NRC-08-0057, Enrico Fermi, Unit 1, Annual Report for the 2nd Quarter of 2008
| ML082480261 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 08/28/2008 |
| From: | Plona J Detroit Edison |
| To: | Document Control Desk, NRC/FSME |
| References | |
| NRC-08-0057 | |
| Download: ML082480261 (13) | |
Text
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Joseph H. Plona Site Vice President 6400 N.Dixie Highway, Newport, M1 48166 Tel: 734.586.5910 Fax: 734.586.4172 DTE Energy-August 28, 2008 NRC-08-0057 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 Renort Period Endina June 30. 2008 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, 2008 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. Plona 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 kegion III T. Strong (Michigan Dept of Environmental Quality)
U kA CGiI
USNRC August 28, 2008 NRC 08-0057 Page 2 bcc: J. Austerberry D. Breiding A. Bodipo-Memba C. Byrd W. Colonnello J. Conen L. Goodman K. Hlavaty 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)
Iktl Fermi 1 Annual Report Enclosure to NRC-08-0057 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, 2007 through June 30, 2008 Approved by: Date: ?/- I Lynne S. Goodman Custodian
Fermi I Annual Report Enclosure to NRC-08-0057 Page 2 ENRICO FERMI ATOMIC POWER PLANT. UNIT 1 ANNUAL REPORT JULY 1, 2007 THROUGH JUNE 30, 2008 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 1 Decommissioning Project, during the past twelve (12) months ending June 30, 2008.
In summary, the Fermi 1 staff conducted the required activities in accordance with the Operating License and Technical Specifications. Detroit Edison submitted one Licensee Event Report due to an uncontrolled release of radioactive material slightly above detection limits due to a pipe breach in the Primary Loop #3 when processing sodium. 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, 2007 through June 30, 2008, all monitored Fermi 1 personnel wore thermoluminescent dosimeters as dosimetry of record. Fermi 1 personnel wore electronic dosimeters from July 1, 2007 through June 30, 2008 as secondary dosimetry at Fermi 1. All visitors were appropriately escorted and wore electronic dosimeters as a minimum when entering all Radiologically Restricted Areas.
The accumulative whole body dose from activities associated with Fermi 1, as measured by thermoluminescent dosimeters was 980 millirem for this reporting period.
2.2 Surveillance Pro2ram 2.2.1 Environmental Surveys No liquid radiological releases occurred during this period; therefore, environmental monitoring samples were not required or obtained.
Fermi 1 Annual Report
. Enclosure to NRC-08-0057 Page 3 2.2.2 Weekly Tests and Inspections
- General area --- Fermi 1 Staff performed walkthroughs and visual inspections as required by Technical Specifications.
2.2.3 Monthly Inspections
" Controlled Area Inspections --- Fermi 1 Staff performed 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.
- Fermi 1 Staff performed monthly inspections which identified a number of minor issues during the period. Each was appropriately resolved. The following sump pump issues were identified and resolved:
- Sump pump #4 external float level control switch would hang up against the side of the sump casing. The pump and piping was restrained to keep float from hanging up until Design Change 07-008-DC was implemented in July 2008.
" Sump pump #10 failed due to a failed external float level control switch, the switch was replaced with a new diaphragm switch.
" Sump pump #3 and #5 had degraded wiring due to age. The wiring was replaced.
2.2.4 Ouarterly Surveillances Radiological Surveys --- Fermi 1 Radiation Protection personnel checked the Reactor Building and the Fuel and Repair Building for presence of gamma radiation and beta, gamma, and alpha contamination. The results of the quarterly contamination surveys indicated general area walkways remained <500-dpm/!100 cm 2 beta/gamma and <20-dpm/1 00-cm 2 alpha until May 20, 2008 when a Loop #3 pipe breach event occurred. The Reactor Building, Fuel and Repair Building, and trestleway were contaminated to 500-dpm/100 cm 2 beta/gamma.
Fermi 1 personnel decontaminated the Reactor Building, Fuel and Repair Building, and trestleway general areas to <500-dpm/l100 cm2 beta/gamma and
<20-dpm/100-cm2 alpha.
3.0 DECOMMISIONING PROJECT The Fermi 1 Decommissioning Project continued during this period. Fermi 1 personnel continued with the sodium cleanup.
Fermi 1 Annual Report Enclosure to NRC-08-0057 Page 4 Reactor Rotating Shield Plug activities included:
Completed the removal of the Offset Handling Mechanism plug from the reactor.
Completed the removal of rings from the top of the reactor.
Lifted and cut the Offset Handling Mechanism shaft.
Completed the removal of the sweep mechanism equipment above the rotating shield plug cover plate.
Completed the removal of the stainless steel encased graphite cans and steel from the Offset Handling Mechanism plug shell.
Completed the removal of the contents of the rotating plug, which made up the top -10 feet of the reactor vessel. This effort took months to complete, since it involved removal of thousands of graphite blocks, metal sleeves, chinkers and metal plates.
Completed the installation of the reactor cover plate.
Fermi 1 personnel completed the removal of the neutron source from the reactor and:
Processed the neutron source to remove any potential sodium residues.
Stored the neutron source temporarily within shielded stand on the Reactor Building operating floor until its shipment.
Shipped neutron source to Barnwell Waste Management Facility in Barnwell, South Carolina on February 6, 2007.
Fermi 1 personnel modified the Sodium Building temporary effluent system in preparation for more extensive future decommissioning activities.
Fermi 1 personnel modified the Fuel and Repair Building temporary effluent system in preparation for higher activity future decommissioning activities.
Fermi 1 Staff conducted periodic groundwater sampling during this period to obtain information for license termination planning. Fermi 1 Staff detected no plant related isotopes.
3.1 Sodium Cleanup During the reporting period, continued sodium cleanup activities which included:
Fermi 1 sodium processing crew processed residual sodium in batches of pipe and equipment inside the sodium reaction chamber.
Fermi 1 sodium processing crew processed the rod extensions and gripper assemblies from the reactor within the individual shielded pipes (rod pods).
Fermi 1 Annual Report Enclosure to NRC-08-0057 Page 5 Fermi 1 personnel continued to work on cutting and grinding graphite blocks that were removed from the reactor rotating plug which may contain sodium based on sample population results.
Reactor Vessel sodium processing activities included:
Fermi 1 personnel completed the physical setup for processing the reactor.
The Fermi 1 sodium processing crew used a detailed procedure and a detailed work request with instructions to:
Perform system valve lineups.
Leak test the reactor system.
Ensure the reactor atmosphere was inert.
Energize the original reactor vessel heaters.
Heat the reactor vessel to a temperature to ensure the sodium was molten.
Monitor reactor vessel temperature using the originally installed thermocouples.
After meeting the setup criteria Fermi 1 sodium processing crew performed the final checks per the procedure, and started the actual sodium reaction with steam.
After the sodiumreactions were completed, steaming was finished on April 13, 2007.
The heating and steaming phases took close to a month to complete, which was dependent on the sodium reactions.
Fermi 1 personnel modified the system and then carefully flooded the reactor with water.
Fermi 1 sodium processing crew recirculated the caustic liquid after flooding, and then neutralized the liquid with acid.
Fermi 1 sodium processing crew performed two evolutions of draining the reactor, by repeating the flooding, recirculating, neutralizing and draining steps to obtain greater assurance that all sodium was reacted. These evolutions took several weeks to complete.
Fermi 1 sodium processing crew completed draining the reactor of water that could be drained using the installed pump.
Fermi 1 Annual Report Enclosure to NRC-08-0057 Page 6 Primary Sodium Loop #3 The Fermi 1 sodium processing crew started the processing procedure for Loop #3 after performing the final system checks.
A pipe breach occurred while processing Loop #3, allowing molten sodium, caustic and nitrogen to leak from the system. Fermi 1 sodium processing crew immediately shut down the Loop #3 sodium processing. Additional details are located in section 5.3, "Licensee Event Report 08-001" of this report.
Fermi 1 personnel performed repairs, modifications and caustic cleanup due to the Loop #3 pipe breach.
Fermi 1 personnel performed radiological decontamination cleanup activities due to the Loop #3 pipe breach.
At the end of the reporting period, Fermi 1 personnel had addressed identified issues and were performing final checks prior to restarting system heating and processing.
3.2 Radiological Surveys Fermi 1 Radiation Protection personnel encountered no unexpected radiological conditions during this reporting period until May 20, 2008 when the Loop #3 pipe breach occurred. Radiation Protection personnel performed extensive radiological surveys covering the exposed areas within the plant, then decontaminated the Reactor Building, Fuel and Repair Building, and trestleway general areas to <500-dpm/100 cm2 beta/gamma and <20-dpm/100-cm2 alpha.
3.3 Radiological Shipments Fermi 1 personnel 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 Shipment Activity ShipmentionGross Volume Weight Gross Number Description Destination Category (mCi) (ft3) (Ibs)
Contaminated Limited EF1-07-009 UnTech Inc. Morris, IL 1.06 117.6 1838 Laundry Quantity EFI-07-010 Samples General Engineering Lab, LLC Limited 2.44E-04 0.1 5 Charleston, SC . Quantity 2.4E-4_ 01_
Contaminated Limited EF1-07-011 Laundry UniTech Inc. Morris, IL Quantity _ 0.99 117.6 134
Fermi 1 Annual Report Enclosure to NRC-08-0057 Page 7 Contaminated .. Limited EFI-07-013 CotLaundry UniTech Inc. Morris IL Quantity 1.0297 117.6 1647 EF107014 Contaminated U Limited 1.01 117.6 1847 EFI__07_014 Laundry UnTech Inc. Morris IL Quantity 1.1 176 14 Smear General Engineering Lab, LLC Limited EF1-07-015 Samples Charleston, SC Quantity 5.74E-04 2 10 Contaminated Limited EFL-07-017 UniTech Inc. Morris IL. 1.06 235.2 2612 Contaminated Limited 104 176 11 EF 1-07-018 Laund UniTech Inc. Morris IL it1.064 117.6 1813 EF10709 Laundry Contaminated Unlc n.Mri LQuantity Limited 104 176 18 EF 1-07-019 Contaminated UniTech Inc. Morris IL Limited 1.014 117.6 1883 Laundry Quantity Contaminated Limited0 EF1-07-020 Laundry UniTech Inc. Morris IL Quantity 1.045 117.6 1720 Contaminated Limited EFI-07-021 Laundry UniTech Inc. Morris IL Quantity0.996 118 1694 Laundry Quantity EFI-07-0 122 Contaminated UniTech Inc. Morris IL Limited 6.02 119 8742 EFI-07-023 Contaminated UniTech Inc. Morris IL Limited 1.84 11 806 Laundry Quantity Laundry Contaminated Quantity Limited5.9 988 EF1-07-024 Laundry UniTech Inc. Morris IL tity.84 9 8 Contaminated Limited EFI-07-026 UniTech Inc. Morris IL L1.05 118 1859 Laundry Quantity Contaminated Limited EF1-07-026 Laundry UniTech Inc. Morris, IL Quantity10.05 118 1591 EFI-07-027 ta EUniTech Inc. Morris IL 6.08 59 891 Laundry Quantity EF1-07-028 DAW/ Metal Energy Solutions BWF, Clive LSA 142 680 40,000 Waste Utah DAW/ Metal Energy Solutions BWF, Clive LA10 60 4,0 EFI1-07-029 Waste Utah LA10 60 4,0 EFI-07-030 DAW/Metal Energy Solutions BWF, Clive LSA 50.4 1080 38,236 Waste Utah EFI-07-031 Contaminated UniTech Inc. Morris IL Limited 11.15 118 1743 Laundry Quantity EF1-08-001 DAW/Metal Energy Solutions BWF, Clive LSA 60 680 12,500 Waste Utah Contaminated Limited121 1873 EFI-08-002 EF10802 Laundry UniTech Inc. Morris IL Qunity Quantity 12.1 118 1736
Fermi 1 Annual Report Enclosure to NRC-08-0057 Page 8 EFI-08-003 DAW/Metal Energy Solutions BWF, Clive. LSA 195 1752 25,245 Waste Utah Depleted EF1-08-004 Neutron Barnwell Waste Management LSA 674 15.9 4,327 Source as Facility, Barnwell SC Waste EF1-08-006 Contaminated Energy Solutions Bear Creek LSA 16.1 641.7 41,565.7 Salt Water Facility, Oak Ridge TN Contaminated Limited EFI-08-007 C Laundry amnate UniTech Inc. Morris IL Limite Quantity 10.84 118 1632 EFI-08-008 Contaminated Energy Solutions Bear Creek LSA 18.2 647.16 42,344 Salt Water Facility, Oak Ridge TN EF 1-08-009 Contaminated UniTech Inc. Morris IL Limited 11.76 118 1814 Laundry Quantity EF1-08-010 Contaminated UniTech Inc. Morris IL Limited 23.26 236 3530 Laundry Quantity EFContminate Limited169 77 28 EFI-08-011
______ Contaminated Laundry UniTech Inc. Morris IL Quantity Qatt 16.9 177 2428 Contaminated Limited EF1-07-026 Laundry UniTech Inc. Morris, IL Quantity 10.05 118 1591 Contaminated Limited6.8 589 EF 1-07-027 Laund Laundry UniTech Inc. Morris IL it6.08 Quantity 59 891
- EFI-07-028 DAW/ Metal Energy Solutions BWF, Clive LSA 142 680 40,000 Waste Utah EF1-08-012 DAW/Metal Energy Solutions BWF, Clive Waste Utah LSA 145 276 33,935 EF1-08-013 DAW/Metal Energy Solutions BWF, Clive LSA 77.4 1656 19,528 Waste Utah Contaminated Limited EFI-08-014 L UnTech Inc. Morris IL 10.62 59 786 EFI-08-015 Air & Smear Framatome AREVA, Limited 1.12E-03 1 Samples Westborough MA Quantity EFI-08-016 Contaminated UniTech Inc. Morris IL Limited 11.88 118 1587 Laundry Quantity Contaminated Limited 1.4 18 18 EF1-08-017 Laundry Laundry UniTech Inc. Morris IL ity12.34 Quantity 118 1789 EFI-08-012 DAW/Metal Energy Solutions BWF, Clive LSA 145 276 33,935 Waste Utah EFI-08-013 DAW/Metal Energy Solutions BWF, Clive LSA 77.4 1656 19,528 Waste Utah
Fermi 1 Annual Report Enclosure to NRC-08-0057 Page 9 4.0 RADIOLOGICAL EFFLUENTS Fermi 1 Radiation Protection personnel recorded no unmonitored radiological gaseous or particulate effluent releases during the reporting period except on May 20, 2008 when a Loop #3 pipe breach occurred (LER 08-001). Fermi 1 Radiation Protection personnel determined no particulate releases occurred during the reporting period with the exception of the May 20, 2008 Loop #3 pipe breach. Fermi 1 Radiation Protection personnel determined the majority of measurable releases were associated with the sodium removal project. The maximum dose to an offsite member of the public from these releases was 9.01 E-7 mrem total effective dose equivalent from tritium. The total activity of tritium released was 1.84 mCi.
Including the conservatively calculated dose due to the May 20, 2008 event of 3.98 E-6 mrem, results in a maximum dose to an offsite member of the public of 4.88E-6 mrem. The gaseous effluent releases were below the Technical Specification air dose limit of 10 mrad of gamma radiation and 20 mrad of beta radiation per year.
The individual dose calculated due to gaseous effluent releases was below the Technical Specification air dose limit of 5 mrem Total Effective Dose Equivalent.
50.59 EVALUATIONS AND DESIGN CHANGES 5.1 10 CFR 50.59 One 10 CFR 50.59 screening conducted during this period determined that a 50.59 evaluation was required:
08-001-SE - 50.59 Evaluation for processing sodium residues in the reactor vessel.
Summary:
The change evaluated is the as-left condition after processing reactor vessel sodium residues. The current conditionis that the reactor vessel contains sodium and contamination deposited on its internal surfaces and the sodium storage tanks contain contaminated liquid. The as-left condition following the change is that the sodium will have been converted to sodium hydroxide and hydrogen gas. The hydrogen gas will have been vented; the reactor will have been flooded and subsequently drained.
The liquid will have been drained to the sodium storage tanks. The majority of contamination will remain in the reactor vessel, some activity will have been contained in the liquid drained to the storage tanks, some activity will have been deposited in filter(s) in the liquid transfer path, some activity will have been deposited in the effluent system filters, and some activity will have been deposited on components in the processing system. Some activity, primarily tritium, will have been released to the environment through the effluent system. The activity potentially available for release is greater than analyzed in the F 1SAR for a catastrophic event.
Fermi 1 Annual Report Enclosure to NRC-08-0057 Page 10 The increase in consequences of an accident was determined to be no more than minimal, and no other 50.59 criteria are affected, so NRC approval is not required.
5.2 Design Changes Fermi 1 Staff did not implement any formal design changes during this report period.
Fermi 1 personnel continued the removal of abandoned systems using work request documents per the Fermi 1 Quality Assurance Program.
5.3 Licensee Event Reports Fermi 1 Licensee Event Report 08-001 (Summary)
Detroit Edison submitted a Licensee Event Report as required by Fermi 1 Technical Specifications Section F.7 as a condition reportable in accordance with Section A.4.
At approximately 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br /> on May 20, 2008, while processing sodium in Primary Loop #3 using inerted superheated steam, a sodium fire occurred at a small pipe breach. When Fermi 1 personnel observed the fire, they terminated sodium processing and the fire was out in 10 minutes.
Portable air sampling for radioactivity was performed within the Fermi 1 Steam Generator Building, Fuel and Repair Building, and outdoors adjacent to the facility immediately following the event. Radiation Protection personnel recorded sampling data results that indicated an unplanned release of radioactive material from the facility slightly above detection limits had occurred during the event.
Four selected samples were sent to an offsite lab to determine if any hard to detect nuclides were released. Lab results showed only Cs-137 was detected. The Licensee Event Report had conservatively assumed Strontium-90 to also be released pending offsite laboratory analysis results.
Radiation Protection personnel used data from the sample results, effluent system discharge samples, and monitoring in the Fuel and Repair Building to estimate a total release from the pathways in the Fuel and Repair Building, Steam Generator Building, and trestleway. There was no detectable release through the Reactor Building effluent filtration system. The total release was calculated to be 16.2 RCi Cs-137 for a total dose to any individual at the site boundary of 3.98 E-6 mrem committed effective dose equivalent.
Fermi 1 Staff estimated the release duration to be approximately two hours based on the air monitor indication in the Fuel and Repair Building. For comparison purposes, if the release had continued for a full year, the dose to any individual at or beyond the
Fermi 1 Annual Report Enclosure to NRC-08-0057 Page 11 site boundary would still have been less than that allowed by Fermi 1 Technical Specification Section C.2 limit for dose due to gaseous effluents.
An evaluation team determined the cause of the pipe breach to be from high temperatures. The failed pipe was a 2" line installed to allow draining the 14" and 16" pipe sections of Primary Loop #3, which contained a large quantity of sodium, into a larger 30" pipe to be processed. The high temperature in the drain line occurred during subsequent steam processing (reacting) of the remaining sodium in the 16" pipe. Sodium overflowed into the 2" drain line while processing the 16" pipe which had not been anticipated, therefore, the temperature control, monitoring, and procedural controls were not adequate.
Fermi 1 Staff used the Corrective Action Program to implement corrective actions including procedure revisions, drain pipe modifications and sealing some building openings to minimize potential out leakage from the Reactor Building during sodium processing evolutions.
6.0 AUDIT SUBCOMMITTEE The Audit Subcommittee inspected the physical facility and reviewed the Technical Specification surveillance records during the reporting period. The Audit Subcommittee did not identify any significant problems.
All audit reports are maintained on file.