ML20235J427
| ML20235J427 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 09/30/1987 |
| From: | DETROIT EDISON CO. |
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| Shared Package | |
| ML20235J388 | List: |
| References | |
| NUDOCS 8710010442 | |
| Download: ML20235J427 (68) | |
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{{#Wiki_filter:U.S. Nuclear Regulatory Commission Docket No. 50-16 NRC License No. DPR-9 i i l Su a alemental Environmental In"ormation I Enrico rermi Atomic Power Plan':, Jnit1 l I l u 1 cry.
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U.S. Nuclear Regulatory Commission Docket No. 50-16 NRC License No. DPR 9 Su 3plemental Environmental In"ormation ! Enrico Fermi Atomic Power Plant, Unit 1 ;
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SUMMARY
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This report provides supplemental environmental' information on the i decommissioned Enrico Fermi Atomic Power Plant, Unit 1,~ located on an 1120-acre site approximately 30 miles southwest.of Detroit on Lake , Erie, in Lagoona Beach, Frenchtown Township,. Michigan.- The site is -f l shared with Fermi 2, a 3294 Mw(t)-General Electric boiling water reactor licensed to operate at 100% of rated power. Fermi 1 was a 200 Mw(t),' sodium-cooled, fast breeder reactor that operated at essentially atmospheric pressure. Fermi 1 received a' low-power operating license in May 1963 and was last operated at power September 1972. 't the request of the AEC, Power Reactor Development Company decided to decommission the facility in November 1972. The decommissioning effort was initiated in October 1972 with the . dismantling and shipping of the radioactive fuel and blanket -] subassemblies offsite. The effort was completed in 1975 when mechanical components had been shipped offsite, plant areas decontaminated, contaminated areas sealed, a restricted area boundry established, and surveillance began in accordance with Technical Specifications. The proposed action to continue the SAFSTOR of Fermi 1 for 40 years will not cause a significant environmental impact and will result in a l reduction of dose rate and personnel exposure at the time of final action and will minimize the risk to the health and safety of the public. l i 1 1 i ! l . i l SEPTEMBER, 1987- ! E_ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
TARIR OF CONTENTS ., i LIST OF TABLES............................................. 111 LIST OF FIGURES........ ....................................iv
1.0 INTRODUCTION
........................................ 1.1 l 2.0 DECOMMISSIONING.0F FERMI'1........................'.. 2.1
2.1 DESCRIPTION
OF THE PLANT..................... 2.1 2.2 DECOMMISSIONING ACTIVITIES................... 2.4 23 DECOMMISSIONING COSTS........................ 2.8
- 30 ENVIRONMENTAL ASSESSMENT............................ 31 31 NON-RADIOLOGICAL IMPACTS..................... 31 32 RADIOLOGICAL' IMPACTS......................... 3 3 4.0 ALTERNATIVES CONSIDERED............................. 4.1 1
4.1 .DEC0N........................................ 4.1 4.2 ENT0MB....................................... 4.2 43 SAFST0R...................................... 4.2
5.0 CONCLUSION
S.................,,....................... 5.1
6.0 REFERENCES
.......................................... 6.1-APPENDIX 1: FERMI 1 STATUS l 11 l
LIST'0F TABLES. Table Title M , 1.1 CHRONOLOGICAL HISTORY OF THE FERMI I PROJECT...... 1 3 2.1 . RADI ATION AND SURFACE CONTAMINATION LEVELS...... .. 2.9
- 2.2 CALCULATED STAINLESS STEEL ACTIVATION IN REACTOR VESSEL - JUNE 1,.1973..................... 2.12 L
l l 23 FINAL DECOMMISSIONING COST........................ 2.13 31 1980 DISTRIBUTION.0F ESTIMATED POPULATION......... 3 13 32 DISTRIBUTION 0F PROJECTED POPULATION IN YEAR 2000......................................... 3 14 FERMI 1 PERSONNEL EXPOSURE EXPERIENCE, j 33 3 15
^
PERSON-REM........................................ 34 TOTAL NUCLIDE INVENTORY (CURIES).................. 3 17 1 1 35 RADIATION AND SURFACE CONTAMINATION 3 18 LEVELS - 1986..................................... 36 ISOTOPIC ACTIVITY AND DOSE RATE PROJECTION........ 3 20 ) l l l 3 iii
1 0 4 LIST OF FIGURES
. Figure M Title 2.1 PLANT. LOCATION................................... 2.15 2.2 FERMI SITE.............................'.......... 2.16 l .-
23 PLOT PLAN OF FERMI'.1 PLANT SITE................'.. 2.17 2.4 FERMI 1 FACILITY LAY 0UT.......................... 2.18 , 2.5 - FERMI 1 RESTRICTED AREA BOUNDRY.................~.2.19' _ _ _ _ _ _ - . _ _ _ _ _ _ _- - _ - _ - =
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1.0 INTRODUCTION
On May 17, 1985, Detroit Edison submitted to the NRC an application to amend the Possession Only license (License No. DPR-9) for.the.Enrico. Fermi Atomic Power Plant, Unit 1 (Fermi 1) to reflect an extension of 40 years to expire in March 2025 (Reference 1). In addition to the request for additional information (Reference 2) there.has been correspondence (References 3, 4, 5, 6, and 7) and a meeting with the NRC staff.concerning the request to provide environmental information pursuant to 10CFR51.45(b). This document is in response to' Reference 7 and addresses the environmental. aspects of the current status of the decommissioned Fermi 1. Fermi 1 was a 200 Mw(t), sodium-cooled, fast breeder reactor that operated essentially at atmospheric pressure. The plant was developed under the AEC Power Demonstration Program and was constructed, owned, and operated by Power Reactor Development Co. (PRDC). PRDC was assisted by Atomic Power Development Associates, Inc. (APDA), who carried out the research and development, the conceptial design, and operated a facility to test the vital components of the reactor. Both of these companies consisted of member companies uho financed the project with some aid from the AEC. A chronologitsi history of the j Fermi 1 project is presented in Table 1.1. Many of the details l surrounding this history can be found in FERMI 1, New Age for Nuclear Power published.in 1979 by the American Nuclear Society. The Fermi 1 decommissioning was ordered via a letter directive from the AEC, L. Manning Huntzing, issued. March 31, 1972 that stated
...an itemization of estimated costs to place the reactor in the proposed decommissioned condition (including costs to package, l transport, and reprocess fuel and costs for j burial of the axial and tadial blankets), and ,
a statement of the assumptions made in 1 arriving at these costs to maintain the j reactor in a proposed decommissioned ! condition. These estimated costs should be based on a proposed plan for decommissioning , and maintenance of the plant in perpetuity. ! The final plans for decommissioning Fermi 1 were submitted to the AEC in September 1973 Since there were no guidelines available from the ; AEC associated with the decommissioning of a sodium-cooled reactor, l studies were conducted by the AEC and PRDC to determine the disposition ; of the irradiated blanket elements and radioactive primary system ' sodium, 1 i 1.1 ' l
I The primary objective of the decommissioning was to perform the ) activities within the funds allocated such that the health and safety-
'of the public was protected at all times. Decommissioning was accomplished through the provisions of 10CFR50.59 and a series of Technical Specification changes and is documented in detail in.two reports issued by PRDC (Reference 8). The major retirement activities and plan for maintenance'of the plant in perpetuity are summarized as o Return of leased' enriched uranium to AEC, Savannah River Plant. j i
o Offsite disposition of blanket subassemblies. ! 1 o Offsite disposition of radioactive and non-radioactive j sodium. j o Passivation of residual sodium, o Disposal of contaminated equipment and mater!als.. 1 o Fencing facility o Surveillance (Technical Specifications). ! o Retention of legal and other significant documents, o Establishment of administrative controls for authorized entry ! into restricted areas, preparation of reports, and general ) l custodial functions. i The present status of Fermi 1 is described in Appendix 1. l l 1.2
1 Table 1.1 - CHRONOLOGICAL HIS'IDRI OF THE FERMI 1 PROJECT l I 1950, October 30 Formation of Dow Chemical-Detroit Edison Study Noup. .j 1954, August 30 Atomic Energy Act of 1954 became law. ; I 1955, January.16 AEC Power Demonstration Program initiated. 1 1955, March 10 Incorporation of APDA. 1955, March 30- Filed proposal to develop a fast breeder reactor under AEC Demonstration Program. 1955, August 8 Proposal to AEC accepted during First Geneva Conference. 1955, August 30 Incorporation'of.PRDC. 1956, January 6 PRDC . filed application for construction permit to erect a fast breeder reactor at Lagoona Beach, Michigan. 1956, April 30 crade and fill work started at site. i 1956, August 4 AEC issued construction permit to PRDC. 1956, August 8 Groundbreaking ceremony.. 1956, August 31 UAW, IUE, and UPA filed petition for intervention before l AEC; case docketed as.F-16. I 1958, December to AEC issued order confirming previously issued construction permit. I 1959, July 25 AFL-CIO appealed to U.S. Court of Appeals asking that ( construction permit be set aside. 1960, June 10 Court of Appeals by 2-1 decision set aside AEC. . construction permit on grounds of illegal departure from. statutes and regulations. 1960, August 12 PRDC filed petition for certiorari with Supreme Court asking that it reverse the decision of Court of Appeals. 1961, June 12 U.S. Supreme Court reversed _ Court of Appeals and confirmed AEC construction permit. 1963, May 10 AEC issued 1-Hw operating license, subject to final inspection by Division of Compliance. 1963, August 23 First criticality of Fermi and start of low-power tests. 13 _________i____---_-_--_--_ - - ]
i. 1964, March 12 Application filed with AEC for license to operate'up to 200 Mw (t). 1965, December 17 Operating license issued to PRDC by-AEC DRL. (License j No. DPR-9) 1966, July 8 First'100-Mw(t) operation.- , L 1966, October 5 Fuel melting incident; plant became inoperative.for 3 years and 9 months.- 1 1970, February 10, PRDC granted permission to load fuel and resume operations up.to 200Mw(t). 1970, July'18 Criticality achieved. Reactor power level of 200 Mw(t) reached. 1970, October 16 1970, November Proposal'to AEC for oxide core. l Master plan for continued operation using oxide core;- 1970, December beginning of attempt to fund $50 million program. 1971, November 20 to December 1 10-day high-power operation logging 1660 Mwd (t). 1972, June 9 AEC ordered PRDC to show cause: (1) why its request for extension of expiration-date of Provisional Operating License DPR-9 should not be denied, and (2) why PRDC should not suspend operation at. Fermi, submit a dismantling plan, and prepare,to implement it. 1972, August 28 AEC determined that PRDC was not financially qualified to warrant extension of its license and set the matter for a hearing. 1972, Sept. 15-22 Last plant operation at low power for operator licensing examinations. 1972, November 27 Decision by PRDC Executive Committtee to decommission. 1973, September 24 Submission to AEC of retirement plan. 1973, November AEC approval of decommissioning plan. 1974, March Retirement of the Enrico Fermi Atomic Power Plant, Report NP-20087 (PRDC) 1975, October Retirement of the Enrico Fermi Atomic Power. Plant, Report NP-20047, Supplement 1 (PRDC) 1.4-
1975, December 31 Decommissioning completed and PRDC dissolved. 1976, January 3 Transfer of License No. DPR-9; possession only from PRDC , to Detroit Edison.. 'l
, 1984, November Completion of. shipment of primary sodium to ANL,
'Scovile, Idaho. .
1985, May 17 Amendment' request for. extension of the Possession only license for Fermi.1 for 40 years'to expire March 2025. l 1 1
.y
't 1.5
2.0 DECOMMISSIONING OF FERMI 1 ,
2.1 DESCRIPTION
OF THE PLANT 2.1.1 General Description Fermi 1 is located on an 1120 acre site approximately 30 miles southwest of Detroit on Lake Erie, in Lagoona' Beach, Frenchtown Township, Michigan (Figure 2.1). The site is shared with Fermi 2, a 3294 Mw(t) General Electric boiling water reactor. rated at 1093 Mw(e) net. Fermi 2 is presently licensed to operate'at 100% of rated power, but is temporarily restricted to levels below 50% (Figure 2.2). Fermi 1 was a fast breeder, sodium-cooled reactor, operated at essentially atmospheric pressure. The plant was designed for a maximum capability of 430 Mw(t); however, the maximum reactor power with the first core loading (Core A) was 200 Mw(t). The plant was composed of l the reactor containment building, which housed the reactor and the l primary coolant system; the steam generator building; the control-l building; and the turbine house. Some distance from this building l complex there was a fuel and repair building, in which fresh and spent I fuel was stored and processed; a waste gas building, in which. waste gas was processed and from which inert gas was supplied and recirculated; a sodium building in which sodium was cold-trapped and stored; and a combined health physics building and chemistry laboratory (Figures 2 3 and 2.4). A brief description of the plant facilities pertinent to'the understanding of the approved plan for decommissioning the facility is presented in the following paragraphs. 2.1.2 Reactor Vessel and Associated Structures The stainless steel reactor vessel is composed of four parts: the lower reactor vessel, the transfer rotor container, the upper reactor vessel, and the rotating shield plug container. The cylindrical lower reactor vessel, which contained the core and blanket is 114 inches in diameter and has a dished ellipital head. The transfer rotor container, used for fuel storage and transfer, is attached to the lower reactor vessel. The upper reactor vessel, which is eccentric with the lower vessel, is also cylindrical and is 174 inches in diameter. The upper portion of the vessel is sealed at the top by the rotating shield plug, which supports the control mechanism, the fuel holddown mechanism (HDM), and the offset handling mechanism (OHM). The plug container is an extension of the upper. reactor vessel and is stepped to maintain the biological shielding effectiveness of the rotating plug. The vessel as a whole contained the reactor and the primary sodium coolant which flowed upward through the core and blanket. Sodium coolant for the core and inner radial blanket entered the lower vessel 2.1
through three equispaced nozzles 14 inches in diameter; sodium coolant for the outer blanket entered the lower reactor vessel through three equispaced nozzles 6 inches indiameter. Sodium from the core and blanket discharged into a common pool and left the upper reactor vessel through three equispaced nozzles 30 inches in diameter. The reactor vessel was surrounded by a graphite neutron shield located in a nitrogen atmosphere inside the primary shield tank. The graphite consisted of an inner 6-inch layer of 5% borated graphite next to the ; reactor vessel wall, a layer of heat insulation, a region of unborated graphite, and a 6-inch layer of borated graphite which lined the inside of the primary shield tank. The upper portion of the primary shield tank served as a biological " shield and was integral in purpose and shielding effectiveness; with the rotating shield plug and the biological shield function of the operating floor. j l 2.1 3 Core and Blanket Components 1 The reactor was an assembly of 870 removable and, to a certain extent, ) interchangeable subassembly units located on a square lattice spacing. i The core subassemblies contained the upper and lower axial blankets and ) occupied a roughly cylindrical region in the center of the lattice. ! The entire core region was about 31 inches in diameter and 31 inches high, while the axial blanket regions were each 17 inches high. The subassembly lattice positions immediately surrounding the core region comprised the inner radial blanket (IRB) region; the 499 i subassembly lattice positjons surrounding the IRB comprised the outer I radial blanket region (ORB). Surrounding the ORB region were 198 lattice positions used for steel subassemblies that provided thermal and irradiation shielding for the reactor vessel. Together the core and blanket regions approximated a cylinder 80 inches in diameter and i 70 inches high. ; The active fuel region of each core subassembly was made up of 140 zirconium-clad uranium 10 w/o-molybdenum alloy pins enriched to 25.6 l w/o in uranium-235 The upper and lower axial blanket regions in each core subassembly contaianed 16 stainless steel clad 3 w/o molybdenum alloy rods containing uranium depleted to 0 35 w/o uranium-235. The radial blanket rods were similar to the axial blanket rods, except they were 71.5 inches long instead of 17 inches long; each radial blanket subassembly contained 25 blanket rods, l 2.2
2.1.4 Fuel and Repair Building The Fuel and Repair Building (FARB) contained process cells, water-filled decay and cut-up pools, a new fuel handling and storage area, a central control room, a 75-ton crane, and a transport car access area for the performance of fuel handling functions; space was provided for a repair and cleaning facility for maintenance of contaminated equipment. The building is located approximately 100 feet north of the Reactor Building and is connected to the Reactor Building. by a covered transport car track. The substructure of the FARB consists of heavy reinforced concrete walls and rests on bedrock. The superstructure consists of two different types of construction. The walls above the operating floor in the new fuel receiving and storage area and the irradiated fuel decay and cut-up pool areas are reinforced concrete. All other superstructure walls consist of structural steel with corrugated asbestos siding. 2.1.5 sodium service System The cold trap system was contained in a separate substructure room diagonally adjacent to the transfer tank room. The sodium lines and equipment were shrouded in a welded carbon steel secondary structure which was inerted with nitrogen. The piping outside the' walled areas was in the repair pit area and was contained in a concrete vault with a removable cover slab. l l 2.1.6 Heat Removal Systems l l The heat removal systems consisted of three primary and three secondary coolant loops. The sodium pumps, one per loop, were all single-stage centrifugal mechanical pumps. Heat was removed from the reactor core and blanket by the primary sodium coolant, transferred to the secondary sodium coolant by three parallel intermediate heat exchangers located in the reactor building, and finally transferred to water and steam in three once-through steam generators located in the Steam Generator Building. 2.1.7 Waste Gas Disposal System The waste gas system disposed of waste gases from the plant by a process which included storage until the gases decayed to a suitable level, dilution below the maximum permissible concentration in air, and dispersion into the atmosphere through a stack. The waste gas disposal building is immediately west of and adjacent to the inert gas building. Piping, valves, and mechanical equipment were housed in chambers below grade; the holdup tanks are housed above grade in shielded cells of the building. 23
2.1.8 Liquid Waste Disposal System Like the waste gas disposal system, the liquid waste disposal system was designed for 430 Hw(t) reactor operation and 6 a/o fuel burnup. It provided for substantial holdup capacity, permitting discontinuous discharge if necessary. The major sources of liquid waste were effluents from subassembly cleaning, miscellaneous decontamination i operations, and laboratory sinks. After process and decay when j necessary, wastes were diluted and discharged to the lagoon from which ; they reached Lake Erie via Swan Creek. l The liquid waste disposal system is located in the FARB. Its major components are three liquid waste surge tanks, a liquid waste test j tank, a liquid waste dump tank, ion exchange units, a liquid waste i metering pump, and the associated piping and valving. l 1 i i 2.1.9 Turbine and Electrical Systems l Steam produced in the three steam generators located within the Steam Generator Building passed to the adjacent turbine house and was used to operate the turbine. The turbine was a tandem-compound, single-flow machine having a guaranteed gross capability of 150 Mw(e). Four stages i of feedwater heating were used. The main condenser was a single-flow, divided-water-box, welded steel unit. Four feedwater heaters, a drain cooler, and a reheated drain cooler were included in the cycle. Three l feedwater pumps were provided, two of which were capable of pumping the flow required for the ultimate 430 Mw(t) conditions. l 2.2 DECOMMISSIONING ACTIVITIES Although the decommissioning plan was not formally approved by the AEC until November 1973, a year after initial submittal, decommissioning activities were initiated in October 1972 with the removal and cleaning of the reactor fuel. Activities were essentially completed in October 1975 with the exception of shipping the primary sodium to the Clinch River project which was accomplished in November 1c34. In December 1975, the corporate existence of PRDC was terminated and in January 1976 Detroit Edison became the legal custodian of the Fermi 1 plant site. 2.2.1 Disposal of Fuel and Blanket Subassemblies Fuel for the Fermi reactor was defined as the 25.6% enriched uranium / molybdenum alloy pins contained in the mid-portion of the fuel subassemblies. This material contained approximately 4000 kilograms of uranium, which was assigned to the project under an AEC lease I 2.4
1 agreement. Under terms of the agreement, the uranium was to be returned to the AEC in the form of UF6 meeting diffusion plant purity specifications, if a private commercial company in the U.S. could do, the work; if no company-were available, the AEC would accept the irradiated materials under the spent fuels chemical processing and conversion provisions of the Atomic Energy Act of.1954, using specified hypothetical plant costs. The AEC agreed to accept the material at its Savannah River Project (SRP). , Two shipping casks were designed, fabricated, and licensed for Fermi fuel. The cask cavity was licensed to accommodate four complete subassemblies, two defective _ subassemblies in canisters, or eight cut fuel segments. Subassembly cutting and cask loading were accomplished on a 24-hour day, 6-day week basis. The casks were loaded manually through the. top with the cask upright on the floor of the pool. The cask lid was set in place prior to lifting the cask out of the pool. After the cask was loaded, it was set in a tray adjacent to the pool assembly, leak checked, and decontaminated. Decontamination of the cask was done by washing with soap and water and wiping with paper towels; it was not difficult because exterior surfaces were smooth and nonporous. During these operations, the spread of contamination was readily controlled and limited to the cut-up pool area, where lab coats and shoecoverswergrequirgd. typically 5x10~ uCi/cm ; this Theactivityofthegoolwatgwas was principally Co and Cs from the surface of the subassemblies. The shipments were scheduled so that one cask would be at the SRP being unloaded, while the other cask was at the site being loaded. Loading or unloading, including decontamination, required approximately 24 hours; transportation time between the site and the SRP was 18 to 24 hours. The first shipment of fuel from the site was made on February 6, 1973; 14 weeks later, on May 15, 1973, the last shipment from Bate 11e Memorial Institute arrived at the SRP. Disposal of all blanket subassemblies, some of which were purposely segmented, was accomplished by shipment to the Idaho Chemical Processing Plant (ICPP). 962 subassemblies or segments containing a total of 6524 ThisinvolyggPu,whichwereshippedin14 grams of J cask loadings between December 17, 1974 and April 18, 1975. Of the 962 subassemblies or segments, 318 were uncut outer radial blankets, 168 were cut outer radial blankets, 73 were cut inner radial blankets, 202 were upper axial blankets, 132 were cut lower axial blankets, and 69 were uncut lower axial blankets. The term " cut" indicates that the-nozzle was removed from the subassembly. 2.5
2.2.2 Materials Removed Nonradioactive secondary sodium was sold and shipped to Fike Chemical Company, Nitro, West Virginia and processed into sodium methylate. The primary cold trap and hot trap, including miscellaneous piping, were shipped to Beatty, Nevada for burial. Other miscellaneous radioactive or contaminated items were buried, including dummy subassemblies, oscillator rods, neutron sources, special reactor and pool h'a ndling tools, etc. Whenever possible, miscellaneous hardware, such as pool racks, were decontaminated and sold as scrap. When this was not possible, they were shipped for burial. 2.2 3 Decontamination and Scaling of Contaminated Arcas Each item slated for disposal was rinsed to remove loose surface contamination and surveyed for contamination level. In general, items with radiation or contamination levels above the maximum permissible concentration (MPC) were logged and sealed for effsite disposal at Morehead, Kentucky, while all items with radiation or contamination levels below MPC were sold as scrap. A significant effort was exerted in decontaminating the FARB decay and cut-up pools. After all equipment was removed from the decay pool, the pool walls were scrubbed with a detergent and soapy water. The final wash consisted of a 10% nitric acid solution and a demineralized water rinse. Protective clothing worn by personnel consisted of plastic coveralls, rubber gloves, plastic shoe covers, and respirators. Personnel exposure was monitored by health physics technicians at all times. Subsequent to the final cleaning and drying, a 20-mil-thick layer of i Cooks Spray Booth Shield White strippable paint was applied in several coats to all surfaces of both pool walls, floor, and tunnel. Approximately 50 gallons of paint were applied using hand rollers. Personnel wore coveralls and oxygen breathing masks and worked from a hanging cage. Additional air horns were provided for ventilation during the painting process. After shipping all the radioactive material that was economically j recoverable off site and decontaminating to the extent practicable, the : only remaining major decommissioning task was sealing the reactor I building, the primary sodium system, and the secondary sodium system. ] Therefore, it was decided to seal the reactor vessel within the primary i shield tank and to seal the outlying components directly, using the ! reactor building as an isolation structure against personnel access to O the primary system. The reactor building superstructure is of a design conducive to long , life with little maintenance. It was decided that since the primary i i 2.6 l
system would be completely sealed and there was no other source of radiation or contamination in the building, closure would constitute only the prevention of personnel access to radiation areas. The building itself would be permitted to breathe. No sealing of building penetrations were made, except as related to closure of the radioactive primary sodium system, service system, and cover gas system. These systems were then sealed and maintained at slightly positive inert gas pressure to prevent the entrance of water or moisture and to minimize dispersal of any remaining radioactive material. After removal of the sodium, the primary system was cooled. A gastight system was then established consisting of the primary sodium system plus the primary shield. tank, the machinery dome, and the primary and secondary sodium service systems extending out to welded pipe _ caps. This system was filled with nitrogen and passivated with carbon dioxide, which reacts with residual sodium to form an inert solid compound.Na200 3 . Nitrogen and CO2 gas is maintanined under positive pressure within the sealed system by use of a N2 and CO2 bottle gas system. The retired. reactor' vessel contains 7 safety rods, 1 control rod, 10 lower guide tubes, 1 neutron source, 4 dummy subassemblies, and 198 stainless-steel thermal shield bars, but no fuel or blanket subassemblies. The sodium service system piping was cut in the cold trap room and in the Reactor Building and caps were welded onto the pipes where they connect to the primary system. Sodium service piping between the Reactor Building and the cold trap room was closed by valves at one end and by welded caps at the other end, wherever they were cut. The insides of the pipes are contaminated with a very thin layer of sodium. One of the tunnel lines contains sodium; this line was sealed with a welded cap in the lower Reactor Building. l The auxilialry fuel storage facility was sealed after 100 pounds of CO2 were added to passivate any residual sodium that may have dripped from the fuel storage pots. The FARB transfer and overflow tanks were drained, ..ealed, and passivated with CO2 , then opened to the air atmosphere of the tank room. The forced circulation cold trap system associated with the transfer tank has been completely removed, disassembled, and shipped for burial. The cold trap room is vacant except for sections of service piping. Access to the tunnel between the Reactor Building and the cold trap room can only be obtained by removing a welded cover.- Access to the tunnel from the cold trap room is closed off by a concrete barrier. Radiation levels in the tunnel have not been measured, but cogtaminationlevelsinDecember1973werelessthan100d/ min /100 Cm 2.7
'j 1
J
'The liquid waste and sump pump system has been. deactivated, but left intact so any potential groundwater leakage can'be pumped from the sumps to the FARB liquid waste storage tanks-for later controlled _ a discharge. Radiation and surface contamination levels-in the 1973-1975. {
period are shown'in Table _2.1; activation sources in the' reactor vessel in 1973 are shown in Table.2.2.
'2.2.4 Restricted Area Boundary The Fermi _1 boundary was revised to exclude many nonradioactive' areas such as the Office and Turbine Building. The new boundary (Figure 2.5) ' is marked by a 7-foot-high chain-link fence and building walls that enclose the FARB, the Reactor-Building, the Sodium Storage Building, and the cold trap room. The. cold trap room contains some contaminated piping. The health physics building has been dismantled.
2.2.5 Surveillance R Surveillance are maintained for Fermi 1 pursuant to Section I.8, Reportir3 Requirements of the Technical Specifications, Amendment 8 to Provisional Operating License No. DPR-9 Surveillance data is . available on an annual basis as submitted to the Commission from the U year ending June 30, 1975 through June 30, 1987 as Reports EF-121' through EF-133 23 DECO GISSI.]II!G COSTS The decommissioning activities for Fermi 1 were influenced by the , following factors: 1 o Detroit Edison's use of the Fermi 1 turbine steam supplied from an j oil-fired boiler for peaking power. (Presently retired on l Economic Reserve) o Detroit Edison's construction of an 1100 Mw(e) boiling water , reactor adjacent to Fermi 1. o The $4 million retirement fund held'in reserve by PRDC. The. major. decommissioning activities and plan for maintenance of the plant in perpetuity formed the' framework for the-decommissioning program. The final decommissioning costs are shown in Table 2 3. The o monies over and above the $4 million were obtained from member company contributions and revenue from salvage sales. 2.8
J j i Table 2.1 RADIATION AND SURFACE CONTAMINATION LEVELS CONTAMINATION RADIATION LEVELS LEVEL 2 mR/h' d/a/ft Lecation Max Avg Max Avg Date Fuel and Repair-Bldg. 1 Repair Pit 1 0.02 150 <100 11/19/75 Decontamination Facility 0.03 0.01 :400 <100 11/19/75 Dry Loading. Tunnel 6 OA 250' <100 7/14/75
-Steam Cleaning Chamber 10 2- 140,000 44,000. 2/8/74' Decay Pool and Room 20 1 0.03 18,000 1 <100 12/1/75
,- Cutup Pool and Room 40 2 0.03 2,200 2 150 '12/1/75 1 1 Mechanical Equipt. Room 2- 0.1 2,8003 <100 1/14/76 ( Control & Receiving Room' .0 3 0.01 183 <100 11/21/75. j Cask Car Maintenance Pit 03 0.01 <100 <100 11/19/75 I Fan Room 1 0.01 110 <100 11/19/75 , Unloading Pit 0.03 0.02 <100 . <100 11/25/75 l 1
)
l l I 20 mR/h on decay pool tunnel to cutup pool wall support beam. Whole pool is covered with strippable paint;.18,000 dpm is on remnants of chain for bridge grapple inside bridge trolley cabinet that is sealed and labeled. 2 40 mR is due to material trapped under alignment pads on bottom 4 of cutup pool. Pads are sealed with metal putty and whole pool is covered with strippable paint; 2200 dpm is on boom crane that is sealed in plastic and labeled.
-3 8300 dpm is on liquid waste pump.that was decontaminated and covered with plastic.
29
I J Table 2.1 RADIATION AND SURFACE CONTAMINATION LEVELS (Cont.) CONTAMINATION j RADIATION LEVELS LEVEL 2 mR/h d/s/ft Location Max Avg Max Avg Date l Lower Fuel' Vault 0.02 0.01 <100 <100 11/19/75 ! I Upper Fuel Vault 03 0.01 <100 <100 11/21/75 ! Transfer Tank Room 7 0.5 <100. <100 2/6/74 j Pool Sump I 0.03 0.02 <100 .<100 11/18/75 l Hot Sump Pit 2 120 2 800 170 11/4/75 l Clean Shop 0.02 0.01 <100 <100 11/24/75 j Cold-Trap Room D.03 0.02 126 <100 .11/6/75 l North Waste Tank Room 100 3 <100 <100 11/19/75 South Waste Tank Room 60- 1 <100 <100 11/19/75' Reactor Building l l Biological Shield Wall Annulus 0.05 0.02 <100 <100 11/18/75 l Below-Floor Area 2 0.2 <100 <100 10/8/75 l Outside Auxiliary Fuel Storage Facility 0.1 0.1 <100 <100 5/7/74 Operating Floor 30 7 200 <100 10/8/75 Machinery Dome 1.5 1 105 <100 4/24/.75 , Secondary Shield Wall Cavity 15 0.1 <100 <100 10/8/75 l Above waterline. Does not include below waterline. 2 Does not include sump below waterline. 2.10
Table 2.1 RADIATION AND SURFACE CONTAMINATION LEVELS (Cont.) CONTAMINATION RADIATION LEVELS LEVEL 2 mR/h d/a/fb ' Location Max Avg Max Avg Date Reactor Building Anti- . i contaisination Bldg. 0.05 0.03 <100 <100 11/7/75 l Cask Car Trsstleway 0.2 0.05 <100 <100 9/14/77 Waste Gas Compressor Rm 0.02 0.01 <100 <100 11/17/75 1 , l Waste Gas Valve Room 0.02 0.02- <100 <100 11/17/75 i Primary Sodium Cold . 3 0.05 108- <100 11/5/75 trap Room Primary Sodium Storage Room 6 3 <100 <100 11/5/75 Primary Sodium Service System Valve Room 03 0.01 <100 <100 11/17/75 ) East Sodium Gallery 0.02 0.02 <100 <100 10/9/75 l West Sodium Gallery. 0.02 0.02 <100 <100 10/9/75 Fission Products Detector Building 0.03 0.02 <100 <100 5/16/74 Inert Gas Tunnel 0.1 0.02 <100 <100 11/26/75 Vent Building 0.03 0.02 <100 <100 11/17/75 Vent Building Equipt. Pit 0.02 0.01 <100 <100 11/17/75 Health Physics Building Office and Lab 0.05 0.02 <100 <100 11/12/75 Locker Room 0.03 'O.02 <100 <100 11/12/75 First Aid Rooms 0.02 0.02 <100 <100 10/17/75 Chem Lab 0.02 0.02 <100 <100 11/12/75 2.11
1 Table 2.2 CALCULATED STAINLESS-STEEL ACTIVATION IN REACTOR VESSEL (NEGLECTING BLANKET SUBASSEMBLIES) - June 1, 1973 i 4 Actlygtion' Source, C1 Component MI "Fe "Co "Co Total Control & safety rod 2 99 22 19 142 channels
'Holddown mechanism 5 206 6 228: 439 Shield bars 22 796 12 105 935 l
.1 Thermal shield. 22 796 1 97 916
# 22 *- 3 25 Holddown column
*
- 3 6 Safety rods 3 Rotating plug
- 1
- 1 2 i
860
- 965 .1849 Support plates 24
- 35 301 Support structure 7 259
- 35 312 Support structure 8 269 Shielding Flow baffles
- 10
- 2 12 Conical flow guide # 1
- 1 2
- 18 174 Lower reactor head 4 152 Shielding
# # 2 i Transfer rotor 1. 1-l 44
- 6 51 1 OHM 1 Reactor Vessel - - -
Total 96 3515 35 1519 5168 4
- Less than 1 C1. i 2.12
l i Table 2 3 FINAL DECOMMISSIONING COST 1
- 1. - Core Fuel Processing $ 418,000. j Includes transferring subassemblies from reactor .!
and other storage areas to FARB, steam cleaning, { underwater segmenting, loading in casks and shipping i ta Savannah River; also includes material and: fabri-cation cost of No. 2 shipping cask and modifications to No. 1 cask.
- 2. ABC Core Fuel Processing 1,783,000 i Includes baste processing and_ conversion charges, processing and conversion losses, and use charges during'the processing period.
3 Blanket Subassembly Processing 67,000 Includes transferring subassemblies from reactor and , other storage areas to FARB, stean cleaning, and storaSe ] in cutup pool. j
- 4. Blanket Subassembly Processing for Disposal at Idaho 386,000 Includes licensing and rental of two casks, design and purchase of special basket and container assemblies, round-trip shipping charges, and cutting and disposing of some nozzles, j l
l' 5 ABC (ERDA) Blanket Subassembly Processing Payment 1,594,000 Blanket accepted by ERDA under Reprocessing pro-visions of 33CFR30.
- 6. Sodium and Cold Trap Disposal 250,000 Includes transferring primary sodium from all systems to storage tanks, constructing a sodium-barreling ,
facility, and dismantling and removing the primary j cold trap for shipment to Beatty, Nevada. Includes l
$75,000 allocated to the trust fund to barrel and ;
ship primary sodium to PMC in 1981 - 1985. !
- 7. Sodium Piping and Contaminated Equipment Disposal 480,000 Includes cutting and sealing pipes and equipment, decontaminating equipment, and packaging solid waste for burial.
- 8. Plant and Administrative Expenses 1,999,700 Includes plant and administrative expenses, nuclear insurance, property tax, regulatory charges, and AEC use charges. Amount is reduced by $376,000 of interest received on invested funds during the- ,
decommissioning period. ' 2.13
.g. :e - .1
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Table 2 3 FINAL DECOWIISSIONIWG COST'(Cont.) :]
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'h Total Cost of Decommissioning .j$6,977,700
, 9;- Provision for Surveilbnce '
, '187,288 1
il fi Total Cost of Decommissioning 1 . .
,j
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30 ENVIRONMENTAL ASSESSMENT , i i The proposed action to continue the SAFSTOR of Fermi 1 for 40 years i will'not cause a significant environmen h1 impact. The Fermi 1 ; decommissioning effort was completed in 1975. 'Since this involved I l dismantling and shipping the radioactive fuel, blanket assemblies,'and i mechanical components offsite, any impact due to decommissioning has j already occurred. l 1 On April 29, 1969, Detroit Edison filed an application with the AEC for a permit to construct Fermi 2; Construction Permit No. CPR-87 was issued on September 26, 1972 following reviews by the AEC staff, ) Advisory Committee on Reactor Safeguards, and public hearings dealing with environmental matters before an Atomic Safety and Licensing Board. The staff's conclusions were issued as a Final Environmental 4 Statement (CP-FES) in July 1972. On April 4, 1975, Detroit docketed the Environmental Report (ER-OL) in support of the application for an operating license. In August 1981, the NRC issued the " Final Environmental Statement Related to the Operation of Enrico Fermi Atomic Power Plant, Unit No. 2", NUREG-0769. The OL-FES presents assessments that supplement those described in the CP-FES. The report is written i in accordance with 10CFR51 which implements the requirements of the National Environmental Policy Act of 1969 (NEPA). As discussed in Section 2.1 and shown in Figure 2.2, Fermi 1 shares the 1120-acre site with Fermi 2. The environmental information presented in this section is based on relevant information and studies presented = in the Fermi 2 ER-OL, Updated Final Safety Analysis Report (UFSAR), and the NRC's OL-FES. The environmental information is applicable since much of the data was collected at the time of decommissioning or after Fermi 1 was decommissioned and in a SAFSTOR status. 31 NON-RADIOLOGICAL IMPACTS The regional demography and land use, water use, site ecology, geology. and meteorology have not changed significantly since described in Section 2 of the Fermi 2 ER-OL and UFSAR. Tables 3 1 and 3 2 ' represent the most recent population data around the site. 3 1.1 Socioeconomic and Cultural Resources The personnel required for maintenance of the facility in SAFSTOR consists of a 12-person Site Committee who inspect the facility annually, a 3-person Audit Subcommittee who audits the facility twice a year, one technician who carries out the surveillance program, and an operator responsible for periodic rounds. All of those individuals are employed by Edison in other capacities and in some cases, at locations ,
+
4 31
1 ll other than the Fermi site. Because of the small number involved and their status as Edison employes, there-is virtually no impact on the community and traffic patterns. 3 1.2 Land Use 1 The SAFSTOR of the facility. will not affect land use onsite or offsite. There are no plans for either construction or dismantling any, portion of the facility over the next 40 years. Periodic maintenance 1 j to the facility will be'done as required to maintain the SAFSTOR status. ] 313 Hydrology q l The hydrology of the site and its environs has not changed significantly since the Fermi 2 ER-OL and UFSAR. It is not anticipated there will bo any significant changes over the next 40 years. ] t i 3 1.4 Water use j While in the SAFSTOR status, Fermi 1 has no requirement for water; thus f the water use on the site is directly attributable to the operation of l Fermi 2. Non-contaminated liquid waste collected in sump systems is j essentially the intrustion of underground or rain water. . These sumps ! discharge to the plant drain system which drains to Lake Erie. .The State of Michigan NPDES Permit No. MI 0001830 (Expires March 31,1990) covers the discharge of waste waters from the Fermi i facility. i 3 1.5 Aquatic and Terrestrial Resources : l The aquatic and terrestrial ecology'of the site and its environs is I presented in the Fermi 2 ER-OL and further discussed in the NRC OL-FES. Since there is no water requirement for the facility and no construction or dismantling activities anticipated, there will be no ; impact on the aquatic or terrestrial resources. 3 1.6 unavoidable Impacts i Fermi 1 will occupy a small restricted area of the present site over the SAFSTOR period. Within that restricted area, Fermi 2 has a thermoluminescent dosimeter (TLD) calibration facility inside the concrete shield walls of the Fuel and Repair Building. , l The unrestricted portions of the Fermi 1 facility are effectively used J by Fermi 2: 32
I o The Office and Turbine Buildings house training, medical, and ] storage facilities. o The water plant' supplies the potable water for Fermi 2. :> o The general service water. intake structure for Fermi'2 is located on the Fermi 1 intake canal. 3 1.7 Local Short-Tern Uses Versus Long-Ters Productivity The site is presently being used for production of electricity by Fermi ! 2 and there are no plans for the next 40 years other than electrical power generation. l 3 1.8 Commitment of Resources The .40 years of SAFSTOR will' not involve commitment of a significant . j amount of resources. It can be reasonably assumed that there will be ; less volume of radioactive waste to dispose of at the end of SAFSTOR' due to the additonal period of decay. Immediate dismantling would require offsite shipment of radioactive material and a larger burial l area at a waste disposal site. -l 32 RADIOWGICAL IMPACTS Tables 2.1 and 2.2 present activation sources in the Reactor. Vessel and radiation and contamination levels, respectively, at the time of decommissioning. On July 23, 1986 Edison submitted supplemental i information in response to NRC questions (References 2.and 3). Relevant information has been included in this section; for the i detailed data, see Reference 3 ; The radiological impacts of 40 years of SAFSTOR consist of: _ o The occupational radiation exposure of workers. involved in' maintenance and surveillance, o The environmental impacts of releases of liquid and gaseous effluents. o The impact of postulated accidents. l 33
1 l i l 1' 3 2.1 Occupational Radiation Exposure i j Specific measures for the maintenance and control of radiation ! exposures and releases of radioactive materials to unrestricted areas are contained in the manual " Decommissioned Enrico Fermi Unit-1 Reactor and Associated Building and Equipment-Administrative and Surveillance Procedures". This manual is reviewed annually by the Fermi'1 Site 1 Review Committee. Any revisions to the manual are reported in the Annual Report to the NRC. ) Every six months the Audit Subcommittee performs an inspection and review of records and evaluates compliance with commitments for periods ) of surveillance. i The Plant Manager of Fermi 2 is the Custodian for Fermi 1 during its f SAFSTOR status. Two Custodial Delegates are appointed or reaffirmed at the annual Review Committee meeting to act on behalf of the Custodian. An ALARA program is maintained by Fermi 1 Administrative Procedures and i the implementation of Fermi 2 procedures that are applicable for radiation protection of personnel entering or working in a Radiation Controlled Area (RCA). A list of these procedures is found in Reference 3 The following controls and surveillance are carried out at Fermi 1. j In some instances the requirements of the Technical Specifications are exceeded; these controls may at any time be revised to reflect the surveillance frequencies required by the Technical Specifications.
- 1. All access points to the Restricted Area are kept locked. Access to the secondary reactor shell is also controlled with a padlock.
Only two keys are available for the locks; one key is kept in the Plant Manager's safe and the other in the critical key cabinet in j the Fermi 1 Control Room. Unescorted access to the restricted ! area must be approved by the Custodian or his delegate. l
- 2. Thermoluminscent Dosimeters (TLD) and Direct Reading Dosimeters (DRD) are supplied for all persons who have been granted ,
permission for unescorted access. Visitors are properly escorted and are issued DRDs. 3 Periodic test and commitment compliance activities are initiated ! by surveillance work orders issued by the Custodial Delegate. l s 4 The following weekly tests are performed: o General walk-through and inspection of the restricted area. o Continuity test of the water intrusion alarm circuits. (Detectors are in the containment building lower level sump, l l i 34 ,
~_-_-_-__O
l the waste water sump, and the biological shield annulus around the Reactor Building). j o Observation of the CC2 cover gas pressure over the ! essentially empty sodium storage tanks. (Small remnants of i sodium remain in the pipes, tanks, pumps, and reactor.) j
.i o Cover gas (CO 2 ) Pressure in the reactor is checked'and recorded in the Reactor Building.
- 5. The following monthly surveillance are performed: l i
o The volume of liquid in the liquid waste tanks is checked and recorded. (Intrusion of rain water into the FARB caused one tank to fill, this was corrected over three years ago by the placement of a concrete apron on the West Side of the FARB). o Detailed inspection of restricted area is made and potential problems are reported to the Custodial Delegate. o Water levels in all active sumps are checked.
- 6. The following quarterly surveillance are performed:
I o Radiation and Smear Survey of FARB rooms. j o Radiation and Smear Survey of Reactor Building. ) i I 7 The following semi-annual and annual surveillance are performed: ! I o Twenty radiological environmental sample analyses of raw surface water and sediment around the plant environs and raw city water are performed by an outside contractor. o Physical tests (wet compress application) are performed of the water intrusion alarms at the detectors. o Hi/Lo pressure alarms for the reactor cover gas are tested, o Reactor carbon dioxide cover gas pressure relief valve is tested annually. 3 2.1.1 Personnel Exposure Table 3 3 represents the personnel exposure experience from 1973 through 1985 This covers three distinct periods in the history of Fermi 1: l 35 1
l o 1973 - 1975:- Exposure experience involved all plant . . personnel for removal'of all highly radioactive material and
. equipment and area decontamination and sealing.
o 1976 - 1981: Surveillance and routine' maintenance activities. o- 1982 - 1985: Preliminary evaluations and planning were made in 1982 for the disposition of the primary sodium stored ~in Fermi 1. Drumming operations were performed.in 1983 and the. sodium was shipped to Idaho Falls in.1984.. In.1985, Fermi 2 established a direct reading dosimeter calibration facility in the machine shop located in the.FARB. This area was selected because of the low background radiation and access control-maintained over the area. Most of the exposure for 1985 was the result of activity .in this facility doing work for Fermi 2. Maintenance,. repair, and surveillance operations over the next 40 years will average about 0.034 person-rem per year or a total of 0.14 person-rem. Fermi 2 dosimetry calibration activities.in the FARB could result in personnel exposures as high as 0.20 person-rem per year not
~
directly attributable to Fermi 1 SAFSTOR. j 1 3 2.1.2 Radionuclides Inventory Activation analyses were performed on various Fermi i ccmponents to determine the 1986 radionuclides inventory and project ~the inventory'at the end of the 40' year SAFSTOR period. Reference 3 provides the l details for Table'3 4, a summary of the results of analyzing the. reactor vessel, primary shield tank, biological shield (concrete), reactor vessel internals, sodium residuals, and. liquid waste samples. The 40 year SAFSTOR will result'in the following estimated reductions: o 85% reduction in activity. o 90% reduction in liquid waste activity. H o 89% to 90% reduction in exposure. ; 3 2.1 3' Radiological Surveys i In 1986, radiological surveys were performed to assess exposure rates. and contamination levels within the Fermi 1 Radiological Controlled l Area. Areas surveyed included: o Fuel and Repair Building 3.6
1 o Reactor Building ! o Cask Car Trestle Shed l 0 . Ventilation Building l- o Outside Areas within the RCA
- I l o Primary & Secondary Sodium & Steam Tunnels o Sodium Service' Building f 1
The results are shown in Table 3 5.- No significant' removable contamination was detected'in any of the surveyed areas at Fermi 1.- Theonlydetectableremovablecontaminationwasfound.ina-fewgpotsin the decay and cutup pools which ranged from 1500-4000.dpm/100cm . , All other pta and gamma contamination levels were less than 1000 dpm/100 cm , the minimum detectable level for'the purpose of this 2 I survey. Alpha contamination levels were all less than 20 dpm/100 cm which. represents the alpha contamination minimum detectable level. Presently, the following areas located within the Fermi 1 restricted area are within the release criteria defined as ".. 5 micro rem per hour at one meter for reactor generated, gamma emmiting isotopes", (Reference 9). o FARB First Floor and Mezzanine 4 Machine pit l o Cask Car Trestle Shed F o Operations Floor.in Reactor Building i o Second Floor of Sodium Building :j o All Outdoor Areas 2 It is estimated that over the SAFSTOR period, the decay and cutup pool i rooms and Reactor Building basement will be atl unrestricted dose rate 'j criteria; the bottom of the decay pool will be at or near unrestricted criteria. I 3 2.1.4 Isotopic Analysis Isotopic analyses were performed at selected locations with enough activity to provide significant data. The inplace analyses were performed with a Quantum Technology transportable gamma spectroscopy , system. Selected locations were those areas.in which the general radiation level was higher than normal background. Only Cesium-137, Cobalt-60 and Sodium-22 were found. The measured activities, present dose rate at the point of measurement, forty year dose rate, forty year dose rate corrected for gamma energy profile 1 change, and percent reduction over the forty. year span are shown in Table 3 6. q 1 37 _______ _ _ L
-]
3 2.2 Radioactive Waste Management o Gaseous Wastes There will be no radioactive gaseous wastes. released from Fermi 1 over the SAFSTOR period.
)
L o Liquid Wastes' Liquid wastes at Fermi 2 are contained within the waste tanks in the FARB. All.potentially contaminated drains and. sumps collect in the hot I sump in the FARB and discharge to the waste tanks. Liquid quantities in these tanks are monitored and recorded. If there is a need to discharge the liquid from the tanks, the water will be processed using an approved portable liquid radwaste processing system until it is' i acceptable for discharge in accordance with the Technical Specifications, j
-323 Postulated Accidents 1
There are three postulated accidents that could occur during SAFSTOR. I These are described in the following sections. i l 3231 Liquid Releases It is assumed that two liquid waste tanks in the Fuel and Repair i Building radioactiverupture. radwasteThetankscontainatotalgf7550gallonsof137 that analyzed 6 mci of 6 Co and 6 mci of Cs. Scenario A: Airborne Release ASSUMPTIONS: o Tanks rupture / malfunction and radioactive inventory is spilled on i floor, o- 25% of the inventory is assumed to be. released through a vent to the environment. o Release occurs over a 2-hour period and individual is exposed for. the entire time at the exclusion area boundry (EAB). o Dose factors from Regulatory Guide 1.109 and ICRP Publication 30 o X/Q = 1.55xE-5 sec/m3 (Fermi 2 UFSAR, Chapter 15, Table 15A-2) 38
2-hour, 50 th' percentile.value'at Fermi 2 exclusion area boundry (EAB) of 915 meters NW. This distance is conservative since the Fermi 1 EAB is approximately 1211 meters NW. o Maximum Permissible' Concentration (MCP) from 10CFR20, Appendix B, Table II. , RESULTS: Scenario A Liquid Water Tank Source - Airborne Release Concentration uCI/a1 Nuclide In Tank- At EAB MPC (air) C/MPC# cobalt-60. 2.10E-4 3 23E-12 -1E-8 3 23E-4 Cesium-137 2.10E-4 3 23E-12 2E-9 1.62E-3
# C/MPC = ratio of EAB concentration to MPC 2-Hour Dose Rate at EAB, aren l' Adult Child l Whole Body 3 27E-4 1.11E-4 l Lung
- 4.46E-3 5.29E-3
# Lung is most critical organ.
Scenario B: Liquid Release to Lake Erie ASSUMPTIONS: o The liquid radwaste tanks are located in the' subbasement of the: FARB. In the unlikely event of an earthquake, minor l cracking of j the structure could occur. The tanks could also undergo' stress i cracking and leaking to allow fluid flow between the interior of l the structure and the surrounding earth. Initially, liquid would, l be retained within the structure and diluted by inflowing ground water from the dolomite aquifer. There would also be a slow inflow of ground water and the water level inside.the structure would rise until it attained the' elevation of the piezometric level of the ground water. At that time the radioactive liquid may be diluted by as much as 10:1; however, no credit is taken for dilution via the influx of water. o Tanks are approximately 450 ft, from the Lake Erie shoreline.
]
39 l
--___.___.______________.]
o Flow rate within the aquifer is 0.24 ft/ day.. o Delay time in traveling from the; tank to' Lake Erie is'1875 days plus 40 days to move upward through.till and lake bottom- I
-sediments, (Fermi 2 UFSAR, Section 15.7 3 2).
o Dilution factor of 77 at Monroe' City Water intake 3200 meters
. south of Fermi 2 (Fermi 2 UFSAR, Appendix 11A).
o Decay with delay time is assumed.
.o. Individual consumed water, fish,'and invertebrates for 24-hour period.
c Dose, factors from Regulat'ory Guide 1.109 o MPC from 10CFR20, Appendix B, Table II. RESULTS: Scenario B Liquid Waste Tank Source - Monroe City Water Intake
-Concentration, uC1/al Entering Nuclide In Tank Lake At Intake MPC (*nter) C/HPCD l Cobalt 60 ' 2.10E-4 1.04E-4 1 35E-6 5.00E-5 0.03-Cesium 137 2.10E-4 1.86E-4 2.41E-6 2.00E-5 0.12 O C/MPC = ratio of concentration at intake'to MPC.
Ingestion Dose Rate, arca. Water Fish ' Invertebrate Total : Adult Whole Body 0 36 29.90 2 38 22.64 ; Adult, Liver 0.53 30 30 3 62 34.15 Child, Whole Body 0.19 4.24 0.54 0.73 Child, Bone 1.10 29 90 3.68 34.68 3232 Airborne Reler.scs It is assumed that a fire or other catastrophic event results in the release to the environment inventory of the residual which contains a totalsodium of 0 98 includjgg mci the entire' radiggyclide ' Na and 4.84 mC1 Cs. I 3 10
l ASSUMPTIONS. ! o 100% of inventory becomes airborne.- ] o- Release occurs over a 2-hour' period and individual is exposed for. the entire time at the EAB. o Dose factors from Regulatory Guide 1.109 and ICRP Publication 30. o' 'X/Q = 1.55xE-5 sec/m3 , 1
- I o MPC from 10CFR20, Appendix B, Table II.
RESULTS: Residual Sodius Airborne Release Concentration uC1/a1 Nuclide- At EAD MPC (air) C/MPCs J Sodium-22 2.11E-12 6E-9 3 52E-4 Cesium-137 1.04E-11 .2E-9 5.21E-3 O C/MPC = Ratio of EAB concentration to MPC. Adult Dose Rates, area Whole Body 1 31E-3 , Liver
- 1.48E-3 0 Liver is most critical organ.
l 3233 Discussion Both Scenario A and B and the releases from the residual sodium result in concentration levels that are well below the MPC values in 10CFR20, Appendix B Table II for releases to unrestricted areas. The dose rates associated with Scenario B are below the limits at which precautionary measures would be taken for an accident-type release. The relatively high dose rates associated with the fish and invertebrates are the result of the concentration factors and the models in Regulatory Guide 1.109 In this Scenario, the radioactive liquid is released to the aquifer and groundwater. The results are extremely conservative since no credit 3 was assumed for o Dilution from the initial influx of water into the FARB. 3 11
a r
, .+- . +
.o. ' Removal of-suspended particulate by filtering. action of the' soil and1
~
g clay. o ' Removal of ionic forms through' adsorption by the soil and, clay. i The 1875-day'. travel time to,the shoreline of Lake Erie-provides ample' time' to sink wells, follow.the' progress to the Lake,.and.take, remedial action'
'should it become necessary.
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.l I
FERMI 1 PERSONNEL EIPOSURE EIPERIDICE, PERSON-REN ;-
~ TABLE 3 3
^
, MONTH '1973. 1974- '1975 )
January- 0.73 0.08 0.44 0.86 1.07 0,49; 4
~ February
. March 1.07- 0.84 . .
0.49 April 0.21 0.22 'O.48- ]
'O.43 0 38. l
'May. 0.24' June 0.08 0.29 2.28 July 0.42 0 31: ,
0 77 0.10 1 30 R
-August 0.86 September- 0.17 0.07 2 39 October 0.03 0 39 'O.48 November 0.98 :0.76 0.18 December 0.14 0.49 0.02 ,
l-l TOTAL 5 79 5.05 9 70 q MONTH 1976 1977 1978 1979 1980 1981 January 0 0 N/A# 0.042 0- N/A. r 1 February 0.010 0.D30 0 0 0 0 March 0 0 0 0 0 0 April 0.015 0 0.031 0 0 0 l
. . - 1 May 0 0 0 0.039 0- 0.011 j June 0 0 0 0 0 0 July 0 0 0 N/A- 0 0 ']
0 0 j August 0 0.D11 0.012 0 September 0 0 0 0 0 0 October 0 0 0 0 N/A. N/A 0 0 0 0 0 N/A, November December 0 0 N/A 0 0 0 0 : 0.011 ! TOTAL 0.025 0.041 0.043 0.081 l i
~
'e-"
3 15
e Ji
)
J Table 3 3' FERMI-1 PERSONNEL EIPOSURE EIPERIENCE, PERSON-REM (Cont.)' MONTH 1982 1983 1984- 1985 January N/A 0.011 0 0.010 'j 0.020- -,i February 0.012- 'O O. March. 0.044 0.071- 0 0 April 0 0 0 0.010
,May 0.010- 0.030 0 0.010 June 0 :0.024 0 'O July 0.016 0 0. O August 0.045- 'O.136 0 0-September 0 0.013 0 ,
o: October 0 0 0 'O November 0.015- 0. 0.020 0.040: g December 0.024 0 0' O.020 ] TOTAL' O.166 0.285 'O.020- 0.110 1 i 1 2 j
.:4 l
l l l
,I
'k i
3 16 l
4 TABLE 3 4 L '!OTAL NUCLIDE INVENTORY (CURIES)
'NUCLIDE TOTAL ACTIVITY 1986 TOTAL ACTIVITY 2026 TOTAL ACTIVITY 2086:
4.0 6E-02
-NC# - NC Nb-94 Co-60 2.75E+02 1.42E+00 5.21E-04 3 92E+00- NC NC' N1-59 Ni 8.72E-01 d.42E+01 4.12E+01 l C-14 1 34E-09 NC NC Fe-55 1.11E+02 ~2.50E-03 2.92E-10.'
Na-22 9.80E-04 2.50E-08 3 20E-15. Cs-137- 1.08E-02 4.52E-03 1.108-03 Eu-152 2.75E-03 3.44E-04 1.52E-05 TOTAL 4.77E+02- 6.95E+01 4.51E+01 ! l
?
-l i
l i
#NC - Essentially no change.
~3 17
Table 3 5 RADIATION AND SURFACE CONTAMINATION LEVELS'- 1986' CONTAMINATION LEVELS, RADIATION LEVELS' dps/100 cm2 IDCATION REN/HR. BETA, GAMMA ALPHA 4 FARB First Floor' 6E-6'TO 10E-5 <1000 <20' Decay pool & cutup area- 1 E-5 to 2E-5 - - Floor drains, pool area 1.5E-5 to 2.5E-4 - - - Mezzanine SE-6 to 8E-6 - - l Decay pool, inside- 1E-5 to 8E-5 - - Decay pool, tunnel 1E-4 to 4E-3 1500 to 3500 <20 Cutup pool, inside BE-5 to 2E-4 1500 - 4000 <20 Cutup pool, tunnel 1E-4 - - Repair Pit l 6E-6 to 1E-5 <1000 <20 ! Waste Tanks 1E-4 to 2E-3 - -
\
Waste dump tank 2 8E-2 <1000 <20 Pump room 1E-5 to 1E-4 - - l Pump room, piping, pumps, etc. SE-5 to 6E-4 <1000 <20 Sump 3 1E-4 2E-3 <1000 <20 I Storage area for Fermi 2 Turbine Bypass Line. 2 Tank currently' full. 3 Water and sludge sa 2.75E-4 uCi/500 ml 60 Co. 2.65'E-4 u C1/500 ml g es Cs.analyzed: 3 18
w Table 3 5 RADIATION & SURFACE CONTAMINATION LEVELS - 1986'(Cont.)- REACTOR BUILDING Elevation 557 ft.- 1E-4 to 1E-3 <1000 ,
<20 Elevation 590.- 2E-6'to 1E-5 <1000- -
<20 Containment Cask. Car Trestle Shed, SE-6 to 1E-5 <1000 <20
,Ventilaton Building 8E-6 to 1E-5 <1000 <20 1 Outside area SE-6.to 1E-5 <1000 <20-i Primary Sodium Tunnel 1E-5 to 9E-5 <1000. <20
<20 i l . Secondary Sodium Tunnel- BE-6 to 1E-5 <1000 Gas Tunnel 1E-5 to'5E-5 <1000 <20-Cold Trap Cell- 2E-5 to SE-5 <1000 <20 Sodium Stort.ge Room 2E-5 to 8E-5 <1000 . <20 Covered Storage Area 8E-6 to 1E-5 <1000 --
Sodium Storage Tanks < 2E-3 <1000 - l Sodium Transfer Room BE-6 to 1.2E-5 <1000 - Sodium Service Building 6E-6 to 1E <1000 - Waste Gas Building 2E-5 to 5E-5 <1000- <20' 'I l j l 1 3 19
-4
'l
'I 1 ,
j Table.3 6 . ISOTOPIC ACTIVITY-AND DOSE RATE PROJECTIONS a s CORRECTED 40 YEAR : PERCENT l CURRENT DS. RATE- ! SURVEY . AREA Co-60 Cs-137 : 40 YEAR. IACATION DS. RATE ACT. ACT. - DS. RATE DS. RATE ' REDUCTION
- Decay Pool 8.5E+01- 8.49f-01 9.86E 3 92E+00 1.28E+00 98.50%*
S. Drain-Decay Pool 8.0E+01 1.12E+00 2.42E-02 1.08+00. .5.76E=-1 :99.28% LSW Pipe: ., i Cutup Pool 1.8E+02 1.89E+001 1.66E-01 6.66E+00- 2 31E+00 98.72% S. Drain Fuel Pool 3 0E+01 4.85E 4.22E-02 1.10E+00' 3 83E-01' 98.72% j Ex. Fan Pump Room 6.0E+02 2.90E+00 1.58E-01 1.53E+01 6.05E+00 98.99% MK 15 1.5E+03 3 87E+00 1.02E+00 1.31E+02 3 74E+01 97 51% ! Tank Room -l RX Bldg. 5.0E+02 7 16E+03 1.14E+00.- 2.63E+00 2.61E+00, ;99.48% , Basement Decay Pool 1.0E+02 4.99E-01 8.12E-01 2.49E+01 6.38E+00 93.62% Tunnel .] l AVERAGE PERCENT DOSE RATE REDUCTION (Co/Cs ACTIVITY) 98.10%'
.l CORRECTED 40 YEAR PERCE:IT l SURVEY AREA Na-22 Cs-137- 40 YEAR CURRC.'T DS.-RATE LOCATION DS. RATE ACT. ACT. DS. RATE DS. RATE REDUCTICU NA Storage 2.00E+03 3 77E-02 7 54E+00 7 94E+02 2.18E+02_ 89.08%'.
Tank l Gas Decay 1.2E+02 7 23E-03 2.13E+00 4.77E+01 1 31E+01 89 06% i AVERAGE PERCENT DOSE RATE REDUCTION'(Na/Cs ACTIVITY) 89.07%
# All dose rates are in micro Rem.
H
-3 20 ,
1 j 1
..)
4.0 ALTERNATIVES CONSIDERED , i Once a nuclear facility has reached the.end of..its useful life,'it must be placed in a condition such that there is no unreasonable risk from -1 the decommissioned facility to the health and safety of the public. 1 Several alternatives are available: DECON, ENTOMB, and.SAFSTOR. The-no action alternative is not viable for Fermi 1 since it is already in.- a decommissioned state. The three alternatives are discussed below. 4.1 DECON DECON is defined as immediately removing all radioactive materials to levels which are. considered acceptable to permit the property to be I released for unrestricted use. DECON is the only one of the j decommissioning alternatives which leads to termination'of.the facility j' license and release of the facility and site for unrestricted use shortly after cessation of facility operations. DECON would involve the removal or decontamination of all equipment, structures, and those portions of the facility containing radioactivity. Although the fuel l has been removed from the Fermi 1 site, the reactor vessel, its I internals, and most of the. sodium piping remain. p , o A major effort would be involved in the complete removal of , the reactor vessel and its internals, the sodium piping, and 6 the Auxiliary Fuel storage facility. Because of size and induced radioactivity, this would require.the removal.and cutup into sections of the various piping and equipment and shipment in commercially available licensed shipping casks to an offsite licensed burial site. This.is undesirable because o Personnel involved would be exposed to additional radioactivity, o There are currently no sites available as repositories for such types of radioactive material. o Razing the site and back fitting for unrestricted use is of little value since Fermi 1 lies within the site boundry of Fermi 2 and could not be used for other purposes. This alternative is not considered viable since little.or no improvement would be realized in personnel exposure, land use, aesthetics, or value. ! 4.1
e l
?-
J
,1 4.2 gNTOMB
.1
~
ENTOMB means to encase and maintain property in a strong and
~
structurally long-lived material-(e.g.', concrete) to. assure retention 'j until radioactivity decays to a level acceptable for releasing the facility forLunrestricted'use. ENTOMB is intended for use where the-
' residual radioactivity will decay to levels permitting unrestricted release of the facility within a reasonable time period of continued structural. integrity of the entombing structure; approximately 100 ,
years is considered to be' consistent with recommended EPA policy on institutional control reliance for radioactivity containment. ~ ;i y Primary. considerations'for retiring the reactor and primary syutem'were (1) removal'of all core and blanket fuel, (2) removal of all sodium, (3) gastight seal of the primary system, and (4) passivation rmd maintenance of the entire primary sodium system with carbon ditmide. The reactor vessel was; sealed within the primary' shield tank and the outlying components were sealed directly, using the reactor building as an isolation structure against personnel access to the primary system. The primary sodium system was filled with nitrogen to'which CO2 was added to reduce the residual sodium deposits to inactive solids. . The y system was.then sealed and maintained at slightly positive inert gas 'j pressure to prevent the entrance of' water or moisture and to minimize , . dispersal of any remaining radioactive material. ., To ENTOMB the Fermi 1 facility at'the present time would not result in any enhancements over the present decommissioned status. o There would be increased personnel exposure due to the removal of
~
radioactive' equipment to accomplish the task. O I o The nickel-63 and niobium-94 in the reactor vessel;would not decay , to levels permitting the release of the facilities for ] unrestricted use within the guidelines of 100 years. 1 1 o Limited surveillance activities would have to be maintained. 4 43 SAFSTOR l 1 SAFSTOR is defined as those activities required to place and maintain a .{ radioactive facility in such condition that the risk to safety.is f I within acceptable bounds and that the facility can be safely stored and-subsequently decontaminated to levelg.which permit. release of the facility'for unrestricted use. SAFSTOR consists of a short~ period of ! preparation for safe storage, a variable safe' storage period of i i f i N.2'
-------_ _ - _ __.__a_______m.__
)L ('* > ; I'
,. 1
-l continuing care consistingLof security, surveillance, and. maintenance-and a'short period of final decontamination. Several. subcategories of.-
SAFSTOR are'~possible. These" subcategories are custodial,'passtuu, or i hardened, the diff'erences among them being the degree of clearep and' 1 surveillance required. , . 1 ; 1 Fermi 1 was decommissioned according to NRC (AEC) rules'andidir'ectives
~
in' effect at:the time ~ ~and was considered 'as being left irr s:' decommissioned state.'.In.accordance with present definitions, it is-in a passive SAFSTOR. condition and at a later_date, in approxiantely 40 years, total removal of the facility could be accomplished.if desired. I A 1 1
.- j 1
1 l 1 i 6 ,
)
I j i 1 1 I
)
1 i i
,. 1 l' , s _' l
- 4.3 [ j P
- -- ---------.--------._____J
j j w l l
)
d
5.0 CONCLUSION
S , l l
.i SAFSTOR is the most viable decommissioning alternative for Fermi 1 over .)
the next 40 years. DECON would result in little'or no improvement over ! SAFSTOR, and ENTOMB is not a viable choice because of the' presence of , j long-lived radioisotopes.- Retaining Fermi 1 in a SAFSTOR status for a 40-year period will reuslt 'I in the following:- 1 1 o Reduction in dose rate of-more than 90%. )
'l o Reduction in personnel exposure at the time of final action. ;
l o Reduction in volume of radioactive wastes at time of final l action. j o Increased availability of repository sites for radioactive i materials. j o Continued compatibility with the long-term use of the Fermi 2 .i site since Fermi 1 buildings are being used for Fermi 2- 1 activities. i o Nominal expense and impact on the community because use of l Fermi 2 personnel for Fermi 1 surveillance activities ] provides readily available manpower. resources. - o Integration of Fermi 1 into the Fermi 2 decommissioning ! program. i o Continued minimization of the risk to the health and safety , of the public. I i o Continued minimization of the environmental impact since any impact due to decommissioning activities has already occurred. .j
.1 f
i 51
6.0 REFERENCES
i
- 1. Letter Detroit Edison to NRC, " Amendment Request for Extension of- <
the ' Possession Only' License for Fermi 1", NE-85-0714, May 17, a. 1985.
- 2. Letter NRC to Detroit Edison, " Request for Additional Information", February 27, 1986.
3 Letter Detroit Edison to NRC, " Supplemental Information on -- Fermi 1", VP-86-0092, July.23, 1986. \ l
- 4. Letter NRC to Detroit Edison, " Request for Additional Information", May 22, 1986.
- 5. Letter Detroit Edison to NRC, " Request for Additional Information As Outlined in 10CFR51.45(b) for Fermi 1", VP-86-0118, September.
15, 1986.
- 6. Letter NRC to Detroit Edison, " Request for Additional Information
- Enrico Fermi Atomic Power Plant, Unit No. 1", December 2, 1986.
- 7. Letter Detroit Edison to NRC, "Sulmittal of Environmental Information'for Fermi 1", NRC-87-0051, May 5, 1987. ,
- 8. " Retirement of the Enrico Fermi Atomic Power Plant", NP-20047 and NP-20047, Supplement 1, PRDC, March 1974 and October 1975; these?
reports are on file at the Department of Energy, Office of Public < Affairs, Technical Information Center, Oak Ridge, Tennessee. I
- 9. Letter John F. Stolz (USNRC) to Dr. Roland A. Finston, Stanford y University, March 17, W?1 (with Enclosure 1).
6.1
'h I
(I
, K' 1
i r Ipd APPENDIX 1 FERH1 1 STATUS ( , e i: i
TABLE OF CONTENTS Fage
1.0 INTRODUCTION
1 2.0 FACILITY DESCRIPTION 1 3.0 ADMINISTRATION 6 4.0 ACCESS CONTROL 7 5.0 MONIT0 TING AND ALARMS 7 6.0 SURVEYS, INSPECTIONS AND TEETING 8 7,0 PROCEDURES 9 Table 1 Ravironmental Survey Regimes s
. Figure 1 Pacility Plan W
S
1.0 INTRODUCTION
The estirement plan for the Enrico Fermi 1 Power Plant was previous!'y prossated to the Atomic Energy Commission via a september 24,1973 1e3ter ! from the Power Reactor Development Company.- The following discussion is en epdate af that information which reflects the corrent states of Fermi 1. As reflected in the September 24, 1973 submittal, the core fuel sectidas-of all 214 Core A fuel subassemblies composed of 25.6 w/o enriched uranida molybdenum alloy were ablpped to the Savannah River Plant facility for reprocessing. m . complete inventory of approximately 70,000 gallons of primary sodium c:s stored frosen in 1344, 55-ga11on drums stored'in the reactor - aosteineent done asad, just prior to shipment, in the cask car trestleway,. This codium wat shipped to Argonne National Laboratory-West between October 29 and November 12, 1984. Though virtually all sodium has been removed from the systems within Fermi 1 a residual heel of sedian [approximately 450 gallons (estimated)] is retained in vessels and piping formerly used far sodium.
~
The main source of activity "in 'tNe facility, concentrated in the lower o1cvstion of the reactor building, was estimated in June 1973 to be 1550 c:rics, of which slightly more than 1500 curies was due to Cobalt 60 prosant in the reactor support plates, holddown' mechanism, and shield bars..- At ths present time, the Cobalt 60 is calculated to have decayed to approximately 320 curies, and in 2025, the time that " safe store condition is intended to be terminated,,it will have decayed to approximately 1.6 curies. Other'sentributors present in 1973 (Co-58 Fe-59, and Cr-51) are now casentially absent.. Typical radiation levels in the high radioactivity regions within the Protected Area presently average between 1.0 and 15 arcs /hr. Areas outside the protected area are less than 5 microres/hr obovo natural background. The safe storage condition of the faellity is maintained on the basis of the Technical Specifications and the Administrative and Surveillance Precedures which prescribe the administration, access control, monitoring, periodic environmental and radiological surveys, long term maintenance provisions, and record keeping requirements. 2.0 FACILITY DESC11pTION N Fermi 1 facility is 13eated within the owner controlled area and cutside the protected area of the searby Fermi 2 Unit. Figure a presents tha current facility plan. As shown in the figure, the following buildings cro identified: 2.1 Rasetor Buildina . The Reactor (or containment) Building contains, below floor, the empty radioactive reactor vessel (which itself is contained in the Primary Shield Tank), heat archangers, primary sodium pusps, 1
and the primary sodium overflow tank (which has been passified and is open to the atmosph'ere). A moisture detector is located l in the area susy that alarms in the manned control station. Operators enter this area twice a year to check the moisture detector operation in sceordance with the Technical specifica-tiens. No moisture has been detected in this area since theI retirement of the facility. Above floor level, the Reactor Building contains the machindry done, containment crane, and other machinery. N primary system has been capped with carbon dioxide at approximately two inches water pressure. Though virtually all sodium has been removed from the system an estimated 450 gallons of residual heel of sodium remains in the vessels or pipes formerly used for sodium. This residual sodium contains an astimated 1.7 aci of co-137 and 0.34 mci of gr-90. N Rasetor Building outer air lock door is kept locked, axcept when occupied, to provide additional security. The interlock on the emergency exit has been removed and the outer door can be
. operated from the inalde in case of an amargency.
2.2 Fuel and Repair Buildina (FARS) This building houses the fetl storage pool and fuel cut up pool which were drained out, cleaned and painted with strippable paint. In addition, above floor, there is the sealed containment steam cleaning chamber and below floor, the sealed transfer tank / room, mechanical equipment room, liquid radioactive maste tank rooms, and the " hot" drains sump. The transfer tank room houses a
- drained and sealed transfer tank containing a heel of passivated resional sodium. The radioactive liquid waste tanks were originally drained. N " hot" sump has been left active. A moisture detector in the sump alarms at the manual control
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station when water gets to the applicable level. m sump pumps presently pump into the liquid waste tanks: IK 7, 8, 9, or 15. In the last 10 years, during which I has been in a safe
. storage condition, approximately , gallons of water have been discharged to the tanks. N quantity of liquid in the tanks is monitored from level' indicators located in the apper floor of 1 and Espair Building. The total capacity of the tanks is gallons. Much of this water came from water in-leakage from pipe penetrations to the Realth Physics Building.
The situation causing the in-leakage has been corrected. Radiation indications within the general area of the ground level floor of the Fuel and Repair guilding are below detectable levels. glight contamination has been found in the fuel and est-up pools and the " hot" susp. 2
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As of May 1985, the activity at the bottom of the sump pump was 100,000dp/200cm2 and at the shaft of the pump was 20,000 dps/200cm . One corner of the bottom of the sump measured 15 ares /br. 2.3 soditan Storate Buildina The primary Sodium Storage Building contains three 15,000 s'allon tanks. The sodium in these tanks was removed and placed in '55 gallon drums. %se drums were shipped to Argonne National' Laboratory-West in Idaho. .The three primary sodium storage tanks have been passivated with a serbon dioxide cover gas which is maintained en the tanks. Entrance to the sodium tank room is through a steel door in the morth wall of the building which has been locked.
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The sodium Storage Tank room was surveyed for radiation levels on April 15, 1985. The radiation levels between tanks range between 0.5-1.0 ares /br. 2.4 waste cas Buildini ~. This building contains two deactivated waste gas tanks and is 5 nonradioactive. - 2.5 Waste cas Tunnel The tunnel runs east' to west from the Raactor Building along-side the south wall of the Waste Cas Building. The tunnel steps down as it approsches the Waste Gas Building and becomes too congested and small for access along its whole length. Access is via a steel cover southeast of the Wasta Gas Building. 2.6 _ Inert cas Buildina N south and of this building contains a 500 cubic foot vacuum t'ank, a 200 cabic foot vapor trap, and a 500 cubic foot hold-up tank. The north room contains three inert gas compressors. Both rooms are nonradioactive. 2.7 Nat Boom The room houses the NaK equipment (used in conjunction with the sodium cold trap) which has been disconnected. The sodlan drumming facility is also located in this room. Radiation surveys indicate only trace amounts of radioactive material present in equipment and structures in this room. 3
2.8 Cold Trap Room This room contains sodium piping needed formerly for sodium drumming, and the piping and valves to and from the primary , sodian tunnel. Some of the latter has been cut and capped. Others have had the valves closed and the handwheels disconnected. Some miscellaneous radioactive materials are being stored in the room. Not shown in Figure 1 is a second story above the Cold Trap ' Room. NaK Room, and part of the Enert Cas Building. This second story contains the handwheels to the sodium valves at the north and of the room (some disconnected) and the electrical feeds for sodium
- heating.
2.9 Vent Buildinz This building has been emptied of all egnipment and the fence has been modified to be continuous past the east doors of the building. 2.10 Primary Sodium Yuanel. , This tunnel is steel lined and runs from the morthwest corner of the Reactor Building to the Cold Trap Reas. The piping in this . tunnel has been drained and capped at the Reactor Building, and either capped or isolated with closed disconsect valves in the Cold Trap Room. Access to this tunnel is via a manhole near the transfer corridor. - 2.11 Fission Product Detector Buildina This is a small building, partly below ground level, to the east of the Rasetor Building. It contains some slightly radioactive piping. 2.12 Sodium Pipina Ca11eries There are two below ground piping galleries that were used to house secondary sodium piping. The west as11ery consists of two chambers (i.e., north and south chambers) which bold the secondary sodium lines that supplied the No. 3 steam generator. The sodium lines have been capped where they amit and enter the Reactor Building. The ground level entry to the north chamber was sealed off as part of the decommissioning program. Entry is now ande via a short 30" diameter tunnel which runs between the biological shield wall space and the north chamber. 4
Access to the south chamber is via a steel door just above ground l 1evel at the north wall of the Steam Generator building. . l ) The east as11ery consists of three separate chambers and contains I the secondary sodium pipe lines that supplied the Nos. I and 2 steam generators. These lines have been capped as in the west gallery. ,, Access to the three chambers is by means of steel doors jusi above ground level outside the southeast quadrant of the Reactor Building. { 2.13 Biolonical Shield Wall Area Thir is approximately a three foot wide annulus that surrounde the building below floor level to about three feet below the concrete pedestal on which the steel Reactor Building stands. Various service piping systems are located in the annulus. It is $ entered via a bolted-in place cover at the west azimuth outside of the containment shell. An access ladder has been left in place. In addition, at, about 30' morth of the entrance, at just below floor level, th' era is an access port to the northwest secondary sodium pipe gallery chamber. The annulus has four floor drains that drain into a collection tank and sump pump system located in the basement of the Steam Generator Building. In addition, there is 'a moisture detector that alarms at the manned control station. The water drained into the tank is nonradioactive. 2.14 Fuel Transfer Corridor This la a covered way covering the tracks of the former fuel handling cask car. The end adjacent to the Reactor Building was modified after 1966 to provide a covered access to the Reactor Building air lock. The area is free of contamination. 2.15 Bealth Physics Buildina This building has been memoved. Only the foun'dation slab remains. There are potentially radioactive drains and lines to the hot susy in the FARB which have been permanently plugged and marked. Due to some problems with rain water in-leakage via these drains and where they penetrate the FARB, the entire area between the foundation slab and the FARB has been covered by a concrete slab. Since this has been done, there has been no consequential in-leakage. Radiation levels above the slab are in the same range as those of natural concrete. 5
2.16 Primary System Cover Ces 1 The primary system is defined as the reactor vessel and all
- connecting volumes. These include the three primary loops, the machinery done, and the primary sodium service, and secondsty sodium systems out to the welded fittings. The primary system is connected to reserve and backup supplies of carbon dioxide to passivate the residual sodium and is kept at approximately'two inches. water pressere with a relief valva set for approximately 5 pois. The relief valve is checked annually for proper operation.
The cover gas is instrumented to alars in the manned control
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station at low (1/2-in water gauge) and high (2 psig increasing pressure) pressure. Primary cover gas alarm tests are performed every six months. 2.17 Lieufd Waste Discherme System All potentially contaminated drains and sumps collect in the hot sump in the Fuel and Repair Building. The liquid waste collected in the hot sump is discharged to the liquid waste tanks (W. 7, 8, 9,.15). Liquid' quantities in these tanka are monitored and recorded. If there is a need to discharge the liquid from the tanks, the water will be processed via a portable liquid radwaste processing syntes, such as is typically used at many power reactor facilities, natil it is acciptable for ' discharge in accordance with the Technical Specifications. Liquid waste collected in non-contaminated susy systems are not part of the Liquid Waste Discharge System. Non-contaminated sumps collect madergrourd water or rain water intruding in non-contaminated areas. These sumps discharge to the' plant drain system which drains to Lake Erie. 2.18 other e The remaining Farsi 1 buildings (e.g., the steam generator, control, and office buildings) were not exposed to the radioactivity resulting from the operation of Fermi 1. Due to this, they have been used for various activities affiliated with the operation of the oil peaker unit (now decommissioned) and Fermi 2. 3.0 ADMIM18TsATIcit Th3 Detroit Edison Company has the responsibility for maintaining a continuing administrative and surraillance program in compliance with current Nuclear Regulatory Commission requirements to ensure that the h2alth and safety of the public and employees are not threatened or injured. 6
Th2 Vice President, Nuclear Operations, who reports to the Group Vice . Frasident has overall responsibility for the Enrico Fermi Unit I! reactor facility. Responsibility for the decommissioned Enrico Fermi Unit I rs:ctor facility is delegated through the line organization of the Vice President, Nuclear Operations, to a qualified Custodian selected from the staff of the adjacent Fermi 2 Atomic Power Plant. The Custodian is casisted in his duties by Custodial Delegates and Custodial Agents. 13 codition, the facility administrative and surveillinee program is l oudited by means of a Review comalttee which will also review and approve all matters of safety associated with any maintenance activities in the facility. Written procedures delineate'the qualification, selection and raspensibilities of the Custodian, Custodial Delegates and Agents, and me:bers of the Review Committee. - A.0 ACCESS CONTROL Th2 crea encompassed by physical barriers and to which access is controlled is Ohe Protected Area. The Protected Area, is enclosed by either a chain link fence or building walls which provide equivalent degree of resistance to penetration. The fonce is topped by three or more strands of barbed ciro or brackets angled outward with an overall height of no less than c v:s feet. Norms 1 entry to the Protected Area is through a normally _ - lockod gate in the fence adjacent to the Sodium Building. Other doors in es11s which act a part of the Protected Area boundary are locked or permanently sealed. Access to the Protected Area is controlled, limited and recorded. The cecoss key is in the manned control station. A second key is held in safe keeping by the Custodian for use only in attenuating circumstances. ,Written procedures delineate the requirements associated with entry into the Protected Area and specific areas within the Protected Area to prevent anauthorised entries and to protect the safety and health of authorised parasanel. 5.0 NONITORING AND ALAINS Monitoring detectors for water intrusion are located in three areas: (1) ths Fuel and Repair Sullding basement hot sump, (2) the lower reactor building overflow tank pit, and (3) the Biological Shield Wall Area. Accumulation of water in these areas activates an alarm in the manned costral station. 7
.The primary system cover gas pressure is also monitored with high and low clares. The monitors and the alara circuitry are periodically checked and eclibrated in accordance with the Technical Specifications and written precedures.
1 6.0 SURVEYS, INSPECTIONS, AND TESTING Two types of surveys are identified, environmental and radiological,',in' oddition to periodic facility inspections and instrumentation testing. Fer the environmental surveys, a number of stations have been established whsre it is estimated that maximum concentrations of radioactive material discharged from the' facility may occur. Two dif ferent regimes of sampling cad analysis are utilised. . A summary of these regimes is given in Table 1.
- 1. Regime I is followed if activity is released.
- 2. Regime II is followed if no activity has been released during the previous 90 days.
Parlodic radiation surveys s're priormed to check for the presence of samma radiation and transferable contamination at the frequency specified in the Technical Specifications. Comma radiation measurements using portable curvey instruments and contamination checks using smears are made of the following areas: Reactor Building - Operating floor, doors and seals around machinery done, breather pipe, sump pump serving Reactor Building annulus.
. Fuel and Repair Building - Pool area, operating floor access points to contamination areas, steam Cleaning Room access plug.
Envirossental and radiological surveys are performed by or under supervision of qualified personnel having parallel duties and responsibilities at Fermi 2. A monthly vid A insp M:Lon of the Protected Area is performed by Custodial Assnts. ' The inspection consists of a visual inspection of the fence, gates cad all anterior doors at the Protected Area, a check and recording of the icvel of liquid in the 11guld water tanks, a check on the condition of the atrippable paint on the decay and cut-up pools in the Fuel and Repair Building, and verifications of the operation of the sump pumps which serve ths Protected Area. All abnormal conditions ' observed are reported to the Forni 2 Nuclear Shift Supervisor so that corrective measures may be taken. Th3 Custodian is also notified of all abnormal conditions immediately, and of the corrective action taken. 8 9
Testing and calibration of the water intrusion monitors, and testing the primary cover gas pressure alarms, is performed every six months. Testing of the carbon dioxide pressure relief valve is performed annually. All testing is performed in secordance with written and approved procedures. 7.0' PROC DURES. , Precedures ansure that the requirements of the Technica1 ' Specification's are corried out in a proper and timely manner. They also serve as training and ( reference units for future Custodians, Custodial Delegates and Custodial < ACn3ts. Administrative procedures include Custodial qualifications, responsibilities and authority, Procedure Manual control, Custodial Delegate and Custodial Agest selection and function, reporting procedures, Ravicw Committee functions and financial accounting procedures. In . cddition, there are appropriate procedures. for details of inspections, curvoillances and operation, t e 0 4 9
TABLE 1 ENVIRONMENTAL SURVEY RECIMES Number of Stations Regime Sample Media Indicator Backaround 1 II s Water l Scuth Lagoon 1 0 C26b C26b
. River Water 1 1 C1b. C26b Lake Water 1 0 C1b C26b Raw City Water
- O 3 C4b C26b Sac' ment Scuth Lagoon Sediment 1 0 C263 C263 River Sediment 1 1 G26g C263 Symbols: .
I C - Crab Sample , Frequency of Sampling:
. 1 - one week interval 4 - four week interval 26 - twenty-six week interval Typs of Analysis:
b - beta 3 samma Imample: C1b - Sample is collected at one week intervals and analysed for beta radioactivity
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