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, Signed by Agrawal, Ami on 02/07/22 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: NPF-41, NPF-51 and NPF-74 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 Enclosure
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 Report Aspect Section Mitigating Green [H.8] - 71111.08P Systems NCV 05000529/2021004-01 Procedure Open/Closed Adherence 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)
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 Report Aspect Section Mitigating Green [H.8] - 71111.08P Systems NCV 05000529/2021004-01 Procedure Open/Closed Adherence 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 Type Designation Description or Title Revision or
Procedure Date
71111.01 Corrective Action 21-14428, 21-14642
Documents
71111.01 Drawings 13-C-ZVA-002 Site Drainage General Arrangement Plan 8
71111.01 Drawings 13-C-ZVC-065 Site Rough Grading Plan Area 1 4
71111.01 Drawings 13-C-ZVC-066 Site Rough Grading Plan Area 2 6
71111.01 Drawings 13-C-ZVC-070 Site Rough Grading Plan Area 6 6
71111.01 Drawings 13-C-ZVC-074 Site Rough Grading Plan Area 10 3
71111.01 Drawings 13-C-ZVC-100 Site Storm Drainage Dikes and Channels Sheet 1 6
71111.01 Procedures 40AO-9ZZ21 Acts of Nature 39
71111.01 Work Orders 4541553
71111.04 Corrective Action 17-06376, 21-15292
Documents
71111.04 Drawings 01-M-AFP-0001 P & I Diagram Auxiliary-Feedwater System 45
71111.04 Drawings 01-M-HJP-001 Control Building HVAC P & I Diagram 27
71111.04 Drawings 02-M-PCP-001 P & I Diagram Fuel Pool Cooling & Cleanup System
71111.04 Drawings 02-M-SPP-001 Essential Spray Pond System 69
71111.04 Miscellaneous 17-06376-002 Design Equivalent Change Package SP-1711 Essential 2
Spray Pond Wall Repair
71111.04 Procedures 40OP-9HJ01 Control Building HVAC (HJ) 37
71111.04 Procedures 40OP-9PC01 Fuel Pool Cooling
71111.04 Procedures 40OP-9SP02 Essential Spray Pond (SP) B 57
71111.04 Procedures 40ST-9AF08 Auxiliary Feedwater Pump AFB-P01 Monthly Valve 6
Alignment
71111.04 Procedures 93DP-0LC07-01 10 CFR 50.59 and 72.48 Administrative Guideline 7
71111.05 Corrective Action 21-09919, 21-10986, 21-11524, 20-12846, 21-13457,
Documents 5387437, 21-15047, FSCCR 5395659, FSCCR 5398202,
FSCCR 5398203, 19-04990, 16-18974
71111.05 Drawings 01-M-FPP-006 P & I Fire Protection System 16
71111.05 Drawings 13-A-ZYD-022 Fire Protection Containment Building Floor Plan at Elevation 12
ft.
71111.05 Miscellaneous Off Site Fire Chief Fire Drill Observation Report 06/24/2021
Inspection Type Designation Description or Title Revision or
Procedure Date
71111.05 Miscellaneous PVGS Pre-Fire Strategies Manual 29
71111.05 Miscellaneous UFSAR, section 9.5.1, Fire Protection System 20C
71111.05 Miscellaneous UFSAR, Appendix 9B, Fire Protection Evaluation Report 20C
71111.05 Miscellaneous Design Basis Manual, Fire Protection System, Section 6.3. 15
Cable Spreading Room
71111.05 Miscellaneous NPL37-D-003C- Unit 1 Fire Drill Summary 06/23/2021
71111.05 Miscellaneous NPL38-D-002B- Unit 1 Fire Drill Summary 08/20/2021
71111.05 Miscellaneous NPL41-D-001A- Unit 1 Fire Drill Summary 10/05/2021
71111.05 Procedures 14DP-0FP02 Fire System Impairments and Notifications 27
71111.05 Procedures 14DP-0FP33 Control of Transient Combustibles 32
71111.07A Calculations 13-MC-DG-0411 DG Heat Exchanger Minimum Flow Rate vs. Inlet SP Water 4
Temperature
71111.07A Calculations 13-MC-DG-0411 DG Heat Exchanger Minimum Flow Rate vs. Inlet SP Water 5
Temperature
71111.07A Calculations 13-MC-SP-0307 SP/EW System Thermal Performance Design Bases 9
Analysis
71111.07A Corrective Action 21-11138, 21-11205, 21-11233, 21-11239, 21-11644, 21-
Documents 11217, 21-11226
71111.07A Procedures 73DP-9ZZ11 Heat Exchanger Program 16
71111.07A Procedures 73DP-9ZZ21 Heat Exchanger Visual Inspection 8
71111.07A Procedures 73TI-9ZZ28 Eddy Current Examination of Tubing 11
71111.07A Work Orders 5174679, 5254569, 5254521, 5254522, 5254523, 5254449,
254450
71111.08P Corrective Action 11-00249, 15-02910, 17-17322, 20-03475, 20-16460, 21-
Documents 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 Type Designation Description or Title Revision or
Procedure 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
71111.08P Corrective Action 21-11808, 21-11814, 21-11815, 21-11818, 21-11820, 21-
Documents 11910, 21-11912, 21-11914, 21-11934, 21-11936, 21-
Resulting from 11975, 21-11977, 21-11982, 21-12001, 21-12048, 21-
Inspection 12059, 21-12062, 21-12284, 21-12486, 21-12491, 21-12493
71111.08P Drawings 13-C-ZCS-0300 Containment Internals Partial Concrete Plan at EL. 80'-0" 16
71111.08P Drawings 13-C-ZCS-0301 Containment Internals Partial Concrete Plan at E
- L. 80'-0", 17
71111.08P Drawings 13-C-ZCS-0361 Containment Internals Steam Generator Foundation 4
Reinforcing Sections and Details
71111.08P Drawings E 77560 & 77560- VALVE ASSY 2 INCH, Y TYPE, 1512 LB, GLOBE, S.W., D
- S.
71111.08P Miscellaneous Relief Request 65 - Unit 2, COVID-19, Request for Relief 03/27/2020
from Bottom Mounted Instrumentation Nozzles and a
Pressurizer Nozzle to Surge Line Weld Overlay Examination
71111.08P Miscellaneous Welder / Brazer Performance Qualification Summary 113
71111.08P Miscellaneous Palo Verde Safety Manual 49
71111.08P Miscellaneous 2-21-00423 Sample Data Sheet - Unit 2 CTMT BLDG 87' ELEV Rm 1A 10/20/2021
RCP Bay
71111.08P Miscellaneous 31MT-9ZZ15 Mechanical Snubber Removal And Reinstallation 32
71111.08P Miscellaneous 4INT-INCO-06 Units 1, 2 & 3 Alloy 600 Management Program Plan 0
71111.08P Miscellaneous 4INT-ISI-2 4th Inspection Interval Inservice Inspection Program 1
Summary Manual PVGS Unit 2
71111.08P Miscellaneous 74DP-9ZZ21-01 RCS Deposits Administrative Guideline 1
71111.08P Miscellaneous ACI 318-71 Building Code Requirements for Reinforced Concrete 10/01/1974
71111.08P Miscellaneous CUP#2899 Nuclear Grade Tape Products 16
71111.08P Miscellaneous CUP#3355 Duct Tape, Non-Nuclear Grade 18
71111.08P Miscellaneous MRP-058 Materials Reliability Program: Boric Acid Corrosion 2
Guidebook, Revision 2: Managing Boric Acid Corrosion
Issues at PWR Power Stations
71111.08P Miscellaneous SDOC No. 02- U2 EW Growth Letter 08/29/2012
Inspection Type Designation Description or Title Revision or
Procedure Date
MN950-A00052
71111.08P NDE Reports 17-VT-2051 Visual Examination for Boric Acid Detection - Closure Head 04/24/2017
CEDM Penetrations
71111.08P NDE Reports 20-VT-2089 Pressure Test Report - RCS PIPING REFUELING 05/21/2020
OUTAGE: Class 1 and Class 2 pressurized and non
pressurized piping inside containment during mode 3
walkdown.
71111.08P NDE Reports 21-PT-2001 RC/2PRCEL096, 2A Drain Line 10/12/2021
71111.08P NDE Reports 21-PT-2002 RC/2PRCEL060 10/12/2021
71111.08P NDE Reports 21-UT-2021 Shutdown Cooling Loop 2 10/14/2021
71111.08P NDE Reports 21-UT-2022 Shutdown Cooling Loop 2 10/14/2021
71111.08P NDE Reports 21-UT-2023 Shutdown Cooling Loop 2 10/14/2021
71111.08P NDE Reports 21-UT-2024 Shutdown Cooling Loop 2 10/14/2021
71111.08P NDE Reports 21-VE-2004 VE bare metal examination of Reactor Vessel ICI 10/11/2021
penetrations (1-31-1 thru 61)
71111.08P NDE Reports 21-VE-2065 VE bare metal examination of Reactor Head CEDM 10/16/2021
penetrations. 2R23 (1 thru 97 including head vent)
71111.08P NDE Reports 21-VT-2009 VT2 of Rx head bolted connection 10/12/2021
71111.08P NDE Reports 21-VT-2034 PC-5-H-11 10/12/2021
71111.08P NDE Reports 21-VT-2035 PC-5-H-11-W 10/12/2021
71111.08P Procedures 01DP-0AP12 Condition Reporting Process 37
71111.08P Procedures 01DP-0AP61 Chemical Control Program 2
71111.08P Procedures 01DP-0FP01 Control of Flammable/Combustible Storage Cabinets 6
71111.08P Procedures 01DP-0XX01 Control and Monitoring of Potential Tornado Borne Missiles 6
71111.08P Procedures 31MT-9SI01 Low Pressure Safety Injection Pump Maintenance 27
71111.08P Procedures 31MT-9SI02 High Pressure Safety Injection Pump Disassembly, 37
Examination and Assembly
71111.08P Procedures 31MT-9SI03 Containment Spray Pump Disassembly And Assembly 26
71111.08P Procedures 40OP-9RC03 RCS Leakage Source Determination 6
71111.08P Procedures 40ST-9RC02 ERFDADS (Preferred) Calculation of RCS Water Inventory 54
71111.08P Procedures 40ST-9SI09 ECCS Systems Leak Test 59
71111.08P Procedures 70TI-9ZC01 Boric Acid Walkdown Leak Detection 25
71111.08P Procedures 73DP-0AP04 Primary Coolant Sources Outside Containment Program 7
Inspection Type Designation Description or Title Revision or
Procedure Date
71111.08P Procedures 73DP-9WP04 Welding and Brazing Control 21
71111.08P Procedures 73DP-9WP05 Weld Filler Material Control 12
71111.08P Procedures 73DP-9ZC01 Boric Acid Corrosion Control Program 10
71111.08P Procedures 73DP-9ZZ16 Testing and Control of PVGS Snubbers 16
71111.08P Procedures 73ST-9ZZ10 Hydraulic Snubber Functional Testing 27
71111.08P Procedures 73ST-9ZZ21 Snubber Visual Examination 18
71111.08P Procedures 73ST-9ZZ22 Mechanical Snubber Function Test 21
71111.08P Procedures 73TI-0ZZ02 Ultrasonic Thickness Measurement 14
71111.08P Procedures 73TI-9RC09 Bare Metal Visual Examination of Reactor Vessel Upper 7
Head
71111.08P Procedures 73TI-9RC10 Bare Metal Visual Examination of Reactor Vessel Bottom 5
Head
71111.08P Procedures 73TI-9SI16 ECCS Sump to RWT Leakage Paths Design Bases Testing 3
71111.08P Procedures 73TI-9ZZ05 Dry Magnetic Particle Examination 19
71111.08P Procedures 73TI-9ZZ07 Liquid Penetrant Examination 19
71111.08P Procedures 73TI-9ZZ10 Ultrasonic Examination of Welds in Ferritic Components 15
71111.08P Procedures 73TI-9ZZ17 Visual Examination of Welds, Bolting, and Components 14
71111.08P Procedures 73TI-9ZZ18 Visual Examination of Component Supports 17
71111.08P Procedures 73TI-9ZZ19 Visual Examination of Pump and Valve Internal Surfaces 16
71111.08P Procedures 73TI-9ZZ22 Visual Examination For Leakage 13
71111.08P Procedures 73TI-9ZZ82 Visual Examination of Metal Containment Building Surfaces 8
71111.08P Procedures EPRI-PIPE-MPA- Procedure for Manual Phased Array Ultrasonic Examination 2
of Austenitic and Ferritic Pipe Welds EPRI-PIPE-MPA-1
71111.08P Procedures EPRI-PIPE-TWS- Procedure for Manual Phased Array Ultrasonic Through- 1
MPA-1 Wall Sizing In Pipe Welds EPRI-PIPE-TWS-MPA-1
71111.08P Procedures PDI-UT-1 PDI Generic Procedure for the Ultrasonic Examination of G
Ferritic Pipe Welds PDI-UT-1
71111.08P Procedures PDI-UT-10 PDI Generic Procedure for the Ultrasonic Examination of G
Dissimilar Metal Welds, PDI-UT-10
71111.08P Procedures PDI-UT-11 PDI Generic Procedure for the Ultrasonic Examination of D
Reactor Pressure Vessel Nozzle-to-Shell Welds and the
Nozzle Inner Corner Radius PDI-UT-11
Inspection Type Designation Description or Title Revision or
Procedure Date
71111.08P Procedures PDI-UT-2 PDI Generic Procedure for the Ultrasonic Examination of I
Austenitic Pipe Welds PDI-UT-2
71111.08P Procedures PDI-UT-3 PDI Generic Procedure for the Ultrasonic Through-Wall G
Sizing of Planar Flaws in Similar Metal Piping Welds PDI-
UT-3
71111.08P Procedures PDI-UT-5 PDI Generic Procedure for the Straight Beam Ultrasonic G
Examination of Bolts and Studs PDI-UT-5
71111.08P Procedures PDI-UT-8 PDI Generic Procedure for the Ultrasonic Examination of I
Weld Overlaid Similar and Dissimilar Metal Welds, PDI-UT-8
71111.08P Self-Assessments 20-04629-001 INPO MRV NDE SIMPLE SELF-ASSESSMENT 06/30/2020
71111.08P Self-Assessments SWMS#17-09564 Welding Program Self Assessment 06/30/2017
71111.08P Self-Assessments SWMS#18- ISI Simple Self Assessment 04/02/2019
14430-002
71111.08P Self-Assessments SWMS#20- Alloy 600 07/23/2020
04621-002
71111.11Q Miscellaneous NLR21S050401 Licensed Operator Continuing Training Simulator Scenario: 11/16/2021
Fire with Spurious Equipment Actuations
71111.11Q Miscellaneous SES-0-05-P-10 Licensed Operator Continuing Training Simulator Evaluation 11/16/2021
Scenario: SIT 1B Air Leak / Control Channel NI #1 Fails
Low / RCP 2A Trip / ATWS / ESD
71111.11Q Procedures 40DP-9OPP02 Conduct of Operations 76
71111.11Q Procedures 73ST-9SI06 Containment Spray Pumps and Check Valves - Inservice 45
Test
71111.11Q Work Orders 5271728
71111.12 Corrective Action 21-08461, 21-06710, 21-09763, 21-09485, 18-17577, 19-
Documents 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
71111.12 Miscellaneous Guidance on Overhaul of Magne-Blast Circuit Breakers 12/2000
71111.12 Miscellaneous Performance Criteria Formulation Bases for SA System 4
(Engineered Safety Features Actuation System)
71111.12 Miscellaneous Vendor Technical Document VTD-C150-0017, Carrier N/A
Corporation 19FA Centrifugal Chiller Parts Catalog S/N
26507-26512
Inspection Type Designation Description or Title Revision or
Procedure Date
71111.12 Miscellaneous Mrule Performance Monitor Group information for Essential
Chilled Water B
71111.12 Miscellaneous Unit 2 Control room logs for 09/17/2021-12/16/2021
71111.12 Miscellaneous Unit 3 Control Room Logs January 1 - December 28, 2021 12/29/2021
71111.12 Miscellaneous MRule Manager Data for Unit 3 SA DAFAS A and B 12/29/2021
71111.12 Miscellaneous 13-NS-C025 Risk Informed Performance Criteria 9
71111.12 Miscellaneous SA-02323 SA - DAFAS A/B Maintenance Rule (a)(1) Issue Tracking 0
Form
71111.12 Miscellaneous SA-02323 SA - DAFAS A/B Maintenance Rule (a)(1) Issue Tracking 1
Form
71111.12 Miscellaneous SAL 361.1 Service Advisory Letter 1
71111.12 Miscellaneous TR-109641 Guidance on Routine Preventive Maintenance for Magne- 10/1998
Blast Circuit Breakers
71111.12 Procedures 01DP-0AP12 Condition Reporting Process 38
71111.12 Procedures 32MT-9ZZ34 Maintenance of AM-4.16-250-9H GE Magne-Blast Circuit 40
Breakers
71111.12 Procedures 32MT-9ZZ38 Overhaul of AM-4.16-250-9H GE Magne-Blast Circuit 26
Breakers
71111.12 Procedures 33MT-9EC01 Essential Chiller 15
71111.12 Procedures 40OP-9EC02, Essential Chilled Water Train B 34
71111.12 Procedures 40OP-9SF01 Control Element Drive Mechanism Control System 31
(CEDMCS) Operation
71111.12 Procedures 70DP-0MR01 Maintenance Rule 46
71111.12 Work Orders 5152532, 5235964, 5218289, 5218290, 5279220, 5360915,
5380847, 5258452, 5257990
71111.13 Corrective Action 21-13903, 21-13663, 21-13799
Documents
71111.13 Miscellaneous Phoenix Risk Monitor - PVGS Unit 1 Current Risk Summary
Report as of 11/18/2021
71111.13 Miscellaneous U1 PHOENIX RICT November 18, 2021 Operator Screen 11/18/2021
Risk at 0433
71111.13 Miscellaneous Work Week 2146 Schedule Risk Evaluation, 11/15/2021-
11/21/2021
71111.13 Miscellaneous Risk Management and Readiness Plan: U2 A ESFAS PS 0
Inspection Type Designation Description or Title Revision or
Procedure Date
Replacement
71111.13 Miscellaneous Work Week 2147 Schedule Risk Evaluation 11/22/2021-
11/28/2021
71111.13 Procedures 02DP-0RS01 Online Integrated Risk 9
71111.13 Procedures 40DP-9RS01 Operations Department Online Nuclear Risk Determination 7
Modes 1 and 2
71111.13 Procedures 40DP-9RS04 RICT PRA Functionality Determination 1
71111.13 Procedures 40DP-9RS05 Calculation of RMAT and RICT 0
71111.13 Procedures 73ST-9XI37 Safety Injection Tank Nitrogen Vent Valves-Inservice Test 9
71111.13 Work Orders 5389532, 5388714, 5390168
71111.15 Calculations 13-CC-ZC-0285 Heat Sink Calculations Containment Building 14
71111.15 Calculations 13-NC-ZC-0237 Maximum Passive Heat Sink for Hydrogen Generation & 7
ECCS Evaluation
71111.15 Calculations N001-1106-00002 Debris Generation Due to LOCA Within Containment for 3
Resolution of GSI-191
71111.15 Corrective Action 21-12899, 21-12438, 21-12529, 21-12563, 21-12578, 21-
Documents 12585, 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
71111.15 Drawings 02-M-SIP-001 Safety Injection & Shutdown Cooling System 56
71111.15 Drawings 02-P-SPF-701 Diesel Generator BLDG. ISO Essential Pray Pond System 3
Train A & B
71111.15 Drawings 02-P-ZYA-0926 Essential Pipe Tunnel piping sections and details 0
71111.15 Drawings 02-P-ZYA-0926 Essential Pipe Tunnel Piping Plan 1
71111.15 Drawings 03-M-SIP-002 P & I Diagram: Safety Injection and Shutdown Cooling 38
System
71111.15 Engineering 2018-00492
Changes
71111.15 Miscellaneous Engineering Evaluation 21-12899-003
71111.15 Miscellaneous PVNGS Design Basis Manual, Essential Spray Pond 23
System
71111.15 Miscellaneous Technical Documents 269457, 274560,274776, 274816,
Inspection Type Designation Description or Title Revision or
Procedure Date
274835, 274865, 274922, 274962, 424156
71111.15 Miscellaneous Updated Final Safety Analysis Report 21
71111.15 Miscellaneous Design Basis Manual: Essential Chilled Water System 18
71111.15 Miscellaneous PVNGS Technical Specification Bases 72
71111.15 Miscellaneous UFSAR Section 9.2.9.2, Essential Chilled Water Systems 21
71111.15 Miscellaneous PVGNS Design Basis Manual, Auxiliary Feedwater System 26
71111.15 Miscellaneous Design Basis Manual: Safety Injection System 41
71111.15 Miscellaneous PVNGS Technical Specification Bases 72
71111.15 Miscellaneous UFSAR Section 15.6.5, Loss-Of-Coolant Accidents 21
71111.15 Miscellaneous UFSAR Section 6.3.3a, LOCA Analysis - CE16STD Fuel 21
71111.15 Miscellaneous Unit 2 Operator Logs, December 20-28, 2021 12/28/2021
71111.15 Miscellaneous Unit 2 Operator Logs, November 11-18, 2021 12/28/2021
71111.15 Miscellaneous 13-MS-A137 Engineering Study, Development of AF System Pipe Arc 1
Length Acceptance Criteria Associated with Calculated Max
Void Volumes
71111.15 Miscellaneous 21-11296-003 MRFF (Maintenance Rule Functional Failure) Evaluation
71111.15 Miscellaneous 21-13294-004 Engineering Evaluation
71111.15 Miscellaneous EER 90-DG-030 Engineering Evaluation Request 04/16/1990
71111.15 Miscellaneous Study 13-NS- Mission time for Operability Determinations 1
C088
71111.15 Procedures 36ST-9AF02 Train B Auxiliary Feedwater Flow Instrumentation Calibration 9
71111.15 Procedures 40DP-9OP19 Locked Valve, Breaker, and Component Tracking 140
71111.15 Procedures 40DP-9OP26 Operations Condition Reporting Process and Operability 47
Determination/Functional Assessment
71111.15 Procedures 40DP-9OPA4 Control Building Watch Station Rounds 125
71111.15 Procedures 40ST-9SI09 ECCS Systems Leak Test 60
71111.15 Procedures 73ST-9AF05 Auxiliary Feedwater Pump B - Comprehensive Pump Test 19
71111.15 Procedures 73ST-9XI04 SI Train B Valves - Inservice Test 40
71111.15 Procedures 73ST-9XI04 SI Train B Valves - Inservice Test 41
71111.15 Work Orders 4922485, 4922486, 5061531, 5057504, 5373506, 5241560,
263109, 5216987, 5191806, 5395606, 5388830, 5388912,
275397, 5273625, 5267591
71111.18 Corrective Action 21-11851, 21-11695
Inspection Type Designation Description or Title Revision or
Procedure Date
Documents
71111.18 Drawings 02-M-CHP-0001 P&I Diagram Chemical and Volume Control System 38
71111.18 Drawings 02-M-RDP-0001 P&I Diagram Radioactive Waste Drain System (Containment 16
Building)
71111.18 Miscellaneous PVNGS UFSAR 21
71111.18 Miscellaneous 21-F014 Licensing Document Change Request 0
71111.18 Miscellaneous PVNGS DBM Chemical and Volume Control System 26
71111.18 Miscellaneous S-21-0043 10CFR50.59 Screening/Evaluation 0
71111.18 Work Orders 5380370
71111.19 Corrective Action 21-07164, 21-11226, 21-14350, 21-14377, 21-13545, 21-
Documents 13557, 21-12088, 21-12485, 21-15116
71111.19 Miscellaneous Unit 1 Control room logs 10/01/2021-
10/03/2021
71111.19 Miscellaneous Unit 2 control room logs for October 2021
71111.19 Miscellaneous TD 276657 Operations Technical Document to Comply with Tech Spec 12/02/2021
3.6.3 for SIA-UV-627 Inoperability
71111.19 Miscellaneous TD 276657 Operations Technical Document to Comply with Tech Spec 12/04/2021
3.6.3 for SIA-UV-627 Inoperability
71111.19 Procedures 32MT-9PE01 Cleaning, Inspecting, and Testing of the Class 1E Diesel 47
Generator
71111.19 Procedures 32MT-9ZZ74 Molded Case Circuit Breaker Test 53
71111.19 Procedures 32ST-9SB02 18 Month Surveillance Test for Westinghouse Type DS-416 8
Reactor Trip Breakers
71111.19 Procedures 33MT-9EC01 Essential Chiller 15
71111.19 Procedures 36ST-9SB44 RPS Matric Relays to Reactor Trip Response Time Test 25
71111.19 Procedures 36ST-9SB52 RTSG Shunt and Undervoltage Trip Functional Test 12
71111.19 Procedures 40DP-9OP18 Motor Operated Valves Operating Guidelines 24
71111.19 Procedures 40DP-9OP19 Locked Valve, Breaker, and Component Tracking 140
71111.19 Procedures 40OP-9PH01 Train A 480V Class 1E MCC 16
71111.19 Procedures 40ST-9DG01 Diesel Generator A Test 51
71111.19 Procedures 40ST-9SI09 ECCS Systems Leak Test 60
71111.19 Procedures 73DP-9ZZ05 Lubrication of Plant Equipment 37
71111.19 Procedures 73ST-9XI20 ADVs - Inservice Test 57
Inspection Type Designation Description or Title Revision or
Procedure Date
71111.19 Procedures 77ST-9SB22 CEA Drop Time Test 15
71111.19 Work Orders 5256867, 5224848, 5254445, 5136175, 5254471, 5256018,
5303866, 5258250, 5270389, 5320369, 5393374, 5258452,
257990, 5382122, 5277571, 5277252, 5282209, 5250921,
249295, 5250944, 5250885
71111.20 Corrective Action 21-03767, 21-09919, 21-11334, 21-11665, 21-11674, 21-
Documents 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
71111.20 Miscellaneous Unit 2 Cycle 23 Specific Maneuver Plan: EOC Coastdown 0
71111.20 Miscellaneous Unit 2 Cycle 23 Standard Maneuver Plan: EOC Shutdown 0
81.93% to 20%
71111.20 Miscellaneous Unit Two 23rd Refueling Outage Shutdown Risk 0
Assessment Team Review Report
71111.20 Miscellaneous CN390-A00183, Safety Analysis Report for Single Failure 0
Proof Trolley (NUREG 0554)
71111.20 Miscellaneous Fatigue Assessment for Technician Following Arc Flash 10/23/2021
Event
71111.20 Miscellaneous21-009 2R23 Refueling Outage Restart PRB Package 0
71111.20 Miscellaneous MN725-A00935 RSB 5-1 Natural Circulation Cooldown Analysis for Power 4
Uprate and SG Replacement at Palo Verde Nuclear
Generating Station Units 1, 2, and 3
71111.20 Procedures 30DP-0MP13 PVGS Rigging Control 27
71111.20 Procedures 30DP-9MP11 Field Use of Rigging 44
71111.20 Procedures 31MT-9RC30 Reactor Vessel Head Removal and Installation 60
71111.20 Procedures 40DP-9RS02 Shutdown Risk Management 6
71111.20 Procedures 40OP-9PC05 Augmentation of Fuel Pool Cooling with Shutdown Cooling 39
71111.20 Procedures 40OP-9SI01 Shutdown Cooling Initiation 58
71111.20 Procedures 40OP-9ZZ03 Initial Reactor Startup Following Refuelings 61
71111.20 Procedures 40OP-9ZZ04 Weekly Shutdown Electrical Distribution Checks 25
71111.20 Procedures 40OP-9ZZ05 Power Operations 151
71111.20 Procedures 40OP-9ZZ11 Mode Change Checklist 104
71111.20 Procedures 40OP-9ZZ23 Outage GOP 85
71111.20 Procedures 40OP-9ZZ26 Tracking Containment Penetrations 29
Inspection Type Designation Description or Title Revision or
Procedure Date
71111.20 Procedures 40ST-9RC01 RCS and Pressurizer Heatup and Cooldown Rates 21
71111.20 Procedures 40ST-9ZZ01 Locked Valve Monthly Surveillance 7
71111.20 Procedures 40ST-9ZZM1 Operations Mode 1 Surveillance Logs 74
71111.20 Procedures 40ST-9ZZM13 Containment Isolation Valves 17
71111.20 Procedures 51DP-9OPM09 Outage Planning and Implementation 20
71111.20 Procedures 70DP-0RA01 Shutdown Risk Assessments 62
71111.20 Procedures 72PY-9RX06 Low Power Physics Testing Using STAR 10
71111.20 Work Orders 5257823
71111.22 Calculations 13-JC-SI-0215 Containment Spray Pump Discharge Flow Indication Loops 18
(SIA-F-338 & SIB-F-348) Uncertainty Calculation
71111.22 Corrective Action 18-14867, 17-11850, 21-13811, 21-12417, 21-12422
Documents
71111.22 Drawings 02-M-SIP-001 P & I Diagram: Safety Injection & Shutdown Cooling System 56
71111.22 Miscellaneous Unit 3 Operator logs: November 16, 2021 11/16/2021
71111.22 Procedures 30DP-9MP01 Conduct of Maintenance 84
71111.22 Procedures 40OP-9OP43 M&TE Gage Installation 2
71111.22 Procedures 73DP-9XI01 Pump and Valve Inservice Testing Program 41
71111.22 Procedures 73ST-9CL01 Containment Leakage Type B and C Testing 49
71111.22 Procedures 73ST-9EC01 Essential Chilled Water Pumps - Inservice test 29
71111.22 Procedures 73ST-9EW01 Essential Cooling Water Pumps - Inservice test 35
71111.22 Procedures 73ST-9SI06 Containment Spray Pumps and Check Valves - Inservice 45
Test
71111.22 Procedures 73ST-9SI06 Containment Spray Pumps and Check Valves - Inservice 45a
71111.22 Work Orders 5266875, 5266874, 5271728
71114.06 Corrective Action 21-14084, 21-14076
Documents
71114.06 Procedures EP-0900-011 ERO Positions Emergency Operations Director (EOF) 1
71114.06 Procedures EP-0902 Notifications 18
71114.06 Procedures EP-0904 ERO/ERF Activation and Operation 13
71114.06 Procedures EP-0905 Protective Actions 13
71124.01 Corrective Action 20-13969, 20-14285, 20-14744, 20-14974, 20-15826, 21-
Documents 01194, 21-02640, 21-03646, 21-03835, 21-04318, 21-
04730, 21-05021, 21-05093, 21-05120, 21-05271, 21-
Inspection Type Designation Description or Title Revision or
Procedure Date
05625, 21-05694, 21-06192, 21-10277, 21-11100, 21-
11774, 21-12245
71124.01 Miscellaneous Radiological Safety Trends 08/31/2021
71124.01 Procedures 75DP-0RP01 RP Program Overview 12
71124.01 Procedures 75DP-9RP01 Radiation Exposure and Access Control 23
71124.01 Procedures 75DP-9RP01 Radiation Exposure and Access Control 23
71124.01 Procedures 75RP-0RP01 Radiological Posting and Labeling 36
71124.01 Procedures 75RP-9ME23 Exposure Evaluation for Lost, Damaged, or Abnormally 14
Indicating Dosimetry
71124.01 Procedures 75RP-9OP02 Control of High Radiation Areas, Locked High Radiation 32
Areas, and Very High Radiation Areas
71124.01 Procedures 75RP-9RP02 Radiation Work Permits 32
71124.01 Procedures 75RP-9RP15 Control and Storage of Radioactive Material and Radioactive 31
Wastes
71124.01 Procedures 75RP-9RP18 Medical Uptakes of Radioisotopes 9
71124.01 Procedures 75RP-9RP29 Radiological Job Coverage 13
71124.01 Procedures NISP-RP-102 Access for Visitors, Escorted Workers and SRD Only 0
Workers
71124.01 Radiation 2-M-20211017-12 140' E cavity CEA cut up area 10/17/2021
Surveys
71124.01 Radiation 3-M-20210412-27 CNTMT South Pump Bay 87' (RCP 2a and 2B) 04/12/2021
Surveys
71124.01 Radiation 3-M-20210426-21 80' Cntmt New HRA,RPHP posting 04/26/2021
Surveys
71124.01 Radiation 3-M-20210427-31 Investigation of dose rate alarm 04/27/2021
Surveys
71124.01 Radiation 3-M-20210721-2 120' Evap Dose Rate Alarm Investigation 07/21/2021
Surveys
71124.01 Radiation Work 2-3000-R23 Control Element Assembly (CEA) Replacement 0
Permits (RWPs)
71124.01 Radiation Work 2-3319-R23 Reactor Coolant Pump Maintenance w/ Motor Replacement 0
Permits (RWPs)
71124.01 Radiation Work 2-3502-R23 Valve, Flange and Pump Maintenance and Inspection 0
Permits (RWPs)
Inspection Type Designation Description or Title Revision or
Procedure Date
71124.01 Radiation Work 2-3518-R23 High Risk - Minor Maintenance in the 120'/127' Regenerative 0
Permits (RWPs) Heat Exchanger Cubicle
71124.01 Radiation Work 3-3504 Minor Maintenance 9
Permits (RWPs)
71124.01 Radiation Work 9-1009 Minor Maintenance 5
Permits (RWPs)
71124.01 Radiation Work 9-1020 Visitor and Escort Tours, Visual Inspections, and Work on 0
Permits (RWPs) Non-Plant Systems or Components
71124.01 Self-Assessments 302-03863 September 2020 Offsite Safety Review Committee Meeting 10/01/2020
20-002, Operations, Chemistry and Radiation Protection
Subcommittee Report
71124.01 Self-Assessments 302-03876 March 2021 Offsite Safety Review Committee (OSRC) 03/25/2021
RJA/RJA Meeting 21-001, Operations, Chemistry and Radiation
Protection Subcommittee Report
71124.01 Self-Assessments Audit 2020-004 Radiation Safety 08/06/2021
71124.02 Corrective Action 20-03640, 20-10685, 20-10881, 20-13950, 20-16029, 21-
Documents 01305, 21-03030, 21-04127, 21-04934, 21-07369, 21-
226, 21-08725, 21-09027
71124.02 Miscellaneous PVGS Radiological Safety Trends 09/06/2021
71124.02 Miscellaneous Palo Verde Generating Station ALARA 5-Year Plan 2018- 10/25/2018
22
71124.02 Miscellaneous Draft Palo Verde Generating Station ALARA 5-Year Plan 10/2021
21-2025
71124.02 Miscellaneous 218-04731 2020 Annual Radiation Protection Program Summary Report 08/25/2021
71124.02 Procedures 75DP-0RP01 RP Program Overview 12
71124.02 Procedures 75DP-0RP03 ALARA Program Overview 6
71124.02 Procedures 75DP-0RP06 ALARA Committee 9
71124.02 Procedures 75DP-0RP08 Managing Radiological Risk 3
71124.02 Procedures 75RP-0RP04 Radiation Protection Periodic Review Program 6
71124.02 Procedures 75RP-9RP02 Radiation Work Permits 32
71124.02 Procedures 75RP-9RP12 ALARA Reports 6
71124.02 Procedures 75RP-9RP16 Special Dosimetry 26
71124.02 Procedures 75RP-9RP26 Radioactive Source Control 17
71124.02 Procedures 75TD-9RP02 ALARA Work Planning 13
Inspection Type Designation Description or Title Revision or
Procedure Date
71124.02 Radiation 2-M-20211009-5 C100 Elevation Overview Containment 10/09/2021
Surveys
71124.02 Radiation 2-M-20211009-8 C140 Elevation Overview Containment 10/09/2021
Surveys
71124.02 Radiation 2-M-20211014-11 Refueling Pool (Enlarged) 140' 10/14/2021
Surveys
71124.02 Radiation 2-M-20211017-12 140' East Cavity CEA Cut Up Area 10/17/2021
Surveys
71124.02 Radiation 2-O-20211016-2 Free Release a PZR Fan Impellor Shaft 10/16/2021
Surveys
71124.02 Radiation 3-M-20210423-1 Unit 3 117' 2A RCP Bay / SIEV227 - Removal of Internals 04/23/2021
Surveys
71124.02 Radiation 3-M-20210526-4 3PSIEV227 Internals of Unit 3 05/26/2021
Surveys
71124.02 Radiation Work 2-3000-R23 Control Element Assembly (CEA) Replacement 0
Permits (RWPs)
71124.02 Radiation Work 2-3002-R23 Reactor Destack and Restack 8
Permits (RWPs)
71124.02 Radiation Work 2-3503 General Tours, Inspections and Job Planning Walkdowns 0
Permits (RWPs)
71124.02 Radiation Work 2-3504-R23 Minor Maintenance 0
Permits (RWPs)
71124.02 Radiation Work 2-3512-R23 Install / Remove Temporary Shielding 0
Permits (RWPs)
71124.02 Radiation Work 3-3521-03 3R22 High Risk Inboard Loop Discharge Check Valve Work 3
Permits (RWPs)
71124.02 Self-Assessments 20-10685-001 PVGS Integrated Performance Assessment Report: 07/24/2020
Radiation Protection 1st Half 2020
71124.02 Self-Assessments 2020-004 Nuclear Assurance Department (NAD) Audit Report: 08/06/2021
Radiation Safety
71124.02 Self-Assessments 218-04716 PVGS 2020 Annual ALARA/Management Evaluations 06/29/2021
Report
71124.03 Corrective Action 20-15807, 21-04915, 21-07758, 21-09097
Documents
Inspection Type Designation Description or Title Revision or
Procedure Date
71124.03 Drawings Control Building HVAC System (HJ)
71124.03 Drawings Auxiliary Building HVAC System (HA)
71124.03 Drawings Fuel Building HVAC System (HF)
71124.03 Miscellaneous 5 Year Hydrostatic Cylinder Report 10/19/2021
71124.03 Miscellaneous Unit 2 control room - self contained breathing apparatus
October 2021 inspection report
71124.03 Miscellaneous Self-Contained Breathing Apparatus (SCBA) test report for 04/13/2021
SCBA # LAC-240-936
71124.03 Miscellaneous SCBA test report for SCBA # LAC-240-932 04/13/2021
71124.03 Miscellaneous Process Change Package # 5265776 10/11/2020
71124.03 Procedures 01DP-0EM20 Respirator Fit Test 2
71124.03 Procedures 01DP-0IS08 PVGS Respiratory Protection Equipment Usage 24
71124.03 Procedures 01DP-0IS10 PVGS Respiratory Protection Program 14
71124.03 Procedures 14DP-0FP42 Respiratory Equipment Inspection and Repair 1
Documentation
71124.03 Procedures 33DP-0AP03 Ventilation Filter Testing Program (VTFP) 8
71124.03 Procedures 33ST-9HF01 Surveillance Testing for the Aux/Fuel Building Nuclear Air 23
Treatment System
71124.03 Procedures 33ST-9HJ02 Surveillance Testing of the Control Room Nuclear Air 22
Treatment System
71124.03 Procedures 33ST-9HJ03 Carbon Analysis for the Control Room Essential Nuclear Air 14
Treatment System
71124.03 Procedures 40ST-9HF01 Train ESF Pump Room and Fuel Building Ventilation 20
System Operability/Functionality Test
71124.03 Procedures 40ST-9HJ01 Control Room Essential Filtration System Operability Test 21
71124.03 Procedures 75RP-9EE07 Operation of the AMS-4 CAM 24
71124.03 Procedures 75RP-9RP08 Radiological Air Sampling 1
71124.03 Procedures 75RP-9RP20 Use of control of HEPA Filtration and Vacuum Equipment 5
71124.03 Work Orders STWO #4915279 Surveillance test package for unit 2 control room nuclear air 05/18/2020
treatment system
71124.03 Work Orders STWO #4986418 Surveillance test package for unit 1 control room essential 06/10/2019
air treatment system
71124.05 Procedures 74RM-9EF43 Actions for Non-Functional Radiation Monitors: Preplanned 18
Inspection Type Designation Description or Title Revision or
Procedure Date
Alternate Sampling Program
71124.05 Procedures 75RP-9EQ65 Calibration and Response Check of the Thermo Fisher 4
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 10/21/2021
Report
71151 Miscellaneous Unit 2 PVNGS Radioactive Effluent Release Permit Summary 10/21/2021
Report
71151 Miscellaneous Unit 3 PVNGS Radioactive Effluent Release Permit Summary 10/21/2021
Report
71151 Procedures 40DP-9LC01 Performance Indicator - Barrier Integrity Cornerstone: RCS 4
Leak Rate
71151 Procedures 40ST-9RC02 ERFDADS (Preferred) Calculation for RCS Water Inventory 54
71151 Procedures 74CH-9ZZ15 Dose Equivalent Xe-133 and Dose Equivalent I-131 8
Determination
71151 Procedures 74DP-0LC01 RCS Activity Performance Indicator 7
71151 Procedures 74ST-9RC02 Reactor Coolant System Specific Activity Surveillance Test 17
71151 Procedures 75RP-0LC01 Performance Indicator Occupational Radiation Safety 5
Cornerstone
71151 Procedures 75RP-0LC02 Performance Indicator Public Radiation Safety Cornerstone 5
71152 Corrective Action 21-00423, 21-01559, 21-01940, 21-03483, 21-03485, 21-
Documents 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
71152 Corrective Action Condition Reports 19-15831, 20-04589, 20-11549, 20-11613, 20-11830, 20-
Documents 12157, 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
71152 Corrective Action Condition Reports 21-04020, 21-05447, 21 08513, 21-12356, 21-13833
Documents (Non)
71152 Corrective Action Level 4 Evaluate the Current Alternate Methods/Compensatory 10/01/2021
Documents Evaluation Report Actions for Emergency Planning Classifications When the
Inspection Type Designation Description or Title Revision or
Procedure Date
21-10262-003 Seismic Monitor is Nonfunctional
71152 Corrective Action Condition Report 21-13938, 21-14096, 21-14281
Documents
Resulting from
Inspection
71152 Drawings Palo Verde Topology 0
71152 Engineering 13-JS-B005 Critical System Determination 4
Evaluations
71152 Engineering OMA-SB-01 Ongoing Monitoring and Assessment (OM&A) Report 0
Evaluations Reactor Protection System (SB) Group 1 & 2, Core
Protection Calculator
71152 Engineering OMA-SB-04 Ongoing Monitoring and Assessment (OM&A) Report 0
Evaluations Reactor Protection (SB) Units 1,2,3, Group 4, CPC
Communication Devices
71152 Engineering OMA-SB-05 Ongoing Monitoring and Assessment (OM&A) Report 0
Evaluations Reactor Protection (SB) Units 1,2,3 Group 5, Converters
71152 Miscellaneous Common Controls Spreadsheet 09/07/2021
71152 Miscellaneous Cyber Security Excellence Plan 10/28/2021
71152 Miscellaneous Palo Verde Nuclear Generation Station Cyber Security Plan 3
(CSP)
71152 Miscellaneous Palo Verde Nuclear Generating Station, Alert December 15, 01/12/2017
2016 Event Summary Report
71152 Miscellaneous Unit 1, 2, 3 Night Order, Seismic Monitor Non-Functional 09/02/2021
71152 Miscellaneous Unit 1, 2, 3 Night Order, Seismic Monitor Non-Functional 09/03/2021
71152 Miscellaneous Licensed Operator Continuing Training 2019-2024 6 Year 4
Long Range Training Plan
71152 Miscellaneous Actual Event Investigation, Seismic Occurrence on 7/4/2019 07/19/2019
- 19-09910-002
71152 Miscellaneous Temporary Approved Procedure Action (TAPA), Procedure 09/02/2021
Number 79IS-9SM01, Revision Number 27, TAPA Letter: A
71152 Miscellaneous Level 3 Evaluation Report 18-02668-002 03/22/2018
71152 Miscellaneous 01DP-0AP59-07 Trend Analysis Administrative Guideline 0
71152 Miscellaneous 102-06866-AKK Palo Verde Nuclear Generation Station (PVNGS) Units 1, 2, 04/10/2014
and 3 and Independent Spent Fuel Storage Installation;
Inspection Type Designation Description or Title Revision or
Procedure 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
71152 Miscellaneous 102-07135- Palo Verde Nuclear Generating Station (PVNGS) Units 1, 2, 10/09/2015
MLL/TNW/DCE 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
71152 Miscellaneous 102-07255- Palo Verde Nuclear Generating Station (PVNGS) Units 1, 2, 05/12/2016
MLL/JF/DCE 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
71152 Miscellaneous CVE-2020-1350 Windows DNS Server Vulnerability 0
71152 Miscellaneous Form 2212 Digital Asset Data Sheet
71152 Miscellaneous Form PV-E0046 Contract Personnel Exit Checklist 27
71152 Miscellaneous Form PV-E0059 Leader Checklist for Exiting Employees 39
71152 Miscellaneous Lesson Plan Acts of Nature 02/05/2019
Number:
NKASMC032104
71152 Miscellaneous Lesson Plan Seismic Monitoring System 9/27/2013
Number:
NKASYC015904
71152 Miscellaneous Lesson Plan Seismic Monitoring System Lesson Plan 04/06/2020
Number:
NKASYC015907
71152 Miscellaneous Lesson Plan Deliberate Acts and Acts of Nature 11/06/2018
Number:
NNR18C060500
71152 Miscellaneous ODP-1 Operations Principles and Standards 44
71152 Miscellaneous ODP-31 Operations Emergency Plan Implementation 5
Inspection Type Designation Description or Title Revision or
Procedure Date
71152 Miscellaneous Repetitive Tasks 199478, 204678, 205318, 205319, 205459, 205460, 205461
71152 Miscellaneous Wireless March, July, & September 2021
Walkdown
Results
71152 Miscellaneous Work Work Scope Excerpt
Authorization
210174
71152 Miscellaneous Work Scope 5153648, 5321051, 5321491, 5342806, 5348690, 5348691,
Library (WSL) 5348692, 5369985
71152 Procedures 01DP-0AP09 Procedure and Work Instruction Use and Adherence 19
71152 Procedures 01DP-0AP12 Condition Reporting Process 38
71152 Procedures 01DP-0AP16 Conduct of Organizational Effectiveness 12
71152 Procedures 01DP-0AP59 Conduct of Organizational Effectiveness 7
71152 Procedures 12DP-0MC08 Control of Purchasing Material and Equipment 37
71152 Procedures 12DP-0MC25 Stores 40
71152 Procedures 16DP-0EP31 Emergency Preparedness Equipment Out of Service 13
71152 Procedures 20DO-0SK39 Palo Verde Badging Procedure 41
71152 Procedures 20DP-0SK40 Access Authorization 46
71152 Procedures 22DP-0AC01 Vulnerability Assessments and Scans 2
71152 Procedures 22DP-0AC04 Cyber Security Incident Response 4
71152 Procedures 22DP-0AC05 Cyber Security Alerts and Advisories 4
71152 Procedures 22DP-0AC06 PVGS Critical Digital Asset (CDA) Management 9
71152 Procedures 22DP-0AC08 Ongoing Monitoring and Assessment 3
71152 Procedures 22DP-0AC10 Palo Verde Cyber Security Defensive Strategy 0
71152 Procedures 22DP-0SK03 Management of Cyber Security Security-Related Keys and 1
Accounts/Passwords
71152 Procedures 40AL-9RK7C Panel B07C Alarm Responses 15, 17, 18
71152 Procedures 40AO-9ZZ21 Acts of Nature 37, 39
71152 Procedures 40DP-9OP02 Conduct of Operations 72, 76
71152 Procedures 40DP-9OP33 Shift Turnover 36
71152 Procedures 79IS-9SM01 Analysis of Seismic Event 27
71152 Procedures EP-0901 Classifications 12
71152 Work Orders 5321491
Inspection Type Designation Description or Title Revision or
Procedure Date
71153 Corrective Action 21-12450, 21-12443, 21-12479, 21-12478, 21-12511, 21-
Documents 12436, 21-14531, 21-14464, 21-14465, 21-14478, 21-
14480, 21-14488
71153 Miscellaneous Unit 1 Operator logs: October 20-22, 2021 10/22/2021
71153 Miscellaneous Unit 2 Operator logs: October 20-21, 2021 10/21/2021
71153 Miscellaneous Unit 3 Operator logs: October 20-22, 2021 10/22/2021
71153 Miscellaneous CPC CEAC Trip Buffers 12/06/2021
71153 Miscellaneous ERFDADS PTARS Data 12/06/2021
71153 Miscellaneous Plant Performance Evaluation Unit 3 12/06/2021
71153 Miscellaneous PC Rod Drop Times 12/06/2021
71153 Miscellaneous Ronan Sequence of Events 12/06/2021
71153 Miscellaneous PC Alarm Sequence of Events 12/06/2021
71153 Miscellaneous 162-16575-JEG Safety Limit Evaluation for Unit 3 Cycle 23 Reactor Trip on 12/06/2021
December 6, 2021
71153 Miscellaneous EN 55626 Event Report for Unit 3 Reactor Trip on December 6, 2021 12/06/2021
71153 Miscellaneous PVE0647 Plant Transient Review Assessment: Reactor Trip While 12/06/2021
Repositioning CEAs to UEL-1 Position
71153 Procedures 02DP-0AO01 Plant Review Board 25
71153 Procedures 36MT-9SB08 PPS Variable Over Power Setpoint Adjustment for Power 5
Ascension After Refueling
71153 Procedures 40AO-9ZZ06 Loss of Instrument Air 45
71153 Procedures 40AO-9ZZ12 Degraded Electrical Power 76
71153 Procedures 40DP-9OP02 Conduct of Operations 75
71153 Procedures 40DP-9OP02 Conduct of Operations 76
71153 Procedures 40OP-9ZZ05 Power Operations 151
71153 Procedures 90DP-0IP06 Reactor Trip Investigation 27
71153 Work Orders 5253920
PALO VERDE NUCLEAR GENERATING STATION - INTEGRATED INSPECTION REPORT 05000528
/2021004, 05000529/2021004, AND 05000530/2021004 DATE February 7, 2022