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Category:DECOMMISSIONING PLANS
MONTHYEARML20247G8691989-04-30030 April 1989 Preliminary Final Decommissioning Plan for Fermi 1 1989-04-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217N4381999-10-25025 October 1999 Safety Evaluation Supporting Amend 17 to License DPR-9 ML20217P3551999-10-22022 October 1999 LER 99-S01-00:on 990922,loaded 9mm Handgun Was Discovered on Truck Cargo Area of Vehicle Inside Protected Area.Caused by Inadequate Vehicle Search.Guidance in Procedures & Security Training to Address Multiple Vehicle Searches Was Provided NRC-99-0095, Monthly Operating Rept for Sept 1999 for Fermi 2.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Fermi 2.With NRC-99-0067, Monthly Operating Rept for Aug 1999 for Fermi 2.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Fermi 2.With NRC-99-0065, Monthly Operating Rept for July 1999 for Fermi 2.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Fermi 2.With NRC-99-0088, Detroit Edison Co Enrico Fermi Atomic Power Plant,Unit 1 Annual Rept for Period 980701-990630. with1999-06-30030 June 1999 Detroit Edison Co Enrico Fermi Atomic Power Plant,Unit 1 Annual Rept for Period 980701-990630. with NRC-99-0064, Monthly Operating Rept for June 1999 for Fermi 2.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Fermi 2.With NRC-99-0062, Monthly Operating Rept for May 1999 for Fermi 2.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Fermi 2.With ML20206J9301999-05-10010 May 1999 SER Concluding That Util Adequately Addressed Actions Requested in GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Powered-Operated Gate Valves ML20206G5081999-05-0505 May 1999 Safety Evaluation Approving Request for Relief PR-8,Rev 2 on Basis That Licensee Committed to Meet All Related Requirements of ASME OM-6 Std & PR-12 on Basis That Proposed Alternative Will Provide Acceptable Level of Safety NRC-99-0022, Monthly Operating Rept for Apr 1999 for Fermi 2.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Fermi 2.With ML20205Q7141999-04-15015 April 1999 Safety Evaluation Supporting Amend 16 to License DPR-9 ML20205P9721999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Fermi 2 ML20204E0371999-03-17017 March 1999 Safety Evaluation Accepting Licensee Request for NRC Approval of Alternative Rv Weld Exam,Per Provisions of 10CFR50.55a(a)(3)(i) & 10CFR50.55a(g)(6)(ii)(A)(5) for Plant,Unit 2 for 40-month Period ML20204D0361999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Fermi 2 ML20198S3341999-01-0606 January 1999 Safety Evaluation Supporting Amend 15 to License DPR-9 NRC-99-0005, Monthly Operating Rept for Dec 1998 for Fermi 2.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Fermi 2.With ML20207B7491998-12-31031 December 1998 1998 Annual Operating Rept for Fermi 2 ML20205Q9621998-12-31031 December 1998 Revised Monthly Operating Rept for Dec 1998 for Fermi 2 NRC-99-0021, 1998 Annual Financial Rept for Detroit Edison Co. with1998-12-31031 December 1998 1998 Annual Financial Rept for Detroit Edison Co. with NRC-98-0153, Monthly Operating Rept for Nov 1998 for Fermi 2.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Fermi 2.With NRC-98-0160, Monthly Operating Rept for Oct 1998 for Fermi 2.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Fermi 2.With ML20154R2331998-10-21021 October 1998 Safety Evaluation Supporting Amend 13 to License DPR-9 ML20154L1031998-10-14014 October 1998 Safety Evaluation Accepting Licensee Response to NRC Bulletin 95-002, Unexpected Clogging of Residual Heat Removal Pump Strainer While Operating in Suppression Pool Cooling Mode NRC-98-0139, Monthly Operating Rept for Sept 1998 for Fermi,Unit 2.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Fermi,Unit 2.With ML20154H8161998-09-30030 September 1998 Rev 0 to COLR Cycle 7 for Fermi 2 ML20153B8811998-09-18018 September 1998 Safety Evaluation Accepting Request for Relief from Certain Requirements of ASME Boiler & Pressure Vessel Code,Section Xi,For Plant,Unit 2 ML20151X0651998-09-11011 September 1998 Safety Evaluation Re Inservice Testing Program Relief Request VR-63 for Plant NRC-98-0111, Monthly Operating Rept for Aug 1998 for Fermi 2.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Fermi 2.With ML20153B7921998-08-31031 August 1998 Rev 0 to Fermi 1 Sar ML20237E1171998-08-25025 August 1998 Safety Evaluation Accepting Licensee Relief Requests for First 10-yr Interval Inservice Insp Nondestructive Exam Program ML20236X8611998-08-0505 August 1998 SER Related to Revised Feedwater Nozzle Analysis to Facility Operating License NPF-43,Enrico Fermi Nuclear Power Plant, Unit 2 NRC-98-0109, Monthly Operating Rept for July 1998 for Fermi 21998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Fermi 2 ML20236K3261998-07-0101 July 1998 SER Accepting Licensee Response Related to Revised Feedwater Nozzle Analysis to License NPF-43 for Enrico Fermi Nuclear Power Plant,Unit 2 NRC-98-0097, Monthly Operating Rept for 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Pump & Valve Inservice Testing Program Per 10CFR50.55a(f)(6)(i) for First 10-yr Interval NRC-98-0015, Monthly Operating Rept for Dec 1997 for Fermi 21997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Fermi 2 ML20217N3821997-12-31031 December 1997 Annual Operating Rept for 970101-1231 NRC-98-0053, 1997 Annual Financial Rept for Detroit Edison Company1997-12-31031 December 1997 1997 Annual Financial Rept for Detroit Edison Company ML20205Q9601997-12-31031 December 1997 Revised Monthly Operating Rept for Dec 1997 for Fermi 2 NRC-97-0141, Deficiency Rept Re Malfunction of EDG Number 11 Automatic Voltage Regulator (AVR) Printed Circuit Board Rev B,Due to Failure of Operational Amplifier U8 Chip.Avr Board Rev B Was Sent Offsite to Independent Engineering Facility1997-12-23023 December 1997 Deficiency Rept Re Malfunction of EDG Number 11 Automatic Voltage Regulator (AVR) Printed Circuit Board Rev B,Due to Failure of Operational Amplifier U8 Chip.Avr Board Rev B Was Sent 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, . ,1 PRELIMINAIN FINAL DECCM4ISSIONING PIAN EQB FEIMI 1 APRIL, 1989
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NBC-89-0100 Page 2 INTRODUCTION Fermi 1 was initially decommisaloned according to Atomic Energy Commission (ABC) rules and directives in effect at the time. A decommissioning plan (retirement program) was submitted to the ABC and was approved in November 1973. Decommissioning activities were initiated in October 1972 and completed in October 1975. These activities are discusse.J in detail in " Retirement of the Enrico Fermi Atomic Power Plant", NP20047, and Supplement 1, NP20047, Power Reactor Develognent Company, March 1974 and October 1975.
The purpose of this Preliminary Final Decommissioning Plan for Fermi 1' is to state Detroit Edisen's intentions regarding the ultimate decommissioning of Fermi 1. Detroit Edison is planning on a SAFS70R period to be followed by a final decommissioning to achieve a rzeliologically releasable site and termination of the Nuclear Regulatory Cammission (NBC) license. It is expected that final decommissioning for the Fermi l plant will be performed concurrently with that for Fermi 2.
This Preliminary Final Decommissioning Plan is strictly an overview of the final decommissioning effort. It would be premature at this time to detail decontamination methods or the specific organization to be used for the final decommissioning staff. Prior to commencement of the final decommissioning effort, a detailed plan will be prepared and submitted to the NRC in accordance with 1(CFR50.82.
PIANNING Prior to the end of the SAFS70R period, detailed planning will be conducted for the final deccumissioning effort. A detailed radiological characterization will be conducted during the final decommissioning planning. The characterization will include an extensive plant radiation survey and sampling of remaining plant systems, structures, site soil, the plant outfall, and other areas associated with plant operation. During the SAFS70R period, routine plant radiation surveys and environmental monitoring will be corducted. This information will also be used for the radiological characterization.
Various methodologies will be evaluated for the decontamination and such dismantling activities as may be feasible and necessary. The state-of-the-art methodologies at the time of the Fermi l final decommissioning may be considerably different from those available today. Therefore, the processes to be used will be selected at that time. It is expected that several methodologies will be utilized
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Page 3 dependent on the specifics of the item being decontaminated or dismantled.
Following coupletion of the iliological characterization and planning for the final decommissioning effort, a detailed plan will be submitted to the NIC.
ORGANIZATION An organization will be established to conduct the final decommissioning effort. The responsibility for the project will remain with Detroit Edison though a part of the work and project management may be performed by outside contractors. The Fermi 1 Review Committee is expected to continue overview of the facility.
SAFETY A radiation protection program and an industrial health and safety program will be implemented during the final decommissioning period.
It is expected that these programs will be continuations of the ones conducted during SAFS'IOR. The programs will be modified as necessary to cover the increased scope of work during the final decommissioning project.
All major decommissioning activities will be performed as controlled pre-planned evolutions. The safety of the public and of the workers will be considered throughout the final decommissioning effort.
The basic goal of the industrial health and safety program will be to ensure the health and safety of Detroit Edison and contract workers.
The program will encompass actions to both control and monitor the hazards to which workers are exposed. Special precautions will be planned for handling of residual sodium and asbestos.
The basic goal of the radiation protection program will still be to ensure the health and safety of the workers and of the public. The philosophy of maintaining dose to the workers As Low As P.e"onably Achievable (ALARA) will continue to be followed. The pros.a Will continue to enconpass actions to both control and monitor radiation exposure to workers.
RADIOACTIVE WASTE MANAGDENT A radioactive waste management program will be implemented during the I final decommissioning project to handle the waste produced by the decommissioning effort. Temporary facilities will be established as necessary.
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l- Contaminated waste generation will be maintained as low as possible so l
that the volume requiring disposition as radioactive waste is minimized. Disposal of all waste will be in accordance with applicable regulations.
FRTIR0tMENI'AL IMPACT In September 1987, Detroit Edison submitted a report entitled
" Supplemental Environmental Information, Enrico Fermi Atomic Power Plant, Unit 1". This document discussed the incremental environmental impacts, radiological and non-radiological, that would be expected over a 40-year SAFS10R period at the Fermi 1 site. l As part of the final deccrnmissioning effort, a review will be conducted and any significant incremental environmental impacts associated with the planned effort will be addressed and submitted as a supplement to the 1987 report. -
COST A decommissioning study will be performed to estimate the cost of achieving a radiologically releasable facility and a submitte. made by July 1990 describing the funding mechanism in accordance with 10CFR50.75.
SITE RELFASE Following completion of the planned decommissioning activities, a final radiological survey of the site and associated areas will be conducted to verify that all residual Fermi 1 generated radioactivity levels are within established limits. The radiological characterization which has been performed will be used to help determine the selection of survey and sample locations. Specific attention will be paid to areas at which any spills occurred during j plant life. If any areas are identified to be above the established j limits, additional actions will be taken to reduce the residual i radioactivity.
The disposition of any structures remaining after the residual -
radioactivity levels are within established limits will depend on what activities Detroit Edison chooses to perform at that time. The remaining facilities may be used for other purposes or selectively demolished.
A final report will be submitted to the NFC following completion of a final satisfactory radiological survey.
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