IR 05000282/2021010
| ML21174A150 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 06/22/2021 |
| From: | Karla Stoedter NRC/RGN-III/DRS/EB2 |
| To: | Domingos C Northern States Power Company, Minnesota |
| References | |
| IR 2021010 | |
| Download: ML21174A150 (16) | |
Text
June 22, 2021
SUBJECT:
PRAIRIE ISLAND NUCLEAR GENERATING PLANT - DESIGN BASIS ASSURANCE INSPECTION (TEAMS) INSPECTION REPORT 05000282/2021010 AND 05000306/2021010
Dear Mr. Domingos:
On June 3, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Prairie Island Nuclear Generating Plant and 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 NRC-identified or self-revealing findings were identified during this inspection.
A licensee-identified violation which was determined to be of very low safety significance is documented in this report. 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 III; the Director, Office of Enforcement; and the NRC Resident Inspector at Prairie Island Nuclear Generating Plant. 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,
/RA/
Karla K. Stoedter, Chief Engineering Branch 2 Division of Reactor Safety
Docket Nos. 05000282 and 05000306 License Nos. DPR-42 and DPR-60
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000282 and 05000306
License Numbers:
Report Numbers:
05000282/2021010 and 05000306/2021010
Enterprise Identifier: I-2021-010-0047
Licensee:
Northern States Power Company
Facility:
Prairie Island Nuclear Generating Plant
Location:
Welch, MN
Inspection Dates:
May 10, 2021 to June 03, 2021
Inspectors:
B. Daley, Senior Reactor Inspector
S. Gardner, Electrical Contractor
T. Hartman, Senior Resident Inspector
M. Jones, Reactor Inspector
G. O'Dwyer, Reactor Engineer
E. Sanchez Santiago, Senior Reactor Inspector
Approved By:
Karla K. Stoedter, Chief
Engineering Branch 2
Division of Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a design basis assurance inspection (teams) inspection at Prairie Island Nuclear Generating Plant, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information. A licensee-identified non-cited violation is documented in report section: 71111.21M.
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 URI 05000282,05000306/2021010-01 Unexpected Opening of the Battery Charger Output Breaker 71111.21M Open
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 Disease (COVID-19), regional inspectors were directed to begin telework. During this time regional baseline inspections were evaluated to determine if all or portions of the objectives and requirements stated in the IP could be performed remotely. In some cases, portions of an IP were completed remotely and on-site.
For the inspection documented below it was determined that the objectives and requirements stated in the IP could be completed remotely.
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)
=
(1)22 Diesel-Driven Cooling Water Pump (DDCLP)
- Technical Specification (TS) Surveillances
- Technical Requirements Manual (TRM) Requirements
- Walkdown
- Seismic Protection
- Flow Capacity & Balance
- Runout and Minimum Flow
- Required Submergence
- Water Supply Availability
- Pump Cooling
- Jacket Water Cooler
- Fuel Oil (Available Volume/Consumption)
- Engine Lubrication
- Component Health, Corrective Maintenance, and Corrective Action History
- Consistency Between Station Documentation (e.g., Procedures) and Vendor Specifications
- Voltage Drop
- Low Pressure Instrumentation
- Control Logic (2)21 Cooling Water (CL) Strainer
- TS Surveillances
- TRM Requirements
- Walkdown
- Operating Procedures
- Maintenance Effectiveness
- Modifications
- System Health
- Environmental Qualifications
- Debris Loading Impact to Flow Capacity/Balance
- Debris Loading Impact to Structural Design
- Instrument Differential Pressure Setpoints
- Mesh Size in Comparison to Downstream Component Openings
- Pneumatic Backwash Compressed Air Capacity
(3)125 Volt Direct Current (DC) Distribution Panel - Panel 21
- Updated Final Safety Analysis Report (UFSAR)/TS/TRM Licensing Basis Requirements
- Walkdown
- Room Heat Up
- Loading Calculations
- Short Circuit Calculations
- Coordination Calculations
- Temperature Effects and Environmental Qualification
- Room Temperature Instrumentation
- Fuse Ratings
(4)4160 Volt Alternating Current (AC) Distribution Bus - Bus 25
- UFSAR/TS/TRM Licensing Basis Requirements
- Walkdown
- Operating/Maintenance Procedures
- System Health Reports
- Short Circuit Calculations
- Coordination Calculations
- Battery Capability to Supply Control Voltage
- Degraded Voltage Protection
- Protective Devices and Trip Set Points
Design Review - Large Early Release Frequency (LERFs) (IP Section 02.02) (1 Sample)
(1)21 Motor-Driven Auxiliary Feedwater (AF) Pump
- UFSAR/TS/TRM Licensing Basis Requirements
- TS Surveillances
- Walkdown
- Corrective Action Documents
- Room Heat Up Calculations
- Submergence/Net Positive Suction Head Calculations
- Suction Swap Calculations
- Design Basis Calculations
- Testing Acceptance Criteria Calculations
- Temperature Effects and Environmental Qualification
- Flooding Calculations
- Pump Motor Degraded Voltage
- Protective Devices
- Minimum Voltage
- Control Logic
Modification Review - Permanent Mods (IP Section 02.03) (4 Samples)
(1)6EQVENG12084 - Replace Cooling Water Strainer Backwash Valve (2)6MOD00026419 - Auxiliary Feedwater Pump Room Unit Cooler Replacement (3)6MOD00025399 - Replacement of 1R Station Reserve Auxiliary Transformer (4)6MOD00025413 - 12 Diesel-Driven Cooling Water Pump Replacement
Review of Operating Experience Issues (IP Section 02.06) (2 Samples)
- (1) NRC Information Notice 2017-06 - Battery and Battery Charger Short-Circuit Current Contributions to a Fault on the Direct Current Distribution System
- (2) NRC Information Notice 2016-05 - Operating Experience Regarding Complications from a Loss of Instrument Air
INSPECTION RESULTS
Unresolved Item (Open)
Unexpected Opening of the Battery Charger Output Breaker URI 05000282,05000306/2021010-01 71111.21M
Description:
As a result of the evaluation of Information Notice (IN) 2017-06 dated August 13, 2018, the licensee obtained vendor information in regard to the response characteristics of the 21 Battery Charger. This information displayed the expected response of the battery charger to a fault experienced downstream of the charger. Contrary to past licensee assumptions that the charger would interrupt current flow when current levels were greater than or equal to 315 Amps, information from the vendor showed that the battery charger would actually supply up to 6000 Amps during the first 10 milliseconds of the fault event rather than interrupting the current flow when the current was 315 Amps or more.
Current levels in excess of 315 Amps could potentially cause the breaker downstream of the battery charger to inadvertently open. The licensee did not recognize the potential for the downstream breaker to open until it was identified by the inspectors.
This tripping of the downstream breaker was different than what was provided in Assumption 6.2.1 of Prairie Island calculation ENG-EE-012, 125VDC Coordination Study, which states, It is assumed that the battery charger output breakers will not operate for external faults. Additionally, this calculation was used for the plants fire protection safe shutdown analysis. The assumption that the battery charger output breakers would not operate and the battery chargers would remain available was used in the plant specific fire protection Probabilistic Safety Assessment (PSA) which supports the NFPA 805 performance based analysis for Prairie Island fire areas. If the characteristics of the battery charger design could result in the inadvertent opening of the output breaker for faults in fire areas in the plant, the PSA that is relied upon for those areas would be altered non-conservatively because the battery charger would now no longer be available. Fire areas that use the performance based approach in NFPA 805 rely upon the PSA to determine the acceptability of the safe shutdown analysis for that area. The PSA is also used to determine the acceptability of potential future changes to fire protection elements in the fire area. An incorrect, non-conservative PSA could adversely affect the acceptability of the safe shutdown analysis, and therefore, the ability of the plant to safely shutdown during a fire event.
The licensees fire protection program, which is required by their plant specific license condition, is maintained in accordance with NFPA 805. Should it be determined, through analysis, that the design (vendor) information for the battery charger received for the IN 2017-06 evaluation could result in the inadvertent opening of the battery charge output breaker, the PSA data would no longer be correct. This issue is being dispositioned as an Unresolved Item (URI) pending the licensees evaluation of fire related faulting of downstream cables (and/or panels).
Planned Closure Actions: The inspectors will review/inspect any adverse effects to the licensee's plant specific fire protection program. Based upon this review, the inspectors will determine if any performance deficiencies exist, if the performance deficiencies are more than minor, and whether a violation of NRC requirements occurred.
Licensee Actions: The licensee entered this issue into their corrective action program to consider the potential impacts on downstream coordination of the battery charger. The licensee will further assess the impact on the downstream DC output breaker on the battery charger due to DC faults.
Corrective Action References: CAP 501000051933: DBAI - IN 2017-06 Not Fully Evaluated
Licensee-Identified Non-Cited Violation 71111.21M This violation of very low safety significance was identified by the licensee and has been entered into the licensee corrective action program and is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
Violation: Title 10 CFR 50, Appendix B, Criterion XI, "Test Control" requires, in part, that all testing required to demonstrate structures, systems, and components will perform satisfactorily in service is identified and performed in accordance with written test procedures which incorporate the requirements and acceptance limits contained in applicable design documents.
Contrary to the above, since March 28, 2017, the licensee has failed to perform testing demonstrating structures, systems, and components will perform satisfactorily in service in accordance with written test procedures which incorporate the requirements and acceptance limits contained in applicable design documents. Specifically, the licensee's design basis assumes the breakers for the 21 Component Cooling Pump and the Bus 26 Source from 2RY are capable of closing with voltage as low as 67 volts DC but have never been tested at that voltage. The lowest voltage they have been verified to operate was 90 volts DC.
Significance/Severity: Green. The inspectors assessed the significance of the finding using Inspection Manual Chapter (IMC) 0609, Attachment 4, Initial Characterization of Findings, dated December 20, 2019, and IMC 0609, Appendix A, The Significance Determination Process for Findings At-Power, dated December 20, 2019. Using Exhibit 2, Mitigating Systems Screening Questions, the inspectors determined that the finding was of very low safety significance (i.e., Green). Although the finding represented a deficiency affecting the design or qualification of a mitigating system, structure, or component (SSC), (e.g. the 21 Component Cooling Pump), neither the operability nor the probabilistic risk assessment (PRA) functionality of the SSC was lost. The licensee determined the equipment was operable because of testing other similar/representative SSCs at the lower voltages without issue.
Corrective Action References: CR 501000035537: Procedures PE0007/0008 Discrepancy
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On June 3, 2021, the inspectors presented the design basis assurance inspection (teams) inspection results to Christopher P. Domingos, Site Vice President and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.21M Calculations
178599.51.2012
Prairie Island Diesel Driven Cooling Water Pump Operating
Time
700063077
SP 1106B-22 DD CL PMP (245-392) 1 M Test
05/01/2020
700068001
SP 1106B-22 Diesel Driven Cooling Water (CL) Pmp
(245-392) 1 Month Test
07/31/2020
91-02-21
Battery 22
DC91L310
Control Room Monitoring of DC Systems
2/16/1995
E-415-EA-9
4KV Bus 25&26 DC Feeder and Vert Pnl DC Coordination
ENG-EE-012
25 VDC Coordination Study
ENG-EE-017
4kV Safeguards Pump/Motor Data Package
ENG-EE-162
Unit 2-4KV Safeguards Switchgear Protective Relay
Settings & Coordination
ENG-EE-170
ETAP Electrical Analysis
ENG-EE-171
Degraded Voltage
ENG-EE-177
AC System Fault Analysis
ENG-EE-200
PINGP ETAP 125 VDC Electrical Analysis
ENG-EE-208
AC System Load Flow Analysis
ENG-ME-020
D1/D2 and DDCLP Fuel Oil Storage Capacity
ENG-ME-021
Auxiliary Feedwater Pump Room Heat Loads
ENG-ME-218
Single Failure Analysis for Cooling Water System
ENG-ME-219
Safeguards CL Pump NPSHR Static Head Requirement
ENG-ME-347
Minimum Required Intake Volume
1D
ENG-ME-458
Highest Acceptable Leak Rate in the CL Pump Rooms
ENG-ME-573
Tube Plugging Limit for 12 and 22 DDCLP Jacket Water
Heat Exchanger
1A
ENG-ME-576
AFP Pump Acceptance Criteria
2H
ENG-ME-820
CL Hydraulic Analysis - LOOP, LOCA, and Seismic
Response
ENG-ME-835
Cooling Water Strainer Hydraulic Loading Analysis
ENG-ME-847
HELB Case Specific Inputs & SEA Room Heat Up
0C
ENG-ME-849
Design Basis Accident Room Heat Up Model Case Specific
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Inputs and Results
ENG-ME-850
2/22 DDCLP Engine Lube Oil Inventory
GEN-PI-096
Nuclear Safety Capability Assessment Analysis for
Compliance with NFPA 805
GEN-PI-097
Safe Shutdown Equipment for Compliance with 10 CFR 50,
Appendix R
SPC-CL-034
Loop B Diesel Pump 22 Start Pressure Switch
Corrective Action
Documents
600000212603
Operating Experience Evaluation of IN 2017-06
08/23/2018
01502331
Pending Room Heatup Analyses Impact Planned/in Flight
Project
11/18/2015
01520318
OE: NRC IN 2016-15 Operating Experience Regarding
Complications from a Loss of Instrument Air
08/25/2016
01552882
EC 26419 PMT - Flow Test Did Not Meet Acceptance
Criteria
03/13/2017
01557766
AFW Rm Unit Cooler Standby Setpoint Too High
03/17/2005
2084
Replace CL Strainer Backwash Valves with SS Valves
05/01/2016
1482702
D5 Output Breaker Annunciator Not Func
06/03/2015
500001496344
D5 Output Breaker Annunciator Not Func
10/11/2015
500001514923
Bkr 25-2 Will Not Rack to "Disconnect"
03/09/2016
500001524719
Annunciator 47524-0601 Reflashed
06/09/2016
500001548783
Preliminary Battery Calculation Results
01/27/2017
500001553539
Results Obtained for New DC Battery Calc
03/30/2017
501000007726
During TP 1789B Minimum Cooling Water Flow Not
Achieved for 12 AFW RM PMP CLR
01/26/2018
501000016553
AFWP Has Low Seal Water Flow
07/05/2018
501000019265
AFW PMP RM CLR Leaking Condensate
10/27/2018
501000019274
AFW PMP RM CLR Leaking Condensation
10/27/2018
501000022683
AFW PMP Bypass Piping Flange Weld
10/13/2019
501000023635
AFW Room Cooler Testing
2/27/2019
501000023925
2019 NRC UHS: AF RM UC DP Testing
03/06/2019
501000026949
Unit Coolers' Fan Blades in AFWP Room Need Cleaning
05/07/2019
501000033246
Possible Oil Leak on 21 MD AFWP
10/13/2019
501000033820
4KV Charging Motor Unsat
10/23/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
501000035537
Procedures PE0007/0008 Discrepancy
2/11/2019
501000037775
2/17/2020
501000040177
Leaking Hose on 22 DDCLP
05/01/2020
501000047556
D5 Output Bkr Remote Racking Capability
01/06/2011
501000049198
TP1789B As Found Flow Out of Band
03/03/2021
501000049319
MD AFWP OB Bearing Seal Buildup
03/08/2021
501000049607
TP 1789A Step 7.4.5 Not Met
03/16/2021
501000049608
TP 1789A Step 7.4.2 Recorded 40 Vice 46
03/16/2021
501000051933
DBAI - IN 2017-06 Not Fully Evaluated
05/12/2021
6100000000812
NRC IN 2019-08
10/16/2019
6DOC00028471
Downgrade Safety Related Backup Air Supply for Cooling
Water Strainer
04/12/2017
Corrective Action
Documents
Resulting from
Inspection
501000051691
21 DBAI Update to RFI II-4 Required
05/07/2021
501000052033
21 DBAI Minor Calc Errors
05/14/2021
501000052262
NRC 2021 DBAIT IDENTIFIED: ENG-ME-021 Rev 4C
Stated AFP Room Max Temp 122F But Data Supports 131F
05/19/2021
501000052363
NRC 2021 DBAIT IDENTIFIED Internal Flooding Signs Cite
Superseded Procedure
05/20/2021
Drawings
NE-116785 Sh.13
D5 Emergency Generator Bus 25 Cubicle 2
NE-40009-71-1
Diesel Cooling Water Pump
NE-40009-71-2
Diesel Cooling Water Pump
NF-116497
Interlock Logic Diagram - Unit 2 Bus 25 Load Rejection-
Restoring
C
NF-39216
Flow Diagram Cooling Water - Screenhouse
100
NF-39774
Instrument Air Supply and Control Piping - Turbine Building -
Unit 2 and Screenhouse Units 1 and 2
NF-40022-2
Circuit Diagram 4KV and 480V Safeguard Busses Unit 2
NF-40547-1
Wiring Diagram DC Distribution Panels "A" Train
Engineering
Changes
6MOD00025399
Replacement of 1R Station Reserve Auxiliary Transformer
01/17/2020
6MOD00026419
Upgrade Unit 1 and 2 Auxiliary Feedwater (AFW) Pump
Room Coolers from Non-Safety Related to Safety Related
05/23/2019
Replacement of 12 Diesel Driven Cooling Water Pump
04/07/2017
Miscellaneous
Response to Generic Letter 91-06: Resolution of Generic
10/28/1991
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Issue A-30, "Adequacy of Safety-Related DC Power
Supplies"
B20.5
4.16KV Station Auxiliary System
CGD PI-0077
Commercial Grade Evaluation Class RK1 UL Listed 140
VDC Fuses
2/01/2001
DBD SYS 20.09
Design Basis Document for the DC Auxiliaries System
DBD SYS-35
Design Basis Document for the Cooling Water System
EM 2.3.7
Electrical Separation/Isolation
LER 1-92-005
Design Basis Reconstitution Effort Identified a Condition
Outside 10 CFR Part 50 Appendix R Requirements
04/27/1992
NMSIP-ELEC-
0008
4KV Breaker Closing and Trip Voltage Pickup Times
10/15/2014
NX-20622-1
Mercoid Pressure Controls
NX-236975
Safety Related Battery Charger
PR2 25-10A
Relay Setting 21 MD AFW Pmp Breaker
11/01/1992
Screening 1620
TRM Change - Delete 3.3.D
STRIDE PI-2018-
ED-03
STRIDE to Extend Emergency Diesel Generator (EDG) Trip
Bypass Testing and Integrated SI Test with a Simulated
Loss of Offsite Power (LOOP) Test Frequencies
09/13/2019
U2-4.160KV
System Health Report
XH-2701-3
5HK 350 Switchgear and Relaying
Z9IL266011
Test Report Performance of Bussmann LPN-RK Fuses at
140 VDC Per UL 198L
Procedures
1C20.5 AP7
Response to Degrading Bus 25 or 26 Voltage
2C20.5
Unit 2-4.16KV System
2C20.5AOP1
Re-energizing 4.16KV Bus 25
515440
Bkr 25-2 Install New Breaker and Perform 52S Checks
01/08/2015
AB-3
C35
Cooling Water
C47041
Alarm Response Procedure AR 42 11/21 or 12/22 AFWP
Room HI TEMP
C47510
Alarm Response Procedure
FP-IP-SFCP-01
Surveillance Frequency Control Program
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
FP-OP-SFCP-01
Surveillance Frequency Control Program
FP-SC-PE-02
Item Equivalency Evaluation
ICPM 2-025A
Unit 2 DC Monitoring Panel Instruments Calibration - Train A 2
IP-ENG-001
Standard Design Process
2000020185
PCR 602000020185 - TP 1789A PCR in Progress and
Started 3-23-2021
03/23/2021
2000020185
Markup
Markup - TP 1789A
2000020186
TP 1789B-PCR in Progress and Started 3-23-2021
2000020186
Markup
Markup - TP 1789B R11
PE-0007
5HK250/350 Breaker Testing Maintenance & Repair - Minor
PE-0008
5HK250/350 Breaker Testing Maintenance & Repair - Major
PE-0009
4KV Switchgear Preventive Maintenance
TP 1789A
AFW Pump Room Cooler Flushing, Flow Balancing, Dp
Monitoring, & Air Side Inspection, Train A
TP 1789B
AFW Pump Room Cooler Flushing, Flow Balancing, Dp
Monitoring, & Air Side Inspection, Train B
Work Orders
00547527
Install New 21 Air Compressor Motor Cooler per EC 26419
06/20/2017
375229
4KV Breaker Testing
10/10/2013
468822
Bus 25 Switchgear Preventive Maintenance
2/11/2013
2067
2S Contacts
05/08/2017
700000603
CV-31653, Replace Valve and Actuator
06/16/2020
700043770
Performance of SP 2103A AFW Comprehensive IST Pump
and Valve Test (Refueling)
11/18/2019
700045586-0010
SP 1083B
Unit 1 Integrated SI Test with Simulated Loss of Offsite
Power Train B
03/05/2019
700046740
Performance of TP 1398 Internal Flooding Walkdown
05/03/2019
700054423
SP 2193A Cycling AFWP AND CL Water MV's
10/18/2019
700058720
Perform ICPM 2-025A Unit 2 DC Monitoring Panel
Instruments Calibration Train A
03/05/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
700060230
Performance of TP 1398 Internal Flooding Walkdown
07/24/2020
700071523
SP 1106B - 22 DD CL PMP (245 - 392) 1 M Test
10/30/2020
700071646-0010
Work Order Task Plan to Replace Valve ZE-5-15 and
Associated ZE Piping
04/14/2021
700075594-SP-
1106B
Diesel Cooling Water Pump Monthly Test
2/22/2021
700077021
SP 1106B - 22 DD CL PMP (245-392) 1 Month Test
03/05/2021
700077662
SP1106A - 12 DD CLP (145 - 392) MNTH Test
03/19/2021
700079090
SP 1106A 12 Diesel CL Pump Monthly
04/19/2021