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||

- ,..

,

6. Complete the information and calculations on the

calibration data sheet.7. Remove the Laminar Flow Mass Transducer r.nd connect

the filter. Do not remove the vacuum gauge.8. Set rotameter to appropriate setting (20-50. Ipm) and. record the vacuum reading and calculate the required

data on the calibratioif sheet under " Normal*

3

Configuration". * e corrected rotameter reading is thethe actual flowrate in s!pm with the rotameter

set at same appropriate setting. Enter this value in the-

blank at the bottem of the page.i 9. Remove vacuum gauge.

Routine Procedure

1. Place a clean filter in the filter holder and turn on'

sampler (Figure 4.5).

| 2. Adjust rotameter to calibration setting and record the ,

required information on the data sheet.

3. Replace the filter if dust loading results in a significantdrop in the flow rate.

4. As each filter is removed, fold the filter in half with the'

exposed surface to the inside. Store the filter in anenvelope which, in turn, is stored in a zip lock bag. Thefilters from the same air monitoring station are to beplaced in the same envelope to comprise a compositesample for that station. Record the necessary information

ont he data sheet.

5. At the en '! a quarter, send the composite filter samples

to a Ibaoratory for radiometric analyses. also include the

total volume of air sampled for each filter papercomposite sample.

I

-14- Revised 9/8/87

Ii

_ _ _ . _ _ _ . _ _ _ _ _ _ - _ - _ - - _ _ _ _ _ _ _ _ _ __

_ - _ _ _ _ _ _ _ _ _ _

.

.

-}I

4.3.2 Radon Sampling

Radon will be measured at the air monitoring stations withTerradex Track Etch cups. The program will be conducted asper the attached manufacturer's instructions. The cups will be

exchanged on a monthly frequency and one additional cup will

be randomly placed at an air monitoring station every other]

month for a quality control check.

4.3.3 Sediment Sampling - Sediment in Squaw Creek is sampled at

two locations on a semi-annual basis. The sample locations are

shown in Figure 4.1 and represent one sample upstream and one

downstream of the restricted area. These samples will be

analyzed for the parameters shown in Table 4.1. This data willbe submitted to the agency and retained at the site for

| comparison with data obtained on samples taken during pre-operation.

!

!-

4.3.4 Soil Sampling - Soil samples are taken at the locations shown in

Figure 4.1 at the frequency shown in Table 4.1 and analyzed for

the parameters shown in Table 4.1. Data obtained on these

samples will be submitted to the agency and retained at the site

for comparison with data obtained on samples taken during and

af ter operations.

-17- Revised 9/8/87

_ _ _ _ _ _ _ _

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_ _ _ _ _ _ . .. . -___ - ______ _ -_____ - - -__

-,_

;,

FERRET EXPLORATION COMPANY OF NEBRASKA,INC.

SURFACE WATER SAMPLING SHEET

DATE SAMPLING TECHNICIAN

SAMPLE. IDENTIFICATION NUMBER

, SAMPLE-LOCATION NUf4BER

SAMPLE DATE WEATHER

-PREVIOUS WEEKS WEATHER

APPEARENCE OF WATER

COLLECTION LOCATION

|I DEPTH WIDTH FLOW

TEMPERATURE *C pH

CONDUCTIVITY X umhos=

QUANTITY OF SAMPLE TAKEN-@ 4"C F -

. QUANTITY OF SAMPLE TAKEN @ 4*C UF

1- ACIDIFIED - HNO F3

ACIDIFIED - H SO F2 4

LABORATORIES TYPE OF ANALYSIS DATE SHIPPED

_

REMARKS

|

'

-28- Revised 9/8/87 _ _ _ _ ______________________J-

..

-

4- - - .

.i.

4.4.4 ' Pond Sampling

Three types of samples are taken in connection with theevaporation ponds on site. 'Ihey are the shallow monitor well

samples, the leak detection system samples, and the samplestaken of the p6nd contents.

'

.

The shallow monitor wells will be sampled by bailing or pumping.

using the procedures outlined in Section 4.4.1.1 above. If liquid

in excess of 6 inches is present in the pond leak detectionsystem it will be sampled. Samples of the pond contents will

. be obtained by collecting one or more grab samples of the liquid

in the pond. The grab samples should not be collected in thevicinity of the inlet pipe.

,

4.4.5 Containers and Preservation Techniques

As samples are collected, they are placed in dif ferent bottles

depending on the analysis to be performed. For samples going to ,

outside Laboratories the bottles are preserved according to the

" Bottle List" (Figure 4.11) and labeled accordingly with thefollowing data:

A)' Sample identification Number

B) Well Location

C) Date Sampled

D) Analyses (metals, common ions, etc.)

E) Sample Treatment

F) Preservation (if any)

The bottles which require cooling at 40C are then placed in an

ice chest. Equipment is properly secured and the process is

!- repeated at the next well. If at any time there is any doubt asto

30- Revised 9/8/87

- _ - _ _ - - _ _ _ . |

-,-- - - - . - - , - , - - - , - - - - - - , - . - - - . . - - - - , , - - - , - - - - , - - .,,--.----r. - - - , - - - - - . - - - - -

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_ __ . - _ _ _ _ _ _ _ _

O

;

On a monthly basis, the. Health Physics Technician or the designee willconduct an inspection of all work and storage areas and wLil review all man-itoring-and exposure data for the month. The Health Physics Tech-

nician will provide to the Pilot Plant Superintendent for his

review a written summary of the month's significant work protection

activities containing at a minimum, (1) a summary of personnel ex-

posure data, including bioassays and time weighted calculations, and

(2) a summary of all pertinent radiation survey records. In addi-

tion, the monthly inspection will specifically address any trends

or deviations from the ALARA program, including an evaluation of

the adequacy of the implementa tion of license conditions regarding

the ALARA. The summary will provide a description of the unresolved

problems and will propose corrective measures. The monthly summary

inspection report will be maintained-on fi'lb and accessible for at least

five years. A copy of the Monthly Summary Inspection Report, ini-| tialled by the Pilot Plant Superintendent, will be forwarded to the

: Vice President of Uranium Development.|

5.1.2 Survey for Airborne Uranium

The Eberline RAS-1 pump will be used at the Crow Butte R&D Project

to conduct surveys for airborne uranium. A volume of air will be

drawn through a high efficiency filter. The alpha activity on this

filter will then be counted using the Eberline SAC-R5 alpha sample

counter and Eberline MS-3 scaler. The filter will be counted . .

*'gpw

at least 72 hours later to allow for correction due to radon daugh-,

| ters. The count time and sample volume will be adjusted to encurc-16

j a lower limit of detection of 1 x 10 uCi/ml as per Reg. Guide

4.14 p 4.14-5. All sampling information and analytical data will

be recorded on the appropriate forms (Figure 5.1). '

Calibration: Same as Environmental Air Particulate Sampling.

IREVISED "9/8/87 i-38-

_ _ _

_ _ _ _ _ _ _ _ _ _ _ _ _ _ - ._ _ _ _ _ - _ _ _ - _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ . - . _ . _ - _ - - - _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ . - _ _ _ - _ - _

-..

-.1

jf,

1

|

CPM = counts per minute measured

[ EF = instrument efficiency factor

Vol = total volume of air sampled in liters

TF* = time factor (radon daughters)

V * always use the (nidpoint of the sample count time for the time factor.'

. :. .

Self Absorption correction should be done as per ANSI Std. N13.81973 Radiation

Protection in Uranium Mines.

5.2 External Radiation Exposure

5.2.1 The area dosimeters will be thermoluminescence dosimeters (TLD's)provided by Eberline Instrument Corporation. The dosimeters will bepositioned in specific plant areas, office trailers, wellfields, and ponds, and

will be exchanged on a quarts:rly cas|s. Specifications for the area TLD's4

are as follows:

|. SPECIFICATIONS FOR THE EBERLINE INSTRUMENTS CORPORATION

.

- DOSIMETERSi

| Detector LiF TLD chips.

2Detec' t Shields One 10 mg/cm ;

One 285 mg/cm2

SensicAvoy 1mRRange I mR - 1000 R

Exchange Frequency Quarterly

The results r ported fro,m Eberline are in millirem of penetrating radiationand milliren i nonpenetrating radiation. 'the results of the areadosimeters wiu >e kept on file at the plant site. |

5.2.2 Personnel Dosimeters

Employee exposure will be monitored using personnel dosimeters. 'Ihe

personnel dosimeters will be exchanged quarterly. Specifications on thepersonnel dosimeters are the same as shown above for the area dosimeters. ;

An action level of 25% of the maximum permissible exposure will beenforced.

-44- Revised 9/8/87

- _ _ _ - _ _ _ _ _ _ _

_ _ _ - _ - - _ - - _ _ - _ _ _ _ - _ - - _ _ _ _ -- _ __ _ - _ _ - __ _ _ _ _ _ - _ _ _ _ _ _ - - _ _ _ _

'-

y

Ol

We results reported from Eberline are in millirem of penetrating radiation

[ and millirem of nonpenetrating radiation. De results of the personnel'

dosimeters will be kept on file at the plant site.

- 5.2.3 Gr.mma Surveys

Gamma surveys will be conducted on a monthly basis at specific locationsI.| through the plant. The measurements are made with a properly calibrated

gamma survey meter, held approximately at waist level and twelve inchesfrom any surface. The results of the surveys are recorded on the " Record

of Gamma Radiation Suryeys" Figure 5.5, along with the date, name of the

inspector, survey instrument serial number, and calibration date. R ese

results are then used to insure plant areas are properly placarded in'

accordance with 10 CFR 20. Additionally, the gamma survey results willbe compared with TLD results for consistency.

5.3 Bioassay Program

All plant personnel are included in the bicassay program. The program ismaintained by the Health physics Technician and the type of bioassay to be ,

performed on a routine basis is the urinalysis. All employees whose routine work

assignment requires them to enter areas where potential yellowcake inhalation

exists will be sampled on a quarterly basis. All other employees will be sampled

on an annual basis. A baseline urinalysis will be performed on all employees

prior to their initial assignment at the plant. In the event of a suspected overexposure to yellowcake dust a sample will be collected after a 48 hour interval

and analyzed as soon as possible. Records will be maintained to document the

sample collection and analysis dates as well as the individuals record to allow the

most recent results to be compared to the employee's previous history (Figures 1

5.6 and 5.7).

-45- Revised 9/8/87

. . . ... I

- , - - - _ _ __ -_ - - - _ _ _ _ _ _ - - _ - - -_

O

Lg

5.4 Surface Contamination

The areas of potential contamination at the Crow Butte pilot plant will be.

associated with the precipitation circuit, slurry storage areas and to a_

lesser extent the recovery circuit. These areas will be designatedrestricted. Eating, drinking and smoking by employees in these areas will

be prohibit,ed. Other plant areas will be considered unrestricted.,

The removable surface contamination will be measured by using a smeari test. A smear test will be performed by wiping a 100 cm2 area of the

surface to be tested with a dry filter paper. The filter paper will then betaken to the laboratory where the alpha activity on the surface of thefilter is measured. The results will be expressed in units of dpm/100 cm2,

~

The instrument used for measuring the alpha activity on the filter is the.same instrument used to measure alpha activity on air particulate filters. .

The limits for surface contamination at the Crow Butte R&D Project arethose shown in Table 5.2. -

Employees who enter an unrestricted area from a restricted one will be

required to survey themselves for surface contamination and ensure that

they meet the guidelines needed to leave a restricted area. This -

monitoring will consist of a visual examination to detect any yellowcakeand a survey meter to ensure that any suspected contamination is below

the acceptable limits. In the event that a nonroutine operation is required

and the potential for contact with the product is present, then awaterproof suit will be worn by the operators. If this clothing becomescontaminated in the course of the operation the clothing may be rinsed offin a controlled area.

Equipment that must be removed from restricted areas for maintenance or

repair must be thoroughly decontaminated. Surface contamination ofequipment, both internal and external, will be reduced to acceptable levels

to prevent the possibility of contamination in the maintenance shops.

1

-47- Revised 9/8/87

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5.8 Exposure Calculations

As ' described in previous sections the ' concentration of yellowcake and. radon daughters in the air will be monitored on a routine schedule, the

7 frequency to be based on the concentration present and the propensity for

I. change. These values will be used in conjunction with occupancy times to

, determir.e employee exposure. The occupancy tiene for routine operations

may be an actual measurement of the time or may be,ol$tained from a time

study. The occupancy times for nonroutine operations will always be from

f actual measurement of the time involved in the operation. The intake of

yellowcake by individual employees will be calculated by using thefollowing equation:

n

1 : b ( Cjt as per Reg. Guide 8.30

i=1

Where:

I = uranium intake uCi

b = breathing rate,1.2 m3/hr

C = average concentration of uranium in breathing zone air during time t1,1 .,

uCi/m3

t; = time of exposure to average concentration Cj, hrsn = number of exposure periods

The exposure to radon daughters will be calculated using the followingquotation:

j Ibg GuideE = 173 y,_ ggWt 8.30

Fonnati=1

'Where:

E = annual radon exposure, working-level months

W = average number of working levels in the breathing zone air duringtime tj, WL

ti = time of exposure to average concentration W , hrs

173 = conversion from working-level hours to working-level months

n = number of exposure periods

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c:.

3. Facility Provided Protection

a. Cleanliness of working space

b. Safety designed features for- process

equipment

c. Ventilation systems and effluent controls

d. Standard operating procedures

.' e. Security and access control to designated 'areas

4. Health Protection Measurements

a. Measurement of airborne radioactive material

b. Bloassays to detect uranium (urinalysis andinvivo counting)

c. Surveys to detect contamination of personnel

'[ and equipment

d. Personnel dosimetry

5. Radiation Protection Regulations

a. Regulatory authority of NRC, MSHA and state

b. Employee rights in 10 CFR, Part 19,

6. Emergency Procedures.

A written test with questions directly relevant to the principals of-

radiation safety and health protection in the R&D facility covered in thetraining course shall be given to each worker. The instructor will review

the test results with each worker and will discuss incorrect answers to thequestions with the worker until worker understanding is achieved. Workers

who fail the exam shall be retested and test results will remain on file...

|- Each permanent worker at the R&D facility will be provided with anabbreviated retraining course annually. The successful completion of the

retraining course will also be maintained on file. Retraining shall include

relevant information that has become available during the previous year, a

review of safety problems that have arisen during the year, and changes in

regulations and license conditions, exposure trends and other currenttopics.

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