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| number = ML18122A085
| number = ML18122A085
| issue date = 05/02/2018
| issue date = 05/02/2018
| title = Three Mile Island Nuclear Generating Station, Unit 1, Design Bases Assurance Inspection (Teams) Report 05000289/2018010
| title = Design Bases Assurance Inspection (Teams) Report 05000289/2018010
| author name = Mangan K A
| author name = Mangan K
| author affiliation = NRC/RGN-I/DRS/EB1
| author affiliation = NRC/RGN-I/DRS/EB1
| addressee name = Hanson B C
| addressee name = Hanson B
| addressee affiliation = Exelon Generation Co, LLC, Exelon Nuclear
| addressee affiliation = Exelon Generation Co, LLC, Exelon Nuclear
| docket = 05000289
| docket = 05000289
| license number = DPR-050
| license number = DPR-050
| contact person = Pindale S M
| contact person = Pindale S
| document report number = IR 2018010
| document report number = IR 2018010
| document type = Inspection Report, Letter
| document type = Inspection Report, Letter
Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:B.HansonUNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 2100 RENAISSANCE BOULEVARD, SUITE 100 KING OF PRUSSIA, PA 19406
{{#Wiki_filter: UNITED STATES NUCLEAR REGULATORY COMMISSION May 2, 2018
-2713 May 2, 2018 Mr. Bryan Senior Vice President, Exelon Generation, LLC President and Chief Nuclear Officer, Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555


SUBJECT: THREE MILE ISLAND NUCLEAR GENERATING STATION  
==SUBJECT:==
- UNIT 1 DE SIGN BASES ASSURANCE INSPECTION (TEAM) REPORT 05000289/2018010
THREE MILE ISLAND NUCLEAR GENERATING STATION - UNIT 1 DESIGN BASES ASSURANCE INSPECTION (TEAM) REPORT 05000289/2018010


==Dear Mr. Hanson:==
==Dear Mr. Hanson:==
O n March 29, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Three Mile Island, Unit 1. On March 29, 2018, the NRC inspectors discussed the results of this inspection with Mr. Ed Callan, Site Vice President, and other members of your staff. The results of this inspection are documented in the enclosed report.
On March 29, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Three Mile Island, Unit 1. On March 29, 2018, the NRC inspectors discussed the results of this inspection with Mr. Ed Callan, Site Vice President, and other members of your staff. The results of this inspection are documented in the enclosed report.


The NRC inspectors did not identify any finding s or more-than-minor violation s. This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading
The NRC inspectors did not identify any findings or more-than-minor violations.
-rm/adams.html and the NRC
's Public Document Room in accordance with Title 10 of the Code of Federal Regulations (CFR), Part 2.390, "Public Inspections, Exemptions, Requests for Withholding."


Sincerely,/RA/ Stephen M. Pindale, Chief Engineering Branch 1 Division of Reactor Safety Docket Number: 50-289 License Number: DPR-50  
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 NRCs Public Document Room in accordance with Title 10 of the Code of Federal Regulations (CFR), Part 2.390, Public Inspections, Exemptions, Requests for Withholding.
 
Sincerely,
/RA/
Stephen M. Pindale, Chief Engineering Branch 1 Division of Reactor Safety Docket Number: 50-289 License Number: DPR-50


===Enclosure:===
===Enclosure:===
Inspection Report 05000289/2018010 cc w/encl: Distribution via ListServ
Inspection Report 05000289/2018010


ML18122A085 SUNSI ReviewNon-SensitiveSensitivePublicly AvailableNon-Publicly AvailableOFFICE RI/DRS RI/DRS RI/DRS NAME KMangan MYoung SPindale DATE 05/01/18 05/01 /18 05/02/18 1 Enclosure U.S. NUCLEAR REGULATORY COMMISSION Inspection Report Docket Number: 50-289 License Number: DPR-50 Report Number: 05000289/2018010 Enterprise Identifier:
==Inspection Report==
I-20 18-010-0038 Licensee: Exelon Generation Company, LLC (Exelon)
Docket Number: 50-289 License Number: DPR-50 Report Number: 05000289/2018010 Enterprise Identifier: I-2018-010-0038 Licensee: Exelon Generation Company, LLC (Exelon)
Facility: Three Mile Island, Unit 1 (TMI)
Facility: Three Mile Island, Unit 1 (TMI)
Location: Middletown, Pennsylvania Inspection Dates: March 12 through March 29, 2018 Inspectors:
Location: Middletown, Pennsylvania Inspection Dates: March 12 through March 29, 2018 Inspectors: K. Mangan, Senior Reactor Inspector, Division of Reactor Safety (DRS), Team Leader J. Brand, Reactor Inspector, DRS S. Elkhiamy, Reactor Inspector, DRS M. Orr, Reactor Inspector, DRS S. Kobylarz, NRC Electrical Contractor R. Waters, NRC Mechanical Contractor Approved By: Stephen M. Pindale, Chief Engineering Branch 1 Division of Reactor Safety Enclosure
K. Mangan, Senior Reactor Inspector, Division of Reactor Safety (DRS), Team Leader J. Brand, Reactor Inspector, DRS S. Elkhiamy, Reactor Inspector, DRS M. Orr, Reactor Inspector, DRS S. Kobylarz, NRC Electrical Contractor R. Waters, NRC Mechanical Contractor Approved By:
Stephen M. Pindale, Chief Engineering Branch 1 Division of Reactor Safety


2 SUMMARY The U.S. Nuclear Regulatory Commission (NRC) continued monitoring Exelon's performance at Three Mile Island, Unit 1 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.
=SUMMARY=
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring Exelons performance at
 
Three Mile Island, Unit 1 by conducting a design bases assurance inspection 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.


No findings or more-than-minor violations were identified.
No findings or more-than-minor violations were identified.


3 INSPECTION SCOPE S This inspection w as 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
=INSPECTION SCOPES=
-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 Bas e s Assurance Inspection (Teams) The team evaluated the following components, permanent modifications, and operating experience during the weeks of March 12, 2018, and March 26, 2018. For the components, the team reviewed the attributes listed in inspection procedure 71111.21M, Appendix A, Component Review Attributes. Specifically, the team evaluated these attributes as per 71111.21M, Appendix B, Component Design Review Considerations and 71111.21M, Appendix C, Component Walkdown Considerations
. Component s (5 Sample s) DH-V-6B, 'B' Decay Heat Suction Isolation Valve. The team used Appendix B guidance for Valves and Electric al Loads and conducted a walkdown of the equipment.
 
EED-PNL-1F, 'F' 125 Volt DC Distribution Panel. The team used Appendix B guidance for Electrical Loads and Motor Control Centers and conducted a walkdown of the equipment.
 
AFRCC B, Heat Sink Protection System Transfer Relays. The team used Appendix B guidance for Instrumentation and conducted a walkdown of the equipment.
 
EE-MCC-SH-1B, Motor Control Center 1B. The team used Appendix B guidance for Motor Control Centers and Circuit Breakers and Fuses and conducted a walkdown of the equipment.


MU-V-0017, Normal Makeup to Reactor Coolant System Control Valve. The team used Appendix B guidance for Valves and conducted a walkdown of the equipment.
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.


Component , Large Early Release Frequency (1 Sample) MS-V-1C, Main Steam Isolation Motor
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.
-Operated Valve. The team used Appendix B guidance for Valves, Cables, and Electric al Loads and conducted a walkdown of the equipment.


4 Permanent Modification s (6 Samples) Service Water P-1A/B Breaker Modification FLEX Reactor Coolant System and Spent Fuel Pool Makeup System Emergency Diesel Generator B Governor Tubing Improvement Replacing Existing Fuel Bridge Speed Controllers Replace Pressurizer Level Transmitter with 3000 PSIG Rated Model Replace Nuclear River Butterfly Valve and Actuator Operating Experience (3 Samples) 10 CFR Part 21 Notification
==REACTOR SAFETY==
- Foxboro Power Supply Potential Failures due to Defective Tie Wraps and Holders, dated 7/5/13 NRC Generic Letter 2016-01, Monitoring of Neutron
-Absorbing Materials in the Spent Fuel Pools, dated 4/7/16 10 CFR Part 21, Potential Defect Involving Failure of Westinghouse DB
-25 Breakers , dated 5/2/07 EXIT MEETING S AND DEBRIEFS The inspectors verified no proprietary information was retained or documented in this report.


On March 29, 2018, the team presented the Design Bases Assurance Inspection (Team s) results to Mr. Ed Callan, Site Vice President, and other members of Exelon staff.
===71111.21M - Design Bases Assurance Inspection (Teams)
The team evaluated the following components, permanent modifications, and operating experience during the weeks of March 12, 2018, and March 26, 2018.


5 DOCUMENTS REVIEWED 71111.21 M - DESIGN BASES ASSURANCE INSPECTION (TEAM S) Calculations C-1101-200-5710-002, Qualified Life Analysis for Limitorque Valves, Revision 0 C-1101-200-5710-005, Effect of Energized Space Heaters on the Qualified Life of Limitorque Operators, Revision 0 C-1101-210-E610-011, LPI/BS Pump NPSH Margin Available Following a LBLOCA, Revision 9A C-1101-700-E510-010, TMI-1 AC Voltage Regulation Study and Appendix 8.1 Load Tables for Steady State Operation, Revision 7 C-1101-733-5350-003, TMI-1 Class 1E 480V Unit Substation Settings, Revision 5 C-1101-734-5350-003, TMI-1 Battery Capacity Sizing and Voltage Drop for DC system, Revision 13 C-1101-823-5450-001, TMI-1 LBLOCA EQ Temperature Profile Using GOTHIC Computer Code (2016), Revision 10 C-1101-900-5450-005, TMI-1 Containment Response to a SBLOCA, Revision 0 C-1101-900-E410-039, MOV Delta P and Basis 07/18/08, Revision 9C C-1101-900-E410-049, Weal Link Calc for TMI GL 89
For the components, the team reviewed the attributes listed in inspection procedure 71111.21M, Appendix A, Component Review Attributes. Specifically, the team evaluated these attributes as per 71111.21M, Appendix B, Component Design Review Considerations and 71111.21M, Appendix C, Component Walkdown Considerations.
-13 Valves, Revision 7 HAGPU-08/98-052.7, Decay Heat Service Cooling River Water Pipe Support R WE-82 Evaluation, Revision 0 MS-V-0001C (TMI
-1), MIDA Calculation, AC Motor
-Operated GL 96
-05 Globe Valve, Revision 4 NAI-1341-001, TMI GOTHIC LP1 and BS Pump NPSH and Sump Strainer Pressure Drop Analysis during Recirculation (2016), Revision 3 Corrective Action Documents (*initiated in response to inspection)
AR01323415 AR01494443 AR01496437 AR01499751 AR01532653 AR01570697 AR01579471 AR01579591 AR01579593 AR01579595 AR01603077 AR01652619 AR01658782 AR01658795 AR01675261 AR01692695 AR02313345 AR02447062 AR02566171 AR02581866 AR02582872 AR02586540 AR02592570 AR02653735 AR02653884 AR02718735 AR03829260 AR03829301 AR03964783 AR04035763*
AR04040576 AR04041355 AR04047288 AR04075459 AR04111741 AR04114893*
AR04115187*
AR04115286*
AR04119589*
AR04120057*
AR04120224*
AR04123991*
Design and Licensing Basis CY-TM-170-300, Offsite Dose Calculation Manual, Revision 5 EQ-T1-103-04, Environmental Qualification, Limitorque Valve SB and SMB Series Actuators with Class B, H, and RH Insulation, Revision 8 EQ-T1-118, Rosemount Inc. Pressure Transmitters and Remote Diaphragm Seals 1153, Revision 13 Exelon Corporate Regulatory Commitment Change Summary Report Commitment 2015
-01, dated 12/15/15 N6100, N6101, N6102, Schulz Electric Motor Rewind, dated 10/18/04


6 RS-16-207, Response to Generic Letter 2016
Components ===
-01 RS-18-007, Response to Request for Additional Information Regarding Generic Letter 2016
{{IP sample|IP=IP 71111.21|count=5}}
-01 Safety Evaluation By The Office of Nuclear Reactor Regulation Related To Holtec International Report HI-202287 Regarding Use of Metamic in Fuel Pool Applications, dated 6/17/03SE 08-00872, 50.59 Evaluation for SFP Project Rerack (Metamic), Revision 0 TDR-648, TMI Qualification for LBLOCA Environments Methodology and List of Electrical Components Requiring Environmental Qualification for LBLOCA/HELB Mitigation, Revision 0 TMI, Unit 1
* DH-V-6B, B Decay Heat Suction Isolation Valve. The team used Appendix B guidance for Valves and Electrical Loads and conducted a walkdown of the equipment.
- Conforming License Amendment to Incorporate the Mitigation Strategies Required by Section B.5.b of Commission Order EA
* EED-PNL-1F, F 125 Volt DC Distribution Panel. The team used Appendix B guidance for Electrical Loads and Motor Control Centers and conducted a walkdown of the equipment.
-02-026, dated 7/18/07 Drawings 10001384-10, Sh. 1 and 2, 30
* AFRCCB, Heat Sink Protection System Transfer Relays. The team used Appendix B guidance for Instrumentation and conducted a walkdown of the equipment.
-150 TricentricValve with Limitorque Motor SMB
* EE-MCC-SH-1B, Motor Control Center 1B. The team used Appendix B guidance for Motor Control Centers and Circuit Breakers and Fuses and conducted a walkdown of the equipment.
-1/HBC-4, Revision 3 16200525, Sh. 1, Assembly
* MU-V-0017, Normal Makeup to Reactor Coolant System Control Valve. The team used Appendix B guidance for Valves and conducted a walkdown of the equipment.
- Booster (Governor), Revision 2 201-069, Sh. 2, 480 V Control Center, 1C, Engineered Safeguards Valves, Revision 41 201-254, 125/250V DC ENGD SFGD Distribution Panel 1F, Revision 21 206-051, Electrical One Line Diagram 250/125V DC sys & 120 AC Vital Instrumentation, Revision 37 208-421, Sh. 3, 480 V Control Center 1C
-ESV-Unit 1C, MSIV MS
-V-1C, Revision 4 208-446, Sh. 1, Electrical Elementary Diagram 480V Control Center NR
-SR System Tie Valve NR-V-2, Revision 0 208-446, Sh. 2, Electrical Elementary Diagram 480V Control Center NR
-SR System Tie Valve NR-V-6, Revision 1 21804-31, Operational Schematic Main Fuel Handling MCC, Revision 3 21804-34, Motor Control Center Wiring Diagram Refueling Machine, Revision 6 21804-37, Interconnection Diagram Refueling Machine, Revision 5 21804-42, Control Console Assembly Refueling Machine, Revision 6 21804-43, Control Console Assembly Refueling Machine, Revision D 302-011, Main Steam Flow Diagram, Revision 26 302-082, Emergency Feedwater Flow Diagram, Revision 25 302-202, Nuclear Services River Water System Flow Diagram, Revision 82 D-84N35833-A2-C024, Train B, Revision 10 D-84N35833-FD-0000, Functional Diagram Elements, Revision 2 D-84N35833-FD-0003, Functional Drawing H.S.P. System Channels II & IV, Generator A Train B EF/FW Control, Revision 8 D-84N35833-FD-0029, Functional Drawing H.S.P. System, OTSG A/EF Pumps EF Initiation
- Train B, Revision 5 E-201-063, Sh. 1 and 2, Electrical 480V Control Center 1B Engineered Safeguards Screen House, Revision 29 and 26 E-20 6-011, Main One Line and Relay Diagram, Revision 57 E-206-032, One Line & Relay Diagram
- ENGD. SFGDS. Screen HSE, Reactor BLDG. H&V, 480V SWGR, Revision 21 P-4464-472, Rockwell Edward Stop
-Check Valve MSIV, 24", Revision 0 Functional, Surveillance and Modification Acceptance Testing 1303-4.16, Emergency Power System, EG
-Y-1A, performed 3/06/18 1303-4.16, Emergency Power System, EG
-Y-1B, performed 3/13/18 MA-AA-723-300, Diagnostic Testing of Motor Operated Valves, performed 11/11/15 MA-AA-723-301, Periodic Inspection of Limitorque Model SMB/SB/SBD
-000, Through 5 Motor Operated Valves, performed 11/8/05 MA-AA-723-301, Periodic Inspection of Limitorque Model SMB/SB/SBD
-000, Through 5 Motor Operated Valves, performed 11/13/09


7 OP-TM-411-203, MS-V-1A/B/C/and D Full Stroke Test, performed 10/8/17 OP-TM-411-203, MS-V-1A/B/C/and D Full Stroke Test, performed 11/23/13 and 11/22/15 OP-TM-411-203, Stroke Timing MS Isolation Valves (Forced Outage), performed 12/3/16 OP-TM-541-252, Leakage Exam of NR System, performed 10/3/17 Miscellaneous 0420-104239, MU
===Component, Large Early Release Frequency (1 Sample)===
-V-17 Specification Sheet, Revision 3 1603077-02, Attachment 1, Technical Evaluation of Potential Adverse Localized Equipment Environment Identified for Intermediate Building 355' due to MSIVs, Revision 0 161 4182-02, Technical Evaluation, TMI
* MS-V-1C, Main Steam Isolation Motor-Operated Valve. The team used Appendix B guidance for Valves, Cables, and Electrical Loads and conducted a walkdown of the equipment.
-Cable and Connection Inspection Summary Report, dated 1/9/14 A2298548-01, Technical Evaluation of Visual Cable Inspection of Non EQ Cables and Connection in Adverse Localized Environments, Revision 0 EQ-T1-103, LIMITORQUE SB AND SMB Actuators with Class B H and RH Insulation, Revision 8 ER-AA-410-1000, Air Operated Valve Categorization, Revision 3 MM-128087-157, Specification for Vertical Bus Bar Support Upgrade, Revision 0 Sargent and Lundy TMI NUC/SEC Service River Water Cross Connect Valve NR
-V-6 Replacement Walkdown Reports, dated 6/09/14, 7/25/14, 1/07/15, 1/22/15 and 2/10/15 SDBD-T1-211, Makeup and Purification, Revision 9 SDBD-T1-212, Decay Heat Removal System, Revision 9 SDBD-T1-411, Main Steam System, Design Basis Document, Revision 7 SI 0-00616, SPEC200, Nuclear (N
-2ARPS Series) and Commercial (2ARPS Series) Power Supply Cable Tie Replacement for Heatsink Mounted Cable Harness, dated May 2013 TMI Unit 1 Cycle 19 Core Loading Plan, Revision 0 TMI Unit 1 Cycle 20 Core Loading Plan, Revision 0 TMI Unit 1 Cycles 20
-22 BOC SFP A Maps, Revision 0 TMI Unit 1 Refueling 20
-22 Pre Offload SFP A Maps, Revision 0 TMI-14-S-0186, 50.59 Screening, Replacement of Nuclear Services River Water Valve NR
-V-6 and Actuator, dated 8/22/14 TMI-15-S-303, 10CFR50.59 Screening ECR 15
-00236 - Screen Wash Pump Motor Circuit Breaker Replacement, Revision 1 TMI-20128, Exelon Power Labs Failure Analysis of a DB
-25E Breaker Auxiliary Switch, Revision 1 TM-MISC-02, AOV Program Risk Ranking Input, Revision 2 TM-MISC-03, MOV Risk Ranking, Revision 2 Modifications and Design Changes EC 14-00032, FLEX RCS and SFP Makeup System, Revision 2 EC 593896, Replace Pressurizer Level Transmitter (RC
-LT-777), with 3000 psig Rated Model, Revision 0 EC 593944, Replace Existing Fuel Bridge Speed Controllers, Revision 0 EC 620347, Modify Opto22 Interface to Encoders of Spent Fuel and Main Fuel Bridges, Revision 0 ECR 14-00155, EG-Y-1A Governor Booster, SS Tubing Improvement, Revision 0 ECR 1 4-00196, Replace NR
-V-6 Valve and Actuator, Revision 3 ECR 15-00236, SW-1-A/B - BK Modification, Revision 2 Operating Procedures 1105-19, Heat Sink Protection System, Revision 30 1107-2A, Emergency Electrical
- 4kV and 480 Volt, Revision 75 1107-4, Electrical Distribution Panel Listing, Revision 238 8 OP-TM-102-106-1001, Operator Response Time Master List at TMI, Revision 5 OP-TM-211-00, Makeup and Purification System, Revision 36 OP-TM-211-472, Manual Pressurizer Level Control, Revision 4 OP-TM-211-901, Emergency Injection (HPI/LPI), Revision 8 OP-TM-212-288, DH-V-6B and Associated Tests, Revision 10 OP-TM-411-000, Main Steam/OTSG, Revision 21 OP-TM-919-911, FSG-1 High Pressure Makeup Using FX
-P-1A or FX-P-1B, Revision 6 OP-TM-EOP-005, OTSG Tube Leakage, Revision 9 OP-TM-PPC-L2204, Alarm Response Procedure, Main Steam Isolation MS
-V 1A (MS-V-1B, MS-V1C, MS-V1D), Revision 1 Procedures 1107-2C, Vital DC Electrical System, Revision 12 1107-4, Electrical Distribution Panel Listing, Revision 238 1302-5.12, Pressurizer Temperature and Level Channel Calibration, Revision 30C 1302-5.2, Surveillance Procedure, RPS High and Low RC Pressure Channels, Revision 38 1302-6.2, RC-LT-777, Pressurizer Level Calibration, Revision 20A 1303-11.39A, HSPS
- EFW Auto Initiation, Revision 47 1410-Y-72, Bolt/Nut Torqueing and Sequences, Revision 28 1420-LTQ-1, Limitorque Valve Operator Maintenance, Revision 31 CC-AA-102, Design Input and Configuration Change Impact Screening, Revision 28 CC-AA-103, Configuration Change Control for Permanent Physical Plant Changes, Revision 29 E-21, Thermal Overload Devices Inspection and Testing, Revision 43 E-4, Switchgear, Bus Duct, MCC Transformer, Inspection and Cleaning, Revision 41 E-5.2, Westinghouse 480 Volt DB
-50 Circuit Breaker Maintenance and Testing, Revision 8 E-5.3, 480 Volt Eaton DB
-25-LV-VSR Vacuum Starter Maintenance and Testing, Revision 1 E-62.1, Molded Case Circuit Breaker Testing Thermal Magnetic Trip, Revision 13 ER-AA-300, MOV Program Administrative Procedure, Revision 11 ER-AA-302-1009, Final JOG MOV Periodic Verification Program Implementation, Revision 3 ES-010T, TMI-1 Environmental Parameters, Revision 8 MA-AA-723-300, Diagnostic Testing of Motor Operated Valves, Revision 12 MA-AA-723-300-1004, Quiklook Diagnostic Test Equipment/Sensor Guideline, Revision 4 MA-AA-723-301, Periodic Inspection of Limitorque Model SMB/SB/SBD
-000 through 5 Motor Operated Valves, Revision 13 MA-AA-723-500, Inspection of Non EQ Cables and Connections for Managing Adverse Localized Environments, Revision 9 MA-MA-716-010-1008, Work Order Work Performance
, 5 NF-AA-301, Special Nuclear Material and Core Component Movement, Revision 1 NF-AA-310, Special Nuclear Material and Core Component Movement, Revision 8 NF-TM-310-1001, PWR Generation of Fuel Moves using SHUFFLEWORKS Revision 2 NF-TM-600-1000, TMI Spent Fuel Rack Boral/Metamic Coupon Program, Revision 5 Vendor Manuals VM-TM-0029, Limitorque SMB Actuators, Revision 0 VM-TM-0069, Rockwell Edwards-Pressure Seal and Univalve Valves, dated 11/30/17 VM-TM-0191, Fairbanks Morse (Colt Industries) Emergency Diesel Generators, Volumes 1&2, Revision 70 VM-TM-0193, Conax Buffalo Corporation, Electric Conductor Seal Assemblies with Long Body for Pipe Thread Equipment Interface, Revision G VM-TM-0255, EIM Co., Inc. Valve Operators, Revision 5 VM-TM-2962, Vendor Technical Manual, Revision 8 VM-TM-3014, Weir Valves and Controls USA, Instruction Manual for 30 Inch Class 150 TCBV w/ Gear Operator, Revision 2 9 Work Orders C2033049 C2033743 C2033849 R2010207 R2076951 R2078373 R2141555 R2142407 R2154245 R2157073 R2157486 R2188444 R2190519 R2192586 R2230884 R2236081 C2029069 03502097 03503764 04185481 04186464 04190782 04353591 04364504 04367361 04373451 04373780 04373807 04374384 04376201 04382571 04581170 04593610 04598030 04599420 04662196 04682875 04685682 04718509 04744773 B.HansonUNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 2100 RENAISSANCE BOULEVARD, SUITE 100 KING OF PRUSSIA, PA 19406
-2713 May 2, 2018 Mr. Bryan Senior Vice President, Exelon Generation, LLC President and Chief Nuclear Officer, Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555


SUBJECT: THREE MILE ISLAND NUCLEAR GENERATING STATION
===Permanent Modifications (6 Samples)===
- UNIT 1 DE SIGN BASES ASSURANCE INSPECTION (TEAM) REPORT 05000289/2018010
* Service Water P-1A/B Breaker Modification
 
* FLEX Reactor Coolant System and Spent Fuel Pool Makeup System
==Dear Mr. Hanson:==
* Emergency Diesel Generator B Governor Tubing Improvement
O n March 29, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Three Mile Island, Unit 1. On March 29, 2018, the NRC inspectors discussed the results of this inspection with Mr. Ed Callan, Site Vice President, and other members of your staff. The results of this inspection are documented in the enclosed report.
* Replacing Existing Fuel Bridge Speed Controllers
* Replace Pressurizer Level Transmitter with 3000 PSIG Rated Model
* Replace Nuclear River Butterfly Valve and Actuator


The NRC inspectors did not identify any finding s or more-than-minor violation s. This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading
===Operating Experience (3 Samples)===
-rm/adams.html and the NRC
* 10 CFR Part 21 Notification - Foxboro Power Supply Potential Failures due to Defective Tie Wraps and Holders, dated 7/5/13
's Public Document Room in accordance with Title 10 of the Code of Federal Regulations (CFR), Part 2.390, "Public Inspections, Exemptions, Requests for Withholding."
* NRC Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in the Spent Fuel Pools, dated 4/7/16
* 10 CFR Part 21, Potential Defect Involving Failure of Westinghouse DB-25 Breakers, dated 5/2/07


Sincerely,/RA/ Stephen M. Pindale, Chief Engineering Branch 1 Division of Reactor Safety Docket Number: 50-289 License Number: DPR-50
==EXIT MEETINGS AND DEBRIEFS==
The inspectors verified no proprietary information was retained or documented in this report.
* On March 29, 2018, the team presented the Design Bases Assurance Inspection (Teams)results to Mr. Ed Callan, Site Vice President, and other members of Exelon staff.


===Enclosure:===
=DOCUMENTS REVIEWED=
Inspection Report 05000289/2018010 cc w/encl: Distribution via ListServ


ML18122A085 SUNSI ReviewNon-SensitiveSensitivePublicly AvailableNon-Publicly AvailableOFFICE RI/DRS RI/DRS RI/DRS NAME KMangan MYoung SPindale DATE 05/01/18 05/01 /18 05/02/18 1 Enclosure U.S. NUCLEAR REGULATORY COMMISSION Inspection Report Docket Number: 50-289 License Number: DPR-50 Report Number: 05000289/2018010 Enterprise Identifier:
71111.21M - DESIGN BASES ASSURANCE INSPECTION (TEAMS)
I-20 18-010-0038 Licensee: Exelon Generation Company, LLC (Exelon)
Calculations
Facility: Three Mile Island, Unit 1 (TMI)
C-1101-200-5710-002, Qualified Life Analysis for Limitorque Valves, Revision 0
Location: Middletown, Pennsylvania Inspection Dates: March 12 through March 29, 2018 Inspectors:
C-1101-200-5710-005, Effect of Energized Space Heaters on the Qualified Life of Limitorque
K. Mangan, Senior Reactor Inspector, Division of Reactor Safety (DRS), Team Leader J. Brand, Reactor Inspector, DRS S. Elkhiamy, Reactor Inspector, DRS M. Orr, Reactor Inspector, DRS S. Kobylarz, NRC Electrical Contractor R. Waters, NRC Mechanical Contractor Approved By:
Operators, Revision 0
Stephen M. Pindale, Chief Engineering Branch 1 Division of Reactor Safety
C-1101-210-E610-011, LPI/BS Pump NPSH Margin Available Following a LBLOCA, Revision 9A
C-1101-700-E510-010, TMI-1 AC Voltage Regulation Study and Appendix 8.1 Load Tables for
Steady State Operation, Revision 7
C-1101-733-5350-003, TMI-1 Class 1E 480V Unit Substation Settings, Revision 5
C-1101-734-5350-003, TMI-1 Battery Capacity Sizing and Voltage Drop for DC system,
Revision 13
C-1101-823-5450-001, TMI-1 LBLOCA EQ Temperature Profile Using GOTHIC Computer Code
      (2016), Revision 10
C-1101-900-5450-005, TMI-1 Containment Response to a SBLOCA, Revision 0
C-1101-900-E410-039, MOV Delta P and Basis 07/18/08, Revision 9C
C-1101-900-E410-049, Weal Link Calc for TMI GL 89-13 Valves, Revision 7
HAGPU-08/98-052.7, Decay Heat Service Cooling River Water Pipe Support RWE-82
Evaluation, Revision 0
MS-V-0001C (TMI-1), MIDA Calculation, AC Motor-Operated GL 96-05 Globe Valve, Revision 4
NAI-1341-001, TMI GOTHIC LP1 and BS Pump NPSH and Sump Strainer Pressure Drop
Analysis during Recirculation (2016), Revision 3
Corrective Action Documents (*initiated in response to inspection)
AR01323415                AR01652619                AR02592570              AR04075459
AR01494443                AR01658782                AR02653735              AR04111741
AR01496437                AR01658795                AR02653884              AR04114893*
AR01499751                AR01675261                AR02718735              AR04115187*
AR01532653                AR01692695                AR03829260              AR04115286*
AR01570697                AR02313345                AR03829301              AR04119589*
AR01579471                AR02447062                AR03964783              AR04120057*
AR01579591                AR02566171                AR04035763*              AR04120224*
AR01579593                AR02581866                AR04040576              AR04123991*
AR01579595                AR02582872                AR04041355
AR01603077                AR02586540                AR04047288
Design and Licensing Basis
CY-TM-170-300, Offsite Dose Calculation Manual, Revision 5
EQ-T1-103-04, Environmental Qualification, Limitorque Valve SB and SMB Series Actuators
with Class B, H, and RH Insulation, Revision 8
EQ-T1-118, Rosemount Inc. Pressure Transmitters and Remote Diaphragm Seals 1153,
Revision 13
Exelon Corporate Regulatory Commitment Change Summary Report Commitment 2015-01,
dated 12/15/15
N6100, N6101, N6102, Schulz Electric Motor Rewind, dated 10/18/04
RS-16-207, Response to Generic Letter 2016-01
RS-18-007, Response to Request for Additional Information Regarding Generic Letter 2016-01
Safety Evaluation By The Office of Nuclear Reactor Regulation Related To Holtec International
Report HI-202287 Regarding Use of Metamic in Fuel Pool Applications, dated 6/17/03SE
08-00872, 50.59 Evaluation for SFP Project Rerack (Metamic), Revision 0
TDR-648, TMI Qualification for LBLOCA Environments Methodology and List of Electrical
Components Requiring Environmental Qualification for LBLOCA/HELB Mitigation,
Revision 0
TMI, Unit 1 - Conforming License Amendment to Incorporate the Mitigation Strategies Required
by Section B.5.b of Commission Order EA-02-026, dated 7/18/07
Drawings
10001384-10, Sh. 1 and 2, 30-150 TricentricValve with Limitorque Motor SMB-1/HBC-4,
Revision 3
200525, Sh. 1, Assembly - Booster (Governor), Revision 2
201-069, Sh. 2, 480 V Control Center, 1C, Engineered Safeguards Valves, Revision 41
201-254, 125/250V DC ENGD SFGD Distribution Panel 1F, Revision 21
206-051, Electrical One Line Diagram 250/125V DC sys & 120 AC Vital Instrumentation,
Revision 37
208-421, Sh. 3, 480 V Control Center 1C-ESV-Unit 1C, MSIV MS-V-1C, Revision 4
208-446, Sh. 1, Electrical Elementary Diagram 480V Control Center NR-SR System Tie Valve
NR-V-2, Revision 0
208-446, Sh. 2, Electrical Elementary Diagram 480V Control Center NR-SR System Tie Valve
NR-V-6, Revision 1
21804-31, Operational Schematic Main Fuel Handling MCC, Revision 3
21804-34, Motor Control Center Wiring Diagram Refueling Machine, Revision 6
21804-37, Interconnection Diagram Refueling Machine, Revision 5
21804-42, Control Console Assembly Refueling Machine, Revision 6
21804-43, Control Console Assembly Refueling Machine, Revision D
2-011, Main Steam Flow Diagram, Revision 26
2-082, Emergency Feedwater Flow Diagram, Revision 25
2-202, Nuclear Services River Water System Flow Diagram, Revision 82
D-84N35833-A2-C024, Train B, Revision 10
D-84N35833-FD-0000, Functional Diagram Elements, Revision 2
D-84N35833-FD-0003, Functional Drawing H.
: [[contact::S.P. System Channels II & IV]], Generator A Train B
EF/FW Control, Revision 8
D-84N35833-FD-0029, Functional Drawing H.
: [[contact::S.P. System]], OTSG A/EF Pumps EF Initiation -
Train B, Revision 5
E-201-063, Sh. 1 and 2, Electrical 480V Control Center 1B Engineered Safeguards Screen
House, Revision 29 and 26
E-206-011, Main One Line and Relay Diagram, Revision 57
E-206-032, One Line & Relay Diagram - ENG
: [[contact::D. SFGDS. Screen HSE]], Reactor BLD
: [[contact::G. H&V]],
480V SWGR, Revision 21
P-4464-472, Rockwell Edward Stop-Check Valve MSIV, 24, Revision 0
Functional, Surveillance and Modification Acceptance Testing
1303-4.16, Emergency Power System, EG-Y-1A, performed 3/06/18
1303-4.16, Emergency Power System, EG-Y-1B, performed 3/13/18
MA-AA-723-300, Diagnostic Testing of Motor Operated Valves, performed 11/11/15
MA-AA-723-301, Periodic Inspection of Limitorque Model SMB/SB/SBD-000, Through 5 Motor
Operated Valves, performed 11/8/05
MA-AA-723-301, Periodic Inspection of Limitorque Model SMB/SB/SBD-000, Through 5 Motor
Operated Valves, performed 11/13/09
OP-TM-411-203, MS-V-1A/B/C/and D Full Stroke Test, performed 10/8/17
OP-TM-411-203, MS-V-1A/B/C/and D Full Stroke Test, performed 11/23/13 and 11/22/15
OP-TM-411-203, Stroke Timing MS Isolation Valves (Forced Outage), performed 12/3/16
OP-TM-541-252, Leakage Exam of NR System, performed 10/3/17
Miscellaneous
20-104239, MU-V-17 Specification Sheet, Revision 3
1603077-02, Attachment 1, Technical Evaluation of Potential Adverse Localized Equipment
Environment Identified for Intermediate Building 355 due to MSIVs, Revision 0
1614182-02, Technical Evaluation, TMI-Cable and Connection Inspection Summary Report,
dated 1/9/14
A2298548-01, Technical Evaluation of Visual Cable Inspection of Non EQ Cables and
Connection in Adverse Localized Environments, Revision 0
EQ-T1-103, LIMITORQUE SB AND SMB Actuators with Class B H and RH Insulation,
Revision 8
ER-AA-410-1000, Air Operated Valve Categorization, Revision 3
MM-128087-157, Specification for Vertical Bus Bar Support Upgrade, Revision 0
Sargent and Lundy TMI NUC/SEC Service River Water Cross Connect Valve NR-V-6
Replacement Walkdown Reports, dated 6/09/14, 7/25/14, 1/07/15, 1/22/15 and 2/10/15
SDBD-T1-211, Makeup and Purification, Revision 9
SDBD-T1-212, Decay Heat Removal System, Revision 9
SDBD-T1-411, Main Steam System, Design Basis Document, Revision 7
SI 0-00616, SPEC200, Nuclear (N-2ARPS Series) and Commercial (2ARPS Series) Power
Supply Cable Tie Replacement for Heatsink Mounted Cable Harness, dated May 2013
TMI Unit 1 Cycle 19 Core Loading Plan, Revision 0
TMI Unit 1 Cycle 20 Core Loading Plan, Revision 0
TMI Unit 1 Cycles 20-22 BOC SFP A Maps, Revision 0
TMI Unit 1 Refueling 20-22 Pre Offload SFP A Maps, Revision 0
TMI-14-S-0186, 50.59 Screening, Replacement of Nuclear Services River Water Valve NR-V-6
and Actuator, dated 8/22/14
TMI-15-S-303, 10CFR50.59 Screening ECR 15-00236 - Screen Wash Pump Motor Circuit
Breaker Replacement, Revision 1
TMI-20128, Exelon Power Labs Failure Analysis of a DB-25E Breaker Auxiliary Switch,
Revision 1
TM-MISC-02, AOV Program Risk Ranking Input, Revision 2
TM-MISC-03, MOV Risk Ranking, Revision 2
Modifications and Design Changes
EC 14-00032, FLEX RCS and SFP Makeup System, Revision 2
EC 593896, Replace Pressurizer Level Transmitter (RC-LT-777), with 3000 psig Rated Model,
Revision 0
EC 593944, Replace Existing Fuel Bridge Speed Controllers, Revision 0
EC 620347, Modify Opto22 Interface to Encoders of Spent Fuel and Main Fuel Bridges,
Revision 0
ECR 14-00155, EG-Y-1A Governor Booster, SS Tubing Improvement, Revision 0
ECR 14-00196, Replace NR-V-6 Valve and Actuator, Revision 3
ECR 15-00236, SW-1-A/B - BK Modification, Revision 2
Operating Procedures
1105-19, Heat Sink Protection System, Revision 30
1107-2A, Emergency Electrical - 4kV and 480 Volt, Revision 75
1107-4, Electrical Distribution Panel Listing, Revision 238
OP-TM-102-106-1001, Operator Response Time Master List at TMI, Revision 5
OP-TM-211-00, Makeup and Purification System, Revision 36
OP-TM-211-472, Manual Pressurizer Level Control, Revision 4
OP-TM-211-901, Emergency Injection (HPI/LPI), Revision 8
OP-TM-212-288, DH-V-6B and Associated Tests, Revision 10
OP-TM-411-000, Main Steam/OTSG, Revision 21
OP-TM-919-911, FSG-1 High Pressure Makeup Using FX-P-1A or FX-P-1B, Revision 6
OP-TM-EOP-005, OTSG Tube Leakage, Revision 9
OP-TM-PPC-L2204, Alarm Response Procedure, Main Steam Isolation MS-V1A (MS-V-1B,
MS-V1C, MS-V1D), Revision 1
Procedures
1107-2C, Vital DC Electrical System, Revision 12
1107-4, Electrical Distribution Panel Listing, Revision 238
1302-5.12, Pressurizer Temperature and Level Channel Calibration, Revision 30C
1302-5.2, Surveillance Procedure, RPS High and Low RC Pressure Channels, Revision 38
1302-6.2, RC-LT-777, Pressurizer Level Calibration, Revision 20A
1303-11.39A, HSPS - EFW Auto Initiation, Revision 47
1410-Y-72, Bolt/Nut Torqueing and Sequences, Revision 28
20-LTQ-1, Limitorque Valve Operator Maintenance, Revision 31
CC-AA-102, Design Input and Configuration Change Impact Screening, Revision 28
CC-AA-103, Configuration Change Control for Permanent Physical Plant Changes, Revision 29
E-21, Thermal Overload Devices Inspection and Testing, Revision 43
E-4, Switchgear, Bus Duct, MCC Transformer, Inspection and Cleaning, Revision 41
E-5.2, Westinghouse 480 Volt DB-50 Circuit Breaker Maintenance and Testing, Revision 8
E-5.3, 480 Volt Eaton DB-25-LV-VSR Vacuum Starter Maintenance and Testing, Revision 1
E-62.1, Molded Case Circuit Breaker Testing Thermal Magnetic Trip, Revision 13
ER-AA-300, MOV Program Administrative Procedure, Revision 11
ER-AA-302-1009, Final JOG MOV Periodic Verification Program Implementation, Revision 3
ES-010T, TMI-1 Environmental Parameters, Revision 8
MA-AA-723-300, Diagnostic Testing of Motor Operated Valves, Revision 12
MA-AA-723-300-1004, Quiklook Diagnostic Test Equipment/Sensor Guideline, Revision 4
MA-AA-723-301, Periodic Inspection of Limitorque Model SMB/SB/SBD-000 through 5 Motor
Operated Valves, Revision 13
MA-AA-723-500, Inspection of Non EQ Cables and Connections for Managing Adverse
Localized Environments, Revision 9
MA-MA-716-010-1008, Work Order Work Performance, 5
NF-AA-301, Special Nuclear Material and Core Component Movement, Revision 1
NF-AA-310, Special Nuclear Material and Core Component Movement, Revision 8
NF-TM-310-1001, PWR Generation of Fuel Moves using SHUFFLEWORKS Revision 2
NF-TM-600-1000, TMI Spent Fuel Rack Boral/Metamic Coupon Program, Revision 5
Vendor Manuals
VM-TM-0029, Limitorque SMB Actuators, Revision 0
VM-TM-0069, Rockwell Edwards-Pressure Seal and Univalve Valves, dated 11/30/17
VM-TM-0191, Fairbanks Morse (Colt Industries) Emergency Diesel Generators, Volumes 1&2,
Revision 70
VM-TM-0193, Conax Buffalo Corporation, Electric Conductor Seal Assemblies with Long Body
for Pipe Thread Equipment Interface, Revision G
VM-TM-0255, EIM Co., Inc. Valve Operators, Revision 5
VM-TM-2962, Vendor Technical Manual, Revision 8
VM-TM-3014, Weir Valves and Controls USA, Instruction Manual for 30 Inch Class 150 TCBV
w/ Gear Operator, Revision 2
Work Orders
C2033049    R2154245 C2029069 04367361 04593610
C2033743    R2157073 03502097 04373451 04598030
C2033849    R2157486 03503764 04373780 04599420
R2010207    R2188444 04185481 04373807 04662196
R2076951    R2190519 04186464 04374384 04682875
R2078373    R2192586 04190782 04376201 04685682
R2141555    R2230884 04353591 04382571 04718509
R2142407    R2236081 04364504 04581170 04744773
B. Hanson
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION I
2100 RENAISSANCE BOULEVARD, SUITE 100
KING OF PRUSSIA, PA 19406-2713
May 2, 2018
Mr. Bryan C. Hanson
Senior Vice President, Exelon Generation, LLC
President and Chief Nuclear Officer, Exelon Nuclear
4300 Winfield Road
Warrenville, IL 60555
SUBJECT:          THREE MILE ISLAND NUCLEAR GENERATING STATION - UNIT 1
DESIGN BASES ASSURANCE INSPECTION (TEAM) REPORT
05000289/2018010
Dear Mr. Hanson:
On March 29, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection
at Three Mile Island, Unit 1. On March 29, 2018, the NRC inspectors discussed the results of
this inspection with Mr. Ed Callan, Site Vice President, 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 NRCs Public Document
Room in accordance with Title 10 of the Code of Federal Regulations (CFR), Part 2.390,
Public Inspections, Exemptions, Requests for Withholding.
Sincerely,
                                                /RA/
Stephen  
: [[contact::M. Pindale]], Chief
Engineering Branch 1
Division of Reactor Safety
Docket Number: 50-289
License Number: DPR-50
Enclosure:
Inspection Report 05000289/2018010
cc w/encl: Distribution via ListServ
ML18122A085
SUNSI Review        Non-Sensitive                    Publicly Available
Sensitive                        Non-Publicly Available
OFFICE          RI/DRS          RI/DRS          RI/DRS
NAME            KMangan        MYoung          SPindale
DATE            05/01/18        05/01 /18      05/02/18


2 SUMMARY The U.S. Nuclear Regulatory Commission (NRC) continued monitoring Exelon's performance at Three Mile Island, Unit 1 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.
U.S. NUCLEAR REGULATORY COMMISSION
Inspection Report
Docket Number:              50-289
License Number:            DPR-50
Report Number:              05000289/2018010
Enterprise Identifier:      I-2018-010-0038
Licensee:                  Exelon Generation Company, LLC (Exelon)
Facility:                  Three Mile Island, Unit 1 (TMI)
Location:                  Middletown, Pennsylvania
Inspection Dates:          March 12 through March 29, 2018
Inspectors:               
: [[contact::K. Mangan]], Senior Reactor Inspector, Division of Reactor Safety
                              (DRS), Team Leader
: [[contact::J. Brand]], Reactor Inspector, DRS
: [[contact::S. Elkhiamy]], Reactor Inspector, DRS
: [[contact::M. Orr]], Reactor Inspector, DRS
: [[contact::S. Kobylarz]], NRC Electrical Contractor
: [[contact::R. Waters]], NRC Mechanical Contractor
Approved By:                Stephen
: [[contact::M. Pindale]], Chief
Engineering Branch 1
Division of Reactor Safety


SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring Exelons performance at
Three Mile Island, Unit 1 by conducting a design bases assurance inspection 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.
No findings or more-than-minor violations were identified.
No findings or more-than-minor violations were identified.
 
INSPECTION SCOPES
3 INSPECTION SCOPE S This inspection w as 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
This inspection was conducted using the appropriate portions of the inspection procedure in
-rm/doc-collections/insp
effect at the beginning of the inspection unless otherwise noted. Currently approved inspection
-manual/inspection
procedures with their attached revision histories are located on the public website at
-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  
http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html.
- Operations Phase."
Samples were declared complete when the inspection procedure requirements most
 
appropriate to the inspection activity were met consistent with Inspection Manual Chapter 2515,
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.
Light-Water Reactor Inspection Program - Operations Phase. The team reviewed selected
 
procedures and records, observed activities, and interviewed personnel to assess licensee
REACTOR SAFETY 71111.21 M - Design Bas e s Assurance Inspection (Teams) The team evaluated the following components, permanent modifications, and operating experience during the weeks of March 12, 2018, and March 26, 2018. For the components, the team reviewed the attributes listed in inspection procedure 71111.21M, Appendix A, Component Review Attributes. Specifically, the team evaluated these attributes as per 71111.21M, Appendix B, Component Design Review Considerations and 71111.21M, Appendix C, Component Walkdown Considerations
performance and compliance with Commission rules and regulations, license conditions, site
. Component s (5 Sample s) DH-V-6B, 'B' Decay Heat Suction Isolation Valve. The team used Appendix B guidance for Valves and Electric al Loads and conducted a walkdown of the equipment.
procedures, and standards.
 
REACTOR SAFETY
EED-PNL-1F, 'F' 125 Volt DC Distribution Panel. The team used Appendix B guidance for Electrical Loads and Motor Control Centers and conducted a walkdown of the equipment.
71111.21M - Design Bases Assurance Inspection (Teams)
 
The team evaluated the following components, permanent modifications, and operating
AFRCC B, Heat Sink Protection System Transfer Relays. The team used Appendix B guidance for Instrumentation and conducted a walkdown of the equipment.
experience during the weeks of March 12, 2018, and March 26, 2018.
 
For the components, the team reviewed the attributes listed in inspection procedure 71111.21M,
EE-MCC-SH-1B, Motor Control Center 1B. The team used Appendix B guidance for Motor Control Centers and Circuit Breakers and Fuses and conducted a walkdown of the equipment.
Appendix A, Component Review Attributes. Specifically, the team evaluated these attributes as
 
per 71111.21M, Appendix B, Component Design Review Considerations and 71111.21M,
MU-V-0017, Normal Makeup to Reactor Coolant System Control Valve. The team used Appendix B guidance for Valves and conducted a walkdown of the equipment.
Appendix C, Component Walkdown Considerations.
 
Components (5 Samples)
Component , Large Early Release Frequency (1 Sample) MS-V-1C, Main Steam Isolation Motor
*  DH-V-6B, B Decay Heat Suction Isolation Valve. The team used Appendix B guidance for
-Operated Valve. The team used Appendix B guidance for Valves, Cables, and Electric al Loads and conducted a walkdown of the equipment.
Valves and Electrical Loads and conducted a walkdown of the equipment.
 
*  EED-PNL-1F, F 125 Volt DC Distribution Panel. The team used Appendix B guidance for
4 Permanent Modification s (6 Samples) Service Water P-1A/B Breaker Modification FLEX Reactor Coolant System and Spent Fuel Pool Makeup System Emergency Diesel Generator B Governor Tubing Improvement Replacing Existing Fuel Bridge Speed Controllers Replace Pressurizer Level Transmitter with 3000 PSIG Rated Model Replace Nuclear River Butterfly Valve and Actuator Operating Experience (3 Samples) 10 CFR Part 21 Notification  
Electrical Loads and Motor Control Centers and conducted a walkdown of the equipment.
- Foxboro Power Supply Potential Failures due to Defective Tie Wraps and Holders, dated 7/5/13 NRC Generic Letter 2016-01, Monitoring of Neutron
*  AFRCCB, Heat Sink Protection System Transfer Relays. The team used Appendix B
-Absorbing Materials in the Spent Fuel Pools, dated 4/7/16 10 CFR Part 21, Potential Defect Involving Failure of Westinghouse DB
guidance for Instrumentation and conducted a walkdown of the equipment.
-25 Breakers , dated 5/2/07 EXIT MEETING S AND DEBRIEFS The inspectors verified no proprietary information was retained or documented in this report.
*  EE-MCC-SH-1B, Motor Control Center 1B. The team used Appendix B guidance for Motor
 
Control Centers and Circuit Breakers and Fuses and conducted a walkdown of the
On March 29, 2018, the team presented the Design Bases Assurance Inspection (Team s) results to Mr. Ed Callan, Site Vice President, and other members of Exelon staff.
equipment.
 
*  MU-V-0017, Normal Makeup to Reactor Coolant System Control Valve. The team used
5 DOCUMENTS REVIEWED 71111.21 M - DESIGN BASES ASSURANCE INSPECTION (TEAM S) Calculations C-1101-200-5710-002, Qualified Life Analysis for Limitorque Valves, Revision 0 C-1101-200-5710-005, Effect of Energized Space Heaters on the Qualified Life of Limitorque Operators, Revision 0 C-1101-210-E610-011, LPI/BS Pump NPSH Margin Available Following a LBLOCA, Revision 9A C-1101-700-E510-010, TMI-1 AC Voltage Regulation Study and Appendix 8.1 Load Tables for Steady State Operation, Revision 7 C-1101-733-5350-003, TMI-1 Class 1E 480V Unit Substation Settings, Revision 5 C-1101-734-5350-003, TMI-1 Battery Capacity Sizing and Voltage Drop for DC system, Revision 13 C-1101-823-5450-001, TMI-1 LBLOCA EQ Temperature Profile Using GOTHIC Computer Code (2016), Revision 10 C-1101-900-5450-005, TMI-1 Containment Response to a SBLOCA, Revision 0 C-1101-900-E410-039, MOV Delta P and Basis 07/18/08, Revision 9C C-1101-900-E410-049, Weal Link Calc for TMI GL 89
Appendix B guidance for Valves and conducted a walkdown of the equipment.
-13 Valves, Revision 7 HAGPU-08/98-052.7, Decay Heat Service Cooling River Water Pipe Support R WE-82 Evaluation, Revision 0 MS-V-0001C (TMI
Component, Large Early Release Frequency (1 Sample)
-1), MIDA Calculation, AC Motor
*  MS-V-1C, Main Steam Isolation Motor-Operated Valve. The team used Appendix B
-Operated GL 96
guidance for Valves, Cables, and Electrical Loads and conducted a walkdown of the
-05 Globe Valve, Revision 4 NAI-1341-001, TMI GOTHIC LP1 and BS Pump NPSH and Sump Strainer Pressure Drop Analysis during Recirculation (2016), Revision 3 Corrective Action Documents (*initiated in response to inspection)
equipment.
AR01323415 AR01494443 AR01496437 AR01499751 AR01532653 AR01570697 AR01579471 AR01579591 AR01579593 AR01579595 AR01603077 AR01652619 AR01658782 AR01658795 AR01675261 AR01692695 AR02313345 AR02447062 AR02566171 AR02581866 AR02582872 AR02586540 AR02592570 AR02653735 AR02653884 AR02718735 AR03829260 AR03829301 AR03964783 AR04035763*
Permanent Modifications (6 Samples)
AR04040576 AR04041355 AR04047288 AR04075459 AR04111741 AR04114893*
*  Service Water P-1A/B Breaker Modification
AR04115187*
*  FLEX Reactor Coolant System and Spent Fuel Pool Makeup System
AR04115286*
*  Emergency Diesel Generator B Governor Tubing Improvement
AR04119589*
*  Replacing Existing Fuel Bridge Speed Controllers
AR04120057*
*  Replace Pressurizer Level Transmitter with 3000 PSIG Rated Model
AR04120224*
*  Replace Nuclear River Butterfly Valve and Actuator
AR04123991*
Operating Experience (3 Samples)
Design and Licensing Basis CY-TM-170-300, Offsite Dose Calculation Manual, Revision 5 EQ-T1-103-04, Environmental Qualification, Limitorque Valve SB and SMB Series Actuators with Class B, H, and RH Insulation, Revision 8 EQ-T1-118, Rosemount Inc. Pressure Transmitters and Remote Diaphragm Seals 1153, Revision 13 Exelon Corporate Regulatory Commitment Change Summary Report Commitment 2015
*  10 CFR Part 21 Notification - Foxboro Power Supply Potential Failures due to Defective
-01, dated 12/15/15 N6100, N6101, N6102, Schulz Electric Motor Rewind, dated 10/18/04
Tie Wraps and Holders, dated 7/5/13
 
*  NRC Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in the Spent Fuel
6 RS-16-207, Response to Generic Letter 2016
Pools, dated 4/7/16
-01 RS-18-007, Response to Request for Additional Information Regarding Generic Letter 2016
*  10 CFR Part 21, Potential Defect Involving Failure of Westinghouse DB-25 Breakers,
-01 Safety Evaluation By The Office of Nuclear Reactor Regulation Related To Holtec International Report HI-202287 Regarding Use of Metamic in Fuel Pool Applications, dated 6/17/03SE 08-00872, 50.59 Evaluation for SFP Project Rerack (Metamic), Revision 0 TDR-648, TMI Qualification for LBLOCA Environments Methodology and List of Electrical Components Requiring Environmental Qualification for LBLOCA/HELB Mitigation, Revision 0 TMI, Unit 1  
dated 5/2/07
- Conforming License Amendment to Incorporate the Mitigation Strategies Required by Section B.5.b of Commission Order EA
EXIT MEETINGS AND DEBRIEFS
-02-026, dated 7/18/07 Drawings 10001384-10, Sh. 1 and 2, 30
The inspectors verified no proprietary information was retained or documented in this report.
-150 TricentricValve with Limitorque Motor SMB
*  On March 29, 2018, the team presented the Design Bases Assurance Inspection (Teams)
-1/HBC-4, Revision 3 16200525, Sh. 1, Assembly  
results to Mr. Ed Callan, Site Vice President, and other members of Exelon staff.
- Booster (Governor), Revision 2 201-069, Sh. 2, 480 V Control Center, 1C, Engineered Safeguards Valves, Revision 41 201-254, 125/250V DC ENGD SFGD Distribution Panel 1F, Revision 21 206-051, Electrical One Line Diagram 250/125V DC sys & 120 AC Vital Instrumentation, Revision 37 208-421, Sh. 3, 480 V Control Center 1C
DOCUMENTS REVIEWED
-ESV-Unit 1C, MSIV MS
71111.21M - DESIGN BASES ASSURANCE INSPECTION (TEAMS)
-V-1C, Revision 4 208-446, Sh. 1, Electrical Elementary Diagram 480V Control Center NR
Calculations
-SR System Tie Valve NR-V-2, Revision 0 208-446, Sh. 2, Electrical Elementary Diagram 480V Control Center NR
C-1101-200-5710-002, Qualified Life Analysis for Limitorque Valves, Revision 0
-SR System Tie Valve NR-V-6, Revision 1 21804-31, Operational Schematic Main Fuel Handling MCC, Revision 3 21804-34, Motor Control Center Wiring Diagram Refueling Machine, Revision 6 21804-37, Interconnection Diagram Refueling Machine, Revision 5 21804-42, Control Console Assembly Refueling Machine, Revision 6 21804-43, Control Console Assembly Refueling Machine, Revision D 302-011, Main Steam Flow Diagram, Revision 26 302-082, Emergency Feedwater Flow Diagram, Revision 25 302-202, Nuclear Services River Water System Flow Diagram, Revision 82 D-84N35833-A2-C024, Train B, Revision 10 D-84N35833-FD-0000, Functional Diagram Elements, Revision 2 D-84N35833-FD-0003, Functional Drawing H.S.P. System Channels II & IV, Generator A Train B EF/FW Control, Revision 8 D-84N35833-FD-0029, Functional Drawing H.S.P. System, OTSG A/EF Pumps EF Initiation  
C-1101-200-5710-005, Effect of Energized Space Heaters on the Qualified Life of Limitorque
- Train B, Revision 5 E-201-063, Sh. 1 and 2, Electrical 480V Control Center 1B Engineered Safeguards Screen House, Revision 29 and 26 E-20 6-011, Main One Line and Relay Diagram, Revision 57 E-206-032, One Line & Relay Diagram  
Operators, Revision 0
- ENGD. SFGDS. Screen HSE, Reactor BLDG. H&V, 480V SWGR, Revision 21 P-4464-472, Rockwell Edward Stop
C-1101-210-E610-011, LPI/BS Pump NPSH Margin Available Following a LBLOCA, Revision 9A
-Check Valve MSIV, 24", Revision 0 Functional, Surveillance and Modification Acceptance Testing 1303-4.16, Emergency Power System, EG
C-1101-700-E510-010, TMI-1 AC Voltage Regulation Study and Appendix 8.1 Load Tables for
-Y-1A, performed 3/06/18 1303-4.16, Emergency Power System, EG
Steady State Operation, Revision 7
-Y-1B, performed 3/13/18 MA-AA-723-300, Diagnostic Testing of Motor Operated Valves, performed 11/11/15 MA-AA-723-301, Periodic Inspection of Limitorque Model SMB/SB/SBD
C-1101-733-5350-003, TMI-1 Class 1E 480V Unit Substation Settings, Revision 5
-000, Through 5 Motor Operated Valves, performed 11/8/05 MA-AA-723-301, Periodic Inspection of Limitorque Model SMB/SB/SBD
C-1101-734-5350-003, TMI-1 Battery Capacity Sizing and Voltage Drop for DC system,
-000, Through 5 Motor Operated Valves, performed 11/13/09
Revision 13
 
C-1101-823-5450-001, TMI-1 LBLOCA EQ Temperature Profile Using GOTHIC Computer Code
7 OP-TM-411-203, MS-V-1A/B/C/and D Full Stroke Test, performed 10/8/17 OP-TM-411-203, MS-V-1A/B/C/and D Full Stroke Test, performed 11/23/13 and 11/22/15 OP-TM-411-203, Stroke Timing MS Isolation Valves (Forced Outage), performed 12/3/16 OP-TM-541-252, Leakage Exam of NR System, performed 10/3/17 Miscellaneous 0420-104239, MU
      (2016), Revision 10
-V-17 Specification Sheet, Revision 3 1603077-02, Attachment 1, Technical Evaluation of Potential Adverse Localized Equipment Environment Identified for Intermediate Building 355' due to MSIVs, Revision 0 161 4182-02, Technical Evaluation, TMI
C-1101-900-5450-005, TMI-1 Containment Response to a SBLOCA, Revision 0
-Cable and Connection Inspection Summary Report, dated 1/9/14 A2298548-01, Technical Evaluation of Visual Cable Inspection of Non EQ Cables and Connection in Adverse Localized Environments, Revision 0 EQ-T1-103, LIMITORQUE SB AND SMB Actuators with Class B H and RH Insulation, Revision 8 ER-AA-410-1000, Air Operated Valve Categorization, Revision 3 MM-128087-157, Specification for Vertical Bus Bar Support Upgrade, Revision 0 Sargent and Lundy TMI NUC/SEC Service River Water Cross Connect Valve NR
C-1101-900-E410-039, MOV Delta P and Basis 07/18/08, Revision 9C
-V-6 Replacement Walkdown Reports, dated 6/09/14, 7/25/14, 1/07/15, 1/22/15 and 2/10/15 SDBD-T1-211, Makeup and Purification, Revision 9 SDBD-T1-212, Decay Heat Removal System, Revision 9 SDBD-T1-411, Main Steam System, Design Basis Document, Revision 7 SI 0-00616, SPEC200, Nuclear (N
C-1101-900-E410-049, Weal Link Calc for TMI GL 89-13 Valves, Revision 7
-2ARPS Series) and Commercial (2ARPS Series) Power Supply Cable Tie Replacement for Heatsink Mounted Cable Harness, dated May 2013 TMI Unit 1 Cycle 19 Core Loading Plan, Revision 0 TMI Unit 1 Cycle 20 Core Loading Plan, Revision 0 TMI Unit 1 Cycles 20
HAGPU-08/98-052.7, Decay Heat Service Cooling River Water Pipe Support RWE-82
-22 BOC SFP A Maps, Revision 0 TMI Unit 1 Refueling 20
Evaluation, Revision 0
-22 Pre Offload SFP A Maps, Revision 0 TMI-14-S-0186, 50.59 Screening, Replacement of Nuclear Services River Water Valve NR
MS-V-0001C (TMI-1), MIDA Calculation, AC Motor-Operated GL 96-05 Globe Valve, Revision 4
-V-6 and Actuator, dated 8/22/14 TMI-15-S-303, 10CFR50.59 Screening ECR 15
NAI-1341-001, TMI GOTHIC LP1 and BS Pump NPSH and Sump Strainer Pressure Drop
-00236 - Screen Wash Pump Motor Circuit Breaker Replacement, Revision 1 TMI-20128, Exelon Power Labs Failure Analysis of a DB
Analysis during Recirculation (2016), Revision 3
-25E Breaker Auxiliary Switch, Revision 1 TM-MISC-02, AOV Program Risk Ranking Input, Revision 2 TM-MISC-03, MOV Risk Ranking, Revision 2 Modifications and Design Changes EC 14-00032, FLEX RCS and SFP Makeup System, Revision 2 EC 593896, Replace Pressurizer Level Transmitter (RC
Corrective Action Documents (*initiated in response to inspection)
-LT-777), with 3000 psig Rated Model, Revision 0 EC 593944, Replace Existing Fuel Bridge Speed Controllers, Revision 0 EC 620347, Modify Opto22 Interface to Encoders of Spent Fuel and Main Fuel Bridges, Revision 0 ECR 14-00155, EG-Y-1A Governor Booster, SS Tubing Improvement, Revision 0 ECR 1 4-00196, Replace NR
AR01323415               AR01652619                AR02592570              AR04075459
-V-6 Valve and Actuator, Revision 3 ECR 15-00236, SW-1-A/B - BK Modification, Revision 2 Operating Procedures 1105-19, Heat Sink Protection System, Revision 30 1107-2A, Emergency Electrical  
AR01494443               AR01658782                AR02653735              AR04111741
- 4kV and 480 Volt, Revision 75 1107-4, Electrical Distribution Panel Listing, Revision 238 8 OP-TM-102-106-1001, Operator Response Time Master List at TMI, Revision 5 OP-TM-211-00, Makeup and Purification System, Revision 36 OP-TM-211-472, Manual Pressurizer Level Control, Revision 4 OP-TM-211-901, Emergency Injection (HPI/LPI), Revision 8 OP-TM-212-288, DH-V-6B and Associated Tests, Revision 10 OP-TM-411-000, Main Steam/OTSG, Revision 21 OP-TM-919-911, FSG-1 High Pressure Makeup Using FX
AR01496437               AR01658795                AR02653884              AR04114893*
-P-1A or FX-P-1B, Revision 6 OP-TM-EOP-005, OTSG Tube Leakage, Revision 9 OP-TM-PPC-L2204, Alarm Response Procedure, Main Steam Isolation MS
AR01499751               AR01675261                AR02718735              AR04115187*
-V 1A (MS-V-1B, MS-V1C, MS-V1D), Revision 1 Procedures 1107-2C, Vital DC Electrical System, Revision 12 1107-4, Electrical Distribution Panel Listing, Revision 238 1302-5.12, Pressurizer Temperature and Level Channel Calibration, Revision 30C 1302-5.2, Surveillance Procedure, RPS High and Low RC Pressure Channels, Revision 38 1302-6.2, RC-LT-777, Pressurizer Level Calibration, Revision 20A 1303-11.39A, HSPS  
AR01532653               AR01692695                AR03829260              AR04115286*
- EFW Auto Initiation, Revision 47 1410-Y-72, Bolt/Nut Torqueing and Sequences, Revision 28 1420-LTQ-1, Limitorque Valve Operator Maintenance, Revision 31 CC-AA-102, Design Input and Configuration Change Impact Screening, Revision 28 CC-AA-103, Configuration Change Control for Permanent Physical Plant Changes, Revision 29 E-21, Thermal Overload Devices Inspection and Testing, Revision 43 E-4, Switchgear, Bus Duct, MCC Transformer, Inspection and Cleaning, Revision 41 E-5.2, Westinghouse 480 Volt DB
AR01570697               AR02313345                AR03829301              AR04119589*
-50 Circuit Breaker Maintenance and Testing, Revision 8 E-5.3, 480 Volt Eaton DB
AR01579471               AR02447062                AR03964783              AR04120057*
-25-LV-VSR Vacuum Starter Maintenance and Testing, Revision 1 E-62.1, Molded Case Circuit Breaker Testing Thermal Magnetic Trip, Revision 13 ER-AA-300, MOV Program Administrative Procedure, Revision 11 ER-AA-302-1009, Final JOG MOV Periodic Verification Program Implementation, Revision 3 ES-010T, TMI-1 Environmental Parameters, Revision 8 MA-AA-723-300, Diagnostic Testing of Motor Operated Valves, Revision 12 MA-AA-723-300-1004, Quiklook Diagnostic Test Equipment/Sensor Guideline, Revision 4 MA-AA-723-301, Periodic Inspection of Limitorque Model SMB/SB/SBD
AR01579591               AR02566171               AR04035763*              AR04120224*
-000 through 5 Motor Operated Valves, Revision 13 MA-AA-723-500, Inspection of Non EQ Cables and Connections for Managing Adverse Localized Environments, Revision 9 MA-MA-716-010-1008, Work Order Work Performance
AR01579593                AR02581866                AR04040576               AR04123991*
, 5 NF-AA-301, Special Nuclear Material and Core Component Movement, Revision 1 NF-AA-310, Special Nuclear Material and Core Component Movement, Revision 8 NF-TM-310-1001, PWR Generation of Fuel Moves using SHUFFLEWORKS Revision 2 NF-TM-600-1000, TMI Spent Fuel Rack Boral/Metamic Coupon Program, Revision 5 Vendor Manuals VM-TM-0029, Limitorque SMB Actuators, Revision 0 VM-TM-0069, Rockwell Edwards-Pressure Seal and Univalve Valves, dated 11/30/17 VM-TM-0191, Fairbanks Morse (Colt Industries) Emergency Diesel Generators, Volumes 1&2, Revision 70 VM-TM-0193, Conax Buffalo Corporation, Electric Conductor Seal Assemblies with Long Body for Pipe Thread Equipment Interface, Revision G VM-TM-0255, EIM Co., Inc. Valve Operators, Revision 5 VM-TM-2962, Vendor Technical Manual, Revision 8 VM-TM-3014, Weir Valves and Controls USA, Instruction Manual for 30 Inch Class 150 TCBV w/ Gear Operator, Revision 2 9 Work Orders C2033049 C2033743 C2033849 R2010207 R2076951 R2078373 R2141555 R2142407 R2154245 R2157073 R2157486 R2188444 R2190519 R2192586 R2230884 R2236081 C2029069 03502097 03503764 04185481 04186464 04190782 04353591 04364504 04367361 04373451 04373780 04373807 04374384 04376201 04382571 04581170 04593610 04598030 04599420 04662196 04682875 04685682 04718509 04744773
AR01579595                AR02582872                AR04041355
AR01603077                AR02586540                AR04047288
Design and Licensing Basis
CY-TM-170-300, Offsite Dose Calculation Manual, Revision 5
EQ-T1-103-04, Environmental Qualification, Limitorque Valve SB and SMB Series Actuators
with Class B, H, and RH Insulation, Revision 8
EQ-T1-118, Rosemount Inc. Pressure Transmitters and Remote Diaphragm Seals 1153,
Revision 13
Exelon Corporate Regulatory Commitment Change Summary Report Commitment 2015-01,
dated 12/15/15
N6100, N6101, N6102, Schulz Electric Motor Rewind, dated 10/18/04
RS-16-207, Response to Generic Letter 2016-01
RS-18-007, Response to Request for Additional Information Regarding Generic Letter 2016-01
Safety Evaluation By The Office of Nuclear Reactor Regulation Related To Holtec International
Report HI-202287 Regarding Use of Metamic in Fuel Pool Applications, dated 6/17/03SE
08-00872, 50.59 Evaluation for SFP Project Rerack (Metamic), Revision 0
TDR-648, TMI Qualification for LBLOCA Environments Methodology and List of Electrical
Components Requiring Environmental Qualification for LBLOCA/HELB Mitigation,
Revision 0
TMI, Unit 1 - Conforming License Amendment to Incorporate the Mitigation Strategies Required
by Section B.5.b of Commission Order EA-02-026, dated 7/18/07
Drawings
10001384-10, Sh. 1 and 2, 30-150 TricentricValve with Limitorque Motor SMB-1/HBC-4,
Revision 3
200525, Sh. 1, Assembly - Booster (Governor), Revision 2
201-069, Sh. 2, 480 V Control Center, 1C, Engineered Safeguards Valves, Revision 41
201-254, 125/250V DC ENGD SFGD Distribution Panel 1F, Revision 21
206-051, Electrical One Line Diagram 250/125V DC sys & 120 AC Vital Instrumentation,
Revision 37
208-421, Sh. 3, 480 V Control Center 1C-ESV-Unit 1C, MSIV MS-V-1C, Revision 4
208-446, Sh. 1, Electrical Elementary Diagram 480V Control Center NR-SR System Tie Valve
NR-V-2, Revision 0
208-446, Sh. 2, Electrical Elementary Diagram 480V Control Center NR-SR System Tie Valve
NR-V-6, Revision 1
21804-31, Operational Schematic Main Fuel Handling MCC, Revision 3
21804-34, Motor Control Center Wiring Diagram Refueling Machine, Revision 6
21804-37, Interconnection Diagram Refueling Machine, Revision 5
21804-42, Control Console Assembly Refueling Machine, Revision 6
21804-43, Control Console Assembly Refueling Machine, Revision D
2-011, Main Steam Flow Diagram, Revision 26
2-082, Emergency Feedwater Flow Diagram, Revision 25
2-202, Nuclear Services River Water System Flow Diagram, Revision 82
D-84N35833-A2-C024, Train B, Revision 10
D-84N35833-FD-0000, Functional Diagram Elements, Revision 2
D-84N35833-FD-0003, Functional Drawing H.
: [[contact::S.P. System Channels II & IV]], Generator A Train B
EF/FW Control, Revision 8
D-84N35833-FD-0029, Functional Drawing H.
: [[contact::S.P. System]], OTSG A/EF Pumps EF Initiation -
Train B, Revision 5
E-201-063, Sh. 1 and 2, Electrical 480V Control Center 1B Engineered Safeguards Screen
House, Revision 29 and 26
E-206-011, Main One Line and Relay Diagram, Revision 57
E-206-032, One Line & Relay Diagram - ENG
: [[contact::D. SFGDS. Screen HSE]], Reactor BLD
: [[contact::G. H&V]],
480V SWGR, Revision 21
P-4464-472, Rockwell Edward Stop-Check Valve MSIV, 24, Revision 0
Functional, Surveillance and Modification Acceptance Testing
1303-4.16, Emergency Power System, EG-Y-1A, performed 3/06/18
1303-4.16, Emergency Power System, EG-Y-1B, performed 3/13/18
MA-AA-723-300, Diagnostic Testing of Motor Operated Valves, performed 11/11/15
MA-AA-723-301, Periodic Inspection of Limitorque Model SMB/SB/SBD-000, Through 5 Motor
Operated Valves, performed 11/8/05
MA-AA-723-301, Periodic Inspection of Limitorque Model SMB/SB/SBD-000, Through 5 Motor
Operated Valves, performed 11/13/09
OP-TM-411-203, MS-V-1A/B/C/and D Full Stroke Test, performed 10/8/17
OP-TM-411-203, MS-V-1A/B/C/and D Full Stroke Test, performed 11/23/13 and 11/22/15
OP-TM-411-203, Stroke Timing MS Isolation Valves (Forced Outage), performed 12/3/16
OP-TM-541-252, Leakage Exam of NR System, performed 10/3/17
Miscellaneous
20-104239, MU-V-17 Specification Sheet, Revision 3
1603077-02, Attachment 1, Technical Evaluation of Potential Adverse Localized Equipment
Environment Identified for Intermediate Building 355 due to MSIVs, Revision 0
1614182-02, Technical Evaluation, TMI-Cable and Connection Inspection Summary Report,
dated 1/9/14
A2298548-01, Technical Evaluation of Visual Cable Inspection of Non EQ Cables and
Connection in Adverse Localized Environments, Revision 0
EQ-T1-103, LIMITORQUE SB AND SMB Actuators with Class B H and RH Insulation,
Revision 8
ER-AA-410-1000, Air Operated Valve Categorization, Revision 3
MM-128087-157, Specification for Vertical Bus Bar Support Upgrade, Revision 0
Sargent and Lundy TMI NUC/SEC Service River Water Cross Connect Valve NR-V-6
Replacement Walkdown Reports, dated 6/09/14, 7/25/14, 1/07/15, 1/22/15 and 2/10/15
SDBD-T1-211, Makeup and Purification, Revision 9
SDBD-T1-212, Decay Heat Removal System, Revision 9
SDBD-T1-411, Main Steam System, Design Basis Document, Revision 7
SI 0-00616, SPEC200, Nuclear (N-2ARPS Series) and Commercial (2ARPS Series) Power
Supply Cable Tie Replacement for Heatsink Mounted Cable Harness, dated May 2013
TMI Unit 1 Cycle 19 Core Loading Plan, Revision 0
TMI Unit 1 Cycle 20 Core Loading Plan, Revision 0
TMI Unit 1 Cycles 20-22 BOC SFP A Maps, Revision 0
TMI Unit 1 Refueling 20-22 Pre Offload SFP A Maps, Revision 0
TMI-14-S-0186, 50.59 Screening, Replacement of Nuclear Services River Water Valve NR-V-6
and Actuator, dated 8/22/14
TMI-15-S-303, 10CFR50.59 Screening ECR 15-00236 - Screen Wash Pump Motor Circuit
Breaker Replacement, Revision 1
TMI-20128, Exelon Power Labs Failure Analysis of a DB-25E Breaker Auxiliary Switch,
Revision 1
TM-MISC-02, AOV Program Risk Ranking Input, Revision 2
TM-MISC-03, MOV Risk Ranking, Revision 2
Modifications and Design Changes
EC 14-00032, FLEX RCS and SFP Makeup System, Revision 2
EC 593896, Replace Pressurizer Level Transmitter (RC-LT-777), with 3000 psig Rated Model,
Revision 0
EC 593944, Replace Existing Fuel Bridge Speed Controllers, Revision 0
EC 620347, Modify Opto22 Interface to Encoders of Spent Fuel and Main Fuel Bridges,
Revision 0
ECR 14-00155, EG-Y-1A Governor Booster, SS Tubing Improvement, Revision 0
ECR 14-00196, Replace NR-V-6 Valve and Actuator, Revision 3
ECR 15-00236, SW-1-A/B - BK Modification, Revision 2
Operating Procedures
1105-19, Heat Sink Protection System, Revision 30
1107-2A, Emergency Electrical - 4kV and 480 Volt, Revision 75
1107-4, Electrical Distribution Panel Listing, Revision 238
OP-TM-102-106-1001, Operator Response Time Master List at TMI, Revision 5
OP-TM-211-00, Makeup and Purification System, Revision 36
OP-TM-211-472, Manual Pressurizer Level Control, Revision 4
OP-TM-211-901, Emergency Injection (HPI/LPI), Revision 8
OP-TM-212-288, DH-V-6B and Associated Tests, Revision 10
OP-TM-411-000, Main Steam/OTSG, Revision 21
OP-TM-919-911, FSG-1 High Pressure Makeup Using FX-P-1A or FX-P-1B, Revision 6
OP-TM-EOP-005, OTSG Tube Leakage, Revision 9
OP-TM-PPC-L2204, Alarm Response Procedure, Main Steam Isolation MS-V1A (MS-V-1B,
MS-V1C, MS-V1D), Revision 1
Procedures
1107-2C, Vital DC Electrical System, Revision 12
1107-4, Electrical Distribution Panel Listing, Revision 238
1302-5.12, Pressurizer Temperature and Level Channel Calibration, Revision 30C
1302-5.2, Surveillance Procedure, RPS High and Low RC Pressure Channels, Revision 38
1302-6.2, RC-LT-777, Pressurizer Level Calibration, Revision 20A
1303-11.39A, HSPS - EFW Auto Initiation, Revision 47
1410-Y-72, Bolt/Nut Torqueing and Sequences, Revision 28
20-LTQ-1, Limitorque Valve Operator Maintenance, Revision 31
CC-AA-102, Design Input and Configuration Change Impact Screening, Revision 28
CC-AA-103, Configuration Change Control for Permanent Physical Plant Changes, Revision 29
E-21, Thermal Overload Devices Inspection and Testing, Revision 43
E-4, Switchgear, Bus Duct, MCC Transformer, Inspection and Cleaning, Revision 41
E-5.2, Westinghouse 480 Volt DB-50 Circuit Breaker Maintenance and Testing, Revision 8
E-5.3, 480 Volt Eaton DB-25-LV-VSR Vacuum Starter Maintenance and Testing, Revision 1
E-62.1, Molded Case Circuit Breaker Testing Thermal Magnetic Trip, Revision 13
ER-AA-300, MOV Program Administrative Procedure, Revision 11
ER-AA-302-1009, Final JOG MOV Periodic Verification Program Implementation, Revision 3
ES-010T, TMI-1 Environmental Parameters, Revision 8
MA-AA-723-300, Diagnostic Testing of Motor Operated Valves, Revision 12
MA-AA-723-300-1004, Quiklook Diagnostic Test Equipment/Sensor Guideline, Revision 4
MA-AA-723-301, Periodic Inspection of Limitorque Model SMB/SB/SBD-000 through 5 Motor
Operated Valves, Revision 13
MA-AA-723-500, Inspection of Non EQ Cables and Connections for Managing Adverse
Localized Environments, Revision 9
MA-MA-716-010-1008, Work Order Work Performance, 5
NF-AA-301, Special Nuclear Material and Core Component Movement, Revision 1
NF-AA-310, Special Nuclear Material and Core Component Movement, Revision 8
NF-TM-310-1001, PWR Generation of Fuel Moves using SHUFFLEWORKS Revision 2
NF-TM-600-1000, TMI Spent Fuel Rack Boral/Metamic Coupon Program, Revision 5
Vendor Manuals
VM-TM-0029, Limitorque SMB Actuators, Revision 0
VM-TM-0069, Rockwell Edwards-Pressure Seal and Univalve Valves, dated 11/30/17
VM-TM-0191, Fairbanks Morse (Colt Industries) Emergency Diesel Generators, Volumes 1&2,
Revision 70
VM-TM-0193, Conax Buffalo Corporation, Electric Conductor Seal Assemblies with Long Body
for Pipe Thread Equipment Interface, Revision G
VM-TM-0255, EIM Co., Inc. Valve Operators, Revision 5
VM-TM-2962, Vendor Technical Manual, Revision 8
VM-TM-3014, Weir Valves and Controls USA, Instruction Manual for 30 Inch Class 150 TCBV
w/ Gear Operator, Revision 2
Work Orders
C2033049   R2154245 C2029069 04367361 04593610
C2033743   R2157073 03502097 04373451 04598030
C2033849   R2157486 03503764 04373780 04599420
R2010207   R2188444 04185481 04373807 04662196
R2076951   R2190519 04186464 04374384 04682875
R2078373   R2192586 04190782 04376201 04685682
R2141555   R2230884 04353591 04382571 04718509
R2142407   R2236081 04364504 04581170 04744773
}}
}}

Latest revision as of 15:47, 2 November 2019

Design Bases Assurance Inspection (Teams) Report 05000289/2018010
ML18122A085
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 05/02/2018
From: Kevin Mangan
Engineering Region 1 Branch 1
To: Bryan Hanson
Exelon Generation Co, Exelon Nuclear
Pindale S
References
IR 2018010
Download: ML18122A085 (11)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION May 2, 2018

SUBJECT:

THREE MILE ISLAND NUCLEAR GENERATING STATION - UNIT 1 DESIGN BASES ASSURANCE INSPECTION (TEAM) REPORT 05000289/2018010

Dear Mr. Hanson:

On March 29, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Three Mile Island, Unit 1. On March 29, 2018, the NRC inspectors discussed the results of this inspection with Mr. Ed Callan, Site Vice President, 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 NRCs Public Document Room in accordance with Title 10 of the Code of Federal Regulations (CFR), Part 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA/

Stephen M. Pindale, Chief Engineering Branch 1 Division of Reactor Safety Docket Number: 50-289 License Number: DPR-50

Enclosure:

Inspection Report 05000289/2018010

Inspection Report

Docket Number: 50-289 License Number: DPR-50 Report Number: 05000289/2018010 Enterprise Identifier: I-2018-010-0038 Licensee: Exelon Generation Company, LLC (Exelon)

Facility: Three Mile Island, Unit 1 (TMI)

Location: Middletown, Pennsylvania Inspection Dates: March 12 through March 29, 2018 Inspectors: K. Mangan, Senior Reactor Inspector, Division of Reactor Safety (DRS), Team Leader J. Brand, Reactor Inspector, DRS S. Elkhiamy, Reactor Inspector, DRS M. Orr, Reactor Inspector, DRS S. Kobylarz, NRC Electrical Contractor R. Waters, NRC Mechanical Contractor Approved By: Stephen M. Pindale, Chief Engineering Branch 1 Division of Reactor Safety Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring Exelons performance at

Three Mile Island, Unit 1 by conducting a design bases assurance inspection 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.

No findings or more-than-minor violations were identified.

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

===71111.21M - Design Bases Assurance Inspection (Teams)

The team evaluated the following components, permanent modifications, and operating experience during the weeks of March 12, 2018, and March 26, 2018.

For the components, the team reviewed the attributes listed in inspection procedure 71111.21M, Appendix A, Component Review Attributes. Specifically, the team evaluated these attributes as per 71111.21M, Appendix B, Component Design Review Considerations and 71111.21M, Appendix C, Component Walkdown Considerations.

Components ===

Main article: IP 71111.21
  • DH-V-6B, B Decay Heat Suction Isolation Valve. The team used Appendix B guidance for Valves and Electrical Loads and conducted a walkdown of the equipment.
  • EED-PNL-1F, F 125 Volt DC Distribution Panel. The team used Appendix B guidance for Electrical Loads and Motor Control Centers and conducted a walkdown of the equipment.
  • AFRCCB, Heat Sink Protection System Transfer Relays. The team used Appendix B guidance for Instrumentation and conducted a walkdown of the equipment.
  • EE-MCC-SH-1B, Motor Control Center 1B. The team used Appendix B guidance for Motor Control Centers and Circuit Breakers and Fuses and conducted a walkdown of the equipment.
  • MU-V-0017, Normal Makeup to Reactor Coolant System Control Valve. The team used Appendix B guidance for Valves and conducted a walkdown of the equipment.

Component, Large Early Release Frequency (1 Sample)

  • MS-V-1C, Main Steam Isolation Motor-Operated Valve. The team used Appendix B guidance for Valves, Cables, and Electrical Loads and conducted a walkdown of the equipment.

Permanent Modifications (6 Samples)

  • Replacing Existing Fuel Bridge Speed Controllers
  • Replace Pressurizer Level Transmitter with 3000 PSIG Rated Model
  • Replace Nuclear River Butterfly Valve and Actuator

Operating Experience (3 Samples)

  • 10 CFR Part 21 Notification - Foxboro Power Supply Potential Failures due to Defective Tie Wraps and Holders, dated 7/5/13
  • 10 CFR Part 21, Potential Defect Involving Failure of Westinghouse DB-25 Breakers, dated 5/2/07

EXIT MEETINGS AND DEBRIEFS

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

  • On March 29, 2018, the team presented the Design Bases Assurance Inspection (Teams)results to Mr. Ed Callan, Site Vice President, and other members of Exelon staff.

DOCUMENTS REVIEWED

71111.21M - DESIGN BASES ASSURANCE INSPECTION (TEAMS)

Calculations

C-1101-200-5710-002, Qualified Life Analysis for Limitorque Valves, Revision 0

C-1101-200-5710-005, Effect of Energized Space Heaters on the Qualified Life of Limitorque

Operators, Revision 0

C-1101-210-E610-011, LPI/BS Pump NPSH Margin Available Following a LBLOCA, Revision 9A

C-1101-700-E510-010, TMI-1 AC Voltage Regulation Study and Appendix 8.1 Load Tables for

Steady State Operation, Revision 7

C-1101-733-5350-003, TMI-1 Class 1E 480V Unit Substation Settings, Revision 5

C-1101-734-5350-003, TMI-1 Battery Capacity Sizing and Voltage Drop for DC system,

Revision 13

C-1101-823-5450-001, TMI-1 LBLOCA EQ Temperature Profile Using GOTHIC Computer Code

(2016), Revision 10

C-1101-900-5450-005, TMI-1 Containment Response to a SBLOCA, Revision 0

C-1101-900-E410-039, MOV Delta P and Basis 07/18/08, Revision 9C

C-1101-900-E410-049, Weal Link Calc for TMI GL 89-13 Valves, Revision 7

HAGPU-08/98-052.7, Decay Heat Service Cooling River Water Pipe Support RWE-82

Evaluation, Revision 0

MS-V-0001C (TMI-1), MIDA Calculation, AC Motor-Operated GL 96-05 Globe Valve, Revision 4

NAI-1341-001, TMI GOTHIC LP1 and BS Pump NPSH and Sump Strainer Pressure Drop

Analysis during Recirculation (2016), Revision 3

Corrective Action Documents (*initiated in response to inspection)

AR01323415 AR01652619 AR02592570 AR04075459

AR01494443 AR01658782 AR02653735 AR04111741

AR01496437 AR01658795 AR02653884 AR04114893*

AR01499751 AR01675261 AR02718735 AR04115187*

AR01532653 AR01692695 AR03829260 AR04115286*

AR01570697 AR02313345 AR03829301 AR04119589*

AR01579471 AR02447062 AR03964783 AR04120057*

AR01579591 AR02566171 AR04035763* AR04120224*

AR01579593 AR02581866 AR04040576 AR04123991*

AR01579595 AR02582872 AR04041355

AR01603077 AR02586540 AR04047288

Design and Licensing Basis

CY-TM-170-300, Offsite Dose Calculation Manual, Revision 5

EQ-T1-103-04, Environmental Qualification, Limitorque Valve SB and SMB Series Actuators

with Class B, H, and RH Insulation, Revision 8

EQ-T1-118, Rosemount Inc. Pressure Transmitters and Remote Diaphragm Seals 1153,

Revision 13

Exelon Corporate Regulatory Commitment Change Summary Report Commitment 2015-01,

dated 12/15/15

N6100, N6101, N6102, Schulz Electric Motor Rewind, dated 10/18/04

RS-16-207, Response to Generic Letter 2016-01

RS-18-007, Response to Request for Additional Information Regarding Generic Letter 2016-01

Safety Evaluation By The Office of Nuclear Reactor Regulation Related To Holtec International

Report HI-202287 Regarding Use of Metamic in Fuel Pool Applications, dated 6/17/03SE

08-00872, 50.59 Evaluation for SFP Project Rerack (Metamic), Revision 0

TDR-648, TMI Qualification for LBLOCA Environments Methodology and List of Electrical

Components Requiring Environmental Qualification for LBLOCA/HELB Mitigation,

Revision 0

TMI, Unit 1 - Conforming License Amendment to Incorporate the Mitigation Strategies Required

by Section B.5.b of Commission Order EA-02-026, dated 7/18/07

Drawings

10001384-10, Sh. 1 and 2,30-150 TricentricValve with Limitorque Motor SMB-1/HBC-4,

Revision 3

200525, Sh. 1, Assembly - Booster (Governor), Revision 2

201-069, Sh. 2, 480 V Control Center, 1C, Engineered Safeguards Valves, Revision 41

201-254, 125/250V DC ENGD SFGD Distribution Panel 1F, Revision 21

206-051, Electrical One Line Diagram 250/125V DC sys & 120 AC Vital Instrumentation,

Revision 37

208-421, Sh. 3, 480 V Control Center 1C-ESV-Unit 1C, MSIV MS-V-1C, Revision 4

208-446, Sh. 1, Electrical Elementary Diagram 480V Control Center NR-SR System Tie Valve

NR-V-2, Revision 0

208-446, Sh. 2, Electrical Elementary Diagram 480V Control Center NR-SR System Tie Valve

NR-V-6, Revision 1

21804-31, Operational Schematic Main Fuel Handling MCC, Revision 3

21804-34, Motor Control Center Wiring Diagram Refueling Machine, Revision 6

21804-37, Interconnection Diagram Refueling Machine, Revision 5

21804-42, Control Console Assembly Refueling Machine, Revision 6

21804-43, Control Console Assembly Refueling Machine, Revision D

2-011, Main Steam Flow Diagram, Revision 26

2-082, Emergency Feedwater Flow Diagram, Revision 25

2-202, Nuclear Services River Water System Flow Diagram, Revision 82

D-84N35833-A2-C024, Train B, Revision 10

D-84N35833-FD-0000, Functional Diagram Elements, Revision 2

D-84N35833-FD-0003, Functional Drawing H.

S.P. System Channels II & IV, Generator A Train B

EF/FW Control, Revision 8

D-84N35833-FD-0029, Functional Drawing H.

S.P. System, OTSG A/EF Pumps EF Initiation -

Train B, Revision 5

E-201-063, Sh. 1 and 2, Electrical 480V Control Center 1B Engineered Safeguards Screen

House, Revision 29 and 26

E-206-011, Main One Line and Relay Diagram, Revision 57

E-206-032, One Line & Relay Diagram - ENG

D. SFGDS. Screen HSE, Reactor BLD
G. H&V,

480V SWGR, Revision 21

P-4464-472, Rockwell Edward Stop-Check Valve MSIV, 24, Revision 0

Functional, Surveillance and Modification Acceptance Testing

1303-4.16, Emergency Power System, EG-Y-1A, performed 3/06/18

1303-4.16, Emergency Power System, EG-Y-1B, performed 3/13/18

MA-AA-723-300, Diagnostic Testing of Motor Operated Valves, performed 11/11/15

MA-AA-723-301, Periodic Inspection of Limitorque Model SMB/SB/SBD-000, Through 5 Motor

Operated Valves, performed 11/8/05

MA-AA-723-301, Periodic Inspection of Limitorque Model SMB/SB/SBD-000, Through 5 Motor

Operated Valves, performed 11/13/09

OP-TM-411-203, MS-V-1A/B/C/and D Full Stroke Test, performed 10/8/17

OP-TM-411-203, MS-V-1A/B/C/and D Full Stroke Test, performed 11/23/13 and 11/22/15

OP-TM-411-203, Stroke Timing MS Isolation Valves (Forced Outage), performed 12/3/16

OP-TM-541-252, Leakage Exam of NR System, performed 10/3/17

Miscellaneous

20-104239, MU-V-17 Specification Sheet, Revision 3

1603077-02, Attachment 1, Technical Evaluation of Potential Adverse Localized Equipment

Environment Identified for Intermediate Building 355 due to MSIVs, Revision 0

1614182-02, Technical Evaluation, TMI-Cable and Connection Inspection Summary Report,

dated 1/9/14

A2298548-01, Technical Evaluation of Visual Cable Inspection of Non EQ Cables and

Connection in Adverse Localized Environments, Revision 0

EQ-T1-103, LIMITORQUE SB AND SMB Actuators with Class B H and RH Insulation,

Revision 8

ER-AA-410-1000, Air Operated Valve Categorization, Revision 3

MM-128087-157, Specification for Vertical Bus Bar Support Upgrade, Revision 0

Sargent and Lundy TMI NUC/SEC Service River Water Cross Connect Valve NR-V-6

Replacement Walkdown Reports, dated 6/09/14, 7/25/14, 1/07/15, 1/22/15 and 2/10/15

SDBD-T1-211, Makeup and Purification, Revision 9

SDBD-T1-212, Decay Heat Removal System, Revision 9

SDBD-T1-411, Main Steam System, Design Basis Document, Revision 7

SI 0-00616, SPEC200, Nuclear (N-2ARPS Series) and Commercial (2ARPS Series) Power

Supply Cable Tie Replacement for Heatsink Mounted Cable Harness, dated May 2013

TMI Unit 1 Cycle 19 Core Loading Plan, Revision 0

TMI Unit 1 Cycle 20 Core Loading Plan, Revision 0

TMI Unit 1 Cycles 20-22 BOC SFP A Maps, Revision 0

TMI Unit 1 Refueling 20-22 Pre Offload SFP A Maps, Revision 0

TMI-14-S-0186, 50.59 Screening, Replacement of Nuclear Services River Water Valve NR-V-6

and Actuator, dated 8/22/14

TMI-15-S-303, 10CFR50.59 Screening ECR 15-00236 - Screen Wash Pump Motor Circuit

Breaker Replacement, Revision 1

TMI-20128, Exelon Power Labs Failure Analysis of a DB-25E Breaker Auxiliary Switch,

Revision 1

TM-MISC-02, AOV Program Risk Ranking Input, Revision 2

TM-MISC-03, MOV Risk Ranking, Revision 2

Modifications and Design Changes

EC 14-00032, FLEX RCS and SFP Makeup System, Revision 2

EC 593896, Replace Pressurizer Level Transmitter (RC-LT-777), with 3000 psig Rated Model,

Revision 0

EC 593944, Replace Existing Fuel Bridge Speed Controllers, Revision 0

EC 620347, Modify Opto22 Interface to Encoders of Spent Fuel and Main Fuel Bridges,

Revision 0

ECR 14-00155, EG-Y-1A Governor Booster, SS Tubing Improvement, Revision 0

ECR 14-00196, Replace NR-V-6 Valve and Actuator, Revision 3

ECR 15-00236, SW-1-A/B - BK Modification, Revision 2

Operating Procedures

1105-19, Heat Sink Protection System, Revision 30

1107-2A, Emergency Electrical - 4kV and 480 Volt, Revision 75

1107-4, Electrical Distribution Panel Listing, Revision 238

OP-TM-102-106-1001, Operator Response Time Master List at TMI, Revision 5

OP-TM-211-00, Makeup and Purification System, Revision 36

OP-TM-211-472, Manual Pressurizer Level Control, Revision 4

OP-TM-211-901, Emergency Injection (HPI/LPI), Revision 8

OP-TM-212-288, DH-V-6B and Associated Tests, Revision 10

OP-TM-411-000, Main Steam/OTSG, Revision 21

OP-TM-919-911, FSG-1 High Pressure Makeup Using FX-P-1A or FX-P-1B, Revision 6

OP-TM-EOP-005, OTSG Tube Leakage, Revision 9

OP-TM-PPC-L2204, Alarm Response Procedure, Main Steam Isolation MS-V1A (MS-V-1B,

MS-V1C, MS-V1D), Revision 1

Procedures

1107-2C, Vital DC Electrical System, Revision 12

1107-4, Electrical Distribution Panel Listing, Revision 238

1302-5.12, Pressurizer Temperature and Level Channel Calibration, Revision 30C

1302-5.2, Surveillance Procedure, RPS High and Low RC Pressure Channels, Revision 38

1302-6.2, RC-LT-777, Pressurizer Level Calibration, Revision 20A

1303-11.39A, HSPS - EFW Auto Initiation, Revision 47

1410-Y-72, Bolt/Nut Torqueing and Sequences, Revision 28

20-LTQ-1, Limitorque Valve Operator Maintenance, Revision 31

CC-AA-102, Design Input and Configuration Change Impact Screening, Revision 28

CC-AA-103, Configuration Change Control for Permanent Physical Plant Changes, Revision 29

E-21, Thermal Overload Devices Inspection and Testing, Revision 43

E-4, Switchgear, Bus Duct, MCC Transformer, Inspection and Cleaning, Revision 41

E-5.2, Westinghouse 480 Volt DB-50 Circuit Breaker Maintenance and Testing, Revision 8

E-5.3, 480 Volt Eaton DB-25-LV-VSR Vacuum Starter Maintenance and Testing, Revision 1

E-62.1, Molded Case Circuit Breaker Testing Thermal Magnetic Trip, Revision 13

ER-AA-300, MOV Program Administrative Procedure, Revision 11

ER-AA-302-1009, Final JOG MOV Periodic Verification Program Implementation, Revision 3

ES-010T, TMI-1 Environmental Parameters, Revision 8

MA-AA-723-300, Diagnostic Testing of Motor Operated Valves, Revision 12

MA-AA-723-300-1004, Quiklook Diagnostic Test Equipment/Sensor Guideline, Revision 4

MA-AA-723-301, Periodic Inspection of Limitorque Model SMB/SB/SBD-000 through 5 Motor

Operated Valves, Revision 13

MA-AA-723-500, Inspection of Non EQ Cables and Connections for Managing Adverse

Localized Environments, Revision 9

MA-MA-716-010-1008, Work Order Work Performance, 5

NF-AA-301, Special Nuclear Material and Core Component Movement, Revision 1

NF-AA-310, Special Nuclear Material and Core Component Movement, Revision 8

NF-TM-310-1001, PWR Generation of Fuel Moves using SHUFFLEWORKS Revision 2

NF-TM-600-1000, TMI Spent Fuel Rack Boral/Metamic Coupon Program, Revision 5

Vendor Manuals

VM-TM-0029, Limitorque SMB Actuators, Revision 0

VM-TM-0069, Rockwell Edwards-Pressure Seal and Univalve Valves, dated 11/30/17

VM-TM-0191, Fairbanks Morse (Colt Industries) Emergency Diesel Generators, Volumes 1&2,

Revision 70

VM-TM-0193, Conax Buffalo Corporation, Electric Conductor Seal Assemblies with Long Body

for Pipe Thread Equipment Interface, Revision G

VM-TM-0255, EIM Co., Inc. Valve Operators, Revision 5

VM-TM-2962, Vendor Technical Manual, Revision 8

VM-TM-3014, Weir Valves and Controls USA, Instruction Manual for 30 Inch Class 150 TCBV

w/ Gear Operator, Revision 2

Work Orders

C2033049 R2154245 C2029069 04367361 04593610

C2033743 R2157073 03502097 04373451 04598030

C2033849 R2157486 03503764 04373780 04599420

R2010207 R2188444 04185481 04373807 04662196

R2076951 R2190519 04186464 04374384 04682875

R2078373 R2192586 04190782 04376201 04685682

R2141555 R2230884 04353591 04382571 04718509

R2142407 R2236081 04364504 04581170 04744773

B. Hanson

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION I

2100 RENAISSANCE BOULEVARD, SUITE 100

KING OF PRUSSIA, PA 19406-2713

May 2, 2018

Mr. Bryan C. Hanson

Senior Vice President, Exelon Generation, LLC

President and Chief Nuclear Officer, Exelon Nuclear

4300 Winfield Road

Warrenville, IL 60555

SUBJECT: THREE MILE ISLAND NUCLEAR GENERATING STATION - UNIT 1

DESIGN BASES ASSURANCE INSPECTION (TEAM) REPORT

05000289/2018010

Dear Mr. Hanson:

On March 29, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection

at Three Mile Island, Unit 1. On March 29, 2018, the NRC inspectors discussed the results of

this inspection with Mr. Ed Callan, Site Vice President, 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 NRCs Public Document

Room in accordance with Title 10 of the Code of Federal Regulations (CFR), Part 2.390,

Public Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA/

Stephen

M. Pindale, Chief

Engineering Branch 1

Division of Reactor Safety

Docket Number: 50-289

License Number: DPR-50

Enclosure:

Inspection Report 05000289/2018010

cc w/encl: Distribution via ListServ

ML18122A085

SUNSI Review Non-Sensitive Publicly Available

Sensitive Non-Publicly Available

OFFICE RI/DRS RI/DRS RI/DRS

NAME KMangan MYoung SPindale

DATE 05/01/18 05/01 /18 05/02/18

U.S. NUCLEAR REGULATORY COMMISSION

Inspection Report

Docket Number: 50-289

License Number: DPR-50

Report Number: 05000289/2018010

Enterprise Identifier: I-2018-010-0038

Licensee: Exelon Generation Company, LLC (Exelon)

Facility: Three Mile Island, Unit 1 (TMI)

Location: Middletown, Pennsylvania

Inspection Dates: March 12 through March 29, 2018

Inspectors:

K. Mangan, Senior Reactor Inspector, Division of Reactor Safety

(DRS), Team Leader

J. Brand, Reactor Inspector, DRS
S. Elkhiamy, Reactor Inspector, DRS
M. Orr, Reactor Inspector, DRS
S. Kobylarz, NRC Electrical Contractor
R. Waters, NRC Mechanical Contractor

Approved By: Stephen

M. Pindale, Chief

Engineering Branch 1

Division of Reactor Safety

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring Exelons performance at

Three Mile Island, Unit 1 by conducting a design bases assurance inspection 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.

No findings or more-than-minor violations were identified.

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

71111.21M - Design Bases Assurance Inspection (Teams)

The team evaluated the following components, permanent modifications, and operating

experience during the weeks of March 12, 2018, and March 26, 2018.

For the components, the team reviewed the attributes listed in inspection procedure 71111.21M,

Appendix A, Component Review Attributes. Specifically, the team evaluated these attributes as

per 71111.21M, Appendix B, Component Design Review Considerations and 71111.21M,

Appendix C, Component Walkdown Considerations.

Components (5 Samples)

  • DH-V-6B, B Decay Heat Suction Isolation Valve. The team used Appendix B guidance for

Valves and Electrical Loads and conducted a walkdown of the equipment.

  • EED-PNL-1F, F 125 Volt DC Distribution Panel. The team used Appendix B guidance for

Electrical Loads and Motor Control Centers and conducted a walkdown of the equipment.

  • AFRCCB, Heat Sink Protection System Transfer Relays. The team used Appendix B

guidance for Instrumentation and conducted a walkdown of the equipment.

  • EE-MCC-SH-1B, Motor Control Center 1B. The team used Appendix B guidance for Motor

Control Centers and Circuit Breakers and Fuses and conducted a walkdown of the

equipment.

Appendix B guidance for Valves and conducted a walkdown of the equipment.

Component, Large Early Release Frequency (1 Sample)

  • MS-V-1C, Main Steam Isolation Motor-Operated Valve. The team used Appendix B

guidance for Valves, Cables, and Electrical Loads and conducted a walkdown of the

equipment.

Permanent Modifications (6 Samples)

  • Replacing Existing Fuel Bridge Speed Controllers
  • Replace Pressurizer Level Transmitter with 3000 PSIG Rated Model
  • Replace Nuclear River Butterfly Valve and Actuator

Operating Experience (3 Samples)

  • 10 CFR Part 21 Notification - Foxboro Power Supply Potential Failures due to Defective

Tie Wraps and Holders, dated 7/5/13

Pools, dated 4/7/16

  • 10 CFR Part 21, Potential Defect Involving Failure of Westinghouse DB-25 Breakers,

dated 5/2/07

EXIT MEETINGS AND DEBRIEFS

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

  • On March 29, 2018, the team presented the Design Bases Assurance Inspection (Teams)

results to Mr. Ed Callan, Site Vice President, and other members of Exelon staff.

DOCUMENTS REVIEWED

71111.21M - DESIGN BASES ASSURANCE INSPECTION (TEAMS)

Calculations

C-1101-200-5710-002, Qualified Life Analysis for Limitorque Valves, Revision 0

C-1101-200-5710-005, Effect of Energized Space Heaters on the Qualified Life of Limitorque

Operators, Revision 0

C-1101-210-E610-011, LPI/BS Pump NPSH Margin Available Following a LBLOCA, Revision 9A

C-1101-700-E510-010, TMI-1 AC Voltage Regulation Study and Appendix 8.1 Load Tables for

Steady State Operation, Revision 7

C-1101-733-5350-003, TMI-1 Class 1E 480V Unit Substation Settings, Revision 5

C-1101-734-5350-003, TMI-1 Battery Capacity Sizing and Voltage Drop for DC system,

Revision 13

C-1101-823-5450-001, TMI-1 LBLOCA EQ Temperature Profile Using GOTHIC Computer Code

(2016), Revision 10

C-1101-900-5450-005, TMI-1 Containment Response to a SBLOCA, Revision 0

C-1101-900-E410-039, MOV Delta P and Basis 07/18/08, Revision 9C

C-1101-900-E410-049, Weal Link Calc for TMI GL 89-13 Valves, Revision 7

HAGPU-08/98-052.7, Decay Heat Service Cooling River Water Pipe Support RWE-82

Evaluation, Revision 0

MS-V-0001C (TMI-1), MIDA Calculation, AC Motor-Operated GL 96-05 Globe Valve, Revision 4

NAI-1341-001, TMI GOTHIC LP1 and BS Pump NPSH and Sump Strainer Pressure Drop

Analysis during Recirculation (2016), Revision 3

Corrective Action Documents (*initiated in response to inspection)

AR01323415 AR01652619 AR02592570 AR04075459

AR01494443 AR01658782 AR02653735 AR04111741

AR01496437 AR01658795 AR02653884 AR04114893*

AR01499751 AR01675261 AR02718735 AR04115187*

AR01532653 AR01692695 AR03829260 AR04115286*

AR01570697 AR02313345 AR03829301 AR04119589*

AR01579471 AR02447062 AR03964783 AR04120057*

AR01579591 AR02566171 AR04035763* AR04120224*

AR01579593 AR02581866 AR04040576 AR04123991*

AR01579595 AR02582872 AR04041355

AR01603077 AR02586540 AR04047288

Design and Licensing Basis

CY-TM-170-300, Offsite Dose Calculation Manual, Revision 5

EQ-T1-103-04, Environmental Qualification, Limitorque Valve SB and SMB Series Actuators

with Class B, H, and RH Insulation, Revision 8

EQ-T1-118, Rosemount Inc. Pressure Transmitters and Remote Diaphragm Seals 1153,

Revision 13

Exelon Corporate Regulatory Commitment Change Summary Report Commitment 2015-01,

dated 12/15/15

N6100, N6101, N6102, Schulz Electric Motor Rewind, dated 10/18/04

RS-16-207, Response to Generic Letter 2016-01

RS-18-007, Response to Request for Additional Information Regarding Generic Letter 2016-01

Safety Evaluation By The Office of Nuclear Reactor Regulation Related To Holtec International

Report HI-202287 Regarding Use of Metamic in Fuel Pool Applications, dated 6/17/03SE

08-00872, 50.59 Evaluation for SFP Project Rerack (Metamic), Revision 0

TDR-648, TMI Qualification for LBLOCA Environments Methodology and List of Electrical

Components Requiring Environmental Qualification for LBLOCA/HELB Mitigation,

Revision 0

TMI, Unit 1 - Conforming License Amendment to Incorporate the Mitigation Strategies Required

by Section B.5.b of Commission Order EA-02-026, dated 7/18/07

Drawings

10001384-10, Sh. 1 and 2,30-150 TricentricValve with Limitorque Motor SMB-1/HBC-4,

Revision 3

200525, Sh. 1, Assembly - Booster (Governor), Revision 2

201-069, Sh. 2, 480 V Control Center, 1C, Engineered Safeguards Valves, Revision 41

201-254, 125/250V DC ENGD SFGD Distribution Panel 1F, Revision 21

206-051, Electrical One Line Diagram 250/125V DC sys & 120 AC Vital Instrumentation,

Revision 37

208-421, Sh. 3, 480 V Control Center 1C-ESV-Unit 1C, MSIV MS-V-1C, Revision 4

208-446, Sh. 1, Electrical Elementary Diagram 480V Control Center NR-SR System Tie Valve

NR-V-2, Revision 0

208-446, Sh. 2, Electrical Elementary Diagram 480V Control Center NR-SR System Tie Valve

NR-V-6, Revision 1

21804-31, Operational Schematic Main Fuel Handling MCC, Revision 3

21804-34, Motor Control Center Wiring Diagram Refueling Machine, Revision 6

21804-37, Interconnection Diagram Refueling Machine, Revision 5

21804-42, Control Console Assembly Refueling Machine, Revision 6

21804-43, Control Console Assembly Refueling Machine, Revision D

2-011, Main Steam Flow Diagram, Revision 26

2-082, Emergency Feedwater Flow Diagram, Revision 25

2-202, Nuclear Services River Water System Flow Diagram, Revision 82

D-84N35833-A2-C024, Train B, Revision 10

D-84N35833-FD-0000, Functional Diagram Elements, Revision 2

D-84N35833-FD-0003, Functional Drawing H.

S.P. System Channels II & IV, Generator A Train B

EF/FW Control, Revision 8

D-84N35833-FD-0029, Functional Drawing H.

S.P. System, OTSG A/EF Pumps EF Initiation -

Train B, Revision 5

E-201-063, Sh. 1 and 2, Electrical 480V Control Center 1B Engineered Safeguards Screen

House, Revision 29 and 26

E-206-011, Main One Line and Relay Diagram, Revision 57

E-206-032, One Line & Relay Diagram - ENG

D. SFGDS. Screen HSE, Reactor BLD
G. H&V,

480V SWGR, Revision 21

P-4464-472, Rockwell Edward Stop-Check Valve MSIV, 24, Revision 0

Functional, Surveillance and Modification Acceptance Testing

1303-4.16, Emergency Power System, EG-Y-1A, performed 3/06/18

1303-4.16, Emergency Power System, EG-Y-1B, performed 3/13/18

MA-AA-723-300, Diagnostic Testing of Motor Operated Valves, performed 11/11/15

MA-AA-723-301, Periodic Inspection of Limitorque Model SMB/SB/SBD-000, Through 5 Motor

Operated Valves, performed 11/8/05

MA-AA-723-301, Periodic Inspection of Limitorque Model SMB/SB/SBD-000, Through 5 Motor

Operated Valves, performed 11/13/09

OP-TM-411-203, MS-V-1A/B/C/and D Full Stroke Test, performed 10/8/17

OP-TM-411-203, MS-V-1A/B/C/and D Full Stroke Test, performed 11/23/13 and 11/22/15

OP-TM-411-203, Stroke Timing MS Isolation Valves (Forced Outage), performed 12/3/16

OP-TM-541-252, Leakage Exam of NR System, performed 10/3/17

Miscellaneous

20-104239, MU-V-17 Specification Sheet, Revision 3

1603077-02, Attachment 1, Technical Evaluation of Potential Adverse Localized Equipment

Environment Identified for Intermediate Building 355 due to MSIVs, Revision 0

1614182-02, Technical Evaluation, TMI-Cable and Connection Inspection Summary Report,

dated 1/9/14

A2298548-01, Technical Evaluation of Visual Cable Inspection of Non EQ Cables and

Connection in Adverse Localized Environments, Revision 0

EQ-T1-103, LIMITORQUE SB AND SMB Actuators with Class B H and RH Insulation,

Revision 8

ER-AA-410-1000, Air Operated Valve Categorization, Revision 3

MM-128087-157, Specification for Vertical Bus Bar Support Upgrade, Revision 0

Sargent and Lundy TMI NUC/SEC Service River Water Cross Connect Valve NR-V-6

Replacement Walkdown Reports, dated 6/09/14, 7/25/14, 1/07/15, 1/22/15 and 2/10/15

SDBD-T1-211, Makeup and Purification, Revision 9

SDBD-T1-212, Decay Heat Removal System, Revision 9

SDBD-T1-411, Main Steam System, Design Basis Document, Revision 7

SI 0-00616, SPEC200, Nuclear (N-2ARPS Series) and Commercial (2ARPS Series) Power

Supply Cable Tie Replacement for Heatsink Mounted Cable Harness, dated May 2013

TMI Unit 1 Cycle 19 Core Loading Plan, Revision 0

TMI Unit 1 Cycle 20 Core Loading Plan, Revision 0

TMI Unit 1 Cycles 20-22 BOC SFP A Maps, Revision 0

TMI Unit 1 Refueling 20-22 Pre Offload SFP A Maps, Revision 0

TMI-14-S-0186, 50.59 Screening, Replacement of Nuclear Services River Water Valve NR-V-6

and Actuator, dated 8/22/14

TMI-15-S-303, 10CFR50.59 Screening ECR 15-00236 - Screen Wash Pump Motor Circuit

Breaker Replacement, Revision 1

TMI-20128, Exelon Power Labs Failure Analysis of a DB-25E Breaker Auxiliary Switch,

Revision 1

TM-MISC-02, AOV Program Risk Ranking Input, Revision 2

TM-MISC-03, MOV Risk Ranking, Revision 2

Modifications and Design Changes

EC 14-00032, FLEX RCS and SFP Makeup System, Revision 2

EC 593896, Replace Pressurizer Level Transmitter (RC-LT-777), with 3000 psig Rated Model,

Revision 0

EC 593944, Replace Existing Fuel Bridge Speed Controllers, Revision 0

EC 620347, Modify Opto22 Interface to Encoders of Spent Fuel and Main Fuel Bridges,

Revision 0

ECR 14-00155, EG-Y-1A Governor Booster, SS Tubing Improvement, Revision 0

ECR 14-00196, Replace NR-V-6 Valve and Actuator, Revision 3

ECR 15-00236, SW-1-A/B - BK Modification, Revision 2

Operating Procedures

1105-19, Heat Sink Protection System, Revision 30

1107-2A, Emergency Electrical - 4kV and 480 Volt, Revision 75

1107-4, Electrical Distribution Panel Listing, Revision 238

OP-TM-102-106-1001, Operator Response Time Master List at TMI, Revision 5

OP-TM-211-00, Makeup and Purification System, Revision 36

OP-TM-211-472, Manual Pressurizer Level Control, Revision 4

OP-TM-211-901, Emergency Injection (HPI/LPI), Revision 8

OP-TM-212-288, DH-V-6B and Associated Tests, Revision 10

OP-TM-411-000, Main Steam/OTSG, Revision 21

OP-TM-919-911, FSG-1 High Pressure Makeup Using FX-P-1A or FX-P-1B, Revision 6

OP-TM-EOP-005, OTSG Tube Leakage, Revision 9

OP-TM-PPC-L2204, Alarm Response Procedure, Main Steam Isolation MS-V1A (MS-V-1B,

MS-V1C, MS-V1D), Revision 1

Procedures

1107-2C, Vital DC Electrical System, Revision 12

1107-4, Electrical Distribution Panel Listing, Revision 238

1302-5.12, Pressurizer Temperature and Level Channel Calibration, Revision 30C

1302-5.2, Surveillance Procedure, RPS High and Low RC Pressure Channels, Revision 38

1302-6.2, RC-LT-777, Pressurizer Level Calibration, Revision 20A

1303-11.39A, HSPS - EFW Auto Initiation, Revision 47

1410-Y-72, Bolt/Nut Torqueing and Sequences, Revision 28

20-LTQ-1, Limitorque Valve Operator Maintenance, Revision 31

CC-AA-102, Design Input and Configuration Change Impact Screening, Revision 28

CC-AA-103, Configuration Change Control for Permanent Physical Plant Changes, Revision 29

E-21, Thermal Overload Devices Inspection and Testing, Revision 43

E-4, Switchgear, Bus Duct, MCC Transformer, Inspection and Cleaning, Revision 41

E-5.2, Westinghouse 480 Volt DB-50 Circuit Breaker Maintenance and Testing, Revision 8

E-5.3, 480 Volt Eaton DB-25-LV-VSR Vacuum Starter Maintenance and Testing, Revision 1

E-62.1, Molded Case Circuit Breaker Testing Thermal Magnetic Trip, Revision 13

ER-AA-300, MOV Program Administrative Procedure, Revision 11

ER-AA-302-1009, Final JOG MOV Periodic Verification Program Implementation, Revision 3

ES-010T, TMI-1 Environmental Parameters, Revision 8

MA-AA-723-300, Diagnostic Testing of Motor Operated Valves, Revision 12

MA-AA-723-300-1004, Quiklook Diagnostic Test Equipment/Sensor Guideline, Revision 4

MA-AA-723-301, Periodic Inspection of Limitorque Model SMB/SB/SBD-000 through 5 Motor

Operated Valves, Revision 13

MA-AA-723-500, Inspection of Non EQ Cables and Connections for Managing Adverse

Localized Environments, Revision 9

MA-MA-716-010-1008, Work Order Work Performance, 5

NF-AA-301, Special Nuclear Material and Core Component Movement, Revision 1

NF-AA-310, Special Nuclear Material and Core Component Movement, Revision 8

NF-TM-310-1001, PWR Generation of Fuel Moves using SHUFFLEWORKS Revision 2

NF-TM-600-1000, TMI Spent Fuel Rack Boral/Metamic Coupon Program, Revision 5

Vendor Manuals

VM-TM-0029, Limitorque SMB Actuators, Revision 0

VM-TM-0069, Rockwell Edwards-Pressure Seal and Univalve Valves, dated 11/30/17

VM-TM-0191, Fairbanks Morse (Colt Industries) Emergency Diesel Generators, Volumes 1&2,

Revision 70

VM-TM-0193, Conax Buffalo Corporation, Electric Conductor Seal Assemblies with Long Body

for Pipe Thread Equipment Interface, Revision G

VM-TM-0255, EIM Co., Inc. Valve Operators, Revision 5

VM-TM-2962, Vendor Technical Manual, Revision 8

VM-TM-3014, Weir Valves and Controls USA, Instruction Manual for 30 Inch Class 150 TCBV

w/ Gear Operator, Revision 2

Work Orders

C2033049 R2154245 C2029069 04367361 04593610

C2033743 R2157073 03502097 04373451 04598030

C2033849 R2157486 03503764 04373780 04599420

R2010207 R2188444 04185481 04373807 04662196

R2076951 R2190519 04186464 04374384 04682875

R2078373 R2192586 04190782 04376201 04685682

R2141555 R2230884 04353591 04382571 04718509

R2142407 R2236081 04364504 04581170 04744773

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