IR 05000482/2021010

From kanterella
Revision as of 22:45, 3 October 2021 by StriderTol (talk | contribs) (StriderTol Bot change)
Jump to navigation Jump to search
Design Basis Assurance Inspection (Teams) Inspection Report 05000482/2021010
ML21243A099
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 09/09/2021
From: Vincent Gaddy
Region 4 Engineering Branch 1
To: Reasoner C
Wolf Creek
References
IR 2021010
Download: ML21243A099 (16)
v • d • e


Text

September 09, 2021

SUBJECT:

WOLF CREEK GENERATING STATION - DESIGN BASIS ASSURANCE INSPECTION (TEAMS) INSPECTION REPORT 05000482/2021010

Dear Mr. Reasoner:

On August 12, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Wolf Creek Generating Station and discussed the results of this inspection with Mr. J. McCoy, Site Vice President, 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, Vincent G. Digitally signed by Vincent G.

Gaddy Gaddy Date: 2021.09.09 09:14:19-05'00'

Vincent G. Gaddy, Chief Engineering Branch 1 Division of Reactor Safety Docket No. 05000482 License No. NPF-42 Enclosure:

As stated cc w/ encl: Distribution via LISTSERV

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a design basis assurance inspection (teams) inspection at Wolf Creek 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

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

Additional Tracking Items

None.

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 reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.

Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the coronavirus (COVID-19), inspectors were directed to begin telework. In addition, regional baseline inspections were evaluated to determine if all or a portion of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In some cases, portions of an IP were completed remotely and on site. The inspections documented below met the objectives and requirements for completion of the IP.

REACTOR SAFETY

===71111.21M - Design Bases Assurance Inspection (Teams) The inspectors evaluated the following components and listed applicable attributes, permanent modifications, and operating experience:

Design Review - Risk-Significant/Low Design Margin Components (IP Section 02.02) (5 Samples 1 Partial)

(1) 125 V DC Bus NK01
  • Walkdown of 125 V DC system
  • System health reports, component maintenance history, and corrective action program documents
  • Calculations for electrical distribution, system load flow/voltage drop, short-circuit, and electrical protection
  • Protective device settings and feeder circuit breaker ratings
  • Procedures for preventive maintenance, inspection, and testing
  • Results of completed preventative maintenance on the bus, load center, transformer, and feeder breakers
  • Maintenance programs for batteries and battery chargers associated with the bus
  • Calculations for the AC input to the battery chargers
(2) 4.16 KV Class 1E Switchgear NB001
  • Design basis calculations
  • Corrective actions resulting from previous violations
  • Vendor documents and recommendations
  • Circuit breaker wiring diagrams
  • Degraded voltage relaying setpoint calculations
  • Component maintenance history
  • Circuit breaker protective device settings
  • Procedures for preventive maintenance, inspection, and testing
(3) Main Steam Isolation Valve ABHV0011
  • Component maintenance history and system health reports
  • Corrective action documents
  • Preventive maintenance bases
  • Maintenance rule status and basis documents
  • Procedures for inservice testing
  • Acceptance criteria for actuation logic and slave relay surveillance testing
  • Completed surveillance and inservice tests
  • Calculations for valve stoke time adjustment
  • Calculations of setpoints and uncertainty
  • Environmental qualification of solenoid valves and limit switches
(4) Non-Safety Auxiliary Feedwater Pump PAP01
  • Walkdown of pump and applicable portions of the system
  • Design calculations
  • Vortex and air intrusion analysis
  • Required operator actions
  • Emergency operating procedures
  • Maintenance and testing
  • Surveillance acceptance criteria
  • Net positive suction head calculations
  • Pump curves
  • System drawings and isometrics
  • Vendor documents and recommendations
  • Corrective action documents
(5) Refueling Water Storage Tank TBN01
  • Setpoint and total loop uncertainty calculations
  • Calibration procedures and acceptance criteria calculations for level instrumentation
  • Seismic calculations for refueling water storage tank anchor bolts
  • Change packages for modifications to tank to support periodic tank inspections and repairs
(6) Evaluation of Operator Procedures and Actions Related to Components
  • Time sensitive action OPA-RHR, Control room operator action to secure residual heat removal pumps during a high-pressure event
Main article: IP 71111.21
(1) 480 V Motor Control Center NG001B
  • Design basis calculations
  • Corrective actions resulting from previous violations
  • Completed work orders
  • Vendor documents and recommendations
  • Circuit breaker/motor starter wiring diagrams
  • Circuit breaker/circuit protector overload settings
  • Circuit cable sizing
  • Component maintenance history
  • Procedures for preventive maintenance, inspection, and testing

Modification Review - Permanent Mods (IP Section 02.03) (6 Samples)

(1) Change Package 20184, Replacement of ITT Barton Flow Indicator
  • Critical design attributes
  • Environmental qualification of indicator
(2) Change Package 20297, Removal of CST Level Indicator APLI0008
  • Operator actions related to APLI0008
  • Walkdown of condensate storage tank
  • Piping and instrumentation drawings of tank and level instrumentation
(3) Change Package 20316, NIS C-2 Setpoint Revision
  • Surveillance test procedures and channel calibration acceptance criteria
  • Alarm response procedures
  • Post modification testing results
(4) Change Package 20347, RCS Narrow Range RTD Lead Resistance Imbalance
  • Change package modifications for critical design attributes
  • Implementing work order
  • Safety analysis of the narrow range RTD change
(5) Change Package 20350, SGK05A/B Fuse Replacement
  • Design package including drawings, analysis, and qualification of the fuses
  • Schematic diagrams
  • Calculations supporting fuse sizing
  • Corrective action documents and implementing work orders
  • Motor data information for protective design information
  • Vendor documentation for the replaced AJT20 amp fuse and the new AJT30 amp fuse
(6) Change Package 20452, BBTY-441A RCS Loop 4 Narrow THOT Lead Resistance Imbalance
  • Critical design attributes
  • Affected electrical cable raceway and interconnection wiring drawings
  • Surveillance test procedure
  • Completed work order

Review of Operating Experience Issues (IP Section 02.06) (4 Samples)

(1) Wolf Creek Operating Experience 2018-0465, NRC Information Notice 2017-06, Battery and Battery Charger Short-Circuit Current Contributions to a Fault on the DC Distribution System
(2) Wolf Creek Operating Experience 2018-0503, Loss of Ultimate Heat Sink Inventory Through Auxiliary Feedwater Minimum Flow Lines During a Loss of the Condensate Storage Tank
(3) Wolf Creek Operating Experience 2018-0847, Discovery of a Condition that Could have Prevented Fulfillment of a Safety Function, Environmental Qualification Requirements for Atmospheric Steam Dumps
(4) Wolf Creek Operating Experience 2019-0417, NRC Information Notice 2019-002, Emergency Diesel Generator Excitation System Diode Failures

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

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

  • On August 12, 2021, the inspectors presented the design basis assurance inspection (teams) inspection results to Mr. J. McCoy, Site Vice President, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.21M Calculations 41-14.02-F RWST Displacements for New Seismic Analysis 0

69466-M-001 Non-Safety Auxiliary Feedwater Pump Drawdown From the 1

Condensate Storage Tank

69466-M-002 Non-Safety Auxiliary Feedwater Pump Net Positive Suction 1

Head

69466-M-003 Non-Safety Auxiliary Feedwater Pump Analysis and System 1

Resistance Curve

69466-M-004 Non-Safety Auxiliary Feedwater Pump Piping Vibration 0

Analysis

AN 98-001 Uncertainty for Refueling Water Storage Tank (RWST) 0

Level-Low, (Lo-Lo-1) Automatic Switchover Setpoint and

Technical Specification changes

AN-98-001-000- Uncertainty for Refueling Water Storage Tank (RWST) 0

CN-001 Level-Low, (Lo-Lo-1) Automatic Switchover Setpoint and

Technical Specification changes

AN-98-026 Determination of RWST Depletion prior to Completion of 0

Recirculation Switchover and ECCS Recirculation Flow

Requirement

BN-20 RWST Volumes and Level Set Points 3

BN-20-CN002 RWST Volume and Level Set Points 3

BN-J-001 RWST Level Transmitter Density Errors 01

BN-J-002 Total Loop Uncertainty Calculation - System BN, Loops 01

0930, 0931, 0932, and 0933

BN-J-002-001- Total Loop Uncertainty Calculation - System BN, Loops 01

CN003 0930, 0931, 0932, and 0933

BN-J-002-01- Total Loop Uncertainty Calculation System BN, Loops 0930 01

CN001 0931 0932 0933

ECCS-47 SI Pumps - NPSH from RWST 0

EJ-30-003- RHR Pumps A & B NPSH 03

CN002

FL-08 Control Building Flooding 003

FL-18 Containment Flood Levels for LOCA and MSLB 03

Inspection Type Designation Description or Title Revision or

Procedure Date

H-08 NB System Protective Relays 5

KJ-M-017 Emergency Diesel Standby Generator (KKJOlB) Runtime 1

Without ESW Flow

NK-E-001-004- 125 VDC Class 1E Battery System Sizing, Voltage Drop and 005

005 Short Circuit Studies.

SA-92-009 Calculation of RWST Depletion Rate and ECCS 0

Recirculation Switchover Time Following a Postulated

Primary/Secondary Pipe Rupture

WES-009-CALC- Wolf Creek/Callaway Post-LOCA Containment Water Level 1

001 Calculation

XX-E-006 AC System Analysis 006

XX-E-006 AC System Analysis 8

XX-E-006 AC System Analysis 9

XX-E-009 System NB, NG, PG Undervoltage/Degraded Voltage Relay 1

Setpoints

Corrective Action Condition Report 2007-01786, 47791, 74322, 104253, 104389, 104390,

Documents (CR-) 128300, 133632, 135223, 66596, 66841, 103323, 104458,

104515, 105136, 105564, 105741, 105744, 105969, 106015,

114883, 118661, 124196, 129263, 130202, 10000916,

10001446, 10002218, 10005090, 10007183, 10007246,

100007975, 00124312, 00138042, 00145626, 00131142,

10000792

Corrective Action Condition Report 10007140, 10007142, 10007145, 10007147, 10007163,

Documents (CR-) 10007662, 10007666, 10007668, 10007802, 10008018,

Resulting from 10007616, 10008023, 10008009, 10007407, 10007596,

Inspection 10007621, 10007625, 10007632, 10007633, 10007667,

10007975, 10008021, 10008065, 10008092, 10008133

Drawings 8809D54 T HAVE Loop 4 (TEST) Protection IV Card Frame 08 5A

Cabinet 04 Interconnecting Wiring Diagram

C-0C0212 Refueling & Reactor Makeup Water Storage Tanks, 7

Concrete Neat Line & Reinforcing Plans and Sections

E-11001 Main Single Line Diagram 13

E-11NB01 Lower Medium Voltage Sys. Class 1E 4.16 kV Single Line 9

Meter and Relay Diagram

Inspection Type Designation Description or Title Revision or

Procedure Date

E-11NG01 Low Voltage System Class 1E 480V Single Line Meter & 16

Relay Diagram

E-11NG01 Low Voltage System Class 1E 480V Single Line Meter & 16

Relay Diagram

E-11NK01 Class 1E 125V DC System Meter & Relay Diagram 20

E-11NK02 CLASS IE 125V DC System, Meter & Relay Diagram 19

E-13EP02A Schematic Diagram Accumulator Isolation Valves 4

E-13GK04 Schematic Diagram Battery Rm. Hydrogen Alarm 00

E-13NB01 Lower Medium Class 1E Meter and Voltage System 4.16 kV 5

Three Line Relay Diagram

E-13NB02 Lower Medium Voltage Sys. Class 1E 4.16 KV Three Line 3

Meter & Relay Diagram

E-13NB03 Lower Medium Voltage Sys. Class 1E 4.16kv Meter and 8

Relay Three Line Diagram

E-13NB12 Schematic Diagram Class 1E Bus NB01 Feeder Brkr. 7

2NB0112

E-13NB13 Schematic Diagram Class 1E Bus NB01 Feeder Brkr. 7

2NB0109

E-13NE10 Schematic Diagram 4.16KV DG Feeder Breaker 152NB0111 22

E-13NG10 Schematic Diagram 4.16KV LC XFMR Feeder Breakers 5

2NB0110 and 152NB0113

E-17000A Termination List Notes 20

J-14001 Control Room Equipment Arrangement. 12

KD-74-96, Sh. 1 One Line Diagram 73

KD-7496 One Line Diagram 73

KD-7496A Distribution System Equipment Lineup Limitations 11

M-12BN01 Piping & Instrumentation Diagram, Borated Refueling Water 1

Storage System

M-1H3311 HEATING VENTILATING & AIR COND. CONTROL 07

BUILDING EL. 2000'-0" AREA 1

M-1P3411 Drainage System (LE & LF) Control Building, EL. 2O16'- 0 01

Area 1

M-622.1-00036- Electrical Motor Data Sheet, Bahnson Ref: N-0027 Thru N- 1W

W03 003`

Inspection Type Designation Description or Title Revision or

Procedure Date

N1387-637A-B1 SGK05A & SGK05B Air Conditioner, Electrical Schematic 08

WIP-M-761- T HAVE Loop 1 (Test) Protection Card Frame 2/4 Cabinet 1 00

2328-W01-A-1 Interconnecting Wiring Diagram.

Engineering 20452 BBTY-441A RCS LP4 Narrow THOT Lead Resistance 00

Changes Imbalance

CP 014426. Utilization of Spare RTD BBTE0430A1, 02

CP 20316 NIS C-2 Setpoint Revision 0

Document EC Engineering for SGK05A/B Fuse Replacement, Rev. 0 0

Number: 020350,

EC. 020347 RCS NARROW RANGE RTD LEAD RESISTANCE 0

IMBALANCE

Engineering LTR-SCS-19-17 Wolf Creek Nuclear Operating Corporation C-2 Interlock 0

Evaluations Setpoint Revision

PQE-J-601B-P01 Atmospheric Relief Valve 8005N I/P Converter w/ Metallic 0

Nozzle Cap

WCAP-11528 RCS Flow Anomaly Investigation Report 04/01/1988

WCAP-9917 Setpoint Study for Kansas Gas and Electric Co./Kansas City 06/01/1981

Power and Light Co. Wolf Creek Unit and Union Electric Co.

Callaway Units 1 and 2 (SNUPPS Projects)

Miscellaneous Technical Requirements Manual 72

04-00383 WOLF CREEK GENERATING STATION - ISSUANCE OF 07/12/2004

AMENDMENT

RE: TECHNICAL SPECIFICATIONS 3.8.1 AND 3.8.4 - AC

AND DC SOURCES

(TAC NO. MB8763)

50.59 for DECP 50.59 screening for RCS Narrow range RTD Lead 0

Resistance Imbalance engineering design change.

AD 20347 Applicability Determination for 50-59 for DCP 020347 0

ANSI/I EEE American National Standard - General requirements for dry- 11/30/1979

C57.12.01-1979 type distribution and power transformers

Bulletin 6.10-2C ITE Series 5600 Motor Control Centers - design and 02/1976

application guide

CJ16224-l Dedication Plan for MERSEN Fuse PIN: AJT30 2, 11/25/19

Inspection Type Designation Description or Title Revision or

Procedure Date

CP 20350 CP 20350 Attachment 2 for XX-E-006 REV 8 ETAP 10-31-2019

MODEL\XX-E-006 REV 8.O

CR 00145500 Level Of Effort Evaluation for NRC 3Q2020 Integrated N/A

Inspection Self-revealing Green NCV

E-009 Technical Specification for Metal-Clad Switchboard for the 8

Standardized Nuclear Unit Power Plant System

E-009-00342 Metal-Clad Switchgear - Types M26 and M36 for Magne- W09

(GEH-1802X) Blast Air Circuit Breakers

E-009B Design Specification for 4.16 KV and 13.8 KV Vertical Lift 1

Vacuum Circuit Breakers

E-009B-00009 Instruction Manual for Siemens Type 3AF-GER/GEU Vertical W06

Lift Direct Replacement Vacuum Circuit Breakers

E-00NG System Description Low Voltage System - 480 V (Class 1E 5

Power System)

E-018 Technical Specification for Motor Control Centers For The 13

Wolf Creek Generation Station

E-018A-00007 Instruction Manual For Molded Case Circuit Breaker W15

E-10NB System Description Lower Medium Voltage System - 4.16 00

kV (Class IE Power System)

E-11NG20 Low Voltage System Class 1E Motor Control Center 312

Summary

Frame Book 29- Westinghouse Series C Motor Circuit Protector 05/1986

111

GEK-7310C Maintenance Manual - GE Power Circuit Breakers Types

AKR-3/3A-50 and AKRU-3/3A-50

LTAM WCNOC- 480 Volt Safety Related MCC Bucket Replacement 1/20/2021

09-0152

LTR-SCS-16-59 Westinghouse Evaluation to Support 95% Probability/95% 0

Confidence Level Uncertainty Values for Non-Westinghouse

Supplied Instrumentation for the Wolf Creek Generating

Station Revised Thermal Design Procedure Uncertainty

Calculations in WCAP-18083-P.

M-10BN Borated Refueling Water Storage 1

Inspection Type Designation Description or Title Revision or

Procedure Date

MGE EOOP-11 Molded Case Circuit Breaker and Ground Fault Sensor 37A

Testing

N/A Maintenance Strategy - XNG01 8/5/201

NB SHR 2020 System Health Report - System NB (Low-Medium Voltage

Q3Q4 4.16 kV) Third and Fourth Quarter

PIR 2007-00368 Supplement to Condition Report 2008-002718 - DG Parallel 06/19/2008

CR Response with Scenario Table

PSA-05-0011 Probabilistic Risk Assessment System Notebook - Electrical 3

Power Systems

TS-19-0001 Fuse list Change for Fuses 109FU, 110FU, 111FU N/A

Procedures AI 12-002 FME Consideration and General Guidance for Major 0A

Components

AI 21-016 OPERATOR TIME CRITICAL ACTIONS VALIDATION 20

AI 29B-003 Guidance To Prevent Unacceptable Preconditioning Prior To 2

Testing

ALR 00-47D RWST Lev LoLo 1 Auto XFR 10B

ALR 00-82A PR Over PWR Rod Stop 11

ALR 301 125 VDC CLASS IE SWITCHBOARD NK01 10

AP 12-003 Foreign Material Exclusion 18

AP 14A-003 Scaffolding Construction 26

CNT-ME-507 Installation & Inspection of Cable Terminations 13

E-009Q-01 13.8 KV and 4.16 KV Switchgear Inspection and Testing 37A

E-017 Technical Specification for Load Center Unit Substations for 07

the Standardized Nuclear Unit Power Plant System

E-020 DC Distribution Switchboards 009

E-050A-00010 Installation Instructions for AT&T Lineage 2000 Round Cell W01

Batteries Racks and Seismic Bracing at Wolf Creek Nuclear

Power Plant

E-050A-00010 Installation Instructions for AT&T Lineage 2000 Round Cell W01

Batteries Racks and Seismic Bracing at Wolf Creek Nuclear

Power Plant

E-051B Electrically Operated Manually Controlled Transfer Switches 01

E-051B-0031 Instruction Manual for Transfer Switch Panels W04

Inspection Type Designation Description or Title Revision or

Procedure Date

E-075-00016 Instruction Manual for Installation, Operations, & W06

Maintenance of ESWS Transformers 225 KVA FOR

SNUPPS 10466

E-10NK System Description for 125-Volt DC System (Class 1E 007

Power System)

E-11013 Installation, Inspe49ction, and Testing Details for Electrical 49

Equipment and Cables.

EMG C-0 Loss of All AC Power 45

EMG ES-12 Transfer to Cold Leg Recirculation 24

EMG ES-12 Transfer to Cold Leg Recirculation 24

EMG FR-H1 Response to Loss of Secondary Heat Sink 37

I-ENG-005 Infrared Thermography 11

MGE EOOP-05 Insulation Resistance Testing 27

MGE EOOP-11 Molded Case Circuit Breaker and Ground Fault Sensor 37A

Testing

MGE TL-001 Wiring Termination and Lug/Connector Installation 26A

MPE E009Q-03 Inspection and Testing Of Siemens Vacuum Circuit Breakers 11

MPE E017Q-04 Circuit Breaker Test for AKR 50 and AKR 30 Breakers 31B

MPE E017Q-07 Load Center Transformer Inspection 17A

OE 2018-0465 NRC Information Notice 2017-06 06/14/2018

OFN NB-042 Loss Of Offsite Power To NB01 (NB02) With EDG Paralleled 15

STC-IC-441 Channel Calibration Nuclear Instrumentation System Power 16A

Range Channel N41

STN KU-010 Station Blackout Diesel and Non-Safety AFW Pump Test 13

STS CH-029 Refueling Water Storage Tank Boron Concentration 8A

Determination

STS EN-100A Containment Spray Pump A Inservice Test 31

STS IC-201A TAVG, Delta T and Pressurizer Pressure Channel 24

Operational Test-Protection Set 1

STS IC-442 Channel Calibration Nuclear Instrumentation System Power 16A

Range Channel N42

STS IC-443 Channel Calibration Nuclear Instrumentation System Power 16A

Range Channel N43

Inspection Type Designation Description or Title Revision or

Procedure Date

STS IC-444 Channel Calibration Nuclear Instrumentation System Power 17A

Range Channel N44

STS IC-500G Delta T/TAVG Instrumentation Loop 4 Channel Calibration 28B

STS IC-508A Refueling Water Storage Tank Level Transmitter Calibration 8

STS IC-508B Refueling Water Storage Tank Level Instrumentation 9

Channel Calibration

STS IC-803A 4KV Undervoltage - Grid Degraded Voltage Channel 8

Calibration of NB01 Bus

STS KJ-011A EDG NE01 24 Hour Run 38

STS MT-018 Weekly Inspection of 125 VDC Lead-Calcium Batteries 23B

STS MT-020 125 VDC Battery Charger Operational Test 26B

STS MT-020 125 VDC Battery Charger Operational Test 26B

STS MT-024A Functional Test of 480 and 120 Volt Molded Case Circuit 16A

Breakers

STS MT-024B Functional Test of 480 and 120 Volt Molded Case Circuit 17

Breakers

STS MT-024C Functional Test of 480 and 120 Volt Molded Case Circuit 16

Breakers

SYS AP-122 Non-Safety Auxiliary Feed Pump Operation 13

Work Orders Work Order (WO- 12-359863-000, 14-389904-000, 18-442405-001, 18-

) 442406-001, 18-442408-001, 18-442426-001, 19-448418-

000, 19-448418-002, 19-448418-004, 20-465688-000, 20-

458894-000, 20-458895-000, 20-458896-000, 20-458898-

000, 20-458900-000, 20-458901-000, 20-458905-002, 20-

461085-000, 20-461085-001, 20-462400-000, 20-462400-

001, 20-465688-000, 20-466586-000, 20-461440-000, 20-

466529-000, 20-466528-000, 19-455924-000, 14-383742-

000, 20-458317-001, 01-224289-000, 10-327766-000, 12-

359819-000, 17-421614-000, 08-303906-000,. 04-259537-

000, 13-372243-000, 15-405081-000, 18-444596-000, 17-

21067-003, 18-437036 000, 20-467595-000, 20-458103-

001

16

Retrieved from "https://kanterella.com/w/index.php?title=IR_05000482/2021010&oldid=3292437"