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Text

Design Bases Assurance Inspection (Teams) Report 05000289/2018010
	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)
	v • d • e

B.HansonUNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 2100 RENAISSANCE BOULEVARD, SUITE 100 KING OF PRUSSIA, PA 19406-2713 May 2, 2018 Mr. Bryan Senior Vice President, Exelon Generation, LLC President and Chief Nuclear Officer, Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 SUBJECT: THREE MILE ISLAND NUCLEAR GENERATING STATION

- UNIT 1 DE SIGN BASES ASSURANCE INSPECTION (TEAM) REPORT 05000289/2018010

Dear Mr. Hanson:

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

The NRC inspectors did not identify any finding s or more-than-minor violation s. This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and the NRC

's Public Document Room in accordance with Title 10 of the Code of Federal Regulations (CFR), Part 2.390, "Public Inspections, Exemptions, Requests for Withholding."

Sincerely,

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

Enclosure:

Inspection Report 05000289/2018010

Inspection Report

Docket Number: 50-289 License Number: DPR-50 Report Number: 05000289/2018010 Enterprise Identifier:

I-20 18-010-0038 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

2

SUMMARY

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

Exelon's performance at Three Mile Island, Unit 1 by conducting a design bases assurance inspection in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRC's program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.

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

3

INSPECTION SCOPE

S This inspection w as conducted using the appropriate portions of the inspection procedure in effect at the beginning of the inspection unless otherwise noted. Currently approved inspection procedures with their attached revision histories are located on the public website at http://www.nrc.gov/reading

-rm/doc-collections/insp

-manual/inspection

-procedure/index.html. Samples were declared complete when the inspection procedure requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter 2515, "Light-Water Reactor Inspection Program

- Operations Phase."

The team reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.

REACTOR SAFETY

71111.21 M - Design Bas e s Assurance Inspection (Teams) The team evaluated the following components, permanent modifications, and operating experience during the weeks of March 12, 2018, and March 26, 2018. For the components, the team reviewed the attributes listed in inspection procedure 71111.21M, Appendix A, Component Review Attributes. Specifically, the team evaluated these attributes as per 71111.21M, Appendix B, Component Design Review Considerations and 71111.21M, Appendix C, Component Walkdown Considerations

. Component s (5 Sample s) DH-V-6B, 'B' Decay Heat Suction Isolation Valve. The team used Appendix B guidance for Valves and Electric al Loads and conducted a walkdown of the equipment.

EED-PNL-1F, 'F' 125 Volt DC Distribution Panel. The team used Appendix B guidance for Electrical Loads and Motor Control Centers and conducted a walkdown of the equipment.

AFRCC B, Heat Sink Protection System Transfer Relays. The team used Appendix B guidance for Instrumentation and conducted a walkdown of the equipment.

EE-MCC-SH-1B, Motor Control Center 1B. The team used Appendix B guidance for Motor Control Centers and Circuit Breakers and Fuses and conducted a walkdown of the equipment.

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

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 Electric al Loads and conducted a walkdown of the equipment.

Permanent Modification s (6 Samples) Service Water P-1A/B Breaker Modification FLEX Reactor Coolant System and Spent Fuel Pool Makeup System Emergency Diesel Generator B Governor Tubing Improvement Replacing Existing Fuel Bridge Speed Controllers Replace Pressurizer Level Transmitter with 3000 PSIG Rated Model Replace Nuclear River Butterfly Valve and Actuator Operating Experience (3 Samples) 10 CFR Part 21 Notification

- Foxboro Power Supply Potential Failures due to Defective Tie Wraps and Holders, dated 7/5/13 NRC Generic Letter 2016-01, Monitoring of Neutron

-Absorbing Materials in the Spent Fuel Pools, dated 4/7/16 10 CFR Part 21, Potential Defect Involving Failure of Westinghouse DB

-25 Breakers , dated 5/2/07

EXIT MEETING S AND DEBRIEFS

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

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

DOCUMENTS REVIEWED

71111.21 M - DESIGN BASES ASSURANCE INSPECTION (TEAM

S) Calculations

C-1101-200-5710-002, Qualified Life Analysis for Limitorque Valves, Revision 0 C-1101-200-5710-005, Effect of Energized Space Heaters on the Qualified Life of Limitorque Operators, Revision 0 C-1101-210-E610-011, LPI/BS Pump NPSH Margin Available Following a LBLOCA, Revision 9A C-1101-700-E510-010, TMI-1 AC Voltage Regulation Study and Appendix 8.1 Load Tables for Steady State Operation, Revision 7 C-1101-733-5350-003, TMI-1 Class 1E 480V Unit Substation Settings, Revision 5 C-1101-734-5350-003, TMI-1 Battery Capacity Sizing and Voltage Drop for DC system, Revision 13 C-1101-823-5450-001, TMI-1 LBLOCA EQ Temperature Profile Using GOTHIC Computer Code (2016), Revision 10 C-1101-900-5450-005, TMI-1 Containment Response to a SBLOCA, Revision 0 C-1101-900-E410-039, MOV Delta P and Basis 07/18/08, Revision 9C C-1101-900-E410-049, Weal Link Calc for TMI GL 89

-13 Valves, Revision 7 HAGPU-08/98-052.7, Decay Heat Service Cooling River Water Pipe Support R

WE-82 Evaluation, Revision 0 MS-V-0001C (TMI

-1), MIDA Calculation, AC Motor

-Operated GL 96

-05 Globe Valve, Revision 4 NAI-1341-001, TMI GOTHIC LP1 and BS Pump NPSH and Sump Strainer Pressure Drop Analysis during Recirculation (2016), Revision 3 Corrective

Action Documents (*initiated in response to inspection)

AR01323415

AR01494443

AR01496437

AR01499751

AR01532653

AR01570697

AR01579471

AR01579591

AR01579593

AR01579595

AR01603077

AR01652619

AR01658782

AR01658795

AR01675261

AR01692695

AR02313345

AR02447062

AR02566171

AR02581866

AR02582872

AR02586540

AR02592570

AR02653735

AR02653884

AR02718735

AR03829260

AR03829301

AR03964783

AR04035763*

AR04040576

AR04041355

AR04047288

AR04075459

AR04111741

AR04114893*

AR04115187*

AR04115286*

AR04119589*

AR04120057*

AR04120224*

AR04123991*

Design and Licensing Basis

CY-TM-170-300, Offsite Dose Calculation Manual, Revision 5 EQ-T1-103-04, Environmental Qualification, Limitorque Valve SB and SMB Series Actuators with Class B, H, and RH Insulation, Revision 8 EQ-T1-118, Rosemount Inc. Pressure Transmitters and Remote Diaphragm Seals 1153, Revision 13 Exelon Corporate Regulatory Commitment Change Summary Report Commitment 2015

-01, dated 12/15/15

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

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 16200525, 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 302-011, Main Steam Flow Diagram, Revision 26 302-082, Emergency Feedwater Flow Diagram, Revision 25 302-202, Nuclear Services River Water System Flow Diagram, Revision 82 D-84N35833-A2-C024, Train B, Revision 10 D-84N35833-FD-0000, Functional Diagram Elements, Revision 2 D-84N35833-FD-0003, Functional Drawing H.

S.P. System Channels II & IV, Generator A Train B EF/FW Control, Revision 8 D-84N35833-FD-0029, Functional Drawing H.

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

- Train B, Revision 5 E-201-063, Sh. 1 and 2, Electrical 480V Control Center 1B Engineered Safeguards Screen House, Revision 29 and 26 E-20 6-011, Main One Line and Relay Diagram, Revision 57 E-206-032, One Line & Relay Diagram

- ENG

D. SFGDS. Screen HSE, Reactor BLD

G. H&V, 480V SWGR, Revision 21 P-4464-472, Rockwell Edward Stop

-Check Valve MSIV, 24", Revision 0 Functional, Surveillance and Modification Acceptance Testing

1303-4.16, Emergency Power System, EG

-Y-1A, performed 3/06/18

1303-4.16, Emergency Power System, EG

-Y-1B, performed 3/13/18

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

MA-AA-723-301, Periodic Inspection of Limitorque Model SMB/SB/SBD

-000, Through 5 Motor Operated Valves, performed 11/8/05

MA-AA-723-301, Periodic Inspection of Limitorque Model SMB/SB/SBD

-000, Through 5 Motor Operated Valves, performed 11/13/09

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

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

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

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

Miscellaneous

20-104239, MU

-V-17 Specification Sheet, Revision 3 1603077-02, Attachment 1, Technical Evaluation of Potential Adverse Localized Equipment Environment Identified for Intermediate Building 355' due to MSIVs, Revision 0 161 4182-02, 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 1 4-00196, Replace NR

-V-6 Valve and Actuator, Revision 3 ECR 15-00236, SW-1-A/B - BK Modification, Revision 2 Operating Procedures

1105-19, Heat Sink Protection System, Revision 30 1107-2A, Emergency Electrical

- 4kV and 480 Volt, Revision 75 1107-4, Electrical Distribution Panel Listing, Revision 238

OP-TM-102-106-1001, Operator Response Time Master List at TMI, Revision 5 OP-TM-211-00, Makeup and Purification System, Revision 36 OP-TM-211-472, Manual Pressurizer Level Control, Revision 4 OP-TM-211-901, Emergency Injection (HPI/LPI), Revision 8 OP-TM-212-288, DH-V-6B and Associated Tests, Revision 10 OP-TM-411-000, Main Steam/OTSG, Revision 21 OP-TM-919-911, FSG-1 High Pressure Makeup Using FX

-P-1A or FX-P-1B, Revision 6 OP-TM-EOP-005, OTSG Tube Leakage, Revision 9 OP-TM-PPC-L2204, Alarm Response Procedure, Main Steam Isolation MS

-V 1A (MS-V-1B, MS-V1C, MS-V1D), Revision 1 Procedures

1107-2C, Vital DC Electrical System, Revision 12 1107-4, Electrical Distribution Panel Listing, Revision 238 1302-5.12, Pressurizer Temperature and Level Channel Calibration, Revision 30C 1302-5.2, Surveillance Procedure, RPS High and Low RC Pressure Channels, Revision 38 1302-6.2, RC-LT-777, Pressurizer Level Calibration, Revision 20A 1303-11.39A, HSPS

- EFW Auto Initiation, Revision 47 1410-Y-72, Bolt/Nut Torqueing and Sequences, Revision 28 1420-LTQ-1, Limitorque Valve Operator Maintenance, Revision 31 CC-AA-102, Design Input and Configuration Change Impact Screening, Revision 28 CC-AA-103, Configuration Change Control for Permanent Physical Plant Changes, Revision 29 E-21, Thermal Overload Devices Inspection and Testing, Revision 43 E-4, Switchgear, Bus Duct, MCC Transformer, Inspection and Cleaning, Revision 41 E-5.2, Westinghouse 480 Volt DB

-50 Circuit Breaker Maintenance and Testing, Revision 8 E-5.3, 480 Volt Eaton DB

-25-LV-VSR Vacuum Starter Maintenance and Testing, Revision 1 E-62.1, Molded Case Circuit Breaker Testing Thermal Magnetic Trip, Revision 13 ER-AA-300, MOV Program

Administrative Procedure, Revision 11 ER-AA-302-1009, Final JOG MOV Periodic Verification Program Implementation, Revision 3 ES-010T, TMI-1 Environmental Parameters, Revision 8 MA-AA-723-300, Diagnostic Testing of Motor Operated Valves, Revision 12 MA-AA-723-300-1004, Quiklook Diagnostic Test Equipment/Sensor Guideline, Revision 4 MA-AA-723-301, Periodic Inspection of Limitorque Model SMB/SB/SBD

-000 through 5 Motor Operated Valves, Revision 13 MA-AA-723-500, Inspection of Non EQ Cables and Connections for Managing Adverse Localized Environments, Revision 9 MA-MA-716-010-1008, Work Order Work Performance

, 5 NF-AA-301, Special Nuclear Material and Core Component Movement, Revision 1 NF-AA-310, Special Nuclear Material and Core Component Movement, Revision 8 NF-TM-310-1001, PWR Generation of Fuel Moves using SHUFFLEWORKS Revision 2 NF-TM-600-1000, TMI Spent Fuel Rack Boral/Metamic Coupon Program, Revision 5 Vendor Manuals

VM-TM-0029, Limitorque SMB Actuators, Revision 0 VM-TM-0069, Rockwell Edwards-Pressure Seal and Univalve Valves, dated 11/30/17

VM-TM-0191, Fairbanks Morse (Colt Industries) Emergency Diesel Generators, Volumes 1&2, Revision 70 VM-TM-0193, Conax Buffalo Corporation, Electric Conductor Seal Assemblies with Long Body for Pipe Thread Equipment Interface, Revision G VM-TM-0255, EIM Co., Inc. Valve Operators, Revision 5 VM-TM-2962, Vendor Technical Manual, Revision 8 VM-TM-3014, Weir Valves and Controls USA, Instruction Manual for 30 Inch Class 150 TCBV w/ Gear Operator, Revision 2

Work Orders

C2033049 C2033743 C2033849 R2010207 R2076951 R2078373 R2141555 R2142407 R2154245 R2157073 R2157486 R2188444 R2190519 R2192586 R2230884 R2236081 C2029069 03502097 03503764 04185481 04186464 04190782 04353591 04364504 04367361 04373451 04373780 04373807 04374384 04376201 04382571 04581170 04593610 04598030 04599420 04662196 04682875 04685682 04718509 04744773

B.HansonUNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION I 2100 RENAISSANCE BOULEVARD, SUITE 100

KING OF PRUSSIA, PA 19406

-2713 May 2, 2018

Mr. Bryan 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 DE SIGN BASES ASSURANCE INSPECTION

(TEAM) REPORT 05000289/2018010

Dear Mr. Hanson:

O n March 29, 2018, the

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

The NRC inspectors did not identify any finding

s or more-than-minor violation s. This letter, its enclosure, and your response (if any) will be made

available for public inspection and copying at http://www.nrc.gov/reading

-rm/adams.html

and the NRC

's Public Document Room in accordance with Title 10 of the Code of Federal Regulations

(CFR), Part 2.390, "Public Inspections, Exemptions, Requests for Withholding."

Sincerely, /RA/ Stephen

M. Pindale, Chief Engineering Branch 1 Division of Reactor Safety Docket Number: 50-289 License Number: DPR-50 Enclosure: Inspection Report 05000289/2018010

cc w/encl: Distribution via ListServ

ML18122A085

SUNSI ReviewNon-SensitiveSensitivePublicly AvailableNon-Publicly AvailableOFFICE RI/DRS RI/DRS RI/DRS NAME KMangan MYoung SPindale DATE 05/01/18 05/01 /18 05/02/18

Enclosure U.S. NUCLEAR REGULATORY COMMISSION

Inspection Report

Docket Number: 50-289 License Number: DPR-50 Report Number: 05000289/2018010

Enterprise Identifier:

I-20 18-010-0038 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

Exelon's performance at Three Mile Island, Unit 1

by conducting a design bases assurance inspection

in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRC's program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html

for more information.

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

INSPECTION SCOPE

S This inspection w

as conducted using the appropriate portions of the inspection procedure in effect at the beginning of the inspection unless otherwise noted. Currently approved inspection procedures

with their attached revision histories are located on the public website at http://www.nrc.gov/reading

-rm/doc-collections/insp

-manual/inspection

-procedure/index.html. Samples were declared complete when the inspection procedure

requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter 2515, "Light-Water Reactor Inspection Program

- Operations Phase."

The team reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.

REACTOR SAFETY

71111.21 M - Design Bas e s Assurance Inspection

(Teams) The team evaluated the following components, permanent modifications, and operating experience during the weeks of March 12, 2018, and March

26, 2018. For the components, the team reviewed

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

and 71111.21M, Appendix C, Component Walkdown Considerations

. Component s (5 Sample s) DH-V-6B, 'B' Decay Heat Suction Isolation Valve. The team used Appendix B guidance for Valves and Electric

al Loads and conducted a walkdown of the equipment.

EED-PNL-1F, 'F' 125 Volt DC Distribution Panel. The team used Appendix B guidance for Electrical Loads and Motor Control Centers and conducted a walkdown of the equipment.

AFRCC B, Heat Sink Protection System Transfer Relays. The team used Appendix B guidance for Instrumentation and conducted a walkdown of the equipment.

EE-MCC-SH-1B, Motor Control Center 1B. The team used Appendix B guidance for Motor Control Centers and Circuit Breakers and Fuses and conducted a walkdown of the equipment.

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

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 Electric

al Loads and conducted a walkdown of the equipment.

Permanent Modification

s (6 Samples) Service Water

P-1A/B Breaker Modification

FLEX Reactor Coolant System and

Spent Fuel Pool

Makeup System

Emergency Diesel Generator

B Governor Tubing Improvement

Replacing Existing Fuel Bridge Speed Controllers

Replace Pressurizer Level Transmitter

with 3000 PSIG Rated Model

Replace Nuclear River Butterfly Valve

and Actuator

Operating Experience

(3 Samples) 10 CFR Part 21 Notification

- 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 MEETING S AND DEBRIEFS

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

On March 29, 2018, the team presented the Design Bases Assurance Inspection (Team

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