ML18081A223

Part B of CSF-1, Application (Selected Parts as Related to the Radiation Safety Program - Part 2)

ML18081A223
Person / Time
Site:	West Valley Demonstration Project
Issue date:	10/12/1962
From:	Nuclear Fuel Services
To:	US Atomic Energy Commission (AEC)
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ML18081A225	List: ML18081A116 ML18081A222 ML18081A223 ML18081A224
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{{#Wiki_filter:~-----------Appendix 9.9 Curriculum for Process Operators and Senior Process Operators A. Chemical Process Operators

1. Introduction-for all trainees -. a. History of plant b. Site description

c. Protection of plant personnel

d. Protection of public e. Licenses and permits required f. Purpose of plant g. Reason for training h. Requirements of trainees i. Type of training j. Results of ~raining k. Industrial relations

2. Lay nuclear physics and chemistry-for all trainees a. General description of reactors ** b. Different types of reactors c. Nuclear reactors--broadly

d. Results of reactions

e. Physical description of various fuels f. Significance of fission products and their build up g. Reasons for recovery of Source and Fi~sionable material 3. Process description-for all trainees a. Pictures of plant b. Model inspection

c. Input material--form and content d. Stepwise handling procedure through process e. End product f. Pack*aging and shipping g. Waste treatment 4 o Reading-for all tr~inees a. Schematics

b. Instruments

c. Definition of terms d. Data recording

5. Health and Safety program-for all trainees a. Elementary radiation theory 1. Types of radiation

2. Radiation in perspective

3. Permissible limits Appendix 9.9 b. Sources of radiation

1. Natural radioactivity

2. Fall out 3. Man-made sources 4. Fuel elements 5. Normal distribution of radioactive materials in the plant 6. NFS zone designations

7. Potential for acci.dents in'lolving radioactive materials

c. Criticality

d. Radiation control meth 1 ~ds I Administrative control e. Radiation control methods II 1. External exposure control 2. Internal exposure 9ontrol f. Radiation control method III Contamination control g. Scope of the radiation monitoring program . 1 *. The purpose of a fuel -processing plant is to make a 3-way split of~incoming fuel elements (plutonium, uranium, fission products)

2. Rad i ation goals to be met 3. General policie~ used in meeting these goals 4. Services provide.d by Health & Safety 5. Sunnary h. Aids to a good radiation zone job 1. Before start of work 2. During and after the job i. Use of monitoring i nstruments for self monitoring

1. Portable alpha counter Alpha station :nonitor 2. Portable beta-gamna counter Beta-ganna station monitor 3. Cutie Pie 4. Self reading dosimeters Appendix 9.9

• j
• Advanced ti_*keeping training 1. Simulated maintenance work with operator keeping time 2. Practice session with small groups k. Radiation arithmetic

1. Plant controls and problems 1. Control features 2. Special problems m. Medical program 1. Physical examination

2. First aid n. Chemical safety 1. Types of chemicals handled 2. Special hazards 3. Protective clothing and equipment

o. Fire safety 1. Description of fire systems 2. Fire brigade organization

3. Fire prevention

p. Safe operations of cranes .and hoists 1. In s pect-ion and preventative maintenance. 2. Co n trols and limit switches 3. Sa f e operating techniques

q. Safe ope r ation of vehicles 1. Heavy equipment

2. Automobiles and light.trucks 3. Snow removal equipment

• 6. Equipment descriptions and u*es by major area--for all trainees a. Fuel Receiving and Storage (FRS) b. General Purpose Cell (GPC) c. Process Mechanical Cell (Pie) d. Equipment Decontamination Room (EDR) e. Chemical Process Cell (CIJC)

Appendix 9.9 f. Product Packaging and Handling (PPH) g. Cold Chemical (CC) h. Control Room (CR) .1 7. Mechanical manipulation-for selective trainees a. Fuel Receiving and Storage (FRS) b. General Purpose Cell (GPC) c. Process Mechanical Cell (PIC) d. Equipment Decontamination Room (EDR) e. Chemical Processing Cell(CPC)

f. Scrap Removal (SR) a. Chemical processing steps-for

~elective trainees a. Sa...,ling

b. Cold Chemical (CC) c. Product Packaging and Handling (PPH) Product Packaging and Shipping (PPS) d. Acid Recovery (AR) e. Waste evaporation

f. Waste tank farm o*perations

9. Control room ope~ations-for selected trainees To inclucfe all of item 8 plus control l'!)om Qperations

10. Process maloper~tion-*1enerally broad--for all trainees a. Utilities

b. Judgment c. Other e.g. (flre) d. Equipment malfunction

• 11. General decontamination procedures-~f~r all trainees a. Personnel

b. Equipment

12. Waste treatment-for all t~*ainees except c,,ntrol room trainees a. Equipment

b. Low level c. High level 13. General emergency measures--for all trainees a. Loss from tankage b. Criticality emergencies

--- () C Apptnclix 2,2 c. Chealcal explo1ion1 d ,> Equi,-nt failun ** Proc*** **rgency procedun 14. Accountability-for all train*** a. EconOlllc con1ideration

b. Criticality con1ideration 1,. Ancillary 1ervice a. Utilitie1

b. Maintenance and Jhops c. lanhou***

d. Security e. Senior ch*ical proce11 operators.

All of the above and in addi tion1 1. Conditions and lialtations in facility llcen1e (or authorization)

2. Design and operating lillltatlon1 in technical specifications

3. Procedures for any changes in (1) and (2) above

• 4. Somewhat aon advanced ch..S.1try and physics ,. Relations with utilitle1--AS::--ESADA--ASDA

6. Somewhat more advanced radioactivity

7. Somewhat aon advanced criticality

.. Appendix 9.17 Protective Clothing and Safety_Eguipnent following is the startup supply of protective clothing and equipnent available at the plant a. 20 dozen wo:k shirt, b. 20 dozen pair work trousers c. 20 dozen pair coveralls

d. 5 dozen laboratory coat& e. 20 dozen pair cloth boots f. 20 dozen surgical type cloth hats g. 5 dozen cloth hoods h. 24 MSA Ultra Filt~r Masks 1. 18 MSA Air Line Respirators

j. 12 MSA Air Masks. k. 12 MSA Face Shields 1. 144 MSA Softsides Goggles m. 12 MSA Plastic Suits n. 500 dozen pair 6 mil PVC gloves o. 36 dozen pair lined latex gloves p. 12 dozen pair dry box gloves q. 12 dozen pair leather palm gloves r. 2 ~.,fety harness

• s. 3 Stretchers

t. 3 Fire Blankets u. 144 Hard Hats v. 1 pair Safety shoes for each production employe~ w. 20 dozen pair shoe covers Maintenance and Inspection of Protective Clothing and Equipment Coveralls, shoe covers, gloves and related items of apparel will be collected, monitored, sorted according to levels of contamination, and laundered after each days use. Any c t othing contaminated to greater than 50 mrad/hr ganna or 50,000 d/m.alpha will be packaged for burial. No attempt will be made to launder these items. All clothing will be spot checked after laundering for residual contamination.

Coratamination in excess of 0.2 mrad/hr beta-ganma or 1000 d/m alpha will require that the clothing be re-* laundered and resurveyed. Items which can not be cleaned below these levels will*be d iscarded. After each use, masks will be surveyed and released if contamination levels are less than 500 d/m~lpha and 100 c/m beta-ganaa. If contamination exceeding these levels is detected, ~e masks will be set aside for special decontamination. The contaminated areas will be cleaned by hand, taking special care to prevent sp~ad of contamination to the inside of the mask. When released, the masks wi-11 be washed in a solution of MSA cleaner-sanitizer, rinsed in clean water, dried, and packaged in plastic bags. filter canisters will be handled separately. Canisters will be surveyed, cleaned if necessary and stored apart from the masks. Contamination limits for non smearable contamination on canisters are 100 d/m alpha and 0.2 mrad/hr beta-ganna. I'. ----... --~~~---'

---

~-AeRtodix 9, 11Hand and Foot couot1r1 Two beta-ganma hand and foot counters are provided.

They*are to be located in the Mai~ Entrance Lobby to serve as a .final contamination check before entering the lunch room or before.leaving the plant. The counters are supplied by Eberline Instrument Corporation, Santa Fe, New Mexico and are described belows 2-Model HFM-2 Beta-Ganna Hand and Foot Monitors with external probe for clothing survey. The system operates continuously using 4 Amperex 90NB GM tubes in each hand and foot cavity * . Cavity shielding is equivalent to 1 inch of lead. The external probe is a halogen quenched GM tube mounted in a Model HP-177 side window hand probe. Four 100 ua relay type meters are used to accept the output from the nand and foot cavities. One four* inch edge reading meter*is used for the external probe. Meter ranges are 0-500,*0-2000, 0-5-000 and 0-20,000 cpm with scale ielector switch mounted internally. A single speaker with variable volume control provides an audio indication of count rate. If the count rate exceeds a preset level, a buzzer alarm sounds and warning lights indicate the source of the contamination. Jesting of Hand and.Foot Monitor* The detectors in the hand and foot counters will be ch*cked for response daily by positioning a beta source over each. ARPfndlx 9.33 Air Sf11Pllng and Alr llonltorlng EqulP!fnt ___ .....;.._, ______ *--*--~ - Appendix 9.33 Air Sampling and Air Monitoring Equipment Site Perimeter Air Monitor Continuous Air Monitors are located at three points around the perimeter of the service center. The units are supplied by Tracerlab, a division of Laboratory for Electronics, Inc., Richmond, California and are described belows 3-Model 11.\-58 Fixed Filter Air Particulate Monitors with specially designed, heated, ventilated, enclosure and filter holder modified to hold one particulate and one charcoal filter in series. 3-MM-68 Log Ratemeter with 2t inch meter indicating from 20 to 200,000 cpm and a switch selected scale for monitorirtg high voltage. Time constants vary with counting rate from 60 seconds at 20 cpm to 50 milliseconds at 200,000 cpm. 3-Model ll>-18 End Window Beta-Gaama G. M. Detector, a 2'-inch o.o. cartridge containing an Amperex 100-NB halogen quenched GM tube. Following the GM tube is a trigger circuit that gives a 4 volt-2 microsecond pulse into a terminated 93 ohm outpu.t cable. 3-L and N model S Continuous Strip Chart Recorders. Each monitoring unit is placed on a ten foot high platform to keep it above the maximum anticipated snow level. Plant Site Air Sampler An air sampler is available for sampling air around the plant site. The unit is supplied by Gelman Instrument Company, Chelsea, Michigan and is described belows 1-Model 26001 Nuclear Air Saq,ler capable of sampling uously at a constant rate of l CFM. The flow is controlled by a limiting orific, installed in the sampling line between the filter bowl and intake of a vacuum pump. The amount of air sampled is recorded on a dry gas meter and a vacuum gauge is included to correct the indicated flow for error due to pressure drop across the filter. A running time meter indicates cumulative operating time in hours and tenths. Samples are collecte~ on two 2-inch in-line type filter holders. The entire assembly is housed in a heavy gauge steel cabinet fitted with louvers for ventilation. ---*--------- -*-------! I -~ C C Appendix 9.33 Plant Air Particulate Sampling System An in-plant air sampling system is available utilizing a central vacuum pump and vacuum headers to all building occupied areas. There are 54 area air sampling stations and 19 in-cell remote air sampling stations available for use. Each area air sampling station consists of a line to the vacuum header with a valve, a Gelman Model 8224, 10-84 1pm air flow meter and a Gelman Model 1200-A, 2 inch diameter open filter hold,r. Each remote air sampling station consists of a line to the vacuum header with a valve, a Gelman Model 8224, 10-84 1pm air flow meter, a Gelman Model 1200-C 2 inch diameter closed filter holder, another valve and an offset penetration to the cell or remote area. Continuous Air Monitors Seven continuous air monitors are provided. The units are supplied by Nuclear Measurements Corporation, Indianapolis, Indiana and are described belows 1-Model PAPM-1 Prograamed Alpha Plutonium Monitor including two ASC-1 alpha scintillation detectors utilizing ZnS phosphor and one LCRM-55 dual logarithmic count-ratemeter with two 5~ cycle meters range 10 to 1,000,000 cpm and power supply. Each ratemeter has a dual contact meter manually set at a chosen scale for alert or fail-safe and alal'ffl condition. One continuous duty positive displacement industrial air pump driveh by a belt coupled, sealed ball bearing motor with an automatic switching valve which shifts collection from one collector to the other. The time cycle is controlled by a programmer with 1 through 24 ho~r cycles available. The count-ratetneter output is recorded oh a* two per\ contlnuous . strip chart recorder. During the last hour of off-collection time, the activity remaining on the filter is counted and the total count is printed out on paper tape. Assuming a 10 cfm sa~~ing rate and a concentration of plutonium in air of 10* ~c/cc, the build-up activity on the filter paper would be 37.8 cpm per hour of which 3~ or 13.8 cpm would be detected. At the end of 12 hours the detector would see 165 cpm above background, not enough to cause an alal'ffl. The ~ir pump would then cycle to the other collector and the natural activity on the first collector would be allowed to decay for 11 hours. Then, from the 23rd to the 24th hour following the lnitial collection, the total count on the first collector would be recorded. The natural activity background should be about 300 to 500 counts per hour and the plutonium count would be about 9,900 for the one hour count. The unit then would alal'ffl after 24 hours in a -----*-- Appendix 9.33 concentfftion approaching the ,IQ hour M.P.C. If the concentration was 10-~c/cc the first detector would see 1100 cpm above background after 8 hours of collection and this would probably cause an alarm in the counting ratemeter. The unit will detect either a low level build up or a sudden burst of plutonium contamination and will alarm before the exposure of personnel exceeds the limits specified in 10 CFR-20. 1-Model AM-2A Fixed Filter Air Particulate Monitor. One ASC-1 alpha scintillation detector with ZnS phosphor. On6 LCRM-2M count ratemeter with one 3 cycle logarithm1c scale of 50-50,000 cpm. Detector is shielded by 2 inches of lead equivalent. The air pump is a continuous duty positive displacement industrial type driven*by a belt coupled, sealed ball bearing electric motor. Manually set alarm points with alert and alarm settings. Count,.~atemeter output is recorded on a ~j~tinuous strip chart recorder. Alpha air contamination of 10 ~c/cc and saq>ling rate of 5 cfm will result in 7 cpm build-up per hour. 5-Model AM-2A Fixed Filter Air Particulate monitor identical to the unit described above exce r t that the detector is a DGM-2 end window GM and the filter holder is modified to accept two filters in series, one particulate and one vated charcoal for collection of iodine-131. A concentration of 10-lO~c/cc and a saq>ling rate of 5 cfm will result in 350 cpm build-up per hour. Calibration and Maintenance of Continuous Air Monitors All the continuous air monitors will be calibrated monthly by analyzing the filters in the counting room and comparing the results with the count rate observed at the air monitors. Response of each unit to radiation will be apparent because of the natural activity filtered out of the air. Medical Monitoring Equipment Thyroid Monitor A thyroid monitoring system is available for detecting iodine~l31 deposited in the thyroid. The system is supplied by Nuclear-Chicago Corporation, Des Plaines, Illinois and is described belows 1-Model 612 Collimated scintillation detector with 3 inch diameter by 11-inch thick sodium iodide, thallium activated

• crystal and DuMont 6363 photomultiplier; 1-Model 1720 Support Stand with arm. The arm can be automatically positioned at any height from 12 to 66 in c hes above floor level with a reversible electric motor wh ic h drives a . /

Appendix 9.33 precision ball-screw in.side the vertical column.

• The motor control switches are lo~ated at the end of a 30-inch *coil cord. 1-Model 132-B Analyzer Computer.

The 132-B combines a precision single-ehannel pulse height analyzer, regulated high voltage supply,* a binary scaler and a computing-circuit. A plutontwn ga11111a detector is available for detecting plutonium contamination in wounds. The detector-ratemeter system is supplied by Nuclear-Chicago Corporation, Des Plaines., *Iliinois and consists of the followings 1-Model 644 (DSB-21) ganma scintillation detector with a j-inch diameter by 2 mm thick sodium iodide crystal. The crystal is coupled to the photocathode of a ten stage photomultiplier tube ** through a short light pipe. The crystal projects through a tight flange and has at-inch diameter by 0.0005.inch thick beryllium window to allow detection .of low energy radiation without appreciable loss. Efficiency is about 90 per cent for ga11111a rays of less than 35 kev. Unshielded background is 5 to 10 cpm. 1-Model 8619 Labitron Ratemeter with 4t-inch meter, speaker with volume control and ranges of 0-5001* 2,0001 5,0001 and 20,000 cpm. Eguipnent.for Detection of Gases and Vapors 1-Universal Testing Kit, Model 2. Kit includes a piston type pump with a turret head and four orifices sized for optimum sampling rates, a calibrated handle to permit sampling volumes of 25, 50, 75, -or 100 cc. and a remote -sampling attachment for hard-to;reach spots. Kit provides capability for sampling carbon monixide, hydrogen sulphide, chlorine, mercury vapor, nitrogen dioxide, carbon dioxide, unsaturated hydrocarbons, phosgene, hydrocyanic acid gas, aromatic hydrocarbons, sulphur dioxide, halogenated hydrocarbons, lead-in-air, chromic acid mist, hydrogen fluoride, arsine, boranes-in-air and unsymmetrical dimethyl hydrazine. 1-Model 53 Gascope for detection of natural gas in air. The instrument has a dual range with one scale grad1Jated from 0-100% of the lower explosive limit of natural gas in air and the second scale graduated from 0-1~ by volume natural gas. -'""-* SC ._ Appendix 9.36 Portable Monitoring Equipment Alpha Detectors Appendix 9.36 Portable Monitoring Equipment The equipment provided for the detection of surface alpha contamination includes four portable alpha counters and one alpha floor monitor. These instruments are supplied by Eberline Instrument Corporation, Santa Fe, Hew Mexico, and are as described belows 4-Model PAC-33 Portable Gas Proportional Alpha Counters. Instrument grade propane flows through the probe at 30 cc per minute. The probe has an active surface area of 61 square centimeters. The instrument has three ranges, 0-1000, 0-10,000 and 0-100,000 cpm. Phones for aural monitoring and a uranium oxide check source are included. I-Model FM-33 Gas Proportional Alpha Floor Monitor. Active probe area of 68 square inches for faster surveying of large, open floor areas. Three ranges, 0-1000, 0-10,000 and 0-100,000 cpm. Speaker and phones supplied for aural monitoring. The unit is mounted on wheels and the probe height from the floor is adjustable for 1/8 to 1/4 inches with additional adjustment to 2 inches for safe transportation. Calibration and Maintenance of Portable Alpha Counters The bi-monthly calibration procedure for portable alpha counters is as* followsa a. Check each scale using the calibrated plutonium-239 sources provided and adjust to the proper response.

b. Check the response *of the instrument to the uranium check source. c. Hold the instrument probe against the radium source container and, using the gain adjustment, tune out any response to the ganna radiation.

d. Recheck each scale with the plutonium-239 sources if a gain adjustment was necessary.

Appendix 9.36 Calibrati~n and Maintenance of Alpha Floor Monitor Twice each month the. response of the alpha floor monitor will be tested using the uranium check sources. Beta-Ganma Detectors Beta-Qanma detection equipment includess four GIi Meters supplied by Victoreen Instnunent. Coq>any, Cleveland, Ohio1 o.ne deep hole monitor supplied by Nuclear.Chicago Corporation, Des Platnes, Illinois1 and one floor.monitor supplied by Ebefline Instl'Ulllent Corporation, Santa Fe, New Mexico. This equipme~t io described" belows 4-Victoreen Model ~9 Thyac II.GM Survey Meter with Model 489-4 probe *. lJle detector has a sliding metal window for beta discrimination and a 360 degree window for maximum beta-gamna sensitivity. The meter has three ranges of 0-800, 0-8,000 and 0~80,000 cpm an4 a built-in check source and phone for aural monitoring. 1-'Huclear

• Chicago.Gaaaa*Radiation Monitor for deep holes. The un~t consists of a gamna scintillation detector in a waterproof, shock resistant housing, 150 feet of cable, Model*8619 ratemeter and a strip chart recorder.

1-Eberline Model FM-1 beta-gamna floor monitor. The detectors, Amperex 912NB.<JI' tubes, are mounted in a steel encased lead shiel~,d*housing with an effective monitoring width of 21 inc~es.. The shield can be rotated 45 degrees to check boards and other vertical surfaces close to ground level. The electronic, Model E-1128-1, has three ranges, (0.2*, 2.Q and 20.0 mr/hr. full scale) with ratemeter, hand probe and phones for aural monitoring. Calibration and Maintenance of Portable GIi Counters Before each use the response of the GIi meter will be tested using the source supplied with each unit. After any maintenance has been performed on a unit, 1t will be calibrated using the calibrated 10 millicurie cobalt-60 source. Calibration afl(l Miintenance of Deep Hole Monitor Before each use the response of the deep 1 hoJe monitor will be checked using the radium source. C .... .,,.,. 9.36 .* CalUpgtlon '""**-of lfta-Gzc* Floor llonltor . . twlce each IIDllth

• NlpOIIN of the beta-9-*floor aonltor wl~l be te1ted uelng beta c~ eource,. , I #! 5 Appendix 9.37 Counting Rooa Eguipll!nt . j C ,-Appendix 9.37 Counting Room Eguipnent Liquid Scintillation Counting System A liquid Scintillation counting sy'atem is provided for the detection of t~'1tium in samples. The system ia supplied by Packard Instrument Company, Irie~, La Grange, Illinois.

The Model 314-EX2, as supplied, includes the following a 1-Tri-Carb Spectrometer, a two channel unit with two scalers, red and green, and an electronic timer. All three units have glow tube decade readout. Each channel has discriminator controls providing separate channels of pulse height analysis. Preset time control is in 20 steps from 3 seconds to 100 minutes. Pre!et cougts may be selected on either scaler in increments from 10 to 10. Preset time and both preset count settings interact so that whenever any limit is reached the count will stop, 1-Model ~-c Automatic Control Unit and 100 sample automatic changer, with two photomultiplier detectors, a monitor detector and an analyzer detector monitoring the sample well. The automatic changer and detectors ~re mounted in an eleven cubic foot freezer for controlled temperature counting. The automatic control unit programs operation of the sample changer. Controls may be set to count anywhere from 1 to 100 samples and the unit will recycle continuously if repeat data are required on a batch of samples. The unit may also be set for repeat counting of a single sample. If power failure should occur while a. count is in progress, the control unit will clear and ~peat the count automatically when voltage is restored. A manual over-ride button allows the operator to select any aample for a special count1 1-Model A Digital Printer provides a printed record of counting data on a strip of paper tape._ For each sample, the printer records sample number, elapsed time and counts on both scalers. In the operation of the liquid scintillation counting system, radioactive decay events occurring in the sample cause scintillations which are seen simultaneously by both photomultiplier tubes, giving rise to pulses at the phototube output. Pulses front the photomultiplier& pass through -preamplifier& and into three separate amplifiers. Pulses from the "Analyzer" phototube then go to the discriminator pairs A-Band C-D for pulse-height analysis. The "Monitor" phototube functions o~ly to determine whether a pulse is the legitimate result of a decay event or whether it arises from photomultiplier tube noise. Pulses falling between A and Bare fed to the red scaler and pulses falling between C and Dare fed to the green scaler. output pulses from all of the discriminators pass through the coincidence circuitry and only pulses occurring simultaneously in ~oth photomultiplier& are counted. This results in some loss of Appendix 9.37 efficiency but effectively eliminates phototube noise. The two channols may be uied to estimate the amount of quenching in a sample so that appropriat~

• correction factor*s may be applied to the count. The gration rate of* an unknown sample may be detel'mined by counting the sample with the two channels ope~ating first separately and then in coincidence.

Based on the approximatio~ that coincidence counting efficiency is a_product of the two.single-channel efficiencies, the integration rate is found from the equations dpm

• Counts red x Counts *reen Counts*. coincidence Calibration and** Maintenance of Sample Counters ' I The gas proportional alpha and beta sampl* counters will be calibrated and source checked according to-the following proc,dure after any maintenance has been performed on the units. a. From a aeries of twenty-five minute counts of a calibrated l ,1pha or beta source dete?1Dine1

1. Chi-square Chi-square

• 2. Geometry -G
• X Source ci/m 3. Standard Deviation s.o.
• j (X -i)2 n-1 4. Error p
• Time of sample count Time of control count b *. From the data derived above, establish a maximum and minimum counting rate for the 9°" and 9~ confidence intervals.

c. Each day check the response of the sample counters to the 1 calibrated source. If more than one count in ten exceeds the 9°" limits or more than one coun t in twenty exceeds the 9~ limits, the unit is removed from service until repaired and recalibrated.

l 1 l l I .. f . .... A o pen c!ix 9.37 Calibration and Maintenance of Liquid Scintillation System The calibration and source check pro~edure for the liquid scintillation system will be identical to that outlined above u,ing a calibrated tritium source. Gaaaa Spectrometer A continuous scan gaaaa energy analyzer is provided for analysis of the 3Ctlvity and*ga11111a energy distribution of any gaama emitting sample. The system, supplied by Nuclear Measurements Corporation, Indianapolis, Indiana, is designated Model GSS-~B and consists of the following components, 1-Model WS:-35 Yfell Scintillation Detector with 3 x 3-inch sodium iodide, thalli\lD activated crystal, apectroaeter grade. The well has 100 cc vol\118. 1-Model US-11 Super Shield providing 4i-inches of lead shielding around the detector and a counter-balanced lid. 1-Model PHA-18 Pulse Height Analyzer with linear count-ratemeter auto scanner and binary scale factor selector. Standard energy range is 30 kev to 3 mev. Count-ratemeter ranges are 0-300, 1000, 3,000, 10,000, 30,000, and 100,000 cpm. Ti* constants are 0.3, 1, 3, 10, and 30 seconds. Spectrometer window width la variable in ten steps from Oto 3~. Three position scan speed selector, 10, 25, and 60 minutes. 1-Model GR-5 X-Y Spectroaet~r Graphic Recorder. Chart size is 81' inches x 11 inches. Maximum pen speed is 7.5 inches per second. 1-Model Sl)S-18 Slave Decade Scaler with timer. The N.c Model GSS-1 8 is an automatic scan pulse height analyzer system which provides a graphic record of the activity and energy distribution of any .ganna emitting sample. A constant percentage of each gamma energy peak is ~nalyzed. The fixed window counts only those pulses brought to it by the amplifier. The system uses a sliding pulse amplification technique and is capable of scanning the gamma spectrum in a range of 0.1 kev to 6 mev. Special recorder paper is available for nonstandard ranges. Both automatic and manual scan control are provided. Individual peak monitoring may be accomplished directly on the graph paper using the slave scaler to integrate the total count under the peak. Calibration and Maintenance of Gaaaa Spectrometer The response of the gamma spectrometer to a ca l ibrated source will be checked daily as outlined above. Pulses will be fed into the x~v recorder from a pulse generator. The recorder will be adjusted to the exact pulse height and input rate. This will be performed when the daily source checks indicate that the instrument res p c , nse has shifted. j .I 1 I I I Apptndix 9.37a Detel'llina~lon of !fta lllitter1 in In-Plan$ Air Sf!Pl** C* C Appendix 9.37a Determination of Beta Emitters in In-Plant , Air Samples concentration of beta emitters in in-plant air samples 11 determined as follows, Ile/ml

• elm aactor) ~c/ml * *Microcuries per milliliter c/*
• Beta counts per minute on sample corrected for background.

M3 Total cubic *ters of air sampled Factor * ---* ... 1 ____ _ cg a Kl~ c

• Collection efficiency
• 98* g
• Geometry of counter
• a
• Absorption correction
• (not applicable. --see paragraph

9. 34 )

• d/(m)/~c)
• 2.22 1o6
• Milliliters pejr cubic *ter
• 106 1 Factor * (.98) {.~} (2.22 x 1o6T Factor *
• 9.2 x 10-13
• i'c/ml *. ,elm (9.2 x 10-13) M3 Since, at 60 1/m a 24-hour sample repre .. nta 86-4113 sampled and the counting error for a one-minute count at 9~* confidence level 11
• 1~ at 400 c/m, .the minimum detectable concentration isa (400) (~2 x io-l 3)
• 4.3 x 10-121'c/ml

.4 with+/- 1~ accuracy.

---

Appendix 9.37b Detellllnatlon of Lonq~Llved Alpha Ealtter1 ln In*Plant Air Sf11Pl** Appen.dix 9.37b Determination of Long-Lived Alpha Emitters in In-Plant Air Samples The concentration of long-lived alpha emitters in in-plant air samples is detel'llined aa followaa pc/ml

• 9.p (Factor) 113 1-LC/ml Cp
• Calculated c/m due to product ->.At
• Q24. Ct* 1-e* At C24
• 24-hour count C6
• 6-hour count At
• Time of 24-hour count minus time of six-hour count 113 = Total cubic meters sampled Factor = 1 cg a Kl K2 c
• Collection efficiency

= 98~ g

• Geometry of counter
• a
• Absorption correction
• 70% K1 ~/(m)/(pc)
• 2.22 x 10 6 K2 = Milliliters per cubic meter
• 1o6 . 1 Factor = (.98) (.~) (.70) (2.22 x 168) (108) Factor*= 1.3 x 10*12 s 9p (1.3 X 10*12) 113 Since the counting error for a five-minute count at 9~ confidence level is t 10% at 75 c/m, the minimum detectable concentration on a 24-hour sample isa (75) (1.3 x 10*12) = 1.1 x 10*12 pc/ml 86.4 with+/- 10% accuracy.

,.,. .. lss Appendix 9.39a Low Background Counting System 6Wnfl* 9.;nb Ptv11tnatlon of 8th llllttep tn flEWHE **m\** -. Appendix 9.39b Dete1111nation of Beta Ellitter1 in Perl*ter Spple1 The concentration of beta eaitter1 in perl*ter 1U1ple1 11 detenalned a1 follow11 ~c/al * (Net Coual) (Factor) Net Count rl Total count for 60 ainute1 le11 60-minute background count. Factor 60 C g a Factor Factor

• Total cubic 11eter1 of air 1aapled 1
• 60 cg a K1 K2 Convert, count, per 60 minute, to counts per minute
• Collection efficiency
• 98*
• Geometry of counter *
• Ab1orption correction (not app~icable, see Paragraph 9.34) *
• d/(m)/(~c):

i 2.22 X lo6

• Milliliters per cubic meter
• 1o6 -1 * (60) (.98) (.~) (2.22 X 100} {166)
• 1.5 X l0-14 ~c/ml * (Net Count)M~l.5 x 10-1 4) Since the counting error for a 60-minute count at 95* confidence level is t l°" at 6.5 net counts per minute, the mininun detectable tion of beta emitters on a weekly sample isa ,c/ml ,c/ml With t l°" accuracy.
• (390) (1.5 X l0-14) 604.8
• 9.9 X 10-15 6PPfnclix 9.39c p,te111ination of llpha Eaitter, in Peri9ter Sppl** l

-Apptndix 9.39c C Dttemination of Alpha Elli tter1 in Peri*ter Sppl** The concentration of alpha emitter, 11 det~l'lllined. a1 follow11 ,c/al * (Net Co';) (Factor) .,.c/ml Net Count* Total count for 60 minutes less 60-minute background count. Factor 60 C g a

• Total cubic .. tar, of air 1ampled 1 *.60 cg a Kl K2 Co.,avert1 count, per 60 minutes to counts per minute.
• Collection efficiency

-9~

• Geometry of counter
• 3~
• Absorption correction

-7~

• cJ<*X,c)
• 2.22 x 1o6 '2
• Milltliters per cubic meters
• 1<>6 Factor Factor * . 1 (60) (.98) {.35) {.70) {2.22 X 166) (166)
• 3.1 X l0-14 * (Net Count) (3.1 x 10-14) . M3 Since the counting error for a 60-minute count at 9~ confidence level is -+/- 10% at 6.5 net counts Rer minute, the minimum detectable concentration of alpha emitters on a wtekly sample 111 uc/ml * (390) (3.l x 10-14) ,.. 604.8 .,.c/ml With+/- 10% accuracy

_ _..._"'""'"" __ .......... ""' __ _....~_____..-- ... ~*-.........._..._--*-*----......--..-.-......__._. __ ........__+ ________ _...,___,,~---

• ----Appendix 9.43 Exposure Record Card

,-.. Ezposed From -To M T . . Becorded For Body Status Bad&e I Name (Last, First. Middle) -.. ----. ----t' ------~ ---** -Appendix 9.43 Exposure Record Card Dosimeter.

Readings . Badie Readino Total w T F' s s Total G B N .Total . ... -Prev. Total I Thi, Card I kc. Dose 15 (n-18) Unused Do.,e I s. s. Number Birth Date Nuclear Fuel Servi~ Inc. West Vallq, New York 0 I +l I I ' t f I I ; j s

_.,....,,, ... ___ . __ ......... _---..--=- .... .-......--~--"--'\ .. ......_.~,,~***~~..__ ........... __ .w.,,.... ... --""..._ \: App_en.dix 9. 47 Routine Survey Form ::: -I I

• I (

-... -------..-..----*-*

• -----------

---

..... -......... .--...._ .. _,,, ***----....... --~~~---------_ __:.__;_ _________________________ __. ..... _..;.....;.;;;;_ C Survey Numbers Frequency1 Titla1

• Appendix 9.47 Routine Survey Form ROUlINE SURVEY LOO NUCLEAR FUEL SERVICES, Itc. SPENT FUEL REPR(X;ESSING PLANT MATERIALS AND EQUIPMENT REQUIRED1 DESCRIPTION OF SURVEY1 SPECIAL SAFETY INSTRUCTIONS1 PREPARED BY1 REVISED BY1 Shift Assigned1 Time Allotted:

DATE1 ... -........... --...-. '-., ..... _ ..... ,. .-.---* ....._R _ _..., , ____ . _____ ........ ~*-----~-~.--,--.,;--

---

Appendix 9.49 Environmental Monitoring Program .,

--~========::=:=:=:::S:=:: -::-=:*=*-=---==-=-=w=*::-:::-

• -*--*~......-~---------*~.., ....... --... -=--I .... \ J Appendix 9.49 Environmental Monitoring Program Phase I -Atmospheric Monitoring Three air-sampling stations have been established at the site perimeter.

These stations consist of a vacuum pump drawing air through a filter, a beta-gamna detector to measure the activity deposited on the filter, a log-count ratemeter and strip-chart recorder to provide a permanent record of activity at each location. These air monitors are serviced weekly. One air-sampling station has been established near the plant site. This station will consist of a vacuum pump pulling air through a filter paper to collect particulates. The filter will be changed and monitored weekly for gross alpha and gross beta activity.

• Water Monitoring A rain and snow collection station has been established at the plant site. Samples of water from this*station are coliected and monitored as available for gross alpha and gross beta activity, iodine-131, and strontium-90.

Surfac~ water samples and mud and silt samples are collected monthly and mon i tored for gross alpha and gross beta-ganuna activity. Samples will be collected from the following locations:

1. Erdman Brook near Buttermilk Creek; 2. Buttermilk Creek near the Emerson Road crossing;

3. Cattaraugus Creek near the Nagel Road crossing.

A well water sample is obtained from the site monthly and monitored for gross alpha and gross beta-ganuna activity. Earth and Biota Monitoring Vegetation samples are collected near the three perimeter monitoring stations in the spring and fall and will be monitored for gross alpha, gross beta-gamma, iodine-131, and strontium-90.

• A milk sample is collected from a neighboring farm weekly and is monitored for gross beta-gamma.

Samples collected.once each month are analyzed for iodine-131 and strontium-90. In the spring and fall a rabb i t or other small game from the site will be analyzed for gross beta, gross alpha and iodine-1 31 activity. Phase II -Atmospheric Monitoring The three air-monitoring stations at the site perimeter, as described in Phase I, will be used and servicad weekly. --.. -..... ~. --**"-*- ____ .. , ..... -.... ~-.,. ............... --....... ...-: .. ._ . ., ________ , .. ..-.-.., _____ . .......-.._. __ *-*-*....__ ............... _________ ....._ ___ .._,. ;,. . *----. l Appendix 9.49 The Plant site air-sampling station, as described in Phase. r., will be used -and serviced weekly. Samples may be autoradiographed on x-ray film to determine number and relative intensity of particulates collected. Wa~er Monitoring A rain and snow collection station is establit: 1ed near the plant site. Samples of water from this station will be collected and monitored as available for gross alpha, gross beta and tritium. A strontium-90 mination will be made twice each year. Su1 , face water, mud, and silt .samples will be collected monthly from the locations specified in Phase I. These samples will be monitored for gross alpha, gross beta-gamma, and tritium. Each month one or more of the samples will be gamma scanned if sufficient activity is present. Well water samples will bt~ collected monthly from the site. These samples will be analyzed for gro~s alpha, gross beta-gamma, and tritium activity. Earth and Biota Monitoring Vegetation samples will be collected in the spring and fall near the three perimeter stations. These samples will be analyzed for gross alpha, ~~oss beta-gamma, and iodine-131. One or more of the samples collected in the spring and fall will be analyzed for strontium-90. Milk samples will be collected weekly from the plant site and analyzed for gross alpha, gross beta-gamma, and iodine-131. In the spring and fall strontium-90 determinations will be made. Twice each year, in the spring and fall, fish and shellfish specimens will be collected from Buttermilk Creek and Cattaraugus Creek. These specimens will be analyzed for gross alpha, gross beta-gamma, and iodine-131. In the spring and fall a rabbit or other small game from the site will be analyzed for gross alpha, gross 'beta-ganma, and iodine-131 activity. . . ~-;.;-;*~-~~:::=::===-= .......----* ..... --------*--*-*-----*----*------.-......~-- ..................... --~...:.:-- .. .:~~ .... -.---,-.. ...: , P.N; ...... pa C Appendix 9.51 Stack Monitoring System -.. __ ... .,........._._ ..... ~,--.-, ............... _._,_ ... _ _.. ... ..........,._ ... ..,.., ........ __ _;......,. _.._.__.. __ .......,. __ .._,, ___ .. _ .. ----~--------------*---Appendix 9.51 *Stack Monitoring System , I The stack monitoring system consists of two channels of monitoring; the first channel for beta-gamma emitting particulates, and the second channel for iodine-131 with readout and alarm locally and at the Control-Room Panel. The system is supplied by Tracerlab, a division of Laboratory for Electronics, Inc., Richmond, California. The following equipment is included: 1-Isokinetic nozzle; 1-Model MX-14C Pumping System with a 10 cfm sliding dry vane pump driven by an electric motor through double V-belts, a control valve, a calibrated fixed orifice, flow gauge, and necessary piping; 1-Model MA-lB Filter Tape Transport Mechanism, an advanced version of the Brookhaven design. A solid capstan with milled slots rides on a Teflon shear valve which limits the air bypass around the filter paper to less than 2 percent. The filter paper is held against the rotating capstan by the pressure differential across the paper and is moved by the rotating capstan. Two filter tape speeds are ded; one inch per hour for normal operation,and 28 inches per minute for fast advance to clear contaminated tape from the detector areas; 1-Model MD-lB Beta-Gamma GM Detector, a halogen-quenched end window detecto~, 2t inches in diameter. The window is mica --less than 4 mg/cm2 thickneps* The detector is shielded by two inches of lead; !-Model RM-20B Precision Log Ratemeter with a ~inch panel meter indicating the counting rate directly in counts per minute on.a switch selected three decade (10 ~o 104 cpm) or five decade (10 to 10 cpm) scale. One additional scale indicates high voltage. Th~ ratemeter has an adjustable alarm point and a manual reset to vide "memory". The meter relay automatically resets to permit meter to read cpm below the alarm point~ 1-Model RM-40B Dual Power Supply with main power switch, high voltage switch, two high voltage adjustment screws and alarm reset. Unit supplies high voltage for the system detectors; 1-Model MI-5B Iodine Sampler and Shield Assembly, with a holder for a two-inch diameter activated charcoai filter and a three-inch thick lead shield for the detector; !-Model MD-5B Gamnd Scintillation Detectors with a Ii-inch diameter x 1-inch sodium iodide, thallium-activated crystal, a Dumont 6292 photomultiplier and a 100-gain preamplifier.

---

J( Appendix 9.51 1-Model RM-20BS Precision Log Ratemeter, identical to the RM-20B described above plus a ~pectrometnr input circuit for pulse height discrimination. Window width adjustable from 2 percent to 100 percent and threshold adjustable from 5 percent to 100 percent of full scale. 1-De Var Series R 300 two-pen recorder, Control Room Panel mounted ****-to record output from particulate and radioiodine stack monitors and to alarm if count rate of either unit exceeds tte preset level. The beta-ga11111a particulate monitor, with two inches of lead shielding around the detector, h as a background of about 25 cpm. A counting rate of twice background is obtained at a concentration in the stack of about 1 x ~o-11 ~c/cc of mixed fission products. The Ganrna Scintillation Detec t or, wtth three inches of lead shielding around the detector, has a background of about 175 cpm for a counting threshold of 100 kev. The detector will show 100 net cpm after an exposure of 30 minutes to a con c entration of 10-10 ~c/cc of iodine-131. Calibration and Maintenance of Stack Monitor The response of the stac k particulate monitor to radioactivity will be apparent from natural activity as well as activity from the stack air stream which will be trapped by the filter paper. Calibration of the particulate monitor, relating detector counts per minute to microcuries per milliliter in the air ~tream, will be accomplished by analyzing a section of the filter in the counting room and comparing the results to the count rate indicated by the stack sampler. After the initial calibration, this check will be made only as the need is indicated but not less than twice annually. The iodine monitor will be calibrated quarterly by analyzing the activated charcoal filter in the counting room and comparing the results with the count r~te indicated by the stack sampler. The collection efficiency of the charcoal filter will be checked by _collecting a caustic scrubber sample independent of the stack monitor and comparing the results with the activity of the charcoal filter. This check will be made ~n each batch of filter paper received. -. *-----, -----~---* .....-=-.,.--*---....,.-*-*- .. ------:-----::-----.------...~ Appendix 9.53 Weather Monitoring Station l I

• I !

) Appendix 9.53 Weather Monitoring Station Two weather-monitoring stations are provided, one at 10 feet and the second at 200 feet above ground level. Each station continuously records wind direction, velocity, and ambient temperature. The weather-monitoring stations are. supplied by Science Associates, Princeton, New Jersey and each station consists of the followings 1-No. 4-120 Aerovane transmitter, a combined anemometer and wind vane in one unit. A three-bladed plastic rotor with a ~tarting speed of 2.5 mph drives a magneto which generates a v~ltage di~ectly proportional to wind speed. The streamlined vane houses a synchro whose rotor position is determined by the vane. The transmitter includes a filter to prevent radio interference and is permanently lubricated. 1-No. 4-141-5 Aerovane Recorder provides instantaneous readout of wind direction and velocity on the same chart. Direction data from 0 to 360 degrees is recorded on one side *of the chart and speed data from Oto 100 mph is recorded on *the other side of the chart. Each recording area is 4i inches wide. 1-No. 170 Stainless Steel sheathed temperature bulb and temperature recorder. Recorder is two pen with range of-50 to 110 Fin one degree divisions. The temperatures from both stations record on one chart. 1-No. 174 Aspirated Solar Radiation Shield to house the temperature bulb. Heat from the sun and from surrounding objects is excluded by the dome-shaped shield, by an inner and outer shield and by a surface orlanted baffle. A motor and blower, located at the remote end of the mounting al'lll, induce a forced ventilation. Tho recording charts for the two weather stations are located in the Control *Room Panel. -APPfndlx 9. . Stre .. Gauging and Sf!Pllnq

• tne 91ua1ng ,oc1 s
• Stations are piovlclecl for gauging and 1aapling the flo, , of Frank* Creek and Cattaraugu1 Creek. v*l'lle gauging station, each consi1t of a calibrated
• level detector and con-*:. tinuou1 recorder.
• The i a1111Pling station, Nch con1i1t of a proportioning pu11p to take a aaxliiull 1ize 1111ple of 10 gallon, per ... 1c*. The saaplen are each houNd *1n an electrically heated, **therproof enclo1un. . .

CJ -Fol'llft for Standard*Operatinq Pz~ceduree and Index of Standard 'Operatlnq Procedures ....... .. -*--. -. -.---*----***-------.-.,lft __ ..._ ... _._ ... _.~,,,_,,_._. ______ .._ ______ -4~------*---*--* --**V'Cl"f:,r

• ~--,=II Appendix 9.93 Format for Standard Operating Procedures

1. Purpose -(Merely a repetition of title.) 2. Scope a. Area b. Major Equipment

c. Startup d. Operations

e. Shutdown 3. General Da*., e Name Draft No. a. Criteria of Operations (functions), e.g. Batch, Surge Tank, F.eed Tank, etc. b. Interfacial Effects, i.e. Equipment on Upstream and stream Side of Subject Equipment

4. Special Precautions

a. Administrative

-Need for approval of Shift Sup~rvisor

b. Criticality

c. Accountability

5. Process Streams a. Influent b. Effluent (overflows included)

6. Operations

a. Start Up b. Operate Shut Down Regenerate

c. d. . . e. Emergency Procedures

7. References l , C I C -.. \. :,,.... ...*. , t1<Stf / 5p:-~_Ql * .. I~ ~I-II tld..,,.. S A !=' E T V A N A L Y S I S )V q {){,r SPENT FUEL PROCESSING PLANT Part B of License Application Volume I Copy No. 79 NUCLEAR FUEL SERVICES, INC. July 1962 ,. ..., 7 3 L-!.. '1.J ..._.-e m -*=--=,===

+ I I I CONIENIS Section Paragraph Numa,~ I . INTRODOCTION II III IV V SITE DESCRIPTION Summary

• Geography Meteorology Geo.logy Hydrology Seismology Environmental Survey PLANT DESCRIPTION Plot Plan
• Process Building PROCESS DESCRIPTION Fuel Receiving and Storage Mechanical Handling: Dissolution Feed Adjustment Solvent Extraction--Partition Cycle *-*. Solvent Extraction--First Uranium Cycle Solvent Extraction--Second Uranium Cycle Solvent Extraction Column--Plutonium Cycle Product Purification and Concentration Solvent Recovery Acid Recovery Rework System Waste Handling EQUIPMENT DESCRIPTION Fuel Receivi~g and Storage Mechanical Handling General Purpose*cell Dissolvers Pulse Columnt Evaporators Acid Fractionator Process Tanks Radioactive Waste Storage Tanks Pumps Miscellaneous Equipment 2.1 2.4 2.11 2.15. 2.33 2.46 2.49 3.1 3.5 4.2 4.9 4.21 4.34 4.35 4.52 4.57 4.63 4.67 4.76 4.80 4.87 4.88 5.3 5.12 5.21. 5.30 5.37 5.41 5.47 5.49 5.50 5.57 5.61 Revision 1, October 3Q, 1964 C -~-/-( . ._. Section VI CONTENTS Continued ENGINEERING ANALYSIS OF THE PLANT Introduction Summary Ventilation Sampling and Analysis Maintenance Shielding Monitoring System Utilities Criticality VII PROTECTION OF THE PUBLIC . VIII Summary Normal Operations Stack Waste Storage Tanks Storage Lagoon Burial Ground Egress of Personnel or Material Product Shipment Conclusion Abn~rmal Operations Loss from High-Level Waste Tank Leakage from waste tank Criticality Incident anywhere in the Plant Criticality Incident in Fuel Pool Chemical Explosioo Failure of Iodine Removal Equipment Conclusion PROTECTION OF PLANT* PERSONNEL Design Criteria Protectio~

from Extern~! Radla~1on Inhalation Ingestion Analysis of Accidents Tank f<upture Criticality Incident in Plant Criticality Incident in Fuel Pool Chemical Explosion Failure of Ioding Removal Equipment Minor Accidents Summary Para<<;Jrapb Number 6.1 6.2 6.3 6.22 6.37 6.59 6.66 6.93 6.103 7.1 7.6 7.6 7.10 7.11 7.14 7.18 7.21 7.22 7.23 7.24 7.29 7.30 7.33 7.35 7.36 7.37 8.1 8.4 8.10 8.14 8.20 8.21 8.24 S.29 8.30 8.32 8.33 8.34 Revision 1, October 30, 1964

• I --CONTENTS continued Section .e.a.i:as,raph Number IX PLANT OPERATION Organization Administration Training of Plant Personnel Training of Outside Organizations Health and Safety Program Emergency Procedures Plant Maintenance Program Production Department Process Maloperation

-9.1

• 9.4 9.9 9.12 9.13 9.64 9.68 9.86 9.97 Revision 1, October 26, 1964 I \

c: Number 2.8 2.lla 2.llb 2.llc 2.14 2.19 2.27 2.2:>a 2.29b 2.29c 2.30a 2.30b 2.30c 2.31 2.32 2.34 2.35 2.36a 2.36b .,,_ Tables Total Population and that of Towns, Villages, and Cities within successive 5-mile Radii of the Western New York Nucle&r Service Center. Mean Temperatures in Western New York. Mean Precipitation in Western New York. Mean ~~nwfall in Western New York. Probable Wind Roses and Diffusion Parameters for the New York Nuclear Service Center. Estimated Rock Section Underlying the Western New York Nuclear Service Center. Chemical Analyses of Glacial Deposits. Ion Exchange Capacities and pH of a numbe1 of Soil Samples. Mechanical Analysis Plus pH of Eight Selected Samples. Cesium Sorption of New York Soil Samples. Cesium Sorption on N~w York Soil Samples. Strontium Sorption on New York Soil S~mp l es. Strontium Sc , rption on New York Soil Samples. Strontium Sorption on New York Soil Samples. Ruthenium Sorption on New York Soil Samples. Approximate Mineralogical Content of New York Soil Samples. Fifteen-Year Summary of Cattaraugus Creek Flow Data Gowanda, New York Results of Discharge Measurements Buttermilk Creek Basin. Public Water Users of Lake Erie Water in the Vicinity vf Cattaraugus Creek. Uses of Cattaraugus Creek Water Downstream fro m Western New York Nuclear Service Center. Number 2.36c 2.41 3.2 3.5 4.9 4.77 5.37 5.4). 5.42a 5.42b 5.42c 5.43a 5.43b 5.46 5.49 5.51 5.57 6.23 6.3Ea 6.36b 6.36c 6.36d Tables continued Table of Off-Site Well Records Western New York Nuclear Service Center, Cattaraugus County, New York. Summary of Hydrologic and Physical Properties of Tills from Drill Hole 7. Distances from Various NFS Facilities to Surrounding Features. Area Designa~ions. Process Mechanical Cell--Equipment List Summary of Process Stream Flows and Concentrations. Solvent Waste Treatment Schedule for Various Fuels. List of Pul$e Columns. Evaporator Summary. High Level Waste Evaporator Data Sheet. !.ow Level Waste Evaporator Data Sheet. Rework Evaporator Data Sheet. Low Enriched Uranium Product Evaporator Data Sheet. High Enriched Uranium Product Evaporator Data Sheet. General Purpose Evaporator Data Sheet. Process Tanks Radioactive Waste Storage Tanks Basic Design Data. Pump Summary Summary of Sampling Requirements. Accountability Sample Summary. Cold Chemical Makeup Process Sample Summary Analytical Methods Revision 1, Oct. 30, 1964 C C C C Number 4.68 4.73 4.79 4.82 4.85 4.89 C 4.91 4.93 4.96 5.33 5.34 5 , 38 5 , 39a 5.39b 5 , 39 c 5.40a 5.40b 5.43 5 , 48 5 , 53 \ \ \ ' ' \ Tables continued Flow Rates and Concentrations for the Solvent Extraction Processing of all Fuels -Plutonium Cycle. Flowsheet Quantities for Uranium Product Evaporation -All Fuels. Flowsheet Quantities and Concentrations for Plutonium Ion Exchange Treatment. Flowsheet Quantities and Concentrations for Plutonium Product Evaporation. Solvent Waste Treatment Schedule for Various Fuels. Flowsheet Quantities and Concentrations for High-Level Waste Evaporation. Flowsheet Quantities and Concentrations for Low-Level Waste Evaporation. F l owsheet Quantities and Concentrations for Acid Fractionation. List of Waste Storage Tanks. Dissolver Off-Gas Condenser. List of Pulse Columns. Evaporat o r Summary. High-Leve l Waste Evaporator Data Sheet. Low-Level Waste Evaporator Data Sheet. Rework Evaporator Data Sheet. Low-Enr i chment Uranium Product Evaporator Data Sheet. H i gh-Enrichment Uranium Product Evaporator Data Sheet. General Purpose Evaporator Data Sheet. Rad i oactive Waste Storage Tanks Basic Des i gn Data. P uls a f eede r Pumps. \ \ \ \ \ \ \ \ \ ' ' . a I I 1 I I I I -=-=====it==========,:z:ia=-=::=====-================-===-====-==========~~,~ ) Number 5.57 5.59 6.23 6.36a 6.36b 6.60 6.61 6.62 6.67a 6.67b 7.5 7.7 . 7 .8 7 .30 7.39 7.40a 7.40b 7.42 8.25 8.28 Tables continued General Pump Table. Miscellaneous Equipment. Sum~ary of Sampling Requirements. Process Sample Summary. Analyt ical Methods. ' Characterization of Consolidated Edison Feed Stream and Allowance for Future Increased Burnup. Calculation of Planar and Volume Source Strengths. Shielding Design Data Summary. Health-Safety Equipment. Health-Safety Counting Equipment. Assumptions Used in Calculations -Sections lZlI and iIII Maximum Concentration of Gaseous Isotopes Under Inversion and Average Meteorological Conditions . Iodine Deposition and Milk Concentration. Quantities and Concentrations of Sr-90, Cs-137 and Ru-106 at Various Points in the Event of Specified Leakage. Quantities of Iodine Isotopes Formed from 1020 Fissions. Total Dose Due to Radioiodine, Rem/Person Individual and Population Doses at Several Points in Event of a Criticality Incident. Gaseous Activities Lost from Fuel Pool During Assumed Criticality Incident. Thyroid Dose During Recycle Coincident with a Criticality Incident. The Prompt Neutron and Gamma Dose at the Outside of a 8 Normal Concrete Shield From a Nuclear Reaction of 101 Fissions. Number 6.60a 6.60b 6.61 6.62a 6.62b 6.63 6.67a 6.67b 6.93 6.105 6.119 6.120 6.129 6.142 7.5 7.7 7.8 7.31 7.32a 7.32b --------...... _......_..._. .. _____ ._........., _____ ._ ........ .. Tables Continued Gamma Curies of Design Fuel. Gamma Spectrum of Design Fuel. Gamma Spectrum of Design Fuel Assembly. Gamma Spectrum of Fuel Basket. Gamma Spectrum of Solutions in Process Vessels. Shielding Summary. Health-Safety Equipment. Health-Safety Counting Equipment. Summary of Utilities. React~1ity Ratio of Specific Fuels. Ch~racteristics of Various Fuels. Safe Dissolver Canister Diameters for Various Fuels. Safe U-235 Concentrations in Dissolver as a Function of Enrichment and of Boron Concentration where used. Maximum TBP Concentrations for Various Fuels in 10" Columns. t; ' p Assumptions Used in Calculations--Sections VII and VIII. Maximum Concentration of Gaseous Isotopes Under Inversion and Average Meteorological Conditions. Iodine Deposition and Milk Concentration. Quantities of Iodine Isotopes Formed from 1020 Fissions. Total Dose Due to Radioiodines, Rem/Person. Individual and Population Doses at Several Points in Event of a Criticality Incident. Revision i, Oct. 29, 1962 Revision 2, Oct. 30, 1964 #4 Number 7.34 8.27 8.29 9.28 9.32a 9.32b 9.32c 9.35 9.47 9.49a 9.49b 9.97 9.98a 9.98b 9.98c 9.98d Tables Continued Gaseous Activities Lost from Fuel Pool During Assumed Criticality Incident. Thyroid Dose During Recycle Coincident with a Criticality Incident. The Prompt Neutron and Gamma Dose at the Outside of a Normal Concrete Shield From a Nuclear Reaction of 1018 Fissions. Gaseous Activities Lost into Fuel Receiving and Storage Area During Assumed Criticality Incident. Rems Per Calendar Quarter. Maximum Allowable Surface Contamination for West Valley Plant. Maximum Permissible Concentration (mic1*ocuries per milliliter). Maximum Permissible Concentration (m i crocuries per milliliter). Startup Schedule for Air Sampling. Routine Surveys. Environmental Monitoring Phase I Environmental Monitoring Phase II Instrument Functions Maloperation in the Fut ~eceiving and Storage Area (FRS) Maloperation in the Process Mechanical Cell Area (PMC) Maloperation in the General Purpose Cell Area (GPC) Malopemtion in the Chemical Process Cell Area (CPC) Revision 1, Oct. 2 9 , 1962 Revision 2, Oct. 30, 1964 ( ...... L Number 9.99 9.100 9.101 9.102 9.103 9.104 9.105 9.106 9.107 9.108 9.109 9.110 9.111 9.112 9.113 9.114 9.115 9.117 Tables Continued Maloperation and*Corrective Action During Maloperation of Feed Adjustment and Accountability Maloperation of Feed Tank to Partition Cycle. Maloperation of HA Column, Partition Cycle Feed Pump Pots, Meter Head Pot. Maloperation of Plutonium Cycle Feed Conditioner Tank Maloperation of Feed Conditioner to First Uraniu~ Cycle. Maloperation of Second Uranium Cycle Feed Conditioner. Maloperation in Plutonium Purification Cell. Maloperation of Uranium Product Purification. Maloperation of the Product Packaging and Shipping Area. Maloperation Summary of Rework Evaporator System. Maloperation of High Level Waste Evaporator Feed Tank, Evaporator, Evaporator Condenser, and High Level Waste Accountability and Neutralizer Tank. Maloperation of Low Level Waste Evaporator Feed Tank, Evaporator, Evaporator Condenser and Low Level Waste Accountability and Neutralizer Tank. Maloperation of General Purpose Evaporator and Evaporator Condenser. Maloperation of Acid Fractionator Feed Tank, Feed Vaporizer, Bottoms Cooler, Hot Acid Storage Tank, Hot Acid Batch Tank, Acid Fractionator, Acid Fractionator Condenser, Weak Acid Catch Tank and Recovered Acid Storage Tank. Maloperation of Dissolver Off-Gas System. Maloperation of Vessel Off-Gas System. Maloperation of Off-Gas in High Level Waste Storage System. Maloperation of Waste Tank Farm and Consol i dated-Edison Storage System. Solvent Treatment Systems. l l Number 2.4 2.7a 2.7b 2.7c 2.8 2.18a 2.18b 2.19a 2.19b 2.22a 2.22b 2.23 2.34 2.35a 2.35b 2.36a 2.36b Figures Map of Western New York State showing location of Western New York Nuclear Service-Center. Site Boundaries and Topographic Features. Aerial Photograph of the Site. A~rial Photograph of the Northwest Corner of the Site sho~ing the Confluence of the Creeks. Population Density in the Area Surrounding the Western New York Nuclear Service Center. Boring Location Plan Western New Y~rk Nuclear Service Center. Seismic Point Location Plan Western New York Nuclear Service Center. Surfa*ce and Bedrock Profiles of Western New York Nuclear Service Center. Stratigraphic Cross Section of the Western New York Nuclear Service Center Site. Map of Construction Area showing Distribution and Lithology of Surficial Deposits. Generalized Engineering Soil Map of the Western New York Nuclear Service Center. Geologic Cross Sections in the Construction Area. Duration Curves of Daily Flow Cattaraugus Creek at Gowanda, New York. Location of Gaging Stations on Western New York Nuclear Service Center. Comparative Discharges of Butter~ and Cattaraugus Creeks. Public Water.Suppl/ Systems in the vicinity of the Western New York t-luclear Service Center. Location of Wells and Springs used in the Immediate Area of Western New York Nuclear Service Center. .'\ i.. Revision 1, October 30, 1964 I I I l l l f ! ! l ! I l J ' I I ( i * .

• l \ I ' I i 1
• t \ I \ C C Nrnpber 2.37 2.40 2.42 3.la 3.lb 3.4 3.5a 3.5b 3.6a 3.6b 3.6c 3.12a . 3.12b 3.12c 3.13a 3.13b 3.15a Figures Continued Jitte Contours of Water Table on Western New York Nuclear Service Center. Hydrographs of Wells in the Construction Area. Map of Construction Area showing Water Levels and Extent of the Shallow Artesial Aquifer. * . .
• Overall Plot Plan. Plot Plan Process and Disposal Area. Plan of Warehouse.

Perspective Sketch of Process Building. Cutaway Perspectives at Various Levels. General Arrangement--Fuel Receiving and Storage Plan. General Arrangement--Fuel Receiving and Storage Section Sheet 1. General Arrangement--Fuel Receiving and Storage Section Sheet 2. Equipment Arrangement--General Purpose Cell--Plans Equipment Arrangement--General Purpose Section Sheet 1. Equipment Arrangement--General Purpose Section Sheet 2. Equipment Arrangement--Chemical Process Elevation. Equipment Arrangement--Chemical Process Plan Schematic Elevation--Equipment Extraction Cell. Revision 1, Oct. 29, 1962 Revision 2, Oct. 30, 1964 1 Nympar 3.15b 3.15c 3.15d 3.15e 3.15f 3.16a 3.16b 3.16c 3.16d 3.16e 3.19a 3.19b 3.19c 4.9a 4.9b 4.9c 4.21a 4.21b 4.26 figures Continued Title Plans--Equipment Arrangement--Extraction Cell-1 Equipment Arrangement--Extraction Cell 2--Schematic Elevation. Equipment Arrangement--Extraction Cell 2--Plans Equipment Arrangement--Extraction Cell ~--Schematic Elevation. Equipment Arrangeoent--Extraction Cell 3--Plans. Schematic Elevation--Equipment Arrangement--Product Purification Cell. Plans~-Equip.nent Arrangement--Product Pruification Cell. Equipment Arrangement--Uranium Product Cell--Plan and Section. Schematic Elevation--Equiprnent Arrangement--Product Packaging and Shipping. Plans--Equipment Arrangement--Product Packaging and Shipping. Office Building Layout First Level. Office Building Layout Second Level. Office Building Layout Third Level. Process Mechanical Cell--Equi""'9nt List. Process Mechanical Cell--Transverse Section. Mechanical Flow Diagram--Process Mechanical Cell. Plant Flow Diagram of all Process Steps from Dissolution throu9h Product Handling. Schematic Flowsheet for Dissolution and Feed Jdju~ment. Treatment of Dissolver off-Gases. Revision 1, Oct. 29, 1962 Revision 2, Oct. 30, 1964 I l 1 I l t ' i ! i . , . l I t . I Q C I ( Hmnta*r 4.3~ 4.63 4.67a 4.67b 4.73 4.74 4.77 4.81 4.83 4.85 4.87 4~89 5.3 5.5 5.6 5.8a 5.8b 5.9 5.11 5.12a figures Continued r1t11 Schematic of Partition Cycle. Schematic of First U Cycle. Schematic of Second U Cycle. Schematic of Plutonium Cycle. Low*Enriched Uranium Product Evaporation and Final Decontamination Schematic. High Enriched Uranium ~roduct Final Decontamination and Evaporation Schematic. Schematic of Pu Ionex Treatment. Pu Product Evaporation First Solvent Wash Cycle--Typical. Schematic High-Level Waste Evaporation. Schematic Low-Level Wiste Evaporation. Schematic of Acid Fractionator. Schematic of Rework System. Schematic General Purpose Evaporator. 100-ton Fuel Receiving and Storage Crane. Fuel Pool Gate. fuel Pool Storage Baskets. Fuel Pool Storage Can Crane. Fuel Pool Service Bridge. Fuel Storage Rack. Underwater Transfer Conveyor. Fuel Handling Bridge Crane. Revision 1, Oct. 29, 1962 Revision 2, Oct. 30, 1964 Hnmber 5.12b 5.14 5.16 5.19 5.20 5.21 5.23a 5.23b l i 5.25 t 5.26 1 I 5.29 5.30

• I 5.36a ' 5.36b 5.36c 5.37 5.39a 5.39b 5.42a 5.42b 5.42c 5.43a figure, Continued Power Manipulator.

Disassembly s *. Bundle She a r. Pin Shear. Maintenance Table. Ttt,11 Chopped fuel Basket Loading Station. GFC*Power Manipulator. CPC Crane. Leached Hull Dumping and Sampling Station CPC Shielding Door Dissolvers. Silver Reactors Dissolver Off-Gas Scrubber. Dissolver Off-Gas Condenser. Pulse Columns PUlse Column Instrumentation. Decanters. High Level Evaporator. Low Level Waste Evaporator Rework Evaporator. Low Enriched Uranium Product Evaporator. Revision 1, Oct. 29, 1962 Revision 2, Oct. 30, 1964 I I \ G Hwnb*t ~.43b 5.45 5.47 5.50a 5.50b 5.50c 5.50d 5.50e 5.55 5.61 5.62 5.63 6.3a 6.3b 6.3c 6.3d 6.17 6.25 6.26 6.27 6.28 6.31 ( figur1s Continued Title High Enriched Uranium Product Evaporator Plutonium Product Evaporator. Acid fractionator.

---

Radioactive Waste Tanks 80-1 & 80-2. Details--Radioactive Waste Tanks 80-1 & 80-2. Details--Radioactive Waste Tanks 80-1 & BD-2. Plans--Vault fo~ 80-1 & 80-2. Sections and lletails--Vault for 80-1 & 80-2. Section through Waste Storage Tank. Plutonium Ion Exchangers Silica*Ge1 Columns Solvent Wash Columns P & ID Controlled Ventilation System to Elevation 131'. P & ID Controlled Ventilation System Above Elevation 131'. P & ID Process Off-Gas and Vent System. flow P & ID Waste Tank Farm. Off-Gas Stack. Glove Box :ampling ~tations. "C" Type Sample Cell Process Sampling System. Mechanical Flow Diagram--Analytical and Sampling Operations.

Floor Plan and Schedules--Laboratory Area Process Building. Revision 1, Oct. 29, 1962 Revision 2, Oct. 30, 1964 ,.-.. --*...-.--*--

• . , -------6.32 6.47 6.67a 6.67b 6.67c 6.67d 6.67e 6.67f 6.67g 6.142 9.4 9.100 figur1s Continued Tit11 Equipment Arrangement and P & ID's for Analytical cells. Sketch of Jumper. General Locations of Radiation Monitoring and Sampling Systems. General Locations of Radiation Monitoring and Sampling Systems. General Locations of Radiation Monitoring and Sampling Systems. General Locations of Radiation Monitoring and Sampling Systems. General Locations of Radiation Monitoring and Sampling Systems. General Locations of Radiation Monitoring and Sampling Systems. General Locations of Radiation Monitoring and Sampling Systems. Maximum Concentration vs U-235 Enrichment.

Plant Organization Chart HETS Variation With Pulse Amplitude I i ( C Numbt[ 2.36 4.1 4.2 5.2 6.121 6.129 6.135 6.140 6.149 6.153 7.7 7.8 7.32 7.34 a.12 8.25

• 9.13 9.17 Appendices Title Public Water Systems -Supporting Data Process Flowsheets for the Base-Line Fuels. Coanonwealth Edison Fuel Yankee Atomic Electric Fuel Consolidated-Edison Fuel Power Reactor Development, Core Zr-U Alloy Fuel Northern States Power Fuel Cask Acceptance Criteria Equipment List Solid Angle Data for Dissolver Cannisters in Air Calculations in Support of Paragraph 6.129 Calculations for Data in Table 6.135 Calculations in Support of Paragraph 6.140 Calculations in Support of Paragraph 6.149 Calculations in Support of Paragraph 6.153 Atmospheric Dispersion Calculation Iodine Deposition Calculation Iodine Dose Thyroid 1o20 Fissions Calculation Calculation of Criticality Incident in Fuel Pool Recycled Iodine Activity Calculation Iodine Thyroid Dose by Recycling During Criticality Incident Curriculum for Chemical Process Operators and Senior Pro*cess Operators.

Area Radiation Alarm System Film Badge and Dosimeter Monitor~ Protective Clothing and Safety Equipmen~ Station Monitors and Hand and Foot Counters Revision 1, Oct. 29, 1962 Revision 2, Oct. 30, 1964 t Number 9.33 9.36 9.37 9.37a 9.37b 9.39a 9.39b 9.39c 9.40 9.43 9.47 9~49 9.51 9.53 9.56 9.64 9.93 Appendicef! Continued Title Air Sampling and Air Monitoring E~ipment Portable Monitoring Equipment Counting Room Equipment Determination of Beta Emitters in In-Plant Air Samples Determination of Long-Lived Alpha Emitters in In-Plant Air Samples Low Background Co~nting System Determination of Beta Emitters in Perimeter Samples Determination of Alpha Emitters in Perimeter Samples Determination of Radioiodine Exposure Record Cerd Routine Survey Form Experimental Monitoring Program Stack Monitoring System Weather Monitoring Station Stream Guaging and Sampling Fire Brigade Organization Format for Standard Operating Procedures and General Index of Standard Operating Procedures

• t I ' i I ' ( -I INTRODUCTION

[i,11 This document, which consbts of nine sections plus appendices presented In two volumes, represents a description and safety analysis of the Spent Fuel Processing Plant which Nuclear Fuel Services, Inc. wishes to build on the Western New York Nuclear Service Center near Riceville, New York. It Is the purpose of this Introductory section to provide a sunmary of the Information contained In the body of this report. Throughout the report the location of material ts tdenttfted by numbering paragraphs consecutively within each section; in this introduction the nunbering relate9 to the particular section being described. 1.12 Sections II, III, :nz, ll, and lZI describe the site plant, process, equipment, and supporting engineering systems, respectively. These descriptive sections form the basis for the safety analysis contained in Sections ll[[, Protection of the Public, and Section 2III, Protection of Plant Personnel. Section II describes the health and safety programs and the start-up plans for the plan:] :rr** Site *Description Geography 1 : 21 . *: The faci 1 ity wi 11 be located on the Western New York Nuclear Service Center in the Town of Ashford, near Riceville, Cattaraugus County, New York, about thirty miles southwest of Buffalo and will be described as the Riceville Site. The site cont~ins 3,331 acres and the processing plant and waste storage facilities are located 3,000 to 4,000 feet from the nearest site boundary. The site is in the middle of a rural area ,f lcw population density -*an average of 90 persons per square mile within a 25-mile radius. The population has not changed within a 10-mile radius over the past 50 years, and the character of the land and community are such that it should not change materially over the next 15 years. There is no town within 25 miles of the site with a population in excess of 10,000. The nearest village Is Springville, 4-1/2 miles to the north with a population of 3,852, and the nearest major population center is the city of Buffalo, the city limits of which are 26 miles north of the site. The immediate area within four miles around the site ts divided between unusable rugged terrain and level fertile land used for farming. All roads through the . site will be used solely for access purp~ses and will be controlled by the applicant. There is a spur of the Baltimore and Ohio Railroad Company rail r*oad used solely for freight traffic running through the site at a d i stance of 1,800 feet at tts closest point to any facility. 1.22 It ts suggested that the geographical factors are favorable. The exclusion area, as ts demonstrated in Section VII, is more than adequa t e to assure that the health and safety of the public wtll not be endangered by normal operation of the facility*or by any credible* accident. The population density beyond the exclusion area and population L 7 within a radius of 25 miles Is small, thus assuring a minimum exposure of the general public, if as a result of an unforeseen accident, activity should not be contained within the area of tne site. Meteorology 1.23 The area has a mean annual temperature of 4SF, an annual rainfall of 40 inches, and an annual snowfall of 80 to 100 inches. The prevailing wind directions are from the northwest In the winter and fran the southwest in the summer. The area to the northeast and southeast are even more sparsely populated than the average set forth in 1.21 above and the closest major population areas in these directions are approximately 80 miles from the site. The area around the site is seldom subject to persistent stagnant high pressure areas and poor diffusion conditions. Thus, the prevailing wind and diffusion conditions are favorable. Geology 1.24 The plant and the waste storage facilities are located on a plateau between two of the ravines which form tributaries flowing into Buttermilk Creek. The geological structure is bedrock overlain by gla~idi deposits consisting of a permeable glacial till, a much less permeable silty till, with sandy tills and various shales underneath. All layers have good ion exchange capacity for cesium and strontium. Hydrology 1.25 The site is an elongated rolling plain cut by ravines with tributaries leading into Buttermilm Creek. All of the tributaries on the site and, therefore, all ground water on the site feed into Buttermilk Creek within the portion of that creek contained wholly within the site. Applicant thereby has control over all surface drainage for the entire site by its control over Buttermilk Creek. At the site boundary, Buttermilk Creek empties int~ Cattaraugus Creek, which in turn flows into Lake Erie, 39 stream mfles from the site. No cities or villages downstream from the site rely on Cattaraugus Creek for their water supply, and there are no potable water sources or large water supplies in the immediate area of the site. 1.26 of 41 cfs. 358 cfs. Buttermilk Creek supplies dilution water at an average rate Cattaraugus Creek has an average flow ~t the site of 1.27 There are three aquifers on the site. One is in the surficial glacial till. Ground water movement in this formation is from 1 to 2 feet per day. On some parts of the site there is an aquifer located in sandy tills underneath the silty till. This does not exist on the plateau selected for the plant facilities. Finally, there is a deep bedrock artesian aquifer which ts situated well below impermeable layers at the facility location. The silty till, in which the waste tanks and the solid burial will be located, ts not an aquifer -. _, -* ( but 1t Is water saturated. Ground wat!~ movement In this very Impermeable layer Is calculated to be about 5 x 10 ft/day. It Is calculated that It would take about 40,000 years for the high level wastes and 5,500 years for the low level wastes to move through this silty till from the point of sto_rage to the nearest ravine. 1.28 The good Ion exchange capacity of the soil, the slow movement from the waste storage facilities to the ravines, the existence of the ravines, and the fact that all ground water flows to a creek within the site render the site adaptable to an excellent monitoring system and allow excellent control over radioactive wastes stored on the site. Seismology 1.29 Western New York ts an area of low selsmlctty and the danger of earthquakes which might rupture any of the plant~s facilities Is minimal. The nearest feult to the site Is at a distance of 35 to 40 miles, and this Is more properly classified as a minor earth structure rather than a fault. Thus, the site presents no seismological problems. Sumnary 1.210 In sunrnary, the characteristics of the site are such that the health and safety of the public should not be endangered by operation at the site of the NFS chemical processing plant or by the storage of low or high level wastes. The remoteness of the site from population centers, the low population density for 25 miles beyond the site, the large exclusion area, and the meteo*rology, all are favorable factors to assure protection both from normal operation of the facility and from any credible accidents. The hydrology and geology are suitable to permit control of low level and high level wastes unde-normal conditions and In the event of : a: credible accident. The ease of monitoring water movements and exercising necessary controls, If excessive radioactivity developed, ls assured by the special conditions existent on the plateau on which these waste facilities will be located. I[[ *pJant Description 1.31 The plant site area, located in the center of the 3,331-acre exclusion area, contains 500 acres. Both areas will be fenced and conspicuously posted, and access will be controlled. The facilities consist of a process building, a waste tank farm, a waste burial ground, a temporary waste storage lagoon, an office building, and a warehouse. Off ic e Building 1.32 The office building and parking for vtsl~ors and employees ts located at the entrance of the plant site area 4',000 feet f rom the process building and warehouse and 3,000 feet from tlie waste disposal ,. 11 I I I. I I I i 11 I areas. It Is thus remote fran the areas where nuclear materials are handled. Of the approximately 130 employees of the applicant, It Is estimated that approximately 30 will be employed In the office building. Process Building 1.33 The process building Is arranged In a Z with fuel receiving and storage area on one end and purified product removal facilities on the other end. In the middle are the mechanical and chemical process cells. On one side of the center line are offices, laboratories, control room, and related facilities. On the other side are shops, a utility area, and a warm equipment aisle. Fuel Receiving and Storage Area 1.34 The fuel receiving and storage area consists of a primary washdown area Into which the fuel shipping cask Is brought by rail or truck, a cask storage area, a cask decontamination pit, a cask unloading pool, a ruptured fuel Isolation pool, a fuel storage pool, and an underwater process pool. The cask unloading pool Is sufficiently deep to permit a mlnlmun water cover of 11 feet over the longest fuel element contemplated. The fuel storage pool has racks and equipment for handling each type of fuel presently contemplated. The underwater process pool *COnt~lns equipment for doing rough underwater cutting of non-active parts of fuel elements If necessary. Each pool can be segregated by removable gates. The spacing of the fuel and the crane and fuel handling fixtures are designed to prevent accidental crlttcaltty. Mechanical and Chemical Process Cells 1.35 The central processing area consists of a process mechanical cell and a chemical process cell. The mechanical cell ts 16 feet wide by 54 feet long by 24 feet high with wall of 6 feet of ordinary concrete or 4 feet of high density concrete. The primary purpose*of the mechanical cell Is to remove extraneous hardware from the fuel element and reduce It to small pieces (1 tn. to 2*1n.) which can be dissolved In the chemical cell. The area has vl~wtng windows and remotely operated cranes and manipulators. The chemical cell Is 16 feet wide by 107 feet long by 4s feet wide with walls of 6 feet of ordinary concrete. It has a remotely operated crane and periscopes, television, and viewing windows to aid in the use of the crane. All high level radioactive equipment requiring f.requelit maintenance which can be performed remotely Is located In this cell. Both cells are tied Into a central ventilation system. On each side of the central processing area are operating aisles containing most of the lnstrLments and controls. Under these aisles are aisles containing sampling stations. Underneath the In terior operating gallery Is a warm equipment aisle consisting of a series of shielding cubicles located below the floor level of the aisle. The cubicles have removable shield covers which permit ma inance of p1.111ps and other mechanical equipment contained therein. I I , l I I Cl G Product Purification Area 1.36 At a 90 degree angle to the central processing area are the principal production purification and recovGry facilities. After dissolution of the fuel element In the chemical cell to form a process fuel solution, the solutions are put *through a Purex solvent extraction process which separates and recovers uranium and plutonium as nitrate solutions. This Is done In a series of perforated-plate pulse columns which have the necessary equipment for metering, transferring and Intermediate storage-of solutions-. Facflttles

• • for c*lean*up and recycle. of solvent are also Included. Product Hand) Ing Area 1.37 Adjoining the product purlflcatlon area are the product concentrating and packaging areas Including evaporation, Ion exchange and silica gel equipment for concentration, final clean-up and packaging of uranium and plutonium.

The entire production purification and product handling area Is 128 feet Jong by 43 feet high by 16 to 22 feet In width. Warehouse 1.38 The warehouse Is located near the process building and will provide storage space for bulk ctiemlcals and other supplies, bird cages, shipping containers, equipment spare parts, and plutonium product solutions. 1J** Deta i 1 ed : Process : Des er i pt I on Basic Process 1.41 The plant Is a multipurpose plant capable of processing any type of fuel element from.which the fuel proper can be reduced to a nitric acid solution. This Includes all but one of the presently contemplated fuels from private nuclear power plants (graphite maxtrlx fuels). No fuel will be processed before It has been cooled for ISO days. The base line process Is a Purex solvent extraction system. designed for pr_ocesslng of low enriched H02 In stainless steel or zirconium al Joy tubes with a maximum throughput

• • of 1,000 kg of uranium per day. In addition, there wl11 be: 1. A head end dissolution treatment for the dissolution of zirconium clad fuels In HN0 1-HF mixtures, permitting a throughput of 600 kg of zirconium per day. Dissolution Is performed In stainless steel dissolvers with controlled additions of HF and HNO. Aluminum nltrat~ Is added to permit extraction of t.J uranium and to minimize corrosion.

Stainless steel tanlcage Is provided for storing the wastes In acidic condition. I

2. 3. 4. A total dissolution scheme (Darex) for stainless steel cermet fuels. using mixtures of hydrochloric and nitric acids with a throughput of 230 kg of stainless steel per day. Special titanium equipment Is required In this head-end step which contains facilities for dlstlllatlon and recycle of the HCI. The dissolver Is located In a special cell over the process ..... mechanical cell and the rem11lnder of the Darex equipment ts located In a contact-m11lntalned cell adjacent to the first extraction cell. The Darex head-end r nay be replaced with electrolytic dissolution which ts simpler. The use of electrolytic dissolution wl 11 .Introduce no new safety questions. A direct nitric acid chemical dissolution process for aluminum or molybdenum al l oy fuels. A deactivation process prior to dissolution for uranium carbide fuels or for those In which sodium Is present as a bonding agent. Receipt and Storage 1.42 The fu~I Is received In shielded.

water-cooled , casks and Is hosed*down In the primary washdown area. After temperature reading. sampling of cask coolants and purging of gases Into the ventilation system. the cask Is placed underwater In the 44-foot deep unloading pool by a hand-operated overhead crane. The fuel Is removed and placed In storage baskets by remotely-operated equipment and the cask Is ~. transferred to a decontamination pit. The storage baskets are ferred by the storage pool crane to the fuel storage pool and placed In safe geometry racks. Any ruptured elements will be stored In sealed canisters. Hechanlcal

• Processlng 1.43 When the fuel Is ready to be processed.

It Is transferred by the storage pool crane to the underwater process pool fran where I t Is transferred through a conveyor and crane to the process mechanical cell. It I s removed fran the basket by remote equipment and dried. The end hardware Is then cut off and the fuel pushed out of its casing. After in spdction it Is chopped Into small pieces In the bundle shear. This operation Is carried out under an inert atmosphere such as CO2, The resulting pieces of fuel are collected In chopped fuel canisters. If s od ium ts In volved. deactivation of the sodium Is accomplished before removal of the chopped fuel fran the CO2 atmosphere. Then the chopped fuel canisters are removed to the chemical processing cell on a transfer cart through an airlock. -( ( ( I

• ____ ..., __ .,... ___________

"""'!1111 _______ .... .--------------------*-t-==l I --, (_ Chemical Processing 1.44 1-n the chemical processing cel 1, the chopped foel cannisters are placed Into one of the dissolver barrels. Nitric acid and water are metered Into the dissolver from the solution makeup area so that the final solution contains no more than 7.5 grams per liter of U-235, a critically safe concentration In all geometries and quantities. Complete dissolution Is expected to take about 12 hours. The off-gas treatment Includes a down-draft condenser on the dissolver, a secondary condenser, a scrubber , Iodine removal on a silver reactor, and filtration through parallel filters. The off-gas Is then added to the general ventilation system for further filtration before discharge to the stack. 1.45 Vhen the dissolution of the fuel Is canplete, the solution Is cooled and Jetted to a 304-L stainless steel accountability and feed adjustment tank. The dissolver ts then heated to dry off the hulls, which are returned to the process mechanical cell. The hulls are Inspected and packaged and sent to the solid waste storage area. The accountability and feed adjustment tank Is equipped with heating coils, a condenser, air sparger, liquid level and specific gravity measurement, circulating sampler, and temperature measurement. After analysis and adjustment

• of the a>ncentratlon and acidity of the feed, It Is Jetted to the partition cycle feed tank from wht.ch It Is fed to the extraction columns. Solvent Extraction 1.1'6 Solvent extraction Is done by a Purex-type process, which Is performed In the contact process area. The base-line fuel Is put through a partition c ycle, In which a TSP-kerosene solvent Is used to extract the.uranium and plutonium from the feed stream, leaving the bulk of the fission products (:)99.9%)

In an aqueous stream which becomes the major fission product waste stream of the plant. " The plutonium and uranium are also separated In this first extraction cycle Into two separate, partlelly d~conta~lnated, aqueous product streams. These two p r oduct streams a r e then sepa r ately put through additional solvent extract i on cycles to complete the removal of remalnln~ fission products. 1.47 The u r an l un and plutonlun product streams are first collected In the feed conditioner tanks for sampling, analysis, and adjustment of acid concentration. The streams are then put through additional solvent extraction cycles In which the product Is extracted Into an organic phase In one column and ther. returned to an aqueous product stream tn a second colunn. The uranium stream goes through two such cycles and the pluton i um through *one. I I I I .I a I ' 11 I ,! I I l l I I I I I I I I n , . Product Purification and Concentration 1.48 The uranium product stream from solvent extraction Is collected I~ a product evaporator feed tank from which It Is Jetted I nto one of l'WO evaporator tanks for concentration. The condensate Is collected In one tank and the concentrate In another. The concentrate Is subjected to a silica gel treatment for final decontamination. The product Is then placed In one of two sampling tanks, and after sampling and analysis It Is transferred to one of a series of storage tanks. Highly enriched uranium Is drawn from th*** tanks In small quantities and mixed with water to a concentration critically safe for shipment In tank trucks; the low. enriched uranium Is already at an acceptable concentration from a crltl~allty standpoint. 1.49 The plutonium product stream Is collect*~ In an Ion exchange condit i oner tank from which It Is p1111ped Into one of three anion exchange columns for concentration and.final decontamination. It Is eluted from the columns and evaporated In a titanium vessel. The condensate Is pwnped back to th* feed adjustment tank and the concentrate Is collected In one of three plutonium storage tanks, from which It Is packaged for shipment. _All of the packaging and shipping equipment Is enclosed In separately ventilated glove boxes. The shipping bottles are placed In secondary containers and stored In the product storage area I n bird cages awaiting shipment. Solvent Recovery 1.410 The plant Is designed to reuse the TIP-kerosene solvent, wh ich must be cleaned of fission products prior to reuse. To accomplish this, the solvent Is first washed with sodium bicarbonate and then with dilute nitric acid. Ac i d Recovery . 1.411 Alt of the aqueous waste streams wilt contain nitric acid which wltl be recovered to reduce the solid loading on the waste tanks. Acid recovery Is accomplished through the use of two waste evaporators following which the acid Is subjected to an acid fractionation step to concentrate It Into a reuseable condition. Rework System 1.412 All waste streams will be sampled and analyzed prior to being discarded to the waste disposal system. In the event that the product In the waste stream Is above specification, facilities are provided to rework the wastes. They are recycled through a feed tank and a rework evaporator. The bottoms from this evaporator are pumped back to the feed adjustment tank to be subjected to further solvent extract I on. ( C C -** -Waste Hind 11 ng 1.413 Liquid wastes are placed In *tanks designed to contain ap~roxlmately 500,000 gallons each. The tanks are constructed In the *~up-and-saucer" design used at Savannah River. They are operated, however, according to the waste management procedures applied at Hanford. Spare tanks are provided so that wastes may be transferred to another tank should leakage develop. l.414 A general purpose evaporator Is provided In the tank farm area for reducing the volune of low level wastes. It Is backed up by an Ion exchange unit for the condensate. The overhead product Is expected to be water, sufficiently pure to be discarded to Buttermilk Creek. 1.415 High level, solid wastes, such as hulls, wlll be stored In the tank farm area In concret&*llned bins burled In the ground and manltored to assure that no water collects In them. Any seepage wl 1.1 be p1.1nped out and processed In the general purpose ev~porator. Low level solid waste will be burled In the silty till of ~ery low permeab 11 I ty ** I Equipment Description I.SI In this section, all major equipment Is described In detail. In general, the equipment Is classified either by the area In which It Is locat~d or by function. Fuel Receiving and Storage Area 1.52 The equipment In this area Is designed to permit ~nderwater handling by remote control of th& fuel elements and to confine radioactive contamination In the event of ruptured elements. The major equipment pieces are: a. o. c. IOO~Ton crane with two auxiliary 5-ton cranes running on a monor~tl attached to the understde of the main bridge beam. The controls are of a faJl*safe type requiring m~mual operation. Fuel storage pool complex with water deminerallzed before use and continuously ft ltered to maintain Its purity and with cleanup equipment. including a filter, demlnerallzer, and resin add tank. The pool has three smaller pools which can be separated by means of removable gates. Storage baskets perforated for cooling and drainage, made of stainless steel with spacers to prevent movement of fuel In the basket during storage or m6vement. l I d. e. f. g. Ruptured fuel canister, water and gas-pressure tight, to conff*ne radioactive contamination. These are adapted to remote control attachment by the crane and have spacers to prevent movement of the fuel. Movable bridge and 2-ton overhead crane which service the storage pool. Th* crane has* limited verfcal lift to assure minimum water shielding. Storage rack for storage of fuel assemblles In the storage pooL It Is designed to prevent* critical arr*'f of any configuration of any fuel. Underwater conveyor for transfer of storage baskets to the mechanical cell. Th* conveyor Is so designed that only one basket can be handled at a time. It has an endless chain and can be controlled either at the fuel receiving area or at the mechanical c~ll area. Process Mechanlcal Area* . :* 1.S3 Equipment Is provided for the transport, disassembly and chopping of the various fuel elements. Flexible facilities are provided for variations In fuel element construction or other specfal conditions In the fuel bundles. The major equipment pieces are: a. b. c. d. e. Remote handling equipment, fncludfng two fuel handling bridge cranes , a power manipulator and four pairs of master-slave manipulators, one pair of which has extended reach. All operations In this area are carried out remotely by the use of this equfp~nt. Pushout table, Including a pushout ram and* drier for removal o f fuel from basket and dr y ing of fuel. There Is a gas loop I n the dr i er wh i ch Is sampled to assure that the fuel Is d ri ed. The p u sh in g pressure Is controlled by a preset regulator. Rad i al saw .. table on which the ends of the element are sawed off after the element Is positioned In a fuel carrier and on which special cutting can be done ff the fuel cannot be pushed out of I ts casing. Fue l bund l e carriers designed to hold a slngle fuel bundle by means of manipulator-operated clamps. I ns pect i on table with a remotely operated vise, vee blocks, gauge s and o the r devices to hold and measure fuel elements. I (1 c.: ,, C f. g. h. I. J. k. I. Dissolvers Fuel bundle tti!!!:. for choppl_ng the fuel Into pre-selected lengths from' to 2 Inches. The: shear blade Is driven by a hydraulic ram which can develop a 250-ton force. The hydraulic power units for this cutting operation are located In the aisle adjacent to ~he processing cell. Casini shear for chopping casings In pre-selected lengths of 1 to Inches. Fuel pin shear, a portable machine shearing single fuel pins If necessary. Maintenance table for the service and adjustment of In-cell equipment. It Is designed for flexibility In h~ndllng the equipment and Includes pneui1atlc portable harness, nibblers, and other power tools for the manipulator equipment. Deactivation autocla~e cart for transport of the baskets containing the chopped fuel. Tr.ansfer cart used In the alr!ock between the mechanical and chemical cells designed to prevent accidental dropping of the fuel basket and remotely removable for maintenance. Remotely operated shielding door for foyer Into which the manipulator and cranes can be removed for decontamination and maintenance. 1.54 There are four batch dissolvers

three are made of 309 SCb* stalnle~, steel with a nominal capacity-of 2,ooo*gallon~ designed to dissolve 1,000 kg/day uranium as U02; the fourth Is made of titanium for the dissolution of stainless steel by the Darex process. It has a nominal capacl-ty of 1,500 gal Ions designed to dlssolv tt 100 1-h/day of stainless steel. They are designed for remote malnt*n*nce and replacement and a r e Isolated from one another. The tanks are cylindric~)

with a heat i ng co l l near the bott~ and a ~ondenser coll located In a bustle around the top. Each dissolver has a series of appurtenant equ i pment for handling the off*gas from It, Including an off-gas scrubber , a condenser, and a silver reactor. During dissolution, the l i qu i d l evel and density of the solution Is continuously recorded and the system pressure Is recorded and controlled by a PRC In the off-gas l i ne, backed up by a manually*controlled valve. Alarms are prov i ded for high and low liquid level, temperature of solu t ion and off-gas , and off-gas pressure. I I I I I I 1 I I j I Pulse ColUIMS 1.55 Continuous solvent extraction Is effected by 12 pulse columns w!th varying functions. The columns are fabricated from 304-L stainless steel and located In three 6Xtractlon cells. They perform the functions of extraction, partition, stripping and scrubbing. With the exception of two columns, all wlll have cartridges of boron*304*L stainless plates Installed In the enlarged disengaging sections to protect against criticality. Control of the columns Is maintained primarily through control of the effluent from the bottoms of the columns and by control of aqueou s effluent removal and Interface level through sensing pots located near the tops of the columns. Further, the column bottom press~1re, temperature at the top and bottom of the column and specific gravity of the organic effluent are recorded. Evaporators 1.56 Produc_ts and wastes are concentrated In seven evaporators: 2 waste evaporators and 1 rework evaporator designed for remote ance; 2*uranlum and* 1 plutonium product evaporators and I general purpose evaporator, designed for contact maintenance. Each Is designed as an

• Integral package with external rebollers and condensors
• supported from ~he shell of the evaporator.

All are made of 304-L stalnless, except the p I uton I um product evaporator wh I ch. Is to be t I tan I um for corros I on resistance. Acid Fractlonator 1.57 This Is a vacuum unit made. of 304-L stainless and designed for contact maintenance. f*rocess Tanks 1.58 These are of eight basic designs, and have variances Ing CY.i size, location within the plant , and type of maintenance. Radioactive Waste Storage Tanks 1.59 These are of four types: 500,000-gallon tanks for high and low level liquid wastes, 100,000-gallon for Darex wa,~e, 30,000-gallon for depleted uranium, and 60,000-gallon for thorium product. Each Is built In a 4-foot high steel pan and the pan and the tank are enclosed

• In a concrete vault with sufficient earth cover to reduce radiation levels at grade to 1 mr/hr. All plate welds will be fully radlographed and al l tanks have Internal columns to support the tank roof and act as ties for the Internal pressure design. The Darex tanks are of 304-L stainless and are cooled by c ir c ulation of cooling water through two vertical cooling coils. The ~Judge In the high level waste tank Is prevented from settl in g by ag i tation with four air agitators.

Limited access to all tanks Is possible through a shielded plug from grade through the t op of the !ank. a C C I C I .., --** Pumps 1.510 A variety of pumps are used Including positive displacement with and without flow adjustment, canned, centrifugal, and remote head diaphragm pumps. Miscellaneous Equipment 1.511 a. Silica gel columns b. Small column for the final solvent extraction product stream. c. Ion exchange units d. Equipment for solvent washing system. II 11 I iI Engineering Analysis of the Plant 1.61 In this section, the salient features of a number of the engineering aspects of this plant are discussed, including:

a. Ventilation

b. Sampling c. Maintenance

d. Shielding

e. Monitoring

f. Utilities There are also sections which discuss the control of criticality and the possible effects of process maloperation.

Ventilation 1 .62 The plant has four ventilation systems which are separate from one another. These are: {1) the general building ventilation, (2) the process ventilation, (3) the process vessel system, and (4) the dissolver off-gas system. The systems are designed so that: (1) the total volume of air is kept to a minimum, (2) all air entering is mechanically or chemically cleaned to remove particulate matter and fumes, (3) air pressure to limited access areas is less than atmospheric and to process areas at an even lower pressure, (4) normal access openings are ventilated from the less active to the more active area, (5) gases from process and laboratory equipment are segregated to permit special treatment and close monitoring, (6) back-up systems are employed where desirable for reliability a.nd continuity, (7) distribution equipment contains volumetric control, isolation, diversion, and concentration, (8) toxic and radioactive aerosols are kept to a minimum, and (9) final exhaust to the atmosphere is accomplished at sufficient volume to insure dilution of irremovable gases and at sufficient height (202 feet above grade) to assure secondary dilution and adequate distribution to the atmosphere. The total volume of air discharged is 46,000 cfm. Fume hood and radiolaboratory exhaust, the process ventilation system, the various vessels and equipment pieces in the proc~ss area are separately vented to duplicated systems of preheaters, prefilters, absolute filters, and exhauster installations prior to release to the stack. The waste tank f.Jrm vent gas system cor.sists of two glass fiber-packed columns and parallel exhaust discharging to its CMn stack. Each system is separately adjusted automatically and has a spare absorber train with automatic start-up and phase-in. The duplicate systems are isolated by butterfly valves. All of the exhaust fans are connected to the emergency electrical system and will come back into operation within ten seconds and automatically start up if static pressure in an area drops below a preset point or if activity increases beyond a preset point. The entire system may be operated manually if desired. *}}