ML19340D928
| ML19340D928 | |
| Person / Time | |
|---|---|
| Site: | 05000131 |
| Issue date: | 05/10/1979 |
| From: | Mullon T DEPT. OF VETERANS AFFAIRS MEDICAL CENTER, OMAHA |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19340D926 | List: |
| References | |
| 636-151C, NUDOCS 8101050589 | |
| Download: ML19340D928 (37) | |
Text
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VETERANS ADMINISTRATION
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OMAHA. NEBRASKA 68105 May 10, 1979
- gad, 636/151C
' Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Co dssion Washington, D. C.
20555 Gentlemen:
It is the purpose of this letter and its enclosures to apply for a renewal of Facility License R-57 issued to the 0=aha Veterans Admin-istration Hospital on June 2,1969.
i The quantity of Special Nuclear Material requested in the license is the " lowest acceptable quantity" necessary to sustain current opera-tions and those projected for the ensuing years. All of the special nuclear material requested is enriched to 20% in the isotope U-235 with the exception of 2 grams that is enriched to 94% and utilized in the fission chamber.
Sincerely,
?
C-T. P. MULLON Director l
Enclosures 1
1 i
After being duly sworn, the person known to me to be T. P. Mullon, Director of the Omaha Veterans Administration Medical Center, Omaha, Nebraska, signed the above document this
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day of May, 1979.
/A' LW) A. $111$
i cmts:3 Notary Publid f,_, In and for said County and State A:L' J T
My commission expires 8-/- [/
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'To care for him who shall have borne the battle, and for his widow, and his orphan. "- AaRAHAM LINCOLN 8101050 M-
P AP)LIC AT ON L
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FOR REsiWAL OF O 3E RATib G LICEN SE NO. R-57 OMA-A VETERAN S ADMLNISTRAT Ob
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ME)lCA CENTER MAY 10,1979 l
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- 1 CHAPTER 4 4
7 BEGENCY PIANNING 4.1 Definitions 20 4.2 Emergency Conditions t
4.2.1 Classification System 20 l
i 4.3 Organizational Control of Emergencies 4.3.1 Facility Emergency Organization 21 4.3.2 Augmentation of Facility Emergency Organiza-tion 23 4.3.3 Coordination with Participating Government Agencies 23 4.4 Emergency Response 24 4.4.1 Activation of Emergency Organi:ation 24
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.n Page 4.5 Assessment Actions 25 4.5.1 Detennnation of Extent of Radiation 25 4.5.2 Documentation and Evaluation 26 4.6 Corrective Actions 26 4.7 Protective Action 27 4.7.1 Evacuation 27 4.7.2. Use of Reactor Facility Protective Equipment and Supplies 27 4.7.3 Contamination Control Measures 27 4.7.4 Aid'to Affected Personnel 28 4.8 Emergency Facilities and Equipment 29 4.8.1 Emergency Control Center 29 4.8.2 Communication Systems 29
.4.8.3 Assessment Facilities 30 4.9 Maintaining Emergency Preparedness 30 4.9.1 Organizational Preparedness 30 4.9.2 Review and Updating of the Plan and Procedures 31 4.10 Maintenance and Inventory of Emergency Equipment and Supplies 31 32 4.11 Recovery Appendix 1 - Plan of Areas 33 Appendix 2 - Copies of Agreement Letters 36 Appendix 3 - Categorical List of Equipment and Supplies 37 Appendix 4 - Written Procedures Implementing Plan 38 39 Appendix 5 - Planning Basis l
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GAPTER 1 GENERAL INFORMATION This part provides the infomation required by 10CFR 50.33 PARAGRAPH (a) NAME OF APPLICANT 1.1 s
Veterans Administration Medical Center 1.2 PARAGRAPH (b) ADDRESS OF APPLICANT 4101 Woolworth Avenue, Onaha, Nebraska 68105 Comunications regarding this applicant should be directed to:
Director, Veterans Administration Medical Center 1.3 PARAGRAPH (c) DESCRIPTION OF BUSINESS OR OCCUPATION OF APPLICANT Medical Research and Education 1.4 PARAGRAPH (d) 1.4.1 (d)(1) Not applicable 1.4.2 (d) (2) Not applicable 1.4.3 (d) (3) n e applicant is unincorporated 1.4.3.1 Omaha, Nebraska is the location of this Medical Center 1.4.3.2 he applicant represents the administrat'or of the Veterans Admin-istration, Mr. Max Cleland, Brough the Chief Medical Director, Dr. J. C. Cnitcher with Mr. T. P. Millon as Director of the Omaha VA Medical Center. Mr. Mullon is responsible to the Chief Medical Director.
1.4.3.3 The applicant is not owned, operated, or controlled by an alien, foreign corporation, or foreign government.
1.4.4 (d) (4) he applicant (Mr. T. P. Millon) is acting as an agent for the Administrator, Veterans Administration through the Chief Medical Director.
1.5 PARAGRAPH (e) 1.5.1 Class of license applied for 1.5.1.1 Renewal of Class 104 1.5.1.2 Renewal of Special Nuclear Material License to receive, possess and use up to 2.210 kilograms of contained uranium -235 for use in connection with operation of the reactor. _.
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1.5.1.3 Renewal of license under 10CFR Part 30 to receive, possess, and use up to 8 curies of sealed polonium-beryllium neutron sources (U.S. Nuclear Corp. Type 383) and a 2 curie sealed Americum-berry 111um neutron source (NUMEC-AM-t.2 Type I), either of which may be used for reactor startup; and to possess, but not to separate, such byproduct material as may be produced by operation of the reactor.
1.5.2 Use to which the facility will be put:
Production and utili::ation facility for the conduct of research, development and educational activities.
1.5.3 NRC Licenses issued for use at the Medical Center Complex.
1.5.3.1
~ Byproduct License #26-00138-10, and Facility License R-57.
1.5.4 Period of time for which the renewal license is sought - 10 years.
1.6 PARAGRAPH (f) 1.6.1 Since the Veterans Administration Medical Center is part of the Veterans Administration it operates on an annual allocation of funds governed by the Office of Management and Budget; therefore, a financial report is not deemed applicable.
1.6.2 Funds will be available to operate the facility.
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O CHAPTER 2 FILING OF APPLICATION This part provides the information required by 10 CFR 50.30 (e)S(f) which is as follows:
2.1 PARAGRAPH (e) FILING 1-r2 - exempt 2.2 ENVIRONMEVTAL REPC]
On the basis of the hb11er/Skovhold Memo dated 1/28/74 it was determined by the NRC that an Environmental Impact Statement is not required for research reactors authorized to operate at
.2MN(t) and less. However, according to 10 CRF 51.7 an Environ-mental Impact Appraisal is necessary and sufficient information is provided below to support and develop the EIA.
2.2.1 Facility 2.2.1.1 There are no exterior conduits, pipelines or transmission lines attached to or adjacent to the facility other than utility service facilities which are similar to those required in other hospital facilities, specifically laboratories.
2.2.1.2 Heat dissipation is accomplished by the use of an air cooled condenser located on the hospital grounds adjacent to the reactor room and is comparable to air cooled condensers associated with air-conditioning systems of office buildings.
The reactor is cooled by natural convection of the pool water.
A 5-ton freon vapor-compression chiller with an air-cooled condenser is used as the heat sink. Water from the reactor tank is pumped in a closed circuit to the water monitor, where the temperatare, gamma activity, and conductivity of the water is measured. It then goes to the suction end of a pump and from there to the chiller unit. From the chiller unit it goes through a filter and then through a demineral-
)
izer. A bypass line is provided from the outlet of the chiller to the inlet of a rotometer where flow rate is measured. The water is then returned to the reactor tank. Make un for the cooling system is readily available from the hospital deionized water system.
l 41 l
2.2.1.3 Radioactive gaseous effluents are limited to Ar. Experiments have shown that in the rotary specimen rggk an equilibrium concentration of 0.54 uci/cm3 of 109-min 1A is established after the reactor has been operated at 18KW for several hours.
41A content is cal-Under these conditions, the equilibrium culated to be 18 mci in the rotary speci en rack and 0.29 mci in the pneumatic transfer tube. After A has been purged from the cavities, it would take several hours to re-establish an equilibrium concentration. The transfer of argon from the rotary specimen rack to the reactor room is inhibited by the
l long, slender access tube. In an exreriment performed with the University of Illinois' 100-kw Liga Mark II reactor, air from the pneumatic tube and the roatry specimen rack was dis-charged into the reactor room and the argon-41 concentration in the room was found to be well below 2 x 10-6uci/cm, which 3
is the maximum permissiable concentration (MPC) for restricted areas. The experiment consisted of operating the reactor at 100 m for several hours, discharging the air from the pneumatic tube into the reactor room, and lowering and raising a sample container in the access tube to pull out some of the air from ten different positions of the rotary specimen rack. A scintil-lation crystal placed at the height of the top of the reactor, between the reactor and the building exhaust, detected no in-crease of radiation exhaust over background in the region 1 to 1.5MeV.
Sensitivity was checked with a cobalt-60 source, which gave a counting rate of 10 times the background for a 2
flux of 8 gammas / cm -sec. According to this calibration, thggammafluxduetoargon-41releasewaslessthan8 gammas /
Converting this surface source of activity to an cm -sec.
equivalent volume source indicates that argon-41 concentration in the reactor room was less than 0.3% of MPC and for operation at 18 W it would be.05% of MPC.
In summary, the argon-41 produced in the reactor cavities is not considered hazardous to the operating personnel. Leakage of air from these cavities into the reactor room is so small that the argon-41 activity would not be detectable at 100 m operation even when some of the air is deliberately discharged into the room.
41 The A activity in the reactor pool water results from irradia-tion of the air dissolved in the water. Calculations by General gon State University and other Triga Licensees show Atomic, OgA decays while in the water, and most(gf the radiat that the is safely absorbed in the E ter. General Atomic 4 has calcu-A from pool water of the 250 KW New lated that the release of York University Mark I Triga, whose p1 dimensions are similar to the Omaha VA Triga, is 0.42 x 10- uc/cc. Using the room volume and room air exhaust rate o# the Omaha VA reactor instal-lation i.e. rgom volume - 7.3 x 10$ cm3 and room exhaust rate of 6 cm /see the activity concentration would be 3.94 x 3
2.34 x 10 10-8 uc/cc for 250 KW operation. Since maximum licensed power for the Omaha VA facility is 18 KW, the argon-41 released from the reactor pool would be well below the MPC for both restricted and unrestricted areas.
2.2.1.4 All liquid wastes are collected in storage containers to allow for decay and monitoring prior to dilution and release to the sanitary sewer system.
(1) General Atomic GA-9864 Safeguard Summary Report for the New York University Triga Mark I Reactor 5-3. -
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2.2.1.5 Solid radioactive wastes are held for decay or packaged and shipped off site for storage at NRC approved sites. The trans-portation of such waste will be done in accordance with existing NRC-DUT regulations in approved shipping containers. However, since 1959 this has not been necessary.
2.2.1.6 he chemical and sanitary waste systems are those of a hospital.
2.2.2 Emrironmental Effects of Site Precaration and Facility Construction Not applicable.
2.2.3 Environmental Effects of Facility Ooeration 2.2.3.1 Release of thermal effluents from the reactor will not have a significant effect on the enviroi1 ment since the small amount of heat is rejected to the atmorphere by a 5 ton air cooled condenser similar to that used to cool a house.
41A which is 2.2.3.2 Release of routine gaseous effluents is limited to generated by neutron activation of air. The 2.34 x 106 cm3/sec reactor room exhaust fan will assure that dilution is adeouate to keep the yearly doses of unrestricted areas at or below established limits.
2.2.3.3 Routine releases of radioactive liquid effluents will be care-fully monitored and controlled in a manner that will assure compliance with current standards. H e only radioactive effluents are those resulting from neutron activation experiments, as the pool water is recirculating and never leaves the system. Monitor-ing of the pool water shows only the presence of small quantities of 15 hour1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> sodium-24 2.2.3.4 Solid radioactive wastes are stored for decay. If it becomes necessary to ship them te an authori::ed disposal site, it will be done in approved containers. This has not been necessary since the reactor was installed in 1959.
2.2.3.5 The annual radioactive release to unrestricted areas has been as follows:
a) Gaseous - <0.03 curies b) Liquid none 2.2.3.6 No release of potentially harmful chemical su'ustances will occur.
2.2.3.7 ne potential effects of the facility are negligible since it has existed since 1959 with no adverse coments.
2.2.4 Environmental Effects of Accidents Accidents ranging from failure of experiments up to the largest core damage and fission product release considered possible have been treated in the FSAR and will result in doses of only a small fraction of 10 CFR 100 guidelines. They will be considered negligible'with respect to the environment.
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f CHAPTER 4 BIERGENU PIANNING This part provides the infomation reouired by Section IV of Appendix E to 10 CFR 50, 4.1 DEFINITIONS - 2ere are no tems that are unique to the facility and hence definitions are not necessary.
4.2 BtERGENCY CONDITIONS 4.2.1 Classification System 4.2.1.1 Personnel Emergency - h is class involves accidents or occurrences onsite that have no potential for escalation to more severe emergency conditions. There may be no effect on the reactor, and immediate operator action to alter reactor status is not neces-sarily required. A Personnel Emergency would not be expected to activate the entire emergency organization but may require special local services such as medical help. The plan is divided into two alternative procAures: The first, Course of Action I, to be taken if there are two or less not grossly contaminated radiation victims and the second, Course of Action II, if more than two accident victims or grossly contaminated victims are involved.
4.2.1.2.
Emergency Alert - This class involves specific situations that can 'oe recognized as creating a hazard potential that was pre-viously nonexistent or latent. The situation has not yet caused damage to the reactor or harm to personnel but warrants an im-mediate shut down of the reactor if it is in an operating mode.
Inherently, this is a situation in which time is available to take percautionary and constructive steps to prevent an accident and to mitigate the consequences should it occur. Examples of situations that should be placed in this class are:
l a.
breaches of security b.
bomb threats c.
civil disturbance d.
flood e.
tornado f.
nearby fire g.
release of a toxic or noxious gas in or near the reactor area.
4.2.1.3 Reactor Emergency - This class includes physical occurrences within the racility requiring emergency organization response.
The initial assessment leading to this class should indicate that it is unlikely that an offsite hazard will be created.
The reactor should be scrammed if it has not already taken place by the actions of the automatic protective systems. Although this class is associated with a judgement that the emergency situation can be corrected and controlled by the onsite staff,,-
notification thru the normal reporting mechanisms of an an-propriate offsite agency to alert it as to the nature and possible extent of the incident should be a measure associated with this class. Protective evacuation or isolation of certain areas may be necessary. Examples of situations that might fall into this class are:
a.
fire in the reactor area b.
minor exolosion such as failure of an experiment under pressure c.
loss of cooling water 4.2.1.3.1 Action Levels should be based on the recognition of an immediate need to implement in-house emergency measures to protect or pro-vide aid to affected persons or to mitigate the consecuence of damage to equipment, coupled with a positive observation that radiological monitors do not indicate the possibility of a more serious emergency.
4.3 ORGANI~ATIONAL CONTROL OF BtERGENCIES Listed below are the authority and responsibilities of key individuals for each class of emergency. Personnel will be alerted by the hospital switchboard operator by hospital page or telephone.
4.3.1 Facility Emergency Organi::ation 4.3.1.1 Personnel Emergency 4.3.1.1.1 Course of Action I a.
Radiation Safety Officer or his designee Designated to take charge of emergency control measures.
b.
Reactor Operator on duty Responsible for taking the necessary steps with the reactor, c.
Chief, Nuclear Medicine Service.
Medical Officer in charge of medical treatment of victims if needed.
d.
Chief of Security Responsible for maintaining security around designated area if needed, Line of succession in absence of Radiation Safety Officer e.
Chief, Nuclear Medicine Service Chief Nuclear Medicine Technologist Chief, Radiology Service -
e 4.3.1.1.2 Course of Action II a.
Radiation Safety Officer or his designee Designated to take charge of emergency control measures.
b.
- Inspital Director Overall responsibility for all occurrences within the hospital.
c.
Chief, Nuclear Medicine Medical Officer in charge of medical treatment of victims.
d.
Chief, Security Responsible for maintaining security around designated area.
e.
Nursing Supervisor Responsible for all nursing assistance required.
f.
Chief, Building Management Responsible for seeing that reouired clean up material is available, g.
Chief, Engineering Service Responsible for giving engineering assistance if required.
h.
Line of succession in the absence of Radiation Safety Officer or his designee.
Chief, Nuclear Medicine Service Chief Nuclear Medicine Technologist Chief, Radiology Service 4.3.1.2.
Emergency Alert a.
Reactor Supervisor Has overall responsibility for all emergency control measures.
b.
Reactor Operator Responsibility for taking necessary action when he is operating reactor.
c.
Chief, Security l
Responsible for providing additional security if deemed necessary.
l d.
Line of succession in the absence of Reactor Supervisor l
Reactor Operator l
4.3.1.3 Reactor Emergency l
a.
Reactor Supervisor
[
Has overall responsibility for all emergency control measures.
b.
Reactor Operator i
Responsible for taking necessary action when he is operating reactor.
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c.
Radiation Safety Officer Responsible for the radiation safety of tle facility and assuring that all actions are in compliance with 10 CFR 20.
d.
Hospital Director Has overall responsibility for all occrnences within the hospital. Upon advice of the Reactor Supervisor will be responsible for notifying NRC and local and state emergency groups.
e.
Chief, Nuclear Medicine Medical Officar in charge of any accident victims, f.
Chief of Security Responsible for maintaining security around designated areas.
g.
Nursing Supervisor Responsible for all nursing assistance required.
h.
Chief, Building Mangement Responsible for seeing that the reouired clean up material is available,
- i. Chief, Engineering Service Responsible for giving engineering assistance (plumbing, heating, ventilation, electrical, mechanical, carpentry) if required.
J.
Li.ne of succession in absence of Reactor Supervisor Senior Reactor Operator Chief, Nuclear Medicine 4.3.2 Augmenution of Facility Emergency Organi::ation a.
Ambulance Not necessary since reactor is in hospital.
b.
Hospital Not necessary since reactor is in hospital.
c.
Medical Medical and nursing treatment will be handled by the staff of the VA Medical Center on the premises.
d.
Fire fighting Supplied by Omaha Fire Department on call.
4.3.3 Coordination with Particinating Government Agencies.
4.3.3.1 State Nebraska Civil Defence Agency By authority of the Governor of the State of Nebraska the agency,
is responsible for state level planning of radiological re-lease incidents within th" e of Nebraska with the excep-tion of those occurring cn
- ral Property such as the VA Medical Center. The agency w uld be involved with any release of radiation outside of the VA Medical Center grounds.
Nebraska State Health Department Division of Radiological Health By authority of the Nebraska State Legislature and by agreement with the U. S. Nuclear Regulatory Commission, the Divirion is responsible for the Evaluation of Radiological Health Hazards.
4.3.3.2 Local Omaha Police Department Responsitie for enforcing police action and supplying bomb squad at the reouest of the Medical Center Director.
Omaha Fire Department Responsible for fire protection of the facility 4.3.3.3 Federal Federal Bureau of Investigation Responsible for assisting in case of threat or theft,upon request of the Medical Center Director.
4.4 EMERGENCY RESPONSE 4.4.1 Activation of Emergency Organization 4.4.1.1 Personnel Emergency - Ccurse of Action I and II a.
Radiation Safety Officer Notified by nearest person to the emergency by means of the telephone or hospital page, b.
Other personnel Notified by Radiation Safety Officer by telephone or hospital page.
c.
Offsite agencies Emergency does not warrant notification.
4.4.1.2 Emergency Alert a.
Reactor Supervisor Notified by the Medical Center Director to whom all threats or weather alerts are referred. Notification will be by telephone or page.
b.
Other personnel Notified by Reactor Supervisor.
c.
Offsite Agencies Federal Bureau of Investigaticn and Omaha Police Department.
Notified simultaneously by Medical Center Directcc in case of threat.
Chaha Fire Department Notified by automatic alam in case of fire or smoke.
4.4.1.3 Reactor Emergency a.
Reactor Supervisor Notified by the Reactor Operator or by the hospital switch-board operator in the case of a loss of cooling water alarm. Notification will be by telephone or page.
4 b.
Other Medical Center Personnel Notified by Reactor Supervisor c.
Offsite Agencies The fo11cwing agencies together with the action level for each will be notified by the Medical Center Director.
Omaha Fire Department if fire or smoke is noticed in the Reactor Area.
Nebraska Civil Defense Agency if there is any possibility of a radiation release from the facility Nebraska State Health Department, Divisien of Radiological Health if there is any possibility of a radiation release from the facility.
Nuclear Regulatory Comission if the incident is reportable under 10 CFR 20.403.
ASSESSME. T ACTIONS V
4.5 4.5.1 Detemination of Extent of Radiation The methods and techniques utili::ed to detemine the extent of any radiation release or contamination can be divided into two phases, non airborn and airbone.
a.
Non airbom Exposure in the reactor laboratory will be indicated by a calibrated non jamung area monitor with an audible alam set at 2 MR/hr. Calibrated survey meters will then be used to accurately assay the exposure.
Film badges have been supplied all perscnnel and have also been positioned at strategic spots within the facility and at the exit boundry of the ventilation fan. l
Direct and indirect pocket dosimeters are also available.
b.
Airborn A calibrated recording constant air monitor is in 24-hour operation in the Reactor Laboratory. Coupled to the monitor is a chqtgoal filter which is capable of allowing measurement of the '-)1I released.
A portable air sampler is also available for sampling any radiation released to an unrestricted area.
4.5.2 Documentation and Evaluation A recording secretary will be appointed by the Radiation Safety Officer to record the radiation readings obtained so that the Radiation Safety Officer can readily determine the radiation ha:ards and define areas where radiation and/or contamination levels exceed permissable amounts.
The Radiation Safety Officer is then responsible for estimating the projected exposure to persons within or beyond the facility boundaries and determining what emergency action levels have been exceeded.
4.6 CCRRECTIVE ACTIONS The following corrective action will be taken in order to lessen any danger from an emergency involving the nuclear reactor.
a.
Fire inside or outside the reactor area.
Scram the reactor and shut off ventilation fan.
b.
Reactor Excursion Scram the reactor and shut off ventilation fan, c.
Removal of an unexpected, highly readioactive sample from the reactor.
Lower sample back into the reactor. Scram the reactor if at the decision of the reactor operator a hazard exists.
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d.
hiinor explosion such as failure of an experiment under pressure.
l Shut off ventilation fan. Scram reactor if explosion occurred in reactor, e.
Break in cooling water piping.
Scram reactor.
Repair pipe leak.
Confine water.
Add additional deionized water, f.
Ioss of Coolant Water Make sure reactor is shut down. Replace water with deioni:ed i
water or in emergency, water frcm the fire hose in reactor room.
g.
Bomb threat in Civil disorder Scram reactor.
Lock hatches with locking bars.
4.7 PROTECTIVE ACTION 4.7.1 Evacuation a.
Personnel will be evacuated from the contaminated area if the reactor operator or the Radiation Safety Officer estimates that personnel arc in danger of receiving more than the levels indicated in 10 CFR 20.
b.
Evacuation will be accomplished by actuating an alam by means of the switch on the reactor console. This alam can be actuated either for the basement reactor facility or both the basement and the first floor above the reactor.
4.7.2 Use of Reactor Facility Protective Ecuipment and Supplies The issuance of the following special protective equipment for persons reentering the contaminated area may be necessary.
Scott Air Pak Protective Clothing Protective shoe covers Protective gloves Protective head covering 4.7.3 Contamination Control Measures a.
Isolation or quarantine and area access If the Radiation Safety Officer, the Reactor Supervisor or the Reactor Operator feels that personnel in a radiation area are in danger of receiving greater than 250 mrem he will sound the evacuation alarm and imediately evacuate all personnel, including himself, from the area.
Control boundaries with guards will be established at the head of the staiIvay leading down to the south doorway of l
Reactor Area and at the north entrance to the Reactor Area.
If the first floor clinic rooms have to be evacuated a guard will also be placed at the entrance to Room 166.
b.
Criteria for permitting return to normal use.
Reentry into the contaminated area will not be attempted by anyone until a complete assessment of the existing ha::ard has been made by the Radiation Safety Officer and the Senior Reactor Operator.
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Access to hazardous areas will be restricted and the areas posted with appropriate signs.
Areas will not be returned to nomal use until the removable surface contamination is equal to or less 3 and fixed contamination Icss than than 10-0 pei/cm 5 mrem / hour.
4.7.4 Aid to Affected Personnel 4.7.4.1 Emergency Personnel Exposure The following exposure guidelines are established.
Entry or reentry in order to remove injured person.
a.
hhole body exposure will be limited to 300 mrem per individual.
If the situation requires greater personnel exposure a maximum of 25 Rem may be authorized by the Chief, Nuclear Medicine Service or the radiation Safety Officer if the Chief, Nuclear Medicine Service or his designee is not available, b.
Entry or reentIy in order to take corrective action, hhole body exposure will be limited to 300 mrem per individual.
If the situation requires greater personnel exposure a maxinn of 25 Rem may be authorized by the Chief, Nuclear Medicine or the Radiation Safety Officer if the Chief, Nuclear Medicine Service or his designee is not avail-able.
Emergency personnel providing first aid, decontamination, c.
ambulance or medical treatment service to injured persons.
hhole body exposure will generally be limited to 300 mrem per individual.
If lifesaving activities are involved, however, the Chief, Nuclear Medicine er Radiation Safety Officer may authorize key personnel to receive up to 25 Rem of whole body dose.
d.
Implementation of emergency personnel exposures.
Prior to allowing any emergency exposure the Radiation Safety Officer will make an imnediate estimate of the exposure personnel will receive and these values will be recorded.
The Radiation Safety Officer together with the Chief, Nuclear Medicine, who serves as the Medical Officer, will determine the stay time of all individuals. Factors governing these decisiens will include an evaluation of risk versus benefit.
All personnel who expose themselves to radiation for emer-gency purposes, both emergency personnel and volunteers, will be appraised of the time they may stay in the area, the radiation exposure they may be expected to receive, and the possible consequences of the exposure.
4.7.4.2 Decontamination and First Aid Room R118 in the adjacent Research Building has been designated as the decontamination room. This room has a large stainless steel sink with capabilities of disconnecting the sink drain so that it can drain into carboys for storage. An operating room is also available across the hall if necessary. Both rooms are in a building separate from the general hospital so the problem of contaninating the hospital does not exist.
Since the facility is located within the Medical Center, all personnel treating the victims will be physicians or nurses.
Security officers have been instructed that if alerted they will seal off the area between the reactor and room R118 al-lowing only necessarv personnel to enter. Personnel will not be allowed togo outside of the contaminated area until they have received radiation safety clearance which will include the monitoring of their hands, feet and clothing.
f 4.7.4.3 Medical Transportation Not necessary since facility is in Medical Center.
4.7.4.4 Medical Treatment All medical treatment will be done at the Omaha VA Medical Center therefore no agreement with outside hospitals is necessary.
Evaluation of radiation exposure and uptake will be done by the Chief, Nuclear Medicine and the Radiation Safety Officer.
4.8 EMERGENCY FACILITIES AND EOUIPMENT 4.8.1 Emergency Control Center - Not applicable.
4.8.2.
Communication Systems a.
Hospital Audio Page System l
Speakers strategically placed throughout the hosuital and Research Building - controlled by switchboard operators..
b.
Hospital pocket page system All physicians, key nurses, radiation safety officer, key adninistration personnel, and key engineering personnel have pocket page. Operated through any telephone in the Stedical Center. Has range of greater than 15 miles.
c.
Telephone 4.8.3.
Assessment Facilities 4.8.3.1 Portable and fixed radiological monitors a.
Geiger-hhller survey meter 0-100 mR/hr.
b.
Geiger->blier survey meter 0.1 mR/h - 100 R/hr.
c.
Ion chamber survey meter 0-300 rR/hr.
d.
Ion chamber survey meter 0-0.1 Kr/hr e.
Gas Proportional Alpha Counter 0-100K cpm 4.S.3.2 Sampling equipment a.
Constant air monitor with fixed filter and iodine cartridge 0-50K cpm b.
Staplex Air Monitor 3
c.
Tritium air Monitor - ion chamber 0-100,000 pci/m d.
In line G1 uter mcnitor in reactor console.
4.8.3.3 Instrumentation for specific radionuclide identification and
- analysis, a.
ND 2400 1024 channel analyzer with 2 each 3" x3" NaI crystals.
b.
ND 600 2048 channel analy er with 80 cm3 Ge(Li) detector, c.
PC-11T Proportional Counter.
d.
Liquid Scintillation Counter.
e.
Single Channel Analyzer System.
4.8.3.4 Fire Detection Device a.
Smoke alam in basement of hospital 4.9 MAINTAINING BtERGENCY PREPAREDNESS 4.9.1
_ Organizational Preparedness 4.9.1.1 Training Emergency personnel will be trained in the following:
a.
Effects of radiation, initial and latent.
b.
Safe handling of radioisotopes including time, distance and shielding.
c.
Manner by which contamination can occur. -- -.
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Response to emergency ala ms.
e.
Role in an emergency.
f.
How to use a Scott Air Pak.
g.
Methods of decontamination.
h.
Methods of reading radiation meters and recording results
- i. How to make an area survey.
4.9.1.2 Drills Emergency test exercises or drills will be held at the follow-ing frequencies and contain the following elements:
a.
Biennial An exercise using a scenerio apprcpriate to a serious emergency accident. Each exercise will centain provisions for contacting outside agencies for coordination with off-site personnel. The exercise will test at a minmum the ccmunication links and notification procedure.
b.
Annually An ensite drill using usirg a scenerio appropriate to test firefighting contamination control measures and evacuatien.
A criticue will be held after each exercise or drill and will include an evaluation of observer coments about the implementation or corrective action that should be.taken.
4.9.2 Review and Uedating of the Plan and Procedures
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4.9.2.1 Review A biennial review of the emergency plan will be done by the Reactor Safeguards Comittee.
4.9.2.2 Updating The Reactor Supervisor will be responsible for improving pro-cedures and incorporating changes suggested as a result of drills or exercises and accounting for changes in the facility or the environs.
4.9.2.3 Comunication Copies of all revisions will be circulated to all elements of the emergency organi:ation either by inter-hospital mail or U. S. mail.
4.10 MAINTANENCE AND IhVENTCRY OF BtERGENCY EQUIPMENT AhB SUPPLIES Supplies in the emergency cart will be sealed by means of seal-ing wires in such a way that the cart cannot be cpened without breaking the wires. A physical inventory of the cart supplies will be taken annually. -_
Fr.ergency survey and sampling instnments will be calibrated annually but checked monthly with a reference source.
4.11 RECCVERY After radiatien safety clearance to enter the contaminated area has been obtained from the Radiatien Safety Officer, the area will be entered by personnel wearing protective clothing as prescribed bv the Radiation Safety Officer. If stay times have been established they will be strictly adhered to and monitored by semeene outside of the contaminated area.
Appropriate cleaning vehicles will be used for decontaminating the area. All waste, cleaning rags, etc. will be stored for radiation monitoring and disposition by the Radiation Safety Officer.
Decontamnation will be complete when removable. surface cen-3 tamination is equal to or less than 10-0 uci/cm and fixed centamination less than 5 mrem /hr.
Upon completion of their services, decontamination personnel will remove protective clothing and pass through monitored centrol points before entering clean areas and donning personal clothing.
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APPENDIX 2 Copies of agreement letters Ncne negotiated.
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APPENDIX 3 Categorical list of equipment and supplies stored and main-tained for emergency use.
Radiation Signs and Tags Applicable Handbooks and Regulations Log Books Tape - Radiation and Masking Plastic gloves and sheeting Rubber gloves Absorbant paper Acid suits Plastic head coverings and boots Radiac Wash Hard hat with light Plashlights Radiation survey meters Batteries Pocket dosimeters Scott Air Pak Tools Plastic bags Stop watch
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APPENDIX 4 Written Procedures Implementing Plan Radioactive contamination accident - course of action I Radioac:ive contamination accident - course of action II Fire cutside of reactor area Fire within reactor area Reactor excursion Reactor console alann during off-duty hours Removal of unexpected, highly radioactive sample from the reactor Loss of cooling water Bomb threat and civil disorders i
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.W APPENDIX 3 Planning Basis This information has previously been submitted and can be found on pages 44-53 of the " Application for Construction Permit and Utili::ation Facility License" submitted March 24, 1959. Decket 50-131.
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