IR 05000528/2025003
| ML25350C236 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 12/16/2025 |
| From: | John Dixon NRC/RGN-IV/DORS/PBD |
| To: | Heflin A Arizona Public Service Co |
| Sanchez A | |
| References | |
| IR 2025003 | |
| Download: ML25350C236 (0) | |
Text
December 16, 2025
SUBJECT:
PALO VERDE NUCLEAR GENERATING STATION - INTEGRATED INSPECTION REPORT 05000528/2025003 AND 05000529/2025003 AND 05000530/2025003
Dear Adam Heflin:
On September 30, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Palo Verde Nuclear Generating Station. On December 9, 2025, the NRC inspectors discussed the results of this inspection with Cary Harbor, Senior Vice President, Site Operations and other members of your staff. The results of this inspection are documented in the enclosed report.
Due to the temporary cessation of government operations, which commenced on October 1, 2025, the NRC began operating under its Office of Management and Budget-approved plan for operations during a lapse in appropriations. Consistent with that plan, the NRC operated at reduced staffing levels throughout the duration of the shutdown. However, the NRC continued to perform critical health and safety functions and make progress on other high-priority activities associated with the ADVANCE Act and Executive Order 14300. On November 13, 2025, following the passage of a continuing resolution, the NRC resumed normal operations.
However, due to the 43-day lapse in normal operations, the Office of Nuclear Reactor Regulation granted the Regional Offices an extension on the issuance of the calendar year 2025 inspection reports that should have been issued by November 13, 2025, to December 31, 2025. The NRC resumed the routine cycle of issuing inspection reports on November 13, 2025.
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.
A licensee-identified violation which was determined to be of very low safety significance is also documented in this report. 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 violations or the significance or severity of the violations 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 Palo Verde Nuclear Generating Station.
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 Palo Verde Nuclear Generating Station.
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 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:
05000528/2025003, 05000529/2025003 and 05000530/2025003
Enterprise Identifier:
I-2025-003-0000
Licensee:
Arizona Public Service
Facility:
Palo Verde Nuclear Generating Station
Location:
Tonopah, AZ
Inspection Dates:
July 1, 2025 to September 30, 2025
Inspectors:
N. Armstrong, Resident Inspector
B. Baca, Health Physicist
N. Greene, Senior Health Physicist
E. Lantz, Sr Resident Inspector
J. Miller, Health Physicist
J. O'Donnell, Senior Health Physicist
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. A licensee-identified non-cited violation is documented in report section: 71111.1
List of Findings and Violations
Partial Loss of Offsite Power and Loss of Spent Fuel Pool Cooling due to Inadequate Procedure Cornerstone Significance Cross-Cutting Aspect Report Section Barrier Integrity Green NCV 05000528/2025003-01 Open/Closed
[H.12] - Avoid Complacency 71153 A self-revealed Green finding and associated Non-cited Violation (NCV) of Technical Specification 5.4.1.a was identified when the licensee failed to adequately establish and perform maintenance procedures appropriate to the circumstances, as required in Regulatory Guide 1.33, Quality Assurance Program Requirements, revision 2. Specifically, procedure 40OP-9SA02, De-Energization of BOP-ESFAS, revision 27, did not adequately ensure that the required step of lifting load shed relays K202 and K204 would be completed, resulting in a subsequent partial loss of offsite power and loos of spent fuel pool augmented cooling.
Additional Tracking Items
Type Issue Number Title Report Section Status LER 05000528/2025-003-00 LER 2025-003-00 for Palo Verde Nuclear Generating Station (PVNGS), Unit 1,
Specified System Actuation due to Loss of Power (LOP)/Load Shed (LS)
Signal 71153 Closed
PLANT STATUS
Unit 1 operated at or near full power for the duration of the inspection period.
Unit 2 entered the inspection period at full power. On September 16, 2025, the reactor was down powered to approximately 94 percent power to perform repairs to a circulating water pump due to increased vibrations and bearing temperatures. On September 20, 2025, the reactor returned to full power following repairs, where it remained for the remainder of the inspection period.
Unit 3 operated at or near full power for the duration 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 monsoon thunderstorms, on August 28, 2025.
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, containment spray train B due to overall system risk, on July 25, 2025
- (2) Unit 3, high-pressure safety injection train A during high-pressure safety injection train B maintenance, on August 22, 2025
- (3) Unit 2, turbine-driven auxiliary feedwater train A following inservice testing, on September 2, 2025
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (6 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, class 1E 4kV switchgear B room and class 1E battery channel B and D rooms, fire zones 5B, 8B, and 9B, on July 15, 2025
- (2) Units 1, 2, and 3, electrical penetration rooms, fire zones 42A and 42B, on July 23, 2025
- (3) Unit 2, lower cable spreading room, fire zones 11A, 11B, 12, 13 and 14, on August 20, 2025
- (4) Unit 2, turbine-driven and motor-driven auxiliary feedwater pump rooms, fire zones 72 and 73, on August 22, 2025
- (5) Unit 3, remote shutdown room fire zones, 10A and 10B, on August 26, 2025
- (6) Unit 2, essential switchgear train A and B rooms and emergency diesel generator train A and B rooms, fire zones 22A, 22B, 5A, and 5B, during emergency diesel generator A super outage, on September 24, 2025
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 licensed operator requalification simulator exam activities, on August 28, 2025.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (3 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) Units 1, 2, and 3, review of the 10 CFR 50.65(a)(3) periodic evaluation, on July 9, 2025
- (2) Units 1, 2, and 3, charging pump pulsation dampener train B, on September 5, 2025
- (3) Unit 2, emergency diesel generator train A, on September 26, 2025
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (5 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) Units 1, 2, and 3, 4.16 kV FLEX diesel generator A nonfunctional due to failed functional testing, on August 8, 2025
- (2) Unit 1, planned work on the number one station blackout generator after surveillance test failure, on September 2, 2025
- (3) Unit 2, high risk for emergent work on train B circulating water pump requiring unit down power, on September 18, 2025
- (4) Unit 2, emergent work on normal chiller containment isolation valve WCB-UV-61, on September 19, 2025
- (5) Unit 2, high risk for planned emergency diesel generator A outage, on September 27, 2025
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (7 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Unit 2, containment power access purge isolation valve, CPA-UV-4B, operability determination due to unexpectedly closing during containment venting, on July 15, 2025
- (2) Unit 3, emergency diesel generator train B operability determination due to master rod stud stretch measurements outside of specification, on July 22, 2025
- (3) Unit 1, main steam system operability determination due to failure of the support hanger 1SG042H011, on August 20, 2025
- (4) Unit 3, emergency diesel generator train A operability determination due to control board indication discrepancy, on August 20, 2025
- (5) Unit 1, control room essential air temperature controller system train B operability determination due to failed calibration, on September 5, 2025
- (6) Units 1, 2, and 3 essential cooling water trains A and B operability determination due to connection to non-seismically qualified piping during alarm response, on September 9, 2025
- (7) Unit 1, primary reactor coolant radiation monitor train B, SQB-RU-151, operability determination due to loss of communication with radiation monitoring system, on September 15, 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) (2 Samples)
- (1) Unit 3, high-pressure safety injection pump B post-maintenance testing following failed breaker replacement, on August 20, 2025
- (2) Unit 2, emergency diesel generator A after super outage, on September 30, 2025
Surveillance Testing (IP Section 03.01) (4 Samples)
- (1) Unit 1, emergency diesel generator train B, 24-hour rated load, load rejection, and hot start testing, on July 21, 2025
- (2) Unit 1, plant protection system bistable trip units functional surveillance testing, on August 6, 2025
- (3) Unit 3, low-pressure safety injection pump surveillance testing, on August 07, 2025
- (4) Unit 3, train B remote shutdown disconnect switch control circuit operability test, on September 19, 2025
71114.06 - Drill Evaluation
Required Emergency Preparedness Drill (1 Partial)
(1)
(Partial)
The inspectors evaluated an emergency preparedness drill, on August 5, 2025. The inspectors completed the inspection procedure sections 03.01 through 03.02.
Additional Drill and/or Training Evolution (2 Partials)
The inspectors evaluated:
(1)
(Partial)
The inspectors evaluated an emergency preparedness drill, on August 19, 2025. The inspectors completed the inspection procedure sections 03.01 through 03.02.
(2)
(Partial)
The inspectors evaluated an emergency preparedness drill, on September 3, 2025.
The inspectors completed the inspection procedure sections 03.01 through
RADIATION SAFETY
71124.05 - Radiation Monitoring Instrumentation
Walkdowns and Observations (IP Section 03.01) (5 Samples)
The inspectors evaluated the following radiation detection instrumentation during plant walkdowns:
(1)area radiation monitors in Unit 3 auxiliary building and radwaste building (2)portable survey instruments located in Unit 3 buildings and in the 'ready for use' shelving in Unit 3 (3)stationary radiation monitors in Units 1 and 3, including small article monitors, personnel contamination monitors, and portal monitors (4)laboratory instruments in Unit 2 count room, including a gamma spectroscopy system and a liquid scintillation counter (5)process radiation monitors in Unit 3 auxiliary building and radwaste building
Calibration and Testing Program (IP Section 03.02) (10 Samples)
- (1) Thermo-Scientific Model RO-20 ion chamber survey meter S/N 1411, September 10, 2025
- (2) Ludlum Model 26-1 frisker, S/N 18522, March 14, 2025
- (3) Mirion Amp-100 high range survey meter, S/N 5021191, January 15, 2025
- (4) Thermo Fischer Scientific SAM-12 small articles monitor, S/N 6710, November 6, 2024
- (5) Thermo Scientific iPCM12 contamination monitor, S/N 12024, January 30, 2025
- (6) Thermo Fischer Scientific PM12 portal monitor, S/N 1216, December 4, 2024
- (7) KAMAN 'B' Train containment high range monitor, SQBRU0149, April 16, 2025 (8)waste gas decay tank process radiation monitor, Unit 1, RU-12, August 20, 2025 (9)gamma spectroscopy system calibration verification, Unit 2, detector 2, S/N 11447, particulate filter on shelf 1, January 3, 2025
- (10) Beckman Coulter liquid scintillation counter, Unit 2, S/N 7070530. May 28, 2020 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) Unit 3, plant vent effluent low range, RU-143, October 30, 2024
- (2) Unit 1, fuel handling building B vent exhaust monitor low, RU-145, May 21, 2025
71124.06 - Radioactive Gaseous and Liquid Effluent Treatment
Walkdowns and Observations (IP Section 03.01) (4 Samples)
The inspectors evaluated the following radioactive effluent systems during walkdowns:
- (1) Units 2 and 3, plant vent exhaust system
- (2) Unit 1, radwaste building ventilation system
- (3) Units 1 and 3, fuel building exhaust system
- (4) Units 1 and 3, auxiliary building ventilation system
Sampling and Analysis (IP Section 03.02) (4 Samples)
Inspectors evaluated the following effluent samples, sampling processes and compensatory samples:
- (1) Unit 3, filter changeout for fuel building exhaust radiation monitoring system (RU-145)
- (2) Unit 2, grab sampling for primary to secondary leak rate (RU-141B) and liquid sampling for condensate demineralizer influent
- (3) Unit 1, auxiliary feed pump A steam release (AFA-P01)
- (4) Unit 3, plant vent exhaust grab sample (RU-143)
Dose Calculations (IP Section 03.03) (2 Samples)
The inspectors evaluated the following dose calculations:
(1)2025 annual dose evaluation for gaseous effluents for Unit 1 (January 1 to September 19, 2025)
(2)2024 annual dose evaluations for gaseous effluents for Unit 3 (January 1 to December 31, 2024)
Abnormal Discharges (IP Section 03.04)
There were no abnormal discharges for the inspectors to evaluate.
71124.07 - Radiological Environmental Monitoring Program
Environmental Monitoring Equipment and Sampling (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated environmental monitoring equipment and observed collection of environmental samples.
Radiological Environmental Monitoring Program (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the implementation of the licensees radiological environmental monitoring program.
GPI Implementation (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated the licensees implementation of the Groundwater Protection Initiative program to identify incomplete or discontinued program elements.
71124.08 - Radioactive Solid Waste Processing & Radioactive Material Handling, Storage, &
Transportation
Radioactive Material Storage (IP Section 03.01)
The inspectors evaluated the licensees performance in controlling, labeling and securing the following radioactive materials:
(1)within the dry active waste processing and storage facility (2)within Units 1 and 3 radwaste truck bays
Radioactive Waste System Walkdown (IP Section 03.02) (1 Sample)
The inspectors walked down the following accessible portions of the solid radioactive waste systems and evaluated system configuration and functionality:
- (1) Unit 3 solid radwaste system, specifically the resin processing and transfer system
Waste Characterization and Classification (IP Section 03.03) (2 Samples)
The inspectors evaluated the following characterization and classification of radioactive waste: (1)concentrates (2)dry active wastes
Shipment Preparation (IP Section 03.04) (1 Sample)
- (1) The inspectors observed the preparation and shipment of package 25-SH-050 containing radioactive material sent for analysis.
Shipping Records (IP Section 03.05) (3 Samples)
The inspectors evaluated the following non-accepted radioactive material shipments through a record review:
(1)shipment package 23-RW-019 containing low specific activity, LSA-II, metal oxides (2)shipment package 24-RW-046 containing type A dry active waste (3)shipment package 25-RW-010 containing low specific activity, LSA-I, metal oxides
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
MS06: Emergency AC Power Systems (IP Section 02.05)===
- (1) Unit 1 (July 1, 2024, through June 30, 2025)
- (2) Unit 2 (July 1, 2024, through June 30, 2025)
- (3) Unit 3 (July 1, 2024, through June 30, 2025)
MS07: High Pressure Injection Systems (IP Section 02.06) (3 Samples)
- (1) Unit 1 (July 1, 2024, through June 30, 2025)
- (2) Unit 2 (July 1, 2024, through June 30, 2025)
- (3) Unit 3 (July 1, 2024, through June 30, 2025)
MS08: Heat Removal Systems (IP Section 02.07) (3 Samples)
- (1) Unit 1 (July 1, 2024, through June 30, 2025)
- (2) Unit 2 (July 1, 2024, through June 30, 2025)
- (3) Unit 3 (July 1, 2024, through June 30, 2025)
MS09: Residual Heat Removal Systems (IP Section 02.08) (3 Samples)
- (1) Unit 1 (July 1, 2024, through June 30, 2025)
- (2) Unit 2 (July 1, 2024, through June 30, 2025)
- (3) Unit 3 (July 1, 2024, through June 30, 2025)
MS10: Cooling Water Support Systems (IP Section 02.09) (3 Samples)
- (1) Unit 1 (July 1, 2024, through June 30, 2025)
- (2) Unit 2 (July 1, 2024, through June 30, 2025)
- (3) Unit 3 (July 1, 2024, through June 30, 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 2025-003-00, Unit 1 Specified System Actuation due to Loss of Power (LOP)/Load Shed (LS) Signal (ADAMS Accession No. ML25156A358)
The inspection conclusions associated with this LER and associated finding are documented in the Inspection Results section 71153. This LER is closed.
INSPECTION RESULTS
Licensee-Identified Non-Cited Violation 71111.15 This violation of very low safety significance was identified by the licensee and has been entered into the licensee corrective action program and is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
Violation: Title10 CFR Part 50, Appendix B, Criterion III, Design Control, states, in part, that design control measures shall provide for verifying or checking the adequacy of design, such as by the performance of design reviews, by the use of alternate or simplified calculation methods, or by the performance of a suitable testing program.
Contrary to the above, until August 1, 2024, the licensee failed to provide design control measures for verifying or checking the adequacy of seismic qualification of the essential cooling water system, such as by the performance of design reviews or by the performance of a suitable testing program. Specifically, the licensees failure to check the adequacy of the design of the essential cooling water system by the performance of design reviews or engineering evaluation resulted in the inability of the essential cooling water system to maintain adequate water inventory to perform its safety-related function for the duration of its mission time during a seismic event resulting in a pipe break when isolation valves between non-quality related seismic category III piping and quality-class seismic category I piping were open, affecting the reliability of the essential cooling water system to respond to initiating events to prevent undesirable consequences.
Significance/Severity: Green. The inspectors determined the performance deficiency is more than minor because it adversely affected the Configuration Control attribute of the Mitigating Systems Cornerstone. The inspectors assessed the significance of the finding using Inspection Manual Chapter 0609 Appendix A, The Significance Determination Process for Findings At-Power, dated January 1, 2021. The inspectors screened the finding using Exhibit 2 - Mitigating Systems Screening Questions. The inspectors determined that the finding had very low safety significance (Green) because the valves in question have not been open for greater than the allowed technical specification outage time and the finding: 1) is not a deficiency affecting the design or qualification of a mitigating structure, system, or component; 2) does not represent a loss of the probability risk analysis (PRA) function of a single train TS system for greater than its TS allowed outage time; 3) does not represent a loss of the PRA function of one train of a multi-train TS system for greater than its TS allowed outage time; 4) does not represent a loss of the PRA function of two separate TS systems for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; 5) does not represent a loss of a PRA system and/or function as defined in the plant risk information e-book or the licensee's PRA for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; and 6) does not represent a loss of the PRA function of one or more non-TS trains of equipment designated as risk-significant in accordance with the licensee's maintenance rule program for greater than 3 days.
Corrective Action References: The licensee has documented the performance deficiency in their corrective action program in Condition Report 24-06486.
Partial Loss of Offsite Power and Loss of Spent Fuel Pool Cooling due to Inadequate Procedure Cornerstone Significance Cross-Cutting Aspect Report Section Barrier Integrity Green NCV 05000528/2025003-01 Open/Closed
[H.12] - Avoid Complacency 71153 A self-revealed Green finding and associated Non-cited Violation (NCV) of Technical Specification 5.4.1.a was identified when the licensee failed to adequately establish and perform maintenance procedures appropriate to the circumstances, as required in Regulatory Guide 1.33, Quality Assurance Program Requirements, revision 2. Specifically, procedure 40OP-9SA02, De-Energization of BOP-ESFAS, revision 27, did not adequately ensure that the required step of lifting load shed relays K202 and K204 would be completed, resulting in a subsequent partial loss of offsite power and loss of spent fuel pool augmented cooling.
Description:
On April 8, 2025, Unit 1 was defueled for refueling outage 1R25. Balance of Plant Engineered Safety Features Actuation System (BOP-ESFAS) trains A and B (safety-related) were deenergized for maintenance and the installation of a modification on train B using procedure 40OP-9SA02, De-Energization of BOP-ESFAS, revision 27. Unit 1 PBA-S03 Class 1E 4.16kV bus, which is normally powered through engineering safety features transformers, was being supplied by offsite power via the NBN-X04 non-class transformer through its alternate supply breaker PBA-S03K because breaker NBN-X03 was tagged out for planned maintenance. The licensee developed [AS2] [NA3] [AS4] Train A Emergency Diesel Generator (DG) Safety Protection Plan, revision 0 [AS5] to maintain the availability of EDG train A during the BOP-ESFAS de-energization and it was staged prior to the maintenance and operator responsibilities were briefed and logged at the beginning of every shift.
At 7:24 p.m., while BOP-ESFAS train A was being reenergized under procedure 40OP-9SA02, a valid loss of power/load shed signal actuated. This opened the PBA-S03K alternate supply breaker resulting in a loss of power to the PBA-S03 bus. The loss of power to PBA-S03 resulted in the associated train A equipment being de-energized, including the train A containment spray pump, which provided augmented cooling to the spent fuel pool and fuel pool cooling pump A. Operators implemented the Train A Emergency Diesel Generator (DG)
Safety Protection Plan, to manually start EDG A. Electrical power was restored to PBA-S03 bus at 7:34 p.m. from EDG A, and spent fuel pool cooling was restored using abnormal operating procedure 40AO-9ZZ23, Loss of Spent Fuel Pool Level/Cooling, revision 35.
The licensee initiated a condition report and performed a level 2 cause analysis to determine the cause of the event. The licensee determined that procedure 40OP-9SA02, De-Energization of BOP-ESFAS, revision 27, step 6.1.14 identified an action step to be performed by multiple users to notify the instrumentation and controls personnel to perform the steps to lift leads on the C2 terminals of the load shed relays K202 and K204.
However, with no subsequent step for operations personnel to confirm completion that instrumentation and controls had completed this step. This critical step to have instrumentation and control personnel lift the load shed relay leads had been marked N/A because of an assumption that lifting the leads was not required and had already been performed. Consequently, during the pre-job brief on the morning of April 8, 2025, for the re-energization of BOP-ESFAS train A, the unit shift manager and control room supervisor did not take issue or challenge the N/A of the non-conditional step to have the load shed leads lifted. The leads of the load shed relays K202 and K204 not being lifted during the energizing of BOP-ESFAS train A resulted in the valid loss of power/load shed signal, opening of the PBA-S03K breaker, and subsequent loss of power to PBA-S03 bus and spent fuel pool cooling.
Corrective Actions: The licensee entered abnormal operating procedures 40AO-9ZZ12, Degraded Electrical Power, revision 84, and 40AO-9ZZ23, Loss of SFP Level or Cooling, revision 35, to manually start EDG A and restore power to the PBA-S03 bus. This restored power to containment spray pump A which restored augmented spent fuel pool cooling.
Corrective Action References: Condition Report 25-04039
Performance Assessment:
Performance Deficiency: The failure to establish and implement written procedures appropriate to the circumstance for maintenance that can affect the performance of safety-related equipment is a performance deficiency. The cause was reasonably within the licensees ability to foresee and correct because the licensee failed to establish written procedures that would ensure the successful completion of lifting the load shed relay leads.
Specifically, the licensees procedure 40OP-9SA-02, De-Energization of BOP-ESFAS, revision 27, step 6.1.14 only required the notification to instrumentation and controls to perform the lifting of the load shed relay leads K202 and K204 without a requirement for confirmation of the completion of this step, directly resulting in a partial loss of off-site power and subsequent loss of augmented spent fuel pool cooling.
Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Configuration Control attribute of the Barrier Integrity cornerstone and adversely affected the cornerstone objective to provide reasonable assurance that physical design barriers protect the public from radionuclide releases caused by accidents or events. The inspectors determined the performance deficiency was more than minor because it was associated with the Configuration Control attribute of the Barrier Integrity cornerstone and adversely affected the cornerstone objective to provide reasonable assurance that physical design barriers protect the public from radionuclide releases caused by accidents or events. Specifically, the licensees failure to establish the procedure to install cross train jumpers and lift leads for the load shed relays to support de-energizing BOP-ESFAS train A was not written in a way to confirm completion. Not lifting the K202 and K204 relay leads resulted the partial loss of offsite power due to a valid loss of power/load shed signal resulting in the containment spray pump A to be deenergized and a loss of augmented cooling to the spent fuel pool, adversely affecting the spent fuel pools ability to protect the public from radionuclide releases caused by accidents or events.
Significance: The inspectors assessed the significance of the finding using IMC 0609 Appendix A, The Significance Determination Process (SDP) for Findings At-Power.
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. 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. Specifically, the licensees procedure 40OP-9SA02, De-Energization of BOP-ESFAS, revision 27, only provided and action step to notify instrumentation and control to install jumpers and lift the load shed relay leads with no subsequent step to confirm completion of their actions.
Enforcement:
Violation: Technical specification 5.4.1.a states in part, that written procedures shall be established, implemented, and maintained coveringthe applicable procedures recommended in Regulatory Guide 1.33, revision 2, Appendix A, section 9, Procedures for Performing Maintenance, which requires, in part, that maintenance that can affect the performance of safety-related equipment should be properly pre-planned and performed in accordance with written procedures, documented instruction, or drawings appropriate to the circumstances. The licensee established operating procedure 40OP-9SA02, De-Energization of BOP-ESFAS, revision 27 to meet this requirement.
Contrary to the above, on April 8, 2025, the licensee failed to adequately pre-plan and perform maintenance that can affect the performance of safety-related equipment in accordance with written procedures and documented instructions. Specifically, operating procedure 40OP-9SA02, De-Energization of BOP-ESFAS, revision 27 failed to include adequate instruction to lift relay leads K202 and K204, which resulted in a valid loss of power/load shed signal causing the loss of power to PBA-S03 bus and subsequent loss of containment spray pump A which was providing augmented cooling to the spent fuel pool.
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 that no proprietary information was retained or documented in this report.
- On September 25, 2025, the inspectors presented the radiation safety inspection results to Cary Harbor, Senior Vice President, Site Operations, and other members of the licensee staff.
- On December 9, 2025, the inspectors presented the integrated inspection results to Cary Harbor, Senior Vice President, Site Operations and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
Control and Monitoring of Potential Tornado Borne Missiles
Procedures
Acts of Nature
Procedures
Control of Doors, Hatches and Floor Plugs
Corrective Action
Documents
16-04430, 17-15953, 25-00048, 24-01709, 25-09056, 25-
09057
Drawings
01-M-SIP-001
P & I Diagram Safety Injection & Shutdown Cooling System
Drawings
2-M-AFP-001
P & I Diagram Auxiliary-Feedwater System
Drawings
2-M-SGP-001
P & I Diagram Main Steam System
Drawings
2-M-SIP-001
P & I Diagram Safety Injection & Shutdown Cooling System
Drawings
03-P-SIF-203
Auxiliary BLDG Isometric Safety Injection System HPSI
Pump DISCH Train A & RWT
Miscellaneous
2-9321469-002
Risk-Informed Application Document - Palo Verde
Generating Station 10CFR50.69 System Categorization
Document for Safety Injection
Procedures
Train B LPSI and CS System Alignment Verification
Procedures
Auxiliary Feedwater A - Inservice Test
Work Orders
25370, 5630668, 5610143, 5749401, 5625370, 5630668
Corrective Action
Documents
18-09532, FSCCR 5740572, 25-08940, 25-09001
Drawings
03-E-FPF-005
Control Wiring Diagram Fire Protection System
Drawings
13-A-ZJD-0501
Control Building and Corridor Building Floor Plan at
Elevation 74, 100, 120
Drawings
13-M-FPP-006
Auxiliary Building Channel B Cable Trays 100 Level East
Half
Drawings
13-M999-00004
Halon Fire Suppression System for Remote Shutdown
Room
Drawings
13-P-FPG-300
Schematic Diagram Halon-1301 Fire Protection System for
Remote Shutdown Rooms Train A and Train B @ 100ft
Elev.- Control BLDG.
Miscellaneous
Pre-Fire Strategies Manual
Procedures
Fire Detection/Protection System Supervised
Circuits/Functional Test - Halon Panels
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
Control of Doors, Hatches and Floor Plugs
Work Orders
5748465, 5749206
Corrective Action
Documents
25-09270
Miscellaneous
SES-0-04-P-09
Palo Verde Nuclear Generating Station Licensed Operator
Continuing Training Exam Scenario
Corrective Action
Documents
25-01315, 25-05599, 25-06225, 25-06227, 25-06328, 24-
07598, 25-01245, 25-01624, 25-02566, 25-02567, 25-
10497, 25-10422
Miscellaneous
Miscellaneous
5069-CH-01
CFR 50.69 System Categorization Chemical and Volume
Control System (CH)
Miscellaneous
5069-CH-01
CFR 50.69 System Categorization Chemical and Volume
Control System (CH)
Miscellaneous
MR-A1-EVAL-
25-0015
MR 2.0 - MR (a)(1) Issue Worksheet
Miscellaneous
PMB-CH, MR 2.0-
Performance Monitoring Bases Document Worksheet: CH
Procedures
CFR 50.69 Program
Procedures
CFR 50.69 Active Component Categorization From
Qualitative Assessment and Defense-In-Depth
Procedures
Installation and Removal of DG A Temporary Piping
Supports
Procedures
Annual Fire Protection Test for QDN-N06
Procedures
Cleaning, Inspection, and Testing of the Class 1E Diesel
Generator
Procedures
Control Room Fire
Procedures
Diesel Fuel Oil Storage and Transfer (DF)
Procedures
Maintenance Rule Monitoring Process
Work Orders
5733844, 5743998, 5635705, 5635582, 5635694, 5635808,
5635581, 5635635, 5631470
Corrective Action
Documents
25-08289, 25-08440, 24-12325, 25-10157, 25-08294, 25-
01094, 25-08699
Drawings
01-J-HJE-051
Instrument LOOP Wiring Diagram Control Building HVAC
Miscellaneous
Integrated Risk Assessment for SURV# 5631303
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
FME Risk Evaluation MEDDET-DB-ID 11341140
Miscellaneous
Site Integrated Risk Assessment Work Task 5744929-0
Miscellaneous
Formal Troubleshooting Game Plan-SBOG Overspeed
Troubleshooter Related to CR 25-08440 and WO 57444939-
Miscellaneous
PV-E2316
Risk Management and Readiness Plan
Miscellaneous
RICT-US-2025-01
Risk Informed Completion Time Summary
Procedures
Work Instruction for CM# 5744104 - Task #0
Procedures
Systematic Troubleshooting
Procedures
Online Integrated Risk
Procedures
FLEX 2 MW Diesel Generator Inspections and Tests
Procedures
Molded Case Circuit Breaker Test
Procedures
ESFAS Train B Subgroup Relay Functional Test
Procedures
Vibration Survey
Procedures
TSG-3: Site Capabilities
Procedures
FLEX Support Guidelines MODE 1, 2, 3, or 4
Procedures
FLEX Support Guidelines MODE 5, 6, or Defueled
Procedures
Diesel Generator Test
Procedures
Assessment and Management of Risk When Performing
Maintenance in Modes 1 and 2
Procedures
M008-00032
Pump Cross Section Bottom Half
Procedures
M008-00041
Assembly of Shaft and Impeller 1076/PI-49 DWG 80257,
Procedures
M008-00049
Assembly of Pump-Top-Half
Work Orders
5556503, 5585720, 5554860, 5744939, 5756974, 5744104,
5631303, 5746709
Calculations
13-MC-SG-0501
Main Steam Line Inside Containment
Corrective Action
Documents
25-07712, 17-13429, 18-14835, 19-03217, 25-01939, 25-
03392, 25-03411, 23-10262, 25-08334, 25-08543, 25-
06563, 25-08699, 24-06486, 24-13966
25-08100, 25-08468
Drawings
2-M-CPP-001
P & I Diagram Containment Purge System
Miscellaneous
PVNGS Design Basis Manual - Containment Purge System
Miscellaneous
EDC# 2005-00359
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
VTD-C628-00051
Cooper Energy Instruction Manual for KSV Turbocharged
Diesel Generating Unit for Nuclear Power Plant Emergency
Stand-By Service
Procedures
Procedure and Work Instruction Use and Adherence
Procedures
Operations Operability Determination Process
Procedures
Essential Cooling Water System (EW) Train A
Procedures
Essential Cooling Water System (EW) Train A
Procedures
Essential Cooling Water System (EW) Train A
Procedures
Procedures
Diesel Generator A Test
Procedures
Surveillance Testing
Procedures
CP (Power Access Purge) Valves - Inservice Test
Procedures
Actions for Non-Functional Radiation Monitors: Preplanned
Alternat Sampling Program
Procedures
RMS/Effluent Action Documentation
Work Orders
5710188, 5570282, 5614092, 5746709
Corrective Action
Documents
25-07934, 25-03940, 25-08564, 25-08739, 25-08808, 25-
08809, 25-09178, 25-09866, 25-09940, 24-06468, 25-
10085, 25-10083, 25-01094
Drawings
01-E-SBB-00005
E/D Plant Protection System Cabling Block Diagram
Drawings
03-M-SIP-0001
P&ID Diagram Safety Injection & Shutdown Cooling System
Drawings
N001-1303-00078
Plant Protection System Simplified Functional Diagram
VCE7914
Drawings
N001-1303-00805
PPS, Initiation Reset Panel Schematic VCE-31245
Procedures
PPS Bistable Trip Units Functional Test
Procedures
Diesel Generator Test Record
Procedures
Diesel Generator A Test
Procedures
Remote Shutdown Disconnect Switch and Control Circuit
Operability - All Modes
Procedures
Class 1E Diesel Generator Load Rejection, 24 Hour Rated
Load and Hot Start Test Train B
Procedures
HPSI Pumps Miniflow - Inservice Test
Procedures
Low Pressure Safety Injection Pumps Miniflow - Inservice
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Test
Work Orders
5553779, 5613929, 5614096, 5625443, 5625514, 5754304,
5631303
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
Procedures
Acts of Nature
Procedures
Standard Post Trip Actions
Procedures
ERO Positions - Operations Manager (TSC)
Procedures
ERO Positions - Emergency Coordinator (TSC)
Calibration
Records
AMS-4 S/N
2930
Certificate of Calibration
10/01/2024
Calibration
Records
DRM 2 S/N
2611031
DRM 1/2 Calibration Data Sheet
03/11/2025
Calibration
Records
H809V-1 S/N
2888
Air Sampler Calibration Data Sheet
2/13/2025
Calibration
Records
Model 30 S/N
25025219
Neutron Detector Calibration Data Sheet
04/19/2025
Calibration
Records
Model 89, SN
20
Shepherd Model 89 Verification Sheet
04/17/2025
Calibration
Records
SAM-12, S/N
6700
Small Article Monitor Calibration Data Sheet
09/25/2025
Calibration
Records
Unit 2, Detector 2
- CCART
MCA HpGE Geometry Calibration - Charcoal Cartridge on
shelf 1
07/21/2023
Calibration
Records
Unit 2, Detector 2
- PFIL
MCA HpGE Geometry Calibration - Particulate Filter on shelf
07/21/2023
Calibration
Records
Radiation Monitor Calibration for Baseline Process Monitors
- B train (1JSQBRU0030)
2/13/2025
Calibration
Records
Radiation Monitor Calibration for RU-144 (1JSQNRE0144)
05/10/2024
Calibration
Records
Radiation Monitor Calibration for Baseline Area Monitors - B
train (2JSQBRU0038)
06/11/2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Calibration
Records
Radiation Monitor Calibration for RU-143 (3JSQNRE0143)
11/04/2024
Corrective Action
Documents
15-08740, 21-01090, 21-10318, 22-13251, 23-06829, 23-
2468, 23-12634, 24-00528, 24-00817, 24-01436, 24-
01573, 24-02126, 24-03012, 24-04492, 24-05497, 24-
06992, 24-07132, 24-07327, 24-07541, 24-07720, 24-
07853, 24-08507, 24-09904, 24-10407, 24-10764, 24-
10782, 24-11204, 24-11352, 24-12110, 24-12712, 24-
2760, 24-13064, 25-00119, 25-03847, 25-06279, 25-
08795, 25-08911, 25-08981
Corrective Action
Documents
Resulting from
Inspection
25-13728
Procedures
Effluent Flowpath Process Flow Calibration
Procedures
Train B Radiation Monitoring Calibration Test for
Containment New Scope Area Monitors
Procedures
Calibration of the Thermo Eberline Model FH40G-L
Procedures
Calibration of the Thermo Scientific Model RO-20 Ion
Chamber Survey Meter
Procedures
Offsite Dose Calculation Manual, Palo Verde Nuclear
Generating Station, Units 1,2, and 3
Self-Assessments 2025-005
Nuclear Assurance Department Audi Report - Radiation
Safety
08/21/2025
Corrective Action
Documents
2-05735, 22-06299, 22-06989, 22-07092, 22-08280, 22-
08417, 22-08516, 22-08606, 22-09286, 22-09697, 22-
09851, 22-10795, 22-11462, 22-12337, 22-12469, 22-
2791, 23-03549, 23-08540, 23-08641, 23-09369, 23-
13094, 24-06225, 24-12924, 24-13086, 24-13186, 25-
04097, 25-05293, 25-07910, 25-07927
Corrective Action
Documents
Resulting from
Inspection
25-10387
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Drawings
01-M-HRP-001
P&I Diagram HVAC Radwaste Building
Drawings
01-P-ZRC-603
Radwaste Building - Level 3 HVAC Plan Between El. 140'-
0" and Roof
Drawings
03-P-ZRC-604
Radwaste Building - Level 4 HVAC Plan at Roof
Miscellaneous
Results of Radiochemistry Cross Check Program: Arizona
Public Service Palo Verde 4th Quarter 2022
04/20/2023
Miscellaneous
Results of Radiochemistry Cross Check Program: Arizona
Public Service Palo Verde 4th Quarter 2023
03/19/2024
Miscellaneous
Results of Radiochemistry Cross Check Program: Arizona
Public Service Palo Verde 4th Quarter 2024
2/25/2025
Miscellaneous
PVNGS Radioactive Effluent Release Permit Summary
Report: Units 1, 2, and 3 - Year 2022 (01/01/2022 -
2/31/2022)
22
Miscellaneous
PVNGS Radioactive Effluent Release Permit Summary
Report: Units 1, 2, and 3 - Year 2023 (01/01/2023 -
2/31/2023)
23
Miscellaneous
PVNGS Radioactive Effluent Release Permit Summary
Report: Units 1, 2, and 3 - Year 2024 (01/01/2024 -
2/31/2024)
24
Miscellaneous
PVNGS Radioactive Effluent Release Permit Summary
Report: Units 1, 2, and 3 - Year 2025 (01/01/2025 -
9/15/2025)
25
Miscellaneous
Offsite Dose Calculation Manual, Palo Verde Nuclear
Generating Station, Units 1, 2, and 3
Miscellaneous
Permit 2025-1-
25
Unit 1, auxiliary feed pump 'A' steam release (AFA-P01)
09/23/2025
Miscellaneous
Permit 2025-3-
110
Unit 3, filter changeout for fuel building exhaust radiation
monitoring system (RU-145)
09/23/2025
Miscellaneous
Permit 2025-3-
111
Unit 3, plant vent exhaust grab sample (RU-143)
09/23/2025
Miscellaneous
RCTSAI 1566
24 Palo Verde Nuclear Generating Station Units 1, 2, and
Annual Radioactive Effluent Release Report
04/17/2025
Miscellaneous
RCTSAI 1566
23 Palo Verde Nuclear Generating Station Units 1, 2, and
Annual Radioactive Effluent Release Report
04/17/2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
RCTSAI 1566
22 Palo Verde Nuclear Generating Station Units 1, 2, and
Annual Radioactive Effluent Release Report
04/24/2023
Miscellaneous
RCTSAI 1566
Updated 2023 Palo Verde Nuclear Generating Station Units
1, 2, and 3 Annual Radioactive Effluent Release Report
11/05/2024
Miscellaneous
RCTSAI 1643
23 Palo Verde Nuclear Generating Station Units 1, 2, and
Annual Radiological Environmental Operating Report
05/10/2024
Miscellaneous
RCTSAI 1643
24 Palo Verde Nuclear Generating Station Units 1, 2, and
Annual Radiological Environmental Operating Report
05/09/2025
Miscellaneous
Sample G2-25-
0845
Unit 2, grab sampling for primary to secondary leak rate
(RU-141B)
09/24/2025
Miscellaneous
Sample L2-25-
0846
Unit 2, liquid sampling for primary to secondary leak rate
with condensate demineralizer influent (CDI)
09/24/2025
Procedures
Operation of Gaseous Radwaste System
Procedures
Gaseous Radioactive Release Permits and Offsite Dose
Assessment
Procedures
Radiation Monitoring System Operations
Procedures
Radiation Monitoring System Alarm Response
Procedures
Radiation Monitor Alarm Setpoint Determinations
Procedures
RMS Sample Collection
Procedures
RU-143/RU-144 Sample Operations
Procedures
RU-145/146 Sample Operations
Procedures
Effluent Monitor Monthly Source Checks
Procedures
Radiation Monitoring System Shiftly Surveillance Test
Procedures
Determination of Primary-To-Secondary Leak Rate
Self-Assessments 2023-004
Nuclear Assurance Department (NAD) Audit Report:
Radiation Safety
09/13/2023
Self-Assessments 2025-005
Nuclear Assurance Department (NAD) Audit Report:
Radiation Safety
08/21/2025
Self-Assessments 302-03922
Offsite Safety Review Committee (OSRC) Meeting 24-001,
Operations, Chemistry, and Radiation Protection
Subcommittee Report
09/21/2023
Self-Assessments 302-03938
Offsite Safety Review Committee (OSRC) Meeting 24-001,
Operations, Chemistry, and Radiation Protection
Subcommittee Report
03/29/2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Self-Assessments 302-03945
Offsite Safety Review Committee (OSRC) Meeting 24-002,
Operations, Chemistry, and Radiation Protection
Subcommittee Report
10/08/2024
Work Orders
WO 5346472, 5397633, 5456538, 5487711, 5540561
Calibration
Records
5505031
77ST9RG051 METEOROLOGICAL SYSTEM
CALIBRATION
( REDUNDANT SYSTEM)
04/16/2024
Calibration
Records
5505114
77ST9RG041 METEOROLOGICAL SYSTEM
CALIBRATION (PRIMARY
SYSTEM)
04/17/2024
Calibration
Records
5550731
77ST9RG051 METEOROLOGICAL SYSTEM
CALIBRATION
( REDUNDANT SYSTEM)
10/28/2024
Calibration
Records
5550833
77ST9RG041 METEOROLOGICAL SYSTEM
CALIBRATION (PRIMARY
SYSTEM)
10/29/2024
Calibration
Records
5594117
77ST9RG051 METEOROLOGICAL SYSTEM
CALIBRATION
( REDUNDANT SYSTEM)
06/13/2025
Calibration
Records
5594490
77ST9RG041 METEOROLOGICAL SYSTEM
CALIBRATION (PRIMARY
SYSTEM)
06/17/2025
Corrective Action
Documents
2-05573, 22-05633, 22-05697, 22-06461, 22-06449, 22-
07142, 22-07921, 22-09005, 22-09144, 22-10006, 22-
11598, 22-12655, 22-13436, 22-13455, 23-01724, 23-
03754, 23-04147, 23-04635, 23-04847, 23-05482, 23-
05484, 23-05726, 23-05767, 23-06383, 23-06793, 23-
06794, 23-07026, 23-07088, 23-07256, 23-07460, 23-
07777, 23-08785, 23-09404, 23-12560, 23-12693, 23-
2897, 23-13147, 24-00302, 24-00356, 24-00886, 24-
2928, 24-03327, 24-03662, 24-04075, 24-04464, 24-
06117, 24-06216, 24-06761, 24-06778, 24-07269, 24-
07445, 24-07503, 24-08229, 24-08393, 24-08468, 24-
09818, 24-10327, 24-10864, 24-10891-001, 25-02622, 25-
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2626, 25-02876, 25-03981, 25-05492, 25-06308, 25-
06630, 25-06719, 25-06724, 25-06892, 25-08002, 25-
08530, 25-10425, 25-10425-001
Miscellaneous
117-127806-
24001
Pace Analytical Report
APS-Palo Verde Nuclear Generating Stat
Sample Delivery Group: L1835676
03/28/2025
Miscellaneous
117-127806-
24001
Pace Analytical Report
APS-Palo Verde Nuclear Generating Stat
Sample Delivery Group: L1851082
05/21/2025
Miscellaneous
ACT 4657834
REMP Air Sampling Siting Evaluation
11/14/2017
Miscellaneous
Legacy Item
No.036843.01
Annual Radiological Environmental Operating Report 2024
Palo Verde Nuclear Generating Station
RCTSAI 1643
05/09/2025
Miscellaneous
Legacy Item
No.036843.01
Annual Radiological Environmental Operating Report 2022
Palo Verde Nuclear Generating Station
RCTSAI 1643
03/30/2023
Miscellaneous
Legacy Item
No.036843.01
Annual Radiological Environmental Operating Report 2023
Palo Verde Nuclear Generating Station
RCTSAI 1643
05/09/2024
Miscellaneous
ODCM_Rev 33
OFFSITE DOSE CALCULATION MANUAL PALO VERDE
NUCLEAR GENERATING STATION
UNITS 1, 2, AND 3
Miscellaneous
PV-3A-0625
Pace Analytical Report
APS-Palo Verde Nuclear Generating Stat
Sample Delivery Group: L1868941
07/14/2025
Miscellaneous
Site 4
Trending_Rev3
Particulate Gross Beta in Air and Radioiodine in Air for 2023
Miscellaneous
TRM 072
Technical Requirements Manual
Miscellaneous
UFSAR REV22B
February 2025
Updated Final Safety Analysis Report
Palo Verde Nuclear Generating Station Units 1, 2, and 3
2B
Miscellaneous
USNRC Docket
24 ANNUAL RADIOACTIVE EFFLUENT RELEASE
04/15/2025
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
No. STN 50-
28/529/530
REPORT
PALO VERDE NUCLEAR GENERATING STATION UNITS
1, 2 AND 3
RCTSAI 1566
Miscellaneous
USNRC Docket
No. STN 50-
28/529/530
23 ANNUAL RADIOACTIVE EFFLUENT RELEASE
REPORT
PALO VERDE NUCLEAR GENERATING STATION UNITS
1, 2 AND 3
RCTSAI 1566
04/13/2024
Miscellaneous
USNRC Docket
No. STN 50-
28/529/530
22 ANNUAL RADIOACTIVE EFFLUENT RELEASE
REPORT
RCTSAI 1566
04/24/2023
Operability
Evaluations
218-04808-
MLC/MLC
Decommissioning Records Review and 10CFR50.75(g)(1)
Applicability Review
for 2021
06/16/2022
Operability
Evaluations
218-04895
22 Spill/Leak Decommissioning Impact Review
04/28/2023
Operability
Evaluations
218-05041
23 Spill/Leak Decommissioning Impact Review
03/19/2025
Operability
Evaluations
218-05042
24 Spill/Leak Decommissioning Impact Review
03/25/2025
Procedures
218-04808
Decommissioning Records Review and 10CFR50.75(g)(1)
Applicability Review
for 2021
07/16/2022
Procedures
218-04895
22 Spill/Leak Decommissioning Impact Review
04/28/2023
Procedures
218-04916
Decommissioning Records Review and 10CFR50.75(g)(1)
Applicability Review
for 2022
08/17/2023
Procedures
218-05041
23 Spill/Leak Decommissioning Impact Review
03/19/2025
Procedures
218-05042
24 Spill/Leak Decommissioning Impact Review
03/25/2025
Procedures
218-05050
Decommissioning Records Review and 10CFR 50.75(g)(1)
Applicability Review 2023 and 2024
04/30/2025
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
74-RM-0EN02
Radiological Environmental Air Sampling
Procedures
Operation of the Liquid Scintillation Systems
Procedures
Radiological Environmental Sampling
Procedures
Environmental TLD Exchange/Reporting
Procedures
Land Use Census
Procedures
Sentinel Well Sampling Instructions
Procedures
Groundwater Protection Program
Procedures
Meteorological System Instrumentation Replacement and
Verification (Primary System)
Procedures
Meteorological System Instrumentation Replacement and
Verification (Redundant System)
Self-Assessments Audit 2023-004
Nuclear Assurance Department (NAD) Audit Report
Self-Assessments Audit 2025-005
Nuclear Assurance Department (NAD) Audit Report
25-005 Radiation Safety
Corrective Action
Documents
23-07436, 23-12134, 23-12205, 24-07632, 24-07632, 25-
07151, 25-07747, 25-07777, 25-07778, 25-07779, 25-
07780, 25-07782, 25-07784, 25-07787, 25-10626
Miscellaneous
LLRMSF and SG Mausoleum Quarterly Testing and
Inspection
03/05/2024
Miscellaneous
LLRMSF and SG Mausoleum Quarterly Testing and
Inspection
09/25/2024
Miscellaneous
LLRMSF and SG Mausoleum Quarterly Testing and
Inspection
2/03/2024
Miscellaneous
Radiation Protection Logbook: Low Level Radioactive
Material Storage Facility (Monthly): July 2024 and February
25
Miscellaneous
LLRMSF and SG Mausoleum Quarterly Testing and
Inspection and Annual Maintenance
06/06/2024
Miscellaneous
ESD 86-35
CFR 37 Security Just in Time Training: Category 2
Radioactive Material
03/12/2014
Miscellaneous
ESD 86-44
Nuclear Security Training Lesson Plan: Protected Area
Mobile
08/22/2023
Miscellaneous
NBA11C000115
Radiation Protection Technician Training Program:
Packaging Radioactive Material
09/14/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
NBA19C000213
Radiation Protection Technician Training Program: Shipping
Radioactive Material
05/14/2021
Procedures
Palo Verde 10 CFR Part 37 Security Program Overview
Procedures
Security Miscellaneous Testing
Procedures
Control and Storage of Radioactive Material and Radioactive
Wastes
Procedures
Radioactive Source Control
Procedures
Radioactive Waste Management Program Overview
Procedures
Radwaste Process Control Program
Procedures
Waste Stream Sampling and Database Maintenance
Procedures
Packaging and Classification of Radioactive Waste
Procedures
Packaging of Radioactive Material
Procedures
Shipping Radioactive Materials
Procedures
High Integrity Container Receipt, Handling, Use, and
Closure
Procedures
Radioactive Waste Inventory
Procedures
Self-Engaging Rapid Dewatering System (SERDS)
Operation
Radiation
Surveys
0-M-20160205-3, 0-M-20170727-4, 0-M-20181126-4, 0-M-
250801-2, 0-M-20250917-3, 1-M-20250302-2, 1-M-
250314-3, 1-M-20250411-19, 1-M-20250702-4, 1-M-
250729-2, 1-M-20250806-2, 1-M-20250909-9, 1-M-
250910-3, 1-M-20250910-5, 2-M-20250320-4, 2-M-
250729-7, 2-M-20250806-1, 2-M-20250807-1, 2-M-
250903-2, 2-M-20250909-2, 2-M-20250909-3, 2-M-
250916-1, 2-M-20250916-2, 2-M-20250917-3, 2-M-
250923-1, 3-M-20250724-2, 3-M-20250724-3, 3-M-
250730-5, 3-M-20250730-8, 3-M-20250825-3, 3-M-
250901-2, 3-M-20250914-1, 3-M-20250917-2, 3-M-
250918-4
Radiation
Surveys
Filtered Radioactive Source Inventory, Leak Test, and
10CFR20 Appendix E Evaluation
07/15/2025
Radiation
Surveys
0-M-20250827-3
Monthly Survey: Dry Active Waste Processing System
Facility - processing area
08/27/2025
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Radiation
Surveys
3-25-00140
Gamma Isotopic Analysis: Soil sample from U3 Yard Non-
09/25/2025
Radiation
Surveys
3-25-00141
Gamma Isotopic Analysis: Soil sample from U3 Yard Non-
09/25/2025
Radiation
Surveys
3-25-00142
Gamma Isotopic Analysis: Soil sample from U3 Yard Non-
09/25/2025
Radiation
Surveys
3-25-00143
Gamma Isotopic Analysis: Soil sample from U3 Yard Non-
09/25/2025
Radiation
Surveys
3-25-00144
Gamma Isotopic Analysis: Soil sample from U3 Yard Non-
09/25/2025
Radiation
Surveys
3-25-00145
Gamma Isotopic Analysis: Soil sample from U3 Yard Non-
09/25/2025
Radiation
Surveys
3-25-00156
Gamma Isotopic Analysis: Soil sample from U3 Yard Non-
09/24/2025
Self-Assessments 2025-005
Nuclear Assurance Department Audit Report: Radiation
Safety
08/21/2025
Self-Assessments 2023-004
Nuclear Assurance Department Audit Report: Radiation
Safety
09/08/2023
Self-Assessments 2023-004
Nuclear Assurance Department Audit Report: Radiation
Safety
09/08/2023
Self-Assessments 2025-002
Nuclear Assurance Department Audit Report: Nuclear
Security
07/01/2025
Self-Assessments 2025-002
Nuclear Assurance Department Audit Report: Nuclear
Security
07/01/2025
Self-Assessments 2025-005
Nuclear Assurance Department Audit report: Radiation
Safety
08/21/2025
71151
Miscellaneous
Engage Health Maintenance Rule reports - Unavailability for
January 2022 - 30 June 2025
71151
Miscellaneous
Engage Health Maintenance Rule reports - MSPI Failures
for 1 January 2022 - 30 June 2025
71151
Miscellaneous
NRC Action Matrix PI Data Results for Palo Verde Unit 1
Second Quarter 2025
71151
Miscellaneous
NRC Action Matrix PI Data Results for Palo Verde Unit 2
Second Quarter 2025
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71151
Miscellaneous
NRC Action Matrix PI Data Results for Palo Verde Unit 3
Second Quarter 2025
71151
Miscellaneous
MSPI Margin Report-U1
07/17/2025
71151
Miscellaneous
MSPI Margin Report-U2
07/17/2025
71151
Miscellaneous
MSPI Margin Report-U3
07/17/2025
71151
Miscellaneous
13-NS-C075
MSPI Bases Document
71151
Procedures
Performance Index Data Mitigating Systems Cornerstone
71151
Procedures
NRC ROP PI Data Collection, Verification, and Submittal
71151
Procedures
Regulatory Assessment Performance Indicator Guideline
Corrective Action
Documents
25-04111
Miscellaneous
Miscellaneous
PCR 25-04111-001
Procedures
Procedure And Work Instruction Use and Adherence
Procedures
Degraded Electrical Power
Procedures
Loss of SFP Level or Cooling
Procedures
Procedures
Work Orders
232544, 5596311