ML25028A366
| 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 Adam Heflin, Executive Vice President and Chief Nuclear Officer Arizona Public Service Company P.O. Box 52034, MS 7602 Phoenix, AZ 85072-2034
SUBJECT:
PALO VERDE NUCLEAR GENERATING STATION - INTEGRATED INSPECTION REPORT 05000528/2024004 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
A. Heflin 2
Docket Nos. 05000528, 05000529 and 05000530 License Nos. NPF-41, NPF-51 and NPF-74
Enclosure:
As stated cc w/ encl: Distribution via LISTSERV
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 01/29/25 01/28/25 01/28/25 01/29/25
Enclosure U.S. NUCLEAR REGULATORY COMMISSION Inspection Report Docket Numbers:
05000528, 05000529 and 05000530 License Numbers:
NPF-41, NPF-51 and NPF-74 Report Numbers:
05000528/2024004, 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
2
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Palo Verde Nuclear Generating Station, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.
List of Findings and Violations No findings or violations of more than minor significance were identified.
Additional Tracking Items None.
3 PLANT STATUS Unit 1 operated at or near full power for the duration of the inspection period.
Unit 2 entered the inspection period at full power. On 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)
4 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) (1 Sample)
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
5 Dye Penetrant Examination safety injection system, 24 inch pipe, welded pipe support, (ISI zone 104),
weld 2-SI-308-H-15-W 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.
6 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:
7 (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
8 71114.06 - Drill Evaluation Additional Drill and/or Training Evolution (1 Sample)
(1)
The inspectors evaluated an emergency preparedness drill, on September 4, 2024.
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
9 (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) (3 Samples)
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) (3 Samples)
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 Sample)
(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.
11 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.
12 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 9
Corrective Action Documents 24-09791, 24-09792, 24-07868, 24-06329, CRDR 2905162, CRAI 3392785, CRDR 2906487 40AO-9ZZ21 Acts of Nature 39 40OP-9ZZ19 Hot Weather Protection 7
71111.01 Procedures 51DP-9OM03-04 Summer Readiness Administrative Guideline 1
Corrective Action Documents 24-08845 Drawings 02-M-SIP-001 P & I Diagram Safety Injection & Shutdown Cooling System 58 71111.04 Procedures 40ST-9SI07 High Pressure Safety Injection System Alignment Verification 21 Calculations 13-MC-FP-808 Combustible Loads - Diesel Generator Building 6
Corrective Action Documents 24-07577, 24-09923, 24-07577, 24-08847-001 Fire Plans Pre-Fire Strategies Manual 31 PVNGS DBM - Fire Protection System 15 FPD01-05-001 Initial Fire Team Member Job Qualification Card 07/15/2022 NPL41-D-3Q1C-24 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 14DP-0FP33 Control of Transient Combustibles 33 40AO-9ZZ19 Control Room Fire 42 40DP-9ZZ19 Operational Considerations Due to Plant Fire 37 12DP-0TR01 Fire Department Training Program Description 22 71111.05 Procedures 14DP-0TR02 Fire Department Training Program Administration 31 Corrective Action Documents 24-11575, 24-12450, 24-06054, 24-07035, 24-06055 71111.06 Drawings 01-M-OWP-003 P & I Diagram Oily Waste and Non-Radioactive Waste 7
13 Inspection Procedure Type Designation Description or Title Revision or Date System (Control Building) 02-M-OWP-003 P & I Diagram Oily Waste and Non-Radioactive Waste System (Control Building) 5 03-M-OWP-003 P & I Diagram Oily Waste and Non-Radioactive Waste System (Control Building) 4 DBM-PVNGS Fire Protection System 15 13-MC-ZA-0810 Flooding Between Adjacent Safety Related Structures 8
13-MC-ZJ-0200 As Built Control Building Flooding Calculation 8
Miscellaneous Study 13-NS-C099 Internal Flooding PRA -PRA Modeling and Quantification 4
Corrective Action Documents 22-02504 Corrective Action Documents Resulting from Inspection 24-09783, 24-09825, 24-09827 Miscellaneous 4INT-ISI-2 4th Inspection Interval - Inservice Inspection Program Summary Manual - PVNGS Unit 2 1
70TI-9ZC01 Boric Acid Walkdown Leak Detection 29 73DP-9WP01 Welder and Procedure Qualification 9
73DP-9WP04 Welding and Brazing Control 21 73DP-9WP05 Weld Filler Material Control 12 73DP-9ZC01 Boric Acid Corrosion Control Program 12 73TI-9ZZ05 Dry Magnetic Particle Examination 19 73TI-9ZZ07 Liquid Penetrant Examination 19 73TI-9ZZ10 Ultrasonic Examination of Welds in Ferritic Components 16 73TI-9ZZ17 Visual Examination of Welds, Bolts, and Components 15 73TI-9ZZ18 Visual Examination of Component Supports 18 73TI-9ZZ22 Visual Examination For Leakage 15 73TI-9ZZ82 Visual Examination of Metal Containment Building Surfaces 8
73TI`0ZZ02 Ultrasonic Thickness Measurement 14 71111.08P Procedures PDI-UT-1 Generic Procedure for the Ultrasonic Examination of Ferritic Pipe Welds 2
14 Inspection Procedure Type Designation Description or Title Revision or Date PDI-UT-10 PDI Generic Procedure For the Ultrasonic Examination of Dissimilar Metal Welds 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 0
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 40DP-9AP10 Excess Steam Demand Technical Guideline 27 40DP-9AP12 Loss of Offsite Power and Loss of Forced Circulation Technical Guideline 28 40DP-9OP02 Conduct of Operations 79 40EP-9EO01 Standard Post Trip Actions 23 40EP-9EO02 Reactor Trip 14 71111.11Q Procedures 40EP-9EO05 Excessive Steam Demand 35 Corrective Action Documents 24-10411 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
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) 0 MR 2.0 - Performance Monitoring Bases Document Worksheet: Engineered Safety Features Actuation System (SA) 0 System Training Manual Volume 49: Plant Protection System (PPS-SA/SB) 2 71111.12 Miscellaneous 13VTD-C628-00051 Cooper Energy Instruction Manual for KSV Turbocharged Diesel Generating Unit for Nuclear Power Plant Emergency 21
15 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 20 DWG M018-01248 ES150136 Voltage Regulator A
MEE-01008 Material Engineering Evaluation: Resistors, Item Type Technical Evaluation 4
N001-1303-02483 Vishay Foil Resistors S Series Data Sheet 0
12DP-0MC46 Receipt Inspection 22 12DP-0MC48 Quality Receiving Checklist Development 8
32MT-9PE01 Cleaning, Inspection, and Testing of the Class 1E Diesel Generator 52 36ST-9SB28 PPS Input Loop Calibrations for Parameter 13, (HI CNT PRESS) and Parameter 17, (H H CNT PRESS) 18 70DP-0MR02 Maintenance Rule Monitoring Process 1
73ST-9DG08 Class 1E Diesel Generator Load Rejection, 24 Hour Rated Load and Hot Start Test Train B 14 Procedures 87DP-0MC39 Commercial Grade Dedication (CGD) Process 6
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 12/11/2024 02DP-9RS01 Configuration Risk Management and Risk-Informed Completion Time Programs 4
32MT-9PK02 Temporary Jumpering of PK Battery Cell 1
32ST-9PK02 92-Day Surveillance Test of Station Batteries 40 40DP-9RS03 Risk Management Actions 1
40DP-9RS05 Calculation of RMAT and RICT 0
Procedures 70DP-0RA05 Assessment and Management of Risk When Performing Maintenance in Modes 1 and 2 27 71111.13 Work Orders 5678487, 5679929
16 Inspection Procedure Type Designation Description or Title Revision or Date Calculations 13-MC-ZY-0527 Outside Area - Essential Spray Pond System 9
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 24 PVNGS - Safety Injection System 42 03-M-SIP-001 P&I Diagram Safety Injection and Shutdown Cooling System 59 03-M-SIP-002 P&I Diagram Safety Injection and Shutdown Cooling System 40 13-SP-030-H-007 Spray Pond Pipe Support Assembly 3
13-SP-030-H-008 Spray Pond Pipe Support Assembly 2
Miscellaneous VTD-I075-00012 INGERSOLL-RAND INSTALLATION, OPERATION AND MAINTENANCE INSTRUCTIONS FOR 8X23WDF CONTAINMENT SPRAY PUMPS 6
32MT-9ZZ74 Molded Case Circuit Breaker Test 54 37DP-9ZZ05 Vibration Survey Review 4
37MT-9ZZ01 Vibration Survey 16 73DP-9ZZ26 Motor Operated Valve MOV Testing with Quicklook 6
73ST-9SI15 Containment Spray Pumps - Comprehensive Pump Test 39 73ST-9XI13 Train A HPSI Injection and Miscellaneous SI Valves 40 Procedures 73TI-9XI01 Vibration Data Collection for Surveillance Tests 26 71111.15 Work Orders 5670922, 5405200, 5550966 71111.20 Corrective Action Documents 24-08414, 24-10090, 24-10727, 24-10068, 24-10169, 24-10171, 24-10941, 24-10956, 24-11157, 24-11259, 24-11260, 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, 24-12001, 24-12009, 24-12013, 24-12025, 24-12027, 24-12044, 24-12057, 24-12080, 24-12173, 24-12247, 24-12275, 24-12285, 24-12290, 24-12337, 24-12353, 24-12611, 24-12618, 24-12660
17 Inspection Procedure Type Designation Description or Title Revision or Date Specific Maneuver Plan: EOC Shutdown 100% to 26.67%
Unit 2 Cycle 25 0
Unit Two 25th Refueling Outage Shutdown Risk Assessment Final Report 0
Miscellaneous Startup Rate Prediction - Unit 2 Cycle 26 11/01/2024 01DP-0AP17 Managing Personnel Fatigue 12 05DP-0NF25 Fuel Integrity Program Implementing Components 8
31MT-9AZ05 Open/Close the Containment Equipment Access Hatch and Missile Shield Doors 43 40DP-9AP19 Lower Mode Functional Recovery Technical Guideline 17 40DP-9RS02 Shutdown Risk Management 8
40OP-9PC01 Fuel Pool Cooling 16 40OP-9PC05 Augmentation of Fuel Pool Cooling with Shutdown Cooling 39 40OP-9SI01 Shutdown Cooling Initiation 59 40OP-9ZZ02 Initial Reactor Startup Following Refuelings 64 40OP-9ZZ11 MODE change checklist 107 40OP-9ZZ23 Outage GOP 91 40OP-9ZZ26 Tracking Containment Penetrations 29 40ST-9RC01 RCS and Pressurizer Heatup and Cooldown Rates 21 40ST-9RC03 RCS Loop/SDC Train Weekly Breaker Alignment and Power Availability Surveillance in MODEs 3, 4, 5, and 6 7
40ST-9ZZ09 Containment Cleanliness Inspection 27 70DP-0RA01 Shutdown Risk Assessments 65 72IC-9RX03 Core Reloading 60 72OP-9RX01 Calculation of Estimated Critical Condition 40 72ST-9RX14 Shutdown Margin - Modes 3, 4, and 5 23 78OP-9FX01 Refueling Machine Operations 67 Procedures 78TI-9RX01 Spent Fuel Inspection 18 02-EC-MA-0221 AC Distribution 16 13-EC-PB-0202 4160 V Degraded Voltage Relay (DVR) and Loss of Voltage Relay (LoVR) Setpoint & Calibration Calculation 5
13-MC-AF-0309 AF Hydraulic Calculation for Q-Trains 10 71111.24 Calculations EWR 4464093 Evaluate the AF Pump Discharge Piping System for Effects 10/10/2013
18 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 02-E-SFB-0001 Elementary Diagram Reactor Control System CEDM M-G Sets 2J-SFN-C02A and 2J-SFN-C02B 1
02-J-RCE-0A7 Instrument Loop Wiring Diagram Reactor Coolant System 10 02-M-CHP-001 P & I Diagram Chemical and Volume Control System 40 DWG 13-N001-1303-00926 Plant Protection System Schematic Bistable Comp card 6
Drawings DWG E-SYS80-411 Plant Protection System Simplified Functional Diagram 2
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 27 13VTD-C628-00051 Cooper Energy Instruction Manual for KSV Turbocharged Diesel Generating Unit for Nuclear Power Plant Emergency Stand-by Service 21 DWG 02-E-PHA-006 Single Line Diagram 480V Class 1E Power System Motor Control Center 2E-PHB-M36, 22 DWG 02-E-SIF-006 Control Wiring Diagram Safety Injection & Shutdown Cooling Sys Safety Injection Tank Iso Valve 2J-SIB-UV-624 3
JN1017-A00022 MG Set Design Verification Test PTVS Unit 2 0
RICT-U2-2024-02 Risk-Informed Completion Time Report for LCO 3.8.4.B.1 12/11/2024 Miscellaneous VTD-E-146-00004 ABB ELECTRO-MECHANICS, INC. OPERATION AND MAINTENANCE INSTRUCTION FOR PLANT PROTECTION SYSTEM 8
01DP-0RS03 Surveillance Test Interval Control 26 30DP-9WP04 Post-Maintenance Testing Development 20 31MT-9SI03 Containment Spray Pump Disassembly and Assembly 27 32MT-9PE01 Cleaning, Inspection, and Testing of the Class 1E Diesel Generator 52 Procedures 32MT-9PK02 Temporary Jumpering of PK Battery Cell 1
19 Inspection Procedure Type Designation Description or Title Revision or Date 32ST-9PK02 92-Day Surveillance Test of Station Batteries 40 32ST-9ZZ03 Surveillance Test Procedure for Class 1E 4160 Volt Bus Undervoltage Protective Relays 25 32ST-9ZZ74 Molded Case Circuit Breaker Surveillance Test 50 36ST-9SA02 ESFAS Train B Subgroup Relay Functional Test 49 36ST-9SA04 ESFAS Train B Subgroup Relay Shutdown Functional Test 29 36ST-9SB02 PPS Bistable Trip Units Functional Test 52 36ST-9SB42 Plant Protection System Bistable and Bistable Relay Response Time Test 39 40OP-9SA01 BOP ESFAS Module Operation 34 40OP-9SF03 CEDM MG Sets Operation 22 73DP-9XI01 Pump and Valve Inservice Testing Program 44 73ST-9CL01 Containment Leakage Type B and C Testing 53 73ST-9DG02 Class 1E Diesel Generator and Integrated Safeguards Test Train B 34 73ST-9DG08 Class 1E Diesel Generator Load Rejection, 24 Hour Rated Load and Hot Start Test Train B 14 73ST-9SI15 Containment Spray Pumps - Comprehensive Test 39 73ST-9XI05 AF Valves - Inservice Test 35 Work Orders 5540863, 5533131, 5540842, 5540884, 5633702, 5546533, 5540879, 5550038, 5544920, 5462268, 5618379, 5363807, 5257972, 5405201, 5540884, 5547913, 5567620, 5540888, 5678487, 5679929 Corrective Action Documents 24-09680 Miscellaneous 2405 Emergency Preparedness - September 4, 2024, Exercise Report 10/22/2024 16DP-0EP23 Emergency Preparedness Drill and Exercise Program Management 19 EP-0900-010 ERO Positions - Emergency Coordinator (STSC) 3 EP-0901 Classifications 17 71114.06 Procedures EP-0902 Notifications 28 71124.01 ALARA Plans 1-3502-R24 00 01 Valve, Flange and Pump Maintenance - ALARA Post-Job Review 02/08/2024
20 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 75DP-0RP01 RP Program Overview 13 75RP-0RP01 Radiological Posting and Labeling 37 75RP-9OP02 Control of High Radiation Areas, Locked High Radiation Areas, and Very High Radiation Areas 34 75RP-9RP02 Radiation Work Permits 32 75RP-9RP07 Radiation and Contamination Surveys 33 75RP-9RP08 Radiological Air Sampling 4
Procedures 75RP-9RP29 Radiological Job Coverage 14 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
21 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 0
2-3006-R25 Medium Risk - In-Core Instrumentation (ICI) and Heated Junction Thermal Couple (HTJC) Maintenance 0
2-3412-R25 Pressurizer (PZR) Heater Cut Out and Replacement 0
2-3501-R25 RP Tours, Inspections and Routine Surveys 0
2-3518-R25 High Risk - Minor Maintenance in the 120' / 127' Regenerative Heat Exchanger Cubicle 0
9-1006 Filter Change Out / Transport / Storage / Packaging 4
Radiation Work Permits (RWPs) 9-1031 Radiation Protection Manager Approved Containment Entries At Power in Modes 1 & 2 0
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 Control Building HVAC P&ID 27 01-M-HJP-002 Control Building HVAC P&ID 18 Drawings AD-A-ZDY-196 Technical Support Center HVAC 10 230822090-01 Compressed Air/Gas Quality Testing 08/22/2023 240228083-00 Compressed Air/Gas Quality Testing 02/29/2024 Miscellaneous 240903027-01 Compressed Air/Gas Quality Testing 09/03/2024 01DP-0IS21 Palo Verde Industrial Health and Safety 7
33ST-9HJ02 Surveillance Testing of the Control Room Nuclear Air Treatment System 22 33TI-9ZY03 NATS Testing - TSC 9
74RM-9EF40 Radiation Monitoring Systems Operations 13 74ST-9SQ21 Radiation Monitoring Calibration Test for Baseline Process Monitors 23 75RP-9RP07 Radiation and Contamination Surveys 33 71124.03 Procedures 75RP-9RP08 Radiological Air Sampling 4
22 Inspection Procedure Type Designation Description or Title Revision or Date WO#5268636 Technical Support Center NATS 01/19/2022 WO#5350006 Unit-1 Train-B Control Room Intake Air Monitor (RU-30) 04/18/2023 WO#5365428 Unit-2 Train-B Control Room Intake Air Monitor (RU-30) 11/15/2022 WO#5369065 HEPA Test, Unit-3 Control Room HVAC 12/01/2022 WO#5397633 HEPA Test, Unit-3 Control Room HVAC 03/07/2023 WO#5400077 Unit-2 Control Room Essential Air Filtering Unit-A 03/28/2023 WO#5421250 Technical Support Center NATS 09/28/2023 WO#5468444 TSC Vent Radiation Monitor (RU-13A) 11/29/2023 WO#5510848 HEPA Test, Unit-3 Control Room HVAC 07/09/2024 WO#5517502 Unit-3 Train-B Control Room Intake Air Monitor (RU-30) 06/24/2024 Work Orders WO#5540561 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 2023 ARERR 2023 Annual Radioactive Effluent Release Report 04/17/2024 Miscellaneous 202408 Radiation Protection Indicator Analysis Detail 09/11/2024 40DP-9LC01 Performance Indicator - Barrier Integrity Cornerstone: RCS Leak Rate 4
74DP-0LC01 RCS Activity Performance Indicator 8
74ST-9RC02 Reactor Coolant System Specific Activity Surveillance Test 17 75RP-0LC01 Performance Indicator Occupational Radiation Safety Cornerstone 5
75RP-0LC02 Performance Indicator Public Radiation Safety Cornerstone 5
Procedures 93DP-0LC09 NRC ROP PI Data Collection, Verification and Submittal 12 71151 Work Orders 5487583, 5496303, 5524189 71152A Corrective Action Documents 23-06802, 24-01963, 24-08552, 24-09241, 24-12985, 16-02625, 24-10633, 24-10825, 24-10873, 24-10876, 24-10904, 24-11072, 24-11093, 24-11411, 24-12065, 24-12093, 24-11072, 24-12825, 24-10873
23 Inspection Procedure Type Designation Description or Title Revision or Date EN#56958, Part 21 - Interim Report for Oil Filled Capacitors 02/09/2024 Part 21 NRC Event 56958 PVGS Applicability Review 02/29/2024 Adverse Condition Monitoring Plan for RCP [1B] Common Trouble for Motor Lower Oil Reservoir Oil Level Low 0
Adverse Condition Monitoring Plan for RCP [1B] Common Trouble for Motor Lower Oil Reservoir Oil Level Low 1
Adverse Condition Monitoring Plan for RCP [2B] Common Trouble for Motor Lower Oil Reservoir Oil Level Low 0
Miscellaneous Adverse Condition Monitoring Plan for RCP [2B] Common Trouble for Motor Lower Oil Reservoir Oil Level Low 1
01DP-0AP12 Condition Reporting Process 48 01DP-0ZZ01 Operational Decision Making 8
65DP-0QQ01 Industry Operating Experience Review 45 Procedures 93DP-0LC18 Part 21 Reporting Process 4
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 01DP-0AP12 Condition Reporting Process 48 01DP-0AP59-06 Human Performance Event Evaluation 5
40DP-9OP02 Conduct of Operations 79 40DP-9OP38 Operations Technical Documents 18 40OP-9DG02 Emergency Diesel Generator B 81 40OP-9SA02 De-energization of BOP ESFAS 26 40ST-9ZZ24 Boron Dilution Alarm System Inoperable 17 74DP-9CY10 Conduct of Chemistry 15 71152S Procedures 74OP-9SS01 Primary Sampling Instructions 57