ML20092P153
| ML20092P153 | |
| Person / Time | |
|---|---|
| Site: | 05000276 |
| Issue date: | 05/25/1984 |
| From: | Karam R Neely Research Reactor, ATLANTA, GA |
| To: | Verrelli D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML20092P150 | List: |
| References | |
| NUDOCS 8407060004 | |
| Download: ML20092P153 (3) | |
Text
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Georgia Institute of Technology R
NEELY NUCLEAR RESEAACH SCHOOL OF NUCLEAR ENGINEERING AND HEALTH PHYSICS ATLANTA. GEORGIA 30332 e (404)094-3800 CENTER May 25, 1984 Mr. David M. Verrelli, Chief Reactor Projects Branch U.S. Nuclear Regulatory Commission, Region II 101 Marietta Street, N.W.
Atlanta, Georgia 30303
Subject:
Inspection Report No. 50-276/84-02 l
Dear Mr. Verrelli:
l This letter is my response to the referenced inspection of the Georgia Tech AGN-201 reactor on April 11-12, 1984.
1 Enclosed is a copy of the Dismantling and Disposal Plan for I the AGN-201 which I sent to Mr. Cecil 0. Thomas of NRC for !
approval. This plan was reviewed and approved by the I.uclear Safeguards Committee of Georgia Tech (see appended letter).
Immediately following approval of this plan by NRC, Georgia Tech will proceed to dismantle and dispose of the AGN-201.
Item: The proposed emergency plan has not been appro-priately revised to reflect changes in the onsite emergency response organization for the AGN-201.
The revised emergency procedures for the AGN-201 are appended. The telephone numbers of the emetgency director and all support organizations ..ce now available in the Nuclear Engineering Program Office.
Item: No radiological exercise has been conducted since September 9, 1980 when Grady Meuorial llospital participated with the licensee in a drill involving a simulated personnel contamination problem.
An emergency drill involving personnel contamination problem is being planned for the summer of 1984 in conjunction with Grady 1lospital.
Item: Update agreement with Grady llospital and provide l'n emergency update.
plan for biennial review and periodic 8407060004 840612 PDR ADOCK 05000276 G PDR A una e the unnewy system d carge Anmm
The agreement with Grady Hospital will be updated this summer. A review of the emergency plan adequacy will be conducted after the emergency drill.
I hope that you will find our answers to the questions raised in the referenced report satisfactory. Should you need additional clarification or information please let me know.
Sincerely yours,
/ h // . f h , [
Ratib A. Karam Interim Director RAK/jlr pc: President Pettit Dr. T.E. Stelson Dr. J. Spurlock D r. J . Brighton Dr. J. Kallfelz Nuclear Safeguards Committee
Enclosures:
As stated
Georgia institute of Technology R
NEELY NUCLEAA AESEARCH SCHOOL OF NUCLEAR ENGINEER:NG AND HEALTH PHYSICS ATLANTA. GEORGIA 30332 (4041894 3600 CENTER May 25, 1984 Mr. Cecil 0. Thomas, Chief Standardization Special Project Branch Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Thomas:
RE: DOCKET 650-276 The Georgia Institute of Technology holds License #R-111 to operate an AGN-201 training reactor on its campus at Atlan*.a, Georgia. The continued use of this reactor in the Institute programs is no longer justified, so the decision has been made to shut down, decommission, and dispose of the reactor. Some attempts have been made to locate another possible user to whora the reactor might be transferred, but up to this time no likely candidate has been identified.
The decision of the Institute is to remove all components of the reactor which contain special nuclear materials, and to return this fuel to its owner, the U.S. Department of Energy.
The purpose of this letter is to inform NRC of our plan.
The reactor may still De in operable condition, but has not been operated since 1979. It contains all of the U-235 fuel of the core, and the fueled control rods. All control instrumentation is connected.
Available records show that the AGN-201 was operated at Georgia Tech for a total of 683.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br />. Assuming that all operations were performed at a power icvel of 100 milliwatts the total energy generated is 68.4 watt-hours. The total radioactivity of fission products in the fuel is estimated to be 0.03 pCi per gram which is about two orders of magnitude less than the natural radioactivity in U-235.
We plan to remove the fuel from the reactor following the procedures outlined in the Dismantling Plan, package it in approved containers (to be specified by DOE representatives at ORNL, Mr. William Pryor, in accordance with NRC and DOT requirements), and move it to the storage vault of the GTRR, Georgia Tech Research Reactor.
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After the fucl has been removed, the Institute will perform a comprehensive radiation survey, will transmit the results to NRC, and will ultimately request termination of license IR-lli and residual reactor hardware and facilities. The Ra-Be neutron source will be retained.
The enclosed Dismantling Plan discusses in detail the procedures to be used, and the precautions to be employed to protect the general public. During the defueling of the reactor, the Institute will utilize the services of a re-licensed AGN-201 senior operator, Dr. J. Narl Davidson of Georgia Tech.
, Review of the license #R-111 and Technical Specifications documentation reveals no requirement for an amendment to reiaove fuel from the Georgia Tech AGN reactor. Farthermore, teview by the Georgia Tech Nuclear Safeguards committee concludes that removal of the fuel is consistent witu the Technical Specifications and that it does not constitute an unreviewed safety question.
Sincerely yours, M A.
R.A. Karam Interim Director Nuclear Research Center RAR/ jlr pc President Pettit Dr. T.E. Stelson Dr. J. Spurlock Nuclear Safeguards Committee 4
1
l I
DISMANTLING AND DISPOSAL PLAN i
f I. Introduction
! The Georgia Institute of Technology currently possesses an (Docket l AGN-291 Training Nuclear Reactor However, under License only the fuel No. R-111This No.59-276) .
l ultimate disposal of the entire reactor. To permit the i
l will transfer be removed of the fuel, andthis relocated document at this time. for the dismantling provides e
)
i 1
of the component parts and disposal of the fuel as presc of Nuclear ReactorL."
The procedure for disassembly will be to remove the reactor
! control rods, the Ra-Be startup source The Ra-seand then source thewill separate be placed j
1ections of the core assembly. The fission plate, fuel l in the source container (a Pb pig).
sections of the control rods and fuel assemblies (polyethylene discs) will be separated into two, approximately equal amounts !
(according to U-235 content), wrapped in polyethylene bags, and placed in NRC and DOT approved shipping containers for storage.
l j
After all fuel and the startup neutron source are removed, the electrical connections for the control rod drives and otherAll components and are
! instrumentation will be disconnected.
- will be checked for contamination and decontaminated where j required, When j The fuel will be temporarily stored in the GTRR vault. '
f all approvals are received the fuel will be shipped of f-site to !
i i DOE, State Regulations.
Oak Ridge, Tennessee in accordance with all Federal andA l 3
ragc, and gloves will be disposed of as rad-waste, according All to ,
the Georgia Tech and other applicable regulations.
+
protective procedures.
clothing will be handled according to Georgia Tech t or normal waste procedures until shown to be within applicable i
limits.
During the entire operation, great care will be'taken to l protect both the operations personnel and the general public from exposure to ionizing radiations, and to keep any necessary i exposure as low as reasonably practicable.
)
1 II. Dismantline Procedure
- A. General Procedures l For the accomplishment of the defueling A licensed operations, operator Dr.
R.A. Karam will be present at all times.In addition the Institute l will.be present as a consultant.
i Radiation safety Officer, Mr. Robert Boyd, will Allmonitor personnel the l
i operations for radiological safety aspects. involved in the op operation at a pre-defueling meeting.
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will be issued for the job.
B. Hazard Evaluation (
- 1. Nuclear Safety. A nuclear excursion would be the most serious type of accident that could uccurHowever, during theit is one l disassembly and removal of the reactor core. To obtain i of the least likely of all credible accidents.
criticality, the complete core assembly, including all fuel discs, the two fueled safety rods and the fueled coarse control j rod must be assembled within a nearly optimum reflector, i Nuclear Safety will be maintained by first removing the in the shipping fuel from safety and control rods and storing it container. The combined fuel content of the rods is approximately 45 grams of U-235.
The core itself contains approximately 620 grams of U-235 and, with the rods removed, has a negative reactivity in excess ,
of three percent (3%) in d k/k.
The core disassembly will be done in the reactor room area.
As the fuel discs are removed, they will be placed on a workbench covered with clean protective paper. Discs trom the two halves of the core will be stored in separate shipping containers, '
approximately 350g U-235 per container.A portable fast neutron surve operation during the disassembly of the core as an indicator of neutron multiplication. However, a detailed critical mass determination by neutron multiplication measurements will not be performed since the maximum reactivity increase that can be achieved by repositioning the fuel discs is less than the worth of the control rods.
- As a further precaution, a temporary cadmium safety rod will be inserted into the core This tank gloryrod cadmium hole will tube prior remain in to place disassembly of the core.
during the disassembly of the top half of the core. The rod will be removed then by pushing it out as the glory hole liner tube is removed.
The removal and disassembly of the reactor core will be left Whenever performed under the supervision of Dr. R.A. Karam.
unattended, the reactor facility will be' locked, with access ;
controlled by Dr. R. A. Karam. I
- 2. Radiation Safety. Radioactive contamination could ;
arise from three sources: the reactor core, activation Fised products surfaco )
outside the core and the Ra-se startup source.
contamination produces external radiation exposures; airborne Thorough surveys of the contamination adds an inhalation nasard. ;
reactor and core components and comprehensive monitoring of air :
and personnel during disassembly will prevent accidental and/or excessive exposures to contamination hazards. such monitoring l
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will be supervised by the Institute's Radiation Safety Officer, and/or the health physics technologist.
Respiratory protective equipment and coveralls will is be worn ,
by all persons in the reactor room when the core tankinitially o ;
has been definitely established.
l The 10 mci Ra-Be startup source will be removedrods. from the The reactor after the removal of the safety and control i
source will be wipe-tested immediately after removal and stored in a shielded container.
Personal monitoring devices are worn by all individualsThis entering the AGN reactor room under any condition.
l regulation will continue to be strictly enforced during all of the procedures contained in this Dismantling Plan.
The n.ost probable type of
- 3. Mechanical safety. be called mechanical and uay result accident is that which might The probability
(
from either human error or mechanical failure.
of human error will be rainimized by making adeguate preparation i
for the work (see Section C) and The by following a predeternined probability of mechanical plan of action (see Section D). failure will be minimized by thorough inspect in advance.
C. Preparation (Check List) i' 1. Radiation Protection
- a. The following instruments will be checked for proper operation, then placed in the reactor room for use.
- 1. Air sampler
- 2. Fast neutron survey meter
- 3. Gamma dose rate survey meter (Cutic Pie or Radector)
- 4. Contamination survey meter (E nd-w indow Geiger Counter) l I b. The following supplies will be collected and placed in the reactor room:
- 1. Glass fiber filteis and filter holdera for air sampling.
- 2. Whatman filters or Nucon smears for wipe l tests.
t
- 3. Individual con'cainers for air sample and l
wipe test filters.
- 4. Shielded storage containe'r for storing the Ha-Be startup source.
5. Appropriate breathing apparatus (face l
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mask) will be worn as required by the i Radiation Safety Officer.
- 6. Coveralls, lab coats and gloves.
- 7. Radioactive waste container.
- 8. Cadmium safety rod. ,
- 2. Work Area and Tools
- a. Clear reactor room of extraneous large items and clean the work area with vacuun cleaner, in
- b. Collect the following tools and placc
! reactor room:
- 1. Hand tools (socket and allen wrenches) required for disassembly.
- 2. Handling tool for removing the Ra-Be source.
Fuel storage and shipping containers.
3.
- 4. Operating crane for lifting the theri..al coluun, core tank and upper graphite reflector.
i
- c. The following items will also be placed in the reactor room:
- 1. Plastic bags or sheeting on which to place control rods and fuel cori.ponents, and for packaging such components.
- 2. Labels for dinnantled core components.
i
' D. Procedures Disassembly
- 1. Removal of the Thermal Tank, Part No.
2-000139.
l a. Remove bolts that secure the thermal l
tank assembly to the water tank,
- b. Attach lifting frame, T-000458, to the flange of the thermal tank with the bolts provided, and hoist carefully from the water tank.
I
- 2. Removal of control and safety rod cap-sules (part No. 2-900184).
- a. Insert temporary cadmium safety rod f
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into glory hole.
- b. Hemove the bottom cover plate (2-900169) by loosening and turning 1
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i 198061h895"1831%?'8askeVpartso.
2-000593, should come off with the c ove r . )
- c. Remove Dash Pot assembly (Part No.
f 2-000510 shown on 2-000184) by l grasping the knurled surface and unscrew by hand (r ight-hand thread) ,
then lower carefully out of the main l frame assembly. .
l
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- d. Remove the rod capsule-and-tube assembly by unscrewing ( r ig h t-hand thread) cap 2-000195, using a 1/2" socket wrench, until detached, and
(
'- lower carefully out of the contr ol rod raain f rame assembly.
- e. Remove rod capsulo from rod tube by gripping the two tubes by hand and unscrewing. This thread is LEFT HAND; if the other direction is used, _ the capsule 0-ring seal will be opened and the active material will be expoced.
- f. Hemove U-fuel from control rods, wipo-test for removable radioactivity wrap in plastic and place in shipping container.
9 Remove and wipe-test the Ra-Be star t-up source. Place it in the portable storage container.
- 3. Core Disassembly The entire disassembly of the reactor core will he performed in the presence of Professor H. A. Karan with a nininu.a of two persons present during each step of the operation.
However, the total number of people present will be minimized.
j The following procedure will be followed in the sequence i indicated
- a. Start membrane filter air sampler l
operating in close proximity to reactor core.
- b. The reactortworoom individuals to beis in as the core the opened will wear the appropriate f ace masks and gloves.
- W' f f s 464 W4 .-4 p
c.
- . . d
- c. The upper end plate of the core tank will be removed, with special care being taken of the 0-ring gasket.
- d. After the air sampler has been allowed to run several minutes, the filter will be removed and counted on the low background gamma ray detector. Another filter will be placed in the air sampler and
- collection of a second sample will started. As soon as the absence of
- an airborne contamination hazard is established, the face masks will be dispensed with,
- c. Lifting lugs will be screwed into the i threadec sockets in the upper main reflector and this reflector will then be lifted out of the core tank.
- f. As each piece of the core assembly is removed, a representative area of approximately 100 cu will be wiped l
with a filter paper or Nucon smear.
The smears will be retained for later analysis to determine quantities of l
removable contamination throughout l the core. Each core component will then be completely wiped with " wiping tissues" and these wipings will be disposed of as radioactive wastes.
1
- g. The fuel discs will be removed one at a time, beginning with the tip of the core and working downward through disc No. 4. Each disc must be removed carefully to avoid jostling, l
and thereby shifting, the remaining l discs. NOTE: ruel from the top half i of the core will be placed in one of the two shipping casks provided.
- h. After removal of all fuel discs in
! the upper half of the core, the L peripheral reflector sections will be
( inspected for possible removal.
l 1. The temporary Cd control rod will be removed, followed by removal of the Glory Hole tube.
- j. The core tank will now be removed from the reactor and lowered to floor
A level.
k..*
The lower main reflector, together with f uel discs 1, 2, and 3 and the
' thermal fuse assembly will now be removed.
- 1. The lower half of the core will be disassembled by compressing the sup-port spring recessed in the The base of the lower nain reflector.
thermal fuse assembly will then be2 and c.ay exposed above fuel disc No.
be released by removing the clip ring. The fuel discs from the lower half of the core, and the thermal fuse will be wrapped for placement in the second shipping container.
- m. All parts, components, etc., will be levels decontaminated to acceptable before the shipping containers are finally closed and secured.
- n. Following removal of all of the fuel, the reactor reflector components will be reinserted, and the tank systou reassembled for future disposition.
Based on prior experience, it is ex-pected that the tank system will contain no measurable radioactivity,
- o. The Ra-Be startup source will.be retained and will be stored according to applicable regulations by Georgia Tech.
Storage of III.
Criticality and Security Safeguards.During of Fuel Awaiting Shipment A.
Storage Location of Fuel and Control Hods As indicatd above, the fuel and fuel portions of the control and safety rods will be wrapped in polyethylene and will ultimately be used to transport the Special i l Nucle The containers will be sealed in theand vault of to Oak Ridge, Tennessee.The containers will be stored properly labeled.
the GTRR until shipment.
B. Criticality Monitoring With half of the fuel stored in each of the two shipping A temote containers, inadvertent criticality is impossible.
l l
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v radiction monitoring instr umen t oxists in the vault.
1 p.
is
4 AGN-201 ;
Emergency Procedures !
(Extracted f rom AGN-201 liealth Physics Procedures) ,
Emergency Procedures 18.1 General l
It is impossible to predict the exact circumstance of an therefore, no emergency situation in the reactor facility and,However, lines of detailed disaster plan can be outlined.
1 responsibility can be drawn and some general rules established to These rules are based on the cope with most situations.following objectives which are listed in the order of the importance or priority.
Prevent injury to Georgia Tech staff and students, and 1
A.
to the general public.
I B. Prevent damage or contamination of facilities and equipment.
' C. Return facilities and equipment to service as rapidly as possible.
j A distinction must be made as to whether or not the event occurs during normal working hours. If the staff of the School of Nuclear Engineering or the Nuclear Research Center is present l
when the emergency arises, decisions based on knowledge of the If the staff
, pertinent is not present, it conditions can be immediately formulated.is necessary that the p emergency and/or the Georgia Tech Police Office make proper notifications and prevent all unqualified persons from 4 approaching the area.
18.2 Responsibilities Emergency Director. The Emergency Director is the A. He will be
'l director of the Nuclear Research Center.
responsible for directing whatever actions are neces-sary to combat the emergency andItwill iscoordinate his duty tothe activities of the other groups.
ensure the safety of Georgia Tech personnel and the
~ public, to notify all appropriate university officials and governmental agencies, and to initiate contact ;
with the Georgia Tech administration related to 1
releases to the public news media.
I B. Health Physics. Members of the staff of the office of l Radiological Safety will be responsible for assessing j any radiological hazards which may be involved andadv the hazards. They will provide monitoring for
i Al emergency workers and all personnel and will d The Campus Police will be re- "!
C. Georgia Tech Police.for the routine checking of the facility In
'sponsible t When Nuclear Engineering staff are not presen .ify all the event of an emergency, this group will not if appropriate persons on the duty roster and,necessar :
they will control access to the area in order to ensure the safety ofOne personnel Georgiauntil Techthe Emergency policeman wil]
be Director assignedarrives.
to the Emergency Director at all times during i
d of the Emergency Director with regard to police an fire personnel.
The city police will be D. Atlanta Police Department.in the event of a serious emergency if to provide called traffic control, prevent injury to spectators, and, necessary, evacuate all persons from neighboring areas specified by the Emergency Director.
This group will be called in E.
Atlanta Fire Department. case a fire is discovered which under control immediately. alarm equipped with self-contained and shall use it if requested
' . ' ' by the Emergency 2nter the Reactor Contr D irec to r . No firemrc Zone except at the direction of the Emergency to ex-Director; however, the firemen shall attempttinguis 18.3 Duty Roster their The Georgia Tech Police Department will maintain at headquarters the current duty roster for the emergency staff asIn contained in this paragraph. in has off hours, the Police Department will call persons i been notified.
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EMERGENCY DIRECTOR Phone Campus Home 3620/3719 455-8031
- 1. R.A. Karam 3726 256-3756
- 2. John Kallfelz 3722 874-8610
- 3. G.G. Eichholz 3605 284-2658 .
- 4. R.M. Boyd HEALTH PHYSICS 3605/3621 284-2658
- 1. R.M. Boyd 3605/3621 938-8092
- 2. S.N. Millspaugh 3605/3621 321-6399
- 3. Marcia Gerber EMERGENCY CALL 894-2500 or 2501 GEORGIA TECH POLICE:
588-4307 GRADY MEMORIAL HOSPITAL:
Dr. A.G. Yancey: 588-4261 Dr. J.W. Pinkston 588-4252 18.4 Action in the Event of an Emergency G e ne r a l_.
The action which must be taken to control any ncy A.
emergency will depend on the specific conditions of the emergesta and upon whether or notIn case some hazard will r,t permit qualified lly storedpersons i present.to obtain radiation survey equipment which is normasupplementary near equipment or within the AGN-201 Reactor Control Zone,is always a Any person, who is not a i Headquarters.
School of Nuclear Engineering, discovering an emergency condit on ff shall not subject himself to a hazard but shall notify a staor if the Geor member, if one is present, no staff member is present.
B. Fire on the Premises (1) During working hours (A)
The person discovering the fire shall extinguish the fire if it is minor and he can do so without endangeringIf ra himself or others. In case further action is warranted, the shall be notified.
person discovering the (NOTE: fire shall activate the buildi notified at phone 894-2500/2501. Its sound does NOT notify the signal is an internal alarm only.
Georgia Tech Police Of fice or the Atlanta Fire Department) .
- . . . g (B)
The Emergency Directorifwill assume responsibility necessary, the Atlanta immediately and assure himself that, he will alert other personnel ' '
Fire Department has been notified, He will cause in the Emerson Building as he deems necessary.
parts of the building which he deems to be endangered to be evacuated.
(C)
If the Emergency Director determines that a hazard or any other .
of any type exists, any ventilation system,he shall shut down all affected op equipment, Health Physics shall determine if radiological (D) If so, they will advise tha Emergency hazards are involved.
Director of any precautions which must be taken by the firemen.
They will advise the Emergency Director on methods of combating the fire with a minimum exposure to radiation and contamination hazards and shall recommend the evaculation of specific areas if necessary.
(E)
The Georgia Tech Police Staff and the Atlanta Police shall control vehicular and pedestrian interference bytraf fic in the area unauthorized in such a manner as to prohibit persons.
(F)
In responding to the alarm, the Atlanta Fire Department shall be prepared to use their self-containedif so direct breathing apparatus, They will follow the directions of the Emergency Director with regard to minimizing their exposure to radiological hazards.
(2) After working hours immodiately (A) The person discovering the fire shall call the emergency number 094-2503/2501.
(B)
The Georgia Tech Police shall proceed to the main l entrance of the building, unlock the door, and await the arriva If the fire is outside of the of the Atlanta Fire Department.the Georgia Tech Police staff member will Reactor Control Zone, allow is thewithin firementhetoReactor fight the Control fire usingzone, their normal the procedures. If the fire Georgia Tech Police shall advise the Atlanta firemen that they are prohibited from entering this zone until the Emergency Director has arrived on the premises and determined that undue hazard to Fire Department personnel does not exist.
(C)
Spread of Radioactive Contamination (1) The person discovering any uncontrolled opread of radioactive contamination shall notify the Emergency Director and Health Physics immediately.
- _ _ . . - . . _ . - _._ -. - ~. - - ....- -.- -. - - . _ - _ _ - - -
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(2) Health Physics will assay the situation to ;
i l- determine the degree of hazard and will l inform the Emergency Director. !
(3) The Emergency Director will direct evacua-tion of the building or other action based
! on recommendations by Health Physics. indivi- The l immediate purpose will be to protect f duals and equipment andThe to prevent clean-up theof the :
spread of contaminant. t l area will await the termination of the l immediate emergency and will be accomplished j based on recommendations by Health Physics. ;
- d. Criticality Accident. All personnel, taking care to .
l avoid the source of criticality, will evacuate the building with j all possible haste and reassemble at the Nuclear Research Center. i l
Other Emergency Events. In case of other emergency l
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events, all groups will follow the directions of the Emergency i l
j Director, who will be kept advised of all information regarding i i
f the event.
1 i 18.5 Emergency Medical Assistance CALL: GEORGIA TECH POLICE DEPARTMENT (894-2500) j The primary consideration in an emergency is the prevention of injury and prompt medical assistance to anyone who requires
- i t; the secondary consideration is prevention Personsofdiscovering damage oranyone j salvage of facilities and equipment.
j who needs emergency medical assistance shall, as soon(894-2500) as j
j possible, notify the Georgia Tech Police Police Departmentand Personnel, who have stay in have all the necessary information.
5 been trained to respond to such emergencies, shall proceed at once to the scene of the accident whLle at the same time the i
j police dispatch office shall notify one of the following:
l RADIOLOGICAL SAFETY OFFICER OR THE EMERGENCY ADMINISTRATO i (see Emergency Notification List on Page 3) !
I The desired procedure is for the Police Dispatcher to be in l communication simultaneously with the Radiological In this manner safety'of theficer j l and the police summoned to the emergency. l police officer can be advised on matters of radiological safety as he approaches the~ accident.
i j
If it is determined that a person has been exposed to. high (
[
radiation and materials levels is in and/oremergency is contaminated need of' prompt with radioactive professional medical f assistance the following actlons shall be taken: .!
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--.....,,--,-%,--,%.r,,--c.r-ywy-.. -w.<,-w .-,-c. .m,v , - r w .-r,,ee ce-
wa ,
de$r$Ia*@ecklokiNI$Y"oSk!!I#INapp!op!kNtNYanb' prepared for transport to Grady Hospital.
- 2. The Georgia Tech Police shall call the Grady Hospital resident in charge of the Surgical Emergency Clinic (588-4307) and notify him of the extent of the emergency. They will then take the patient to Grady Hospital and/or follow instructions from the Emergency Clinic Team. They will assist the hospital staff as appropriate for the specific emergency.
- 3. The Police Department will stay in radio and telephone communication with the Radiological Safety Officer or the Emergency Director if he is not already on the scene.
The Grady Hospital Disaster Plan includes provisions for handling emergencies involving radiation and radioactive contamination. It is the responsibility of the Georgia Tech Radiological Safety Officer to keep the campus radiation emergency response program current and all persons concerned properly informed.
- 19. Incidents 19.1 Reporting All incidents or near incidents involving the exposure of personnel to radioactivity, or the uncontrolled spread of radioactive contamination, or the violation of Health Physics procedures, shall be reported to Health Physics immediately.
Health Physics shall determine the extent of follow-up which will be necessary. ,
19.2 Investigation If required by the Emergency Director or the Radiological Safety Officer, the Nuclear Safeguards Committee shall investigate an actual or potential incident in order to determine the cause and take whatev_er action is necessary to prevent a repetition.
19.3 Nuclear Regulatory Commission Notification Under the provisions of 10 CFR, Part 20, Paragraph 20.402 and 20.403, Georgia Tech is required to notify the Nuclear Regulatory Commission within a specified time period of incidents of sufficient magnitude as defined in the regulations Health Physics shol. determine the need for this notification and make the required report as is necessary. The Nuclear Safeguards Committee.shall convene as soon as possible to study the matter.
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y c Compliance with Radiation Safety Procedures P
- 20. P 20.1 Authority d by the All Radiation Safety Procedures are authorized by the President l
Nuclear Safeguards Committee, which is appointeThe Procedur 6 of Georgia Tech.including Standards for Protection Againstd s is 6 Regulations, Compliance by all persons with these proce ureinterpretation sh Radiation. All questions concerning if necessary, the mandatory. to the attention of Health Physics and, brought Nuclear Safeguards Committee.
20.2 Noncompliance mpliance with Health Physics shall continually observe for coWherever these procedures. in observed, Health Physics shall immediatelyCases l
of persons who per correct the condition. noncompliance shall be n.
referred to the Nuc earT Committee for action. access to the Reactor Control Zone to any perso l
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m (Gg Georgia Institute of Technology ENGINEERING EXPERIMENT STATION Atlanta. Georgia 30332 15 May 1984 Dr. R. A. Karam Director, Neely Nuclear Research Center -
Georgia Inst. of Technology Atlanta, Georgia 30332
Dear Dr. Karam:
The Nuclear Safeguards Committee has reviewed your Dismantling and Disposal Plan for the AGN-201 training reactor, License #R-lll, and finds it an acceptable pro-cedure for removing and storing the core and startup source materials. Please advise me if the committee can be of further service toward decommissioning the AGN-201.
rgneerely, i
-0. I Dr. James A. Mahaffey Chairman - Nuclear Safeguards Committee JAM:jd cc: NSC Members GEORGI A TECH IS A UNIT OF THE UNIVERSITV SYSTEM OF GEORGIA AND AN EQU AL EMPLOYMENT / EDUCATION OPPORTUNITY INSTITUTION j i
l