ML19273B309

Requests Amend to License SNM-1107 to Authorize Operations W/Special Nuclear Matl in Expansion of Facility.W/Check for $34,600 Fee

ML19273B309
Person / Time
Site:	Westinghouse
Issue date:	03/07/1979
From:	Dipiazza R WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:	Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
WRD-LS&S-683, NUDOCS 7904060114
Download: ML19273B309 (39)

Text

{{#Wiki_filter:' Westinghouse Water Reactor Pa 3* Electric Corporatlan Olvisions P'"* *""" *

• 3U March 7, 19 PJ WRD-LS & S-6 3 3 U.

S. Nuclear Regulatory Commission Office of Nuclear Material Safety & Safeguards Division of Fuel Cycle & Material Safety Washington, D. C. 20555 Attention: Mr. L. C. Rouse, Chief Fuel Processing & Fabrication Branch Gentlemen:

Subject:

Application for Amendment to Expanc Facility, License SNM-1107, Docket 70-1151_ The Westinghouse Electric Corporation hereby requests an amendment to License SNM-1107 to authorize operations with special nuclear material in the expansion to our Columbia Facility, in accordanca with the attached application. The proprietary portio:t of this application is ' ing transmitted under separate correspondence in accordance w.4 e provisions of 10 CFR 2.790. Please find enclosed a check payable to the U. S. Nuclear Regulatory Commission in the amount of $34,600 in accordance with 10CFR170.31. If you have any questions regarding this natter, please write to me at the above address or telephone me on 412-373-4652. Very truly yours, - [- ,nj [ / t tonald P. DiPiazza, b.ager NES License Administration slw/ Attachment 7 9 04 06 0 {\\'h,

s I, ATrtcILE7r 1 00LILEIA PUNT EXPANSION This e>:pansion consists of the construction of an approximately 100,000 square feet addition to the present manufacturing building. 75,000 square feet of the new areais allocated for factory space, 5,000 square feet for tr'ick docks and 20,000 square feet for nezzanines. This addition is adequate to house new pro-duct inprovanent. equiprent, a chenical process facility, equipmnt to increase production and increased in-process inventory. Also included for use in this area are a second ixineration system for recovery of uraniun fran waste materials and a systan for uraniun recover" fran scrap by solvent extraction. The building expansion will be effected by the extension of the present manu-facturing space in the north and west directions, Figure 1.3.2.1. The exterior walls will be prefabricated, prestressed concrete, tee panels which are consistent with the stringent specifications of the present building. Approximately 75,000 of the 100,000 square feet space will be used for new or expanded chenical and mechanical areas. The remaining space will be utilized for in-plant offices and service areas. 'Ihree basic new itens will be operat.ed in the expanded chemical manufacturing a Each is listed beloa with a brief description of the operation and/or area. equipmnt. (1) Solvent Extraction The solvent extraction equipmnt includes a dissolver system similar to the units now used in the present scrap recovery operation, preparatory equipent, feed and adjustnent tanks, and extraction column ard a stripping colu'n, storage and blending tanks, sitdge concentration and collection system and necessary piping, ventilation, instrumntation, and operation platform. (2) Chanical Process.Developmnt Facility The basic equiprnt for the developmnt lab will provide an environment for

experimental work. A walk-in ventilated hood, snull funn hood and dust collectors will be used for dust and fume control. A. tube calciner and sintering furnace units will be used to simulate the present production units for develognant purposes. Material haMling, scales, etc. are ex-anples of support equignant to Le utilized in the lab. Special equignant for specific develognant projects will be provided as needed. (3) Incinerator System The secord incinerator system will be installed in the new building addition. The systcm will consist of an incinerator, quench tower, absorber tm.er, heat exchanger, stup tank, condenser, reheater, oil tank, filter house and notor control center. Tne expansion area will be covered by the plant criticality alarm system and all personnel working in this area will be covered by the licensee's bioassay program as describcd in Section 3.2.3 of the present license. ? e

= ATTIOrENT 2 PI1FP EyPANSION VS W ENVIFORINTAL LVAUJATIGI, 3NCI 1975 The proposed operations in the plant expansion have been cxrapared with the March 1975 W Environmental Evaluation. In general, all parancters are within the limits based upon a throughput of 1600 nutric tons of uraniun per year as discussed in the report. The following table lists the Enviromental Evaluation cminit:mnts and the corresponding plant expansion parameter: ENVIROCOETTAL LVAUATIGJ CCt@lITbETT FIR 7T EXPANSION PARNMR 1. The developed area occupies less 1. The plant expansion consists of an 2 than 5% of the total site area of area-pf approx.100,000 ft. The 1158 acres (i.e. 1158 x.05 = total disturbed area (including the 57.9 acres) existing building, plant expansion, lagoons, waste treatnent, parking lot, etc.) is less than 50 acres. 2 2. A 50,000 ft building is described 2. The total area of the plant expansion 2 to accmodate fabrication of mac-is of apprcx.100,000 ft and will 2 hined caponents plus a 50,000 ft accmodate additional operations to expansion of the contamination increase capacity. controlled area. 3. The plant additions will increase 3. The capacity is expected to be less production to 1600 MrU/ year. than 1200 MrU/ year. 4. The building is of modern design, 4. The plant expansion is architecturally architecturally expressed by its similar to the existing building. long simple lines of rectangular interconnecting areas, and designcd to cmplement its rural flat sur-roundings. 5. The total gaseous discharge rate to 5. The total expected gaseous discharge 3 enviroment is less than 160,000 rate will be less than 160,000 ft / min. thg/ min. ft 6. Gaseous effluent discharge rates 6. The average weekly gaseous effluent were estimated at 26.94 alpha discharge rate for 1978 was less than uCi/ week (400 MrU/yr.) and 71.94 50 alpha uCi/ week. This is well within alpha uCi/ week (1600 MrU/yr. the environmntal estimate. The plant expansion contribution is expected to be mimmal. 7. Gaseous effluent exhaust stacks 7. All effluents will be discharged throuch are described. existing stacks except for the new in-cinerator which will exhaust through a separate stack. Activity effluents frce the incinerator are expected to be less than the present incinerator.

i EVIINEITTAL LVALUATIO1 CO@ll'IMEt7f PIR7P EXPA!EIOJ PAPNETER 8. Exhaust effluents will be natn-8. Average stack effluents for 1978 were tained belm MPC. well within MPC. Exhaust concentrat-ions for the plant expansion ventila-tion will also be well belm MFC. 9. Liquid waste stream concentrations 9. Mditional liquid wastes will include nust be less than 3 x 10-5 alpha solvent extraction tank system scrubber uCi/ml before leaving the plant. water and iicinerator scrubber water. No significant increases over present operations are expected. All liquid effluents will be directed into existing i P ping.

10. Solid wastes are either treated to

10. Burial disposal of cmbustible waste recover uraniun or buried at an hTC will be reduced with the additional licensed burial ground. Approxi-incinerator capacity. The total antely 40-60 bales / day of cmbusti-quantity of non-cambustible contaminated ble waste and 4 bales / day of non-ccm-waste is expected to decrease because bustible contaminated waste will be of increased scrap recovery capabilities.

generated.

11. Exposure pathways include uranium

11. No new pathrays are expected.

release via air and water.

12. Population dose ccrmitI:ents are

12. Both scrap and waste shiptents should calculated for transportation of be reduced vhlen the plant expansion uraniun bearing nuterials, in-becans operable.

cluding scrap and waste. 1

i ATTA0 DENT 3 LIQUID h%STE DISPOSAL PFOPOSAL The following plan describes a proposed method for recovering uranium contained in a CaF matrix in on-site waste lagoons. The concept includes ranoval of sludge 2 frcm the lagoons, transfer to a mixing tank to solubilize the uranium, " naturalize" the material by addition of depleted uranium ard appropriately sample the material to verify that a natural uranium equivalency has been achieved. This material will then be used as feed to an operation which extracts uranium from natural phosphate deposits. This operation will recover essentially all of the uranium and fluorides as salable products and dispose of the calcium as gypsuin (CaSo ). 4 Liquid waste treatnunt operations at Columbia have generated approximately 2.5 matrix. Table I million gallons of sludge containing uranium in a CaF2 presents the physical and chemical properties of the CaF. This material will 2 be transferred from the lagoons to a tank where it will be heated and mixed with sulfuric acid and diatanatious carth to solubilize tha uranium. Depleted uranium in an aqueous form will be added to the slurry in sufficient quantities to " naturalize" it to a maximum 0.71% U-235 enrichment, adjusted downward to account for the sampling error. Once the naturalization step has been confirned, the natural mixture will be transferrcd to storage tanks. Frcm these tanks, it will be transferred to tank trucks (ncminal 4000 gallon capacity) and shipped to Lakeland, Florida where the material will be introduced into the uranium recovery operation at a rate of approximately 4000 gallons per day. At this point, the material will becane an integral part of the uranium recovery unit process. Key elcments of the operation include: assuring a hcmogenous slurry in the lagoons radiological controls and surveillance dur ng lagoon and tank transfers to minimize contam.ination

sampling and analyses of the naturalize 3 slurry to assure uniform con-centration and thus uniform enrichment control of each shi runt batch to a nnximum U-235 quantity t minimize seInration of solids fran liquids verify naturalization of the mixture selection of a transportation mode to safely transIrrt the material Enviromentally, the proposal is very attractive when capared with the alter-native of disposal of the sludge in an NRC licensed burial ground. First, the bulk of the uranium will be recovered for reuse in the light water fuel cycle. Second, the fltorides will be recovered as fluorosisilic acid. The only waste product will be gypsum which is a nornal waste fran the phosphate mining operations. Approxinutely 1,000 tank truck shipmnts are required to renove the existing inventory. If the program is successful, routine shipnents will be nude to proccas the 550,000 gallons per year of sludge which is generated annually. Based upon measured external radiation levels fran the sludge, tir Iopulation dose ominitnent is expected to be minimal. A test program is planned to determine whether the uranium in the sludge can be converted to the soluble form and whether this material is chenically con-sistent with the phosphate plant's systen. The folloaing licensing actions are requested: 1. Westinghouse is currently licensed to perform waste processing, incitling acid treatment and dissolution, within existing facilities. We intend to perform the sludge preparation in specially designed equiprnt located near the waste lagoons. Details of this installation will be supplied at a later date.

2. Approval is requestcd for the downgrading of the existing sludge fran the present enriclrent (approx 1nntely 2.71%) to natural. Muumum criteria for the downgrading is requested, including a definition of natural uranium and nnximum acceptable sampling error. A detailed sampling plan will be supplied at a later date. 3. Approval is requested to remve this material fran hT jurisdiction and transfer to the State of South Carolina jurisdiction. Subsequent approvals for material transfers, transport and recovery will then be pursued at the appropriate state levels. f

TABLE I PIlYSICAL AND CIDIICAL PPOPL:ICIES OF CaF2 6 1. 2.5 X 10 gallons by end of 1978 2. 3.05 :: 106 gallons by end of 1979 3. 550,000 gallons per year ( 1500 gallons / day at 800 MIU/yr.) 4. Properties LLI h. W S ph 12.5 10.1 % Solids 38.6 35.5 % Water 61.4 64.5 U, ppn 286 152 U Enrich, % 2.71 Soluble F, ppn 33 27 5. Major Impurities (Wt. %) Al 0.7 0.3 Si 2.0 0.6 Fe 0.3 0.3 M3 1.0 1.0 Ti 0.03 0.03 Ni 0.02 0.01 Mn 0.01 0.01 Cu 0.003 0.001

i SNM-1107 REVISION RECORD ( .bvision Date of A - tJ o. Revision Pages Revised Revision Reason / 4 12-30-77 223, 224, 225 Revised criteria to agree with 0.3 fraction critical. (,, 4 12-30-77 226 Data deleted. 4 12-30-77 230.1 Page added. 4 12-30-77 233 0.3 fraction critical was 0.4. (' 4 12-30-77 234 Clarified requirements for indepen-dent review of data. 4 12-30-77 254 Clarified retention of rec rds of o component approvals. 5 2-6-78 208 Revised to read "open face and labor-atory-type hoods." 5 2-6-78 208.1, 209 Deleted airborne concentration option. 5 2-6-78 228 Revised to qualify concrete reflection and calculation assumptions. .y 6 3-3-78 22 Expanded description of systems provided with emergency power. 6 3-3-78 24 Specified that waste processing is conducted in the Contamination Con-trolled Area. 6 3-3-78 100 Specified that liquid waste evaluation is conducted in the Contamination Controlled Area. 6 3-3-78 210 Inserted word " automatically." ~ 235 7 3-28-78 204 0 increased to 50,000 kilograms ~ 7 3-28-78 263.1 Revised to update bioassay frequency data. 7 3-28-78 263.2 Revised In-vivo action levels. 7 3-28-78 263.3 New table on urinalysis action levels. 7 3-28-78 263.4, 263.5 Pages renumbered 8 3-5-79 18 Revised Figure 1.3.2.1 8 '3-5-79 20 Revised to include side entrance to facility I 8 '3-5 79 21' Revised to include side entrance to facility Docket 70- 1151Dufe: 8-28-74 Revision No. '8 Dole: ' 3-5 79' Page 6 C

5 SNM-1107 REVISION RECORD Revision Date of NO. Revision Pages Revised Revision Reason 8 3-5-79 76 Revised to include solvent extraction to scrap treatment and to delete the last sentence of the third paragragh. 8 3-5-79 77 Revised Figure 1.9.0.1 to reflect plant expansion. 8 3-5-79 122 Delete "1.9.4 Reserved" from middle of page. 8 3-5-79 122a-p Incorporate new section entitled "Purifi ' tion of Contaminated Scrap Through Solvent Extraction" 8 3-5-79 145-145f Incorporate new section entitled " Chemical-Manufacturing Developnent Laboratory" 8 3-5-79 151 Revised to include solvent extraction to scrap treatment and to delete the last sentence of the third paragraph. 8 3-5-79 153 Delete " Proprietary Information" at top of page. 8 3-5-79 158 Delete the words "the material" on third and fourth lines and replace with "and purify the materials if needed." 8 3-5-79 160 Add the words "or UO " to "U3 8" 0 betweentheblocksl$beled" Thermal Processing" and Packaging and Storage". 8 3-5-79 164 Modify section 1.9.4.5 to read "Various solid materials which are uncontaminated may be introduced into a thermal processing step direc-tly to convert them into desired uranium oxide form." 8 3-5-79 194 Delete section 1.10 entitled "Off-Site Release Evaluation" 8 3-5-79 194a-k Add new section entitled " Auxiliary Incineration System." 8 3-5-79 194g Reprint section 1.10 entitled "Off-Site Release Evaluations" previously printed on page 194. 8 3-5-79 206 Modify the first sentence in subpara-graph 2.2.1 to read "Four emergency standby generators with rated capacity of 250 kw, 300 kw, and 2 at 500 kw will be maintained. 8 3-5-79 1941-p Add new section entitled " Chemical Man-ufacturing Development Laboratory". 8 3-5-79 1940 Add new section entitled " Purification of Cont,aminated Scrap through Solvent Extrc Docket 70-ll5 more: 8-24-74 Revision No. Ytion.Dofe: 3-5-79 Page 7

Sit:4-1107 ELECTRIC SUB-STATIO:t CALCIU;1 FLUORIDE g LAG 001 #3 (PROPOSED) TAf1K FARi1 CALCIUt1 FLUORIDE CALCIU1 FLUORIDE LAG 00:1 #2 LAG 00ii *1 UATER TANK (STORAGE r' PUMP HOUSE STORi! RU:!OFF TO d lisl UPPER SU:! SET LAKE UF6 STORAGE PAD SHIPPIi!G C0'tTAIiER SAfilTARY LAG 00:1 b\\ STORAGE FREA X -9 f \\ \\ OIL HOUSE " BUTLER" BUILDIfiG y l ]\\L 2 fl0RTH & SOUTl! ---DITCH PROCESS WASTE e LAGOONS l' - f %,J ~ u \\ \\ FRAf4E HOUSE

]

i q l f w -v \\ XPAflSIO;l r EAST LAGOON C00LIiiGk EQUIPl4ENT SHED WASTE TREATriEllT BUILDIf1 og SCRAP STORAGE o AREA / / PLANT 1 C j - /,, BOILER HOUSE 6 C0llTRACTOR CHANGE CAFE - v P,00:4 0FFICE O ADVANCED: WASTE TREATf4ENT BUILDING (PROPOSED) VISITOR PARKIfiG PARKIftG HF STORAGE TANK U:lH STORAGE TA!!KS N [ DITCH . t 0 150 300 450 600 HHHHH SCALE OF FEET COLUliBIA SITE BUILDING LOCATI0ils FIGURE 1.3.2.1 Docket 70-1151 Date: 8-24-74 Revision No.1 Dofe: 2-6-79 Page

SNM-1107 i 1.3.4 (continued) Access to the facility during normal working shifts is granted to: (1) Certain NPD employes and certain other Westinghouse employes assigned to the Columbia Site, through the front main entrance upon or second 8 side entrance upon display of their identification badges to the security force on duty. (2) Other NPD employes to the NFD offices directly, upon display of their identification badges to the security force on duty at the front entrance or second side entrance of the facility. 8 (3) Other Westinghouse employes assigned to the Colunbia Site through the front entrance to the facility. Such visitors must sign a visitor's register and be issued a visitor's badge by the a person on duty. (4) Other visitors by registering at the appropriate NPD reception desk. All visitors must be issued a visitor's badge and all non-Westinghouse visitors are escorted. (5) Vehicles (as far as the shipping-receiving docks) through electrically-operated gates controlled by the security force. 20 Docket 70-1151 Defe: 8/28/74 Revision No. 8 Dofe 3-5-79 Page

SNM-1107 ( l.3.4 (continued) During off-shifts, the entrances are locked and the facility is regularly patrolled at intervals not exceeding .( four hours by a member of the site security force. All access during these shifts is through the front entrance or second side entrance to-the facility and is co.ntrolled by a member 8 of the site security force who is stationed there at all such times. A security service report is initiated on a shift basis by the security guard and is kept on file by the Manager, Security and Services. Keys for the locked doors controlling access to the Columbia facility are issued to the NFD Manufacturing / Columbia Plant Manager and to the Manager, Security and Services. The site security force is issued keys for locked doors controlling access to the NFD Manufacturing building. The Facilities Engineering Manager and the Maintenance Supervisors are issued keys to the factory area of the facility. Additional security measures as specified in Amendment SG-4, as amended, are implemented when mixed oxide fuel is possessed on-site. 1.3.5 Utilities and Services The Columbia Site is served by a single electrical supply line. Four diesel-powered standby 8 generators are installed to meet the emergency electrical k power requirements of the site in the event of a temporary 21 Dockel 70-1151 Dafo: 8/28/74 Revision No. 8. DatS{ 3-5-79 Poco

i SNM-1107 ( l.9 Processing operations, The processing operations to be performed on radioactive materials f under this license may be divided into a number of distinct categories. The first category is the ADU conversion operations .which employ chemical means to convert UF to uranium oxide-6 powder. The second category, then, is the fabrication operations which use essentially mechanical processes to produce fuel assemblies containing encapsulated UO2 pellets. Another category is the analytical operations which use a variety of spectrographic and wet chemical operations on small samples of material to assure that material specifications are met. Still another category is the treatment of scrap generated on site to permit it to be recycled into production operations or more closely controlled prior to discarding. This treatment in:1udes chemical dissolution and precipitation, solvent extraction and dry processes. 8 Westinghouse also has developed and is currently operating an alter nate process for converting UF to uranium oxide. This is the Direct

• 6 Conversion Fluidized Bed (DCFB) process which may contribute to reduced chemical effluent levels.

Q)- i %; Dockel 70-1151 Date: 8/28/74 Pevision No. 8 Oct' n 3-5-79 Poco _151 o

i SNM-1107 g f-1.9.1.2 UF to UO Conversion 6 2 The chemical operations required to convert UF to uranium oxide are carried out in a con-6 tinuous processing line which is a closed r system. Engineered safeguards are applied to particular operations as required to prevent, or to detect and control, abnormal conditions. Low enriched uranium in a closed system requires only routine radiation protection precautions. The engineered safeguards specified above will effectively minimize the possibility of a significant material release. Individual items of processing equipment are designed ( within the MPV for diameter, slab thickness, mass or

• volume.

For subcrits that are, or could credibly become moderated, the equipment spacing is established using surface density or solid angle criteria. The system would remain subcritical for the maximum 235U enrichment authorized for Model 30A or 30B cylinders. Powder 1.9.1.3 Storage of Uo2 The dry uranium oxide powder is stored in a closed system until it is released by Quality Control for .use in the fabricating areas or for shipment in licensed packages to other facilities. Low enriched uranium in a closed system or sealed k-packages requires only routine radiation protection 5-79 Revision No. Dofe: . Pope 153 Docket 70-ll51 Dde 8/28/74

SNM-1107 ( l.9.4 Scrap Recovery Operations 1.9.4.1 General Scrap recovery process operations are characterized as batch operations involving a variety of input and purify 3 forms. The preliminary operations concentrate the materials if needed and convert it to forms readily pro-cessed into U 0 3 8 sing through the entire sequence of operations. The basic processing sequence includes dissolution of solid forms, conversion to slurry form by precipitating ADU from the solution, dewatering the slurry form by wet mechanical separation, calcining the resulting sludge in furnaces, and packaging and storing the resulting product. The product is sampled and analyzed before release to manufacturing. Various other inputs are fed into the basic sequence at appropriate points. Liquids containing disolved uranium are introduced into the solution hold tanks used to supply the precipitator columns. Clean ( aqueous suspensions from mopping or off-gas scrubbing operations and from laundering cloth filters, poly bags, etc. are introduced prior to the wet mechanical separation operation. Clean powder scrap, scrapped pellets and other quality solids may be subjected to a dry mechanical separation step and then are introduced, along with the vet sludge, to the calcining operation. Thermal processing capabilities also exist to convert this clean scrap material directly into usable UO2 Powder. 158 Revision No.8 Dofet 3-5-79 Pooe Dockel 70-1151 Defe 8/28/74

SNM-1107 CA*; '7,O n" P14Ci3:, J NPUT MATr.RT AT. Ar f [ 2,. Equipment Cican-out A LicL mtion 2. Ul;!! Cryntalu To /WU __p U:UI :olution Lines (Optional) g Chenical 3. Convernion /1rea C1can-out Precipitation B Solution ADU Slurry Cartridge Piltero g 6 a. 11a ching UO 5. Filter Prcnc Cloths Operations 4 C 6. Polybags ..g 7. Dunt Collector liar s Uct 8. Mop Water Mechanical D 9. Scrubber Clean-out-Separations ADU, UO2 U@g udge ). Conversion Area s Solid Clean-out ADb, UO. hu 2 E UO 3g Processing 0 s 11. Pellet'Arca UO, U3 3 2 ~ 12. Floor Sucepingo Dry F Mechanical 13. Absolute Filters separationn U0 38 ( or UO 8 2 \\.4. Tank Vento + Misc. C Operations

15. Waste Solutiono v

k' To Waste y y Packaging & H Storage iY SCRAP RECOVERY SROCESSCOPERATIONS' FLOW SHEET Figure 1.9 A.3 Dockel 70-1151 Dafo: 8 /2B /74 Revision No. 8 Dofe:- 3-5-74 Pone 1 160,

SNM-1107 1.9.4.5 (continued) Various solid materials which are uncontaminated may< be introduced into a thermal processing step directly to convert them into the desired uranium oxide form. 1.9.4.6 Dry Mechanical Separation (Category F) Non-homogeneous uranium oxides are crushed to a powder in a mechanical, granulator prior to the dissolution operation to promote the speed of the reaction. Contaminated UO2 and U 038 such as that found in floor sweepings is screened in a vibratory separator to remove trash and gross impurities. In addition, accumulations of chemically uncontaminated UO rU03 8 such as those occurring on absolute filters 2 in the Controlled Area are removed for further process-ing by manual techniques such as shaking, scraping, etc. Dry materials charging, dry meci inical separation, pellet and powder ~ granulation, and final packaging are performed in hoods, hopper dryboxes, or similar enclosures equipped with individunl blowers and IIEPA filters to minimize airborne contamination levels. The filtered air from the enclosures is exhausted back into ( the Controlled Area. Continuous air sampling heads are strategically located throughout the scrap recovery area to obtain representative samples of " breathing ( zone" air. DOP tests and face velocity measurements 164 Docket 70-1151 Dafo: 8/28/74 Revision No. Defe: 3-5-79 Pope

SNM-1107 1.9.6.8 (continued) indicated by the differential pressure monitoring device on the incinerator control panel. It will also be indicated by the analyses of the stack samples. If this occurs, immediate shut down of the incinerator will be initiated manually so that appropriate corrective action can be taken. As enumerated above, sufficient means are provided for immediate detection and correction of problems that could occur in the incinerator system. For this reason, adverse in-plant and offsite effects due to system f ailures are not considered likely. 8 ~ A~'A Revision No. 8 Date: Page 194 3~5~79 Docket ~ Dole:

SNM-1107 1.9.7 Auxiliary Incineration System 1.9.7.1 "urpose of Incineration Combustible waste may be treated by incineration to reduce the volume of waste disposed to licensed burial grounds and to permit the recovery of SNM when practical. 1.9.7.2 Typical Materials to be Incinerated Typical materials are paper, plastic shoe covers, gloves, mops, plastic bags, tape, fiberboard contain-ers, burnable liquids, etc. from licensee's various laboratories and fuel fabrication processes. 1.9.7.3 Incinerator System Location The auxiliary incineration system is located in the Contamination Controlled Area of the Westinghouse Columbia Plant. The specific location is shown in Figure 1.9.0.1., Revision 8 (Page 77). 1.9.7.4 Incinerator System Description and Operation The incinerator is a controlled air, dual chambered, 9 gas fired unit. The two chambers, ignition (lower) will operate at approximately 1500 F and the (upper) combustion chamber will operate at approximately 2000'F. In addition, the ignition chamber is equipped with a combustible liquid burner. There is also a continuous Ash Removal System opening at the rear of the ignition chamber. Exhaust gases leaving the upper combustion chamber will be transferred into a Quench Tower. 70-1151 Date: 8-24-74 Revision No. 8 Dofe: 3-5-79 Page 194a Docket

SNM-1107 1.9.7.4 Incinerator System Description & Operation (cont.) The exhaust gases are sprayed with conditioned water and are condensed and cooled. This condensed liquid is adjusted for pH and reused in the gas scrubbing system. Material movement through the auxiliary incineration system is described as follows: 1.9.7.4.1 Boxes of contaminated waste, with the amount of contamination recorded, will be delivered to the incinerator. 1.9.7.4.2 The boxes will be fed via a conveyor into the incinerator feed system. 1.9.7.4.3 The incinerator feed door will raise auto-matically as a hydraulic RAM pushes the box into the ignition chamber of the incinerator. 1.9.7.4.4 The feed system can be adjusted from four (4) boxes to twelve (12) boxes per hour. 1.9.7.4.5 Live steam may be injected into the chamber to assist control of the combustion pro-Cess. 1.9.7.4.6 The gaseous products of the combustion at approximately 2000*F will enter the Quench Tower where the temperature will be lowered to approximately 160 F. 1.9.7.4.7 The gases will pass through a Venturi Scrubber section and into a hcl Acid Stripper (packed column). Pogo 194b "Dbcket 70-1151 Octo: 8-24-74 Revision No. 8 Dofe: 3-5-79

SNM-1107 1.9.7.4.8 The gas flow then travels through a con-denser and any liquid removed is returned to the scrubber pump. 1.9.7.4.9 The dewatered exhaust gases are reheated by the duct heater before entering the HEPA filter house. All duct work between the condenser and the exhaust blower will be heated and insulated. The top, bottom and sides of the HEPA filter. house will also be heated and insulated. 1.9.7.4.10 The exhaust blower will be mounted in the second floor equipment room with a stack up through the roof. An isokinetic probe will be installed a minimum of 5 duct diameters above the blower. A small back-up blower will be installed in parallel with the primary blower. The back-up blower will only operate when the primary blower fails. The back-up blower is only to permit an orderly shut-down. 1.9.7.5 Radiological Safety Control The incinerator system is installed within the Contam-ination Controlled Area of the plant. Only authorized personnel are allowed into this area. Operating personnel are required to submit to the bioassay program for routine urinalyses. Lung burden determin-ations (subparagraph 3.2.3) and the use of external radiation exposure monitoring devices (subparagraph Docket Date: Revision No. Date: Page 194c

.i SNM-11oy 1.9.7.5 Rediological Safety Control (cont. ) 2.2.3) may also be required. An isakinetic air sampler, described in subparagraphs 1.9.6.4 and 1.9.7.4.10 is installed downstream of the HEPA filters in the incinerator filter house. This air sampler continuously collects samples representa-tive of the exhaust effluents discharged to the atmos-phere. The samples are analyzed daily during operations. If the exhaust effluent at the point of release -12 reaches a level of 2 x 10 microcuries per milli-liter, an investigation will be made and the results -12 evaluated. If the investigation reveals that 4 x 10 microcuries per milliliter may be exceeded as an annual average concentration, the cause will be deter-mined and' corrective action taken. These release and action limits are consistent with those applied to all other exhaust effluents. Effluent exhaust concentrations from the existing incinerator have averaged less than 20% of MPC. The exhaust system for the new incinerator is expected to represent an improvement over the existing inc'in-erator and thus lower exhaust concentrations even further. Air sampling requirements for the incinerator will be evaluated in accordance with subparagraph 2.2.6 and 3.2.2 of this license. Permanently mounted continuous air sampling stations will be established 8-24-74 Revision No. 8 Date: 3-5-79 Page 194d Dockel 70-1151 Date:

SNM-1107 1.9.7.5 Radiological Safety Control (cont. ) where the greatest concentration of airborne activity is expected under adverse circumstances and consis-tent with operator work locations during the initial loading operations, and during ash removal operations. The exhaust blower maintains the combustion chambers at a negative pressure with respect to atmospheric. Under normal conditions, the combustion chamber will operate at a negative pressure of 0.1 " H O or more. 2 I The exhaust system will be maintained (filter change, sc) 2bber maintenance, etc.) to assure that this mini-mtm negative pressure drop of 0.1 " H O is maintained. 2 This should be sufficient to ensure adequate contain-ment since the combustion chambers are relatively air tight to assure that a proper combustion atmos-phere is retained. Minimum instrume14tation and con-trols are described in subparagraph 2.2.12 of this license, and apply to the auxiliary incinerator. Incinerator ashes are continuously transferred from the combustion chamber directly to a ventilated enclosure. This is performed within containment under negative pressure. After transfer to an approved container, appropriate precautions will be exercised during removal of the containers to minimize airborne radioactivity. Typically, all ash handling will be conducted within a ventilated enclosure designed to meet the requirements of subparagraph 2.2.5 of this license. Docket 70-1151 Date: 8-24-74 Revision No. 8 Dofe: 3-5-79 Page 194e

SNM-1107 1.9.7.5 Radiological Safety Control (cont.) At any time, liquids from the scrubber can be manually or automatically transferred to the final filtration tank where it is combined with conversion operation process wastes. These materials are then pumped through an on-line monitor system uhcre uranium content is determined and if within acceptable limits is pumped to the plant waste treatment facility. Here they are refiltered and discharged to the environment in accordance with the limits specified in 10CFR20.106. Due to the increased efficiency and improvements on this new system, total discharges of wastes are ex-pected to be decreased. 1.9.7.6 Nuclear Safety Control The area is monitored by a criticality alarm station which is part of the plant system and alarms both throughout manufacturing areas and at the plant Health Physics Laboratory. The incinerator is operated on a nuclearly safe batch basis in accordance with the maximum permissible values of mass listed in Figure 2.3.2.1. The enrichment used to determine the maximum permissible mass will be the highest value assigned to any of the wastes accumulated for incin-eration. All associated equipment, such as the scrubber pump tank, heat exchanger, filter housing in the scrubber recirculating system, and the vacuum cleaner to be used for ash removal is designed for processing 235 wastes having a maximum enrichment of 4.15 w/o g, Docket 70-1151 Dofe: 8-24-74 Revision No.8 pote: 3-5-7 9 Page 194f

SNM-1107 1.9.7.6 Nuclear Safety Control (cont. ) However, if it becomes necessary to process wastes 35 having enrichments between 4.15 w/o U and 5.0 w/o

235U, this equipment, (if required), will be resized and respaced in accordance with the applicable criteria given in Figures 2.3.2.1 through 2.3.2.4.

In addition, the batch size will be appropriately reduced. Combustible wastes delivered to the incinerator area are contained in 30-55 gallon, metal or fiberboard drums, or fiberboard boxes presently used for baled waste shipments. These containers of waste are scanned in a gamma counting facility. After scanning, the containers are stored in an area adjacent to the incinerator, under established criteria for the Con-tamination Controlled Area. The applicable storage criteria are those described in Paragraph 1.3.7. Wastes accumulated without regard to origins are assumed to contain uranium having a maximum enrichment, 235 normally 4.15% U. Proper storage of this material and storage area posting requirements are monitored routinely by the Plant Criticality Engineer. Waste accumulated with known origins or enrichments are assigned the known enrichment. They are stored correspondingly segregated in accordance with estab-lished operating procedures. Storage areas for these wastes are reviewed and approved by the manager of the Radiation Protection Component. Docket 70-1151 Dofe: 8-24-74 Revision No. 8 Date: 3-5-79 Page 194a

i SUM-1107 1.9.7.6 Nuclear Safety Control (cont. ) 235 All containers are marked with grams of U contained therein as determined by licensee's gamma counting . facilities. Each container is limited to 35C grams 235U reduced by 501 to reflect the measurement un-certainty associated with the gamma count. The gamma counting facilities are calibrated at least monthly, and checked daily during counting operations, using phantoms loaded with known quantities of U. Size and geometry of the phantoms are identical to those of the waste containers. An incinerator log is maintained by the operator, in-5 dicating the 0 content of waste charged to the system and ash removed from the system. Until the limit specified below is reached, waste can be charged. When the incinerator system is cleaned and the ash removed, the nuclearly safe containers of ash are gamma counted, the SNM content recorded in the log and a comparison made with the amount charged. The difference will be considered MUF and recorded in the log. Ash may also be analyzed chemically to verify the U content. A particular batch portion is not charged when the sum of such an additional charge plus the recorded quantity of MUF plus the amount already charged ex-coeds a nuclear safe batch of SNM reduced by 50% to reflect the measurement uncertainty. When this limit Dockel 70-1151 Date: 8-24-74 Revision No. 8 Dofe: 3-5-79 Pogo 194h

SNM-1107 1.9.7.6 Nuclear Safety Control (cont.) reached, incinerator operations are suspended, ash removed and gamma counted, and a survey of the system made to measure any biases which may exist between the feed and ash counting steps. The recirculating scrubber solution can be smmpled and analyzed by alpha proportional counting techniques. When loaded, HEPA filters are gamma counted in a similar manner as feed material. In addition, certain. sections of the system may be surveyed visually, or with direct reading portable instruments. Alternatively, the MUF may be adjusted to zero after each burn. In this case, the ash would be removed and the entire incin-erator system would be thoroughly cleaned, visually inspected, and surveyed for residual contmmination prior to release by the Radiation Protection Component. After operation of the incinerator, ash is removed with a vacuum cleaner or other means and loaded into containers such as polypaks, fiberpaks or metal pails. Both the vacuum cleaner and the ash containers are either limited to a nuclearly safe volume or a nuclearly safe diameter. The applicable maximum permissible values specified in Figures 2.3.2.2 and 2.3.2.3 respectively for 4.13 w/o homogeneous oxides will be used. The ash is gamma counted and a compar-ison of ash count with charge count is made and a MUF determined. Whenever the total MUF (initial plus adjustments) approaches the safe mass limit, Docket 70-1151 Date: 8-24-74 Revision No. 8 Date: 3-5-79 Pace,oa4

SNM-1107 1.9.7.6 Nuclear Safety Control (cont. ) the system is thoroughly cleaned and, if necessary, new components are installed and the system is resur-veyed to establish a new system (initial holdup) MUP. Each container of ash is limited to a maximum of 350 grams U reduced by 50% to reflect the measurement uncertainty. Containers of ash are stored in a desig-nated section of the Contamination Controlled Area near the incinerator in accordance with the applicable nuclear critica]ity control criteria established in subparagraph 2.3.2.2. Ash may be processed for recovery of the SNM or disposed of to a licensed burial facility. The wet scrubber system sump tank (water reservoir), filters and heat exchanger are each in the form of cylinders with an effective inside diameter of 10.2" or less. The heat exchanger is considered a flow through device and the sump tank and filters are spaced in accordance with surface density criteria. 10.2" is the maximum permissible cylinder diameter for 4.15 w/o material specified in Figure 2.3.2.3 for homogeneous material. 1.9.7.7 Safety Mechanisms Safety controls exist in several are s of the system to insure safe operation of the system as well as control operational upsets and/or malfunctions that could occur. These are listed as follows: Docket 7 0-1151Defe: 8-24-74 Revision No. 8 Date: 3-5-79 Page 194j

SNM-1107 1.9.7.7 Safety Mechanisnc (cont.) 1.9.7.7.1 liigh temperature (approximate 250 F) detected in che Quench. Tower Sump. Alarm Indication. Appropriate actions are taken to correct the situation. 1.9.7.7.2 Low indications in the scrubber system weir liquid flow. Alarm Indication. Appro-priate actions are taken to correct the situation. 1.9.7.7.3 Low indication on system air flow. Alarm Indication. Appropriate actions are taken to correct the situation. 1.9.7.7.4 AP IIEPA filter high. Alarm Indication. Appropriate actions are taken to correct the situation. As enumerated above, sufficient means are provided for immediate detection and correction of problems that could occur in the incinerator system. For this rea-a son, adverse in-plant and off-site effects due to system failures are not considered likely. 1.9.7.8 Improvements in the operation, logic and functional control of this system may be made as indicated by new regulations and/or operating experience. Docket 70-115Date: 8-24-74 Revision No. 8 Dale: 3-5-79 Page

SNM-1107 N 1.9.'8 Chemical-Manufacturina Dovelopment Laboratory 1. 9. 41 1 Purpose of Chemical-Manufacturing Development Laboratory The purpose of the Chemical-Manufacturing Development Laboratory is to provide a separate area where developme of processes and equipment can be accomplished with minimum impact on normal production operations. This area will be used for development, prototype developmen' f and equipment checkout prior to installation in the production operations. i 1 1.9.g.2 Typical operations That Mav occur In the Develooment Laboratory The three typical areas of operation that may occur I, g are listed below:

1. 9. 8. 2.1 Chemical Development such as Waste Treatment Studies, Uranium Chemical l

3 1 Processing, Uranium Recovery, etc. I l 1.9.8.2.2 Ceramic Development such as Powder a Preparation and Characterization, Pellitization Studies, Sintering Studies, etc. 'i.9.8.2.3 Mechanical Development such as Rod Loading Devices, Rod Plugging and Welding Development, etc. k 1.9 8.3 Specific Examples of Development Operations a,c, Description of development projects (3 pages) . ]} I l Docket 70-1151 Defe: 8-24-74 Revision No. 8 D ate: ~ 3-5-7 9 Pope 1941

t SNM-1107 1.9.8.4 Chemical-Manufacturing Development Laboratory Location The Chemical-Manufacturing Development Laboratory is located in the Contamination Controlled Area of the Westinghouse Columbia Plant. The specific location is shown in Figure 1.9.0.1, Revision 8 (page 77). Defe: 3-5--79 Page 194m Docket 70-115Date: 8-24-74 Revision No. 8

1 SNM-1107 .o

1. 9. t e. 5 Chemical-Manufacturing Development Laboratory Descrip-tion The laboratory will occupy approximately 4,4 00 square feet total area of floor space.

It will be located l ' adjacent to the Production Manufacturing Area and will be isolated by a wall or fence. Services such as ventilation, water chemicals, etc. l will be provided as needed. Equipment and operations i used for development will be evaluated by the Radiation Protection Component for compliance with existing license and regulatory requirements prior to operation. l The laboratory will be monitored by the area criti-cality alarm system. The personnel bioassay program 1 described in Section 3.2.3. will apply to persons working in this area.

1. 9. t. 6 Chemical-Manufacturing Development Laboratory Controls The scope of projects anticipated for this area is 1

necessarily very broad. This will require the follow-ing administrative controls to assure that radiological and nuclear safety concerns are addressed and appro-priate controls are implemented. In this regard, lines of organizational authority for the laboratory follow the philosophy outlined in sub-paragraph 3.1 of the license, i.e. line management is responsibic for all aspects of the operations, in-cluding safety. t I 194n j D ket 70-1151 Date: 8-24-74 Revision No. 8 Dofe: 3-5-79 Poge

l SNM-1107

1. 9.8. 6 Chemical-Manufacturing Dev. Lab. Controls (cont. )

The radiation protection function's responsibility is to review all development work from a radiological and nuclear safety standpoint. All work involving radioactive materials require either an effective detailed procedure or a job safety analysis. Proco-dures are reviewed by the radiation protection function for radiological and nuclear safety. Whether the work is performed under approved procedures or job safety analyses, the responsible line manager is required to submit sufficient information to permit the proper review. The radiation protection function then issues the nuclear safety posting criteria and inspects installed equipment as appropriate. Air sampling requirements for the laboratory will be evaluated in accordance with subparagraphs 2.2.6 and 3.2.2 of this license. Permanently mounted continuous air sampling stations will be established where the greatest concentration of airborne activity is expected under adverse circumstances and consistent with operator work locations. However, engineering controls .o will be used where possible to control airborne radio-activity at its source. Ventilated enclosures are used as appropriate to con-trol airborne concentrations. Examples include a walk-in ventilated hood for testing large pieces of equipment, small fume hoods, dust collectors, etc. 194 Docket 70-1151 Date: 8-24-74 Revision No. 8 Dofe: 3-5-79 Page

-a_.--- 1 SNM-1107

1. 9.,8. 6 Chemical-Manufacturina Dev. Lab. Controls (cont. )

All enclosures will be designed and operated to meet the ventilation specifications in subparagraph 2.2.5 of this license; ventilation control procedures will conform to subparagraph 3.2.2 of this license. ~ i l l I s 4 1 i k 70-1151 Date: 8-24-74 Revision No. 8 Date: 3-5-79 Page 194D

i SNM-1107 a,C, 1.9.9 Purification of Contaminated Scrap through Solvent Extraction Description of Process (16 pages). 1.10 Off-site Release Evaluations Westinghouse has postulated a variety of accidents in the handling of large quantities of source and low enriched special nuclear materials and has found the consequences of any of them to be well within established guidelines. The most significant type of accident would be a release of an appreciable quantity of radioactive material off site. A quantity of uranium may be established, which, if released, would produce a downwind concentration at ground level equal to the maximum allowable concentration specified in 10 CFR 20.106 (a). 8-24-74 Revision No.8 Date: 3-5.79 Page 194 9 70-ll51Date: Dodel

,e. SNM-1107 l 2.2.1 (continued) 8 Four emergency standby generators with rated capacities of 250 kw, 300 kw, and two at 500 kw will be maintained. The standby generators will j be activated automatically in the event of a facility power outage. 2.2.2 Emergency Equipment Equipment required to cope with a radiation emergency will be kept at designated locations and will be sufficient to provide emergency personnel adequate radiation protection to meet the requirements of 10 CFR 20 during corrective activities. Film and/or TLD badges and pocket dosimeters capable of detecting and measuring gamma and x-radiation will be available to emergency personnel. Portable instrumentation, which is available at various locations on the site for the evaluation of beta-gamma radiation, will have capabilities over the range of 0.1 mR/hr - 300 R/hr. Personnel protective equipment, such as respirators, self-contained breathing apparatus and protective clothing; and other required equipment, such as signs, rope or tape for marking exclusion areas, smear papers, blank data forms, and floor plans of buildings including equipment layout will also be maintained. 2.2.3 Personnel Monitorina Devices ( Film badges or thermoluminescent dosimeters (TLD's) provided = by a commercial supplier, capable of detecting an. measuring gamma and x-radiation will be used. In addition, neutron IY detection capability will be available when specified by the radiation protection function. Revision No. 8 pot. 3-5-79 Pope 206 Dockel 70-1151 Date: 8/28/74

DOCKET f0. 7B - //f/

• O n

}l/fl7y' l: 6u L. :. fl0TICE T0 flRC PUBLIC DOCUMEllT ROOM l The following item (s) are being withheld from public disclosure pursuant to the Atomic Energy Act of 1954, as arnended, and the Energy Reorganization Act of 1974. LJa. cud sMr9 w& Pror. Podh 7 M&2 A 'hI - appi,iak -41 a s =}}