ML20148T505
| ML20148T505 | |
| Person / Time | |
|---|---|
| Site: | 05000356, University of Illinois |
| Issue date: | 06/30/1997 |
| From: | Holm R ILLINOIS, UNIV. OF, URBANA, IL |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20148T507 | List: |
| References | |
| NUDOCS 9707090183 | |
| Download: ML20148T505 (37) | |
Text
{{#Wiki_filter:. Radiation Sci ^nc7 Laboratory Univ:rsity of lilinois at Urbana-champaan [ j" n Department of Nuclear Engineering / College of EnginMring
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Administrator Rohard L. Holm r-holm@uluc edu Heg!!h Physicist Mark Kac,zor m-kaczor@utuc edu S==:) June 30,1997 Docket No. 50-151 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station Pl-137 Washington, DC 20555
Dear Sir,
Please fmd enclosed a copy of the Emergency Plan for the Nuclear Reactor Laboratory at the University ofIllinois in Urbana, Illinois. I am submitting this plan in accordance with 10 CFR 50.54(q). No. changes were made that decrease the effectiveness of the plan. The three attachments to this letter are as follows
- A memo from the Emergency Coordinator outlining the changes made to the Plan.
- A draft revision with revision bars showing the changes that were made.
- A fmal version with the changes incorporated and the revision bars removed.
If there are any questions concerning the Energency Plan please do not hesitate to contact me. Sincerely,
/-
Richard L. IIolm ,j Reactor Administrator [k c: file Q(f USNRC, Region til I' Mr. Alexander Adams, Jr, USNRC, NRR 9707090183 970630 kk!!kf!!!!
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I i t c , Radiation Science Laboratorv i University of Illinois at Urbana-champaign 1 Department of Nuclear Engineering / College of Engineering l 1 214 Nuclear Engineering Laboratory 217-333-77550866 . I h 103 South Goodwin Avenue 217-244-5916 fax , l p-* 2 _, Urbana,IL 618o1-2984 *
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Administrator Health Physicist
- Richard L. Holm Mark Kaczor , e r-hokn@uluc.edu m-kaczor@uiuc ah To: Rich L. Holm l Emergency Director and Reactor Administrator Fmm: Mark A. Kaczor i Emergency Coordinator and Reactor Health Physicist ,
Date: May 22,1997 (Item # 8. added on 6/2797). l l
Subject:
Summary of Changes to the Emergency Plan in Revision 1, May 1997. l I have completed the first biennial review and update of the new Emergency Plan, Revision 0, dated March 1995, and accepted by ! the NRC by letter dated, September 26,1995. This review resulted in the changes listed below and is designated Revision 1, May ! 1997: !
- 1. Incorporated all comments received to date on Revision 0. l
- 2. Incorporated all " Lessons Learned" from the 1995 Emergency Drill and the 1996 Emergency Exercise as outlined in the Critiques for these events. .i
- 3. Incorporated format changes to the Emergency Action Levels (EALs) and Emergency Classification System as suggested in the l April 1997 " ERRATA" referencing "NUREG-0849" received from the NRC Office of Resources Management on May 5,1997. l
- 4. Updated the Agreement with the Offsite Support Agency, Champaign County Emergency Senices and Disaster Agency ;
(ESDA). j
- 5. As a result of 2) and 4) above, changed the notification of the " Senior University Police or Fire OfIicer On Duty" as the 1 indhidual authorized to place a call to Champaign County ESDA to the " Reactor Operator / Acting Emergency Director or the l
Emergency Director" as the individuals authorized to place a call to 9-911 and request that the Champaign County Emergency Senices and Disaster Agency (ESDA) activate Onsite coordination with local hospitals and suppon agencies. l
- 6. . Removed Equipment Inventory Lists for equipment we had no control over that belonged to other campus organizations, This '
did not change the minimum equipment required to be operable at all times to maintain Emergency Preparedness, located in the Emergency Equipment Locker in Room 106B NEL. l
- 7. Made minor grammatical and document format changes as appropriate.
- 8. As a result of Reactor Committee Review on 6/23/97 the Carle Clinic Association," Radiation Accident Program" was removed from Attachment 5 to the Emergency Plan. This document is controlled by Carle Clinic and provides guidance to hospital personnel. Since it gives no instruction to our own Emergency Plan Members it was removed and placed in the Emergency Preparedness files where it can be reviewed by interested panies.
Thank you for your time and consideration of this matter. MAK/mak pc: Reactor Committee and Head, D. Miller E. Wiener B. Jones Department of Nuclear Engineering D. Hang D. Scherer i as noted to the right: B. Heuser R. Holm (eplan\rvsumS97, doc) I
Draft Revision for Review ~ i i i EMERGENCY PLAN
! for the i
i NUCLEAR REACTOR LABORATORY j i at the i UNIVERSITY OF ILLINOIS in i j URBANA, ILLINOIS l 4 l Facility I.ivenses flo. R-115; R-117 j Dock :t Nas. ',0-151; 50-356 i 4 i 1 1
) Revision 01 . March-1495 May 1997 1
Page 1 of 29
, .-. . .- - . - . - . . - - . - . _ . = . - .- . - _. . ..
TABLE OF CONTENTS - for this Revision Markup Section Page Number L i Table +f-Contents 2-3 Preface 4 1.0 Introduction 5 1.1 Description of the Reactors 5 l 12 Location of the Reactor Facility 5 [ 1.3 Identification of Owner / Operator 5' ! 1.4 Objective of the Emergency Plan 5 2.0 Definitions 5 3.0 Organization and Responsibilities 7
..._311imergency_ Response O_rganization f ERO) 8
_3 l.1. EmergenprDirector_(ED) 8 3 1.2_ Emergency.Coonlinator (EC.) 9 3, l .3_ Reactor Operator (RO) 9 ! 3.1.4 Emergency Radiation Protection ManagerIFRPM) 9 3.1.5 Emergency Medical, Security, Fire, and Plant Services Manager _(EPSM) 9 3.1.6 Emergency Public Information Manager _(EPIM) 10 j 3.1.7 University Office of Public Affairs 10
- 3. l .8 Senior-University-Policeer-Fire-Officer-On-Duty Police. I ire. and Medical 10 Assistance l 3.1.9 Radiation Safety Oflice (RSO) 10 ;
3.2 Coordination and Notification of Federal, State, and Local Govenunental Agencies 10 l 3.2.1 Nuclear Regulatory Conunission (NRC) andAmerican Nuclear Insurers _(ANI) 11 l 3.2.2 Champaign County Emergency Services and Disaster Agency (ESDA) I1 3.2.3 University ofIllinois Police and Fire Depanments 1i l 3.2.4 University Division of Environmental Ilealth & Safety (Dell &S) 12 l 3.3 Termination of an Emergency 12 3.4 Authorization for Reentry 12 3.5 Authorization fbr Planned Special Exposures 12 t 4.0 Emergency Action Levels (EALs) and Emergency Classification System 12 4.1 Non Reactor Safety Related Events (NRSRE) 12 l 4.2 Notification of Unusual Events (NOUE) 13 4.3 Alert 14 4.4 Site Area Emergency 15
' 4.5 General Emergency 15 4.6 Emergency Action Levels (EALs) for Members of the General Public Onsite 15 t i 5.0 Emergency Planning Zones (EPZs) 15 6.0 Emergency Response 15
, 6.1 Activation of the Emergency Response Organization (ERO) 15 . 6.2 Protective Action Vahies 16 6.3 Emergency Response for a Non-Reactor Safety Related Event (NRSRE) 16 Page 2 of 29 l
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'6.3.1 Activation of Emergency Organization for a NRSRE
- 16
!- 6.3.2 Assessment Actions for a 1 M 16 6.3.3 Corrective Actions for a NRSRE 17 6.3.4 Protective Actions for a NRSRE 18 6.4 Emergency Response for a Notification of Unusual Event (NOUE) 18 l 6.4.1 Activation of Emergency Organization for a NOUE 18 , 6.4.2 Assessment Actions for a NOUE 18 ! 6.4.3 Corrective Actions for a NOUE 19 l 6.4.4 Protective Actions for a NOUE 20 l 6.5 Emergency Response for an Alert 20 , 6.5.1 Activation of the Emergency Organization for an Alen 20 6.5.2 Assessment Actions for an Alert 21 l 6.5.3 Conective Actions for an Alen 21 6.5.4 Protective Actions for an Alert 22 6.6 Site Area Emergency 22 7.0 Emergency Facilities and Equipment 22 1 7.1 Emergency Suppon Centers 22 7.2 Assessment Facilities 23 7.3 First Aid, Medical, and Decontamination Facilities 23 7.4 Communications Equipment 24 8.0 Reentry and Recovery Operations 24 9.0 Maintainhg Emergency Preparedness 24 9.1 Training 24 9.2 Conduct of Drills an,d Exercises 25 9.3 Critiques of Drills and Exercises 25 l 9.4 Drill;uld Exercise. Scenarios 25 9.5 Emergency Plan Review and Update 25 9.6 Emergency Equipment Maintenance and Surveillance 26 9.6.1 Inventory of Equipment and Supplies 26 9.6.2 Radiation Monitoring Equipment Calibration 28 9.7 Emergency Plan Implementing Procedures (EPIPs) List 28 10.0 Attachments N/A
- 1) Champaign-Urbana Area Map. N/A i
- 2) Nuclear Reactor Lab Immediate Area Map. N/A -
- 3) Diagram of Reactor Building showing: site boundary, location of the reactors, and associated equipment. N/A
- 4) Block Diagram of Emergency Response Organization (ERO). N/A
- 5) Written Agreements with local support organizations. N/A Page 3 of 29
PREFACE Planning for possible emergencies at the Nuclear Reactor Laboratory (NRL) was staned with the publication of the llazards Analysis in October,1959. This report contained written procedures to be followed in the_ case of.a sudden or threatening increase in radiation levelsgere to occur-After the+ tan-up After the conunencement of operations in 1960, these procedures were incoq) orated into the ," Rules and Regulations for the Operations of the NRL". Because of extensive changes in 1968-69, a new Utilization License was required. Appendix A of this License," Technical Specifications for the Illinois Advanced TRIGA Reactor", required written procedures for emergency conditions involving potential or actual release of radioactivity, including provisions for evacuation, re-entry, recovery, and medical support. Criteria for re-entry and recovery were added to the Rules and Regulations ". Medical suppon was provided by a decontamination room at McKinley llospital. Appendix E of 10 CFR 50 was added on December 31,1970. This required Emergency Plans for all nuclear reactors. Following the guidelines that were available, a Radiation Emergency Plan for NRL was reviewed and approved by the Nuclear Reactor Committee on April 12,1973. This Plan was then reviewed by personnel from l the OfIice ofInspection and Enforcement of the Nuclear Regulatory Commission (NRC) and was found to be adequate. For a number of years, most of the attention for approved Emergency Plans was directed toward Nuclear Power Reactors. On November 2,1982, a Radiation Emergency Plan was submitted to the Director of the Office of Nuclear Reactor Regulation as required by 10 CFR 50.54(r). The Plan followed the outline of the ," Standard for Emergency Planning for Research Reactors"(ANSI /ANS 15.16), and was basically the original Plan with sections added to address areas that wew not previously covered. On March 20,1984, a notice was received that the Plan was inadequate in certain areas. The areas were listed with the notice. The deficient items were covered in a letter that was sent on July 9,1984. A letter was received from the NRC on November 16,1984, stating that the Emergency Plan was acceptable. The Plan was fully implemented on March 16,1985, and accepted by the NRC on September 17,1985. The Emergency Plan then implemented, was a combination of the items sent on November 1982 and A.ly 1984. l When completed,it was reviewed and approved by the Nuclear Reactor Committee. Copies were then submitted to th NRC to replace the earlier documents. This plan remained relatively unchanged from 1985 until this revision; with the exception of annual reviews that included minor modifications such as; changes to names, telephone numbers, a relocation of the decontamination center, and a relocation of the assembly area. A letter dated April 12,1994, from the Emergency Preparedness Branch , Division of Radiation Safety and Safeguards of the NRC stated that the revisions submitted on March 3,1994, were acceptable in accordance with 10 CFR 50.54(q). Ilowever, the letter included some suggestions for improvements to the plan that would ensure that it more closely followed the guidance in NRC Regulatory Guide 2.6, ANSI /ANS 15.16-1982, and NUREG-0849. These documents were reviewed and compared to the existing plan and as a result this a major l revision to the scope and content of the plan was completed as " Revision 0". The major thrust of the changes were to more completely follow the guidance given in the aforementioned documents, correct deficiencies noted in the April 12 letter from the NRC, and to replace the " Group Concept" of the Emergency Organization in the previous plan with "the normal hierarchy where one individual is given responsibility with a line of succession" This revision was wilWe reviewed and approved by the Reactor Committee and submitted to the NRC on in March 111995. The NRC accepted theylan in a letter datedlentember 26.1995. - l Page 4 of 29 i 1
1*0 INTRODUCflON 1.1 Qtsenilion of the Reacto s: The Illinois Advanced TRIGA and LOPRA reactors utilize fuel produced by General Atomics. He , authorized maximum steady state power levels are 1.5 MW for the TRIGA reactor and 10 kW for the LOPRA reactor. He TRIGA is used for education, training operators, the production of radioactive isotopes, and research. The I.OPRA is coupled to the TRIGA through a thennal column. Although the LOPRA was originally built to study coupling effects, the only present use is for eciucation and training. t 1.2 Location ofthe Reactor Facility J The reactors are housed in a concrete block building near the Northeast end of the University ofIllinois Campus in Urbana-Champaign. The actuallocation is 200 feet East of Goodwin Avenue between Green i Street and Springfield Avenue. A semi-alley way called Western Avenue dead ends at the facility. Two maps are included to show access and locations of the reactor building and alternate emergency centers. One is a ; partial map of Champaigi-Urbana showing access from Interstate 'l to the reactor and the location of Carle i Medical Center (Attachment 1). The second map shows the immediate area and gives access routes to the j reactor and the altemate sites that would be used as emergency centers (Attachment 2). A third map is ; included as a diagram of the reactor building shmving the site boundary, the location of the reactors witlun the building, and associated equipment locations (Attachment 3). 1,3 Identification of the Owner / Operator: l i Both reactors are owned by the University ofIllinois Board of'Imstees and operated by the Nuclear [ Engineering Department in the College of Engineering. i 1.4 Obiective of the Emergency Plan. , i i The Emergency Plan contains provisions for a graded response to possible tmplanned adverse radiological conditions both within and beyond the facility boundaries. The content follows the guidelines of ANSI /ANS l i 15.16-1982 " Emergency Planning for Research Reactors", NRC Regulatory Guide 2.6, and NUREG-0849. Since the postulated radioactive releases from credible accidents at this facility falls in the first category,
" Authorized Pmver Level... Equal to or less than 2 MW", in the Section 3.6, Table 2 Guidelines of ANSI /ANS 15.16-1982," Alternate Method For Detennining %e Size of an EPZ", (Emergency Planning Zone) the EPZ for this plan is established at the Operations (Site) Iloundary and the Emergency }
Classification " General Emergency"is not used. -t I 2.0 DEFINITIONS l s Confinement System: is defined at the Reactor Building Walls and is designed to confine and maintain control of 3 i the dispersal of radioactive material in the gaseous, particulate, and liquid states. Controlled Area: is that area, outside the restricted area but inside the site boundary, access to which is limited by l the licensee for any reason. It is defined 4he+aneenhe-ereas4eferred4o+elow-as4he-Operations andeite f Boundaries-IFis+ontrolledfor-tlelmrposeofeecurity controlled at the NRL for the purpose of %curity and is l identical to the Operations and Site Boundaries as defined below. l 1 Emegeney:c is a condition that calls for immediate action, beyond the scope of nonnal operating procedures, to l avoid an accident or to mitigate the consequences of one. ; Page 5 of 29 l
t l l . Emergency Action Levels (EALs): are specific instrument readings or observations; radiological dose or dose rates; specific contamination levels of airbome, waterbome, or surface-deposited radioactive material; that may be used as thresholds for establishing emergency classes and initiating emergency measures. E.mergency Classes: are classes of accidents grouped by severity level for which predetermined emergency measmes should be taken or considered. e gency Plan: is a document that provides the basis for actions to cope with an emergency. It outlines the objectives to be met by the emergency procedures and defines the authority and responsibilities to achieve such objectives. Emergency Planning Zone (EPZj: is an area for which offsite emergency planning is performed to assure that prompt and effective actions can be taken to protect the public in the event of an accident. The EPZ for this plan is the Operations (Site) Botmdary and is defined by the Reactor Building Walls (Confinement). I Emergency Plan Implementation Procedures (EPIPs): are documented instructions that detail the implementation l actions and methods required to achieve the objectives of the Emergency Plan and are contained as a distinct group ofprocedures as an appendix to this plan. Emergency Support Centers (ESCs): is an4rea are areas designated for assembly after an evacuation. The l purpose of these facilities is to provide: a control center; an accountability station; and a radiological monitoring area for frisking ofpersonnel and evaluation of radiological samples. LOPRA Reactor: Low Power Reactor Assembly; which refers to the smaller of the two reactors located onsite j that utilizes General Atomics designed TRIGA Type Fuel Elements and has a maximum steady state power l ratmg of 10 kW. l l N. uclear Reactor Laboratory (NRL_): is defined in the introduction to this plan. i Offsite: is the geographical area outside the walls (the confinement) of the Reactor Lab and is not controlled by i the operator of the lab, the Nuclear Engineering Depaitment. l l l Onsite: is the geographical area inside the walls (the confinement) of the Reactor Lab and is under the control of
)
the operator of the lab, the Nuclear Engmeenng Department. 1 4 l l Op.erations Boundary: is the area where the Reactor Administrator (Emergency Director) has direct authority over all activities. This is defined by the Reactor Building Walls (Confinement) and the area within this boundary l l has prearranged evacuation procedures known to people fiequenting the area. This area is also referred to as the i Site Boundary. l Protective Action Guides (PAGs): are projected radiological dose or dose commitment valucs to individuals that i warrant protective action following a release of radioactive material. Protective actions would be warranted i provided the reduction in individual dose expected to be achieved by carrying out the protective action is not offset by excessive risks to individual safety in taking the protective action. The projected dose does not include j
- the dose that has unavoidably occurred prior to the assessment. '
Reactor Staff: are those individuals with assigned duties at the Reactor Lab who have both Security and Restricted Area Access. They are trained to respond to breaches of 3ecurity and have the appropriate level of 1 Page 6 of 29 l l
= l ddiologital training to have unescorted access to, and escon individuals into, the restricted area. They also have , an assigned position in this plan.
I Research Reactor: is a device designed to suppon a self-sustaining neutron chain reaction for research. l developmental, educational, training, or experimental purposes, and which may have provisions fm production of l non-fissile radioisotopes. 1 Restricted Area: is that area, access to which is limited by the licensee, for the purpose of protecting indisiduals l against undue risk from exposure to radiation and radioactive material. This area is clearly posted within the reactor building and the boundaries are known by all members of the Reactor Staff. Site Ilmmdary: is the area where the Reactor Administrator (Emergency Directoa has direct authority over all , , activities. This is defined by the Reactor fluilding Walls (Confinement) and the area within this boundary has l l prearranged evacuation procedures known to peopic fiequenting the area. This area is also refened to as the l Operations lloundary. This area may also be fiequented by people unacquainted with reactor operations; such as ! ! Visitors and Tour Groups; however, these individuals are always under the direct supersisien and control of a l member of the Reactor Stafl.
]
1 Shall, Shouldm andliay: the word "shall"is used to denote a requirement; the word "shoul f' to denote a l recommendation; and the word "may" to denote pennission, neither a requirement nor a re commendation. I i l TRIGA Reactor: Training, Research, Isotope pProduction, General Atomics;is the acronym used to refer to the main and larger of the two reactors at the NRL with a maximum steady state power rating of L5 MW.. l 3.0 ORGANIZATION AND RESPONSillILITIES The Nuclear Reactor Laboratory (NRL)is a facility of the Nuclear Engineering Department, through which it l receives primary ftmding for staff and equipment, and is operated under license from the NRC. The Reactor l l Administrator, a licensed Senior Reactor Operator (SRO), is directly responsible for all act i vities conducted at the NRL including, but not limited to: Iluilding Security, Special Nuclear Material (SNM) Custodian, the : Emergency Plan, and Supervision of the Reactor Staff. The Reactor Administrator is responsible,in a line of authority to the llead of the Department of Nuclear Engineering, who is responsible to the Dean of the College of Engineering. The Reactor Administrator shall be designated as the Emergency Director in the Emergency Plan. The Reactor Administrator shall be responsible to infonn the individuals designated in the Emergency , Organization on their pan in the overall plan. lie shall keep these individuals infonned regarding changes to their roles in the Emergency Organization and changes to the Emergency Plan. The Reactor llealth Physicist is responsible for radiological controls at the NRL and shall be designated as the Emergency Coordinator and the Emergency Radiation Protection Manager in the Emergency Plan. The Reactor llealth Physicist is responsible for ensuring that the radiation monitoring and supplementary equipment required for an emergency is available as opecified in the Emergency Plan. The Reactor Operating Staff consists ofindividuals who have a current SRO m Reactor Operator (RO) License and shall be responsible to take immediate action that may be necessary to respond to a potential emergency and/or to activate the Emergency Plan. Other Reactor Staff members shall be assigned roles in the Emergency Plan commensurate with their training and experience. The Reactor Committee is a pennanent standing committee of the Depanment of Nuclear Engineering and reports directly to the Department llead Their responsibilities include: review of reactor operation, experiments, changes to operations procedures, and to review and approve the Emergency Plan in accordance with the facility Technical Specifications and 10 CFR 50. Page 7 of 24 l
3.1 Emergency Response Organization (ERO) The ERO shall consist of an Emergency Director and Emergency Staff acting under the authority of the Emergency Director as outlined in this Plan and the Emergency Plan Implementing Procedures (EPIPs) The positions in the ERO shall be filled by Reactor Staff personnel and augmented, as necessary, by staff from the Radiation Safety OfIice MSO) in the Division of Environmental llealth & Safety (Dell &S), and the Nuclear Engineering Department. Onsite and Offsite organizations may be required to assist the ERO for emergency event response. This assistance may include the University Police for security matters, trallic control and limited building evacuation; the University Fire Depanment for firefighting, emergency medical trauma response, and/or rescue; the University OfIice of Public Affairs for media contact; and the Champaign County Emergency Services and Disaster Agency (ESDA) for outside assistance with police, fire and medical facilities. A Block Diagram outlining the reponing responsibilities, lines of authority, and line of succession to the Emergency Director is included as Attachment 4. Written agreements for those organizations that would be available to the ERO staff are included as Attachment 5. More complete details on the ERO's organization and responsibilities may be found in EPIP-01. 3.1.1 Emergency Director (ED) The Reactor Administrator is the Emergency Director. The ED has ultimate authority over Onsite activities and personnel. The ED is in charge of classifying an emergency based on Emergency Action Levels (EALs) or events and directing the activation of the Emergency Plan as detailed in EPIP-08. The details of the ED's responsibilities may be fotmd in EPIP-04. The authority and responsibility of this position includes:
*a) classification of an emergency, upgrading and downgrading; b) initiating response and activation of the Emergency Response Organization (ERO);
c) ensuring the reactors are shutdown, and terminating or minimizing releases ofradioactive material; d) protecting facility personnel and visitors; c) exchange ofinformation with authorities responsible for offsite emergency measures and summoning assistance as necessary;
- f) protective action decisions;
*g) authorizing radiation exposures in accordance with NRC Ryulatory Guide 8.35 " Planned Special Exposures";
h) declaring the termination of an emergency and diiecting iesimation, i) providing for a final repon on the emergency with revisions to the Emergency Plan if necessary, including informing the ERO ofplanned organizational actions or changes.
- Indicates authorities and responsibilities which may not be delegated by the ED.
Other personnel, listed below, are also assigned to the position of ED (as alternates) with the same responsibilities and authorities described above. This assures the immediate availability of an individual to respond if the Emergency Director is not available. Line of Succession to ED: Reactor IIealth Physicist Operations Supersisor Senior Reacter Operator Campus Radiation Safety Oflicer Page 8 of 29
.. _- - ~ . . _ _ _ _ __ .. ~
3/1.2 Emergency CoordinatorjiCJ i l- , The Recctor Heilth Physicist is the Emergency Coordinator. The EC is responsible for the overall coordination of the Emergency Plan as detailed in EPIP-05. These responsibilities include: , l t l- a) developing and maintaining the Emergency Plan and Implementing Procedures (EPIPs); , I l b) advising the Reactor Administrator on the selection and training ofindividuals assigned to key , emergency plan positions; c) providing training and exercises for facility personnel and outside agencies; d) procuring equipment and supplies required by the Emergency Plan; e) providing a critique of drills or exercises for the purpose ofupdating the plan; l f) conducting the biennial review of the plan; ! g) coordinating plans with other applicable organizations. l t Line of Succession to EC: Operations Supervisor i Senior Reactor Operator { 3.1.3 Reactor Operator (RO / SRO) , The Reactor Operator is responsible for the shutdown and securing of the reactors in emergency i situations which occur during reactor operation. The operator shallinform the Duty SRO of the observed action levels and shall take immediate action in case ofpossible reactor damage or tmcontrolled radioactivity release. The operator shall refer to EPIP-02, " Reactor Operator Immediate Action Procedures" and EPIP-03, " Nuclear Reactor Lab Emergency Call List - Intrusion / Emergency" for guidance and for details on other responsibilities. i 3.1.4 Emergency Radiation Protection Manager (ERPM) i The Reactor IIcalth Physicist is the Emergency Radiation Protection Manager. The ERPM is responsible for the initial assessment of actual or potential radiological hazards onsite and offsite. This ; responsibility includes; onsite and offsite dose assessments, recommended protective actions, and all i radiation protection services within the provisions of the Emergency Plan. The ERPM is also the Emergency Director until the ED arrives. The details of the ERPM's responsibilities may be found in EPIP-06. Other mdividuals that may act as ERPM if the primary ERPM is not available are- f Line of Succession to ERPM: Reactor 11eahh Physicist Assistant [ Campus Radiation Safety Oflicer (RSO) l' Radiation Safety Office Health Physicist 3.1.5 Emergency Plant Services Manager (EPSM): Medical, Security, and Fire. ! I The Duw Senior Reactor Operator (SRO)is the EPSM and is responsible for obtaining first aid, i police, and fire-fighting assistance from the Senior University Police Oflicer or the Senior University Fire l Oflicer On Duty as warranted by the situation. The EPSM is responsible for assessment of actual or l potential security aspects of all radiation emergencies and shall provide advice and consultation to the ED l on all matters relating to security and traflic control upon activation of the Emergency "lan. In addition, the SRO is responsible for advising the ED on Plant Senices and Equipment and for ot aining needed ! equipment from the University Operations and Maintenance Department. The details of the EPSM's Page 9 of 29
. 1 rdsponsibilities may be found in EPIP-07. Other individuals that may act as EPSM if the primary EPSM
. is not available are: Line of Succession to EPSM: Any SRO Reactor llealth Physicist Safety Specialist from Dell &S I 3.1.6 linnergency r Public Information Manager (EPIM) The Ilead, Department of Nuclear Engineering is the EPIM. The EPIM shall provide information, as discretion dictates, to the University Office of Public Affaim. when such information is provided by the Emergency Director. The EPIM shall act as primary spokesperson for the Emergency Director. The EPIM shall review all press releases written by the University Office of Public Affairs. In the absence of the duly appointed EPIM, the following individuals shall act as temporary EPIM: Alternaie_s to EPIM: Assistant Head, Depanmer.t of Nuclear Engineering Director, Division of Environmental llealth & Safety 3.1.7 University Ollice of Public Afliiirs The University OfEce of Public Affairs will handle all ofUcial news releases conceming emergency conditions at the Nuclear Reactor Lab. The Reactor Administrator shall be responsible for the technical content ofinfonnation prepared for release by the Office of Public Affairs. 3.1.8 Senior-Universityfolice-orfire-Offeer-On-Duty Police. FireJmd Medical Assistance l The Senior University-Police +r-Fire-OfEcer-On-Duty Reactor Operator / Acting Emergency Director or the Emergency Director (ED) shall be authorized to place a call to 9-911 and request that the Champaign County Emergency Services and Disaster Agency (ESDA) activate Onsite coordination with local hospitals and suppon hospital agencies. These calls should be regarded as being properly sanctioned by l the University. Police and Fire senices are available at all times. The University Police may be called to provide security assistance, emergency radio communications, traffic and crowd control; as necessary. The University Fire Depanment may be called to fight a fire, provide emergency medical assistance or rescue senices. Both the Police and Fire Departments are instructed, on a biennial basis, on the special aspects of the NRL including building seemity and fires involving potential radiation exposure or areas with radioactive material present. shall be authorized to place a call to activate Onsite coordination with local hospitals and suppua agencies. 3.1.9 Radiation Safety Office (RSO) The RSO is te Section within the Division of Environmental lleal ht & Safety responsible for Radiation Safety on the Campus outside the confines of the NRL Professional and Technical llealth Physics staff from the RSO are e.,ilable to assist in the event of an emergency at the NRL. The Director of the Radiation Safety Oflic , k also the Campus Radiation Safety Officer and shall be notified in the event of an emergency at the N %. 3.2 Coordination and Notification of Federal. State. and Local Governmental Agencies The postulated credible accidents associated with the operation of the Nuclear Reactor Laboratory will not result in a radiological hazard affecting the General Public. He credible emergency events will not require the direct involvement of Federal, State, and Local Governmental Agencies; however, these agencies shall be notified as specified in Sections 3.2.1,3.2.2,3.2.3, and 3.2.4 below. The contents ofinitial and follow-up Page 10 of 29 i i i
l emergency messages; to the extent the infonnation is known, and dependent upon the agency being notified; ! - should include some or all of the following: a) Name, title, and telephone number of the caller; ! b)'Ihe location of the incident and the emergency class; c) A description of the emergency event; d)'the date and time of the incident initiation; e) The type and quantity ofradionuclides released or expected to be released. f) Projected or ac?uel dose rates outside the operations (site) boundary. g) Ask the recipient of the message to place a return telephone call to authenticate the message. 3.2.1 Nucl_ ear Regulatory Commission _(NRC) and American Nuclear Insurer 1(ANI) The NRC Region lli Ollice ofInspection and Enfbrcement is located at Lisle, Illinois. Assistance from this oirice would be in accordance with the provisions of the license,10 CFR 20, and commensurate with the seriousness of the emergency. Notification of the Ileadquarters Operations Center at the telephone and , facsimile numbers noted below will result in Region 111 being notified in the event of an emergency, therefore, l a separate call to Region 111 is not required. l Locntion Telephone Number Availability _ NRC Operations Center Voice: 1-301-816-5100 24 hours / day l Voice backup : 1-301-951 0550 24 hours / day i Facsimile: 1-301-816-5151 24 hours / day l l NRC Region Ill Voice: 1-708-829-9500 24 hours / day American Nuclear Insurers (ANI) Voi.ce 1- 860-561-3433 24 hours /rigy , Fac.si.milent-860-56_l-4655 24 liours/dal American-Nuclear-Insurers 2-Voice-1--203-561-3433 ?
?24-hours / day I
3.2.2 Champaign County Eme_tgency Sersices and Disaster AgencyLESDA_) ESDA has overall responsibility for providing coordination oflocal police, fire, rescue, and medical response for large scale disasters and emergencies. The Senior UniversityPolice-or-FireOfIicer-On Duty Reactor _ Operator / Actingjimergency_ Director or the Emergep_cy Director $;D) shall be authorized to place a call to l 9-911 and request that the Champaign County Emergency Services and Disaster Agency (ESDA) activate j l Onsite coordination with local hositals and suppon hospital agencies. These calls should be regarded as being properly sanctioned by the University. 3.2.3 University ofIllinois Police and Fire Departments The University Police and Fire Depanments shall provide immediate response to a security event or fire within or without the Reactor Building and near environs. The Emergency Director (EDL or_an individual such as the Duty a Senior Reactor Operator (SRO) acting as the ED or at the direction of the ED, shall be authorized to request assistance from the University-Police-and Fire Depanmentscr-to-notifythem ofe potential emergency et-theWRidfhe-Senior-UniversityPolice or-Fire-Oflicer-On-Duty + hall be the only individuals authorized to-place a-call to4he Champaign Gmmty-EmergenerServices emi Disaster-Agency l Page 11 of 29
,. . . . . ~ --. - - . . . - - . - - .. - - * (ES17A)when the-need- ChampaigtLCounty ESDA. ESDA will notiTy the University Police and Fire l-Repartments. as well as other appropiar cuppon agencies,_of_a_ potential emergency at the NRL arises-and-request-th:t-ESDA-activcte ' -Onsite-coordination *ith4helocal hospitals.-Theseells+hould4>e :'
regarded-es being properly sanctimi y the-University: 3.2.4 University _ Division of Envi,onmental llealth & Safety (Dell &S) The Director of the Radiation Safety Office is also the Campus Radiation Safety OfIicer and shall be notified in the event of an emergency at the NRL. 3.3 'Lermination of an Emergency 1 The Emergency Director (ED)is responsible for declaring the termination of an emergency. Prior to , termination of an emergency the ED shall conclude that no foreseeable subsequent events could cause the ; action limits of the emergency to be exceeded. The ED shall verify that all areas to be reopened to personnel ; or to the General Public meet the requirements of 10 CFR 20 and all areas to be restricted for entry or which l require controlled access are properly posted. l 3.4 Authorization for Reentry The Emergency Director (ED) shall authorize any reentry into the NRL, or portions thereof, previously ; evacuated during an emergency, in accordance with the guidelines established in EPIP-10, " Reentry and , Recovery Procedures" I i 3.5 Authorization for Planned Special Exposures ; With the concurrence of the llead of the Depanment of Nuclear Engineering and after consultation with the ) Emergency Radiation Protection Manager, the Emergency Director may authorize Planned Special l Exposures for emergency team members. The criteria used to establish exposure limits for this authorization shall be in accordance with NRC Regulatory Guide 8.35 " Planned Special Exposures. 4.0 EMERGENCY ACTION I EVELS (EALs) AND EMERGENCY CIASSIFICATION SYSTEM The Emergency Action Levels (EALs) and Emergency Classes described below for the Nuclear Reactor Laboratory are based on credible accidents associated with reactor operation and other non-reactor safety related events that have minimal, if any, radiological consequences. More specific guidance on any of the topics listed in i Section 4.0 can be found in EPIP-08, " Emergency Action Levels (EALs) and Emergency Classification Procedures" 4.1 Non-Reactor Safety Related Event (NRSR_F_) This class ofemergency consists of an event that does not endanger the General Public. Notification of or assistance from the University Police and Fire Departments may be warranted. The following Emergency Action Levels _IEALs) or events shallinitiate emergency measures associated with this Emergency Class: a) Significant personnel injury with or without radiological complications. l b) Minor fire or explosion not specific to the reactors. l c) Significant contamination of an individual or of the facihty. j d) Civil distuibances or receipt of a bomb threat that is not specific to the Nuclear Reactor Lab. l Page 12 of 29
- More' specific guidance on this topic can be fotmd in EPIP-08," Emergency Action 1 evels (EALs) and Emergency Classification Procedures" l
l 4.2 Notification of Unusual Event (NOUE) This class of emergency consists of an event that may be initiated by eithen man-made or natural phenomena that can be recognized as creating a significant hazard potential that was previously nonexistent. There is usually time available to take precautionary and corrective steps to prevent escalation of an accident or to l mitigate the consequences should it occur. No releases of radioactive material requiring offsite response are expected. Some elements of the Emergency Organization may be activated or notified to increase the state of readiness, as warranted by the circumstances. Although the situation may not have caused damage to the reactors, the reactors shall be shutdown. The following Emergency Action LevelslEALs) or events shallinitiate emergency measures associated with this Emergency Class: a) Actual or proiected radiological ellluents at the siteloperations) boundary calculated to produce a whole bodploseof4& mrem 1]eep Dose Equivalent (DDE) of 15 mrem (0.15 mSv) accumulated within 24 hours. j i The following guideline shall be used to calculate this-projected 41ose a Committed Effective Dose Equivalent (CEDli): 50 *-EC
- 24-hours *45-mRendfor-noble-gases) 400 +-EC
- 24 hours *4&mRemifor-nuclidesother4han-nobletases) 100
- EC
- 24 hours = 2.4 E' EC-hr = 15 mrem (0.15 mSv) for radionuclides other than nohle_ gas _es e 50
- EC
- 24 hours = 1.2 E' EC-hr = 15 mrem f 0.15 mSv) for noble gases l Note: EC = EfIluent Concentration values listed in 10 CFR 20, Appendix I}, Table 2.
1 This can be determined by observingthe e fbilowing radiation levels on the facilityladiological momtors: ii) Area Radiation Monitors (ARMS) > 20 mR/htfbr the West and LobJyy and Reactor Top ARMS for more than 10 minutes with the reactor shutdown and ne other sources of radiation pregnt and; iii) Continuous Air Monitors (CAMS): Mezzanine nnd Reactor Top CAMS > 2000_ cpm above background and Exhaust Stack Monitor > 380 eps Note: Iffhe East ARM is creater than 20 mR/hr. this is an Alen. Proceed to section 4.3. b)Jiepon or observation of severe natural phermmena. such as tornadoes in the immediate sicinity of the Nuclear Reactor Lab. or earthquakes felt in the facility. c) Receipt of a bomb threat specific to the Nuclear Reactor Lab or a bomb discovered in or near the facility with potential radiological release implications. d) Fire or explosion within the facility that cannot be controlled immediately with an onsite CO 2 extinguisher and requiring the assistance of the University Fire Department for control. e) Failure of a fuel element or failure of an experiment with a release of radioactivity. Page 13 of 29
Mon! specific guidance on this topic can be ibund in EPIP-08, " Emergency Action Les els (EALs) and - Emergency Classification Procedures" 4.3 Alert This class of emergency consists of' events that would be of such radiological significance as to require notification of the Emergency Response Organization (ERO) and their response as appiopiiate for the specific emergency situation. Under this class it is unlikely that offsite response or monitoring would be necessary. Substantial modification of reactor operating status is a highly probable corrective action. Protective evacuations or isolation of certain areas within the operations (site) boundary may be necessary. Situations that may lead to this class include: 1) severe failure of fuel cladding or of fueled experiments where containment boundaries exist to reduce releases or less severe cladding failures in situations where fission products are not well contained, or 2) significant release of radioactive material as a result of experiment failures. The following Emergency Action LevelsEALs) or events shallinitiate emergency measures associated with this Emergency Class: a) Actual or projected radiological efUuents at the siteloperations) boundary calculated to produce a whole body-doseef-75-mrem Deeg Dose _ Equivalent (DDE) of 75 mrem (0.75 mSv) accumulated within 24 hours. ij The following guideline shall be used to calculate a Conuuitted Effectise Dose Equivalent (CEDIi); this projected 41oset 250 +-EC '24-hours *-7& mrem {for-noble ~ gases) 500A-EG *-24hoursa-7& mrem {for-nuclides+ther-thanmobletases) 4 500
- EC
- 24 hours ,1.2 E EC-hr = 75 mrem (0.75 mSv) for radionuclides other than noble cases 250
- EC
- 24 hours = 6.0 E' EC-br = 75 mReml0.75 mSv) for noble gases Note: EC = EfUuent Concentration values listed in 10 CFR 20, Appendix IL Table 2. l This_can_be_ determined by oltselving the_finlowingradiation levels on the facility radiolocical monitors:
i.i). Area Radiation Monitors.(ARMS) > 100 mR/hr fbr the West and Lobby and Reactor Top ARMS fbr more than 10 minutes with the reactor shutdonu and no other sources of radiation present and; iii)_ Continuous Air Monitors (CAMS): Mezzanine and Reactor Top CAMS > 10,000 epm above background and Exhaust Stack Monitor > 999 cas. b) Actual or projected radiation levels at the site (operations) boundary of 20 mRenrhr for4 hour-whole body ((L2 mSv/hr) Deep Dose Equivalent (DDElfor 1 hour, based on East Wall Area Radiation Monitor (ARM); or 100 mrem projected thyroid-dose:(1.0 mSv) Committed Dose Equivalent _(C_DElto the thyroid. g) Severe failure of fuel cladding, as indicated bnthe Demitieralizer ARM alarming 3vith an indication M0 mR/hr and_cor1Ermed by_indigations in Sections 7.2 a}_ii) & iii) above;_or failure of fiieled experiments where containment boundaries exist to reduce releases or less severe cladding failures in situations where fission products _are_not well contained. d) Significant releases of radioactive material as a result of experiment failures. Page 14 of 29
)
^
e) Loss 01 physical control of the facility. More specific guidance on this topic can be found in EPilW8," Emergency Action Levels (EALs) and Emergency Classification Procedures" 4.4 Site Area finlege: Ley No credible accidents attributable to the reactor or its operation are postulated which could cause emergency I conditions beyond the operations (site) boundary. Chapter XIV of the Safety Analysis Repo 1 (SAR) analyzed a number of accidents, including the release of radioactive eflluents to the environment. The analysis of a fuel cladding failure with complete loss of coolant, and the ventilation system off, indicate that an 1 emergency of this class would never occur. Ilowever, an emergency condition where the Emergency Response Organization (ERO) may consider setting up traflic control or the evacuation of adjacent buildings may require limited entry into the provisions of this classification, ! More specific guidance on this topic can be found in EPIP-08, " Emergency Action Levels (EALs) and Emergency Classification Procedures" l 4.5 deneral Emergency (Not Applicable) i i I No credible accidents attributable to the reactor or its operation are postulated which could cause emergency conditions beyond the operations (site) boundary. Chapter XIV of the Safety Analysis Report (SAR) , analyzed a number of accidents including the release of radioactive efIluents to the environment. The analysis ! of a fuel cladding failure with complete loss of coolant, and the ventilation system off, indicate that an emergency of this class would never occur. Therefore, this emergency class is not addressed in this plan. i 1 4.6 Emergency Action Levels (EALs) for Members of the General Public Onsite Before exposure levels equal to or exceeding the Protective Action Guides (PAGs) of bRem-whole body and 5-Rem: 1 RemIl0 mSv) Total Effective Dose Equivalent f_fEDE) or 5 Rem (50 mSv) Committed Dose j liquivalent LCDE) to the thyroid, within the operations (site) boundary;; have been reached members of the general public shall have been evacuated from the building. 5.0 EMERGENCY PLANNING ZONES (EPZs) j Since the postulated radioactive releases from credible accidents at this facility fiills in the first category, j
" Authorized Power Level... Equal to or less than 2 MW", in the Section 3.6, Table 2 Guidelines of ANSI /ANS 15.16-1982, ' Altemate Method For Determining The Size of an EPZ" and Appendix 11 of NUREG-0849, the EPZ for this plan is established at the Operations (Site) Boundary and is defined by the Reactor Building Walls (Confinement).
l 6.0 EMERGENCY RESPONSE 6.1 Activation of the Emergency Response Organization [ERO) The Emergency Director (ED)is responsible for initiating the Emergency Plan and for notifying and mobilizing the ERO. During periods of time when the NRL facility is unattended and an unusual situation (lights on at night, alarm signal, etc.)is detected by the University Police or reported to the University Dispatcher, a member of the NRL Staffis contacted by telephone or beeper. A copy of the Emergency Call Page 15 of 29
- List is kept by the Police Dispatcher and telephone numbers are visible through the front window of the lab cntrance. The Dispatcher is on duty around the clock thus ensuring that an NRL Staff member on the list can be notified of an unusual situation. The NRL Staffmember notified shall resolve the situation and determine whether a real emergency condition exists. If the potential for an emergency condition exists the NRL Staff l member shall notify the Emergency Director (ED) and take charge of the potential emergency until the ED l anives. The ED shall give instmetions on steps to be taken prior to the anival of the ED at the Nuclear l Reactor Lab and detennine if additional notifications are warranted.
1 More specific guidance on this topic can be found in EPIP-03," Nuclear Reactor Lab Emergency Call List - Intmsion / Emergency" and EPIP-08, " Emergency Action i evels (EALs) and Einergency Classification Procedures" 6.2 Protective Action Values No credible accidents attributable to the reactor or its operation are postulated which could cause emergency conditions beyond the operations (site) botmdary. Chapter XIV of the Safety Analysis Repoit (SAR) analyzed a number of accidents including the release of radioactive efiluents to the environment. The analysis of a fuel cladding failure with complete loss of coolant, and the ventilation system off, indicate that the Protective Action Guides (PAGs) of 1 Rem whole-body (10 njSv) Total Effective Dose Eouivalent (TEDE) or 5 Rem (_50 mSv) Committ_cd Dose _F_quivalent (CDElto the thyroid for members of the public offsite could not be reached. As stated in Section 4.6 above, "Before exposure levels equal to or cxceeding the Protective Action Guides (PAGs) of-1-Remwhole-body-and4-Rem;I Rem (10 mSv) Total Effecti.ve Dose Equivalent (TEDE) or 5 Rem (50 mSv) Committed Dose Equivalent (CDE) to the thyroid, within the operations (site) boundary,; have been reached members of the general _public shall have been evacuated from the building" Exposures of Emergency Personnel would be expected to be within the limits of 10 CFR 20, however, Chapter XIV of the Safety Analysis Report (SAR) indicates that, under the worst case scenario, thyroid doses within the operations (site) boundary could be limiting. The ED has the authority to authorize Planne<l Special Exposures as described in Section 3.5 above,"With the concurrence of the Ilead of the Depanment of Nuclear Engineering and after consultation with the Emergency Radiation Protection Manager, the Emergency Director may authorize Planned Special Exposures fbr emergency team members. The criteria used to establish exposure limits fbr this authorization shall be in accordance with NRC Repu!atory Guide 8.35 " Planned Special Exposures" 6.3 Emergency Response for a Non-Reactor Safety Related Event (NRSRE.) l 6.3.1 Activation of the Emergency _ Organization for_a NRSilE The complete activation of the emergency organization for this emergency class would not normally be regned. Ihe Emergency Director (ED) shall activate that portion of the emergency organization necessary to respond to the event. 6.3.2 Assessment Actions for a NRSRE This class of emergency consists of events that do not endanger the General Public. Notification of, on assistance from, the University Police and Fire Departments may be warranted. The following Assessment Actions shall be considered appropriate for this Emergency Class: l i l a) Significant personnel iniury with or without radiological comglications- The ED shall assess the ! 1 Page 16 of 29
l .. e.xtent of the injmy and whether radioactive contamination is present. The assessment will consider the !
< nature of the injury, the appropriate first aid, the need for transportation to medical treatment facilities, and the levels of radioactive contamination, ifpresent. :
i b) Minor fire or explosion not specific to the reactors: The ED shall assess fire or explosion events to l detennine the magnitude of the event, the need for prompt control, and the need for support from outside ! agencies. The reactor staff will monitor the area to determine if radioactive contamination is present. ! t c) Sinnificant contamination of an individual or of the facility: Significant personnel contamination that l repeatedly fails to be removed by ordinary decontamination procedures shall be evaluated by the ED for ! possible consultation with appropriately trained medical personnel before funher decontamination is ! attempted. Significant contamination of the facility shall be assessed by the ED, after consultation with l the Emergen.c y_ Radiation Protection Manager (ERPM), to determine whether a formal decontamination ; i procedure needs to be developed for this event. ! l L d) Civil disturbances or receipt of a bomb threat thatt is not specific to the Nuclear Reactor Lab: Civil I disturbances :,ha!! be evaluated by the ED, for potential impact on the facility, aller consulting the l l University Police and Campus Administration. Bomb threats shall be assessed by the ED, for validity, l after consulting the University Police and evaluating the infonnation source. ! 6.3.3 Corrective Actions for a NRSRE j i This class of emergency consists of events that do not endanger the General Public. Notification of or ! assistance from the University Police and Fire Depanments may be warranted. The following Corrective : Actions shall be considered appropriate for this Emergency Class: ! l a) Significant personnel injury with or without radiological complications: For cases ofpersonnel injury l with or without radiological complications, the ED shall detennine what medical assistance is needed, and ! l may contact the Polic+ Dispatcher Champaism County ESDA at 9-911 to request transportation, if the injured individual is contaminated, decontamination will be attempted only ifit isjudged that this will not further aggravate the injury. A contaminated injured individual will be transported using contamination ! control and isolation methods. b) Minor fire or explosion not specific to the reactors: For minor fires or explosions not specific to the l reactor-or-its controksystems or their control systems the ED shall be notified and reactor staff members shall attempt to control the fire with portable fire extinguishers ifit is safe to do so. The ED shall detennine if the scope of the fire or explosion requires the assistance of the University Fire Depanment, i l and if so, the Dispatcher 4,halkbe-notified: Champaign County ESDA shall be notified al 9-911. c) Significant contamination of an individual or of the facility: The ED, aller consultation with the 1mergency_ Radiation Protection Manager (ERPM), shall detennine the decontamination procedure . appropriate for the individual or the facility. Goals shall be established to detennine when further decontamination is not warranted. These goals should consider retuming contamination levels to 10 CFR 20 limits. : d) Civil disturbances or receipt of a bomb threat that is nonpecific to the Nuclear Reactor Lab: In the ! event of a civil disturbance or receipt of a bomb threat that is not specific to the reactor, the University Police shall be notified and will initiate the appropriate controls to insure the protection of personnel and I l propeny. The ED shall notify the Head of the Depanment of Nuclear Engineering and keep him infonned of the emergency status. Page 17 of 29
614 Protective Actions for a NRSRE Some protective actions at this level of emergency (e.g., fine alanns) necessitate the evacuation of the Reactor lluilding. In this case reactor staff members will assemble at the nonh entrance to the Nuclear Engineering Laboratory to detennine if their services are needed. All evacuations will be initiated by notifying personnel on the public address system. Should fire or other event involve areas with radioactive material, the IllU)M shall control access to the areas and shall be responsible, with suppon l fiom the reactor staff, for the segregation of potentially contaminated personnel. More specific guidance on the methods, systems, and equipment for gathening and processing infonnation and data on which to base decisions to escalate or de-escalate emergency response actions are contained in EPIP-09," Assessment, Corrective, and Protective Action Procedures". Other specific guidance on this topic can be found in EPIP-08, " Emergency Action Levels (EALs) and Emergency Classification Procedures" 6.4 Entgrgency Response for a Notification of Unusual Event (NOUE) 6.4. I Activation of the Emergerigy Organization ihr a NOUli The complete activation of the cuen;ency organization for this emergency class would not nonnally be required. The Emergency Director (LD) shall activate that ponion of the emergency organization necessary to respond to the event. This class of emergency consists of events that may be initiated by either man-made or naturd phenomena that can be recognized as creating a significant hazard potential that was previously nonexistent. There is usually time available to take precautionary and corrective steps to prevent escalation of an accident or to mitigate the consequences should it occur. No releases of radioactive material requiring offsite response are expected. Some elements of the Emergency Organization may be activated or notified to increase the state ofreadiness, as warranted by the circumstances. Although the situation may not have caused damage to the reactors, the reactors shall be shutdown. 6.4.2 Assessment Actions for a NOUE a) Actual or projected radiological ellluents at the sitehperations) boundary _ calculated to produpe_a wholebodidose of-lkmRem Deep Dose Equivalent _(DDEbf 15 mrem (0.15 mSv) or a Committed Effective Dose Equivalent (CEDE) of 15 mrem (0.15 mSv1 accumulated within 24 hours: Fuel damage, experiment failure, or any event manifested by unusual radiation levels within the Reactor Laboratory, or the release of radioactive efIluents offsite, shall be assessed by the ED with assistance from the reactor staff. Additional suppon for assessment shall be requested from the Radiation Safety Office (RSO), if needed. The assessment shall consist of an observation and evaluation of the facility Continuous Air Monitors (CAMS) and Area Radiation Monitors (ARMS)in the control room and by smveys with portable ion chambers or other appropriate smvey instruments. Both high and low volume air samplers are available and collected air filters and smear samples can be counted in Room 106B NEL or, for gamma spectroscopy, in Room 222 MRL. The results can be used to assess whether the source is due to fission products, activation products, or a non-reactor source. Excessive airborne or radiation levels may require evacuation of the Reactor Building and further assessment will be made from outside the facility with the infonnation provided to the Emergency Support Center (ESC). b) R_qpon or observation of severe natural _phenomerta, such as tornadoes in the immediate vicinity _o_f the Nuclear Reactor Lab,_o_r_ earthquakes felt in the facility: This situation requires immediate shutdown of the reactors and notification of the ED. The ED shall establish contact with the University-Police l Page 18 of 29
l Disp:tcher Champaign County ESDA for funher assessment of the severe natural phenomenon and for recommendations on seeking shelter at appropriate assembly areas. c) %reats to orire_ aches of security. such as a bomb threat or civil disturbance. specific to the Nuclear Reactor Lab: Civil disturbances shall be evaluated by the ED, for potentialimpact on the facility, afler consulting the University Police and Campus Administration. Bomb threats shall be assessed by the ED, for validity, aller consulting the University Police and evaluating the infbnnation source. ; d) Fire or explosion within the facility that cannot be controlled immediately with an onsite CO 2 , extinguisier and requiring the assistance of the University Fire Depanment for control: The ED shall assess the severity of the fire or explosion to determine if the assistance of the University Fire Depanment l is required. i e) Failure of a_ fuel element or failure of an experiment with a release of radioactivity: The assessment ! actions for this event are the same as those detailed in 6.4.2 a)immediately above. ! More specific guidance on the methods, systems, and equipment for gathering and processing information and data on which to base decisions to escalate on de-escalate emergency response actions are contained in EPIP-09, " Assessment, Corrective, and Protective Action Procedures". Other specific guidance on this topic can be found in EPIP-08, " Emergency Action Levels (EALs) and Emergency Classification Procedures" 6.4.3 Corrective Actions for a NOUE a) Actual or projected radiological efiluents at the site (operations) boundary calculated to produce a whole-bodydose+f45-mrem Deep Dose Equivalent (DDE) of 15 mrem (0.15 mSv) or a Committed l Effective Dose Equivalent (CEDE) of 15 mrem (0.15 mSv) accumulated within 24 hours: If a l Notification of-Unusual-Event NOUE is dictated by assessment ofhigh radiation or airbome radioactivity I levels, the Reactor Building shall be evacuated pending an evaluation and identification of the probable { source. The ED shall direct the ERO to control access to the Reactor Building until radiation and airborne activity levels have been restored to normal. All personnel that were evacuated from the Reactor Building shall assemble at the nonh entrance lobby to the Nuclear Engineering Laboratory (NEL), which is the Primary Emergency Support Center (ESC); or at the nonh entrance lobby to the Division of Environmental Health & Safety (DEH&S), which is the Alternate Emergency Suppon Center (ESC). The location of these buildings is shown on the detailed map (Attachment 2). Both buildings are within 150 yards of the Nuclear Reactor Laboratmy. Since one is in a westerly direction and the other in an easterly direction, the choice could depend on the wind direction. All personnel who were in the Reactor Building at the time of the emergency shall be accounted for. b) Report or observation of severe natural _ phenomena. such as tomadoes in the immediate vicinity.gf tAq Nuclear Reactor Lab. or can_h_ quakes felt in the facili.t.y: This situation requires immediate shutdown of the reactors and notification of the ED. The ED shall establish contact with the University PoliceDispatcher Champa.ign__ County ESDA for funher assessment of the severe natural phenomenon and for recommendations on seeking shelter at appropriate assembly areas. c) Threats to or breaches of securityguch as a bomb threat or civil disturbance. specific to the Nuclear Reactor IA: Civil disturbances shall be evaluated by the ED, for potential impact on the facility, after consulting the University Police and Campus Administration. Bomb threats shall be assessed by the ED, for validity, afler consulting the University Police and evaluating the infonnation source. The police may l initiate controls to insure the protection ofpersonnel and propeny. The reactors shall be shut-down and Page 19 of 29
ptrsonnel evacuated to the Nuclear Engineering Laboratory or the ESC. All personnel who were in the facility at the time of the emergency shall be accotmted for. d) Fire or explosion within the facility _that cannot be controlled immedia_tely with an onsite CO2 extinguisher and requiring the assistance of the University Fire Department for control: The-ED-shall assess 4he+everity+f4he4ireor-explosion 4o<letermine-if4he-assistancemf theUniversity-Police-and Fire Depanments are required-The police or fire depanment may initiate controls to ensure the protection of i personnel and property. The reactors shall be shut-down and personnel evacuated to the Nuclear l Engineering Laboratoiy or the ESC, All personnel who were in the facility at the time of the emergency shall be accounted for. e) Failure of a fuel element or failure of an experiment with_p release of radioactivity: The corrective actions for this event are the same as those detailed in 6.4.3 a)immediately above. l 6.4.4 Protective Actions for a NOUE j If the Reactor fluilding has been evacuated, all personnel who were in the facility at the time of the emergency shall be accounted for. All individuals who evacuated the Reactor Building shall be surveyed for contamination with ponable instruments. Those individuals who are contaminated shall remain in an area designated by the ED or ERPM for decontamination. The ED is responsible for limiting access to the Reactor Building to rescue and emergency response operations personnel. The ERPM is responsibh for l minimizing personnel emocuie and the spread of contamination. Emergency exposure levels for j personnel shall be in s;cordance with Section 3.5 of this plan. l More specific guidance on the methods, systems, and equipment for gathering and processing information and data on which to base decisions to escalate or de-escalate emergency response actions are contained in EPIP-09, " Assessment, Corrective, and Protective Action Procedures". Other specific guidance on this ! topic can be found in EPIP-08, " Emergency Action Levels (EALs) and Emergency Classification Procedures" 1 i 1 6.5 limergency Response for an Alen 6.5.1 Activation of the Emercency Organization for an Alert i The complete activation of the emergency organization Ihr this emergency class is required. The l Emergency Director (ED) shall activate the entire emergency organization in response to an event of this j class. This class of emergency consists of events that would be of such radiological significance as to { require notification of the Emergency Response Organization (ERO) and their response as appropriate for the specific emergency situation. Under this class it is unlikely that offsite response or monitoring would be necessary. Substantial modification of reactor operating status is a highly probable corrective action. Protective evacuations or isolation of certain areas within the operations (site) boundary may be i necessary. Situations that may lead to this class include: 1) severe failure of fuel cladding or of fueled experiments where containment boundaries exist to reduce releases or less severe cladding failures in situations where fission products are not well contained, or 2) significant release of radioactive material as a result of experiment failures. Page 20 of 29
. 6.5.2 Assessment Actions for an Alert a) Actual or projected radiological effluents at the site _(operations) boundary calculated to produce a whole bodydose+f-75 mrem Deep Dose EquivalentJDDE) of 75 mrem (0.75 mSylor_a Committed Effective Dose EquivalendCEDE) of 75 mrem (0.75 mSyj_ accumulated within 24 hours: Fuel damage, experiment failure, or any event manifested by unusual radiation levels within the Reactor Laboratory, or ;
the release of radioactive efiluents offsite, shall be assessed by the ED with assistance from the reactor l staff. Additional support for assessment shall be requested from the Radiation Safety Oflice (RSO), if needed." . assessment shall consist of an observation and evalnation of the facility Continuous Air Monitor.,(CAMS) and Area Radiation Monitors (ARMS)in the control room and by surveys with portable ion chambers or other appropriate survey instruments. Both high and low volume air samplers are available and collected air filters and smear samples can be counted in Room 106B NEL or, for i gamma spectroscopy, in Room 222 MRL. The results can be used to assess whether the source is due to i fission products, activation products, or a non-reactor source. Excessive airborne or radiation levels may i require evacuation of the Reactor Building and funher assessment will be made from outside the facility ; with the information provided to the Emergency Suppoit Center (ESC). 1 b) Actual orittpje_ctest radiation levels at the site (operations) boundary of 20 mrem /In_(0.2 mSv/hrj whole boAfor-1-hour Deep Dose Equivalent (DDELfor 1 hour. based _ on East Wall Area Radiation Monitor (ARMk or 100 mrem gojected thyroid 41ose mrem (1.0 mSv) Committed Dose Equivalent (CDE) to the thyroid: Same as in a) immediately above. l l c) Severe failure of fuelMaddina or of fueled experiments where containment boandanica hist m reduce releases or less severe cladding failures in situations where fission products are not well contained: Same as in a) & b)immediately above. d) Significant releases of radioactive material as a result of experiment failures: Same as in a), b),4 and_c)immediately above. c) Loss ofphysical control of the facility: The ED shall consult the University Police, the Nuclear j Engineering Department llead, and the Campus Administration on steps to be taken to regain control of l the facility. This will depend entirely en the nature of the loss of control. 6.5.3 Corrective Actions for an Alert l a) Actual or proiected radiolonical eflluents at the sitejoperations) boundary calculated to produce a whole body < lose of-75-mrem I)eep Dose Equivalent (DDE) of 75 mrem (0.75 mSv) or a Committed Efrective Dose Equivalent (CEDE) of 75 mrem (0.75 mSv) accumulated within 24 hours: If a Notification of an Alert is dictated by assessment of high radiation or airborne radioactivity levels, the Reactor Building shall be evacuated pending an evaluation and identification of the probable source. The ED shall direct the ERO to control access to the Reactor Building until radiation and airborne activity levels have been restored to normal. All personnel that were evacuated from the Reactor Building shall as.semble at the north entrance lobby to the Nuclear Engineering Laboratory (NEL), which is the Primary Emergency Support Center (ESC); or at the north entrance lobby to the Division of Environmental llealth & Safety (Dell &S), which is the Alternate Emergency Support Center (ESC). The location of ; these buildings is shown on the detailed map (Attachment 2). Both buildings are within 150 yards of the j Nuclear Reactor Laboratory. Since one is in a westeily direction and the other in an easterly direction, the l choice could depend on the wind direction. All personnel who were in the Reactor Building at the time of the emergency shall be accounted for. l Page 21 of 29 l 4
l . b) Actual orgoje.qted radi;ttion levels at the siteloperations) boundary of 20 c.Pam/hr10.2 mSv/hr) ! - wholebody for-Ohour Deep Dose Equivalent (DDE) for I hour. based on East Wall Aiea Radiation Monitor MRM); or 100 mrem ptojectedilmoid dose mRent(1.0 mSv) Committed Dose Equivaknt (CDE) to the thyro. id: Same as in a)immediately above. c) Severe failure of fuel cladding or of fueled experiments where containment boundaries exist to r_ educe releases or less severe clad _ ding failures _iinituations where fissio_n products are not well enmained: Same as in a) & b) immediately above. d) Significant releases of radioactive material as a result of experiment failures: Same as in a), b),-& and c)immediately above. e) Loss ofphysical control of the facility: The ED shall consult the University Police, the Nuclear Engineering Department Head, and the Campus Administration on steps to be taken to regain control of the facility. This will depend entirely on the nature of the loss of control. 6.5.4 Protective Actions for an Alen If the Reactor Building has been evacuated, all personnel who were in the facility at the time of the emergency shall be accotmted for. All individuals who evacuated the Reactor Building shall be surveyed for contamination with ponable instruments. Those individuals who are contaminated shall remain in an area designated by the ED or IJRPM for decontamination. The ED is responsible for limiting access to the Reactor Building to rescue and emergency response operations. The ERPM is r sponsible for minimizing personnel exposure and the spread of contamination. Emergency exposure levels for personnel shall be in accordance with Section 3.5 of this plan. More specific guidance on the methods, systems, and equipment for gathering and processing information and data on which to base decisions to escalate or de-escalate emergency response actions are co. Mined in EPIP-09," Assessment, Corrective, and Protective Action Procedures" Other specific guidance a :his topic can be found in EPIP-08, " Emergency Action Levels (EALs) and Emergency Classification Procedures" 6.6 Site Area Emergency No credible accidents attributable to the reactor or its operation are riostulated which couid cause emergency conditions beyond the operations (site) boundary. Chapter XIV of ti e Safety Analysis Repon (SAR) . analyzed a number of accidents, including the release of radioactive emuents to the environment. The analysis I of a fuel cladding failure with complete loss of coolant, and the ventilation system off, indicate that an i emergency of this class would never occur. Ilowever, an emergency condition where the Emergency Response Organization (ERO) may consider setting up traffic control or the evacuation of adjacent buildings may seguire limited entg into the provisions of this classification. j 7.0 EMERGENCY FACILITIES AND EQUIPMENT 1 l 7.1 Emergency Suppon Centers l The Nuclear Engineering Laboratog (NEL) is the Primary Emergency Suppon Center (ESC) and the Division of Environmental llealth & Safety (Dell &S)is the Alternate Emergency Support Center (ESC) The nonh building entrance lobby of each building shall constitute the assembly area. The location of these 9ge 22 of 29
{ .
- buildings is shown on the detailed map ( Atta hment 2) lloth buildings are within 150 yards of the Nuclear 1
(- Reactor Laboratory. Since one is in a westerly direction and the other in an easterly direction, the choice could depend on the wind direction. The yrpose of these facilities is to provide: a control center. an accountability station; and a radiological unnitoring area for frisking of personnel and evaluation of radiological samples Room 106B in NEL is designated as the radiological counting room and the Emergency Equipment Locker is located there. Emey.ency Response directions would be given from one of these locations. Telephones and fax machines .cc available in both locations and the telephones and fax machine in NEL are under the control of the Nuca . Engineering Department. In addition, dedicated telephone lines are on each telephone in the Reactor Billdi a. These are unpublished numbers to be used only in an emergency. l Fax capability is also available by em ar moderu on several one of the computers in the Reactor Building. 7.2 Assessment Facilitie.s The Reactor Lab has Area Radiation Monitors (ALvin nith readouts and alann indications locally, by each detector, and in the c mtrol room; and Codnuous Air y onitors (CAMS), both of which readout locally and one ofwhich reads ou: in the control room and provie . ; building wide alann, as well as a trip that closes the damper in the Buiiding Exhaust Ventilation Syster, sending the air ef1luent through a charcoal filter bed prior to release out of the stack at ar elevation of 60 het above grade. The Depanment of Nuclear Engineering has counting labora!< cies at 106B NEL and 222 Materials Research Lao (MRL). Portable survey instruments are kept near the m mee to the Reactor Lab and could easily be taken along during an , evacuation. In addition, portak ouwey instruments may be readily obtained fiom: the Emergency Equipment i l Locker in Room 106B NEL, the ILab in Room 2r MRL, and the Campus Radiation Safety Office at the alternate ESC noted above. Ga uma Spectroscopy equipment is available in both 106B NEL and 222 MRL. and under the control of the Department of Nuclear Engineering. Portable high and low volume air samplers are available in the Reactor Lab and the Emergency Equipment Locker. Non-radiological monitors that may provide pettinent infonnation include: the primary and secondary control consoles, in the control room, which display all reactor status infonnation; a smoke detector in the control room; and meteorological data that is :eaaily available from the Illinois State Water Survey Oflice located On , I Campus. More specific guidance on this topic can be found in EPIP-09, " Assessment, Corrective, and Protective Action Procedures" l 7.3 first Aidjiedicalamd Decontamination Facilities I Car',: Clinic Association would be utilized as the decontamination center by the Champaign County l Et9ergency4ervices-and-Disaster-Agency (ESDA) ESDA. The " Radiation Accident Program" procedures for i Carle Clinic a"e included in Attachment 5. This hospital is about 3/4 mile from the reactor facility and is shown on the area map (Attachment 1). Because of the close proximity, transportation would be either by University Police, private ambulance sersice, or automobiles owned by Reactor Staff personnel. If an wtaal'accomes contaminated with no physical injmy requiring immediate treatment, decontamit en I would be Jone in the Ddecon sink or shower located in the lower level of the Reactor Building. 'lht 3 ains to this sink and shower are collected in the Retention Tank, which is pumped through a 0.45 micron filtu and monitor x1 for+olubleradionnelides to a holdup tank where it is sampled and counted _for sohihle and insoluble radioactivity prior to release to the sanitary sewer system. More specific guidance on this topic can be found in EP'P-03,"Nucleer Reactor Lab Emergency Call List - Intrusion / Emergency", EPIP-06," Radiation Protection Manager Procedures", EPIP-07, " Emergency Page 23 of 29
2 Medical, Security, Fire, and Plant Se'/ ices Manager Procedures", EPIP-09, " Assessment, Corrective, and !
- Protective Action Procedures", and EPIP-11," Support Agency Procedures", as well as Attachment 5 7.4 Conununications Equipment i
Telephones and fax machines are availabin in both Emergency Support Centers (ESC) and the telephones and , fax machine in the NEL Suppon Center r re under the control of the Nuclear Engineering Depanment. In addition, dedicated telephone lines ate ou each telephone in the Reactor Building. These are unpublished , numbers to be used only in an emerge t.:y. Fax capability is also available by computer modem on several one l of the computers in the Reactor Buildng. The University Police can also be sununoned on activation of the ; intrusion alarm system by pressing a button in the control room. The University Police and Fire Depanment personnel also maintain a radio system for conununication with the Dispatcher. - More specific guidance on this topic can be found in EPIP-07, " Emergency Medical, Security, Fire, and Plant Senices Manager Procedures". 8.0 REENTRY AND RECOVERY OPERATIONS , This authority is vested with the Emergency Director (ED). The Reactor Building can be isolated and secured following any emergency with any operation in progress delayed until a complete recovery is made. Since any i water would drain to a hold up tank (Retention Tank) and any paniculate activity in the air would be trapped in the 11 EPA exhaust filters, ample time would be available to meet at some other location and fonnulate plans for a , given scenario. Specific recovery procedures for an actual emergency event will be written and approved as needed. Guidelines on recovery and reentry are given in EPIP-10, " Reentry and Recovery Procedures". Several , of the areas investigated prior to reentry would include:
- 1. Evaluation of airborne activity adjacent to entryways and in the building by remote sampling.
- 2. Evaluation ofdose rate $ on the building exterior and within the building as conditions warrant.
- 3. Contamination outside the facility and within the building as conditions warrant.
Personnel entering the building would be required to wear appropriate protective clothing until contamination i levels have been evaluated. Doses to individuals should be kept within the 10 CFR 20 limits, except for Planned j Special Exposures as noted in Section 3.5. j 9.0 MAINTAINING EMERGENCY PREPAREDNESS l 9.1 Training initial training will sl all i be provided to all individuals occupying positions designated in this plan. -when this pla n-ba s-beeirapproved4>y-the44 RG-Becau se-this-i+ Revision 4cf-a-complet ely4evise4 Emergency-Pla n Emergency-Preparedness 4 vill-be-maintained-as-outlined 4iethe<:urrent-approved " Radiation-Emergency-Plan; Revisioir March 4994". Subsequently, Emergency Plan Training shall be provided on an annual basis, at intervals not to exceed 15 months, and as needed for new personnel or for personnel whosejob assignment has changed and this change also results in a change in their designated position in the plan. This retraining ! will be limited to the responsibilities of their new emergency plan position assignment. The University Police and Fire Department personnel shall be trained biennially on a rotating basis. Elements of the annual training shall include:
- 1. A review of the Emergency Plan and Implementing Procedures.
- 2. A review of emergency monitoring equipment and its location.
Page 24 of 29 n ___._.c +. _ _ - - __
3.*A review of the Emergency Call List and procedure. 1
- 4. Methods by which to recoptize that an adverse radiological condition exists by use of the Continuous Air Monitors (CAMS) and Area Radiation Monitors (ARMS).
- 5. Directions regarding those areas of the lab where a radiological release might occur in conjunction with l a fire or other disturbance.
More specific guidance on this topic can be found in EPIP-12, " Training Procedures", EPIP-13," Drills and Exercises", and EPIP-14," Emergency Equipment Maintenance and Surveillance" 9.2 Conduct of Drills and Exercises Onsite emergency 41 rills r to-besonducted es-ectionshillehall be-held-on-en Emergency Drills or Exercises. to be conducted as Action Drills. shall be held on an alt _ernating annual basis, at intervals not to exceed 15 months. An action 4 hill Action Drill or Exercise tests the integrated capability of the Emergency Plan, or a component thereof, and may include instruction periods to develop and maintain skills in a panicular operation. All telephone numbers in the plan shall be verified annually, at intervals not to exceed 15 months. More specific guidance on this topic can be fotmd in EPIP-13," Drills and Exercises" l 9.3 Critiques of Drills and Exercises l A critique +f the41 rill Critique of the Drill or Exercise shall be held immediately following its completion. 'Diis ; shall include comments from those participating, review of problems encountered, corrections ofidentified deficiencies, and the status of the verification of the Emergency Call List. More specific guidance on this topic can be found in EPIP-13, " Drills and Exercises", l 9.4 Drill and Exercise Scenarios
'lhe Emergency Coordinator, with the assistance of the Emergency Director, shall develop a mitten scenario l for the conduct of the annual-action 41 rill alternating. annual Action Drill or Exercise, at intervals not to exceed 15 months.
More specific guidance on this topic can be found in EPIP-13," Drills and Exercises" 9.5 Emergency Plan Review and Up1 1_ ate i The Emergency Plan, the Emergency Plan Implementing Procedures, and the Agreements with Offsite l Suppon Agencies (Champaign County ESDA) shall be revised and updated on a biennial basis. Each revision shall be reviewed and approved by the Emergency Director, the Emergency Coordinator, and the Nuclear Reactor Committee. Modifications resulting from action-drills Action Drills,_ Exercises, or changes in the facility or environs, shall be incorporated into each revision. Updated revisions shall be distributed to all i organizations affected by; or mentioned as a participating organization in; the plan. Any revisions to the Emergency Plan or the Emergency Plan Implementing Procedures (EPIPs) shall be approved by the Reactor l Committee Administrator. reviewed by the Reactor Committee, and transmitted to the_ authorized recipients within 30 days after the revised plans have been issued. More specific guidance on this topic can be found in EPIP-05, " Emergency Coordinator Procedures" l Page 25 of 29
]
9.6 limergency_ Equipment Maintenance and Surveillance i The major sources of radiation monitoring equipment that would be immediately available in an emergency ; are: 1) the Control Room and Reactor Health Physicist's Oflice at the Nuclear Reactor Lab in or near the lobby area by the main door; 2) the Radiation Safety Oflice (RSO) at both, a) 101 S. Gregory St., Urbana and b) the Dynamics Testing Laboratory,601 E. Curtis Road, Champaign; c) Room 106B NEL; and d) , Room 222 MRL. Additional equipment,if the need arises, may also be made available from the various facilities that utilize radioactive material on the University ofIllinois Campus. Lists of equipment available at the major sources are given in Section 9.5.1 below. , More specific guidance on this topic can be found in EPIP-14, " Emergency Equipment Maintenance and Surveillane" 9.6.1 Jnventory ofEquipmmt and Suppljes I The instmments that would be used in an emergency are those that are used routinely for monitoring , radiation and contamination levels at the Nuclear Reactor Lab, those instruments dedicated for use in an emergency and stored in the Emergency Equipment Locker in 106B NEL, those instruments available within the Department of Nuclear I ugbdne (primarily gamma spectrometers)in 106B NEL and 222 MRL,-and those-instruments 4mder-the control-of the-Radidion-f afety-Oflice(RSO) that-are-used-eampus wide-form variety-of f urposes. The Reactor Lab instruments are function tested as part of the " Health Physics f%iy Checklist" on each day of the work week that the reactors are operated, all other portable instruments, including those stored in the Emergency Equipment Locker, are ftmetionally tested as part of their semiannual or annual calibration. The minimum frequency for inventory of Emergency Equipment and l ! Supplies shall be annually, at intervals not to exceed 15 months, and include all instruments listed in this section of the Emergency Plan. i More spepfic guidance on this topic can be found in EPIP-14," Emergency Equipment Maintenance and Surveillanc 3". Nuclear Rea Ltat Lab Equipment: l Total Number Available Equipment Designation Range 21 Victoreen 450 (Ion Chamber) 0 - 50 R/hr l l 1 Eberline RO - 2 (Ion Chamber) 0 - 5 R/hr I 1 N_eutron Rem Meter 0 - 5 Rem /hr 1 DosipolHC-dTe-Semiconductor) 0-10004/hr 2 Neutron-Rem-Meters 0-5-and4-2-Rem /hr 8 Electronic Pocket Dosimeters 0 - 9999 mrem 1 120 V. A.C. Air sampler 0 - 70 cfm 2 Eberline RM-14 Count Rate Meters 0 - 50,000 and 0 - 5,000,000 cpm 1 Johnson GSM-15 Count Rate Meter 0 - 500,000 cpm i 1 Johnson GSM-5 Count Rate Meters 0 - 50,000 cpm l f 1 Eberline BC-4 Beta Counter 0 - 999.999 Counts l 1 Eberline SAC-4 Alpha counter 0 - 999,999 Counts I 1 Canberra IIPGe y-ray spectrometer 0 - 3000 kev 1 Alpha Scintillation Probe ASP-2 N/A 4 Ganberra-Nal-y-ray +pectrometer 0-2000-kev 4 Alpha-Seintillation-Probe-ASP-2 N/A Page 26 of 29
1 IIP-210T Probe N/A ! I lip-265 Probe N/A I IIP-260 Probe N/A l Emeggency Equipment Locker (106I1 NEL): Total Number Available Equipment I)esignation Range i Victoreen 450 (lon Chamber) 0 - 50 R/hr 1 Eberline E-140 Count Rate Meter 0 - 60,000 cpm 5 Quartz Fiber Dosimeters 0 - 200 mrem 2 Quartz Fiber Dosimeters 0 - 600 Rem 1 Dosimeter Charger N/A 1 120 V. A.C. Air sampler 0 - 100 lpm 10 50 mm Glass Fiber Filter Papers N/A ; 1 Johnson GSM-5 Count Rate Meters 0 - 50,000 cpm 1 HP-260 Probe N/A l 1 Johnson GSP-2A -Nal Probe N/A , 3 boxes 100 each Paper Smears N/A ! 9/11 Protective Clothing Coveralls / Hoods N/A 24-pairst Dozen Rubber Gloves and Liners N/A 62-pairs 4 Dozen Plastic Shoe Covers N/A , i 1 Dozen R_ubbers N/A 9tairs Plastio-Boot-Liners N/A 49-pairs Rubbers N/A , l Radiat ioiFSa fety-OfTice4 RSO) Equip ment + Total-Number 4vailable Equipment-1)esignation l Range 6 Geiger 41ueller-instniments 0-50,000<pm 3 Low-energygamma-Nal letector Iodine +uiveynnd thyroid < hecks , 4 lev-Volume-Air-Sampler dependent 4merificeused ) 1 Iligh-Vohime-Air-Sampler dependent +n-orifice-used 4 lonizationeGhamber-instrument G--2-R/hr 4 lonizatiomC-hamber-instrument 045-R/hr 4 lonizatioiFGhamber-instrument 0-h000-R/hr 1 4 Lowenergwair-ionizatioiemeter 0.00005-500-R/hr 5 Quartz-Fiber-Dosimeters 0- -200anR 4 Liqui 4 Scintillation Counter 0-4S44S9munis 4 Gas 41owProportionalGounter 0--999899-Counts 6 IIP-265-Probes N/A 4 Alpha-SeintillatiomProbe-ASP-2 N/A 2 Dosimeter-chargers N/A l RadiationFSafetwOflicM RSO)-Imboratoiv-AnalyticalEmdpment+ Internal 4iquid +cintillation-spect rophotomet er Gas-Howproportional-counting-system NalfTI)--Multichannel-Analyzer Page 27 of 29 1
S1olidary-stand:rd condenser-Roentgen-nreter Capint eo+econdary st anda r d -elect r ometer Noteilhis equipment $houl@e available but;ite)oimnderJhesontrol of tlie Reactor SialToMuclear littgit)eenifig-1)epanment itergmuel. hiaterial_s Researqh 1,ab (MRL) Room 2_22 Total Number Available Equipment Designation Range i Victoreen 450 (lon Chamber) 0 - _50 R/hr 1 Johnson GSM__I 5. Count _ Rate Meter 0__500,000 epm i IIP-265 Probe N/A 2 Gamma Spectroscopy Detectors N/A Note: The minimum equipment _ required to be operable at all times to maintain Emergency Preparedness shall be: Llo!LChamber m5 Self-Reading.Pogket Dosimeters. I Count Rate Mete _r with G_M_ probe and 1 Air Samplerm This equipment shall be located in the EmergencyJiquipment Locker in Room 10611 NEL Ifat
;my timeany_of the above listed eqttpment i should become inoperable it shall be immediately replaced 9.6.2 Radiation MonitoringXguipment Calibration:
All portable instrmnents ate-calibrated 4m-anamnual basis,-alland i.'boratory analytical instruments are calibrated at-least-once-per-year-Thetwo+econdary+tandard+rayand-gamma rayexposureinteinstruments are-calibrated-per-manufacturer-instructions-or-everytwo-yearon an annual basis. More specific guidance on this topic can be found in EPIP-14, " Emergency Equipment Maintenance and Surveillance" 9.7 Emergency Plan Implementing ProceduresfiPIPs) List: No. Title EPIP-01 General Instructions and Organizational Responsibilities. EPIP-02 Reactor Operator Inuuediate Action Procedures. EPIP-03 Nuclear Reactor Lab Emergency Call List - Intrusion / Emergency. __ EPIP-04 Emergency Director (ED) Procedures. EPIP-05 Emergency Coordinator (EC) Procedures. EPIP-06 Emergency Radiation Protection Manager (ERPM) Procedures. _ EPIP-07 Emergency Medical. Security. Fire, and Plant Services Manager (EPSM ) Procedures EPIP-08 Emergency Action Levels (EALs) and Emergency Classification Procedure. EPIP-09 Corrective and Protective Action Procedures EPIP- 10 Reentry and Recovery Procedures. EPIP-i l Coordination of Offsite Agencies Procedures. EPIP-12 Training Procedmes. EPIP- 13 Drills and Exercises. EPIP-14 Emergency Equipment Maintenance and Sun'eillance. EPIP-15 Documentation and Records. Page 28 of 29
__7...____ t l. Revised Bv: Mark A. Kaczor
Title:
Emergency Coordinator Date: ! i geviewed By:
Title:
Operations Sup_ervisor Rate: l Jonathan M. Ralston ! t Approved By:
Title:
Emerge. ncy Director Date: l Rich L. Ilolm j i ! Date Reviewed by the Reactor Committee: } i h (eplankplammy-395) ; (eplan\eplanrev.597) i I III I i
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E-Plan Attachment 4 ) Pzge 1 of I l I i Emergency Response Organization (ERO) l I l Emergency Director j (ED) l l l i Emergency Emergency Duty Emergency Plant Emergency Public ! Coordinator Radiation SRO Services Manager Information Manager !
. (EC) Protection (EPSM) (EPIM)
"" E RO/SRO (ERPM)
Champaign County University Office l Emergency Services of Public Affairs ! Division of Reactor and Disaster Agency Envirorunental Staff (ESDA) Health & Safety l (DEH&S) ! Police, Fire, and l Radiation Medical j Safety Officer ! (RSO) i l h i t
-(eplan\attchmt4. doc) ;
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. C-Plan Attachinent 5 4 Page I of 2 ,
CHAMPAIGN COUNTY ; Emergency Services and Disaster Agency 1905 East Main, Urbana, IL 61802 217 + 384-3826 IsDA March 26, 1997 Richard L. Holm ' Reactor Administrator 214 Nuclear Engineering Laboratory 103 S. Goodwin Ave. Urbana, IL. 61801-2984
Dear Sir:
In checking with Carle Hospital and covenant Medical Center, I believe you and I have h most cu nt Radiation Safety P1 for . ar(e. dosfi hm nedge , Champaign County E.S.D.A. will respond to any incident for coordination or resource support. To activate ESDA call 911. If we can be of any assistance please feel free to call. Sincerely, L' I'/k~d)/
. /.N/
Bill L. Keller, Coordinator l BLK:jh l l i
I e .* -
- , E-Plan Attachinevit 5
Page 2 of 2 ; 1 i The Carle Clinic Association l " Radiation Accident Program" l is available for review at the Nuclear Reactor . Lab and is located in the Emergency Preparedness Files. ! i
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