ML25128A015
| ML25128A015 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 05/12/2025 |
| From: | John Dixon NRC/RGN-IV/DORS/PBD |
| To: | Heflin A Arizona Public Service Co |
| References | |
| IR 2025001 | |
| Download: ML25128A015 (1) | |
Text
May 12, 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 05000528/2025001 AND 05000529/2025001 AND 05000530/2025001
Dear Adam Heflin:
On March 31, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Palo Verde Nuclear Generating Station. On April 22, 2025, the NRC inspectors discussed the results of this inspection with Jenn Spina, Vice President, Nuclear Regulatory and Oversight, and other members of your staff. The results of this inspection are documented in the enclosed report.
No NRC-identified or self-revealing findings were identified during this inspection.
A licensee-identified violation which was determined to be of very low safety significance is 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 violation or the significance or severity of the violation documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN:
Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region IV; the Director, Office of Enforcement; and the NRC Resident Inspector at Palo Verde Nuclear Generating Station.
A. Heflin 2
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; 05000530 License Nos. NPF-41; NPF-51; NPF-74
Enclosure:
As stated cc w/ encl: Distribution via LISTSERV Signed by Dixon, John on 05/12/25
Non-Sensitive
Sensitive
Publicly Available
Non-Publicly Available OFFICE SRI:DORS/PBD RI:DORS/PBD SPE:DORS/PBD BC:DORS/PBD NAME LMerker NCuevas ASanchez JDixon SIGNATURE
/RA/
/RA/
/RA/
/RA/
DATE 05/09/25 05/09/25 05/08/25 05/12/25
Enclosure U.S. NUCLEAR REGULATORY COMMISSION Inspection Report Docket Numbers:
05000528; 05000529; 05000530 License Numbers:
NPF-41; NPF-51; NPF-74 Report Numbers:
05000528/2025001; 05000529/2025001; 05000530/2025001 Enterprise Identifier:
I-2025-001-0000 Licensee:
Arizona Public Service Facility:
Palo Verde Nuclear Generating Station Location:
Tonopah, Arizona Inspection Dates:
January 1, 2025 to March 31, 2025 Inspectors:
N. Armstrong, Project Engineer M. Bloodgood, Senior Project Engineer N. Cuevas, Resident Inspector P. Elkmann, Sr Emergency Preparedness Inspector S. Hedger, Sr Emergency Preparedness Inspector J. Hickey, Senior Project Engineer L. Merker, Senior Project Engineer 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: 71111.05.
List of Findings and Violations No findings or violations of more than minor significance were identified.
Additional Tracking Items None.
3 PLANT STATUS Unit 1 was shut down for refueling outage 1R25 on March 29, 2025.
Units 2 and 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 Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)
(1)
The inspectors evaluated the sites readiness for seasonal extreme weather conditions prior to the onset of seasonal low temperatures for Units 1, 2, and 3, on January 21, 2025.
71111.04 - Equipment Alignment Partial Walkdown Sample (IP Section 03.01) (2 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
(1)
Unit 3, emergency diesel generator train A following maintenance, on March 10, 2024 (2)
Unit 3, low-pressure safety injection system train B during unplanned maintenance on low-pressure safety injection system train A, on March 14, 2025 71111.05 - Fire Protection Fire Area Walkdown and Inspection Sample (IP Section 03.01) (3 Samples)
The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:
(1)
Unit 2, class 1E 4kV switchgear B room, channel D class battery room, and channel B class battery room; fire zones 5B, 8B, and 9B, on March 6, 2025
4 (2)
Unit 3, high-pressure safety injection system trains A and B pump rooms; fire zones 31A and 31B, on March 26, 2025 (3)
Unit 3, charging system trains A and B, and standby pump and valve gallery rooms; fire zones 46A, 46B, and 46E, on March 26, 2025 Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)
(1)
The inspectors evaluated the onsite fire department training and performance during an unannounced fire drill, on March 25, 2025 71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01)
(1 Sample)
(1)
The inspectors observed and evaluated licensed operator performance in the main control room during the Unit 1 planned down power and shutdown for refueling outage 1R25, on March 28, 2025.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (2 Samples)
(1)
The inspectors observed and evaluated licensed operator continued training simulator activities, on January 21 and 28, 2025.
(2)
The inspectors observed and evaluated licensed operator continued training simulator activities, on February 4, 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 3, emergency diesel generator train A, on March 28, 2025 Quality Control (IP Section 03.02) (1 Sample)
The inspectors evaluated the effectiveness of maintenance and quality control activities to ensure the following SSC remains capable of performing its intended function:
(1)
Units 1, 2, and 3, 600V silicon controlled rectifier for the class 1E 125Vdc power system, on March 3, 2025 71111.13 - Maintenance Risk Assessments and Emergent Work Control Risk Assessment and Management Sample (IP Section 03.01) (7 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:
5 (1)
Unit 1, high risk for planned supplementary protection system functional testing, on January 17, 2025 (2)
Unit 3, high radiological risk for dry cask loading of transportable storage canister, on January 17, 2025 (3)
Unit 2, high risk for emergent maintenance to replace control oil pump A air bleed valve, on February 5, 2025 (4)
Unit 3, emergent work on engineered safety features actuation system channel C containment spray actuation signal manual actuation switch, on February 14, 2025 (5)
Unit 3, planned maintenance on emergency diesel generator train A, on March 1, 2025 (6)
Unit 1, planned maintenance on charging pump B, on February 25, 2025 (7)
Unit 3, planned steam bypass control system troubleshooting with multiple reactor control systems in manual control (not in automatic), on March 25, 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 1, containment building atmosphere monitor RU-1 operability determination due to channel spiking, on January 8, 2025 (2)
Units 1 and 2, qualified safety parameter display system functionality assessment due to upper head saturation margin differences, on March 18, 2025 (3)
Unit 1, emergency diesel generator B operability determination due to jacket water cooler leak, on March 21, 2025 (4)
Unit 3, high-pressure safety injection long-term cooling valve, SIA-HV-604, functionality assessment due to circuit breaker issue during surveillance testing, on March 21, 2025 (5)
Unit 3, essential chiller A operability determination due to low oil temperature during operator rounds, on March 24, 2025 (6)
Unit 3, containment spray system train A operability determination due to air voids in piping, on March 24, 2025 (7)
Unit 3, auxiliary feedwater flow indicator, AFB-FI-41A, functionality assessment for reading less than zero in standby, on March 27, 2025 71111.18 - Plant Modifications Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02)
(1 Sample)
The inspectors evaluated the following temporary or permanent modifications:
(1)
Unit 1, permanent modification to replace the charging pump B gas-filled discharge pulsation dampener with a bladderless pulsation dampener, on March 14, 2025
6 71111.20 - Refueling and Other Outage Activities Refueling/Other Outage Sample (IP Section 03.01) (1 Partial)
(1)
(Partial, Sections 03.01(a) and 03.01(b))
The inspectors evaluated the Unit 1 refueling outage 1R25 activities starting on March 28, 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) (6 Samples)
(1)
Unit 1, plant protection system channel C post-maintenance testing following resistor replacement, on January 15, 2025 (2)
Unit 3, containment spray pump A discharge to shutdown cooling valve SI-HV-684 post-maintenance testing following diagnostic testing and maintenance on January 29, 2025 (3)
Unit 2, normal chilled water system water return and containment isolation valve WCB-UV-61 circuit breaker post-maintenance testing following auxiliary contact replacement, on February 25, 2025 (4)
Unit 1, coolant charging pump B post-maintenance testing following discharge valve replacement, March 11, 2025 (5)
Unit 3, low-pressure safety injection pump A discharge to discharge valve SI-HV-635 post-maintenance testing following breaker maintenance, on March 17, 2025 (6)
Unit 2, steam generator 1 line 2 atmospheric dump valve ADV-178 post-maintenance testing following close limit switch arm replacement, on March 26, 2025 Surveillance Testing (IP Section 03.01) (2 Samples)
(1)
Unit 1, containment spray train A testing, on January 8, 2025 (2)
Unit 1, engineered safety features actuation system train A subgroup relay testing, on January 21, 2025 Inservice Testing (IST) (IP Section 03.01) (1 Sample)
(1)
Unit 3, high-pressure safety injection pump A inservice testing, on March 13, 2025 71114.01 - Exercise Evaluation Inspection Review (IP Section 02.01-02.11) (1 Sample)
(1)
The inspectors evaluated the biennial emergency plan exercise conducted on March 4, 2025. The exercise scenario simulated a control rod malfunction with a subsequent anticipated transient without reactor trip. This was followed by fuel clad damage and subsequent safety bus power losses. A steam generator tube rupture occurred, including failures in associated main steam safety valves. This resulted in a simulated radiological release offsite involving response organization evaluation versus protective action guidelines.
7 71114.04 - Emergency Action Level and Emergency Plan Changes Inspection Review (IP Section 02.01-02.03) (1 Sample)
(1)
The inspectors evaluated the PVNGS Emergency Plan, revision 76, that was submitted to the NRC on January 28, 2025.
Several screenings and evaluations associated with the 10 CFR 50.54(q) emergency plan change process were reviewed. These evaluations do not constitute NRC approval.
71114.08 - Exercise Evaluation - Scenario Review Inspection Review (IP Section 02.01 - 02.04) (1 Sample)
(1)
The inspectors reviewed the licensee's preliminary exercise scenario that was submitted to the NRC on January 3, 2025 (ML25003A176), for the exercise scheduled on March 4, 2025. The inspectors discussed the preliminary scenario comments with Mr. A. Radosevic, Manager, Emergency Preparedness, and other members of the emergency preparedness staff on January 28, 2025. The inspectors' review does not constitute NRC approval of the scenario.
OTHER ACTIVITIES - BASELINE 71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
IE01: Unplanned Scrams per 7000 Critical Hours Sample (IP Section 02.01) (3 Samples)
(1)
Unit 1 (January 1, 2024, through December 31, 2024)
(2)
Unit 2 (January 1, 2024, through December 31, 2024)
(3)
Unit 3 (January 1, 2024, through December 31, 2024)
IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02) (3 Samples)
(1)
Unit 1 (January 1, 2024, through December 31, 2024)
(2)
Unit 2 (January 1, 2024, through December 31, 2024)
(3)
Unit 3 (January 1, 2024, through December 31, 2024)
IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (3 Samples)
(1)
Unit 1 (January 1, 2024, through December 31, 2024)
(2)
Unit 2 (January 1, 2024, through December 31, 2024)
(3)
Unit 3 (January 1, 2024, through December 31, 2024)
EP01: Drill/Exercise Performance (DEP) Sample (IP Section 02.12) (1 Sample)
(1)
Units 1, 2, and 3, January 1, 2024, through December 31, 2024
8 EP02: Emergency Response Organization (ERO) Drill Participation (IP Section 02.13)
(1 Sample)
(1)
Units 1, 2, and 3, January 1, 2024, through December 31. 2024 EP04: Emergency Response Facility and Equipment Readiness (ERFER) (IP Section 02.14)
This is a new NRC performance indicator, introduced in NEI 99-02, Revision 8 (ML24331A114). Licensees began collecting data for this performance indicator on January 1, 2025. Therefore, at the time of inspection, there was no quarterly data compiled and submitted to the NRC as of yet. Verifications will take place on later inspections.
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 issues:
(1)
Unit 3, effectiveness of corrective actions related to plant protection system channel C indication spiking resulting in voltage setpoint change, on January 30, 2025 71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02) (1 Sample)
(1)
The inspectors reviewed the licensees corrective action program for potential adverse trends that might be indicative of a more significant safety issue. The inspectors performed an in-depth review of the licensees ability to identify issues regarding feedwater isolation valves high rod end hydraulic pressures, evaluate each occurrence, and implement corrective actions. No issues of more than minor significance were identified.
INSPECTION RESULTS Licensee-Identified Non-Cited Violation 71111.05 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: Technical specification 5.4.1.d requires, in part, that written procedures shall be implemented covering fire protection program implementation.
Contrary to the above, on November 16, 2023, the licensee failed to implement a written procedure covering fire protection program implementation. Specifically, the licensee failed to implement the daily restoration steps in section 6.4 of procedure 14FT-9FP08, CO2 Fire Suppression System Functional Test, revision 21, during fire suppression system testing activities resulting in the carbon dioxide fire suppression system remaining isolated to the Unit 2, class 1E 4.16 kV switchgear B room and class 1E 125 Vdc train B battery rooms for approximately four days without an hourly fire watch.
9 Significance/Severity: Green. The inspectors assessed the significance of the finding using Inspection Manual Chapter 0609 Appendix F, Fire Protection and Post - Fire Safe Shutdown Significance Determination Process, dated January 1, 2025. The inspectors determined that the finding had very low safety significance (Green) because, while the degraded or non-functional detection or fixed suppression system adversely affected the ability of the system to protect any equipment important to safe shutdown, the plant had a fire probabilistic risk assessment capable of adequately evaluating the risk associated with the finding, as determined by a senior reactor analyst, and the licensees risk-based evaluation for this fire finding indicated a delta-core damage frequency (CDF) of 1.39E-7 (less than 1E-6) that was reviewed and accepted by a senior reactor analyst.
Corrective Action References: Condition report 23-12317 EXIT MEETINGS AND DEBRIEFS The inspectors verified no proprietary information was retained or documented in this report.
On January 28, 2025, the inspectors presented the emergency preparedness exercise scenario review inspection results to Andrew Radosevic, Manager, Emergency Preparedness, and other members of the licensee staff.
On April 16, 2025, the inspectors presented the emergency preparedness exercise inspection results to Jenn Spina, Vice President, Nuclear Regulatory and Oversight, and other members of the licensee staff.
On April 22, 2025, the inspectors presented the integrated inspection results to Jenn Spina, Vice President, Nuclear Regulatory and Oversight, and other members of the licensee staff.
10 DOCUMENTS REVIEWED Inspection Procedure Type Designation Description or Title Revision or Date Calculations CALC 13-MC-DF-0307 Diesel Fuel Oil Transfer System - Line Sizing, Pressure Drop and NPSH 2
PVNGS DBM - Main Steam 34 PVNGS DBM - Auxiliary Feedwater System 27 Engineering Evaluation Request 92-QJ-002, Temporary Freeze Protection Miscellaneous PVNGS DBM - Essential Spray Pond System 24 40AO-9ZZ21 Acts of Nature 39 71111.01 Procedures 40OP-9ZZ17 Essential Spray Pond System 24 Corrective Action Documents 22-06095, 25-00116, 25-02189 03-M-SIP-001 P & I Diagram Safety Injection and Shutdown Cooling System 59 Drawings 03-M-SIP-002 P & I Diagram Safety Injection and Shutdown Cooling System 40 Miscellaneous CRAI 3127427 Engineering Evaluation of [Emergency Diesel Generator]
Fluid Lea[k]age and Potential Operability Concerns 2
40DP-9OPA4 Control Building Watch Station Rounds 133 40OP-9DG01 Emergency Diesel Generator A 86 40OP-9SP01 Essential Spray Pond (SP) Train A 63 40ST-9DG01 Diesel Generator A Test 52 71111.04 Procedures 40ST-9SI13 Train A LPSI and CS System Alignment Verification 37 Product Characteristics and Installation Instructions: 165F ETL Electro thermal Link 05/01/2015 13-MC-FP-0803 Combustible Loads - Control Building 17 Calculations 13-MC-FP-0809 Combustible Loads - Auxiliary Building 13 Corrective Action Documents 23-12209, 23-12317, 25-01998, 25-02060, 25-03130 Pre-fire Strategies Manual 31 Fire Plans Pre-fire Strategies Manual 32 71111.05 Miscellaneous FSCCR 5581849
11 Inspection Procedure Type Designation Description or Title Revision or Date Unit 2 C Shift Unannounced Fire Drill, NPL41-1Q3C-25 03/21/2025 01DP-0AP09 Procedure and Work Instruction Use and Adherence 23 14DP-0FP01 Firewatch Requirements 14 14DP-0FP02 Fire System Impairments and Notifications 29 14DP-0FP33 Control of Transient Combustibles 33 14DP-0FP33 Control of Transient Combustibles 34 14FT-9FP08 CO2 Fire Suppression System Functional Test 21 14FT-9FP08 CO2 Fire Suppression System Functional Test 22 Procedures 38FT-9QK14 Fire Detection/Protection System Supervised Circuits Test and Functional Test - Carbon Dioxide Panels 17 Work Orders 5466305 Corrective Action Documents 25-00973 SES-0-03-T-09 LT-110X Fails Low/Inadvertent AFAS/LOCA/Loss of PBB-S04/A HPSI FTAS/CSAS FTAA 9
SES-0-09-AI-10 Dropped CEA/Loss of NC/Loss of PBA-S03/LOOP/Loss of B EDG/ Blackout 01/30/2024 Miscellaneous SES-0-09-AR-05 SG #1 DP Transmitter Failure/A TC Pump Trip/Condenser Tube Rupture/LBLOCA 6
Specific maneuvering plan 500 EFPD 100 to 26.7% for EOC shutdown Unit 1 cycle 25 0
40AO-9ZZ03 Loss of Cooling Water 16 40AO-9ZZ04 Reactor Coolant Pump Emergencies 34 40AO-9ZZ11 CEA Malfunctions 31 40AO-9ZZ17 Inadvertent PPS-ESFAS Actuations 27 40DP-9OP02 Conduct of Operations 80 40EP-9EO01 Standard Post Trip Actions 24 40EP-9EO03 Loss of Coolant Accident 46 40EP-9EO09 Functional Recovery 66 40EP-9EO10-107 Appendix 107: Aligning a Containment Spray Pump for Injection 0
40OP-9SI01 Shutdown cooling initiation 60 71111.11Q Procedures 40OP-9ZZ05 Power Operations 153
12 Inspection Procedure Type Designation Description or Title Revision or Date 40OP-9ZZ23 Outage general operating procedure (GOP) 92 40ST-9RC01 Reactor coolant system (RCS) and pressurizer Heatup and Cooldown rates 21 72ST-9RX14 Shutdown margin - modes 3, 4, and 5 23 EP-0900-010 ERO Positions - Emergency Coordinator (STSC) 4 EP-0902 Notifications 29 ODP-14 Operations Department Performance Improvement Program 40 Corrective Action Documents 25-01667 4201098; Revise Inspection Plans for Various SCRs 107245, 114660, 44840014, and 44840160, as Necessary to Comply with ITTE 01009 Rev 2, 07/18/2012 ITEM 44840160 QRC 11154-24 600V SCR Commercial Grade Dedication Test/Inspection Results 02/14/2025 Explanation of Sample A vs 100% According to MEE-1009 03/03/2025 13VTD-C628-00051 Cooper Energy Instruction Manual for KSV Turbocharged Diesel Generating Unit for Nuclear Power Plant Emergency Stand-by Service 21 DT-01009-44840160 Commercial Grade Dedication Test: 600V Silicon Controlled Rectifier 1
MEE-01009 Material Engineering Evaluation: Commercial Grade Item Type Technical Evaluation of Diode/Rectifier 2
Miscellaneous QRC 11154-24 Quality Receiving Checklist for APN 44840160 01/03/2025 12DP-0MC46 Receipt Inspection 22 32MT-9PE01 Cleaning, Inspection, and Testing of the Class 1E Diesel Generator 52 73ST-9DG08 Class 1E Diesel Generator Load Rejection, 24 Hour Rated Load and Hot Start Test Train B 14 77DP-0MC01 Commercial Grade Dedication (CGD) of Parts Process 3
87DP-0MC09 Item Procurement Specification (IPS) Requirements 61 Procedures 87DP-0MC39 Commercial Grade Dedication (CGD) Process 6
71111.12 Work Orders 5578080, 5582630, 5582692, 5582721, 5582631, 5582652 71111.13 Corrective Action Documents 25-00643, 18-13900, 23-01988, 25-01011, 25-01654, 25-01579
13 Inspection Procedure Type Designation Description or Title Revision or Date PVNGS DBM-Reactor Protection System 18 Pressurizer Pressure RCA-P-199A, RCA-P-199B, RCA-P-199C, RCA-P-199D SPS Setpoint and Uncertainty Calculation 4
Site Integrated Risk Assessment Work Task 5624670-0 01/03/2025 Risk Management and Readiness Plan for WO 5693555, 2MCONP01A 02/05/2025 Risk Management and Readiness Plan for Unit 2 A Control Oil Pump Air Bleed Valve Replacement, WO #5693555 02/04/2025 Phoenix Risk Monitor - Unit 1, Plant State as of 02/23/2025 11:00 AM Protected Equipment for Charging pump B 02/10/2025 Phoenix Risk Monitor - Unit 3, Plant State as of 02/14/2025 11:00 AM Phoenix Risk Monitor - Unit 3, Plant State as of 03/1/2025 11:00 AM Protected Equipment for DG, EW, EC, and EW INOP 02/24/2025 PVNGS DBM-Engineered Safety Features Actuation System 16 01-E-SBB-001 Elementary Diagram Reactor Protection System Reactor Trip Breakers Channel A and B 7
01-E-SBB-002 Elementary Diagram Reactor Protection System Reactor Trip Breakers Channel C and D 7
312152 Technical Document: Establish A Control Oil Pump Clearance 02/04/2025 Miscellaneous 312247 Technical Document: Restore A Control Oil Pump 02/05/2025 01DP-0AP57 Management of Critical Evolutions and Infrequently Performed Tests or Evolutions 2
02DP-0RS01 Online Integrated Risk 12 30DP-0MP13 PVGS Rigging Control 28 40DP-9AP21 Protected Equipment 8
40DP-9RS01-02 Revising the Phoenix Profile Administrative Guideline 0
Procedures 70DP-0RA05 Assessment and Management of Risk When Performing Maintenance in Modes 1 and 2 27
14 Inspection Procedure Type Designation Description or Title Revision or Date 78OP-9FX03 Spent Fuel Handling Machine 78OP-9ZZ04 MAGNASTOR Cask loading Operations 17 78OP-9ZZ06 MAGNASTOR Contingency Actions 4
Work Orders 5569179, 5693555, 5685819, 5697782, 5578080 13-JC-RI-0200 Reactor Vessel Level System Rix-L-000x Setpoint and Uncertainty Calculation 3
13-JC-SQ-0232 Time Response of Radiation Monitoring System 0
Calculations 13-JC-SQ-0243 RU-01 Setpoint Evaluation for Particulate and Gaseous Channels 0
Corrective Action Documents 24-03585, 24-05091, 25-01613, 18-19179, 20-06732, 25-01986, 25-01987, 25-02049, 24-10056, 24-12000, 25-03046 PV Design Basis Manual - Qualified Safety Parameter Display System 6
CRAI 3127427 13-M018-00606 19R CPT Exchanger 10 13-MS-B067 Containment Spray System Evaluation for Minor Amounts of Air Remaining in Piping Following Normal Venting Activities 2
13-MS-B086 Development of ECCS Suction Side Piping Arc Lengths Associated with Calculated Max Void Volumes 4
13-MS-B092 Development of ECCS Discharge Side Piping Arc Lengths Associated with Calculated Max Void Volumes 3
13-VTD-1981-000101 ITT Standard Storage, Installation, Operation and Maintenance of Heat Exchangers 0
Miscellaneous N001-1101-00341
, Investigate the Waterhammer Pressures and Axial Forces for Different Length High Points 0
36ST-9SH01 Post Accident Monitoring QSPDS Channel A Calibration 21 40DP-9OP08 Diesel Generator Test Record 55 40DP-9OP26 Operations Operability Determination Process 48 40DP-9OP26-01 Operations Operability Determination Process Administrative Guideline 0
40EP-9EO09 Functional Recovery 66 40EP-9EO10-015 Appendix 15: RCS Void Control 1
71111.15 Procedures 40ST-9SI13 Train A LPSI and CS System Alignment Verification 37
15 Inspection Procedure Type Designation Description or Title Revision or Date 74AL-9SQ01 Radiation Monitoring System Alarm Validation and
Response
2 74RM-9EF42 Radiation Monitoring System Alarm Setpoint Determination 35 74ST-9SQ07 Radiation Monitoring System Shiftly Surveillance Test 10 Work Orders 5421243, 5480101 Corrective Action Documents 15-02755, 24-06479, 24-06480, 24-06585, 24-13699, 25-00871, 25-01221, 25-01567, 25-01845, 25-02069, 25-02071, 25-02091 4663700 CH-1671 Replace Charging Pump Pulsation Dampener with New Design that Prevents Possibility of Gas Intrusion 0
Engineering Changes 4663700 CH-1671 Replace Charging Pump Pulsation Dampener with New Design that Prevents Possibility of Gas Intrusion 1
13-MN-1020 Procurement Specification for Charging pump Discharge Pulsation Dampeners for Palo Verde Units 1, 2, and 3 0
13-MS-A160 Discharge Pulsation Dampener Replacement Feasibility Design Study 0
1346-0079-RPT-003 Bladderless Pulsation Dampener Performance Qualification Report 0
FCR-APS-2024-0898 Modify Pedestal for Pulsation Dampener Implementation 01/15/2025 FCR-APS-2024-0899 Access Path Interference Relocation 12/20/2024 N001-0701-00129 Project Specification for Pulsation Dampeners for Arizona Nuclear Power Project Palo Verde Units 1, 2, and 3 2
S-24-0020 Replace Existing Charging Pump Bladder-type Discharge Pulsation Dampeners with New Bladderless-type Pulsation Dampeners 0
Miscellaneous S-24-0020 Replace Existing Charging Pump Bladder-type Discharge Pulsation Dampeners with New Bladderless-type Pulsation Dampeners 1
81DP-0EE02 Design Change Request 18 81DP-0EE10 Design Change Process 57 93DP-0LC07 10 CFR 50.59 and 72.48 Screenings and Evaluations 36 71111.18 Procedures 93DP-0LC07-01 10 CFR 50.59 and 72.48 Administrative Guideline 12
16 Inspection Procedure Type Designation Description or Title Revision or Date Work Orders 5616026 Corrective Action Documents 25-03409, 25-03410, 25-03407, 25-03411 Miscellaneous Unit 1 Cycle 25 72ST-9RX14, Shutdown Margin, Data 03/29/2025 40OP-9SI01 Shutdown cooling initiation 60 40OP-9ZZ23 Outage (GOP) 92 40ST-9RC01 Reactor coolant system (RCS) and Pressurizer Heatup and Cooldown rates 21 71111.20 Procedures 72ST-9RX14 Shutdown margin - modes 3, 4, and 5 23 13-JC-HC-0201 Containment Pressure Narrow Range (PPS Input)
Instrument (HCx-P-351x, x=A,B,C,D) Setpoint and Uncertainty Calculation 5
13-JC-SI-0212 HPSI (Cold Leg) Flow Indicators (F-311, F-321, F-331, & F-341) Decision Points and Total Loop Uncertainty 10 13-JC-SI-0215 Containment Spray Pump Discharge Flow Indication Loops (SIA-F-338 & SIB-F-348) Uncertainty Calculation 18 13-MC-SI-0215 HPSI System Performance Evaluation and Surveillance Requirement Basis Calculation 8
Calculations 13-MC-SI-0220 Containment Spray System Hydraulic Analysis and Pump Surveillance Testing Requirements 7
Corrective Action Documents 24-10411, 24-13058, CRDR 9-8-0790, 25-01988, 25-02650 01-E-SIB-009 Elementary Diagram Safety Injection Shutdown CLG System HPSI 1 Flow Control to Reactor Coolant Valve 1J-SIA-UV-617 8
03-E-SIB-025 Elementary Diagram Safety Injection-Shutdown CLG System Shutdown CLG Heat Exch Iso Valve 3J-SIA-HV-684 4
Drawings 03-E-SIF-025 Control Wiring Diagram Safety Injection-Shutdown CLG System Shutdown CLG Heat Exch Iso Valve 3J-SIA-HV-684 2
2024-00405 Update Design Documents for EC 24-10411-003 10/15/2024 Engineering Changes 24-10411-003 Alt Detail DEC to Support the Use of an Alternate Drop Resistor Within the Process Protective Cabinet 0
PVNGS DBM - Safety Injection System 42 71111.24 Miscellaneous PVNGS DBM-Engineered Safety Features Actuation 16
17 Inspection Procedure Type Designation Description or Title Revision or Date System Vibration Data: Charging Pump Mod for Charging Pump B 02/25/2025 02-E-WCF-UV-61 Control Wiring Diagram Chilled Water System NORM Chilled WTR RTR and CTMT ISO VALVE 2J-WCB-UV-61 2
03-E-SIB-008 Control Wiring Diagram Safety Injection-Shutdown CLG System LPSI Flow Cont to Reactor Coolant Valve 3J-SIA-UV-635 3
03-E-SIF-008 Control Wiring Diagram Safety Injection-Shutdown CLG System LPSI Flow Cont to Reactor Coolant Valve 3J-SIA-UV-635 3
13-VTD-L200-0003-3 Instructions and Maintenance Manual For Limitorque Type SMB Valve Operators 3
N001-1303-02483 Vishay Foil Resistors S Series Data Sheet 0
32MT-9ZZ74 Molded Case Circuit Breaker Test 54 32ST-9ZZ74 Molded Case Circuit Breaker Surveillance Test 50 36ST-9SB28 PPS Input Loop Calibrations for Parameter 13, (HI CNT PRESS) and Parameter 17, (H H CNT PRESS) 18 36ST-9SB28 PPS Input Loop Calibrations for Parameter 13, (HI CNT PRESS) and Parameter 17, (H H CNT PRESS) 18a 40DP-9OP06 Operations Department Repetitive Task Program 131 40DP-9OP06-002 Operations Department Repetitive Task Program Vol. 3, Tasks WC001 through ZZ059 2
40ST-9ZZM1 Operations MODE 1 Surveillance Logs 75 40ST-9ZZM1 Operations MODE 1 Surveillance Logs 75a 73DP-9XI01 Pump and Valve Inservice Testing Program 44 73DP-9XI05 Check Valve Condition Monitoring Program 19 73DP-9ZZ12 Motor Operated Valve MOV Program 23 73DP-9ZZ24 MOV Diagnostic Test Preparation Instructions 2
73DP-9ZZ26 Motor Operated Valve MOV Testing with Quiklook 6
73ST-9SI06 Containment Spray Pumps and Check Valves - Inservice Test 49 Procedures 73ST-9SI06 Containment Spray Pumps and Check Valves - Inservice Test 49a
18 Inspection Procedure Type Designation Description or Title Revision or Date 73ST-9SI10 HPSI Pumps Miniflow - Inservice Test 56 73ST-9SI10 HPSI Pumps Miniflow - Inservice Test 56a 73ST-9XI03 SI Train A Valves - Inservice Test 44 79ST-9CH06 Charging Pump - Inservice Test 39 Work Orders 5503860, 5662955, 5562442, 5567138, 5577274, 5575878, 5621495, 5540888, 5685819, 5573922, 5578082, 5705731, 5707514 Corrective Action Documents 23-01724, 23-09921, 23-10098, 24-00898, 24-00979, 24-02109, 24-02747, 24-02789, 24-04557, 24-07378, 24-08486, 24-08488, 24-09439, 24-09590, 24-09496, 24-09597, 24-09598, 24-09636, 24-09680, 24-10908, 24-11236, 24-12109, 24-13224, 24-13465, 25-00569, 25-00578, 25-00703, 25-02207, 25-02235, 25-02265, 25-02266, 25-02331, 25-03093, 25-03103, 25-03106, 25-03109, 25-03114, 25-03134, 25-03160, 25-03171 Corrective Action Documents Resulting from Inspection Condition Reports 25-03490, 25-03491, 25-03995, 25-04089 INPO EMPE Drill Report 01/31/2023 NRC Evaluated Exercise Report 03/07/2023 Emergency Preparedness 2304 Drill Report 08/04/2023 Emergency Preparedness 2305, 2306 Drill Report 9/19/2023, 9/26/2023 Emergency Preparedness 2401 Dress Rehearsal Drill Report 01/30/2024 Emergency Preparedness 2402 Exercise Report 3/05/2024 Emergency Preparedness 2403, 2404 Drill Report 07/30/2024, 08/13/2024 Emergency Preparedness 2405, 2406 Drill Report 09/04/2024, 09/10/2024 Palo Verde Executive Management Debrief, NRC Evaluated Full Scale Exercise, March 4, 2025 03/26/2025 71114.01 Miscellaneous Evaluation Report HU4.2 Fire Alarm in Containment Event Report (Actual 05/03/2024
19 Inspection Procedure Type Designation Description or Title Revision or Date 24-03363-01 Event)
Joint Public Information Procedure (JPIP) 37 EP-0900-006 ERO Positions - Dose Assessment Health Physicist (EOF) 3 EP-0900-010 ERO Positions - Emergency Coordinator (STSC) 4 EP-0900-011 ERO Positions - Emergency Operations Director (EOF) 5 EP-0900-012 ERO Positions - Engineering Director (EOF) 5 EP-0900-019 ERO Positions - HPN Communicator (EOF) 1 EP-0900-025 ERO Positions - Operations Advisor (STSC) 2 EP-0900-029 ERO Positions - Radiation Protection Coordinator (TSC) 4 EP-0900-030 ERO Positions - Radiation Protection Monitor (STSC) 3 EP-0900-031 ERO Positions - Radiological Assessment Communicator (EOF) 1 EP-0900-032 ERO Positions - Radiological Assessment Coordinator (EOF) 5 EP-0900-036 ERO Positions - RP Support Technician (TSC) 1 EP-0900-037 ERO Positions - Security Director (TSC) 5 EP-0900-039 ERO Positions - Shift Technical Advisor (STSC) 1 EP-0900-040 ERO Positions - STSC Communicator (STSC) 1 EP-0903 Accident Assessment 9
EP-0904 ERO/ERF Activation and Operation. Appendix B 20 Procedures EP-0906 Termination and Recovery 6
102-08902-AR/TR Palo Verde Nuclear Generating Station (PVNGS), Units 1, 2, and 3 and Independent Spent Fuel Storage Installation; Docket Nos. 50-528, 50-529, 50-530 and 72-44; License Nos. NPF-41, NPF-51 and NPF-74; PVNGS Emergency Plan, Revision 76 1/28/2025 Evaluation Tracking Number:
2024-02E Revision 76 Emergency Plan 12/19/2024 Miscellaneous Screening Tracking Number 24-004S Revision 76 Emergency Plan 12/13/2024 71114.04 Procedures 16DP-0EP22 Emergency Plan Maintenance 17
20 Inspection Procedure Type Designation Description or Title Revision or Date Dose Assessment User Manual 10 Miscellaneous 102-08894-AR/LMW Palo Verde Nuclear Generation Station (PVNGS), Units 1, 2, and 3 and Independent Spent Fuel Storage Installation; Docket Nos. 50-528, 50-529, 50-530 and 72-44; License Nos. NPF-41, NPF-51 and NPF-74; 2025 PVNGS NRC Evaluated Exercise Manual 1/3/2025 EP-0901 Classifications 17 EP-0902 Notifications 26 EP-0903 Accident Assessment 9
EP-0904 ERO/ERF Activation and Operation 20 71114.08 Procedures EP-0905 Protective Actions 19 Corrective Action Documents 24-01358, 24-01480, 24-01889, 24-01894, 24-12643 Units 1, 2, and 3 Power Profile PI Vision, January 1, 2024 through December 31, 2024 Miscellaneous 2024 Initiating Events Performance Indicator Data 73DP-9PP01 Thermal Performance Monitoring and Evaluation 8
Procedures 93DP-0LC09 NRC ROP PI Data Collection, Verification and Submittal 12 71151 Work Orders 5600793, 5602457 Calculations 12-JC-SE-0201 Excore Safety Channel Log Power Instrument (Sex-J-0001x)
Setpoint and Uncertainty Calculation (x = A,B,C,D) 11 Corrective Action Documents 16-05525, 16-07210, 17-00002, 18-11241, 18-11315, 18-11534, 18-14393, 18-18483, 24-11959 Drawings 03-J-SEE-0057 Engineering Changes 18-18483-008 13-JS-A093 Excore Log Channel Calibrations 5
Miscellaneous VTD-C490-00007 Combustion Engineering Inc. Operation-Maintenance Instructions for Ex-core Neutron Flux Monitoring System
[Pub. # CENTM-16]
10 36ST-9SE01 Excore Safety Channel Log Calibration 115 40DP-9OP26 Operations operability determination process administrative guidance 71152A Procedures 81DP-0EE02 Design change request
21 Inspection Procedure Type Designation Description or Title Revision or Date Work Orders 5034837, 5292278 Corrective Action Documents 19-10308, 24-05395, 24-05528, 24-05605, 24-05866, 24-06233, 24-06713, 24-06784, 24-07044, 24-07129, 24-12530, 24-13489, 24-13628, 25-01143, 25-01260, 25-02006, 25-02050 2024-002 Operations and Chemistry Audit 05/31/2024 2024-004 Maintenance and Modifications Audit 08/29/2024 2024-005 Corrective Action Audit 08/23/2024 4429530 High Rod End Pressure Engineering Evaluation 07/10/13 Miscellaneous VTD-A391-00010 Anchor/Darling Instruction Manual for Main Steam Isolation Valves (MSIV) and Feedwater Isolation Valves (FWIV)
[Pub.#E9023-9]
15 01DP-0AP12 Condition Reporting Process 49 01DP-0AP12-01 Condition Reporting Process Administrative Guideline 25 01DP-0AP59 Conduct of Organizational Effectiveness 10 01DP-0AP59-07 Trend Analysis Administrative Guideline 1
01DP-0AP59-10 Self-Assessment and Benchmarking Administrative Guideline 2
40AL-9RK6A Panel B06A Alarm Responses 28 71152S Procedures 60DP-0QQ19 Internal Audits 36