Regulatory Guide 2.6: Difference between revisions

From kanterella
Jump to navigation Jump to search
(StriderTol Bot change)
(StriderTol Bot change)
 
Line 1: Line 1:
{{Adams
{{Adams
| number = ML12184A008
| number = ML17263A472
| issue date = 01/31/1979
| issue date = 09/30/2017
| title = Emergency Planning for Research Reactors.
| title = Emergency Planning for Research and Test Reactors and Other Non-Power Production and Utilization Facilities.
| author name =  
| author name = Lynch S, Wertz G
| author affiliation = NRC/RES
| author affiliation = NRC/NRR/DPR/PRLB
| addressee name =  
| addressee name =  
| addressee affiliation =  
| addressee affiliation =  
| docket =  
| docket =  
| license number =  
| license number =  
| contact person =  
| contact person = Gardocki S
| document report number = RG-2.006
| case reference number = DG-2004
| document report number = RG-2.006, Rev. 2
| package number = ML17136A018
| document type = Regulatory Guide
| document type = Regulatory Guide
| page count = 10
| page count = 9
}}
}}
{{#Wiki_filter:U.S. NUCLEAR REGULATORY COMMISSION                                                                                   January    1979 REGULATORY GUIDE
{{#Wiki_filter:U.S. NUCLEAR REGULATORY COMMISSION                                             September 2017 OFFICE OF NUCLEAR REGULATORY RESEARCH                                                        Revision 2 REGULATORY GUIDE                                                                     Technical Leads:
                            OFFICE OF STANDARDS DEVELOPMENT
                                                                                                                        S. Lynch G. Wertz REGULATORY GUIDE 2.6 (Draft was issued as DG-2004 dated February 2017)
                                                                  REGULATORY GUIDE 2.6 EMERGENCY PLANNING FOR RESEARCH REACTORS
        EMERGENCY PLANNING FOR RESEARCH AND TEST
  REACTORS AND OTHER NON-POWER PRODUCTION AND
                                        UTILIZATION FACILITIES


==A. INTRODUCTION==
==A. INTRODUCTION==
velop a completely detailed plan encompassing every conceivable type of emergency situation, Section 50.34, "Contents of Applications;                                        advance planning, including the pr aration of Technical Information," of 10 CFR Part 50,                                             procedures to implement the pý- ing objec-
Purpose This regulatory guide (RG) provides licensees and applicants with a method that the staff of the U.S. Nuclear Regulatory Commission (NRC) considers acceptable for use in complying with the regulations on the content of emergency plans for research and test reactors and other non-power production and utilization facilities licensed under Title 10 of the Code of Federal Regulations (10 CFR),
"Domestic Licensing of Production and Utiliza-                                        tives and provisions for ensurin"                              availabil- tion Facilities," requires that each application                                      ity of necessary equipment.. suplA, and for a license to operate a facility include in a                                      services, can create a hio .'or*4. of p pared- Final Safety Analysis Report (FSAR), along                                            ness and ensure an or d                          ,          timely deci- with other information, the applicant's plans                                          sionmaking process a                      ei..          lS.
Part 50, Domestic Licensing of Production and Utilization Facilities (10 CFR Part 50) (Ref. 1).
Applicability This RG applies to all applicants and holders of licenses for research and test reactors and other non-power production and utilization facilities under 10 CFR 50.21, Class 104 Licenses; for medical therapy and research and development facilities, and 10 CFR 50.22, Class 103 Licenses; for commercial and industrial facilities.


for coping with emergencies, including the items specified in Appendix E,                                 "Emergency                   In the judgment                  t ?NRC1        taff, the poten- Plans for Production and Utilization Facilities,"                                    tial radiologic                ha      s          the public asso- to 10 CFR Part 50.                                                                    ciated with                        r            f research reactors are considerab]                      i th n those involved with Appendix E refers to a document entitled                                          nuclear                         
Applicable Regulations
* Moreover, because there
      *  10 CFR 50.34(a)(10) requires that each application for a construction permit include a discussion of the facilitys preliminary plans for coping with emergencies as part of a preliminary safety analysis report. The items which shall be included in the preliminary plan are set forth in Appendix E, Emergency Planning and Preparedness for Production and Utilization Facilities, to
"Guide to the Preparation of Emergency Plans                                          are m. y                          kinds of research reactors, for Production and Utilization Facilities,"1                                          the            nti      o emergency situations arising which was developed to help applicants estab-                                        and                ns        ences thereof vary from facility lish adequate plans for coping with emergen-                                                  fa            These differences and variations cies. This regulatory guide provides additional                                                      ct      to be reflected realistically in the guidance on emergency planning for research                                                -          y plans and procedures developed for reactors and describes a method acceptable                                      *tig    a        esearch reactor facility.
          10 CFR Part 50.


the NRC staff for complying with the om sion's regulations with regard to the content                                              General guidance for meeting the regulations emergency plans for these facilities.                                                        Appendix E to 10 CFR Part 50 is provided in ANSI standard ANSI/ANS 15.16-1978, "Emer-
*  10 CFR 50.34(b)(6)(v) requires that each application for a Part 50 license to operate a facility include a final safety analysis report that contains, along with other information, the applicants plans for coping with emergencies, including the items specified in Appendix E to 10 CFR
          Part 50.


==B. DISCUSSION==
Written suggestions regarding this RG or development of new guides may be submitted through the NRCs public Web site under the Regulatory Guides document collection of the NRC Library at http://www.nrc.gov/reading-rm/doc-collections/reg- guides/contactus.html.
gency Planning for Research Reactors. "2 This regulatory            guide          provides          more      detailed The Commission's interest in, emergency                                h-       guidance for emergency planning for research ning is focused primarily on situations that may                                      reactors.


cause or may threaten                                ause radiological hazards affecting the                                  and safety of                       In the development or modification of emer- workers or the public o                                    in damage to              gency plans for a specific research reactor, property. Emergenc                        1        ho        be directed            the applicant should be guided by the follow- toward mitigatin                        .     n        ences of emer-                ing:
Electronic copies of this RG, previous versions of this guide, and other recently issued guides are available through the NRCs public Web site under the Regulatory Guides document collection of the NRC Library at http://www.nrc.gov/reading-rm/doc- collections/. The RG is also available through the NRCs Agencywide Documents Access and Management System (ADAMS) at http://www.nrc.gov/reading-rm/adams.html, under ADAMS Accession No. ML17137A096. The regulatory analysis may be found in ADAMS under Accession No. ML16035A477 and the staff responses to the public comments on DG-2004 may be found under ADAMS Accession No. ML17137A099.
gencies and sho                      pro        e easonable assur- ance that ap              p,       e m        ures can and will be                        1. The plans should be an expression of the taken to p                c , et              d safety and prevent                  overall concept of operation that describes how damage to                      ty            e event of an emer-                    the elements of advance planning that are gency. Alth                      it is not practicable to de-                         identified in Appendix E to 10 CFR Part 50
    'Copies may be obtained by written request to the U.S.


2 Nuclear Regulatory Commission, Washington, D.C.                        20555.              Copies may be obtained from the American Nuclear Society, Attention: Director, Office of Nuclear Reactor Regulation.                            555 North Kensington Avenue, La Grange Park, Illinois 60525.
*  10 CFR 50.54(q) requires Part 50 licensees to follow and maintain the effectiveness of emergency plans that meet the requirements of Appendix E to 10 CFR Part 50.


USNRC REGULATORY GUIDES                                          Comments should be sent to the Secretary of the Commision. U.S. Nuclea Regulatory Commision, Washington, D.C. 20655. Attention: Docketing and Regulatory Guides are issed to describe and make available to the public              Service Branch.
*  10 CFR Part 50, Appendix E, Emergency Planning and Preparedness for Production and Utilization Facilities identifies the minimum requirements for the emergency plans to be included with the safety analysis report submitted as part of the construction permit or license application. It also indicates that because operation of facilities other than power reactors involve distinct considerations, the size of the emergency preparedness zone (EPZ) and degree of compliance with requirements in Appendix E, sections I through V, as necessary, will be determined on a case-by-case basis using this regulatory guide for research and test reactor, and other non-power production and utilization facility emergency response plans.


methods acceptable to the NRC staff of implementing specific parts of the Commission's regulations, to derineate techniques used by the staff in evalu-         The guides we issued in the following ton broad divisions:
Related Guidance
ating specific problemn or postulated acciident., or to provide guidance to                                                      6. Products applicants. Regulatory Guides are not substitutm for regulations, and com-           
  *  NUREG-1537, Parts 1 and 2, Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors (Ref. 2), provides guidance for applicants preparing license applications for non-power reactor licenses and the NRC staff in its review of these license applications.


===1. Power Reactors===
*  Final Interim Staff Guidance (ISG) Augmenting NUREG-1537, Parts 1 and 2, Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors (Ref. 3)
                                                                                      2 Research and Test Reactors               7. Transportation piasce with them. not required. Methods and solutions daffere from those              3. Fuels and Materials Facilities          8. Occupational Health st out in the guides will be acceptable if they provide a basis for the findings      4. Environmental and Siting                9. Antitrust and Financial Review requisite to the issuance or continuance of a permit or license by the                5. Materials and Plant Protection          10. General Commnion.
      provides guidance for applicants preparing license applications for radioisotope production facilities and aqueous homogeneous reactors and the NRC staff in its review of these license applications.


Comments and suggestions for improvements In these guides re encouraged              Requests for single copies of Iued guides (which may be reproduced) or for
*  NUREG-0849, Standard Review Plan for the Review and Evaluation of Emergency Plans for Research and Test Reactors, provides guidance for the NRC staff in its review of emergency plans for research and test reactors (Ref. 4).
.at an time, and guides will be revised, a appropriate, to acoomnodate com-            plmemenwt on an autoratic distribution list for single copies of future guides ments and to reflect new information or experience. However, comments on              in specific divisions should be made i writing to the U.S. Nuclear Regula    y this guide, if received within about two months after its issuance, will be          Commission, Washington. D.C. 206,            Attention: Director. Diviskii  of particu "layuseful In evaluating the need for an ealy remvion.                        Technical Information end Document Control.
  *  Regulatory Information Summary (RIS) 2005-02, Revision 1, Clarifying the Process for Making Emergency Plan Changes (Ref. 5), provides specific information with regard to processing changes to emergency plans. The RIS includes information to determine whether a decrease in effectiveness resulted from the proposed emergency plan change.


have been considered and the provisions that          scribe this planning basis and the correspond- have been made to cope with emergency situa-          ing arrangements and agreements among the tions. Guidance on the scope and content of           licensee and the local, State, or Federal agen- such plans is provided in Annex A, "Scope and          cies expected to respond.
Applicable Information Notices
  *  Information Notice (IN) 92-79, Non-Power Reactor Emergency Event Response (Ref. 6),
      describes an event that required interface with the public and highlights the need for licensees to quickly apprise the NRC of the circumstances of an emergency classification.


Content of Emergency Plans for Research Reactors," to this guide.                                2. The scope and content of emergency plans for research reactors authorized to operate at
*  IN 97-34, Deficiencies in Licensee Submittals Regarding Terminology for Radiological Emergency Action Levels in Accordance with the New Part 20 (Ref. 7), updates Appendix I of NUREG-0849 to reflect revised 10 CFR Part 20 regulations in the radiological emergency action levels (EALs).
  2. Features and candidate subjects that            power levels of approximately 100 kW or more should be considered in the preparation of spe-       and reactor facilities presenting comparable cific procedures for implementing the emergen-         risks should be substantially equivalent to cy plans are described in Annex B, "Imple-             those described in Annex A to this guide. The menting Procedures for Emergency Plans," to            scope and content of emergency plans for this guide.                                            research reactors authorized to operate at power levels less than 100 kW should include at
  *  IN 2009-31, Non-Power Reactor Licensee Notifications to the NRC during an Incident (Ref. 8),
  3. Details that can reasonably be expected to       least those elements of Annex A to this guide change from time to time, e.g., names and              except those that are marked with an asterisk.
      describes lessons learned from an emergency declaration at a non-power reactor regarding the appropriate NRC office to contact and the types of information that the NRC may request from licensees at that time.


telephone numbers, specific items of equipment and supplies, inventory lists, and step-by-              3. To ensure that a state of preparedness is step procedures or checklists that may be al-          maintained, provisions should be made (1) for tered as a result of experience or test                a biennial review and updating of the emergen- exercises, should not be incorporated into the        cy plans and implementing procedures to re- plans. Implementing procedures that are not            flect changes onsite or in the environs and (2)
RG 2.6, Rev. 2, Page 2
expected to change with time may, but need            for specified periodic testing, exercises, and not, be incorporated into the plans described          drills.


in the SAR.
Purpose of Regulatory Guides The NRC issues RGs to describe to the public methods that the staff considers acceptable for use in implementing specific parts of the agencys regulations, to explain techniques that the staff uses in evaluating specific problems or postulated events, and to provide guidance to applicants. RGs are not substitutes for regulations, and compliance with them is not required. Methods and solutions that differ from those set forth in RGs will be deemed acceptable if they provide a basis for the findings required for the issuance or continuance of a permit or license by the Commission.


==D. IMPLEMENTATION==
Paperwork Reduction Act This RG provides guidance for implementing mandatory information collections covered by 10
CFR Parts 50 and 52 that are subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et. seq.).
These information collections were approved by the Office of Management and Budget (OMB), under control numbers 3150-0011 and 3150-0151 respectively. Send comments regarding this information collection to the Information Services Branch, U.S. Nuclear Regulatory Commission, Washington, DC
20555-0001, or by e-mail to Infocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0011 and 3150-0151) Office of Management and Budget, Washington, DC 20503.


==C. REGULATORY POSITION==
Public Protection Notification The NRC may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a currently valid OMB control number.
The purpose of this section is to provide
    1. Each applicant's emergency plans should        information to applicants and licensees regard- include provisions for coping with emergencies        ing the NRC staff's plans for using this regu- within and beyond the immediate boundary of            latory guide.


the facility. Responsibility for planning and implementing all emergency measures within the          Except in those cases in which the applicant facility boundaries rests with the licensee. In        or licensee proposes an acceptable alternative this context, the licensed facility boundaries        method for complying with specified portions of should be clearly defined. Planning and imple-        the Commission's regulations, the method de- mentation of measures to cope with reactor-            scribed herein will be used in evaluating emer- related emergencies beyond the facility bound-        gency plans submitted with new and renewal ary should be commensurate with and based            applications for research reactor operating upon the potential consequences of credible ac-      licenses until this guide is revised as a result cnidents or incidents and specified emergency        of suggestions from the public or additional action criteria. The emergency plan should de-        staff review.
RG 2.6, Rev. 2, Page 3


2.6-2
==B. DISCUSSION==
Reason for Revision This revision of the guide (Revision 2) addresses new issues identified since the guide was last revised in March 1983 (Revision 1). This revision endorses the latest version of the consensus standard, American National Standards Institute (ANSI)/American Nuclear Society (ANS) standard ANSI/ANS-
15.16-2015, Emergency Planning for Research Reactors (Ref. 9) (ANSI/ANS-15.16 or the standard).
The scope of RG 2.6 was expanded to address non-power 10 CFR Part 50 facilities other than research and test reactors. Other changes to RG 2.6 include editorial changes, and the current program guidance for RGs.


A
Revising this RG to endorse the use of, in whole or in part, a consensus standard is consistent with the NRC policy of evaluating the latest versions of national consensus standards to determine their suitability for endorsement by RGs. This approach also complies with the NRCs Management Directive (MD) 6.5, NRC Participation in the Development and Use of Consensus Standards, (Ref. 10) and is in accordance with Public Law 104-113, National Technology Transfer and Advancement Act of 1995 (Ref.
              SCOPE AND CONTENT OF EMERGENCY          PLANS FOR RESEARCH        REACTORS
                1. DEFINITIONS                                 


===2. EMERGENCY CONDITIONS===
11).
  Definitions of any terms that are unique to         2.1 Classification System the facility under consideration or are given connotations that differ from normally accepted            An emergency plan should characterize sev- usage should be provided. Listed below are              eral classes of emergency situations. The sys- some terms used in this guide along with the           tem of classification used should consist of definitions that should be applied to these            mutually exclusive groupings, and it should terms when they are used in emergency plans.           cover the entire spectrum of credible radiologi- cal emergency situation
Background The Commissions interest in emergency planning is focused primarily on situations that may cause or threaten to cause radiological hazards that could affect public health and safety. Emergency plans should be directed toward mitigating the consequences of emergencies and should provide reasonable assurance that appropriate measures can and will be taken to protect public health and safety in the event of an emergency. Although developing a completely detailed plan encompassing every conceivable type of emergency situation is not practical, advanced planning and provisions for ensuring the availability of necessary equipment, supplies, and services can create a high order of preparedness and ensure an orderly and timely decision making process at the time of an emergency. The plans should express the overall concept of operation that describes how the elements of advanced planning have been considered and the provisions that have been made to cope with emergency situations.


====s. Each class defined====
From its review of safety analysis reports for research and test reactors and other non-power production and utilization facilities, and based on the radionuclide inventory and postulated radioactive releases at these facilities, the NRC staff determined that the potential radiological hazards to the public associated with the operation of these facilities are less than those associated with the operation of commercial nuclear power plants. However, the types and potential consequences of emergencies vary from facility to facility. As such, the NRC staff expects that the emergency plans and procedures developed by or for each facility should realistically reflect the hazards and consequences of each facility.
1.1 Assessment actions-those actions taken dur-        should be associated with a particular set of ing or after an accident to obtain and process          immediate actions that are to be taken to cope information that is necessary to make decisions        with the situation.


to implement specific emergency measures.
The ANSI and the ANS issued ANSI/ANS-15.16, which is generally consistent with current regulatory requirements. Originally developed in 1982, and updated in 2008 and 2015, the current standard provides specific acceptance criteria for research and test reactors and other non-power production and utilization facilities to comply with the applicable requirements set forth in 10 CFR 50.34, Contents of Applications; Technical Information, 10 CFR 50.54, Conditions of Licenses, and Appendix E to 10 CFR Part 50. These criteria provide a basis for licensees and applicants to develop acceptable emergency response plans and improve emergency preparedness at their facilities.


Specific implementing procedures should be
RG 2.6, Rev. 2, Page 4
1.2 Corrective actions-those measures taken to          prepared for each identified class of emergency ameliorate or terminate an emergency situation          (see Annex B).
at or near the source of the problem in order to prevent an uncontrolled release of radio-              An acceptable classification scheme is de- active material or to reduce the magnitude of a        scribed in qualitative terms in the following release.                                                subsections.


1.3 Protective actions-those measures taken in            2.1. 1 Personnel Emergency anticipation of or after an uncontrolled release of radioactive material has occurred for the               This class involves accidents or occurrences purpose of preventing or minimizing radiologi-         onsite in which emergency treatment of one or cal exposures to persons that would be likely          more individuals is required. It includes those to occur if the actions were not taken.                 situations that have no potential for escalation to more severe emergency condition
The NRC staff issued NUREG-0849 in 1983 as a standard review plan for evaluating emergency plans submitted by research and test reactor licensees.1 Consistent with ANSI/ANS-15.16, NUREG-0849 provides areas of review, planning standards, and evaluation items for NRC staff to evaluate a licensees or applicants compliance with the applicable emergency planning requirements described above. Both NUREG-0849 and ANSI/ANS-15.16 were incorporated by reference into NUREG-1537, Section 12.7, Emergency Planning, and the ISG augmenting NUREG-1537. This guidance forms the basis for all construction permit and operating license application reviews of research and test reactors and other non- power production and utilization facilities. Relevant non-reactor emergency planning guidance contained in the ISG augmenting NUREG-1537 is based on NUREG-1520, Revision 1, Standard Review Plan for the Review of a License Application for a Fuel Cycle Facility, published in May 2010 (Ref. 12).2 Harmonization with International Standards The International Atomic Energy Agency (IAEA) has established a series of safety standards constituting a high level of safety for protecting people and the environment. Safety standards present international good practices and increasingly reflect best practices to help users striving to achieve high levels of safety. Relative to this RG, IAEA Safety Requirements NS-R-4, Safety of Research Reactors (Ref. 14), addresses emergency planning in Sections 7.72 through 7.78. While the NRC has an interest in facilitating the harmonization of standards used domestically and internationally, the agency does not specifically endorse or approve the use of NS-R-4 and is only acknowledging that it may be a useful reference for general information. The NRC could consider the use of the international standard in a licensing action following adequate justification by a licensee or applicant and technical review by the NRC.


====s. There====
Documents Discussed in Staff Regulatory Guidance This RG endorses, in part, the use of one or more codes or standards developed by external organizations, and other third party guidance documents. These codes, standards and third party guidance documents may contain references to other codes, standards or third party guidance documents (secondary references). If a secondary reference has itself been incorporated by reference into NRC
1.4 Population at risk-those persons for whom          may be no effect on the reactor, and immediate protective actions are being or would be taken.        operator action to alter reactor status is not necessarily required. A Personnel Emergency would not be expected to activate an entire emergency organization but may require special
regulations as a requirement, then licensees and applicants must comply with that standard as set forth in the regulation. If the secondary reference has been endorsed in an RG as an acceptable approach for meeting an NRC requirement, then the standard constitutes a method acceptable to the NRC staff for meeting that regulatory requirement as described in the specific RG. If the secondary reference has neither been incorporated by reference into NRC regulations nor endorsed in an RG, then the secondary reference is neither a legally-binding requirement nor a generic NRC approved acceptable approach for meeting an NRC requirement. However, licensees and applicants may consider and use the information in the secondary reference, if appropriately justified, consistent with current regulatory practice, and consistent with applicable NRC requirements.
1.5 Recovery actions-those actions taken after          local services such as ambulance and medical.


the emergency to restore the facility to a safe        Emergencies in this class may be expected to status.                                                occur during the life of a research reactor.
1        Appendix I of NUREG-0849 was updated in April 1997 to reflect revisions to 10 CFR Part 20 requirements in radiological EALs. The NRC staff issued IN 97-34 (Ref. 7) in June 1997 to inform licensees of this revision to the NUREG.


1.6 Protective action guides (PAG)-projected              Implementing procedures for handling this
2         Since the publication of the ISG augmenting NUREG-1537, the NRC published Revision 2 to NUREG-1520 in June
-Rdiological dose or dose commitment values to         class of emergency may also be incorporated individuals in the general population that war-         into the reactor's radiation protection proce- rant protective action following a release of ra-      dures and general safety procedures.
          2015 (Ref. 13). Licensees and applicants should refer to the most recent revisions of NRC guidance documents when developing license applications and implementing NRC requirements.


dioactive material. Protective actions would be warranted provided the reduction in individual            Included in this class are injuries that may dose expected to be achieved by carrying out            be complicated by contamination problems or the protective action is not offset by excessive        radiation exposures to onsite personnel.
RG 2.6, Rev. 2, Page 5


risks to individual safety in taking the protec- tive action.     The projected dose does not              The recognition of this class of emergency is include the dose that has unavoidably occurred          primarily a judgment matter for supervisory prior to the assessment.                               personnel. Its importance as part of the classi- fication scheme rests to some extent on its
C. STAFF REGULATORY GUIDANCE
                                                        "negative" information content, viz., that the
        The NRC staff endorses the guidance in ANSI/ANS-15.16-2015 for use as a means for research and test reactor and other non-power production and utilization facility licensees and applicants to comply with the requirements in 10 CFR 50.34(a)(10), 10 CFR 50.34(b)(6)(v), 10 CFR 50.54(q), and 10 CFR
1.7 Emergency action levels-radiological    dose       incident giving rise to the emergency is rates; specific contamination levels of airborne,      restricted in its scope of involvement.
Part 50, Appendix E. The following clarifications are added:
1.       Radiation Dose Levels for Emergency Action Levels The radiation dose levels of the emergency action levels established in ANSI/ANS-15.16 for the various emergency classes differ from those specified for power reactors. However, in the judgment of the NRC staff, the radiation dose levels specified in Table I of the standard are adequate for the credible accidents associated with the operation of research and test reactors and other non-power production and utilization facilities and the specified action levels provide reasonable assurance that protective measures associated with the action levels specified in Table I can and will be taken, provided that the licensee also gives appropriate emphasis to developing emergency action levels that relate directly to facility parameters (e.g., pool water levels and area radiation monitors).
2.       NRC Notification The licensee should notify the NRC headquarters operations center of events classified under Table I of the standard.


waterborne, or surface-deposited concentra- tions of radioactive materials; or specific in-            2.1.2 Emergency Alert strument readings that may be used as thresh- olds for initiating specific emergency measures,          This class involves specific situations that e.g., designating a particular class of emer-          can be recognized as creating a hazard poten- gency, initiating a notification procedure, or          tial that was previously nonexistent or latent.
3.      Implementing Procedures The licensee should establish and maintain procedures for implementing the requirements of the emergency plan. The implementing procedures should be readily accessible for use by the staff of the implementing organization (e.g., operators, facility management, etc.). The emergency implementing procedures should be maintained and made available at the facility for inspection and review at any time by an NRC representative.


initiating a particular protective action.             The situation has not yet caused damage to the
4.       Procedure Review and Revision The procedural system that the licensee uses for the review and approval of emergency implementing procedures should contain instructions governing the writing, revising, and updating of implementing procedures. The instructions should specify the methods that the licensee will use to ensure that procedures, revisions, and changes are reviewed for adequacy, approved for use, and distributed to user organizations and individuals responsible for implementing the procedures.
                                                  2.6-3


reactor or harm to personnel but may warrant                          do not indicate the possibility of a more serious an immediate shutdown of the reactor if it is in                      emergency.
5.      Plan Details Subject to Routine Change The plan should not incorporate details that may routinely change (e.g., names and telephone numbers, specific items of equipment and supplies, inventory lists, and step-by-step procedures or checklists that may be altered as a result of experience or test exercises). These details are useful, but are better maintained in the facilitys implementing emergency procedures.


an operating mode. This is a situation in which time is available to take precautionary and con-                          2.1.4 Facility Emergency*
RG 2.6, Rev. 2, Page 6
structive steps to prevent an accident and to mitigate the consequences should it occur.                                Because of measures taken to guard against Emergency Alert situations may be brought on                          their occurrence, emergency situations more by either manmade or natural phenomena and                            severe than a Reactor Emergency are not can be expected to occur during the Life of a                        expected to occur during the life of a research research reactor.                                                     reactor. Nevertheless, it is considered neces- sary and prudent that facilities make provi- Emergency Alert conditions imply a rapid                          sions for a class that involves an uncontrolled transition to a state of readiness by the reactor                      release of radioactive materials into the air, personnel and possibly by some offsite emer-                          water, or ground to an extent that the initial gency support organizations,                  the possible            assessment indicates protective actions offsite cessation of certain routine functions or activ-                      should be considered. 4 I Alerting principal ities that are not immediately essential, and                          offsite emergency organizations is a recom- possible precautionary actions that a specific                        mended associated measure. Assessment actions situation may require. Examples of situations'                        should include provisions for monitoring the that should be placed in this class are threats                        environment.


to or breaches of security measures such as bomb threats or civil disturbance; 3 severe                                Emergency action levels for declaring a Facil- natural phenomena in the reactor environment                          ity Emergency should be defined in terms of such as a flood, hurricane, or tornado; emer-                          instrument readings or alarms. To avoid un- gency situations such as nearby fires; or                              necessary response to false alarms, the activa- release of a toxic or noxious gas in or near the                      tion criteria for monitors should be defined so reactor area.                                                          as to require a rapid method of corroborating an actual alarm conditio
==D. IMPLEMENTATION==
 
The purpose of this section is to provide information to applicants and licensees regarding the NRCs plans for using this RG. The regulatory position held in this guidance demonstrates the method that the NRC staff finds acceptable for an applicant or licensee to meet the requirements of the underlying NRC regulations. Methods or solutions that differ from those described in this RG may be deemed acceptable if they provide sufficient basis and information for the NRC staff to verify that the proposed alternative demonstrates compliance with the appropriate NRC regulations. Current licensees may continue to use guidance the NRC found acceptable for complying with the identified regulations as long as their current licensing basis remains unchanged.
====n. The bases and====
    2.1.3 Reactor Emergency                                          criteria used to specify these emergency action levels should be described and their relation- This class includes physical occurrences                          ship to protective action guides explained.
 
within the facility requiring emergency organi- zation response. The initial assessment leading                            An example of a situation that might fall into to this class should indicate that it is unlikely                      this class is an act, circumstance, or event, that an offsite hazard                will be created.                e.g., a serious failure of an experiment, that However, substantial modification of reactor                          results in a major disruption of the core with operating status is a highly probable corrective                      subsequent fission product release.
 
action to ensue if the automatic protective sys- tems have not already produced such action.                                    3.  ORGANIZATIONAL CONTROL OF
Although this class is associated with a judg-                                                EMERGENCIES
ment that the emergency situation can be cor-                              Starting with the normal operating organiza- rected and controlled by the onsite staff, noti-                      tion as a base, the plan should describe the fication through normal reporting mechanisms                          emergency organization that would be activated of an appropriate offsite agency to alert it as                        at the facility and any augmentation from off- to the nature and possible extent of the inci- site groups as necessary. Authorities and re- dent should be a measure associated with this sponsibilities of key individuals and groups class. Protective evacuations or isolations of                        should be delineated. Adequate communication certain areas of the facility may be necessary.                        links established for notifying, alerting, and mobilizing all emergency personnel should be Situations that might fall into this class are                    identified.
 
those accidents that are predicted to have in- sufficient radiological consequences offsite to                        3._1 Facility Emergency Organization warrant taking protective measures. Fires and minor explosions in the facility, e.g., the                                The mobilization billets of staff personnel for failure of an experiment under pressure,                              emergency situations should be described. In- should fall into this class.                                          clude the position title of that person who is designated to take charge of emergency control Activation levels for declaring Reactor Emer-                    measures and the specific line of succession for gencies should be based on the recognition of                          this authority.
 
an immediate need to implement in-house emer- gency measures to protect or provide aid to                                 Item need not be included in emergency plans for research affected persons or to mitigate the conse-                            reactors authorized to operate at power levels of less than quences of damage to equipment, coupled with                          100 kW (see Regulatory Position C.2).
                                                                        4 a positive observation that radiological monitors                          "Background Material for the Development of Radiation Pro- tection Standards," Federal Radiation Council, Report No. 5,
  3                                                                  July 1964, and Report No. 7, May 1965.
 
Details of measures to cope with security incidents should be described in the facility physical security plan required            sManual of Protective Action Guides and Protective Actions pursuant to 10 CFR 50.34(c) and should be withheld from pub-          for Nuclear Incidents (Chapter 2), U.S. Environmental Protec- lic disclosure pursuant to 10 CFR 2.790(d).                          tion Agency, EPA-520/1-75-0O1, September 1975.
 
2.6-4
 
3.2 Augmentation of Facility Emergency Organi-                      cy situation. The details of assessment func- zation                                                        tions should be incorporated in explicit imple- menting procedures. The plan should include a The extension of the organizational capability                    description of the methodologies and techniques for    handling    emergencies      to be provided by              to be used to an extent sufficient to demon- ambulance, medical, hospital, and firefighting                        strate, in a timely manner, that there is organizations should be described. The ar-                            reasonable assurance (1) that the magnitudes rangements          and any written agreements                      of releases of radioactive materials can be reached with such organizations should be                            determined, (2)      that the magnitude of any included.                                                            resulting radioactive contamination can be de- termined,      (3) that projected exposures to
3.3 Coordination with Participating Government                      persons within or beyond the facility bound- Agencies                                                      aries can be estimated, and (4) that emergency action levels specified can be determined.
 
The principal State agency (designated State authority) and other governmental agencies                          4.3 Corrective Actions (local, county, State, and Federal) having action responsibilities for radiological emergen-                        In some emergency situations, actions can be cies in the area in which the reactor is located                    taken to correct or mitigate the situation at or should be identified. A description should be                      near the source of the problem to prevent an given of the authority and responsibility of                        uncontrolled release of radioactive materials or each such agency for emergency preparedness                        to reduce the magnitude of a release. Correc- planning and for emergency response, particu-                      tive actions should be considered as a supple- larly in relation to those of the licensee and to                  ment to design features and as both a backup those of other agencies. Copies of any written                      and an extension of automatically initiated ac- agreements        with such agencies should be                      tions. Proficiency in corrective actions such as
            6 included.                                                          firefighting, repair, and damage control should constitute a major objective of the training
              4.    EMERGENCY        RESPONSE                        effort and onsite drill program.
 
Specific emergency response measures should                      4.4 Protective Actions be identified for each emergency class and related to action levels or criteria that specify                      This section should describe the nature of when the measures are to be implemented.                            protective actions for which the plan provides, the criteria (Protective Action Guides) for im- The planning represented by this section                        plementing these protective actions, the area should lead to more detailed emergency plan                          involved, and the means of notifying or warn- implementing procedures and assignments for                          ing the persons at risk.
 
executing tasks by appropriate members of the emergency organization. Emergency measures                              4.4.1 Protective Cover, Evacuation,    Person- begin with the activation of an emergency class                                  nel Accountability*
and its associated emergency organization. The additional measures may be organized, where                            The emergency plan should provide for time- applicable to each class, into assessment ac-                        ly evacuation of persons in order to prevent or tions, corrective actions, protective actions,                      minimize radiological exposure. The following and aid to affected persons.                                        items should be included:
4.1 Activation of Emergency Organization                                1. Facility The communication steps taken to alert or                            a. Action criteria, activate emergency personnel under each class of emergency, including, in particular, action                            b. The means to provide rapid warning or levels for notification of off site agencies, should be described and should ensure that                          advice to persons involved, i.e. :
they can be taken rapidly. The existence, but                                (1) Employees or    students not having not the details, of a message authentication                        emergency assignments, scheme should be noted for such agencies.
 
(2) Working and nonworking visitors.
 
4.2 Assessment Actions
                                                                        2. Offsite areas Effective coordination and direction of all elements of the emergency organization require                            a. Actions planned to immediately protect continuing assessment throughout an emergen-                        persons beyond the boundaries of the facility and criteria for their implementation,
  6 As an alternative method of providing the information re- quested in these subsections, the applicant may choose to sub-            b. The means to warn or advise the per- mit copies of such agencies' radiological emergency response plans as evidence of acceptable, coordination.                      sons involved.
 
2.6-5
 
4.4.2 Use of Reactor Facility Protective Equip-          4.5.4 Medical Treatment ment and Supplies*
                                                            Arrangements made for local hospital and Additional protective actions that should be          medical services and the capability for the considered in emergency planning include                evaluation of radiation exposure and uptake measures for minimizing the effects of radiolog-        should be described.
 
ical exposures or contamination problems by the facility distribution of special equipment or          For both hospital and medical service, the supplies to reactor personnel. Measures that             plan should incorporate assurance not only that should be considered for persons within the             the required services are available, but also reactor facility include individual respiratory          that persons providing them are prepared and protection and the use of protective clothing.          qualified to handle radiological emergencies.
 
Written agreements with respect to arrange-
  4.4.3 Contamination Control Measures                  ments made should be included.
 
Provisions should be made for preventing or minimizing exposure to radioactive materials              5.    EMERGENCY    FACILITIES AND EQUIPMENT
deposited on floors, the ground, or other sur- faces. Such measures should include:                        The emergency plan should identify, de- scribe briefly, and give the locations and gen-
    1. Isolation or quarantine  and area access        eral type of items to be used or maintained by
-ontrol,                                                the licensee.
 
2. Criteria for permitting return to normal use.                                                    5. 1 Emergency Control Centers*
                                                            This section should identify the principal lo-
4.5 Aid to Affected Personnel                            cation from which effective emergency control direction is given.
 
The emergency plan should describe meas- ures that will be used by the licensee to pro- vide necessary assistance to persons injured or          5.2 Communications Systems exposed to radioactivity. The following matters should be included:                                          The plan should include descriptions of facility communications systems that would be required to perform vital functions in transmit-
    4.5.1 Emergency Personnel Exposure                  ting and receiving information throughout the course of an emergency.
 
This should specify exposure guidelines for entry or reentry to areas in order to (1)
remove injured persons and (2) undertake                  5.3 Assessment Facilities corrective actions. Exposure guidelines should also be specified for emergency personnel who              The plan should identify monitoring systems will be providing first 'aid, decontamination,            and laboratory facilities that are to be used to ambulance, or medical treatment services to              determine the need to initiate emergency meas- injured persons, and a description of how                ures, as well as those to be used for continu- these guidelines will be implemented. Methods            ing assessment, e.g.:
for permitting volunteers to receive radiation exposures in the course of carrying out life-                1. Portable and fixed radiological monitors, saving activities should ensure expeditious                  2. Sampling equipment, decisionmaking and a reasonable balance of                  3. Instrumentation for specific radionuclide relative risks.                                          identification and analysis,
                                                            4. Nonradiological monitors or indicators that
    4.5.2 Decontamination and First Aid                  may provide pertinent system or status infor- mation, Capabilities for decontaminating personnel                5. Fire detection devices.
 
for their own protection and to prevent or minimize further spread of contamination should          5.4 First Aid and Medical Facilities be included, along with a brief description of first aid training and capabilities of appro-                A summary desbription of medical and first priate members of the emergency organization.            aid facilities should be provided.
 
4.5.3 Medical Transportation                          6.    MAINTAINING    EMERGENCY PREPAREDNESS
    Arrangements for transporting injured per- sonnel, who may also be contaminated with                    The plan should include a description of how radioactive material, to medical treatment facil-        the plan will continue to be effective througlh- ities should be specified.                              out the lifetime of the facility.
 
2.6-6
 
6. 1 Organizational Preparedness                      6.3 Maintenance and Inventory of Emergency Equipment and Supplies
  6.1.1 Training The operational readiness of all items of The plan should include a description of spe-      emergency equipment and supplies should be cialized training to be provided to emergency          ensured. The provisions for performing main- personnel.                                            tenance, surveillance testing, and inventory on emergency equipment and supplies should be
  6.1.2 Drills and Exercises                          described.
 
The plan should describe provisions for the
 
===7. RECOVERY===
conduct of periodic drills and exercises to test the adequacy of timing and content of imple- menting procedures and methods, to test emer-            General plans, including applicable criteria, gency equipment, and to ensure that emergen-          for restoring the facility to a safe status cy organization personnel are familiar with            should be described.
 
their duties. Preplanned descriptions or simu- lations of accidents or similar events should be
 
===8. APPENDIX===
used to prepare scenarios appropriate to the objectives of each drill or exercise.
 
The appendix to the plan should include the The plan should provide for emergency test          following items:
exercises, one prior to initial criticality and biennially thereafter, using scenarios appro-              1. General building layout  plans  and area priate to serious emergency situations. Each of        maps.
 
these exercises should contain provisions for coordination with offsite emergency personnel            2. Copies of agreement letters with offsite and should test, as a minimum, the communica-          emergency response supporting organizations tions links and notification procedures with            and copies of referenced interfacing emergency those offsite agencies.                                plans.
 
The plan should also provide for annual on-            3. Listings, by general category, of emer- site drills using scenarios appropriate to test        gency kits, protective equipment, and supplies firefighting, contamination control measures,          that are stored and maintained for emergency and building evacuation. These drills should be        purposes. A detailed catalog of individual items conducted onsite as action drills with each re-        should not be included in the plan.
 
quired emergency measure being executed as realistically as is reasonably possible. Provi-          4. Listings, by title, of written procedures sions should be made for critiques of all drills        that implement the plans.
 
and exercises, including timely evaluation of observer comments about the implementation                The written procedures themselves and a and corrective action.                                  detailed catalog of protective equipment and supplies should be available at the facility for
6.2 Review and Updating of the Plan and Pro-            inspection at any time by a representative of cedures                                            the Commission's Office of Inspection and Enforcement.
 
Provision should be made for a biennial review of the emergency plan and for updating              5. An analysis that sets forth the basis for and improving procedures to incorporate                the emergency plan (Planning Basis). This results of training and drills and to account for      should include descriptions of the types of changes in the facility or in the environs.            credible incident and accident situations, their Means for informing elements of the .total              expected consequences, and their conserva- emergency organization of the revisions to the          tively analyzed potential consequences. If this plan or relevant procedures should be de-              analysis, in whole or in part, has been sub- scribed. Provisions for reviewing and updating          mitted previously to NRC, a clear and specific all written agreements at these times of revi-          reference thereto is acceptable,        and the sion should be included.                                analysis need not be repeated.
 
2.6-7
 
ANNEX    B
                          IMPLEMENTING PROCEDURES FOR EMERGENCY PLANS
                  (Applicable to Research Reactors Authorized to Operate at Power Levels Approximating 100 kW or Greater or Reactor Facilities Presenting Comparable Risk)
  This annex provides guidance regarding the              purpose of the procedure        should be stated preparation and content of procedures that                separately.
 
implement the emergency plan.
 
1.4.2 Conditions and Prerequisites
  1.  CONTENT AND FORMAT OF PROCEDURES
                                                              Each procedure should specify the prerequi- This section describes desirable features that          sites and conditions that should exist before should be incorporated, where appropriate,                the specified actions or operations are per- into individual implementing procedures.                  formed. These should be in the form of action levels or protective action guides.
 
1.1 Organization and Responsibilities
                                                              1.4.3 Actions and Limitations Wherever appropriate, each procedure should specify the individual (by title) or organiza-                Procedures should present the required ac- tional element having the authority and respon-            tions in a succinct and concise manner and in sibility for performing specific critical tasks            step-by-step order and logical sequence. The covered by the procedure.                                  instructions should be sufficiently detailed for
                                                          -a--qualified individual to perform the required
1.2 Action Levels                                          actions without supervision, but they need not provide a completely detailed description of the Emergency action levels and protective action            actions, methods, or processes.
 
guides should be specified in procedures, along with the emergency actions or protective                If the user is given the latitude to exercise actions required and the individuals or organi-            judgment in implementing specific actions or zational units responsible for their implementa-            parts of the procedure, guidelines should be tion.                                                      provided in the procedure to aid the user in making decisions.
 
1.3 Actions by Support Agencies
                                                              1.4.4 Cautions and Precautions The specific actions to be performed by sup- port groups should be identified in the proce-                Important steps or precautions should be dures dealing with their activities. If the emer-          noted or highlighted within the procedure.


gency actions performed by these groups require coordination with other elements of the                1.4.5 References emergency organization, the particulars and requirements of this coordination should be                    When procedural steps require other func- specified in the controlling procedure.                     tions or jobs to be performed, the controlling procedure should contain the reference to
The guidance in this RG is not a backfit, as that term is defined in 10 CFR 50.109, Backfitting, because non-power facilities licensed under 10 CFR Part 50 are not included within the scope of entities protected by 10 CFR 50.109.
1.4 Procedure Format                                        other applicable procedures.


A rigid format for implementing procedures is              1.4.6 Signoff Sheets and Checklists not. suggested in this guide. An acceptable format should display the action steps so the                  Complex or lengthy controlling procedures user of the procedure can clearly understand                should have provisions for signoff sheets or his duties. The format of procedures that                  checklists to document the fact that required specify immediate actions to be taken has                  actions    have been taken or have been special significance because the user needs                completed. Examples include notification call brief and explicit instructions that can be                lists and personnel accountability checks.
RG 2.6, Rev. 2, Page 7


followed easily and quickly. These immediate actions should be memorized by major partici-                  2.  SCOPE OF IMPLEMENTING PROCEDURES
REFERENCES3
pants with a follow-up check of the procedure to ensure that needed actions were included.               2.1 Immediate Action Procedures
1.  U.S. Code of Federal Regulations (CFR), Domestic Licensing of Production and Utilization Facilities, Part 50, Chapter 1, Title 10, Energy, U.S. Nuclear Regulatory Commission, Washington, DC.
  1.4.1 Title and Purpose                                    There should be a separate procedure or procedure subsection for each identified class Each procedure should have a title that is              of emergency to specify and implement the descriptive of its purpose. However, if the                planned response actions required for that title is not sufficiently descriptive,         the        emergency condition. Each procedure should
                                                    2.6-8


(1) clearly identify the action level, the pro-         should refer to or be related to those proce- tective action guide, or the conditions for             dures    for   personnel  accountability  and declaring the emergency condition; (2) list by          personnel monitoring.
2.  U.S. Nuclear Regulatory Commission (NRC), NUREG-1537, Parts 1 and 2, Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors, Washington, DC, February 1996. ADAMS Accession Nos. ML042430055 and ML042430048.


priority the individuals and elements of the emergency organization that are to be notified              2.2.5 Personnel Accountability and mobilized; and (3) specify the emergency actions that are to be taken by designated in-             A method of personnel accountability should dividuals (by title) and elements of the emer-           be specified in procedures to ensure that, at gency organization. Communications procedures            all times, all individuals in the area and should require formality; acknowledgements of            buildings onsite are warned of imminent threats orders and reports; and designation of relative          or hazardous conditions and evacuated from priority of communications with the scene of            affected areas if required.
3. NRC, Interim Staff Guidance (ISG) augmenting NUREG-1537, Parts 1 and 2, Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors, for Licensing Radioisotope Production Facilities and Aqueous Homogeneous Reactors, Washington, DC,
    October 2012. ADAMS Accession Nos. ML12156A069 and ML12156A075.


the emergency, the facility emergency control center,     outside activities,    etc.  Effective          The procedures should designate individuals methods for rapid internal and external trans-          having the responsibility of accounting for mission of information may include preposi-              persons within the reactor facility. The pro- tioned messages (fill in the blanks in specified          cedures should contain appropriate checksheets sequence) and instructions for use of voice,             and signoffs and should provide for reporting telephone, and radio transmission.                       of information to the central authority in charge of the emergency response actions.
4.  NRC, NUREG-0849, Standard Review Plan for the Review and Evaluation of Emergency Plans for Research and Test Reactors, Washington, DC, October 1983. ADAMS Accession No.


2.2 Emergency Action Procedures The following sections list subjects that                2.2.6 Assessment Actions should be covered by written procedures. The Procedures should describe the system for titles of specific procedures, as well as their contents, may vary among licensees, but the              gathering information and data on which to base decisions to escalate or de-escalate emer- actions or subjects described below should be gency response actions. They should identify covered within the group of procedures that implement the emergency plan.                            the types and sources of information available.
ML062190191.


The procedures should specify action levels,
5.  NRC, Regulatory Information Summary (RIS), 2005-02, Revision 1, Clarifying the Process for Making Emergency Plan Changes, Washington, DC, April 19, 2011. ADAMS Accession No.
  2.2.1 Notifications                                    protective action guides, and other guidelines as a basis for decisions to initiate emergency Call lists to alert and mobilize the emergency        measures and actions or to terminate or other- wise modify -emergency actions in progress.


organization and supporting agencies should be The procedures should assign responsibilities specified for each identified class of emergen- for gathering and using assessment data and cy. If call lists are not too lengthy or complex,        information.
ML100340545.


they should be incorporated into the immediate action procedure.
6.  NRC, Information Notice (IN), 92-79, Non-Power Reactor Emergency Event Response, Washington, DC, December 1, 1992. ADAMS Accession No. ML031190745.


2.2.7 First Aid and Medical Care
7. NRC, IN 97-34, Deficiencies in Licensee Submittals Regarding Terminology for Radiological Emergency Action Levels in Accordance with the New Part 20, June 12, 199
  2.2.2 Radiological Surveys The procedures that specify the methods and instructions for receiving, transporting, and Procedures should specify the methods, and handling injured persons and providing for planned locations if feasible, for emergency their medical treatment should specifically radiological surveys onsite and offsite. The              include the precautions and special handling procedures      should include provisions for            required for contaminated patients. The proce- transmitting collected data and information to            dures should cover separately the provisions the individual or organizational element respon-        for and use of medical treatment facilities in sible for emergency assessment functions.                both onsite and offsite areas.


2.2.3 Personnel Monitoring and Decontamina-              2.2.8 Firefighting tion The procedures should require monitoring of              The procedures should cover precautions for individuals leaving restricted areas or other            fighting fires involving radioactive materials.
===7. ADAMS===
    Accession number ML031050574.


areas known or suspected to be contaminated.            They should cover the responsibilities and The procedures should specify contamination              capabilities of both onsite, and, if applicable, levels that require decontamination actions.            off site firefighting teams and equipment. The They should also include or refer to decontami-          procedures should include the clear decision- nation procedures for various types and levels          making chain for interface with offsite agen- of radioactive contamination.                            cies. They should include specific instructions for monitoring the exposure to radiation of off-
8.  NRC, IN 2009-31, Non-power Reactor Licensee Notifications to the NRC during an Incident, Washington, DC, December 10, 2009. ADAMS Accession No. ML092680467.
  2.2.4 Evacuation of Onsite Areas                      site personnel involved in firefighting.


Procedures for evacuation should include the            2.2.9 Reentry action levels that require evacuation of speci- fied areas and buildings, and the site. Primary            Procedures and guidelines should be devel- and secondary evacuation routes and assembly            oped for reentry to previously evacuated areas areas should be designated. These procedures            for the purposes of saving lives, search and
9. American National Standards Institute/American Nuclear Society standard (ANSI/ANS) 15.16-
                                                  2.6-9
    2015, Emergency Planning for Research Reactors, American Nuclear Society, La Grange Park, IL, February 2015.4
10. NRC, Management Directive 6.5, NRC Participation in the Development and Use of Consensus Standards, Washington, DC, December 2011. ADAMS Accession No. ML100600460.


rescue of missing and injured persons, or ma-          with the equipment. Procedures should include nipulation, repair, or recovery of critical            inventory lists of kits, equipment, and instru- equipment    or systems.     These procedures        ments and provisions for periodic inventory, should include specific guidelines for maximum          inspection, calibration, and maintenance.
3  Publicly available NRC documents are available electronically through the NRC Library on the NRCs public Web site at http://www.nrc.gov/reading-rm/doc-collections/ and through the NRCs Agencywide Documents Access and Management System (ADAMS) at http://www.nrc.gov/reading-rm/adams.html. The documents can also be viewed online or printed for a fee in the NRCs Public Document Room (PDR) at 11555 Rockville Pike, Rockville, MD. For problems with ADAMS, contact the PDR staff at 301-415-4737 or (800) 397-4209; or e-mail pdr.resource@nrc.gov.


emergency radiation exposures for reentry and rescue personnel. Procedures should be devel-              2.3.4 Training oped for permitting the voluntary acceptance of emergency exposure for lifesaving actions.                  The training program for the emergency or- ganization should be documented in the form of
4   Copies of ANSI/ANS standards may be purchased from the American Nuclear Society (ANS) Web site (http://www.new.ans.org/store/); or by writing to: American Nuclear Society, 555 North Kensington Avenue, La Grange Park, Illinois 60526, U.S.A., Telephone 800-323-3044.
  2.2.10 Facility Security                            schedules and lesson outlines. The program should include training for licensee employees The facility security procedures should pro-        and for offsite organizations and personnel who vide for security and access control during            are to provide support in the emergency emergency conditions.                                  response. The training for off'site personnel who may be required to enter the facility
  2.2.11 Recovery                                      should typically include familiarization with the facility layout and instructions on site proce- Action levels and guidelines should be devel-        dures necessary for their safety and for their oped for restoring operations and property to a        effective interface with onsite personnel. Off- safe status. The less complex operations such          site personnel training may include emergency as personnel emergencies and emergency alerts          dosimeter issue procedures, firefighting equip- should require only brief recovery action pro-         ment locations, vehicle access routes, and fa- cedures. The more complex emergency opera-             cility alarms.


tions, however, will generally require corre- spondingly complex recovery actions. It is not              Training should include delineation of meth- practicable to plan detailed recovery actions          ods to evaluate its effectiveness and to correct for all conceivable situations, but procedures          weak areas through feedback with emphasis on that include at least the initial planning consid-      schedules, practical training, or periodic exa- erations for recovering, repairing, decontami-          minations.
RG 2.6, Rev. 2, Page 8


nating, etc., potentially affected portions of the facility should be developed.                           2.3.5 Tests and Drills During recovery operations, personnel expo-             Procedures should provide for onsite practice sures to radiation should be maintained within          drills that use detailed scenarios to test both
11. National Technology Transfer and Advancement Act of 1995, Public Law No. 104-113 (1996).
10 CFR Part 20 limits.                                  specific procedures and implementation of the major aspects of the emergency plan. The sce-
12. NRC, NUREG-1520, Revision 1, Standard Review Plan for the Review of a License Application for a Fuel Cycle Facility - Final Report, Nuclear Regulatory Commission, Washington, DC,
2.3 Supplemental Procedures                              narios should be planned simulations of emer- gency situations, and they should be approved This section lists subjects for procedures            by facility management after they have been that supplement those covering emergency                reviewed for scope and adequacy.
    May 2010. ADAMS Accession No. ML101390110.


response actions. The specific titles and con- tents may vary, but the described subjects                  The procedures should consider testing on should be covered in the licensee's procedural          both an announced and unannounced basis.
13. NRC, NUREG-1520, Revision 2, Standard Review Plan for Fuel Cycle Facilities License Applications - Final Report, Nuclear Regulatory Commission, Washington, DC, June 2015.


system.                                                 They should require the use of observers during the conduct of test drills and should
ADAMS Accession No. ML15098A115.
  2.3.1 Communications                                  contain provisions for appropriate critique of the drills.


Procedures should be available for activat- ing, operating, testing, and maintaining the emergency communications systems.
14. International Atomic Energy Agency (IAEA), Safety Requirements, NS-R-4, Safety of Research Reactors, International Atomic Energy Agency, Vienna, Austria, 20055.


3.   REVIEW AND APPROVAL OF PROCEDURES
5   Copies of International Atomic Energy Agency (IAEA) documents may be obtained through their Web site:
     2.3.2 Documentation and Records Procedures should include requirements for recording the implementation and completion or               The procedural system used by licensees termination of emergency response actions,              should contain written rules and instructions logging assessment data, reports of personnel            governing the writing, revising, and updating accountability, and maintenance of required              of implementing procedures. The instructions records and logs.                                       should specify the methods to be used to ensure     that  procedures,  revisions,   and
     WWW.IAEA.Org/ or by writing the International Atomic Energy Agency P.O. Box 100 Wagramer Strasse 5, A-1400
  2.3.3 Equipment and Instrumentation                    changes are reviewed for adequacy, approved for use, and distributed to user organizations Operating instructions for equipment and in-           and individuals having the responsibility for strumentation should be prepared and stored              implementing the procedures.
     Vienna, Austria. Telephone (+431) 2600-0, Fax (+431) 2600-7, or E-Mail at Official.Mail@IAEA.Org.


2.6-10}}
RG 2.6, Rev. 2, Page 9}}


{{RG-Nav}}
{{RG-Nav}}

Latest revision as of 12:46, 18 March 2020

Emergency Planning for Research and Test Reactors and Other Non-Power Production and Utilization Facilities.
ML17263A472
Person / Time
Issue date: 09/30/2017
From: Steven Lynch, Geoffrey Wertz
NRC/NRR/DPR/PRLB
To:
Gardocki S
Shared Package
ML17136A018 List:
References
DG-2004 RG-2.006, Rev. 2
Download: ML17263A472 (9)
v • d • e


U.S. NUCLEAR REGULATORY COMMISSION September 2017 OFFICE OF NUCLEAR REGULATORY RESEARCH Revision 2 REGULATORY GUIDE Technical Leads:

S. Lynch G. Wertz REGULATORY GUIDE 2.6 (Draft was issued as DG-2004 dated February 2017)

EMERGENCY PLANNING FOR RESEARCH AND TEST

REACTORS AND OTHER NON-POWER PRODUCTION AND

UTILIZATION FACILITIES

A. INTRODUCTION

Purpose This regulatory guide (RG) provides licensees and applicants with a method that the staff of the U.S. Nuclear Regulatory Commission (NRC) considers acceptable for use in complying with the regulations on the content of emergency plans for research and test reactors and other non-power production and utilization facilities licensed under Title 10 of the Code of Federal Regulations (10 CFR),

Part 50, Domestic Licensing of Production and Utilization Facilities (10 CFR Part 50) (Ref. 1).

Applicability This RG applies to all applicants and holders of licenses for research and test reactors and other non-power production and utilization facilities under 10 CFR 50.21, Class 104 Licenses; for medical therapy and research and development facilities, and 10 CFR 50.22, Class 103 Licenses; for commercial and industrial facilities.

Applicable Regulations

  • 10 CFR 50.34(a)(10) requires that each application for a construction permit include a discussion of the facilitys preliminary plans for coping with emergencies as part of a preliminary safety analysis report. The items which shall be included in the preliminary plan are set forth in Appendix E, Emergency Planning and Preparedness for Production and Utilization Facilities, to

10 CFR Part 50.

  • 10 CFR 50.34(b)(6)(v) requires that each application for a Part 50 license to operate a facility include a final safety analysis report that contains, along with other information, the applicants plans for coping with emergencies, including the items specified in Appendix E to 10 CFR

Part 50.

Written suggestions regarding this RG or development of new guides may be submitted through the NRCs public Web site under the Regulatory Guides document collection of the NRC Library at http://www.nrc.gov/reading-rm/doc-collections/reg- guides/contactus.html.

Electronic copies of this RG, previous versions of this guide, and other recently issued guides are available through the NRCs public Web site under the Regulatory Guides document collection of the NRC Library at http://www.nrc.gov/reading-rm/doc- collections/. The RG is also available through the NRCs Agencywide Documents Access and Management System (ADAMS) at http://www.nrc.gov/reading-rm/adams.html, under ADAMS Accession No. ML17137A096. The regulatory analysis may be found in ADAMS under Accession No. ML16035A477 and the staff responses to the public comments on DG-2004 may be found under ADAMS Accession No. ML17137A099.

  • 10 CFR Part 50, Appendix E, Emergency Planning and Preparedness for Production and Utilization Facilities identifies the minimum requirements for the emergency plans to be included with the safety analysis report submitted as part of the construction permit or license application. It also indicates that because operation of facilities other than power reactors involve distinct considerations, the size of the emergency preparedness zone (EPZ) and degree of compliance with requirements in Appendix E, sections I through V, as necessary, will be determined on a case-by-case basis using this regulatory guide for research and test reactor, and other non-power production and utilization facility emergency response plans.

Related Guidance

  • NUREG-1537, Parts 1 and 2, Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors (Ref. 2), provides guidance for applicants preparing license applications for non-power reactor licenses and the NRC staff in its review of these license applications.
  • Final Interim Staff Guidance (ISG) Augmenting NUREG-1537, Parts 1 and 2, Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors (Ref. 3)

provides guidance for applicants preparing license applications for radioisotope production facilities and aqueous homogeneous reactors and the NRC staff in its review of these license applications.

  • NUREG-0849, Standard Review Plan for the Review and Evaluation of Emergency Plans for Research and Test Reactors, provides guidance for the NRC staff in its review of emergency plans for research and test reactors (Ref. 4).
  • Regulatory Information Summary (RIS) 2005-02, Revision 1, Clarifying the Process for Making Emergency Plan Changes (Ref. 5), provides specific information with regard to processing changes to emergency plans. The RIS includes information to determine whether a decrease in effectiveness resulted from the proposed emergency plan change.

Applicable Information Notices

describes an event that required interface with the public and highlights the need for licensees to quickly apprise the NRC of the circumstances of an emergency classification.

  • IN 97-34, Deficiencies in Licensee Submittals Regarding Terminology for Radiological Emergency Action Levels in Accordance with the New Part 20 (Ref. 7), updates Appendix I of NUREG-0849 to reflect revised 10 CFR Part 20 regulations in the radiological emergency action levels (EALs).
  • IN 2009-31, Non-Power Reactor Licensee Notifications to the NRC during an Incident (Ref. 8),

describes lessons learned from an emergency declaration at a non-power reactor regarding the appropriate NRC office to contact and the types of information that the NRC may request from licensees at that time.

RG 2.6, Rev. 2, Page 2

Purpose of Regulatory Guides The NRC issues RGs to describe to the public methods that the staff considers acceptable for use in implementing specific parts of the agencys regulations, to explain techniques that the staff uses in evaluating specific problems or postulated events, and to provide guidance to applicants. RGs are not substitutes for regulations, and compliance with them is not required. Methods and solutions that differ from those set forth in RGs will be deemed acceptable if they provide a basis for the findings required for the issuance or continuance of a permit or license by the Commission.

Paperwork Reduction Act This RG provides guidance for implementing mandatory information collections covered by 10 CFR Parts 50 and 52 that are subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et. seq.).

These information collections were approved by the Office of Management and Budget (OMB), under control numbers 3150-0011 and 3150-0151 respectively. Send comments regarding this information collection to the Information Services Branch, U.S. Nuclear Regulatory Commission, Washington, DC

20555-0001, or by e-mail to Infocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0011 and 3150-0151) Office of Management and Budget, Washington, DC 20503.

Public Protection Notification The NRC may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a currently valid OMB control number.

RG 2.6, Rev. 2, Page 3

B. DISCUSSION

Reason for Revision This revision of the guide (Revision 2) addresses new issues identified since the guide was last revised in March 1983 (Revision 1). This revision endorses the latest version of the consensus standard, American National Standards Institute (ANSI)/American Nuclear Society (ANS) standard ANSI/ANS-

15.16-2015, Emergency Planning for Research Reactors (Ref. 9) (ANSI/ANS-15.16 or the standard).

The scope of RG 2.6 was expanded to address non-power 10 CFR Part 50 facilities other than research and test reactors. Other changes to RG 2.6 include editorial changes, and the current program guidance for RGs.

Revising this RG to endorse the use of, in whole or in part, a consensus standard is consistent with the NRC policy of evaluating the latest versions of national consensus standards to determine their suitability for endorsement by RGs. This approach also complies with the NRCs Management Directive (MD) 6.5, NRC Participation in the Development and Use of Consensus Standards, (Ref. 10) and is in accordance with Public Law 104-113, National Technology Transfer and Advancement Act of 1995 (Ref.

11).

Background The Commissions interest in emergency planning is focused primarily on situations that may cause or threaten to cause radiological hazards that could affect public health and safety. Emergency plans should be directed toward mitigating the consequences of emergencies and should provide reasonable assurance that appropriate measures can and will be taken to protect public health and safety in the event of an emergency. Although developing a completely detailed plan encompassing every conceivable type of emergency situation is not practical, advanced planning and provisions for ensuring the availability of necessary equipment, supplies, and services can create a high order of preparedness and ensure an orderly and timely decision making process at the time of an emergency. The plans should express the overall concept of operation that describes how the elements of advanced planning have been considered and the provisions that have been made to cope with emergency situations.

From its review of safety analysis reports for research and test reactors and other non-power production and utilization facilities, and based on the radionuclide inventory and postulated radioactive releases at these facilities, the NRC staff determined that the potential radiological hazards to the public associated with the operation of these facilities are less than those associated with the operation of commercial nuclear power plants. However, the types and potential consequences of emergencies vary from facility to facility. As such, the NRC staff expects that the emergency plans and procedures developed by or for each facility should realistically reflect the hazards and consequences of each facility.

The ANSI and the ANS issued ANSI/ANS-15.16, which is generally consistent with current regulatory requirements. Originally developed in 1982, and updated in 2008 and 2015, the current standard provides specific acceptance criteria for research and test reactors and other non-power production and utilization facilities to comply with the applicable requirements set forth in 10 CFR 50.34, Contents of Applications; Technical Information, 10 CFR 50.54, Conditions of Licenses, and Appendix E to 10 CFR Part 50. These criteria provide a basis for licensees and applicants to develop acceptable emergency response plans and improve emergency preparedness at their facilities.

RG 2.6, Rev. 2, Page 4

The NRC staff issued NUREG-0849 in 1983 as a standard review plan for evaluating emergency plans submitted by research and test reactor licensees.1 Consistent with ANSI/ANS-15.16, NUREG-0849 provides areas of review, planning standards, and evaluation items for NRC staff to evaluate a licensees or applicants compliance with the applicable emergency planning requirements described above. Both NUREG-0849 and ANSI/ANS-15.16 were incorporated by reference into NUREG-1537, Section 12.7, Emergency Planning, and the ISG augmenting NUREG-1537. This guidance forms the basis for all construction permit and operating license application reviews of research and test reactors and other non- power production and utilization facilities. Relevant non-reactor emergency planning guidance contained in the ISG augmenting NUREG-1537 is based on NUREG-1520, Revision 1, Standard Review Plan for the Review of a License Application for a Fuel Cycle Facility, published in May 2010 (Ref. 12).2 Harmonization with International Standards The International Atomic Energy Agency (IAEA) has established a series of safety standards constituting a high level of safety for protecting people and the environment. Safety standards present international good practices and increasingly reflect best practices to help users striving to achieve high levels of safety. Relative to this RG, IAEA Safety Requirements NS-R-4, Safety of Research Reactors (Ref. 14), addresses emergency planning in Sections 7.72 through 7.78. While the NRC has an interest in facilitating the harmonization of standards used domestically and internationally, the agency does not specifically endorse or approve the use of NS-R-4 and is only acknowledging that it may be a useful reference for general information. The NRC could consider the use of the international standard in a licensing action following adequate justification by a licensee or applicant and technical review by the NRC.

Documents Discussed in Staff Regulatory Guidance This RG endorses, in part, the use of one or more codes or standards developed by external organizations, and other third party guidance documents. These codes, standards and third party guidance documents may contain references to other codes, standards or third party guidance documents (secondary references). If a secondary reference has itself been incorporated by reference into NRC

regulations as a requirement, then licensees and applicants must comply with that standard as set forth in the regulation. If the secondary reference has been endorsed in an RG as an acceptable approach for meeting an NRC requirement, then the standard constitutes a method acceptable to the NRC staff for meeting that regulatory requirement as described in the specific RG. If the secondary reference has neither been incorporated by reference into NRC regulations nor endorsed in an RG, then the secondary reference is neither a legally-binding requirement nor a generic NRC approved acceptable approach for meeting an NRC requirement. However, licensees and applicants may consider and use the information in the secondary reference, if appropriately justified, consistent with current regulatory practice, and consistent with applicable NRC requirements.

1 Appendix I of NUREG-0849 was updated in April 1997 to reflect revisions to 10 CFR Part 20 requirements in radiological EALs. The NRC staff issued IN 97-34 (Ref. 7) in June 1997 to inform licensees of this revision to the NUREG.

2 Since the publication of the ISG augmenting NUREG-1537, the NRC published Revision 2 to NUREG-1520 in June

2015 (Ref. 13). Licensees and applicants should refer to the most recent revisions of NRC guidance documents when developing license applications and implementing NRC requirements.

RG 2.6, Rev. 2, Page 5

C. STAFF REGULATORY GUIDANCE

The NRC staff endorses the guidance in ANSI/ANS-15.16-2015 for use as a means for research and test reactor and other non-power production and utilization facility licensees and applicants to comply with the requirements in 10 CFR 50.34(a)(10), 10 CFR 50.34(b)(6)(v), 10 CFR 50.54(q), and 10 CFR Part 50, Appendix E. The following clarifications are added:

1. Radiation Dose Levels for Emergency Action Levels The radiation dose levels of the emergency action levels established in ANSI/ANS-15.16 for the various emergency classes differ from those specified for power reactors. However, in the judgment of the NRC staff, the radiation dose levels specified in Table I of the standard are adequate for the credible accidents associated with the operation of research and test reactors and other non-power production and utilization facilities and the specified action levels provide reasonable assurance that protective measures associated with the action levels specified in Table I can and will be taken, provided that the licensee also gives appropriate emphasis to developing emergency action levels that relate directly to facility parameters (e.g., pool water levels and area radiation monitors).

2. NRC Notification The licensee should notify the NRC headquarters operations center of events classified under Table I of the standard.

3. Implementing Procedures The licensee should establish and maintain procedures for implementing the requirements of the emergency plan. The implementing procedures should be readily accessible for use by the staff of the implementing organization (e.g., operators, facility management, etc.). The emergency implementing procedures should be maintained and made available at the facility for inspection and review at any time by an NRC representative.

4. Procedure Review and Revision The procedural system that the licensee uses for the review and approval of emergency implementing procedures should contain instructions governing the writing, revising, and updating of implementing procedures. The instructions should specify the methods that the licensee will use to ensure that procedures, revisions, and changes are reviewed for adequacy, approved for use, and distributed to user organizations and individuals responsible for implementing the procedures.

5. Plan Details Subject to Routine Change The plan should not incorporate details that may routinely change (e.g., names and telephone numbers, specific items of equipment and supplies, inventory lists, and step-by-step procedures or checklists that may be altered as a result of experience or test exercises). These details are useful, but are better maintained in the facilitys implementing emergency procedures.

RG 2.6, Rev. 2, Page 6

D. IMPLEMENTATION

The purpose of this section is to provide information to applicants and licensees regarding the NRCs plans for using this RG. The regulatory position held in this guidance demonstrates the method that the NRC staff finds acceptable for an applicant or licensee to meet the requirements of the underlying NRC regulations. Methods or solutions that differ from those described in this RG may be deemed acceptable if they provide sufficient basis and information for the NRC staff to verify that the proposed alternative demonstrates compliance with the appropriate NRC regulations. Current licensees may continue to use guidance the NRC found acceptable for complying with the identified regulations as long as their current licensing basis remains unchanged.

The guidance in this RG is not a backfit, as that term is defined in 10 CFR 50.109, Backfitting, because non-power facilities licensed under 10 CFR Part 50 are not included within the scope of entities protected by 10 CFR 50.109.

RG 2.6, Rev. 2, Page 7

REFERENCES3

1. U.S. Code of Federal Regulations (CFR), Domestic Licensing of Production and Utilization Facilities, Part 50, Chapter 1, Title 10, Energy, U.S. Nuclear Regulatory Commission, Washington, DC.

2. U.S. Nuclear Regulatory Commission (NRC), NUREG-1537, Parts 1 and 2, Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors, Washington, DC, February 1996. ADAMS Accession Nos. ML042430055 and ML042430048.

3. NRC, Interim Staff Guidance (ISG) augmenting NUREG-1537, Parts 1 and 2, Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors, for Licensing Radioisotope Production Facilities and Aqueous Homogeneous Reactors, Washington, DC,

October 2012. ADAMS Accession Nos. ML12156A069 and ML12156A075.

4. NRC, NUREG-0849, Standard Review Plan for the Review and Evaluation of Emergency Plans for Research and Test Reactors, Washington, DC, October 1983. ADAMS Accession No.

ML062190191.

5. NRC, Regulatory Information Summary (RIS), 2005-02, Revision 1, Clarifying the Process for Making Emergency Plan Changes, Washington, DC, April 19, 2011. ADAMS Accession No.

ML100340545.

6. NRC, Information Notice (IN), 92-79, Non-Power Reactor Emergency Event Response, Washington, DC, December 1, 1992. ADAMS Accession No. ML031190745.

7. NRC, IN 97-34, Deficiencies in Licensee Submittals Regarding Terminology for Radiological Emergency Action Levels in Accordance with the New Part 20, June 12, 199

7. ADAMS

Accession number ML031050574.

8. NRC, IN 2009-31, Non-power Reactor Licensee Notifications to the NRC during an Incident, Washington, DC, December 10, 2009. ADAMS Accession No. ML092680467.

9. American National Standards Institute/American Nuclear Society standard (ANSI/ANS) 15.16-

2015, Emergency Planning for Research Reactors, American Nuclear Society, La Grange Park, IL, February 2015.4

10. NRC, Management Directive 6.5, NRC Participation in the Development and Use of Consensus Standards, Washington, DC, December 2011. ADAMS Accession No. ML100600460.

3 Publicly available NRC documents are available electronically through the NRC Library on the NRCs public Web site at http://www.nrc.gov/reading-rm/doc-collections/ and through the NRCs Agencywide Documents Access and Management System (ADAMS) at http://www.nrc.gov/reading-rm/adams.html. The documents can also be viewed online or printed for a fee in the NRCs Public Document Room (PDR) at 11555 Rockville Pike, Rockville, MD. For problems with ADAMS, contact the PDR staff at 301-415-4737 or (800) 397-4209; or e-mail pdr.resource@nrc.gov.

4 Copies of ANSI/ANS standards may be purchased from the American Nuclear Society (ANS) Web site (http://www.new.ans.org/store/); or by writing to: American Nuclear Society, 555 North Kensington Avenue, La Grange Park, Illinois 60526, U.S.A., Telephone 800-323-3044.

RG 2.6, Rev. 2, Page 8

11. National Technology Transfer and Advancement Act of 1995, Public Law No. 104-113 (1996).

12. NRC, NUREG-1520, Revision 1, Standard Review Plan for the Review of a License Application for a Fuel Cycle Facility - Final Report, Nuclear Regulatory Commission, Washington, DC,

May 2010. ADAMS Accession No. ML101390110.

13. NRC, NUREG-1520, Revision 2, Standard Review Plan for Fuel Cycle Facilities License Applications - Final Report, Nuclear Regulatory Commission, Washington, DC, June 2015.

ADAMS Accession No. ML15098A115.

14. International Atomic Energy Agency (IAEA), Safety Requirements, NS-R-4, Safety of Research Reactors, International Atomic Energy Agency, Vienna, Austria, 20055.

5 Copies of International Atomic Energy Agency (IAEA) documents may be obtained through their Web site:

WWW.IAEA.Org/ or by writing the International Atomic Energy Agency P.O. Box 100 Wagramer Strasse 5, A-1400

Vienna, Austria. Telephone (+431) 2600-0, Fax (+431) 2600-7, or E-Mail at Official.Mail@IAEA.Org.

RG 2.6, Rev. 2, Page 9


Retrieved from "https://kanterella.com/w/index.php?title=Regulatory_Guide_2.6&oldid=2623008"