IR 05000528/2024002
| ML24206A051 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 07/29/2024 |
| From: | John Dixon NRC/RGN-IV/DORS/PBD |
| To: | Heflin A Arizona Public Service Co |
| References | |
| IR 2024002 | |
| Download: ML24206A051 (1) | |
Text
July 29, 2024
SUBJECT:
PALO VERDE NUCLEAR GENERATING STATION - INTEGRATED INSPECTION REPORT 05000528/2024002 AND 05000529/2024002 AND 05000530/2024002
Dear Adam Heflin:
On June 30, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Palo Verde Nuclear Generating Station. On July 9, 2024, the NRC inspectors discussed the results of this inspection with Todd Horton, Senior Vice President, Nuclear Regulatory and Oversight, 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 07/26/24 Docket Nos. 05000528, 05000529, 05000530 License Nos. NPF-41, NPF-51, NPF-74
Enclosure:
As stated
Inspection Report
Docket Nos.
05000528, 05000529, 05000530 License Nos.
NPF-41, NPF-51, NPF-74 Report Nos.
05000528/2024002, 05000529/2024002, 05000530/2024002 Enterprise Identifier:
I-2024-002-0006 Licensee:
Arizona Public Service Facility:
Palo Verde Nuclear Generating Station Location:
Tonopah, AZ Inspection Dates:
April 1, 2024, to June 30, 2024 Inspectors:
L. Merker, Senior Resident Inspector N. Cuevas, Acting Senior Resident Inspector E. Lantz, Resident Inspector R. Kopriva, Senior Project Engineer P. Nwafor, Project Engineer J. Mejia, Reactor 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
Type Issue Number Title Report Section Status LER 05000528/2023-003-00 LER 2023-003-00 for Palo Verde Nuclear Generating Station, Unit 1, Control Room Essential Filtration Actuation Signal (CREFAS)
Actuation with Essential Spray Pond Pump Start 71153 Closed
PLANT STATUS
Units 1 and 2 operated at or near full power for the duration of the inspection period.
Unit 3 entered the inspection period at approximately 94 percent power during a coastdown for refueling outage 3R24. On April 6, 2024, the unit was shut down for refueling outage 3R24. On May 11, 2024, the reactor was made critical following completion of the refueling outage and returned to full power on May 15, 2024, where it remained for the remainder of the inspection period.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors performed activities described in IMC 2515, Appendix D, Plant Status, observed risk significant activities, and completed on-site portions of IPs. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
REACTOR SAFETY
71111.01 - 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 high temperatures for Units 1, 2, and 3, essential spray pond train A and B and offsite AC power systems, on May 24, 2024.
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Unit 3, safety injection and shutdown cooling train B following shutdown cooling initiation, on April 12, 2024
- (2) Unit 3, safety injection and shutdown cooling train A in gravity feed alignment during lowered inventory, on April 12, 2024
- (3) Unit 2, essential cooling water train A during essential cooling water train B maintenance outage, on June 11, 2024
- (4) Unit 1, turbine-driven auxiliary feedwater system train A, on June 27, 2024
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations during a complete walkdown of the Unit 3 fuel pool cooling and cleanup train B, on May 7, 2024.
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:
- (1) Unit 3, main control room, fire zone 17, on April 10, 2024
- (2) Unit 3, containment building 100-foot elevation, fire zones 66A, 66B, 67A, and 67B, on April 16, 2024
- (3) Unit 3, control building air handling room train A, fire zone 1, on June 21, 2024
- (4) Unit 2, upper cable spreading room, fire zone 20, on June 28, 2024
Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the onsite fire department training and performance during unannounced fire drills, on February 29, 2024, and March 15, 2024.
71111.07A - Heat Exchanger/Sink Performance
Annual Review (IP Section 03.01) (1 Sample)
The inspectors evaluated readiness and performance of:
- (1) Unit 3, essential cooling water train A heat exchanger, on April 29, 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 are appropriately monitored for degradation and that repairs and replacements were appropriately fabricated, examined, and accepted by reviewing the following activities in Unit 3 during refueling outage 3R24 from April 8-18, 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 downcomer feedwater, weld 60-17, pipe to penetration
- Steam generator downcomer feedwater, weld 60-16, valve to pipe
- Steam generator downcomer feedwater, weld 60-15, pipe to valve
- Steam generator downcomer feedwater, weld 60-7, pipe to elbow
- Steam generator downcomer feedwater, weld 60-14, valve to pipe
- Reactor coolant dissimilar metal weld, 1B spray 11-11, vessel to spray Dye Penetrant Examination
- Safety injection, SI-70 H2
- Safety injection, SI-89 H1 Visual 3 Examination
- Safety injection, SI-70 H2
- Safety injection, SI-89 H1
- Safety injection, SI-90 H4 Welding Activities
Charging system, 5333988 replace CHN-V813 o
Pressurizer auxiliary spray system, 5481755 weld replace obsolete Dresser valve CHE-VM36 with a 1-inch 1500 lb Kerotest model ARZ D-21508G-(2)o Pressurizer auxiliary spray system, 5482012 weld replace obsolete Dresser valve CHE-V045 with a 1-inch 1500 lb Kerotest model ARZ D-
===21508G-(2).
PWR Inservice Inspection Activities Sample - Vessel Upper Head Penetration Inspection Activities (IP Section 03.02)===
The inspectors verified that the license conducted the following vessel upper head penetration inspections and addressed any identified defects appropriately:
- (1) Reactor pressure vessel head penetrations: 01, 08, 10, 22, 25, 32, 39, 56, 67, and 72 PWR Inservice Inspection Activities Sample - Boric Acid Corrosion Control Inspection Activities (IP Section 03.03) (1 Sample)
The inspectors verified the licensee is managing the boric acid corrosion control program through a review of the following evaluations:
- (1) CR 23-06248-002 3JCHNUV0510**valve Body to bonnet 04/16/2024 CR 22-12122-002 3JRCNPT0181**ixmitr plug 04/16/2024 CR 23-07529-002 3MCHNP05A**pump seal 04/16/2024 CR 23-01062-003 3MPCBE01**htexch body to bonnet 04/16/2024 CR 22-10525-002 3MRCEP01B**pump 04/16/2024 CR 23-10229-002 3MSIAP02**pump seal 04/16/2024 CR 22-10122-002 3MSIAP03**valve 04/16/2024 CR 22-09957-003 3MSIBP03**pump 04/16/2024 CR 22-10523-002 3PCHEVM36**valve pipe cap 04/16/2024 CR 23-01072-003 3PCHNV126**valve 04/16/2024 CR 22-12418-003 3PCHNV164 04/16/2024 CR 22-09882-002 3PCHNV788**valve packing 04/16/2024 CR 22-09878 3PCHNV809**valve packing 04/16/2024 CR 22-11748-003 3PCHNV813**valve packing 04/16/2024 CR 23-01480-002 3PCHNV985**valve flange 04/16/2024 PWR Inservice Inspection Activities Sample - Steam Generator Tube Inspection Activities (Section 03.04) (1 Sample)
The inspectors verified that the licensee is monitoring the steam generator tube integrity appropriately through a review of the following examinations:
- (1) One hundred percent of the tubes in SG31 and SG32 were inspected using bobbin probe. Additional eddy current inspections using specialized probes, such as the
+Point Probe and/or X Probe, were used to address areas where the bobbin probe flaw detection capabilities are limited, such as at local geometric disturbances. No steam generator tubes were subject to in-situ pressure testing.
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 control room during the Unit 3 response following the declaration of an unusual event due to receipt of a fire alarm in containment, on April 6, 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 May 23, 2024.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (3 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 2, essential chiller train B, on May 6, 2024
- (2) Unit 1, pressurizer vent valve to reactor drain tank, RCA-HV-103, on May 29, 2024
- (3) Unit 2, emergency diesel generator train B, on June 28, 2024
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, metal bellows pump and motor assembly for the radiation monitoring system, on April 26, 2024
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (8 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 2, emergent work on engineered safety features transformer, NBN-X04, and risk informed completion time entry, on April 3, 2024
- (2) Unit 1, emergent containment entry at power and troubleshooting of safety injection tank 1A lowering pressure trend, on May 9, 2024
- (3) Unit 2, planned supplementary protection system functional testing, on May 17, 2024
- (4) Unit 1, planned main turbine control valves, stop valves, and combined intermediate valves testing, on May 20, 2024
- (5) Unit 3, emergent main turbine control valve testing due to increasing thrust bearing rear plate metal temperatures, on May 21, 2024
- (6) Unit 2, planned main turbine generator over excited and under excited testing, on May 22, 2024
- (7) Unit 2, emergent replacement of the main turbine control oil train B main filter, on May 23, 2024
- (8) Unit 2, planned maintenance on emergency diesel generator train B, on June 13, 2024
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (4 Samples)
The inspectors evaluated the licensees justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Units 1, 2, and 3, safety injection tank pressure relief valves operability determination due to missing blowdown thrust load in pipe stress calculations, on April 2, 2024
- (2) Units 1, 2, and 3, class 1E 125 Vdc batteries operability determination due to sediment buildup, on April 5, 2024
- (3) Unit 3 class 1E 125 Vdc batteries operability determination due to low recorded voltage during service discharge testing, on June 25, 2024
- (4) Unit 2, emergency diesel generator train B operability determination for a high priority trip due to testing the diesel beyond 110 percent full load capacity, on June 26, 2024
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (2 Samples)
The inspectors evaluated the following temporary or permanent modifications:
- (1) Unit 1, permanent modification to upgrade the motor generator sets with new equipment to address component obsolescence, minimize maintenance, reduce system induced noise and harmonics, and improve overall system reliability, on May 20, 2024
- (2) Unit 3, permanent modification to enhance the main turbine sequential trip logic by zeroing VARs upon a turbine trip via the excitation system and providing a transfer to offsite power upon verification of main turbine stop or control valves and intercepts/intermediate stop valves are closed, on June 14, 2024
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated the Unit 3 refueling outage 3R24 activities from April 6 through May 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) (8 Samples)
- (1) Unit 3, high-pressure safety injection pump train A post-maintenance testing following mechanical seal replacement, on April 30, 2024
- (2) Unit 3, low-pressure safety injection pump train B suction valve, SI-HV-683, post-maintenance testing following body to bonnet gasket replacement, on April 30, 2024
- (3) Unit 3, containment spray pump train A post-maintenance testing following pump mechanical seal, lower casing wear ring, motor, and impeller replacements, on May 7, 2024
- (4) Unit 3, balance of plant-engineered safety features actuation system train B post-maintenance testing following fuel building essential ventilation actuation signal, control room essential filtration actuation signal, and load sequencer module and switch replacement, on May 9, 2024
- (5) Unit 3, low-pressure and high-pressure safety system injection discharge check valve, SI-EV-540, and safety injection tank 2A discharge check valve, SI-EV-217, post-maintenance testing following valve maintenance and replacement on May 17, 2024
- (6) Unit 3, main feedwater isolation valve, SGA-UV-177, post-maintenance testing following actuator replacement, on May 24, 2024
- (7) Unit 3, main steam isolation valve, SGE-UV-171, post-maintenance testing following actuator replacement, on May 24, 2024
- (8) Unit 3, turbine sequential trip logic post-maintenance testing following installation of a permanent modification, on June 14, 2024
Surveillance Testing (IP Section 03.01) (3 Samples)
- (1) Unit 3, emergency diesel generator A and integrated safeguards train A testing, on April 15, 2024
- (2) Unit 3, control element assembly reed switch position transmitter functional testing, on May 20, 2024
- (3) Unit 3, engineered safety features actuation system train B subgroup relay functional testing, on May 28, 2024
Inservice Testing (IST) (IP Section 03.01) (1 Sample)
- (1) Unit 1, turbine-driven auxiliary feedwater system A inservice testing, on June 25, 2024
Containment Isolation Valve (CIV) Testing (IP Section 03.01) (1 Sample)
- (1) Unit 3, chemical and volume control system letdown into regenerative heat exchanger containment isolation valve, CHA-UV-516, and letdown containment isolation valve, CHB-UV-523, testing, on April 29, 2024
71114.06 - Drill Evaluation
Required Emergency Preparedness Drill (1 Sample)
- (1) The inspectors evaluated an emergency preparedness drill, on March 5,
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04)===
- (1) Unit 1 (April 1, 2023, through March 31, 2024)
- (2) Unit 2 (April 1, 2023, through March 31, 2024)
- (3) Unit 3 (April 1, 2023, through March 31, 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) Unit 1, use of 10 CFR 50.69 alternative treatment to replace condensate storage tank pressure relief and vacuum breather valves, CTN-PSV-008 and CTN-PSV-023, on June 5, 2024
71153 - Follow Up of Events and Notices of Enforcement Discretion Event Follow up (IP Section 03.01)
- (1) The inspectors evaluated the licensees response to the Unit 3 unusual event declaration, based on emergency action level HU4.2, for the receipt of a single fire alarm in containment that could not be verified within 30 minutes of the alarm on April 4, 2024. The licensee subsequently entered containment and verified that no fire existed.
Event Report (IP Section 03.02) (1 Sample)
- (1) LER 05000528/2023-003-00, Unit 1 Control Room Essential Filtration Actuation Signal (CREFAS) Actuation with Essential Spray Pond Pump Start (ADAMS accession: ML24032A443). The inspection conclusions associated with this LER are documented in this report under Inspection Results section 71153. This LER is closed.
INSPECTION RESULTS
Minor Violation 71153 Failure to Identify and Correct a Condition Adverse to Quality for Train A Control Room Ventilation Intake Monitor Minor Violation: The control room ventilation intake monitors SQA-RU-29 and SQB-RU-30 are redundant train radiation monitors that monitor the control room air intake for radioactive gas concentrations. If an increase above established high-high setpoints is detected, a signal is sent to the balance of plant engineered safety features actuation system (BOP-ESFAS) to initiate a control room essential filtration actuation signal (CREFAS) ensuring a controlled environment in the control room to protect operators from exposure to increased radiation levels during potential accidents.
From January 31 through December 6, 2023, operators in the control room noted five instances where RU-29 exhibited signal spiking of varying amplitudes. On March 22, 2023, maintenance personnel requested permission from the control room to commence troubleshooting and repairs on RU-29, but the work was not approved by control room staff over concerns of placing RU-29 out of service due to ongoing issues with RU-30. The licensee considered the work order to troubleshoot and repair RU-29 low priority and rescheduled it to the next available work window 487 days later. On December 6, 2023, a large signal spike occurred that exceeded RU-29s high alert setpoint, resulting in a valid actuation of the CREFAS system and the start of both trains of essential spray pond pumps.
Licensee troubleshooting identified that the power supply for RU-29 exhibited increased voltages above acceptance criteria, a ruptured capacitor, and heat related discoloration on the control board.
Screening: The failure to correct spurious signal spiking on RU-29, train A control room intake air monitor, in a timely manner was a performance deficiency. Specifically, the licensee delayed performance of troubleshooting and repairs for spurious signal spiking on RU-29, which resulted in an actuation of CREFAS and a valid start of the train A essential spray pump.
The performance deficiency was minor because it could not be reasonably viewed as a precursor to a significant event; would not have the potential to lead to a more significant safety concern if left uncorrected; and while it was associated with the Human Performance attribute of the Barrier Integrity Cornerstone, it did not adversely affect the cornerstone objective to provide reasonable assurance that physical design barriers maintain functionality of control room to protect the public from radionuclide releases caused by accidents or events. Specifically, the licensees failure to correct the spurious signal spiking in RU-29 resulted in the actuation of CREFAS, placing the control room in the alignment required during an accident or event.
Title 10 CFR 50 Appendix B, Criterion XVI, Corrective Action states, in part, measures shall be established to assure that conditions adverse to quality, such as failures, malfunctions, deficiencies, deviations, defective material and equipment, and nonconformances are promptly identified and corrected. Contrary to the above, from January 31 through December 6, 2023, the licensee failed to ensure that a condition adverse to quality such as failures malfunctions and defective material and equipment were promptly identified and corrected. Specifically, with RU-29 exhibiting sporadic spiking in the detector output, the licensee failed to perform troubleshooting to identify and correct the condition promptly, resulting in the detector output spiking above the high alarm setpoint and subsequent CREFAS actuation when the conditions were not present to require one.
Enforcement:
This failure to comply with 10 CFR 50 Appendix B, Criterion XVI constitutes a minor violation that is not subject to enforcement action in accordance with the NRCs enforcement policy. The licensee entered this issue into the corrective action program under Condition Report 23-12746.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On April 18, 2024, the inspectors presented the Palo Verde Unit 3 inservice inspection results to Rex Meeden, Vice President, Nuclear Engineering, and other members of the licensee staff.
- On July 9, 2024, the inspectors presented the integrated inspection results to Todd Horton, Senior 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
13-MC-SP-0307
SP/EW System Thermal Performance Design Bases
Analysis
Corrective Action
Documents
20-14449, 23-00021
Miscellaneous
PVNGS DBM - Essential Spray Pond System
Miscellaneous
PV System Health Report - Essential Cooling Water Units 1,
2, and 3
05/24/2024
Miscellaneous
PV System Health Report - Essential Spray Pond Units 1, 2,
and 3
05/24/2024
Miscellaneous
PV System Health Report - Non-class 1E 13.8kV Power
Units 1, 2, and 3
05/24/2024
Procedures
Infrared Thermography Inspection of Plant Components
Procedures
Acts of Nature
Procedures
Switchyard Administrative Control
Procedures
Hot Weather Protection
Procedures
Summer Readiness Administrative Guideline
Work Orders
5512862, 5527103, 5307945, 5500846
Corrective Action
Documents
16-15303, 17-03343, 17-12194, 18-07873, 18-08186, 19-
00315, 20-11800, 20-11801, 20-11821, 20-11796, 20-
13661, 23-08974, 24-00179, 24-04919, 24-04946, 17-
15096, 20-05422,
20-05393
Drawings
01-M-AFP-001
P & I Diagram Auxiliary Feedwater System
Drawings
2-M-EWP-001
P & I Diagram Essential Cooling Water System
Drawings
03-M-CHP-002
P & I Chemical and Volume Control System
Drawings
03-M-NCP-002
P & I Diagram Nuclear Cooling Water System
Drawings
03-M-PCP-001
P & I Diagram Fuel Pool Cooling & Cleanup System
Drawings
03-M-RCP-001
P & I Diagram Reactor Cooling System
Drawings
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
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
CFR 50.69 System Categorization Fuel Pool Cooling &
Cleanup System (PC)
Miscellaneous
PVNGS Design Basis Manual - Fuel pool cooling and
Cleanup system
Procedures
Lower Mode Functional Recovery
Procedures
Essential Auxiliary Feedwater System (AF) Train A
Procedures
Essential Cooling Water System (EW) Train A
Procedures
P & I Diagram Reactor Cooling System
Procedures
Outage GOP
Calculations
13-MC-FP-0803
Combustible Loads - Control Building
Calculations
13-MC-FP-0803
Combustible Loads - Control Building
Calculations
13-MC-FP-0805
Combustible Loads - Containment Building
Corrective Action
Documents
24-03551, 24-01972, 24-00643, 23-08826, 24-05786, 24-
04943, 24-04945
Drawings
03-E-QKF-001
Control Wiring Diagram Fire and Smoke Detection Control
Panel 3J-QKN-E04D System D Control BLDG EL 140 FT
Drawings
13-A-ZYD-029
Fire Protection Control Building Floor Plan At Elevation 140
-0, Level 3
Fire Plans
Pre-Fire Strategies Manual
Miscellaneous
FSCCR 5628572
Miscellaneous
FSCCR 5623529
Miscellaneous
FSCCR 5615990
Miscellaneous
5602936
Transient Combustible Control Permit
2/23/2024
Miscellaneous
5602938
Transient Combustible Control Permit
2/23/2024
Miscellaneous
5602941
Transient Combustible Control Permit
2/23/2024
Miscellaneous
5602947
Transient Combustible Control Permit
2/23/2024
Miscellaneous
5606441
Transient Combustible Control Permit
03/06/2024
Miscellaneous
5612226
Transient Combustible Control Permit
03/28/2024
Miscellaneous
5613630
Transient Combustible Control Permit
04/02/2024
Miscellaneous
5613646
Transient Combustible Control Permit
04/02/2024
Miscellaneous
5615431
Transient Combustible Control Permit
04/07/2024
Miscellaneous
NPL41-D-1Q2B-
Palo Verde Nuclear Fire Department Fire Drill: Unit 2 B
Shift Unannounced Fire Drill Scenario Packet
2/27/2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
NPL41-D-1Q2B-
Palo Verde Nuclear Fire Department Fire Drill: Unit 2 B
Shift Backshift/Unannounced Fire Drill After Action Review
Summary
05/01/2024
Miscellaneous
NPL41-D-1Q3C-
Palo Verde Nuclear Fire Department Fire Drill: Unit 1 C
Shift Unannounced Fire Drill After Action Review Summary
03/15/2024
Procedures
Emergency Notification and Response
Procedures
Control of Transient Combustibles
Procedures
Operational Considerations Due to Plant Fire
Calculations
13-MC-SP-0307
[Spray Pond]/[Essential Cooling Water] System Thermal
Performance Design Bases Analysis
Corrective Action
Documents
2-01887, 24-04073, 24-04074, 24-04125
Drawings
13-M071-0046
Tube Layout for Essential Cooling Water Heat Exchanger
Miscellaneous
Essential Cooling Water Heat Exchanger (3MEWAE01)
Thermal Performance Test Report
Miscellaneous
MR 2.0 - Performance Monitoring Bases Document
Worksheet: Essential Cooling Water System
Procedures
Tube Plugging of the Essential Cooling Water Heat
Exchanger
Procedures
Essential Cooling Water System (EW) Train A
Procedures
Guidelines for Heat Exchanger Thermal Performance
Analysis
Procedures
Heat Exchanger Program
Procedures
Heat Exchanger Visual Inspection
Procedures
Eddy Current Examination of Tubing
Work Orders
29769, 5357185, 5502134, 5501558
Corrective Action
Documents
21-02087, 22-00913, 22-09880, 22-09882, 22-09887, 22-
09889, 22-09890, 22-09894, 22-10519, 22-10520, 22-
10525, 22-11637, 23-01480, 23-06258, 23-09848, 23-
229, 23-10882, 23-11369, 23-12650, 24-01908, 24-
03508, 24-03575, 24-03458, 24-0364524-04007, 24-04096
Corrective Action
Documents
Resulting from
24-03583, 24-03775, 24-04030, 24-04031, 24-04032, 24-
04042, 24-04043, 24-04044, 24-04045, 24-04067, 24-04079
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Inspection
Miscellaneous
4th Inspection Interval Inservice Inspection Program
Summary Manual PVGS Unit 3
Miscellaneous
LTR-SGMP-14-64 Foreign Object Prioritization Strategy for the Palo Verde
Replacement Steam Generators in Accordance with the
EPRI Loose Part Handbook Methods
09/26/2014
Miscellaneous
SWMS # 20-
04621-002
Alloy 600
07/23/2020
Procedures
Condition Reporting Process
Procedures
Self-Assessment and Benchmarking Administrative
Guideline
Procedures
Mechanical Snubber Removal and Reinstallation
Procedures
Boric Acid Walkdown Leak Detection
Procedures
Boric Acid Walkdown Leak Detection
Procedures
Welder and Procedure Qualification
Procedures
Welding and Brazing Control
Procedures
Weld Filler Material Control
Procedures
Boric Acid Corrosion Control Program
Procedures
Snubber Visual Examination
Procedures
Mechanical Snubber Function Test
Procedures
Bare Metal Visual Examination of Reactor Vessel Upper
Head
Procedures
Liquid Penetrant Examination
Procedures
Ultrasonic Examination of Welds in Ferritic Components
Procedures
Visual Examination of Welds, Bolting, and Components
Procedures
Visual Examination of Component Supports
Procedures
Visual Examination of Pump and Valve Internal Surfaces
Procedures
Visual Examination For Leakage
Procedures
Visual Examination of Metal Containment Building Surfaces
Procedures
MN755-A00005
SI-UT-218
Procedures
MN755-A00005
SI-UT-218, Procedure For Encoded Phased Array Ultrasonic
Examination Of Dissimilar Metal Piping Welds EPRI-END-
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
DMW-PA-1
Procedures
MN756-A00001
PDI-UT-1 PDI Generic Procedure for the Ultrasonic
Examination of Ferritic Pipe Welds
G
Procedures
MN756-A00001
PDI Generic Procedure for the Ultrasonic Examination of
Ferritic Pipe Welds, PDI-UT-1
Procedures
MN756-A00002
PDI Generic Procedure for the Ultrasonic Examination of
Austenitic Pipe Welds PDI-UT-2
Procedures
MN756-A00003
PDI-UT-5 PDI Generic Procedure for the Straight Beam
Ultrasonic Examination of Bolts and Studs, PDI-UT-5
Procedures
MN756-A00011
PDI-UT-3 PDI Generic Procedure for the Ultrasonic
Through-Wall Sizing of Planar Flaws in Similar Metal Piping
Work Orders
5617651, 5344420, 5618249, 5618251, 5158836, 5510452,
5502840, 5502997
Corrective Action
Documents
24-03314, 24-03316, 24-04124, 24-04557
Fire Plans
Pre-fire Strategies Manual
Fire Plans
EAL Classification Matrix: All Conditions
C
Fire Plans
FSCCR 5614824
Nonfunctional TRM Detection: 3JQKNE14D fire point
367AFR01
04/04/2024
Miscellaneous
NLR24S030102
Main Generator Malfunctions
05/17/2024
Miscellaneous
NLR24S030401
Station Blackout
05/17/2024
Procedures
Emergency Notification and Response
Procedures
Procedures
Load Rejection
Procedures
Degraded Electrical Power
Procedures
Conduct of Operations
Procedures
Conduct of Operations
Procedures
Containment Entry in Mode 1 Through Mode 4
Procedures
Operational Considerations due to Fire
Procedures
Blackout
Procedures
ERO Positions - Emergency Coordinator (STSC)
Procedures
Classifications
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
Notifications
Procedures
Termination and Recovery
Calculations
13-EC-PB-0203
Motor Starting Times
Corrective Action
Documents
19-06357, 19-06968, 19-13869, 24-04399, 24-04403, 23-
257, 24-01568, 24-02530, 24-04151, 24-04153, 24-
04488, 23-11758, 23-11767, 23-11775, 23-11865, 23-
11882, 24-06380, 24-06336, 24-06353, 24-06348, 24-
06338, 24-06340, 24-06341, 24-06384
Miscellaneous
MR 2.0 Performance Monitoring Bases Document
Worksheet - Essential Chilled Water
Miscellaneous
13-EN-0306
Installation Specification for Cable Splicing and Terminations
for the Palo Verde Generating Station Units 1, 2 and 3
Quality Class Q, QAG and NQR
Miscellaneous
13-M018-00720
Overspeed Shutdown Butterfly Valve
Miscellaneous
13-NS-E022
System RC PRA Component to Basic Event Mapping for
10CFR50.69 Risk Assessment
Miscellaneous
13-NS-E023
System RC Shutdown Safety Assessment for 10CFR50.69
Miscellaneous
13-VTD-C150-
0002
Carrier Instruction Manual for Centrifugal Refrigeration
Machine
Miscellaneous
13-VTD-C628-
00045
Cooper Energy Services Engineering Standard Tightening of
Threaded Fasteners and Use of Torque Wrench
Accessories
Miscellaneous
00051
Cooper Energy Instruction Manual for KSV Turbocharged
Diesel Generating Unit for Nuclear Power Plant Emergency
Stand-by Service
Miscellaneous
5069-RC-01
CFR 50.69 System Categorization Reactor Coolant
System (RC)
Miscellaneous
AT-RC-00001
50.69 Alternative Treatment Plan to Remove Reactor Vessel
Head Vent Valves to Reactor Drain Tank RCA-HV-101 and
RCB-HV-102, Pressurizer Vent Valves to Reactor Drain
Tank RCA-HV-103 and RCB-HV-105, and Pressurizer Vent
Valve to Containment, RCA-HV-106, (All Units)
Miscellaneous
M723-00224
Seismic Category I Analysis for Centrifugal Liquid Chiller
Miscellaneous
MEE-01131
Item Type Technical Evaluation for Metal Bellows Pump
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
VTD-T020-00052
Target Rock Project Technical Manual for High
Temperature, High Pressure, Single Pilot, Bolted Bonnet
Solenoid Operated Valve (PUB. #TM 110-111)
Procedures
CFR 50.69 Program
Procedures
CFR 50.69 Active Component Categorization from
Qualitative Assessment and Defense-In-Depth
Procedures
CFR 50.69 Active Component Categorization from Risk
Hazard Assessments
Procedures
CFR 50.69 Passive Component Categorization
Procedures
CFR 50.69 Alternative Treatment Requirements
Procedures
CFR 50.69 Alternative Treatment Implementation
Administrative Guideline
Procedures
Receipt Inspection
Procedures
Receipt Inspection
Procedures
Cleaning, Inspection, and Testing of the Class 1E Diesel
Generator
Procedures
Essential Chiller
Procedures
Maintenance Rule Monitoring Process
Procedures
Class 1E Diesel Generator Load Rejection, 24 Hour Rated
Load and Hot Start Test Train B
Procedures
Reactor and Pressurizer Vent Valves - Inservice Test
Procedures
Reactor and Pressurizer Vent Valves - Inservice Test
Procedures
Reactor and Pressurizer Vent Valves - Inservice Test
28a
Procedures
Commercial Grade Dedication (CGD) of Parts Process
Procedures
Commercial Grade Dedication (CGD) Process
Work Orders
5579588, 5589281, 5578491, 5621631, 5519396, 5519464,
5519442, 5519388, 5303327
Corrective Action
Documents
24-03022, 24-02828, 24-05445, 24-05641, 24-05580, 24-
05598, 24-03249, 24-05650, 22-06616, 21-07258, 24-
00544, 23-06579, 24-06371
Miscellaneous
Phoenix Risk Monitor Unit 2 - 2413 Schedule Evaluation
03/25/2024
Miscellaneous
Unit 2 Night Order for RICT for LCO 3.8.1 A
03/27/2024
Miscellaneous
Risk Management and Readiness Plan: Main Turbine
Quarterly Control Valve Testing
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
Risk Management and Readiness Plan: Unit 1 SIT 1A
Containment Entry
05/01/2024
Miscellaneous
Level 4 Evaluation Report, Unit 2 Thrust Bearing Deep Dive
KT Analysis Findings
06/22/2022
Miscellaneous
Risk Management and Readiness Plan: Supplementary
Protection System Channel Calibration
Miscellaneous
MR 2.0 Performance Monitoring Bases Document
Worksheet - Reactor Protection System
Miscellaneous
Site Integrated Reis Assessment Work Task 5595750
Miscellaneous
High Risk Activity Mitigation Summary - Work Week 2421
Miscellaneous
Protected Equipment for CONP01B OOS
05/23/2024
Miscellaneous
Protected Equipment for B Train Super outage - A Train
protected
06/08/2024
Miscellaneous
Phoenix Risk Monitor-Work Week Schedule Evaluation
6/10/2024 to 6/16/2024
06/12/2024
Miscellaneous
2-E-SBB-001
Elementary Diagram Reactor Protection System Reactor
Trip Breakers Channel A and B
Miscellaneous
2-E-SBB-002
Elementary Diagram Reactor Protection System Reactor
Trip Breakers Channel C and D
Miscellaneous
2-J-RCE-0A8
Instrument Loop Wiring Diagram Reactor Coolant System
Miscellaneous
2-M-COP-001
P and I Diagram Main Turbine Control Oil System
Miscellaneous
Appendix B Protected Equipment Scheme
03/25/2024
Miscellaneous
RICT-U2-2024-01
Risk Informed Completion Time for 2NBN-X04
03/24/2024
Procedures
Management of Critical Evolutions and Infrequently
Performed Tests or Evolutions
Procedures
Online Integrated Risk
Procedures
Risk Challenge Meetings
Procedures
Configuration Risk Management and Risk-Informed
Completion Time Programs
Procedures
Conduct of Maintenance
Procedures
ESF and Normal Service Transformer Maintenance
Procedures
Supplementary Protection System Functional Test
Procedures
Load Rejection
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
Protected Equipment
Procedures
Operations Department Repetitive Task Program Vol. 2
Tasks GH003 Through SP002
Procedures
Risk Management Actions
Procedures
Calculation of RMAT and RICT
Procedures
Containment Entry in Mode 1 thru Mode 4
Procedures
CVCS Normal Operations
Procedures
Electro-Hydraulic Control System
Procedures
Main Generator and Excitation
Procedures
Procedures
Operation of the Reactor Power Cutback System
Procedures
Operation of the Reactor Regulation System
Work Orders
5611279, 5614917, 5510768, 5595750, 5573225, 5519388,
5435830, 5519396, 5519342, 5519438, 5303327, 5519464,
5519442, 5587181
Calculations
13-EC-PE-122
Diesel Generator Electrical Protection
Calculations
13-MC-GA-0502
Containment Building Isometric Service Gas System High
Pressure Nitrogen
Calculations
C-017002-11
Battery Seismic Qualification and Design Life
Corrective Action
Documents
24-00684, 24-01039, 20-08643, 24-04040, 24-06525
Drawings
01-P-GAF-129
Containment Building Isometric Service Gas System High
Pressure Nitrogen
Drawings
13-M-18-00610
Turbocharger ET2414
Drawings
13-M018-00157
Control Schematic Generator - High Voltage and Regulator
Miscellaneous
PVNGS DBM - Diesel Generator, Class 1E Standby
Generation, Fuel Oil Storage and Transfer System
Miscellaneous
PVNGS DBM - Class 1E 125 VDC Power System
Miscellaneous
EN050B-A00024
Installation Operation and Maintenance Manual for Class 1E
Batteries and Racks
Miscellaneous
VTD-C628-00037
Cooper Energy Services ET-24 Turbocharger for Nuclear
Standby Service
Procedures
31-Day Surveillance Test of Station Batteries
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
Surveillance of Class 1E Station Batteries Service Test
Discharge
Procedures
Class 1E Diesel Generator Load Rejection, 24 Hour Rated
Load and Hot Start Test Train B
Work Orders
5480191, 5496458
Calculations
13-EC-MA-0232
Main Generator Reverse Power Relay Actuation Time
Calculations
JN1036-A00007
APS Palo Verde Motor and Generator Set Sizing Calculation
Corrective Action
Documents
23-10858, 23-11071, 23-12004, 23-12900, 23-03479, 23-
211, 23-12784
Drawings
03-E-MAB-008
Elementary Diagram Main Generation System Generator &
Transformer Primary Protection Unit Tripping
Drawings
03-E-MAD-001
Logic Diagram Generator Tripping
Engineering
Changes
23-03479-030
Engineering
Changes
4542596
Miscellaneous
13-VTD-G080-
0464
General Electric Instruction Manual for Magne-Blast Circuit
Breaker AM-13.8-1000-4H
Miscellaneous
E-21-0003
CFR 50.59 Screening/Evaluation for EC 4542596
Miscellaneous
E-23-0002
50.59 Screening and Evaluation for [Engineering Change]
23-03479-030
Miscellaneous
E-24-0001
50.59 Screening and Evaluation for [Engineering Change]
23-03479-030
Miscellaneous
JN1017-A00020
Unit 1 MG Set Design Validation Test - SMP Phase 2
Miscellaneous
M400-0315-
00826
Excitation System (MB) - Shutdown Mode Field Modification
Instruction
Miscellaneous
M400-0315-
00827
MA-1866 - Design Validation Testing (DVT) of Excitation
Shutdown Mode & Fast Bus Transfer Enhancement
Procedures
Maintenance of AM-13.8-1000-4H GE Magne-Blast Circuit
Breakers
Procedures
Design Change Process
Procedures
Conduct of Modifications
Procedures
Conduct of Modifications
Procedures
CFR 50.59 and 72.48 Screenings and Evaluations
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Work Orders
5359100, 5363801, 5363804, 5502320, 5547294, 5564590,
5564593
Calculations
CENPSD-770
ABB Combustion Engineering Analysis for Lower Mode
Functional Recovery Guidelines
Corrective Action
Documents
23-02564, 24-01320, 24-02923, 24-02924, 24-03239, 24-
03366, 24-03451, 24-03517, 24-03524, 24-03533, 24-
03648, 24-03736, 24-03747, 24-03786, 24-03787, 24-
03821, 24-03847, 24-03849, 24-03750, 24-03751, 24-
03776, 24-04056, 24-04135, 24-04205, 24-04341, 24-
04434, 24-04440, 24-04442, 24-04546, 24-04570, 24-
04618, 24-04621, 24-04654, 24-05151, 24-05221, 24-05231
Miscellaneous
Unit THREE 24th Refueling Outage Shutdown Risk
Assessment Final Report
Miscellaneous
Shutdown Safety Function Assessment Pressurizer Many
On, SDC Entry Conditions Met
04/07/2024
Miscellaneous
TD#301211, Operations Technical Document: Clearance
439963 - 2649 SGEUV171 - Replace & Test the MSIV
3JSGEUV0171 Actuator with Reconditioned Spare
04/09/2024
Miscellaneous
TD#301250, Operations Technical Document: Clearance
439961 - 2646 SGAUV0177 - Replace & Test the FWIV
3JSGAUV0177 Actuator with Reconditioned Spare
04/09/2024
Miscellaneous
Tagging Picture Book
2/08/2024
Miscellaneous
3R24 Outage Summary
04/03/2024
Miscellaneous
13-NS-C113, Additional Heat Sink Quantities for ECCS
Performance Analysis
Miscellaneous
Specific Maneuver Plan: EOC Shutdown 90% to 20% Unit 2
Cycle 24
Miscellaneous
3R24 Refueling Outage Restart [Plant Review Board]
Package
05/03/2024
Miscellaneous
Protected Equipment Scheme: U3R24 Core Offloaded &
Pools Isolated (A Train Work Window),
04/18/2024
Procedures
Managing Personnel Fatigue
Procedures
Fuel Integrity Program Implementing Components
Procedures
Foreign Material Exclusion Controls
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
Open/Close the Containment Equipment Access Hatch and
Missile Shield Doors
Procedures
Refueling Water Level Indicating System Instrumentation
Calibration - Train A
Procedures
Lower Mode Functional Recovery Technical Guideline
Procedures
Lower Mode Functional Recovery Technical Guideline
17a
Procedures
Standard Post Trip Actions
Procedures
Operations Maintenance Activities
Procedures
Fuel Pool Cooling
Procedures
Augmentation of Fuel Pool Cooling with Shutdown Cooling
Procedures
Shutdown Cooling Initiation
Procedures
Plant Startup Mode 2 to Mode 1
Procedures
Power Operations
151
Procedures
Outage GOP
Procedures
RCS and Pressurizer Heatup and Cooldown Rates
Procedures
Containment Cleanliness Inspection
Procedures
Outage Planning and Implementation
Procedures
Shutdown Risk Assessments
Procedures
Shutdown Risk Assessments
64a
Procedures
Core Reloading
Procedures
Calculation of Estimated Critical Condition
Procedures
Shutdown Margin - Modes 3, 4, and 5
Procedures
Refueling Machine Operations
Calculations
13-MC-SI-0220
Containment Spray System Hydraulic Analysis and Pump
Surveillance Testing Requirements
Calculations
13-MC-SI-0250
Safety Injection, Containment Spray, and Shutdown Cooling
System Pump NPSH Evaluations
Corrective Action
Documents
24-03429, 24-03456, 24-03468, 24-03484, 24-03572, 24-
03581, 24-03587, 23-10229, 24-04228, 24-04406, 21-
10456, 24-03906, 24-03908, 24-04014, 24-04220, 24-
277, 24-04319, 24-04428, 24-04499, 24-04506, 24-
04523, 24-04698, 24-04870, 24-05128, 23-08071, 24-
04580, 23-11226, 24-03910, 21-07807, 24-03590, 24-
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
04692, 24-05035, 24-05217, 24-05245, 24-05263, 24-
05303, 24-05304, 24-05310, 24-05501, 24-05696
Drawings
03-E-SGB-023
Elementary Diagram Main Steam System Main Steam
Isolation Valves 3J-SGE-UV-170, UV-171, UV-180 & UV-
181
Drawings
03-E-SGB-044
Elementary Diagram Main Steam System MSIV & FWIV
Hydraulic Oil Reservoir Level Alarm
Drawings
Drawings
Schematic for Anchor/Darling Self-Contained Hydraulic
Actuator
Drawings
N0001-1302-
00153
CEDM Reed Switch Assembly
Miscellaneous
Tagging Picture Book
2/08/2024
Miscellaneous
PVNGS Updated Final Safety Analysis Report
Miscellaneous
PVNGS Design Basis Manual for Auxiliary Feedwater
System
Miscellaneous
01-M-AFP-001
P & I Auxiliary Feedwater System
Miscellaneous
Condition Reporting Process
Miscellaneous
03-E-HAF-004
Control Wiring Diagram HVAC-Auxiliary Building System
Essential Cooling Water Pump Room A Essential ACU
Miscellaneous
03-E-ZZI-0003
Electrical Equipment Database
Miscellaneous
03-M-SIP-001
P & I Diagram Safety Injection and Shutdown Cooling
System
Miscellaneous
03-M-SIP-002
P & I Diagram Safety Injection and Shutdown Cooling
System
Miscellaneous
13-VTD-G080-
0464
General Electric Instruction Manual for Magne-Blast Circuit
Breaker AM-13.8-1000-4H
Miscellaneous
Conduct of Operations
Miscellaneous
Operations Operability Determination Process
Miscellaneous
M400-0315-
00826
Excitation System (MB) - Shutdown Mode Field Modification
Instruction
Miscellaneous
M400-0315-
00827
MA-1866 - Design Validation Testing (DVT) of Excitation
Shutdown Mode & Fast Bus Transfer Enhancement
Miscellaneous
SPEC 13-PN-
Installation Specification for Field Installation of Valve Discs
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
0411
in Motor Operated Borg Warner Gate Valves and Installation
of New Motor Operated Borg Warner Gate Valves
Miscellaneous
TD#301211
Operations Technical Document: Clearance 439963 - 2649
SGEUV171 - Replace & Test the MSIV 3JSGEUV0171
Actuator with Reconditioned Spare
04/09/2024
Miscellaneous
TD#301250
Operations Technical Document: Clearance 439961 - 2646
SGAUV0177 - Replace & Test the FWIV 3JSGAUV0177
Actuator with Reconditioned Spare
04/09/2024
Miscellaneous
VTD-G063-00002
GENERAL ATOMIC SORRENTO DIVISION INSTRUCTION
MANUAL FOR BALANCE OF PLANT ENGINEERED
SAFETY FEATURES ACTUATION SYS BOP ESFAS
Miscellaneous
VTD-I075-00012
Ingersoll-Rand Installation, Operation and Maintenance
Instructions for 8X23WDF Containment Spray Pumps
Procedures
Post-Maintenance Testing Development
Procedures
High Pressure Safety Injection Pump Disassembly,
Examination and Assembly
Procedures
Containment Spray Pump Disassembly and Assembly
Procedures
Borg-Werner 12 inch and 14 inch Check Valve Disassembly
and Assembly
Procedures
Train A integrated Safeguards (ISG) Testing
Procedures
Maintenance of AM-13.8-1000-4H GE Magne-Blast Circuit
Breakers
Procedures
Balance of Plant Engineered Safety Features Actuation
System Functional Test
Procedures
ESFAS Train B Subgroup Relay Functional Testing
Procedures
FBEVAS, CREFAS and CRVIAS 18 Month Functional Test
Procedures
CEA Reed Switch Functional Test
Procedures
Diesel Generator Test Record
Procedures
Essential Auxiliary Feedwater System
Procedures
Essential Auxiliary Feedwater System
71a
Procedures
Procedures
Containment HVAC (HC)
Procedures
Procedures
Shutdown Cooling Initiation
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
Outage GOP
Procedures
ECCS Systems Leak Test
Procedures
Containment Leakage Rate Testing Program
Procedures
Pump and Valve Inservice Testing Program
Procedures
Pump and Valve Inservice Testing Program
Procedures
Motor Operated Valve MOV Program
Procedures
Auxiliary Feedwater A - Inservice Test
Procedures
Auxiliary Feedwater A - Inservice Test
63a
Procedures
Containment Leakage Type B and C Testing
Procedures
Class 1E Diesel Generator and Integrated Safeguards Test
Train A
Procedures
MSIVs - Inservice Test
Procedures
Leak Test of SI/RCS Pressure Isolation Valves
Procedures
Containment Spray Pumps - Comprehensive Pump Test
Procedures
Containment Spray Pumps - Comprehensive Pump Test
38a
Procedures
SI Train A Valves - Inservice Test
Procedures
Economizer FWIVs - Inservice Test
Procedures
HPSI Pump and Check Valve Full Flow Test
Procedures
Check Valve Disassembly, Inspection, and Manual Exercise
Procedures
Conduct of Modifications
Work Orders
5517303
Work Orders
5496474, 5496487, 5496490, 4761541, 5403126, 5496469,
5370365, 5499959, 5496493, 554974, 5487733, 5621826,
5478942, 4513785, 5483066, 5526137, 5502752, 2714402,
5356479, 5496451, 5502186, 5502187, 5496467, 5496529,
5496530, 5498306, 5502320, 5547294, 5564590, 5564593
Corrective Action
Documents
24-02108, 24-02109, 24-02110, 24-20128, 24-02160, 24-
2169, 24-02386
Drawings
01-M-SIP-001
P&I Diagram: Safety Injection & Shutdown Cooling System
Miscellaneous
2401 Dress Rehearsal Drill Report
03/29/2024
Miscellaneous
2402 Emergency Preparedness March 5, 2024, Exercise
Report
04/25/2024
Procedures
Emergency Preparedness Drill and Exercise Program
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Management
Procedures
Excessive RCS Leakage
Procedures
Acts of Nature
Procedures
Power Operations
151
Procedures
Analysis of Seismic Event
Procedures
ERO Positions - Emergency Coordinator (STSC)
Procedures
ERO Positions - Emergency Operations Director (EOF)
Procedures
ERO Positions - NAN Communicator (EOF)
Procedures
ERO Positions - Radiological Assessment Communicator
(EOF)
Procedures
ERO Positions - Reactor Analyst (TSC)
Procedures
Notifications
71151
Miscellaneous
SSFF 1 April 2023 - 31 March 2024 PIC Data
04/24/2024
71151
Procedures
NRC ROP PI Data Collection, Verification and Submittal
71151
Procedures
SSFF Mitigating Systems Performance Indicator
71152A
Calculations
13-MC-CT-0302
[Condensate Storage Tank] Relief Valves
71152A
Corrective Action
Documents
21-00317, 21-04989, 22-03262, 23-10192, 24-02534, 24-
2838
71152A
Drawings
J694-00002
Condensate Storage Tank Breather VLV-PSV-8 & 23
71152A
Drawings
J694-00010
Condensate Storage Tank 94020 Breather Valve 10 RF
Open Vent
71152A
Miscellaneous
5069-CT-01
CFR 50.69 System Categorization Condensate Transfer
& Storage (CT)
71152A
Procedures
Condition Reporting Process
71152A
Procedures
CFR 50.69 Alternative Treatment Requirements
71152A
Procedures
CFR 50.69 Alternative Treatment Implementation
Administrative Guideline
71152A
Procedures
Quality Receiving Checklist Development
71152A
Procedures
IST Program Off-Line Set Pressure Verification
71152A
Procedures
Item Procurement Specification (IPS) Requirements
71152A
Work Orders
5071688, 5071689, 5308895, 5432029, 5557626
Corrective Action
Documents
23-12746, 24-03314, 24-03316, 24-03322, 24-03354, 24-
03363, 24-03915, 24-03916, 24-03918, 24-03991, 24-
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
04124, 24-04557, 24-04903, 24-05284
Drawings
03-E-QKF-001
Control Wiring Diagram: Fire and Smoke Detection System
Fire Detection Control Panel 3J-QKN-E14D System R
Containment Building Sheet 15
Fire Plans
Pre-Fire Strategies Manual
Miscellaneous
Miscellaneous
EAL Classification Matrix: All Conditions
C
Miscellaneous
Event Reporting Manual
Miscellaneous
DEP Actual Event Classification Form
04/04/2024
Miscellaneous
DEP Actual Event Notification Form
04/04/2024
Miscellaneous
Operator Logs: April 4, 2024
Miscellaneous
Emergency Action Logs: April 4, 2024
Miscellaneous
04/04/2024
Miscellaneous
Unit 3 RP Island Logbook
04/04/2024
Miscellaneous
ERO Participant Comment and Critique Forms
Miscellaneous
Initial Emergency Plan Assessment Brief Sheet
04/04/2024
Miscellaneous
Command and Control Transfer Form
04/04/2024
Miscellaneous
PVNGS Design Basis Manual - Engineered Safety Features
Actuation System
Miscellaneous
PVNGS Design Basis Manual - Radiation Monitoring
System
Miscellaneous
PVGS Operator Information Manual
April 2020
Miscellaneous
5069-SQ-01
CFR 50.69 System Categorization Radiation Monitoring
System (SQ)
Miscellaneous
Palo Verde Nuclear Generating Station HU4.2 Fire Alarm in
Containment Event Report (Actual Event)
05/03/2024
Miscellaneous
FSCCR 5614824
Nonfunctional TRM Detection: 3JQKNE14D fire point
367AFR01
04/04/2024
Procedures
CFR 50.69 Alternative Treatment Requirements
Procedures
Emergency Notification and Response
Procedures
Actual Event Investigation
Procedures
Panel B05A Alarm Responses
Procedures
Degraded Electrical Power
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
Loss of Class Instrument Or Control Power
Procedures
Conduct of Operations
Procedures
Containment Entry in Mode 1 Through Mode 4
Procedures
Operational Considerations due to Fire
Procedures
20 Vas Class 1E Instrument Channel A
Procedures
Procedures
Radiation Monitoring System Operations
Procedures
Radiation Monitoring System Alarm Response
Procedures
Actions For Non-Functional Radiation Monitors: Preplanned
Alternate Sampling Program
Procedures
ERO Positions - Emergency Coordinator (STSC)
Procedures
ERO Positions - ENS Communicator (STSC)
Procedures
ERO Positions - Shift Technical Advisor (STSC)
Procedures
ERO Positions - STSC Communicator (STSC)
Procedures
Classifications
Procedures
Notifications
Procedures
Termination and Recovery
Work Orders
5614921