IR 05000317/2018010
| ML18292A579 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 10/19/2018 |
| From: | Mel Gray Division of Reactor Safety I |
| To: | Bryan Hanson Exelon Generation Co, Exelon Nuclear |
| References | |
| IR 2018010 | |
| Download: ML18292A579 (13) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 2100 RENAISSANCE BOULEVARD, SUITE 100 KING OF PRUSSIA, PA 19406-2713 October 19, 2018 Mr. Bryan Senior Vice President, Exelon Generation Company, LLC President and Chief Nuclear Officer, Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT: CALVERT CLIFFS NUCLEAR POWER PLANT
- DESIGN BASES ASSURANCE INSPECTION (TEAMS) REPORT 05000 3 17/20 18 0 1 0 AND 05000 3 18/20 18 0 10
Dear Mr. Hanson:
On October 5, 2018 , the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Calvert Cliffs Nuclear Power Plant (CCNPP), Units 1 and 2. The NRC inspectors discussed the results of this inspection with Mr. Todd Tierney , Plant Manager , and other members of your staff. The results of this inspection are documented in the enclosed report.
The NRC inspectors did not identify any findings or more
-than-minor violations.
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 the NRC
's Public Document Room in accordance with Title 10 of the Code of Federal Regulations (10 CFR), Part 2.390, "Public Inspections, Exemptions, Requests for Withholding."
Sincerely,/RA/ Mel Gray, Chief Engineering Branch 1 Division of Reactor Safety Docket Nos.
50-317 and 50
-318 License Nos.
-69
Enclosure:
Inspection Report 050003 17/20180 10 and 050003 18/20180 10 cc w/encl:
Distribution via ListSer v
ML18292A579 SUNSI Review Non-Sensitive Sensitive Publicly Available Non-Publicly Available OFFICE RI/DRS RI/DRP RI/DRS NAME JSchoppy JGS ECarfang MGray DATE 10/11/18 10/16/18 10/19/18 1 Enclosure U.S. NUCLEAR REGULATORY COMMISSION Inspection Report Docket Numbers: 50-3 17 and 50-3 18 License Numbers: DPR-53 and DPR
-69 Report Numbers: 05000 3 17/20 18 0 10 and 05000 3 18/20 180 10 Enterprise Identifier:
I-2018-0 10-00 1 3 Licensee: Exelon Generation Company, LLC Facility: Calvert Cliffs Nuclear Power Plant, Units 1 and 2 Location: Lusby, MD Inspection Dates: September 1 7, 2018 , through October 5, 2018 Inspectors:
J. Schoppy, Senior Reactor Inspec tor, Division of Reactor Safety (DRS), Team Leader J. Lilliendahl, Senior Emergency Response Coordinator, DRS M. Orr, Reactor Inspector, DRS S. Pindale
, Senior Reactor Inspector, DRS C. Baron, NRC Mechanical Contractor S. Kobylarz, NRC Electrical Contractor Approved By:
M. Gray , Chief Engineering Branch 1 Division of Reactor Safety 2
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring
Exelon's performance at Calvert Cliffs Nuclear Power Plant Units 1 and 2 by conducting a design bases assurance inspection in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRC's program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.
No findings or more-than-minor violations were identified.
3
INSPECTION SCOPES
This inspection was conducted using the appropriate portions of the inspection procedure in effect at the beginning of the inspection unless otherwise noted. Currently approved inspection procedures 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 inspection procedure requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter 2515, "Light-Water Reactor Inspection Program - Operations Phase." The team 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
71111.21 M - Design Bases Assurance Inspection (Teams)
The team evaluated the following components, permanent modifications, and operating experience during the weeks of September 1 7, 2018, and October 1 , 2018. For the components, the team reviewed the attributes listed in IP 71111.21M, Appendix A, Component Review Attributes, such as those listed below. Specifically, the team evaluated these attributes as per 71111.21M, Appendix B, Component Design Review Considerations and 71111.21M, Appendix C, Component Walkdown Considerations. Specific documents review ed are listed in the Documents Reviewed section.
Components (4 Samples) Unit 2 No. 21 High Pressure Safety Injection Pump o Material condition and installed configuration (e.g., visual inspection/walkdown) o Normal, abnormal, and emergency operating procedures o Consistency among design and licensing bases and other documents/procedures o System health report, maintenance effectiveness and records, and corrective action history o Equipment/environmental controls and qualification o Design calculations o Surveillance testing and recent test results o System and component level performance monitoring o Equipment protection from fire, flood, and water intrusion or spray o Heat removal cooling water and ventilation The team used Appendix B guidance for Valves, Pumps, Instrumentation, and As-Built System. Unit 1 No. 11 125 Vdc Battery o Material condition and installed configuration (e.g., visual inspection/walkdown)o Normal, abnormal, and emergency operating procedures o Consistency among design and licensing bases and other documents/procedures o System health report, maintenance effectiveness and records, and corrective action history o Operator actions o Design calculations o Surveillance testing and recent test results o Environmental conditions o Contactor and fuse ratings; Component adequacy for minimum voltage o Equipment protection from fire, flood, and water intrusion or spray o Heat removal cooling water and ventilation The team used Appendix B guidance fo r Instrumentation, Circuit Breakers and Fuses , Cables, Electric Loads, and As-Built System
. Unit 1 No. 14 4160V Bus o Material condition and installed configuration (e.g., visual inspection/walkdown)o Normal, abnormal, and emergency operating procedures o Consistency among design and licensing bases and other documents/procedures o System health report, maintenance effectiveness and records, and corrective action history o Control logic o Design calculations o Surveillance testing and recent test results o Equipment protection (sealing of cable and conduits)o Environmental conditions o Protection coordination; Load in
-rush and full load current o Range, accuracy, and setpoint of installed relays o Equipment protection from fire, flood, and water intrusion or spray The team used Appendix B guidance for Instrumentation, Circuit Breakers and Fuses , Cables, Electric Loads, and Motor Control Centers (MCCs).
Unit 1 Containment Sump Recirculation Valve 1-MOV-4144 o Material condition and installed configuration (e.g., visual inspection/walkdown)o Normal, abnormal, and emergency operating procedures o Consistency among design and licensing bases and other documents/procedures o System health report, maintenance effectiveness and records, and corrective action history o Equipment/environmental controls and qualification o Operator actions o Design calculations o Surveillance testing and recent test results o Equipment protection (sealing of cable and conduits)o Equipment protection from fire, flood, and water intrusion or spray The team used Appendix B guidance for Valves, Instrumentation, Cables, Electric Loads, and As-Built System
.
Component, Large Early Release Frequency (1 Sample) Unit 2 Containment Penetration Room Ventilation System o Material condition and installed configuration (e.g., visual inspection/walkdown)o Normal, abnormal, and emergency operating procedures o Consistency among design and licensing bases and other documents/procedures o Maintenance effectiveness and records, and corrective action history o Operator actions o Design calculation s o Surveillance testing and recent test results o Environmental conditions o Equipment protection from fire, flood, and water intrusion or spray o Heat removal cooling water and ventilation The team used Appendix B guidance for Instrumentation, Motor Control Centers (MCCs), and As-Built System
. Permanent Modifications (5 Samples) ECP-14-000064; ESR-13-000829 - 4kV Normal Incoming Supply Feeder Breaker Modification ECP-14-000159: AFW Emergency Ventilation System Upgrade ECP-15-000727: ESR-15-002466 - Provide Engineering to Raise RAS Setpoint ECP-16-000353: ESR-16-000050 - Enable RWT Outlet MOVs 4142 and 4143 to Close Automatically on a RAS ECP-16-000462: Update Fairbanks Morse Trip Circuit Design Operating Experience (3 Samples) NRC Information Notice 2014
-03: Turbine-Driven Auxiliary Feedwater Pump Overspeed Trip Mechanism Issues , dated February 25, 2014 Prairie Island 2 10CFR21 (2017-45-00), EDG High Crankcase Pressure Switch Mounting Bracket Fastener System Failure , dated September 14, 20 1 7 Report of Defect per 10CFR21, Basler Electric SBSR Automatic Voltage Regulator Card Solder Joints, dated September 21, 2007
INSPECTION RESULTS
No findings or more
-than-minor violations were identified.
EXIT MEETING S AND DEBRIEFS
The team verified no proprietary information was retained or documented in this report.
On October 5, 2018, the team presented the Design Bases Assurance Inspection (Teams) results to Mr. Todd Tierney , Plant Manager
, and other members of Exelon staff.
7
DOCUMENTS REVIEWED
71111.21M
- DESIGN BASES ASSURANCE INSPECTION (TEAM
S) Audits and Self
-Assessments
04058864, Readiness Review for 2018 NRC Design Bases Assurance Inspection Self Assessment, dated 6/1/18
Calculations
95-0188, Seismic II/I Evaluation
of ILRT Piping to Containment Penetration #50, Revision 0
A01080.F02
-002, Pressure Locking Thrust Calculation, Revision 1
CA0772, AC Load Flow Study, Revision 2
CA04079, Comparison of Available and Required NPSH for the Safety Injection and Containment Spray Pumps during Post
-RAS Operation, Revision 0
CA04691, Circulating Water Flooding in the Turbine Building through a Ruptured Expansion Joint, Revision 0
CA07773, AFW Pump Room Cooler Sizing, Revision 0
CA10206 , Refueling Water Tank Level
RAS Setpoint Determination, Revision 0
E-85-010, 125VDC Battery 01, 11, 12, 21 and 22 Fault Current Calculation, Revision 2
E-87-009, 125VDC System Short
-Circuit Review, Revision 1
E-89-005, SBO & LOCA Battery Duty Cycle
- Bus 11, Revision 4
E-89-042, Voltage Drop in DC Systems, Revision 4
E-90-033, Master
Fault Calculation, Revision 4
E-90-038, MOV Minimum Voltages Lasting More than 5 Seconds, Revision 11
E-90-071, 4kV Bus 14 Protective Devices, Revision 6
I-94-003 , Refueling Water Tank Level(s) and Capacity, Revision 4
M-91-044, MOV Weak Link Analysis, Revision 2 M-90-193, Flood Heights Resulting from a Pipe Break in the Turbine Building, Revision 0
M-91-197, Maximum Line and Differential Pressure Valves 1 & 2
-MOV-4144 & 4145 May Experience During Operation, Revision 0
Completed Surveillance, Performance, and Functional Tests
2013-29, Unit 2 Integrated Leakage Rate Test Report, dated 5/8/13
OP-6 , PreStartup Checkoff, performed 3/15/18
STP-M-152-1, 11 Station Battery Weekly Check, performed 8/30/18 STP-M-352-1, 11 Station Battery Quarterly Check, performed 6/23/16, 9/22/16, 12/21/16, 3/23/17, 6/22/17, 9/21/17, 12/19/17, 3/22/18, and 6/21/18
STP M544A-2, #21 Penetration Room Exhaust Filter Test, performed 4/6/18
STP M5445-2, #22 Penetration Room Exhaust Filter Test, performed 5/8/18
STP-M-552-1, 11 Station Battery Service Test, performed 11/5/13, 4/1/16, and 4/9/18
STP M-651 A-2A , SIAS B-10 Trip Bypass for 2A Diesel Generator , performed 7/31/18
STP M-651 A-2B , SIAS B-10 Trip Bypass for 2B Diesel Generator , performed 1/16/15 and 5/16/17 STP M-651C-1B, SIAS B-10 Trip Bypass for 1 B Diesel Generator , performed 12/6/16
STP O-4B-1 , "B" Train Integrated Engineered Safety Features Test, performed 3/17/18
STP O-5A21-2, 21 Auxiliary Feedwater Pump Quarterly Surveillance
Test, performed 7/25/18
STP O-7A-1, "A" Train Engineered Safety Features Logic Test, performed 5/1/18
STP O-7B-2, B Train Engineered Safety Features Logic Test, performed 10/20/17
STP O-7C-2, A Train Engineered Safety Features Logic Test, performed 5/3/18
STP O-14 A-2 , A Train Safety Injection, Containment
Spray, and SDC Gas Accumulation
Test , performed 7/5/18
STP O-55-2, Unit 2 Containment Integrity Verification Mode 1
-4, performed 7/30/18
STP O-70-2, Monthly Test of "A" Train Containment Cooling Units, Iodine Removal Units, & Penetration Room Exhaust Filt er , performed 5/22/18
STP O-7 1-2, Monthly Test o
f " B" Train Containment Cooling Units, Iodine Removal Units, & Penetration Room Exhaust Filter , performed 6/4/18
STP O-73G-2, HPSI Pump Large Flow Test , performed 2/19/17
STP O-731A-2, A-Train HPSI Pump and Check Valve Operability Test , performed 8/1/18
STP XM-503-1 Calibration Check of #14 4KV Bus LOCI and Shutdown Sequencer, performed 3/15/16 TURB-04, AFW Turbine Overspeed Trip Adjustment, performed 3/17/18
Completed Preventive Maintenance, Calibrations, and Inspections
1-44-2-O-Q, Condensate Level Switch, performed 4/3/18
2-44-2-O-Q, Condensate Level Switch, performed
2/22/18 Initial Scoping Report 0027, Aging Related Degradation Inspection Check List for Identification of Aging Effects, Unit 2 5' Fan Room, dated 1/4/11
Corrective Action Issue Report
s (IR s) 4-024-38 6 2009-6043 2009-6251 2009-6252 2014-0396 1700131 1700348 1786965 1803213 1803587 1803588 1803624 1803831 1851368 1852812 1855691 1856563 1856715 1856779 1857138 2010203 2402107 2409006 2454706 2464168 2482579 2494780 2497552 2498947 2528973 2552315 2552673 2554032 2555303 2574382 2574385 2580916 2581489 2581500 2589648 2595124 2633221 2639867 2644934 2668740 2676847 2682276 2689863 2703487 2714272 3980419 4007684 4025294 4029406 4033503 4054408 4056915 4058864 4063744 4064642 4065747 4090677 4106197 4111139 4113435 4113450 4113717 4114625 4116170 4130071 4144777 4149542 4154234 4155119 4161927 4170441* 4175196* 4175295* 4177713* 4178917* 4179072* 4179914* 4179941* 4180135* 4180558* 4180563* 4180 608* *IR written as a result of this inspection
Drawings 61-076-B, Schematic Diagram High Pressure Safety Injection
Pump 13, Revision 6
2083-34, Terry Steam Turbine, Revision 1
2103-0001, High Pressure Safety Injection Pump Outline Dimension, Revisio
n 4 12103-0014, Piping
-Bearing and Stuffing Box w/Seal Circulation, Revision 5
33810, High Pressure Safety Injection Pump Performance Curve, dated 12/19/69
60307, Area & Equipment Drains Containment & Aux
. Bldg. Unit 1 Plan at El 27', Revision 8
60710 Sh.1, Component Cooling System, Revision 46
60722 Sh. 2, Auxiliary Building Ventilation System, Revision 48
60722 Sh. 3, Auxiliary Building Ventilation System, Revision 17
60723 Sh. 2, Ventilation Systems Containment Turbine and Penetration Rooms, Revision 38
60731 Sh. 1, Safety Injection and Containment Spray Systems, Revision 94
60733 Sh. 3 , Miscellaneous Drain & Sump Piping Turbine & Diesel Bldg. and Yard , Revision 64
61001 Sh. 1, Electrical Main Single Line Diagram, Revision 48
61005, Meter and Relay Diagram 4KV System Unit Buses 11 and 14, Revision 36
61022 Sh. 1, Single Line Diagram 120VAC Vital System, Revision 57
61024 Sh. 1, Single Line Diagram 125VDC Vital System Bus 11, Revision 57
61024 Sh. 2, Single Line Diagram 125VDC Vital System Bus 14, Revision
61024 Sh. 3, Single Line Diagram 125VDC Vital System Bus 15, Revision 3
61071 Sh. 7, Schematic Diagram 4KV Bus 14 Feeder Breaker 152
-1401, Revision 19
61071 Sh. 8, Schematic Diagram 4KV Bus 14 Feeder Breaker 152
-1414, Revision 20
61076 Sh. 4, Schematic Diagram High Pressure Safety Injection Pump 12, Revision 18
61076 Sh. 7, Schematic Diagram High Pressure Safety Injection Pump 13, Revision 17
61076 Sh. 30B, Schematic Diagram Reactor Safeguards Containment Sump Discharge Valve 1MOV4144, Revision 4
61076 Sh. 31, Schematic Diagram Reactor Safeguards CS & SI Pumps Recirc Valve 1MOV659, Revision 18
61740 Sh. 1, Containment Liner Plan, Elevation and Penetrations, Revision 22
61740 Sh. 2, Containment Structure Penetrations, Revision 8
2151 Sh. 1, Appendix "R" Separation Requirements Aux. Bldg. & Containment Structure Floor Plan at El. 27', Revision 10
2731 Sh. 1, Safety Injection and Containment Spray Systems, Revision 84
63076 Sh. 31, Reactor Safeguards CS and SI Pumps, Recirc Valves 2MOV659, Revision 14
63076 Sh. 31A, Reactor Safeguards CS and SI Pumps, Recirc Valves 2MOV660, Revision 2
64311, Simplified System Drawing
- Safety Injection and Containment Spray, Revision 14
64316, Containment and Penetration Room Ventilation SL
-065A, Revision 12
84311, Safety Injection and Containment Spray System, Revision 15
ECP-16-0462-CN-001, Update Fairbanks Morse EDG Trip Circuit Design, Revision 0
ECP-16-0462-CN-006, Update Fairbanks Morse EDG Trip Circuit Design, Revision 0
ECP-16-0462-PCN-1002-CN-005, Update Fairbanks Morse EDG Trip Circuit Design, Revision 0
N2010-FCU-4-FAB Sh. 5, Auxiliary Feedwater Pump Room Emergency Cooler/Fan Coil Unit Fabrication Drawing, Revision 1
Engineering Evaluations 1MOV4144, MIDACALC Results
- AC Motor Operated GL96
-05 Gate Valve, Revision 2 Comments on Calculation CA07773, AFW Pump Room SR Ventilation Gothic Evaluation and Unit Sizing, dated 4/27/12
ECP-12-000318 , AFW Pump Room Emergency Ventilation System, Revision 0
ECP-14-000064 Form 7 and 7A
, Design Change Technical Evaluation, Revision 3 ECP-14-000064 Form 9 , Installation Testing Instructions, Revision 4
ECP-14-000159-015-7-01, Form 7, Design Change Technical Evaluation, Revision 3
ECP-14-000159-015-7A-01, Form 7A, Design Change Technical Evaluation Continuation , Revision 8
ECP-14-000159-5059-01 , AFW Pump Room Emergency Ventilation System Upgrade
50.59 Screen, Revision 9
ECP-15-000023, Technical Evaluation for Connection Resistance Methodology, Revision 0
ECP-15-000727, Raise RAS Setpoint, Revision 2
ECP-16-000353, Enable RWT Outlet MOVs 4142 and 4143 to Close Automatically on a RAS , Revision 0
ECP-16-000462, Update Fairbanks Morse Trip Circuit Design, Revision 0
ECP-17-000523, Vortexing in the Refueling Water Tank Technical Evaluation, Revision 0
ES-001, Flooding, Revision 5
ES-034, Electrical Device Settings, Revision 1
ES199801327, MOV Pressure Locking Evaluation, Revision 0
Operability Evaluation 17
-002, 2CV5171: 21 ECCS Cooler Outlet Control Valve, Revision 0
Project No. 11562
-061, AFW Pump Room Elevated Temperature Issue
- NRC Comment Resolution, Revision 0
QL00847, Barrier Function Table
, Revision 2 SE00558 , Automatic Closure of the RWT Outlet Valve MOVs
50.59 Evaluation, Revision 0
Maintenance Work Orders
C 12 023668 C20072161 C20074962 C20074963 C2 0083624 C90728304 C90767769 C91408624 C91426157 C91909242 C91910467 C91944763 C91945787 C92413803 C92543727
C92813807 C92935353 C92957877 C92957878 C92957879 C92957880 C92967907 C93110332 C93445185 C93466890 C93476179 C93509570 C93549452 C93609295 C93622647 C 93640623 C93644323 C936 44324 Miscellaneous
004, 4160 VAC Electrical
Power Distribution System Description, Revision 3
2, Auxiliary Building Ventilation System Description, Revision 7
2-1401, CCNPP Protective Relaying Setting Sheet, Revision 3
2-1410/2/SB2, CCNPP Protective Relaying Setting Sheet, Revision 2
2-1414, CCNPP Protective Relaying Setting Sheet, Revision 3
A116, NRR Letter: Request for Additional Information Regarding Generic Letter 2004
-02, dated 7/23/10 Fairbanks Morse Owners' Group, Maintenance Guidelines, Voltage Regulator and Excitation System Maintenance Recommendations, Revision 4
Master Calibration Data Package for 2
-PS-4779, dated 2/3/17
Normal and Special (Abnormal) Operations Procedures
1C10-ALM , ESFAS 13 Alarm Manual
, Revision 51
1C19-ALM, 13KV &
4KV Essential Feeder Bkrs Contr Board Alarm Manual, Revision 40
1C62/2C62/2C61, 1B/2A/2B Diesel Generator Alarm Manual, Revision 10
AOP-3B , Abnormal Shutdown Cooling Conditions, Revision 30
AOP-71, Loss of 4KV, 480 Volt or 208/120 Volt Instrument Bus Power, Revision 33
EOP-3, Loss of All Feedwater, Revision 23
EOP-5, Loss of Coolant Accident, Revision 30
EOP-8 , Functional Recovery Procedure , Revision 41
OI-3A, Safety Injection and Containment Spray, Unit 2, Revision 35
OI-11A , Condensate System , Revision 4 3 OI-21A, 2A Diesel Generator Operating Instructions, Revision 25
OI-22G, Penetration Room Exhaust System, Revision 6
OI-26A, 125 Volt Vital DC, Revision 21
OI-27C, 4.16 KV System, Revision 28
OI-32A, Auxiliary Feedwater System, Unit 1, Revision 39
OI-32A, Auxiliary Feedwater System, Unit 2, Revision 32
OP-6 , PreStartup Checkoff, Revision 53
Operating Experience
NRC Information Notice 2014
-03: Turbine
-Driven Auxiliary Feedwater Pump Overspeed Trip Mechanism Issues, dated 2/25/14
Report of Defect per 10CFR21, Basler Electric SBSR Automatic Voltage Regulator Card Solder Joints, dated 9/21/07
Procedures
BUS-014K, 4 KV Buses 13 and 14 Inspection, Testing and Cleaning, Revision 1
E-10, Testing and Adjustment of Agastat Relays, Revision
ER-AA-200-1001 , Equipment Classification, Revision 4
ER-CA-450, Structure and System Walkdowns , Revision 0
FTE-59, Periodic Maintenance, Calibration and Functional Testing of Protective Relays, Revision 8
FTM-11, Rotating Equipment Vibration Monitoring, Revision 3
HVAC-03 , Inspection and Replacement o
f V-Belts, Revision 8
LS-AA-104 , Exelon 50.59 Review Process, Revision 10
LS-AA-104-1000 , 50.59 Resource Manual , Revision 12
MN-1-209, Predictive Maintenance Program, Revision 7
NSWP-S-06, Core Drilling, Revision 1
OP-CA-102-106 , Operator Response Time Program at Calvert Cliffs , Revision 6
TURB-04, AFW Turbine Overspeed Trip Adjustment, Revision 5
Risk and Margin Management
Plant Risk Information e
-Book for Calvert Cliffs Nuclear Power Plant
, dated 3/1/1 7 Risk-Informed Inspection
Notebook for Calvert Cliffs Nuclear Power Plant Units 1 and 2 , Revision 2.1a
System Health Reports, System Walkdowns, & Trending
HPSI Pump IST Trend Data, dated 1/20/98
- 2/6/18 Auxiliary Feedwater (System 036) System Health Report, dated 7/25/18
High Pressure Injection (System 052) System Health Report, dated 7/23/18
MRFF/MPFF Report Data, 2013
- 2017 Unit 1 and Unit 2 AFW Pump Room Temperature Logs, 7/31/17
- 8/10/18 Vendor Technical Manuals & Specifications
2400-206-1006, GE Magne
-Blast Circuit Breaker Instructions GEI
-88771D , Revision 0 15138-002-1001, Installation and Operating Instructions for GNB Lead
-Calcium Batteries, Revision 8
ES200800209, Borg
-Warner High Pressure Heat Exchanger, dated 11/1/84
Installation, Operation and Maintenance for Bingham Pump Type MSD, dated 11/1/84
VTD 12 083-010-1017, Terry Corporation Std Instructions, Section 7, dated 12/9/91