ML20203M578
| ML20203M578 | |
| Person / Time | |
|---|---|
| Site: | 07000693 |
| Issue date: | 10/14/1983 |
| From: | Sengupta S NUCLEAR RESEARCH CORP. |
| To: | Donna-Beth Howe NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML20203M523 | List: |
| References | |
| 01501, 1501, NUDOCS 8605010588 | |
| Download: ML20203M578 (2) | |
Text
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NUCLEAR RESEARCH
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CORPORADON 125 Titus Avenue Warrington, Pa.18976 October 14, 1983 Phone: 215-343 5900 U.S. Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, PA 19406 Attention:
Dr. Donna-Beth Howe Nuclear Materials Section 3 Division of Engineering and Technical Programs
Reference:
License No. SNM-631 Docket No.
070-00693 Control No. 01501
Dear Dr. Howe:
Enclosed please find the completed NRC-3131 form in duplicate for renewal of Special Nuclear Material License No. SNM-631.
Nuclear Research Corporation manufactures Radiac Alpha (AN/PDR-56) and X-Ray Probe DT-590/PDR detectors for the three branches of the U.S. Department of Defense.
The Special Nuclear Materials are used to calibrate these instruments.
The Alpha calibrator AN/UDM-7 was supplied to Nuclear Research Corporation from Naval Electronic Systems Command, Charleston, South Carolina with the certificate of calibration (enclosed).
I am also enclosing Certificate of Calibration for Th-230 and Am-241 Alpha Sources.
Please note that these sources are not certified as NBS traceable.
- However, I discussed with the manufacturer (Isotope Products) regarding this matter and they informed me that there is no difference in the accuracy or uncertainty in these measurements whether the source is NBS traceable 4
or not.
Please advise us regarding this matter.
gggyOd9Qyg 860402 OCT 1 g ggg3 SNM-0631 PDR
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.Q, U
O Nuclear Research Corporation shall provide certified NBS traceable sources if necessary.
Recently, Nuclear Research Corporation,-Warrington Division, has been awarded a contract (Contract No.
N00102-83-C-0537) by the U.S.. Navy to-manufacture
-Neutron Survey Meters AN/PDR-70..'This contract requires to calibrate the Neutron Survey Meter with Pu-Be Neutron Source.
Nuclear Research Corporation's Dover Division possesses a 3Ci Pu-Be. Neutron Source (S/N -. M595) under License SNM-331'.
We would like to use this source at both the facilities i.e., Warrington, Pennsylvania and Dover, New Jersey.
The source will be transported in accordance with the DOT regulations.
Should you need any further information, please feel free to contact me at (215) 343-5900, extension 276.
Thank you.
Sincerely, NUCLEAR RESEARCII CORPORATION J.As94 S.
Sengupta Radiation Safety Officer SS/cib
Enclosures:
NRC 313I Form in duplicate Attachment #1 Attachment #2 Calibration Certificate of AN/UDM-7 Calibration Certificate of Th-230 Source Calibration Certificate of Am-241 Source Calibration Certificate of AmBe Source Calibration Certificate of Pu-Be Source Data Sheet for Pu-Be Source Resumes P.S.
License Renewal Fee for $110.00 (Ck #28629) was sent with original license renewal application on June 28, 1983.
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s FORM NRC-313 I U.S. NUCLEAR REGULATORY COMMISSION
- 1. APPLICATION FOR:
(Check and/or complete as appropriate)
(3-80) 10 C F R 30 APPLICATION FOR BYPRODUCT MATERIAL LICENSE
- s. NEW LICENSE INDUSTRIAL
- b. AMENDMENT TO:
See attached mstructions for details.
LICENSE NUMBER Completed applications are filed in duplicate with the Division of Fuel Cycle and Material Safety, Office of Nuclear Material Safety, and Safeguards, U.S. Nuclear Regulatory Commission,
- f lYshington, DC 20SSS or applications may be filed in person at the Commission's office at
R'",'*#'*'h w g n,g uu 1717 H Street, NW, Washington, D. C. or 191S Eastern Avenue, Silver Spring, Maryland.
- 2. APPLICANT'S NAME (Institution, firm, person, etc.)
- 3. NAME AND TITLE OF PERSON TO BE CONTACTED REGARDING THIS APPLICATION NUCLEAR RESEARCII CORPORATION SUBHASH SENGUPTA TELEPHONE NUMBER: ARE A CODE - NUMBER EXTENSION TELEPHONE NUMBER: ARE A CODE - NUMBER EXTENSION (215) 343-5900 (215) 343-5900
- 4. APPLICANT'S MAILING ADDRESS (loclude Zip Codel
- 5. STREET ADDRESS WHERE LICENSED MATERIAL blLL t!E USED (Address to which NRC correspondence, notices, bulletins, etc.,
(Include Zip Code) should be sent.)
125 TITUS AVENUE 125 TITUS AVENUE WARRINGTON, PA 18976 WARRINGTON, PA 18976 (IF MORE SPACE IS NEEDED FOR ANY ITEM, USE ADDITIONAL PROPERLY KEYED PAGES.)
- 6. INDIVIDUAL (S) WHO WILL USE OR DIRECTLY SUPERVISE THE USE OF LICENSED MATERIAL (See items 16 and 17 for required training and experience of each indivkfuel named belowl FULL N AMF.
TITLE 2-EARL ?!. POLLOCE PRESIDENT
- b. SUBHASII SENGUPTA RADIATION SAFETY OFFICER c.T.W.
SCI! WAGER ASSISTANT RAD. SAFETY OFFICEP.
I A ttach a resume of person's training and experience as outlined in Items
- 1. RAD 1ATION PROTECTION OFFlCER l 16 and 17 and describe his responsibilities under item IS.
SUBL!AS!! SENGUPTA l
- 8. LICENSED MATERIAL L
ELEMENT CHEMICAL NAME OF MANUF ACTURER MAXIMUM NUMBER OF AND MILLICURIES AND/OR SEALED i
AND AND/OR N
MASS NUMBER PHYSICAL FORM MODEL NUMBER SOURCES AND MAXIMUM ACTI-(If Sealed Source)
VITY PER SOURCE WHICH WILL E
BE POSSESSED AT ANY ONE TIME NO.
A 8
C D
Dispersed in Atomchem, Monsanto
("
Plutonium 239 Resin / Plated on AN/UDM-7 10 Milligram Steel.
(2)
(Pu-Be)
Encapsulated in Neutron Source s
(3)
Plutonium 239 Stainless Stee:
S/N - ?1595/!!onsanto 47.98 Gram (4)
Uranium 235
' lated on Steel Monsanto 1 Millivram DESCRISE USE OF LICENSED MATERIAL E
in Nuclear Research Corporation manufactures Alpha Survey Pie t er (2)
AN/PDR-56, X-Ray Probe DT-590/PDR and Neutron Survey ?!eter AN/PDR-70 (3)
(Snoopy NP-2) for the U.S.
Department o f De fense.
The radiation (4) sources are used to calibrate these instruments.
FORM NRC-313 i (3-80) c an n,rm DCT 191983 u n vror 1 iy
9.STORA E( F SEALED SOURCES Y
CONTAINER AND/OR DEVICE IN WHICH EACH SEALED NAME OF MANUFACTURER MODEL NUMBER g
SOURCE WILL BE STORED OR USED.
NO.
A.
B.
C.
Alpha Sources are stored in wood n,
and Aluminum box.
Atomchem/?!onsanto AN/UD"-7 Nautron Source is stored in a (2) 15 callon para f fin drum.
?tonsanto Chenical UN !f-595 (3)
(4)
- 10. RADIATION DETECTION INSTRUMENTS TYPE M AN U F ACTU R E R'S MODEL NUMBE R RADIATION SENSITIVITY
(
OF NAME NUMBER AVAILABLE DETECTED RANGE N
1NSTRUMENT (alpha, beta, (milliroentgens/ hour Q,
gamme, neutron) or counts / minute)
A B
C D
E F
Alpha, Xray Nuclear Re-AN/PDR-56 Alpha, Pu 6
Survey ?!eterscarch Corp. DT/590 2
L Xray 0-10 CP!'
Aloha Scin-
'2'
?'D-3 C,
6 ti11ation De t.
?.fD-34 1 Each A l t,h a 0-10 CPB!
3F-3 AN/PDR-70
Counter (Snoow/NP -2) 2 Neut ron 0-2 Ren/Ifr
.'lica tl indow 727 Alpha, Beta G?.! Detector LND 2
Ganna 0-105 c p;.
- 11. CAllBRATION OF INSTRUMENTS LISTED IN ITEM 10 Ca. CALIBRATED BY SERVICE COMPANY Qb. CALIBRATED BY APPLICANT NAME, ADDRESS, AND FREQUENCY A ttach a separate sheet describing method, frequency and standards used for cabbrating instruments.
SEE ATTAC!!?!ENT # 1
- 12. PERSONNEL MONITORING DEVICES ICheck and/or compt te as appropriate.)
(Serv ce Co any)
A B
0C(1) FILM BADGE R.S.
LANDAUER, JR. 6 CO.
@ MONTHLY DIVISION OF TEC!!/0PS, INC.
@ (2) THERMOLUMINESCENCE GLENT!OOD SCIENCE PARK O QUARTERLY DOSIMETER (TLD)
G L E N !l0 0 D, ILLINOIS 60425 O (31 OTHER (Specifyl:
O OTHE R ISpecity):
- 13. FACILITIES AND EQUIPMENT (Check were appropriate and attach annotated sketch (es) and description (s).
O a. LABORATORY FACILITIES, PLANT F ACILITIES, FUME HOODS (include filtration,if any), ETC.
O b. STORAGE FACILITIES, CONTAINERS, SPECI AL SHIELDING (fixed and/or temporary), ETC.
O c. REMOTE HANDLING TOOLS OR EQUIPMENT, ETC.
p O d. RESPIRATORY PROTECTIVE EQUIPMENT, ETC.
N/A
- 14. WASTE DISPOSAL
- a. NAME OF COMMERCI AL WASTE DISPOSAL SERVICE EMPLOYED N/A
- b. IF COMMERCIAL WASTE DISPOSAL SERVICE IS NOT EMPLOYED, SUBMIT A DETAILED DESCRIPTION OF METHODS WHICH WILL BE USED FOR DISPOSING O.' R ADIOACTIVE WASTES AND ESTIMATES OF THE TYPE AND AMOUNT OF ACTIVITY THE APPLICATION IS FOR SEALED SOURCES AND DEVICES AND THEY WILL BE RETURNED TO THE MANUFACTURER, SO STATE.
N/A FORM NRC 3131 (3-80)
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INFORMATION REQUIRED FOR ITEMS 15,16 AND 17 Describe in detail the information required for items 15,16 and 17. Begin each item on a separate page and key to the application as follows:
- 15. RADIATION PROTECTION PROGRAM. Describe the radiation protection program as appropriate for the material to be used including the duties and responsibilities of the Radiation Protection Officer, control measures, bioassay procedures (1/ needed), day to-day general safety instruction to be followed, etc. If the application is for sealed source's also submit leak testing procedures, or if leak testing will be performed using a leak test kit, specify manufacturer and model number of the leak test kit.
SEE ATTACHMENT #2
- 16. FORMAL TRAINING IN RADI ATION SAFETY. Attach a resume for each individual named in items 6 and 7.
Describe individual's formal training in the following areas where applicable, include the name of person or institution providing the training, duration of training, when training was received, etc.
- a. Principles and practims of radiation protection.
- b. Radioactivity measurement standardization and monitoring techniques and instruments.
- c. Mathematics and calculations basic to the use and measurement of radioactivity.
- d. Biological effects of radiation.
17.
EXPERIENCE. Attach a resume for each individual named in items 6 and 7.
Describe individual's work experience with radiation, includin2 where experience was obtained. Work experience or on-the-job training should be commensurate with the proposed use. include list of radioisotopes and maximum activity of each used.
ATTACHED RESUMES
- 18. CERTIFICATE (This item must be completed by applicant)
The applicant and any official executing th!s certificers on uhalf of the applicant named in item 2, certify that this application is prepared in conformity with Title 10, Code of Federal Reputations, Part 30, and that all Information contained herein, including any supplements attached hereto, is true and correct to the best of our knowledge and belief.
WARNING.-18 US4., Section 1001 Act of June 25,194=: 62 Stat. 749; makes h a criminal offense to make a willfully feles statement or representation to any department or egency of the United States as to any matter within its jurioWetion,
- s. LICENSE FEE REQUIRED
- b. CERTIFYING QFFICIAL (Signature)
(See Section 170.31,10 CFR 170) l f
- c. NAME ITyp5 or prinTI f S.
Sengupta (1) LICENSE FEE CATEGORY:
RENEMAL Radiation Safety Officer (2) LICENSE FEE ENCLOSED: $ $110.00 FORM NRC-313 I (3 80)
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ATTACH!!ENT.#1 (ITEM lib)
E CALIBRATION OF INSTRUMENTS
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1.
AN/PDR-56.
The Alpha Survey Radiac AN/PDR-56 is cal-ibrated with-Pu-239 Alpha Radiac Calibration, AN/
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UDM-7_at a frequency of 6 months.
The Alpha Radiac Calibrator was supplied to Nuclear. Research Corporation from Naval Elect ronic Systems Command, Charleston,
Detail calibration procedure'is given'in the technical manual of AN/UD31-7.
SENSITIVITY:
1 CP.'! = 6. 2 x 10- 6.,uCi/100 cm or 2
0.01 ugm/n' 2
WINDOW TIIICKNESS:
0.5 mg/cm DETECTOR TYPE:
Scintillation:ZnS (Ag)
ACTIVE AREA:
17 cm 2.
X-RAY PROBE DT-590/PDR.
The X-Ray Probe detects the ~ 17 key Pu-239 L X-Rays.
The X-Ray Probe is calibrated with the Pu-239 Alpha Radiac Calibrator
)
AN/UDM-7 at a frequency of 6 months.
2 2
SENSITIVITY:
1 CPM = 12.4 x 10" uCi/cm or 0.2 ugm/m 2
WINDOW TilICKNESS:
0.5 mg/cm DETECTOR TYPE; Scintillation - CaF i
2 ACTIVE DIA.
- ~ 1.5" inches 3.
MD-3C/MD-34 DETECTOR.
These detectors are calibrated (efficiency) with Pu-239 (AN/UDM-7), Th-230 and
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.Am-241 sources. 'The efficiency of the detectors are approximately 30% - and they are determined prior to any l!
measurements.
The MD-3C is an Alpha Detector and MD-34
'I, ii is Alpha / Beta Detector.
The MD-34 is very low background f
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- n. detector (" I CPM).
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MD-3C DETECTOR:
Scintillation - Zn S(Ag)
ACTIVE DIAMETER:
'"1.5" MD-34 DETECTOR:
Phow-switch type:
Plastic Scintillator with Zn S(Ag).
ACTIVE DIAMETER:
~ 1.5" inches 2
WINDOW TilICKNESS:
0.5 mg/cm 4.
G.M.
DETECTOR _S.
The G.M. Detector has mica window-2 approximately 1.5 - 2mg/cm thick and active diameter
-s1 inch.
The G.M. detector is housed in lead shield to minimize the background coun ts.
The efficiency of the detector is determine'd with alpha sources, Am-241, Th-230 prior to measurement.
The scaler CP-792 i
l has accuracy + 1 count.
5.
NEUTRON SURVEY METER - AN/PDR-70 (SNOOPY - NP-2)
The instrument consists of a unique moderator /attenuator assembly, BF3 detector and associated'clectronics used t
to. convert the detector pulse output 'to a meter reading in mrem /hr.
The detector is calibrated with Am-Be neutron source, at.a frequency of 6 months.
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6000 counts per. mrem.
.GA. fA SENSITIVITY:
No response to gamma radiation in
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fields up to 500R/hr of CS-137 F
DYNNIIC RANGE:
Four Linear Ranges:
'0 { mrem /hr;~
0 20 mrem /hr;;0-200 mrem /hr; 0-2000 t
s
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mrem /hr.
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] ti ENERGY RESPONSE:
Thermal (0.'25 ev) to 15 mei.
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10%
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ATTACilMENT #2 (BLOCK 15)
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4 RADIATION PROTECTION-PROGRAM ~
-Nuclear Research Corporation's Radiation. Safety !!andbook
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zoutlines'the radiation protection program'in general.
The 4
.following safety procedures specifically provide the radiation
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't protection plan for special nucicar material (s).
E i
41.
'SPECIAL NUCLEAR MATERIAL AS AN ALPHA' SOURCE The Special Nucicar Materials are in scaled form, l
plated on stainless steel or dispersed in resin.
There l
l is no external radiation hazard from these sources.
[
Plutonium-235 is highly toxic radionuclide.
Therefore protection against personal contamination resulting from l
inhaling, injesting or tactically transmitted radio-I activity must be taken.
Since the sources are in. sealed i
form, it is not likely that contamination can occur through inhalation or injestion.
Safety and contamination con-trol training and procedures must be observed during handling of special nuclear material as indicated below:
i 1
A.
GENERAL SAFETY PROCEDURES c
1.
Personnel.being qualified for duty at the facility will be instructed concerning hazards of exposure to specific sources, necessary i
precautiona ry procedures, and approved methods-of utilizing the calibration sources.
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SaIe methods of handling various sources to-2:.
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preclude rough handling and mis-use must be j !'
stressed.:
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- 3.
Emphasis must be place on' avoidance of personal
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G' contact'with the surface'of the source to in-ciude:
Avoiding touching the' source with open cut wounds, prohibition of eating and drinking while handling the sources, and l
i preventive measures such as washing and l
drying hands throughly after handling the sources.
i 4.
Procedures must be established which avoid con-tact by tools, instruments, and equipment with the source.
l 5.
The safety education must continuous, measures supervised, and cautions posted.
L l
B.
CONTAMINATION CONTROL IN CASE OF ACCIDENT INNOLVING l
RUPTURE SEALED SOURCES.
l 1.
Immediately cordon the area when the accident occurs and institute a trafficicontrol program i'
to minimize trackage.
2.
All fans and air conditioners shall be shut off O:s and everyone shall Icave the area.
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- 3.. Vacuum cican the area wearing coveralls and shoe
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$5
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. covers (plastic over shoe or ordinary brown paper
- i rd' bag).
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4.
Survey the contaminated area with AN/PDR-56 E'
Alpha Probe and with the X-Ray Probe (Pu-239
- f-j 17 kev U X-Ray) and the readings recorded on an area map.
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5.
After dry vacuum cleaning, damp mopping with a detergent should be done to remove the con-tamination.
1 6.
Survey the area periodically with AN/PDR-56 and X-Ray Probe to check for contamination.
I-7.
Take wipes with filter paper and read them with the Alpha Detector (MD-3C, MD-34 Scintillation
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Type or GM Detector (2mg/cm*, window thickness) for final contamin'ation check.
8.
All the refuse shall be kept in a drum in the L
hot cell for disposal by licensed disposal' service.
C.
_ PERSONNEL DECONTAMINATION 1..
All suspected persons should be surveyed for radioactive contamination.
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Survey the clothing, shoes'with an X-Ray Probe
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for contamination.
Contaminated clothing should be removed carefully and'placed in some type-of-disposable container of = bag.
.jj 3.
Monitor skin with the Alpha Probe ( AN/ PD R'.56) o<
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l or with the X-Ray-Probe aad' isolate the contamination if area.
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Wash with copious amounts of' detergent, chelating
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(
5.
Monitor again with Alpha or X-Ray Probe, o
l 6.
Wash again and continue routine until activity is no longer present.
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7.
If activity persists, the involved area only s[
should be treated with a saturated-solution of potassium permanganate followed by sodium b
bisulphite.
L NOTE:
Consult with a physician l
8.
If the face and head are contaminated, the eyes I
and nasal cavities should be irrigated with water of normal saline.
The mouth will be treated d.
similarly.
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9.
If the' contaminated area occurs with cut, and wash the wounded area with large. volumes of water, W..
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1, spread cut edges so as to flesh the wound well and stimulate bleeding.-
Survey the wounded area
,3 with the X-Ray Probe only for contamination.
10.
A light tourniquet may bc. applied to restrict.
venuous return without restricting arterial 1
flow.
Suitable precautions in tourniquet must be 'followed.
11.
Report immediately thereaf ter for definitive medical care.
12.
If ingestion is suspected, consult physician for medical care.
All stool and uring sample should be collected for the evaluation of body burden.
2.
SPECIAL NUCLEAR MATERIAL AS A. NEUTRON SOURCE n
The 3 curie Pu-Be source is used in the calibration of
' neutron detection instrument.
The Pu-Be source is con-tained in a hermetically sealed stainless steel capsule which in turn stored in a 15 gallon, paraffin-filled drum.
A 2 inch pipe in the center of paraffin permits the source to be raised vertically out of the drum for r.
calibration use.
Following radiation safety procedures will be performed.
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SAFETY PROCEDURE g
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The source and calibration area will be located
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i The access door will be under lock and key.
1 2.
The source and the calibration area will be shielded for neutron dose with paraffin wall to 4
meet requirements of 10 CFR Part 20 3.
A warning light is placed outside the paraffin shield (which is visible from the access door) to indicate the source exposed condition.
The light is powered on by an alarm signal from a neutron detector (BF-3 proportional counter) which g
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is placed near the source container.
4.
Personnel who are to be qualified for use of j
the facility will be instructed concerning the hazards of exposure to the source, the necessary L.
4 precautions and the approved method of utilizing the calibration facility.
5.
Operator must wear neutron sensitive film badge while using the neutron source.
6.
Operator must log date, duration of stay in the
[
llot Cell Log Book.
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s.
V,I B.
EMERGENCY PROCEDURES 1.
If the source container (paraffin drum) is broken (or para ffin is lost due to heat or fire), shield the source with barrel or drum containing water.
2.
Survey the area with neutron survey meter AN/PDR-70 (Snoopy NP-2) and cordon the area.
3.
In case the source capsule is ruptured, survey the area with an X-Ray Probe (DT-590/PDR) and follow the procedures listed under "Special Nuclear Material as an Alpha Source", for con-tamination cont rol and personnel decontamination.
3.
SURVEY AND WIPES 1.
Neutron Survey will be performed with a REM counter (AN/PDR-70) monthly.
2.
Building wipes will be performed monthly.
n 3.
Source wipes will be performed at an interval of 4.
three (3) months and read with Alpha Detectors.
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OwaadaJee,a wrg MOMSANTO ME S6 AMCM COSIPOM4f1 Ops e
r Daytoa Laboeetory jy I " 45 1515 Necholas head P. O. Das 8. Station B
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Dayton.Choo 4S407 Phones: ($13) 269-6789 (513) 2S 8 -3 418 Tel*0raoh: Tw* 810- AS9 1681 For:
fluclear Research Corpora tion 1105 Industrial Highway Southhampten, PA.
18966 Attn:
A.
J.
Cassel This is to certify that Monsanto Research Corporation's S. 11.
AnBe-2516 neutron source sold to LFE Corporation on 4-08-75 cas determined as having a neutron output of 2.34 X 107 n/sec 3% by direct comparison to MRC neutron source S. fl. AmEe-1505, an in-house secondary standard which'has been calibrated with the same equipment and geometry against MRC Pu-239-Be neutron source S. fl.
PuBe-320 calibrated at the !;ational Bureau of Standards on 2-14-67.
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lia rol d L. Coleman l'a n a g e r, !!anuf acturing Support Date 3-14-78 l'
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PLUTONIUM NEUTRON SOURCE CALIBRATION DATA Source - /W o/[
Calibration date - T*4 ' e' ' E
/$/N/
Total neutron emission rate (Q)- f6 #/)'//
neutrons /second Mound Laboratory comparison standard source - A/ ['//
Relative uncertainty of comparison with Mound Laboratory source - f.Z
% (one std dev)
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Absolute uncertainty of Q -
f.:
(one std dev)
Anisotropy (Ref " Anisotropy of Neutron Emission for Cylindrical Pu Be Sources") ve (O') - [, f (903 - /, /f a(1807 t.'/
j s
- Determmed from measurements of this source
- Typical value for sources of this approximate size and shape Plutonium isotopic analysis (Ref " Increases in Neutron Yields of Plutonium-Beryllium (e.n) Sources") ~
isotopic analysis of the plutoniurn used in this source is not available. A i'
method of estimating the variation in total neutron emission rate with time is given in the appendix of the referenced article. The estimated value for the quantity R in equation A-2 of this article is 0 O/ M d'O M and the "birthdate" of the source is
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y m my n nmg ~ g n CERTIFICATE OF RADIOACTIVITY CAllBRATION I isotope:/$,.Avs. Half Life: 432.2 f 7 Source No.: 7f/F-7_ Was assayed as containing: 9,9 g y 6,. l;As of: 2-t-33 METHOD' OF CAllBRATION: ( ') The source was assayed on a 3" x 3" Nal (TI) crystal in conjunction with a single-channel analyzer, using the MeV peak ( a value of gamma rays per decay was used in the calculations), against standard No. , in the same geometrical arrangement. (K ) The source was assayed in a windowiass internal proportional counter against C./ N{ standard No. 49 e7-(,/ ( ) The source was assayed by alpha spectrometry on a surface barrier detector in conjunction with a single-channel analyzer, against standard No. in the same geometrical arrangement. ( ) The source was prepared from a weighed eliquot of a solution whose activity in pCi/gm was determined by the method indicated above. ERROR CALCULATION: a) Systematic errors (SE) 1. Accuracy of the standard: # /. 7f 2. /o b) Random errors (RE) 1. Precision of source count, e,: 2. Precision of standard count, e, : 3. Error due to background, e : 3 RE = Ge2 + e g +,2 f /. c) Total Error TE = SE + RE ! 3.00/ NOTES I ( )() The error given is calculated at the $% confidence level. l ( ) This calibration is directly/ indirectly based on NBS Standard Ref rence Material No. I ISOTOPE PRODUCTS LABORATORIES 7 e: Kenneth He\\m Health Physicist i L ' 1800 NO. KEYSTONE ST, BURBANK, CALIFORNIA 91504
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(lso ope: 73.EJ o Half Life: i . Source No.: ' 7 S/T-6 i, y ,s Wasy.ssayed as containing: ' P,o y g (, - As of: 2 90 METHOD OF CAllBRATION: ( ) .The wurce was assayed on a 3" x 3" Nat (TI) crystal in conjunction with a single-channel analyzer, using the MeV peak ( a value of gamma rays per decay was used in the calculations), against standard No. , in the same geometrical arrangement. ()() The source was assayed in a windowless internal proportional counter against Gef-/*/i standard No.*f to?-G/ ( ) The source was assayed by alpha spectrometry on a surface barrier detector in conjunction with a single-channci analyzer, against standard No. in the same geometrical arrangement. ( ) The source was prepared from a weighed aliquot of a solution whose activity in pCi/gm was determined by the method indicated above. ERROR CALCULATION: a) Systematic errors (SE) 1. Accuracy of the standaid: 1 /. 7 b) Random errors (RE) 1. Precision of source count, e,: 2. Precision of standard count, e, : 3. Error due to background, e, : j RE=he + ej + e' f I 17 i 2 c) Total Error TE = SE + RE I 2 97 NOTES ( )() The error given is calculated at the M % confidence level. ( ) This' calibration is directly/ indirectly based on NBS Standard Reference Material No. l ISOTOPE PRODUCIS LABORATORIES Tiff '/' 'V Kenneth IIelm Health Physicht i 1800 NO KEYSTONE ST.. BURBANK. CALIFORNIA 91504 I j m,
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g o o EARL M. POLLOCK - PRESIDENT 3 8 EDUCATION: University of Pennsylvania, B.A. in Physics l Drexel Institute of Technology, Chemical Engineering University of Tennessee, Nuclear Engineering .f E w QUALIFICATIONS: 18 years experience as Senior Executive Officer i of successful small business enterprise - manufacturing. industrial nuclear systems for process industries, applying twenty years experience in engineering manage. f ment, design, development and markettng. ( I Specific experience includes' design of nuclear instrumentation and controls for ? ndustrial, military ) and medical applications, as 'well as environmental monitoring and radiation safety.. Design of industrial systems for non destructive testing and quality control. Process inspection systems for thickness, density and level, using both isotopic and x-ray methods, involving principles of measurement through transmission, reflection and fluorescence. Research scientist and instructor' responsible for j setting up programs at Oak Ridge Institute of Nuclear E Studies for training engineers in the -industrial uses - of nuclear energy for process control applications. 8 PREVIOUS ' '? i AFFILIATIONS: Imperial Chemical Corporation; President Ohmart Corporation Vice President-t g Oak Ridge Institute of Nuclear Studies, Research Scientist I 5 Victoreen Instrument Company, Chief Engineer, k k El-Tronics. Inc.. Research Physicist' E. I. DuPont de Nemours 1 Company,- Assistent Chemist l MEMBERSHIPS: American Nuclear Society Health Physics Society .i American Physical Society Instrument Society of Mrica q J American Association for the Advancement of Science ~
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o o RESUME SUBHASH SENGUPTA EDUCATION: M.S. - Instrumental' Sciences Department of Electronics & Instrumentation University of Arkansas.1971 B.S. Physics University of Calcutta, India 1959 l EXPERIENCE: 1978 - PRESENT PROJECT ENGINEER - NUCLEAR RESEARCH CORPORATION Responsibilities include development work on I nucleonic detection and monitoring equipments, radiation sensors and related instrumentation; i radiation calibration and radiation protection and Health Physic Services. 1976 SCIENTIST - National Instruments Ltd., Calcutta, India Responsibilities: In charge of Analytical Instrumentation Development Project - which included engineering development,' negotiation and collaboration with a major I European instruments manufacturing company (MOM). Also involved with the development project on liquid-level measuring instruments, touchless tachograph and solar energy measuring instruments. 1973-1976 PROJECT ENGINEER - Ardac, Inc., Willoughby, Ohio 1 Responsibilities included research and development work on detection techniques for paper. currency validation; electro-optics systems design; circuitry I design; analysis of the existing detection techniques and solve their problems evaluation of performance characteristics of various sensors selection and e I specification of components; contact vendors; purchase laboratory equipments; correspond with the customers in technical matters. 15 Developed a color detection system from conception through to production. This project involved with spectrophoto-la da metropto-electronics', circuitry design;and o'ptics. m l- $ -t (1971-19731 CONSULTING ENGINEER - General Nucleonics, Inc. J}} ,Q Brunswick, Ohio 2 .g-f i Consul'tation work involved ' ith he deve13pment of an w ,.' i. !c
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E O o SUBHASH SENGUPT (Page Two) 1970-1971 ENGINEER - Calark, Inc., Little Rock, Arkansas In charge of all production work for this electronic firming instruments manufacturing company. 1968-1970 GRADUATE RESEARCH ASSISTANT - Dept. of Electronics & Instrumentation, University of Arkansas, Little Rock. 1 ~ Responsibilities included re' earch work on Holographic s Interferometry. This project was supported by NASA and title of the technical report " Separate Reference l Beam Holographic Interferometry.and It's Application To the Measurement of Small Phase Variations in Sub-Fringe Systems". Also responsible for maintenance of lasers and other laboratory instruments. E Worked on research project on cold electron emitter for M.S. thesis. Title of the thesis: " Characteristic of Self-sustained Tin Oxide Thin Film Electron Emitters." l Laboratory experience with course work in Analytical i l Instrumentation and Process Control Instrumentation. 1 1967-1968 RESEARCH ASSISTANT - Nuclear Enterprises, Inc. Winnipeg, Manitoba, Canada Responsibilities included production of plastic and liquid scintillators. 1960-1967 SCIENTIFIC ASSISTANT - Bhaba Atomic Research Center N Bombay, India Responsibilities included radiation protection, safety analysis, recommendation according to ICRP regulations; personnel monitoring. -R & D. work on film and thermoluminescent dosimetry. Experience E in nuclear detectors and instrumentation; radio-isotope methodology in medicine and industry; redical and industrial application of x-rays. E y v 6 t s I e 3 - o
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,i t-n. =n ~ as EDUCATION: Master's work-in Biomedical En'gineering:, ]j L ~ UNIVERSITY OF PENNSYLVANIA PilIIADELPIIIA, PENNSYLVANIA U!! i 9 i a, 3 e Training included course work in the' fb110w$ng:lC 4. i) Principles and practices of radiation : - h protection 4 ii) Radioactivity measurement standardi::ation - and monitoring techniques iii) Mathematics and calculations basic to the!ude and measurement of radioactivity : P iv) Biological effects of radiation.- 10RK EXPERII? ICE: APRIL 1981 - PRESENT NUCLEAR RESEARDI CORPORATION Warrington, PA -c s ASSISTANT RADIATION SAFLTY OFFICER 1[
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