IR 05000528/2025002
| ML25209A466 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 07/29/2025 |
| From: | John Dixon NRC/RGN-IV/DORS/PBD |
| To: | Heflin A Arizona Public Service Co |
| References | |
| IR 2025002 | |
| Download: ML25209A466 (1) | |
Text
July 29, 2025
SUBJECT:
PALO VERDE NUCLEAR GENERATING STATION - INTEGRATED INSPECTION REPORT 05000528/2025002 AND 05000529/2025002 AND 05000530/2025002
Dear Adam Heflin:
On June 30, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Palo Verde Nuclear Generating Station. On July 8, 2025, the NRC inspectors discussed the results of this inspection with Mike DiLorenzo, Acting Director, Nuclear Regulatory Affairs, 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 Docket Nos. 05000528; 05000529; and 05000530 License Nos. NPF-41; NPF-51; and NPF-74
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000528; 05000529; and 05000530
License Numbers:
Report Numbers:
05000528/2025002; 05000529/2025002; and 05000530/2025002
Enterprise Identifier:
I-2025-002-0000
Licensee:
Arizona Public Service Company
Facility:
Palo Verde Nuclear Generating Station
Location:
Tonopah, Arzona
Inspection Dates:
April 1, 2025, to June 30, 2025
Inspectors:
C. Alldredge, Health Physicist
N. Armstrong, Project Engineer
L. Carson, Senior Health Physicist
N. Cuevas, Resident Inspector
J. Hickey, Senior Project Engineer
E. Lantz, Senior Resident Inspector
A. Sanchez, Senior Project Engineer
A. Tran, Resident Inspector
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
Type Issue Number Title Report Section Status LER 05000530/2024-003-00 LER 2024-003-00 for Palo Verde Nuclear Generating Station, Unit 3, Violation of Technical Specifications 3.9.2 and 3.3.12 71153 Closed
PLANT STATUS
Unit 1 entered the inspection period shut down for refueling outage 1R25. On May 9, 2025, the reactor was made critical following completion of the refueling outage and returned to full power on May 14, 2025, where it remained for the remainder of the inspection period.
Unit 2 operated at or near full power for the duration of the inspection period.
Unit 3 entered the inspection period at full power. On April 25, 2025, the reactor was down powered to approximately 12 percent power to perform repairs to a switchyard breaker due to a hot spot. On April 27, 2025, the reactor returned to full power following repairs, 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) (3 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Unit 1, shutdown cooling train A during the 1R25 outage, on April 2, 2025
- (2) Unit 1, spent fuel pool cooling trains A and B during the 1R25 outage, on April 7, 2025
- (3) Unit 2, Cardox fire protection system following maintenance, on May 8, 2025
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, 100-foot elevation auxiliary building rooms, fire zones 42C and 42D, essential cooling water heat exchangers A and B rooms, fire zone 43, on April 30, 2025
- (2) Unit 3, 100-foot elevation auxiliary building rooms, fire zones 42C and 42D, essential cooling water heat exchangers A and B rooms, fire zone 43, on April 30, 2025
- (3) Unit 1, containment during 1R25 outage, fire zones 63A, 63B, 66A, 66B, 67A, and 67B, on May 2, 2025
- (4) Unit 2, main control room, fire zone 17, on June 18, 2025
71111.06 - Flood Protection Measures
Flooding Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated internal flooding mitigation protections in the Units 1, 2, and 3 essential pipe density tunnels, on May 29, 2025.
71111.07A - Heat Exchanger/Sink Performance
Annual Review (IP Section 03.01) (1 Sample)
The inspectors evaluated readiness and performance of:
- (1) Unit 1 essential cooling water train B heat exchanger, on April 6, 2025
===71111.08P - Inservice Inspection Activities (PWR) 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 the following activities in Unit 1 during refueling outage 1R25 from April 7 to 18, 2025, on site and completion of the inspection on May 30, 2025, via in office review.
PWR Inservice Inspection Activities Sample - Nondestructive Examination and Welding Activities (IP Section 03.01)===
The inspectors verified that the following nondestructive examination and welding activities were performed appropriately:
- (1) Ultrasonic Examination
- auxiliary and downcomer feedwater steam generator 2, weld 59-19, pipe to elbow
- auxiliary and downcomer feedwater steam generator 2, weld 59-21R, pipe to elbow
- charging line, weld 37-33, reducer to pipe
- charging line, weld 37-34, pipe to elbow
- pressurizer spray 1B, weld 28-41, pipe to elbow
- pressurizer spray 1B, weld 28-42, pipe to elbow
- pressurizer spray 1B, weld 28-45, safe-end to pipe
- safety injection B, weld 75-27, pipe to elbow Dye Penetrant Examination
- safety injection, part SI-119-H-014-W
- charging system, part CH-005-H-019-W Visual VT-1 Examination
- pressurizer manway studs and nuts, component 1MRCEX02 Welding Activities
- automatic gas tungsten arc welding o
pressurizer instrument half-nozzle repair PWR Inservice Inspection Activities Sample - Vessel Upper Head Penetration Inspection Activities (IP Section 03.02)
The inspectors verified that no upper reactor vessel head penetration inspections were required this outage.
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)
- CR-25-2585 1PSIAVA07
- CR 25-2586 1JSICUV0653
- CR 25-2663 1PRCEV242
- CR 25-2665 1JSIAPSV0469
- CR-25-2666 1JSIBUV0616
- CR-25-2668 1JSIBUV0614
- CR 25-2675 1JSIBUV0638 PWR Inservice Inspection Activities Sample - Steam Generator Tube Inspection Activities (Section 03.04) (1 Sample)
The inspectors verified that the licensee is monitoring the steam generator tube integrity appropriately through a review of the following examinations:
(1)
- one-hundred percent of the tubes in steam generator SG11 and SG12 were inspected via eddy current methods
- secondary side steam generators SG11 and SG12 were visually inspected
- high pressure feedwater heaters 5A and 6A were visually inspected and tubes inspected via eddy current methods
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)
The inspectors observed and evaluated licensed operator performance in the control room during the following activities:
- (1) Unit 3, down power to repair a switchyard motor operated disconnect, on April 28, 2025
- (2) Unit 1, startup activities following completion of refueling outage 1R25, on May 9, 2025
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, class 1E 480 Vdc load center train B, on May 23, 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, planned maintenance on emergency diesel generator train B, on June 10, 2025
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) Unit 1, class 1E 125 Vdc battery PK-C functionality assessment due to discharge test results showing lower capacity than expected, on April 3, 2025
- (2) Unit 1, emergency diesel generator train A operability determination due to automatic voltage regulator swap following failure to control voltage, on April 22, 2025
- (3) Unit 1, steam generator atmospheric dump valves, SGB-HV-178 and SGB-HV-185, operability determination due to excessive leakage during inservice testing, on April 7, 2025
- (4) Unit 1 containment spray train A operability determination due to voids discovered during surveillance testing, on May 21, 2025
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) Unit 1, permanent modification to upgrade the balance of plant engineered safety features actuation system channel B to address component obsolescence and equipment failure issues, on May 13, 2025
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated the Unit 1 refueling outage 1R25 activities from March 28 to May 14, 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) (9 Samples)
- (1) Unit 2, coolant charging pump E seal lube pump replacement, on April 4, 2025
- (2) Unit 1, refueling water tank level transmitter channel A post-maintenance testing following transmitter replacement, on April 30, 2025
- (3) Unit 1, low-pressure safety injection pump B post-maintenance testing following mechanical seal replacement, on April 30, 2025
- (4) Unit 1, shutdown cooling suction from containment recirculation sump valve SIB-UV-675 post-maintenance test following seat ring replacement, on April 30, 2025
- (5) Unit 1, essential chiller B post-maintenance testing following eddy current testing and repairs, on May 6, 2025
- (6) Unit 1, safety injection tank B to reactor coolant loop check valve SIE-V-247 post-maintenance test following repairs, on May 15, 2025
- (7) Unit 3, emergency diesel generator train A post-maintenance testing following maintenance outage, on May 16, 2025
- (8) Unit 1, engineered safety features train B post-maintenance testing following balance of plant engineered safety features actuation system upgrade, on May 20, 2025
- (9) Unit 1, reactor coolant pump 2A post-maintenance testing following mechanical seal replacement, on June 17, 2025
Surveillance Testing (IP Section 03.01) (2 Samples)
- (1) Unit 1, remote input system voltage testing, on April 30, 2025
- (2) Unit 2, turbine-driven auxiliary feedwater pump testing, on June 5, 2025
Inservice Testing (IST) (IP Section 03.01) (1 Sample)
- (1) Unit 1, low-pressure safety injection pump B inservice testing, on May 14, 2025
Containment Isolation Valve (CIV) Testing (IP Section 03.01) (1 Sample)
- (1) Unit 1, pressurizer steam space sample header containment isolation valve SSA-UV-205 testing, on May 27, 2025
Diverse and Flexible Coping Strategies (FLEX) Testing (IP Section 03.02) (1 Sample)
- (1) Units 1, 2, and 3, FLEX spent fuel pool make up pumps, on May 6,
RADIATION SAFETY
71124.01 - Radiological Hazard Assessment and Exposure Controls
Radiological Hazard Assessment (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated how the licensee identifies the magnitude and extent of radiation levels and the concentrations and quantities of radioactive materials and how the licensee assesses radiological hazards.
Instructions to Workers (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated how the licensee instructs workers on plant-related radiological hazards and the radiation protection requirements intended to protect workers from those hazards.
Contamination and Radioactive Material Control (IP Section 03.03) (3 Samples)
The inspectors observed/evaluated the following licensee processes for monitoring and controlling contamination and radioactive material:
(1)surveys of potentially contaminated packages/equipment from the radiologically controlled area and workers exiting potentially contaminated areas (2)labeling for several nonexempt radioactive sources listed in the licensee's source inventory in Unit 2 and Unit 3, including the following specific Unit 1 RP sources13-011, 24-001, and RP-179 (3)physical and programmatic controls for highly activated and contaminated non-fuel materials stored within the spent fuel pool including radwaste filter canisters
Radiological Hazards Control and Work Coverage (IP Section 03.04) (4 Samples)
The inspectors evaluated the licensee's control of radiological hazards for the following radiological work:
(1)medium and high risk radiological work and job coverage for reactor inboard loop discharge check valve disassembly, inspection, lapping in-body seats for low-pressure safety injection and repair of safety injection valves SIE-V-245 and 247 (RWPs 1-3125 and 3321 tasks 30 and 50)
(2)medium and high risk radiological work and job coverage for primary side steam generator (SG-1) maintenance and eddy current (ET) testing activities for Unit 1 reactor (RWP 1-3306-R25, all tasks)
(3)high risk radiological work and job coverage for pressurizer nozzle work (RWP 1-3425-R25)
- (4) Unit 1 in-core instrumentation area chase inspections (RWP 1-3325-R25)
High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (4 Samples)
The inspectors evaluated licensee controls of the following high radiation areas (HRAs) and very high radiation areas (VHRAs):
(1)
(VHRA) Unit 1 under vessel access on the 80-foot containment elevation (2)
(HRA) Unit 1 regenerative heat exchanger room on the 111-foot containment elevation (3)
(HRA) Unit 1 reactor vessel head stand on the 140-foot containment elevation (4)
(LHRAs) Units 1, 2, & 3 high level storage area on the 120-foot elevation of the radwaste building Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 03.06) (1 Sample)
- (1) The inspectors evaluated radiation worker and radiation protection technician performance as it pertains to radiation protection requirements.
71124.04 - Occupational Dose Assessment
Source Term Characterization (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated licensee performance as it pertains to radioactive source term characterization.
External Dosimetry (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated how the licensee processes, stores, and uses external dosimetry.
Internal Dosimetry (IP Section 03.03) (3 Samples)
The inspectors evaluated the following internal dose assessments:
- (1) CR-1-23-11265, Dose Assessment, dated July 23, 2024
- (2) PCE 2-24-0005, Dose Assessment, dated November 26, 2024
- (3) CR-1-23-11087, Dose Assessment, dated April 28, 2024
Special Dosimetric Situations (IP Section 03.04) (2 Samples)
The inspectors evaluated the following special dosimetric situations:
- (1) use of multi-pack dosimetry and dose assignment on activities related to work orders
===5405544, 5419142, and 5456945 (2)monitoring of three declared pregnant workers and their associated NRC Form 5s
OTHER ACTIVITIES - BASELINE
71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04)===
- (1) Unit 1 (April 1, 2024, through March 31, 2025)
- (2) Unit 2 (April 1, 2024, through March 31, 2025)
- (3) Unit 3 (April 1, 2024, through March 31, 2025)
OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)
- (1) Units 1, 2, and 3 (October 1, 2024, through March 31, 2025)
PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample (IP Section 02.16) (1 Sample)
- (1) Units 1, 2, and 3 (October 1, 2024, through March 31, 2025)
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 issue:
- (1) Accidental discharge during a dry fire exercise inside of the security training building on February 11, 2025. This included the site level one evaluation 25-01522-002 completed on March 27, 2025.
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 05000530/2024-003-00, PVNGS Unit 3 Violation of Technical Specifications 3.9.2 and 3.3.12, Agencywide Documents Access and Management System (ADAMS) Accession No. ML24347A138. The inspection conclusions associated with this LER are documented in inspection report 050000530/2024003. This LER is closed.
Personnel Performance (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated the loss of Unit 1 emergency diesel generator A resulting in a declaration of unusual event CU2.1, Loss of all but one AC Power source to emergency buses for 15 minutes or longer and the licensee response on April 10,
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On April 14, 2025, the inspectors presented the occupational radiation safety inspection results to Jennifer Spina, Vice President, Nuclear Regulatory & Oversight, and other members of the licensee staff.
- On June 27, 2025, the inspectors presented the Unit 1 inservice inspection results to Jennifer Spina, Vice President, Nuclear Regulatory & Oversight, and other members of the licensee staff.
- On July 8, 2025, the inspectors presented the integrated inspection results to Mike DiLorenzo, Acting Director, Nuclear Regulatory Affairs, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
25-02122
Drawings
01-M-NCP-002
Piping & Instrumentation Diagram Nuclear Cooling Water
System
Drawings
01-M-PCP-001
Piping & Instrumentation Diagram Fuel Pool Cooling &
Cleanup System
Drawings
03-M-CHP-002
Piping & Instrumentation Diagram Chemical and Volume
Control System
Drawings
03-M-FPP-004
P & I diagram fire protection system (CO2 system)
Drawings
03-M-SIP-001
Piping & Instrumentation Diagram Safety Injection &
Shutdown Cooling System
Drawings
03-M-SIP-002
Piping & Instrumentation Diagram Safety Injection &
Shutdown Cooling System
Engineering
Evaluations
4758718
Engineering Evaluation
Procedures
CO2 fire protection (CARDOX)
Procedures
Loss of [spent fuel pool] SFP Level or Cooling
Procedures
Reduced Inventory Operations
Procedures
FLEX Support Guidelines Mode 5, 6, or Defueled
Procedures
Fuel Pool Cooling
Procedures
Shutdown Cooling Initiation
Procedures
Reactor Coolant System Drain Operations
Procedures
Outage General Operating Procedure (GOP)
Calculations
13-MC-FP-0803
Combustible Loads - Control Building
Corrective Action
Documents
25-05151, 19-06334, 23-10795, 23-05322, 25-06454,
FSCCR 5729570, CRDR 2960716, CRDR 2960717
Drawings
M650-00410
Auxiliary Building 100 Northeast Corridor
Miscellaneous
Palo Verde Generating Station Pre-Fire Strategies Manual
Miscellaneous
Pre-Fire Strategies Manual
Procedures
Fire Point Inactivation and Activation Administrative
Guidance
Calculations
13-MC-ZA-0809
As Built Auxiliary Building Flooding Calculation
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Calculations
13-MC-ZY-0599
Essential Pipe Density Tunnel Flooding
Calculations
13-MC-ZY-0599
Essential Pipe Density Tunnel Flooding
Corrective Action
Documents
23-07148
Corrective Action
Documents
25-04112, 25-03985
Miscellaneous
25-0360
Eddy Current Examination Report
Miscellaneous
AN449-A00029
Belzona 1111 Super Metal Product Data and Application
Instructions
Miscellaneous
AN449-A00030
Belzona 1321 Super Metal Product Data and Application
Instructions
Miscellaneous
VTM-S445-00001
Struthers Wells Corporation Turbine, Nuclear, Fuel Pool and
Essential Cooling Water Heat Exchangers
Procedures
Mechanical System Cleanliness
Procedures
Tube Plugging of the Essential Cooling Water Heat
Exchanger
Procedures
Tube Plugging of the Essential Cooling Water Heat
Exchanger
Procedures
Control of Painting and Coating Operations
Procedures
Heat Exchanger Visual Inspection
Procedures
Eddy Current Examination of Tubing
Work Orders
5591895, 5592316, 5574324
Corrective Action
Documents
25-04561
Engineering
Changes
23-10254-025
RC-1911 Unit 1 Pressurizer Upper and Lower Head
Instrument Nozzle Replacement
04/14/2025
Engineering
Evaluations
25-03798-002
Lever 3 Evaluation Report
04/20/2025
Engineering
Evaluations
MN725-A02143
Palo Verde Generating Station U1R25 Steam Generator
Condition Monitoring Evaluation
05/05/2025
Miscellaneous
Standard Maneuver Plan: Unit 3 Cycle 25, 350 EFPD 100%
to 12%
Procedures
Initial Reactor Startup Following Refuelings
Procedures
Power Operations
153
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
VTD-A915-00165
ABB Installation/Maintenance instructions for I-T-E low
voltage AC metal-enclosed power switchgear K-Line
Miscellaneous
VTD-A915-00169
ABB Installation & Maintenance instructions for low-voltage
power circuit breakers type K-225 thru 2000& K-6000s thru
2000s
Miscellaneous
VTD-A915-00175
ABB Maintenance and Surveillance for low-voltage
switchgear equipment K-Line
Procedures
Inspection/Cleaning of 1E and Non-1E 480 Volt Load
Centers
Work Orders
5591598
Corrective Action
Documents
25-03388, 25-04140, 25-00893, 25-00893-002, 24-00699,
25-00978, 25-00980, 25-02049, 25-02086, 25-05395
Drawings
13-M01-01239
Regulator Chassis Schematic
Engineering
Evaluations
25-00893-001
Minor Leaks Identified Per CMWO 5596546
Miscellaneous
13-MS-B067
Containment Spray System Evaluation for Minor Amounts of
Air Remaining in Piping Following Normal Venting Activities
Miscellaneous
13-MS-B092
Development of ECCS Discharge Side Piping Arc Lengths
Associated with Calculated Max Void Volumes
Miscellaneous
VTD-E940-0003
Engine System Company Installation Operating And
Maintenance Manual For Dual Automatic Voltage Regulator
System Upgrades
Procedures
Conduct of Maintenance
Procedures
Toolpouch and Minor Maintenance Process
Procedures
Operations Operability Determination Process
Procedures
Operations Operability Determination Process Administrative
Guideline
Procedures
Procedures
Train A LPSI and CS System Alignment Verification
Procedures
Surveillance Testing
Procedures
[Atmospheric dump valves] ADVs - Inservice Test
Corrective Action
Documents
25-01352, 25-04326, 25-04144, 25-04396, 25-04748, 25-
04748
Miscellaneous
CFR 50.59 Screening/Evaluation for EC 2589411
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
BOP-ESFAS Replacement
Miscellaneous
Specification 13-
JM-0104
Balance of Plant Engineered Safety Feature Actuation
System
Procedures
Work Orders
5600334, 5232544
Miscellaneous
Specific Maneuvering Plan 500 EFPD 100 To 26.7% For
EOC Shutdown Unit 1 Cycle 25
Miscellaneous
Specific Maneuver Plan: EOC Shutdown 90% to 20% Unit 2
Cycle 24
Miscellaneous
Reactor Coolant System Pressure And Temperature Limits
Report (PTLR), Technical Requirements Manual Appendix
TA
Miscellaneous
TRM APPX TA Reactor Coolant System Pressure and
Temperature Limits Report
Procedures
Field Use Of Rigging
Procedures
Reactor Vessel Head Removal And Installation, Multiple
Pass Multi-Stud Tensioner
Procedures
Miscellaneous Containment Building Heavy Loads
Procedures
Lower Mode Functional Recovery Technical Guideline
Procedures
Standard post trip actions
Procedures
Lower Mode Functional Recovery
Procedures
Reactor Coolant Pump Operation
Procedures
Procedures
Shutdown Cooling Initiation
Procedures
Outage general operating procedure (GOP)
Procedures
Reactor Coolant System (RCS) and Pressurizer Heatup and
Cooldown Rates
Procedures
Containment Cleanliness Inspection
Procedures
Shutdown Margin - Modes 3, 4, and 5
Calculations
2011-00315
Incorporated Essential Chiller Tubing Minimum Allowable
Wall Calculations
Calculations
Eddy Current Examination Of Tubing
Corrective Action
25-04471, 25-04298, 25-03122, 21-07136, 25-05929
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Documents
Corrective Action
Documents
Resulting from
Inspection
25-06490
Drawings
01-M-ECP-0001
Piping & Instrumentation Diagram Essential Chilled Water
System
Drawings
N001-0902-
00039
Sectional Assembly (LPSI pumps) DMWO 00739596
Drawings
N001-0902-
00040
Sectional Assembly (LPSI pumps) DMWO 00739596
Drawings
N001-0902-
00042
Mechanical Seal Drawing (LPSI pump)
Engineering
Evaluations
24-04772-001
Commercial Grade Item Dedication Technical Evaluation For
Item 50001406
Miscellaneous
PVGS Diverse and Flexible Coping Strategies (FLEX)
Program
Procedures
FLEX SFP Makeup Pump Inspections and Tests
Procedures
Reactor Coolant Pump Sulzer Bingham Seal Replacement
Procedures
Low Pressure Safety Injection Pump Maintenance
Procedures
Cleaning, Inspection, and Testing of the Class 1E Diesel
Generator
Procedures
PPS Input Loop Calibration for Parameter 20, LO RWT
LEVEL
Procedures
PPS Transmitter Response Time Test Outside Containment
Procedures
Disassembly/Assembly of Limitorque Type SMB/SB-00
Actuators
Procedures
FLEX Support Guidelines
Procedures
CVCS Normal Operations
Procedures
Containment Leakage Rate Testing Program
Procedures
Containment Leakage Type B and C Testing
Procedures
Class 1E Diesel Generator Load Rejection, 24 Hour Rated
Load and Hot Start Test Train B
Procedures
Low Pressure Safety Injection Pumps Miniflow - Inservice
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Test
Procedures
LPSI Pumps Full Flow - Inservice Test
Procedures
Containment Recirculation Sump Isolation Valve Leak
Testing
Procedures
Out of Tolerance Program Controls
Work Orders
5707412, 5692288, 5584954, 5589654, 5585313, 5605691,
5589705. 5585313, 5578080, 5582630, 5582692, 5582721,
5582631, 5582652, 5362206, 5585266, 5585309, 5600216,
5592425, 5592040, 5392331
ALARA Plans
ALARA 5-Year Plan 2021 - 2025
2/16/2023
ALARA Plans
RWP-3002
Reactor Destack and Restack
ALARA Plans
RWP-3306
Steam Generator Maintenance and Support
ALARA Plans
RWP-3411
Repairs on Pressurizer Nozzles
ALARA Plans
RWP-3502
Valve, Flange, and Pump Maintenance and Inspection
ALARA Plans
RWP-3521
High Risk - Inboard Loop Discharge Check Valve Work
Corrective Action
Documents
24-11031, 24-11601, 24-11695, 25-00057, 25-00238,
25-00437, 25-00536, 25-00872, 25-02109, 25-02190,
25-03348
Corrective Action
Documents
Resulting from
Inspection
25-03726, 25-03980, 25-4016, 25-4021, 25-04083,
Procedures
Control of SNM Configuration, Inventory & Reporting
Procedures
Radiological Posting and Labeling
Procedures
Radiation Exposure and Access Control
Procedures
Control of High Radiation Areas, Locked High Radiation
Areas, and Very High Radiation Areas
Procedures
Personnel Contamination Monitoring
Procedures
Contamination Dose Evaluation
Procedures
Radiation and Contamination Surveys
Procedures
Conduct of R.P. Operations
Procedures
Special Dosimetry
Radiation
Surveys
0-M-20240826-1
Low-Level Radioactive Material Storage Facility (LLRMSF)
08/26/2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Radiation
Surveys
1-M-20230919-5
U1R24 Containment Power Entry
09/22/2023
Radiation
Surveys
1-M-20231102-10
1R24 55' and 100' Incore Chase
11/04/2023
Radiation
Surveys
1-M-20240628-1
AD08 - Equipment Drain Tank
06/28/2024
Radiation
Surveys
1-M-20240816-3
R124 Resin Transfer Gallery
09/11/2024
Radiation
Surveys
1-M-20240816-4
R101 High Level Storage Area
09/24/2024
Radiation Work
Permits (RWPs)
1-3002-R25
Reactor Head Destack/Restack (High Risk)
Radiation Work
Permits (RWPs)
1-3306-R25
Steam Generator Maintenance (High Risk)
Radiation Work
Permits (RWPs)
1-3502-R25
Valve, Flange, and Pump Maintenance (Medium Risk)
Radiation Work
Permits (RWPs)
1-3521-R25
Inboard Loop Discharge Check Valve (High Risk)
Radiation Work
Permits (RWPs)
RWP-9-1021
L..R. Evaporator and Boric Acid Concentrator System
Maintenance
Self-Assessments
Integrated Performance Assessment -Radiation Protection
01/31/2025
Self-Assessments 202502
Radiological Safety Trends
2/28/2025
Self-Assessments24-002
Offsite Safety Review Committee Meeting
10/09/2024
Calculations
Intake Dose Assessment - HPID 25371 PCE 2-24-0005
11/26/2024
Calculations
Intake Dose Assessment - HPID 31511 CR 1-23-11087
04/28/2024
Calculations
Intake Dose Assessment - HPID 20995
2/21/2023
Calculations
Intake Dose Assessment - HPID25801
07/23/2024
Corrective Action
Documents
23-04285, 23-05711, 23-07340, 23-07524, 23-07659,
23-07738, 23-09984, 23-11516, 23-11679, 24-04309,
24-06677, 24-08113, 24-10135, 24-12058, 24-12127,
25-00306, 25-01640
Miscellaneous
National Voluntary Laboratory Accreditation Program On-
Site Assessment
05/24/2024
Miscellaneous
1-23-0050
Air Sample
10/29/2023
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
1-23-00548
Air Sample
10/26/2023
Miscellaneous
1-23-00549
Air Sample
10/29/2023
Miscellaneous
1-23-00694
Air Sample
11/2/2023
Procedures
Radioactive Contamination Control
Procedures
Radiation Exposure and Access Control
Procedures
DLR Issue, Exchange, and Termination
Procedures
Dosimetry Processing, Evaluation, and Documentation
Procedures
Operation of the Whole Body Counters with APEX-InVivo
Software
Procedures
Bioassay Analysis
Procedures
Personnel Contamination Monitoring
Procedures
Special Dosimetry
Self-Assessments
Palo Verde Generating Station Dosimetry Program 2022
NVLAP Internal Audit
05/11/2023
71151
Miscellaneous
SSFF 1 April 2024 - 31 March 2025 PIC Data
71151
Miscellaneous
Unit 1 OR/PR01
Performance Indicator Occupational/Public Radiation Safety
Cornerstone Summary Report - Unit 1
03/18/2025
71151
Miscellaneous
Unit 2 OR/PR02
Performance Indicator Occupational/Public Radiation Safety
Cornerstone Summary Report - Unit 2
03/18/2025
71151
Miscellaneous
Unit 3 OR/PR03
Performance Indicator Occupational/Public Radiation Safety
Cornerstone Summary Report - Unit 3
03/18/2025
71151
Procedures
Performance Indicator Public Radiation Safety Cornerstone
71151
Procedures
NRC ROP PI Data Collection, Verification, and Submittal
71151
Procedures
SSFF Mitigating Systems Performance Indicator
Corrective Action
Documents
25-01522
Corrective Action
Documents
Resulting from
Inspection
25-05964
Corrective Action
Documents
25-004142, 24-03849, 22-06446
Miscellaneous
Formal Troubleshooting Game Plan: Troubleshoot
1JDGAB02 Bridge 2 Components
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
Excore Startup Channel and Boron Dilution Alarm System
Calibration
Procedures
Operations Operability Determination Process,
Procedures
Boron Dilution System Inoperable
Work Orders
5503044, 5617375