IR 05000528/2023002
| 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:
Report Numbers:
05000528/2023002, 05000529/2023002 and 05000530/2023002
Enterprise Identifier:
I-2023-002-0008
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
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 Aspect Report Section Mitigating Systems Green NCV 05000528, 05000529, 05000530 2023002-01 Open/Closed None 71111.06 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.
REACTOR SAFETY
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,
RADIATION SAFETY
71124.01 - Radiological Hazard Assessment and Exposure Controls
Radiological Hazard Assessment (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated how the licensee identifies the magnitude and extent of radiation levels and the concentrations and quantities of radioactive materials and how the licensee assesses radiological hazards.
Instructions to Workers (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated how the licensee instructs workers on plant-related radiological hazards and the radiation protection requirements intended to protect workers from those hazards.
Contamination and Radioactive Material Control (IP Section 03.03) (2 Samples)
The inspectors observed/evaluated the following licensee processes for monitoring and controlling contamination and radioactive material:
- (1) 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)
- (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 NCV 05000528, 05000529, 05000530 2023002-01 Open/Closed None 71111.06 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
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
17-16819, 17-18094, 22-05649, 22-05829, 22-05881, 22-
05891, 22-06427, 22-06438, 23-03210, 23-06020, 23-06024,
23-06172
Procedures
Switchyard Administrative Control
Procedures
operator outside logs desiccant and dehydrating breather oil
sump level
Procedures
Hot Weather Protection
Procedures
Summer Readiness Administrative Guideline
Work Orders
5446121, 5447303, 5447635, 5448858, 5523266, 5540278,
5540279
Corrective Action
Documents
2-11014, 22-04854, 21-04705
Drawings
2-M-CHP-002
P and I Diagram Chemical and Volume Control System
Drawings
2-M-ECP-001
P & I Diagram Essential Chilled Water System
Drawings
2-M-EWP-001
P & I Diagram Essential Cooling Water System
Drawings
2-M-RCP-001
P & I Diagram Reactor Coolant System
Drawings
2-M-SIP-001
P & I Diagram Safety Injection and Shutdown Cooling
System
Drawings
2-M-SIP-002
P & I Diagram Safety Injection and Shutdown Cooling
System
Drawings
2-M-SIP-003
P & I Diagram Safety Injection and Shutdown Cooling
System
Drawings
03-M-EWP-001
P & I Diagram Essential Cooling Water System
Miscellaneous
DBM
Essential Chilled Water System
Procedures
Essential Chilled Water Train A
Procedures
Essential Cooling Water System (EW) Train A
Procedures
Recovery From Shutdown Cooling To Normal Operating
21
Procedures
Essential Chilled Water Valve Verification
Calculations
13-MC-FP-0802
Fire Hazard Zones Surface Areas
Calculations
13-MC-FP-0803
Combustible Loads - Control Building
Corrective Action
Documents
2-03027, 23-02065, 23-05514, FSCCR 5542265, 23-
05988, 23-06653, 23-06654, 23-06701
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Drawings
01-M-FPP-004
P & I Diagram Fire Protection System (CO2 System)
Fire Plans
Pre-fire Strategies Manual
Miscellaneous
2-R002/22-F009
LCDR: TRM 3.11.104 and UFSAR various Chapter 9 and
Appendix 9B Sections
Miscellaneous
BTP ASB 9.5-1
Guidelines for Fire Protection for Nuclear Power Plants
Miscellaneous
NPL41-D-2Q1B-
Palo Verde Nuclear Fire Department Fire Drill: Unit 1 B
Shift Drill Scenario
05/17/2023
Miscellaneous
NPL41-D-2Q3A-
Palo Verde Nuclear Fire Department Fire Drill: Unit 3 A
Shift Drill Scenario
06/20/2023
Procedures
Emergency Notification and Response
Procedures
Control of Transient Combustibles
Procedures
Fire Protection Test Program Requirement
Procedures
Unit 2 Fire Hose Station Inspection
Procedures
Significant Turbine Building Oil System Leaks
Procedures
Operational Considerations Due to Plant Fire
Procedures
PR-0904
Fire Protection Program Requirement Description
Calculations
13-MC-DG-0204
Diesel Generator Building Flooding Analysis
Calculations
13-MC-DG-0204
Diesel Generator Building Flooding Analysis
Calculations
13-MC-DG-0204
Diesel Generator Building Flooding Analysis
Calculations
13-MC-DG-0204
Diesel Generator Building Flooding Analysis
Corrective Action
Documents
23-00816, 23-01814, 21-12899, 23-05514, 23-06559, 23-
06832
Drawings
01-M-OWP-002
P & I Diagram Oily Waste and Non-Radioactive Waste
System (Diesel Generator Building)
Drawings
2-M-SPP-001
P & I Diagram Essential Spray Pond System
Drawings
13-M095-00003
As-Built ESPS Pump 2-M-SPA-P01 Outline Drawing
Fire Plans
Pre-Fire Strategies Manual
Miscellaneous
15-02910-015
SP-1695 Spray Pond Piping Replacement Phase 1 -
Replace deteriorated Spray Pond piping using a corrosion-
resistant material in the Spray Pond Vaults
Procedures
Panel B02A Alarm Responses
Corrective Action
Documents
23-02856
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
Resulting from
Inspection
23-04228
Drawings
13-SI-174-H008
Pipe Support Assy-CTMT
Drawings
13-SI-174-H008
Pipe Support Assy - Ctmt
Miscellaneous
Inservice Inspection Program Summary Manual
Miscellaneous
VER2-23-OB1-A
Bobbin 24 IPS
NDE Reports
21-UT-2036
RCS Primary Piping
10/14/2021
Procedures
Procedures
Controls for Use of Measuring and Test Equipment (M&TE)
Procedures
Measuring and Test Equipment
Procedures
Boric Acid Walkdown Leak Detection
Procedures
Welder and Procedure Qualification
Procedures
Settlement Monitoring Program
Procedures
Radiographic Examination
Self-Assessments 02-MS-A185
U2R22 Condition Monitoring Evaluation
04/27/2020
Self-Assessments 02-MS-A186
U2C23/25 Steam Generator Operational Assessment
07/22/2020
Self-Assessments 22-03152
Unit 2, 4th Interval, First Period ISI
Self-Assessments 22-06769
Unit 1, 4th Interval, First Period ISI
Work Orders
5406040 TO
Corrective Action
Documents
23-03441, 23-03692, 23-04906, 23-05543, 23-05739, 23-
06116, 23-06319
Miscellaneous
Standard Maneuver Plan: EOC Shutdown 89% to 20% Unit
Cycle 24
Miscellaneous
2305301133
23 Cycle 3 Crew 34 Scenario SES005K07 Evaluation
Summary Sheet
06/16/2023
Miscellaneous
2305301343
23 Cycle 3 Crew 14 Scenario SES005K07 Evaluation
Summary Sheet
06/16/2023
Miscellaneous
374309
Observation: 2023 Cycle 3 - AC Distribution LOCT
06/16/2023
Miscellaneous
SES-0-05-K-07
UV Relay Failure / SG Lvl Xmitter Failure / RCP Seal Fail /
RCP Seizure / ATWS / Feed Line Break
Procedures
Conduct of Operations
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
Standard Post Trip Actions
Procedures
Procedures
Reactor Startup
Procedures
Plant Startup Mode 2 to Mode 1
Procedures
Mode Change Checklist
106
Procedures
Calculation of Estimated Critical Condition
Corrective Action
Documents
23-02792, 23-03074, 21-06458, 23-03479, 22-07768, 23-
2682, 23-05200, 23-05202, 23-05203, 23-05220, 23-06056,
23-06057
Miscellaneous
Phoenix Risk Monitor - PVGS Unit 1 Current Risk Summary
Report as of 4/4/2023 15:30
04/06/2023
Miscellaneous
Risk Management and Readiness Plan for WO 5408456
(A/B) and WO 5408457 (C/D)
Miscellaneous
Risk Management and Readiness Plan to Troubleshoot and
Correct the Continuous Gripper High Voltage for Subgroup 8
and Indication of Blown Fuse
Miscellaneous
High Risk Activity Mitigation Summary - Work Week 2315
Miscellaneous
WW 2315 Schedule Evaluation (4/10-4/162023)
04/12/2023
Miscellaneous
Unit 1 Reactor Trip - April 8, 2023, Plant Review Board
Presentation
Miscellaneous
Shutdown Safety Function Assessment, Unit 2
04/09/2023
Miscellaneous
Shutdown Safety Function Assessment, Unit 2
04/10/2023
Miscellaneous
Shutdown Safety Function Assessment, Unit 2
04/11/2023
Miscellaneous
Shutdown Safety Function Assessment, Unit 2
04/12/2023
Miscellaneous
Site Integrated Risk Assessment Work Task 5519274 - 0
03/21/2023
Miscellaneous
Risk Management and Readiness Plan for WO# 5519274,
Replace U2 CEDMCS PSA for SG 6
Miscellaneous
Risk Management and Readiness Plan: Perform Inspection
and Acceptance Testing of New or Overhauled Breaker, and
Install in Cubicle
06/06/2023
Miscellaneous
Risk Management and Readiness Plan: Unit 2 'B' Control Oil
Pump Filter Change, WO# 5540035
06/06/2023
Miscellaneous
Risk Management and Readiness Plan: Unit 2 'A' Control Oil
Pump Compensator, WO# 5539924
06/07/2023
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
Risk Management and Readiness Plan: WO# 5539924, U2,
CO A - Compensator Adjustment, Adjust Compensator to
1600 psi
06/07/2023
Miscellaneous
Protected Equipment Scheme for CON-P01B B Control Oil
Pump OOS
06/06/2023
Miscellaneous
Phoenix Risk Monitor - PVGS Unit 2 WW 2323 Schedule
Evaluation (6/5/2023 - 6/11/2023
06/07/2023
Miscellaneous
System Training Manual Volume 40 Safety Injection System
(SI)
Miscellaneous
System Training Manual Volume 72 Radioactive Waste
Drain System (RD)
Miscellaneous
Unit 3 Phoenix Risk Monitor-WW 2323 Schedule Evaluation
06/05/2023-06/11/20203
06/09/2023
Miscellaneous
High Risk Activity Mitigation Summary - Work Week 2324
06/13/2023
Miscellaneous
Site Integrated Risk Assessment Work Task 5420476-0
2/17/2023
Miscellaneous
Site Integrated Risk Assessment Work Task 5420475-0
2/17/2023
Miscellaneous
Protected Equipment Scheme for Reactor Trip Breaker A
INOP
06/07/2023
Miscellaneous
Phoenix Risk Monitor - PVGS Unit 3 WW 2323 Schedule
Evaluation (6/5/2023 - 6/11/2023)
06/05/2023
Miscellaneous
Risk Management and Readiness Plan: 36ST-9SB44 - RPS
Matrix Relays to Reactor Trip Response Time Test and
Miscellaneous
Shunt and Undervoltage Trip Functional Test
06/16/2023
Miscellaneous
Risk Management and Readiness Plan: 18-month Reactor
Trip Switchgear Breaker Maintenance and 32ST-9SB02 - 18-
month Surveillance
Miscellaneous
Testing for Westinghouse Type DS-416 Reactor Trip
Switchgear Breakers
06/16/2023
Miscellaneous
TD# 297099
Operations Technical Document for 2JSIAHV0606**VALVEX
- SIT 2B Vent Valve (296984),
05/17/2023
Procedures
Procedure and Work Instruction Use and Adherence
Procedures
Condition Reporting Process
Procedures
Management of Critical Evolutions and Infrequently
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Performed Tests or Evolutions
Procedures
Online Integrated Risk
Procedures
Risk Challenge Meetings
Procedures
Maintenance of Low Voltage Circuit Breakers Type K-600S
and K-Don-600S
Procedures
Month Surveillance Test for Westinghouse Type DS-416
Reactor Trip Breakers
Procedures
Supplementary Protection System Functional Test
Procedures
RPS Matrix Relays to Reactor Trip Response Time Test
Procedures
RTSG Shunt and Undervoltage Trip Functional Test
Procedures
Panel B01B Alarm Responses
Procedures
Protected Equipment
Procedures
Power Block Clearance and Tagging
Procedures
Shutdown Risk Management
Procedures
Containment Entry in MODE 1 through MODE 4
Procedures
Electro-Hydraulic Control System
Procedures
480 Vac Non-Class 1E Switchgear
Procedures
Control Element Drive Mechanism Control System
(CEDMCS) Operation
31A
Procedures
Recovery from Shutdown Cooling to Normal Operating
Lineup
21
Procedures
Containment Cleanliness Inspection
Procedures
Assessment and Management of Risk When Performing
Maintenance in Modes 1 and 2
Work Orders
5408456, 5408457, 5520229, 5399515, 5398794, 5399318,
5399330, 5399020, 5519274, 5534545, 5534542, 5534533,
5443760, 5497627, 5540035, 5539924, 5420475, 5420476,
5402936, 5402969, 5394721, 5402937
Calculations
13-JC-ZZ-0412
Motor Operated Valve Thrust and Torque Calculation for
13JSIBUV0615, 13JSIBUV0625, 13JSIBUV0635 and
13JSIBUV0645
Calculations
13-MC-EC-0252
EC System Water Requirements and Chiller Sizing
Calculations
13-MC-HS-200
Transient Temperature in the Spray Pond Pump Room with
HVAC Exhaust Fan Off
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Calculations
13-MC-SI-0806
Maximum Operating Pressures for Low Pressure CS, SDC
Calculations
13-MC-SI-226
Maximum Operating Pressures for Low Pressure SIS, SCS,
Corrective Action
Documents
23-01616, 17-06807, 23-01904, 21-15236, 23-01202, 17-
06020, 3976805, 3976785, 3989294, 3989295, 23-05193,
23-05437
Drawings
01-P-SIF-136
Containment Building Isometric Safety Injection system HP &
LP Lines Loops 2A, 2B Sheets 1 and 2
Drawings
13-M-SIS-002
ISI Boundary Identification Safety Injection and Shutdown
Cooling System,
Drawings
13-P-ZCG-107
Piping and Mechanical Containment Penetration Reqmts for
Flued Heads
Miscellaneous
13-MC-HS-0008
Spray Pond Ventilation and Equipment Adequacy
Calculation - Appendix A
Miscellaneous
13-MM-095
Specification for Vertical centrifugal pumps, ASME section
III, for the APS company PVNGS Units 1,2,and 3
Miscellaneous
13-NS-C088
Mission Times for the EW, SP, SI, AF, and DG systems
Miscellaneous
13-VTD-D970-
00001
Dresser-Rand (Formerly Terry) Steam Turbine Instruction
Manual
Miscellaneous
CRDR 3012684
Miscellaneous
EC DBM
Essential Chilled Water System
Miscellaneous
EWR 4891467
Miscellaneous
M021-00026
Schematic-Oil Piping
Miscellaneous
PVNGS DBM
Essential Spray Pond System
Miscellaneous
SDOC M095-
00074
Qualification Report Essential Spray Pond Pump Motors
Procedures
Preventive Maintenance Program
Procedures
Panel B02B Alarm Responses
Procedures
Panel B02B Alarm Responses
59B
Procedures
Control Building Watch Station Rounds
28
Procedures
Essential Spray Pond (SP) Train A
Procedures
Auxiliary Feedwater A - Inservice Test
Procedures
Leak Test of SI/RCS Pressure Isolation Valves
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
Leak Test of HPSI/LPSI Containment Isolation Check Valves
Work Orders
5389779, 5513701, 5400419, 2832812, 5404924, 5405419,
5483158
Corrective Action
Documents
23-04392, 23-04573, 23-04863
Drawings
MN725-A00031
Primary Head Palo Verde 2 RSG
Drawings
MN725-A00052
Primary Closure Parts Palo Verde 2 RSG
Engineering
Changes
23-04392-002
Unit 2 Steam Generator 2 - Cold Leg Primary Manway
Gasket Retainer Plate Requires Modification from Original
Design
Miscellaneous
23-00224
Update Vendor Documentation Based Engineering Change
23-04392-002
Miscellaneous
MN725-A00179
Structural and Fatigue Analysis of Primary Manway
Miscellaneous
MN725-A0071
Tentative Sizing of RSG Pressure Boundary
Procedures
Steam Generator Primary Manway Removal and Installation,
MST Method
Procedures
Steam Generator Primary Manway Removal and Installation,
MST Method
28A
Procedures
Design Change Process
Procedures
Conduct of Modifications
Work Orders
5405370, 5405371, 5529567
Corrective Action
Documents
23-03441, 23-04046, 23-03984, 23-04013, 20-02176, 23-
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
Miscellaneous
Unit Two 24th Refueling Outage Shutdown Risk Assessment
Final Report
Miscellaneous
PVGS Unit 2, 24th Refueling Outage
Miscellaneous
Standard Maneuver Plan: EOC Shutdown 89% to 20% Unit
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Cycle 24
Miscellaneous
2R24 Offload Move Package
Miscellaneous
Unit 2 Core and SFP Time To Boil Calculations
04/20/23
04:33
Miscellaneous
Unit 2 Cycle 25 STAR Low Power Physics Testing Without
RMAS Test Data Package
05/11/2023
Miscellaneous
Time Sheet Exceptions Within Date Range 04/08/2023 to
04/22/2023
05/03/2023
Miscellaneous
Time Sheet Exceptions Within Date Range 04/23/2023 to
05/07/2023
05/11/2023
Miscellaneous
Standard Maneuver Plan for Unit 2 Cycle: 75 EFPD 100 to
19%
Procedures
Managing Personnel Fatigue
Procedures
Fuel Integrity Program Implementing Components
Procedures
Foreign Material Exclusion Controls
Procedures
Reactor Vessel Head Removal and Installation
Procedures
Loss of SFP Level or Cooling
Procedures
Conduct of Operations
Procedures
Standard Post Trip Actions
Procedures
Procedures
Lower Mode Functional Recovery
Procedures
FLEX Support Guidelines MODE 1, 2, 3, or 4
Procedures
FLEX Support Guidelines MODE 5, 6, or Defueled
Procedures
Filling and Draining the Refueling Pool using the CS, LPSI,
and HPSI Pumps
Procedures
Refueling Pool Operations
Procedures
Reactor Coolant System Fill and Vent
Procedures
Reactor Startup
Procedures
Power Operations
151
Procedures
Mode Change Checklist
106
Procedures
Outage GOP
Procedures
Short Notice Outage
Procedures
RCS and Pressurizer Heatup and Cooldown Rates
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
Containment Cleanliness Inspection
Procedures
Shutdown Risk Assessments
Procedures
Control of SNM Configuration, Inventory, and Reporting
Procedures
Control or Reactivity Maneuver Plans
Procedures
Core Reloading
Procedures
Calculation of Estimated Critical Condition
Procedures
STAR Low Power Physics Testing Without RMAS
Procedures
Shutdown Margin - Modes 3, 4, and 5
Procedures
Refueling Machine Operations
Work Orders
5405009
Corrective Action
Documents
23-02861, 22-13479, 23-03648, 23-03729, 23-03590, 23-
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
Drawings
PVNGS DBM - Safety Injection System
Drawings
01-M-CHP-002
P & I Chemical and Volume Control System
Drawings
01-M-COP-001
P & I Diagram Main Turbine Control Oil System
Drawings
13-N001-1104-
00041
Valve Assembly Gate 8 Inch, 300 LB., MOTOR OPER.,
CRES
Drawings
13-PN-0220
Specification For Installation of Valve Stem Packing for the
The Arizona Public Service Company Palo Verde Nuclear
generating Station Units 1, 2, and 3
Drawings
VTD-N383-00037
BQ/IP Valves Graphite Bonnet Seal Installation Procedure
Miscellaneous
System Training Manual Volume 9: Main Steam System
(SG)
Miscellaneous
13-EN-0306
Installation Specification for Cable splicing and Terminations
for the Palo Verde Generating Station Units 1, 2, and 3
Quality Class Q, QAG, and NQR
Miscellaneous
PVNGS DBM
Diesel generator, Class 1E Standby Generation, Fuel Oil
Storage and Transfer System
Miscellaneous
VTD-A391-00010
Vendor Technical Document: Anchor/Darling Instruction
Manual for Main Steam Isolation Valves (MSIV) and
Feedwater Isolation Valves (FWIV) [PUB.#E9023-9]
Miscellaneous
VTD-G250-00002
Greer Hydraulics Operation and Maintenance Instructions for 5
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Gallon Pulse-Tone
Procedures
Controls for Use of Measuring and Test Equipment (M&TE)
Procedures
Train A Integrated Safeguards (ISG) Testing
Procedures
Low Voltage Motor Testing (Less Than 600 Vac)
Procedures
Essential Chiller
Procedures
Panel B06B Alarm Responses
Procedures
Charging Pump Suction Stabilizer and Discharge Pulsation
Dampener Operation
Procedures
Electro-hydraulic Control System
Procedures
Procedures
Procedures
2a
Procedures
Containment Leakage Rate Testing Program
Procedures
ASME Section XI Inservice Inspection
Procedures
Motor Operated Valve (MOV) Program
Procedures
Heat Exchanger Visual Inspection
Procedures
Motor Operated (MOV) Testing with Quiklook
Procedures
Charging Pumps - Comprehensive Test
Procedures
Charging Pumps - Inservice Test
Procedures
Containment Leakage Type B and C Testing
Procedures
Class 1E Diesel Generator and Integrated Safeguards Test
Train B
Procedures
Essential Chilled Water Pumps - Inservice Test
Procedures
Leak Rate of SI/RCS Pressure Isolation Valves
Procedures
ADVs - Inservice Test
Procedures
SIT Isolation and Outlet Check Valves Inservice Test
Procedures
IST Program Off-Line Set Pressure Verification
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
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
2-04540, 22-04727, 22-04731, 22-04830, 22-04831,
2-04837, 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
Corrective Action
Documents
Resulting from
Inspection
284, 04249, 04460
Miscellaneous
List of non-fuel items stored in spent fuel pools
03/17/2023
Procedures
Condition Reporting Process
Procedures
Radioactive Contamination Control
Procedures
ALARA Program Overview
Procedures
Radiological Posting and Labeling
Procedures
Radiation Protection Periodic Review Program
Procedures
Radiological Controls for Diving Operations
Procedures
Control of High Radiation Areas, Locked High Radiation
Areas, and Very High Radiation Areas
Procedures
Radiation Work Permits
Procedures
Radiation and Contamination Surveys
Procedures
Control of Vehicles. Equipment and Material
Procedures
Control and Storage of Radioactive Material and Radioactive
Wastes
Radiation
Surveys
2-M-20230418-20
Transfer Canal
04/18/2023
Radiation
Surveys
2-M-20230419-22
Breach of valve SIE247
04/19/2023
Radiation
Surveys
2-M-20230419-25
Grinding/weld prep for valve 532
04/19/2023
Radiation
Surveys
2-M-20230419-7
Transfer Canal
04/19/2023
Radiation
Surveys
2-M-20230420-23
Dose rate verification survey on gate valve SCN-V104
04/20/2023
Radiation
2-M-20230420-28
Valve 247 troubleshooting
04/20/2023
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Surveys
Radiation Work
Permits (RWPs)
RWP 2-1330
Spent Fuel Transfer Canal Upender Maintenance
Radiation Work
Permits (RWPs)
RWP 2-3306
Primary Side Steam Generator Maintenance
Radiation Work
Permits (RWPs)
RWP 2-3502
Valve, Flange, and Pump Maintenance/Inspection
Radiation Work
Permits (RWPs)
RWP 2-3504
Minor Maintenance
Radiation Work
Permits (RWPs)
RWP 2-3521
Inboard Loop Discharge Check Valve Disassembly,
Inspection, and Repair
Radiation Work
Permits (RWPs)
RWP 9-1035
High Risk Radiography Inside the Protected Area
Radiation Work
Permits (RWPs)
RWP-2-1330
Spent Fuel Transfer Upender Maintenance
Work Orders
245515-0
Borg Warner Check Valve - Radiographic Testing Required
04/20/2023
Work Orders
5405721-0
Spent Fuel Handling Machine
04/20/2023
Corrective Action
Documents
20-15826, 21-02705, 21-03859, 21-04318, 21-05093, 21-
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
Procedures
RP Program Overview
Procedures
Radiation Exposure Access Control
Procedures
Special Dosimetry
Procedures
DLR Issue, Exchange, and Termination
Procedures
Dosimetry Processing Evaluation Documentation
Procedures
Dosimetry Performance Testing
Procedures
Operation of the Whole Body Counters with APEX-In-Vivo
Software
Procedures
Bioassay Analysis
Procedures
Radiological Air Sampling
Procedures
Conduct of R.P. Operations
Procedures
Medical Uptakes of Radioisotopes
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71151
Procedures
Performance Indicator Public Radiation Safety Cornerstone
71151
Procedures
NRC ROP PI Data Collection, Verification and Submittal
71151
Procedures
SSFF Mitigating Systems Performance Indicator
Calculations
13-MC-FP-0315
10CFR50 Appendix R Safe Shutdown Equipment List
Corrective Action
Documents
18-07903, 20-15752, 20-15757, 20-15943, 21-06669, 21-
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
Drawings
01-E-ZPL-001
Power Block Safe Shutdown Emergency Lighting Sheet 1
Drawings
01-E-ZPL-001
Power Block Safe Shutdown Emergency Lighting Sheet 1
Drawings
01-E-ZPL-002
Power Block Safe Shutdown Emergency Lighting Sheet 2
Drawings
01-E-ZPL-003
Power Block Safe Shutdown Emergency Lighting Sheet 3
Drawings
01-E-ZPL-004
Power Block Safe Shutdown Emergency Lighting Sheet 4
Drawings
2-E-ZPL-002
Power Block Safe Shutdown Emergency Lighting Sheet 2
Drawings
2-E-ZPL-003
Power Block Safe Shutdown Emergency Lighting Sheet 3
Drawings
2-E-ZPL-004
Power Block Safe Shutdown Emergency Lighting Sheet 4
Drawings
03-E-ZPL-002
Power Block Safe Shutdown Emergency Lighting Sheet 2
Miscellaneous
13-JN-1034
Procurement Specification for SMP Phase 2 CEDMCS
Upgrade
Miscellaneous
4655260
Control Element Drive Mechanism Control System
Replacement Modification/Advanced Rod Control Hybrid
(ARCH) SF-1669-SMP phase 2
Miscellaneous
JN603-A00030
Project Technical Manual for Target Rock SOV Model No.
Miscellaneous
PV-E0772
Level 4 Evaluation Report 22-10492-01
Miscellaneous
QB DBM
Emergency Lighting System
Miscellaneous
SDOC N001-
1104-00309
inch BW OL OPER GLOBE VALVE Y PAT
- T. SI-659, 660
- V-CE-31753, 21JA85
Miscellaneous
WNA-PJ-00713-
CVER1
APS Palo Verde Units 1, 2, & 3 Ovation Strategic
Modernization Program
Procedures
Fire Systems Impairments and Notifications
Procedures
Administrative Controls for Appendix R Equipment
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
Safety Injection Tank Operations
Procedures
Pump and Valve Inservice Testing Program
Procedures
Train A HPSI Injection and Miscellaneous SI Valves -
Quarterly - Inservice Test
Procedures
Train B HPSI Injection and Miscellaneous SI Valves
Quarterly - Inservice Test
Procedures
Safety Injection Tank Nitrogen Vent Valves-Inservice Test
Procedures
Train A HPSI Injection and Miscellaneous SI Valves - Cycle
- Inservice Test
Procedures
Stroke Time Testing of Combined Recirc to RWT Valves with
Flow
Work Orders
5349035, 5297809, 5531867, 5531870, 5472104, 5515244,
5515550, 5405916, 5514449, 5405920, 5457808, 3470565
Corrective Action
Documents
23-03479, 23-05983, 23-05990, 23-05997, 23-06003, 23-
06018, 23-06125, 23-06128
Miscellaneous
Unit 1 Operator logs: April 8-9
04/10/2023
Miscellaneous23-004 June 02,
23
Emergent PRB for U2 Short Notice Outage Restart
Procedures
Loss of Charging or Letdown
Procedures
Load Rejection
Procedures
Degraded Electrical Power
Procedures
Degraded Electrical Power
Procedures
Standard Post Trip Actions
Procedures
Procedures
Loss of Offsite Power / Loss of Forced Circulation
Procedures
Mode 3 to Mode 5 Operations
2