IR 05000315/2023002
| ML23201A212 | |
| Person / Time | |
|---|---|
| Site: | Cook  (DPR–058, DPR–074) |
| Issue date: | 07/24/2023 |
| From: | Nestor Feliz-Adorno NRC/RGN-III/DORS/ERPB |
| To: | Lies Q Indiana Michigan Power Co |
| References | |
| IR 2023002 | |
| Download: ML23201A212 (1) | |
Text
SUBJECT:
DONALD C. COOK NUCLEAR PLANT - INTEGRATED INSPECTION REPORT 05000315/2023002 AND 05000316/2023002
Dear Q. Shane Lies:
On June 30, 2023, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Donald C. Cook Nuclear Plant. On July 17, 2023, 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.
No findings or violations of more than minor significance were identified during this inspection.
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, Néstor J. Féliz Adorno, Chief Engineering and Reactor Projects Branch Division of Operating Reactor Safety Docket Nos. 05000315 and 05000316 License Nos. DPR-58 and DPR-74
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000315 and 05000316
License Numbers:
Report Numbers:
05000315/2023002 and 05000316/2023002
Enterprise Identifier:
I-2023-002-0051
Licensee:
Indiana Michigan Power Company
Facility:
Donald C. Cook Nuclear Plant
Location:
Bridgman, MI
Inspection Dates:
April 01, 2023 to June 30, 2023
Inspectors:
S. Bell, Health Physicist
B. Bergeon, Senior Operations Engineer
T. Hartman, Senior Project Engineer
T. Hooker, Health Physicist
J. Mancuso, Resident Inspector
C. St. Peters, Acting Senior Resident Inspector
Approved By:
Néstor J. Féliz Adorno, Chief
Engineering and Reactor Projects Branch
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Donald C. Cook Nuclear Plant, 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
No findings or violations of more than minor significance were identified.
Additional Tracking Items
Type Issue Number Title Report Section Status LER 05000315/2022-003-00 LER 2022-003-00 for Donald C. Cook Nuclear Plant, Unit 1, Automatic Reactor Trip on Loss of Flow Due to Reactor Coolant Pump Trip 71153 Closed LER 05000315/2022-003-01 LER 2022-003-01 for Donald C. Cook Nuclear Plant, Unit 1, Automatic Reactor Trip on Loss of Flow Due to Reactor Coolant Pump Trip 71153 Closed
PLANT STATUS
Unit 1 began the inspection period at rated thermal power. On April 18, 2023, power was reduced to approximately 49 percent to perform main feed pump (MFP) water box cleaning and MFP control valve maintenance. The unit returned to rated thermal power on April 21, 2023, and remained at or near full rated thermal power for the remainder of the inspection period.
Unit 2 began the inspection period at rated thermal power and remained at or near full rated thermal power for 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
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (3 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Unit 2 west residual heat removal (RHR) train on April 6, 2023
- (2) Unit 2 "CD" emergency diesel generator (EDG) after test run on April 14, 2023
- (3) Unit 1 east motor driven auxiliary feedwater pump (MDAFW) on June 5 through June 9, 2023
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:
- (1) Unit 1 and 2 main feedwater pump areas, Fire Zones 91, 92, 96, and 99 on April 26, 2023
- (2) Unit 1 charging pump areas, Fire Zones 62 A/B/C, elevation 587' on April 27, 2023
- (3) Unit 2 AB diesel generator room, Fire Zone 19, elevation 587' on May 24, 2023 (4)essential service water (ESW) pump 1E/1W/2E/2W, Fire Zones 29A/B/C/D, elevation 591' on May 30, 2023
Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the on-site fire brigade training and performance during an announced fire drill on May 9, 2023.
71111.06 - Flood Protection Measures
Flooding Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated internal flooding mitigation protections for the Unit 1 charging pumps on June 20 through 23, 2023.
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated an emergency planning drill in the simulator on May 16, 2023.
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 2 main feedwater a(1) plan on May 23 through June 5, 2023
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 work control during down power on April 19, 2023 (2)risk control work control during 4kV bus degraded voltage relay work on May 3, 2023 (3)protected equipment in response to a K7 geomagnetic storm warning on May 11, 2023
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) Action Request (AR) 2002-8198; 1-CCW-256 Went Closed Past Its Closed Seat on April 3, 2023
- (2) AR 2023-2822; 2-PP-35W Casing Bolt Thread Engagement Less than Flush on April 6, 2023
- (3) AR 2023-2707; 1-BATT-CD High Cell Resistance on April 3, 2023
- (4) AR 2023-3961; Borax Residue On/Around/Above 1-HV-AES-1 on May 24, 2023
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (1 Sample)
The inspectors evaluated the following temporary or permanent modifications:
- (1) Engineering Change (EC) 53366: Replace EDG Fuel Oil Transfer Pump 1-QT-106-CD2, June 13 through 26, 2023
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) (4 Samples)
- (1) Unit 1 east MDAFW pump test following breaker failure on April 8, 2023 (2)diesel driven fire pump following planned work on April 25, 2023
- (3) Unit 1 east component cooling water post-maintenance test following planned work on May 8, 2023
- (4) Unit 2 2-VCR-104, containment lower compartment purge exhaust train 'A' CIV solenoid replacement and post-maintenance test on June 2, 2023
Surveillance Testing (IP Section 03.01) (3 Samples)
- (2) Nuclear Instrumentation Power Range Channel Operational Test and Calibration with New Flux Data Equivalent Voltages, on May 10, 2023 (3)1-OHP-4030-117-050W; Unit 1 west RHR Pump Operability Test on May 31, 2023
Inservice Testing (IST) (IP Section 03.01) (2 Samples)
- (1) ESW full flow test on May 10, 2023
- (2) 1-OHP-4030-109-007E; east containment spray system test on May 22, 2023
Diverse and Flexible Coping Strategies (FLEX) Testing (IP Section 03.02) (1 Sample)
- (1) FLEX reactor coolant system functional test on June 27, 2023
71114.06 - Drill Evaluation
Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)
The inspectors evaluated:
- (1) Emergency Response Organization dress rehearsal 2 drill, for Team 4 on April 25,
RADIATION SAFETY
71124.05 - Radiation Monitoring Instrumentation
Walkdowns and Observations (IP Section 03.01) (9 Samples)
The inspectors observed the following radiation detection instrumentation during plant walkdowns:
- (1) The portable radiation survey instrumentation available for use at the radiation protection instrumentation laboratory and the radiation protection access control facility
- (2) A source check of whole body counter FS-1 in the radiation protection access control building
- (3) Periodic performance tests of the following radiation survey monitors in the radiation protection access control building's instrument storage area using the Hopewell irradiator: E600-2623 and associated HP270 probe, RDS-31-710750, Telepole-083, and RM20-959
- (4) Periodic performance tests of the following ion chambers in the radiation protection access control building's instrument storage area using the Hopewell irradiator:
R020-4375 and Victoreen 451-1313
- (5) A source check of the following equipment at the exit of the radiologically controlled area in the radiation protection access control building: the small area monitors SAM12-153 and SAM12-147, the gamma exit monitor GEM5-1, and the whole body contamination monitor ARGOS-6
- (6) A calibration of the liquid scintillation counter SGL049191214 in the chemistry lab on elevation 636' in the turbine building
- (7) The following continuous air monitors in the corresponding locations: AMS-4-527 in the radiation waste handling building on the 609' elevation, AMS-4-579 in the spent fuel pool room on the 650' elevation, and ABPM-130 in the high-level radiative waste drumming room on the 587'/591' elevation of the auxiliary building
- (8) Multiple area radiation monitors on the 587'/591', 609'/612', and 650' elevations of the auxiliary building
- (9) The following discharge monitors: the liquid effluent monitor 12-RRS-1001-B-DET and the Unit 1 gaseous effluent vent stack gamma monitor 1-VRS-1506
Calibration and Testing Program (IP Section 03.02) (13 Samples)
The inspectors evaluated the calibration and testing of the following radiation detection instruments:
- (1) Ortec Fastscan Whole Body Counter, Serial Number FS-1
- (2) Hopewell Designs Box Calibrator, Serial Number G10-2-2600-2SR
- (3) Mirion iDC-3000 Calibrator, Serial Number 171701
- (4) Containment High Range Area Monitor, 1VRA-1410
- (5) Mirion RDS Survey Instrument, Serial Number 712426
- (6) Victoreen V451 Survey Instrument, Serial Number 1312
- (7) Mirion Alpha Beta Particulate Monitor, Serial Number ABPM-130
- (8) OneSource Liquid Scintillation Counter, Serial Number SGL049191214
- (9) Canberra Gamma Spectroscopy, Serial Number 11923598
- (10) Mirion Gamma Exit Monitor, GEM-5-1
- (11) Mirion Personnel Contamination Monitor, ARGOS-6
- (12) ThermoScientific Small Articles Monitor, SAM12-153
- (13) Mirion Telescopic Radiation Survey Meter, TelePole-083 Effluent Monitoring Calibration and Testing Program Sample (IP Section 03.03) (2 Samples)
The inspectors evaluated the calibration and maintenance of the following radioactive effluent monitoring and measurement instrumentation:
- (1) Radioactive Liquid Waste Disposal Effluent Monitor, 12-RRS-1001-B
- (2) Unit 1 Auxiliary Building Vent Noble Gas Effluent Monitor, 1 VRS1505A
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
MS07: High Pressure Injection Systems (IP Section 02.06)===
- (1) Unit 1 (April 1, 2022 through March 31, 2023)
- (2) Unit 2 (April 1, 2022 through March 31, 2023)
MS10: Cooling Water Support Systems (IP Section 02.09) (2 Samples)
- (1) Unit 1 (April 1, 2022 through March 31, 2023)
- (2) Unit 2 (April 1, 2022 through March 31, 2023)
71152A - Annual Follow-up Problem Identification and Resolution Annual Follow-up of Selected Issues (Section 03.03)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (2) AR 2023-3174, LCO 3.7.10 Training Requested, 04/21/2023
71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02)
- (1) The inspectors conducted a semiannual review of the licensee's Corrective Action Program (CAP) for potential adverse trends with the effects of software in digital controllers that might be indicative of a more significant safety concern on May 30, 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 2022-003-00 for Donald C. Cook Nuclear Plant Unit 1, Automatic Reactor Trip on Loss of Flow Due to Reactor Coolant Pump Trip, (ADAMS Accession No.
ML22292A277). The inspectors determined that it was not reasonable to foresee or correct the cause discussed in the LER, therefore no performance deficiency was identified. The inspectors did not identify a violation of NRC requirements. This LER is Closed.
- (2) LER 2022-003-01 for Donald C. Cook Nuclear Plant Unit 1, Automatic Trip on Loss of Flow Due to Reactor Coolant Pump Trip, (ADAMS Accession No. ML23053A162).
The inspectors determined that it was not reasonable to foresee or correct the cause discussed in the LER, therefore no performance deficiency was identified. The inspectors did not identify a violation of NRC requirements. This LER is Closed.
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On July 17, 2023, the inspectors presented the integrated inspection results to Q. S. Lies, Senior Vice President and Chief Nuclear Officer, and other members of the licensee staff.
On May 11, 2023, the inspectors presented the radiation protection inspection results to Q. S. Lies, Senior Vice President and Chief Nuclear Officer, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
AR 2023-2814
NRC ID: Unused Rad Bag Found in RCA
04/06/2023
Corrective Action
Documents
Resulting from
Inspection
AR 2023-2822
2-PP-35W Casing Bolt Thread Engagement Less Than Flush
04/06/2023
OP-1-5151A-51
Flow Diagram Emergency Diesel Generator "AB" Unit No. 1
07/13/2021
OP-1-5151B-64
Flow Diagram Emergency Diesel Generator "AB" Unit #1
05/11/2022
Drawings
OP-2-5143
Flow Diagram Emerg. Core Cooling (RHR) Unit No. 2
1-OHP-4030-156-
East Motor Driven Auxiliary Feedwater System Test - East
MDAFP Valve Lineup
2-OHP-4021-032-
008CD
DG2CD Lube Oil System Valves
Procedures
2-OHP-4030-208-
053V
E.C.C.S. Valve Position Verification
Fire Pre-Plans -
Volume 1
Fire Zone 62B Centrifugal Charging Pump Unit 1
Elev. 587'-0"
Fire Pre-Plans -
Volume 1
Fire Zone 91 Turbine Building Unit 1 (S.E. Portion)
Elev. 609'-0"
Pre-Fire Plans
Volume 1
Fire Zone 19, 2 AB Diesel Generator Room, Unit 2,
Elevation 587'
Pre-Fire Plans
Volume 1
Fire Zone 29B - Essential Service Water Pump 1W Unit 1
Elev. 591'
Pre-Fire Plans
Volume 1
Fire Zone 29C - Essential Service Water Pump 2E, Unit 2
Elev. 591'
Pre-Fire Plans
Volume 1
Fire Zone 29D - Essential Service Water Pump 2W Unit 2
Elev. 591'
Pre-Fire Plans
Volume 1
Fire Area AA 32
Pre-Fire Plans
Volume 1
Fire Area AA 33
Fire Plans
Pre-Fire Plans
Volume 1
Fire Zone 29A, Essential Service Water Pump 1E, Unit 1,
Elevation 591'
Miscellaneous
Cook Nuclear Plant Fire Drill Package OHI-2270, Fire Drills
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
FP-E-9500/Fire Drill
23-001-A, Fire
Drill Package
Fire Pump House MCC
06/22/2023
2-FPP-2270-
066-001
Portable Fire Extinguisher Inspections
2-OHP-4025-
001-002
Fire Response Guidelines
DTG-OPFP-002
Periodic Review of Fire Pre-Plans
Fire Pre-Plans
Volume 1
Fire Zone 91 Turbine Building Unit 1 (S.E. Portion)
Elev. 609'0"
Fire Pre-Plans
Volume 1
Fire Zone 92 Turbine Building Unit 1 (S.W. Portion)
Elev. 609'0"
Fire Pre-Plans
Volume 1
Fire Zone 96 Turbine Building Unit 1 (N.E. Portion)
Elev. 609'0"
Fire Pre-Plans
Volume 1
Fire Zone 99 Turbine Building Unit 1 (N.W. Portion)
Elev. 609'0"
Procedures
Fire Pre-Plans
Volume 1
Fire Area AA 54 Unit 2 Control Room Elev. 633'-0"
PRA-FLOOD-004
Internal Flooding - Qualitative Screening Analysis
06/30/2017
PRA-FLOOD-007
Floor Drains Capacity
2/11/2012
PRA-FLOOD-008
Flood Sources and the Associated Flood Mechanisms
06/30/2017
PRA-FLOOD-013
Internal Flood Human Reliability Analysis
06/30/2017
Calculations
PRA-FLOOD-014
Internal Flood Detailed Analysis
06/19/2006
Corrective Action
Documents
23-1564
Generate and Present (a)(1) Consideration for FW-01
2/22/2023
Cook Nuclear Plant Excellence Plan Indicator
05/01/2023-
05/31/2023
Maintenance Rule Scoping Main Feedwater
Miscellaneous
DB-12-FW
Design Basis Document for the Main Feedwater System
2/27/2023
2-EHP-5035-
Maintenance Rule Program Administration
2
Procedures
DTG-MRE-001
Maintenance Rule Evaluation
Procedures
PMP-2291-OLR-
001
On-Line Risk Management
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
AR 2020-8198
1-CCW-256 Went Closed Past Its Closed Seat
10/05/2020
AR 2023-2707
1-BATT-CD High Cell Resistance
04/03/2023
AR 2023-2822
2-PP-35W Casing Bolt Thread Engagement Less Than Flush
04/06/2023
Corrective Action
Documents
AR 2023-3961
Borax Residue On/Around/Above 1-HV-AES-1
05/23/2023
2-CCW-50
Component Cooling Water
Drawings
OP-1-5135
Flow Diagram: CCW Pumps and CCW Heat Exchangers
1-OHP-4022-016-
004
Loss of Component Cooling
PMI-7030
Corrective Action Program
Procedures
PMP-7030-OPR-
001
Engineering
Changes
Replace EDG Fuel Oil Transfer Pump 1-QT-106-CD2
Miscellaneous
FCR-53366-001
Field Change Request: Replace EDG Fuel Oil Transfer
Pump 1-QT-106-CD2
Procedures
1-OHP-4030-132-
27CD,
CD Diesel Generator Operability Test (Train A): Fuel Oil
Transfer Pump 1-QT-106-CD2 Auto Start Test and
In Service Test [IST]
Work Orders
55353006-09
1-QT-106-CD2: Replace Pump EC-53366
05/23/2023
1-OHP-4030-109-
007E
East Containment Spray System Operability and Group B
Pump Test
05/06/2023
1-OHP-4030-109-
007E
East Containment Spray System Test
1-OHP-4030-117-
050W
West Residual Heat Removal Train Operability Test
Modes 1-4
2-OHP-4021-
066-001
Fire Protection System (Water) Operation; Start and Stop of
the West Diesel Fire Pump
04/25/2023
Procedures
2-OHP-4030-232-
27AB
AB Diesel Generator Operability Test (Train B)
04/25/2023
55467358-01
2-FLEX-PP-103-10 & 11; FLEX Blended RCS Makeup
Pumps Engine Functional Test
06/27/2023
C10029304001
2-XSO-124: Install ASCO Solenoid Valve for 2-VCR-104
05/31/2023
C1002934005
2-XSO-124: Perform PMT
05/31/2023
Work Orders
C10050318001
Perform Power Range Calibration for 2-NRI-44
05/04/2023
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
C10050643001
MTE, Replace Breaker, 12-BKR-V-407
04/08/2023
C10050695001
MTE: 12-BKR-V-4070 Repair Breaker
04/11/2023
Miscellaneous
Scenario Manual
DC Cook Emergency Response Organization Dress
Rehearsal 2 Team 4
04/25/2023
Mirion Alpha Beta Particulate Monitor,
Serial Number ABPM-130
10/06/2022
Mirion iDC-3000 Calibrator, Serial Number 171701
06/22/2022
Victoreen V451, Serial Number 1312
2/08/2023
Mirion RDS Survey Instrument, Serial Number 712426 with
Probe GMP12, Serial Number 330180
01/07/2023
JL Shepherd Model 89, Serial Number 1
11/10/2021
ASP-9872
Model 877 and Model 896A Victoreen Containment
High Range Area Monitor
03/31/1986
FS-1
Ortec Fastscan Whole Body Counter
07/06/2022
G10-2-2600-2SR
Hopewell Designs Box Calibrator
09/29/2022
Radioactive Liquid Waste Disposal Effluent Monitor,
2-RRS-1001-B
04/27/2022
Containment High Range Monitor, 1 VRA-1401
05/11/2022
Calibration
Records
C10005186001
Unit 1 Auxiliary Building Vent Gaseous Noble Gas Effluent
Monitor, 1VRS1505A
2/05/2022
AR 2021-5151
Radiation Protection Instrument Calibration Source for the
Hopewell BX-3 is Broken
06/14/2022
AR 2021-7370
Water Observed when Changing Filters on 2-VRS-2500A
08/26/2021
AR 2021-7596
2-VRS-2500A Alarming due to Water Intrusion
09/08/2021
AR 2022-8294
Use History Analysis: As Found Calibration Could not be
Collected on Radiation Protection WBC1
10/16/2022
Corrective Action
Documents
AR 2022-8392
Sample Flow on 1-SRA-1800 is Out of Range
10/18/2022
Radioactive Sealed Source Certificates
(ICN 2391, 2392,2374, and 2377)
Various
Miscellaneous
Radiochemistry Interlaboratory Comparison Data Third
Quarter 2021 through First Quarter 2023
Various
2-THP-4030-
013-002
Mirion Liquid Process Monitor Calibration
Procedures
2-THP-4030-
Mirion NGM 216 Normal Range Noble Gas Monitor
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
013-005
2-THP-6010-
RPC-570
Calibration of the Argos-5 Personnel Monitors
2-THP-6010-
RPC-571
Calibration of the Canberra GEM-5 Portal Monitor
2-THP-6010-
RPC-596
Calibration of the Thermo Scientific Small Article Monitor
SAM-12
2-THP-6010-
RPI-805
Radiation Monitoring System Setpoints
Self-Assessments 2022-8066-2
Radiation Protection Instrumentation
Undated
71151
Procedures
PMP-7110-PIP-
001
Reactor Oversight Program Performance Indicators and
Monthly Operating Report Data
AR 2022-4193
PPC2 Point L9000 for U-2 CCW Surge Tank Level
05/12/2022
AR 2022-7750
RMS "Apply" Button did not Function as Anticipated
09/29/2022
AR 2023-0249
2-EHP-5040-DICE-001 Insufficient for Digital Changes
01/10/2023
AR 2023-1708
1-VR5-1510 Setpoint Change Dropped Exponent During
Change
2/27/2023
AR 2023-3163
U1 MT Stop Valve #2 Failed to fully Close during Surv Test
04/20/2023
AR 2023-3174
LCO 3.7.10 Training Requested
04/21/2023
AR 2023-3262
2-RRS-1021 Indicates Software Malfunction
04/25/2023
AR 2023-3566
As-Left Unseating Torque Above VDS Limit 1-WMO-733
05/08/2023
Corrective Action
Documents
AR 2023-4016
Long Stroke Time Due to Software Delays
05/25/2023
Procedures
1-EHP-4030-128-
230
Unit 1 Control Room Tracer Gas Test
Corrective Action
Documents
AR 2022-9291
U2 Rx Trip
11/10/2022
Engineering
Changes
RCI Upgrade, Replace Feedwater Regulating Valve
Positioners and Feedwater Isolation Solenoid Valves
Procedures
2-IHP-6030-IMP-
043
Air Operated Valves (AOV) with Digital Valve Positioner
Diagnostics Testing and Calibration
6