IR 05000313/2024001
| ML24127A096 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 05/08/2024 |
| From: | John Dixon NRC/RGN-IV/DORS/PBD |
| To: | Pehrson D Entergy Operations |
| References | |
| IR 2024001 | |
| Download: ML24127A096 (17) | |
Text
May 08, 2024
SUBJECT:
ARKANSAS NUCLEAR ONE - INTEGRATED INSPECTION REPORT 05000313/2024001 AND 05000368/2024001
Dear Doug Pehrson:
On March 31, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Arkansas Nuclear One. On April 11, 2024, 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, John L. Dixon, Jr., Chief Reactor Projects Branch D Division of Operating Reactor Safety Docket Nos. 05000313, 05000368 License Nos. DPR-51, NPF-6
Enclosure:
As stated
Inspection Report
Docket Nos.
05000313, 05000368
License Nos.
Report Nos.
05000313/2024001, 05000368/2024001
Enterprise Identifier:
I-2024-001-0008
Licensee:
Entergy Operations, Inc.
Facility:
Arkansas Nuclear One
Location:
Russellville, AR
Inspection Dates:
January 1, 2024, to March 31, 2024
Inspectors:
T. DeBey, Resident Inspector
R. Kopriva, Senior Project Engineer
T. McGowan, Acting Senior Resident Inspector
A. Sanchez, Senior Project Engineer
Approved By:
John L. Dixon, Jr., Chief
Reactor Projects Branch D
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Arkansas Nuclear One, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.
List of Findings and Violations
Failure to Properly Evaluate Reactor Coolant System Leakage for Emergency Plan Declarations Cornerstone Significance Cross-Cutting Aspect Report Section Emergency Preparedness Green NCV 05000313/2024001-01 Open/Closed
[H.12] - Avoid Complacency 71111.11Q The inspectors identified a Green finding and associated non-cited violation of 10 CFR Part 50, appendix E, section IV.C(2), for the licensees failure to establish and maintain the capability to assess, classify, and declare an emergency condition for reactor coolant system leakage that would be timely and accurate. Specifically, the licensee failed to properly calculate reactor coolant system leakage when the water volume being assessed has a density that is significantly different from the reactor coolant system water that is lost from the system.
Additional Tracking Items
Type Issue Number Title Report Section Status LER 05000313/2023-001-00 Automatic Reactor Trip due to Reactor Protection System Actuation 71153 Closed
PLANT STATUS
Unit 1 began the period at full power. On January 21, 2024, Unit 1 experienced an automatic down power to approximately 78 percent due to a false indication of a failed reactor coolant pump input to the integrated control system. The erroneous signal was removed, and the unit was returned to full power later that same day. Unit 1 operated at full power for the remainder of the inspection period.
Unit 2 began the period at full power and remained there for the remainder of the inspection period.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors performed activities described in IMC 2515, Appendix D, Plant Status, observed risk significant activities, and completed on-site portions of IPs. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
REACTOR SAFETY
71111.01 - Adverse Weather Protection
Impending Severe Weather Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the adequacy of the overall preparations to protect risk-significant systems from impending severe cold weather on January 11, 2024.
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (2 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Unit 2 reactor protection system during work on the control element drive system on February 6, 2024
- (2) Unit 2 emergency diesel generator train A, during train B inoperability for surveillance activities on March 3, 2024
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:
- (1) Unit 2 vital dc equipment room, fire zone FZ-2056, on January 3, 2024
- (2) Unit 2 corridor to emergency diesels and battery rooms, fire zone FZ-2049, on January 4, 2024
- (3) Unit 1 main control room, fire zone FZ-1052, on February 6, 2024
- (4) Unit 1 intake structure, fire zones FZ-1030 and FZ-1061, on February 9, 2024
- (5) Unit 1 refuel floor, fire zones FZ-1054 and FZ-1039, on February 26, 2024
Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the onsite fire brigade training and performance during an announced fire brigade drill, with personnel injury, in the Unit 1 south emergency diesel generator room, fire zone FZ-87-H, on February 13, 2024.
71111.06 - Flood Protection Measures
Flooding Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated internal flooding mitigation protections in the Unit 2 auxiliary building (535-foot elevation) on March 21, 2024.
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (2 Samples)
- (1) The inspectors observed and evaluated licensed operator performance in the control room during Unit 2 control element drive troubleshooting, control element movements, and re-pressurization of safety injection tanks on February 14, 2024.
- (2) The inspectors observed and evaluated licensed operator performance in the control room during Unit 1 emergency diesel generator endurance testing on February 17, 2024.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (2 Samples)
- (1) The inspectors observed and evaluated the Unit 1 simulator exercise involving loss of subcooling margin and emergency system actuation on January 12, 2024.
- (2) The inspectors observed and evaluated the Unit 2 simulator exercises involving excess steam demand on February 27 and 28, 2024.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (1 Sample)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
- (1) Unit 1 125 Vdc battery charger (D03B) maintenance to clean and inspect and load test on January 31, 2024
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 emergent power runback to 78 percent due to integrated control system detecting reactor coolant pump trip on January 21, 2024
- (2) Unit 2 vital inverter 2Y-2224 planned work on March 12, 2024
- (3) Unit 1 emergent work to fix seal leakage on high pressure injection pump P-36B on March 28, 2024
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (4 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
(1)operability assessment of emergency diesel generator 2K-4B after failure and replacement of the C current potential transformer on January 23, 2024 (2)functionality assessment of site seismic monitors after failure of two of the monitors on January 24, 2024 (3)functionality assessment of Unit 1 diesel room exhaust fan VEF-24C on March 20, 2024 (4)functionality assessment of the alternate ac generator on March 26, 2024
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 temporary modification for emergency diesel generator hallway heater per operating procedure 2106.032, Unit 2 Freeze Protection Guide revision 33 on January 10, 2024
- (2) Unit 1 temporary modification for integrated control system runback per engineering change EC-54105613, Defeat Loss of Single RCP Runback Feature in ICS on February 29, 2024
- (3) Unit 2 temporary modification for control element drive motor control system power after blown fuses and circuit breaker malfunction on March 8, 2024
71111.24 - Testing and Maintenance of Equipment Important to Risk
The inspectors evaluated the following testing and maintenance activities to verify system operability and/or functionality:
Post-Maintenance Testing (PMT) (IP Section 03.01) (3 Samples)
- (1) Unit 2 emergency diesel generator 2K-4B testing after replacement of associated current potential transformer on January 24, 2024
- (2) Unit 2 service water isolation valve to containment cooling (2CV-1511-1) after relay replacement and major preventive maintenance on March 5, 2024
- (3) Unit 1 sluice gate 6 after major preventive maintenance on March 14, 2024
Surveillance Testing (IP Section 03.01) (8 Samples)
- (1) Unit 1 emergency feedwater pump P-7A valve strokes on January 4, 2024
- (2) Unit 1 low pressure injection pump P-34A quarterly run on January 10, 2024
- (3) Unit 2 emergency diesel generator 2K-4B on February 18, 2024
- (4) Unit 2 core protection calculator B temperature inputs calibration for B reactor coolant system temperature input loops on February 28, 2024
- (5) Unit 1 emergency diesel generator K-4A on March 7, 2024
- (6) Unit 2 emergency diesel generator 2K-4B on March 13, 2024
- (7) Unit 2 plant protection system channel A test on March 19, 2024
- (8) Unit 1 engineered safeguards actuation system analog channel 2 test on March 20, 2024
Inservice Testing (IST) (IP Section 03.01) (1 Sample)
- (1) Unit 2 service water isolation valves to spent fuel pool cooling on January 3, 2024
71114.06 - Drill Evaluation
Required Emergency Preparedness Drill (1 Sample)
- (1) ERO Red team (radiological release drill) on February 13, 2024
Additional Drill and/or Training Evolution (1 Sample)
The inspectors evaluated:
- (1) Unit 1 simulator scenario for turbine control system failures on February 1,
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
IE01: Unplanned Scrams per 7000 Critical Hours Sample (IP Section 02.01)===
- (1) Unit 1 (January 1, 2023, through December 31, 2023)
- (2) Unit 2 (January 1, 2023, through December 31, 2023)
IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02) (2 Samples)
- (1) Unit 1 (January 1, 2023, through December 31, 2023)
- (2) Unit 2 (January 1, 2023, through December 31, 2023)
IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (2 Samples)
- (1) Unit 1 (January 1, 2023, through December 31, 2023)
- (2) Unit 2 (January 1, 2023, through December 31, 2023)
71153 - Follow Up of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)
The inspectors evaluated the following licensee event reports (LERs):
- (1) LER 05000313/2023-001-00, Automatic Reactor Trip due to Reactor Protection System Actuation (Agencywide Documents Access and Management System
[ADAMS] Accession No. ML23104A162). The inspection conclusions associated with this LER are documented in Inspection Report 05000313/2023004 (ML24039A084)under Inspection Results Section 71153. This LER is Closed.
INSPECTION RESULTS
Failure to Properly Evaluate Reactor Coolant System Leakage for Emergency Plan Declarations Cornerstone Significance Cross-Cutting Aspect Report Section Emergency Preparedness Green NCV 05000313/2024001-01 Open/Closed
[H.12] - Avoid Complacency 71111.11Q The inspectors identified a Green finding and associated non-cited violation of 10 CFR Part 50, appendix E, section IV.C(2), for the licensees failure to establish and maintain the capability to assess, classify, and declare an emergency condition for reactor coolant system leakage that would be timely and accurate. Specifically, the licensee failed to properly calculate reactor coolant system leakage when the water volume being assessed has a density that is significantly different from the reactor coolant system water that is lost from the system.
Description:
The inspectors observed a simulator training scenario involving reactor coolant system (RCS) leakage from the pressurizer to the quench tank and noted that no density correction was made even though the leaking water cooled significantly when collecting in the quench tank. The leak rate determination (gpm) was made by assuming that the rate of water level increase in the quench tank (gpm) was equal to the rate of RCS water lost from the pressurizer (gpm). The density changed in the water as it moved from the pressurizer to the quench tank volume caused a nonconservative assessment of the RCS leak rate. The inspector-identified deficiency stemmed from inadequate procedures for identifying RCS leakage that would exceed either 10 gpm or 25 gpm, requiring the declaration of an Unusual Event (UE). Specifically, determination of RCS leakage by water volume changes is done by site Procedures OP-1103.013, RCS Leak Detection, revision 48, and OP-1203.039, Excess RCS Leakage, revision 22.
These procedures may produce leak rate determinations that are significantly nonconservative due to not making an appropriate water density correction. For example, if the rate of RCS leakage from a pressurizer instrument tap leak is determined by the rate of water decrease in the RCS makeup tank, the change of density from the ~110 F makeup tank to the ~650 F pressurizer water will cause a nonconservative error of ~65 percent in the leak rate determination. If unidentified RCS leakage was determined to be causing a makeup tank level decrease of 8 gpm (not a UE entry), the actual RCS (density corrected) leak rate would be ~13.2 gpm (a UE entry for unidentified leakage greater than 10 gpm). Procedure OP-1903.010, Emergency Action Level Classification, revision 62, states that, for RCS leakage, The emergency director should declare the event promptly upon determining that the time limit has been exceeded or will likely be exceeded. The nonconservative leak rate evaluation could delay or prevent the required emergency action level declaration.
Corrective Actions: The licensee documented the RCS leakage assessment concern and is evaluating changes to site procedures and training programs.
Corrective Action References: condition reports CR-ANO-C-2023-03340 and CR-ANO-1-2024-00274
Performance Assessment:
Performance Deficiency: The licensees failure to maintain an appropriate capability to assess, classify, and declare an emergency condition involving excess RCS leakage is 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 Emergency Preparedness cornerstone and adversely affected the cornerstone objective to ensure that the licensee is capable of implementing adequate measures to protect the health and safety of the public in the event of a radiological emergency. Specifically, it could impact the ability to correctly classify a loss of reactor coolant system leakage.
Significance: The inspectors assessed the significance of the finding using IMC 0609, Appendix B, Emergency Preparedness SDP. The finding was determined to be of very low safety significance (Green) because it could result in a Notice of Unusual Event not being declared when it should have been, resulting in a failure to comply with a regulatory requirement associated with a risk-significant planning standard that did not result in the loss or degradation of that risk-significant planning standard function.
Cross-Cutting Aspect: H.12 - Avoid Complacency: Individuals recognize and plan for the possibility of mistakes, latent issues, and inherent risk, even while expecting successful outcomes. Individuals implement appropriate error reduction tools. The inspectors determined that the most significant contributing cause of this performance deficiency was failure of the site to recognize the latent issue of density change errors in RCS leakage calculations.
Enforcement:
Violation: Title 10 CFR Part 50, Appendix E, Section IV.C(2), Activation of Emergency Organization, requires, in part, the licensee to establish and maintain the capability to assess, classify, and declare an emergency condition within 15 minutes after the availability of indications to plant operators that an emergency action level has been exceeded.
Contrary to above, the licensee failed to maintain an appropriate capability to assess, classify, and declare an emergency action level within 15 minutes for an RCS leak rate in excess of emergency action level entry requirements. The ANO Unit 1 Procedures OP-1103.013, RCS Leak Detection, revision 48, and OP-1203.039, Excess RCS Leakage, revision 22, for determining leakage from the RCS included potentially significant, nonconservative errors because they did not account for density differences in the water volumes being assessed during RCS leakage determinations. These errors could lead the operators to conclude that an emergency action level had not been exceeded when it had been exceeded.
Enforcement Action: This violation is being treated as a non-cited violation, consistent with section 2.3.2 of the Enforcement Policy.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On April 11, 2024, the inspectors presented the integrated inspection results to Doug Pehrson, Site Vice President, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
CR-ANO-
2-2023-02765, C-2022-00735, C-2023-00746
Procedures
OP-1104.039
Plant Heating and Cold Weather Operations
Procedures
OP-2106.032
Unit 2 Freeze Protection Guide
Corrective Action
Documents
CR-ANO-
2-2020-01467, 2-2024-00167
Drawings
M-2217, Sheet 2
Piping and Instrument Diagram Emergency Diesel Generator
Starting Air System
Drawings
M-2217, Sheet 3
Piping and Instrument Diagram Emergency Diesel Generator
Auxiliary Systems
Miscellaneous
STM 2-31
Emergency Diesel Generators (System Training Manual)
03/03/2024
Miscellaneous
ULD-2-SYS-15
ANO-2 Reactor Protection and Core Protection Calculator
Systems
Procedures
OP-2203.030
Procedures
OP-2304.037
Unit 2 Plant Protection System Channel A Test
Work Orders
WO 514400, 54108727
Fire Plans
FZ-1030
Intake Structure
Fire Plans
FZ-1039
Refuel Floor
Fire Plans
FZ-1052, Fire
Zone 129-F
Turbine Building Area Control Room (Unit 1)
Fire Plans
FZ-1054
Refuel Floor
Fire Plans
FZ-1061
Intake Structure
Fire Plans
Unit 1 Prefire Plans
Fire Plans
Unit 2 Prefire Plans
Miscellaneous
Fire Hazards Analysis
Procedures
Fire Brigade Drills
Calculations
CALC-15-E-0007-
Reduced Latching Requirements for Watertight Doors
Calculations
CALC-ANOC-CS-
15-00003
ANO Flood Protection Design Basis
Drawings
A-7001, Sheet 1
Flood Protection Drawing Index Penetration Drawing Index,
General Notes and Legend
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Drawings
A-7001. Sheet 5
Unit 2 Auxiliary Building Flood Protection (EL 335'-0")
Miscellaneous
Unit 2 Operations Logs
03/22/2024
Miscellaneous
(FI-11537)
Door 455 (opened) in support of Reverse Osmosis Skid
Installation (T-MOD)
03/22/2024
Procedures
1000.120
ANO Fire Impairment Program
Procedures
1015.052
Passive Barrier Breach Permitting Process
Corrective Action
Documents
CR-ANO-
2-2024-00167
Miscellaneous
SES-2-018
Arkansas Nuclear One Unit 2 Dynamic Exam Scenario
Procedures
1903.010
Emergency Action Level Classification
Procedures
202.001
Standard Post Trip Actions
Procedures
202.005
Excess Steam Demand
Procedures
203.024
Loss of Turbine Load
Procedures
Conduct of Operations
Procedures
Time Critical Action Program Standard
Procedures
Conduct of Simulator Training
Procedures
OP-1104.036
Emergency Diesel Generator Operation
Procedures
OP-1202.002
Loss of Subcooling Margin
Procedures
OP-1202.010
Procedures
OP-2105.009
CEDM Control System Operation
Work Orders
WO 53013692, 53033927, 54108727
Procedures
1307.013
Unit 1 Class 1E Battery Charger Load Test
Procedures
1412.81
Battery Chargers Cleaning and Inspection
Work Orders
53007808-01
D-03B Perform 18 Month Load Test IAW OP-1307.013
01/30/2024
Work Orders
53013380-01
D-03B Thermography Clean Inspect Lube & CK Meter
(preventive maintenance)
01/31/2024
Calculations
CALC-97-R-1002-
-01
ECCS Leakage Quantities to Aux Bldg
Corrective Action
Documents
CR-ANO-
1-2024-00084, 1-2024-00400, 2-2021-01235, 2-2024-00380
Procedures
COPD-024
Risk Assessment Guidelines
Procedures
Protected Equipment Postings
Procedures
Online Risk Assessment
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
OP-2104.046
Unit 2 120 VAC 10 kVA Inverter Inspection, Test, and
Maintenance Instructions
Work Orders
WO 53012016, 54123608
Corrective Action
Documents
CR-ANO-
1-2023-00288, 1-2024-00373, 2-2002-02036, 2-2023-02352,
2-2023-02353, 2-2023-02996, C-2024-00076, C-2024-00077,
C-2024-00099, C-2024-00137, C-2024-00497
Engineering
Evaluations
DCP 89-2017
Alternate AC Power Source
Engineering
Evaluations
DCP 92-2011
Alternate AC (AAC) Generator System
Engineering
Evaluations
ER-ANO-2003-
0198
Functional Test Phase Tests
03/08/2006
Miscellaneous
Emergency Diesel Generator Voltage Regulator Problems
11/15/2007
Miscellaneous
Instrumentation for Earthquakes
Miscellaneous
STM 1-72
Seismic Monitoring System
Miscellaneous
ULD-0-SYS-19
Alternate AC Generator System (AAC)
Miscellaneous
ULD-0-TOP-03
Seismic
Miscellaneous
ULD-2-SYS-01
ANO Unit 2 Emergency Diesel Generator System
Miscellaneous
Unit 1 UFSAR
Chapter 2.7 Seismology
Amendment
Procedures
Predictive Maintenance Program
Procedures
OP-2104.036
Emergency Diesel Generator Operations
104
Procedures
OP-2104.037
Alternate AC Diesel Generator Operations
Work Orders
WO 53034621, 54066803, 54089370, 54094397, 54095582
Calculations
CALC-85-E-0053-
Fire Area JJ Combustible Loading Evaluation
Corrective Action
Documents
CR-ANO-
1-2024-00084, 2-2003-0041, 2-2014-00345, 2-2024-00167
Engineering
Changes
Justification for Additional Non-Q Battery Room Heating
Engineering
Changes
Unit 2 Combustible Loading Calculations for Area JJ
Engineering
Changes
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Engineering
Changes
Use Installed Spare Breaker to Re-Energize Power Switch
Assembly Associated with CEDMCS Subgroup 6
Miscellaneous
ER-ANO-2002-
0145-000
Justification for Temporary non-Q Battery Room Heating
Miscellaneous
PC 95-8010
Ground Fault Monitoring for MG and CEDMCS
08/23/1995
Procedures
OP-2106.032
Unit 2 Freeze Protection Guide
Work Orders
WO 54105685, 54108727
Corrective Action
Documents
CR-ANO-
1-2024-00397, 2-2023-02996, 2-2024-00134, 2-2024-00326,
C-2023-00487
Drawings
M-204, Sheet 3
PI&D Unit 1 Emergency Feedwater
Drawings
M-204, Sheet 4
PI&D Unit 1 Emergency Feedwater
Drawings
M-204, Sheet 5
PI&D Unit 1 Emergency Feedwater
Drawings
M-2210, Sheet 3
PI&D Unit 2 Service Water
Engineering
Changes
Baseline the Reference Values for the ANO1 IST Components
Engineering
Evaluations
ER-ANO-2004-
0507-001
Thermal Binding Evaluation for Stroke Testing CV-1050 and
CV-1410 During 1R19 Cooldown
Miscellaneous
Unit 1 Operations Logs
03/06/2024
Miscellaneous
SEP-ANO-1-IST-
ANO Unit 1 Inservice Testing Bases Document
Miscellaneous
SEP-ANO-2-IST-
ANO Unit 2 Inservice Testing Bases Document
Miscellaneous
ULD-2-TOP-03
ANO-2 Containment Response to Design Basis Accidents
Procedures
1304.050
Unit 1 ESAS Analog Channel 2 Test
Procedures
2104.036
Emergency Diesel Generator Operations, Supplement 2C-
2DG2 Semi-Annual Test (Fast Start)
104
Procedures
2104.036
(Supplement 1A)
2DG1 Monthly Test with 2T-31B Aligned (Slow Start)
104
Procedures
2304.037
Unit 2 Plant Protection System Channel A Test
Procedures
Limitorque Valve Operator Model SMB/SB/SBD-000 through 5
MOV and HBC Periodic Inspection
Procedures
OP-1104.004
Decay Heat Removal Operating Procedure
140
Procedures
OP-1104.029
Service Water and Auxiliary Cooling System
28
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
OP-1104.036
Emergency Diesel Generator Operation
Procedures
OP-1106.006
Emergency Feedwater Pump Operation
20
Procedures
OP-2104.029
Service Water System Operations
27
Procedures
OP-2104.033
Containment Atmosphere Control
Procedures
OP-2104.036
Emergency Diesel Generator Operations
104
Procedures
OP-2107.001
Electrical System Operations
139
Procedures
STM-2-31
Emergency Diesel Generators (U2 System Training Manual)
03/03/2024
Work Orders
53016033-01
Perform 18 Month Test Per 2304.187 CPC Channel B RCE
Temp I
2/28/2024
Work Orders
54037428-01
Monthly 2 EDG#2 Diesel Test per 2104.036 SUP 2B (Slow
Time Allowed)
2/18/2024
Work Orders
WO 53018387, 54017970, 54040272, 54058738, 54060059,
54064162, 54094397, 54103261,
Self-Assessments
24 ANO
24FSD1 Red
Team
Radiological Release (simulated)
2/13/2024
Self-Assessments
U1 Scenario
(DEP)
SES-1-025A (EAL classification)
2/01/2024
71151
Corrective Action
Documents
CR-ANO-
1-2023-00743, 2-2023-00026, 2-2023-01929, 2-2023-01938
71151
Miscellaneous
EN-LI-114, Att 1
NRC Performance Indicator Technique/Data Sheet
and 21
71151
Miscellaneous
Narrative Logs
71151
Miscellaneous
Regulatory Assessment Performance Indicator Guideline
Corrective Action
Documents
CR-ANO-
1-2023-00252, 1-2023-00290, 1-2023-00325, 1-2023-00399,
1-2023-00611, 1-2023-00650, 1-2023-00837
Miscellaneous
LER 2023-001-00
Automatic Reactor Trip due to Reactor Protection System
Actuation
04/14/2023