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Application for Amend to Licenses DPR-33,DPR-52 & DPR-68 Authorizing Storage of Low Level Radwaste Generated by Onsite Operation for Life of Plant.Facility Description, Const Schedule & Related Drawings Encl
	ML19330B791
Person / Time
Site:	Browns Ferry
Issue date:	07/31/1980
From:	Mills L; TENNESSEE VALLEY AUTHORITY
To:	;
References
	NUDOCS 8008050558
	Download: ML19330B791 (630)
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Docket Nos. 54 259' In the Metter of the Temmessee Valley Authority.. )

50-260 50-296;

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~In"ameerdanes with 10 CFR Parts 50.59.and 50.90 we are submitting a d

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to.fasility,operattag lineases DPR-33. DFR-52,.and a

Brt-68 for. the Broums Ferry Musleer Plant' units 1, 2, and.3."The ~he 2anthertses TTA to store the lar-level-radleestive weste generated from _

operatism of Breams Ferry emaise for the life of.the plant. Emeleomre'l s

'is a proposed 11samos,eenditissR Enclosure 2 is a descripties of the s

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.fmettity and,all aspectsfef operatian. M 1asure'.3 refleets the facility esmetrustion~=haa=1a.. A gemoral diasmosism of the TTA volume reduction and antiaMisaties system being plausned is provided as Enclosure 4.

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Y JIs aeemedesee with tho' requirements of 10 CFR Part 170.22,~we have i,

determined this proposed amendment to be Claes III for unit 1 and

' Class I for unite 2 and 3.x These classifiaations~ are hesed 'em the-facts.

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that the propeeed ammedmont involves a single safety issue whiah does met imselve a sianifiamme hrsard seasideratism fee unit 1, and the propeeed 4

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= for unita 2 and'3 are dup 11estas of the unit'l proposed W.. The remittamos for M,800 (M,000 for unit 1 and $800 for tuaits~2 and 3) is belag wired to the NRC, Attentism Licensing Fee v
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Very truly years, Teasunitre VALLET AUTWORITT M. . M. Mills.- r Nuclear Regislation and safety Subscribed'andsworntfbefore me this 3/sf day of \\M<AP1980. v. U t% Y W lY metar{/hblia V W Coundssian Empires #/ D ~ unnlamanegg es ("-+ : r s) : Mr. Charles R. Christopher Chairman,' Limestone County Ceandssion 'F.O. Boa 188 Athene,1 A1=h=== 33611 Dr. Ire L. W state mesich cefiner state Department of Publia Esalth stasm offsee ne12 dias l. Heatsomery, Alabama 36104 - Mr. E. D. Essen, Superviser - tha*1aae t i emmenal Elastria Company ~, s32 seersta domene - Chattanooga, h ~37402 2 J 1. M .g W '4 + w

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?* ENCLOSURE 1 REQUEST FOR AMENDMENT TO FACILITY OPERATING LICENSE NOS. DPR-33, DPR-52, AND DPR-68 BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, AND 3 J. // _50-259, 50-260, 50-296) (DOCKET NOS. [ It is requested that facility operating licenses DPR-33, DPR-52, and DPR-68 for operation of the Browns Ferry Nuclear Plant units 1, 2, and 3 be amended / by adding a license condition to read as follows: The licensee may store low-level radioactive waste onsite in the facility as described in and subject to all conditions as stated in the application for license amendment from licensee (Letter from L. M. Mills to H. R. Denton) dated July 31, 1980. 4 I + = m .w a m . ~i ,t 1,, Eh', (g* M _g g'#. a 4 i - y;g J-Je A g 4 u.-

ENCLOSURE 2 LONG-TERM, LOW-LEVEL RADIOACTIVE WASTE STORAGE FACILITY BROWNS FERRY NUCLEAR PLAEI .m e =*y 6 e

TABLE OF CONTENTS

1.0 INTRODUCTION

1.1 Purpose 1.2 Backgrour.d 1.3 Need

1. 4 Scope 2.0 FACILITY DESIGN DESCRIPTION 2.1 Structural Design 2.2 Security 2.3 Crane 2.4 Fire Protection

2. 5 Radiation Bonitoring & Protection

2. 6 Quality Assurance 2.7 Electrical Beguirements

2. 8 Equipment Codes 3.0 FACILITY OPERATION 3.1 Handling and Storage Operations - Description 3.2 sonitoring Operations 4.0 RADIOLOGICAL CONSIDERATIONS 4.1 Radiological Assessment 4.2 Incremental Occupational Exposures 4.3 Doses to Unrestricted Areas 5.0 ENVIRONMENTAL ASSESS 5ENT 5.1 Environmental Impacts of the Proposed Action 5.2 Unavoidable Adverse Environmental Impacts 5.3 Irreversible and Irretrievable Commitments of Resources 6.0 SAFETY ANALYSIS 6.1 Handling and Storage Accidents

6. 2 Environmental Design Accidents

6. 3 Summary 7.0 DECOHNISSIONING 7.1 Ultimat'e Disposal of Waste i

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= a LIST OF FIGURES Fiqure No. Title 1 General Plan and Incation of Structures 2 Structural-Storage Modules and Gatehouse-Outline and Reinforcement 1 3 Structural-Trash Storage Module-outline and Reinforcement 4 Structural-Resin Storage Module-Outline and Reinforcement i we

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BFNP i

1.0 INTRODUCTION

1.1 PURPOSE This document is provided as supporting information for a ) proposed amendment to the operating license for each unit of i the Browns Ferry Muclear Plant. The proposed amendment is i to allow onsite storage of low-level radioactive waste at Browns Ferry. This document is intended to be fully adequate for the staff of the U.S. Nuclear Regulatory Commission to make a decision regarding the acceptability of the action authorized by the proposed amendment.

1.2 BACKGROUND

The Tennessee Valley Authority (TVA) owns and operates the three-unit Browns Ferry Nuclear Plant located in Limestone i County, Alabama. Each unit is licensed for a thermal power level of 3,293 megawatts. Commercial operation of units 1, 2, and 3 began on August 1, 1974, sarch 1, 1975, and sarch 1, 1977, respectively. Operation of Browns Ferry results in planned and controlled generation of low-level radioactive waste. This waste consists of ion exchange and condensate demineralizer resins and miscellaneous trash as described in Table 1.2-1. At the present time, TVA is shipping the waste offsite to a licensed radioactive waste burial facility. However, for the reasons outlined in section 1. 3 Need, TVA is seeking authorization by way of amendment to the existing facility operating licenses, to store the low-level radioactive waste onsite at Browns Ferry for the operational life of the facility. Iong-term storage on-site until the end of the plant's. operational life has a number of distinct benefits. It'can provide a management method for low-level radioactive waste in lieu of using increasingly scarce and uncertain space at commercial disposal facilities. These facilities are i subject to unexpected shutdowns for indefinite periods for reasons such as commercial or regulatory concerns. Because of the..long. lead times TVA's proposed action will prevent undesirable impacts on plant operation. This action will also allow time for the Federal government or commercial firms to open new disposal facilities for low-level radioactive waste. Another benefit of long-term storage comes as a result of the dramatic decrease in the amount of radiation emitted from containers at the time of disposal because of the radioactive decay. such of the radioactive waste contains radionuclides with half-lives of one year or less. For \\ 1-1 ,y4 .-,.--.-,,.._,-----m..-..-..-..-.,-w- ---<-r-w- ,-e v-

BFNP 1 l l storage times of 10 to 30 years, radioactive decay removes essentially all radionuclides except cesium-137, strontium-90, and cobalt-60 (all of which are minor contributors to the initial overall activity and container dose rate). Retaining the waste onsite for this period of decay will j result in lower exposure of individuals in unrestricted i areas during transportation of waste for ultimate offsite disposal. Lower curie contents could result in less radiological impact on disposal facilities and possibly the use of less restrictive disposal areas. Ri9 from a transportation accident will be reduced because of the lower curie content. 1.3 NEED Since the startup of Browns Ferry Nuclear Plant unit 1, TVA has packaged and shipped low-level radioactive waste (LLRW) generated at Browns Ferry to Chem-Nuclear Systems, Inc. 's (CNSI) commercial radioactive waste disposal site in Barnwell, South Carolina. In the past few months, however, significant restrictions have been placed on the amount of packaged LLRW that Barnwell will accept for burial. CNSI has announced a policy that will result in further restrictions on the volume that TVA can send to Barnwell in the very near future, and it now appears that acceptable disposal space will become increasingly scarce and uncertain within the next 10 years. The problem of the lack of sufficient available disposal space at Barnwell for the LLRW generated at Browns Ferry will progressively intensify as other TVA nuclear plants come on line, because the announced burial restrictions are being applied to each utility as opposed to each plant. This situation could worsen over the next two years because of cutbacks in TVA's monthly allocation of disposal space and the startup of Sequoyah unit 1. Even without these restrictions it is likely that additional disposal options would be needed because no other waste disposal facilities are being planned in the southeast or midwest regions of the nation. The need to develop alternatives to disposing of LLRW at CNSI's Barnwell facility is immediate. The intent of the proposed action is to ensure that the uncertain availability of commercial disposal space will not adversely af fect future electric power generation'at Browns Ferry. Browns Ferry is a major contributor to the TVA electric power system and adds significantly to the reliability at the sytem. Operation of Browns Ferry increases TVA's ability to comply with the Nation's policy of attaining energy indepedence and could continue to minimize future dependence on foreign oil. Implementation of the proposed action will make.TVA's operations at Browns Ferry essentially immune 1-2 j -,. ~., - ,e - ~. - -

BFNP i from outside restrictions on disposal of LLRW for the foreseeable future. f ^ The need for immediate action requires an LLRW management plan that can be initiated promptly. The continuing nature of the problem requires a solution that will extend into the foreseeable future. Therefore, the proposed action combines immediate administrative actions with long-term design change and plant additions as they become available. Delaying action at this time would offer TVA no advantages in resolving the present and future LLRW storage needs at Browns Ferry. Delaying action now would only make the situation more dif ficult when action is mandatory. There are no foreseeable occurrences which would help alleviate the situation in the short term that could justify TVA's waiting before taking any action. Therefore, delaying action would have the same effect as taking no action. TVA's assessment indicates that taking no action or delaying action could severely curtail electric power generating capability at Browns Ferry during a period in which use of domestic energy sources must be maximized. 1.4 SCOPE The scope of this document is limited to the waste storage facility. The information provided consists of the facility design criteria, the environmental and radiological assessments, and a safety or accident analysis, as well as 3 information regarding facility operation and decommissioning. 'Ihe design basis for the Browns Ferry long-term low-level radioactive waste storage facility as given in this document is based on USNRC Regulatory Guide 1.143. Regulatory Guide 1.143 was utilized by TVA as a minimum design basis because it was determined to be the most applicable to the nature of the facilities, although it was not specifically prepared and issued for this purpose. The actual design parameters employed by TVA in the facilities' design are in some cases I more conservative than those documented. This is done in l order to fac'ilitate the development of a standardized design acceptable for use at all TVA nuclear power plants. l 1-3 _.-..,r.- --.-a,ww.,,

TABLE 1.2-1 Scintillation Liquids Scintillation Vials oil / Water mix from lubrication and diesel oil PVC's Polyethylene Boots Rubber Shoe Covers Ion Exchange Resins Rubber Hose Plastic Hose (Malgene) Cotton Gloves, Inserts, Coveralls, and Surgical sasks Paper Coveralls Pine Crates Oak Crates Plywood Crates Scrap Iron and Steel Copper Wire Small Hand Tools Chains Cables Hops Brooms Wood used for scaffolding and ladders cable Insulation Laboratory Equipment (vials, glassware, plastic bottles) HEPA Filters Other wood and small metal objects i l l l s 1-4

BFNP i 2.0 FACILITY DESIGN DESCRIPTION 2.1 STRUCTURAL DESIGN 2.1.1 General 'Ihe maximum number of storage modules to be constructed at Browns Ferry is 22. This includes a minimum of 5 resin storage modules (25 compartments) and a minimum of 9 trash storage modules (45 compartments). The resin storage acdules and trash storage modules will be above ground, safety-related structures constructed of reinforced concrete. All storage modules will be designed to withstand the design basis events specified in 2.1.2 and will be designed and constructed for the normal loads, severe environmental loads, and extreme environmental loads specified in 2.1.3. Details of the site facility layout, the storage modules, and the gatehouse are provided in Figur.es 1 through 4. 2.1.2 Design Basis Events 2.1.2.1 Design Basis Earthquake Each storage module will be designed to withstand the design basis earthquake (DBE). The DBE is defined as a top-of-ground motion with three statistically independent orthogonal components. The peak acceleration will be a minimum 'of 0.1G. Response spectrum for this event will be taken in accordance with Regulatory Guide 1.60. 2.1.2.2 Design Basis Flood ~~ ~~ Each storage module will be located above the design basis flood elevation. The design basis flood elevation will be above the 500-year flood elevation at the site. 2.1.2.3 Design Basis Wind Each storage module will be designed to withstand the forces exerted by a wind having a maximum speed of 95 mi/h and a recurrence. interval of 100 years. 2-1 k: 9 -m-vr m

BFNP 2.1.2.4 Design Basis Precipitation Normal rainfall of 4 inches / hour has a precipitation frequency value of once l every 100 years. Grading for the facility will be such that buildup of water around the structure during and after precipitation will be minimized. 2.1.3 Loads, Definition, Nomenclature 2.1.3.1 Definition of Inad Terms for Safety-Related Structure The following terms are used in the load combination equations for safety-related structures: Normal Loads - those leads to be encountered during normal facility operation and include: Dead loads or their related internal moment and forces including any permanent equipment loads. I Live loads or their related internal moment and forces including any movable equipment loads. Thermal effect loads during normal operating conditions based on the most critical transient or steady-state condition. Severe :?nvironmental Loads include: Loads generated by the design basis wind specified for the facility. l l 2-2 n.

BFNP Extreme Environmental Ioads' include: Load generated by design basis earthquake specified for the facility. Other Loads: Construction live loads. 2.1.3.2 sinimum Live Loads 4 l The minimum roof live load is 50 lb/fte, 2.1.3.3 Precipitation Loads The maximum snow load and glaze ice load for the facility is less than the minimum roof live load specified. No rainfall buildup on the roof is anticipated since there will be no parapets and the roof will be sloped and free draining. 2.1.4 Load Combination 2.1.4.1 Rethodology For these concre te structures, the required sectio. strength used in design is the maximum value amng the several values determined for the required loading combinations of ACI 318-77, " Building Code Requirements for Reinforced Concrete." Situations occur where one or more loads in a loading combination have opposite signs from the other loads in the same combination. The following situations will be investigated for possible reversal of net effects and for determination of maximum moments and forces: A. Area distribution for live load. B. Maximum value for live load. C. Zero value for live load. Other loads will be combined with these live load situattons. 4 2.1.4.2 Ioad combinations for Concrete Structures 2-3 g w n,, s

BFNP For service load conditions, the strength design method will be used. The required section strength will be at least equal to the greatest of the load combinations given in ACI 318-77. All storage modules will meet the requirements for watertight structures. 2.1.5 Foundation 2.1.5.1 Foundation Design Each storage module foundation will be a structure composed of concrete base slab and walls placed on either in situ soil or compacted fill. The foundation of the module will be designed to withstand normal, severe, and extreme environmental loading conditions. 2.1.5.2 Soil Properties The ultimate bearing capacity for the storage module foundation will be determined by standard methods. The maximum allowable bearing capacity will have a factor of safety of 2.5 with respect to the ultimate capacity. The i minimum factor of safety for sliding and overturning f.or the storage modules will be 1.3 for normal conditions but may be reduced to 1.1 for severe and extreme environmental conditions. 2.1.5.3 Settlement The storage modules will be designed for the anticipated total and differential settlement. 2.1.6 Concrete ~ 2.1.6.1 Structural Concrete 1 All structural cast-in-place concrete and precast concrete beams and caps will have a specified minimum compressive strength of 3000 lb/in. a 2.1.7 Steel ~ 2.1.7.1 Reinforcing Steel 2-4

BFNP Reinforcing steel will be grade 60 deformed bara per specification ASTN & 615. 2.1.7.2 Structural Steel Rolled shapes, plates, and bars will be per ASTN specification A 36. 2.1.8 Drainage and Sampling Each of the compartments of a storage module will be provided with internal liquid collection and drainage capability routed to an external sampling collection point. The collection point consists of a stainless steel 2-inch drain valve and a smaller sampling valve at the low point of the drain. The external collection point is surrounded by a covered concrete sump connected to the module. The concrete sump will be utilized to collect any liquid and provided with decontaminable coating on the interior surface. 2.1.9 Decontaminable Coatings The interior surfaces of each storage module (excluding the cap) will be coated with an approved decontaminable coating system in accordance with TVA's General Construction Specification G-14, Part No. N-935. 2.1.10 Wall Thickness and Radiation Shielding The storage modules will be shielded using concrete. The outer walls of each resin storage module will be a minimum of 42 inches thick while the cater walls of each trash storage module will be a minimum of 24 inches thick. The concrete caps for resin and trash storage modules will be 24 inches thick. The resin storage modules (including foundations, walls, beams, and 24-inch caps) will be designed to support an additional 18-inch (maximum) concrete cap for additional shielding if needed. The concrete beams which I shield the joint between the concrete caps will be a minimum of 24 inches thick (vertically). s 2-5

BFNP 2.2 SECURITY The storage facility will be surrounded by a wire fabric fence with three strands of barbed wire, totaling eight feet in height with a 20-foot isolation zone on each side. An intrusion detection system and CCTV system are provided and terminate in a gatehouse. The gatehouse is designed for 24-hour operation with communications with the nuclear plant via radio and telephone. Yard lighting of 0.2 foot-candle and a patrol road within the fenced area is provided for surveillance purposes. Two points of access through the fence will be provided. 'the primary source of power for all electrical security equipment is offsite power. Backup power will be provided by a diesel generator located within the facility boundary. 2.3 CRANE 4 The crane to be used at the IIRW facility will be a rubber-tired, diesel-powered, mobile gantry crane. It will have two cross beams, a 15-ton capacity trolley on the front beam and two 30-ten capacity trolleys on the rear beam. The 15-ton hoist will be used to handle the 11RW containers and the 30-ton hoists will be used to handle the storage module caps. In order to facilitate movement from one module to another, the crane will be driven and steered by the same wheels and these wheels will be capable of turning 90* in either direction. In addition to its standard features, the crane will be equipped with an ac generator, an air compressor, eight 500-watt lights, a cable reel and a hose reel to provide air and electric power to the 15-ton book, and a CCTV monitoring system. The CCTV monitoring system will be designed to allow remote handling of the LLRW containers beyond the line of sight of the operator. The CCTV monitors, the CCTV controls, and all crane controls will be mounted in a cab. Three special lifting devices will be furnished. Handling of the resin liners will be accomplished using a rigid frame with air-actuated lifting lugs. The 55 gallon drums will be handled using a standard gravity-actuated barrel grapple. A magnetic lifting system will be provided to handle the support grating that is to be used for stability between levels of drums er liners. 2.4 FIRE PROTECTION The only significant potential for fire at the storage facility is an exterral exposure fire. The facility is of noncombustible construction and designed to provide a 3-hour i fire resistance rating from external exposure fires. The fire protection water supply is taken from the nuclear plant yard fire main. Hydrants and hydrant houses are provided around the perimeter of the storage facility in l accordance with NFPA Standard No. 24. Two points of entry are provided through the security fence to accommodate 2-6 t

BFNP standard fire department pumpers. Each storage module compartment has been sized to collect and contain that quantity of water used for manual fire fighting from two 2-1/2-inch hose streams simultaneously for a duration of at least one hour. The-storage facility will also be provided uith multipurpose dry chemical fire extinguishers in accordance with NFPA Standard No. 10. All fires will be fought by specially assigned personnel with support from the BFNP fire brigade. 2.5 RADIATION BONITORING AND PROTECTION 2.5.1 Radiation Bonitoring Radiation monitors will be permanently installed only at the security gatehouse. All other necessary radiation monitoring will be performed by the plant Health Physics staff using portable equipment. Monitoring wells in clusters will be provided and placed outside the security fence. The initial well of the cluster was core drilled under the supervision of a geologist. Representative ground water samples will be collected before waste is stored in the modules. The design and number of additional wells in the cluster should be I determined on the basis of the initial core. All wells will be fully developed, grouted, sealed, and capped to prevent the introduction of any extraneous material. Bonitoring well identification markers will be erected above ground.

2. 5. 2 Radiation Protection Except for trash, the design basis radioactivity levels of the LLRW will be based on plant operation with expected radioactivity concentrations in the reactor coolant.

The design basis radioactivity levels for trash will be a i factor of 10 higher than average levels measured at Browns Ferry Nuclear Plant through June 30, 1979. The facility will be designed for implementation of the control measures for radiation and high radiation areas as defined in 10 CFR 20. The facility will also be desiped such that the probability is small that any person would receive a dose equivalent greater than 500 mrem during any calendar year in unrestricted areas from storage' facility operation (which includes handling operations). As part of the provisions to l implement this restriction on dose equivalent in 2-7

BFNP unrestricted area, the dose equivalent rate at the storage facility security fence will not exceed 0.6 mrem per hour. During handling operations this dose rate will be temporarily exoeeded. 2.6 QUALITY ASSURANCE 'Ib ensure the storage medule structures will perform as i intended, a quality assurance program will be established l and documented. As a minimum, this program shall conform to the requirements of Regulatory Position 6 of USNRC Regulatory Guide 1.143. 2.7 ELECTRICAL REQUIRE 8ENTS The LTOSF will be provided with electrical power from offsite by the local utility. As a backup, the facility will have an electrical power generator sufficiently sized to provide the power required to operate all security features for a minimum of 12 hours. The generator will be remote from the securit.y gatehouse with manual controls located inside the gatehouse. wa

M l

L I 2-8 r v - - -

2.8 EQUIPMENT CODES All storage facility equipment shall be designed, procured, constructed, and inspected in accordance with the codes and standards identified below: EQUIPMEh7 CODES ~~ DESIGN & INSPECTION COMPONEh7 FABRICATICN MATERIALS WELDING & TESTING P1F11;G AND VALVES

a. Storage !!odule ANSI B31.1 (QA 304-L or ANSI B31.1 ANSI B31.1 Drains shall be in 316-L accordance with attachment RW of MEB E.P.23.5.5)

b. Storm AASHTO AASHTO Drains

c. Potable water National National National National cud sewers Plumbing Plumbing Plumbing Plumbing Code Code Code Codt

d. Fire NFPA Code hTPA Code hTPA Code hTPA Code Protection Standard 24 Standard 24 Standard 24 Standard 24 C}5UIE Joint Industrial AS[M AWS AlSC, ASI!!,'

Council & AISC & AVS TVA Spec. Decontamin-TVA Spec. G-14 ANSI N512 G-55 abic coatings Electrical, IPCEA Standards kSTMndustry Industry Industry Security, and Industry Radiation Standards Standards Standards Standards ANSI-N13.1-1969 Mcnitoring NEMA. Standards ANSI-N13.10-1974 Equipment RDT Standards RDTCl-1T FIRE PROTECTION NFPA Code

a. Extinguishers hTPA Code NFPA Code Standard 10 Standard 10 Standard 10

b. Hydrants, NFPA Code hTPA Code NFPA Code hTPA Code Houses, Hoses, Standard 24 Standard 24 Standard 24 Standard 24 etc.

2-9

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BFNP 3.0 FACILITY OPERATION 3.1 HANDLING AND STORAGE OPERATIONS - DESCRIPTION steel liners containing dewatered resins and SS-gallon steel drums containing trash will be transported to the storage site in shielded casks or in van-type trucks depending on dose rates. All shipments will be in compliance with DOT and NRC requirements before transport. Access to the storage facility will be through the facility's main gate. The vehicle will be taken to either a resin module or a trash module depending on the type of radioactive waste to be stored. Each module will be identified by a sign denoting its intended contents and storage status. A gantry crane will then be positioned over the module cell to be loaded, and the top hatch of the module removed and set aside. The vehicle will then be parked under the gantry crane. For resin shipments in a shielded cask, the cask cover bolts will be removed using an air wrench. The cask cover will then be removed from the cask using the gantry crane and set aside. An air-actuated remote lif ting device will remove the liner from the cask and place it into a predetermined space in the module. All operations will be observed on closed-circuit television to reduce employee exposures. The remote lifting device will then be unhooked. The cask cover will then be replaced and bolted, and the cask returned to the plant. For drum shipments in a truck, the truck will be parked i under the gantry crane. For trucks with removable tops, the drums will be unloaded directly from the truck using a remote drum handling device and placed into the module. For l trucks with rear doors, a movable ramp and forklift will be l used to unload the drums to the outside of the truck. The drums will then be lifted into the module using a remote drum handling device. All vehicles will be monitored for i contamination and excessive dose rates before they are ) returned to the plant. Steel grating will be placed between each layer of containers to provide stability. Drums will be stored up to 3-layers high. Resin liners will be stored up to 2-layers high.. i When all containers in the shipment have been stored, the top hatch will then be placed back on the module. When containers are removed for final disposition or for the contents to be volume reduced, this procedure will be reversed. ^ Records kept in the plant will indicate the placement of each container. These records will also indicate the l container identification number, curie content, dose rate, j 3-1 [ L

BFijP - type of radioactive waste, and whether the contents are volume-reducible. All laborers, crane operators, and truck drivers will be furnished by the plant. All operations at the storage facility will be monitored by plant health physics employees. Bonitoring activities include vehicle and container surveys during shipment and module loading and unloading. Periodic surveys shall also be conducted in the area outside the modules as well as regular checks to determin'e the presence of liquid at the external sampling i collection points. sampling wells in the storage area will be checked on a regular basis to indicate if any radioactive contamination has reached the underlying aquifer. Because of the potentially high radiation dose rate emitted from inside the storage module, all loading of containers into the module will be done remotely utilizing a closed-circuit television monitor to observe the placement of the container in the module. The monitor will be used to ensure that a container is placed in the correct storage cell j without damaging either the container, the storage module, or other containers in storage. The CCTV system consists of two monitors and four cameras, all completely independent of each other except for their power source. Each monitor is equipped with manual control capabilities to select display from any of the four cameras. The cameras are equipped with individual pan and tilt control. Should a camera fail, no major interruption of the system would occur. Cameras are paired and placed in such a manner that loss of a camera would not affeet the operational procedure. The crane is equipped with permanent scaffolds to provide easy access to all cameras. Replacement of a camera for repair involves replacing the damaged camera with minimal exposure to personnel. Since each monitor can survey the area through all four cameras, independent of the other monitor, the loss of one monitor would not demobilize the system. However, should a monitor fail, procedures may be slowed. Should a total failure occur of either both monitors or all cameras (low probability but possible in the case of a total power failure), one of the following courses of action would i be taken, depending on the position of the container: (1) If CCTV capability is lost while the container is outside of the storage module, the container will be -immediately returned to the truck or shipping cask from i which it was removed. If repairs to the CCTV are expected to take an excessive amount of time, the truck 3-2

BFNP or shipping cask shall be taken to a secure area of the f site for storage until the CCTV is repaired. (2) If CCTV capability is lost while the container is inside the module (but not in a stored position), several options exist. In any case, the crane and container will not be moved laterally. One option involves the use of a portable camera system available from the nuclear plant which can be rigged to observe the container. At the operations supervisor's option, the container can then be either retrieved and placed in temporary storage until the CCTV is repaired or lowered into place in the module under observation using the portable camera system. At the Operations supervisor's option, container storage may be continued utilizing the portable camera. Another option is to repair the CCTV - (if possible) while the crane remains in the position where it was when the CCTV was lost. This may not be possible if the failed equipment is in a high radiation field. The design of the mobile crane will allow storage operations at night. However, because of the decreased visibility, storage operations will normally be carried out only during daylight hours. Night operations will not be undertaken unless plant operations will be affected using only daylight storage operations. Extra lights will be used to increase visibility and to ensure that the CCTV system can be used. Low-level radioactive waste volumes are not expected to require night operations. Storage operations will not be conducted during inclement weather, such as rain or snow storms. Should the cables of the mobile crane lock due to motor or ~ power failure making it impossible for the trolley to transfer the container to its storage position, the 7 container can be remotely lowered into the cask or module by manually releasing the brake. If the trolley locks in a position that is not directly above a cask or module, the containgr can be moved laterally by driving the crane to a safe position and the container lowered manually by releasing the brake. The crane is then moved back to an area where repairs can be done. The container would remain isolated, shielded locally, and guarded until repairs are completed and the crane could return to safely place it in its stored position. A possible alternative if the liner is not above a cask or module is to position the cask truck in an area clear of the modules such that the crane can lower the liner into the shielded cask. The truck would then be taken to a secure site for storage until repairs on the crane were completed. Security operations 3-3

BFNP closed-circuit television (CCTV) monitors will be used to detect and observe potential intrusion into the storage area. sonitor screens will be located in the gatehouse. In the event of a loss of a CCTV, security personnel will call for immediate repaire A spare CCTV will be put into service, if available. During the time that the CCTV is out of service, the area normally covered by CCTV observation shall be continuously patrolled by security personnel to ensure that the security of the area is not compromised. Additional security personnel shall be utilized when necessary. 4 ALARA All employee exposures will be kept as low as reasonably achievable (ALARA). When containers with excessively high a radiation doses are handled, remote methods will be used. only employees required to handle the shipment will be allowed in an area where containers are being handled. All container and vehicle dose rates and contamination levels will be within DOT limits before shipment. Employees and containers will be monitored during all operations by health physics employees to ensure that dose limits are not exceeded and that good work practices are followed. All operations will be conducted in accordance with written procedures. 3.2 NONITORING OPERATIONS 4 3.2.1 Module Interior 1 Before low-level radioactive waste is packaged, all containers will be visually examined and/or pneumatically tested to ensure that the container is not damaged and is leaktight. When corrosion potential exists, a coated container will be used. Hodules will not be opened during inclement weather, such as rain or snow storms, to prevent unnecessary introduction of water into the module. Hatch sealing surfaces will be examined to ensure that they are in proper condition. i ~ Th'e sump in each module will be sampled periodically to detect the presence of water and/or radioactive releases in the module. Detection of water or radioactive releases in a module will require an intensive check of all containers and the inside of the module to determine the source. Corrective actions, including repackaging of a leaking container or repair of a defective hatch seal, will be i undertaken. Radioactive liquids will be collected and transported to the plant for processing by the radwaste system. Nonradioactive liquids will be 3-4

BFNP disposed of in accordance with established plant disposal operations. 3.2.2 Environment Sampling wells in the storage area will be checked on a regular basis to indicate if any radioactive contamination has reached the underlying aquifer. The area outside the module' walls will be checked routinely to detect leakage. we

m 3-5

~ BFNP 4.0 RADIOLOGICAL CONSIDERATIONS 4.1 RADIOLOGICAL ASSESS 5ENT .TVA has - performed a radiological assessment of the long-term waste storage facility, covering the operational releases expected as a result of operator error or equipment malfunction and the releases from an accidental fire. The attached Tables 4.1-1 and 4.1-2 present the major assumptions used in the assessment and the results of the assessment, respectively. Os

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I TABLE 4.1-1 BROWNS FERRY NUCLEAR PLANT - MAJOR ASSUMPTIONS FOR RADIOLOGICAL ASSESSMENT OF LONG-TERM. ONSITE LOW-LEVEL WASTE FACILITY 4 General Type of Waste LLW - miscellaneous trash and spent resins Activity 9875 Ci/yr - resin ll3'Ci/yr - trash Isotopic Breakdown About 89 percent Cs-137 and Ba-137m, 1 percent Co-60, 2 percent Co-58, .7 percent Cs-134, and 1 percent other fission, activation, and corrosion-products. OSF Operational Releases Under normal operation, any potential leachate in the storage modules will be collected and sampled prior to' release. However, it is postulated that due to operator error or equipment malfunction, a certain portion of the estimated ennual leach reaches the river via ground water. 1 Maximum Stored Activity Releases are assumed to occur when the activity in the OSF reaches a 5 maximum (at 40 yrs.). The 40-year activity is estimated at about 2.3 x 10 Ci-composed of essentially all Cs-137. Annual Leach Fraction 1 percent of the 40-year activity is assumed to leach out of the storage container per year. Travel Distance to River 700 m(2300 ft) Ground Water Velocity 1.5 m/d (5 ft/d) Total Soil Porosity 50 percent Bulk Soil Density 1.6 g/cm 3 Distribution Coefficient (K ) 500 cm /8 for Cs d 16 c,37 River Dilution Spillage is assumed to mix with 1/10 of the average river flow (4x10 yr) before reaching potential receptor pathways.

TABLE 4.1-1 (Continued) OSF Accidental Fire Release 'Non-volume-reduced LLW trash from one section of a storage-module (about 1/11 of one year's_ waste) is~ assumed to catch fire due to an unspecified incendiary event. Activity in Module Section About 10.7 Ci Co-60 8 Fractional Release from Fire 0.01 for particulates - X/Q (fif ty-percentile,1-hour, 4.7x10 37,3 ~ -2 ground level) Distance to Site Boundary 164 m (540 ft) a. WASH-1238. T w e

TABLE 4.1-2 BROWNS FERRY NUCLEAR PLANT - SUF&fARY OF RADIOLOGICAL ASSESSMENT FOR LONG-TERM ONSITE LOW-LEVEL WASTE FACILITY OSF Operational Releases -4 -Leach to River 1.6x10 mem/p (whole body) (10 CFR 50 Appendix.I -5 guidelines: 9 mrem /yr - 5.0x10 mrem /yr (thyroid) whole body;'30 mrem /yr- - organ)., f OSF Accidental Fire Air Submersion Dose at Site 2.8 mrem (whole body) Boundary [ Inhalation Doses at Site Boundary 2.4 mrem (whole body) (10 CFR 20 guidelines: 500 mrem /. 970 mrem (lung) yr to whole body and 1,500 mrem /yr to -individual organs other than the thyroid i

= BFNP 4.2 INCREMENTAL OCCUPATIONAL EXPOSURE Annual occupational personnel exposures have been estimated for the handling and placement of low-level waste in the proposed long-term waste storage facility. Dose estimates are given in Table 4.2-1 and include exposures to waste handlers, health physics monitors, crane operators, nuclear plant employees, and transport personnel.

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b -TABLE 4.2-1 -BROWNS FERRY NUCLEAR PLANT - OCCUPATIONAL DOSE ESTIMATES FOR LONG-TERM LLW'STORACE FACILITY General-Assumptions-11.; Waste is volume reduced.into 55-gallon drums with reduction' factor of 15 for resins and 36 for combustible trash 2. About 13.6' drums.of RWCU resins, 243 drums of condensate demineralizer resins, 190 drums of combustible-t'~ ash, r and 1580 drums of non-combustible trash are stored per year -3.- Exposure rates.at contact from individua1' drums are 210 R/h for RWCU resins, 43.2 R/h for condensate demineralizer resins, 3.2 R/h for combustible trash,qand 0.13 R/h for non-combustible trash

4.. Maximum num'ber.of curies in facility is about 2.3x10 Ci 5.

Maximum number of curies in a module cell is about 5542 Ci 6. Modules have 3.5-ft concrete walls'(trash modules have 2.0-ft walls) and 2.0-ft concrete cap (cap is removed for waste placement) Transport Personnels Person-rem /yr One driver exposed to 2.mR/h, 50 h/yr 0.1 4- '4 . Crane Operator -3 Two operators exposed to 7.5x10-R/h", 53 h/yr;.and 9.2x10 R/h", 418 h/yr 15.7 Waste Handlers -3 b 4.3x R 9.2 Two handlers and one health-physics tgchnician exposed to:R/h,53h/yr;and3.4x10}0R/h"/h, 101 h/yr;'0.01'R/h, 56 h/yr; 1.9x10- , 418 h/yr Monitoring Personnel -3 d One health physics staff member exposed to 9.6x10 R/h, 156 h/yr 1.5 . Includes direct and skyshine radiation from facility during waste placement; Crane operator is adjacent to a. module wall, waste handling individuals assumed to be 40 feet from the facility. b. Average exposure rate during reniote handling of drums assuming workers at 40 feet from drum, Exposure during cask removal for only one worker c. d. Includes direct and skyshine radiation from facility with cap in place; individual assumed to be 10 feet from facility.

1ty5 c TABLE 4.2-1 (Continued) Nuclear Plant Employees. Person-rem /yr ..t', 1. Distance.is'~approximately 975 m'(3,200 feet) to. plant 1.2. 2. 2,500 persons exposed, assuming.no shielding by building Exposed to 1.0x10- R/h, 2,000 h/yr -6 Exposed to 5.2x10 R/h", 53 h/yr T ~ l m

\\ BFNP 4.3 DOSES TO UNRESTRICTED AREAS The doses in unrestricted areas due to waste handling and storage in the OSF have been calculated and are given in Table 4. 3-1. These doses include direct and skyshine radiation from the facility to the site boundary, nearest resident, and nearest onsite non-nuclear facility. All assumptions are the same as for Sebtions 4.1 and 4.2, except as noted in Table 4.3-1. e b we

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~_ s TABLE 4.3-1 ' BROWNS FERRY NUCLEAR PLANT - DOSES IN UNRESTRICTED AREAS Onsite'Non-Nuclear Facility' mrem /yr '1. Distance to-nearest non-nuclear. facility is 425 m (1,400 feet)'from-4.2 a nearest module -4 b 2. Non-nuclear. personnel exposed to 6.0x10 mR/h, 2,000 h/yr and -2 exposed to 5.5x10 mR/h",'53.h/yr- -Site Boundary 1. Distance to nearest site boundary is about 165 m (540 feet) from 90 . nearest module

2., Exposed to.87. mR/h", 53 h/yr and exposed to 4.8x10- mR/h, 8,766 h/yr 7

'e Nearest Resident-1. Distance to nearest resident is about 400 m (1,310 feet) from 10 nearegt module -2 e -4

2., Exposed to 6.4x10 mR/h, 53 h/yr and exposed to 7.6x10 mR/h,

8,766 b/yr 0.08 person -rem /yr for 20 employees at this' location, a. b. Includes direct and skyshine radiation from facility with cap in place c. Includes. direct and skyshine radiation during waste placement

BFNP 5.0 ENVIRONMENTAL ASSESS 5ENT I 5.1 ENVIRONMENTAL 15 PACTS OF THE PROPOSED ACTION 5.1.1 Construction-Related Impacts i construction impacts associated with this project include fugitive dust, gaseous emissions, siltation, noise, socioeconomic, and potential impact on existing structures at Browns Ferry. Construction began in June 1980. Present planning schedules indicate that the first LLRW storage module will be available by December 1980, with additional resin and trash modules to be completed by July 1, 1982. Air Quality The construction activities associated with the radwaste storage facilities will result in some temporary degradation of local air quality. Air pollutants generated from this activity will primarily include (1) fugitive particulate emissions from various activities, including cleaning of steel and concrete, drilling, and painting; (2) - fugitive dust from earth excavation and grading; (3) particulate emissions from the open burning of small amounts of wood scraps; and (4) small amounts of particulates, hydrocarbons, nitrous oxides and carbon monoxide emissions from fossil-fuels construction and construction employee vehicles. ] The construction site mitigation program will consist of fugitive dust suppression, by methods j such as water sprinkling, which will substantially reduce this problem. Periodic inspections will be conducted to ensure proper maintenance of construction and control equipment to minimize exhaust emissions. Open burning will be conducted in accordance with all applicable Federal, State, and local regulatory requirements. t f i 1 S e L 5-1 l l

BFNP i concrete production during construction of the OSF will be approximately 150 yds 8 per hour at an offsite contractor facility. i I Land Use Impacts The construction of the OSF as currently conceived will require approximately 30 acres of land, all within the Browns Ferry reservation boundary. The proposed action involves no offsite land use conflicts. Offsite land use in the immediate vicinity is row crop farming. The proposed action will be compatible with the land use plans within the Browns Ferry reservation for the nuclear plant and its support facilities. Siltation l Approximately 80,000 yd3 of soil will be moved for the construction of the OSF to a spoils area on i the Browns Ferry reservation. During construction of this facility storm water runoff will be collected, where necessary, to prevent erosion and to minimize the amount of sediment reaching local water bodies. This method is in accordance with the best management practices developed by the Environmental Protection Agency (EPA) pursuant to the Feder&l Water Pollution Control Act. (Guidelines for Erosion and Sediment Control Planning and Implementation, EPA Environmental Protection Technological Series--EPA-R2-72-015, August 1972). Soil removal and site grading will be accomplished in a manner as to eliminate reduced flooding elsewhere and contain runoff in already present low-lying drainage areas south of the OSF site which have no discharges. Grading along the NW boundary of the OSF site will be i accomplished so that drainage will be contained within the Browns' Ferry reservation. A 1:uffer zone of approximately 1,000 feet is present between the runoff holding areas and Wheeler Reservoir. With these precautions construction activities are not expected to have a significant impact on water quality. Noise The usual sources of noise associated with construction activity will be present.

However, these noise impacts are temporary and intermittent and are limited to the site area.

The concrete, 5-2

BFNP batch plant noise is acceptable to the landowner leasing the site to the contractor. Solid Waste There will be a small amount of solid. waste generated due to the construction of the OSF. Solid wastes generated during construction will be handled in accordance with state and Federal regulations. sanitary Waste During the construction period, portable chemical toilets will be provided for use by construction personnel. There will be no onsite effluent from these facilities. TVA will obtain the use of a contractor who will dispose of the waste in State approved treatment facilities. Cultural since the proposed action will be constructed entirely within previously disturbed areas on the Browns Ferry reservation, the proposed action will have no effeet on any known archaelogical or cultural resources. Endangered or Threatened Species No known population of endcngered, threatened, or otherwise sensitive species will be adversely af fected by the development of the proposed project. Floodplains and Wetlands The site for the proposed action is not located in a ficodplain nor is it expected to directly or indirectly support or encourage floodplain developnent. There are no wetlands which will be af,fected by the project. Drainage will be developed to prevent induced offsite flooding. socioeconomic The proposed action will require a significant construction effort in view of the urgency of the situation. There is now and will continue to be significant ongoing renovations and additions to Browns Ferry, and there is manpower, housinM and services available in the area to fill the. l 5-3 ,_-_,,,-m,,__, r---,--.

BFNP construction and labor skill requirements for the OSF. As a result of an adequate supply of manpower, no overall population increase is expected as a result of this construction activity, and because this plant is near urban t areas (Huntsville and Decatur, Alabama), no significant socioeconomic impacts are expected. 5.1.2 Operation of the OSF Air Quality Operation of the OSF storage facility will have no significant effect on air quality. Water Quality i 4 The operation of the OSF will not result in an unmonitored liquid release during normal or emergency conditions (i.e., fire). Liquids resulting from operation or fire fighting will be { collected, monitored, and disposed of in 1 accordance with established plant disposal operations. Sanitary facilities will be provided in the OSF gatehouse but the liquids will be piped directly to the existing sanitary system at the Browns Ferry biothermal research facility located approximately 2,000 feet southwest of the OSF. The small flows expected from the OSr sanitary facilities (normal occupancy--two pecple) will not hinder operation of the biothermal-research facility's sanitary waste treatment system. Noise Noise, onsits or offsite, from the operation of the OSF will be minimal and will not have any significant effects on the site area. Solid Waste Management I The Resource Conservation and Recovery Act of 1976 (RCRA) specifically exludes nuclear material regulated under the Atomic Energy Act of 1954, as amended (which covers LLRW). Because the operation of the OSF will result in no significant additional amounts of solid waste to be bandled, other.than LLRW, the proposed action for these facilities does not have solid waste management impacts associated with it. Should solid and hazardous wastes other.than LLRW be generated, they would be managed in accordance with 5-4

i BFNP applicable EPA regulations for solid and hazardous wastes. 5.2 UN AVOIDABLE ADVERSE ENVIRONMENTAL IMPACTS There are no significant environmental impacts associated with the construction and operation of the OSF. During construction some siltation may occur and the release of small amounts of nonradioactive gaseous and particulate pollutants can be expected. 5.3 IRREVERSIBLE AND IRRETRIEVABLE COMMITMENTS OF RESOURCES Irreversible and irretrievable commitments of resources will include fuel oils involved in the construction of the proposed facilities along with materials used for the construction of the OSF. 4 e D W

me-1 l

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l BFNP 6.0 SAFETY ANALYSIS 6.1 LTOSF MODULE DAMAGE 6.1.1 Dropping a Storace sodule can Into a Bodule The worst case would be a recently filled resin liner storage module about to be closed. The cap could only drop into the module if at least two of four suspension cables failed and the cap were suspended higher than approximately five feet above the open module. The cap could then conceivably fall into the open module, rupturing LLRW containers and causing abrasive damage and possible minor fracture to the walls of the modules. The cap could also be damaged. No release of resins would occur since all material would be contained within the module. Plant personnel can removd the waste through the module drainage connections, repackage, and transfer it to an undamaged module cell, leaving the damaged cell to be decontaminated and repaired as required. A two-fold prevention of dropping a module cap into a module is employed, making this accident event highly %ble.- Crane lifting cables and i lifting lur asigned to withstand five times 4 the maximun.jerating load expected, and the cap lifting heights never exceed 5 feet above an open module. By designing the lifting cables and lugs to withstand five times the maximum operating load, failure of a cable or a lifting lug during 4 the handling operation is highly improbable. Therefore, the dropping of a cap is also highly improbable. However, should the cables or lugs fail an additional operational measure is employed to prevent the cap from falling into the storage module. The cap is 9 feet 5 inches wide; and for it to rotate into a position from which it could conceivably fall into the module, would require it to be in excess of 5 feet higher than the upper most rim of the module. By not lifting the cap higher than.5 feet above the mobile, it becomes impossible for the cap to fall into the module should the cables or lugs fail. As noted previously, the failure of a cable or a lug is highly improbable; therefore, the combined probability of this accident is very low, thus, the associated risk is very low. 6-1 L

BFNP 6.1.2 Dropping A Storage Module Cap Onto a Module i The worst case would be the dropping of a cap on a recently filled open module about to be closed. Damage could occur to both the cap and the module walls, consisting of possibly abrasive damage and fracture. We have determined that neither the module walls nor the cap would collapse into the module's interior. Because LLRW containers are spaced away from the module walls, only slight damage to the containers from falling bits of concrete would be encountered and the consequential release of radioactivity would be minimal. Plant personnel can gain access to the a containers and LLnW, remove the LLRW and repackage where needed, remove the undamaged containers to an undamaged module, and leave the damaged containers to be decontaminated and/or repaired. 4 The opportunity for this accident event is highly improbable since the only source of the accident is the crane's lifting lugs and cables, which have been designed to withstand five times more stress than the maximum operating stresses expected. However, to further reduce damage to the module by dropping a cap, a cap lift height of 5 feet maximum for the modules will be administratively imposed on daily crane operations. Up to this height, dropping a cap would cas;3e only minor abrasive damage to the module anit cap, leaving the integrity of the cap seals unimpaired. 6.1.3 Dropping a Storace Module C/:p Onto Another Cap see 6.1.2 6.1.4 Droppinq a Storace Module Cap Onto the Ground Should a storage module cap fall to the ground, only the cap would suffer damages. No radiation health hazard would result. The cap could be replaced with either a spare or a cap taken from an unused storage module. To eliminate the possibility of the-cap falling to the ground, the overground time of transporting the cap shall be kept to a minimum. 6.1.5 Collision of the sobile crane or Transport vehicle with storage sodule k 6-2 f -y n 4 ,---r c.,, - -,.

BFNP Due to the slow speeds involved collision of either the mobile crane or transport vehicle with a storage module would result in only minor abrasive damage to the module wall. No release of radioactivity would be involved. In the LTOSF, the transport vehicle will be moving no faster than 20 mph and the mobile crane moves no faster than 5 mph. With the combined resistive forces of the 8-inch curb and the steel reinforced concrete module wall, an impact at less than 20 mph with a storage module by a fully loaded transport vehicle would result in only abrasive damage to the module wall with no significant impact on the structural integrity of the module. 6.2 LLRW CONTAINER DAM AGE 6.2.1 Dropping an LLRW Container Into a Module The worst case would be dropping a dewatered resin liner into an open module with a resulting 100 percent spillage. Since the release would be contained withic the module, plant personnel can remove the radioactive material through the module drainage connections to a new liner and cask assembly and locally decontaminate the storage module. The potential for this accident event to occur is highly improbable due to design considerations. Lifting cables and lugs are designed to withstand five times their maximum operating stress and, therefore, are not expected to fail. Additionally, liner and 55 gallon-drum lifting devices are designed not to release unless driven i to do so by a pneumatic or mechanical force delivered by the operator. The switches that deliver these forces are totally segregated from the controls that position the trolley and crane, thus reducing confusion. In the case of the liner lifting device, should the pneumatic system fail, the device is designed such that its center of gravity and configuration lets it keep a firm grip on the liner. As for the 55-gallon drum lifting device, the drum is held basically by its own downward force. The only way to release a drum is to completely remove its downward force on the i lifting device by setting the drum down on the ground or other surface, and mechanically driving i the gripping claws apart. l 1 I 6-3

BFNP 6.2.2 Droppinq a LLRW Container Outside of a Storage sodule The worst case would be the dropping and the subsequent-release onto the LTOSF grounds of the entire contents of a dewatered resin liner. Appropriately protected LTOSF personnel could collect and repackage all spilled LLPW and contaminated soil to locally decontaminate the area. Should the rupturing of a dewatered resin liner with a subsequent loss of all LLRW onto the LTOSF grounds be followed by a rainfall, no significant amounts of radioactivity would be expected to enter potential drinking water sources due to the long distance to the river and sorptive soil properties. 6.2.3 Dropping a shield cask Lid Onto Its open Cask No damage to the liner within the cask can occur, nor would there by any damage to the cask itself. Precautionary design considerations given to the crane's lifting cables are noted in 6.1.1. 6.2.4 Collision Between a Transport Vehicle and the Mobile crane The likelihood of a collision between a transport vehicle and the mobile crane is reduced since both machines are not in motion at the same time. The only time that such an accident has the potential to occur is when the crane straddles the module and transport vehicle. The wheel of the crane is kept from the transport vehicle by an 8-inch-high curb. Should the crane override the curb, its speed is too slow to do any damage to either the LLRW containers or to the transport vehicle. 6.2.5 Loaded Transport Vehicle Fire or Explosion We have determined that a resin liner in its transportation cask is safe from fire or explosion through a review of the safety performance history of interstate transit of LLRW. Explosion or fire of a transport vehicle carrying the 55-gallon drums is likewise considered to be highly unlikely. 6.2.6 Sabotage of LTOSF Damage to LLRW containers inside shipping casks, as well as inside the storage modules, as a result l l 6-4

BFNP of sabotage is highly improbable, due to the high quality of the design and security measures employed. Sabotage of the LTOSF is considered a highly improbable occurence for the following reasons: (1) A security fence is provided around the facility. The grounds and surrounding area are monitored by CCTV and patrolled by security personnel on an around-the-clock i basis. The facility is completely illuminated at all times, including tops and sides of all structures within the security fence. The fence totals 8-feet tall topped with 3 strands of barbed wire, and is bounded by a total of 40 li near feet of cleared land entirely around its perimeter, and is equipped with an intrusion detection system, and tamper indication attached to an alarm in a security gatehouse. The security gatehouse will contain the CCTV monitors and facilities for telephones and PSS radio. All locking devices for doors and gates will be key-controlled, high-security locks. Altogether, the security system provides advanced intruder detection, penetration determent, and rapid communication and alert capabilities that make sabotage virtually impossible. (2) The wastes stored at the LTOSF are low in radioactivity, making them unlikely targets j of sabotage. (3) Storage modules and resin liner transportation casks are extremely shock resistant because of their design to l withstand transportation accidents and seismic activity. 6.2.7 Liner Breech Due sto Freezinq of Resins The breech of a liner by the crystallization expansion due to freezing of water mixed with resins inside the liner is improbable. Experimental results submitted to the NRC by GPU Service Corporation dated November 17, 1979, proved that resin liners, filled to capacity with dewatered resins, do not rupture when freezing of the dewatered resin contents occuro. 6-5

= BFNP 6.3 SunnARY In summary, to provide long term LLRW storage facility integrity and longevity, the storage modules, associated facilities, and equipment will be designed, operated, and maintained in order to minimize the consequences of, if not totally eliminate, the potential for these highly unlikely accidents to occur. e we e g i 6-6 f f l

BFNP l 7.0 DECONHISSIONING 7.1 ULTIMATE DISPOSAL OF WASTE i Low-level radioactive waste storage in the proposed facility is planned to begin as needed (but not earlier than December 1980) and end at the end of the operational life of the plant. Near the end of plant life, a final decision will be made as to the method for decommissioning the storage facility. There are currently several options under consideration for decommissioning. These options are: 1. Placing the storage facility in an inactive state and providing a security and monitoring force for an indefinite time. 2. Sealing all radioactive material inside the storage facility (utilizing a material such as concrete) in a technique known as entombment. 3. Retrieving all radioactive waste containers and trans-porting all of this material to another f acility. The storage site can then be decontaminated as necessary, leaving the area in as close to its original state as possible. This method may also involve dismantling and removing the storage facility. No specific method will be selected at this time since actual decommissioning for the storage facility will not be necessary for approximately 30 years. Other methods may be developed in this time period which are more advantageous than the above methods. It is TVA's intention at this time to retrieve all stored radioactive waste. If, for some reason, TVA cannot remove the stored material for offsite disposal, the material can remain in the storage facility. Security and environmental monitoring precautions will be continued until either the material is disposed of offsite or the facility is released for unrestricted use. The viability of the latter option depends on container doco rates and specific activities as well as a regulatory definition of the radiation and concentration levels which are considered acceptable. Although the exact decommissionirig method will not be determined until needed, the third method above is preferred by TVA at this time. Af ter all containers of low-level radioactive waste hav e been removed and the scructure is no longer needed as a radioactive wacte storage area, the facility will be decommissioned in accordance with the following guidelines: l 7-1

BFNP i 1. TVA will make a reasonable ef fort to eliminate residual contamination. 2. No radioactive surface will be covered by painting, plating, or other method until it is known that contamination levels, to be determined by a survey and documented, are below a reasonably achievable limit. 4 3. TVA will use the limits presented in Table I of USNRC Regulatory Guide 1.86 as guidelines. 4. Before release of the premises for unrestricted use, TVA will make a comprehensive survey establishing that the level of residual contamination is as low as reasonably achievable. A report describing the survey and its results will be filed with the Director, Of fice of Nuclear Reactor 99gulation, U. S. Nuclear Regulatory commission, with copies to the Director, Office of-Inspection and Enforcement Headquarters and to the Director, Region II OIE office. The survey report will be filed at least 30 days before the planned date of abandonment of the storage area. 5. TVA may use the storage facility and surrounding area for other plant operations following decommissioning. TVA is also implementing the following guideline criteria and additional considerations related to facility decommissioning: 1. Decontaminable coatings will be used in the onsite storage facility to facilitate decontamination. 2. saterials that cannot be decontaminated to the unrestricted levels identified in Table I of Regulatory Guide 1.86 will be disposed of by transporting to a permanent disposal site the same as for the radwaste containers. 3. saterials that meet the unrestricted levels of Regulatory Guide 1.86 will be disposed of in routine fashion. i' i t 7-2 l

e ENCLOSURE 3 CONSTRUCTION SCHEDULE LONG-TERM, LOW-LEVEL " ADI0 ACTIVE WASTE STORAGE FAC11T BROWNS FERRY NUCLEAR PLANT O

FACILITY CONSTRUCTION SCHEDULE i 1 An evaluation was performed pursuant to 10 CFR Part 50.59, in which i it was concluded that construction of the storage facility did not constitute an unreviewed safety question. Therefore, NRC's approval

was not needed before initiation of construction activities. Initial

-phases of construction began in June 1980. The present schedule cal's for completion of one year's storage i capacity by December 1, 1980. Completion of all modules is targeted - for' July 1, 1982. The accompanying figure shows the major milestones of constructions. Five years worth of storage of as-produced waste represents long-term storage for volume reduced waste for the remaining life of the plant. 1, f s e n 5 x...

LOW LEVEL WASTE STORAGE FACILITY CONSTRUCTION SCHEDULE 80 81 82 83 JAN JAN JAN JAN LONG TERM ONSITE CS CC STORAGE FACILITY (LTOSF) ~~ ist YEAR CAPACITY w 7-1-82 - 5th YEAR CAPACITY CS Denotes start of construction ( June 12, 1980 ) CC Denotes completion of construction ( July 1,1982 ) NOTE: The LTOSF may be expanded in the future if the need arises; however, the total number of storage modules shall not exceed 22. 4 4 O

ENCLOSURE 4

SUMMARY

VOLUME REDUCTION AND SOLIDIFICATION SYSTEMS FOR SOLID AND LIQUID LOW-LEVEL RADIOACTIVE WASTE (LLRW) PROPOSED FOR TVA NUCLEAR PLANTS INTRODUCTION The radioactive waste volume reduction and solidification systems proposed for TVA nuclear plants combine the processes of evaporation and incineration to process a variety of liquid and/or chemical wastes, spent ion exchange resins, filter treatment sludges, contaminated lubricating oils, and miscellaneous contaminated combustible solids such as paper, rags, protective clothing, and wood. The volume reduction system can reduce the volume of the LLPH which is produced at a particular nuclear plant by an overall factor of 10 or more. Equally important to reducing the volume of the LLRW generated at a nuclear plant is the final form of the LLRW to be stored or disposed of. The solidification system will immobilize in a suitable binding agent the granular solids and ashes that result from the volume reduction of LLRW by evaporation and inciner-tion. DEFINITIONS (1) Low-Level Radioactive Waste - That waste which is contaminated with radioactivity such that it must be packaged for safe handling and transportation to a USNRC or state licensed commercial burial site. 1 l \\

kn ir-4 l' (2) Evaporation - To remove liquid or moisture by heating so as to make dry or reduce to a denser state. ~ (3)' Incineration - To burn or reduce to ashes. VOLUME REDUCTION SYSTEM .The volume reduction system to evaporate and incinerate the LLRW arising from power generation at TVA nuclear plants will result in an overall reduction in the volume of LLRW by a factor or 10 or more. ~ Incineration takes place inside of a metal process vessel that is normally 24 to 48 inches in diameter and 20 to 30 feet tall. The vessel is constructed of acceptable corrosion-resistant materials and may be either refractory lined or provided with an external - cooling shroud in order to maintain external surface temperatures at acceptable levels. Combustible materials such as spent ion exchange resins, filter treatment sludges,. contaminated lubricating oils, and miscellaneous, contaminated combustible solids are remotely fed-to the incinerator vessel at a controlled rate to maintain process temperatures and are subsequently reduced to ashes or dry powder. .The gases resulting from the incinerator process which exit the incinerator vessel are treated for removal of entrained particulates and hazardous gases by an efficient off-gas cleanup system which consists of wet scrubbing solution (caustic), a high efficiency particulate filtration system followed by continuous radiation -2

l monitoring and control. If preset acceptable radiation levels'are exceeded,Jthe incineration process is automatically shut down and the gaseous release terminated. Water, not released as water vapor to the atmosphere, is collected in the wet scrub. solution tank and can be recycled to the evaporation portion of the volume reduction system. Several types of equipment are available to evaporate to dryness the liquid and/or chemical wastes which are collected at a nuclear plant. Included in this list are fluid bed dryers, wiped film type evaporators, and extruder-evaporators. In some processes, the aqueous slurries are reduced to dryness and immobilized in an acceptable binding agent in one step whereas in other processes such as the fluid bed dryer, the water is driven off to leave behind the dry solids in the form of a free-flowing granular material which is subsequently immobilized. Each of the processes result in a reduction in volume with the fluid bed dryer achieving the maximum volume reduction attainable for liquid wasias. SOLIDIFICATION SYSTEM The free-flowing granules and ashes resulting from the volume reduction system must by USNRC regulations be immobilized and packaged in a suitable container prior to their being transported to a commercial disposal site. TVA believes that these same requirements 3

a

4 should be applied to the solid granular residues before they dre stored onsite. Thus, a solidification system will provide a solidification agent that will immobilize the granular solids and ashes resulting from the volume reduction process. Several solidification agents are available; however, the properties that -

TVA considers of primary importance in the choice of the particular binding agent are: 1. low leachability of radioactivity 2. high thermal conductivity 3 chemical stability 4. resistance to radiation effects 5. meci snical ruggedness 6. noncorrosiveness to container 7. minimum volume 8. flexibility in its application 9. lowest cost to achieve acceptable results VOLUME REDUCTION FACILITY STRUCTURE TVA proposes to construct a new and separate building to house the volume reduction system and solidification system equipment at each nuclear plant site, because existing building space is not available. The new structure will-be approximately 80 x 140 x 70 feet tall ar.d will be constructed adjacent to auxiliary plant facilities in the '4 n

i immediate vicinity of existing LLRW processing areas. The design of the structure will be in accordance with all applicable regulatory requirements and as a minimum will satisfy NRC Regulatory Guide 1.143, " Design Guidance for Radioactive Waste Management Systems, Structures, and Components Installed in Light-Water-Cooled Nuclear Power Plants." Construction of the facility will be conducted in such a way as to not adversely impact the safety or continued operation of the nuclear plant's operating units. RADIOLOGICAL AND NONRADIOLOGICAL IMPACTS Of primary concern to TVA in deciding to pursue the volume reduction of LLRW was the potential radiological and nonradiological impacts on the overall plant operation due to the incorporation of the volume reduction system. These impacts were investigated by TVA for the different volume reduction systems available. Topical safety analysis reports for several different volume reduction systems are currently J undergoing review or have been approved by the USNRC. In particular, the topical-reports for the Newport News Industrial and Aerojet volume reduction systems have been undergoing review of the USNRC since June .1977 and October 1979, respectively. A review by TVA of these topical reports reveals that on a generic basis the impacts of these systems on overall nuclear plant operations from a radiological and nonradiological standpoint are minimal and well within acceptable 4 4 limits. 5

I EXISTING PROCESSING SYSTEMS The conventional type LLRW processing systems which are presently installed at TVA's Browns Ferry, Sequoyah, and Watts Bar Nuclear Plants were procured, designed, and installed several years ago. Neither of these installed systems produce a final solidified product that will satisfy the disposal facility requirements and federal regulations that will exist today or that will be implemented in the near future. As such, TVA has been for some time evaluating the alternatives available, and considering implementation of new systems and equipment. The proposed volume reduction and solidification systems will produce in a safe, efficient, and cost effective manner a final solidified product that will satisfy all current and pending regulations known to TVA. THE NEED Since the startup of Browns Ferry Nuclear Plant unit 1, TVA has packaged and shipped the LLRW generated at Browns Ferry to Chem-Nuclear Systema, Inc.'s (CNSI), commercial radioactive waste disposal site in Barnwell, South Carolina. In the past few months, however, significant restrictions have been placed on the amount of packaged LLRW that Barnwell will accept for burial. Depending on the amount of TVA's monthly allocation, without volume reduction, Browns Ferry may generate more LLRW than Barnwell will accept from TVA. CNSI has announced a policy that will result in further restrictions on the volume that TVA can send to Barnwell in the very near future, l i 6 8

e . and it now. appears that acceptable disposal space will become l The exceedingly scarce and expensive within the next 10 years. problem of available disposal space at Barnwell for the LLRW generated at Browns. Ferry will be significantly worsened as other TVA nuclear plants come on line, because the announced burial restrictions are being applied to each utility as opposed to each plant. This situation could worsen over the next two years due to cutbacks in TVA's monthly allocations of disposal space and the startup of Sequoyah unit 1. Even without these restrictions it is likely that volume reduction will be needed because no other waste disposal facilities are being planned in the southeast or midwest regions of the nation. The need to ensure the ability of disposing of LLRW at CNSI's Barnwell facility is immediate and represents a potentially serious impact to the future operation of TVA's nuclear plants. The intent of the' proposed action is to ensure that the unavailability of commercial disposal space will not restrict future electric power generation at TVA's nuclear plants. TVA's existing and planned nuclear plants will contribute significantly to the TVA electric power system and will increase the reliability of the system. Continued operation of these plants will increase TVA's ability to comply with the Nation's policy of attaining energy independence and could continue to minimize future dependence on foreign oil. Implementation of the proposed action will .make operation of TVA's nuclear plants considerably less dependent on restrictions'on disposal of LLRW for the foreseeable future. '7 m 'l

~, . The.need for immediate action requires that TVA action be initiated If no action is taken to provide volume reduction of LLRW promptly. at TVA nuclear plants,.TVA's ability to continue nuclear plant . operations may be severely hampered. Operating costs and the The potential for health effects will also increase substantially. availability of commercial disposal space in the future is at best uncertain. At the present time the public concerns regarding nuclear waste -disposal makes it unlikely that new LLKW disposal facilities will be commissioned by private or governmental groups soon enough to If no action prevent significant impact on TVA generating capacity. is taken at this time, TVA would have to consider limiting or ceasing operation of its nuclear plants at some time in the future. Furthermore, if power generations are halted, the nuclear plant would still continue to generate small amounts of LLRW due to plant maintenance and decommissioning activities. e e 8 6

i. l Delaying action at this time would offer TVA no advantages in resolving the present and future LLRW needs. Delaying action now 'would only make the situation that much more difficult when action is mandatory.. There are no foreseeable occurrences which would help alleviate the situation in the short term that could justify TVA's waiting before taking any action. Therefore, delaying action would have the same effect as taking no action. TVA's assessment indicates j that taking no action or delaying action would severely curtail electric power generating capability at a period in which use of domestic energy sources must be maximized. Jeopardization of the ~ operation at TVA's nuclear plants must be avoided, because of the i need for power. Therefore, neither the no action nor delayed action alternative is acceptable. i

SUMMARY

The overall concept of LLRW volume reduction, solidification, and packaging provides a method of LLRW management which is very cost effective and amenable to a variety of LLRW management concepts, such long-term onsite storage, regional waste disposal / storage [ facilities, shallow land disposal, and deep geological disposal. The combined use of volume reduction systems and solidification systems provided substantial-improvement over present methods of LLRW treatment _and disposal,-such as: O 9

4 *, 1. Significant reduction of LLRW volumes. 2. Reduction of disposal costs. 3 Solidified waste forms with physical pronerties superior to those forms produced by present methods. 4. Flexibility to meet the criteria of a variety of ultimate waste disposal concepts. 5. Potential for retrievability and further processing, if desired by future needs.- I E40176.08 o 10 - -}}

ML19330B791

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1.0 INTRODUCTION

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1.2 BACKGROUND

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SUMMARY

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ML19330B791

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1.0 INTRODUCTION

1.0 INTRODUCTION

1.2 BACKGROUND

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SUMMARY

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