ML20207N570
| ML20207N570 | |
| Person / Time | |
|---|---|
| Site: | 07000854 |
| Issue date: | 03/19/1987 |
| From: | Harrison J ISOTOPIC ANALYSIS, INC. |
| To: | |
| Shared Package | |
| ML20205C186 | List: |
| References | |
| 461440, NUDOCS 8810190223 | |
| Download: ML20207N570 (19) | |
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r Harch 15, 1987 1.
Identification,of Applicant Isotopic
- Analysis, Inc was incorporated in the State of Oklahoma on December 24, 1975 by the Secretary of State.
The office and laboratory of Isotopic
- Analysis, Inc.
are located at 8335 East Sist Street,
- Tulsa, Oklahoma 74145.
The me,iling address is p.
G.
Box
- 35622, Tulsa, Oklahoma 74153.
P The officers of the Corporation are:
Name and Title Address citizenship Jon W.
Harrison 4993 East 26th Place USA President and Operations Tulsa, Oklahoma 74114 Manager i
Thomas C. Westmoreland 5959 South Birmingham Ave USA Vice President Tulsa, Oklahoma 74105 Richard W. Johnson 4808 S.
267th East Ave USA Secretary-Treasurer and Broken Artcw, Oklahoma Mass Spectroscopist 74012 Isotopic
- Analysis, Inc.
is completely owned by the above three officers, and no additional stock has been issued.
No control is exercised over the applicant by any
- client, j
foreign corporation, or foreign government.
2.
Activity to be Performed l
This facility has been established to provide mass spectrographic analysis of nuclear materials.
The special nuclear materials received under this license shall consist of (1) samples of enriched uranium from core manufacturers and from prime contractors engaged in monitoring military and civilian reactor programs.
(2) a small quantity of U-233 for use as an internal standard in trace analyses, and i
(3) NBS uranium standards of various enrichment levels.
The i
processing of this material will consist of four steps:
(1) chemical separation of the uranium from interfering l
elements by extraction or ion exchange techniques, (2) loading microgram quantities of the purified uranium i
onto filaments for analysis on the mass spectrometer, l
(3) analysis of the material on the mass spectrometer, and j
(4) salvage of unused samples for return to the customer if
(
recoverable :r for burial if non-recoverable.
l l
All processing of enriched uranium shall be done in chemical hoods.
All processing of U-233 shall be done in glove boxes up to the point where quantities less than 50 micrograms are to be handled.
These quantities shall then be handled in chemical hoods over absorbent paper.
l l
l l
Page 1 of 14 i
i
' March 15, 1987 This operational activity shall be conducted at 8335 East Sist Street, Tulsa, Oklahoma 74145.
3.
Duration of License r
The license is requested for a period of five (5) years.
4.
Type and Quantity of special Nuclear Material Uranium enrilhed in the 235 isotope will be received in solid form as oxide, alloy or pure metal, and in solution as nitrate or sulfate with various impurities such as
The total quantity of enriched uranium possessed at any one time will not exceed 200 grams of Uranium-235.
Uranium-233 shall be received in solid form as
- oxide, or nitrate solution.
A maximum of 10 grams shall be possessed i
at any one time.
l r
5.
Qualifications of Supervisory and Technical Personnel Mr.
Jon W.
harrison shall be designated operations Manager and Radiation Safety Officer.
Mr. Harrison possesses a B.S.
Degree in Chemistry, and 22 years experience working with Special Nuclear Materials.
He was employed for 10 years at Kerr McGee Nuclear Corporations' Cimarron
- facility, Crescent, Oklahoma where he held the position of Supervisor of the Mass Spectrographic Laboratory.
He has been t
employed by Isotopic Analysis, Inc. for the past 11 years.
Mr.
Richard W. Johnson shall be designated Security Officer and Document Custodian.
Mr. Johnson has 20 years experience working with Special Nuc1 car Materials, including 10 years with the Tulsa operation of Avco corporations' Electronics l
- Division, in the Mass Spectrographic Services Laboratory.
He has been employed by Isotopic Analysis, Inc. for the past 11 years.
i Mrs.
Grace Williams is designated as office
- Manager, L
Document custodian, and alternate Security Officer.
t Mrs. Williams has been employed by Isotopic Analysis for 5
[
- years, j
L 6.
Facilities and Equipment Reference drawings of the laboratory are attached as Drawings 1 and 2.
These drawings indicate the location of the chemical
- hoods, glove
- boxes, ventilation
- system, i
j airborne radioactivity sampling stations, sample storage t
- areas, fire-fighting equipment, holding
- tank, airlock,
- shower, laundry equipment, mass spectrometer, and personnel monitoring stations.
Page 2 of 14 t
I March 15, 1987 a.
General Construction Details The facility is divided into four areas as follows (Drawing 1):
(1) office area, (2) cold laboratory, (3) instrument
- room, and (4) the hot laboratory for radioactive material preparation.
Outer walls in all areas are of windowless concrete construction (except for windows in office area) with sheet rock interior surfaces.
Ceilings are of precast metal panels with caulked joints and asphalt and gravel outer surfaces.
For security reasona, the Restricted Area walls extend from floor to outer ceiling up through the acoustical ceiling drop on all four sides.
This was also necessary in the hot laboratory because it is a
negative pressure area.
The entire area is of fireproof construction.
All
- services, ducts, and joints have been scaled with plaster or caulking with a phenolic sealing compound to render them dust and air tight.
The floor of the hot laboratory and air lock is covered with an epoxy coating which is scrubbed weekly.
The floor of the instrument room is covered with vinyl tile, which is scrubbed weekly.
The walls of the hot laboratory are covered with two coats of oil base enamel paint for scrubability.
There are no floor drains in the hot laboratory.
All water from the hot laboratory and washer laundry is transferred to a 300 gallon holding tank in the hot laboratory area.
Sampling outlets are provided which permit analysis of all effluent before it is released into the sanitary sewer system.
(Permissible dumping
'.imits are discussed in Section 7.g.)
All cooling water for the hot laboratory analytical equipment is provided by a closed loop refrigeration unit.
The water from this unit shall be transfered to the holding tank if a change is necessary.
b.
Personnel Monitoring Stations and Clothes Changing Personnel monitoring stations are located between the hoods in the hot laboratory and at the exit to the instrument room as shown in Drawing 1.
Personnel leaving these areas are required to monitor their clothing and person with the Ludlum alpha survey meters described in Section 6.c.
(2) Maximum permissible contamination is called out in Section 7.c.
Covered metal containers and plastic bags are provided for contaminated clothing.
Section 7.c.
calls out procedures and limits for changes and laundering or disposal of contaminated clothing.
c.
Clove Boxes, Hoods and Ventilation Page 3 of 14 UV@
March 15, 1987 Two chemical fume hoods are located in the hot laboratory.
These are Lab-Con-Co Advance 70 Fiberglass and epoxy units designed especially for handling radioactive materials.
The hoods are of constant volume minimum turbulence design and are operated at a minimum linear face velocity of 150 FPH.
A line of glove boxes is located in the preparation area.
One of these boxes is operated without gloves as a minimum opening box.
The glove boxes are operated at a
negative pressure of 1/2 inch of water relative to the room and with an air change of 50 cfm per three-foot box.
The minimum opening box is oprated at a
i minimum linear face velocity of 150 FPM.
Details of the exhaust and supply system, as well as the filters used, are shown in Drawing 2.
The incoming air in the hot lab is filtered through absolute filters which prevent backstreaming in the event of an exhaust blower failure.
The instrument room exhausts through the air lock into the hot lab.
The door between the airlock and the hot lab is fitted with special gasketing and an absolute filter so that it may be scaled off to prevent backstreaming in the event of an exhaust blowar failure.
The system is designed to j
maintain a negative pressure of 0.06 inches of water in the airlock and 0.25 inches of water in the hot lab relative to the instrument room.
I The hot lab exhausts through the hoods and glove boxes to a
pre-filter and an absolute filter to a separate duct and blower which serve only this area.
Two i
emergency switches are located in the hot lab (one switch) and the instrument room (one switch) to permit emergency shutdown of the exhaust blower.
The pre-filter in the exhaust system is located at the exhaust vents of the individual hoods.
The absolute filters are located just ahead of the exhaust blower.
The absolute filters discussed in this section are replaceable Cambridge filters capable of removing 99.95%
of particulate matter 0.3 microns or larger.
All filters have Underwriters Laboratory Class II fire i
resistance ratings.
All pre-filters are the rough Fiberglas typc used to prolong the useful life of the absolute filter.
The pre-filters are checked monthly and changed if they appear to need so.
In the past, our type of laboratory operation has found it necessary to change the absolute filters usually on an annual basis, the linear face velocity of the hoods and glove boxes is checked monthly to determine the effective operation of the filtering system pursuant to Regulatory Guido 8.24.
Page 4 of 14
March 15, 1987 d.
Air Sampling Stations Eight (8) permanent air sampling stations are located as shown in Drawing 1.
These stations provide adjustable flow rates and are fitted with quick-change
- heads, in
- addition, a portable air sampler (STAPLEX High Volume) is available for evaluation of new operations and special hazards such as spills or glove failures.
Air sampling schedules and maximum permissible levels are discussed in Section 7.d.
c.
Radiation Instrumentation (1)
Personnel Monitoring Devices Manufacturer:
Eberline Type Instrument:
Thermoluminescent Badge Sensitivity:
Beta-Gamma When Checked:
Monthly (Eberline will read badges and provide exposure reports)
(2)
Radiation Protection Instruments DescMiption Radiation Detected Range Ludlum Scalet/Ratemeter Alpha, Beta 0 to 10 counts with nample IIolder and gas proportional detector Model 2200 Technical Associates Alpha, Beta 0 to 10 counts Proportional Gas Flow Counter Lc31um Model 2 Alpha, Beta, 0-100K cpm, Portable Surve)..eter Gamma 0-50 mR/hr, in 4 ranges Ludlum Model 12 Alpha 0-5K cpm, in 4 Portable Survey Meter ranges Ludlum Mode 16 Alpha, Beta, 0-500K cpm, Portable Earvey Meter Gamma 0-250K mR/hr, in 4 ranges STAPL2X liigh Volume Not Not Applicable Air Sampler Applicsble At least one of the Beta-Gamma Murvey meters shall be calibrated once each calendar quarter by an NRC regulated facility using a Ceatum-137 source.
The Alpha Survey meters and the Alpha-Beta gas proportional counters shall be calibration checked in-house each day that they are in use, using Uranium Alpha standards prepared by Eberline Instrument Corporation, Page 5 of 14
i MOrch 10, 1987 l
Albuquerque, New Mexico, and traceable to NBS standards.
i i
f.
Fire Fighting Equipment j
Three (3) 15-pound carbon dioxide fire extinguishers are located as shown in Drawing 1.
Because metal quantities shall not exceed 1.0 gram per sample, it is
.It that no metal extinguishers shall be required as long as processing is limited.
g.
Protective Clothing Laboratory coat, coveralls, surgeons
- caps, booties, respirators, and rutber gloves are provided for each l
individual.
Use requirements and change schedules are discussed in Section 7.c.
h.
Storage Area l
Enriched uranium sampics are stored in a locked metal NRC approved safe in the sample preparation area.
I This cabinet is fabricated of steel and has a
baked enamel
- finish, all samples are stored in polyethylene bottles or glass ampules, i.
General Supplies f
Absorbent paper, plastic bags, chemwipes, masking tape, metal cans, and laboratory trays are provided for use where necessary for contamination control.
i 7.
operational and Radiation Control Procedures a.
Receipt of Samples Samples received shall include uranium as solids and as f
acid solutions.
Samples shall be individually I
contained in scaled glass or polyethylene bottles.
The i
individual samples shall be packed inside a container with vermiculite or other absorbing material separating them.
The container shall be plainly marked with appropriate radiation warning signs.
This container shall then be packed in an approved cardboard,
- wooden, or metal shipping container.
In all cases, packages i
received which contain uranium samples must comply with all applicable NRC regulations pursuant to Title 10,
[
Code of Federal Regulations, part 71.
The samples will be material from fuel manufacturers which has no t
appreciable beta-gamma contamination.
When received, the shipping container shall be monitored and smeared j
(unless the package contains an exempt quantity of material as specified in Title 10, Code of Federal i
Regulations, Part 20, Paragraph 20.205) to assure that the beta-gamma rate does not exceed 200 mr/hr at the
[
i page 6 of 14
j'
+
Harch 13, 1987 surface and that the fixed and removable alpha contamination does not exceed 500 DPH per 100 square centimeters.
When the container is known to meet these
- criteria, it will be taken into the sample preparation I
toom.
The sampics shall then be placed in the previously described storage safe until ready for analysis.
The shipping containers shall be monitored fnside and out and, if necessary, decontaminated to below 200 mr/hr beta-gamma and 10 DPM por 100 square centimeters alpha.
Containers and packing material which cannot be decortaminated shall be discarded as hot waste for burial at an approved burial site.
[
b.
Processing of Material f
i Analyses involving two types of special nuclear materials shall be carried out.
These are (1) isotopic analysis of enriched uranium, and (2) trace analysis i
for enriched uranium using U-233 as an internal standard.
(1)
Enriched Uranium Laboratory coats shall be worn or preparation of these samples.
Respirators, coveralls, booties, surgeon caps, and rubber gloves shall be available for use when cleaning up spills and other operations where air and surface contamination levels exceed those called out in Section 7.d.
Samples in batchts not to exceed ten (10) samples shall be removed from the storage cabinet and taken to the chemical hood.
(Individual samples as received will ususally not exceed 1.0 gram contained uranium.)
Appropriate aliquots (0.05 to 0.25 gram) will be removed from the sample container for purification.
The unused sample shall be returned to the storage safe.
The uranium in the sample aliquots shall be purified by acid
- fuming, liquid-liquid extraction, ion exchange or electro-deposition.
The end product will be a solutJon of pure uranyl nitrate.
This solation shall be transferred to the previously described minimum opening glove box where up to 100 micrograms of the uranyl nitrate will be evaporated to dryness on a tungsten filament.
The loaded tungsten filament shall be tranoferred to the lodding hood in the mass spectrometer room in a
closed disposable ice cream carton.
The filament shall be loaded into the mass spectrometer source for analysis.
After the analysis is completed, the spent filament shall be removed from the mass spectrometer and i
discarded in a covered container for eventual l
shipnent to an approved burial site as non-i recoverabic waste.
The unused sample and any recoverable liquid waste resulting from its i
Page 7 of 14 i
Merch 15,'1987 purification shall bo salvaged into a polyethylene salvage bottle and returned to the customer for purification and recovery.
Shipments of radioactive material shall be made in accordance with all applicable NRC and DOT regulations.
Any low level non-recoverable water solutions shall be discardud into a screw cap polyethylene salvage container within the hood.
When
- full, the container shall be analyzed.
If the radioactivity level does not exceed the limits called out in Section 7.g.,
it shall be dumped in the sanitary sewer.
If the level exceeds these
- limits, it shall be concentrated and shipped to a licensed burial site.
All solid waste, absorbent
- paper, and salvage shall be placed in the proper containers and work surfaces decontaminated below the levels called out in Socion 7.d.
before proceeding with the next batch of samples.
(2)
Trace Uranium Jrotective clothing requirements for this operation are the same as tho'ae described for e.;riched uranium.
The major difference in this process involves the preparation of the U-233 internal standard.
The desired quantity of U-233 shall be weighed out in the glove oox in the uranium preparation room.
it shall then be dissolved in nitric acid and diluted t,o a solution concentration of approximately 200 micrograms U-233/ml.
Up to 10 aliquota containing 200 micrograms U-233 cach shall then be transferred into polyethylene centrifuge tubes.
These polyethylene centrifuge tubes shall be capped and transferred to the chemical fume hood.
Aliquots of unknown sample containing up to 50 micrograms of enriched uranium shall be added to each beaker.
From this point on, the processing is identical to the previously described enriched uranium.
The total purified uranium is evaporated to dryness on the filament for analysis in the mass spectrometer.
The remaining U-233 standard solution is retained for future use.
At no time will the total U 233 content of the box exceed in
- grams, c.
General Procedures Protective disposable laboratory coats for uranium processing will be discarded whenever monitoring indicates as alpha contamination level grea*.er than 50 DPM per 100 square centimeters.
These laboratory coats will never be worn outside the restricted area Page 8 of 14
Harch 15, 1987 1
described in Section 7.h.
If, during personnel monitoring, protective clothing is i
found to be contaminated in excess of the above limits, the following procedures shall be followed.
If contamination is not in excess of 1000
- CPH, the individual shall proceed to the change area and change
- clothing, placing the contaminated clothing in the l
plastic bag provided.
If contamination in excess of j
1000 CPM is observed, a change of clothing shall be j
1 brought to the individual i t.
the sample preparation I
toom.
Any persoal clothing with contamination of less than 5000 CPM shall be placed in a plastic bag for special laundering and monitoring.
Clothing contaminated in excess of 5000 CPM shall be placed in t
a plastic bag and sealed for eventual shipment to a
licensed hurini site.
An immediate check of the preparation room shall be performed to determine the source of the contamination whenever contaminated O
clothing in excess of 50 DPM per 100 square centimeters l
is observed.
Respirators shall be made readily available to all personnel.
Respirators shall be worn during box glove i
- changes, hood filter
- changes, in the event of any i
uranium spill outside the enemical hoods or glove i
- boxes, or whenever the routine or special air sample checks indicate and airborne radioactivity concentration above the maximum permissible concentration for uranium in a
restriced area as specified in 10 CFR, Part 20, Paragraph 20.103.
In 1
- general, respirators shall be
- selected, stored, j
maintained and used pursuant to Regulatory Guide 8.15.
1 i
Samples shall be processed in batches as previously j
j described.
All salvage and cleanup operations shall be 7
i completed for one batch before the next batch is L
1 started.
A portable alpha survey meter will be placed in the uranium preparation area, and another in the mass spectrometer room to permit immediate checking of
- hands, gloves, equipment, and work surfaces when l
required.
d.
Radiation Surveys Eight (8) permanent air sampling stations are provided, I
as described in Section 6.d.
The air sampling j
stations shall be in operation whenever personnel are working within the Restricted Area.
The filter heads are changed and the filers analyzed on a weekly basis.
l The sampling head flow rate shall be measured and adjusted weekly, and corrections for accumulative flow l
rate loss shall be applied pursuant to Regulatory Guide j
8.24, Section C.l.3..
Maximum airborne radioactivity levels shall not be permitted to exceed 1 x
10-g0 l
)
Page 9 of 14
March 15, 1987 microcuries per m1, the maximum permissible concentration for Uranium-235 in Title 10,
- CFR, Part 20, Appendix B.
Respirators chall be required for any emergency, such as a spill waere levels in excess of these limits are known to exist for short periods of time.
Any operation such as a new operation, bag or glove
- change, which could result in exceeding these limits shall be monitored with the portabic air sampler.
Air samples of the effluent air from the hot lab exhaust system shall be taken at least once a week over an 8
hour work day to assure that the airborne radioactivity in the effluent air does not exceed 4 x
10-12 Aci/ml for uranium-235 as stated in Title 10, CFR, Part 20, Appendix D.
Weekly smears of all floors and working surfaces shall be taken.
Fixed and removable aplha contamination levels shall be held to the lowest possible level, but removable alpha contamination levels shall not be permitted to exceed 200 DPM per 100 square centimeters j
in any case.
Smears shall be scheduled so that they s
are taken just before the weekly scrubbing.
All scrub water shall be dumped into the hot lab sink for 4
transfer to the holding tank to guarantee that no effluent can be released without first being analyzed.
i The scrub equipment used in this area shall not be used for other areas of the facility.
The radiation survey program shall be implemented in accordance with the "as low as is reasonably achievable" (ALARA) philosophy, and with reference to Regulatory Guides 8.10 and 8.25.
Permanent records of the results of all radiation surveys shall be maintair,id.
e.
Per9onnel Monitorino All personnel working in the Restricted Area shall be required to wear film badges.
These badges shall be char.ged and evaluated on a monthly basis.
Bioassays by urinalysis will be performed pursuant to Regulatory Guide 8.11 for Restricted Area employees initially upon employment, quarterly thereafter, and upon termination of employment.
Additional bioassays shall be reques:ed if there is reason to suspect high exposure.
Examples of incidents requiring additional bioassays are spills, high air counts, and cuts while handling special nuclear materials.
Permanent records of the results of those surveys shall be maintained for each individual.
Monitoring meters shall be provided in the locations Page 10 of 14
March 15, 1987 previously described in Section 6.b.
Alpha survey meters are used at these stations.
Personnel shall be required to monitor their protective clothing whenever leaving the sample preparation room for the mass specrometer room.
Personnel shall be required to monitor their personal clothing and all exposed areas of the body whenever leaving the restricted area as decignated in Section 7.h.
for other areas of the building.
Contamination icvels of personal clothing shall not exceed 50 DPM per 100 square centimenters.
Contamination levels on skin shall not exceed 0 DPM per square centimeters.
Decontamination of skin shall be done in accordance with Regulatory Guide 8.24, Section C1.6..
f.
Decontamination of Equipment No equipment or materials shall be removed from the restricted area described in Section 7.h.
unless monitored by the Radiation Safety Officer or his assistant and found to have less than 50 DPM per 100 square centimeters total fixed and removable alpha contamination.
All waste material to be shipped to a licensed disposal site shall be monitored and inspected by the Radiation Safety Officer or his assistant.
No such materials shall be removed from the restricted area unless accompanied by a signed statement from the Radiation Sr.fety Officer or his assistant that the packaging and contamination levels conform to standards established by the DOT and Title 10,
- CFR, PA:t 20.
Release of any equipment or material for unrectricted use shall be in accordance with Annex A "Guidelines for Decontamination of facilities and Equipment Prior to Release for unrestricted Use or Termin3 tion of I.icenses for Byproduct, source or Special Nuclear Material," dated November 1976.
g.
Waste Disposal As previously described, the laundry water and hot lab sink waste shall be held in the holding tank.
When
- full, the contents of the holding tank shall be analyzed on the previously described proportional gas flow counter.
If the total alpha activity of the holding tank does not exceed 3 x 10-5 microcuries per m1, the maximum permissible concentration for u Unm-235 in Title 10, CFR, Part 20, Appendix B, the c s
of the tank shall be released into the sanitary sc.
This material shall be further diluted by a factor of 10 to 1 by a quantity of water released into the sewer by the applicant.
A permanent record of the results of these analyses will be maintained.
Page 11 of 11
March 15, 1987 All non-recoverable waste which exceeds the contamination levels permissible for uranium-235 established by Title 10, CFR, Part 20 shall be packaged l
and shipped to a NRC approved burial site for disposal.
l The packaging and shipping of this waste shall be in accordance with all applicable NRC requirements of 10 i
- CFR, including Parts 19 through 71, all applicable DOT requirements of 49 CFR, including Parts 170 through 179, and pursuant to I E Bulletin No. 79-19.
h.
Destricted Area The in s t r u mer.t room and the hot lab area shall be designated as the "Restricted Area".
The applicant limits access to this area to authorized personnel only.
These areas are posted in accordance with 10 CFR, Parts 19 and 20.
o 1.
Security Against Unauthorized Use of Special Nuclear l
~~
Materials' All uranium samples shall be stored in the previously i
described storage safe.
The cabinet shall be locked except when samples are being transferred.
The sample l
preparation hot lab is locked except when under the surveillance of authorized laboratory personnel.
Keys and combinations to the storage safe and sample preparation room shall be maintained only by laboratory supervision.
The Restricted Area is also locked with NRC approved combination locks during off-shift hours to prevent unauthorized entry.
j.
Indoctrination Procedures Copies of the Isotopic
- Analysis, Inc.,
Standard i
Procedures for Radiation Safety, individual processing procedures, fire fighting and emergency procedures, and l
selected reading topics describing general procedures t
for handling radioactivity shall be required reading for all new personnel assigned to this area.
Annual reviews and audits of all procedures assure periodic reinstruction of all personnel.
Records of all audits shall be maintained, k.
Fire and Emerger.cy Procedures To limit the likelihood of fires, all flammable organic solvents shall be stored in one specific metal storage cabinet.
No combustible materials shall be stored in j
the chemical hoods or glove boxes.
Most of the material received will not be in metallic form.
i However, the following procedures have been established l
for handling metal.
Total uranium metal content in a i
hood shall be limited to 3 grams in individual and separated aliquots of 0.3 grams.
All metal shall be i
Page 12 of 14
Horch 15, 1987 handled in platinum crucibles which shall contain the metal in the event of fire.
The following emergency procedures shall be adopted in the event of a major spill or fire within the process arcat (1)
Shut down all exhaust fans within the immediate laboratory area.
(This is done with either of two master switches located within the area as shown on Drawing 1.)
(2)
Evacuate the preparation area.
(3)
Notify the Radiation Safety officer and seal off the area to prevent unauthorized entrance.
(An
+
emergency call list is posted on the door outside t
the restricted area and at the event of an emergency, this list contains the
- names, l
addresses, and telephone numbers of the members of
~
the damage control team and the order in which they are to be called.)
l (4)
A damage control team under the direction of the Radiation Safety Officer will re-enter the
- area, if
- safe, to combat the emergency.
Pevsonnel l
assigned to the damage control team have been instructed in the methods of fighting fires and I
warned of the dangers involved in pressurizing i
glove boxes and hoods with extinguishing
- agents, Decause of the small quantities of metal involved, fire control efferts of metal fires will be i
directed primarily to isolating the material rather than extinguishing it.
j Copies of the emergency procedure are pro:ided to local e
fire fighting and police rescue units.
Members of the L
local fire department and police rescue units have been I
guided through the facility and the potential hazards i
discussed with them.
l 1.
Radiation Safety Officer - Duties and Responsibilities j
l The Radiation Safety Officer shall be responsible for all operations related to radiation safety, including i
but not limited to the following:
1.
Personnel indoctrination and training in areas related to radiation safety.
2.
Operation and calibration of radiation protection l
equipment and instrumentation.
3.
Operation of ventilation and air filtration systems.
4.
Radiation Surveys.
i 5.
Personnel monitoring.
6.
Fire and emergency procedures, l
f Page 13 of 14 r
March 15, 1987 7.
Waste disposal.
8.
Effluent monitoring.
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