IR 05000528/2025004
| ML26033A406 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 02/04/2026 |
| From: | John Dixon NRC/RGN-IV/DORS/PBD |
| To: | Heflin A Arizona Public Service Co |
| Sanchez A | |
| References | |
| IR 2025004 | |
| Download: ML26033A406 (0) | |
Text
February 04, 2026
SUBJECT:
PALO VERDE NUCLEAR GENERATING STATION - INTEGRATED INSPECTION REPORT 05000528/2025004 AND 05000529/2025004 AND 05000530/2025004
Dear Adam Heflin:
On December 31, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Palo Verde Nuclear Generating Station. On January 16, 2026, the NRC inspectors discussed the results of this inspection with Jenn Spina, Vice President, Nuclear Regulatory &
Oversight 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, John L. Dixon, Jr., Chief Reactor Projects Branch D Division of Operating Reactor Safety Signed by Dixon, John on 02/04/26 Docket Nos. 05000528 and 05000529 and 05000530 License Nos. NPF-41 and NPF-51 and NPF-74
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000528, 05000529 and 05000530
License Numbers:
Report Numbers:
05000528/2025004, 05000529/2025004 and 05000530/2025004
Enterprise Identifier:
I-2025-004-0000
Licensee:
Arizona Public Service
Facility:
Palo Verde Nuclear Generating Station
Location:
Tonopah, AZ
Inspection Dates:
October 1, 2025 to December 31, 2025
Inspectors:
N. Armstrong, Resident Inspector
E. Lantz, Senior Resident Inspector
J. Mejia, Reactor Inspector
D. You, Senior Operations 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 Palo Verde Nuclear Generating Station, 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
None.
PLANT STATUS
Units 1 and 2 operated at or near full power for the duration of the inspection period.
Unit 3 entered the inspection period at full power. On October 3, 2025, the reactor was shut down for refueling outage 3R25. On December 2, 2025, the reactor was made critical following completion of the refueling outage and returned to full power on December 6, 2025, where it remained 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
71111.04 - 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, high-pressure safety injection train B due to system risk significance, on October 21, 2025
- (2) Unit 2, condensate transfer system train A following comprehensive testing, on October 28, 2025
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) Unit 3, containment spray train A during 3R25 outage, on October 15, 2025
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 3, containment building 140-foot elevation, fire zones 66A, 66B, 67A, and 67B, on October 11, 2025
- (2) Unit 3, essential chiller units and essential air handling units train A and B rooms, fire zones 1 and 2, on October 20, 2025
- (3) Unit 1, control building 140-foot elevation and main control room fire zones 15A, 15B, 16, and 17, on October 23, 2025
Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the onsite fire department training and performance during unannounced fire drills, on July 8, 2025, September 26, 2025, and November 21, 2025.
71111.08P - Inservice Inspection Activities (PWR)
Due to the government shutdown, this inspection was completed remotely via in office document review. The inspectors verified that the reactor coolant system boundary, 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 documents associated with the following activities in Unit 3 during refueling outage 3R25 from October 6 through December 4, 2025.
PWR Inservice Inspection Activities Sample - Nondestructive Examination and Welding
Activities (IP Section 03.01) (1 Sample)
The inspectors verified that the following nondestructive examination and welding activities were performed appropriately:
- (1) Ultrasonic Examination
- safety injection, 25-6, pipe to valve
- safety injection, 25-8, pipe to elbow
- steam generator,41-100, nozzle to shell
- steam generator,41-101, nozzle to shell
- low pressure safety injection,71-113, tee to pipe
Dye Penetrant Examination
- charging line, CH-005-H-032-W, lugs
- steam generator,41-100, nozzle to tubesheet
- steam generator,41-101, nozzle to tubesheet Visual # Examination
- charging line, CH-005-H-022, strut
- charging line, CH-005-H-032, support
- reactor coolant, RC-017-H-040, pipe support
- pressurizer, 5-37-5, instrument nozzle
- pressurizer, 5-37-6, instrument nozzle
- pressurizer, PSV-200, -201, -202, -203, nuts, studs, washers, hydra nuts Welding Activities
- gas tungsten arc welding, o
reactor pressure vessel head, 5502327-1, valve to pipe o
reactor pressure vessel head, 5502327-2, pipe to valve o
reactor pressure vessel head, 5502327-3, elbow to pipe o
reactor pressure vessel head, 5502328-1, valve to pipe o
reactor pressure vessel head, 5502328-2, pipe to valve o
reactor pressure vessel head, 5502328-3, elbow to pipe PWR Inservice Inspection Activities Sample - Boric Acid Corrosion Control Inspection Activities (IP Section 03.03) (1 Sample)
The inspectors verified the licensee is managing the boric acid corrosion control program through a review of the following evaluations:
(1)
- 24-04228
- 24-05210
- 24-05239
- 24-05618
- 24-06188
- 24-06191
- 24-06192
- 24-07084
- 24-09593
- 25-08257
71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance
Requalification Examination Results (IP Section 03.03) (1 Sample)
- (1) The inspectors reviewed and evaluated the licensed operator examination failure rates for the requalification annual operating exam administered from August 20 to November 7, 2025.
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 main control room during Unit 3 shutdown for outage 3R25, on November 4, 2025.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated licensed operator continued training and emergency coordinator training simulator activities, on December 10, 2025.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (2 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, turbine-driven and motor-driven feedwater pumps due to increased vibrations, on October 22, 2025
- (2) Unit 2, safety related radiation monitors, on December 12, 2025
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (1 Sample)
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 3, emergent work on feedwater economizer isolation valve SGA-UV-174, on December 9, 2025
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (4 Samples)
The inspectors evaluated the licensees justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Unit 1, turbine-driven auxiliary feedwater train A operability determination due to oil leak from pump oil gauge on, October 8, 2025
- (2) Unit 3, auxiliary spray valves CHA-HV-205 and CHB-HV-203 functionality assessment due to seat leakage, on October 22, 2025
- (3) Unit 3, high-pressure safety injection train B operability determination due to pump oil leak, on November 20, 2025
- (4) Unit 2, missile resistant door for diesel generator train B room, G-1-06, functionality assessment due to failure of external undogging mechanism, on December 17, 2025
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated the Unit 3 refueling outage 3R25 activities from October 3 to December 6, 2025.
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 3, containment spray pump B post-maintenance testing following mechanical seal replacement, on November 4, 2025
- (2) Unit 3, emergency diesel generator train B post-maintenance testing following master rod replacement, on November 4, 2025
- (3) Unit 3, station class 1E 120Vdc battery PKA-F11 post-maintenance testing following replacement of two cells, on November 18, 2025
Surveillance Testing (IP Section 03.01) (2 Samples)
- (1) Unit 3, emergency diesel generator B integrated safeguards testing, on October 7, 2025
- (2) Unit 1, essential cooling water train A comprehensive test, on October 30, 2025
Inservice Testing (IST) (IP Section 03.01) (1 Sample)
- (1) Unit 2, emergency diesel generator fuel oil transfer pump inservice testing, on October 9, 2025
Containment Isolation Valve (CIV) Testing (IP Section 03.01) (1 Sample)
- (1) Unit 3, safety injection and shutdown cooling containment header containment isolation check valve SIB-V-165 testing, on October 14, 2025
Reactor Coolant System Leakage Detection Testing (IP Section 03.01) (1 Sample)
- (1) Unit 2, manual calculation of reactor coolant system water inventory balance during adverse trend, on November 20, 2025.
71114.06 - Drill Evaluation
Required Emergency Preparedness Drill (1 Sample)
- (1) The inspectors evaluated an emergency preparedness drill on October 3, 2025. The inspectors completed inspection procedure sections 03.03 through 03.05.
Additional Drill and/or Training Evolution (2 Samples)
- (1) The inspectors evaluated an emergency preparedness drill on October 8, 2025. The inspectors completed inspection procedure sections 03.03 through 03.05.
- (2) The inspectors evaluated an emergency preparedness drill on October 14, 2025. The inspectors completed inspection procedure sections 03.03 through 03.05.
OTHER ACTIVITIES - BASELINE
71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10) (3 Samples)
- (1) Unit 1 (October 1, 2024, through September 30, 2025)
- (2) Unit 2 (October 1, 2024, through September 30, 2025)
- (3) Unit 3 (October 1, 2024, through September 30, 2025)
BI02: RCS Leak Rate Sample (IP Section 02.11) (3 Samples)
- (1) Unit 1 (October 1, 2024, through September 30, 2025)
- (2) Unit 2 (October 1, 2024, through September 30, 2025)
- (3) Unit 3 (October 1, 2024, through September 30, 2025)71152A - Annual Follow-up Problem Identification and Resolution
Annual Follow-up of Selected Issues (Section 03.03) (2 Samples)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) Unit 1, evaluation of corrective actions related to Unit 1 reactor trip as documented in NRC inspection report 05000528/2023004-05, on October 22, 2025
- (2) Unit 1, response to and effectiveness of corrective actions of high-pressure safety injection pump train B failure to start, on December 4, 2025
71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02) (1 Sample)
- (1) From February 2 through May 5, 2025, the licensee wrote nine condition reports documenting issues regarding essential chill water train A oil level tracking documentation. The inspectors assessed the licensees problem identification threshold, evaluations, and corrective actions related to these condition reports. In each instance the licensee adequately followed site procedures to identify, evaluate, and correct the issue. No issues of more than minor significance were identified.
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On December 4, 2025, the inspectors presented the Unit 3 inservice inspection results to Jeremia Mueller, Regulatory Affairs, and other members of the licensee staff.
- On January 16, 2026, the inspectors presented the integrated inspection results to Jenn Spina, Vice President, Nuclear Regulatory & Oversight, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
25-11461, 25-11462, 23-09437, 21-00975, 24-09416
Drawings
2-M-CTP-001
P and I Diagram Condensate Storage and Transfer System
Drawings
2-M-DGP-001
P and I Diagram Diesel Generator System
Drawings
2-M-ECP-001
P and I Diagram Essential Chilled Water System
Drawings
2-M-EWP-001
P and I Diagram Essential Cooling Water System
Drawings
2-M-PCP-001
P and I Diagram Fuel Pool Cooling & CleanUp System
Drawings
2-M-SIP-001
P & I Diagram Safety Injection & Shutdown Cooling System
Drawings
2-M-SIP-002
P & I Diagram Safety Injection and Shutdown Cooling
System
Drawings
03-M-SIP-001
P & I Diagram Safety Injection & Shutdown Cooling System
Drawings
03-M-SIP-002
P & I Diagram Safety Injection & Shutdown Cooling System
Drawings
03-M-SIP-003
P & I Diagram Safety Injection & Shutdown Cooling System
Procedures
Shutdown Cooling Initiation
Procedures
Outage GOP
Procedures
High Pressure Safety Injection System Alignment
Verification
Procedures
Condensate Transfer System - Comprehensive Pump Test
Work Orders
5638192
Calculations
13-MC-FP-0805
Combustible Loads - Containment Building
Calculations
13-MC-FP-803
Combustible Loading Calculation - Control Building Units 1,
2, 3
Corrective Action
Documents
25-11948, 5765838, 25-11207, 25-07548, 25-07551, 25-
10708
Drawings
03-E-QKF-0001
Control Wiring Diagram Fire and Smoke Detection System
Fire Detection Control Panel 1J-QKN-E01D System A
Control BLDG EL 74 FT
Fire Plans
Pre-Fire Strategies Manual
Miscellaneous
NPL41-D-3Q1C-
Fire Drill After Action Review Summary
07/08/2025
Miscellaneous
NPL41-D-3Q3A-
Fire Drill After Action Review Summary
09/26/2025
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
Fire System Impairments and Notifications
Procedures
Fire Detection/Protection System Functional Test Honeywell
One Detector Type Panels
Procedures
Control Room Fire
Procedures
Control Room Envelope Habitability Program
Work Orders
5678517, 5765652
Corrective Action
Documents
24-04590, 24-07703, 25-02856, 25-04383, 25-04462, 25-
04590
Miscellaneous
4th Inspection Interval Inservice Inspection Program
Summary Manual PVGS Unit 3
Procedures
Welding and Brazing Control
Procedures
Boric Acid Corrosion Control Program
Procedures
Dry Magnetic Particle Examination
Procedures
Liquid Penetrant Examination
Procedures
Visual Examination of Welds, Bolting, and Components
Procedures
Visual Examination of Component Supports
Procedures
Visual Examination For Leakage
Procedures
Welding of Stainless and Nickel Alloys
Procedures
MN756-A00002
PDI Generic Procedure for the Ultrasonic Examination of
Austenitic Pipe Welds, PDI-UT-2
Procedures
MN756-A00004
PDI Generic Procedure for the Ultrasonic Examination of
Weld Overlaid Similar and Dissimilar Metal Welds, PDI-UT-8
Procedures
Appendix G
LOCT Annual and Biennial Exam Administration Results
Summary
11/11/2025
Miscellaneous
NLR25S050401
Palo Verde Nuclear Generating Station Licensed Operator
Continuing Training Simulator Scenario
10/21/2025
Procedures
Management of Critical Evolutions and Infrequently
Performed Tests or Evolutions
Procedures
Standard Post Trip Actions
Procedures
Plant Shutdown Mode 1 to Mode 3
Procedures
Outage GOP
Corrective Action
Documents
25-09941, 25-07101, 25-03074
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
23-05310, 23-06829, 25-13034, 25-14098
Miscellaneous
MR 2.0 - Performance Monitoring Bases Document
Worksheet for System Name Auxiliary Feedwater
Miscellaneous
5069-AF-01
Risk Basis Document
Miscellaneous
5069-SQ-01
CFR 50.69 System Categorization Radiation Monitoring
System (SQ)
Procedures
CFR 50.69 Program
Procedures
CFR 50.69 Active Component Categorization from
Qualitative Assessment and Defense-In-Depth
Procedures
Passive Component Categorization
Procedures
CFR 50.69 Alternative Treatment Requirements
Procedures
CFR 50.69 Alternative Treatment Implementation
Administrative Guideline
Procedures
Maintenance Rule Monitoring Process
Procedures
Pump and Valve Inservice Testing Program
Procedures
Auxiliary Feedwater A - Inservice Test
Procedures
Auxiliary Feedwater B - Inservice Test
Procedures
Auxiliary Feedwater A - Comprehensive Pump Test
Procedures
Auxiliary Feedwater B - Comprehensive Pump Test
Procedures
Vibration Data Collection For Surveillance Tests
Work Orders
5631225, 5721417, 5585337, 5579353, 5373446, 5684820,
5739359, 5739855, 5672027, 5606005
Work Orders
5535241, 5545679
Corrective Action
Documents
25-13936
Drawings
Schematic for Anchor/Darling Self Contained Hydraulic
Actuator
Drawings
A/DV Hydraulic Actuator ASSY for Feedwater Isolation
Valves
Miscellaneous
Integrated Risk Assessment for CM# 578336 of Task 0
Miscellaneous
Integrated Risk Assessment for CM# 578336 of Task 2
Miscellaneous
PV-E1572, Integrated Risk Screening Determination
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
Economizer FWIVS - Inservice Test
Work Orders
5789336, 5660318
Calculations
13-MC-DG-0204
Diesel Generator Building Flooding Analysis
Corrective Action
Documents
25-10714, 25-10802, 25-11022, 25-13061, 25-09150, 25-
244, 25-09258
Engineering
Evaluations
18-16090-002
Miscellaneous
PVNGS Design Basis Manual - Safety Injection System
Miscellaneous
13-NS-C088
Mission Times for the EW, SP, SI, AF, and DG systems
Miscellaneous
2968814
Prompt Operability Determination HPSI Pump Bearing
Leaks
Miscellaneous
MN725-A00935
RSB 5-1 Natural Circulation Cooldown Analysis for Power
Uprate and SG Replacement at Palo Verde Nuclear
Generating Station Units 1, 2, and 3
Miscellaneous
NPL41-D-3Q3A-
Fire Drill After Action Review Summary
09/26/2025
Procedures
Control of Doors, Hatches, and Floor Plugs
Procedures
Control of Doors, Hatches, and Floor Plugs
Procedures
Essential Auxiliary Feedwater System
Procedures
Managing Personnel Fatigue
Procedures
Heat Stress Prevention Program
Procedures
Foreign Material Exclusion Controls
Procedures
Reactor Vessel Missile Shield, Cable Support Structure,
Riser Duct & RV Flange Insulation Removal and Installation
Procedures
RV Head Removal and Installation, Single Pass MST
Procedures
Reactor Vessel Upper Guide Structure Removal and
Installation
Procedures
Miscellaneous Containment Building Heavy Loads
Procedures
Lower Mode Functional Recovery Technical Guideline
Procedures
Standard Post Trip Actions
Procedures
Lower Mode Functional Recovery,
Procedures
Filling and Draining the Refueling Pool Using the CS, LPSI
and HPSI Pumps
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
Managing Personnel Fatigue
Procedures
Plant Startup Mode 2 to Mode 1
Procedures
Power Operations
154
Procedures
RCS Drain Operations
Procedures
Outage GOP
Procedures
RCS and Pressurizer Heatup and Cooldown Rates
Procedures
RCS Loop/SDC Train Weekly Breaker Alignment and Power
Availability Surveillance in Modes 3, 4, 5, & 6
Procedures
Train B LPSI and CS System Alignment Verification
Procedures
Containment Cleanliness Inspection
Procedures
Shutdown Risk Assessments
Procedures
Spent Fuel Handling Machine
Procedures
Calculation of Estimated Critical Condition
Procedures
Shutdown Margin - Modes 3, 4, and 5
Procedures
Class 1E Diesel Generator and Integrated Safeguards Test
Train B
Procedures
LPSI Pumps Full Flow - Inservice Test
Procedures
Containment Spray Pumps - Comprehensive Pump Test
Procedures
HPSI Pump and Check Valve Full Flow Test
Procedures
Refueling Machine Operations
Work Orders
4903478, 5621607, 5621594, 5596978, 5631523, 5596978,
21606, 5621601, 5641145, 5334769, 5640585, 5296711,
4903478, 5596978, 5500030, 5628670*, 5693477, 5640726,
5640478, 5631501, 5631503, 5631505, 5761755, 5765060,
5501109, 5640692, 5640572, 5783870
Corrective Action
Documents
25-12242, 25-11386, 25-07021, 25-12980
Miscellaneous
TSCCR 3998585
Procedures
Train B Integrated Safeguards (ISG) Testing
Procedures
2-Day Surveillance Test of Station Batteries
Procedures
Surveillance of Class 1E Station Batteries Modified
Performance Test Discharge
Procedures
ESFAS Train B Subgroup Relay Shutdown Functional Test
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
Procedures
Procedures
RCS Leakage Source Determination
Procedures
Diesel Generator B Test
Procedures
ERFDADS (Preferred) Calculation of RCS Water Inventory
Procedures
Shutdown Cooling Flow Verification
Procedures
SDC Piping Water Volume Check
Procedures
Containment Leakage Type B and C Testing
Procedures
Class 1E Diesel Generator And Integrated Safeguards Test
Train A
Procedures
Class 1E Diesel Generator And Integrated Safeguards Test
Train B
Procedures
Class 1E Diesel Generator and Integrated Safeguards Test
Train B
Procedures
Class 1E Diesel Generator Load Rejection 24 Hour Rated
Load and Hot Start Test Train B
Procedures
Essential Cooling Water Pumps - Comprehensive Pump
Test
Procedures
Containment Spray Pumps and Check Valves - Inservice
Test
Procedures
Containment Spray Pumps - Comprehensive Pump Test
Work Orders
5638118, 5638118, 5456469, 5631538, 5631297, 5639201,
5631523, 5641212, 268462, 5768885, 5640570, 5664602,
5664302, 5638221, 5631543, 5640585, 5763462, 5631518,
4903478, 5638209, 5767807
Miscellaneous
MESSAGE: 1.1 OPS ADV - SEISMIC EVENT, ATWS,
HPSC LEAK, SURGE TANK OVERFLOW, 148/149 LEVELS
2503 ERO Drill
Miscellaneous
2503 Drill Objectives Work Sheet
Miscellaneous
2503 Drill General Information
Miscellaneous
Emergency Preparedness 2503 ERO Drill Report - August
5th, 2025
Miscellaneous
Emergency Preparedness 2504 ERO Drill Report - August
19th, 2025
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
Emergency Preparedness 2505 ERO Drill Report -
September 3rd, 2025
Procedures
Acts of Nature
Procedures
Standard Post Trip Actions
Procedures
ERO Positions - Operations Manager (TSC)
Procedures
ERO Positions - Emergency Coordinator (TSC)
71151
Miscellaneous
Units 1, 2, and 3 PI RCS Leakage Data 10/2024-9/2025
71151
Miscellaneous
Units 1, 2, and 3 NRC PI RCS Activity Data 10/2024-9/2025
71151
Procedures
Performance Indicator - Barrier Integrity Cornerstone: RCS
Leak Rate
71151
Procedures
RCS Activity Performance Indicator
71151
Procedures
NRC ROP PI Data Collection, Verification, and Submittal
Corrective Action
Documents
23-03479, 23-03648, 23-04398, 23-03665, 17-13171, 25-
05692, 25-08739, 25-08808, 25-08809
Drawings
01-E-MAA-0004
Drawings
01-E-MAB-0001
Drawings
03-E-PBB-006
Elementary Diagram 4.16 kV Class 1E and Non-Class 1E
Breaker Internal Switchgear
Drawings
03-E-SIB-001
Elementary Diagram Safety Injection and Shutdown Cooling
System HPSI Pump 3M-SIA-P02
Miscellaneous
Level 1 Evaluation 23-03479-006
Miscellaneous
EPCR 23-03106-001
Miscellaneous
ENG-EC: 23-03479-030 (MA-1866)
Miscellaneous
ENG-EC: 21-10389-002 (CO-1830)
Miscellaneous
EDC 2023-00343
Miscellaneous
DCR: 23-03665-001
Miscellaneous
Action items:
23-02035-006, 23-03479-024, 23-03479-025, 23-03479-037,
23-03479-040, 23-03479-041, 23-03479-042, 23-03479-043,
23-03479-044, 23-03479-045, 23-03479-046, 23-03479-047,
23-03479-048, 23-03479-049, 23-03479-050, 23-03479-051,
23-03479-052, 23-03479-053, 23-03479-055, 23-03479-056,
23-03479-057, 23-03479-058, 23-03479-059, 23-03479-060,
23-03479-061, 23-03479-063, 23-03479-064, 23-03479-067,
23-03479-068, 23-03479-069, 23-03479-077, 23-03479-078,
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
23-03479-079, 23-03479-080, 23-03479-081, 23-03479-082
Miscellaneous
ODP-1
Operations Department Practices
Miscellaneous
VTD-G080-00164
General Electric Instructions for HMA11 Auxiliary Relays
Procedures
Operational Decision Making
Procedures
Maintenance of AM-4.16-250-9H GE Magne-Blast Circuit
Breakers
Procedures
Overhaul of AM-4.16-250-9H GE Magne-Blast Circuit
Breakers
Procedures
Panel B06B Panel Responses
Procedures
Electro-Hydraulic Control System
Procedures
HPSI Pumps Mini-flow Inservice Test
Procedures
Design Change Process
Procedures
PV-E0303
Specification 13EN-0306, Installation Cables Splicing and
Terminations
Work Orders
5453249, 5525396, 5525368, 5525920, 5526199, 5526200,
5633253, 5633519, 5545663, 5545664, 5545665, 5547291,
5564369, 5564370, 5564371, 5534681, 5746983, 5625443
Corrective Action
Documents
25-01162, 25-03218, 25-04347, 25-04598, 25-04655, 25-
04797, 25-05231, 25-05305, 25-05364
Engineering
Evaluations
Unit 1 chiller reads 12-16-25, Logs
Engineering
Evaluations
87-EC-019
Determine Min/Max Volume of Lube Oil Required to
Maintain Chiller at Full
Engineering
Evaluations
88-EC-003
Provide Method to Determine if Chiller is Adequately
Charged to Provede Required 235 Tons
Procedures
Essential Chiller
Work Orders
5576226, 5580421, 5582856, 5586475, 5588956, 5714417,
5594472, 5717138, 5597033, 5598983, 5609936, 5613908,
5615844