IR 05000528/2021004
| ML22021B651 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 02/07/2022 |
| From: | Ami Agrawal NRC/RGN-IV/DRP |
| To: | Lacal M Arizona Public Service Co |
| References | |
| IR 2021004 | |
| Download: ML22021B651 (42) | |
Text
February 7, 2022
SUBJECT:
PALO VERDE NUCLEAR GENERATING STATION - INTEGRATED INSPECTION REPORT 05000528/2021004, 05000529/2021004, AND 05000530/2021004
Dear Mrs. Lacal:
On December 31, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Palo Verde Nuclear Generating Station. On January 20, 2022, the NRC inspectors discussed the results of this inspection with you and other members of your staff.
The results of this inspection are documented in the enclosed report.
One finding of very low safety significance (Green) is documented in this report. This finding involved a violation of NRC requirements. We are treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2 of the Enforcement Policy.
If you contest the violations or the significance or severity of the violations documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN:
Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region IV; the Director, Office of Enforcement; and the NRC Resident Inspector at Palo Verde Nuclear Generating Station.
If you disagree with a cross-cutting aspect assignment in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region IV; and the NRC Resident Inspector at Palo Verde Nuclear Generating Station. This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, Ami N. Agrawal, Acting Chief Reactor Projects Branch D Division of Reactor Projects Docket Nos. 05000528 and 05000529 and 05000530 License Nos. NPF-41 and NPF-51 andNPF-74
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000528, 05000529 and 05000530
License Numbers:
Report Numbers:
05000528/2021004, 05000529/2021004 and 05000530/2021004
Enterprise Identifier:
I-2021-004-0123
Licensee:
Arizona Public Service Company
Facility:
Palo Verde Nuclear Generating Station
Location:
Tonopah, AZ
Inspection Dates:
October 1, 2021 to December 31, 2021
Inspectors:
L. Merker, Senior Resident Inspector
E. Lantz, Resident Inspector
N. Cuevas, Resident Inspector
J. Drake, Senior Reactor Inspector
N. Greene, Senior Health Physicist
M. Hayes, Operations Engineer
S. Hedger, Sr Emergency Preparedness Inspector
G. Pick, Senior Reactor Inspector
J. O'Donnell, Senior Health Physicist
D. Antonangeli, Health Physicist
J. Lee, Reactor Inspector
Approved By:
Ami N. Agrawal, Acting Chief
Reactor Projects Branch D
Division of Reactor Projects
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Palo Verde Nuclear Generating Station, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information. A licensee-identified non-cited violation is documented in report section: 7115
List of Findings and Violations
Failure to Identify and Correct Exposed Rebar in Steam Generator Pedestals in a Timely Manner Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000529/2021004-01 Open/Closed
[H.8] -
Procedure Adherence 71111.08P The inspectors identified a Green, non-cited violation of 10 CFR Part 50, Appendix B,
Criterion XVI, for the licensees failure to identify an issue associated with the steam generator pedestals in Unit 2 as a condition adverse to quality and correct the condition. Title 10 CFR 50, Appendix B, Criterion XVI, Corrective Actions, requires, in part, that measures shall be established to assure that conditions adverse to quality, such as failures, malfunctions, deficiencies, deviations, defective material and equipment, and nonconformance are promptly identified and corrected.
Additional Tracking Items
None.
PLANT STATUS
Unit 1 operated at or near full power for the duration of the inspection period.
Unit 2 entered the inspection period at approximately 89 percent power during a coastdown for refueling outage 2R23. On October 9, 2021, the unit was shut down for the refueling outage.
On November 10, 2021, the unit reached criticality and returned to full power on November 14, 2021. The unit remained at full power for the remainder of the inspection period.
Unit 3 entered the inspection period at or near full power. On December 6, 2021, the unit automatically tripped on low departure from nucleate boiling ratio as a result of control element assembly calculator penalty factors generated due to a dropped control element assembly during control element assembly manipulations. Unit 3 was restarted on December 9, 2021, and returned to full power on December 11, 2021, 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, conducted routine reviews using IP 71152, Problem Identification and Resolution, 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.
Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the coronavirus (COVID-19), resident and regional inspectors were directed to begin telework and to remotely access licensee information using available technology. During this time, the resident inspectors performed periodic site visits each week, increasing the amount of time on site as local COVID-19 conditions permitted.
As part of their onsite activities, resident inspectors conducted plant status activities as described in IMC 2515, Appendix D; observed risk significant activities; and completed on site portions of IPs. In addition, resident and regional baseline inspections were evaluated to determine if all or a portion of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In some cases, portions of an IP were completed remotely and on site. The inspections documented below met the objectives and requirements for completion of the IP.
REACTOR SAFETY
71111.01 - Adverse Weather Protection
External Flooding Sample (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated readiness to cope with external flooding on December 28, 2021.
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (3 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Unit 2, fuel pool cooling systems A and B, on October 14, 2021
- (2) Unit 1, auxiliary feedwater system B, on November 23, 2021
- (3) Unit 3, control room essential air handling unit system B, on December 15, 2021
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) Unit 2, essential spray pond system B, on December 30, 2021
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:
- (1) Unit 2, upper cable spreading room, Fire Zone 20, on November 16, 2021
- (2) Unit 1, auxiliary feedwater pump rooms A and B, Fire Zones 72 and 73, on November 23, 2021
- (3) Unit 1, main turbine bearings and operating deck, Fire Zones TB9 and TB10, on November 23, 2021
- (4) Unit 3, class 1E 4kV switchgear B, Fire Zone 5B, on December 17, 2021
- (5) Unit 2, class 1E 4kV switchgear A and B, Fire Zones 5A and 5B, on December 22, 2021
Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated fire brigade performance during an annual fire drill on October 5, 2021.
71111.07A - Heat Sink Performance
Annual Review (IP Section 03.01) (2 Samples)
The inspectors evaluated readiness and performance of:
- (1) Unit 2, emergency diesel generator A, lube oil heat exchanger, on October 22, 2021
- (2) Unit 2, emergency diesel generator A, jacket water heat exchanger, on October 22, 2021
71111.08P - Inservice Inspection Activities (PWR) PWR Inservice Inspection Activities Sample (IP Section 03.01)
- (1) The inspectors verified that the reactor coolant system boundary, steam generator tubes, 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 from October 11, 2021 to October 22, 2021:
03.01.a - Nondestructive Examination and Welding Activities.
Ultrasonic Examination:
o Shutdown Cooling Loop 2, Elbow to Pipe Weld 22-5 o
Shutdown Cooling Loop 2, Pipe to Elbow Weld 22-6 o
Shutdown Cooling Loop 2, Elbow to Pipe Weld 22-7 o
Shutdown Cooling Loop 2, Pipe to Pipe Weld 22-31
Dye Penetrate Examination:
o Reactor Coolant System, 2PRCEL096, 2A Drain Line pipe to valve o
Reactor Coolant System, 2PRCEL060, 1A Drain Line pipe to valve
Visual 1 Examination o
Fuel Pool Cooling, Attachment Weld PC-5-H-11-W
Visual 3 Examination:
o Fuel Pool Cooling, Pipe Support PC-5-H-11
Welding:
o Steam Generator 1 Economizer Feedwater Isolation Valve, Weld 5256026-1 o
Steam Generator 1 Economizer Feedwater Isolation Valve, Weld 5256026-2 o
Steam Generator 1 Economizer Feedwater Isolation Valve, Weld 5256026-3 o
Steam Generator 1 Economizer Feedwater Isolation Valve, Weld 5256026-4 03.01.b - Pressurized-Water Reactor Vessel Upper Head Penetration Examination Activities.
The inspectors reviewed or observed visual inspections for the following reactor head penetrations:
o RVCH Penetration 2 to 95.
03.01.c - Pressurized-Water Reactor Boric Acid Corrosion Control Activities.
21-05923, 21-05972, 21-06081, 21-06098, 21-06152, 21-06185, 21-06258, 21-06388, 21-06905, 21-06906, 21-06908, 21-06910, 21-06912, 21-07945, 21-07965, 21-09517, 21-09519, 21-10276, 21-10548, 21-10552, 21-10576 The inspectors reviewed 32 condition reports associated with inservice inspection activities and concluded that NDE/ISI related issues and operating experience are put into the corrective action program system at low levels to ensure conditions and problems are identified. No findings or violations of more than minor significance were identified.
71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance
Requalification Examination Results (IP Section 03.03) (1 Sample)
- (1) The inspectors reviewed and evaluated the licensed operator examination failure rates for the requalification annual operating exam administered on December 8, 2021.
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 following activities:
Units 1 and 3 response following a partial loss of offsite power, on October 20, 2021
Unit 2 containment spray system A surveillance testing, on December 2, 2021
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated licensed operator requalification simulator training activities, on November 17, 2021
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (4 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, troubleshooting and repairs for control element drive mechanism control system, subgroup 13 failure, on October 20, 2021
- (2) Unit 2, essential cooling water pump B breaker failure, on November 12, 2021
- (3) Unit 2, essential chiller system B maintenance during outage, on December 15, 2021
- (4) Unit 3, diverse auxiliary feedwater actuation systems A and B, on December 29, 2021
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (3 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, high risk for emergent replacement of failed power supply to engineered safety features actuation system auxiliary relay cabinet A, on November 17, 2021
- (2) Unit 1, risk assessment for emergent troubleshooting and correcting the cause of a spurious actuation for containment spray actuation signal channel D, on November 18, 2021
- (3) Unit 2, risk assessment for emergent replacement and testing of safety injection tank 2A vent valve reed switch, on November 22, 2021
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (9 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Units 1, 2, and 3, emergency diesel generators A and B operability determinations due to air intercooler bolt torque requirement discrepancies, on October 6, 2021
- (2) Unit 2, safety injection tank 1A operability determination due to nitrogen leakage, on November 11, 2021
- (3) Unit 2, essential spray pond system B operability determination after gasket replacement and water hammer event, on November 12, 2021
- (4) Unit 1, auxiliary feedwater systems A and B operability determinations after void discovery in flow transmitter lines, on December 1, 2021
- (5) Unit 2, motor driven auxiliary feedwater pump operability determination after high outboard horizontal bearing vibrations, on December 1, 2021
- (6) Unit 3, safety injection tank 2A fill and drain valve SIB-UV-611 operability determination for valve stroking closed outside of ASME OM Code reference range, on December 13, 2021
- (7) Unit 3, essential chiller B operability determination for low refrigerant level, on December 16, 2021
- (8) Unit 2, containment spray system B suction header valve SIB-V104 operability determination due to a reach rod failure during a surveillance test, on December 28, 2021
- (9) Unit 2, containment sump operability determination for unqualified coating on replacement containment evacuation speakers, on December 28, 2021
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (1 Sample)
The inspectors evaluated the following temporary or permanent modifications:
- (1) Unit 2, permanent modification 21-11851-004 to remove the regenerative heat exchanger shell vent valves and sight glass, on October 27, 2021
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (8 Samples)
The inspectors evaluated the following post-maintenance test activities to verify system operability and functionality:
- (1) Unit 2, emergency diesel generator A following maintenance outage, on October 3, 2021
- (2) Unit 2, containment spray system B suction header valve SIB-V104 following the replacement of a sheer pin on the reach rod, on October 22, 2021
- (3) Unit 2, essential spray pond system B gasket replacement following inline ultrasonic testing inspections, on October 27, 2021
- (4) Unit 2, control element drive mechanism control system power switch assembly retests following replacements, on November 9, 2021
- (5) Unit 3, high pressure safety injection system A flow control valve SIA-UV-627 following hand switch and circuit breaker contact replacements, on December 10, 2021
- (6) Unit 2, essential chiller system B following oil and refrigerant filter replacement and calibration of indicators and controls, on December 10, 2021
- (7) Unit 1, reactor trip switchgear D following reactor trip circuit breaker replacement, on December 14, 2021
- (8) Unit 2, atmospheric dump valve system B following nitrogen accumulator calibration, on December 22, 2021
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 2R23 activities utilizing guidance from operating experience smart sample 2007/03, Crane and Heavy Lift Inspection, Supplemental Guidance to [Inspection Procedure] 71111.20 and [Inspection Procedure] 71111.13, Revision 3, from October 8 through November 15, 2021.
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
- (1) Unit 3, essential cooling water pump B inservice testing, on November 16, 2021
- (2) Unit 3, essential chilled water pump B inservice testing, on November 16, 2021
- (3) Unit 2, containment spray system A inservice testing, on December 6, 2021
Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)
- (1) Unit 2, containment penetration valves for containment hydrogen concentration system A from recombiner isolation valve HPA-UV-5 and containment post-LOCA hydrogen monitor outlet isolation valve HPV-HV-7B, on October 19, 2021
71114.06 - Drill Evaluation
Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated an emergency preparedness drill, on November 23,
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 reviewed the following:
Radiation Work Packages
2-3000-R23, "Control Element Assembly (CEA) Replacement," Revision 0
2-3319-R23, "Reactor Coolant Pump Maintenance w/ Motor Replacement,"
Revision 0
2-3502-R23, "Valve, Flange and Pump Maintenance and Inspection,"
Revision 0
2-3518-R23, "High Risk - Minor Maintenance in the 120'/127' Regenerative Heat Exchanger Cubicle," Revision 0 Electronic Alarming Dosimeter Alarms
CR 2-21-11100, Spurious dose rate alarm while on Unit 2 Turbine Building Roof
CR 2-21-11774, Unanticipated dose rate alarm during insulation removal for 2A Reactor Coolant Pump (RCP) loop drain in Unit 2
CR 3-21-04318, Unanticipated dose rate alarm during activities in 2A RCP bay in Unit 3
CR 3-21-05271, Unanticipated dose rate alarm during activities on 80' level of Unit 3 Containment Building Labeling of Containers
Yellow bags at Sea/Van City
Sea/Van inside the Dry Active Waste Processing System (DAWPS) building
B-25 Box in the DAWPS yard
Sea/Van in the DAWPS yard
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) Observed licensee surveys of potentially contaminated material leaving the Radiologically Controlled Area (RCA)
- (2) Observed workers exiting the Unit 2 Containment Building during a refueling outage
Radiological Hazards Control and Work Coverage (IP Section 03.04) (4 Samples)
The inspectors evaluated in-plant radiological conditions during facility walkdowns and observation of radiological work activities. The inspectors also reviewed the following radiological work packages:
(1)2-3000-R23, "Control Element Assembly (CEA) Replacement," Revision 0 (2)2-3319-R23, "Reactor Coolant Pump Maintenance w/ Motor Replacement,"
Revision 0 (3)2-3502-R23, "Valve, Flange and Pump Maintenance and Inspection," Revision 0 (4)2-3518-R23, "High Risk - Minor Maintenance in the 120'/127' Regenerative Heat Exchanger Cubicle," Revision 0 High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (5 Samples)
The inspectors evaluated licensee controls of the following High Radiation Areas and Very High Radiation Areas:
- (1) Unit 2 Containment - 80' level, Reactor Drain Tank Access
- (2) Unit 2 Containment - 100' level, In-Core Instrument Access (Very High Radiation Area)
- (3) Unit 2 Containment - 120' level, Regenerative Heat Exchanger Room
- (4) Unit 2 Containment - 140' Deck, Reactor Vessel Closure Head Stand enclosure
- (5) Unit 2 Containment - 140' Deck, Control Element Assembly (CEA) liner containment for CEA disassembly 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.
71124.02 - Occupational ALARA Planning and Controls
Implementation of ALARA and Radiological Work Controls (IP Section 03.03) (4 Samples)
The inspectors reviewed as low as reasonably achievable practices and radiological work controls. The inspectors reviewed the following activities:
- (1) RWP 2-3504, "R23 Minor Maintenance," Revision 00
- (2) RWP 2-3512, "Install/Remove Temporary Shielding," Revision 00
- (4) RWP 2-3002, "Reactor Destack and Restack," Revision 08
Radiation Worker Performance (IP Section 03.04) (1 Sample)
The inspector observed the following activities:
- (1) Cutting up control element assemblies in containment
Calibration of a personnel monitor
Minor maintenance activities in containment
Installation and removal of temporary shielding
Surveillance of installed radiation monitoring instrumentation
Egress from the containment control area and the primary RCA exit
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) Unit 3 Control Room Essential Air Ventilation System
- (2) Unit 3 Fuel & Auxiliary Building Essential Air Ventilation System
Temporary Ventilation Systems (IP Section 03.02) (1 Sample)
The inspectors evaluated the configuration of the following temporary ventilation systems:
- (1) High efficiency particulate air filter unit, RP #0081, in service in unit 2 letdown heat exchanger room during welding activities.
Use of Respiratory Protection Devices (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated the licensees use of respiratory protection devices.
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.
71124.05 - Radiation Monitoring Instrumentation
Walkdowns and Observations (IP Section 03.01) (10 Samples)
The inspectors evaluated the following radiation detection instrumentation during plant walkdowns:
- (1) Alpha Beta Sample Counter, #3030P
- (2) RM-20 Ion Chamber Survey Meter, #1367
- (3) Thermo Scientific Small Article Monitor (SAM) 12, #667 (4)iPCM-12, Personnel Contamination Monitor, #12028
- (5) RO-20AA Ion Chamber Survey Meter, #1404
- (6) Thermo Fisher Multi-Purpose Digital Survey Meter, FH40G-L, #19512
- (7) AMP-100 Monitor, #5006185
- (8) SWENDI Neutron Detector, #110763
- (9) Steam Generator Main Steam Gamma Radiation Detector, 2JSQNRE142B, Turbine Building
- (10) Plant Vent Stack Low Range Monitor, 2JSQNRE143, Turbine Building
71124.08 - Radioactive Solid Waste Processing & Radioactive Material Handling, Storage, &
Transportation
Radioactive Waste System Walkdown (IP Section 03.02) (2 Samples)
Inspectors walked down the following accessible portions of the radioactive waste systems and evaluated system configuration and functionality:
- (1) Dry Active Waste Processing and Storage Facility
- (2) Mobile Radwaste Resin Dewatering and Drying System
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10)===
- (1) Unit 1 (July 1, 2020 through September 30, 2021)
- (2) Unit 2 (July 1, 2020 through September 30, 2021)
- (3) Unit 3 (July 1, 2020 through September 30, 2021)
BI02: RCS Leak Rate Sample (IP Section 02.11) (3 Samples)
- (1) Unit 1 (July 1, 2020 through September 30, 2021)
- (2) Unit 2 (July 1, 2020 through September 30, 2021)
- (3) Unit 3 (July 1, 2020 through September 30, 2021)
OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)
- (1) Units 1, 2, and 3 (October 1, 2020 through September 30, 2021)
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 (October 1, 2020 through September 30, 2021)
71152 - Problem Identification and Resolution (PI&R)
Semiannual Trend Review (IP Section 02.02) (1 Sample)
- (1) The inspectors reviewed the licensees corrective action program for potential adverse trends that might be indicative of a more significant safety issue. The inspectors performed an in-depth review of the licensees ability to identify issues regarding operator performance, evaluate each occurrence, and implement corrective actions. The inspectors determined evidence of an emerging trend in this area, verified the licensee was aware of this trend, and documented one observation and minor violation.
Annual Follow-up of Selected Issues (IP Section 02.03) (2 Samples)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) Units 1, 2, and 3, response to failure of seismic monitoring system from August 31 through September 10, 2021
- (2) Units 1, 2, and 3, effectiveness of corrective actions related to the full implementation cyber security program inspection findings as described in NRC Cyber Security Inspection Report 05000528/2020401; 05000529/2020401; and 05000530/2020401 (ML20338A537) dated December 3, 2020
71153 - Follow-Up of Events and Notices of Enforcement Discretion Personnel Performance (IP Section 03.03)
- (1) The inspectors evaluated Unit 1 and Unit 3 partial loss of offsite power, and Unit 2 loss of instrument air, due to a loss of the startup transformer NAN-X02, and the licensees response, on October 20, 2021.
- (2) The inspectors evaluated the Unit 3 automatic reactor trip and licensees response, on December 9,
INSPECTION RESULTS
Failure to Identify and Correct Exposed Rebar in Steam Generator Pedestals in a Timely Manner Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000529/2021004-01 Open/Closed
[H.8] -
Procedure Adherence 71111.08P The inspectors identified a Green, non-cited violation of 10 CFR Part 50, Appendix B, Criterion XVI, for the licensees failure to identify an issue associated with the steam generator pedestals in Unit 2 as a condition adverse to quality and correct the condition. Title 10 CFR 50, Appendix B, Criterion XVI, Corrective Actions, requires, in part, that measures shall be established to assure that conditions adverse to quality, such as failures, malfunctions, deficiencies, deviations, defective material and equipment, and nonconformance are promptly identified and corrected.
Description:
On April 6, 2011, the licensee discovered exposed rebar and uncoated concrete on the SG pedestals for Unit 2 during a civil/structural component monitoring inspection. The condition was documented in condition report (CR) 11-00249. Engineering Evaluation 4450633 was developed to further assess the condition and provide appropriate repair methodology. The condition was determined to not be a structural concern and CMWO 3688852 was generated to complete the repairs and restore the pedestal structures back to as-designed condition. Design Drawing 13-C-ZCS-0300, Rev. 16, Containment Internals Partial Concrete Plan at EL. 80'-0" Areas CAA & CAB, Design Drawing 13-C-ZCS-0301, Rev. 17, Containment Internals Partial Concrete Plan at EL. 80'-0", Areas CAC & CAD, and Design Drawing 13-C-ZCS-0361, Rev. 4, Containment Internals Steam Generator Foundation Reinforcing Sections and Details require that a minimum of two inches of concrete shall cover the reinforcing steel material. The initial evaluation failed to identify the nonconformance with design drawings as a condition adverse to quality, and incorrectly identified the exposed # 18 rebar as stirrups rather than as the primary reinforcement component. The evaluation was captured on Evaluation 11-00249-001.
On October 12, 2021, NRC inspectors observed exposed rebar on the concrete pedestals for the steam generators in Unit 2. Following initial discussions, the licensee provided NRC inspectors with the CR initially identifying and evaluating the issue on April 6, 2011, CR 11-00249 and CR 11-00249-001 respectively. The repair work order CMWO 3688852 had not been completed to date. The evaluation again misidentified the exposed rebar as stirrups rather than primary reinforcement members and did not recognize that the exposed rebar was a nonconformance and therefore a condition adverse to quality.
Condition Report 21-11975 was generated following NRC discussions with the licensee and field walkdowns to evaluate the condition of the rebar. Following review by the screening committee the licensee again evaluated the exposed rebar as Not a Condition Adverse to Quality. At the conclusion of field inspections, the condition of the exposed rebar and uncoated concrete on the concrete pedestals was evaluated as having not further degraded and that since there was no concern of structural impact there was no condition adverse to quality. The inspectors challenged this determination and pointed out that Procedure 01DP-0AP12, Condition Reporting Process, Revision 37, section 3.3, defines Condition Adverse to Quality as An all-inclusive term used in reference to any of the following: failures, malfunctions, deficiencies, defective items, and non-conformances. At PVNGS this term is applied to: failures, malfunctions, deficiencies, defective items, and non-conformances in items, activities, software, and services that fall within the Current Licensing Basis (CLB) as well as failures to comply with procedures that implement the CLB.
The deviations from Design Drawing 13-C-ZCS-0300, Rev. 16, Containment Internals Partial Concrete Plan at EL. 80'-0" Areas CAA & CAB, Design Drawing 13-C-ZCS-0301, Rev. 17, Containment Internals Partial Concrete Plan at EL. 80'-0", Areas CAC & CAD, and Design Drawing 13-C-ZCS-0361, Rev. 4, Containment Internals Steam Generator Foundation Reinforcing Sections and Details are a nonconformance and a condition adverse to quality. The licensee acknowledged that the exposed rebar was a condition adverse to quality and implemented actions to correct the issue.
Corrective Actions: The licensees immediate actions were to perform field inspections and issue CR 21-12486.
Corrective Action References: CR 11-00249, CR 21-11975, CR 21-12486
Performance Assessment:
Performance Deficiency: The licensees failure to characterize a condition adverse to quality related to the steam generator pedestals, provide adequate evaluation, and take prompt corrective actions to resolve was a performance deficiency.
Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Design Control attribute of the Mitigating Systems cornerstone and adversely affected the cornerstone objective to ensure the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences. Specifically, the licensee failure to identify that the exposed rebar in the steam generator pedestals as a condition adverse to quality was a performance deficiency.
Failure to correct the condition in over a 10-year period was untimely.
Significance: The inspectors assessed the significance of the finding using Appendix A, The Significance Determination Process (SDP) for Findings At-Power. The inspectors assessed the significance of the finding in accordance with Inspection Manual Chapter 0609, Appendix A, The Significance Determination Process (SDP) for Findings At-Power, dated June 19, 2012, Exhibit 2, Mitigating Systems Screening Questions, dated July 1, 2012. The inspectors determined that the finding was of very low safety significance (Green)because even though the finding
- (1) was a deficiency affecting the design, it did not impact the qualification of a mitigating structure, system, or component, and did not result in a loss of operability or functionality;
- (2) did not represent a loss of system and/or function;
- (3) did not represent an actual loss of function of at least a single train for longer than its allowed outage time, or two separate safety systems out-of-service for longer than their technical specification allowed outage time; and
- (4) does not represent an actual loss of function of one or more non-technical specification trains of equipment designated as high safety-significant for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in accordance with the licensees maintenance rule program.
Cross-Cutting Aspect: H.8 - Procedure Adherence: Individuals follow processes, procedures, and work instructions. Specifically, Procedure 01DP-0AP12, Condition Reporting Process, Revision 37, was not followed with regards to screening the missing concrete and exposed rebar as a condition adverse to quality. In the original write up of CR 21-11975, the field evaluation reached the same conclusions as CR 11-000249 write up, and the Conditions Review Group failed to screen the exposed rebar as a condition adverse to quality as defined in the corrective action program
Enforcement:
Violation: Title 10 CFR Part 50, Appendix B, Criterion XVI, Corrective Action, requires, in part, that measures shall be established to assure that conditions adverse to quality, such as failures, malfunctions, deficiencies, deviations, defective material and equipment, and nonconformances are corrected in a timely manner. Contrary to the above, from initial operations until October 22, 2021, the licensee failed to identify a condition adverse to quality and correct it. Specifically, the licensee failed to identify that the exposed rebar in the steam generator pedestals was a condition adverse to quality and failed to take actions to correct it in a timely manner.
Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
Observation: Operator Performance Trend Review and Minor Violation 71152 The inspectors performed an in-depth review of the licensees ability to identify issues regarding operator performance, evaluate each occurrence, and implement corrective actions. The inspectors determined evidence of an emerging trend in this area, verified the licensee was aware of this trend, and identified one minor violation.
The inspectors reviewed seven condition reports documenting human performance errors by operations personnel. The inspectors noted the human performance errors were evenly distributed across the three units (two events in Unit 1, two events in Unit 2, and three events in Unit 3, respectively), and while four events occurred in the first half of 2021, the remaining three events occurred within a two-month period from September through November. The inspectors determined the licensee adequately followed site procedures to document and correct each human performance error. However, the inspectors questioned the licensees evaluation of the human performance errors due to the licensees inconsistent classification of the condition reports. The inspectors identified that five of the seven condition reports were classified as not a condition adverse to quality (NCAQ), whereas two similar condition reports were classified as conditions adverse to quality (CAQs). The inspectors noted the licensee documented the trend in operator performance under an eighth condition report as a condition adverse to quality (CAQ). While reviewing the inspectors concern, the licensee concluded a condition adverse to quality classification would be more appropriate for three of the condition reports previously classified as not a condition adverse to quality.
The inspectors determined the failure to identify three conditions adverse to quality was a performance deficiency and contrary to 10 CFR 50 Appendix B, Criterion XVI, Corrective Action, which states, in part, that conditions adverse to quality are promptly identified. 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 Mitigating Systems Cornerstone, it did not adversely affect the cornerstone objective to ensure the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences.
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 CR 22-00399.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On October 21, 2021, the inspectors presented the Radiation Safety inspection results to Mr. T. Weber, Director of Nuclear Regulatory Affairs, and other members of the licensee staff.
On October 22, 2021, the inspectors presented the Unit 2 Inservice inspection results to Mr. B. Rash, Vice President, Nuclear Engineering and Regulatory, and other members of the licensee staff.
On December 8, 2021, the inspectors presented the Cyber Security Problem Identification and Resolution inspection results to Mr. B. Rash, Vice President, Nuclear Engineering and Regulatory, and other members of the licensee staff.
On January 4, 2022, the inspectors presented the Seismic Monitoring System Corrective Action Review inspection results to Ms. C. Shields, Emergency Preparedness Manager, and other members of the licensee staff.
On January 20, 2022, the inspectors presented the integrated inspection results to Mrs. M. Lacal, Executive Vice President, Chief Nuclear Officer, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
21-14428, 21-14642
Drawings
13-C-ZVA-002
Site Drainage General Arrangement Plan
Drawings
13-C-ZVC-065
Site Rough Grading Plan Area 1
Drawings
13-C-ZVC-066
Site Rough Grading Plan Area 2
Drawings
13-C-ZVC-070
Site Rough Grading Plan Area 6
Drawings
13-C-ZVC-074
Site Rough Grading Plan Area 10
Drawings
13-C-ZVC-100
Site Storm Drainage Dikes and Channels Sheet 1
Procedures
Acts of Nature
Work Orders
4541553
Corrective Action
Documents
17-06376, 21-15292
Drawings
01-M-AFP-0001
P & I Diagram Auxiliary-Feedwater System
Drawings
01-M-HJP-001
Control Building HVAC P & I Diagram
Drawings
2-M-PCP-001
P & I Diagram Fuel Pool Cooling & Cleanup System
Drawings
2-M-SPP-001
Essential Spray Pond System
Miscellaneous
17-06376-002
Design Equivalent Change Package SP-1711 Essential
Spray Pond Wall Repair
Procedures
Control Building HVAC (HJ)
Procedures
Fuel Pool Cooling
Procedures
Essential Spray Pond (SP) B
Procedures
Auxiliary Feedwater Pump AFB-P01 Monthly Valve
Alignment
Procedures
CFR 50.59 and 72.48 Administrative Guideline
Corrective Action
Documents
21-09919, 21-10986, 21-11524, 20-12846, 21-13457,
5387437, 21-15047, FSCCR 5395659, FSCCR 5398202,
FSCCR 5398203, 19-04990, 16-18974
Drawings
01-M-FPP-006
P & I Fire Protection System
Drawings
13-A-ZYD-022
Fire Protection Containment Building Floor Plan at Elevation
ft.
Miscellaneous
Off Site Fire Chief Fire Drill Observation Report
06/24/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
PVGS Pre-Fire Strategies Manual
Miscellaneous
UFSAR, section 9.5.1, Fire Protection System
20C
Miscellaneous
UFSAR, Appendix 9B, Fire Protection Evaluation Report
20C
Miscellaneous
Design Basis Manual, Fire Protection System, Section 6.3.
Cable Spreading Room
Miscellaneous
NPL37-D-003C-
Unit 1 Fire Drill Summary
06/23/2021
Miscellaneous
NPL38-D-002B-
Unit 1 Fire Drill Summary
08/20/2021
Miscellaneous
NPL41-D-001A-
Unit 1 Fire Drill Summary
10/05/2021
Procedures
Fire System Impairments and Notifications
Procedures
Control of Transient Combustibles
Calculations
13-MC-DG-0411
DG Heat Exchanger Minimum Flow Rate vs. Inlet SP Water
Temperature
Calculations
13-MC-DG-0411
DG Heat Exchanger Minimum Flow Rate vs. Inlet SP Water
Temperature
Calculations
13-MC-SP-0307
SP/EW System Thermal Performance Design Bases
Analysis
Corrective Action
Documents
21-11138, 21-11205, 21-11233, 21-11239, 21-11644, 21-
217, 21-11226
Procedures
Heat Exchanger Program
Procedures
Heat Exchanger Visual Inspection
Procedures
Eddy Current Examination of Tubing
Work Orders
5174679, 5254569, 5254521, 5254522, 5254523, 5254449,
254450
Corrective Action
Documents
11-00249, 15-02910, 17-17322, 20-03475, 20-16460, 21-
05449, 21-05718, 21-05792, 21-05923, 21-05972, 21-
06081, 21-06098, 21-06152, 21-06159, 21-06165, 21-
06181, 21-06185, 21-06258, 21-06388, 21-06414, 21-
06517, 21-06522, 21-06905, 21-06906, 21-06908, 21-
06910, 21-06912, 21-07207, 21-07225, 21-07381, 21-
07445, 21-07636, 21-07800, 21-07803, 21-07945, 21-
07962, 21-07965, 21-09210, 21-09517, 21-09519, 21-
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
09660, 21-09698, 21-09913, 21-10226, 21-10236, 21-
276, 21-10421, 21-10479, 21-10548, 21-10552, 21-
10554, 21-10576, 21-11610, 21-11825
Corrective Action
Documents
Resulting from
Inspection
21-11808, 21-11814, 21-11815, 21-11818, 21-11820, 21-
11910, 21-11912, 21-11914, 21-11934, 21-11936, 21-
11975, 21-11977, 21-11982, 21-12001, 21-12048, 21-
2059, 21-12062, 21-12284, 21-12486, 21-12491, 21-12493
Drawings
13-C-ZCS-0300
Containment Internals Partial Concrete Plan at EL. 80'-0"
Drawings
13-C-ZCS-0301
Containment Internals Partial Concrete Plan at E
Drawings
13-C-ZCS-0361
Containment Internals Steam Generator Foundation
Reinforcing Sections and Details
Drawings
E 77560 & 77560-
VALVE ASSY 2 INCH, Y TYPE, 1512 LB, GLOBE, S.W.,
CRES.
D
Miscellaneous
Relief Request 65 - Unit 2, COVID-19, Request for Relief
from Bottom Mounted Instrumentation Nozzles and a
Pressurizer Nozzle to Surge Line Weld Overlay Examination
03/27/2020
Miscellaneous
Welder / Brazer Performance Qualification Summary
113
Miscellaneous
Palo Verde Safety Manual
Miscellaneous
2-21-00423
Sample Data Sheet - Unit 2 CTMT BLDG 87' ELEV Rm 1A
RCP Bay
10/20/2021
Miscellaneous
Mechanical Snubber Removal And Reinstallation
Miscellaneous
Units 1, 2 & 3 Alloy 600 Management Program Plan
Miscellaneous
4th Inspection Interval Inservice Inspection Program
Summary Manual PVGS Unit 2
Miscellaneous
RCS Deposits Administrative Guideline
Miscellaneous
Building Code Requirements for Reinforced Concrete
10/01/1974
Miscellaneous
CUP#2899
Nuclear Grade Tape Products
Miscellaneous
CUP#3355
Duct Tape, Non-Nuclear Grade
Miscellaneous
Materials Reliability Program: Boric Acid Corrosion
Guidebook, Revision 2: Managing Boric Acid Corrosion
Issues at PWR Power Stations
Miscellaneous
SDOC No. 02-
U2 EW Growth Letter
08/29/2012
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
MN950-A00052
NDE Reports
17-VT-2051
Visual Examination for Boric Acid Detection - Closure Head
04/24/2017
NDE Reports
20-VT-2089
Pressure Test Report - RCS PIPING REFUELING
OUTAGE: Class 1 and Class 2 pressurized and non
pressurized piping inside containment during mode 3
walkdown.
05/21/2020
NDE Reports
21-PT-2001
RC/2PRCEL096, 2A Drain Line
10/12/2021
NDE Reports
21-PT-2002
RC/2PRCEL060
10/12/2021
NDE Reports
21-UT-2021
Shutdown Cooling Loop 2
10/14/2021
NDE Reports
21-UT-2022
Shutdown Cooling Loop 2
10/14/2021
NDE Reports
21-UT-2023
Shutdown Cooling Loop 2
10/14/2021
NDE Reports
21-UT-2024
Shutdown Cooling Loop 2
10/14/2021
NDE Reports
21-VE-2004
VE bare metal examination of Reactor Vessel ICI
penetrations (1-31-1 thru 61)
10/11/2021
NDE Reports
21-VE-2065
VE bare metal examination of Reactor Head CEDM
penetrations. 2R23 (1 thru 97 including head vent)
10/16/2021
NDE Reports
21-VT-2009
VT2 of Rx head bolted connection
10/12/2021
NDE Reports
21-VT-2034
PC-5-H-11
10/12/2021
NDE Reports
21-VT-2035
PC-5-H-11-W
10/12/2021
Procedures
Condition Reporting Process
Procedures
Chemical Control Program
Procedures
Control of Flammable/Combustible Storage Cabinets
Procedures
Control and Monitoring of Potential Tornado Borne Missiles
Procedures
Low Pressure Safety Injection Pump Maintenance
Procedures
High Pressure Safety Injection Pump Disassembly,
Examination and Assembly
Procedures
Containment Spray Pump Disassembly And Assembly
Procedures
RCS Leakage Source Determination
Procedures
ERFDADS (Preferred) Calculation of RCS Water Inventory
Procedures
ECCS Systems Leak Test
Procedures
Boric Acid Walkdown Leak Detection
Procedures
Primary Coolant Sources Outside Containment Program
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
Welding and Brazing Control
Procedures
Weld Filler Material Control
Procedures
Boric Acid Corrosion Control Program
Procedures
Testing and Control of PVGS Snubbers
Procedures
Hydraulic Snubber Functional Testing
Procedures
Snubber Visual Examination
Procedures
Mechanical Snubber Function Test
Procedures
Ultrasonic Thickness Measurement
Procedures
Bare Metal Visual Examination of Reactor Vessel Upper
Head
Procedures
Bare Metal Visual Examination of Reactor Vessel Bottom
Head
Procedures
ECCS Sump to RWT Leakage Paths Design Bases Testing
Procedures
Dry Magnetic Particle Examination
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
EPRI-PIPE-MPA-
Procedure for Manual Phased Array Ultrasonic Examination
of Austenitic and Ferritic Pipe Welds EPRI-PIPE-MPA-1
Procedures
EPRI-PIPE-TWS-
MPA-1
Procedure for Manual Phased Array Ultrasonic Through-
Wall Sizing In Pipe Welds EPRI-PIPE-TWS-MPA-1
Procedures
PDI-UT-1
PDI Generic Procedure for the Ultrasonic Examination of
Ferritic Pipe Welds PDI-UT-1
G
Procedures
PDI-UT-10
PDI Generic Procedure for the Ultrasonic Examination of
Dissimilar Metal Welds, PDI-UT-10
G
Procedures
PDI-UT-11
PDI Generic Procedure for the Ultrasonic Examination of
Reactor Pressure Vessel Nozzle-to-Shell Welds and the
Nozzle Inner Corner Radius PDI-UT-11
D
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
PDI-UT-2
PDI Generic Procedure for the Ultrasonic Examination of
Austenitic Pipe Welds PDI-UT-2
I
Procedures
PDI-UT-3
PDI Generic Procedure for the Ultrasonic Through-Wall
Sizing of Planar Flaws in Similar Metal Piping Welds PDI-
UT-3
G
Procedures
PDI-UT-5
PDI Generic Procedure for the Straight Beam Ultrasonic
Examination of Bolts and Studs PDI-UT-5
G
Procedures
PDI-UT-8
PDI Generic Procedure for the Ultrasonic Examination of
Weld Overlaid Similar and Dissimilar Metal Welds, PDI-UT-8
I
Self-Assessments 20-04629-001
INPO MRV NDE SIMPLE SELF-ASSESSMENT
06/30/2020
Self-Assessments SWMS#17-09564
Welding Program Self Assessment
06/30/2017
Self-Assessments SWMS#18-
14430-002
ISI Simple Self Assessment
04/02/2019
Self-Assessments SWMS#20-
04621-002
Alloy 600
07/23/2020
Miscellaneous
NLR21S050401
Licensed Operator Continuing Training Simulator Scenario:
Fire with Spurious Equipment Actuations
11/16/2021
Miscellaneous
SES-0-05-P-10
Licensed Operator Continuing Training Simulator Evaluation
Scenario: SIT 1B Air Leak / Control Channel NI #1 Fails
Low / RCP 2A Trip / ATWS / ESD
11/16/2021
Procedures
Conduct of Operations
Procedures
Containment Spray Pumps and Check Valves - Inservice
Test
Work Orders
271728
Corrective Action
Documents
21-08461, 21-06710, 21-09763, 21-09485, 18-17577, 19-
10419, 21-12252, 21-12351, 21-12367, 21-12088, 19-
269, 19-10579, 19-10910, 19-12574, 19-18009, 20-
05452, 20-05813, 20-07365, 21-03326
Miscellaneous
Guidance on Overhaul of Magne-Blast Circuit Breakers
2/2000
Miscellaneous
Performance Criteria Formulation Bases for SA System
(Engineered Safety Features Actuation System)
Miscellaneous
Vendor Technical Document VTD-C150-0017, Carrier
Corporation 19FA Centrifugal Chiller Parts Catalog S/N
26507-26512
N/A
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
Mrule Performance Monitor Group information for Essential
Chilled Water B
Miscellaneous
Unit 2 Control room logs for 09/17/2021-12/16/2021
Miscellaneous
Unit 3 Control Room Logs January 1 - December 28, 2021
2/29/2021
Miscellaneous
MRule Manager Data for Unit 3 SA DAFAS A and B
2/29/2021
Miscellaneous
13-NS-C025
Risk Informed Performance Criteria
Miscellaneous
SA-02323
SA - DAFAS A/B Maintenance Rule (a)(1) Issue Tracking
Form
Miscellaneous
SA-02323
SA - DAFAS A/B Maintenance Rule (a)(1) Issue Tracking
Form
Miscellaneous
SAL 361.1
Service Advisory Letter
Miscellaneous
TR-109641
Guidance on Routine Preventive Maintenance for Magne-
Blast Circuit Breakers
10/1998
Procedures
Condition Reporting Process
Procedures
Maintenance of AM-4.16-250-9H GE Magne-Blast Circuit
Breakers
Procedures
Overhaul of AM-4.16-250-9H GE Magne-Blast Circuit
Breakers
Procedures
Essential Chiller
Procedures
Essential Chilled Water Train B
Procedures
Control Element Drive Mechanism Control System
(CEDMCS) Operation
Procedures
Maintenance Rule
Work Orders
5152532, 5235964, 5218289, 5218290, 5279220, 5360915,
5380847, 5258452, 5257990
Corrective Action
Documents
21-13903, 21-13663, 21-13799
Miscellaneous
Phoenix Risk Monitor - PVGS Unit 1 Current Risk Summary
Report as of 11/18/2021
Miscellaneous
U1 PHOENIX RICT November 18, 2021 Operator Screen
Risk at 0433
11/18/2021
Miscellaneous
Work Week 2146 Schedule Risk Evaluation,
11/15/2021-
11/21/2021
Miscellaneous
Risk Management and Readiness Plan: U2 A ESFAS PS
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Replacement
Miscellaneous
Work Week 2147 Schedule Risk Evaluation
11/22/2021-
11/28/2021
Procedures
Online Integrated Risk
Procedures
Operations Department Online Nuclear Risk Determination
Modes 1 and 2
Procedures
RICT PRA Functionality Determination
Procedures
Procedures
Safety Injection Tank Nitrogen Vent Valves-Inservice Test
Work Orders
5389532, 5388714, 5390168
Calculations
13-CC-ZC-0285
Heat Sink Calculations Containment Building
Calculations
13-NC-ZC-0237
Maximum Passive Heat Sink for Hydrogen Generation &
ECCS Evaluation
Calculations
N001-1106-00002
Debris Generation Due to LOCA Within Containment for
Resolution of GSI-191
Corrective Action
Documents
21-12899, 21-12438, 21-12529, 21-12563, 21-12578, 21-
2585, 21-12623, 21-12752, 21-11058, 21-13285, 16-
13938, 21-12286, 21-08850, 21-13780, 21-14537, 21-
10885, 21-11296, 21-13294, 20-05888, 21-14814, 21-12485
, 21-13692, 21-13671, 21-14937, 21-14929, 20-10476, 17-
06807
Drawings
2-M-SIP-001
Safety Injection & Shutdown Cooling System
Drawings
2-P-SPF-701
Diesel Generator BLDG. ISO Essential Pray Pond System
Train A & B
Drawings
2-P-ZYA-0926
Essential Pipe Tunnel piping sections and details
Drawings
2-P-ZYA-0926
Essential Pipe Tunnel Piping Plan
Drawings
03-M-SIP-002
P & I Diagram: Safety Injection and Shutdown Cooling
System
Engineering
Changes
2018-00492
Miscellaneous
Engineering Evaluation 21-12899-003
Miscellaneous
PVNGS Design Basis Manual, Essential Spray Pond
System
Miscellaneous
Technical Documents 269457, 274560,274776, 274816,
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
274835, 274865, 274922, 274962, 424156
Miscellaneous
Updated Final Safety Analysis Report
Miscellaneous
Design Basis Manual: Essential Chilled Water System
Miscellaneous
PVNGS Technical Specification Bases
Miscellaneous
UFSAR Section 9.2.9.2, Essential Chilled Water Systems
Miscellaneous
PVGNS Design Basis Manual, Auxiliary Feedwater System
Miscellaneous
Design Basis Manual: Safety Injection System
Miscellaneous
PVNGS Technical Specification Bases
Miscellaneous
UFSAR Section 15.6.5, Loss-Of-Coolant Accidents
Miscellaneous
UFSAR Section 6.3.3a, LOCA Analysis - CE16STD Fuel
Miscellaneous
Unit 2 Operator Logs, December 20-28, 2021
2/28/2021
Miscellaneous
Unit 2 Operator Logs, November 11-18, 2021
2/28/2021
Miscellaneous
13-MS-A137
Engineering Study, Development of AF System Pipe Arc
Length Acceptance Criteria Associated with Calculated Max
Void Volumes
Miscellaneous
21-11296-003
MRFF (Maintenance Rule Functional Failure) Evaluation
Miscellaneous
21-13294-004
Engineering Evaluation
Miscellaneous
EER 90-DG-030
Engineering Evaluation Request
04/16/1990
Miscellaneous
Study 13-NS-
C088
Mission time for Operability Determinations
Procedures
Train B Auxiliary Feedwater Flow Instrumentation Calibration
Procedures
Locked Valve, Breaker, and Component Tracking
140
Procedures
Operations Condition Reporting Process and Operability
Determination/Functional Assessment
Procedures
Control Building Watch Station Rounds
25
Procedures
ECCS Systems Leak Test
Procedures
Auxiliary Feedwater Pump B - Comprehensive Pump Test
Procedures
SI Train B Valves - Inservice Test
Procedures
SI Train B Valves - Inservice Test
Work Orders
22485, 4922486, 5061531, 5057504, 5373506, 5241560,
263109, 5216987, 5191806, 5395606, 5388830, 5388912,
275397, 5273625, 5267591
Corrective Action
21-11851, 21-11695
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Documents
Drawings
2-M-CHP-0001
P&I Diagram Chemical and Volume Control System
Drawings
2-M-RDP-0001
P&I Diagram Radioactive Waste Drain System (Containment
Building)
Miscellaneous
Miscellaneous
21-F014
Licensing Document Change Request
Miscellaneous
PVNGS DBM
Chemical and Volume Control System
Miscellaneous
S-21-0043
10CFR50.59 Screening/Evaluation
Work Orders
5380370
Corrective Action
Documents
21-07164, 21-11226, 21-14350, 21-14377, 21-13545, 21-
13557, 21-12088, 21-12485, 21-15116
Miscellaneous
Unit 1 Control room logs
10/01/2021-
10/03/2021
Miscellaneous
Unit 2 control room logs for October 2021
Miscellaneous
TD 276657
Operations Technical Document to Comply with Tech Spec
3.6.3 for SIA-UV-627 Inoperability
2/02/2021
Miscellaneous
TD 276657
Operations Technical Document to Comply with Tech Spec
3.6.3 for SIA-UV-627 Inoperability
2/04/2021
Procedures
Cleaning, Inspecting, and Testing of the Class 1E Diesel
Generator
Procedures
Molded Case Circuit Breaker Test
Procedures
Month Surveillance Test for Westinghouse Type DS-416
Reactor Trip Breakers
Procedures
Essential Chiller
Procedures
RPS Matric Relays to Reactor Trip Response Time Test
Procedures
RTSG Shunt and Undervoltage Trip Functional Test
Procedures
Motor Operated Valves Operating Guidelines
Procedures
Locked Valve, Breaker, and Component Tracking
140
Procedures
Train A 480V Class 1E MCC
Procedures
Diesel Generator A Test
Procedures
ECCS Systems Leak Test
Procedures
Lubrication of Plant Equipment
Procedures
ADVs - Inservice Test
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
CEA Drop Time Test
Work Orders
256867, 5224848, 5254445, 5136175, 5254471, 5256018,
5303866, 5258250, 5270389, 5320369, 5393374, 5258452,
257990, 5382122, 5277571, 5277252, 5282209, 5250921,
249295, 5250944, 5250885
Corrective Action
Documents
21-03767, 21-09919, 21-11334, 21-11665, 21-11674, 21-
11680, 21-11681, 21-11682, 21-11685, 21-11686, 21-
11688, 21-11691, 21-11693, 21-11695, 21-11874, 21-
2436, 21-12457, 21-12545, 21-12546
Miscellaneous
Unit 2 Cycle 23 Specific Maneuver Plan: EOC Coastdown
Miscellaneous
Unit 2 Cycle 23 Standard Maneuver Plan: EOC Shutdown
81.93% to 20%
Miscellaneous
Unit Two 23rd Refueling Outage Shutdown Risk
Assessment Team Review Report
Miscellaneous
CN390-A00183, Safety Analysis Report for Single Failure
Proof Trolley (NUREG 0554)
Miscellaneous
Fatigue Assessment for Technician Following Arc Flash
Event
10/23/2021
Miscellaneous21-009
2R23 Refueling Outage Restart PRB Package
Miscellaneous
MN725-A00935
RSB 5-1 Natural Circulation Cooldown Analysis for Power
Uprate and SG Replacement at Palo Verde Nuclear
Generating Station Units 1, 2, and 3
Procedures
PVGS Rigging Control
Procedures
Field Use of Rigging
Procedures
Reactor Vessel Head Removal and Installation
Procedures
Shutdown Risk Management
Procedures
Augmentation of Fuel Pool Cooling with Shutdown Cooling
Procedures
Shutdown Cooling Initiation
Procedures
Initial Reactor Startup Following Refuelings
Procedures
Weekly Shutdown Electrical Distribution Checks
Procedures
Power Operations
151
Procedures
Mode Change Checklist
104
Procedures
Outage GOP
Procedures
Tracking Containment Penetrations
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
RCS and Pressurizer Heatup and Cooldown Rates
Procedures
Locked Valve Monthly Surveillance
Procedures
Operations Mode 1 Surveillance Logs
Procedures
Containment Isolation Valves
Procedures
Outage Planning and Implementation
Procedures
Shutdown Risk Assessments
Procedures
Low Power Physics Testing Using STAR
Work Orders
257823
Calculations
13-JC-SI-0215
Containment Spray Pump Discharge Flow Indication Loops
(SIA-F-338 & SIB-F-348) Uncertainty Calculation
Corrective Action
Documents
18-14867, 17-11850, 21-13811, 21-12417, 21-12422
Drawings
2-M-SIP-001
P & I Diagram: Safety Injection & Shutdown Cooling System
Miscellaneous
Unit 3 Operator logs: November 16, 2021
11/16/2021
Procedures
Conduct of Maintenance
Procedures
M&TE Gage Installation
Procedures
Pump and Valve Inservice Testing Program
Procedures
Containment Leakage Type B and C Testing
Procedures
Essential Chilled Water Pumps - Inservice test
Procedures
Essential Cooling Water Pumps - Inservice test
Procedures
Containment Spray Pumps and Check Valves - Inservice
Test
Procedures
Containment Spray Pumps and Check Valves - Inservice
45a
Work Orders
266875, 5266874, 5271728
Corrective Action
Documents
21-14084, 21-14076
Procedures
ERO Positions Emergency Operations Director (EOF)
Procedures
Notifications
Procedures
ERO/ERF Activation and Operation
Procedures
Protective Actions
Corrective Action
Documents
20-13969, 20-14285, 20-14744, 20-14974, 20-15826, 21-
01194, 21-02640, 21-03646, 21-03835, 21-04318, 21-
04730, 21-05021, 21-05093, 21-05120, 21-05271, 21-
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
05625, 21-05694, 21-06192, 21-10277, 21-11100, 21-
11774, 21-12245
Miscellaneous
Radiological Safety Trends
08/31/2021
Procedures
RP Program Overview
Procedures
Radiation Exposure and Access Control
Procedures
Radiation Exposure and Access Control
Procedures
Radiological Posting and Labeling
Procedures
Exposure Evaluation for Lost, Damaged, or Abnormally
Indicating Dosimetry
Procedures
Control of High Radiation Areas, Locked High Radiation
Areas, and Very High Radiation Areas
Procedures
Radiation Work Permits
Procedures
Control and Storage of Radioactive Material and Radioactive
Wastes
Procedures
Medical Uptakes of Radioisotopes
Procedures
Radiological Job Coverage
Procedures
NISP-RP-102
Access for Visitors, Escorted Workers and SRD Only
Workers
Radiation
Surveys
2-M-20211017-12
140' E cavity CEA cut up area
10/17/2021
Radiation
Surveys
3-M-20210412-27
CNTMT South Pump Bay 87' (RCP 2a and 2B)
04/12/2021
Radiation
Surveys
3-M-20210426-21
80' Cntmt New HRA,RPHP posting
04/26/2021
Radiation
Surveys
3-M-20210427-31
Investigation of dose rate alarm
04/27/2021
Radiation
Surveys
3-M-20210721-2
20' Evap Dose Rate Alarm Investigation
07/21/2021
Radiation Work
Permits (RWPs)
2-3000-R23
Control Element Assembly (CEA) Replacement
Radiation Work
Permits (RWPs)
2-3319-R23
Reactor Coolant Pump Maintenance w/ Motor Replacement
Radiation Work
Permits (RWPs)
2-3502-R23
Valve, Flange and Pump Maintenance and Inspection
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Radiation Work
Permits (RWPs)
2-3518-R23
High Risk - Minor Maintenance in the 120'/127' Regenerative
Heat Exchanger Cubicle
Radiation Work
Permits (RWPs)
3-3504
Minor Maintenance
Radiation Work
Permits (RWPs)
9-1009
Minor Maintenance
Radiation Work
Permits (RWPs)
9-1020
Visitor and Escort Tours, Visual Inspections, and Work on
Non-Plant Systems or Components
Self-Assessments 302-03863
September 2020 Offsite Safety Review Committee Meeting
20-002, Operations, Chemistry and Radiation Protection
Subcommittee Report
10/01/2020
Self-Assessments 302-03876
RJA/RJA
March 2021 Offsite Safety Review Committee (OSRC)
Meeting 21-001, Operations, Chemistry and Radiation
Protection Subcommittee Report
03/25/2021
Self-Assessments Audit 2020-004
Radiation Safety
08/06/2021
Corrective Action
Documents
20-03640, 20-10685, 20-10881, 20-13950, 20-16029, 21-
01305, 21-03030, 21-04127, 21-04934, 21-07369, 21-
226, 21-08725, 21-09027
Miscellaneous
PVGS Radiological Safety Trends
09/06/2021
Miscellaneous
Palo Verde Generating Station ALARA 5-Year Plan 2018-
22
10/25/2018
Miscellaneous
Draft Palo Verde Generating Station ALARA 5-Year Plan
21-2025
10/2021
Miscellaneous
218-04731
20 Annual Radiation Protection Program Summary Report
08/25/2021
Procedures
RP Program Overview
Procedures
ALARA Program Overview
Procedures
ALARA Committee
Procedures
Managing Radiological Risk
Procedures
Radiation Protection Periodic Review Program
Procedures
Radiation Work Permits
Procedures
ALARA Reports
Procedures
Special Dosimetry
Procedures
Radioactive Source Control
Procedures
ALARA Work Planning
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Radiation
Surveys
2-M-20211009-5
C100 Elevation Overview Containment
10/09/2021
Radiation
Surveys
2-M-20211009-8
C140 Elevation Overview Containment
10/09/2021
Radiation
Surveys
2-M-20211014-11
Refueling Pool (Enlarged) 140'
10/14/2021
Radiation
Surveys
2-M-20211017-12
140' East Cavity CEA Cut Up Area
10/17/2021
Radiation
Surveys
2-O-20211016-2
Free Release a PZR Fan Impellor Shaft
10/16/2021
Radiation
Surveys
3-M-20210423-1
Unit 3 117' 2A RCP Bay / SIEV227 - Removal of Internals
04/23/2021
Radiation
Surveys
3-M-20210526-4
3PSIEV227 Internals of Unit 3
05/26/2021
Radiation Work
Permits (RWPs)
2-3000-R23
Control Element Assembly (CEA) Replacement
Radiation Work
Permits (RWPs)
2-3002-R23
Reactor Destack and Restack
Radiation Work
Permits (RWPs)
2-3503
General Tours, Inspections and Job Planning Walkdowns
Radiation Work
Permits (RWPs)
2-3504-R23
Minor Maintenance
Radiation Work
Permits (RWPs)
2-3512-R23
Install / Remove Temporary Shielding
Radiation Work
Permits (RWPs)
3-3521-03
3R22 High Risk Inboard Loop Discharge Check Valve Work
Self-Assessments 20-10685-001
PVGS Integrated Performance Assessment Report:
Radiation Protection 1st Half 2020
07/24/2020
Self-Assessments 2020-004
Nuclear Assurance Department (NAD) Audit Report:
Radiation Safety
08/06/2021
Self-Assessments 218-04716
PVGS 2020 Annual ALARA/Management Evaluations
Report
06/29/2021
Corrective Action
Documents
20-15807, 21-04915, 21-07758, 21-09097
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Drawings
Control Building HVAC System (HJ)
Drawings
Auxiliary Building HVAC System (HA)
Drawings
Fuel Building HVAC System (HF)
Miscellaneous
Year Hydrostatic Cylinder Report
10/19/2021
Miscellaneous
Unit 2 control room - self contained breathing apparatus
October 2021 inspection report
Miscellaneous
Self-Contained Breathing Apparatus (SCBA) test report for
SCBA # LAC-240-936
04/13/2021
Miscellaneous
SCBA test report for SCBA # LAC-240-932
04/13/2021
Miscellaneous
Process Change Package # 5265776
10/11/2020
Procedures
Procedures
PVGS Respiratory Protection Equipment Usage
Procedures
PVGS Respiratory Protection Program
Procedures
Respiratory Equipment Inspection and Repair
Documentation
Procedures
Ventilation Filter Testing Program (VTFP)
Procedures
Surveillance Testing for the Aux/Fuel Building Nuclear Air
Treatment System
Procedures
Surveillance Testing of the Control Room Nuclear Air
Treatment System
Procedures
Carbon Analysis for the Control Room Essential Nuclear Air
Treatment System
Procedures
Train ESF Pump Room and Fuel Building Ventilation
System Operability/Functionality Test
Procedures
Control Room Essential Filtration System Operability Test
Procedures
Operation of the AMS-4 CAM
Procedures
Radiological Air Sampling
Procedures
Use of control of HEPA Filtration and Vacuum Equipment
Work Orders
STWO #4915279
Surveillance test package for unit 2 control room nuclear air
treatment system
05/18/2020
Work Orders
STWO #4986418
Surveillance test package for unit 1 control room essential
air treatment system
06/10/2019
Procedures
Actions for Non-Functional Radiation Monitors: Preplanned
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Alternate Sampling Program
Procedures
Calibration and Response Check of the Thermo Fisher
Scientific Contamination Monitor Type PM12
71151
Miscellaneous
RCA Entries Greater than 80 millirem
09/21/2021
71151
Miscellaneous
Units 1, 2, and 3 RCS Leakage Data
11/05/2021
71151
Miscellaneous
Units 1, 2, and 3 RCS Dose Equivalent Iodine-131 Data
11/05/2021
71151
Miscellaneous
Unit 1
PVNGS Radioactive Effluent Release Permit Summary
Report
10/21/2021
71151
Miscellaneous
Unit 2
PVNGS Radioactive Effluent Release Permit Summary
Report
10/21/2021
71151
Miscellaneous
Unit 3
PVNGS Radioactive Effluent Release Permit Summary
Report
10/21/2021
71151
Procedures
Performance Indicator - Barrier Integrity Cornerstone: RCS
Leak Rate
71151
Procedures
ERFDADS (Preferred) Calculation for RCS Water Inventory
71151
Procedures
Dose Equivalent Xe-133 and Dose Equivalent I-131
Determination
71151
Procedures
RCS Activity Performance Indicator
71151
Procedures
Reactor Coolant System Specific Activity Surveillance Test
71151
Procedures
Performance Indicator Occupational Radiation Safety
Cornerstone
71151
Procedures
Performance Indicator Public Radiation Safety Cornerstone
Corrective Action
Documents
21-00423, 21-01559, 21-01940, 21-03483, 21-03485, 21-
06035, 21-07093, 21-00942, 21-07326, 21-11051, 21-
11154, 21-13953, 21-14269, 21-14595, 18-02605, 18-
2668, 19-09910, 21-00963, 21-10262, 21-11121
Corrective Action
Documents
Condition Reports
19-15831, 20-04589, 20-11549, 20-11613, 20-11830, 20-
2157, 20-12213, 20-12214, 20 12253, 20-12282, 20-
13187, 20-14092, 20-14172, 20-14272, 20-14470, 20-
14522, 20 14525, 20-14601, 20-14606, 20-14609, 21-04020
Corrective Action
Documents
Condition Reports
(Non)
21-04020, 21-05447, 21 08513, 21-12356, 21-13833
Corrective Action
Documents
Level 4
Evaluation Report
Evaluate the Current Alternate Methods/Compensatory
Actions for Emergency Planning Classifications When the
10/01/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
21-10262-003
Seismic Monitor is Nonfunctional
Corrective Action
Documents
Resulting from
Inspection
Condition Report
21-13938, 21-14096, 21-14281
Drawings
Palo Verde Topology
Engineering
Evaluations
13-JS-B005
Critical System Determination
Engineering
Evaluations
OMA-SB-01
Ongoing Monitoring and Assessment (OM&A) Report
Reactor Protection System (SB) Group 1 & 2, Core
Protection Calculator
Engineering
Evaluations
OMA-SB-04
Ongoing Monitoring and Assessment (OM&A) Report
Reactor Protection (SB) Units 1,2,3, Group 4, CPC
Communication Devices
Engineering
Evaluations
OMA-SB-05
Ongoing Monitoring and Assessment (OM&A) Report
Reactor Protection (SB) Units 1,2,3 Group 5, Converters
Miscellaneous
Common Controls Spreadsheet
09/07/2021
Miscellaneous
Cyber Security Excellence Plan
10/28/2021
Miscellaneous
Palo Verde Nuclear Generation Station Cyber Security Plan
(CSP)
Miscellaneous
Palo Verde Nuclear Generating Station, Alert December 15,
2016 Event Summary Report
01/12/2017
Miscellaneous
Unit 1, 2, 3 Night Order, Seismic Monitor Non-Functional
09/02/2021
Miscellaneous
Unit 1, 2, 3 Night Order, Seismic Monitor Non-Functional
09/03/2021
Miscellaneous
Licensed Operator Continuing Training 2019-2024 6 Year
Long Range Training Plan
Miscellaneous
Actual Event Investigation, Seismic Occurrence on 7/4/2019
- 19-09910-002
07/19/2019
Miscellaneous
Temporary Approved Procedure Action (TAPA), Procedure
Number 79IS-9SM01, Revision Number 27, TAPA Letter: A
09/02/2021
Miscellaneous
Level 3 Evaluation Report 18-02668-002
03/22/2018
Miscellaneous
Trend Analysis Administrative Guideline
Miscellaneous
2-06866-AKK
Palo Verde Nuclear Generation Station (PVNGS) Units 1, 2,
and 3 and Independent Spent Fuel Storage Installation;
04/10/2014
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Docket Nos. 50-528, 50-529, 50-530, and 72044; License
Nos. NPF-41, NPF-51 and NPF-74; Revision 5 to EP-0901,
Classifications, and Revision 52 to the PVNGS Emergency
Plan
Miscellaneous
2-07135-
MLL/TNW/DCE
Palo Verde Nuclear Generating Station (PVNGS) Units 1, 2,
and 3 and Independent Spent Fuel Storage Installation;
Docket Nos. 50-528, 50-529, 50-530 and 72-44; License
Nos. NPF-41, NPF-51 and NPF-74; Request for NRC
Approval of Proposed Changes to PVNGS Emergency
Action Levels
10/09/2015
Miscellaneous
2-07255-
MLL/JF/DCE
Palo Verde Nuclear Generating Station (PVNGS) Units 1, 2,
and 3 and Independent Spent Fuel Storage Installation;
Docket Nos. 50-528, 50-529, 50-530 and 72-44; License
Nos. NPF-41, NPF-51 and NPF-74; Response to Request
for Additional Information Regarding Proposed Changes to
PVNGS Emergency Action Levels
05/12/2016
Miscellaneous
CVE-2020-1350
Windows DNS Server Vulnerability
Miscellaneous
Form 2212
Digital Asset Data Sheet
Miscellaneous
Form PV-E0046
Contract Personnel Exit Checklist
Miscellaneous
Form PV-E0059
Leader Checklist for Exiting Employees
Miscellaneous
Lesson Plan
Number:
NKASMC032104
Acts of Nature
2/05/2019
Miscellaneous
Lesson Plan
Number:
NKASYC015904
Seismic Monitoring System
9/27/2013
Miscellaneous
Lesson Plan
Number:
NKASYC015907
Seismic Monitoring System Lesson Plan
04/06/2020
Miscellaneous
Lesson Plan
Number:
NNR18C060500
Deliberate Acts and Acts of Nature
11/06/2018
Miscellaneous
ODP-1
Operations Principles and Standards
Miscellaneous
ODP-31
Operations Emergency Plan Implementation
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
Repetitive Tasks
199478, 204678, 205318, 205319, 205459, 205460, 205461
Miscellaneous
Wireless
Walkdown
Results
March, July, & September 2021
Miscellaneous
Work
Authorization
210174
Work Scope Excerpt
Miscellaneous
Work Scope
Library (WSL)
5153648, 5321051, 5321491, 5342806, 5348690, 5348691,
5348692, 5369985
Procedures
Procedure and Work Instruction Use and Adherence
Procedures
Condition Reporting Process
Procedures
Conduct of Organizational Effectiveness
Procedures
Conduct of Organizational Effectiveness
Procedures
Control of Purchasing Material and Equipment
Procedures
Stores
Procedures
Emergency Preparedness Equipment Out of Service
Procedures
Palo Verde Badging Procedure
Procedures
Access Authorization
Procedures
Vulnerability Assessments and Scans
Procedures
Cyber Security Incident Response
Procedures
Cyber Security Alerts and Advisories
Procedures
PVGS Critical Digital Asset (CDA) Management
Procedures
Ongoing Monitoring and Assessment
Procedures
Palo Verde Cyber Security Defensive Strategy
Procedures
Management of Cyber Security Security-Related Keys and
Accounts/Passwords
Procedures
Panel B07C Alarm Responses
15, 17, 18
Procedures
Acts of Nature
37, 39
Procedures
Conduct of Operations
2, 76
Procedures
Shift Turnover
Procedures
Analysis of Seismic Event
Procedures
Classifications
Work Orders
21491
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
21-12450, 21-12443, 21-12479, 21-12478, 21-12511, 21-
2436, 21-14531, 21-14464, 21-14465, 21-14478, 21-
14480, 21-14488
Miscellaneous
Unit 1 Operator logs: October 20-22, 2021
10/22/2021
Miscellaneous
Unit 2 Operator logs: October 20-21, 2021
10/21/2021
Miscellaneous
Unit 3 Operator logs: October 20-22, 2021
10/22/2021
Miscellaneous
CPC CEAC Trip Buffers
2/06/2021
Miscellaneous
ERFDADS PTARS Data
2/06/2021
Miscellaneous
Plant Performance Evaluation Unit 3
2/06/2021
Miscellaneous
PC Rod Drop Times
2/06/2021
Miscellaneous
Ronan Sequence of Events
2/06/2021
Miscellaneous
PC Alarm Sequence of Events
2/06/2021
Miscellaneous
2-16575-JEG
Safety Limit Evaluation for Unit 3 Cycle 23 Reactor Trip on
December 6, 2021
2/06/2021
Miscellaneous
Event Report for Unit 3 Reactor Trip on December 6, 2021
2/06/2021
Miscellaneous
PVE0647
Plant Transient Review Assessment: Reactor Trip While
Repositioning CEAs to UEL-1 Position
2/06/2021
Procedures
Plant Review Board
Procedures
PPS Variable Over Power Setpoint Adjustment for Power
Ascension After Refueling
Procedures
Loss of Instrument Air
Procedures
Degraded Electrical Power
Procedures
Conduct of Operations
Procedures
Conduct of Operations
Procedures
Power Operations
151
Procedures
Reactor Trip Investigation
Work Orders
253920
FR
HG
EL
LM
VG
NC
MH
JE
PALO VERDE NUCLEAR GENERATING STATION - INTEGRATED INSPECTION REPORT 05000528
DATE
/2021004, 05000529/2021004, AND 05000530/2021004
February 7, 2022