Text

May 1, 2017

Mr. Paul Fessler, Senior VP and Chief Nuclear Officer DTE Energy Company Fermi 2 - 210 NOC 6400 North Dixie Highway Newport, MI 48166

SUBJECT: FERMI POWER PLANT, UNIT 2-NRC INTEGRATED INSPECTION REPORT 05000341/2017001

Dear Mr. Fessler:

On March 31, 2017, the U.S. Nuclear Regulatory Commission (NRC) completed an integrated inspection at your Fermi Power Plant, Unit 2 (Fermi 2). On April 11, 2017, the NRC inspectors discussed the results of this inspection with Mr. M. Caragher and other members of your staff. The inspectors documented the results of this inspection in the enclosed inspection report. The NRC inspectors documented two findings of very low safety significance (Green) in this report. Each of these findings involved violations of NRC requirements. In addition, one licensee-identified violation was documented in this report. The NRC is treating each of these violations as Non-Cited Violations consistent with Section 2.3.2.a of the NRC Enforcement Policy. If you contest the violations or significance of the Non-Cited Violations, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001, with copies to: (1) the Regional Administrator, Region III; (2) the Director, Office of Enforcement, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; and (3) the NRC Resident Inspector at the Fermi 2 Power Plant. In addition, if you disagree with the cross-cutting aspect assignment to any finding in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the Regional Administrator, Region III, and the NRC Resident Inspector at the Fermi 2 Power Plant. In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, "Public Inspections, Exemptions, Requests for Withholding," of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRC's Public Document Room or from the Publicly Available Records System (PARS) component of NRC's Agencywide Document Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely,/RA Karla Stoedter Acting for/

Kenneth Riemer, Chief Branch 2 Division of Reactor Projects Docket No. 50-341 License No. NPF-43

Enclosure:

Inspection Report 05000341/2017001 cc: Distribution via LISTSERV

SUMMARY OF FINDINGS

........................................................................................................ 2

REPORT DETAILS

................................................................................................................... 4 Summary of Plant Status

REACTOR SAFETY

....................................................................................................... 5

1R01 Adverse Weather Protection

Main article: IP 71111.01

.............................................................. 5

1R04 Equipment Alignment

Main article: IP 71111.04

........................................................................ 5

1R05 Fire Protection

Main article: IP 71111.05

................................................................................... 6

1R06 Flooding

Main article: IP 71111.06

............................................................................................. 7

1R07 Heat Sink Performance

Main article: IP 71111.07

..................................................................... 8

1R11 Licensed Operator Requalification Program

Main article: IP 71111.11

...................................... 9

1R12 Maintenance Effectiveness

Main article: IP 71111.12

.............................................................. 10

1R13 Maintenance Risk Assessments and Emergent Work Control

Main article: IP 71111.13

........ 10

1R15 Operability Determinations and Functionality Assessments

Main article: IP 71111.15

............ 11

1R18 Plant Modifications

Main article: IP 71111.18

.......................................................................... 12

1R19 Post-Maintenance Testing

Main article: IP 71111.19

............................................................... 13

1R20 Refueling and Other Outage Activities

Main article: IP 71111.20

............................................ 14

1R22 Surveillance Testing

Main article: IP 71111.22

........................................................................ 14

1EP6 Drill Evaluation

Main article: IP 71114.06

OTHER ACTIVITIES

.................................................................................................... 16

4OA1 Performance Indicator Verification

Main article: IP 71151

....................................................... 16

4OA2 Identification and Resolution of Problems

Main article: IP 71152

............................................ 18

4OA3 Follow-Up of Events and Notices of Enforcement Discretion

Main article: IP 71153

............... 26 4OA5 Other Activities ................................................................................................... 40 4OA6 Management Meetings ...................................................................................... 41 4OA7 Licensee-Identified Violations ............................................................................ 41

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee

N. Avrakotos, Manager, Radiological Emergency Response Preparedness

L. Bennett, Director, Nuclear Operations

R. Breymaier, Manager, Performance Engineering

M. Caragher, Executive Director, Nuclear Production

D. Domski, Engineer, Plant Systems Engineering

I. Finney, General Supervisor, NSSS Systems Engineering

J. Haas, Supervisor, Licensing

C. Harris, Manager, Performance Improvement

D. Hemmele, Superintendent, Nuclear Operations

E. Kokosky, Director, Organization Effectiveness

R. Laburn, Manager, Radiation Protection

B. Leimkuehler, Performance Engineering

M. Lake, Supervisor, Reactor Engineering & PSA

K. Locke, General Supervisor - Electrical, Plant Systems Engineering

J. Louwers, Manager, Nuclear Quality Assurance

S. Maglio, Manager, Licensing

K. Mann, Supervisor, Regulatory Compliance

R. Matuszak, Manager, Plant Systems Engineering

D. Noetzel, Director, Nuclear Engineering

M. O'Connor, Manager, Nuclear Security

G. Patzsch-Velaquez, Performance Engineering

K. Polson, Site Vice President

W. Raymer, Director, Nuclear Maintenance

N. Schafer, NSSS Systems Engineering

U.S. Nuclear Regulatory Commission K. Riemer, Chief Reactor Projects, Branch 2

LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED

Opened

05000341/2017001-01 NCV Inadequate Work Instructions for Maintenance on EDG 14 (Section 4OA2.2.b.1)

05000341/2017001-02 NCV Failure to Maintain Adequate SLC Storage Tank Boron Concentration (Section 4OA3.8)

Closed

05000341/FIN-2017001-01 NCV Inadequate Work Instructions for Maintenance on EDG 14 (Section 4OA2.2.b.1)

05000341/LER-2016-001-01 LER Turbine Stop Valve Closure and Turbine Control Valve Fast Closure Reactor Protection System Functions

Considered Inoperable Due to Open Turbine Bypass

Valves, Supplement 1 (Section 4OA3.1)

05000341/LER-2016-010-00 LER Secondary Containment Pressure Exceeded Technical Specification Due to Adverse Weather (Section 4OA3.2)

05000341/LER-2016-013-00 LER Secondary Containment Pressure Exceeded Technical Specification Due to Adverse Weather (Section 4OA3.3)

05000341/LER-2016-014-00 LER Secondary Containment Pressure Exceeded Technical Specification Due to Adverse Weather (Section 4OA3.4)

05000341/LER-2016-015-00 LER Secondary Containment Pressure Exceeded Technical Specification During Reactor Building HVAC Restart Due to High Winds (Section 4OA3.5)

05000341/LER-2016-016-00 LER Secondary Containment Pressure Exceeded Technical Specification Due to Adverse Weather (Section 4OA3.6)

05000341/LER-2016-017-00 LER Secondary Containment Pressure Exceeded Technical Specification During Reactor Building HVAC Restart Due to High Winds (Section 4OA3.7)

05000341/FIN-2017001-02 NCV Failure to Maintain Adequate SLC Storage Tank Boron Concentration (Section 4OA3.8)

05000341/LER-2016-011-00 LER Standby Liquid Control Inoperable Due to Sodium Pentaborate Concentration Outside of Technical Specifications (Section 4OA3.8)

05000341/LER-2016-012-00 LER Unanalyzed Condition for Control Rod Drop Accident at Low Reactor Power (Section 4OA3.9)

05000341/LER-2017-002-00 LER High Water Level Indications at Low Reactor Pressures Causes Some Functions of High Pressure Coolant Injection System and Reactor Core Isolation Cooling System to Be Inoperable (Section 4OA3.10) 2515/192 TI Inspection of the Licensee's Interim Compensatory Measures Associated with the Open Phase Condition

Design Vulnerabilities in Electric Power Systems

(Section 4OA5.1)

Discussed

05000341/2014004-03 NCV Failure to Promptly Correct a Condition Adverse to Quality on EDG 11 (Section 4OA2.2.b.1)

05000341/2016002-01 NCV Failure to Control Combustible Materials (Section 4OA2.3.2)

05000341/2016001-03 NCV Failure to Satisfy 10 CFR 50.72 and 10 CFR 50.73 Reporting Requirements for Loss of RPS Trip Safety

Functions (Section 4OA2.3.3)

05000341/2016001-05 NCV Failure to Satisfy 10 CFR 50.73 Reporting Requirements for a Condition Prohibited by the Plant's Technical Specifications (Section 4OA2.3.3)

05000341/2016001-10 NCV Failure to Satisfy 10 CFR 50.72 and 10 CFR 50.73 Reporting Requirements for Primary Containment

Isolation Valve Actuations (Section 4OA2.3.3)

05000341/2016001-02 NCV Failure to Correctly Interpret and Implement TS Requirements for RPS Trip Functions (Section 4OA2.3.3)

05000341/2016007-16 NCV Failure to Timely Identify, Document, and Evaluate Conditions that Challenge Operability (Section 4OA2.3.3)

05000341/2016007-01 NCV Inadequate Procedure for Addressing Non-Functional Mechanical Draft Cooling Tower Fan Motor Brake System

(Section 4OA2.3.3)

05000341/2016003-01 NCV Failure to Perform an Operability Determination for Division 1 RPV Reference Leg Backfill System Not

Providing Adequate Flow (Section 4OA2.3.3)

05000341/2016004-03 NCV Failure to Satisfy 10 CFR 50.73 Reporting Requirements for Loss of LOP Instrumentation and AC Electrical Power

Safety Functions (Section 4OA2.3.3)

05000341/2016004-02 NCV Failure to Correctly Interpret and Implement TS Requirements for LOP Instrumentation and AC Electrical

Power Functions (Section 4OA2.3.3)

05000341/2016008-00 LER Past Instances of Secondary Containment Pressure Exceeding Technical Specification Due to Adverse Weather (Section 4OA3.2)

05000341/2016005-00 LER Secondary Containment Pressure Exceeded Technical Specification Due to Reactor Building HVAC Restart

During High Winds (Sections 4OA3.5 and 4OA3.7)

LIST OF DOCUMENTS REVIEWED

The following is a partial list of documents reviewed during the inspection.

Inclusion on this list does not imply the NRC inspectors reviewed the documents in their entirety, but rather, selected sections of portions of the documents were evaluated as part of the overall inspection effort.

Inclusion of a document on this list does not imply NRC acceptance of the document or any part of it, unless this is stated in the body of the inspection report. 1R01 Adverse Weather - Procedure 20.000.01; Acts of Nature; Revision 50 - Procedure MOP01-200; Severe Weather Guidelines; Revision 0 1R04 Equipment Alignment - CARD 15-29757; Condensation Puddles Under South End of East Turbine Building Closed Cooling Water Heat Exchanger - CARD 16-00420; Outboard Bearing for the South Turbine Building Closed Cooling Water System Pump (P4300C003) is Warmer than the North Pump - CARD 16-21657; N3021C013, Number Five Low Pressure Intercept Valve Unitized Actuator Oil High Temperature Alarm, 4D6 - CARD 16-24321; P4300 Turbine Building Closed Cooling Water System was Evaluated to be (a)(1) - CARD 16-25572; N3021C005, High Pressure Stop Valve 1 Turbine Valve Actuator (Unitized Actuator) - CARD 16-26225; 7D61:

West Station Air Compressor Trouble Due to High Oil Temperature - CARD 16-26994; Extent of Condition:

Request Work Order to Replace High Pressure Unitized Actuator Inlet/Outlet Turbine Building Closed Cooling Water Isolation Valves - CARD 16-28298; Extent of Condition:

Request Work Order to Replace High Pressure Unitized Actuator Inlet/Outlet Turbine Building Closed Cooling Water Isolation Valves - Fermi 2 Health Summary; Third Quarter 2016 Turbine Building Closed Cooling Water System

- Procedure 23.128; Turbine Building Closed Cooling Water System; Revision 45 - Procedure 23.205, Attachment 11A; Shift to Division 1 Residual Heat Removal Shutdown Cooling Verification - Procedure 23.205; Placing Division 1 Residual Heat Removal in Shutdown Cooling Mode; Revision 132 - Procedure 23.205; Residual Heat Removal System; Revision 131 - Procedure 23.208; Residual Heat Removal Complex Service Water Systems; Revision 111 - Procedure 23.307; Emergency Diesel Generator System; Revision 122

- Sketch 6M721-5734; Emergency Diesel Generator System Functional Operating Sketch; Revision BF -

WO 38081729; P43F405 (Turbine Building Closed Cooling Water D/P Containment

Valve) - Valve does not Appear to be Moving While Actuator is Moving -

WO 45408702;

EDP 37709 Turbine Building Closed Cooling Water System Implementation - SPV - Work Week 1705 Strategy Document; Division 2 Residual Heat Removal/ Residual Heat Removal Service Water Train Outage; January 30, 2017 1R05 Fire Protection - CARD 17-20633; C02 Boundary Door D41 Latch Broken

- Fire Protection Pre Plan

FP-AB-3-14c; Auxiliary Building, East Reactor Protection System Division 1 Motor Generator Set Room, Zone 14, Elevation 643'6"; Revision 3 - Procedure

FP-AB-1-6d; Auxiliary Building First Floor Mezzanine, Zone 6, Elevation 603'6"; Revision 4 - Procedure

FP-TB; Turbine Building; Revision 9 1R06 Flood Protection - CARD 08-23459; NRC Concern: Unshrouded Division 2 Emergency Equipment Cooling Water Piping Routed in Division 1 Switchgear Room - CARD 08-23602; NRC Concern:

Moderate Energy Line Break Drain Path Compromised by Unsealed Hatch - CARD 16-29475; Potential Misclassification of AB 3/4 and 4/5 Hatches as Limiting Condition of Operation 3.0.9 Barriers - CARD 17-21851; NRC Identified - Update UFSAR Section 3.6.2.3.4.1.2 - CARD 17-21865; NRC Identified - Investigate Revision of 35.000.242

- Procedure 35.000.242; Barrier Identification/Classification; Revision 55

- Regulatory Issue Summary

RIS 01-009; Control of Hazard Barriers; April 2, 2001

- Technical Evaluation

TE-A58-08-069; Temporary Removal of Auxiliary Building Fourth and Fifth Floor Hatch Covers; Revision 0 - Technical Service Request

TSR-36051; Add Spray Barrier Over AB4 Hatch Cover; Revision 0 - UFSAR Section 3.6.2; Protection Against Dynamic Effects Associated with the Postulated Rupture; Revision 20 1R07 Heat Sink Performance - CARD 17-20735; Verify Acceptability of Installed Tube Bundle for Heat Exchangers for

EDG 14 - CARD 17-20759;

EDG 11 Heat Exchanger Bundles not Oriented Correctly

- CARD 17-20788;

EDG 14 Tube Bundle Orientation to Eddy Current Results

- CARD 17-22773; Residual Heat Removal Heat Exchanger Coating - Engineering Functional Analysis

EFA-R30-17-001;

EDG 11 Heat Exchanger Tube Bundles Mis-oriented; Revision 0 - Heat Exchanger Inspection Report;

EDG 14 - Air Coolant Heat Exchanger; January 23, 2017 - January 25, 2017 - Heat Exchanger Inspection Report;

EDG 14 - Jacket Cooling Heat Exchanger; January 23, 2017 - January 25, 2017 - Heat Exchanger Inspection Report;

EDG 14 - Lube Oil Heat Exchanger; January 23, 2017 - January 25, 2017 -

MES 54; Heat Exchanger Component Monitoring Program; Revision 5 - Technical Evaluation

TE-R30-17-008; CARD 17-20759 Past Operability; Revision 0 1R11 Licensed Operator Requalification Program - Procedure 22.000.03; Power Operation 25% to 100% to 25%; Revision 101 - Procedure 22.000.04; Plant Shutdown from 25% Power; Revision 79 1R12 Maintenance Effectiveness - CARD 16-30023; Nitrogen Bottles for E1156C001A, Mechanical Draft Cooling Tower Fan A, Found to be at Zero Pounds

- CARD 17-20553; Low Nitrogen Bottle Pressure on the High Pressure Bottle for A Mechanical Draft Cooling Tower Fan Brake - CARD 17-21143; Mechanical Draft Cooling Tower A Brake Pressure Regulator is Indicating 0 psig - CARD 17-21163; Dipstick Dropped in Oil Tube

- Fermi 2 Control Room Log; February 9, 2017

- System Health Report E1156; RHR Mechanical Draft Cooling Tower Fans and Ultimate Heat Sink; 3rd and 4th Quarter 2016 1R13 Maintenance Risk Assessment and Emergent Work Control - CARD 17-21058; South Heater Drain Pump Tripped Causing a Subsequent Plant Transient and Reactor Recirculation Runback - CARD 17-21060; Instantaneous Core Thermal Power Level Exceeded Reportability Assessment Power Level in MOP19 - ODMI 17-001; North Reactor Feed Pump Vibration Step Change; Revision 0 - Reactivity Maneuvering Plan; January 2017 Radiation Protection Advisor; Revision 0 1R15 Operability Determinations and Functionality Assessments - CARD 08-25246; Reactor Building Auxiliary Steam Heating and Control Rod Drive Line Break Definition - CARD 11-23400; IER Level 1 11-1 Review Result:

DC-5426 Volume I Discrepancies

- CARD 12-25925; Self-Assessment Deficiency:

Revisit and Re-Evaluated Moderate Energy Line Break Definition Previously Addressed in 08-25246 - CARD 14-25229; Design Discrepancy Related to Assumed High Energy Line Break Area for 15psig Heating Steam - CARD 15-28013; T2300F410 Running Torque High During As-left Air Operated Valve Testing

- CARD 16-26153; Limerick Tech Spec Change - High Pressure Coolant Injection-Reactor Core Isolation Cooling Level 8 Trip Signal - CARD 16-26697; 2016 CDBI Inspection - Main Steam Isolation Valve Calculation

DC-0469 Discrepancy with UFSAR 5.5.5.1.e - CARD 16-27189; Main Steam Isolation Valve TS Surveillance Requirement 3.6.1.3.7 not Correlated to Plant Safety Analysis - CARD 16-28470; Operations Decision Expectation-12 Remote Shutdown System Section Review - CARD 16-28585; Review

DC-6538 for Potential Impact on License Agreement Request - CARD 16-29382; Request Evaluation for the Minimum Design Temp for Emergency Diesel Generator's Fuel Oil Storage Room(s) - CARD 16-29742; Inappropriate Operability Determination in CARD 14-25229

- CARD 16-29743; CARD 14-25229 Investigation Failed to Identify Potential Operability Issue

- CARD 16-29897; Potential Auxiliary Steam Line High Energy Line Break not Discussed in Auxiliary High Energy Line Break

EFA-T41-16-008 - CARD 17-20083; Evaluate Site Processes for CARDs with Operable but Degraded or Non- Conforming Status - CARD 17-20173; Weld Found Leaking After the Associated Work Order was Returned to Service - CARD 17-20643; Review Timeliness of Evaluation of Limerick Unresolved Item Regarding High Pressure Coolant Injection/Reactor Core Isolation Cooling in CARD 16-26153 - CARD 17-21165; Mispositioned Component Nitrogen Pressure Regulator Mechanical Draft Cooling Tower Fan A

- CARD 17-21717; Nuclear Safety Review Group Question on HPCI/RCIC Level 8 Trip Signal at Low Reactor Pressure - Design Calculation

DC-5991; Air Operated Valve Stem Force Requirements and Actuator Capacity for B2103F022A; Revision A - DTE Letter

NRC-17-0010 to NRC; License Amendment Request to Revise Technical Specifications for Emergency Core Cooling System Instrumentation and Reactor Core Isolation Cooling System Instrumentation; February 23, 2017 -

EFA-T41-16-008; Pipe Break Evaluation of Heating Steam Lines; Revision 0

-

GEH 003N8634; Fermi 2 Main Steam Isolation Valve Closing Speed Evaluation; Revision 0 - Letter from Exelon to NRC; Emergency License Amendment Request - Proposed Changes to the High Pressure Core Spray System and Reactor Core Isolation Cooling System Actuation Instrumentation Technical Specifications; November 26, 2016 - Letter from Exelon to NRC; License Amendment Request - Proposed Changes to the High Pressure Coolant Injection System and Reactor Core Isolation Cooling System Actuation Instrumentation Technical Specifications; April 4, 2016 - NRC Information Notice 90-53; Potential Failures of Auxiliary Steam Piping and the Possible Effects on the Operability of Vital Equipment; August 16, 1990 - Operations Department Expectation

ODE-12; Limited Condition of Operations; Revision 39

- Operations Department Expectation

ODE-11; CARD Operability/ Reportability Determination Expectations; Revision 22 - Procedure 22.000.02; Plant Startup to Twenty-five Percent Power; Revision 95

- Procedure 23.202; High Pressure Coolant Injection System; Revision 110

- Procedure 23.206; Reactor Core Isolation Cooling System; Revision 99A

- Technical Evaluation

TE-B21-16-035; Cycle 18 Main Steam Isolation Valve Closure Surveillance Test; Revision 0 - Technical Evaluation

TE-E11-17-016; Analysis of Degraded Mechanical Draft Cooling Tower Fan Brake; Revision 0 1R18 Plant Modifications - Apparent Cause Evaluation 16-22815; Temporary Modification 15-0042: Ahlberg Mast Camera; Revision 0 - CARD 15-22955; NQA - Inadequate Documentation Justifying Application of

RTV 732 Sealant to Penetrations per Work Order

42565748 - CARD 15-27651; NQA - ASME Parts Installed and Welded on B31N004B Prior to NQA Review for Traceability - CARD 15-27707; E1100F620B is Leaking Through its Tell Tale Drain Valve E1100F625B - CARD 16-22815; Currently Installed Temporary Modification 15-0042 Has an Expected Removal Date of Post RF17 - CARD 16-28367; NQA Audit Deficiency - Temporary Video Equipment/ Free Air Cables, Cameras not Removed as Required by Technical Evaluation

TE-D50-12-070 - CARD 17-10751; Assumption Error in Appendix R Calculation

DC-5783 Volume 1 - CARD 17-20480; Request Work Order for Implementation of

EDP 37731 Residual Heat Removal Cross-tie - CARD 17-20481; Request Work Orders for Implementation of

EDP 37792, Remove Residual Heat Removal Reservoir Cross tie Valves - CARD 17-21293; Post Modification Testing Failure - Open Stroke Time of T4600F407 Outside of Acceptance Criteria Band Following Hardened Containment Vent System Modification Tie- in - CARD 17-21726; NRC Identified

EDP 37272 States 2 to 1 Ratio on All Socket Welds. Engineering Change Request Required to Change this Verbiage

- Design Calculation

DC-0559; Volume of Reservoir - Residual Heat Removal Complex; Revision D - Design Calculation

DC-0622; RHRSW System - Direct Water Injection to Reactor Pressure Vessel - Hydraulic Analysis; Revision C -

EDP-37272; Reactor Core Isolation Cooling Pump Discharge High Point Vent Relocation; Revision 0 -

EDP-37731; Change Valves E1150F601A/B and E1150F601A, E115F601B, E1150F602A, and E1150F602B; Revision 0 - Fermi 2 UFSAR 9.2; Revision 20 - Sketch 6WM-E51-5307-1; Piping Isometric Reactor Core Isolation Cooling Pump Discharge Vent Line Reactor Building; Revision 0 -

WO 43579247;

EDP-37272 Cycle 18 Refueling Outage Installation Reactor Core Isolation Cooling High Point Vent -

WO 46896660; Request Work Orders for Implementation of

EDP 37792, Remove Residual Heat Removal Reservoir Cross Tie Valves 1R19 Post-Maintenance Testing - CARD 17-22281; E1150F015A Failed Motor Inspection - CARD 17-22391; Air Leak from P5000F402 Actuator - CARD 17-22435; P5000F402 Failed to Stroke During As-Left Diagnostic Testing - Procedure 23.307; Emergency Diesel Generator System; Revision

- Procedure 24.129.04; Control Air Valve Operability/Position Indication Verification/ Isolation Integrity Test; Revision 46 - Procedure 24.204.01; Division 1 Low Pressure Coolant Injection and Suppression Pool Cooling/Spray Pump and Valve Operability Test; Revision 79 - Procedure 24.307.10;

EDG 11 - Emergency Core Cooling System Start and Load Rejection Test and Logic Functional Tests of Bus 64B Breakers; Revision 42 - Procedure 24.307.11;

EDG 12 - Emergency Core Cooling System Start and Load Rejection Test and Logic Functional Tests of Bus 64C Breakers; Revision 45 -

WO 38444863; Perform American Society of Mechanical Engineers as Found and as Left Relief Valve Testing -

WO 43656061; Replace Agastat Relay in P50P402A, Division 1 Non-Interruptible Air Supply Dryer Control Cabinet -

WO 44152016; Perform 24.307.10

EDG 11 Emergency Core Cooling System Start and Load Rejection Test and Logic Functional Tests of Bus 64B -

WO 44152934; Perform 24.204.05 Section 5.1 Division 1 Residual Heat Removal Local Valve Position Indication and Stroke -

WO 44152950; Perform 24.307.11

EDG 12 Emergency Core Cooling System Start and Load Rejection Test and Logic Functional Tests of Bus 64C -

WO 44606373;

EDP-37115 Cycle 18 Refueling Outage, Tie-in Tubing, Shuttle Valve and Post Modification Testing for Air Operated Valve P5000F440 (Division 1 Control Air Compressor) -

WO 46676663; Replace West Control Rod Drive Pump Water

-

WO 46966894;

EDG 11 Heat Exchanger Bundles not Oriented Correctly

-

WO 46974874; Perform 24.307.34 Diesel Generator Service Water Operability Test -

EDG 11

- WO A394130100; Perform Valve Actuator Overhaul and Air Operated Valve Diagnostic Testing 1R20 Refueling and Other Outage Activities - Operations Conduct Manual MOP13; Conduct of Refueling and Core Alterations; Revision 17

- Procedure 82.000.04; Refueling and Core Post - Alteration Verification; Revision 50 - Procedure 23.205; Residual Heat Removal System; Revision 132

- Procedure 22.000.05; Pressure/Temperature Monitoring During Heatup and Cooldown; Revision 49 1R22 Surveillance Testing - CARD 17-21352; While Performing Procedure 42.307.01, Acceptance Criteria Step Failed During 72 Hour Limited Conditions of Operation - Card 17-22310; Clarification to 24.623 - CARD 17-22310; Clarification to 24.623

- Procedure 24.204.01; Division 1 Low Pressure Coolant Injection and Suppression Pool Cooling/Spray Pump and Valve Operability Test; Revision 79 - Procedure 24.208.02; Division 1 Emergency Equipment Service Water and Emergency Equipment Cooling Water Makeup Pump and Valve Operability Test; Revision - Procedure 24.307.14;

EDG 11 - Start and Load Test; Revision 58

- Procedure 24.307.34; Diesel Generator Service Water, Diesel Fuel Oil Transfer and Starting Air Operability Test -

EDG 11; Revision 52 - Procedure 24.623; Reactor Manual Control/Reactor Mode Switch/Refueling

Platform - Refueling Interlocks; Revision 56 - Procedure 24.623; Reactor Manual control/Reactor Mode Switch/Refueling

Platform - Refueling Interlocks; Revision 56 - Procedure 42.307.01; Logic System Functional Test of Division 1 Emergency Diesel Generator Emergency Core Cooling System Emergency Start Circuits and Auto Trip/Bypass Circuits; Revision - Procedure 43.000.003; Visual Examination of Snubbers; Revision 48 - Procedure 43.401.303; Local Leakage Rate Testing for Penetration X-9A; Revision 38

- Procedure 43.401.304; Local Leakage Rate Testing for Penetration X-9B; Revision 43

-

WO 43250733; Perform 42.307.01Division 1 Emergency Diesel Generator Emergency Core Cooling System Emergency Start Circuits and Auto Trip/Bypass Logic Functional Test -

WO 44087703; Perform 24.208.02 Division 1 Emergency Equipment Service Water Pumps and Valve Operability -

WO 44097723; Perform 24.208.02 Division 1 Emergency Equipment Cooling Water Makeup Pump and Valve Operability -

WO 44107717; Final 43.401.304 Local Leak Rate Testing for X-9B (Test-1:B2100F010B) -

WO 44134176; Final 43.401.303 Local Leak Rate Testing for X-9A (Test-1:B2100F010A) 4OA1 - Performance Indicator Verification -

NEI 99 02; Regulatory Assessment Performance Indicator Guideline; Revision 7 - NUREG 1022; Event Report Guidelines, 10

CFR 50.72 and 50.73; Revision 3 4OA2 - Problem Identification and Resolution - Apparent Cause Evaluation 16-26255; Recurrent Trend in Foreign Material Found in Discharged Irradiated Fuel; Revision 2 - Apparent Cause Evaluation 16-28674;

EDG 14 Shutdown Due to Thick Smoke Coming from the Opposite Control Side Exhaust Manifold; Revision 0 - Apparent Cause Evaluation 16-28286; Multiple Entries Into Offsite Power Limiting Condition for Operation Due to Declaration of Internal N-1 Contingency Delta Voltage of Greater Than 1.6%

- Apparent Cause Evaluation 16-21857; Adverse Trend in Reportability Related Issues; Revision 1 - Archive Narrative Log; Fermi 2 Archived Operator Log; October 31, 2016 to November 1, 2016 - CARD 14-22612;

EDG 11 Manually Tripped During Surveillance Test Due to Fire from Turbo Lagging - CARD 14-25079;

EDG 11 Control Side Exhaust Manifold Blanket Rework

- CARD 16-21857; Adverse Trend in Reportability Related Issues

- CARD 16-23605; Emerging Trend of Design Deficiency Rework Events Within Engineering

- CARD 16-23868; Declining Trend in Reliability in Off Gas System Radiation Monitoring and Acceptance - CARD 16-24239; Emerging Trend in Maintenance: Rework Due to Inadequate Procedure Use and Adherence - CARD 16-24400; NQA Audit Deficiency - Non-compliances with Flammable Liquids Locker Controls, Repeat Audit Deficiencies - CARD 16-24413; Emerging Trend with Transient Combustible Storage - CARD 16-24839; Trend of Marotta Regulator Failures

- CARD 16-25524; NQA Audit Deficiency - Trending has not been Effectively Implemented to Identify Adverse Trends in Training Related Activities/ Events - CARD 16-25717; Emerging Trend in Operator Performance - CARD 16-26154; Trend in Reactivity Management Issues from Human Performance - CARD 16-26255; Recurrent Trend in Foreign Material Found in Discharged Irradiated Fuel

- CARD 16-26267; Adverse Trend of Events Associated with the High Pressure Stop Valves, Low Pressure Stop Valves and Low Pressure Isolation Valves - CARD 16-26558; Spent Fuel Pool Foreign Material Trend

- CARD 16-26633; 2016

CDBI-NRC Concern for Operability Determination Justifications and Timeliness - CARD 16-26798; Inadequate Interpretations of Technical specifications Identified by NRC

- CARD 16-26944; Emerging Trend in Implementation of the Corrective Action Program

- CARD 16-27909; NQA - Notice of Escalation - Untimely Initiation of CARDs

- CARD 16-28123; Change Management Failure - CARD 16-28286; Internal N-1 Contingency Threshold Exceeded Four times On 10/17/2016 - CARD 16-28293; Common Cause Analysis of Rework Events

- CARD 16-28410; NQA Audit Deficiency - Trending has not been Effectively Implemented to Identify Adverse Trends in the Design Configuration Management Program - CARD 16-28674;

EDG 14 Shutdown During 24.307.17

- CARD 16-29205; Third Quarter 2016 Station Trend Report - Emerging Trend in Corrective Action Program Quality - CARD 16-29512; MRC Identified Cognitive Trend in Unanalyzed Condition NRC Reportable Events During 3rd and 4th Quarters of 2016 - CARD 16-29513; MRC Identified Cognitive Trend in Secondary Containment NRC Reportable Events During 3rd and 4th Quarters of 2016 - CARD 17-21593; Evaluate Screening Determination for CARD 16-28674 - CARD 17-22240; Foreign Material Exclusion Plan Violation

- CARD 17-22312; Foreign Material Exclusion Introduced into Suppression Chamber Torus - CARD 17-22432; Loss of Foreign Material Exclusion Controls

LPT-2 During Disassembly

- CARD 17-22452; NQA - LP2 Foreign Material Exclusion Area Control/ Postings

- CARD 17-22494; NQA - Reactor Core Isolation Cooling High Risk Foreign Material Exclusion Plan Requirements not Followed - CARD 17-22556; NQA - Poor Housekeeping Observed in Reactor Core Isolation Cooling Quad

- CARD 17-22664; Work in High Risk Foreign Material Exclusion Area Without Foreign Material Exclusion Monitor - CARD 17-22732; Recovered Piece of Foreign Material from Spent Fuel Pool - CARD 17-22805; South Heater Drain Pump - Drop Bolt into Pump Suction Tank - CARD 17-22819; Inadequate Lanyard on Tool in High-risk Foreign Material Exclusion Area

- Common Cause Analysis Report; Trend in Reactivity Management Issues from Human Performance; August 4, 2016 - DTE Letter

NAPI-16-0021; From C. Tomkinson, Corrective Action Program, to C. Harris, Performance Improvement Manager; Third Quarter Station Trend Report; November 16, 2016 - DTE Letter

NAPI-17-0001; From C. Tomikinson, Corrective Action Program, to C. Harris, Performance Improvement Manager; Fourth Quarter 2016 Station Trend Report;

February 21 , 2017 - DTE Letter

NAQA-16-0057; From J. Louwers, Manager of Nuclear Quality Assurance, to M. Caragher, Nuclear Production Director; Notice of First Level Issue Escalation - Untimely Initiation of CARDs; October 5, 2016 - DTE Letter

NP-16-0039; From M. Caragher, Nuclear Production Director, to J. Louwers Manager of Nuclear Quality Assurance; Response to Notice of First Level Issue Escalation -

Untimely Initiation of CARDs; October 14, 2016 - DTE Letter

NPOP-16-0054; From G. Piccard, Nuclear Operations Manager, to M. Caragher, Nuclear Production Director, and L. Peterson, Nuclear Engineering Director; Reactivity Management Trends for June 2016; July 12, 2016 - Final Report; 2015 Fermi 2 Nuclear Power Plant Grid Reliability Analysis for Year 2016 System, Performed by Ming Wu, PE and Joshua Niemi, ITC Holdings Corp.;

December 9, 2015 - Hazard Barrier Target Analysis; Prevention of Foreign Material Depositing on Spent Fuel Assemblies; June 20, 2013 -

NUC-001; Nuclear Plant Operating Agreement for the Fermi 2 Nuclear Power Plant; Revision 9 - Reactor Engineering Standing Order 18-005; Revision 0

- Technical Evaluation 14-22612;

EDG 11 Manually tripped During Surveillance Test Due to Fire from Turbo Lagging - Technical Evaluation

TE-R30-17-013; Review of Shutting Down

EDG 14 During Surveillance 24.307.17 Due to Thick Smoke; Revision 0 - Technical Evaluation

TE-S40-17-017; N-1 Past Operability; Revision 0

- TMPE 15-0191; Letter from K. Hullum-Lawson, Manager, PSE, DTE Energy to J. Andree, Manager, METC/ITC Transmission Planning, ITC Holdings Corp., 2015 Fermi 2 Input Parameters for 2016 Study Grid Adequacy Study Fermi PST Event AG80; October 9, 2015 - UFSAR 8.2-1; Offsite Power System; Revision 20

-

WO 38298165; Modify Exhaust Blankets on

EDG 14 -

WO 43259825; Torque Check

EDG 14 Front Cover Fasteners 4OA3 Follow-Up of Events and Notices of Enforcement Discretion - 50.59 Evaluation 16-0251; Revision A of

DC-4804 Volume 1, "Secondary Containment Drawdown During Design Basis Accident Loss of Coolant Accident", and Related

LCR-16-082-UFS Revision 0, Affecting UFSAR Section 6.2.3.3.2 and Figure 6.2-2.1;

Revision 0 - Apparent Cause Evaluation CARD 16-20156; Turbine High Pressure Stop Valve 1 Closed, Isolating a Turbine Steam Lead; Revision A - Apparent Cause Evaluation CARD 16-28619; Sodium Pentaborate Concentration Low Identified in Standby Liquid Control Tank; Revision 0

- CARD 16-20156; Number 1 High Pressure Stop Valve Drifted to 25% Open from 100% Open at Power - CARD 16-28545; High Wind Condition Encountered on Site Result in the Technical Specification for Secondary Containment Pressure Boundary not Being Met Numerous Times - CARD 16-28552; Revise

LER 2016-001 to Reflect Changes to Cause and Corrective Actions

- CARD 16-28616; Abnormal Indications While Investigating 3D3, Standby Liquid Control Tank Level High Alarm - CARD 16-28619; Sodium Pentaborate Concentration Low

- CARD 16-28628; Request Work Order to Replace the Demineralized Water Isolation Valves for Standby Liquid Control Storage Tank - CARD 16-28738; Non-Conservative Fermi 2 Control Rod Drop Accident Licensing Design Basis - CARD 16-29351; Division 1 Reactor Building Differential Pressure Recorder Response

- CARD 16-29353; Due to High Winds, Reactor Building Pressure Exceeded the Technical Specification Limit (-0.125 Inches WC) Several Times - CARD 16-29518; Secondary Containment Declared Inoperable Due to High Winds

- CARD 16-29951; Secondary Containment Pressure > Technical Specification Limit Momentarily During Reactor Building HVAC Startup - CARD 16-29971; Due to the High Winds, Reactor Building Pressure Exceeded the Technical Specification Limit (-0.125 Inches WC) Several Times - CARD 16-29978; Reactor Building HVAC Outside Air Damper Failed to Open

- Correspondence, DTE Letter from J. Owens and C. Metheny, Engineering Support Organization, to D. Valleroy; Failure Analysis of 2 Cannon Connectors and Associated Cable for Fermi 2 QA Traveler No. N/A, Test Req.

WO 35802373, P.O. No. N/A, Test Material Master No. N/A, Stock Material Master No. N/A, Engineering Support Organization Report 16J075-0037; June 24, 2016 - DTE Letter

NRC-17-0029; Cancellation of Licensee Event Reports for Secondary Containment Wind Events; March 17, 2017 - Engineering Functional Analysis

EFA-T41-16-007; Impact of GSE Release Path on Radiological Consequences of the Control Rod Drop Accident; Revision 0 - Engineering Functional Analysis

EFA-T41-16-007; Impact of GSE Release Path on Radiological Consequences of the Control Rod Drop Accident; Revision A - Equipment Apparent Cause Evaluation CARD 16-20156; Number 1 High Pressure Stop Valve Drifted to 25% Open From 100% Open at Power - Equipment Apparent Cause Evaluation CARD 16-28619; Sodium Pentaborate Concentration Low - Event Notification 16-0016; Unanalyzed Condition for Control Rod Drop Accident at Low Power - Event Notification 17-002; Retracted Event Notifications: 52076, 52084, 52205, 52320, 52380, 52398, 52432, 52434, and 52437 - Event Notification 52320; Secondary Containment Technical Specification not Met - Event Notification 52331; Standby Liquid Control Technical Specification not Met - Event Notification 52331; Standby Liquid Control Technical Specification not Met

- Event Notification 52380; Secondary Containment Technical Specification not Met

- Event Notification 52398; Secondary Containment Technical Specification not Met

- Event Notification 52432; Startup of the Reactor Building HVAC System Resulted in the Technical Specification for Secondary Containment Pressure Boundary not Being Met for Approximately One Second - Event Notification 52434; Secondary containment Technical Specification Not Met

- Event Notification 52437; Startup of the Reactor Building HVAC System Resulted in the Technical Specification for Secondary containment Pressure Boundary not Being Met for Approximately One Second - Failure Analysis FA16N0735-01-01; Averaging Circuit and Gain Amplifier PCB P/N:

650-30X-3156, DTE Energy PO#

4700965738, ATC Nuclear JN16N0735; Revision 0 - Failure Analysis FA16N0735-02-001; Linear Variable Differential Transformer. Driver and Demodulator PCB P/N: 650-30X-3153, DTE Energy PO#

4700965738, ATC Nuclear

JN16N0735; Revision 0 - Fermi 2 Control Room Log; October 28, 2016 - Fermi 2 Control Room Log; October 29, 2016 -

LER 2016-001-01; Turbine Stop Valve Closure and Turbine Control Valve Fast Closure Reactor Protection System Functions Considered Inoperable Due to Open Turbine Bypass Valves; Revision 1 -

LER 2016-010-00; Secondary Containment Pressure Exceeded Technical Specification Due to Adverse Weather; Revision 00 -

LER 2016-011-00; Standby Liquid Control Inoperable Due to Sodium Pentaborate Concentration Outside of Technical Specifications -

LER 2016-012-00; Unanalyzed Condition for Control Rod Drop Accident at Low Reactor Power; Revision 0 -

LER 2016-013-00; Secondary Containment Pressure Exceeded Technical Specification Due to Adverse Weather; Revision 00 -

LER 2016-014-00; Secondary Containment Pressure Exceeded Technical Specification Due to Adverse Weather; Revision 0 -

LER 2016-015-00; Secondary Containment Pressure Exceeded Technical Specification During Reactor Building HVAC Restart Due to High Winds; Revision 0 -

LER 2016-016-00; Secondary Containment Pressure Exceeded Technical Specification Due to Adverse Weather; Revision 0 -

LER 2016-017-00; Secondary Containment Pressure Exceeded Technical Specification During Reactor Building HVAC Restart Due to High Winds; Revision 0 -

LER 2017-002-00; High Water Level Indications at Low Reactor Pressures Causes Some Functions of High Pressure Coolant Injection System and Reactor Core Isolation Cooling System to be Inoperable; Revision 0 - Licensing Position Paper; Capability of Standby Liquid Control to Perform Required Functions; January 2017 - Technical Evaluation

TE-T41-17-009; Review of 2016 Secondary Containment LERs Due to Wind Effects; Revision 1 4OA5 Other Activities - 120 kV Switchyard/Relay House Walkdown Checklist - 345 kV Switchyard/Relay House Walkdown Checklist - Augmented Quality Program

AQP-0002; ITC - Fermi Interface 120 kV and 345kV Switchyards; Revision 6 - CARD 12-26876; Training Review of New Procedure

- DTE Letter

NANL-12-0054; from T. Conner; Fermi 2 Response to Automatic Reactor Scram Resulting from a Design Vulnerability in the 4.16-k-V Bus Undervoltage Protection Scheme;

August 13, 2012 - Nuclear Training Course Plan

LP-GN-909-1121M; Just-In-time Training, IER L2 12-14 - Nuclear Training Lesson Plan

LP-OP-802-2002; Integrated Electrical Events; Revision 7

- Operating Procedure 47.000.88; Infrared Inspection; Revision 6

- Procedure 20.300.PHASE; Loss of Phase; Revision 0

- Procedure 24.307.14;

EDG 11 - Start and Load Test; Revision 58 - Procedure 24.307.15;

EDG 12 - Start and Load Test; Revision 58

- Procedure 24.307.16;

EDG 13 - Start and Load Test; Revision 56 - Procedure 24.307.17;

EDG 14 - Start and Load Test; Revision 57 -

SS-OP-802-2001; Operating Characteristics and Procedures Emergency/Abnormal Events Scenarios; Revision 17 - Temporary Instruction 2515/192; Inspection of the Licensee's Interim Compensatory Measures Associated With the Open Phase Condition Design Vulnerabilities in Electric Power Systems; November 9, 2016