ML21028A440

PV 2020 004 Integrated Inspection Report CAP

ML21028A440
Person / Time
Site:	Palo Verde
Issue date:	01/28/2021
From:	John Dixon NRC/RGN-IV/DRP
To:	Lacal M Arizona Public Service Co
References
IR 2020004
Download: ML21028A440 (16)

Text

January 28, 2021 Mrs. Maria Lacal Executive Vice President / Chief Nuclear Officer Arizona Public Service Company P.O. Box 52034, MS 7602 Phoenix, AZ 85072-2034

SUBJECT:

PALO VERDE NUCLEAR GENERATING STATION UNITS 1, 2, AND 3 -

INTEGRATED INSPECTION REPORT 05000528/2020004, 05000529/2020004 AND 05000530/2020004

Dear Mrs. Lacal:

On December 31, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Palo Verde Nuclear Generating Station Units 1, 2, and 3. On January 5, 2021, the NRC inspectors discussed the results of this inspection with you and other members of your staff. The results of this inspection are documented in the enclosed report.

No findings or violations of more than minor significance were identified during this inspection.

This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely, John L. Digitally signed by John L. Dixon Dixon Date: 2021.01.28 14:13:34 -06'00' John L. Dixon, Jr., Chief Reactor Projects Branch D Division of Reactor Projects Docket Nos. 05000528, 05000529 and 05000530 License Nos. NPF-41, NPF-51 and NPF-74

Enclosure:

As stated cc w/ encl: Distribution via LISTSERV

ML21028A440 SUNSI Review Non-Sensitive Publicly Available Pvossmar Sensitive Non-Publicly Available OFFICE SRI:DRP/D RI:DRP/D RI:DRP/D BC:DRS/EB2 BC:DRS/OB CPeabody NAME RBywater RLB ELantz ERL CYoung chy GWerner / GEW CAP DATE 1/27/2021 1/26/2021 1/26/2021 1/26/2021 01/26/2021 OFFICE BC:DRS/RCB TL:DRS/IPAT BC:DNMS/RIB BC:DRS/EB1 SPE:DRP/D BC:DRP/D NAME MHaire MH AAgrawal ANA GWarnick /RA VGaddy VGG PVossmar PJV JDixon JLD For/ NAG DATE 01/26/2021 1/26/21 1/27/2021 1/27/2021 01/26/21 1/28/2021 U.S. NUCLEAR REGULATORY COMMISSION Inspection Report Docket Numbers: 05000528, 05000529 and 05000530 License Numbers: NPF-41, NPF-51 and NPF-74 Report Numbers: 05000528/2020004, 05000529/2020004 and 05000530/2020004 Enterprise Identifier: I-2020-004-0001 Licensee: Arizona Public Service Company Facility: Palo Verde Nuclear Generating Station Units 1, 2, and 3 Location: Tonopah, AZ Inspection Dates: October 1, 2020 to December 31, 2020 Inspectors: C. Peabody, Senior Resident Inspector R. Bywater, Senior Resident Inspector E. Lantz, Resident Inspector J. Drake, Senior Reactor Inspector N. Greene, Senior Health Physicist M. Hayes, Operations Engineer N. Hernandez, Operations Engineer D. You, Operations Engineer Approved By: John L. Dixon, Jr., Chief Reactor Projects Branch D Division of Reactor Projects Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Palo Verde Nuclear Generating Station Units 1, 2, and 3, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.

List of Findings and Violations No findings or violations of more than minor significance were identified.

Additional Tracking Items Type Issue Number Title Report Section Status LER 05000529/2020-001-01 LER 2020-001-01 for Palo 71153 Closed Verde, Unit 2, Reactor Trip on Low Steam Generator Level Signal 2

PLANT STATUS Unit 1 entered the inspection period at full power then shut down for a planned refueling outage between October 9 and December 2, 2020. Unit 1 operated at full power for the remainder of the inspection period.

Units 2 and 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 plant status activities described in IMC 2515, Appendix D, Plant Status, and conducted routine reviews using IP 71152, Problem Identification and Resolution. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.

Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the Coronavirus Disease 2019 (COVID-19), resident inspectors were directed to begin telework and to remotely access licensee information using available technology. During this time, the resident inspectors performed periodic site visits each week; conducted plant status activities as described in IMC 2515, Appendix D, Plant Status; observed risk-significant activities; and completed on-site portions of IPs. In addition, resident and regional baseline inspections were evaluated to determine if all or portions of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In some cases, portions of an IP were completed remotely and on-site. The inspections documented below met the objectives and requirements for completion of the IP.

REACTOR SAFETY 71111.01 - Adverse Weather Protection External Flooding Sample (IP Section 03.03) (1 Sample)

(1) The inspectors evaluated readiness to cope with a seismic event following the September 30, 2020, magnitude 4.9 earthquake near Westmoreland, CA, by performing walkdowns of plant systems, structures, and components, on October 1, 2020.

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71111.04 - Equipment Alignment Partial Walkdown Sample (IP Section 03.01) (3 Samples)

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

(1) Unit 3, Class 1E 4.16kVac power distribution system A, on December 13, 2020 (2) Unit 3, Class 1E 125Vdc power distribution system A and C, on December 13, 2020 (3) Unit 2, Class 1E 125Vdc power distribution system A and C, on December 13, 2020 71111.05 - Fire Protection Fire Area Walkdown and Inspection Sample (IP Section 03.01) (4 Samples)

The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:

(1) Unit 3, diesel generator A and B rooms, Fire Zones 21A and 21B, on October 6, 2020 (2) Unit 2, control room, Fire Zone 17, on December 3, 2020 (3) Unit 3, control room, Fire Zone 17, on December 9, 2020 (4) Unit 2, main turbine operating deck and main turbine bearings, Fire Zones TB9 and TB10, on December 13, 2020 71111.06 - Flood Protection Measures Inspection Activities - Internal Flooding (IP Section 03.01) (1 Sample)

The inspectors evaluated internal flooding mitigation protections in the:

(1) Unit 3, essential pipe density tunnel, on November 16, 2020 71111.08P - Inservice Inspection Activities (PWR)

PWR Inservice Inspection Activities Sample (IP Section 03.01) (1 Sample)

(1) The inspectors verified that the reactor coolant system boundary, steam generator tubes, reactor vessel internals, risk-significant piping system boundaries, and containment boundary are appropriately monitored for degradation and that repairs and replacements were appropriately fabricated, examined and accepted by reviewing the following activities from October 12 to October 30, 2020:

03.01.a - Nondestructive Examination and Welding Activities.

The inspectors evaluated non-destructive examination activities by reviewing the following records:

(1) Ultrasonic Examinations a) Reactor Coolant System, Hot leg, Weld 3-100-JR 4

b) Reactor Coolant System, Hot Leg, Weld 3-100-IR (2) VT-3 Examinations a) Reactor Coolant System, Reactor Head to Vessel Bolted Connection b) Reactor Coolant System, Pressurizer manway bolting c) Steam Generator, Steam Generator 1 manway bolting d) Steam Generator, Steam Generator 2 manway bolting (3) Magnetic Particle Examinations a) Polar Crane, 225 Polar Crane Hook b) Reactor Head lifting equipment, Delta Beam Lifting Bale c) Reactor Head lifting equipment, Delta Beam Lifting Yoke 03.01.c - Pressurized-Water Reactor Boric Acid Corrosion Control Activities.

The inspectors reviewed the following boric acid condition reports and associated boric acid evaluations:

• 19-06111

• 19-04985

• 19-04891

• 19-04946

• 19-06586

• 19-06702

• 19-04892

• 19-04890

• 19-04893

• 20-06694

• 20-10549

• 20-10421

• 20-12917 The inspector evaluated a sample of 43 condition reports associated with inservice inspection activities. The inspector did not identify any findings or violations of more than minor significance.

71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance Requalification Examination Results (IP Section 03.03) (1 Sample)

(1) The inspectors reviewed and evaluated the licensed operator examination failure rates for the requalification annual operating exam administered August 27 through October 3, 2020.

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71111.11B - Licensed Operator Requalification Program and Licensed Operator Performance Licensed Operator Requalification Program (IP Section 03.04) (1 Sample)

(1) The inspection was completed and documented in Palo Verde Inspection Report 05000528/2020011, 05000529/2020011, and 05000530/2020011.

71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01)

(1 Sample)

(1) The inspectors observed and evaluated Unit 1 operators conducting a controlled shutdown and cooldown to begin refueling outage 1R22 on October 9-10, 2020.

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

(1) The inspectors observed and evaluated a loss of offsite power and loss of forced circulation simulator exercise on December 3, 2020.

71111.12 - Maintenance Effectiveness Maintenance Effectiveness (IP Section 03.01) (3 Samples)

The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:

(1) 10 CFR 50.69 system categorization review and integrated decision-making panel for the chemical and volume control system, on October 1, 2020 (2) 10 CFR 50.69 system categorization review and integrated decision-making panel for the fuel pool cooling and cleanup system, on October 20, 2020 (3) 10 CFR 50.69 system categorization review and integrated decision-making panel for the essential cooling water system, on November 13, 2020 71111.13 - Maintenance Risk Assessments and Emergent Work Control Risk Assessment and Management Sample (IP Section 03.01) (3 Samples)

The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:

(1) Unit 1, spent fuel pool cooling shutdown safety assessment, on October 28, 2020 (2) Unit 3, application of freeze seal to repair charging pump B isolation valve, on November 9, 2020 (3) Unit 1, emergent work to de-energize Class 1E 4kV B electrical bus to replace a damaged alternate feeder breaker line bushing, on November 13, 2020 6

71111.15 - Operability Determinations and Functionality Assessments Operability Determination or Functionality Assessment (IP Section 03.01) (4 Samples)

The inspectors evaluated the licensees justifications and actions associated with the following operability determinations and functionality assessments:

(1) Unit 1, start-up channel 1 neutron instrumentation intermittent spiking prior to core offload, on October 20, 2020 (2) Unit 2, core monitoring computer reverted from mid core life to early core life input files when resetting to synch with the core operating limits supervisory system, on November 4, 2020 (3) Unit 3, diesel generator B fuel oil transfer pump low discharge pressure alarm, on November 12, 2020 (4) Unit 3, steam generator 2 high-level alarm setpoint drift, on November 20, 2020 71111.19 - Post-Maintenance Testing Post-Maintenance Test Sample (IP Section 03.01) (3 Samples)

The inspectors evaluated the following post-maintenance test activities to verify system operability and functionality:

(1) 73ST-9SI10, Unit 1 high pressure safety injection pumps A and B mini-flow test following low flow indication and alarm flow transmitter replacement, on November 10, 2020 (2) 73ST-9XI52, Unit 1 motor operated valve testing on low pressure safety injection valve SIB-UV-307 following periodic valve operator maintenance, on November 12, 2020 (3) 72IC-9RX03, Unit 1 start-up channel #1 neutron instrumentation response check following repairs, on November 17, 2020 71111.20 - Refueling and Other Outage Activities Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated Unit 1 Refueling Outage 22 activities from October 10 to December 2, 2020.

71111.22 - Surveillance Testing The inspectors evaluated the following surveillance tests:

Surveillance Tests (other) (IP Section 03.01) (3 Samples)

(1) Unit 1, integrated safeguards A testing, on October 13, 2020 (2) Unit 1, containment sump B to safety injection containment isolation valve, SIB-UV-675, testing on October 29, 2020 (3) Unit 3, diesel generator fuel oil transfer pump B test, on November 18, 2020 7

Inservice Testing (IP Section 03.01) (1 Sample)

(1) Unit 1, containment sump B to safety injection containment isolation valve SIB-UV-676 testing, on October 29, 2020 OTHER ACTIVITIES - BASELINE 71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:

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

(1) April 20, 2019, through September 30, 2020 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) April 20, 2019, through September 30, 2020 71152 - Problem Identification and Resolution Semiannual Trend Review (IP Section 02.02) (1 Sample)

(1) The inspectors reviewed the licensees corrective action program for trends in vendor-contractor performance, oversight and communications that might be indicative of a more significant safety issue.

Based the reviewed activities, the inspectors concluded that the licensee was aware of this trend and is taking actions accordingly to improve vendor and contractor communication and oversight around the station. The licensee initiated Condition Report 20-16860 in response to this inspection.

71153 - Followup of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02) (1 Sample)

The inspectors evaluated the following licensee event reports (LERs):

(1) LER 05000529/2020-001-01, Unit 2 Reactor Trip on Low Steam Generator Level Signal (ADAMS Accession No. ML20255A153). The inspectors determined that it was not reasonable to foresee or correct the cause discussed in the LER therefore no performance deficiency was identified. The inspectors did not identify a violation of NRC requirements.

INSPECTION RESULTS No findings were identified.

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EXIT MEETINGS AND DEBRIEFS The inspectors verified no proprietary information was retained or documented in this report.

• On October 22, 2020, the inspectors presented the radiation safety inspection results to Mr. T. Horton, Senior Vice President, Site Operations, and other members of the licensee staff.

• On October 30, 2020, the inspectors presented the Unit 1 Inservice Inspection results to Mr. B. Rash, Vice President, Nuclear Engineering and Regulatory Affairs, and other members of the licensee staff.

• On January 5, 2021, the inspectors presented the integrated inspection results to Mrs. M. Lacal, Executive Vice President, Chief Nuclear Officer, and other members of the licensee staff.

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DOCUMENTS REVIEWED Inspection Type Designation Description or Title Revision or Procedure Date 71111.01 Corrective Action Condition Reports 20-12376, 20-12377 Documents Miscellaneous EP-0930A EAL Classification Matrix Procedures 40AO-9ZZ21 Acts of Nature 39 79IS-9SM01 Analysis of Seismic Event 27 71111.04 Corrective Action Condition Reports 18-15079, 20-06739, 20-01996, 20-07309, 20-12061 Documents Drawings 02-E PKA-002 Single Line Diagram 125V DC Class IE and 120V AC Vital 21 Instrument Power System DC Control Center 3E-PKA-M41 02-E PKA-003 Single Line Diagram 125V DC Class IE and 120V AC Vital 8 Instrument Power System DC Distribution Panel 3E-PKA-D21 02-E PKA-004 Single Line Diagram 125V DC Class IE and 120V AC Vital 14 Instrument Power System DC Control Center 3E-PKA-M43 and 3E-PKA-D23 02-E-PKA-001 Main Single Line Diagram 125V DC Class IE and 120V AC 8 Vital Instrument Power System 03-E PKA-002 Single Line Diagram 125V DC Class IE and 120V AC Vital 20 Instrument Power System DC Control Center 3E-PKA-M41 03-E PKA-003 Single Line Diagram 125V DC Class IE and 120V AC Vital 7 Instrument Power System DC Distribution Panel 3E-PKA-D21 03-E PKA-004 Single Line Diagram 125V DC Class IE and 120V AC Vital 13 Instrument Power System DC Control Center 3E-PKA-M43 and 3E-PKA-D23 03-E-PBA-001 Single Line Diagram 4.16kV Class 1E Switchgear 3E-PBA- 14 S03 03-E-PKA-001 Main Single Line Diagram 125V DC Class IE and 120V AC 8 Vital Instrument Power System 71111.05 Corrective Action Condition Reports 18-02692, 20-12625, 20-12640 Documents Miscellaneous PVGS Pre-Fire Strategies Manual 29 10

Inspection Type Designation Description or Title Revision or Procedure Date DEC-00093 DG Roll-Up Door Replacement USAR Sect 9B Fire Hazards Analysis 19 Procedures 40DP-9ZZ17 Control of Doors, Hatches, and Floor Plugs 64 71111.06 Miscellaneous Updated Final Safety Analysis Report 20B 13-MC-ZY-599 Essential Pipe Density Tunnel Flooding 0 Procedures 40DP-9ZZ17 Control of Doors, Hatches, and Floor Plugs 64 71111.08P Corrective Action Condition Reports 18-00825, 18-01203, 18-02177, 18-04095, 18-05832, Documents 18-06500, 18-11707, 18-12490, 18-13148, 18-13165, 18-14430, 18-17446, 18-18657, 19-03488, 19-03490, 19-03492, 19-03493, 19-03494, 19-06374, 19-06472, 19-10534, 19-14378, 19-15680, 19-18430, 19-18565, 20-04629, 20-04524, 20-05105, 20-05322, 20-05978, 20-07930, 20-09968, 20-10421, 20-10634, 20-11240, 20-11304, 20-11579, 20-11583, 20-10007, 20-11584, 20-12149, 20-12176, 20-12247, 20-12490, 20-12176 Corrective Action Condition Reports 20-12382, 20-14736, 20-14737, 20-14738 Documents Resulting from Inspection Procedures 70TI-9ZC01 Boric Acid Walkdown Leak Detection 23 73DP-9WP04 Welding and Brazing Control 11 73DP-9ZC01 Boric Acid Corrosion Control Program 8 73TI-9ZZ05 Dry Magnetic Examination 19 73TI-9ZZ07 Liquid Penetrant Examination 19 73TI-9ZZ10 Ultrasonic Examination of Welds in Ferritic Components 15 73TI-9ZZ17 Visual Examination of Welds, Bolting, and Components 14 73TI-9ZZ18 Visual Examination of Component Supports 17 73TI-9ZZ22 Visual Examination For Leakage 13 73WP-9WP05 Weld Filler Material Control 11 MN756-A00009, Generic Procedure for the Ultrasonic Examination of D PDI-UT-11 Reactor Pressure Vessel Nozzle-to-Shell Welds and the Nozzle Inner Corner Radius MRP-058 Materials Reliability Program: Boric Acid Corrosion 2 Guidebook: Managing Boric Acid Corrosion Issues at PWR 11

Inspection Type Designation Description or Title Revision or Procedure Date Power Stations PDI-UT-1 PDI Generic Procedure for the Ultrasonic Examination of 1G Ferritic Pipe Welds PDI-UT-2 PDI Generic Procedure for the Ultrasonic Examination of 4 Austenitic Pipe Welds PDI-UT-5 PDI Generic Procedure for the Straight Beam Ultrasonic 3 Examination of Bolts and Studs Self-Assessments 17-09564 Welding Program Self Assessment 06/28/2017 18-14430-002 ISI Simple Self Assessment 03/29/2019 20-04619-002 BACC Simple self-assessment 08/27/2020 20-04629-002 NDE Self Assessment for MRV 07/02/2020 Work Orders 4151839 Remove and reinstall 1PSIEL210 4959314 Replace Valve 1PSGEV023 5127352 Resurfacing of cladding at Head Flange 71111.11A Miscellaneous 2020 PVNGS Annual Operating Exam Results 10/03/2020 OT03 2019-2020 2020 Annual Operating Test Sample Plan Procedures 15DP-0OT04 LOCT Annual and Biennial Exam Administration 7 71111.11Q Corrective Action Condition Reports 20-12809 Documents Miscellaneous NLR20S050101 Licensed Operator Continuing Training: LOOP/LOFC 11/04/2020 Procedures 40OP-9ZZ23 Outage GOP 83 71111.12 Drawings 01-M-PCP-001 Fuel Pool Cooling & Cleanup System 36 Miscellaneous Palo Verde Generating Station 10CFR50.69 System 10/06/2020 Categorization Fuel Pool Cooling & Cleanup Palo Verde Generating Station 10 CFR 50.69 System 11/13/2020 Categorization Document Essential Cooling Water System Palo Verde Generating Station 10 CFR 50.69 System 10/01/2020 Categorization Document Chemical and Volume Control System Procedures 01DP-0RS07 10 CFR 50.69 Program 1 01DP-0RS08 10 CFR 50.69 Active Component Categorization from 1 Qualitative Assessment and Defense in Depth 01DP-0RS09 10 CFR 50.69 Active Component Categorization from Risk 2 12

Inspection Type Designation Description or Title Revision or Procedure Date Hazard Assessments 01DP-0RS10 10 CFR 50.69 Passive Component Categorization 1 01DP-0RS11 10 CFR 50.69 Alternative Treatment Requirements 2 01DP-0RS12 10 CFR 50.69 Requirements for Immediate Reviews, 0 Periodic Reviews, and Performance Monitoring 71111.13 Corrective Action Condition Reports 20-14015, 20-14118, 20-14815 Documents Drawings 01-M-PCP-001 1R22 Outage Control Center Turnover 10/26/2020 01-M-PCP-001 Fuel Pool Cooling and Cleanup System 36 Miscellaneous 1R22 Outage Control Center Turnover 10/28/2020 1R22 Outage Control Center Turnover 10/27/2020 417947 Clearance Order Tagout and Restoration for Unit 1 B Class 11/15/2020 1E 4kV Bus Deenergization for Emergent Work Repairs PRB Meeting Plant Review Board Meeting Presentation to discuss 11/12/2020 Shutdown Risk Assessment Impacts of Unit 1 B Class 1E 4kV Bus Deenergization for Emergent Work Repairs Procedures 02DP-0RS01 Online Integrated Risk 9 02DP-9RS01 Configuration Risk Management and Risk Informed 3 Completion Time Programs 40DP-9RS02 Shutdown Risk Management 6 40DP-9RS03 Risk Management Actions 0 Work Orders 5285491 71111.15 Corrective Action Condition Reports 19-10645, 20-13464, 20-14855, 20-15290 Documents Miscellaneous Palo Verde Unit 3 Work Week 2046 Online Risk Assessment 11/09/2020 Revision to Support Freeze Seal for Charging Pump B Isolation Valve Repair 20-14855 11/09/2020 Procedures 36ST-9SB02 PPS Bistable Trip Units Functional Test 50 40DP-9OP26 Operations Condition Reporting Process and Operability 47 Determination / Functionality Assessment Work Orders 5282335, 5284212 71111.19 Corrective Action Condition Reports 20-14889, 20-15133 Documents 13

Inspection Type Designation Description or Title Revision or Procedure Date Procedures 72IC-9RX03 Core Reloading 54 73ST-9SI10 HPSI Pumps Miniflow - Inservice Test 54 73ST-9XI52 Safety Injection Train B ECCS Throttle Valves - Inservice 3 Test Work Orders 4939054, 4939061, 5160348, 5161298, 5284212-2 71111.20 Corrective Action Condition Reports 20-14072, 3721627 Documents Miscellaneous 102-03641- Nuclear Regulatory Affairs Position Statement Regarding 03/29/1996 AKK/NLT TS Definition 1.9, CORE ALTERATION Procedures 40OP-9ZZ23 Outage GOP 83 71111.22 Corrective Action Condition Reports 20-12972, 20-12291, 20-13788 Documents Drawings 01-M-SIP-001 Safety Injection and Shutdown Cooling System 60 Procedures 73ST-9DF01 Diesel Fuel Oil Transfer Pump - Inservice Test 36 73ST-9DG01 Class 1E Diesel Generator and Integrated Safeguards Test 31 Train A 73ST-9XI04 SI Train B Valves Inservice Test 40 73ST-9XI43 Containment Recirculation Sump Isolation Valve Leak 6 Testing Work Orders 5286827, 5152726, 5208728 71151 Miscellaneous RCTSAI 1566 Palo Verde Nuclear Generating Station 2018 Annual 04/16/2019 Radioactive Effluent Release Report RCTSAI 1566 Palo Verde Nuclear Generating Station 2019 Annual 04/17/2020 Radioactive Effluent Release Report 71152 Corrective Action Condition Reports 17-13171, 18-00202, 18-02605, 18-07903, 18-15177, Documents 19-10949, 19-16201, 19-16938, 19-18595, 19-18776, 20-01928, 20-06558, 20-06565, 20-07210 14