Text

October 20, 2010

Mr. Jack Senior Vice President and Chief Nuclear Officer Detroit Edison Company Fermi 2 - 210 NOC 6400 North Dixie Highway Newport, MI 48166

SUBJECT: FERMI POWER PLANT, UNIT 2 INTEGRATED INSPECTION REPORT 05000341/2010004

Dear Mr. Davis:

On September 30, 2010, the U.S. Nuclear Regulatory Commission (NRC) completed an integrated inspection at your Fermi Power Plant, Unit 2. The enclosed report documents the results of this inspection, which were discussed on October 6, 2010, with J. Plona, Fermi 2 Site Vice-President, and other members of your staff. The inspection examined activities conducted under your license as they relate to safety and compliance with the Commission's rules and regulations and with the conditions of your license.

The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel. Based on the results of this inspection, no findings were identified. In accordance with 10 CFR 2.390 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 Public Document Room or from the Publicly Available Records System (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely,/RA/ John B. Giessner, Chief Branch 4 Division of Reactor Projects Docket No. 50-341 License No. NPF-43

Enclosure:

Inspection Report 05000341/2010004

w/Attachment:

Supplemental Information cc w/encl: Distribution via ListServ Enclosure U.S. NUCLEAR REGULATORY COMMISSION REGION III Docket No: 50-341 License No: NPF-43 Report No: 05000341/2010004 Licensee: Detroit Edison Company Facility: Fermi Power Plant, Unit 2 Location: Newport, MI Dates: July 1 through September 30, 2010 Inspectors: R. Morris, Senior Resident Inspector R. Jones, Resident Inspector M. Mitchell, Health Physicist J. Bozga, Reactor Engineer C. Zoia, Operations Engineer

Observers: V. Myers, Health Physicist

Approved by: J. Giessner, Chief Branch 4 Division of Reactor Projects Enclosure

SUMMARY OF FINDINGS

........................................................................................................... 1

REPORT DETAILS

....................................................................................................................... 2Summary of Plant Status

REACTOR SAFETY

.................................................................................... 21R01Adverse Weather Protection (71111.01) ..................................................... 21R04Equipment Alignment (71111.04) ................................................................ 31R05Fire Protection (71111.05) ........................................................................... 41R06Flooding (71111.06) .................................................................................... 51R07Annual Heat Sink Performance (71111.07) ................................................. 61R11Licensed Operator Requalification Program (71111.11) ............................. 71R12Maintenance Effectiveness (71111.12) ....................................................... 71R13 Maintenance Risk Assessments and Emergent Work Control (71111.13) .. 81R15Operability Evaluations (71111.15) ............................................................. 91R18Plant Modifications (71111.18) .................................................................. 101R19Post-Maintenance Testing (71111.19) ...................................................... 111R20Outage Activities (71111.20) ..................................................................... 121R22Surveillance Testing (71111.22) ................................................................ 121EP6Drill Evaluation (71114.06)

RADIATION SAFETY

................................................................................ 142RS1Radiological Hazard Assessment and Exposure Controls (71124.01) ...... 142RS2Occupational As-Low-As-Is-Reasonably-Achievable Planning and Controls (71124.02)

OTHER ACTIVITIES

................................................................................. 194OA1Performance Indicator Verification (71151) ............................................... 194OA2Identification and Resolution of Problems (71152) .................................... 224OA3 Follow-Up of Events and Notices of Enforcement Discretion (71153) ....... 234OA6 Management Meetings .............................................................................. 25

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee

J. Plona, Fermi 2 Site Vice President

T. Conner, Plant Manager

D. Coseo, Operations Training Manager

M. Caragher, Engineering Director

J. Fline, Licensing

R. Johnson, Licensing Manager

E. Kokosky, Radiation Protection Manager

J. Stroud, Site Nurse

C. Walker, Operations Director

Nuclear Regulatory Commission

R. Orlikowski, Acting Chief, Reactor Projects Branch 4

J. Giessner, Chief, Reactor Projects Branch 4

LIST OF ITEMS

OPENED, CLOSED AND DISCUSSED Opened 0500341 2010-004-01 URI Inadequate procedures to control the plant from the dedicated shutdown panel Closed 0500341 2010-001-00 LER Automatic Reactor Shutdown due to Generator Current Transformer Wiring Failure 0500341 2010-002-00 LER Automatic Reactor Scram and Loss of Offsite Power due to Severe Weather

05000341/2009-010-01 NOV Failure to Provide Complete and Accurate Information Regarding License Operator Medical Examinations

Discussed

None.

Attachment

LIST OF DOCUMENTS REVIEWED

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

Inclusion on this list does not imply that the NRC inspectors reviewed the documents in their entirety, but rather, that 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 IR. Section 1R01 - Adverse Weather Protection - CARD 09-29842; Increase in

EDG 12 Jacket Coolant Expansion Tank Level; 12/24/2009 - CARD 09-29284;

EDG 14 Jacket Coolant Expansion Tank Level High; 12/04/2009 - CARD 10-26097; Procedure 27.000.06, Hot Weather Operations, suggested timeline not followed; 07/19/2010 - Procedure 27.000.06; Hot Weather Operations; Revision 2

-

WO 27643514; Perform 27.000.06, Attachment 3, Hot Weather System Readiness Review Checklist(s); 11/01/2009

Section 1R04 - Equipment Alignment - Drawing 6M721-5715-3; Standby Feedwater System Functional Operating Sketch; Revision M - Drawing 6M721-5706-3; RHR Service Water Make Up Decant and Overflow Systems; Revision Z - Drawing 6M721-5712-1; Fuel Pool Cooling and Clean Up System; Revision R - Drawing 6M721-5712-2; Fuel Pool Filter Demin System; Revision I

- Drawing 6M721-5729-2, Emergency Equipment Cooling Water (Division II) Functional Operating Sketch; Revision AU - Procedure 23.107.01, Attachment 1; Standby Feedwater System Valve Lineup; 02/22/06 - Procedure 23.708, Attachment 1, FPCCU Valve Lineup; 01/09/07 - Procedure 24.207.02; EECW/EESW Valve Lineup Verification; Revision 42 Section 1R05 - Fire Protection - Drawing 6A721-2401; Fire Protection Evaluation Reactor Building Sub-Basement Plan,

EL 540'0"; Revision L - Drawing 6A721-2402; Fire Protection Evaluation Reactor and Auxiliary Buildings Basement Plan,

EL 562'0"; Revision P - Procedure

FP-RB-B-4d; Reactor Building Basement Southeast Corner Room, Zone 4, EL. 564'0"; Revision 3 - Procedure

FP-RB-SB-2a; Reactor Building Sub-Basement Northwest Corner Room, Zone 2,

EL 540'0"; Revision 3 - Procedure

FP-RB-B-2b; Reactor Building Basement Northwest Corner Room, Zone 2,

EL 562'0"; Revision 3 - Procedure

FP-RB-SB-4c; Reactor Building Sub-Basement Southeast Corner Room, Zone 4, EL. 540'0"; Revision 3 - Procedure

FP-TB; Turbine Building; Revision 7 Section 1R06 - Flood Protection - CARD 07-20204; Flush the Reactor Building Equipment Drain and Floor Drain Header Piping; 01/12/2007

Attachment - CARD 10-24512; Watertight Penetration Seals; 06/02/2010 - CARD 10-26737; Develop PMs for the Electrical Manhole Dewatering Pumps; 08/04/2010

- CARD 10-27087; NQA Surveillance Report 10-1006 Reveals Programmatic Breakdown of the Manhole Dewatering System Maintenance and Monitoring Strategies; 08/14/2010 - CARD 10-27671; Compensatory Actions Identified for Manhole Dewatering System - Update Weekly PST Event MH03; 08/31/2010 - Design Specification 3071-128-EG; Electrical Engineering Standard Specification Boxes; Revision AK - Drawing 5E721-2837-10C; Class 1 Conduit Support Tabulation Sheet Reactor Building

EL 562'-0" Basement; Revision E - Drawing 5E721-2837-10D; Class 1 Conduit Support Tabulation Sheet Reactor Building

EL 562'-0" Basement; Revision E - Drawing 5I721-2612-32; Auto Temp Control System, Panel H21 P537; Revision L

- Drawing 5I721-2612-27; Auto Temp Control System, Panel H21P532; Revision L - Drawing 6E721-2838-10F; Class 1 Conduit As-Built Install Sect. Power, Control and Instrumentation Reactor Building S.E. Quad - El 540'-0" & 562'-0"; Revision F - Drawing 6I721-2201-01; Residual Heat Removal Pump "A" E1102C002A; Revision T

- Drawing 6I721-2211-02; Core Spray Pump "B" E2101C001B; Revision I

- Drawing 6I721-2211-09; Core Spray Minimum Flow Bypass Valves A & B; E2150F031A and F031B; Revision Q - Drawing 6I721-2251-12; R/W System Reactor Building Equipment Drain Sump 74, Pumps G1103C037A and B; Revision J - Drawing 6I721-2538-2; Excess Flow Check Valves Test Panels H21-P402C; Revision D

- Drawing 6I721-2838-10B; Class I Conduit As-Built Install Sects Power, Control and Instrumentation Reactor Building N.E. Quad - Elevation 540'-0" and 562'-0"; Revision J - Fermi 2 UFSAR 3.6.2.3.4.1.2; Reactor/Auxiliary Building - Sub-basement Flooding; Revision 16 - Nuclear Plant Event Notification Form; 07/20/2010

- Nuclear Plant Event Technical Data; Drill; 07/20/2010

- Nuclear QA Surveillance Report 10-1006 - Procedure 20.000.01; Acts of Nature; Revision 39 - WO Log; Sumps; 05/15/09 - 05/15/2010

- WO Log; Sump Pumps; 05/15/09 - 05/15/2010

- WO Log; Water Tight Doors; 05/15/09 - 05/15/2010

- WO F547080100; Inspect and Megger the Motor and Associated Motor Leads to the Bucket; 09/13/2008 -

WO 29342619; Lube & Inspect Reactor/Auxiliary Building Water Tight Doors; 12/20/2009 Section 1R07 - Annual Heat Sink Performance - CARD 10-27334;

RB-3 Jib Hoist; 08/23/2010 - CARD 10-27377; Fuel Pool Heat Exchanger B Internal As-Found and As-Left Condition; 08/24/2010 - CARD 10-27378; Documentation of As-found Condition of a FPCCU Heat Exchanger; 08/24/2010 - CARD 20-27379; Green Team ATOM Absence; 08/24/2010 - Fermi 2 Heat Exchanger Program Health Report, First Quarter 2010

- Heat Exchanger IR; FPCCU Heat Exchanger A

-

WR 000Z062740; Replace Channel Cover Gasket Due to Failed PMT; 08/20/12010

Attachment

Section 1R11 - Licensed Operator Requalification Program - Fermi 2 Evaluation Scenario

SS-OP-904-0183; SRVs Inoperable / Jet Pump Failure / RPV Flooding; Revision 4 - Fermi 2 Evaluation Scenario

SS-OP-904-1016; 2B Transformer Leak / Turbine Vibration / Trubine Trip with CF Flashover / ATWS ; Revision 2 Section 1R12 - Maintenance Effectiveness - CARD 08-21741; T23N010B Failed Calibration, AFCC2; 03/12/2008 - CARD 08-22430; Evaluate System T2300 "Primary Containment" for (a)(1) under the Maintenance Rule; 04/11/2008 - Design Basis Document

T23-00; Primary Containment; Revision A

- Maintenance Rule Functional Failure Evaluation, System ID - B3100; 28-Jun-2010

- Maintenance Rule Functional Failure Evaluation, System ID - E5100; 20-Aug-2010 - Maintenance Rule Functional Failure Evaluation, System ID - T2300; 23-Apr-2009 - Root Cause Determination for CARD 08-21741; 04/09/2008

- System Status; System T2300, Primary Containment; Second, Third, and Fourth Quarters 2009, and First Quarter 2010 - Technical Evaluation

TE-T23-08-017; Secondary Containment to Torus Vacuum Breakers Functionality; March 14, 2008 Section 1R13 - Maintenance Risk Assessments and Emergent Work Control - Fermi 2 Plan of the Day; July 14, July 30, August 30, September 1-3, 2010 - Fermi 2 Plan of the Day; July 30, 2010

- Fermi 2 Plan of the Day; September 13, 15, 16,and 17, 2010

- Fermi 2, T+1 Performance Analysis Review, Work Week 1038; 09/13-19/2010

- Scheduled Risk Profile Summary (Week of 8/30/2010

- Scheduler's Evaluation for Fermi 2; 07/12/2010 - Scheduler's Evaluation for Fermi 2; 08/16/2010 - 08/20/2010 - Scheduler's Evaluation for Fermi 2; 08/30/2010 - 09/03/2010

- Scheduler's Evaluation for Fermi 2; 09/03/2010 - 09/09/2010 Section 1R15 - Operability Evaluations - ALC: Archive Narrative Log; 06/11/2010 - CARD 04-24254; Higher than Expected Pressure Drops in Division 1 and 2 EESW; 09/16/2004 - CARD 04-24254-01; Perform Maintenance Necessary to Clean Unit and Restore Original Pressure Drop; 01/31/2005 - CARD 04-24254-02; Clean P4400B001B; 07/01/2005

- CARD 04-24254-03; Inclusion of Temperature Effects on Hx dP; 02/18/2005

- CARD 04-24254-05; Prepare and Issue INPO OER Discussing Cause on EECW Heat Exchanger Plugging; 08/30/2005 - CARD 04-24254-06; Implement Modification to Prevent Channel Plugging; 09/19/2005 - CARD 10-24829;

EDG 11 Upper Crankshaft Thrust Out of Specifications

- CARD 10-25403; Evaluate EECW Heat Exchanger Design Basis Function Concurrent with Fouling from Mayflies - CARD 10-27615; Main Turbine First Stage Pressure Gage Reading Low Out of Green Band; 08/30/2010

Attachment - CARD 10-28090; Reactor Building Superstructure Re-analysis; 09/14/2010 - CARD 10-28350; Structural Welding Code Change Incorporated into Work Order; 09/21/2010

- CARD 10-28359; Reactor Building Crane Clip Identified with Surface Indication; 09/21/2010 - CARD 10-28568; NRC Question with

TE-N21-10-076; 09/27/2010 - Compensatory Monitoring Plan; Reactor Building Crane / Tornado Watch; 09/23/2010

- Design Calculation

DC-6286; EECW HX Performance Requirements with Plugging; Revision 0

- Engineering Change Requests

ECR-36592-1 and

ECR-36592-2; Modification to the Reactor Building Fifth Floor Superstructure Enclosure; Revision 0 -

EDP-29805; Replacement of EECW Heat Exchangers; Revision 0 -

EDP-36591; Installation of Additional Reactor Building Crane Bridge Rail Clips; Revisions B and D -

EDP-36592 and

EDP-36592-1, Modification to the Reactor Building Fifth Floor Superstructure Enclosure; Revision 0 - Engineering Functional Analysis

EFA-T22-10-008; Reactor Building Superstructure Girts; Revision A - Engineering Functional Analysis

EFA-T22-10-009; Reactor Building Crane Rail Clips Underneath the Crane and South Wall Girts; Revision 0 - Fermi Control Room Log - Unit 2; August 30, 2010

- Fermi Operations Conduct Manual MOP05; Control of Equipment; Revision 34 - Fermi Operations Department Expectation

ODE-11; CARD Operability Determination Expectations; Revision 3 -

TCECE-36592-2; Reactor Building Girt Framing Sections and Details; Revision 0

- TCEDP

EDP-36591.001; Installation Sketch, Clip Details; Revision D

- TCEDP

EDP-36591.001; Installation Sketch, New East Crane Rail Clips; Revision D

- TCEDP

EDP-36591.001; Installation Sketch New West Crane Rail Clips; Revision D - Technical Evaluation Number

TE-ANL-10-049; Evaluation and Characterization of Wind Phenomena Against Plant Design; Revision A -

TE-N21-10-076; SBFW Pumps Test Isolation Valve Will Not Open Enough to Allow Sufficient Test Flow Section 1R18 - Plant Modifications - CARD 10-27645; Issues with 20.000.18; 08/31/2010 - Fermi 2 SER; SSER 5.9.5.1; Fire Protection - Fermi 2 UFSAR; 9A.3; Plant Safe Shutdown - Fire Protection Engineering Evaluation

FPEE-05-0012; Manual Action Feasibility Study for

AOP 20.000.18, Revision 36; 07/25/2005 -

ODE-9; Manpower Scheduling; Revision 8

- Procedure 20.000.18; Control of the Plant from the Dedicated Shutdown Panel; Revision 45 Section 1R19 - Post-Maintenance Testing - CARD 10-27297; North TBHVAC Exhaust Fan Vibrating in Excess of Admin Limits during

SOE 10-04 Run; 08/20/2010 - Consumable Materials Evaluation; Nashua, 357N Red Tape; 09/25/1997

- EDP=36506; Modification Testing Requirements; Revision 0

- Procedure 35.106.009; Control Rod Drive Hydraulic Control Unit General Maintenance and Repair; Revision 47 - Procedure 44.030.252; ECCS Reactor Vessel Water Level (Levels 1, 2, and 8), Division 2, Channel B Functional Test; Revision 48 - Procedure 54.000.03; Control Rod Scram Insert Time Test; Revision 51

Attachment - Technical Evaluation; Item

100075145, TAPE,ADHSV,DUCT,2IN,60YD,CLTH,RED;

20040524 - WO A427100100; Replace Division 2 Ads Logic 'B', Channel 'B', High DW Pressure Bypass Relay; 08/02/2010 -

WO 29385678; Perform 44.030.252; ECCS Reactor Water Level 1,2,and 8, Div 2, Channel B, Functional; 08/02/2010 -

WO 30106931; 02-31 2009/2010 HCU Accumulator Replacement; 07/31/2010

-

WO 30107129; 04- (22-31) 2009/2010 HCU Accumulator Replacement; 07/31/2010

-

WO 31624092;

EDP-36506 Reprogram Refuel Platform Section 1R20 - Outage Activities - CARD 10-24856; Foreign Material Located in the Drywell during Forced Outage 10-02; 06/11/2010 - Foreign Material Control Log; Drywell; 06/11/2010

- NSSS Engineering Assessment of Foreign Materials Found in the Drywell as listed in CARD 10-24856 on 06/11/2010; Revision 0 Section 1R22 - Surveillance Testing - Procedure 24.107.03; SBFW Pump and Valve Operability and Lineup Verification Test; Revision 37 - Procedure 24.413.01; Division 1 and 2 Control Center Chilled Water Pump and Valve Operability Test; Revision 34 - Procedure 24.413.03; Control Room Emergency Filter Monthly Operability Test; Revision 35

- Procedure 24.413.04; Division 1 Control Room Emergency Filter Auto Transfer Test; Revision 35 - WO T392060100; Perform 24.413.04 (Partial) for Stroke Time T4100F041; 07/21/2010 - WO Y606090100; Perform 24.413.03 (Partial) PMT for T4100D011; 07/21/2010 -

WO 29173505; Perform 24.404.06 Division 2 LPCI and Torus Cooling/Spray Pump and Valve Operability Test; 07/01/2010 -

WO 29316046; Perform 24.107.03 Section 5.2 SBFW Pump 'A' Flow Test; 07/16/2010

-

WO 29714192; Perform 24.413.03 Section 5.3 Division 1 CCHVAC Monthly 15 Minute Flow Test; 07/21/2010 -

WO 30367070 /

27332674; Perform 24.413.01 Section 5.1 for Dl CCHVAC Chill Water Pump Section 1EP6 - Drill Evaluation - Fermi RERP Drill 2010; July 20, 2010 - Fermi RERP Drill Forms; 09/21/2010 Section 2RS1 Radiological Hazard Assessment and Exposure Controls - CARD 09-26108; High Radiation Area Boundary Violation; August 7, 2009 - CARD 09-28083; Improper Radworker Practice Removing Pipe Cap from Contaminated System; October 15, 2009 - CARD 09-28885; Audit Finding:

Radiation Protection Practices Observed at the Main Control Point Are Not in Accordance with MRP04 - CARD 10-20281; Dose Estimate for Scaffold Build Exceeded; January 12, 2010

- CARD 10-20520; Handling of High Radiation Trash; January 21, 2010

- CARD 10-21079; Unexpected Dose Rates Found in Chemistry Hood Containing Reactor Water Clean-up Resin; February 6, 2010

Attachment - CARD 10-21419; Radiation Area Access Boundary Not Restored After Access; February 26, 2010 - CARD 10-24955; Personnel Violating Radiological Postings per MRP04; June 15, 2010 - CARD 10-27522; Evaluate Radiation Protection Release Log for Supervisor Approval Criteria Investigation; August 27, 2010 - Procedure 23.606; Traversing In-Core Probe System; Revision 31

- Procedure 64.713.050; Source Leak Testing; Revision 9

- Procedure 65.000.515; Receipt, Storage, Inventory, Inspection, and Packing of Radioactive Material Shipping Packages; Revision 15 - Procedure 65.000.519; Radioactive Material Receipt/Source Control; Revision 28 - NRC Form 748; National Source Tracking Transaction Report; January 20, 2009

- Quick Hit Self Assessment:

Access Control for Radiologically Significant Areas;

- March 16, 2009

- Quick Hit Self-Assessment:

ALARA Panning, Access Control and Occupational Exposure Control Effectiveness; September 24, 2009 - Quick Hit Self-Assessment:

ALARA Panning, Access Control and Occupational Exposure Control Effectiveness; July 22, 2010 -

RWWI-043; Shipping Preparation, Oversight and Document Review; November 4, 2009

- Spent Fuel Pool Non-Fuel Inventory; December 11, 2008 - Survey No. 03614-R10; Reactor Building Fuel Pool Component Cooling Unit Room; August 19, 2010 - Survey No.05222-R09; Reactor Water Cleanup Pump Room; September 7, 2009

-

WO 27056593; Perform 64.713.050 Source Leak Test; June 9, 2009

-

WO 27875003; Perform 64.713.050 Source Leak Test; December 4, 2009

-

WO 29101526; Perform 64.713.050 Source Leak Test; May 27, 2010 Section 2RS2 Occupational ALARA Planning and Controls -

CA 09-28096; Locked High Radiation Area Stay Time Tracking; October 15, 2009 -

CA 09-29473; Higher Dose than Budget for High Pressure Core Injection Run; December 11, 2009 - Procedure 63.000.200; ALARA Reviews; Revision 27

-

RWP 10-3007; Drywell Scaffolding; Revision 0

-

RWP 10-3012; Drywell In-Service Inspection Weld Inspections; Revision 0 -

RWP 10-5001; Refuel Floor; Revision 0 - Quick Hit Self-Assessment:

ALARA Panning and Controls; March 16, 2009 Section 4OA1 - Performance Indicator Verification - Archive Narrative Log; 12/01/2009 - 08/02/2010 - Archived Operator Log; 08/01/2009 - 09/01/2009; 11/01/2009 - 12/01/2009; 02/01/2010 - 03/01/2010; and 05/01/2010 - 06/01/2010 - CARD 09-20559; Blown Control Power Fuse Results in Unplanned Division 2 EECW and HPCI Inoperability; 01/28/2009 -

COS 116; Chemistry Laboratory Procedure Use Guidelines; Revision 7

- LCO Log for HPCI; 11/26/2008 - 12/01/2009

- LCO Log; 02/01/2010 - 03/01/2010; 05/01/2010 - 06/01/2010

- MGA03; Procedure Use and Adherence; Revision 20

- MSPI Derivation Report; MSPI High Pressure Injection System; 04/08/2010 - MSPI Derivation Report; MSPI Heat Removal System - RCIC, Unreliability Report; June 2010

Attachment - Procedure 73.714.01; Plant Process Sampling P33-P405A, Reactor Building Sample Panel; Revision 2 - Procedure 76.000.05; Operation of Chemistry Gamma Spectroscopy Systems; Revision 15 - Procedure 76.000.34; Reactor Coolant Analysis; Revision 10 - Reactor Water Total Isotopic Data; June 2009 to July 2010

-

WO 27094435; Perform 24.206.01 RCIC System Pump Operability and Valve Test at 1000 PSIG Section 4OA2 - Identification and Resolution of Problems - Active Operations Challenges Indies; 08/17/2010 - Open Operator Challenges (ODE-006); August 2010 - Operator Burdens; 09/09/2009 - 08/10/2010 - Operator Challenges Average Age; 09/09/2010 - 08/10/2010

- Operator Distractions; 09/09/2009 - 08/10/2010

- OWAs, Additional INPO PI 1; 09/09/2009 - 08/10/2010

- OWAs Equipment Reliability Metric 1; 09/09/2009 - 08/10/2010

- Total Operator Challenges; 09/09/2009 - 08/10/2010 Section 4OA3 - Follow-Up of Events and Notices of Enforcement Discretion - Licensee Event Report 2010-001; Automatic Reactor Shutdown due to Generator Current Transformer Wiring Failure; May 19/2010 - Licensee Event Report 2010-002; Automatic Reactor Scram and Loss of Offsite Power Due to Severe Weather; August 3, 2010 Section 4OA5 - Other Activities - A sample of currently licensed operator medical records - Root Cause Evaluation Report CARD 09-26243, Fermi Licensed Operator Physical Exam Does Not Meet ANSI Standard; August 2009 - Medical Job Familiarization Guide SAP #32011975/42004025; March 23, 2010 - Audit Planning Guide,

APG-25, Operations, Revision 4

- Fermi 2 General Administration Conduct Manual, MGA13, Revision 9, Fermi Medical Requirements.

Attachment

LIST OF ACRONYMS

USED [[]]

ADAMS Agencywide Document Access Management System

ASME American Society of Mechanical Engineers

CAP Corrective Action Program

CA [[]]

RD Condition Assessment Resolution Document

CFR Code of Federal Regulations

EDG Emergency Diesel Generator

EDP Engineering Design Package

EECW Emergency Equipment Cooling Water

EESW Emergency Equipment Service Water

FPC [[]]

CU Fuel Pool Cooling and Cleanup

FP [[]]

EE Fire Protection Engineering Evaluation

HRA High Radiation Area

HVAC Heating, Ventilation, and Air Conditioning

IMC Inspection Manual Chapter IP Inspection Procedure

IR Inspection Report

LER Licensee Event Report

MSPI Mitigating Systems Performance Index

NEI Nuclear Energy Institute NRC U.S. Nuclear Regulatory Commission

OD [[]]

CM Offsite Dose Calculation Manual

OWA Operator Workaround

PI Performance Indicator

RETS Radiological Effluent Technical Specifications

RHR Residual Heat Removal RP Radiation Protection

RPM Radiation Protection Manager

RWP Radiation Work Permit

PI Performance Indicator

SBFW Standby Feedwater TS Technical Specifications

UFS [[]]

AR Updated Final Safety Analysis Report

UHS Ultimate Heat Sink

URI Unresolved Item

VH [[]]

RA Very High Radiation Area

WO Work Order

UNITED [[]]

STATES [[]]

NUCLEA R

REGULA TORY

COMMIS [[]]

SION [[]]

REGION [[]]

III [[]]

2443 WARREN [[]]

VILLE [[]]

ROAD ,

SUITE [[]]

210 LISLE ,

IL 60532-4352 EA-09-267 October 20, 2010 Mr. Jack M. Davis

Senior Vice President and

Chief Nuclear Officer Detroit Edison Company Fermi 2 - 210 NOC

6400 North Dixie Highway

Newport,

MI 48166

SUBJEC T:

FERMI [[]]

POWER [[]]

PLANT ,

UNIT 2

INTEGR ATED

INSPEC [[]]

TION [[]]

REPORT 05000341/2010004 Dear Mr. Davis: On September 30, 2010, the U.S. Nuclear Regulatory Commission (

NRC) completed an integrated inspection at your Fermi Power Plant, Unit 2. The enclosed report documents the results of this inspection, which were discussed on October 6, 2010, with J. Plona, Fermi 2 Site Vice-President, and other members of your staff. The inspection examined activities conducted under your license as they relate to safety and compliance with the Commission's rules and regulations and with the conditions of your license.

The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel. Based on the results of this inspection, no findings were identified. In accordance with

10 CFR 2.390 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 Public Document Room or from the Publicly Available Records System (

PARS ) component of

NRC 's document system (

ADAMS ).

ADAMS is accessible from the

NRC Website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). Sincerely, /RA/ John B. Giessner, Chief Branch 4

Division of Reactor Projects Docket No. 50-341 License No. NPF-43

Enclosure: Inspection Report 05000341/2010004 w/Attachment: Supplemental Information cc w/encl: Distribution via ListServ See Previous Concurrence

DOCUME [[]]

NT [[]]