ML20040E573
| ML20040E573 | |
| Person / Time | |
|---|---|
| Site: | 07002626 |
| Issue date: | 10/07/1981 |
| From: | Horne S, Savaiko B ARMY, DEPT. OF |
| To: | |
| Shared Package | |
| ML20040E569 | List: |
| References | |
| 20113, NUDOCS 8202050125 | |
| Download: ML20040E573 (31) | |
Text
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DEPARTMENT OF THE ARMY COMMUNICATIONS - ELECTRONICS COMMAND ENVIRONMENTAL ASSESSMENT AND FINDING OF N0 SIGNIFICANT IMPACT FIELDING OF THE AN/UDM-7C RADIAC CALIBRATOR SET FORT MONMOUTH, NEW JERSEY OCTOBER 7, 1981 PREPARED BY:
APPROVED BY:
bf is (f}]gj STEVEN A. HORNE BERNARD M. SAVAIKO CHIEF, READINESS DIVISION CHIEF, SAFETY OFFICE SAFETY OFFICE COMMANDER DESIGNEE
@202050125 811223 PDR ADOCK 07002626 C
l FINDING OF NO SIGNIFICANT IMPACT AND ENVIRONMENTAL ASSESSMENT Proposed Action:
Fielding of the AN/UDM-7C Radiac Calibrator Set Lead Agency:
Commander US Army Communications-Electronics Command Affected Jurisdiction: Lexington-Blue Grass Depot Activity (LBDA), Lexington, Kentucky, the US Army Ionizing Radiation Dosimetry Center of the Test Measurement Diagnostic Equipment Support Grcup at LBDA, and Department of Defense Installations and Activities Worldwide Preparer:
Commander US Army Communications-Electronics Command -
ATTN: DRSEL-SF-H Fort Monmouth, New Jersey 07703 Coordinator:
Steven A. Horne Ch%f, Readiness Division Safety Office (201) 544'-4427 Rev e y:
Bernard M. Savaiko-4-
Chief, Safety Office (201) 544-4427 D
D
...y
. _,. ~...
TABLE OF CONTENTS I.
Finding of No Significant Impact II.
Environmental Assessment A.
Summary and Conclusion B.
Description and Proposed Fielding of the AN/UDM-7C Radiac Calibrator Set C.
Environmental Impact of Fielding the AN/UDM-7C Radiac Calibrator Set D.
' Evaluation of Alternatives E.
Status of Compliance F.
Listing of Agencies / Persons Contacted G.
References H.
Inclosures 1.
MIL-R-24265 (SHIPS) 2.
NAVSHIPS 0967874-9010 l
3.
TM 3-6665-247-10
- 4. - 7.
Technical Drawings RE-F2696577 (RE 101 F2002) u
/
i L '
I
I.
Finding of No Significant Impact 1.
Fielding of the AN/UDM-7C Radiac Calibrator Set into the US Army Supply System has been proposed for February 1982. These calibrators incorporate Plutonium (Pu)-239 for the calibration of alpha radiation detection instruments. The AN/UDM-7C Radiac Calibrator Set has been selected for use based on its capability of calibrating all existing type classified Army alpha radiation detection instruments and previous successful use by the US Navy for the past twenty years. The Environ-mental Assessment documents all safety protocol implemented during use, transfer or disposal and demonstrates compliance with all regulatory requirements. The following etatements briefly summarize the program developed for safety and control:
Maximum safety is designed into the material and equipment with quality a.
assurance testing for source and unit integrity prior to release for use.
b.
Authorized users must meet minimum radiation protection training require-ments before they are qu'alified to perform activities involving the AN/UDM-7C Radiac Calibrator Set.
Technical Manuals and instructions are supplied concerning proper operating c.
procedures and radiation safety policies with notice given regarding potential hazards and precautions to be implemented.
d.
Logistical control and accountability procedures are rigorous, insuring authorized possession and proper distribution.
'~
e.
Facilities are specifically designed for storage and use of the calibrator set.
f.
Transfer procedures are compliant with packaging and labeling safety
- criteria, g.
Disposal procedures are specific for the calibrator set.
II. Quarterly leak testing is performed insuring no detectable levels of remov-able contamination.
2.
Based upon its stringent control, all hypothetical incidents involving occupa-tional hazards or release to the environment due to the possession of the AN/UDM-7C are considered highly improbable.
Incidents included the evaluation of source leak-age, improper disposal, installation fire, and transport accidents leading to contam-ination of the occupational worker and/or environmental release. The evaluations determined that there were no external or internal dose levels above those permitted by regulatory standards or recommendations.
It was further determined that no significant radiological health or environmental hazard was discernable with the impicmentation of the AN/UDM-7C Radiac Calibrator Set incorporating Pu-239.
Alterna-tive radionuclides considered as substitutes for Pu-239 as an alpha calibration source are not identified to possess any significant overall advantage due to similar radio-tox icit y, less tisu optimal energy required, increased external exposure and greater expense. The adoption of the AN/UDM-7C Radiac Calibrator Set provides the ideal immediate calibration source for all existing type classified alpha detection instru-mentation eliminating unnecessary redesign of another radiac calibrator assembly.
3.
The proposed action is non-substantive, exclusive of environmental quality degradation, and therefore does not require an Environmental Impact Statement. The Environmental Assessment is available for review upon request from Commander, US Army Communications-Electronics Command, ATTN: DRSEL-SF-H, Fort Monmouth, New Jersey 07703.
1
II.
Environmental Assessment A.
Summary and Conclusion 1.
The US Army Communications-Electronics Command (CECOM), concurrent with an application for a US Nuclear Regulatory Commission (NRC) license to receive, own, acquire, deliver, possess, use, and transfer special nuclear material, has prepared the following environmental assessment in compliance with Title 32, Code of Federal Regulations (32 CFR), Part 651, Environmental Quality, Environmental Effects of Army
^
Actions. The assessment is required prior to acquisition of radioactive materials into the CECOM material life cycle control which has been proposed for February 1982 with the introduction of the AN/UDM-7C Radiac Calibrator Set incorporating Pu-239.
2.
This document includes:
a.
The proposed use, need, and description of the AN/UDM-7C Radiac Calibra-tor Set, inclusive of maximum safety design specifications and Army policies more restrictive than governing regulatory requirements.
b.
Alternatives available for substitution based on resources, risk, and benefit anal"sc=.
Radiological impacts with resulting dose assessments from hypothetical c.
accidents or misuse.
The comprehensive evaluation is in support of a Finding of No Significant Impact documenting no potential degradation of environmental quality or significant radiologi-cal impact to occupational or public health.
3.
The intended use of the AN/UDM-7C Radiac Calibrator Set is solely for cali-bration of alpha radiation detection instruments employed for tactical (field) and health and safety purposes. All unit design specifications, authorized user qualifica-tions, location and control of calibrator use and accountability, transfer and disposal are outlined in Section B.
These meet stringent Army safety policies compliant with governmental agencies having jurisdictional control. For the AN/UDM-7C Radiac Calibra-tor Set, further control has been established as distribution is limited by approval from the Department of the Army based upon previously established authorization of user organizations to receive the item from a supply standpoint along with specific storage requirements, special handling and maintenance procedures, and exclusive dis-posal through the US Department of Energy (DOE).
4.
Properly implemented safety procedures for actions involving calibrator sets precludes any unnecessary radiation exposure to the cccupational worker and excludes consideration of any potential release to the environment.
In determining radiological l
hazards to the occupational worker, assessments for both external and internal doses l
were performed.
The annual external dose received from continuous exposure to the 1.86E+06 becquerels (Bq) (5.03E+01 microcuries (uC1)) of Pu-239 is conservatively esti-mated to be 4.38E-07 sieverts (Sv) (4.38E-05 rem) or 8.76E-04 percent of the occupational exposure limits set forth in 10 CFR Part 20.
This is also consistent with the As Low As Reasonably Achievable (ALARA) c,oncepts adopted by the NRC.
For the internal dose, it l
was assumed that the individual ingested Pu-239 af ter coming directly into contact with a contaminated source. This evaluation yielded the greatest potential hazard assessable j
2 l
l f
for all incidents.
The maximum committed dose equivalent of 2.44E-02 Sv (2.44E+00 rem) was obtained for the bone surface which has a high fractional deposition factor and the longest biological half-life for retention of Pu-239.
This is below non-stochastic dose equivalent limits recommended in the International Commission on Radiological Pro-tection (ICRP) Publication 30.
The total activity ingested was 5.80 percent of the Annual Limit of Intake (ALI) also specified in ICRP 30.
Hypothetical incidents involving improper disposal, installation fire, and transport leading to potential release of radioactive material to the environ or possible intake into the body are described and also result in committed dose equivalents below recommendations.
Complete derivation of the evaluations is provided for review in Section C.*
5.
The specific need for the AN/UDM-7C Radiac Calibrator Set is evident with its capability to calibrate all type classified alpha radiation detection instruments presently, or which will be incorporated into the Army supply system. Alternatives considered in Section D provide no overall advantage. Department of Defense (D0D) policy precludes development of new items when existing supply items are available and are adequate for functional needs. Minimal radiological risk is associated with the AN/UDM-7C Radiac Calibrator Set which has been used under US Navy control for approxi-mately twenty years with no adverse indication demanding discontinuation of calibrator usage.
It is estimated that ten years of research and development would be required for redesign of a calibrator set necessitating tremendous needless financial and manpower resources.
6.
This assessment does not consider the worldwide fielding of the AN/UDM-7C Radiac Calibrator Set environmentally controversial, as it is neither capable of signi-ficantly af fecting the quality of the human environment nor is it demonstrative of radiological impact.
B.
Description of the AN/UDM-7C Radiac Calibrator Set 1.
The AN/UDM-7C Radiac Calibrator Set incorporates two radioactive sources, one containing 1.84E+06 Bq (4.97E+0 luc 1) and one of 1.84E+04 Bq (4.97E-01 uCi) as Pu-239 Chloride. Military Specification R-24265 (SHIPS) (Incl 1) outlines standards for manuf acturing requirements, source / resin composition and integrity, and quality assurance testing for all calibration components. To summarize, one hundred percent of the radioactive source disks are tested for uniformity requirements prior to assembly into casings. Onehundred percent of the sources are also tested for accuracy and leak-age requirements in their completed configuration. In addition, a random sampling of ten percent of the completed AN/UDM-7C Radiac Calibrator Sets are tested for specific resin properties, uniformity, accuracy, enclosure, shock, vibration, and leakage requirements. Any calibration not meeting test standards will not be incorporated into the Army supply system. Design is suitable to performance requirements and without any portion of the equipment creating hazard to personnel or vital systems.
2.
Reference should be made to NAVSHIPS 0967 874-9010 (Inc1 2), Technical Manual (TM) 3-6665-247-10 (Incl 3), and Technical Drawings (Inci 4, 5. 6 and 7) for diagrams and complete detail of the structural design of the calibrator set.
The radiac calibrator set is composed basically of two aluminum source holders containing the Pu-239 alpha sources, an accessory drawer providing storage of attenuators, instruc-tion manual, tweezers and probe positioner, a surrounding aluminum cabinet and a hardwood carrying case securing all components.
Calibrators are marked with adequate radiation labels containing the radiation caution symbol and the appropriate warnings 6
- The use of exponential (scientific) notation, i.e.,1.86E+06 (1.86 x 10 ) is employed in lieu of standard notation, i.e.,
1,860,000.
3
with instructions for proper handling. Radiation safety policies dictate assurance of qualified users, proper labeling and provision for the technical (operating) manual outlining potential hazards, precautions to be implemented and procedure for calibration of alpha radiation detection instruments for maximum user safety. The aluminum shield-ing provides complete attenuation of the Pu-239 alpha particle during storage and transport. The very low percent abundance of gamma emission does not present external dose hazard as assessed in Section C.
All packaging and labeling of the calibrators meet UC Department of Transportation (DOT) Specification 7A Type A packaging.
~
3.
The AN/UDM-7C Radiac Calibrator Set will be utilizel at Lexington-Blue Grass Depot Activity (LBDA), Lexington, Kentucky, the US Army Ioni:Ang Radiation Dosimetry Center of the US Army Test Measurement Diagnostic Equipment Support Group located at LBDA, and DOD installations and activities worldwid e possessed under the control of the US Army military and/or civilian personnel on the basis of approved facilities, radiation safety standards, procedures, and qualifications of authorized user, i.e., TM 3-6665-247-10 (Inci 3) and Army Regulation (AR) 385-11.
Radiac Calibrator Sets issued to authorized activities are for calibration of specific alpha raciation detection instruments, i.e.,
the AN/PDR-54, AN/PDR-56F, and AN/PDR-60 Radiac Sets.
Operations are supervised by a qualified radiation protection of ficer (RPO) and performed with maximum safety procedures as outlined in IM 3-6665-247-10 insuring lowest achievable occupational exposures. For personnel dosimetry purposes, bicassays are available and provided when needed by the Surgeon General of the Army.
4.
Elements authorized to possess alpha radiation detection instrumentation will not necessarily be authorized to possess the calibrator set.
Typically, instrumentation will be sent to authorized calibration activities or will be calibrated by a visiting mobile calibration team. Most of the sets will be used by four to seven-man mobile calibration teams. Individuals utilizing these calibrators will have received at least 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> training in the principles and practices of radiation protec-tion which includes specific training in the safe use of the calibrator set.
Users are provided with specific instructions on the operations, safe handling, control and main-tenance of the calibrator as described in inclosure 3.
5.
CECOM will individually control the logistics of the AN/UDM-7C, serve as National Inventory Control Point (NICP) for the item, and assure that requesting elements are authorized to, and technically capable of, receiving the item in accordance with the NRC license. The Army program for control of radioactive items of supply is prescribed in two regulations, AR 385-11 and AR 700-64.
CECOM has adopted special procedures in addition to standard Army supply practices used for all type classified items. The control point maintains records of procurements, receipts, storage locations, shipments, using locations, authorizes, issues, and assures adequate supply.
It reviews requisitions submitted and when approved, issues material release orders to the designated depot for shipment of the material to the requisitioner.
6.
Each major command has established at the headquarters level a radioactive material control point (RMCP) and appointed a radiation control officer (RCO) to admin-ister control of radioactive items within the command. The RCO reviews and concurs in the qualifications of local RP0s within the command, maintains records of radioactive items by location and assures periodic inventory and leak tests by using activities, performs periodic inspections / audits of accountable installations / activities to assure that items are properly handled in accordance with Army and NRC regulations, and to assure the submission of inventory and leak test reports and accident / incident reports.
4
The local RPO is responsible for administering the local radiation protection program.
Local programs provide for designated controlled areas, dosimetry, instrumentation, operating procedures supplementing published manuals for the items, receipts, transfers, storage and records. Requisitions originated by using elcments are forwarded to NICP where all requisitions are reviewed and approved.
7.
Facilities for use and storage of the AN/UDM-7C Radiac Calibrator Set will be designated radiation controlled areas for those purposes as approved by the local Rp0.
Sets used by the mobile calibration teams will be used and stored in specially designed vans, access to which is limited to team members. The sets will be used and stored in fire resistant buildings, in controlled areas and secured against unauthorized removal. Areas / buildings will be posted with appropriate radiation warning signs. LBDA storage, maintenance and serviceability installations used for bulk storage of the AN/UDM-7C Radiac Calibrator Set are constructed of concrete block and steel. The cali-bration and storage rooms are constructed of 36 inch poured concrete with a door containing k inch of lead shielding. The installation is protected by a fire sprinkler system which is tied to the LBDA self supporting fire department. The fire department has a maximum response time of two to three minutes to its furthest building. The recurity of the installation is such that all buildings are locked when not inhabited and the perimeter of LBDA is secured by chain-linked fence with roving patrols and sentries at the gate again eliminating any possibility of unauthorized possession.
8.
Packaging and shipment of the AN/UDM-7C is in compliance with DOT regulations as outlined in inclosure 3.
No more than ten each AN/UDM-7C Radiac Calibrator Sets will be transported per individual shipment following CECOM instructions insuring maximum safeguarding against the worst conceivable transport incident.
9.
Ultimate disposal of the AN/UDM-7C Radiac Calibrator Set will be in accor-dance with AR 385-11, AR 700-64 and 10 CFR.
Request for disposition of Pu-239 as contained in the AN/UDM-7C Radiac Calibrator Set must be made through Army channels to headquarters US DOE, This agency provides disposition instructions inclusive of com-pliance requirements under DOT regulations for shipment to the DOE site located in Oak Ridge, Tennessee. No radioactive waste is anticipated except in cases of damage beyond use of the sources. Unserviceable calibrator sets will be returned to LBDA for repair or replacement of nonradioactive components and examination, leak testing, reorientation of the sources if necessary, recalibration and return to depot stock.
10.
The described parameters associated with use of the AN/UDM-7C Radiac Cali-brator Set indicates the most stringent governing policies practically applicable for prevention of any radiological hazard to any individual involved occupationally or nonoccupationally during the use or transport of the calibrator set.
Army regulations are compliant with NRC and DOT requirements and are implemented in the most restrictive manner for maximum safety.
C.
Environmental Impact of Fielding the AN/UDM-7C Radiac Calibrator Set 1.
No radiological impact can be associated with the AN/UDM-7C Radiac Calibra-tur Set under normal operating conditions following proper procedures. The external dose equivalent from gamma emission for an occupational worker revealed a total whole body dose f rom the 1.84E+06 Bq (4.97E+01 uCi) Pu-239 source based on continuous exposure tobe4.38E-g7Sv (4.38E-05 rem) per year (yr) derived from the following dosimetric calculations and assumptions:
5
P e
i 8
I h
I
~
n e
l I
R I
o g FIGURE C-1 Assuming a diek source (Figure C-1) of uniform activity distribution a.
at an operating position (P) of height (h) 30.5 centimeters (cm) above and distance (d) 30.5cmawayfromthecenter(Q)ofthesourcewhoseradius(R)gquals15.9cmanf),
ityconcentrationperunitarea(C)is2.32E-03Bq7cm (6.30E-08 Ci/cm whose actly/sec) at P is calculated by:
A I
(MeV/cm (R
+h
- d ) + [(R
+h
-d) +4dh]
I,= 2.96E+09 EC 7r in A
2 2h Upon substitution of appropriate values, each individual gamma energy of Pu-239 with its associated intensity determined final flux (I ) calculations as summarized in g
Table C-1.
b.
For the absorbed dose rate (Gy/h) to tissue the following formula was employed:
Gy/h = 5.76E-05 (u,med/ med)I /100 g
where u ""d = linear absorption coefficient (cm- )
[med = mass density of the absorbing medium (g/cm ; fgr tissue the value is assumed equivalent to water, i.e., 1.0 g/cm )
med u
/ med = mass absorption coefficient (cm /gm) or equivalent to mass energy absorption coef ficients at varying energies in a tissue medium.
6
.w r
TABLE C-1 Individual Gamma Flux Values and Final Absorbed Dose Rates E(MeV)
Camma Intensity MeV/disintigration I (McV/cm /sec) u tissue Gy/h (rad /hr) 1.
0.039 7.00E-05 2.73E-06 2.17E-04 7.29E-02 9.10E-12 (9.10E-10) 2.
0.052 2.00E-04 1.04E-05 8.28E-04 3.74E-02 1.78E-11 (1.78E-09) 3.
0.129 5.00E-05 6.45E-06 5.14E-04 2.65E-02 7.86E-12 (7.86E-10) i 4.
0.375 1.20E-05 4.50E-06 3.58E-04 3.27E-02 6.74E-12 1
(6.74E-10) 5.
0.414 1.20E-05 5.00E-06 3.98E-04 3.29E-02 7.54E-12 (7.54E-10) 6.
0.650 8.00E-07 5.20E-07 4.14E-05 3.27E-02 7.80E-13 (7.80E-11) 7.
0.770 2.00E-07 1.54E-07 1.23E-05 3.22E-02 2.28E-13 j
(2.28E-11) l f
l i
t l
i.e., (H O) since / med is equivalent to 1.0 g/cm.
2 Table C-1 can be used for review of substituted values and final absorbed dose rates determined for each gamma flux which when summed result in 5.00E-11 Gy/h (5.00E-09 rad /
hr). Assuming a quality factor and dose modifying factor of one (1) for gamma energies, the dose equivalent value can be stated as 5.00E-ll Sv/h (5.00E-09 rem /hr) or 4.38E-07 Sv/yr (4.38E-05 rem /yr).
c.
For occupational exposure, the ICRP recommends the value of 0.05 Sv per year for the stochastic dose-equivalent limit for uniform irradiation of the whole body.
The NRC occupational exposure limits, as specified in 10 CFR Part 20 allow for an occupational whole body dose of 5 rem per year. The exposure presented under normal usage demonstrates no excessive occupational radiation level and is, in fact, magnitudes below standards specified for the general public or non-occupational individuals, d.
Estimates given for external dose were not inclusive of the greater operating distance the user maintains and are therefore in excess of the theoretical dose calculated. The radionuclidic purity of the Pu-239 source is greater than 99.0 percent eliminating consideration of any other gamma energies associated with the decay scheme and applicable to dosimetric calculations. Consideration of alpha particle absorption is insignificant since tge distance traveled in air for the 5.11 MeV and 5.16 MeV alpha particles is calculated to be approximately 3.78 centimeters and would not penetrate the uppermost layers of epithelial tissue or reach any radiosensitive tissues. Thus, the greatest radiobiological hazard from Pu-239 results from inhalation or ingestion limiting the biological damage to closely surrounding tissues.
2.
In the event safety criteria are not properly implemented, internal exposure due to the highly ionizing alpha particles of Pu-239 subsequent to inhalation or ingestion is considered in order to demonstrate levels less than those permissible under ICRP 30 recommendations and regulatory standards. The hypothetical incidents cited assess possible radiological hazards presented to either the occupational worker or the general public. The described incidents are highly improbable but demonstrate unequivocally the final resolution that there would be no significant environmental impact resultant from implementation of the AN/UDM-7C Radiac Calibrator Set.
a.
Source Leakage:
(1) The AN/UDM-7C Radiac Calibrator Set is required to be leak tested for removs'le contamination every three months under safety requirements employing pro-tective har.dling procedures as outlined in inclosure 3 for every user.
In a highly improbable situation of source leakage without detection, the following severe condi-tions are presented:
(a) Ten percent of the total Pu-239 activity (1.86E+05 Bq or 5.02E+00 uC1) is available for contamination evenly distributed over an accessible area.
(b) The access having a total area of 737.8 an{ble area is considered tg be the probe pos{tioning well yielding 2.52E+02 Bq/cm (6.80E-03 uC1/cm ).
8
l (c) Twenty-five percent of the contaminated area (184.45 cm ) transfers to the user resulting in a total of 4.60E+04 Eq (1.25E+00uci) of contamination.
Twenty-five percent of the contamination (1.16E+04 Bq or 3.10E-01uci) is ingested.
(2) The committed dose equivalents to various organs f rom ICRP 30 data are tabulated in Table C-2.
The maximum dose equivalent of 2.44E-02 Sv estimated for the bone surface area is below non-stochastic dose equivalent limits. The total ingested activity of 1.16E+04 Bq is 5.80 percent of the given ALI (2.00E+05 Bq).
(3) The occurrence of this incident is not recognized as having a high pro-bability due to user training, technical manuals indicating potential hazards, protective handling requirements, and routine testing for removable contamination.
b.
Source Loss Leading to Improper Disposal to an Incinerator:
(1) The following case has assessed incineration of AN/UDM-7C Radiac Calibra-torSetsimplementingtheanalysisprovidedinNUREC/CR-1156,gnvironmentalAssessment
+
of Ionization Chamber Smoke Detectors Containing Americium-241. It is inconceivable that a Pu-239 source mounted onto its aluminum shelf or the entire unit itself could be transferred unknowingly to an incinerator.
Both the aluminum shelf and calibrator set are marked with radiation symbols and radioactive material identification labels to exclude occurrence. The assumptions used to estimate the amount of Pu-239 in incinera-tor emissions are as follows:
(a) Five AN/UDM-7C Radiac Calibrator Sets are incinerated giving an initial activity (Q ) of 9.29E+06 Bq (2.51E+02 uC1) releasing one hundred percent (f )
i 1
s twenty four hours. The installed air pollution control system ef ficiency is 90 percent (f = 0.1).
r (b) Fif ty percent excess of the thgorectical volume of air required for complete combustion of one pound (1b) is 2.00E+06 cm /lb (V ).
The weight of refuse incinerated j
(W ) is 6.60E+05 pounds.
(2) The atmospheric dispersion coef ficient (X/Q) is assumed to be 2.00E-05 3
g (3) The total activity released in a day (Q), given by the formula Q=Q f f,
f*#
is 9.29E+05 Bq (2.51E+01 uCi).
(4) The continuous release rate (Q') over twenty-four hours is 1.07E+01 Bq/s (2.90E-04 uCi/sec).
(5) Assuming a constant wind speed of one meter per sec under stable meteo-1
]
generalformulaX=Q'(X/Q)isestimatedtobe2.15E-04Bq/m}substitutingin5).the rological conditions, the maximum downwind concentration (X (5.80E-09 uCi/m (6) If an average daily breathing rate of 20.0m per day is assumed, the maximum exposed individual would inhale approximately 4.30E-03 Bq (1.16E-07 uC1).
(7)
If the average person is proposed to inhale one-third of this concentration, the total activity is 1.41E-03 Hq (3.86E-08 uCi). Approximations of committed dose equivalents to various organs using ICRP 30 data are summari' zed in Table C-3.
(8) Realistic consideration of the above incident is eliminated based on user ability to maintain proper authorized possession and accountability with negligible occassion arising where its control escapes user awareness to the extent a calibrator set 9
1
I TABLE C-2 a t Committed Dose Equivalents to Various Organs Following Ingestion Activity Ingested Gonads R. Marrow Bone Surface Liver 1.16E+04 Bq 3.02E-04 Sv 1.86E-03 Sv 2.44E-02 Sv 5.10E-03 Sv j
(3.10E-01 uCi)
(3.02E-02 rem)
(1.86E-01 rem)
(2.44E+00 rem)
(5.10E-01 rem) i l
I
(
\\
TABLE C-3 c$
Committed Dose Equivalents to Various Organs Resultant fromInhalation Following Source Incineration o
Activity Inhaled Conads R. Marrow Bone Surface Liver Average Exposed Person 1.43E-03 Bq 4.57E-08 Sv 2.86E-07 Sv 3.57E-06 Sv 7.57E-07 Sv (3.86E-08 uC1)
(4.57E-06 rem)
(2.86E-05 rem)
(3.57E-04 rem)
(7.57E-05 rem)
I Maximum Exposed Person 4.30E-03 Bq 1.38E-07 Sv 8.60E-07 Sv 1.10E-05 Sv 2.28E-06 Sv (1.20E-07 uC1)
(1.38E-05 rem)
(8.60E-05 rem)
(1.10E-03 rem)
(2.28E-04 rem) i I
4
is transferred to an incinerator.
3 (9) The maximum downwind concentration was estimated to be 2.15E-04 Sq/m 3
(5.80E-09 uCi/m ) which is below regulatory standards. The air concentration limit for unrestricted areas as specified in 10 CFR Part 20 is given as 2.22E-03 Bq/m3 (6.00E-14 uCi/ml) for soluble forms and 3.70E-02 Bq/m3 (1.00E-12 uCi/ml) for insol-uble forms. This limit is based on the standard for non-occupational radiation exposure which is 5.00E-03 Sv/yr (5.00E-01 rem /yr).
3 c.
Source Loss Resulting in Improper Disposal Directly to a Public Landfill:
(1) Under the assumption five incinerated calibrator sets are hypothetically disposed in a solid waste landfill. Exposure could result to population groups through ingestion of contaminated ground water or food crops and inhalation of resuspended radioactivity. The environmental health impact resulting from the contamination of ground water by disposal of calibrator sets in a landfill is assessed witc the following parameters:
(a) Leaching d source activity from five incinerated AN/UDM-7C Radiac Cali-brator Sets is assumed to be 100 percent. The total activity (A ) in the landfill is t
9.30E+06 Bq (2.51E+02 uC1),
(b) Fifty percent of the leached activity (fL1) enters the groundwater with-out further dispersion.
(c)
The total volume (V ) of leachate generated per year from an average 25 t
acre landfill based on US Environmental Protection Agency (EPA) estimates is 6.76E+06 gallons (2.57E+10ml) accounting only for the average precipitation infiltrate of ten inches per year.
(d) There is no significant dilution (fL2) of the zone of contamination from surrounding groundwater (fL2 equals one (1) assuming no significant dilution).
(e) One percent of the contaminated water is withdrawn for domestic water supply (fdl) and five percent is consumed as drinking water (fd2)*
(2) The concentration (Bq/m3) of Pu-239 in the leachate (A ) as it enters L
the zone of saturation would be calculated by:
AL " A 'L1 L2 L t
SubstitutAng the appropriate values, the average Pu-239 concentration in all the leachats generated would be 1.81E+02 Bq/m3 (4.90E-09 uCi/ml).
(3) The amount of activity ingested (A as a result of contaminated water in the public drinking water supply is estimatek"$y):
^ing " L'd1'd2b Substituting values estimated "in c(1)(c and e) and :(2), the dietary intake by the entire population (73,000) surrour. ding the landfill would be 2.30E+03 Bq (6.30E-02 uC1).
The average individual dietary intake would be 3.20E-02 Bq (8.60E-07 uCi).
I1
(4) The dose commitment to the maximally exposed individual is assessed with the assumption that the annual dietary intake of water (I is 370 liters (1) and consists entirely of ground water contaminated with Pu-235)at the same concentration 3
as calculated for leachate (AL = 1.81E+02 Bq/m ) incorporated into the formula:
Aing " I AL W
The resultant ingestion is 6.70E+01 Bq (1.80E-03 uCL). The Pu-239 intake and committed dose equivalents due to leaching from a landfill to accessible drinking water is summarized in Table C-4.
(5) The maximum permissible water concentration for unrestricted areas is specified in 10 CFR Part 20 and given for Pu-239 to be 1.85E+05 Bq/m3 (5.00E-06 uCi/ml) for soluble forms and 1.11E+06 Bq/m3 (3.00E-05 uCi/ml) for insoluble forms. The con-3 centration of the radionuclide in the leachate (1.81E+02 Bq/m ) is a very small fraction of the permissible limits, i.e.,
approximately 9.80E-02 percent of the soluble limit and 1.60E-02 percent of the insoluble limit.
l d.
Installation Fire:
(1) The proposed incident involves an installation fire occurring during bulk storage at LBDA in which AN/UDM-7C Radiac Calibrator Sets are incorporated releasing Pu-239. The warehouse facility is equipped with complex sprinkler systems covering 100 percent of the area and an automatic alert to the LBDA firefighting unit which has at maximum a two to three minute response time. The firefighter unit is aware of the radioactive material storage area and has standard operating procedures inclusive of protective clothing, self-contained respiratory devices and procedures limiting water usage and evacuation of personnel from downwind areas immediately if necessary. The hypothetical incident assumes the following for occupationally involved firefighters in the immediate vicinity performing extinguishing operations:
(a) The maximum number possibly stored at any time in the installation is 300 units, each containing 1.86E+06 Bq (5.03E+01 uCi).
(b) Prior to extinguishing the fire, 100 units are involved releasing 0.01 percent of the Pu-239 activity as airborne particulates, i.e., 1.86E+04 Bq (5.00E-01 uCi) during a one hour time interval.
(c) The volume of air in the warehouse is 1.23E+04m3 yielding 1.50E+00 Bq/m3 3
@.06E-05 uCi/m ),
3 (d) The breathing rate of persons involved is 1.2m /hr.
(e) The total intake for each firefighter is 1.81E+00 Bq (4.91E-05 uCi) i assuming no implementatinr of respiratory protective devices during the one hour period.
(2) The committed does equivalents as calculated using ICRP 30 data are given in Table C-5 No estimates were considered for the general public due to conservative dose estimates derived for occupational individuals in the immediate vicinity and dispersion factors which would further reduce dose commitments.
It should be noted that no consideration in the dose estimates for firefighters included ventilation of the 12
- - -. - -, - -. - - - - -.. ~.
TABLE C-4 Committed Dose Equivalents Due to Leaching from a Landfill to Public Drinking Water Activity Ingested Conads R. Marrow Bone Surface 1.1ve r Total Public 2.30E+03 Bq 6.00E-05 Sv 3.70E-04 Sv 4.80E-03 Sv 1.10E-03 dv (6.30E-02 uC1)
(6.00E-03 rem)
(3.70E-02 rem)
(4.80E-01 rem)
(1.10E-01 rem)
Average Exposed Person 3.20E-02 Bq 8.30E-10 Sv 5.10E-09 Sv 6.78E-08 Sv 1.40E-08 Sy (8.60E-07 uC1)
(8.30E-08 rem)
(5.10E-07 rem)
(6.70E-06 rem)
(1.40E-06 rem)
I j
Minimum Exposed Person 6.70E+01 Bq 1.70E-06 Sv 1.10E-05 Sv 1.40E-04 Sv 2.90E-05 Sv i
(1.80E-03 uci)
(1.70E-04 rem)
(2.90E-03 rem) i U
TABLE C-5 Committed Dose Equivalents to Various Organs Following Inhalation Due to Installation Fire Activity Inhaled Conads R. Marrow Bone Surface Liver 1.80E+00 Bq 5.76E-05 Sv 3.60E-04 Sv 4.50E-03 Sv 9.54E-04 Sv (4.91E-05 uC1)
(5.76E-03 rem)
(3.60E-02 rem)
(4.50E-01 rem)
(9.54E-02 rem) t i
I l
4 building during extinguishment or the use of respiratory protective devices. The committed dose equivalent limit for bone surface remains below recommended non-stochastic dose equivalenc limits and the total inhaled activity is 0.9 percent of the ALI (2.00E+02 Bq) recommendatiotj for inhalation. The air concentragion stated in dl(c) is equivalent to 1.50E+00 Bq/m (4.06E-11 uCi/ml) or 4.10E-03 Bq/m (1.10E-13 uCi/ml) when i
averaged over 1.40E-02 Bq /m3 =(2.00E-12 uCi/ml) for soluble forms and 1.48E+00 Bq/mFR Part 20 is v a" c"
"'ra
=
"" "Pe (4.00E-11 uCi/ml) for insoluble forms. Concentration levels are below one third maximum permissible limits accounting for variatior of individual doses.
(3) Operations in the unlikely event of occurrence would be conducted with some awareness of the potential hazard and with measures of protection reducing inhala-tion risks. The probability of fire at the installation involving the AN/UDM-7C Radiac Calibrator Sets approaches zero due to institution structural composition, fire walls between warehouse sections, complex sprinkler systems, and firefighter units which would respond prior to any conceivable incorporation of units containing radioactive materials.
i e.
Individual Storage Area Fire:
(1) The AN/UDM-7C Radiac Calibrator Sets fielded will be used by mobile calibration teams in specially designed vans, The calibrator set is stored within a locked fire resistant cabinet. Hypothetically, if the unit were subjected to heat or j
fire causing breach of the calibrator source integrity, the following assumptions are i
presented:
4 (a) Within a fif teen minute time f rame, fire surrounds the cabinet causing 10 percent release of activity to the calibrator encasement, i.e., 1.86E+05 Bq (5.03E+00 uCi).
(b) Ten percent of the activity escapes the gncasement to the cabinet i
3 "'*#1 releasing one pgreent to the van interior (2.14E+01 m ) yielding 8.70E+00 Bq/m (2.30E-04 uCi/m ) within the fifteen minute time interval.
(c) Assuming an occupational worker with a breathing rate of 1.2 m /hr were present for the 5 minutes prior to implementing a respiratory device, the total activity inhaled would be 8.70E-01 Bq (2.30E-05 uCi).
(2) The committed dose equivalents using ICRP 30 data are summarized in Table C-6.
The evaluation presented considered the minute plausibility of fire enveloping the specifically designed fire-resistent cabinet and the attempt to arrest the fire without respiratory protective devices or air exchange causing dilution and decrease in inhaled 3
activity. Release of activity prior to extinguishment is realistically improbable with the availability of firefighting devices and user response. The total inhaled activity is 1.3 percent of the recommended ALI for inhalation. The concengration guides for restricted areas as specifled itj 10 CFR Part 20 are 1.40E-02 Bq/m (2.00E-12 uCi/ml) for soluble forms and 1.48E+00 liq /m (4.00E-11 uCi/mg)(2.30E-lO uCi/ml) or averaged over one for insoluble forms. The presented H.70E400 Hq/m air concent rat lon in equ i va jent to year equal to 2.40E-02 liq /m (6.30E-13 uCi/ml). The air concentration levels are below one third of permissible limits which are based on standards for occupational exposure levels of 5.00E-02 Sv/yr (5.00E+00 rem /yr).
14 l
t l.
TABLE C-6 i
Committed Dose Equivalents from Inhalation Due to Individual Storage Area Fire Activity Inhaled Conads R. Marrow Bone Surface Liver 8.70E-01 Bq 2.66E-06 Sv 1.74E-04 Sv 2.18E-03 Sv 4.61E-04 Sv
{
(2.'30E-05 uCi)
(2.66E-04 rem)
(1.74E-02 rem)
(2.18E-01 rem)
(4.6*E-02 rem) i l
4 o
f.
Transportation Accidents:
(1) Transport of the AN/UDM-7C Radiac Calibrator Sets between facilities is rare except upon initial delivery f rom LBDA to the area of proposed user activity which would lend to a decrease in the probability of incident occurrence. The trans-port scenario involves vehicular collision resulting in fire, explosion and subse-quent release of calibrator source activity to the environ.
Inhalation risk is considered the primary immediate mode of exposure to individuals in the vicinity.
under the assumptions:
(a) The maximum number of AN/UDM-7C Radiac Calibrator Sets transported is ten giving a total activity of 1.86E+07 Bq (5.03E+02 uCi),
(b) Fifty percent of the total activity is instantaneously and uniformly distributed within a hemispherical volume whose radius equals 200 meters yielding a total volume of 1.67E+07 m3 and whose activity concentration per unit volume is 5.50E-01 Bq/m3 (1.50E-05 uCi/m3),
3 (c) Individuals within the prescribed area have a breathing rate of 1.2 m /hr.
(d) Assuming no change in activity per unit volume through dispersion for an hour or evacuation of any individual, the total activity inhaled within the one hour time period would be 5.30E+00 Bq (1.40E-04 uCi).
(2) Approximations of committed dose equivalents to various organs using ICRP 30 evaluation are summarized in Table C-7.
The air concentration assumed in f(1)(b) averaged over a one year time interval is 1.50E-03 Bq/m3 (4.11E-14 uCi/ml) and below maximum permissible unrestricted air concentrations specified in 10 CFR Part 20.
Further reduction in quantities inhaled and committed dose equivalents would occur through wind dispersion and evacuation of contaminated areas.
(3) The following final statements are offered supporting minimum transport incident probability as assessed:
(a) There has been no documented history of any accident involving transport of the AN/UDM-7C Radiac Calibrator Set over the past twenty years while under US Navy control.
(b)
In general, the number of transport incidents involving radioactive materials is insignificant in comparison to the total number of shipments.
(c) Transportation and packaging of the calibrator set is in compliance with l
all DOT regulations.
(d) Any conceivable damage to the unit in transit would not be of a severe nature but rather from jolting or compression which would not release material to the environ. Upon occurrence, damage wou3d be immediately obvious to the authorized user who would take appropriate action to contain the unit for return or disposal as specified in inclosure 3.
16 I
I l
i.
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I E
TABLE C-7 Committed Dose Equivalents to Various Organs Resultant from Inhalation Following a Transport Incident Activity Inhaled Gonads
'R.' Marrow Bone Surface-Liver
.j 5.30E+00 Bq 1.70E-04 Sv 1.06E-03 Sv 1.33E-02 Sv 2.81E-03 Sv y
(1.40E-04 uC1)
(1.70E-02 rem)
(1.33E+00 rem)
(2.81E-01 rem) 1 I
lk 1
1 1
- I.
9 i
I l
3.
In summarr. :.u occupational worker under hypothetical assumptions presents himself with the an mum unnecessary internal exposure to Pu-239 through improper use of the AN/UDM 7. lauiac Calibrator Set.
Under normal conditions no radiological impact can be assa:12:=d with the calibrator set.
Maximum safety control and strict operating procedures as described in Section B have been determined to be more than adequate to meet :ce needs of all personnel involved with this device. These con-trols determine the final conclusion that any incident has a neglible probability of occurrence.
Each reposed incident although regarded as highly inconceivable demonstrated levels ;eicw those recommended by ICRP or regulatory standards. The total intake of activity for each evaluation is an estimate based on general assump-tions and should be considered in excess of the actual intake and calculated commit-ted dose equivalents ta various organs.
D.
Evaluation of A1:arnatives 1.
All feasible radionuclides listed in Table D-1 were considered as alter-natives to the use of Pu-739.
These alternative alpha emitters do not offer any significant advantage over Pu-239.
Certain of these radionuclides are categorized as having similar radiotoxicity as Pu-239 and/or possess unacceptable characteris-tics such as short half life, less than optimum energy, increased external exposure and greater expense.
The Pu-239 provides an immediate calibration source for all of the alpha radiation detection instruments. The Pu-239 remains an ideal source for special purposes involving quantitative and qualitative assessment since the use of these alpha radiation detection instruments are basically for the detection of Pu-239 con tamina tion.
2.
Budgeting and manpower resources expended for the research and development in the design of another calibrator set would be cost ineffective.
Based upon previous experience in the research and development or similar equipment, it is estimated that a ten year time frame would be required for the development of a new calibrator set.
3.
The AN/UDM-7C Radiac Calibrator Set is type classified as Standard A which was procurred by the Navy and has been successfully used for approximately twenty years for the calibration of the AN/PDR-56( ) Radiac Set.
This radiac set is being adopted with modifications for Army use.
The AN/UDM-7C will also be used to calibrate existing Army alpha radiation detection instruments, the AN/PDR-54 and AN/PDR-60 Radiac l
Sets, which will eventually be replaced by the AN/PDR-56F. The AN/UDM-6 Alpha Radiac Calibrator Set, wnich also utilizes Pu-239, and is presently used for the calibration of the AN/PDR-54 and AN/PDR-60, will eventually be replaced by the AN/UDM-7C Radiac Calibrator Set.
Currently, the Army utilizes the AN/UDM-6 Alpha Radiac Calibrator Set which does not have the design capabilities for calibration of the AN/PDR-56F alpha radiation detection instrument. Thus, the adoption by the Army of the AN/UDM-7C Radiac Calibrator Set is mest advantageous for immediate implementation and capabilities of operation with all existing type classified alpha detection instruments.
E.
Status of Compliance The AN/UDM-7C Radiac Calibrator Set containing pecial nuclear material, Pu-239, is subject to regulation by the NRC.
The extent of the regulation is stated in 10 CFR.
The CECOM NRC license application for this material has identified all areas of compli-ance to 10 CFR.
No specific state or local permits or licenses are required due to Federal control.
The proposed action includes transport of calibrator sets between installations for which CECOM has demonstrated compliant measures with regard to shipment and packaging as required by the DOT regulations.
I 18
TABLE D-1 Alpha Radionuclides for Instrument Calibration 4 Alpha Energy (MeV),
Half-Life Advantage /
Radionuclide Abundance (Percent)
(Years)
Disadvantane 148 3.18 9.30E+01 Low Energy Gd 230Th 4.617, (24) 7.70E+04 Radiotoxic 4.684, (76) 1 239Pu 5.105, (12) 2.44E+04 Ideal Energy, 5.143, (15)
Radiotoxic 5.156, (73) 210 5.305, (100) 3.79E-01 Short Half-Life po Am 5.442, (13) 4.33E+02 Radiotoxic 241 5.484, (86) 238Pu 5.456, (28) 8.78E+01 Radiotoxic 5.499, (72) t j
5.806,.(23) 1.78E+01 Radiotoxic, 244Cm 5.764, (77)
Expensive 252Cf 6.076, (16) 2.65E+00 Radiotoxic, 6.119, (84)
Expensive, Short Half-Life, Neutron Hazard e
19
F.
Listing of Agencies and Persons Consulted During Preparation of the Assessment 1.
Edward Abney: Physicist US Army Ionizing Radiation Dosemetry Center Lexington, Kentucky 2.
C. Christianson:
Naval Surface Weapons Systems Silver Spring, Maryland 3.
Jack Cooley:
President Nuclear Research Cooperation Denville, New Jersey 4
Richard Yates:
US Department of Energy Germantown, Maryland 20
.... - - -, - -.... ~..
I G.
References.
1.
Fitzgerald, John J., Applied Radiation Protection and Control, Gordon and Breach Inc., New York, 1970.
2.
US Department of Health, Education and Welfare, Radiological Health Handbook, Public Health Service, Rockville, Maryland, 1970 3.
- Belanger, R.,
Luckley, D. W., and Swenson, J.
B., Environmental Assessment of Ionization Chamber Smoke Detectors Containing Americium-241, NUREG/CR-1156, Science Applications, Inc., California, 1979 4
American National Standards Insititue, Radiation Protection Instrumentation Test and Calibration, Institute for Electrical and Electronics Engineers, New York, 1977.
5.
International Commission on Radiological Protection, Publication 30, Limits for Intakes of Radionuclides 'ay Workers, Pergamon Press, New York, adopted 1978.
G 21
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MIL-R-24265(SillPS) 7 November 1966 MILITAltY SPECIFICATION itAULAC CAL 1131tATOR SET AN/UDM-7( )
1.
SCOPE 1.1 This spectitcattu i cuvers a rautae cattbratur sut AN/UDM-7( ) tur cattisralimt alpaid radiac in-atrumenta.
i 2.
APPL 1 CABLE DUCUMENTS 2.1 The tullowing docuinunts, ut the tasuu un effect un date ut invitattuu tur b"'
r request for pro-posal turnt a part of this specttication to the extent specilted hereta:
S PECIFICATIONS MILITARY MIL-F-1/1386 - Electron Tube, Type 7540.
MIL-S-901
- Shuck Tests, H.I. (High bupact); Shipboard Machttiery, Equipment and Systems, Requirements tur.
MIL-Q-9658
- Qualaly Prograta Requirements.
Primer Pretreatment (Fortnula No.117 tur Mutals).
MI L-P-15328 -
MIL-E-17555 - Electronic and Electrical Equipment and Ansuctated Repair Parts, Preparation for Delivery ut.
MIL-M-19590 - Marking of Commodities and Cuntanterm tu bidicate fladtuactive Matu rtal.
STANDARDS MILITARY MIL-STD-106 - Dutuittauna ut and Basse Requirements sur Euctumures for Electrte and Electronic Equipment.
MIL-STD-lu7 - Meeruntcal Vibrattort of Shipboard Equtomunt.
DRAWINGS MILITAMY RE101F2002 - Alpha stadtac Cahbrator AN/UDM-7A (Cunu# A specificattuna, standards, drawings, and publicattuna required by suptalturm in cotudettun with apuus2 procurement luncttuna should be obtaused from the procuring activity or as directed by the contr t.th.g utlicer.)
I
- 2. 2 Othe r publicattuum. - The fulluwung document forms a part of tina spectiteation. Unless vther-wlme indicated, the issue in ettect un datu ut tuvttatton for btds or requent for pruta.smal stuli apply.
CODE OF FEDERAL REGULATIONS INTEILY1' ATE COMMERCE COMMISSION Tartti No.10 - Literstate Commerce Couuninston Regulattuns for Transportation of Exptustves and Other Dangerous Articles by 1.and and Watur in Ratt Freignt Serytce and by Motor Vehicles (itighway ami Water) including Specifications Iur Shipp&ng Contauters.
FSC 6665 O
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(Appitcation for copies should be addressed to the Supertutendent ut Docuanents, Coverrunent Prtattng Otttee. Washington, D.C. 203ti0. )
3.
REQUIREMENTS 3.1 Preproduction sample. - Prtur to beguuiuig production a sainple shall be tested as spectitud in
- 4. 2.1 (see 6. 2).
9
- 3. 2 Generat description. - rhe radiac cattbratur set AN/UDM-7( ) is a calibrating set wiuch pro-vides suttable radioactive sources for calibrating alpha radiac survey equipment.
I 3.2.1 The calibration met shall be constructed and assembled in accordance with the raquarements I
of this specification and Drawing RE101F2002. Wherethe requirements of this specification conflict f
with the drawing, the requirements of this spectitcation shall govern.
3.3 Mate rtal. - Matertals spectiled hereut and un Drawuig RE101F2002 snail be entirely suitable for the purpose intended. Use of other matertal shall have the approval of the procuring activity.
3.s Equipment composition.- The calibration set shall consist of the followtng:
(4) Two radioactive sources "A" and "C".
(b) Two radtoactive source holders.
(c) Adjustable positioner.
(d) Two attenuators.
(e) Alumutum housing.
( f) Calibrator carrytng case.
(g) One paar of tweezers.-
(h) Instruction book.
}
3.4.1 Two radioactive mources.. The two radtuactive sources shall eontatn Plutonamn-239 depostted in a reou component. The resui componeut shall tm ut the compomation spectiled tn MIL-P-15328.
- 3. 4.1.1 Source configuratwn and desertotion. - The sources sh411 be about 12-1/2 inches in diam-A set of two thtu and emit alpha energies, 90 percent of which are 4MEV or greater.
ete r, 1.0 mg/cm3 a
sources (Labeled A and C, and of activities of 10' OPM and 10 DPM respectively) are contaused in each When a source is posttioned in the mut, only a 4 inch x 10 inch area as exposed for calibrattou.
un u t.
The muurces shall be prepared in accordance with the Appendix to this specificatton.
- 3. 4.1. 2 Uniformity ot radioactive sources. - The sources shall have no area count rate which ex-cecom plus or manus 5 percent from the averagtPepunt rate winen to ited am spectited in 4.4.1.
3.4.1.3 Accuracy.- The activity of each sourcu sha11 be determined by compartson with a standard l
sous ce to be approved by the procuring activity. Thta utformation shall be recorded and included with each cattbrator delivered under the contract.
- h. formation shall be on a prtuted card or sunilar methcd of j
presentation.
- 3. 4. 2 Source mounting.. The two radioactive sources shall be momsted in accordance with Drawing ItE101 F2002.
3.4.3 Adjustable probe posattuner.- Construction of the probe postttoner sha11 tv. tu accordance with Drawing RE101Y2002.
J.4.4 Alununuin housing. - Each calibratton met shall ou provided with a lightweight housing, made of alumtumn in accordance wtth Drawing RE101F2002, designed to house the following:
(a) Two radioactive mource holders.
(b) Accessory drawer.
(c) The top of the unit shall be destgned as a source-postttosung well.
The housing shall be labeled in accordance with MIL-M-19590.
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l MIL-R-24265(SillPS) 3.4.4.1 h two radauacts re muurce holderas shall be contained in removable drawers, numbered (or source identtitcation, and Labeled un accurttance with MIL-M-19590.
3.4.4.1.1 Each drawer with source stull be removable as a unit tur replaccinent un the proper punt-i ttuti under the probe puenttuner.
3.4.5 Catturator carrying case. - The cattbrator carrytag case saw11 be cunatructed to contaus the alummura housing. The carryuig came aluLt be constructed un accordance with Drawing RE101F2002.
3.4.5.1 Size and weicht un calibratur. - The overall size asul weight of the calibratur shall be as follows:
Height - 1 27/32 unches.
13-23/3 2 unches.
Wtdth 13-17/32 utches.
Depth Not to exceed 17 puwids.
Wetght 3.4.5.2 Size and weignt of carrying case.- The overall size and weight of the carrytng case shall be as follows:
I Height 15/16 inches l
14-7/8 inches Width 15-1/16 unches Depth f
Weight - Not to exceed 7-1/2 tuuida.
}
t 3.5 Shuck and vibration.-
3.5.1
- m. Shuck requirements slull be tur grade A, etama 1, type A in accordance with MIL-S-901, except tlwt the drop shall be 1, ?.usd 3 teet in Lieu of 1, 3.uul 5 feet.
3.5.2 V ib rattuu. - Vtbratton requirements alw11 be in accord.uice with type 1 of MIL-STD-167.
t
- 3. tl Degree ut enclumure. - Degrew ut enctumure for the calibratur atull be aptamhproul in accord.mee with MIL-STD-108.
3.7 Tem tw rature. - The avurces alwit be catable of withalamiing a temperature ut 120*F in an in-verted posttton,.and meet the requirements ut 3.0.
3.6 llumidity.- The muurces shall be catubte of withstandtag 95 perucut relative humidity at 100*F lur 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, and ineet the requirements of 3.3.
3.9 Leakage.- When tested un accordance with 4.4.5, the removable radtuactive matertal slull nut exceed 0.005 microcurses of Plutuntum-230. Luakage tent stall be perturmed tuuuedtately alter the Lem-i twrature, hwntdity, shuck and vibration testa.
3.10 Workmanstup.- The calibrattuu act alull be manufactured and fintahed un a thoroughly wurkman-Like inanner and shall be tree troen all burra, rough edges, smudges and scratches.
4.
QUALITY ASSURANCE PROVISIONS 4.1 Responsibility for inspection.- Unluma utherwise spectaied in the contract u. purchase order the suppiter is responsible for the performance ut all utspection requirements as spectitud heretn. Except as otherunne spectiled, the supplier may utilize hLs own factllties or any commercial laboratory acceptable to the Government. The Government reserves the right to perform any of the inspecttune set torth in the spec-tlication where such inspections are deemed necessary to assure supplies and services conform to pre-scribed requirements.
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Mit.-ft 24265(SlitPS) 4.1. I Quality contrut system. - Tiw contractor shall provide and tuauttain a qualtty system acceptable to the guvurnment for the supphes covered by the cuatract. The system ut quality contrut alwl1 be ut ac-curdance with MIL-Q-9858. The procedures uuttuned un MIL-Q-9558 = hall serve to supplement and imple-ment LLe design, performance and test ruguarFnsents os this st=ctiteattun.
4.2 Guneral inavuttiun. - Thu niethuda ut u.wmanattuu and tunting ut thu cultbration acta stwil tall withus the followtug clamatf acattuus:
(a) Preproduction mapection (see 4.2.1).
(b) Qvality conformance unapuction (see 4. 2.2).
4.2.1 Preproduction utspection. - Preproduction uispection sull be made on the preproduction model and shall consist of the examutation us 4.3 and the tests of 4.4.
4.2.2 Quality conformanco inspection. - Quality cuadormance utspection shall consist of the produc-tion inspection of 4. 2.2.1 and production contrut hispection of 4.2.2.2.
4.2.2.1 Pruduction inspeciton.- Production uispection shall be made on each equipnient utfered for delivery to determine compliance with this specificattun. Producttuu inspection shall constal of the exam-ination of 4.3 and the untformity, accuracy and leakage tests of 4. 4.1, 4. 4. 2 and 4. 4. 5.
4.2.2.2 Production contrul tuntettion.- Production control tuspection shall be made un une out 01 each 10 calthrutton mets produced, tube selected at random by the Govermuent representattve. Production contrut inspection shail constat of the exantuuttuu ul 4.3 and the tests specified in 4.4.
l l
4.3 Ceneral examuiation. - The cahbrattun sul shall be examined to determine compliance with the requirements of this specification and shall include the fullowing:
i (a) Workmanship, assembly, maze and Itt.
(b) Materials, parts and fbush.
- 4. 4. Test procedures. -
4.4.1 Uniformity.. The untformaty check to determute conformance with 3.4.1.2 stuu ue inade with a type 7840 tune conforming to MIL-E-1/1388, used with a conventional type scaler (1 meuuhm, 0.5 micro-second resolvuig time).
4.4.2 Accuracy.- The calabrutton met shall be tested to determine conformance with 3.4.1.3.
4.4.3 Enclosure.- The houstug and the carrytng came shall be tested to determtne conformance with J. 6.
4.4.4 Shock and vtbration.- The cattbratton met shall be tested to determine conturmance with 3.5.1 and 3. 5. 2.
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4.4.5 ltakai;e test.- The leauge test shall be capable of dutecitng the presence of 0.005 micro-n curius ut Plutuntum-230. The method of the test alull be submitt3d to the command or agency concerned tur approval prior to performing the test.
i 5.
PitEPARATION FOR DELIVEltY 1
5.1 Preservation, nackagtnic amt packing.- The equipnient shall be packaged by lovel A or C.und e
packed by level A, B or C as spectfied un the contract or order bt accordance with MIL-E-17555. Method
!!! preservation shall apply for level A packaging. As a mLutmum, the requirements shall conform to the interstate Commerce Commisaton Tartf! No.10.
- 5. 2 Marking.- The equipment.md containers shall be marked in accordance with M11-M-19590.
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NatE3 6.1 Ordertng data. - (*rucurunautil docuaneista simid spectly ttw title, nusut=r.uid date ut (fita spec-t!!cattuu.
6.2 Preproduct tuu. - Laivitattussa tur inda ahuund provada that (tw Guvus'tansuut remurvum the rtit,ht to watve (tw requarctuent fut prepsuduttuti aaanplea as to tinome htdders utturlisi; a pruduct wh&cli lam (sees I
previously procured ur tested tsy the Goveruutent, and that bidders utturtug auch products, who wtah to rely oss sucft producttuei ur tunt, suuat turutati uvtdetice wtLit tiae bid llut prtur Governinent approval tu pre-mently appropriate for the pending procuruinent.
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MIL.R-24265(SHIPS)
A PPENDtX l'itot.r:OUR$ FOlt PREPAlt1NG "Til1N" A LPilA SOUltCES 10.
Tec hu tuue. - The techeuque is relatively sinspie. The alpha mm.tter is diasutved in an alcohol-ream cotupunent insature atas attrred to untlurnsity. The !!nal mixture la then puured through a fusmel onto a plastic danx located un a luvulang table dirt;ctly below the fuimet spuut. The resuittag radioactive sources have excellent uutturmattes - wdh any muurce the sourcs area count rate varies 25 percent or less from the average Count rate.
6 10.1 Procedure.- The procedure shall be as follows:
(a) One cubic centimeter (cc) of radtuactive solution (tuotope in chlottde turm) is added to a mixture of 9 - 10 cc of resta component (MIL-C-15328) and 29 cc of ethyl alcohol (99 percent). The i
total mixtt.re is carefully =ttrred for a minimam of 15 minutes to as.ure a uniform dispersion e
I of the radiataolope in the aulution.
(b) The radtoactive solutton te. t'.nen poured through a funnel unto a 12-1/2 CY/eQ) inch diameter l
diak on a leveled tabler. The tunnel (spout inner diameter - 11 millimeter (mm) is positioned rigt.11y wah the spout perpemilcular to the center of the plastic disk (Cit-39 transparent plastic; tant acrylic)., Ttu distaNo between spout and disk is 47 mm. The spout inuter diameter and Liw 47 mm utstauce n11maste aream of reduced activity in the center of the disk.
Prior to pouring, the disk ts leveled by means of a leveling table with adjustable legs (NASL uoes a 12 tache a m 12 tLches stainless steel table). A wetting agent applied to the surncu > the disk before pourtng fact 11tates spreading of the radioactive mtxture.
Ten cc ut alevhol, curefully hand apread over the disk has bee been used with good i
results.
(c) After spreadtng treely on the disk, the radicactive mixture ta allowed to att dry. During this thse two facturn of cuadrol are necessary. First, safety precauttuna are needed to protect persv usel and equipment from possible cortamination. A hood to recommended, with condi-r tions to keep air currents trum pasang over the dryutg radioactive Ltquad. Secondly, humidity control as impus tant and a dust free atmosphere is desirable. A relative humidity of 40 per-cent or tems at 70*F. ur less wali ptevent spotty, nonuniform distrtbutions. The water content I
of the mixture to critical and should never be allowed to exceed 0.3 cc m 5 cc of mtxture.
10.2 Source.- The resalting source. tf the conditions above a a employed, will have a high degree of unuurmity. Any area count rate will be t$ percent or less from the average count rate. A uutformity etwck can be made with 7840 GM tube (maca wuutow thickness of 2.5 mg/cm2 or less) used with a conventional type mealer (1 meguhm, 0.5 gaec resuiving ttmsd. The alpha source in a " thin" source, meaning alt alpha ener-gles at the surfa'ce are 4 Mov or greater. Care thould be taken not to guage or severely rub the source mate rla1.
10.3 Smnmary of maturtal and condititms.- Jummary of nuttertal and cond L!ona shall be as fpllows:
(a) Radioactive mtxture. -,
Radtoisotope - Plutomum 239 am PuC1 tn tic 1 (6 0.5 N) 3 610 pg/cc for source 1 - aqwalent to approxtmately 10 4g/m2 4
2 pg/m2 4.1 g/cc for source 2 - eQankri..t to approntmately 10 Resta comgnent - 9 10 cc of Mt L-C-15323 Solvent - 20 cc ut ethyl alcanol N0 percent)
Total volume of rntxts.ru - 40 cc - bring up with alcuhut u necessary (b) Plastle disk 1/2 inch diameter,1/8 inch thick, CR-39 transparent, cast acrytte (c) Leveling table - At least 12 inches x 12 inches for rela.tively untform evaporation i
(d) Funnel - Spuut (inner diamets r - timm, length - 25mm) l Mouth dtameter 465:am l
(e) Mixture beaker - 125 cc (graduated) with pouring spout l
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MIL-it-24205(SillIN 9
(1) bearsing rtal - Glase, slurable, apprumaanately d inctnea lung (g) C.f,fa,la una 1(.11. - 40 percent ur lose, teinperature 70* F ur fema Dual-Ireu atnivepliere lismal lur matuty pr6%40ttessus
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