ML20245G522

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Application for Amend to License SNM-1020,reflecting LP Jeffery as President & Br Hershenson as Acting Dean & That Univ No Longer Uses Interex Co for Disposal of long-lived Waste
ML20245G522
Person / Time
Site: 07001067
Issue date: 09/21/1987
From: Jeffrey L
MASSACHUSETTS COLLEGE OF PHARMACY & ALLIED HEALTH
To:
Shared Package
ML20245G494 List:
References
107871, NUDOCS 8902140467
Download: ML20245G522 (40)
v • d • e


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U.S NUCLEAR NE2CLATORV COMMIS$10N NRC FORM 313'.

APPROVED BY OMS (Set n eo -

APPLICATION FOR MATERIAL LICENSE.

f1840120 10 CFR 30,32,33,34,'

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wet INST 4UCTIONS: SEE THE APPROPRIATE LICENSE APPLICATION GUIDE FOR DETAILED INSTRUCTIONS FOR COMPLETING APPLICATION. SEND TWO COPIES' OF THE ENTIRE COMPLETED APPLICATION TO THE NRC OFFICE SPECIFIED BELOW.

FEDETAL AGENCIES FILE APPLICATIONS WITH:

IF YOU ARE LOCATED IN:

U.S. NUCLE AR REGULATORY COMMISSION ILLINOIS, INDI ANA, IOWA, MICHlGAN, MINNESOTA, Ml8SOURl, OHIO, QR -

DIVI $lON OF FUEL CYCLE AND MATERIAL SAFETY, NMSS WISCONSIN, SEND APPLICATIONS TO:

EfASHINGTON,DC 20566 U.S. NUCLE AR REGULATORY COMMISSION, REGION ill ALL CTHER PERSONS FILE APPLICATIONS AS FOLLOWS,lF YOU ARE MATERI ALS LICENSING SECTION LOCATED IN t 790 ROOSEVELT ROAD GLEN ELLYN,lL 60137 CONNECTICUT, DELAWARE, DISTRICT OF COLUMSIA.' MAINE. MARYLAND, MASSACHUSETTS. NEW HAMP9 HIRE, NEW JERSEY, NEW YORK, PENNSYLVANIA, ARKANSAS, COLORADO, ICAHO, MANSAS, LOUlslANA MONTANA, NiiBR ASKA, RHOJE ISLAND, OR VERMONT, SEND APPLICATIONS TO:

NEW ME XICO, NORTH DAKOT A, OK LAHOMA. SOUTH DAKOTA, TEXAS, UI AH, -

OR WYOMING, SEND APPLICATIONS 70-.

U.S. NUCLE AR REGULATORY COMMIS$10N, REGION I U.S. NUCLE AR REGULATORY COMMISSION REGION IV.

NUCLE AR MATkRIAL SECTION B '

MATERIAL RADIATION PROTECTION SECTION 631 PARK AVENUE

- KING OF PRUS$lA,PA 19406 '

611 RY AN PLAZA DRIVE, SUITE 1000 ARLINGTON,TX 76011 ALLSAMA, FLORIDA, GEORGIA, KENTUCKY, MISSIS $1PPl, NORTH CAROLINA.

f'UE ATO RICO, SOUTH CAROLINA, TE NNESSEE, VIRGINIA, VIRGIN ISLANDS, OR ALASKA, ARIZONA, CALIFORNI A, HAWAll, NEVADA, OR EGON, WASHINGTON, -

WEST YlROINIA, SEND APPLICATIONS TO:

AND U.S. TERRITORIES AND POSSES $10NS IN THE PACIFIC, SEND APPLICATIONS TO:

' U.S. NUCLE AR REGULATOR Y COMMISSION, R EQlON ll

. MATERIAL RADIATION PROTECTION SECTION U.S NUCLEAR REGULATORY COMMIS$10N, REGION V 101 MARIETTA STREET,3UITE 2900 MATERIAL RADIATION PROTECTION SECTION ATLANTA, GA 30323

?450 MARIA LANE,SulTE 210 WALNUT CREEK,CA 94596 f.

PEMONS LOCATED IN AGREEMENT STATES SEND APPLICATIONS TO THE U.S. NUCLEAR REOULATORY COMMISSION ONLY IF THEY WISH TO POSSESS AND USE LICENSED MATERIAL IN STATES suSJECT TO U.S. NUCLE AR REGULATORY COMMISSION JURISDICTION.

1,THIB 15 AN APPLICATION FOR (Check appropr#efe item /

2. NAME AND MAILING ADDRESS OF APPLICANT (includelp Covel

^ " ' * ' ' ' ' * " '

Massachusetts College of Pharmacy and Allied Health Sciences (MCP/AHS)

B. AMENOMENT TO uCENSE NUMB'"

SNM,1020 C. RENEWAL OF LICENSE NUMBER 179 Longwood Avenue Rise +rm Mneesr&ren++e M11 C

3. ADDRES$1ESIWHERE LICF.NSED MATERIAL WILL BE USED OR POSSESSED.

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179 Longwood Avenue Boston, Massachusetts O'2115

4. NAME OP PERSON TO BE CONTACTED ABOUT TH18 APPLICATION TELEPHONE NUMBER Dr. George Matelli (617) 732-2933

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EU$MIT ITEMS S THROUGH 11 ON 84 a 11" PAPER. THE TYPE AND SCOPE OF INFORMATION TO BE PROVIDED 18 DESCRIBED IN THE LICENSE APPLICATION GUIDE.

S. RADIOACTIVE MATERIAL a, Element and mass number, b, chemical end/or physical form, and e. mammum smount 6 PURPOSEISI FOR WHICH LICENSED MATERI AL WILL BE USED.

which will be possessed si eny one time.

T.

NDlVIDUA S RESP S BL FOR RADIATION SAFETY PROGRAM AND THEIR

8. TRAINING FOR INDIVIDUALS WORKING IN OR FREQUENTING RESTRtCTED AREAS,
9. FACILITIES AND EOUIPMENT.
10. RADIATION SAFETY PROGRAM.

I2, LICENSE E F EEG ISee 10 CFR 110end Sectoon 11021) 170.11 (4) p~" CLOSED s

11. WASTE MANAGEMENT.

FEE CATEGORY

13. CERTIFICATION. (Atust es completed by sophcent) THE APPLICANT UNDERSTANDS TMAT ALL ST ATEMENTS AND REPRESENT ATIONS MADE IN THl3 APPLICATION ARE BINDING UPON THE APPLICANT.

THE APPLICANT AND ANY OFFICIAL EXECUTING THIS CERTIFICATION ON BEHALP OF THE APPLICANT. NAMED IN ITEM 2, CERTIFY THAT THl3 APPLICATION IS y

PREPARED IN CONFORMITY WIT H TITLE 10. CODE OF FEDERAL REGULATIONS. PARTS 30,32. 33,34. 36, AND 40 AND THAT ALL INFORMATION CONTAINED HEREIN.

18 TRUE AND CORRECT TO THE BEST OF THEIR KNOWLEDGE AND BELIEF.

W ARNING: 10 U S.C. SECilON 1001 ACT OF JUNE 25,1948.62 STAT. 749 MAKES IT A CRIMINAL OFFENSE TO MAKE A WILLFULLY FALSE STATEMENT OR REPRESENTATION TO ANY DEPARTMENT OR AGENCY OF THE UNITED STATES AS TO ANY MATTER WITHIN ITS JURISDICTION I TYPED / PRINTED NAME lTITLEPresident IDATE SIGNATURE -CERTIFYING OF FICER Louis P. Jeffrey 14 VOLUNTARY l CONOMIC DAT A

a. ANNu LL R CE!PTR D. NUMBER OF EMPLOYEES ITots/ for d WOULD YOU SE WILLING TO PURNISM COST INFORMATION (itoI/er enaer ste# hoursi

'""" * *"d"8*8 8"'d' contreetoral ON THE ECONOMIC IMPACT OF CURRENT NRC REGULATIONS OR ANY FUTURE i

<S250K -

SIM-3 SM PROPOSED NRC REGULATIONS THAT MAY AFFECT YOUP (NRCreputerionspermn

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M to pmtect conMenper commercost or nnoncent-pmomMry-onformenon turntshed te

$26nK-600K S3.SM-7M the agency in conhdancel

c. NUMBER OF BEDS 8500K-760K

$7M-10M S?SOK-1M

> $10M YES NO FOR NRC USE ONLY l-TYP F EE FEE OG FEE CATEGOR Y COMMENTb APPRO D a

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890214046 871216

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REG 1 LIC PNU DATE AMOUNT R Of VED4 CHE.CK NUMBER L

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  1. ?6 PRIVACY _ACT STATEMENT ON THEllT Al(Stj

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PRIVACY ACT STATEMENT.

Pursuant to 5 U.S.C. 552a(e)(3), enacted into law by section 3 of the Privacy Act of 1974 (Public Law 93 579),the follow-

~ing statement is furnished to individuals who supply information to the Nuclear Regulatory Commission on NRC Form L 313. This information is maintained in a system of records designated as NRC 3 and described at 40 Federal Register 45334 (October 1 1975).

1. AUTHORITY: Sections 81 anci 161(b) of the Atomic Energy Act of 1954, as amended (42 U.S.C. 2111 and 2201(b)).
2. PRINCIPAL PURPOSE (S):-The information is evaluated by the NRC staff pursuant to the criteria set forth in 10 CFR Parts 30,32,33,34,35 and 40 to determine whether the application meets the requirements of the Atomic Energy Act of 1954, as amended, and the Commission's regulations, for the issuance of a radioactive material license or amendment thereof.
3. ROUTINE USES: The information may be (a) provided to State health departments for their information and use; end (b) provided to Federal, State, and local health officials and other persons in the event of incident or exposure, for their information, investigation, and protection of the public health and safety. The information may also be dis-closed to appropriate Federal, State, and local agencies in the event that the information indicates a violation or potential '

violation of law and in the course of an administrative or judicial proceeding. In addition, this information may be trans-ferred to an appropriate Federal, State, or local agency to the extent relevant and necessary for an NRC decision or to an appropriate Federal agency to the extent relevant and necessary for that agency's decision about you.

4. WHETHER DISCLOSURE IS MANDATORY OR VOLUNTARY AND EFFECT ON INDIVIDUAL OF NOT PROVID-ING INFORMATION: Disclosure of the requested information is voluntary. If the requested information is not furn.

ished, however, the application for radioactive material license, or amendment thereof, will not be processed. A request

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that information be held from public inspection must be in accordance with the provisions of 10 CFR 2.790. Withhold-ing from public inspection shall not affect the right, if any, of persons properly and directly concerned need to inspect the document.

5. SYSTEM MANAGER (S) AND ADDRESS: U.S. Nuclear Regulatory Commission Director, Division of Fuel Cycle and Material Safety -

Of fice of Nuclear Material Safety and Safeguards Washington, D.C. 20555 NRC FORM 313

._-___- --__-__-______-_____-_-_ w

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'c Application for Renewal of Special Nuclear Material License (License No. SNM-1020)

To U.S. ' Nuclear Regulatory Commision Region 1, Nuclear Material Section B 631 Park Avenue King of Prussia, Pennsylvania 19406 Massachusetts College of Pharmacy and Allied Health Sciences (MCP/AHS) 179 Longwood Avenue Boston, Massachusetts- 02115 No control or ownership is exercised over the applicant by any alien, foreign corporation, or foreign government.

Principal Administration Officers:

Louis P. Jeffrey, President Citizenship, U.S.

Massachusetts College of Pharmacy and Allied Health Sciences 179 Longwood Avenue Boston, MA 02115 Benjamin R. Hershenson, Acting Dean Massachusetts College of Pharmacy and Allied Health Sciences 179 Longwood Avenue Boston, MA 02115 Person in charge of Radioisotopes Laboratory:

i George Matelli, Radiation Safety Officer and Coordinator of Radiological Sciences Programs Citizenship, U.S.

Massachusetts College of Pharmacy and Allied Health Sciences 179 Longwood Avenue Boston, MA 02115 l

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Activities to be performed:

The main objective of thg radioisotopes program at the Massachusetts College of Pharmacy is the education of undergraduate and graduate students in the technique of handling, counting, and preparation of radioactive elements and compounds, with particular emphasis on medical and pharmaceutical applications.

The neutron facility is used as an educational tool to familiarize students with the properties of neutrons.

The experiments performed with the neutron facility consist of activation of elements and compounds (e.g. Mn, KI, AgI, Au foils) for the determination of half-life and for scintillation spectrometry with a multichannel analyzer.

All irradiations of samples are performed with the neutron source in the central hole of its storage container.

All experiments are performed in one of three laboratory rooms, below ground level, which constitute the radioisotopes laboratory at the Massachusetts College of Pharmacy.

3.

Specifications of Special Nuclear Material-No. of Sources; One (1)

Isotope:

Pu-Be T o na:

Sealed Activity:

2 Ci Mass:

32 grams Manufacturer:

NUMEC, Apollo, Pennsylvania Model No..

Numec C Source description please see brochure (. attachment 1) 4 Technical Qua li fi ca ti o ns-o.f-Pe rs o nnel :

See attachment 2 5.

Description of Equipment, Facilities, and Instrumentation:

A.

Type and length of handling devices:

A 30" long source lif ting tool with a permanent magnet is used for handling the 2 Ci source of Pu-Be and a 171" long plexi-3 glas sample container removal tool is used for the positioning of materials to be irradiated Lper brochure).

B.

Description of Storage Container:

The source is'used and stored at all times in the NUMEC Neutron.

PAC: I rra di a to r-Howi tz e r, Model 7000.

The dimensions of this model are: 35" H.

X 22" diam., and it is paraffin moderated.

See attached brochure for physical arrangement.

It is equipped with lock and key.

The 2-curie source is kept in the howitzer l

at all times and is removed only during leak-testing pro-cedures.

NUMEC indicates that the dose rate at the surf ace of the howitzer is less than 2 mrem per hour for a 2-curie Pu-Be source in the central position.

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L., C.. Description of. Physical: Plant, Laboratory, and' Working Area = Facilities:

Three basement: laboratories, each of. an average size-of 20' feet by. 25 feet house the radioisotopes' equipment,;which includes 8 complete GM counters including: scalers,

. 3 ratemeters, 3 manual gama ray spectrometers,.1 liquid ' scintillation spectrometer, 2: multichannel analyzers. 2. GM monitors, various beta-gama survey meters, -1 '.' cutie-pie.", and miscellaneous other equipment and accessories used in laboratories uti,

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.lizing radioisotopesttechniques, including fumeLhood:and storage facility.1A..

' diagram of the central laboratory (the storage and preparation room) is' attached

(Attachment 3).

. D.

Radiation Detection Instruments to be used:

for surveying:

1..Victoreen 444 ionization chamber survey meter for alpha beta, gamma and X-rays.

Window-thickness.1.5 mg/cm2

~ Ranges 3-300 mR/hr

2.

Victoreen 493 alpha, beta, gamma portable GM surveymeter.

Window thickness 1.3-2 mg/cm2 Ranges-0-300, 0-3000, 0-30000 cpm.

for; monitoring:

3.

Nuclear-Chicago Model 1613 A Classmaster G-M' alpha, beta, gamma ratemeter la'b-oratory monitor, ranges:

0-1500, 0-15K cpm.

-4.

Atomic Accessories Model RM-36B G-M alpha, beta, gamma ratemeter laboratory monitor, ranges:

0-50, 0-500, 0-5K, 0-50K cpm.

'for assayinS:

5.

Packard Tri-Carb Model 3320 liquid scintillation spectrometer.

6.

Capintec CRC-4 radioisotope calibrator, ranges:

0-200 uCi, 0-2 mci,.0-20 mci, 0-200 mci, 0-2 Ci, 0-20 Ci.

7.

Baird Atomic Model 530 single channel spectrometer with Nel (T1) well detector.

9 8.

G-M Counters for low level alpha, beta, gamma.. Window thickness 1.5 mg/cm'.

9.

Trator NortheruModel TN-1705 pulse height analyzer,1024 channels.

In addition to the above, a supplementary sheet of instrumentation available for use through Harvard University, is enclosed (attachement 4).

E.

Instrument Calibration Procedures:

All instrument calibrations are performed by the Radiation Safety Officer, Dr. George Mate 11i.

Calibrations are perfomed every six months, prior to the assay of-' leak-test and contamination samples, and as part of laboratory exercises in the Radiation Physics and Radiopharmaceutics courses.

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, The Victoreen 444 ion'ilation chamber survey meter is calibrated with a Co-60 point source:

Supplier:

NEN Corporation Catalog No:

400 H Activity:

1 m Ci on 4/75 Calibration:

gamma dose rate at 1 m

+

't, NBS traceable The source is normally housed in a padlocked spherical shield,16.5 cm in diameter and weighing approximately 27 kg.

During calibration a handling rod is used to lift the source out of its shield.

A ring stand and clamp arrangement allows the source to be held in air a measured distance from the center of the ionization chamber.

The calibration is performed at source - chamber distances of 50 cm and 70 cm.

The Capintec CRC-4 Radioisotope Calibrator is calibrated with the NEN Co-60 source described above and with a capintec Cs-137 reference source.

Information on this source is provided in attachment 5.

The calibration procedure, using the above sources, is described in the brochure (Attachment 6).

Calibration checks on the Victoreen 493 portable GM survey meter are performed with a built-in aranium check source.

The GM counters used in the assay of leak-test and contamination samples are cal-ibrated with Cl-36 and Tc-99 reference sources.

Information on these sources is provided in attachement 7.

The reference sources are counted with fixed geometry in a shielded sample hcider.

The sources are counted for five minutes and the readings are converted to count rates in cpm and compared to the disintegration rate in dp m to obtain the counting efficiency.

6.

Description of Procedures to Protect Health and Minimize Danger:

A.

The howitzer and source are kept in the radioisotopes laboratories at the Massachusetts College of Pharmacy.

The laboratories are kept locked when not in use.

The howitzer is also kept locked when noTin use.

Handling of the source is performed only by Dr. Matelli, Radiation Safety Officer and Director of the laboratories.

B.

Film badges, (including lapel and wrist badges) and finger rings are supplied through Harvard University and are processed, evaluated and subsequent action taken (if necessary) by their heelth physics staff.

l C.

The laboratory, areas including the benches sinks, refrigerators, and hoods are j surveyed routinely on a monthly basis and immediately after any laboratory.

procedur?.The surveys consist of not only physical evaluations including meter reading and wipe tests, but any evaluation of the entire handling of the laboratory.

No contamination is acceptable which means that it is realized

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that instances will occur in which contamination will be detected but it must j

be decontaminated immediately upon notification.

Survey records are maintained j both at Harvard and the Massachusetts Colleg'e of Pharmacy on a permanent basis.

D.

All short-lived emitters will be stored for appropriate decay and released to the normal waste only af ter a comprehensive survey with the appropriate survey l

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meter.

Otherwise, all long-lived waste will be disposed via the sewerage system in accord with 10-CFR-20, 20.303.

E.

Wipe tests on the Pu-Be source are performed every six months k

by members of the Department of Environmental Health and Safety of Harvard University. Leak-test records are main-tained both at Harvard and the Massachusetts College of Phar-macy on a permanent basis.

l F.

Copies of the Radiation Safety Instructions and emergency pro-I cedures in effect in the radioisotopes laboratories are attached

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l (Attachment 8).

G.

Training program - Our training program consists of formal courses in Radiation Physics, radiation biology, and radiopharmaceuticals.

Information on these courses will be found on the enclosed syllabi (Attachment 9).

In addition, the Department of Environmental Health at Harvard University presents a course including an indoctrination for technicians which is offered to any of our personnel who are

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either working with radioisotopes or contemplating working with them.

We certify that all statements made in the above application for re-newal of our Special Nuclear Material License are true and accurate.

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GeorgeMabli,Ed.D.

Coordinator Radiological Sciences Programs Radiation Safety Officer wP

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LouisP.Jeffey,phsi,ddn~t

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!$ llO Ben [aminR.Hershenson, Acting Dean Gent 21, MdP7

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BETWEEN:

C. James Holloway, Chief.

License Fee Management Branch Office of Resource Management

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John E. Glenn, Chief ky /po Nuclear. Materials Safety,& Safeguards Section B Division of Radiation Safety and Safeguards g /'f 7 LICENSE FEE TRANSMITTAL A.

REGION ~

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APPLICATION ATTACHED Applicant / Licensee:

Massachnent+e eni,._ -c nu_

Allied Health Sciences Application Dated:

September 91. log 7 Control No.:

107871 License No.:

SNM 1020 2.

FEE ATTACHED Amount:

Check No.:

' 3.

COMMENTS Signed bp Date 10/1/87 b.k0N B.

LICENSE FEE MANAGEMENT BRANCH I 24= L31Lbf11 cl 1.

Fee Category and Amount:

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Correct Fee Paid. Application may be processed for:

Amendment

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Renewal l

License I

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'4 LM Signed b/7/ 99 Date 7-REGION I FORM 213 (MARCH 1987)

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. Application fo rRenewa of Special NucleaWiaterial License (Licen'se;No.SNM-1020;-Mail _ Control No. 11286)'

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-i Radioisotopes Licensing. Branch, Division of Fuel Cycle and Material Safety m

Office of Nuclear Material Safety and-Safeguards g

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Nucl ea r' Reg ul a to ry Commi s si on h

Washington, D.C.

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Applicant; j $@ N$t I

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Massachusetts College of Pharmacy and Allied Health Sciences (MCP/AHS)

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4 Boston, Massachusetts 02115 No control or ownership is exercised over the applicant by any alien, foreign corporation, or foreign government.

_Pri ncipal Admi nis tra tive Officers :

Raymond.A. Gosselin, President jf.,

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Citizenship, U.S.

Massachusetts College of Pharmacy

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179 Longwood Avenue 7 / SEP Boston, MA 02115 2

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" C0 Sumner M.

Robinson, Dean o

O Ci ti z ens hi p, U.S.

Massachusetts College of Pharmacy 4 m;;O""' =

O gol n #g and Allied Health Sciences i

179 Longwood Avenue Boston, MA 02115 Person in charge of Radioisotopes Laboratory:

George Matelli, Radiation Safety Officer and Coordinator of Radiological Sciences Programs Citizenship, U.S.

Massachusetts College of Pharmacy and Allied Health Sciences 179 Longwood Avenue Boston MA 02115 g Q.2 7 l~._____________

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2.* Activities to be performed:

The main objective of the radioisotopes program at the Massachusetts College of Pharmacy is the education of undergraduate and graduate students in the technique of handling, counting, and preparation of radioactive elements and compounds, with particular emphasis on medical and pharmaceutical applications.

The neutron facility is used as an educational tool to familiarize students with the properties of neutrons.

The experiments performed with the neutron facility consist of activation of elements and compounds (e.g. Mn, K1, Agl, Au foils) for the determination of half-life and for scintillation spec trometry wi th a mul tichannel analyzer.

All irradiations of samples are performed with the neutron source in the central hole of its s torage container.

All experiments are performed in one of three laboratory rooms, below ground level, which constitute the radioisotopes labora tory at the Massachusetts College of Pharmacy.

3.

Specifications of Special Nuclear Material:

No. of Sources; One (1)

Isotope:

Pu-Be Form:

Sealed Activity:

2 Ci Mass:

32 grams Manufacturer:

NUMEC, Apollo, Pennsylvania Model No.:

Numet C Source description please see brochure (attachment 1) 4.

Technical Qualifications of Personnel See attachment 2 5.

Description of Equipment, Facilities, and Instrumentation:

i A.

Type and length of handling devices:

A 30" long source lifting tool with a permanent magnet is used for handling the 2 Ci source of Pu-Be and a 17h" long plexi-glas sample container removal tool is used for the positioning of materials to be irradiated (per brochure).

i B.

Description of Storage Container; The source is used and stored at all times in the NUMEC Neutron

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PAC: I rra di a to r-Howi tz e r, Model 7000.

The dimensions of this model are: 35" H.

X 22" diam., and it is paraffin moderated.

See attached brochure for physical arrangement.

It is equipped with lock and key.

The 2-curie source is kept in the howitzer at all times and is removed only during leak-testing pro-cedures.

NUMEC indicates that the dose rate at the surface of the howitzer is less than 2 mrem per hour for a 2-curie Pu-Be source in the central cosition.

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C.,

Description of Physical Plant, Laboratory, and Working Area Facilities:

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Three basement laboratories, each of an average size of 20 feet by 25 feet house the radioisotopes equipment, which includes 8 complete GM counters including scalers, 3 ratemeters, 3 manual gama ray spectrometers,1 liquid scintillation spectrometer, 1

2 multichannel analyzers, 2 GM monitors, varioJs beta-gama survey meters, l " Cutie-pie", and miscellaneous other equipment and accessories used in laboratories uti-l lizing radioisotopes techniques, including fume hood and storage facility.

A diagram of the central laboratory (the storage and preparation room) is attached (Attachment 3).

D.

Radiation Detection Instruments to be used:

for surveying:

1.

Victoreen 444 ionization chamber survey meter for alpha beta, gamma and x-rays.

Window thickness 1.5 mg/cm2 Ranges 3-300 mR/hr 2.

Victoreen 493 alpha, beta, gamma portable GM surveymeter.

Window thickness 1.3-2 mg/cm2 Ranges 0-300, 0-3000, 0-30000 cpm.

for monitoring:

3.

Nuclear-Chicago Model 1613 A Classmaster G-M alpha, beta, gamma ratemeter lab-oratory monitor, ranges:

0-1500, 0-15K cpm.

4.

Atomic Accessories Model RM-36B G-M alpha, beta, gamma ratemeter laboratory monitor, ranges:

0-50, 0-500, 0-5K, 0-50K cpm.

for assaying:

5.

Packard Tri-Carb Model 3320 liquid scintillation spectrometer.

6.

Capintec CRC-4 radioisotope calibrator, ranges:

0-200 uCi, 0-2 mci, 0-20 mci, 0-200 mci, 0-1 Ci, 0-20 Ci.

7.

Baird Atomic Model 530 single channel spectrometer with Nal (Tl) well detector.

2 8.

G-M Counters for low level alpha, beta, gamma.

Window thickness 1.5 mg/cm,

9.

Tracor NortheruModel TN-1705 pulse height analyzer,1024 channels.

In addition to the above, a supplementary sheet of instrumentation available for use through Llarvard University, is enclosed (attachement 4).

E.

Instrument Calibration Procedures:

All instrument calibrations are performed by the Radiation Safety Officer, Dr. George Matelli.

Calibrations are performed every six months, prior to the assay of leak-test and contamination samples, and as part of laboratory exercises in the Radiation Physics and Radiopharmaceutics courses.

]

-4 h-The'Victoreen 444 ionization chamber survey meter is calibrated with a Co-60

-i point source:

Supplier:

NEN Corporation e,

Catalog No: 400 H Activity:

1-m Ci on 4/75 Calibration:

gamma dose rate 'at 1 m

+ 3%, NBS traceable The source.is normally housed in a padlocked spherical shield,16.5 cm in diameter and weighing approximately 27 kg.

During calibration a handling rod is used to lift the source out of its shield.

A ring stand and clamp arrangement allows the source to be held in air a measured distance from the center of the ionization chamber.

The calibration is performed at source - chamber distances of 50 cm and 70 cm.

The Capintec CRC-4 Radioisotope Calibrator is calibrated 'with the NEN Co-60 source described above and with a capintec Cs-137 reference source.

Information on this source is provided in attachment 5.

The calibration procedure, using the above sources, is described in the brochure (Attachment 6).

Calibration checks on the Victcreen 493 portable GM survey meter are performed with a built-in uranium check source.

The GM counters used in the assay of leak-test and contamination samples are cal-ibrated with Cl-36 and Tc-99 reference sources.

Information on these sources is provided in attachement 7.

The reference sources e.re counted with fixed geometry in a shielded sample holder.

The sources are counted for five minutes and the readings are converted to count rates in cpm and compared to the disintegration rate in dpm to obtain the counting efficiency.

6.

Description of Procedures to Protect Health and Minimize Danaer:

A.

The howitzer and source are kept in the radioisotopes laboratories at the Massachusetts College of Pharmacy.

The laboratories are kept locked when not in use.

The howitzer is 61so kept locked when noTin use.

Handling of the source is performed only by Dr. Matelli, Radiation Safety Officer and Director of the laboratories.

B.

Film badges, (including lapel and wrist badges) and finger rings are supplied through Harvard University and are processed, evaluated, and subsequent action taken (if necessary) by their health physics staff.

C.

The laboratory areas including the benches, sinks, refrigerators, and hoods are surveyed routinely on a monthly basis and immediately after any laboratory procedure.The surveys consist of not only physical evaluations including meter reading and wipe tests, but any evaluation of the entire handling of the laboratory.

No contamination is acceptable which mcans that it is realized that instances will occur in which contamination will be detected but it must be decontaminated immediately upon notification.

Survey records are maintained both at Harvard and the Massachusetts College of Pharmacy on a permanent basis.

D.

All short-lived emitters will be stored for appropriate decay and released to the normal waste only af ter a comprehensive survey with the appropriate survey

h

- 5.-

c I-i.

meter.4 Otherwise, all long-lived waste.will be disposed via the sewerage system.in accord 1with'10-CFR-20, 20.

303 or.by transfer to Interex Company

-which has'a commercial license for. waste disposal.

E.

Wioe tests on the Pu-Be: source are performed every six months by members of the' Department of Environmental Health and Safety of Harvard University.

Leak-test records are maintained both at. Harvard and 'the Massachusetts. College of Pharmacy on a permanent basis.

.F.

. Copies. of the Radiation Safety Instructions and emergency procedures inf effect

'in the. radioisotopes laboratories.are attached'(Attachment 8).

G.

Training program - Our training program consists of formal courses in Radiation Physics, radiation biology, and radiopharmaceuticals.

Information on these courses will be.found on - the er. closed syllabi. ( Attachment.9).

I

.In addition, the Department of Environmental Halth at. Harvard Universityf presents a course including an indoctrination for technicians which is offered' to any -

[

of _ our~ personnel who are either working with radioisotopes or contemplating

-. working with them.

. e' certify that all statements made in the above application for renewal of cor' W

Special Nuclear ~ Material-License are true and accurate.

YE GMgeMatbli,Ed.D.

Coordinator Radiological Sciences Programs Radiation Safety Officer RahondA. Gosselin, President-l7?1 SAnL Sumner M. Robinson, Dean 0cc:e7dEY '??V N f {

/

Date

Neutron-P

.AttachmeO

inragtg, itzer o

NI I M *- ' i e

The Neutron-Pac 6 is an unusually versatile neutron irradiator howitzer that permits a wide range of ex-periments in the fields of chemistry, physics, biology and metallurgy.

O O

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Neutron-Pac' Irradiator-Howitzer O

Unique Capabilities and Features High-efficiency thermal neutron flux in a reproducible geometry y

Simultaneous thermal neutron irradiations in up to k

/j six reproducible positions

[

Thermal or fast neutron irradiations of small animals L

infinitely variable geometry for thermal neutron Y-irradiation in liquid

/

Fast and thermal neutron beams for irradiation and l

attenuation experiments J

l Safety at high neutron fluxes l

s

[y

/

Portability

' 1 Versatility to perform a wide range of experiments N

Self-contained shielding to safe biological levels during operation or permanent storage of the sources k

Economical neutron experiments and instruction j '

Model 7000 Instructor oriented experiment manual

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" Activation Analysis,- Quantitative and Qualitative -

7000 Foil Sample Container Spacers.

.' Isotopic' Analysis by Absorptiometry 7000-90

. Animal Cage

.j Production of Short Lived Isotopes 7000-01 Boric Acid'(enriche'd to approx. 92%)

- (l'28, Mn55, P32, Ag'08, V52 lnJ'5, Ir'82, Re'88, l

i 1

several rare earths, and others)

' Standard NUMEC Neutron Sources 1

isotope Dilution Technique-

' C'Pu cri.nnero -

- {

  • t t 'o""a

cur,es voe.i 4enom Physical Chemistry Studies (solubilities, electrode Stren219 (N SI go) reactions, etc.)-

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NuMcc-AM 3t 3A c 575

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NuMEC AM 93 3A 0 87o.

2.3 s 1ot 4

NuMEc-AM-123-3A t.020 84mtoe Irradiation of Biolohical Specimens including Small 5

NuMEC AM 154 3A :

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Animals, Plants and Seeds. '

s NuMec-AM tas-3A t320

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Translocation of l'85 and MOS in Animals and Plants I

epu seurce camerers.. v.ato inenes Radioactive Decay and Statistics j

Activat, ion Foils.

Radioactive Equilibrium yol"'a,a,L /:".,,'A, ouantar u ier.ai -

in.utron Pac and Accessories uocei roco-oi 12 each sa. r psi e

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$!CIEu, 7000-92 Stainless Steel Work Tray

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Experiment Wellinsert Assemblies C# ~

s Fod Forcets 7000 50 Full Aluminum Clad Asphalt uooenooc-eta E cu e st.or;al Same as the 7000 01 hit oncept f*st osameter is %"

7000-51 Split Aluminum Clad Asphalt (upper) roa kit

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7000-52 Split Aluminum Clad Asphalt (lower)

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O Liquid Tanks g,,ct,",','l a'l, g*;",*,'g",c,;*,',;,,cy,er m i rn, io.ccommo.

7000-60

- Stainless Steel DISTRIBUTOR 7000-61 Aluminum 7000-62 Cadmium Liner for 7000-60 or 7000-61 liquid tank 7000-70 Liquid Experiment System l

7000-80 Source Lif ting Tool h

Plixiglass Parts and Spacers 7000-81 Foil Sample Container 7000 82-Magnetic Source Plugs

'7000-83 Magnetic Source Spacers a

7000-84 Foil Sample Container Removal Tool l

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Nucliar Materials and Equipment Corporation. Apollo, Pennsylvania 15613 + Phone 412/472 8411 e Twx 510/467 5781 + Cable NuMEC b

l l

M_1________

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9 3ection 4 ATTACHMENT 2 l4 f

Technical Qualifications of Personnel George Matelli 40 Squire Road

.Winchester, MA Home: (617) 729-7467 Work: (617) 732-2933 Education:

Ed.D.

- 1980 - Boston University, Department of Education Media Technology. Dissertation: Assessment of Teaching Effec-tiveness of the Massachusetts College of Pharmacy and Allied Health Sciences Externship Program.

Advisor: Dr. Gerald F.

McVey M.S.

Eng.

- 1970 - Northeastern University, Department of Electrical Engineering.

M.S.

- 1965 - Boston College, Department of Physics.

T hesi g r:ys {my sDependent Polarization Effect in YF3 Doped T

CaFp a

Advisors: Dr. Francis MacCaffrey B.S.

- 1963 - Tufts University, Department of Physics.

Special Programs:

NSF

- 1968 - Summer Institute in Nuclear Engineering, North Carolina State University.

1969 - Special Summer Institute in Quantum Physics, San NSF Diego State College.

MIT

- 1971 - Summer Program in Physical Aspects of Nuclear Medicine.

MIT

- 1974 - Summer Program in Biomedical Physics and Bio-materials Science IAEA 1977 - Summer Institute in Radiopharmacy, Universi ty of Southern California.

Work Experience:

i MCP/AHS

- 1981 - Associate Professor of Physics and Coordinator of R a d i o ~l o g i c a l Sciences Programs.

MCP/AHS

- 1965 to 1980 Assistant professor of Physics and Chair-man De'partment of Math and Physics (since 1974)

h1 g

4 2-x f

L>R MasstGeneral Hospital:

1971-to~1974

.-Research.Fel-low in Radio -

L l ogi cal physi cs' i n ' Ra.dio Togy: (part time).

Handled =

L gram quantities > ofx Ra.226,Lperformed? radiation. pro-H tection surveysuof radiographic, fluoroscopic-and.

p gamma-ray.-(Co-60) therapy units.

.Research Projects:

Investigation of time dependentfpolarization effect in CaF crystals-doped with YF3 under an Air Force 2

funded research grant. ' Boston College 1965 (M'.SSthesis).

Quantitative ' evaluation of brain scans;using.a Nuclear Chicago 4096 computer.

Ma s s: General Hos pi tali,1972.

Investigation of~ Skeletal DYnamicsiusing-99mTc HEDSPA in conjunction-with Scintillation camera and: CDS-4096 Multichannel Analyzer with F.Castronovo.

LR..Callahan, M. Potgaid, and.H. Pendergrass,TMass.

Gener:al Hospi tal,1973.

Computer ev'aluati.on of bone scans with Dr. Frank =

Ca s tronovo, Ma s s General Hos pi tal', '19.74.

Measurement of x-ray. transmission through building, materials with Dr. Edward W. Webster,JMass General Hospital,.1975.

.Measuremerit of rate dependance of ionization chamber survey meter, Mass-General Hospital,.'1975.

Publication and Manuscripts:

"The Pho/ Gamma Scintillation Camera", MGH, 1975.

Laboratory Manual for Radiation Physics Course,.MCP,1975.-

Developed laboratory protocols for x-ray physics course, Harva-d School for Public Health, 1974 Developed protocols for the radiation protection surveys of Radiographic, Fluoroscopic, Therapy -X-Ray and gamma'-ray beam units (Co-60, Cs-137), MGH 1973.

Professional Societies:

Health Physics Society Society of Nuclear Medicine American Association of Physicists in Medicine American Association of Colleges of Pharmacy Rho Chi Honor Society Phi Delta Chi Pharmaceutical Fraternity

._--____--_-_-__i-_________o

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P - Removable wood partition l(6'. high)

, C{.. Wood' cabinet' with'.forinica top.

C7-Filing Cabinets ST uStorage-area ofL4" cement blocks to a height of 6-feet

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' ATTACHMEtlT '4 ADDITIONAL INSTR ENTS AVAILABLE FROM ENVIRONMEt L HEALTH & SAFETY OF HARVARD UNIVERSITY Section: SD N Radiation Detection Instruments a.

For contamination i

2 GM Counter 1.4 mg/cm end window Gm tube detects alpha particles above 1.9 MEV beta, gamma.

Picker Cliniscaler !600-150 with precision discriminator.

Liquid Scintillation.

Spectrometer Packard Tri-Carb with 3 channels b.

Low level' GM survey instruments Picker Labmonitor 600-081 2

End window geiger tube 1.4 mg/cm for alpha, beta, gamma Ranges (5) 300-30,000 c/m Contains battery pack for portable use in field.

c.

Neutron survey instrument Fairport Instruments Inc.

Model 420 Fast Neutron Dosimeter (tissue euqivalent) 1 Victoreen 488A Detector proton recoil' proportional counter Ranges 0-25, 0-250, 0-2500 mrem /hr.

d.

Tritium monitor Texas Nuclear Instrument Co.

Model 9160 "snif{er" tritium monitor

^

3 Range 100 uc T.m air to 100,000 uc T/m air e.

Air sampling equipment The Staplex Company Model TF-la Hi-Vol Air Sampler Flow rate 20 CFM with TFA #41 filter of 4 inches diameter.

f.

8 Eberline E-120 GM survey meters with thin end window probe and audible speaker 0-50 mr/hr 1 Victoreen Thyac with thin end window probes and audible speaker 0-200 mr/hr 2 Victoreen 440 survey meters - ionization chambers 300 mr/hr.

1 Victoreen 440RF survey meter -

1 Eberline PAC 4A with alpha probe model AC-21 and tritium probe model 1 Nuclear fieasurements PCC10-A Ser.673 Proportional Counter Converter (with windowless flow counter) 1 Baird Atomic Scintillation Detector Model 810 using zns phosphor alpha detector 1 Iluclear Chicago Model 2592 Exposure Ratemeter with Model 2593 ion chamber 0-10 E-A N = ^"

y..

77 ATTACHt1ENT 5

/^s

'

'd

. c Cs-137.

Page,1 of 2 i

CESIUM-137 Y

SERIAL 0 #lC/ ~/ /C ~ Y A - /]

I j

The activity'of the source was C

L ill V microcuries ( 4 / 7 We s-1) 1 3.8%*,

1 l.'

on we l

, 1978.

The half-life of Cs-137 has been determined to be 30 years 0.2 years.

i i

DESCRIPTION OF SOURCE The activity is uniformly distributed throughout approximately 20 milliliters of epoxy resin in a 27 milliliter multi-dose plastic vial.

METHOD OF CALIBRATION The source was calibrated by direct comparison with a source certified by the National Bureau of Standards.

The calibration was performed using a Capintec Radioisotope Calibrator.

MEANING OF CALIBRATION 4

The source was intercompared with a standard source consisting of a 5 mi solution in a borosilicate ampoule and no corrections were made for the difference in source configuration.

The re fo re.

if approximately 5 ml of solution of the stated activity is placed in a 5 ml ampoule, i.e., if an SRM from NBS is placed in the calib ra t or, the correct reading will be obtained.

The source therefore, simulates an SRM f rom NBS.

This simulator is only valid for a Capintec Radioisotope Calibrator.

- ~ ~ -. - - - - - _ - _. _ - - - _. - - - - -. - _ _ _ _ _ -. -

D f).

(J

..fw Cs-137 Pagt 2 of 2 l

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CESIUM-137 PRINCIPAL RADIATIONS This Cs-137 source is actually Cs-137 and Ba-137 in equilibrium.

TYPE ENERGY (kev)'

INTENSITY (%)

u.

. K x-ray 32.9 7.03 Y1 661.6 85.05

  • ERRORS 1.

Uncertainty (99% confidence level) tl.5%

(This is the error with respect to the standard source.)

2.

Uncertainty of the activity of the standard source 12.3%

3.

Overall Uncertainty

!3.8%

4.

Accuracy as a function of time Due to the measured error in the half-life, the accuracy of the activity of the source decreases by 0.015% per year.

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ATTACHMEilT 6 J.:

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Section SE

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m OWM Performance Monitoring of Your Calibrator Capintec recommends that a performance check be made on your Calibrator, on a routine basis, to verify continued correct operation of the entire system, including: Ionization Chamber, Bias Supply Battery, Electrometer and Digital Readout. The check consists of-1.

Monthly Calibration checks using at least three radionuclides standards covering low, medium, and high energies Log and compare results to previous measurements. Capintec Reference Standards Set, Model CR-486E, is recommended for this purpose. See paragraphs 1 through 5 of Calibration Check Procedures (pages 5,6)

CR-486E Reference Standard Set Activity Accuracy

" Cobalt 1 mci

4.5%
3.5%

"' Cesium 100u Ci t3.3%

2. Monthly Calibration checks on all routinely used activity ranges should.

be made.See Paragraph 5of Calibration Check Procetture for details (page 5).

3. Dally Calibration checks with at least one long lived radionuclides standard (e 9. "'Cs). Capintec Standard Model CR-154E is recommended. The result :

should be logged and compared to previous results. See paragraph 6 of :

Calibration Check Procedures (page 6).

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. Standard Reference Sources CHECKING YOUR CALIBRATOR If your department has a set of reference calibration sources (e g Capintec-Model CR-486E), a calibration check can be performed on your caliorator to venty the condition of the ionization Chamber, Bias Supply Battery, Elec-trometer and Digital Readout. We have listed the specifications for the Capintec CR-486E in paragraph 2 of " Performance Monitoring of Your C alibra tor."

CALIBRATION CHECK PROCEDURE

1. Verify that the Dose Calibrator is zeroed properly. (See Calibrator owners manual for details)
2. Verify that the Dose Calibrator has been properly adjusted to offset the

~

effect of background radiation. (See Calibrator owners manual for details)

' 3.

Set the Calibration dial for "Co to 990. Insert a "Co reference source

~( 100uCi). Verify that the reading is within the accuracy limitation set by calibrator and source. The uncertainty of the source should be :5% or less.

4.

Set the calibrator dial for "Co to 112. Insert a "Co source (~1 mci).

Vorify that the reading is within the accuracy limitation of calibrator and source. The uncertainty of the source should be 15e.s or less.

IF THE RESULTS OF STEP (3) AND (4) ARE WITHIN THE PRESCRIGED LIMITS, YOUR CAllBRATOR IS CHECKED AND THIS DATA SHOULD BE LOGGED IN A PERMANENT RECORD. IF NOT, CONTACT YOUR CAPINTEC SERVICE CENTER (412-781-5300) FOR INSTRUCTIONS.

5.

To check the accuracy of the calsb*ator at its upper ranges and to verify that the internal bias supply battery is operating properly the foilowing

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F (a) Measure the activity of a whole vial containing high activity (e.g. out.

put from a "mTc generator). Ascertain the volume of the. activity.

measured.

Extract a sample fraction of known volume from the whole vial.

(b)

(c) Measure the activity of the extracted sample and compare the results with the measured reading of the whole vial.The ratio of the ac-tivities should be in the same ratio as the volumes. The accuracy of this measurement is a function of calibrator accuracy and volume measurement. With reasonable care in drawing-up the volumes, a total uncertainty of t10% is possible. The results should be entered into your log book.

LE'R AN CE, IF THE RESULTS OF THIS LINEARITY CHECK ARE OUT OF T CONTACT YOUR CAPINTEC SERVICE CENTER (412-781 INSTRUCTIONS.

6. A consistency check should be performed on a daily basis:

Verify that the Dose Calibrator is zeroed properly. (See Calibtator (a) owners manual for details).

Verify that the Dose Calibrator has been properly adjusted to offset -

(b) the effect of background radiation. (See Cahbrator owners manual for details).

(c) Set the calibration dial for"'Cs to 220. Insert a"'Cs sour Ci), Verify that the reading is within the accuracy limitation of cahbrator and standard The results should be recorded and compared to previous o or less.

readings. The uncertainty of the source should be :Sc IF THE RECORDED RESULTS DEMONSTRATE A TREND GREATER INACCURACY. CONT ACT YOUR CAPINTE (412 761 5300) FOR INSTRUCTIONS.

l w---___-______________-___-

i

S'ection ' 5E.

,m.

,rx (j

ATTACHMENT-7

()

c h.

CERTIFICATE OF RADIOACTIVITY CALIBRATION Chlorine-36 Peferenca Source f;ES-2GG Hal f-Life :

3.0 x 10S y Lot t' umber: o f.74.oo f The activity of Chlorine-35 was found to be, Augosf 1973

0. 0 90 2 wcrocuri e m

DESCRIPTION OF THE SOURCE The activity was deposited between two approximately 1 mg/cm2 aluminized mylar films sealed to an aluminum ring with a 24 mm outer diameter.

The source is housed in an aluminum holder which is 10 mm in height and 32 mm in diameter.

_I'E..TiiOD OF CALIBRATION An aliquot was taken of a solution calibrated by liquid scintillation counting.

The counting efficiency was determined using standards based on fiational Cureau of Standards assays.

I."P U.? ! TI ES Less than li, of Sulfur-35 cccording to manufacturer specifications.

EP.RCR5 r.

Random Errors (3 times the standard deviation)

Precision of the NSI measurement 2.5L Systematic Errors a.

Estimated naximum error in efficiency determination

0.5%

b.

trror in p1 petting t 0.2%

l Overa]l Error j

i 2.5

+

0.5

+

0.2

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($ New England Nuclear 575 Albany Street, Boston. Mass. 02118 j

CUSTOMER SERVICE: (617) 482-9595 U_--_-------_----_------__----_---

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I 3

CERTIFICATE OF L

RADIOACTIVITY CALIBRATION Technetium-99 P.eference Source NES-250 Hal f-Li fe:

2.1 x 105 y Lot.flumber: o/- 74-oo/

The activity of Technetium-99 was 'found to be, 0.0 37 rnicrocurie in Apr,/ /973 DESCRIPTION OF THE SOURCE The activity was deposited between two approximately 1 mg/cm2 aluminized mylar films sealed to an aluminum ring with a 24 m outer diameter. The source is housed in an aluminum holder which is 10 mm in height and 32 mm in diameter.

METHOD OF CALIBRATION An aliquot was taken of a solution calibrated by liquid scintilla tion.ccunting.

The countina efficiency was deternined using standards based on National Bureau of Standards assays.

Ii!PURITTES Less than 1% according to isotoce manufacturer specifications.

ERRORS

-Random Errors (3 times the standard deviation)

Precision of the ilEtl measurement 2.5%

Systematic Errors, a.

Estinated maximum error in efficiency determination 1 0.5%

b.

Error in pipetting 0.2%

Overall Error 2.5

+

0.5

+

0.2 3.7%

=

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h New England Nuclear 575 Albany Street, Boston. Mass. 02118 CUSTOMER SERVICE: (617) 482-9595 l

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' Section ~ 6F-.-

m ATTACHEMENT'8.

sq Regulations for' Users of' Radioactive Materials AUTHROIZATION '- No person shall bring in, use or remove from the laboratory any radioactive material without= authorization ~ from the Radiatio.n Safety.0fficer..

QUALIFICATION - No person shall be allowed to work with radioactive materials who hasLnot received adequate instruction and training in the safe preparation,. use-and disposal of radioisotopes.

All users of radioisotopes must begrei gistered with the Radiation Safety Officer.

PERFORMANCE ~

. Work with radioactive materials shall be perfonned accordingLto the~. guide:

~

lines set forth;in NBS Handbood 92, Safe Handling of.' Radioactive materials" and in. NCRP Report No. '39 Basic Radiation Protection' Criteria.

Copies of these manuals are available from the Radiation Safety Officer.

NOTIFICATION - Users of radioactive materials shall notify the~ Radiation Safety 0fficer of any case of over exposure, spill or accident involving. radioisotopes.

. Users.shall also notify the Radiation Safety Officer if any amount of'

- radioactive material is' lost or misplaced.

Safet'y Precautions to be Followed by Users of Radioactive Materials 1.

Eating, drinking, smoking and the use of cosmetics in the laboratory are not.

permitted.

2.

Pipetting is not to.be done by mouth suction.

t3.

Always wear protective clothing including gloves when handling radioactive material s.

4.

Always wear a personnel dosimeter in the laboratory.

5.

Active liquid wastes should never by poured into a standard drain. They.should be poured into labeled containers and stored for commercial disposal.

6.

Active solid wastes and contaminated materials should be placed in the designated' containers.

7.

Before leaving the laboraotry check for personal contamination using a beta-gamma survey meter.

In accordance with the provisions of the Code of Federal Regulations, Title 10, Part.19, Section 11, employees are notified that copies of the NRC By-product Materials License and amedments issued to Massachusetts College of Pharmacy the NRC regulations in 10-CFR-19 and 20 and the above mentioned handbooks are available for examination in the office of the Radiation Safety Officer Room 102, Newton Building, Massachusetts College of Pharmacy, Boston, Mass.

i

m n

[e '

Emergency Procedures 4s-A.

Spills 1.

Notify.all other persons in the room at once.

2.

If -the spill is on the skin, flush thoroughly.

3.

If the spill is on clothing,- discard outer or protective clothing at once.

4.

If the spill'is on laboratory accessories, confine the spill immediately.

Liquid spills:

Don protective gloves Drop absorbent paper on spill Dry spills:

Don protective gloves Dampen thoroughly taking care not to spread the contamination 5.

Notify the Radiation Safety Officer, Dr. G. Matelli, 2-2933 The Radiation Safety Officer may be reached when at home at 729-7467 6.

Decontaminate personnel involved.

7 Decontaminate the area.

8.

Monitor all persons involved in the cleaning.

9.

Permit no person to resume work in the area until a survey is made and aooroval of the Radiation Safety Officer is secured.

10.

Prepare a complete history of the accident for the laboratory records.

B.

Fires and other major emergencies 1.

Notify all other persons in the room and building at once.

2.

Attempt to put out fires if radiation hazard is not immediately present.

3.

Notify the fire department and the Superintendent of Buildings and Grounds, Mr. Paluzzi 2-2885.

4.

Notify the Radiation Safety Officer.

5.

Following the emergency, monitor the area and determine the protective devices necessary for safe decontamination, c

6.

Decontaminate.

7.

Permit no person to resume work without approval of Radiation Safety Officer.

8.

Monitor all persons involved in combating the emergency.

9.

Prepare a complete history of the emergency for the laboratory records.

l l

l I

-j

Section 6G

(~ ;

ATTACHMENT 9

(i 9\\

PhohosalForRevised' Course e ',

' Lecture Hours / week:

3 Elective:

yes LLaboratory Hours / week:

3 Required:

no

Credit Hours / Quarter

4 Department:

Chemistry and Physics A.

Course

Title:

Radiation Physics B.-

Course Number:

Phy 783 C.-

Admission Particulars:

By consent of the instructor.

One year of College Physics or its equivalent is required for entry into this course.

D.

Instructor:

Dr. Matelli E.,

Year (s) Offered:

Every Year F.

. Catalogue

Description:

A non-calculus presentation of the basic principles of radiation and nuclear physics.

Topica include:

radioactive decay of radionuclides, types of decay modes, artificial production of radionuclides, interaction of radiation with matter, detection and measurement of radiation, exposure, dose and principles of radiation protection.

The focus is on radionuclides useful in nuclear medicine and in biological research.

G.

Objectives:

The objectives of this course are the acquisition of know-ledge and the development of intellectual and manipulative skills that will enable students to perform specific tasks safely and ef fectively.

These tasks, given below under competencies, require knowledge and skills in the following areas :

1.

Basic aspects of atomic and nuclear structure with emphasis on composition, stability and energy states of atoms and nuclei; 2.

Characteristics of atomic and nuclear radiation processes ;

3.

Radioactive decay modes with emphasis on beta decay, electron capture and isomeric transition; H

4.

Activity and mathematics of radioactive decay; 5.

Characteristics of particulate and non-particulate radiations ;

6.

Nuclear reactions and production of radionuclides-7.

Interaction of radiation with matter for both particulate and non-particulate radiation; 8.

Radiation detectors:

G-M counters, proportional counters,

ionization chambers, scintillation detectors and their asso-ciated electronic instruments; 9.

Nuclear counting statistics; 10.

Energy selective counting and pulse-height analysis; 11.

Calculation and measurement of exposure and absorbed dose; 12.

Radiation protection practices and procedures; 13.

Government regulations pertaining to the use of radionuclides.

H.

Competencies:

At the completion of this course the students should be able to perform the following tasks:

1.

Operate nuclear instrumentation a.

G-M detectors:

1)

Plot characteristic curve and measure plateau slope.

Use measured slope to determine condition of tube; 2)

Determine optimum operating voltage for detector; 3)

Determine overall counting ef ficiency using standards ;

4)

Measure resolving time using paired-sources method.

b.

Dose calibrator (ionization chamber) :

1)

Ascertain linearity over entire range of radionuclides activity to be measured; 2)

Test accuracy for commonly used radionuclides that have adequate reference standards available; 3)

Check for constancy using a long-lived radionuclides standard.

)

f, m,'

f 1

2':.

%^ A$

ic.; ShintiNion E 'ouriters:.

-h'-

C

-1),..Carzorate.withf Cs-13 7;

m g
1. c f. g 2)).DetermineLpercent FWHM; energy 0 resolution;

.3)J Conduct s,ensitivity checks;-

4)

Perform:an' energy"linearityJcheck; E

~5)

' Identify unknown radionuclides. from; pulse-heighty Janalysis.

E d '. ; Survey Meters:

1)

Calibrate. according ' to, NRC. specifications ;,

-2 ) _ _ Select' proper surveyLmeter for~each; type andslevel'.--

of-activity.

'2.

Perform Calculations-a.

Activity and dose:.

1); Perform activityLcalculation using1 decay.' factor;-

2). Calculate. half life from' series.of: counting

. measurements;-

.s 3)

Calculate correct' volume forLa particular dose'fromL f

specific activity.

b.

Statistics of nuclear counting:

1)

Determine. standard error for counting. measurements; 2)

Determine statistical significanceJof difference 1

. between twof counting measurements ;

3)

Perform chi-square-calculation;-

' Calculation of exposure and absorbed-dose:

E

-c.

1)

Calculate exposure using specific gamma? ray constant; 2); Calculate _ absorbed dose from'known externa 1' exposure;-

3) " Calc'ulate thickness of shielding' required toireduce 1

exposure'by a given factor.

3.

Radiation: Protection and Maintenance of Radiopharmaceutical o

Laboratory _

La.

Radiation protection:

1)

Employ personnel. monitoring devices; 2)

Take appropriate measures to reduce exposures-when necessary; 3)

Keepfexposure as low as is reasonably achievable

_ ( ALARA) using appropriate orotection parameters continuously;

4) ' Select and use' proper shielding-to reduce ' radiation exposure; 5)

Use proper methods for_the storage of radioactive materials; 6)

Perform radiation protection surveys; 7)

Perform wipe tests where applicable; 8)

Perform leak tests on sealed sources _when appropriate; 9)

Perform decontamination procedures; 10)

Dispose of waste properly according to licence specifications.

b.

Maintain Radiopharmaceutical Laboratory:

1)

Maintain required records; e

2)

Initiate purchase orders for supplies of radiopharma-M ceuticals:

3)

Perform inspection on all radioactive shipments received;-

4)

Log in the receipt of' radioactive materials in a record book; l

5)

Store radioactive materials in appropriate area.

L

-1.

Text:

Sorenson and Phelps, " Physics in Nuclear Medicine' R

J.

Required Reading:

Text

_ ~. _ -

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x

( j,,

~

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Y

- LK.3 Suggested TRoading:bournal5 o'f c Nuclear ~Msdicina,h Tubis Hand Wolf,'

7, J.,

Radiopharm:cy";; Rhodes, l " Quality Control.~in. Nuclear ' Medicine" ;.

~

.. Wagner,." Principles of: Nuclear? Medicine".

^

rL.

Library andLother: assignments _=None 4Le

References:

- Same as1 suggested reading zN.J 1 Guest Lecturers: ^None Os (VisualEAids:

. Transparencies, slides' f

.P... ~ Grading;and Exams:

Midterm ? Exam' -:- 30 %

Final ExamL-30%

' Laboratory' -l 4 0 %

Q '. ; Lecture Outline

,'. 'l.. ' Ato.mic ~ and Nuclea'r ' Physics-a '. ~ Review ofiphysical quantities and' units

'b.

'Bohr theory of atomic structure c.

Shells', s ubshells ~, quantum. numbers.

c 13.

X-ray spectra Nuclear! structure, nuclear. forces, bindin~g' energy,' nuclear.

e.

stability.

f.

Isotopes, ' radioactivity

. g _..The chart'of the nuclides-2.

Properties of radionuclides a.

. Kinds of radiations 2

-b.

Units of activity, specificLactivity c.

Disintegrations schemes d..

Decay, half life,. average life

.3.

Production of' radionuclides a.

. Nuclear: Reactions

_b.

The cyclotron c.

The nuclear. reactor d.

-Radionuclides generators-4.' Measurement and Detection of' Radiation I a '.

Counting systems b.

Gas amplification, proportional. counters c.

Geiger counters, quenching, plateau

'd.

Resolving time, efficiency' 5.-

Indeterminate Errors in Measurement a.

Background

b.

Statistics c.

Standard deviation, confidence limits d.

Inverse square law e.

Comparative counting, absolute counting 6.

Interaction of Radiation with Matter I - Charged Particles a.

Range of alpha.and beta particles b.

Ionization and excitation c.

Linear energy transfer d.

Scattering, self absorption 7.

Interaction of Radiation With Matter II - Photons o

s a;

Absorption coefficient b.

Half value layer c.

Photoelectric absorption d.

Compton.effect e.

-Pair production 8.-

Measurement and Detection of Radiation II a.

Scintillation detectors b.

Photom,ultiplier tubes c.

Pulse height distribution d.

Energy resolution e.

Scalers and distriminators n

f.

Wall nunters 9

Sing 1 hannel and multi-channel (. lalyzers h.

Calibration of analyzers i.

Identification of radionuclides 9.

Exposure and Dose a.

The roentgen b.

The rad c.

The quality factor and the rem d.

The exposure rate constant e.

The ALARA concept and radiation safety f.

Maximum permissible doses R.

Laboratory Outline 1.

Sample preparation techniques.

The G-M counter 2.

Sta~istics of Radiactive Decay t

3.

Resolving Time - instrument efficiency 4.

Operating characteristics of a NaI(Tl) scintillation detector 5.

The gamma ray spectrometer and pulse height analysis I 6.

The gamma ray spectrometer and pulse hieght analysis II 7.

The multi-channel analyzer-multichannel scaling and measurement of half life 8.

Measurement of attenuation of gamma rays 9.

Calibration of personnel dosimeter and ionization chamber survey meter-radiation protection survey 10.

Calibration and quality control of dose calibrator l

l I

I l

l l

4 l

l w.

__L

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(

n PHY 784 -: Nuclear Medije Instrumentation - Class, 3 L'rs; Credit, 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />;

"~

Ope quarter John A'. Correia, Ph.D.

Lecture Outline:

Lecture l'

Introduction, Tracer Studies 2

Static and Dynamic Imaging, Examples 3

The Gamma Camera - General Considerations, Collimators 4.

The Gamma Camera - Detector System; crystal light guide, position computing network.

5.

The Gamma Camera - Pulse height' selection, resolution, sensitivity, linearity, edge effects.

Exampl es.

6.

Radionuclides Scanning devices - collimators, resolution, sensitivity,

.etc.

Comparison with stationary devices.

7.

Other imaging devices - atuogluroscope, solid state. cameras, multiwire proportional chambers 8.

Introduction to Computers - general description of. computer hardware and software 9.

Nuclear Medicine Computer systems, data acquisition, dispaly image manipulation and image processing - Examples.

10 Dynamic function studies - mathematical modelling, data analysis methods, functional imaging-11 Theoretical Discussion of Imaging Systems Sources of Image degradation, statistical effects, system response, point source response function.

modulation transfer function.

Comparison of systems.

12.

Instrument Quality control measurements, calibration procedures.

13.

Dose calibrators in the N.M. Pharmacy proerties, corrections, calibration.

l

i:' '

  • c, A

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, ; !.y

\\,_,)

a

l.ecture

'14-Well counters,. liquid scintillation counting.

'15 Concepts-of transverse section reconstruction.

Transmission and emission CT.

16.

Emission CT,(cont):

Single. photon devices. -Positron devices.

17.

~ Quantitation of transverse section a:tivity distributions.

Examples of transverse section imaging 18 Other instrumentation in nuclear medicine.

In hospital' cyclotrons, i!-

etc.

Comparison'of NM with other modalities (ECT, ultra-sound, NMR).

. 19 Tour of MGH facilities.

20 Final' Exam.

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.4 EM m,g 3. :n

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7pgv78N'R'adiationL31ogy-class,L3.0.honrs;cr'edd3 hours;-;.onelquarter n'w-x a..,

. ' '. Instructor:

Fra d P..'~CastronoVo, Jr. Ph.D.:

t F

Top 1c Chaoter Assignment

  • s L

lecture'#

4 Lt

'1 Introduction', the' Media,-

Y-f-

14L LNatural Radiation r

L 12?

- Radiation Interaction with Matter I.

L l',2 -

3:

Radiation Interaction w'ith Matter.II:

.4.

. Radiation Interaction with Matter III:

l ',2 ;

5 Dosimetry I,Definitio'ns and Measurements; 3' ' '

Lu -

46

- Radiation-Chemistry I 4

L

'7 Quiz.

8

- Radiation ChemistryLII..

4 9:

Radiation Chemistry III 5

10 Cellular Effects:1, 5',7,13

-11'.

Cellular Effects II,III

-5,7,13!

s L12 Radiosensitivity.I.

8' q.

13 Radiosensitivity II.

8 1

14'

- Quiz 15 Effects on Major. Organs I.

9-1

16-Effects'on' Major ~0rgans II

.9'

17

Acute Effects-oniWhole Body -I' 10-

=181

~. Acute Effects-on whole. Body.II

.10'

'19 Latent Effects.of Radiation.

12 21 Modification.of Injury -

11 20

~

Miscellaneous Topics--

22-

- Exam Week-1* Course Text Book - Casarett, A.P., Radiation Biology, Prenctice-Hall, Inc., Englewood Cliffs, New Jersey.

i l

+

-~#

7

-m, g^

+

30 4

4: #t. Credit,1 ' hours; _

Dr.CCall5han' "I.

Introduction-l LA.; Orientation to. Nuclear Medicine-

'l..

Internal admin'istration of ~ radioph'amaceuticals r

2.

External detection of gamma rays 3.

-Determination of size, shape,' position and-function of various :

'4" organ systems o

'4.

. Data processingi 5.

In vitro studies' l

B. ~ Role'of the Radiopharmacist in Nuclear Medicine-

'l.

Purchasing,; compounding, dispensing and_ quality control of.

radioa'ctive_ materials intended for patient use.

2.

. Development and maintenance of~ appropriate quality control proceduress including ~. chromatography, particle size determinations, filtration techniques and sterility and _ pyrogenicity testing.

3.

Health. Physics considerations-4.

Maintenance of proper-records; 5.

Selection of products used in Nuclear. Medicine
6.

Research and-teaching

~C.

Properties of anlldeal Radioph'armaceutical

-I 1.

Definitior, of problems and understanding the role of radio-pharmaceuticals in their solution q

2;

- Proper selection of the most effective radiopharmaceutical a.

physical half life b.'

biological half life c.

effective half life d.

biological distribution e.

traget to non-target ratio-f.

toxi _ city II.

Technetium - 99m A.

Physical Properties B.

Chemical Properties C.

Molybdenum - 99m - Technetium - 99m Generator Systems

-l.

Parent - daughter relationship 2.

Structure and operation

~

3.

Quality control-o 4.

Generators vs alternate sources of supply a.

" instant technetium" b,

solvent extraction 4

a--

F~,$

L('N -..,D g7

. )

Q

'kV.9=1.II. LRadiophannaceutNals Lin Diagnosis-lFor each.igrouplof. agents several; individual radiopharmaceuticals will' bo r-

. discussed i'n' detail, including aiechanism of action, method.of preparation, q'uality-control,' toxicity, cost'.and practical considerations regarding b

.their use"in-Nuclear Medicine.-

n A.

CentraliNervous System.

l'.

Brain s' canning ~ agents 2.

Cisternography agents :

B.

Respiratory System--

(

-.1.

Psrfusion' lung scanning _ agents 2e

. Ventilation:1ung scanning agents a.

radioactive gases

-b..radiocative aerosols

. C. l Hepatic and.Reticu1~ endothelial System o

1.

' Liver 1 scanning. agents a.

. colloidal agents b.

biliary-tract agents l2.

. Spleen scanning' agents-3.

Bone marrow scanning agnets D.

SkeletaljSystem 1.

Calcium analogs-2.

Phosphate analogs

'E.

Renal.Ssytem 1.

-Tubular agents

.2.

Chelates F.

Cardiovascular System 1.

Blood pool agents 2.

Myocardial agents G.

Pancreas-H.

Thyroid I.

Tumor Localizing Agents

'J.

Miscellaneous Radiopharmaceuticals K

In' Vitro, Agents I V.'

Radiopharmaceuticals in Therapy V.

R'ules.and Regulations i

7 3-o

,x

(~~ \\

C',

O

%)

1.

o =

. Nuclonr R:gulatory Commission - Food and Drug Administration 1.

' Licensure 2.

Purchasing of radioactive materials

'3.

Storage of radioactive materials 4.

Disposal of radioactive materials VI.

Laboratory.

1.

Introduction to instrumentation, equipment and laboratory regulations.

2.

Radiation protection measures: ordering, receipt and inventory of radionuclides; room survey; personnel monitoring; radionuclides transport.

3.

General Quality Control Procedures.

4.

The Molybdenum-99-Technetium-99m Generator: Construction, Handling, and Elution.

5.

Technetium-99m Lung Imaging Agents: Preparation and Quality Control.

6.

Technetium-99m Liver Agents: Preparation and Quality Control 7.

Biodistribution of Liver Agents.

8.

Technetium-99m Blood Pool Agents: Preparation and Quality Control.

9.

Extemporaneous Kit Preparation.

10.

Cell Labeling Techniques.

11.

Trip to New England Nuclear.

.

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