Generic Procedures for Response to a Nuclear or Radiological Emergency at Research Reactors

Transcription

1 EPR- RESEARCH REactR Generic Prcedures fr Respnse t a Nuclear r Radilgical Emergency at Research Reactrs EmERGENcy PREPaREDNESS and RESPNSE P u b l i c at i n D at e : S E P t e m b E R

2 IAEA SAFETY STANDARDS AND RELATED PUBLICATIONS IAEA SAFETY STANDARDS Under the terms f Article III f its Statute, the IAEA is authrized t establish r adpt standards f safety fr prtectin f health and minimizatin f danger t life and prperty, and t prvide fr the applicatin f these standards. The publicatins by means f which the IAEA establishes standards are issued in the IAEA Safety Standards Series. This series cvers nuclear safety, radiatin safety, transprt safety and waste safety. The publicatin categries in the series are Safety Fundamentals, Safety Requirements and Safety Guides. Infrmatin n the IAEAs safety standards prgramme is available at the IAEA Internet site The site prvides the texts in English f published and draft safety standards. The texts f safety standards issued in Arabic, Chinese, French, Russian and Spanish, the IAEA Safety Glssary and a status reprt fr safety standards under develpment are als available. Fr further infrmatin, please cntact the IAEA at PO Bx 100, 1400 Vienna, Austria. All users f IAEA safety standards are invited t infrm the IAEA f experience in their use (e.g. as a basis fr natinal regulatins, fr safety reviews and fr training curses) fr the purpse f ensuring that they cntinue t meet users needs. Infrmatin may be prvided via the IAEA Internet site r by pst, as abve, r by t Official.Mail@iaea.rg. RELATED PUBLICATIONS The IAEA prvides fr the applicatin f the standards and, under the terms f Articles III and VIII.C f its Statute, makes available and fsters the exchange f infrmatin relating t peaceful nuclear activities and serves as an intermediary amng its Member States fr this purpse. Reprts n safety and prtectin in nuclear activities are issued as Safety Reprts, which prvide practical examples and detailed methds that can be used in supprt f the safety standards. Other safety related IAEA publicatins are issued as Radilgical Assessment Reprts, the Internatinal Nuclear Safety Grups INSAG Reprts, Technical Reprts and TECDOCs. The IAEA als issues reprts n radilgical accidents, training manuals and practical manuals, and ther special safety related publicatins. Security related publicatins are issued in the IAEA Nuclear Security Series. The IAEA Nuclear Energy Series cnsists f reprts designed t encurage and assist research n, and develpment and practical applicatin f, nuclear energy fr peaceful uses. The infrmatin is presented in guides, reprts n the status f technlgy and advances, and best practices fr peaceful uses f nuclear energy. The series cmplements the IAEAs safety standards, and prvides detailed guidance, experience, gd practices and examples in the areas f nuclear pwer, the nuclear fuel cycle, radiactive waste management and decmmissining.

3 Generic Prcedures fr Respnse t a Nuclear r Radilgical Emergency at Research Reactrs

4 The fllwing States are Members f the Internatinal Atmic Energy Agency: AFGHANISTAN ALBANIA ALGERIA ANGOLA ARGENTINA ARMENIA AUSTRALIA AUSTRIA AZERBAIJAN BAHRAIN BANGLADESH BELARUS BELGIUM BELIZE BENIN BOLIVIA BOSNIA AND HERZEGOVINA BOTSWANA BRAZIL BULGARIA BURKINA FASO BURUNDI CAMBODIA CAMEROON CANADA CENTRAL AFRICAN REPUBLIC CHAD CHILE CHINA COLOMBIA CONGO COSTA RICA CÔTE D IVOIRE CROATIA CUBA CYPRUS CZECH REPUBLIC DEMOCRATIC REPUBLIC OF THE CONGO DENMARK DOMINICAN REPUBLIC ECUADOR EGYPT EL SALVADOR ERITREA ESTONIA ETHIOPIA FINLAND FRANCE GABON GEORGIA GERMANY GHANA GREECE GUATEMALA HAITI HOLY SEE HONDURAS HUNGARY ICELAND INDIA INDONESIA IRAN, ISLAMIC REPUBLIC OF IRAQ IRELAND ISRAEL ITALY JAMAICA JAPAN JORDAN KAZAKHSTAN KENYA KOREA, REPUBLIC OF KUWAIT KYRGYZSTAN LATVIA LEBANON LESOTHO LIBERIA LIBYAN ARAB JAMAHIRIYA LIECHTENSTEIN LITHUANIA LUXEMBOURG MADAGASCAR MALAWI MALAYSIA MALI MALTA MARSHALL ISLANDS MAURITANIA MAURITIUS MEXICO MONACO MONGOLIA MONTENEGRO MOROCCO MOZAMBIQUE MYANMAR NAMIBIA NEPAL NETHERLANDS NEW ZEALAND NICARAGUA NIGER NIGERIA NORWAY OMAN PAKISTAN PALAU PANAMA PARAGUAY PERU PHILIPPINES POLAND PORTUGAL QATAR REPUBLIC OF MOLDOVA ROMANIA RUSSIAN FEDERATION SAUDI ARABIA SENEGAL SERBIA SEYCHELLES SIERRA LEONE SINGAPORE SLOVAKIA SLOVENIA SOUTH AFRICA SPAIN SRI LANKA SUDAN SWEDEN SWITZERLAND SYRIAN ARAB REPUBLIC TAJIKISTAN THAILAND THE FORMER YUGOSLAV REPUBLIC OF MACEDONIA TUNISIA TURKEY UGANDA UKRAINE UNITED ARAB EMIRATES UNITED KINGDOM OF GREAT BRITAIN AND NORTHERN IRELAND UNITED REPUBLIC OF TANZANIA UNITED STATES OF AMERICA URUGUAY UZBEKISTAN VENEZUELA VIETNAM YEMEN ZAMBIA ZIMBABWE The Agency s Statute was apprved n 23 Octber 1956 by the Cnference n the Statute f the IAEA held at United Natins Headquarters, New Yrk; it entered int frce n 29 July The Headquarters f the Agency are situated in Vienna. Its principal bjective is t accelerate and enlarge the cntributin f atmic energy t peace, health and prsperity thrughut the wrld.

5 E P R - R E S E a R c H R E a c t R Emergency Preparedness and Respnse Generic Prcedures fr Respnse t a Nuclear r Radilgical Emergency at Research Reactrs

6 COPYRIGHT NOTICE All IAEA scientific and technical publicatins are prtected by the terms f the Universal Cpyright Cnventin as adpted in 1952 (Berne) and as revised in 1972 (Paris). The cpyright has since been extended by the Wrld Intellectual Prperty Organizatin (Geneva) t include electrnic and virtual intellectual prperty. Permissin t use whle r parts f texts cntained in IAEA publicatins in printed r electrnic frm must be btained and is usually subject t ryalty agreements. Prpsals fr nn-cmmercial reprductins and translatins are welcmed and cnsidered n a case-by-case basis. Enquiries shuld be addressed t the IAEA Publishing Sectin at: Sales and Prmtin, Publishing Sectin Internatinal Atmic Energy Agency Vienna Internatinal Centre PO Bx Vienna, Austria fax: tel.: sales.publicatins@iaea.rg Fr further infrmatin n this publicatin, please cntact: Incident and Emergency Centre Department f Nuclear Safety and Security Internatinal Atmic Energy Agency Vienna Internatinal Centre PO Bx Vienna, Austria fficial.mail@iaea.rg GENERIC PROCEDURES FOR RESPONSE TO A NUCLEAR OR RADIOLOGICAL EMERGENCY AT RESEARCH REACTORS IAEA, VIENNA, 2011 IAEA-EPR IAEA, 2011 Printed by the IAEA in Austria September 2011

7 FOREWORD Under Article 5.a(ii) f the Cnventin n Assistance in the Case f a Nuclear Accident r Radilgical Emergency (Assistance Cnventin), ne functin f the IAEA is t cllect and disseminate t States Parties and Member States infrmatin cncerning methdlgies, techniques and results f research relating t respnse t nuclear r radilgical emergencies. The IAEA publishes the Emergency Preparedness and Respnse Series t fulfil that functin. This publicatin is part f that series. IAEA Safety Standards Series N. GS-R-2 Preparedness and Respnse fr a Nuclear r Radilgical Emergency, cntains the fllwing requirement: T ensure that arrangements are in place fr a timely, managed, cntrlled, crdinated and effective respnse at the scene. The IAEA General Cnference, in reslutin GC(53)/RES/10, cntinues t encurage Member States t enhance, where necessary, their wn preparedness and respnse capabilities fr nuclear and radilgical incidents and emergencies, by imprving capabilities t prevent accidents, t respnd t emergencies and t mitigate any harmful cnsequences. This publicatin is intended t assist Member States meet the requirements f GS-R-2 and enhance their preparedness by prviding guidance n the respnse by facility persnnel t emergencies at research reactr facilities. The IAEA fficer respnsible fr this publicatin was G. Winters f the Department f Nuclear Safety and Security.

8 EDITORIAL NOTE The use f particular designatins f cuntries r territries des nt imply any judgement by the publisher, the IAEA, as t the legal status f such cuntries r territries, f their authrities and institutins r f the delimitatin f their bundaries. The mentin f names f specific cmpanies r prducts (whether r nt indicated as registered) des nt imply any intentin t infringe prprietary rights, nr shuld it be cnstrued as an endrsement r recmmendatin n the part f the IAEA.

9 CONTENTS 1. INTRODUCTION Backgrund Objective Scpe Structure OVERVIEW Emergency Respnse Prcess Emergency Class Prtective Actin Planning Emergency Respnse Team Facility Respnse Manager Radilgical Prtectin Manager Envirnmental Analyst Decntaminatin Team Leader Prtective Actin Manager Prjectin Analyst Nuclear Cnditin Analyst Cmmunicatr Plant Security Manager INFORMATION TABLES Emergency Classificatin Table Table A Emergency Respnse Pririties Table A Guidance Values fr Limiting Expsure f Emergency Wrkers Table B Envirnmental Mnitring Pririties Table B.2 in Part Prtective Actins Based n Envirnmental Measurements Table C.2, Part 1, and Table B.3, Part Default Screening OILs fr Fd, Milk, and Water Cncentratins, Default Radinuclide-specific OILs fr Fd, Milk, and Water Activity Cncentratins and Equilibrium Radiactive Chains Tables C.3, C.4 and C.5, Part 1 nly Cntainment Release Rate Guide Table D.1, Part WORKSHEETS SITE EMERGENCY PLAN AND TRAINING PART 1: RESPONSE TO A NUCLEAR OR RADIOLOGICAL EMERGENCY AT THREAT CATEGORY II RESEARCH REACTORS ACTION GUIDES AG.A.1. FACILITY RESPONSE MANAGER AG.B.1. RADIOLOGICAL PROTECTION MANAGER AG.B.2. ENVIRONMENTAL ANALYST AG.B.3. DECONTAMINATION TEAM LEADER AG.C.1. PROTECTIVE ACTION MANAGER AG.C.2. PROJECTION ANALYST AG.D.1. NUCLEAR CONDITION ANALYST AG.E.1. COMMUNICATOR AG.F.1. PLANT SECURITY MANAGER... 62

10 WORKSHEETS WORKSHEET A.1. RESPONSE ORGANIZATION ASSIGNMENTS WORKSHEET A.2. FACILITY RESPONSE MANAGER S CHECKLIST WORKSHEET B.1. SITE RADIATION ENVIRONMENT WORKSHEET B.2. NEAR-SITE DOSE RATE MEASUREMENTS 400 METRES WORKSHEET B.3. FAR-FIELD DOSE RATE MEASUREMENTS 8 KILOMETRES WORKSHEET B.4. REGISTRY FORM FOR PERSONS INVOLVED IN EMERGENCY WORKSHEET B.5. VICTIM CONTAMINATION CONTROL RECORD (ON-SCENE ASSESSMENT) WORKSHEET C.1. EVACUATION, THYROID BLOCKING AND SHELTERING MAP WORKSHEET C.2. FOOD RESTRICTION AND RELOCATION MAP WORKSHEET C.3. PROTECTIVE ACTION PROJECTIONS WORKSHEET C.4. ON-SITE PROTECTIVE ACTIONS WORKSHEET C.5. PREPARATION FOR OFF-SITE PROTECTIVE ACTIONS WORKSHEET C.6. RECOMMENDED OFF-SITE PROTECTIVE ACTIONS WORKSHEET D.1. EMERGENCY CONDITION ASSESSMENT WORKSHEET D.2. FUEL DAMAGE AND CONTAINMENT ASSESSMENT WORKSHEET E.1. CALL LIST FOR OFF-SITE CONTACT POINTS WORKSHEET E.2. EMERGENCY NOTIFICATION RECORD APPENDICES TO PART 1 APPENDIX I: EMERGENCY RESPONSE EQUIPMENT APPENDIX II: EMERGENCY WORKER BRIEFING APPENDIX III: CONTACT WITH THE MEDIA APPENDIX IV: DETERMINATION OF THE UPZ SIZE FOR THREAT CATEGORY II RESEARCH REACTORS PART 2: RESPONSE TO A NUCLEAR OR RADIOLOGICAL EMERGENCY AT THREAT CATEGORY III RESEARCH REACTORS ACTION GUIDES AG.A.1. FACILITY RESPONSE MANAGER AG.B.1. RADIOLOGICAL PROTECTION MANAGER AG.C.1. MONITORING TEAM LEADER AG.C.2. DECONTAMINATION TEAM LEADER AG.C.3. COMMUNICATOR AG.D.1. PLANT SECURITY MANAGER WORKSHEETS WORKSHEET A.1. RESPONSE ORGANIZATION ASSIGNMENTS WORKSHEET A.2. FACILITY RESPONSE MANAGER S CHECKLIST WORKSHEET A.3. EMERGENCY CONDITION ASSESSMENT WORKSHEET B.1. SITE RADIATION ENVIRONMENT WORKSHEET B.2. ON-SITE PROTECTIVE ACTIONS WORKSHEET C.1. CALL LIST FOR OFF-SITE CONTACT POINTS WORKSHEET C.2. EMERGENCY NOTIFICATION RECORD

11 WORKSHEET C.3. VICTIM CONTAMINATION CONTROL RECORD (ON-SCENE ASSESSMENT) WORKSHEET C.4. REGISTRY FORM FOR PERSONS INVOLVED IN EMERGENCY APPENDICES TO PART 2 APPENDIX I: EMERGENCY RESPONSE EQUIPMENT APPENDIX II: EMERGENCY WORKER BRIEFING APPENDIX III: CONTACT WITH THE MEDIA LIST OF ABBREVIATIONS REFERENCES CONTRIBUTORS TO DRAFTING AND REVIEW

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13 1. INTRODUCTION 1.1. BACKGROUND Under Article 5(a)(ii) f the Cnventin n Assistance in the Case f a Nuclear Emergency r Radilgical Emergency, ne functin f the IAEA is t cllect and disseminate infrmatin cncerning nuclear and radilgical emergency respnse methdlgies, techniques and available results f research t States Parties and Member States relating t respnse t such emergencies. Several publicatins have been published with generic guidelines fr respnse t radiatin emergencies [1, 2, 3, 4]. The IAEA published guidance t prvide Member States a set f emergency respnse prcedures fr nuclear pwer plants [1]. This publicatin prvides guidance fr develpment f emergency respnse prcedures and implementatin f an Emergency Plan at research reactrs in Threat Categries 1 II and III. A research reactr in Threat Categry III is nt expected t create a situatin where members f the public beynd the site bundary are threatened by any reactr emergency. Research reactrs with pwer levels up t abut 2 MW are usually in this categry. Research reactrs with higher pwer levels are in Threat Categry II and may threaten the public beynd the site bundary during severe emergencies.[5] The difference in affected ppulatins creates a difference in the respnse rganizatin as well as a difference in the scpe f the respnse actins that may be required. Each research reactr perating rganizatin shuld evaluate the cnsequences f reactr emergencies, including events with lw prbability [6] and determine the apprpriate Threat Categry fr that reactr. The analyses perfrmed fr the reactr Safety Analysis Reprt [7] may already include the necessary wrk t determine if there is a risk t the ff-site ppulatin and the extent f that risk in terms f ptential radiatin dses t members f the public and the distance frm the reactr that culd warrant implementatin f urgent prtective actins by members f the public. The guidance in this publicatin is expected t be suitable fr research reactrs with pwer levels frm zer-pwer critical facilities t several tens f MW OBJECTIVE The bjectives f this publicatin are: T describe apprpriate respnses t a range f emergencies at Threat Categry II and III research reactr sites; T describe the n-site rganizatin needed t respnd t these emergencies; T prvide tls t rganize the emergency respnse actins at these reactr sites; T prvide prcedures n hw t determine the need fr n-site and ff-site prtective actins. 1 The term threat categry is used here as described in Ref. [5] and nly fr the purpses f emergency preparedness and respnse; this usage des nt imply that any threat, in the sense f an intentin and capability t cause harm, has been made in relatin t facilities, activities r surces. 1

14 1.3. SCOPE The guidance in this publicatin cncerns emergencies at research reactrs in Threat Categry II and III. Prcedures are prvided fr the n-site respnse and, fr Threat Categry II nly, the additinal apprpriate ff-site respnse. This guidance is presented in tw separate parts that fllw this Intrductin. Each part cntains all the material fr the respnse t emergencies at a research reactr in the applicable Threat Categry. This publicatin cvers the determinatin f the apprpriate emergency class and prtective actins fr a nuclear r radilgical emergency at research reactrs. It des nt cver nuclear security at research reactrs. The term threat categry is used in this publicatin as described in Ref. [5] and fr the purpses f emergency preparedness and respnse nly; this usage des nt imply that any threat, in the sense f an intentin and capability t cause harm, has been made in relatin t facilities, activities r surces. The threat categry is determined by an analysis f ptential nuclear and radilgical emergencies and the assciated radiatin hazard that culd arise as a cnsequence f thse emergencies STRUCTURE The publicatin cnsists f fur parts. This sectin is an Intrductin t the backgrund, bjective, scpe and structure f the publicatin. Sectin 2, Overview, explains hw the emergency respnse prcedures are rganized, the respnse team structure n which the guidelines are based, respnsibilities f each respnse team member and infrmatin t assist develping site-specific prcedures frm the generic prcedures prvided here. The remaining tw parts are labelled Part 1 and Part 2. Each Part cntains a cmplete set f generic emergency respnse prcedures fr Threat Categry II research reactrs and Threat Categry III research reactrs, respectively. Research reactrs up t several tens f MW are cvered by these generic emergency respnse prcedures. Appendices with each Part prvide supplementary infrmatin. The emergency respnse prcedures in each Part cnsist f Actin Guides that are the generic emergency respnse prcedures fr the site emergency respnse team psitins and Wrksheets that may be used t assist infrmatin rganizatin and recrding during the respnse. Emergency respnse infrmatin adapted t the TRIGA design and details f TRIGA fuel and ptential releases frm the fuel in reactr emergencies are prvided in Ref. [8] fr use with the emergency respnse prcedures in Part 1 r Part 2. The terms used in this publicatin are defined in Refs [9] and [10] and a List f Abbreviatins is included befre the References. Further, the terms site and facility are used interchangeably thrughut the publicatin EMERGENCY RESPONSE PROCESS 2. OVERVIEW An emergency at a research reactr initiates tw different sets f actins. The reactr perating persnnel react t the emergency by implementing the apprpriate emergency perating prcedures. These prcedures are intended t return the reactr and the assciated supprt systems t a safe and stable cnditin. Guidance fr the emergency perating 2

15 prcedures is prvided in ther publicatins, including sme publicatins published by the IAEA such as Refs [7] and [11]. The emergency respnse actins are intended t prevent r mitigate radilgical threats t individuals, bth at the reactr site and beynd the site bundary. An Emergency Respnse Team at the reactr site has the respnsibility t implement this emergency respnse prcess. The size f the Emergency Respnse Team needed t adequately manage the actins necessary t prtect peple frm the radilgical threat that ccurs due t the emergency will depend n the size f the site, the reactr threat categry and the number and lcatin f peple at risk frm the emergency. Research reactr sites may have mre than ne nuclear r radilgical installatin. In this publicatin, n distinctin is made between the research reactr facility and the site n which the research reactr is lcated. Further, in this publicatin the wrds facility and site are used interchangeably. The prcedures prvided here may serve either a single research reactr r an entire site. The reactr perating rganizatin may adapt these prcedures t either situatin. The individuals wh are needed t fill the rles n the Emergency Respnse Team may cme frm the reactr staff r the verall site rganizatin. Sme sites may wish t implement these prcedures at bth rganizatin levels, and crdinate the respnse actins. Research reactr pwer level and perating schedule determines the reactr fissin prduct inventry that culd be released during an emergency. Mst f the emergencies at research reactrs create a risk t individuals due t the ptential fr fuel damage that culd release the fuel fissin prducts. Lw pwer research reactrs are less f a risk because the decay heat frm fissin prducts is unlikely t cause a grss failure f the fuel, and less severe fuel damage limits the amunt f fissin prducts released frm the fuel. In cases where a threat assessment shws that n event, even thse with lw prbability, creates a risk t peple beynd the site bundary, then the research reactr is a Threat Categry III facility. The Emergency Respnse Team fr Threat Categry III may be smaller due t the absence f need t prtect peple beynd the site bundary. Figure 1 shws an Emergency Respnse Team suitable fr Threat Categry III facilities. The prcedures in Part 2 f this publicatin are based n this rganizatin. FIG. 1. Threat Categry III Emergency Respnse Team. Research reactrs that can create a risk t ff-site persnnel are Threat Categry II facilities and require additinal psitins n the Emergency Respnse Team t respnd t the ff-site 3

16 cnsequences. The rganizatin in Figure 2 is intended t prvide the necessary psitins. Threat Categry II research reactrs ften are lcated at sites with mre resurces and the larger Emergency Respnse Team can be accmmdated. There are multiple ways t rganize an Emergency Respnse Team and the nes presented here may nt fit the needs f every research reactr. Additinal psitins may be needed t accmplish tasks nt directly assciated with mitigating the radilgical threat. Each site shuld determine a suitable rganizatin and then mdify the Actin Guides depending upn the actins assigned t each individual rle n the Emergency Respnse Team. FIG. 2. Threat Categry II Emergency Respnse Team. The emergency respnse prcess may be viewed as cnsisting f three phases: Early Phase T stabilize the reactr cnditin; T rapidly assess the emergency and initiate actins t mitigate the cnsequences f the emergency; T minimize radiatin expsure t n-site persnnel and arriving ff-site respnders; Middle Phase T request the apprpriate level f ff-site assistance; T determine the need fr ff-site prtective actin; T keep the public infrmed; and Late Phase T return the facility t a nrmal perating state. The first step in the early phase is the respnsibility f the reactr perating persnnel with directin prvided by reactr emergency perating prcedures. The remaining steps are the respnsibility f the Emergency Respnse Team with directin frm emergency respnse prcedures, such as thse in this publicatin. A part f the late phase cnsists f recvery actins rather than emergency respnse actins. The transitin frm emergency respnse t recvery is an imprtant step and ne that must be planned. The Emergency Respnse Team and any rganizatins external t the site that were invlved in the emergency respnse must 4

17 develp a set f cnditins that need t be achieved t allw this transitin t ccur. Once the recvery respnse begins, it is assumed that sme ther rganizatin, perhaps even the nrmal facility rganizatin, is respnsible fr recvery actins, and the Emergency Respnse Team has cmpleted its respnsibilities EMERGENCY CLASS An internatinally recgnized emergency classificatin system is used t classify an emergency depending n the severity level f the emergency and the respnse actins are initiated accrdingly. Ref. [6] describes fur classes fr nuclear and radilgical emergencies. The classes, in rder f highest severity t lwest, are General Emergency, Site Area Emergency, Facility Emergency and Alert. Threat Categry II research reactrs can experience emergencies at any f these levels f severity. The classes f General Emergency and Site Area Emergency invlve threats t peple beynd the site bundary s Threat Categry III facilities d nt require thse tw classes. A General Emergency shuld be declared if an actual release r substantial risk f a release is present and radiatin expsure t members f the public culd ccur unless urgent prtective actin is implemented ff-site. An event that includes significant fuel damage is ne situatin that may meet these cnditins. Nte that a release des nt have t ccur t declare a General Emergency. The presence f significant fuel damage may present enugh f a substantial risk that a General Emergency shuld be declared. When the event causes a majr decrease in the level f prtectin fr thse n the site and the ff-site ppulatin near the facility then the apprpriate emergency class is Site Area Emergency. An example f the cnditins fr this emergency class is a risk that culd, if the cnditin wrsened, result in fuel damage r a cnditin where sme minr fuel damage has already ccurred. Facility Emergency is an emergency class that des nt pse a risk t the ff-site ppulatin, but represents a majr decrease in the level f prtectin fr n-site persnnel nly and is nt expected t evlve int a situatin psing a threat ff-site. On-site persnnel are expected t have t implement urgent prtective actin t reduce the risk. The least severe emergency class is an Alert. This class invlves unknwn r significant decrease in the level f prtectin fr n-site persnnel r the public. The expectatin fr every emergency class is that an Emergency Respnse Team f psitins described in Sectin 2.4 will be activated at a level apprpriate t the emergency situatin. The purpse f activating the Team is t relieve the perating staff f the dual duties f perating the reactr and fulfilling the rles n the Team as they must d initially. The replacement Team members allw the perating staff t give their undivided attentin t mitigatin f the cnsequences f the event in the reactr facility withut distractins frm ff-site inquiries and ther cmmunicatins. There are als emergencies that d nt require an emergency respnse at even the level f an Alert because there is n r nly an insignificant threat f radilgical cnsequences frm the event. The facility may initiate sme prtective measures and may require ff-site assistance, but unless a radilgical threat is present, the emergency respnse wuld nt be expected t fllw these respnse prcedures. 5

18 The classificatin prcess invlves judgement. These prcedures are nt a substitute fr gd judgement, but are intended t prvide descriptive scenaris t allw much f that judgement t be prvided in the frm f written guidance, including: Symptms defined by specific values f parameters bservable by the peratrs, Operating status f reactr safety systems, r Cnditins external t the facility. This cncept shuld be recgnized during the preparatin prcess f adapting these respnse prcedures t the needs f the facility and the facility persnnel PROTECTIVE ACTION PLANNING There is ptential risk f radiatin expsure t n-site r ff-site persnnel in all radiatin emergencies. Planning is needed t determine hw t implement the apprpriate prtective actins fr the emergency situatin. Prtective actins may be urgent r lng term. Urgent prtective actins are thse which must be implemented prmptly, usually within a few hurs, t be effective. Examples are evacuatin, sheltering, decntaminatin r restrictin f cnsumptin f certain fds. Relcatin is an example f a lng term prtective actin. Ref. [5] describes tw prtective actin znes: urgent prtective actin planning zne (UPZ); and precautinary actin zne (PAZ). Bth are rughly circular areas cantered n the reactr facility and the PAZ is the area clsest t the reactr facility. Fr Threat Categry III research reactrs bth f these znes are expected t be within the site bundary. This is a direct cnsequence f the absence f risk t the ff-site ppulatin. Threat Categry II research reactrs are expected t have the PAZ within the site bundary, but the UPZ may extend a few kilmetres utward frm the site bundary. The bundary f the UPZ must be determined by the facility based n an analysis f the radilgical cnsequences f the emergencies that pse a risk t the ff-site ppulatin. Then the UPZ bundaries need t be cmmunicated t the ff-site rganizatin that has the authrity t implement prtective actins in the UPZ. Determinatin f the sizes f the znes is described in Appendix IV f Part 1. In sme cases, the research reactr threat assessment may shw exceptins t the expectatins that the PAZ des nt extend ff-site. Sites with small cntrlled areas r residential areas clse t site bundaries culd determine that the PAZ includes areas beynd the site bundary. These situatins require clse cperatin with the ff-site authrities. The specific scenari fr the emergencies ptentially affecting the ff-site ppulatin needs t be included in the emergency planning s that n the ccurrence f such an emergency prmpt urgent prtective actin based slely n plant cnditins can be recmmended t the ff-site authrities. One difference between the PAZ and the UPZ with regard t prtective actin implementatin is the prcess t determine when prtective actins are necessary. Fr the UPZ, urgent prtective actins are usually implemented nly if radilgical mnitring shws that radiatin levels exceed peratinal interventin levels (OIL) that have been established based upn natinal regulatins r internatinal standards. In cntrast, within the PAZ, urgent prtective actins are implemented immediately n the basis f cnditins at the facility [6] with the aim f preventing r reducing the ccurrence f severe deterministic effects [2]. Since the UPZ fr Threat Categry II is ff-site, the facility can nly recmmend urgent prtective actins t the ff-site authrities, and may nt even be perfrming the envirnmental mnitring that is evaluated t determine if urgent prtective actins are 6

19 necessary. Nevertheless, Ref. [5] requires that there be arrangements with the ff-site authrities t make decisins n prtective actin prmptly upn ntificatin f a nuclear r radilgical emergency at the facility. Prtective actins based n envirnmental measurements are determined by cmparing the measured radiatin levels t OILs. Default, als called baseline, OIL values are prvided in this publicatin based n Ref. [12]. Mst cmmnly available radiatin mnitrs are suitable fr cmparing measured values t the baseline OILs. Ref. [12] als cntains a methd t verify instrument suitability t cmpare instrument reading t the baseline OILs EMERGENCY RESPONSE TEAM The psitins n the Emergency Respnse Team are temprary rles, needed fr the emergency respnse nly, and then ended when the recvery phase begins. The site Emergency Plan must identify the individuals wh are designated t fill thse rles when an emergency ccurs. Nrmally several individuals will be designated fr each rle t ensure adequate emergency respnse fr extended perids f time and adequate respnse during times f individual unavailability such as business travel, illness r vacatins. Certain rles are s imprtant that individuals must always be available at the research reactr t fill the rle. One f these imprtant rles is the Facility Respnse Manager. This psitin has immediate duties t perfrm when an emergency ccurs and Ref. [5] requires that there always be an individual n the site t perfrm thse duties. The psitins n the Emergency Respnse Team are described in the fllwing paragraphs. Where the respnsibility differs between Threat Categry II and Threat Categry III thse differences are discussed. The usual difference is that with fewer psitins, the Threat Categry III respnse team cmbines respnsibilities. Hwever, as part f the prcess f adapting these prcedures t a particular facility, it culd be decided t use a larger rganizatin and nt cmbine respnsibilities as is described belw. The nly cnstraint shuld be what the facility can supprt with persnnel and wrking space Facility Respnse Manager The senir individual respnding t the emergency is designated the Facility Respnse Manager in these prcedures and takes charge at the site. The Emergency Plan shuld identify wh is assigned this respnsibility based n psitin at the facility, and with a single chain f preferences. Fr example, the chain f individuals wh are designated the Facility Respnse Manager may shw the Reactr Manager, r the site equivalent, as the first chice, the Chief Operatr as the secnd chice and the n-duty Reactr Operatr as the third chice. The purpse f this chain f individuals is t always have smene at the reactr r the site prepared and authrized t perfrm the functins assigned t the psitin f Facility Respnse Manager. This psitin is needed fr bth Threat Categry II and Threat Categry III research reactrs. The Facility Respnse Manager is respnsible fr assessment f the emergency cnditins in rder t determine the emergency classificatin and then initiate the apprpriate respnse, including ntificatins that cause a respnse team t assemble and warn the ff-site authrities f the emergency cnditin. The psitin is the leader f a team f mre detailed specialists wh are expected t respnd t the emergency. Respnsibilities f the Facility Respnse Manager include: 7

20 Determine that an emergency has ccurred and establish the apprpriate respnse team; Cncur with the emergency class determined by the Nuclear Cnditin Analyst; Direct the actins f the Emergency Respnse Team; Annunce the emergency n-site and rder n-site prtective actins; Ntify ff-site authrities and recmmend ff-site prtective actins r preparatin fr ff-site prtective actins; Verify accuntability f all the persnnel wh were n the site when the emergency began; Declare an end t the emergency phase f the respnse, thus cmmencing the recvery phase Radilgical Prtectin Manager The facility psitins that serve in the rle f Radilgical Prtectin Manager shuld als be designated by the Emergency Plan, and are usually frm the rganizatin respnsible fr radiatin prtectin at the reactr. This individual may be a Radiatin Prtectin Technician at first if n ther individuals frm the Radiatin Prtectin rganizatin are present. The Radilgical Prtectin Manager is respnsible t: Develp a plan t mnitr the radiatin envirnment n the site first, then ff the site (r simultaneus if enugh Mnitring Teams are available) and supervise the cllectin f the data; Evaluate the need fr medical assistance and/r decntaminatin and recmmend an assistance request fr the needed supprt frm ff-site thrugh the Facility Respnse Manager; Assess envirnmental mnitring data as it is reprted and alert the Prtective Actin Manager when mnitring shws that OILs are being exceeded; Specifically authrize unnecessary persnnel t leave the site; Authrize Emergency Wrkers t exceed ccupatinal expsure limits; Obtain infrmed cnsent frm Emergency Wrkers prir t their assignment t interventin tasks. This psitin is needed fr bth Threat Categry II and Threat Categry III research reactrs. The Radilgical Prtectin Manager is assisted with an Envirnmental Analyst and a Decntaminatin Team Lead Envirnmental Analyst The envirnmental mnitring is dne by Mnitring Teams using a mnitring plan apprved by the Radilgical Prtectin Manager. The Envirnmental Analyst is respnsible t supervise these Mnitring Teams, including, but nt limited t: Cnducting briefings fr assigned tasks t the Mnitring Teams; Verifying suitability f mnitring equipment fr the assigned tasks; 8

21 Prmptly reprting results t the Radilgical Prtectin Manager and, if directed, t the Prtective Actin Manager; Ensuring persnal safety f the Mnitring Teams. Threat Categry III facilities may have the Mnitring Teams directly supervised by the Radilgical Prtectin Manager, and this is the arrangement shwn n Figure Decntaminatin Team Leader This may be a large r small team depending n the particular event. Hwever, several key respnsibilities are assigned. Specifically: Evaluating medical and radilgical cnditin f injured individuals; Recmmending the need fr prmpt ff-site medical first-aid when apprpriate; Determining if n-site persnnel are cntaminated, decntaminating them when necessary, and then recmmending their release t the Radilgical Prtectin Manager. The Threat Categry III research reactr may als chse t have the Radilgical Prtectin Manager directly supervise the Decntaminatin Team Prtective Actin Manager The Prtective Actin Manager may be immediately required t initiate certain prtective actins. The Emergency Plan shuld identify wh is assigned t this psitin s a clear respnsibility t perfrm the required duties assigned t a particular psitin. The respnsibilities are: Recmmend apprpriate prtective actins t the Facility Respnse Manager fr n-site persnnel; Recmmend ff-site prtective actins, based n emergency class r envirnmental data; Evaluate cllected envirnmental data and prject where OILs may be exceeded in rder t assist planning fr envirnmental mnitring; Revise default OILs if detailed analysis permits such revisin and infrm the Facility Respnse Manager f the ptin t implement the revised OILs. The Prtective Actin Manager is assisted by a Prjectin Analyst. The scpe f the prtective actins is reduced fr Threat Categry III research reactrs since there is n need fr ff-site prtective actins. Figure 1 mits this psitin and the n-site prtective actin respnsibility is transferred t the Radilgical Prtectin Manager Prjectin Analyst The Prjectin Analyst reprts t the Prtective Actin Manager and perfrms the prjectins that can alter the envirnmental mnitring plan. This psitin is als respnsible t cnsider revising OILs when mre detailed analysis f the radiactive material is perfrmed. The psitin may als perfrm hand r cmputer calculatins f radilgical cnsequences f a release frm the facility as part f the prjectin analysis. There is n need fr this psitin at Threat Categry III facilities. 9

22 Nuclear Cnditin Analyst The Nuclear Cnditin Analyst is a technical expert assigned t prvide detailed technical advice t the Facility Respnse Manager. The specific respnsibilities are: Evaluate the initial emergency cnditins and determine an emergency class; Maintain a clse awareness f reactr and cntainment cnditins t determine if a change t the emergency class is necessary, and if perating persnnel are successfully mitigating the emergency; Advise the Radilgical Prtectin Manager f actual r imminent fuel damage and ptential releases t the external atmsphere. Nte that fr sme research reactrs this psitin may be a team f individuals due t cmplexity f the reactr r the emergency. Even thugh there may be several technical specialists assigned t this team, the team must have a leader wh shall have the respnsibilities f Nuclear Cnditin Analyst. At Threat Categry III research reactrs the respnsibilities f this psitin may be perfrmed by the Facility Respnse Manager. Figure 1 des nt shw this psitin; hwever, the psitin may be added t reduce the wrk lad f the Facility Respnse Manager Cmmunicatr The Cmmunicatr assists with cmmunicatins between the Facility Respnse Manager and the ff-site authrities and media. Multiple ff-site cntact pints culd require mre than ne individual perfrming cmmunicatin functins. Hwever, nly ne f thse shuld be the Cmmunicatr t preserve cntrl f the cmmunicatins t ff-site authrities. The specific respnsibilities are: Initiate all ff-site ntificatins apprpriate t the emergency when directed t d s by the Facility Respnse Manager; Draft a media statement fr apprval by the Facility Respnse Manager and the apprpriate ff-site authrities; Infrm the Facility Respnse Manager f infrmatin r queries received frm ff-site that necessitate a respnse frm the site; When directed, initiate calls t ff-duty facility persnnel and request they reprt t the facility t assist with the emergency respnse. This psitin is needed fr bth Threat Categry II and Threat Categry III research reactrs Plant Security Manager The Plant Security Manager takes charge f site security, usually with specific actins determined by the site security plan. This psitin n the Emergency Respnse Team is t crdinate the actins in the site security plan with the emergency respnse prcedures. Specific functins f the Plant Security Manager are: Establish cntrl ver the site entry and exit pints such that nly necessary emergency respnse supprt can enter the site and nly individuals that the Radilgical Prtectin Manager determines t be unnecessary t the respnse may leave; Crdinate with lcal plice fficials if their respnse is necessary; Respnd t security threats t the facility as determined by the site security plan. 10

23 This psitin is needed fr bth Threat Categry II and Threat Categry III research reactrs. The n-duty perating persnnel may be the initial emergency respnders. This is mst likely t ccur when emergencies ccur utside the nrmal business hurs. In the emergency respnse rles they must assume, it may be necessary fr a single individual t perfrm the actins f multiple emergency respnse rles. Fr example, the senir peratins persn, perhaps the Shift Supervisr, at a Threat Categry II research reactr that experiences an emergency may have t perfrm sme steps frm the Facility Respnse Manager Actin Guide, since declaring an emergency cnditin and activating the respnse team are immediate actins fr this respnse psitin, and steps frm the Nuclear Cnditin Analyst Actin Guide since determining the emergency class is an immediate task f that respnse psitin. The facility staffing levels will determine hw the immediate respnse actins can be divided amng available persnnel. The facility Emergency Plan must make clear hw thse respnse rles are assigned t the n-duty peratins staff as well as identifying thse individuals authrized t replace peratins persnnel in the respnse rles. The psitin descriptins abve are nt the nly arrangement f respnsibilities that can be develped and each research reactr site shuld use an arrangement that best fits the circumstances. The nly cnstraint is t have sme ne persn respnsible fr the verall respnse, the Facility Respnse Manager, with subrdinate psitins slely respnsible fr a well-defined set f duties. The emergency respnse prcedures in this publicatin are, hwever, develped with the team structure described abve and shwn n Figure 1 r Figure 2. Each f the psitins has an Actin Guide that prvides sequential instructins fr perfrmance f the assigned tasks INFORMATION TABLES Tables accmpany sme f the Actin Guides t prvide infrmatin that is used in the decisin making prcess fr a particular Emergency Respnse Team psitin. The use f the tables is described belw. Sme tables are mitted frm Part 2 fr Threat Categry III research reactrs because f the respnse differences regarding ff-site threats Emergency Classificatin Table Table A.1 The classificatin table is the basis fr establishing the emergency class f an event. It is an aid t the Emergency Respnse Team by prviding symptms f an emergency and then descriptins f cnditins that determine levels f severity f that emergency. The severity descriptins are intended t use instrument values and reactr r reactr system cnditins related t the event s the peratrs may quickly establish an emergency class withut the need fr detailed calculatins r cnsultatins with individuals wh are nt n the site when the emergency is first recgnized. Each site may add detail and mre specific infrmatin t increase the usefulness f the table. When adding site-specific details t the Emergency Classificatin Table, the perating rganizatin shuld cnsider the level f severity f an event that requires activatin f an n-site emergency respnse team. A descriptin f an event that des nt need an emergency respnse team wuld nt be expected t be listed n the table. The intent f the emergency classificatin table is t describe events and severity that d require the assistance f an emergency respnse team in additin t the nrmal reactr peratins persnnel. Emergency classificatin tables that have been mdified t better describe events at TRIGA research reactrs are included in Ref. [8]. Bth Threat Categry II and Threat Categry III TRIGA Emergency Respnse Tables are prvided. 11

24 Observable symptms f an emergency are shwn in the left side clumn labelled Fr the fllwing entry cnditins. These are the abnrmal cnditins that alert the perating persnnel f a ptential emergency. The remaining clumns are descriptins f severity, with the mst severe cnditins that will determine the emergency class n the left. Cnditins with severe fuel damage are cnsidered t be a General Emergency due t the ptentially large release f fissin prducts which may escape frm the facility. The severity cnditins are described in terms f specific values n readily bserved instrumentatin r perating status f reactr equipment, cmpnents, such as cntrl rds, r systems. The Table in this publicatin is an example f a generic table, ne nt adapted t the terminlgy and details f a specific research reactr. The research reactr perating staff needs t mdify this example Table using reactr specific infrmatin that custmizes the Table t the facility. Additinal entry cnditins may be necessary t include a full range f the abnrmal cnditins that can indicate an emergency. Sme entry cnditins may be deleted if the situatin des nt cause an emergency situatin at the specific research reactr. The site-specific table, like that shwn fr Threat Categry II, may nt present severity descriptins fr all fur emergency classes fr every initiating event. Sme severity descriptins may nt be applicable fr a particular emergency event. Fr example, the site may cnclude that a particular event has n severity that crrespnds t Facility Emergency because if the severity is mre than an Alert, there is a ptential threat t the ff-site ppulatin and the crrect emergency class is Site Area Emergency. There may als be events that can never threaten the ff-site ppulatin and s d nt have the class f Site Area Emergency r General Emergency. The Nuclear Cnditin Analyst, with infrmatin frm bservatins f reactr parameters r with reprts frm the reactr perating persnnel uses the Emergency Classificatin Table t determine the emergency class that best matches the current cnditins. When the current cnditins fit mre than ne emergency class under different entry cnditins, the emergency class representing the mst severe emergency is the crrect chice. As always, selecting an emergency class requires judgement. The Classificatin Table is ne tl that can reduce the amunt f judgement needed in the stress f recgnizing an emergency by preparing written and carefully described guidance in the Table t assist the emergency respnders. The Classificatin Table fr Threat Categry III facilities is cnsiderably simpler than fr Threat Categry II due t needing nly tw emergency classes. Nevertheless, adapting the Table t the specific Threat Categry III research reactr is just as imprtant. The determinatin f the emergency class is a significant decisin because subsequent actins depend n that decisin, and the urgency f subsequent actins is als influenced by the emergency class. The initial decisin n emergency class is made by the Nuclear Cnditin Analyst. The decisin is expected within 15 minutes [6] f recgnizing an emergency cnditin. Infrmatin cllectin must be brief and quickly cncluded t make the decisin. The expectatin, and develpment f the Emergency Classificatin Table, is such that infrmatin readily available frm facility instrumentatin can prvide the necessary input t the decisin. Calls t managers r supervisrs wh are nt at the facility r assembling a grup f individuals wh are n the site t hld a meeting are imprper respnses t the need fr a prmpt decisin Emergency Respnse Pririties Table A.2 The purpse f this Table is t establish pririties f respnse actins and respnse time bjectives based n the emergency class. The respnse time bjectives are different fr Threat 12

25 Categry II and Threat Categry III. Specific values are taken directly frm Appendix VI f Ref. [6]. The pririties are imprtant in the first few hurs, r less, f the emergency respnse when there are ften mre tasks t initiate than the facility is able t respnd t. Ntificatin f ff-site authrities is anther prmpt actin and delays will cause subsequent actins t als be delayed. Fr example, failure t prmptly ntify ff-site authrities affects their ability t meet the time bjectives t activate the lcal level respnse rganizatin r the time bjective fr the natinal level rganizatin t react. The actins that initiate respnse frm ff-site authrities are expected t ccur sner than in situatins where the ff-site authrities are nt expected t react with their wn respnse actins. Thus, the emergency class and threat categry f the facility alter the respnse time bjectives. The actins and respnse time bjectives in Table A.2 are nly thse that are the respnsibility f the facility. There are als respnse time bjectives fr the lcal (ff-site) respnse rganizatins and the natinal rganizatin. These are nt included in this publicatin, but may be fund in Refs [2] and [6] Guidance Values fr Limiting Expsure f Emergency Wrkers Table B.1 When an emergency has been declared, certain radilgical standards are changed. Table B.1 is nly applicable during a declared emergency and permits increased radiatin expsure criteria in sme defined situatins assciated with the emergency. These exceed the ccupatinal expsure limits that apply during ther situatins, including the recvery phase. The individuals wh are Emergency Wrkers are determined by the individual site and may include bth n-site persnnel, such as reactr perating persnnel r radiatin mnitring persnnel, and ff-site persnnel such as the first respnders t a request fr assistance, nrmally fire fighters, emergency medical supprt and individuals with similar emergency respnse skills. Emergency wrkers wh undertake actins in which the dse received might exceed the single year dse limit fr ccupatinal expsure shuld d s vluntarily, shuld have been clearly and cmprehensively infrmed in advance f the assciated health risk, and shuld be trained, t the extent feasible, in the actins that may be required [12]. These prcedures establish the Radilgical Prtectin Manager as the Emergency Respnse Team psitin respnsible t ensure the apprpriate briefing ccurs t prvide infrmed vluntary cnsent. Appendix 2 prvides a sample briefing Envirnmental Mnitring Pririties Table B.2 in Part 1 Threat Categry II facilities have mre area t mnitr fr the radilgical cnsequences f an emergency than a Threat Categry III facility. Table B.2 in Part 1 is nly fr the Threat Categry II site and is an aid t the Radilgical Prtectin Manager wh is respnsible t quickly establish an envirnmental mnitring plan. Part 2 f this publicatin des nt have an envirnmental mnitring pririty table since all envirnmental mnitring will be perfrmed n the site. The pririties in this table are t mnitr fr radilgical threats n-site first, then extend that mnitring t ff-site areas. The basis fr that pririty is that n-site persnnel are the first t be affected by the emergency cnditin and any release wuld be mre easily identified by n-site mnitring where the release wuld be less diluted and dispersed. The mnitring results are then evaluated t determine if the apprpriate prtective actins have been implemented. Further, mnitring fr cnditins warranting urgent prtective actins takes pririty ver mnitring fr lng term prtective actins. 13