IR 05000289/2018010: Difference between revisions
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| number = ML18122A085 | | number = ML18122A085 | ||
| issue date = 05/02/2018 | | issue date = 05/02/2018 | ||
| title = | | title = Design Bases Assurance Inspection (Teams) Report 05000289/2018010 | ||
| author name = Mangan K | | author name = Mangan K | ||
| author affiliation = NRC/RGN-I/DRS/EB1 | | author affiliation = NRC/RGN-I/DRS/EB1 | ||
| addressee name = Hanson B | | 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 | | 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: | {{#Wiki_filter: UNITED STATES NUCLEAR REGULATORY COMMISSION May 2, 2018 | ||
SUBJECT: THREE MILE ISLAND NUCLEAR GENERATING STATION | ==SUBJECT:== | ||
- UNIT 1 | THREE MILE ISLAND NUCLEAR GENERATING STATION - UNIT 1 DESIGN BASES ASSURANCE INSPECTION (TEAM) REPORT 05000289/2018010 | ||
==Dear Mr. Hanson:== | ==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 | The NRC inspectors did not identify any findings or more-than-minor violations. | ||
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 | Inspection Report 05000289/2018010 | ||
==Inspection Report== | |||
I- | 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 | |||
=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= | |||
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 === | |||
{{IP sample|IP=IP 71111.21|count=5}} | |||
- | * 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)=== | |||
-V- | * 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)=== | |||
- | * 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 - 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 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 | |||
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 | |||
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 | |||
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, | 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. | performance and compliance with Commission rules and regulations, license conditions, site | ||
procedures, and standards. | |||
REACTOR SAFETY | |||
EED-PNL-1F, | 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, | |||
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 | 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. | |||
- 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 | * 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 ( | 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. | |||
-13 Valves, Revision 7 HAGPU-08/98-052.7, Decay Heat Service Cooling River Water Pipe Support | 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 | Permanent Modifications (6 Samples) | ||
AR04040576 AR04041355 AR04047288 | * 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) | |||
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 | |||
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 | 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 | 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 | |||
-Check Valve MSIV, 24 | 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 | |||
(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 | 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 | 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 | 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* | ||
- | AR01532653 AR01692695 AR03829260 AR04115286* | ||
- EFW Auto Initiation, Revision 47 1410-Y-72, Bolt/Nut Torqueing and Sequences, Revision 28 | 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 | 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
ML18122A085 | |
Person / Time | |
---|---|
Site: | Three Mile Island ![]() |
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) | |
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 ===
- 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)
- 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 - 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 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
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
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
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
- S. Elkhiamy, 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.
- 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)
- 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 - 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 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
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