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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)
Shared Package
ML18081A225	List: ML18081A116; ML18081A222; ML18081A223; ML18081A224;
References
	Download: ML18081A223 (79)
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Appendix 9.9 Curriculum for Proce ss Opera tors and Senio r Proce ss Opera tors A. Chemical Process Opera tors

1. Intro ducti on-fo r all train ees -.

a. Histo ry of plant

b. Site descr iption

c. Prote ction of plant perso nnel

d. Prote ction of publi c

e. Licenses and perm its requi red

f. Purpose of plant

g. Reason for train ing

h. Requirements of train ees

i. Type of train ing

j. Resul ts of ~rain ing

k. Indus trial relati ons

2. Lay nucle ar physi cs and chem istry- for all train ees

a. General descr iption of react ors **

b. Diffe rent types of react ors

c. Nuclear react ors-- broad ly

d. Resul ts of react ions

e. Physi cal descr iption of vario us fuels

f. Signi fican ce of fissio n produ cts and their build up

g. Reasons for recov ery of Source and Fi~si onabl e mater ial

3. Proce ss descr iptio n-for all train ees

~ a. Pictu res of plant

b. Model inspe ction

c. Input mater ial--f orm and conte nt

d. Stepwise handl ing procedure throu gh proce ss

e. End produ ct

f. Pack*aging and shipp ing

g. Waste treatm ent 4o Readi ng-fo r all tr~in ees

a. Schematics

b. Instru ments

c. Defin ition of terms

d. Data recor ding

5. Healt h and Safet y program-for all train ees

a. Elementary radia tion theor y

1. Types of radia tion

2. Radia tion in persp ectiv e

3. Perm issibl e limit s

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 meth1~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. Radi ation goals to be met

3. General policie~ used in meeting these goals

4. Services provide.d by Health & Safety

5. Sunnary

h. Aids t o 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. Radiatio n arithme tic

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. Protecti ve clothing and equipment

o. Fire safety

1. Descript ion of fire systems

2. Fire brigade organiza tion

3. Fire preventi on

p. Safe operatio ns of cranes .and hoists

1. Inspect-ion and preventa tive maintenance .

2. Controls and limit switches

3. Saf e operatin g techniques

q. Safe oper ation of vehicles

1. Heavy equipment

2. Automobiles and light .trucks

3. Snow removal equipment

6. Equipment descript ions and u*es by major area--fo r 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 manipu lation-f or selecti ve trainee s

a. Fuel Receiving and Storage (FRS)

b. General Purpose Cell (GPC)

c. Process Mechanical Cell (PIC)

d. Equipment Decontamination Room (EDR)

e. Chemical Process ing Cell(CPC)

f. Scrap Removal (SR)

a. Chemical process ing steps-f or ~electi ve trainee s

a. Sa...,ling

b. Cold Chemical (CC)

c. Product Packaging and Handling (PPH)

Product Packaging and Shipping (PPS)

d. Acid Recovery (AR)

e. Waste evapor ation

f. Waste tank farm o*perati ons

9. Contro l room ope~at ions-fo r selecte d trainee s To inclucfe all of item 8 plus control l'!)om Qperations

10. Process malope r~tion- *1enera lly broad- -for all trainee s

a. Utiliti es

b. Judgment

c. Other e.g. (flre)

d. Equipment malfunction

11. General decontamination proced ures-~f ~r all trainee s

a. Personnel

b. Equipment

12. Waste treatm ent-for all t~*ainee s except c,,ntrol room trainee s

a. Equipment

b. Low level

c. High level

13. General emergency measur es--for all trainee s

a. Loss from tankage

b. Critic ality emergencies

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 addition1

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.

7.

Somewhat more advanced radioactivity Somewhat aon advanced criticality C

Appendix 9.17 Prote ctive Clothing and Safe ty_Eguipnent nent following is the start up supply of prote ctive cloth ing and equip avail able at the plan t

a. 20 dozen wo:k shir t,

b. 20 dozen pair work trous ers

c. 20 dozen pair cove ralls

d. 5 dozen labor atory coat&

e. 20 dozen pair cloth boots

f. 20 dozen surg ical type cloth hats

g. 5 dozen cloth hoods

h. 24 MSA Ultra Filt~ r Masks

1. 18 MSA Air Line Resp irato rs

j. 12 MSA Air Masks .

k. 12 MSA Face Shie lds

1. 144 MSA Softs ides Goggles

m. 12 MSA Plas tic 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 leath er palm gloves

r. 2 ~., fety harne ss *

s. 3 Stret cher s

t. 3 Fire Blankets

u. 144 Hard Hats

v. 1 pair Safe ty shoes for each production employe~

w. 20 dozen pair shoe covers Maintenance and Inspe ction of Prote ctive Clothing and Equipment Cove ralls , shoe cove rs, gloves and relat ed items of appaand rel will be colle cted ,

monitored, sorte d according to level s of contamination, laundered afte r each days use. Any ct othin g contaminated to grea ter thanNo50attem mrad/hr beta-al. pt will be ganna or 50,000 d/m .alpha will be packaged for burispot check ed after made to launder these items . All cloth ing will be in exce ss of 0.2 laund ering for resid ual contamination. Coratamination mrad/hr beta-ganma or 1000 d/m alpha will requ ire that ed the cloth ing be re-

these leve ls laundered and resur veye d. Items which can not be cleanyedbelow relea sed will *be disca rded . Afte r each use, masks will be surve 100and c/m beta-ganaa.

if contamination leve ls are less than 500 d/m~ lpha and mask s will be If contamination exceeding these leve ls is detec ted, ~e areas will be set aside for spec ial decontamination. The contaminatedof contamination to cleaned by hand, takin g spec ial care to preve nt sp~a d the insid e of the mask. When relea sed, the masks wi-11 be washed in a

, and solut ion of MSA clean er-sa nitiz er, rinse d in clean wate r,leddried sepa ratel y.

packaged in plas tic bags . filte r cani sters will be hand d apar t from Cani sters will be surveyed, cleaned if necessary and storemina tion on the masks. Contamination limit s for non smearable conta cani sters are 100 d/m alpha and 0.2 mrad/hr beta- gann a.

I'.

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AeRtodix 9, 11--

Hand 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 contin-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.

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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.

C 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 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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 hours1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months . 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 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in a C

Appendix 9.33 concen tfftion approaching the ,IQ hour M.P.C. If the concen tration was 10- ~c/cc the first detecto r would see 1100 cpm above background after 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months of collect ion and this would probably cause an alarm in the counting rateme ter. 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 specifi ed in 10 CFR-20.

1-Model AM-2A Fixed Filter Air Particu late Monitor. One ASC-1 alpha scintil lation detecto r with ZnS phosphor. On6 LCRM-2M count rateme ter with one 3 cycle logarithm1c scale of 50-50,000 cpm. Detecto r is shielde d by 2 inches of lead equiva lent. The air pump is a continuous duty positiv e displacement indust rial type driven *by a belt coupled, sealed ball bearing electri c motor. Manually set alarm points with alert and alarm setting s.

Count,.~atemeter output is recorded on a ~j~tinuous strip chart recorde r. Alpha air contamination of 10 ~c/cc and saq>lin g rate of 5 cfm will result in 7 cpm build-u p per hour.

5-Model AM-2A Fixed Filter Air Particu late monitor identic al to the unit describ ed above excer t that the detecto r is a DGM-2 end window GM and the filter holder is modified to accept two filters in series, one particu late and one acti-vated charcoal for collect ion of iodine- 131. A concen tration of 10-lO~ c/cc and a saq>ling rate of 5 cfm will result in 350 cpm build-u p per hour. /

Calibra tion and Maintenance of Continuous Air Monitors All the continuous air monitors will be calibra ted monthly by analyzing the filters in the counting room and comparing the results with the count rate observed at the air monito rs. Response of each unit to radiati on will be apparen t because of the natural activit y filtere d out of the air.

Medical Monitoring Equipment Thyroid Monitor A thyroid monitoring system is availab le for detecti ng iodine~l31 deposit ed in the thyroid . The system is supplie d by Nuclear-Chicago Corpor ation, Des Plaines , Illinoi s and is describ ed belows 1-Model 612 Collimated scintil lation detecto r with 3 inch diamet er by 11-inch thick sodium iodide, thalliu m activat ed

crystal and DuMont 6363 photom ultiplie r; 1-Model 1720 Support Stand with arm. The arm can be automa tically positio ned at any height from 12 to 66 inches above floor level with a reversi ble electri c motor which 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

Appendix 9.36 Portab le Monitoring Equipment Alpha Detecto rs The equipment provided for the detecti on of surface alpha contamination include s four portabl e alpha counte rs and one alpha floor monitor. These instrum ents are supplie d by Eberlin e Instrument Corpor ation, Santa Fe, Hew Mexico, and are as describ ed belows 4-Model PAC-33 Portabl e Gas Propor tional Alpha Counte rs.

Instrument grade propane flows through the probe at 30 cc per minute. The probe has an active surface area of 61 square centim eters. The instrum ent has three ranges, 0-1000, 0-10,000 and 0-100,000 cpm. Phones for aural monitoring and a uranium oxide check source are include d.

I-Model FM-33 Gas Propor tional 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 supplie d for aural monito ring. The unit is mounted on wheels and the probe height from the floor is adjusta ble for 1/8 to 1/4 inches with additio nal adjustment to 2 inches for safe transpo rtation .

Calibra tion and Maintenance of Portab le Alpha Counters The bi-monthly calibra tion procedure for portab le alpha counter s is as*

followsa

a. Check each scale using the calibra ted plutonium-239 sources provided and adjust to the proper respons e.

b. Check the response *of the instrum ent to the uranium check source .

c. Hold the instrum ent probe agains t the radium source contain er and, using the gain adjustm ent, tune out any response to the ganna radiati on.

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

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 base-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 1

Before each use the response of the deep hoJe monitor will be checked using the radium source.

I #! 5

.....,,.,. 9.36 CalUpgtlon ' " " * *. - of lfta-Gzc* Floor llonltor twlce each IIDllth

NlpOIIN of the beta *floor aonlto r wl~l be te1ted uelng beta c ~ eource,.

C

Appendix 9.37 Counting Rooa Eguipll!nt

. j

Appendix 9.37 Counting Room Eguipnent Liquid Scint illatio n Counting System A liquid Scint illatio n counting sy'atem is provided for the detect ion of t~'1tium in samples. The system ia suppli ed by Packar d Instru ment Compa ny, Irie~, La Grange, Illino is. The Model 314-EX2, as suppli ed, includ es the following a 1-Tri-Carb Spectrometer, a two channel unit with two scaler s, red and green, and an electr onic timer. All three units have glow tube decade readou t. Each channel has discri minat or contro ls provid ing separa te channels of pulse heigh t analy sis. Prese t time contro l is in 20 steps from 3 seconds to 100 minutes. Pre!et cougts may be select ed on either scaler in increments from 10 to 10. Preset time and both preset count settin gs intera ct so that whenever any limit is reached the count will stop, 1-Model ~-c Automatic Control Unit and 100 sample automatic changer, with two photo multip lier detec tors, a monitor detect or and an analyz er detect or monitoring the sample well. The automatic changer and detect ors ~re mounted in an eleven cubic foot freeze r for contro lled temperature counti ng. The automatic contro l unit C programs operat ion of the sample changer. Contro ls may be set to count anywhere from 1 to 100 samples and the unit will recycl e continuously if repeat data are requir ed on a batch of samples. The unit may also be set for repeat counting of a single sample. If power failur e should occur while a. count is in progre ss, the contro l unit will clear and ~peat the count autom aticall y when voltag e is restor ed. A manual over-r ide button allows the operat or to select any aample for a specia l count1 1-Model A Digita l Printe r provides a printe d record of counting data on a strip of paper tape._ For each sample, the printe r record s sample number, elapsed time and counts on both scaler s.

In the operat ion of the liquid scinti llatio n counting system, radioa ctive decay events occurr ing in the sample cause scinti llatio ns which are at seen simultaneously by both photo multip lier tubes, giving rise to pulses the phototube outpu t. Pulses front the photomultiplier& pass through

-preamplifier& and into three separate ampli fiers . Pulses from the for "Analyzer" phototube then go to the discri minat or pairs A-Band C-D pulse- heigh t analy sis. The "Monitor" phototube functi ons o~ly to or determine whether a pulse is the legitim ate result of a decay event whether it arises from photo multip lier tube noise. Pulses fallin g between A and Bare fed to the red scaler and pulses fallin g between C and Darepass fed to the green scaler . outpu t pulses from all of the discri minataneou ors through the coincidence circui try and only pulses occurr ing simultof sly in ~oth photomultiplier& are counted. This result s in some loss

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 disinte-gration rate of* an unknown sample may be detel'mined by counting the I

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 dis-integration rate is found from the equations dpm

Counts red x Counts *reen Counts*. coincidence Calibration and**Maintenance of Sample Counters 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

,1pha or beta source dete?1Dine1 l

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.

1

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

l l

I.

f .

Aopenc!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. j

.I 1-Model GR-5 X-Y Spectroaet~r Graphic Recorder. Chart size is 81' 1 inches x 11 inches. Maximum pen speed is 7.5 inches per second.

1-Model Sl)S-18 Slave Decade Scaler with timer. II I

The N.c Model GSS-18 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 cal 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 respc,nse has shifted.

Apptndix 9.37a Plan$ Air Sf !P l**

Detel'llina~lon of !ft a llli tte r1 in In-

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 )

C*

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 3

(400) (~2 x io-l )

4.3 x 10-121'c/ml

.4 with+/- 1~ accuracy.

C

Appendix 9.37b Detellllnatlon of Lonq~Llved Alpha Ealtter1 ln In*Plant Air Sf11Pl**

Appen.d ix 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 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 106 K2 = Milliliters per cubic meter

1o6

. 1 Factor = (.98) (.~) (.70) (2.22 x 168) (108)

Factor *= 1.3 x 10*12 1-LC/ml 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 12 (75) (1.3 x 10* ) = 1.1 x 10*12 pc/ml 86.4 with+/- 10% accuracy.

Appendix 9.39a Low Background Counting System

~

lss

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.

Total cubic 11eter1 of air 1aapled 1

Factor

60 cg a K1 K2 60 Convert, count, per 60 minute, to counts per minute C

Collection efficiency

98*

g

Geometry of counter * ~

a

Ab1orption correction (not app~icable, see Paragraph 9.34) *

d/(m)/(~c):i 2.22 X lo6

Milliliters per cubic meter

1o6 Factor - 1

(60) (.98) (.~) (2.22 X 100} {166)

Factor

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 concentra-tion of beta emitters on a weekly sample isa

,c/ml * (390) (1.5 X l0-14) 604.8

,c/ml

9.9 X 10-15 With t l°" accuracy.

6PPfnclix 9.39c p,te111ination of llpha Eaitter, in Peri9ter Sppl**

l

Apptndix 9.39c C

Dttemination of Alpha Ellitter1 in Peri*ter Sppl**

The concentration of alpha emitter, 11 det~l'lllined. a1 follow11

,c/al * (Net Co';) (Factor)

Net Count* Total count for 60 minutes less 60-minute background count.

Total cubic ..tar, of air 1ampled 1

Factor *. 60 cg a Kl K2 60 Co.,avert1 count, per 60 minutes to counts per minute.

C

Collection efficiency - 9~

g

Geometry of counter

3~

a

Absorption correction - 7~

cJ<*X,c)

2.22 x 1o6

'2

Milltliters per cubic meters

1<>6

. 1 Factor (60) (.98) {.35) {.70) {2.22 X 166) (166)

Factor

3.1 X l0-14

.,.c/ml * (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

- - - - --~ ~

0

+l I

II Appendix 9.43 Exposure Record Card

. Badie Readino Ezposed Dosimeter. :Readings Total From - To M T w T F ' s s Total G B N .Total Becorded For Body Status Prev. Total IThi, Card Ikc. Dose 15 (n-18) Unused Do.,e Bad&e I Name (Last, First. Middle) Is. s. Number Birth Date Nuclear Fuel Servi~ Inc.

West Vallq, New York f

I I

~

j

_.,....,,, . .___ .__ ......... _---..--=-.....-......--~--"--'\ ........_.~,,~***~~..__ . . . . . .__.w.,,.......- -"" ..._ \:

App_en.dix 9. 47 Routine Survey Form - I I

I

(

~~~--------- _ --- ------------

Appendix 9.47 Routine Survey Form ROUlINE SURVEY LOO NUCLEAR FUEL SERVICES, Itc.

SPENT FUEL REPR(X;ESSING PLANT Survey Numbers Shift Assigned1 Frequency1 Time Allotted:

Titla1 MATERIALS AND EQUIPMENT REQUIRED1 DESCRIPTION OF SURVEY1 SPECIAL SAFETY INSTRUCTIONS1 PREPARED BY1 REVISED BY1 DATE1 C

... - ........... --...-. '-.,....._ .....,. .-.---* ....._R _ _...,,_ _ _ _._ _ _ _ _ ........~ *-- - - - ~ - ~ . - - , - - . , ; - -

Appendix 9.49 Environmental Monitoring Program

--~========::=:=:=:::S:=::-::-=:*= --- -=w=*::-:::-::* -*- -*~......-~---------*~.., . . . .--.. -=--

-===-=

Appendix 9.49 Environmental Monitoring Program Phase I - Atmospheric Monitoring Three air-sa mplin g statio ns have been establ ished at the site perim eter.

These statio ns consis t of a vacuum pump drawing air through a filter , a beta-gamna detect or to measure the activi ty depos ited on the filter , a log-co unt ratem eter and strip- chart record er to provid e a permanent record of activi ty at each locati on. These air monito rs are servic ed weekly.

One air-sam pling statio n has been establ ished near the plant site. This statio n will consis t of a vacuum pump pullin g air through a filter paper to collec t partic ulates . The filter will be changed and monitored weekly for gross alpha and gross beta activi ty.

Water Monitoring A rain and snow collec tion statio n has been establ ished at the plant site.

Samples of water from this *statio n are coliec ted and monitored as availa ble for gross alpha and gross beta activi ty, iodine -131, and stront ium-9 0.

Surfac ~ water samples and mud and silt samples are collec ted monthly and moni tored for gross alpha and gross beta-ganuna activi ty. Samples will be collec ted from the follow ing locati ons:

1. Erdman Brook near Butter milk Creek;

....I

2. Butter milk Creek near the Emerson Road crossi ng;

\

3. Cattar augus Creek near the Nagel Road crossi ng.

A well water sample is obtain ed from the site monthly and monitored for gross alpha and gross beta-ganuna activi ty.

Earth and Biota Monitoring Veget ation samples are collec ted near the three perim eter monito ring statio ns in the spring and fall and will be monitored for gross alpha, gross beta-gamma, iodine -131, and stront ium-9 0.

A milk sample is collec ted from a neighboring farm weekly and is monitored for gross beta-gamma. Samples collec ted. once each month are analyzed for iodine -131 and stront ium-9 0.

In the spring and fall a rabbi t or other small game from the site will be analyz ed for gross beta, gross alpha and iodine -131 activi ty.

Phase II - Atmospheric Monitoring The three air-mo nitorin g statio ns at the site perim eter, as descri bed in Phase I, will be used and servic ad weekly.

J

-- -..... ~. --**"-*-

.., ~-.,................ --....... ...-: ..._..,________,....-.-..,_____........-.._. __*-*-*....__*----

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 deter-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 Appendix 9.51 Stack Monitoring System C

-.. __....,........._._.....~,--.-,..............._._,_..._ .............,._.....,..,........ __~------ __ _____ _ ..---- I

.._,, .. -~ ~

Appendix 9.51

Stack Monitoring System 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 provi-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 pro-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 9.5 1 1-Model RM-20BS Pre cis ion Log Ratemeter, des crib ed above plu s a ~pectrometnr inpide nti cal to the RM-20B dis crim ina tion . Window width adj ust abl eut cir cui t for pul se hei ght per cen t and thr esh old adj ust abl e from 5 from 2 per cen t to 100 ful l sca le. per cen t to 100 per cen t of 1-De Var Ser ies R 300 two-pen rec ord er, to rec ord out put from par tic ula te and Con rad trol Room Panel mounted to alarm if count rat e of eit her uni t exc ioio din e sta ck monitors and eeds tte pre set lev el.

The beta-ga11111a par ticu late mo nito r, wit h the det ect or, has a background of abo ut two inc hes of lea d shi eld ing around background is obt ain ed at a con cen trat ion25 cpm. A counting rat e of twi ce

~c/ cc of mixed fiss ion pro duc ts. in the sta ck of about 1 x ~o- 11 The Ganrna Sci nti lla tio n Detect or, wtt around the det ect or, has a backgroundhofthr ee inc hes of lea d shi eld ing thr esh old of 100 kev. The det ect or wil l about 175 cpm for a counting of 30 minutes to a concen tra tio n of 10-10 show 100 net cpm aft er an exposure

~c/ cc of iod ine -13 1.

Ca lib rat ion and Maintenance of Sta ck Mo nitor The response of the sta ck par ticu late mo app are nt from nat ura l act ivi ty as we ll asnitor to rad ioa ctiv ity wil l be which wil l be trap ped by the fil ter pap act ivi ty from the sta ck air stream mo nito r, rel ati ng det ect or cou nts per miner. Ca lib rat ion of the par ticu late in the air ~tream, wil l be accomplished ute to mic roc urie s per mi llil ite r in the cou ntin g room and comparing the res by ana lyz ing a sec tion of the fil ter by the sta ck sampler. Aft er the ini tia l ult s to the count rat e ind ica ted made only as the need is ind ica ted but notcal ibr atio n, thi s check wil l be les s tha n twi ce ann ual ly.

The iod ine monitor wil l be cal ibr ate qua cha rco al fil ter in the cou ntin g roomdand rte rly by ana lyz ing the act iva ted count r~t e ind ica ted by the sta ck sample com paring the res ult s wit h the cha rco al fil ter wil l be checked by _col lecr. The col lec tio n eff icie ncy of the independent of the sta ck monitor and com tin g a cau stic scr ubb er sample of the cha rco al fil ter . Thi s check wil l paring the res ult s wit h the act ivi ty pap er rec eiv ed. be made ~n each bat ch of fil ter

-.*-----, -----~---* . . .-=-.,.--*---....,.-*-*-..------:-----::-----.------...~

Appendix 9.53 Weather Monitoring Station l

I

I!

Appendix 9.53 Weather Monitoring Station Two weather-monitoring station s are provided, one at 10 feet and the second at 200 feet above ground level. Each station continu ously records wind directi on, velocit y, and ambient temper ature. The weather-monitoring station s are .

supplie d by Science Associ ates, Princet on, New Jersey and each station consis ts of the followings 1-No. 4-120 Aerovane transm itter, a combined anemometer and wind vane in one unit. A three-b laded plastic rotor with a ~tartin g speed of 2.5 mph drives a magneto which genera tes a v~ltage di~ectl y propor tional to wind speed. The stream lined vane houses a synchro whose rotor positio n is determined by the vane. The transm itter include s a filter to preven t radio interfe rence and is permanently lubrica ted.

1-No. 4-141-5 Aerovane Recorder provide s instant aneous readou t of wind directi on and velocit y on the same chart. Directi on 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 recordi ng area is 4i inches wide.

1-No. 170 Stainle ss Steel sheathed temperature bulb and temperature record er. Recorder is two pen with range of-50 to 110 Fin one degree

) divisio ns. The temperatures from both station s record on one chart.

1-No. 174 Aspira ted Solar Radiati on 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 orlante d baffle. A motor and blower, located at the remote end of the mounting al'lll, induce a forced ventila tion.

Tho recordi ng charts for the two weather station s are located in the Control

Room Panel.

APPfndlx 9. ~ .

Stre.. Gauging and Sf!Pllnq

tne 91ua1ng ,oc1 s Statio ns are piovlclecl for gauging and 1aapling the flo,, of Frank* Creek and Cattaraugu1 Creek.

v* l'lle gauging statio n, each consi1t of a calibr ated*l evel detect or and con-

. tinuou1 record er.

The ia1111Pling statio n, Nch con1i1t of a proportioning pu11p to take a aaxliiull 1ize 1111ple of 10 gallon , per ...1c*. The saapl en are each houNd

1n an electr ically heated, **ther proof enclo 1un. . .

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 Da*.,e Name Draf t No.

1. Purpose - (Merely a repe titio n of title .)

2. Scope

a. Area

b. Major Equipment

c. Star tup

d. Ope ratio ns

e. Shutdown

3. General

a. Crit eria of Ope ratio ns (fun ctio ns), e.g. Batch, Surg Tank, F.eed Tank, etc. e

b. Inte rfac ial Effe cts, i.e. Equipment on Upstream and strea m Side of Subj ect Equipment Down-

4. Spec ial Prec autio ns

a. Adm inist rativ e - Need for approval of Shif t Sup~ rviso

b. Crit ical ity r

c. Acco unta bilit y

5. Proc ess Streams

a. Influ ent

b. Effl uent (overflows inclu ded)

6. Ope ratio ns

a. Star t Up

b. Operate

c. Shut Down . .

d. Regenerate

e. Emergency Procedures

7. References

l - , t1<Stf/

.. \. :,,.... .. .*. 5p:-~_Ql *.. ~

tld..,,. . I~~I- II S A !=' E T V A N A L Y S I S ~)V {){,r q SPENT FUEL PROCESSING PLANT Part B of

,C I License Application Volume I Copy No . 79 NUCLEAR FUEL SERVICES, INC.

July 1962 C

,. .'., 1 7 3 .JL-

..._.-e m -*=--=,===+

I I

I Section CONIENIS Paragraph Numa,~

I . INTRODOCTION II SITE DESCRIPTION Summary 2.1

Geography 2.4 Meteorology 2.11 Geo.logy 2.15 .

Hydrology 2.33 Seismology 2.46 Environmental Survey 2.49 III PLANT DESCRIPTION Plot Plan 3.1

Process Building 3.5 IV PROCESS DESCRIPTION Fuel Receiving and Storage 4.2 Mechanical Handling: 4.9 Dissolution 4.21 Feed Adjustment 4.34 Solvent Extraction--Partition Cycle 4.35

-*. Solvent Extraction--First Uranium Cycle 4.52 Solvent Extraction--Second Uranium Cycle 4.57 Solvent Extraction Column--

Plutonium Cycle 4.63 Product Purification and Concentration 4.67 Solvent Recovery 4.76 Acid Recovery 4.80 Rework System 4.87 Waste Handling 4.88 V EQUIPMENT DESCRIPTION Fuel Receivi~g and Storage 5.3 Mechanical Handling 5.12 General Purpose *cell 5.21.

Dissolvers 5.30 Pulse Columnt 5.37 Evaporators 5.41 Acid Fractionator 5.47 Process Tanks 5.49 Radioactive Waste Storage Tanks 5.50 Pumps 5.57 Miscellaneous Equipment 5.61 Revision 1, October 3Q, 1964

CONTENTS Continued C

Section Para<<;Jrapb Number VI ENGINEERING ANALYSIS OF THE PLANT Introduction 6.1 Summary 6.2 Ventilation 6.3 Sampling and Analysis 6.22 Maintenance 6.37 Shielding 6.59 Monitoring System 6.66 Utilities 6.93 Criticality 6.103 VII PROTECTION OF THE PUBLIC Summary 7.1 Normal Operations 7.6 Stack 7.6 Waste Storage Tanks 7.10 Storage Lagoon 7.11 Burial Ground 7.14 Egress of Personnel or Material 7.18 Product Shipment 7.21 Conclusion 7.22

-~- Abn~rmal Operations Loss from High-Level Waste Tank Leakage from waste tank 7.23 7.24 7.29 Criticality Incident anywhere in the Plant 7.30 Criticality Incident in Fuel Pool 7.33 Chemical Explosioo 7.35 Failure of Iodine Removal Equipment 7.36 Conclusion 7.37

. VIII PROTECTION OF PLANT* PERSONNEL Design Criteria 8.1 Protectio~ from Extern~! Radla~1on 8.4 Inhalation 8.10 Ingestion 8.14 Analysis of Accidents 8.20 Tank f<upture 8.21 Criticality Incident in Plant 8.24 Criticality Incident in Fuel Pool S.29 Chemical Explosion 8.30 Failure of Ioding Removal Equipment 8.32 Minor Accidents 8.33 Summary 8.34 Revision 1, October 30, 1964

/-

.( ._.

I --

I CONTENTS continued Section .e.a.i:as,raph Number IX PLANT OPERATION Orga nizat ion 9.1 Adm inistr ation

9.4 Train ing of Plan t Perso nnel 9.9 Train ing of Outs ide Orga nizat ions 9.12 Heal th and Safe ty Program 9.13 Emergency Proce dures 9.64 Plant Maintenance Program 9.68 Prod uctio n Department 9.86 Proce ss Malo perat ion 9.97

\

Revi sion 1, October 26, 1964

Tables Number 2.8 Total Population and that of Towns, Villages, and Cities within successive 5-mile Radii of the Western New York Nucle&r Service Center.

2.lla Mean Temperatures in Western New York.

2.llb Mean Precipitation in Western New York.

2.llc Mean ~~nwfall in Western New York.

2.14 Probable Wind Roses and Diffusion Parameters for the New York Nuclear Service Center.

2.19 Estimated Rock Section Underlying the Western New York Nuclear Service Center.

2.27 Chemical Analyses of Glacial Deposits.

Ion Exchange Capacities and pH of a numbe1 of Soil Samples.

2.2:>a Mechanical Analysis Plus pH of Eight Selected Samples.

c: 2.29b 2.29c Cesium Sorption of New York Soil Samples.

Cesium Sorption on N~w York Soil Samples.

2.30a Strontium Sorption on New York Soil S~mpl es.

2.30b Strontium Sc,rption on New York Soil Samples.

2.30c Strontium Sorption on New York Soil Samples.

2.31 Ruthenium Sorption on New York Soil Samples.

2.32 Approximate Mineralogical Content of New York Soil Samples.

2.34 Fifteen-Year Summary of Cattaraugus Creek Flow Data Gowanda, New York 2.35 Results of Discharge Measurements Buttermilk Creek Basin.

2.36a Public Water Users of Lake Erie Water in the Vicinity vf Cattaraugus Creek.

2.36b Uses of Cattaraugus Creek Water Downstream from Western New York Nuclear Service Center.

Tables C continued Number 2.36c Table of Off-Site Well Records Western New York Nuclear Service Center, Cattaraugus County, New York.

2.41 Summary of Hydrologic and Physical Properties of Tills from Drill Hole 7.

3.2 Distances from Various NFS Facilities to Surrounding Features.

3.5 Area Designa~ions.

4.9 Process Mechanical Cell--Equipment List Summary of Process Stream Flows and Concentrations.

4.77 Solvent Waste Treatment Schedule for Various Fuels.

5.37 List of Pul$e Columns.

5.4). Evaporator Summary.

5.42a High Level Waste Evaporator Data Sheet. C 5.42b !.ow Level Waste Evaporator Data Sheet.

5.42c Rework Evaporator Data Sheet.

5.43a Low Enriched Uranium Product Evaporator Data Sheet.

5.43b High Enriched Uranium Product Evaporator Data Sheet.

5.46 General Purpose Evaporator Data Sheet.

5.49 Process Tanks 5.51 Radioactive Waste Storage Tanks Basic Design Data.

5.57 Pump Summary 6.23 Summary of Sampling Requirements.

6.3Ea Accountability Sample Summary.

6.36b Cold Chemical Makeup 6.36c Process Sample Summary 6.36d Analytical Methods C

Revision 1, Oct. 30, 1964

. a I

\

\ \

C \

\

Tables \

\

continued \

\

Number \

4 . 68 Flow Rates and Concentrations for the Solvent Extraction Processing of all Fuels - Plutonium Cycle.

4 . 73 Flowsheet Quantities for Uranium Product Evaporation - '

All Fuels .

4 . 79 Flowsheet Quantities and Concentrations for Plutonium Ion Exchange Treatment.

4 .82 Flowsheet Quantities and Concentrations for Plutonium Product Evaporation.

4 .85 Solvent Waste Treatment Schedule for Various Fuels.

4 .89 Flowsheet Quantities and Concentrations for High-Level Waste Evaporation .

4 . 91 Flowsheet Quantities and Concentrations for Low-Level C Waste Evaporation .

I 4.93 Fl owsheet Quantities and Concentrations for Acid Fractionation . 1 4 . 96 List of Waste Storage Tanks.

5 . 33 Dissolver Off-Gas Condenser.

5 . 34 List of Pulse Columns . I I

I 5 , 38 Evaporator Summary .

5 ,39a High- Leve l Waste Evaporator Data Sheet.

5. 39b Low-Level Waste Evaporator Data Sheet .

5 ,39c Rework Evaporator Data Sheet .

5 . 40a Low-Enr ichment Uranium Product Evaporator Data Sheet.

5 .40b High-Enrichment Uranium Product Evaporator Data Sheet.

5 .43 General Purpose Evaporator Data Sheet.

5 , 48 Rad ioactive Waste Storage Tanks Basic Des ign Data.

5 ,53 Pulsaf eede r Pumps .

-=-=====it==========,:z:ia=-=::=====-================-===-====-==========~~,~

I

Tables continu ed Number 5.57 General Pump Table.

5.59 Miscell aneous Equipment .

6.23 Sum~ary of Sampling Requirements.

6.36a Process Sample Summary.

6.36b Analyt ical Methods.

6.60 Charac terizati on of Consol idated Edison Feed Stream and Allowance for Future Increas ed Burnup.

6.61 Calcula tion of Planar and Volume Source Strengt hs.

6.62 Shieldi ng Design Data Summary.

6.67a Health- Safety Equipment.

6.67b Health- Safety Counting Equipment.

7.5 Assumptions Used in Calcula tions - Section s lZlI and iIII 7.7 Maximum Concen tration of Gaseous Isotope s Under Inversi on and Average Meteor ologica l Conditi ons .

. 7 .8 Iodine Deposi tion and Milk Concen tration.

7. 30 Quanti ties and Concen trations of Sr-90, Cs-137 and Ru-106 at Various Points in the Event of Specifi ed Leakage.

7.39 Quanti ties of Iodine Isotope s Formed from 1020 Fission s.

7.40a Total Dose Due to Radioio dine, Rem/Person 7.40b Individ ual and Popula tion Doses at Several Points in Event of a Critica lity Inciden t.

7.42 Gaseous Activi ties Lost from Fuel Pool During Assumed Critica lity Inciden t.

8.25 Thyroid Dose During Recycle Coincid ent with a Critica lity Inciden t.

8 . 28 The Prompt Neutron and Gamma Dose at the Outside of a Normal Concre te Shield From a Nuclear Reactio n of 101 8 Fission s .

)

-- ~~ ...... _......_..._... _____._........., _____ ._. ....... t; ' p #4 Tables Continued Number 6.60a Gamma Curies of Design Fuel.

6.60b Gamma Spectrum of Design Fuel.

6.61 Gamma Spectrum of Design Fuel Assembly.

6.62a Gamma Spectrum of Fuel Basket.

6.62b Gamma Spectrum of Solutions in Process Vessels.

6.63 Shielding Summary.

6.67a Health-Safety Equipment.

6.67b Health-Safety Counting Equipment.

6.93 Summary of Utilities.

6.105 React~1ity Ratio of Specific Fuels.

6.119 Ch~racteristics of Various Fuels.

6.120 Safe Dissolver Canister Diameters for Various Fuels.

6.129 Safe U-235 Concentrations in Dissolver as a Function of Enrichment and of Boron Concentration where used.

6.142 Maximum TBP Concentrations for Various Fuels in 10" Columns.

7.5 Assumptions Used in Calculations--Sections VII and VIII.

7.7 Maximum Concentration of Gaseous Isotopes Under Inversion and Average Meteorological Conditions.

7.8 Iodine Deposition and Milk Concentration.

7.31 Quantities of Iodine Isotopes Formed from 1020 Fissions.

7.32a Total Dose Due to Radioiodines, Rem/Person.

7.32b Individual and Population Doses at Several Points in Event of a Criticality Incident.

Revision i, Oct. 29, 1962 Revision 2, Oct. 30, 1964

Tables Continu ed Number 7 . 34 Gaseous Activi ties Lost from Fuel Pool During Assumed Critic ality Inciden t.

Thyroid Dose During Recycle Coincid ent with a Critica lity Inciden t.

8.27 The Prompt Neutron and Gamma Dose at the Outside of a Normal Concre te Shield From a Nuclea r Reactio n of 1018 Fission s.

8.29 Gaseous Activi ties Lost into Fuel Receivi ng and Storage Area During Assumed Critica lity Inciden t.

9.28 Rems Per Calend ar Quarte r.

9.32a Maximum Allowable Surface Contam ination for West Valley Plant.

9.32b Maximum Permis sible Concen tration (mic1*ocuries per millili ter) .

9.32c Maximum Permis sible Concen tration (mi crocuri es per millili ter).

9.35 Startup Schedu le for Air Sampling.

9.47 Routine Survey s.

9.49a Environ mental Monito ring Phase I 9.49b Environ mental Monito ring Phase II 9.97 Instrum ent Functio ns 9.98a Malope ration in the Fut ~eceivi ng and Storage Area (FRS) 9.98b Malope ration in the Process Mechanical Cell Area (PMC) 9.98c Malope ration in the Genera l Purpose Cell Area (GPC) 9.98d Malope mtion in the Chemical Process Cell Area (CPC)

Revisio n 1, Oct. 29 , 1962 Revisio n 2, Oct. 30, 1964

Tab les Continued Number 9.9 9 Ma lop erat ion and *Co rrec tive Action During Ma lop erat ion of Feed Adjustment and Acc Dis solu tion -

oun Ma lop erat ion of Feed Tank to Par titi on Cyc tab ility Tank-le.

9.1 00 Ma lope rati on of HA Column, Par titi on Cycle Meter Head Pot . Feed Pump Pot s, 9.101 Maloperation of Plutonium Cycle Feed Con diti one r Tank 9.10 2 Ma lop erat ion of Feed Con diti one r to Fir st Uraniu~ Cycle.

9.1 03 Ma lope rati on of Second Uranium Cycle Feed Con diti one r.

9.1 04 Ma lope rati on in Plutonium Pur ific atio n Cel l.

9.1 05 Ma lope rati on of Uranium Pro duc t Pur ific atio n.

9.1 06 Ma lope rati on of the Pro duc t Packaging and Shipping Area.

9.1 07 Ma lope rati on Summary of Rework Eva por ator System.

( 9.1 08 Ma lop erat ion of High Level Waste Eva por ator

...... Eva por ator , Eva por ator Condenser, and High Feed Tank, Acc oun tab ility and Neu tral izer Tank. Level Waste 9.1 09 Maloperation of Low Level Waste Eva por ator Eva por ator , Eva por ator Condenser and Low Lev Feed Tank, Acc oun tab ility and Neu tral izer Tank. el Waste 9.1 10 Maloperation of General Purpose Eva por ator Condenser. and Eva por ator 9.11 1 Maloperation of Acid Fra ctio nat or Feed Tan Vap oriz er, Bottoms Coo ler, Hot Acid Sto rag k, Feed Acid Batch Tank, Acid Fra ctio nat or, Acid Fra e Tank, Hot Condenser, Weak Acid Catch Tank and Recove ctio nat or Sto rag e Tank. red Acid 9.1 12 Ma lope rati on of Dis solv er Off-Gas System.

9.1 13 Ma lope rati on of Ves sel Off-Gas System.

9.1 14 Ma lope rati on of Off-Gas in High Level Was te Sto rag e System.

9.1 15 Ma lope rati on of Waste Tank Farm and Consoli Sto rag e System. date d-E diso n L 9.1 17 Sol ven t Treatment Systems.

Figures Number 2.4 Map of Western New York State showing location of Western New York Nuclear Service- Center.

2.7a Site Boundari es and Topographic Features .

2.7b Aerial Photograph of the Site.

2.7c A~rial Photograph of the Northwest Corner of the Site sho~ing the Confluen ce of the Creeks.

2.8 Populati on Density in the Area Surround ing the Western New York Nuclear Service Center.

2.18a Boring Location Plan Western New Y~rk Nuclear Service Center.

2.18b Seismic Point Location Plan Western New York Nuclear Service Center.

2.19a Surfa*ce and Bedrock Profiles of Western New York Nuclear Service Center.

2.19b Stratigr aphic Cross Section of the Western New York Nuclear Service Center Site.

2.22a Map of Construc tion Area showing Distribu tion and Litholog y of Surficia l Deposits .

2.22b Generali zed Engineer ing Soil Map of the Western New York Nuclear Service Center.

2.23 Geologic Cross Sections in the Construc tion Area.

2.34 Duration Curves of Daily Flow Cattarau gus Creek at Gowanda, New York.

2.35a Location of Gaging Stations on Western New York Nuclear Service Center.

2.35b Comparative Discharg es of Butter ~ and Cattarau gus Creeks.

2.36a Public Water .Suppl/ Systems in the vicinity of the Western New York t-luclear Service Center.

2.36b Location of Wells and Springs used in the Immediate I Area of Western New York Nuclear Service Center. I l .'\ l l

i. .

~ Revision 1, October 30, 1964 ll f

Figures

\

Continued Nrnpber Jitt e 2.37 Contours of Water Table on Western New York Nuclear Serv ice Cent er.

2.40 Hydrographs of Wells in the Con struc tion Area.

2.42 Map of Con struc tion Area showing Water Levels and Exte of the Shallow Arte sial Aqu ifer. * . nt 3.la Ove rall Plot Plan .

l 3.lb Plot Plan Proc ess and Disp osal Area.

I 3.4 Plan of Warehouse.

lJ 3.5a Pers pect ive Sketch of Proc ess Buil ding .

'I 3.5b Cutaway Pers pect ives at Various Leve ls.

I

( 3.6a General Arrangement--Fuel Receiving and Stor age Area --

i.

Plan .

C 3.6b General Arrangement--Fuel Receiving and Stor age Area ---

Sect ion Shee t 1.

l\ 3.6c General Arrangement--Fuel Receiving and Stor age Area--

Sect ion Shee t 2.

I' 3.12 a

. 3.12 b Equipment Arrangement--General Purpose Cell --Pla ns Equipment Arrangement--General Purpose Cell --

I i

Sect ion Sheet 1.

1 3.12 c Equipment Arrangement--General Purpose Cell --

t Sect ion Shee t 2.

\

I 3.13 a Equipment Arrangement--Chemical Process Cell --

Elev ation .

3.13 b Equipment Arrangement--Chemical Process Cell --

Plan 3.15 a Schematic Elevation--Equipment Arrangement--

Extr actio n Cell .

C Revi sion 1, Oct. 29, 1962 Revi sion 2, Oct. 30, 1964

figures l

Continued 1 I

Nympar l Title t

3.15 b Plans--Equipment Arra ngem ent- -Ext ract ion Cell -1 i' 3.15 c Equipment Arra ngem ent- -Ext ract ion Cell 2--S chem atic Elev atio n. i.,.

3.15 d Equipment Arra ngem ent- -Ext ract ion Cell 2--P lans 3.15 e Equipment Arra ngem ent- -Ext ract ion Cell ~--Schematic Elev atio n.

3.15 f Equipment Arra ngeo ent- -Ext ract ion Cell 3--P lans .

3.16 a Schematic Elevation--Equipment Arrangement--Product Pur ific atio n Cel l. l 1 3.16 b Plans~-Equip.nent Arrangement--Product Pru ific atio n Cel l.

3.16 c Equipment Arrangement--Uranium Product Cell --Pl an Sec tion . and 3.16d Schematic Elevation--Equiprnent Arrangement--Product Packaging and Ship ping .

3.16 e Plans--Equipment Arrangement--Product Packaging and Ship ping .

3.19 a Offi ce Buil ding Layout Firs t Lev el.

3.19b 3.19 c Offi ce Buil ding Layout Second Level.

Offi ce Buil ding Layout Thir d Lev el.

It 4.9a Process Mechanical Cell --Eq ui"" '9nt List .

4.9b Proc ess Mechanical Cell --Tr ansv erse Sec tion .

4.9c Mechanical Flow Diagram--Process Mechanical Cel l.

4.21 a Plan t Flow Diagram of all Process Step s from Diss olut throu9h Product Han dlin g. ion I

4.21b Schematic Flowsheet for Diss olut ion and Feed Jdju ~me nt.

4.26 Treatment of Diss olve r off- Gas es.

Revision 1, Oct. 29, 1962 Rev ision 2, Oct. 30, 1964 I

figures Continued Hmnta*r r1t11 4.3~ Schematic of Parti tion Cycle .

Schematic of First U Cycle.

Schematic of Second U Cycle .

4.63 Schematic of Plutonium Cycle.

4.67a Low* Enriched Uranium Product Evaporation and Final Decontamination Schematic.

4.67b High Enriched Uranium ~roduct Final Decontamination and Evaporation Schematic.

4.73 Schematic of Pu Ionex Treatment.

4.74 Pu Product Evaporation 4.77 First Solvent Wash Cycle --Typ ical.

4.81 Schematic High-Level Waste Evaporation.

Q 4.83 Schematic Low-Level Wiste Evapo ration .

4.85 Schematic of Acid Fract ionat or.

4.87 Schematic of Rework System.

4~89 Schematic General Purpose Evaporator.

5.3 100-ton Fuel Receiving and Storage Crane.

5.5 Fuel Pool Gate.

5.6 fuel Pool Storage Baske ts.

5.8a Fuel Pool Storage Can Crane.

5.8b Fuel Pool Servi ce Bridg e.

5.9 Fuel Storage Rack.

5.11 Underwater Trans fer Conveyor.

5.12a Fuel Handling Bridge Crane.

C Revision 1, Oct. 29, 1962 Revision 2, Oct. 30, 1964 I

(

I I figure, \

Continued Hnmber Ttt,11 5.12 b Power Manipulator.

5.14 Disassembly s*.

5.16 Bundle Shear.

5.19 Pin Shear.

5.20 Maintenance Tab le.

5.21 Chopped fue l Basket Loading Sta tion .

5.23 a 5.23 b GFC

Power Manipulator.

li 5.25 CPC Crane.

t 5.26 Leached Hull Dumping and Sampling Sta tion 1

I* 5.29 5.30 CPC Shi eldi ng Door Dis solv ers.

I' 5.36 a Silv er Reactors 5.36 b Dis solv er Off-Gas Scrubber.

5.36 c Dis solv er Off-Gas Condenser.

5.37 Pulse Columns 5.39a PUlse Column Inst rum enta tion .

5.39b Dec ante rs.

5.42a High Level Evaporator.

5.42b Low Level Waste Evaporator 5.42 c Rework Evaporator.

5.43a Low Enriched Uranium Product Evaporator.

Revision 1, Oct . 29, 1962 Revision 2, Oct. 30, 1964

figur1s G Continued Hwnb*t Title

~.43b High Enriched Uranium Product Evaporator 5.45 Plutonium Product Evaporator.

5.47 5.50a Acid fractio nator.

Radioa ctive Waste Tanks 80-1 & 80-2.

5.50b Details --Radio active Waste Tanks 80-1 & 80-2.

5.50c Details --Radio active Waste Tanks 80-1 & BD-2.

5.50d Plans-- Vault fo~ 80-1 & 80-2.

5.50e Section s and lletails --Vaul t for 80-1 & 80-2.

5.55 Section through Waste Storage Tank.

5.61 Plutonium Ion Exchangers 5.62 Silica *Ge1 Columns 5.63 Solven t Wash Columns 6.3a P & ID Contro lled Ventila tion System to Elevati on 131'.

6.3b P & ID Contro lled Ventila tion System Above Elevati on 131'.

6.3c P & ID Process Off-Gas and Vent System.

6.3d flow P & ID Waste Tank Farm.

6.17 Off-Gas Stack.

6.25 Glove Box :amplin g ~tation s.

6.26 "C" Type Sample Cell 6.27 Process Sampling System.

6.28 Mechanical Flow Diagram --Analy tical and Sampling Operat ions.

6.31 Floor Plan and Schedu les--La borator y Area Process Buildin g.

Revision 1, Oct. 29, 1962

( Revision 2, Oct. 30, 1964

figur1s Continued Tit11 6.32 Equipment Arrangement and P & ID's for Analy tical cells.

6.47 Sketch of Jumper.

6.67a General Locations of Radiation Monitoring and Sampling Systems.

6.67b General Locations of Radiation Monitoring and Sampling Systems.

6.67c General Locations of Radiation Monitoring and Sampling Systems.

6.67d General Locations of Radiation Monitoring and Sampling Systems.

6.67e General Locations of Radiation Monitoring and Sampling Systems.

6.67f General Locations of Radiation Monitoring and Sampling Systems.

6.67g General Locations of Radiation Monitoring and Sampling Systems.

6.142 Maximum Concentration vs U-235 Enrichment.

9.4 Plant Organization Chart 9.100 HETS Variat ion With Pulse Amplitude I

i

(

Appendices Numbt[ Title 2.36 Public Water Systems - Supporting Data 4.1 Process Flowsheets for the Base-Line Fuels.

Coanonwealth Edison Fuel Yankee Atomic Electri c Fuel Consolidated-Edison Fuel Power Reactor Development, Core Zr-U Alloy Fuel Northern States Power Fuel 4.2 Cask Acceptance Criteri a 5.2 Equipment List 6.121 Solid Angle Data for Dissolv er Cannis ters in Air 6.129 Calcul ations in Support of Paragraph 6.129 6.135 Calcul ations for Data in Table 6.135 6.140 Calcula tions in Support of Paragraph 6.140 C 6.149 Calcula tions in Support of Paragraph 6.149 6.153 Calcula tions in Support of Paragraph 6.153 7.7 Atmospheric Dispers ion Calcula tion 7.8 Iodine Deposition Calcula tion 7.32 Iodine Dose Thyroid 1o20 Fission s Calcula tion 7.34 Calcula tion of Critica lity Inciden t in Fuel Pool a.12 Recycled Iodine Activit y Calcula tion 8.25 Iodine Thyroid Dose by Recycling During Critica lity Inciden t Curriculum for Chemical Process Operato rs and Senior Pro*cess Operat ors.

9.13 Area Radiati on Alarm System 9.17 Film Badge and Dosimeter Monitor~ Protect ive Clothing and Safety Equipmen~ Station Monitors and Hand and Foot Counters Revision 1, Oct. 29, 1962 Revision 2, Oct. 30, 1964

Appendicef!

Continued Number Title 9.33 Air Sampling and Air Monitoring E~ip ment

t 9.36 Porta ble Monitoring Equipment 9.37 Counting Room Equipment 9.37a Dete rmin ation of Beta Emit ters in In-P lant Air Samples 9.37b Dete rmin ation of Long-Lived Alpha Emit ters in In-P lant Air Samples 9.39a Low Background Co~nting System 9.39b Dete rmin ation of Beta Emit ters in Perim eter Samples 9.39c Dete rmin ation of Alpha Emit ters in Perim eter Samples 9.40 Dete rmin ation of Radioiodine 9.43 Exposure Record Cerd 9.47 Routine Survey Form 9~49 Experimental Monitoring Program t 9.51 Stack Monitoring System

~ 9.53 Weather Monitoring Stati on 9.56 Stream Guaging and Sampling 9.64 Fire Briga de Orga nizat ion 9.93 Format for Standard Oper ating Procedures and General Index of Standard Oper ating Procedures I

' i

I I INTRODUCTION

[i,11 This document, which con sbts of nine pres ente d In two volumes, repr esen ts a desc ript ionsect ions plus appe ndic es of the Spen t Fuel Proc essi ng Plan t which Nuclear and safe ty anal ysis wishes to buil d on the Western New York Nuc Fuel Serv ices , Inc .

lear Serv ice Cen ter near Ric evil le, New York . It Is the purpose of this Intr prov ide a sunmary of the Info rma tion cont aine d In odu ctor y sect ion to repo rt. Throughout the repo rt the loca tion of matthe body of this by numbering para grap hs cons ecut ivel y with in each eria l ts tden ttfte d intro duct ion the nunbering rela te9 to the part icul sect ion; in this desc ribe d.

ar sect ion being 1.12 Sect ions II, III, :nz, ll, and lZI desc ribe the proc ess, equipment, and supp ortin g engi neer ing site plan t, These desc ript ive sect ions form the basi s for the syst ems , resp ecti vely .

cont aine d in Sect ions ll((, Prot ecti on of the Pub safe ty anal ysis Prot ecti on of Plan t Pers onne l. Sect ion II desc ribelic, and Sect ion 2III ,

safe ty programs and the star t-up plan s for the s the heal th and pla n:]

rr** Site *Des crip tion Geography 1: 21 . *: The faci 1 ity wi 11 be loca Nuclear Serv ice Cen ter in the Town of Ashford,tednear on the Western New York Catt arau gus County, New York, abou t thir ty mile s Ric evil le, and will be desc ribe d as the Rice ville Site . The sout hwe st of Buff alo acre s and the proc essi ng plan t and was te stor age site cont ~ins 3,331 3,00 0 to 4,00 0 feet from the near est site boundaryfaci litie s are loca ted mid dle of a rura l area ,f lcw pop ulat ion den sity . The site is in the pers ons per squa re mile with in a 25-m ile radi us. - *an aver age of 90 not changed with in a 10-mile radi us over the past The pop ulat ion has cha ract er of the land and community are such that 50 year s, and the mat eria lly over the next 15 year s. There is no town it should not change the site with a pop ulat ion in exce ss of 10,000. with in 25 mile s of The Spr ingv ille, 4-1/ 2 mile s to the nort h with a pop ulat near est vill age Is the near est major pop ulat ion cent er is the city of ion of 3,85 2, and limi ts of which are 26 mile s nort h of the site . TheBuf falo , the city with in four mile s around the site ts divi ded betw immediate area terr ain and leve l fert ile land used for farming. een unusable rugged

. site will be used sole ly for acce ss purp~ses and All roads through the the app lica nt . There is a spur of the Balt imo re will be con trol led by Company rail r*oad used sole ly for frei ght traf fic and Ohio Rail road site at a d ista nce of 1,800 feet at tts clos est poin runn ing thro ugh the t to any faci lity .

1.22 It ts sugg este d that the geog raph ical The excl usio n area , as ts demonstrated in Sect ion fact ors are favo rabl e.

adequat e to assu re that the heal th and safe ty of VII, is more than

( ~

endangered by normal oper atio n of the faci lity *or the pub lic wtll not be acci den t. The pop ulat ion den sity beyond the excl by any cred ible *

- usio n area and pop ulat ion

L 7 wit hin a rad ius of 25 mil es Is sma ll, thu of the gen eral pub lic, if as a res ult of s ass urin g a minimum exp osu re act ivit y sho uld not be con tain ed wit hin an unf ores een acc ide nt, rad io-the are a of tne site .

Meteorology 1.23 The are a has a mean ann ual tem rain fall of 40 inch es, and an ann ual sno wfaper atur e of 4SF, an ann ual pre vai ling wind dire ctio ns are from the nor ll of 80 to 100 inch es. The the sou thw est in the summer. The are a to thw est In the win ter and fran are even more spa rsel y pop ulat ed than the the nor the ast and sou the ast and the clo ses t major pop ulat ion are as in ave rag e set for th in 1.21 above 80 mil es from the site . The are a around the se dire ctio ns are app rox ima tely per sist ent stag nan t high pre ssu re are as andthe site is seldom sub ject to Thu s, the pre vai ling wind and diff usi on poor diff usi on con diti ons .

con diti ons are fav ora ble.

Geology 1.2 4 The pla nt and the was te stor age fac pla teau between two of the rav ines which ilit ies are loca ted on a But term ilk Creek. The geo log ical stru ctu form trib uta ries flowing into gla~ idi dep osit s con sist ing of a perm re is bed rock ove rlai n by eable gla cia l til l, a much less permeable silt y til l, wit h sandy till s and All lay ers have good ion exchange cap acit var iou s sha les und erne ath.

y for cesi um and stro ntiu m.

Hydrology 1.25 The site is an elon gate d roll trib uta ries lead ing into But term ilm Cre ek.ing pla in cut by rav ines wit h on the site and , the refo re, all ground wat All of the trib uta ries But term ilk Creek wit hin the por tion of tha er on the site feed into wit hin the site . App lica nt ther eby has cont cre ek con tain ed who lly for the ent ire site by its con trol ove r But trol ove r all sur fac e dra inag e boundary, But term ilk Creek emp ties int~ Cat term ilk Creek. At the site turn flows into Lake Eri e, 39 stre am mfl es tara ugu s Creek, which in vill age s downstream from the site rely on from the site . No citi es or wat er sup ply , and the re are no pot abl e watCat tara ugu s Creek for the ir sup plie s in the immediate are a of the site er sou rces or larg e wat er 1.26 But term ilk Creek sup plie s dilu tion wat er of 41 cfs . at an ave rag e rate Cat tara ugu s Creek has an ave rag e flow ~t 358 cfs . the site of

1. 27 The re are thre e aqu ifer s on the site sur fici al gla cia l till . Ground wat er mov . One is in the from 1 to 2 fee t per day . On some par ts ement in this form atio n is aqu ifer loca ted in sandy till s und erne ath of the site the re is an not exi st on the pla teau sele cte d for the the silt y till . Thi s does the re is a deep bed rock arte sia n aqu ifer pla nt fac ilit ies . Fin ally ,

impermeable lay ers at the fac ilit y loc atiowhich ts situ ate d wel l below the was te tank s and the sol id bur ial wil l n. The silt y till , in which be loc ated , ts not an aqu ifer

but 1t Is water satura ted . Ground wat!~ movement In this very Impermeable layer Is calcul ated to be about 5 x 10 ft/day . It Is calcul ated 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 neares t ravine .

1.28 The good Ion exchange capac ity of the soil, the slow movement from the waste storag e facili ties to the ravine s, the existe nce of the ravine s, and the fact that all ground water flows a creek within the site render the site adapta ble to an excell ent to monito ring system and allow excell ent contro l over radioa ctive wastes stored on the site.

Seismology 1.29 Western New York ts an area of low selsm lctty and the danger of earthq uakes which might ruptur e any of the plant~ s facili ties Is minimal. The neares t feult to the site Is at a distan ce of 35 to 40 miles, and this Is more proper ly classi fied as a minor earth struct ure rather than a fault. Thus, the site presen ts no seismo logica l problems.

Sumnary 1.210 In sunrnary, the chara cteris tics of the site are such that

( the health and safety of the public should not be endangered by operat ion at the site of the NFS chemical proces sing plant or by the storag e of low or high level wastes . The remoteness of the site from popula tion cente rs, the low popula tion densit y for 25 miles beyond the site, the large exclus ion area, and the meteo*r ology, all are favora ble factor s to assure protec tion both from normal operat ion of the facili ty and 11 from any credib le accide nts. The hydrology and geology are suitab le to permit contro l of low level and high level wastes unde- normal I condit ions and In the event of :a: credib le accide nt. The ease of I monito ring water movements and exerci sing necess ary contro ls, If excess ive radioa ctivity developed, ls assure d by the specia l condit ions I.

existe nt on the platea u on which these waste facili ties will be locate d. I I((

pJant Descr iption I 1.31 The plant site area, locate d in the center of the 3,331- acre exclus ion area, contai ns 500 acres. Both areas will be fenced and I

conspi cuousl y posted , and access will be contro lled. The facili ties consis t of a proces s buildi ng, a waste tank farm, a waste burial ground, a temporary waste storag e lagoon, an office buildi ng, and a warehouse.

Off ice Buildi ng i

11

1. 32 The office buildi ng and parking for vtsl~o rs and employees I ts locate d at the entran ce of the plant site area 4',000 feet f rom the proces s buildi ng and warehouse and 3,000 feet from tlie waste dispos al

are as. It Is thu s remote fra n the areas handled. Of the app rox ima tely 130 employe where nuc lea r ma teri als are esti ma ted tha t approximately 30 wil l be es of the app lica nt, It Is employed In the off ice bui ldin g.

Process Bui ldin g 1.33 The pro ces s bui ldin g Is arra nge d and sto rag e are a on one end and pur In a Z wit h fue l rec eiv ing the oth er end. In the middle are the mecifie d pro duc t removal fac ilit ies on cel ls. On one sid e of the cen ter lin e hanical and chemical pro ces s are off ice s, lab ora tor ies ,

room, and rela ted fac ilit ies . On the oth er sid e are shops, a uticon lity tro l are a, and a warm equipment ais le.

Fuel Receiving and Sto rag e Area 1.3 4 The fue l rec eiv ing and sto rag e are washdown are a Into which the fue l shi ppi a con sis ts of a primary tru ck, a cas k sto rag e are a, a cas k decont ng cas k Is brought by rai l or unloading poo l, a rup ture d fue l Iso lati on am ina tion pit , a cas k and an underwater pro ces s poo l. The cas poo l, a fue l sto rag e poo l, deep to permit a mlnlmun wat er cov er of k unl oad ing pool Is suf fic ien tly element con tem pla ted . The fue l sto rag e 11 fee t ove r the lon ges t fue l for handling each typ e of fue l pre sen tly poo l has racks and equipment pro ces s pool *COnt~lns equipment for doing con tem pla ted . The underwater non -ac tive par ts of fue l elem ent s If nec rou gh und erwater cut tin g of seg reg ate d by removable gat es. The spa ess ary . Eac h pool can be and fue l handling fix tur es are des ign ed cin g of the fue l and the cra ne crl ttc alt ty. to pre ven t acc ide nta l Mechanical and Chemical Process Cel ls I

1.35 The cen tra l pro ces sin g are a con sis cel l and a chemical pro ces s cel l. The by 54 fee t long by 24 fee t hig h wit h wal or 4 fee t of high den sity con cre te. The mec l

han of ts of a pro ces s mechanical ical cel l ts 16 fee t wide 6 fee t of ord ina ry con cre te I mechanical cel l Is to remove ext ran eou s and reduce It to small pie ces (1 tn. to prim hard war ary purpose* of the e from the fue l element 2

1n. ) which can be dis sol ved

,lI In the chemical cel l. The are a has vl~wtn I cra nes and ma nip ula tors . The chemical g windows and remotely ope rate d cel long by 4s fee t wide wit h wa lls of 6 fee l Is 16 fee t wide by 107 fee t has a remotely ope rate d cra ne and per isc t of ord ina ry con cre te. It windows to aid in the use of the cra ne. ope s, tele vis ion , and viewing equipment req uir ing f.requelit maintenance All high level rad ioa ctiv e Is loc ate d In thi s cel l. Both cel ls arewhich can be performed remotely system . On each sid e of the cen tra l pro tied Int o a cen tra l ven tila tio n ais les con tain ing most of the lnstrLment ces sin g are a are ope rati ng ais les are ais les con tain ing sampling stas and con tro ls. Under the se Inte rio r ope rati ng gal ler y Is a warm equ tio ns . Underneath the a ser ies of shi eld ing cub icle s loc ate d ipment ais le con sist ing of ais le. The cub icle s have removable shi below the flo or lev el of the nance of p1.111ps and oth er mechanical equeld cov ers which per mit ma int e-ipment con tain ed the rei n.

Cl Product Puri ficat ion Area I 1.36 At a 90 degree angle to the cent ral proce ssing area are princ ipal prod uctio n purif icati on and recovGry faci litie the disso lutio n of the fuel element In the chemical cell to form a s. Afte r fuel solu tion, the solut ions are put *through a Purex solve nt extra proce ss proce ss which sepa rates and recovers uranium and plutonium as ction solu tions . This Is done In a serie s of perfo rated -plat e pulse nitra te which have the nece ssary equipment for mete ring, trans ferri ng columns Intermediate storage- of solut ions- . Facf lttle s** for c*lean*up and of solve nt are also Included . and recyc le .

Product Hand) Ing Area

1. 37 Adjoining the product purlf lcatl on area conc entra ting and packaging areas Including evap oratiare on, the product and silic a gel equipment for conc entra tion, final clean -upIon and exchange packaging of uranium and plutonium. The entir e prod and product handling area Is 128 feet Jong by 43 feetuctio high n purif icati on by 16 to 22 feet In width .

Warehouse 1.38 The warehouse Is locat ed near the proce ss build ing and prov ide stora ge space for bulk ctiemlcals and othe r supp lies, bird will shipp ing cont ainer s, equipment spare parts , and plutonium produ cage s, G solu tions . ct 1J** Deta i 1ed :Process :Des er i pt Ion Basic Process 1.41 The plan t Is a mult ipurp ose plan capable of proce ssing any type of fuel element from .which the fuel prop ert can reduced to a nitri c acid solut ion . This Includes all but one of the be prese contemplated fuels from priva te nucle ar power plan ts (grap hitently fuels ) . No fuel will be processed befo re It has been cooled maxtrlx days . The base line process Is a Purex solve nt extra ction syste for ISO designed for pr_o cessl ng of low enric hed H02 In stain less steel m.

zirconium al Joy tubes with a maximum throughput**of 1,000 kg of or per day. In addi tion, there wl11 be: uranium

1. A head end disso lutio n treat ment for the disso lutio n of zirconium clad fuels In HN0 -HF mixt ures, perm itting a throughput of 600 kg of zirco 1 nium per day. Diss oluti performed In stain less steel disso lvers with cont rolleon d Is addi tions of HF and HNO. Aluminum nltra t~ Is added to perm it extra ction of t.J uranium and to minimize corro sion.

Stain less steel tanlcage Is provided for stori ng the waste s In acid ic cond ition .

(

2. A total disso lution scheme (Darex) for stain less steel cermet fuels . using mixtu res of hydro chlor ic and nitri c acids with a throughput of 230 kg of stain less steel per day . Special titani um equipment Is required In this head-end step which conta ins facil ities for dlstl llatlo n and recyc le of the HCI .

The disso lver Is locate d In a speci al cell over the proce ss mechanical cell and the rem11lnder of the Darex equipment ts locate d In a contact-m11lntalned cell adjac ent to the first extra ction cell . The Darex head-end rnay be replac ed with elect rolyt ic disso lution which ts simpl er. The use of elect rolyt ic disso lution wl 11 .Intro duce no new safet y quest ions .

3. A direc t nitri c acid chemical disso lution proce ss for aluminum or molybdenum al loy fuels .

4. A deact ivatio n proce ss prior to disso lution for uranium carbi de fuels or for those In which sodium Is prese nt as a bonding agent .

Recei pt and Stora ge 1.42 The fu~I Is receiv ed In shield ed. water -cool ed ,cask s and Is hosed

down In the primary washdown area. After tempe rature readi ng.

sampling of cask coola nts and purging of gases Into the venti lation system . the cask Is place d underwater In the 44-fo ot deep unloading pool by a hand- opera ted overhead crane . The fuel Is removed and place

(

In stora ge baske ts by remot ely-o perate d equipment and the cask Is d trans ferre d to a decontamination pit. The stora ge baske ts are trans ~.

ferre d by the stora ge pool crane to the fuel stora ge pool and place d -

safe geometry racks . Any ruptu red elements will be store d In sealed In canis ters.

Hechanlcal

Proce sslng 1.43 When the fuel Is ready to be proce ssed. It Is trans ferre d by the stora ge pool crane to the underwater proce ss pool fran where Is trans ferre d through a conveyor and crane to the proce ss mechanicalIt cell. It Is removed fran the baske t by remote equipment and dried .

The end hardware Is then cut off and the fuel pushed out of its casin After inspd ction it Is chopped Into small piece s In the bundle shear g.

This opera tion Is carri ed out under an inert atmosphere such as CO2, .

The resul ting piece s of fuel are colle cted In chopped fuel canis ters.

If sod ium ts Invol ved. deact ivatio n of the sodium Is accom befor e removal of the chopped fuel fran the CO2 atmosphere.plishe d Then chopped fuel canis ters are removed to the chemical proce ssing cell the on a trans fer cart through an airlo ck.

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_ _ __ . . . ,_ _ .--------------------*-t-==l

.,..._ _ _ _ _ _ _ _ _ _ _"""'!1111_ _ _ _ _ _ _....

I I

~

- Chemical Processi ng I I

1. 44 1-n the chemical processi ng cel 1, the chopped foel canniste rs are placed Into one of the dissolve r barrels . Nitric acid and water are metered Into the dissolve r from the solution makeup area so that the ~

final solution contains no more than 7. 5 grams per liter of U-235, a critical ly safe concentr ation In all geometries and quantiti es . Complete dissolut ion Is expected to take about 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . The off-gas treatmen t I I Includes a down-draft condenser on the dissolve r, a secondary condense r, .I a scrubber , Iodine removal on a silver reactor, and filtratio n through a parallel filters . The off-gas Is then added to the general ventilat ion system for further filtratio n before discharg e to the stack. I 1.45 Vhen the dissolut ion of the fuel Is canplete , the solution Is cooled and Jetted to a 304-L stainles s steel account ability and feed '

adjustme nt tank. The dissolve r ts then heated to dry off the hulls, 11 which are returned to the process mechanical cell. The hulls are Inspecte d and packaged and sent to the solid waste storage area. The account ability and feed adjustme nt tank Is equipped with heating coils, I

a condens er, air sparger, liquid level and specific gravity measurement, circulat ing sampler, and temperat ure measurement. After analysis and adjustme nt* of the a>ncentr atlon and acidity of the feed, It Is Jetted to the partitio n cycle feed tank from wht.ch It Is fed to the extracti on columns .

-, Solvent Extracti on 1.1'6 Solvent extracti on Is done by a Purex-ty pe process, which Is performed In the contact process area. The base-lin e fuel Is put ,!

through a partitio n cycle, 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 II the major fission product waste stream of the plant. "The plutonium and uranium are also separate d In this first extracti on cycle Into two l separate , partlell y d~conta~ lnated, aqueous product streams . These l two product streams a re then separate ly put through addition al solvent extract ion cycles to complete the removal of remalnln~ fission products .

1.47 The uran l un and plutonlu n product streams are first collecte d In the feed conditio ner tanks for sampling, analysis , and adjustme nt of II I

acid concentr ation. The streams are then put through addition al solvent extracti on cycles In which the product Is extracte d Into an organic phase II 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 I pluton i um through *one . I I

(_

n,

Product Purific ation and Concentration (

1.48 The uranium product stream from solven t extract ion Is collect ed I~ a product evapor ator feed tank from which It Is Jetted Into one of l'WO evapor ator tanks for concen tration . The condensate Is collect ed In one tank and the concen trate In another . The concen trate Is subject ed to a silica gel treatment for final decontamination. The product Is then placed In one of two sampling tanks, and after sampling and analysi s It Is transfe rred to one of a series of storage tanks .

Highly enriche d uranium Is drawn from th*** tanks In small quanti ties and mixed with water to a concen tration critica lly safe for shipment In tank trucks; the low. enriched uranium Is already at an acceptable concen tration from a crltl~a llty standp oint.

1.49 The plutonium product stream Is collect *~ In an Ion exchange condit ioner 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 concen trate Is collect ed In one of three plutonium storage tanks, from which It Is packaged for shipment . _All of the packaging and shipping equipment Is enclosed In separa tely ventila ted glove boxes. The shipping bottles are placed In secondary contain ers and stored In the product storage area In bird cages awaitin g shipment.

Solvent Recovery C

1. 410 The plant Is designed to reuse the TIP-kerosene solven t, wh ich must be cleaned of fission products prior to reuse. To accomplish this, the solven t Is first washed with sodium bicarbonate and then with dilute nitric acid.

Ac id 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 subject ed to an acid fractio nation step to concen trate It Into a reuseable conditi on.

Rework System 1.412 All waste streams will be sampled and analyzed prior to being discard ed to the waste disposa l system. In the event that the product In the waste stream Is above specifi cation, facilit ies are provided to rework the wastes . They are recycled through a feed tank and a rework evapor ator . The bottoms from this evapor ator are pumped back to the feed adjustment tank to be subject ed to further solven t extrac t Ion .

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 constru cted In the

~up-an d-sauce r" design used at Savannah River. They are operate d, however, according to the waste management procedures applied at Hanford.

Spare tanks are provided so that wastes may be transfe rred to another tank should leakage develop.

l.414 A general purpose evapor ator 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, suffici ently 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 collect s In them. Any seepage wl 1.1 be p1.1nped out and processed In the general purpose ev~por ator. Low level solid waste will be burled In the silty till of ~ery low permeab 11 I ty **

I Equipment Descrip tion I.SI In this section , all major equipment Is described In detail.

In genera l, the equipment Is classif ied either by the area In which It Is locat~d or by functio n.

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 radioac tive contamination In the event of ruptured elements. The major equipment pieces are:

a. IOO~Ton crane with two auxilia ry 5-ton cranes running on a monor~tl attache d to the understde of the main bridge beam.

The contro ls are of a faJl*sa fe type requiri ng m~mual operati on.

o. Fuel storage pool complex with water deminerallzed before use and continu ously ft ltered to maintain Its purity and with cleanup equipment. including a filter, demlne rallzer, and resin add tank. The pool has three smaller pools which can be separat ed by means of removable gates.

c. Storage baskets perfora ted for cooling and drainag e, made of stainle ss steel with spacers to prevent movement of fuel In the basket during storage or m6vement.

l

d. Ruptured fue l can iste r, water and gas -pre ssu conff*ne rad ioa ctiv e contamination . These arere tig ht, to I e.

con trol attachment by the crane and have spa adapted to remote movement of the fue l.

Movable brid ge and 2-to n overhead crane which cers to prevent stor age pool . Th* cran e has

lim ited ver fca ser vic e the l lif t to ass ure minimum water shi eld ing .

f. Storage rack for storage of fue l assemblles pooL It Is designed to pre ven t* cri tica In the stor age con figu rati on of any fue l . l arr* 'f of any

g. Underwater conveyor for tran sfe r of stor age mechanical cel l. Th* conveyor Is so designe baskets to the basket can be handled at a time . It has an d tha t only one can be con trol led eith er at the fue l rec eivi end less cha in and mechanical c~l l area. ng area or at the Process Mechanlcal Area* . :*

1.S3 Equipment Is provided for chopping of the var iou s fue l elements the .

tran spo rt, disassembly and Fle for var iati ons In fue l element con stru ctio n xib le fac ilit ies are provided In the fue l bundles . The major equipment pieor oth er spe cfal con diti ons ces are :

a. Remote handling equipment, fncludfng two fue cran es , a power manipulator and fou r pai rs ofl handling bridge man ipu lato rs, one pai r of which has extended master-slave ope rati ons In thi s area are car ried out rem reach. All of this equ fp~ nt . otely by the use

b. Pushout tab le, Including a pushout ram of fue l from basket and dry ing of fue l . and

dri er for removal The In the dr ier wh ich Is sampled to ass ure tha t re Is a gas loop dri ed . The push ing pre ssu re Is con trol led the fue l Is reg ula tor . by a pre set

c. Rad ial saw .tab le on which the ends of the elem off aft er the element Is pos itio ned In a fue ent are sawed which spe cial cut ting can be done ff the fue l car rier and on pushed out of Its cas ing . l cannot be

d. Fue l bund le car rier s designed to hold a sln gle by means of manipulator-operated clamps . fue l bundle

e. Insp ect ion tab le with a remotely ope gauges and othe r devices to hold and rate d vis e, vee blo cks ,

measure fuel elements .

I (1 f. 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.

g. Casini shear for chopping casings In pre-selected lengths of 1 to Inches .

h. Fuel pin shear, a portable machine shearing single fuel pins I II If necessary.

I. 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 .

J. Deactivation autocla~e cart for transport of the baskets containing the chopped fuel.

k. 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. I

,, I. Remotely operated shielding door for foyer Into which the c.: manipulator and cranes can be removed for decontamination and maintenance . I Dissolvers 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 I 1 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 I

I a nominal capacl-ty of 1,500 gal Ions designed to dlssolvtt 100 1-h/day of stainless steel . They are designed for remote malnt*n*nce and replacement and are Isolated from one another. The tanks are cylindric~)

with a heat ing col l near the bott~ and a ~ondenser coll located In a bustle around the top . Each dissolver has a series of appurtenant equ ipment for handling the off*gas from It, Including an off-gas scrubber , a condenser, and a silver reactor. During dissolution, the l iqu id level and density of the solution Is continuously recorded and the system pressure Is recorded and controlled by a PRC In the off- gas l ine, backed up by a manually* controlled valve . Alarms are prov ided for high and low liquid level, temperature of solut ion and off-gas , and off-gas pressure .

C j

Pulse ColUIMS a

1.55 Continuous sol ve w! th varying fun cti on s. The ntcolex um tra cti on Is eff ect ed by 12 pu lse col umns ste el and loc ate d In thr ee 6X tra ctlns are fab ric ate d from 304-L sta inl ess of ex tra cti on , pa rti tio n, str ipp ingon ce lls . They perform the fun cti on s of two columns, all wl ll have car and scr ub bin g. With the exception Ins tal led In the enl arg ed disengagi tri dg es of boron*304*L sta inl ess pla tes cr iti ca lit y. Control of the colum ng sec tio ns to pro tec t ag ain st co ntr ol of the eff lue nt from the ns Is maintained pri ma ril y through of aqueou s eff lue nt removal and Int bottoms of the columns and by co ntr ol loc ate d ne ar the tops of the colum erf ace lev el through sen sin g pots temperature at the top and bottom ns . Fu rth er, the column bottom pre ss~1re, the org ani c eff lue nt are recorded. of the column and sp ec ifi c gra vit y of Evaporators 1.56 Produc_ts and wastes are con 2 waste eva po rat ors and 1 rew cen tra ted In seven eva po rat ors :

ance; 2* uranlum and* 1 plutonium pro ork eva po rat or designed for remote mainten-ev ap ora tor , designed for co nta ct du ct eva po rat ors and I general purpose Int eg ral package with ex ter na l reb ma int ena nce. Each Is designed as an *

~he sh ell of the ev ap ora tor . All oll ers and condensors *supported from are the pI uton I um product eva po rat or wh made of 304-L sta lnl ess , exc ept Ich. Is to be t I tan I um for co rro s I on res ist an ce . C Acid Fra ctl on ato r 1.57 This Is a vacuum un it made.

for co nta ct maintenance. of 304-L sta inl ess and designed f*rocess Tanks 1.58 These are of eig ht ba sic de Ing CY.i siz e, loc ati on wi thi sig ns, and have variances depend-n the pla nt , and type of maint enance.

Radioactive Waste Storage Tanks 1.59 These are of fou r typ es: 50 low lev el liq uid wa ste s, 100,0 0,000-gallon tanks for high and for dep let ed uranium, and 60,000-g 00 -ga llo n for Darex wa,~e, 30,000-gallon bu ilt In a 4-f oo t high ste el pan all on for thorium product. Each Is In a con cre te va ult with su ffi cie nt and the pan and the tank are enclosed

at grade to 1 mr/hr . All pla te we ea rth cover to reduce rad iat ion lev tanks have Int ern al columns to sup lds wi ll be ful ly radlographed and al lels the Int ern al pre ssu re design . The port the tan k roof and ac t as tie s for and are cooled by c irc ula tio n of coo Darex tanks are of 304-L sta inl ess coo lin g co ils . The ~Judge In the lin g water through two ve rti ca l hig from se ttl ing by ag ita tio n with fou h lev el waste tan k Is prevented all tanks Is po ssi ble through a shi r air ag ita tor s. Limited acc ess to t op of the !an k. eld ed plug from grade through the I

C Pumps 1.510 A vari ety of pumps are used Incl udin g pos itive with and with out flow adju stme nt, canned, cen disp lace men t diaphragm pumps. trifu gal, and remote head Mis cella neou s Equipment 1.511 I

a. Sili ca gel columns

b. Small column for the fina l solv ent extr acti on prod uct strea m.

c. Ion exchange unit s

d. Equipment for solv ent washing system.

C I ..,

II iI Eng inee ring Ana lysi s of the Pla nt 1.61 In this sec tion , the sal ien t fea eng inee ring asp ects of this pla nt are disc ture s of a number of the uss ed, incl udi ng:

a. Ven tila tion

b. Sampling

c. Maintenance

d. Shi eld ing

e. Mo nito ring

f. Uti liti es The re are als o sec tion s which disc uss the the pos sibl e eff ect s of pro ces s mal ope rati con trol of cri tic ali ty and on.

Ven tila tion 1 .62 The pla nt has fou r ven tila tion from one ano the r. These are : {1) the gensyst ems which are sep ara te (2) the pro ces s ven tila tion , (3) the pro ceseral bui ldin g ven tila tion ,

dis sol ver off -ga s syst em. The syst ems are s ves sel sys tem , and (4) the tota l volume of air is kep t to a minimum, des ign ed so tha t: (1) the mec han ical ly or che mic ally clea ned to rem (2) all air ent erin g is 11 fumes, (3) air pre ssu re to lim ited acc ess ove par ticu late mat ter and and to pro ces s are as at an even lower pre are as is less than atm osp her ic ope ning s are ven tila ted from the less act ssu re, (4) normal acc ess (5) gas es from pro ces s and lab ora tory equive to the more act ive are a, spe cial trea tme nt and clo se mon itor ing , ipment are seg reg ated to per mit where des irab le for rel iab ilit y a.nd con tinu(6) back-up systems are employed equipment con tain s vol ume tric con trol , iso ity, (7) dis trib utio n con cen trat ion , (8) tox ic and rad ioa ctiv e lati on, div ersi on, and and (9) fina l exh aus t to the atm osp here aer oso ls are kep t to a minimum, volume to insu re dilu tion of irre mov able is acc omp lish ed at suf fici ent (202 fee t above grad e) to ass ure seco nda rygas es and at suf fici ent hei ght dis trib utio n to the atm osp here . The tota dilu tion and ade qua te 46,0 00 cfm. Fume hood and rad iola bor ato l volume of air disc har ged is ven tila tion syst em, the var iou s ves sels andry exh aus t, the pro ces s pro c~s s are a are sep ara tely ven ted to dup equipment pie ces in the pre filt ers , abs olu te filt ers , and exh aus lica ted syst ems of pre hea ters ,

rele ase to the stac k. The was te tank f.Jrm ter ins tall atio ns prio r to I two gla ss fibe r-pa cke d columns and par alle ven t gas syst em cor.sis ts of CMn stac k. Each syst em is sep ara tely adj l exh aus t disc har gin g to its spa re abs orb er trai n wit h auto mat ic sta rt-uuste d aut om atic ally and has a syst ems are iso late d by but terf ly val ves p and pha se-i n. The dup lica te

. All of the exh aus t fan s are con nec ted to the emergency ele ctri cal syst ope rati on wit hin ten seco nds and aut om aticem and wil l come back into pre ssu re in an are a dro ps below a pre set ally sta rt up if sta tic beyond a pre set poi nt. The ent ire syst empoi nt or if act ivit y incr eas es des ired . may be ope rate d man uall y if

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