ML19350D725
| ML19350D725 | |
| Person / Time | |
|---|---|
| Site: | 07000250 |
| Issue date: | 04/16/1981 |
| From: | Morgan W BOEING CO. |
| To: | Jim Hickey NRC |
| Shared Package | |
| ML19350D726 | List: |
| References | |
| 18996, 4-1635-81R-0086, 4-1635-81R-86, NUDOCS 8105180469 | |
| Download: ML19350D725 (19) | |
Text
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10- M g'
y THE BOEING COMPANY j/8 h g ] 4, c a psp, p 4f g -/
MAIL STOP 2T-04
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-yy,g P. O. Box 3707
-f seattle, washington 98124
- _f IJAYl5 7 cat m d 4-1635-81R-0086 W \\ " s ma em f d
g April 16,1981
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J0iN HICKEY, Section Leader Nm Industrial Branch Nu rR atory Commission DOCKET NUMBER 070-00250 Washington, D.C.
20555
Subject:
AMENDMENT TO THE B0EING COMPANY'S SPECIAL NUCLEAR MATERIAL LICENSE SNM-255.
Dear Mr. Hickey:
It is requested that the subject License be amended to reflect the following changes:
6.
Add:
7.
Add:
8.
Add:
F.
Plutonico-236 F.
CRVL Sealed Sources F.
3.8 nanograms G.
Urani um-233 G.
ORNL Sealed Sources F.
200 milligrams H.
Uranium-235 H.
ORNL Sea 1ed Sources H.
l.8 grams
-b /
Applicact..$ b'W ' ' ' "
9.
Add:
Check No..
800gyq* y F.
Calibration af instruments.
G.
Calibration of instruments.
Type et Fee..
n.4 H.
CaliDration of instruments.
ISts Check c'd.. '/ Af#/...
R*CtI198 BYb ' -
bl-s'?3%
- 10.
Add:
Licensed material specified in Items 6.D, 6.F, 6.G, and 6.H may be used at Boeing operations in the State of Washington.
The amendment is necessary to allow us to use the six SNM Sources that will be pur-chased from the Oak Ridge National Laborator les.
As can be seen from the attachments these Sources will be used to measure the response and resolution from high energy Ganma Detectors.
The Sources will be sealed in such a way that they will meet the requirements of "SPECIAL FORM" in the Department of Transportation regulations.
I am enclosing copies of The Boeing Company's " Application For Use of RadioactLve Matetial", the "Expetimental Test Plan", the "Isot. ope 5 Technical Service Orde.t Foam" for ORNL, and a copy of the Operating Procedure that will be used in connection with this program.
Mr. A. R. Lowery is alreadi named USER on our Special Nuclear Material License.
ThisNtestiprogram is in connection with the Department of Defense's MX Pro-gram.
Because.4tHs a. National Defense Item, your prompt attention to this amendment will be greatly tppreciatsd'.'
Sincerely,
,6J !! ;' l
,7 ; -, ;,,
T' WILLIAM RGAN WEM:gn Chief, Radiation Health Protection Attachments (5)
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Whg ensamp re i hw am. e f-APPUCATl001 FOR 55E OF EAsl0 ACTIVE BATRIAL Apa N APR 131981 o,,,
INST RUCTIONS: Complete leems 1 through 13 ond submit two copies to the Rodiation Health Protection Unit. Org.11881 Mail Stop ptzAssrype
- 1. APPLICANT
- 2. Building and location of which radioactive meterial will be used.
some A. R. Lowrey Title Mes. Engineer Bldg. 9-101 Tunnel 1 4-M b Org.
Nuclear Counting Laboratory Mail Stop 43-12 Phon.
5-4922
- 3. Name of individual (s) who will use moverial other
- 4. APP LICANT'S SUPERVISOR than applicant Nom.
K. D. Fridde11 Alan S. MacArthur Org.
2-3646 B. J. Henderson Charles Vick
- 5. Radioactive Meteeial (Elements and mass
- 6. Chemical ande'er physical form and maximum number of millicuries of number of each) each chemical and/or physical form that you will possess at any one ume.
~3 Pu - 236 2 each,1 microcurie sources t.@SX/0 g U - 233 2 each, 100 milligram sources U - 235 2 each, 0.9 oran sources Each source doubly encapsulated in welded steel cases, see drawing ORNL-79-16238.
Encapsulation satisfies Tit;e 10 CFR #173.398 (a) and IAEA Safety Series #6,1973 (Rev. Ed)
- 7. Describe purpose for =hich radioactive material will be used (flow sheet of experiment and diagram of apporotus will be helpful).
Sources will be used to measure the response of both high resolution and high efficiency gama ray detectors to mixed gama rays from the sources and their daughter products, both f or direct exposure and a variety of shielding configurations.
~
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. ITR A4NfMG AND EXPERIENCE OF APPLICANT (Use Seppiamental $heets if Nece: eery)
- 8. TYPE OF TRAINING WHERE TRAINED
.. wieles d -c, ices.i
,og;,;e,,,, g,;,,
University of South Carolina and Boeing
- b. Redi.octiv.ty
.surement stonderdinatio" ond monitoring techniques and instruments UWWh#heMNWBW
- c. Mothematics and calculations besic to the use and measurement of radioectivity University of South Carolina and Boeing
- d. Biological eHects of radiation The Boeing Company i
DURATICN OF TRAINING (for hv.
ON THE JOB FORMAL COURSE (Circle Answer)
(Circle Answer)
- P>P go.
y No e
No c.
d.
No Yes t,
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- 9. EXPERIENCE WITH RADIATION (ACTUAL USE OF RADIOISGTCPES OR EculVALENT EXPERIENCE)
ISOTOPE MAXIMUM AMOUNT WHERE EXP. WAS GAINED DURATION CF EXP.
TYPE CF USE U & Pu 10's of grams The Boeing Company 5 years Activation Analysis
- 10. RADIATION DETECTION INSTRUMENTS WINDOW TYPE OF INSTRUMENTS NUMBER RADIATION SENSITIVITY THICKNESS (INCLUDE MAKE & MODEL NO.)
AVAILABLE DETECTED RANGE (meAr)
(mg/cm2)
USE To be supplied by Radiation Health Protection, Orgn. 4-1635
- 11. Method, Frequency, and Standards Used in Calibrating Instruments Listed Above.
To be done by Radiation Health Protection, Orgn. 4-1635 Items 12 and 13 to be submitted en additionel sheets
- 12. F ACILITIES AND EQUIPMENT.. Describe laboratory facilities and remote hondling equipment storoge containers, es No shielding, fume hoods, etc. Emplonatory slietch of facility is attached. (Circle Answer)
- 13. Describe any specific radiation protection or control measures used in your laboratory which are not e ed in Industrial Hozords Control Bulletin No. 76 (source security, contaminotion surveys, etc.)
ISOTCPES COMMITTEE ACTION L
Approved C Disopproved l
}l1 Chairman
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200R OR BM Rod.SafetDye pr
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RADIATION HEALTH PROTECTION
~~
EXPERIMENTAL TEST PLAN DATE:
12/19/80 Page 1 of 2 PART I - GENERAL INFORMATION FROM: (Test tendet Name, Orgn, M/S, Phone)
TO:
I RADIATION HEALTH PROTECTION A. R. t owrev 7-3649 47-11 Orgn 4-1635, M/S 2T-04 Agg-?nia REQUIREMENTS EXIST FOR USE OF THE FOLLOWING FACILITIES:
Fe ifira Recuested U.se Pedad(s)
Nuclear Counting Laboratory Jan - tvc 1991 9-101 Bldg. Tunnel 1 PART II - HAZARDOUS MATERI ALS & EQUIPMENT TO BE USED IN EXPERIMENT HAZARDOUS ITEMS TYPE AMOUNT (Cu, des) 236Pu, 235, 233U,238U Sealed Sources U
Q Radioactive Material AA Th, AA Ra, "i, f 4,1 mci
=
=
g Sealed Sources 5 100 mci g
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TYPE
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g L__j Explosives Carrosives PART III - PROPOSED TEST PLAN A.
TITLE OF EXPERIFINT:
DESCRIBE ITEMS TO BE EXPOSED & EQUIPMENT TO BE USED IN TEST AREAS:
B.
(Desc,tibe metJtod and t.ime tJ:a.t expednent wilt. be conducted, and include any ha:a.tdous results expec.ted, assceia.ted mechanical or chenic t reacticrts tJtat P.tovide photo-may occu.t du. ting and aftet expetimental setup is i,&inted.
graphs and/or sketches.)
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RADIATION HEALTH PROTECTION EXPERIPENTAL TEST PLAN PART III (contd. )
Page 2 of 2 C.
TEST PLAN:
The purpose of these tests will be to measure the response of a large volume detector to mixed radiation of transuranic sources with both high-and-low energy msolution. To accomplish this various combinations at the sources listed on page 1 will be set up and the neutron and garmia ray counting rates and spectra 238 will be measured at various distances and with varying amounts at U, Pb, and Fe shielding. When not in use sources will be stored in a locked safe, cabinet, or drawer.
D.
PERSONNEL WHO MAY BE EXPOSED TO RADIATION IN EXPERIMENT:
Futt Name S Title Clock B. J. Henderson - Senior Soec. Encineer 3325 2-3646 A. S. MacAuthor - Enoineer 2031 2-3645 A. R. towrev Research Encineer 2729 2-3646 E.
PROCEDURES ATTACHED:
D295-10520-1 (in preparation)-
APPROVAL SIGNATURES TEST MANAGER:
RADIATION HEALTH PROTECTION:
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W' (NOTEt Sign.1tu.te indienre A you have re-s viexed the h:.:a.td.s assceinrod utith tJtis expc,timent, and agnee to corrply i
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form. quantity. Isotopic concentration State isotope, chemics (specifying desired enrighment. n**namum ennchment).
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A OPERATING PROCEDURE-AGREEMENT
SUBJECT:
OPERATION AGREEMENT for
'2PECIAL NUCLEAR MATERIAL U-233, U-235, and PU-236 S&LL4i&tri
/
AFFECTED ORGANIZATIONS:
Approved by Physical Date Sciences Boeing Aerospace Company M&SG--Physical Sciences Seattle Services Division Approved diation
'Da te' Medical Health P ection Radiation Health Protection
REFERENCES:
a.
Industrial Hazards Control Bulletin (IHCB) No. 76, "Codral af Radiological. Hazards".
b.
Title 10 CFR, Parts 20, 70, 71 & 150 (Nuclear Regulatory Comission Rules
& Regulations for Radiation Protection at Federal Sites).
c.
Title 49 CFR, Parts 170-189, (Department of Transportation Hazardous Materials Regulations).
I.
PURPOSE This document is intended to establish and identify the following protection requirements for using special nuclear material.
A.
Radiation protection requirements B.
Inter-organizational responsibilities C.
Nonnal operating procedure D.
Emergency operating procedures II.
GENERAL INFORMATION AND SOURCE DATA The U-233, U-235 and PU-236 sources will be obtained from the Isotope Sales Division of The Oak Ridge National Laboratory, Oak Ridge, Tennessee, 37830.
The two Uranium 233 sources are each a nominal 100 milligrams (0.94 mC1),
the two Uranium 235 sources are each a nominal 900 milligrams (1.89 xCi),
and the two Plutonium 236 sources are a nominal 1.9 nanograms (1.0 xC1).
Each of the U-233, U-235 and PU-236 sources are evaporatively deposited and contained in a doubly encapsulated stainless steel container with each container having a nominal wall thickness of 0.030 inches, not to exceed 0.050 inches. Each container is welded and leak tested (see ORNL-DWG 79-16238). The encapsulation satisfies D0T Regulation Title 49 CFR 173.398 for "Special test" special fonn 5
materials. The following data are applicable:
1 i
Page 1 of 12
OPERATING PROCEDURE-AGREEMENT (contd.)
i i
II.
GENERAL INFORMATION AND SOURCE DATA (contd.)
a.
U-233 Source Radiation - alpha, garra, daughters 5
Half-life - 1.62 x 10 years Specific Activity - 9.48 x 10-3 Ci/gm b.
U-235 Source Radiation - alpha, gamma, daughters 8
Half-life - 7.1 x 10 years Specific Activity - 2.1 x 10-6 Ci/g c.
Pu-236 Source Radiation - alpha, gamma, neutrons, daughters Half-life - 2.85 years Specific Activity - 533 Ci/g
~
The exposure and dose rates of each isotope are not known precisely at this time because of the growth of daughter products, however they are expected to be as shown in Figure 2 for the U-233 and U-235. The exposure rate for the PU-236 is 10,000 times less than that shown for U-233, and is considered negligible. The two curves were calculated based on daughter product' build-up resulting from trace elements in the parent isotopes. The exact amount of trace isotopes is not known and Figure 1 is based on Oak Ridge estimates.
Exposure versus distance data in Appendix A is based on peak values from Figure 1.
Each source will be measured upon receipt from the vendor using ionization chambers and exposure rates versus distance curves will be modified based on measured data.
III.
OPERATING POLICIES A.
Only individuals approved by the Corporate Isotope Committee shall use the special nuclear materials (SNM).
B.
Individual operator and one other knowledgeable person must be in attendance whenever the SNM sources are exposed.
C.
The transfer, use, storage, and final disposition of the SNM sources will be in compliance with:
1.
Nuclear Regulatory Commission (NRC) rules and regulations.
2.
Department of Transportation (DOT) rules and regulations.
3.
IHC'B No. 76 (Reference a).
I i
Page 2 of 12
OPERATING PROCEDURE-AGREEMENT (contd.)
III.
OPERATING POLICIES (contd.)
D.
Normal Operating Procedures The sources referred to in this procedure will be used singly and in groups to measure the response of a variety of nuclear radiation detectors in various experimental configurations, i.e., different geometrical arrangements and different shielding geometries. When not in use the sources will be stored in a locked metal cabinet (see Figure 3). Shielding will be provided as necessary so that the exposure rate at the surface of the cabinet does not exceed 5.0 mr/hr.
The sources will be transferred from the storage cabinet to the detector area using tweezers or tongs as necessary to reduce hand exposure. Film badges, pocket dosimeters and finger rings will be worn when these sources are in use. The sources will be periodically wipe tested by Organization 4-1600, Radiation Protection, to ensure that the sources are not leaking. The sources will be returned to the storage cabinet after each counting test, and the cabinet will be kept locked when the sources are not in use.
IV.
RADIATION PROTECTION REQUIREMENTS A.
Personnel Protection 1.
Dosimetry:
The following personnel dosimetry devices shall be worn by each user whenever the SNM sources are exposed.
a.
One Beta, Gamma and Neutron *-sensitive Film Badge packet.
b.
One TLD Finger Ring.
c.
One Gamma / Neutron
- sensitive pocket chamber.
2.
External Exposure Controls:
SNM sources operation shall be conducted within time limits as listed in the Weekly Exposure Level Guide (Appendix B).
In keeping with "As Low As Reasonably Achievable"(ALARA) principles, exposure levels will be maintained within non-cccupational limits unless prior approval is obtained by Radiation Health Protection. The following methods shall be used to comply with these levels:
a.
Normal Conditions A 6-foot radius controlled area shall be established during source exposures. Non-essential personnel shall remain outside this control area.
- Requited because of otJtet neittton cmitting radionuclides assoc. lated sci.th titis ptog. tam.
I i
Page 3 of 12 r
m
' OPERATING PROCEDURE-AGREEMENT (contd.)
IV.
RADIATION PROTECTION REQUIREMENTS (contd.)
~
2.
b.
Special Circumstances If it becomes necessary for individuals to be closer than 6 feet to the exposed source, their name, organization, Social Security Number, and exposure periods shall be recorded. Exposures shall not exceed 2 mrem in any one hour or 10 in any one week.
3.
Instrumentation available at D.C. Counting room:
One calibrated portable Geiger Counter (Eberline Model E-120/HP 190),
a.
I b.
One calibrated Eberline PAC 45 portable alpha counter for contamination surveys.
4.
Surveys:
Radiation surveys shall be conducted during the following circumstances:
a.
During initial tests and calibration of the SNM sources, b.
Monthly radiation surveys and wipe tests shal'. be conducted during use periods of the SNM sources.
5.
Leak Tests i
Semi-annual sealed source leak tests shall be conducted during the t
total program.
B.
Material Controls 1.
Storage Conditions i
The SNM sources will normally be placed in a labeled metal container which will be locked in a metal cabinet. This cabinet will be kept in the locked Isotope Vault adjacent to the Counting Room. The Isotope Vault must be entered through the Counting Room which has a combination dial locking system on the entrance door. Boeing Security Department has approved the area as meeting Military Security requirements for storing restricted data. The area is labeled t
"CAUTI0tt-RADI0 ACTIVE MATERIAL" and " CAUTION-RADIATION AREA".
2.
Transportation i
l a.
Shipping Containers I
(1) Manufacturing Requirements Manufacturing requirements must meet 00T-7A specifications and be certified to meet these specifications.
(2) Marking Requirements (a) " Type A" Page 4 of 12
OPERATING PROCECURE-AGREEMENT (contd.}
IV.
RADIATION PROTECTION REQUIREMENTS (contd.)
B.
Material Controls 2.
Transportation (contd.)
a.
(2) Marking Requirements (contd.)
(b) " USA 00T-7A Type A" (c) "Ldioactive Materials, Special Form, n.o.s."
(d) Company's name and address (3) Labeling Requirements:
Two each DOT Category Warning Labels must be placed on opposite sides of the shipping container.
b.
Documentation - Boeing " Sole Use" Transportation The following documents must acccmpany SNM sources when they are transported by Boeing vehicles.
(1) Completed Shipping Papers.
(2) This Operating Agreement.
V.
RESPONSIBILITIES A.
Using Organization 1.
Comply with this Operating Agreement, its Appendixes, IHCB No. 76, and specific conditions listed on Boeing's radioactive material possession license for the SNM soJrces.
2.
Conduct tests and calibrations within weekly exposure level guide shown in Appendix B and according to " Normal Operating Procedure".
3.
Store radioactive sources in shipping / storage containers in locked, labeled, and approved storage area when not in use.
4.
Conduct wipe tests of source wheneve'r it is suspected
- sources have been damaged.
Count wipes on GM, and report to p m per persons if any contamination is detected. All wipes shall eventually be forsarded in a plastic bag to Radiation Health Protection for laboratory analysis.
I
(
Page 5 of 12
OPERATING PROCEDURE-AGREEMENT (contd.)
V.
RESPONSIBILITIES (contd.)
A.
Using Organization (contd.)
5.
Be familiar with, and prepared to implement, any applicable EMERGENCY PROCEDURES (Appendix C) that are listed in this Operating Agreement.
(See page 12)
- A visibly damaged source is to be treated per Section C of "ENERGENCY PROCEDURES" in Appendix C.
(See page 12)
B.
Radiation Health Protection 1.
Obtain proper licensing authority for possessing and using the SNM sources.
2.
Monitor initial SNM sources tests and calibrations to establish an adequate protection program concerning the use, transfer, and storage of any radioactive materials.
3.
Provide recuired calibrated radiation survey instrumeats and personnel dosimetry devices.
4.
Conduct semi-annual leak tests and monthly surveys / wipe tests during source use periods.
5.
Maintain required records for Federal and State Regulatory Agency inspections.
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Page 8 of 12
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NUCLEAR COUNTING LABORATORY LAYOUT
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g Operating Procedure Agreement Special Nuclear Material APPENDIX A RADIOLOGICAL DATA WHEN SOURCES ARE EXPOSED l
DISTANCE FROM U-233 U-235 ll SOURCE SOURCE SOURCE i
(Inches)
(mr/hr)
(mr/hr) 12 5.4 21.5 18 2.4 9.6 24 1.4 5.4 30 0.86 3.4 t
36 0.60 2.4 48 0.34 1.4 60 0.22 0.86 72 0.15 0.60 120 0.05 0,22 r
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4 APPENDIX B WEEKLY EXPOSURE LEVEL GUIDE EXPOSED SOURCE OCCUPATIONAL EXPOSURE NON-0CCUPAT!0NAL EXPOSURE TO WEEKLY TIME LIMIT WEEKLY TIME LIMIT BODY (100 mrem / Week)
(10 mrem / Week)
DISTANCE U-233 U-235 U-233 U-235 12 in.
18.6 hrs 4.6 hrs 1.8 hrs 28 min 18 in.
NR 10.4 hrs 4.2 hrs 1.0 hrs 24 in.
NR 18.5 hrs 7.4 hrs 1.8 hrs j
30 in.
NR 29.0 hrs 11.6 hrs.
2.9 hrs 36 in.
NR NR 16.7 hrs 4.2 hrs
~
48 in.
NR NR 29,8 hrs 7.4 hrs 60 in.
NR NR NR 11.6 hrs 72 in.
NR NR NR 16.7 hrs 120 in.
NR NR NR NR I
NR = No restriction on time.
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APPENDIX C l
EMERGENCY PROCEDURES RADIATION HEALTH PROTECTION PHONE:
(206) 655-0500 A.
Situation:
_ LOST OR STOLEN SOURCE Action:
1.
Notify Radiation Health Protection and Nuclear Lab Manager IMMEDIATELY.
2.
An intense visual and radiation survey investigation shall connence as soon as possible.
3.
If source is located, it shall be surveyed and wiped to detect potential damage.
4.
If source is not located, Federal and State Regulatory Agencies will have to be notified.
B.
Situation:
UNUSUAL HARSH USE OF SOURCE--N0 VISIBLE DAMAGE NOTED Action:
1.
Put on rubber gloves and take Nu-Con Smear of suspected damage area. Use remote methods to wipe Probe so that hands do not directly touch source (i.e., use tongs or put wipes on end of stick).
?.
Remove smear to LOW BACKGROUND radiation level area.
3.
Count wipe on Open Window Geiger Counter and PAC 45 Alpha Counter.
4.
If no contamination is detected, continue operations under normal conditions.
Forward wipe to Radiation Health Protection in plastic bag for laboratory analysis.
5.
If contamination is detected, call Radiation Health Protection for further instructions.
C.
Situation:
VISIBLE DAMAGE TO SOURCE FROM ANY CAUSE Action:
1.
Halt operations IMMEDIATELY.
2.
Stay with source.
3.
If possible, place source in plastic bag.
4.
Maintain 25-foot radius personnel-free area around source.
5.
Stay with Source until relieved by Radiation Health Protection.
6.
Radiation Health Protection will conduct surveys and wipe tests to determine extent of damage.
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