ANSI ANS 15.16-2015 Emergency Planning for Research Reactors.pdf

《ANSI ANS 15.16-2015 Emergency Planning for Research Reactors.pdf》由会员分享，可在线阅读，更多相关《ANSI ANS 15.16-2015 Emergency Planning for Research Reactors.pdf（21页珍藏版）》请在麦多课文档分享上搜索。

1、An American National StandardPublished by the American Nuclear Society 555 N. Kensington AveLa Grange Park, IL 60526ANSI/ANS-15.16-2015 Emergency Planningfor Research ReactorsANSI/ANS-15.16-2015ANSI/ANS15.162015American National Standard Emergency Planning for Research ReactorsSecretariatAmerican Nu

2、clear SocietyPrepared by theAmerican Nuclear SocietyStandards CommitteeWorking Group ANS15.16Published by theAmerican Nuclear Society555 North Kensington AvenueLa Grange Park, Illinois 60525 USAApproved February 11, 2015 by theAmerican National Standards Institute, Inc. American National Standard AN

3、SI/ANS-15.16-2015Designation of this document as an American National Standard attests that the principles of openness and due process have been followed in the approval procedure and that a consensus of those directly and materially affected by the standard has been achieved.This standard was devel

4、oped under the procedures of the Standards Committee of the American Nuclear Society; these procedures are accredited by the American National Standards Institute, Inc., as meeting the criteria for American National Standards. The consensus committee that approved the standard was balanced to ensure

5、 that competent, concerned, and varied interests have had an opportunity to participate.An American National Standard is intended to aid industry, consumers, govern-mental agencies, and general interest groups. Its use is entirely voluntary. The ex-istence of an American National Standard, in and of

6、 itself, does not preclude any-one from manufacturing, marketing, purchasing, or using products, processes , or procedures not conforming to the standard.By publication of this standard, the American Nuclear Society does not insure anyone utilizing the standard against liability allegedly arising fr

7、om or after its use. The content of this standard reflects acceptable practice at the time of its ap proval and publication. Changes, if any, occurring through developments in the state of the art, may be considered at the time that the standard is subjected to periodic review. It may be reaffirmed,

8、 revised, or withdrawn at any time in accord ance with established procedures. Users of this standard are cautioned to determine the validity of copies in their possession and to establish that they are of the latest issue.The American Nuclear Society accepts no responsibility for interpretations of

9、 this standard made by any individual or by any ad hoc group of individuals. Responses to inquiries about requirements, recommendations, and/or permissive statements (i.e., “shall,” “should,” and “may,” respectively) should be sent to the Standards Department at Society Headquarters. Action will be

10、taken to provide appropriate response in accordance with established procedures that ensure consensus.Comments on this standard are encouraged and should be sent to Society Headquarters.Published byAmerican Nuclear Society555 North Kensington AvenueLa Grange Park, Illinois 60526 USAThis document is

11、copyright protected.Copyright 2015 by American Nuclear Society. All rights reserved.Any part of this standard may be quoted. Credit lines, should read “Extracted from American National Standard ANSI/ANS-15.16-2015 with permission of the publisher, the American Nuclear Society.” Reproduction prohibit

12、ed under copyright convention unless written permission is granted by the American Nuclear Society.Printed in the United States of AmericaAmerican National StandardAmerican National Standard ANSI/ANS-15.16-2015The American Nuclear Society (ANS) Standards Committee will provide responses to inquiries

13、 about requirements, recommendations, and/or permissive statements (i.e., “shall,” “should,” and/or “may,” respectively) in American National Standards that are developed and approved by ANS. Responses to inquiries will be provided according to the Policy Manual for the ANS Standards Committee. Nonr

14、elevant inquiries or those concerning unrelated subjects will be returned with appropriate explanation. ANS does not develop case interpretations of requirements in a standard that are applicable to a specific design, operation, facility, or other unique situation only and therefore is not intended

15、for generic application.Responses to inquiries on standards are published in ANSs magazine, Nuclear News, and are available publicly on the ANS Web site or by contacting the ANS Standards Administrator.Inquiry requests must include the following:(1) the name, company name if applicable, mailing addr

16、ess, and telephone number of the inquirer;(2) reference to the applicable standard edition, section, paragraph, figure and/or table;(3) the purposes of the inquiry; (4) the inquiry stated in a clear, concise manner; (5) a proposed reply, if the inquirer is in a position to offer one.Inquiries should

17、 be addressed to: American Nuclear SocietyATTN: Standards Administrator 555 N. Kensington AvenueLa Grange Park, IL 60526or standardsans.orgInquiry RequestsInquiry FormatAmerican National Standard ANSI/ANS-15.16-2015-i-American National Standard ANSI/ANS-15.16-2015(This Foreword is not a part of the

18、American National Standard “Emergency Planning for Research Reactors,” ANSI/ANS15.162015.)The American Nuclear Society (ANS) established Subcommittee ANS15, Operation of Research Reactors, in the fall of 1970 for the purpose of prepar ing a standard for the operation of research reactors. In January

19、 1972, this charter was expanded to include the multiple tasks involved in preparing all standards for research reactors. To implement this enlarged responsibility, a number of subcommittee work ing groups were established to develop standards for consideration and complementary action by Subcommitt

20、ee ANS-15. ANS-15.16 is one of these groups.In August 1980, the U.S. Nuclear Regulatory Commission (NRC) published new rules for Code of Federal Regulations, Title 10, “Energy,” Part 50, “Licensing of Production and Utilization Facilities,” Appendix E, “Emergency Planning and Preparedness for Produc

21、tion and Utilization Facilities.” The changes to the regulations place emphasis on emergency preparedness in regard to notifying off-site authorities and initiating protective actions on the basis of severity of facility damage and potential as well as actual radiological releases that are occurring

22、 or have occurred. The regulations also require the identification of a spec trum of radiological emergencies applicable to a reactor facility and the grouping of these emergencies into specified classes of emergencies. They also require that a facilitys emergency plan identify emergency action leve

23、ls (EALs) that are to be used to in itiate the planned emergency responses for each emergency. In addition, the regula tions require the determination of the need for establishing an offsite emergency planning zone (EPZ) on a casebycase basis and require the identification of predetermined actions f

24、or protecting individuals within this zone.In January of 1994, Code of Federal Regulations, Title 10, “Energy,” Part 20, “Standards for Protection Against Radiation” (10 CFR 20) was extensively revised to use the International System of Units (SI) and terminology. The NRC issued supportive guidance

25、in the form of Appendix 1 to NUREG0849 in April 1997. NRC Information Notice 97-34, issued in June 1997, informed licensees of revised guidance. As a result of the changes to 10 CFR 20, the working group was tasked to revise ANSI/ANS15.161982 (R2000) to be consistent. The present revision incorporat

26、es the use of SI units, the regulatory positions from NRC Regulatory Guide 2.6, Revision 1, March 1983 relative to the content, approval, and revision control of emergency procedures, and the recognition of reactor facility physical security issues for emergency planning.In 2014, ANSI/ANS-15.16-2008

27、 was revised to incorporate security-related events into the emergency plan in a risk-informed way. Because of the low inventory of radioactive material, most research and test reactors do not meet the threshold levels that initiate either a General Emergency or a Site Area Emergency. In fact, many

28、do not meet the threshold for an Alert classification. As such, the revisions ensured that security-related events were incorporated into emergency plans without creating emergency classifications that did not or would not otherwise exist.ANSI/ANS-15.16-2015 identifies the elements of an emergency p

29、lan. It pro vides criteria and guidance that should be considered in formulating an emergency plan. The standard identifies the emergency classes that should be used to categorize the spectrum of radiological emergencies and provides guidance for establishing the emergency classification system. It

30、provides examples of typical EALs associated with each emergency and guidance for establishing an EPZ. This standard is intended to be applicable to all research reactors. Research reactors that are not licensed by the NRC, such as those operated for the U.S. Department of Energy (DOE) will also fin

31、d Foreword-ii-this standard applicable. However, it is understood that more proscriptive guidance, for example, DOE Order 151.1C, Comprehensive Emergency Management System, provides more detail (DOEspecific) than is found in this standard.The applicability of the emergency plan elements presented in

32、 this standard will vary from one research reactor facility to another depending upon the reactor power level and the potential radiological consequences that result from postulated events. The risk from credible radiological emergency situations at many research reactor facilities is usually minima

33、l and may not require the application of all the emergency plan elements in this standard or the establishment of an EPZ.This standard might reference documents and other standards that have been superseded or withdrawn at the time the standard is applied. A statement has been included in the refere

34、nce section that provides guidance on the use of references.The membership of the ANS-15.16 Working Group contributing to the current standard is as follows:S. R. Reese (Chair), Oregon State UniversityS. OKelly, National Institute of Standards and TechnologyL. Bobek, University of Massachusetts, Low

35、ellJ. Bryson, Sandia National LaboratoryL. Foyto, University of Missouri, ColumbiaS. Miller, Armed Forces Radiobiology Research InstituteM. Norris, U.S. Nuclear Regulatory CommissionSubcommittee ANS15, Operation of Research Reactors, of the American Nuclear Society Research and Advanced Reactor Cons

36、ensus Committee, had the following membership at the time of its approval of this standard:D. S. OKelly (Chair), National Institute of Standards and TechnologyA. Adams, Jr., U.S. Nuclear Regulatory CommissionL. M. Bobek, University of Massachusetts LowellJ. Jenkins, Thermo ScientificM. Krause, Unive

37、rsity of TexasL. Foyto, University of MissouriColumbiaS. Miller, AFRRI/NMCM. Morrison, Idaho National LaboratoryS. R. Reese, Oregon State UniversityG. Steingass, University of California at DavisB. Shea, University of FloridaThe American National Research and Advanced Reactor Consensus Committee had

38、 the following membership at the time it reviewed and approved this standard:G. Flanagan (Chair), Oak Ridge National LaboratoryB. Bevard (Vice Chair), Oak Ridge National LaboratoryS. OKelly (Vice Chair), National Institute of Standards the word “should” is used to denote a recommenda-tion; and the w

39、ord “may” is used to denote a permission, neither a requirement nor a recommendation.2.2 Definitionsemergency: An emergency is a condition that calls for immediate action beyond the scope of normal operating procedures to avoid an acci dent or to mitigate the consequences of one.emergency action lev

40、els (EALs): Specific instrument readings or observations, radiological dose or dose rates, or specific contamination levels of airborne, waterborne, or surface-deposited radioactive materials that may be used as recognized conditions that result in actions such as (a) establishing emergency classes

41、and (b) initiating appropriate emergency measures.emergency classes: Emergency classes are classes of accidents grouped by severity level for which predetermined emergency measures should be taken or considered.emergency plan: An emergency plan is a docu ment that provides the basis for actions to c

42、ope with an emergency. It outlines the objectives to be met by the emergency procedures and defines the au-thority and responsibilities to achieve such objectives.emergency planning zone (EPZ): Area for which off-site emergency planning is performed to as-sure that prompt and effective actions can b

43、e taken to protect the public in the event of an ac cident. The EPZ size is dependent on reactor power level and the distance beyond the site boundary at which the protec tive action guides could be exceeded.emergency procedures: Emergency procedures are documented instructions that detail the imple

44、mentation actions and methods required to achieve the objectives of the emergency plan.off-site: The geographical area that is beyond the site boundary.on-site: The geographical area that is within the site boundary.operations boundary: The area within the site boundary such as the reactor building

45、(or the nearest physical personnel barrier in cases where the reactor building is not a principal physical personnel barrier) where the reactor chief administrator has direct authority over all activities. The area within this boundary shall have prearranged evacuation procedures known to personnel

46、frequenting the area.protective action guides: Projected radio logical dose or dose commitment values to in dividuals that warrant protective action follow ing a release of radioactive material. Protective actions would be warranted provided the reduc tion in individual dose expected to be achieved

47、by carrying out the protective action is not off set by excessive risks to individual safety in tak ing the protective action. The projected dose does not include the dose that has occurred prior to the assessment.Emergency Planning for Research Reactors32American National Standard ANSI/ANS-15.16-20

48、15research reactor: A device designed to support a self-sustaining neutron chain reaction for research, developmental, educational, training, or experimental purposes and that may have provisions for pro-duction of nonfissile radioisotopes.site boundary: The site boundary is a boun dary that does no

49、t necessarily have restrictive barriers and surrounds the operations boundary wherein the reactor administrator may directly initiate emer-gency activities. The area within the site boundary may be frequented by people unac quainted with the reactor operations.3 Content of emergency planAn emergency plan shall be prepared that addresses the necessary provisions for coping with emer-gencies within and beyond the site boundary. The emergency plan provisions shall be implemented by detailed emergency procedures. Activation of the emergency plan or portions thereof shall be