IR 05000528/2023002

– Integrated Inspection Report 05000528/2023002 and 05000529/2023002 and 05000530/2023002

ML23219A111
Person / Time
Site:	Palo Verde
Issue date:	08/08/2023
From:	John Dixon NRC/RGN-IV/DORS/PBD
To:	Heflin A Arizona Public Service Co
References
IR 2023002
Download: ML23219A111 (32)

Text

August 08, 2023

SUBJECT:

PALO VERDE NUCLEAR GENERATING STATION - INTEGRATED INSPECTION REPORT 05000528/2023002 AND 05000529/2023002 AND 05000530/2023002

Dear Adam Heflin:

On June 30, 2023, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Palo Verde Nuclear Generating Station. On July 7, 2023, the NRC inspectors discussed the results of this inspection with Todd Horton, Senior Vice President, Site Operations, 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 violation or the significance or severity of the violation 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. This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely, John L. Dixon, Jr., Chief Reactor Projects Branch D Division of Operating Reactor Safety Docket No 05000528,05000529 and 05000530 License No NPF-41 and NPF-51 and NPF-74

Enclosure:

As stated

Inspection Report

Docket Numbers: 05000528, 05000529 and 05000530

License Numbers: NPF-41, NPF-51 and NPF-74

Report Numbers: 05000528/2023002, 05000529/2023002 and 05000530/2023002

Licensee: Arizona Public Service

Facility: Palo Verde Nuclear Generating Station

Location: Tonopah, AZ

Inspection Dates: April 1, 2023 to June 30, 2023

Inspectors: L. Merker, Senior Resident Inspector E. Lantz, Resident Inspector N. Cuevas, Resident Inspector J. Drake, Senior Reactor Inspector S. Makor, Senior Reactor Inspector D. Antonangeli, Health Physicist E. Simpson, Nuclear Systems Scientist

Approved By: John L. Dixon, Jr., Chief Reactor Projects Branch D Division of Operating Reactor Safety

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.

List of Findings and Violations

Failure to Verify Adequacy of Emergency Diesel Generator Building Flooding Calculation Criteria Cornerstone Significance Cross-Cutting Report Section Aspect Mitigating Green None 71111.06 Systems NCV 05000528, 05000529, 05000530 2023002-01 Open/Closed Introduction: The inspectors identified a Green finding and associated non-cited violation (NCV)of 10 CFR 50, Appendix B, Criterion III, Design Control, when the licensee failed to verify or check the adequacy of the design of the emergency diesel generator building flooding calculation by the performance of design reviews or by the use of alternate or simplified calculation methods. Specifically, the licensee failed to verify the adequacy of the flooding calculation for a postulated worst-case fluid piping break within the emergency diesel generator room.

Additional Tracking Items

None.

PLANT STATUS

Unit 1 entered the inspection period at or near full power. On April 8, 2023, the unit tripped on low departure from nucleate boiling ratio due to the reactor coolant pumps losing power. The unit was restarted on April 12, 2023, and stayed at 51 percent power from April 16-18, 2023, to perform repairs to main feedwater pump B. On April 19, 2023, the unit returned to full power. On June 13, 2023, power was reduced to 88 percent power to perform maintenance on the heater drain tank A normal level controller before returning to full power on June 14, 2023, where it remained for the remainder of the inspection period.

Unit 2 entered the inspection period at approximately 94 percent power during a coastdown for refueling outage 2R24. On April 8, 2023, the unit was shut down for refueling outage 2R24. On May 11, 2023, the reactor was made critical following completion of the refueling outage and returned to full power on May 16, 2023. On May 22, 2023, the unit was shut down for short notice outage 2M25A to repair a steam leak on the steam generator 2 economizer feedwater header check valve, SGE-V-006. On May 28, 2023, the reactor was made critical following completion of the short notice outage and returned to full power on May 31, 2023. On June 2, 2023, the unit tripped on low steam generator water levels due to degraded flow from main feedwater pump A. The unit was restarted on June 3, 2023, and returned to full power on June 7, 2023, where it remained for the remainder of the inspection period.

Unit 3 operated at or near full power for the duration of the inspection period.

INSPECTION SCOPES

Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors performed activities described in IMC 2515, Appendix D, Plant Status, observed risk significant activities, and completed on-site portions of IPs. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.

71111.01 - Adverse Weather Protection

Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated the site's readiness for seasonal extreme weather conditions prior to the onset of seasonal high temperatures for Units 1, 2, and 3, essential spray pond train B and offsite AC power systems, on June 13, 2023.

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (2 Samples)

The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:

(1) Unit 2, essential chilled water train A following maintenance, on May 1, 2023

(2) Unit 3, essential cooling water train A during essential cooling water train B maintenance outage, on June 12, 2023

Complete Walkdown Sample (IP Section 03.02) (1 Sample)

(1) Unit 2, containment spray train B following the unit refueling outage 2R24, on May 22, 2023

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (2 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, containment building 80-foot elevation, fire zones 66A, 66B, 67A, and 67B, on May 3, 2023

(2) Unit 1, class 1E 4kV switchgear B room, fire zone 5B, on June 15, 2023

Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Partial)

(1) (Partial)

The inspectors evaluated the onsite fire department training and performance during announced fire drills on May 18, 2023, and June 21, 2023.

71111.06 - Flood Protection Measures

Flooding Sample (IP Section 03.01) (1 Sample)

(1) Units 1, 2, and 3, emergency diesel generator train A and B rooms due to clogged floor drains and nonfunctional sump pumps, on May 31, 2023.

===71111.08P - Inservice Inspection Activities (PWR)

The inspectors verified that the reactor coolant system boundary, reactor vessel internals, risk-significant piping system boundaries, and containment boundary are appropriately monitored for degradation and that repairs and replacements were appropriately fabricated, examined and accepted by reviewing the following activities from April 17-26, 2023.

PWR Inservice Inspection Activities Sample - Nondestructive Examination and Welding Activities (IP Section 03.01)===

The inspectors verified that the following nondestructive examination and welding activities were performed appropriately:

(1) Ultrasonic Examination Main steam (east) steam generator 1 (MSSS), 23-UT-2020, 48-29 weld on SIBV532, a pipe to end cap weld zone 48 Main steam (east) steam generator 1 (MSSS), 23-UT-2018, 48-27 weld on SIBV532, a pipe to sweepolet zone 48 Main steam (east) steam generator 1 (MSSS), 23-UT-2019, 48-28 weld on SIBV532, a branch connection zone 48

Dye Penetrant Examination Safety injection, 23-PT-2004, hanger SI-174-H-008

Visual # Examination Containment LPSI header to loop 2B, 23-VT-2070, pipe support assembly

Welding Activities Gas tungsten arc welding o Feedwater header to steam generator (RCEE01A), 2PSGL008 o Feedwater header to steam generator, (RCEE01A), 2PSGL008 o B HPSI injection to loop 2 check valve, 2PSIBV532

PWR Inservice Inspection Activities Sample - Vessel Upper Head Penetration Inspection

Activities (IP Section 03.02) (1 Sample)

The inspectors verified that the license conducted the following vessel upper head penetration inspections and addressed any identified defects appropriately:

No ASME code head inspection required during this outage.

PWR Inservice Inspection Activities Sample - Boric Acid Corrosion Control Inspection Activities (IP Section 03.03) (1 Sample)

The inspectors verified the licensee is managing the boric acid corrosion control program through a review of the following evaluations:

23-03045 23-03499 23-03451 23-03454 23-03456

PWR Inservice Inspection Activities Sample - Steam Generator Tube Inspection Activities (Section 03.04) (1 Sample)

The inspectors reviewed the results of the 100 percent full length eddy current inspection of all tubes with bobbin coil probe. No tubes exhibited degradation exceeding the tube integrity criteria provided in the Degradation Assessment (DA).

(1) Steam generators 1-2 1. No tubes required in situ pressure testing to support the condition monitoring (CM) assessment based on the DA and electric power research institute (EPRI) in situ pressure test guidelines.

2. No tube leakage was reported during this operating interval.

The inspectors verified that the licensee is monitoring the steam generator tube integrity appropriately through a review of the examinations.

71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance

Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (2 Samples)

The inspectors observed and evaluated licensed operator performance in the control room during the following activities:

(1) Unit 2, shutdown for refueling outage 2R24, on April 8, 2023

(2) Unit 2, reactor startup following the automatic reactor trip on low steam generator level, on June 3, 2023

Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)

(1) The inspectors observed and evaluated licensed operator continued training simulator exam activities, on May 30, 2023.

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (9 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 1, high risk for planned maintenance to perform pre-charge check alignments on the main turbine electro-hydraulic control system fluid accumulators, on April 6, 2023

(2) Unit 2, high risk for emergent maintenance to replace a blown fuse on the control element drive mechanism control system, on April 12, 2023

(3) Units 1, 2, and 3, site-wide weekly risk management during Unit 1 short notice outage 1M24 and Unit 2 planned refueling outage 2R24, on April 13, 2023

(4) Unit 2, high risk for emergent replacement of the control element drive mechanism control system subgroup 6 power switch assembly, on April 13, 2023

(5) Unit 2 risk management supporting multiple containment entries at 100 percent power to drain containment recirculation actuation signal sump B due to feedwater leakage from steam generator 2 economizer feedwater header check valve SGE-V-006 and to perform emergent maintenance on safety injection tank 1A vent valve SIB-HV-633 and safety injection tank 2B vent valve SIA-HV-606, on May 25, 2023

(6) Unit 3, high risk for testing of the supplementary protection system, on June 9, 2023

(7) Unit 2, high risk for emergent work to replace the control oil pump B circuit breaker and adjust the control oil pump A compensator, on June 12, 2023

(8) Unit 3, high risk for planned maintenance to perform pre-charge checks of the electro-hydraulic control oil accumulators A, B, C, and D, on June 14, 2023

(9) Unit 3, high risk for planned 18-month reactor trip switchgear breaker A testing, on June 20, 2023

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (4 Samples)

The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:

(1) Unit 2, essential chiller B operability determination due to low refrigerant level, on May 4, 2023

(2) Unit 2, essential spray pond train A operability determination after pump house exhaust fan failure, on May 16, 2023

(3) Unit 1, turbine-driven auxiliary feedwater pump operability determination due to oil leak, on May 18, 2023

(4) Unit 2, low-pressure safety injection trains A and B operability determination due to high pressure in the injection header piping, on June 21, 2023

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 to replace the steam generator 2 cold leg primary manway gasket retainer plate, on May 25, 2023

71111.20 - Refueling and Other Outage Activities

Refueling/Other Outage Sample (IP Section 03.01) (1 Sample, 1 Partial)

(1) The inspectors evaluated the Unit 2 refueling outage 2R24 activities from April 8 through May 16, 2023. Operating Experience Smart Sample (OpESS) 2007/03, Crane and Heavy Lift Inspection, Supplemental Guidance to [Inspection Procedure]

===71111.20 and [Inspection Procedure] 71111.13, revision 3, was used to inform this sample.

(2) (Partial)

The inspectors evaluated the Unit 2 short notice outage 2M25A activities following a planned reactor shutdown for emergent repairs from May 22-29, 2023.

71111.24 - Testing and Maintenance of Equipment Important to Risk

The inspectors evaluated the following testing and maintenance activities to verify system operability and/or functionality:

Post-Maintenance Testing (PMT) (IP Section 03.01)===

(1) Unit 2, atmospheric dump valves train B, SGB-HV-178 and SGB-HV-185, post-maintenance testing following maintenance outage, on April 3, 2023

(2) Unit 1, main turbine electro-hydraulic control system fluid reservoir level switch post-maintenance testing following replacement, on April 19, 2023

(3) Unit 1, main steam isolation valve SGE-UV-181 post-maintenance testing following 4-way control valve replacement, on April 27, 2023

(4) Unit 1, control oil pumps A and B post-maintenance testing following troubleshooting and repairs, on May 2, 2023

(5) Unit 2, safety injection tank 1B outlet valve SIA-UV-644 post-maintenance testing following repairs, on May 3, 2023

(6) Unit 2, essential chiller B post-maintenance testing following refrigerant leak repairs, on May 8, 2023

(7) Unit 2, essential chilled water system A post-maintenance testing following maintenance overhaul, on May 10, 2023

(8) Unit 2, containment spray pump B flow control valve SIB-UV-671 post-maintenance testing following component replacement, on May 11, 2023

(9) Unit 1, charging pump A post-maintenance testing following discharge pulsation damper replacement, on May 16, 2023

Surveillance Testing (IP Section 03.01) (2 Samples)

(1) Unit 2, emergency diesel generator A and integrated safeguards train A testing, on April 25, 2023

(2) Unit 2, leak rate surveillance testing of safety injection system to reactor coolant system pressure isolation valves following manipulation during 2M25A short notice outage, on May 28, 2023

Inservice Testing (IST) (IP Section 03.01) (1 Sample)

(1) Unit 3, charging pump A, B, and E inservice testing, on June 1, 2023

Containment Isolation Valve (CIV) Testing (IP Section 03.01) (1 Sample)

(1) Unit 2, fire protection containment isolation valve FP-EV-090 testing, on May 8,

71124.01 - Radiological Hazard Assessment and Exposure Controls

Radiological Hazard Assessment (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated how the licensee identifies the magnitude and extent of radiation levels and the concentrations and quantities of radioactive materials and how the licensee assesses radiological hazards.

Instructions to Workers (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated how the licensee instructs workers on plant-related radiological hazards and the radiation protection requirements intended to protect workers from those hazards.

Contamination and Radioactive Material Control (IP Section 03.03) (2 Samples)

The inspectors observed/evaluated the following licensee processes for monitoring and controlling contamination and radioactive material:

(1) The inspectors observed the licensee conduct surveys of potentially contaminated packages/equipment from the radiologically controlled area for release offsite and workers exiting potential contaminated areas

(2) The inspectors observed workers exiting the reactor containment building, a contamination area, at Unit 2 during the refueling outage

Radiological Hazards Control and Work Coverage (IP Section 03.04) (4 Samples)

The inspectors evaluated the licensee's control of radiological hazards for the following radiological work:

(1) Unit 2 spent fuel transfer canal upender maintenance (RWP 2-1330)

(2) Radiography within PVGS owner-controlled area (RWP 9-1035)

(3) Primary side eddy current testing for steam generator A (RWP 2-3306)

(4) Job preparation and removal of check valve SIEV247 (RWP 2-3521)

High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (3 Samples)

The inspectors evaluated licensee controls of the following High Radiation Areas and Very High Radiation Areas:

(1) Unit 2 regenerative heat exchanger room

(2) Unit 2 under vessel access

(3) Unit 2 reactor head stand access

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.

71124.04 - Occupational Dose Assessment

Source Term Characterization (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated licensee performance as it pertains to radioactive source term characterization.

External Dosimetry (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated how the licensee processes, stores, and uses external dosimetry that is used to assign occupational dose.

Internal Dosimetry (IP Section 03.03) (1 Sample)

The inspectors evaluated the following internal dose assessments:

(1) A radiation workers intake evaluation to an airborne radioactivity exposure dated May 1, 2022, and evaluated based on whole-body counting and lapel air sample results, Evaluation #22-0002

Special Dosimetric Situations (IP Section 03.04) (2 Samples)

The inspectors evaluated the following special dosimetric situations:

(1) Dose assessments for declared pregnant workers

(2) Effective dose equivalent for external exposure (EDEX) evaluation for radiation work permit #2-1330-R24, Task 51, High Risk LHRA Decon of Fuel Transfer Canal Entry

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification

The inspectors verified licensee performance indicators submittals listed below:

MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04)===

(1) Unit 1 (April 1, 2022, through March 31, 2023)

(2) Unit 2 (April 1, 2022, through March 31, 2023)

(3) Unit 3 (April 1, 2022, through March 31, 2023)

OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)

(1) Units 1, 2, and 3 (April 1, 2022, through March 31, 2023)

PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample (IP Section 02.16) (1 Sample)

(1) Units 1, 2, and 3 (April 1, 2022, through March 31, 2023)

71152A - Annual Follow-up Problem Identification and Resolution Annual Follow-up of Selected Issues (Section 03.03)

The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:

(1) Units 1, 2, and 3, effectiveness of corrective actions following multiple safety injection tank vent valve failures, on April 24, 2023

(2) Units 1, 2, and 3, effectiveness of corrective actions following discovery of 10 CFR 50 appendix R 8-hour emergency lighting not being properly positioned, on May 24, 2022

(3) Units 1, 2, and 3, inservice testing history of train A and B safety injection pumps combined recirculation valves SIA-UV-660 and SIB-UV-659 and effectiveness of corrective actions following the failure of the Unit 1 train A safety injection pumps combined recirculation valve SIA-UV-660 to open during quarterly testing, on May 30, 2022

(4) The inspectors reviewed the cyber security implementation of the control element drive mechanism control system ovation modification by examining associated modification documentation and evaluations. Specifically, the inspectors reviewed the critical digital asset characterization, impact review, staff qualifications, and verified that the critical digital asset assessment to identify appropriate controls was completed prior to installation. The inspectors also performed interviews with the control element drive mechanism control system project manager and cyber staff to discuss the modification and noted that the modification was performed in phases and only Unit 3 had been installed and tested at the time of the review, on June 15, 2023.

71153 - Follow Up of Events and Notices of Enforcement Discretion Event Follow-up (IP section 03.01)

(1) The inspectors evaluated the Unit 1 automatic reactor trip on low departure from nucleate boiling ratio due to the reactor coolant pumps losing power and the licensees response, on April 9, 2023.

(2) The inspectors evaluated the Unit 2 automatic reactor trip on low steam generator level and the licensees response, on June 2,

INSPECTION RESULTS

Failure to Verify Adequacy of Emergency Diesel Generator Building Flooding Calculation Criteria Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green None 71111.06 NCV 05000528, 05000529, 05000530 2023002-01 Open/Closed The inspectors identified a Green finding and associated non-cited violation (NCV) of 10 CFR 50, Appendix B, Criterion III, Design Control, when the licensee failed to verify or check the adequacy of the design of the emergency diesel generator building flooding calculation by the performance of design reviews or by the use of alternate or simplified calculation methods.

Specifically, the licensee failed to verify the adequacy of the flooding calculation for a postulated worst-case fluid piping break within the emergency diesel generator room.

Description:

On January 25, 2023, during a planned cycling of the Unit 1 emergency diesel generator B room sump pumps, the licensee noted that the floor drains to the sump in the room immediately backed up when water was added. The licensee documented the clogged floor drains in condition report (CR) 23-00816, declaring that the condition did not impact emergency diesel generator train B operability.

The inspectors reviewed the internal flooding calculation 13-MC-DG-0204, Diesel Generator Building Flooding Analysis, revision 6, and performed a walkdown of the Unit 1 emergency diesel generator train A and B rooms to assess the impact of the clogged floor drains on the emergency diesel generators. Criteria 3 of the calculation states that internal flooding resulting from postulated breaks of the worst-case fluid piping within a room is considered on a room-by-room basis for 30 minutes (based on the expected operator action within 30 minutes to isolate the effected system and thus isolate the leak), which for the emergency diesel generator rooms, is the 10-inch supply and return essential spray pond pipes. The inspectors questioned the ability of the licensee to isolate a leak in the essential spray pond supply piping since there is no means to isolate the leak in the line between the essential spray pond and the piping within the emergency diesel generator room, other than securing the essential spray pond pump.

The licensee acknowledged that there was no means of isolating this supply line of the essential spray pond piping and performed an engineering evaluation to determine the impact of the continued flow from a postulated worst case deterministic crack due to gravity flow fed from the elevation difference of the essential spray pond (normal water level of 106-11) and the worst-case pipe break location (95-6) with the essential spray pond pump secured. The licensee calculated that the rate of flooding from this postulated leak would be large enough to result in the potential impact of safety-related components in the emergency diesel generator room in approximately three hours. Normal operator rounds performed every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> would not be sufficient to be able to detect the flooding and take mitigating actions. However, the licensee also noted that the assessed deterministic crack in the essential spray pond piping was not a credible failure mechanism due to the size of the crack and duration of auxiliary operator rounds to detect crack growth and its corresponding leakage. Additionally, using Branch Technical Position MEB 3-1, Postulated Rupture Locations in Fluid System Piping Inside and Outside Containment, revision 1, the licensee evaluated that the deterministic sized crack in the essential spray pond piping was not required to be considered due to it being an intermediate pipe break in moderate energy piping outside of containment where the combined stresses can be shown to not exceed the required stress limits in the branch technical position.

Following the evaluations, the licensee revised the calculation, 13-MC-DG-0204, to replace the inaccurate criteria and flooding scenario with a more credible leak from the essential spray pond piping due to corrosion/pitting. This credible leak was calculated to be within operators ability to detect and take mitigating actions within normal operator rounds.

The licensee also revised the calculation to account for the inspectors raising concerns over a 15-minute response time for the onsite fire department to respond to a potential internal flooding scenario.

Corrective Actions: The licensee performed an engineering evaluation and revised the diesel generator building flooding analysis calculation to correct the noted inaccuracies.

Corrective Action References: Condition reports 23-00816, 23-01814, 23-05514, 23-06559, 23-06832, 23-07148.

Performance Assessment:

Performance Deficiency: The failure to verify the adequacy of the emergency diesel generator room flooding calculation 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, incorrectly crediting an operator action to isolate the postulated leak within 30 minutes affects the reliability and availability of plant mitigation systems and could cause undesirable consequences.

Significance: The inspectors assessed the significance of the finding using Inspection Manual Chapter 0609 Appendix A, The Significance Determination Process (SDP) for Findings At-Power. Using Exhibit 2, Mitigating Systems Cornerstone Screening Questions, the finding was screened as having very low safety significance (Green) because the finding did not represent a deficiency affecting design or qualification of a mitigating structure, system, or component; did not involve a single-train TS system; did not represent the loss of probabilistic risk assessment (PRA) function one train of a multi-train system for greater than its TS allowed outage time; did not represent the loss of PRA function of two separate TS systems for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; did not represent the loss of a PRA system and/or function as defined in the PRIB or the licensees PRA for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; and, did not represent the loss of the PRA function of one or more non-TS trains of equipment designated as risk significant in accordance with the licensees maintenance rule program for greater than 3 days. Additionally, the finding did not involve external events mitigating systems, the reactor protection system, fire brigade, or flexible coping strategies.

Cross-Cutting Aspect: Not Present Performance. No cross-cutting aspect was assigned to this finding because the inspectors determined the finding did not reflect present licensee performance.

Enforcement:

Violation: 10 CFR 50, Appendix B, Criterion III, Design Control states, in part, that design control measures shall provide for verifying or checking the adequacy of design, such as by the performance of design reviews, by the use of alternate or simplified calculation methods, or by the performance of a suitable testing program.

Contrary to the above, from February 25, 1992, to July 12, 2023, the licensee failed to provide design control measures for verifying or checking the adequacy of emergency diesel generator room flooding calculations, such as by the performance of design reviews, by the use of alternate or simplified calculation methods, or by the performance of a suitable testing program.

Specifically, the licensees failure to check the adequacy of the design of the emergency diesel generator room flooding calculation by the performance of design reviews or by the use of alternate or simplified calculation methods resulted in the criteria for internal flooding resulting from postulated breaks of the worst-case fluid piping within the emergency diesel generator room being inadequate, affecting the reliability and availability of the emergency diesel generator to respond to initiating events to prevent undesirable consequences.

Enforcement Action: This violation is being treated as a non-cited violation, consistent with section 2.3.2 of the enforcement policy.

EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

On April 25, 2023, the inspectors presented the occupational radiation safety inspection results to Cary Harbor, Vice President, Nuclear Regulatory & Oversight, and other members of the licensee staff.

On April 26, 2023, the inspectors presented the inservice inspection results to Rex Meeden, Vice President, Nuclear Engineering, and other members of the licensee staff.

On July 7, 2023, the inspectors presented the integrated inspection results to Todd Horton, Senior Vice President, Site Operations, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.01 Corrective Action 17-16819, 17-18094, 22-05649, 22-05829, 22-05881, 22-

Documents 05891, 22-06427, 22-06438, 23-03210, 23-06020, 23-06024,

23-06172

71111.01 Procedures 40DP-9OP34 Switchyard Administrative Control 22

71111.01 Procedures 40DP-9OP49 operator outside logs desiccant and dehydrating breather oil

sump level

71111.01 Procedures 40DP-9ZZ19 Hot Weather Protection 7

71111.01 Procedures 51DP-9OM03-04 Summer Readiness Administrative Guideline 0

71111.01 Work Orders 5446121, 5447303, 5447635, 5448858, 5523266, 5540278,

5540279

71111.04 Corrective Action 22-11014, 22-04854, 21-04705

Documents

71111.04 Drawings 02-M-CHP-002 P and I Diagram Chemical and Volume Control System 59

71111.04 Drawings 02-M-ECP-001 P & I Diagram Essential Chilled Water System 31

71111.04 Drawings 02-M-EWP-001 P & I Diagram Essential Cooling Water System 30

71111.04 Drawings 02-M-RCP-001 P & I Diagram Reactor Coolant System 37

71111.04 Drawings 02-M-SIP-001 P & I Diagram Safety Injection and Shutdown Cooling 56

System

71111.04 Drawings 02-M-SIP-002 P & I Diagram Safety Injection and Shutdown Cooling 37

System

71111.04 Drawings 02-M-SIP-003 P & I Diagram Safety Injection and Shutdown Cooling 12

System

71111.04 Drawings 03-M-EWP-001 P & I Diagram Essential Cooling Water System 30

71111.04 Miscellaneous DBM Essential Chilled Water System 18

71111.04 Procedures 40OP-9EC01 Essential Chilled Water Train A 32

71111.04 Procedures 40OP-9EW01 Essential Cooling Water System (EW) Train A 34

71111.04 Procedures 40OP-9SI02 Recovery From Shutdown Cooling To Normal Operating 121

71111.04 Procedures 42ST-2EC01 Essential Chilled Water Valve Verification 16

71111.05 Calculations 13-MC-FP-0802 Fire Hazard Zones Surface Areas 3

71111.05 Calculations 13-MC-FP-0803 Combustible Loads - Control Building 17

71111.05 Corrective Action 22-03027, 23-02065, 23-05514, FSCCR 5542265, 23-

Documents 05988, 23-06653, 23-06654, 23-06701

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.05 Drawings 01-M-FPP-004 P & I Diagram Fire Protection System (CO2 System) 11

71111.05 Fire Plans Pre-fire Strategies Manual 30

71111.05 Miscellaneous 22-R002/22-F009 LCDR: TRM 3.11.104 and UFSAR various Chapter 9 and

Appendix 9B Sections

71111.05 Miscellaneous BTP ASB 9.5-1 Guidelines for Fire Protection for Nuclear Power Plants

71111.05 Miscellaneous NPL41-D-2Q1B-Palo Verde Nuclear Fire Department Fire Drill: Unit 1 B 05/17/2023

Shift Drill Scenario

71111.05 Miscellaneous NPL41-D-2Q3A-Palo Verde Nuclear Fire Department Fire Drill: Unit 3 A 06/20/2023

Shift Drill Scenario

71111.05 Procedures 14DP-0FP32 Emergency Notification and Response 38

71111.05 Procedures 14DP-0FP33 Control of Transient Combustibles 33

71111.05 Procedures 14DP-0FP44 Fire Protection Test Program Requirement 7

71111.05 Procedures 14FT-2FP12 Unit 2 Fire Hose Station Inspection 6

71111.05 Procedures 40AO-9ZZ27 Significant Turbine Building Oil System Leaks 0

71111.05 Procedures 40DP-9ZZ19 Operational Considerations Due to Plant Fire 37

71111.05 Procedures PR-0904 Fire Protection Program Requirement Description 2

71111.06 Calculations 13-MC-DG-0204 Diesel Generator Building Flooding Analysis 3

71111.06 Calculations 13-MC-DG-0204 Diesel Generator Building Flooding Analysis 4

71111.06 Calculations 13-MC-DG-0204 Diesel Generator Building Flooding Analysis 5

71111.06 Calculations 13-MC-DG-0204 Diesel Generator Building Flooding Analysis 6

71111.06 Corrective Action 23-00816, 23-01814, 21-12899, 23-05514, 23-06559, 23-

Documents 06832

71111.06 Drawings 01-M-OWP-002 P & I Diagram Oily Waste and Non-Radioactive Waste 3

System (Diesel Generator Building)

71111.06 Drawings 02-M-SPP-001 P & I Diagram Essential Spray Pond System 72

71111.06 Drawings 13-M095-00003 As-Built ESPS Pump 2-M-SPA-P01 Outline Drawing 12

71111.06 Fire Plans Pre-Fire Strategies Manual 31

71111.06 Miscellaneous 15-02910-015 SP-1695 Spray Pond Piping Replacement Phase 1 - 0

Replace deteriorated Spray Pond piping using a corrosion-

resistant material in the Spray Pond Vaults

71111.06 Procedures 40AL-9RK2A Panel B02A Alarm Responses 15

71111.08P Corrective Action 23-02856

Documents

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.08P Corrective Action 23-04228

Documents

Resulting from

Inspection

71111.08P Drawings 13-SI-174-H008 Pipe Support Assy-CTMT 2

71111.08P Drawings 13-SI-174-H008 Pipe Support Assy - Ctmt 1

71111.08P Miscellaneous 4INT-ISI-2 Inservice Inspection Program Summary Manual 1

71111.08P Miscellaneous VER2-23-OB1-A Bobbin 24 IPS 0

71111.08P NDE Reports 21-UT-2036 RCS Primary Piping 10/14/2021

71111.08P Procedures

71111.08P Procedures 30DP-0WM07 Controls for Use of Measuring and Test Equipment (M&TE) 15

71111.08P Procedures 34DP-0ME02 Measuring and Test Equipment 17

71111.08P Procedures 70TI-9ZZ84 Boric Acid Walkdown Leak Detection 6

71111.08P Procedures 73DP-9WP01 Welder and Procedure Qualification 9

71111.08P Procedures 73ST-2ZZ12 Settlement Monitoring Program 12

71111.08P Procedures 73TI-0ZZ13 Radiographic Examination 21

71111.08P Self-Assessments 02-MS-A185 U2R22 Condition Monitoring Evaluation 04/27/2020

71111.08P Self-Assessments 02-MS-A186 U2C23/25 Steam Generator Operational Assessment 07/22/2020

71111.08P Self-Assessments 22-03152 Unit 2, 4th Interval, First Period ISI

71111.08P Self-Assessments 22-06769 Unit 1, 4th Interval, First Period ISI

71111.08P Work Orders 5406040 TO

71111.11Q Corrective Action 23-03441, 23-03692, 23-04906, 23-05543, 23-05739, 23-

Documents 06116, 23-06319

71111.11Q Miscellaneous Standard Maneuver Plan: EOC Shutdown 89% to 20% Unit 0

Cycle 24

71111.11Q Miscellaneous 2305301133 2023 Cycle 3 Crew 34 Scenario SES005K07 Evaluation 06/16/2023

Summary Sheet

71111.11Q Miscellaneous 2305301343 2023 Cycle 3 Crew 14 Scenario SES005K07 Evaluation 06/16/2023

Summary Sheet

71111.11Q Miscellaneous 374309 Observation: 2023 Cycle 3 - AC Distribution LOCT 06/16/2023

71111.11Q Miscellaneous SES-0-05-K-07 UV Relay Failure / SG Lvl Xmitter Failure / RCP Seal Fail / 7

RCP Seizure / ATWS / Feed Line Break

71111.11Q Procedures 40DP-9OP02 Conduct of Operations 77

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.11Q Procedures 40EP-9EO01 Standard Post Trip Actions 23

71111.11Q Procedures 40EP-9EO02 Reactor Trip 14

71111.11Q Procedures 40OP-9ZZ03 Reactor Startup 64

71111.11Q Procedures 40OP-9ZZ04 Plant Startup Mode 2 to Mode 1 77

71111.11Q Procedures 40OP-9ZZ11 Mode Change Checklist 106

71111.11Q Procedures 72OP-9RX01 Calculation of Estimated Critical Condition 38

71111.13 Corrective Action 23-02792, 23-03074, 21-06458, 23-03479, 22-07768, 23-

Documents 02682, 23-05200, 23-05202, 23-05203, 23-05220, 23-06056,

23-06057

71111.13 Miscellaneous Phoenix Risk Monitor - PVGS Unit 1 Current Risk Summary 04/06/2023

Report as of 4/4/2023 15:30

71111.13 Miscellaneous Risk Management and Readiness Plan for WO 5408456 0

(A/B) and WO 5408457 (C/D)

71111.13 Miscellaneous Risk Management and Readiness Plan to Troubleshoot and 0

Correct the Continuous Gripper High Voltage for Subgroup 8

and Indication of Blown Fuse

71111.13 Miscellaneous High Risk Activity Mitigation Summary - Work Week 2315

71111.13 Miscellaneous WW 2315 Schedule Evaluation (4/10-4/162023) 04/12/2023

71111.13 Miscellaneous Unit 1 Reactor Trip - April 8, 2023, Plant Review Board

Presentation

71111.13 Miscellaneous Shutdown Safety Function Assessment, Unit 2 04/09/2023

71111.13 Miscellaneous Shutdown Safety Function Assessment, Unit 2 04/10/2023

71111.13 Miscellaneous Shutdown Safety Function Assessment, Unit 2 04/11/2023

71111.13 Miscellaneous Shutdown Safety Function Assessment, Unit 2 04/12/2023

71111.13 Miscellaneous Site Integrated Risk Assessment Work Task 5519274 - 0 03/21/2023

71111.13 Miscellaneous Risk Management and Readiness Plan for WO# 5519274, 0

Replace U2 CEDMCS PSA for SG 6

71111.13 Miscellaneous Risk Management and Readiness Plan: Perform Inspection 06/06/2023

and Acceptance Testing of New or Overhauled Breaker, and

Install in Cubicle

71111.13 Miscellaneous Risk Management and Readiness Plan: Unit 2 'B' Control Oil 06/06/2023

Pump Filter Change, WO# 5540035

71111.13 Miscellaneous Risk Management and Readiness Plan: Unit 2 'A' Control Oil 06/07/2023

Pump Compensator, WO# 5539924

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.13 Miscellaneous Risk Management and Readiness Plan: WO# 5539924, U2, 06/07/2023

CO A - Compensator Adjustment, Adjust Compensator to

1600 psi

71111.13 Miscellaneous Protected Equipment Scheme for CON-P01B B Control Oil 06/06/2023

Pump OOS

71111.13 Miscellaneous Phoenix Risk Monitor - PVGS Unit 2 WW 2323 Schedule 06/07/2023

Evaluation (6/5/2023 - 6/11/2023

71111.13 Miscellaneous System Training Manual Volume 40 Safety Injection System 4

(SI)

71111.13 Miscellaneous System Training Manual Volume 72 Radioactive Waste 3

Drain System (RD)

71111.13 Miscellaneous Unit 3 Phoenix Risk Monitor-WW 2323 Schedule Evaluation 06/09/2023

06/05/2023-06/11/20203

71111.13 Miscellaneous High Risk Activity Mitigation Summary - Work Week 2324 06/13/2023

71111.13 Miscellaneous Site Integrated Risk Assessment Work Task 5420476-0 02/17/2023

71111.13 Miscellaneous Site Integrated Risk Assessment Work Task 5420475-0 02/17/2023

71111.13 Miscellaneous Protected Equipment Scheme for Reactor Trip Breaker A 06/07/2023

INOP

71111.13 Miscellaneous Phoenix Risk Monitor - PVGS Unit 3 WW 2323 Schedule 06/05/2023

Evaluation (6/5/2023 - 6/11/2023)

71111.13 Miscellaneous Risk Management and Readiness Plan: 36ST-9SB44 - RPS

Matrix Relays to Reactor Trip Response Time Test and

36ST-9SB52 - RTSG

71111.13 Miscellaneous Shunt and Undervoltage Trip Functional Test 06/16/2023

71111.13 Miscellaneous Risk Management and Readiness Plan: 18-month Reactor

Trip Switchgear Breaker Maintenance and 32ST-9SB02 - 18-

month Surveillance

71111.13 Miscellaneous Testing for Westinghouse Type DS-416 Reactor Trip 06/16/2023

Switchgear Breakers

71111.13 Miscellaneous TD# 297099 Operations Technical Document for 2JSIAHV0606**VALVEX 05/17/2023

- SIT 2B Vent Valve (296984),

71111.13 Procedures 01DP-0AP09 Procedure and Work Instruction Use and Adherence 22

71111.13 Procedures 01DP-0AP12 Condition Reporting Process 44

71111.13 Procedures 01DP-0AP57 Management of Critical Evolutions and Infrequently 2

Inspection Type Designation Description or Title Revision or

Procedure Date

Performed Tests or Evolutions

71111.13 Procedures 02DP-0RS01 Online Integrated Risk 12

71111.13 Procedures 02DP-0RS01-01 Risk Challenge Meetings 1

71111.13 Procedures 32MT-9ZZ25 Maintenance of Low Voltage Circuit Breakers Type K-600S 41

and K-Don-600S

71111.13 Procedures 32ST-9SB02 18 Month Surveillance Test for Westinghouse Type DS-416 9

Reactor Trip Breakers

71111.13 Procedures 36ST-9SB13 Supplementary Protection System Functional Test 21

71111.13 Procedures 36ST-9SB44 RPS Matrix Relays to Reactor Trip Response Time Test 25

71111.13 Procedures 36ST-9SB52 RTSG Shunt and Undervoltage Trip Functional Test 12

71111.13 Procedures 40AL-9RK1B Panel B01B Alarm Responses 13

71111.13 Procedures 40DP-9AP21 Protected Equipment 7

71111.13 Procedures 40DP-9OP29 Power Block Clearance and Tagging 68

71111.13 Procedures 40DP-9RS02 Shutdown Risk Management 6

71111.13 Procedures 40DP-9ZZ01 Containment Entry in MODE 1 through MODE 4 44

71111.13 Procedures 40OP-9CO01 Electro-Hydraulic Control System 32

71111.13 Procedures 40OP-9NG01 480 Vac Non-Class 1E Switchgear 53

71111.13 Procedures 40OP-9SF01 Control Element Drive Mechanism Control System 31A

(CEDMCS) Operation

71111.13 Procedures 40OP-9SI02 Recovery from Shutdown Cooling to Normal Operating 121

Lineup

71111.13 Procedures 40ST-9ZZ09 Containment Cleanliness Inspection 26

71111.13 Procedures 70DP-0RA05 Assessment and Management of Risk When Performing 25

Maintenance in Modes 1 and 2

71111.13 Work Orders 5408456, 5408457, 5520229, 5399515, 5398794, 5399318,

5399330, 5399020, 5519274, 5534545, 5534542, 5534533,

5443760, 5497627, 5540035, 5539924, 5420475, 5420476,

5402936, 5402969, 5394721, 5402937

71111.15 Calculations 13-JC-ZZ-0412 Motor Operated Valve Thrust and Torque Calculation for 2

13JSIBUV0615, 13JSIBUV0625, 13JSIBUV0635 and

13JSIBUV0645

71111.15 Calculations 13-MC-EC-0252 EC System Water Requirements and Chiller Sizing 15

71111.15 Calculations 13-MC-HS-200 Transient Temperature in the Spray Pond Pump Room with 1

HVAC Exhaust Fan Off

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.15 Calculations 13-MC-SI-0806 Maximum Operating Pressures for Low Pressure CS, SDC 2

and LPSI MOVs

71111.15 Calculations 13-MC-SI-226 Maximum Operating Pressures for Low Pressure SIS, SCS, 1

and CS MOVs

71111.15 Corrective Action 23-01616, 17-06807, 23-01904, 21-15236, 23-01202, 17-

Documents 06020, 3976805, 3976785, 3989294, 3989295, 23-05193,

23-05437

71111.15 Drawings 01-P-SIF-136 Containment Building Isometric Safety Injection system HP & 3

LP Lines Loops 2A, 2B Sheets 1 and 2

71111.15 Drawings 13-M-SIS-002 ISI Boundary Identification Safety Injection and Shutdown 4

Cooling System,

71111.15 Drawings 13-P-ZCG-107 Piping and Mechanical Containment Penetration Reqmts for 9

Flued Heads

71111.15 Miscellaneous 13-MC-HS-0008 Spray Pond Ventilation and Equipment Adequacy 5

Calculation - Appendix A

71111.15 Miscellaneous 13-MM-095 Specification for Vertical centrifugal pumps, ASME section 12

III, for the APS company PVNGS Units 1,2,and 3

71111.15 Miscellaneous 13-NS-C088 Mission Times for the EW, SP, SI, AF, and DG systems 1

71111.15 Miscellaneous 13-VTD-D970- Dresser-Rand (Formerly Terry) Steam Turbine Instruction 12

00001 Manual

71111.15 Miscellaneous CRDR 3012684

71111.15 Miscellaneous EC DBM Essential Chilled Water System 18

71111.15 Miscellaneous EWR 4891467

71111.15 Miscellaneous M021-00026 Schematic-Oil Piping 8

71111.15 Miscellaneous PVNGS DBM Essential Spray Pond System 23

71111.15 Miscellaneous SDOC M095-Qualification Report Essential Spray Pond Pump Motors 6

00074

71111.15 Procedures 30DP-9MP08 Preventive Maintenance Program 30

71111.15 Procedures 40AL-9RK2B Panel B02B Alarm Responses 59

71111.15 Procedures 40AL-9RK2B Panel B02B Alarm Responses 59B

71111.15 Procedures 40DP-9OPA4 Control Building Watch Station Rounds 128

71111.15 Procedures 40OP-9SP01 Essential Spray Pond (SP) Train A 61

71111.15 Procedures 73ST-9AF02 Auxiliary Feedwater A - Inservice Test 62

71111.15 Procedures 73ST-9SI03 Leak Test of SI/RCS Pressure Isolation Valves 55

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.15 Procedures 73ST-9SI05 Leak Test of HPSI/LPSI Containment Isolation Check Valves35

71111.15 Work Orders 5389779, 5513701, 5400419, 2832812, 5404924, 5405419,

5483158

71111.18 Corrective Action 23-04392, 23-04573, 23-04863

Documents

71111.18 Drawings MN725-A00031 Primary Head Palo Verde 2 RSG 5

71111.18 Drawings MN725-A00052 Primary Closure Parts Palo Verde 2 RSG 2

71111.18 Engineering 23-04392-002 Unit 2 Steam Generator 2 - Cold Leg Primary Manway 0

Changes Gasket Retainer Plate Requires Modification from Original

Design

71111.18 Miscellaneous 2023-00224 Update Vendor Documentation Based Engineering Change 0

23-04392-002

71111.18 Miscellaneous MN725-A00179 Structural and Fatigue Analysis of Primary Manway 1

71111.18 Miscellaneous MN725-A0071 Tentative Sizing of RSG Pressure Boundary 2

71111.18 Procedures 31MT-9RC35 Steam Generator Primary Manway Removal and Installation, 28

MST Method

71111.18 Procedures 31MT-9RC35 Steam Generator Primary Manway Removal and Installation, 28A

MST Method

71111.18 Procedures 81DP-0EE10 Design Change Process 53

71111.18 Procedures 85DP-9MS01 Conduct of Modifications 7

71111.18 Work Orders 5405370, 5405371, 5529567

71111.20 Corrective Action 23-03441, 23-04046, 23-03984, 23-04013, 20-02176, 23-

Documents 04574, 23-04550, 23-04676, 23-04683, 23-04666, 23-04586,

23-04654, 23-03322, 23-03872, 23-03875, 23-03902, 23-

03905, 23-03912, 23-03923, 23-03945, 23-03904, 23-04414,

23-04592, 23-04640, 23-03702, 23-03799, 23-03769, 23-

04426, 23-04574, 23-04588, 23-03461, 23-03156, 23-04099,

23-04359, 23-04791, 23-04975, 23-05020, 23-05337, 23-

05412, 23-05516, 23-05714, 23-05818, 23-05836, 23-05844,

23-05751, 23-05815, 23-05866

71111.20 Miscellaneous Unit Two 24th Refueling Outage Shutdown Risk Assessment 0

Final Report

71111.20 Miscellaneous PVGS Unit 2, 24th Refueling Outage 0

71111.20 Miscellaneous Standard Maneuver Plan: EOC Shutdown 89% to 20% Unit 0

Inspection Type Designation Description or Title Revision or

Procedure Date

Cycle 24

71111.20 Miscellaneous 2R24 Offload Move Package

71111.20 Miscellaneous Unit 2 Core and SFP Time To Boil Calculations 04/20/23

04:33

71111.20 Miscellaneous Unit 2 Cycle 25 STAR Low Power Physics Testing Without 05/11/2023

RMAS Test Data Package

71111.20 Miscellaneous Time Sheet Exceptions Within Date Range 04/08/2023 to 05/03/2023

04/22/2023

71111.20 Miscellaneous Time Sheet Exceptions Within Date Range 04/23/2023 to 05/11/2023

05/07/2023

71111.20 Miscellaneous Standard Maneuver Plan for Unit 2 Cycle: 75 EFPD 100 to 0

19%

71111.20 Procedures 01DP-0AP17 Managing Personnel Fatigue 12

71111.20 Procedures 05DP-0NF25 Fuel Integrity Program Implementing Components 8

71111.20 Procedures 30DP-9MP23 Foreign Material Exclusion Controls 11

71111.20 Procedures 31MT-9RC30 Reactor Vessel Head Removal and Installation 61

71111.20 Procedures 40AO-9ZZ23 Loss of SFP Level or Cooling 33

71111.20 Procedures 40DP-9OP02 Conduct of Operations 77

71111.20 Procedures 40EP-9EO01 Standard Post Trip Actions 23

71111.20 Procedures 40EP-9EO02 Reactor Trip 14

71111.20 Procedures 40EP-9EO11 Lower Mode Functional Recovery 38

71111.20 Procedures 40MG-9ZZ07-001 FLEX Support Guidelines MODE 1, 2, 3, or 4 1

71111.20 Procedures 40MG-9ZZ07-002 FLEX Support Guidelines MODE 5, 6, or Defueled 1

71111.20 Procedures 40OP-9PC02 Filling and Draining the Refueling Pool using the CS, LPSI, 45

and HPSI Pumps

71111.20 Procedures 40OP-9PC07 Refueling Pool Operations 65

71111.20 Procedures 40OP-9RC02 Reactor Coolant System Fill and Vent 47

71111.20 Procedures 40OP-9ZZ03 Reactor Startup 64

71111.20 Procedures 40OP-9ZZ05 Power Operations 151

71111.20 Procedures 40OP-9ZZ11 Mode Change Checklist 106

71111.20 Procedures 40OP-9ZZ23 Outage GOP 89

71111.20 Procedures 40OP-9ZZ24 Short Notice Outage 55

71111.20 Procedures 40ST-9RC01 RCS and Pressurizer Heatup and Cooldown Rates 21

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.20 Procedures 40ST-9ZZ09 Containment Cleanliness Inspection 26

71111.20 Procedures 70DP-0RA01 Shutdown Risk Assessments 63

71111.20 Procedures 72DP-9NF01 Control of SNM Configuration, Inventory, and Reporting 62

71111.20 Procedures 72DP-9ZZ08 Control or Reactivity Maneuver Plans 9

71111.20 Procedures 72IC-9RX03 Core Reloading 58

71111.20 Procedures 72OP-9RX01 Calculation of Estimated Critical Condition 38

71111.20 Procedures 72PY-9RX07 STAR Low Power Physics Testing Without RMAS 3

71111.20 Procedures 72ST-9RX14 Shutdown Margin - Modes 3, 4, and 5 22

71111.20 Procedures 78OP-9FX01 Refueling Machine Operations 65

71111.20 Work Orders 5405009

71111.24 Corrective Action 23-02861, 22-13479, 23-03648, 23-03729, 23-03590, 23-

Documents 03647, 23-03717, 23-03718, 23-03595, 23-03477, 20-

04849, 23-03479, 23-04068, 23-04479, 22-05222, 22-07620,

2-09232, 23-04824, 23-05837, 23-05270

71111.24 Drawings PVNGS DBM - Safety Injection System 41

71111.24 Drawings 01-M-CHP-002 P & I Chemical and Volume Control System 64

71111.24 Drawings 01-M-COP-001 P & I Diagram Main Turbine Control Oil System 11

71111.24 Drawings 13-N001-1104-Valve Assembly Gate 8 Inch, 300 LB., MOTOR OPER., 17

00041 CRES

71111.24 Drawings 13-PN-0220 Specification For Installation of Valve Stem Packing for the 24

The Arizona Public Service Company Palo Verde Nuclear

generating Station Units 1, 2, and 3

71111.24 Drawings VTD-N383-00037 BQ/IP Valves Graphite Bonnet Seal Installation Procedure 1

71111.24 Miscellaneous System Training Manual Volume 9: Main Steam System 3

(SG)

71111.24 Miscellaneous 13-EN-0306 Installation Specification for Cable splicing and Terminations 23

for the Palo Verde Generating Station Units 1, 2, and 3

Quality Class Q, QAG, and NQR

71111.24 Miscellaneous PVNGS DBM Diesel generator, Class 1E Standby Generation, Fuel Oil 28

Storage and Transfer System

71111.24 Miscellaneous VTD-A391-00010 Vendor Technical Document: Anchor/Darling Instruction 14

Manual for Main Steam Isolation Valves (MSIV) and

Feedwater Isolation Valves (FWIV) [PUB.#E9023-9]

71111.24 Miscellaneous VTD-G250-00002 Greer Hydraulics Operation and Maintenance Instructions for 5

Inspection Type Designation Description or Title Revision or

Procedure Date

Gallon Pulse-Tone

71111.24 Procedures 30DP-0WM07 Controls for Use of Measuring and Test Equipment (M&TE) 15

71111.24 Procedures 32MT-9DG03 Train A Integrated Safeguards (ISG) Testing 11

71111.24 Procedures 32MT-9ZZ20 Low Voltage Motor Testing (Less Than 600 Vac) 8

71111.24 Procedures 33MT-9EC01 Essential Chiller 17

71111.24 Procedures 40AL-9RK6B Panel B06B Alarm Responses 40

71111.24 Procedures 40OP-9CH13 Charging Pump Suction Stabilizer and Discharge Pulsation 32

Dampener Operation

71111.24 Procedures 40OP-9CO01 Electro-hydraulic Control System 32

71111.24 Procedures 40OP-9OP43 M&TE Gauge Installation 2

71111.24 Procedures 40OP-9SG01 Main Steam 82

71111.24 Procedures 40OP-9SG01 Main Steam 82a

71111.24 Procedures 73DP-9CL02 Containment Leakage Rate Testing Program 37

71111.24 Procedures 73DP-9XI03 ASME Section XI Inservice Inspection 28

71111.24 Procedures 73DP-9ZZ12 Motor Operated Valve (MOV) Program 22

71111.24 Procedures 73DP-9ZZ21 Heat Exchanger Visual Inspection 8

71111.24 Procedures 73DP-9ZZ26 Motor Operated (MOV) Testing with Quiklook 6

71111.24 Procedures 73ST-9CH02 Charging Pumps - Comprehensive Test 15

71111.24 Procedures 73ST-9CH06 Charging Pumps - Inservice Test 38

71111.24 Procedures 73ST-9CL01 Containment Leakage Type B and C Testing 51

71111.24 Procedures 73ST-9DG01 Class 1E Diesel Generator and Integrated Safeguards Test 33

Train B

71111.24 Procedures 73ST-9EC01 Essential Chilled Water Pumps - Inservice Test 30

71111.24 Procedures 73ST-9SI03 Leak Rate of SI/RCS Pressure Isolation Valves 55

71111.24 Procedures 73ST-9XI20 ADVs - Inservice Test 57

71111.24 Procedures 73ST-9XI25 SIT Isolation and Outlet Check Valves Inservice Test 18

71111.24 Procedures 73ST-9ZZ20 IST Program Off-Line Set Pressure Verification 46

71111.24 Work Orders 5398794, 5399318, 5399330, 5399020, 5526199, 5526200,

5399515, 5525813, 5526108, 5525906, 5405000, 5236837,

5086559, 4559301, 5087230, 5405496, 5405191, 5525506,

25507, 5525408, 5441294, 5525396, 5525494, 5405412,

5405831, 5247323, 5510300, 5461392, 5405891, 5419397,

5471828, 5532150, 5262915, 5537106, 5362779

Inspection Type Designation Description or Title Revision or

Procedure Date

71124.01 Corrective Action 22-04540, 22-04727, 22-04731, 22-04830, 22-04831,

Documents 22-04837, 22-04838, 22-04890, 22-06019, 22-07460,

2-07675, 22-07875, 22-08094, 22-09388, 22-10003,

2-10096, 22-10914, 22-11199, 22-11841, 23-04021,

23-00855, 23-03514, 23-03520

71124.01 Corrective Action 04284, 04249, 04460

Documents

Resulting from

Inspection

71124.01 Miscellaneous List of non-fuel items stored in spent fuel pools 03/17/2023

71124.01 Procedures 01DP-0AP12 Condition Reporting Process 44

71124.01 Procedures 75DP-0RP02 Radioactive Contamination Control 26

71124.01 Procedures 75DP-0RP03 ALARA Program Overview 7

71124.01 Procedures 75RP-0RP01 Radiological Posting and Labeling 37

71124.01 Procedures 75RP-0RP04 Radiation Protection Periodic Review Program 6

71124.01 Procedures 75RP-9OP01 Radiological Controls for Diving Operations 13

71124.01 Procedures 75RP-9OP02 Control of High Radiation Areas, Locked High Radiation 33

Areas, and Very High Radiation Areas

71124.01 Procedures 75RP-9RP02 Radiation Work Permits 32

71124.01 Procedures 75RP-9RP07 Radiation and Contamination Surveys 33

71124.01 Procedures 75RP-9RP09 Control of Vehicles. Equipment and Material 46

71124.01 Procedures 75RP-9RP15 Control and Storage of Radioactive Material and Radioactive 31

Wastes

71124.01 Radiation 2-M-20230418-20 Transfer Canal 04/18/2023

Surveys

71124.01 Radiation 2-M-20230419-22 Breach of valve SIE247 04/19/2023

Surveys

71124.01 Radiation 2-M-20230419-25 Grinding/weld prep for valve 532 04/19/2023

Surveys

71124.01 Radiation 2-M-20230419-7 Transfer Canal 04/19/2023

Surveys

71124.01 Radiation 2-M-20230420-23 Dose rate verification survey on gate valve SCN-V104 04/20/2023

Surveys

71124.01 Radiation 2-M-20230420-28 Valve 247 troubleshooting 04/20/2023

Inspection Type Designation Description or Title Revision or

Procedure Date

Surveys

71124.01 Radiation Work RWP 2-1330 Spent Fuel Transfer Canal Upender Maintenance 0

Permits (RWPs)

71124.01 Radiation Work RWP 2-3306 Primary Side Steam Generator Maintenance 0

Permits (RWPs)

71124.01 Radiation Work RWP 2-3502 Valve, Flange, and Pump Maintenance/Inspection 0

Permits (RWPs)

71124.01 Radiation Work RWP 2-3504 Minor Maintenance 0

Permits (RWPs)

71124.01 Radiation Work RWP 2-3521 Inboard Loop Discharge Check Valve Disassembly, 0

Permits (RWPs) Inspection, and Repair

71124.01 Radiation Work RWP 9-1035 High Risk Radiography Inside the Protected Area 06

Permits (RWPs)

71124.01 Radiation Work RWP-2-1330 Spent Fuel Transfer Upender Maintenance 01

Permits (RWPs)

71124.01 Work Orders 5245515-0 Borg Warner Check Valve - Radiographic Testing Required 04/20/2023

71124.01 Work Orders 5405721-0 Spent Fuel Handling Machine 04/20/2023

71124.04 Corrective Action 20-15826, 21-02705, 21-03859, 21-04318, 21-05093, 21-

Documents 09436, 21-12459, 21-13124, 21-14301, 22-02675, 22-02699,

2-03016, 22-04183, 22-04837, 22-04838, 22-07517, 22-

07529, 22-07963, 22-09416, 22-11301, 22-12190, 23-00875,

23-00976, 23-00985, 23-02599

71124.04 Procedures 75DP-0RP01 RP Program Overview 13

71124.04 Procedures 75DP-9RP01 Radiation Exposure Access Control 24

71124.04 Procedures 75DP-9RP16 Special Dosimetry 27

71124.04 Procedures 75RP-9ME21 DLR Issue, Exchange, and Termination 16

71124.04 Procedures 75RP-9ME24 Dosimetry Processing Evaluation Documentation 06

71124.04 Procedures 75RP-9ME26 Dosimetry Performance Testing 12

71124.04 Procedures 75RP-9ME29 Operation of the Whole Body Counters with APEX-In-Vivo 02

Software

71124.04 Procedures 75RP-9RP03 Bioassay Analysis 11

71124.04 Procedures 75RP-9RP08 Radiological Air Sampling 02

71124.04 Procedures 75RP-9RP10 Conduct of R.P. Operations 40

71124.04 Procedures 75RP-9RP18 Medical Uptakes of Radioisotopes 09

Inspection Type Designation Description or Title Revision or

Procedure Date

71151 Procedures 75RP-0LC02 Performance Indicator Public Radiation Safety Cornerstone05

71151 Procedures 93DP-0LC09 NRC ROP PI Data Collection, Verification and Submittal 12

71151 Procedures 93DP-0LC10 SSFF Mitigating Systems Performance Indicator 6

71152A Calculations 13-MC-FP-0315 10CFR50 Appendix R Safe Shutdown Equipment List

71152A Corrective Action 18-07903, 20-15752, 20-15757, 20-15943, 21-06669, 21-

Documents 06191, 22-05883, 22-03311, 22-05590, 22-03087, 22-01297,

23-01320, 23-01710, 19-04990, 23-01821, 23-04712, 23-

04714, 23-05586, 23-05588, 23-02133, 22-07259, 22-07261,

23-05454, 23-05643, 18-07903

71152A Drawings 01-E-ZPL-001 Power Block Safe Shutdown Emergency Lighting Sheet 1 14

71152A Drawings 01-E-ZPL-001 Power Block Safe Shutdown Emergency Lighting Sheet 1 15

71152A Drawings 01-E-ZPL-002 Power Block Safe Shutdown Emergency Lighting Sheet 2 16

71152A Drawings 01-E-ZPL-003 Power Block Safe Shutdown Emergency Lighting Sheet 3 10

71152A Drawings 01-E-ZPL-004 Power Block Safe Shutdown Emergency Lighting Sheet 4 18

71152A Drawings 02-E-ZPL-002 Power Block Safe Shutdown Emergency Lighting Sheet 2 18

71152A Drawings 02-E-ZPL-003 Power Block Safe Shutdown Emergency Lighting Sheet 3 11

71152A Drawings 02-E-ZPL-004 Power Block Safe Shutdown Emergency Lighting Sheet 4 16

71152A Drawings 03-E-ZPL-002 Power Block Safe Shutdown Emergency Lighting Sheet 2 20

71152A Miscellaneous 13-JN-1034 Procurement Specification for SMP Phase 2 CEDMCS 0

Upgrade

71152A Miscellaneous 4655260 Control Element Drive Mechanism Control System 1

Replacement Modification/Advanced Rod Control Hybrid

(ARCH) SF-1669-SMP phase 2

71152A Miscellaneous JN603-A00030 Project Technical Manual for Target Rock SOV Model No.

77L-001BB-1

71152A Miscellaneous PV-E0772 Level 4 Evaluation Report 22-10492-01 4

71152A Miscellaneous QB DBM Emergency Lighting System 10

71152A Miscellaneous SDOC N001-4 inch BW OL OPER GLOBE VALVE Y PAT

T. SI-659, 660 2

1104-00309 ; V-CE-31753, 21JA85

71152A Miscellaneous WNA-PJ-00713-APS Palo Verde Units 1, 2, & 3 Ovation Strategic 1

CVER1 Modernization Program

71152A Procedures 14DP-0FP02 Fire Systems Impairments and Notifications 28

71152A Procedures 40DP-9ZZ16 Administrative Controls for Appendix R Equipment 13

Inspection Type Designation Description or Title Revision or

Procedure Date

71152A Procedures 40OP-9SI03 Safety Injection Tank Operations 38

71152A Procedures 73DP-9XI01 Pump and Valve Inservice Testing Program 41

71152A Procedures 73ST-9XI13 Train A HPSI Injection and Miscellaneous SI Valves - 37

Quarterly - Inservice Test

71152A Procedures 73ST-9XI14 Train B HPSI Injection and Miscellaneous SI Valves 41

Quarterly - Inservice Test

71152A Procedures 73ST-9XI37 Safety Injection Tank Nitrogen Vent Valves-Inservice Test9

71152A Procedures 73ST-9XI53 Train A HPSI Injection and Miscellaneous SI Valves - Cycle 15

- Inservice Test

71152A Procedures 73ST-9XI54 Stroke Time Testing of Combined Recirc to RWT Valves with 0

Flow

71152A Work Orders 5349035, 5297809, 5531867, 5531870, 5472104, 5515244,

5515550, 5405916, 5514449, 5405920, 5457808, 3470565

71153 Corrective Action 23-03479, 23-05983, 23-05990, 23-05997, 23-06003, 23-

Documents 06018, 23-06125, 23-06128

71153 Miscellaneous Unit 1 Operator logs: April 8-9 04/10/2023

71153 Miscellaneous23-004 June 02, Emergent PRB for U2 Short Notice Outage Restart

23

71153 Procedures 40AO-9ZZ05 Loss of Charging or Letdown 35

71153 Procedures 40AO-9ZZ08 Load Rejection 35

71153 Procedures 40AO-9ZZ12 Degraded Electrical Power 81

71153 Procedures 40AO-9ZZ12 Degraded Electrical Power 80

71153 Procedures 40EP-9EO01 Standard Post Trip Actions 23

71153 Procedures 40EP-9EO02 Reactor Trip 14

71153 Procedures 40EP-9EO07 Loss of Offsite Power / Loss of Forced Circulation 31

71153 Procedures 40OP-9ZZ10 Mode 3 to Mode 5 Operations 72

29