Text

July 30, 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 05000341/2010003

Dear Mr. Davis:

On June 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 inspection findings, which were discussed on June 28, 2010, with T. Conner and other members of your staff. The inspection examined activities conducted under your license as they relate to safety and to 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, one NRC-identified finding of very low safety significance was identified. The finding involved no violation of NRC requirements. If you contest the subject or severity of this finding, 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 a copy to the Regional Administrator, U.S. Nuclear Regulatory Commission - Region III, 2443 Warrenville Road, Suite 210, Lisle, IL 60532-4352; the Director, Office of Enforcement, U.S. Nuclear Regulatory Commission, Washington, DC 20555 0001; and the Resident Inspector Office at the Fermi Power Plant. In addition, if you disagree with the cross-cutting aspect assigned 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 Power Plant. In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely,/RA by M. Kunowski Acting for/

R. Orlikowski, Acting Chief Branch 4 Division of Reactor Projects Docket No. 50-341 License No. NPF-43

Enclosure:

Inspection Report 05000341/2010003

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: 05000341/2010003 Licensee: Detroit Edison Company Facility: Fermi Power Plant, Unit 2 Location: Newport, MI Dates: April 1 through June 30, 2010 Inspectors: R. Morris, Senior Resident Inspector R. Jones, Resident Inspector D. Betancourt, Reactor Engineer J. Bozga, Reactor Engineer M. Learn, Reactor Engineer V. Meghani, Reactor Inspector M. Mitchell, Health Physicist J. Neurauter, Senior Reactor Inspector B. Palagi, Senior Operations Engineer J. Rutkowski, Senior Resident Inspector, Davis-Besse C. Scott, Reactor Engineer J. Tapp, Health Physicist

Approved by: R. Orlikowski, Acting Chief Branch 4 Division of Reactor Projects Enclosure

SUMMARY OF FINDINGS

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

REPORT DETAILS

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

REACTOR SAFETY

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

OTHER ACTIVITIES

....................................................................................................... 124OA1Performance Indicator Verification (71151) ............................................... 124OA2Identification and Resolution of Problems (71152) .................................... 134OA3 Follow-Up of Events and Notices of Enforcement Discretion (71153) ....... 154OA5Other Activities .......................................................................................... 164OA6 Management Meetings .............................................................................. 19

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee

J. Plona, Site Vice-President

T. Conner, Plant Manager

M. Caragher, Director, Nuclear Engineering

R. Johnson, Manager, Licensing

J. Korte, Manager Nuclear Security

C. Walker, Director, Organization Effectiveness

R. Buehler, Fatigue Management Administrator

S. Hanson, Licensing Engineer

R. Salmon, Supervisor Compliance / Licensing Nuclear Regulatory Commission

J. Giessner, Chief, Branch 4

R. Orlikowski, Acting Chief, Branch 4

LIST OF ITEMS

OPENED, CLOSED AND DISCUSSED Opened and Closed 0500341/2010003-01 FIN Failure to Adequately Control Loose Materials near the Switchyard

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 inspection report. Section 1R04 - Equipment Alignment - Design Basis Document E21-00; Core Spray System; Revision C - Drawing 6M721-5708-1; High Pressure Cooling Injection System Functional; Revision AL - Drawing 6M721-5709-1; Reactor Core Isolation Cooling Functional; Revision AK - Drawing 6M721-5737; SGTS Functional Operating Sketch; Revision P

- Procedure 23.202; HPCI RCIC System Valve Lineup; Revision 101

- Procedure 23.206; Attachment 1; RCIC System Valve Lineup;

020309

- Procedure 23.404, Attachment 1; SGTS Initial Valve Lineup;

042309 Section 1R05 - Fire Protection - CARD 10-23318; NRC question related to beam pocket coverage in computer room (Zone 13); 04/20/2010 - Fire Protection Pre-Plan

FP-TB, Turbine Building; Revision 7

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FP-RB-SB-4a; HPCI Pump and Turbine Room, Zone 4; Revision 4 - USFAR 9A.2; Methodology - Fire Hazards Analysis; Revision 16 - UFSAR 9A.4.1.4; HPCI and Turbine and Control Rod Drive Pump Room, Fire Zone 03RB; Revision 16 - UFSAR Figure 9A10; Fire Protection Evaluation Reactor and Auxiliary Buildings Fifth Floor Plan; Revision 14 Section 1R06 - Flood Protection - Drawing 5-046-15-096-014; No. 15096 "CPR" Exchanger Assembly - Photos;

EDG 11 Lo HX R 3001B002, Control Side Bottom

- Sketch; Typical EDG HX Channel Head to Tube Sheet/Shell Joint Section 1R07 - Annual Heat Sink Performance - CARD 10-23300;

EDG 11 heat exchanger trend cleaning; 04/19/2010 - CARD 10-23325; Exposed gasket material on

EDG 11 lube oil cooler channel gasket; 04/20/2010 Section 1R11 - Licensed Operator Requalification Program - Event Notification, Unusual Event; Abnormal Red Level/Radiological Effluents Fermi IC Number; AU2; Plant Message Number 001; 04/20/2010 -

SS-OP-904-1100; Fire/MT Trip/Pressure Regulator Failure/SCRAM/SC Leak -

SS-OP-904-1101; CRD Pump Failure/RR Pump Walkaway/ Fuel Failure/MT Vibration; Revision 2 - Procedure 24.202.08; HPCI Time Response and Pump Operability test at 1025 PSI; Revision 3

Attachment

Section 1R12 - Maintenance Effectiveness - CARD 10-20637; The corrective actions to address CARD 06-10300, N3021 Maintenance Rule (a)(1) status have not been completely effective; 01/26/2010 - Maintenance Rule Functional Failure Evaluation; System ID: T4102; May 18, 2010 Section 1R13 - Maintenance Risk Assessments and Emergent Work Control - Fermi 2, License Amendment No. 149, Revision to Control Room Emergency Filtration System Requirements - Fermi 2 Plan of the Day; Wednesday, May 12, 2010

- Maintenance Rule Conduct Manual, MMR APP E; Maintenance Rule SSC Specific Functions; Revision 7 - NRC TAC No. ME3930; Fermi 2 - Issuance of Emergency Amendment Regarding One-Time Extension of the Completion Time for Technical Specification 3.7.3, "Control Room Emergency Filtration (CREF) System," (Condition B; May 15, 2010) - Plan of the Day; 04/19/2010; 05/25/2010; and 06/10/2010 - Risk Profile Summary; Week of 04/24/2010 - Risk Profile Summary; Week of 05/10/2010

- Risk Profile Summary; Week of 05/17/2010

- Risk Profile Summary; Week of 05/29/2010

- Risk Profile Summary; Week of 06/12/2010 - Scheduler's Evaluation for Fermi 2; 04/19-24/2010 - Scheduler's Evaluation for Fermi 2; 05/24-28/2010

- Scheduler's Evaluation for Fermi 2; 06/7-12/2010

- TS; 3.7.3, Control Room Emergency Filtration System; Amendment 149 Section 1R15 - Operability Evaluations - CARD 10-22696; Impact of Impairments to Drywell Coolers #10 and 11 - CARD 10-23155; AOV Margin Issue at Low NIAS Air Pressure System Isolation; 04/14/2010Receiver Size and SBGT - CARD 10-23476; MSO Issue - RHR Flow Diversions; 04/26/2010

- CARD 10-24065; Failure of the T4F092B SOV for the T4100F069A Division 2 CCHVAC Heating Coil Shutoff Damper; 05/16/2010 - CARD 10-24617; ARP 4D121 - 345 kV Breaker Position CFR Open - Design Basis Document T47-00; Drywell Cooling System; Revision A

- Drawing 6M721-5736-3; Control Center A/C Air System; Revision I

-

FP-GSW-1-31; General Service Water Pumphouse Zone 31; Revision 7

- ODMI 09-007B, Impact of Drywell Fan 10 being off

- Operator Required Reading Index Sheet; Package 10-04-10; 04/30/10 -

TE-T47-09-051; Impact of Impairments to Drywell Coolers #10 and 11; Revision D - UFSAR 6.4-6, 9.4-3, 9.4-5; Revision 16 Section 1R18 - Plant Modifications - 50.59 Evaluation No. 10-0095; Replacement of the existing analog T41K14CCHVAC static pressure controller manufactured by Air Monitor with new digital controller manufactured by Siemens (formerly Moore Products); Revision 0

Attachment - CARD 10-22991; Division 2 CREF not maintaining main control room pressure positive; 04/07/2010 - Drawing I-2612-11; Auto Tem Control System Control Panel H21P296B Front Sub Panel; Revision 0 - Drawing I-2612-77; Special Channel Base for Control Panel H21-P296A and P296B; 04/10/10 - Drawing I-2612-77A; Mounting Bracket Details for Pressure Controller T41K414

- Drawing I-2613-63; Control System Control Panel H21P296B Point-to-Point Wiring Diagram; Revision 0 - Drawing I-2613-62; System L/D for Static Pressure Cont. Control Room Panel H21P296B; Revision 0 -

EDP-36457; Upgrade CCHVAC Static Pressure Controller from Analog to Digital; Revision B

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EDP-36457; Index Item No. 005, Rev 0; Replacement of existing analog T41K414CCHVAC static pressure controller manufactured by Air Monitor with new digital controller manufactured by Siemens (formerly Moore Products); Revision B -

EDP-36457, Index Item No. 006; Modification Testing Requirements; Revision B -

EDP-36457; Index Item No. A001; General; Revision B

-

EDP-36457; Index Item No. B005; ETAP Load Data Entry Form; Revision B

-

EDP-36457; Index Item No. B006; Air Monitor Electronic Perfectron; Revision B

-

EDP-36457; Index Item No. B008; Seismic Qualification Test Report Moor Models 352 and 353; Revision B -

EDP-36457; Index Item No. B010, Rev 0; Panel H21P296B; Revision B

-

EDP-36457-1; Upgrade CCHVAC Static Pressure Controller from Analog to Digital; Revision 0

- Letter

NRC-10-0047; Proposed Emergency License Amendment for a One-time Extension of the Completion Time in Technical Specification 3.7.3, "Control Room Emergency Filtration

(CREF) System, Condition B; 05/14/2010 - Temporary Modification 10-0019; Install a plate to cover hole in fan housing where the fan shaft protrudes on the Division 2 Control Room West Return Air Fan T4100C030; Revision 0 Section 1R19 - Post-Maintenance Testing - CARD 10-23977; High Vibration Division 2 CCHVAC Return Fan; 05/12/2010 -

WO 31022276; Perform Mini Periodic MOV Inspection and VPM Stroke Test (When Required); 03/09/2010 -

WO 31022429; Perform Mini Periodic MOV Inspection and VPM Stroke Test; 03/09/2010

-

WO 31022435; Perform Mini Periodic MOV Inspection and VPM Stroke Test; 03/09/2010

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WO 31272982; Inspect and Replace Division 2 CCHVAC Return Air Fan Inboard Bearing; 05/12/2010 - WO Y750120100; Inspect AB/RB Buildings Metal Siding Fasteners, Replace if Broken or Missing; 06/09/2010 -

WR 31294288; Added additional PMT's to check contact function of E51A-K15 relay during performance of 44.020.231; 05/18/2010 Section 1R20 - Outage Activities - Procedure 22.000.01; General Operating Procedure, Plant Startup Master Checklist; Revision 63

Attachment

Section 1R22 - Surveillance Testing - Procedure 24.000.02, Attachment 1; Eight Hour - Mode 1,2,3 - Control Room - Procedure 27.109.01, LPSV/LPIV Test, (routine); - Procedure 27.207.04, Division 2 EECW Throttled Valve Flow Verification (routine); - Procedure 24.202.08, HPCI Time Response and Pump Operability Test (in-service testing); and - Procedure 43.401.206, Sections 6.1 and 6.2, LLRT for Airlock T2301.A001D (PCIV).

-

WO 27068887; Perform 27.207.04 Division 2 EECW Throttled Valve Flow Verification; 05/06/2010 -

WO 29013899; Perform 27.109.01 Section 5.7 thru 5.12 LPSV?LPIV Test; 05/07/2010 Section 1EP6 - Drill Evaluation - Nuclear Plant Event Notifications; Plant Messages 1 - 10; 05/12/2010

Section 4OA1 - Performance Indicator Verification - RCS Operational Leakage 3.4; Amendment No. 134 - Safety System Functional Failures MS05; 05/20/2010 Section 4OA2 - Identification and Resolution of Problems - CARD 09-28823; Control Center HVAC not maintaining pressure >.125 inches water with D2 CCHVAC in recirculation; 11/13/2009 - CARD 09-28823 - System Engineering NSSS; Control Center HVAC not maintaining pressure >0.125 inches water with D2 CCHVAC in emergency recirculation mode; 12/07/2009 - Effectiveness Review CARD 09-28823-09; 02/18/2010

- Equipment Apparent Cause Evaluation Guide Template; Control Center HVAC not maintaining pressure >0.125 inches water with D2 CCHVAC in Emergency Recirculation Mode; 11/13/2009 - Fermi 2 Equipment Reliability; April 10, 2010 - Fermi 2 Equipment Reliability Excellence Plan; June 30, 2011 - Nuclear Engineering Performance Indicators - May 2010; June 15, 2010

- System Health Fermi 2; Drywell Cooling; First Quarter, 2010

- System Health Fermi 2; Reactor Recirculation system; First Quarter, 2010 Section 4OA3 - Follow-Up of Events and Notices of Enforcement Discretion - WO Y750120100; Inspect AB/RB Buildings Metal Siding "Fasteners, Replace if Broken or Missing"; 06/16/2010 - Procedure 20.000.01; Abnormal Operating Procedure, Acts of Nature; Revision 39 Section 4OA5 - Other Activities - CARD 08-26161; Wood in switchyard; 09/19/2008 - CARD 10-24570; NRC Concern with Tarp Covering Rebar Near the 345 kvV Switchyard; 06/03/2010 - Operations Training and Qualification Program Description

QP-OP-914-0009; Operations Orientation; Revision 7 - Personnel Qualifications for RERP Radiological Emergency Teams,

42001591; 06/03/2010

Attachment -

QC-OP-725-0100; Reactor Operator; Revision 14 -

QC-OP-725-0200; Senior Reactor Operator Upgrade; Revision 10

-

QC-OP-725-0400; Senior Reactor Operator Instant; Revision 9 -

QP-ER-665; Selection, Training and Qualification Description; Revision 33 -

QP-OP-915-0001; Reactor Operator Program Description Flowchart; Revision 4

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QP-OP-915-0002; Senior Reactor Operator Program Description Flowchart; Revision 5

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QP-RC-912-0004; Chemistry Technician Task to Training Crossmatrix; Revision 7 - RERP Plan, Table B-1; Staffing for Fermi 2 Emergency Response Organization; Revision 38

Attachment