IR 05000528/2025001
| 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
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. 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
Inspection Report
Docket Numbers:
05000528; 05000529; 05000530
License Numbers:
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
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: 71111.0
List of Findings and Violations
No findings or violations of more than minor significance were identified.
Additional Tracking Items
None.
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
- (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:
- (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
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.
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)===
- (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 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)
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) 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.
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.
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
PVNGS DBM - Main Steam
PVNGS DBM - Auxiliary Feedwater System
Engineering Evaluation Request 92-QJ-002, Temporary
Freeze Protection
Miscellaneous
PVNGS DBM - Essential Spray Pond System
Acts of Nature
Procedures
Essential Spray Pond System
Corrective Action
Documents
2-06095, 25-00116, 25-02189
03-M-SIP-001
P & I Diagram Safety Injection and Shutdown Cooling
System
Drawings
03-M-SIP-002
P & I Diagram Safety Injection and Shutdown Cooling
System
Miscellaneous
CRAI 3127427
Engineering Evaluation of [Emergency Diesel Generator]
Fluid Lea[k]age and Potential Operability Concerns
Control Building Watch Station Rounds
133
Essential Spray Pond (SP) Train A
Diesel Generator A Test
Procedures
Train A LPSI and CS System Alignment Verification
Product Characteristics and Installation Instructions: 165F
ETL Electro thermal Link
05/01/2015
13-MC-FP-0803
Combustible Loads - Control Building
Calculations
13-MC-FP-0809
Combustible Loads - Auxiliary Building
Corrective Action
Documents
23-12209, 23-12317, 25-01998, 25-02060, 25-03130
Pre-fire Strategies Manual
Fire Plans
Pre-fire Strategies Manual
Miscellaneous
FSCCR 5581849
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Unit 2 C Shift Unannounced Fire Drill, NPL41-1Q3C-25
03/21/2025
Procedure and Work Instruction Use and Adherence
Firewatch Requirements
Fire System Impairments and Notifications
Control of Transient Combustibles
Control of Transient Combustibles
CO2 Fire Suppression System Functional Test
CO2 Fire Suppression System Functional Test
Procedures
Fire Detection/Protection System Supervised Circuits Test
and Functional Test - Carbon Dioxide Panels
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
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
Specific maneuvering plan 500 EFPD 100 to 26.7% for EOC
shutdown Unit 1 cycle 25
Loss of Cooling Water
Reactor Coolant Pump Emergencies
CEA Malfunctions
Inadvertent PPS-ESFAS Actuations
Conduct of Operations
Standard Post Trip Actions
Loss of Coolant Accident
Functional Recovery
Appendix 107: Aligning a Containment Spray Pump for
Injection
Shutdown cooling initiation
Procedures
Power Operations
153
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Outage general operating procedure (GOP)
Reactor coolant system (RCS) and pressurizer Heatup and
Cooldown rates
Shutdown margin - modes 3, 4, and 5
ERO Positions - Emergency Coordinator (STSC)
Notifications
ODP-14
Operations Department Performance Improvement Program
Corrective Action
Documents
25-01667
201098; 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
2/14/2025
Explanation of Sample A vs 100% According to MEE-1009
03/03/2025
00051
Cooper Energy Instruction Manual for KSV Turbocharged
Diesel Generating Unit for Nuclear Power Plant Emergency
Stand-by Service
DT-01009-
44840160
Commercial Grade Dedication Test: 600V Silicon Controlled
MEE-01009
Material Engineering Evaluation: Commercial Grade Item
Type Technical Evaluation of Diode/Rectifier
Miscellaneous
QRC 11154-24
Quality Receiving Checklist for APN 44840160
01/03/2025
Receipt Inspection
Cleaning, Inspection, and Testing of the Class 1E Diesel
Generator
Class 1E Diesel Generator Load Rejection, 24 Hour Rated
Load and Hot Start Test Train B
Commercial Grade Dedication (CGD) of Parts Process
Item Procurement Specification (IPS) Requirements
Procedures
Commercial Grade Dedication (CGD) Process
Work Orders
5578080, 5582630, 5582692, 5582721, 5582631, 5582652
Corrective Action
Documents
25-00643, 18-13900, 23-01988, 25-01011, 25-01654, 25-
01579
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
PVNGS DBM-Reactor Protection System
Pressurizer Pressure RCA-P-199A, RCA-P-199B, RCA-P-
199C, RCA-P-199D SPS Setpoint and Uncertainty
Calculation
Site Integrated Risk Assessment Work Task 5624670-0
01/03/2025
Risk Management and Readiness Plan for WO 5693555,
2MCONP01A
2/05/2025
Risk Management and Readiness Plan for Unit 2 A Control
Oil Pump Air Bleed Valve Replacement, WO #5693555
2/04/2025
Phoenix Risk Monitor - Unit 1, Plant State as of 02/23/2025
11:00 AM
Protected Equipment for Charging pump B
2/10/2025
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
2/24/2025
PVNGS DBM-Engineered Safety Features Actuation
System
01-E-SBB-001
Elementary Diagram Reactor Protection System Reactor
Trip Breakers Channel A and B
01-E-SBB-002
Elementary Diagram Reactor Protection System Reactor
Trip Breakers Channel C and D
2152
Technical Document: Establish A Control Oil Pump
Clearance
2/04/2025
Miscellaneous
2247
Technical Document: Restore A Control Oil Pump
2/05/2025
Management of Critical Evolutions and Infrequently
Performed Tests or Evolutions
Online Integrated Risk
PVGS Rigging Control
Protected Equipment
Revising the Phoenix Profile Administrative Guideline
Procedures
Assessment and Management of Risk When Performing
Maintenance in Modes 1 and 2
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Spent Fuel Handling Machine
MAGNASTOR Cask loading Operations
MAGNASTOR Contingency Actions
Work Orders
5569179, 5693555, 5685819, 5697782, 5578080
13-JC-RI-0200
Reactor Vessel Level System Rix-L-000x Setpoint and
Uncertainty Calculation
13-JC-SQ-0232
Time Response of Radiation Monitoring System
Calculations
13-JC-SQ-0243
RU-01 Setpoint Evaluation for Particulate and Gaseous
Channels
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
CRAI 3127427
13-M018-00606
19R CPT Exchanger
13-MS-B067
Containment Spray System Evaluation for Minor Amounts of
Air Remaining in Piping Following Normal Venting Activities
13-MS-B086
Development of ECCS Suction Side Piping Arc Lengths
Associated with Calculated Max Void Volumes
13-MS-B092
Development of ECCS Discharge Side Piping Arc Lengths
Associated with Calculated Max Void Volumes
13-VTD-1981-
000101
ITT Standard Storage, Installation, Operation and
Maintenance of Heat Exchangers
Miscellaneous
N001-1101-
00341
, Investigate the Waterhammer Pressures and Axial Forces
for Different Length High Points
Post Accident Monitoring QSPDS Channel A Calibration
Diesel Generator Test Record
Operations Operability Determination Process
Operations Operability Determination Process Administrative
Guideline
Functional Recovery
Appendix 15: RCS Void Control
Procedures
Train A LPSI and CS System Alignment Verification
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Radiation Monitoring System Alarm Validation and
Response
Radiation Monitoring System Alarm Setpoint Determination
Radiation Monitoring System Shiftly Surveillance Test
Work Orders
21243, 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
Engineering
Changes
4663700
CH-1671 Replace Charging Pump Pulsation Dampener with
New Design that Prevents Possibility of Gas Intrusion
13-MN-1020
Procurement Specification for Charging pump Discharge
Pulsation Dampeners for Palo Verde Units 1, 2, and 3
13-MS-A160
Discharge Pulsation Dampener Replacement Feasibility
Design Study
1346-0079-RPT-
003
Bladderless Pulsation Dampener Performance Qualification
Report
FCR-APS-2024-
0898
Modify Pedestal for Pulsation Dampener Implementation
01/15/2025
FCR-APS-2024-
0899
Access Path Interference Relocation
2/20/2024
N001-0701-
00129
Project Specification for Pulsation Dampeners for Arizona
Nuclear Power Project Palo Verde Units 1, 2, and 3
S-24-0020
Replace Existing Charging Pump Bladder-type Discharge
Pulsation Dampeners with New Bladderless-type Pulsation
Dampeners
Miscellaneous
S-24-0020
Replace Existing Charging Pump Bladder-type Discharge
Pulsation Dampeners with New Bladderless-type Pulsation
Dampeners
Design Change Request
Design Change Process
CFR 50.59 and 72.48 Screenings and Evaluations
Procedures
CFR 50.59 and 72.48 Administrative Guideline
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
Shutdown cooling initiation
Outage (GOP)
Reactor coolant system (RCS) and Pressurizer Heatup and
Cooldown rates
Procedures
Shutdown margin - modes 3, 4, and 5
13-JC-HC-0201
Containment Pressure Narrow Range (PPS Input)
Instrument (HCx-P-351x, x=A,B,C,D) Setpoint and
Uncertainty Calculation
13-JC-SI-0212
HPSI (Cold Leg) Flow Indicators (F-311, F-321, F-331, & F-
341) Decision Points and Total Loop Uncertainty
13-JC-SI-0215
Containment Spray Pump Discharge Flow Indication Loops
(SIA-F-338 & SIB-F-348) Uncertainty Calculation
13-MC-SI-0215
HPSI System Performance Evaluation and Surveillance
Requirement Basis Calculation
Calculations
13-MC-SI-0220
Containment Spray System Hydraulic Analysis and Pump
Surveillance Testing Requirements
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
03-E-SIB-025
Elementary Diagram Safety Injection-Shutdown CLG System
Shutdown CLG Heat Exch Iso Valve 3J-SIA-HV-684
Drawings
03-E-SIF-025
Control Wiring Diagram Safety Injection-Shutdown CLG
System Shutdown CLG Heat Exch Iso Valve 3J-SIA-HV-684
24-00405
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
PVNGS DBM - Safety Injection System
Miscellaneous
PVNGS DBM-Engineered Safety Features Actuation
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
System
Vibration Data: Charging Pump Mod for Charging Pump B
2/25/2025
2-E-WCF-UV-61
Control Wiring Diagram Chilled Water System NORM Chilled
WTR RTR and CTMT ISO VALVE 2J-WCB-UV-61
03-E-SIB-008
Control Wiring Diagram Safety Injection-Shutdown CLG
System LPSI Flow Cont to Reactor Coolant Valve 3J-SIA-
UV-635
03-E-SIF-008
Control Wiring Diagram Safety Injection-Shutdown CLG
System LPSI Flow Cont to Reactor Coolant Valve 3J-SIA-
UV-635
13-VTD-L200-
0003-3
Instructions and Maintenance Manual For Limitorque Type
SMB Valve Operators
N001-1303-
2483
Vishay Foil Resistors S Series Data Sheet
Molded Case Circuit Breaker Test
Molded Case Circuit Breaker Surveillance Test
PPS Input Loop Calibrations for Parameter 13, (HI CNT
PRESS) and Parameter 17, (H H CNT PRESS)
PPS Input Loop Calibrations for Parameter 13, (HI CNT
PRESS) and Parameter 17, (H H CNT PRESS)
18a
Operations Department Repetitive Task Program
131
Operations Department Repetitive Task Program Vol. 3,
Tasks WC001 through ZZ059
Operations MODE 1 Surveillance Logs
Operations MODE 1 Surveillance Logs
75a
Pump and Valve Inservice Testing Program
Check Valve Condition Monitoring Program
Motor Operated Valve MOV Program
MOV Diagnostic Test Preparation Instructions
Motor Operated Valve MOV Testing with Quiklook
Containment Spray Pumps and Check Valves - Inservice
Test
Procedures
Containment Spray Pumps and Check Valves - Inservice
Test
49a
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
HPSI Pumps Miniflow - Inservice Test
HPSI Pumps Miniflow - Inservice Test
56a
SI Train A Valves - Inservice Test
Charging Pump - Inservice Test
Work Orders
5503860, 5662955, 5562442, 5567138, 5577274, 5575878,
21495, 5540888, 5685819, 5573922, 5578082, 5705731,
5707514
Corrective Action
Documents
23-01724, 23-09921, 23-10098, 24-00898, 24-00979, 24-
2109, 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-
207, 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
Miscellaneous
Evaluation Report HU4.2 Fire Alarm in Containment Event Report (Actual
05/03/2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
24-03363-01
Event)
Joint Public Information Procedure (JPIP)
ERO Positions - Dose Assessment Health Physicist (EOF)
ERO Positions - Emergency Coordinator (STSC)
ERO Positions - Emergency Operations Director (EOF)
ERO Positions - Engineering Director (EOF)
ERO Positions - HPN Communicator (EOF)
ERO Positions - Operations Advisor (STSC)
ERO Positions - Radiation Protection Coordinator (TSC)
ERO Positions - Radiation Protection Monitor (STSC)
ERO Positions - Radiological Assessment Communicator
(EOF)
ERO Positions - Radiological Assessment Coordinator
(EOF)
ERO Positions - RP Support Technician (TSC)
ERO Positions - Security Director (TSC)
ERO Positions - Shift Technical Advisor (STSC)
ERO Positions - STSC Communicator (STSC)
Accident Assessment
ERO/ERF Activation and Operation. Appendix B
Procedures
Termination and Recovery
2-08902-
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:
24-02E
Revision 76 Emergency Plan
2/19/2024
Miscellaneous
Screening
Tracking Number
24-004S
Revision 76 Emergency Plan
2/13/2024
Procedures
Emergency Plan Maintenance
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Dose Assessment User Manual
Miscellaneous
2-08894-
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
Classifications
Notifications
Accident Assessment
ERO/ERF Activation and Operation
Procedures
Protective Actions
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
24 Initiating Events Performance Indicator Data
Thermal Performance Monitoring and Evaluation
Procedures
NRC ROP PI Data Collection, Verification and Submittal
71151
Work Orders
5600793, 5602457
Calculations
2-JC-SE-0201
Excore Safety Channel Log Power Instrument (Sex-J-0001x)
Setpoint and Uncertainty Calculation (x = A,B,C,D)
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
Miscellaneous
VTD-C490-00007
Combustion Engineering Inc. Operation-Maintenance
Instructions for Ex-core Neutron Flux Monitoring System
[Pub. # CENTM-16]
Excore Safety Channel Log Calibration
115
Operations operability determination process administrative
guidance
Procedures
Design change request
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-
233, 24-06713, 24-06784, 24-07044, 24-07129, 24-12530,
24-13489, 24-13628, 25-01143, 25-01260, 25-02006, 25-
2050
24-002
Operations and Chemistry Audit
05/31/2024
24-004
Maintenance and Modifications Audit
08/29/2024
24-005
Corrective Action Audit
08/23/2024
29530
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]
Condition Reporting Process
Condition Reporting Process Administrative Guideline
Conduct of Organizational Effectiveness
Trend Analysis Administrative Guideline
Self-Assessment and Benchmarking Administrative
Guideline
Panel B06A Alarm Responses
Procedures
Internal Audits
36