IR 05000289/2018010
| ML18122A085 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| 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
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:
Report Number:
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===
- 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)
AR01494443
AR01499751
AR01570697
AR01579591
AR01579595
AR01652619
AR01658795
AR01692695
AR02447062
AR02581866
AR02586540
AR02653735
AR02718735
AR03829301
AR04035763*
AR04041355
AR04075459
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
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
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. 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
Sensitive
Publicly Available
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:
Report Number:
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)
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
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)
AR01494443
AR01499751
AR01570697
AR01579591
AR01579595
AR01652619
AR01658795
AR01692695
AR02447062
AR02581866
AR02586540
AR02653735
AR02718735
AR03829301
AR04035763*
AR04041355
AR04075459
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
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
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