ML20210K096

Forwards Emergency Plan for Nuclear Reactor Lab at Univ of Il in Urbana,Il. Ltr Attached to Rev Bar Copy,Outlines Changes Made to Plan

ML20210K096
Person / Time
Site:	University of Illinois
Issue date:	08/15/1997
From:	Holm R ILLINOIS, UNIV. OF, URBANA, IL
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9708190142
Download: ML20210K096 (37)

Text

_ _ _ _ _ _ _ _

k Radiation Scienca Laborttory, Univer lty of Illinob at Urbana-Champaign Department of Nuclear Engineering / College of Engineering 4- '- r - - 214 Nuclear Engineering Laboratory 217-333-7755/0866 ,

1_ 103 South G,xxiwin Avenue 217-244-5916 fax g Urbana. IL 61801 2984

• W[y ,

7 Administratet Heahh Physicist

• _b_ Rchard L. Holm Mark Kaczor ,

r hohn @uluc odu m-kactor@uiuc.edu y-August 15,1997 S Docket No. 50-151 U.S. Nuclear Regulatory Commission ATrN: Document Control Desk Mail Station PI-137 Washington, DC 20555 SUD.IECT: Submittal of changes to the UlUC Nuclear Reactor Laboratory Emergency Plan pursuant to 10 CFR 50.54(q) that do not decrease the effectiveness of the Plan.

Please find attached copies of the UlUC Nuclear Reactor Laboratory Emergency Plan in revision bar and final form. These changes do not decrease the effectiveness of the Plan.

A letter is attached to the revision bar copy that outlines the changes made to the Plan.

Training was completed on the changes on August 14,1997 and the changes were then implemented.

Sincerely, Richa d L. Holm Reactor Administrator 9 090l ,

c: USNRC, Region Ill 4 ^ ^ " "

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/ : R University ofIllinois at Urbana-Champaign g[hyk. J. Nuclear Reactor 1,aboratory .-

/ Depanment of Nuclear Engmcenng / College of Engmeenng

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\ 9 / 214 Nuclear Engmoenng Laboratory (217) 333-7755/0S66 Voice l 1 103 South Goodwm Avenue (217) 244-5916 Fax Urbana, IL 61801-29S4 To: Rich L. Holm Emergency Director and Reactor Administintor From: Mark A. Kaczor /l(

Emergency Coordinator and Reactor Heahh Physicist Date: May 22,1997.

Subject:

Summary of Changes to the Emergency Plan in Revision 1, May 1997.

l 1 have completed the first biennialieview 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.

2) Incorporated all" Lessons Leamed" from the 1995 Etnergency Ddll and the 1996 Emergency Exercise as i outlined in the Cdtiques for these events i

3) Incorporated format changes to the Emergency Action Levels (EALs) and Emergency Classification System as suggested in the April 1997 " ERRATA" referencing "NUREG-0849" received from the NRC 00 ice of Resources Management on May 5,1997.

4) Updated the Agreement with the Offsite Sappon Agency, Champaign County Emergency Services and Disaster Agency (ESDA).

5) As a result of 2) and 4) above, changed the notification of the " Senior Uruversity Police or Fire Officer On Duty" as the individual authorized to place a call to Champaign Cotmty ESDA to the " Reactor Operator /

Acting Emergency Director or the Emergency Director" as the individuals authorized to place a call to 9-91 I and request that the Champaign County Emergency Seivices and Disaster Agency (ESDA) activate Onsite coordination with local horpitals and support agencies,

6) Removed Equipment Inventory Lists for equipment we had no control over that belonged te 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.

7) Made minor grammatical and document format changes as appropdate.

Thank you for your time and consideration of this matter.

MAK/mak pc: Reactor Committee and Head. D. Miller E. Wiener B. Jones Depanment of Nuclear Engineering D. Hang D. Scherer as noted to the right: B. Heuser R. Holm (eplanuvsumS97. doc)

Draft Revision for Review EMERGENCY PLAN for the NUCLEAR REACTO~R LABORATORY at the l

UNIVERSITY OF ILLINOIS in URBANA, ILLINOIS I

Facility Licenses No. R-115; R-117 Docket Nos. 50-151;50-356 Revision 01 Moreh4994 May 1997 Page 1 of 29

=. .

TAllLE OF CONTENTS - for this llevision Markup Section Page Number s

T*ble4>fGentents 2 3 Preface 4

~

1.0 Introduction 5

1.1 Description of the Reactors 5

1.2 Location of the Reactor Facility 5

l.3 Identification of Owner / Operator __

5 1.4 Objective of the Emergency Plan 5

2.0 Definitions 5

j. 3.0 Organization and Responsibilities 7

l

__ 3 I Enjernency Resynse OrnanizationlERO) .

8

._ 3.L1 Emergencv_ Director (EDj 8 3.1.2 Emernency Coordinator 1IiCJ 9

__ 3.1.3 Reactor Opgator (RO) 9 3.1.4 Eme gency Radiation Protection Manager 1ERPM) 9 1 3.1.5 Emergency Medical, Security, Fire, and Plant Services ManagerJEPSM) 9 1 3.1.6 Emergency Public Infonnation ManagerJEPIM) 10 l 3.1.7 University Oflice of Public Affairs 10 3.1.8 Senior-Univetsity-Police-or-Fire-Omeer-On-Duty Police. Fire. and Medical 10 Assistance j i

3.1.9 Radiation Safety OfEce (RSO) 10  !

3.2 Coordination and Notification of Federal. State, and Local Govemmental Agencies 10 3.2.1 Nuclear Regulatory Commission (NRC) and American Nuclear insurers (ANI) I1 3.2.2 Champaign County Emergency Services and Disaster Agency (ESDA) 11 3.2.3 University of Blinois Police and Fire Depanments 11

- 3.2.4 University Division of Environmental Health & Safety (DEH&S) 12 3.3 Termination of an Emergency 12 3.4 Authorization for Reentry 12 3.5 Authorization for Planned Special Exposures 12 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 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 Values 16 6.3 Emergency Response for a Non-Reactor Safety Related Event (NRSRE) 16 Page 2 of 29

6.3.1 Activation of Emergency Organization for a NRSRE 16 6.3.2 Assessment Actions for a NRSRE 16 6 3.3 Coaective 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 6.4.1 Activation of Ernergency Organization for a NOUE 18 6.4.2 Assessment Actions for a NOUE 18 6.4.3 Cortective Actions for a NOUE 19 6.4.4 Protective Actions for a NOUE 20 6.5 Emergency Response for an Alen 20 6.5.1 Activation of the Emergency Organization for an Alen 20 6.5.2 Assessment Actions for an Alert 21 6.5.3 Corrective Actions for an Alen 21 6.5.4 Protective Actions for an Alen 22 6.6 Site Area Emergency 22 7.0 Emergency Facilities and Equipment 22 7.1 Emergency Suppon Centess 22 7.2 Assessment Facilities 23 7.3 First Aid, Medical. and Decontamination Facilities 23 7.4 Communications Equipment 24 8.0 Reentry and Recovciv Opciations 24 9.0 Maintaining Emergency Preparedness

_ 24 9.1 Training 24 9.2 Conduct of Drills and Exercises 25 9.3 Critiques of Drills and Exercises 25 l 9.4 Drill and 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 AttacInnents N/A

1) Champaign Urbana Area Map.

N/A

2) Nuclear Reactor Lab Imruediate Area Map.

N/A

3) Diagram of Reactor Building showing: site boundary, location of the reactors, and associated equipment.

N/A

4) Block Diagrarr of Emergency Response Organization (ERO). N/A

5) Written Agreements with local suppon organizations. N/A Page 3 of 29

PR E FM 'I'.

Planning for possible emergencies at the Nuclear Reactor Lrboratory (NRL) was staned with the publication of the 11azards Analysis in October,1959. His repon contained written proceduies to be folleved in t.l.le_ case of a sudden or threatening increase in radiation levels _ were4owen-AReHhe+ tart-up AHer the commencement of operations in 1960, these piocedures were incorporated 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 cf this l License," Technical Specifications for the Illinois Advanced TRIGA Reactor", required written procedures for cmcrgency conditions involving potential or actual release of radioactivity, including provisions for evacuation, re-entry, recovery, and medical suppon. Criteria for re entry and recovery were added to the " Rules and Regulations ". Medical suppon was provided by a decontamination room at McKinley Hospital.

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 Emeigency Plan for NRL was reviewed and approved by the Nuclear Reactor Committee on April 12,1973. This Plan was then reviewed by personnel from '

the Oflice ofluspection and Enforcement of the Nuclear Regulatory Conunission (NRC) and was found to be adequate. For a number of yeais, most of the attention for approved Emergency Plans was directed toward i Nuclear Power Reactors l

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 theCStandaid for l

Emergency Planning for Research Reactors"(ANSI /ANS 15.16), and was basically the original Plan with  ;

sections added to address areas that were not previously coverei On March 20,1984, a notice was received that the Plan was inadequate in cenain 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.

t he Emergency Plan then implemented, was a combination of the items sent on November 1982 and July 1984.

When completed, it was reviewed and approved by the Nuclear Reactor Committee. Copies were then submitted to the 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 ecceptable in accordance with 10 CFR 50.54(q). However, 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, ANSUANS 15.16-1982, and NUREG-0849. Tnese 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 thnist of the changes were to more completely follow the guidance given in : 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" a

This revision wramill4e reviewed and approved by the Reactor Committee and submitted to the NRC gn in March 13.,1995. The NRC acccoted the olan in a letter dated. September 26.1995.

Page 4 of 29

1.0 INTitODUCTION I I Description of the Reactois:

The Illinois Advanced TRIGA and LOPRA reactois utilize fuel produced by General Atomics. The authorized maximum steady state power levels are 1.5 MW for the TRIGA seactor and 10 kW for the LOPRA reactor. The TRIGA is used for education, training operators, the production of radioactive isotopes, and research. The LOPRA is coupled to the TRIGA through a thesmal column. Although the 1

LOPRA was originally buik to study coupling effects, the only present use is foi education and training.

1.2 Location of the Reactor Facility:

The reactors are housed in a concrete block building near the Nonheast end of the University ofIllinois Campus in Urbana-Champaign. The actuallocation is 200 feet East of Goodwin Avenue between Green 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 attemate emergency centers. One is a panial map of Champaign-Urbana showing access from Inteistate 74 to the reactor and the location of Carle Medical Center (Attachment I). The second map shows the immediate area and gives access routes to the reactor and the alternate sites that would be used as emergency centers ( Attachment 2). A third map is included as a diagiam of the reactor building showing the site boundaiy, the location of the reactors within the building, and associated equipment locations (Attachment 3).

l.3 Identification of the Owner / Operator:

Both reactors are owned by the University ofIllinois Board ofTmstees and operated by the Nuclear Engineering Depanment in the College of Engineeiing.

1.4 Obiective of the Emercency Plan:

The Emergency Plan contains provisions for a graded response to possible unplanned adverse radiological conditions both within and beyond the facility boundaries. The content follows the guidelines of ANSI /ANS 15.16-1982 " Emergency Planning for Research Reactors", NRC Regulatoiy Guide 2.6, and NUREG 0849.

Since the postulated radioactive releases from credible accidents at this Ocility falls in the first categoty,

" 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",(Emergency Planning

' Zone) the EPZ for this plan is established at the Operations (Site) Boundary and the Emergency Classification " General Emergency"is not used.

2.0 DEFINITIONS Confinement System: is defmed at the Reactor Building Walls and is designed to confine and maintain control of 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 the licensee for any reason. It is dermed 4he-some-es4he-areas-referred-to-below-es4he-Operations 4nd, Site Boundaries-It-is+ontrolled-for4he-purpose +f 6eeurity controlled at the NRL for the purpose of Security and is identical to the Operations and Site Boundaries. as defined below.

Emereency: is a condition that calls for immediate action, beyond the scope of normal operating procedures, to avoid an accident or to mitigate the consequences of one.

Page 5 of 29

timergency Action Levels (EALst are specific instmment ieadings 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 emeigency measures.

Emergency Chsses: are classes of accidents grouped by severity level for which pi: determined emergency measures should be taken or considered.

Emernency Fun: is a document that provides the basis for actions to cope with an emergency, it outlines the ob'ectives to be met by the emergency procedures and defines the authority and r,:sponsibilities to achieve such objectives.

Emergency Plannine 7one (EPZ): is an area for which olTsite emergency planning is perfoimed to assure that prompt and efTective actions can be taken to protect the public in the event of an accident. The EPZ for this plan is the Operations (Site) Boundary and is dermed by the Reactor Building Walls (Confinement).

Emergency Plan Implementation Procedures (EPIPst are documented instructions that detail the implementation actions and methods required to achieve the objectives of the Emergency Plan and are contained as a distinct group of procedures as an appendix to this plan.

Emernency Support Centers (ESCst is-an-eiea are areas designated for assembly aller an evacuation. The l

purpose of these facilities is to provide: a control center; an accountability station; and a indiological monito ing area for fdsking of personnel and evaluation of radiological samples.

LOPRA Reactor: Low Power Reactor Assembly; which refers to the smaller of the two reactors located onsite

[ that utilizes General Atomics designed TRIGA Type Fuel Elements and has a maximum steady state power rating of 10 kW.

Nuclear Reactor Laboratoiv(NRLt is defined in the introduction to this plan.

Offsite: is the geographical area outside the walls (the confinement) of the Reactor Lab and is not controlled by the operator of the lab, the Nuclear Engineedng Department.

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 Engincedng Department.

Operations Boundarv: is the area where the Reactor Administrator (Emergency Director) has direct authority over all activities. This is defmed by the Reactor Building Walls (Confinement) and the area within this boundary has prearranged evacuation procedures known to people frequenting the area. His area is also referred to as the Site Boundary.

Protective Action Guides (PAGsh are projected radiological dose or dose commitment values to individuals that warrant protective action following a release of radioactive material. Protective actions would be warranted 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 the dose that has unavoidably occurred prior to the assessment.

Reactor Staff; are those individuals with assigned duties at the Reactor Lab wl o have both Security and Restricted Area Access. They are trained to respond to breaches of security and have the appropriate level of Page 6 of 29

sadiological tiaining to have unesconed access to. and s con individuals into. the restricted area. They also have an assigned position in this plan.

Research Reactor: is a device designed to suppon a self-sustaining neutron chain reaction for research.

{

developmental, educational, training, or experimental purposes, and which may have piovisions for production of l non fissile radioisotopes.  !

Restricted Area: is that area. access to which is limited by the licensee, for the purpose of protecting individuals 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 StafE i Site Boundary: is the area where the Reactor Administrator (Emergency Director) has direct authority over all activities. This is defmed by the Reactor Building Walls (Confinement) and the area within this boundary has preananged evacuation procedures known to people frequenting the aica. This area is also icferred to as the Operations L omdary. This area may also be frequented by people teacquainted with reactor operations; such as Visitors and Tour Groups; however, these individuals are always under the direct supeivision and control of a

- member of the Reactor Staff Shall. Should. and Mav: the word "shall"is used to denote a icquirement; the word "should" to denote a secommendation; and the word "may" to denote pennission neither a requirement nor a secommendation.

l TRIGA Reactor: Training, Res: arch, Isotope pProduction, General Atomics;is the acronym used to roer to the main and larger of the two reactors at the NRL with a maximum steady state power rating of 1.5 MW.

I r 3.0 ORGANIZATION AND RESPONSIIHLITIES He Nuclear Reactor Laboratoiy (NRL) is a facility of the Nuclear Engineering Depanment, through which it receives primary funding for staff and equipment, and is operated under license from the NRC. The Reactor Administrator, a licensed Senior Reactor Operator (SRO), is directly responsible for all actoities conducted at the NRL including, but not limited to: Building Security, Special Nuclear Material (SNM) Custodian, the Emergency Plan, and Supervision of tl:e Reactor Staff The Reactor Administrator is responsible in a line of authority to the Head 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. He shall keep these individuals informed regarding changes to their roles in the Emergency Organization and changes to the Emergency Plan. The Reactor Health 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 Health Physicist is responsible for ensuring that the radiation monitoring and supplementaty equipment required for an emergency is available as specified in the Emergency Plan. The Reactor Operating Staff consists ofindividuals who have a current SRO or 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 Department of Nuclear Engineering and reports directly to the Department Head. 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 29

O 3 I li!!!c!gmy_EcSponse_Orgajlzatio i J 1]IRJ)

'ihe 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 Office (RSO)in the Division of Environmental llealth & Safety (DEH&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, traflic control and '

limited building evacuation; the University Fire Depanment for firefighting, emergency medical trauma response, and/or rescue; the University Office of Public AfTairs for media contact; ar.d the Champaign County Emergency Services and Disaste. Agency (ESDA) for outside assistance with police, fire and medical facilities. A Block Diagram outlining the reponing sesponsibilities, lines of authority, and line of succession to the Emergency Director is included as Attachment 4. W itten 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. I Emerg.0cv Diiectol.111D)

The Reactor Adminit trator is the Emergency Diiector. The ED has ultimate authoiity over Onsita 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 found in l' PIP-04. The authority and responsibility of this r 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 minhnizing releases of radioactive mateiial; d) protecting facility personnel and visitors; e) exchange ofinfonnation with authorities responsible for offsite emergency measures and summoning assistance as necessaiy:

• f) protective action decisions;

• g) a'ithorizing radiation exposures in accordance with NRC Regulatory Guide 8,35 " Planned Special Exposures";

h) declaring the termination of an emergency and directing restoration; i) providing for a fmal 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 attemates) with the same responsibilities and authorities described above. This assures the immediate wailability of an individual to respond if the Emergency Director is nct available.

Line of Succession to ED: Reactor Health Physicist Operations Supervisor Senior Reactor Operator Campus Radiation Safety Officer Page 8 of 29

0 31.2 lituttgenry CronlinalottliC)

'the Itcactor licahh Physicist is the Emergency Coordinator. The !!C is responsible los the m etall coordination of the timengency Plan as detailed in 1: PIP 05.1hese responsibilities include a) developing and maintaining the Emergency Plan and implementing Pioceduies (EPIPs).

b) advising the Reacim Administrator on the selection and liaining ofindividuals assigned to hey emergency plan positions; c) providing training and exercises ihr fscility personnel and outside agencies; d) procuring equipment and supplies required by the Emergency Plan; c) providing a caitique ofdiills or exe cises for the purpose of updating the plan.

O conducting the biennial ieview of the plan; l g) coordinating plans with other applicable ciganizations.

l Line of Sqqqqisi 'o EC Opciations Supcivison Senior lleactoi Operator 3.1.3 [kanm Opstumfl(O / SROJ The Itcactc.r Operator is iesponsible fm the shutdo on und seeming of the ienctors in emergency situations which occur during teactor operation. The operator shallinfonu the Duty SRO of the observed action levels and shall tahe immediate action in case of possible reactor damage or uncontiolled radioactivity release. The operator shalliefer to EPIP-02," Reactor Operator Inunediate Action Procedures"and rPIP-03," Nuclear Reactor Lab Emergency Call List Intmsion/ Emergency" for guidance and for details on other responsibili'ies.

3.1.4 Eintigency Radiglion Protec11cn Manager LFSPM)

The Reactor llealth Physicist is the dmergency Radiation Protection Manager. The ERPM is responsible for the initial essessment of actual or potential radiological hazards onsite and offsite, This iesponsibility includes: onsite and offsite dose assessments, recommended protective actions, and all radiation protection senices within the provisions of the Emergency Plan. The ERPM is also the Emergency Director until the ED anives. The details of the ERPM's iesponsibilities may be found in EPIP-06. Other iudividuals that may act as ERPM if the primary ERPM is not available aie:

Lipuduq.q.qssion to ERPM: Reactor Health Physicist Assistant Campus Radiation Safety Omccr (RSO)

Radiation Safety Omce Health Physicist 3.1.5 Emergency Plant Senices Manager (EPSM): Medical, Security, and Fire.

The Duty Senior Reactor Operator (SRO) is the EP5ni and is responsible for obtaining Frst aid, policg and fire fighting assistance from tlie Senior University Police Omcer or the Senior University Fire Omcer On Duty as warranted by the situation. The EPSM is responsible for assessment of actual or potential security aspects of all radiation emergencies and shall provide advice and consultation to the ED on all matters: elating to security and trame control upon activation of the Emergency Plan. In addition, the SRO is respocible for advising the ED on Plant Services and Equipment and for obtaining needed equipment fJom the University Operations and Maintenance Depanment. The details of the EPSM's Page 9 of 29

sesponsibilities may be found in 1: PIP-07. Other individuals that may act as I!PSM if the piimaiy l!PSM is not available arc.

litted.S.!Lcesssion to._UPSht: Any SRO Reactor llealth Physicist Safety Specialist fiom Dell &S l

3.1.6 limergency PublirJttfontLation Maitayer (EPIM)

The ficad, l>cpartment of Nucienr 1:ngineering is the EPIM. He EPIM shall piovide infonnation, as discietion dictates, to the University Oflice of Public Affairs, when such infonnation is provided by the Emergency Director. The EPIM shall act as piimary spokesperson for the Emergency Director. He EPIM shallieview all press icleases written by the Univeisity Omce of Public Affairs in the absence of the duly appointed EPIM. the following individuals shall act as temnora:y EPIM:

Miematesjo !!PIM: Assistant licad. Depaitment of Nuclear Engineering

Director. Division of Environmental 1-lealth & Safety l

l

3. I 7 (Aivrisity O@geMPublicAllints De University Office of Public Alliairs will handle all omcial news releases conceming emergency conditions at the Nuclear Reactor Lab. Le Reactor Administrato shall bc tesponsible for the technical content ofinformation prepaied for telease by the Oflice of Public Affalis.

3.1.8 Senioi44iveisilvhliee-oi-Fiie4meer-On-Duty Police. Fire. and Medical Assistance l .

The Senior Univeisityfolice*Fhe4moer-Gn-Duty &cac. lor Operator / Actina Emeigeitev Director or the Emercency Director (ED) shall be authorized to place a call to 911[the Champaign Cotmty Emergency Senices and Disaster Agency (ESDA)] when the need arises and request that ESDA activate the Onsite coordination with the local hospitals and support hospitalacencits. These calls should be regarded as being properly sanctioned by the University. Police and Fire services aie available at all times.

The University Police may be called to provide secutity assistance, emergency radio communications, traflic and crowd control; as necessary. The University Fiie Depaitment may be called to fight a fire.

provide eme gency medical assistance or rescue senices. Both the Police and Fire Depaitments aie instructed, on a biennial basis, on the special aspects of the NRL including building secuiity and fin es involving potenti?) radiation exposure on areas with radioactive material present.

3.1.9 Radigion Saiety Ollice (RSO)

The RSO is the Section within the Division of Environmental llealth & Safety responsible for Radiation Safety en the Campus outside the confines of the NRL. Professional and Technical llealth Physics staff from the RSO are available to assist in the event of an emergency at the NRL. The Director of the Radiation Safety OfIice is also the Campus Radiation Safety OfIicer and shall be notified in the event of an emergency at the NRL.

3.2 Coordination and Notifica_ lion of Fedstal. State. and Local Govemmental Agencie_s The postulated credible accidents associated with the operation of the Nucleas Reactor Laboratory will not result in a radiological hazard affecting the General Public. The credible emergency events will not require the direct involvement of Federal, State, and Local Govenunental 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

~

emeigency messages; to the extent the info mation is known, and dependent upon the agency being notilled; should include some or all of the following:

a) Name, title. and telephone number of the caller; b) The location of the incident and the emeigency class; c) A desetiption of the emetgency event; d) ne date and time of the incident initiation; c)'llie type and quantity of radionuclides ecleased or expected to be teleased f) Projected or actual dose rates outside the operations (site) boundaiy.

g) Ask the recipient of tiie message to place a ictum telephone call to authenticate the message.

3.2.1 Nucl.c;.I Reculatory Commission WRC) and American Nuclean insulns ( ANI)

'Ilie NRC Region ill Oflice ofinspection and Enfoicement is located at Lisle, Illinois. Assistance from this ofIice would be in accordance with the piovisions of the license,10 CFR 20, and commensurate with the seriousness of the emergency. Notification of the licadquancis Opeintions Center at the telephone and facshnile numbeis noted below will icsult in Region 111 being notified in the event of an eme gency, theiefoie, a sepaiate call to Region ill is not icquiied.

Location Telephone Number Availability NRC Operations Center Voice: 1 301 816 5100 24 hotu s/ day Voice backup ; l 301951-0550 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> / day Facsimile: 1 301 816 5151 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> / day NRC Region 111 Voice: 1708 829 9500 24 houis/ day dim!katLMigkatliist!rm(A_NI) V_oice: 1 860 5613433 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> / day Facsiipile- 1 860 561 4615 M_hetu s/ day Ameiioan-Nuc4 ear-Insmeis 2-Voice 4-m-564-3433  ?

224-homs/ day 3.2.2 Chanapaicu County Emngency Services and Disaster Acency(ESD.A)

ESDA has overall responsibility for providing cooidination oflocal police, fire, rescue, and medical response for large scale disasters and emergencies. The Senior University-Police-or-Fire-OfIioer,On-Duty + hall 4>eahe only4ndividuals Reactor Operator / Acting Emercemy Director or the Emernency Direngt(ED) shall be authorized to place a call to-the&hampaigneounty4imetgeney4enseend-Disaster-Agency-(9.11 (Champaicn County _ESDA) when the need arises and rquest that ESDA activate the Onsite cooidination with the local hospitals and support agencies. These calls should be regarded as being properly sanctioned by the University.

3.2.3 U.giversity ofIllinois Police and Fire Departments The University Police and Fire Departments shall provide immediate response to a security event or fire witidn or without the Reactor Building and near environs. The Emergency Director (ED), gran individual such as the4)uty a Senior Reactor Operator (SRO) acting as the ED or at the direction of the ED, shall be authorized to request assistance from the4Jniversity-Police-and-Fire-Depenmentsrer-tocotifv4hernef-a potentiebemergeney-aHhe-NRb-The4enior-University-Polioe+r-Fire-Officer-On-Duty-shall-be4heenly individ u als-a uthorized-to-plaomall4 o4 he Ch a mp aigu4ount y4mer gency4ervioennd-Disast er-A gency Page 1I of 29

(ESDA)when theneed ChaDUMiEiLOHuttJMDLESMWillDEli[YJMIQiVMitJfolieC ADdfitc l Drjuullut!!!UutEgli as otittuunnojuiatutyymit anentigLn[1JmtentialculgingitO9Hlig NRL n oises imd <equest4hurliSDA-notivate4he-Onsite+oordinetionavith4heloeni hospitals-lhesernlls +hould he segneded es being-propenly-sanc4ioned bythe University-1 3 2.4 tjuiysnity Divisiqu oflinvi!ctungntalljealth & Safety 1 DELI &S)

The Director of the Radiation Safety Oflice is also the Campus Radiation Safety Oflicer and chall be notified in the event of an emergency at the NRL "

3.3 Tennittation of an Emercency The Emergency Director (ED)is iesponsible for declaiing the tennination of an eme gency. Psion to tennination 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 he scopened to peisonnel on to the General Public meet the seguirements of 10 CFR 20 and all nicas to be testiicted for entiy m which icquite controlled access nie propenly posted 3 4 outhorization for Re9H10' The Eme gency Directoi (ED) shall autboiite any icentiy into the NRL, os poitions the cof, pieviously evacuated during an eme gency. in accoidance with the guidelines established in 1: PIP 10,"Reentiy and Recove y Proceduies" 3.5 Aullwiization for Planned Snecial Exposutes With the concurrence of the Head of the Depaitment of Nuclear Engineering and aller consultation with the Emergency Radiation Protection Manager, the Emergency Director may authoiize Planned Special Exposures for emergency team members. The critesia used to establish exposure limits for this authorization shall be in accordance with NRC Regulatoiy Guide 8 35 " Planned Special Exposuies.

4.0 EMEllGENCY ACTION LEVELS (CALs) AND EMEllGENCY CLASSIFICATION SYSTEM The Emergency Action Levels (EALs) and Emeigency Classes d: scribed below for the Nuclear Reactor Laboiatoiy aie based on credible accidents associated with reactor opeiation and other non icactor safety ielated events that have minhnal, if any, radiological consequences. Moie specific guidance on any of the topics listed in Section 4.0 can be found in EPIP-08, " Emergency Action Levels (EALs) and Emergency Classification Pioceduies" 4.1 NLon-Reactor Safety Related Event (NRSRE)

This class of emergency 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 Emercency Action Levels (EALs) or events shall initiate emergency measures associated with this Emergency Class.

a) Significant persormelinjury with or withont radiological complications.

b) Minor fire or explosion not specific to the reactors.

c) Significant contamination of an individual or of the facility.

d) Civil disturbances or receipt of a bomb threat that is not specific to the Nuclear Reactor Lab.

Page 12 of 29

- )

• L

. . j.

C More specific guidance on this topic can be found in 1:Pll'-08. "limelpency Action i evck (FAl.s) and limergency Classification Procedures" k 4 2 tiotifiutinndunusual livent (NOtK)

This class ofemergency consists of an event that may be initiated by either man made os natuial phenomenn that can be recognized as cicating a significant hazaid potential that was previously nonexistent. '1hete is usually time available to tabe precautionary and conective steps to pievent escalation of an accident or to mitigate the consequences should it occui. No ecleases of endioactive material requiiing offsite response ate expected. Some elements of the Emergency Organization may be activated or notified to incicase the state of readiness, as warranted by the circumstances Ahhough the situation may not have caused damage to the reactors, the reactors shall be shutdown.

The following Enttigt!Lc16slism I evels (lidlenements shall initiate emergency mensmes associated with this Emergency Class:

a) Aginnlor proitstedndiolonicaj_gj]utnis at thLsittinpeLntions) boundaty calculated to produce a whole body 410seef46anRem QLejtQgEg.jiquivajenLIDDji).nf.j $ mrem (0 l 5 mSy) accumulated within 24 houis.

i)'Ihe following guideline shall be used to calculate thisjuojectedslose a Committed li(rective Dosq

[Lquivalent (CEDE):

50 8-EC

• 24-houiss.-14-mRemMHlobletaseS) 400 *-EG 8-24-homs*-14anRem&i-nuelides+theHhan+0ble-gases) 3 100

• EC

• 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> = 2.4 E EC-br = 15 n1 Rem (0.15 mSv) for indionuclides other than noble galg3 50

• EC

• 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> = 1.2 E' EC br = 15 mrem (015 mSv) for noble gases l Mnts: EC = EfIluent Concentration values listed in 10 CFR 20, Appendix 11_. Table 2.

This can be detennined by obseiving the followinc y on levels ottihe facility :adiological mopitors-ii) Area Radiation Monitors (AllMs) > 20 mlUhr for the West and I.obby and Rggeto Top ARMS f(n more than 10 minutes with the reactor shutdown and no other sources of radiatin!unesent and; iii) Continuous Air Monitors (CAMS): Menanine and Reactor Top CAMS > 2000 cpm above background and Exhaust Stagj; Monitor s380 epi Note: If the East ARM is greater than 20 mlyhr. this is an Alert. Proceed to section 4.3 b).llsport or observ_a. tion of severe naturalpjtengmena. such as torn 3does in the immediatnicinity of the Nuclear Reactor Lab. or canhquakes felt in thg 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 CO2 extinguisher and requiring the assistance of the University Fire Department for control.

e) Eailure of a fuel element or failure of an experiment with a release of radioactivity.

Page 13 of 29

O9LTMFWW O

?

@ More speci6c guidance on this topic can he found in 1:l'11'.08. "limergency Action Levels (EAl.s) and

^ Eme gency Classi6 cation Piocedures" 4 3 Alen This class ofemergency consists of events that would be of such radiological significance as to require notification of the Emergency Response Organization (ERO) and their sesponse 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 conective action.

k Protective e,acuations or isolation of certain areas within the operatiens (site) boundary may be necessaiy.

Situations that may lead to this class include: 1) severe failure of fuel cladding on of fueled experiments wheie ~

containnwnt boundaries exist to redu releases or less sevene cladding failures in situations where fission products are not well contained, of 2) significant release of sadioactive mateiial as a iesult of experiment failuies.

9 1he following liturtatitty_^SitotticielsflMLSlm_cXents shall initiate emergency measures associated with this Emergency Class:

a) Actual.ntJ1LojtEled iadigipnit altal ittnis at the sitelupetations))oundaty calculaica to pioduce a whole body 41meof4hnRem Qcep Dose lhjoivalent (DDii)_of 75 uRem J (0.75 mS39 accumulated within 24 houis.

i) The following guideline shall be used to calculate a Committed Effective Dmiliquivalent (Clil1111; thistiojecaed<loset 250 LEC ' 244touis*45anRemffor-nobletases)

GOO 14?CA244ouis*>hnRem{formuclides+thet-thou+obletases) 100

• EC

• 24 ho4Ls = 12 E' EC br = 75 mrem (0 75 mSv) for utdionuclidesnther than noble gases 250

• EC

• 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> = 6_0 E' EC br = 75 mrem (0.75 mSv) for noble gusts Nntg: EC = Efiluent Concentration values listed in 10 CFR 20dppIndix IL Table 2. l 111itt31Lbe delennined by observine the [g]lowingjgdiation levels on the facility indiologigaltnonitors:

ii) Area Radiation Mnpitors (ARMS) > 100 mi%r for the West and I,nhiapnd ReactorTop ARMS foi more than 10 minutes wath the reaglor shutdownJnd no other so3nces of rajligi_qttpresenimut; iii) Continuous Air Moni!nts (CAMS) MeznJtine and Reactor Top CAMS > 10.000 cpm abovs hat.kground and Exhaatst Stack Monitor > 999 cp1 b) Actual or projected radiation levels at the site (operations) boundary of 20 mrem'hr for+ hour + hole body (0.2 mSv/hr) Deep Dose Egivalent (DDE) for 1 hotg, based on East Wall Area Radiation Monitor (ARM); or 100 mrem projected 4hyroid41ose-(1.0 mSv) Committed Dose Eouivalent (CDE) to the thyroid, gl3evere failige of fttel claddine. as indisaled by the Detnineralizer ARM alarming with an indication >40 midt and confimied by indications in Sections 7.2 a)ii) & iii) above: or failure of fueled experimegij n!1 pre containment boundaries exist to reduce releases or less seve+e cladding failures in shuntions where fission product _s are not weRsontainedm d) Significant releases of radioactive material as a result of experiment failures.

Page 14 of 29

c) id!a9fPJusdsntittoj of the facility, More specific guidance on this topic can be found in EPIP-08, "Eme:gency Action Levels (EALs) and Emergency Classification Procedures".

4A Sits Aten Emergent.y No credible accidents attributable to the reactor or its operation are postulated which could cause emerge ey conditions beyond the ope ations (site) boundary. Chapter XIV of the Safety Analysis Report (SAR) analyzed a number of accidents, including the release of radioactive efIluents to the environment. De analysis of a fuel cladding failure with complete loss of coolant, and the ventilation system off. indicate that an i

emerrency of this class would never occur. llowever, an emergency condition where the Emergency

' - Response 0 ganization (ERO) may consider setting up traflic control or the evacuationsf adiacent buildings may requite limited ently into the provisions of this classification, Mote specific guidance on this topic can be found in EPIP-08,"Emeigency Action Levels (EALs) and Emergency Classification Psocedules" 4.5 Egnatallitue:gency(Not Applicable)

No credible accidents attributable to the reactor or its operation are postulated which could cause emergen conditions beyond the operations (site) boundary. Chap;er 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 failute with complete loss of coolant, and the ventilation system off, indicate that an -

emergency of this class would never occur. Therefore, this emercency class is not ad_ dressed in this p.lm.

4.6 Enttigegev Actionj,evels (EAls) for Members of thg_Qeneral Public Onsite Before exposure leveh equal to or exceeding the Protective Action Guides (PAGs) of+ Rem wholehod,Wmd Mem: 1 Rem (10 mSv) Total Effective Dose Equivalent (TEDE) or 5 Rem (50 mSv) Committed DoEg

- [igulyalgnt (CDE) to the thytold, within the operations (site) boundary;; have been reached members orthe general public shall have been evacuated from the building.

5.0 EMERGENCY PLANNING ZONES (EPIs) 1 Since the postulated radioactive releases from credible accidents at this facility falls in the first category,

" Authorized Power Level... Equal to or less than 2 MW", in the Section 3.6, Table 2 Guidelines of ANSI /ANS 15.161982," Alternate Method For Determining ne Size of an EPZ" and Appendix 11 of NUREG 0849, the

' EPZ for this plan is established at the Operations (Site) Doundasy and is defined by the Reactor Duilding Walls (Confinement).

6.0 EMERGENCY RESPONSE b.l' Ap1Lvation of the Emergency Response Organization (EPfD The Emergency Director (ED)is responsible for initiating the Emergency Plan and for notifying and '

mobilizing th: ERO. During periods of time when the NRL facility is unattended and an unusual rituation (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 Cal]

_ Page 15 of 29 -

list is kept by the Police Dispatches and telephone numbers are visinic throuph the fiont window of the lab entiance lhe Dispatcher is on duty atound the clock thus ensming that an NRL Sicil'membei on the hst can be notified of an unusual situation. De NRL Staff member notified shall resolve the situation and determine whether a real emergency condition exists if the potential for an emergency condition exists the NRL Staff member shall notify the Emergency Ditector (UD) and take charge of the potential emergency until the ED anives. The ED shall give instructions on steps to be taken priar to the anival of the ED at the Nuclear Reactor Lab and detennine if additional notifications ate wananted More specific guidance on this topic can be found in EPil'-03,"Nucleat Reactor Lab Emergency Call List -

mtnision / Emergency"and EPIP 08," Emergency Action Levels (EALs) and Emergency Classification Procedures".

l l

6.2 l'iolegdve Action Valac3 No credible accidents attributable to the scactor or its operation ate postulated which could cause emeigency conditions beyond the operations (site) boundasy. Chaptes XIV of the Safety Analysis Repon (SAR) analyzed a number of accidents including the telease of radioactive efDuents to the envitonment. 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 whole4,ody (10 mSv) Tota 1 Effective Dose EquivalenLLEQli) i or 5 Rem (50 mSv) Connuitted Dose Equivalent (CQli) to the thyioid foi members of the public offri ts could  !

not bc scached. As stated in Section 4.6 above,"Befoie exposure levels equal to or exceeding the Protective  ;

) Action Guides (PAGs) of-1-Remwhole+ody-andMem: 1 Rem (10 mSv) TotdBTective Dose Equivdeni '

(TEDE) or 5 Rem (50 mSv) Committed Dose EquiyalsatICDE) to thg thyioid, nithiitthe operations (site) I hanudaly;; have been scached nigmbers of the_ general public shall have been evacuated from the building" l Exposures of Emergency Personnel would be expected to be within the limits of 10 CFR 20, however, Chapter XIV of the Safety Analysis Repon (SAR) indicates that, under the worst case scenatio, thyroid doses within the operations (site) boundary could be limiting. The ED has the autho ity to autho ize Planned Special Exposutes as desciibed in Section 3.5 above,"With the concuneace of the liend of the Depanment of Nuclear Engineesing and after consultation with the Emergency Radiation Piotection Manager, the Emergency Director may authorize Planned Special Exposmes for emeigency team members. The criteria used to establish exposure limits for this authorization shall be in accoidance with NRC Regulatory Guide 8.35 " Planned Special Exposures" 6.3 liintigency Response for a Non Ruttor Safely 2siated Event (NRSM) 6.3.I Activation of the Emergency OrganintioJ1f9tj NRSE The complete activation of the emergency organization foi this emergency class would not nonnally be required. The Emergency Director (ED) shall activate that ponion of the emergency organization necessary to respond to the event.

6.3.2 Assessment Acdons for a NRSRE This class of emergency consists of events that do not endanger the General Public. Notification of, or assistance from, the Uitiversity Police and Fire Depanments may be warranted. The following onessual 6.9110Bs shall be considered appropriate for this Emergency Class:

a) Sitnifigant personnel iniury with or without radiological complications: The ED shall assess the Page 16 of 29

extent of the injmy and whethei sad.oactive contamination is present lhe assessment will consider the nature of the injury, the appropriate liist aid, the need liu tiansponatmn to medic.il ticatment facilities, and the levels of radioactive contamination, if piesent.

b) Minnt fire or explosion not snttift9JAthttruints: He ED shall assess lite of explosion events to detennine the magnitude of the event, the need for piompt contiol. and the need for suppon from outside agencies. %e reactm staff will monitor the area to detennine if radioactive contamination is present c) Sigttifiqant contaminationi of an individual or of the faqi!jly. Significant personnel contamination that repeatedly fails to be removed by ordinary decontamination pioceduies shall be evaluated by the ED for possible consultation with appropriately trained medical personnel before further decontamination is attempted. Significant contamination of the facility shall be assessed by the ED, aller consultation with l l the limetrency Radiation Protection Manages (ERPM), to detennine whether a formal decontamination pioceduie needs to be developed for this event.

d) Civil disturbances or neceipt of a bomb threat that is not s!!tgingjo the Nitticar Reactor Lab: Civil distuibances shall be evaluated by the ED, for potentialimpact on the facility. alles consulting the t

Univeisity Police and Campus Administintion. Ilomb tlucats shall be assessed by the ED. Ibi validity.

atlet consulting the University Police and evaluating the inibnnation souice.

6.3.3 Conective Actions for a NRSRB This class of emergency consists of events that do net endanges the General Public. Notification of or assistance from the University Police and Fire Depanments may be wananted. The following Conective Agiinns shall be considered appropiinte for this Emeigency Class-a) Sinnificant personnel inimv with oi willtmLLtJ4inlogical complications: For cases of personnelinjury with or without radiological complications, the ED shall detennine what medical assistance is needed. and l may contact the Police @ispatcher Champairm County ESDA at 91 I to request transponation. If the injured individual is contaminated, decontamination will be attempted only ifit isjudged that this will not funher aggravate the injury. A contaminated injured individual will be transponed using contamination control and isolation methods.

b) Minor fire or explosion not spegiDe to the teactois: For minor fires or explosions not specific to the l reactor-or-itwontrol-systems or their control systems the ED shall be notified and reactor stafTmembers shall attempt to control the fire with ponable fire extinguishers ifit is safe to do so. The ED shall determine if the scope of the fire or explosion requiies the assistance of the Univeisity Fire Depanment, l and if so, the Dispatcher-shalWe-notified: Cliampairm County ESDA shall be notified at 911.

c) Significant contamination of an individual or of the facility: The ED, after consultation with the limernency Radiation Protection Manager (ERPM), shall detennine the decontamination procedure appropriate for the individual or the facility. Goals shall be established to determine when funher decontamination is not warranted. These goals should consider returning contamination levels to 10 CFR 20 limits.

d) Civil djs!mbances or receipt of a 1,omb threat that is not specific 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 property. The ED shall notify the licad of the Department of Nuclear Engineering and keep him infonned of the emergency status.

Page 17 of 29

6 3 A lio ktiive k lio MetaMRSRB Some piotective actions at this level of eineigency (e p., fue alanus) necessitate the evacuation of the Reactor lluilding. In this case teactor stafTmembers will assemble at the nonh entrance to the Nucleai Engineering Laboratoiy to determine if their services are needed All evacuations will be initiated by notifying personnel on the public addiess system Should fire m other event involve areas with indioactive material, the ERPM shall contial access to the niens and shall be iesponsible. with suppon from the reactor staff, for the segregation of potentially contaminated pelsonnel.

More specific guidance on the methods, systems. and equipment foi gathering and piocessing infonnation and data on which to base decisions to escalate or de escalate emergency sesponse actions are contained in EPIP-09," Assessment Conective, and Protective Action Procedures" Other specific guidance on this topic can be found in EPIP-08. " Emergency Action Levels (EAl.s) and Emcigency Classification Procedures" 0 4 Emtreenev Resanme_futa Notihntion of thwtuaLErgnt (NOUE) 0 4. l Mtjygtion of thtynteistilgy_Ojanindon foi a NOtX

'lhe complete activation of the emeigency oiganization for this emergency class would not nonnally be acquited. The Eincigency Director (ED) shall activate that portion 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 natuial phenomena that can be iccognized as cicating a significant hazald potential that was previously nonexistent. There is usually time available to take piccautionary and conective steps to prevent escalation of an accident or to mitigate the consequences should it occur. No selens:s of radioactive insterial acquiring offsite iesponse ate expected. Some elements of the Emergency Oiganization may be activated or notified to incicase the state ofreadiness, as warranted by the circumstances. Although the situation may not have caused damage to the scactors, the reactors shall be shutdown.

6 4.2 Assessment Actions for a NOlJE a) Actual or projected radiologini emuents at the site (oitentions) boundary calculated to 11taduceJ whole+odulose-of&nRem Deep _D.qEe Equif alent (DDE) of 15 mrem (015 mSv) or a Committed j

Effective Dose Equivalent (CEDE) of 15 mrem (015 mSv) accum.nlaEd within 24 Itonts: Fuel damage,!

experiment failure, o, any event manifested by unusual radiation levels within the Reactor Laboratoiy, or the release of radioactive emuents offsite, shall be assessed by the ED with assistance from the reactoi staff. Additional suppon for assessment shall be requested from the Radiation Safety OfIice (RSO), if needed. The assessment shall consist of an obsen ation and evaluation of the facility Continuous Air Monitors (CAMS) and Area Radiation Monitors (ARMS)in the control room and by surveys with portable ion chambers or other appropriate survey instruments. Both itigh 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 resuhs can be used to assess whether the source is due to fission products, activation products, or a non-reactor source. Excessive airbome or radiation levels may require evacuation of the Reactor Building and funher assessment will be made from outside the facility with the information provided to the Emergency Support Center (ESC).

b) Report or observation of severe naturalylttnomena. such as tomadoes in the immediate vicinity _of the Nuclear Reactor Lab. or canhquakes felt in the fa.til.ity: This situation requires immediate shutdown of the reactors and notification of the ED. The ED shall establish contact with the Univevsity-Police l Page 18 of 29

, e l Dispatcher Chaj] gig!1fanity ESDd foi funhet assessment of the seveie natuial phenomenon and foi recommendations on seeking sheltei at appiopnate assembly areas c)'DILgMs to or bigqhes of sectnitydnglutLa bomhjhtgat of civil distuihti!tgrupscific to thg.Eglgj!!

lig3SigLbth: Civil disturbances shall be evaluated by the ED. for potential impact on the facility. alles consulting the University Police and Campus Administration. Domb thients shall be assessed by the ED.

for validity, aller consulting the Univeisity Polict and evaluating the infonnation source.

d) [itMLg3plosion witidilthe fasiblykaLeannot be controllgd immediately with an onsite CO 2 q31inguisher and_rsauirine the assistattge of the University Fire Depanment foi control: The ED shall assess the severity of the fire or explosion to detennine if the assistance of the University Fire Depanment is required.

c) EnihnufAfuel elementotinihite of an eweriment with a telease of,Ladinasdyily: The assessment actions for this event are the same as those detailed in 6.4.2 a)immediately above.

Mose specific guidance on the methods, systems, and equipment for gathering and piocessing infonnation and data on which to base decisions to escalate or de-escalate emergency tesponse actions nic contained in 1: PIP-09," Assessment, Conective. and Piotective Action Piocedures". Othei specific guidance on this topic can be found in EPIP-08, " Emergency Action Levels (EALs) and Emeigency Classification Procedules" 6.4.3 C_Qnective Actions for a NOUJi a) A_q1 pal or pioiected radiological ellluentiat the site (opetations) boundatY calgulMed tutgduce a svl]t91e+odyslose-of4-kmRem Deep Dose Equivalent (DDE) of 15 mRent(0.15 mSv) or a Committgji Effective Dose Equivalent (CEDE) of l$ mrem (0.15 mSv) accumulated within 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s: Ifa Notification-of-Unusual 4ivent NO_tg is dictated by assessment of high radiation or airbome indioactivity levels, the Reactor Building shall be evacuated pending an evaluation and identification of the piobable source. The ED shall direct the ERO to control access to the Reactor Building until radiation and airbome activitylevels have been iestored to nonnal. All personnel that were evacuated fiom the Reacto:

Duilding shall assemble at the nonh entrance lobby to the Nuclear Engineering Laboratory (NEL), which is the Primary Emergency Suppon Center (ESC); or at the nonh entrance lobby to the Division of Enviromucutalllealth & Safety (DEH&S), which is the Alternats Emergency Suppon Center (ESC). The location of these buildings is shown on the detailed map (Attacluneut 2). Both buildings are within 150 yards of the Nuclear Reactor Laboratoiy. 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) Rgpon or observation of severe natural phenomena. surJLas tomadoej in the immediate vicinity 2f the Nuclear Reactor L.pb. or canhquakes 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 4)ispeteher Champaign County.jiS_D_A for further assessment of the severe natural phenomenon and for reconunendations on seeking shelter at appropriate assembly areas.

c) Threats to or breaches of security. such as a bomb threaLor civil disturbance. specific to the Nucigju Enctor I ab: 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, after consulting the University Police and evaluating the information source. The police l may l initiate controls to insure the protection of personnel and propeny. The reactors shall be shut-down and Page 19 of 29

e, pelsonnel evacuated to the Nuclear lingincenny Labointory on the I!SC All pelsonnel who weie in the facdity at the tiene of the emelgency shall be accounted fin.

d) Ei i.c_QLe.splosion within the facility 111ALW!ilgt be cottisolled imtnediatelv willt an onsite CO2 tslitigunber altittquiring tl tissistance t of tht.Unive sity Five Deltantitent for contin] ne-lid shall '

a ssess4 hei,eveiit y-o f4 he fu eci-evplosiend o <leten nine 4 f t h e-a ssist a nee o f4 h e4)niver sit y-Police-e nd fin e Depai1ments ereaequired-ne police or fine department may initiate controls to ensure the piotection of .

personnel and property. He scactors shall be shut down and personnel evacuated to the Nuclea l

Engineering Laboratory or the ESC. All personnel who weie in the facility at the time of the emergency shall be accounted for.

c) failule of a htpl elemeyLgL[ajl!LgJf_ tin cN!q.tillignLuith a sekate_ofindioactivity The corrective actions foi this event aie the same as those detailed in 6 4 3 a)immediately above.

6 4 4 Protective Actions for a NOUG If the Reactoi lluilding has been evacuated, all personnel who weie in the facility at the time of the eme gency shall be accounted for. Allindividuals who evacuated the Reactor lluilding shall be smveyed foi contamination with portable instmments. Dose individuals who alc contaminated shall lemain in an anca designated by the ED oi BRPM for decontamination. He ED is icsponsible foi limiting access to the Reactor Building to iescue and emergency nesponse opeintions personnel He ERPM is responsible for  !

minimizing personnel eq)osuie and the spicad ofcontamination. Emergency exposme levels for personnel shall be in accordance with Section 3.5 of this plan.

Moie specific guidance on the methods, systems, and equipment for gathening and processing information and data on which to base decisions to escalate or de escalate emergency iesponse 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" 6.5 Emergency Response for an Alen 6.5.1 Activation of the finescency Organization for an Algn The g_qiunlete activajon of the emergency organization for this emergency class iasttitsd. The Emergency Director (ED) shall activate the entire emergency org,nization in response to an event of this class. This class of emergency consists ofevents that would be of such radiological significance as to require notification of the Emergency Response Organization (ERO) and their response as appropiiate 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 ceitain 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 i'i situations where fission products are not well contained, or 2) significant release of radioactive material as a result of experiment failures.

i' age 20 of 29

o 5.2 AmsminLMiinnihtJ!LAlta a) 6ttynhtplojtLLc11.JLdigjpgical ellhtentLal11gjitglgp_ gin 11pns) bmm.diuv calculatssLtg_ptgdageat whole body <loseof-7kmRe:Rjlefp Dose EquivalentfilDE) of 75 mRegi(0 75 mSv) or a Committed Elfsetive Dose Equiulent (GilHlof 75 mrem (0 75 mSv) accumuhited within 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s: Fuel damage, experiment failure, or any event manifested by unusualindiation levels within the Reactor Laboratory, or the sclease of radioactive efiluents offsite, shall be assessed by the ED with assistance from the teactor staff. Additional support for assessment shall be icquested from the Radiation Safety Office (RSO),if needed. He assessment shall consist of an observation and evaluation of the facility Continuous Air Monitois(CAMS) and Aiea Radiation Monitois (ARMS)in the contialloom and by sutveys with ponable ion chambers or other appropriate survey instmments. Both high and low volume air samplers are available and collected air filters and smear samples can be counted in Room 106H NEL or, for gamma spectroscopy, in Room 222 MRL. The sesults can be used to assess whether the souice is due to fission pioducts. activation pioducts, or a non icactor source. Excessive aisbome or indiation levels may icquite evacuation of the Reactor Building and funher assessment will be made from outside :he facility with the infonnation provided to the Emergency Suppon Center (ESC) b) Miual or piojgstqd sadiation levels at the site (ongations) bi nuidnLuGO mlig10 /hr (0.2 mSv/ht) whole+ody foH-hout Deep Dose Equivalent (DDEHor i hour. based on East Wall Area Radiali.on Monitor ( ARM): oi 100 mRemiusjectedahvioid41ose mrem (l 0 mSy) Committed Dose Equivale:11 (CDE) to the thvioid: Same as in a)immediately above, c) Seveie failuie of fuel cladding or of fueled expetiments wheie containment boundaiics exist to indug.g teleases m less eveie cladding failures in situations where fission products are not well ganlahtssb Same as in a) & b)immediately above.

d) Significant releases of radioactive natenial as a result of exocringut failures: Same as in a), b),-&

trtd_c) immediate!y above.

e) Loss of pjlysical contiol of the facility: The ED shall consult the Univeisay Police, the Nuclear Engineering Depanment liend, 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.

6.5.3 Conective Actions for an Alen a) Actual or projsets.d radiological efiluents at the site (operations) boundalv calculated to produce a wlioletody-dese of 75anRem Dg_ep Dose Egivalent (DDE) of 75 mReml0.75 mSv) or a Committed EffectiveJose Equivalent (CEDE) of 75 mrem (0.75 mSv) accumulated witjiin 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s: Ifa Notification of an Alen is dictated by assessment ofhigh radiation or airbome 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 nonnal. All persoimel that were evacuated from the Reactor Building shall assemble at the north entrance lobby to the Nuclear Engineering Laboratory (NEL), which is the Primarv Emergency Suppon Center (ESC); or at the north entrance lobby to the Division of Environmental licalth & Safety (DEHAS), which is the Altemate Emergency Support Center (ESC). He location of these buildings is shown on the detailed map (Attachment 2). Both buildings are within 150 yards of the Nuclear Reactor Laboratory. Si: ce 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.

Page 21 of 29 4

o

b) ocitM1ou1Lojt91td.Ut d jalioJLlevch>L1hejtglannatimts) houndaryM10 mReny]itJ01nSv/ht) h!!!ddP!ylethh0MLDECRE!!E935QiliYJtLe11t(DilOfutlltm!LlutusLWLliRM Wall Attdadiation I

Moni19tIARM): or 100 mRenutt9jesmLil l vividsle2s.mRetit(M ttisv) iC numitirincaliquiraletti (CDJi) to the thvioid: Same as in a)inunediately above.

c) Severe failme of fuel cladding or gfftteled experimentLwittitSattalmneatt.l!mmitalies esist to tq1dnF_4 teleases or less severe clad1 1jngfailuies i Lsititatji 3t tis where fissiosuudpIls aie not welj contaittg5j: Same as in a) & b)immediately above d) Siemftcant releases of radioactive malerial as a sesult ofexpenment failutgr Same as in a), b),-&

altic) immediately above.

e)1,oss ofyjiysical control of the facility: 1he ED shall consult the University Police, the Nuclea l Engineering Depanment licad, and the Campus Administration on steps to be taken to regain control of l

the facility This will depend entirely on the natme of the loss of control 6.5A boLettive Actioitsfittfu1Alfo If the Reactor 13uilding has been evacuated, all personnel who weie in the facility at the time of tiie emergency shall be accounted for. Allindividuals who evacuated the Reactor 13uilding shall be suiveyed for contamination with ponable instruments. Those individuals who nic contaminated shall temain in an area designated by the ED or ERPM for decontamination. The ED is responsible for limiting access to the Reactor lluilding to rescue and emergency response operations. The ERPM is responsible for minimizig personnel exposuie and the spiend of contamination. Emergency exposure levels for perronnel shall be in accordance with Section 3.5 of this plan.

More specific guidance on the methods, systems, and equipment for gathening and processing infbnuation and data on which to base decisions to escalate or de escalate emergency response actions are contained in EPIP-09," Assessment, Conective, and Piotectis e Action Proceduies". Other specific guidance on this topic can be fomid in EPIP-08,"Emagency Action Levels (EALs) and Emergency Classification Proceduies" 6.6 Site Area Emergqilty No credible accidents attiibutable to the ienctor or its operation are postulated which could cause emergency conditions beyond the operations (site) boundary. Chapter XIV of the Safety Analysis Repon (SAR) analyzed a number of accidents, including the release of radioactive emuents to the environment. The analysis of a fuel cladding failure with complete loss of coolant, and the ventilation system off, indicate that ai!

emergency of this class would never occur. Ilowever, an emergency condition where th: Emergency Response Organization (ERO) may consider setting up trame control or the evacuation of adjacent buildings may require limited ently into the provisions of this classification.

7,0 EMERGENCY FACILITIES AND EQUIPMENT 7.I Entemency Support Center 3 The Nuclear Engineering Laboratory (NEL) is the Primary Emergency Support Center (ESC) and the Division of Environmentallicalth & Safety (Dell &S)is the Alternate Emergency Support Center (ESC).

The north building entrance lobby of each building shall constitute the assembly area. The location of these Page 22 of 29

.o

a

' 8 buildings is shown on the detailed map ( Attachment 2) lloth buildings are within 150 yards of the Nuclear Reactor Laboratory. Since one is in a westeily direcuon and the other m an easteily diicction. the choice could depend on the wind direction. De purpose of these facilities is to provide; a conttol center, an accountability station; and a radiological monitoring area for frisking of pessonnel and evaluation of sadiological samples Room 106B in NEL is designated as the nadiological counting ioom and the Emergency Equipment Locker is located there. Emergency Response diiections would be given fiom one of these locations. Telephones and fax machines are available in both locations and the telephones and fax machine in NEl. are under the control of the Nuclear Engineering Department. In addition, dedicated telephone lines are l

' on each telephone in the Reacto lluilding. Dese are anpublished numbes s to be used only in an emergency.

l Fax capability is also available by computer modem on sevetal ons of the computels in the Reactor fluilding, 7 2 A_E19MDLci1 lea.gilities

'lhe Reactor 1.ab has Atea Radiation Monitors (ARMS) with sendouts and alarm indications locally, by each t

ator, and in the control room; and Continuous Air Monitois (CAMS), both ofwhich acadout locally and one of which reads out in the control soom and prmides a building wide alann, as well as a trip that closes the damper in the Building Exhaust Ventilation System sending the ait effluent thiough a charcoal filten bed piior to release out of the stack at an elevation of 60 feet above grade. De Depaitment of Nuclear Engineeling has counting laboiatolics at 10611 NEL and 222 Mateiials Research Lab (MRL). Portable survey instruments are kept ucar the entrance to the Reactoi Lab and could easily be taken along during an evacuation. In addition, pottable sutvey instruments may be leadily obtained ftom: the Emergency Equipment l Locket in Room 106D NEL, the ILab in Room 222 MRL. and the Campus Radiation Safety Office at the attemate ESC noted above. Gamma Spectroscopy equipment is available in both 106D NEL and 222 MRL and under the control of the Depaitment of Nuclear Engineeting. Ponable high and low volume air samplets ate available in the Reactor Lab and the Emeigency Equipment Locker.

Non radiological monitors that may piovide peninent infonnation include: the piimary and secondaiy contiol consoles, in the control room, which display all reactor status infonnation; a smoke detector in the contiol room; and meteorological data that is readily available flom the Illinois State Water Suivey Office located On Campus.

Moie specific guidance ou this topic can be famid in FPIP 09, " Assessment, Conective, and Protective Action Procedures" 7.3 First Aid. Medical. and Decontamination Facilities Carle Clinic Association would be utilized as the decontamination center by the Champaign County l Emergency-Sen4ces-and-Disaster-Agency @SDA) ESJDA. The " Radiation Accident P ogram" procedmes for Carle Clinic are included in Attachment 5. His hospitalis about 3/4 mile from the teactor facility and is shown on the area map (Attachment 1). Because of the close proximity, transportation would be eithei by University Police, private ambulance senice, or automobiles owned by Reactor Staff peisonnel, if an individual becomes contaminated with no physical injury requiring immediate treatment, decontamination would be done in the Ddecon sink or shower located in the lower level of the Reactor Building. The drains to this sink and shower are collected in the Retention Tank, which is pumped through a 0.45 micron futer and monitored-for-soluble 4adionuclides to a holdutuank where it is satnpled and counted for soluble and insoluble radioactivitv prior to release to the sanitary sewer system.

More specific guidance on this topic can be found in EPIP-03, " Nuclear Reactor Lab Emergency Call List -

Intrusion / Emergency", EPIP-06," Radiation Protection Manager Procedures", EPIP-07," Emergency Page 2;

Medical, Security, Fire. and Plant Services Manaper Piocedures" EPIP-09 " Assessment. Conective, and Protective Action Proceduies" and EPIP 11. "Suppoit Agency Procedures", as well as Anachment 5 7.4 Communigatioigjiquipfugni Telephones and fax machines aie available in both Emeigency Support Centers (liSC) and the telephones and fax machine in the NEL Support Center are undei the control of the Nuclear Engineering Depanment. In addition dedicated telephone lines are on each telephone in the Reactor fluilding. These are unpublished numbers to be used only in an emergency. Fax capability is also available by computer modem on several eng I

! of the computers in the Reactor 11uilding. He University Police can also be summoned on activation of the intrusion alarm system by pressmg a button in the control room. 'Ilie University Police and Fire Depanment personnel also maintain a indio system for communication with the Dispatchen.

Moie specific guidance on this topic can be found in EPIP-07, " Emergency Medical. Secunty. File, and Plant Scavices Manager Procedures" 8.0 ItEENTI(Y AND RECOVERY OPEl(ATIONS This authority is vested with the Eine gency Diicctos (IID) The Reactor 13uilding can be isolated and seemed following any emergency with any operation in piopiess delayed until a complete recovery is made. Since any water would drain to a hold up tank (Retention Tank) and any paiticulate activi:y in the air would be tiapped in the 11 EPA exhaust filters, ample time would be available to meet at some other location and fonnulate plans fin a given scenario. Specific iccovery procedures for an actual emergency event will be w1itten and appioved as needed. Guidelines on iecoveiy and reentry are given in EPIP-10,"Reently and Recovery Procedules" Several of the areas investigated piior to reentry would include:

1. Evaluation of airbome activity adjacent to entiyways and in the building by temote sampling.

2. Evaluation of dose rates on the building exteiior and within the building as conditions wa: Tant.

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 levels have been evaluated. Doses to individuals should be kept within the 10 CFR 20 limits. except for Planned Special Exposures as noted in Section 3.5.

9.0 MAINTAINING EMEllGENCY PREPAllEDNESS 9.1 Igining Initial training will 1,lall be provided to allindividuals occupying positions designated in this plan. 4vhenahis plan 4t as4>een+pp roved 4>ya he-NRG--Heoauseihis-is-Revision-0-of+oompletely-s evised-Emet genoy411a n Emergency-Prepe rednesswill4>equain t eined-as+utlined4n-the-ou rrent-eppi oved3Radin tion-EmetgeneyPla n; Revision- March-1994" 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 whose job 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 assigmuent. He University Police and Fire Department personnel shall be trained biennially on a rotating basis.

Elements of the annual trainine 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

• 0,

3. A review of the Emergency Call 1.ist and procedule l

4. Methods by which to recognize that an adverse radiological condition exists by use of the Contmuous Air Monitois(CAMS) and Aica Radiation Monitors (ARMS)

5. Directions regarding those areas of the lab where a indiological iclease might occur in conjunction with 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 ExcitiEe3 Onsite emergency < hills.aohe conduc4ed+s-netion4hillsn.hnlihe-held <mmu Enigtggn.cy Drills oi Exercias, to be conducted as Action. Dills. shall be held on an attemating annual basis, at inteivals not to exceed 15 months. An ac4 ion < hill A. c tion Drill os Exercise tests the integrated capability of the Emergency Plan, or a component thereof, and may include instniction peiiods to develop and maintain skills in a particulas 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 found in 1: PIP-13. " Drills and Exercises" 9.3 Critiques of Drills attd thessas l A etitique-of-the< hill Ciitique of the Diill or Exercise shall be held immediately following its completion. This shall include comments from those paiticipating, review of problems encountered, conections 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 Ddll and_ Exercise Scen!Ltio3 The Emergency Coordinator, with the assistance of the Emergency Director, shall develop a wiitten scenario l for the conduct ofthe annualmotionshill altematine annual Action Drill or Estreise. at intervals not to exceed 15 months.

More specific guidance on this topic can be found in EPIP-13," Drills and Exercises" 9.5 [imergency Plan Review and Update The Emergency Plan, the Emergency Plan Implementing Procedures, and the Agreements with Offsite l Support Agencies (Chanpaign County ESDA) shall be revised and.aimLated on a biennial basis. Each revision shall be reviewed and appraved by the Emergency Director, the Emergency Coordinator, and the Nuclear Reactor Conunittee. Modifications resulting from actionwirills Asson Drills. Exercisss, or changes in the facility or environs, shall be incorporated into each revision. Updated revisions shall be distributed to all 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 d Gmnmittee 6drninistrator. reviewed by the Reactor Committee. and transmitted to die. 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" Page 25 of 29

O 6 llpgigenoiliquipm;nthtainteMnX9 a:Ld]M!wiljaige

'lhe majoi souices of radiation monitoring equipment that would be immediately available in an emesgency are: 1) the Control Room and Reactor llcalth Physicist's Office at the Nuclear Reactor Lab in os nea the lobby area by the main door; 2) the Radiation Safety Ollice (RSO) at both, a) 101 S. Giegory St , Urbana and b) the Dynamics Testing Laboratory, col E. Cuitis Road, Champaign; c) Room 106B NEL; and d)

Room 222 h1RL. Additional equipment, if the need arises, may also be made available from the various

! facilities that utilize radioactive material on the University ofIlli mis Campus. Lists of equipment available at the majoi sources are given in Section 9 5.1 below.

More specific guidance on this topic can be found in EPIP 14," Emergency Equipment Mainteuance and Surveillance" 9 6 I inventory of Eggjp2 pent and SuppJigj The instruments that would be used in an emergency ate those that are used soutinely for monito ing radiation and contamination levels at the Nuclear Reactor Lab, those instruments dedicated for use in an emergency and stoicd in the Emergency liquipment Lockci in 10611 NEL, those instruments available within the Depaitment of Nuclear Engineering (piimaiily ganuna spectiometers)in 10611 NEL and 222 MRLrmd e l those-in stiu men t samd es h ewn t foi-o f-t he-Ra dia t ion 4a fet y4 fliee4 REG) 4 h a t-a t e + sed +a mp u savide4+c vaiiety+f-puiposes The Reactor Lab instruments are function tested as part of the " Health Physics Daily Checklist" on each day of the work week that the scactors nic opeinted, all other portable instruments.

including those stated in the Emergency Equipment Locker, aie functionally tested as part of their semiannual or annual calibration. The minimum frequency for inventony of Emergency Equipment and l Supplies shall be annually, at intervals not to exceed 15 months, and include allinstmments listed in this section of the Emergency Plan.

More specific guidance on this topic can be found in EPIP-14, " Emergency Equipment Maintenance and Surveillance" Nuclear Reactor Lab Equigntent:

Total Number Available Equipment Designation Range 21 Victoreen 450 (lon Chamber) 0 50 R/hr l 1

Ebeiline RO - 2 (lon Chamber) 0 5 R/hr 1 NeutrottRem Meter 0-slendg 4 DosipoleiCdTe4emiconductor-) 0-lOOO-RAu 2 Neutron 4em-Meters 0-4-end-0-2-Remthe 8 Electronic Pocket Dosimetes.; O - 9999 mrem i 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 Jolmson GSM 15 Count Rate Meter 0 - 500,000 cpm 1 Johnson GSM-5 Count Rate Meters 0 50,000 cpm 1 Eberline BC-4 Beta Counter 0 999,999 Counts 1- Ebtriine SAC-4 Alpha cotmter 0 - 999,999 Counts 1 Canberra HPGe y ray spectrometer 0 - 3000 kev 1 Alpha Scintillation Probe ASP-2 NLA 4 Genberra-Nol--y-rev+pectrometer 0-2000-kev 4 Alpha,Sointillation-Probe-ASP-2 N/A Page 26 of 29

I IIP 210'l ICbe N/A l iip 205 l> robe N/A I IIP 260 P iobe N/A l

[itut!ggngylgtjipment Logip1(10611 NIIL):

Total Number Available 1:quipinent Designation ilatige i Victorcen 450 (lon Chambes) 0 - 50 R/hr i Eberline E 140 Count Rate Mete 0 - 60.000 cpm  !

5 Quanz Fiber Dosimeters 0 200 inRem 2 Quartz Fiber Dosimeters 0 600 Rem i Dosimeter Change N/A l l 120 V. A C. Air sample: 0 - 100 Ipm l 10 50 nun Glass Fiber Filtes Papeis N/A

_I Johnson GSM 5 Count Rate Meters 0 - 50,000 cpm i lip 260 Piobe N/A l .

Johnson GSP 2A -Nal Piobe N/A 3 boxes 100 each Paper Smeats N/A 9/l 1 Protective Clothing Coveralls /Iloods N/A l 24-pains l_Dorep Rubber Gloves and Liness N/A l 62-pait s4_Doren Plastic Shoe Coveis N/A LDozer) Ba@ns N!A 0-paits Plastio41oot-Linets N/A 4%niis Rubbeis N/A Rediat ionf a fet v-Omoe4 R6014iquipment t

~

Total-Number-Available Exiuipment-Designation l Range 6 Geigei-Muellei-instiuments 0-60A00+pm 3 leenergy-ganuna-Nol-deteetor lodine +uiveys-and-thyicid+ hecks 1 Low-VoluineAir4amples dependent-<meinc+used I liigh-VelumeAir4amples dependent-on-orifice-used 4 fonization-Ghamber-instiument 0-2-R/hr 4 fonization-C-4 ambet-instiument 0-24-PJhi 4 fonizationehamber-insttument 0-4Nir 4 bow-energwii-ionizatioiHHelet- 0-00005400-R/la 6 Quanz-Fiben-Dosimeters G-200-mR

+ Liquid 4eirtillation-Gounter 0 0,9^9,999 Counts 1 Gas 4aw-Pioponional-Gounter 0 "99,999 Counts 6 14P -265-Piobes N/A 4 Alpha 4cintillation44obe-ASP-2 N/A

, 2 Dosimeter-ehangets l N/A Badiation4afetwomeMRSO14*iboratorvAna yjt j oal& ui.l pane.nb Int em al4iquid-scintilla tion-spect rophotometer Gas 4ow-proportional-counting 4ystem Nal-(T4)-MultichannelAnalyzer Page 27 of 29

t u , .' ,

l Secondo s ystondee d wm den see -Roent gen-metes t

Ga p in t co+econd a ey 4,t a u d a id-elect i o met e Nott-31isfjuijuneosatonid bewwshdtl_ebulis31elinni;1]heselittolef-thehentoMt!t(Eni-MupLent i

lintllniintlhtta1110tutter Mm n el-ME9fedfLEsscair!Llat) i M RL) IWari 222

)

.; E!1tal Nunjher Avail 2e Equipment Designation Range

_ ,_ 1 _ Victojeen 450 (19n Chamher) 0 50 IWr 1

__ _ ,lpbnsorLGSM 11C910LRatglieter 0 - 50_0,000 cprg 4

1 .. , ,,, , ,, _ IIP:b5 Probe N/A l 2

_ l Gamma Spectioscopy thytots -N/A l N_01tAtaninimum equijunent tcauired to be ojttttible at alltiuntt9Jnaintain Emerge.ncy Prelinsdness shall be:

J lon Chamhg1,.1Self Readinrt Pocket Dojiimeten I Count Rate Meter with G M papbe. and I Air Sjijpjtler This conipment shall be located inflic limernettsy_{Lquipinent lacket in IWpm 10611 NiiL ILa_t ,

l amjiing any of tlic above listed equipment shnitld become ingperab!p_!Lhhall be imniediately senlacsd.

9.6.2 Radiation Monitorintt Equipment Calibration All ponable insttumentssueelibrated<m-enanmuel+asiscalland laboiatory analytical instruments are calibiated at-least-oncetee-yeat--The-two+econdasystendaid*any-and-gainmaieyeposuie4 ate-insteumonts aieclibtated 5er-menufacturer4nstructionsel-evetymotenton 1 an annual basis.

More specific guidance on this topic can be (bm d in EPIP-14, " Emergency Equipment Maintenance and Surveillance".

-9 7 [imergency Plan implementint> Procedures (EPIPs)1.ist:

No. Title EPIP-01 Generallustructions and 0 ganizational Responsibilities.

EPIP-02 Reactor Ope ator Immediate Action Proceduies.

EPIP 03 Nuclear Reactor Lab Emergency Call List Intmsion / Emergency.

EPIP-04 Emergency Director (ED) Procedures.

EPIP-05 Emergency Coordinator (EC) Procedures.

EPIP-06 Emergency Rauiation Protection Manager (ERPM) Procedures.

dPIP 07 Emergency Medical, Security, Fire, and Plant Services Manager (EPSM) Procedures.

EPIP-08 Emergency Actiou Levels (EALs) and Emergency Classification Procedure.

EPIP-09 Corrective and Protective Action Procedures.

EPIP-10 Reentry anji Recovery Procedures.

EPIP 11 Coordination of 0ffsite Agencies Procedures.

, EPIP-12 Training Proctdures.

EPIP 13 Drills and Exercises.

EPIP 1/. Emergency Equipment Maintenance and Surveillance.

EPIP 15 Documentation and Reccrds.

Page 28 of 29

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),

. .I. h$$ _ Y-b i Nk$ ((Nkh kb kdIkkbl0J Q$kker MBLk.OJY1 CIDE Rninvrstily Titisi Ottelationsstutmio) Datt ,_

Jonathan M Ralston 61uitoved fly' Titk_litng.tgg1 Ley Dir1Eint DJ!Lc1-IMgh L lloln) l Date Reviewed by the Reactor Comruittee:

1 1

(eplankeplanneW496)

LettlanklilaJJttev.597)

+

Page 29 of 29

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I'-Plan Att:climent 4 Page 1 of t Emergency Response Organization (ERO) l Emergency Director (ED)

Emergency Emergency Duty Emergency Plant Emergency Public Coordinator Radiation SRO Services Manager Infonnation Manager (EC) Protection (EPSM) (EPIM)

Manager RO/SRO (ERPM)

Champaign County University Office Emergency Services of Public Affairs Division of Reactor and Disaster Agency Environmental Staff Health & Safety (ESDA)

(DEH&S)

Police, Fire, and Radiation Medical Safety OfTicer (RSO)

(eplan\attchmt4. doc)

____ j

o. g.t E-Plan Altnehment 3 Page 1 of 2 C.HAMPAIGN COUNTY '

Emergency Services and Disaster Agency  ?

l 1905 East Main, Urbana, IL 61802 ^

217

• 384-3826 Isn a

March 26, 1997 Richard L. Holm Reactor Administrator 214 Nuclear Engineering Laboratory 103 S. Goodwin Ave.

Urbana, IL. 61801-2984 i

Dear Sir:

In checking with Carle Hospital and Covenant Medical Center, I believe you and I have h most cur nt Radiation Safety P1 for ,

arledosf9 hCt nod. c).

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 k }/ ?

Bill L. Keller, Coordinator BLK:jh m_._____.__.----.-

. , G ,.=

• rn E-l'lasi Attaclininesit 5 l' age 2 of 2 Tlic Carle Clinic Association l

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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EMERGENCY PLAN ~

for the i

, NUCLEAR REACTOR LABORATORY l

at the i UNIVERSITY OF ILLINOIS l

l in URBANA, ILLINOIS Facility Licenses No, R-115; R-117 Docket Nos, 50-151;50-356 Revision 1

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May 1997 Dl 19 a s h ,%19;w t [

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TABLE Ol' CONTENTS S:ction Page Nember Preface 4 1.0 Introduction 5 1.1 Description of the Reactors 5 1.2 Location of the Reactor Facility 5 1.3 Identification of Owner / Operator 5 1.4 Objtetive of the Emergency Plan 5 2.0 Definitions 5 3.0 Organization and Responsibilities 7 3.1 Emergency Response Organization (ERO) 7 3.1.1 Emergency Director (ED) 8 3.1.1 Emergency Coordinator (EC) 8

< 3.1.3 Reactor Operator (RO) 9 l 3.1.4 Emergency Radiation Protection Manager (ER141) 9 3.1.5 Emergency Medical, Security, Fire, and Plant Services Manager (EPSM) 9 3.1.6 Emergency Public Information Manager (EPIM) 10 3.1.7 University OfDcc of Public Affairs 10 3.1.8 Police, Fire, and Medical Assistance 10 3.1.9 Radiation Safety Ollice (RSO) 10 3.2 Coordin. tion and Notification ofFederal, State, and Local Govemmertal Agencies 10 3.2.1 Nuclear Regulatory Commission (NRC) and American Nuclear Insurers (ANI) 11 3.2.2 Champaign County Emergency Services and Disaster Agency (ESDA) 11 3.2.3 University ofIllinois Police and Fire Departments 11 3.2.4 University Division of Environmental Health & Safety (DEH&S) 11 3.3 Tennination of an Emergency 11 3.4 Authorization for Reently 12 3.5 Authorization for Planned Special Exposures 12 4.0 Emergency Action Levels (EALs) and Emergency Classification System 12 4.1 Non Reactor Safety Related Events (NRSRE) 12 4.2 Notification of Unusual Events (NOUE) 12 4.3 Alert 13 4.4 Site Area Emergency 14 4.5 GeneralEmergency 15 4.6 Emergency Action Levels (EALs) for Members of the General Public Onsite 15 5.0 Emergency Planning Zones (EPZs) 15 6.0 Emergency Response 15 6.1 Activation of the Emergency Response Organization (ERO) 15 6.2140tective Action Values 15 6.3 Emergency Response for a Non-Reactor Safety Related Event (NRSIW) 16 6.3.1 Activation of Emergency Organizat:o: fbr a NRSRE 16 6.3.2 Assemnent Actions for a NRSRE 16 Page 2 of 27 j L. -

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6.3.3 Corrective Actions for a NRSRE 17 6.3.4 Protective Actions for a NRSRE 17 6.4 Emergency Response for a Notification of Unusual Event (NOUE) 18 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 6.4.4 Protective Actions for a NOUE 19 6.5 Emergency Response for an Alert 20 6.5.1 Activation of the Emergency Organization for an Alert 20 6.5.2 Assessment Actions for an Alert 20 6.5.3 Corrective Actions for an Alert 21 6.5.4 Protective Actions for an Alert 21 6.6 Site Area Emergency 22 7.0 Emergency Facilities and Equipment 22 7.1 Emergency Support Centers 22 7.2 Assessment Facilities 22 7.3 First Aid, Medical, and Decontamination Facilities 23 7.4 Communications Equipment 23 8.0 Reentry and Recovery Operations 23 9.0 Maintaining Emergency Preparedness 24 9.1 Training 24 l

9.2 Conduct ofDrills and Exercises 24 9.3 Critiques of Drills and Exercises 24 9.4 Drill and Exercise Scenarios 25 9.5 Emergency Phn Review and Update 25 9.6 Emergency Equipmerit Maintenance and Surveillance 25 7

9.6.1 Inventory ofEquipment and Supplies 25 9.6.2 Radiation Monitoring Equipment Calibration 27 9.7 Emergency Plan Implementing Procedures (EPIPs) List 27 10.0 Attachments N/A

1) Champaign-Urbana Area Map. N/A

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 27 l l

• . j PREFACE Planning for possible emergencies at the Nuclear Reactor Laboratory (NRL) was staned with the publication of the llanrds Analysis in October,1959. This report contained written procedures to be followed in the case of a sudden or threatening increase in radiation levels. Afler the conunencement of operations in 1960, these procedures were incorporated 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 support 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 the OfIice ofInspection and Enforcement of the Nuclear Regulatory Commission (NRC) and was found to be l

adequate. For a number of years, most of the attention for approved Emergency Plans was directed toward i Nuclear Power Reactors.

l On November 2,1982, a Radiation Emergency Plan was submitted to the Director of the Oflice of Nuclear Reactor Regulation as required by 10 CFR 50.54(r). The Plan follmved 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 were not previously covered. On March 20,1984, a notice was received that

( the Pim was inadequate in certain areas. The arcas were listed with the notice. The deficient items were covered l 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 July 1984.

When completed, it was reviewed and approved by the Nuclear Reactor Committee. Copies were then submitted to the NRC to replace the earlier documents. This plan remained relatively unchanged from 1955 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 ofRadiation 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). However, 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 a major 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, cerrect 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 reviewed and approved by the Reactor Committee and submitted to the NRC on March 13, 1995. The NRC accepted the plan in a letter dated, September 26,1995.

Page 4 of 27

4

1.0 INTRODUCTION

1.1 Rescrip1Lon of the Reactor $:

The Illinois Advanced TRIGA and LOPRA reactors utilize fuel produced by General Atomics. The authorized maximum steady state power levels are 1.5 MW for the TRIGA reactor and 10 kW for the LOPRA reactor. The TRIGA is used for education, training operators, the production of radioactive (

isotopes, and research. The LOPRA is coupled to the TRIGA through a thermal column. Ahhough the LOPRA was originally built to study coupling effects, the only present use is for education and training.

1.2 Location ofthe Reactor Facility:

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 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 Champaign-Urbana showing access from Interstate 74 to the reactor and the location of Carle Medical Center (Attachment 1). The second map shows the immediate area and gives access routes to the reactor and the alternate sites that would be used as emergency centers (Attachment 2). A third map is included as a diagram of the reactor building showing the site boundary, the location of the reactors within the building, and associated equipment locations (Attachment 3).

1.3 hLentification of the Owner / Operator:

Both reactors are owned by the University ofIllinois Board ofTrustees and operated by the Nuclear Engineering Department in the College of Engineering.

1.4 Obiective of the Emergency Plan:

The Emergency Plan contains provisions for a graded response to possible unplanned adverse radiological conditions both within and beyond the facility boundaries. The content follmvs the guidelines ofANSI/ANS 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 Power 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 Determining The Size of an EPZ", (Emergency Planning Zone) the EPZ for this plan is established at the Operations (Site) Boundary and the Emergency Classification " General Emergency"is not used.

2.0 DEFINITIONS Confinement System: is defined at the Reactor Building Walls and is designed to confine and maintain control of 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 the licensee for any reason. It is controlled at the NRL for the purpose of Security and is identical to the Operations and Site Boundaries, as defined below.

Emernency: is a condition that calls for immediate action, beyond the scope of normal operating procedures, to avoid an accident or to mitigate the consequences ofone.

Page 5 of 27

' Emelgensy Action Levels (E61a): are specific instrument readings or observations; radiological dose or dose rates; spe:ific contamination levels of airbome, waterbome, or surface-deposited radioactive material; that may be used as thresholds for establishing emergency classes and iniciating emergency measures.

Emernency Classes: are classes of accidents grouped by severity level for which predetennined emergency measures should be taken or considered.

Emergency 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.

Famergency Planning zone _(Ef2): is an area for which offsite emergency planning is perfonned 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) Boundary and is defined by the Reactor Building Walls (Confinement).

Emergency Plan Implementation Procedures _(EPIPS): are documented instructions that detail the implementation 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): are areas designated for assembly afler an evacuaoon. The purpt icnrthese facilities is to provide: a control center; an accountability station; and a radiologicaliaonitoring area for trisis 3 ofpersonnel and evaluation ofradiological samples.

LOPRA Reactot: Low Power Reactor Assembly; widch refers to the smaller of the two reactors located onsite that utilizes General Atomics designed TRIGA Type Fuel Elements and has a maximum steady state power rating of10 kW.

Nuclear Reactor Laboratory (NRL): is defined in the introduction to this plan.

OfTsite: is the geographical area outside the walls (the confinement) of the Rer.ctor Lab and is not controlled by the operator of the lab, the Nuclear Engineering Depanment.

Onsite: is the geographical area inside the walls (the confinement) of the Reactor Lab and is tmder the control of the operator of the lab, the Nuclear Engineering Department.

Operations Boundary: is the area where the Reactor Administrator (Emergency Director) has direct authority over all activities. This is defmed by the Reactor Building Walls (Confinement) and the area witida this boundary has prearranged evacuation procedures known to people frequenting the area. This area is also referred to as the Site Boundary.

Protective Action Guides (PAGs): are projected radiological dose or dose commitment values to individuals that warrant protective action following a release of radioactive material. Protective actions would be warranted 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 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 security and have the appropriate level of radiological training to have unescorted access to, and escon individuals into, the restricted area. They also have an assigned position in this plan.

Page 6 of 27 I

G l Research Reactor: is a device designed to support a self-sustaining neutron chain reaction for research, l developmental, educational, training, or expedmental purposes, and which may have provisions for production of non fissile radioisotopes, ILestrictedArea: is that area, access to which is limited by the licensee, for the purpose ofprotecting individuals against undue dsk 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 Bmmdary: 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 has '

prearranged evacuation procedures known to people frequenting the area. This area is also referred to as the Operations Doundary. This area may also be frequented by people unacquainted with reactor operations; such as Visitors and Tour Groups; however, these indhiduals are ahvays under the direct supervision and control of a member of the Reactor StafE ShalLShmild. and May: the word "shall"is useu to denote a requirement; the word "should" to denote a recommendation; and the word "may" to denote pennission, neither a requirement nor a recommendation.

TRICA Reactor: Training, Research, Isotope Production, 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 1.5 MW.

3.0 ORGANIZATION AND RESPONSillILITIES The Nuclear Reactor Laboratory (NRL) is a facility of the Nuclear Engineering Department, through which it receives primary funding for staff and equipment, and is operated under license from the NRC. The Reactor Administrator, a licensed Senior Reactor Operator (SRO), is directly responsible for all activities conducted at the NRL including, but not limited to: Building Security, Special Nuclear Material (SNM) Custodian, the Emergency Plan, and Supervision of the Reactor StafE The Reactor Administrator is responsible, in a line of authority to the Head of the Department ofNu: lear 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 part in the overall plan. He shall keep these individuals informed regarding changes to their roles in the Emergency Organization and changes to the Emergency Plan. The Reactor Health 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 Health Physicist is responsible for ensuring that the radiation monitoring and supplementary equipment required for an emergency is available as specified in the Emergency Plan. The Reactor Operating Staffconsists ofindividuals who have a current SRO or 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 conunensurate with their training and experience. The Reactor Committee is a permanent standing committee of the Department of Nuclear Engineering and reports directly to the Department Head. 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, 3.1 Emervncy 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 Page 7 of 27 1

.w Radiation Safety OfDee (RSO) in the Division of Environmental Health & Safety (Dell &S), and the Nuclear Engineering Department. Onsite and Offsite organizations may be required to assist the ERO for emergency event response. 'Ihis assistance may include the University Police for security matters, traflic control and limited building evacuation; the University Fire Department for firefighting, emergency medical trauma response, and/or rescue; the University Oflice of Public Affairs for media contact; and the Champaign County Emergency Senices and Disaster Agency (ESDA) for oatside assistance with police, fire and medical facilities. A Block Diagram outlining the reporting responsibilities, lines of authority, and line cf succession to the Emergency Director is included as Attachment 4. Written agreements for those organizations that would be available to the ERO stalTate iricluded as Attachment 5. More complete details on the ERO's organization and responsibilities may be found in EPIP-01.

3.1.1 Emergency Direttor(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 found in EPIP-04. He authority and responsibility of tiiis 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 of radioactive material; d) protecting facility persormel and visitors; c) exchange ofinformation with authorities responuible for offsite emergency measures and r summoning assistance as necessary;

• f) protective action decisions;

• g) authorizing radiation exposures in accordance with NRC Regulatory Guide 8.35 " Planned Special Exposures";

h) declaring the termination of an emergency and directing restoration; i) providing for a final report on the emergency with revisions to the Emergency Plan ifnecessary, including infonning 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 Health Physicist Operations Supervisor Senior Reactor Operator Campus Radiation Safety Oflicer 3.1.2 Emergency Coordinator (EC)

The Reactor IIcalth Physicist is the Emergency Coordinator. The EC is responsible for the oserall coordination of the Emergency Plan as detailed in EPIP-05. These responsibilities include:

a) developing and maintaining the Emergency Plan and Implementing Procedures (EPIPs);

Page 8 of 27 )

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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 of updating the plan; f) conducting the biennial review of the plan; g) coordinating plans with other applicable organizations.

Line of Succession to EC: Operations Supervisor 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 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 uncontrolled radioactivity release. He 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.

3.1.4 Emergency Radiation Protection Manacer(ERPM)

The Reactor Health Physicist is the Emergency Radiation Protection Manager, The ERPM is

- responsible for the initial assessment of actual or potential radiological hazards onsite and offsite. Tids responsibility includes; onsite and offsite dose assessments, recommended protective actions, and all 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 individuals that may act as ERPM if the primary ERPM is not available are:

Ling of Succession to ERPM: Reactor Health Physicist Assistant Campus Radiation Safety OfIicer (RSO)

Radiation Safety Office Health Physicist 3.1.5 Emergency Plant Services Manager (EPSM): Medical, Security, and Fire.

The Duty Senior Reactor Operator (SRO) is the EPSM and is responsible for obtaining first aid, police, and fire-fighting assistance from the Senior University Police Officer or the Senior University Fire Officer On Duty as warranted by the situation. The EPSM is responsible for assessment of actual or potential security aspects of all radiation emergencies and shall provide advice and consultation to the ED on all matters relating to security and traffic control upon activation of the Emergency Plan. In addition, the SRO is responsible for advising the ED on Plant Services and Equipment and for obtaining needed equipment from the University Operations and Maintenance Department. The details of the EPSM's responsibilities 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 Health Physicist Safety Specialist from DEH&S Page 9 of 27

r .a ..o.- -s +

3.1.6 Emergency Public Infonnation Managgr (EPIM) ne IIcad, Department of Nuclear Engineering is the EPIM. He EPIM shall provide information, as discretion dictates, to the University Ollice of Public Affairs, when such information is provided by the Emergency Director. The EPIM shall act as primary spokesperson for the Emergency Director, ne EPIM shall review all press releases written by the University Omce of Public Afrairs. In the absence of the duly appointed EPIM, the following individuals shall act as temporary EPIM:

Altemates to EPIM: Assistant licad, Department ofNuclear Engineering Director, Division of Erwironmental Health & Safety 3.1.7 University Omcc ofPub3 Affairs ne University OfIice of Public Affairs will handle all ofIicial news releases concerning emergency conditions at the Nuclear Reactor Lab. He Reactor Administrator shall be responsible for the technical content ofinformation prepared for release by the OfIice of Public AfTairs.

3.1.8 Police. Fire. and l\igdical Assistan.cs The Senior 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 Senices and Disaster Agency (ESDA) activate Onsite coordination with local hospitals and support agencies. These calls should be regarded as being properly sanctioned by the University. Police and Fire services are available at all times. The University Police may be called to provide security assistance, emergency radio communications, trafIic and crowd control; as necessary, ne University Fire Department 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 security and fires involving potential radiation exposure or areas with radioactive material present.

3.1.9 Iladiation Safety Office (RSO)

The RSO is the Section within the Division of Etwironmental Health & Safety responsible for Radiation Safety on the Campus outside the confines of the NRL. Professional and Technical Health Physics staff from the RSO are available to assist in the event of an emergency at the NRL. The Director of the Radiation Safety OfIice is also the Campus Radiation Safety OfIicer and shall be notified in the event of an emergency at the NRL.

3.2 Coordination and Notifica1 ion of Federal. State. and Local Govemmental Agencies The postulated credible accidents associated with the operation of the Nuclear Reactor Laboratoiy will not result in a radiological hazard affecting the General Public. The credible emergency events will not require the direct involvement of Federal, State, and Local Govemmental 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 emergency messages; to the extent the information 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) The location of the incident and the emergency class; c) A description of the emergency event; d) The date and time of the incident initiation; j

Page 10 of 27

c) The type and quantity of radionuclides released or expected to be released.

f) Projected or actual 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 Muclear R6gulatory Commission (NJtC) and American Nuclearinsurers(ANJ)

The NRC Region ill OfIice ofInspection and Enforcement is located at Lisle, Illinois. Assistance from this oflice would be in accordance with the provisions of the license,10 CFR 20, and commensurate with the seriousness of the emergency. Notification of the lieadquarters Operations Center at the telephone and facsimile numbers noted below will result in Region 111 being notified in the event of an emergency, therefore, a separate call to Region IIIis not required.

Location Telephone Number Availability NRC Operations Center Voice; l-301-816-5100 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> / day Voice backup : 1-301-951-0550 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> / day Facsimile: 1 301-816-5151 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> / day NRC Region III Voice: 1-708-829-9500 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> / day American Nuclear Insurers (ANI) Voice: 1- 860-561-3433 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> / day Facsimile: 1-860-561-4655 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> / day 3.2.2 Champaim1 County Emergency Senices and Disaster Agency (ESDA)

ESDA has overall responsibility for providing coordination oflocal police, fire, rescue, and medical response for large scale disasters and emergencies. The Senior 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 Senices and Disacter Agency (ESDA) activate Onsite coordination with local hospitals and suppon agencies. These calls should be regarded as being properly sanctioned by tl.e University.

3.2.3 University ofIllinois Police and Fire Departmenu The University Police and Fire Departments shall provide immediate response to a security event or fire within or without the Reactor Building and near environs. The Emergency Director (ED), or an individual such as a Senior Reactor Operator (SRO) acting as the ED or at the direction of the ED, shall be authorized to request assistance from Champaign County ESDA. ESDA will notify the University Police and Fire Departments, as well as other appropriate support agencies, of a potential emergency at the NRL.

3.2.4 Lh.tiyersity Division of Environmental Health & Safety (DEH&S)

The Director of the Radiation Safety Oflice is also the Campus Radiation Safety Oflicer and shall be notified in the event of an emergency at the NRL 3.3 Termination of an Emergsney 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 I

l Page 11 of 27 i b

- .~ .n.,

or to the General Public meet the requirements of 10 CFR 20 and all areas to be restricted  ! for ent require controlled access are properly posted 3.4 Authorization for Reentry The Emergency Director (ED) shall authorize any reentry into the NRL, or portions thereof, previo evacuated during an emergency, in accordance with the guidelines established in EPIP-10, " Reentry an Recovery Procedures".

3.5 Authorization for Planned Special E2pfsures With the concurrence of the Head of the Department of Nuclear Engineering and afier consultation t with t Emergency Radiation Protection Manager, the Emergency Director may authorize Planned Special Exposures for emergency team members. The criteria used to establish exposure limits for this authodza shall be in accordance with NRC Regulatory Guide 8.35 " Planned Special Exposures.

4.0 EMERGENCY ACTION LEVELS (EALs) AND EMERGENCY CLASSIFICATION SYS

' Die 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 react events that have minimal, if any, radiological consequences. More specific guidance on any of the top Section 4.0 can be found in EPIP-08, " Emergency Action Levels (EALs) and Emergency Classification ProCCdures".

4.1 Non Reactor Safety Related Event (NRSRE)

This class of emergency consists of an event that does not enaanger the General Public. Notification of o assistance from the University Police and Fire Departments mar e warranted. The following E 641 ion Levels (EALs) or events shallinitiate emergency measures associated with this Emergenc a) Significant personnel injury with oi without radiological complications.

b) Minor fire or explosion not specific to the reactors.

c) Significant contamination of an individual or of tlwacmty.

d) Civil disturbances or receipt of a bomb threat that is not specific to the Nuclear Reactor Lab.

More specific guidance on this topic can be found in EPIP-08, " Emergency Action Levels (EALs) a Emergency Classification Procedures".

4.2 Notification of Unusual Event fNOUE)

This class of emergency consists of an event that may be initiated by either man-made or natura that can be recognized as creating a significant hazard potential that was previously nonexistent. There i 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 ofradioactive material requiring offsite expected. Some elements of the Emergency Organization may be activated or notified to increase the sta readiness, as warranted by the circumstances. Although the situation may not have caused dam reactors, the reactors shall be shutdown.

The following Emergency Action Levels (EALs) or events shallinitiate emergency measures associa this Emergency Class:

Page 12 of 27

. m,y 9

a) Actpal or projected radiological effluents at the site (operations) boundary calculated to produce a Deep Dose Equivalent (DDE) of 15 mrem (0.15 mSv) accumulated within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

i) The following guideline shall be used to calculate a Committed Effective Dose Equivalent (CEDE):

3 100

• EC

• 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> = 2.4 E EC-hr = 15 mrem (0.15 mSv) for radionuclides other than noble gases

• 50

• EC

• 24 ~ urs = 1.2 E' EC-br = 15 mrem (0.15 mSv) for noble gases Npiq: EC = EfIluent Concentration values listed in 10 CFR 20, Appendix B, Table 2.

This can be determined by observing the following radiation levels on the facility radiological monitors:

ii) Area Radiation Monitors (ARMS) > 20 mR/hr for the West and Lobby and Reactor Top ARMS for more than 10 minutes with the reactor shutdown and no other sources of radiation present and:

iii) Continuous Air Monitors (CAMS): Meaanine and Reactor Top CAMS > 2000 cpm above I

background and Exhsust Stack Monitor > 380 cps.

NLo_te: If the Ea_si ARM is greater than 20 mR/hr, this is an Alert. Procecd to section 4.3.

l b)ILeport or observation of severe naiural phengmena.Juch as tornadoes in the immediate vicinity of thq Nuclear Reaclor Lab. or carthquakes felt in the facil.hy.

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.

More specific guidance on this topic can be found in EPIP-08, " Emergency Action Levels (EALs) and Emergency Classification Procedures" 4.3 Alen 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 ; heir 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 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 Levels (EALs) or events shall initiate emergency measures associated with this Emergency Class:

Page 13 of 27

. m y-a) Actual or projected radiniggical efilusnts at the site.{cperatione boundary calculated to produce a Deep Dose Equivalent (DDE) of 75 mrem (0.75 mSv) accumulated within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

i) The following guideline shall be used to calculate a Committed Effective Dose Equivalent (CEDE):

d 500

• EC

• 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> = 1,2 E EC-hr = 75 mrem (0.75 mSv) for radionuclides other than noble gases 250

• EC

• 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> = 6.0 E EC-hr = 75 mrem (0.75 mSv) for noble gases o

N_ols: EC = EfDuent Concentration values listed in 10 CFR 20, Appendix B, Table 2.

This can be detennined by observing the following radiation levels on the facility radiological monitors:

ii) 6_rea Radiation Monitors (ARMS) > 100 inR/hr for the West and Lobby and Reactor Top ARMS for more than 10 minutes with the reactor shutdown and no other sources ofradiation present and:

iii) Continuous Air Monitors (CAMS): Mezzanine and Reactor Top CAMS > 10,000 cpm above background and Exhaust Stack Monitor > 999 cps.

b) Actual or projp_qted radiation levels at the site (operations) boundary of 20 mrem /hr (0.2 mSv/hr) Deep Dose Equivalent (DDE) for I hour, based on East Wall Area Radiation Monitor (ARM); or 100 mrem (1.0 mSv) Committed Dose Equivalent (CDE) to the thyroid.

c) Severe failure of fuel cladding, as indicated by the Demineralizer ARM alarning with an indication >40 mlUhr and confirmed by indications in Sections 4.3 a) ii) & iii) above; or failure of fheled exneriments where containment boundaries exist to reduce releases or less severe cladding failures in situations where fission products are not well contained.

d) Sinnificant releases of radioactive material as a result of experiment failures.

e) Loss of physical control of the facility.

More specific guidance on this topic can be found in EPIP-08, " Emergency Action Levels (EALs) and Emergency Classification Procedures".

4.4 Site Area Emergency 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 ofE indicate that aji emergency of this class would never occur. However, an emergency conditian where the Emergency Response Organization (ERO) may consider setting up traflic control or the evacuation of adiacent 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".

Page 14 of 27 {

, l i

4.5 General Ernergency(Not Applicable)

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 Report (SAR) analyzed a number of accidents including the release of radioactive effluents to the emironment. 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. Tnerefore, this emergency class is not addressed in this plan.

4.6 Emergency Action Levels (EALs) for Members of the General Public Onsits Befere exposure levels equal to or exceeding the Protective Action Guides (PAGs) of: 1 Rem (10 mSv) Total Effective Dose Equivalent (TEDE) or 5 Rem (50 mSv) Committed Dose Equivalent (CDE) to the thyroid, witidn the operations (site) botmdary; have been reached members of the general public shall have been evacuated from the building.

5.0 EMEltGENCY PLANNING ZONES (EPZs)

Since the postulated radioactive releases from credible accidents at this facility falls in the first category,

" Authorized Power 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 ne Size of an EPZ" and Appendix II of NUREG-0849, the EPZ for this plan is established at the Operations (Site) Boundary and is defined by the Reactor Building Walls (Confinement).

6.0 EMERGENCY llESPONSE l 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 List is kept by the Police Dispatcher and telephone numbers are visible through the front window of the lab entrance. The Dispatcher is on duty around the clock thus ensuring that an NRL Staff member on the list can be notified of an tmusual situatiott The NRL Staffmember notified shall resolve the situation and detennine

• whether a real emergency condition exists. If the potential for an emergency condition exists the NRL Staff member shall notify the Emergency Director (ED) and take charge of the potential emergency until the ED arrives. The ED shall give instmetions on steps to be taken prior to the arrival of the ED at the Nuclear Reactor Lab and determine if additional notifications are warranted.

More specific guidance on this topic can be found in EPIP-03, " Nuclear Reactor Lab Emergency Call List -

Intrusion / Emergency" and EPIP-08, " Emergency Action Levels (EALs) and Emergency Classification Procedures" 6.2 Protective Action Vahin No credible accidents attribetable to tne reactor or its operation are postulated which could cause emergency conditions beyond the operations (site) botmdary. 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 ventilcion system off, indicate that the Protective Action Guides (PAGs) of 1 Rem (10 mSv) Total Effective Dose Equivalent (TEDE) or 5 Rem (50 Page 15 of 27 l

, s . < - ~.m on n e .

mSv) Committed Dose Equivalent (CDE) to 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 exceeding the Protective Action Guides (PAGs) of: 1 Rem (10 mSv) Total Effective Dose Equivalent (TEDE) or 5 Rem (50 mSv) Committed Dose Equivalent (CDE) to the thyroid, within the operations (site) boundarv; have been reached members of LlagtngnLpubli_q 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 Repon (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 Planned Special Exposures as described in Section 3.5 above, "With the concurrence of the Head of the Depanment of Nuclear Engineering and after consultation with the Emergency Radiation Protection Manager, the Emergency Director may authorize Planned Special 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".

6.3 Emergency Respons_q for a Non-Reactor Safety Related Event (NRSRE) 6.3.1 Activation of the E JH e.Lrgency Organization for a NRSRE The complete activation of the emergency organization for this emergency class would not nonnally be required. The Emergency Director (ED) shall activate that ponion 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, or assistance from, the University Police t.nd Fire Departments may be warranted. The following Assessment Actia ns shall be considered appropriate for this Emergency Class:

a) Significant personnel injury with or without radiological complications: The ED shall assess the extent of the injury and whether radioactive contamination is present. The assessment will consider the nature of tLe injury, the appropriate first aid, the need for transportation to medical treatment facilities, and the levels ofradioactive contamination ifpresent.

b) Minor fire or explosion not specific to the reactors: The ED shall assess fire or explosion events to 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 detennine ifradioactive contamination is present.

c) Sinnificant contamination of an individual or of the facility: Significant personnel contamination that repeatedly fails to be removed by ordinary decontamination procedures shall be evaluated by the ED for possible consultation with appropriately trained medical personnel before further decontamination is attempted. Significant contamination of the facility shall be assessed by the ED, after consultation with the Emergency Radiation Protection Manager (ERPM), to determine whether a formal decontamination procedure needs to be developed for this event.

d) Civil disturbances or receipt of a bomb threat that is not specific to the Nuclear Reactor Lah: 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, after consulting the University Police and evaluating the infonnation source.

I Page 16 of 27

6.3.3 Cmtective Actionsfpta NRSRF

'ntis class of emergency consists of events that do not endanger the General Public. Notification of or assistance from the University Police and Fire Departments may be warranted. The following Corrective Actiorg shall be considered appropriate for this Emergency Class:

a) Significan1 personnel iniury with or without radiolcical comJ lications: For cases of personnelinjury with or without radiological complications, the ED mil determine what medical assistance is needed, and may contact the Champaign County ESDA at 9-911 to request transportation. If the injured individualis contaminated, decontamination will be attempted only ifit isjudged that this will not funher aggravate the injury. A contaminated injured indMdual will be transported using contamination control and isolation methods.

b) Minor fire or expjosion not specific to the reactos: For minor fires or explosions not specific to the reactors or their control systems the ED shall be notified and reactor staff members shall attempt to control the fire with ponable fire extinguishers ifit is safe to do so. The FD shall determine if the scope of the fire or explosion requires the assistance of the University Fire Depanment, and if so, the Champaign County ESDA shall be notified at 9-911.

c) Sjgnificant contamination of an individual or of tne facility: The ED, after consultation with the Emergency Radiation Protection Manager (ERPM), shall detennine the decontamination procedure appropriate for the individual or the facility. Goals shall be established to detennine when funher decontamination is not wananted. These goals sho tid consider returning contamination levels to 10 CFR 20 limits.

d) Civil dislurbances or receipt of a bomb threat that is_ cot specific 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 willinitiate the appropriate controls to insure the protection ofpersonnel and propeny. The ED shall notify the Head of the Department of Nuclear Engineering and keep him infonned of the emergency status.

6.3.4 Protective Actions for a NRSRE Some protective actions at this level of emergency (e.g., fire alanns) necessitate the evacuation of the Reactor Building. In this case reactor staff members will assemble at the north entrance to the Nuclear Engineering Laboratory to determine 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 ERPM shall control access to the areas and shall be responsible, with support from the reactor staff for the segregation ofpotentially contaminated personnel.

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" Page 17 of 27

6.4 EmergenevJltsp2nse for a No_lifLcation of UnusuaLEvcnt (NOUli) 6.4.1 /Letivation of the Emergency Organization for a NOUE The complete activation of the emergency organization for this emergency class would not normally be required. The Emergency Director (ED) 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 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 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 l 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 r

a) Actual or p_rqiteted radiological efUnents at the site (operations) boundan> calculated to prodttera D_eep Dose Equivalent (DDE) of 15 mrem (0.15 mSv) or a Committed Effective Dose Equivalent LCEDE) of 15 mrem (0.15 mSv) accumulated within 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s: Fuel damage, experiment failure, or any event manifested by unusual radiation levels within the Reactor Laboratory, or the release ofradioactive efiluents offsite, shall be assessed by the ED with assistance from the reactor staff. Additional support for assessment shall be requested from the Radiation Safety Office (RSO), ifneeded. 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 surveys with portable ion chambers or other cppropriate 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 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 funher assessment will be made from outside the facility with the infonnation provided to the Emergency Support Center (ESC),

b) Report or observation of severe natural phenomena. such as tornadoes in the immediate vicinity of the Nuclear Reactor Lab. or canhquakes felt in the facility- This situation requires immediate shutdown of the reactors and notification of the ED. The ED shall establish contact with the Champaigu County ESDA for further assessment of the severe natural phenomenon and for recommendations on seeking shelter at appropriate assembly areas.

c) Threats to or breaches of security. such as a bomb threat or civil disturbance. specific to the Nuclear Reactor L.ab: 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, after consulting the University Police and evaluating the information source.

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: The ED shall assess the severity of the fire or explosion to determine if the assistance of the University Fire Department is required.

e) Failure of a fuel element or failure of an experiment with a release of radioact_ivity: The assessment actions for this event are the same as those detailed in 6.4.2 a)immediately above.

Page 18 of 27 l

More specific guidance on the methods, systems, and equipment for gathering 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".

6.4.3 Corrective Actions for a NOUE a) 6_g1Ral o_r_proiected radiological efUuents at the site (operations) boundary calculated to. produce a

_Dee.p e Dose Equivalent (DDE) of 15 mrem (0.15 mSv) or a C_emmitted Effective Dose Equivakn1 (CEDE) of 15 mrem (0.15 mSv) accumulated within 24 houn: If a NOUE 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 nonnal. 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 Suppon Center (ESC); or at the nonh entrance lobby to the Division of Environmental Heahh & 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 Laboratory. Since one is in a i

westerly direction and the other in an casterly 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)ILepen or observation of severe natural phenomena. such as tornadoes in the immediate vicinity of the Nuclear Reactor Lab. or earthquakes felt in the facility: This situation requires inunediate shutdown of the reactors and notification of the ED. The ED shall establish contact with the Champaign County ESDA for further assessment of the severe natural phenomenon and for recommendations on seeking shelter at appropriate assembly areas.

c) Threats to or breaches of security. such as a bomb threat or civil disturbance. specific to the Nuclear i

Reactor Icab: 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, after consulting the University Police and evaluating the infonnation source. The police may initiate controls to insure the protection ofpersonnel and propeny. The reactors shall be shutdown and personnel 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 immediately with an onsite CO 2 extinguisher and requiring the assistance of the University Fire _D. egartment for control: The police or fire department may initiate controls to ensure the protection of personnel and property. The reactors shall be shutdown and personnel evacuated to the Nuclear Engineering Laboratory 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 a release of radioactivity: The corrective actions for this event are the same as those detailed in 6,4.3 a)immediately above.

6.4.4 Protective Actions for a_NOUli If the Reactor Building has been evacuated, all personnel who were in the facility at the time of the emergency shall be accounted for. Allindividuals who evacuated the Reactor Building shall be surveyed for contamination with portable instruments. Those individuals who are contaminated shall remain in an l

Page 19 of 27 l

, , . , m.

area designated by the ED or ERPM for decontamination. The ED is responsible for limiting access to the Reactor Building to rescue and emergency n esponse operations personnel. The ERPM is responsible 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 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".

6.5 Emergency Response for an Alert 6.5.1 Activation of the Emergency Orghnization for an Aleti The complete activation of the emergency organization for this emergency class is required. The Emergency Director (ED) shall activate the entire emergency organization in response to an event of this class. This class of emergency consists of - ents 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 necessary. Situations that may lead to this class include: 1) severe faihire 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.

6.5.2 Assessment Acti_ons i for an Alen a) Actual or projected radiological efiluents at the site (operations) boundary calculated to_ produce a Deen Dose Equivalent (DDE) of 75 mrem (0.75 mSv) or a Committed Effective Dose Equivalent (CEDE) of 75 mrem (0.75 mSv) accumulated within 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s: 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 frmn the reactor staff. Additional support for assessment shall be requested from the Radiation Safety Oflice (RSO), ifneeded. 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 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 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 airbome or radiation levels may require evacuation of the Reactor Building and further assessment will be made from outside the facility with the information provided to the Emergency Support Center (ESC),

b) 6ctual or proiected radiation levels at the site (operations) boundary of 20 mrem /hr (O m 2 mSv/hr)

D_gp Dose Equivalent (DDE) for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. based on East Wall Area Radiation Monitor (ARM): or 100 mrem (1.0 mSv) Committed Dose Equivalent (CDE) to the thyroid: Same as in a) immediately above.

c) Severe faihire of fuel claddinn or of fueled experiments where containment boundaries exist to reduce releases or less severe cladding failures in situations where fksion products are not well Page 20 of 27

' 99atairmd: Same as in a) & b)immediately above.

• d) Signifier.t releases ofradioactive material as a rewit.pr ;ggimetttfailures:

e Same as in a), b), anLi c) immediately above.

e) Loss of&ysical coritrol of the faciEty: 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.

6.5.3 Corrective Actions for an Alert a) Actual or proiected radiological effluents at the site (o_perations) boundary calculgt.ed to rtrsduce a Deep Dose Equivalent (DDE) of 75 mrem (0.75 mSv) or a Committed Effective Dose E_quivalent (CEDE) of 75 mrem (0.75 mSv) accumulated within 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s: If a Notification of an Alert is dictated by ,

assessment ofhigh radiation or airborne radioacthity 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 airbome acthity levels have been restored to normal.

All personnel that were evacuated from the Reactor Building shall assemble 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 Dhision of Environmental Health & Safety (DEH&S), which is the Altemate Emergency Support Center (ESC). The location of these buildings is shown on the detailed map (Attachment 2). Both bundings are within 150 yards of the Nuclear Reactor Laboratory. 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) Astital or projected radiation levels at the site (op_grations) boundary of 20 mrem /hr (0.2 mSv/hr)

Regp Dose Equivalent (DDE) for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. based ortEast Wall Area Radiation Monitor (ARM): or 100 mrem (1.0 mSv) Committed Dose Equivalent (CDE) to the thyroid: Same as in a)immediately above, c) Severe failure of fuel cladding or of fueled experiments where containment boundaries exist to reduc _s releases or less severe claddina failures in situations where fission products are not well containe_d: Same as in a) & b) immediately above.

d) Significant releases ofradioactive material as a result of experiment failures: Same as in a), b), and c) immediately above.

c) Loss of physical 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 Alert If the Reactor Building has been evacuated, all personnel who were in the facility at the time of the emergency shall be accounted for. Allindhiduals who evacuated the Reactor Building shall be surveyed for contamination with portable instruments. Those indhiduals 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. The ERPM is responsible for minimizing personnel exposure and the spread of contamination. E;nergency exposure levels for personnel shall be in accordance with Section 3.5 of this plan.

Page 21 of 27

, = , . . - . . . , . .

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".

6.6 Site Area Emergerigy 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 Repon (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 ofcoolant, and the ventilation system off, indicate that n

. emergency ofthis class would never occur. Hewever, an emergency condition where the Emergency Response Organization (ERO) may consider setting up traflic control or the evacuation of adiacent buildings may require limited entry into the provisions of this classification.

7.0 EMERGENCY FACILITIES AND EQUIPMENT 7.1 Emergency Suppon Centers The Nuclear Engineering Laboratory (NEL)is the Primary Emergency Suppon Center (ESC) and the Division of Environmental Health & Safety (DEH&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 buildhigs is shown on the detailed map (Attachment 2). Both buildings are within 150 yards ofthe Nuclear Reactor Laboratory. Since one is in a westerly direction and the other in an casterly direction, the choice could depend on the wind direction. The purpose of these facilities is to provide: a control center; an accountability station; and a radiological monitoring 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. Emergency Response directions would be given from one of these locations. Telephones and fax machines are available in both locations and the telephones and fax machine in NEL are under the control of the Nuclear Engineering Depanment. In addition, dedicated telephone lines are on each telephone in the Reactor Building. These are unpublished numbers to be used only in an emergency.

Fax capability is also available by computer modem on one of the computers in the Reactor Building.

7.2 Assessment Facilities The Reactor Lab has Area Radiation Monitors (ARMS) with readouts and alarm indications locally, by each detector, and in the control room; and Continuous Air Monitors (CAMS), both ofwhich readout locally and one of which reads out in the control room and provides a building wide alarm, as well as a trip that closes ,

the damper in the Building Exhaust Ventilation System sending the air ellluent through a charcoal filter bed prior to release out of the stack at an elevation of 60 feet above grade. The Department ofNuclear {

Engineering has counting laboratories at 106B NEL and 222 Materials Research Lab (MRL). Portable survey instrumems are kept near the entrance to the Reactor Lab and could easily be taken along during an evacuation. In addition, portable survey instruments may be readily obtained from: the Emergency Equipment Locker in Room 106B NEL, the Lab in Room 222 MRL, and the Campus Radiation Safety OfIice at the alternate ESC noted above. Gamma Spectroscopy equipment is available in both 106B NEL and 222 MRL and under the control of the Department ofNuclear Engineering. Ponable high and low volume air samplers are available in the Reactor Lab and the Emergency Equipment Locker.

Page 22 of 27

e Non-radiological monitors that may provide peninent information include: the primary and secondary control consoles, in the control room, which display all reactor status information; a smoke detector in the control room; and meteorological data that is readily available from the Illinois State Water Survey Office located On Campus.

More specific guidance on this topic can be found in EPIP-09, " Assessment, Corrective, and Protective Action Procedures".

7.3 First Aid. Medical. and Decontamination Facilities Carle Clinic Association would be utilized as the decontamination center by the Champaign County ESDA.

The " Radiation Accident Program" procedures for Carle Clinic arc included in Attachment 5. This hospitalis 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 senice, or automobiles owned by Reactor Staffpersonnel. If an individual becomes contaminated with no physicalinjury requiring immediate treatment, decontamination would be done in the decon sink or shower located in the lower level of the Reactor Building. He drains to this sink and shower are collected in the Retention Tank, which is pumped through a 0.45 micron filter to a holdup tauk where it is sampled and counted for soluble and insoluble radioactivity prior to release to the sanitary sewer system.

l More specific guidance on this topic can be found in EPIP-03, " Nuclear Reactor Lab Emergency Call List -

Intrusion / Emergency", EPIP-06, " Radiation Protection Manager Procedures", EPIP-07, " Emergency Medical, Security, Fire, and Plant Services Manager Procedures", EPIP-09, " Assessment, Corrective, and Protective Action Procedures", and EPIP-II,"Suppon Agency Procedures", as well as Attachment 5.

7.4 Communications Equipment Telephones and fax machines are available in both Emergency Support Centers (ESC) and the telephones and fax machine in the NEL Support Center are under the control of the Nuclear Engineering Department. In addition, dedicated telephone lines are on each telephone in the Reactor Building. These are unpublished numbers to be used only in an emergency. Fax capability is also available by computer modem on one of the computers in the Reactor Building. The University Police can also be summoned on activation of the intrusion alarm system by pressing a button in the control room. The University Police and Fire Department personnel also maintain a radio system for connuunication 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 water would drain to a hold up tank (Retention Tank) and any particulate activity in the air would be trapped in the HEPA exhaust filters, ample time would be available to meet at some other location and formulate plans for a given scenario. Specific recovery procedures for an actual emergency event will be written and approved as needed. Guidelines on recovery and rcentry 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 rates on the building exterior and within the building as conditions warrant.

3. Contamination outside the facility and within the building as conditions warrant.

Page 23 of 27

o .

, mwom P:rsonnel entering the building would be required to wear appropiiate protective clothing until contamination levels have been evaluated. Doses to individuals should be kept within the 10 CFR 20 limits, except for Planned

- Special Exposures as noted in Section 3.5.

9.0 MAINTAINING EM'ERGENCY PREPAREDNESS 9.1 Training Initial training shall be provided to all individuals occupying positions designated in this plan. 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.

3. A review of the Emergency Call List and proced ire.

4. Methods by which to recognize 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 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 Smveillance".

9.2 Conduct ofDrills and Exercises Onsite Emergency Drills or Exercises, to be conducted as Action Drills, shall be held on an alternating annual

- basis, at intervals not to exceed 15 months; An 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 particular 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 found in EPIP-13, " Drills and Exercises".

9.3 Critiques of Drills and Exercises A Critique of the Drill or Exercise shall be held immediately following its completion. This 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".

Page 24 of 27

9.4 Ilill and Exercise Scenarios ne Emergency Coordinator, with the assistance of the Emergency Director, shall develop a written scenario for the conduct of the alternating annual Action Drill or Exercise, at inten'als not to exceed 15 months.

More specific guidance on this topic can be found in EPIP-13," Drills and Exercises".

9.5 Eme1gency Plarmeview and Update The Emergency Plan, the Emergency Plan Implementing Procedures, and the Agreements with Offsite 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, Exercises, or changes in the facility or environs, shall be incorporated into each revision. Updated revisions shall be distributed to all 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 Administrator, .t reviewed by the Reactor Conuuittee, and transmitted to the authorized recipients within 30 days afler the revised plans have been issued.

More specific guidance on this topic can be found in EPIP-05, " Emergency Coordinator Procedures" 9.6 Emergency Equipment Maintenance and Surveillance The major sources ofradiation monitoring equipment that would be immediately available in an emergency I are: 1) the Control Room and Reactor Health Physicist's Office at the Nuclear Reactor Lab in or near the l lobby area by the main door; 2) the Radiation Safety Oflice (RSO) at both, a) 101 S. Gregon St., Urbana

{ and b) the Dynamics Testing Laboratory,601 E. Curtis Road, Champaign; c) Room 106B NEL; and d)

Room 222 MRL Additional equipment, ifthe 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 Surveillance" 9.6.1 Inventory ofEquipment and Supylies e The instruments 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 instmments available within the Department of Nuclear Engineering (primarily gamma spectrometers)in 106B NEL and 222 MRL. The Reactor Lab instruments are function tested as pan of the " Health Physics Daily 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 functionally teste i as pan of their semiannual or annual calibration. The minimum frequency for inventory of Emergency Equipment and Supplies shall be annual, at intervals not to exceed 15 months, and include allinstruments listed in this section of the Emergency Plan.

More specific guidance on this topic can be found in EPIP-14," Emergency Equipment Maintenance and Surveillance" Page 25 of 27 l

)

Nuclear Reactor Lab Equiprusnl:

l Total Number Available Equipment Designation Range 1

Victoreen 450 (Ion Chamber) 0 - 50 R/hr 1

Eberline RO - 2 (Ion Chamber) 0 - 5 R/hr 1 Neutron Rem Meter 0 - 5 Rem /hr 8 Electronic Pocket Dosimeters 0 - 9999 mrem i 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 1- Johnson GSM-5 Count Rate Meters 0 - 50,000 cpm 1 Eberline DC-4 Beta Comiter 0 - 999,999 Counts 1 Eberline SAC-4 Alpha counter 0 - 999,999 Counts

1 Canberra HPGe y-ray spectrometer 0 - 3000 kev 1 Alpha Scintillation Probe ASP-2 N/A 1 HP-210T Probe N/A 1 HP-265 Probe N/A 1 HP-260 Probe _

N/A Emergency Equipment Locker (106B NEL):

Total Number Available Equipment Designation Range 1

Victorcen 450 (Ion Chamber) 50 IMr 1 Eberline E-140 Count Rate Meter 0 - 60,000 com 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 nun Glass Fiber Filter Papers N/A 1

Johnson GSM-5 Count Rate Meters 0 - 50,000 cpm 1 HP-260 Probe N/A 1 Johtison GSP-2A Probe N/A 3 boxes 100 each Paper Smears N/A 9/11 Protectivefdothing Coveralls / Hoods N/A 1 Dozen Rubber Gloves and Liners N/A 4 Dozen Plastic Shoe Covers N/A-1 Dozen Rubbers N/A Materials Research Lab (MRL) Room 222 Total Number Available Equipment Designation Range-1 Victoreen 450 (lon Chamber) 0 - 50 R/hr 1

Johnson GSM-15 Count Rate Meter 0 - 500,000 cpm 1 IIP-265 Probe N/A 2 - Gamma Spectroscopy Detectors N/A N_pte: The minimum equipment required to be operable at all times to maintain Emergency Preparedness shall be:

Page 26 of 27 9

.  ?

1 Ion Chamber. 5 Self-Reading Pocket Dosimeters.1 Count Rate Meter with G-M probe. and 1 Air Sampler. 'Ihis equipment shall be located in the Emergency Equipment Locker in Room 106B NEL. If, at any time, any of the above listed equipment should become inoperable it shall be immediately replaced.

9.6.2 Ea_diation Monitoring Eauipment Calibration:

All portable and laboratory analytical instruments are calibrated on a semiannual or annual basis.

More specific guidance on this topic can be fotmd in EPIP-14, " Emergency Equipment Maintenance and Surveillance".

9.7 Emergency Plan Implementing Procedures (EPIPs) List:

No. Title EPIP-01 General Instructions and Organizational Responsibilities.

EPIP-02 Reactor Operator Immediate 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, Secmity, 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-11 Coordination of 0ffsite Agencies Procedurcs.

EPIP-12 Training Procedures.

EPIP-13 Drills and Exercises.

EPIP-14 Emergency Equipment Maintenance and Surveillance.

EPIP-15 Documentation and Records.

Revised By: [ -

fark A. Kacio f@

Title:

Emergency Coordinator Date: _gff/

Reviewed By:

\]ionathan M. Ralston

Title:

Operations Supervisor Date: 5/22/6

' ' ~ ~

Approved By:*

~

Title:

Emergency Director Date: Yi ~)

_ " kich L. Holm Date Reviewed by the Reactor Conunittee: b h mA (eplan\eplanrev.597)

Page 27 of 27

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• E-Pla2 Attachment 4 Pcge1cf1 Emergency Response Organization (ERO)

Emergency Director (ED)

~

Emergency Emergency Duty Emergency Plant Emergency Public Coordinator Radiation SRO Services Manager Infonnation Manager

-(EC) Protection (EPSM) (EPIM)

Manager RO/SRO (ERPM)-

Champaign County University Omcc

. Emergency Services of Public Affairs Dm, ,ston of Reactor and Disaster Agency Emiromnental StafT (ESDA)

Health & Safety 4 (DEH&S)

Police, Fire, and Radiation Medical Safety Omccr (RSO)

(eplau\attchmt4, doc) -

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