NRC-09-0051, Enrico Fermi Atomic Power Plant, Unit 1 - Annual Report Period Ending June 30, 2009

Enrico Fermi Atomic Power Plant, Unit 1 - Annual Report Period Ending June 30, 2009

ML092520033
Person / Time
Site:	Fermi
Issue date:	08/27/2009
From:	Plona J DTE Energy
To:	Document Control Desk, NRC/FSME
References
NRC-09-0051
Download: ML092520033 (10)

Text

Joseph H. Plona Site Vice President 6400 N.Dixie Highway, Newport, MI 48166 Tel: 734.586.5910 Fax: 734.586.4172 DTE Energy-August 27, 2009 NRC-09-0051 U. S. Nuclear Regulatory Commission Attn.: Document Control Desk Washington, D.C. 20555

Reference:

Enrico Fermi Atomic Power Plant, Unit 1 NRC Docket No. 50-16 NRC License No. DPR-9

Subject:

Enrico Fermi Atomic Power Plant, Unit 1 Annual Report Period Ending June 30, 2009 Pursuant to Section 1.8 (Reporting Requirements) of the Technical Specifications for Provisional Operating License No. DPR-9, the annual report for the period ending June 30, 2009 for the SAFSTOR Fermi 1 facility is enclosed.

Should you have any questions, please contact Lynne S. Goodman, Manager, Fermi 1 at 734-586-1205.

Sincerely, Joseph H. Pona Site Vice President, Nuclear Generation JHP/BD/ljd Enclosure cc:, NRC Regional Administrator, Region III T. Smith, NRC (Washington, D.C.)

NRC Resident Inspector- Fermi 2 P. Lee, NRC Region III T. Strong (Michigan Dept of Environmental Quality)

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• USNRC NRC-09-0051 August 27, 2009 Page 2 bcc: J. Austerberry D. Breiding A. Bodipo-Memba C. Byrd W. Colonnello J. Conner J. Conen L. Goodman K. Lindsey R. Nearhoof D. Niemeyer J. Robinson S. Stasek J. Thorson T. VanderMey Fermi 1 Staff Information Management (140 NOC) - Fermi 1 Records NRR Chron File (Licensing)

NRC Notebook (Fermi 1)

Fermi 1 Annual Report 2009 Enclosure to NRC-09-0051 Page 1 DETROIT EDISON COMPANY ENRICO FERMI ATOMIC POWER PLANT, UNIT 1 Docket No. 50-16 License No. DPR-9 Annual Report for Period July 1, 2008 through June 30, 2009 Approved by: Date: / &

Lynne S. Goodman Custodian

Fermi 1 Annual Report 2009 Enclosure to NRC-09-0051 Page 2 ENRICO FERMI ATOMIC POWER PLANT. UNIT 1 ANNUAL REPORT JULY 1, 2008 THROUGH JUNE 30, 2009 1.0 PREFACE This report provides a summary of the activities performed and the results of the facility surveillance program of the Enrico Fermi Atomic Power Plant, Unit I Decommissioning Project, during the past twelve (12) months ending June 30, 2009.

In summary, required activities were conducted in accordance with the Operating License and Technical Specifications. Fermi 1 continues decommissioning activities with the removal of contaminated components as well as residual sodium to achieve license termination.

2.0 SAFSTOR STATUS 2.1 Health Physics 2.1.1 Personnel Exposure From July 1, 2008 through June 30, 2009, all monitored Fermi 1 personnel wore Thermoluminescent Dosimeters (TLDs) as dosimetry of record. Electronic Dosimeters (EDs) were worn from July 1, 2008 through June 30, 2009 as secondary dosimetry at Fermi 1. All visitors were appropriately escorted and wore EDs as a minimum when entering all Radiologically Restricted Areas (RRA).

The accumulative whole body dose from activities associated with Fermi 1, as measured by TLDs, was 2275 millirem for this reporting period.

2.2 Surveillance Program 2.2.1 Environmental Surveys No liquid radiological releases occurred during this period; therefore, environmental monitoring samples were not required or obtained 2.2.2 Weekly Tests and Inspections

• General area --- The Fermi 1 staff performed walk through and visual inspections as required by Technical Specifications.

2.2.3 Monthly Inspections

• Controlled Area Inspections --- The Fermi 1 staff conducted visual inspections of the fences, gates, and doors within the specified intervals and surveyed the water level in the sump from the top access of all active sumps.

• Monthly inspections identified a number of minor issues during the period. The Fermi 1 team appropriately resolved the issues.

• Reattached loose Sodium Building weather flashing

Fermi 1 Annual Report 2009 Enclosure to NRC-09-0051 Page 3

• Radiation Sign temporarily covered by a fire blanket during hot work, removed fire blanket after the hot work activities (no. access issues resulted from this discrepancy)

• Sump pump #4 would not pump, replaced the pump

• Barrier fence rip-rap rock disturbed during crane activities, replaced the rip-rap rock 2.2.4 Ouarterly Surveillances Radiological Surveys --- The Radiation Protection technicians checked the Reactor Building and the Fuel and Repair Building (FARB) for presence of gamma radiation, as well as beta, gamma, and alpha contamination. The results of the quarterly contamination surveys indicated general area walkways remain <500-dpm/100 cm2 beta/gamma and <20-dpm/100-cm2 alpha.

3.0 DECOMMISSIONING PROJECT The Fermi 1 Decommissioning Project continued during this period. Sodium cleanup and Reactor vessel disassembly is discussed below.

The Fermi 1 staff collected one set of groundwater monitoring wells samples to obtain information for license termination planning. No plant related isotopes were detected.

3.1 Sodium Cleanup During the reporting period sodium cleanup activities continued and included:

0 Completed the sodium processing of the primary loops, heat exchangers and pumps

• Completed processing the last batch of sodium containing pipe and equipment in the reaction chamber

• Continued remediating sodium from graphite blocks that were removed from the reactor vessel rotating plug NaK filled instrument lines have been removed from the Reactor Building basement and processing continued 3.2 Radioactive Liquids

• Commenced evaporating batches of radioactive liquid produced during sodium processing

• Commenced evaporating batches of the remaining radioactive liquid from the FARB Liquid Waste System inside a 55 gallon drum evaporator located in the FARB 3.3 Reactor System Components e Removed the Rotating Plug from the reactor vessel and stored it on the Reactor Building operating floor

Fermi 1 Annual Report 2009 Enclosure to NRC-09-0051 Page 4

" Removed the Hold-down Mechanism from the reactor vessel and shipped the mechanism for disposal

" Removed the Offset Handling Mechanism and the core sweep assembly from the reactor vessel

" Filled the lower reactor vessel with grout

• Commenced cutting primary system piping from the Intermediate Heat Exchangers and Primary Sodium Pumps

" Commenced removing steel shot and bars, graphite blocks and asbestos from the Primary Shield Tank

• Removed embedded piping in the Inert Gas Building 3.4 FARB

• Completed cutting up the Sodium Transfer Tanks 0 Commenced dismantling the fuel pool bridge cranes

• Commenced dismantling the radwaste control room

• Disassembled the Radwaste Pump Room equipment

• Removed approximately 59,000 lbs of steel shot from penetrations in the liquid radwaste rooms

• Commenced cutting up the tanks and equipment in the liquid waste tank room 3.5 Radiological Surveys No unexpected radiological conditions were encountered during this reporting period.

Technicians performed characterization surveys as part of the license termination planning. Technicians also performed surveys in the areas that were excavated for the site cable vault project work and lighting installation that are located within the Fermi 1 footprint.

3.6 Radiolo2ical Shipments The Fermi 1 team shipped the following materials offsite from Fermi 1 during the reporting period. Tools and equipment shipped to Fermi 2 are not included in this table.

Shipment Material Number Description EF1-08-014 Contaminated UniTech, Morris IL Laundry Framatome - AREVA, EF1-08-015 Samples Westborough MA

Fermi 1 Annual Report 2009 Enclosure to NRC-09-0051 Page 5 Activity Volume Goss Weight Gross Shipment Material Shipment Number Description Destination Category (mCi) (ft3) (lbs)

EF1-08-016 Contaminated UniTech, Morris IL LQ .11.88 118 1,587 Laundry Contaminated EF1-08-017 Laundry Laundry UniTech, Morris IL LQ 12.34 118 1,789 EF1-087018. DAW/Metal Energy Solutions BWF, LSA 139 720 34,950 Waste Clive UT EF1-08-019 Contaminated UniTech, Morris IL LQ 18.82 177 2,746 Laundry EFI-08-021 Contaminated UniTech, Morris IL LQ 18.03 177 2,557 Laundry Control Rod Energy Solutions BWF, EF1-08-022 Cg LSA 3,270 36.36 946.5 Extensions Clive UT DAW/Metal Energy Solutions BWF, LSA 133 1,256 19,840 EF1-08-023 & Graphite Clive UT Can Waste EF1-08-024 Contaminated UniTech, Morris IL LQ 12.68 118 1,926 Laundry EF1-08-025 Contaminated UniTech, Morris IL LQ 18.15 177 2,539 Laundry EF-08-026 D

&AConcretel W/M e tal E n r y Solutions Energy S l t o s BWF, LSA 41.8 670 32,405 B VF EF1-8-06& oncete Clive UT Waste EF1-08-027 Filter Unit Energy Solutions, NSSF SCO 19.76 100 1,220 Barnwell SC EF1-08-028 Contaminated UniTech, Morris IL LQ 12.48 118 1,845 Laundry EF1-08-029 Contaminated UniTech, Morris IL LQ 12.15 118 1,722 Laundry DAW/Metal EF1-08-030 & Upper Energy Solutions BWF, LSA 61.7 641 27,165 Control Rod Clive UT Extensions EFV-08-031 EmptyVanSea UniTech, Morris IL EMPTY NA NA 8,000 EFI-08-032 Samples Gel Laboratories, LQ 2.68E-04 1 15 Charleston SC EF1-08-033 Contaminated UniTech, Morris IL LQ 11.52 118 1,422 Laundry EF1-09-001 Reactor Hold Energy Solutions, Bear Creek LSA 9,880 208 60,000 Down Mech. Operations, Oak Ridge TN EF1-09-002 DAW/Metal Energy Solutions BWF, LSA 17.7 1464 33,535 Waste Clive UT

Fermi 1 Annual Report 2009 Enclosure to NRC-09-0051 Page 6

• Volume Shipment Activity Goss Weight Gross Shipment Material Description Destination Category (mCi) Gross Gross Number (ft3) (lbs)

EF1-09-003 DAW/Metal Energy Solutions BWF, LSA 22.7 960 38,584 Waste Clive UT EFI-0-004 Contaminated EFI-09-004 Laundry UniTech, Morris IL LQ 11.52 118 1,422 EFl-09-005 Samples Gel Laboratories, LQ 3.49E04 1 7 Charleston SC Reactor Hold Energy Solutions BWF, EF1-09-006 Down Mech Cne utiLSA 147 670 25,784 Shaft _Clive IUT EFI-09-007 DAW/Metal Energy Solutions BWF, LSA 13.8 1368 20,400 Waste Clive UT EF1-09-008 Contaminated UniTech, Morris IL LQ 0.45 118 1,832 Laundry EFI-09-009 Steel Shot Energy Solutions Bear Creek LSA 15.9 670 41,750 Operations, Oak Ridge TN EF1-0-010 Contaminated EFL-09-010 UniTech, Morris IL LQ 0.907 236 3,625 Laundry EFI-09-011 Contaminated UniTech, Morris IL LQ 2.5 118 1,985 Laundry EFI-09-012 CotmntdUniTech, Morris IL LQ 2.32 118 1,777 Laundry EFl-09014 DAW/Metal Energy Solutions BWF, LSA 4.53 670 22,120 Waste Clive UT EF1-09-015 DAW/Metal Energy Solutions BWF, LSA 58.3 3840 176,617 Waste Clive UT EF1-09-016 Contaminated Laundry UniTech, Morris IL LQ 3.81 177 3,150 BWF - Bulk Waste Facility NSSF - Nuclear Services Support Facility 3.7 License Termination Plan

• The Fermi 1 staff completed and submitted the Fermi 1 License Termination Plan to the NRC. The plan describes the remaining work and how the facility will be surveyed to determine that the license termination criteria are met. The License Termination Plan also includes a historical review, cost estimate update and environmental assessment.

" The NRC accepted the Fermi 1 License Termination Plan for review.

• The NRC held a public meeting on June 30, 2009 on the Fermi 1 License Termination Plan in Monroe, Michigan.

Fermi 1 Annual Report 2009 Enclosure to NRC-09-0051 Page 7 4.0 RADIOLOGICAL EFFLUENTS There were no unplanned radiological gaseous effluent releases during the reporting period. All measurable releases were associated with the sodium removal project.

The maximum dose to an offsite member of the public from these releases was 2.41E-6 mrem Total Effective Dose Equivalent (TEDE) from tritium. The total amount of tritium released .was 4.9 mCi. The gaseous effluent releases were below the Technical Specification air dose limit of 10 mradof gamma radiation and 20 mrad of beta radiation per year. The individual dose calculated due to gaseous effluent releases was below the Technical Specification dose limit of 5 mrem Total Effective Dose Equivalent.

5.0 50.59 EVALUATIONS, DESIGN CHANGES AND LER's 5.1 10 CFR 50.59 The Fermi 1 team conducted one 10 CFR 50.59 evaluation during this period.

Screenings determined that 50.59 evaluations were not required for other activities.

08-050-SE, 50.59 Evaluation for cutting and removing the reactor vessel Summary:

This 50.59 evaluation supports the work request for diamond-wire cutting or plasma arc cutting the reactor vessel and removing it for shipment and disposal.

The current condition is that the reactor vessel is in place with the neutron source removed and sodium residues processed, such that some internal contamination remains in the reactor vessel prior to starting this activity. Following cutting and removal of the reactor vessel, the only reactor vessel activity that remains would be contained in other parts of the primary system that are still in place, the liquid in the primary sodium storage tanks, some activity may be deposited in filter(s) until they are disposed, and some activity deposited on components in the Slurry/Water Collection and Containment systems until they are removed and/or disposed.

The diamond-wire cutting or plasma arc cutting and removal of the reactor Yessel was evaluated against the FISAR, Rev. 5 to determine whether this activity could result in higher accident dose rates or whether the current accident calculations bound reactor vessel removal.

The reason these calculations were performed in support of this 50.59 is that some of the contamination detected by smearing the reactor vessel could be released by this segmentation effort, plus cutting the activated metal of the reactor vessel creates particulate that could be available for release in an accident. Previously, activated reactor vessel radionuclides were considered immobile and not available for release in any postulated accident. The diamond wire saw cooling liquid, liquid filter(s), and air filter(s) have the potential to be contaminated with activated stainless steel cutting fines. Calculations determined that the existing FISAR, Rev. 5 accident analyses bound the cutting operations for the case of a liquid release of the water used to cool the diamond wire cutting operation, an airborne accident due to evaporation during a

Fermi 1 Annual Report 2009 Enclosure to NRC-09-0051 Page 8 liquid release, and direct airborne accident due to release of all removed contamination and activated fines activity directly to the air.

Note that after this 50.59 evaluation was approved, the Reactor Project team decided to change the wire cooling media to carbon dioxide. Personnel are performing a revision to this 50.59 evaluation.

5.2 Design Changes The Fermi 1 team implemented design change, 07-008-DC, which modified East and West Sodium Gallery Sumps #3 and #4 discharge piping to combine the discharges into a heat traced common discharge.

Removal of abandoned systems continued using work request documents per the Fermi 1 Quality Assurance Program.

5.3 Licensee Event Reports There were no Licensee Event Reports during this reporting period.

6.0 AUDIT SUBCOMMITTEE The Audit Subcommittee inspected the physical facility and reviewed the Technical Specification surveillance records during the reporting period. No significant problems were identified.

All audit reports are maintained on file.