
CARK2-RV030-TR-
CF-000001
Justification for 50% Relaxation Factor for ANO 2 Laser
Peening Surface Stress Acceptance Criterion
0-A
Miscellaneous
CEP-BAC-001
Boric Acid Corrosion Control (BACC) Program Plan
Miscellaneous
Boric Acid Corrosion Control Program (BACCP)
Miscellaneous
Chemical Control Program
Miscellaneous
ER-ANO-2003-0245-
058
Document Effective Degradation Years (EDY) for ANO-2
Head at Start of 2R18
Miscellaneous
ER-ANO-2006-0266-
000
Guidance for Concrete Repair of Intake Structure Stairwell
Opening in Slab at El. 366'-0
Miscellaneous
LTR-SDA-18-124
ANO 2 Reactor Vessel Head Penetration Peening
Mitigation Sketches
Miscellaneous
Materials Reliability Program: Technical Basis for Primary
Water Stress Corrosion Cracking Mitigation by Surface
Stress Improvement
Miscellaneous
Materials Reliability Program: Topical Report for Primary
Water Stress Corrosion Cracking Mitigation by Surface
Stress Improvement
3-A
Miscellaneous
Materials Reliability Program: Specification Guideline for
Primary Water Stress Corrosion Cracking Mitigation by
Surface Stress Improvement
Miscellaneous
SEP-BAC-ANO-001
Boric Acid Corrosion Control Program Inspection and
Identification of Boric Acid Leaks for ANO-1 and ANO-2
Miscellaneous
SEP-ISI-ANO2-105
ASME Section XI, Division 1, ANO-2 Inservice Inspection
Program
Miscellaneous
SPEC-ANO-M-2555
Unit 2 Piping Class Sheets
Miscellaneous
Technical Basis for Laser Peening (LP) of ANO 2 Reactor
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Vessel Head Penetrations (RVHP)
Miscellaneous
WDI-TJ-1122
ASME Section V, Article 14, Technical Justification for
Dye Penetrant Examination of Reactor Vessel Head
Penetration Wetted Surface
NDE Reports
Visual Inspection Service for 42 Pipe at Arkansas
Nuclear One Plant Unit 2
11/08/2021
Procedures
CEP-NDE-0404
Manual Ultrasonic Examination of Ferritic Piping Welds
(ASME XI)
Procedures
CEP-NDE-0407
Straight Beam Ultrasonic Examination of Bolts and Studs
(ASME XI)
Procedures
CEP-NDE-0423
Manual Ultrasonic Examination of Austenitic Piping Welds
(ASME XI)
Procedures
CEP-NDE-0504
Ultrasonic Examination of Small Bore Diameter Piping for
Thermal Fatigue Damage
Procedures
CEP-NDE-0640
Description - Liquid Dye Penetrant Procedure
Procedures
CEP-NDE-0901
VT-1 Examination
Procedures
CEP-NDE-0902
VT-2 Examination
Procedures
CEP-NDE-0903
VT-3 Examination
Procedures
CEP-NDE-0955
Visual Examination (VE) of Bare-Metal Surfaces
308
Procedures
Control of Combustibles
Procedures
Limitorque Valve Operator Model SMB/SB/SBD-000
Through 5 MOV and HBC Periodic Inspection
Procedures
WDI-STD-1041
Reactor Vessel Head Penetration Ultrasonic Examination
Analysis
Procedures
WPS-CS-1/1-A
Manual Gas Tungsten Arc Welding (GTAW) and Shielded
Metal Arc Welding (SMAW) of P-No. 1 Carbon Steels
Procedures
WPS-CS-1/1-B
Manual Gas Tungsten Arc Welding (GTAW) of P-No. 1
Carbon Steels
Procedures
WPS-LA-5A/1-A
Manual Gas Tungsten Arc Welding (GTAW) and Shielded
Metal Arc Welding (SMAW) of P-No. 5A Low Alloy Steels
to P-No. 1 Carbon Steels
Procedures
WPS-LA-5A/5A-A
Manual Gas Tungsten Arc Welding (GTAW) and Shielded
Metal Arc Welding (SMAW) of P-No. 5A Low Alloy Steels
Procedures
WPS-SS-8/8-B
Manual Gas Tungsten Arc Welding (GTAW) of P-No. 8
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Stainless Steels
Self-
Assessments
Pre-NRC 2R28 ISI Activities Self-Assessment Report
05/18/2021
Work Orders
WO-ANO-
087669, 300901, 522875, 540245, 541519, 542001,
2781192, 52857697, WR-ANO-076667, WR-ANO-
258250
Miscellaneous
A2SPGLORTCSJITT
Procedures
2102.001
Plant Pre-Heatup and Pre-Critical Checklists
Procedures
2102.002
Plant Heatup
Procedures
2102.004
Power Operation
Procedures
2102.016
Reactor Startup
Corrective Action
Documents
CR-ANO-
1-2021-01551, 1-2021-01664, 1-2021-02781, 1-2021-
2844, 1-2021-02938, 1-2021-02977, 1-2021-02978, 1-
21-02992, 1-2021-03011, 1-2021-03110, 2-2021-
01343, 2-2021-01362, 2-2021-01481, 2-2021-01495, 2-
21-01570, 2-2021-01964, 2-2021-01981, 2-2021-
247, 2-2021-02855, 2-2021-02880, 2-2021-03027, 2-
21-03032, 2-2021-03355, 2-2021-03507, 2-2021-
03756, C-2021-02880
Miscellaneous
Standardized Operations Metrics
Miscellaneous
CALC-15-E-0007-20
Reduced Latching Requirements for Watertight Doors
Miscellaneous
CALC-95-R-0024-01
Basic Requirements for the Component Database on
Station Doors and Hatches
Miscellaneous
CALC-ANOC-CS-15-
00012
ANO Flood Protection Room Evaluations - Units 1 and 2
Miscellaneous
CALC-ANOC-SE-20-
00001
Maintenance Rule 10CFR50.65 (a)(3) Periodic
Assessment January 1, 2019 to June 30, 2020
Miscellaneous
Focused Self-Assessment for Upcoming Phase 4 License
Renewal NRC Inspection
08/23/2021
Miscellaneous
STM 1-66
Emergency Feedwater Initiation and Control
Procedures
COPD-013
Operations Maintenance Interface Standards and
Expectations
Procedures
Maintenance Rule Monitoring Procedure
Procedures
Maintenance Rule A(1) Process
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
EN-FAP-OP-023
Operations Performance Indicators
Procedures
OP-1105.005
Emergency Feedwater Initiation and Control
Procedures
OP-1304.041
Unit 1 Reactor Protection System Channel A Calibration
Procedures
OP-1402.100
Watertight Door Maintenance
Work Orders
WO 495653, 52918059
Corrective Action
Documents
CR-ANO-
1-2021-02896
Procedures
On-Line Risk Assessment
Corrective Action
Documents
CR-ANO-
1-2021-01664, 1-2021-03032, 1-2021-03136, 1-2021-
03183, 2-2019-00887, 2-2020-01594, 2-2021-01281, 2-
21-01597, 2-2021-02416, 2-2021-02534, 2-2021-
2770, 2-2021-02988, 2-2021-02989, C-2021-03142
Drawings
M-2236, Sheet 1
Engineering
Changes
Inlet to 2P-35A Containment Spray Over Pressure
Miscellaneous
0062-0213-LTR-001
Evaluation of ANO MOV-2CV-1023-2 for Continued
Operation
Miscellaneous
CALC-15-E-0007-20
Reduced Latching Requirements for Watertight Doors
Miscellaneous
CALC-95-R-0024-01
Basic Requirements for the Component Database on
Station Doors and Hatches
Miscellaneous
CALC-ANOC-CS-15-
00012
ANO Flood Protection Room Evaluations - Units 1 and 2
Miscellaneous
FHA20
Fire Hazards Analysis
Procedures
EN-EP-S-003-MULTI
ENS Magnesium Rotor MOV Management Plan
Procedures
Use of VIPER or VOTES Infinity Motor Operated Valve
Diagnostics
and 8
Procedures
OP-2104.005
Procedures
OP-2202.003
Loss of Coolant Accident
Work Orders
WO 548076, 556664, 50234647, 52936561
Corrective Action
Documents
CR-ANO-
2-2021-01631, 2-2021-01634, 2-2021-02198, 2-2021-
220, 2-2021-02415, 2-2021-02507, 2-2021-02510, 2-
21-02566, 2-2021-02688, 2-2021-02703, 2-2021-
2841, 2-2021-02950
Engineering
Evaluate Temporary Modification to Provide Alternate
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Changes
Source of Power to Spent Fuel Pool Cooling Pump 2P-
40A or 2P-40B
Engineering
Changes
Evaluate and Provide Guidance for Providing Temp
Power to Both Unit 2 SFP Cooling Pumps 2P-40A and
Miscellaneous
FFN-2021-003
Turbine Control System Upgrades for Main Turbine and
Main Feed Pump Turbine Digital Electro-Hydraulic
Control/ EC 83032
Miscellaneous
FCR 89720/ANO Unit 2 Refuel Machine Upgrade EC 83562 FCR
Miscellaneous
ULD-0-SYS-03
ANO New and Spent Fuel Storage, Spent Fuel Cooling,
New and Spent Fuel Handling Systems
Procedures
Process Applicability Determination
Procedures
CFR 50.59 Evaluations
Procedures
OP-2104.006
Fuel Pool Systems
Procedures
OP-2203.002
Spent Fuel Pool Emergencies
Procedures
OP-2503.003
Operation of Fuel Handling Equipment
Corrective Action
Documents
CR-ANO-
2-2020-01858, 2-2020-01911, 2-2021-00728, 2-2021-
2339, 2-2021-02502, 2-2021-02542, 2-2021-02594, 2-
21-02626, 2-2021-02649, 2-2021-02651, 2-2021-
2684, 2-2021-02700, 2-2021-03394, 2-2021-03415, 2-
21-03655, C-2021-02669,
Drawings
M-2204
Piping & Instrumentation Diagram Emergency Feedwater
Drawings
M-2236, Sheet 1
Engineering
Changes
ANO-2 EFW Pump Woodward Governor Controls
Upgrade 2R28
Miscellaneous
ECT 77577-003
Post Modification Online Test of Unit 2 EFW Digital
Governor
Miscellaneous
STM 2-19-2
ANO Unit 2 System Training Manual, Emergency
Feedwater and Auxiliary Feedwater Systems
Procedures
Post Maintenance Testing
Procedures
OP-1025.019
System Cleanliness Controls During Modification and
Maintenance
Procedures
OP-1104.033
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
OP-2103.005
Pressurizer Heater Operations
Procedures
OP-2104.001
Safety Injection Tank Operations
Procedures
OP-2104.005
Procedures
OP-2104.033
Containment Atmosphere Control
Procedures
OP-2106.006
Emergency Feedwater Pump Operation
104
Procedures
OP-2107.001
Electrical System Operations
135
Procedures
OP-2305.006
Cold Shutdown Valve Testing
Procedures
OP-2307.009
Pressurizer Proportional Heater Checkout
Procedures
OP-2402.132
Installation of the U2 Pzr Code Relief Valves
Procedures
OP-2502.003
Preparation for Refueling
Procedures
Pressurizer
Proportional Heater
Checkout
Pressurizer Heater Removal and Replacement
Work Orders
WO 457653, 518475, 543054, 547623, 547788, 547805,
548457, 52937865
Corrective Action
Documents
CR-ANO-
2-2021-02594, 2-2021-02602
Procedures
2102.001
Plant Pre-Heatup and Pre-Critical Checklists
Procedures
2102.002
Plant Heatup
Procedures
2102.004
Power Operation
Procedures
2102.016
Reactor Startup
Corrective Action
Documents
CR-ANO-
2-2021-01597, 2-2021-01855, 2-2021-02770, 2-2021-
2804, 2-2021-02830, 2-2021-02988, 2-2021-02989
Drawings
M-2206, Sheet 1
Steam Generator Secondary System
156
Drawings
M-2236, Sheet 1
Miscellaneous
Unit 2 Updated Final Safety Analysis Report, Table
15.1.0-1
Miscellaneous
Unit 2 Narrative Log
11/12/2021
Miscellaneous
CALC-95-R-0011-08
ANO 2 GL 89-10 MOV Safety Significance Determination
Miscellaneous
ULD-2-SYS-05
Containment Spray System
Procedures
OP-2104.005
Procedures
OP-2104.039
HPSI System Operation
Procedures
OP-2104.040
LPSI System Operations
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
OP-2304.112
Plant Protection System Response Time Test Ch A
Procedures
OP-2305.005
Valve Stroke and Position Verification
Work Orders
WO 518526-32, 525716-01, 543054, 548076, 548826-01,
549055-04, 52932027
Miscellaneous
Arkansas Nuclear One Emergency Plan
Procedures
1903.010
Emergency Action Level Classification
Procedures
1903.011
Emergency Response/Notifications
71151
Miscellaneous
ANO-1 and ANO-2 NRC Performance Indicator
Technique/Data Sheets - Residual Heat Removal
Q4-2020
71151
Miscellaneous
ANO-1 and ANO-2 NRC Performance Indicator
Technique/Data Sheets - Residual Heat Removal
Q1-2021
71151
Miscellaneous
ANO-1 and ANO-2 NRC Performance Indicator
Technique/Data Sheets - Residual Heat Removal
Q3-2021
71151
Miscellaneous
ANO-1 and ANO-2 NRC Performance Indicator
Technique/Data Sheets - Cooling Water System
Q1-2021
71151
Miscellaneous
ANO-1 and ANO-2 NRC Performance Indicator
Technique/Data Sheets - Cooling Water System
Q2-2021
71151
Miscellaneous
ANO-1 and ANO-2 NRC Performance Indicator
Technique/Data Sheets - Cooling Water System
Q3-2021
71151
Miscellaneous
ANO-1 and ANO-2 NRC Performance Indicator
Technique/Data Sheets - Cooling Water System
Q4-2020
71151
Miscellaneous
ANO-1 and ANO-2 NRC Performance Indicator
Technique/Data Sheets - Residual Heat Removal
Q2-2021
Corrective Action
Documents
CR-ANO-
2-2000-00751, 2-2021-00060, 2-2021-01597, 2-2021-
01772, 2-2021-01834, 2-2021-02061, 2-2021-02234, 2-
21-02245, 2-2021-02304, 2-2021-02313, 2-2021-
2339, 2-2021-02496, 2-2021-02562, 2-2021-02693, 2-
21-02770, 2-2021-03658, 2-2021-03756, C-2018-
03443, C-2018-04349, C-2021-00614, C-2021-02730, C-
21-02842
Drawings
M-2202, Sheet 4
Lube Oil, Lube Oil Cooling, Electro/Hydraulic Controls and
Drawings
M-2206, Sheet 1
Steam Generator Secondary System
154
Engineering
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Changes
Miscellaneous
ANO-1 Technical Requirements Manual
Miscellaneous
ANO-2 Technical Requirements Manual
Miscellaneous
CALC-92-E-0077-09
Design Basis for ANO Common Feed Water System Flow
Miscellaneous
SEP-ANO-2-IST-
1_008
ANO Unit 2 Inservice Testing Bases Document
Miscellaneous
STM 1-26
Common Feedwater System
Miscellaneous
ULD-2-SYS-12
ANO-2 Emergency Feedwater System
Procedures
1015.008
Unit 2 SDC Control
Procedures
2402.017
Unit 2 CEA Extension Shaft Uncoupling Using Scout Tool
Procedures
EN-EP-S-003-MULTI
ENS Magnesium Rotor MOV Management Plan
Procedures
OP-1106.007
Common Feedwater System
Procedures
OP-2106.006
Emergency Feedwater System Operations
106
Procedures
OP-2402.089
2MS-39 A/B Check Valve Maintenance
Procedures
OP-5120.140
Check Valve Disassembly and Inspection
Work Orders
WO 545479, 546187, 554463
Corrective Action
Documents
CR-ANO-
1-2021-03129, 2-2021-01980
Miscellaneous
Unit 2 Technical Specifications
25-B82
Procedures
1102.002
Plant Startup
116
Procedures
1102.004
Power Operation
Procedures
1102.008
Approach to Criticality
Procedures
202.001
Procedures
2103.011
Draining the Reactor Coolant System
Procedures
2502.001
Refueling Shuffle
61