SifiQiQiQif_)sisfjiffG@il sisisisfiefsi sisisisisfii iffsfsi-@ ifsisisisisisisOiUifi sf_EsfifsdiO 8 FORM 3'74 U.S. NUCLEAR REGULATORY COMMISSION I* ' * ' MATERIALS LICENSE Amendment No. 03 f Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title to, Code of g Federal Regulations, Chapter I, Parts 30,31,32,33,34,35,36,39,40, and 70, and in reliance on statements and representations heretofore made g by the licensee, a license is hereby issued authorizing the licensee to receive, acquire, possess, and transfer byproduct, source, and special nuclear g material designated below; to use such material for the purpose (s) and at the place (s) designated below; to deliver or transfer such materia | to p ~ , persons authorized to receive it in accordance with the regulations of the applicable Part(s). This license shall be deemed to contain the conditions | S specified in Section 183 of the Atomic Energy Act of 1954, as amended, and is subject to all applicable rules, regulations, and orders of the k| s Nuclear Regulatory Commission now or hereaf ter in effect and to any conditions specified below. E E. E i 2 E || 'i"'" $ In accordance with the application dated Ei $ August 3 1994, E! E l Whitehead Institute for 3. License Nur'ber 20-20706-01 is amended in E| f Biomedical Research its entirety to read as follows: ( ! 2-9 Cambridge Center E| E Cambridge, Massachusetts 02142 . 4. Expiration Date May 30, 2000 El E i A i g 5. Docket or g Reference No. 030-20746 g ' 3 6. Byproduct. Source, and/or 7. Chemical and/or Physical 8. Maximum Amount that Licensee g ;; Special Nuclear Material Form May Possess at Any One Ttme g ! j Under This License g 5 A. Cesium 137 A.- Sealed sources A.'4,000 curies total E| ! J ;(AECL/Nordion Model. El b * ;C-161 Type 8) t , El B . .- E i
! p- >b . El 9. Authorized use , _ . _ B - :. ,. ~ E N A. In AECL/Nordion apimacel ?)f h E N explosives, flam@mables,38[Model1409IrradiatorNo6t'!- @ e # radiation ofE material except rjjcorro'sivbsii y f N B m -W a ;; J s N ,V@ 6 5 ~, 4 ~ $ g u CONDITIONS g g c |p, E v s -' m. ; W, g E! s 10. Licensed material may'be used oilly at the 1icedsee's facilities located at El ~ '' s 9 Cambridge Center, Cambridge, Massachusetts. /i E R 4 A -|, E B 11. A. Licensed material shall only be used by, or undeF the supervision and in the E B physical presence of, individuals who have(rieceived the training described in E s application dated August 3, 1994 and have been designated in writing by the E E Radiation Safety Officer. E * E i B. The Radiation Safety Officer for this license is Richard C. Mulligan, Ph.D. E| ' E 12. Sealed sources or detector cells containing licensed material shall not be opened or E e sources removed from source holders by the licensee. E t$$ El g"ot13. A. Sealed sources and detector cells containing licensed material shall be tested E for leakage and/or contamination at intervals not to exceed six months or at E such other intervals as are specified by the certificate of registration El h referred to in 10 CFR 32.210, not to exceed three years. El o m: .o u E ,eg B. Notwithstanding Paragraph A of this Condition, sealed sources designed to emit E ' -< alpha particles shall be tested for leakage and/or contamination at intervals E i * not to exceed three months. El SE El oao e 1000E2 Ej
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l I I Amendment No. 03 | I I | C. In the absence of a certificate from a transferor indicating that a leak test I i has been made within six months prior to the transfer, a sealed source or | | detector cell received from another person shall not be put into use until i I tested. | I I D. Each sealed source fabricated by the licensee shall be inspected and tested for I | I i construction defects, leakage, and contamination prior to any use or transfer as I a sealed source. j
l I I E. Sealed sources and detector cells need not be leak tested if: i I I (1) they contain only hydrogen-3; or I | I i . I (ii) they contain only a radioactive gas; or , . ~ | I I I (iii) the half-lifelf the isotope is 30 days or less;'or i I I (iv) they contain'not more than 100 microcuries>of beta and/or gamma emitting i
| - i material;or not more'th:n 10 microcuries of alpha emitting material; or ~ | I i I (v) they are;not designedito emit alpha particles, are infstorage, and are not i I being used. However, when they are removed from storage for use or | transfef to another person, and have not been tested within the required I | I i leak test interval, they ~shall be tested before use or transfer. No sealed , I source or . detector, cell shall be 1 stored for a period- of more than 10 years | | without being tested for. leakage and/or contamination. , I ., i | F. The test shall be, capable of detecting the presence of;0.005 microcurie of I If the testsreveals the presence of I g radioactive material . on the test sample. | i 0.005 microcurie or more of removable contamination, a report shall be filed | | with the U.S. Nuclear Regulatory Commission and the source or detector cell | | shall be removed immediately from service and decontaminated, repaired, or g I disposed of in accordance with Commission regulations. The report shall be p filed within five days of the date the leak test result is known with the i | U.S. Nuclear Regulatory Commission, Region I, ATTN: Chief, Nuclear Materials i i a i Safety Branch, 475 Allendale Road, King of Prussia, Pennsylvania 19406. The I report shall specify the source or detector cell involved, the test results, and | | corrective action taken. g I g i G. The licensee is authorized to collect leak test samples for analysis by the I | I y licensee. Alternatively, tests for leakage and/or contamination may be | | performed by persons specifically licensed by the Commission or an Agreement | - | : | State to perform such services. i I g | | 14. The licensee shall not perform repairs or alterations of the irradiator involving I removal of shielding or access to the licensed material. Removal, replacement, and I i I i disposal of sealed sources in the irradiator shall be performed by persons I specifically licensed by the Commission or an Agreement State to perform such j i services. p ' i N 15. The licensee shall conduct a physical inventory every six months to account for all I | P i i sealed sources and devices containing licensed material received and possessed under l
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______I umsma-m--=m------mmm--..... mmm ...... ,9 | CRC Form 374 A U.S.gLEA"1 RE!ULATORY COMMISSON & Pact 3 or 3 paces I! w License rum > ' - ' ' * 20-20706-01 MATERIALS LICENSE ' ' " " * ' * * " " " [ SUPPLEMENTARY SHEET P! 030-20746 pj P ' * ' Amendment No. 03 p| >| , 16. The procedures contained in the manufacturer's instruction manual for the irradiator E| authorized by this license shall be followed and a copy of this manual shall be made ( available to each person using or having responsibility for the use of the device. j
: 17. The licensee is authorized to transport licensed material in accordance with the provisions of 10 CFR Part 71, " Packaging and Transportation of Radioactive Material." .; 18. Except as specifically provided otherwise in this license, the licensee shall conduct its program in accordar,ce with the statements, representations, and procedures contained in the documents, including any-pnclosures, listed below. The Nuclear shallrgdvern un ess the statements,. Regulatoryrepresentations, Commission's and procedures regulations,he 1.in~t licensee'su)pplication and correspondence are more restrictive than the r;5,ghlations. D ' .(/ b A. Applicationdatedgugust3,1994 Q , s - | ' CQ .2 0, ||
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License No. 20-20706-01 Docket No. 030-20746 Control No. 120214 Mr. John Pratt Associate Director, WIBR Whitehead Institute for Biomedical Research 9 Cambridge Center Cambridge, MA 02142 Dear Mr. Pratt: Please review the enclosed document carefully and be sure that you understand all conditions. If there are any errors or questions, please notify the U.S. Nuclear Regulatory Commission, Region I office, the Licensing Assistance Section, (610) 337-5093 or 5239, so that we can provide appropriate corrections and answers. Please be advised that your license expires at the end of the day, in the month, and year stated in the license. Until your license is terminated, you must conduct your program involving byproduct materials in accordance with the conditions of your NRC license, representations made in your license application, and NRC regulations. In particular, note that you must:
1. Operate in accordance with NRC regulations 10 CFR Part 19. " Notices, Instructions and Reports to Workers; Inspections," 10 CFR Part 20, " Standards for Protection Against Radiation," and other applicable regulations.
2. Notify NRC, in writing, within 30 days when the mailing' address on the license changes (no fee is required if the location of byproduct material remains the same). 3. In accordance with 10 CFR 30.36(b) and/or license condition, notify NRC, promptly, in writing, and request termination of the license when you decide to terminate all activities involving materials authorized under the license. 4. Request and obtain a license amendment before you:
a. change Radiation Safety Officer;
b. order byproduct material in excess of the amount, or radionuclide, or form different than authorized on the license; c. add or change the areas of use, or address or addresses of use identified in the license application or on the license; or
0FFICIAL RECORD COPY ML 10 ______i *- $ 4 g 4 1 * W !
.. . 4 J. Pratt, Associate Director WIBR -2- | |- Whitehead Institute for ; ' Biomedical- Research j
' d. change ownership of your organization. i 5. Submit a complete renewal application with proper fee or terminat' a I request at least 30 days before the expiration date of your 16 gise. You i will receive a reminder notice approximately 90 days before the 1 i expiration date. Possession of byproduct material after your Utense . I expires is a violation of NRC regulations. A license will not numally be renewed, except on a case-by-case basis, in instances whers 'tcensed ! material has never been possessed or used. |
In addition, please note that NRC Form 313 requires the applice t, ty his/her j signature, to verify that the applicant understands that all statemet' j contained in the application are true and correct to the best of the applicant's knowledge. The signatory for the application should ue the ! licensee or a certifying official of the licensee rather than the avation i Safety Officer or a consultant. 1 You will be periodically inspected by the NRC. Failure to conduct your program in accordance with NRC regulations, license conditions, and representations made in your license application and supplemental correspondence with NRC will result in enforcement action against you. This could include issuance 'of a notice of violation, or imposition of a civil j penalty, or an order suspending, modifying or revoking your license as .| specified in the General Policy and Procedures for NRC Enforcement Actions, ' 10 CFR Part 2, Appendix C. Since seriods consequences to employees and the public can result from failure to comply with NRC requirements, prompt and vigorous enforcement action will be taken when dealing with licensees who do not achieve the necessary meticulous attention to detail and the high standard of compliance which NRC expects of its licensees. Thank you for your cooperation. Sincerely, I Original Signed By:-
James M. Bondick , Nuclear Materials Safety Branch ! Division of Radiation Safety and Safeguards
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1. Amendment No. 03 -;- 2.-10 CFR Parts 2, 19, 20, 30,- 71, and 170 ' 3.. Regulatory Guide 10.9, Revision 1
DOCUMENT NAME: R:\WPS\MLTR\L2020706.01 l |0FFICE- DRSS/RI N / | / | -| |
, |NAME JBondick/jmbo/3 |DATE 04/20/95 04/ /95 04/ /95 04/ /95 ,
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TELEPIIONE CONVERSATON RECORD Date:8/30/94 Time:2:35
, Mail Control No.: 120214 License No.: 11ocket No.: 20-20706-01 030-20746 , 4 Person Called: Frank Masse Organization: Telephone Whithead Inst. for Number:617- - Research 245-9217 '
Person Calling: Jim Bondick Organization: Telephone NRC Number:6951
Subject: Renewal application , Summary: Mr. Masse will send the corrected page referencing new Part 20 instead of
Old Part 20. . Action Required /Taken:MS15
Signature: Date: 8/30/94
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TELEPHONE CONVERSATON RECORD Date:8/24/94 Time:9:30 Mail Control No.:120214 License No.: Docket No.: 20-20706-01 030-20746 | Person Called: Frank X. Masse Organization: Telephone Whitehead Inst.for Number:617- Biomedical 245-9217
Research ; Person Calling: Jim Bondick Organization: Telephone NRC Number:6951 >
Subject: Renewal Application ,
' Summary: The renewal application did not have Dr. Lodish's training and experience with irradiators. After discussion with Mr. Masse, he decided to change the RSO fmm ' the named individual, Harvey I.odish, PhD, to Dr. Richard C. Mulligan, who is the supervisor of the irradiator facility. He will send the appmpriate information by fax and harti copy. ' Action Required /Taken: //f/) Signature: Date: 7 gy9
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' gg MEDICAL DEPARTMENT - ' /f//f[(. .. j ' 77 MASSACHUSETTS AVENUE,20B 238 . I i I ' 4" CAMBRIDGE, MASSACHUSETTS 02139 4307. , . bbice .
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, . August 30, 1994 ; ' ,
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.: Control No. 120214 4
US-Nuclear Regulatory Commission : 7 Region I ( n -475'Allendale Road : King of Prussia PA 19406 n { Attention: James Bondick j
Dear Mr. Bondick: I
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- - . This is to provide the necessary information for completion of the .j . license renewal on the ' Whitehead Institute irradiator license. The - irradiator'i~s under the control of Professor Richard Mulligan, who * has been ' the' principal supervisor of that irradiator since-its 1 installation. ' As such, Professor Mulligan is the logical choice to- !
serve as RSO on,that license, since he.is the most knowledgeable r
' person at' Whitehead on its ' operation and use. .As with_ the I radionuclide license at Whitehead, the actual day-to-day radiation ! safety activities.are carried out by the MIT RPO staff through a' ;I contract with Whitehead, but Professor Mulligan is.the Whitehead I individual RPO. personnel ~ interf ace - most s closely with on the. i irradiator. :
. . . i In addition to the years '.. Professor Mulligan has gained direct ; experience on the Whitehead irradiator, he has also been involved ;
for several years and been " specifically trained . at MIT on a- , comparable irradiator unit. In my opinion, Professor Mulligan is 't ' fully qualified to serve as RSO under this license.
Please contact the me at 617-253-9217 if further~information is required. Yours truly, .&houW i F.X. Mass 6, CHP, CMP i Director, MIT Radiation ! Protection Programs
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.: ; Supplementary Information Renewal Application License #20-20706-01
10.1) Personnel monitoring equipment, as specified in 10 CFR 20.1502, is required. : All personnel are required to wear a film badge as and external radiation monitor. ; The frequency of film badge exchange is monthly via Landauer, Inc. film badge ' service. j
10.2) The licensee has available at all times a calibrated, operable survey meter. As ! indicated in Attachment B, Appendix A, The installation is equipped with both i Ludlum Model 177 and Ludlum Model 3 radiation monitors. Both are maintained and calibrated by the M.I.T. Radiation Protection Office as part of the instrument calibration program described in application for license #20-01537-02.
Additionally, the Radiation Protection Office provides a monthly survey of the i room including an operational check of each instrument. >
10.3) Leak testing is performed at 6-month intervals by the M.I.T. Radiation Protection * Office as described in the application for license #20-01537-02. Analysis is performed in the M.I.T. Radiation Protection Office counting room and is capable
of detecting 0.005 pCi of radioactivity. j
10.4) Attachment C is a complete instruction manual available to the users, each of whom have been fully trained as described in item 8. Additionally, a copy of i
Appendix A of this manual is posted in the room housing the unit. |
11. Spent sources are disposed via transfer to the licensed installer of the new source at the ! time of installation. Ultimate disposal will be via transfer to a licensed recipient or waste disposal agency.
12. License Fee: The required fee, as stated in 10 CFR 170.31, of $760 is enclosed.
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w =;w + . p; * 3 -m , a ':x.'; sw. y ' - , As I 2 804: . . 7:c :| -1, , -! ~ License No. ' 20-20706-01 l ' ' Docket No. 030-20746; | Control No. 120214 ! : r: : Whitehead Institute for; 1 Biomedical Research. , ' - . ATTN: F. X. Masse - ' 9 Cambridge Center | . Cambridge, Massachusetts 02142 c -| , . Dear Mr. Masse: ii ! SUBJECT: LICENSE RENEWAL APPLICATION l This is to acknowledge receipt of your application for renewal of material (s) license identified j above. -Your application is deemed timely filed, and accordingly, the license will not expire until final action has been taken by this office. ! Any correspondence regarding the renewal application should reference the control number : specified above. .; . 1 Sincerely, Original Signed By: , -; Sheryl Villar, Chief 1 - . Nuclear Materials Safety Branch ; ' Division of Radiation Safety and Safeguards ! ! t | I ; ; i !- DRSS:RI DRSS:RI rkins/amw Villar 8// 194 8/ 4/94 .! | | OFFICIAL RECORD COPY - S:\PENDING\WHTEHEAD.DTL - 08/09/94 | ML 10 i . _ * Q y J s *& A ~ L $ NRC FORM 313 , U. S. NUCLE %R REGULATORY C;MMISSION * APPROYED BY OMS: NO. 31864120 , g,.g33 EXPIRES s-304s to CTR 30. 32,33 ESTIMATED BURDEN PER RESDONSE TO COMPLY WITH THIS e 34. 35, 38. 30 and 40 NFORMATON COLLECTION REQUEST, 9 HOURS. SUBMllTAL OF THE . APPUCATION IS NECESSARY TO DETERMINE THAT THE APPUCANT l$ e QUAUFIED AND THAT ADEQUATE PROCEDURES EXIST TO PROTECT 6 THE PUSUC HEALTH AND SAFETY. FORWARD COMMENTS APPLICATION FOR MATERIAL LICENSE ReGARDNo BURDEN ES= ATE To mE NFORMAToN AND RECORDS MANAGEMENT BRANCH (MNB8 7714), U.S. NUCLEAR REGULATORY COMMISSON, WASHINGTON, DC 2m nnni, AND TO THE PAPERWORK REDUCTON PROJECT (3150 4120). OFFICE OF MANAGEMENT AND BUDGET WASHINGTON DC 20503 INSTRUCTIONS: SEE THE APPROPRIATE UCENSE APPLICATION GUIDE FOR DETAILED INSTRUCTIONS FOR COMPLETING APPUCATION. ! SEND TWO COPIES OF THE ENTIRE COMPLETED APPLICATION TO THE NRC OFFICE SPECIFIED BELOW, APPUCATiON FOR DISTR 180 TION OF EXEMPT PRODUCTS FILE APPUCATIONS WITH: IF YOU ARE LOCATED IN: C:VISCN OF INDUSTRIAL ANO MEDCAL NUCLEAR SAFETY ILUNOIS, INDIANA, IOWA, MICHIGAN, MINNESOTA, MISSOURL OHlo, OR WISCONSIN, OFFCE OF NUCLEAR MATERIALS SAFETY AND SAFEGUARDS SEND APPUCATONS TO- U S NUCLEAR REGULATORY COMMISSON W,t,$H:NGTON,DC 20555 0001 MATERIALS UCENSING SECTON ALL CTHER PERSONS FILE APPUCATONS AS FOLLOWS: 801 WARRENVILLE RD, IF YOU ARE LOCATED IN: USLE, IL 80532 4351 CONNECTICUT, DELAWARE, DISTRCT OF COLUMSIA MAINE, MARYLAND, ARKANSAS, COLORADO, IDAHO. KANSAS, LOUtslANA. MONTANA NESRASKA, NEW f ASSACHUSETTS, NEW HAMPSHIRE, NEW JERSEY, NEW YORK, PENNSYLVANIA, MEXICO, NORTH DAKOTA, OKLAHOMA, SOUTH DAKOTA, TEXAS, UTAH, OR WYOMING, EHODE ISLAND, OR VERMONT, SEND APPUCATIONS TO: SEND APPUCATIONS TO: LCENSING ASSISTANT SECTON NUCLEAR MATERALS UCENSING SECTION N R RE R COM ,, REGON I 4 5 ARENOM ROAD 1 R E. SU!TE 400 ARLNGTON, TX 78011 9084 KING OF PRUSSIA. PA 19406 1415 K,LABAMA, FLORIDA, GEORotA, KENTUCKY, MIS $1SSIPPI, NORTH CAROUNA PUERTO ALASKA, ARIZONA, CAUFORNIA, HAWAll, NEVADA, OREGON, WASHINGTON, AND U.S. KICO, SOUTH CAROUNA, TENNESSEE, VIRGINLA, VIRGIN ISLANDS, OR WEST VIRGIN'A, TERRITORIES AND POSSESSONS IN THE PACIFIC, SEND APPUCATIONS 70- SEND APPUCATIONS TO: eW NUCLEAR MATERIALS UCENSING SECTON RADCACTIVE MATERIALS SAFETY BRANCH U S NUCLEAR REGULATORY COMMISSC% REGON N U S. NUCLEAR REGULATORY COMMISSION, REGCN V 101 MARIETTA STREET, NW, SUrTE 2900 1450 MARIA LANE ATLANTA. GA 303:5 0190 WALNUT CREEK, CA 94506.5388 PEKSONS LOCATED IN AGREEMENT STATES SEND APPUCATONS TO THE U.S. NUCLEAR REGULATORY COMMIS$10N CNLY IF THEY WISH TO POSSESS DUSE CENSED MATERIAL IN STATES SUBJECT TO U.S. NUCLEAR REQULATORY COMMISSION JURISDICTONS. 1 THIS IS AN APPUCATON FOR (ChecA appmenese HenV 2. NAME AND MAluNG ADDRESS OF APPUCANT pnclude Zp eode) 4. NEw uCENSE Whitehead Institute for - B. AMENDMENT TO UCENSE NUMBER Biomedical Research T C. RENEWAL OF UCENSE NUMBER 20-20706-01 9 Cambridge Center -'~ Cambridge, MA 02142 3 ADDRESS (ES) WHERE UCENSED MATERIAL WILL BE USED OR POSSESSED 4. NAME OF PERSON TO BE CONTACTED ABOUT THIS APPUCATON Same Frank S. Maose TELEPHONE NUMBER (617) 253-9217 SUBuff ITEMS 5 THROUGH 11 ON 81/2 X 11" PAPER. THE TYPE AND SCOPE OF NFORMATON TO BE PROVDED IS DESCRIBED N THE LCENSE APPUCATON GUCE. 3 RADCACTIVE MATERIAL. e. Element and mass number; b chem cei and/or physical form; and c. enenomum emouni 6 wench will be possessoa et any one ame PURPOSE (S) FOR WHCH UCENSED MATERIAL WILL BE USED. T INDiv0UAL(S) RESPONSIBLE FOR RADiATON SAFETY PROGRAM AND THEiR - TRAINING EXPERIENCE. 8. TRAINING FOR NDIVIDUALS WORKING IN OR FREQUENTNG RESTRCTED AREAS. 9 FACluTTES AND EQUIPMENT. 10. RADIATON SAFETY PROGRAM. 12. UCENSEE FEES (See 10 CFR f 70 and Seccan f 70 Jf) 11 WASTE MANAGEMENT aAMOUNT rEE CATEGORY 3E I ENCtOSED $ 760 13 CERT)FCATON (Must be competed by appJzent) THE APPLICANT UNDERSTANDS THAT ALL STATEMENTS AND REPRESENTATONS MADE IN THIS APPUCATON ARE BINDING UPON THE APPUCANT. THE APPLCANT AND ANY OFFil.;1AL EXECtTflNi'HIS CERTECATON ON BEHALF OF THE APPLCANT, NAMED IN ITEM 2 CERTIFY THAT THIS APPUCATION 13 PREPARED N CONFORMITY WITH TfTLE 10. CODE OF FEDERAL REGULATONS, PARTS 30,32,33,34. 35,36,30 AND 40, AND THAT ALL NFORMATON CONTAINED HEREIN IS TRUE AND CORRECT TO THE BEST OF THEIR KNOWLED(4 AND BEUEF. W ARNING 18 U S C. SECTON 1001 ACT OFJUNE 25,1948 62 STAT. 749 MAKES ff A CRIMINAL OFFENSE TO MAKE A WILLFULLY FALSE STATEMENT OR REPRESENTATION TO ANY DEPARTMENT OR AGENCY OF THE UN!TED STATES AS TO Aer( MATTER WTTHIN ITS JURISDICTION.f j CIERT18YING OFFCER TYPED / PRINTED NAME AND TrTLE SIGNATURE DATE N John Pratt, Assoc. Director WIBR /,j.y 3 jQ ,) /#f N FOR NRC USE ONLY O TYP FE g FE LOG 2(Jf FEE CATEGORY AMQWNT Msu.3V CHECK NUMBER COMMENT 4 ) g }| .W h0 NS & 3 "- APPROVED BY / / / DATE La, / Ur yy os k 4 1 3/?y ~~ ~= * cmCW.FsM OCWG M N AW -6 9F-"" "" 9 ;5 - 'q g ., g ' g - . . W f , , "" Supplernentary Infonnation i Renewal Application License #20-20706-01 ' ! ' "7 5. Cs, not to exceed 4000 Ci, sealed source #AECL Model C-161 Type 8 housed in AECL Gammacell 40 Laboratory Irradiator. i 6. Research studies investigating the effects of irradiation on cells and biological systems. < 7. F.X. Masse, C.H.P., M.I.T. Radiation Protection Officer - Harvey Lodish, Ph.D., Whitehead Institute Radiation Protection Officer (see c.v.in Attachment A.) . Both individuals fill the requirements of 10 CFR 30.33(a)(3). ; 8. 8.1) All users must first be approved by the Radiation Protection Office after ; satisfactorily completing the training course and exam described in Attachment ! B. ) 8.2) The passing grade for the Gammacell quiz is 70% or better. Individuals who do not obtain a passing grade are required to review their examinations with a member of the M.I.T. Radiation Protection Office staff. When the examinee has verbally demonstrated his or her understanding to the staff member, the review - ! is complete and a passing grade is obtained. , 8.3) Each individual receives on-the-job training in the actual operation and use of the ; irradiator as part of the Gammacell Irradiator training program. t 8.4) Course instruction is provided by members of the M.I.T. Radiation Protection Office staff ' These individuals meet the requirements of 10 CFR 30.33(a)(3). | , 8.5) Records documenting the training of each individual will be maintained. i 9. The sources will be housed in AECL Gammacell 40 Irradiator located in Whitehead Institute room 232. The specifications of the device were provided to the architect : during the early planning phases, and the room was specifically designed to house this unit, considering the weight of the unit as well as its service needs. The irradiator is * located in a room that can be locked when a user is not present to prevent access by I unauthorized persons. 10. Radiation Safety Program: The following Radiation Safety Program description follows the outline prescribed in the October 1984 proposed revision to Regulatory Guide 10.9. ; ' The licensee, Whitehead Institute for Biomedical Research, accepts responsibility for the conduct of the irradiator program and all actions of its employees. I , A 54 - h, .d h h e1 - w .< s 7 Supplementary Information . Renewal Application License #20-20706-01 L. P 10.1) ' ersonnel monitoring equipment, as specified in 10 CFR 20.202, is required. All | personnel are required to wear a film badge as and external radiation monitor. ! The frequency of film badge exchange is monthly via Landauer, Inc. film badge , service. ; 10.2) The licensee has available at all times a calibrated, operable survey meter. As . indicated in Attachment B, Appendix A, The installation is equipped with both ' Ludlum Model 177 and Ludlum Model 3 radiation monitors. Both are maintained : and calibrated by the M.I.T. Radiation Protection Office as part of the instrument calibration progiam described in application for license #20-01537-02. Additionally, the Radiation Protection Office provides a monthly survey of the room including an operational check of each instrument. . 10.3) Leak testing is performed at 6-month intervals by the M.I.T. Radiation Protection i Office as described in the application for license #20-01537-02. Analysis is performed in the M.I.T. Radiation Protection Office counting room and is capable of detecting 0.005 pCi of radioactivity. . r 10.4) Attachment C is a complete instruction manual available to the users, each of whom have been fully trained as described in item 8. Additionally, a copy of Appendix A of this manual is posted in the room housing the unit. 11. Spent sources are disposed via transfer to the licensed installer of the new source at the time of installation. Ultimate disposal will be via transfer to a licensed recipient or waste disposal agency. , 12. License Fee: The required fee, as stated in 10 CFR 170.31, of $760 is enclosed. , 6 4 , | I. I 1 . . 4 '. $ m i j- - w ! e a ! . | | 1 1 : ! I t Renewal applicaiton License #20-20706-01 ATTACIIMENT A , r. * .- * .g- ; gr 4 m, s * . ' Harvey F. Lodish, Ph.D. Member, Whitehead institute for Biomedical Research and Professor of Biology, Massachusetts institute of Technology, _ Cambridge, MA Dr. Lodish received his A.B. degree in chemistry and mathematics, summa cum laude, from Kenyon College in 1962, and his Ph.D. degree in genetics with Norton Zinder from the Rockefeller University in 1966. Following two years of postdoctoral research at the M.R.C. Laboratory of Molecular Biology with Sydney Brenner and Francis Crick, he Joined the faculty of the MIT Department of Biology. He was promoted to Professor in 1976, and in 1983 was appointed Member of the new Whitehead Institute. He is also a member of the MIT Biotechnology Process Engineering Center. Initially,19s work focused on translational control of protein synthesis, and on regulation of gene expression during differentiation of the cellular slime mold. Beginning in 1973, his laboratory has increasingly concentrated on the biogenesis, structure, and function of secreted and plasma membrane glycoproteins. He defined the biosynthesis and maturation of the vesicular stomatitis virus glycoprotein, identified the intracellular- organelles that mediate recycling of the asialoglycoprotein and transferrin receptors, and clarified the role of pH changes in delivery of iron to cells and recycling of the transferrin receptor. More recently, his group has elucidated steps in folding and oligomerization of several proteins within the endoplasmic reticulum, shown that exit of newly-made proteins from this organelle requires that they be properly folded, and developed probes for measurement of the redox state within the endoplasmic reticulum. His group has cloned and sequenced mRNAs encoding the erythrocyte glucose transporter, the anion exchange (Band 3) protein, the human asialoglycoprotein receptors, intestinal sucrose-isomaltase, the murine erythropoietin receptor, the calcitonin and endothelin receptors, and two subunits of the TGF receptor. These have been used to define the structure and synthesis of the proteins, to identify and sequence related genes that encode proteins of related physiological function, and, most recently, to elucidate the modes of signal transduction of the TGFE and erythropoietin receptors and their roles in tumorigenesis. Another major focus of his ! research is on the biosynthesis, folding, oligomerization, and degradation cf proteins within the endoplasmic reticulum. , 1 1 , - - _ _ - - . _ - _ _ - ______* . ' @ O . Dr. Lodish is on the Board of Reviewing Editors of Science, was Editor of Molecular and Cellular Biology from 1981 to 1987, and has been on the ' editorial boards of a number of journals, including the Joumal of Cell Biology, the Jaumal of Biological Chemistry, and Nucleic Acids Research. Dr. Lodish has served on advisory panels for the NIH, NSF, and American Cancer Society, and on the advisory boards of several institutions, including the the Biozentrum of the University of Basle. He is currently on the advisory board of the European Molecular Biology Laboratory in Heidelberg and the PEW Scholars ProCram in Biomedical Sciences and is a member of the Board of Trustees of Kenyon College. He is chair of the advisory boards of the Division of Basic Sciences of the Fred Hutchinson Cancer Center and of the Cleveland Clinic Research Institute, and chairs the International Committee to Evaluate Biochemistry in Denmark. He is the co-author with Jim Damell and David Baltimore of the textbook Molecular Cell Bio /cgy. Dr. Lodish is the recipient of a Guggenheim Fellowship, an honorary D.Sc. from Kenyon, and the Stadie Award from the American Diabetes Association. Dr. Lodish is a Fellow of the American Association for the Advancement of Science, is a Member of the National Academy of Sciences, and is a member of the Cleveland Heights High School Hall of Fame. D Lodish was a founder and scientific advisory board member of Damon Biotech, Inc., and was a founder and is currently on the advisory boards of Genzyme, Inc., Arris Pharmaceuticals, Inc., and Sugen, Inc. ; i e 2 r i > < 's ' ' A r h w . . f. 4 ! ; ! , Renewal applicaiton License #20-20706-01 ATTACIIMENT B , . | I i I I - + .7 . .. , .,a. , .y .: .. (g A 7 , a 9 TRAINING PROGRAM .y. n Time: 3 hours ; . I. Source Information ! ' .A. Source l. Source Activity. : ' i- 2. Half-life / Energy 3. Basic Decay Law II. Machine Operation . A. Machine Desien 1. Machine Cut-aways | 2. Area Monitor / Survey Instruments ' 3. Load Position / Irradiate Position 4. Access Controls , B. Isodose Curves . 1. Ambient Radiation 12vels: Rest and Irradiate Positions ' ^ 2. leakage Radiation ! C. Pre-Oneration Checks 1. Survey Meter i 2. Compressor / Machine Start Up 3. Pneumatics 4. Sample Chamber III. Film Badge Program : - IV. Basic IIealth Physics Concepts - , A. Time. Distance. Shielding 1. Inverse Square Law ' 2. Attenuation (e*') 3. Half-value Layers i B. 10 CFR Part 19. and Part 20 V. Emergency Procedures j ! A. Discussion of Any Previous Problems j B. Common Causes of Exposure-Safety Precautions VI. Gammacell Test VII. Ilands on Training 1 e - 1 , -! :5 - u ? }| |, -; I p y- . - .t y ' 4 :. , , - 1 i .; : : ! 1 s 4 4 . APPENDIX D * Whitehead Institute Gm=== cell' Users' Ouiz- : | i ~ '1.- Radiation levels have been measured along the cavity door with I the source in the rest position and -in.the irradiate position. - , .The expected levels are ) ' arads/hr with the. machine on, y- 'and , arads/hr.while the machine is off. - J a. 400-500,.50-60. i b. 100-500, 0-10. -j '' "a c. 10-20, 0-1.- .d.' 500-1000, 10-20.- ] ! > . . | 2. The annual maximum permissible whole body dose to a radiation ~! worker is. t a. 3000 mram.- q b.- 500 mram. ; L c. 5.0 ram. [ d. 1. 2 5 rem. . t i > 13. The maximum' permissible whole body dose to a pregnant worker for the 9' month duration of pregnancy is: a '. 500 mrom. ! b. 3000 mram. ' C. 5.0 ram. d. 50 rem. [ t .. 4 ~. If the alarm in the irradiator facility is sounding, you- j should: ' | a. immediately evacuate the building. .e b. ! run through all the pre-operative. checks to determine the- I cause. I c. continue your work as planned, the alarm was falsely sounded by an electrical' surge, j d. turn off the irradiator, leave and secure the room, notify , -R.P.O. ! ' ! i I -1 i D-1 -; | i i - ._ ._ ___1 _- u y .~- : ~.. 4 A . * s; . . AEL L.).* .) , W . . . . 5. The area monitor in the irradiator facility is set to sound an alarm if the dose rate exceeds: a. 2 mrads/ min. b. 2 mrads/hr. , c. 5 mrads/ min. d. 5 mrads/hr. . i , 6. Match the following acute whole body doses to the correct probable effect: , a. 0-25 rads 1. blood changes, some injury, no disability b. ~ , 50-100 rads 2. no obvious physical injury i c. 450 rads 3. fatal within 60 days to 50% of those d. >600 rads receiving dose 4. 100% fatal ' r 7. From the choices listed below, select the material that should not be irradiated in the gammacell: a. corrosive and explosive materials. b. pyrophoric, highly flammable material. i c. metal containers, d. a and b only. e. a, b, and c. ; 8. When using the irradiator, the R.P.O. should be notified when: ; a. the survey monitor battery is dead. * b. there is any indication of malfunction of the Gammacell-40 unit. c. higher than normal radiation levels are detected during operation. d. all of the above. 9. The source configuration usedtin the Gammacell-40 is: a. a single "7Cs source located on a sliding drawer - directly above the same cavity. , b. -two "7Cs double encapsulated sources housed in drawers, ; one above and one below the cavity. ' c. a "Co single source located on a sliding drawer directly above the sample cavity. ' d.- two "Co double encapsulated sources housed in drawers, one above and one below the cavity. I D-2 f| ' * : 2 .- .. . . A C)-- y ' ., . . . . 10. i If Lthere is a low pressure condition in the Gammacell-40 -- ~ -for example, during initial machine start-up, the " low 4 air / timer.on" indicator lamp lights up -- you should:. a. leave and secure'the room, contact R.P.O. b. turn the machine off and try again later. E c. wait until the correct internal pressure has been reached and the light indicator turns off. your experiment.. You can then begin d.- notify the building manager. 11. Which of the following statement (s) is/are correct: a. The sample cavity door cannot be opened when the source drawers are in the irradiate position. .. b. If the sample cavity door is open, or not comolete.ly , closed, the source drawers can be moved into the irradiate position. c. both a and b. d. none of the above. 12. Each sealed source in the Gammacell shall be tested for leakage and/or contamination at intervals not exceed months. The test shall be taken from appropriate accessibleis permanently surfaces mounted. of the machine in which the sealed source a.- 3. b. 6. C. 12. ; ' d. 24. 13. The Gammacell ""Cs source has a half-lifa of , and I emits X-rays with an energy of about . ! I a. 15.7 days, 1.117 MeV. " b. 30.0 days, 662 MeV. c. 30.0 years, 662 kev. . d. 15.7 years, 1.117 MeV. 14. I On June 12, 1984 the Gammacell-40 contained two *"Cs sources I with a total activity of 3930 Curies. What is the total activity remaining 6 years later on June 12, 1990? a. 3421 Ci. b. 3241 Ci. c. 3930 C1. d. 3583 Ci. ) D-3 ! i L l _ ~ av _ < > }| , u . :\ %j'' A(e- -, ,r Q - W , _ ; &,: , . . . . ;.. ..e: . .! 1 E* . .. 'I ~ ...... ; L 15. . ' ' r ' ' The dose rate8 at the center of the' chamber was measured ~ to:be .6. 50 ?: X 10 ' rads /hre on June ; 12,-1984. .Using the data fromi - ' question ; #14 ', determine the dose rate on? June'12, 1990.- a. 5.'66'X 108I rads /hr. |b. 8 . 5.59 L X 108 rads /hr. ; i. , ?a. 7.47 X 10 rads /hr.- c a. 8 j 6.50 X 10 rads /hr. i f I 16. ! If the dose from a source is 10..arads/hr at 10 cm, what~is. l the dose-at 100 cm under the same conditions?- -M 1 a. . O.Ol'mrads/hr. ^ 'b. '. 0.1 mrads/hr. l c. .1 mrads/hr. ! d. 10 mrads/hr. : , . , a 17-. What primary shielding material' has been installed in'the- i Gammacell-40 to protect the operator?- ! I a. ' concrete. 'I , b. plexiglass. c. lead.- ' ! -d'.- polystyrene. I i 'i 18. What instruments are used as area survey monitors in the j irradiator facility? ! , a. i Boron Triflouride neutron detectors.. ! b. air ionization' chambers.- c. NaI scintillationcdotectors. | d. G.M. survey meters. .; . 'l '19. The maximum dose rate deviation within the irradiation. - i chamber from the center of the sample chamber to the outer { perimeter is: . f , . ' a.- 5%. b. 10%. c; 15%. d. 20%. ; , - 20. ~ , If-you remain in a room'with a 0.5 mrad /hr dose-rate for 15 ' i minutes, what is your total whole body absorbed dose? ; : a. 0.5.mrads, "! b. 0.05 mrads. ! - c. 0.125 mrads. d. Background. ! D-4 I -l > 6 , _ _ _ . . _ . . - - _ - + ------. _ . , , - _ ._. .__ . , - - - . .. ; y.,, _- , - ;,; p . ' 7, ' .' ki . .A ,.a + h , u ,[Wi :, z L,? I p '; ' ! . :: V : < ~ ' ' ' 5 21. Choose', from the4 following,;.the access control procedures in @ < :effect for the Gama'a cell facility: q " ' ca. all' authorized' users' names are posted on the~ door. b. .'a.specified individual ~'is responsible for the irradiator j - room-key. q c. R.P.O. must be called prior to-each use. ' ' -d. a and b only. .j ; e. -a=,;b, Land c. 'c j ; , '22. All users:of1the Gammacell Irradiator must: , l y a. ' log in. b. monitor-the' sample' cavity after use. . . . c. insure that the. facility.is locked when finished using " ' . the irradiator. d. 'all of the above. . 'l : 23. You are standing in front of the control panel of the ~irradiator. Under normal operating conditions, whatidose' , rate (mram/hr) do you expect to receive with:. a)~ the ' source ' in the irradiate ' position, and b) .the source in the rest position? i ; ' a b a. 20' '20 b. 50 10 c. 80 50 . d. ; 10 0 , ! , 24. While.using the'irradiator, you. discover higher than normal background radiation. You phoned ' the R.P.O. and . notified . .4 them of-the situation. A wipe test of~theLarea was taken > over.a 100 cm2 area. The scintillation counter measured 1000 CPM. The counter's' officiency for '87Cs was - 10 % . The back round measurement was 100 CPM. The activity (in DPM) of. .the 73 7 2 Cs on the wipe test per 100 cm was : ! . a. 90 DPM. b. 900 DPM. , , 1 c. 9000 DPM. ' i d. 1000 DPM. ' 25. What is the activity, in microcuries (gCi), of. the wipe result in question #24? a. 0.553 pC1. - b. 0.900 gCi. c. 0.243 gCi'. d. 0.004'gCi. D-5 '| - ______- _ _ - - . y ~ p- ,c = "1 _. - . . , I ' 1 .,g,.. i ;;J ~^ f - .. - .' . 4, , # .,. . ?:. - s.... r , . , , , , ANSWER' SHEET- -| ~.;- ,. .. .. , i A ~1. 12. . _ ... - f 2. 13. i 3. ,. 14. 4. 15. -5. 16. " 6. A 17. B 18. C 19. D 20. 7. 21. S. 22. 9. 23. '10. 24. 11. 25. : Name:- Date: . D-6 ...... -- - ., - - . -. . . , . ' .pg..., . ' .- ; r g- .. ,, - -. ..4 ;-.' + ' ' ~ . - , .:- .s'- ,g ; . ; e-(-) -a J| . w.. 9- 8 $ m .: s' - ( f. . - | t t > .~ ANSWER KEY '? I i h ! '1.- .C I i 2.- C ! ! 3. 'A * *i 4. -D j 5. B' ' -6.- 'A- 2 : - l' B. 1- * C 3 .t > ~, D- 4 '. 7. D '' 8. D ! :9. B ,! 10. C .: 11.- ~ n| A ' 12.- B ! -13. C t .14. A ; ., ' 15. LA ,'- 16. B- t ' 17 . - C ' '! 18. 'D- '! 19. A ; 20. 'C- r{ 21. D ' : 22. D '' .~23. D i,' . 24. C i 25. D- |! . - I : i i 1 'I i e e l _ . ! ! ! F ! I 'i. : , t D-7- k i 1 h '! ! ! ! l f * . - . , _ , - - _ , . . . . ., ~ .- , , . . - . . , . . . . , . -.. . - - . - ,. ,.- . . - . * ,-a, .. . , g * U w .. o E. Renewal applicaiton License #20-20706-01 ATTACIIMENT C : i ; | ' - _ _ _ _ r; * . . , ' .. .- O a ; w . , . . . . b ,- GAMMA-CELL 40 TRAINING MANUAL ; i for all WHITEHEAD INSTITUTE GAMMA-CELL 40 USERS t by the M.LT. RADIATION PROTECI10N OFFICE I. INTRODUCTION : , A. Purpose: This training manual is provided to prospective Gamma-Cell 40 users in order to supplement their training in radiation protection. It is to be used in conjunction with the " Whitehead Institute Required Procedures for Radiation Protection" issued - by the Radiation Protection Committee (RPC), and the Gamma-Cell 40 instruction manual provided by Atomic Energy of Canada, Ltd. (AECL). This manual is not intended to be distributed in lieu of specific specialized Gamma-Cell 40 training provided by the M.I.T. Radiation Protection Office (RPO). | II. GAMMA-CELL 40 RADIOACTIVE SOURCE INFORMATION I A. Description 1. Construction: - The Gamma-Cell 40 utilizes two doubly encapsulated "7 Cesium (l'7@ source capsules (Model C-161, Type 8). They are mounted in brass encased ; lead filled horizontal cylinders (2.5 inch X 16 inch), and are held in place by ! retaining rings. i 1 1 ; | . f.~ ., ,,. * . - , g U w r . . i, i B. Decay Characteristics 1. Activity: Each scaled source contains approximately 1800 Curies (Ci) of'"Cs(12/74) as CsCl powder. 2. Decay scheme: '"Cs decays bgbeta emission (1176 kev [7%),514 kev [93%]) with a 30.0 * . year half-life to 2 Barium- ('""Ba). 2""Ba emits 661.2 kev x-rays [85%] with ; a 2.6 minute half-life to stable "Ba. 137 30.o y * Cs B' 661.6 kev rr v 137 Ba | Figure 1:''7Q Day S&m ! , 3. Dose rate i a. General: The unshielded dose rate from a 1 Curie 8"Cs point source is ~ about 330 mrem / hour at I meter (or, 3.3 Rem-cm2 /hr-mci) b. Chamber: The chamber dose rate was measured to be 146 Rad / minute in 1/84. To calculate the present chamber dose rate, use the following formula: D = D (e -9 ; 2 l i D . -.. g , Q- f' ,g[ .y " . - .w- + ... .. q ' c . .: = y _ .Where: D(9 Dose rate'at desired time t f D(,i = Initial dose rate - -i " A- = Decay constant [In2/tm] = 0.0231 yrt j - t = : Time interval (in years) i ; " Note: The chamber dose rate on 8/94 was calculated to be 115 rad / minute. 1 -t * .i , IU. LICENSE REQUIREMENTS - | ' - - . i A.- Nuclear Regulatory Commission (NRC) . .s I 4 1. Description: g 2 The NRC has issued the Whitehead Institute a special license for two "Cs j scaled sources (AECL model C-161, type 8) with a maximum activity of 2000 _ | Ci/ source. The sealed sources will be housed in a Gamma-Cell 40 unit ~ ! manufactured by AECL. : 1 2. Conditions - . i a) The Gamma-Cell 40 unit shall be used by, or under the supervision of,- ; individuals designated by the M.I.T. Radiation Protection Committee. 'j i b) The scaled sources be shall be leak tested at intervals not to exceed six - months. ! I c) The procedures in the AECL Gamma-Cell 40 instruction manual shall be | followed by each user. j ! B. Radiation Protection Committee (RPC) , .| i 1. Description: | The M.I.T. RPC grants the Whitehead Institute for Biomedical Research :! under the supervision of Dr.13ichard C. Mulligan an authorization (RPO. | - ..._ ._ reference number W-V) to use and possess the radioactive material contained . . :| in tlie~Gisinia-Cell 40 unit. :i ! - 2. Conditions .| :| a). There shall be compliance with the provisions of the document entitled .| '" Regulations and Procedures for Use of the Gamma-Cell 40. Irradiation | Unit"(see Appendix A). , j ! ! .! !. 3 I : | | I J o , -. - * w . _ _ ,-,..r- , 7,, . , _ ...... - - - , - y ., - . , _ ; 1,:i {Q , .g g i es m ., ;; . a : . . . i b). A copy of the Regulations and Procedures shall be posted in' Room WI-- 1 '232. ! ' ! n c) | Prior to being permitted to operate the Gamma-Cell 40 unit, each person .; must (a) receive adequate training in the use of the unit, (b) be authorized 1 : by Professor Mulligan and (c) be registered with RPO. | i . d) The names of persons authorized to operate the Gamma-Cell 40 unit shall | P be posted on the front of(the door to) the unit. ,! : 'E e) The project will ensure that a properly functioning survey meter' is available. j! IV. RADIATION PROTECTION CONCEPTS -| ! A. Regulations: Title 10, Chapter 1, Code of Federal Regulations (CFR)'. . . | i ' 1. Part 20: " Standards for Protection Against Radiation". 2. Part 19: " Notices, Instructions and Reports to Workers; Inspections". | : B. Radiation Exposure 1. Exposure Limits- It is the responsibility of each Gamma-Cell 40 user to maintain their ''! exposure to ionizing radiation As Low As Reasonably Achievable (ALARA), and within the limits specified. ! i ^ ' . AREA EXPOSED.. ANNUAL LIMIN - l , |(rem)1 < ! > : Total effective whole body dose equivalent. 5. ! t Lens of the eyes. 15 i .: - Skin of whole body, and extremities. 50 ! Minors (under 18 years of age)2 0.5 - Pregnant worker 0.5 i (for 9 months) | ; 'Each radiation worker who may receive a radiation dose in excess of 10% of these limits will be provided j with appropriate personnel '.nonitoring badges by the Radiation Protection Office. ' 2With parental / guardian perrnission. 5 ) 4 ! ! ! | ._. -- - - - . . & ' .E4 3 , I ; , w g y s- .. . . u , , . . 2. Exposure Minimization Methods: ., , Radiation exposures can be minimized by the use of one, or a , combination of, the following radiation protection principals- f a) . Time: Minimize the time spent in room WI-232 while the unit is inL operation. Make use of the preset time interval counter. .: ; " b) Distance: Maximize the distance from radiation sources (such'as the' l radiation streaming from the sample chamber drawer). . The dose rate .; . within the room itself does not fall off as a function of'th'e inverse .| square, since the scattered secondary radiation emitted from the unit : ' shielding does not present a true point source configuration. j l c) Shielding: Shielding the primary radiation from the '7Cs sources is , . accomplished by the manufacturer through the use of lead. To calculate j , the shielding effectiveness, use the following formula: , . D(,) = D(,) (e ~"*) B ! i . . ' Where: D(,) = Shielded dose rate at desired point D(,) = Unshielded dose rate at desired point - u = Linear attenuation co-efficient for 662 kev gamma ray in lead = 1.29 cur 2 - = X . Shielding thickness , = B Buildup factor to account for the secondary. ! scattered radiation produced in the shield = 2.7 : ' , For example; calculate the dose rate on contact with the six inch lead walls surrounding the sources: | = D(,) D(,)(e -"*)B ! D(,) = 1,800,000 mQi x 3.3 Rem-cm2 /hr-mci x (15cm) 2 = 26,400 Rem / hour at 15cm (6 inches) . ; ' D(,) = 26,000 Rem /hr x (e -(i.29 x ts)) x 2.7 - D(,) = 0.0003 Rem /hr or 0.3 mrem /hr at the shield wall ) .! . | 5 - _ F 3 ^ (ej V .: ,; g. m - w . e i :i) V. MACHINE OPERATION : A. Construction Design: (see Appendix' B for drawings) | B. Components (iefer to AECL instruction manual for details) .. 1. Electrical Power: 120 VAC,60 Hz, single phase,2 kVa, by the use of a 10 foot three- ' pronged power cable. . 2. Air Compressor: t Provides air for both the sealed source drawer movement and sample - i chamber. 3. Scaled Sources: (See II)- , 4. Sample Chamber: Allows samples (mice, cells, etc.) to be irradiated uniformly for a specified time period. The sample chamber can be accessed only when the , Gamma-Cell 40 sources are in the stored (off) position. t 5. Control Panel: Provides a centralized location for all of the controls necessary for the operation of the unit. a) Keyswitch: Controls electrical supply to the unit. b) " Manual / Auto" mode switch: Allows switching between auto and manual operation. , c) Timer Assembly: Allows operation of the unit for a preset time while in the auto mode. ! d) " Source On" Switch: Controls movement of the source drawers to the ; irradiate position while operati,ng in the manual mode. 1 e) " Source Off" Switch: Controls movement of the source drawers to the * shielded stored position while operating in the manual mode. f) " Low Airfrimer On" Indicator Lamp , g) " Chamber Air" Switch: Allows air to be supplied to the chamber during irradiation. 6 r - .. - , kg 7' ] * A . ! f' _ w. w % , .. j .. . j - C. Pre-operational Checks ! '1. L Survey Meter ' : a) 7 Area Monitor: Area Monitor (AC) is used for surveying the radiation | level of the ~ area; it should not be moved firem its location. Check it for ! proper working order by performing the following checks: I ; (1) power check - AC power light "on" '; (2) response check -~ unit responds to background radiation of ' : - about 0.02-0.05 mrem / hour. )+ ' . . l b) Survey Meter: The Suivey Meter (DC) is used for surveying the i radiation levels around the operating unit. Check it for proper working .. i order by performing the following checks: - 1 , (1) battery check - needle deflects to BAT OK ' i . ._ (2) response check - unit responds to background radiation levels- t of about 0.02-0.05 mrem / hour. j q 2. Sample Chamber Drawer: ' Sample chamber drawer loaded with acceptable sample (s) [no corrosive,- j explosive, pyrophoric, or highly flammable material]; lid on tight (if ; necessary), sample air turned on (if necessary). 3. Timer Setting: ' Preset time of irradiation (if auto mode chosen) according to instruction manual. j , t 4. Air Compressor: Air compressor should be in operation if tank pressure is below 40 psi j! (and key is switched on). ! 1 1 !' D. Operation: Refer to Gamma-Cell opera, ting manual. ! ! E. Operational Checks , -| 1. Timer Operation: -! Check the timer for elapsed time countdown. If the timer is not j functioning properly, switch to manual mode, and self-time the irradiation. 'l Notify the Radiation Protection Office during normal business hours of the -j faulty timer. - : . 7 I 1 1 l t ; rg ~* :6:*- . .; . n- . A &, w ... . . * 2. Radiation Levels: Monitor area for radiation levels. The radiation levels at the location of the survey meter s'nould be below the alarm set-point of 2 mrem / hour. VI. RADIATION PROTECTION OFFICE PROCEDURES - A. Refer to Appendix A VII. TEST A. Complete the enclosed test (see Appendix D), and be prepared to discuss the answers during the training session. VIII. HANDS-ON EXPERIENCE A. Prepare for hands-on instruction by RPO. . 8 _ g * ' pg. j e : ,. , g ., * w y ' . . < 6 APPENDIX A ...: , : ' R3GULATIONS AND PROCEDURES FOR USE OF THE GAMMA-CELL 40 IRRADIATION UNIT - ' 1. Operauing Procedures ! a) Only persons approved by Dr Harvey Lodish or Dr. Richard C. Mulligan and. registered and trained by the Radiation Protection Office (RPO) will be authorized to operate the ; unit. ' b) The Gamma-Cell 40 unit'shall be operated and~ maintained in ' accordance with the AECL instruction manual. A copy of_the . manual shall be kept in the room (WI-232) housing the Gamma- ! Cell 40 unit. . c) No corrosive, explosive, pyrophoric or highly flammable' material shall be irradiated in the unit, d) The door to room WI-232 will be kept locked when the room is_ i unoccupied. Only persons authorized to operate the Gamma- 1 Cell 40 unit will have access to the key. ; l e) A log shall be kept in WI-232 of all use of the Gamma-Cell 40 j unit. Information recorded will include length of ! irradiation and name of operator, plus any unusual circumstances or occurrences. ' f) To minimize personnel exposure, operators should spend a minimum amount of time in the area immediately in front of the lock on the irradiation chamber door (approximately 10 mrem / hour.at 5 cm). 2. Emergency Procedures In case of an emergency, the use of the unit will be ! discontinued, the room evacuated, and the Radiation Protection Office notified by calling 13-2180. In particular,_ the . Radiation Protection Office will be notified for any of the following occurrences: a) Higher than normal radiation levels are detected or suspected. ! b) There is any reason to question the proper functioning of the ! AC operated area monitor. ' c) There is any indication of malfunction of the Gamma-Cell 40 unit involving radiation protection. A-1 L ^ . g . . ~ w .- . .. , v In the event that the Radiation Protection Office is notified of an emergency, qualified. RPO personnel will visit the Gamma-Cell 40 installation to determine the nature of the emergency. If the emergency involves a malfunction of the Gamma-Cell 40 unit, AECL will.be notified of the situation and the RPO assessment. Operation of the unit will be discontinued until repair has been completed by AECL or its authorized representative and the unit ; has been determined to be ready for safe operation by RPO. 3. Radiation Monitoring Requirements | Monitoring requirements for the Gamma-Cell installation will ; include the following three categories: Personnel, Gamma-Cell 40 room (WI-232), and Gamma-Cell 40 unit. a) Personnel: All personnel authorized to operate the unit will be provided with film badges by RPO. These will be worn ' whenever the person is in room WI-232. When not being worn, . the film badges will be stored in a location where they will ! be exposed only to natural background radiation. Prior to 7 authorization, all persons will be interviewed by a staff ' member of RPO, and registered as radiation workers. b) Gamma-Cell 40 Room (WI-232) : The ambient radiation levels in the room will be monitored by an AC powered instrument, supplemented as necessary by a battery operated survey meter. The instruments will be tested monthly by a member of RPO, and evaluated at monthly intervals. Film badge monitors will be installed by RPO, and evaluated I at monthly intervals. Monthly inspection surveys will be made by a member of RPO. c) Gamma-Cell 40 Unit: Wipe tests will be performed by a member . of RPO on the sample drawer cavity at intervals not to exceed j six months. , ! All personnel involved in the use of the Gamma-Cell 40 unit, and its radiation monitoring, will comply with the provisions of the above regulations and procedures. ! Mitchell S. Galanek Harvey Lodish, Ph.D. Associate RSO Radiation Safety Officer M.I.T. Whitehead Institute . A-2 y , ' , 1 - 3 /., . . A &- w i . . . . 1 , Appendix B ! i a ' i 6) , .. .. j~ ' 5; ; W :. .* - q .(, . ..n~ , . | : ,_ _ _ O ' ~ g ,f l' 9 % @ m . @ @ , 's ' @ 7, f- @ SW . - (n' I . - - h ,- . O u. u.cr, QD % N~ ' & ]' 9 @ -D< -Q CL CT '( @ u .. o c..,, ,u ,... q - s, @ ...... e g 1/c IN 9 ent x j.0 |N (2,suan } qg 1ArP[D H0tlD (3) ---. - - ' , * , , p M'53 * ., - x . . _(,1) N ' B @ q # ?.4 I . v. . * -(J) i 'N j ' . /--* g.J 2; -7- . ._g S i . . [O . s...... y~ + . h f q / '. ; u ------w--.^ a _ __3 ..____ u__ _ - . . .: {j . / . e:: SKID WIDT11 nort 1 Dirtusion$ iN eacxf15 ARE |26.375th(66.99)H'5" ',8, , ,* ',6"' 36.375 (92.3) i crut stiit Rs. FRONT 'I# 78' REAR PARTS LIST ] ttulANICAL Inf[Rt00. (CPf1R) 13 ACCES5/VENIltAflutt filBL (3) 22 (*/0FF SWliCH ' 2 AlitklA10R (UPPtR) 14 5AITLC DRAWER LOCX 23 SOURCE *0rt PUSH 0Gil0H SWito. 3 54r3'tt UvitY 15 5AtrtC OIArtiLR CAVl1Y RING 24 501,RCI *0FF" PUSHBul10M SWliCH 13.0 := (13.0 cal .i. 4.51 in (12.31 W DELP 21,.375 in (Lt,.9) 25 tinNuAL/Auf0 SELECTOR PUSIrgutinN Swit(N e. 5Arftt DRAW [R 1 RAY (A!!5 PLA5flC) 1.00 := (11.1) 26 Dir.!!At liftR 5. alt (NnAtuR (LOWIRI %.025 sa il4N.9) 21 DIArtLR AIR litDNINAftD PU'.IIPutinN 6 P1 ' HAWil AL If3'l RLOO- (t"dt81 30 IS '" (th 13 2b IlftR rRl/tuW AIR INDICAIDR LAff' / 501:PC1 *uM* P05111G3. 16 AIR CLRfRl5$0A E $10RAGL IAltK Willi CAUll 21 SAtrL[ Ovilt C0tt triA10R - t 50URCl lira 4 R CYtlNDI P (UPPtR1 11 PRL5tf VLMillAllGI VA14 Kf: Alti PRODUCI IM).lu-O';9. 1 SOURLt ' tis F* P0511 tim 18 fltilR (Cril(ptAL NOT ILLU51RAllDI 10 SL'URLL DRAW R CYliff'.A R tifWt R) 19 PRESSUltL 'QN'.lNr. 5Ul101 11 (tRitROL PAdtt & AIR PIILSSUltL RCGULA!UR 12 fDt A CABlt 10 t , i D ) 21 iUnRICAIna GAMMACELL 40 GENERAL DIMENSIONS B- 1 _ i ' Le - - . . a e * " * APPENDIX C , -e. , , Rev 7/94 L Whitehead Institute Gamma-Cell 40 Radiation Survey ~ . The following are results of the radiaiton survey performed in each area adjommg the irradiation room which houses the AECL Gamma-Cell 40 Laboratory Irradiator. See attached drawing for area locations. #- Imcation Exposure' Rate- Exposum (mR/hr)| .j(mR/hr) | Source Off Position - Source On' Position 1 Corridor < 0.05 < 0.05 2 Room 234 < 0.05 < 0.05 3 Room 234 < 0.05 < 0.05 4 Back room 230 < 0.05 < 0.05 5 Room 230 < 0.05 < 0.05 6 Bench top < 0.05 0.3 7 Front chamber door < 0.05 9.0 (@ 5 cm from door) 8 Left wall rm 232 < 0.05 0.1 9 Right side of GC 0.08 0.7 10 Back of GC < 0.05 1.0 11 Control Panel < 0.05 0.4 12 Mid-room 232 <0.05 0.3 Note: The highest observed dose rate was at the door to the irradiation chamber (10 mR/hr on contact with door; source in on postion.) C-1 , , . . :, e^ '* ._ , g g ~ " ' . Whitehead Institute Gamma-Cell 40 Radiation Survey WI-234 2 8 3 WI- 23 2 12 1 11 ' ' 6 9 Gamma-Cell 40 to . WI-23 0 (Not Drawn To Schle) C-2 _ _ _ _ > p6g g , . ; '' . .. g _ g i Q"oD4 *!| . . ' .w ; - c...,. > ; 7, .x j + 1 t APPENDIX.D ! ! , Whitehead Institute Gm=== cell Users' Ouiz | 'I ' i '1. - Radiation ' levels have been measured along the cavity door with - the source .in the rest position and in the irradiate position. -! ' The expected levels are ! arads/hr.with.the machine on,- i and arads/hr while the machine is.off. i 1,8 a.- .400-500, 50-60.- . | b. 100-500, 0-10. |~ c. 10-20, 0-1. d.. 500-1000, 10-20. - f, . . - - i 2. The annual maximum' permissible whole.-body dose to a radiation- worker is: j| | a. 3000 mram. b. 500 mrem. c. 5.0 rem. d.- 1.25 rem. 4 3. The maximum permissible whole body dose to a pregnant-worker' for the 9 month duration of pregnancy is- ' a. I 500 mrem. > b. 3000 mrem. ! c. 5.0 rem. ! d. 50 rem. l ! ! 4. If the alarm in the irradiator facility is sounding, you I should: , a. immediately evacuate the building. -; b. run through all the pre-operative checks to determine the | cause. I c. . continue your work as planned, the' alarm was falsely 1 sounded by an electrical surge. d. '|. turn off the irradiator, leave and secure the room, notify ' l * . R.P.O. 'l D-1 4 - 4 Y ' tp .--.y .-,s e,. , < _ . . M. . - - . . - . - - . . * ,r _ . _ . f? , , Ei ! Q- [ * - x. ;&_ '| . , h, '.;.. .. J: n . : *' - .. . ! -5.. The area monitor -in'the irradiator facility is set to sound an ; p alarm'if1the; dose rate exceeds: 1 i ^ a. 2 mrads/ min. { b. 2 mrads/hr. '; c.1 5,mrads/ min. > d. .5 mrads/hr.- | .i 1 ! 6 '. ' Match the.following. acute whole body. doses to thercorrecti 'l probable effect. , a. 0-25 rads 1. blood. changes, some injury, no' disability: . ~ b. 50-100 rads' '2. no obvious physical injury j c. 3. fatal within 60 days to 50% of those 450 rads f d. >600 rads receiving. dose- ! 4. 100% fatal- | ; ! 7. From the choices listed _ below,' select the material that should- 'I not be irradiated?in the'gammacell, i ~\ a. corrosive-and explosive materials. ; b. pyrophoric, highly flammable material. | c. metal containers. ! d. a and b only.. :| e. a, b, and c. j 1 i 8. When using the irradiator, the R.P.O. should be notified when:- ~l . . a. the survey monitor battery is dead. l( b. there-is any indication of malfunction' of the' Gammacell-40 | ' unit. l c. higher than. normal' radiation levels are detected during j operation. -j d. all of the above. ! ! ., 9. The source configuration used.in:the Gammace'll-40 is: ' '! I a. a. single "*Cs source located on'a sliding. drawer j . -directly above the-same cavity. _ . _ .; b. two "#Cs double encapsulated-sources housed in drawers, i one above and one below the cavity. ! ' c. 'a "Co single source located.on_a sliding; drawer directly- 1 above the sample. cavity. | L d. two "Co double' encapsulated sources - housed in drawers, one above and one below the cavity.- j{ J ! ? -i 5 D-2 i i ! | h - e - _ _ _ . _ . . . _ . _ .._.-.___..:. - __ . _ _ _ a . _ . - . _ , ,. _ . , . . _- ._ |hf f. , g A C w- ! + ! , ;, 7., . . t # j i M' .10. . -If there.is.a'- low pressure condition.in the Gammacell-40 -- j ' _ .for' example,..during., initial 2 machine start-up, the " low; air / timer.on"-indicator lamp lights up -- you should- ! ' ; a. leave and ' secure the roony contact-R.P.O. ! b.- turn the machine off and tay again later. .. ! ' c.; wait until-the correct intereal pressure has been. reached- a and ths' light-indicator turns off. -You can.then begin. , your. experiment. f d.- notify the building manager. li r i. 11.- Which of the following statement (s) is/are' correct: N . - ! a. The sample ~ cavity door cannot be opened when the source i , drawers are.in the irradiate position.. b. _ . . r If the sample cavity door is open, or.not comoletelv l closed,-the source drawers can be moved into the irradiate i position. ! c. both a and b. d. none.of the above. ! ; 12. . a Each sealed source in the Gammacell shall be tested'for ! leakage and/or contamination at . intervals not exceed i months. The test shall. be taken from appropriate ; accessible surfaces of the machine in which the sealed' source ; is permanently mounted. a. .3. -j b. 6. .i c. 12. i d. 24. ! ! ! 13. The Gammacell '87Cs source has a' half-life of , and ] emits X-rays with an energy of about . , a, 15.7 days, 1.117.MeV. ! b. 30.0 days, 662 MeV. ! c. 30.0 years, 662 kev. . i d.. -15.7 years, 1.117 MeV. l ! ! _r 14 . - On June 12, 1984 the Gammacell-40 contained two 87 , Cs sources | with a total activity of 3930 Curies. . What is the total .. I activity remaining 6 years later on June 12, 1990? ~j ~ .i a. 3421 Ci. ' b. 3241 Ci. .c. 3930 Ci. | d. 3583 Ci. ' i . ' D-3 i ) I i ) | ' . . . . _ , . . - - ,_ s , , . _ , e _ . - . , _ A . - -._.l.______-_.______. . - _ . _ _ 4. -w -4 . .; - 6 . 15. The dose rate at the center of.the chamber was measured to be 6.50'X 10 8 rads /hr on June 12, 1984. Using the data from . question #14, determine t* dose rate on June 12, 1990. a '. 5.66 X 108 rads /hr. b. 5.59 X 108 rads /hr. a. 7.47 X 108 rads /hr. a. 6.50 X 108 rads /hr. 16. If the dose from a source is 10 mrads/hr at 10 cm, what is the dose at 100 cm under the same conditions? a. 0.01 mrads/hr. b. 0.1 mrads/hr. c. 1 mrads/hr. d. 10 mrads/hr. 17. What primary shielding material has been installed in the Gammacell-40 to protect the operator? a. concrete. b. plexiglass. c. lead. d. polystyrene. 18. What instruments are used as area. survey monitors in the irradiator facility? a. Boron Triflouride neutron detectors. b. air ionization chambers. c. NaI scintillation detectors. d. G.M. survey meters. 19. The maximum dose rate deviation within the irradiation chamber from the center of the sample chamber to the outer perimeter is: . a. 5%. b. 10%. c. 15%. d. 20%. 20. If you remain in a room with a 0.5 mrad /hr dose rate for 15 minutes, what is your total whole body absorbed dose? a. 0.5 mrads, b. 0.05 mrads, c. 0.125 mrads, d. Background. D-4 . ,. _ _--- . _ ' g.ai $ . a. ' all authorized users' names are posted on the door. , b. a specified individual is responsible for the irradiator ! room key. . c. R.P.O. must be called prior to each use. ' d. a and b only. , e. a, b, and c. - r -22. All users of the Gammacell Irradiator must: , i a. log in. b. monitor the sample~ cavity after use. c. insure that the facility is locked when finished using the irradiator. ! d. all of the above. !. 23. You are standing in front of the . control panel of the ,irradiator. Under normal operating - conditions,' what dose : rate (mrem /hr) do you expect to receive with: a) the source in the irradiate position, and b) the source in the rest ' position? | a b a. 20 20 b. 50 f 10 , c. 80 50 * d. 10 0 ! 24. While using the irradiator, you discover higher than normal ; . background radiation. You phoned the R.P.O. and notified them of the situation. A wipe test of the area was taken- 2 over a 100 cm area. The scintillation counter measured 1000 ; CPM. The counter's efficiency for '87Cs was 10%. The ; background7 measurement was 100 CPM. The activity (in DPM) of the Cs on the wipe test per 100 cm2 was : : , - a. ! 90 DPM. ! b. 900 DPM. ' c. 9000 DPM. d. 1000 DPM. ! , 25. ! What is the activity, in microcuries -(yci), of the wipe ' result in question #24? a. 0.553 pCi. : b. 0.900 pCi. c. 0.243 gCi. d. 0.004 yCi. D-5 , I * ^ - , _ , , _ - _ _ _ _ _ - _ _ _ _ _ - , - - - . . . .. - . . . -- p:.: -;: . -~ +. -- - , .j. - p. . .+ f #| |g.- . . . . A' . ' ' .W [ 4.-? ;, .. o w:. t; < < i > + f ' ANSWER SHEET ! - ! -- ; ! ( ! L i : ) ! 1. ; - 12. , . . 2 .' 13. ! 3. 14.- ' , ! - t 4 '. 15. ~ ! ; 5.- 16. ' -6. A 17. * ' . r 5 - B 18 . - ' i C 19. i - : D 20. , . , 7. i 21. - i 8. r 22. I ; -9. 23. i 10. 24. j: , 11.- 25. ! t : - . . , ,f s P ! i Name:- Date: - ' -; f I .: ; i D-6 - t U.L 10 M i OFFICIAL RECORD COPY ~ , . * '" .-m i%w-,-. g.m e.me-..e -+i.-g ,=,-,,.r rw++ e - a,., e+w. , .m ca,n . e w. sew .-tw mv 9' - . . - .. . . . g - w . . . . . 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