ML20150B355
| ML20150B355 | |
| Person / Time | |
|---|---|
| Site: | 07000854 |
| Issue date: | 12/01/1976 |
| From: | ISOTOPIC ANALYSIS, INC. |
| To: | |
| References | |
| NUDOCS 7811010256 | |
| Download: ML20150B355 (56) | |
Text
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December 1, 1976 Nuclear Regulatory Commission Washington, D.C.
20555 Attn: William A. Nixon, Div. of Fuel Cycle and Material Safety Gentlemen:
Request for amendment is hereby applied for to Special Nuclear Material License SNM 791 which was last applied for on January 16, 1976. The amendment requested is made due to changing the location of our labor-i atory facility.
The following information is submitted in sextuplicate in fullfillment of the requirements of Section 70.22, Title 10, Code of Federal Regula-tions, Part 70, "Special Nuclear Material".
1.
Isotopic Analysis, Inc. was incorporated in the State of Oklahoma on December 24, 1975 by the Secretary of State.
a 1
The office and laboratory of Isotopic Analysis, Inc. presently located at 10700 E. Independence St., Tulsa, Oklahoma 74115, will be relocated on or about December 15, 1976 to 8335 East 51st St.,
Tulsa, Oklahoma 74145. Our new mailing address will be P.O. Box 35622, Tulsa, Oklahoma 74. 35.
The officers of the Corporation are:
Name and Title Address Citizenship Thomas C. Westmoreland 5609 S. Yorktown Pl.
USA President and Operating Tulsa, Oklahoma 74105 Manager Jon W. Harrison 5819 E. 21st Pl.
USA Vice President & Chemist Tulsa, Oklahoma 74114 Richard W. Johnson 4808 S. 267th E. Ave.
USA Secretary-Treasurer Broken Arrow, Oklahoma
& Mass Spectroscopist 74012 Isotopic Analysis, Inc. is completely owned by the above three officers. No additional stock has been issued.
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l Nuclear Regulatory Commission Page 2 December 1, 1976 No control is exercised over the applicant by any client, foreign corporation, or foreign government.
2.
Activity to be Performed This facility has been established to provide mass spectrographic analysis of nuclear materials. The special nuclear materials received under this license will consist of (1) samples of enriched uranium, Uranium-233, and plutonium from core manufacturers I
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 (3) NBS uranium and plutonium standards of various enrichment levels. The pro-cessing of this material will consist of four steps:
(1) chemical separation of the ruanium or plutonium from interfering elements by extraction or ion exchange techniques, (2) loading microgram quantities of the purified uranium or plutonium onto filaments for analysis on the mass spectrometer, (3) analysis of the material on the mass spectrometer, and (4) salvage of unused samples for return to the customer if recoverable or for burial if non-recoverable.
All processing of enriched uranium will be done in chemical hoods.
All processing of U-233 and plutonium will be done in glove boxes up to the point where quantities less than 50 micrograms are to bc handled. These quantities will then be handled in chemical hoods over absorbent paper.
This operational activity will be conducted at 8335 East 51st St.,
Tulsa, Oklahoma 74145.
3.
Duration of License The amended license is requested for a period of five (5) years.
4.
Type and Quantity of Speci 1 Nuclear Material Uranium enriched 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 iron, chromium, nickel, and circonium. The total quantity of enriched uranium possessed at any one time will not exceed 200 grams.
Uranium-233 will be received in solid form as oxide, alloy or pure metal, and in solution as nitrate or sulfate with various impurities such as iron, shromium, nickel, and zirconium. A maximum of 10 grams will be possessed at any one time.
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'o Nuclear Regualtory Commission Page 3 December 1, 1976 Plutonium will be received as metal, oxide, alloy, and as sulfate, nitrate, or chloride solutions. The samples will contain various metallic impurities such as iron, nickel, chromium, and zirconium.
A maximum of 3 grams will be possessed at any one time.
I 5.
Qualifications of Supervisory and Technical Personnel Mr. Thomas C. Westmoreland is designated Manager, Security Officer, and Alternate Radiation Safety Officer of the laboratory.
Mr.
l Westmoreland possesses a B.S. degree in Chemistry and has twelve (12) years experience as an analytical chemist. He was employed at the Avco/ Tulsa facility for four (4) years in the Mass Spectro-graphic Laboratory. During that time, he has been trained in managing the overall laboratory operation.
Mr. Richard W. Johnson, Lead Mass Spectroscopist, is designated Alternate Security Officer.
Mr. Johnson has eleven (11) years experience in operating various functions of our laboratory.
Mr. Jon W. Harrison is Lead Chemist and the Radiation Safety Officer for the laboratory.
Mr. Harrison had had eleven (11) years exper-icnce workit' with special nuclear materials at Kerr-McGee Corpora-tion's Cimmaron Nuclear Facility and possesses a B.S. degree in l
Chemistry.
Messrs. Westmoreland, Johnson, and Harrison are designated qualified
" Users" of the special nuclear material.
6.
Facilities and Equipment Plan and elevation drawings of the laboratory are attached as Drawings 1 and 2.
These drawings indicate the location of the chemical. hoods, glove boxes, ventilation system, airborne reaioactivity sampling stations, sample storage areas, firefighting equipment, holding tank, airlock, shower, laundry equipment, mass spectrometer, and personnel monitoring stations.
a.
General Construction Details The facility is divided into four areas as follows:
(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 win-
{
dows in office area) with sheet rock interior surfaces. Ceilings I
are of precast metal panels with caulked joints and asphalt and i
gravel outer surfaces. For security reasons, the Restricted Area
Nuclear Regulatory Commission Page 4 December 1,1976 walls extend from floor to outer ceiling up through the acousti-cal ceiling drop on all four sides. This was also necessary in the hot laboratory because of it being 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 a seamless phenolic 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 scrubbility. There are no floor drains in the hot laboratory. All water from the hot laboratory and washer laundry is transferred to a 350 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 limits are discussed in Section 7.g.)
All cooling water for the hot laboratory, analytical equipment is provided from a small, portable closed loop refrigeration unit.
The water in this unit is drained into the sink when a change is necessary. The cooling water for the mass spectrometer is pro-vided by a closed loop cooling system which cannot be contaminated by operation of the mass spectrometer. Any change in cooling water in the hot laboratory would be transferred to the holding tank.
b.
Personnel Monitoring Stations and Clothes Changing Personnel monitoring stations are located at the exit to 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 Technical Associates or Nuclear Chicago alpha survey meter described in Section 6.e. (2). Max-imum permissible contamination is called out in Section 7.c..
Covered metal containers and plastic bags are provided for con-taminated clothing. Section 7.c. calls out procedures and limits for changes and laundering or disposal of contaminated clothing.
c.
Glove Boxes, Hoods and Ventilation Two chemical fume hoods are located in the hot laboratory. These are Lab-Con-Co Advance 70 Fiberglas and epoxy units designed es-pecially for handling radioactive materials. The hoods are of
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Nuclear Regulatory Commission Page 5 December 1,1976 constant volume minimum turbulence design and are operated at a minimum linear face velocity of 100 FPM.
A line of glove boxes is located in the preparation area. Chic 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 rnininsuna opening box is operated at a rnin-inauna linear face velocity of 100 FPhd.
j Details of the exhaust and supply system, as well as the filters used, are shown in Drawing 2.
Intake air ducts supply 100%
new air from the central air conditioning to all areas. 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 blower failure. These rooms are balanced to maintain a negative pressure of 0.06 inches of wate in the airlock and 0.25 inches of water in the hot lab relative to the instrument room.
The hot lab exhausts through the hoods and glove boxes to pre-filters and an absolute filter to a separate duct and blower which serve only this area. Two emergency switches are located in the hot lab (one switch) and in the instrument room (one switch) to permit emer-gency shutdown of the exhaust blower. The pre-filters in the exhaust system are located at the exhaust vents of the individual hoods. The absolute filters are located just ahead of the exhaust blower and the glove boxes have the canister type absolute filter.
The absolute filters discussed in this section are replaceable Cam-bridge filters capable of removing 99.95% of particulate matter 0.3 micron or larger. All filters have Underwriters Laboratory Class II fire resistance ratings. All pre-filters are the rough Fiberglas type used to prolong the useful life of the absolute filter.
The pre-filters are checked quartecly 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 periodically to determine the effective operation of the filtering system.
1 Nuclear Regulatory Commission Page 6 December 1, 1976 d.
Air Sampling Stations Eight (8) permanent air sampling stations are located as shown J
in Drawing 1.
These stations provide adjustable flow rates and are fitted with quick-change heads.
In addition, a portabic air sampler (Atomic Accessories Model HV-300) is available for evaluation of new operations and special hazards such as spills or glove failures. Air sampling schedules and maximum permissible icvels are discussed in section 7.d.
e.
Radiation Instrumentation (1)
Personnel Monitoring Devices Manufactur er:
Eberline Type Instrument:
Thermoluminescent Badge Sensitivity:
B eta -G amma When Checked:
Monthly (Eberline will continue to read badges and provide exposure reports)
Manufactur er:
Bendix Corporation
~
Type Instrument:
Model 862 Direct Reading Dosimeter Sensitivity:
0-200 mr When Checked:
Twice daily (2)
Radiation Protection Instruments Des cription Radiation Detected Range Technical Associates Alpha 0-3 0,000 in Frisker Monitor 6 ranges Model FM (2 ea.)
Technical Associates Alpha -B eta -
0-50, 0-500, Juno Survey Meter Gamma 0-5000 mr/hr Model SRJ7 (1 ea.)
Technical Associates Alpha Beta 0 to 10 counts Proportional Gas Flow Counter (1 ca. )
Nuclear Chicago Alpha 0-150,000 c/m Portable and Survey Meters in 7 ranges Model 2672 (3 ea.)
Nuclear Regulatory Commission Page 7 December 1,1976 (2)
Radiation Protection Instruments (Continued)
Description Radiation Detected Range Atomic Accessories Not Applicable Not Applicable 1
HV-300 Air Sampler (1 ea.)
Nuclear Chicago B eta -G amma 0.1, 0. 3, 1, 3, Model 2650 Portable 10, 30,100 mr /hr Survey Meter Instruments are calibrated once each calendar quarter and after every replacement of components per manufacturer's instructions, using National Bureau of Standards Reference Standards. Oper -
ational check sources are affixed to each instrument for instan-taneous check of operability.
f.
Fire Fighting Equipment Three (3) 15-pound carbon dioxide fire extinguishers are located as shown on Drawing 1.
Because metal quantities will not exceed 0.3 grams per sample, it is felt that no metal extinguishers will be required as long as processing is limited.
g.
Shield i_ng Lead b:icks are provided for operations requiring shielding.
h.
Pro ective Clothing Laboratory coat, coveralls, surgeons caps, booties, res pirators, and rubber gloves are provided for each individual. Us e require-ments and change schedules are discussed in Section 7.c.
i.
Storage Area Enriched uranium samples are stored in a locked metal NRC approved safe in the sample preparation area. This cabinet is fabricated of steel and has a baked enamel finish. All samples are stored in polyethylene bottles or glass ampules.
Plutonium samples are stored in glass or polyethylene bottles on a shelf in the glove line in the preparation area. U-233 is stored in glass or polyethylene bottles in the gbve box in the uranium preparation room.
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Nuclear Regulatory Commission Page 8 December 1, 1976 j.
General Supplies Absorbent paper, plastic bags, chemwipes, masking tape, metal cans, and laboratory trays are provided for use where necessary for contamination control.
7.
Operational and Radiation Control Procedures a.
Receipt of Samples j
Samples received will include uranium and plutonium as solids and as acid solutions. Samples will be individually contained in sealed glass or polyethylene bottles. Plutonium and U-233 samples will be further protected by a second scaled bottle. The individual samples will be packed together inside a metal container with ver-miculite or other absorbing material separating them. The metal container will be plainly marked with appropriate radiation warning signs. This container will then be packed in an approved cardboard, wooden, or metal shipping container. The samples will be either material from fuel manufacturers which has no appreciable beta-gamma contamination or samples from post-irradiation studies from which<the beta-gamma contamination has been removed. When received, the shipping container will be monitored and smeared 4nless the package contains an exempt quantity of material as specified in paragraph 20.205 of Part 20) to assure that the beta-gamma rate does not exceed 200 mr /hr at the surface and that the fixed and removable alpha contamination does not exceed 500 DPM per 100 square centimeters. When the container is known to meet these criteria, it will be taken into the sample preparation room.
The samples will then be placed in the previously described storage safe until ready for analysis. Plutonium and U-233 samples will be placed in the minimum opening box for removal from the ship-ping container and checking individual sample vials. If the con-tamination levels do not exceed those described above, the indi-vidual samples will be removed to the glove line for storage until ready for analysis. The shipping containers will be monitored inside and out and, if necessary, decontaminated to below 200 mr /hr beta-gamma and 10 DPM per 100 square centimeters alpha. Con-tainers and packing material whi<.h cannot be decontaminated will be discarded as hot waste for burial at an approved burial site.
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s Nuclear Regulatory Cocunission Page 9 December 1, 1976 b.
Processing of Material J
Analyses involving four types of special nuclear materials will be carried out. These are (1) isotopic analysis of enriched uranium, (2) trace analysis for enriched uranium using U-233 as an internal standard, (3) isotopic analysis of U-233 fuel samples, and (4) isotopic 5
analysis of plutonium. To avoid ambiguity, each procedure is discussed separately.
(1)
Enriched Uranium Laboratory coats will be worn for preparation of these samples. Respirators, coveralls, booties, surgeon caps, and rubber gloves will be available for use when cleaning up spills and other operations where air and surface con-tamination levels exceed those called out in Section 7. d.
Samples in batches not to exceed ten (10) samples will be removed from the storage cabinet and taken to the chemical hood. (Individual samples as received will usually not exceed 0. 3 gram contained uranium. ) Appropriate aliquots (0. 05 to 0.1 gram).will be weighed or pipetted into beakers for purification. The unused sample will be returned to sthe storage safe. The uranium in the sample aliquots will be purified by acid fuming, liquid-liquid extraction, ion exchange or electro-deposition. The end product will be j
a solution of pure uranyl nitrate. This solution will be trans-ferred 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 will be transf erred to the loading hood in the mass spectrometer room in a closed disposable ice cream carton. The filament will be loaded into the mass spectrometer source for analysis. After the anal / sis is completed, the spent filament will be removed fr am the mass spectrometer and discarded in a covered container for eventual shipment to an approved burial site as non-recoverable waste.
The unused sample will be salvaged into a polyethylene sal-vage bottle. When 50 grams of uranium have been accumulateds it will be returned to the customer for purification and re-covery. The low level waste solutions will be discarded into a screw cap polyethylene salvage container within the hood.
When full, the container will be analyzed. If the radioactivity level does not exceed the limits called out in Section 7.g., it
Nuclear Regulatory Commission Page 10 December 1, 1976 will be dumped in the sanitary sewer. If the 1cvel exceeds these limits, it will be concentrated and shipped to a licensed i
burial site. All solid waste, absorbent paper, and salvage will be placed in the proper containers and work surfaces decontaminated below the levels called out in Section 7.d.
before proceeding with the next batch of sarnples.
(2)
Trace Uranium Protective clothing requirements for this operation are the same as those described for enriched uranium. The major difference in this process involves the preparation of the U-233 internal standard. The desired quantity of U-233 will be weighed out in the glove box in the uranium preparation r oom. It will then be dissolved in nitric acid and diluted to a solution concentration of 5 micrograms U-233 ml. Up to 10 aliquots containing 5 micrograms U-233 each will then be pipetted into 100 m1 beakers. These beakers will be trans-ferred to the chemical fume hood. Aliquots of unknown sa'mple containing up to 50 micrograms of enriched uranium will 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 10 grams.
(3) U-233 Fuel Samples Protective clothing requirements for this operation will be the same as those described for enriched uranium. The major dif-ference here involves the preparation of the fuel sample inside the glove box instead of in the open hood. Samples in batches not to exceed ten samples will be removed from the storage cabinet for reproces sing. Individual samples received will not exceed 0.1 gram contained Uranium-233. Appropriate aliquots of 0. 01 gram contained U-233 will be weighed or pipetted into beakers inside the glove box. The unused samples will be returned to the storage cabinet. The uranium in the sample aliquot will be purified by acid fuming, liquid-liquid extraction, or ion exchange. The end product will be pure uranyl nitrate. This solution will be diluted to a con-centration of 1 mg/ml. Fifty micrograms of this solution will be l
l transferred to the minimum opening glove box where up to 10 micro-
e Nuclear Regulatory Commission j
Page 11 December 1,1976 grams of the uranyl nitrate will be loaded onto a tungsten or tanta-lum filament. The loaded filament will be transferred to the loading hood in the mass spectrometer room in a disposable ice cream car-ton.
The filament will be loaded into the mass spectrometer for analysis.
After the analysis is completed, the spent filament will be removed from the mass spectrometer and discarded in a covered ice cream carton for eventual shipment to an approved burial site as non-recoverable waste. The unused sample will be salvaged in a poly-ethylene salvage bottle for return to the customer. All unused U-233 l samples will be returned to the customer within 90 days of receipt of the sample.
All low level waste solutions will be salvaged in a screw cap poly-ethylene salvage bottle within the glove box. When full, the solution in the container will be analyzed. If recoverable quantities are present, the material will be returned to the customer for reproces-sing. - If the quantities are nonrecoverable, the material will be added to a container containing a gel to render it solid and packaged for shipment to an approved burial site. No material will be shipped for burial until permission is first obtained from the customer.
(4) Plutonium C overalls, surgeons caps, and bootics are required for all operation (
involving plutonium. Respirators and rubber gloves are carried at all times and are worn whenever any plutonium is handled outside the glove box and whenever the possibility of accidental release of airborne contamination exists. It should be pointed out that all hand 14 ing procedures are designed to maintain safe limits of airborne con-tamination at all times. Respirators are worn as an additional pre-caution, but are not used in lieu of maintaining proper airborne con-tamination levels. Transfer of filaments to the mass spectrometer, glove changes, salvage bag changes, opening the airlock on the glove ;
line, hot spot cleanup, and mass spectrometer source changes are 1
examples of op2 rations where use of the respirator and gloves will be r equir ed.
The following operations will be conducted in glove boxes. Samples in batches not to exceed 10 samples will be removed from the storage rack in the first box for processing. Individual samples will!
contain no more than 20 milligrams of plutc,nium each. Appropriate
Nuclear Regulatory Commission Page 12 December 1,1976 quantities (not to exceed 10 milligrams plutonium) are weighed on an<
analytical balance in the first box. The unused sample is r eturned l to the storage rack. The plutonium in the sample aliquot is purified '
by acid dissolution, liquid-liquid extraction, and ion exchange tech-niques. The end product will be a solution of pure plutonium nitrate,
A maximum of 10 micrograms of this plutonium or chloride.
or chloride will be evaporated to dryness on a tungsten filament for analysis on the mass spectrometer. The loaded filament will be placed in a specially designed container which is partially inserted through a fitting in the wall of the glove box. The fitting and con-tainer are designed to permit insertion through the glove box wall, placement of the filament within the container, closing the con-tainer, and removal of the container, all without ever permitting a direct leak path from the glove box to the room atmos phere. As the container is removed, the outside surface of the container and inside surface of the fitting are monitored with a portable alpha sur-vey meter to assure that no contamination to either surface has occurred. Respirators will be worn as a precautionary measure during this operation. The closed container will be taken to the mass spectrometer hood where the container will be opened and the loaded filament placed in the mass spectrometer source. R es pir -
ators and rubber gloves will be worn as a precautionary measure.
Respirators are not considered to eliminate the need for maintain-ing proper air contamination levels. Rather they represent an added precaution in the event of an accidental release of material. After analysis, the spent filament will be removed from the mass spec-trometer source and placed back in the container. The container will be closed, the outside surface will be monitored, and the con-tainer returned to the mass spectrometer preparation room. The container will be inserted into the fitting and the spent filament removed and salvaged in a covered stainless steel beaker for eventual shipment to a licensed burial site. The unused sample will be salvaged into a polyethylene salvage bottle. When 1 grams of plutonium have been accumulated, the material will be returned to the customer for purification and recovery. All low level solutions generated in the purification process will be concentrated, analyzed to determine radioactivity level, and shipped to a licensed burial site as nonrecoverable waste. All absorbent paper, ccantaminated glassware, and other contaminated solid waste will be placed in appropriate plastic bags or metal salvage containers for eventual shipment to a licensed burial site.
Nuclear Regulatory Coranission Page 13 December 1, 1976 c.
G.eneral Procedur es Protective laboratory coats for uranium processing will be changed on a weekly basis or whenever the Technical Associates Frisker Monitor indicates an alpha contamination level greater than 50 DPM per 100 square centimeters. These laboratory coats will never be worn outside the restricted area described in Section 7.h.
Cover-alls, booties, and caps for plutonium processing will be changed daily and whenever alpha contamination levels exceed 50 DPM per 100 square centimeters. Daily changes will be made just before the lunch period. These coveralls will not be worn outside the restricted 1 l
area described in Section 7.h.
li, during personnel monitoring, protective clothing is found to be contaminated in excess of the above limits, the following procedures will be followed. If contamination is not in excess of 1000 CPM, the individual will proceed to the change area and change clothing, placing the contaminated clothing in the covered container provided.
If contamination in excess of 1000 CPM is observed, a change of clothing will be brought to the individual in the sample preparation room. Clothing with contamination of less than 5000 CPM will be placed in a plastic bag for special laundering and monitoring.
Clothing contaminated in excess of 5000 CPM will be placed in a plastic bag and scaled for eventual chipment to a licensed burial site. An immediate check of the preparation room will be performed' to determine the source of the contamination whenever contaminated clothing in excess of 50 DPM per 100 square centimeters is observed Respirators will be changed on a weekly basis and whenever the daily' or special air sample chgks indicate an airborne radioactivity con-centration above 2 x 10 microcuries /ml, the maximum permis- '
sible concentration for plutonium in Section 20,103 of 10 CFR 20, has occurred. Changes will include laundering of the face pieces and replacement of the filter cartridges.
Samples will be processed in batches as previously described. All salvage and cleanup operations will be completed for one batch beford the next batch is started. A portable alpha survey meter will be placed in the plutonium preparation room, another in the uranium preparation room, and another in the mass spectrometer room to permit immediate checking of hands, gloves, equipment, and work surfaces when required. It is expected that plutonium samples will be received on only an occasional basis. When the plutonium line is not in use, the line will be cleaned up and glove port covers placed over all glove ports as additional precautionary measures.
'a Nuclear Regulatory Commission Page 14 December 1, 1976 d.
Radiation Surveys Eight
( 8 ) permanent air sampling stations are provided, as described in Section 6.d.
The filter heads will be changed and counted daily when plutonium is being processed and weekly when only uranium is being processed. Maximumgrborne radioactivity levels will not be permitted to exceed 2 x 10 microcuries per m1, the maximum permissible concentration for plutonium -239 in Section 20 of 10 CFR 20. Respirators will be required for any emergency, such as a spill where levels in excess of these limits are known to exist for short periods of time. Full face supplied air masks are available for use when cleaning up a spill which results in dangerous levels of airborne activity. Any operation such as a new operation, bag or glove change, which could result in exceeding these limits will be monitored with the portable air sampler. Permanent records of the results of these surveys will be maintained.
Air samples of the effluent air from the blower system will be taken once a-week over an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> work day when uranium is being processed and continuously when plutonium is being processed to assurethatthy4 airborne radioactivity in the effluent air does not exceed 6 x 10-microcuries per m1, the maximum permissible con-centration for plutonium-239 in Section 20 of 10 CFR 20.
Permanent records of the results of this survey will be maintained.
Weekly smears of all floors and working surfaces will be taken.
Fixed and removable alpha contamination icvels will be held to the lowest possible level, but will not be permitted to exceed 10 DPM per 100 square centimeters in any case.
Smears will be acheduled so that they are taken just before the weekly scrubbing.
All scrub water will be dumped into the hot lab sink for transfer to the holding tank to guarantee that no effluent will be released without first being analyzed. The scrub equipment used in this area will not be used for other areas of the facility.
In addition, a portable air sampler (Atomic Accessories Model 11V-300) is available for evaluation of new operations and special hazards such as spills or glove failures.
Permanent records of the results of all radiation surveys will be maintained.
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i Nuclear Regulatory Commission Page 15 December 1,1976 c.
_ Personnel Monitoring All personnel working in the Restricted Area will be required to wear film badges. These badgen will be changed on a monthly basis. Bioassays will be performed for Restricted Area employees initially upon employment, quarterly thereafter, and upon ter-mination of employment. Additional bioassays will be requested if there is reason to suspect high exposures. Examples of incidents requiring additional bioassays are spills, high air counts, and cuts while handling special nuclear materials. Permanent records of the results of these surveys will be maintained for each indi-vidual. Direct reading dosimeters are available and will be worn I
when processing irradiated fuel samples meeting the beta-gamma activity levels called out in Section 7.a.
Permanent monitoring meters are provided in the locations pre-l viously described in Section 6. b.
Technical Associates Frisker j
or Nuclear Chicago Monitors are used at these stations. Person-nel are required to monitor their protective clothing whenever leav-ing the sample preparation room for the change room or mass spectrometer room. Personnel are required to monitol their personal clothing whenever leaving the restricted area as desig-nated in Section 7. h.
for other areas of the building.
f.
Decontamination of Equipment No equipment or materials will be removed from the restricted area described in Section 7.h.
unless monitored by the 2 adiation control officer or his assistant and found to have less than 10 DPM per 100 square centimeters total fixed and removable alpha con-tamina tion. All waste material to be shipped to a licensed disposal site will be monitored and inspected by the radiation control officer or his assistant. No such materials will be removed from the restricted area unless accompanied by a signed statement from the radiation control officer or his assistant tlnt the packaging and con-tamination levels conform to standards established by the Interstate Commerce Commission and Section 20 of 10 CFR.
g.
Waste Disposal i
As previously described, the laundry water and het lab sink waste water are held in the holding tank. When full, the contents of the holding tank will be analyzed on the previously described gass pro-portional flow counter.
If the total alpha act!.vity of the holding tank does not exceed 1 x 10-4 microcuries per m!
the maximum per-missible concentration for plutonium-239 in Sect. ion 20 of 10 CFR 20, the contents of the tank will be released into the sanitary sewer. This I t
Nuclear Regulatory Commission Page 16 December 1,1976 1
material will be further diluted by a factor of 10 to 1 by the daily quantity of water released into the se.ver by the applicant. A permanent record of the results of these analyses will be maintained.
All low level nonrecoverable waste which exceeds the contamination levels permissible for plutonium as established in 20.303 will be packaged and shipped to a licensed burial site for disposal per 20.304.l h.
Restricted Areas i
The instrument room and the hot lab area are designated as the
" Restricted Area".
The applicant limits access to this area to authorized personnel only. These areas are posted in accordance with Section 20 of 10 CFR 20.
1.
Security Against Unauthorized Use of Special Nuclear Materials All uranium samples are stored in the previously described storage l
safe. The cabinet is locked except when samples are being trans-ferred. The sample 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 are 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 Procedures for Radiation Safety (enclosed), individual processing procedures, fire j
fighting and emergency procedures, and selected reading topics describing general procedures for handling radioactivity are required i reading for all new personnel assigned to this area. Annual reviews of 'all procedures assure periodic re-inst'ruction of all personnel.
k.
Fire and Emergency Procedures To limit the likelihood of fires, all flammable organic solvents are stored in one specific metal storage cabinet. No combustible materials,are stored in the chemical hoods or glove boxes. Most of t
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N Nuclear Regulatory Commission Page 17 December 1, 1976 the material received will not be in metallic form. However, the following procedures have been established for handling metal.
Total uranium metal content in a hood is limited to 3 grams in individual and separated aliquots of 0.3 gram. Total plutonium metal in a glove box is limited to 2 grams in individual and separated aliquots of 20 mg each. All metal will be handled in platinum crucibles which will contain the metal in the event of fire.
The following emergency procedures have been adopted in the event of a major spill or fire within the process area:
(1).
Shut down all exhaust fans within the immediate laboratory (This is done with either of two master switches area.
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 the restricted area and at the main switchboard. This list contains the names, addresses, and telephone numbers of the members of the damage control team and the order in which they are to be called. )
(4)
A damage control team under the direction of the Radiation Safety Officer will re-enter the area, if safe, to combat the emergency. Personnel assigned to the damage control team have been instructed in the methods of fighting fires and warned of the dangers involved in pressurizing glove boxes and hoods with extinguishing agents. Because of the small quantities of metal involved, fire control efforts of metal fires will be directed primarily to isolating the material i
rather than extinguishing it.
Copies of the emergency procedure are conveniently posted through-out the facility and provided to local fire fighting units. Annual reviews of radiological and emergency procedures are held. Member s of the local fire department and police rescue units have been guided through the facility and the potential hazards discussed with them.
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Q X FIRc EinNc-vasHcas Q PERSONNEL MONITOR STATIOW m
2xipt uS T' Sf3 72"A S h'/ T'c d isotopic analysis, Inc.
8335 E. Sist St.
Tulsa, OK 74145 B A S T*
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STANDARD POLICY AND PROCEDURE FOR l
RADIATION SAFETY PROGRAM i
Originally Issued:
September 1, 1965 Revised:
January 16, 1976 December 15, 1976 By:
Isotopic Analysis, Inc.
8335 East 51st Street Tulsa, OK 74145 Former address:
10700 East Independence Tulsa, OK 74115
/
, Y /.
C
/
--?
,,, n JonfW. Harrison Radiation Safety Officer f $- l5 ~
(,
Date
.1 4
l TABLE OF CONTENTS l
Page 1.
P O LI C Y - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
1 2.
R ES PON SIBI LIT Y - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
1 3.
GENERAL REQUIREMENTS:
3.1 Li c e n s i n g - - - - - - - - - - -- - - - - - - - - - - - - - - - - - - - - -
1 j
3.2 Health Physics and Safety Requirernents -----
2 1
4.
PROCEDURES - GENER AL:
2 4.1 Obtaining Licenses 4.2 Ordering of Radioactive Material -----------
3 3
4.3 Receipts of Radioactive Materials 5.
PROCEDURES - SPECIFIC:
5.1 Special Nuclear Material 4
5.2 Area Postings 4
5.3 Exposure Limits 5
6 5.4 Personnel Monitoring 7
- 5. 5 R ec ord s
- 5. 6 R eports 7
- 5. 7 Wa s t e D i s p o s a l - - - - - - - - - - - - - - - - - - - - - - - - - - -
8 8
- 5. 8 Instruction of Personnel APPENDIX I Abstract of Part 20, Title 10, Code of Federal R egulations
. APPENDIX II
.R equired Radiation Surveys and Monitoring Procedures
s POLICY AND PROCEDURE FOR R ADIATION SAFE'TY PROGRAM l.
PO LICY i
To provide a clear understanding of the procedures and responsibilities with regard to the Radiation Safety Program at Isotopic Analysis, Inc.,
it is the policy of this Corporation that these procedures and responsibilities be understood by all personnel concerned in order to insure strict compliance with Nuclear Regulatory Commission (NRC) regulations and to insure the health and safety of employees.
4 2.
R ESPONSIBILITY Mr. Jon W,llarrison is designated the Radiation Safety Officer (RSO) for Isotopic Analysis, Inc., and is responsible for seeing that all phases of the Radiation Safety Program are carried out in strict compliance with NRC regulations. Mr. T.C. Westmoreland is designated alternate RSO. Both j
~
Mr. Westmoreland and Mr. Harrison are capable and aware of the respons-ibilities of their duties under this program.
l 3.
GENERAL R EQUIREMENTS 3.1 Lic ensing The NRC issues two types of licenses: gener al and s pecific. A general license is issued to all percons to receive, possess, use, and trans port byproduct and source marrial in very limited quantities.
These limits are shown in Table A of Appendix I to this manual. In addition, general licenses have been issued to receive, possess, and use certain devices which contain greater than general license quantities of radioactive material, providing such devices have been manufactured under the terms of a specific license and are installed by a person authorized for such installation under a specific license. Thes e general licenses are described in full in Section 30 of Title 10 of the
Code of Federal Regulations.
In addition to the general licenses described above, the NRC issues specific licenses to persons, organizations, and corporations to receive, use and/or possess byproduct, source, and/or special nuclear material under specified conditions. In every case the specific license limits the type and quantity of material, the location where used, the use permitted, and the persons using the material.
It is important that this be understood because a license to possess a given quantity of radioactive material does not permit additional quantities or uses without amending the license. Assumptions to the contrary are the most common cause of license violations.
At pr esent we have one,s pecific license at Isotopic Analysis, Inc. The Mass Spectrographic Laboratory is licensed for possession and use of i
plutonium and uranium up to specified limits.
i
/
3.2 Health Physics and Safety Requirements Material rec'cived either under a general license or a specific license must be handled in accordance with the regulations of Section 20 of Title 10, Code of Federal Regulations. A brief abstract of these require-monts is given in Appendix I to assist all personnel in evaluating their procedures. The actual procedures required to assure compliance with these regulations are detailed in the following section. Definitiions of terms used in this section are included in Appendix I of this manual.
1 4.
PROCEDURES - GENERAL 4.1 Obtaining Licenses '
The RSO or alternate RSO shall be solely responsible for obtaining all NRC licenses and no license application will be filed without their examination or without one of their signatures on the accompanying letter.
Any individual requiring a radioactive source or source material will contact the RSO and furnish all information requested by him in writing.
At least one employee who will be working with and responsible for radioactive materials will be named as a " User" in the application.
This person must have had adequate experience in the handling of radioactive materials to be acceptable to the NRC as a " User. "
)
In the event that the individual named as a " User" Icaves the employ of the company, the RSO shall at that time designate a replacement unless other employees, who are named on the license as " Users, "
still remain in that particular group. The RSO will then file appli-cation for license amendment naming the new individual.
4.2 Ordering of Radioactive Material All purchase requisitions for radioactive materials will be originated by the RSO. All materials ordered must be shipped to 8335 East Sist Street, Tulsa, Oklahoma 74145. Other individuals can write specifications, but these must be reviewed and accepted by the RSO.
If correspondence must be by telephone, the call must be made by the RSO or with the RSO on conference line. This is to prevent statements being made which are in conflict with the terms of our lic en s e.
4.3 Receipts of Radioactive Materials Only the RSO or alternate RSO will have the authority to inspect and accept incoming radioactive materials. The RSO or alternate RSO will oversee unpacking and removal of the material.
4
~3-
-m-
-w+
5.
PROCEDURES -- SPECIFIC
- 5..
' Special Nuclear Material 5.1.1 Handling Procedures All material received is subject to the handling procedures called out in the specific operating procedures of Appendix II.
5.1. 2 Maximum airborne contamination and fixed contamination limits for plutonium will be used as limits for this laboratory.
5.1. 3 Radiation surveys for fixed contamination, effluents, and airborne contamination will be conducted as called out in the specific operating procedures in Appendix II of this material.
5.1. 4 All shipments of material from the laboratory must be approved by the RSO.
- 5. 2 Area Postings 5.2.1 Radiation Areas All areas in which there exists radiation sufficient to cause a whole body dose of 5 millirems per hour or 100 millirems in any. period of 5 consecutive days shall be posted with a sign bearing the radiation symbol and the words " CAUTION -
RADIATION AREA. "
All areas in which there exists a radiation level sufficient to cause a whole body dose of 100 millirems per hour shall be posted with a sign bearing the radiation symbol and the words
" CAUTION - HIGH RADIATION AREA. "
All areas used for the storage of special nuclear materials shall be posted with a sign bearing the radiation symbol and 4_
P and the words " CAUTION - RADIOACTIVE MATERIALS. "
All storage containers used to store a quantity of licensed material in excess of the limits called out in Table C of Appendix I of this manual shall have attached a label bearing the radiation symbol and the words " CAUTION - RADIOACTIVE MATERIAL. " Additionally, the labe: shall identify the quantity
]
and type of material. Permanent areas will be so posted by the RSO.
All permanent restricted areas will be posted with copies of
" Notice to Employees. " (See Appendix I, 1. 5 b. ) The RSO will be responsible to so post these areas.
5.3 Exposure Limits 1
- 5. 3.1 Radiation Exposures No personnel will be permitted to receive radiation in excess of the following limits:
a)
Whole body, head and trunk, active blood-forming organs, lens of eyes, or gonads:
- 1. 25 rem / calendar quarter.
b)
Hands and forearms, feet and ankles: 18.75 rem / calendar
- quarter, i
c)
Skin of whole body:
- 7. 5 rem / calendar quarter.
The RSO will review all personnel exposure reports and inform personnel when they approach 25% of the permissible quarterly dose.
5.3.2.
Airborne Radioactivity arsonnel will be permitted exposure to atmospheres con-an.
more than 2 x 10~
microcuries per day. _
j i
No personnel will be permitted to handle radioactive material in such manner to receive a maximum equilibrium body burden of 2 x 10 microcuries per day.
The RSO will review the results of the daily and/or weekly airhead samples and quarterly bioassay reports and immediately report excessive exposures to personnel concerned.
5.4 Personnel Monitoring
- 5. 4.1 Radiation Areas u
All personnel entering a radiation area are required to wear a film badge or pocket dosimeter at all times. Dosimeters will be read before entering the area and upon leaving the area.
Readings are to be recorded in a permanent log book with date and user. Exposures in excess of 5 mr per hour should be reported immediately to the RSO. Film badges will be changed i
once each month.
The RSO will recommend proper personnel monitoring devices.
The RSO will periodically check to determine that all personnel are complying with these requirements.
5.4.2.
Radioactive Material Areas All personnel working in an area where licensed quantities of radioactive materials are processed are required to wear a film badge at all times. Additionally, each person will monitor his hands, feet, and clothing each time he Icaves the area to i
assure that no radioactive material is being carried on his person.
All persons working with licensed quantities of radioactive materials as unsealed sources are further required to submit
- i a
e -.
nw,,
urine samples for bioassay on a quarterly basis.
The RSO will recommend appropriate monitoring devices and s er vic es.
5.5 Records The RSO will maintain permanent records of the individual per-sonnel exposure records from film badges and bioassay reports, as well as records of all disposals.
4
- 5. 6 R eports l
- 5. 6.1 R eport to Employees
)
{
Jpon receipt of a request from any employee, the RSO will supply a written re srt of the individual's occupational exposure record r
on an annual basis, i
5.6.2 Report to Former Employees Upon receipt of a written request, the RSO will supply within 30 days a written report of the employee's occupational exposure record covering the period of his employment.
J
- 5. 6. 3 R eporting Incidents The RSO shall be informed immediately of any incident involving licensed matter which indicates:
a)
Loss or theft of licensed material b)
Whole body exposure in excess of 5 rem c)
Release of radioactive material in excess of the limits called out in Table B of Appendix 1 of this manual,
d)
Loss of one day's operation of the affected facilities.
e)
Damage to facilities of $1,000 or more.
5.7 Waste Disposal
- 5. 7.1 Special Nuclear Matericls No liquid effluents shall be disposed of into the sanitary sewage system until the effluent has been analyzed and shown to contain less than 1 x 10~ microcuries per milliliter.
-l4 Airborne effluents may not contain activity in excess of 6 x 10 microcuries per ml of air.
Management will assure that sufficient surveys are conducted to show compliance with these requirements. The RSO will periodically r eview thes e surveys.
No waste may be shipped for disposal without the approval of the RSO.
5.8 Instruction of Personnel
- 5. 8.1 Instruction Aids All pctsonnel shall be provided with and required to read pertinent parts of the following material:
a)
Part 20, Title 10, Code of Federal Regulations b)
Isotopic Analysis, Inc., Radiation Safety Policy and Pro-cedures c)
Specific operating procedures for the licensed activity in which he is engaged. *
-=-
- 5. 8. 2 R es ponsibilities The RSO will provide copies of Part 20, Title 10, Code of Federal Regulations, Isotopic Analysis, Inc., radiation manual and specific operating procedures as requested by the cognizant group. leader. Additionally, he will provide any guidance or j
clarification of regulations as requested by any individual.
i The cognizant group leader will assure himself that each individual engaged in the licensed activity under his direction has read all required instructional material before he is permitted to engage in licensed activities.
i 4
1 i
1
)
l 1
l 2
1 1
j
_9
(
i
APPENDIX I Abstract of Part 20, Title 10, Code of Federal Regulations i
1.
Standards for Protection Against Radiation 1.1 Exposure Limits (Radiation)
(a)
Restricted Area - No licensee shall possess, use, or transfer licensed material in such a manner as to cause any individual in a restricted area to receive a dose in excess of the following:
(1)
Whole body, trunk and head, active blood-forming organs, lens of eyes, or gonads: 1.2 5 rems / calendar quarter (2)
Hands and forearms, feet and ankles: 18. 75 r ems /
calendar quarter I
(3)* Skin of whole body:
- 7. 5 rems /calehdar quarter (b)
Unrestricted Area - The radiation limits for an unrestricted area must be such that no individual will receive a whole body dose in excess of 0. 5 rem per calendar year. Com-pliance is assured when the radiation level is kept below 2 millirems for, any one-hour period and below 100 millirems for any five consecutive days.
1.2 Exposure Limits - Radioactive Material (a)
Restricted Area - No licensee shall use, possess, or transfer licensed material in such a manner as to expose any individual in a restricted area to airborne radioactivity in excess of the limits shown in Table B.
Expos e in this instance is taken to mean that the individual is present in this airborne concentration. No allowance shall be made for protective clothing or equipment.
(b)
Unrestricted Areas - No licensee may use, possess, or transfer restricted material in such a manner as to release to an unrestricted area concentrations of radioactive materials in excess of the limits listed in Table B.
1.3 Personnel Monitoring Equipment Each licensee must supply and require the use of appropriate personnel monitoring equipment to each individual who enters a restricted area under such circumstances that he may receive a dose in any calendar quarter in excess of 25% of the applicable limits as called out in paragraph 1.1 of this Appendix, and to minors who may receive a dose in excess of 5% of those limits and to all individuals entering a "high radiation area. "
- 1. 4 Caution Signs, Labels and Signals (a)
Radiation Area - Each ar ea in which there exists radiation in sufficient quantity to cause a whole body dose of 5 milli-rems per hour or 100 millirems per any consecutive five-day period shall be posted with a sign bearing the radiation symbol and the words " CAUTION - RADIATION AREA. "
(b)
High Radiation Area - Each area in which there exists radiation in sufficient quantity to cause a whole body dose of 100 millirems /hr shall be posted with a sign bearing the radiation symbol and the word' " CAUTION - HIGH RADIATION AR EA. "
(c)
Airborne Radioactivity Area - Any area in which the concentration of airborne radioactivity exceeds the limits -
4 in Table B shall be posted with a sign bearing the radiation symbol and the words " CAUTION - AIRBORNE RADIOACTIVITY AREA. "
(d)
Radioactive Materials - Any area used for the storage of special nuclear materials, natural uranium or thorium shall be posted with a sign bearing the radiation symbol and the words " CAUTION - RADIOACTIVE MATERIALS. "
(e)
Containers - Any container in which is stored a quantity of licensed material in excess of limits called out in Table C shall have attached a durable, clearly visible label bearing the radiation symbol and the words " CAUTION - RADIOACTIVE MAT ERIAL, " In addition, the quantity and type of material shall be shown.
(f)
Exceptions to Posting R equirements Caution signs need not be posted in rooms containing radio-active materials for periods of less than eight (8) hours, provided the materials are constantly attended by an individual who will take all required precautions to assure against excessive exposure.
- 1. 5 Instruction of Personnel (a)
All individuals frequenting any portion of a restricted area shall be informed of the occurrence of radioactive materials or radiation and shall be instructed in the safety problems associated with exposure to such materials or radiation and in the proper procedures for minimizing exposure.
All personnel shall be further instructed in the applicable regulations and licenses governing handling of such materials and shall be advised of reports of radiation exposure which employees may request pursuant to these regulations. _ -
(b)
A " Notice to Employees" shall be posted where employees engaged in licensed work may observe a copy on the way to or from their place of employment. The notice will inform workers that the following documents are available for their inspection:
(1)
The regulations in Part 19 and in Part 20, Title 10, Chapter 1, Code of Federal Regulations; (2)
The license, license conditions, or documents incorporated into a license by reference, and amendments thereto; and (3)
The operating procedures applicable to licensed activities.
1.6 Disposal of Waste l
No Mcensee shall dispose of licensed material except by:
(a) Transfer to an authorized recipient as provided by regulations CFR Part 30, 40, or 70, (b) As provided by specific authorization of ti.e NRC, or (c) As provided in Part 20, Title 10, Code of Federal Regulations.
or 1
1
- 1. 7 Records (a)
Each licensee is required to maintain records of the radiation exposures of all individuals for whom personnel monitoring is required pursuant to Part 20, Title 10, Code of Federal Regulations.
(b)
Each licensee must maintain permanent records of all surveys and disposals made in fulfillment of these regulations.,
..-7
l s
i
- 1. 8 R eports (a)
Each licensee must report by telephone and telegraph to the Director of the appropriate Regional Inspection and Enforce-
)
ment Office immediately any known loss or theft of licensed material in such quantities and under such circumstances j
that it seems likely that a substantial hazard may exist to persons in unrestricted areas.
(b)
Each licensee must immediately notify the appropriate Director of Regional lnspection and Enforcement by tele-phone and telegraph of any incident which may have caused 1
(1) a whole body exposure of 25 rems or more, (2) a whole skin exposure of 150 rems, (3) a hands and forearm, or feet and ankle exposure of 375 rems, (4) the release of radioactive reaterial which, averaged over a 25-hour period, would result in concentrations in excess of 5000 times the amount in Table B, (5) a loss of one working week of operation of the facilities affected, or (6) damage to property in excess of $100,000.
(c)
Each licensee shall within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notify the Director of the appropriate Regional Inspection and Enforcement Office of any incident which results in (1) whole body exposure of 5 rems or more, (2) whole skin exposure of 30 rems or more, (3) hand, forearm, feet and ankle exposure of 75 rems, (4) release of radioactive material which, when averaged over a 24-hour period, results in concentrations in excess of 500 times the limits specified in Table B, (5) loss of one day operation of the facilities affected, or (6) damage of property in excess of $1000.
(d)
Each licensee must at the request of a former employee furnish a report of the former employee's exposure to I
^ '
o 1
l l'
radiation within thirty days of the request.
i (e)
Each licensee must make a report in writing within 30 days to the Director, Division of Licensing, of (1) all exposures in excess of the applicable limits in this section, l
(2) all incidents requiring immediate or 24-hour notification of the Regiona11nspection and Enforcement Office, and (3) a111evels of radiation or concentrations of radioacti've materials in unrestricted areas in excess of 10 times the j
applicable limits shown in this part or the employee's license.
(f)
At the request of any employee, each licensee shall advise l
said employee of the employee's exposure on an annual basis.
i i
- 1. 9 Violations An injunction or court order may be o5tained prohibiting any violation of any provision of these regulations. Any person i
who willfully violates these regulations may be guilty of a crime and upon conviction may be punished by fine or im-prisonment or both as provided by law.
4 i
i i
i l
t 4 -
e TABLE A Exempt Quantities Not Requiring Licenses Column Column N o. I No. Il D)pmduct metertal Mi. g
,,A,',*
i,d source svurce (micro.
(mlero-curies) curies)
A nelmany (9b 174).
I 10 A rvete 7e ( As 76).,
30 10 Ararnic 77 i As 77)...
10 10 J
Ibtrium Iw n. ant bauum 140 1
(H tl.a 140)....
I 10
{
Te rr ylisu m ( He 1)...... -..........
80 30 i
Cadmium l> 8siver la (CdAt lem n......,......
10 to Caleiune et (Ca 43)..
80 80 10
. 10 Car ben 14 (C i4)..................
Crrium 14 4-Preseed p mlum ice Pr 144)..........
I 30
. Cetmm-Dariuos 622 (Is.........
I 80 He 137)..
Chlorme 36 (Cl 3e)...
I 10 C hronhm Al (Cr 61)..
80 A0 4 'obalt fdl (Co rdH.....
I 10 Culqire he (Cu Att............
80 M
Furalitum IM (f.o 184)......
80 In I
to
> luor me 14.........
15.nlleum 72 (fle 72)..........
10 10 Ocrm uuum 21 (Os 11)l_-
80 no C (1o1.6 luR ( Au 39ftl.,.
30 lo rg fluid Igu i A u 109)............
360
'MO 10 le g Bl ystrewen 3 (Tritium) (li 3)....
0'*
Indium 114 (!s 114)..
I 80 elme tal (1 111)...........,
In 10
.redium IU2 (It IW2)...
10 to N
ron 65 (F'r AA)..
80 80
'rees 69 ( D e 69).............
I 10 1.amthanum 140 (la 140).......
30 10 blansanesr 82 ( Mn p2)....
I le bla.igenese 86 (Ma ut._ -.
80 30 hf allbuenum U9 (Me 99)._
10 10 Ntrhel 39 (Ni Avl....
I 10 hwkel 63 (Ni 63)...
I 10 h sulgm 93 (Nb 95) -
10 10 Pallausum 100 (Pd 100)............
10 le Falladium 10>-Rhodlum 103
( Pd R h 803).........,.
80 80 Phosphorus 32 (P 82)....
10 10 Polonium 210 (Po slo) 6.1 I
Potautura 42 (K-42)............
10 16 Prnseedimium 143 (Pr 143)....
10 10 l'romethium 147 (Pm 1471-30 40 Rhenium lM (Pe lM).......
10 10 Ithminum im (Rh 12)..
30 10 Itubidsum 86 (Ilh pl.............
30 10 Ruthenium lhtthodium 100 (It u It h LW)............
1 50 Famarms 463 (8m 153)..
30 to i
Fraudtum 46 (8e 40)......
I 10 (4f ver lit $ ( A g 105).........,...
I 10 l
fulver til ( As Ill)...- -
10 60 6ml um 72 (No 22) to 10 liodium 24 (No 34)...
10 10 Pirontlurn 89 (flr 09)...............
I lo Ottoutium St>-Ytulum 90 (8rY)..
O. I 1
Buttur 35 (8 35) 80 50 Tantalum lit 2 (Ts 112) 30 10 Technellum 96 (Te M)-_~
1 ID
'Iethnetium 99 (Te 90)-
l lo
" Tellurium 177 (Te 127)........
10 le i
Tellurium 129 (Te 129).......
I 10 Thalhum 3D4 (T4 3D4) 80 A0 Tin 113 (Sn 1831............
10 to
'funfitan IRA (W 1531........
10 10 Vanadium 48 (V 48) a 10 Ttirium 4 Y 00) -
I lo Ytirluen ei Y 91)..........
1 IH Ztne 66 (Za )..-
10 10 Ilela andfor Osmma emilling u
i b
n estlualertalrialllPlel 3
Ig 1
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1
TABLE B Maximum Permissible Concentrations of Material Table I Restricted Areas Table II -
Unrestricted Areas PART 20 - STANDARDS FOR PROTECTION AGAINST RADIATION Appendix B Concentrations in Air and Water Above Natural Background Table I Table II Element (atomic number)
Isotope Column 1 Column 2 Column 1 Column 2 Air Water Air Water (pCi/ml)
(pCi/ml) (uCi/ml) (uCi/ml)
-10
~4
-6 Ur anium (92 ) - - -- ---- - - - - - U 230 S
3X10 1X10 IX10"Il 5X10 I
1X10~
1X10 4X10" 5X10"
-4
~
U 232 S
1X10 8X10 3X10~
3X10' I
3X10' 8X10 9X10~
3X10~
4
-5 U 233 S
5X10~
9X107 2X10' 3X10
~
I 1X10 9X10 4X10" 3X10'
~4
~
~
~
U 234 S
6X10 9X10 2X10 3X10
~4 I
1X10 9X10 4X10' 3X10'
~
~
U 235 S
5X10 3X10' 2X10 3 X10' 5 I
1X10' 8X10' 4X10' 3X10--5
~
U 236 S
6X10 IX10 2X10" 3X10
~
~
I IX10 1X10 4X10 3X10' U 238 S
7X10~
IX10~
3X10~
4X10~
4
-5
~
IX10" SX10' 4X10 I
1X10
-5 U-natural S
1XIO" 1X10' 5X10 3X10
~
I 1X10~
1X10" 5X10 3X10~
~
~4
-6 Plutonium (94) ---------
Pu 238 S
2X10-1X10 7X10~
5X10
~4
-5 I
3 X10' 8X10 1X10 3X10
~
~4
-6 Pu 239 S
2X10~
IX10 6X10-5X10 -5
~
~
I 4X10 8X10~
1X10 3X10
~4
~I4
-6 Pu 240 S
2X10~
1X10 6X10 5X10
~4
-5 4X10"11 8X10 IX10"I' 3X10 I
~3
~
2X10 -4 Pu 241 S
9X10-7X10 3X10 ~9 4X10~
4X10~
IX10 1X10~
-4
-l4 Pu 242 S
2X10' IX10 6X10 5X10 -5 I
4X10' 9X10 IX10 3X10
~
~
o Soluble (s); Insoluble (I)
TABLE C J
Quantities Exempt From Labeling Requirements Material M kro, curies 1
At'#..........
i0 4:*..............
As=4.As......
to Au i0 a
A u ia............
10 n.a*+ te....
e n >..
Ou..
Cass..........
O la Cd * + A g'",.
10 Ce* t Pr*...
. ?..
I I
Cia......
I Cc"......
60 C rn..........
I Cs*+ Dam..
Cu'...
50 s
I F.a' u..
M Ft..
30 re s.
s F e...
a I
G a'8....
10 50 Gen...........
250 Pl6:llTO or U50) 30 188....
I
.nm.,,..
r'88. ~.....
10 K n...
lo 10 1.a *.........
a 1
M n,..
M n#....
So M e"..............
10 10 Nam......
la Na,,
u N IM....
10 N hH,,
I N I*8.......
1 Pu...,..,,,.
10 Pd'e + R hm...,
So Pd '"c....
10 Po'd..
10 Pmi..
- 0. I l0 PrH8..
...i m
I 1
Pu 8...
0.1 R a*..
H b"...
10 10 H e '#.....
10 Rh*............
I Rue + Rb*....
..g...
80 i
B#.......
I P bm..
I Bc"....
10 Sm*..........
Bn"8....
30 Br*.......
t Br#+ Y#..
O. I i
10 T a *........
Te#..
1 1
T c"...
10 Teise..
I Tem.........
Th (natural)...
50 50 T18...........
U (natural)..
2M Tritium. Ses U8..
So I
U us.....
60 U ni. t; ms...
I Va....
w in.,
10 Yu....
3 I
Y 8'u....
10 7.n Unidentined radioactive materinJs or any of the above in unlinewn mixtures..
O. I Note: For purposes of Il 20.203 and 20.304 where there is involved a ecmbination of iso.
Lopes in known amounts the limit for the combination should be derived as follows:
Determine, for each isotope in the combina.
tion, the ratio between the quantity present in the combination and the limit otherwise established for the spect0c isotope when not in combination. The sum of such ratios for all the isotopes in the combination may not exceed "1" (1 e., " unity").
Ex4 M Pt.a : For purposes of I 20.304. !! a particular batch contains 2,000 me of Au" and 25.000 se of C". It may also include not more than 3.000 se of 1*. This limit was de-termined as follows:
3.onn e lisi
+ts.nno me C'8 1.Ono se Aum n
-l ITJun me to.orn ne
+60,tmose The denominator in each of the above ratins was obtained by multipt ins the flertste in f
thb fablS be i rWWI en bbselstad let $ th ene v.
rww
DEFINITIONS 1.
" Airborne radioactive material" means any radioactive material dispersed in the air in the form of dusts, fumes, mists, vapors, or gases.
2.
"Dyproduct material" means any radioactive material (except special nuclear material) yielded in or made radioactive by exposure to the radiation incident to the process of producing or utilizing special nuclear material.
3.
" Calendar quarter" means any period determined according to either of the following subdivisions:
(i)
The first period of any year may begin on any date in January; provided that the second, third, and fourth periods accordingly begin on the same date in April, July, and October, respectively, and that the fourth period extend into January of the succeeding year, if necessary to complete a three-month quarter. During the first year of use of this method of determination by a licensee, the first period for that year shall also include any additional days in January preceding the starting date for the first period.
(ii)
The first period in a calendar year of 13 complete, consecutive calendar weeks; the second period in a calendar year of 13 complete, consecutive calendar weeks; the third period in a calendar year of 13 complete, consecutive calendar weeks; the fourth period in a calendar year of 13 complete, consecutive calendar weeks.
- Alternatively, the four periods may consist of the first 14 complete, consecutive calendar weeks; the next 12 complete, consecutive calendar weeks; the next 14 complete, consecutive calendar weeks; and the last 12 complete, consecutive calendar weeks. If at the end of a calendar year there are any days not falling within a complete calendar week of that year, such days shall be included (for purposes of this part) within the last complete calendar week of that year, If at the beginning of any calendar year there ar e days not falling within a complete calendar week of that year, such days shall be included (for purposes of this part) within the last complete calendar week of the previous year.
No licensee shall change the method observed by him of determining calendar quarters for purposes of this part except at the beginning of a calendar year.
4.
" Commission" mcons the Nuclear Regulatory Commission or its duly authorized representatives.
I Definitions (Continued) 5.
" Curie" means that amount of radioactive material which disintegrates at the rate of 37 billion atoms per second.
6.
" Dose" as used in this part is the quantity of radiation absorbed, per unit of mass, by the body or by any portion of the body. When the regu-1ations in this part specify a dose during a period of time, the dose means the tota! quantity of radiation absorbed, per unit of mass, by the body or by any portion of the body during such period of time. Several different units of dose are in current use. Definitions of units as used in this part are set forth in paragraphs (b) and (c) of this section.
7.
" License" means a license issued under the regulations in Part 30, 40, or 70 of Title 10, Code of Federal Regulations.
" Licensee" means the holder of such license.
8.
" Licensed material" means source material, special nuclear material, or byproduct material received, possessed, used, or transferred under j
a general or specific license issued by the Commission pursuant to the regulations in Title 10, Code of Federal Regulations.
9.
" Microcurie" means that amount of radioactive material which disintegrates at the rate of 37 thousand atoms per second.
10.
" Natural uranium and natural thorium. "
(1)
For purposes of the regulations in this part, one curie of natural 10 uranium (U-natural in Appendix B or C) means the sum of 3. 7 x 10 10 disintegrations per second from U-238 plus 3. 7 x 10 dis /sec from 8
U-234 plus 9 x 10 dis /sec from U-235. Also, a curie of natural thorium (thorium-natural ingpendix B or C}0means the sum of
- 3. 7 x 10 dis /sec from Th plus 3. 7 x 10 dis /sec from Th228 10 (2)
For the purpose of the regulations in this part, one curie of natural uranium (U-natural in Appendix B or C) is equivalent to 3,000 kilograms, or 6,615 pounds of natural uranium; and one curie of natural thorium (thorium-natural in Appendix B or C) is equivalent to 9,000 kilograms or 19,850 pounds of natural thorium.
11.
" Occupational dose" includes exposure of an individual to radiation (i) in a restricted ar ea; or (ii) in the cours "f employment in which the individual's duties involve exposure to radiation; provided, that
" occupational dose" shall not be deemed to include any exposure of an.
-m
,m
I i
f Definitions (Continued) individual to radiation for the purpose of medical diagnosis or medical therapy of such individual.
12.
The rad, as used in this part, is a measure of the dose of any ionizing radiation to body tissues in terms of the energy absorbed per unit mass of the tissue. One rad is the dose corresponding to the absorption of 100 ergs per gram of tissue.
(One millirad (mrad) = 0. 001 rad. )
13.
Radioactivity is commonly, and for purposes of the regulations in this part shall be, measured in terms of disintegrations per unit time or in 10 curies. One curie (c) = 3. 7 x 10 disintegrations per second (dps) =
12 2.2 x 10 disintegrations per minute (dpm). A commonly used sub-multiple of the curie is the microcurie (pc). One pc = 0. 000001 c =
4 6
- 3. 7 x 10 dps - 2. 2 x 10 dpm.
14.
" Radioactive material" includes any such material whether or not subject to licensing control by the Commission.
15.
" Radiation" means any or all of the following: alpha rays, beta rays, gamma rays, X-rays, neutrons, high-speed electrons, high-speed protons, and other atomic particles; but not sound or radio waves, or visible, infrared, or ultraviolet light.
16.
The rem, as used in this part, is a measure of the dose of any ionizing radiation to body tissue in terms of its estimated biological effect relative to a dose of one roentgen (r) of X-rays. (One millirem (mrem)
= 0. 001 rem. ) The relation of the r em to other dose units depends upon the biological effect under consideration and upon the conditions of irradiation. For the purpose of the regulations in this part, any of the following is considered to be equivalent to a dose of one rem:
(1) A dose of 1 r due to X - or gamma radiation; (2) A dose of 1 rad due to X
, gamma, or beta radiation; (3) A dose of 0.1 rad due to neutrons or high energy protons; (4) A dose of 0. 05 rad due to particles heavier than protons and with sufficient energy to reach the lens of the eye; If it is more convenient to measure the neutron flux, or equivalent, than to determine the neutron dose in rads, as provided in subparagraph (3) of this paragraph, one rem of neutron radiation may, for purposes of the regulations in this part, be assumed to be equivalent to 14 million.
Definitions (Continued) neutrons per square centimeter incident upon the body; or, if there exists sufficient information to e. ilmate with reasonabic accuracy the
)
approximate distribution in energy of the neutrons, the incident number of neutrons per square centimeter equivalent to one rem may be estimated from the following table:
Neutron Flux Dose Equivalents Neutron Number of neutrons per Average flux to deliver 100 Energy square centimeter equiva-millirem in 4p hours (neutr ns /cm Per sec. )
(Mev) lent to a dose fir m 2
(neutrons /cm )
6 Ther mal 970 x 10 670 1
6 0.0001 720 x 10 500 6
0.005 82 0 x 10 570 6
- 0. 02 400 x 106
- 0. I 12 0 x 10 80 6
- 0. 5 43 x 10 30 6
- 1. 0 26 x 10 8
6 2.5 2 9 x 10 20 6
- 5. 0 26 x 10 0
6
- 7. 5 24 x 10 l7 6
10 24 x 10 6
10 to 30 14 x 10 10 17.
" Restricted area" means any area access to which is controlled by the licensee for purposes of protection of individuals from exposnre to radiation and radioactive materials.
"R estricted ar ea" shall not include any areas used as residential quarters, although a separate room or ronms in a residential building may be set apart as a restricted area.
18.
"Si ted source" means any byproduct material that is encased in a caps 11e designed to prevent leakage or escape of the byproduct material.
19.
" Source material" means (i) uranium or thorium, or any combination thereof, in any physical or chemical form; or (ii) ores which contain by weight one-twentieth of one percent (0. 05%) or more of a. uranium
- b. thorium or c. any combination thereof. Source material does not include special nuclear material.
i e
b 1
Definitions (Continued)
?
k 20.
"Special nuclear material" means (i) plutonium, uranium 233, uranium enriched in the isotope 233 or in the isotope 235, and any other material which the Commission, pursuant to the provisions of section 51 of the act, 3
determines to be special nuclear material, but does not include source material; or (ii) any material artificially enriched by any of the fore-going but does not include source material.
21.
" Unrestricted area" means any area access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, and any area used for residential quarters.
a b
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APPENDIX II J
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h 4
REQUIRED RADIATION SURVEYS AND i
MONITORING PROCEDURES t
-f a
l
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l Required Radiation Surveys and Monitoring Procedures j
1
)
)
I Introduction In the handling of special nuclear materials, Section 20 of Title 10, 1
Code of Federal Regulations, requires that radioactivity levels of working surfaces in the laboratory, airborne contamination in the laboratory, air and water contamination of laboratory effluents, and personnel exposure to radiation and radioactive materials be controlled within specified limits. This manual abstracts those portions of the Code which apply to the operation of the Mass Spectrographic Laboratory at Isotopic Analysis, Inc. A program for demonstrating compliance with these regulations is outlined.
t 1
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f'.-.
II Permissible Limits The following table lists the maximum permissible limits for radioactivity with which we must be concerned. These limits are based upon the limits for Pu-239 because this is the most active isotope with which we will be concerned. By adhering to these limits, the analytical problems associated with differentiating between plutonium and uranium are eliminated.
Type of Contamination Maximum Permissible Limits Total radiation exposure per 1-1/4 rem / calendar quarter individual
~
Maximum permissible equilibrium 2 x 10 microcuric/ day body burden determined by bioassay
~
Airborne radioactivity in r estricted 2 x 10 microcuries/ml. of air laboratory area Airborne radioactivity in exhaust 6 x 10~ 4 microcuries /ml. of air effluent into unrestricted area
~
Total radioactivity in waste water 1 x 10 microcuries /ml. solution to be dumped into sanitary sewer Total fixed and removable alpha 10 dpm/100 sq. cm.
contamination on floors and bench tops and equipment removed from restricted area Total alpha contamination on 50 dpm/100 sq. cm, protective clothing before clothing change is required Total beta-gamma radiation dose 200 mr /hr. at surface from shipping container 1 mr/hr. at 1 meter from surface Total alpha contamination 500 dpm/100 sq. cm, permissible on shipping container Total amount of material buried Less than ten (10) microcuries at one time U 233, 234, 235, and/or Pu 239. -
III Compliance Surveys and Records The following surveys and records are required to demonstrate com-i pliance with the previously described regulations and limits.
Survey Scheduled Interval Records Required l
1.
b)ersonnel Exposure:
a.
Film Badge Monthly Permanent for each individual b.
Bioassay Upon initial employ-Permanent for each ment, quarterly individual thereafter, and upon termination.
2.
Airborne radioactivity Daily when handling Pu, Permanent in restricted area Weekly when handling Permanent U only.
3.
Airborne radioactivity Continuous when handling Pu, Permanent in effluent Weekly 8 hr. working period when handling U only.
4.
Total radioactivity in Before dumping any Permanent waste water holding tank 5.
Total fixed and Weekly smears of Permanent r emovable alpha in
- area, work area In addition to the above routine surveys, there are certain specific operations which require on-the-spot surveys to assure that no exposures in excess of the previously described limits occur. These are described under general operating procedures in the following s ection.
IV Specific Operating Procedures It is the intent of this section to outline procedures for conducting surveys and maintaining records which will assure compliance with Section 20, Title 10 of the Code of Federal Regulations.
A.
Personnel Monitoring Film badges are to be worn by all personnel working in the restricted area to obtain a measure of total radiation dosage.
Visitors to the area will not be required to wear film badges unless initial surveys indicate significant beta-gamma dosages are present. Badges will be monitored on a monthly basis.
Each person working in the restricted area will be required to submit urine specimens periodically for bioassay. A specimen is required initially on hire, quarterly thereafter, and upon ter mination. In addition, specimens will be required whenever conditions such as cuts from contaminated equipment, high airborne contamination, or major spills warrant rechecking.
The results from these two surveys will be entered on the individual's permanent exposure record. (See Form MS-1)
Records will be maintained for a period of five (5) years after termination of employment for each individual.
B.
Calibration of Gas Proportional Counter Whenever in use, the gas proportional counter must be re-calibra-ted over its expected operating range. This is done as follows:
Using a certified standard, determine the geometry factor for the instrument-Certified Count Rats F _ Observed Count Rate All results must be multiplied by this factor when determining total radioactivity of a sample.
1 s l
C.
Airborne Radioactivity 1.
Permanent Sampling Stations Eight (8) continuous air sampling heads are operated in the restricted area. When plutonium is being processed in the area, these air heads are to be changed on a daily basis. When only uranium is being handled, the air heads are to be changed on a weekly basis. The step-wise procedure is as follows:
a.
Duplicate sample heads a.
Duplicate filter heads are containing new filters are available for each sampling obtained from the counting station to permit counting of area in a closed carrying one set while the other set case.
is in place in the samplers.
Fresh filter papers are inserted when the con-taminated filter is removed.
The clean filter heads are then stored in a carrying case until installed.
b.
Each filter head is replaced b.
Each filter station is adjusted with a clean unit. The con-to a flow of 2 cubic feet taminated head is placed in per min..
The flow is read the carrying case for future through a clean filter.
ana ly s es.
c.
After changing filter heads, c.
return the contaminated heads to the counting room, remove the filter paper and count for five minutes or until a good statistical count is obtained.
d.
From the observed count d.
rate, calculate the airborne radioactivity as follows:
microcuries per ml. of air =
CxF 0
T x V x 2. 2 x 10 F = Counting efficiency factor where C = The observed total count T = Counting time in minutes V = Volume of air through the filter in cubic meters 1 microcurie = 2.2 x 10 disintegrations per minute 1 cubic meter = 10 ml.
I cubic meter = 35. 32 cubic feet In general, airheads will Log the calcultated r esults c.
e.
for each airhead in the sample at the rate of 2 appropriate space on cubic feet
/ min.
Form MS-2.
If the Therefor e, for a 24-hour Observed value exceeds sampling period, C x F 2 x 10-12 microcuries per should not exceed 1056 dpm.
l ml., notify laboratory super-A week's sample would be vision immediately.
7 times this, or 7392 dpm.
Actual volume through the air sampling system is to be checked at various intervals, adjusting each airhead to 2 cubic feet /
min. with clean filter papers in all heads, f.
The completed survey sheet f.
(Form MS-2) is to be turned over to the secretary for filing. These sheets are to be I etained permanently as r equir ed by law.
2.
Effluent from Exhaust Blower l
l During at least one 8 hr. working period each week, we are required to sample the effluent from the exhaust blower if we are processing uranium.
j If plutonium is being processed, continuous effluent sampling is required.
This is accomplished by use of a special air sampling unit installed in an area beyond the final absolute filtering system where maximum mixing j
of air is taking place. Data required during sampling are (1) flow rate and (2) total collection time. The sample is counted and calculated as in s ection C.1.
The results are entered on Form MS-2 and given to the s ecr etary for filing. This sheet is retained as a permanent record as required by law.
3.
Other Air Samples Certain special operations require that the atmosphere in the area of the special operation be sampled. Examples of such operations are glove changes, bag changes, new operations, and spill cleanups. For these situations, the portable U. S. Nuclear air sampler is to be used.
A minimum of 20 cubic meters of air must be sampled. The sample is counted and calculated as in section C.1.
The results are entered on Form MS-2.
If the calculated results exceed 2 x 10~
microcuries per ml., notify laboratory supervision immediately.
l I.
D.
Surface Contamination 1.
Weckly Survey We are required by law to survey floors and working surfaces once each week for surface contamination. This is accomplished by taking smears of selected locations to determine the removable contamination. The maximum permissible level here is 10 dpm per 100 square centimeters. Each smear should be taken over an ar ea 12 " x 12 ". This is equivalent to 929 sq. cm.
The maximum permissible count per square is then 92. 9 dpm, Smears are taken with 2" diameter filter papers. They may then be counted in exactly the same manner as the air samples.
Smears are always to be taken before scrubbing rather than after.
a.
On Form MS-3 enter the a.
This form is a scale draw-required data for identifi-ing of the laboratory which cation of date, operator, is marked off in numbered etc.
squares. These numbers indicate the location of the smears.
b.
Using a dif>posable sample b.
Smears will be collected collection book, collect the alternately from odd and requir ed smears.
even numbered squares on a weekly basis. In this way every square will be sampled on a bi-weekly
- basis, c.
Count each sample for 5 c.
minutes.
d.
Enter the counts per minute d.
on Form MS-3 and give to laboratory supervision for ins pec tion. If any hot areas are found, irnmediately notify personnel working within the area.
t
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a i
i Laboratory supervision will e.
c.
give.the work sheet to the secretary for filing. The 4
results of these surveys are to be maintained as permanent records.
2.
Spot Surveys Whenever a major spill occurs or a group of hot airheads are observed, a complete survey of the affected az ca will be 4 immediately te determine the extent of the con-c.
4 ta n.
nults are to be recorded and filed in exactly 1
the san.
3r as in section C.1.
3.
Survey of L pment to be R emoved from R estricted Area No equipment may be removed from the restricted area unless it has been monitored and found to have no more than 10 dpm i
of fixed and removable contamination. In checking such equipment, the surface should first be checked with the portable alpha survey meter. All interior surfaces and hard to monitor exterior surfaces should then be smeared ei counted in the gas proportional flow counter. If fixed and removable contamination is below 10 dpm, an approval for release tag signed by the monitor and laboratory supervisor is attached to the equipment before removal. If contamination levels are in excess of these limits, the equipment must be further decontaminated before r elease.
4 4
_9
~ -
E.
Liquid Waste Disposal Before any liquid waste is released for disposal into the sanitary
~4 sewer it must be shown to contain less than 1 x 10 mic rocuries per ml. of total radioactivity. To accomplish this, two separate holding tanks are provided. The larger of these two tanks retains the water waste from the shower room and laundry. The smaller of these tanks retains water from the sink in the hot room. An automatic alarm will sound indicating when the tanks are full.
The procedure to be followed is described below.
1.
Close the waste dump valve.
1.
on the tank.
i 2.
Open the recirculating valve.
2.
3.
Turn on the pump and circu-3.
late the tank contents for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
4.
Open the sampling valve ar.d 4.
withdraw approximately 30 mi. of the sample solution.
5.
Pipette two 10-ml. aliquots 5.
into cican beakers.
6.
To one aliquot add 1 ml. of 6.
This spike solution is used spike standard solution to calculate self adsorbtion contair.ing 1 x 10-4 micro-by salts in the waste solution, curies /ml. of uranium.
to 7.
7.
Add 5 ml. of conc HNO3 each beaker and evaporate the solution to near dryness under an infrared lamp.
8.
Transfer the solution to a 8.
Car e should be taken to counting planchette with a distribute the film as minimum quantity of evenly as possible over distilled water and evaporate the surface of the planchette. ;
to dryness.
2 e
i o
1 i
9.
When dry, heat to dull red 9.
heat over a bunsen burner for 15 seconds.
10.
Cool and count in the gas 10.
i proportional counter after l
first checking the counter efficiency factor with a i
r eference standard.
j 11.
Calculate recovery factors 11.
by the following formula:
i l
C - Cu s
K=
'T wher e K = recovery factor C
s = counts for spiked sample i
Cu = counts uns. piked sample C
= theoretical counts from spike (This is the 4
T theoretical count rate multiplied by counter efficiency. )
j 12.
Calculate microcuries /ml.
12.
as follows:
Cu pc /ml. = V x K E x 2.2 x 10 6 i-where Cu = observed counts of unknown i
l V = volume of sample K = recovery factor E = counting efficiency 13.
Enter the results of this
. 13.
calculation on Form MS-4 c.
together with all pertinent data and sign the form.
l 1
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,.<,,-e,,,,.
-w..,-.--v,,..,,..,,,..n--
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- 14. Give the form to laboratory 14.
j supervision for a decision as to whether the salvage may be dumped.
j 4
i
- 15. Supervision will sign the 15.
form and return to the sec-i retary for filing. This form will be retained as part of j
our permanent records.
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n
r V
General Operating Procedures In addition to the specific surveys previously discussed, there are several general operating procedures whicn muet be adhered to by all operating personnel. These are described in the following section.
A.
Protective Clothing When handling radioactive materials, certain minimum protective clothing standards must be adhered to.
These standards are as follows :
Uranium - Under normal conditions a laboratory coat is considered s ufficient. A respirator must be kept available. In the event of a major spill, converalls, surgeons cap and gloves, booties, and a respirator are required.
Plutonium - When handling plutonium, c overa lls, surgeons cap and booties are to be worn. A respirator and surg aons gloves are to be carried at all times. Respirators and gloves must be worn for transferring samples, cutting salvage bags, changinggloves on the boxes, and for any other operation where the uncontrolled release of plutonium could occur. Clothing to be changed daily just before lunch.
B.
Monitoring Protective Clothing Each person is required to monitor his clothing and person each time he leaves the hot area for the mass spectrometer room or the shower room. Each person is required to monitor his clothing before leaving the mass spectrometer room for other areas of the pla nt.
% 'j t,
If in checking protective clothing a hot spot is observed, the fonowing procedures are to be followed:
1.
0-50 dpm Clothing is considered cold and may be used.
2.
50-1000 dpm Proceed to the change room and change clothing.
Place hot clothing in the covered containers provided.
3.
1000-5000 dpm A change of clothing will be brought to the individual in the hot area. The contaminated c1cthing will be placed in a plastic bag and marked for special laundering.
4.
>5000 dpm A change of clothing will be brought to the hot area. The contaminated clothing will be sealed in a plastic bag and placed in a salvage drum for offsite burial. 4 y
s
adt Y C.
Instrument Operability Checks Each survey meter must be checked daily to determine if it is operable. The procedure is as follows:
1.
Using a calibrated source, 1.
obtain a reading from the instrument under test.
2.
If the two counts differ by 2.
more than 20%, the meter must be recalibrated.
3.
During each quarter, each 3.
meter must be recalibrated using certified standards and manufactur er 's sugges ted procedures.
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a APPROVED:
q, u
/.,,, / J /
/ '/-.
= u w o g J6n'W. Harrison
/ Radiation Safety Officer
/
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/