ML25350C236
| 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 Adam Heflin, Executive Vice President and Chief Nuclear Officer Arizona Public Service P.O. Box 52034, MS 7602 Phoenix, AZ 85072-2034
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:
A. Heflin 2
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 cc w/ encl: Distribution via LISTSERV Signed by Dixon, John on 12/16/25
Non-Sensitive
Sensitive
Publicly Available
Non-Publicly Available OFFICE SRI:DORS/PBD RI:DORS/PBD SPE:DORS/PBD BC:DORS/PBD NAME ELantz NArmstrong ASanchez JDixon SIGNATURE
/RA/
/RA/
/RA/
/RA/
DATE 12/16/25 12/16/25 12/16/25 12/16/25
Enclosure U.S. NUCLEAR REGULATORY COMMISSION Inspection Report Docket Numbers:
05000528, 05000529 and 05000530 License Numbers:
NPF-41, NPF-51 and NPF-74 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
2
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: 71111.15.
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
3 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
4 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
5 (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
6 (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 03.02.
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 (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.
8 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) (2 Samples)
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.
9 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) (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)
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) (1 Sample)
The inspectors evaluated the following licensee event reports (LERs):
10 (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.
11 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
12 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.
13 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.
14 DOCUMENTS REVIEWED Inspection Procedure Type Designation Description or Title Revision or Date 71111.01 Procedures 01DP-0XX01 Control and Monitoring of Potential Tornado Borne Missiles 6
71111.01 Procedures 40AO-9ZZ21 Acts of Nature 41 71111.01 Procedures 40DP-9ZZ17 Control of Doors, Hatches and Floor Plugs 70 71111.04 Corrective Action Documents 16-04430, 17-15953, 25-00048, 24-01709, 25-09056, 25-09057 71111.04 Drawings 01-M-SIP-001 P & I Diagram Safety Injection & Shutdown Cooling System 64 71111.04 Drawings 02-M-AFP-001 P & I Diagram Auxiliary-Feedwater System 36 71111.04 Drawings 02-M-SGP-001 P & I Diagram Main Steam System 84 71111.04 Drawings 02-M-SIP-001 P & I Diagram Safety Injection & Shutdown Cooling System 58 71111.04 Drawings 03-P-SIF-203 Auxiliary BLDG Isometric Safety Injection System HPSI Pump DISCH Train A & RWT 6
71111.04 Miscellaneous 182-9321469-002 Risk-Informed Application Document - Palo Verde Generating Station 10CFR50.69 System Categorization Document for Safety Injection 2
71111.04 Procedures 40ST-9SI14 Train B LPSI and CS System Alignment Verification 3
71111.04 Procedures 73ST-9AF02 Auxiliary Feedwater A - Inservice Test 64 71111.04 Work Orders 5625370, 5630668, 5610143, 5749401, 5625370, 5630668 71111.05 Corrective Action Documents 18-09532, FSCCR 5740572, 25-08940, 25-09001 71111.05 Drawings 03-E-FPF-005 Control Wiring Diagram Fire Protection System 9
71111.05 Drawings 13-A-ZJD-0501 Control Building and Corridor Building Floor Plan at Elevation 74, 100, 120 29 71111.05 Drawings 13-M-FPP-006 Auxiliary Building Channel B Cable Trays 100 Level East Half 6
71111.05 Drawings 13-M999-00004 Halon Fire Suppression System for Remote Shutdown Room 9
71111.05 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.
3 71111.05 Miscellaneous Pre-Fire Strategies Manual 32 71111.05 Procedures 38FT-9QK16 Fire Detection/Protection System Supervised Circuits/Functional Test - Halon Panels 10
15 Inspection Procedure Type Designation Description or Title Revision or Date 71111.05 Procedures 40DP-9ZZ17 Control of Doors, Hatches and Floor Plugs 69 71111.05 Work Orders 5748465, 5749206 71111.11Q Corrective Action Documents 25-09270 71111.11Q Miscellaneous SES-0-04-P-09 Palo Verde Nuclear Generating Station Licensed Operator Continuing Training Exam Scenario 71111.12 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 71111.12 Miscellaneous 71111.12 Miscellaneous 5069-CH-01 10 CFR 50.69 System Categorization Chemical and Volume Control System (CH) 0 71111.12 Miscellaneous 5069-CH-01 10 CFR 50.69 System Categorization Chemical and Volume Control System (CH) 1 71111.12 Miscellaneous MR-A1-EVAL-2025-0015 MR 2.0 - MR (a)(1) Issue Worksheet 0
71111.12 Miscellaneous PMB-CH, MR 2.0-Performance Monitoring Bases Document Worksheet: CH 0
71111.12 Procedures 01DP-0RS07 10 CFR 50.69 Program 3
71111.12 Procedures 01DP-0RS08 10 CFR 50.69 Active Component Categorization From Qualitative Assessment and Defense-In-Depth 2
71111.12 Procedures 31MT-9DG05 Installation and Removal of DG A Temporary Piping Supports 6
71111.12 Procedures 32FT-9QD06 Annual Fire Protection Test for QDN-N06 15 71111.12 Procedures 32MT-9PE01 Cleaning, Inspection, and Testing of the Class 1E Diesel Generator 52 71111.12 Procedures 40AO-9ZZ19 Control Room Fire 42 71111.12 Procedures 40OP-9DF01 Diesel Fuel Oil Storage and Transfer (DF) 45 71111.12 Procedures 70DP-0MR02 Maintenance Rule Monitoring Process 1
71111.12 Work Orders 5733844, 5743998, 5635705, 5635582, 5635694, 5635808, 5635581, 5635635, 5631470 71111.13 Corrective Action Documents 25-08289, 25-08440, 24-12325, 25-10157, 25-08294, 25-01094, 25-08699 71111.13 Drawings 01-J-HJE-051 Instrument LOOP Wiring Diagram Control Building HVAC 6
71111.13 Miscellaneous Integrated Risk Assessment for SURV# 5631303
16 Inspection Procedure Type Designation Description or Title Revision or Date 71111.13 Miscellaneous FME Risk Evaluation MEDDET-DB-ID 11341140 71111.13 Miscellaneous Site Integrated Risk Assessment Work Task 5744929-0 71111.13 Miscellaneous Formal Troubleshooting Game Plan-SBOG Overspeed Troubleshooter Related to CR 25-08440 and WO 57444939-1 71111.13 Miscellaneous PV-E2316 Risk Management and Readiness Plan 3
71111.13 Miscellaneous RICT-US-2025-01 Risk Informed Completion Time Summary 0
71111.13 Procedures Work Instruction for CM# 5744104 - Task #0 71111.13 Procedures 01DP-9ZZ01 Systematic Troubleshooting 12 71111.13 Procedures 02DP-0RS01 Online Integrated Risk 12 71111.13 Procedures 14MT-9BD21 FLEX 2 MW Diesel Generator Inspections and Tests 5
71111.13 Procedures 32MT-9ZZ74 Molded Case Circuit Breaker Test 54 71111.13 Procedures 36ST-9SA02 ESFAS Train B Subgroup Relay Functional Test 49 71111.13 Procedures 37MT-9ZZ01 Vibration Survey 16 71111.13 Procedures 40MG-9ZZ03-003 TSG-3: Site Capabilities 0
71111.13 Procedures 40MG-9ZZ07-001 FLEX Support Guidelines MODE 1, 2, 3, or 4 2
71111.13 Procedures 40MG-9ZZ07-002 FLEX Support Guidelines MODE 5, 6, or Defueled 3
71111.13 Procedures 40ST-9DG01 Diesel Generator Test 52 71111.13 Procedures 70DP-0RA05 Assessment and Management of Risk When Performing Maintenance in Modes 1 and 2 27 71111.13 Procedures M008-00032 Pump Cross Section Bottom Half 7
71111.13 Procedures M008-00041 Assembly of Shaft and Impeller 1076/PI-49 DWG 80257, 9
71111.13 Procedures M008-00049 Assembly of Pump-Top-Half 4
71111.13 Work Orders 5556503, 5585720, 5554860, 5744939, 5756974, 5744104, 5631303, 5746709 71111.15 Calculations 13-MC-SG-0501 Main Steam Line Inside Containment 25 71111.15 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 71111.15 Drawings 02-M-CPP-001 P & I Diagram Containment Purge System 23 71111.15 Miscellaneous PVNGS Design Basis Manual - Containment Purge System 8
71111.15 Miscellaneous EDC# 2005-00359
17 Inspection Procedure Type Designation Description or Title Revision or Date 71111.15 Miscellaneous VTD-C628-00051 Cooper Energy Instruction Manual for KSV Turbocharged Diesel Generating Unit for Nuclear Power Plant Emergency Stand-By Service 21 71111.15 Procedures 01DP-0AP09 Procedure and Work Instruction Use and Adherence 25 71111.15 Procedures 40DP-9OP26 Operations Operability Determination Process 48 71111.15 Procedures 40OP-9EW01 Essential Cooling Water System (EW) Train A 33 71111.15 Procedures 40OP-9EW01 Essential Cooling Water System (EW) Train A 34 71111.15 Procedures 40OP-9EW01 Essential Cooling Water System (EW) Train A 35 71111.15 Procedures 40OP-9SG01 Main Steam 82 71111.15 Procedures 40ST-9DG01 Diesel Generator A Test 52 71111.15 Procedures 73DP-9ZZ14 Surveillance Testing 34 71111.15 Procedures 73ST-9XI15 CP (Power Access Purge) Valves - Inservice Test 12 71111.15 Procedures 74RM-9EF43 Actions for Non-Functional Radiation Monitors: Preplanned Alternat Sampling Program 20 71111.15 Procedures 74RM-9EF80 RMS/Effluent Action Documentation 7
71111.15 Work Orders 5710188, 5570282, 5614092, 5746709 71111.24 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 71111.24 Drawings 01-E-SBB-00005 E/D Plant Protection System Cabling Block Diagram 1
71111.24 Drawings 03-M-SIP-0001 P&ID Diagram Safety Injection & Shutdown Cooling System 42 71111.24 Drawings N001-1303-00078 Plant Protection System Simplified Functional Diagram VCE7914 4
71111.24 Drawings N001-1303-00805 PPS, Initiation Reset Panel Schematic VCE-31245 3
71111.24 Procedures 36ST-9SB02 PPS Bistable Trip Units Functional Test 52 71111.24 Procedures 40DP-9OP08 Diesel Generator Test Record 55 71111.24 Procedures 40ST-9DG01 Diesel Generator A Test 52 71111.24 Procedures 40ST-9ZZ25 Remote Shutdown Disconnect Switch and Control Circuit Operability - All Modes 15 71111.24 Procedures 73ST-9DG08 Class 1E Diesel Generator Load Rejection, 24 Hour Rated Load and Hot Start Test Train B 16 71111.24 Procedures 73ST-9SI10 HPSI Pumps Miniflow - Inservice Test 56 71111.24 Procedures 73ST-9SI11 Low Pressure Safety Injection Pumps Miniflow - Inservice 43
18 Inspection Procedure Type Designation Description or Title Revision or Date Test 71111.24 Work Orders 5553779, 5613929, 5614096, 5625443, 5625514, 5754304, 5631303 71114.06 Miscellaneous MESSAGE: 1.1 OPS ADV - SEISMIC EVENT, ATWS, HPSC LEAK, SURGE TANK OVERFLOW, 148/149 LEVELS 2503 ERO Drill 0
71114.06 Miscellaneous 2503 Drill Objectives Work Sheet 1
71114.06 Miscellaneous 2503 Drill General Information 0
71114.06 Procedures 40AO-9ZZ21 Acts of Nature 41 71114.06 Procedures 40EP-9EO01 Standard Post Trip Actions 24 71114.06 Procedures EP-0900-026 ERO Positions - Operations Manager (TSC) 03 71114.06 Procedures EP-0900-09 ERO Positions - Emergency Coordinator (TSC) 05 71124.05 Calibration Records AMS-4 S/N 112930 Certificate of Calibration 10/01/2024 71124.05 Calibration Records DRM 2 S/N 12611031 DRM 1/2 Calibration Data Sheet 03/11/2025 71124.05 Calibration Records H809V-1 S/N 2888 Air Sampler Calibration Data Sheet 02/13/2025 71124.05 Calibration Records Model 30 S/N 25025219 Neutron Detector Calibration Data Sheet 04/19/2025 71124.05 Calibration Records Model 89, SN 8920 Shepherd Model 89 Verification Sheet 04/17/2025 71124.05 Calibration Records SAM-12, S/N 6700 Small Article Monitor Calibration Data Sheet 09/25/2025 71124.05 Calibration Records Unit 2, Detector 2
- CCART MCA HpGE Geometry Calibration - Charcoal Cartridge on shelf 1 07/21/2023 71124.05 Calibration Records Unit 2, Detector 2
- PFIL MCA HpGE Geometry Calibration - Particulate Filter on shelf 1
07/21/2023 71124.05 Calibration Records W/O 5496234 Radiation Monitor Calibration for Baseline Process Monitors
- B train (1JSQBRU0030) 02/13/2025 71124.05 Calibration Records W/O 5509856 Radiation Monitor Calibration for RU-144 (1JSQNRE0144) 05/10/2024 71124.05 Calibration Records W/O 5518707 Radiation Monitor Calibration for Baseline Area Monitors - B train (2JSQBRU0038) 06/11/2024
19 Inspection Procedure Type Designation Description or Title Revision or Date 71124.05 Calibration Records W/O 5549247 Radiation Monitor Calibration for RU-143 (3JSQNRE0143) 11/04/2024 71124.05 Corrective Action Documents 15-08740, 21-01090, 21-10318, 22-13251, 23-06829, 23-12468, 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, 24-12760, 24-13064, 25-00119, 25-03847, 25-06279, 25-08795, 25-08911, 25-08981 71124.05 Corrective Action Documents Resulting from Inspection 25-13728 71124.05 Procedures 74ST-9SQ12 Effluent Flowpath Process Flow Calibration 15 71124.05 Procedures 74ST-9SQ35 Train B Radiation Monitoring Calibration Test for Containment New Scope Area Monitors 2
71124.05 Procedures 75RP-9EQ45 Calibration of the Thermo Eberline Model FH40G-L 4
71124.05 Procedures 75RP-9EQ66 Calibration of the Thermo Scientific Model RO-20 Ion Chamber Survey Meter 2
71124.05 Procedures ODCM Offsite Dose Calculation Manual, Palo Verde Nuclear Generating Station, Units 1,2, and 3 33 71124.05 Self-Assessments 2025-005 Nuclear Assurance Department Audi Report - Radiation Safety 08/21/2025 71124.06 Corrective Action Documents 22-05735, 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, 22-12791, 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 71124.06 Corrective Action Documents Resulting from Inspection 25-10387
20 Inspection Procedure Type Designation Description or Title Revision or Date 71124.06 Drawings 01-M-HRP-001 P&I Diagram HVAC Radwaste Building 18 71124.06 Drawings 01-P-ZRC-603 Radwaste Building - Level 3 HVAC Plan Between El. 140'-
0" and Roof 1
71124.06 Drawings 03-P-ZRC-604 Radwaste Building - Level 4 HVAC Plan at Roof 0
71124.06 Miscellaneous Results of Radiochemistry Cross Check Program: Arizona Public Service Palo Verde 4th Quarter 2022 04/20/2023 71124.06 Miscellaneous Results of Radiochemistry Cross Check Program: Arizona Public Service Palo Verde 4th Quarter 2023 03/19/2024 71124.06 Miscellaneous Results of Radiochemistry Cross Check Program: Arizona Public Service Palo Verde 4th Quarter 2024 02/25/2025 71124.06 Miscellaneous PVNGS Radioactive Effluent Release Permit Summary Report: Units 1, 2, and 3 - Year 2022 (01/01/2022 -
12/31/2022) 2022 71124.06 Miscellaneous PVNGS Radioactive Effluent Release Permit Summary Report: Units 1, 2, and 3 - Year 2023 (01/01/2023 -
12/31/2023) 2023 71124.06 Miscellaneous PVNGS Radioactive Effluent Release Permit Summary Report: Units 1, 2, and 3 - Year 2024 (01/01/2024 -
12/31/2024) 2024 71124.06 Miscellaneous PVNGS Radioactive Effluent Release Permit Summary Report: Units 1, 2, and 3 - Year 2025 (01/01/2025 -
9/15/2025) 2025 71124.06 Miscellaneous Offsite Dose Calculation Manual, Palo Verde Nuclear Generating Station, Units 1, 2, and 3 33 71124.06 Miscellaneous Permit 2025 125 Unit 1, auxiliary feed pump 'A' steam release (AFA-P01) 09/23/2025 71124.06 Miscellaneous Permit 2025 110 Unit 3, filter changeout for fuel building exhaust radiation monitoring system (RU-145) 09/23/2025 71124.06 Miscellaneous Permit 2025 111 Unit 3, plant vent exhaust grab sample (RU-143) 09/23/2025 71124.06 Miscellaneous RCTSAI 1566 2024 Palo Verde Nuclear Generating Station Units 1, 2, and 3 Annual Radioactive Effluent Release Report 04/17/2025 71124.06 Miscellaneous RCTSAI 1566 2023 Palo Verde Nuclear Generating Station Units 1, 2, and 3 Annual Radioactive Effluent Release Report 04/17/2024
21 Inspection Procedure Type Designation Description or Title Revision or Date 71124.06 Miscellaneous RCTSAI 1566 2022 Palo Verde Nuclear Generating Station Units 1, 2, and 3 Annual Radioactive Effluent Release Report 04/24/2023 71124.06 Miscellaneous RCTSAI 1566 Updated 2023 Palo Verde Nuclear Generating Station Units 1, 2, and 3 Annual Radioactive Effluent Release Report 11/05/2024 71124.06 Miscellaneous RCTSAI 1643 2023 Palo Verde Nuclear Generating Station Units 1, 2, and 3 Annual Radiological Environmental Operating Report 05/10/2024 71124.06 Miscellaneous RCTSAI 1643 2024 Palo Verde Nuclear Generating Station Units 1, 2, and 3 Annual Radiological Environmental Operating Report 05/09/2025 71124.06 Miscellaneous Sample G2 0845 Unit 2, grab sampling for primary to secondary leak rate (RU-141B) 09/24/2025 71124.06 Miscellaneous Sample L2 0846 Unit 2, liquid sampling for primary to secondary leak rate with condensate demineralizer influent (CDI) 09/24/2025 71124.06 Procedures 40OP-9GR01 Operation of Gaseous Radwaste System 51 71124.06 Procedures 74RM-9EF20 Gaseous Radioactive Release Permits and Offsite Dose Assessment 21 71124.06 Procedures 74RM-9EF40 Radiation Monitoring System Operations 14 71124.06 Procedures 74RM-9EF41 Radiation Monitoring System Alarm Response 24 71124.06 Procedures 74RM-9EF42 Radiation Monitor Alarm Setpoint Determinations 35 71124.06 Procedures 74RM-9EF60 RMS Sample Collection 35 71124.06 Procedures 74RM-9EF63 RU-143/RU-144 Sample Operations 4
71124.06 Procedures 74RM-9EF65 RU-145/146 Sample Operations 3
71124.06 Procedures 74ST-9SQ04 Effluent Monitor Monthly Source Checks 9
71124.06 Procedures 74ST-9SQ07 Radiation Monitoring System Shiftly Surveillance Test 10 71124.06 Procedures 75RM-9EF01 Determination of Primary-To-Secondary Leak Rate 4
71124.06 Self-Assessments 2023-004 Nuclear Assurance Department (NAD) Audit Report:
Radiation Safety 09/13/2023 71124.06 Self-Assessments 2025-005 Nuclear Assurance Department (NAD) Audit Report:
Radiation Safety 08/21/2025 71124.06 Self-Assessments 302-03922 Offsite Safety Review Committee (OSRC) Meeting 24-001, Operations, Chemistry, and Radiation Protection Subcommittee Report 09/21/2023 71124.06 Self-Assessments 302-03938 Offsite Safety Review Committee (OSRC) Meeting 24-001, Operations, Chemistry, and Radiation Protection Subcommittee Report 03/29/2024
22 Inspection Procedure Type Designation Description or Title Revision or Date 71124.06 Self-Assessments 302-03945 Offsite Safety Review Committee (OSRC) Meeting 24-002, Operations, Chemistry, and Radiation Protection Subcommittee Report 10/08/2024 71124.06 Work Orders WO 5346472, 5397633, 5456538, 5487711, 5540561 71124.07 Calibration Records 5505031 77ST9RG051 METEOROLOGICAL SYSTEM CALIBRATION
( REDUNDANT SYSTEM) 04/16/2024 71124.07 Calibration Records 5505114 77ST9RG041 METEOROLOGICAL SYSTEM CALIBRATION (PRIMARY SYSTEM) 04/17/2024 71124.07 Calibration Records 5550731 77ST9RG051 METEOROLOGICAL SYSTEM CALIBRATION
( REDUNDANT SYSTEM) 10/28/2024 71124.07 Calibration Records 5550833 77ST9RG041 METEOROLOGICAL SYSTEM CALIBRATION (PRIMARY SYSTEM) 10/29/2024 71124.07 Calibration Records 5594117 77ST9RG051 METEOROLOGICAL SYSTEM CALIBRATION
( REDUNDANT SYSTEM) 06/13/2025 71124.07 Calibration Records 5594490 77ST9RG041 METEOROLOGICAL SYSTEM CALIBRATION (PRIMARY SYSTEM) 06/17/2025 71124.07 Corrective Action Documents 22-05573, 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, 23-12897, 23-13147, 24-00302, 24-00356, 24-00886, 24-02928, 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-
23 Inspection Procedure Type Designation Description or Title Revision or Date 02626, 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 71124.07 Miscellaneous 117-127806-24001 Pace Analytical Report APS-Palo Verde Nuclear Generating Stat Sample Delivery Group: L1835676 03/28/2025 71124.07 Miscellaneous 117-127806-24001 Pace Analytical Report APS-Palo Verde Nuclear Generating Stat Sample Delivery Group: L1851082 05/21/2025 71124.07 Miscellaneous ACT 4657834 REMP Air Sampling Siting Evaluation 11/14/2017 71124.07 Miscellaneous Legacy Item No.036843.01 Annual Radiological Environmental Operating Report 2024 Palo Verde Nuclear Generating Station RCTSAI 1643 05/09/2025 71124.07 Miscellaneous Legacy Item No.036843.01 Annual Radiological Environmental Operating Report 2022 Palo Verde Nuclear Generating Station RCTSAI 1643 03/30/2023 71124.07 Miscellaneous Legacy Item No.036843.01 Annual Radiological Environmental Operating Report 2023 Palo Verde Nuclear Generating Station RCTSAI 1643 05/09/2024 71124.07 Miscellaneous ODCM_Rev 33 OFFSITE DOSE CALCULATION MANUAL PALO VERDE NUCLEAR GENERATING STATION UNITS 1, 2, AND 3 33 71124.07 Miscellaneous PV-3A-0625 Pace Analytical Report APS-Palo Verde Nuclear Generating Stat Sample Delivery Group: L1868941 07/14/2025 71124.07 Miscellaneous Site 4 Trending_Rev3 Particulate Gross Beta in Air and Radioiodine in Air for 2023 3
71124.07 Miscellaneous TRM 072 Technical Requirements Manual 72 71124.07 Miscellaneous UFSAR REV22B February 2025 Updated Final Safety Analysis Report Palo Verde Nuclear Generating Station Units 1, 2, and 3 22B 71124.07 Miscellaneous USNRC Docket 2024 ANNUAL RADIOACTIVE EFFLUENT RELEASE 04/15/2025
24 Inspection Procedure Type Designation Description or Title Revision or Date No. STN 50-528/529/530 REPORT PALO VERDE NUCLEAR GENERATING STATION UNITS 1, 2 AND 3 RCTSAI 1566 71124.07 Miscellaneous USNRC Docket No. STN 50-528/529/530 2023 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT PALO VERDE NUCLEAR GENERATING STATION UNITS 1, 2 AND 3 RCTSAI 1566 04/13/2024 71124.07 Miscellaneous USNRC Docket No. STN 50-528/529/530 2022 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT RCTSAI 1566 04/24/2023 71124.07 Operability Evaluations 218-04808-MLC/MLC Decommissioning Records Review and 10CFR50.75(g)(1)
Applicability Review for 2021 06/16/2022 71124.07 Operability Evaluations 218-04895 2022 Spill/Leak Decommissioning Impact Review 04/28/2023 71124.07 Operability Evaluations 218-05041 2023 Spill/Leak Decommissioning Impact Review 03/19/2025 71124.07 Operability Evaluations 218-05042 2024 Spill/Leak Decommissioning Impact Review 03/25/2025 71124.07 Procedures 218-04808 Decommissioning Records Review and 10CFR50.75(g)(1)
Applicability Review for 2021 07/16/2022 71124.07 Procedures 218-04895 2022 Spill/Leak Decommissioning Impact Review 04/28/2023 71124.07 Procedures 218-04916 Decommissioning Records Review and 10CFR50.75(g)(1)
Applicability Review for 2022 08/17/2023 71124.07 Procedures 218-05041 2023 Spill/Leak Decommissioning Impact Review 03/19/2025 71124.07 Procedures 218-05042 2024 Spill/Leak Decommissioning Impact Review 03/25/2025 71124.07 Procedures 218-05050 Decommissioning Records Review and 10CFR 50.75(g)(1)
Applicability Review 2023 and 2024 04/30/2025
25 Inspection Procedure Type Designation Description or Title Revision or Date 71124.07 Procedures 74-RM-0EN02 Radiological Environmental Air Sampling 22 71124.07 Procedures 74CH-9ZZ69 Operation of the Liquid Scintillation Systems 18 71124.07 Procedures 74RM-0EN03 Radiological Environmental Sampling 38 71124.07 Procedures 74RM-0EN05 Environmental TLD Exchange/Reporting 19 71124.07 Procedures 74RM-0EN07 Land Use Census 15 71124.07 Procedures 74RM-9EN01 Sentinel Well Sampling Instructions 4
71124.07 Procedures 75DP-9AP01 Groundwater Protection Program 4
71124.07 Procedures 77ST-9RG04 Meteorological System Instrumentation Replacement and Verification (Primary System) 4 71124.07 Procedures 77ST-9RG05 Meteorological System Instrumentation Replacement and Verification (Redundant System) 4 71124.07 Self-Assessments Audit 2023-004 Nuclear Assurance Department (NAD) Audit Report 0
71124.07 Self-Assessments Audit 2025-005 Nuclear Assurance Department (NAD) Audit Report 2025-005 Radiation Safety 0
71124.08 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 71124.08 Miscellaneous LLRMSF and SG Mausoleum Quarterly Testing and Inspection 03/05/2024 71124.08 Miscellaneous LLRMSF and SG Mausoleum Quarterly Testing and Inspection 09/25/2024 71124.08 Miscellaneous LLRMSF and SG Mausoleum Quarterly Testing and Inspection 12/03/2024 71124.08 Miscellaneous Radiation Protection Logbook: Low Level Radioactive Material Storage Facility (Monthly): July 2024 and February 2025 71124.08 Miscellaneous LLRMSF and SG Mausoleum Quarterly Testing and Inspection and Annual Maintenance 06/06/2024 71124.08 Miscellaneous ESD 86-35 10 CFR 37 Security Just in Time Training: Category 2 Radioactive Material 03/12/2014 71124.08 Miscellaneous ESD 86-44 Nuclear Security Training Lesson Plan: Protected Area Mobile 08/22/2023 71124.08 Miscellaneous NBA11C000115 Radiation Protection Technician Training Program:
Packaging Radioactive Material 09/14/2021
26 Inspection Procedure Type Designation Description or Title Revision or Date 71124.08 Miscellaneous NBA19C000213 Radiation Protection Technician Training Program: Shipping Radioactive Material 05/14/2021 71124.08 Procedures 20DP-0SK37 Palo Verde 10 CFR Part 37 Security Program Overview 0
71124.08 Procedures 20DP-0SK77 Security Miscellaneous Testing 1
71124.08 Procedures 75RP-9RP15 Control and Storage of Radioactive Material and Radioactive Wastes 32 71124.08 Procedures 75RP-9RP26 Radioactive Source Control 18 71124.08 Procedures 76DP-0RP01 Radioactive Waste Management Program Overview 9
71124.08 Procedures 76DP-0RP03 Radwaste Process Control Program 9
71124.08 Procedures 76RP-0RW03 Waste Stream Sampling and Database Maintenance 3
71124.08 Procedures 76RP-0RW05 Packaging and Classification of Radioactive Waste 6
71124.08 Procedures 76RP-0RW06 Packaging of Radioactive Material 5
71124.08 Procedures 76RP-0RW07 Shipping Radioactive Materials 16 71124.08 Procedures 76RP-0RW08 High Integrity Container Receipt, Handling, Use, and Closure 5
71124.08 Procedures 76RP-0RW14 Radioactive Waste Inventory 6
71124.08 Procedures 76RP-0RW82 Self-Engaging Rapid Dewatering System (SERDS)
Operation 4
71124.08 Radiation Surveys 0-M-20160205-3, 0-M-20170727-4, 0-M-20181126-4, 0-M-20250801-2, 0-M-20250917-3, 1-M-20250302-2, 1-M-20250314-3, 1-M-20250411-19, 1-M-20250702-4, 1-M-20250729-2, 1-M-20250806-2, 1-M-20250909-9, 1-M-20250910-3, 1-M-20250910-5, 2-M-20250320-4, 2-M-20250729-7, 2-M-20250806-1, 2-M-20250807-1, 2-M-20250903-2, 2-M-20250909-2, 2-M-20250909-3, 2-M-20250916-1, 2-M-20250916-2, 2-M-20250917-3, 2-M-20250923-1, 3-M-20250724-2, 3-M-20250724-3, 3-M-20250730-5, 3-M-20250730-8, 3-M-20250825-3, 3-M-20250901-2, 3-M-20250914-1, 3-M-20250917-2, 3-M-20250918-4 71124.08 Radiation Surveys Filtered Radioactive Source Inventory, Leak Test, and 10CFR20 Appendix E Evaluation 07/15/2025 71124.08 Radiation Surveys 0-M-20250827-3 Monthly Survey: Dry Active Waste Processing System Facility - processing area 08/27/2025
27 Inspection Procedure Type Designation Description or Title Revision or Date 71124.08 Radiation Surveys 3-25-00140 Gamma Isotopic Analysis: Soil sample from U3 Yard Non-RCA 09/25/2025 71124.08 Radiation Surveys 3-25-00141 Gamma Isotopic Analysis: Soil sample from U3 Yard Non-RCA 09/25/2025 71124.08 Radiation Surveys 3-25-00142 Gamma Isotopic Analysis: Soil sample from U3 Yard Non-RCA 09/25/2025 71124.08 Radiation Surveys 3-25-00143 Gamma Isotopic Analysis: Soil sample from U3 Yard Non-RCA 09/25/2025 71124.08 Radiation Surveys 3-25-00144 Gamma Isotopic Analysis: Soil sample from U3 Yard Non-RCA 09/25/2025 71124.08 Radiation Surveys 3-25-00145 Gamma Isotopic Analysis: Soil sample from U3 Yard Non-RCA 09/25/2025 71124.08 Radiation Surveys 3-25-00156 Gamma Isotopic Analysis: Soil sample from U3 Yard Non-RCA 09/24/2025 71124.08 Self-Assessments 2025-005 Nuclear Assurance Department Audit Report: Radiation Safety 08/21/2025 71124.08 Self-Assessments 2023-004 Nuclear Assurance Department Audit Report: Radiation Safety 09/08/2023 71124.08 Self-Assessments 2023-004 Nuclear Assurance Department Audit Report: Radiation Safety 09/08/2023 71124.08 Self-Assessments 2025-002 Nuclear Assurance Department Audit Report: Nuclear Security 07/01/2025 71124.08 Self-Assessments 2025-002 Nuclear Assurance Department Audit Report: Nuclear Security 07/01/2025 71124.08 Self-Assessments 2025-005 Nuclear Assurance Department Audit report: Radiation Safety 08/21/2025 71151 Miscellaneous Engage Health Maintenance Rule reports - Unavailability for 1 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
28 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 17 71151 Procedures 70DP-0PI01 Performance Index Data Mitigating Systems Cornerstone 10 71151 Procedures 93DP-0LC09 NRC ROP PI Data Collection, Verification, and Submittal 13 71151 Procedures NEI-99-02 Regulatory Assessment Performance Indicator Guideline 8
71153 Corrective Action Documents 25-04111 71153 Miscellaneous I&C RT 064561 71153 Miscellaneous PCR 25-04111-001 71153 Procedures 01DP-0AP09 Procedure And Work Instruction Use and Adherence 25 71153 Procedures 40AO-9ZZ12 Degraded Electrical Power 84 71153 Procedures 40AO-9ZZ23 Loss of SFP Level or Cooling 35 71153 Procedures 40OP-9SA02 De-energiazation of BOP ESFAS 27 71153 Procedures 40OP-9SA02 De-energiazation of BOP ESFAS 28 71153 Work Orders 5232544, 5596311