IR 05000528/2024004
| ML25028A366 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 01/29/2025 |
| From: | John Dixon NRC/RGN-IV/DORS/PBD |
| To: | Heflin A Arizona Public Service Co |
| References | |
| IR 2024004 | |
| Download: ML25028A366 (27) | |
Text
January 29, 2025
SUBJECT:
PALO VERDE NUCLEAR GENERATING STATION - INTEGRATED INSPECTION REPORT 05000528/2024004 AND 05000529/2024004 AND 05000530/2024004
Dear Adam Heflin:
On December 31, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Palo Verde Nuclear Generating Station. On January 17, 2025, the NRC inspectors discussed the results of this inspection with Cary Harbor, Senior Vice President, Site Operations, and other members of your staff. The results of this inspection are documented in the enclosed report.
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 Signed by Dixon, John on 01/29/25 Docket Nos. 05000528, 05000529 and 05000530 License Nos. NPF-41, NPF-51 and NPF-74
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000528, 05000529 and 05000530
License Numbers:
Report Numbers:
05000528/2024004, 05000529/2024004 and 05000530/2024004
Enterprise Identifier:
I-2024-004-0002
Licensee:
Arizona Public Service
Facility:
Palo Verde Nuclear Generating Station
Location:
Tonopah, AZ
Inspection Dates:
October 1, 2024 to December 31, 2024
Inspectors:
L. Merker, Senior Resident Inspector
N. Cuevas, Resident Inspector
R. Azua, Senior Reactor Inspector
L. Carson, Senior Health Physicist
J. O'Donnell, Senior Health Physicist
K. Pfeil, Resident Inspector
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.
List of Findings and Violations
No findings or violations of more than minor significance were identified.
Additional Tracking Items
None.
PLANT STATUS
Unit 1 operated at or near full power for the duration of the inspection period.
Unit 2 entered the inspection period at full power. On October 4, 2024, the unit was shut down for refueling outage 2R25. On November 8, 2024, the reactor was made critical following completion of the refueling outage. On November 10, 2024, the unit was shut down to repair an oil leak from a main turbine bearing due to a missing oil port plug. On November 11, 2024, the reactor was made critical following repairs and returned to full power on November 15, 2024, where it remained for the remainder of the inspection period.
Unit 3 operated at or near full power for the duration of the inspection period.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors performed activities described in IMC 2515, Appendix D, Plant Status, observed risk significant activities, and completed on-site portions of IPs. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
REACTOR SAFETY
71111.01 - Adverse Weather Protection
Impending Severe Weather Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the adequacy of the overall preparations to protect risk-significant systems from impending severe weather due to monsoon season, on October 24, 2024.
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (1 Sample)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Unit 2, high-pressure safety injection train B following maintenance, on December 19, 2024
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (6 Samples)
The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:
- (1) Unit 1, emergency diesel generator B room and emergency diesel generator B control room, fire zones 21B and 22B, on December 11, 2024
- (2) Unit 2, low-pressure safety injection train A and B pump rooms, fire zones 32A and 32B, on December 16, 2024
- (3) Unit 1, main control room, fire zone 17, on December 18, 2024
- (4) Unit 1, train A and B remote shutdown rooms, fire zones 10A and 10B, on December 18, 2024
- (5) Unit 3, containment spray train B pump room, fire zone 30B, on December 18, 2024
- (6) Unit 2, motor-driven auxiliary feedwater pump room, fire zone 73, on December 18, 2024
Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the onsite fire brigade training and performance during an unannounced fire drill, on July 17, 2024.
71111.06 - Flood Protection Measures
Flooding Sample (IP Section 03.01) (1 Sample)
- (1) Units 1, 2, and 3, control building 74-foot elevation due to sump pump failures, on December 17, 2024
===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 were appropriately monitored for degradation and that repairs and replacements were appropriately fabricated, examined and accepted by reviewing the following activities in Unit 2 during refueling outage 2R25 from October 6 to October19, 2024.
PWR Inservice Inspection Activities Sample - Nondestructive Examination and Welding Activities (IP Section 03.01)===
The inspectors verified that the following nondestructive examination and welding activities were performed appropriately:
- (1) Ultrasonic Examination
- steam generator 1 auxiliary and downcomer feedwater pipe (ISI zone 58)circumferential weld 58-23A
- steam generator 1 auxiliary and downcomer feedwater pipe (ISI zone 58)circumferential weld 58-24A
- cold leg 1B safety injection line dissimilar metal weld, piping nozzle-to-safe end (ISI Zone 24) weld 11-10; phased array, axial and circumferential coverage Dye Penetrant Examination
- steam generator 2, 2MRCEE01B**HTEXCH test line isolation valve 2JSGBUV-0226, welds 5548110-1 and 5548110-2 Visual 1 Examination
- auxiliary feedwater pipe welded support (ISI zone 300) weld 2-AF-005-H-001-W
- essential cooling water pipe restraint (ISI zone 300) 2-EC-062-H-005 Visual 3 Examination
- auxiliary feedwater pipe support (ISI zone 300) strut 2-AF-027-H-002
- essential cooling water pipe restraint (ISI zone 300) 2-EC-062-H-005
- safety injection pipe (ISI zone 104) support 2-SI-308-H-015 Magnetic Particle Examination
- steam generator 2 2MRCEE01B**HTEXCH support stand skirt weld Radiographic Examination
- pressurizer spray pipe weld 5555570-2 Welding Activities
- gas tungsten arc welding
- steam generator 2 2MRCEE01B**HTEXCH test line isolation valve 2JSGBUV-0226, welds 5548110-1 and 5548110-2 PWR Inservice Inspection Activities Sample - Vessel Upper Head Penetration Inspection Activities (IP Section 03.02)
No vessel upper head penetration inspections were scheduled or performed this refueling 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) The inspector performed a boric acid walkdown on October 11 and 12, 2024, and evaluated the licensee's actions relating to the following condition reports:
CR 22-02504, CR 24-09783, CR 24-09825, and CR 24-09827.
PWR Inservice Inspection Activities Sample - Steam Generator Tube Inspection Activities (Section 03.04)
No steam generator tube inspections were scheduled or performed during this refueling outage.
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 2 shutdown for refueling outage 2R25, on October 5, 2024.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated licensed operator continued training simulator activities, on December 17, 2024.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (2 Samples)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
- (1) Unit 1, emergency diesel generator train B, on October 30, 2024
- (2) Unit 1, plant protection system channel C, on November 20, 2024
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 2, use of risk-informed completion times for planned maintenance to jumper out degraded battery cell 50 on the class 1E 125 Vdc channel D battery, on December 17, 2024
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (3 Samples)
The inspectors evaluated the licensees justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Units 1, 2, and 3, essential spray pond system operability determination due to the identification of mild corrosion on pipe supports, on November 14, 2024
- (2) Unit 3, high-pressure safety injection pump A long term recirculation valve SIA-HV-604 operability determination due to circuit breaker trip during testing, on December 2, 2024
- (3) Unit 2, containment spay pump A operability determination due to vibration survey in the alert range for y-axis vibration point, on December 11, 2024
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated the Unit 2 refueling outage 2R25 activities from October 4 through November 15, 2024. Operating experience smart sample 2007-03, Crane and Heavy lift Inspection, Supplemental Guidance to 71111.20 and 71111.13, revision 3, was used to inform this sample.
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, emergency diesel generator train B post-maintenance test following maintenance outage, on November 5, 2024
- (2) Unit 1, plant protection system parameter 19, steam generator 2 low level setpoint, channel B post-maintenance testing following bistable card replacement, on November 7, 2024
- (3) Unit 2, containment spray train B post-maintenance testing following pump mechanical seal replacement, on November 8, 2024
- (4) Unit 2, control element drive mechanism control system motor generator set A and B post-maintenance test following replacement, on November 12, 2024
- (5) Unit 2, emergency core cooling system safety injection tank 2B isolation valve SIB-UV-624 circuit breaker post-maintenance testing following component replacement, on November 25, 2024
- (6) Unit 2, class 1E 125 Vdc channel D battery post-maintenance testing following jumpering of degraded battery cell 50, on December 13, 2024
Surveillance Testing (IP Section 03.01) (3 Samples)
- (1) Unit 1, class 1E 4.16kV train A undervoltage protective relays testing, on October 9, 2024
- (2) Unit 2, emergency diesel generator B and integrated safeguards train B testing, on October 31, 2024
- (3) Unit 3, motor-driven auxiliary feedwater pump testing, on October 31, 2024
Containment Isolation Valve (CIV) Testing (IP Section 03.01) (1 Sample)
- (1) Unit 2, chemical and volume control system to seal injection for reactor coolant pumps containment isolation check valve, CH-NV-835, testing, on October 31, 2024
71114.06 - Drill Evaluation
Additional Drill and/or Training Evolution (1 Sample)
- (1) The inspectors evaluated an emergency preparedness drill, on September 4,
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) (2 Samples)
The inspectors observed/evaluated the following licensee processes for monitoring and controlling contamination and radioactive material:
- (1) Unit 2, surveys of potentially contaminated material leaving the radiologically controlled area
- (2) Unit 2, workers exiting the containment building during a refueling outage
Radiological Hazards Control and Work Coverage (IP Section 03.04) (3 Samples)
The inspectors evaluated the licensee's control of radiological hazards for the following radiological work:
- (1) Unit 2 pressurizer heater replacement activities under radiation work permit (RWP)2-3412-R25, revision 0
- (2) Unit 2 in-core instrumentation removal activities under RWP 2-3006-R25, revision 0
- (3) Unit 2 filter storage transfer activities (F36 RCS purification filter) under RWP 9-1006, revision 4 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 2 under vessel access on the 80-foot containment elevation (2)
(HRA) Unit 2 regenerative heat exchanger room on the 111-foot containment elevation (3)
(HRA) Unit 2 reactor vessel head stand on the 140-foot containment elevation (4)
(HRA) Unit 2 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.
71124.03 - In-Plant Airborne Radioactivity Control and Mitigation
Permanent Ventilation Systems (IP Section 03.01) (2 Samples)
The inspectors evaluated the configuration of the following permanently installed ventilation systems:
- (1) Units 1, 2, and 3 control room ventilation air intake systems (HJA/HJB-F04) and radiation monitors (RU-29 and RU-30)
- (2) Technical Support Center ventilation air intake system (AM-ZYN-A04) and radiation monitors (RU-13A)
Temporary Ventilation Systems (IP Section 03.02) (2 Samples)
The inspectors evaluated the configuration of the following temporary ventilation systems:
- (1) Unit 2, temporary high efficiency particulate air (HEPA) ventilation systems pressurizer area
- (2) Unit 2, temporary HEPA ventilation reactor vessel head stand
Use of Respiratory Protection Devices (IP Section 03.03) (1 Sample)
- (1) During this inspection, the only respiratory protection devices that were issued for use were powered air purifying respirators for the pressurizer heater cut out, removal, and replacement project (RWP-3212).
Self-Contained Breathing Apparatus for Emergency Use (IP Section 03.04) (1 Sample)
- (1) The inspectors evaluated the licensees use and maintenance of self-contained breathing apparatuses (SCBAs). The inspectors observed control room operators in all three units and an emergency response team member prepare and use SCBAs. In addition, the inspectors toured the SCBA fill station, maintenance facility, and areas where the licensee securely stored backup SCBAs.
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10)===
- (1) Unit 1 (October 1, 2023, through September 30, 2024)
- (2) Unit 2 (October 1, 2023, through September 30, 2024)
- (3) Unit 3 (October 1, 2023, through September 30, 2024)
BI02: RCS Leak Rate Sample (IP Section 02.11) (3 Samples)
- (1) Unit 1 (October 1, 2023, through September 30, 2024)
- (2) Unit 2 (October 1, 2023, through September 30, 2024)
- (3) Unit 3 (October 1, 2023, through September 30, 2024)
OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)
- (1) Units 1, 2, and 3 (April 1, 2023, through June 30, 2024)
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 (April 1, 2023, through June 30, 2024)
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) Units 1, 2, and 3, effectiveness of corrective actions following discovery of Ametek oil filled capacitor Part 21 notification, on December 12, 2024
- (2) Unit 1, effectiveness of corrective actions and adverse condition monitoring plans following discovery of low oil level in the lower oil reservoirs of reactor coolant pumps 1B and 2B pump motors, on December 26, 2024
- (3) Unit 2, effectiveness of corrective actions following discovery of the multiple stud tensioner in a seismic category IX storage condition during core alterations, on December 30, 2024
71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02)
- (1) From April 8 to November 20, 2024, the licensee wrote condition reports documenting issues regarding performance errors in operations. The inspectors assessed the licensees problem identification threshold, evaluations, and corrective actions related to these condition reports. In each instance the licensee adequately followed site procedures to identify, evaluate, and correct the issue. No issues of more than minor significance were identified.
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On October 15, 2024, the inspectors presented the Unit 2 inservice inspection results to Cary Harbor, Senior Vice President, Site Operations, and other members of the licensee staff.
- On October 25, 2024, the inspectors presented the occupational radiation safety inspection results to Todd Horton, Senior Vice President, Nuclear Regulatory and Oversight, and Ryan Lane, Director, Technical Support Organization, and other members of the licensee staff.
- On January 17, 2025, the inspectors presented the integrated inspection results to Cary Harbor, Senior Vice President, Site Operations, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Calculations
13-MC-SP-0307
SP/EW System Thermal Performance Design Bases
Analysis
Corrective Action
Documents
24-09791, 24-09792, 24-07868, 24-06329, CRDR 2905162,
CRAI 3392785, CRDR 2906487
Acts of Nature
Hot Weather Protection
Procedures
Summer Readiness Administrative Guideline
Corrective Action
Documents
24-08845
Drawings
2-M-SIP-001
P & I Diagram Safety Injection & Shutdown Cooling System
Procedures
High Pressure Safety Injection System Alignment
Verification
Calculations
13-MC-FP-808
Combustible Loads - Diesel Generator Building
Corrective Action
Documents
24-07577, 24-09923, 24-07577, 24-08847-001
Fire Plans
Pre-Fire Strategies Manual
PVNGS DBM - Fire Protection System
FPD01-05-001
Initial Fire Team Member Job Qualification Card
07/15/2022
NPL41-D-3Q1C-
Summary/After Action Review for Regulatory Fire Drill
07/19/2024
NPL41.3Q1C.24
Unit 1 TB07 Main Turbine Lube Oil Storage Room Fire
Scenario Drill Packet Final
07/19/2024
Miscellaneous
NPL41.3Q1C.24
C-Shift Fire Drill After Action Review Summary Final
Revised
08/22/2024
Control of Transient Combustibles
Control Room Fire
Operational Considerations Due to Plant Fire
Fire Department Training Program Description
Procedures
Fire Department Training Program Administration
Corrective Action
Documents
24-11575, 24-12450, 24-06054, 24-07035, 24-06055
Drawings
01-M-OWP-003
P & I Diagram Oily Waste and Non-Radioactive Waste
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
System (Control Building)
2-M-OWP-003
P & I Diagram Oily Waste and Non-Radioactive Waste
System (Control Building)
03-M-OWP-003
P & I Diagram Oily Waste and Non-Radioactive Waste
System (Control Building)
DBM-PVNGS Fire Protection System
13-MC-ZA-0810
Flooding Between Adjacent Safety Related Structures
13-MC-ZJ-0200
As Built Control Building Flooding Calculation
Miscellaneous
Study 13-NS-
C099
Internal Flooding PRA -PRA Modeling and Quantification
Corrective Action
Documents
2-02504
Corrective Action
Documents
Resulting from
Inspection
24-09783, 24-09825, 24-09827
Miscellaneous
4th Inspection Interval - Inservice Inspection Program
Summary Manual - PVNGS Unit 2
Boric Acid Walkdown Leak Detection
Welder and Procedure Qualification
Welding and Brazing Control
Weld Filler Material Control
Boric Acid Corrosion Control Program
Dry Magnetic Particle Examination
Liquid Penetrant Examination
Ultrasonic Examination of Welds in Ferritic Components
Visual Examination of Welds, Bolts, and Components
Visual Examination of Component Supports
Visual Examination For Leakage
Visual Examination of Metal Containment Building Surfaces
73TI`0ZZ02
Ultrasonic Thickness Measurement
Procedures
PDI-UT-1
Generic Procedure for the Ultrasonic Examination of Ferritic
Pipe Welds
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
PDI-UT-10
PDI Generic Procedure For the Ultrasonic Examination of
G
Work Orders
5548608, 5548699, 5555570
Corrective Action
Documents
24-10518, 24-10519, 24-10520, 24-10521, 24-10522
Specific Maneuver Plan: EOC Shutdown 100% to 26.67%
Unit 2 Cycle 25
NLR24S050301
Excess Steam Demand and Pressurizer Thermal Stress
Prevention Training
05/17/2024
Miscellaneous
NLR24S050701
Loss of Offsite Power and Loss of Forced Circulation
10/17/2024
Excess Steam Demand Technical Guideline
Loss of Offsite Power and Loss of Forced Circulation
Technical Guideline
Conduct of Operations
Standard Post Trip Actions
Procedures
Excessive Steam Demand
Corrective Action
Documents
24-10411
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
Commercial Grade Dedication Test/Inspection Results of
Item #500003039
10/16/2024
Inspection Plan for Item #500003039
10/13/2024
MR 2.0 - Performance Monitoring Bases Document
Worksheet: Reactor Protection System (SB)
MR 2.0 - Performance Monitoring Bases Document
Worksheet: Engineered Safety Features Actuation System
(SA)
System Training Manual Volume 49: Plant Protection
System (PPS-SA/SB)
Miscellaneous
00051
Cooper Energy Instruction Manual for KSV Turbocharged
Diesel Generating Unit for Nuclear Power Plant Emergency
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Stand-by Service
24-10411-004
Commercial Grade Item Dedication Vishay
Y0785250R000T9L Resistor Technical Evaluation
10/14/2024
DWG 13-M018-
00147
Control Schematic - Engine Governor Control System
DWG M018-
248
ES150136 Voltage Regulator
A
MEE-01008
Material Engineering Evaluation: Resistors, Item Type
Technical Evaluation
N001-1303-02483
Vishay Foil Resistors S Series Data Sheet
Receipt Inspection
Quality Receiving Checklist Development
Cleaning, Inspection, and Testing of the Class 1E Diesel
Generator
PPS Input Loop Calibrations for Parameter 13, (HI CNT
PRESS) and Parameter 17, (H H CNT PRESS)
Maintenance Rule Monitoring Process
Class 1E Diesel Generator Load Rejection, 24 Hour Rated
Load and Hot Start Test Train B
Procedures
Commercial Grade Dedication (CGD) Process
Work Orders
5544920, 5544775, 5544941, 5462268, 5536346, 5503860,
5662955
Corrective Action
Documents
24-13060, 24-13476, 24-13592, 24-13633, 24-13642, 24-
13660
Miscellaneous
RICT-U2-2024-02
Risk-Informed Completion Time Report for LCO 3.8.4.B.1
2/11/2024
Configuration Risk Management and Risk-Informed
Completion Time Programs
Temporary Jumpering of PK Battery Cell
2-Day Surveillance Test of Station Batteries
Risk Management Actions
Procedures
Assessment and Management of Risk When Performing
Maintenance in Modes 1 and 2
Work Orders
5678487, 5679929
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Calculations
13-MC-ZY-0527
Outside Area - Essential Spray Pond System
Corrective Action
Documents
24-04349, 24-04546, 24-06665, 24-12000, 23-04544, 24-
11133, 24-05924
PVNGS Design Basis Manual - Essential Spray Pond
System
PVNGS - Safety Injection System
03-M-SIP-001
P&I Diagram Safety Injection and Shutdown Cooling System
03-M-SIP-002
P&I Diagram Safety Injection and Shutdown Cooling System
13-SP-030-H-007
Spray Pond Pipe Support Assembly
13-SP-030-H-008
Spray Pond Pipe Support Assembly
Miscellaneous
VTD-I075-00012
INGERSOLL-RAND INSTALLATION, OPERATION AND
MAINTENANCE INSTRUCTIONS FOR 8X23WDF
CONTAINMENT SPRAY PUMPS
Molded Case Circuit Breaker Test
Vibration Survey Review
Vibration Survey
Motor Operated Valve MOV Testing with Quicklook
Containment Spray Pumps - Comprehensive Pump Test
Train A HPSI Injection and Miscellaneous SI Valves
Procedures
Vibration Data Collection for Surveillance Tests
Work Orders
5670922, 5405200, 5550966
Corrective Action
Documents
24-08414, 24-10090, 24-10727, 24-10068, 24-10169, 24-
10171, 24-10941, 24-10956, 24-11157, 24-11259, 24-
260, 24-11293, 24-11626, 24-11721, 24-11722, 24-
11723, 24-11726, 24-11730, 24-11731, 24-11734, 24-
11735, 24-11737, 24-11746, 24-11757, 24-11774, 24-
11777, 24-11784, 24-11786, 24-11787, 24-11788, 24-
11790, 24-11796, 24-11797, 24-11800, 24-11804, 24-
11811, 24-11813, 24-11825, 24-11831, 24-11836, 24-
11846, 24-11847, 24-11854, 24-11864, 24-11903, 24-
2001, 24-12009, 24-12013, 24-12025, 24-12027, 24-
2044, 24-12057, 24-12080, 24-12173, 24-12247, 24-
275, 24-12285, 24-12290, 24-12337, 24-12353, 24-
2611, 24-12618, 24-12660
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Specific Maneuver Plan: EOC Shutdown 100% to 26.67%
Unit 2 Cycle 25
Unit Two 25th Refueling Outage Shutdown Risk Assessment
Final Report
Miscellaneous
Startup Rate Prediction - Unit 2 Cycle 26
11/01/2024
Managing Personnel Fatigue
Fuel Integrity Program Implementing Components
Open/Close the Containment Equipment Access Hatch and
Missile Shield Doors
Lower Mode Functional Recovery Technical Guideline
Shutdown Risk Management
Fuel Pool Cooling
Augmentation of Fuel Pool Cooling with Shutdown Cooling
Shutdown Cooling Initiation
Initial Reactor Startup Following Refuelings
MODE change checklist
107
Outage GOP
Tracking Containment Penetrations
RCS and Pressurizer Heatup and Cooldown Rates
RCS Loop/SDC Train Weekly Breaker Alignment and Power
Availability Surveillance in MODEs 3, 4, 5, and 6
Containment Cleanliness Inspection
Shutdown Risk Assessments
Core Reloading
Calculation of Estimated Critical Condition
Shutdown Margin - Modes 3, 4, and 5
Refueling Machine Operations
Procedures
Spent Fuel Inspection
2-EC-MA-0221
AC Distribution
13-EC-PB-0202
4160 V Degraded Voltage Relay (DVR) and Loss of Voltage
Relay (LoVR) Setpoint & Calibration Calculation
13-MC-AF-0309
AF Hydraulic Calculation for Q-Trains
Calculations
EWR 4464093
Evaluate the AF Pump Discharge Piping System for Effects
10/10/2013
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
of a Metal Temperature of 131 deg F
Corrective Action
Documents
21-11923, 21-11924, 23-06164, 24-10659, 24-10660, 24-
10684, 24-11535, 24-11849, 24-10792, 24-12111, CRDR
116301, CRAI 90882, 24-12551, 24-11362, 24-13633
2-E-SFB-0001
Elementary Diagram Reactor Control System CEDM M-G
Sets 2J-SFN-C02A and 2J-SFN-C02B
2-J-RCE-0A7
Instrument Loop Wiring Diagram Reactor Coolant System
2-M-CHP-001
P & I Diagram Chemical and Volume Control System
DWG 13-N001-
1303-00926
Plant Protection System Schematic Bistable Comp card
Drawings
DWG E-SYS80-
411
Plant Protection System Simplified Functional Diagram
Engineering
Changes
2006-00346
Add the GE Letter on Magne-blast Breaker Driving PAWL
Adjustment to VTD-G080-00409, 00464, 00259. Add Fues
Resistance Values in VTD-G080-00261.
09/05/2006
Design Basis Manual - Auxiliary Feedwater System
00051
Cooper Energy Instruction Manual for KSV Turbocharged
Diesel Generating Unit for Nuclear Power Plant Emergency
Stand-by Service
DWG 02-E-PHA-
006
Single Line Diagram 480V Class 1E Power System Motor
Control Center 2E-PHB-M36,
DWG 02-E-SIF-
006
Control Wiring Diagram Safety Injection & Shutdown Cooling
Sys Safety Injection Tank Iso Valve 2J-SIB-UV-624
JN1017-A00022
MG Set Design Verification Test PTVS Unit 2
RICT-U2-2024-02
Risk-Informed Completion Time Report for LCO 3.8.4.B.1
2/11/2024
Miscellaneous
VTD-E-146-00004
ABB ELECTRO-MECHANICS, INC. OPERATION AND
MAINTENANCE INSTRUCTION FOR PLANT
PROTECTION SYSTEM
Surveillance Test Interval Control
Post-Maintenance Testing Development
Containment Spray Pump Disassembly and Assembly
Cleaning, Inspection, and Testing of the Class 1E Diesel
Generator
Procedures
Temporary Jumpering of PK Battery Cell
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2-Day Surveillance Test of Station Batteries
Surveillance Test Procedure for Class 1E 4160 Volt Bus
Undervoltage Protective Relays
Molded Case Circuit Breaker Surveillance Test
ESFAS Train B Subgroup Relay Functional Test
ESFAS Train B Subgroup Relay Shutdown Functional Test
PPS Bistable Trip Units Functional Test
Plant Protection System Bistable and Bistable Relay
Response Time Test
Pump and Valve Inservice Testing Program
Containment Leakage Type B and C Testing
Class 1E Diesel Generator and Integrated Safeguards Test
Train B
Class 1E Diesel Generator Load Rejection, 24 Hour Rated
Load and Hot Start Test Train B
Containment Spray Pumps - Comprehensive Test
AF Valves - Inservice Test
Work Orders
5540863, 5533131, 5540842, 5540884, 5633702, 5546533,
5540879, 5550038, 5544920, 5462268, 5618379, 5363807,
257972, 5405201, 5540884, 5547913, 5567620, 5540888,
5678487, 5679929
Corrective Action
Documents
24-09680
Miscellaneous
2405 Emergency Preparedness - September 4, 2024,
Exercise Report
10/22/2024
Emergency Preparedness Drill and Exercise Program
Management
ERO Positions - Emergency Coordinator (STSC)
Classifications
Procedures
Notifications
ALARA Plans
1-3502-R24 00 01
Valve, Flange and Pump Maintenance - ALARA Post-Job
Review
2/08/2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2-3002-R24_00
Reactor Destack and Restack - ALARA In-Progress Review
and ALARA Post-Job Review
08/12/2023
2-3502-R24 0
Valve, Flange and Pump Maintenance - ALARA Post-Job
Review
08/08/2023
3-3002-R24_00
Reactor Destack and Restack - ALARA In-Progress Review
and ALARA Post-Job Review
09/06/2024
3-3306-R24_00
SG Primary Side Maintenance - ALARA In-Progress Review,
and Post Job Review
08/21/2024
3-3502-R24_00
&_01
Valve, Flange and Pump Maintenance - ALARA Post-Job
Review
08/21/2024
Corrective Action
Documents
24-02050, 24-11601, 24-11583, 23-09137, 24-00553, 24-
04022, 24-04405, 24-09032, 23-07338, 23-07340, 23-
07525, 23-07749, 23-08377, 23-12688
Corrective Action
Documents
Resulting from
Inspection
24-11546, 24-10145, 24-10148
RP Program Overview
Radiological Posting and Labeling
Control of High Radiation Areas, Locked High Radiation
Areas, and Very High Radiation Areas
Radiation Work Permits
Radiation and Contamination Surveys
Radiological Air Sampling
Procedures
Radiological Job Coverage
2-M-20241006-6
114' Rx Cavity Seal Table Significant Evolution for In-Core
10/06/2024
2-M-20241008-3
114' Rx Cavity/ posting change
10/08/2024
2-M-20241009-25
New MST (Multi-Stud Tensioner) testing
10/09/2024
2-M-20241009-5
Rx Head Insulation Removal Verification
10/09/2024
2-M-20241010-11
Top of UGS (Upper Guide Structure)
10/10/2024
2-M-20241013-14
U2R25 Top of Reactor Head Dose Rate Only
10/13/2024
2-M-20241014-12
Rx head stud hole after removing MST
10/14/2024
2-M-20241014-13
U2R25 Transfer Gaps
10.14/2024
Radiation
Surveys
2-M-20241020-12
R101-High Level Storage Area
10/20/2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2-M-20241021-16
A232 - Filter Access Gallery
10/21/2024
2-M-20241023-14
LHRA Entry for filter offload into HICS
10/23/2024
2-3002-R25
Reactor Destack and Restack
2-3006-R25
Medium Risk - In-Core Instrumentation (ICI) and Heated
Junction Thermal Couple (HTJC) Maintenance
2-3412-R25
Pressurizer (PZR) Heater Cut Out and Replacement
2-3501-R25
RP Tours, Inspections and Routine Surveys
2-3518-R25
High Risk - Minor Maintenance in the 120' / 127'
Regenerative Heat Exchanger Cubicle
9-1006
Filter Change Out / Transport / Storage / Packaging
Radiation Work
Permits (RWPs)
9-1031
Radiation Protection Manager Approved Containment
Entries At Power in Modes 1 & 2
Corrective Action
Documents
24-09961, 24-09494, 24-07921, 24-07679, 24-06452, 24-
05172, 24-04584, 24-04248, 24-02431
Corrective Action
Documents
Resulting from
Inspection
24-11281, 24-11568, 24-11560, 24-11674
01-M-HJP-001
01-M-HJP-002
Drawings
AD-A-ZDY-196
230822090-01
Compressed Air/Gas Quality Testing
08/22/2023
240228083-00
Compressed Air/Gas Quality Testing
2/29/2024
Miscellaneous
240903027-01
Compressed Air/Gas Quality Testing
09/03/2024
Palo Verde Industrial Health and Safety
Surveillance Testing of the Control Room Nuclear Air
Treatment System
NATS Testing - TSC
Radiation Monitoring Systems Operations
Radiation Monitoring Calibration Test for Baseline Process
Monitors
Radiation and Contamination Surveys
Procedures
Radiological Air Sampling
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
01/19/2022
Unit-1 Train-B Control Room Intake Air Monitor (RU-30)
04/18/2023
Unit-2 Train-B Control Room Intake Air Monitor (RU-30)
11/15/2022
HEPA Test, Unit-3 Control Room HVAC
2/01/2022
HEPA Test, Unit-3 Control Room HVAC
03/07/2023
Unit-2 Control Room Essential Air Filtering Unit-A
03/28/2023
09/28/2023
TSC Vent Radiation Monitor (RU-13A)
11/29/2023
HEPA Test, Unit-3 Control Room HVAC
07/09/2024
Unit-3 Train-B Control Room Intake Air Monitor (RU-30)
06/24/2024
Work Orders
Unit-1 Control Room Essential Air Filtering Unit-A
09/03/2024
Corrective Action
Documents
24-01358, 24-01894
Units 1, 2, and 3 PI RCS Leakage Data 10/2023-9/2024
11/15/2024
Units 1, 2, and 3 NRC PI RCS Activity Data 10/2023-9/2024
11/15/2024
Unit 1 PI Summary Report for OR01 and PR01
09/18/2024
Unit 2 PI Summary Report for OR01 and PR01
09/18/2024
Unit 3 PI Summary Report for OR01 and PR01
09/18/2024
23 ARERR
23 Annual Radioactive Effluent Release Report
04/17/2024
Miscellaneous
2408
Radiation Protection Indicator Analysis Detail
09/11/2024
Performance Indicator - Barrier Integrity Cornerstone: RCS
Leak Rate
RCS Activity Performance Indicator
Reactor Coolant System Specific Activity Surveillance Test
Performance Indicator Occupational Radiation Safety
Cornerstone
Performance Indicator Public Radiation Safety Cornerstone
Procedures
NRC ROP PI Data Collection, Verification and Submittal
71151
Work Orders
5487583, 5496303, 5524189
Corrective Action
Documents
23-06802, 24-01963, 24-08552, 24-09241, 24-12985, 16-
2625, 24-10633, 24-10825, 24-10873, 24-10876, 24-
10904, 24-11072, 24-11093, 24-11411, 24-12065, 24-
2093, 24-11072, 24-12825, 24-10873
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
EN#56958, Part 21 - Interim Report for Oil Filled Capacitors
2/09/2024
Part 21 NRC Event 56958 PVGS Applicability Review
2/29/2024
Adverse Condition Monitoring Plan for RCP [1B] Common
Trouble for Motor Lower Oil Reservoir Oil Level Low
Adverse Condition Monitoring Plan for RCP [1B] Common
Trouble for Motor Lower Oil Reservoir Oil Level Low
Adverse Condition Monitoring Plan for RCP [2B] Common
Trouble for Motor Lower Oil Reservoir Oil Level Low
Miscellaneous
Adverse Condition Monitoring Plan for RCP [2B] Common
Trouble for Motor Lower Oil Reservoir Oil Level Low
Condition Reporting Process
Operational Decision Making
Industry Operating Experience Review
Procedures
Part 21 Reporting Process
Work Orders
5545666, 5664048
Corrective Action
Documents
24-03776, 24-03451, 24-12989, 24-08924, 24-03534, 24-
03737, 24-03817, 24-03856, 24-06221, 24-04580
Miscellaneous
Appendix B DP 14 - Operator Fundamental Critique
04/07/2024
Condition Reporting Process
Human Performance Event Evaluation
Conduct of Operations
Operations Technical Documents
Boron Dilution Alarm System Inoperable
Conduct of Chemistry
Procedures
Primary Sampling Instructions
57