ML20056B357

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Nonproprietary Revised Pages to Application for Renewal of License SNM-1097
ML20056B357
Person / Time
Site: 07001113
Issue date: 08/24/1990
From:
GENERAL ELECTRIC CO.
To:
Shared Package
ML20056B355 List:
References
NUDOCS 9008280174
Download: ML20056B357 (51)
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5 TABLE OF CONTENTS l I - / 't Section1 Title Page j \\_f 4 1 i, 15.13 Fuel Bundle Assembly.......................... II-15.63 1 15.14-Fuel Bundle Leak Test and Final Inspection.... II-15.65 g 15.15-LFuel Bundle Storage........................... II-15.66 i 15.16= Packaging of Fuel Bundles and Loose Rods 'for Transport................................. II-15.68 q i 15.17 Uranium Recovery and Waste Treatment Operations II-15.69 j i 15~.18 Uranyl" Nitrate Conversion..................... II-15.136 l 15.19-Chemical-Metallurgical Laborptory.... 4....... II-15.141.- 3 - 15.20 . Process Technology Laboratory................. II-15.143' 15.21 Outside Product Can Scorage................... II-15.145-15.22 Uranium Recovery from Lagoon Sludge Facility... II-15.146: L i t f~T- -CHAPTER 16 l (_) ACCIDENT ANALYSES II-16.1 i I I 9 [ } ()c NRC LICENSE SNM-1097 DATE 8/24/90 PAGE - DOCKET # 70-1113 REVISION 1, k 1 ~ .g._ -...,r

REVISIONS BY PAGE r Application Application Application Page Date Page Date Page Date TABLE OF CONTENTS CHAPTER 2 I-3.11 5/22/89 I-3.12 1 5/22/89 I-2.1 5/22/89 I-3.13 2 I-2,2 I-3.14 3 I-2.3 I-3.15 4 I-2.4 I-3.16 5 I-2.5 I-3.17 6 8/24/90 I-2.6 I-3.18 7 8/24/90 I-2.7 I-3.19 I-2.8 I-3.20 I-2.9 I-3.21 I-2.10 I-3.22 PART I I-2.11 I-3.23 I-2.12 I-3.24 I-2.13 I-3.25 CHAPTER 1 I-2.14 I-3.26 I-2.15 I-3.27 I-1.1 5/22/89 I-2.16 I-1.2 I-2,17 I-1.3 I-2,18 I-1.4 I-2.19 CHAPTER 4 I-1.5 8/24/90 I-2.20 I-2.21 I-4.1 5/22/09 I-1.6 I-1.7 I-2,22-I-4.2 I-1.8 I-2.23 I-4.3 I-1.9 I-2.24 I-4.4 I-1.10 I-2.25 I-4.5 I-1.11 I-4.6 I-1.12 I-4.7 I-1.13 I-4.8 I-1.14 CHAPTER 3 I-4.9 I-1.15 I-4.10 I-1.16 I-3.1 5/22/89 I-4.11 I-1.17 I-3.2 I-4.12 I-1.18 5/22/89 I-3.3 I-4.13 I-1.19 I-3.4 I-4.14 I-1.20 I-3.5 I-4.15 . I-1.21 I-3.6 I-4.16 I-3.7 I-4.17 I-3.8 I-4.18 I-3.9 I-4.19 I-3.10 I-4.20 NRC LICENSE SNM-1097 DATE 8/24/90 PAGE DOCKET # 70-1113 REVISION 1 ) s { x i REVISIONS BY PAGE I i i ^-' Application Application Application Pace Date Pace pate Pace Date II-14.31 5/22/89 II-15.22 5/22/89 II-15.64 5/22/89 II-14.32 II-15.23 II-15.65 II-14.33 II-15.24 II-15.66 II-14.34 II-15.25 II-15.67 II-14.35 II-15.26 II-15.68 II-14.36 II-15.27 II-15.69 II-14.37 II-15.28 II-15.70 II-14.38 II-15.29 II-15.71 II-14.39 II-15.30 II-15.72 II-14.40 II-15.31 II-15.73 II-14.41 II-15.32 II-15.74 h II-14.42 II-15.33 II-15.75 II-14.43 II-15.34 II-15.76 II-14.44 II-15.35 II-15.77 II-14.45 II-15.36 II-15.78 II-14.46 II-15.37 II-15.79 II-15.38 II-15.80 II-15.39 II-15.81 II-15.40 II-15.82 CHAPTER 15 II-15.41 II-15.83 II-15.42 II-15.84 (~) II-15.1 '5/22/89 II-15.43 II-15.85 (_/ II-15.2 II-15.44 II-15.86 II-15.3 II-15.45 II-15.87 II-15.4 II-15.46 II-15.88 II-15.5 II-15.47 II-15.89 II-15.6 II-15.48 II-15.90 II-15.7 II-15.49 II-15.91 II-15.8 II-15.50 II-15.92 II-15.9 II-15.51 II-15.93 II-15.10 II-15.52 II-15.94 II-15.11 II-15.53 II-15.95 II-15.12 II-15.54 II-15.96 l II-15.13 II-15.55 II-15.97 II-15.14 II-15.56 II-15.98 j II-15.15 II-15.57 II-15.99 II-15.16 II-15.58 II-15.100 II-15.17 II-15.59 II-15.101 l II-15.18 II-15.60 II-15.102 II-15.19 II-15.61 II-15.103 II-15.20 II-15.62 II-15.104 [ II-15.21 II-15.63 II-15.105 l o k_ NRC LICENSE SNM-1097 DATE 5/22/89 PAGE DOCKET # 70-1113 REVISION O >O 3EVISIONS BY PAGE Application Application Application Pace _D a t e ' Pace Date _ Pace Date II-15.106 5/22/89 II-15.151 8/24/90 II-15.107 II-15.152 II-15.108 II-15.153 .II-15.109 II-15.154 II-15.110 II-15.155. II-15.111 II-15.156 II-15.112. II-15.157 II-15.113 II-15.158 II-15.114 II-15.159 II-15.115 II-15.160 II-15.116 II-15.161 II-15.117 II-15.162 II-15.118 II-15.163 II-15.119 II-15.164 II-15.120 II-15.165 11-15.121 II-15.166 II-15.122 II-15.167 II-15.123 II-15.168 II-15.124 II-15.169 II-15.125 II-15.170 II-15.126 II-15.171 11-15.127 II-15.172 II-15'128 II-15.173 II-15.129 II-15.174 II-15.130 II-15.175 II-15.131 II-15.176 II-15.132 II-15.133 CHAPTER 16 II-15.134 II-15.135 II-16.1 5/22/89 II-15.136 II-15.137 II-15.138 II-15.139 II-15.140 II-15.141 II-15.142 II-15.143 II-15.144 II-15.145 II-15.146 8/24/90-II-15.147 II-15.148 II-15.149 II-15.150 NRC LICENSE SNM-1097 DATE 8/24/96 PAGE DOCKET # 70-1113 REVISION 1.

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.j a. i 1.5 AUTHORIZED ACTIVITIES ,),

v This application for license renewal requests l

acthorization to. receive, possess, use, store and ship j authorized'apecial nuclear materials pursuant-to 10 CFR j Parts 19. 20, 21, 70, 71, 73, 74 and 75. 1.5.1 Product Processino Operations 'I 1.5.1.1 UP. Conversion - ConversAon of uranium hexafluoride to i uranium oxides by ADU, GECO, and a steam hydrolysis l go process. 1.5.1.2 Fuel Manufacture - Fabrication of nuclear reactor fuels-containing uranium, j 1.5.1.3 Scrap Recovery - Reprocessing of.unirradiated scrap from GE-Wilmington and from other sources with nuclear {~'f ~ safety characteristics similar to GE-Wilmington' f in-process materials. },! 1.5.*.4 Waste Recovery.- Recovery of uranium from. wet and' dry sludges stored in.on-site lagoons, pits and basins. The . recovered uranium ~will'be returned.to the fuel processing facility. ? 1.5.2 Process Technology Operations j l 1.5.2.1 Development'and fabrication of reactor fuel, fuel-elements and fuel assemblies in small amounts or of advanced design. y i l 1.5.2.2 Development of scrap recovery processes, o 'f~)i (s NRC LICENSE-SNM-1097 DATE 8/24/90 PAGE DOCKET # 70-1113 REVISION 1 I-1.5

j 7 (bW 1.5.2.3 Determination of interaction between fuel additives and fuel materials. 1.5.2.4 Chemical analysis 6nd material testing, including physical and chemical testing and analysis, metallurgical examination and radiography of uranium compounds, alloys and mixtures. l-1.5.2.5 Itatrument research and calibration, including development, calibration and functional testing of L nuclear instrumentation and measuring devices. l'.5.2.6 Other process technology development activities related to, but not_ limited by, the above. 1.5.2.7 Ccnversion of UF, to UO, and other intermediate compounds using wet and dry processes. i h 1.5.3 Laboratory operations Chemical, physical or metallurgical analysis and testing of uranium compounds and mixtures, including but not limited to, preparation of laboratory standards. 1.5.4 General Services operations 1.5.4.1 Storage of unirradiated fuel assemblies, uranium compounds and mixtures in areas arranged specifically for maintenance of criticality and radiological safety, 1.5.4.2 Design, fabrication and testing of uranium prototype processing equipment. NRC LICENSE SNM-1097 DATE 8/24/90 PAGE I DOCKET # 70-1113 REVISION 1 I-1.6

C o u, + 1 j -f f ' u 1;5'4.3 Maintenance and repa1r of uranium processing equipment ~"- s ) .and auxiliary systems. I w/ o l 1.5.4'.4 Storage and nondestructive testing of fuel rods ] o i containing licensed amounts of plutonium.- 1 1.5.5 Waste Treatment and Disposal 1.5.5.1 Treatment, storage and disposal and/or shipment of. i L o P liquid and solid wastes whose discharges are regulated-h l T 1.5.5.2 Decontamination of non-combustible contaminated wastes to reduce uranium contamination levels, and subsequent shipment of such low-level radioactive wastes to licensed burial sites for disposal or as authorized by l the NRC. 5 l'5.5.3 Treatment or. disposal of combustible wastes and scrap' (N material pursuant to 10 CFR 20.302(a) and 10 CFR >~] 20.305. 1.5.6 Off-Site Activities } 4 Testing, demonstration, nondestructive modification, and-storage-of materials and devices'containing unirradiated uranium, provided that such materials and devices shall remain under the control of GE-Wilmington. s 4 1.6 EXEMPTIONS AND SPECIAL AUTHORIZATIONS i is 1.6.1 Requirements for Prior Authorization of Activities by License Amendment '/'s ls I NRC LICENSE SNM-1397 DATE 8/24/90 PAGE DOCKET # 70-1111 REVISION 1 I-1.7

) I Prior authorization by license amendment shall be required for the following activities: k 1.6.1.1 Major changes or major additions to existing processes which may involve a significant increase in potential or actual environmental impact resulting from utilizing such changes or additions. i 1.6.1.2 Major-process changes or major additions which involve a new process technology for which a criticality safety demonstration has not been previously submitted to the NRC. In determining whether a new process technology requires auch prior authorization by license amendment, the following factors will be considered: (1) type of equipment utilized, (2) chemical reactions involved and (3) potential and/or actual. environmental impact. 1.6.1.3 Proposed activities for which specific application and prior approval are required by NRC regulations. lll 1.6.2 Conte. nation-Free Articles Authorization to use the guidelines and contamination and exposure rate limits specified in license pages I-1.18 through I-1,21. " Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of Licenses for Byproduct, Source, or Special Nuclear Material," US NRC, August 1907, for decontamination and survey of surfaces or premises and equipment prior to abandonment or release for unrestricted use. 1.6.3 Disposal of Contamination-Free Liquids NRC LICENSE SNM-1097 DATE 8/24/90 PAGE DOCKET # 70-1113 REVISION 1 I-1.8 I

l ?. 1.6.3.1 -Hydrogen Fluoride Solutions O Authorisation, pursuant to 10 CFR 70.42(b) (3) to transfer liquid hydrofluoric acid to-Brush Wellman, Elmore, Ohio, through the chemical supplier, Consolidated Chemical Company, Kansas City, Missouri, without either company possessing an NRC or Agreement State license for special nuclear material, provided-that the concentration of uranium does not exceed three parts per million by weight of the liquid and the enrichment is less than 6 weight. percent U885 The hydrofluoric acid is transferred and used in such a manner that the minute quantity of uranium does not enter into any food, beverage, cosmetic, drug or other commodity designated for ingestion or inhalation by, or application to, a human being such that 'he uranium concentretion in these items would exceed that which (} naturally exists. Additionally, the acid is used in a process which will not release the low levels of radioactivity to the atmosphere.as airborne material and whese residues will remain in a lagoon system. Prjor to shipment, each transfer is sampled-and measured to assure that the concentration does not exceed three parts per million of uranium. GE-Wilmington shall maintain records under this condition of license including, as a minimum, the date, ^ uranium concentration and quantity of all hydrofluoric acid transferred. NRC LICENSE SNM-1097 DATE 8/24/90 PAGE DOCKET # 70-1113 REVISION 1 I-1.9

o f 1.6.3.2 Nitrate-Bearino' Liquids k Authorization, pursuant to 10 CFR 20.302(a), to dispose of nitrate-bearing liquids, provided that the uranium concentration does r.at exceed a 30-day average of 5 parts per million by weight of the liquids and the enrichment is less than 6 weight percent U885, by transport to an off-site liquid treatment system located at vederal Paper Board Corporation, Riegelwood, North Carolina, in which decomposi. ion of the nitrates will occur and from which the denitrified liquids will be discharged in the effluent from the system. The environmental monitoring program as described in Table 5.1 is used to control these activities. 1.6.4 Use of Materials at Off-Site Locationg lll 1.6.4.1 Authorization to use up to 15 grams of U885 at other sites within the limits of the United States and at temporary job sites of the licensee anywhere in the United States where the Nuclear Regulatory Commission maintains jurisdiction for regulating the use of licensed material. The manager of the radiation safety function shall establish the safety criteria for material being used at of f-site locations and shall designate tiae individual who will be responsible for carrying out these criteria. 1.6.4.2 Authorization to store at nuclear reactor sites, uranium fully packaged as for transport in any Fissile Class I package, in accordance with the conditions of a license NRC LICENSE SNM-1097 DATE 8/24/90 PAGE DOCKET # 70-1113 REVISION 1 I-1.10

m j [.. - ' E authorizing' delivery of such containers to a-carrier for ( ) Fissile class I. transport, at locations in the United States providing such locations minimizet the severity of p potential accident conditions to be no greater than-l those in'the design bases for the containers during transportation. L Provisions for' compliance-with applicable 10.CFR 73 requirements are described in the NRC-approved GE-Wilmington Physical Security Plan dated June 6,~ 1986, as' currently revised in accordance with regulatory. provisions. Storage at nuclear reactor sites is subject to the financial protection and indemnity provision of 10 CFR L 140. 1.6.4.3 Authorization to store at nuclear reactor sites, arrays ( { of. finished reactor fuel rods and/or assemblies in any of theLinner metal ~ containers of the RA-series shipping-t -. package described in NRC~ Certificate of: Compliance Number 4986 at locations in the United States providing such locations minimize the severity of potential . accident conditions to be no greater than those in the-design bases for the containers during tra'nsportation. l L [ Arrays may be constructed without limit to the number of l containers so stored, except that each array shall be stacked to the smaller of 4 containers high car the height demonstrated.to comply with criticality safety L requirements. Each container must be separated by nominal 2-inch wooden studs, with the width and length j l for each array and separation between arrays determined I l only by container handling requirements. l l NPC LICENSE SNM-1097 DATE 8/24/90 PAGE ' DOCKET # 70-1113 REVISION 1 I-1.11

h l Provisions.for compliance with applicable 10.CFR 73 requirements are described in the NRC-approved GE-Wilmington Physical Security Plan dated June 6, 1986, as currently revised in accordance with regulatory provisions. Storage at nuclear reactor sites is' subject to the financial protection and indemnity provision of 10 CPR 140. 1.6.4.4 Authorization to transfer, possess, use and store unirradiated reactor fuel of GE-Wilmington manufacture or procured to GE specification at nuclear reactor c sites, for purposes of inspection, fuel bundle disassembly and assembly, including fuel rod replacement, provided that the' following conditions are met. 1.6.4.4.1 A valid NRC license has been issued to the reactor . lll licensee, which authorizes receipt, possession and i storage of the fuel at the reactor site, and that GE-Wilmington possesses the fuel only within the indemnified locction. 1.6.4.4.2 Not more than one fuel assembly plus unassembled rods so that the total number of rods, including the l assembly, possessed by GE-Wilmington at any one reactor i i site at any one time does not exceed 99 except when the j fuel has been packaged for transport or as described in Section 1.6.4.3. The fuel rods must be of the types described in NRC Certificate of Compliance Number 4986. I 1.6.4.4.3 All operations involving the fuol are conducted by or under the direct supervision of a member of the GE-NRC LICENSE SNM-1097 DATE 8/24/90 PAGE DOCKET # 70-1113 REVISION 1 I-1.12

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Wilmington staff who shall be responsible for all work on the fuel element assembly. The person shall be knowledgeable of and shall have access to all applicable procedures and license conditions at the reactor site and appropriate actions that are to be taken in the event of emercancies at the site. 1.6.4.4.4 All operations involving the fuel are so conducted that neither mechanical damage nor flooding is credible. 1.6.4.4.5 Loose rods are stored in RA-series inner metal containers. 1.6.4.4.6 Fuel is handled in accordance with pertinent provisions of the reactor license and in accordance with written procedures which are jointly approved by GE-Wilmington and the reactor licensee. () 1.6.4.4.7 Records of the operation, including the procedures used, are maintained at the GE-Wilmington facility. 1.6.5 Disposal of Industrial Waste Treatment Products Notwithstanding any requirements for state or local government agency disposal permits, GE-Wilmington is authorized to dispose of industrial waste treatment products without continuing NRC controls provided that either of the two following conditions are met. 1.6.5.1 All free-standing liquid sha'll be removed prior to shipment. The uranium concentration in the material shipped for disposal shall not exceed 30 pCi per gram after all O~ NRC LICENSE SNM-1097 DATE 8/24/90 PAGE DOCKET # 70-1113 REVISION 1 I-1.13

V free-standing liquid has been removed. The licensee shall possess authorization from i. appropriate state officials prior to disposing of the waste material. The authorization shall be available for inspection at the GE-Wilmington facility. 1.6.5.2 The uranium concentration in the material shipped for disposal only at the RCRA hazardous waste burial facility in Pinewood, South Carolina (licensed by the State of South Carolina), shall not exceed 250 pCi per gram of uranium activity, of which no more than 100 pCi per gram shall be soluble. The minimum burial depth shall be at least four feet below the surface. 1.6.6 Dilution Factor for Airborne Effluents I Authorization to utilize a dilution factor to the measured stack discharges for the purpose of evaluating ggg the airborne radioactivity at the closest site boundary of stack discharges from the uranium processing facilities. For purposes of control, this dilution factor shall be no greater than 100. For other purposes, specific dilution factors, which consider dispersion model parameters, may be calculated and used. I 1.6.7 Monitor System Exemption Authorization for ekemption from the criticality _ accident monitoring system requirements of 10 CFR 70.24 for each area in which there is not more than: 1 NRC LICENSE SNM-1097 DATE 8/24/90 PAGE DOCKET # 70-1113 REVISION 1 I-1.14 w

i ~ li 1 + I# A quantity of finished-reactor fuel. rods equal to or j jn less than 45%"of a minimum critical number under n conditions in which double batching'is credible, or J p F equal to or less than 75% of a minimum critical number under conditions in which double batching is not credible, or L The number and type of finished reactor fuel rods and/or assemblies authorized for delivery to a carrier for' transport asia Fissile Class I shipment in the model RA-series shipping ~ package described in NRC Certificate of Compliance Number 4986, without limit on the number of such stored containers, provided the storage locations preclude mechanical damage and flooding, or e The quantity of uranium authorized for delivery to a carrier for transport as a Fissile Class I package (JY

when fully packaged as.for transport according to a valid NRC authorization for such packages without limit on the number of such packages, provided storage locations preclude mechanical' damage and flooding, or Arrays of firished reactor fuel rods and/or assemblies in any of the inner metal containers of 1

the RA-series shipping package described in NRC Certificate of Compliance Number 4986, under storage conditions described in Section 1.6.4.3. 1.6.8 Waste oxidation-Reduction Facility Authorization, pursuant to 10 CFR 20.302(a) and 10 CFR 20.305, to treat or dispose of waste and scrap material i /. r'% l.. NRC LICENSE SNM-1097 DATE 8/24/90 PAGE y DOCKET # 70-1113 REVISION 1 I-1.15 i 1-B.

n containing special nuclear material by oxidation-ll[ reduction. 1.6.9 Posting For those areas within the Controlled Access Area in which radioactive materials are processed, used, or stored, where it is deemed impractical to label individual containers pursuant to 10 CFR 20.203 (f), a sign stating "Every container in this area may contain radioactive material" shall be posted. 1.6.10 Uranium Recovery Enrichment Control Some parts of the uranium recovery process have been analyzed and demonstrated to be safe for a maximum enrichment of up to 5%, while other parts have been analyzed and de Snstrated to be safe for a lower maximum enrichment. maximum enrichment allowed in uranium g recovery at c time shall not exceed the lowest maximum enrichment for which any part of the system has been analyzed and demonstrated to be safe. This will allow processing of higher enrichments when critdcality safety has been demonstrated. 1.6.11 Sanitary Sludge Accumulation Authorization to accumulate treated sanitary sludge containing trace amounts of uranium, in the sanitary sludge land application area pending final disposal. i 1.6.12 Transfer of Calcium Fluoride Test Quantities Authorization to transfer test quantities of calcium NRC LICENSE SNM-1097 DATE 8/24/90 PAGE DOCKET # 70-1113 REVISION 1 1-1.16 i 5 l

fluoride (CaF,) to' potential buyers for the purpose of b( f-their examination and evaluation as described in GE-Wilmington's letter dated March 21, 1988, to the NRC. Test quantities may not contain more than 30 pCi per . gram on a dry weight basis and are limited to 1 gram U'85 at each off-site location. Test activities and end uses of'the material will be limited to those that do not allow chemical separation of the uranium or entry of the product into the food chain. O: e NRC LICENSE SNM '.097 LATE 8/24/90 PAGE DOCKET # 70-1113 REVISION 1 I-1,17

s I O GulMLINES FOR DECONTAMINATION OF FACILIT!!$ AND LOUIPNCNT PRIOR 70 RELEA$t POR UIntilTalCTED U$t OR ftmthAT10N OF LICEN$t$ POR BtPRODUCT. SOURCt. 'OR $PECIAL NUCLEAR MAftRIAL 1 O; U.S. nuclear Regulatory Casmission - Division of Industrial and IIedical iluclear Safety Washington. SC 20566 August 1947 ) NRC LICENSE SNM-1097 DATE 5/22/89 PAGE DOCKET # 70-1113 REVISION O I-1.18'

m, h O' l l':;. r' 15.'21 OUTSIDE PRODUCT CAN STORAGE e 15.21.1-Process Description I West of the fuel manufacturing building are fenced pads utilized for temporary storage of 5-gallon cans of uranium compounds. Each can is separated 12 inches from adjacent cans in a row by physical barriers with 3-foot aisleways between adjacent rows. Only closed containers which are free of surface contamination are stored in these outside storage areas. 15.21.2 Criticality Safety I The criticality nafety of the outside can storage areas has been demonstrated by an analysis performed with the KENO IV Monte Carlo code and using JRK Modified Hansen-Roach 16 group cross section sets. Calculations ( s. were performed for an infinite planar array of ^ \\/ containers with a minimum separation between containers of 12 inches with each container limited to 35 kgs of 4.0% U s: enriched UO,, with optimum moderation by water 7 of the UO,, and with full reflection on the top and bottom of the array by 12 inches of water. The KENO IV result demonstrates compliance with the f multiplication requirements of Section 4.2.2.3. Stored containers'are protected against rearrangement under l.. severe wind conditions. l l l' l l l l- ) NRC LICENSE SNM-1097 DATE 5/22/89 PAGE DOCKET # 70-1113 REVISION O II-15.145 ~

15.22 URANIUM RECOVERY FROM LAGOON SLUDGE FACILITY O 15.22.1 Introduction The purpose of the URLS facility is to recover uranium from the various sludges that have accumulated in storage lagoons, basins and pits from the treatment of the waste streams generated at our fuel manufacturing facility in Wilmington, N.C. These sludges will be removed from their storage locations and processed to remove the uranium. The solid waste generated will be disposed off-site in accordance with the provisions of Section 1.6.5 of the license. 'The liquids generated will be transferred to the lagoons. The resulting uranium will be sent to the existing uranium purification facility for further purification. O Concentration is the criticality control mechanism utilized throughout the URLS facility with the exception of the precipitation system where geometry is the primary control and mass-is the secondary control mechanism. To date, the highest enrichment processed through the conversion plant is 4.025% U-235 which is used as a basis for process evaluation. According to the Criticality Handbook ARH-600, this results it. a-minimum critical concentration value of 360 g U/L for UO, and water. A control limit of 180 g U/L, which is half the minimum critical concentration, forms the basis of all concentration limits. NRC LICENSE SNM-1097 DATE 8/24/90 PAGE DOCKET # 70-1113 REVISION O II-15.146 i l

o { 1 r. L, ' - Process chemicals used in the URLS facility will;be .s ' kf checked for; chemical makeup (e.g. molarity,: purity, { etc.) by the.URLS laboratory. l l L Although this discussion addresses the West Nitrate o i ~ lagoon sludges, the chemical composition of the. sludges from other lagoons, basins and pits are essentially the [. same.; 15.22.2' Facility Description f i -) As shown in Figure 1, the facility is located on the' east side of the existing boiler building at the site's waste treatment area. This single-level structural extension (Figure 2) has a roofed area of'about:2,000 j square feet. The entire poured' concrete area is curbed. j for containment of spills. The building has a- [ self-contained HVAC system, including stack sampling. t h,, The outside tanks for chemical and sludge-storage'are y curbed'or d1ked to contain spills. All major utilities and support services are supplied by the existing waste treatment facility. The generali::ed URLS processing. system is shown in Figure 3 15.22.3 Process Description & Criticality Safety Analysis. -f v - 15.22.3.'1 Dredge and Feed System i 15.22.3.1.1 Process Description L' The purpose of this system is to dredge, settle, and queue sludge for eventual processing. The feed sludge is dredged out of the lagoon and transferred to the 3 Nitrate Settling Tank T-1010 located in a diked area NRC LICENSE SNM-1097 DATE 8/24/90 PAGE DOCKET'# 70-1113 REVISION O II-15.147 -n-

I + 1 e FIGURE 1 LOCATION OF SLUDGES AT THE WILMINGTON SITE l %M ' S ~_ ~~ o i n 1848'Ig I J 9 p li 1 11 d 11 !"j iv i J I [ s:000 i l(I ig It I i i i I I 1l i l l t i I I i I I Itz NRC LICENSE SNM-1097 DATE 8/24/90 PAGE DOCKET # 70-1113 REVISION O II-15.148

PIGUP.E 2 i URLS P ANT PLAN VIEW O ! f' l i I l i 1 li- .niii n n O f 1, ! p t't[ 7 @ k] m ,cr5 <I o ey$.$o< l;g q 1 n ...+, i e c a =a N dih d e' g.h. _w g $$ h $ e h-Ig" Y ,im NRC LICENSE SNM-1097 DATE 8/24/90 PAGE DOCKET # ~10-1113 REVISION O II-15.149

FIGURE 3 GENERALIZED URLS PROCESS FLOW SHEET l Laaoon SitIdges v O '[f~ v Storage m, j s, v n _.' t v T; v Acid rf; ~ Recycle v r First Leachl I th .m t g# Solvent Solvent Filter D ecycle Extraction, mg7-Acid R C l D'n

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( l"jv I 6 D v Y* v f AqYee5 ~~ Y b.ih.- Filtrate r- \\ 4 ou v v 1 l "*'C46 H. J ' Second' 5 v: 3 < Leach. ~ y ; E Filter E l vj y,{' h r< . W,-- 1 r ! affinate Di sa, R gf Treatment j \\- / U Extract x/ o o' Filtrate y T g y 1 9 I Filter (p. la l k ' Solids To Uranium v Precipitation, ugy Disposal Filtrate E@ o O (t - el a TI ILiquidRecycl2; Jj. 7 LToLagoon ) m I Uquid lp\\ (Regle} 1 j $ ran um Froduct' rt i To UPMP NRC LICENSE SNX-1097 DATE 8/24/90 PAGE DOCKET 4 70-1113 REVISION 0 11-15.150

65 ] r nortueast of the Uranium Recovery of Lagoon Sludge j i_) (URLS) facility. Sludge is allowed to settle'in this 1 tank, while supernate is decanted back to the lagoon. From T-1010,. the sludge.is pumped to the Sludge Storage Tank T-2020 or T-2030.. A diagram of this system is 6 shown.in Figure 4. ) 15.22.3.1.2-Concentration Analysis ' Samples taken of lagoon sludge that has settled for 4 . years, indicate that the solids settle to form a sludge normally containing no more than 2n% solids.

However, past studies and analysis of these sludges indicate that j

they can be as high as 30% solids with 8.4% uranium on a dry Weight basis. Assuming this sludge can be i physically transferred at this concentration, a maximum of 30% solids.is used for this evaluation..The density of this sludge is 1.3 g/cc which recults in a maximum ( ). concentration of 33 g U/L. Values based on the expected [ operating conditions would be a sludge density of 1.12 ) and 15% solids. This would result in a uranium-concentration of 14 g U/L. i t 15.22.3.1.3 - Safety Features To ensure that the maximum uranium concentration for this system of 33 g U/L is not exceeded, the following controls have been established. L Use of a closed, dedicated sludge transfer line i restricts the addition of any material to the sludge transfer system. The only material that will be added to this system is lagoon liquid and water during the NRC LICENSE SNM-1097 DATE 8/24/~90 PAGE DOCKET # 70-1113 REVISION O II-15.151 , - ~ -w

FIGURE 4 DREDGE AND FEED SYSTEM 1 I LA0GON $LOOOE N T-t010 rv-; 23 N17E AT[ id E *'. ATE grnt e* i

  • Aw

/^N O ' O C# t.2020 1-2030 CAST atsi / stuDct stvoGt STORAGE STORAGE 2.045 GAL 2,045 GAL. 91 \\ / / \\ N/ g ',! \\ 6 I ~- Q,a.- _se _I 1 Pv-2024 rv-20J4

  • . 3c;o rest.ta:

+Aw il i 1 NRC LIC SE SNX-1097 DATE 8/24/90 PAGE DOCKET # 70-1"13 REVISION O II-15.152 1 l

n .g, p fpi 9 dredging operations,to create la slurry suitable for- ' transfer to T-1010. LThe only plant: system'that is interconnected with this

> i system is the leaching system 4 v.

Backflow into this system and within this; system is . prevented.by introducing all feed streams into the tops of the tanks, above the overflow, to provide an air. break.. In' addition, a-level sensing system monitors the levels in T-1010, T-2020 and T-2030. This system-is-interlocked through the digital control system and automatically terminates feed at a preset level below the overflow. 15.22.3.1.4 Safety: Analysis '{). By virtues of the nature of the material and the controls described above, adequate protection against -precipitation:or other circumstances which may increase concentration _has been provided and the maximum uranium concentrati" 4"able in this system is 33 g U/L. ,d 15.22.3.2 Leaching /_F itracion 15.22.3.2.1 Process v 3r The purpos~ .IL 1 ac;ing process is to remove the uranium from cat .udge. This process is a multi-stage, counter' current acid leach 11g process. Most of the uranium is removed in the f.rst stage leach; the remaining uran.dv is removed in the second stage leach. A diagram of this system is shown in Figure 5. NRC LICENSE SNM-1097 DATE _. 8/24/90 PAGE DOCKET # 70-1113 REVISION 0 II-15.153

{,; ', m s r 1 FIGURE 5' g', LEACH SYSTEM i 'g g g5 1 2 g g 8o f hM d se is <a $a ga fa gv B gae e W mSt 5;g d f. 1 1 ~ = 3 ^ i. .n m g._ 4 Sh 'gd!1 j"Eo N n - - ggry (/ e ws wo WW2 Et: 8 l \\ IiN/ 3 b In y g e1 u e e i g ~ Sy $553 ao r-!giw/g e a sus-nu u h n g rZ fg l i Qt l ! I I l l 9 r 0 -gf_d ^ 5.- / q-d n n e g ~ \\. R M y D$n l 'NRC LICENSE SNM-1097 DATE 8/24/90 PAGE l DOCKET # 70-1113 REVISION 0 II-15.154

' A. !_ i,, ~Sludgeistored in either Sludge Storage Tank T-2020/ .T-2030Lis transferred to the First Stage Leach Tank s T-3020, where it is contacted with the acid filtrate. -from.the second leach' filter. This mixture is continuously l agitated.. Heating the slurry in the first' leach tank is not expected to be required. For future leaching of'other sludges, it may be'necessary to heat-this system by a heat exchanger or direct injection'of' steam to improve the efficiency of removing uranium from the sludge. When the first stage leach cycle is completed, the l 7 ] J slurry is pumped to a plate-and-frame Filter F-4050 for solids-liquid separation. Once filtered, the solids may 1 be washed with liquid from the Filter Wash; Holdup Tank -{ 4 T-2050, which is the final acid wash water from the i l second stage flicer F-4060. If wash water is not j available, a dilute acid is prepared from~ plant water ] 7-1 (_y.). and concentrated acid. The uranium. bearing filtrate.and' wash water are'sent to the Aqueous Receiver Tank T-5010. l ~ and'becomes the~ feed to the solvent extraction process. J The solids are-discharged-from the First Leach Filter-1 F-4050 through a chute, repulped with acidic alum solution from the Aluminum Sulfate Storage Tank-T-7050, in the Repulp Blender BL-4150, then transferred to the j i Solids' Holding Tank T-4020. i H Slurry in the T-4020 tank is pumped to the Second Stage Leach. Tank T-3010 where it is contacted with. fresh acid-m from the Sulfuric Acid Tank T-2010. The slurry is continuously agitated and heated either by a heat exchanger or direct steam injection to enhance the leaching efficiency. Following the second leach, the f~) + '~' NRC LICENSE SNM-1097 DATE 8/24/90 PAGE DOCKET # 70-1113 REVISION 0 II-15.155

o .o. . solids contain very low levelscof uranium.- Uranium. recovery. in excesse of: 99% -is expected. lll ? After completing the;second stage. leaching,' slurry is pumped to a plate-and-frame Filter F-4060 1)r solids-liquid separation. Filtrate is transferred to the Primary Filtrate Tank T-4010 to be used as liquid feed to the first stage leaching process.- The second stage leach cake is washed with' dilute acid from the Filter Wash Makeup Tank T-5220 then air-purged to. reduce excess liquid. The filtrate and air purge are discharged into the Filter Wash Holdup Tank T-2050. The solids from the filter are discharged through a chute and into a waste; box for future disposal. The cake will be analyzed for.p(I, % moisture, and radioactivity. If further removal of uranium =from second stage leach solids is necessary, the cake may be returned to the lll Repulp Blender BL-4150, transferred to the Solids Holding Tank T-4020, and reprocessed in the Second Leach Tank T-3010. 15.22.3.2.2 Concentration' Analysis .The~URLS leaching system contains numerous large volume tanks and two large filter presses. The chemicals and' other materials that.may be added:to this system are 98% sulfuric. acid, alum (aluminum sulfate), water, and calcium hydroxide (Second Stage Filter only). i When sulfuric acid'is added to the sludge, the uranium is solubilized as uranyl sulfate. Any uranium present as the highly soluble uranyl ion is immediately solubilized; otherwise, the uranium must be oxidized to NRC LICENSE SNM-1097 DATE 8/24/90 PAGE DOCKET # 70-1113 REVISION 0 II-15.156

t 'the:plus sixLstate by theLsulfuric acid which is-a [ relatively slow l process. The calcium salts are- { converted to calcium sulfate. Aluminum-is utilized to complex the fluoride-to enhance-the dissolution ~of the calcium fluoride.- The dissolution of the calcium fluoride is necessary because it is assumed that some.of. the uranium is integrated within the crystalline -structure of the calcium fluoride.; This structure must f p be brohen in order to solubilize the. uranium. To evaluate possible worst case uranium concentration 4 values in the leaching system, two worst case scenarios are considered. Based on a-sludge containing 30%. solids and 8.4% uranium by weight, these are: i 1 a) If, because of some failure of,the. process j chemistry, the sludge failed,to' leach in the first stage but was completely leached in the second

([

stage and this filtrate completely' leached the -uranium from the fresh sludge in the first. stage, the result would be a first stage filtrate containing about~37 g U/L. b) If the sludge was not leached in either the first or= second stage then was filtered. The resultant cake from the second leach filter could be.70% solids. This could result in an uranium concentration in this cake of 117 g U/L. 15.22.~3.2.3 Safety Features To provide assurance that the maximum uranium concentrations discussed above are not exceeded, controls have been established to prevent the

?) '

NRC LICENSE SNM-1097 DATE 8/24/90 PAGE 1 DOCKET # 70-1113 REVISION 0 II-15.157

[? l w b ^ inadvertant addition:of precipitation: agents into the-s' . system. ~The-following is.a description of these-llh[ k

controls, ay

.~25.22.3.2.3.1-Valvino Interlocks / controls r Since.the second leach filter has.a dual role-(i.e., it is used to filter the second leach slurry,and the slurry from the lime treatment of raffinate) a pathway exists .} for the addition of calcium hydroxide (a precipitant) to' the leach system. To prevent cross contamination of l calcium hydroxide and uranium bearing solution the following system of valving interlocks / controls has been employed. I Valve Positioning To ensure proper-valve positioning the following has } been provided: lll The feed valve from the Second Leach Tank and the-feed valve from the Raffinate Treatment Slurry Tank are interlocked to prevent ~the simultaneous introduction of these streams to.the filter press. The Second Stage Filter-filtrate valve and the feed valve from the Raffinate Treatment Slurry Tank are interlocked to prevent material from being fed to o the Primary Filtrate Tank when treated raffinate is fed to the Second Stage Filter. 'NRC LICENSE SNM-1097 DATE 8/24/90 PAGE ' DOCKET # 70-1113 REVISION 0 II-15.158

r, : t.- k . Valve' Leak. l -I LA system of double block and bleed valves are installed on the following process lines:in the.

event of a valve-leak:

1 Feed line from Second. Leach Tank to Second Stage Filter. The block valves close and the bleed valve; opens when treated raffinate~is fed to the filter. This system is interlocked to-the feed valve from U the Raffinate Treatment Slurry Tank. Feed line from.Raffinate Treatment Slurry Tank to L Second Stage Filter.- The block valves close and the L bleed valve opens when second leach stage slurry *is: l fed to the filter. This system is interlocked to 'l the feed valve from the Second Leach. Tank. (); Feed line from second Stage. Filter to Primary l-Filtrate. Tank. 'The block valves close and the' bleed valve opens when treated raffinate is fed to the filterothus preventing any:raffinate filtrate from- ] entering the' Primary Filtrate Tank. This system is j ' initiated when the feed valve from the Raffinate' ]e Treatment' Slurry Tank opens-l All of.the above. valving systems are fail safe and automatically interlocked through the digital control; -i system. 15.22.3.2.3.2 Backflow Prevention t To ensure adequate ~ process control, any backflow out of or within the system is prevented by the following ~ rf NRC LICENSE SNM-1097 DATE 8/24/90 PAGE DOCKET # 70-1113 REVISION 0 II-15.159 1

{ 2- ~' E {

methods.

All feed streams are introduced.into the top - ofrthe leaching / filtration system tanks, above'the' Ih overflow to provide an airbreak. In addition, each tank Econtains'a level sensing system devi e which-interlocks through the digital control system, stopping incoming. liquid feed prior to the liquid levels reaching the . overflow height. Since steam injection may be usedLin the leaching process,- a vacuum break has been installed' on the q incoming steam line to. prevent solution addition to the ..n. ] steam system.' This vacuum break, located between the solution and a steam control valve, opens and bleeds ~ atmospheric air into the line if a vacuum develops. In addition, a block and bleed valving system is installed on the main steam line feeding all injection spargers'. 15.22.3.2.4. Safety Analysis g 1 Based on the controls / interlocks described above, d adequate protection against precipitation or other _j circumstances which may. increase concentration has been j provided.and the maximum uranium concentration

{

1 attainable in solution and solid form are 37'g U/L and 117 g U/L respectively. l 15.22.3.3 Solvent Extraction / Scrubbing / Stripping .j

15.22.3.3.1 Process Description The purpose of the solvent extraction system, j

illustrated in Figure 6, is to selectively recover ] uranium from the leach solution. The two immiscible phases,-aqueous and organic, flow ccunter-current NRC LICENSE SNM-1097 DATE 8/24/90 PAGE DOCKET # 70-1113 REVISION O II-15.160 i I

t ' s~; i r,- e, FIGURE 6 '() SOLVENT EXTRACTION SYSTEM i 10 i.5230 = AC10 f t!D. l 1 ,-a-x I T-5210 sem>e I-5040 T-5050 m tup sine scme f(LD fil0 C-5080 T-50 V) [#'W'I'0" mit - '"5"" T-5110 Nur C-5090 e tsIocinon C cavun - -t] \\ /,o m m w C 5100 a O T-5150 C "aveuw ~~ A m Sf

  • e 8

D r."sii3 t ca"uun A ON -LINE ~ m,, =. OENSITY y W5ML o.osto i NC"u ( 1-5170 I- [p sine [_j A):. = contRCL L k/- Wsstl-T-5060 r-Sin a oncmc. e oecac l W IUP .) EGMR g Deuw j -1 g. 1-6070 ~~ ~ a T-6010 - 7J [_ N < -,.u u noi~i n' } }' C-$120 gso2 - - u)utous tuo '"0" '*50 oncm c T-5070 rito d IRLAfuCN' T-5230 onowc 1 mix cotuu" FtID N '/ \\/ '."7."3 <x1 H, I ' i 1 f-6023 !O - pa atent watta l sceue ma, 'M I-MM I M l 5210 i NRC LICENSE SNM-1097 DATE 8/24/90 PAGE DOCKET # 70-1113 REVISION 0 II-15.161 i 'l

t 'throughitwo: pulsed, perforated plate columns. The- . uranium is transferred ~from the aque'ous-phase;.into the- .g organic phase. The' filtrate-from the First Leach Filter.is' received in thd Aqueous Receiver Tank T-5010. The liquid is then s transferred through a polishing = filter F-5015 into the-Aqueous: Feed Tank T-5020. Then it'is pumped through'- another polishing filter F-5023 into Extraction Column C-5090. I i t Organic extractant is.made up in a chemical makeup area outside of the main' process building. The mixture of solvent is transferred to the' Organic Feed Tank T-5070. The barren organic phase is introduced into the bottom section-of:the Extraction Column C-5080, flowing up l through the column and out the top.~ It is then pumped into the lower section of Extraction Column C-5090, and j out tae top of~the column as pregnant (uranium-bearing) ggg. j organic. The aqueous phase is supplied to C-5090'at a midpoint flowing down through the organic phase, exitstat the bottom, and then is: pumped to the top of C-5080. 1This aqueous phase exits the bottom of C-5080 as raffinate. The top section of C-5090 above the feed point-functions i as a scrub section. This scrub solution from the Scrub Peed Tank T-5050 is made up of very dilute. acid., enters the top of the column, contacts-the pregnant organic,. then mixes with the aqueous phase and exits the bottom of the column with the partially extracted feed. NAC LICENSE SNM-1097 DATE 8/24/90 PAGE o p-DOCKET # 70-1113 REVISION 0 II-15.162 4.

The uranium is removed from the pregnant organic phase lh by contact with a stripping solution in Strip Column C-5100. The strip solution is made up in the Strip Makeup Tank T-5030. The organic is pumped into the bottom of the column. It flows up through the strip solution, which is flowing downward, then out the top to e the Organic Receiver Tank T-5060. The strip, containing the uranium, flows out the bottom of the column into the Strip Control Vessel T-5170 through the coalescing filter F-5173, to remove any carry over of organic, then into the Strip Effluent Tanks T-6070 and T-6010. 15.22.3.3.2 Concentration Anal'ysis Following extraction of the uranium from the acidic sulfate leach solutions, the organic is scrubbed with 0.1M dilute sulfuric acid. The scrub combines in Extraction Column C-5090 to form a single aqueous phase llh process stream to extraction column C-5080. The uranium is then stripped from the organic. No known precipitation agents exist in this system. Worst case uranium concentrations will be based on the maximum uranium concentrations achievable in the organic phase, aqueous phase, and sodium carbonate strip. The worst case aqueous phase concentration is the same as the worst case concentration for the leach solutions (i.e., 37 g U/L) The 0.1M dilute sulfuric acid will not back-extract uranium from the organic phase. The organic phase uranium concentration values are dependent on the extraction capabilities of the chemicals used in the system. Detailed concentration O NRC LICENSE SNM-1097 DATE 8/24/90 PAGE DOCKET # 70-1113 REVISION O II-15.163

K ' analyses!have'shown_that the: worst caseuuranium concentration present-in the' organic phase is.less:than lk the 180~g U/L limit. The strip solution uranium concentration is dependent on-the ability of'the strip solution,to extract uranium from the organic phase. Detailed concentration analyses have shown that the worst case uranium' concentration present if the strip solution is less than the 180 g U/L limit. 15.22,3.3.3 Safety Features In order to limit the uranium concentration in the organic'and strip streams-to less than 180 g U/L, the .following controls are in place on the makeup of these streams. Organic - the organic solutions will be analyzed for llh content by two independent methods.using the following procedure. After the organic is prepared the container will-be sampled, sealed, and numbered._ The sample will be analyzed by two-independent methods. If'the analyses provides acceptable results, the container will be tagged indicating acceptance. The results will:be recorded in the lab and control room logs. When needed, the container will be transferred to the organic loading station, the seal broken, and attached to the solvent transfer system. The container number will be recorded in the control room log. Strip - the strip solution will be prepared in the Strip Makeup' Tank T-5030. After mixing, the strip solution will be analyzed for content by a density measurement to NRC LICENSE SNM-1097 DATE 8/24/90 PAGE ' DOCKET # 70-1113 REVISION 0 II-15.164

I t sg-l' e t . ensure' proper preparation. If the strip makeup is' f acceptable, it is transferred.to Strip Feed = Tank T-5040. As a backup, an'inline density monitor, placed~between T-5030 and T-50401will be utilized to prevent the, transfer-ofEhigh density strip solution into the process.. This instrument. operates a block valve if the density is, unacceptable. 15.22.3'.3.4. Safety Analysis i Based.on the chemical makeup controls' established above,' adequate protection against precipitation or other circumstances-which-may increase concentration above 180 g U/L has been provided. 15;22.~3.4 Uranium Precipitation / Filtration f 15.22.3.4.1-Process Description v, The purpose of the uranium precipitation system is'to' produce a uranium product. A-diagram of the system.is shown in Figure 7. .A measured volume of uranium bearing strip solution is transf.arred to the Uranium Precipitation Tank T-6020. I Thi.s solution is acidified-by lowering the pH with acid from the Acid Tank T-6050. Then a preciptation agent . solution from-T-6060 is added to precipitate uranium ~as ~ a diuranate. compound. The uranium' solids are filtered out by the Product. Filter F-6030, washed, air purged, then transfer 12d to 3 or 5-gallon containers. The I L filtrate is collected in Tank T-6040, and sampled for - uranium concentration. If within limits, it is i I l. f). 'J NRC LICENSE SNM-1097 DATE 8/24/90 PAGE O . DOCKET # 70-1113 REVISION O II-15.165 l.

m in, -FIGURE'7 + URANIUM PRECIPITATION' SYSTEM y =, 3 S l-y i 3 l. [ [ ~ l ]- 1 l " j "5j O

  • l

!I f.s I 3g-I i p l l I I- -) L J p 1 h ClX j .5- ~C 1 I 5 .r'- l F =i !;) il 1l! r~ I l L ->r <1 ',i -( ~ w-i a l- = i g,!:'-I 3 i e fE'. ( i-1 m, - 6 i l 1j j a v r <05~ h j 25 y$ ei e 5 i a, 1

NRC' LICENSE SNM-1097 DATE 8/24/90 PAGE DOCKET # 70-1113 REVISION O

II-15.166

[f AN '. ; \\' transferred to the recycle water-tankLT-7070. -If it:is-l above the limit, it will=be' retreated in T-6020. 15. 2 2. 3. 4 '. 2 l. Safety Features & Analysis = 15.22.3.4.2.1 Unload Hood 7 .The Product Filter is 24.5" wide, 37".long, and 6" thick. The dischirge chute is/ pyramid shaped, 11"-long and fabricated ^out of 11 gage SS sheeting.e-At the end' of the chute is a 3" long, 4.5" diameter discharge cylinder. End_ product material is discharged'into a standard 5 gallon' carbon steelican. All of these components are inside of a 11 gage, SS hood. The overall hood dimensions are'38" X 38" X 62". .Using the GEKENO Monte Carlo-Code', it was determined-that the maximum effective neutron multiplication factor- ) for' accident conditions (i.e., fuel region completely-filled with 4.025% enriched UO, at optimum moderation and full waterfreflection) is 0.9442 + 0.0044. This value is in conformance with the 0.97 limit specified in Section 4.2.2.3 of the license. i ,15.22.3.4.2.2 - Precipitation System Tanks \\ All. tanks in. this system, with the exception of T-6090, are 10" Schedule 80 PVC pipe. T-6090 is an 8" Schedule 40 Stainless Steel pipe tank.. The length of the-tanks are different with the longest being 14' 2.5" long. For purposes of unit analysis it was assumed that all tanks were infinite length 10" SCH 80 PVC. The fuel was assumed to be enriched to 4.025% U225 NRC LICENSE SNM-1097 DATE 8/24/90 PAGE DOCKET # 70-1113 REVISION 0 II-15,167

% (ah g; -i ~ "Y W a 1> '+ -i it e> e-M

  • Using1GEKENO, theLhighest K-effective valuefealculated.

f[ with optimum-UO, and H,-O mixtures,--fully reflected by- {lh water, was 0.8472'+ 0.0047. This value is acceptable F runder'theLprovisions in Section 4.2.2.3 of the license.: o 1 .1 ~15. 2 2 ~. '3. 4. 2. 31 Determination of Safe Mass p Cal'culations-have been conducted with 30 kg of UO,_ t gp servint as-the basis to establish this as the mass , limit, g p b GEKENO' calculations were conducted using 30 kg, of UO,. 4 (( in-a spherical shape reflected-by 12" of water. Under optimum moderation conditions the maximum effective neutron multiplicatianufactor attained was 0.8821 + l 0.004. This value.is acceptable for normal conditions j as s-*' .ed in Section 4.2.2.3 of the. license.

l 4

lk 15.22.3.4.2.4-Neutron Interaction Interaction in the precipitation system area has been analyzed by the solid angle technique.' This analysis has shown the-interaction to bel acceptable. -The largest - subtended solid angle found was :2.17 steradians. This value was'for a unit for which 7.7 steradians would have. i been acceptable. '15.22.3.4.2.5 Backflow Prevention Backflow from safe geometry equipment to unsafe geometry equipment is prevented by the combination of airbreaks and level sensing devices. I NRC LICENSE SNM-1097 DATE 8/24/90 PAGE

DOCKET #- 70-1113 REVISION 0

II-15.168

C i. -15.22'.3.4/2;6 Filtrate' Control

y Li All> liquids transferred from the Filtrate. Tank T-6040 to the Recycle Water Tank T-7070 will be analyzed-for uranium concentration.

This' analysis will be performed 1 using two independent methods. The filtrate is continually recirculated to ensure that the sample is representative of the material in the-tank. 15.22.3.5-Raffinate Treatment 15.22.3.5.1 Process Description The purpose of the raffinate treatment system is to process waste liquids generated in the plant for release .3 into existing site waste streams (see Figure 8). The raffinate liquids' discharged from the solvent extraction i process.are collected in Raffinate Holdup. Tanks T-2060 cm() and T-2070. This solution is pumped into the Raffinate Treatment Mix Tank T-4040 at a controlled rate where it is mixed with lime slurry to control the pH and to precipitate impurities so that it will be compatible with the plants waste stream.- The slurry formed in the treatmer.t tank overflows into the Raffinate Treatment Holdup Tank T-4030. When this tank is full, the slurry *is filtered by the Second Leach Filter F-4060. The filtrate is collected in T-2080, then discharged to the lagoon through the Discharge Monitor Tank T-7040. The cake is discharged into a waste box, sampled for uranium and activity, and staged for disposal off-site. A ~ NRC LICENSE SNM-1097 DATE 8/24/90 PAGE DOCKET # 70-1113 REVISION O II-15.169

FIGURE 8 h: WASTE TREATMENT SYSTEM I I I, li gi 11 d I i 11-p lar xi -xl it

! il al\\

i eg L7 r A w 11 -l / i M [ ~ "li g gl I a 2 I g: Ai x[! I i .x1 a\\ !}, = ,1!! I \\- E r !!l1 )bH . % __ ! ) s ii' i Q 1a1 5 lji! ~ I~ - 7, i gil e it 1 1 1 1n ' lia I i.l lll i

5 a

'i$ l:: NRC LICENSE SNM-1097 DATE 8/24/90 PAGE DOCKET # 70-1113 REVISION 0 II-15.170 i

O E.o 'U \\ .h t t ?' '15.'22;3.5 2i conceritration Analysis )L / ~ Analyses have been'conductedito-developLa< scenario in: whichLthe. uranium concentration would' exceed: 180 g U/L.. It/was concluded 1that this concentration-could be ' attained >only if the feed to'the raffinate. treatment contained a: concentration of 61 g U/L.' Normal ~ uranium ' content'in the raffinate leaving-the SX system is L expected to be less than~100 PPM. =The. maximum. credible concentration in the raffinate stream would be the same. as that of-the incoming aqueous feed to'the SX system ~ '(37 gfU/L). -i ~15.22.3.5.3-Safety Features To provide adequate assurance thst the above concentration-is not attained the following controls are' provided-on the raffinate feed stream: <~\\ Q./

  • The raffinate leaving the solvent. extraction system is continuously monitored for uranium.

If preset limits n. are exceeded, the stream is' diverted back to the.SX j feed-receiver, l

  • The raffinate col 10cted in Raf finate Holdup : Tanks

] T-2060 and~T-20'd is sampled and analyzed'for uranium } content prior to being released for lime treatment'. Recirculati'on is provided to assure sample representativeness, i i i As previously discussed in the leaching / filtration portion of this analysis, the lime based slurry that:is passed through the second leach filter is prevented from 7 entering other parts of the process by a series of I l (~'i I ~ \\~' - NRC LICENSE SNM-1097 DATE 8/24/90 PAGE p DOCKET # 70-1113 REVISION 0 II-15.171 L Ll. J m

a i (, n t I' valving interlocks; controlled by -the dig 1Eal control. h; system.- 6 Backflow within-this system and out of this system is prevented bycthe combination'of airbreaks and level sensing; devices.- i 15. 2 2. 3. 5 ~. 4 - Safety Analyses-

t.;

Based on the controls establishedLabove, adequate ~j e protection against precipitation or oth'er circumstances' which may increase concentration above that presented in Section 15,22.3.5.2 has been provided. [ 15.22.4 Radiological Safety i The facility will be operated according:tosthe radiological control program requirements which exists- 'jl[, for the' current fuel manufacturing building. This ' includes-exposure-controls, personnel monitoring-techniques, bioassay programs, area posting and radiation surveys. i Process areaslof the-facility are, designated as airborne controlled areas-similar toLthe controlled process areas lof the existing fuel manufacturing building.

Radiation workers will access the controlled areas through a designated changeroom(s), where they will don standard controlled area protective clothing i.e.,

f coveralls, head covering, shoe covers or controlled area-shoes, rubber gloves). Persons exiting the controlled area will monitor for contamination following removal of protective clothir.g. L NRC LICENSE SNM-1097 DATE 8/24/90 PAGE DOCKET # 70-1113 REVISION O II-15.172

3z

i q-

?,q. Lq n.-' The-facility-processes have been designed to offer , kf complete' containment to the work' areas, thus minimizing ( the potential-for' surface and airborne contamination. Process tanks are vented to a scrubber exhaust' system. This exhaust' system is water scrubbed then filtered i throughlHEPA filters before discharge to the atmosphere. ? All. process areas are curbed to contain any spills or-l'aks. The curbed areas have collecting sumps-and' e automatic pumping systems to return the' spills-to the ~ ll proper' vessel. The recovered-uranium-bearing product is i ei transferred out-of the process areas in closed three and/or five-gallon. pails which'are not opened outside of i approved hoods. p The existing fuel manufacturing building contamination control plan and: action guides will be'used for the l facility. If contamination in. excess of the guideline. ] -73~ limits occurs, the necessary' decontamination action is (.-) l taken per existing procedures, based upon knowledge,of: j the:particular circumstances and the behavior of the l[ material involved. ~i The' operation-of the~ facility will be conducted. accoretng to wrftten instructions prepared'by process > engineers with inputs from nuclear safety engineering i e I personnel. These documents provide on-the-floor. w instructions to operations personnel and contain criticality and radiological safety provisions. Each j jl equipment operator is provided adequate training to follow these operating documents. -l q b ?\\[ NRC LICENSE SNM-1097 DATE 8/24/90 PAGE 1 DOCKET # 70-1113 REVISION 0 II-15.173 9 d i a.

~ i c 2 15.2215- 'Pfant safetyi 91 115.22.5.1 Fire Protection The fire protection provided meets or exceeds'the plant crequirements and the recommendation of_the Factory Mutual Insurers. The organic liquid in the solvent extraction' system has-a flash point > 160*F which is. classified by NFPA as~a, j combustible liquid Class III A,-liquids with a_ flash point > 140*F and <.200'F. Fire safety devices--designed into the system include: smoke detectors in the exhaust system e i

  • l Sprinkler system in the organic liquidc processing areas.

h'. Secondary liquid containment with a fusible link fire safe valve on the organic makeup lines. J Strategically located fire extinguishers designed for -specific fire. control utilization'.-. i Sprinkler system incorporates an automatic shutdown i system for all pumps in the organic processing area. 15.22.5.2 Chemical Safety Personnel working in the process area containing hot ~ -acid are required to wear full face shields in addition to the standard protective clothing required for the controlled area. NRC LICENSE SNM-1097 DATE 8/24/90 PAGE i DOCKET # 70-1113 REVISION 0 II-15.174 t i l

7 c (

  • IU Process vessels-are vented to a central 1 system 1which

) maintains'a slight negative pressure in the tanks. s r L ~ Any' spills or overflows are contained within a curbed oro -diked area. l15.22.5.3 Process Control The facility is controlled from a' central. control system a located in the URLS building. The control system - I controls and monitors the uranium recovery operation. An operator in the control-room is responsible for monitoring and controlling the process in addition to the operators on the floor. Instrumentation is installed, operated, and maintained according to plant standards and requirements. All 3 critical systems fail safe ifLthere is an electrical or j ,,'l plant air. failure. s e. 15.22.6 Environmental All effluents, whether gaseous, liquid or solids,-are monitored to ensure release-criteria are met. 'The-release of radiological and non-radiological particulates, aerosols, fumes, and vapors is controlled i to as low a level as reasonably achievable by filtration through high efficiency filters and by scrubbing the air j through a packed air-water scrubbing system. Liquids-are returned to the lagoons. Solids are analyzed and if-within discharge limits, are released for off-site _e The uranium product is recycled to the 1 disposal. 't existing fuel processing facility. l i g ~ 'NRC LICENSE SNM-1097 DATE 8/24/90 PAGE DOCKET # 70-1113 REVISION 0 II-15.175 i

a. The-process areas.are mainta'ined at a' negative pressure with' respect to atmosphere and adjacent areas. 'All gg exhaust air from the facility will be1 discharged through- ^ a single exhaust-stack. Effluent constituents of. concern will be continuously sampled; or monitored tus-described in the current facility license information. Favorable environmental impacts are expected from these-activities by.the elimination of uranium inventory from fluoride'and nitrate waste treatment lagoons. An: anticipated longer range benefit of;the process, if' successful, will be the uranium recovery and decommissioning of all uranium-bearing lagoons cn1 site. . 4 0 t NRC LICENSE SNM-1097 DATE 8/24/90 PAGE DOCKET # 70-1113 REVISION 0 II-15.176}}

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