ML20055H011
| ML20055H011 | |
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|---|---|
| Site: | 05000072 |
| Issue date: | 07/17/1990 |
| From: | Sandquist G UTAH, UNIV. OF, SALT LAKE CITY, UT |
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| NUDOCS 9007250046 | |
| Download: ML20055H011 (353) | |
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.t DECOMMISSIONING PLAN, .:
UNIVERSITY OF UTAII ' AGN 201M REACTOR No.107 License No. R 26 ,_
-/
Decket No. 50 72 10i l 1
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, ' July-17,1990 Prepared by: .1; Gary M. Sandquist '%*i:t John S. Bennion University of Utah '
Nuclear Engineering Laboratory
;- Salt Lake City, Utah 84112 i
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s p i!' Table of Contents u , l .0 P1an B aek gto u n d and Man a geme n t ...................................... ................ 1 1.1 S u mm ary D e s e ri p tio n . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . 1 Synopsis of the Decommissioning Plan .......................................... 2 1.2 Faeillty Ope ra tin g Ilis tory .... .. .... .-......... .. .. .. ... . .... .. .. .. .. ... . . . .. .. . . . 3 , 1.3 Rad 101ogica1 S tatus of the Facility ...............m.................................? 1.4 Decommisslonin g A1ternative s ................ ...- . .... ..... ....... ........... 5 1.5 Decommissioning Organization and Responsibilities ........... .............. 6 1.6 Regulations, Regulatory Guides and Standards ................. ............. 8 1.7 Tral nin g a nd Q u allfications . .. ....... ....... ...... . . .. .. . .. . . ... .. .... . . ..... . ..... . 9 2.0 Occupational and Radiation Protection Programs ...................................... 9 2.1 R adiation Fro te e t to n Program ................................ ........ .. ........ ... . 9 2.2 Industrial Safety and i1yglene Program ......................... ................10 2.3 Co n t ra c t o r A s s i s t a n c e .. . . ... . . . . .. .. . .. ....... .. .. . . .. . . . . . . . . .. . . . . . . . . .. . . . . . . . . . I 1 2.4 Co st E s timat e and Fu ndin g ...... ...... ........... ........ .... ... ..... ... ... ...... . I 1 3.0 Dismantling and Decontamination Tasks and Schedules .............................11 3.1 Tasks .................................................................................I1 3.2 Schedule ....................................................m...o..................I1 3 . 3 T a s k A n a 1 y s i s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12 3.4 Safe Storage ......................................................................12 4.0 S afe g u ard s a nd P hysical S ecurit y ....................... ..... ............ . ..... ........ 12 5.0 R aJlologieal Aecidents Analysis ........................................................,13
. 6,0 Radioactive Materials and Waste Management ........................................13 6.1 Fue1 Disposa1.......................................................................13 6.2 R adionetiye Wa ste Proce s sin g ......... ...................... ...... ...... ... ... .. 13 7.0 Teehnieal and Environmental Specifications .......................................... 13 g 8.0 Proposed Termination Radiation Survey P1ai. ........................................ 14 i
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Appendices ........................................................................................I8 ; Appendix A: Description of AGN 201M Training Reactor ........... ............ A 1 l I Appendix B: Fission Product Radioactivity of the Fuel ............................ A 7 Appendtx C: Qualifications and Training of Decommissioning Personnel ....... A 9 i Appendix D: University vf Utah Radiation Safety Policy Manual ...............A 10 Appendix E: University of Utah Safety and Health Manual ......................A 11 Appendix F: Decommissioning and Disassembly Procedures .................<. A 12 Concrete Block Surveillance Procedure r Form NEL 100: Radiation Survey Procedure for Reactor Components Form NEL 101: AGN Component Radiation Survey Rexd Form . Form NEL-103: Dismantling Plan for the UUAGN Reactor Form NEL 104: AGN 201 Reactor Defueling Procedure i i Form NEL 105: Procedure for Removal of AGN Control Rods Form NEL-106: Procedure for Removal of Ra Be Neutron Source I Form NEL 107: AGN 201 Reactor Defueling Checklist 27 September 1989 Memorandum to RSC Reporting on AGN Decommissioning Activities ! AppendixG: Outline of Procedures Regarding Reactor Safeguards and Physical Seeurity................................................................. A 13
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v Appendix H: UU AGN Technical Specifications ................................... A 14 t [ ii
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- List of Tables and Figures
;- Tables Table 1. Summary of AGN 201M Reactor Operations 1957 19 8 5 .................... 4 o
Figures q(- Figure 1. Map of University of Utr.h campus showing location of the Merrill Engineering Building which contains the AGN 201M nuclear reactor .................... 15 Figure 2. University of Utah Nuclear Engineering Laboratory floor plan showing location o f AG N 201 M n uct e ar te ac tor ............ ....................................... 16 Figure 3. Administrative organization for the University of Utah AGN 20lM nuclear teaef or decommissioning project ................................................. 17 Figure' 4. AON 201M reactor core can and contents ..................................... A 5 Figure 5. AGN 201M reaetot unit .......................................................... A 6 O m
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i i () n DECOMMISSIONING PLAN FOR THE UNIVERSITY OFUTAH AGN 20lM NUCLEAR REACIOR ) l I 1.0 Pla!LBackground and Management
,accon ce with 10 CFR 50.82, this dismantling and decommissioning plan is !
submit 4 to rr fort the University of Utah's request for authority to surrender License R- ; 25 volm, 5 and to decommission the University of Utah AGN 20lM Nuclear Reactor l' (UUAGh ' .d dispose ofits component parts. This plan des,cribes the organized means by which au radioactive or contaminated components wil! be removed and the facility will be decontamianted. 'Ihis plan provides reasonable assurances that the dismantling of the facility and the disposal of its component parts will be performed in accordance with the Code of Federal Regulations and will not be inimical to the common defense and security or to the health and safety of the public. The format cf this plan follows the outline proposed by the NRC Standardization ' f and Special Projects Branc b and includes infonnation on the facility operating history, the current radiological status of the facility, the dismantling alternatives under consideration, the dismantling organization and resynsibilities, the regulations and regulatory guides and standards that will guide the dismant.ing activities, and the qualifications of the dismantling l staff. The plan describes the dismantling occupational and radiation protection programs, the dismantling and decontamination tasks and schedules, the conduct of safeguards and physical security, radioactive materials and waste management, technical and environmental specifications, and the proposed termination radiation survey plan. 1y p L' In anticipation of dismantling operations, the special nuclear material (SNM) of the UUAGN reactor has been removed fmm the reactor core and is stored in the UUNEL fuel storage facility pending transfer of the SNM to the Department of Energy, owner of the fuel. The SNM will be shipped to DOE facilities under the existing operating license and in accordance with DOE, Nuclear Reguletory Commission, and Department of Transportation l requirements as soon as authorization for fuel transfer is received from DOE. As per 10 CFR 50.59 assessment, shipment of the nuclear material represents no unreviewed safety l questions and the fuel components will be shipped under the current license to keep radiation levels during the dismantling and decommissioning effort at the facility ALARA. . The UUAGN dismantling effort will be managed by the University of Utah Nuclear Engineering Laboratory (UUNEL) staff and the Radiological Health Department (RHD). Per this decommissiomng plan, UUNEL staff will be responsible for the safe conduct of the decommissioning efforts at the facility. The organization will consist of the UUNEL Laboratory Director, the University of Utah Radiation Safety Officer (RSO), and personnel associated with the UUNEL and RHD. It is anticipated that all UUAGN decommissioning i activities can and will be performed by these University of Utah personnel. In addition, all decommissioning activities have been reviewed and approved by the University of Utah Reactor Safety Committee (RSC). l i 1.1 Summary Descriotion , The University of Utah filed application on 1 June 1957 to acquire and possess an AGN 20lM nuclear reactor, Serial No.107, from the Aerojet General Nucleonics Corporation. The original license to operate the reactor was issued on 1 September 1957 for a maximum thermal power level of 100 milliwatts. Initial criticality was achieved on 16 September 1957. The license has been amended ten times. A few of the more significant 1 1 ,
73 amendments were Number 4, dated 3 January 1%2, which allowed operation of the reactor I ("/ at power levels up to 100 milliwatts in the newly constructed Merr 'l Engineering Building l following relocation of the reactor from its original location in e Fuel Technology ; Laboratory; Number 7, issued 15 July 1969, which increased the r Mimum power level of j the UUAGN to 5 watts; and Number 10, granted 2 June 197v, which extended the operating license to the year 1997. A detailed description of reactor is provided in j Appendix A. j As shown in Figure 1, the UUAGN is located in the Merrill Engineering Building ; (MEB) in the northeast part of campus. The Nuclear Engineering Laboratory (NEL), ; shown in Figure 2, is located on the 11rst floor of the MEB an;l comprises approxirnately j 2000 square feet of the southwest comer of the building. NEL rooms 1205 E, F, and -G j are maintained as restricted areas. Room 1205 E contains the AGN and an operational ; TRIGA research reactor (license R 126). Rooms 1205 F and O nre reserved for i radiochemistry operations and sample preparation. Room 1205 A contains a californium- l 252 irradiator and neutron generator. Room 1205 B is the office of the Director of the 1 Nuclear Engineering Laboratory. Room 1205 C is a dedicated low level counting area l reserved for vanous detectors and includes an intrinsic germanium spectrometer and a ; computer based multichannel analyzer for gamma radiation spectroscopy. Room 1205 D . contains the control console for the TRIGA reactor and serves as the office of the TRIGA i L Reactor Supervisor.
]4 All areas of the facility are under the control of the Director of Nuclear Engineering ]
and the Reactor Supervisor for the TRIGA reactor. Both are NRC licens. Jenior Reactor . Opemtors (SRO). ! O sv g i erts o e m mi i i 8 vi - , The selected decommissioning method is DECON in which the facility is 1 dismantled and any residual radioactivity of the reactor structure or its component I parts is removed or decontaminated to a level that permits the property to be released for unrestricted use. No other decommissioning alternative can be ) reasonably applied. Costs of the decommissioning project are expected to total ; ! $35,000, including the cost of the termination radiation survey Funding has been ) l committed by the University of Utah Administration. This decommissioning plan j appil:s only to the AGN reactor,its structure and component parts, and includes any wastes, radioactive or otherwise, that may be generated during the , decommissioning effort. All areas within the UUNEL site inclusive of the floor ; immediately beneath the base of the reactor stmeture and all drains and associated i piping will not be addressed in this plan as the UUNEL will remain licensed for l operations under the provisions of the TRIGA reactor operating ilcense (R 126) and ! l the University of Utah Broad Scope License (UT 1800001). The criteria for I unrestricted release shall be in accort ance with the recommended limits established in Regulatory Guide 1.86. Specifically, the exposure rate due to surface contamination shall be less than 5 R/h above natural background at a distance of one meter or less. Any components with residual radioactivity levels in excess of these criteria will be transferred to the Radiological Health Department for disoosal in accordance with all applicable federal, state, and local regulatlons. 1 Decommissioning activities will be performed under the existing radiatio'n safety I program to ensure that occupational exposures are kept ALARA. Further, these activities will be performed with an adherence to established industrial safety practices. All activities have been planned in advance and have been reviewed, and Q-. approved by the Reactor Safety Committee and will be completed within six months of receiving approval from NRC to proceed with decommissioning. No special L 1 2 e
b f3 '('j' equ,ipment, tools, or contractor assistance will be required and quality assurance reviews and audits will be conducted as needed by the RSC. All solid and liquid radimetive wastes generated during the project will be transferred to the RHD for disposal. The co lective dose equivalent to decommissioning personnel is
- anticipated to be less than 0.5 person-rem. A final report will be submitted to NRC requesting temtination of the UUAGN operating license following comptetion of a comprehensive termination radiation survey which will provide the bases for verifying that the facility meets prescribed radioactivity ;cvels that permits its unrestricted release.
L 1.2 Facility Onerating llistorv , The reactor was operated as a sub entity of various departments throughout its history, but was always used for the training of nuclear engineering graduate and undergraduate students. The reactor was generally operated in conjunction with a Nuclear Reactor Laboratory course taught during the Winter Quarter of each academic year and used primarily for perfonning basic reactor physics experiments. Prior to July 1969, the reactor was operated at power levels up to one hundred milliwatts for approximately 20 hours per year, thereby generating about two watt hours of energy per year. From July 1969 until final shut down in February 1985, the reactor was operated at power levels up to 5 watts and generated an average of 16.4 watt hours of energy per year. Operation at 5 watts required the construction of an eighteen inch thick concrete block shield around the reactor for additional radiation protection. . The total integrated power during operations over the entire lifetime of the AGN n reactor is ;iven in Table I. Operations from 1983 to final shutdown in February 1985 were U concernec with satisfying surveillance requirements of the Technical Specifications and generated negligible energy. Throughout the 27 years of active AGN o >eration, a total of approximately 287 watt hours (11.9 watt days) of energy was generatec during 473 hours of operation at critical. The reactor was' shutdown in February of 1985, and the facility has not been operated since that time. However, surveillance required by the Technical Specifications ' has been performed continuously since then. Dismantling of the concrete block shielding commenced in September,1987, as the first step in preparing the reactor for decommissioning. Each block was carefully surveyed for radioactive contamination or activation in excess of background levels according to a written ?rocedure approved by the
'.>niver:!ty's Reactor Safety Committee. More than 2700 b ocks were surveyed and transferred onto pallets for removal from the facility. Transfer of the block was completed !
on 25 March 1988 following a finalindependent survey conducted by the RHD. None of the blocks was found to be contaminated or exhibit radioactivity in excess of background levels. The reactor was defueled on 18 August 1989 in accordance with a detailed defueling plan which had been submitted to and a? proved by the RSC. Appendix B contains an estimate of the radioactivity of the fue, as a result of the fission products generated during operation of the UUAGN reactor. 1.3 Radiological Status of the Facility The UUAGN reactor was a polyethylene moderated, graphite refle'eted, water-shielded cord The reactor core consisted of a series of nine circular polyethylene disks,25 ; centimeters in diameter, containing a uniform dispersion of uranium oxide enriched to less (s than 20% U 235. Both safety rods and the coarse control rod contained the same fuel 3 material sealed in aluminum capsules, so that reactivity increased as rods were inserted into the reactor core. Extensive radiological surveys conducted in preparation of defueling 3 j
i showed no evidence of radioactive contamination due to activation of reactor components or the leakage of fission pmducts. Table 1. Summary of AGN.20lM Reactor Operations 1957 1985. Initial Criticality; 12 September 1957 Final Shutdown: 19 February 1985 Reacw Defueled: 18 August 1989
%r h rw.mt r - .v rw- A twan hourni 1957 negligible negligible 1958 88 4 8.86 1959 71.5 7.16 1960 22.6 . 2.26 1961 14.7 1.47 1962 16.5 1.65 1963 24.4 2.44 1964 19.9 1.99 1965 10.8 1.08 1966 11.6 1.16 1967 11.3 1.13 1968 22.4 2.24 1969 28.8 58.11 1970 19.0 38.19 1971 23.6 115.02 1972 10.0 8.00 1973 5.2 2.61 1974 7.7 16.62 6.57
- O.
1975 1976 4.2 9.0 2.00 1977 15.0 2.50 1978 10.5 3,40 1979 8.1 0.62 1980 12.1 0.72 1981 3.8 0.64 1982 0.7 0.11 1983 0.0 0.00 1984 0.0 0.00 1985 1.2 negligible 1986 present 0.0 0.00 Total: 473.3 hours 286.55 watt hours The 10 mci radium beryllium neutron start up source was removed from the graphite reflector and placed in a paraffin lined shipping container prior to removal of tne fuel from the reactor. This task was performed under the supervision of the RHD according to written procedure in order to keep radiation exposures ALARA during reactor defueling. Wipe tests of the scaled source gave no indication of any leakage of the source material. The start up source was transferred to the RHD on 31 August 1989 and subsequently shipped to RAMP, Inc. in Denver, Colorado, on 7 September 1989 for disposal at the U.S. Ecology site in Beatty, Nevada. With the removal of the source, defueling proceeded as per written procedure. Prior to removal of the fuel from the reactor, a gaseous sample was taken from the hermetically-sealed core can and analyzed for the presence of radioactive contamination No fission products were observed in the gamma radiation spectrum of the sample. Wipes of internal 4 I
I a ( fx components of the reactor adjacent to the core and on the exterior of the core can showed l t
") ' no evidence of contumination or fission product leakage. Therefore, the reactor core can i
was removed from the graphite reflector and placed on plastic sheeting spread over the floor of the reactor room to contain any possible release of radioactive material during disassembly. The fuel disks were taken out of the core can, inspected, surveyed, . Inventoried, scaled in plastic bags, and secured in two separate po,1yethylene containers with cadmium and borated paraffin to preclude criticality. Calculations performed by the Reactor Supervisor confirmed that the value of k, for the proposed storage array in the fuel storage pits was much less than 0.8 as required by the Technical Specifica6s. Fuel from ; the safety and control rods were similarly inspected, surveyed, mventoried, sealed, and stored in a steel barrel and secured in the fuel storage pits. Rasilation levels in the vicinity ; of the fuel storage facility have not increased noticeably since the fuel was moved into the > alts. The radiation levels around the reactor structure have dccreased to nominal packground levels since defueling and disposal of the Ra Be start up source. ; Upon removal from the reactor core and storage in the fuel storage pit, the fuel had ' an c.verage container surface exposure rate of 1.1 mR/h with a high rate of 1.8 mR/h and a low rate of 0.2 mR/h. The low exposure rate was indicative of the low burn up of the fuel , and the low flux in the reactor and the fact that the reactor had not operated since 1985. Because the flux and usage was so low, no measurable contamination and/or activation has been found in extensive radiological surveys performed by the RHD. A m!nor amount of fixed and removable contamination was, however, found on a few of the intemal surfaces of the reactor core that were in direct contact with the fuel material. Most of these components have been decontaminated and scaled in plastic. Components containing unremovable contamination or radioactivit - Guide 1.86 have also been sealed in plastic.y All com in excess ponents removed of defueling during the criteria provided in h,- procedure are stored in the thermal column tank wh:ch has been reinstallec in the reactor structure and rescaled. No further activity will be pursued until approval to decommission the UUAGN facility has been received from NRC. - Removal of the start up source and the fuel constituted tasks in which expcaure of personnel to radiation was unavoidable. Since the start up source has been transferred from UUNEL and only minimal handling of the fuel will be required in preparation of fuel transfer to DOE facilities, it is unlikely that significant radiation exposures to personnel will result from any of the remaining decommissioning activities. All personnel have been and continue to be monitored for radiation exposure with film badges provided by the RHD. Neutron detection badges were utilized by personnel during the start up source removal and , defueling procedures to monitor possible neutron doses. No radiation exposures in excess of nominal background levels have been reported by the RHD since the inception of this > project. The total radiation dose equivalent received by personnel as a result of the decommissioning project has been estimated to be less than 0.5 person rem. 1.4 Decommissioning Alternatives The University of Utah is seeking authority to surrender License R 25 and continue use of the facility under its current TRIGA reactor operating license (R 126). The University of Utah hhs selected DECON as the method for decommissioning the AGN ' reactor. All reactor equipment and stmetures containing radioactive contaminants will be decontaminated to levels that permits their release for unrestricted use. It is the~ intention of the licensee to remove all radioactive fluids, radioactive waste, and other materials connected with the mechanism, operation, and decontamination of the UUAGN nuclear O reactor and use the existing react r area for radioactive materials st rage and other activities associated with the operation of the TRIGA research reactor. All physical areas within the UUNEL including the floor immediately beneath the AGN base and all drains and 5
associated piping are not considered a?plicable to this decommissioning plan, but will be considered at such a time that the TR (GA reactor is decommissioned. Any materials or components not satisfying the conditions for unrestricted release will be retained in the UUNEL facility (restricted area) or transferred to the RSO for disposal as radioactive Waste. No other decommissioning alternative is reasonable because the reactor has not been used in over five years and is at present of no value to the University of Utah. The space occupied by the UUAGN could be better u>ed for other purposes and activities associated with the operation of the TRIGA research reactor and the UUNEL. 1.5 Decommiccinnina Orcanintion and Resnonsibilities The organization of responsibility for the UUAGN decommissioning is diagrammed in Figure 3. Individuals at various management levels are responsible for safeguarding the public and facility personnel from undue radiation exposures and for adhering to all requirements of the facility license. The assignment of specific responsi silities is described below. President . The President is the Chief Administrative Officer responsible for the University and its activities and is ultimately responsible to the Institutional Council in whose name the reactor facility license is made. Vice President for Research .The Vice President for Research is the Administrative Officer responsible to the President for all research facilities at the University, in this capacity, the Vice President represents the President in all health and safety O- matters pertaining to the reactor facihty. Director of the Nuclear Enrineerine Laboratorv The Director of the Nuclear
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Engineering Laboratory (DNEL) is the Administrative Officer responsible for the reactor facility and its operation, maintenance, and safety, in this capacity, the DNEL has final onsite authority ead ultimate responsibility for the reactor facility and, within the limitations m forth by the facility license, makes final policy decisions on all phases of reactor operation; appoints personnel to all positions reporting to him as described in the Technical Specificauons of the facility license; is advised in all matters concerning health and safety by the Radiation Safety Committee: and is advised in all matters concerning reactor safety by the Reactor Safety Committee (RSC). Reactor Safety Committee . The Reactor Safety Committee (RSC) is responsible for independent reviews and audits of facility operations to insure that the reactor is decommissioned in a safe and competent manner within the requirements of the NRC and advises the Vice President for Research in all matters related to reactor safety and personnel safety. The RSC holds periodic meetings and has the authority to conduct reviews Ard audits of facility operations. Badiation Safety Committee - The Radiation Safety Committee advises the Vice President for Research in all matters concerning the health and safety of personnel who might be exposed to radiation produced by University-owned and/or Joperated sources or equipment, This committee reviews, approves, and promulgates the University's Radiation Safety Program. This committee is ir. formed of all
'O rep rtable occurrences related t radiation health and safety and reactor safety which are reportable to any authorities outside the University, and advises the President of ,
6
i j g-b such occurrences and makes recommendations to the Vice President with regard to any such matters. l Reactor Administrator - The Reactor Administrator (RA) is the chairperson of the l RSC and is responsible to the Vice President for Research for insuring regulatory compliance of the reactor facility. In this capacity, and within the policies set forth j by the DNEL and the facility license, the RA prepares all regulations for the facility, reviews and ap aroves all procedures, seeks approval of all procedures and proposals i for changes anc 3xperiments fmm the RSC and the Radiation Safety Committee, and is responsible for the health and safety of all personnelin the facility. Reactor Sunervisor The Reactor Supervisor (RS)is a licensed Senior Reactor j Operator (SRO) and is responsible for the preparation, promulgation, and : enforcement of administrative controls including all rules, regulations, instructions l and operating procedures to insure that the facility has been operated and is being decommissioned in a safe, competent, and authorized manner at all times. Radiation Safety Officer - The Radiation Safety Officer (RSO) administers the University's radiation safety program and provides technical assistance to the Radiation Safety Committee and the RSC (the RSO serves ex officio as a member of each committee). The RSO is authorized and directed to promulgate and enforce j such procedures as are necessary to assure compliance with applicable federal and state regulations and to ensure the accurate inter)retation and effective implementation of the policies and rules established )y the Radiation Safety Committee. The RSO is the head of the Radiological Health Department (RHD) ] and oversees the activities of the Radiological Health Department Personnel. ; 3 (J Decommissioning Staff The decommissioning staffis responsible for performing decommissioning activities as directed by and under the supervision of the DNEL. The Director of the Nuclear Engineering Laboratory (DNEL) and the Radiation Safety Officer (RSO) will have overall responsibility for the actual performance of the ! decommissioning plan and clean up of the reactor site. The DNEL will be responsible for l the preparation of the final report to the NRC. The principal personnel for the decommissioning project include: ; Dr. Gary M. Sandquist, DNEL and AGN Reactor Supervisor l Dr. Keith J. Schlager, RSO l 1 Mr. Byron L. Hardy, Health Physicist (RHD) Mr. John S. Bennion, UUNEL Staff ! Qualifications and training of the above personnel relevant to the decommissioning effort 1 are summarized in rdsumds included in Appendix C. l Quality assurance will be the responsibility of the Reactcr Safety Committee which will review and audit the progress of the decommissioning project. No special equipment or tools will be required for the dismantling of the UUAGN facility. The current . membership roster of the RSC is as follows: I Dr. Dietrich K. Gehmlich, Reactor Administrator and RSC Chainuan Dr. Gary M. Sandquist, DNEL and AGN Reactor Supervisor Dr. Keith J. Schiaper, Radiation Safety Officer Mr. John S. Bennion Mr. James M. Byme Dr. Kevan C. Crawford l ~h Dr. Vern C. Rogers j l' 7 i
I All procedures associated with the execution of this decommissioning plan as well as the J decommissioning plan itself have been reviewed and approved by the RSC. Records of all surveys and procedures that have been accomplished to defuel the reactor and prepare the
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facility for dismantling have been audited by the RSO. 1.6 Rerulations. Rerulatnry Guides and Standards The dismantling operations will be govemed by the relevant federal, state, and local regulations, regulatory guides, and standards assoclated with nuclear research reactor dismantling, safety, radiological and environmental health, and industrial hygiene. These include the followmg: ,
- 1. American National Standard for Decommissioning of Research Reactors, ANSI /ANS 15.10-1981,
- 2. U. S. Nuclear Regulatory Commission Operating License No. R 2', Docket No.
407.
- 3. 10 CFR 50: Domestic Licensing of Production and Utilization Facilities 4 10 CFR 20: Standards for Protection Against Radiation
- 5. 10 CFR 30: Rules of General Applicability to Domestic Licensing of Byproduct Material
- 6. 10 CFR 71: Packaging and Transportation of Radioactive Waste
- 7. 10 CFR 73: Physical Protection of Plants and Materials
- 8. 49 CFR: Department of Transportation Regulations Governing the Transportation of Radioactive Matenals
- 9. U. S. Atomic Energy Commission Regulatory Guide 1.86, " Termination of Operating Licenses for Nuclear Reactors," June 1974,
- 10. " Guidance and Discussion of Requirements for an Application to Terminate a Non-Power Reactor Facility Operating License," Revision 1 U. S. Nuclear Regulatory Commission Standardization and Special Projects Branch, September 1984,
- 11. U. S. Nuclear Regulatory Commission Draft Regulatory Guide DG 1005, " Standard Format and Content for Decommissioning Plans for Nuclear Reactors," September 1989.
- 12. U. S. Nuclear Regulatory Commission Draft Regulatory Guide DG 1006, " Records important for Decommissioning Plans for Nuclear Reactors," September 1989,
- 13. International Atomic Energy Agency Safety Series No. 74, " Safety in Decommissioning of 'mearch Reactors," 1986. ,
- 14. Manion, William J., and Thomas S. LaGuardia, " Decommissioning Handbook," U.
S. Department of Energy, November 1980.
- 15. Konzek, G. J., et al., " Technology, Safety, and Costs of Decommissioning Reference Nuclear Research and Test Reactors," (prepared for the Nuclear 8
y y . . _ - - _ _ I l O Regulatory Commission by Pacific Northwest Laboratory), NUREG/CR 1756, C/ March 1982, and Addendum 1, July 1983. ;
- 16. " Radiation Safety Policy Manual," University of Utah Radiological Health Department, January 1990.
- 17. " Safety and Health Manual," University of Utah Department of Public Safety, Safety Services Division,1982. -
1 The University of Utah Research AGN 20lM Reactor will be dismantled and submitted for unrestricted release per the requirements s pecified in the above documents. Specifically, the UUAGN facility and its components will be disassembled and disposed of in such a manner that retained or released components will be within the contamination limits specified in Regulatory Ocide 1.86 and within 5 pR/h above background at one ' meter orless from the surface at the time of the termination radiation survey. Any materials or com )onents not satisfying the conditions for unrestricted release will be retained in the UUNE facility (restricted area) or transferred to the RHD for disposal as radioactive waste. All dismantling operations have been and will be conducted and executed in such a l manner as to comply with the princiales of ALARA in minimizing radiation exposure to the ; decommissioning personnel. Raclatiori safety during dismantling operatLons will be j assured through personnel monitoring, surveys, and procedures that have been reviewed i and approved by RSO and the RSC. All such operations will be conducted within the j scope of the existing radiation safety program. G V 1,7 Training and Oualifications All activities have been and will be perfomied by the DNEL who is also the Reactor Supervisor for the AGN-20lM reactor and the Radiation Safety Officer, both of whom are American Board Certified Health Physicists, and the staff of the UUNEL, as well as personnel from the Radiological Health Department. All personnel to be utilized are well- ' trained in the use of radiological equipment and decontamination work. Rdsum6s of the principal decommissioning personnel are included in the Appendix. 2.0 Occuentional and Public Safety and Radiation Protection Programs 2.1 Radiation Protection Program The radiation protection program will be in accordance with the regulations and guides listed in section 1.6 of this plan and the University of Utah Radiation Safety Policy Manual. A copy of the University's Radiation Safety Policy Manual is included in Appendix D. The responsibility for pro >er control of radiation hazards at the UUAGN rests with the Radiation Safety Officer. Radiation protection policies and procedures are established in accordance with University of Utah Radiation Safety Committee star.dards and include procedures for personnel monitoring, personnel dose limitations, environmental monitoring, radiation and contamination surveys, and radioactive material handling. ; All decommissioning activities will be conducted and executed in such a manner as to comply with the principles of ALARA in minimizing radiation exposure to the decommissioning personnel and will be conducted within the scope of the University's
-t. n]'
existing radiation safety pmgram. Radiation safety during dismantling operations will be 4 assured through personnel monitoring, surveys, and procedures that have been reviewed and approved by both the RSO and the RSC. 9
UUNEL maintains various radiation detection and survey equipment. Additional equipment it available as needed from the Radiological Health Department. This equipment includes a three inch intrinsic germanium crystal connected to a computer based multichanrel analyzer for gamma radiation spectrosco sy, gas proportional counter, a Ludlum M xiel 43-1 zine sulfide scintillation probe for alp ia pamcLe detection, scalers, and portable survey meters. 'Ihe portable survey meters consist of Technical Associates TBM-3S Contanination Survey Meters, Ludlum Model 19 Micro R Meters, and a Eberline Model E 5008 Geiger Counter. Sodium iodide and liquid scintillation detectors are also available,if needed. Gaseous or airbctne radionuclides are monitored by a continuous air monitor located in the exhaust duct of the facility's ventilation system. This calibrated system is designed to divert normal air flow through a HEPA filter before being exhausted from the facility in the event that elevated radiation levels are detected by the fixed radiation monitors located at various positions within UUNEL. No significant personnel exposures are anticipated since little contamination or activation has been found in preliminary surveys. Personnel exposures will be monitored with portable radiation detectors and individual film badges. 2.2 Indstrial Safety and Hveiene Prorram The decommissioning of the UUAGN reactor will be executed in such a manner that is consistent with all ap ricable OSHA and industrial safety requirements. The Safety Services Division of the Un versity of Utah Department of Public Safety is responsible for providing continuing accident prevention, momtoring environmental health, and providing advice and technical assistance for developing effective health and safety practices. Safety Services employees routinely inspect Umversity facilities and include an Environmental Safety Coordinator, an Industrial Hygienist, a Chemical / Biohazard Specialist, Fire Marshall, a Fire Prevention Specialist, and a Fire Safety Coordinator. These personnel are supervised by the Manager of Safety Services who is directly responsible to t le University Administration for promoting good health and safety practices within the University community. UUNEL decommissioning personnel are obliged to adhere to the health and safety practices outlined in the University's Safety and Health Manual. This manual contains general procedures for emergency response, laboratory safety, industrial safety, general safety, non radioactive hazardous waste disposal, and fire safety. Decommissioning personnel are familiar with the contents of this manual as well as other departmental safety regulations. A copy of the Safety and Health Manualis included in Appendix E. The most probable type of accident is that which might be called " mechanical" and might result from either human error or mechanical failure. The probability of human error will be minimized by making adequate preparation for the work and by following predetermined procedures which will be discussed in a briefing of all personnel before the actual work is commenced. The probability of mechanical failure will be minimized by thorough inspection of all equipment in advance ofits use. Exposure to airborne non radioactive particulates is not anticipated but will be monitored with a high volume air sampler Workers will be supplied with coveralls and gloves. Filter masks will be available and supplied as necessary. Chemical solvents may be required to reduce or eliminate removable radioactive contammation from certain reactor
- h. components. The use and disposal of non radioactively contaminated solvents will be in accordance with standard Umversity practices. Disposal of radioactively contaminated solvents will be in accordance with the policies of the RHD.
10
s-L 2.3 Contractor Atti=tance No contractor assistance is anticipated as all waste that needs to be discharged can be performed as part of the University s low level waste disposal program. No other special assistance :.s anticipated. 2.4 Cost Estimate and Funding - The University of Utah administration has committed to provide adequate financial support to ensure the safe and timely decommissioning of Jhe UUAGN reactor, it is estimated that the total cost of decommissioning will be less than $35,000 due to the fact that no contaminadon or activation of the reactor structure in excess of 10 CFR 20 and Regulatory Guide 1.86 limits have been found. This amount includes the anticipated cost of the temiination radiation survey. 3.0 Dismantling and Decontamination Tnes and Schedules The UUAGN dismantling plan will include those tasks rec uired to remove all radioactive components from the defueled UUAGN facility such t1at any components remaining within the facility at the time of the final survey will be within the contamination limits of the Regulatory Guide 1.86 and below 5 nR/h above background at distances up to one meter. A general survey of the area has indicated this is already the case. A copy, of the Detailed AGN Reactor Disassembly Procedure and other procedures followed dunng reactor defueling are included in Appendix F. 3.1 Tasks All fuel has been removed from the reactor and is stored in a NRC approved fuel storage facility pending transfer to the Department of Energy repository at Oak Ridge, Tennessec. The reactor start up source, Ra Be, has been transferred to the RSO and has been shipped to an approved disposal site. Specific tasks requiring completion in the UUAGN decommissioning project include:
- 1. tansfer fuel from site to DOE facilities,
- 2. sample, analyze, and drain the shielding water from the reactor tank structure, and document radiation levels of all reactor components,
- 3. disassemble,
- 4. decontaminate any ra survey,dioactively contaminated reactor components, and
- 5. dispose of all radioactive materials including any waste generated during decontamination.
The firial tasks will be the termination radiation survey of the UUAGN facility and the 1 reparation of the final report to the NRC requesting termination of the facility operating
.icense, in addition to any reactor components not meeting criteria for releases for unrestricted use, all waste generated during the removal of the fuel from the reactor core and subsequent decontamination will be transferred to the RSO for proper disposal.
It has been previously stated that the only contamination observed thus far occurred while defueling the reactor. Minor contamination was found on some internal surfaces of a few core components that were in direct contact with the fuel material. Since the Ra Be neutron start up source has been transferred from UU~NEL and only a minim:il amount of fuel handling will be required for fuel transfer, all subsequent decommissioning tasks will result in negligible radiation exposures to aersonnel. The collective dose equivalent to
'O. decommissionmg personnelis estimated to 3e less than 0.5 person rem.
3.2 Schedule 11
Further decommissionin activities beyond removal of the fuel from the reactor cort and transfer of the fuel to DOE will not be undertaken until approval to decommission the UUAGN facility is given by NRC. Transfer of the fuel to DOE facilities will occur as soon as approval to ship the fuel is granted by DOE. The remaining major decommissioning activities will be completed within six months of receiving approval from NRC to dismantle and decommission the UUAGN reactor facility. The termmation radiation survey will bc prformed and the final report requesting termination of the UUAGN facility operating
.icense will be submitted to NRC within twelve months of receiving decommissioning approval.
3.3 Tad Analysis There are no special health or safety considerations required in the dismantling or decommissioning of the UUAGN, Except for a few components that were in direct contact with the SNM, no radioactive contamination or activation of the structure has been found in extensive surveys; therefore, there will be minimal exposure to personnel. It is estimated that a radiation dose of less than 0.5 person rem will be received by decommissioning personnel. 3.4 Safe Storage There will be no requirements for safe storage since all radioactivity associated with the UUAGN reactor will be removed from the UUNEL. All components that were removed from the reactor during defueling have been scaled in plastic and placed in the thermal column tank for storage. The thermal column tank has been reinstalled in the reactor tank structure. These components will remain scaled within the reactor structure until NRC grants ap royal to decommission the UUAGN facility. The thermal safety fuse and the unitradiatec fission plate remaining in the UUNEL have been transferred to the University of Utah's Broad Scope License (UT 1800001); therefore, the UUNEL will
. remain under NRC license (R-126) and the Utah Broad Scope License when the UUAGN is finally decommissioned.
4.0 Safeguards and Physical Security The UUAGN fuel has been stored in locked fuel storage pits located in the controlled access area (CAA) of the UUNEL since it was removed from the reactor in August 1989, as allowed by the revised Physical Security Plan (PSP) which was approved by NRC on 10 July 1989. UUNEL is currently waiting for approval from DOE (fuel owner) to sVp the fuel to DOE's Y-12 Scrap Plant in Oak Ridge, Tennessee for final disposition. Pending fuel transfer, the SNM us periodically inspected and inventoried to ensure that the material is secure and has not been tampered with. In addition, periodic radiological surveys are performed to assure that the integrity of the fuel and its storage containers is maintained. All reactor components removed during the defueling process have been surveyed and scaled in plastic wrapping and placed in the thermal column tank. The thermal column has been reinstalled and rescaled in the reactor structure pending approval from NRC for decommissioning and disassembly of the UU AGN. Upon receiving approval for the fuel transfer, UUNEL will transfer the fuel in accordance with pertinent safeguards requirements of 10 CFR 73.67(g) and the facility's PSP. Thereafter, the only SNM connected with the UUAGN is the core fuse and an
. unitradiated fission plate, both of which have been transferred to the University's Broad Scope License. An amended PSP will be submitted to NRC following fuel shipment that will reflect the fact that all fuel from the UUAGN has been removed from the facility. An 12
- =
cutline of procedures for physical security of UUAGN SNM during decommissioning and
. dismantling is included in Appendix G.
5.0 Radiolocical Accidents Analvsis Due to the fact that all fuel 1.as been removed from the reactor core, the Ra Be neutron source has been disposed of and very little contamination and no activated materials have been found, no credible radiological accident can be postulated. 6.0 Radioactive Materink and Wace Management 6.1 Fuel Disnosal All fuel has been removed from the UUAGN reactor and is currently being stored in NRC approved locked fuel storage pits located in the reactor room, a controlled access area. The core fuse and an unirradiated fission plate will be retained by UUNEL for possible use in future experiments and have been transferred to the University's Broad Scope License (UT 1800001). The rest of the fuel will be shipped to DOE's Y 12 Scrap Plant in Oak Ridge, Tennessee as soon as DOE gives approval for fuel transfer. Final arrangements for the transfer are being made by DOE and it is anticipated that the fuel will be removed from UUNEL before 1 September 1990. 6.2 Radioactive Waste Processing No gaseous or airborne radioactive wastes have been observed in the UUAGN facility or are expected to be generated during the decommissioning process. A small L amount of aqueous radioactive waste (less than three gallons) may be generated in the decontamination of reactor components. A much smaller amount of radioactively contaminated chemical solvents may also result from decontamination efforts. Liquid wastes will be rendered into a form that facilitates disposal as directed by the RSO. Approximately 2 cubic feet of solid contaminated waste comprised of wipes, disposable gloves and arotective clothing, and drop cloths was generrited during the defueling procedure. Lt is anticipated that a total of less than 5 cubic feet of solid waste will be produced throughout the entire decommissioning project. All generated waste will be disposed of through the University's low level radioactive waste program managed by the Radiologicalllealth Department. . Except for a few core components that were in direct contact with the fuel material, 1reliminary radiological surveys have found no evidence of any radioactive contamination. Reactor components not in durct contact with the fuel material are not expected to be contaminated nor show any evidence of activation. Any reactor components which do not meet the unrestricted release criteria established in this plan will be transported to a low-level radioactive materials burial site in accordance with NRC and DOT regulations. 7.0 Technical and Environmental Specifications Since the reactor has been defueled, most of the operating license technical specifications are no longer 2pplicable. Nonetheless, no special changes in,the existing Technical Specifications for the UUAGN are believed to be necessary during the decommissioning project. Radiation monitoring is performed monthly as part of the general UUNEL facility inspections and surveillances. Pending transfer of fuel offsite, the AGN fuel will be secured in locked NRC approved fuel storage facilities located within the controlled access area of the UUNEL and maintained in an array such that kar is less than 0.8 for all conditions of moderation and reflection. While onsite, the fuel will be inspected 13
periodically to ensure that the matetial is secure and that the integrity of the fuel and its 1 containers is maintained. A copy of the current Technical Specifications is included in Appendix H. Experience gained durinJ the decommissioning of similar AGN reactor facilities (e.g., Oregon State University ;NRC License R-511, Memphis State University (NRC License R-127), and the University of Oklahoma [R 53)) has demonstrated that such activities may be successfully completed with only negligible changes in the amounts of effluents that may be released offsite and without any significant increase in individual or cumulative occupational radiation exposare. Because c ecommissioning of the UUAGN facility involves no significant hazard to the public or the environment,it is believed that no environmental impact statement need be prepared. 8.0 PropwA Terminadon Radiadon Survey Plan The proposed termination survey will include only the reactor tank and the component parts associated with the UUAGN reactor which are to be released for unrestricted use. Other areas within the facility are used under the terms of NRC License R 126 and the University of Utah Broad Scope License. Radioactive sources will still exist in those areas of the UUNEL. The tank will be marked off in one meter grids. The survey will include a wipe sample of 100 square centimeters taken within each square meter of the grid system to indicate removable contamination. A gamma sutvey will also be performed centered on each square meter of the grid system at a given distance from the sur' ace. Acceptable levels of exposure due to residual radioactivity will be limited to 5 R/h above background at a L distance of one meter from the surface being surveyed, Wipes for each grid location will be taken and counted foi alpha, beta, and gamma contamination. Limits for removable beta / gamma contaminatien will be 200 dpm/100 cm2 and 20 dpm/100 cm2 for removable alpha contamination as }'er Regulatory Guide 1.86. Results of the survey and the procedures used to obtain and analyze data will be audited by the RSO to ensure the accuracy and completeness ot *he data. UUNEL maintains varios radiation detection and survey instruments that will be used for the termination survey. Additional equipment is available as needed from the Radiological Health Department. This equipment includes a three inch intrinsic germanium crystal connected to a computer-based multichannel analyzer for gamma radiation spectroscopy, a Ludlum Model 431 zinc sulfide scintillation probe for alpha particle detection, a gas proportional counter for beta radiation counting, and portable survey meters. The portable survey meters consist of Technical Associates TBM 3S Contamination Survey Meters, Ludlum Model 19 Micro-R Meters, and a Eberline Model E-500B Geiger Counter, Sodium iodide and liquid scintillation detectors are also available, if needed. Allinstruments used for these surveys will be currently calibrated in accordance with approved University of Utah Radiological Health Department procedures. O 14
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l I 1 i i Figure 1. Map of University of Utah campus showing location of the Merrill Engineering l Building which contains the AGN 20lM nuclear reactor, O i l l I
l i f}- I NUCLEAR ENGINEERINGLABORATORY I AND ENVIRONS MERRE ENGNEERNG BUGING (GROUND FLOOR,SOUTHWESTCORNER) ,, 4 Thermal Science Laboratory West Side , , Building (1156) Exit (1205 G) North ) Heat Power Laboratory (1156a)
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- i. (1205 F) ..
- lu n n) u n llfill!!!Ill!!!mimiimimmuummum i TRIGA Supervisor
. A Counting Laboratory I ,,.
l EEEE !j ',,TRIGA l.i Control Room (1205 C) i 5
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(1205 D) ] Truck ) Loading . Laboratory Classroom ' Door C) (1205) N Reactor Room O (1205 E) - t . 1 AGN AGN Control ; Fuel Storage eacto j Console Pits Neutron Generator i: DNEL Office and l-(1205 A) Californium 252 ; (1205 B) : l l . South Door ! West Side .. L l '. Nuclear Engineering Laboratory Boundary . l
.]. Figure 2. University of Utah Nuclear Engineering Laboratory floor plan showing location of AGN 201M nuclear reactor.
16
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- \
! l President of the
- University of Utah 1
I 1 Vice President i l- for Rmah l L 1 O' oirecter ertac " ncie , Engineering Laboratory
.... ne cters retx Committee
...- a oietien seretx Committee r L
r l AGN Reactor Supervisor Reactor Administrator r- Radiation Safety Officer 7-I l Decommissioning Staff ------ - - -- .---------- -- !- Radiologicalllealth Department Personnel t Line of Responsibility l --.--- --.- -..--- --- . . Line of Communication Figure 3. Administrative organization for the University of Utah AGN 20lM nuclear c reactor decommissioning project. L 17
O O APPENDICES O 4 e O 18
l i n' l
/ i 'v') ;
APPENDIX A DESCRIPTION OF AGN 201M TRAINING REACTOR l i
- 1. . GENERAL DESCRIPTION l The AGN 20lM consists of two basic units, the reactor unit and the control console.
The reactor unit consists of the reactor surrounded by a graphite reflector which in turn is enclosed by lead and water shielding. Control and safety rods are installed vertically in the l i bottom of the reactor unit and pass through the shields and graphite reflector into the uranium polyethylene core. The control console consists of instruments and control 1 mechanisms for measuring the power level of the core and for actuating the control and l safety rods so as to provide safe and efficient operation of the nuclear reactor, q As an aid to a better understanding of some of the physical parts described herein, - drawings (figures 4 and 5) are supplied
- 2. ' DIE REACTOR UNIT _ j 2.1 Cmt .
r ,
~ \
The AGN 201 M reactor core is comprised of a series of disks formed from a mixture of polyethylene and UO2 (the uranium content 20% enriched in the isotope U 235). Figure 4 shows the assembly arrangement of the core within the core tank and its respective position with the graphite and control rod components. The estimated critical mass of the reactor is ap?roximately 660 gm of U 235. The e design volume of the core allowing for the void resu ting from the glory hole and the fuse assembly is 12,000 cm3 The core is loaded initially with a U 235 density of 54 mg/cm3 and will thus contain about 650 grams of U 235, 2.2 Core Tank Design The core tank has been designed to contain any fission product gases the might be given off by the polyethylene-uranium oxide core Sixty five mil commercial (61 ST) , aluminum is used throughout as the stmetural material. The core tank may be considered to be made of an upper and lower section, separated by an aluminum baffle passing through the core iri the same plane as the glory hole. The aluminum serves to separate the core into - two parts, and is part of the safety fuse system. Detachable top and bottom cover plates as well as control and safety rod thimbles form an integral part of the gas tight core tank (Figure 5). The lower section of the core tank contains one half of the core material as well as a
~
cylindrical section of graphite reflector. These pieces of core material and inner piece of graphite reflector are supported by an aluminum rod hanging from the fuse link which in n turn is supported by a telescoping aluminum tube which is screwed into the bottom cover g () plate of the core tank. Ample space at the bottom of the cylinder, coupled with a tapered graphite to graphite joint is provided to insure free fall of the bottom half of the core plus A1
. reflector section when the fuse melts in the event of an accidental nuclear excursion. The upper section of the core tank contains six of the core disks. A space for core expansion and gas accumulation is provided in the top section of the core tank. 2.3 Reflector and 1 nd Shield Desien The reflector consists of 20 cm of high density (1.7 'g/cm3 ) graphite on all sides of the core. Appropriate holes are provided for the glory hole, the two safety rods, the two control rods, and the four access ports. All of the components of this section of the assembly are easily accessible from the toa of the reactor. Ten centimeters of lead completely surrounds the oore, reflector, and tiermal neutron shield. 2.4 Reactor Tank The lead shielding, reflector, and core are enclosed in and supported by a S/16-inch-thick steel wall tank (47.5 cm radius). A removable top cover is provided. This tank acts as a secondary container for the core tank assembly, and with the glory hole and access ports closed,is gas tight. The control ruds and safety rods enter through the bottom of the reactor tank. The upper or " thermal column tank" serves as a shield tank when filled with water or thermal column when filled with graphite. 2.5 EaterTank The water tank is the third and outermost of the fluid tight concentric containers. This main structural member is 61/2 feet in diameter and constructed of steel. Access may be gained to the top of the tank even with water in the reactor tank by removing the top manhole cover plate. Another cover is provided at the bottom of the reactor tank over the control a::d safety rods, which serves to maintain the secondary gas tight seal. The fast neutron water shield is formed by filling the tank with about 1,000 gallons of water. 2.6 Safety and Control Rods The AGN 20lM reactor has two safety rods and two control rods. Each rod operates in a manner such that reactivity is increased as the rod is inserted. Two of the rods are used as safety rods and the other two rods are used as fine and coarse control rods. The amount of reaetivity each rod controls is nearly proportional to Se amount of contained active material. With the same uranium concentration in the rods as is used in the core, each rod contains 14.4 grams of U 235 and controls about 1.6% reactivity. The rods are lifted into the core by a pair of lead screws. The screws are coupled to the coarse and safety rods through an electromagnet. This allows decoupling when the scram signal is received. The fine rod is driven in a like manner but without the magnet coupling. It was felt that it controlled too little reactivity to be of practical value in a scram. The active length of each rod is 15 cm of UO2 embedded in stabilized polyethylene, the same composition as in the reactor core. This active fuel materialis enclosed in two aluminum containers, the outermost cover provides the gas seal from the core tank, and the innermno aluminum container seals the active fuelin the rod. By this design, a double ps tight seal is maintained for the control and safety rods as well as for the core. For small adjustments of the U-235 in the reactor, the safety and control rods offer a A2
1 i l -Q convenient method of adding or removing fuel. For safety reasons, the safety rods will V always contain at least 5 gm of U-235. When fuel disks are removed from the rods they are replaced by pure polyethylene disks. ,
)
2.7 Fusing System j The concept of the fuse in the AGN reactor is directly analogous to the electrical fuse ! used in every household. The reactor core fuse is made of polystyrene containing 108 ) 1 mg/cm3 of U 235 that acts as the su? port for the bottom half of the reactor core and a section of the reflector. The load on tus fuse is 15 kg. Most of the stress in the fuse is in i compression and sheer so as to circumvent any possible creep. problems of polystyrene in j tension. 1 The higher loading density is used to generate heat at a higher rate in the fuse than in the ; core such that the fuse rises in temperature about twice as fast as does the core proper. At about 120 oC, the fuse melts and the core separates completely, thereby shutting down the , reactor in the event of an accidental excursion. Polystyrene is used as the fuse material rather than polyethylene because of its resistance to changes in hysical properties induced ; by radiation. Experiments indicate that the melting point of p lystyrene is unaffected by i radiation doses below 100 megarep. Thus, the properties of t e fuse are not affected by several severe nuclear excursions, nor by normal operation for decades. Care has been taken in the design of the reflector plug to insure that the plug actually ! drops after the fuse melts. Ample clearance and the tapered design have been provided to insure a free fall. The separation of the core reduces the reactivity by at least 5%, and more likely 10%. 2.8 Safety Rod Oneration l The safety rods are in the safe or suberitical condition when they are in their outermost aosition. The total distance of travelis 25 cm. In the out position the active fuel in the rod s just inside the lead shield and partially in the graphite reflector. The rods are inserted one at a time by the drive mechanism 'Ihe maximum rate of travel inward is 0.46 cm/sec. The magnet release mechanism is constmeted in such a manner that if a scram signalis received during insertion, both rods are driven to their outermost positions.
= The safety magnets allowm, g the rodssystem to be accelerated is a " fail safe" outward design by both gravityin and that the spring scram signal open loading. ,
The spring constant is such that the rods are initially accelerated with a force of 5 g, i requinng a total withdrawal time of 150 milliseconds. The reactivity change of both safety rods is minus 0.7% during the first 45 milliseconds. The rods are decelerated by an air dash pot in the last 12.5 cm of travel. 2.9 Control Rod Operation Both the coarse and fine control rods are driven by reversible motors through lead screw assemblies which are controlled by switches at the control console. The maximum speed of travel of the rods is .46 cm/sec, yielding a maximum reactivity change of 3 x 104 sec-1 for the coarse rod. p The position of both control rods are indicated remotely at the control console. In the V event of a scram, the coarse rod is automatically and instantaneously moved out to its safe position while the fine rod is automatically moved out by reversing the lead screws until it A3
i i' . E is in its outermost position. Interlocks prevent their movement unless the safety rods are
" cocked". The safety rods cannot be cocked until the control rods have reached their safe or starting positions.
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( ~ ^~ b r,. s ) t,/ APPENDIX B FISSION PRODUCT RADIOACTIVITY OF THE FUEL The expected radioactivity of the UUAGN reactor core is computed from the operating . history of the reactor (Section 1.2). The total energy release vias 286.6 watt hours, over a time period of 27 years (1958 to 1985). The actual operating time over this 27 year period was 473.3 hours. For the purpose of this calculation, two different operating scenarios were assumed: j 4
- 1. Continuous operation over a 27 year period, at an average power level (1,212 x 10 3 W) determined by dividing the total energy release (286.6 watt hours) by the total time (27
- years).
- 2. Operation at maximum licensed power (5.0 W) continuously for 57.32 hours, ending on 19 February 1985, the date of final reactor shutdown, such that the total energy release is again 286.6 watt hours.
For both scenarios, a shutdown time of 5.4 years (19 February 1985 to 30 June 1990) is assumed after operation. For both scenanos, the following equation was used to calculate fission product activity in the core: 6 A = (1.4 x 10 ) P ,t.a2 - (t + T) a2 where A = total fission product activity (Ci) ! P = operating power level (MW) T = operating time (days) t = shutdown time (days) Results of the calculation are: . Seenario #1 Scenario #2 P (MW) 1.21 x 10 9 5.00 x 10 6 T (days) 9855 57.32 t (days) 1957 1957 .* A (Ci) 1.13 x 10 4 3.75 x 10 4 A (pCi) 113 375 Scenario #2 should represent an upper limit, conservative estimate of the fission-3roduct activity. The actual fission product activity in the core should be somewhere aetween the values calculated by Scenario #1 and #2; for future calculations in this section, however, the maximum, conservative value obtained from Scenario #2 will be assumed, it is relevant to compare the fission product activity of the core to the natural activity of the core due to the uranium present: A7
Natural Core Activity = (specific activity of U 235)(amount of U 235) + (specific activity of U 238)(amount of U 238)
= (2.16 pCi/gm)(660 gm) + (0.33 pCi/gm)(2700 gm)
- = 2317 Ci Thus, the ratio of natural core activity (2317 pCi) to fission product activity (375 pCi) is about 6.2 The dose equivalent rate from the fission products in the core can also be estimated.
Assume that the core is unshielded in air, and it can be approximated by a point source, rather than the actual cylindrical volumetric source that it,is. This should again be conservative, as no self-absorption within the source is assumed. Also assume that the fission Foducts yield one gamma ray of 1 MeV per disintegration. The point source strength, S, is then: 4 7 S = (375 pCi) 3.7 x 10 , dis , The point source flux, @, at 1 foot is then: 7 4, S (1.39 x 10 ) Y
, = 1188 2 2 4nr 4 (30.48)2 cm -see The dose equivalent rate, H, at 1 foot is:
$ H = 0.0576 @ E 'p
' p.'
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=(0.0. N1188)(1)(0.0300)
= 2.1 * *h Rom the above, it may be concluded that the fission-product radioactivity of the UUAGN presents no significant hazard beyond that of the unitradiated reactor core.
O A-8
I 1-t _f k APPENDIX C - OUALIFICATIONS AND TRAINING OF DECOMMISSIONING PERSONNEL x - s; e s t
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L sin.. i , t s te,v . 60) c.,,i..i - vit.., oi,.et , er te. u i . it er ut * ~ ,i NAME. . Gary Marlin SANDQUIST TITLES Professor of Mechanical Engineering at the University of Utah AND' Director of Nuclear Engineenng Pmgram at the University of Utah POSITIONS Licensed Senior Reactor Operator (U.S. NRC) Registered Professional Engineer (UT, CA, MN) Chief Nuclear Reactor Supervisor American Board Certified Health Physicist Nuclear Science Expert (United Nations - IAEA) Utah State Representative, National Council of Examiners for Engineering and Surveying (NCEES)
- Observer, Accreditation Board for Engineering and Technology (ABET)
Fellow of the American Nuclear Society BUSINESS Nuclear Engineering Laboratory, Mechanical Engineering Department,
. ADDRESS . Room 1205, Merrill Engineering Building, University of Utah, Salt Lake City, Utah 84112 USA TI '.EPHONE (801) 5817372,(801) 581-6441,' FAX (801) 581- 8692
' EDUCATION - B.5. 2.techanical Engineering, University of Utah,1960 M.S. Engineer Science, University,of California Berkeley,1961.
- h. ~ Ph.D. Mechanical and Nuclear Engmeering, Minor Mathematics, University '
of Utah,1964. Postdoctoral Fellow, Nuclear Engineering, Controlled Fusion Program, Massachusetts Institute of Technology,1969-70, EXPERIENCE Professor, Mechanical Engineering, University of Utah, July 1970 - present. Visiting Scientist, Nuclear Engineering, MIT, Sept 1969 - Aug 1970. Consultant to industry, state and federal govemment, and technical societies Chief Scientist for Rogers & Associates Engineering Corp..'1980 ' present Staff Scientist: Los Alamos Scientific Laboratory,1966 Idaho National Engineering Laboratory,1963 64 CONTRACTS Principal Investigator for 36 major R&D Contracts and Grants
& GRANTS with NSF, DOE, NIH, DOD, EPRI, NIH, HEW, NRC, etc..
PUBLICATIONS Published 107 refereed Journa! Artic!ce, prested 105 Technical Papers, authored 155 Technice.1 Reports and Articles in the fit.M of nuclear science, er:rgy, health physics, engineering and environmentai pudies. WORK Have 26 years of experience in nuclear sciences, radiation and health phy sics STATEMENT including extensive experience in regulatory matters with NRC, EPA and the Utah Bureau of Radiation Control. Familiar with radiation licen ;ing and application preparation 1 INI Il Ell ll
x y 0 O P RADIOLOGICAL HEALTH RECORD: '200 TRAINING AND EXPE Q M -(12/82) Radiological lhalth =12/20/82 re i t h .i schino c. ph n- Director (Title), (Department) (Date)
- (Name) ,
On-the Formal ' Duration ' Job Course TYPE OF TRAINING: - Where Trained A. Principles & Practices ~ALL FOUR SUBJECT AREAS WERE INCLUDED AT EACH INSTITUTION of Radiation Protection LISTED 8ELGl:
- .yes University of Washington 9 months (1356-57)
- 8. Radioactivity Measurement -
Seattle, Washington Standardization & Monitor- -(AEC Special-Fellowship in Radiological Physics) Ing Techniques & Instrunents Hanford Works 3 months (1957) yes - C. Mathematics & Calculattuns Richland Washington Basic to Use & Measurement of Radioactivity University of Mfchigan yes 3 years (1961-64) Ann ArSor, Pf fchigan D. Biological Effects of Radiation (Master of pus 11c Health Radiological Health Specialty,1962;Ph.D. in Envir EXPERIENCE WITH RADIATION: Duration. Typa of Use Isotope Naximum Amount Where Experience Gained
~
Argonne National Lab 4 years Health Phy'ics s operations in All megacuries s Biomedical, Radiochemistry. (1957-61) Hot cells Research Reactor, etc. Colorado State University 9 years Health Physics . training and All kilocuries research; University RSO (1964-73) _18 months Waste Management research'a'nd . transuranics kilocuries Los Alamos Mattonal Lab
. environmental surveillance University of Pittsburgh 3 1/2 years. Health Physics teaching and All millicuries research; Director. Industrial (1975-78)
Radiation Assistance Program CERTIFIED, 1964, AMERICAN BOARD OF HEALTil'PHfSICS; RECERTIFIED. THROUGil 1985
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IByron Lynn Hardy ' Health Physicist Radiological Health 11/21/89' ' (Name) . (Title)- (Department) (Date)' TYPE OF TRAINING:- -Where Trained Duration . ghe - {og A. Principles & Practices University of-Utah 3' yrs.:(1979-80) (1987-present) y,, . y. . .. of Radiation Protection Oak Ridge Associated Univ. 5 wks. (1982) ,
'Yes 11 professional.short courses 6+wks. (1978-89) Yes-B. Radioactivity Measurement University of. Utah- 3 yrs. (1979-80) (1987-present) -
. Yes .. Y 5 wks. (1982) Yes-Standardization & Monitoring Oak Ridge Associated. Univ. Yes:
Techniques ~& Instruments 11 nrofessional short-courses 6+wks. (1978-89) Rio Algon Corporationi ~3.5' yrs. (1981-84) -Yes C. Mathematics & Calculations. University of~ Utah .3 yrs. (1979-80) (1987-present) Yes- Yes_ Oak' Ridge Associated Univ. 5 wks. (1982) Yes.. Basic to Use & Measurement 'Yes-of Radioactivity 11 professional short courses 6+wks._(1978-89) Rio Algom Corporation 3.5 yrs. (1981-84) Yes University of Utah 3. yrs.-(1979-80) (1987-present) Yes' Yes-D. Biological Effects of Yes-Radiation Oak Ridge Associated Univ. 5 wks. (1982) 11 professional short courses 6+wks. (1978-89) Yes Note: All four subject types were. included in most programs listed above. Master of Science. Nuclear Engineering 't progress EXPERIENCE WITH RADIATION: . Isotope Maximum Amount Where Experience Gained . Duration TypeoffUse C-14, Cr-51 H-3, I-125 millicuries University of Utah (Dept. of BP&T) (10?S-79) Biochemical tracer studies.. P-32 All kilocuries University of Utah (Radiological (1979-80) University radiation analysis and Health) research.- U"*E and unlimited Rio Algon Corporation (1981-34) Uranium processing, radiochemistry daughters environmental surveillance. All megacuries University-of Utah'(Nuclear Engg.) (1987-present) Research reactors, neutron source.
e' John S. Bennion 1116 East South Temple #6 J Salt Lake City, Utah 84102 (801) 363 9477 EDUCATION: Master of Science - Nuclear Engineering (September,1990) University of Utah, Seit Lake City, Utah 84112. Bachelor of Science- Chemis (March,1987) University of Utah Salt e City, Utah 84112. Bachelor of Science - Chemical Engineering (March,1987) University of Utah, Salt Lake City, Utah 84112.
. CERTIFICATIONS:
En
- U.f.incer-in Training GraduateNuclear Regulatory Commission Licensed tI Senior
'\
HONORS AND AFFILIATIONS: Phi Kappa Phi National Honor Society , d
. Alpha Nu Sigma Nuclear Engineering Honor Society American Nuclear Society {
Health Physics Society (Great Salt Lake Chapter) j EXPERIENCE: h Senior Reactor Engineer (1987_- Present) Nuclear Engmeering Laboratory, University of Utah {' - . Responsible for the operation and maintenance of the University's 100 kW TRIGA Mark I nuclear reactor. Ensure operations are in compliance with all r H applicable federal, state, local, and university regulations. Maintain required; documentation of facility operations, expenments, inspections, equipment j repairs and maintenance. Perform tests and experiments for contracting ' organizations including sample irradiation, neutron activation analysis, gamma radiation spectroscopy and dosimetry, and neutron fluence rieasure-a ments. Member, Reactor Safety Committee (1987 - Present) University of Utah The committee is responsible for independent reviews and audits of facility . y operations to insure that the reactor is operated in a safe and competent manner within the requirements of the Nuclear Regulatory Commission. The committee advises the Vice President for Research in all matters related to reactor and personnel safety. Laboratory Assistant (1986 - 1987) Nuclear Engineering Laboratory, University of Utah Responsible for maintaining spectroscopy equipment and radiation ! monitoring station operated for the U.S. Environmental Protection Agency and general upkeep of laboratory. Assisted in reactor operations and experiments. AV Carpenter (1974 - 1986) Don Bailey Construction Co., Salt Lake City, Utah. Al Gittins Construction Co., Roy, Utah. Sessions Development Co., Inc., Jeremy Ranch, Utah. Residential and commercial construction. Rough framing and finish carpentry; concrete forming and finishing. Lead carpenter. ll J .
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APPENDIX D- ? 1 UNIVERSITY OF UTAH RADIATION SAFETY POLICY MANUAL i d 1:: m/ .
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{_ i t s 1 . i t UNIVERSITY;0F:: UTAH-- s RADIATIONLSAFETY POLICY 1 MANUAL; 4 F *' 6). i
; Prepared:and issued-under the auspices of' THE RADIATION _ SAFETY-COMMITTEE January-1990-i ,
t 1 s 1 For-' additional.information, contact THE RADIATION SAFETY OFFICER = Radiological Health Department G 100 Orson Spencer-Hall j .. 581-6141
TABLE OF CONTENTS PURPOSE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 EMERGENCY PROCEDURES ............................. 1 BASIS FOR RADIATION PROTECTION POLICIES . . . . . . . . . . . . . . . . . . . 2 Radiation-Induced Health Effects .................... 2 Principles of Radiation Protection ................... 3 Radi ation Doses and Risks . . . . . . . . . . . . . . . . . . . . . . . . 3 Individual Dose Limits .......................... 4 ALARA Policy ............................... 4 RESPONSIBILITIES ............................... 5 Radiation Safety Committee ....................... 5 Radioactive Drug Research Committee . . . . . . . . . . . . . . . . . . . . 6 Radiation Safety Officer ........................ 6 Radiological Health Department ..................... 7 Radiation Users . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 Responsible User ............................ 8 RADIATION SAFETY TRAINING . . . . . . . . . . . . . . . . . . . . . . . . . . 8 CONTROL AND MONITORING OF EXPO 5URES TO EXTERNAL RADIATION SOURCES . . . . . . 9 X-ray M *hines .............................. 9 Radioactive Materi al s . . . . . . . . . . . . . . . . . . . . . . . . . . 9 Exposure Evaluation and Monitoring ................... 10 Personal Dosimeters (Badges) ...................... 10 CONTROL AND MONITORING OF INTAKE OF RADI0 ISOTOPES . . . . . . . . . . . . . . 10 Handling Precautions .......................... 11 Contamination Surveys . . . . . . . . . . . . . . . . . . . . . . . . . . 11 Airborne Activity . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 Bionssays . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 Potassium Iodide ............................ 12 SERVICE FEES ................................ 12 Extraordinary Costs . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 Optional Services . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 Incentive Fees or Fines . . . . . . . . . . . . . . . . . . . . . . . . . 13 LABORATORY EVALUATIONS; SURVEYS AND AUDITS ........ ........ 14 CALIBRATION OF INSTRUMENTS ......................... 15 SEALED SOURCE LEAK TESTS .......................... 15 TRANSPORTATION AND SHIPMENT OF RADIOACTIVE MATERIALS ............ 15 RADI0 ACTIVE WASTE MANAGEMENT ........................ 16 BIBLIOGRAPHY ................................ 16 GLOSSARY .................................. 18
u . O UNIVERSITY 0F UTAH
; - RADIATION SAFETY POLICY MANUAL i
- Prepared and-issued under the auspices of-THE RADIATION-SAFETY COMMITTEE-January 1990 1
For additional information, contact THE RADIATION-SAFETY OFFICER-
. Radiological Health; Department-100 Orson Spencer Hall 581-6141 I
O
TABLE OF CONTENTS PURPOSE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 EMERGENCY PROCEDURES ............................. 1 BASIS FOR RADIATION PROTECTION POLICIES . . . . . . . . . . . . . . . . . . . . 2 Radiation-Induced Health Effects ..................... 2 Principles of Radiation Protection .................... 3 Radiation Doses and Risks . . . . . . . . . . . . . . . . . . . . . . . . . 3 Individual Dose Limits .......................... 4 ALARA Policy ............................... 4 RESPONSIBILITIES ............................... 5 Radiation Safety Comittee ........................ 5 Radioactive Drug Research Committee . . . . . . . . . . . . . . . . . . . . 6 Radiation Safety Officer ........................6 Radiological Health Department ...................... 7 Radiation Users . . . . . . . . . .................... 7 Responsible User ............................. 8 RADIATION SAFETY TRAINING . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 CONTROL AND MONITORING OF EXPOSURES TO EXTERNAL RADIATION SOURCES . . . . . . . 9 X-ray Machines .............................. 9 Radioacti ve Materi al s . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 Exposure Evaluation and Monitoring ................... 10 Personal Dosimeters (Badges) ...................... 10 CONTROL AND MONITORING OF INTAKE OF RADI0IS0 TOPES . . . . . . . . . . . . . . 10 Handling Precautions .......................... 11 Contamination Surveys . . . . . . . . . . . . . . . . . . . . . . . . . . 11 Airborne Activity . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 Bioassays . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 Potassium Iodide ............................ 12 SERVICE FEES ................................ 12 Extraordinary Costs . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 Optional Services . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 Incentive Fees or Fines . . . . . . . . . . . . . . . . . . . . . . . . . 13 LABORATORY EVALUATIONS; SURVEYS AND AUDITS ................. 14 CALIBRATION OF INSTRUMENTS ......................... 15 SEALED SOURCE LEAK TESTS .......................... 15 TRANSPORTATION AND SHIPMENT OF RADI0 ACTIVE MATERIALS ............ 15 RADI0 ACTIVE WASTE MANAGEMENT ........................ 16 BIBLIOGRAPHY ................................ 16 GLOSSARY .................................. 18
4 RADIATION SAFETY POLICY MANUAL O
. PURPOSE Detailed instructions for coping with radiation emergencies are prepared only '
fiis manual conveys the official policies for a few special facilities and a few of the University of Utah for the control categories,of emergency res,ponse person- , of all sources of, and exposures to, nel. The Emergency Guide in the front ionizing radiation that are within the of the Campus Directory provides general jurisdiction of the University. The instructions: on what to do- in various. manual defines responsibilities of kinds of emergency situations. individuals and organizations for radia-tion control, it specifies the policies Protect Peoplet that guide specific decisions on radiation control matters, and it provides general The first consideration in any emergency safety rules and procedures that are obli- is to assist injured persons and to pre-gatory for all users of radiation sources. vent any further injury. For medical Requirements and procedures not included assistance, dial 9-911 inmediately and in this manual are developed, promulgated report the nature of the illness or and enforced as necessary to implement injury. If the person may be contaminated the overall philosophy and policies for with radioactive material,-inform the 911 radiation protection as presented herein, dispatcher of the situation. If you are qualified to render first, aid, do so. Federal and state regulations require a without regard to the presence of radio-written radiation protection program, activity. There are no radiation soun:es. which includes provisions for keeping at the University that produce radiation s doses ALARA (see page 4). All radiation exposure risks large enough to prevent-users must be included in the program and giving first aidl, : Except for the usual must be informed of the program and of precautions for moving an injured person,. L their individual responsibilities. This individuals should immediately leave the j manual is intended to satisfy these regu- room or area until the extent of. the J 1atory requirements. radiological hazard hu been evaluated. However, all individuals should remain available in the vicinity until. checked ' f r contamination or exposure. EMERGENCY PROCEDURES HERSHICY TELEPHollE IMBERS Any accident, injury or loss of control Fire, W ance or of a radiation source that could cause an excessive or uncontrolled radiation ex- Medical Assistance: 9-911 posure to any individual is referred t as a radiation emergency. The proper Radiation Safety Officer: response to any radiation emergency depends upon a thorough understanding of Office Hours: 581-6141 the magnitude of risks, priorities for action and - the application of common All Other Times: sense. Each user of radiation sources should be familiar with the basic emergen- University Police: 581-7944 l
- cy responses listed below and methods for l
applying them in his or her own work area. RADIATION SAFETY POLICY MANUAL (1/90) - Page 1 h
Get Halot The RSO shall evaluate, record and report, as necessary, any radiation exposures to Each individual using radiation sources personnel, loss of radioactive material, should know in advance who to call in case or damage to radiation facilities result-of a radiation emergency. If fire, injury ing from the emergency. If required by or other emergency conditions in addition the RS0, individuals involved in a radia-to radiation are involved, first call the tion emergency shall submit specimens for appropriate numbers listed in the front bioassay, surrender personal clothing or of the Campus Directory. Then call the other articlos for decontamination or Radiological Health Department: extension assay, and pr svide pertinent information. 6141 during normal office hours; extension 7944 (University Police) during off-duty The Vice Prasident for Research is the hours. official spikesman for the University on matters per taining to radiation protec-When reporting any emergency, be sure to tion. Indi riduals involved in radiation state the exact nature of the emergency; emergencies should refrain from discussing then give your name and the phone number the event with anyone other than Univer-from which you are calling, the exact sity officials until after a complete location of the emergency (building, room, evaluation has been made. nearest entrance, etc.) and the name of the Responsible User, if known. Do not hang upt Let the person called end the BASIS F0R RADIATION conversation after all pertinent informa-tion is clearly understood. PROTECTION POLICIES Contain the Hazard! Ionizing radiation is capable of producing biological effects that are detrimental Any of the following actions appropriate to health. It is assunod that any radia-to the situation should be performed tion dose, no matter tow small, could orovided they can be carried out safely: produce some effect. The purpose of a radiation safety program is to prevent Cover containers of radioactive materials. unnecessary radiation exposures, and to control those that are necessary. Place absorbent material on spilled liquids. Each person who is exposed to radiation must be informed of the risks and of Close the sash on fume hoods, but do not appropriate protection methods, and must turn off hood exhaust fans. accept personal responsibility for using the available protection. Close doors to the area and post signs or guards to prevent unauthorized entry. Radiation-Induced Health Effects Allow no one to leave the area without Health effects from exposure to ionizing being checked for contamination. radiation may be stochastic (random in an exposed population) or non-stochastic Follow-un Arling (predictable for an individual). Any necessary decontamination or repairs Non-stochastic effects may be observed required after a radiation emergency shall in an exposed individual when a relatively be performed only under the direction of large radiation dose, exceeding a thresh-the Radiation Safety Officer (RS0). Re. old value, is received in a rather short entry or re-occupancy must be authorized time. A dose smaller than the threshold t.v the RSO. value will not produce the effect. Once l RADIATION SAFETY POLICY MANUAL (1/90) Page 2
4 I
.- the threshold dose for a particular effect For anyone who does not receive a direct is exceeded, the effect is almost sure to benefit, e.g. a salary, related to their occur, but the severity of the effect is radiation exposure, the individual dose proportional to the dose, limits are much smaller than those for radiation users. These "non-occupational" Stochastic effects are those that occur limits are based on comparisons with the randomly in an exposed population, usually ordinary risks of living, rather than on after a long latent period. Since these risks due to employment.
effects cannot be distinguished from those that occur in an unexposed population, the Radiation Doses and Risks cause-and-effect relationship cannot be
- established on an individual basis, but Radiation dose limits are specified in only on a statistical basis. For these units of millireas. The doses and related effects it is assumed that there is no health risks produced by non-occupational threshold dose and that the probability radiation exposures may be- helpful for of occurrence is proportional to the understanding the risks from occupational dose. However, the severity of the doses. In the U.S., the annual averate effect, if it occurs, is independent of whole-body dose from cosmic rays and othor the dose, natural sources is 100 mrem, the effective dose from radon in homes is' 200 mrem, Principles of Radiation Protection medical examinations contribute an average of 53 mrem and consumer products and other Two basic principles apply to every indi- manmade sources deliver another 9 mrem, vidual that may be exposed to radiation: for a total of approximately 360 mrem per (1) all radiation doses are to be kept as year.- In Utah, because of increased low as reasonably achievable (ALARA),and cosmic radiation and greater concentra-(2) no dose to an individual shall be al- tions of radioactive minerals in. the lowed to exceed the appropriate individual ground, the average annual dose is more dose limit. than 400 area.
The ALARA principle is applicable even The risk of fatal cancer from all causes, when the potential dose is well below the averaged over the entire U.S. population, individual- dose limit because it is is approximately 1 in 4, or 25%. It is assumed that some risk may be associated recognized, however, that certain sub-with any dose of radiation, no matter how groups, e.g. smokers or residents of small. ALARA also means balancing the large cities, have cancer risks that are benefits of dose reduction against social above average while other groups have needs and economic considerations, risks that are below the average. For most stochastic effects, a given dose of Dose limits are intended to limit the radiation is believed to increase the individualf s lifetime risk of stochastic baseline risk for a population group by effects from small chronic exposures as a constant fraction or proportion. well as to prevent nor. -tochastic effects , from large' doses. A continuous dose rate of 400 mrem per year for 70 years is estimated to con-For individuals who are exposed to ioniz- tribute 1% to the baseline risk of fatal ing radiation as a direct result of their cancer. The majority of radiation users employment, individual dose limits are receive occupational doses of much less based on the philosophy that their total than 400 mrem per year. An additional health risks should be no greater than the dose of 400 mrem per year for 20 years risks accepted by workers in comparable would increase the baseline risk by 0.3%. occupations or industries who are not O exposed to radiation. RADIATION SAFETY POLICY MANUAL (1/90) - Page 3
Individual Dese Limits ALARA Policy The primary occupational dose limit is i 9 University is committed to an effec-5,000 milliress per year, or 1,250 mrem tive radiation protection program to per calendar quarter, for the whole body, eliminate unnecessary exposures to radia-head and trunk, blood-forming organs, tion and to r9 duce all exposures to levels gonads and lens of the eye, that are as low as reasonably achievable (ALARA), taking into account all social The dose limit for members of the general and economic considerations. The ALARA public, including all persons who are not principle is a formal requirement of the classified as radiation users, is 500 U.S. Nuclear Regulatory Commission and ailliress per year, or 125 mrem per cal- the Utah Department of Health, endar quarter. No person shall be clas-sified as a radiation user simply to The ALARA principle is implemented by a just1fy a higher dose limit, comprehensive radiation protection program that includes specific requirements and F The embryo-fetus may be more susceptible procedures for: to radiation effects than an adult and is, I training of all radiation users, therefore, subject to a lower dose limit. 2 safety evaluations of proposed facil-The dose limit for the embryo-fetus is 500 ities or projects utilizing radiation mil 11 rams during the entire gestation in any way, period. As a further precaution, it is 3 regular surveys of work areas for advisable to keep the monthly doses below contamination and exposure rates, 50 millirems. This degree of protection 4 monitoring of radiation exposures to for the embryo-fetus can only be achieved groups and individuals, with the cooperation of the employee, who 5 investigations of all exposures that should notify her supervisor or the RSO exceed predetermined levels, and - as soon as the pregnancy is known. 6 audits of the program by the Radiation Safety Committee. RADIATION DOSE LIMITS t Dose Eauivalent farea) Portion of Body 8nnual Quarter Occupational Exposure of Adults: Whole body; head and trunk; active blood-forming organs; lens of eyes; gonads 5,000 1,250 Hands and forearms; feet & ankles 75,000 18,750 Skin of whole body 30,000 7,500 Exposure of Minors (under 18) in Restricted Areas: 10% of limits above Exposure of Any Individual in Unrestricted Areas: 500 N.A. Exposure of an Embryo or Fetus: 500 total 50/ month RADIATION SAFETY POLICY MANUAL (1/90) - Page 4
Each facility or program utilizing radia- Rules and procedures promulgated for use 9 tion machines or radioactive ma.erials must be justified on its merits and must within the University shall comply with the regulations and requirements of the be specifically authorized by the Radia- federal and state agencies that license tion Safety Committee. The review and and regulate radiation sources and uses. evaluation by the Committee covers the Technical assessments, evaluations and training and experience of individuals interpretations shall also be consistent authorized to use radiation sources, the with the guidance and recommendations of adequacy of facilities and equipment, and authoritative advisory bodies, such as the procedures for the safe use of radiation International Commission on Radiological sources. Protection, the National Council on Radia-tion Protection and Measurements, the Specific rules and procedures may be is- Comittee on the Biological Effects of sued by the Radiation Safety Officer (RS0) lonizing Radiation of the National Academy in support of the ALARA concept as well of Sciences and the American National as to assure compliance with all legal and Standards Institute. regulatory requirements. The RSO and supporting staff provide training, consul- Radiation Safety Commaittee (RSC) tation and other services to radiation users to assist them in controlling radia- The Radiation Safety Comittee (RSC) is tion sources and reducing exposures, the governing body for all aspects of radiation protection within the Univer-sity, including all affiliated research, RESPONSIBILITIES clinical, instructional and service units utilizing radiation sources in facilities The possession and use of radioactive owned or controlled by the University. The RSC will ensure that all possession, O materials and other sources of ionizing radiation are governed by regulations of use and disposition of radiation sources by University personnel complies with several federal and state agencies, and pertinent federal and state regulations by conditions of specific licenses issued and with the specific conditions of to the University. The Utah State Board licenses issued to the University, and of Regents delegates authority to the that all concomitant radiation exposures President of the University who appoints and empowers the organizations and indi. are maintained ALARA. viduals described hereinaf ter to develop, The RSC 1s empowered and directed to maintain and administer an effective promulgate policies, rules and procedures program for radiation protection, for the safe use of radiation sources. The University permits the use of ioniz- The RSC is responsible for assuring that ing radiation sources for beneficial only qualified individuals are permitted applications in teaching, research, med- to use radiation sources, or to supervise icine and comunity service only when ac, such use by others. The RSC oversees, quired and used in accordance with the reviews and audits the activities of the policies, principles and rules contained Radiation Safety Officer (RS0) and sup-in this manual. The protection of the porting staff, and all users of University health and welfare of each member of the radiation sources. The RSC reports to the f aculty, staff, student body and general Vice President for Research. The RSC may, public is of primary importance; however, at its discretion, establish subcomit-the financial, legal and societal obliga- tees to perform specific functions on tions of the University are also consid. behalf of the entire comittee. ered in the implementation of practical radiation protection practices. RADI ATION SAFETY POLICY MANUAL (1/90) - Page 5
The RSC must review- recommendations on The RDRC is composed of five or more ways to maintain individual and collec- individuals professionally qualified in tive doses ALARA. On the basis of safety, the use of radiation- in medicine and and with regard-to-training and experi- clinical research. The Chairperson of the ence, the RSC shall approve or disapprove RSC and the Radiation Safety Officer are any individual who is to be listed as the ex-officio members. The RDRC meets as RSO or as a responsible user in a new often as necessary to review and act on license application or request for amend- applications for use of radiation sources ment or renewal of an existing license, in or on human subjects.. The RDRC reports to the RSC in writing at least once each On the basis of- safety, and with the calendar quarter. advice and consent of the RSO and the management representative, the Committee Radiation Safety Officer (RS0) shall review and approve or disapprove The Radiation - Safety Officer (RS0) is
- minor changes in radiation safety proced-ures that are not potentially important the individual appointed to administer the to' safety, radiation protection program and to pro-vide technical guidance to the RSC and to With the assistance of the RSO, the Com- radiation users. The tenn "RS0" is also mittee shall review quarterly a summary used to mean any individual designated to of the occupational radiation dose records perfore certain functions on behalf of, of all personnel working with byproduct and under the supervision of, the RSO.
material, and shall annually review the radiation safety program. The RSO is authorized and directed to promulgate and enforce such procedures as A written procedure, available from the are necessary to assure compliance with chairperson or from the Radiation Safety applicable federal and state regulations Officer, specifies the membership, resp- and to ensure the accurate interpretation onsibilities, authority and operating and effective. implementation of the poli-rules of the RSC.. cies and rules established by the Radia-tion Safety Committee. The RSO is author-Radioactive Drug Rasaarch Cassittee (RDRC) ized to terminate immediately any project or operation that presents a radiological
-The Radioactive Drug Research Committee threat to health or property.
(RDRC) is empowered and required to evalu-ate and to approve or disapprove all The RSO must establish radiation expos-research and developmental uses of radio- ure investigation levels that, when ex-isotopes in humans in accordance with Food ceeded, will initiate a prompt investiga-and Drug Administration regulations. The tion by the RSO of the cause of the ex-
' RDRC also serves as the Human Uses Subcom- posure and a consideration of actions mittee of the RSC. In this capacity, the that might be taken to reduce the proba-RDRC evaluates and approves or disapproves bility of recurrence, all proposed uses of radiation machines or radioactive materials on or in humans The RSO is responsible for:
for investigational or nonroutine clinical procedures. The review of an application 1 maintaining copies of pertinent regula-for the use of radiation on or in human tions, license applications, licenses subjects is conducted by this subcommittee and amendments; only after the adequacy of the facilities and qualifications of the investigator 2 maintaining all records of the have been verified by the Radiation Safety acquisition, use and disposition of Officer. radiation sources within the juris-diction of the University; RADIATION SAFETY P01.!CY MANUAL (1/90) - Page 6
-9 p- 3 maintaining records of radiation moni- per quarter, as well as some who rarely :
' ('l toring and surveillance related to ex-posures of individuals from University receive more than 100 mrem in a quarter, but who work with sources that could controlled sources;_and produce a significant dose accidentally.
4 providing instruction and services to A " minimally exposed" radiation user is radiation users for the safe and auth- an individual who is unlikely to receivs orized use of radiation, one tenth (10%) of the occupational radia-tion dose limit in any calendar quarter. With' respect to the use of radioactive This category includes individuals who 1 materials, the RSO is responsible for routinely handle only small quantities of
. investigating spills, losses, thefts, un- radioactive materials, and others exposed authorized receipts, uses, transfers, only intermittently, e.g. most nurses, disposals, misadministrations, and other emergency and security personnel, main-deviations from approved radiation safety tenance, receiving, custodial and house-practice and implement corrective actions keeping personnel. I as necessary.
Each user must understand and follow the H The RSO reports to the Vice President general rules and procedures for working for Research on administrative matters safely with radiation sources as presented I and to the Radiation Safety Committee on in this manual. Each radiation user must technical matters. The RSO receives participate in radiation safety training direction from the RSC with regard to as specified by the RSO. policy and provides technical advice to the Committee, radiation users and the As a condition of employment, each radia-administration. The RSO shall brief tion user is required to provide certain management annually on the radiation personal information to the RSO. The t O. protection program. required information includes (1) primary identification data, e.g. full name, Radiological Health Department birth date, sex, and social security number; (2) previous training and experi-The Radiological Health Department is the ence with radiation sources; and (3) organizational, entity that provides the current employment status, including job administrative and technical services in title or description, department, super-support of the radiation protection pro- visor, and work location, gram. TheDirector(RS0)reportstothe Vice President for Research. Personal records of radiation users also + contain the scores obtained on tests-Radiation Users taker, to demonstrate knowledge of radia-tion safety procedures, data obtained A " radiation user" is any individual from monitoring of external and internal whose official ' duties or authorized radiation exposures, and reports on any activities include handling, operating, injuries or abnormal incidents related to < or working in the presence of, any type '
~
the use of radiation sources. Individual of radiation source, whether or not such radiation user records are treated as use is confined to a restricted area. confidential and are available only to , those with a legitimate need for the A "normally exposed" radiation user is an information. An individual may review the individual who could receive more than contents of his or her personal radiation one tenth (10%) of the occupational rad- user file at any time, and may obtain a iation dose limit in any calendar quart- summary of his or her radiation history er. This category includes individuals annually, or upon termination of employ-
- j. who normally receive more than 100 mrem ment, upon written request to the RSO.
L RADIATION SAFETY POLICY MANUAL (1/90) - Page 7 i-
Any. radiation user may communicate- di- e performing regular bioassays, ex-rectly, in confidence and without posure and/or contamination surveys prejudice, with the RSO or any member of and records as appropriate to the the Radiological Health Department, the nature of the radiation use and as Utah Bureau of Radiation Control or the specified by the RS0; U.S. Nuclear Regulatory Commission on any matter concerning radiation protection. f notification of the RSO of any accident, injury or abnormal incident Responsible User related to radiation sources; and A " responsible user" is an individual g arranging for authorization of authorized by the Radiation Safety Com- another individual to assume the pre- - mittee to acquire and use specific radia- ceding responsibilities, or to suspend tion sources, and to supervise such use or terminate all radiation uses, prior by others. An individual is designated to any extended absence. ' to serve as a responsible user only after: 1 providing to the RSC a detailed plan RADIATION SAFETY TRAINING for the proposed use of radiation sources including secure storage, safe handling, Each individual working with or in the control of exposures and appropriate waste presence of radioactive materials or disposal methods and updating such infor- other radiation sources is required to mation by means of periodic revisions or receive training in the applicable provi-renewals of the authorization request as sions of regulations and license condi-required by the Committee; tions, in the potential health problems 2 demonstrating to the satisfaction of d 'he '
$" precaution a cedures r quired the.RSO and the RSC that he or she has for safe use of radiation, and in the had sufficient training and experience in proper use of protective and measurement the safe use of radiation sources; devices. The extent of the training is to be commensurate with the potential 3 acknowledging and accepting in writing risk of radiation exposure to the indi-the responsibility for: vidual, a instruction in radiation protection "Normally exposed" and "potentially ex-practices for all personnel working posed" radiation users are required to with radiation sources and/or within have more extensive training than are facilities for which he or she is " minimally exposed" users. Because of the responsible; ongoing experience acquired by individuals working regularly with radiation sources, b acquisition of equipment, supplies retraining is not required except in and services necessary for the safe use unusual situations. Records of training of radiation sources; . for "normally" and "potentially exposed" c security against misuse or theft radiation users are kept ir9vidually with of radiation sources; their dosimetry recordi Since many " minimally e.aosed" users are d maintaining reasonably accurate only infrequently or intermittently ex-inventory records for all radionuc-lides, including acquisitions, uses, posed, and may not benefit from regular transfers, disposals and decay; experience with radiation protection, retraining on a regular schedule is re-quired. Records of training attendance for these users are maintained on a group RADIATION SAFETY POLICY MANUAL (1/90) - Page 8
h basis, since most " minimally exposed" survey, the potential exposure rates to users do- not have individual- dosimetry operators are evaluated to assure that records, they are- ALARA and that operators are monitored appropriately. - The primary responsibility for providing adequate training for radiation users During medical x-ray procedures, patients - rests with their responsible users or should be immobilized without being held, supervisors. - Generally, the responsible if at all >ossible. Never allow any part user or supervisor will fulfill this of the bocy of anyone but the patient to responsibility by assuring that each be in the primary x-ray beam. person attends the appropriate training
. program offered by the RSO. The super- During medical fluoroscopic procedures, visor or responsible user may also provide the primary source of exposure to attend-the training personally and submit a ing personnel is radiation scattered from statement to the RSO listing the individ- the patient. Since radiation intensity uals trained and the content of the decreases rapidly with distance from the training, source, it is advisable to step back from The' RSO is responsible for developing, conducting and documenting appropriate Even a little shielding is very effective training on radiation protection for all against the low-energy radiation scattered categories of radiation users. For each from the patient. If you must stay near category the RSO shall establish an ap- the patient, wear a lead apron.
propriate frequency and minimal require-ments for the content of the training Radioactive Materials
. program. The RSO shall maintain appropr-The O iate records of training offered and completed to assure compliance with regul-
- atory requirements.
intensity of radiation exposure decreases rapidly with distance from the source. Radionuclide sources that emit penetrating radiations should be stored away from regular work areas; they should CONTROL AND MONITORING OF be handled, when necessary, with tongs or f rceps to eliminate direct contact and EXPOSURES TO EXTERNAL to increase the distance from the source. RADIATION SOURCES Radionuclide sources that emit penetrating Sources that emit penetrating radiations radiations should be stored and handled (gam a and x rays, energetic beta parti- within appropriate shielding- whenever cles, neutrons, etc.) can cause radiation physically possible. For gamma and x exposures from outside the body. These rays, high-density materials, e.g. lead, 4 external exposures must be controlled by provide the most effective shielding. For appropriate shielding and by limiting the energetic beta-particle emitters, e.g. time spent in close proximity to the P-32, low-atomic-number materials, e.g.
-source. plastics, should be used as the primary shielding to minimize bremsstrahlung X-ray Rachines production. Radioactive materials should be stored in designated containers and X-ray machines, particle accelerators and locations when not in actual use.
other fixed radiation sources must be surveyed at least annually to verify adequacy of shielding, alarms, interlocks, and other safety-related apparatus or equipment. During the annual safety RA0!ATION SAFETY POLICY MANUAL (1/90) - Page 9 l
Exposure Evaluation and Manitoring All radiation users who are "normally exposed" or "potentially exposed" to External exposures are readily detectable external sources of penetrating radiation with portable instruments and personal are required to wear one or more personal monitoring devices (dosimeters). Radio- dosimeters. Users subject to general isotope work and storage areas should be whole-body exposures are issued " body surveyed for external exposure rates badges", which are to be worn on the whenever changes are made in the quan- front of the torso at all times while tities, locations or shielding of radia- working with radiation sources, or on the tion sources. The results of such surveys collar if a lead apron is worn. Females must be provided to all individuals work- subject to significant radiation exposures ing in the area to help them to control may be issued a second badge to be worn their own exposures, on the front of the abdomen under the lead apron. The purpose of the second badge Potential radiation exposures from any is to monitor the potential dose to the source, or within any facility, are evalu- embryo-fetus in the event of pregnancy. ated by the RSO to determine protection and monitoring requirements. In most Extremity dosimeters (finger or ring cases, exposures are evaluated for groups badges) are required when significant of individuals engaged in similar activi- quantities of radioisotopes that emit ties and exposed to comparable sources. penetrating radiations must be routinely In other situations, monitoring of handled directly, or when the hands or individual exposures may be necessary, fingers could be exposed accidentally to a high intensity source such as an x-ray Personal Desimeters (Badges) diffraction unit. A radiation dosimeter does not provide Radiation users who are " minimally ex-protection; it merely verifies, after the posed" to penetrating radiation from fact, the adequacy of the radiation con- external sources, i.e. those who are trol program. Also, radiation dosimetry unlikely to receive more than 100 milli-data are not, of themselves, appropriate rems to a major portion of the body or to determine risk to any individual; 1,000 millirems to the hands or fingers however, they can sometimes help an during any calendar quarter, are not individual to develop safe work habits. required to wear personal dosimeters. The primary purposes for performing When not being worn, dosimeters must be individual monitoring are: stored away from heat and radiation sources but they should not be taken home 1 to monitor the individual's radiation or worn away from work. All dosimeters environment and to evaluate the ade- must be returned promptly at the end of quacy of the radiation control program, the monitoring period. 2 to promote safe radiation working habits by individuals, CONTROL AND MONITORING 0F 3 to document radiation accidents, INTAKE OF RADI0IS0 TOPES 4 to satisfy medical and legal require- In research facilities, application of ments as are necessary to protect the the ALARA principle dictates that no employee and the employer, and removable contamination shall be tolerated indefinitely. Whenever contamination is 5 to comply with pertinent federal, state detected, it must be removed promptly to and local regulations. prevent its spread and the possible RADIATION SAFETY POLICY MANUAL (1/90) - Page 10
exposure of other individuals. Refer to (pipettes, pencils, etc.), by prohibiting ,
" CONTAMINATION LIMITS AND ACTION LEVELS" eating, drinking and smoking in radio- '
-(RPR 108) for specific limits required isotope handling areas and by careful responses, attention to personal hygiene. Gloves and other protective apparel should be used .
Each person who works with unsealed or to prevent contamination of skin and dispersible radioactive materials is personal clothing.
' responsible for:
Cantamination Surveys 1 knowing the basic properties of the radioactive materials to be used, e.g. the Surveys for contamination on the hands and
. half-life of the nuclide(s), the type (s) clothing must. be performed immediately of radiation emitted, the annual limit on after working with significant quantities ..
-intake (ALI) and any shielding that may of radioisotopes to assure detection and be required. removal before any radioactive material l w enters the body. Any radioactive material 2 being aware of actual or potential on the skin must be removed promptly by radiation exposures and keeping all normal washing. If it cannot be removed exposures to levels that are as low as easily, the RSO should be contacted to i reasonably achievable (ALARA). assist with decontamination. Follow the !
instructions in "RADI0 ISOTOPE LABORATORY l 3 following safe work practices and the SAFETY PROCEDURES" (RPR 11) for performing I instructions or procedures provided by the and reporting contamination surveys. l responsible user and the RSO. j Airborne Activity 4 the control and containment of radio-T~ activity and for performing regular sur- Inhalation of radioactive materials must voys of personnel, personal effects, be prevented by performing all operations equipment and work areas using methods that release or generate gases, vapors or that will assure the detection of con- dusts in approved fume hoods. In emer-tamination before significant exposures gency situations, filtered or supplied-air occur, respirators may be required to prevent inhalation of contaminants. Whenever the t 5 providing a~ urine sample, ootaining a probability of airborne contamination is i thyroid count, or wearing a personal significant, the RSO should be notified dosimeter as specified by the RSO. and air sampling may be required. 1 6 - recording the results of all radiation Bionssays ! surveys and screening bioassays promptly, completely and accurately. Although the emphasis of radiation protec-tion is primarily on prevention of expos-The responsible user must assure that the ures, measurement and evaluation of expos-necessary monitoring is performed, record- ures is also necessary. Bioassay is the ed and reported. ' Routine evaluations of determination of the kind and amount (and all radioisotope laboratories, including possibly the location) of radioactive surveys for contamination, are also per- material in the human body by direct (h
- formed by the RSO. y_tyn) measurement or by analysis h vitro of materials excreted or removed from the Handling Precautions body. Bioassay is an important tool for evaluating actual or suspected internal Ingestion of radio:ctivity must be pre- contamination with radioactive material s.
vented by avoiding mouth contact with any O items handled in a radioisotope Iaboratory RADIATION SAFETY POLICY MANUAL (1/90) - Page 11
Monitoring and dose assessment must be radiciodine, it is W totally risk free. performed f ar any individual with an Theriskofanadversereactionto$1is annual intal.e of all nuclides combined of estimated to be approximately 5 x 10 per 0.3 ALI or more. To assure that this dose (NCRP 1977). This is essentially the requirement is met in all cases, individ- same risk as produced by the ir.gstion of ual intakes of smaller quantities must be 300 nanocuries of iodine-125, or an uptate detected and evaluated at lower levels. of 100 nCi by the thyroid (ICRP 1977). The "810 ASSAYS FOR INTERNAL RADI0 ACTIVITY" procedure (RPR 12) specifies Conditions, Regular contamination surveys and thyreid frequencies and methods for performing monitoring have proven to be effective in bioassays to assure that an annual intake preventing unnecessary exposures to radio-of 0.1 ALI, whether as a single intake or iodine. Routine thyroid measurement.5 are as chronic or multiple intakes, is not capable of detecting approximately 10 nCi only detected, but determined quantita- in the thyroid and verification measure-tively. ments are required at thyroid burdens of 20-70 nCi, depending on the time since the Individuals who handle dispersible radio- last measurement. iodine compounds may be required to obtain J.D Y.112 measurements by the RSO of radio- Users should rely on careful handling iodine in the thyroid. Individuals who techniques to prevent unnecessary expor-handle other radioisotopes in dispersible ures to radioiodine. Under the nor.nal form may be required to pertona assays of conditions of contamination contro'. and radioactivity in urine on a routine basis monitoring required in radioisotope labor-to verify the absence of radioactivity in atories, the risk of radiation exposure the body or to determine the magnitude of is not sufficient to justify any additian-any exposure. Other types of assays may al risk from KI ingestion. be utilized if, in the judgement of the RSO, such assays will meet the intent of this policy more effectively. SERVICE FEES A bioassay is required whenever personal Routine radiation protection services are contamination or injury caused by a con' provided by the University to all radia-taminated object occurs, or if airborne radioactivity may have been inhaled. tion users. However, services that are not routine and that involve extraordinary Routine bicassays, at intervals determined costs are charged to the user incurring by the nuclides used, are required from the costs. Optional services, not recom-each user who handles more than minimal mended or required for radiation protec-quantities of soluble radionuclides. A routine bioassay may be waived when ap-tion, but provided upon request, will be propriate surveys for contamination, charged to the requesting user. For nonroutine and optional services, the fees conducted during and after each use of are intended to reimburse the actual radioactive material according to recom- service costs and to remove these items mended procedures, demonstrate that there was essentially no exposure to unconfined, from the University's base budget. dispersible radioactive material. Incentive fees, or fines, are imposed on Potassitan Iodide users who fail to meet certain obligations related to their use of radiation sources. Potassium iodide (KI) is not to be used ions nd 1 brary overd e book n for routine protection against the uptake they are not intended to generate revenue, of radiciodine by the thyroid. Al though but to improve compliance with radiation KI is effective if taken at about the same protection requirements. time, or shortly before, an intake of l RADIATION SAFETY POLICY MANUAL (1/90) - Page 12
4 Charges for nonroutine and optional serv- for failure to comply with certain re-O. ices are administrative decisions to be made by the Director of Radiological quirements. Health in consultation, or by negotiation, A late fee will be charged for each per-with the Vice President for Research and, sonal dosimeter returned after the spect-if appropriate, with the affected radia- fied exchange period for the month of use tion user (s). Incentive fees are program- but before the exchange period for the matic and are reviewed and approved by following unth. A lost fee will be the Radiation-Safety Cr,mmittee, charged for a personal dosimeter reading that is lost or invalidated because of Extraordinary Costs physical damage to or loss of the dosimet-
. er, contamination of the dosimeter with Any major cost item incurred unexpectedly radioactivity, exposure of the dosimeter by a single radiation user may fall into to radiation sources while it is not being this category. One example would be the worn as directed on the person to whom it disposal of exceptionally large volumes was issued, etc.
or activities of radioactive wastes in-volving special' handling or disposal A fee will be charged for each bionssay surcharges. Another example would be a result or sample not submitted to the RSO
- fine levied against the University as a within the interval scheduled for comple-result of gross negligence or willful tion of the assay. If an individual will violation of procedures by a user. The not be available for the bioassay within method of reimbursement will depend upon the scheduled interval, the late fee may
-the circumstances. be avoided by prompt notice to the RSO and a request to reschedule the bioassay.
Incentive fees are intended to be large Any supplies or services that are not enough to be significant to the individual recommended or required for radiation and to achieve the intended compliance protection, or that are normally the with monitoring requirements. The fees responsibility of the user but are provid- authorized by the Radiation Safety Commit-ed by the Radiological Health Department tee for each occurrence are-
?s a convenience to the user, will be ailled to the user at cost plus handling Personal dosimeters returned late but expenses. One : example of an optional resulting in a valid reading: $5.00 service is furnishing personal dosimeters to individuals who do not require personal Personal dosimeter readings lost or in-
. monitoring under the criteria containea validated due to damage, contamination, in' this manual. Protective- clothing, improper exposure, etc.: $10.00 equipment,-instrument repairs, etc. are other examples of services or supplies Bioassay results or samples not submitted that may be provided for the convenience within the scheduled interval: $5.00-of users.
When these fees are billed to the Respons-Incentive Fees or Fines ible User, the account number provided by the user for processing the Campus Order Procrastination or negligence on the part must not be a restricted fund, e.g. a of radiation users may result in viola- ledger 5 account. However, the Respons-tions of regulations or license conditions ibb user is expected to obtain reimburse-and/or additional expense to the Univers- ment to the account from the personal ity. To encourage adiation user * ;,o funds of the individual. fulfill their obligations in an appropri-O ate and timely manner, fees are assessed RA0!ATION SAFETY POLICY MANUAL (1/90) - Page 13
LABORATORY EVALUATIONS, the frequency of routine evaluations by the RSO or designee is based on the SURVEYS AND AUDITS " interval inventory" of all isotopes com-bined and the most restrictive bioassay The RSO shall ensure that all areas where interval. The " interval inventory" is the radiation sources of any kind are stored total quantity of radioisotopes introduced or used are evaluated with respect to into the lab in a month, averaged over potential radiological exposures and the bioassay interval, expressed in ALIs. risks, and that appropriate exposure The routine evaluation frequencies for control and monitoring measJres are used. various average monthly inventories are A pre-start evaluation is required before shown in the box below. radioisotopes may be initially introduced into a laboratory, or before a radiation- If no work with radioisotopes is being generating machine may be installed. done, and all radionuclides are stored in a locked location conspicuously labeled A routine evaluation may consist of only with a sign that requires notification of a survey for contamination or it may be the RSO prior to any further use of radio-a complete audit of all radiation protec- nuclides, the l aboratory may be considered tion devices, procedures and records. A to be inactive and need be inspected only special evaluation may be required as a annually. result of an accident or unusual incident. When use of a room or facility for radia- The nominal survey frequencies given in tion work is terminated, a close-out tha box are to be interpreted as guide-evaluation is required to assure that all lines. In cases where continuing con-conditions for an unrestricted area are tamination problems are found, the inter-met, with particular emphasis on removable val between surveys will be shortened. contamination. If survey results obtained over a period of a year indicate no contamination or Laboratory evaluations shall be performed exposure problems, the routine survey by technically qualified personnel using interval may be increased. In no case, instruments appropriate to the nature of however, will the interval be more than the radioactive materials to be detected double the nominal interval. To assure or radiation exposures to be measured. a realistic and independent evaluation of typical conditions, the schedule for For radioisotope laboratories, i.e. those surveys may be varied randomly. where dispersible radioisotopes are used, ROUI'INE RADI0 ISOTOPE LABORATORY EVALUATIONS Interval Inventory
- Nominal Frecxxy
>30 ALIs Monthly 1-30 ALIs Each bioassay interval
<1 ALI Semi-ar'ually Inactive ** Annual iy
- Monthly average during interval.
** See text.
l l RADIATION SAFETY POLICY MANUAL (1/90) - Page 14
?
4
,OALIBRATION OF INSTRUMENTS using procedures approved by the Radiation 1
O ? Portable radiation survey instruments in Safety Officer. Records of sealed source leak tests are maintained by the Radio-
, active service are calibrated annually, logical Health Department.
or following repair, by personnel of the Radiological- Health Department using procedures in " CALIBRATION AND USE OF TRANSPORTATION AND SHIPMENT PORTABLE SURVEY INSTRUMENTS" (apa 52). Instruments for measuring exposure rates 0F RAD 10 ACTIVE MATERIALS , are calibrated for linearity of response on all useful ranges. Instruments used Radioactive materials of any kind may be ' for contamination surveys are calibrated transported -on public roads on or off for- detection efficiencies for various University property only if packaged and nuclides, as weli as for linearity of labeled in compliance with U.S. Department response. of Transportation (DOT) regulations. Radioactive materials may be shipped from , Dose calibrators are checked for linear. the University to ancther organization or ity, geometrical variation and accuracy individual only after verification by the at the time of installation. Linearity RSO that all transfer, packaging, labeling tests are performed quarterly. The and transportation requirements have been accuracy and precision of each dose cali. met. brator is checked daily with N8S-traceable Co-57, Ba-133 and Cs-137 standards. The To assure that all requirements for ship- i
~ daily readings are recorded on a log ment are met, and that appropriate records l sheet; if not within 5% of the comparable are maintained, a written authorization readings obtained - previously, the form and one or more check' lists must be
,O instrument is adjusted, recalibrated or prepared by the individual responsible for
(> removed from service for repair. All the shipment and approved by the RSO before the shipment is made. The instruc-
- appropriate tests will also be repeated following repair or adjdstment of a Calib. tions and forms for various applications rator, depending upon the nature of the are contained in Radiation Procedures and i: adjustment or repair. For specific _ Records related to those applications.
instructions, see "RADI0 PHARMACY" (RPR IranSfers of radioactive materials betWeen ' 20), the University and the Veterans Adminis-o tration Medical Center are recorded on "UU-VA RADI0 ACTIVE MATERIAL TRANSFER" (RPR - j SEALED SOURCE LEAK TESTS iss). Instructions for " SHIPMENT OF LIMITED QUANTITIES OF RADI0 ISOTOPES" are p' contained in RPR 14. Transfers of radio-- : Sealed sources of radioactive material active wastes from non-University gener-- ! shall be: tested for leakage at regular ators to the University are recorded on intervals to verify the integrity of the " MANIFEST AND RECEIPT FOR RADIOACTIVE source containment and, in the unlikely WASTE" (RPR 540). For all other transfers event of failure, to detect the escape of or shipments, the instructions and forms radioactive material before serious con- are contained in ' TRANSPORTATION OF
. tamination of. facilities, equipment or RADI0 ACTIVE MATERIAL" (RPR 55).
; personnel occurs. The frequency of leak
' tests, and the sensitivity of detection of escaping radioactivity, shall comply with the regulations or license conditions specified by the agency authorizing the possession of the aurce. Leak tests are to be performed by qualified individuals l
RADIATION SAFETY POLICY MANUAL (1/90) - Page 15 L
r RADIOACTIVE WASTE MANAGEMENT Protection of the Thyroid Gland in the Event of Releases of - Radiofodine, Report 55 (1977). Radioactive wastes (radwastes) shall be collected, stored, packaged, shipped and-disposed of in accordance with all per- Operational Radiation Safety Program, tinent state and federal regulations. The Report 59 (1978). RSO shall prepare and maintain procedures for handling radwastes that will ensure Management of Persons Accidentally Con-the protection of the employees involved taatnated with Radionuclides, Report in such duties and keep all radiation 65 (1980). exposures ALARA. Specifications for segregation and packaging of radwastes Operational Radiation S $ ty - - shall be based on specific regulations or Training, Report 71 (1983). regulatory guidance, and include a record-keeping system that will allow complete Radiation Protection and #easurement tracking and accounting for all radwastes for los Voltage Neutron Generators, shipped to a disposal site or disposed of Report 72 (1983)'. 1 , Refer *RADI0 ACTIVE MASTE General Concepts for the Dostaetry of Internally Deposited Radionuclides, Report 84 (1985). 8IBLIOGRAPHY Use of Bionssay Procedures for Assess-ment of Internal Radionuclide International Comudssion on Radiological Deposition, Report 87 (1986). Protection (ICRP): Reconnendations for Limits for Exposure Reconnendations of the ICRP, Pub 1. 26 to ionizing Radiation, Report 91 (1977). (1987). Limits for Intakes of Radionuclides by g,s, nuc1 ear Regulatory Commission, Code Workers, Publ . 30 (1979-88). of Federal Regulations, Title 10 (10 CFR): General Principles of Monfioring for Notices, Instructions and Reports to Radiation Protection of Workers, Publ. Workers; Inspections, Part 19. 35-(1982). Radionuclide Transformations: Energy Standards for Protection Against Radiation, Part 20. '
-and Intensity of Entssions, Pub 1. 38 (1983). Rules of General Applicability to Individual Monitoring for Intakes of Domestic Licensing of Byproduct Material, Part 30.
Radionuclides by Workers: Design and Interpretation, Publ. 54 (1988). Specific Domestic Licenses of Broad Scope for Byproduct Material, Part 33. National Council on Radiation Protection .and Measurements (NCRP): Human Uses of Byproduct #aterial, Part 35. Review of NCRP Radiation Dose Limit for Embryo and Fetus in occupationally Packaging of Radioactive Material for Exposed Women, Report 53 (1977). Transport and Transportation of Radio-active Material under uttain Conditions, Part 71. l RADIATION SAFETY POLICY MANUAL (1/90) - Page 16
g-Utah Department- of Health,' Radiation Control Rules:-
' Standartis ' for Protection Against Radiation, R447-15.
General Requirements Applicable to the Insta11stfon, Registratton, inspectton and Use of Radiation Machines,-R447-16. Notices, Instructfans and Reports to Workers by Licensees or Registrants - Inspections, R447-18. Specific Licenses, R447-22. Use of X Rays in the Healing Arts, R447-28.
-Medical Use of Radianctive Material, R447-32.
Radiation Safety Requirements for
. Analytical X-Ray Equipment, R447-40.
Radiation Safety Requirements for O Particle Accelerators, R447-44.. O - RADIATION SAFETY POLICY MANUAL (1/90) - Page 17
f l \ ! GLOSSARY Quantities of radioactivity of biological l l or environmental interest are commonly < M AM AMRNIATIMS expressed in submultiples of the curie: t 7
]
The basic premise of radiation 1 millicurie (mC1) = 3.7 x 10 s'1 AL S : protection, i.e. that all radiation doses 1 microcurie (A i) = 3.7 x 10 4 s.3 , should be kept es Law As Seasemably 8
- 2.2 x 10 min *8 (dps) '
&chievable, taking into account social I and economic considerations, through the 1 nanocurie (nC1) = 37 s.i = 2,220 dpa l
application of sound radiation protection 1 picoeurie (pCi) = 0.037 s'l = 2.22 dpm ' t s, procedures and engineering
- The new international standard unit for .
activity is the becquerel (84) , ALI: The 4Mual Limit en latake is the 1 Bq = 1 transformation per second. ) quantity of any radionuclide which, if taken into the body, produces an effec- %re er: either to absorbed dose or to doseDose{ tive dose to internal organs that is ' equivalent ir risk to the annual whole equivalent, depending upon the context and the units used. body dose limit of 5 rens. Because of ; differences in physiological transport : i mechanisms, the ALIs vary depending on Absorbed dose is the mean energy per unit ! the route of intake. For purposes of mass imparted to any matter by ionizing l contamination control and bioassay pro, radiation. The common unit of absorbed , l cedures, the ALI for ingestion is used, dose is the rad, defined as an absorbed l since that is the most common route of energy of 100 ergs per gram of material, accidental intake in research labora. The new international standard unit is the gray (Gy), defined as an absorbed & l tories, energy of 1 joule per kilogram of mater- W M: The Radiation Safety Officer (RS0) tal; I Gy = 100 rads, i is the individual specifically appointed by the University, and named on the radio- Dese equivalent refers to the biologic-active materials licenses, to establish ally effective dose, defined as the pro-and enforce such procedures as are neces, duct of absorbed dose and a quality fac-sary to assure compliance with applicable tor dependent upon the type of ionizing regulations and license conditions, and radiation. The common unit of dose to ensure effective implementation of the equivalent is the rum, defined as the policies and rules established by the absorbed dose in rads multiplied by the Radiation Safety Committee. Depending on quality factor. The new international 9a context, *R50" may also refer to any standard unit for dose equivalent is the individual designated to act on behalf of sievert (Sv), defined as the nbsorbed l l the RSO. dose in grays multiplied by the quality
- l factor; 1 Sv = 100 rems. Regulatory dose l QUANTITIES A M LAIITS limits are expressed in rems to permit i equivalent biological doses from differ- !
Activity: A quantity of a radionuclide ent kinds of radiation to be combined, specified by the mean rate of spontaneous nuclear transformations Mch it under. Exposure: " Exposure" usually refers to 1 goes. The common unit of ictivity is the any condition which creates the potential t curie (Ci), defined as 1.he quantity of for any individual to receive a radiation l radioactivity which decayr at the rate of dose, either from external irradiation or 37 billion transformations per second. from internal contamination with radio- ; active materials, j RADIATION SAFETY POLICY MANUAL (1/90) Page 18
I l For radiation measurements, "exposuce' AREAS O refers to the intensity of x or gamma irradiation, specified by the ionization university Facility: Any real property i i produced in air. The common unit of owned by or under the control of the exposure is the reentgen (R). An exposure University, whether permansntly or temp-of 1 ' delivers almost I rad (0.869 rad orarily. in #1! <r 0.93 rad in soft body tissues). Submultiples of the roentgen are nomally b diaise+---I S tory: Any room or area combined with time units to express in which 10 or more Reference Quantities exposure rates, e.g., milliroentgens per of unsealed radioactive materials are hour (mR/hr), etc. stored or used. sounct.s Centre 11C Arna: Any area to which access ) is limitou for any reason. X-ray rooms l
. Radiatiam source: Any " Radiation Machine" are controlled administrative 1y by the or " Radioactive Material" emitting or personnel who operate the x-ray equipment.
capable of producing ionizing radiation. Radioisotope laboratories are controlled by posting and locking for the purpose Radiation Nachlam: Any device capable of of preventing unauthorized removal of producing ionizing radiation except those radioactive materials. Exposure to radio-which produce radiation only from radio- active materials is prevented by control-active material. ling the materials, not by limiting normal access to the laboratory when 4 is open l Radleactive Material: Any solid, liquid and attended. l or gaseous substance which spontaneously l i emits any type of ionizing radiation. Restricted Area: Any area to which access is limited for the purpose of protecting O Radleinstape: 6 used in this manual and related procedures, a " radioisotope" is individuals against undue risks from exposure to radiation and/or radioactive ' any radioactive nuclide used in unsealed material. The mere prasence of any radia-or dispersible form. This terminology is tion source, if adequately controlled to used primarily to characterize the form limit potential exposures, does not neces-of the material and the nature of the use, sitate a restricted ard designation. Areas containing sources wOh the poten- , Reference Guantity: A quantity of any tial for produc< ng significi at expoNres radioisotope related to its relative require sincific authorizat ons and pro-hazard potential and used to prescribe cedures or posting for accer 4 control and '
. requirements for handling, monitoring, are dasignated as restr$ct>d areas. ;
labeling and disposal. Radistion Area: Any accessible area in Interval Inventory: The total quantity which an ihdividual could receive a dose of radioisotopes introduced into the lab equivalent exceeding 5 mres in 1 hour at each month, averaged over the bioassay 30 cm (1 ft) from the source or froo any interval, expressed in ALIs. surf %4 the radittion penetrates. , Jealed Source: Radioactive material that High Radiation.Atta: Any accessible area is permanently bonded or fixed in a cap- in which an hidividual could receive a sule or matrix designed to prevent release dose equivalent exceeding 100 mrem in 1 - and dispersal of the radioactive material hour at 30 cm (1 ft) from the source or under the most severe conditions which are from any surface the radiation penetrates. likely to be encountered in normal use and handling. RADIATION sAFEif POLICY MANUAL (1/90) - Page 19
4 USDts responsibility for all r^stion sources under their control. 3ggjatian user: Any individual whose official duties or authorized activities IEINITORIIIS AM SLEVE:YIIIS include handling, operating, or working in the presence of any type of radiation Cantaminatian Survav: A systematic inves-source is dassified as a radiation user. tigation to determine the presence, or to For purposes of evaluatihg radiation verify the absence, of radioactive mater-protection requirements, radiation users ials in unwanted locations, e.g. on the may be considered as belonging to one of body or personal clothing, on surfaces of the following groups: objects that may be touched or handled, on equipment or materials to be removed . pierna11v amposed users are those who may from a restricted area, etc. be expected to receive doses exceeding 10% of the occupational limits. Radiation Wipe Test: The detection and evaluation - doses to these individuals are individu- of removable contamination by measurement ally monitored, of radioactive material wiped from the surface onto an absorbent material such Potantially azartand users are those who as a filter paper. are unlikely to receive a dose greater than 10% of any occupational limit, but f.xnesure Survey: A systematic investiga-who work with sources that could produce tion to determine external radiation large accidental doses, e.g. accelerators exposure rates at specific locations where or therapy units. Radiation doses to individuals may be present and potentially these users are individually monitored, exposed. Itinimally exposed users are those who are unlikely to receive any radiation dose Penetrati% Radialmien: Ionizing radiation from ext;rnal sources capable of deliver-T greater than 10% of any occupational ing significant doses to organs : r tissues limit. This category includes individuals more than I cm deep in the boy , e.g. x who do not work routinely with radiation or gamma rays and neutrons. sources, but whose official duties may occasionally bring them into areas where lionpenetrating Radiation: lonuing radia-radiation exposures may occur, e.g. most tion from external sources that is not nurses, emergency, security, maintenance, likely to deliver significant doses to receiving and shipping personnel, custo- organs or tissues more than I cm deep in dial and housekeeping staff. Radiation the body, e.g. beta particles and low-training and monitoring for these users energy photons. - are conducted and recorded on a group, rather than an individual, basis. Bioassar Interval: The bioassay interval for a particular radioisotope is the ' Itaspensible User: An individual author- maximum time that may elapse between ized by the Radiation Safety Committee to bioassays that will assure detection of acquire and use specific radiation the verification level for a given assay sources, and tu supervise their use by method. The bicassay interval for a < others, in compliance with pertinent particular radioisotope is determined by regulations and under conditions approved its physical and metabolic character-by the Committee. Responsible users must istics, and by the instrument 7. tion used demonstrate, to the satisfaction of the for the measurement. See BIDASSAYS FOR Committee, competence in the safe use of INTERNAL RADI0 ACTIVITY (RPR 12). radiation sources by virtue of appropriate training and experience. Responsible users must be in a position to assume full RADIATION SAFETY POLICY MANUAL (1/90) - Page 20 1:
b
. g INDEX T0' RADIATION PROCEDURES AND RECORDS 1 January 1990 bt, * ' '
sUh1E5$obaEloYogIc*a15eelth 0epYr'tment, txt. 614Y. BEgg Applicabilitvc Title iStatus or Date of Latest Revision 1 ltadiattan Users Data and Applications 1 Radiation User Personal Data (1/90) 2 Radiation Use Applications (1/90) 4
- for muitetsotana ygagg 10- tadionuclide Categories and Data (1/90) 11 %dioisotope Laboratory Safety Procedures (1/90) 12 . doassays for Internal .Radioac'ivity (1/90) 13' Radioisotope Aquisition and Disposition (1/90) 14 Shipment of Limited Quantities of Radioisotopes (1/90) 15 Housing and . Handling of Radioactive Animals (1/90)
Precadures for Medical Users 20 Emergency P.oom - Handling of Radiation Accident Victims (7/89) 21 Radiation Protection for Nurses and Therapists (1/90) 22 Reporting Misadministrations (proposed) 23 Diagnostic Radiology (proposed)
, 24 Brachytherapy (7/86, to be revised)
~25 O 26
.27' Radiation l'. trapy (proposed Special Procedures (proposed))
Nuclear _ Medi:ine (12/83, to be revised) 28' Radiopharmacy (proposed) Procedures for Miscellaneous Users 3C . Analytical X-ray Machines:(10/89) 31 Self-Shielded Irradiators (12/89)- 321 Particle Accelerators (proposed)
~33 NuclearReactors(proposed) 34 Solid State Fusion (5/89)
Radiation Safety Management
+ .40 Radiation Safety Committee (1/90)
'- 41= Radiation Safety. 0f ficer (1/90) 42 -Radiation Procedures and Records (1/90) 43 44 Authorization Training forUsers of Radiation Radiation (4/84, toUse (1/90)be revised)
- 45. Radiation Emergency Response (3/83, to be revised) 46 Investigation Levels and Reports (1/90) 47 Enforcement Actions (8/89)
Radiation Safety Services 50 Radioisotope Laboratory Evaluations (1/90) 51 Leak Testing of Sealed Sources (11/89) 52 Calibration and Use of Portable Survey Instruments (11/89) O 53 54 55 Radioactivity Measurements (draft) Radioactive Waste Management (11/89)
' Transportation of Radioactive Materials (11/89) i
i 1
- . 8 j
RADIATION SAFETY DIRECTORY l < 91 l 1 RADIOLOGICAL HEALTH DEPARTIGli J 100 Orson Spencer Hall Phone: 581-6141 j RADIATION SAFETY OFFICER I i Keith.J. Schlager, MPH, PhD h Director and RSO J Byron L. Hardy : Health Physicist and Alternate RSO ": TEQ5tICAL STAFF ! Clark Clements,: Radiation Analyst i Ray Jones, Radiation Analyst Tony Macklyn, Radiation Analyst i Nolan Smith, Radiation Analyst Gary Stubbs, Radiation Analyst . Sean Macklyn,' Radweste Technician ? AININISTRATIVE STAFF- - ;)
, 5 Keith Hughes, Pregranner and Database Manager Arlene Taylor Burs,. Administrative Assistant-
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Sheryl Bohn, Administrative Secretary M
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y 7.; , RADIATION USER PERSONAL DATA PURPOSE obtain a summary of his or her radiation monitoring records upon written request This procedure specif s the personal to the RSO, no more often than annually, data that must be provided by each radia-tion user, including a summary of training and experience with radiation sources and, PROCEDURE if necessary, a form to request radiation exposure or radiation safety training Each radiation user shall submit a records from previous employers. 1he completed " RADIATION USER TRAINING & cor.fidentiality of personal data, and the PERSONAL. DATA" form (RPR 1A) to the RSO right of individuals to review their own before starting work with any radiation records and to obtain written summaries sources. If any previous employment of radiation exposures are also specified. involved potential exposure to ionizing radiation, a " REQUEST FOR RADIATION EXPOSURE HISTORY AND/OR TRAINING POLICY VERIFICATION" form Gr:: m shall also be A " radiation user
- is any individual whose official duties or authorized activities include handling, operating, or working REGULATORY BASIS in the presence of, any type of radiation source on a regular basis. As a condition The Privacy Act of 1974, as amended.
of performing such duties or activities, O each radiation user is required to provide certain personal information to the Radia-tion Safety Officer (RS0).. The recuired Utah Bureau of Radiation Control, Utah Radiatfon Control Rules: information includes (1) primary icenti- Speciffe Licenses, R447-22. fication data, e.g. full nsme, birth date, sex, and social security number; (2) Standards for Protection Against previous it aining and experience with Radiation, R447-15. radiation sources; and (3) current employ-ment status, including job title or de- Notices, Instructions and Reports to scription, department, supervisor, and Workers by Licensee or Registrants - work location. - Inspectfons, R447-18. Personal records of radiation users also U.S. Nuclear Regulatory Commission: contain the scores obtained on tests taken to demonstrate knowledge of radia- Notices, Instructions, and Reports tion safety procedures, data obtained from to Workers; Inspectfons,10 CFR 19. monitoring of external and internal radia-tion exposures, and reports on any Standards for Protection Against injuries or abnormal incidents related to Radiation, 10 CFR 20. the use of radiation sources. Specific Domestic Licenses of Broad Individual radiation user records are Scope for Byproduct #aterf a7,10 CFR treated as confidential and are available 30. only to individuals with a legitimate need for the information. An individual may Medical Use of Byproduct #aterial, O review the contents of his or her personal radiation user file at any time, and may 10 CFR 35. RPR 1. PER$0NAL DATA (1/90) - 1
l 1 RPR 1A. RADIATION USER TRAINING & PERSONAL DATA , (Please type or print legibly) l Surname (family or last name): Given names (first and middle or initial): Previous or other names known by: University ID iio. (Soc. Sec. No.): Sex: Male Female Birth date: Month Day Year Job Title or Duties: .' Department: Division /Section: ) Work Location: Phone: Responsible User: or Supervisor: ' Date of first radiation use at University of Utah: _,_ _ _ { Enter the date(s) of University of Utah training: Required radiation safety training includes the following topics: I (1) nature of radiation sources, 1 (2) biological effects and risk estimates, (3) risks to the unborn and control of prenatal exposure, ) (4) ALARA principle and minimizing exposure, \ (5) correct use of protective devices, 1 (6) provisions of regulations and licenses, j (7) response to radiation emergencies, i (8) responsibilities and rights of radiation users, ' (9) availability of monitoring and inspection reports, and, for radioisotope users only: , (10) safe handling and storage of radioactive materials. Check here if you have received training on ALL of the topics listed above at another institution. Check here if you have had previous work experience with radiation sources. If you checked either of the above statements, complete a " REQUEST FOR RADIATION EXPOSURE HISTORY AND/0R TRAINING VERIFICATION" (RPk 18) for each such institution or employer. ) The information above is accurate and complete. I understand that I may communicate directly, in confidence and without prejudice, with the Radiation Safety Officer, the Utah Bureau of Radiation Control or the U.S. Nuclear Regulatory Commission on any matter concerning radiation protection. Signature: Date: O RPR 1. PERSONAL DATA (1/90) ?
i
^ RPR 18. REQUEST FOR RADIATION EXPOSURE HISTORY and/or TRAINING VERIFICATION (Please type or print legibly) -
Organization: Address: l l l Attention: Radiation Safety Officer, if known, or Supervisor (Indicate which). To whom it may concern: 1 If checked here, please send my radiation exposure history to the address indicated below. 1 If. checked here, please verify that I received radiation safety training O appropriate for independent work with radioactive materials. Surname: Given names: Previous or other names known by: l Soc. Sec. #: . Birth date: Mo:. _ Day: Yr: Inclusive dates of work with radiation: From: To: Please send the requested information to: i Radiation Safety Officer l Radiological Health Department 100 Orson Spencer Hall. University of Utah i Salt Lake City, UT 84112 I Signature: Date: , O M i l RPR 1. PERSONAL DATA (1/90) - 3
9 G O 4 THIS PAGE INTENTIONALLY LEFT BLANK O RPR 1. PERSON.'l DATA (1/90) - 4
l RADIATION USE APPLICATION PURPOSE INF0fMATION TO BE SUMMUTED This procedure specifies the requirements All applicants for tuthorization to be a that must be met and the information that responsible user most submit: must be provided to the Radiation Safety i Committee in support of an application to 1 RADIATION USEF. PERSONAL DATA (RPR 1) use ionizing radiation sources of any kind at the University of Utah. 2 RESPONSIBLE USER'S TRAINING & EXPERIENCE (RPR 2A)
- POLICY l l Applicants for unsealed, dispersible i The Radiation Safety Committee is the radioactive materials not to be used in governing body for all aspects of racia-or on humans must submit:
tion protection within the University, l L including all affiliated research, clinic- 3 RAD 10 ACTIVE MATERIAL USE APPLICATION al, instructional and service units util- (RPR 28) izing radiation sources in facilities i owned or controlled by the University. Applicants. for radiation generating ) Each proposed use of radioactive mater. machines or self-shielded irradiators not ; i ials, x-ray or other radiation generating to be used on humans must submit: machines must be submitted to the Commit- . tee, yla the Radiation Safety Officer 3 RADIATION MACHINE USE APPLICATION l (RS0), for review before implementation. (RPR 2C) Specific forms and data to be submitted l are prescribed in the attachments to this Applicats for use of any source of radia-fi V procedure. The descriptions of facilities tion on or in humans must submit: and equipment, the training and experlence 3 CLINICAL RADIATION USE APPLICATION of the user, and the operating or hrodling (RPR 20) I procedures shall be provided in suf /icient l l detail to permit the Committee to ovaluate An applicant for research use of any the safety of the proposed use, radiation machines or radioactive mater-ials applied to humans must first be INITIAL APPLICATIONS approved as a responsible user by the Radiation Safety Committee; use whichever A first-time applicant to become a re- application form is most appropriate. sponsible user should obtain a copy of the Radiation Safety Policy Manual from the An application for any research use of a RSO. The index to all current Radiation radioactive drug must be submitted to the Procedures and Records included in the Radioactive Drug Research Committee (RDRC) . Manual should be reviewed to identify any for review and approval. The RDRC is ! that may be applicable to the planned constituted in accordance with, and speci- l radiation use; these should also be fically approved by, the Food and Drug obtained from the RSO. This Cr0mittee Administration (FDA). also serves as the Human Use Subcommittee After becoming thoroughly familiar with (HUS) of the Radiation Safety Committee the pertinent requirements, the applicant to review and approve any experimental use should complete the appropriate checklists of radiation in research on human and forms attached to this procedure and subjects. Certain protocols involving submit them to the RSO. Allow 2-4 weeks radioactive drugs are submitted to the O to receive notification of the Committee's action. FDA, and all experimental protocols ap-RPR 2. RADIATION USE APPLICATIONS (1/90) - 1
proved by the RORC-HUS are reported to the REGULATORY BASIS Radiation Safety Comittee. The Privacy Act of 1974, as amended.
. Application forms for research use of radiation in human subjects are available Utah Bureau of Radiation Control, Utah from the Chairperson of the RDRC. Radiation Control Rules:
Specific Licenses, R447-22. REVISIONS TO AUTHORIZATIONS Use of X-Rays in the Healing Arts, Any desired revisions to an authoriza- R447-28. tion should be discussed with the RSO, If the RSO determines that the proposed Medical Use of RadfoactIve Material, revision does not involve any change from R447-32, the initial safety evaluation, and is within the intent of the initial authori- Radiation Safety Requirements for zation, the revision may be approved by Ana7ytica7 X-ray Equipment, R447-40. the RSO without further Comittee action. The RSO may, however, require additional Radiation Safety ' Requirements for' information before granting approval. Particle Accelerators, R447-44. If a proposed revision to an initial authorization involves significant changes U. S. Nuclear Regulatory Comission, Guide in sources or conditions of use from those for the Preparatfon of Appifcations for specified initially, the proposal must be Medical Programs, Regulatory Guide 10.8, resubmitted to the Comittee for authoriz- Rev. 1, 1980: ation, To assure that all records related to Acceptable Training and Experience for Medical Uses of Byproduct h radiation sources, users and conditions #aterial, Appendix A. of use are accurate and up-to-date, the RSO may require that parts or all of the Medical Jsotopes Comittee, App. B. application be verified or resubmitted periodically. If the updated information includes changes that are significant to safety, the application will be submitted to the Committee for reauthorization. O RPR 2. RADIATION USE APPLICATIONS (1/90) - 2
i
,\ j l,
i <- RPR 2A. RESPONSIBLE USER'S TRAINING & EXPEP.IENCE ! (Please type or print legibly) ! Surname: Initials: Soc. Sec. No: Trainina in Basic Radiation Sciences: Tvoe & Hours of Trainina Formal Supervised 1 Courses On-the Job Subiects location & Dates (hours) (hours) : Radiation Physics
& Instru=antation Radiation
_ Protection . l Mathematics of Radioactivity ! Biological Effects of Radiation , Radiopharmaceutical Chemistry *
- Medical users only 1 Experience in Using Radiation: List radiation sources used personally; list nuclides and quantities, description of machines, dates and nature of each use. -(Attach supp'lemental sheets if necessary.) For each location where experience was obtained, complete one " REQUEST FOR ... TRAINING VERIFICATION" form (RPR IB).
O- 2 All appltpants who will use radiation on or 1.1 humans must complete the following: Soecialty Board Citecory Mo/Yr Certified ~ If.not board certified in a specialty that includes radiation training, attach preceptorship statement. (Form available from the RSO.) The information above is accurate and complete.
- 3 Signature Date
( RPR 2. RADIATION USE APPLICATIONS (1/90) - 3
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RPR 2B. RADI0 ACTIVE MATERIAL USE APPLICATION (FOR UNSEALED OR DISPERSIBLE MATERIALS NOT USED IN OR ON HLMANS) Maximum Order Nuclide ALI Monthly use Malide Physical #.hanical Forse g.1 How Often? (nC1)* (No. of Alls)
- See "RADIONUCLIDE CATEGORIES AND DATA" (RPR 10A)
In addition to the RESPONSIBLE USER'S TRAINING & EXPERIENCE (RPR 2A), the PERSONAL DATA form (RPR 1A), submit the following:
" RADIATION USER TRAINING & PERSONAL DATA" forms (RPR 1A) for all other individuals who will work in the same location (faculty, staff, students).
Brief description of experimental objectives and methods, with justification for the spec 1fic radionuclides and quantities. Description of facilities where radiation sources will be used and stored, including building, rooms, fume hoods, shielding, security arrangements; include diagram of layout if appropriate. Description of radiation survey instruments that will be readily available for contamination and exposure control, and analytical instruments that will be used for determination of radioactivity w wipe test papers or urine samples. Animals to be used, if any, including nuraer, individual doses, holding facilities and handling methods. Brand names of liquid scintillation fluor (s) and tissue solubilizars, if any, that will be used. Written justification must be provided for any fluors other than "NHNT" and vials larger than " minis". See " LIQUID SCINTILLATION MEDIA" on next page. Description and estimated quantities of radioactive wastes to be generated. If any radioactive wastes will also contain any hazardous materials, as defined by the EPA, provide written justificat - an for producing them. I have read the University's Radiation Safety Policy Manual and understand the conditions and regulations contained in it. With respect to the requested radiation sources and proposed uses, I acknowledge and accept the responsibility for: (a) radiation protection instruction for all involved personnel; Lb? acquisition of the equipment. suppites and/or services necessary for radiation protection; Lc3 security to prevent misuse or theft of radioactive materials; (di maintaining accurate records of acquisitions and dispositions; l ej regular contamination and/or exposure surveys and records; I,fl notification of the R$0 of any accident or abnormal incident; Lgj arranging for authorization of another individual to assume the preceding responsiblittles, or to suspend or terminate all radiation uses, prior to any extended absence. Signature of Responsible User: Das:- RPR 2. RADIATION USE APPLICATIONS (1/90) - 5
LIQUID SCINTILLATION MEDIA g Fluors containing non-hazardous, non-toxic (IHIT) solvents are required unless a specific exception is obtained from the RSO or the Radiation Safety Committee. Examples of such fluors are: , Opti-Fluor Stores & Receiving, University of Utah Ext. 8671 Ultima, & others; Packard Inst. Co., Downers Grove, IL 60515 312-969 6000 Ready Safe, Beckman Instruments, Fullerton, CA 92634 714-773 8061 Ecolume,Ecolite(+),Cytoscint-ES,Betamax-ES,Universo1-ES ICN Radiochemicals, Irvine, CA 92713 800-854-0530 c Solvent-Free, Isolab, Inc., Akron, OH 44321 800-321-9632 i Bio-Safe II and Bio-safe NA - e i Research Products International Corp., Mount Prospect, IL 800-323-9814 Ecoscint A (aqueous samples), Ecoscint 0 (organic samples) National Diagnostics, 1013-1017 Kennedy Blvd. l Manville, NJ 08835-2031 800-526-3867 , Fluors containing toxic or flammable solvents.may not be purchased without rior approval from the RSO. Examples are: - Beckman: CP, HP, HP/b, EP MP, NA, Ready Solv, Ready Protein ICN: Universa11 NEN: Aquasol, Aquasol-2, Econofluor, Econofluor-2, Formula 963, Liquifluor, , Omnifluor, Atomlight, Aquasure, Biofluor, Riafluor, and all "NEF" numbers Packard: Scint A, Insta-gel , I RPR 2. RADIATION USE APPLICAil0NS (1/90) - 6
l RPR 20. RASIATION MACHINE USE APPLICATION (X-RAY McHINES, PARTICLE ACCELERATORS Als SEALED-SOURCE IRRADIATORS IlOT TO BE USED ON HUEllS) In additico , the RESPOIISIBLE USER'S TRAINING & EXPERIENCE (RPR 2A), the PERSORL DATA fors , d 1A), submit the following:
" RADIATION USER TRAINING & PERSONAL DATA" forms (RPR 1A) for all other individuals who will work in the same location (faculty, staff, students).
Detailed description of irradiators or radiation machines including safety devices, e.g. open beam, closed beam, interlocks, warning lights, shutter indicators (open-closed) x-ray tube status (on-off). De-cription of facilities where radiation machines or irradiators will be used, it.uiuding building, rooms, shielding, security arrangements, etc.; include diag-ram of layout as appropriate. Description of any available instruments for radiation surveys or monitoring, Step by step operating procedures to be used by all personnel while operating equipment.= Outline of instruction to be given to all users addressing items such as possible hazards, significance of safety devices, operating procedures, symptoms of acute localized exposure, and procedures to be followed in reporting sus sected or actual exposure. (No person will be permitted to use equipment without th< s instruction). I have read the University's Radiation Safety Manual and understand the conditions and regulations contained in it. With respect to the requested radiation sources and proposed uses, I acknowledge and accept the responsibility for: aL radiation protection instruction for all involved personnel; b; i acquisition of the equipment supplies and/or services noenssary for radiation protection; c;I notification of the RSO of any accident or abnormal incident; d;I arranging for authorization of another individual to assvme the preceding responsiblitties, or to suspend or terminate all radiation uses, prior to any extended absence. Signature of Responsible User: . Date: O RPR 2. RADIAT!0N USE APPLICATIONS (1/90) - 7
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l 9 RPR 2. RADIATION USE APPLICATIONS (1/90) - 8 I 1
4 i g RPR 20. CLINICAL RADIATION USE APPLICATION
-(FOR ALL USES OF RADIQ4CTIVE MTERIALS A W RADIATION-GEERATING MCHINES IN OR ON HLMANS)
In addition to the RESPONSIBLE USER'S 1 RAINING & EXPERIENCE (RPR 2A), the PERSONAL ! DATA form (RPR 1A)s submit the following: l Evidence of board certification, or preceptorship statement, or other record verifying the required training and experience for each category checked below. Check each cateeory of use for which vou are mon 1rina: Diagnostic radiology (R447-28 350). Uptake, elution and excretion studies (R447-32-910). ! Imaging and localization studies (R447-32-920). Therapeutic use of radiopharmaceuticals (R447-32-930). Treatment of hyperthyroidism (R447-32-932). l _, Treatment of thyroid carcinoma (R447-32-934). I i Use of brachytherapy sources (R447-32-940). Ophthalmic use of strontium-90 (R447-32-941). Use of sealed sources for diagnosis (R447-32-950). Teletherapy (R447-32-960). Teletherapy physicist (R447-32-961). Therapeutic use of linear accelerator. i Acknowledgement: I 1 have read thw University's Radiation Safety Manual and understand the conditions and regulations contained , in it. With respect to the requested radiation sources and proposed uses. I acknowledge and accept the 1 respons!bility fort a) radiation protection instruction for all involved personnel; b) acquisition of the equipnient. supplies and/or services necessary for radiation protection; c) notification of the R$0 of any misadministration. accident cr abnorinal incident. ' Signature of Reeponsible User: _ Date: O RPR 2. RADIATION USE APPLICATIONS (1/90) - 9
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- RADIONUCLIDE-DATA (RPR 10) m it kW' ', -
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RADIONUCLIDE DATA O PURPOSE Dose Rates (area / hour): l This procedure provides a ready reference Penetrating - the dose rate from pho- l to radiation protection data for commonly tons at 1 meter from a point source I used radionuclides. Data for nuclides of I millicurie, assumed to be propor-not listed herein may be obtained from tional to the inverse of the square
-the RSO. of the distance between the point source and the receptor, j POLICY Skin dose - dose rate to the basal l epidermal cells from contamination on Radionuclide data used for radiation the skin, expressed in micrgeuries per protection calculations shall be obtained unit area of skin (pgi/cm ) over an from regulatory authorities or reputable area of at least I cm .
scientific advisory organizations. REFERENCES DEFINITIONS International Commission on Radiological Reference Quantity (RQ): A quantity of Protection Recoamendations of the JCRP, l a radionuclide (expressed in microcuries) Publ . No. 26, 1977. I related to its relative hazard potentiti and used to prescribe requirements for Ibid., limits for Intakes of Radio-handling, monitoring, labeling and dis- nucliJ.s by Workers, Publ. No. 30, in 4 i posal.. parts with supplements. 1979-88. Annual Limit on Intake (ALI): The quan- US Environmental Protection Agency, tity of a radionuc11de (expressed in Lfm/ ting of Radfonucifde Intake and Air millicuries) which, if taken into the Concentration and Dose Conversion factors body, produces an effective dose equiva- for Dose Conversion Factors for Inhala-lent in risk to the - annual whole body tfon, Submersion, and Ingestfon, Federal dose limit of 5 rems. Because of dif- Guidance keport No. II, EPA-520/1-88-020, ferences in physiological transport mech- September 1988. ' anisms, the ALIs vary depending on the , route of intake. For purposes of con- Utah Bureau of Radiation Control, Utah tamination contro1 and bionssay proced- Radiation Control Rules, Standards for ures, the ALI for ingestion is used, Protection Against Radf ation, R447 since that is the most common route of 430 accidental intake in research labora-tories. I RPR 10. RADIONUCLIDE DATA (1/90) - 1
l RPR 10A'. RADIONUCLIDE CATEGORIES AND DATA (For data on radionuclides not listed below, contact the RSO.) base rates (mren/heur): , Reference Penetrating Skin dose l Quantity Ingestion At 1 meter at 0.07 mm l Huclide Half-life fdi) ALI imC1) frem.1 aci nar aci/cur ; l
'LO-KTAS* - low-energy beta or electron emitters with negligible external exposure ;
potential and ALI's 21 mil 11 curie. 4 H-3 12 yrs 1000. 80. O. l C 14 5730 yrs 100, 2. O. 1200 S 35 8 days 100. 6. O. 1300 *.. 1 L C1-36 3x10{ yrs 10. 2. O. 7200 i l Ca-45 165 days 10. 2. O. ! Cr-51 28 days 1000. '40.* 0.02 I Fe 55 2.7 yrs 100. 9. 0, 1 Ni-63 logyrs 10, 9. 0, ; Tc-99 2x10 yrs 10. 4, O. l Pm-147 2.6 yrs 10, 4. O.
'HI-8ETAS* - high-energy beta emitters with negligible gamma emission but capable I of significant breasstrah7ung production if not properly shielded. Emphasis is on !
control of doses to extremities and prevention of intake. J P-32 14.3 days 10. 0.6 0. 8900 Rb-86 18.7 days 100, 0.5 0.05 Sr-90 28.6 yrs 0.1 0.03 0.
'IODIES" - radiciodines are treated as a separate category for exposure evaluation.
Emphasis is on prevention of intake by ingestion or inhalation. , 1 1-125 6gdays 1. 0,04 0.07 l l I-129 6x10 yrs 0.1 0.005 0.13 I-131 8 days 1. 0.03 0.22 6300 l
' GASES * - noble gases present minimal exposure potential or waste disposal problems.
- i Kr-85 10.7 yrs 100. NA 0.
Xo-133 5.2 days 100. NA 0.1 5
" NATURAL" - naturally occurring nuclides, primarily alpha emitters. Emphasis is on prevention of intake by ingestion or inhalation.
Th-232 (nat) 14x10l yrs 100, 0.0007 0,
- U-238 (nat) 4.5x10 yrs 100. 0.2 0, O
RPR 10. RADIONUCLIDE DATA (1/90) - 2 J
1 Seference Penetrating Skin dose O bc11de Half-life Quantity idi1 Inlpstion AC iafii At 1 meter frem.1 act at 0.07 am-nar di/cm8
*GAf8tR5' - gamma emitters with ALI 11 millicurie; emphasis is on external exposure control and monitoring.
Na 24 0.625 days 10. 4. 1.89 Mn 54 312 days 10, 2. 0.51 Co-57 271 days 100. 4.* 0.15 290
- Ga-67 3.3 days 100. 7. 0.11 1100 Ga-68 68 min 100. 20. 0.54 Go-68 288 days 100. 5. 0.06
< Sr-85 64.8 days 10, 3.* 0.75 55 Mb 95 35 days 10, 2.* 0.48 970 No.99 2.8 days 100. 1. 0.11 Tc-99m 0.25 days 100. 80. 0.12 890 Ru-103 39 days 10. 2.* 0.33 2400 In-111 2.8 days 100. 4.* 0.5 1400 Sn-113 115 days 10, 2.* 0.18 I-123 0.542 days 100. 3. 0.28 Gd-153 242 days 10. 5.* 0.17 460 Au-195_ 183 days 10, 5. 0.09 Hg-195m 1.7 days 10. 2. 0.1 Hg-197 2.7 days 100. 3. 0.07 Au-198 2.7 days 100. 1. 0.29 3 days 100. 20. 0.09 O T1 201 Pb 203 1.2 days 10. 5. 0.68 970 ALL OTHER 1RICLIDES not included in one of the above groups are assumed to have significant potentials for both external and internal exposures and must be evaluated individually. Na-22 2.6 yrs 10. 0.4 1.33 7200 Sc-46 84 days 10. 0.9* 1.17 5100 Fe-59 44.6 days 10. 0.8 0.66 4600 Co-60 5.27 yrs 1. 0.2 1.37 Zn 65 244 days 10. 0.4 0.33 Se-75 118 days 10. 0.5 0.86 360
-Ru-106 367 days 1. 0.2 0. < Cd-109 453 days 10. 0.3* 0.18 Ir-192 74 days 10. 0.9 0.59 Hg-203 47 days 10. 0.5 0.25
- The ALI is not oppitcable to microspheres, which are highly insoluble particles, typically greater than 0.01 uun diameter. They require external exposure control and monitoring, but are not readily absorbed from the gastrointestinal tract. If inhaled because of their size. they are most likely to be depostted in the upper respiratory tract, from which they wou.d be cleared by the mucous transport and swallowed.
O RPR 10. RADIONDCLICE DATA (1/90) - 3
i. RPR;108. CONTAMINATION LIMITS AND ACTION LEVELS * !
- sinr CATran"Y REIWWARLE CMTAltillATIM LIltIT (RCL18 Electron and/or photon emitters: ,
with ingestion ALI 21 mci 1. nCi (2,000 dpm; 40. dps) per 100 ca r with ingestion ALI <1 mci 0.1 nCi (200dpm; 4. dps) per 100 cm' i Alpha-particle emitters: 0.01 nCi (20 dpm; 0.4 dps) per 100 cm' inrATIGI GuMTITY DmilRED ACTIM Skin or hair Any Immediate removal by gentle washing * - 8
>l RCL Immediate removal and bioassay within normal .,
interval ,, ; 8
>10 RCL Immediate removal and bioassay within 5 days ,
i Clothing personal >l RCL from the lab wash in
'or protective Don the ab $tremoveclothin!ecayofactivI'ty or store for i Skin contact likely >10 RCL Bioassay 3 within five (5) days Skin contact unlike- >10 RCL Bloassay 8 within normal interval ly -
Surfaces or objects >l RCL Untildecontaminated,is$ late cover 'abel ' that are readily etc. to prevent personne contact;ind'cate, accessible or location and activity in survey record. normally touched , e.g. bench tops, j handles, etc. i
>10 RCL Decontaminate 'emedia".ely bioassay required 8 l
' within normal nterval f'or; potentially exposed I individuals
>100 RCL Decontami ate "mmediatal i bioassay8 I within5Saysforpotentkallyexposedrequired individuals )
P Equ'oment or >0,5 RCL Do not release until criteria are satisfied , L fac<11 ties to be r**ovable: released for >5 RCL ) unrestricted use fi=*d s ; Other surfaces or >l RCL Label the contaminated area or object; objects fnot readily indicate location and activity on survey accessib!e or record i normally touched) ;
>10 RCL Decontaminate within one week i sed on NRC Regulatory Guide 8.23. Radiation Safety Surveys at Medical Institutions, Rev. 1, Jan, et t are!e!! e !. o thecon[aminationmaybeaveragedovernomorethan30b e o n!W 'F a ufcs'e!c forde!Nminingtheappropriateack1on.I' kN, 3
All requirements for bloassays in this table are for screening bicassays. I: j; RPR 10. RADIONUCLIDE DATA (1/90) - 4 t
RADI0IS0 TOPE LABORATORY SAFETY PROCEDURES PURPOSE RESPONSIBILITIES l This procedure provides criteria, refer- Each person who works with unsealed or ence data, and specific instructions for dispersible radioactive materials is safe handling of radioisotopes in unsealed responsible for: contamina or tiondispersible control andfoms, includinf monitoring o exposures. I knowing the basic properties of the radioactive materials to be used, e.g. E It also specifies the require: nts for E W monitoring records to be maintained by the the half-life of the nuclide(s), the users, type (s) of radiation emitted, the an-
- nual limit on intake (All) and any shielding that may be required. Refer POLICY to "RADIONUCLIDE CATEGORIES AND DATA" (RPR 10).
It is the responsibility of each radiation user to follow safe work practices, to be 2 following the instructions or proced-aware of actual or potential radiation ures provided by the responsible user exposures, and to keep all exposures to and the RSO, or provided in the Radia-levels that are as low as reasonably tion Safety Policy Manual. achievable gALARA). Each person who handles unsealed radioisotopes is respons- 3 surveying of gloves, clothing, equip-ible for the control and containment of ment and work area frequently during radioactivity and for performing regular procedures in which more than 1 All is surveys of personnel, personal effects, manipulated, and surveying of hands and equipment and work areas using methods personal clothing before leaving the that will assure the detection of con- laboratory. tamination before significant exposures occur. 4 providing a urine sample, or obtaining a thyroid count, at intervals specified in research facilities, application of the by the RSO. Refer to "B10 ASSAYS FOR ALARA principit dictates that no removable INTERNAL RAD 10 ACTIVITY" (RPR 12) . contairination shall be tolerated indefin-itely. Whenever contamination is detect- 5 recording the results of all radiation ed, it must be removed promptly to prevent surveys and screening bioassays its spread and the possible exposure of promptly, completely and accurctely. other individuals. The responsible user must assure that the necessary monitoring The responsible user must ensure that: is performed, recorded and reported. Routine evaluations of all radiois,' tope 1 all radiation users have received ade-laboratories, including surveys f ::on- quate radiation safety instruction. tamination, are also performed by the RSO. 2 the equipment, supplies and services necessary for radiation protection are provided. A U RPR 11. RADLAB SAFETY (1/90) -1
l 3 radioactive materials are secured 30 cm (1 ft.) fro.ii an accessible source against theft, misuse anti access by un- or a surface, the room must be labeled authorized personnel, with a " Caution - Radiation Area" sign. 4 4 radioactive wastes are segregated prop-erly and placed in appropriate contain- SURVEY INSTRLSENTS . J ers. The containers are to be provid- l ed by the usert labels are available The responsible user shall assure that from the RSO. Follow the instructions instruments used for determining exposure I in SRADIO!S0 TOPE ACQUISITION AND rates or for direct detection of contamin- , DISPOSITION" (RPa 13). ation are capable of responding appropria- , tely to the kinds of radiation anticipated ' 5 accurate records of acquisitions and and have been calibrated within the past ., dispositions of radioactive materials year. For most radioisotope laboratories, are maintained. Refer to "RADI0 ISOTOPE a thin window Geiger-Mueller (GM) survey , ACQUISITION AND DISPOSITION (RPR 13). meter with an audible response is prefer- I red. For low-energy photon emitters, e.g. ) 6 regular exposure and contamination I-125 or Cr-51, a thin-crystal scintilla- 1 surveys are performed and recorded. tion detector, also with udible response, I is preferred. l 7 the RSO is notified promptly of any I accident or abnormal incident involving The user must know the detection efficien-radioactive materials, cy, e.g. cp#dps, for each survey instru- ) ment and record it with all survey 8 prior to any extended absence, another results. The reporting forms attached to i individual is authorized to assume the this procedure include provisions for i preceding responsibilities, or to recorting all pertinent instrument data, suspend or terminate the use of radio-active materials. In laboratories where only tritium (H-3) or less than 1 ALI of low-energy beta emitters are used, direct surveys are not POSTING 0F RADI0IS0 TOPE LABORATORIES necessaary and all contamination surveys Each room containing more than 10 refer-ence quantities of all radioisotopes If an analytical instrument is to be used combined must be labeled with a " CAUTION for counting urine samples or contamina-RADI0 ACTIVE MATERIALS" label. This label tion wipe tests, the user must know the a should indicate the most important iso- counting efficiency for each sample type topes - present, and the name and phone and for each anticipated nuclido. The RSO numbers (home and office) of the respons- will help the user to determine appro- s ible user, priate sample sizes and counting times for urine samples, and the results that would A " NOTICE TO WORKERS", provided by the require verification. Utah Bureau of Radiation Control and available from the RSO, must be posted where anyone entering the lab can see it. If any dose rate exceeds 2 mreWhour at i 30 cm (1 ft.) from an accessible source or surface, the room must be )osted to prevent entry of unauthorized incividuals. If any dose rate exceeds 5 mrem / hour at ( RPR 11. RADLAB SAFETY (1/90) - 2 L l l
P EXTERNAL EXPOSURE C0KiBOL EXPOSURE RATE SURVEYS If nuclides that emit penetrating radia- A survey of exposure rates must be per- , tion are used, shielding may be required formed- whenever sources of penetrating for storage and work locations. radiation are first acquired, when the Phosphoreus-37.should be shielded with 8 quantities of these radionuclides are i m -(3/8") of any material with a low increased and when physical arrangements atomic number, e.g. plastic or wood, for handling or storage are modified. Iodine-125- should be shielded with at Additional surveys should be performed least 3 m (1/8") of lead. Other nuclides occ sionally to assure that inadvertent that emit higher energy gama rays may changes in exposure rates have not oc-require 5 cm (2") or more of lead. The
- curred. If the user does not have a-shielding must extend entirely around the curvey instrument that is calibrated for-source; verify by making measurements of N:,osure-rate measurements, a survey exposure rates above, below, in back and should be requested from the RSO.
at the sides of storage locations. The potential quarterly gama dose from PREVENTit5 0F IMTAKE OF , each radionuclide used may be estimated RADIQ4CT E MATERIAL as: , D - A.X.T(1/g)),where: Ingestion of radioactivity must be preven-ted by avoiding mouth contact with any D - estimated dose (millirem / quarter) items handled in a radioisotope 1aboratory A - activity handled (millicuries) (pipettes, pencils, etc.), by prohibiting eating, drinking and smoking in raaionucl-L. X - external dose-rate constant ide handling areas and by careful atten-(mrem /hr-mci at Im) tion to personal hygiene.
- ' T - exposure time (hours / quarter) Gloves, lab coats, or other protective ~ l 1/g = distance correction clothing, should be available and worn to '
prevent contamination of skin and personal
- 10,000 for contact hand dose clothing. Lab coats and gloves should not (d m 1 cm)-
be worn to.the cafeteria, library, class- ' rooms or hoine. Sandals or other open- . - 10f for hand dose using tongs toed shoes are not a with radionuclides. ppropriate for work (o - 10 cm) l 40 for body dose during entire Work, storage and waste areas should be I handling time (d - 30 cm) provided with secondary containers and covered with absorbent paper. Plastic For high energy beta-particle emitters, trays and dish pans are s11 table for use e.g. P-32, the dose rate to the hands (1 as secondary containers. The protective cm distance) from a point source with no covering should be replaced w hen it shielding is approximately 200 mrem / hour becomes excessively dirty or contaminated, per millicurie.- Multiply activity handled at oae time (mC1) by the hand contact time Inhalation of radioactive materials must hou s/ a t r) by 200 to estimate the be prevented by performing all operations that re, lease or generate gases, vapors or dusts in approved fume hoods. The sash g of a fume hood is intended to serve as a shield to protect the face from' spatters, L as well as to control air flow. To pro- 1 RPR 11. RADLAB SAFETY (1/90) - 3 l l' l
1 4 vide the proper protection, the hood must in each radioisotope laboratory : on a be free of major obstructions to the' flow regular basis according.to the level of
.of air and the sash should be set at the use, as indicated below. An evaluation height that was labeled with the green of the radiation protection status of each label when the air flow rate was measured. radioisotope laboratory, including a The average face velocity should be in the contamination survey,. will- al so - be range of 100 to 150 fpm. If the desired performed by-or on behalf of the RSO at velocity cannot' be maintained in a re- least once during each bioassay interval.
quired hood, the user must make arrange-ments for the necessary repairs or modifi- The appropriate frequency for performing ' cations. routine laboratory surveys-is determined by the nature and quantities of radio-In emergency situations, filtered or nuclides, and the conditions of use. The supplied-air respirators are used to frequency of routine contamination surveys prevent inhalation of contaminants. is based on the total quantity of unsealed Whenevar the probability of airborne (dispersible) radioisotopes on hand at the contatination is significant, the RSO beginning of a bioassay interval, plus should be notified and air sampling may the total quantity acquired during the be required. interval, i.e. the interval inventory", expressed in ALIs. - CONTAMI G SM SURVEYS The nominal survey frequencies shown in-the table are to be interpreted as guide-Surveys for contamination on the hands and lines. In cases where contamination clothing must be performed immediately occurs regularly, the interval between-after working with radioisotopes to allow surveys should be shortened. If the detection and removal before the material survey results obtained over a period of
-enters the body. Any radioactive material a year indicate no contamination problems, on the skin- must be removed promptly by the routine survey interval may be
. normal washing. If it cannot be removed increased. In no case, however, should easily, request advice from the RSO, .the interval be - more . than double the nominal interval in the table.
A thorough survey of the entire laboratory must be performed and recorded by the user INTERVAL
- INVENTORY ROUTINE CONTAMINATION SURVEY FREQUENCY .
<1 ALI Personal surveys EVERY DAY and laboratory surveys EVERY MONTH .-
when radionuclides are in use. 1-30 ALIs Personal surveys EVERY DAY and laboratory surveys EVERY WEEK when radionuclides are in use.
>30 ALIs Both personal and laboratory 5,urveys EVERY DAY when radio-nuclides are actually in use.
- Monthly average during the bloassa, interval.
O RPR 11. RADLAB SAFETY (1/90) - 4
Measurements of contamination by direct for each object or location surveyed,
~ detection, wipe tests, or both, should be following the instructions on the form made of representative surfaces. An under " CONTAMINATION SURVEY RESULTS".
audible instrument response should be used during direct surveys because of the 3 At locations with positive survey re-faster and. more sensitive response and sults, first ascertain whether the i>ecause it eliminates the need to watch reading could be penetrating radiation the meter constantly, coming through the surface, rather than from contamination on the surface. If To - determine quantities of remov0ble significant penetrating radiation is
+ contamination, or to survey areas that are detected, i.e. more than 0.2 mrem /hr inaccessible to a survey instrument, wipe (approximately 10 times background), an testsghouldbetaken. An area of 100 - exposure rate survey should be made as
- i. 300 cm - should be wiped with absorbent previously described, paper for each test. If energetic beta emitters are involved, the activity on the 4 At locations with positive results from filter may be measured directly with a contamination, or surfaces that are not thin-window GM survey meter. If tritium accessible for a direct measurement, or other low-energy beta emitters are use a dry filter paper to tgke a wipe involved, the wipe filter should be of'300 (preferred) or 100 cm . (A 300 analyzed. with a liquid scintillation cm crea is any equivalent of a 7-inch counter, square or a strip 2 cm2 wide and 1.5 meter long; a 100 cm area is any equivalent of a 4-inch square or a CONTAMINATION SURVEY DATA strip 1 cm wide and 1 meter long.)
1 Unless the only nuclides used are 5 Using the portable survey instrument in - tritium or small quantities (<1 ALI) of a low-background location, make a other low-energy beta emitters, direct measurement of the contamination - a direct survey should be made with a on the filter paper. Record the portable instrument. For each portable results according to the directions on survey- instrument used, record the the survey form, make, model and serial number (s) of: survey meter (s) used for the survey on 6 If contamination from low-energy bets the "" CONTAMINATION SURVEY - PORTABLE emitters, e.g. C-14, S-35, is detected INSTRUMENT" form (RPR 11A). Indicate the at a' level close to the RCL, the wipes calibration date and the detection ef- should be kept and edunted in a liquid
' ficiency for the critical nuclide, i.e. scintillation counter.
the one with the largest number of ALIs in use. Calculate the net response 7 If only tritium or small quantities of -
, rate expected from the instrument for other low-energy beta emitters are the removable contamination limit used, take wipe samples of all objects (F.CL), Note that all of the instrument and surfaces that are normally touched response information needs to be or readily accessible.
entered only once uitil the instrument is recalibrated. 8 On the " CONTAMINATION SURVEY - WIPE TESTS" form (RPR llB), record the data 2 With the audible responce turned on, identifying the counting instrument, move the detector slowly over all sur- the efficiencies for the critical faces that might be contaminated, hold- nuclide and the expected response for ing the detector 1-2 cm from the sur- a wipe with more than the RCL. face. Record the nighest net responsse O RPR 11. RADLAB SAFETY (1/90) - 5 l
.ej .#
REC 01BS All ' radioisotope inventory forms must be kept up to.date and forwarded to the RSO as-soon as the material item is used up. Sink disposals should be logged and- sum-
. marized on the inventory disposition form.
Refer to "RADI0 ISOTOPE ACQUISITION AND DISPOSITION" (wra 130 for instructions. The' results of radiation surveys arer to be recorded and retained for a minimum
, of three years; They are to . be- made ;.
available for review and evaluation by the RSO and the appropriate licensing agency. A suitable form for recording survey results ..is attached to' this procedure; however, other formats that provide com-parable information may be .used. Personnel surveys should indicate the name
. of the. individual surveyed and, if any contamination was found, the location on
- the body or.on the clothing.
s 9: RPR 11. RACLAB SAFETY (1/90) - 6
, i 7y RPR:11A.' CONTAMINATION SURVEY - PORTABLE INSTRUMENT 7( J- .
M Page'l of survey recorti initiated by (mes.) on (date) ! User: Subgroup: Bldg / Room (s): 1 Nuclides used: Critical nuclide: ALI: mci l
. Removable contamination limit (RCL): dpm or dps (circle one) per 100 cm 2 ., SURVEY INSTIMENT RESPONSE TO CRITICAL WCLIDE ;
Critical Expected Net Response: S ;se; Inst, tis) Used Nuclide to 1 Rct (c== or cas) Bkgd. Efficiency [1] [2] [3] Calib.. Rate Point Area Wipe of Wipeo{
.Make. Model. Ser. No. Date teom/cos) Source Egyrgg Direct 100 cm 300 cm 1.
2. 3. (1) RCL x Area Source Efficiency . [2] RCL x Point Source Efficiency (3) 3 x RCL x Point Source Ef f. CONTANINATION SURVEY RESULTS ,[ 4 -(A) Repeated entries for persons or locations that are surveyed regularly may b identified by initials ', or a code letter following a clearly identified entry on the same or previous sheets; (B) Enter "0" for a direct measurement "100" for a 100 cm2 wipe or "300" for a 300 cm2 ,gp , (C) Not count. rate of meter with probe near the contaminated surface or the wipe filtsr.
' (0) <lf the count rate in (C) is greater than the expected response to 1 RCL, as -listed above, enter the multiple of the RCL.
l l [A] [B) (C]' [D] I Survey ' Inst, Object, Lo ttion in Room Arga Net Rate Multiple Surveyed l Date MaasL or Name of Person . cm ( ) (com/cos) of RCL By l
.. j l
I
'l l
l l l l l ALL SURVEY RECORDS MUST BE RETAINE0 FOR AT LEAST THREE YEARS I O ' RPR 11. RADLAB SAFETY (1/9J) - 7 g ,
iI-ei - RPR 11A. CONTAMINATION SURVEY - PORTABLE-INSTRUMENT- gl Continuation sheet #' of record initiated on (cate) User: Subgroup: __. Bldg / Room (s): Nuclides used: Critical nuclide: ALI: mci Removable contamination limit (RCL): dpm or dps (circle one) per 100 cm' [A] [B) (C) [0] surys/ Inst. Object, Location in Room Arga Net Rate. Multiple Surveyed Date Iked_ or Name of Person f em') (com/cos) (" '".L By . i 54
. j l
6 O E-h i ALL SURVEY RECORDS MUST BE RETAINED FOR AT LEAST THREE YEARS RPR 11. RADLAB SAFETY (1/90) - 8
. _ _ . _ _ _ _ __ _ . _ ~ _ .. . . _ _ ,
o RPR 11B'. CONTAMINATION SURVEY - WIPE TESTS
.Page 1 of survey record initiated by (nese) on (date)
User:- Subgroup: Bldg / Room (s): p Nuclides used:- Critical nuclide: ALI: mci. Removable contamination limit (RCL): dpm dps nCi (circle one) per 100 cm2 COUNTING INSTRLNENT DATA 1 Type! LSC Gamma Other Model, serial #: 7 Progra# Setup: Preset: minutes or counts l Units of Readout: L Counting Channel: Ill I21 I31
Background:
Critical nuclide efficiency: l- Expected Net. Response to 1 RCL. l l WIPE TEST COLNITING RESULTS u
-[A] Repeated entries for persons or locations tha t are surveyed regularly may be identified by initials 'l or a code letter af ter a clearly identified entry on the same or continuation sheets.' I O
' (B) Enter "100" for-a 100 cm2 wipe or "300" for a 300 cm2 wipo. 'i
'h (C)- Net-response in each channel in same units as recorded above. I
'[0] If primary channel response is greater than that expected for 1 RCL, enter the multiple of the RCL.
- l l
Survey a Net Chann Resoonse Mu ple Surveyed Date Ob.iect or Location (cm ) Ill I21 I31 of RCL By l l l l l 4 i o i l' , ALL SURVEY RECORDS MUST BE RETAINED r0R AT LEAST THREE YEARS RPR 11. RADLAB SAFETY (1/90) - 9
+w -
RPR llB. Continuation sheet # CONTAMINATION SURVEY of record initiated on WIPE TESTS (cate) g User: Subgroup: Bldg / Room (s): Nuclides used: Critical nuclide: ALI: mci Removable contamination limit (RCL): dpm dps nCi (circle on.) per 100 cm2 (A) [B) (C) [0] Survey Arga Net Channel Resoonse Multiple Surveyed Date Obiect or Location Ill I21 l 31__ _ of RCL By _(SE_). i epsutts , m M O 4
- es dln k
!NkW '
re _ _ . L' 'M M . _ _" en* __ ALL SURVEY IECORDS MUST BE RETAINED FOR AT LEAST THREE YEARS O RPR 11. RADLAB SAFETY (1/90) - 10
y / t z
~BI0 ASSAYS FOR INTERNAL RADI0 ACTIVITY L PURPOSE of any exposure. Other types of assays may be utilized if, . in the judgement of This procedure specifies the requirements, the RSO, such assays will meet the intent responsibilities and methods for perform- of this policy more effectively.
! ing and reporting measurements for detect-ing and verifying the presence or absence A bioassay is required whenever personal- !
- of radioactivity in the body, contamination or injury caused'by a con- ;
- taminated object occurs, or if airborne- ,
radioactivity may have been . inhaled.. POLICY Routine bioassays, at intervals determined f' by the nuclides used, are required' from - Although the ' emphasis of a radiation each user who handles more than minimal ; protection program is primarily on quantities of dispersible radionuclides. prevention of unnecessary exposures, A routine bioassay may be waived when ap. ! measurement- and evaluation of exposures propriate surveys- for . contamination, b is also necessary. Bioassay is the deter- conducted during and after each use of mination 'of the kind and - amount (and radioactive material according to recom-
- possibly the location) of radioactive mended procedures, demonstrate that there -
L
- material in the human body by direct (in was essentially no exposure to unconfined, Y112) measurement or by analysis in vitro dispersible radioactive material, of materials excreted or removed from the L ; body. Bioassay is an important tool for Ls evaluating -actual or suspected in Yha DEFINITIONS Od- contamination with radioactive material s.
AL11 The annual ]h il on intake is the Monitoring and dose assessment must be quantity of any radionuclide which, . if. performed for any individual with an taken into the body, produces an effective annual intake of all nuclides combined dose to internal organs that is equivalent of 0.3 ALI or more. To assure that this in risk to the annual whole body dose requirement is met in all casos, individ- limit of 5 rems. Because of differences ual intakes must be detected and evaluated in physiological transport mechanisms, the at lower levels. The conditions requiring ALIs vary depending on the route of bioassays, as well as the methods and intake. For purposes of contamination maximum intervals specified in this proce- control and bioassay procedures, the ALI s-dure are designed to assure that an annual for ingestion is used, since that is the intake exceeding 0.1 ALI, whether as a most common route of accidental intake in single intake or as chronic or multiple research laboratories. , intakes, is not only detected, but deter-mined quantitatively. Removable Contamination Limit: A basic limit for removable surface contamination, - Individuals who handl9 dispersible radio- specified in " CONTAMINATION ' LIMITS ~ AND
, iodine compounds may be required to obtain ACTION LEVELS" (RPR 108).
Anyh2 measurements of radioiodine in the
% thyroid, performed by the RSO, at speci- Intake & Uotake- The total quantity of fied intervals. Individuals who handle radioactive uterial entering the body l_ other radionuclides in dispersible forms is referred to as the intake, whereas the ll may be required to perform assays of quantity absorbed into organs, tissues L radioactivity in urine on a routine basis or interstitial fluids is referred to as l to-document the absence of radioactivity the uptake.
Li in the body or to determine the magnitude I RPR 12. BI0 ASSAY (1/90) - 1 L___________________________________ - - -
Di scersible: In the context of bioassay Dosimetric assay: A quantitative bioassay requirements, "dispersible" refers to performed by an accredited laboratory to radicsctive materials in any form that provide data for annual dose determination could be taken into the body and poten- is called a dosimetric assay. The need tially transferred to body organs, tissues for a dosimetric assay will be determined or fluids, by the RSO, but it is generally required for any individual whose cumulative annual Bioassay interval: The bioassay interval intake is likely to exceed 0.1 ALI. is the maximum time that may elapse be-tween bioassays that will assure detection Investication level: An assay result that of the verification level for a given indicates a possible intake of 0.05 ALI nuclide and assay method. The bioassay or more will be investigated by the RSO interval for a particular nuclide is to decermine the cause of the exposure and g determined by its physical and metabolic corrective measures to prevent or reduce characteristics, and by the instrumenta- exposures in the future, tion used for the measurement. For most commonly used nuclides and typical analyt- Minimally exoosed: A radiation user who ical systems, the bioassay interval is 13 handles a cumulative quantity of radio-t weeks (one calendar quarter); for P-32, active materials in dispersible form of and a few other very short-lived nuclides, less than 1 ALI per month, averaged over however, the bioassay interval is only one the bioassay interval, is very unlikely month. to experience an annual intake of 0.1 All and does not require routine bioassays. Elaosed interval: The elapsed interval If exposed to contamination exceeding the is the time since an assumed intake of levels specified under " Conditions Requir-radioactive materials or, if the time of ing Bioassays", however, a nonroutine intake is unknown, since the last bios bioassay will be required. say without a positive result. ie elapsed interval is used to calculat .1e Potentially exoosed: A radiation user who intake and the effective dose froi.. a handles a cumulative quantity of radio-positive bioassay result. active materials in dispersible form of more than 1 ALI per month, averaged over Screenino assav: A screening assay is the bioassay interval, is considered to one that is performed simply tc determine be potentially exposed to an annual intake whether radioactivity may be present in of more than 0.1 ALI and must perform or the body, but without precise quantifica- obtain bioassays routinely unless the tion of activity or dose, records of contamination surveys of both the user and the RSO verify that there was Verification level: The verification no exposure to unconfined radioactive level is a result of a screening bioassay materials exceeding the levels specified , that indicates a possible intake exceeding below. 0.002 ALI sultiplied by the elapsed inter-val in weeks. A screening assay result that exceeds the verification level must C0lWITIONS REQUIRING BI0 ASSAYS be verified. The optimum time for performing a bioassay Verification assay 1 A verification assay is within a few days after a potential is one that is performed to obtain a exposure. Each user should perform a reasonable estimate of the actual quantity screening assay within a few days after of radioactivity taken into or present in handling any unusually large quantities, the body. The verification assay is or after performing any procedure involv-performed by, or under the direction of, ing a greater than usual opportunity for the RSO. exposure. Subsequent routine bioassays RPR 12. B10 ASSAY (!/90) -2
would not be required again until the end work assignments as defined by the respon-of another full bloassay interval unless sible user. Routine bioassays may be O- another unusual- exposure situation oc- waived at the discretion of the RSO if the records of contamination surveys of both curred. The RSO will notify users when a bioassay is due, i.e. the expiration of the user and the RSO verify that there was no exposure to unconfined, radioactive the bioassay interval, but it is the responsibility of the user to complete the materials exceeding the levels specified bionssay promptly. Since the last bio- above and no incidents- of personal-assay, if no work with radioactive mater-- contamination since the last bioassay, ials was performed, or if survey records
, verify that there was no exposure to contamination exceeding the levels indi- RADIGIODINE ASSAYS cated below, this may be reported by checking the appropriate statement on the The preferred bioassay method for
" URINALYSIS SCREENING ASSAY" report form gamma-emitting radioiodines is by .in y.iya (RPR 12A). measurement of the thyroid gland. These assays are performed by the RSO at pre -
1 A bioassay is required within 5 days announced locations on a regular schedule, for each individual having contamination It is the responsibility of the user to of the skin or hair exceeding 10 RCL. obtain the thyroid assay whenever appro-priate. Records of the results of these 2 A bioassay is , required within the ass 6ys are maintained by the RSO, but are normal bioassay interval.for any individ- available to the monitored individuals ual having skin or hair contamination upon request. exceeding 1 RCL. 3 A bioassay is required within 5 days SCREENING URINALYSIS for each individual involved in a spill, or other uncontrolled release, of >1 ALI A screening assay is one performed simply of radioactive material outside of a to determine whether radioactivity is properly functioning fume hood or >10 ALI present in the body, but without precise inside a hood. quantification of activity or dose. For radionuclidos other than iodines, routine 4 A bioassay is required within 5 days bioassays are most easily performed by j.D for each ;1dividual who was present in an y.Br.q analyses of urine. The same instru-area during a time when removable ments that are - used - to. measure radio-contamination exceeding 100 RCL was activity in research samples may be used
. present on any readily accessible surface. to detect the same radioisotopes in urine samples. Routine screening assays are to 5 n bioassay is required within the be performed by or for each potentially
. normal bioassay interval for each exposed individual and reported to the RSO individual who was present in an area on the " URINALYSIS SCREENING ASSAY" form during a time when removable contamination (RPR 12A).
exceeding 10 RCL was present on any read-ily accessible surface. For the nuclides used recently, determine the verification level (dpm/mL of urine) 6 A bioassay is required within the for the elapsed interval. For several normal bioassay interval for each commonly-used nuclides, the "B10 ASSAY "potentially exposed" radiation user. The GUIDELINES" that follow list the action determination of the cumulative quantity levels for various elapsed times up to the handleo will be based primarily on records maximum elapsed interval. For other of receipts and disposals of radioactive nuclides, or for elapsed times not listed, materials, with adjustments for individual RPR 12. B10 ASSAY (1/90) - 3
the action levels must be obtained from VERIFICATI0ll ASSAYS-
-the RSO, - .
If the result of a screening assay indi-The sample volume and minimum counting cates the possible presence of radioactive time must be selected so as to achieve a material in the body, at least one addi-
. lower _ limit of detection (LLD) at least. tional assay must be performed to verify equal to the required verification level. the result. A verification assay for a The "BI0 ASSAY GUIDELINES" provide examples urine sample involves spiking the ur.ine for several' common nuclides and liquid and water samples with a known amount of scintillation counting conditions, and may activity to obtain the true efficiency of be used, i f: appropriate. The minimum the counting system for the samples. '
counting time may be calculated as Follow the steps on the "URIflALYSIS VERI-illustrated later in this procedure or it FICATION ASSAY" form (RPR 128). If the may also be requested from the RSO.- bioassay result exceeds the investigation o level or indicates a potential annual for urinalysis by liquid scintillation intake exceeding 0.1_ ALI, the RSO will counting, select a fluor that is suitable determine appropriate corrective measures. ft,r large aqueous samples; Cherenkov counting- may be used for P-32 or other high-energy beta emitters. REFERENCES For urinalysis by gamma counting, as well International Commission on Radiological as by liquid scintillation counting, Protection: aroceed as follows: General Principles of Monitoring for To assure adequate sensitivity of the Radiation Protection of Workers, ICRP a measurement, use the largest vial and Publ . 35,1982. - sample volume that the counting system can accommodate. Limits for Intakes of Radionuclides by Workers, - ICRP Publ . 30, Parts 1, 2 Prepare urine and tap water samples 2 and 3 with Supplements, 1979-82. of equal volumes. Count both the urine and- the tap water sampies for the same Evaluation of Radiatton Doses to Body times. Tissues from Internal- Contamination Due to Occupational Exposure, ICRP 3 Record the sample data and results on Publ . 10, 1968. the " URINALYSIS SCREENING ASSAY" form ' (RPR 12A)'. Calculate the activity An Assessment of Internal Contamin-concentration (dpm/mL) in the urine ation Resulting from Recurrent or Pro-sample, using a nominal counting effic- longed Uptakes, ICRP Publ .10A,1971, ' iency (as provided by the vendor) for the nuclide of greatest concern. National Council on Radiation Protection and Measurements: 4 Compare the assay result with the verification level for the nuclide(s) of General Concepts for the Dosimetry of interest, based on the elapsed interval Internally Deposited Radionuclides, since last use (or last negative bioas- Report No. 84, 1984. say). If the assay result is less than the verification level, send the signed Use of Bioassay Procedures for Assess-form to the RSO. If the assay result ment of Internal Radionuclide Depost-exceeds the verification level, perform tion, NCRP Report No. 87, 1987. a " Verification Assay". RPR 12. BI0 ASSAY (1/90) - 4
m
't U.Si Nuclear Regulatory Commission:
- Acceptable Concepts, Models, Equations and - Assumptions for a -Blosssay Program, Reg. Guide 8.9. 1973.
Applications of Bionssay for 1-125 and 1-131, Reg.- Guide 8.20, Rev.1,1979. Informat ton for' Estoblishing Bloassay
, Measurements- and Evaluations of-Tritium Exposure, NUREG-0938, 1983, t
MINIMUM COUNTING TIME. CALCULATION. The lower limit of detection (LLD) for which the risks of false negative _ results and Laf false positive results are each 5% is defined as follows: LLD =
'4.66(SD3 )/Eff where:
LLD = disintegrations in sample in time T = VL x Vol x T 4.66 = the product of the distribution parameters needed to establish-the 5% error limits SD 3 = standard deviation of the background (tap water) count
-- No - - (R 3xT)' 5 N3 = total background counts in time T R3 = background count rate, in cpm Eff = detection efficiency,_in counts / dis (a nominal efficiency may be used for screening assays, whereas it should be determined experimentally for verification assays)
VL = . verification level for elapsed interval since last bioassay, in dpm/mL Vol = volume of urine in sample, in mL T = minimum counting time required, in minutes
=
R3 (4.66/VL x Vol x Eff)2 O RPR 12. B10 ASSAY (1/90) - 5
1 m B10 ASSAY' GUIDELINES g FOR URINALYSES FOR SELECTED RADI0lWCLIDES*' j Assumed Values Minimum Values I Elapsed ' Action Levels Bkgd. Count. . Sample count
' Interval- (dom /mL) Rate . Effic. Volume. Time
.Nuclide (weeks) Veri f. Invest. iggal (%)- (ml) Iminl
.E H-3 1 5,800 145,000 <25- >30% 0.2' 2 . 1 8 1,500 4,800 0.2 2
. maximum:'13 220 420 0.2 10 .t
. C-14 1 1 47 NA NA-s' ,
maximum: 8 6 20 <30 >40% 1.0 100 P-32 1 16 400 <60 >80% 0.8- 20 2 13 160 1.0 -20 3- 10 87 1.0 20 maximum: 4 7 48 1. 0_ 40_
.S-35 1 64 1,600 <30 >40% 0.2 30 4 100 660 0.2 10 I
8 65- 200 0.2- 30 maximum: 13 25 48 0.8- 20 C1'-36 1- 270 6,700 <30 >50%- 0.2 2 4 250 1560 0.2 2 y' 8 71 220 0.2- 20
.naximum: 13 10 19 1.0 30 t
-Cr-51 1 130 3,300. <25 >30% 0.2 10~ ,
4 48 300 0.4. 20 8 19- 60 l'. 0 20 .s maximum: 13 9 17 1.0 80 j FOR THYRDID NONITORING FOR RADI0 IODINES * !. , Elapsed I-125 Action Levels I-131 Action Levels Interval (nCi in-thyroid) (nci in thyroid) 4 Jweeksi Verify Investiaate ' Verify Investiaate 1 21 530- 9.4 235 l: 2 38 470 9.9 120 E 4 59 370 5.4 34-9 72 230 0.8 3 m , 13 64 120 0.05 1 h-
.
- If the nuclide(s) you work with are not listed above, or if your counting instrument has a significantly
- dif ferent background count rate or counting efficiency f rom that listed above, contact the RSO for appropriate maximum intervals, sample volumes and counting times.
L' , RPR 12. BIDASSAY (1/90) - 6
, .4 , a
RPR 12A. URINALYSIS' SCREENING ASSAY
-Name:: Soc. Sec. No.
Department: Work _ Location:- Radi-- lides u.-a since last binassay: - Action levels ~ Nuclide- . ligt My,rj).1 How Lona &ggi Verification ~ Irestiaation Mi weeks dpm/mL , dpm/mL
, mti 1 weeks dpm/mL _dpm/mLD zi- Check here if all records of contamination surveys, both by the user and the-RSO, indicate no-personal contamination ancL no exposure to unconfined radioactive materials exceeding the leveh specified under
" Conditions of use that require bioassays" in the procedure.
Check here if you have used no dispersible radioactive materials since your last bioassay. If you have checked either of the above exemption statements, provide the signatures and return the form to the RSO. Assaw Data: -Sample collection date: Date counted: Instrument used (make, model, S.N.): Sample: mL Fluor: mL Count time: minutes' Total counts from. samples :- Urine: Water: Nominalicounting efficiency for the-assay = counts / dis Concentration in dom /mL: (Urine samnle counts) 'fWater samale counts) (Sample volume, mL) x (Count time, min) x (Efficiency, counts / dis)
- dpm/mL Less than verification level? 'Yes No If less than the verification level, sign the form and obtain the signature of
, the authorized user; then send the form promptly to the RSO.
If the result exceeds the verification level, proceed with a verification assay,
. using the following form (RPR.128) for reporting.
Signatures: Counted by: Responsible User: RS0 verification of survey data: (Analyst or RS0) kPR 12. B10 ASSAY (1/90) - 7
u l RPR 128. URINALYSIS VERIFICATION' ASSAY. h
. Name: Soc. Sec. No.
X . Sample collection date: _Date counted: Instructions:
~
- 1. Complete the " Screening Assay" procedure.
- 2. Add a known activity of the nuclide of greatest concern to each sample (urine and -
water) and count again to determine the true efficiency. (NOTE: The volume of: the spike must be small enough so that it does not change the original- counting - characteristics of the sample.) If the appropriate nuclide is not available in; s a solution of known concentration from which a spike can be obtained, discuss the requirement with the RSC.
- 3. Calculate the counting efficiency and coavert the final results to disintegrations per minute per mil _liliter of. sample (dpm/ml).
Assaw Data: Instrument used: Sample: -mL Fluor: mL Count time: minutes Activity added to sample for efficiency determination: Source: Inventory No. Concentration: ~dpm/mL Volume added: mL Activity:- dpm Total counts obtained from samples: Untreated Soiked . Urine samples: Tap water samples. Efficiency in counts / dis: (Soiked urine samnle counts) - ~ f untreated urine- samole counts! (Count time, min) x (Spike activity, dpm)
=
counts / dis Concentration in don /mL: s (Untreated urine s==nle counts) - (Untreated water samole counts) (Sample volume, mL) x (Count time, min) x (Efficiency, counts / dis)
- dpm/mL Less than investigation level? Yes No If less than the investigation level, complete the signatures and mail the form
'to the RSO.- If the result exceeds the investigation level, confer with the RSO to determine appropriate follow-up assays.
Sianatures: Counted by: Responsible User: RPR 12. B10 ASSAY (1/90) - 8
. RPR 12C. THYROID MONITORING-REPORT Name: Soc. Sec. No.:
. Instructions:
, =1. Record successive counts for one individual until the sheet is filled, or until l
' ~
a verification assay is required,as long as the same instrument is used and the t calibration is still valid.
- 2. Use the same counting time for all counts.
'3. Convert to, thyroid activity if counts exceed an action level.
Instrument and calibration data: :
;p Scal er - model : - _-- - Ser. No.
- Detector - model: . Ser. No.
Calibration date: Count time: min or sec Efficiency (net counts /nC1): 1-125: I-131: I-129 check source ID: Net counts in phantom: , Screening assay data: Elapsed Verif. Phantom Thyroid Data '= Nuclide Interval Level Counts Gross Net Date Used (weeks) InfJl Bkad. L-121 (cts) .{.c.11). 10.Gil Bv-ol( l l
'l Submit the form for filing after the above spaces have been filled, or after one
, verification assay has been recorded, whichever comes first. i l
Verification assay data: . ., If screening assay exceeds the verification level, make a measurement on the thigh I to determine contribution from blood pool Use the thigh measurement as the background to determine net activity in thyroid: (Total counts from thyroid) - (Total counts from thiah) = nCi (Efficiency, net counts per nC1) l 1 If the verification assay result does not exceed the investigation level, submit the I form although no further action is required. If the investigation level is exceeded, report to the RSO and initiate an investigation. J Reviewed by: Date: cO RPR 12. B10 ASSAY (1/90) - 9
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O RPR 12. B10 ASSAY (1/90) - 10
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L L RADI0IS0 TOPE ACQUISITION AND-DISPOSITION PURPOSE disposal. For the safety of all personnel involved in radioactive waste disposal, This procedure specifies measures for the users must take all reasonable precautions control of radioactive materials from to deactivate, -detoxify and neutralize initial acquisition to final disposition. hazardous waste materials. All radio-It describes the prerequisites for order- active waste materials must be prepared Ling, or otherwise acquiring, radioactive and labeled properly before they will be
~
materials. It specifies the procedures picked up for disposal; if wastes are and forms for surveying and reporting found to be improperly prepared or the receipt of packages of radioactive labeled, they may be returned to the user i materials. Procedures for maintaining for reprocessing or repackaging under radioactive inventory records and for the supervision of the RSO. reporting all transfers and disposals of radioactive materials. Radioactive waste categories -are described, along with DEFINITIONS acceptable methods for segregation, pack-aging, labeling and reporting the disposal " Animal" waste means carcasses or parts of such wastes. of animals administered radioactive mater-ials; it also includes collected excreta and combustible bedding materials, e.g. POLICY shavings or sawdust. Radioactive materials may'be used for any " Aqueous" means a liquid that is soluble
- legitimate educational, clinical or or readily dispersible in water and which research purpose. However, they may be contains no chemicals classified as toxic purchased, or otherwise obtained, only by or hazardous; except for limits on radio-individuals specifically authorized by the activity, aqueous liquid wastes are those Radiation Safety Committee. The ongoing- which may be discarded to the sewer.
use of radioactive materials is condi-tional upon compliance with specific pro- "Campactible" waste means any -solid, cedures_ established by the Committee, nonputrescible, dry waste, e.g. paper, plastics, glassware and metals, that does The receipt of'any radioactive material, not contain any compressed gases, pyro-
.regardless of the manner in which it is phoric or other hazardous materials, obtained, must be reported promptly to the including lead.
RSO a form provided for that purpose.
"LS media" means any mixture of solvents Each user of radioactive materials must and fluors used for liquid scintillation maintain a complete record of all counting.
acquisitions, uses, transfers and dis-posals of such materials and provide "lHIT" means nonhazardous, nontoxic, non-these data to the RSO in a timely manner, flammable LS media that may be classified Before any radioactive materials may be as an aqueous liquid for disposal. I transferred to another responsible user, or to another organization, authorization " Pathogenic" means any material poten- > must be obtained from the RSO. tially containing pathogenic organisms, toxins, infectious agents, etc. Radioactive waste materials must be prop-erly segregated, packaged and labeled by O the user prior to collection for RPR 13. ISOTOPE ACQUISITION & DISPOSITION (1/90) - 1
t
" Reference quantity" means a specific the results of the external survey of the quantity of any radionuclide related to package. The first part of the form (RPR its hazard potential and used to prescribe 13A) is retained by the RSO. The second requirements for handling, labeling and and - third parts, containing the same disposal . Reference quantities for common serial number and identification data, are nuclides are listed in "RADIONUCLIDE forwarded with the package to the user.
CATEGORIES AND DATA" (RPR 10). RECEIPT AND VERIFICATION (ara las) PURCHASING PROCEDE .3 ' Each new acquisition of radioactive mate-
- All purchases of radioactive materials rial is reported on the "RADI0 ISOTOPE must be initiated on a Requisition sub- RECEIPT AND VERIFICATION" form (RPR 138).
mitted to the Purchasing Department. The user must survey the inner container i Departmental purchase orders, commonly and packing materials for contamination, referred to as "under $300 orders
- are not according to the instructions provided on to be used for radioactive materials! The the form. Any damage to, or leakage from, requisition must contain the name of the the package must be reported immediately responsible user and an accurate descrip- to the RSO. Any discrepancy in the pack-tion of the radioactive material, includ- age contents is to be noted on the form, ing the isotope and the total activity, but no radioactive materials are to be e.g. millicuries, not just a catalog returned to the vendor without notifica-number. If the order is for an authorized tion of the RSO. The survey data and isotope and quantity, the order will be verification of the package contents are processed promptly; otherwise the requisi- to be recorded and the form returned tion may be returned to the purchaser promptly to the RSO.
until proper authorization is obtained. DISPOSITION RECORD (ara 13c) RADI0 ACTIVE MATERIAL CONTROL RECORDS All dispositions of radioactive materials A serially numbered, multi-part form is are to be recorded on the "RADI0IS0 TOPE used for tracking radioactive material DISPOSITION RECORD" (RPR 13C). To avoid from the time it arrives at the University incomplete records and possible over-until it is transferred or disposed of as sights, the disposition of material should . waste. For radioactive materials acquired be recorded either directly on the dis-through normal purchasing channels, the position form (RPR 13C) or on a " DISPOSAL , forms for reporting the contamination LOG" sheet (RPR 13D) at the time it is survey of a package, for verification of placed in a waste container. However, the its contents and for reporting the dis- material will not be removed from the , position of the material will be initiated computerized inventory until the disposi-by the RSO. For materials acquired by any tion form is returned to the RSO. other means, the user is responsible for promptly notifying the RSO and providing To minimize errors in calculation of the the information necessary to initiate activity used or disposed of at various the form, times, dispositions should be reported as percentages of the original quantity, without regard to the radioactive decay PACKAGE ARRIVAL REPORT (ara 13A) or subsequent dilutions. Quantities may be reported as actual activities, e.g. When radioactive material is received, the microcuries or millicuries, but care must record is initiated by entering the iden- be taken to avoid errors. The reported tification or the user, the material, and dispositions must account for the original RPR 13. ISOTOPE ACQUISITION & DISPOSITION (1/90) - 2
q quantity- within; a reasonable degree of forms should be obtained. from the RSO.) ; g- accuracy or the form will be returned to If the material has already been entered the user for correction. into the University's inventory, this transfer form must be used in addition to reporting the transfer on the " RADIO-TRMSFERS TO OTHER LMIVERSITY USERS ISOTOPE DISPOSITION RECORD" (RPR 13c). Radioactive materials may be transferred between responsible users provided that DISPOSAL LOG the receiving user is authorized to have
- the material- and that the transfer is The " DISPOSAL LOG" (RPR 130) is an option-recorded and reported properly. It is the al form to aid radiation users in account- l responsibility of the user giving up the ing for frequent disposals of small quan- '
g material to check with the RSO to verify tities of radioisotopes. Each " DISPOSAL-the authorization of the receiving user, LOG" sheet should be used for only one and to report the transfer on the " RADIO- disposal method. A separate " DISPOSAL ISOTOPE DISPOSITION RECORD" (RPR 13C). It LOG" sheet may be used for each inventory is the responsibility of the receiving item, i.e. each " DISPOSITION RECORD", or user to request a new "RADI0 ISOTOPE DIS- -disposals from several inventory items POSITION RECORD" from the RSO and to of similar materials may be recorded on report the receipt of the material, one sheet. The total activity disposed of by each method must be transferred to the " DISPOSITION RECORD" for reporting to TRANSFERS TO NDNUNIVERSITY USERS the RSO,
- Radioactive materials may be transferred i L m to anothe; institution holding a license EMPTY C0KTAINERS issued by -the U. S. Nuclear Regulatory 4 Commission or an agreement state. It is Radiation symbols and warning labels must the responsibility of the user who wishes be obliterated before an empty radio-to send radioactive material to another isotope container is discarded. If the institution - to notify the. RSO of the container is not contaminated, it should i intended transfer. The user must not be disposed of as nonradioactive trash, i transfer any material until specific l approval is received from the RSO.
l l UNCONTANINATED DRY WASTES The RSO must obtain written confirmation of the other institution's license before Whenever possible, potentially radioactive the transfer is made. The RSO must also waste materials should be surveyed before verify that the material is shipped or disposal. Materials such as the absorbent l
, transported in accordance with the regula- paper used for covering lab benches, tions of the U. S. Department of Transpor- gloves, etc. should be disposed of as non-tation. Refer to " SHIPMENT OF LIMITED radioactive trash if the absence of radio-QUANTITIES OF RADI0 ISOTOPES" (RPR 14) ~ or active contamination Can be assured by .
" TRANSPORTATION OR SHIPMENT OF RADI0AC- direct survey. Since tritium (H-3) con- l l TIVE HATERIALS" (RPR 55) for instructions, tamination Cannot be detected by direct I L survey, materials potentially contaminated !
In the special case of transfers to or with tritium must be assumed to be from the Veterans Administration Medical contaminated. : Center (VAMC), a special transfer form l (RPR 13G) is Used; it is a multi-part form For other low-energy beta emitters, e.g. l with copies provided to the users and C-14, S-35, etc., direct surveys can l the RS0s at both institutions. (These detect contamination only on directly RPR 13. ISOTOPE ACQUISITION & DISPOSITION (1/90) - 3 ' L- _ _ - - _ _ _ _ _ _ _. _ _ . . .
I ir accessible surfaces.- For high-energy beta any one day, and that the release is e.g. P-32), x ray (e.g.1-125) or gamma recorded either on the "RADI0 ISOTOPE e.g. Na-24) emitte, s, direct surveys with DISPOSAL - RECORD" (RPR 13C) _0r on a dDIS-appropriate instruments can detect con- POSAL LOG" (RPR 130). Any sink to be used tamination beneath surface layers. for sewage disposal of radioactive mater-ials inust be approved by the RSO and shall If a careful survey verifies the absence be identified with a " CAUTION RADIOACTIVE of contamination, remove or obliterate all MATERIAL" label on the drain trap as well radiation labels and discard the material as on the sink itself. 3 Waste water from washing of contam-inated persons or equipment containing COMPACTIBLE RADIGACTIVE WASTES morethanone(1)referencequantityper i day may be released to the sewer provi-
. Solid wastes containing no putrescible or ded that the RSO is informed prior to the pyrophoric materials, no compressed gases release and that the total activity to be and no free liquids are collected and released is estimated with reasonable handled as compactible dry waste. Any accuracy.
solid wastes that would be dangerous if compacted must be segregated and clearly Subject to the preceding conditions, users labeled. The user must provide a covered are encouraged to utilize the sanitary. metal garbage can of an appropriate size sewer for disposal of biologically active (no larger than 25 gallons); the RSO pro- liquid wastes, for excreta from experimen-vides labels and plastic bag liners for tal animal s, and for wash water from dry waste containers. As materials are animal cages, laboratory glassware, etc. added to the cont /iner, the isotopes and Although it is often advantageous or even quantities should be recorded on a necessary to collect and store radioactive ,
" DISPOSAL LOG" (RPR 130) or the " RADIO- wastes containing short-lived nuclides in -
ISOTOPE DISPOSITION RECORD" (RPR 13C). order to take maximum advantage of decay: prior to release, no such benefit is obtained by. collection and storage of DISP 0 SAL TO THE SANITARY SEWER SYSTEM long-lived nuclides. Users are, there-fore, encouraged to avoid tho unnecessary
- Radioactive materials may be released to collection and storage of wastes contain-the = sanitary sewer system only if they ing H-3 and C-14.if they can be safely meet one of the following criteria: released to the sanitary sewer under the preceding criteria. .
1 Excreta from patients administered radionuclides for diagnostic or therapeu- LIQUID WASTE COLLECTION ABB SEGREGATION tic purposes may be released directly to . the sanitary sewer system regardless of Any radioactive liquid wastes that cannot total activity or concentration, be released to the sanitary sewer system under the criteria specified above are to 2 Small quantities of radionuclides that be segregated and collectsd by the waste are readily soluble or dispersible in generator for disposal by the RSO. Separ-
; water, and contain no toxic or hazardous ate containers are to be provided for substances, may be released to the sewer materials which would be incompatible 'f without prior approval of the RSO provided placed in the same container, e.g. aqueous that no more than one (1) reference quan- solutions and organic solvents, as well tity of all nuclides combined (by the sua as for nuclides with different half-lives, of the fractions of reference quantities In particular, liquid wastes containing for the indivual nuclides) may be P-32 or I-125 should be placed in separate released by any one responsible user in containers, if possible.
RPR 13. ISOTOPE ACQUISITION & DISP 00!T10N (1/90) - 4
Liquid waste containers are to be unbreak- Used vials are to be segregated, according b able, e.g. plastic jugs or metal cans, and to the LS medium and radionuclides they are.to be placed in a secondary container contain, into one of the following of sufficient volume to collect all of the categories: liquid in _the- event of a leak in the primary container. Acquisition of 1 "NHNT" media containing only H 3 and/or appropriate containers'is the responsi- C-14. bility of the user but plastic jugs for . liquid waste collection are usually avail- 2 "NHNT" media containing only H-3, C-able from the RSO at no cost. 14 and/or short-lived nuclides, (i.e.
. half-lives of less than 65 days) should Aqueous wastes must - be neutralized to be further segregated by individual prevent violent- chemical reactions when nuclides, a' the wastes are transferred. Organic solvents must be clearly and completely 3 "NHNT" media containing lom-lived identified to permit safe handling and nuclides, i.e with half-lives of greater disposal. No solid objects are to be than 65 days, other than H-3 or C-14.
placed in any liquid waste container and the materials must be~ sufficiently fluid 4 Any flamable solvent containing only to - be. poured from the container, even H-3 ar.d/or C-14. after storage for decay.- 5 Any flammable solvent containing only Biologically active materials are to be H-3, C-14 and/or short-lived nuclides, deactivated or detoxified at the time they (i.e. with half-lives of less than 65 are placed in the waste containers. A days) should be further segregated by chlorine disinfectant (e.g. Chlorox brand nuclides. liquid bleach) should be added to putresc-J O ible. liquid wastes to retard putrifica-tion;.-the quantity depends on the con-6' Any flammable solvent containing long-lived nuclides other than H-3 or C-14. , centration of organic material in the waste. Used vial: containing LS ndia should be returned to their original containers for Individual disposals to a liquid waste collection and storage; standard vials container may be recorded on a " DISPOSAL should be returned to their cardboard LOG" (RPR 13D) . Transfer the totals to the trays and cartons; mini-vials should be "RADI0 ACTIVE WASTE TAG" (RPR 12E) before pl&Ced in plastic bags of approXimately l- final disposal of the waste package. the same capacity as the original bags, he Transfer the totals disposed of from each ! inventory item to the appropriate " RADIO- "RADI0 ACTIVE MATERIAL" labels should be ISOTOPE DISPOSAL RECORD" (RPR 13C). reBoved fr05 All Vials, trays, bags and a - boxes of vials before they are transferred to the RSO for disposal. The "RADI0 ACTIVE LIQUID SCINTILLATION MEDIA Ale VIALS WASTE TAG" (Rra 1st) should be the only label indicating that the package contains Users are required to use "NHNT" LS media radioactive material. and to minimize the quantities of LS media y used, to the maximum extent that is com- Vials are to be securely capped; cartons
; patible with research requirements. The are to be securely taped and labeled to use of flam6ble LS media or standard indicate the top, e.g. "this side up".
vials must be-justified in writing and l approved by the Radiation Safety Committee. O RPR 13. ISOTOPE ACQUISITION & O!SPOSITION (1/90) - 5 L
'l ANIMAL HASTES 2 Check one material category and one or more nuclide categories contained in . Animal carcasses and body parts to be the package, picked up and stored by the RSO prior to the day of incineration are to be packaged 3 List the isotopes and their activities l and frozen for extended storage. Large in.the spaces provided. A description of animals should be dismembered so that each the material should be included for i . package contains no more than 10 kg. No materials in categories 4 or 5.
other type of material, e.g. plastic containers, glassware, syringes, needles, 4 For liquid wastes', enter the volume , etc. may be packaged with animal waste. (gallons) in a bulk container or the size The user generating animal wastes must of L.S. vials. provide sufficient freezer space for , storage of such wastes for up to one month 5 Verify whether the package contains 3 ' before collection. Combustible bedding any RADI0 ACTIVE MATERIAL labels and tape; materials, e.g. shavings or sawdust, may circle "YES" or "NO". be collected in plastic bags or cardboard cartons provided that they are tight and 6 Enter the name of the Responsible User sturdy and will not leak during handling. (or non-University generator) and the l location from which the waste originated. 1 SPECIAL WASTES Date and sign the tag to indicate " compliance with the waste generator's Any radioactive wastes not included in the certification. above categories, or exhibiting unusual hazards, or requiring special precautions 7 Tie or tape the ' tag securely to the of any kind, are handled under special waste package. - arrangements with the RSO, Costs associ-ated with - handling, packaging, and/or Labels for waste containers and packages disposal of abnormal radioactive wastes are available from the RSO. Packages that may be charged to the responsible user, are incompletely or inadequately labeled, Whenever unusual wastes are anticipated, or that in any other way do not comply
.the user should contact the RSO to plan with the criteria contained in this pro-for disposal before the wastes are cedure, will not be accepted for disposal .
generated. WASTE COLLECTION l LABELING OF RADI0 ACTIVE WASTES l Radioactive wastes of all types are col- . I All containers in which radioactive wastes lected on regularly scheduled days. Users are collected must be labeled " CAUTION - that generate large enough volumes of RADI0 ACTIVE MATERI AL" or " CAUTION - RADIO- waste to require collection at least : ACTIVE WASTE". Packages in which radio- weekly may arrange for regular collec-active wastes are stored or transported tions. Otherwise, users must. call the i must be labeled with a "RADI0 ACTIVE WASTE Radiological Health Department (Ext. ll TAG" ( RPR 13E). The tag must be completed 6141) to request pickup of the waste. To and attached to each radioactive package avoid running out of space in waste con-before it will be accepted for disposal. tainers, it is important to request pickup several days before the container will , 1 Each package may contain only one actually. be filled. The Radiological material category of waste and must be Health Department cannot guarantee waste ' L labeled with its own tag. collection on unscheduled days. O RPR 13. !$0 TOPE ACQUISITION & DISPOSITION (1/90) - 6 l
N , , ,
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D RADI0 ACTIVE WASTE INSTRUCTIONS
- AlL1 USE OF RADI0 ACTIVE MATERIALS IS CONDITIONAL UPON COMPLIANCE WITH THE. FOLLOWING REQUIREMENTS FOR PACKAGING- AND - LABELING RADIOACTIVE WASTES. .THE UNIVERSITY HAS ZERO TOLERANCE FOR NONCOMPLIANCE SINCE-IT 1 JEOPARDIZES-ALL LEGITIMATE USES. WASTE PACKAGES ARE BEING INSPECTED; 1
- INCORRECTLY LABELED ' PACKAGES MAY RESULT IN IMMEDIATE CURTAILMENT OF 1
.THE USE OF RADI0 ACTIVE MATERIAL.
4 I.ALL RADI0 ACTIVE WASTES MUST BE PROPERLY SEGRE6ATED - BY MATERIALS I AND BY-NUCLIDES. i
- 2. THE RADIOACTIVE WASTE TAG MUST BE FILLED OUT COMPLETELY AND ACCURATELY '
BEFORE THE WASTE WILL-BE PICKED UP.
- 3. THE ACTIVITY OF EACH NUCLIDE MUST BE ESTIMATED AS ACCURATELY AS j POSSIBLE AND MUST BE ENTERED IN MILLICURIES OR MICR0 CURIES.
- 4. IN ADDITION TO CHECKING THE APPROPRIATE CATEGORIES, THE WASTE TAG MUST INCLUDE A DESCRIPTION OF THE WASTES.
- 5. CHEMICAL CONSTITUENTS OF THE WASTE MUST BE IDENTIFIED BY NAME.
SCINTILLATION. FLUORS MUST BE IDENTIFIED BY BRAND NAME OR BY COMPLETE l CHEMICAL ~ COMPOSITION.
- 6. IF ANY MATERI AL IN A WASTE PACKAGE IS IGNITABLE, HA~ZARDOUS, T0XIC -
OR CORROSIVE, AS DEFINED BY-THE EPA, A " HAZARDOUS MATERIAL DISPOSAL l REQUEST" MUST ALSO BE COMPLETED BEFORE THE WASTE WILL BE PICKED UP. i ATTACH THIS FORM TO THE RADI0 ACTIVE WASTE TAG. l_
- 7. IF ALL THE NUCLIDES IN A WASTE PACKAGE HAVE HALF-LIVES OF LESS THAN 65-DAYS, AND IF THE PACKAGE CONTAINS NO "RADI0 ACTIVE MATERIAL" TAPE l
- l .0R LABELS, ANSWER "N0" TO THE QUESTION. ABOUT " RADIOACTIVE MATERI AL" ,i L LABELS; OTHERWISE, ANSWER "YES". 1 L
.- 8. PLACE. ALL SHARP OBJECTS IN' SEPARATE " SHARPS CONTAINERS".
- 9. LEAD MUST BE KEPT SEPARATE, BUT WILL BE PICKED UP. I l ,
l .IO. CALL FOR WASTE PICKUP AT LEAST 2 DAYS BEFORE IT BECOMES URGENT. L 1 L If you have any questions or problems, call Ext. 6141:
]
v 1 l: 'l Keith J. Schiager, Ph.D. , Radiation Safety Officer and ' Director, Radiological Health RPR 13. ISDf0PE ACQUISITION & DISPOSITION (1/90) - 7 l l 1
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RPR 13. ISOTOPE ACQUISITION & DISPOSITION (1/90) - 8
RPR 13A. RADI0 ISOTOPE PACKAGE ARRIVAL REPORT Inv. # User #: Responsible User: Pe9t.: P0/Ref. #: Date: Nuclide: Activity: _ mil 11 curies
Description:
~
This package contains other items: Nos. - Verify every item and return all RECEIPT & VERIFICATION forms, but ONLY ONE PACKAGE SURVEY is required. This inventory item is in packages. Return all attached RECEIPT & VERIFICATION foms. Only one DISPOSITION fem (attached) is to be completed. Exnosure Rate Survey Results: Contamination Survey Results:
<0.5 mretn/hr at surface ] <2000 net dpm/100 cm 2 direct or: _ _ mrem /hr at surface or: nec dpm/100 cm 2 on wipe mrem /hr at 1 meter Above results by survey meter.
If >SO at surface or Recipient to be notified by phone if >l at 1 meter, label if contamination is found on wipe should be Yellow II or III. by liquid scintillation count.
'RADI0 ACTIVE" vehicle placards required to transport packages with YELLOW III labels.
G Instruments: Model Ser. No. Calib. Date Efficiency Contamination: Exposure rate: __ Liquid Scint.: Count time: min Wipe results: Total count rate Backaround Net count rata Survey meter: cpm cpm
. LS counting: cpm cpm If incorrect labeling is suspected, or if any contamination is found on the package, notify the recipient promptly.
If personal or vehicle contamination is suspected, notify the Radiation Safety Officer immediately. Any required notifications to the carrier or regulatory agencies is to be made by the RSO. Package survey by: Original - Initiated and retained by Radiological Health Copies to send with the package (s): RECEIPT & VERIFICATION form (RPR 138) for each nackage and/or item. 9 OlSPOSITION form (RPR 13C) for eacn item number. l l
i t RPR 13B. RADI0 ISOTOPE RECEIPT & VERIFICATION Inv.- # User #:
- Responsible User:
Dept.: P0/Ref. #: Date: Nuclide: Activity: mil 11 curies
Description:
This package contains other items: Nos. - Verify every item and return all RECEIPT & VERIFICATION forms, , but ONLY ONE PACKAGE SURVEY is required. This inventory item is in packages. 7' Return all attached RECEIPT &~ VERIFICATION forms. Only one DISPOSITION form (attached) is to be completed. Fwnasure Rate Survev Results: Contamination Survey Results: 2
<2000 net dpm/100 cm direct-
<0.5 mrem /hr at surface ]
or: ares /hr at surface or: net dpW100 cm' on wipe areNhr at 1 meter Above results by survey meter. If >SO at surface or Recipient to be notified by phone if >1 at 1 meter, label if contamination is found on wipe should be Yellow II or III. by liquid scintillation count. RECIPIENT: YOUR PHONPT ACTION IS REQUIREDI OPEN THE PACKAGE CAREFULLY ABB SURVEY FOR CONTANINATION. VERIFY THE CONTENTS. COMPLETE AND RETURN THIS FORN.
.. PACKAGE OPENING INSTRUCTIONS:
- 1. Assume that container and packaging materials may be contaminated.
- 2. Opent in hood, if possible; wear gloves; work over absorbent paper.
, 3. Use shielding and tongs fra cgetic beta or gamma emitters.
- 4. Monitor thoroughly for con 11.. nation, including packaging materials, work area, clothing, hands, etc.
- 5. - Survey the inner container for removable contamination: .
Wipe with a small piece of filter paper and check the paper for activity. Use liquid scintillation counter for low-energy betas such as H-3, gamma counter for Cr-51', I-125 etc. or portable survey meter for energetic beta emitters such , as P-32. Report results below.
- 6. If packing materials are not contaminated, 08 LITERATE RADI0 ACTIVE NATERIAL LABELS; then discard in ordinary trash.
7.. Verify that the material' description, nuclide and activity listed above are correct, or make corrections as necessary. WIPE TEST RESULT: net cps, by Survey Meter or Sample Counter PACKAfnE RECEIVED IN GOOD CONDITION? Yes or describe: DESCRIPTION ABOVE IS ACCURATE OR HAS BEEN CORRECTED. Opened, surveyed and verified by: Date: Fold'and staple with return address visible. Mail to Radiological Health,100 Orson Spencer Hall
c RPR 13C. RADIGISOTOPE LISPOSITION RECORD Inv. # User #: , Responsible User: Dept.: P0/Ref. #: Date: _ Nuclide: Activity: mil 11 curies a
Description:
_ Ill5TRICT10ll5:
- 1. Record all uses and disposals of the material listed above.
- 2. EACH DmtY SHOULD BE EKMtESSED AS A PERCEIRAGE OF TME TOTAL QUANTITY LISTED ABOVE.
Activity may be used if decay corrected and if the units are specified clearly, ^ h 3. Transfer to another user must be approved in advance by the RSO and recorded in the space provided at the bottom of this form. 1 4. When all of the material listed above has been disposed of, return the form promptly to Radiological Health. i Sanitary Liquid Dry Scint. Animal User Date Sewer Waste Waste Vi al s Waste Initials I k O b
, TOTALS Remaining material transferred to:
-, Date approved by Rad. Health: ---
Date transferred: IF TRANSFERRED TO THE VA EDICAL CENTER, CofrLETE FORM RPR 13G (old RPR 4008) Have you accounted for all of the original material? Yes No
, To the best of my knowledge, this record is complete and accurate.
User Signature: Date: When completed, fold and staple with return address visible. Mail to Radiological Health,100 Orson Spencer Hall O
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RADIOLOGICAL HEALTH DEPARTMENT 100 ORSON SPENCEA HALL 05409 9 RPR 13. 110TOPC ACQUISITION & OISP011T10N (1/90) - 12
l RPR 13D. DISPO3AL LOG Instructions: Record individual disposals on this form. Transfer total for container to "RADIDACTIVE WASTE TAG" (ara ist) and total for each inventory item to "RADI0 ISOTOPE DISPOSITION RECORD" (apa 13c). Disposal Method: Sink Aqueous Liquid Container Organic Liquid Container Other _
, Nuclides: H3 _C-14 Itef. Quant. (pci): 1000 100 ' RPR 13C Data Inv. # _
Microcuries ner Disnesal Initials M
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1 W M M N O RPR 13. ISOTO?E ACQUISITION & DISP 051T10N (1/90) - 13
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RPR 13E. RADIOACTIVE WASTE TAG h 1 g- ; L + L i CAUTION - RADI0 ACTIVE WAITE i 1 GHLY GE MTERIAL CATEGORY ALLONED PDt PACXAGEl ,! KEEP LEAD CONTAIIIEltS SEPARATE FRt31 MSTESI I i
- 1. DRY, COMPACTIBLE, SOLIO WASTE l
- 2. ANIMAL OR OTHER BIOLOGICAL WASTE t i
- AQUEOUS LIQUID, NOT HAZARDOUS OR T0XIC
_ 3. {
* $ 4. FLAMMABLE, H'ZARDOUS OR T0XIC LIQUID 1
- t 5. OTHER MATERIAL'S i
!
- FOR #3 or #4: W LK CONTAINER: ga'lons 1 l-or VIAL SIZE: Stanerd or Minis / Baggies !
KSCRIBE MTERIAL; give names or chemicals & fluors: j
$ If any constituent is a ' HAZARD 0US M TERIAL',
p complete & attach a HAZ"mt MTERIAL DISPml ermrgy, j NUCLIDES Af;TIVITY l CHECK ALL APPLICABLF CAT]IES: H 3 and/or C-14 CWLY ] HALF-LIFE <65 days i
~
~
HEAVY ELEMENTS (mass >204) l
- l. ANY .)THER NUCLIDES l DOES THIS PACV/4E CONTAIN ANY Circle One: )'
'RADI0 ACTIVE MTERIAL' LABELS 7 YES NO IMPORTANTI MSTE GENERATOR CERTIFIES THAT PATH 0GDIS i MVE BEEN DEACTIVATED, STRONG ACIDS OR BASES MVE BEEN l NEUTRALIZED Als THAT CONTENTS ARE KSCRIBED ACCURATELY. '
l Responsible User: ; (or non-University Waste Generator) Prepared by: Date: H I RADIOLOGICAL HEALTH USE ONLY: Storage Location: Weight: lb l 1 Incinerated 2 Absorbed 3 Biostabilized 4 Compacted -5 Uncompacted Procese bete Container f: S Released 11guld 7 Released solid 8 Other Exposure rate at contacts arom/hr Disposal Date By: RPR 13E (12/89) O RPR 13. ISOTOPE ACQUISITION & DISPOSITION (1/90) - 14
- , - - . . . - - . . ~ , - . . - - ~ . . . . _ ~ - . . . . _ - . . . _ . _ . _ -. 't y 1, :.
RPR 13F, DELIVERY APPROVAL LABEL f] ! 1 i l 1
- p. - j t
- V I
\
'1 l
RADIATION SURVEY DONE I Acceptable for Delivery j By Date
} ,
- l l
I i j l 1 1 I I
, l 1
4' RPR 13. ISOTOPE ACQUISITION & DISPOSITION (1/90) - 15 l
i RPR 13G. UV-VA RADI0 ACTIVE MATERIAL TRANSFER h) Jastructions: l 1 L 1. Complete this form for all transfers of radioactive material between the ! University of Utah and the Veterans Administration Medical Center.
- 2. Verify the authorization of the intended receiver with the Radiation Safety Officer (RS0) of the receiving institution before actual transfer, i ,
- 3. All packages transported on public roads must comply with the shipping regulations of the U. S. Department of Transportation ,
t
- 4. Send appropriate copies of this fom to addresses shoun.
Licensee Identification: University of Utah (UU) VA Medical Center (VA) Utah License No. UT1800001 NRC License No. 43-03299-01 Radiological Health Dept. Radiation Safety Office 100 Orson Spencer Hall Nuclear Medicine (115) 581-6141 584-1266 Transaction: UU to VA OR VA to UU Date: Material Descrintion: Nuclide: Activity: mil 11 curies l Form (compound): . Purchase Order #: UU Item #: User Identification ftygLar_AtiA Llegibly): j Responsible User: Authorized User: . I UU Address: VA Address 1l I 1 l Sender sign here and keep 4th (goldenrod) copy: l l Send 3rd (pink) copy to RSO of sending institution. j Receiver sign here and keep 2nd (canary) copy: l Send original (white) to RSO of receiving institution. O PPR 13. ISDTOPE ACQUl$lil0N & DISP 051110N (1/90) - 16 l i
SHIPMENT OF LIMITED QUANTITIES OF RADI0 ISOTOPES O ' PURPOSE Radioactive Material: Any material with This procedure contains' instructions and a specific activity greater than 2 nCi/g. check lists to assure compliance with (173.403(y)) federal and state regulations for ship-ment of limited quantities of radio- Limitad Guantities: Packages that are isotopes to other licensees, exempt from specific packaging and label-e ing requirements because they contain no POLICY more than the following: ' Solids: 0.001 At of special form or Limited quantities of radioisotopes may 0.001 A, of other solids be shipped to another licensee only after Liquids: 0.0001 A 2 verification that all transfer, packaging, Gases: 0.001 Ai of special form or labeling and transportation requirements 0.001 A of other gaseous forms (. have been met. To assure that all /.dditio,al n limits for tritiated water.
- requirements are met, and that appropriate 3ritium gas and for instruments and
- records are maintained, a check list must devices are provided in 173.423.
l be prepared by the individual responsible for the shipment and approved by the RSO Flammable Liould: Any liquid having a before the shipment is made, flash point below 100 degrees fahrenheit. (173.115(a)] SHIPPING PNOCEDURES Limited a - titv: Flammable liquids in ( l The person plar.ning to ship a radio- individual containers having a capacity
% isotope to another institution must first of not over 1 pint, packed in strong ascertain whether the material is a limi- cutside containers, are exempt from the l ted quantity. Refer to the DEFINITIONS labeling and specification packaging i and to Table 1. If the material is a requirements. (173.118(a))
l limited quantity, use this procedure; if not, follow the instructions in C Ystible Liauid: Any liquid with a
" TRANSPORTATION CF RADI0 ACTIVE MATERIAL" flash point of 100 to 200 degrees fahren-(RPR 56). heit. [173.115(b))
l 2 Before packaging or labeling the mater- Cantamination Limits: Removable contamin-l ial, complete the "RADI0 ISOTOPE LIMITED ation on-the surfaces of any package or l QUANTITY CHECK LIST" (RPR 14LQ). vehicle shall,be determined by wiping an r area of 300 cm ; the measured activity on l - 3 Prior to shipment, the RSO must verify the wipe shall not exceed 3 nCi (6600 dpm) ! the license status and shipping address of beta emitters, natural uranium or l of the consignee, and approve the packag- thorium, or 0.3 nci (660 dpm) for other l ing and contamination survey, alpha emitters. (173.443) AIRBORNE SHIPMENTS Shipping Paner: A shipping order, bill of lading, manifest or other shipping ! The only radioactive materials that document serving a similar purpose and may be transported on a passenger-carrying containing the information required by aircraft are those intended for use in, 172.202, 172.203 and 172.204. L or incident to, rer,earch or medical diag-I nosis or treatment. USDOT DEFINITIONS-RPR 14 LIMIT [D QUANTITY SHIPMENTS (1/90) - 1
1
)
Table 1. DDT TYPE A QunNTITIES From 173.435 except as indicated by *. Nuclide A1 (C1) A2 (C1) Nuclide A1 (C1) A2 (Ci',, l l H-3 20. 20. Be-7 300. 300. I C-14 1000, 60. Na-22 8. 8. ' Na-24 5. 5. P-32 30. 30. S-35 1000, 60. Cl-36 300. 10. , l Ca-45 1000. 25. Sc-46 8. 8. I Cr-51 600, 600. Mn-54 20, 20, i Fe-55 1000. 1000. Fe 59 10. 10. . I Co-57 90. 90. Co 60 7. 7. , Ni-63 1000. 100. Zn-65 30. 30. I Ga-67 100. 100. Ga-68 20. 20. ! 40, Ge-68 20. 10. Se-7E 40. Kr-85 5. 5. Rb 86 30. 30. Sr 85 30, 30. Sr-90 10. 0.4 Nb-95 20, 20. No 99 100. 20. Tc-99 1000. 25. Tc-99m 100. 100. ' Ru 103 30, 25. Ru-106 10, 7. Cd 109 1000. 70. In-111 30. 25. In-113m 60. 60. Sn-113 60. 60. 1-123 50, 50. 1-125 1000. 70. 1-129 1000. 2. 1-131 40. 10. Xe-133 5. 5. Ba-133 40. 10. Cs-134 10, 10. Cs-137 30. 10. Ce-139 100. 100. Ce-141 300. 25. Pm-147 1000, 25. Gd-153 200, 100. Ir-192 20. 10. Au-198 40, 20.
%-197 200. 200. Hg-203 80. 25.
.T1-201 200. 200. T1-204 300. 10.
Pb-210 100, 0.2 Po-210 200. 0.2 - Ra-223 50, 0.2 Ra-224 6. 0.5 Ra-226 10. 0.05 Ra-228 10. d 05 Ac-227 1000. 0.003 Ac-228 10. 4. . Th-227 200. 0.2 Th-228 6. 0.008 Th-229* 2. 0.002 Th-230 3. 0.003 Th-231 1000, 25. Th-232 Unlimited , Th-234 10. 10. Th-natural Unlimited Pa-231 2. 0.002 U-232 30. 0.03 U-233 100, 0.1 U-234 100, 0.1 U-235 100, 0.2 U-238 Unlimited U-natural Unlimited Np-237 5. 0.005 Fu-238 3. 0.003 Pu-239 2. 0.002 > Pu-241 1000. 0.1 Pu-242 3. 0.003 Am-241 8. 0.008 cm-243 9. 0.009 Cm-244 10. 0.01 Bk-249 1000. 1. Cf-249 2. 0.002 Cf-252 2. 0.009
- Calculated per 173.433 RDR 14. LIMITED QUANTITY SHIPMENTS (1/90) - 2
RPR 14LQ. RADI0 ISOTOPE LIMITED QUANTITY CHECK LIST Instructions: This form is to be completed for shipments of limited quantities of any radioactive material other than waste, to any licensee other than the VAMC. The individual desiring authorization to ship the material shall complete this form and submit it to the RSO for approval before the material is shipped. Consignor funiversity of Utah Ramanasible User): Name: Phone: Department: Address: t Consignee (Individual and Omanization): Name: Phone: Address: Authorization: Consignee's License #: Expiration Date: ! Consignee's RSO: Ph'one: l' License copy on file? or other verification: LO Packaos Contaniy and Hazardous Material Classification: Initials Contents Radionuclide: Activity: mci DOT Limits:- A 3 C1 A2 C1 Limited Guantity Criteria , If special form material (i.e. sealed source), less than 10'3 A. 3 i If other solid material, less than 10 3 A,. If liquid material, less than 10 A .2 [173.423] Less than 15 grams U-235. [173.421] The package contains no hazardous material other than radioactive material. l I-(If this is not true, the packaging and labeling requirements are determined by the other hazardous material.) Other Hazardous Material in Package: (Continued on next page) O RPR 14 LIMITED QUANTITY $HIPMEhis (1/90) - 3 L___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - --
l Initials Caatainer Strong, tight package that will not leak during conditions normally incident to transportation [173.24 and 173.42!1 Good physical condition with no evidence of damage, corrosion or leakage. [173.475) Labels and Markings Names of consignee and consignor on outside of package. The following statement must be on the package and on the shipping paper:
"This package conforms to the conditions and limitations specified in 49 .,
CFR 173.421 for excepted radioactive material, limited quantity, n.o.s., L212910.' [173.421-1(a)] If to be shipped oi. a passenger-carrying aircraft, the following certifica-
- tion is required on the shipping paper: "The above-named materials are intended for use in, or incident to, research or medical diagnosis or treatment.' (172.204(c)]
The outside of the inner package or, if there is no inner packaging, the outside of the packaging itself bears the marking " Radioactive". (173.421(d)] Prepared by (signature): Date: Initials Radiation Survey Exposure rates measured with (Model) Ser. No.: Calibration date: Maximum at surface = mR/hr Less than 0.5 mR/hr at all points on the surface of the container. [173.421) Contamination measured with (Model) Ser. No.: Efficiency: _ Calibration date: Count rates: Gross: cpm Backg) wnd: cpm Net: cpm less than 0.3 nCi (660 dpm) alpha and less than 3 nCi (6600 dpm) beta-gamma removable contamination per wipe of 300 ca'. [173.421,173.443(a)) 1 Surveyed by (signature): Date: RSO approval (signature): Date: O RPR 14 LIMITED QUANTITY $HIPMENTS (1/90) - 4
i_ O aoustaa ano ainotino or a^oroactive ^ainats 1 PURPOSE Contaminated bedding material and animal l carcasses must be treated as radioactive 1 This procedure specifies conditions and waste and handled as outlined in i methods for handling animals, bedding and "RADI0 ISOTOPE ACQUISITION AND DISPOSITION" l excreta from experiments involving radio- tRPR 13). Excreta may be put down the I isotopes administered to animal subjects, sewer provided that a record of the ( This procedure addresses only the radia- activity released to the sewer is kept as tion protection aspects of such experi- specified in RPR 13. ments; all other aspects of animal care are controlled by the Director of Animal l Resources. ANINALS NOT REQUIRING RADIOLOGICAL CONTROL DEFINITIONS Animals may be housed in the Animal l l Resource Center or other areas not specif-An animal unit is one large animal occupy- ically controlled for radiation protection I ing a single cage or run, or a g.aoup of purpose, if they can be cared for by l small animals housed in cages carried on nonradiation workers without regard to ! a single rack or cart, or any comparable radioactivity content. Animals that meet I grouping oT experimental animals, the following criteria represent no hazard i to the individuals that handle them, and A cambined reference quantity is the sum require no special control of contamina-
/~
of the fractions of individual isotopic tion or external exposure: l reference quantities ccntained in one ) animal unit. Refereuce quantities for 1 :imals that are not subject to radia- 4 l most commonly used radionuclides are Lion controls may contain only l l listed in "RADIONUCLIDE CATEGORIES AND nuclides that are present in such , DATA" (RPR 10A). small quantities, or that are so tightly bound, that no more than one l A controlled area is a 1aboratory or combined reference quantity is excret-animal room that is posted and secured for ed per animal unit per day. A record ' l r41ation control purposes, that verifies this allowed release by .
' calculation or measurement must be I maintained. 1 i ANIMALS REQUIRING RADIOLOGICAL CONTROL 2 The external dose rate from animals Animals must be housed in controlled areas that are not subject to radiation if they exceed either one of the following controls may not exceed 0.25 mrem /hr criteria: at one meter from one animal unit. '
I the external dose rate at one meter All administrations of radionuclides are from one animal unit exceeds 0.25 to be performed in an established radio-mrem /hr,or active material work area before the animals are placed in the Animal Resource 2 the radioactivity that will be Center or other uncontrolled area, excreted from one animal unit exceeds one combined reference quantity per Bedding material may be put in ordinary day, dry trash and excreta may be put down the O sewer. Carcasses of animals that did not RPR 15. RADI0 ACTIVE ANIMALS (1/90) - 1 1
i require radiation controls for handling Ex==al e 2: The dog is labeled with the and housing must still be disposed of as same quantities of Sr-85 and Nb-95, but radioactive waste (see RPR 13). The only 300 #Ci of Se-75. The dose rate at 1 exception to this requirement would be meter would now be: animals that contain only H-3 or C-14 at a concentration of less than 50 nanocuries Dose rate = (0.09x0.75) + (0.085x0.48) per gram, averaged over the mass of the + (0.3x0.86) = 0.37 mrem /hr entire animal. These animals may be released directly to the Animal Resource The investigator should plan to keep this Center for disposal, provided that a animal in a controlled area, at least , record of the radionuclide concentration until a measurement of the external ex-and disposition is reported (RPR 13). posure rate with an appropriate instru- , ment demonstrated it to be less than 0.25 ' An animal unit containing more than 10 mrem /hr. combined reference quantities must be labeled with a CAUTION RADIOACTIVE MATER-IAL sign on the cage, run or cage rack, DETEMINATION OF DAILY EXCRETION RATE , even though the external dose rate is l 1ess than 0.25 mrem /hr at one meter. The daily excretion rate of the admini-stered radionuclides will depend on the elemental characteristics of the radio-CALCULATION OF EXTERNAL DOSE RATE nuclide, the chemical form, the method of administration and the animal species. A calculation can be made prior to label- Frequently, a significant fraction of the ing an animal to estimate whether or not material 1: excreted within the first day - the 0.25 mres/hr dose rate limit is likely or two af~er administration. If the to be exceeded. The dose rate in mrem /hr metabolic >ehavior of the administered at one meter will be the sum of the pro- material h not known in advance, the ducts of the activity of each isotope in investigator -hould plan to keep the millicuries (mC1) and the external dose animals in a controlled area for the rats constant (X), as found in " RADIO- first day or two and measure the activity NUCLIDE CATEGORIES AND DATA" (RPR 10A). excreted. Wnen it Can be demonstrated that the excretion rate has decreased to Dose rate (areng/hr) less than one combined reference quantity per day, and if the exoosure rate is less
- SLM(Ai (mCl) x Xi (ares /hr-mC19 Im)] than 0.25 mrem /hr se he meter, the ani-mais could then b woused in the Animal e Ex== ale 1: A dog is labeled with 90 #Ci R0 source Center ur other uncontrolled of Sr-85, 85 #Ci of Nb-95 and 90 #Ci of area.
Se-75; the dose rate at I meter would be:
- s If the metabolic behavior of the admini-Dose rate = (0.09x0.75) + (0.085x0.48) stered material is well known, calcula-
+ (0.09x0.86) = 0.19 mrem /hr tions of expected excretion may be sub-stituted for measurements. If the excre-This would be an acceptable dose rate tion even during the first day after '
and, based on the external dose-rate administration will be less than one criterion, the dog could be kept in the combined reference quantity, the animals Animal Resource Center. However, the may be housed in an uncontrolled area excretion-rate criterion would also have immediately, to be satisfied. O RPR 15. RADIDACTIVE ANIMALS (1/90) - 2
HANDLING OF RADIATION ACCIDENT VICTIMS PURPOSE These procedures provide guidelines for the handling, isolation, decontamination and exposure evaluation of individuals requiring emergency medical treatment following accidental exposure to radioactive contamination and/or to external radiation sources.. They are specific for the Emergency Department (ED) of the University of Utah Hospital and are intended to prevent unnecessary exposure to ED personnel and to prevent contamination of ED equipment and facilities. IlgtEDIATE NOTIFICATIONS As soon as word is received that a patient will be arriving, or as soon as the pa-tient arrives at the ED, notify immediately at least one individual in Anth of the following categories: DAY HllitiL PAGER Emergency Department ED Supervisor (via Operator) 581-2121 (day or night) Attending Physician 581-2291 581 2291 535-3522 Radiation Safety Officer (RS0) Attempt to contact in the order listed: Keith J. Schiager 581-6141 484-5007 Byron L. Herdy 581-6141 968-8149 John H. Moeller 581-2396 571-5679 Security 581-2295 (day or night) (or Hospital Operator) 581-2121 (day or night) Hamatoloav Dr. James P. Kushner 581-6734 943-0174 Dr. John W. Athens 581-6734 277-5214 Hematology Fellow on call 581-2121 535-3862 O RPR 20. RADIATION ACCIDENT VICTIMS (1/90) - 1
RADIATION DERGDICY EQUIPENT 1 A Radiation Emergency Kit is located in the Air Medic Cabinet, Ambulance h Entrance Foyer. The kit contains: a Survey meter b Direct reading dosimeters and charger c Radiation warning tape, rope and labels 2 A portable lead shield is available from the Sixth South Nursing Station. 3 Absorbent, plastic-backed sheeting is available from the Radiopharmacy. PATIENTS CONTAMINATED WITH RADIGACTIVE MATERIAL Evaluation of Patient's Contamination Status 1 Lifesaving care of critically injured accident victims takes priority over all other considerations. Patients should be treated in the trauma room, i using the contamination control precautions described below. l l 2 The type of accident should be determined as quickly as possible. Write down any information provided by the accident victim or witnesses and give it.to the Radiation Safety Officer (RS0) as soon as he arrives. 3 Persons with known or suspected contamination from radioactive materials on , or in the body, and attending personnel who have come in contact with these ! patients, must be surveyed by the RSO to determine the extent of contamination. 4 Identify contaminated patients or attending personnel with radioactive material warning tape or labels until decontamination has been completed. Facility Contamination Cogiggl 1 Extreme care should be used to prevent the possible spread of contamination. Avoid transporting possibly contaminated patients or personnel through hospital. Critically injured patients may be treated in the ED trauma room. All others should wait on the dock outside the ED and have their movements < restricted until they are surveyed. 2 Restrict traffic flow into and out of areas with known or suspected contamination and limit access to essential personnel. Survey all individuals leaving these areas. 8ttendina Persggp1 Ernature and Contamination Control 1 Minimize the number of attending personnel. 2 Attending personnel must wear protective clothing (surgic' gowns, masks, caps, gloves) obtainable from the ED supply room. RPR 20. RADIATION ACCIDENT VICTIMS (1/90) - 2 O
l 3 If exposure rates to attending personnel exceed 50 mR/hr, direct-rwading ! dosimeters should be worn, preferably under the protective clothing. It may , also be necessary to obtain and u.e the portable lead shields as directed by l the RSO. , 4 Personnel coming in contact with contaminated patients must be surveyed for contamination before leaving the immediate area. ] Patient. Care and_Dosimetr_v 1 Collect nasal swabs or nose blowings, urine, feces and possibly gastric i contents for analysis to determine the possibility of internal contamination. Decontamination or gastric lavage procedures, if required, are to be done in 2 the decontamination shower stall (in the outside foyer of ED) under the , supervision of the RSO, If necessary to perform elsewhere, the floor should ' be covered with plastic backed absorbent pads. 3 Remove the patient's clothing completely and retain in a plastic bag for i anal;' sis and decontaminktion. 4 Wash the skin with warm soap and water, until decontamination is considered - adequate by the RSO. PATIENTS WITN HIGH RADIATION EXPOSURES 1 Patients found by the RSO not to be contaminated may receive normal care under , the direction of the supervising surgical resident and the hematologist. - l 2 Patients that were exposed only to external radiation sources, e.g. x-ray machines, particle accelerators, sealed radioactive sources, radiation therapy , machines, neutron sources, etc. pose no risk to attending personnel and may be handled in routine fashion. 3 If the exposure is not known, or if it is estimated to exceed 25 rem to a major portion of the body, the victim must be admitted to the hospital for observation of possible radiation effects. 4 Blood samples may be requested by the hematologist for white cell counts. l 5 For patients receiving neutron exposures, blood and urine should be collected i for radioassay. Rings, watches, and other metal objects also should be collected for activation analysis. O RPR 20. RADIATION ACCIDEhi VICTIMS (1/90) - 3
ADDITIONAL PERS0181EL 10 BE INF015ED IN RADIATION ACCIDDfT CASES Hospital Administration: Asst. Administrator for general services 581-2680 Administrator "on call" Sal-???S 581-2121 (Page #: 530-8097) For patients having accidentally ingested or inhaled radioactive materials: Nuclear Medicine Physician (on call) 581-2716 482 6616 (beeper) Nuclear Medicine Technician (on call) 581-2716 482-6591 (beeper) For patients exposed to x-ray machines, linear accelerators, or other external sources; also internal sealed sources (. Iridium, Iodine, Cesium): J. R. Stewart (Radiologist) 581-8793 322-3252 D. G. 8ragg (Radiologist) 581 7553 277-3516 For serious accidents: To be contacted by the RSO: Utah Bureau of Radiation Control 533 6734 Nuclear Regulatory Commission 1-817-860 8100 h v 7 p RPR 20. RADIATION ACCIDENT VICTIMS (1/90) - 4 9'
RADIATION PROTECTION OF NURSES AND THERAPISTS PURPOSE Demonstrate knowledge of radiation dose limits and individual monitoring This pre" % e establishes guidelines for requirements for radiation users, and radiatie b $ction of nurses, therapists for the embryo / fetus. and othd wno attend patients during fluoroscopic examinations or radiation Report a suspected pregnancy to the therapy with radioactive implants. Head Nurse promptly to assure appro-Responsibilities for assuring the various priate work assignments. aspects of radiation protection are specified. The Physician shall: POLICY Inform the nursing unit of fluoro-scopic techniques that will be re-Personnel who are required to attend quired or of the location of implanted patients undergoing various radiological sources, procedures are to be protected from rad-iation exposure to the greatest extent feasible, consistent with providing safe, The Head Nurse shall: competent care of the patient. Ensure that all employees who may be attending patients curing fluoroscopy RESPONSIBILITIES or radiation therapy are provided with appropriate training. (.* radiation O- . The following individuals are responsible safety training session may be re-for the specific aspects of radiation quested annually from the RSO, Radio-protection described for each of them. logical Health Department, Ext. 6141. A handout for new employees is also available from the RSO.) The Nurse, Therapis'. or Other Employee shall: Provide lead aprons for use by anyone who must be within 3 feet of the pa-Demonstrate knowledge of radiation tient during fluoroscopic procedures, protection principles, particularly the use of time, distance and shield- Assign pregnant employees to duties ing for minimizing radiation that will minimize exposures to radia-exposures, tion. Utilize lead aprons, and other protec- Inform staff, patient and family of tive apparel or equipment, as any activity or time restrictions for instructed, care or visitation. Avoid placing any part of the body in the direct beam of a fluoroscopy unit The Radiology Department shall: at any time. (If there is ever an absolute need to place a hand in the Provide specific, written instructions beam for any reason, lead gloves must for control of radiation exposures and be worn in addition to a lead apron.) contamination during care of patients with radioactive implants or thera-peutic doses of radiopharmaceuticals. RPR 21. NURSES AND THERAPISTS (1/90) - 1
The Radiation Safety Officer shall: Establish consistent University and Hospital policies for radiation pro-tection,. training and monitoring. Provide radiation safety training sessions upon request or at the fre-quency required by regulations. Evaluate the exposure potential of radiation users to assure that they are properly classified for monitoring purposes. Provide individual radiation dosi-meters (film badges) to all normally exposed radiation users. 9 O RPR 21. NURSES AND THERAPl$T$ (1/90) - 2
L i RADIATION SAFETY IN DIAGNOSTIC RADI0i.0GY PURPOSE INSPECTIONS This procedure defines the responsibili- Each x-ray machine must be inspected at ties for protective equipment, radiation regular intervals by a qualified ex)ert and safety surveys, operating procedures (UBRC, R447-16). The inspection sia11 and quality assurance programs for x-ray include machine function, film processing, machines used on humans fer diagnostic facility design including shielding, purposes, operator procedures, documentation of operator qualifications, and evaluation of patient exposures. The RSO is respons-POLICY ible for assuring that appropriate inspec-tions are performed and documented for all Users of x-ray machines for diagnostic University x-ray facilities. purposes are responsible for radiation l protection of empicyees and patients. The Radiology Department employs qualified Quality assurance for equipment and pro- experts who perform the regular inspec-cedures is an integral part of the re- tions of x-ray machines belonging to the s)onsibility for patient welfare and is, Radiology Department and maintain the t1erefore, the responsibility of the records of such surveys. Any defect or ! medical and administrative staffs of the malfunction identified during such sur-University Hoepital and other University- veys is to be reported in writing to the related patient care facilities. RSO, who is responsible for assuring that corrections are made and for the necessary
\ The Radiation Safety Officer (RS0) ja documentation, responsible for assuring that all equip-ment, facilities, procedures and practices involving ionizing radiation comply with QUALITY ASSURANCE PROGRAMS applicable federal and state laws and regulations, and that complete and Each department or user that is respons-accurate records of actions pertaining to ible for an x-ray machine used on humans radiation protection are maintained, shall develop and maintain a quality 1 assurance (QA) program in accordance with guidelines published by the U.S. Food and l
REGISTRATION Drug Administration (FDA), the American i Association of Physicists in Medicine ! The RSO will maintain complete records of (AAPM) and/or the National Council on the x-ray machines possessed by the Uni- Radiation Protection and Measurement versity, based on information submitted (NCRP). The QA program will be reviewed. by the individual responsible. for each regularly by the RSO and documented in a machine. All x-ray machines must be report to the Radiation Safety Cassaittee. registered annually with the Utah Bureau l of Radiation Control (UBRC). To avoid duplication or omission of records, TRAINING OF PERS0000EL registration forms are to be submitted to the UBRC only by the RSO. Departments All users of radiation sources require having x-ray cachines will reimburse the training on radiation protection; adequate Radiological Health Department for the training is especially important for those cost of registration. who apply radiation to humans. The Radi-
,, ology Department provides training for its own employees and trainees and RPR 23. RADIAfl0N SAFETY IN DIAGNOSTIC RADIOLOGY (1/90) - 1 1
r-.-,-... ,, - . , . . . - _ _ _ , _ , , _ _ . _ _ _ _ _ _ . _ _ _ . _ . , _ . , . , , _ . _ _ _ _ , _ , _ , _ _ _ _ _ _ , _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ . _ , , _ . _ . , _ _ . _ _ _ _ _ _ _ _
i i maintains the records of such training. The same training is made available to , users .of x-ray machines in other ! departments but the records' of training ; for personnel from other departments must i be submitted to, and retained by the RSO. 1 The RSO offers additional . specialized i training to groups with unique radiation ; protection problems. REVIEW Als ALBIT 3
-All records of surveys, inspections, i
quality assurance programs and 1 monitoring, training re lated to radiation protection j will be available for review and auditing by the RS0 and/or the Radiation Safety Committee. REFERDICES , l National Council on Radiation Protection ; and Measurements, Quality Assurance for J
~ Otagnostic Inaging Equipment, NCRP Report !
No. 99, Bethesda, MD, 1988. l Utah ~ Bureau . of Radiation Control, Utah ! Radiation Control Regulations: ' General requirements applicable to the
- ssta11ation, registration, inspec- i tito and use of radiation machines, .
R44,- 16. Use of x-rays in the healing arts, R447-28. 0 RPR 23. RADIATION SAFETY IN DIA6h0$ TIC RADIOLOGY (1/90) - 2
ANALYTICAL X-RAY MACHINES PURPOSE ' Fail safe' u.eans features that prevent exposure of personnel upon the failure of This procedure specifies requirements for a safety or warning device. analytical x-ray machines, including registration, physical safety features, 'Open beam' means any mode of operation training and operational recuirements for in which any portion of the user's body users, and regular safety inspections. could be placed into the primary beam during normal operation if no further safety devices were incorporated. POLICY A *nonna11y exposed radiation user" is an All operable x-ray generating machines individual who could receive more than one used in University of Utah facilities must tenth (10%) of the occupational dose limit be authorized by the Radiation Safety in any calendar quarter. This category Committee and must be registered with the includes individuals who rarely receive Utah Bureau of Radiation Control. All radiation exposures, but who work with authorizations and registrations (includ- sources that could produce a significant ing fees) shall be submitted to the Radia- dose accidentally. tion Safety Officer (RS0) for review and processing. The RSO must also be notified A ' minimally exposed radiation user" is before moving, transferring or disposing an individual who is unlikely to receive
. .. of any x ray machine, one tenth (10%) of the occupational radia-tion dose limit in any calendar quarter.
The responsible user for each analytical x-ray machine shall assure that detailed o>erating procedures are available and REFERENCE t1at each operator has received appropri-ate training and understands and follows " Radiation Safety Requirements for Analyt-the correct procedures, ical X-ray Equipment", R447-40, Utah Radiatton Control Rules, Utah Department of Health. Each responsible user should DEFINITIONS obtain a copy of R447-40 from the RSO and be familiar with its contents.
" Analytical x-ray" refers to machines or systems used to determine the composition or microstructure of materials by means EQUIPMENT REQUIRDIENTS of diffraction or fluorescence analysis.
The requirements specified in regulation
' Beam-blocking device" means any part of R347-40-30 apply to all of the Univer-an analytical x ray machine or accessory sity's analytical x-ray equipment. The that may be struck by x-rays, such as important requirements are itemized in radiation source housings, ports and " ANALYTICAL X-RAY MACHINE SAFETY INSPEC-shutter assemblies, collimators, sample TION" (RPR 30A). This record is to be holders, cameras, goniometers, detectors completed by the responsible user at the and shielding, time the machine is first registered and submitted to the RSO. The inspection
" Exposed beam' means the operation of a form is also to be used as a safety check nonnally enclosed analytical x ray machine list after any maintenance or modifica-with any beam-blocking device removed and tion that requires disassembly, the x-ray beam on.
1 RPR 30. ANALYTICAL K RAY SAFETY (10/89) 1
q f f ] i OPERATIM REQUIRDElfiS EXP0 0RE MONITORIE g Each person who will operate or maintain Users of open beam analytical x-ray ur.its, ! analytical x-ray equipment shall first and users of enclosed units who are receive appropriate instruction and demon- approved to perfom maintenance procedures ' strate competence on all topics specified with an exposed beam, are classified as in R447-40 60(1). normally exposed. Each nomally exposed , radiation user of analytical x-ray equip-Written operating procedures covering ment must complete the
- RADIATION USER :
both normal and abnormal (emergency) PERSONAL. DATA" form (RPR 1A). A finger conditions shall be available to, and dosimeter (TLD ring) will be issued within followed by, all users of analytical x- approximately one week after the data form ray equipment. The operating procedures is received by the RSO. The dosimeter shall include detailed instructions for must be worn whenever the x-ray machine , sample insertion and manipulation, equip- is operating and must be kept in an ment alignment, routine maintenance by unexposed location at all other times, the user and recording of data related to radiation safety. Dosimeters are exchanged monthly; new dosimeters are distributed within the No person shall bypass a safety device first three working days of the month and
- without the written authorization of the used dosimeters must be returned to the RSO (R447-40-50) . Individuals who expect RSO by the 9th of the month. Fines are to perform maintenance that requires the imposed for late or lost dosimeters (see i presence of the primary beam when beam- the Radiation Safety Polfey #anual),
blocking devices are renoved must be authorized in advance by the Radiation Users of enclosed x-ray equipment who are Safety Committee and must notif,I the RSO not specifically approved to perform that such work is expected. maintenance procedures with an exposed beam are classified as minimally exposed and are not issued personal dosimeters. RADIATION SURVEYS , Experience has shown that accidental l The RSO will survey the radiation expos- x-ray ure rates in accessible areas near an exposuresfromenclosed(cabinet) equipment have usually been to finger analytical x-ray machine at least once a tips and were not accurately recorded year. The responsible user must request, even when dosimeters were worn. Further-or perfom and recorti, a radiation survey: more, accidental exposures have often been so severe that biological effects 1 following any change in the arrange- appeared before the ' user dosimeter was ment, number or type of components, processed. Under such circumstances, dosimeters contribute nothing to radia-2 following and maintenance requiring tion protection or to long-term exposure l disassembly on removal of a component, records. 3 during any maintenance or alignment Any suspected ' exposure to the primary procedure that requires the presence beam of an analytical x-ray machine must of a primary x-ray beam when a com- be reported promptly to the RSO. ponent is disassembled or removed, or 4 any time a visual inspection reveals an abnormal condition. O RPR 30. ANALYTICAL X-RAY SAFETY (10/89) - 2
- - m , - , - - - - - - - , , - - - - -
RPR 30A. ANALYTICAL X-RAY MACHINE SAFETY INSPECTION Responsible user Phone R.u.# suberup : 1.ocation (Bldg. & Room) Installation date , Tvoe and use Manufacturet Model Serial No.
. Open beam control unit:
_, Fully enclosed (Cx) X-raytube(s): Diffraction (x0) Number of ports available: _ In use: Fluorescence [xr) Target material kVp mA Accessory equipment (powder cameras, goniometers, etc.) Inspection date FAtlLITY a[0UIREM ETS "CAUil0N - X RAY (QUlPM(NT" (or equivalent) sign at entrance? Yes Bo "N0ilCE TO WORKER $" (BRC 04) posted conspicuously? Yes to Was the last radiation survey performed no more than 12 months ago? Yes to
$1nce the last radiation survey, have any of the following conditions occurred?
Removal or disassembly of any component that normally t, tops the primary beam? Yes to Exposure of more than 1.000 mrem per quarter to any finger destmeter? Tee 5o IGulPR[ET REQUIREMENTS Safety Devices Required on open beam unita - a device that prevents any portion of the body from entering the primary beam, or a device that terminates the beam if obstructed. Tes Bo IF "N0". has esseption been filed? Yes to tiens and Labels
*CAUil0N: HIGH IN W.411Y X-RAY 8EAM" - on source housing? Yes to "CAUil0N - RA01A110N. THl$ (QUIPMENT PRODUCES RADIATION VHEN [N(RG12[0"
- near switch used to turn on unit? Yes Bo
" CAUTION - RA010 ACTIVE MAffRIAL" - on housing. If appropriate. Tes to Warning Lights or Devices - All units "X RAY ON" light - near any switch that energires and near any x ray port Yes No if radioactive source near any switch that opens a housing or shutter Yes to On new equipment installed after November 1983 Itght shall be fati safe Yes to Additional Warning Devices Required for Open beam units X RAY TU8E STATUS. "0N/0FF" - located near the radiation source housing, and at or near the port, if the primary beam is controlled in this manner Yes Bo Shutter Status *0 PEN /CLO$t0" - located near each port on the radiation source housing. If the primary beam is controlled in this manner Yes to On equipment installed af ter November 1983, all warning devices must be f ati safe Yes to Ports and shutters Unused ports on radiation source housing shall be secured in the " closed" position in a manner that will prevent casual opening. 1.e. without the use of tools Yes No On equipment installed after November 1983, open beam units shall have ports equipped with a shutter that cannot be opened unless an experimental device has been connected Yes Bo O
l R8R 30. ANALYTICAL K-RAY $AFETY (10/89) - 3
i l GPEA&IlbE RfelllREKEil i Are written operating procedures available to all users of x ray equipment? Yes to Has written approval been granted by the Radiation $afety Committee or the RSO for operation of the unit in a manner other than specified in the written procedure or for bypassing safety devices? Yes to PER10AREL REIMilREKEIS Have all persons operating x-ray equipment received instruction and demonstrated adequate knowledge of: Tee he ; radiation hazards associated with use of equipment: Too be j significance of radiation warning and safety devices: Tee be operating procedures Yes Be symptoms of acute localized exposures and fes lie ; procedure for reporting actual or suspected exposure? Yes he Personnel nonttoring Have personal monitoring devices (ring badges) been issued? Yes to if "Yes", are they used in compliance with University requirements? Tee be j RADIAfl0E SIEVET RATA Radiatten survey ester (s) available at facility: Make/Model: Ser. No.: Calibration Dates ] Make/Model Ser. No.: Calibration Dates ! Radletten survey meter (s) used for thle survey, if differents l Make/Modelt $er. No.: Calibration Dates ! Make/Model Ser. No.: Calibration Date: Survey results: With machine operating at usual kVp and mA Maximum exposure rate within 6 cm from tube housing mR/hr is the dose rate less than 2.5 mrem /hrt fes lie Maximum exposure rate within 5 cm from protective cabinet mR/hr Is the dose rate less than 0.25 ares /hrt fee he Maximum exposure rate at operator's position mR/hr Surveyed By: ) l I Upon completion, send this inspection report to: l Radiological Health D partaaet, 100 Orson Spencer Hall l l 4 0 . RPR 30. .- ,YT! CAL K-RAY SAFETT (10/89) - 4
~l l ,
s
'O v SELF-SHIELDED IRRADIATORS PURPOSE only be issued to authorized users, and the room must not be accessible to custod-This procedure presents the requirements ial or maintenance personnel when author-
- for acquisition and use of self-shielded, ized users are not present. The door to
, dry-source-storage irradiators. It also the room must bc locked whenever an describes the required qualifications and authorized user is not present.
authorization of individuals intending to use such irradiators. If control is by means of a lock on the irradiator itself, the locking device n4t arevent any movement of the source or POLICY iousing, as well as access to the irradia- , tion chamber. The keys that control ' The acquisition, installation and use of access to the irradiator (or room) shall large gama-ray irradiators involves long- be kept by the responsible user in a . term comitments of University resources, location or under conditions that will space and administrative controls. In positively preclude key access and irradi-addition to concerns of safety and secur- ator use by unauthorized individuals. A ity, the issues of long-term custody and nonuser of the irradiator may be desig-ultimate disposal costs must be carefully nated as key custodian, but such designa-considered by individuals and departments tions must be done in writing with a copy acquiring an irradiator and by the Radia- to the Radiation Safety Officer (RS0). tion Safety Comittee (the "Comittee"). Records of keys issued shall be maintained g for inspection by the RSO and the licens-Large irradiators are licensed separately ing agency. from other radioactive raaterials. The complete description of the irradiator and its intended location must be submitted PERSOMEL QUALIFICATIONS AE TRAINING with the license application. Th appli-cation must be approved by the Comitten The responsible user for the irradiator before submittal to the licensing agency, must submit an application in accordance No comitment to purchase an irradiator with " RADIATION USE APPLICATION" ( RPR 2).
- should be made until the license applica- The " RESPONSIBLE USER'S TRAINING &
tion has been approved by the Comittee. EXPERIENCE" form (RPR 2A) must Clearly demonstrate competency on the subjects Individual users of an irradiator must listed below. The " RADIATION MACHINE USE meet the specified qualifications and APPLICATION" (RPR :), must also include training requirements. No individual information on the same items. shall use an irradiator without specific approval by the Comittee, 1 Principles and good practices of radi-ation protection. SOURCE SECURITY Z The use of radiation detection instru-ments. Each self-shielded irradiator must be secured against unauthorized use. This 3 The design and operation of the normally requires a lock that can be irradiator, completely controlled by the responsible gg) v user (s) either on the door to the room or on the source itself. If a room lock is 4 Procedures to be followed in the event of an equipment malfunction or other the primary access control, keys shall emergency. RPR 31. SELF-SHIELDED !RRADIATORS (12/89) 1
The res >onsible user must ensure that each Leak tests of all sealed sources, includ-indivicual who will use a self-shielded ing those in self-shielded irradiators, irradiator has received the appropriate are performed by the RSO in accordance training, based on the materials submitted with " LEAK TESTS OF SEALED SOURCES" in the application and approved by the (RPR st). Committee. Each individual user shall complete a " RADIATION USER TRAINING & PERSONAL DATA" fom (RPR 1 A) indicating the OPERATIONAL PROCEDURES date that the required training was re-ceived. The RSO will then administer a A copy of the normal operating procedures, written examination for verification of based on the manufacturer's recommended the adequacy of the training, procedures, is to be available at the l irradiator control panel. Each user of i The qualifications of the individuals who the irradiator is personally responsible l have satisfactorily completed the training for followinc <> reocedures, and examination shall be submitted to the Comittee for review and approval. A 11st Emerge 1c' :@MW must be prepared of currently authorized users of the by the r spw we mer nd posted at the irradiator shall be prepared annually and control ores Wre iky can easily be submitted to the Comittee by the RSO. seen by 2 emm The emergency procedures Wd mtMr current names and - phone numbeh. M & wfied in the event RADIATION SURVEYS Als MONITORING of: A detailed survey of radiation exposure 1 malfunction of the irradiator unit rates in the vicinity of the irradiator (responsible user, RSO, and the manu-and adjacent areas shall be made by the facturer), RSO imediately after the initial instal- - lation of the irradiator and after any 2 any event which could physically dam-suspected malfunction, modification, or age the source, such as fire, explo-repair of the irradiator. Measurements sion, earthquake etc. Ohilversity shall be made both with the irradiator Police, RSO, Fire Department). on, i.e. with a sample being irradiated, and with the irradiator off, i.e. with no The emergency instructions should also sample in the cavity and with power to the inform users in the case of a malfunction control unit turned off. The measurements to attempt no repairs by themselves, and shall be made with a calibrated exposure- in the event of possible physical damage ; rate survey instrument. of the source to evacuate the area and restrict access until cleared by the RSO. ' Radiation dosimeters must be worn by all individuals involved in the installation . repair, modification, transfer or disposal REFERENCE of a self-shielded irradiator. Individ-uals who use a self-shielded irradiator Nuclear Regulatory Comission, Guide for on a routine basis must wear personni the Preparation of App 1tcations for dosimeters if there is a reasonable chance Licenses for the use of Self-Conta/ned Dry of receiving an exposure of more than Source Storage Gamma Irradiators, Reg. ' 100 mrem to a major portion of the body Guide 10.9, Rev.1, Dec. 1988. in any calendar quarter from all radiation sources encountered. (SeetheRadiatton . Safety Policy Manual for more information on the policy and procedures for use of personal dosimeters.) RPR 31. SELF-SHIELDED IRRADIATORS (12/89) - 2
I O SAFETY OF SOLID STATE FUSION EXPERIMENTS NUCLEAR FUSION SAFETY CopplITTEE REPORTINS OF UNUSUAL EVENTS The University administration has es- Any accident or unusual event involving tablished a comittee to review and injury, sudden large release of energy recommend safety precautions for solid (thermal or nuclear) or damage to the state fusion expariments. The charge to facility, should be reported promptly to the comittee includes: the Radiation Safety Officer. I responsibility for maintaining safety of cold fusion experiments, 2 reviewing fusion experiments with REC 0000ElWED SAFETY GUIDELINES respect to safety issues, and 3 reviewing an;* accidents or unusual 1 Since solid state fusion experiments events occurring in fusion experiments. evolve hydrogen, make sure that gases The comittee includes representatives are properly vented and avoid all igni-from Chemistry, Physics, Engineering and tion sources. Exercise caution in mah Mines & Mineral Industries. The comit- ing and breaking electrical contacts. tee operates under the auspices of the Radiation Safety Comittee, and all 2 Wear safety goggles when working in correspondence or questions for the the immediate vicinity of the fusion committee should be routed through the cells. Radiation Safety Officer (RS0). 3 DO NOT CONDUCT EXPERIMENTS USING O SUBMISSION OF EXPERIMENTAL PLANS TRITIUMI ANY PROPOSED USE OF TRITIUM REQUIRES PRIOR APPROVAL OF THE RADIATION SAFETY COMMITTEE. To meets its charge, the committee re-quires that an experimental plan for 4 Initially, experiments should mimic each sianificantiv different experiment those that have been performed for ex-be submitted for its review. The plan tensive periods of time by Pons and should emphasize any deviations from the Fleischmann. This means palladium elec-RECOMMENDED SAFETY GUIDELINES and the trodes of not more than 4 mm in diameter safety precautions that will be taken. and pure deuterium. ; The committee will review the plan and provide comments and advice to the ex- 5 Do not use powdered metals, perimenter, as appropriate. The plan should include the location of the ex- E For more exotic metals, start with periment, and the name(s) and telephone electrodes of 1 mm diameter, numbers of responsible individuals. 7 Do not use electrodes with sharp ACCESS TO EXPERIMENTAL FACILITIES edges. Do not subject D+ in the elec- ' Access to laboratories for the purpose of reviewing safety precautions must be 8 Avoid rapid changes in temperature granted to representatives from Radio- and current; use backup power and bat-logical Health, Safety Services or the tery to avoid power loss, if possible. committee. Requests for access will be Reduce current gradually, i.e. by halv-limited to those considered necessary ing every 24 hours. f or safety evaluations. O RPR 34. s0 LID STATE FUs10N ($/89) - 1 I
RADIAT10Il Moll!TORIIIG REQUIREMENTS Tritium may be monitored by passive, Continuous monitoring for potential integrating methods for T2 0, since the radiation emissions shall be provided at exposure limit for the oxide is more all times that fusion reactions are than 4 orders of magnitude more restric-being ettempted. Detectors for radia- tive than for the gas. The annual limit tion safety monitoring should be posi- on intake (Al.1) for T 0 is 80 mC1, 3x10' tioned within 1 m of the reaction cell Bq (dps), or 1.7x10 h atoms. If ary and connected to a continuous recording reaction appears to be producing tritium device located at least 10 meters from at rates greater than -10 17 s*1, the need the reaction apparatus. Digitized data for continuous monitoring shall be re-compatible with computer analysis would evaluated, be helpful, but is not required. For a detector at 1 meter, an alara at RADIAT12 SAFETY CONIACT
-10 area /hr is appropriate; working for 10 hours at just below the alarm setting All experimental plans and reports of would deliver less than 100 mrem (the unusual events, as well as any comments weekly occupational dose limit). or questions regarding safety of fusion experiments are to Le directed to the For photons of 1-10 MeV, 10 mrem /hr3 Radiation Safety Officer:
corresponds to a fluence rate of ~3x10 cms'1, representing a source term of Dr. Keith J. Schinger or
-3x10s s'1 at a distance of 1 meter. Mr. Robert J. Hoffmhn (alternate RS0)
Photon detectors should respond to ener- Radiological Health Department gies from 0.1 to 20 MeV at fluence rt.tes 100 Orson Spencer Hall, Ext. 6141 from -30 to 3x10 6 cm'8s'1 (0.1-10,000 mrem /hr). All fusion experiments shall be monitored for photons. For neutrons of 1-10 MeV, a fluence rate of -40 cms'1 produces 10 mrem /hr, and represents a source term of -5x106 s *1 at a distance of 1 meter. Detectors for neutrons should be able te respond to energies from 0.1 to 15 MeV at fluence rates from 10 to 106cm-r s*1 (0.25-25,000 mrem /hr). All fusion experiments con-ducted without at least 20 cm of water anderator surrounding the fusion cell shall be monitored for neutrons. If an experimenter produces a fusion reaction with radiation emissions approaching the above alarm levels, the RSO shall be notified innediately. O RPR 34. SOLID STATE FUSION (5/89) - 2
f RADIATION SAFETY COMMITTEE PURPOSE or to supervise such use by others. The Comittee oversees, reviews and audits the This procedure defines the responsibil- activities of the Radiation Safety ities, authority, membership, and operat- Officer, the Radiological Health Depart-
.ing: rules of the University's Radiation ment, the Radioactive Drug Research Com-
, , Safety Comittee. . mittee and all users of University radia-tion sources. The Comittee reports to the Vice President for Research.
POLICY MEIBERSHIP
- The. Radiation Safety Comittee' is the governing body for all aspects of radia- The Comittee chairperson and members are tion' protection within the University, appointed by the President for indefinite including all affiliated research, clini- terms on the basis of professional quali-cal, instructional and service units fications. Appointments are made to-utilizing radiution sources in facilities provide representation from all major owned or controlled by the University, academic, clinical and research areas that The Comittee will ensure that all posses-- use radiation sources. The membership may sion, ce and disposition of radiation also include representatives of groups of sources by University personnel complies workers who may be involved only occasion-with pertinent federal and state regula- ally with radiation sources, e.g. nurses, tions and with the specific conritions of custodians, maintenance personnel, etc.
licenses issued to the University, and The following are members ex-officio: the that all concomitant radiation exposures Vice President for Research or designee, tre maintained ALARA. the Radiation Safety Officer (RS0), the Alternate RSO, the Director of Public Safety or designee, and the Purchasing DEFINITIONS Agent-or designee. ALARA. - one of! the basic p;emises of The membership of the Comittee is re-radiation protection, i.e that all radia- viewed at least annually, and additions tien exposures should be kept as low as or replacements are normally appointed at teasonably achievable, taking into con- the beginning of the Fall Quarter. sideration all social and' economic factors.. MEETINGS, AGElmA ABE QUORUM
, Radiation source - a general term that Jincludes any radioactive material or The Comittee meets at least once during-
. radiation-generating machine that can emit each calendar quarter, or more frequently ionizing radiation. at the call'of the chairperson. A recom-mended standard agenda for Comittee meetings is attached (RPR 40A). A majority RESPONSIBILITIES Alm AUTHORITY of the appointed members plus the RSO or Alternate RS0 constitutes a quorum. A The Comittee is empowered and directed simple majority of voting members present to promulgate policies, rules and proced- (appointed and ex-officio) is required for ures. for the . safe use of. radiation action. Between meetings, action may be sourca. The Comittee is responsible for taken by mailed ballot upon approval by assuling t!.at only qualified individuals a majority of all voting members; such are permitted to use radiation sources, actioJ, shall be reported in the minutes RPR 40. RADIATION SAFE 1Y COMMITTEE (1/90) - !
b ' a~ ' + # (sA7
of the next Comittee meeting. Parlia- The ther Authorization Subcomittee re-mentary procedures shall be determined by views and evaluates all new aplications Robert's Rules of Order, for authorization to use radiation sources and all applications for revisions to previous authorizations that involve RECORDS AND REPORTS significant changes in conditions or radiation exposure potential. Unanimous The Comittee publishes its basic policies approval by the members of the subcomit-and rules in the form of a Radiation tee constitutes official authorization on Safety Policy #anual and it authorizes and behalf of the parent Committee and is directs the RSO to develop and promulgate reported at the next, Comittee meeting. such procedures and records as are neces- It a subcomittee member is not available sary for compliance with all federal and to review an application in 6 timely state radiation control regulations and manner, the Committee chairperson may for effective interpretation and implemen- appoint an alternate member to cerve tation of the policies of the Comittee. temporarily. Applications not receiving unanimous approval by the subcomittee are The minutes of the Committee's meetings, refe nd to the parent Comittee for together with all reports submitted to the action. Comittee, serve as the primary documen-tation of the radiation protection program The Human Uses Subcommittee evaluates and of the University, and are submitted approves or disapproves all proposed uses annually to the University Archivist for of ianizing radiation sources on or in permanent storage in accordance with humans for investigational or non-routine University Po1fcy and Procedures Manual clinical procedures. The review of the 1-3. The list of topics to be reported proposed protocol and of the investi-by or to the Comittee, and filed with the gator's qualifications to use radiation Comittee's records, is indicated in the on human subjects is conducted by this recomended standard agenda (RPA 40A). subComittee after the adequacy of facili-Although not all of the listed topics ties and general conditions for radiation are addressed at every meeting, the topi- protection have been verified by the R50. cal numbering system is retained to assure Because of the professional qualifications consistency in identifying all components and functions represented among the mem-of the annual record. bership of the Radioactive Drua Resear,jl GggniitmL1BDBQ, it also serves as the The Radiological P9alth Department pro- Human Uses Subcomittee. The chairperson vides the secretarial supprt fc all of of the RDRC is a member of the Comittee, the Committee's activitien Audit Subccanittees, each usually consist-ing of one person, are appointed by the SU8CONUTTEEh Comittee chairperson each year to perform audits of topics selected by the Committee The Comittee may estatlish subcommittees to be performed during the year. The to perfonn specific functicos. Each topics to be audited are listed in RPR subcommittee must subm:t a written report 408. The Committee selects the topics to of its activities and actions to the be audited on the basis of their relative Committee for each cater.dar quarter in importance and the time that has elapsed which it was active. Ead subcomittee since the last audit. Audits are to be report accepted by the Committee becomes preplanned and conducted to assess the part of the record filed in the University performance of the RSO, the Radiological Archives. The active subcommittees and Health Department and of users of radia-their functions are: tion sources. Audits are conducted in four general steps: RPR 40. RADIATION SAFETY CO.~ TTEE (1/99) - 2 Y gg*h&l ' ' ' j l; . w -
~"y
~
b
'hs l~fl'E'[$s*j f'
1 f* W; 5 Guide for the Preparation of 1 ' determine the regulatory require- App,ifcations for Medical Programs, b ments,' license' conditions or other Regulatory Guide 10.8, . Appendix B, guidelines or commitments that the Medical isotopes committee, and Appen-University must satisfy, dix 0, Model program for maintaining occupational' radiation exposures at
.2 determine whether the University medical institutions ALARA.
has a formal procedure for complying with ,aach identified requirement, 6-Tng,Occupatfonal Principles and Practices Radiation for Keep-Exposures 3 determine whether compliance with at Medical- Institutions As low As each requirement can be demonstrated Reasonably Achievable, NUREG-0267. by objective documentation, and 7 Utah Bureau of Radiation Control, 4 submit a. written report of the Special Requirements for Specific audit findings and recommendations not Licenses of Broad Scope, URC-22-50. later than the Spring Quarter meeting. The audits are performed whenever con-venient for the auditor; the necessary background materials .and documents will be - provided ..by the Radiological Health Department. The Fusion Safety Subccasittee establishus
- safety procedures for cold fusion vesearch and . reviews incidents or' significant research results that are of significance to safety or radiation protection.
REFERENCES 1 Food and Drug Administration, Radio-active Drugs for Certain Research Uses, 21 CFR 361.1, (functions and membership of the Radioactivo Drug Research Committee). E National Council on Radiation Protec-tion and Measurements, Operationa7 Radiation Safety Program, Report No.
-59, 1977.
3 Nuclear Regulatory Ccxiission, Specif-ic Domestic Licenses of Broad Scope for Byproduct Material, 30 CFR 33.13(- c) and 33.17(b). 4 , Guide for the Preparation of Ap-
.Ticaticns p for Type A Licenses of Broad Scope, Regulatory Guide 10.5.
O RPR 40. RADI AT!LK Sff-ITY COMMITTEE (1/90) - 3
--w
RPR 40'A. RADIATION SAFETY COMMITTEE STANDARD AGENDA $ I. Ooenina Business A. Attendance and agenda B.' '. Approval of minutes C. Appointments'and announcements _II. Subcommittee Reports A. User Authorizations B. Huoan Uses (RDRC) C. Audits D.- Cold. Fusion III. Recommendations a Responses A. Cumulative List _of Open Recommendations B.. Responses to Recommendations IV. ' Radiation Safety Officer's Reoort p A. Licensing, registration or regulatory actions B. Radiation policy, procedures and records C. Radiation safety training and user qualifications D. Occupational radiation exposures E.: Misadministrations F. Radiation surveys and monitoring G. Radioactive material- control and. inventory H. Radioactive waste management. I.- Radioactive effluents and environmental releases J. Other V. Index & Other usiness 9 i RPR 40. RADIATION sAFFTY COMMITTEE %/90) - 4
....s , ,
- RPR-408... RADIATION SAFETY COMMITTEE AUDIT TOPICS Eub.iect of Audit References
- 1. Program Management, including: FDA, 21 CFR 361 NRC, 10 CFR 33.13 a a. Radiation . Safety. Committee and NRC, Reg. Guide 10.5 s
Radioactive Drug Research Committee.- NRC, Reg. Guide ~10.8, App. O i.ca membership and operations; NCRP, Report No. 59 (2.2) A UBRC, R447-15-10
~b. Radiation Safety Officer, functions UBRC, R447-22-50 and performance;- UU, Radiation' Safety Manual UU, RPR 40 - 42
?
- c. ALARA policy and implementation.
d.- Record management; retrievability, NRC, 10 CFR 20.401, 30.51 security, and retention VBRC, R447-12-51, 15-401
\"; Policy and Procedures, 1-3 l UU, kPR 100-1
- 2. User Authorizations
- a. Non-medical use of radioisotopes NRC, Reg. Guide 10.9-and radiation-generating machines; UBRC, R447-22-50 9 UBRC,.R447-40-60 UBRC, R447-44-30 UU, RPR 2, 30 - 32:
- b. Medical (human) use of radiation: NRC,_10 CFR 35 sources for diagasis, treatment or NRC, Reg. Guide 10.8- ,
research. UBRC, R447-22-50 UBRC, R447-32-900 - 972 ; UBRC, R447-40-60 ' UBRC, R447-44-30 UU, RPR 2, 30 32
- 3. Organizational Interfaces
-1 a . , Radiology Programs UBRC, R147-22-070 UBRC, R447-28-31, -350 UBRC, R447-32 (all)
UBRC, R447-44-40 NRC, Reg. Guide 10.8
- b. ' Nuclear Engineering Laboratory ANSI, ANS 15.16-1982
. Research Reactor, emergency plan- NRC, 10 CFR 50.7
.ning, personnel protection. NRC, 10 CFR 20.201
, NRC, 10 CFR 50, App. E y NRC, Reg. Guide 2.6 O
RPR 40. RADIATION $AFETY COMMITTEE (1/90) - 5
~ .
4 1
- 4. Training; g
- a. Normally exposed radiation users, ANSI, N43.2-1977-including radioisotope and machine NCRP, Report No. 71-users NRC, 10 CFR 19.12 NRC, Reg.. Guides 8.13
- b. Emergency personnel, e.g. police, NRC, Reg. Guide 8.27 firefighters, security, etc. NRC, Reg. Guide 8.29 NRC.-NUREG 0267, 3.4.1.6
.. c. . Minimally exposed'(ancillary) per- UBRC, R447-18-12 sonnel, e.g. nursesi . maintenance, . UBRC, R447-28-350 custodians, etc. UU, RPR 43
- 5. Radioactive Material Control
- a. Procurement; ' package. receiving; NRC, 10 CFR 20.205 inventory records (broad license and VBRC, R447-15-204, -207 radiopharmacy);- user's disposal UU, RPR 13-records;
- b. Waste handling, packaging and ship- NRC, ~10 CFR 20.301 .315 '
ping; effluent and environmental VBRC,'R447-15-106 releases. -UBRC, R447-15-101-- 401 6.- Individual Dosimetry- Requirements and Records
- a. = External (badges)' and internal NCRP Report 59- ,
(bioassays) NRC, 10 CFR 20.101 - 108
-NRC, 10 CFR 20.202, 401 NRC,-Reg. Guide 8.9 NRC,.NUREG 0938 UBRC, R447-15-101 - 108 UBRC, R447-15-202,.401 UU,. Radiation Safety Manual' UU, RPR 12' i
O RPR 40. RA01AT10N SAFETY COMMITTEE (1/90) - 6 i1
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7.= Radiation Exposure Control, Surveillance. q-Ej , d, J . and Monitoring -1
'a. Radioisotope Lab Surveys NCRP, Report No. 59 p NRC,-10 CFR.20.201, .401-NRC, Reg.; Guide 8.21 l J UBRC, R447-15201, -401 e UU, RPR 11, 50
- b.- Radiation Machine Surveys ANSI N43.2-1977-FDA 21 CFR'1020 1 UBRC, R447 all :
, UBRC, R447-40 all . !
UU, RPR 30- l e c. Sealed Source Leak Tect UBRC, R447-15-107- ; UBRC, R447-32-59' r- [. , UU, RPR 51' zi k 'd. ' Radiation Oncology; Brachytherapy .NCRP Reports 37 and 40 L NUREG 0267 t lJ URC-32-020 " RPR 304-
' e. Nuclear Medicine NRC Reg. Guide 10.8 l: p NCRP Reports 37 and 48 L3 NUREG 0267-f.L Radiation Therapy URC-32-030 NUREG 0267
- g. Diagnosite: Radiology I
- h. . Radiopharmacy License # 18000145
- 8. . Support Functions L La. Instrument Calibrations, including: ANSI,.N13.5-1972 :
. survey meters, 'nstalled monitors, ANSI, N323-1978 # analytical instruments and direct- NCRP, Report No. 58 L reading dosin ters n.
ll il! 4 RPR 40. RADIATION SAFETY COMMITTEE (1/90) - 7 g a :q > (( ji dg:. - > c ii [ 'f 'f . I
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RADIA' TION SAFETY OFFICER PURPOSE Depending on the context, "RS0" inay also refer to any individual This procedure defines the qualifi- designated to perform specific
. cations, authority and responsibil- tasks on behalf of the RSO.
ities of. the- Radiation Safety
.0fficer (RS0) for implementing the Alternate or Associate RSO is an University's radiation protection individual designated by the RSO program, i
who, in the absence of L the R50, shall assume the authority and responsibilities the RSO. POLICY The University'is committed to an- QUALIFICATIONS effective radiation- protection program based upon recommendations The minimum qualifications for-of authoritative organizations such appointment as the RSO are: as the International Commission on
. Radiological Protection (ICRP), the 1 An advanced degree.in-a scien-National Council on Radiation Pro- tific field directly related to tection and Measurements (NCRP) and radiation protection, including the American National S t and a rd:. graduate-level training in:-
Institute-(ANSI), and in compliance with the rules and regulations of a physics of radiation sources, O the=U.-S. Nuclear Regulatory Com-mission (NRC) and the Utah Bureau b radiation and radioactivity of Radiation Control (UBRC). The measurements methods, instru-appointment of a qualified individ- ments and calibrations,
- ual to the position of Radiation Safety Officer carries with that- c mathematics and calculations appointment the automatic delega- related to radiation
. tion of authority and responsibil- protection, ities described in this procedure.
d biological effects of radia-tion, and DEFINITIONS e radiologica' protection Radiation Safety Officer (RS0)-is practices.
'he individual appointed by the l~iversity, and named on the radio- 2 Experience in a position with e.tive materials licenses, to responsibility for radiation establish and enforce such proced- protection:
.res as are necessary to assure compliance with applicable regula- a sufficient to be eligible tions and license conditions, and for certification by the to ensure effective implementation American Board of Health of the policies and rules estab- Physics, and
'11shed- by the Radiation Safety
' Committee. b with at least 2 years in a major institutional program.
DDR 41. RA0:ATION SAFETY OFFICER (1/90) - 1
k' t' 3 Experience in personnel admini-stration and_ financial manage-3 establishinvestigationlevels'h for radiation exposures to per-ment of a program comparable in sonnel that, when exceeded, will-scope to the Radiological Health initiate a prompt investigation Department, of the cause of the exposure and
~
consideration of actions that
- 4 Any other qualifications deemed might be taken to reduce the appropriate - by the University probability of recurrence; -
Administration. 4 investigate overexposuris, acci- ' An individual designated as the dents, spills, losses, thefts, i alternate or associate RSO shall unauthorized receipts,. uses, ., L have most of the qualifications transfers, disposals, misadmin-- 1 h for.-the position of RSO, with the istrations, and other deviations ~ likelihood of becoming fully qual- from approved radiation safety- . L ified within one year, practices, and implement correc-tive actions as necessary;- 1 AUTHORITY 5 provide training for radiation users on the proper procedures
. The RSO is authorized and directed for the use of radioactive ;
to promulgate and enforce such material and other radiation
. procedures as are necessary to sources; assure compliance with applicable federal and state regulations.and 6 assure proper calibration and to ensure-the accurate interpre- operation of radiation measuring - .
'tation and: effective implementa- and surveying instruments used-tion . of the policies and rules to determine- compliance with'- -
established by the Radiation Safety regulations:or procedures: Committee. The RSO is authorized and directeo to terminate-immedi- 7 perform periodic' radiologichl -i ately-'any: project or operation that evaluations and surveys of all presents a radiological threat to radiation-g'nerating e machines j health or property, and all areas where' radioactive materials are stored or used;
.1 RESPONSIBILITIdS 8 establish written policies and procedures for purchasing, rece-The RSO shall: iving, opening, storing, using, 4
and disposing of radioactive 1- maintain cognizance and general materials; surveillance over all activi-
- ties involving- radioactive 9 maintain an inventory of all o
material and other sources of radioactive materials and limit-ionizing' radiation; the quantities in possession to the amounts authorized by the L 2 establish criteria for using license (s); personal monitoring devices and for performing bioassays, and 10 receive and survey all incoming maintain personnel exposure and shipments, and packaging and bioassay records; shipping all outgoing shipments of radioactive material; 1 RPR 41. RADIATION SAFETY OFFICER (1/90) - 2 1 \ L
,p F -( -11 supervise Land coordinate the Utah Bureau of Radiation Control, radioactive waste disposal Utah Radiation Controi' Rules:
program, including keeping waste 1. storage and- disposal- records Specific Licenses, R447-22. and monitoring effluents; Medical- Use of Radioactive 12 perform leak tests on all sealed #aterial, R447-32. sources; 13 maintain copies of all licenses, regulations, policies, proced-ures and other records pertain-ing to the radiation protection program; 14 assist,-advise and serve on the Radiation Safety Committee, the Radioactive Drug Research Com-mittee and the Reactor Safety Committee. REFERENCES National Council- on Radiation
' Protection and -Measurements, l , Operatfonal ,Radiatton Safety Program, Report No. 59, 1978.
L US Nuclear. Regulatory Commission: App 1tcations for Type A Licenses of Broad Scope, Reg. Guide 10.5,- 1981. Guide for the Preparation of I Applications for Medical Use ; Programs, Reg. Guide 10.8, Rev. ~
'2, 1987.
Specific Domestic Licenses for Brcod Scope of Byproduct
#aterial, 10 CFR 33.
Medical Use of Byproduct i
#aterial, 10:CFR 35.
RPR 41. RADIATION SAFETY OFFICER (1/90) - 3
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' A. .
,g h 4 g. I 's THIS PAGE' INTENTIONALLY LEFi BLANK ; m O RPR 41. RADIATION SAFETY OFFICER (1/90) - 4
L y RADIATION PROCEDURES AND RECORDS PURPOSE tion protection orogram, e.g. financial or personnel acministration, are not This procedure establishes design criteria considered to be radiation procedures and and standard formats for detailed proced- are not covered in this procedure.) ures and records required for effective operations, comunications and management Radiation record - any written or printed of the University's radiation protection informat8cn related to radiation sources, program. Specific attention is given to radioacti >e materials, radiation expos-generation, authr.atication, . linkage, ures, etc. acquired and retained by the
. storage and recovery of records related RSC, RSO or RHD.
'to the radiation protection program.
RPR - acronym referring to all radiation procedures and records . POLICY File - a groap of similar records covering Procedures and records developed, used a specific category of information, and maintained for the radiation protec-tion program shall conform to standard Key - the datum identifying one particular procedures and policies established by the record in a file. The key itself might University of Utah. Procedures shall be not be unique; in this case, each record sufficiently detailed and comprehensive must contain supplementary information, to assure consistent and unambiguous which combined with the key, positively communication of instructions. Records identifies a single record. For example, O. shall be complete, consistent and in the social security number is usually the conformance with standard procedures to unique key to a record in a personnel assure that all data can be recovered, file; for convenience, however, records verified, interpreted and legally accept- may be filed alphabetically by surname, ed. Records shall be retained in a loca- but must contain the social security tion protected against damage from natural number or other information to assure or manmade causes for the length of time positive identification. required by law, regulation or University Link - a data field that is repeated in policy. more than one file in order to cross reference, or point to, another record or DEFINITIONS file where additional relevant information is located. Links form the basis for RSC - Radiation Safety Committee. relational databases, avoiding unnecessary redundancy. RSO - Radiation Safety Officer. Fom - a prepared outline, often preprint-RIE) - Radiological Health Department. ed, used to acquire or retain data for a radiation record. Radiation procedure - a detailed procedure - issued by the RSO as an iristruction or Database - a comprehensive, relational guideline for users of radiation sc.r ces compilation of data stored on the depart-to supplement the Radiation Safety Policy mental computer network. The database is Manual, or to define RHD procedures af- a management tool; it is not considered
- fecting the University's radiation protec- to be a repository of primary records.
tion program and its documentation. (RHD procedures that do not affect the radia-I RPR 42. PROCEDURES AND RECORDS (1/90) - 1
/
V ,
- Ministerial changes - changes in format Policy - consisting of a statement of &
or wording of procedures or records that University, RSC or RHD policy that neces- W
- do not conflict witi any regulatory re- sitates the procedure, quirement or license condition, and that
- do not diminish or adversely affect radia- Definitions - limited - to unisue terms tion protection, required to understand the proceiura.
Instructions.- detailed procedures under AUTHORIZATION Als ADDPTION OF RPRs as many sub-headir:gs as are appropriate. The RSO may make ministerial changes to References - a listing of regulations, any RPR that do not affect policy state- regulatory guidance documents and publica-ments. Changes to policy statements must tions of advisory organizations that are be submitted to the RSC for approval; any directly related -to the procedure; any , proposed change that affects license deviations or exceptions from the guidance conditions or commitments previously made contained in the references should be to the licensing agency must be submitted explicitly explained in the procedure. , to the licensing agency as a request for i license amendment. If revisions to RPRs Forms or other record formats - a sample affect only the functions and efforts of or facsimile of each form or record used RHD personnel, the changes may be imple- for management of any data generated by l mented immediately, but shall be submitted operations covered by the procedure should ! to the RSC for information and documenta- be appended to the procedure, tion. If the revisions potentially affect - the requirements placed on- radiations users, the changes should be reviewed and DESIGN CRITERIA FOR RECORDS approved by the RSC before they are imple-
. mented, unless the change is mandated by The radiation protection records system- '
the licensing. agency, shall be designed and maintained accordf rg to the following essential' criteria:: The RSO maintains a master chronological. ) file' of all revisions to RPRs and the 1 All records shall be on paper ("hard" u minutes of the RSC include the revisions copies)'. Data may be entered initial- I reviewed at any meeting, ly into the database, but file copies shall be printed out for permanent retention. Note that a variety of FORMAT FOR PROCEDURES listings, reports and- summaries may be generated and used in routine oper-Radiation procedures should contain the ations, but they are not classified following elements, if appropriate: as " records" unless they have a speci-fled retention requirement. Permanent Title - short and concise, but informa- records are those that have no defined tive.- limit to the required retention time; individual exposure records are con-Header or footer - appearing on every page sidered to be permanent. -Temporary
- and containing the procedure number, and records have prescribed retention abbreviated title, and the date issued or times, typically varying from 3 .to revised. 10 years.
Purpose - a short statement of the objec- 2 Filing systems for all records shall tive and applicability of the procedure, be desig1ed with future recoverability as a prvnary consideration; this is of paramount importance for permanent , RPR 42. PROCEDURES AND RECORDS (1/90) - 2
- . -- - - _ ~ _ _ . -.
s e i , 1 1 records,. for which recovery must' not 2 Forms should carry an appropriate l be dependent upon the memory of any header or footer identifying the form ) particular individuals. The identifi- number, title, and the date of issue cation of each file, . and- the key to or revision. Multiple-page forms l each record, shall- be the data most should have spaces for page numbers, I
. likely< to' be available and used to initials and dates on each page, initiate.the search for the informa-tion. For example, general informa-3 Forms should contain specific spaces-tion on. radiation protection policies for entering data; each space should !
and practices are most likely. to be be unambiguously labeled as to the : n desired for a specific time period, type and units of the datum.to be ! so general programmatic documentation entered. Generally accepted termino 1-. ' L is : filed chronologically by years, ogy, abbreviations. and units should i On the other hand, records of individ- be used; unorthodox notations.are not
? ual assignments or authorizations, to be used. Every form should provide y~ radiation safety training, radiation space for signature (s) or initials and 4 i
monitoring, exposures, incidents, etc. date(s) prepared for every individual 7 are most likely to'be sought in con- completing any. portion of the form. > 1 nection with a particular individual The required distribution and filing and shall, therefore, be filed alpha- of the record should be stated on each betically by surname, form. i 3' Procedures and forms used to produce 4 Forms should be provided with margins , records shall assure completeness and of at least 3/4 inch on all sides to l specificity of > the -information, and mininize loss of information due to ' p shall- include the date and positive copy misalignment, punching holes, I. V identification of the person who cre-ated or revised or revised it. Pro-mounting in notebooks or file folders, as well as to enhance appearance. L - cedures shall also assure the confi-dentiality of personal and proprietary l information. UNFORMATTED RECORDS For data that are to be collected--and
. DESIGN CRITERIA FOR FORMS recorded by means other than preprinted forms, specific check lists should .be Many records consist of preprinted forms prepared and incorporated into written containing information entered by RHD procedures to assure that the records are pet sonnel or by radiation users. Forms consistent and complete. Unformatted should be designed according to the cri- written records shall include precise ,
i teria listed below and must be approved identification of the nature of the record ' R: .by the Director or RSO before use. and the originator's signature and date prepared. 1 A form should be given a brief title that clearly identifies its purpose and that can be remembered easily by individuals who use it rarely and may not remember a number. A form number is usually assigned also, primarily ll for abbreviated referencing by those L who use it frequently. Form numbers are generally extensions of the number O of the procedure that contains the u U instructions for its use. 3~ RPR 42. PROCEDURES AND RECORD 5 (1/90) - 3 l '1 .. .
?
RECORD FILES Als STORAGE .used, are filed alphabetically by name of . responsible user. However, this file is ! The- major files of radiation . records separate from the main authorization file, maintained by the RSO and the RHD are: since the required retention times are different. - Radiation Safety Committee Minutes l. Radiation Devices The RSC minutes contain a record of all official actions of the Comittee, e.g Records of special equipment or fac Dities j adoption of policy statements and authori- used for producing, using or controlling zations of specific radiation users, radiation are placed in a " devices" file. , Major activities of the RSO and the entire Examples of the records in this file are i radiation protection program are reported accelerators, x-ray machines, self-con-regularly to the RSC even when specific tained irradiators, calibration sources, ; action by the committee is not required, etc. As a result,: the minutes of RSC meetings serve as the primary mechanism for docu- Radioactive Mat' dali mentation of the overall radiation f program. Licenses authorning the possession of radioactive materials are filed by license Radiation Users numbers in a license file. Licensing information on other institutions to which Records of all individuals identified as radioactive materials may be sent is-radiation users' are- maintained maintained in a file alphabetized by indefinitely. These records are filed institution names, alphabetically by names, but social secur-ity numbers are used as the key to the The current inventory of radioactive personnel database file. The records for materials possessed by the University is 4 individual radiation us:rs contain data maintained in the computer database in a l on radiation safety training and form that allows selective outputs of L experience, as well as on personal radia- inventory by users, by buildings, by form L tion monitoring and exposures. of the material, by individual nuclides, etc. Records of receipts, transfers _and Responsible (Authorized) Users dispositions of radioactive materials, in-cluding surveys of incoming packages and Records of authorizations of responsible transfers to waste containers, are
. users and general information pertaining retained in a ' chronological file. A to the personnel or activities of the summary of the University's total posses-entire group for whom the authorized user sion by. form and nuclide that permits .
is responsible, are filed alphabetically comparison with license limits is printed by the responsible users naus. In the out periodically to be retained with the , computer database, a " responsible user RSC minutes. < l' ' number" is assigned sequentially and serves as the key to the file. Records of shipments of radioactive wastes to waste brokers or to disposal sites are Both individual personal data records and kept in a separate waste shipments file. responsible user records are combined in i L the permanent files of inactive users. Environmental Releases and Monitorino Area Surygyi Records of environmental releases and , monitoring are maintained in chronological Surveys of radioisotope laboratories, and files. A summary is included with the other areas where radiation sources are minutes of the RSC annually, with suffi-p RPR 42. PROCEDURES AND RECORDS (1/90) - 4 u
cient information for cross referencing procedures by specific request. As part to the primary data files, of taeir routine audits of radiation users' facilities, Radiation Analysts will ascertain that the users have the most IEEXIE recent versions of the appropriate RPRs. Each file containing radiation records
-shall be provided with an index and a DATABASE ENTRIES AM REVISIONS means of keeping it current. Indexing takes several different forms; the file Many items in the computerized database of inactive radiation users occupies are inter-related, and changes to one several- file cabinets, and the index record may have unexpected' results in consists only of alphabetical labeling on another record. Database records are to the file drawers. The records of active be entered or edited only by individuals-radiation users are also filed alphabeti- who have been specifically trained and cally, but occupy only one file cabinet, authorized by the Director to manipulate However, active users are also entered in the specific file or records, the database, which provides additional means of indexing, e.g. by social security Changes to data on responsible user or number, by dosimetry devices, by depart- individual radiat'.,n users shall be veri-ment or location, etc. fled on the pri .ed summary sheet as soon as possible r..ter a new or revised entry In some cases, all of the records on a is made. The summary sheet is then to be subject may be contained in one, or just filed in the individual's file folder.
a few, file folders. File folders should Backup files shall be maintained to be provided with ari index to their con- insure against loss. tents to expedite recovery of specific information. RECORD RETENTION ~ A current index to all RPRs is prepared and distributed whenever procedures are Records are listed below in categories added or revised. The index to RPRs according to their required retention
. includes the- RPR number, title and date time. The Director of the RHD is re-of latest revision, sponsible for assuring that records are retained and sent to University archives, as appropriate. .
DISTRIBUTION OF RPRs Records to be retained Indefinitely All RPRs are distributed to members of the RSC and to all RHD personnel . - 1 All licenses and registrations, in - cluding applications, supporting in-Personal data forms are provided to radia- formation, responses to agency quer-tion users when they first attend a radia- ies, amendments, etc.
-tion safety training course or first begin work with radiation sources, whichever 2 All program documentation, including occurs first. Responsible user applica- minutes of RSC meetings and all RPRs.
tion forms are provided upon request. 3 All records of individual radiation Most radiation users need only a few RPRs users' training and exposure monitor-pertaining specifically to their author- ing data, including the determination ized uses. RPRs are distributed only to of need for personal dosimeters or routine bioassays, dosimeter assign-O the t esponsible users to whom they apply. Anyone else may obtain a copy of these ments, dosimetry and bioassay results, RPR 42. PROCEDURES AND RECORDS (1/90) - 5
n investigations of . unusual' exposure University of Utah: incidents,;etc. Policy and Procedures Manual' 4 All measurements = and evaluations ob-tained for the purpose of determining Radiation Safety Po7 fey Manual individual exposures, e.g. area sur-veys,-air samples, etc. US Nuclear Regulatory Commission:
- 5. A11 measurements ard evaluations of . Standards for Protection Against Radi-effluents and environmental radio- ation, 10 CFR 20, Para. 20.401.-
activity, including sunnaries of quan-tities-released to the atmosphere or Rules of General Appitcabf 71ty . to
-to the sanitary sewer, measurements Domestic Licensing, 10 CFR 30, Para.
of concentrations- in effluents or 30.51. environmental media, etc. Utah Bureau of Radiation Control, ~ Utah Records to be retained at least 10 years Radiation Control Rules: 6 Records of. misadministrations, con- Standards for Protectfon Against Radf-taining names of all individuals in- ation, R447-15. volved in the event (physician, allied health personnel, patient, referring Notices, Instructions and Reports to physician), patient's social security Workers by Licensees or Registrants - or, identification number, brief de- Inspections, R447-18. scription of the event,'effect on the patient, and action taken to prevent Medical Use of Radioactive Material,
' recurrence (UBRC R447-32-33).' R447-32.
Records-to be retained at least-3 years or until insoected by the licensina acency 7 Records of receipts of radioactive materials shall be retained for at
'_least 3 years after the date of dis-posal or transfer (10 CFR 30.51).
8 Records of sureveys of incoming pack-
-ages of radioactive materials, surveys of. laboratories for contamination, i, cords of leak test of sealed sources and records of instrument calibra-tions, unless directly used to deter-mine exposures to personne), in which case they shall be retained indefin-
=itely.
REFERENCES National Council on Radiation Protection and: Measurements, -Maintaining Radiatfon f Protection Records, in preparation. RPR 42. PROCEDURES AND RECORDS (1/90) - 6 g
e ,. ... ._ - - -. - - - - - - - - 11 () C AUTHORIZATIONS FOR RADIATION USE PURPOSE EVALUATION OF APPLICATIONS This procedure provides a standardized Evaluations by the RS0 and the RSC are format for documenting the evaluation and intended to: authorization of new or amended radiation uses by the Radiation Safety Committee, I assure that the applicant is competent and for notifying users of their authori- to use the requested materials safely; zations. 2 assure that the applicant's facilities i POLICY and equipment are adequate for the ' proposed work; Each application for use of any source of ionizing radiation is first reviewed by 3 verify that the work is done with the the RSO to assure that it is complete. smallest practical quantities of radioisotopes If the application is for possession of , , no more than 10 reference quantities (RQ) l l of radioisotopes, and acquisition of no 4 assure minimal production and optimum I more than an. average of 1 RQ per month, segregation of radioactive wastes;
- it may be approved by the RSO without ;
review by the Radiation Safety Comittee 5 determine appropriate monitoring l (RSC). All other applications'shall be methods for external or internal rad-p: submitted to the User Authorization Sub- iation exposures. committee of the RSC for evaluation and
! approval. If the subcomittec does not Initial applications are first reviewed d_(O vote- unanimously for approval, the ap- by the RSO, who verifies that they are i
plication shall be referred to the parent complete and recommends any conditions I committee (RSC) for resolution. The RS0 for approval as well as the monitoring i shall notify the applicant promptly of the requirements. When the application is : action taken by the RSC. satisfactory, it is submitted to the ! subcomittee for review and approval. If l An amendment to an existing authorization unanimeusly approved by the subcomittee, ; may be approved by the RSO if it does the applicant is notified and may begin i not involve a different radionuclide radiation work imediately. If questions category, as identified in RADIONUCLIDE are raised by the subcommittee, the RSO l DATA (RPR 10), nor an increased quantity attempt to obtain the' necessary informa-that requires additional protective tion to answer the questions. If unani-
! devices.or monitoring. Other amendments mous approval by the subcommittee is not .1 shall be referred to the RSC. obtained, the RSO shall refer the applica-tion to the parent comittee (RSC).
Reference Quantity (RQ): A quantity of REFERENCE any radioisotope related to its relative hazard potential and used to prescribe Utah Bureau of Radiation Control, Utah requirements for handling, monitoring, Radiation Control Rules, Standards for labeling and disposal. Values of the RQ Protection Against Radiation, R447-15. for many cornanly-used nuclides are tabu-lated in "RADIONUCLIDE DATA" (RPR 10).
-/7 y
RPR 43. AUTHORIZATION (1/90) - 1
jf
~
RPR-43A. AUTHORIZATION FOR RADI0 ISOTOPE USE
, User No.- Responsible User: Phone:
Department: Mailirg Address: Complete Application received (date): Dispersible Radioisotopes to be authorized (* indicates revisions): Anticipated Monthly ~ Receipts Maximum Order of Disnersible Radioisotones-Nuclide Physical Form mci ,f,tgouency mC1 No. of ALIs-1 Laboratory Evaluation completed: Dosimeters required for penetrating external radiation:
' U Body film badge [tf 2((mCl/ month)*(mrom/hr mCl 01m)) 33)
U Finger TLD ring [if high-energy beta + gamma emitters > 5 mCl/mo)) Routine bioassays required for >l ALI received per month: U Quarterly thyroid count for iodine U Quarterly urinalysis for g U Monthly urinalyt,is for Other conditions or comments: Authorization recommended Approved by the R$0 as within the intent of RSC authorization RS0: Date: RADIATION SAFETY COMITTEE, USER AUTHORIZATION SUBCOMITTEE, ACTION: (Signatures indicate approval; if not approved, attach statement with reasons to be forwarded by the RSO to the applicant.) _ Subcommittee Members Sianature Date 27 M 9 RPR 43. AUTHORIZATION (1/90) - 2
uhHEiveasiry O
- UTAH Current Date NAME OF RESPONSIBLE USER CAMPUS ADDRESS AUTHORIZATION TO USE RADIGISOTOPES Dear Dr. Surname You are authorized by the Radiation Safety Com"iittee to acquire and use the. radioactive materials listed below and to supervise such use by others. All radiation use is subject to the conditions stated; in your application and the rules and procedures specified by_ the-Committee. ~ You must notify this office promptly of any changes in-your radiation -use or among personnel for whom you are responsible.
As of this date, you are euthorized to obtain a maximum of: Nuclide mci /ordet Frecuency O
-This authorization is valid indefinitely, subject to periodic review and verification of your needs and actual use.
Pletse do not hesitate to contact this office-for assistance on any. qt.estion or_ problem related to radiation protection. Sincerely, Ksfth~J. Schiagar, Ph.D. Director and Radiation Safety Officer xc: RU authorization file
'RSC agenda file Radiation Analyst O
Radiologkalllealth Department Sal ke City Ltah 112 g ison sei. m i
1 RADIATION SAFETY TRAINING u PURPOSE radiation protection applicable to all categories of radiation users. For each This procedure prescribes the training in category of users, the RSO thall establish radiation ~ protection required for all an appropriate schedule or frequency and j indi riduals who may be exposed to ionizing the minimal requirements for content of radiation in the course of their official the program. The RSO shall maintain i
. ' duties. The content and frequency of appropriate records of training offered I training sessions are specified for each and completed to assure compliance with '
category of radiation user. regulatory requirements. l i d POLICY- TRAINING CONTENT J l Regulations governing the possession and All minimally exposed personnel must be use of radioactive materials and other instructed on specific conditions: that. radiation sources require that every could involve exposure, and proper proced-individual working with or in the presence ures-for avoiding unnecessary exposure. -l of such sources be instructed in the Such instruction must_ include: appilcable provisions of regulations and The nature and risks of exposure to license conditions, 'in the potential ionizing radiation. health problems associated with exposure Recognition and meaning of radiation to : radiation, in the precautions and warning signs. procedures required for safe use of radia- Precautions for avoiding unnecessary s' tion, and in the proper use of protective radiation exposure. and measurement devices. The extent of Who to call for information or assis-the training is to be commensurate with tance on radiat'.on exposure situa - the potential risk of radiation exposure tions. to.the. individual. Ra?pe:,4icilities and rights of indivi- l dual employees. I The primary responsibility for providing I adequate training for individuals who work All normally exposed radiation users must routinely with radiation sources rests receive instruction on the following with their responsible users. For topics: individuals who are only occasionally , exposed to radiation, e.g. most nurses, Characteristics of radiation sources. , housekeeping, maintenance, security and Interaction of radiation with matter.' delivery personnel, the responsibility for Radiation detection and measurement, training lies with their supervisors. ' Biological effects and risk estimates. Generally, the responsible user or super- Risks to the unborn and control of visor will fulfill this responsibility by prenatal exposure. assuring that each person attends the ALARA principle; optimizing radiation appropriate training program offered by protection. the Radiation Safety Officer (RS0). The Proper use of protective devices. ' supervisor or responsible user may also Provisions of regulations and provide-the training and submit a state. licenses. ment to the RSO listing the individuals Response to radiation emergencies. trained and the content of the training. Responsibilities and rights of indivi-dual radiation users. J The RSO is responsible for developing, Availability of monitoring and inspec-O conducting and documenting training- on tion reports. RPR 44. TRAINING (5/119) - 1
Radioisotope users must also receive in-struction on: REFERENCES & W Safe handling and storage of radio- National Council on Radiation Protection active materials. and Measurements, Operational Radiation Procedures for monitoring both Safety - Training, NCRP Report No. 71, internal and external exposures. 1983. Users of x-ray machines with accessible U.S. Nuclear Regulatory Commission: beams, including users of special radio- Notices, Instructions, and Reports tc graphic or fluoroscopic procedures, must Workers; Inspections, 10 CFR 19. also receive instruction on: Effects of machine attributes and Instruction Concerning Risks from 0ccupa-usage on patient dose, tional Radiation Exposure, Regulatory Source and intensity of scattered Guide 8.29, July 1981. radiation. Proper use of gonadal shielding. Instruct ion Concerning Prenat a1 Radiat ion Placement e/ dosimeters for monitoring Exposure, Regulatory Guide 8.13, Rev.1, partial-body exposures. Nov. 1975. Proper use cf special shielding devices. Otah Department of Health, Notices, Instructfons and Reports to Workers by Users of analytical x-ray machines with t f censee or Registrant - Inspections, Utah completely emclosed beams, mut receive Radiation Control Regulations URC-48. instruction on proper use of shutters, interlocks and other safety devices, and ATTACHENTS on the requirement for a safety survey following any modification or repair. I "RADI0 ISOTOPE USERS TRAINING OUTLINE" is for all radioisotope users; separate handout materials are identified in the TRAINING FREQUEMCY AE RECORDS outline. Normally exposed radiation users are 2 " BASICS OF RADIATION SAFETY" is a required to receive training only once, handout for groups of minimally-exposed prior to beginning work with radiation personnel that don't need the entire sources. Training received at another Radiation Safety Policy Manual. institution is acceptable to the extent that it directly fulfills current require- 3 " RADIATION SAFETf TRAINING ATTENDANCE ments. The RSO will establish criteria RECORD" is for recording group training, or procedures for verifying and accepting training received elsewhere. The documen- 4 " RADIATION PROTECTION IN CARDIOLOGY" tation of training is retained in the is a handout used tugether with item 2 for permanent dosimetry record for the in- cardiology fellows. dividual. 5
- RADIATION SAFETY FOR INRSES AND Minimally exposed personnel are offered THERAPISTS" is a handout used together radiation safety training annually . with item 2 for nurses and occupational Supervisors of such personnel are respons- therapLts.
ible for encouraging attendance. Training records for these personnel are retained 6 " RADIATION SAFET'I FOR EMERGENCY in the form of attendance sheets (see RESPONSE PERSONNEL" is a handout for fire attached) listing the name of the group, fighters, police and security officers, the date, the instructor, any handout and energency medical teams. materials used and the attendees. RPR 44. TRAINIE ($/89) - 2
- - - ----maaremmer.-- -
h RADI0 ISOTOPE USERS TRAINING OUTLINE Radiation users are encouraged to study (315-minute video presentations and 215-the handout materials for this training, minute demonstrations) available from the RSO at any time. Planning experimental pi icedures RADIATION SOURCES AE INTERACTIONS Preparation and use of fume hoods; (Handout and 60-minute lecture) checking air flow Contamination control; secondary Basic definitions; energy units containment Interactions of charged particles Proper wearing of gloves, lab coats and (electrons) with matter monitoring devices Electron ranges and bremsstrahlung Proper use of survey instruments; wipe production tests for contamination Interactions of photons with matter Opening and surveying packages; recording Half-value layers for photons changes to inventory Radioactive decay modes and emissions Waste segregation and labeling Radioactivity units: curie, becquerel Response to radiation emergencies, e.g. Radioactivity calculations: decay spills, injuries, etc. constant, half-life Units of radiation exposure and dose IS IVIDUAL EXPOSURE NONITORING Common sources of radiation exposure, (30-minute lecture with visual aids) natural and manmade Criteria for exemption from individual BIOLOGICAL EFFECTS A E RISK FACTORS monitoring Calculating potential external exposures 9 (Handout and 40-minute lecture) Sources of information on radiation Bioassay intervals determined by ALI and metabolism of nuclides effects and risks Bioassay measurements, screening and Deterministic (non-stochastic) effects of verification radiation Bioassay exemption based on absence of Probabalistic (st .hastic) effects of contaminatian radiation Confidentiality of dosimetry records and Somatic vs. genet.c effects of radiation rights of individuals Dose-response models; linear, nonthresh-old model REGutATORY NGD ADMINIST' .<E REQUIREMENi~S Risk projection models; absolute and (15-minute iecture witn visual aids) relative Organization: radiation safety conunittee, PRINCIPLES OF RADIATION PROTECTION RSO (30-minute lecture and handout materials) Radiation Safety Manual and procedures Responsible user definitica and Justification of practices producing responsibilities radiation exposures Procurement and security of radioactive Optimization of radiation protection materials (ALARA) Radioactive material inventory and dis-Individual dose limits; annual limits posal records based on lifetime risk Comparison of radiation rirks with other EXAMINATION common risks (20 multiple-choice questions; 30-10 External radiation dose limits mioutes) Annual limits on intake (All) CONTROL OF RADI0 ACTIVE NATERIALS 1 RPR 44. TRAINING ($/19) -3 c
J i i + - I l RADIATION-SAFETY TPAINING ATTENDANCE RECORD 4 Group: Date: /F ' p
. Instructor:-
Handout:.__ ! On this date, the undersigned attended radiation safety training, received'the listed i p _ handout material and were given an opportunity to ask questions pertaining to radiation l f. n risks and protection. I i
;f? PRINT NAME LEGIBLY PRINT _NAME LEGIBLY
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7 . ._. . ._ l 1 l
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I BASICS OF RADIATION SAFETY , 1
= RADIATION PRDTECTION POLICIES RADIATION DOSES Als RISKS Ionizing radiation is capable of producing Radiation doses are specified in units of biological effects that are detrimental- millirems. In the U.S., the annual aver- ! ~
to health. It is assumed that any radia- age dose from cosmic rays and other nat- ] tion dose, no matter how small, could ural sources is 100 mrem, the effective 4 produce some effect. The purpose of a dose from radon in homes is 200 mrem, radiation safety. program is to prevent medical examinations contribute an average i unnecesary radiation exposures, and to of 53 mrem and consumer products and other control those that are necessary, manmade sources deliver another 9 mrem, for a total of approximately 360 mrems per Each person who is exposed to radiation year. In Utah, . because of increased l must be informed of the risks and of cosmic radiation and greater concentra-
- appropriate protection methods, and must tions of radioactive minerals in the l l accept personal responsibility for using ground, the average annual dose is more
- l. the available protection. than 400 aren. !
The risk of fatal cancer from all causes RAD:ATION-IlWUCED HEALTH EFFECTS is approximately 1 in 4, or 25%, when averaged over the entire U.S. population, i Health effects from exposure to ionizing It is recognized, however, that certain I radiation may be stochastic (random in an sub-groups, e.g. smokers or residents of exposed population) or .nonstochastic large cities, have cancer risks that'are (predictable for an individual), above average while other groups have risks that are below the average. For Nonstochastic effects may be observed in most stochastic effects, a given dose of l an exposed individual when a relatively radiation is believed to add a constant large radiation dose, exceeding a thresh- fraction to the baseline risk. old value, is received in a rather short time. A dose smaller than the threshold A non-occupational dose- of 400 mrem per value will not produce the effect. Once year for 70 years is estimated to increase the threshold dose for a particular effect the baseline risk by approximately .1%. is exceeded, the effect is almost sure to The majority of radiation users receive occur, but the severity of the effect is occupational doses of much less than 400 proportional to the dose, mrem per year. An additional dose of 400 mrem per year for 20 years would increase Stochastic effects are those that occur the baseline risk by 0.3%. randomly in an exposed population, usually
- after a long latent period. Since these PRINCIPLES OF RADIAT1uN PROTECTION effects cannot be distinguished from those that occur in an unexposed population, the Two basic principles apply to every indi-cause-and-effect relationship cannot be vidual that may be exposed te radiation
established on an individual basis, but only on a statistical basis. For these I all radiation doses are to be kept as effects it is assumed that there is no low as reasonably achievable (AUUtA), threshold dose and that the probability and of occurrence is proportional to the dose. 2 no dose to an individual shall be However, the severity of the effect, if allowed to exceed the appropriate it occurs, is independent of the dose. individual dose limit. RPR 44. TRAINING (5/89) - 5
'l The' Al. ARA principle is applicable even dose limit for the embryo-fetus is 500 when the potential dose is well below the millirens during the entire gestation individual dose limit because it is period. As a further precaution, it-is assumed that some risk is associated with advisable to keep the monthly doses below any dose of radiation, no matter how 50 millirems. This degree of protection small. ALARA also means balancing the for the embryo-fetus can only be achieved benefits of dose reduction against social with the cooperation of the employee, who needs and economic considerations, should notify her supervisor or the RSO '
as soon as the pregnancy is known. r Dose limits are intended to limit the ' individual's lifetime risk of stochastic RADIATION USERS : effects from small chronic exposures as well as to prevent nonstochastic effects A ' radiation user" is any individual whose from large doses, official duties or authorized activities-include handling, operating, or working For individuals who are exposed to ioniz- in the presence of, any type of radiation ing radiation as a direct result of their source, whether or not such use is employment, individual dose limits are confined to a restricted area, based on the philosophy that their total health risks should be no greater than the A "normally exposed" radiation user is an risks accepted by workers in comparabic individual who could receive more than one occupations or industries who are not tenth (10%) of the occupational radiation ' exposed to radiation, dose limit in any calendar quarter. This category includes individuals who normally For anyone who does not receive a direct receive more than 100 mrem per quarter, benefit, e.g. a salary, related to their as well as some who rarely receive more radiation exposure, the individual dose than 100 mrem in a quarter, but who work l limits are much smaller than those for with sources that could produce a sig-
- radiation users. These "non-occupational" nificant dose accidentally, l limits are based on comparisons with the ordinary risks of living, rather than on A " minimally exposed" radiation user is risks due to employment. an individual who is unlikely to receive one tenth (10%) of the occupational radia-tion dose limit in any calendar quarter.
IlEIVIDUAL DOSE LIMITS This category includes individuals who routinely handle only small quantities of The primary occupational dose limit is radioactive materials, and others exposed 5,000 millirems per year, or 1,250 mrems only intermittently, e.g. most nurses, per calendar quarter, for the whole body, emergency and security personnel,. main-head and trunk, blood-forming organs, tenance, receiving, custodial and house-l gonads and lens of the eye. keeping personnel. l L The dose limit for members of the general Individual training and dosimetry records public, including all persons who are not are maintained by the RSO for normally classified as radiation users, is 500 - ? sed users; records for minimally millirems per year, or 125 mrem per cal- exposed users are maintained on a group i endar quarter. No person shall be clas- basis. Any radiation user may communicate sified as a radiation user simply to directly, in confidence and without justify a higher dose limit. prejudice, with the RSO or any member of the Radiological Health Department, the ! The embryo-fetus is more susceptible to Utah Bureau of Radiation Control or the radiation than an adult and is, there- U.S. Nuclear Regulatory Commission on any I fore, subject to a lower dose limit. The matter concerning radiation protection. RPR 44. TRAINING (5/89) - 6 _- _-____ __ __U
h
] RADIATION PROTECTION IN CARDIOLOGY
-RADIATION SAFETY REVIEW mounted shield should be used to providu 4 additional protection for the eyes and-Cardiac catheterization procedures produce head. Position the shield so that you large radiation doses to patients and to would have to look through it to see the attending personnel; the use of good portion of the patient's body that inter-radiation protection techniques is impera- sects the primary x-ray beam.
tive. One of the most effective ways to minimize Review " BASICS OF RADIATION SAFETY". radiation exposure is to develop an aware- i ness of the locations and intensity of ! radiation associated with various proced-EXPOSURE REDUCTION ures. For this purpose, direct-reading dosimeters (pencil type) are available Increasing tube voltage (kVp) and beam from the Technical Director (Pat Sine). filtration reduces the dose to the patient They should be used often to measure but also reduces image contrast. Reducing exposures to various parts of the body the tube voltage in,.reases the dose to the from various procedures. These dosimeters patient but gives higher contrast, are not used for official dose records, but are very useful for developing a , Decreasing the field size reduces the " sixth sense" for avoiding unnecessary . l total risk to the patient and also reduces radiation exposures. L the amount of radiation scattered from the l s patient to nearby personnel. Direct-reading dosimeters are not assigned l' ' to specific individuals and are not used Exposures from external sources can be for permanent dosintry records. minimized by: 1 using the shortest exposure time con- PERSONAL D0SIDETERS sistent with diagnostic requirements, 2 increasing one's distance from the Each individual (except the patient) who L source, and is regularly present during any cathe-E 3 by using appropriate shielding. terization procedure is required to wear - one or more personal dosimeters, usually During any medical fluoroscopic proced- film badges, assigned by the RSO and used ure, including cardiac catheterization or as the official dose record. Each badge angiography, the primary source of ex- is issued to a specific individual: and posure to attending personnel is radiation must not be worn by any other person. scattered from the patient. A useful rule of thumb is that the exposure rate at 1 One dosimeter is issued to each person to meter from the patient is 1/1000 of the record the maximum dose to the head, entrance exposure rate to the patient. considered to be the only critical tissue Since radiation intensity decreases rapid- exposed when a lead apron, thyroid shield ly with distance from the source, it is and goggles are worn. This badge may be advisable to step back from the patient referred to as the " collar" badge, since whenever possible, it is to be worn at the collar outside of any protective apparel and as close to the Shielding is very effective against the exposed area of the head as possible. The low-energy radiation scattered from the " collar" badge mu ' not be worn on the patient. In addition to wearing a leaded sleeve. O apron to protect the body, the ceiling-RPR 44. TRAINING (5/89) - 7
4
' A second dosimeter is issued to each investigation is to prevent overexposures h female to record the potential dose to an before they happen or from recurring; this embryo or fetus in case of pregnancy. can only be effective with the cooperation This badge is. referred to as the belly" of the employee, badge, since it is to be worn at waist level under the lead apron. For any investigation of an actual over-exposure, the University requires a When not being worn, dosimeters must be written, signed statement from the exposed stored away from heat and radiation- individual describing the reasons for the sources but they should not be taken home excessive exposure and the steps that will or worn away from work. All dosimeters be taken to control exposures in. the must be returned promptly at the end of future, the monitoring period.
A dose exceeding any quarterly or annual All regularly assigned dosimeters are limit must be reported by the University issued (placed on the wall board) on the (RS0) to the Utah Bureau of Radiation first working day of each calendar month. Control. Badges used during the preceding month must be returned (to the wall boarti) within the next week. To ensure that valid dosimeter readings are obtained,
' fees (fines) are assessed for badges that are lost or not returned for processing.
RECORDS Als REPORTS Each employee who may be "normally ex-posed" to radiation must complete a l RADIATION USER PERSONAL DATA form. The l required information includes (1) primary identification data, e.g. full name, birthdate, sex, and social security number; (2) previous training and exper-ience with radiation sources; and (3) current employment status, including job title or description, department, super-visor, and work location. Individual radiation user records are treated as confidential and are available only to those with a legitimate need for the information. An individual may re-view the contents of. his or her personal l- radiation user file at any time, and may obtain a summary of his or her radiation history annually, or upon termination of employment, upon written request to the RSO. Any radiation dose that exceeds the normal for the type of work performed is inves-tigated by the RSO. The intent of the & T l RPR 44 TRAINING (5/89) - 8
l
] RADIATION-SAFETY FOR NURSES AND THERAPISTS LEARNER OBJECTIVES During fluoroscopic procedures, the
- primary source of exposure to attending
- 1. Describe two basic principles of personnel is radiation scattered from the radiation protection, patient.'
2.. Describe two practical techniques for Even a little shielding is very effective reducing exposures to external sources of against the low-energy radiation scattered radiation, e.g. x-ray machines. from the patient. Typical leaded aprons stop more than 95% of the x-ray _ beam, i
- 3. Define the terms "normally exposed Even an apron that appears to be cracked radiation user" and " minimally exposed is an effective barrier against scattered ~
radiation user" as used for radiation x rays. If you must be near the patient, ' protection purposes, wear a lead apron.
- 4. State the quarterly dose limits for Since radiation intensity decreases for members of the general public, for rapidly with distance from the source, it the embryo-fetus, and.for radiation users, is advisable to step back from the patient whenever possible. At 6 feet or more from
- 5. State the quarterly radiation dose the patient, the exposure rate is low that justifies the wearing of a personal enough that wearing of leaded' aprons _is radiation dosimeter (film badge). not necessary.
EXPOSURE REDUCTION (]
- EXPOSURE EVALUATION Alm MONITORING Understanding and using basic methods for controlling radiation exposures is impor- External exposures are readily detectable tant for all radiation users, including with portable instruments and personal those who are only minimally exposed, monitoringdevices(dosimeters). Poten-tial radiation exposures from any source, L The most important concern in protection or within any facility, are evaluated by i
during fluoroscopic procedures is to avoid the RSO to determine protection and moni-i exposure to the primary beam. Patients toring requirements. In most cases, should be immobilized for x-ray examina- exposures are evaluated for groups of tions without being held, if at all pos- individuals engaged in similar activities sible. Never allow any part of your body and exposed to comparable sources. In to be in the primary x-ray beam. If it other situations, monitoring of individ-is absolutely necessary to hold the x- ual exposures may be necessary, ray film cassette, or a patient with your hands anywhere near the x-ray beam, wear y leaded gloves. Exposures can be minimized by: l l I keeping the exposure time as short as L possible, l 2 increasing one's distance from the source and by using appropriate shielding. O_-3 RPR 44. TRAINING ($/89) - 9
g3 pelts 0HAL DDSIIETEltS (BADGES) them and toproperly, to them exchange protect them from promptly damage . at the A radiation dosimeter does not provide beginning of each month, Fines are im-protection; it merely verifies, after the posed for dosimeters that are lost or not fact, the adequacy of the radiation con- returned within the scheduled exchange trol program. Also, radiation dosimetry period, data are not, of themselves, appropriate to determine risk to any individual; however, they- can sometimes help an individual to develop safe work habits. All radiation users who are "normally exposed" to external sources of penetrat- , ing radiation are required to wear one or more personal dosimeters. Users subject to whole-body exposures are issued " body badges", which are to be worn on the front of the torso at all times while working with radiation sources. Females subject to significant radiation exposures may be issued a second badge to be worn on the front of the abdomen under the lead apron. The purpose of the- second badge is to monitor the potential dose to the embryo-fetus in the event of a pregnancy, ; Radiation users who are " minimally ex-posed" to penetrating radiation from external sources, i.e. those who are h unlikely to receive more than 100 mrem to a major portion of the body during any calendar quarter, are not required to wear personal dosimeters.
, When adequate evidence exists to conclude that indivuals in a particular group or job function 'are unlikely to receive 100 mram per calendar quarter, radiation . doses are not monitored individually and-lifetime exposure- records are not maintained.
At the discretion of the RSO, groups of minimally exposed radiation users may be issued individual dosimeters for a limited time period to obtain exposure data for the group. The results of such monitor-ing are analyzed statistically to deter-mine the exposure potential for individual members' of the group. Individuals who are issued personal dosi-meters for any reason are required to wear RPR 44. TRAINING (5/89) - 10
l pd RADIATION SAFETY FOR EMERGENCY RESPONSE PERSONNEL- 1 i NATURE OF RADIATION SOURCES RADIATION DETECTION Radioisotopes used in many laboratories Geiger-Mueller survey vtters (" Geiger are easily dispersed and may cause counter") are very sensitive and excellent contamination of the skin and may be taken for detecting contamination. However, a into the body. The quantities found in Geiger counter may be swamped (saturated) research laboratories are usually too by a high exposure rate and give a false small to be of concern as an external zero reading. To be safe, start reading radiation source during an emergency. the instrumnt away from the source, then mov- arer. Sealed radionuclide sources are normally shielded and produce minimal risks. An ionization chambers survey mater is not However, if the shielding is damaged or as sensitive as a Geiger counter, but the source is otherwise exposed, high can measure the actual exposure rate, even radiation intensities may be present. If at high intensities. ' the source capsule is ruptured, serious
' contamination is also possible. EXPOSURE Am CONTAMINAYiON CONTROL i X-ray machines produce radiation only when Dose rates are reduced greatly by distance the power - switch is on; they do not and shielding; don't linger near a source.
, produce radioactivity and there is no ! possibility of contamination. Air contamination is not a concern unless l ' fire or explosion occurs; avoid obvious smoke and dust. ! DOSE RATES AE BIOLOGICAL HARM Most personal contamination comes from For general use in emergency situations, direct contact; keep pedestrian and the radiation dose units of roentgen (R), vehicular traffic out of area. rad and rem are interchangable. Dose rates are usually given in milliroentgens Evacuation of the immediate area is jus-(0.001 R) per hour (mR/hr). tified in the event of fire or explosion - . involving a radiation source or radio-The dose rate depends upon the distance isotope laboratory. from the source and shielding. Contamination should be detected and The dose received depends on the total confined or removed as promptly as pos-time of exposure; dose - dose rate x time, sible; keep potentially exposed persons in the area until cleared by the Radiation Detectable biological damage occurs only Safety Officer. when a dose of more than 10 mm (10,000 millirem) is received in a shoi o interval . l RPR 44. TRAINING (5/89) - 11
1 SPECIAL RADIATION FACILITIES Pathology Irradiator (5B202 SON)- This is a self-shielded irradiator, which ,
. Nuclear Engineering (Reactor) Laboratory . means that it can only irradiate samples '
(2005 K B) placed inside the unit; there is no exter-nal beam of radiation. This unit could Radiation monitors and alarms: the red become a hazard only under conditions of light in the fire hose cabinet indicates very severe damage to the containment. a radiation alarm has been activated - . possible high dose rate in reactor room; _ l the monitor above the door inside the Radiological Health Department (100 OSH) classroom indicates it is unsafe to enter if needle is above the middle of the The calibration source in the back room scale; before assuming that a low reading of 100 OSH is a sealed source that pro-is safe, make sure the monitor is on, duces an external radiation beam when the source is exposed (turned on). Except. Reactor room, fuel storage wells and when being used, the source is contained neutron source room contain sealed in its shield and presents no risk unless sources; these rooms, as well as the the source housing has been damaged, radiochemistry and counting laboratories, ; may contain small quantities of unsealed i radioisotopes with possible contamination. Intermountain Radiopharmacy (Bldg. 453) The laboratory and storage area in the north end of the first floor contains some relatively large unsealed sources with h possibilities for serious personal contamination if disturbed. Radioactive waste packaging facility, (Bldg. 502) ,' This building contains limited quantities of radioactive materials in various forms: i dry combustible wastes in partially filled drums, flammable liquids in flammable liquid storage cabinets. nonflammable liquids in plastic jugs on shelves, l e RPR 44 TRAINING (5/89) - 12
O RADIATION EMERGENCY RESPONSE PURPOSE This procedure provides general guidelines RADIATION EERGENCY for response by radiation protection ASSISTANCE & NOTIFICATION personnel to radiation emergencies of all types. It also provides specific proced. Radiological Health 581-6141 ures for responding to radiation emergen. Keith Schiager 484-5007 , cies in a few key facilities. Byron Hardy 968-8149 Clark Clements 581-1191 Ray Jones 571-7550 POLICY Anthony Macklyn 292-2355 Gary Stubbs 364-7529 .i The Public Safety Department is ; o responsible for overall emergency Nuclear Engineering 581-4188 : response, communication and coordination. Gary Sandquist 486-8521 The Radiation Safety Officer (RS0) is Kevan Crawford 943-9714
- responsible providing technical advice and John Bennion 363-9477 assistance on all emergencies potentially involving radioactivity or radiation Radiophamacy 581-8189 exposures. Responsible users of radiation Kelly Crebs 583-3366 l ',
sources are responsible for clean up of Farand Smith 967-5995 f s illed materials and for assuring that a 1 individuals within their jurisdiction Nuclear Medicine 581-2716.
. comply with monitoring and reporting Paul Christian 278-1798 requirements established the RSO.
Radiation Therapy 581-2396 John Moeller 571-5679 PREPAREDNESS Dennis leavitt 272-3908 The most important factor that determines Vice President , the adequacy and success of the response for Research 581-7236 to an emergency is the preparedness of the James Brophy 467-7590-responding . individuals or organization. Ronald Pugmire 277-6724 True preparedness is a mental condition much more than it is a physical condi . Regulatory Aoencies tion. Although detailed procedures and Utah BRC 538-6734
- . specialized equ?nent are sometimes impor. NRC Region IV 817-860-8100
( tant,-predetermined priorities and sys-tematic thought processes ' are essential in all cases.- Careful planning of who detailed emrgency procedures and notifica-should do what and when is often of great- tion procedures. For all other radiation er importance than practicing of how emergencies, the Radiological - Health , specific jobs should be done, at least for Department or the RSO will be notified, individuals who are already technically The first individual thus notified should l competent. ascertain the nature and extent of the emergency, the names of any other radia-Some facilities, e.g. the University tion safety personnel already notified and Hospital Emergency Department and the the need for additional assistance. l Nuclear Engineering Laboratory, have RPR 45. EMERGENCY RESPONSE (1/90) - 1 i
CGetsliCATI0llS specialist has been notified and in-- structions are given to cease. For Second only to mental preparedness in each person contacted, record name and importance, an effective communications . time. system is vital to prompt emergency re-sponse. One characteristic of an emer- Other emergency response personnel that gency is that it cannot be handled with are to be notified are indicated for each just one routine phone call. A reliable of the following major types of emergency - network is required to contact the neces- situations: sary individuals and organizations and to relay information accurately. Fire, explosion, structure collapse: Dial 9-911 to notify the Fire Department- ! The initial notifications of a radiation and the Public Safety Department. . emergency should be to the University Police or, during normal office hours, Illness or injury: directly to the Radiological Health Dial 9-911 to call an ambulance; if the Department. The University Police will patient could be contaminated, notify the notify appropriate individuals for spec- Hospital Emergency Room, Ext. 2291 or ' ific facilities and the Radiation Safety 2121 (Hospital Operator). Officer or alternates as shown in the box or in other detailed procedures. When a utility or equipment failure: member of the Radiological Health Depart- Facility Maintenance, Ext. 7221, and ment receives an emergency call, whether Safety Services, Ext 6590. in the office or elsewhere, the following actions are important: Radioactive material spills or releases: Safety Services, Ext. 6590, if other - 1 Ask the caller to stay on .the line chemicals are involved. until.you are sure that you have all of the necessary information. RADIOLOGICAL CLASSIFICATI0ll 2 Write down all of the information you 0F EERGDICIES receive. It is better to take a little extra time to assure complete Determining the proper response to an and accurate information than to over- emergency requires that the type and look something through haste. magnitude be determined - as rapidly as Information to request and record: possible.- If in doubt, it is better to a Date and time of call, over-classify and over-respond than to b Name of caller, under-classify and under-respond. c Location of emergency, i.e. build- Regardless of the type of emergency, ing, specific rooms, etc. radiation protection persmnel must con-d Exact nature of the emergency; centrate on the radiath aspects of the e.g. injuries, fire, spill, quan- response and leave other concerns to the tities of materials, etc. appropriate professionals, if possible. e Names of others already notified or tried but not reached. The nature of radiation hazards in an l' emergency may be any or all of the 3 Determine how much additional help may following: be needed and, before disconnecting, determine whether or not the caller External exposure to penetrating , will or should call additional indi- radiation viduals. Be certain that the calling effort is continued at least until a External personal contamination, e.g. professional radiation protection on skin, hair or clothing RPR 45. EMERGENCY RESPONSE (1/90) - 2
!L a
/ Internal personal contamination, e.g. RESPONSE GUIDELINES injected through wounds, absorbed <
skin, inhaled or ingested In most radiation emergencies the RSO (or-Alternate. RS0). will be in charge of the Equipment or facility contamination radiological response, if available. In , the specific facilitin listed below,.the : Environmental' re1 ease and responsibility for the emergency response contamination may be delegated to, or shared wit 1, the indicated individual (s):
.The magnitude of radiation hazards may be categorized as: Nuclear Engineering Laboratory: Reactor Supervisor or Senior Reactor _ Operator Extremely serious. Radiation doses ,
of - biological significance, large Radiology Department (Hospital): Radiolog- ~ releases of radioactivity to the ical Physicist ; environment, and accidents that cause ' major facility damage are considered 1 The person in charge of the radiation to be extremely serious. Such events response to an emergency should avoid, if j require immediate notification of the possible, becoming directly involved in ; regulatory agency by telephone and performing rescues, giving first aid- or telegraph. containing radiation sources. Instead, he should devote his attention to assur-Serious. - Any radiation dose that ing that all necessary actions are being exceeds the annual occupational dose carried out as efficiently as possible. L limit, any significant releases of i radioactivity to the environment, or 2 Personnel control and dosimetry should L k h. b moderate facility damage is considered to be serious. Such events require be assigned to one or more specific in-dividuals. For this task, the response u 24-hour notification by telephone and involves identifying and recording all telegraph, individuals involved in the emergency, rendering first aid, surveying for per-sonal contamination, decontaminating or EERSENCY EQUIPMENf containing clothing or personal articles, determining possible external exposures, Emergency kits containing basic survey collecting badges for special reading, L instruments, protective clothing, and releasing individuals to leave the area,. i supplies needed in emergencies are main- etc. If injured persons are sent to the tained in two Radiological Health Depart- Emergency Room, be sure to attach a tag ment vehicles. The instruments are minia- or note describing any contamination that ture GM survey meters'. with internal, may be present on skin or clothing. The energy-compensated, miniature GM tubes for most important equipment for this task measuring exposure rates, and external, will usually be a thin-window GM survey I thin-window GM detectors for evaluating meter and a personnel decontamination kit contamination. For evaluating contamina- containing detergent, waterless hand , tion on personnel, these emergency instru- cleaner, plastic bags, coveralls, towels, ments should be supplemented as soon as tape, etc. possible with survey instruments with larger window areas. 3 Control of radiation sources and faci-lity contamination is the second major response category. If enough help is ' available, this task should normally be ,p assigned jointly to a radiation specialist Q and someone thoroughly familiar with the l RPR 45. EMERGENCY RESPONSE (1/90) - 3
facility. The response includes control- an air sample at the most likely location I ling the event (fire, spill, etc.), deter- of exposure or highest concentration. Be mining the extent of any unconfined radio- sure to record start time, air flow rate, active materials, determining any. areas . location and relevant environmental condi-of high radiation exposure, controlling tions. This task also involves checking access to the area, etc. Since this task for possible surface contamination in requires approaching or entering the likely locations outside the immediate emergency site, a personal dosimeter, emergency zone, e.g. walkways, vehicles, - appropriate protective clothing and, in etc. some cases, respiratcry protection should be worn. Be sure of adeg ate protection 5 Documentation and reporting of all before proceeding. An exposure rate meter data collected and actions taken in an (ion chamber) with a thin window would be emergency are very important. Each in-the primary radiation survey instrument dividual involved in the response should for this response. - The facility and prepare and submit a written report cover-source conditions must be reported to the ing his or her own activities. The report person in charge as quickly as possible, need not be lengthy or polished but it must be factual . The RSO will determine 4 Area and environmental sampling is the to whom any comprehensive reports should third major task to be assigned. The be submitted and will prepare. such re-most urgent aspect of this_ task is to ports, ascertain the likelihood of an airborne release and exposure areas, whether indoors, outdoors or both. This involves NOTIFICATIONS TO REGULATORY AGENCIES a determination of airflow and extaust patterns from the location of potential Notifications will be made only by or with release and the wind direction. If a the concurrence of the RSO. The NRC and R. significant release is possible, initiate Utah BRC requirements for urgent notifica- W tions are shown in the box below. NOTIFICATION CRITERIA Event Imendiate Notice 24-Hour Notice Whole Body Exposure 2 25 rem 2 5 rem Skin Exposure 2 150 rem 2 30 rem i Extremity Exposure 2 375 rem 2 75 rem Radioactivity release l (24-hour average) 2 5000 L i 2 500 DAC l Loss of facility use 2 1 work week 2 1 day Property Damage 2 $200,000 2 $2,000 e RPR 45. EMER6ENCY RESPONSE (1/90) - 4 l
F
-h RPR 44A. REACTOR LAB (NEL) EMERGENCY RESPONSE NEL FACILITY RSO RESPONSE The Nuclear Engineering Laboratory, In this section, "RS0" refers to any of located in 1205 Merrill Engineering Build- the qualified radiation safety personnel ing, houses the TRIGA research reactor, on the notification list who is first to the Californium-252 neutron sources and be notified and arrive at the NEL; this a few small radiation sources. The pri- individual will be responsible for all mary entrance to the facility is from the radiological evaluations until the ;
South _ Main Corridor, through classroom University's Radiation Safety Officer 1205. An emergency exit connects from the arrives. , radiochemistry laboratory, room 1205G, to
- the Heat Power Laboratory next door north. Emergency Instruments Local Radiation Alams In response to any emergency at the NEL, the RSO should bring one or more radiation Alarm bells and a small red light inside survey meters capable of quick determina-the fire hose cabinet beside the entrance tions of external exposure rates or sur-to room 1205 MEBdin icate that the radia- face contamination. Emergency radiation tion alarm has been tripped. (This light survey meters are available just inside should not be confused with the red light the entrance to the Classroom (1205) for ! - ^
above the door which is on whenever the emergency use. The instrument (s) are reactor is operating; the light above the capable of making exposure rate measure-4 door also indicates that at least one ments up to at least 500 mR/hr and detect-operator is present.)' The radiation alarm ing surface contamination from alpha and bells and 11aht will be on even if trioned beta emitters, by an electrical malfunction so they do
- not necessarily indicate the oresence of hazardous radiation. C(NOIAls AIE COORDINATION A radiation monitor readout is mounted A command post will be established by the inside the entry direct 1v above the door. University Police or by the Salt Lake City If the meter needle is in the left half Fire Department, depending upon the nature of the meter dial (i.e. <3-5 mR/hr) and of the emergency. Radiation Safety and the alarm is not sounding, it is safe to Reactor Facility personnel shall check in enter any part of the facility. If the with the command post, identify them-
- needle on the radiation monitor is in the selves, and provide technical advice to
- right half of the meter dial(i.e. >5 the emergency-response personnel, mR/hr) or the alam is sounding, do not proceed into the facility without an Access Control operating exposure-rate survey meter.
Define area boundaries for contamination control. Instruct University Police to set up control boundaries as required. If there is any potential impact on the general public due to security measures such as traffic control, non-University civil authorities are to be notified by University Police. RPR 45. EMERGENCY RESPONSE (1/90) - 5
i
-If there is any potential for radiation In the absence of any noticeable physical exposure to members of the general public, damage, fire fighters should enter the g including University staff and students facility through classroom 1205 and ob-not directly involved with.the facility, , serve the radiation monitor mounted inside the RSO or his representative shall notify the entry directiv above the door,. If the city and state health departments, and the meter needle is in the left half of the ,
Nuclear Regulatory Commission, as re- meter dial and the alarm is not sounding, quired. it is safe to enter any part of the facil-ity in order to fight a fire. If there If radioactive material may have been is a fire in the classroom (1205), control released to the environment, or carried room (12050) or counting laboratory away as contamination on personnel or (1205C), use conventional methods for fire vehicles, make arrangements to collect and control. analyze samples as appropriate. Monitor all persons directly involved in the If the needle on the radiation monitor is emergency and the response personnel for in the right half of the meter dial or the contamination prior to their departure alam is sounding, fire fighters should from the area, not proceed beyond the classroom unless necessary to rescue an injured person. Contacts with Outside Anencies Before anyone enters the reactor room (1205E) for any other reason, an exposure-In the event of a release of radioactive rate survey must be performed. If high ! material to the environment, Reactor exposure rates are found, e.g. >500 Facility or Radiation Safety personnel mrem / hour, fire fighters may break out the should request the University Police to windows between the classroom and the contact off-campus agencies to help with reactor room and fight the fire from the security or radiation control measures, classroom. Otherwise, proceed to enter Building Evacuation Fire fighters or other emergency personnel i l The only reason to direct the evacuation are not to leave the facility until their of the building would be a bomb threat to clothing and equipment has been surveyed the facility or known occurrence of fire by the RS0 to verify the absence of radio-or other major disaster at the facility, active contamination. Fire Fiahtina NEL EMERGENCY CLASSIFICATION Since fire fighters are likely to arrive at the facility before the RSO, they must The primary response to any emergency in be instructed on protective measures. the Nuclear Engineering Laboratory (NEL) Fire fighters required to enter the facil- is the responsibility of the NEL operating
-ity to respond to an actual or potential staff. The NEL staff, usually in consul-fire or explosion shall wear full turn- tation with the RSO, will determine the out gear and self-contained breathing classification of the emergency and the apparatus until the absence of radioactive appropriate magnitude of the response.
contamination is confirmed. In addition to any other reasons for protective cloth-ing,- this requirement is a precaution against contamination with radioactive I material . Fire fighters shall also wear direct-reading radiation dosimeters pro-vided with their equipment. RPR 45. EMERGENCY RESPONSE (1/90) - 6 l
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[s Personnel Emergencies and any other emergency personnel who responded, should not leave until they '
, Personnel- emergencies include accidents have been surveyed and found to be free or occurrences _which. involve actual or
- .of. contamination.
potential exposures to personnel report-able under 10 CFR 20.403. Such emergen- The RSO is responsible for determining - cies include radiation exposure and con- whether or not a report is required under tamination of facility personnel although the provisions of 10 CFR 20.403. The RSO . the operational status of the laboratory is also responsible for maintaining any or reactor is not affected and no immedi- records of radiation exposure to personnel ate reactor safety action is required, and of release of radioactive materials If radiation exposure to non-facility to the environment. Facility personnel personnel is possible, e.g. due to a are responsible for maintaining all other-release of radioactive material, the event records related to the emergency event. may be classified as an Unusual Event or as an Emergency Alert (see page 9).. Emergency Condition Alerts If an accident or incident involves Emergency condition alerts include situa- 'i injured or potentially contaminated in- tions recognized as potentially hazardous
-dividuals, the RSO shall evaluate such that could affect the operability of the ,
persons for contamination. Remove con- reactor or the safety of facility person-taminated clothing, if possible, before nel. Civil disturbance, breach of secur-sending an injured person for medical ity, or severe natural disorders are ' treatment. If the injury requires medi- examples of conditions necessitating an cal treatment, but involves no radioactive emergency condition alert, contamination, the injured person may be i
, sent (or.taken by ambulance) directly to If the emergency involves actual or poten-the Emergency Room at the University tial release of radioactive material Hospital, and/or radiation exposure to non-facility personnel, the RSO in conjunction with If an ambulance is required, it can be facility personnel, shall determine the obtained most rapidly by radic from the Emergency Class (see following table),
command post. If a commend post with Notify other personnel as required by the radio has not yet been established, dial emergency classification.. 9-911. Notify the Emergency Room (Ext. 2291 or through the Hospital Operator, Reactor Emergency L Ext. 2121) that a potentially contami-nated victim will be arriving. Collect, Reactor emergencies are physical occur-or ask the Emergency Room to collect, rences which require emergency response appropriate samples to be analyzed for actions although an off-site hazard is contamination or activation products, e.g. unlikely. Substantial modification of hair, rings, nose wipes, etc. Arrange for reactor operations might be necessary if L prompt analysis and interpretation of the automatic protective systems are not j samples. already activated. If radioactive contamination is present, Account for all personnel known or sus- ' confine the source of contamination to pected to be in the area. The possibility l keep it from spreading and contaminating for abnormal radiation exposures must be
- i. additional people. Remove contaminated evaluated, and the appropriate Emergency clothing; remove contamination on skin and Class determined.
hair by normal washing, taking care not to spread the contamination. All facility personnel present during the emergency, 1 l RPR 45. EMERGENCY RESPONSE (1/90) - 7 l L ! l - o
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Facility Emergency Ranctor Raam Entiv Procedure ! A facility emergency is any event which 1 Security Officer must open Classroom involves the uncontrolled release or and Counting Laboratory, potential release of radioactive material l into the air, water or ground to the 2 Obtain the keys to the Centrol Room
- extent that protective measures off-site and the Reactor Room, might be required. The Eurgency Class shall be determined by the criteria listed 3 Open the Control Room door, o
in the table on the fo14 wing page. 4 Check the reading on area radiation L. l Establish a location for Emergency Control monitor mounted in the left-hand Center (ECC). The ECC is to be the pedestal of the control console. A reactor control room unless it is not portable survey meter is also avail-
- usable because of damage or contamina- able at the console for further ex-tion. If it is not possible to use the posure rate measurements, control room the ECC should be set up as I
close as possible to the NEL. 5 Turn off the security alarm at the switch above the door to the Reactor Inform the following individuals promptly Room; key slot vertical, of any emergency situation which may involve damage to, or contamination of, 6 Unlock the door and enter the Reactor i any University or -private property, or Room. I for which the release of information to the news media or the general public may 7 Turn off the alarm at the terminal be necessary or desirable: (right hand) box at the northeast corner of the Reactor Room. If pos-Vice President for Research Ext. 7236 sible, reset the alarm with the key i Dr. James J. Brophy 467-7590 switch on the front of the terminal l l or Dr. Ronald Pugmire 277-6724 box. Alarms may also be disabled by l
- 1. turning off 2 toggle switches inside j Associate Dean of Enaineerina Ext 8363 the terminal box.
Dr. Dietrich Gehmlich 467-8978 or Dean of Enaineerina Ext. 6911 - Dr. David W. Pershing 355-7734 l l l 1 l l RPR 45. EMERGENCY RESPONSE (1/90) - 8
.{
t RADI0 LOGICAL CRITERIA FOR DETElBIINING DERGENCY CLASS h raency Lg11- . . . Classification Criteria . Purnose and Resnonse y Unusual- Bomb threat.. Prepare facility staff for i Event. Severe natural phenomenon. emergency response, if neces-sary. . Actual or projected radiation exposures at site boundary: Provide basis for systematic 10MPC(24-hravg.) recording- and reporting of 240 MPC-hours unusual' event information. i 15 mrem to whole body in 24 i hours Alert 50MPC(24-hravg.) Place emergency response'per- ' 1200 MPC-hours sonnel on standby. 75 mrom to whole body in 24 hours Provide off-site authorities: with current status informa-- 20 areW hr in I hour t 100 mrem to thyroid tion. Site Area 250 MPC (24-hr avg.) Initiate off-site monitoring *
~ Emergency 6000 MPC-hours for airborne and external ex-375 mrem to whole body in 24 hours posures, j '
100 mrem /hr in 1 hour Prepare - for evacuation' of - O1 500 mrem to thyroid nearest areas (on ~or.' off-l site). Consult with off-site authori- 'I ties. Provide information to the ! public through approved i' channels; ,e General 500 mrem / hour.to whole body at Evacuate nearest areas (on and [ Emergency. site boundary off campus). 1000 mrem to whole body ! 5000 mrem to thyroid Provide frequent updates of - l: information to the public, p, n u :, Teedefinitionsandexplanationsonnextpage,
- l l
l , O ! l RPR 45. EMERGENCY RESPONSE (1/90) - 9 )
4 i 1 INTDtPRETf4 TION OF RADIOLOGICAL CRITERIA
*pFC" means the maximum permissible concentration of any radionuclide in an unrest-h l ricted area. Breathing air containing 1 MPC for an entire year (8760 hours) will result in an intake of radioactive material that will deliver the maximum dose 1 permitted to a member of the general public in any year, i.e. 500 millirem (mrem) to the whole body, or 2500 mrem to the thyroid.
2 The annual limit on intake (ALI) for radiation workers is the quantity of any radionuclide which, when taken into the body, will deliver an effective dose l equivalent to 5000 mrem. Thus, 8760 MPC-hours is equivalent to an intake of 0.1 l ALI. Since the volume of air assumed to be inhaled ear is 7500 m3 ,then l one MPC is also equivalent to 0.1/7500, or 1.3 x- 10'{n one ALI/m. Under adverse meteorological conditions _ and for the situation in which material- ! is released at or near ground level, the atmospheric dispergion factor, X/Q, is i no larger than 10-2 37,3 at 100 meters and no larger than 10' s/m3 at 500 meters. The nearest occupied buildings are at least 100 meters from the NEL in the S, SW, , W and NW directions, and 500 meters from the NEL in the N, NE, E and SE directions. 4 The radiological criterion for an "unusugl event" is a 24-hour integrated exposure of 240 MPC-hours, or 3.2 x 10's ALI-hr/m . Th _ tot i release required to achieve thisintegratgdconcentgation,withX/Q--10' s/m , would be: 3.2 x 10~ ALI-hr/m x 3,600 sec/hr x 10' s/m = 1150 ALI. The integrated exposure of 240 MPC-hours could only occur if the meteorolodcal l conditions remained unchanged and the exposed individual remaingd at the locetion , of highest concentration during the entire release. For X/Q = 10' s/m3 , the release 1 limit would be 11,500 ALI. 5 - Values of ALIs for inhalation of all radionuclides of concern are available in ICRP ! Publication 30 (in SI units) or in the draft revision of 10 CFR Part 20, published in the Federal Register on January 9,1986. The following examples may be useful: H-3 80. millicuries : Na-24 5. mil 11 curies P-32 0.9 millicuries , S-35 10. mil 11 curies ' Sr-90 0.02 mil 11 curies Cs-134 0.1 millicuries i Cs-137 0.2 mi111 curies 1 U-235 0.04 microcuries ! U-238 0.04 microcuries Cf-252 0.04 microcuries Mixed beta emitters (no alpha emitters): 0.7 microcuries < O RPR 45. EMERGENCY RESPONSE (1/90) - 10
h PERSONAL EXPOSURE INVESTIGATIONS AND REPORTING PURPOSE For internal exposures, the IL is 0.05 ALI per single intake or per calendar This procedure specifies the requirements quarter. Intakes exceeding 0.25 ALI per and responsibilities for conducting, quarter must be reported to the licensing documenting and reporting investigations agency, and intakes exceeding 0.3 ALI per ; of incidents involving actual or suspected year must be converted to effective dose ' radiation exposures to individuals, equivalent and added to any measured dose a from external sources, t POLICY ; Potential exposures due to contamination ~ A' radiation dose received by any person or injury involving radioactive materials in one calendar quarter that exceeds 25 shall be investigated regardless of the percent of an-annual dose limit must be actual radiation dose, investigated and reported to the regu-latory agency. The RSO directs the inves- PROCEDURES tigation, evaluates the results and sub-mits the report to the regulatory agency. The R50 shall ensure that any overexposure 1 The exposed individual must provide infor- reported by the dosimetry service con-mation regarding the circumstances of the tractor is investigated promptly. The exposure. The responsible user must be RSO shall also ensure that the monthly
-informed of the exposure and of any subse- dosimetry reports are reviewed promptly quant restrictions that may need to be to determine whether'any reported doses , imposed on the individual. exceed the relevant investigation level. '
t A " PERSONAL EXPOSURE INVESTIGATION REPORT" The University is committed to maintaining (RPR 46A) is initiated for each reported ; all radiation doses to levels that are as dose-that exceeds an IL. low as reasonably achievable (ALARA). One of the methods for accomplishing the ALARA Dosimeter readings shall be accepted as goal is to investigate situations and valid and shall not be changed on the incidents that lead to unusual exposures, permanent record unless there is a com-even if no regulatory limit is exceeded. plete, written description of the cir-To assure that unexpected radiation ex- cumstances that produced an invalid dost- 1 posures are evaluated, investigation meter exposure, and the report is signed
^
levels are established well below the dose by the exposed individual, the responsible limits. user and the RSO. j For external exposures, the investigation for each overexposure requiring a report level (IL) is based on the expected to the regulatory agency, a written state-(normal) exposure for a category or spe- ment shall be submitted by the exposed l cific group of radiation users. For individual describing the circumstances example, for certain cardiologists, the that led to the exposure, and the measures ! Il for whole-body exposure may be as high that will be taken to prevent a recur'- l - as 250 mrem / month, whereas for most radio- rence, isotope laboratories the IL is only 50 mres/ month. Values of the Il for other The original Investigation Report and I l groups and for doses to the extremities all attachments shall be filed in the I are listed in the following table, personal dosimetry reesrd for the individ-ual. A copy of the report shall be pro-vided to +he exposed individual, i: RPR 46. INVESTIGATIONS (1/90) - 1 I a - - - -
- _ _ - . _ . _ - - _ - - _ _ - - - _ - _ - - _ - - - _ _ - _ - _ _ - . - - _ _ _ _ _ _ _ _ - - . _ _ -
INVESTIGATION AfD REPORTING LEVELS i External Dose External Dose Intake by : to Whole Body to Extremeties any route Reportable overexposure: 1,250 arem 12,500 mrem 0.25 ALI per quarter per quarter (500 DAC-hrs) per quarter Investigation Levels: Exceeds ALARA for: i Cardiology Fellows 250 mrem NA NA , per month s Diagnostic Radiology .100 mrem NA NA ! per month ! i Nuclear Medicine 100 mrem 500 mrem 0.05 ALI per month per month per event , or per ! calendar : quarter ;
- Radiopharmacy 100 mrem 2,500 mrem "
per month per month All Others 50 mrem 500 mrem "' per month per month .; i O RPR 46. INVESTIGATIONS (1/90) - 2 m-~m__--__.-- _ _ _ - _ . _ _ _ - . - - _ . - _ . - . - - _ . . - _ _ . - - . - _ . -
.. ~ - . - .- . . ---- -. . -_ . - .. --
l RPR 46A.- PERSONAL EXPOSURC INVESTIGATION REPORT
/]
Name: Soc. See. No.: Work Location: Paone: ' Responsible User: Departnent: Reason for Investigation: Abnormal dosimeter reading For the period: J Badge No.: Series: Type: Body [ Collar Ring Reported dose - Penetrating: mrem; Non-penetrating: mrem L- Abnormal bioassay - Urine ; Thyroid Date: l Personal contamination or injury Date: \ l l Results of Investigation: (description of event, cause, etc.) j l Intake of radioactive material - Estimated: ALI; Verified: ALI , Intake verified by: Date: L Employee interviewed by: Date:
- l Employee statement attached? Yes No Date:
l' Other information needed? (e.g. calibration, training, etc.) fes No ! If yes, explain: Requested by: Date: Received: Recommendations to prevent recurrence: Report of overexposure required? (see preceding table) Yes No i ! Reported by: Date: e Additirnal documentation attached: Date:
Description:
l Date:
Description:
i O RPR 46. INVESTIGATIONS (1/90) - 3
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4 O RPR 46. INVESTIGATIONS (1/90) - 4
1 ENFORCEMENT ACTIONS i
!] \
l PURPOSE 2 Repeated failure to submit required l bioassay results or samples. I The fol' awing procedure contains the steps 1 that are to be taken when it becomes 3 Repeated failure to perform required ne'.essary to notify a Responsible User of laboratory surveys. 1 erious deficiencies in complying with radiation safety procedures and, if neces- 4 Repeated failure to return the RADIO- i sary, to restrict the acquisition of ISOTOPE RECEIPT AND VERIFICATION form o radicnuclides until the deficiencies are (RPR 138). r corrected. 5 Repeated failure to return or to pro-vide adequate information on the POLICY RADI0 ISOTOPE DISPOSITION RECORD (RPR 13C). Actions to restrict the acquisition of radioisotopes or the use of any radiation Before taking the enforcement actions source, for. the purpose - of enforcing described below, it is important that a compliance with radiation protection conscientious effort be made to obtain regulations or procedures shall be compliance through personal discussions initiated only by the. Radiation Safety with the Responsible User or appropriate Officer. The affected user may appeal the individuals in the User's group. action to the Radiation Safety Committee or to the Vice President for Research. y ENFORCEDENT PROCEDURE
- i. RESPONSIBILITIES 1 Send the User a NONCONPLIANCE NEMD (sample attached). This memo should An individual in the Radiological Health be addressed and printed individually Department will be assigned the respons- from the word processor, listing only ibility for maintaining the records re- the specific items of noncompliance ;
lated to compliance enforcement actions, applicable to the User.
~
This individual may relea'se the restric-tion on acquisition of radionuclides or 2 Give a copy of the NONCONPLIANCE BEND use of a radiation source after verify- to the Administrative Assistant to ing that all of the deficiencies that include in the agend for the next initiated the restriction have been cor- meeting of the Radiation Safety rected. Committee. 3 Change the entry in field #17 of the ColEITIONS FOR ACTION User's authorization file in the RADIATION' SAFETY DATABASE to "N" to Any significant violations of radiation remove the authorization as an safety policies or procedures may be approved radioisotope purchaser, grounds for enforcement actions. Some of the most common deficiencies or viola- 4 Make an entry on the USER'S FILE IlWEX tions are: SHEET indicating that-the compliance memo was sent, the date and the 1 Repeated failure to return dosimetry reason. devices. RPR 47. ENFORCEMENT ACTIONS (1/90) - 1
1 5 Place a copy of the form or memo de-scribing the nature of the noncompli-d Make sure _that all forms and records related to this noncom-gi ' t ance in the 'ENFORCDGIT ACTION' file- pliance action are filed properly. in. the slot correstonding- to the' User's surname initial. l 6 Once a month, the Secretary shall review the items in the ENFORCEMENT ACTION-file and inform the Director of any that are more than one month old. _7 7 The Director will determine whether the authorization as. a Responsible User should be terminated, submitted to the Radiation Safety Committee, or # other course of action. CLEARING OF NONCONPLIANCE ACTIONS 1 All information, e.g. memos, forms or other records, relating to a current noncompliance enforcement action shall be given to the Secretary, who shall - proceed with action 2 or 3, below. 2- If there are still some unresolved noncompliance items,-add the new in-formation to the ENFORCEMENT ACTION file. If the notice was sent more , than_ one month : earlier, ' notify the Director.- If all noncompliance items have been resolved, the Secretary shall: a Make. the appropriate entry in field #17 of the User's authoriza-tion record on the RADIATION SAFETY DATABASE. b Enter the date the noncompliance i was cleared on the USER'S FILE IEEX SHEET. c Inform the Administrative Assist-ant of the date the noncompliance 1 was cleared for reporting to the Radiation Safety Committee. 1 1 RPR 47. ENFORCENENT ACTIONS (4,90) - 2 l
a n v UhHElVERSITY
" UTAH
. INSERT DATE T0: INSERT NAME OF RESPONSIBLE USER.
r FROM: Keith Schiager, Radiation Safety Officer t
SUBJECT:
COMPLIANCE WITH RADIATION SAFETY PROCEDURES This is a reminder that your authorization to use radioactive materials is I conditional on your compliance with the regulations, policies and procedures of the Utah Bureau of Radiation Control and the University's Radiation Safety Committee. 1 According to our records, you are presently not in compliance with requirements in i the areas listed below. The Radiation Safety Committee has instructed me to take action to assure compliance. The specific items of noncompliance that require immediate correction are: Failure to perform required bioassays and submit the data to this office as required by RPR 12, BI0 ASSAYS FOR-INTERNAL RADI0 ACTIVITY. , Failure to perform and record contamination surveys -on a regular basis, as '
- required by RPR 11, RADI0 ISOTOPE LABORATORY SAFETY PROCEDURES.
V Failure to return RADI0 ISOTOPE RECEIPT & VERIFICATION forms (RPR 138) promptly after a package of radioactive materials has been received. Our records show reports not returned by you. Failure to return RADI0 ISOTOPE DISPOSITION RECORDS (RPR 13C) and/or to complete it properly as required by RPR 13, RADI0 ISOTOPE ACQUISITION & DISPOSITION. (We can't tell from our records which of your, outstanding inventory items have been used up, but the records indicate a rather large accumulation of old items.) Failure to label radioactive wastes accurately and completely, as required by RPR 13, RADI0 ISOTOPE ACQUISITION & DISPOSITION. Effective immediataly, no further acquisitions of radioisotopes by you will be j approved until compliante has been achieved. If this creates a hardship. for your ' research, I am willing to discuss other means of obtaining the same objectives. Your prompt attention and action to resolve this problem will be greatly appreciated.
'O Radiologicalllealth Department Salt ke it th 11 2 (801) 581 6141
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RPR 47. ENFORCEMENT ACTIONS (1/90) - 4
)
, I RADI0IS0 TOPE LABORATORY EVALUATIONS V(T PURPOSE over the most restrictive bioassay inter-val, expressed in ALIs The routine This procedure provides instructions to evaluation frequencies for various average radiation safety personnel for performing monthly inventories are shown in the box. l radiological evaluations of radioisotope l laboratories. It also contains instruc- If no work with radioisotopes is being tions and forms for recording and rc, Sort- done, and all radioisotopes are stored in ing the results of such evaluations, a locked location conspicuously . labeled with a sign that requires notification of .
POLICY the RSO prior to any further use of radio- ! isotopes, the 1aboratory may be considered l The RSO shall ensure that all areas where to be inactive and need be inspected only radioactive materials are stored or hand- annually. led are inspected at appropriate intervals to ascertain the radiological risks and The nominal survey' frequencies given in to evaluate the control measures in use, the box are to be interpreted as guide-Radiation surveys shall be performed, when lines. In cases where continuing con-necessary, by technically qualified per- tamination problems are found, the inter-sonnel using instruments appropriate to val between surveys will - be shortened. the nature of the radioactive materials If survey results obtained overLa period to be detected or radiation exposures to of a year indicate no contamination or be measured. exposure problems, the routine survey interval may be increased. In no case,. r for radioisotope laboratories, i.e. those however, will the interval be more than where dispersible radioisotopes are used, double the nominal interval. To assure the frequency of routine evaluations is a realistic and independent evaluation of based on the " interval inventory", as typical conditions, the ~ schedule for defined in the Radiation Safety Policy surveys may be varied randomly. Manual . The " interval inventory" is the total quantity of radioisotopes introduced into the laboratory in a month, averaged ROUflNE RADI0 ISOTOPE LABORATORY EVALUATIONS Interval Inventorv* Nominal Frecuency
>30 ALIs Monthly 1-30 ALIs Each bioassay interval
<1 ALI Semi-annually Inactive ** Annually
- Monthly average during interval.
** See text.
O RPR $0. LAB EVALUATIONS (1/90) - 1
i i DEFINITIONS Radiatiortatta: Any accessible area in which an individual could receive a dose Bioassay Interval: The maximum time that equivalent exceeding 5 mrem in I hour at may elapse between bioassays that will 30 cm (1 ft) from the source or from any assure detection of the verification level surface the radiation penetrates. for a given assay method. See "BI0 ASSAYS FOR INTERNAL RADI0 ISOTOPES" (RPR 12). Hlah Radiation Area: Any accessible area in which an individual could receive a Radioisotone Laboratory (Lab): Any room dose equivalent exceeding 100 mrem in 1 ; or area in which 10 or more Reference hour at 30 cm (1 'ft) from the source or ; Quantities of unsealed radioactive mater- from any surface the radiation penetrates. ials are stored or used. Since the only . . : laboratories referred to in this procedure Airborne Radioactivity Area:-- Any room or are radioisotope 1aboratonies, they are enclosure in which airborne radioactive referred to simply as " labs", material exists in' concentrations exceed- l ing the derived air concentrations (DACs) Reference Ouantity: A quantity of any or in which any individual could be ex-radioisotope related to its relative posed to more than 0.6% of the ALI in one l hazard potential and used to prescribe calendar week. L l requirements for handling, monitoring, i labeling and disposal. See "RADIONUCLIDE PRE-START EVALUATIONS L CATEGORIES AND DATA" (RPR 10A). Before radioactive materials .are intro-Interval Inventory: The total quantity duced into a laboratory, a general evalua-of radioisotopes introduced into the lab tion is made by the RSO to ascertain that each month, averaged over the bioassay equipment, instruments and supplies neces-interval, expressed in ALIs. sary for controlling contamination and exposures are present or will be available Controlled Area: Any area to which access when work with radioisotopes begins. is limited for any reason, Radioisotope Unless the lab is very small and simple, laboratories are controlled by posting and a floor plan map should be prepared during locking for the purpose of preventing the pre-start evaluation. This map should ' l unauthorized removal of radioactive mater- be approximately to scale and should l ials. Exposure to radioactive materials identify the locations of major l 1s prevented by controlling the materials, radioisotope storage and work areas, waste not by limiting normal. access to the storage locations, hoods, sinks, etc. l- laboratory when it is open and attended. l The authorized quantities and frequencies ! Restricted Area: Any area to which access of radioisotope orders should be reviewed I is limited for the purpose of protecting and verified with the user. Calculate the individuals against undue ' risks from expected average monthly inventory, in exposure to radiation and/or radicactive ALIs, and review with the user the material. The mere presence of any radia- significance of the inventory to - the tion source, if adequately controlled to routine survey and bioassay requirements, limit potential exposures, does not neces- If animals are to be used, review " HOUSING sitate a restricted area designation. AND HANDLING OF RADI0 ACTIVE ANIMALS" (RPa l Areas containing sources with the poten- 1s) with the user, tial for producing significant exposures require specific authorizations and pro- Procedures for handling and storing cedures for access and are designated as radioisotopes, for surveying and l restricted areas. monitoring, for waste dis)osal and for l record keeping should be c Iscussed with RPR 50. LAB EVALUATIONS (1/90) - 2 l
L l - the responsible user. If an analytical to be recorded on the ' CONTAMINATION O instrument is to be used for counting urine samples or contamination wipe tests, WIPE TEST RESULTS" fonn (RPn soc). review with the user the counting 3 Unless the lab uses only tritium, the efficiency for each sample type and for first priority should be a direct each anticipated isotope. Review with survey for contamination. For I-125, the user appropriate sample sizes and a thin crystal scintillation detector counting times for urine samples, and the is best. Otherwise, use a thin window results that would require verification. G M survey meter with audible indi-cator. Move the detector slowly over Prior to the start of work with all surfaces that might be contan-radioisotopes in the laboratory, waste inated, holding the detector 1-2 cm containers are to be available and the from the surface. If positive (above necessary - signs and labels are to be background) responses are detected, losted. The ' LABORATORY EVALUATION CHECK stop and record the actual count rate.
.IST" (nra scA) is used as a guideline for Reference the . recorded results ' to items to be evaluated and is retained in specific objects or locations.
the RS0's laboratory survey flie. 4 At locations with positive indications ROUTINE LYALUATIONS of exposure or contamination, first ascertain whether the reading could haparation be penetrating radiation coming through the surface, rather than from 1 Review the emissions, energies and contamination on the surface. If Alls of the isotopes used. Determine significant penetrating radiation is the removabic contamination limit (s) detected, i.e. more than 0.2 mrem /hr that apply to the isotopes used. (approximately 10 times background), O- Review the user's current radioisotope an eposure rate measurement should be macle, usually at 30 cm (1 ft) from 2 inventory. Which isotopes are the surface. Record the results and significant for contamination or post the area, if necessary. exposure potential? What is the interval inventory? 5 At incations with a positive indica-tion of contamination, or surfaces 3 Review the previous survey results. that are not accessible for a direct Were there any problems? Were there measurement, take a wipe with an ab-recommendations that should be fol- sorbent material, e.g. fil'ter paper. lowed up on this time? If possible wipe 300 cm s if not, wipe 100,cm, or the entire surface. Ernosure and CoAtcination Survtys (A 300 cm area is any equivalent of a7-inchsquareorastrip3cmwide 1 Record tlne makt , model and serial and 1.5 meter long; a 100 cm area is numbers of survey meters used for the any equivalent of a 4-inch square or survey on the ' DIRECT RADI ATION SURVEY a strip 1 cm wide and 1 meter long.) RESULTS" form (RPR 508). Indicate the calibration date and the appropriate 6 With the survey meter in a low-detection efficiencies for the criti- background location, make a direct cal isotopes. measurement of the contamination on the filter paper. Record these 2 If the lab uses only tritium, the results and convert them to multiples entire contamination survey must be of the removable contamination limit done by wipe testing. The results are (RCL). RPR 50. LAB EVALUAi!0NS (1/90) 3
emitter, e.g. P-32. Use the If Ctected contamination could be appropriate efficiency for the 7 from low energy beta emitters, e.g. portable survey meter to quantify the C 14, S 35, etc., the wipes should be result, kept and counted in a liquid scintillation counter. The results f If the result obtained through 1 mm should be recorded on ' CONTAMINATION Al is more than 50% of the first, the WIPE TEST RESULTS" (nPR soc). contaminant is a gamma emitter. If it is important to identify the 8 If contamination is detected and the isotope, take a wipe or sample of the isotope is not known, the procedure contamination for spectral analysis in the following section may be used with the Ge(L1 detector and to categorize the contaminant for multi-channel analy)zer. further analysis. Routine Audit Canitainant_ Evaluation by Direct Meauttatut A radiation safety audit is a systematic review of all operational and administra-a Make a measurement of the contaminated tive radiation protection requirements in surface or of a wipe with the thin- addition to a survey for exposure rates window G-M survey meter, and removable contamination. An audit includes, but is not necessarily limited b Make a second measurement after to, the following items: placing a sheet of paper over the contamination while keeping the meter Storaae and Security in the same position relative to the contamination. If the second result The regulations governing the use of is less than 1% of the fi.'st, the most radioactive materials require that they likely contaminant is an alpha be secured from unauthorized removal. To emitter. Use either the gas-flow, accompli h this, the lab entrance and any internal proportional counter or a cabinets, refrigerators or freezers in liquid scintillation counter to make which radioisotopes are stored, must be a quantitative measurement. locked when the lab is unattended. This should be verified by noting that locks c If the second result is reduced to are availabia and by querying the users, about 15% of the first, the contamination is most likely a low- Fune Hoods energy beta emitter, e.g. C-14, S-35, or C-45. Use a liquid scintillation The velocity of air entering the hood counter to make a quantitative should be measured annually. Since the measurement, sash of the hood is intended to serve as a shield to protect the face from d If the second result is more than 50% spatters, as well as to control air flow, of the first,, the contamination could it should be set at an appropriate work-be a high-energy beta and/or gamma ing height when measuring the air flow , emitter. Make a third measurement rate. Because it is difficult to get with a 1-mm thick piece of aluminum people to use the sash ?roperly, it is over the contamination, usually necessary to ciscuss working habits with the person who uses the hood e If the third result is less than 20% before deciding where the sash should be of the first, the isotope is most for the measurement. It is also import-likely a high-energy, pure-beta ant to clear the hood of major obstruc-RPR 50. LAB EVALUATIONS (1/90) - 4 m
tions to the flow of air. This necessity eating, drinking, smoking or mouth O should also be discussed with the user to assure that the hood provides the intended pipetting in the lab is considered de facto evidence of violation of this protection. requirement. However, it is important to watch for other personal contacts, e.g. With the hood free of major obstructions pencils in the mouth, application of and with the sash at the appropriate makeup, etc. height, measure the face velocity with a small anemometer held with the inlet Ernosure Control facing directly out from the hood. Make at least six measurements at different If isotopes that omit penetrating radia-locations within the opening and record tion are used, the appropriate use; of the average velocity in feet per minute shielding and distance shou id be reviewed. ,> (fpm). No single measurement should be Phosphorous-32 should be shielded witn at less than 60 fpm or more than 150 fpm; the least 8 mm average face velocity should be in the material, e(3/8")lastic
.g. p or wood. Iodine-of any low atomic range of 80 to 100 fpm. If the desired 125 should be shielded with at leas! 3 en velocity cannot be attained, discuss (1/8") of lead. Other isotopes that emit possible modifications in techniques or higher energy gamma rays may require 5 cm to the equipment with the user. If the (2 ) or more of lead. Make sure that the face velocity is acceptable, record the shielding extends entirely around the velocity, the date and your name on a source by making measurements of exposure green fume hood label ("CLOSE SASH TO rates above, below, in back and at the HEREFORPROPERAIRFLOW")andattachit sides of storage locations. Adjacent to the frame at the level of the bottom locations with elevated exposure rates 4 edge of the sash, should not be regularly occupied. If any O The fume hood should be visually inspected during each routine audit to assure that dose rate exceeds 5 mrern/ hour at 30 cm from a source or a surface, the room must be labeled with a " CAUTION - RADIATION it is functioning and being used properly. AREA
- sign. If doses to the head or trunk could exceed 100 mrem in a calendar quart-Contamination Control er, body badges should be issued.
Gloves, lab coats, or other protective Review handling techniques and the use clothing as needed for the work, should of tongs with the user. If doses be available and worn in the lab. Lab exceeding 1,000 mrem per calendar quarter coats and gloves should not be worn to the to the hands are possible, ring badges cafeteria, library, classrooms or home, should be issued. Sandals or other open-toed shoes are not appropriate for work with radioisotopes. Instruments Work, storage and waste areas should be Verify that appropriate survey instruments provided with secondary containers and are available, operable and- in use. covered with absorbent pa)er. Plastic Verify that no repairs or modifications trays and dish pans are su table for use have been made since the instrument was as secondary containers. The protective calibrated and that the calibration is not covering should be replaced when it overdue. becomes excessively dirty or contaminated. If the user has a sample counting instru-There should be no evidence of mouth or ment used for wipe tests or urine samples, skin contact with objects used in the verify the efficiency used for calculating radioisotope work areas. Any signs of O RPR 50. LAB EVALUATION $ (1/90) - 5
t activity in samples and the user's under- be current and should be forwarded to the , standing of sample counting results. RSO as soon as the inventory item is used ' up. Sink disposals should be logged and i Waste Containers and storace Areas summarized on the inventory disposition form. All survey records should contain Verify that radioactive wastes are being the identification, efficiency and cali-segregated properly and placed in appro- bration date of the instrument used, priate containers. Wastes must be segre- Personnel surveys should indicate the name - gated by material categories, e.g. dry, of the individual. surveyed and, if any animals, scintillation vials, bulk contamination was found, the location on l liquids, etc. the body or on the clothing.- If records are not complete and up-to-date, bring Dry waste containing isotopes with half- this to the attention'of the user. ' lives of less than 65 days, and containing i no " radioactive material" labels or tape, Recommended Survey Frequency , should be segregated from other dry waste. As part of a routine audit .the frequency Scintillation vials containing only H-3, for routine lab evaluations . should: be C-14 and/or isotopes with half-lives less reviewed. The default frequency should than 65 days, in enviromnentally safe. be followed for at least the first year. (NHNT) fluors, and with rs " radioactive If contamination is found other than materials" labels or tape, should be rarely, the intervals , between surveys segregated from other vials, should be shortened. If contamination has l been well controlled, the survey interval Bulk liquids containing radioiodines should be lengthened. However, the inter-should be segregated from other isotopes, val shall not be increased by more than a factor of 2. Waste containers should be conspicuously labeled and should be in secondary con- REFERENCES tainers in locations that do not create unnecessary exposures to nearby personnel. U. S. Nuclear Regulatory Commission, Standants for Protectfon Against Sions and Labels Radiatfon, 10 CFR 20. The entrance to the lab should be posted Utah Department of Health, Standards for with 4 " CAUTION RADIOACTIVE MATERIAL" Frotection Against Radtation, Utah Radia-label. This label should show the iso- tion Control Rules, Chapter R447-15. topes used in the lab, the name of the ! responsible user and his or her office and I home phone numbers. 1 Personal Monitorino Observe and note whether dosimeters issued to lab occupants are being used. If they are not, bring this to the attention of the responsib'e user and the RSO. Records Review the records prepared and maintained by the users. All inventory forms should O RPR 50. LAB EVALUATIONS (1/90) - 6
ATTACWlENTS A LABORATORY EVALUATION CHECK LIST B OIRECT RADIATION SURVEY RESULTS C CONTAMINATION WIPE TEST RESULTS D RADI0 ISOTOPE LABORATORY EVALUATION REPORT E ' CAUTION - RADI0 ACTIVE MATERIALS' ' self-adhesive label used on entrances to radioisotope laboratories, with ' space for entering isotopes and the responsible user. i F. 'CLOSE SASH TO HERE FOR PROPER AIR FLOW" self-adhesive label for fume hood.
' NOTICE TO EMPLOYEES' (BRC-04), with added footnote and reduced in size, to be posted at each entrance to a radioisotope laboratory.
Other commercially available signs and labels used regularly in radioisotope laboratories:
" CAUTION - RADI0 ACTIVE MATERIALS" self-adhesive labels, 3"x4" or 5"x6",
used on cabinets, refrigerators, freezers etc. l l " CAUTION - RADIATION AREA", 8'XIO" ! paper or metal signs "N0 SM0 KING, EATING OR DRINKING IN THIS ROOM" l n-1 l U RPR 50. LAB [ VALUATIONS (1/90) - 7 1
, . - . . _ _ _ . . . _ - . _ _ _ _ - , , . .. ,_- __ _ _ . . ____________m_ _ ________
^
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/^'i RPR 50A. LABORATORY EVALUATION CHECK LIST U
- Responsible User: Sub-group: Date Building: _ Room (s): !
Reason: Pre-stert Contamination survey Routine audit $pecial Close-out ! Authorized Isotopes: Interval Inventory (Alls): Combined interval inventory: <1 ALI l-30 Alls >30 Alls Uses: Only In v/tro? If animals, what kind? i How many? Housed where? Storage & Security: Room security? Isotope storage in 7ockable cabinet? freezer? refrigerator? Fume Hood: Face velocity (fpm) _. Labeled? Date Contamination Control: Gloves & lab coats available and used? Trays, secondary containers, absorbent paper in use? No evidence of eating, smoking, mouth pipetting, etc.? Exposure Control: Distance / shielding used? Instruments: For surveys (type, S/N)
,e Appropriate for isotopes used? Operational test date
( For counting samples (type) Efficiency known? , Wastes: Segregated by categories and required containers? Short-lived isotopes in dry waste, NO LABELS? Other compactible dry wastes? Aqueous bulk liquids (1 or 2.5 gal.)? Organic bulk liquids (1 or 2.5 gal.)? Animals (kg/mo.); adequate freezer space? LS vials, quantities and types of fluor? Signs & Labels: Reom entrance posted? Notice to Employees posted? Refrigerator Freezer Sink Hood Waste containers Personal Monitoring: Body dosimeters issued? ._ In use? , Ring dosimeters issued? In use? Records: Radioisotope inventory, uses, dispositions Sink disposals Area surveys Personnel surveys Personnel changes? No Yes (if yes, attach RPR 1A or list of names and SS Nos.) Evaluation by: Survey Frequency: days Attachments: Direct survey data vipe test data survey map other RPR 50. LAB [ VALUATIONS (1/90) - 9
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i 4 O RPR 50. LAB EVALUATIONS (1/90) - 10 t
I r's/ l RPR 508. DIRECT RADIATION SURVEY RESULTS l
. User: _ Subgroup: Bldg / Room (s): !
Isotopes used: Critical isoto' pe: ALI: mci i Removable contamination limit (RCL): dpm dps nCi (circle one) per 100 cmI 59RVEY INSTRLMENT RESPONSE TO CRITICAL ISOTOPE Critical Expected Net Response Survey Instrument (s1 Died _J.gotone to 1 RCL _ (en= or cl>sl Bkgd. Point Area [1]. -[2]- ,3; . Calib. Rate Source Eff. . Wipe o{ Wipe of Make. Model. Ser. No. Date icom/cos) Eff._ Ratio Direct 100 cm 300 co' [1] RCL x Area Souret Efficiency (2) RCL x Point Source [f ficiency [3] 3 x RCL x Point $ource Eff. SURVEY RESULTS lA; Enter "0" for a direct measurement, "100" for a 100 cmI wipe or "300" for a 300 cmI wipe. ,
,8 Net count rate of meter with probe near the contaminated surf ace or the wipe f11ter.
;Ch If the count rate in [C] is greater than the expected response to 1 RCL, as Itsted above, enter the '
~ mult1ple of ihe RCL.
, [0] Inter exposure rate for any direct measurement not due to removable contamination.
[A] (B) [C] [D] Object, location in Room Arga Net Rate Multiple Exposure Raa ling or Name of Person Surveyed _ (cm ) (com/cos) of RCL (mrem /hr) 1 2 3' 4 5 6 7 _ 8 9 10 11 _ 12 13 _ 14 l L dp RPR 50. LAB [ VALUATIONS (1/90) - 11
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l r
)
^ RPR 500. CONTAMINATION WIPE TEST RESULTS - U User: Subgroup: Bldg /Roon(s): i Isotopes used: Critical isotope: _ -'ALI: mci Removable contamination limit (RCL): dpm dps nCi (ctrole one) per 100 co' l COUNTING INSTRUMDIT DATA Type: LSC Gamma Other Model, serial #: Program / Setup: Preset: minutes or counts Units of Readout: Counting Channel:- fil I21 I31
Background:
Critical isotope efficiency: Expected Net Response to 1 RCL: WIPE TEST COUNTING RESULTS lAt Enter "100" for a 100 cet wipe or "300" for a 300 cet ,gp,, Net response in each channel in same units as recorded above. >
' Bl' lC If primary channel response is greater than that expected for i RCL, enter the multiple of the RCL.
O d (A) Arga (B) Net Channel Response [C] Multiple . Ling Obiect or Location- (cm ) Ill I21 l31 of RCL 1 2 3 4 5 , 7 8 9 10 11 _ 12 13 14 / RPR 50. LAB [ VALUATIONS (1/90) - 13
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RPR 500, RADI0 ISOTOPE LABORATORY EVALUATION REPORT To: (tesponsible User) User #: Sub-group: Building: Room (s): Reason: contaminetton survey toutine audit $pecial/:ncident close out SLBetARY OF SIGNIFICANT SURVEY RESULTS: No removable contamination or significant exposure rates were found during this survey. We appreciate p w effort to keep it that way! Serious contamination (t] was found on: Contamination must be removed before work continues in the area. The contamination has been cleaned up. Unacceptable contamination (U) was found on: Until it is removed, it must be covered, isolated, labeled, etc. to prevent contact by individuals in the area. Low-level contamination (L) was found on: Although this contamination poses no undue risk to personnel, it indicates that improvement in handling techniques is possible and desirable. A screening bioassay is required promptly [P) (within 5 days) from each potentially exposed individual. A screening bioassay is required within the normal bioassay interval [B) from each potentially exposed individual. Significant exposure rates (>0.5 arem/ hour at 30 cm) were found at: Contaminated area categories: ,_Quantitles faultiples of RCL)
>100 -- 10-100 1 - <1 skin, hair or clothing in contact with skin ($P) ,,,,,,,($ . P) ,,,,,_[ $ . B) (U)
Readily accessible surfaces uncontrolled contact ,_($.P] ,,,,,(S . 8) (U) (t) Inaccessible surfaces 11mited contact potential (U) (U) (L) (L) > OBSERVATIONS ON PROCEDURES, EQUIPMENT, RECORDS, ETC. (cont.snt included if checked) contamination control Exposure control Survey instruments Area monitoring & records j' Personal surveys & records Veering of dostmeters Storage, security, signs and labels Vaste segregation Inventory and disposition records Surveyed by: Date: Attachments: check list with comments Measurements data Survey map other RPR 50. LAB [VALUAil0NS (1/90) - 15
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O _ Q' O CAUTION - RADIOACTIVE MATERIALS 4. MAJOR NUCLIDES: IN CASE OF EMERGENCY NOTIFY: UNIVERSITY POLICE: 7114 RADIATION SAFETY OFFICER: 6141 AMBULANCE, FIRE::9-911 l w
*is 2:
- eRc-04 UTAH DEPARTMENTOF HEALTH oees CUREAU OF RADIARON CON'IROL NOTICETO EMPLOYEES
- STANDARDS FOR PROHICTION AGAINST RADIABON;
NOUCES, INSTRUCTIONS AND REPORTS TO WORKERS; ! ] INSPd' CTIONS 3 i l In R447-15 of the Utah Radiation Cor*d Rules for fio Carmel of 2. N you work where persorwool monitoring le requwod. and if you l lonizing P--f -1,.i the Utah Deperiment of Heniet hee estatmohed request informeGon ort your r% esposures: standards for protection agamst radisson hazards. In R447-18 .
; of the Rules. Department has estat4shed eeetem provisions for s. Your employer must give you a weteen report uport
- the opeans of workers engaged in work under a rM metode;ne temiinallon of your _ ,"_,..._..
- .of your espesures, and
- license or radiaton machme regist ston.
! b. Your employer svimet advise you annumEy of your exposuse to t l YOUR EMPLOYER 3 RESPONS191UTY: r=4= man. t i
- Your employw is required to - INSPECTIONS- i
! 1. Apply the Departmorit of Heellh rules to work Irwolving sources A51iconomd or registered ac9vitse are subject to' , _ Li by i et radienen. represente#ves of tie Bureau et Rede6en Cor*ol. In adeteri, I
any wodier or ., - _ - _ '. _ ef wadiers who bonswee that there le -
- 2. Post or otherwese make aveseble to you a of the UtriY a vial-man of the Utah R=e=ma=i Ceseel Rules, or the terms of Radioson Cor*os R.4es, scon.es. and the empioy='s seense or . . wei rogard to . _ r > , -
! wh di apply no work you ars ==,eged in, and e their, werkng condtone in which Ihe washorie engaged, may request en 4 provisono to you. Inspecoon by sendng a nocoe of tie eseged vloisson to the ; Utah Bureev of Radleton Coreal The request must set forti the j , 3. Post no6co of violaton Irwolving radological wortong speculic grounds for tio nodoe, and must be signed by the wadier : conditone, proposed unposihan of dv5m T _ _, and orders. as the representeere of Wie workers. During inspectons, BRC
~
i inspectors mey cordw prweissy wei eny wormw and any worter mer YOUR RESPONSIBluTY AS AWORKER: to tie anoncort of the hopectors any past er present wNeh he besovos careenned to a eeused any vioiseen. ! You should femaiorize yourself witi those pro 6sione of Wie Utah l Redetion Coreal Rules, and the opereeng procedures wNdi** apply to MOUIRES: Sie work you are engsgod in. You should etsmerve 9 sir r. i _ for your own protecton and protection of your co.wodiers. Irwysires doeEng wies sie nietters euened abase een be sont to sie WHAT IS COVERED BY HEALTH DEPARintENT RULES AND OPERATING PROCEDURES: Utah Departraevit of Hoenh ITrvisonof ErwironmentalNo 19e , 1. Limits ori exposure to redeGon and r==#a=neve meterialin Buroes of R=4da's Central l restricted and unrestricted arees; P.O. Boir 19800 j 2. Measures to be tehon after accidental exposuse; Seit Lahe City,' Utah 94116 0000 i S. Pwsonnelmondoring, surveys and _ 4 Phone: ""_ _ - _ 530 4734 } 4. Cavison signe lebels, and seesty interh,k -, ', _ . :. After Hours "' ,-
- 538 4333 j 5. Exposure records and reports; j 0. Opeone for worliers regenSng BRC inspooGone; and
- 7. Related matters.
REPORTS ON YOUR RADIATION EXPOSUfME DESTORY POSTING REQUW4iRENT
- 1. The Utah Radia6on Cor*al Rules require tiet your "_,- COPIES OFTHIS NOTICE RE.fST BE POSTED M A SUFFICIENT
- give you a wntion N you receive an exposure in encoes NUMBER C'c PLACES M EVERY ESTAGUSHMENT WHERE -
set forth in tie rulee or in the noense. EMPLOYEES ARE ERFLOYED M ACTTVITIES UCEPISED OR of .any The limite for exposure to ...f_, a are set fortiin REGISTERED, PURSUANT TO R447-16 or R447-19. BY THE R447-15. This seeson speellies limite on exposure to redeten SUREAU OF RADIATION CONTROL TO PERMIT EMPLOYEES and esposure to concentrations of r==e===*e metodelin air WORKING H OR FREQUENTING ANY PORTION OF A RESTRtCTED i and water. AREA TO OBSERVE A COPY ON THE WAY TO OR FROM T>EilR i Pt. ACE OF EhrLOM. j l'or LICERSE CTIOli REstfLTS, EXP95WE RECOR95 SR STER isFemineffen. pasttehe rse.1 in .us, n .r% teen % t ..,, u ,,, _ _ _ . __=_.___m . _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
i l I 1 O LEAK TESTING OF SEALED SOURCES ! O, 1 PURPOSE 1 Any sealed source containing 100 pCi This procedure specifies criteria and or less of beta and/or gamma emitting l methocs for performing leak tests of material is exempt from leak testing. sealed sources in accordance with regula-tory requirements or license conditions. 2 Any sealed ' source containing.10 pCi or less of alpha emitting material is POLICY exempt from leak testing.e
.t .
o, i Sealed sources of radioactive material 3 An unused ~ sealed source in storage ] shall be tested for leakage at regular need not be testedt however, it must- ! intervals to verify the integrity of the be tested upon removal from storage l source containment and, in the unlikely before use. l event of failure, to detect the escape of l radioactive material before serious con- 4 Any sealed source for which a diff- i tamination of facilities, equipment or erent frequency for leak testing is l personnel occurs. The frequency of leak specified as a license condition shall tests, and the sensitivity of detection be tested in accordance .with that ) of escaping radioactivity, shall comply condition. ulations or license conditions ( with the reby the agency authorizing the specified possession of the source. Leak tests are
- O to be performed by qualified individuals REQUIRED DETECTION LIMITS V using procedures approved by the Radiation For most sealed sources leak tests must Safety Officer. Records of sealed source be capable of detecting 0.005 pCi of leak tests are maintained by the Radio- activity on the outside of the source logical Health Department, capsule or the source housing. For radium 226 sources, the test criterion is '
the detection of radon-222 leakage of DEFINITION 0.001 pCi in 24 hours. The basic ration-ale underlying these criteria is that a Sealed source means radioactive material non-leaking source will exhibit only that is permanently bonded or fixed in a background activity levels on leak tests, capsule or matrix designed to prevent whereas a source that is leaking enough release and dispersal of the radioactive to present a health hazard will be easily material under the most severe conditions identified at the required detection which are likely to be encountered in level. normal use and handling (UBRC rules). PROCEDURES FOR DRY-STORAGE SOURCES LEAK TEST FREQUENCY The most common method for detecting Each sealed source containing radioactive radioactivity leaking from a sealed source material other than tritium, with a half-- is to wipe the source with a soft-textured life greater than 30 days, and in any form paper and measure the removed activity, other than gas, shall be tested for leak- If the source activity is in the range of age or contamination prior to initial use mil 11 curies, the source capsule should be and at intervals not to exceed 6 months, wiped directly, if possible, for sources O with the following exceptions: in the multi-curie range of activity, the RPR 51. LEAK TE$11NG OF SEALED $0VRCEs (11/89) - 1
i wipes should be made on the accessible 2 As long as the concentration of radio-surfaces of the source housing, activity in water is less than that allowed for release to unrestricted areas. Leak tests of sources containing Co-57, it poses no risk to anyone, regardless of Co-60, Cs-137, etc. may be evaluated by the amount of activity that may have a either beta or gamma emissions. Since leaked from the source. The sources that ! proportional or GM detectors offer high gli into this category are the 5 curie detection efficiencies for beta particles, PuBeneutronstart-upsgceusedin beta counting and comparison with a beta - the TRIGA reactor and 3 Cf neutron emitting source is preferred. Leak tests sources used for sample irradiation. Both l of sources containing Pu, Am, Cf etc. are of these nuclides are alpha emitters, with ' best evaluated by alpha particle measure- concentration limits in water in unre-ments, stricted areas of 5 and 7 pCi/ml, respect-Diely. The simplest and most direct method for > converting instrument count rates to total As long as the sources remain in the water ) activity on a sample is to compare the tenu, the 6 month leak test will consist 1 count rate with that from a known refer- of measurement of the alpha activity in : ence source in approximately the same the tank water. A concentration exceeding i geometry. The reference source should be 5 pCi/mL will be used as a threshold for ! either the same nuclide as the source to further action. If the measured concen-be tested or a relatively long-lived tration exceeds 5 pCi/ml, the sources will nuclide with comparable emission energy, be removed from the tank, wiped immedi. The reference source activity should be ately and placed in dry storage. . If in the order of a few nanocuries (a few removed from the water tank for any other thousand dpm) and should be documented reason, the source (s) will also be wiped appropriately as a standard, immediately and placed in dry storage. After 72 hours of dry storage, the source The results of measurements of the activ- . If either the ity wiped from the source or its housing, will be wiped immediate (wet) or the again (dry) follow-up (dry) and the measurements of the reference 11,000 source, are to be recorded on the " SEALED wipe dpm),exhibits the source morewill than be0.005 remove pCi (d from SOURCE LEAK TEST RECORD" (Rra slA). If the service for further evaluation, removed activity exceeds 0.005 pC1, the source shall be removed from service and assumed to be defective until proven PROCEDURES FOR RADILM SOURCES l otherwise. A source that shows evidence l of leaking must also be reported to the Radium-226 sources are no longer in gen-licensing agency within 5 days, eral use. If any are encountered and require leak testing, the RSO will super-vise a test for leakage of the radon-222 PROCEDURES FOR SU8 MERGED SOURCES decay product. The method .used will l depend on the instrumentation available: The method used for leak testing sealed the two most appropriate test methods are sources that are normally stored and used the " charcoal sorption test" and the " jar in a large tank of water are based on two test". For leak tests of radium sources, reasonable assumptions: the activity to be detected is from.the i short-lived radon-222 decay products: 1 Any activity leakir.g from a source pha), Pb-214 and 81-214 (beta-- that is continually stored and used under gamma) Po 214 (alpha).Po-218 (and al ! water will be dispersed in the water and will not be readily detectable on a source In the " charcoal sorption test" the radium recently removed from the water, source is placed in a container with h RPR 51. LEAK TESTING OF SEALED s0URCEs (11/89) - 2
m a > proximately Ig of activated charcoal. days. The report must include a descri - O. lie container is sealed and allowed to stand for 24 hours after which the char-tion of the equipment used to perfom tie leak tests, the results obtained, and the coal is counted with a gamma spectrometry corrective action taken. system to detect the gamma rays of the r radon decay products. An appropriate source for ca11bration or comparison would REFERENCES be a vial or ampule containing approxi-mately 0.001 pCi of Ra-226. The vial must American National Standards Institute, be sealed airtight to assure the contain- Inc.,1973, American #ational Standanifer ment of all of the radon in equilibrium Leak-Testin Radfoactive Brachytherapy I with the radium. Sources,AN$1N44.2-1973, New York, NY. In the " jar test" the source is sealed for National Council on Radiation Protection 24 hours in a jar havingi a metal lid. and Measurements,1972 hotectfon Agafnst At the end of this period the lid is Radiation from Brachytberapy Sources, NCRP removed and the alpha activity on its Report No. 40 Washington, D.C. inner surface is measured. The count rate L from the jar lid would be compared with U.S. Nuclear Regulatory Commission,1974, an a1pha-emitter on a f1xed planchet, e.g. leak Testing RadfonctIve Brachytherapy Th 230. Since the first radon decay Sources, Regulatory Guide 6.1, Washington,
)roduct (Po-21M has only a 3-minute D.C.
1alf-life, the ple count should be made at least 15 ' s es, but no more than 30 Utah Department of Health, Bureau of L minutes, afu s emoving the lid from the Radiation Control, Utah Radiat ton Control jar. The ccepLrison of count rates will Rules. paragraphs R447-12-3(64), R447-a then be sufficiently accurate to meet the 15 107 and R447-32-59. intent of the leak test criterion. If leak testing of a radium source is recuired, the details of the method used anc the results will be documented as a special report. RECORDING Am REPORTING RESULTS Leak test data for radionuclides other than radium should be recorded on the
' SEALED SOURCE LEAK TEST RECORD" (RPR 51A) or equivalent. If the results of the leak test are negative, i.e. <0.005 pCi remov-able activity from a the source or its housing, the leak test record shall be filed with the previous survey records for that responsible user or device. The date of completion of the leak test shall be entered in the computer database to main-tain scheduling for future tests. in the event that a leaking source is detected, i.e. the test results exceed the detection criterion, a written report must be sub-mitted to the licensing agency within 5 RPR 51. LEAK it$1thG OF stAttD $0VRCis (11/89) - 3 summei -- um -
i RPR 51A. SEALED SOURCE LEAK TEST RECORD g; Responsible User: User #: Location: Source description: If irradiator, Device #: , Manufacturer: Serial No.: Nuclide: Activity: ____ pCi mci C1 (Circleone) , Analysis of liquid in which immersed. Sample volume, V - mL Counted as a liquid or as an evaporated solid l Acceptance criterion for famersion Ifquid - S pCf/L - 10 net alpha dpn/nl., ., Direct wipe of source capsule or accessible surface of housing l Acceptance criterion = 0.005 uCi on wipe. Counting instrument: Model: Ser. No.: Cal, date:
- Reference source identification: Nuclide:
Activity, A, - #Ci (preferably <0.005 901 or 10,000 dps) Background obtained from tap water or from instrument only i ( Result: Backaround Reference Samole Total counts recorded: Cb- C, - C, - Total count time (minutes): Tb- T, = T, - Countrate(counts / minute): R-3 R, = R, - Efficiency, E = (Rr R 3 )/A, - net ep##Ci, or cp#dpm Activity on wipe. A, - (R,-R3)/E = pC1, or Concentration in liquid, A, - (R,-R3 )/(E.V) - #C1/mL If the result is less than the acceptance criterion, the source is acceptable for use. If the result exceeds the acceptance criterion, the source is assumed to be leaking and must be repaired or disposed of as radioactive waste. Any sealed source that shows evidence of leaking must be reported in writing to the licensing agency (NRC or state) within 5 days. 1 Tested by: Date: O RPR $1. LCAK TESTING OF $(ALED $0VRCEs (11/89) - 4
i
. s
(] CALIBRATION AND USE OF PORTABLE SURVEY INSTRUMENTS PURPOSE a measurement system, to a standard source of radiation emissions (see the following This procedure provides basic criteria and specific definitions), methods for calibration of instruments used for radiation detection, measurements Detector Intrinsic Efficiency - the or surveys. fraction of nuclear particles or photons reaching a detector that interact with the detector in'such a POLICY way as to deposit ~ detectable energy. All instruments used for measuring ex- Measurement (Overall) Efficiency- the posure rates or determining the quantities fraction of the particles or photons of radioactivity present in samples or on emitted by a standard. source during surfaces (as contamination) are to be a fixed time period that are detected calibrated at least once a year. Calibra- by an instrument during the same time tions are to be performed by individuals interval. The overall measurement who meet the specified qualifications and efficiency includes the detector using sources and procedures that assure intrinsic efficiency, geomutry factor, compliance with federal and state regula- absorption corrections, scatter cor-tions and license conditions, rections, etc. Point-Source Efficiency - the fraction DEFINITIONS of the particles or photons emitted ( by a point source that are detected Calibration - the determination and cor- by the survey instrument. For practi-rection of the response of an instrument cal pur)oses, a point source is one relative to a series of known radiation with a ciameter much smaller than the values over the range of the instrument, detector diameter or the source-to-detector distance, whichever is Check Source (Reference Source) - a radio- l arger, active source (not necessarily calibrated) used to confirm the satisfactory operation Area-Source Efficiency - the fraction of an instrument, of the particles or photons emitted by an area source that are detected Contamination Detection - the direct by the survey instrument. For practi- ! detection of radioactivity present on cal purposes, an area source is one persons, objects, or surfaces; any numeri- with a diameter much larger than the cal values obtained by direct detection detector diameter or the source-to- l of contamination must always be regarded detector distance, whichever is as qualitative rather than quantitative, larger. Directional Resnonse - the variation in Enerav Dependence - a change in instrument response of an instrument to a radiation response with respect to the energy of l field of constant intensity as a result radiation at a constant exposure or ex-of changes in orientation of the instru- posure rate, ment with respect to the radiation source. Exposure (Rate) Measurement - the determ-Efficiency - a term used to describe (1) ination of the intensity of a radiation the intrinsic response of a specific field. Although the term " exposure"
\ detector, or (2) the overall response of technically applies only to measurements RPR s2. INSTRUMENT CAllBRAil0N & USE (11/89) - 1 l l
l
1 l of electromagnetic radiation by means of 2 Radioactivity measurement standardiza-ionization in air, it is used here also tion, monitoring techniques and ! in a general sense to refer to any measur- instruments, ement of field intensity, e.g. beta part-icles or neutrons, regardless of the 3 Mathematics and calculations pertinent detection mechanism, to the use and measurement of radio-Geometry Factor - the fraction of all photons or nuclear particles emitted from 4 Normal operating procedures and emerg-a radiation source that would be inter- ency procedures for all calibration cepted by a detector if not scattered or sources to be used, absorbed. For a point source, it is the .' ' solid angle subtended by a detector: Evidence of. ap>ropriate training L may! external to the source divided by 4w. include satisfac;ory completion of foma14 academic courses on the subjects listed ! Response Check - the verification of above, certification by the American Board proper operation of.a survey instrument of Health Physics cer cification in radio-by observing its response to a check logical physics by the American College j source, of Radiology, re istration by the National ' Registry of Ra lation Protection Tech-Standard Source - a radiation source nologists, or by specific training and exhibiting a disintegration, emission or examination administered by the R50, exposure rate certified by or traceable , to the U.S. National Bureau of Standards. I CALIBRATION SOURCES l Survey Instrument - a portable instrument used for direct detection and/or measure- Exposure rate:_ The 70 curie Cs-137 ment of radioactivity or radiation field "Radiac" calibrator is used for essen-intensities, tially all photon exposure-rate calibra-tions. (The complete designation of the Transfer Instrument - an instrument or unit is the Radiac Calibrator AN/UDM-1A. dosimeter exhibiting high precision which also sometimes referred to as the 'UIW.) has been calibrated against a standard The source provides three radiation field source, intensities by means of a rotatable source container and a movable aperture plug. Transfer Standard - a radiation source The calibration room permits a range of whose emission or exposure rate has been calibration distances from approximately j determined and documented by comparison 0.5 to 5.0 meters. An adjustable calibra- I with one or more standard sources, tion table rolls on a track to provide I arecise positioning of the instruments to 1 3e calibrated. Available exposure rates PERSONNEL QUALIFICATIONS range from approximately 0.5 mk/hr to nearly 100 R/hr; these exposure rates have Calibrations of instruments used for been verified many times with a var!ety ! radiation protection purposes are to be of transfer instruments, resulting in a performed by, or under the direct super- high degree of confidence in the radiation vision of, individuals who have had spe- field intensity, cific training on the following subjects: A 1 mci Cs-137 source (Amersham CDC.701, 1 Principles and practices of radiation X.7) is available for calibration of protection, exposure rates below 0.5 mR/hr. O RPR s2. INSTRUMENT CAllBRATION & U$t (11/89) - 2
'w
, 4o'5 y i
; Aloha activity: Alpha survey instruments ment screw on the meter movement is to be 1
are calibrated with a set of electro- used only for setting the mechanical zero deposi}ed Pu-239 gources ranging from point of the meter and never for adjusting
, 1.1x10 to 1.44x10 alpha particles per the electrical zero- response point.
minute emitted from the source surfaces Unless the meter has been heavily jarred or tampered with the mechanical zero (i.e. 2x emission), I should need no adjustment. Beta activity: Calibration sources con-taining various beta emitting nuclides are Directional and energy response charact-available for determining the energy eristics of survey instruments are normal-response of survey instruments. 0ther ly taken from manufacturers' specifica-sources containing various amounts of the tions. Calibrations are performed with same nuclide are avail able for determining the detector oriented toward the source the linearity of beta-detecting instru- in a' manner comparable to that 11n which l monts over several operating ranges, it is ordinarily used..!!onization chamber' I survey instruments with ? air-equivalent For testing linearity of ressons'e, the wall materials normally ~ exhibit little calibration sources consist of sets of 4 directional dependence throughout :the planchets containing Tc-99 with activities hemisphere directly facing the detector covering 4 orders of magnitude. The chamber. For calibration using a gamma sources are calibrated for 2x emission source of moderate to high energy (e.g. rates, i.e. beta particles per minute Cs-137), the ion chamber is positioned emitted from the source surfaces, with its axis perpendicular to'the primary radiation beam. This allows greater i For testing energy dependence of the precision in determining the distance from l instrument response, sets of sources the source to the effective center of the
, containing several nuclides, e.g. C-14, chamber.
C1-36, Sr-Y-90 and Pm-147, are available. Select calibration source configurations Neutron fluence rates: and distances to provide two exposure rates for each linear meter scale (or Two neutron sources are available for switch-selectable digital readout range) checking the response of neutron survey to be used. The two exposure rates should meters: be within the lower 1/3 and the upper 1/3 of the range. Select one exposure rate a 10 mci of Am-Be (=2x10' n/s) near the midpoint of each decade for an instrument with a logarithmic meter b 2 Ci of Pu-Be (uix10' n/s) readout (or non-switchable digital readout). Set the calibration. table at the appropriate distance and observe the CALIBRATION PROCEDURES background radiation reading of the instrument at that )osition. Be sure that Exnosure Rate Instruments the instrument reac ing is visible through the mirror to the source control position Before attempting to calibrate an instru- outside the calibration room. Leave the ment, verify that the instrument is not room, close the door, expose the source damaged, is not contaminated and that the and observe the instrument reading, batteries are in good condition, i.e. that Return the source to the safe position, the instrument responds satisfactorily to a check source. The mechanical zero of If the instrument response is within 110% the meter should be checked with the of the true exposure rate at the calibra-instrument off and resting or held in a tion distance, record the results and ( normal position. The mechanical adjust- proceed to the next exposure rate con-RPR s2. lksTRUMINT cALIBRAT!oh & U$t (11/89) - 3
4 I i figuration. If the instrument response should be verified each day the instrument < deviates by more than 105 from the true is used and recorded at least quarterly. . exposure rate, adjust the instrument For instruments calibrated for low ex- l according to the manufacturer's reconnend- posure rates (<0.5 mR/hr), a Coleman ations until it reads correctly. After lantern mantle is adequate asna check ' any instrument adjustments, previous source (... RPR srt). measurements may require recalibration as l the adjustn:ents may be interdependent. Contamination Surver Instruments Repeat the above procedure until all calibration points have been recorded on Instruments used to detect surface con- 1 the ' EXPOSURE RATE HETER CALIBRATION tamination are not calibrated in the same . RECORD" (RPR srA), sense as are exposure rate survey.instru- 1 ments. 'Instead of. adjusting the'instru2 ; For ionization chambers that are not ment response.to'a predetermined value, 1
. hermetically sealed, corrections for air the response to any density (temperature and barometric pres- recorded, ' as longas' .given itJis'source withinisthe simply ,
i sure) can be made in two ways. For instru- normal range for the instrument. Because ments to be used only on the University the absorption correction factors cannot campus, or at the same elevation, the be quantitatively . determined, ' direct preferred method is to adjust the instru- surveys for surface contamination 'are ment to read exposure rate directly at always qualitative by nature. However, this altitude. The instrument will then surface contamination measurements-give correct readings without the use of be reported as cctivity per 100 co'must and correction factors; this fact should be data must be provided for translating noted on the calibration record (RPR srA) instrument readings into appropriate and on the calibration sticker attached units, e.g. dpm per 100 cm,. to the instrument. The detection efficiency will vary tremen-W > The second method is to adjust the instru- dously with the tyoe of radiation and its i ment readings to those which would have energy. Thin window, gas-filled detect-been attained if the instrument had been ors, e.g. GM or proportional counters, calibrated at sea level. This method usually exhibit approximately the same requires a correction for barometric detection efficiency over the entire pressure and temperature, both at the time window area. The overall measurement l of calibration and at the time of use, efficiency should be expressed as a frac- l tion, representing the ratio of instrument If the instrument response is within 120%, response to source activity, e.g. counts but not within 110%, of the true exposure per disintegration, cpnVdpm or cps /dps, rate on all scales, the instrument may be used provided it is accompanied by a The point-source efficiency should be I calibration chart or graph that permits determined for each appropriate beta- l the correction of instrument readings to particle energy range. If the instrument I true exposure rates. If all readings are is used exclusively for measuring a single i within 110%, a calibration graph i s not nuclide, the calibration need be done only- ) required. Affix a green calibration label for that nuclide. Instruments used for (kPR Sr6) indicating the calibration date a Wide variety of nuclides - should be and results, calibrated for one nuclide in each beta- l particle energy range, e.g C-14 (low), Cl-Immediately after the instrument has been 36 (medium) and Sr-Y-90 (high). Since calibrated, the regular user of the in- each of these nuclides is not available strument should record its response to a in several sources with a range of convenient, long-lived check source. The activities, a single measurement is made ' instrument response to the check source for each nuclide, with the source at I cm l RPR Sr. INSTRUMENT CAtlBRAil0N & U$[ (11/89) - 4
1 I C
\
from the r, enter of the detector window is To convert instrument readings to surface i used to determine the Wint-source contamination values, _ both the point- ! efficiency. Table 1 lists a fn nuclides source and the area source efficiencies by energy grou)s and typical id.rument are needed. For direct measurements of measurement efficiencies for each energy surface contamination, the area-source group, efficiency is normally used. For measure-ment of the activity on a wipe sample with When using calibration sources that do not an area smaller than the area of the emit the detected ) article or photon with detector, the point-source efficiency every disintegrat< on, it is important to should be used, include the abundance of emissions in the . calculation of efficiency. The efficiency Alpha scintillation probes are generally
'should be calculated as the fraction of larger than thin window GM probes and may the appropriate emissions that are exhibit very significant cifferences in detected. To calculate the actual emis- detection efficiency at various positions sion rate, multiply the source disintegra- across the detector window. The efficien- 1 tion rate (e.g. dpm) by-the fractional cy for a' measurement at the center of the abundance of the detected emission. Note window may be considered to be.the point-in Table 1 that the emission abundances source efficiency, whereas the average of for some sources are less than 1 and some at least 5 measurements distributed over are greater than 1. the window area should be used as the area-source efficiency.
The linearity of response on all usable ranges of the instrument is determined Both the point-source and the area-source only for Tc-99. The calibration data efficiencies for radionuclides most often should be recorded on " CONTAMINATION encountered should be on the label METER POINT CALIBRATION RECORD" (RPR 628), attached to the instrument (RPR sty) or in some place of ready reference if estimates The area-source efficiency should be of quantitative surface contamination are determined for each beta source by averag- needed. l ing the efficiencies for 5 measurements of a point source at 13, 31, 40, 47 and Immediately after the instrument has been + 53 mm offset from the center of the win- calibrated, the regular user of the in-dow. Each of these positions represents strument should determine and record its the area weighted midpoint of an annulus response to a convenient, long-lived check of 20 cm' and together they represent the source. The instrument response to the measurement efficiency for a detector 1 check source should be verified each day cm,from the center of circular area of 100 before being used to make measurements, em . The contribution to the instrument Coleman lantern mantles are often used as reading from contamination outside of the check sources for contamination _ survey , 100 cm area is generally negligible, meters and low range exposure-rate meters. The results of the area-source response for reproducibility and record kee)ing, calibration should be recorded on the a combined holder and record of cieck-
" CONTAMINATION METER AREA CALIBRATION source readings is available for_ routine RECORD" (RPR stC). If the )oint-source use of these check sources (RPR s2[).
energy and linearity calibrat' on responses for an instrument are within 110% of those Neutron Instruments' obtained during the previous calibration, the area-source response need not be If a neutron survey instrument is to be repeated, but may be assumed to be the used to make dose-rate measurements, it same as before, must be calibrated by a qualified vendor, since the University has no calibrated O neutron source. The response may be RPR s!, INSTRUMENT CALIBRAi!0N & USE (11/89) - 5
checked after calibration by a vendor, and before using the instrument with either ! the 10 mci Am-Be source or the 2 Ci Pu-Be source. REFERDICES American National Standards Institute, Radia t ton Pro t ect ton Ins t rumen t a t f on Test and Calibration, ANSI N323-1978. International. Commission on ' Radiation < - c: . Units and Measurements, Determination 5 of Dose Equivalents Resulting fron ; n' External Radiation Sources,-llCRU Report 1 39, 1985. . Deterninstion of Dose ' Equivalents Result ing from External Radiat ton Sources
- Part 2, ICRU Report 43, 1988.
National Council on Radiation Protection and Heasurements, instrumentation and Monitoring Methods for Radiation Protection, NCRP Report No. 57, 1978.
- Calibration of Survey Instruments for the Assessment of ionizing Radiatton Fields and Radioactive Surface Contamina-tion, in preparation.
U.S. Nuclear Regulatory Commission,1980, Guide for the Preparation of App 1tcations for Medical Programs, Reg. Guide 10.8, Rev. 1, Appenc ix D, Calibration of Instruments. O RPR 52. INSTRUMENT CALIBRATION & USE (11/89) - 6
TABLE 1. TYPICAL INSTRUMENT RESPONSE _
~
, . nes te reist s ora, n.----- to aree s. ora Nuclide. E lAveraeel. "i_ ' - - - - Ameroortate Serwev Instruent Efficiency w rta Efficleecy cam /mC1/100 mE Very S.; -. ,, electren/ beta m itters j H-3, 6 kev. 100% TA PUG-7 w/TS-6 0.27 l Fe-55, 6 kev. 60% N1-63, 17 kev. 100% . i Low-energy beta emitters ' C-14, 50 kev, 100% TA TBM-3 or TBS-6 0.04 80 0.007 15 S-35, 50 kev. 100% Ca-85 70 key, 1001 Tc-99 101 kev. 100% TA TBM-3 or TBS-6 0.1 200 0.03 60
- Medi m-energy beta sunftters
- Cl-36, 279 kev. 981 TA TBM-3 or TBS-6 0.20 400 0.05 100 l Nip,_ -.., beta emitters Sr-Y-90 565 kev. 200% TA TBM-3 or TBS-6 0.22 450 0.05 100 P-32, 695 kev.100%
Low-energy photon emitters I-125, 27-35 kev. 147% TA TBS-6 (Ext. probe) I-129 29-40 kev. 78% j Nedim-energy photen emitters Co-57 122 kev. 861 136 kev. 11% Cr-51 320 kev. 101
- Nigh-energy photon emitters i Cs-137 662 kev. 85%
! Co-60 1.173 kev 100% l 1.332 kev. 100% i This table is to be expanded and revised as more data are accumulated. l
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RPR '2A, EXPOSURE RATE METER CALIBRATION RECORD USER: User #: Task f: Address: Phone: INSTRUMENT: Manufacturer: Model: Ser.f: Batteries: U Replaced U OK, not replaced Detector / Probe: Hermeti ally sealed 7 Yes No Temperatur< : - 'C Pressure, P = mm Hg Air Densit3 ~ tection Factor - 760.(273 + T)/295.P = (shoulci be 88 1.2) CALIBRATION SOURCE (S): 0 70 Ci Cs-137, AN/UDM-1A for gamma exposure rates >0.5 mR/hr O 1 mci Cs-137, Amersham CDC.701, X.7 for exposure rates <0.5 mR/hr U 10 mci Am-Be or 2 Ci Pu-Be for neutron response check O Other: RESULTS: Distance Exposure Rate Instrument Response (aR/hr. R/hr) Error as left (ca) (mR/hr. R/hr) icals As found As left Corrected .6 m If error on any scale to be used exceeds 20%, the instrument is unacceptable; affix RED LABEL. If error exceeds 10%, but is less than 20%, the instrument is acceptable ONLY IF a calibration chart must be attached to the instrument. If the error is within 10%, the instrument is acceptable without a calibration chart. If the fastrument is acceptable, affix a GREEN LABEL. O Calibrated by: Date: _ RPR 52. INSTRUMENT CAllBRATION & USE (11/89) - 9
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RPR 52, INSTRUMENT CAllBRATION & USE (11/89) - 10 l l l
i- - RPR.528. CONTAMINATION METER POINT CALIBRATION RECORD USER: User #: Task #: ___ Address: Phone: INSTRlMENT: Manufacturer: Model:- Serial #: Batteries replaced? Yes Ko Detector / Probe: Window t'@.knest mg/car Window area: cm' CALIBRATIC# W#dT(S): f.berli m PA-239 source sei, IDA: for alpha activity
. O Eberline Tc-99 source set (DNS-19), ID#: for beta linearity response O N.E.N. multiple nuclide set (NES-269), ID#: for beta energy response Other:
POIKT SOURCE CALIBRATION RESULTS: (Source at I cm from center of detector window) Detection Efficiency Instrument Retpsnig Cal. Point Scale Avg. Nuclide Activity Units Scale Units As Found As left (com/ dom) (com/ dom) O If detection efficiencies for the same nuclide on different scales are within 110% of each other. and the efficiencies for different energies are within the expected (nominal) range, affix a YELLOV LABEL to the instrument. Calibrated by: Date: RPR 52. INSTRUMENT CALIBRATION & USE (11/89) - 11
1 RPR 520.- CONTAMINATION METER AREA CALIBRATION' RECORD USER: User #: Task #: ! Address: Phone: INSTRLMENT: . Manufacturer: Model: Serial #: Batteries replaced? Yes No Detector / Probe:
, Window thickness: mg/cm' Window area: cm' CALIBRATIONSOURCE(S):
N.E.N. multiple nuclide set (NES-269), IDf: for beta energy response Other: AREA SOURCE CALIBRATION RESULTS: (To be done only after the point source calibration). The Eachcalibration hortrontalsource of fset is movedisinlocated position a planeat1 the cm center from, and parallel of an annulusto, with the detector an area window. of 20 cm2 Horiz, Meter Nuclide Activity Units Offset Scale Units Response Efficiency C-14 1.3 cm 3.1 cm 4.0 cm 4.7 cm 5.3 cm C-14 Area-source efficiency (average of the 5 above): Cl-36 1.3 cm _ 3.1 cm 4.0 cm 4.7 cm 5.3 cm C1-36 Area-source efficiency (average of the 5 above): i Sr-Y-90 1.3 cm 3.1 cm 4.0 cm 4.7 cm 5.3 cm Sr-Y-90 Area-source efficiency (average of the 5 above): Calibrated by: Date: O RPR 52. INSTRUMENT CALIBRATION & USE (11/89) - 12
..i s
RPR 52D.. SURVEY INSTRUMENT CALIBRATION LABELS- .] Reduce ~ to 1%" X 2%" (64%) before printing; permanent- self-adhesive labels. CUT-OF-SERVICE - RED LABEL, RPR 52R: OUT OF SERVICE DO NOT'USE UNTILLCALIBRATED CALL' RADIOLOGICAL HEALTH (EXT.- 6141) RPR52R(1/90) , 3 i CONTANINATION SURVEYS - YELLOW LABEL, RPR 52Y: USE ~ ONLY - FOR CONTANINATION AlO RELATIVE .;i EXPOSURE RATES. C-14 Cl-36 P-32
. Point Efficiency:
Area Efficiency: Effective Window Area:- cm' 1 By: Date: RPR52Y(1/90) EXPOSURE RATE SURVEYS - GREEN LABEL, RPR 52G: l [ ] WITHIN 105 ON ALL USABLE SCALES. . [ ] WITHIN 205; USE CALIBRATION GRAPH. SCALES NOT CALIBRATED OR USABLE: (Cs-137 calibration; consult instrument manual for response at other energies.) ' I By: Date: RPR526(1/90) l O 1 RPR 52. INSTRUMENT CALIBRATION & USE (11/89) - 13 l
=m -- . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
t i RPR.52E. C H EC K' .SOU RC E = R E S PONS E.- :
. ;- -l: :
Instrument reading should be recorded immediately after calibration and at least quarterly thereafter.
-Manufacturer Model Serial f Date Readina Date Readino
_(. 1 i k i i t fold here ,,,,,,,,,,,,,,, Instrument Check Source Property of I.
.1 l.
o l~ a / L ! Instructions: )? Cut a 1" diameter hole For replacement, call: l centered on the cross lines. Radiological Health Mount Coleman lantern mantle Ext. 6141 r f 's inside the folded card. ! Take reading with the detector . centered on the cross lines. RPR 52E (1/90) ! l.
~ -l RPR 52. INSTRUMENT CALIBRATION & USE (11/89) - 14 i
l q l J O a^oto^c'tve w^ste "^"^oe"e"' PURPOSE l "Compactible" waste means any nonputresc-This procedure specifies how radioactive ible, dry waste, e.g. paper, plastics,
. waste will be collected, segregated, glassware and metals, that does not con-stored, processed and packaged by the tain any compressed gases, pyrophoric or Radiological Health Department. The other hazardous materials, requirements for segregation, packaging and labeling also apply to other waste "LS media" means any mixture of solvents generators who offer prepackaged contain- and fluors used for liquid scintillation
- ers (drums) to the University to store counting. . "LS media" must.be segregated
-and ship in its role as a broker, for disposal,- based on the ' solvents and nuclides they:contain:
POLICY 1 "NMT" refers to nonhazardous, non-toxic, nonflammable solvents.- ' Radioactive wastes (radwastes) shall be collected, stored, packaged, shipped and 2 Flammable or toxic solvents, e.g. disposed of in accordance with all pert- . toluene, xylene, dioxane, - pseudocu-inent state and federal regulations. The mine, etc. shall not be used except' RSO shall 3repare and maintain procedures with special authorization ~ from. the
- t. for handl ng radwastes that will ensure Radiat<on Safety Officer..~
L the protection of the employees involved L in such duties and keep all radiation ,~L exposures ALARA. Specifications for SCHEDULING ABE) NOTIFICATION segregation and packaging of radwastes shall be based on specific regulations or Waste pickups for laboratories that gener-regulatory guidance, and include a record- ate significant quantities of wastes keeping system that will allow complete should be scheduled on a regular basis. tracking and accounting for all radwastes If the wastes cannot be picked up-at the shipped to a disposal site or disposed of scheduled time, notify the laboratory and . j locally, inform the user as to when the pickup will be made.- Request for unscheduled waste pickups will be made by phone to the DEFINITIONS Radiological Health office; a waste pickup request form (RPR 54A) Will be filled out
" Animal" waste means carcasses or parts and provided to the person collecting the of animals administered radioactive mater- wastes, ials; it also includes collected excreta and combustible bedding materials, e.g.
shavings or sawdust. PROTECTIVE CLOTHING Als DEVICES
" Aqueous" means a liquid that is soluble The minimum requirement for all phases of or readily dispersible in water and which waste handling is the wearing of a lab contains no chemicals classified as toxic coat and plastic or rubber gloves. Lab or hazardous; except for limits on radio- coats and gloves will not be worn to the activity, aqueous liquid wastes are those cafeteria or other public areas on or off which could be discarded to the sewer. the campus.
l p " Biological" waste means any biodegradable materials, including " animal" wastes, During packaging or disposal of liquid wastes, a plastic-lined lab coat and face l RPR 54. RADVASTE MANAGEMENT (11/89) - 1 l
shield shall be worn. A face shield or place the bottle in a plastic bag and safety glasses shall be worn while com- close the bag, tape the user-prepared pacting dry waste. For operations that waste label on bag, and place the baq and present greater risks of contamination, bottle in transfer drum. Remove g' oves overalls, shoe covers, aprons and respi- and place them in a dry waste container, rators are available. Check with the survey waste in transfer drum, and survey RSO if there are any questions regarding hands for contamination. Place an ap-conditions that may require the use of propriate (iodine or- noniodine) empty additional protective devices. non-contaminated waste bottle in secondary container. PICKUP OF WASTE Animal Waste: A thin-window GM survey meter'will be Before accepting animal carcasses, ascer-1taken on all waste pickup runs to survey tain that they have been frozen in
' waste , containers for contamination or packages exceeding 10 kg. - Procedures are excessive exposure levels'. Before taking the same as for dry waste except that any waste package, make sure that a radio- frozen animals should not be allowed to active waste tag (RPR 548) has been filled thaw. Provisions can be made in advance out properly and signed by the user. Do to pick up animals that have not been not take any waste that has not been treated with formalin if they are to be properly labeled, incinerated immediately.
Drv Waste: Liould Scintillation Vials: Remove the lid of the waste can and check Liquid scintillation vials may be picked the exposure rate. Visually check con- up and transported in plastic bags or the tents to ensure that only dry waste is in original cardboard trays. Verify that the container. Carefully remove the bag they are properly segregated and labeled
.from the waste container; inspect for according to the nuclides and' solvents protruding hypodermics needles, pipettes present.
or other objects that may rupture the bag or cause injuries; also, check for leak-age. Securely close the bag, then place TRANSPORT OF WASTES the bag in the plastic transfer drum or cart. Before leaving the lab, put a new The vehicle used for transporting wastes bag in the waste container with top folded from on-site generators to the radwaste over the rim and replace the container management facility must be placarded on lid. Remove gloves and put in dry waste all four sides with "RADI0 ACTIVE" placards and survey hands for contamination; survey whenever radioactive materials are present the transfer drum to determine the ex- in the vehicle. 'When no radioactive posure rate. materials are in the vehicle, the placards should be switched to the' " DRIVE SAFELY"- Linuld Waste: position. A wheeled cart or drum is used to transport waste packages of all types-Check the exposure rate from the contain- to the waste transport vehicle. Liquid er Lift the container out of its second- waste must be placed in secondary con-ary containment and inspect for leakage tainers in the vehicle for transportation; and solid objects. If solid objects are the transfer cart or drum normally serves found return container to secondary con- as the secondary container. Dry, biolog-tainment and inform lab personnel that the ical and frozen animal wastes can be objects must be removed before waste will transported in plastic bags or fiberboard be picked up. If no solids are observed, boxes. g RPR 54. RADWASTE MANAGEMENT (11/89) - 2
IL taining' only H-3 and C-14 will be set
,O .When unattended, the vehicle
. locked at all times when it contains will be kept aside for immediate incineration. All radioactive waste. All radioactive mater- animal wastes containing other nuclides ials will be removed from the vehicle at will be stored for radioactive decay as the end of each work day. If the vehicle long as practical prior to incineration, is involved in an- accident while trans- The activity of each nuclide present in porting radioactive waste, Campus Police the waste will be compared with the in-(Ext. 7944) and the RSO (Ext. 6141) must cineration limits prior to transporting be notified as soon as >ossible. The RSO wastes to the Vivarium for incineration, or his designee will cetermine if there If a biological waste package contains too is any contamination problem and supervise much activity to be incinerated it,will
^cleanup-1f necessary, be set aside-for packaging. c Liguid Scintillation Vialsi i-
- SORTING Ale SEGREGATION OF RADWASTE .
Representative vials . from each package Dry Wasta will be retrieved and counted using pro-l cedures outlinted in "RADI0 ACTIVITY MEAS-i Dry waste that consists strictly of p' aper UREMENTS" (RPR 53). The recults will; be l . products, i.e. containing no plastic, recorded on form RPR 548. Any vials that rubber, etc., and which contains no trans- contain toluene, xylene, = dioxane,. ior .
' uranic or. iodine nuclides, may be set . pseudocumene will be set aside for packag-
- aside for incineration; all Other dry, ing. Packages containing only H-3 and C-
- solid waste, e.g. mixed paper, plastics, 14 in an NHNT solvent at less .than 50 pipettes, glassware, etc. will be com- nCi/g will be placed in a dumpster .for .
pacted. disposal after comp 1etely obliterating or removing all radioactive material labels. Liould Waste Vials containing P-32 or' Cr-51 in NHNT fluors will be held for a period of ten Aqueous liquid wastes containing only H-3 half lives, then surveyed to assure that and C-14 will be disposed of to the sani- the external exposure rate is not above tary sewer through the disposal sink in background; these packages may then be the radwaste management facility. Aqueous disposed of in in a dumpster. as ordinary liquid wastes containing no transuranic trash. Vials containing any other 'nuc-or iodine nuclides will be held for decay lides in NHNT fluors will be segregated as long as practical, with the time to be for packaging. , determined by storage space available. < The activity of all nuclides to be dis-carded to the sanitary sewer shall be COMPACTION OF DRY WASTE determined, and the monthly average con-centrations and cumulative annual activity Put a 2-3 inches of absorbent in a non-- calculated, prior to each sewer disposal. specification drum lined with a 4' mil If the quantities are within the current plastic liner. Place the drum in' the limitations, the aqueous wastes will then compactor and make sure that the exhaust. be discarded to the sewer. All other fan is turned on. Place dry waste pack-liquid wastes will be segregated for ages in the drum and compact in accordance. packaging. with manufacturer's instructions; repeat until the drum is full. Seal the drum Biolocical Waste liner and secure the lid with lock ring. Survey and weigh the drum and mark in Biological wastes containing radium or accordance with procedures in "TRANSPORTA- l transuranics will be segregated for TION OF RADI0 ACTIVE MATERIALS" (RPR 56). O) ( special packaging. All animal wastes con-RPR 54. RADVASTE MANAGEMENT (11/89) - 3 1
k INCINERATION liquids, or the packages of vials, will be placed within the inner liner with. l Animal _and paper wastes will be inciner- enough absorbent material to completely ' ated at the Animal Resources Center pro- absorb twice the actual. volume of liquid vided that they are within the activity contained in the drum. Both liners will - , limits established to assure compliance be sealed and the drum lid will be closed ! with concentration limits in the inciner- with a locking ring. The drum will be ator effluent. Compliance with the in- weighed and labeled in accordance with cinerator effluent limits is verified by " TRANSPORTATION 0F RADIDACTIVE MATERI AL5"
- running the computer program for that (RPR 56).
purpose that is on the Radiological Health . - network. The program calculates the ratio Liould Wastes for Burial ,, of the average concentration in the stack . t: effluent to the regulatory concentration- Radiobiology liquid waste to beEsentito limit for each nuclide and then sums the the DOE site for disposal will be packaged ratios for all nuclides. The calculated ' in compliance with requirements found in concentrations are- based on the total the Hanford Radioactive Waste Packaging volume of. air exhausted since the last - manual. Liquids wastes to be 'sent direct-incineration ai,d on the assumption that ly to the commercial burial site will be all nuclides are volatile and are released solidified in accordance with instructions in the exhaust gas. in US Ecology license. Before absorbing, solidifying -or packaging liq uids. ' for Tne morning after the incineration, all burial, check the , latest Lrev1sions i of . ash will be removed and the fire box of license conditions or -regulations : to ' the incinerator will be vacuum cleaned, determine approved materials for absorp-During recovery of the ash, aersonnel will tion or solidification, wear a labcoat, gloves anc a dust mask. All ash will be disposed of as compactible If nonreclaimable liquid wastes are 'sent dry waste. All of the activity initially to another broker for solidification, in the wastes is conservatively assumed they should be packaged for transportation to be in the ash. the same as reclaimable liquids. Animal Wastes for Burial l PACKAGING OF RADWASTES All animal waste containing nuclides that ! Reclainable Liould Wastes have effluent concentration limits so low that incineration is not possible, will liquid waste comprised of organic solvents be packaged in conformance with the' site containing nuclides and activity concen- use requirements found in the DOE manual trations that are sufficiently low are or the US Ecology license, sent to a commercial reclaimer. Scintil-lation vials in this category shall be packaged in separate drums from bulk STORAGE OF PACKAGED RADWASTE solvents in cans or jugs. Both vials and bulk liquids will be packaged as low Sealed drums are to be placed on wooden specific activity (LSA) wastes as required pallets with drum covers.- ;The storage by the Department of Transportation (00T) . yard must be posted with' signs " CAUTION A nonspecification drum with a plastic - RADI0 ACTIVE MATERIALS" and kept locked liner containing 4 at all times. Waste shipments should be material (Pearlite,,6or inches of,") absorbent Paxlite will be scheduled often enough to prevent exces-used for liquid LSA wastes. A second sive accumulation of filled drums. If plastic liner will be placed inside the stored for decay and subsequent local first liner, and the cans or jugs of bulk disposal, waste drums only need to be g RPR 54. RADWASTE MANAGEMENT (11/89) - 4
ts 1 ' marked with the container number. If in REFERENCES l
\ storage awaiting shipment for disposal, they should be marked with all labels and U.S. Nuclear Regulatory Commission: 10 CFR markings required for shipment. 20.301-311 and 10 CFR 61; 10 CFR 71.
Utah Department of Health, Utah Radiation RECORDS Contro Rules, Requirements of General Applicability to Licensing of Radioactive The front copy of the waste tag (RPR lat) #aterial, R447-19.- , will be collected from each waste package. The initial disposition and date will be #anfortf Radioactive Solid Waste Packaging, entered and initialed on the' waste' tag . Storage, and Disposal Requirments,.WHC- ' which will then be entered in the RADSAFE EP-0063, Westinghouse Hanford " Comapny, computer data base. At the time of, final " ' 1988. ' " ' final disposition, 'the methodEand; date- . . .
~ : (when different from the initial disposi- State of Washington, Radioactive Materials tion) will be entered and initialed. License issued to US . Ecology, Inc.
The last copy of the waste tag will remain with the waste package if it is packaged- Utah radioactive material' - licenses in a drum for shipment.- The last copy of UT1800001' (broad license) and UT1800202 the waste tags for: incinerated materials- (waste broker's license).. will . be retained and packaged with the- . package-of ash. . The last copy of' the z
~
waste tags from released liquids or relea-- sed solids will be removed at'the time of disposal. Records will be kept that verify the , exempt concentration of H-3 and C-14 vials (r - 548). Radiation surveys of packages L L ot vials containing short-lived nuclides, e.g. P-32 and Cr-51, will also be record-ed on RPR 54B. Summaries of all radioactive waste dis-posals will be generated at least annually from the computer data base. These sum-maries will be filed with the annual reports prepared for the records of the Radiation Safety Committee. The computer data base will also be used to summarize i information required for waste shipment ! manifests, as described in " TRANSPORTATION l- 0F RADI0 ACTIVE-MATERIALS" (RPR 56).- O RPR 54. RADWASTE MANAGEMENT (11/89) - 5 t
k RPR 54A.. RADWASTE PICKUP- REQUEST ! This form is used by the Radiological. Health Department to record requests ~for radioactive waste pickup. i RPR 54A RADWASTE PICKUP. REQUEST , 2/88 Responsible User-
. . . . . a ~
Caller / contact- . Phone' '
~,
c.c , Bldg. , Room 7 Tvoe: Dry Vials - Animal Liq. ( G a l s . ) ': 1 2% 5 Iodine
^
MAKE SURE WdSTE' TAG IS READY 1 Comments on back Date By i O RPR 54. RADWASTE MANAGEMENT (11/89) - 6
- k O aea 548. saae's o^ta roa '.s. via's i
The following 4"x6" card is used for recording counting data from ! representative samples of liquid scintillation vials. RPR 548 SAMPLE DATA FOR L.S. VIALS 5/89 F Check one or-both categories: Pkg. ID # R 0 Isotopes with half life < 65 days , l[] Sampling' not require unless contains H-3; or C-14. N 1 Held for 10 half lives? (Y) (N)
<T l(( H-3 and/or C-14,: sampling required.-(See back) l If H-3 and.C-14-only, no other nuclides detecte d..
H-3 + C-14 < 50 nci/g Package exposure rate at surface mR/hr Check only one category: l[l "NHNT" L'.S. Vials; Released Solid Requirements for package release have been met.- l~l Requirements for package release are not met. O Package placed in Container # . Date Initial i O RPR 54. RADWASTE MANAGEMENT (11/89) - 7
.,; r ,
4 , , i . RPR 54B (BACK) .- (. l (H-3) (C-14) (Other) l 1 l EL. L.b1 Ch2. Chl- l 5 l 1. l
- l. '2 l-
- l. 3 'l. -
ll t; - l 4 I 5 I: , l 6 -lL
;- 7 .
.i:
g ' l- 8- l .- l l 9 'l= l 10 _l l:Bkg. l ! l Avg. Net epm , l' . I l-h.- l Eff_. .l l Net nci- cpm /(Eff.x'2200) l [ l ' l l l l Vial size: Std - .15 g: /vi al l i l Mini = 5 g/ vial. l p' l Avg. nCi/g (Ch1 + Ch2 must be <50) l
.i l .l _
l l Ch3 must be zerol- l l: L O' RPR 54. RADWASTE MANAGEMENT (11/89) - 8 l- \
$ RPR 54C. RADWASTE CONTAINER DATA The followinc 4"x6" card is to be completed for every container (drum) of radioactive waste at the time it is packaged. The card is to be delivered to the Radiological Health office before the container is listed for shipment.
RPR 54C CONTAINER DATA 2/88 F R Container # (yr. prefix; four digits) 0 Container Size: 55 Gal. or N Container Type: Spec. 7A or NonSpec. T Weight: ,_ lbs. Weight recorded on Drum? Y or N Physical form: Solid Vi al s Bulk Liquids Waste Description Code (see back of card): Solidified or Absorbent Media Code (see back): Contents / Chemical Form: Contents Cateaory: LSA Flam. Liq., Bulk lSAF Type A Quantity" LSA Vials'SA Limited Quantity'0 LSA Dry Solids tsA Special Form sr Other 0THER
Description:
9 Preliminary Survev: Date: By: Meter Used: Calib. Date: Exp Rate (mR/hr.) 9 surface: 9 1 meter: O RPR 54. RADWASTE MANAGEMENT (11/89) - 9 1
?
o o ; o RPR-54C (back) l Waste-Description Codes: ! B- 2. Dry Solid- '
- 10. Absorbed Aqueous Liquid.
A 3. Solidified Liquid 11. Absorbed Organic Liquid C 4. Biological 12.. Scintillation or Organic K. Liquid in Vials in= Absorbent
- 7. Filter Media 13. Aqueous Liquid in' Vials in Absorbent . .
.8. Dewatered Resins 14. Animal Carcasses in1 Absorbent. ~!
- 9. Solidified Resins .99. Other Solidified or Absorbent Media Codes: ,,
- 2. Speedil-Ory 10. Zonolite, Grades 2,3,41
- 3. Celatom~(MP-78) 11. Dow Media ,
- 4. Floor Dry / Super Fine.12. Cement '
- 5. Hi Dri 13. Asphalt t Dr 15. to l 8.= Safe-T-Sorb 16..Krolite
- 99. Other O
l i G RPR 54. RADWASTE MANAGEMENT (11/89) - 10
- a + +.a-. - .u a ..n- a--a - ams . - ~ . a... ea.. - aa r ~
,. 3 RPR 54D. RADI0 ACTIVE WASTE MANIFEST AND RECEIPT i CONSIGNEE: RADIOLOGICAL HEALTH DEPARTMENT, UNIVERSITY OF UTAH CONSIGNOR:
(Waste Generator's Organization) This form is to be used for local transportation of radioactive wastes to the University of Utah. See the next page (or reverse side) for definitions and limitations. .The ' waste GENERATOR must complete this form (in addition to the required PACKAGE labels) before transfer of wastes. Keep a copy and ATTACH THE ORIGINAL TO THE PACKAGE DURING TRANSPORT. The radioactive wastes listed below were transferred to thef Universits ofl Utah?in-accordance with License No. UT1800202: s P Form: Limited Combined 'um s Package Solid or Activities Quantity 'less than the ID No. Liouid Nuclides ,(mC1) (mC1) Limited Quant'.? j L O V Packages that contain less than the Limited Quantity must bear the Limited Q'uantity label, but may be transported in any vehicle. Packages that contain more than a Limited Quantity should be listed on a separate manifest, labeled as " Radioactive Material - LSA, UN2912" and must be transported in an exclusive use vehicle bearing RADI0 ACTIVE PLACARDS on all four sides. For transport, contact the Broker (581-6141). Cross out one of the followina statements:
> All packages conform to the conditions and limitations specified in 49 CFR 173.421 for excepted radioactive material - LIMITED QUANTITY, N.O.S., UN2910.
> Packages contain RADI0 ACTIVE MATERIALS - LSA, UN2912.
This is to certify that the above-named materials are properly classified, described, packaged, marked and labeled, and are in proper condition for transportation according to the applicable regulations of the Department of Transportation. For the GENERATOR / CONSIGN 0R: Accepted under the conditions stated in the RADWASTE SERVICE AGREEMENT between the University of Utah and the GENERATOR. For the University of Utah: Date: _ i-RPR 54. RADWAsTE MANAGEMENT (11/89) - 11 l
RPR540(continued) Low-level radioactive wastes are not " hazardous wastes" by EPA or DOT definition. ' Limited Ouantities: Packages that are exempt from specific packaging and labeling requirements because they contain no more than the following: Solids: 0.001 A1 or A 2, as appropriate Liquids: 0.0001 A g-Gases: 0.001 A or A , as appropriate 2 Additionallimiksfortritiatedwater,tritiumgasand'for.instrumentsand ij devices are provided in 49 CFR 173.423.
-L Limited Ouantities for Selected Radionuclides: (49CFR173.435)'
-Quantities in millicuries i lhtGlidit Solids Liouids H-3 20 2 C-14 60 6 ,'
D P-32 30 3 S-35 60 6 t Co-57 90 9 , I-125 70 7 For Limited Quantities of other radionuclides, or any other questions regarding ' packaging, labeling or transporting of radioactive wastes, call 581-6141. Label Reauired for limited Quantity Packaoe:
"This package conforms to the conditions and limitations specified in 49 CFR 173;421 for excepted radioactive material - LINITED QUANTITY, N.O.S., UN2910." 4 Low Specific Activity (LSA): The following materials are classified as LSA:
.U or Th ores and concentrates Unirradiated natural U or Th, or depleted U Tritiated oxide in aqueous solutions not exceeding.5 mci /mL .
Materials in-which the radioactivity is essentially uniformly distributed, , and with a concentration not exceeding: 1 0.0001 mci /g if A is not more than 0.05 Ct. ' O.005 mci /g if A,2is between 0.05 Ci and 1 C1. 0.3 mci /g if A2 is more than 1 C1. Labels- (2) Reouired for LSA Packaoe:
"RADI0 ACTIVE MATERIALS - LSA, UN2912" O
RPR 54, RADWASTE MANAGEMENT (11/89) - 12
TRANSPORTATION OF RADI0 ACTIVE MATERIAL PURPOSE 3 U.S. Postal Service Publication #6, Radioactive Materials, December 1975. This procedure identifies pertinent regu-lations and provides guidelines and check 4 U.S. Environmental Protection Agency lists to assure compliance with federal (EPA) regulations, 40 CFR, Parts 260 - and state regulations during transporta- 262, tion of radioactive materials on or off University property and when preparing DEFINITIONS (from 49 CFR) . radioactive materials for shipment tc - I another organization or individual. Carao loss Reoortina System and Procedures fl01-4.51:L FOLICY . . . .. .~ .
.L,..m .~
Bill of Ladina: ~ The document by which a Radioactive materials of any kind may be carrier acknowledges receipt of. freight- 1 y transported on public roads on or off and contracts for its carriage. , University property only if packaged and 1abeled in compliance with U.S. Department Manifest: A tabulation of waybills oli the of Transportation (DOT) regulations. loaded vehicle. (For hazardous wastes Radioactive materials may be shipped from as defined in 40 CFR 261,:the manifest is the University to another organization or EPA form 8700-22 and 8700-22A,tif neces-individual only after verification by the sary.) ; Radiation Safety Officer that all trans- . . . fer, packaging, labeling and transporta- llaybill: A document prepared from a " bill tion requirements have been met, of lading" that accompanies shipment from origin to destination;J also -known7 as To tssure that all requirements for ship- ' freight bill". . ment are met, and that _ appropriate records are maintained, a written authorization Definitions and Abbreviations I171.81: form and one or more check lists must be prepared by the individual responsible' for Qttlan A person engaged -in the trans-the shi) ment and approved by the RSO portation of passengers or property by:. before t1e shipment is made. The instruc- (1) Land or water, as a comen, contract, tions and forms for various applications or private carrie, or (2) Civil aircraft, are contained in Radiation Procedures and Records related to those applications. Desianated Facility: A hazardous waste treatment, storage, or disposal facility REFERENCES that has been designated on the manifest by the generator. 1 U.S. Department of Transportation
-(DOT) regulations, 49 CFR, Parts 171 Hazardous Material: A substance or mater-through 178. Unless otherwise speci- ial which has been determined by the fied, all references throughout this Secretary of Transportation to be capable procedure are to DOT regulations and of posing an unreasonable risk to health, the "49 CFR" designation may be omit- safety, and property when transported in ted, commerce, and which has been so desig-nated. (All radioactive materials except 2 U.S. Nuclear Regulatory Commission homogeneous substances with specific (NRC) regulations,10 CFR, Parts 61 activities of less than 2 nC1/g are con-and 71. sidered hazardous materials.)
O RPR 55. RADIDACTIVE MATERIAL TRANSPORT (11/89) - 1
I i Hazartlous Waste: Hazardous wastes are Shinoine Paner: A shipping' order, bill ) - defined by the EPA in 40 CFR 161.3. ~ For of lading,serving manifest or other transportation purposes, a hazardous waste document a similar purposeshipping and gJ is any material that is subject to the containing the information required by Hazardous Waste Manifest Requirements of '172.202, 172.203 and 172.204. l the EPA specified in 40 CFR 262. Suboart 0 - Flammable. Combustible. and 40 CFR 262.11 states that a person who Pyrochoric Materials generates a solid waste should first determine if the waste is excluded from Fl%1e Liouid: Any liquid having a regulation. Section 40 CFR 261.4, flash point below 100 degrees farenheit. Exclusions, states: [173.115(a))
"(a) The following are not solid wastes '
for purpose of'this part:" Under (a), Limited Duantities: Flammable liquids in only one subparagraph is relevant: individual containers having a capacity
"(4) Source, special nuclear or by- of not over 1 : pint, ; packed in strong product material - as defined by the outside containers, are exempt from the Atomic Energy Act of 1954, as amended, the labeling and specification packaging 42 U.S.C._2011 g.t i m " requirements.[173.118(a)]
10 CFR 20.3(a)(3) defines byproduct mater- Eombustible Lieutd1 Any liquid with a ial as any radioactive material (except flash point of 100 to 200 degrees faren-special nuclear material) yielded in or heit. [173.115(b)] made radioactive by exposure to the radia-tion incident to the process of producing Suboart I - Radioactive Materials - Defin-or utilizing special nuclear material. itions f173.4031: 10 CFR 61.2 states: " Waste" means those low-level radioactive wastes containing source, special nuclear, or byproduct Contamination Limits: Removable contamin-ation on the surfaces-of any package or h vehicle shall,be determined by wiping an material that are acceptable (or disposal area of 300 cm ; the measured activity on in a land disposal facility, the wipe shall not exceed 3 nci (6600 dpm) of beta emitters, natural uranium or (According to these definitions, low- thorium, or 0.3 nCi (660 dpm) for other level radioactive *.astes are not "haz- alpha emitters. (173.443) ardous wastes" by EPA definition, although the definitions do not include acceler- Tyne A Quantities: A is the maximum 3 ator-produced or naturally-occurring activity of "special form" material and radioactive materials. To avoid confus- A2 is the maximum activity for any other ion, the term " waste" should not be used radioactive material that may be shipped on the manifest or shipping papers for in a Type A sackage. Values of A1 and A low-level radioactive wastes.) for selectec radionuclides are listed in, 173.435 or Table 1 of this procedure. Limited Quantity: The maximum amount of a hazardous material for which there is Exclusive Use: The sole use of a con-a specific labeling and packaging excep- veyance by a single consignor, and for tion. which all initial, intermediate, and final loading and unloading are carried out in N.O.S. or n.o.s.: Not otherwise speci- accordance with the direction of the fled, consignor or consignee. Any loading or unloading must be performed by personnel DBH1 Other Regulated Materials. having radiological training and resources appropriate for safe handling of the g RPR 55. RADIDACTIVE MATERIAL TRANSPORT (11/89) - 2
/3 consignment. Specific instructions for Radioactive Material: Any material with [
V maintenance of exclusive use shipment
, controls must be issued in writing and a specific activity greater than 2 nci/g.
[173.403(y)] (By this definition, any i included with the shipping paper informa- relatively homogeneous material with a i tion provided to the carrier by the con- concentration, or specific activity, of l signor.- less than 2 nC1/g is considered non-radio- , active for transport purposes only.) l FissileMaterial: Any material containing one or more of the fissile nuclides Pu- Specific Activity: For a radionuclide, 238, Pu-239, Pu-241, U-233 and U 235. For s)ecific activity means the ~ activity of controls see 173.455; for exclusions see tle radionuclide perg uniti mass.'of the 173.453. nuclide. . ForJ aimaterial s in which; the radionuclide D is1 essentially nuniformlyJ Hlahway Route Controlled Quantity:' - distributed, . specific activity.means' the ' A single package which contains 3,000 times activity perl unit mass'of the: material, the relevant A or A quantity or 30,000 3
.. .'. D ,
t curies, whichever is,least.-.~ Any package Transport Index: T A dimensionless ' number . ! containing a highway ~ route controlled derived from.the maximum exposure rate at-quantity must bear a " Radioactive 1 meter from the package surface expressed Yellow-III" label regardless of external in mre#hr and rounded : upward ; to 1the exposure rates. Any vehicle carrying nearest 0.1 mrem /hr. highway route controlled quantity must
' display the ' Radioactive" placard. Tyne A Packane: One de$igned to retain the integrity of containment and shielding l Limited Quantities _: Packages that are under norma 1Jconditions=of transport as exempt from specific packaging and label- demonstrated by tests specified in 173.465 l ing requirements because they contain no and 173.466. Standard requirements for O more than the following:
Solids: 0.001 A or A t i all packages are contained in 173.24 and : the specifications for Type A packages are Liquids: 0.0001 A 2 defined by Specification 7A.in 178.350. Gases: 0.001 A or A 3 Additional limits for tritiated water, Tvoe B Packane: . Meets special test .re-tritium gas and for instruments and quirements for normal and hypothetical devices are provided in 173.423. accident conditions of transport as speci-fled in 10 CFR 71.51, 71 and 73. Any 4 Low Specific Activity (LSA): The follow- quantity of radioactive material exceeding -' ing materials are classified as LSA: the A or A 2quantities is a Type B.quan-U or Th ores and concentrates tity 3 Unirradiated natural U or Th Depleted U LOCAL TRANSPORTATION PROCEDURES Tritiated oxide in aqueous solutions not exceeding 5 mci /mL Transportation authorization: Materials in which the radioactivity is essentially uniformly distributed, Transportation of radioactive materials and with a concentration not exceed- between individuals or facilities within ing: the University is permitted only if auth-0.0001 mci /g if Ag is not more than orized in advance by the RSO. The Receiv-0.05 Ci. ing Department is authorized to deliver 0.005 mci /g if A2 is between 0.05 unopened packages of radioactive materials C1 and 1 C1. after they have been checked by the RSO. 0.3 mC1/g if A2 is more than 1 C1. O RPR 55. RAD 10 ACTIVE MATERIAL TRANSPORT (11/89) - 3
L 9tiainal' onckanes from vendors: nosis or treatment. Detailed regulations . for air shipments of materials requiring ! Packages containing radioactive materials Yellow-II or Yellow-III labels are con-received by common carrier may be trans- tained in 175.700, ported in the original, unopened con-l tainer. If the package has been opened, SHIPPING PROCEDURES l care must be taken to assure that it has l been resealed and that no contamination 1 Before any radioactive material other is present before it can be reused, than wastes may be shipped from .the University, the responnble user must Non-spqx:ification containers: complete the " CONSIGNEE IDENTIFICATION AND AUTHORIZATION" form (RPR ssio)iand Many of the radioactive materials that obtain authorization: from thelR$0.E are transported locally,: such as radio . Prior to shipment, the RSO must verify; active wastes, meet the - definitions ~ of the license"statusLand'shippingiad-i Limited -Quantities ' t or Low Specific dress of the consignee'.* " ^ g Activity. For these materials, non-speci- Ei. W fication containers may be used provided 2 As part of the preparation for!shi ? that they , are strong and tight. For ment, the appropriate check list ( ); Limited Quantities, the transport vehicle must be completed'and approved by t e'~ does not require placarding; however, RSO. The contents of the package and-placarding is required for LSA materials the proposed method of shipment will in an exclusive-use vehicle. Arrangements determine which check list:is to be for transport of any radioactive material used. If there is no standard check on public roads must be made in advance list for a proposed material or ship-with the~RSO. ment method, the RSO will supervise the preparations for the shipment and Transfer and Shinnent Records: the appropriate documentation. i Each transfer of radioactive material, CHECKLISTS (attached) even locally, must be accompanied by an appropriate record which also serves as RPR 551D. CONSIGNEE IDENTIFICATION AND 0 shipping document. Transfers of radio- AUTHORIZATION FOR SHIPMENT OF RADI0 ACTIVE a:tive materials between the University MATERIAL and the Veterr.ns Administration Medical Center are recorded on form "UV-VA RADIO- RPR 55A. C0t990N CARRIER SHIPMENT OF TYPE ACTIVE MATERIAL TRANSFER" (RPR 136). A RADI0 ACTIVE MATERIAL Shipments of limited quantities of radio- ' isotopes are recorded on "RADI0IS0 TOPE RPR 55RW. COMMON CARRIER SHIPMENT OF LIMITED' QUANTITY CHECK . LIST" (RPR 14Lo). RADWASTE Transfers of radioactive wastes fromlocal generators to the University are recorded RPR 55LSA. EXCLUSIVE-USE VEHICLE SHIPMENT on " RECEIPT FOR RADI0 ACTIVE WASTES" (RPR OF LSA RADWASTE sso). All other transfers or shipments are to be recorded on the forms attached RPR 55EUV. EXCLUSIVE USE VEHICLE SURVEY to this procedure. AND DRIVER'S INSTRUCTIONS AIRBORNE SHIPMENTS The only radioactive materials that may be transported on a passenger-carrying aircraft are those intended for use in, or incident to, research or medical diag- g RPR 55. RADIDACTIVE MATERIAL TRANSPORT (11/89) - 4
4 l Table 1. DDT TYPE A QUANTITIES from 173.435 except as indicated by *. '; Nuclide A1 (Ci) A2 (C1) Nuclide Al (Ci) A2 (C1) . H-3 20. 20. Be-7 300. 300. C-14 1000, 60. Na-22 8. 8. Na-24 5. 5. -P-32 30, 30. S-35 1000, 60. C1-36 300. 10. Ca-45 1000, 25. Sc-46 8.- 8. Cr-51 600. 600. Mn 54 20. 20. Fe-55 1000.. 1000. .Fe-59 10. 10.
'Co-60. 7. J7.
Co-57 90. . 90.- Ni-63 1000. 100;- l Zn-65~ ~ 30. - ' 30. Ga-67' 100. -100. Ga-68 .20. ~ 20.
'Se-75 40.c ' 40.
Ge-68 20. 10. Kr-85 5: 5. Rb-86 30. "30 - Sr-85 30. - 30. - Sr-90 10 1 , . 0.4 Nb-95 20. - 20. Mo-99 100. 20/ Tc-99 1000. 25. Tc-99m .100.4 .100.- Ru-103 30. 25. Ru-106 10. 7. Cd-109- 1000. 70. In-111 30. 2 5.~ In-113m 60. 60. Sn-ll3- 60. : '60. I-123 50. 50. I-125 1000. -70. 1-129 1000. 2. 1-131 40. 10. (* ' Xe-133 5. 5. Ba-133 40. - 30. 10. Cs-134 10. 10. Cs-137 10. l Ce-139 100. 100. Ce-141 300. 25. Pm-147 1000.-- 25. Gd-153 200. 100. Ir-192 20. 10. Au-198 40. 20. Hg-197 200. 200. Hg-203 80. 25. l -T1-201 200. 200. T1-204 300. 10. l Pb-210 100, 0.2 Po-210 200. 0.2 Ra-223 50, 0.2 Ra-224 6. 0.5 l Ra-226 10. 0.05 Ra-228 10.. 0.05 Ac-227 1000. 0.003 Ac-228 10. 4. l Th-227 200. 0.2 Th-228 6. 0.008 Th-229* 2. 0.002 Th-230- 3. . 0.003 Th-231 1000. 25. Th-232 Unlimited Th-234 10. 10. Th-natural Unlimited Pa-231 2. 0.002 U-232 30. 0.03 U-233 100, 0.1 U-234 100,- 0.1 U-235 100, 0.2 U-238 Unlimited U-natural Unlimited Np-237 5. 0.005 Pu-238 3. 0.003 Pu-239 2. 0.002 Pu-241 1000. 0.1 Pu-242 3. 0.003 Am-241 8. 0.008 cm 243 9. 0.009 Cm-244 10. 0.01 Bk-249 1000. 1. Cf-249 2. 0.002 Cf-252 2. 0.009 l
- Calculated per 173.433 RPR 55. RADIDACTIVE MATERIAL TRANSPORT (11/89) - 5
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5 1 RPR 5510. CONSIGNEE IDENTIFICATION AND AUTHORIZATION FOR RADI0 ACTIVE MATERIAL SHIPMENT-Instructions: This form is to be completed for shipments of any radioactive material other than limited quantities or wastes, to any location other than to the VAMC. The individual desiring authorization to ship a radioactive material shall complete this form and the appropriate check lists. The completed check lists shall be submitted to, approved and retained by the RSO. Consianor (University of Utah Resoonsible User): Name: Phone:; Department: Address: Consianee fIndividual and Omanization): . Name: ' Phone:
~
Address: Authorization: Consignee's License f: Expiration Datei Consignee's RSO: Phone: License copy on file? or other verification: Packane Contents and Hazardous Material Classification: Initials Contents Radionuclide(s): Activities: Other Hazardous Materials: Tvoe A Packaoe limits Sealed source or metal? (Y/N) A3 Limit: . Ci Other solid or liquid? (Y/N) A2 Limit: Ci O RPR 55. RAD 10ACilVE MATERI AL TRANSPORT (11/89) - 7
; , 9' .
Limited Duantity Criteria Initials-g Less than 10~ 8A for special form materials. 3 W > Tritiated water? (Y/N) Concentration: C1/L Less than total activity specified in 173.423. Other solid or liquid? (Y/N) A2 Limit: If solid, less than 10'8 Ar-If liquid, less _than 10 A .g '(173.'423] Less than 15 grams U-235. [173.42i] - If limited quantity, use RPR 14LQ! ' Low Snecific Activity Criteria' , ,,, [, , Unirradiated nattiral or dep1'eted uranium or natural:l thorium. > Tritiatedwaterinaconcentrationlessthan5mC1/mL'. Less than 0.0001 mC1/g if A, is not more than 0.05 Ci. Less than 0.005 mci /g if A, is between 0.05 Ci and 1 C1. Less than 0.3 mC1/g if Ag is more than 1 C1.
~
Externally contaminated non-ragioactive material if' contamination 1evel, averaged over no more than 1 m , does not exceed: [49CFR~173.403(n)) 0.0001 mci if A gLis not more than 0.05 C1. 0.001 mci for all other radionuclides. Low specific activity material that conforms to the definitions of.special wastes in 10 CFR 20.306, are exempt from all of the requirements of Part 173, but are still subject to the requirements of any other hazard class, t e.g. flammable. [173.425(d)] Check the appropriate material classification and shipping method below and complete the indicated check lists. Limited Quantity; complete RPR 14LQ. Type A quantity or Low Specific Activity material to be shipped by common carrier; complete RPR 55RW. Prepared _by(signature): Date: RSO approval (signature): Date: O RPR 55. RADIDACTIVE MATERIAL TRANSPORT (11/89) - 8
l
.p) RPR 55A. COMMON CARRIER SHIPMENT OF d TYPE A RADI0 ACTIVE MATERILAL Instructions: Use this check list for any radioactive materials exceeding the limitea quantity other than wastes. (Use RPR 14LQ for limited quantities; Use RPR 55RW for radwastes.) Unless otherwise indicated, all references are to 00T regulations (G '
CFR). Initial each item um completion or verification. The person responsible im the shipment must sign anc uate the check list after all items have been completed. The completed check list shall be submitted to, approved and retained by'the RSC Initials Container . - quantity-is : Must be[173.425(a))- DOT specification 7A, Type Q1 Ampackage (or
~
exceeded). ,
,3 containers must be in good physical condition with no evidence of damage, corrosion or leakage. [173.24,173.475) ,
Each container must be secured with a seal that is not readily breakable as evidence that the package has not been opened. [173.412(b)) Radiation Surygy Exposure rates measured with i(Model) p Ser. No.: Calibration date: Y Maximum at surface - mR/hr; at 1 meter = mR/hr Less than 200 mR/hr at all points on the surface of- the container. Transport index does not exceed 10, i.e. less than 10 mR/hr'at I meter. [173.441(a)) Contamination measured with (Model). l Ser. No.: Efficiency: Calibration date: Count rates (cpm or cps): Gross:
Background:
Net: i Less than 0.3 nci (660 dpm) alpha and less than 3 nci (6600 dps) bsta-gamma removable contamination per wipe of_300 cu'. [173.443(a)] Surveyed by: O RPR 55. RADIDACTIVE MATERIAL TRANSPORT (11/89) - 9
1 k Initials Labels and Markinos The names and address of both the consignor and the consignee are legibly : affixed to each container that is subj::t to vehicle transfer enroute.- ! [172.306)' Two (2) radioactive material labels, of the type current 13 authorized, and marked with the quantity and units of activity, are to be affixed to opposite sides of the package; the quantities, units.and transport-index mustagreewiththeentriesontheshippingpapers.f(172.403) All markings must be durable, legible, displayed on'a background of sharply contrasting color, unobscured and located away from any other marking (e.g. advertising).[172.304]
- : C j
. 1 Each container'must be marked with lettering at least 1/2-inch high-
"RADI0 ACTIVE MATERIAL, N.O.S. UN2982"; this marking should be within six (6) inches of each radioactive material label. [172.101,7 172.301]
. Each container must be marked with lettering at least 1/2-inch h'igh:' " USA' DOT-7A,' TYPE A" and with the name and-address (or registered symbol) of.
the person making the specification marking. (178.350,173.24(c)(1)] For each container weighing more than 110 pounds, the weight and unit ~of ; measurement must be marked on the container. [172.310) ! If the contents include flammable liquids in containers of more than 1 pint , capacity, each package must be marked with the following: "THIS END UP" ! and an arrow pointing .p, and a " FLAMMABLE LIQUID" label. [172.312] ; Vehicle Requirements , Verify that packages are blocked and braced so that they cannot change position during conditions normally incident to - transportation. [173.425(b)(6),177.842(d)] The sum of the transport index numbers on the vehicle does not exceed 50. [177.842] 9 RPR 55. RADICACTIVE MATERIAL TRANSPORT (11/89) - 10 , i l
l l l l [ $ldaping Papers Enter the proper shipping name and hazard class, and number of packages of each class, on the shipping paper [172.202 and 172.203(d,)]:
" Radioactive material, instruments and articles, UN2911 4
' Radioactive material, LSA, n.o.s., UN2912" i
" Radioactive material, LSA, n.o.s., Flammable Liquid, UN2912' i
' Radioactive material, fissile, n.c.s., UN2918' ,
" Radioactive material, special form, n.c.s., UN2974*
' Radioactive material, n.o.s., UN2982* ;
Enter the name and activity of each radionuclide contained in the package, , and the physical and chemical form if not special form; entries must agree ' with information on the pack, age labels. - uired for~the Enter index ifthe the catego{y pac age labelof label is regellow-!! or-Ye low- II;acka e, and the Exce)t for Limited Quantities, sc. following certification must de printed on tie shipping paper and signed by the RSO (172.204):
'This is to certify that t.% above-named materials are properly classified, described, packaged, marked and labeled, and are in proper condition for transportation according to the applicable. regulations of the Department of Transportation." See RPR 14LQ for the certifica--
tion required for Limited Quantities.' ! For shipment in a passenger carrying aircraft, the follosing additional l
- c 1:
certification must bematerials includedare (172.204(de)d for use in, or incident te,
'1he above-named inten research or endical diagnosis or treatment."-
1 Retnin a legible co)y of the completed shipping paper for RadiologNa1 Health Departnor.t f< 1es. Preparedby(signature): .- Date: RSO approval (signature): _ Date:
)
l O RPR 55. RADIDACTIVE MATERIAL TRANSPORT (11/89) - 11
- _sAuus._, E-_a- 45 --oMJn,-.Aae4 se 4s-A e. ,a- a.4.4A e e- - M m e b--re44==*om4--A n &so+-a.a s e kae.ean um m -- m W4,.-'4enm a -wGsus&ap.m,amaem-wa.m A 4
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RPR 55RW. COMMON CARRIER SHIPMENT OF RADWASTE l Instructionn Use this check list for LSA or Type A quantities of radioactive wastes to be shipped by common carrier. Unless otherwise indicated, all references are to U. S. Department of Transportation regulations, found in Title 49 of the Code of Federal i Reulations (49 CFR). Obtain the contents of the waste containers from the RADSAFE database. Initial each item upon completion or verification. The person responsible for the shipment must sign and date the check list after all items ~ have been completed. ' The completed check list shall be submitted to, approved and retained by the RSO. Initials Tvoe A Centainers. Markinas and Latut]2 s Must be DOT specification 7A,' Type A package (br Thpe B if A, quantity is ! exceeded). [173.425(a)) Each container must be marked with lettering at'least 1/2-inch high: ' USA l
)
DOT-7A, the personTYPEt.iakingA*the and with the name specification and address marking. (or registered symbol)]o [178.350,173.24(c)(1) On each reconditioned drum, the reconditioner's ID ~ numNr and! drum certification date has been marked within 10 inches of. the opening. [173.28) Each as container evidence must that the be secured package withopened. has not been a seal that is not readily) breakable [173.412(b)- t Two radioactive material labels, of the type currently authorized, and , markad with the quantity and units of' activity, are to be affixed to i opposite sides of the package. [172.403)
. Each container must ' be marked with lettering at least 1/2ilnch ' high:
'RADIDACTIVE MATERIAL, N.0.S. LAN2982' (172.101,172.301)
If the contents include flammable liquids in containers of more than 1 pint capacity, each ptcha.Je must be marked with the following: "THIS END UP' and an arrow pointing up, and a ' FLAMMABLE LIQUIO" label. [172.312) , LSA Containers. Markinos and labels Strong, tight package that will not leak during conditions normally incident to transportation. [173.24and173.425) l Each container must be marked with lettering at least 1/2-inch high:
' RADIOACTIVE MATERIAL, LSA, N.O.S. UN2912". [172.101,172.301) t If the contents include flammable liquids in containers of more than 1 pint l- capacity, each package must be marked with the following: "THIS END UP' and an arrow pointing up, and a " FLAMMABLE LIQUID" label. [172.312]
O l RPR 55. RADIDACTIVE MATERIAL TRANSPORT (11/89) - 13 l
I i 1 Initials General for Arw ContaintC I Containers corrosion or must be in173.24,173.475) leakage. g[ood physical condition with no evidence of damagj All metal drums with a capacity of 55 gallons or greater sha'il have a 5/8 l inch or larger bolt for securin 'vthe closure ring. Bolt should be torquod j to approximately 45 foot-pounds. (US Ecology recemmended) All metal containers shall have an intact heavy duty closure device when . presented for disposal. Wooden boxes must be banded with metal bands. ! (US Ecology Washington license) w All markings must be durable, legible, displayed on a background of sharply ~ contrasting color, unobscured and located away from any other marking (e.g.,
-advertising) [172.304) ~
Each container weighing more tl.an 110 pounds must be clearly marked with - thegrossweightandunitofmeasurement(pounds). For shipments directly to the burial ground o must be marked on each container in letteherator/ ing more broker, thanthewaste 1/2 inch class highn . Choices: Class A Unstable, Class A Stable, Class 8 or Class C. [10CFR< 61.57 and US Ecology Washington license) Shipments to a processing broker need not be marked with waste class. Radiation surver . Exposure rates measured with (Nortei) l Ser. No.: _, Calibration date: , Maximum at surface = _ mR/hrt at I meter - mR/hr less than 200 mR/hr at all points on the surface of the container. Transport index does not exceed 10, i.e. less thin 10 mR/hr at 1 meter. [173.44)(a)) Contamination measured with (Model) Ser. No.: Efficiency: Calibration date: Countrates(cpmorcps): Gross:
Background:
Net: Less than 0.3 nCi (660 dpm) alpha and less than gamma removable contamination per wipe of 300[173.443(a)]- . cu'3 nci (6600 dpm) beta-Surveyed by: O RPR 55. RADIDACTIVE MATERIAL TRANSPORT (11/69) - 14
I l Initials Vehicle Requirements Verify that packages are blocked and braced so that they cannot change : osition during conditions normally incident to transportation. 173.425(b)(6),177.842(d)) _ The sum of the transport index numbers on the vehicle does not exceed 50. [177.842) i
$hipp;,ina Paners -8 Other Panerwork Verify that each waste generator having materials in the shipment has a '
valid Si.'s Use Permit and that there is a' signed Certification form for each geneaator bearing a name identical to that. appearing on the Site Use Permit. L, _ Note that there are three different Certification forms:. ' RHF-31A for commercial generators. . RHF-318 for state and local government generators. - RHF-31C for. federal government generators.n - Verify that the complete listing of the-contents of .all containers is available from the RADSAFE databsse. . _ _ _ On the front sheet of the manifest, and on the bill of lading, enter [the proper shipping name and bazard class, and number of packages or each class. 1 > [172.202 and 172.203(d)d, LSA, n.o.s., UN2912' I O 'P.adioactive materi
' Radioactive material, fissile, n.o.s., UN2918? ,
' Radioactive material, special form, n.o.s.. UH2974"
" Radioactive material, n.o.s., UN2982"
_. Enter the name and activity of each radionuclide contained in the package, and the physical knc' chemical form if not special form; entries must agree with inf ormttion an the package labels, for Type A quantities, enter the category of label required for the package, and the transport index if the package label is Yellow-II or Yellow-III. Exce)t for Limited Quantities, the following certification must be printed on ta shipping paper and signed by the RSO [172.204):
"This is to certify that the above-named materials are properly classified, described, packaged, marked and labeled, and are in proper condition for transportation according to the applicable regulations of the Department of Transportation." See RPR 14LQ for the certifica-tion required for Limited Quantities.
O RPR 55. RADloACTIVE MATERIAL TRANSPORT (11/89) - 15 1
3 I t If shipment contains Special Nuclear Material (SNN), or 1 kilogram or more of Source Material (10 CFR 40.64), a DOE /NRC Forn 741 has been prepared.
._ The RSM (manifest) is complete and signed. Retain a legibic co)y of the completed shipping papers for Radiological Health Department (11es.
The number of containers listed on the RSM agrees with the physical count of containers loaded. The consignee has been notified of the expected time of shipment arrival. , Prepared by (signature): Date: RSO approval (signature): Date: a l l 1 l 1 l O RPR 55. RAD 10 ACTIVE MATERIAL TRANSPORT (11/89) - 16
l
)
Q RPR 55LSA. EXCLUSIVE-USE VEHICLE SHIPMENT OF LSA RADWASTE ) I Instructions: This check list should be used for all radwaste shi mants to be made by exclusive ase vehicle. The check list for the exclusive-use vehicle RPR 55EUV must ) also be comt,leted. Unless otherwise indicated, all references are to U. S. Department i of Transputation regulations, found in Title 49 of the Code of Federal Reulations (49 CFR . Initial each item upon completion or verification.-The person responsible for th:):hipment must sign and date the check list after all items have been completed. The completed check list shall be submitted to, approved and retained by the RS0. Initials Contents ,. l ,
,y The contents of the shipment will be obtained from thh RADSAFE database ,
and need not be entered on this check list. However, the contents must be verified to meet the criteria for LSA. l Contents of all containers meet the LSA criteria. If not, use RPR 55RW. Containers , All cont' ainers .are. s'trong, - tight packages that will not' leak Ering - conditions normally incident ~ to transportajion.,;[173.24 and:173.425) u i All containers are in good physical condition with.no evidence of damage, l corrosion or leakage. [173.475) All drum lids are provided with gaskets and fit securely. [173.475)? All metal drums with a capacity of 35 gallons or greater shell have a 5/8 r inch or larger bolt for securing the closure ring. Bolt should be torqued ' to approximately 45 foot-pounds. (USEcologyrecommended) All metal containers shall have an intact heavy duty closure device when presented for disposal. Wooden boxes must be banded with metal bands. , (US Ecology Washington license) Labels and Markinas l All markings must be durable, legible, displayed on a background of sharply contrasting color, unobscured and located away from any other marking (e.g. advertising) [172.304) Each container is usually marked with lettering at least 1/2-inch high:
"RADI0 ACTIVE MATERIAL, LSA, N.O.S. UN2912". [172.101,172.301) Howaver, for LSA materials shipped in an exclusive-use vehicle, the LSA label on each package is not required. [172.400(b)(10))
If the contents include flammable liquids in containers of more than 1 pint capacity, each package must be marked with the following: "THIS END UP' and an arrow pointing up, and a " FLAMMABLE LIQUID" label. [172.312) O RPR 55. RADIDACTIVE MATERIAL TRANSPORT (11/89) - 17
~___ _ _ ___________ _ _ __ _.___ ._ .._. __ _..___ _ __. _.
I f Each container weighing more than 110 pounds must be clearly marked with thegrossweightandunitofmeasurement(pounds), For shipments directly to the burial site, the waste class must be marked hl ; i on each container in lettering more than 1/2 inch high. [10 CFR 61.57 and ! US Ecology Washington license) I Radiation Survey of Containers - Exposure rates measured with (Model) j Ser. No.: Calibration, dates: Maximum.at' surface - mR/hrt ' > at:1 meter : mR/hr.- g, w, ,7 ; ;
^ . Less than 200 mR/hr. at all accessible pointsion(the surfde'Jofithe'~
container,. unless shi sped in a closed vehicle and secured ~ so' that its ' position remains'fixec during transportation, in which case lthe limit'at 1 the surface of the container is 1000 mR/hr. [173.441)- z. . . Contamination measured with -(Model) < Ser. No.: Efficiency: ' Calibration date: Countrates(cpmorcps): Gross:
Background:
Net: ~ Less than 0.3 nCi (660 dpm) alpha and less than gamma removable contamination per wipe of 300 . cu'3 nCi (6600 dl)m) bet [173.443(a)) Surveyed by: Shipnina Pepp,D 2mLQLher_tanensttk Verify that each vaste generator having materials in the shipment has a i valid Site Use Permit and that there is a signed Certification form for each generator bearing a name identical to that appearing on the Site Use g Permit. Note that there are three different Certification forms: RHF-31A for commercial generators, RHF-31B for state and local government generators. RHF-31C for federal government generators. Verify that the complete listing of the contents of all contat ars:is available from the RADSAFE database. On the front sheet of the manifest, and on the bill of lading, enar the proper shipping name and hazard class, and number of packages of each class. [172.202and172.203(d)),e.g.:
" Radioactive material, LSA, n.o.s., UN2912"
" Radioactive material, LSA, n.o.s., Flammable liquid, UN2912" O
RPR s5. RAD 10ALTIVi NATERIAL TRANSPCRT (11/89) - 18
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.( ' . O Enter the name and activity of each radionuclide contained in the package, ! 'V end the physical and chemical form if not special foral entries must agree with information on the package labels.
1 Except for Limited Quantities, the following certification must be printed s on tie shipping paper and signed by the RSO [172.204):-
'This is to certify that the above-named attorials are properly '
classified, described, packaged, marked and labeled, and are in proper ! condition for transportation according to the applicable regulations of the Department of Transportation." , The RSM (manifest) is complete and signed.J Retain a legible coiy 'of the completed shipping papers for Radiological Health Department; f
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lesh l The number of containers listed on the RSM agrees with'the physical' count of containers loaded. The consignee has been notified of the expected time of shipment arrival. w Prepared by (signatcre): . 'Date:- : l
N RSO approval (signature): ._, . . _ Date:
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J O RPR 55. RADIDACTIVE MAi[RI AL TRANSPORT (11/89) - 19 _. _ __ _ _ _ _~- _ _ _ _ ._ . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
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RPR 55EUV. EXCLUSIVE USE VEHICLE SURVEY l AND DRIVER'S INSTRUCTIONS All references are to U. S. Desartment of Transportation regulations, found in Title 49 of the Code of Federal Reulations (49 CFR). 1 Initials ItaDsnort Vehicle Surver (by Constanor): , Before loading, verify that there is no loose radioactive material in the vehicle. (173.425(b)(5)) F Naximum exposure rates after loading:- 1 At the external surface of the vehicle: 3 W erea Not to exceed 200 mreW hr [173.441(b)(2)). ' .
; . , X.,/hr ',
VA At any point 2 meters from the' sides . ' inre#hr Not to exceed 10 mre#hr l173.441(b)(3)].. t "c . At any normally occupied :ocation: _ 'are#hr Not to exceed 2 mrem /hr (173.441(b)(3),'177.842(g)] Verify that packages are blocked and braced so that they cannIt' change position during: conditions normally incident to' transportation - (173.425(b)(6),177.842(d));
" RADIOACTIVE" placards on all 4 sides of vehicle at least 3 inches'away from other markings, e.g. advertising. [172.504 Table l', Note 5).
._ Additional placards for other hazardous materials applied to vehicle, if appropriate. When the gross weight of all hazardous materials covered by 172.504 Table 2 (flammable, combustible or corrosive liquids, etc.) is less than 1000 pounds, no placard is required for the Table 2.~ material (172.504(c)]. The " RAD 10ACTIVC" placards are still required.. "If the e vehicle contains more than 1000 pounds of a Table ~ 2 material, the appropriate placards, e.g. " FLAMMABLE LIQUID", " COMBUSTIBLE LIQUID", etc..
must also be placed on all 4 sides of the vehicle. If the vehic1c'contains. more than one Table 2 material, but less than 5000 pounds of any one class of material, the second set of placards may say " DANGEROUS" (172.504(b)] [ Instructions for exclusive-use vehicle have been reviewed with the carrier , and provided in writing. [173.441(c,e)) , Checked and Surveyed by: Date & time: RSO Approval (signature): l-L l RPR 55. RADI0 ACTIVE MATERIAL TRANSPORT (11/89) - 21 L
a .- > INSTRUCTIONS TO CARRIER , FOR MAINTAINING CONTROL 0F SHIPMENT BY EXCLUSIVE-USE VEHICLE GDIERAL IftSTRUCTIONS: This shipment, loaded by consignor, must be unloaded only by the consignee, or by individuals having radiological training _and resources and approved by the consignor. [173.403(1)] No additional materials, r'a'dioactive or otherwise, are to be transported. with this consignment. [173.425(b)(4)) The load must remain blocked and braced, and the vehicle must remain placarded, during the entire trip. [173.425(b)(6)) Personsshouldnotremainunnecessarilyinthevehicle(177.842(e)]. DEllGDICY 100TIFICATION: ,. In the event of an emergency situation where the vehicle configuration must be changed, the consignor must be notified prior to initiation of the change: During normal office ' hours (8 am to 6 pm, Monday - Friday): University of Utah Radiological Health Department 801-581-6141 Other hours: Dr. Schiager 801-484-5007 or University of Utah Police 801-581-7944 l AQ300in.EDGDIENT: This instruction sheet is to be retained with the shipping papers. [173.425(b)(9)). Carrier hereby certifies that he has read and understands the instructions for exclusive use shipments. Name of Carrier: Driver's Signature: Date: RPR 55. RADIDACTIVE MATERIAL TRANSPORT (11/89) - 22 l
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APPENDIX E . t UNIVERSITY OF UTAH SAFETY AND HEALTH MANUAL 4
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PCTUTITTTUTTRWI C M I L M W IVI C U I VM L MQ O U U i M I 11 bTE INDUSTRIAL COlV VISSION OSHA NIOSH ETY CODE GUID ELI N ES FOR HANDICA PPED SSIBILITY LABORATORY SA F ETY HAZARD 7E DISPOSAL UNIFORM BUILDING COJE EF tOClATION AM ERICAN M EDLCAL ASSOCIATli TE INDUST RI AL CO VI V ISS!ON OSHA NIOSH ETY CODE GUIDELI N ES FOR HANDICA 3 3 ED ,ESSIBl LlTY LABORATO RY SA C ETY HAZARD STE DISPOSAL U NIF09M BUILDING CODE EF
;PR ESS ED GAS ASSOCIATION AIV ERICAN M OCI A.TIO N U"A H STAT E I NDUSTRI AL COlV M N DIC i R S CAR DOUS W E . L U NI:ORM 3UIL[
( CO MPR ES: R "'OC ; ATIO N AM E ; AT;ON UTAH ST; N ME ICA _ ASSOCIA~I xTE INDUSTR ! A L COlV MISSIO N OS HA NIOSF AFETY CODE GUIDELINES FOR HANDICAPl?E 3CESSl 3iLITY LA3 ORATORY SAFETY HAZAR ASTE DISPOSA_ UNI CO RIV BUILDING CODE E IV PRESSED GAS ASSOCIATION AMERICAN I SOCI ATIO N UTAH STATE IN DUST RI A _ COlV HA NIOSH Ll:E SAFETY CODE GJIDELINES NDICAPPED ACCESSIBl L:- Y LA30RATORY ZAR DO US WAS~ E DIS 3OSA L UN ! FO R Vl BUI A COM PR ESS ED GAS ASSOC l A lON UTAH S' FORM BUILDING CODE E3A COM?RESSE3 G OCI AT"ON /ddFVI$fR3fWO'FtJ5AM ASSOCI AT a gE INDUST RI AL CO M M ;SSIO N OS KA NIOS H TTY CO DE 't t $ 31CA3 PED OESSI 31L LT . TY HAZARD S"E DIS 30 SAL L
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VI .
!NG CODE ER MtERESSED GAS _ASSOE1K1CLLsLAVLERLCAhLM
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' University of Utah Department of Public Safety Safety Services Division 1982 I
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p ] i-l t L TABLE OF-CONTENTS. . - 1
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i CHAPTER I- INTRODUCTION CHAPTER VI- HAZARDOUS WASTE ; DISPOSAL General inf ormation . .3 Safety Services Responsibilities . .3 Definition of Hazardous Waste , 33 j General 3 Regulations , 34 : Functional .4 Responsibilities of University Personnel 34 T Departmental Responsibilities .7 Handling Hazardous Chemicals .35 Emergency Response information .8 P;ck-up for Disposal .35 Emergency Telephone Instructions Final Disposal 35 and Numbers , B Public Safety Telephone Numbers , 8 , Notification and Procedures for CHAPTER Vil- FIRE SAFETY Chemical Spills 8 Notification and Procedures for Fume. Responsibility of Fire Marshals 36 Vapors. Gas Leak incidents. 9 Preparedness . .36 Evacuation Procedures .9 Fue Procedures 36 ; Reporting . 36
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CHAPTER 11 - LABORATORY SAFETY 370,$g Nar' I n I mrnable f ta and Combustible Liquids 36 General Sately Recornmendations . 10 Residence Hall Safety 38 Carcinogen Safety Standards 13 , Biological Safety Guidelines 14 l
. Etiologic Agents. 15 i
CHAPTER lli -INDUSTRI AL HYGIENE Ventilation 20 Air Contaminants Gases, Vapors, Fumes, Dusts and Mists . 20 Personal Protectivo Equipment 21 Welding, Cutting, Heating, Brazing 22 Non-ionizing Radiation . 24 Kilns, Furnaces 25 t CHAPTER IV - EMPLOYEE SERVICES Worker's Compensation . ,27 Health Monitoring 28 CHAPTER V - GENERAL SAFETY Compressed Gas Cylinders . 29 Electrical 29
- l. Power Machinery and Equipment 30 Power Mowers .30 Ladder Safety 31 l- Grinders and Buffers 32
.o CHAPTERI INTR 09UCTiON .
3 Safety Services Division of the Department
-of Public Satety has been estabhshed to pro. SAFETY SERVICES RESPONSIBILITY-
. vide a comprehensive and contnuing accident - GENERAL prevention .and environmental health ettori compatible with the function of the administra- The office of Safety Services reviews acci-tion of the University. The program is designed deM experience and allied saf ety problems that
. to create a more hemthf ul and safe atmosphere anse on or are connected with the University of tot study, reseatch, service and employment, Utah property. The staff reviews reports of'
< ond to promote good health and safety prac- serious accidents and fates and submits recom-tices by the student body, the faculty, and the mondahons to conect hazardous conditions
. staff. and to increase safety efficiency, in line with Good health and safety is not the exclusive these dulles it is necessary to recommend -
responsibWty of the Safety Services othee as essential changes in existing policies to im-it is imporiart that evervone share in this re, prove saf ety efhciency; to recommend physical spon6ibill'iy and become " safety conscicus." or structurai alterations required to eliminate
'L The function of Safety Services is to asvist too or control harards; to recommend and provide f actr ty, n'af t ant' student body in meeting these programe designed to create and maintain ulely und environmental health responsibili, interest in safety; and to enforce regulations 9 eg, and policles established by the University.
Division employees ur. der the supervision of Promotion and Publicity - The o;fice of the Manager of Salety Services include an Safety Services conducts a campus-wide Environmental 5afety Coordinator, Worker's safety / health promotion and publicity program.
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.Compensatien Coordinator, Industria! Hygien. It makes use of the University facilities, news a c f . it1, Chemical / Biohazard Specinhst, a Fue media, and the campus Safety Newsletter, to Marshal, a Fire Safety Coordinator, and a Fire publicize the vanous aspects of ssfety and
- Prevention Specialist, health.
This manual should serve to describe the Purchase and Design of Equipment - The safety and environmental health servicos avau- office of Safety Services assists administrative able on campus and as a guide to environ. divisions'and departments in determining the mental hazard control New employees should need for specific types of safety guards, ap-tamlharize themsulves with this manual as well parel, storago containers, or any other safety as any other departmental safety regulations. equipment and on request will provide source Safety Services will provide advice and tech. and standatos information. nical assistance to academic and management Procurement of Safety and Health Materlats offices for developing and cartying out eff ective and Printed Matter - Saiety Services main-safetyihealth practices in departmental opera- tains a current up-to-date library of safety / tions under their control. All personnel should health pubhcations and hat access to safety review the manual periodically. A copy of the hbraries of such organizations as the Utah Oc-manual should be found in every university lab- cupational Safety and Health Administration, oratory and workshop Copies can be obtained the National Safety Council, the National Fire from Safety Services (ext. 6590) Appropriate Protection Association and the various film standards promulgated by federal state and hbraries The resources of the Safety Services local agencies and professional orgamzations othce library are available to all members of the have served as guidelines for the Sately Ser. University commumty. Safety Services has im. vices otbce in estabhshing rules, regulations mediate access to the cornputer data bases of and standards apphcable to the University. the National Library of Medicine, Ior research-ing environmental y occupational health problems
-: . Safety and Health Training - The offlue of Satety Services will provide on request, quah-bed instructional personnel to assist all depart-i l
r r IN T RODUC l lON 4 ments in training personnel in fire prevention of the on the-job injury or illness, it must be ( and minor fire fighting, accident prevention, reported on the injury / Illness form. occupational environmental health and sanita- Where University facilities are unsafe and tion, personal first aid, lab safety and other have contributed to the accident, Safety Sel-related subjects. Topics and scheduling will be vices investigates the problem and makes : arranged to meet departmental needs. recommendations regarding ways to correct Miscellaneous - The office of Safety Set- hazardous conditions. The office of Safety vices will from time to time publish safety fact Services initiates corrective action through the sheets and statistics in order that department proper administrative channels if the situation heads may have the most current information warrants it. The Worker's Compensation Coor- , for their safety and health program. In addition, dinator conducts periodic preventive injury / ; charts, graphs, posters, training aids and other illness training with high-risk departments, and , related (tems will be prepared as deemed conducts studies to identify factors for risk necessary to further the safety and health goals reduction procedures injury statistics are re-of the University, ported bi-monthly to these departments. Annual
- 1. At present the following University Policies Reports of injuries and flinesses are posted ,
and procedures pertain to the function of this according to Utah Occupational Health and othee: Safety Regulations. Accident and injury Prevention,2 73 Accident and injury Reporting Procedures, Plan Reviews , 2-74 Safety Services is responsible for reviewing Animal Control, 5-13 sll current and future remodeling plans at the . Saf ety, 2-73 University to insure total code compliance be- . Health Monitoring,2-4 fore actual construction begins. A Plan Review Saf ety, 2-73 Notice is sent to the division et which time the
- Smoking Policy,8-10.10 Safety Coordinator and a Fire Marshal review Worker's Compensation, 2-21,2-72 . the plans to insure code compliance. Code
- 2. In addition to the Policies and Procedures compliance priorities consist of the following: ,
of the University and recommended guidelines 1. Egress ' in the Safety and Health Manual, where ripplic- 2. Fire suppression and detection able and feasible, all rules, regulations and 3. Electrical systems standards developed and required by state and 4. Hazardous materials federal regulatory agencies will be complied 5. Mechanical equipment with in all operations of the University of Utah. 6. Handicapped code compliance , inspections and Evaluations FUNCTIONAL R utine periodic inspections are scheduled , for specific safety equipment such as fire j alarms, fire detect;on systems, and fire fighting injury and illness Reporting Procedures equipment, in addition, surveys of all buildings , All on the job injuries are reported on the and departments are made to detect physical University of Utah Occupational Injury / illness hazards. These surveys are prioritized accord-Report form. The University's Policy and Proce- ing to risk in the college or department. dures Manual states that an employee and his The fire marshals are entrusted with the or her supervisor must complete the Occupa- responsibility or maintaining all fire safety tional Injury / Illness Report whether the injury equipment. Monthly test inspections are con-was serious, minor, or did not require medical ducted in different segments of the campus to attention at all. insure the proper functioning of audible signal A Worker's Compensation Brochure .is is-devices, a circuitry signal transmission between sued to allincoming employees and is posted the University of Utah equipment and a remote : at various places throughout the campus. The station receiving panel. A written report indi-brochure states that. regardless of the severity cating the results of the periodic inspection is i
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IN TRODUC T ION s e ; ^. f l . v -g [ logged in the maintenatice record, 1. Complaints J '" ' LAlt fire extinguishers located in the various~ E R eferral buildingt, of the carnpus are inspected, re- 3 Requested evaivations
, . , chatged and tagged if necessary, on an annual 4. Routine preventive surveys
. basis. The sprinkler systems'are tested by a An inf ormation t,etvice is also off ered to any .
D LPlant : Operations maintenance crew, and a- person wishing data 'on' occupational health Fire Marshal on' a regular preventive-mmnte- harards. Equipment is avaliable to mea 9ure bg -
- . nance schedulef environmental toxicants, ventilation, noise and .
m . Obannually, courtesy tire and sniety inspec- other factors which relate to envannmental Z .tions are made m allot the 18 fraternity and health.
'sdronty houses. The Fire and Safety inspection
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- Toam is escorted by an oppotnted representa, Emergency Preparedness live of chch chapter Verbat rncommendations Sately Services has develaped an omen.
are made to correct vatious unsafe conditions gericy plan for both natural and nuclear disas-at the timo of the lnspectionl A w4tten summary ters. Campus-wide emergency coordinators of the' inspection findings is also filed with the have been designated and plans are being Luth intra Fraternity Council for thmt records. mitted as key segments of the University Master
* - The Residence HMl; Addsory Committee Ph n; schedules comprehensive tire and safety in, in order to help coordinators better prepare spections tot all carnpus residence halls at the for their tunctiotial sosponsiblhties during a nh
- beginning of each academic school yeat Rou. disper, the Univecsity participates in Salt Lake
' tine inspections are'mado during the rest of County's Operation B oadscope and conducts the year to correct specific hre and safety annual campus mock disasters. During these
' exerclSes, Safety Services estabbshes control thatards. File safety guidelmes are given to at!
residents. T he fire extinguishots and hoses are as the emergency coordinating center for the ~3 o . .. , inspected semi-annually-as part of the overall campus nnd develops scenarios for simulated 4 fire prevention program, earthquakes . which require tesponses flom '. ?j a '
. Departmental evaluations are conducted by each coordinator j 1 the Safety Coordinator and Industrial Hyglenist, Safety Services has initiatnd a class through j
. The goal of the inupection is to educate depart, the Cohge of Health entitled, " Emergency s ments about Safety Services, provide a safety / Preparedness" (Health Sciences 5?0). The
. health inspection of the af eat make recommen. course is oftered through the Division of Con- j (1ations for feasible changes and provide _ tinuing Education during each sprin0 and .!
. assistance for secunng a method for correcting j autumn quarters -
* ** ! Health Monitoring j ig : htdustrial Hygiene Services !
- Safety Services evMuates the individual in l The divistorl is responsible for environmental relation to the work environment in order to {
> health and indestrial hygiene services for the categuard against adverse health effects from :)
i 4 ; University of Utahc The concern of this service specifically regulated materiats and processes. _l
'is to. solve occupational health problems by if the material or process by law requlres j recognizing toxic substances and operMions, worker medicht evaluation, Safety Services ;
evaluating environmental factors, and then ap. refers the employee for such treatment, Adde i 4
; plying control measures tionally, if the environmental evaluation cannot !!
Air contaminants, raw materials, and physt. be accomplished in a manner other than by cal agents that rmght be hazardous to health health monitoring, such tests will be conducted of employees are in common use in many areas. Io insure environmental safety- j g ' of the University In ordet to protect employee Carcinogen Control h, . health and avoid citation. the environmental health personnel of Safety Services attend to All departments on campus are sent a yearly /- memo notifying personnef about current regula-problems with the following prionty: , tions and recomrnended work practices relatJve _f { ([_ Y m> %-1 -< .
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[IMnDMII*hnIed [ i [ d b 3 dI[ 5 i M f [ h,8 s M [T V [ .h @[M k h to carcinogen use. departments on campus This conbultanon All pnncipal investigators are requesled to work is done in conlunction with Plant Opera. Inform Safety Seivices of the tocation of cm. tenu and Facilities Planrung These problems cmogens. authonzed personnel, c ur'ent inven- are identified during college and depattrnental tory, accidents, and materials that require evaluabons by Safety Services coordinators or hazardous waste disposal are brought to the attention of the division pet. sonnel by those working in the area of the Chemical Spill Control problem. Instalhng traffic rnitrors between the e and amics Enmnng buMngs aM All spills (f a potentially hazardoub nature " * " " cub" U U " "" are reported to Safety Services and to the head
' 90" of the department and the Sately Committee 9"Y '" UU ""9 "U"" U"' "'#
two examples of work in this cateDory. A Safety Safsty Services personnel handle the con- recommendabon form is available to all campus tainment and removal of the hazardous chem- departments The form is completed by per. Further action needed (such as evacublion. " "" '"" # "" ventilation, or custodici assistance) is delet-mined by Safety Services. Indoor Clean Air Act Pesticide Application Control Complaints concerning smoking in campus Safety Services supervises the safety of bulidmgs are investigated by the division. Sur. pesticide apphcation by Grounds personnel _ mys, includmg air ~ movement studies. are uti-Prior to the apphtation, Saf ety Services checks bred to evaluate conditions pertaining to the the posticide toxicity, re-entry restnctions, and Act Areas are posted as " Smoking Permitted" manufacturer apphcation recommendations. A or "No Smoking", and in cases of non-comph-check is made with Grounds personnel re, ance, the compimnt is referred to the appropri-gatdmg the above, ate supervisor or vice. president f or action. All departments affected by the soraying; the scheduhng office custodial services, Pubisc Space Analysis Safety dispatch, and secunty guards are noti- **" '8 " * "C " U " '" tied of pesticlde spraying poor to the apph- space allocation are planned The area to be cation, occupied is evaluated in order to ensure that the new occupants will be working in condi-Hazardous Waste tions suitable to their needs and that health and Safety Services estabbshed University pro- safety codes are met. cedures that ensure that hazardous wastes are identified properly, handled safely, and trans- Research Grant Review ported and disposed in accordance with state ulations, Safety Services reviews grants submitted to and federal environmental The University is identihed with th control reg'e United Research Administration on a monthly basis. States EnvironmentalProtection Agency (EPA) Space is allocated on the Document Summary as a large quantity generator of hazardous Sheet fm a Walth and Safety Review by Safety wastes, and must follow federal regulations Services Researchers should check this cate-that stipulate that the wastes be disposed of by gory if they anticipate working with hazardous an EPA licensed f acihty and that the wastes be ma a m undM hazardous conditions. packaged to conform with Department of Trans- Safety Services meets with researchers to dis-portation regulations, cuss the safetyr heahh needs of the proposed research project Safety Complaints Safety Services responds to compla,nts trom Safety Contingency Fund Safety Services evaluates structural camnss I
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j ' i r;afety problems, makes recommendations for
,. ' cost estimates and f unding to the Construction, ' DEPARTMENTAL RESPONSIBILITIES Maintenance and Safety Committeoc
; Safety Services tokows up on the projects Each college or aaministrative dWision
, through the desigh and construction phases shoukt establish a suitable health and safety
!i ' ' and ensures the satisfactory completion of tho' training program d.esigned to; W project. T hese projects are mlnot in remodehng 1. Instruct each employee in the recognition 4 ! scope but ' correct significant safety hazards and aMdance of unsafe conditions and '
?N Funding is available through a Pubhc Safet the regulations applicable to h;sther work ' i
-account estab;is!.ed for auch projects: - environment to control or otiminute any hazards or other exposures to illness or Capitol Facil!!!es Recommendations for IRI"% - -
, J Approptlation. 2. Instruct employeeF Who are required tol Safety Services evaluates structurat prob- handle or use hazardous substances e g.
- lems which pertain to saf ety, health, and handi- ca nogens in theu Sak tandkng and l capped code compliance. The projects a e m, and make them aware of the potential t n
- prioritized and submitted to Facilities Planning h"*"' d"' E""" ""! h E9 i""" ""d P"'" ""!
' protective measures required-i to include with other items for Capltol Facilhics E> appropriation requests on an annual basis. 3. Instruct employees who may be exposed to environments wher0 harmful plants or animals are present, the dang 6rs of the raining J
environment. how to avoid injury and the , i University departments ere provided train,n9 i first aid procedures to be'used -in the c relating to safety, health and fire prevention event of injury, > upon -request. In l addition, specific. training is 4. Instruct all-employees required to enter - recommended to high risk departmen!s and a nto confined or enclosed spaces as to the i course =in Laboratory- Safety is offered bian-nature of the hazardsinvolved.the neces-Lnually through the College of Health Science sary precautions to be taken and in the i and the Division of Continuing Education, use of protective and emergency equip. .) ment require.- 'l
, Animal Control - " Confined or enclosed space". means-Safety Services is responsible for control of any space having a limited means of
. stray animals on campuro Policy and proce'
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.' egress, which is subject to the accumula-
- dures chavei been developed regarding this tion of toxic or flammable contaminants or problem and animals which are found in cam-
- pus build _ings or roaming the campus urp ir>
has an oxygen dE*icient atmospriere. Con- l , fined or enclosed spaces includei but are - i pounded. il possible, the owner is notihed and not limited' to,. storage tanks, process : ! asked to; remove the animal before impound- vessels, bins, boilers, ventilation or ex. ] ment takes p. lace. haust ducts, sewers, underground utlhty. .I 7' vaults, tunnels, pipehnes and open top
, i Miscellaneous Activilles spaces more than four feet in depth such 4tah ECampus Safety . Association - the as pits, tubs, vaults and vessels;
- 5. The department head is responsible for 4 wociation was organized at the University of 4 l Utah?in October of '1978, Members from requinng the wearing of appropriate per- 1
/throughout the state attended the founding sonal protective equipment in all opera- 'l meeting and the quarterly meetings which are tions where there is an exposure to y held at different campuses, hazardous conditions. Each college or . !
. The purpose of the organization is to bnng administrative division giere work is ,
- v. together campus saf ety per sonnel with common carned out with hazardous substances or _!
d interests in order to more fully develop a total operations should form a safety commit- -j tee A "Guice for Effective Safety Commit-
~
preventive Safety program throughout the state,
7 i INTRODdCfl0N ; . f 1 3 , S K D f . ? C M L.f M .L Q W N g h i tees" is available on request; Safety d.The Custodial supervisor and staff ; Services extension 6590. snould be called for any atsistance '
,,,, requested by Safety Services per- {
5 ""# EMERGENCY RESPONSE INFORM ATION e in the mot that Safety Services cannot be reached at extension 6590 major 1, Emergency Telephone Instructions and spiils should be reported to the campus Numbers - Each campus phone should Dispatcher at extension 7944. T he Db;- be equipped with an emergency phone patcher will attempt to tocate someone numt er sticket. Stickers can be obtamed hem SaMy Seca M more appean from Safety Services (ext. 6b90) 1 W a fue huud M Camnus Ne Marshal and the Salt Lake Cny Fire IN CASE OF EMERGENCY OR FOR AS. l Department will oc notified The area StSTANCE: should be kept free of non essential
- a. DIAL 9-911 FOR POLICE, AMBUL ANCE P"U""
OR FIRE OR 7-114 f. If there is any involvement with radio. b REPORT ALL other campus emergen, actne material the Carnpub Radio-cios to Safety Sinv,ces extension 6500 logical Health Safety Othcer at exten-sion 6141 should be contacted.
- 2. Public Safety Telephone Numbers g All reports concerning chemical spill, Service Location Number eithef to the University of Utah Safety Services, or any other department, Pome Oldg. 301 7944 Safety Bldg.301 6590 must include the name and number of :
the c Iler, and the exact location of the Fire Bldg 436 5370 spill If there are any illnesses or in-Secunty Bldg' . 436 8669 jurieb the suspected nature of the spill.
- 3. Nolitication and Procedures For Chemi- and the name of the department asso-cal Spilts ciated with the npill should also be Spills of potentially hazarduub chemicals reported shall be remedied according to the follow- h. "No Smoking" is allowed in close prox-mg procedures: imity of a chemical spill. Every depart-
- a. All such spills shall be reported imme. ment should mmntmn a spill-contain-diately to Snfety Semces. ext. 6%0 ment kit which is to be used only when and to the Head of the Department it is deemed snadvisable to wait for the Safety Committee arrival of someone from Safety Set-vices The kit should contam:
b, Safety Services personnel will handle
- two 10 lb. containers of sodrum bi-the containment and removal of the carbonate, or commercial acio neu-hatardous chormcal but will do so only Wer and homW in the presence of a knowledgeable - to 10 h mWners W mee supervisor from the laboratory associ' or Oil-Dn or other absorbant.
ated with the spill - two 10 lb. contamers of citoc acid, c, Safety Services personnel will deter- or commercial caustic neutraliter mine the need of any further achon, and absorbant. Such as ventilation of the area sum. - a supply of red and blue litmus paper, moning the Fire Department, or evac- or pH papen uation of the area, unless the spillis of - two pairs of rubber gloves such a nature that it is life threatemng, - one lobby broom and dustpan then evacuat on should take place im- - two pans of safety goggles ; mediately and the Fue Department - twe ' Area Closed" signs should be immediately notitied I - two pans of rubber boots
i s i ; 3 ' INTRODUC110N
.- 9 1
"4j'
- where a possibility ot a chemical structed 'to do's.o by authorized per-spiti exists, overy department should . sonnel or Saf ety Services personnel
- also mamtain at least one self-con.
.tained breathing unit.
, f 4
.4. Notification - and ' procedures for fumo, +
i .' vapors, gas leak incidents.
- it a vapor, fume or' gas enters your work-place and you cannot determine the 3 tource; leave your area irnmediutely. Post d, - a "Da Not Enter" rtgn and' notify Safety lieMices; ext. 6590. It in important to re.
. port the f oliovinD; D. Your telephorie extension and location
- b. Ulness or injurieb associated with ihe l probier1 c Tirno of onset of prob;ern ,
- d. Namo of substanco, if possible.
- e. If name is unknown-description or in-tensity of smell
' fe Physicaleffects (o g. irritating to throat, , ~
eyes, etc.)
- 5. Evacuation Procedures Universliy buildings are to be evacuated
-immediately under the following condi-tions;
. a. lilip alarm (unless notif ed of tobting
. procedure)
, b. Powe, outago affecting chemical fume
-hoods c, When notified by Soloty Services or
, person of authority in the building d, Threat to lite and health as determined by Individual good judgement, e9 natural disaster if you are asked to evacuate the building
. or hear a ido alarm, do the toHowing
'a'. Stop work Jmmediately b; Put out all flames or heat sources
' cc Rapidly proceed to the nearest exit in 4
! an orderly manner
- d. NEVER USE ELEVATORS -
t
- e. Supervisorscheck that employees have vacated their-workplace if condrtions permit ,
. f.Juse a preplanned evacuation route, or the most suitable exit under the cir-curd $ lances -
~ g, Reconvene outsido the butiding to in-J sure everyone has lef t the building
; h Do not re-enter the butiding unless in-
)
CHAPTER fl I i h
<.; .; f ., [' g I
i Proper Handling of Glassware GENERAL 1. Glass breakage is a common cause of 5 mjunes produced in laboratones Only glass in
- 1. Students will not be permitted to work gooo condition should be used, Discard broken alone in a laboratory. They must be actnm' glass uto waste cot: tainers marked GLASS.
panied by personnel on the level of graduate 2. When using glass !Ubing, all ends should student or above, unless they have specihc 9e f,re polished. Lubricato tubing with g!ycerin approval from the department head or water before inserting into rubber stoppers 2 Avoid unnecessary exposure to all chem- or rubber tubing. icals Never taste a chemical 3 Protect hands with gloves or towel when 3 All soNentt, minera' acids, and other haz' inserting glass tubing. Hold etbows close to the ardous chemica;s should be transported i9 body to krnit movement when handhng tubing. safety carriers. 4 Do not stote glassware near the edge of
& Ur.e only the necessary length of rubb' r of shel es. Store large or heavier glassware on other fiexible tubing and keep it in the rear of fower shelves the set up. Fasten all connecting hosts with S Use glassware of the proper size Allow at either clarnpa or wire least 20% free space Grasp a three neck flask
- 5. Bench tops should be kept clean and un' by the rniddle neck, not a side neck.
clutteru, Unless specifically required for 6. Discard or send for repair all broken, furthoc work-up or recovery, all parent com' chipped, starred or badly scratched glassware, pounds l column foreruns and tails, etc. should 7. Rinse out all glassware before sending be promptly discardei Do not leave open con- for cleaning or repair. tainers of volatile material on your bench. 8. Do not attempt to catch glasswate if !! is ; 6 Do not use flames or equipment which dropped or knocked over. may spark, near flammable material. Defore 9. Conventional laboratory glassware must lighting a gas burner deterrnine il laboratory never be pressurized conditions are suitable for having an open Flammable Gases and Liquids flame.
~1 A!! f!ammable and combustible hquids
- 7. Precaution must be taken to control unex-pected exotherms whenever a reaction is run should be stored and used as specihed by ior the first time or is being scaled up Pro. University regulations for the storage and hand visions should be made for the rapid removat hog of flammable and combustible hquids (Ses of heating sources dunng distillations. 2 Refrigerators and coolers used for storage 8 Do not scale-up reactions more than one of flammable fiquids should be used only if order of magnitude they are approved explosive-proof Commer- ,
- 9. All reactions which produce a toxic, cial refngerators can be made explosive proof i noxious, or otherwise hazardons gas must have by removing or relocating and controlkng all provisions tor tendering it harmless by passing possible sources of ignition. This solution is it through a scrubber prior to letting it escape not considered satisfactory for storage of all into the hoods- types ot flammable hquids For laboratories con.
- 10. Column chromatography, except with udenng the purchase of new refrigerators or aqueous buffers. must be done with adequate freezers, Underwriters Laboratories have ap-ventilation, Fractions are to t'e collected and proved several such appliances for the stor-stored in a hood or securely sealed Latge age of flammable hauids.
columns should be grounded 3 All contmnets sha0 De clearly labeled.
)
i1 Vacuum pumps and other belt driven special chemicals and gases shall be dated equ cment must have belt guards. All vacuum and owner idenlihed so that correct handhng pum; s or apparatus which exhaust noxious or and disposal procedures can be followed toxic fumes must be vented into a hood. Pump 4 Quantities of gases and flammable hauids oil shotM be changed frequently, in any laboratory should be stnctly cor! trolled ; As a general rule, no more than one week sup-
1 1 1 . ; i L ABOR ATORY SAFE TY 11 'l ;
.i i
ply should be on hand at any one time. sidered hazardous. Solvent transfers, such as 'I
- 5. Solvents should be stored in a separate j reaction vessels. reagent bottles, or fil.
filling l cabinet away from other laboratory equipment trations of suspensions should be carried out' ! to minimite breakago. Neither safety cans nor in a f uma hood or other vented apparatus. 'j
, glass containers should be stored on labora- 3. Elemental mercury should be stored in a j
. tory bench tops or on shelves above working sealed bottle in a well ventilated area Do not .l arcas_ flush met cury containing compounds or wastes -{
- 6. Never store flammable or explosive gases down the drain. Call Safety Services for assis- 1 and oxygen togetherL A distance of twenty feet tance in containing mercury spWs- -i should seSarate the storage of oxygen and & Containers of extremely toxic, corrwivef .
7 flammablo or explosive gases. I,ll coinpressed flammablo, or vnstable matenal thowd be gas cylinders shall be secured in piace at all c early identlfied and stored in vented cabinets. I
' times. 5. All reagents must be properly labeled with Control of Sources of ignition their fut name. No unlabeled matenahi should be kept.
j + 1l Explosion proof electricat equ'pment shall G. Do not store incompatibie chemicals near - l be provided in all areas where flammable va' each other, i e. acids and bases, oxidizing and I pors are present or could be produced. Non- reducing agents, etc. Safety Services has a i explosive-proot plugs, switches, motors and manual available on requWt for compatible d elociiicalcontacts shall be romoved f rom areas - chemical storage. . which are subject to flammable vapors, 7. Do not mix incompatible chemicals. If in [
. . - 2. Smoking shall not be permitted in labora- dout,1, always check a source book betore mix- i tones. ing chemicalt Ventilation 8. Never pour water into concentrated acids - l
' OI " 8
.t. Laboratory ventilation hoods shall be 01 g 001 maintain extra supplies of chemi- !
adequate size and in proper ' operating g. t condition,
- 2. Fume hoods are not to be used as stor, future.
- 10. Drying a0ents and chromatographic ab-
] ,
age places Hoods must be kept clean and free sorbants should be placed into special con. from excess combustibles.. lainers provided for this purpose after_ the ori 3i All reactions should be conducted in j ganic solvents have been allowed to drain, operating fume hoods. Whenever possible keep hood windows closed at all tier as. Use the Safety Apparel , sliding panels for temporary access and opet Hazardous laboratory operations -will not ; panels only as much as necessary. commence until all personnel concerned are j
- 4. Check fume hoods on a daily basis Vane- weaving the appropriate safety appatel Safety .j ometers are available from Safety Services. gloves, shoes. glasses, eye shields, aprons, ;
- 5. Respiraturs shall be provided and us3d in and respirators are examples of safety apparel '
areas where ventilation is insufficient to dissi- available The Safety Services Office offers l pate the toxic flammable vapors as an interim assistance and advice in determining the ; measure Approval for respirator type and f t proper apparel needed for a particular opera- !!
~
should bel arranged with Safety Services tion
- 1. American National Standards Institute
-Safe Handling and Storage of Chemicals (ANSI) approved industnal safety glasses or
- 1. Ether and other compounds that form goggles are to be worn in a laboratory at all ;
peroxides rnust be handled with extreme care times
- Quantibes of other should rat exceed that 2. Contact lenses should not be worn in a !
which can be used in two months Every effort laboratory should be made to limit the exposure of ether 3 L aboratory coats or other protective
.10 ambient air. clothing should be worn when handling chemi-
~ 2. All solvents except water, should be con- cals.
- a. _ .=- -.w. - - _ . . ~ . , . _ - __ .
t.asoRATORY SAFEW f ( : . [ 7 ' _ , TIL0fT[.f,C LM h i 4 Sandals, thongs, cloth sneakers and i 10 Do not store flammsble or explosive ma-shorts should not be worn in a laboratory ! terialin non explosion proof retngerator$
$ Dtra caution should be exercised by indo 11. Keep all materials at least 16" below the viduals with long hair or loose clothing around level of spnnkier headt, Do not hang anythmg moving equipment and sources of ignrhon. f tom spunkler lines of the ceihng.
12 Clean allequipment bequently1o prevent ! Personal Hygiene a buildup of dust. All operating equipment and
- 1. Wash hands af ter aD iaboratory operations service knes must be kept clean and m good or experiments and beh ere eatmg working order,
- 2. Do not store food' or beverages in ting. 13 Hee all leaks and loose vahes 'epaired e.ators ln hny labo atory a exi ' youahfieupersciinet Makeshtfirepairs arenot o
- 3. Do net use ice from isboratary sce ma. permitted chines for beverages. 14 Do not allow miscellaneous articles such 4, Do not eat 0; drink from any laboratory as bottleb, soiled rags, etc. to accumulate Cca-glassware. duct a penodic clean-up.
5 Eating fond. e moking. onahmn beverages 15. Intrequently used equipment shoulo not chewing gum, and the use of cosmettes are not be stored in the labor atory, but in a designated permitted 6r laboratory or work areas storage aioa.
- 6. Laboratory coats and other protective 16 Keep oc,ulpment and chemicals in the clothing should riot be worn out of tha labora- hood to a rmnimum Hemove them when rtot in tory in areas designated for eating, drinking use Keep hood doo.s closeo at all times.
smokmg, etc. Vacuum Operations General Housekeeping 1. When working with a vacuum be awara of 1, Keep masks, gloves, and clothmg clean implosion hazards $ Apply vacuum only to glass-Rep' ace it contamination is suspected ware specihcally designed for this purpose, i a
- 2. All drains in the laboratory shouk~ be filled biter flasks desiccators. etc.
periodically with water to prevent gas back-up 2. Never evacuate scratched, cracked or from sewers etched glassware Always check for stars of 3 Sinks should have a rubber webbed mat- cracks before use. ting. 3 Vacuum glassware which has been cooled 4 Work areas should be clean. dry, and un- to liquid nitrogen temperature should be an-cluttered i neated poor to reuse under vacuum S. Do not obstruct msles, tae doors ratety 4
- 4. Rotary evaporator condensers, receiving exits, hre hghting equipment. electncal panel '
flasks and traps should be taped or kept be-boxes, spnnklet heads, safety showers or eye hind safety shields when under vacuum. Washes 5 All condensers connected to rotary eva-6 The contents of refngerators in labora- poraters must at least be cocied with eit culating tones should be reviewed and inspected at ice water. regular intersals which should not exceed s!x 6 The use of a vacuum for the distiUation of months. the more volatile solvents, e g. ether, low bo;hng
- 7. Retngerated substances which are no '
petroieum ether and components, methylene longer needed should be destroyed in accor- ; chloriae, etc should be avoided whenever dance with the approved procedures or if hal- possible. When reduced pressure cannot be ardous, call Safety Services for disposal ! avoided, a part:al vacuum should be used with
- 8. All inventor) of all contents in c ommumty ; these so! vents refugerators should be posted on the door and ' 7 When a vacuum ts suppmd by a compres-kept current Rettigerators should be cleaned sor or vacuum pump lo distit) volable solvents.
at regular intervals, not to exceed s.'x months ( a 1 quid mtrogen trap should be used to contain 9 Do not store matenais in open contamers { soNent vapors it such a trap is not used, the in the refrigerator. t pump or compression exhaust must be wnted
I ; , r . -- . m.
,di i
L ABORATORY SAFETY, - i 13 to the Gutdide using explosion proof rnethods.
- 8. After vacuum distitiations, the not residue CHEMICAL CARCINOGENS must be cooled to room temperature before alt
=is admitted to apparatus, All departments and colleges within the Uni-
_ 9 Never store anythingin a deciccatot higher
,s .than the lid, All desiccators under vacuum msh m chental ca@ogens are uM, t>hould be taped with electrical tape.
shan inM@ a nec saW and WM p gram for work involving chemical carcinorjens Researchers should report the followmg infor- ,s Safety Showers and Eye Wash Fountains mation to Safety Services: 1, il cortos;ve materials are in use, suitable 1. The current locahon nf work areas where f acilitie's for quick drencrang ot flushing of t'io enemical carcinogens are stored or used. 6m crus and body shall be provideo within the work 2 A current listing of personnel authorized
* - . area (within 25 feet) for immediate eme-rgency to work in chemical carcinogen areas.
- use 3 A current mventory of quantitma of chers
- 2. If you splH a chemical which contacts your cal cartdnegans on %and.
clothes or skin, do not wash it off with solvents. 4.' All accident reports involvmg chemical
< bleacn, alkalt or any other chermcal solution carejnogens.
Rince with copicus qt antities of cold water. k All spills involving chemical carcinogens. Report all such spills to your supervisor. 6 All carcinogen-coittaminated substances which require disposal.
. . i; t aboratory Safety instruction Work practices and engineering controis for
. At the beginning of each course of instruc- infrequent users of smati quantities of material j . tiorb the instructor shall advise his student of . are enumerated below. However, safety during
", 3 .the requirements for saf ety apparel and acces- these operations can normally be achieved by soties and the particular hazards that may be strict adherence to good laboratory ptactice.
encountered and rules and procedures to pro- Such users may include individuals involved in vent or mmimize the hazards Fire and accident mictobial or tissue culture test procedure, per.. lfirst aid procedures, to include location and sons using small quantities of chloroform for - use of fire extinguishers and safety showers, - the inactivation of microorganisms and users of "should be reviewed. " Safety in the Laboratory" o toluidene test papersJ Upjohn Company, Kalamazoo, Michigan, is an - 1. Eating, drinking, smoking, chewing gum or excellent reference publication. tobacco, application of co$;netics, or storage of food in areas where chemical carcinogens. Fire Safety are used or stored is. prohibited. T 1.. Every laboratory should develop emer- 2. A f ully-f astened laboratory coat and gloves gency procedures to provide for fire alarm should be worn when handling or working with activationfevacuation, equipment and utility chemical carcinogens.
- shutdown, use of fire extinguishers, and loss 3. Chemical carcinogens should be stored controlf in an unbreakable outer container which is
, 2. All electrical installations, both fixed and labeled: " CAUTION - CHEMICAL CAR-portable shall comply with the National Electnc CINOGEN"
- 4. All work surfaces should be covered with
[ Code (NFPAproof
- 3. Explosion 70),electricalequipment shall impervious matenal such as plastic trays, stain-L be providod in all areas where flammable vapors less steel, or dry absorbent plastic-backed are present. paper.
- 4. Housekeeping - accumulation of waste 5 The preparation of 'a diluted solution or
- paper, empty containcts, unused apparatus, the removal of small amounts of a chemical l and equipment should be avoided- caremogen f rom stock quantibes should always i 5 Fire extinguishers, routesof egress. safety be performed with a laboratory type hood equipment. and devices should not be ob- 6. Mechanical pipettmg aidt shauld be used structed for au pipetting procedures d
a
PGdC16MiVMMtIk X[ 1,2.[? [ [ $ [-[ 9 [ . I.' 7, storage of chemical carcmogens should be limited to th0 minimum quantity required for BIOLOGICAL SAFETY GUIDELINES efficient ube. 6 Hands should be thoroughty washed af ter The following regulations apply to all f acih-using a carcinogen. ties at the Urnveruly ct Utah in which micro-9 Only persons authorized to work with car. organisms infectious or nonintectious, are Cinogens $hould be workbig in a Carcinogen hDudIPd use area 1. Work with these agents I;hould be conf med
- 10. Work Area identification, Entrances to to a spcific well defined area in the laboratory.
all work areas, when chemical car;inogors are 2 Contammated materials including a!! bio-heing used, shall be posted wit permanent logicao such as animal fissues,9uids, wastes, and tissue culturo cells, in addihon to micro-yoe signs baaring the legend: ' DANGER - CHEMICAL CARCINOGEN Authonzed Person organisrns. Should be pbced to a marked con-nel Only " tmr.er and stenhred as seon after use as pos-
- 11. Access Control, Work areas,when chem. sible, and in any event. prior to cleanmg or ical carcinogens are being used. shall be eq. discarding the containers.
tered only by persons authunted by the prMca. 3 All personnel are required to wear 'ull pal investigator AccMs doors to work areas length laboratory coats and to remove them shall be kept closed when chemical carcino. befom leavmg the labotatory gens are being used. 4. Pipettmg by mouth is prohibited. S No tmoking, eating or drinkir;g is permitted within the laboratory facilities SUDSTANCES CURREN1LY REGULATED BY 6 Employees should be aware of the repro-THE UTAH OCCUPATIONAL SAFETY AND ductive hazards that may exist in laboratories HEALTH ADMINISTRATION AS CARCINO- wher e animal viruses, caremogens, or cytoto xic GENS: agents are used-
- 7. All personnel should wash their hands thoroughly before leaving these facihties.
Asbestos 8. Immunitation of laboratory personnel is 4 Nitrobiphenyl re .ommended when working with infectious alpha-Naphthylamine age t Methyl chloromethyl ether 9 Access should be limited to authorized 3,3'-Dicnlorobenridene (and its salts) personnel bis-Chloromethyt ether 10 Transfer 01 infectious agents is restricted beta Naphthylamine to vertical laminar flow hoods enzidine 11 B ohazard and hmited access signs are 4 Aminodiphenyl to be placed on the doors of all laboratories, Ethylenimine animal rooms, and storage f acibiles in which beta-Propiolactone these agents are handled 2-Acetylaminofluorone 12. Laboratory coats and other clothing are 4-Nitrosodimethylamine to be sterilized immediately after obvious con-Vinyl Chionde tamination. Inorganic attenic Benrene Harard ControlWork With Laboratory Animals Coke oven omissions Biomedical experimentation with animals necessitates hazard control to protect per-sonnel from injury or disease Control is also if the above hsted carcinogens are used fre- necessary to protect animals from diseases quently or in large quantities, more rigorous which may prevent successful completion of controls and practices are required and Safety experiments Although disease control is of Services should be contacted for pertinent prime concern, other harards can also be regulations. sonous and should be recognized =
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1 I p%.4 f LABORATORY SAFETY - 9 -
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[" ' 1 General Recommendations . - good laboratory practice and soun' d scienkifici O
. T IL Triorough training.in the handiing of a judgement. However, in an' adequatety isolated ! ]
- particular species _of anlmal shoWd be com. and properly eq uipped laboratory with correctly - s j if , ' pleted prior;to handston exputience. directed airflow, a scientifically and technically j competent investigator can' confidently work -i 2, Animal bites.are a source of significant _
even with the most hazardous agents, provided
~
, " infectious agents and ~ should' b'e reported promptly to the laboratory supervisor.' All em, the safety cabinets are. selected to meet the ,.
Lptoyees should complate an Occupational 11;. requirements of the work The investigatorL 1 ness form; which:should' be_ completed and should select the cabinet that meets the re-
, ; signud by thosupervisor, quirements for the maximum risks he expects .
3, Gloves should be' worn when' handimg- to enc (,unters Human etiologic agents are ( labor'alory animals, . , placed in four classes o' increasing hararde A j fifth class, composed- of dangerous anirnal
. 4. Allergies to iAimal proGucts and animals !
Ecart develop among laboratory workers Addi- agents are excluded from the United States j o tionally, disease agents are difficult to estimate, by law. - n
'Increfore; all Jaboratory personnel should re. Irnportant factors must be considered when duce the time of exposure tcianimals or animal planning experiments with - etiologic agents.) l8 s products. Face masks or respirators should be particularly with thosein Classes 3 and 4 These '1
' worn by all personnetc factors obviously vary from situation to situa-
; 5. Care should be taken when inoculating tionc Therefore, each investigator must use ,
animals with ne6dles; Self in'oculation with a scientific judgement in interpreting the classi-mg needle causes injury and possible exposure to fication Aerosol studies, passage in. animals and mfoction of arthropod vectors increase the 4 lj '
. needle contents and disease.,
6 Close contact with newly arrived animals, hazard, whereas strict adherence to -in vitro especially non-human primates. -is a disease expariments decreases the. hazard. . j hazard and should be avolded. Animals should / % Jne planning to work with etiologic d
< be~ quarantined before use, age should be aware of the animal agents 1n
- L 2
. _ h A veterinarlan or other trairmd profes- .Clao 5 which are excluded from the United 1]
- storal knowledgeable about laboratory proce. States by law (virus of foot and rnouth disease) 9 dure shouldi develop an]nimal health care and a USDA administrative policy (etiologic j
- program and monitor for zoonoso problems. agents of the following: African horse sickness, j
, B All sohd anima!-wastes'should either be African swine fever l Asiatic type strains of New- ;
storikred by autoclaving before disposal or castle disease, Borna' disease, bovine infec ,
~
l ,; L jncinerated. Carcasses r.hould always be incin. t!ous potechiat fever, contagious agalactia.of l' eraled<The autoclaving procedures should be sheep, contagtous bovine pleuro-pneumonia, carefully monitored to assure destruction of all - cutaneous bosnoitisis, east coast lever, ,
~
ephemeral lever, f owl plague, heartwater, loup < 3
- viable agents.
y : 9. All < animal carcasses which are trans- ing ill, lumpy skin disease, nagana, Nairobi- y [? 'pcrted shall be tightly contained arid properly
. labeled to provent exposure of personnel sheep disease, pox disease of camels, goats, and sheep, pseudotarcy, Rift Valley fever rin '
j p"
' derpest, teschen disease, vesicular exanthema, ?7 and Wesselstnon disease). 'I ETIOLOGIC AGENTSL {
principais of Classification 7
' General Safety The least hazardous agents are in Class 1.
-The.best way to maintain laboratory safety and those requiring tne greatest restrictions are . ,
~
is to . practice correct and careful laboratory in Class 4. Since the number of relatively or lechnique; includmg effective .decontamina. completely nonpathogenic agents is very large, ~
~
"!!on and sterlHzation procedures at all times, .
lishng all of them in Class I would be impracti. H._/ - 'The laboratory's isolution and contaminant re. cal Therefore, all agents which are not listed in
. quirements are to supplement, not to supplant. Class 2 througn 4 belong to Class I p 1
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i CLASS 1 - Agents of no or minimal hazard - C. pseudotuberculosis ; under ordinary conddions of handling. C. pyogencs, C. renale [ CLASS 2 - Agents of ordinary potential Diplocor r.u s (St re pt ococc u s) pn e u m o nia e hazard. This class includes agents which may Erysipelothrix insidiosa t produce disease of varying degrees of severity Eccherichia coil - all enteropathogenic from accidentalinoculation or in}echon or other serotypes means of cutaneous penetrabon but which are Haemophilus ducreyi. H. influentae contained by ordinaty laboratory techniques. Herellae vaginicola CLASS 3 - Agents involving special hazard Kiebsiella - all species and all serotypes or agents derived from outside the United Leptospira interrogans - all serotypes States which requito a federal permit for im- Listoria - all species pcrtation unless.they are specified for higher Mima polymorpha classification. This class includes pathogens Moraxella - all species which require special conditions for con- Mycobacteria - aH species except those i taminants.' hsted in Class 3 s CLASS 4 - Agents that require the most Mycoplasma - all species except Myco-stringent conditions.for their containment be- plasma mycoides, which is in Class 5 cause they are extremely hazardous to labora- Neisseria gonorrhoeae, N. meningitidis tory personnel or may cause serious epidemic Pasteurella - all species except those listed ( disease.This classincludes Class 3 agents f rom in Class 3 ; outside the United States when they are em. Salmonella - all species and all serotypes ; ployed in entomologicat experiments or when Shigella - all species and all serotypes l other entomological experiments are con. Sphaerophorus ecrophorus ; ducted in the same iaboratory area. Staphylococcus aureus CLASS 5 - Foreign animal pathogens that Streptobacillus monikformis , are excluded from the United States by law Streptococcus pyogenes or those'whose omry is restocted by USDA Treponema carateum, T. pallidum, and T. administrative policy. pertenue Note: Federally hcensed vaccines containing Vivrio fetus. V. comma, including biotype live bacteria or viruses are not bubject to these E. Tor, and V, parahemolyticus classifications. These classifications are ap- CLASS 3 plicable, however, to cullutes of the strains Actinobacillus mallei
- used for vaccine production. Bartonella - all species Brucel;a - all species Classification of Agents Francisella tularensis Classification of Bacterial Agents: Mycobacterium avium. M bovis. M tubercu-CLASS 1 - All bacterial agents not ncluded I SS in higher classes according to " Basis for Agent Pasteurelia muitocida type B (" buff alo" and Classifications" c'ther foreign virulent straind)"
CLASS 2 - Actmobacilius, all species ex- Pseudomonas pseudomalleP 7 cept A. mallet, which is in Class 3. Yersenia pestis Arizona hinshawii- all nerotypes 'usoA omme am mwed ter impan m mtmtata Bacillus anthracis " N o" Bordmella - all species Classification of Fungal Agents Borrelia recurrentis, G. vincenti CLASSI Clostridium botuhnum. Cl. chauvoei, Cl ' 3molyhcurn, f u n g al gents not mduded m NgMr Cl. histolyticum. nevvi i clams according to " Basis for Agent Classi-Ci septicum. Cl tetan, ' I heations' Corynebautorium dipthemm CLASS 9 : C equi. C haemo!yhcum Achnomycete uncludmg Nocardia r,pecies
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LABORATORY SAFETY 17
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Y!M .. . .. ,. . , S:' ' and Actinomyces species and' Arachnia Herpes viruses - except Herpesvirus simlae ;; hit o propionica)1 .; u (Monkey B virus) which is in Class 41 l.g ' LBalstomyces dermatihdis . infectious. bronchitis like virut- . . j] {g]ig3
~ Cryptococcus neoformans. Influenza viruset -- all types except A /PRB/ !.
(h y- Paracoccidioides brasiliensis- 34, which is in Class .1
'Langat virust 4
, a CLASS 3 j N[n s ~
- Coccidioides immitis - Lymphogranuloma venereumiagent J!
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Histoplasma capsulatum Measles ms ; y 3 Mumps virus. ._ _ . , y
-W h Classification of Parasitic Agents ; Parainfluenza viruses - all types except 1
-ma 3: Parainfluenza virus 3, SF4 strain, which is pg- y .- CL ASS . 1 Ein Class 1. lh j l1
- All parasitic agents not included in higher Polioviruses -- all types, wild and attenuated :
$g/gfQ yg j. classes according to " Basis for Agent Classi- Poxviruses +-- all types texcept Alastrim and :' 5 fp . ficatio n." Smallpoxi which depending on experi R
,, CL ASS. 2 ments, are in Class 3 or Class 4 .' O Rabies virus - all strains except Rabies-
?!( s _ . : Endamooba histoly'ica 47W' : Leishmania sp. Street virus;which should be classified irl P q i4 W Naegleria gruberi _ Cf ass 3 when moculated into wild animals m ,
- Toxoplasma gondii . or domestic carnivores 0 h i , > Toxocara canis Rooviruses - all types ~
.I (y " lim . Trichinella spiralis Respiratory syncyllal virus 4 [ Rhinoviruses - all types LTrypanosoma cruzi j kW l CLASS 3 - Rubella virus j iz?, ,
ISchistosoma mansoni Simian viruses-all types except Herpesvirus simlae (Monkey' B . virus) and Marburg
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M _ virus,'which are in Class 4 4 g 4 Classification of Viral, Rickettsial, and Sindbis virus S
$gg n Chlamydial l Agents Tensaw virus ~ ,
CL ASS .1. Turlock virus- 3
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' Class 1 includes all viratcr ickettsial; and Vaccinia virus: a y '!- '
, . chlamydial agents not included;in higher Varicella virus- q y "
; classes according to " Basis for Agent Classi- Vote rickettsia 4 g"g : fication," Specifically listed are: Yellow tover virus,17D vaccine strain j Tlnfluenza virus A/PR8/34- CLASS 3 9 q ' '
, Newcastle virus - strains licensed for vac^ Alastnm, when used in vitro -
p " cine use 'in U.Sc Arboviruses- all strains except those in [
)g Parainfluenza virus 3, SF4 Strain Class 2 ano 4 (Arboviruses in'digenous to ' #
lL ' s 4 = (These viruses are included because the the' United States are in Class 3- except
. Committee agreed that 'they are suitable for p}g
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; scierico experiments at a junior level.)
those listed in Claus 2.- West Nile and Semliki Forest viruses may be classified
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@ 1 CLASS 2 up or down, depending on the conditions -
-of use and geographical location of the y%
Q, l c:g Aderioviruses . Cache -Valley virus - human - all types laboratory) K' -Coxsackte A and B viruses ~ Lymphocytic chorimemngihs virus (LCM)' -
% Cytomegaloviruses Monkey pox virus d ..Echoviruses - all types l Psittacosis Ornithosis-Trachorna group of 1 p ei , Encept.mlomyocarditis virus (EMC) agents !
[ ] Flanders virus Rabms street virus, when used in inocula- '? J Hart Park viruses tions of wild animals or domestic carni- ! Hepatitis candidate viruses vores (See Class 2) L l[ , i. h jk. 6
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' . 1,8 .h Rickettsla-all species except Volo rickettsia one would expect in a college department of when used for transmission or animal microbiology and who have had special train-inoculation experiments ing in handling dangerous agents and are Smallpox virus, when used in vitro supervised by competent scientists. For aero-Vesicular stomatitis virus
- sol studies, passage in animals, arid infection Yellow fever virus-wild, when used in vitro of arthropod vectors, the laboratory should be
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"USDA permit abo mquired for import or interstate located in a geographical area in which the ranspon chance of accidental establishment of the CLASS 4 agent in a susceptible ecologic tocus is mini-Alastrim virus when used for transmission or mal. Requests for agents in Class 3 are signed _
animal inoculation experiments by the chairman of the department or the head Dengue wrus, when used for transmission or of the laboratory or research institute where animal inoculation experiments the work will be carried out. Conditions for con-Hemc rhagic fever aDents, including Cri. tainment include: mean hemorrhagic fever (Congo), Junin, 1. A controlled access facility; suite or room and Machupo viruses, and others as yet separated from the activities cf individuals not undefined. engaged in handling Class 3 agents and f rom the Herpesvirus simiae (Monkey B virus) general traffic pattern of the rest of the build-Lassa virus ing or laboratory. Marburg virus 2. Negative air pressure is maintained at the Mucambo virus site of work in a preparation cubicle or under a Smallpox virus, when used for transmission hood. Air is recirculated only after it has been or animal inoculation experiments dequately decontaminated through high c!fi-Tick-borne encephalitis virus complex, in. ciency filters. cluding R sian spring-summer encepha, i Atmal experiments, including. cage steri-litis Kyasanur forest disease, Omsk lization, refuse handling. disposal of animals, hemorrhagic fever, and Central European etc., are conducted with a level of precaution encephalitis viruses equivalent to conditions required for laboratory Yellow fever virus-wild, when ut , for experiments, transmission or animalinoculation experi- 4. Personnel at risk are immunized 'against ments agents for ivhich immune prophylaxis is avanable.
; Level of Competence and Physical Contain. CLASS 4
_ ment Recommended For Each Class Distribution of laboratones whose stalls have U leve s f competency equal to or. greater than
' The following recommendations desenbe one would expect in a college department of the level of competence and physical contain-microbiology and who have had special training ment suggested for working with agents of in handling dangerous pathogens and . are each class.
supervised by competent scientists. For aero-CLASS 1 sol studies, passage in animals and infection of Distribution to all users, no special compe- arthropod vectors, the laboratory should be to-T tence or containment required cated in a geographic area in which the risk of
- CLASS 2 accidental establishment of the agent in a sus-Distribution to laboratories whose staff s have ceptible ecologic locus is minimal. Requests for levels of competency equal to or greater than agents in Class 4 are signed by the director cf one would expect in a college department of the department where the work is to be carricd microbiology- out Conditions for containment include all CLASS 3 those required for Class 3 agents and the Distribution to taboratories whose statts have following levels of competency equal to or greater than 1. Work areas are in a f acility which is in l
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I , LABORATORY SAFETY . -
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effect a separate building, or they are sepa-rated frorn'other work areas by effective air-locks:
- 2. If the work arx is not in a separate build-ing, the entire area used for Class 4 agents has a separate air exhaust and negative pressure with respect to other areas of the building. Ex-haust air ls decontaminated by filtration through nigh efficiency filters or by some other sultable process. Class 4 agents are manipulated only in safety cabinets equipped with absolute filters.
_ 3. Access to work areas is restricted to indi- l viduals immunized or othorwise under specific . control. l
- 4. Protective clothing is worn, and it is de- )
contaminated before being removed from the i laboratory area
- 5. When an agent is used in entomological i experiments, the windows, walls, ficor, ceiling, and airlock of the work area are inseci proof, and pure pyrethrum insecticide or a suitable {
. Insect killing device is available in the airlock.
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E l-E CH APTER 111 INDU$7RIALHYGlifME . A ; .. J ) f L.N 'i L L 1 - 1 i L f M i h nants from exhaust systems, process vents, or INDUSTRIAL HYGIENE other sources.
- 6. Exhaust hoods should be designed and All atmospheres in which industrial pro- located to provide the necessary air velocity of cesses generate and/or liberate harmful con- 100 knear f t./ min.
centrations of gases, fumes, vapor, dusts, and 7 Inlets should be arranged and located so mists (creating harmful exposures by inhata- that workers are not subject to drafts of air tion, ingestion, skin absorption) at or above the having a temperature of more than 10=F. below threshold hmit values, shall be saf eguarded by room temperature. feasib!c engineering controls (a properly de- 8, in areas where dry grinding, dry polishing, signed ventilation system, etc ) or administra- cutting, or buffing occurs, suitable hoods or live controls (rotating personnel to minimize the enclosures that are connected to exhaust sys-individuals exposure, eic.) Such todustrial tems shall be provided, except as provided in processes include heating, welding, burning, (9) below. Exhaust systems shall be operded degreasing, plating, melting, curing, mixing. continuously whenever such operations ate preservation. etc Where these controls are carried on, and be capable of preventing con-not possible or practical and personal protec- taminants from entering the breathing zone. ! tive equipment is used,it must be approved for 9 Equipment operations, and processes t each specific application by Safety Services. may be exempt from the provisions of thid stan-dard when the concentration of any contami- , nant generated by the gnnding, pokshing or l VENTILATION buffing of metals does not exceed the threshold l limit. I
- 10. For maximum protection from exposure !
Mechanical Ventilation and Equipment to toxic fumes, vapor, and dusts, exhaust hoods l Where mecharucal ventilation equipment is and spray booths should be checked daily or i used to reduce the contaminant concentrations before each use. A vaneometer is recom- l to or below the specihed hmits, periodic testing mended for this purpose, and may be obtained i f;hould be done to maintain safe levels. Where from Safety Services contaminant concentrations are flammable, approved explosion-proof or other equipment shall be used in accordance with the require- AIR CONTAMINANTS 7 ment of the National Electncal Code. Chap- ! ter 5. Gases. Vapors, Fumes, Dusts, and Mists 'G .. Exposures by inhalahon, ingestion, skin ab-A Local Exhaust Systems sorption. or contact to any material or sub- l
- 1. Work space layout and construction shall stance at a concentration above those specihed
-include exhaust ventilahon requirements- in the Utah Occupational Safety and Health
- 2. Processes to be exhausted by a singie Rules and Regulations (UOSHA) Chapter G system should be located close together shall be avoided. Protective equipment con be
- 3. Where processes generate diff erent dusts. provided and used. as a temporary measure i fumes, or vapors which could. if intermixed, only. Safety Services must grant authonzahon result in an explosive atmosphere, such con- for this temporary measure y taminants shall be exhausted by separate sys-tems 50 as to eliminate this possibihty l Control Measures 4 Provision should be made for the entrance 1 Feasible administrative or engmeenng con-of clean, lempered air into the building to re- l tro!s such as work rotation _ time hmitatio%
place air removed by exhaust systems The i process or local exhaust ventilahon and:or volume flow of such make-up should be j process isotahon. can be used to lirmt total en-equal to or greater than the exhaust rate vironmental exposure provided a ceilmg hmtt is
- 5. The intake for the air supply shall be so , not exceeded as shpu!ated by U O S.H.A J located as to prevent the intake of contami- ! standards 1
o lRbl%illAIMYMtk hhN MM2hk$hh$$k (( h h ,h [.M, Hazardous or Potentially Hazardous Atmo. l spheres PERSONAL PROTECTIVE ! EQUIPMENT 1, Contined Work Spaces: Bef ore employees are imtially permitted to enter any confmed Head Protection work space (tank. underground structure, vat. 1, Employees should use protective head etc ), the atmosphere within the space to be gear whcn workmg in areas where there is a entered shall be tested to determine the con, danger of head injury from impact, from f alling centrations of flammable vapors or gases, toxic ct flying objects, or from electrical shock and i atmospheric contaminants and oxygen. If such burns. tests indicate that the atmosphere in the space 2. Helmets for the protection of employees ) to be entered contains (1) a concentration of against impact and penetration of falling and j flammable vapor or gn greater than 10 per. flying objects shall meet the specifications con- l cent of the lower explouve limit, and/or (2) a tained in ANSI Z891 - 1969. Safety Require-concentration of toxic contaminants above the ments for industrial Head Protection. threshold limit value and/or (3)less than 19.5 3. Helmets for protection of employees ex-percent oxygen, appropriate control measures posed to high voltage electrical shock and shal! be instituted. Control measures may con. burns shall meet the spectUcations contained sist of forced or natural ventilation, use of per, in ANSI Z89.2 - 1971 sonal protective equipment, admmistr alive con ~ Hearing Protection l trols or a combination of these. Wherever it is not feasible to reduce the noibe levels or duration of exposures to those ; Entry and Work in Toxic or Flammable Atmo, specified in the table below, Permissable Noise ! spheres Exposures, ear protection devices shal! be used 1 in those circumstances where a person must Permissible Noise Expo!,ure ! enter an area before a sale levelis achieved, (in
' order to set up explosion proof ventilation hundI M Dorat.on per dB ( A) Mow equipment, etc.), approved personal protective day hours mettu responne 4 i
equipment for the hazards mvolved shall be g 99
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6- 92 4 95 Emergency Procedures 3 97 l 2 100 1 1' 109 ' In all cases when an employee is stationed j outside a compartment, tank, or space as a j j f gg terider for the personnel working inside, he j 1, orie33 m shall have immediately available for emergency ; use all necessary personal protective equip- i Eye and Face Protection ment When a tender is stationed outside a j 1. Employees shall utmze eye and f ace pro-compsetmerit for personnel working inside a i tection equipment when machmes or opera-compmtment. etc he shall wear the personal tions present potential eye or f ace in,iury f rorn protecto e eqd; ment if r,e n exoosed for pro- physical chemical or ramtion agents. longed pOYhJds WIHch may De haldroOur !U his 2 Eye arid f ace protechon eqmpment re health. Rescue equ pment appropnate for the quired by this part shall meet the requirements hazardslnvolvfd in the work assignment should , specified in AN5! Z87.1 - 1968, Practice fo-ba provided e g. harness lead. dnd self con- l Occupat,onal and Educational Eye and Face tained breathing appara!US lor workers ente' Protection ing contined spaces with patenhal for tox>c 3 3 Employees whose vis an requires the use gaSet ! Of corrNtive lerm in spectacles who art. re-
y I i INDUSTRIAL. HYGIENEm ' - Q, ', 22 quired by this part to wear eye protection, shall - inspected regularly and maintained in good be protected by goggles or spectacles of one condition. Gas mask canisters and chemical ot the following types: cartridges shall be replaced as necessary so
- a. Spectacles with ANSI approved protec- as to avoid undue resistance to breathing. . .
tive lenses. 3. A light yet comfortable fit is the first step
- b. Goggles that can be worn over corrective in proper selection of a respiratorf To accomp-spectacles without disturbing the adjust- lish this Safety Services will perform a qualita- .
ment of the spectacles. tive fit test to assure a tight seal with minimum O. Goggles that incorporato corrective leakage for employees wht se respirators. ; lenses mounted behind the protective lenses. Hand and Foot Protection Employees shall use hand and foot protec-Laser Beam Eye Protection tion when machines or operations present
- 1. Employees whose occupation or assign- potential injury to the hands and/or feet from -
ment requires exposure to laser beams shall be physical, chemical, or radiation agents, furnished suitable laser safety goggles which will protect for the specific wavelength of the Safety Belts and Lifelines laser and be of optical density adequate for 1. Lifelines and safety belts shall be used the energy involved. only fm employee safeguarding. Such devices ,
- 2. All protective goggles shall bear a label must be used where there is a danger of falling identifying the following data. from 6 feet above the ground or a platform.
- a. The laser wavelength for which use is 2. Lifelines used in areas where the line may .
intended be subjected to cutting or abrasion, shall be a
- b. The optical density of those wavelengths minimum of b-inch wira core manila rope. l c, The visible light transmission 3. All safety belts shall be drop forged or pressed steel, cadmium plated in accordance Respiratory Protection with Type 1, Class B plating specified in Federal
- 1. In emergencies, or when controls f ail of Specification 00-P-416. Surf ace shall be -
are inadequate to prevent harmful exposure :o smooth and free.of sharp edges, employees, appropriate respiratory protective devices shall be used- WELDING CUTTING, HEATING
- 2. Respiratory protective devices shall be AND BRAIING
. approved by the National Institute for Occo-pational Safety and Health or be acceptable to Welding or cutting shall not be done in the the U.SL Department of Labor for the specific following situabons in the presence of explo-contaminant to which the employee is exposed- sive atmospheres; and in areas near the stor-age of quantities of readily ignitable materials.
Respirator Selection The physical and chemical properties of the Acetylene Generation contaminant, as well as the toxicity and con. Acetylene sha'l not be generated, piped or ; centration of the hazardous matenal shall be utilczed at a pressure in excess of 15 psig (30 ! considered in selecting the proper respirators psia) The use of hquid acetylene is prohibited, Arc Welding and Cutting: Grounding issue, Use and Care of Respirators The frame or case of the welding machine ;
- 1. Employees required to use respiratory racept erigine driven machines) shall be protective equipment approved for use in at- grounded under conditions and according to mospheres immediately dangerous lo hfe shall ine methods prescribed in Article 630 of the be thoroughly trained in respirator usage Em- National Electric Code.
ployees required to use other types of respira, tory protective equipment shall be instructed Press Welding Machines ; in the use and limitations of such equipment. AU press welding machine operahons shall ( 2 Respiratory protective equipment shali be be effectivoli guar led by ruoNction simuar to
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c that prescribed for power press operationsJ the other side due to conduction or radiation o , _ Shielding of Welding Machines (preferably by relocating combustibles), Where : j
- Shield guards of opaque safety glass or suit- combustibles are not relocated, a fire watch on
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Eable fire-resistant material shall be installed at the opposite side from the work sha!) be proy nthe point of operation to protect the welder and vided; g
.I Lother employees from flying sparks and ultra- 5, Cutting or welding on pipes or_ other metali
- violet radiation exposurec in contact with combustible walls, partitions, ,
q A - Welding Bays 4Where arc welding is regu. - ceiling or roofs shall not be undertaken if the 3 larly carried.on in a building, the walls of the _ work is close enough to cause ignition by con. ( ductionf
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g y twelding bay should be painted with a finish of d
- I ilow reflectivity. . .
- 6. Portable fire; extinguishers, appropriate Welding Booths- Arc Welding - The worker for the type of possib" fire, shall-be concen- -9
- should be enclosed in an Individual booth trated at the work arem ..
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' painted _with a finish of low reflectivity or shall 7, Surface coatings that may contain such ; j be enclosed with noncombustibl0 screens simia hazards as lead and zinc chromate should be q
. larly painted, Booths and screens shail permit removed before cutting or welding.
circulation of a'ir at floor level. . 8< Prior to welding, the University Fire Mar- , Adjacent Work Spaces- Arc Welding-Work- shal's Office must_ be notified by written notifi-
' ers or! others adjacent to the welding areas cation, or by phone if time is not available, ,
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'shall be protected from the rays by noncom- j bustible screens or shields or shall be required Chlorinated Hydrocarbons-Degreasing q
_g : to wear appropriate _ goggles. Degreasing or other cleaning operations in- 1 ij Fire Protection volving chlonnated hydrocarbons shall be so 'l
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- Precautions Before Welding -- Before cut- i cated that no vapors from these operations
- ting or welding is permitted, the area shall be will reach or be drawn into the atmosohere sur-
_ inspected by the individual responsible for r unding any welding operations in addition,
' authorizing. cutting and welding operations. trichloroethylene and perchlorethylene should :
The following precautionary measures should not be used where gas shielded welding oper-
' be taken before beginning to weld, ations are conducted.
0 Where :combustibic materials such as Containers That Have Held Combustibles .I paper clippings; wood shavings or textile fibers No welding, cutting or.other hot; work Lshall ~! L are on the floor <the floor shall be swept clean be performed on used drums, barrels, tanks or .
-for a radius of 35'!oet, Combustible floors shall 4 other containers until they have been cleaned {
be protected by fire resistant shields so thoroughly as to make absolutely certain -
- 2. Where practicable all combu;tibles shall that there are not flammable residues which be relocated at least 35 feet from the_ work site. when subjected to heati may produce flam- j$
d ; Where relocation is :Impracticabtef combus' mable or toxic vapors. Any pipelmes o_r con- a ?1 '.tibles shallLbe protected with flamo-proofed nection to the drum or vessel shall be discon- 9 } covers or otherwise shielded with metal or cur- nected or blanked. R, . tainsl Edges of covers at the floor should be
, tight t_o prevent sparks from going under them. Ventitation !
7, 7 This precaution is also important at overlaps Mechanical Ventilation shall be - provided { p t where several coven are used to protect a when welding or cutting is done: iarge pue. 1. In a space of less than 10,000 cubic feet f 3 Where cutting or welding is done near per welder. ,
- Walls, partitions 4 ceilings. or roof of combusti- 2, in a room having a ceiling height of less ,
Die construction, fire-resistant shields or than 16 feet j guards shall be provided to prevent ignition. 3. In confinect spaces or where the welding ; i,- 4. It weldmg is to be done on n metal wall, space contains partitions, balconies or other ; O partit,on. cethng or roof, precautions shall be structural barriers to the extent it they sig-taken to' prevent igmtion of combustibles on nificantly obstruct ventilation. i s [! Ei :
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- 4. On materials or under conditions likely to welding arcs, xenon discharge lamps, laser, cause the release of harmful quantaies of toxic and certain fluorescent tubes being the pre-airborne contaminants. Such ventilations shall dominant man-made sources. Major biological be at the minimum rate of 2 000 cubic fest per effects of prolonged intense exposure to U. V.
minute per; welder, except when local exhaust mdiation a'e irritation and damage of eye tis-ventilation or supplied air respirators are pro- sue, sunburn, and possible skin cancer. vided. Most standards are based on the reddening Local Exhaust Ventilation - Mechanical lo- of the skin in response to U. V. A good rule of cal exhaust ventilation may be by meat s of thumb is that a reddening of the skin, to U. V. freely. movable hoods intended to be placed by exposure indicates an over-exposure. the welder and provided with a rate of air flow , The following guidehnes apply to U. V. radia-sufficient to maintain a velocity in the direction tion producing equipment: of the hood of 100 hnear feet per minute in the 1: Never look directly at a source of U. V. zone of welding when the hood is at its most radiation without protective eyewcar designed remote distance from the ' point of welding. to absorb U V, radiation of the wave length (Note: increased rates of ventilation may be encountered required for specific airborne contaminants.) 2. Wnen weld ng, wear specially designed gog es or face sM and pope cWng Personal Protection to shield eves and skin. Eye Protection - Helmets or head shields 3. All employees should avoid unnecessary shall be used during all arc welding or cutting exposure to U. V, sources. operations. Goggles or other suitable eye pro. tection sha!! be used during a!! gas welding or infrared Radiation cutting operations. Eye protection shall be pro- Infrared radiation (l. R.)is emitted by a large vided where needed for brazing operations. variety of sources including the sun, heated Protective Clothing - All welders should metals, electrical appliances, incandescent wear f!ameoroof gauntlet gloves Flameproof bulbs, iurnaces, welding arcs. lasers, and aprons may be desirable as protection against . plasma torches Exposure to I. R. can cause radiated heat sparks. Cotton clothing, if used, seriovs permanent damage to parts of the eye should be chemically treated to reduce its com- (cataracts) and may burn the skin. bustibility. All clothing should ue reasonably 1 All employees and students should wear free from oil or grease. For heavy work, fire re" goggles designed to screen out I. R. radiation sistant leggings, high boots or other equivalent when working with an I. R. source. protection should be used. 2. Clothing that completely covers the body Respiratory Protection - should be worn when working' with or around
- a. Respiratory protection devices should be & Mah worn when welding metals which pro-3 If necessary, shielding should be used for duce fumes such as cadmium, nickel or rotection chromium in larger quantities than can be readily exhausted by local exhaust venti-lation. Microwave Radiation
- b. All respirators should be NIOSH approved ,
Typical primary sources of rmcrowave radia-and fit tested by Safety Services t tion are klystrons rnagnetrons, backward wave l osc:llators semiconductor transit time devices. i induction heating equipment dtathermy equip-ment and solar radf ation Mtcrowaves can
. NONIONIZING RADIATION cause sermus damage to vanous parts of the body because of us heahng effect-Ultraviolet Radiation 1 Employees shotl not be exposed to micro-The sun represents the major scurce of uttr+ wave densrties .n excess of 10 milliwatis per violet (U,V ) radiation with hgth arid tow per.s. sat.are centimeter for penods of 01 hcur or sure mercury discharge lampt plasma torches i mo<e
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a: - p 4,nsy < . /2[ Employees or. studentsL who work ,withi :Codese+mcluding >those listed below[ , E [e if y/micrbwave energyisbodid be trained friproper . ialNFPA;=1gFire Protection Code L lb.NFPA *$4 Na_ti_onal Fuel' Gas Cod _e : h ! y@gWhpypmational procedyre measures and shouldpotentjal hazardsJOvens and Furnaces
-3 Engineering control be tc. NFPA;=,86A
~
4O ykV dLNFPAp86B1r$1ustrial Furnacesj _ . ' $"; %@y@yOp/f@@j g%e(ri!considefation%er any us'e p fotective equip _ men ( j h 1 .e NFPA = 800 industrial Furnaces Special f H gM w42 Engineonng contrpis to be consider od are : E Processings . , .. O ' MMstdelding[enclosurespinterlocks to prevent; f NFPAw 91. Blower and Exhaust Systemsc - , iThe electrical-wiringchestingf elemerit$l hhM,' j%lsMod dummy load pg terminations?acsidentatie.nergipng ofofcucuitsl warning sigi contlots,llocatiordand operation electrici hdd 04 M tired- kilnsLovensfahd-furnaces should meet! [hypp' ,
' f flasct Eqisipment?
all applicable National. Fire1 Association Codesi including those listed belod , (j "
$ 0nly qualit:cd arid tr'ained employees shall; a NFPA' =1 Fire Prevention Code MM@ < !E ' y" ' 4 Lbe'asslined to iristall, adjust and operate laser biNFPA = 70 Na_tiona! Electric Code
- c. NFPA =86A Ovens and Furnaces hi+ f6quipmenty T 12; Proof [ohthe qualification of the ' laser d NFPA- x 868 todustrial Furnacess ,
gj%ii Sequipment' operator shall be.available and..in :ec NFPA x86C Industrial Fumaces Speciaf _ ; ' y@f' h[R6 yp,,GP
'Mtioss'eusion of operator at all times.
L3(Employeesfwheni working "in areas ,in . Protection
- f. NFPA x 91. Blower and Exhaust Systems: ~
*+ '
c Which~ potential exp' o sure to direct or reflected ' 4. Fumaces and kiins st ould be _operatedi 1
$" ,4
' Q' oni_y in rooms that.are properly ventilated and y p#? i Llaser lightgreaterthan 0.005 watts'(5 milliwatts) air conditionedfit necessary.
Uexistkshall; he (provided- with- antilaser eye, .
, 1 s i ' prote6tidn1
~
AFurnaces and kilns that use hydrogen gas ; l" i gg M : $4f Area 9 fin which lasers are used shall be; lot operati_on should have tholhydrogen gase exhaust vented outslde land, should meet-'alli
$pg 4 Y ' fpofited with standard laser placards _- ,
P hini /5) Beam 1 shutters oricaps shallbe utilizec, - applicable Natio'nal.Firo Protection Association? y [@7 4' 1 , M
' IisI noti 6actuMlyjequitsd/When the laser is lef t t the lasei turned off, when f aser transmission Codes includmgtthoselisted belosvi ,
a NFPA ?= 50A' Gaseous l Hydrogen System'
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q M ini ' Nmuttended kiraa : substantial-petiodsof-time; .bJNFPA"x.68 Explosion Venti;ng [
,J 5subhias dOIirT Idnch. hour, overnightL or4atL . c. NFPA1=,860 industrial Eurnaces :Special! ,'
Processing
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! 1 ibhange of Shiftsithe lader should be turned off.
; j6d0nly mechanicalfor electronic means - 6/; Gas fired furnaces and kilns shouldtbe Myf ishould be(ussd as a detector for guiding the designed to;elirmnate the possibility of explo-C ' [lnternhl alignment of the laser sion when hghting the apparatus. ,
q Mj N 7 ~ 7. Goggles designed to' protect the eyes f ro$n O 11Th%1aser beam should not be directed at Jemployees1 ultraviolet- and infrared radiation should -be hp4. w m z t , 'B$aser ' equipment 'shall bearf a label to worn when working around furnaces and. kilns , q& ' + [ indicate maximum ; output; at temperatures'in excess of. 700'C.- . j' g 7- 8. Eye and face protection should be worn i W - when working around-a furnace or klin that is-pn thas We pods" as Mne case of some: 4 ' " NS"AND FURNACES ceramic kilns. d- ^
! 9. Furnaces and kilns constructed of. fire
'f y Att kilns and furnaceswhether gas or elec" brick and mortar- should have the moisture d 2 ,
itric should be designed to prevent the furnace dried from the mortar and bncks slowly.This is p 4' fron] over heating' best accomphshed with a slow temperature
- 72. Tho; gas supply, plumbing, burner con- heat up of long duration. Excessive heating of -
p("79 , trolsjyocation.and operation of all gas kilns' wel bricks and mortar can cause structural f 'l furnaced and Ovens should meet all applicable f aHure and explosions fgg, LNationaf Fire Protection Assocmtion (N F.P A.) 10. The support structure of aD furnaces and g m f 7,.. ,,[ __ hr Ws -f y 6 i ht I Q l sq fhY ,x -$ g 'e , ;
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, 1- -, 3 INDUSTRIAL.tiVGIENE ' . ' ~ .
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-: .~ 26 kilns should be designed to support the weight .
-of the kiln or furnace.at the highest operating I temperatures f or which the f urnace is desiD ned. 4
- 11. Metal pouring is a particularly hazardous operation, due to the possible presence of im.
purities in~ the molds, ladies, pouring troughs, or the metalitself which could cause " splutter- i ing" or puddling.
' 12, Individuals operating metal furnaces or ;
kilns must be provided with and required to j wear approved eye shield, heat resistant gloves ' and' aprons, preferab!y of non-asbestos ma. p i
'- terials.
l: 13. The appropriate class fire extinguishers l should be immediately availatna in the furnace area.in the event of a fire. i I, ( 4;
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>CHAPTERIV? ~ %j W% 3 g;fy ;. :: n; ' -m i
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- 2JWhen medical treatmentE!s required for?
gr e iWORKER'S. COMPENSATION- _ minor: Injury?the employee may go to the1 Uni f
'/1 versity Hospital Emorgency Room or to'a physte '
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f it is the responsibility of the Un!versity to prof clan of his/her choice. The University ot Utah /
@1 4 Ovide af safe _ work environment:and to' require Occupational ' injury /IllnessiReport1must be' ,
b .x i f compliancewithoccupational_safetyand health; completed within 24 hours by th's employee and J
]Qi ,,a istandards in order 3that work related injuries - his/her supervisor and sent to Safety Servicesc 4
m (and-illnessoc be ~ reduced to a minimum. It asi Lthe resr onsibil.ity: of ;inspuctional , personnel,-
' Reporting of Accidents _Not Requiring Medical; i ' y : administrators and people engaged in a super. Malment .
,g1 [visoryccapacity to p'rovide for. safety in the en, in work-related injury / illness cases, wherei '
. o , vironment and operations under their control? : medical treatment is unnecessary, the'Univer.
M " IHowever(should a1 work;related? injury occur; sity of Utah OccupationalInjury/ Illness Report 7 u 4
. it is _the joint responsibility of the employee and must be completed withinl24 hours by the em-k \ [ supervisor.to complete the~ University of Utah ployee and his/her supervisor and returned to O >
; Occupational.-Illness and iniuryf Report land . Safety Services.
;,1 .
'g isubmit It to Safety ServicesTvithin 24 hours of Compensation of " Lost Work Days" w othe illness or accident. (if the medical condition - '
, i(k j. a ' Jof :the 'emplojee allows;): - 1 When the -attending phisician - requires . ,
#+ . ;1 .3 that an employee be off the job for more thanu
, y : Def tnlilons.
three days (due to anloccupationallinjury/Ill+
." : Occupallonallnjury -- is any injury such as a ness) that employee is then eligible for Workerfs '
,Y ., cut; fracture,= sprain; etc. which results frarn ' Compensation " days lost" payments.:
U Lan accident _ or from'an exposure occurring in - 2. In order to initiate, these _" cays lost" pay-- 4 cthe work environment? ments. Safety Services must have recolved the i D"s . 10ccupational ' illness _ls ariy ' abnormal Occupational injuryilliness Report. After verl< P ' 1t ying the claim, Safety Services will submit the; condition or disorder of the employee ;other. fl <
! thsn one resulting from an occupational injury, report to State InsuranceuFund after which:
W fcaused by exposure to environmental factors State Inasrance Fund will initiate action; D,' associated with employment. It includes Ecute 4.in accordance with:the Worket's Com-L and chronic llineshss or diseases which may be pensation Act, payments to an employee a_re p
- caused by inhalation. absorption < ingestion, or ' based _on a percentage of salary and number' direct contact of hazardous substances found . : of eligible dependents; .
1 v inlthe workplace or conditions, 4 Employeo Services Center ^ will receive:. p' 4 - Lost Work Days- are those days which the Worker's Compensationt" days lost" payments-from State Insurance Fund; Accrued sickleave. leinployee would have worked ,but could not
~
because of tecupationalinjury or illness The will be utilized t.o make up the difference bor
! , number of days includes all days lwhether they ; tween _the- Workeri Compensation -payment" d
p
- are consecutive or not, ~
and the-employee's regular weekly pay'.until
. or unless sick leave is not available. Employees';
L .
, -: Reporting ..of Accidents ' Requiring Medical are eligible for _" days lost" compensation only e
f g 1 Treatment l after 3 days off-the-Job. Those initial 3 ' days;. y ', s 11; Serious injuries which occur on campus will be reimbursed only af ter more than 2 weeks -
- (or within close proximity to campus) should off the job (including weekends) u .be-treated immediately at the University Hospi-
. " 1tal Emergency Room. The -Safety Services Investigation .
j @ Office shall be notified within one hour, The - 1. Reported incidente which are considered + Un_iversity-of Utan Occupational Injury /tlinet.s to be of questionable validity will be investr 1 Report must be completed and sent to the gated. and if appropriate. compensation for the T . Safety Services Office within 24 hours by his/ incident will be challenged. -l f her supervisor and the employee (if medical 2, Reported mcidents mdicating hazardous ! condition allows). working conditions or practices will be investi-f i
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yi- _ YA - - - _ _ _ _ _ _ _ . . _ . _ .~ _ .- _ _ .. - _ - - o GMPh0V$E$$k TMMgdWMMi?@ }MM,;f f 3 h gated, and if necessary, Safety Services will health record which may help assess the rela-initiate action through the department head to tionship of future medical problems to work have the conditions corrected, exposure Safety Services Division will help evaluate Record Keeping substances and /or environrnental or employeo 1, Federal regulations issued under th9 conditionu to determine if periodic health as-Occupational Safety and Health Act require sessments, return from illness physicalsi job that records of work related injunes/ illnesses transfer examinations, or separation, termina-be maintained for all University departments. tion or retirement examinations are needed. The Safety Services Office will maintain these Departments are required to alert Safety records An annual summary of work-related Services -if health hazards aust in their area. injuries / illnesses will be recorded on OSHA l Utah state laws require that employees ex-form 200 and be posted in each %ce Presid*nts posed io the following substances receive othce from February 1 to March ? each year- health monitoring services: The Safety Services Office will complete each 1. Inorganic Arsenic form and distribute them for posting High risk 2. Carcinogens departments will receive bimonthly reports of 3. Lead injuries / illnesses in their area. 4. Asbestos Health momtoring will be recommended and HEALTH MONITORING arranged by Saf ety Services. Payment f or medi-cal exams and laboratory work will be made Health Monitoring examinations are de- U M b"N * - signed to evaluate the health status of the Any additional problems which are identified individual in relation to the work environment coring the examination regarding health of the = in order to safeguard against adverse health empt yee and/or safety of the employee s effects from exposure to specific materials or workplace wil! be brought to the attention of processes. There are several forms of health University of Utah Safety Services monitoring which the University may utilize. If an employee does not agree to receive physical examinations and/or medical survelb Health Monitoring or Medical Surveillance: lance, a waiver, releasing ihe University from A health status evaluation conducted to assess rep nsibi!ity must be signed by the employee. the interaction of the employee and his/her work environment. Preplacement Examination: An aid to suit-able lob placement. Under special circum-stances, OSHA requires examinations as part of a medical survelliance program. } Periodic Heatth Assessment: Medical exam- ' inations performed at intervals to evaluate the ; health status of the individual in relation to !
. hazardous work conditions Return From lliness/ Absence Assessment: ;
Employees returning to work following illness or injury may require reevalaanon to assure theh continued fitness for their regular job. Job Transf er Evaluations: E xamm ations con-ducted when an employee is transf erred into an operat>on having known hazardous exposure , Separation, Termination and Retirement , Examinations: Post-employment examinationt ; may be recommended to provide an accurate i
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WMW rw - t wppcn 1 j e xi . . iqe ' GENERAL SAFETY -
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V j i',' , m . . , . M F 9EClose cplinder valves when not in use'as ' 4 y LCOMPRESSED GAS; CYLINDERS!-i follows7 .
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,s :a; Close main tank valve, u & -
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~ b;Open; low pressure valve,
- s Gas Cylinders map contain up 10:3,000 psi c. increase pressure on 'pressuro' regulator j
. 'pressuret Accidents have occurrod when the:
+ . -
gg bleed regulator assembly.- pg , m"-
; heads of thesofcylinders were broken off. Es; id[Close lo'w' pressure valved W' f 6 aping gases create jet action of sufficient force e Set' pressure 1regulatorEcontrolfto aerof i_
9 7t o propel the cylindersf through the walls of pressure, dt 1 lbiJildingsgereating Dres and injuring persons = > p' 5E fin;the vicinitti flammablo gases crehte addi-- . Removal '
< tional_ hazards of:cato!ytic actio.n or oxidation- ' 1.?A cylinder ofla nonsq'vifiable gas should, t vunder certain conaltions; '
always contain more than_100' psi of. postilve O c pressuretat 100 psi the cylinder is considered .
, 1
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' identify cylinders contents! by a stenciled 2. Close valves on. empty cylinders and mark (
'j the cylindersj" Empty".or,'?MT" with atsleast lh' ' label.or-tag attached to Itf Do not rely on color >
j J three inch letters, h y q'. s (code as this'will vary from supplier to supplier, 3, Never. attempt to rehil a cylinder:orirnh r gases in a cylinder. Call Sto'res and Rec 6iving!
% . Transportation at ext. 8671 to pick up empty cylindersc Valve protective capsJmustLbe > fastened 4. Return allInfreq'uently used gas cylinders s g '*
. tightly tolthe cylin, der prior to moving; to tho Stockroom,- regardles_s of pressure 1 g _ All cylinders larger t_han a lecture bottio must t
, i be tratisported by a' gas cylinder hand, truck Usage.
% Nith safety chain _in_ usee Dolnotiroll or ' drag Hydrogen cylindors:are; permitted only in 4
fcy.inder;toflocationion l arrtval at the point'of, specially designated . laboratories,tH drogen 3 ' ouserthe cylinder should be firmly fastened to icyl{nders should be stored in a coolicleani and - g $ preclude, accidental t_oppling. well 7ventilated areat protected from the weather - m ;or direct rays of the sun"and away from large h, g
-lInstEl!Ntion,g-
... 2. . .
amounts of fiammable solvents. Do-not store : oxidizing gases with flammabJe gases, All cylin- m
.VGrou:;nd all gas cyhnders. ,Y 4R_ +
EClean valve seat of any dust or debn.s-ders should be~ capped when.not in;useg . Stores and Receiving' deliver compressed
} ' '
3 Afpressure regul.ator of suitable design, (for pressure and type of gas, must be employed gas _ cylinders within 24 hours unless a special- y" ly gas that;is requested is_ out of stockDThis"
;(see vendorsicatalogues for information), '
makes storage:of cylinders unnecessary.- 4f Do4not force connections or use home- - -- g , . made adaptors . ql
+
, :5. Do not use glyctrin or oil when connect
- ELECTRICAL SAFETY L ^V Mp
' i ling pipes orl regulators to gas cylindersc
_. "q
>M - Gull the' cylinder is to be connected to rup- 1. All electrica! installations, both fixed a'ndi d@d , p~ I turable ettuipment e.g. laboratory glassware, an { portable shall conform to the requirements of ' '
Tadequats safety trap should be inser_ted in the - the National Electric Code (NFPA 70L
]@, '
s linesi 2. No unauthonzed person shad tamper with - :q
,, 97 A closed vessel must not be -used for electrical fuse boxes, alter emsting wiring or a
- 1 reactions where pressure may be generated- install wiring. When electrical trouble develops. 9
,,, Jmless it is equipped witn a venting valve, a 7 pressure gauge. and a rupture disc or sprmg- 1 inc Shop. or for installation, notify Plant Operahons Elec, ] y~ : loaded relief valve- 3. Appliances that are deemed unsafe by { .;. f 8. Test all connections for gas leaks with a i Safety Services shall be removed %(f' J
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soap' solution or leak-test solution. i 4. Appliances available for use shalt meet d 1i
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s , _ . . _ . .y _ . . _ . _ i l si . DENERALSAFETV _1ilR; T WMfA&f f, i f - J . 30 i L ,, the requirements of this section as though they j shall give the following proper instruction for are in use. j their safe operation: 3
- 5. Hot plates, coffee pots, electric irons, 1, Protective eye equipment shall be used heating elements and other special heating when operating machines which could cause j equipment shalt be placed on noncombustible particles to be discharged in such a manner ,
surf aces They shall not be closer than eighteen. as to cause injury. l g inches to any combustible wall. Some of these .
- 2. Ground all tools unless double insulated. '
items may not be a!! owed in certain areas on { if tool is equipped with three-prong plug, it a campus. should be plugged into a three-hole electrical
' 6f Live parts of electncal equipment oper- receptacle, the adapter wire must be attached ,
atin0 at 50 volts or more shall be guarded , to a known ground. Never remnve third prong. against accidental contact. } 3. Keep guards in place and in working ,
'd"'
Electric Panels [
- 4. Keep work area clean. Cluttered orcas
- 1. Know the location of circuit breakers in and benches invite accidents. ;
your workplace' 5, Avoid hazardous environments. Do not t
- 2. Sufficient access and working space shall use power tools in damp or wet locations. Keep be maintained about all electric equipment, and ! work area well lit. Do not work around highly . t electric panels. j combustible rnalerials. I Electric Cords j 6 Don't force a tool it v'ill do the job better 1, Extension cords and electrical apphance ! and safer at the rate for which it was designed.
wiring shall be maintained in good repair and , 7. Do not splice an apphance cord. If you must bear the Underwriters Laboratory Label , accidentally cut the cord or damage the insula- l (U.L.)er meet the requirements of the National ! tion in any way, do not attempt to repair he i Electric Code (NFPA 70). , cord yourself. Have authorized personnel re- 3
- 2. Extension cords are not to be usea out- .
place the cord immediately. Never wrap cord ( side the room in which the fixture outlet is 10- around shoulder when machine is operating. L cated. 8 Do not abuse a cord Never carry the tool
- 3. Under no circumstances shall any ex- by the cord er pullit to disconnect from a re- g' tension cord or electrical cord be spliced :
centacle Keep the cord from heat, oil and sharp '
- 4. No more than one extension cord shall ba l edges.
used for each piece of electrical equipment. 9. Secure your work. Use clamps or a vise to
- 5. Flexible cords and cables are not per- hold work. It's safer than using your hand and i mitted as a substitute for fixed wiring. and are , it frees both hands to operate the tool. j not to run through holes wails. ceihngs floors. 10. Do not overreach Keep proper footing ,
doorways, wmdows or other openings . and balance at all times 1 6< Extension cords are not to be draped over 1 11. Disconnect tools when not in use; before doorways, windows, furniture, fixtures, pipes or . smicing; when changing accessories such as other objects, and they are not to be placed ' blades, bits, cutter, etc.
- under carpet, rugs, or heavy objects. 12. Know your power tool Learn its applica-
- 7. All electric cords shall be properly bons and limitations as well as the specific po- i grounded when in use 1 tuntial hazards pecuhar to the tool.
8, Household-type extension cords shall not _ exceed eight feet m length. POWER MOWERS j POWER MACHINERY AND r EQUIPMENT Supervisors should inform emolayees about
- the safe operation of power mowers and the maw causes of accidents with Imyn mowers _i Each supervisnr shall allow only emenencN which include l personnel to operate power machmes and 1 Contact with the rotahng blade-This i
- . _ , . . . , , , - . . m _ _ _ _ _ _ . _ _ . _ _ _
y\ w' M > ' _.._____._,--a,__.a_._.__.w_ __ Y + s g e 3 GENERA WAf W . V M L ) @ )MNhliTW O M M M V 2 MhN' of. ten occurs when the victim is clearing the 10, Push, do not pull a hand mower. discharge chute of grass chppings or is adjust- 11. Never remove the safety shield or any - ing the machine without turning it o1f and wait- ; other safety devices on a lawn mower, ing for the blade to stop. i 12 Never refuel a mower while it is running
- 2. Propelled objects - Wire, rocks and Iwigs ! or while the engine is hot etc., can be shot out either through the dis- 13. Never refuel a mower indoors because charge chute or from under the housing. Many the unseen vaport may be ignited by a spark.
of the victims in these cases are bystanders. 14, Start the mower outdoors, not in a gar-
- 3. Overturning-This occurs pnmarily with age or basement where carbon monoxide can riding mowers which are used on steep slopes ! collect.
or embankments, The victims come in contact i 15. Do not smoke around the mower or the with the blades or sustam injuries dunng the } gasoline storage can. The gaschne fumes can fall. j easily ignite.
- 4. Mower running over the victim - This r of ten occurs when a ridmg roower or garden trsctor is being dnven in reverse; the victims are LADDERS usually young children who, unseen by the i operator of the mower, are in the vicinity of the l mowet which is operating Another frequent Supervisors should make sure all ladders accident occurs ficm the operator pulling the meet the below listed specifications and that mower backwards over h.is or her foot. i employees are f amiliar with safe ladder use Operation i guidehncs.
., 1, Road the manual and pay attention to its 1. Check your ladder for load capacity and -
- ~
recommendations. make sure it has a label of the American Ladder
- 2. Wear sturdy, rough-soled work shoes and Institution, close fitting slacks and shirts. Never operate 2. Metal ladders should have shp icsistant the mowerin bare feet, sandals, or sneakers caps at the tops of the side rails and wide, slip-
- 3. Rake away wires cans, rocks and twigs resistant feet before mow,ng. 3. Make sure the steps on your ladder are at
- 4. Never mow a wet lawn because you could least three inches wide.
shp and come in contact with rotating blades. 4. Make certain that the ladder you are using The wet grass could c!og the blades and tempt is long enough to rest at a safe angle and is still you to try to clear the machine without f rst i high enough for use The base should be one turning it off. f oot out for each four feet in height to the point
- 5. Always turn off the mower and wait for i of support (a ladder 20 f t. at its support point the moving parts to stop before leavmg the ; should be set 5 feet from the perpendicular).
mower. 5. Safety standards specify that no ladder -
- 6. Always turn off the machine and discon- should be used for access to a roof untess the nect the spark plug wire or electnc plug when j top extends at least 3 feet above the point of
. unciogging or adjusting the machme. shght suppott rotation of the blade could start the engine 6. The top of the ladder should rest on a flat,
- 7. Mow across the slope when using a hand firm surface. Do not lean it against unsecured mower. With a ridmg mower drive up and down objects.
the slope for stabihty. 7. If you must p! ace a radder in front of a
- 8. When usmg an vectric rnower. be very door, make certam the door is locked.
careful not to run over the cord or entangle it 8. Never use a metal ladder when there is a in the blades. Start mowing the grass nearest , possib!hty of gethng within 4 feet of any elec-to the electrical outlet and graduahy move out- incal equipment or wmng. 9, Wait for at least one-half minute af ter !
~~
=
9 The footing of a ladder must be f irm and shutting off the engine to be certam the blades even Bwid up the surf ace if necemary, or have stopped place a wide flat boara under one or both of
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r the ladder- feet to level thera or to keep them L
' frorn sinking into the ground.
l
- 10. Always face the ladder, both ascending i iand descendingi and never-skip rungs,-
f
- 11. Never use a ladder in heavy wind. Post. 1
- pone the project until it subsides. I
- 12. Never reach too f ar on a ladder. Two
. good guides arq to never reach beyond a com-
. fortable arm's length and keep your belt buckle ;
Detween the two upright sides. L1.3, if you becorno ill or panicky, lean your l head against the ladder and wrap your arms
= through the rungs until you receiver sufficiently to climb down.
14 Never chmb a stepladder past the second step from the top. Do not use a stepladder as a 3 straight ladder by leaning the top against a wall, j
.15 Check your equipment A ladder can be- t come defectwo. in storage by developing i ,
' cracks, drying out, rotting or insect damage.
16, Look for splits and cracks Test the sup- 4 ports under the rungs. .
- 17.. Do not paint your ladder. Paint can hide i Splits and cracks. Use oil or varnish instead. : i 1E Store your ladder in a dry place such as j +
a garage-nbver behind bushes, on the ground, ! ! :or exposed to the elements. l
\
GRINDERS AND BUFFERS j .- f. Serio'us eye damage can result from im-l proper use of grinders. In order to prevent this ; l- danger, wheels should not be used without the i l metal guard and eye shield in place. L
- 2. Prior to use, the wheels should be checked l out for scoring or cracking. !
3 When new wheels are installed, the RPM capacity of the wheels should be checkea 3f l: against the rnaximum RPM capacity of the l motor. l 4 L A face shield will be hung on or near each ll l grinder and is to be worn by any person oper-ating the grinder. 5.. Work rests shall be adjusted close to the i wheel with a maximum opening of 1/8 inch. { . I y
tpwh pifyi $;7 W. ' .
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M [hib h 'b ' I k y*: ON j i i pfp WW '-2)s .it n QS y( [yM] y , w' HAZARDOUS WASTE
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spontaneous chemical change's and wh;en igL y
% _ , ', ,# HAZARDOUS'. WASTE DISPOSAL 4 nited burns so vigoiously and persistently thatt * '
1 ["F, iL_']' j R, ,- y? - vit creates a:hazardE . 13/It:is ar[ ignitable compressed gas as'de E
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It j y 4 Q. .m .;The' purposejof these procedutes for haz- fined.in 49 CFR ;173,300f ' d g; 2 ardous waste handling and dJsposa_lis to insure ~
~d , Jg e that hazardous w,astes are identified properly +
4fttifs[an oxidizer as de' fined in99 CFR) ;
. 173 51, r M 4
. :h_andled safely, and transported arid disposed
.i .
n *, N jof in?accordance with:tho' Stato and Federal' Characteristics of Corrosivityi y
. deguiutions, 121t isiqueous"and lias a pH lessithdn 'or: ,
T' . equal to% or greater than or equal to 12.6ya's) ,
%$y $ - 1 DEFINITIONS:OF HAZARDOUS- '
d**I"*d \DY
- PN
- 1* - - - -
- " ' "e
- WASTEO
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- 2 tit is a liquid and corrodes stect(SAE'l1020): 3
@u ,M al'a' rate greater thaa 6.35 mm (0l250 inch) per- , *9 R@ ;4 o 4 t . a
. A waste is. hazardous if it meets any of the-year at a test temperature of 55 degrees Celslus : 4 1
- (130, F.) .au ceiermined by the test. -method c a
a
,4. followingt. -
q$ [4 y*m/yh specified Lin NACE (Natic.nal- AssociationL ofJ ' _11 4ttis]a colid waste or combination of solid
' Q Corrosion Engineers)s- n A L/; m_y s
c .g. , y
, @wastestwhichsbecause ol itsectious quantitygcon- %ff y4n entfatidn(orf physicat, chemical l or.inf 7 characteristics may cause or significantly con--
Characteristics of Reactivky = , y 1;it is normally unstable and readily under4 ' <O Qf ; tribute' to 'an increase in mortality?or. an in-- goes violent change without detonating,- 1 VM [ crease in serious irreversible or incapacitating- 2J !! rnacts violently.with waterc s@ j j, glJnessior may poseLa substantial present or .
- 3. It f orms potentially explosive mixtures w'ith (
Ed R" (potsntial hazard ,toLhuman; health, or the en- water- "[ .. (vironmenb whenfimproperly treatet storedt . ' .4,'.When mixed with waterc it generates toxic ,d gQ;
, ^ gtransported [or disposed olcor otherwise man
- gases l vapord or fumes in a quantity suf ficienOo) y Ng jaged".a.u ., present a dinnger to' human health or' the en; t , [22tt is included in a list of specifically identh vironment
~, ,
. ifiabid names pubushed by the' Environmental' ']4
! 5 fit Liafa' cyanide 'or sulfide-bearitig waste L
yy# l Prot'ectl6n Agency (EFLAM ._
. which,when exposAd to pH conditions betwee'n < y 11 3nitils listed and <ls mixed with non-haZO 2 nnd?t2 Sfcah generatejoxic g'sesivaporst a t ardous -' material; fumes inD gbanlity sufficient to pr_esent a danc ]j g, j[ ' _ . M soird waste Msiuoda semisond. iiowa tu notNned . . ger to human health or the environment _ ]
g .; ::Daseous maw 6..lt is :capatile :of detonation or explosive 3'< d ^ i' Mit has characteristics of being ignitable, reaction if it is subjected to ai ing imtlating; yk L r eorrosive.-redctive. or : extraction procedure - : source.or it heated under confinement
- 7. It:is readily capable of detonation or ex-p(
'Itoxic as defined by the E.P.A; d
Silt is personally known to you to be haz. . plosive decomposition or reaction at standard 'y vardous based upon knowledge of the materials temperature and pressure. . ,
M Mrbcesses used in producing the waste. 8. It in a forbidden explosive as defined in d
,k "[m i 3The four characteristics that determine if a 49 CFR 173,51, or a Class A explosive as;de- f +< 4 dwaste is hazardous are as follows. fined in 49 CFR 173.53, or a Class B explosive j
^ . . . . as defined in 49 CFR 173 88. 1 a Jfo TCharacteristics of Ignitability -
~ ^
~
igli tcit is a liquid, other than an aqueous solu. Characterirtic of Extraction Procedure (EP)- ,
.m 4 7 iort t containing less than 24 percent alcohol by Toxicity'- L
-- E
- volume, and has a flash point of less than 60 . ' A sohd waste exhibits the characteristic of j._ : degrees Celsius .(140'F), ! EP toxicity if, usirig the test methods described, y
- Y '
'2.ftt is not a liquid and is' capable, under an extract from a representatwo sampie of the '
[ _i : standard temperature and pressure, of causing waste contams any of the contaminants listed , O' fde through triction, absorption of motsture, or in the tatWe on the following page, at a con- I t, sm I N g) .' x ; ,p m ,y - i .J
+-~-----~~--~~~~O
g . .~ M yh[hhk;-[ [yhh 9'f g k [ [ [? [ [ h'h..h k ( contration equal to or greater than the respec-tive value given iri the table t elow RESPONSIBILITIES OF UNIVERSITY PERSONNEL REGULATIONS Responsibilities of University Personnel
- 1. University personnel determine which ma-The Utah Hazardous Waste Management tonals are hazardous waste by consulting the Regulations and the EPA Hazardous Weste preceding characteristics. For specific ques-Regulations prohibit the improper disposal of tions call Safety Services, (ext 6590).
Hazardous Waste.. 2. Appropriate containers must be used, if All wastes that are identified as hazardous possible the same contalner (i e, bottle, jar, must be disposed of by an EPA licensed T reat. can, etc ) that the materiai arrived in should be
. ment Storage and Disposal Facility (TSDF) This used for disposal. All bottles and cans must necessitates proper packaging for shipment on have a secure tilling screw cap and must not public roads. leak when inverted. Corks, cotton plugs, plastic The U.S. Department of Transportation sheeting, etc. are not acceptable stoppers for-(DOT) requires that all ha7ardous matenals be bottles and cans. The outside containets must properly identified, labeled and containerited. be clean, Leakint, containers will not be picked The DOT and the EPA require a shipping mani- up. Loose sokd materials, such as the residue fest Civil and criminal penalties can be as- f rom a spill, should be placed in a box or carton sessed against those persons responsible for hned with at least two plastic bags. All glash improper disposal of hazardous waste.
containers must be packaged to prevent break-4 MAXIMUM CONCENTRATION OF CONTAMINANTS FOR CHARACTERISTIC OF EP TOXICITY Maximum EPA Hazardous Concentrahon Waste (milligrams Number Contaminant per hter) D004 Atsenic 5.0 D005' Banum 1000 D006 Cadmium 10 D007 Chrom;um (VI) 50 D008 1.ead 5.0 0000 Mercury 02 0010 Selenium 1.0 D011 Silver 5.0 D012 Endrin (1,2.3,4,10.10.hexachlorod ,7 epoxy-14 4a,S.G 7, 0.02 8,8a octa hydro-1,4-endo, endo-5,8 dimethano naphthalena) D013 Linaane (1,2.3 Ab 6 hexachloro-cyclohex ane. gamma insomer) 04 D014 Methoxychlor (1 1,1-Trichloro-2,2-bis (p-methoxyphenyl)etnane) 10 0 DOIS Toxaphene (Cdh0Cle Technical Chionnated camphone, 05 67-69 peicerit chlorine) .. D016 2.4-D, (2,4 Dichlorophenoxyacetic acid) 10 0 f D017 2,4.5-T P Silex G!.4.5-Tnch!oro-phenoxypropionic acid) 10
b m_.-< _ 1 l age dunng transport. Safety Services wiu pro-
. vide special containers upon request. FINAL DISPOSAL OF HAZARDOUS
' 3, Personnet munt clearly label each con. WASTE tainer with the following intormation:
- a. Name of the material (chemical name) Harardoos waste matenals are transported
- b. Volume or weight. to a temporary storage / accumulation building
- c. Name of person requesting disposal. where they are property packaged, labeledc d Disposal date. an;t containerized for shipment to a licensed
- e. Building and room number. EPA treatment storage and disposal f acility.
l.. lelephone extension.
- 4. A Hazardous Waste Manifest form must be completely tilled out and must accompany the waste. Information on the form includes' a Name of person requestin0 disposal.
- b. Department, building, room and phone.
c Description of waste.
-d Quantity, e Hazard class.
f, Signatures. HANDLING HAZARDOUS CHEMICALS 1 For the control of health hazards asso-ciated with toxic chemicals, au researchers should f amiliarize themselves with the specific chemical compound in use, includmg their physical proportiesl their toxicology and any remedial measures that must be taken.
- 2. Unless it is definitely known thtt a sub-stance is not toxic, treat it as though it is.
- 3. Protect exposed areas of the skin and eyes when working with the toxicants, wear goggles, gloves, aprons, etc 4 The personnel should utilize a respirator or gas mask where appropriate.
- 5. The toxic substance should be stored away from any potential fire hazard which would rapidly spread a toxicant.
PICK UP FOR DISPOSAL When the hazardous waste materials have been properly packaged and labeled and the hazardous waste manifest form filled out, call extension 6590 :o request a hazardous waste pick up. Please be prepared to give your name. department, extension, and location and de scription of the waste. Safety Services will make arrangements to pick up the waste. l
2 CHAPTER Vil u
&$T~'? Y 1:. ! . Y ll $$ k NY "; hb ! A: : - RESPONSIBILITY OF FIRE REPORTING MARSHALS
- 1. If you notice an unusual odor, a natural The University Fue Marshals have been gss leak, gasoline spill, or observe anything sworn in as deputy State Fhe Marshals with that might pose a fire / safety hazard, call the authority and jurisdiction on University proper- Department of Public Safety immediately at ty. Their responsibiblies incluele Fire and Life 581-7944 and provide as much information Safety Code Enforcement, conducting firer
~
as possible. safety surveys in each building, inspecting and 2. All fires, regardless of how tmnor or if testing fire equipment and devices, training in burned out prior to discovery shall be reported fire prevention and fire safety, responding to to the Department of Public Safety. and investigating all fires, arson detection and inveshgation, and reviewing all plans for re-PORTABLE FIRE EXTINGUISHERS modeh.ng and new construchon on campus. _
b '"'Y 8*'" I'* * " S "'" S I""' " '"" **'
btEPAREDNESS finguishers and hoses are inspected annually. Extinguishers must be mounted.
- 1. Be alert to any potential fire hazards and 2. Hand type extinguishers are to be located .
take appropriate corrective action. not more than hve feet above the floor. Under i
- 2. Know all possible exit ioutes from your "O C'rcumstances shall fire extinguishers be re-building. moved or relocated by anyone other than Safety
- 3. Keep all exit routes clear and unob. or Security Services fire extinguisher . main- -
'structed. tenance personnel except for use in hre fight- i
- 4. Learn whether your building has a fire ing. .j ^
alarm system ll an alarm system exists, learn 3. Fire hose and extinguisher cabinets shall be kept clear of obstruction a all times. the locahons of the fire alarm pull stations.
- 5. Have emergency telephone numDers 10 4 ff any fire extinguishers au considered to cated by each phone be dehcient or damaged, Safety Services Of-G Know the locetions of fire extinguishers tice shall be notified in order that the necessary 1 and how to.use them corrective measures be taken. l 5 Tags on fire nxtinguisherl, shall. not be l
=!
removed or altered. FIRE PROCEDURES 6 Safety Services is responsible for deter. l mining the number and type of ble extin- I When a fire is ciscovercd or suspected da guishers required in University buildings Cor-the following: rect information with respect to type, number,
.1. Sodnd the alarm,by pulling a local fire pull location and refilhng of these extinguishers j station, shouting or knocking on doors to warn may be obtained by calling the Safety Services !
Responsibihty of recharging this eouip-Il t Ire Departrnent by clairng 9 911. ment is assigned to the fire extinguisher ser-Give as much information as possible about the , nature of the fire, and exact location (use build- l vice personnelin the Safety Services off ce ing name and number) ,
- 3. Leave the building. Remember to quickly i secure any on-go ng hazardous operahons l STORAGE FLAMMABLE AND AND HANDLING OF COMBUSTIBLE Don't panic or run and do not use elevators. i LIQUIDS As you leave close doors behmd you and re-main a safe dwtance from the umiding. When Def mtions ;
fire fighters arnve provido any addihnnalinfor 1 Approved - Signifies acceptance by tne , mahon that may be helpful ' authority having junsdiction of design, equip-L
fl%El54fETi ..' .]'y f4 J Q j * ) [ ' I $ ? ' N ) 7 . n 1 ;.' .. . " s j 7 ment, installation, or intended use as required points at or above 73*F. (22.8*C.). l by National Fire Protection Association (NFPA) 6. Flash Point - of a liquid shall mean the
- 30. Devices that have been tested and accepted temperature at which it gives off vapor in suffi- i for a specific purpose by a nationally recog- cient concentration to form an ;grsitable mixture nized testing laboratory may be deemed to bs with air near the surf ace of the liquid within the j acceptable (i.e. Underwriter's Laboratories, vessel as specified by appropriate test proce-Inc. listed or Factory Mutual approved). dure and apparatus. l
- 2. Bolling Point -is the boliing point of a 7. Safety Can - Shall mean an approved- !
liquid at a pressure of 14.7 p.s.l.a. Where an container, of not more than five-gallon capac-accurate bolling point is unavailable for the ma- ity, having a spring-closing lid and spout cover terial in question, or for mixtures which do not and so designed that it will safely relieve inter-have a constant boiling point, for purposes of nal pressure when subjected to fire exposure. ; this classification, the 10 percent point of a 8. Vapor Pressure - Shall mean the pres- l
' distillation performed in accordance with the sure measured in pounds per square inch (ab- i-
{- - Standard Method of Test for Distillation of solute) exerted by a volatile liquid as deter- I Petroleum Products, American Society for mined by the " Standard Method of Test for Testing and Materials D86-62 may be used as Vapor Pressure of Petroleum Products"(Reid the boiling point of the liquid. Method), (ASTM D323-68). !
- 3. Combustible Liquid -Is a liquid having a flash point at or above 100*F. (37.8 C.). Com. Storage of Flammable and Combustible bustible liquids shall be subdivided as follows: Liquids
- a. Class ll liquids shall include those having 1. Size of containers - Containers and por-3 .
flash points at or above 100*F. (37.8 C.) and table tanks for flammable- and combustible below 140*F. (60*C.). liquids shall conform to the Table on the fol-I b, Class Ill-A liquids shall include those lowing page. ! liquids having flash points at or above 140 F- 2. Storage Inside Buildings and below 200 F. (93.4 C.)- a. Flammable or combustible liquids shall
- c. Class lil-B liquids shall include those not be stored so as to limit use of exits, i liquids having flash points at or above 200 F. stairways, or areas normally used for the (93,4 C.). safe egress of people.
- 4. Fire Area - Shall mean an area of a build- b. Storage shall be limited to that required ing separated from the remainder of the for operation of office equipment, main- A building by construction having a fire resis- tenance, demonstration, treatment and tance of at least one hour and having all com- laboratory work. Allliquids shall meet the .
- municating openings properly protected by an following storage provisions: I assembly having a fire resistance of at least
- 1. Not more than 10 gallons of Class I and one hour. Class liliquids combined shall be stored a
- 5. Flammable Liquid - Any liquid having a outside of an approved flammable li-flash point below 100*F. (37.8"C.) and having quid storage cabinet.
a vapor pressure not exceeding 40 pounds per 2. Not more than 25 gallons of Class I and square inch (absolute) at 100 F. (37.8'C.) and Class illiquids combined shall be stored shall be known as Class I liquids. Class I liquids in safety cans outside of an approved shall be subdivided as follows: flammable liquid storage room.
- a. Class IA shall include those having flash 3. Not more than 60 gallons of combusti-points below 73 F. (22.8 C.) and having a ble liquids shall be stored outside of an boiling point below 100 F. (37.8 C.), approved flammable liquid storage cab-
- b. Class IB shall include thoso having flash net, or approved flammable liquid stor-points below 73*F. (22.8 C.) and having age room.
1 a bolling point at or above 100 F. 4. The University of Utah Safety Services (37.8"C.). 17ivision may impose a quantity limita-
- c. Class IC shall include those having flash tion or require greater protection where
],
i FIRE SAFNTY -
..L J : . .
W. .
~
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. S8; -
unusual hazard to life or property is b An approved safety pump must be used . involved. An increase in these amounts - with C! ass I and Il hquids. Dispensing Class ill A . may be authorized where the type of houids requires the use of an approved self-construction, fire protection provided, closing cafety f aucetc a bonding wire betwaen , or other factors substantially reduce the drum and the container being filled, and a the hazard. _ grounding were connecting the drum to ground. . c, Not more than 120 gallons of flammable in locations where flammable vapors are pres- [ or combustible liquids shall be stored in a ent, precautions should be taken to control or .; flammable liquid storage cabinet with no eliminate sources of ignition. container exceeding five gallon capacity. Of this total, not more than 60 gallons may be of Class I and Class 11 liquids. Not more RESIDENCE HALLS FIRE SAFETY than three flammable liquid storage cabi-nets may be located in a single fire area b. An approved safety pump must be used
- d. Quantities greater than defined shall be with Class I and ll liquids. Dispensing Class 1ll A stored in an approved flammable liquid liquids requires the use of an approved self-storage room (approved by the Safety c% sing safety faucet a bonding wire between Services Division). the drum and the container being filled, and a
- e. The University Central Stores and Receiv- grounding wire connecting the drum to ground, ,
ing/ Purchasing will purchase flammable in locations where flammable vapors are pres, and combustible liquids in quantity and ent, precautions should be taken to control or resell to the departments as needed. eliminate sources of ignition
- f. Ref rigerators and coolers used for storage Behavior which disregards fire and emer-of flammable liquids shall be used only if gency regulations must be identified and re-they are approved explosion proof appli- l ported for immediate disciphnary action.
ances.
- 1. Fire Prevention Measures: The residence
- 3. Dispensing Flammable Liquids hall directors or resident advisors,in coopera-
- a. T he dispensing of Class I,11, or lil A liquids tion with Safety Services. l from containers larger than five-gallon capa- n Make certain that fire and emergency
! city shall be in an approved flammable liquid procedures are explained to residents at y storage room and is limited to not more than the beginnmg of each quarter.
d + three.55-gallon drums at any one time- b.' Know content of the University of Utah 1, MAXIMUM ALLOWABLE SIZE OF CONTAINERS AND PORTABLE TANKS Flammable Combustible Liquids Liquids Cgntainer ,JypyL, Class I A Class IB Class IC Class ll Class HI Glass 1 pt 1 at 1 gM 1 ga! 5 gal c Metal (Other than DOT Drums) or appromd plastic 1 gal 5 gal 5 gal 5 gal 5 gal Safety Cans 2 gal 5gM 5 gal 5 gM 5 90 Metai Drum (DOT Specl 60 gai 60 gai 60 gai 60 gm 60 gal Approved Portable Tanks 660 gat _ _ 660 gai %D g-i 660 gm 660 gal ; (References NFPA 30-Flammable and Combusth Lmum Code Umf W Fire Gods CMpte 7 's ) e i
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FfRE SAFETY . 1 39
#P I
'> Emergency Preparediness Manual. be subject to discipimary action'L .
t c; Schedule an'd conduct fire exit drills each d. The twilding is not to be reoccupied by' Nuarteri _
=
any student until the hall directof or his/ J1? Staff member maintains confidentiality her representative gives the "all clear? if nes drill schedule.L .
. signal, y 2 F repares Fire and Safety Exit Drill. Re- . e. A full Report of Fire will be submitted im-1
* ' port Form and forwards'to the Safety.
. mediately by the head resident or his'/here i Services Office. - representative and forwarded to ths Safety'
- p - dLinspect unit r'egularly to make certain no Services Office. %1
( motorcycles, motorscooters, .or, other ' q
, 3. Equipment Damage and Abuse: LAuto ,
motor vehicles are parked or stored in.the matic closing. devices on fire doors must NOT -
; residence hall AT ANY TIMEJ be damaged < Fire doors shall:NOT .be~ wired,
] '
l> . e; Inspects Unit._ regularly to make certain blocked open, or abused. It is staff and student [ . that aWeiits are clear of obstructions AT responsibility _to keep all fire doors closed ande q ALL TIMES. to prevent abuse. Tampering with fire andi d B ,
~ f.; Repe is all tampering with1 fire alarms to; emergency equipment of any kind may result in. j
.the !,afety Services Office. (Staff and/or injury or death. 4 9
stud mts should not attempt to make.any 4. Storage Rooms:. All storage 1 rooms and =[ L. . 1 rept%'or adjustments.) closets and other limited access areas are staff D . g.'Causes the; entire residence hall to be responsibility and should be kept clean and free +. ti'nspected regularly, including rooms, giv- of debris at all times. [ - . ing special attention to?1) overloading of 5. Wastebaskets: All wastebaskets in ]^ Q7 circuits,D2) misuse of: frayed-- cords, 3) - lounges, lobbies and. student' rooms will be of KfV' s 4 combustible materials. and 4) open or in-metal or fire resistant materials.
~ operable fire doors-
- 6. Unsafe Smoking Practices Prohibited: j
,, hiThe use;oficandles.or any other open- ' Smoking is not allowed in bed. Lighted ciga-flame devices is forbidden for any pur- rettes should not be discarded on .the floor, 3
l pose in-the residence halls. ,
, . ground or from a vehicle. Do not leave ciga-
' 2? Fire or Emergency Evacuation Procedure: rettes burning unattended in an ashtray or on a: .
- aTSee th' a t evacuation plan is posted in a ' table ledge, Do.not place burning cigarettes in : '{
U . conspicuous place on'each floor. trash receptacles or trash chutesi J bcWher) there is an alarm in'a residence hall; 7. Fire Lanes: Fire lanes are around most of : every person (employees and students) is the residence halls and must be kept clear in . N l z to evacuate the building immediately, case of ernergency. These have been desig. 7 Some general rules are. nated as " Tow Away Zones" and will be en-
. 1. Elevators shall not be used for evacua; forced by Parking. Services, ]J tion / ,
- 2. Evacuation applies every time the alarm j sounds, regardless of the cause J
-. 3. With the sounding of % aiarm, the hall ~',
director or his Ther representative is to i notify Pic Safety Dispatcher at _once :?
' by dialing 9 911.- !
4; Students should turn off lights, close all windows, leave door open, use nearest . stairway. _. c When there is an evacuation, a staff mem. ! ber will make a complete check to see
' that everyone is out of the bui_iding Doors >j will be closed as rooms are checked Any j f
h^ j? . student who remains _in the buildmg will 4
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3 ~_ p' t ' ,,j 4 i e! i. ', - 4 44
, . APPENDIX F-s.
DECOMMISSIONING AND DISASSEMBLY PROCEDURES 4 [ ,' i
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< U ,j University of Utah Nuclear Engineering Laboratory
- l. .- . AGN 201M Decommissioning Project Concrete Block Surveillance Procedure Introduction .
This report details the procedure to be followed during the removal of the concrete block used as shielding for the University of Utah Nuclear Engineering Laboratory (UUNEL) AGN 20lM nuclear reactor. The removal of the block is a necessary first step in the decommissioning process of the AGN reactor.. Surveillance of the block is required to preclude the release of potentially contaminated material from UUNEL. This procedure has been developed by the staff of UUNEL in collaboration with and the approval of the University of Utah-Radiological 11enhh Department (UURHD) following guidelines established by the U.S. Nuclear Regulatory Commission. Safety Considerations The removal of the concrete block requires transferring the block from its present location onto wooden pallets while monitoring the block-to assure contaminated block is not removed from UUNEL. It has been estimated that there
.T are approximately 5700 block enclosing the AGN reactor as shielding. Moving l_ such a large number of blocks presents a great potential for injury,to personnel and laboratory equipment. Therefore, at any time work is m progress in laboratory, the safety _of personnel must be of primary concern. Carelessness,' horse play, and unsafe 3rocedure will not be tolerated of the personnel engaged in the block remova. and surveillance project. In addition, the overhead crane is not to be operated without the permission and/or presence of UUNEL staff. Furthermore, the TRIGA reactor tank will be covered with plastic sheeting whenever blocks are moved to prevent contamination of TRIGA tank water by concrete dust.
General Procedure
' The block will be monitored with portable survey meters, viz. Technical Associates Model TBM-3S " friskers." Readings will be made such thst the bottom -
surface of the detector is nominally one inch from the surface of the block. In order i-. to reduce variability in the readings, only one person will be allowed to perform the survey portion of the procedure per shift. The survey will be performed during the transfer of block onto the pallets as follows. Each pallet is to be loaded with five to seven layers of block (depending upon the lifting capacity of the overhead crane and other safety considerations) with each layer compnsed of 15 blocks compactly arranged. The first stage of the survey involves passing the frisker over 15 blocks (i.e., one pallet layer) in situ. Any blocks with readings found to be in excess of the maximum allowable activity will be marked and set aside for retention within UUNEL. Blocks with an acceptable g-l
- - - - . . . ~ . _ . . . .. .
activity level, which is defined in the next section, will be loaded onto the pallets in (] G such a way that the surface of the block which was surveyed in the first stage is placed face down on the pallet or previously loaded layer of block. The second sta;;e of the survey therefore involves passing the frisker over this surface of the bloc c; , i any blocks with readings in excess of the maximum will again be marked and set aside. Following the loading of each layer, a record will be made on the special-survey form prepared by UURHD (see attached sheet) in which the pallet number, number of block, maximum reading (in epm), and the number of blocks set aside a.c
, recorded. In this manner, individual pallets will be loaded. Plastic shecting will be 4
used to cover loaded pallets to prevent accidental contamination. A radiation safety technician from UURHD will be contacted to Arform an independent survey of loaded pallets to verify and assure blocks exceec,ing the criteria of acceptability are not released from UUNEL. ' Upon completion of the block transfer and surveillance, and the final 1 I independent the reactor room wi survey,ll be opened to allow for the removal of approved bloc r overhead crane will be used to aid in the transfer of the pallets from UUNEL onto flatbed trucks. Following removal of the loaded pallets, the utility door will be > rescaled as quickly as possible to minimize TRIGA reactor downtime, Steps will be-taken to assure adequate security of the UUNEL during the entire period the utility i entrance is breached. Accentable Activity Limits
/T 'V The criterion for the rejection of concrete block as contaminated material as recommended by the Radiological Health Department is a tneasurable count rate in excess'of twice the average area background count rate on the day of measurement.
The average area background in the vicinity of the present location of the block runs between 100 to 150 c am on the TBM 3S. Blocks exceeding a count rate of 250 cpm on any surface will be rejected as contaminated material. These blocks will be marked and set aside. Blocks with a count rate at or below 250 cpm will be stacked on pallets and will be removed from UUNEL. Final Disnosition 1 Once the blocks have been surveyed, an'd only those at or below the ; acceptable activity limit have been transfened onto pallets, they will be subjected to a final survey to be performed by UURHD. Following approval by UURHD that the l block meet the criteria of acceptability, the block will be transferred to the University of Utah Broad Form License No UT18-00001. The block will subsequently be L released from UUNEL to a preapproved contactor for final disposition. V g
Form NEL 100 Sheet 1 RSC Appmval: 5/25/88 UNIVERIITY OF UTAH AGN REACIOR 3ECOMMISSIONING RADIATION SURVEY PRONDURM FOR RHACIDR COMPONENTS
- 1. Perform a direct radiation survey over all surfaces of a component using a portable G M survey meter with a thin window (1.5 2.0 mg/cm2) probe. (NOTE: No direct surface
+
survey will be made for the Ra Be startup source.)
- 2. If a component shows no detectable radioactivity above normal background after the direct survey,if the survey effectively covered all the component's surfaces, and if no undetected radioactivity is deemed to be present for some other reason, then the component may be inventoried and released for campus storage or transfer to an off-(:
campus location.
- 3. If a component shows an detectable radioactivity obove normal background after the direct survey, and if it meets all other criteria specifiW in step 2 (above), it may still be desirable to make representative wipes over 100 300 cm2 areas (see # 5). The number
_ and frequency of such wipes will be the decision of the radiation protection staff member conducting the survey, but items with surfaces close to the reactor core should be given to) prionty in the absence of other factors. Components which have been wiped shou d be held until the wipe counting results are obtained. Components with wipes showing no detectable radioactivity above normal background should be tagged and released for campus storage or transfer to an off campus location. Should a component wipe indicate radioactivity above normal background, the item must be handled in accordance with the actions outlined in step 6 of these procedures. J' 4. If a component shows no detectable radioactivity above normal background after the
.- dhect survey, but the 3resence of potentially undetected radioactivity still cannot be eliminated with a higi degree of confidence (srimarily because of the inability to g effectively survey all component surfaces) then t1e item will be stored as a radioactive component in the University of Utah Nuclear Engineering Laboratory (UUNEL).
- 5. If a component shows radimetivity levels above normal background during the direct-survey (normally a g, <. citing rate on the portable G M detector equal to 1.5 to 2 times the norraal backgmund rate for the instrument F1 be sufficient to establish thir conclusion), then representative sections of surfaca showing elevated radioactisv levels will be wipiin 100-300 cm2 increments to determine whether the radioactivit) a removable. Act.vity on wipe samples will be measured quantitatively and converted te 1
dpm/100 cm2 L 2 6. If the radioactivity is removable, then decontamination of the component will bc
- attempted and a comolete re survey will be performed according to these procedures. If decontamination is successful and no detectable radioactivity in excess 01 nonnal back-ground is found, then the component should be inventoried and released for campus storage or transfer to an off campus location.
- 7. If decontandation falls to remove all removable radioactivity (such that removable
+
radioactivity persists), or if the elevated radioactivity previously detected appears fixed in the component (it is probably the result of material activation), then the component will
-- be stored as a ndioactive item under controlled conditions in UUNEL 9 8. Written records of all radiation surveys shall be made using, as appropriate, the "AGN Component Radiation Survey Record Form" (see Appendix A) or the form emitted "U of U Record of Rdation Survey"(so Appendix B).
--- - -m___.- _ . _ _ _ _ _ _ _ _m.__.__._ ,_ _ ___.____ _ _ . _ _ _ _ _ _ _ , _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _
Form NEL 100 Sheet 2 RSC Approval: $/25/88 O NOTE: Several Components of the AGN may be radioactive due to the presence of radioactive materials. *Ihese are the core can, the control rods, and the Ra.Be neutron source. It is planned to store these components as radioactive items in the Nuclear Engineering Laboratory for subsequent transfer as appropriate as radioactive waste. Each component will be surveyed according to these procedures except that no direct surface survey will be made of the Ra Be startup source. It will be leak tested, however, before transfer from UUNEL. O O
h 1 Form NEL 101 1' y RSC Approvat: $/25/88
/
l AGN COMPONENT RADIATION SURVEY RECORD FORM 3 L
- i. '
j .- Survey Form #: , Survey Location AGN Reactor. Nuclear Enrineering Lab. Survey Date: ; SURVEY OROSS NLT NETdpm mremAour (s wrface) NO, ; TTDi SURVEY P OENERALDESCRFN INSTRIJ) TYPF#) cpn epm 100 cm2 a S y Total i i t. b t L T > 1 1 k-
,e ,
\'-) DETECTOR USED: REMARKS:
h I l l (t)Ilackground counting rate at (location) was: if epm = _ dpm = mrem /hr. (2) !!ackground counting rate for this instrument was: cpm = dpm. The LLD at 95% confidence level was: , net dpm = net pCl. No wipes wipos showed removable contamination slove the LLD, cacept from the following items: t
, TJ) Survey Instrument Codes:
TAGM = Technical Associates ponable O M with pancake pobe (thin window): Serial #: Calitration Date: , Other; m (4) Survey Type Codes: D = Direct Survey over the entire surface of the object. WA = 100-300 cm2 wipe counted with an alpha detector. WO = 100 300 cm2 wipe counted with a portable O M. WL = 100 300 cm2 wipe counted with a liquid scintillation counter (3 11). WGS = 100-300 cm2 wipe counted with a gamma spectrometer. i CT U SURVEY PERFORMED BY-
Form NW105 - RSC Approval: .W5/88 Dismantilng Plan for the University of Utah AGN 201 Reactor ; O I Intmduction The Dismantling Plan for the University of Utah AGN 201 Reactor gives the general
, procedures to be followed for disassembly of the reactor. These procedures give more specific details regarding the preparation needed prior to disassembly and the actual disassembly steps themselves.
NO'Hi: Check ti&ms in the appmpriate place as each step is accomplished. Maintain one master copy for reference. II. Prenaration Prior to Dieaecanth
- 1. P>adiation Projardion
- a. De following instniments will be checked for proper operation, then placed in the reactor room for use:
- 1) Continuous airmonitororhighvolume airsampler,
- 2) Neutron survey meter (spherical TMC Neutron survey meter).
- 3) Beta gamma dose rate survey meter (Cutie Pie or Radector).
- 4) Contamination survey meter (thin win.bw Gelper counter). t
- b. The following supplies will be collected anc placed m the reactor room for use ,
as needed.
- 1) Filters for air sampling.
- 2) Smearing materia:s for wipe tests.
- 3) Containers for air samples and wipe test smears. t
- 4) Shicided storage container for storing the Ra Be startup source.
- 5) Coveralls, lab coats, gloves, and shoc covers.
- 6) Radioactive waste containers.
T 7) Cadmium foil for core can insen.
\ 8) Respiratory protection equipment.
- 2. Work Area and Tools
- a. Survey reactor room area in preparation for proposed activities,
- b. Relocate equi pment as necessary to maximize working area room.
- c. Collect the fo: lowing tools and place in reactor room:
- 1) Hand Tools (socket and Allen wrenches) required for disassembly.
- 2) Handling tool for removing the Ra Be source. *
- 3) Lifting lugs and rigging for themial column, core tank, and upper graphite reflector, '
- 4) Cart for transponing the core can to the designated storage area.
._ d. The following items wil also be placed in the reactor room:
- 1) Plastic bags for packing components.
- 2) Labels for dismantled components.
- 3) Camera with flash and film for photographically documenting the procedure at key stages.
III Detailed Disassembly Pmcedures u NOTE: The assembly pan numbers are correlated with the pan listing on drawing number E-2 000100,
- 1. The Health Physicist will make a pre disassembly radiological survey. He will also initiate special access procedures, personnel and equipment monitoring
- procedures and other procedures needed to keep radiation exposure as low as l reasonably achavable. An operational check will be made of radiation monitoring equipment present, if all ec uipment responds properly, the operation will proceed.
- 2. The Reactor Supervisor will brief the disassembly group on each step prior to its accomplishment, with clarification made,if necessary, of the tasks to be performed.
- 3. Insure that the temporary cadmium md is in the glory hole and well fixed.
l l; I
m, , Fonn NEL.103 RSC Appront: 5/25/88
'4. Remove bottom cover plate (2 000169). De gasket (2 000593) should come off l
(') with the cover. Bag the cover plate thumb screws (H 1007 10) and label.
- 5. Insure that the control and safety rods have indeed been removed earlier, as l
declared. Label rods and store in approved fuel storage locations. Safe Rod Assembly: 2-000550 I Safe Rod Assembly 2-000550 II . Coarse Control Rod Assembly 2-000550 til i Fine Control Rod Assembly 2 000550 IV I
- 6. Remove the three dash pots (2-000510), label and store for future shipment. !
- 7. Remove the four control rod drive mechanisms. I
- a. Console power off(neutron detection channels 1,2, & 3 remain on). ;
- b. Disconnect rod drive power plugs. Identify and label each,
- c. Remove (2 each) jam nuts (1/4 28) from the tie bolts and carefully lower each rod drive frame assembly until free. Identify and label each frame.
Bag thejam nuts and label.
- 8. Insert cadmium in the control and safety rod holes in the core can.
- 9. Remove the top cover plate (2 000226). The gasket (2-000591) should come off with the cover. Bag the eight cover plate bolts (H 1069 12) and label.
- 10. Drain the thennal column,
- a. Obtain permission from the Health Physicist to drain thennal column water to sewer (a water sample will have been previously taken and analyzed for )
radioactivity as a basis for release of the water). )
- b. Pump water to sewer until thennal column is as dry as possible, j NOTE: The entries for health physics records will oc made in the Waste Log, f including: date/timet estimated water volume dumpcci; gross sample results
- in pCl/mt, % of applicable mpc, estimated activity dumped.
(~ 11. Remove the thermal column (2-000139): NOTE: . Dermal column could weigh 2,000 to 2,400 pounds, o
- a. Unbolt thermal column from reactor tank (16 each 3/4 inch bolts),
- b. Attach lifting sling and dynamometer to crane and thennal column. l
- c. Lift thermal column from well (the dynamometer will indicate the weight of the lead lined thermal column), lbs.
- d. Remove thennal colu:nn from reactor and move to an appropriate space on the ;
floor. Set thermal column on absorbent paper. ;
- c. Label thermal column. Bag the 16 cach 3/4 inch hold down bolts and label.
- 12. Remove the Ra Be neutron source (H 3018) from the graphite reflector. Leak test the source and place it in the storage container.
- 13. Conduct a core survey. Since the core tank will not be opened at this time, an off ;
gas sample will not be taken. A direct radiation survey and smear survey of the core ' tank top will be made.
- 14. Remove cadmium rod from glory hole (operator monitor neutron detector channels 1 ;
through 3, H.P. representative monitor portable neutron survey meter response). ; Only a slight increase in reading may be noted. (Log any reading change.) BEFORE AFTER CRM: LOG: LINEAR:
- 15. Remove glory hole tube,
- a. Remove glory hole flange (2-000419) (2 each) by removing (4 each) socket HD -
machine screws,1/4 20 X 1/2 (H-1023-C), b, Remove glo hole flange "0" ring (H 4009) (2 each). O V
- c. Remove glo hole tube (2-000422). Extreme care should be taken when removing th tube, it should not be bendstraight pull) and if binding is excessive,it may be necessary to lift the core tank slightly to relieve the bind.
1 2
< > Fonn NEL-103 ,i RSC Approval:5/25R8 '
COMMENTS:
)
I NOTE: The Health Physici:t will monitor very closely the removal of the core can. All radiation and criticality momtors wih be checked for proper operation just prior to the removal of the core, and surveys of radiation l levels from the core can will be made continuously during removal. : I
- 16. Core Can Removal (2-000114):
- a. Make a refemce mark on the core can and graphite reflector for reassembly J orientation.
- b. Attach lifting frame with cap screws (sock HD.,10 X 24) to core tank.
- c. Attach lifting frame and dynamometer to hoist. De dynamometer will monitor ;
lifting loads. 4 NO'E: Holst must be positioned with care to insure vertical alignment. Any_ l deviation from the vertical will cause binding of the core tank in the reflector i and shielding of the reactor. The unit being lifted weighs approximately 250 pounds. Tension should be ap) lied with the hoist and the core tank lifting frame should be manipulatec until any excess force is relieved. Tension is then again applied. The misuse of the electrical hoist could cause damage to the man will stand by thereactor reflector,if hoist circuit binding breaker (Panel occurs B, Breaker and
#5 in the force is ap) event of an "'sp" button failure of the hoist. Binding should be expected for l approximate 4y 4 inches until the thimbles have cleared the lower housing. !
Q V
- d. Lift the core tan't from the reactor.
- 17. Place an appropriare piece of cadmium in glory hole.
- 18. Conduct radiation survey to determine direct radiation levels from the core can and ,
removable surface contamination on the exterior surface of the can.
- 19. Transfer the core to its storage container,
- a. Remove lifting frame.
- b. Seal and label core can container and hold in Reactor Room.
- 20. Ilealth Physics will perform a radiation survey of accessible intemal surfaces to ascertain direct (induced) radiation levels and removable contamination levels.
NOTE: This concludes the nuclear portion of the disassembly process. The remaining disassembly will be conventional mechanical and electrical, with radiation surveys made as directed by the Health Physicist.
- 21. Remove the four eight access port cover assembly (2 000476):
- a. Remove the eig1t access port cover assembly (2 000476)
- b. Use a pole to push from one end, while another person is at the other end of the port, remove the port fillers (2 wood (2 000342),4 lead (2 000341),2 graphite (2 000340) each).
- c. Remove access port flanges (2 000418) (8 each) by removing (4 each) screws (H 1023 8)(socket HD mach., 1/4 201/2),
- d. Remove access port flange "0" rings (H-4008) (8 each).
- e. Remove access port tubes (2 000420)(4 each).
- f. Conduct health physics survey on the access port tubes, l
- g. Label all parts and store.
- 22. Remove the outer graphite shield (2-000140),
e a. Make alignment marks in the graphite shield and lead shield ring #1.
! b. Screw in lifting eyes.
NOTE: The lifting eye size will be determined and acquired sometime after the 3
l t Form NEL 103 ; RSC Approval:5/25E8 < thermalcolumn has been removed. () U
- c. Attach sling to hoist. (The graphite renector will weigh ~700 pounds.)
- d. Slowly raise graphite shield until clear of reactor,
- c. Actualreflectorweight: lbs. >
- f. Transfer to appro riate storage area and label.
- 23. Remove the fourlead shield rings,
- a. Make alignment marks on the first lead shield and reactor structure for .
reassembly,
- b. Screw in lifting eyes. (perhaps the graphite reflector eyes can be used.)
- c. Attach sling and dynamometer to hoist.
- d. Slowly raise lead ring; monitor for binding until clear of reactor.
NOTE: 1. cad rings 1 and 4 weigh 600 pounds, ring 2 weighs ~900 pounds, and ' ring 3 weighs ~800 pounds.
. e. Transfer to an appropriate storage area and label,
- f. Place alignment marks on next ring, and repeat process for all four rings.
Ring #1 (2-000123) ActualWel ht _._. _ lbs. Ring #2 (2 000122) ActualWel ht . Ibs. Ring #3 (2 000121)- ActualWel ht Ibs. Ring #4 (2 000123) ActualWel ht lbs.
- 24. Remove the core support plate (2111253),
- a. Place alignment marks on core su nort plate (top and bottom).
- b. From beneath reactor, remove ho:c down bolts (H 1114 96)(4 each, right. hand thread). Do not change positi on of tension nuts (H 2017).
CAUTION: Control rod drive tie bolts are still attached to core support plate. , Take care not to bend or break bolts.
- c. Manually lift plate from the top and transfer to floor area for storage.
(' 25. Remove the lead base plate shield (2 000124).
\ a. Make alignment marks on the lead base and reactor structure,
- b. Screw in lifting eyes.
__ c. Attach sling and dynamometer to hoist. (This piece should weigh slightly less than the thermal column.)
- d. Slowly raise lead base plate; watch for binding until clear of reactor.
Actual weight: lbs.
- c. Transfer to floor area for storage. -
COMMENTS:
- 26. Drain the shield water tank (2 000655).
- a. Obtain permission from the Health Physicist to drain shield water to sewer (a water sample will have been taken and analyzed for radioactivity as a basis for release of the water).
- b. Connect hose to drain valve (H 3009) at bottom of shield tank and drain water to sewer. Reactor manhole cover should be off.
NOTE: Entries win be made in the Waste Log, including: date/ time; estimated quantity dumped; activity of sample; estimated activity dumped.
- c. Close drain valve and remove hose.
- REMARKS
(}
- 27. Reactor electrical and instrumentation disassembly:
4 l
Form NEl.103 RSC Approval:.V25/88 i m De electrical and instrumentation cables will be disconnected in the following ! ( stattal sequence. Dey will be identified for future reassembly, surveyed, and i V; packaged for transportation. {
- a. Nuclear Channel #1: 3
- 1) Detector channel H.V. on. l
- 2) Ratemeter main power off. '
- 3) Open and remove access manhole cover. ;
- 4) ' Remove detector dry well from reactor tank shield water. l
- 5) Disassemble dry well.
- 6) Disconnect and tag pre am (2) and H.V (1) cables. -
- 7) Transfer components to clean area for radiological survey (gross smears),
and packing.
- b. Nuclear Channels #2 and #3:
- 1) Disconnect and tag H.V. cables at battery supply pack (rear of control ;
console).
- 2) Remove detector dry wells from reactor tank shield water.
- 3) Disassemble dry wells. '
- 4) Disconnect and tag signal and H.V. cables.
- 5) Transfer components to clean area for radiological survey and packing.
- c. Maindistributioncable: .
- 1) Main power switch Geft side reactor console) off.
- 2) Disconnect and tag P 15 (control console).
- 3) Disconnect and tag P 16 (control console).
- d. Miscellaneous:
- 1) Disconnect and tag monitor cable at control console. Pull it to storage beneath reactor tark.
G 2) Disconnect and tag main power cable. V 3) Remove the EARTHQUAKE SCRAM ASSEMBLY ball 013005), bag ! and label. l 4) Remove the THERMO SWITCH (E 10035). I a. Labelelectricalleads.
- b. Disconnect electrical leads.
- c. Label thermo switch and bag for shipment.
- 28. Console The console will be retained in its present location until fmal disposition.
l l l O 5
From NEL 104 ' RSC Approval: 5/25/88
~
University of Utah Nuclear Engineering Laborstory ,
/ 'i AGN 201 Reactor Defueling Procedure Gy I. Introduction This document gives the general procedures to be followed for defueling the AGN 201 reactor. These procedures give details regarding the preparations, monitoring, setup, j general procedures and spectTic defueling procedures.
NOTE: Check and date each item in the appropriate place as each step is accomplished. Maintain one mastercopy forreference,
- 11. Preonratinn prior to Defueling
- 1. Radiation Protection ,
- n. The following instruments will be checked for proper operation, then placed in 1205 E for use: '
- 1) High volume air sampler.
- 2) Neutron survey meter (Texas Nuclear Bonner Sphere).
- 3) Beta / gamma dose rate survey meter (Eberline). ,
t
. 4) Contamination survey meter (TBM 3S),
- b. he following supplies will be collected and placed in the reactor room for use I
as needed.
- 1) Filters for high volume air sampling.
- 2) - Smearing materials for wipe tests.
- 3) Containers for air filters and wipe test smears. '
- 4) Shielded storage container for storing the Ra Be neutron source.
- 5) Coveralls, lab coats, gloves, and shoe covers.
- 6) Radioactive waste containers.
, 7) Cadmium foil for core can insert. ;
- 8) Respira 2.
Work Area and grotection equipment (retain at first aid station unless requ
- a. Survey reactor room area in preparation of defueling actNities. ;
- b. Relocate equi pment as necessary to maximize working area room.
- c. Collect the following tools and place in reactor room:
- 1) Hand Tools required for disassembly (socket and Allen wrenches).
- 2) Handling tool for removing tl.e Ra Be source.
- 3) Lifting lugs and rigging for thermal column, core tank, and upper graphite reflector,
- d. The following items will also be placed in 1205 E:
- 1) Plastic bags for storing components. ,
- 2) Camera with flash and film for photographically documenting the !
procedure at key stages. III. Detailed Dicactembly Pmeezinres ' NOTE: The assembly part numbers are correlated with the part listing on drawing number E 2-000100. The ventilation system and air sampler should be operating during all disasssembly arocedures. ,- 1. A representative from the Radiological lealth Department will perform a pre-I defueling radiological survey l
- 2. The Reactor Supervisor will initiate special access procedures, personnel and i
equipment monitoring procedures and other procedures as needed to kee p personnel - radiation exposures as low as reasonably achievable (ALARA). An operational check will be made of radiation monitoring equipment. If all equipment responds properly, the operation may proceed. He Reactor Supervisor will bnef personnel involved in the l defueling operation on each step prior to its completion, with clarification made, as n necessary, of 'he tasks to be performed. V 3. Insure that the temporary cadmium rod is in the glory hole and well fixed.
- 4. Remove the top cover plate (2-000226). Drain the thermal column.
1
l I From NEL 104 RSC /,pprovah 5/25/88 I i
- a. Obtain permission from the llealth Physicist to drain thermal column water i to sewer (a water sample will have been previously taken and analyzed for l/}
b< radioactivity as a basis for release of the water). j
- b. Pump water to sewer until thermal column is as dry as possible.
NOTE: The entries for health physics records will be made in the Waste Log, j including: date/ time; estimated water volume dumped; gross sample results : in pCi/ml, % of applicable rnpe, estimated activity dumped. l S. Remove the thermal column (2-000139): i NOTE: 'Ihermal column is estimated to weigh 2,400 pounds. :
- a. Unbolt thermal column from reactor tank (16 each 3/4 inch bolts).
- b. Attach lifting sling to crane and thermal column.
.c c. Remove thermal column from reactor and move to an appropriate space on the floor. Set thermal column on plastic sheet or absorbent paper. -
- d. Label thermal column. Bag the 16 cach 3/4 inch hold down bolts and label. ,
- 6. Place borated paraffin over Ra Be source and perform radiation survey of thermal ;
column cavity. Replace top cover plate and secure to flange at top of reactor tank : until ready for removal of neutron source. Survey exterior surface of top plate cover . for radiation level and possible contamination; mark area as a radiation hazard as I appropriate.
- 7. Remove and survey each lead brick fmm thermal column. Use paper towels to dry the lead and dispose of towels as low level contaminated waste. Should any surface 1 of a brick yield a dose rate greater than 3 times the background rate, label and segregate from unactivated bricks; place bricks on polyethylene sheeting until a confirmatory survey by a Radiological Health Dept. representative indicates release of the bricks for unrestricted use. Any activated or contaminated bricks will be retained by UUNEL .
f .
- 8. Remove bottom cover plate (2-000169). The gasket (2 000593) should come oft i with the cover. Bag the cover plate thumb screws (H 1007 10) and label. .
- 9. Insure that the control and safety rods have indeed been removed earlier, as ;
declared. Label rods and store in approved fuel storage locations. Safe Rod Assembly: 2-000550 I Safe Rod Assembly 2-000550 II Coarse Control Rod Assembly 2 000550 III Fine Control Rod Assembly 2-000550 IV
- 10. Remove the three dash pots (2-000510), label and store for future disposition.
- 11. Remove the four control rod drive mechanisms,
- a. Console power off(neutron detection channels 1,2, & 3 remain on),
- b. Disconnect md drive power plugs. Identify and label each.
_ ._, c. Remove (2 each)jarn nuts (1/4-28) fmm the tie bolts and carefully lower each md drive frame assembly until irce. Identify and label each frame. ' Bag thejam nuts and label.
- 12. Insert neutmn absorber in the control and safety rod holes in the core can.
- 13. Remove the top cover plate (2-000226). The gasket (2-000591) should come off with the cover. Bag the eight cover plate bolts (H 106912) and label.
- 14. Remove the Ra.Be neutron source (H 3018) from the graphite reflector. Wipe test the source and place it in the storage container. Survey storage container,
- 15. Conduct a core survey. Since the core tank will not be opened at this time, an off ,
gas sample will not be taken. A direct radiation survey and smear survey of the core tank top and environs will be made.
- 16. Remove cadmium rod from glory hole (operator monitor neutron detector channels 1 through 3, H.P. representative monitor portable neutron survey meter
, n response). Only a slight increase in reading may be noted. (Log any reading l V change.) BEFORE AFTER l 2
From NEL 104
' RSC Approval: $/25/88 f 3 CRM:
73 LU LINEAR:
- 17. Remove glory hole tube.
- a. Remove glory hole flange (2-000419) (2 cach) by removing (4 each) socket HD machine screws,1/4-20 X 1/2 (H 1023 8).
- b. Remove glory hole flange "0" ring (H 4009)(2 each).
- c. Remove glory hole tube (2 000422). Extreme care should be taken when removing this tube. It should not be bent (straight pull) and if binding is l excessive,it may be necessary to lift the core tank slightly to relieve the bind.
- COMMENTS:
t NOTE: The Health Physicist will carefully monitor the removal of the core can. All radiation and criticality monitors will be checked for pro)er ' operation just prior to the removal of the core, and surveys of radiat.on levels from the core can will be made continuously during removal.
._ 18. Core Can Removal (2-000114): '
- a. Attach lifting frame with cap screws (sock HD.,10 X 24) to core tank.
- b. Attach lifting frame and to hoist.
NOni: Holst must be positioned with care to insure vertical alignment. Any deviation from the venical will cause binding of the core tank in the reflector and shielding of the reactor. The unit being lifted weighs approximately 250 pounds. Tension should be apalled with the hoist and the core tank
-v(}^ lifting frame should be manipulatec, until any uneven tension is relieved.
Tension is then again applied. The misuse of the electrical hoist could cause i damage to the reactor reflector, if binding occurs and force is applied. A man will stand by the hoist circuit breaker (Panel B.-Breaker #5) in the button failure of the hoist. Binding should be expected for event of an 4"up" inches until the thimbles have cleared the lower hou approximately
- d. Lift the core tank from the reactor.
NOTE OF INTEREST: Other facilities have measured a loss of reactivity.after removing the core tank : U.S Naval Postgraduate School and Colorado State University).
- 19. Place an appropriate piece of neutrun absorber (Cd or In)in glory hole.
- 20. Conduct radiation survey to determine direct radiation levels from the core can and removable surface contamination on the exterior surface of the can,
- 21. Transfer the core to its storage container.
- a. Remove lifting frame.
- b. Seal and label core can container and hold in Reactor Room.
- 22. Health Physics will perform a radiation survey of accessible internal surfaces to ascertain dutet (induced) radiation levels and removable contamination levels.
NOTE: This concludes the nuclear portion of the disassembly process. The remaining disassembly will be conventional mechanical and electrical, with radiation surveys made as directed by the Health Physicist. O. 3
From NEL.105 Procedure for Removal of AGN Control Rods OV Precautions: Be sure pro procedure. per ventilation and air sampling equipment is in operati materials.
- 1. Remove the nuts securing the control rod drive assembly to the AGN structure taking care to suppnet the assembly as t1e last nut is removed.
- 2. Carefully lower the control rod avoiding binding and remove the assembly from the crawl >
space beneath the reactor. ,
- 3. Survey the rod and record radiation levels in spaces provided below. Wi e the exterior !
surface of the fuel cladding to determine if surface contamination exists. hote below any removablecont. amination discovered. j Instrument:
' Serial No.: !
Calibration Date: CR1 CR2 Fine Coarse Max level
@ contact .
Max. level ,
@ l foot
']\
; 4. Unserew the fueled control rods from the remainder of the assembl and place in the temponry storage container. Survey the drive assemblies for any residu 1 contaminatior. or activation. Note below any elevated radiation levels. Set the drive assemblies aside for future use as necessary. ,
- 5. Re gat steps 1 through 4 for each controi rod. Insert borated paraffin between the control _;
rod s and secure container lid when all fuel has been loaded.
- 6. Load borated paraffin into the reactor core through the control rod guide tubes assuring that the paraffin will remain in place.
- 7. Place the temporary storage container in the Middle Fuel Storage Pit and secure until ready for shipment to DOE.
- 8. Comments: '
t 4 Date Procedure Started: __ Date Procedure Finished: Procedure reviewed and approved on behalf of the Reactor Safety Committee by: AGN Reactor Supervisor:
Form NEL 106 L
; RSC Approval: 5/8/89 Procedures for Removal of Ra Be Neutron Source from AGN.201 Reactor
- )
v Precautions: Be sure proper ventilation and air sampli,ng equipment are operating during this l procedure. Gloves and personnel dosimetry must be worn throughout this L procedure.
- 1. Remove the top cover plate from the reactor and remove the borated paraffin covering the Ra Be source.
- 2. Using a remote swiping tool, obtain a wipe of the top of the source and the area immediately surrounding the source. Minimize the exposure time and use the AGN tank to provide as much shielding as possible.
- 3. Analyze the wipe with both a contamination survey meter and gamma spectroscopy. Record the results below.
Survey Instrument: j SerialNumber: Calibration Date:
Background:
Gross Counts: Net Counts: Conunents:
'bc
Gamma Spectroscopy (Attach spectrum): Instrument: Visible Peaks: Radium Daughter Products: ___yes no Conments: 4, If any evidt.nce of leakage of the neutron source exists, notify the Reactor Supervisor. Otherwise, follow the remaining items of the procedure.
- 5. Place the neutron source transfer container next to the AGN reactor on the upper floor of the f' reactor Toorit -
4 - l 6. Make sure a strong neutron absorbing material such as boron or cadmium has been inserted i o
\
+ ;- l Form NEL 106 j RSC Approval: 5/8/89 1
!, 4 h: J into the core through at least two control rod guide tubes. l t
' s\
Absorbing material: mass: grams
- 7. Transfer the source from the AGN reactor to the transfer container using a remote handling j tool and secure container. Wipe the source while transferring to container. Also wipe and survey the location of the reactor containing the source. Record data below. ,
3 Survey Instmment: i Serial Number:
, Calibration Date:
Source Wine Reactor Wine ,
Background
Gross Counts , i Net Counts Radiation level @ contact at source location: mr/hr ; Gamme Spectroscopy (Attach spectrum): ; Instrument: Peaks: ; Comments:
, X.
[ v}
- 8. Place lid on and secure neutron source container. Perform external radiation corev of container. Mark container with radiation hazard signs and label with source ac'hity. Store b MEB 1205 A (Irradiation Facility Room).
Extemal radiation survey of container: Survey Instrument: ' Serial Number-Calibration Date: Maximum dose rate @ contact: mr/hr Maximum dose rate @ l foot: mr/hr L
- 9. Replace and secure top cover plate of reactor. .
I Surveys Performed by: Date: Procedure reviewed and approved on behalf of the Reactor Safety Committee by: 7) V AGN Reactor Supervisor: Date:
n. Form NEL 107 RSC Approval: 8/18/89 g L < AGN.201 REACI'OR DEFUELING CilECKLIST I Date oflast teactor operation: Date control rods removed: }' Date Ra Be neutron source removed: ._, Calculated kerr of fuel remaining in core:
- 1. Briefing conducted for defueling personnelincluding precautions and procedures:
1 Initial conditions satisfied: Reactor Supervisor
- 2. a. Glory Holelinerremoved:
- b. Thermal Column Tank removed:
- c. Core tank top (cover on): mr/hr on contact Survey Insrument: _
Serial Number: Calibration Date:
- d. Activity of gaseous sample from core tank: pCi/mL l e,f. Top reflector activity:
- g. Top of core (cover off): mr/hr on contact
- h. (1) Poly disk activity:
(2) Top of fuel: mr/hr fixed alpha wipe c i. Top (T) t/4 thk fuel disk: 3 ( ID Number: Weight: grams p,y _ mr/hr fixed alpha wipe (T 1)1/4 thk. fuel disk: ID Number: Weight: grams p,y mr/hr fixed alpha wipe (T-2) in thk. fuel disk: l ID Number: Weight: grams ; D,y mr/hr j fixed alpha wipe (T 3) in thk. fuel disk: ID Number: Weight: grams
,y mr/hr fixed alpha Wlpe (T 4) in thk. fuel disk:
ID Number: Weight: grams
,y mr/lu
/7 fixed alpha d wipe
- j. Dummy disks and graphite 4 reflector installed:
f f Form NEL 107 '! i RSCApproval: 8/18/89
- k. Core tank cover and !
l i lifting ringinstalled: - k'-
- l. Surface of the core tank: mr/hr m,n. Thimble fitup to upper core half full thk. disk:
COMMENTS: ! I i
- o. (T 5) full thk. fuel disk: i ID Number: ._ Weight: grams
@,Y fixed alpha -
wip '!
- p. Thimble contamination: mr/hr '
q,r. lower core half: (T 6) full thk. disk: ID Number: . Weight: grams j
@iT fixed alpha -,
wipe j (T-7) full thk. disk: ID Number: ,_. Weight: grams - P,Y [') LJ fixed alpha wipe (T 8) full thk. disk: ' ID Number: Weight: _. grams E.Y fixed alpha , wjpe 4 Core fuse ID Number: . Weight: grams j P.Y fixed alpha smear
- s. Lower reflector activity: I
- t. Core tank interior p,y. mr/hr wipe
- u. Final disposition of core tank and fuel tanks: I Comments-r Surveys performed by: _ Date:
Form reviewed and approved on behalf of the Reactor Safety Committee by: i' ( K' AGN Reactor Supervisor: Date: .
- . . , .~ -
~
l l MEMORANDUM To: Reactor Safety Committee (RSC) i Prom: John BennionM 4 Date: September 21r!N9
Subject:
Repon of AGN Reactor Decommissioning Activities j The following summarizes AGN decommissioning activities completed to date, those in progress, and those that will be accomplished in the future. The RSC has previously approved several 1 documents pertaining to this effort including the detailed disassembly procedure, procedure for the ; removal of the Ra Be neutron source, the defueling procedure (both control and safety rods and the ; reactor core), as well as the radiation survey procedure and the forms on which those surveys are I recorded. ; The first major decommissioning project involved the surveillance and disposal of the concrete shielding block originally surrounding the AGN reactor. More than 2700 blocks were carefully surveyed for contamination or radioactivity in excess of background levels and loaded onto pallets fcr transfer from UUNEL. On March 25,1988, nearly six months after the project was started, all blocks designated for disposal had been surveyed and transferred to a contractor for ultimate disposition following a independent final survey conducted by the Radiological Health Depanment. (3 None of the blocks was found to be contaminated or exhibit activity in excess of background, v in April,1989, water from the thennal column was sampled for radioactivity content. Analysis showed no detectable concentrations of any radionuclides (except for naturally-occurring K 40). Approximately 254 liters of this water was siphoned to the sanitary sewer for disposal. The themial column was then removed from the reactor structure using the overhead crane and placed on plastic sheeting on the reactor room floor. At this time wipes were taken from the underside of the thermal column and the interior cavity of the AGN structure immediately above the core tank can Borated paraffin was placed over the Ra Be neutron source upon lifting the thennal column to reduced the I neutron dose to personnel. The lead brick layer at the bottom of the thennal column was removed. Each brick was surveyed for radioactivity, but no contaminated brick was found. The remaining l water in the thennal column was filtered, analyzed, and discharged to the sewer. The epoxy lining of the column began to blister and peel as soon as the top of the AGN was unsealed. Uaon removal L of the lead brick and water from the column, the remaining epoxy was scraped off anc placed in a p lock bag for further anal sis. Analysis of the wipes showed no indication of fission products, 1, or other radioisotopes, n addition, no activity was detected in the epoxy linmg. The control and safety rods were removed from the reactor on May 2,1989. A total of 35 grams of lR cadmium was inserted into the core through the guide tubes of the rods and locked in place to l ensure that ke rt was less than 0.8 as required by AGN Technical Specifications. The fueled portions of the rods were detached from the drive assemblies and sealed in plastic after wiping the exterior surfaces. No evidence of fission products or other radioactive lea < age or contammation was observed. The fueled rods were then secured in the Middle Fuel Storage Pit. The control and safety rod drives were surveyed and found to be free of contamination. L
-P d
On May 5,1989, the 10 mci Ra Be neutron source was removed from the reactor and placed in a paraffin lined shipping container. This task was accomplished under the supervision of Gary
I Reactor Saety Committee Memorandum Report of AGN Reactor Decommissioning Activities i
, September 27,1989 !
) page 2 l
paraffin lined shipping container. This task was accomplished under the supervision of Gary Sandquist, AGM Reactor Supervisor, and Bob Hoffman, alternate Radiation Safety Officer. The 1 source was stored on the lower floor of the reactor room behind the TRIGA reactor tank. A cave l made from concrete block surrounding the source container was constructed to reduce exposure l from the source until transfer from UUNEL occurred. The source was leak tested by the J I Radiological Health Department on August 23,1989; no evidence of leakage was observed. The source was transferred to Radiological Health and removed from UUNEL on August 31,1989 for i final disposition. A core gas sample was obtained in preparation of defueling the reactor by connecting the core tank spigot to an evacuated chamber and opening the spigot to allow the pmssure in the core tank and the i ' chamber to ecullibrate. The gas sample was counted using the Nal(TI) detector; no detectable activity was osserved. A gamma spectrum of the sample using the intrinsic germanium detector showed no evidence of any fission products. Defueling occurred on August 18,1989, under the direction of Dr. Sandquist. The core tank can was hoisted out of the reactor structure and placed on plastic sheeting spread over the floor of the reactor room to contain a possible release of radioactive , o material. Strict procedures wem followed to minimize any contamination of the area or personnel, in addition, a high volume air sampler was operated throu ghout the procedure to collect airborne . j particulates for analysis of radioactivity. The hermetical y-scaled core can was opened and its contents were carefully removed, surveyed, and inventoried. The fuel discs were placed into two storage containers (one half of the core in each) with blocks of borated paraffin to reduce further the reactivity of the fuel. The containers were then secured in the Fuel Storage Pit. Subsequent detailed surveys of each piece of fuel and all core components for both fixed and removable alpha (V3 activity as well as beta and gamma activity and the decontamination of contaminated components is still in progress. All fuel has been surveyed, weighed, and sealed in plastic and is being stored in , the Fuel Storage Pit pending the return of the fuel to its owner, U.S. DOE A letter requesting assistance in the return of the fuel has been sent to the DOE Idaho Operations Office. We are presently waiting for instructions for transfer of the fuel to the repository at Oak Ridge, Tennessee. The next major task to be completed is the submittal of the final version of the Decommissioning Plan to the Nuclear Regulatory Commission. Other important tasks remaining to be completed are: l 1. Sample, analyze, and drain the water shield,
- 2. Complete transfer of fuel to Oak Ridge, l 3. Complete and document all surveillances of AGN reactor components and structures and decontaminate contaminated components as necessary, and
- 4. Submit Request for License Termination to NRC.
O
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APPENDIX G- i OUTLINE OF PRONIT1"RRR REGARDING REANR SAFEGUARDS AND PHYSICAL SECURITY ., t t 4 i
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i I Outline of Procedures for Physical Security of l AGN 210M Reactor SNM During Decommissioning and Dismantling < l i The University of Utah AGN 20lM Nuclear Reactor (UUAGN) was defueled on 18 August j 1989 as allowed by the facility operating license (R 25). Following removal from the reactor dt loc p s ep n con lle a ess ar a( ) of the Nuclear Engineering Laboratory (UUNEL). The fuel was removed from the reactor in j accordance with a detailed defueling plan submitted and approved by the Reactor Safety + Committee and as permitted by the revised Physical Security Plan (PSP) which was approved by the NRC on 10 July 1989. , { ! [ j The UUNEL is currently awaiting approval from DOE (Idaho Operations Office), which 7 i h owns the fuel, to ship the fuel to DOE's Y 12 Scrap Plant in Oak Ridge. Tennessee for final disposition. - Pending fuel transfer, the UUAGN special nuclear material (SNM, i.e., the fuel) i will be periodically inspected and inventoried to insure material security and safety from l tampering or damage. In addition, periodic radiological surveys will be performed to assure that f
- the integrity of the SNM and its storage containers is maintained. All reactor components ,
l- : removed during the defueling process have been surveyed and sealed in plastic wrapping and placed in the thermal column tank. The thermal column has been reinstalled and sealed in the [ reactor structure pending approval from NRC for decommissioning and disassembly of the , UUAGN. l Upon receiving appmval for the fuel transfer, UUNEL will ship the fuel in accordance with l pertinent requirements of 10 CFR 73.67(g) and the facility's PSP. Thereafter, the only SNM connected with the UUAGN is the core fuse and an unirradiated fission plate, both of which have been transferred to the University's Broad Form License (UT 1800001). An amended PSP will be submitted to NRC following fuel shipment that will reflect the fact that all fuel from the UUAGN has been removed from the UUAGN and transferred to DOE or other appropriate l facility licenses.
7 3 1 l- . ! 1 1
'[l s, = l APPENDIX H UUAGN TECHNICAL SPECIFICATIONS 4
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. 1 APPENDIX A :
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L TO FACILITY OPERATING LICENSE NO. R-25 3CHNICALSPECIFICATIONS ; FOR i THE INSTITUTIONAL COUNCIL OF THE UNIVERSITY OF UTAH
, 1 AGN-201M REACTOR (SERIAL #107) 1 DOCKET NO. 50-72 g
.i Amendment No.10 l- Dated: May 2, 1979' t
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- ' S i t.'t s..,
i TABLE OF CONTENTS jl?i1' V' l <
' PAGE i i
, i ~ 1.0 ' DEFINITIONS .<... .~. . . . . . . . . . . . . . . . . , . . -1 ,{
y, I t 2.0 ' SAFETY- LIMITS - Ahi) LIMITING SAFETY SYSTEM SETTINGS . . . . . 4 l i 2.1 Safety Limits . . . . . . . . . . . . . . . .. . . . . 4 ; 2.2 1 Limiting Safety System Settings . ........... 4 i
. j
- 3.0' LIMITING CONDITIONS FOR OPERATION. . . . . . . ...1 . . 5 !
L, -3.1 Reactivity, Limits;. . . . . . . . . . . . . .. . . . . 5 3.2 Control-and Safety Systems. . ... . . ... . .. . . . . 6 I 3.3 Limitations on: Experiments. . ..,... . .. . . . . 9- j
-a 3.4 Radiation Monitoring, Control and Shielding. . . . . . . 10 "
i T 4.0 SURVEILLANCE REQUIREMENTS. . . . . . . . . . . . .. . . . . 11
)
4.1 Reactivity Limits . . ..... . . . . . . .. . . . 11 i 4.2- Control and Safety System . ....... . . . . . . 12
-4.3 Reactor Structure . . . .
. . . . . . . . . .. . . . 13
. 4.4 Radiation Monitoring and Control. . . . . . . . . . . 13 5'. 0 DESIGN FEATURES. . . . . . . . . . . . . . . . . .. . .. . . 14 5.1 Re a c t o r L . . . . . . . . . . . . . . . . . : . . . . . . . 14 5.2 Fuel Storage. . .- . .... ...... . .. . . . 15 5.3 Reactor' Room. . .-. . ....... . . . . . . : . . . . - 15 6.0 ADMINISTRATIVE!CONIROLS. . . . . . . . . . . . . .. . . . 15 6.1 ' Organization. . . . . . . . . . . . . . . . .. ... . 15 6.2 -Staff. Qualifications. . . . . . . . . . . . .. . . . 20 6.3 Training. ............ ..........20 6.4 Reactor Safety Committee. . . ...... .-.. . . . . 20 6.5 ' Approvals . . .. . . - . . . . .
. . . . . . . .. . . . 22
- 6. 6 -- Proc e d ur e s . :. ' . - . . . . . . . . . . . . . . . . . . , 2 2
' 6. 7 : Experiments ' . .. . . . . . .--. . . . . . . . .. . . . 23 6.8 Safety Limit Violation. ... . . . . . . . . .. . . . 23 6.9 Reporting Requirements. ......... . .. . . . 23 -
6.10 Record Retention. . . . . ., . . . . . . . . .. . . . 25
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g~ , n; v' ; (j 1.0 DEFINITIONS , The terms Safety Limit (SL), limiting Safety System Setting '(L555), i and Limiting conditions'for Operation (LCO) are as defined in 50.36. of 10 CFR Part 50. i c . 1 '.1 - Channel Calibration A channel calibration is an adjustment of , the enannel such that its output responds, within acceptable range , and accuracy, to known values of the parameter wnich the channel . ! measures. Calibration shall encompass the entire channel, including f M equipment, actuation, alarm, or trip. ['V 1.2 Channel Check - A channel check is a qualitative verification of acceptable performance by observation of channel behavior. This verification may 1.nclude comparison of the channel with other independent channels or methods measuring the same variable, o 1.3 Channel Test - A channel test is the introdu: tion of.a signal into ' the enannel to verify that it is operable. 1.4 Exoeriment . ~
- a. An experiment is any of the following:
(1) An activity utilizing the reactor system or its components . or the neutrons or radiation genera:eo therein; " I (2) An evaluation or test of a reactor system oper'ational. 1 surveillance, or maintenance technique; or (3) The material content of any of the foregoing, including structural components, encapsulation or confining l. boundaries, and contained fluids or solids,
- b. Secured EIceriment - Any experiment, or component of an experiment is deemed to be secured, or in a secured position, if it is held in a stationary position relative to the reactor ,
by mechanical means. The restraint shall exert sufficient force on the experiment to overcome the expected effects of hydraulic, pneumatic, bouyant, or other forces which are normal to the c ocerating environment of the experiment or whien mignt arise + as a result of credible malfunctions. w
- c. Unsecured Experiment - Any experiment, or component of an experiment is deemed to be unsecured whenever it is not secured as defined in 1.4.b above. Moving parts of experi-
' ments are deemed to be unsecured when they are in motion. ct D
'V) p4 1 _
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- d. Movable Exoeriment - A movable experiment is one which may be insertec, removec, or manipulated while the reactor is critical .
; ) !
l C' e. Removable Exoeriment A removable experiment is any experiment. l experimental facility, or component of an ex;eriment, other than # a permanently attached appurtenance to the reactor system, which can reasonably be' anticipated to be moved one or more times
- during the life of the reactor. .
1.5 Exeerimental Facilities - Experimental facilities are those portions of the reactor assembly that are used for the introducticn of experi-ments into or adjacent to the reactor core region or allow beams of radiation to exit from the reactor shielding. Experimental facilities - r shall include the thermal column, glory hole, and access ports. I 1.6 Exelesive Material - Explosive material is any solid or liquid which is categorized as a Severe, Dangerous, or Very Dangerous Explosion Hazard in " Dangerous Properties of Industri-al Materials" By N. L. Sax, Third Ed. (1968), or is given an Identification of Aeactivity (Stability) index of 2, 3, or 4 by the National Fire Protection Association in its publication 704-M,1966, "Identifica-tien System for Fire Hazards of Materials," also' enumerated in the '
" Handbook for Laboratory Safety" 2nd Ed. (1971) published by The Chemical Rubter Company. - -
1.7 Measurino channel - A measuring channel is the combination of sensor,
/] lines, amplifiers, and output devices which are connected for the .
G purpose of mearuring or responding to the value of a process variable. 1.8 Deerable - Operable means a component or system is capable of per-forming its intended function in its normal manner, 1.9 Deeratino ,- Operating means a component or system is performing its intended function in its normal manner. 1.10 potential Reactivity Worth _ - The potential reactivity worth of an experiment is the maximum absolute value of the reactivity change that would occur as a result of intended or anticipated ; changes or credible malfunctions that alter experiment position or configuration. Evaluations of potential reactivity worth of experiments also shall include effects of possible trajectories of the experiment in motion relative to the reactor, its orientation along each trajectory and circumstances which an cause internal changes such as creating or filling of void spaces or motion of mechanical components. For removable experiments, the potential reactivity worth is equal to or creater than the static reactivity worth. 1.11 React:r Comoonent - A reactor ::::enent is any a:carttus, devi:e, , or material :na: is a normal : art of the rea :or assemoly. i '.12 Esact:r Ooera:itn - Rea:::r c: era: ion is any 00ntition wntrein tne rea:::r is n:: shut e:wn. 2
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- 1.13 Reteter Safety System . The reactor safety system.is that c:mtination. ;
y, of safety enannels and associated circuitry which forms the avt:matic 7Y prctective system for the reactor or provides information whi:h G requires manual protective action be initiated. 1.14 Retetor Shutdewn - The reactor shall be considered shutdown whenever
- a. either: 1. All safety and control rods are fully withdrawn l from the core, or
,I 2. The' core fuse melts resulting in separation of the l core, .
and:
- b. The reactor consol' e key switch is in the "off" position and the key is removed from the console and under the control of a licensed operator or the Reactor Administrator.-
1.15- Safety Char.nel - A safety channel is a measuring channel in the + rea::or safety system. , l
,,i 1.16 Stati: Reactivity Worth - The static reactivity worth of an .
experiment is the aosolute value of-the reactivity change which is measurable by calibrated control or regulating red c:mparison methods between two defined terminal positions or configurations of the experiment. For removable experiments, the terminal positions
; (~') '
v are fully removed from the reactor and fully inserted or installed ,
,o in the normal functioning or intended position. ;
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(v. ,) 2.0 S ATCTY 11MITS AND LTMITING SATETY SYS~EM SETTINGS 1 s
.2.1 Safety Limits Applicability This specification applies to the maximum steady state power level l and maximam core temperature daring steady state or transient opera-tion.-
Oblective , i To assure.that the integrity of the fuel material is maintained and all fission products are retained in the core matrix. ' Specification
- n. The reactor power level shall not exceed 100 watts,
- b. The maximum core temperature shall not exceed 2000C during either steady state or transient operation.
Bases r- The polyethylene core material does not melt below 20000 and is expected ,
-! to maintain its integrity and retain essentially all of the fission products at temperatures below 2000C. The Hazards Summary Report dated February 1962 submitted on Locket F-15 by Aerojet-General Nucleonics (AGN) calculated a steady state core average temperature rise of 0.44 C/vatt..
Therefore, a steady state power level of 100 watts would-result in an avetage core temperature rise of 4400. The corresponding maximum core temperature would be below 2000C thus assuring integrity of the core and retention of fission products. 2.2 timiting Safety System Settings Applicability This specification applies to the parts of the reactor safety system which will limit maximum poser and core temperature. b Objective . To assure that automatic protectiva action is initiated to prevent a safety. limit from being exceeded. Seecification
- a. The safety channels shall initiate a reactor scram at the following limiting safety system settings:
lI 3 _
n ! 1 Ccndition LSSS Channel Nuclear Safety #1 High Pcwr 1 10 watts l Nuclear Safety #3 High Power 110 watts
- b. The core thermal fuse shall :nelt when heated to a temperature et l about 1200C resulting in core separation and a reactivity loss greater than Sid. [
Bases hsed an instnanentation resr/ase timas and scran tests, the &N ' Hazards Report concluded that reacter periods in excess of 30-50 f milliseconds would be adequately arrested by the screa system. Since the mart == available excess reactivity in the reactor is less than one dollar the reactor cannot bocae pnznpt critical and the ! corzusponding shortest possible period is greater than 200 milli- 4 seconds. D e high power LSSS of 10 watts in conjunction with auto-
- natic safety systams and/or ====1 scram capabilities will assure that the safety limits will not be exceeded during steady state or as a re-
, sult of the most severe credible transient.
In the event of failure of the reacter to scrInn, the self-limiting characteristics due to the high negative tanperature coefficient, and the melting of the thermal fuse at a temperature below 120*C will C assure safe shutdown without exceeding a core temperature of 200*C, 3.0 LDGTING CCNDITICNS FOR OPSATICN 3.1 Reactivity Limits Acca ability This specification applies to the reactivity condition of the reactor l and the reactivity worths of c::ntrol mis and experiments. Cbiective To assure that the reactor can be shut down at a11 times and that the safety limits will not be exceeded. Scecification
- a. The available excess reactivity with all control and safety rods fully inserted and including the potential reactivity worth of all experiments shall net exceed 0.551 ak/k referenced to 20'C.
O
4 , '"k b.-_ The shutdown margin with the most reactive safety or_ contal
- m d fully: inserted shall be at lesst 14 A k/k.
- c. - The reactivity worth of the control and safety mds shall ensure sub-criticality on the withdrawal of the coarse control rod or-any one safety rod.
Bases The limitations on total core excess reactivity assure reactor per-' iods of_ sufficient length so that the reactor pw.ection system and/or operator action will be able to shut the res.cor down with-out arcHtag any safety limits. The shutdown margin and control and safety md' reactivity limitations assure that the reactor can be brought and maintained subcritical if the highest reactivi v rod Edu to scrum and rammins in iu most reactive positions. 3.2 Contro.1 and Safety Q3 3 3y, Aeolicability-nese specifications apply to the reactor control and safety systems. Chiective h To specify lowest acceptable level of performance, instrument set
; points,~ and the mir+== number of operable components for the reactor control and' safety systems.
Soecification a; -The total scram withdrawal time of the safety rods and coarse control rod- shall be less *Juin 200 milliteconds.
- b. The. average reactivity addition rate for each control or safety rod.shall not exceed 0.065% ak/k per second.
- c. Tne safety rods and coarse control rod shall be interlocked
.such that:
'1. Reactor startup cannot m ma v e unless both safety rods and coarse control rod are fully withdrawn frem the core.
- 2. Only one safety rod can be inserted at a time.
- 3. ne coarse centrol :od cannet be inserted taless both safety rods are fully inserted.
J. M1 reactor safety system instrumentation shall be operable in accordance with Table 3.1 whenever the reactor control or safety 9 rods are not in their fully withdrawn position. anfety channel dl may be bypassed for operation at However "uclear power levels excet: ding 0.1 wat t . l 4
- - -- - ~ - - - - - - - - - - - - - - - -
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TABLE 3.1 f
' Safety Chamel . Set Point Ftmeticm, I Nuclear Safety #1* "
i
' Low count rate. ,
t 10 cps scram below 10 cps t y NuclearSafpty#2l . - s .High power- < 10 watt _ scram at power >10 watt 3
. Iow power. t 1.0 x 10-12 amps scram at source levels '
t
< 1.0 x 10-12 ,,p, l.
, ; Reactor period
. >, 5 see scram at" periods < 5 sec j 1
Nuclear Safety #3_~ (Linear Power) High Powerf < 10 watt
- scram at power >10 watt '
Low pc9 :: > 5% f.111 scale 1: scram at source levels S 4 +
< 5% -of f.11.1 scale 1
L! %
. nual 5Cr3m -------------
scram at cperator optica Nuclear Saf et" Chanr.el vil mav i:e 'e passed a: power levels exceeding 0.1 watt. ,s , l i
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'e. The shield water level interlock shall be set to prevent reactor -;
, startup and scram the reactor if the shield water level falls-10.5: 4 inches below the highest point on the reactor shield tank manhole ,
. opening.
- f. The shield water temperature interlock shall be set to prevent '
reactorstartugandscram'thereacteriftheshieldwatertemperature falls below 15 C.
- g. The seismic displacement interlock sensor shall be installed in such I f
a manner to revent reactor startup and scram the reactor.during: j a seismic lacement. '
- h. A loss of electric power shall cause the reactor to scram. !
Bases ! The specifications on scram withdrawal time in conjunction with the safety y system instnanentation and set points assure safe reactor -shutdown durdag - the most severe foreseeable transients. Interlocks on centrol and safety rods assure an orderly approach to criticality and an adequate, shutdown ; c?pability. The-limitations on reactivity addition rates allow'on1.y relatively slow in:reases of reactivity so that ample time will be available (or manual
-or automatic scram during any operating conditions.
.d The neutron detector channels (nuclear safety channels 1 through '3) assure that reactor power levels are adequately monitored during reactor startup i
and operation. Requirements en minimum neutron levels will prevent reactor startup unless channels are operable.and responding, and will cause a scram in the event of instnnentatica failure. The power level scrams
. initiate rehat automatic protective action at power level scrams low i enough to assure safe shutdown withcut. exceeding any safety limits. The period scram conservatively limits the rate of rise of reactor power to
. periods which are manually centro 11able and will autcmatically scram the reactor-in the event of unexpected large reactivity additions.
,' The AGN-201's negative temoerature coefficient of reactivity causes a reactivity increase with' decreasing :cre temperature. The shield water temperature interlock will prevent reactor operation at te=peratures below 15*C thereby limiting potential reactivity additiens associated with temperature decreases. .
Water in the shield tank is an imcortant c:moonent of the reactor snield and operation without the kater =av produce excessive radiation levels. The shield tank water level interlock will crevent reactor cperatien without adecuate uter levels in .;e shield tank. .O
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l(~i)?; - The reactor is designed to withstand 0.6g accelerations and 6 en _
) 'D' displacements. A seismic instrtanent causes a reactor. scram whenever the instrument receives a horizontal acceleration that causcs a ;
hori:antal disp 1mes==nt of 1/16 inch or gteater. The seismic I 1: displacement interlock assures that the reactor will be su J and ; brought to a'subcrithal configuration during any seismic disturbance-
.. ,+- that may cause damage to the reactor or its camponents.
' The mann=1 scram allows the operator to -=nn=11y shut down the reactor ;
- a. J- -if an unsafe or otherwise abnormal A loss .ofemdition electricaloccurs power that does not de-energi:es
% .otherwise scram the reactor.
the safety and coarse control rod holding magnets causing a reactor e
' Q' ' ' M screa thus assuring safe and imediate shn+d~n in case of a power T outrage.
3.3 t4=4tations an Experiments og
- Applicability f w /
This specification applies to experiments installed in the reactor and
.W : , its experimental f=e4Hties. - .
Objective n o To prevent damage to the reactor or excessive release of radioactive
' h, materials in the event of an egeriment failure, e2 1 Specification v .o
- a. Experiments containing materials corrosive to reactor c ==smts
$o or which contain liquid or gaseous, fissianable materials shall be douoly encapsulated. t
- b. Explc,sive materials shall not be inserted into experimental facilities of the reactor or stored within the. confines of the reactor facility.
> c. The radioactive material content, including fissicn products of any experiment shall be limited so that the complete release of all gaseous, particulate, or vMatile components fran the 4 experiment will not result in nses in excess of 10% of the 3 equivalent =mn=1 doses statei .n 10 CFR Part 20 for persons occupying -(1) unrestricted areas continuously for r,c hours <
i starting at time of release or (2) restricted areas during the C 1ength of time reouired to evacuate the restricted area.
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-O(; 'd. The radioactive material content,. including fission products of any doubly encapsulated exper:. ment shall be limited so that -
the complete release of all gasecus, particulate, or volatile components of the experiment shall not result in exposures 6 excess of 0.5 Ram whole body or 1.5 Ram thyroid te persons occupying an unrestricted area continuously for a-period of.two hours-starting at. the ti:ae of release or exposure in excess of 5 Ram whole body or 30 Rem thyroid to persons occupying a restricted area during the length of time required to evacuate the restricted area. Bases: These specifications are intended to reduce the likelihood of damage to reactor ccapponents and/or radioactivity releases resultir4 frm an experiment failure and to protect operating personnel and the public from excessive radiation doses in the event of an experiment failure. '
- 3. 4' Radiation Monitoring, Control and Shielding Applicability This specification applies to radiation monitoring, control and reactor shielding required during reactor operation.
Objective To protect facility personnel and the public from radiation exposure. Specification
- a. An operable portable and installed radiation survey instrument capable of detecting gamma radiation shall be immediately available to reactor operating personnel whenever the reactor is not shutdown.
- b. The reactor room shall be considered a restricted area whenever
.the reactor is not shutdown. "
- c. The following shielding requirements shall be fulfilled during reactor operation:
- 1. The reactor shir.ld tank shall be filled with water to a height within 10 inches of the highest point on the manhole opening.
- 2. The thermal column shall be filled with water or graphite except during a critical experiment (core loading) or during measurement of reactivity worth of thermal column water er graphite.
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I y i neutron radiation dose rate in the reactor room, at.the closest approach to the reactor, is less than 100 mrem /hr at reactor. power levels 11ess- l than or equal to 5.0 watts and the thermal column filled with water.
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. radiation areas is designe.i to limit radiation deses to facility i,> - personnel and to the public to.a level below 10 CFR 20 limits under N operating conditions, and to a level below criterion 19, Appendix A,
. 10 CFR 50 reer==endations'under accident conditions.
'4.0 SURVEILIANCE REGUIRBGNTS Actions specified in this section are not required to be im G sei if ,
during the specified surveillance period the reactor has not been brought critical or is maintained in a shutdown condition extending s
- beyond the specified surveillance period. However, the surveillance requirements nust be fulfilled prior to subsequent startup of the . x~.r reactor.
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.L 4.1 Reactivity Limits 'i
- Aeolicability
< This specification applies to the surveillance requirements for reactivity limits.
Objective To assure that reactivity limits for Specification 3.1 are act exceeded. Soecification
- a. ~ Safety and cantal rod reactivity worths shall be :neasured annually,
, but at intervals not to exceed 16 months.
- b. Total excess reactivity and.shutdewn margin sF4.1 be detennined am"=1'y, but at intervals not to exceed 15 ':nenths.
- c. The reactivity worth of an experiment shall be estd::ated or
- neasured, as app % i ate, before or during the first starr.:p subsequent to the experiment's insertion.
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The control and safety rods are inspected and their reactivity worths
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-measured annually to assure that no degr'. cation or unexpected' changes have occurred which could adversely affect reactor shutdown margin.or total. excess. reactivity.- The shutdovr margin and total excess reactivity
~are- deterr.ined to assure that the rea'. tor can always be safely shutdown j
with one rod rot functioning and that. the ==v1== possible reactivity i l
- insertion wi.L1 not result in reactor periods shorter thanLthose that- :
. scan be ada@=197 teminated by eitler operator or automatic actionL I
> Based an expet.Lence with AG4 reactors, significant changes-in reactivity J i
or 21x1 worth are not expected W. thin a 16-month period,
. 1 4.2 Control and Safety System ,
Apolicability This specificarica applies to the surveillance requirements of the reactor.centrol and safety systems. Objective I To assure-that the reactor control and and safety systems.are operable as required by Specification 3.2. -
- a Specification
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- a. Safety and control rod scram times and average reactivity insertion rates shall be measured annually, but at intervals not~to exceed-
, 16 months..
i b.15afSty and control rods and drive shall be inspected fer ' daterieration at intervals not to exceed 2 years..
^===1 test of tha following safety charinels shall be performed
- c. A prior to de first reactor startup of the day or prier to each -
opetutien extending more than ene day:
" Nuclear Safety fl, f 2, and #3
%tm ml scram
- d. A channel test of the seismic displacement interlock shall be' perfor:nd se = nt=11y. .
- e. A chmmel el 't of the fo11ow2ng safety channels shall be perfor.ned daily whent . the reactor is in operation:
Ncclear Safety fl, #2, and 43
- f. Prior to each day's operatien or prict to each cperatien extending more dan ene day, safety rod 11 shall be inser:ed and ss...e d vO to verify cperability,
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- g. The period, count rate, and power level measuring channels shall-
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be calibrated and set points verified annually, but at intervals not to axceed 16 months. The shield tank water level-interlock, shield water temperature h. interlock and seismic displacement safety channel shall be
. calibrated by perturbing the sensing element to the appropriate
. set point. These calibrations shall be-performed annually, but
'at intervals not to exceed 16 months.
Bases h ,
. The channel tests and checks required daily or before' each sta.rtup will assure that the safety eh==p1= and scram functions are operable.
Based on operating ex:erience with reactors of'this type, the annual scram measurements, cunnel calibrations, set point verifications, and inspections are of sufficient frequency to assure, with a high degree of
~41d=c a , that the safety system settings will be within acceptable i drift tolerance for operation.
4.3 Reactor Structure
' Applicability ., ,
This specification applies to surveillance requirements for reactor components-other than control and safety rods. Obiective To assure integrity of the reactor structures. Specification a.- The shield tank shall be visually inspected every two years. If apparent excessive corrosion or.other damage is' observed, corrective - measures shall be taken prior to subsequent reactor operation.:
- b. Visual inspection for water leakage from the shield tank shall be per-formed annually. . I,eakage shall be corrected prior to subsequent reactor operation.
Dr_ g , Bases e ' i Based on experience with reactors of this type, the frequency of inspection
" - and leak test requirements of the shield tank will assure capability for-radiation protection during reactor operation.
4.4 Padiation Monitorine and Control A olicability
~his specification applies to the surveillance requirements of :he radiation monitoring and control systems.
,- i I 4
i Objective = To assure.that the radiation monitoring and control systems are operable-and that all radiation areas within the reactor facility are identified and controlled as required by Specification 3.4. Specification
.a. All portable and installed radiation survey instruments assigned to the reactor facility shall-be calibrated under the supervision of .
thelRadiation Safety Officer annually, but at intervals not'to exceed 16 months. I b. Prior to each day's-reactor operation or prior to each reactor operation extending more than one day, the reactor room high radiation L alarm shall be verified to be operable.
.c. A' radiation survey of the reactor room and reactor control room shall be performed under the supervision of the Radiation Safety
' Officer annually, but at intervals not to exceed 16 months', tg determine the location of radiation and high radiation areas cor-
. ' responding to reactor operating power levels.
J Bases 1 The periodic calibration of radiation monitoring equipment and the surveil-lance of the reactor room high radiation area-alarm will assure
' that che ' radiation monitoring and control systems' are , operable during
. reactor; operation.
lTh e : periodic radiation surveys will verify the location of radiation and-high radiation areas and will assist reactor facility, personnel in properly labeling and controlling each location in accordance with' 10 CFR 20.
- 5.0; DESIGN FEATURES
'5.1- Reactor
- a. The reactor core, including control and safety rods, contains approxi-mately 660 grams of U-235 in the' form of C07. enriched UO2 dispersed in approximately 11 kilograms of polyethylene. The lower section of the core is supported by an aluminum rod hanging from a fuse link.
The fuse melts. at a fuse temperature of about 120 0C causing the lower core section to fall away from the upper section reducing reactivity by at least 57. 4 k/k. Suf ficient. clearance between core and reflector is provided to insure free fall of the bottom half of the core during the mosc severe transient. f 9' b. The core is surrcunded by a 20 cm thick high density (1.75 gm/um3) graphite reflector followed by a 10 cm thick lead gar:.a shield. The core and part of the graphite reflector are sealed in a fluid-tight aluminum core tank designed to contain any fission gases that might l leak from the core.
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- c. -The core, reflector, and:leid shielding.are enclosed in and supported ,
(f by-a-fluid-tight' steel 1 reactor l tank. 'An upper or " thermal column tank" may serve as a shield tank'when filled with water or a thermal _ i column.when filled with graphite.- ;
- d. The 64 foot diameter,' fluid-tight: shield tank is filled with water.
constituting a 55 cm; thick fast' neutron shield. The fast neutron
~
shield is- formed by filling the' tank with approximately 1000 gallons of water. The complete.reaci.or shield shall' limit doses to operating personnel in restrictedTand unrestricted areas to levels less than permitted by 10 CFR 20 under operating conditions.
. e. Two safety rods and one control rod 4(identical in size) ,contain up to 20 grams of U-235 each in the same form as~the core material..
These rods are lif ted into_ the core by~ electromagnets, driven by l reversible DC motors through lead screw assemblies. Deenergi:ing 1 the magnets causes a spring-driven, gravity-assisted scram. The t fourth rod or fine control rod (approximately one-half the diameter '> of the other-rods), is driven directly by a lead screw. This rod may contain fueled or. unfueled' polyethylene. 5.2 Fuel Storate
'I Fuel,- including fueled experiments and fuel devices not in the < reactor, shall be' stored in locked rooms in the nuclear enginee. ring department /W l'ab oratorie s . - The storage array shall-be such that K ff is no greater i d than 0.8 for all conditions of moderation and reflection.
5.3 Reactor-Room
- a. The reactor room houses the reactor assembly and accessories required
. for_ its operation' and' maintenance. i
- b. 'The reactor room is a-separate room in the Merrill Engineering Building '
constructed with' adequate shielding and other radiation protective features to limit doses in restricted and unrestricted areas to a levels no greater ~than permitted by 10 CFR 20, under normal operating conditions, and to a level below Cr1terion.19, Appendix'A, 10 CFR 50 recommendations under accident conditions, c.
' Access doors to and~ f rom the reactor rooms will contain locks.
6' . 0 ADMINISTRATIVE CONTROLS , ! 6.1 Organi:ation 2e administrative organization for control of the reactor facility and I
.the operation shall be as set forth in Figure 1 attached hereto. The authorities and responsibilities set forth below are designed to comply
.eith the intent and requirements for administrative controls of the
- g. reactor facility as set forth by the Nuclear Pegulatory Ccmmission.
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Institutional. '
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Council AV _; jji i
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- f. x t liniversity of Utah s A
y , President l. L.i.', c. i
*' Vice President for
..' " ' . Research- a
' u, ; .. L.-( 2 I.', ,f ? % ^ Director Nuclear Reactor Safer- Radiolo'gical e - - - - Consnittee ----<
- Health Comittee Engineering Laboratory c l ,
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i - Reactor.- __ Reactor _ __
. Radiation Safety 1 E
Supervisor. - q Administrater Officer ,
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.Winistratin ;:;r.i:ation ior
. Nuclear Reactor : erations
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6.1.1 ' President- he President is the chief Ari-inistrative Officer responsible
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Lior the University and is responsible to the Institutional Counc11 fn -
. whose name the application for licensing is made.
- 6;1.2 Vice President- for Research-The Vice President is .the Administrative 1 officer responsible to tne President for all research facilities l at the University. In this capacity he shall represent the Preside t-
-in all health and safety matters pertaining to the' reactor facility.
6.1.3: Director Nuclear Engineering' Laboratory-The Director of the Nuclear Engineering Laooratory is the hinunistrative officer responsible for the Reactor Facility and its operation, maintenance, and safety. In this capacity he shall' have final authority ahd ultimte responsibility for the reactor facility and, within the linitations set forth by the facility. . _! license, mke final policy decisions on all phases of reactor operation; ; appoint personnel to all positions reporting to him as described in i Section 6.1 of the Technical Specifications and as shown on Figure 1 of these specifications; be advised in all r.atters concerning health and sJety by the Ra,diological Health Co:r.ittee; and be advised in all matters concerning reactor safety b:. the Reactor Safhty Committee.
. 6.1.:: Reactor Administrator-The Reactor Mninistrator (RO is responsible to the Reactor Safety Comnattee and the Vice President for Re>earch for insuring regulatory compliance of de reactor facilitv. In this j
h v capacity, he shall, within the policies set forth by the Director and the facility license, prepare all regulations for the facility, review i,
.and approve all procedures, seek approm1 of all procedures and proposas for changes and experiments from the Reactor Safety and Radiological Health . Committees, and be responsib'.e i r the health and safety of all personnel in the reactor facility. .;
6.1.5 Reactor Suoervisor-The Reactor Supervisor (ES) shall be a licensed ] Senior Reactor Operator and shall be responsible for the preparation, i promulgation, and enforcement of admim strative controls including j all rules, regulations, instructions ani operating procedures to l insure that the-facility is operated in a safe, competent, and I author 1ied manner at all times. He shall direct the activities of : L Operators and Technicians in the daily et eration of the reactor; i schedule reactor operations ud maintenance; be responsible for the : preparation, authentication, tnd stcrage of all prescribed logs and operating records of the facil.'ty; auth:riie all experiments, procedures, and changes thereto which have .first received _ approval of the Reactor : Safety Comittee, the Radiological Heal-h Comittee, and the Reactor l l Administrator, and be responsible fcr .he preparation of all instructions; manuals and experimental procedures involving use of the reactor. i
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.l V f o.l.6 Reactor Operators-Peactor Operators shall be respons'ible for the-manipulation of the reactor controls, monitoring of instrumentation, _
-operation of reactor related equipment, and maintenance of complete and current records 'during operation of the facility. A Reactor Operator shall be _ in direct charge of the reactor console at all times during reactor operation and when the reactor is not secured and confom to the rules, instructions, and procedures established by-the Panctor :
Administrator and Reactor Supervisor for operation of the reactor and - the performance-of experiments. 6.1.7 Reactor Safety Comittee- The Reactor Safety Committee (RSC) shall be responsible for independent reviews and audits of facility operations ! to insure that the reactor is-operated in a safe and competent manner
.within the requirements of the NRC and advise the Vice President for Research in all matters related to reactor safety and personnel safety. ;
- The Reactor Safety Comittee shall hold periodic meetings and have the authority to conduct reviews and audits of reactor operations.
.6.1.S Radiological Health Comittee This Cort'.ittee (RCSC) shall advise the Vice President -for Researen in all matters conceming the health and safety of personnel who might be exposed to radiation produced by .
University owned and/or operated sources or equipment. This comittee . shall review, approve, and promulgate a Radiation Safetv Program for n the University. This comittee shall be infomed of all reportable U occurrences related to radiation health and safety and reactor safety which are reportable to any authorities outside the University, and ' advise the President of such occurrences and make recomendations to the Vice President with regard to any such matters, i L i i i- {- J 1: 1
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,x 16.1.3 Radiation Safety Officer-The Radiation Safety Officer (RS0) shall be.
tne cniet ac::a:ustrative officer of -he Committee and represent the committee in matters _concerning the radiation safety aspects' of reactor - -; operation. He'shall prepare die University's Radiation Safety ranual. ' and have the authority to enforce the regulations, rules, and procedures , '! set forth by die Radiological !!ealth Cennittee, suspend the operation ' and use of radiation producing devices when their use is in violaticA x of these rules, and secure such scurces of radiation until correctivs ; action -is taken._ He shall also have the authority to disapprove the - L acquisition of radiation producing sour:es until satisfactory evidence
, is presented to ensure the safe st: rage and use of these facilities.
The Radiation Safety Officer is. also responsible for _ the reporting of ' all reportable occurrences to the appspriate regulatory ' agency and for ensuring that the appropriate follow up action is taken.
- 6.1.10 Opera ting Staf f-
- a. The minimum operating staff'during any time in vnich the reactor is not shutdown shall consist of:
- 1. One licensed Reacto'r Operator in' the ' reactor control room.' '
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- 2. One-other person in the reactor room or reactor control room 7)
v/ certified by the Reactor Supervisor as qualified to activate s manual scram and initiate emergency procedures.
' 3. One licensed Senior . Reactor Operator readily available on call.
This requirement can be satisfied by having a licensed Senior Reactor Operator perform the duties stated in paragraph 1 or.2 above_or by designating a licensed Senior Reactor Operator who
- can be readily contacted by telephone and who can arrive at-the reactor facility within 30 minutes.
b.. A;1icensed Senior Reactor Operator shall supervise all reactor maintenance or modification which could af fect the reac:ivity of
- he reactor, i
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,3 ig 6.2 -Staff' Qualifications ?
the Reactor Supervisor, j
. licensed The Director of the Reactor Nuclearand Operators, Engineering techniciansLaboratory,ing perform reactor maintenance ,
shall meet the minM= qualifications set forth in ANS 15.4. Reactor
;afety Committee members shall han a ninimun of five (5) years emerience- l in their profession or a baccalaureate degree and two (2) years of professional' -
everience.. Reactor Safety committee members will generally be University
- faculty members with considerable emerience in their area of egertise. - The Radiation Safety Officer shall' have a baccalaureate degree in biological
- or physical science and have at least two (2) years emerience in health physics. -
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- 6.3 , Training i
Ihe. Director of the Nuclear Engineerbg Laboratory shall be responsible for -
- directing training as set forth in ASS '.5.4, " Standards- for Selection and !
Training of Personnel for Research P:4ctors". All licensed reactor operators 1
-shall participate in requalifiention training as set forth in 10 CFR So.
-1 6.4 Reactor Safety Comit t e e y
6.4.1 Meetinas and ouorum - - 1 1 Reactor Safety Comittee shall. meet as often as deemed necessary by the .i A ' Reactor Safety Committee Chairman who i.s the Reactor Administrator but : shall meet at least once each calendar > ear. A quorum for the conduct of 1 x V ~ official business shall.be the chairman, .or his designated alternate, and two (2) other regular members. At no time shall the operating organi:atien ] comprise a voting majority of the me:sers at any-Reactor Safety comittee 1q meeting. 6.4.~2 Reviews-The Reactor Safety Comittee shall review: :
.i
- a. Safety evaluations for changes to orocedures, equipment or systems, and tests or emeriments,_ conducted wi'thout. Nuclear Regulatory Comission ,
approval under the provision of 10 CFR 50.59, to verify that such actions. do not constitute an unreviewed safety question.
- b. Proposed changes to procedures, equipment or systems that change the original intent or use, and are non-conservative, or those that involve an unreviewed safety question as defined in 10 CFR 50.59. ;
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i N'l c.- -Proposed tests or experbaents which are significantly different j from previously approvedi tests or experiments, or those that involve ;
>> an tnreviewed safety question as defined in 10 CFR 50.3!. .l o
- d. Proposed changes in Technical Specifications or licenses.
Violations of applicable statutes, codes, regulations, orders,
- e. - Technical Specifications, . license requirements, or of internal a procedures or instructions having nuclear safety significance.
- f. Sigtificant operating abnomalities or deviations froti nomal and' g' '
epected perfomance of facility equipment that affect nuclear safety.
-g. Reportable occuiTences.
- h. Audit reports..
6.4.3. Audits Audits of facility activities shall be perfomed . i under the cognizance of the Reactor Safety Comittee but 'in no case by 1 the personnel responsible for the item audited. These audits shall examine the operating ncords and encompass but shall not be limited to 7 3 - the following: l
- a. The confomance of the facility operatica to the Teic.ical Specific- 1 ationsland applicable license conditions, at least re.ually, j
- b. The Facility Emergency plan and implementing procedures, at least :
ever/ two years.
- c. The Facility Security Plan and implementing procedures, at least every two years.
6.4;4 Authority The Reactor Safety Comittee shall report to the' Vice president and shall advise the Director of the Nuclear Engineering Laborator. en those areas of respcasibility outlined in section 6.1.7 of these Tec'.ni:a1 Specifications.
-6.4.5 Minutes of the Reactor Safety Comittee The Reactor .Aiainistrator shall direct the preparatien, :rintenance, r.d .
distributica of minutes of its activities. These minutes shall include a su=a:y of all meetings, actions taken, audits, and reviews.
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6.5 Approvals The procedure'for obtaining approval for any change, modification, or procedure which ~ requires approval of the Reactor Safety Comittee shall be as follows 1
-a. The Reactor Supervisor shall prepare the propo' sal'for review and-approval by the Director of the Nuclear Engineering Laboratory.
- b. The Director of the Nuclear Engineering Laboratory shall submit:
the proposal ~to the Chairman of the Reactor Safety Committee. ?
- c. The' Chairman of the Reactor Safety Committee shall submit.the proposal to the Reactor Safety Committee members for review and l '
comment. i
- d. The Reactor Safety Committee can approve the proposal by majority #
vote.
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'6.6 procedures There shall be written procedures that cover the following activities: i
- a. Startup, cperation, and shutdown of the reactor.
- b. - Fuel movement and changes to the core and experiments that could 1 affect reactivity.
. c. Conduct of' irradiations and experiments-that could affect the J
operation or safety of the reactor. t
'd . Preventive or corrective maintenance which could affect the safety- .
of the reactor.
- e. Surveillance, testing, and cali'craticn of instruments, ccmponents, and systens as specified in section 4.0 of these Technical
' Specifications.
- f. Implementation 'of the Security. Plan and Sergency Plan.
The:above listed procedures shall be approved by the Director of the Nuclear Engineering Labcratory and the Reactor Safety Committee. Te=porary procedures which do not change the intent of previously approved procedures and which do not involve any unreviewed safety question may be employed on approval by the Reactor Supervisor or Director of the Nuclear Engineer 1nc Laboratory. i 3 6.7 Experiments prior to initiating any new reactor experiment an experimental
~
a. procedure shall be: prepared by the Reactor Supervisor and reviewed. and approved by the Director of the Nuclear Engineering Laboratory , and the Reactor = Safety Committee,
- b. ; Approved experiments shall only be performed under the cognizance- ,
of the Director of thel Nuclear Engineering Laboratory and the ! 4 ~ Reactor Supervisor. 6.8 Safety Limit Violation
,ne folicwing ac icns shall be taken i. the event a Safety '3 d: is Lv:.olated: . a. The rsae:or will be shut down imediately and reactor cperation will i not be resumed without zuthori:aticn by the Nuclear Regulaay. t Camission (Y4C) . ' ;
b .- The Safety Limit viciation shall be reported'to the appropriate NRC Regional Office of Inspection and E.forcement, the Director of de - NRE, and the Reactor Safety committee not later than the next work day.
, c. A Safety Linit. Violation Recr: shall be prepared for review by the Reactor Safe y Committee. This report shall describe the applicable circumstances preceding the violatica, the effects of the violation upon facd":y campenents, systems or structures, and ccrree:ive action to prevent recurrence.
- d. D e Safety Limit Violation Repc t shall be submitted to the NRC, and Reactor Safety Committee within 14 days.of the violation.
0.9. Reporting-Requirements
- In addition- to,the a:rplicable reporting requirements of Title 10, Code of Federal Regu..ations, the follcwing reports shall be submitted i
to the Director of the appropriate NRC Regional Office.
- 6. 9.1 : Annual Operating Report a
Routine arnzual cperating reports shall be submitted no later than
' thirty;(30)' days following the end of the operating year. Each annual report shall include a sumary of the following activities occurring during the operating year:: .
- a. Facility nedifications.
- b. Results of major survei1Me* tests and inspections,
- c. Cctrective maintenance perfm ned.
p i i i
.j j
- d. Energy pr M by the reactor in watt hours. j u7 0 -
e.: Unscheduled shm % . f. R8 actor Safety Committee action pertinent to the facility.-
- g. Any activities which require reporting per 10 CFR 50.59.
- h. Any i ble occurTences as defined in section 6.9.2 of these
-Tach *+=1_ Specifications.
. 6. 9.2 Reportable Occurrences Reportable occurrences, including causes, probable consequences, corrective I actions and measures to prevent recurrence, shall be reported to the NRC. '
l
- a. Promet Notification With Written Fo11cwuo. The types of events listed !
shall oe reported as expeditiously as possible by telephone and . telegraph to the Director of the appropriate NRC Regional Office, . _J or his designated representative no later than the first work day following the event, with a written followup report witMn two weeks. Information provided shall contain narrative material to provide complete explanation of the circumstances surrounding the event.- ll 1 (1) Failure of the reactor protection system subject to limiting ' AV safety system settings to initiate the required protective function by:the' time-a monitored parameter reached the serpoint - specified as the limiting safety system setting in the Technical ~i specifications. t (2) Operation of the reactor when any parameter or operation subject to a limiting condition is less conservative than the limiting candition for operation established in the 1echnical specifications. (3) Abnormal degradation discovered in a fission product barrier. s (4) Reactivity balanca ==11es involving: ' (a) disagreement between expected and actual critical' positions of .pp4wdmately 0.3% Ak/k; (b) =xceeding excess reactivity limit; ,
. i (c) shutdown margin less conservative than specified in T:chnical specificaricas; ,
u
5 (5): - Failure or malfunction of one = (or more) componet (s) Wtich prevent, or could prevent, by itself, the fulfillasnt of the
.m- >
functional requirmats of syste(s) used to cope with accidents (f analyzed in the Safety Analysis Report.. (6) Personnel error or y.xm&gul iudaquacy Wtich prevents, or could~ . prevent, by itself, the fulf411=mt of the functional regi sts. ' of syst e s required to cope with accidents analyzed in the: Safety Analysis Report. (7) Errors disew I.4 in the transient or accident analyses or in the methods usei for such analyses as described in the Safety Analysis , Report or in the bases for the Technical Specifications that have , pennitted reactor operation in a manner less conservative than
. assumed in the analyses. ,
(8) Perim -we of stmetures,' systems, or compenanta that requires < r d =1 action or w..wi.ive measures to prevent operation in a , manner less conservative than assumed'in tw accident analyses in the Safety Analysis Report er Technical specification _ bases; or discovery during plant life of canditaans not specifically considered i in the Safety Analysis Report or Tech _ial Specificaticas that require r==44=1 action or corrective measures to prevent the existence . or developnent of an unsafe candition, e '6.10 Record Retention
- 6 Records to be retained for :he life of the facility:
O .LO.1
- a. Annual reports,
- b. Records of contro11od or uncontrolled release of radioactive effluents to the environment.
- c. Fuel inventories and fuel transfers,
- d. Operating logs. 4
-e. Maintenance logs.
f.. Updated drawings of the reactor facility,
- g. Personnel dosimetry records on file with the Radiation Safety
.c Officer,
- h. Minutes of the Ranctor Safety committee meetings.
'6.10.2 Records to be retained for a period of at least three years: '
- a. Surveillance activities required by Technical Specifications.
- b. Facility radiation and contn*ntien surveys.
' gb .;0.3 Perscnnel requalificatien and training records will be kept at least ene 6
year after terminatica of employment. I _23_ _ __ __- - - _ _ _ _ _ _ _ _ _ - _ - _ _ _ - _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _}}