ML25209A466
| ML25209A466 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 07/29/2025 |
| From: | John Dixon NRC/RGN-IV/DORS/PBD |
| To: | Heflin A Arizona Public Service Co |
| References | |
| IR 2025002 | |
| Download: ML25209A466 (1) | |
Text
July 29, 2025 Adam Heflin, Executive Vice President and Chief Nuclear Officer Arizona Public Service Company P.O. Box 52034, MS 7602 Phoenix, AZ 85072-2034
SUBJECT:
PALO VERDE NUCLEAR GENERATING STATION - INTEGRATED INSPECTION REPORT 05000528/2025002 AND 05000529/2025002 AND 05000530/2025002
Dear Adam Heflin:
On June 30, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Palo Verde Nuclear Generating Station. On July 8, 2025, the NRC inspectors discussed the results of this inspection with Mike DiLorenzo, Acting Director, Nuclear Regulatory Affairs, and other members of your staff. The results of this inspection are documented in the enclosed report.
No findings or violations of more than minor significance were identified during this inspection.
This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, John L. Dixon, Jr., Chief Reactor Projects Branch D Division of Operating Reactor Safety Docket Nos. 05000528; 05000529; and 05000530 License Nos. NPF-41; NPF-51; and NPF-74
Enclosure:
As stated cc w/ encl: Distribution via LISTSERV Signed by Dixon, John on 07/29/25
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 07/28/25 07/28/25 07/28/25 07/29/25
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:
05000528/2025002; 05000529/2025002; and 05000530/2025002 Enterprise Identifier:
I-2025-002-0000 Licensee:
Arizona Public Service Company Facility:
Palo Verde Nuclear Generating Station Location:
Tonopah, Arzona Inspection Dates:
April 1, 2025, to June 30, 2025 Inspectors:
C. Alldredge, Health Physicist N. Armstrong, Project Engineer L. Carson, Senior Health Physicist N. Cuevas, Resident Inspector J. Hickey, Senior Project Engineer E. Lantz, Senior Resident Inspector A. Sanchez, Senior Project Engineer A. Tran, Resident Inspector Approved By:
John L. Dixon, Jr., Chief Reactor Projects Branch D Division of Operating Reactor Safety
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.
List of Findings and Violations No findings or violations of more than minor significance were identified.
Additional Tracking Items Type Issue Number Title Report Section Status LER 05000530/2024-003-00 LER 2024-003-00 for Palo Verde Nuclear Generating Station, Unit 3, Violation of Technical Specifications 3.9.2 and 3.3.12 71153 Closed
3 PLANT STATUS Unit 1 entered the inspection period shut down for refueling outage 1R25. On May 9, 2025, the reactor was made critical following completion of the refueling outage and returned to full power on May 14, 2025, where it remained for the remainder of the inspection period.
Unit 2 operated at or near full power for the duration of the inspection period.
Unit 3 entered the inspection period at full power. On April 25, 2025, the reactor was down powered to approximately 12 percent power to perform repairs to a switchyard breaker due to a hot spot. On April 27, 2025, the reactor returned to full power following repairs, where it remained for the remainder of the inspection period.
INSPECTION SCOPES Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors performed activities described in IMC 2515, Appendix D, Plant Status, observed risk significant activities, and completed on-site portions of IPs. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
REACTOR SAFETY 71111.04 - Equipment Alignment Partial Walkdown Sample (IP Section 03.01) (3 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
(1)
Unit 1, shutdown cooling train A during the 1R25 outage, on April 2, 2025 (2)
Unit 1, spent fuel pool cooling trains A and B during the 1R25 outage, on April 7, 2025 (3)
Unit 2, Cardox fire protection system following maintenance, on May 8, 2025 71111.05 - Fire Protection Fire Area Walkdown and Inspection Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:
(1)
Unit 1, 100-foot elevation auxiliary building rooms, fire zones 42C and 42D, essential cooling water heat exchangers A and B rooms, fire zone 43, on April 30, 2025
4 (2)
Unit 3, 100-foot elevation auxiliary building rooms, fire zones 42C and 42D, essential cooling water heat exchangers A and B rooms, fire zone 43, on April 30, 2025 (3)
Unit 1, containment during 1R25 outage, fire zones 63A, 63B, 66A, 66B, 67A, and 67B, on May 2, 2025 (4)
Unit 2, main control room, fire zone 17, on June 18, 2025 71111.06 - Flood Protection Measures Flooding Sample (IP Section 03.01) (1 Sample)
(1)
The inspectors evaluated internal flooding mitigation protections in the Units 1, 2, and 3 essential pipe density tunnels, on May 29, 2025.
71111.07A - Heat Exchanger/Sink Performance Annual Review (IP Section 03.01) (1 Sample)
The inspectors evaluated readiness and performance of:
(1)
Unit 1 essential cooling water train B heat exchanger, on April 6, 2025 71111.08P - Inservice Inspection Activities (PWR)
The inspectors verified that the reactor coolant system boundary, reactor vessel internals, risk-significant piping system boundaries, and containment boundary are appropriately monitored for degradation and that repairs and replacements were appropriately fabricated, examined and accepted by reviewing the following activities in Unit 1 during refueling outage 1R25 from April 7 to 18, 2025, on site and completion of the inspection on May 30, 2025, via in office review.
PWR Inservice Inspection Activities Sample - Nondestructive Examination and Welding Activities (IP Section 03.01) (1 Sample)
The inspectors verified that the following nondestructive examination and welding activities were performed appropriately:
(1)
Ultrasonic Examination auxiliary and downcomer feedwater steam generator 2, weld 59-19, pipe to elbow auxiliary and downcomer feedwater steam generator 2, weld 59-21R, pipe to elbow charging line, weld 37-33, reducer to pipe charging line, weld 37-34, pipe to elbow pressurizer spray 1B, weld 28-41, pipe to elbow pressurizer spray 1B, weld 28-42, pipe to elbow pressurizer spray 1B, weld 28-45, safe-end to pipe safety injection B, weld 75-27, pipe to elbow Dye Penetrant Examination safety injection, part SI-119-H-014-W
5 charging system, part CH-005-H-019-W Visual VT-1 Examination pressurizer manway studs and nuts, component 1MRCEX02 Welding Activities automatic gas tungsten arc welding o
pressurizer instrument half-nozzle repair PWR Inservice Inspection Activities Sample - Vessel Upper Head Penetration Inspection Activities (IP Section 03.02)
The inspectors verified that no upper reactor vessel head penetration inspections were required this outage.
PWR Inservice Inspection Activities Sample - Boric Acid Corrosion Control Inspection Activities (IP Section 03.03) (1 Sample)
The inspectors verified the licensee is managing the boric acid corrosion control program through a review of the following evaluations:
(1)
CR-25-2585 1PSIAVA07 CR 25-2586 1JSICUV0653 CR 25-2663 1PRCEV242 CR 25-2665 1JSIAPSV0469 CR-25-2666 1JSIBUV0616 CR-25-2668 1JSIBUV0614 CR 25-2675 1JSIBUV0638 PWR Inservice Inspection Activities Sample - Steam Generator Tube Inspection Activities (Section 03.04) (1 Sample)
The inspectors verified that the licensee is monitoring the steam generator tube integrity appropriately through a review of the following examinations:
(1) one-hundred percent of the tubes in steam generator SG11 and SG12 were inspected via eddy current methods secondary side steam generators SG11 and SG12 were visually inspected high pressure feedwater heaters 5A and 6A were visually inspected and tubes inspected via eddy current methods 71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01)
(2 Samples)
The inspectors observed and evaluated licensed operator performance in the control room during the following activities:
6 (1)
Unit 3, down power to repair a switchyard motor operated disconnect, on April 28, 2025 (2)
Unit 1, startup activities following completion of refueling outage 1R25, on May 9, 2025 71111.12 - Maintenance Effectiveness Maintenance Effectiveness (IP Section 03.01) (1 Sample)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
(1)
Unit 1, class 1E 480 Vdc load center train B, on May 23, 2025 71111.13 - Maintenance Risk Assessments and Emergent Work Control Risk Assessment and Management Sample (IP Section 03.01) (1 Sample)
The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:
(1)
Unit 3, planned maintenance on emergency diesel generator train B, on June 10, 2025 71111.15 - Operability Determinations and Functionality Assessments Operability Determination or Functionality Assessment (IP Section 03.01) (4 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
(1)
Unit 1, class 1E 125 Vdc battery PK-C functionality assessment due to discharge test results showing lower capacity than expected, on April 3, 2025 (2)
Unit 1, emergency diesel generator train A operability determination due to automatic voltage regulator swap following failure to control voltage, on April 22, 2025 (3)
Unit 1, steam generator atmospheric dump valves, SGB-HV-178 and SGB-HV-185, operability determination due to excessive leakage during inservice testing, on April 7, 2025 (4)
Unit 1 containment spray train A operability determination due to voids discovered during surveillance testing, on May 21, 2025 71111.18 - Plant Modifications Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (1 Sample)
The inspectors evaluated the following temporary or permanent modifications:
7 (1)
Unit 1, permanent modification to upgrade the balance of plant engineered safety features actuation system channel B to address component obsolescence and equipment failure issues, on May 13, 2025 71111.20 - Refueling and Other Outage Activities Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
(1)
The inspectors evaluated the Unit 1 refueling outage 1R25 activities from March 28 to May 14, 2025.
71111.24 - Testing and Maintenance of Equipment Important to Risk The inspectors evaluated the following testing and maintenance activities to verify system operability and/or functionality:
Post-Maintenance Testing (PMT) (IP Section 03.01) (9 Samples)
(1)
Unit 2, coolant charging pump E seal lube pump replacement, on April 4, 2025 (2)
Unit 1, refueling water tank level transmitter channel A post-maintenance testing following transmitter replacement, on April 30, 2025 (3)
Unit 1, low-pressure safety injection pump B post-maintenance testing following mechanical seal replacement, on April 30, 2025 (4)
Unit 1, shutdown cooling suction from containment recirculation sump valve SIB-UV-675 post-maintenance test following seat ring replacement, on April 30, 2025 (5)
Unit 1, essential chiller B post-maintenance testing following eddy current testing and repairs, on May 6, 2025 (6)
Unit 1, safety injection tank B to reactor coolant loop check valve SIE-V-247 post-maintenance test following repairs, on May 15, 2025 (7)
Unit 3, emergency diesel generator train A post-maintenance testing following maintenance outage, on May 16, 2025 (8)
Unit 1, engineered safety features train B post-maintenance testing following balance of plant engineered safety features actuation system upgrade, on May 20, 2025 (9)
Unit 1, reactor coolant pump 2A post-maintenance testing following mechanical seal replacement, on June 17, 2025 Surveillance Testing (IP Section 03.01) (2 Samples)
(1)
Unit 1, remote input system voltage testing, on April 30, 2025 (2)
Unit 2, turbine-driven auxiliary feedwater pump testing, on June 5, 2025 Inservice Testing (IST) (IP Section 03.01) (1 Sample)
(1)
Unit 1, low-pressure safety injection pump B inservice testing, on May 14, 2025 Containment Isolation Valve (CIV) Testing (IP Section 03.01) (1 Sample)
(1)
Unit 1, pressurizer steam space sample header containment isolation valve SSA-UV-205 testing, on May 27, 2025
8 Diverse and Flexible Coping Strategies (FLEX) Testing (IP Section 03.02) (1 Sample)
(1)
Units 1, 2, and 3, FLEX spent fuel pool make up pumps, on May 6, 2025 RADIATION SAFETY 71124.01 - Radiological Hazard Assessment and Exposure Controls Radiological Hazard Assessment (IP Section 03.01) (1 Sample)
(1)
The inspectors evaluated how the licensee identifies the magnitude and extent of radiation levels and the concentrations and quantities of radioactive materials and how the licensee assesses radiological hazards.
Instructions to Workers (IP Section 03.02) (1 Sample)
(1)
The inspectors evaluated how the licensee instructs workers on plant-related radiological hazards and the radiation protection requirements intended to protect workers from those hazards.
Contamination and Radioactive Material Control (IP Section 03.03) (3 Samples)
The inspectors observed/evaluated the following licensee processes for monitoring and controlling contamination and radioactive material:
(1) surveys of potentially contaminated packages/equipment from the radiologically controlled area and workers exiting potentially contaminated areas (2) labeling for several nonexempt radioactive sources listed in the licensee's source inventory in Unit 2 and Unit 3, including the following specific Unit 1 RP sources13-011, 24-001, and RP-179 (3) physical and programmatic controls for highly activated and contaminated non-fuel materials stored within the spent fuel pool including radwaste filter canisters Radiological Hazards Control and Work Coverage (IP Section 03.04) (4 Samples)
The inspectors evaluated the licensee's control of radiological hazards for the following radiological work:
(1) medium and high risk radiological work and job coverage for reactor inboard loop discharge check valve disassembly, inspection, lapping in-body seats for low-pressure safety injection and repair of safety injection valves SIE-V-245 and 247 (RWPs 1-3125 and 3321 tasks 30 and 50)
(2) medium and high risk radiological work and job coverage for primary side steam generator (SG-1) maintenance and eddy current (ET) testing activities for Unit 1 reactor (RWP 1-3306-R25, all tasks)
(3) high risk radiological work and job coverage for pressurizer nozzle work (RWP 1-3425-R25)
(4)
Unit 1 in-core instrumentation area chase inspections (RWP 1-3325-R25)
9 High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (4 Samples)
The inspectors evaluated licensee controls of the following high radiation areas (HRAs) and very high radiation areas (VHRAs):
(1)
(VHRA) Unit 1 under vessel access on the 80-foot containment elevation (2)
(HRA) Unit 1 regenerative heat exchanger room on the 111-foot containment elevation (3)
(HRA) Unit 1 reactor vessel head stand on the 140-foot containment elevation (4)
(LHRAs) Units 1, 2, & 3 high level storage area on the 120-foot elevation of the radwaste building Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 03.06) (1 Sample)
(1)
The inspectors evaluated radiation worker and radiation protection technician performance as it pertains to radiation protection requirements.
71124.04 - Occupational Dose Assessment Source Term Characterization (IP Section 03.01) (1 Sample)
(1)
The inspectors evaluated licensee performance as it pertains to radioactive source term characterization.
External Dosimetry (IP Section 03.02) (1 Sample)
(1)
The inspectors evaluated how the licensee processes, stores, and uses external dosimetry.
Internal Dosimetry (IP Section 03.03) (3 Samples)
The inspectors evaluated the following internal dose assessments:
(1)
CR-1-23-11265, Dose Assessment, dated July 23, 2024 (2)
PCE 2-24-0005, Dose Assessment, dated November 26, 2024 (3)
CR-1-23-11087, Dose Assessment, dated April 28, 2024 Special Dosimetric Situations (IP Section 03.04) (2 Samples)
The inspectors evaluated the following special dosimetric situations:
(1) use of multi-pack dosimetry and dose assignment on activities related to work orders 5405544, 5419142, and 5456945 (2) monitoring of three declared pregnant workers and their associated NRC Form 5s
10 OTHER ACTIVITIES - BASELINE 71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04) (3 Samples)
(1)
Unit 1 (April 1, 2024, through March 31, 2025)
(2)
Unit 2 (April 1, 2024, through March 31, 2025)
(3)
Unit 3 (April 1, 2024, through March 31, 2025)
OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)
(1)
Units 1, 2, and 3 (October 1, 2024, through March 31, 2025)
PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample (IP Section 02.16) (1 Sample)
(1)
Units 1, 2, and 3 (October 1, 2024, through March 31, 2025) 71152A - Annual Follow-up Problem Identification and Resolution Annual Follow-up of Selected Issues (Section 03.03) (1 Sample)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issue:
(1)
Accidental discharge during a dry fire exercise inside of the security training building on February 11, 2025. This included the site level one evaluation 25-01522-002 completed on March 27, 2025.
71153 - Follow Up of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02) (1 Sample)
The inspectors evaluated the following licensee event reports (LERs):
(1)
LER 05000530/2024-003-00, PVNGS Unit 3 Violation of Technical Specifications 3.9.2 and 3.3.12, Agencywide Documents Access and Management System (ADAMS) Accession No. ML24347A138. The inspection conclusions associated with this LER are documented in inspection report 050000530/2024003. This LER is closed.
Personnel Performance (IP Section 03.03) (1 Sample)
(1)
The inspectors evaluated the loss of Unit 1 emergency diesel generator A resulting in a declaration of unusual event CU2.1, Loss of all but one AC Power source to
11 emergency buses for 15 minutes or longer and the licensee response on April 10, 2025.
INSPECTION RESULTS No findings were identified.
EXIT MEETINGS AND DEBRIEFS The inspectors verified no proprietary information was retained or documented in this report.
On April 14, 2025, the inspectors presented the occupational radiation safety inspection results to Jennifer Spina, Vice President, Nuclear Regulatory & Oversight, and other members of the licensee staff.
On June 27, 2025, the inspectors presented the Unit 1 inservice inspection results to Jennifer Spina, Vice President, Nuclear Regulatory & Oversight, and other members of the licensee staff.
On July 8, 2025, the inspectors presented the integrated inspection results to Mike DiLorenzo, Acting Director, Nuclear Regulatory Affairs, and other members of the licensee staff.
12 DOCUMENTS REVIEWED Inspection Procedure Type Designation Description or Title Revision or Date 71111.04 Corrective Action Documents 25-02122 71111.04 Drawings 01-M-NCP-002 Piping & Instrumentation Diagram Nuclear Cooling Water System 15 71111.04 Drawings 01-M-PCP-001 Piping & Instrumentation Diagram Fuel Pool Cooling &
Cleanup System 38 71111.04 Drawings 03-M-CHP-002 Piping & Instrumentation Diagram Chemical and Volume Control System 40 71111.04 Drawings 03-M-FPP-004 P & I diagram fire protection system (CO2 system) 10 71111.04 Drawings 03-M-SIP-001 Piping & Instrumentation Diagram Safety Injection &
Shutdown Cooling System 59 71111.04 Drawings 03-M-SIP-002 Piping & Instrumentation Diagram Safety Injection &
Shutdown Cooling System 59 71111.04 Engineering Evaluations 4758718 Engineering Evaluation 1
71111.04 Procedures 14OP-9FP02 CO2 fire protection (CARDOX) 10 71111.04 Procedures 40AO-9ZZ23 Loss of [spent fuel pool] SFP Level or Cooling 35 71111.04 Procedures 40DP-9ZZ30 Reduced Inventory Operations 4
71111.04 Procedures 40MG-9ZZ07-002 FLEX Support Guidelines Mode 5, 6, or Defueled 2
71111.04 Procedures 40OP-9PC01 Fuel Pool Cooling 16 71111.04 Procedures 40OP-9SI01 Shutdown Cooling Initiation 60 71111.04 Procedures 40OP-9ZZ16 Reactor Coolant System Drain Operations 87 71111.04 Procedures 40OP-9ZZ23 Outage General Operating Procedure (GOP) 92 71111.05 Calculations 13-MC-FP-0803 Combustible Loads - Control Building 17 71111.05 Corrective Action Documents 25-05151, 19-06334, 23-10795, 23-05322, 25-06454, FSCCR 5729570, CRDR 2960716, CRDR 2960717 71111.05 Drawings M650-00410 Auxiliary Building 100 Northeast Corridor 1
71111.05 Miscellaneous Palo Verde Generating Station Pre-Fire Strategies Manual 32 71111.05 Miscellaneous Pre-Fire Strategies Manual 32 71111.05 Procedures 14DP-0FP02-02 Fire Point Inactivation and Activation Administrative Guidance 1
71111.06 Calculations 13-MC-ZA-0809 As Built Auxiliary Building Flooding Calculation 8
13 Inspection Procedure Type Designation Description or Title Revision or Date 71111.06 Calculations 13-MC-ZY-0599 Essential Pipe Density Tunnel Flooding 0
71111.06 Calculations 13-MC-ZY-0599 Essential Pipe Density Tunnel Flooding 1
71111.06 Corrective Action Documents 23-07148 71111.07A Corrective Action Documents 25-04112, 25-03985 71111.07A Miscellaneous 25-0360 Eddy Current Examination Report 71111.07A Miscellaneous AN449-A00029 Belzona 1111 Super Metal Product Data and Application Instructions 2
71111.07A Miscellaneous AN449-A00030 Belzona 1321 Super Metal Product Data and Application Instructions 2
71111.07A Miscellaneous VTM-S445-00001 Struthers Wells Corporation Turbine, Nuclear, Fuel Pool and Essential Cooling Water Heat Exchangers 5
71111.07A Procedures 30DP-9MP03 Mechanical System Cleanliness 25 71111.07A Procedures 31MT-9EW02 Tube Plugging of the Essential Cooling Water Heat Exchanger 5
71111.07A Procedures 31MT-9EW02 Tube Plugging of the Essential Cooling Water Heat Exchanger 5
71111.07A Procedures 38DP-0MI01 Control of Painting and Coating Operations 27 71111.07A Procedures 73DP-9ZZ21 Heat Exchanger Visual Inspection 8
71111.07A Procedures 73TI-9ZZ28 Eddy Current Examination of Tubing 11 71111.07A Work Orders 5591895, 5592316, 5574324 71111.08P Corrective Action Documents 25-04561 71111.08P Engineering Changes 23-10254-025 RC-1911 Unit 1 Pressurizer Upper and Lower Head Instrument Nozzle Replacement 04/14/2025 71111.08P Engineering Evaluations 25-03798-002 Lever 3 Evaluation Report 04/20/2025 71111.08P Engineering Evaluations MN725-A02143 Palo Verde Generating Station U1R25 Steam Generator Condition Monitoring Evaluation 05/05/2025 71111.11Q Miscellaneous Standard Maneuver Plan: Unit 3 Cycle 25, 350 EFPD 100%
to 12%
0 71111.11Q Procedures 40OP-9ZZ02 Initial Reactor Startup Following Refuelings 65 71111.11Q Procedures 40OP-9ZZ05 Power Operations 153
14 Inspection Procedure Type Designation Description or Title Revision or Date 71111.12 Miscellaneous VTD-A915-00165 ABB Installation/Maintenance instructions for I-T-E low voltage AC metal-enclosed power switchgear K-Line 2
71111.12 Miscellaneous VTD-A915-00169 ABB Installation & Maintenance instructions for low-voltage power circuit breakers type K-225 thru 2000& K-6000s thru 2000s 3
71111.12 Miscellaneous VTD-A915-00175 ABB Maintenance and Surveillance for low-voltage switchgear equipment K-Line 2
71111.12 Procedures 32MT-9ZZ92 Inspection/Cleaning of 1E and Non-1E 480 Volt Load Centers 36 71111.12 Work Orders 5591598 71111.15 Corrective Action Documents 25-03388, 25-04140, 25-00893, 25-00893-002, 24-00699, 25-00978, 25-00980, 25-02049, 25-02086, 25-05395 71111.15 Drawings 13-M01-01239 Regulator Chassis Schematic 5
71111.15 Engineering Evaluations 25-00893-001 Minor Leaks Identified Per CMWO 5596546 71111.15 Miscellaneous 13-MS-B067 Containment Spray System Evaluation for Minor Amounts of Air Remaining in Piping Following Normal Venting Activities 2
71111.15 Miscellaneous 13-MS-B092 Development of ECCS Discharge Side Piping Arc Lengths Associated with Calculated Max Void Volumes 3
71111.15 Miscellaneous VTD-E940-0003 Engine System Company Installation Operating And Maintenance Manual For Dual Automatic Voltage Regulator System Upgrades 2
71111.15 Procedures 30DP-9MP01 Conduct of Maintenance 85 71111.15 Procedures 30DP-9MP27 Toolpouch and Minor Maintenance Process 2
71111.15 Procedures 40DP-9OP26 Operations Operability Determination Process 48 71111.15 Procedures 40DP-9OP26-01 Operations Operability Determination Process Administrative Guideline 0
71111.15 Procedures 40OP-9DG01 Emergency Diesel Generator A 86 71111.15 Procedures 40ST-9SI13 Train A LPSI and CS System Alignment Verification 37 71111.15 Procedures 73DP-9ZZ14 Surveillance Testing 32 71111.15 Procedures 73ST-9XI20
[Atmospheric dump valves] ADVs - Inservice Test 61 71111.18 Corrective Action Documents 25-01352, 25-04326, 25-04144, 25-04396, 25-04748, 25-04748 71111.18 Miscellaneous 10 CFR 50.59 Screening/Evaluation for EC 2589411 0
15 Inspection Procedure Type Designation Description or Title Revision or Date 71111.18 Miscellaneous EC 2589411 BOP-ESFAS Replacement 0
71111.18 Miscellaneous Specification 13-JM-0104 Balance of Plant Engineered Safety Feature Actuation System 6
71111.18 Procedures 40OP-9SA01 BOP ESFAS Modules Operation 34 71111.18 Work Orders 5600334, 5232544 71111.20 Miscellaneous Specific Maneuvering Plan 500 EFPD 100 To 26.7% For EOC Shutdown Unit 1 Cycle 25 0
71111.20 Miscellaneous Specific Maneuver Plan: EOC Shutdown 90% to 20% Unit 2 Cycle 24 0
71111.20 Miscellaneous Reactor Coolant System Pressure And Temperature Limits Report (PTLR), Technical Requirements Manual Appendix TA 69 71111.20 Miscellaneous TRM APPX TA Reactor Coolant System Pressure and Temperature Limits Report 69 71111.20 Procedures 30DP-9MP11 Field Use Of Rigging 47 71111.20 Procedures 31MT-9RC30 Reactor Vessel Head Removal And Installation, Multiple Pass Multi-Stud Tensioner 63 71111.20 Procedures 31MT-9ZC07 Miscellaneous Containment Building Heavy Loads 45 71111.20 Procedures 40DP-9AP19 Lower Mode Functional Recovery Technical Guideline 17 71111.20 Procedures 40EP-9E01 Standard post trip actions 24 71111.20 Procedures 40EP-9EO11 Lower Mode Functional Recovery 33 71111.20 Procedures 40OP-9RC01 Reactor Coolant Pump Operation 58 71111.20 Procedures 40OP-9SG01 Main steam isolation valves 82 71111.20 Procedures 40OP-9SI01 Shutdown Cooling Initiation 60 71111.20 Procedures 40OP-9ZZ23 Outage general operating procedure (GOP) 92 71111.20 Procedures 40ST-9RC01 Reactor Coolant System (RCS) and Pressurizer Heatup and Cooldown Rates 21 71111.20 Procedures 40ST-9ZZ09 Containment Cleanliness Inspection 28 71111.20 Procedures 72ST-9RX14 Shutdown Margin - Modes 3, 4, and 5 23 71111.24 Calculations 2011-00315 Incorporated Essential Chiller Tubing Minimum Allowable Wall Calculations 00 71111.24 Calculations 73TI-9ZZ28 Eddy Current Examination Of Tubing 11 71111.24 Corrective Action 25-04471, 25-04298, 25-03122, 21-07136, 25-05929
16 Inspection Procedure Type Designation Description or Title Revision or Date Documents 71111.24 Corrective Action Documents Resulting from Inspection 25-06490 71111.24 Drawings 01-M-ECP-0001 Piping & Instrumentation Diagram Essential Chilled Water System 36 71111.24 Drawings N001-0902-00039 Sectional Assembly (LPSI pumps) DMWO 00739596 2
71111.24 Drawings N001-0902-00040 Sectional Assembly (LPSI pumps) DMWO 00739596 2
71111.24 Drawings N001-0902-00042 Mechanical Seal Drawing (LPSI pump) 6 71111.24 Engineering Evaluations 24-04772-001 Commercial Grade Item Dedication Technical Evaluation For Item 50001406 71111.24 Miscellaneous PVGS Diverse and Flexible Coping Strategies (FLEX)
Program 4
71111.24 Procedures 14MT-9BD61 FLEX SFP Makeup Pump Inspections and Tests 7
71111.24 Procedures 31MT-9RC23 Reactor Coolant Pump Sulzer Bingham Seal Replacement 44 71111.24 Procedures 31MT-9SI01 Low Pressure Safety Injection Pump Maintenance 28 71111.24 Procedures 32MT-9PE01 Cleaning, Inspection, and Testing of the Class 1E Diesel Generator 52 71111.24 Procedures 36ST-9SB32 PPS Input Loop Calibration for Parameter 20, LO RWT LEVEL 28 71111.24 Procedures 36ST-9SB51 PPS Transmitter Response Time Test Outside Containment 17 71111.24 Procedures 39MT-9ZZ06 Disassembly/Assembly of Limitorque Type SMB/SB-00 Actuators 17 71111.24 Procedures 40MG-9ZZ07 FLEX Support Guidelines 0
71111.24 Procedures 40OP-9CH01 CVCS Normal Operations 82 71111.24 Procedures 73DP-9CL02 Containment Leakage Rate Testing Program 38 71111.24 Procedures 73ST-9CL01 Containment Leakage Type B and C Testing 54 71111.24 Procedures 73ST-9DG08 Class 1E Diesel Generator Load Rejection, 24 Hour Rated Load and Hot Start Test Train B 14 71111.24 Procedures 73ST-9SI11 Low Pressure Safety Injection Pumps Miniflow - Inservice 41
17 Inspection Procedure Type Designation Description or Title Revision or Date Test 71111.24 Procedures 73ST-9SI14 LPSI Pumps Full Flow - Inservice Test 27 71111.24 Procedures 73ST-9XI43 Containment Recirculation Sump Isolation Valve Leak Testing 8
71111.24 Procedures 82DP-0PP01 Out of Tolerance Program Controls 12 71111.24 Work Orders 5707412, 5692288, 5584954, 5589654, 5585313, 5605691, 5589705. 5585313, 5578080, 5582630, 5582692, 5582721, 5582631, 5582652, 5362206, 5585266, 5585309, 5600216, 5592425, 5592040, 5392331 71124.01 ALARA Plans ALARA 5-Year Plan 2021 - 2025 02/16/2023 71124.01 ALARA Plans RWP-3002 Reactor Destack and Restack 71124.01 ALARA Plans RWP-3306 Steam Generator Maintenance and Support 3
71124.01 ALARA Plans RWP-3411 Repairs on Pressurizer Nozzles 71124.01 ALARA Plans RWP-3502 Valve, Flange, and Pump Maintenance and Inspection 2
71124.01 ALARA Plans RWP-3521 High Risk - Inboard Loop Discharge Check Valve Work 3
71124.01 Corrective Action Documents 24-11031, 24-11601, 24-11695, 25-00057, 25-00238, 25-00437, 25-00536, 25-00872, 25-02109, 25-02190, 25-03348 71124.01 Corrective Action Documents Resulting from Inspection 25-03726, 25-03980, 25-4016, 25-4021, 25-04083, 71124.01 Procedures 72DP-9NF01 Control of SNM Configuration, Inventory & Reporting 64 71124.01 Procedures 75DP-0RP01 Radiological Posting and Labeling 37 71124.01 Procedures 75DP-9RP01 Radiation Exposure and Access Control 24 71124.01 Procedures 75RP-9OP02 Control of High Radiation Areas, Locked High Radiation Areas, and Very High Radiation Areas 34 71124.01 Procedures 75RP-9RP04 Personnel Contamination Monitoring 12 71124.01 Procedures 75RP-9RP05 Contamination Dose Evaluation 8
71124.01 Procedures 75RP-9RP07 Radiation and Contamination Surveys 33 71124.01 Procedures 75RP-9RP10 Conduct of R.P. Operations 40 71124.01 Procedures 75RP-9RP16 Special Dosimetry 10 71124.01 Radiation Surveys 0-M-20240826-1 Low-Level Radioactive Material Storage Facility (LLRMSF) 08/26/2024
18 Inspection Procedure Type Designation Description or Title Revision or Date 71124.01 Radiation Surveys 1-M-20230919-5 U1R24 Containment Power Entry 09/22/2023 71124.01 Radiation Surveys 1-M-20231102-10 1R24 55' and 100' Incore Chase 11/04/2023 71124.01 Radiation Surveys 1-M-20240628-1 AD08 - Equipment Drain Tank 06/28/2024 71124.01 Radiation Surveys 1-M-20240816-3 R124 Resin Transfer Gallery 09/11/2024 71124.01 Radiation Surveys 1-M-20240816-4 R101 High Level Storage Area 09/24/2024 71124.01 Radiation Work Permits (RWPs) 1-3002-R25 Reactor Head Destack/Restack (High Risk) 0 71124.01 Radiation Work Permits (RWPs) 1-3306-R25 Steam Generator Maintenance (High Risk) 0 71124.01 Radiation Work Permits (RWPs) 1-3502-R25 Valve, Flange, and Pump Maintenance (Medium Risk) 0 71124.01 Radiation Work Permits (RWPs) 1-3521-R25 Inboard Loop Discharge Check Valve (High Risk) 0 71124.01 Radiation Work Permits (RWPs)
RWP-9-1021 L..R. Evaporator and Boric Acid Concentrator System Maintenance 4
71124.01 Self-Assessments Integrated Performance Assessment -Radiation Protection 01/31/2025 71124.01 Self-Assessments 202502 Radiological Safety Trends 02/28/2025 71124.01 Self-Assessments24-002 Offsite Safety Review Committee Meeting 10/09/2024 71124.04 Calculations Intake Dose Assessment - HPID 25371 PCE 2-24-0005 11/26/2024 71124.04 Calculations Intake Dose Assessment - HPID 31511 CR 1-23-11087 04/28/2024 71124.04 Calculations Intake Dose Assessment - HPID 20995 12/21/2023 71124.04 Calculations Intake Dose Assessment - HPID25801 07/23/2024 71124.04 Corrective Action Documents 23-04285, 23-05711, 23-07340, 23-07524, 23-07659, 23-07738, 23-09984, 23-11516, 23-11679, 24-04309, 24-06677, 24-08113, 24-10135, 24-12058, 24-12127, 25-00306, 25-01640 71124.04 Miscellaneous National Voluntary Laboratory Accreditation Program On-Site Assessment 05/24/2024 71124.04 Miscellaneous 1-23-0050 Air Sample 10/29/2023
19 Inspection Procedure Type Designation Description or Title Revision or Date 71124.04 Miscellaneous 1-23-00548 Air Sample 10/26/2023 71124.04 Miscellaneous 1-23-00549 Air Sample 10/29/2023 71124.04 Miscellaneous 1-23-00694 Air Sample 11/2/2023 71124.04 Procedures 75DP-0RP02 Radioactive Contamination Control 26 71124.04 Procedures 75DP-9RP01 Radiation Exposure and Access Control 24 71124.04 Procedures 75RP-9ME21 DLR Issue, Exchange, and Termination 16 71124.04 Procedures 75RP-9ME24 Dosimetry Processing, Evaluation, and Documentation 6
71124.04 Procedures 75RP-9ME29 Operation of the Whole Body Counters with APEX-InVivo Software 2
71124.04 Procedures 75RP-9RP03 Bioassay Analysis 11 71124.04 Procedures 75RP-9RP04 Personnel Contamination Monitoring 11 71124.04 Procedures 75RP-9RP16 Special Dosimetry 27 71124.04 Self-Assessments Palo Verde Generating Station Dosimetry Program 2022 NVLAP Internal Audit 05/11/2023 71151 Miscellaneous SSFF 1 April 2024 - 31 March 2025 PIC Data 71151 Miscellaneous Unit 1 OR/PR01 Performance Indicator Occupational/Public Radiation Safety Cornerstone Summary Report - Unit 1 03/18/2025 71151 Miscellaneous Unit 2 OR/PR02 Performance Indicator Occupational/Public Radiation Safety Cornerstone Summary Report - Unit 2 03/18/2025 71151 Miscellaneous Unit 3 OR/PR03 Performance Indicator Occupational/Public Radiation Safety Cornerstone Summary Report - Unit 3 03/18/2025 71151 Procedures 75RP-0LC02 Performance Indicator Public Radiation Safety Cornerstone 5
71151 Procedures 93DP-0LC09 NRC ROP PI Data Collection, Verification, and Submittal 12 71151 Procedures 93DP-0LC10 SSFF Mitigating Systems Performance Indicator 6
71152A Corrective Action Documents 25-01522 71152A Corrective Action Documents Resulting from Inspection 25-05964 71153 Corrective Action Documents 25-004142, 24-03849, 22-06446 71153 Miscellaneous Formal Troubleshooting Game Plan: Troubleshoot 1JDGAB02 Bridge 2 Components 0
20 Inspection Procedure Type Designation Description or Title Revision or Date 71153 Procedures 36ST-9SE13 Excore Startup Channel and Boron Dilution Alarm System Calibration 39 71153 Procedures 40DP-9OP26 Operations Operability Determination Process, 48 71153 Procedures 40ST-9ZZ24 Boron Dilution System Inoperable 17 71153 Work Orders 5503044, 5617375