ML20092C812
| ML20092C812 | |
| Person / Time | |
|---|---|
| Site: | 05000077 |
| Issue date: | 12/31/1991 |
| From: | Keene W CATHOLIC UNIV. OF AMERICA, WASHINGTON, DC |
| To: | |
| Shared Package | |
| ML20092C810 | List: |
| References | |
| NUDOCS 9202120106 | |
| Download: ML20092C812 (29) | |
Text
{{#Wiki_filter:_ _ _ _ _ _ _ _ _ .___ _ . . _ _ _ - _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ - _ - _ - _ _ _ _ _ _ _ _ _ . __ ______-_-_ _ _-__ _ _ .. s <* DECOMMISSIONING PLAN TiiE CATil0LIC UNIVERSITY OF AMERICA AGN-201 REACTOR Serial No. 101 ) License No. H-31 Docket. No . 50-77 DECEM11ER 1991 Prepared by: Warren E. li e e n e , Ph.D. The catholic University of Arnerica Washington DC 20064 9202120105 920206 PDR ADOCK 05000077 P PDR
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Table of cont ents List of Figures.................................s ....... 11 List of Appendices...................................... iii 1.0 Orientation............................................... 1 1.1 Introductior......... ................................ 1 1.2 Synopsis of the Decommissioning Plan................. 2 1.3 Facility History............ ........................ 3 1.4 Radiological Status of the Facility.................. 4 1.5 Decommissioning Alternatives.......... .............. 5 1.6 Organization and Responsibilities................ ... 5 1.7 S ta f f Qu a l i f i c a t i o n s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 1.8 Regulations, Regulat7ry Guides, and Standards........ 7 1.9 Cost and Funding..................................... 7 2.0 Tasks and 9chedules....................................... 7 3.0 Personnel Protectien.... ................................. 8 3.1 Hazard An11ysis....................................... 8 3.? Radiation Protection.............. . ................. 9 3.3 Industrial Safety and Hyg1ene......................... 9 4.0 Security and Safeguards.................................. 10 4.1 Fr.el................................................. 10 4.2 Radioactive Waste................ ................... 11 5.0 Risk An lysia............................................ 11 6.0 Radioactive Material Management.................... .. 11 6.1 'r u e l D i s po s a l . . . . . . . . . . . . . . . . . . . . . . . . . . -. . . . . . . . . 11 6.2 Radioactive Waste Processing..................... . 11 6.3 Radior-tive Waste St; rage............................ 12 7.1 Technical Specifications................................. 12 8.0 Environmental Impact..................................... 13 y 9.0 Termination Radiation Survey ............................ 13 I i
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p.c ' List of Figurea-Figure 1. Map _of The Catholic' University of Ameriec campus-showing location of the Pangborn - ~ - Engineering _ Building which contains the. AGN-201 nuclear - reactor f acility. _. . . . . . . . . . . . ... . . .15 , Figure-2. The catholic University of America, Pangborn Hal1_ north wing,-basement floor plan ~, showing- ' location. of the AGN-201 nuclear reactor. . . . . . . . . . .16
-F'aure 3.- Administrative' organization for decommissioning- ~t Tt.e Catholic University of America AGN-2^3 e n u c l e a r r e a c t o r . . . . . . . ~. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17 .
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l List of Appendices !
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~ Appendix'A-
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Description of AGN-201-Reactor I I
. Appendix:B CAGN Opernt.ing-History
" Appendix C- Estimated Fuel Fission Product Inventory Appendix;D Qualifications and Training of Decommissioning Personnel
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" Appendix E- CUA RSC Membership
-Appendix-F- Dference-Documents >
-Appendix G: The Catholic University of America Radiation
- Safety _ Manual l Appendix =H. ' The Catholi'c - University of America: Chemical
-Materials Safety. Manual- ,
. Appendix-1-I-- CAGN Technical' Specifications- d
-_ Appendix"J , Abbreviations-and Acronyms E
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DECOMMISSIONING PLAN l for the CATHOLIC UNIVERSITY OF AMERICA AGN-201 NUCLEAR REACTOR 1.0 ORIENTATION 1.1 Introductiqn In accordance with 10 CFR 50.82, this dismantling and decom-missioning plpn is submitted to the U.S. Nuclear Regulatory Com-mission - (NRC)- in support of the request of The Catholic Univer-sity of America (CUA) for authority to surrender License R-31 voluntarily and to decommission the CUA AGN-201 Nuclear Reactor , (CAGN) and -dispose of its components. The plan describes the.means i by which all radioactive or contaminated components will be removed ) and the facility will be decontaminated. The plan provides rea-sonable assurance that dismantling the facility and disposal of its - , components will be performed in accordance with the Code of Federal Regulations (CFR) and will not be inimical to the co.nmon defense ; and security ner to the health and safety of the public. The- format of this plan has been adapted f rom that which pre-vi.ously had been accepted with respect to the University of Utah AGN-20lR reactor. The plan includes information on the history of the facility, its current radiological = status, dismantling alter-
- natives, the decommissioning organization and its responsibilities, the regulations, regulatory guides and standards which will guide
-.the decommissioning activities, and the qualifications of the de-commissionang' staff. The plan describes the personnel protection program, tasks and schedules, physical security and safeguards, radioactive materials management, technical specifications, en-vironmental impact and the termination radiation survey plan which together comprise the decommissioning plan.
In anticipation of decommissioning, the fuel has been removed from the reactor and is stored in-the CUA fuel storage facility, pending transfer to its owner, the Department of Energy (DOE). DOE has stated tentatively that the fuel will be shipped to the DOE Op-erations Office (ORO), Y-12 Facility, Oak Ridge, TN. The fuel will be shipped under the existing license and in accordance with DOE,
.NRC, and Department of Transportation (DOT) requirements as soon as
. final DOE instructions for transfer are received. CUA has received a scrap declaration form and related forms f rom ORO. It is expected that sh ipping containers and consignment instruct. ions for the fuel will be provided by ORO, in a timely manner, following completion I
A list of all abbreviations ard acronyms used is included
-as Appendix J.
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2 & and return of the forms by CUA. As per 10 CFR 50.59 assessment by CUA, shipment of the fuel represents no unreviewed safety questions and the fuel will he shipped under the current license as soon as _ practicable. The decommissioning effort will be managed by the CUA Radia-tion' Safety Office (CRSO). The Director of Radiation Safety (DRS) has been designated Reactor Administrator (RA) for the purpose of decommissioning.-The staff consists of the Director,-who is the
.CUA Radiation Safety Officer (RSO) and one full-time health physics ,
, technician (in training to become a health physicist); two part- ) time personnel provide electronics maintenance, and computer entry ! and clerical assistance. It is anticipated that all CUA decommis-sioning activities can and will be performed by these University I personnel . This decommissioning plan and all prior decommissioning activities have been reviesed and approved by the CUA Radiation Safety Committee (RSC). 1.2 Synopsis of the Decomnissioning Plan The selected decommissioning method is D E c 0 N through which the reactor structure will be-dismantled--to the extent necessary to insure that the radioactivity of _its components is consistent
-with their release for unrestricted use or dispusition, or to identify components which must be disposed of as radwaste. No other decommissioning alternative is considered to be reasonable. The cost of the decommissioning project is expected to total about
$11,000, including the cost of the termination radiation survey, and not including disposition of the decontaminated reactor struc-ture. _ Post-decommissioning disposition of the structure is the responsibility of the Mechanical Engineering Department. It is l anticipated that it will- be cut up for scrap, in pieces whose size will permit either burial in the present reactor pit or removal from the building via existing doorways. Decommissioning funding has been committed by the-cUA Administration via ~ the normal budget of the.CRSO. This decommissioning plan applies to the CAGN, its structure and components,_and to Room B-16R, Pangborn Hall, in-cluding radioactive waste that may be generated during the decom-missioning process. The criteria for unrestricted release shall be the limits _ recommended.in NRC Regulatory Guide (RG) 1.86. In ad-dition, the. exposure rate due to surface contamination shall be less than 5 uR/h above natural background at a distance of one meter. Any components which cannot be decontaminated to comply with these criteria will-he transferred to the CRSO for disposal in
-accordance vith applicable federal, state, and local regulations.
Decommissioning activities wi11 be performed under the existing CUA radiation safety program to ensure that occupational exposures are ALARA. These activities also-will be performed in conformance with established industrial safety practices. All activities will be - completed within one year of receiving approval f rom NRC to proceed L with decommissioning. No'special equipment, tools, or contractor I assistance will be required and quality assurance reviews and aud-l its will be conducted as needed by the RSC. All solid and 1 quid j radioactive wastes generated during the project wil1 be transferred to the CRSO for disposal . The collective dose equivalent to decom-missioning staff is anticipated to be less than 0.1 person-rem. A 2
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I l final report will be subu.tted to NRC, requesting termination of the CACN possession-only license certif ying complet. ion of a compre-hensive termination radiation urvey which will verify t h a t. the facility, including residaal CAGN components, satistles the cri-teria for release to unrestrict.ed use. 1.3 falli t y Hi s t o_r_y The original application to acquire and possess an AGN-201 nu-clear reactor was filed by CUA on 10 July 1957 and amended on 23 August and 13 November 1957. Pursuant, to License No. R-31, issued 15 November 1957, AGN-201, Serial No. 103, was acquired from the Aerojet-General Nucleonics Corporation (AGN). The original license was _ ar a period of twenty years and specified a maximum thermal - power of 100 milliwatts. Initial criticality was achieved on 20 Novenber 1957. The license has been amended nine times. The more significant amendments were Number 3, dated 26 April 1961, which allowed relocation of the reactor to the newly constructed Pangborn Engineering Building from its original location in the Power Plant Bu ' ding, Number 7, of 14 March 1979, which extended the operating li mse to the year 1997, and Number 9, of 5 March 1986, which , changed its status from operational to possession-only. A descrip-tion of the CAGN is provided in Appendix A. The CAGN is located in the Pangborn Engineering Building in the northeast part of the campus (Fig. 1). The Reactor Room (B16-R), is located on the basement floor of Pangborn llall (Fig. 2) and comprises approximately 1000 square feet of the northeast corner of the basement floor of the north wing of the building. The cinder block wall which had been proposed to di. vide B16R, creating a new room B16A (as shown in the figure), was never built. Therefore the reactor f acility consists of the spaces shown in the figure as B16A and B16R. Room B18-A (Fig. 2) houses the CRSO and a portion of the . Radiation Safety Laboratory. These are the only two restricted areas in Pangborn Hall. Both areas are under the control of t.he DRS. The reactor was operated first by the Department of Nuclear Science and Engineering, and subsequently by the Department of Mechanical Engineering, for training nuclear engineering graduate students. The reactor usually was operated in conjunction with a Nuclear Reactor Laboratory course and used primarily for performing basic reactor physics experiments. The reactor was operated at pow-er levels up to one hundred milliwatts. The total thermal power produced during operations under Li-cense No. R-31 is estimated to have been 16.2 watt-hours. (It is understood that the reactor had been operat ed at various times and places prior to its receipt by CUA. No record of these operations is held.) Appendix B provides an annual summary of operating time and power at CUA. The reactor was last shut down in December of 1982. Surve11-lance required by the Technical Specifications has been continued. The reactor was defueled un 17 March 1990, in accordance with a detailed defueling plan which had been approved by the RSC and 3
m Si i submitted to the-NRC. Appendix C contains an estimate of the fis- l sion product inventory of the fuel resulting from operating the
- CAGN'at CUA.-
1.4 Radiologir_al Status _-of the Facility The CAGN had a polyethylene-moderated, graphite-reflected, water-shielded core. The reactor core consisted of a set of nine circular polyethylene disks, approximately 25 centimeters -in dia- - meter, containing'a uniform dispersion of uranium oxide enriched to l 1ess than-204 U-235. Both safety _ rods and-the_ coarse control. rod - contained.similar fuel material, in the form of_ columns of right , circular cylindrical segments, collectively sealed _in aluminum capsules, so_that reactivity increased as rods sere insertedfinto the ' reactor core; the fine control rod consisted of aluminum-encapsulated polyethylene (unfueled). Monthly radiation surveys ! prior an_d subsequent to defueling have shown no evidence of radio- -! active contamination 'due to activation of reactor components or the s leakage _of fission products.
'The 10Lmci radium-beryllium start-up neutro. source was re-moved and placed in a neutron' source storage tank prior to removal of the fuel-from the reactor, to keep radiation exposures ALARA ',
during-defueling. Wipe tests of the sealed source gave no indita-
' tion 7of leakage. The ocurce was shipped to_ RAMP, Inc.- in-Denver,
!CO, in the summer of 1990 for disposal at the low level waste site at-Beatty, NV. *
-Following _ removal of the start-up source, defueling proceeded Las-- per ' w ritten procedure. Wipes of reactor components adjacent to the core can and of the exterior of' the core can showed no evidence of contamination or fission-product leakage.-The core can was re-moved from the-reactor and transferred to the fume hood in the Ra- -
dlaLion' Safety Laboratory. A_ gaseous- sample was taken f rom the her-metically-sealed-core can and analyzed for th'e presence of radio.- active contamination..~ No fission products.were ' observed in the gam-ma spectrum of the sample. The control rod guide tubes were remov
-f rom the core can and replaced with pre-fabricated caver plates ta i permit insertion of the core'can.into a storage safe. At a.later
~date, the fue1Ldisks were remo_ved from the-core can, inspected, surveyed, inventoried, sealed in plastic _ bags, and re-stowed on two
- separate shelves of the safe. Calculations performed by the RA con-
, firmed 'that the value of km for the storage array in the fuel safe was much>1ess than the value of 0.'8 required by the Technical spe--
-cifications. Fuel from the safety-and control rods was similarly ,
inspected, surveyed, inventoried, sealed, and stored in a separate
-safe in- the -Reactor Room. Radiation levels around . the reactor structure decreased to nominal background levels promptly _ upon remova1 of the core can..
Upon removal of-the core-can from the reactor, the fuel had a maximum container surface exposure rate of 4.5 mR/h and a minimum ,
-of 0.1- - mR/ h ' The - low exposure rates are indicative of the low burn-up_of the' fuel, the low neutron flux in the reactor'at full 1icensed power, and the fat that the reactor had not been operated since.1982 (approximately seven years). Because both the neutron 4
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,y .V is flux and usage were low, no measurable contamination-and/or acti- j
-ation has been found _ during extensive surveys performed by_ Lhe '
CRSO. A minor amount. of- fixed and removable contamination is ex-ected to be found onl surf aces of reactor core components _ which were-in direct contactL with t.he fuel. All such components- have - been
-sealed in-plastic, and remain stored in the reactor room, pending furthe - survey. These components will be disposed of in accordance with RG 1.86-after NRC approval to decommission has been received.
1.5 p_econnissioning Alternatives The Catholic University of America . is seeking authori ty-- to - surrender License R-31 and revert the facility to unrestricted use. The University has selected D E C O N as the method for decommis-sioning the CAGN. It_is expected that all reactor equipment and l structures contai :ing radioactive contaminants will be decontami-nated to levels which permit their release for unrestricted use. It I
- -- -is the intention of the licensee to remove all radioactive fluids, j radioactive-waste, and other materia 1s connected with the~mecha- I nism, operation, and decontamination of t.he CAGN and reassign t.he l
-reactor room for. unrestricted use. The reactor pit and the reactor j l
room floors are vinyl-tile-surfaced concrete, slab-on-grade. There are no sewer drains in the facility. No other spaces are pertinent to this decommiusioning plan. Any materials or components which do I' not satisfy the conditions for unrestricted release will be trans- l ferred to the CRSO for disposal as radioactive waste. Alt. hough not L part of the decommissioning plan, it is intended to cut the decon-taminated structure into pieces small enough for either removal through existing doorways or burial in the reactor pit, which would be- back-filled and topped by a concrete slab, continuous with t.he present reactor room floor'. No other decommissioning alternative is reasonable. The reac- i l tar has-not been=usedLin over eight years; it is of no present (or i:
- perceived f uture)fvalue . to CUA. It la-desired to use the _ space L occupied by the-CAGN for-other purposes.-There-is no known market l -. for- the intact reactor structura and/or controi console. To remove
- t.he structure, intact, would require removal and replacement of a -
portion of_the exterior wall of the reactor room, a costly effort. L l The= Smithsonian. Institut. ion had expressed an -interest .in the struc-ture and control console; they__ subsequently dropped the matter. 1.6 Organization and Responsibilities The organization responsible for the decommissioning is diagrammed . L in Figure 3. Individuals at various management levels have respon-sibilities related La safeguarding the public and facility per-i: sonnel-from undue-radiation exposure'and for-adhering to all re-L quirements of.-the facility license. The - assignment of speaific responsibilities is described below, i F President - The President is the chief Administrative Of ficer l; responsible for the University and its activities. l Executive Vice President (EVP) - The EVP i s responsible to the j President for the day-to-day operation of the university. and repre-i
_ _ ______ _ ___ _._ _.-..-_ _ ._ _ _ _.. _ .. _.___ _ m-___ o - ?ol' __ sents the -President Lin- all_ health andl safety matters, including those pertaining Lo_the reactor facility. .The EVP promulgates the Univertit y Radiation - Safety-- Program, with the- advice of the RSC. Reactor Administrator-(RA) - The RA (who-is also the DRS)-is the -Universit y Administrative ' Of ficer responsible-Lo the-EVP for the reactor facil1Ly and for related Technical Specification com-plianc o, safety and decommissioning, and for insuring regulatory compliance with respect to the reactor facility. In this capacity, and in conformance with the faellity license and the policies-sel
- fort.h by the RSC, the RA prepares all regulations for the facility, reviews all_ procedures, seeks _ approval of_all procedures and pro -
posals for changes and experiments f rom t.he RSC, and is responsible for- the health and safety of all personnel in the f acility. The RA will prepare the final decommissioning report Lo the NRC.
- Rad'iation Safety Committee RSC) - The.'RSC advises the EVP in all' matters concerning the radiological health and safety of per-sonnel who might. be exposed to radiation produced- by universily-owned and/or -operated sources or equipment. The committee reviews
- and approves-the University's RadiaLion. Safety Program, fer pro-E mulgation by the EVP. The commit. Lee is informed of any occurrences - '
related to radiation health and safety _ and/or _ reactor safet.y .which are reportable to any authorities outside the-University, advises the EVP of-such occurrences and makes recommendations Lo-Lhe'EVP with regard to~ any such matters. The cocuuittee holds periodic meet-
'ings and has the: responsibility and authority to conduct audits and-
- reviews of the records of the RA and-the DRS. !
- The decommissioning plan has been reviewed and approved by th'e RSC.-The RSC has audited the recorda of the ' Reactor Administ.rator-and RSO which relate to pre-decommissioning activiLies conducted to date, -and will- continue to audit related activities until the-de-commissioning is completed.
The. current membership'of the RSC is shown in Appendix:0. Director of Radiation Sa fety (DRs t - The DRS is the~ University RSO, who administers the Universit-y's radiation safety program _and provides technical assistance t.o the RSC- (the RSO serves ex officio
- as-a member of-the committee). The RSO is aut.horized and directed to promulgate and enforce such procedures as are necessary to as-sure compliance _with applicable federal regulations _and to ensure the accurate interpretation and effective-implementation of poli-cies established by the RSC. The DRS is t.he head of the CRSO and.
oversees the activit.ies of its personnel . Decommissioni ng Staf f - The. decommissioning staf f consists of the RA and 'the HeaRh Physics Technician assigned -to the CRSO. The staff is responsible for performing all decommissi_oning acLivities. Contractor assistance will not be required. These personnel are: Dr. Warren E. Eeene, Reactor Adninistratur and Director of Radialion Sa fety , 6
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,, -\ q Mr. Mohammad S. Saba, Health Physics Technician and llealth Physicist in Training.
H 147- Staff Qualifications 1 l All-decommissioning-related activities have been and will be i performed by'the RA/RSO, assisted by the Health Physics-Technicianf in the CRSO. The RA ib well-trained in the use of radiological l equipment. and in perLinent decontamination work. The liealth Physics Technician is in-training and will be appropriately supervised. The qualifications and training of the st.aff, relevant. Lo 1.he decommis - sioning effort, are summarized in resumes included in Appendix E. 1.8 Regulations, Regulat.ory Guides and Standards Decommissioning-relat.ed operat. ions will be governed by pert.in-ent portions of' relevant f edera l , - s ta te , and local regulations, regu l a t.o ry : g uid es , and st.andards associated with nuclear research reactor dismantling, safely, radiological and environmental health, and-industrial hygienm A list of such which are held and believed applicable is included as Appendix F. The list is.not intended Lo be exhaustive; it-la deemed adequate. 1.9 Cost and Funding The Catholic University of America has comm1LLed to provide adequate l financial support to ensure the safe and t.inely decommis-sioning of the CAGN. It is estimated that the Lotal cost of de-commissioning will be less than S12,000, due to the fact t. hat, con-
-Lamination or activation of the.reaet.or.utructure in excess of 10 CFR 20 and RG 1.86 limits has neither been found, nor is anticipat-ed. This amount includes the anticipated cost of- radwaste disposal and ~ the terminat. ion radiation survey. Funding is via the budget of the Radiation Safety. Office.
2.0 Tasks and Schedules The CAGN decommissioning plan includes all tasks whose com-pletion:is required in order to remove all radioact.ive' components from the CAGN facility so that any components remaining in: the facilit.y at the time of the final survey will-be within the con-tamination limits of RG 1.86 and below 5 uR/h'above backgroundfat a distance of one meter. A preliminary survey has indicated this is - already the case. TASK STATUS / SCI!EDULE
- 1. Sample & dispose of shield water Completed
- 2. Remove startup source Completed
- 3. ' Dispose of startup source Completed
- 4. Remove core can Completed :
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- 5. Disassemble and inspect Completed fuel segments
- 6. Submit: fuel _ scrap declaration 1 FEB 92 and related forms to Ono 7._ Ship: fuel to DOE designee 60 days after receipt of containers and shipping-authority l_
- 8. Disassemble reactor strue- Decommissioning approval L Lure to the extent necessary plus 6 months to determine the radioae-Livity of all componenth !
- 9. Deccataminate reactor Decommissioning approval components plus 6 months a
10.-Transfer all radwaste Decommissioning approval to CRSO for disposition plus 6 months
- 11. Termination radiation sur- Decommissioning approval l
Vey of the CAGN facility, plus nine months 12.. Submit final report. Lo the Decommissioning approval l' NRC requesting Lermination plus 12 months of the facility license. 3.0 Personnel Protection 3.1 ,.azard Analysis There are no special health or safety considerations which are pertinent Lo the dismantling or decommissioning:of the CAGN. Normai radictogical health _ protection considerations are appropriate to fuel handling--and-componenL decontamination activity and wilI be observed. Except:for a few components which were in direct contact with the fuel, no radioactive contamination or activation of the structure has been found in extensive preliminary surveys; there - fore, radiation exposure of personnel will be minimal. Removal of the start-up source and the fuel constituted tasks
-in'which exposure.cf-personnel to radiation was unavoidable. How-ever neither whole body nor finger dosimeters recorded measurable exposure incident to these operations. Additional _ handling-of the fuel will be required incident to quarterly inspection and inven-tory, measurements required for the ORO scrap declaration, and L packaging the fuel for shipment. However it-is unlikely that sig-nificant radiation exposuren to personnel.will result from any of these activities. No other decommissioning procedures will involve any radiation exposure above. natural background. Involved personnel are provided film (beta-gamma-neutron) and extremity (beta-gamma) badges hy the-RSO, incident t o their other duties; therefore moni-toring of exposure incident to fuel handling will be included in their exposure records. No radiaLion exposures in excess of nominal background levels have been reported by the dosimetry vendor for 8
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7 Q l-periods during which start.-up source or f uel- have been handled. It i s estimated that a collective : dose-equivalent of less than 0.1 person-rem (whole-body and/or extremity) will have been received by idecommissioning personnel when decommissioning is completed.
- 3. 2 - Radia t 1-o n Protection _
l The radiation protection program will be consistent with ap-plicable portions of.the publications-listed in Appendix F. A copy of the Universit.y's Radiation Safety Manual is included as Appendix G. Responsibility.for proper control of radiation hazards at the CAGN rents with the RSO. All decommissioning activities will be conducted to comply with the ALARA principle to minimize radiation exposure - of decorn-missioning staf f and will be conducted within the scope of the : University's existing radiation safety _ program. Radiation safety 7 durinij all operations will be assured through personnel monitoring, surveys, and _ procedures ~ that are reviewed and approved by the RSO. l The CBSO possesses , ~' uses , maintains.and calibrates various radiation ' detect. ion and survey equipment. It includes 3 inch by 3 inch sodium i~o dide and Ge(L1) ' detectors connected to a' multichannel l analyzer for gamma spectroscopy,-a windowless gas-flow proportional j counter! for alpha and beta particle detection, _and portable survey- t meters.- The port.able survey metera, which-are provided by the Caso ' to all =laboratorie's which require them, include Johnson Associates Model'GSM-15, Ludlum Model ESP,- and ' Eberline .Model E-120 Geiger counter survey meters.' A liquid scintillation detector is available
'in the CBSO.1 No -significant personnel exposures are anticipated since lit-Lle contamination _ or activation has been found =in preliminary sur-
~
veys.LPersonnel texposure will be monit.ored with portable. radiation
' det.ectors, individual. film (whole -body), . and TLD (ext remity L dosi-meters, . when-thez latter are appropriat.e. 1 L3.3 I__ndustrial safety andjlvoiene. I
-Decommissioning the CAGN wil1 proceed in a manner consistent swith~ applicable OSHAT and District of ' Columbia industrial safety requirements. The 'UniversityL Department of ' Environmental Safety (DES)7 maintains a continuing accident-prevention program, monito'rs 1
+ the campus for hazards to environmental health, and provides lab-oratories and- inCividuals with advice and technical ' assistance for developing effective health and safety-practices. Its accomplish- ! ments have been recognized by being_ named _a 1991 recipient of an-
- Award of Merit by -the National . Safety Council . DES conducts regular inspections of University f acilities._ The staf f includes the Direc-torK(a' Certified Industrial Hygienist), an Occupational Safety &
-Health Specialist, and a Chemical Inventory and Waste Manager. The Director is responsible to the EVP for promoting good health and
; safety practices within the University community. The Director i s a - member of . t.he RSC.
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Decommissioning personnel are obliged t.o adhere ~ to healt h and safety practicos outlined in.the University's Chemical Materials safely Manual . The manual cont.ains general procedures for emergency response, laboratory safety, industrial safety, general safety, disposal _of non-radioactive hazardous waste, and fire safety. It also incorporates the OS!!A-mandat.ed Chemical Hygiene Plan. Decom-missioning personnel are f amiliar with the cont ents of this manual . A copy of the manual is included as Appendix H. The.most probable type of accident _ related to decommissioning isLLhat which might be called " mechanical" and might result from either human error or nechanical failure. The probability of human- I error will be minimized by making adequate preparation for the work and by following pr~ determined procedures which will be discussed by participating personnel before the actual work is commenced. The
- probability of mechanical failure will be minimized by t.horough inspection of all equipment in advance of its use.
Decommissioning staff are supplied with coveralls, gloves, safety glasses and safety shoes, to be used when appropriate; dust masks and respirators are available and t. heir use is required when appropriate. Chemical solvents may be used to remove - rad ioact.ive contaminat. ion f rom some reactor component.s. Appropriate ventilation will_be provided. The_use and disposal of solvents, which are-not i radioat 1.1vely contaminated will be in accordance with standard ) University practice. Disposal of radioactively contaminated sol- =l ventu-will be in- accordance wit.h the policies of t.he CRSO. = , 4.0 SECilRITY AND SAFEGUARDS Two categories of storage safety are discussed, that for the fuel:and t. hat for - residual radwa s t.e pending i t.s dicpusition ofC-site. 4.1 End A11.CAGN SNM (reactor fue1) held under-1leense No'. R-31, in-cluding t.h e thermal fuse and the unirradiated-fission plate, has been stored in locked fuel storage safes in the reactor room since
-it was removed from the reaet.or on 17 March 1990. It will remain there until it .is packaged for shipment to DOE's designee.- The react.or room is a controlled access area, equipped with a security system which has been described in prior communication with NRC.
Pending its t. ra n s f e r , the fuel is inspect.ed and inventoried periodically, in accordance wit.h t.he technical specifications, to ensure t. hat t he material is secure, has not. been Lampered with, and that the physical integrity of t.he fuel and its cont.ainers has not d e t.e r io ra ted . After receiving appropriat.e shipping containers and shipment
-authority, CUA will t ransfer the f uel in accordance wi t.h per tinent safeguards requirements of 10 CFR 73.67(g) and DOT regulations.
10
. _ . _ .- .. _. _ .- . - - . .- ._ _ . . - - ---._m __ ._- _ - . --- -_,
l a 4.2 Radi oac t. i ve- Wa s t e Reactor components removed daring the defueling process have been - surveyed and sealed in plasLie wrapping and are stored in t.he reactor room, pending NRC approval to proceed with decommissioning. .l After receipt of decommissioning a ut.ho r i ty , redetor-related contaminated-material, parts or components which can'not be de-contaminated to RG 1.06 standards will be t.ransferred t o the CRSO, for interim storage and/or disposal--depending on the availability ' of low level wast.e site access. , i The CUA byproduct material', special nuclear material and source material licenses a re adequa t.e to provide for lawf ul reten-Lian of residual radwaste until such Lime as il can be deposit.ed in a los level waste site. The CRSO radwaste handling and storage facility is described in Sect. ion 6.3. 5.0- Risk Analysis Because all fuel has been removed from the reactor and is stored in a configurat. ion which insures t. hat k , < 0.0, the Ra-Be neutron source has been disposed of, and very II,LLle conLamination and no acLivated materials have been found, no credible radiologi- . cal accident can be post.ulated. Criticality can be achieved only by ! reassembling the core and control' rod material in the presence of an_ adequale reflector-moderator, such an occurrence by accident is impossible. . 6.0 Radioactive Material Management 6.1- Fuel Disoo gl
~
All fuel has been removed f rom the CAGN arid' is stored as de- - scribed in Sec. 4.1. The fuel wilI be shipped t.o DOE's designee as soon as appropriate approval for fuel transfer is received. Sche-duling was discussed in Sec. 2.0. 6.2 .g.,$ d i oa c t i ve Lste Processing No gaseous or airborne radioactive sastes have been ebserved in-Lhe CAGN facility or are expected Lo.be generated during the
' decommissioning orocess. A sma11 amount of aqueous radioacLive waste (estimated to be less than three gallons) may be generated in the decontamination of reactor components. A much smaller amount of radioact.ively_ contaminat.ed chemical solvents may also resul t. f rom-decontaminaLion efforts. Liquid wastes will be rendered into a form that f acil-i ta tus disposal, as directed by the RSO. Less than one cubic foot of solid contaminated waste (comprised of wipes, dispos-able gloves and protective clot hing, and drop cloths) was generated during the defutling; it has been disposed of by the CRSO. It 'is anticipated that a toLal of less than 5 cubic feet of additional i
solid waste will be produced incident to decommissioning. The waste 11
- .- ---- .- .- -- . -~ - - - - .-- - ..
, ,. i 1
will be_ disposed of through the Universit.y's low-level radioactive
- wdsbe ipt ogram managed by- the CRSO, and described _i.n Appendix G.
Except for core components which were in direct contact with the fuel, preliminary surveyb have found no evidence of radioact.ivo contamination in the facility. Reactor components not in direct contact with the fuel are not expected to be contaminated or show any evidence of activation. However, any parts, components, or ma-Lerial which do nut meet the unrestricted release criteria des-cribed in Sec. 1.2 and 2.0 will be delivered to the CRSO--for dis-posal in a low level radioactive wa ale s i t.e , in accordance with NRC and DOT regulations, at a time when site access exists. Mixed waste generation is nul anticipated. However the Univer-sity's Vit.reous State Laboratory has extensive experience in radio-active and mixed waste management research. Separation ~of any small quantity of mixed waste, which might be generated, into its respee-Live t.oxie and radioactive conponents is expect.ed to be feasible. 6.3 Radioact ive Wste Sto ran ) The CUA radioactive waste handling and storage facility con- j sists of a. quonset but of.approximately 600 square feet,_with a
= central -ceiling- height of twelve _ feet. IL is not shown on.the campus nop (Fig. 1); it is located adjacent Lu the south and east wings;ofSL. John's Hall, which is shown. It is equipped with a f ume hood with HEPA-filtered exhaust and a stainless steel sink where all licensee sewer diapesa) of radioactive .na t eria l origi-nat.es. - A 30,000 pound force in-d rum compact or is un order. I t. _ w i l l be installed during - the' early part of 1992. Given the present rad-waste- genera tion rate and -anticipated increases lhetein, it is es-timated that CUA has the capaelty to store radwaste on site for more than_five_ years,-should lack of access to a low level waste site make that_neuemaary. Plans exist to enhance the security of 1.he facility, consistenL with t.he potential increase in the average
._ ra dwa s te inventory which will result from prolonged site unavall-a bi l i ty _. -
7.0 TECHNICAL SPECIFICATIONS Th'e reactor has been def ueled and the reactor license has been ' amended .to " possession only," with appropriately revised technical-specifications. No further changen in the technical specificat. ions are believed to be necessary ~during the decommissioning project. (certain of the Technical Specifications will become inapplicable -i when the fuel has been shipped.) Radiation. monitoring in the CAGN , facility is performed monthly as part of routine campuu aut; veil-lance by the CRSO. Pending transfer of f uel of f site, the CAGN fuel will remain secured in locked-safe fuel storage-facilities in the controlled access .t eoilor room and maintained in an array such that kg 'is less than 0.8 for all conditions of moderation ~and reflee-t.lon. While onsite, the fuel will continue to be inspeeled period-ically lo ensure that the mat.erial is secure and that the integrity of the fuel and its containers is mdintained. A copy of Lhe current
-Technical Specificallons is included as Appendix I.
12 f 1
. . . . ~ . _ - - .- ._ . - - . . _ . . - . - -~ . --
, .s 0.0 ENVIRONMENTAL IMPACT Experience gained daring the deccomissioning of similar AGN reactor facilities (e.g., Oregon Stale Universit y [NRC License R-511,' Memphis State University [R-1271], and the University of
-Oklahoma [R-53]), has demonalrated that such det.iviLies may be completed successfully with only negligible changes in Lhe amounts of effluents t hat may be released of f site and without any signif i--
cant increase in individual or cumulative occupational radiation exposure. Because decommi ssioning of the CAGN f acilit y involves no significant hacord to the public or the environment nu environmen-Lal impact statement has been prepared. Identification of the use of Room B-16R, Pangborn Ha11 as a reactor faciliLy wilI be main-Lained in the permanent records of the CRSO. 9.0 Termination Radiation Survey The Lermination f ae t ~ lity survey will include the reactor room and al l component s , material and equipment associated with the CAGN faciliLy which are Lo be released for unrestricLed use. On complet-lon of decommisaiuning, only normal background radioactivity will renain in the reactor ruum. In the reacLuc facility, al1 surface ereas larger than one square meLer will be marked off.in a grid of one meter square blocks. The survey will include a wipe sample of 100 cm' (nominal) Laken within udeh block Lu identify removable contamindLion. Wipes for each grid location will be counted for alpha and beta cont. amin-ation. . Limits for removable cont. amination will be 200 den /100 cm* (beLa/ gamma) and 20 dpm/100 cm d (alpha) (RG 1.86). A bela-gamma survey also will be performed centered on each block al e distance of-one meter from the surface. Residual radioacLivity wi.ll 1*e con-sidered acceptable if measu rements so-made a rc* noL more than 5 uR/h above background, where lhe reference background value is obtained as the highesL of corresponding .neasurements of Limilar uLrucLural material made elsewhere in Pangbora Hall. Results of the survey and t.he. prueedures used to obtain and analyze data will be audited by the RSO and Lhe RSC Lo ensure the accuracy and completeness of the data, small objects, for which o one- meter grid is inapplicable will be nipe Lested and-surveyed in a manner which is'consistenL hiLh the-procedure used by the CRSO for inspeelion of incoming packages of radioacLive material. L im i. L s for removable *:on tami na tion and radioactivity will be those described in the preceding paragraph. The CUA RSO mainLains various radiation detecLion and survey instruments . which may be used for the termination survey. This equipment was described in Section 3.2. Additional- inbLrument a tion may be acquired for the purpose. InstrunenLu used for these surveys wil1 be current 1y-calibraLed in aceurdanee with approved CUA RSO procedures, which are consistent with appropriate ANSI Standards. 13
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,, '.o Board of Trustees President of The catholic University of America i
i Executive Vice President i Laboratory' Safety' Committee Radiation Safety Committee Reactor Administrator Radiation Safety Officer Decommissioning Radiation Safety Staff- Office Personnel Figure 3. Administrative Organization for Decommissioning The catholic University of America AGN-201 Nuclear Reactor
' =,
I Appendix A: Description of AGN-201 Reactor A.1 Introduction The following description is excerpled from the Final Safety Analysis Report (FSAR) which was submitted in Oct.ober 1977, in sup-port of the license renewal applicat. ion. The description applies to an inLaet., fueled reactor. It should be noted that, in the case of the CAGN, all f uel has been removed and disassembled, and the elec-trical cable which connected the conso'e and the reactor has been removed and destroyed. A more complete description is found in Chapter 4 of the FSAR. A.2 DeserirLion The CUA AGN-201 Reactor, Serial No. 101, is a campact, port-able, self-contained nuclear reactor designnd to operate at a power level of 0.1 watt. The core, together with the fueled cont. col and safety rods, contains approximately 602 9 of U-235 in the for,a of 19.909 enriched UO micro particles embedded in radiat. ion-stabi-lized polyethylene ; moderator. Shielding of graphite, lec d and water surrounds t.he core. The maximum thermal flux is 5x 10 n cd s" . The conplete reactor unit stands approximately 3 m (10 f t) high and 2.1 m ( 7 f t) in diameter. When so-licensed, continuous power levels as high as 20 w are possible with additional shielding. The core is doubly sealed in an aluminum core tank and the steel reactor tank. A thermal fuse-link prevents d e l ibe ra t.e high power operation. The reactor system consists of two basic units, the neactor and the Control Console. The reactor unit includes the uranium-polyethylene core, graphite r e f l ec t.o r , and t.h e lead and water shielding. Fuel-loaded control and safety rods are installed ver-t.ically from the bottom of the reactor unit. The weight of the reactor unit., with the water shield, is approximately 9,000 kg (20,000 lb); the weight of the console unit is 350 kg (800 lb). Power requirements are 2 kW of 100 VAC elect.rical power. The critical mass necessary for operatica of the Reactor is approximately 665 g of U-235. The uranium, in the form of UO mi-crospheres, is homogeneously enbedded in approximately 10,900) g of polyethylene formed into a right circular cylindrical core 25.75 cm (10.15 in) in diameter and 23.75 cm (9.34 in) high. The reactor is operated al suf ficiently low power that, if all of the radioactive fission products f ormed in normal operation sere to escape, they would not be danger'us to a pecsun in Lhe least ad-vantageous position. Similarly, in the event of an escursion, no person would be seriuusly harmed under any plausible circumstances.
9 f' sos. Appendix Bi_ stannary of HeacLar operationn 1957 - 1982. Tile CATil0LIC UNIVERSITY OF AMERICA AGN-201, Serial No. 101 Initial criticality: 20 November 1957 Final Shutdown: 4 December 1982 Reactot- Defueled: 17 March 1990 Year' firs Operated Energy Generated (watt-hours) 1957 5.4 .27 1958 12.8 .56 1959 14.1 .92 1960 25.9 .79 1961 13.1 .26 1962 19.1 .70 1963 2.4 .00 1964 10.4' .07 1955 16.2 .10 1966 32.5 .52 1967 29.6 .85 1960 46.6 1.52 1969 29.0 1.44 19'S 45.5 1.43 J971 137.8 3.14 , 1972- 10.9 .41
-1973 56.1 1.09 1974 16.0 .34 1975 3.2 .03
.1976 0 0 1977 0 0
.1978 0 0 1979 17.6 .28
-1900 36.9. .83 1981 22.1 .52-1982 6.6 .12 Total: 609.8 hours 16.19 watt-hours
. ~ . - . . .- - -. . - . - ~ . , -. - .- , -
i Appendix C: Estimated Fission Product inventory of CAGN Fuel The fission product activity inventory of the CAGN fuel is not known. However it is possible to place $n upper bound on it, using an estimating technique given by Cember. Assuming a mean value of 190 MeV heat energy per fission, one watt is equivalent to 3.3 E10 fissions per second. It is estimated (App.-B) that the total thermal energy released during all opere tion of the CAGN was 16.19 w h. Then, assuming all fissions to have been of U-235,_the burnup of U-235 is estimated to be: (3.3 E10 fiss s'I) * (16.19 w h) * (3600 s hd) = 1.9 E15 atoms, which corresponds to about 750 nanograms of-U-235. , This estimated burnup occurred over a period of about 25 years. To place an upper bound on the fission product activity at final _ shutdown (DEC 82), it is assumed that all fission product
- production occurred during the final operation. Then (Cember, op cit), the fission product activity at times up to 1000 hours (46.67 d) later is estimated fron- ;
1.03 E-16 T4'2 A- = Ci/ fission, with T in days, and our upper bound-for the fission product activity in mid-January 1983 would be approximated by A = .(1.03E-16 Ci/fiss) * (1.9 E15 fiss) * ( 4 6. 67 ) ~I'2, or about 1.9 millicuries. , To estimate an upper bound for_the current (DEC 91) fissign product' activity, use is made of information given by Eichholz . In Table 164, Eichholz provides data relating the fission product
-activity of high level waste at 5 y to _ that at 1 y af ter reprocess-ing. From these values'it can be inferred that the effective half life of the fission product activity-during this period is about 1.9'y. Making the assumption that this value is reasonable over the nine years since last operation of the CAGN, our upper bound on the
- present fission product activity in the CAGN fuel is estimated to be A = (1.9 E-3 Ci) exp(-9 In 2 /1.9) -= 7.1 E-5 Ci.
Thus, it- is estimated -- that . the present fission product activity of the CAGN fuel is less than 71 microcuries. Cember, Herman,, Introduction to Health Physics, 2nd Ed., Pergamon Press, Elmsford, NY, 1983. 3 Eichholz, Geoffrey G., Environmental Aspects of Nuclear .
-Power, Ann Arbor Press, Ann Arbor, MI, 1977 f
.. 8..
Appendix D:' Qualifications and Training of Decommissioning personnel WARREN E. KEENE Position: Director of Radiation Safety, The Catholic Univers. tty of America Experience: 14 Years Experience Summary: , Dr. Keene has held the position of Director of Radiation safety (formerly titled Radiation Safety officer) at The Catholic University of America since 1977. He has held numerous positions in the Baltimore-Washington Chapter of the Health Physics Society, serving as President during the 1987-88 Chapter year. For many years, he has been a lecturer in professional and technician level training courses conducted by the Chapter. In 1987 and 1988 he served as a member of the advisory panel to the Board of Directors of the Health Physics Society for the purpose of guiding the creation of a transition education program for health physicists, health physics technicians, and management personnel having corporate responsibility for compliance with radiation safety regulations. The program was intended to assist the target audiences in complying with anticipated changes to 10 CFR 20. Specific Experience:
- Engaged in basic and applied research in radiation donimetry and environmental radiation measurements 1966-1977.
- Engaged in basic and applied research in the application of porous glass-based ion exchange techniques to the management of both low and high level radioactive waste 1977-1987. This work required.the design and fabrication of special tools and equipment for hot cell use, as well as-training hot cell operators in their-use.
- Guided the development of an off-gas handling system for a laboratory scale slurry-fed melter used to produce uranium-thorium glass for radioactive waste management research in support of the reclamation of the West Val-ley, NY site.
Education: Ph.D., Nuclear Science and. Engineering, The Catholic University of America, 1987 M.S., Nuclear Science and Engineering, . The catholic University of America, 1966 B.S., Engineering Management, The George Washington University, 1957
i
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; Appendix.~D. Qualifications and Training of Decommissioning
' Personnel MOllAMMAD SADEGH SABA .-
i l Position: Health Physics Technician - I. ! The Catholic University of Amerim April 1991_ present q Experience: March 1984-March 1986. Nuclear Power Plant Management, Atomic Energy Of Iran (ADEI). Reviewed nuclear design and_modifica-tions - and the contract of nuclear power plant._ Prepared sorting computer program for inventory of_all the equipments and materials for the Iran Nuclear Power Plants. 0-tober 1980-March 1984. Nuclear Rosearch Center /Isfehan Technology Center, AEOI.. Studied aspects of nuclear fuel design- using computer codes such as PANTER, EREBUS and METHUSELAH.- Designed. a fuel lattice for the suboritical reactor in'Isfehan. LSeptember'1979-October 1980. Exxon Nuclear, Richland, WA.
-IAEA' Fellow. Performed nuclear core analysis fuel management for BWR's and PWR's. Compared-the results of XTG:and X F'iR E computer codes with General Electric codes. Performed the preliminary < design of spent fuel assembly storage, using-ORIGEN computer code. Used PDQ-7 to compare the results of point depletion-and zone depletion. methods. -
Sep ember 1978-June 1979. Kraf t Werk Union, Erlangen, Germany. Alo igside Engineer in the fuel management department. Studied - rt= alts _of- the - MEDIUM computer code 'for different fuel strategies.- L May 1976-September 1978.- Nuclear Research- Center, , AEOI. Studied criticality ' and _ f uel burnup of Iran 1 &__2 Nuclear Power Plants using METHUSELAH and-EQUIPOSE computer codes. Education: Bachelor of Science in-Physics, Pahlavi University, Iran June 1974 t Special training in nuclear reactor technology, AEOI,_ April ~ I 1976.. (Applied Mathematics, Nuclear Reactor Engineering, Nuclear Reactor Physics, Reactor _ Fuel Design, Heat Transfer, Computer Programming, and Numerical Analysis. Graduate student, Joint Center for Graduate Studies, Richland,
- WA. Passed. Nuclear Fuel Management and Nuclear Reactor Engineering courses, February 1980, Graduate student (M.S. in Health Physics), Georgetown Univer-sity, Washington DC, September 1991 present.
. . _ _ _ _ _ . . _m _ _ _ .
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.7 A.
Appendix,E = .The CUA RSC' Membership
-1 1
Dr. Roland M. Nardone- Director of t.he Center for -l Advanced Training in. Cell U and Molecular Biology, and RSC Chair ; Dr.--Gregory ,rewer Assistant Professor of > Chemistry Mr. Robert Fawbush Manager , ' El ect.rical /Mechanica l .; Services -I Mr. Clay Goldaton Director of Public Safety Dr. Jan Hallal. Associate Paofessor of Nursing Dr. Warren E.'Keene Reactor Administrator and . Director of Radiation Safety
-Dr. Scott-Heimig Director of Environment.al Safety
'Dr. Isabelle Muller Staff Scientist. ,
Vitreous State L'aboratory i Dr. Daniel Sober Professor of Physics
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a Reference Documenta Appendix F. I R-31 50-77.
- 1. Reactor License No. i Docket No.
U. S. Nuclear Regulatory Commiss on ( ANSI /ANS-15.10-1981 Decommissioning of r 2 American Nallonal Standard for Research Reactorb 3 10 CFR 20 t Radiation Standarda for Protection Agains 10 CFR 30 to Domestic Licensing 4. Rules of General Applicabilit.y of Lyproduct Material 5 10 CFR 50 d Utilization Domestic Licensing of Production an Fa::il ities 6 10 CFR 71 f Radioactive Waste Packaging and Transportation o 10 CFR 73
- 7. of Plants and Materials Physical Protection 49 CFR l tions Governing the 8.
Department of Transportation Regu aof Radioactive Material Transportation l Regulatory Guide 1.86 1974, Termination of 9 . U. S. Atomic Energy Commission,for Nuclear React. ors Operating Licenses Radiation Safety Manual 1980, as amended
- 10. i The Catholic University of Amer ca, i is
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- APPENDICES - G, H, & I ARE- SEPARATELY DOUND.
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st +=+a i Appendix J: Abbreviations and Acronyms i AGN Aerojet General Nucleonica -j
-ALARA As Low As Reasonably Achievable CAGN CUA AGN-201 Nuclear Reactor, Serial No. 101 CFR Code of Federal Regulatiors l CRSO CUA Radiation Safety Office -j CUA The Catholic University of America DOE- U.S. Department of Energy '
DOT U.S. Department of Transportation DRS Director of Radiation Safety EVP Executive Vice President , NRC U.S. Nuclea.r Regulatory Commission ORO DOE Oak Ridge-Operat. ions-Office RA Reactor Administrator RG (NRC) Regulatory Guide RSC- Radiation Safety Committee RSO Radiation Safety Officer SNM Special Nuclear Material J'- a .}}