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1、ANSUANS-3.8.1 -1 995 ANS 3-8-1 95 0724818 0202434 TT2 criteria for radiological emergency response functions and organizations COPYRIGHT American Nuclear Society (ANS) Licensed by Information Handling Services COPYRIGHT American Nuclear Society (ANS) Licensed by Information Handling Services ANS 3.8
2、.1 95 0724838 0202435 939 ANSVANS-3.8.1-1995 . American National Standard Criteria for Radiological Emergency Response Functions and Organizations Secretariat American Nuclear Society Prepared by the American Nuclear Society Standards Committee Working Group ANS-3.8 Published by the American Nuclear
3、 Society 555 North Kensington Avenue La Grange Park, Illinois 60526 USA Approved November 15,1995 by the American National Standards Institute, Inc. ANS 3.8.3 95 m 0724838 0202q3b 875 m American National Standard Designation of this document as an American National Standard attests that the principl
4、es 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 developed under procedures of the Standards Committee of the American Nuclear Society; these procedures are
5、accredited by the Amer- ican National Standards Institute, Inc., as meeting the criteria for American National Standards. The consensus committee that approved the standard was balanced to ensure that competent, concerned, and varied interests have had an opportunity to participate. An American Nati
6、onal Standard is intended to aid industry, consumers, governmental agencies, and general interest groups. Its use is entirely volun- tary. The existence of an American National Standard, in and of itself, does not preclude anyone from manufacturing, marketing, purchasing, or using products, processe
7、s, 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 from or after its use. The content of this standard reflects acceptable practice at the time of its approva
8、l and publication. Changes, if any, occurring through develop- ments in the state of the art, may be considered at the time that the standard is subjected to periodic review. It may be reaffirmed, revised, or withdrawn at any time in accordance with established procedures. Users of this standard are
9、 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 this standard made by any individual or by any ad hoc group of individuals. Requests for interpretation
10、 should be sent to the Standards Department at Society Headquarters. Action will be taken to provide appropriate response in accordance with established procedures that ensure consensus on the inter- pretation. Comments on this standard are encouraged and should be sent to Society Headquarters. Publ
11、ished by American Nuclear Society 555 North Kensington Avenue La Grange Park, Illinois 60526 USA Copyright O 1995 by American Nuclear Society. All rights reserved. Any part of this standard may be quoted. Credit lines should read “Extracted from American National Standard ANSUANS-3.8.1-1995 with per
12、mission of the publisher, the American Nuclear Society.“ Reproduction prohibited under copyright convention unless written permission is granted by the American Nuclear Society. Printed in the United States of America COPYRIGHT American Nuclear Society (ANS) Licensed by Information Handling Services
13、 COPYRIGHT American Nuclear Society (ANS) Licensed by Information Handling Services (This Foreword is not a part of American National Standard Criteria for Radiological Emergency Response Functions and Organizations, ANSUANS-3.8.1-1995.) Foreword Every nuclear power plant owner organization is requi
14、red by federal regulations to have a detailed radiological emergency response plan. The plant operators are required to perform routine, abnormal, and emergency actions in a manner to reduce to the extent feasible the likelihood of any particular event developing into an emergency condition. An obje
15、ctive of sound operations is to prevent emergency conditions. The objective of an emergency response program is emergency mitigation. The plant operators are the key to emergency prevention and mitigation at all times. If a situation arises which activates the radiological emergency response plan, t
16、he plant operators identify developing trends and take the appropriate action to prevent or mitigate a radiological release. The plant operators identiSr the need for emergency support, make initial contact with emergency response organizations, and activate the radiological emergency response plan.
17、 As the emergency develops, the administrative, notification, and coordinating functions are transferred from the plant operators to other individuals within the emergency organization as defined in the radiological emergency response plan. Regardless of the functions shifted from the plant operator
18、s to the emergency organization, the responsibility for placing the plant in a safe configuration remains with the plant operators. The ANS-3.8 series of standards provides guidance to nuclear power plant utilities pertaining to radiological emergency response plan preparation based upon the experie
19、nce of the licensed nuclear facilities. The American National Standards in this series are: ANSUANS-3.8.1-1995 - Criteria for Radiological Emergency Response Functions and Organizations ANSUANS-3.8.2-1995 - Criteria for Functional and Physical Characteristics of Radiological Emergency Response Facil
20、ities ANSUANS-3.8.3-1995 - Criteria for Radiological Emergency Response Plans and Implementing Procedures ANSUANS-3.8.4-1995 - Criteria for Maintaining Radiological Emergency Response Capability ANSUANS-3.8.5-1992 - Criteria for Emergency Radiological Field Monitoring, Sampling, and Analysis ANSUANS
21、-3.8.6-1995 - Criteria for Conduct of Offsite Radiological Assessment for Emergency Response for Nuclear Power Plants Working Group ANS-3.8 of the American Nuclear Society Standards Committee had the following members at the time this standard was processed and approved: C. K. Brown, Chairman, South
22、ern Nuclear D. M. Barss, U. S. Nuclear Regulatory A. R. Chesley, Vermont Yanhe Nuclear D. I. Fawcett, Assocbted Technical A. G. Grosjean, New York Power Authority J. J. Hawxhurst, Yankee Atomic Electric Company M. A. Hobe, Consumers Power Company S. F. LaVie, Duquesne Light Company E. E. M. Lloyd, E
23、XITECH Corporation E. J. Michael, Stone and Webster Engineering R. W. Myers, Myers “should“ to denote a recommendation; and “may“ to denote per- mission, neither a requirement nor a recom- mendation. thyroid blocking agent. A material intro- duced into the body that minimizes uptake of radioiodine i
24、nto the thyroid by saturating the thyroid with stable iodine. 3 . Emergency Response Functions This section specifies those functions necessary to support the plant operators effectively and respond to the needs of government agencies in protecting the health and safety of the general public during
25、an emergency. The licensee shall ensure that the functions described in this section are implemented, recognizing that some individuals are assigned two or more functions within their assigned responsibilities. Effective response to any emergency at a nuclear power plant requires the performance of
26、four basic functions: emergency manage- ment, plant operations, emergency assessment, and recommendations of protective actions. Support functions are identified to ensure that basic functions are adequately fulfilled. To ensure the performance of these basic and support functions, the radiological
27、emergency response plan (referred to hereinafter as the Plan) shall provide for augmentation of the on-shift staff of the plant by additional personnel. The appropriate activation of the emergency response organization is contingent upon the emergency conditions (i.e., which emergency class is in ef
28、fect) that occur and the resulting emergency functions. The number of personnel required to staff each Emergency Response Facility (ERF) shall be predeter- mined. This should be done by functional analysis. 2 COPYRIGHT American Nuclear Society (ANS) Licensed by Information Handling Services COPYRIGH
29、T American Nuclear Society (ANS) Licensed by Information Handling Services The minimum staffing of the emergency organization shall be documented to indicate the number of individuals assigned to each ERF. Table 1 indicates the relationship be- tween basic and support functions and the emergency cla
30、ssification level at which they may be required. Table 2 identifies the support functions which may be necessary to perform each basic function. Table 3 identifies the recommended ERF(s) where the support func- tions should be implemented. 3.1 Basic Functions. Four basic emergency response functions
31、 shall be performed inde- pendent of the emergency conditions and the emergency classification. These functions are: 3.1.1 Emergency Management. The ac- tions taken to maintain and coordinate re- quired human and physical resources available to the licensee in responding to an emergency. 3.1.2 Plant
32、 Operations. The actions taken or directed by licensed operators to mitigate the emergency, to stabilize the event, and to return to or maintain the plant in a safe condition. Plant operations shall be performed at all times to minimize the impact of the emergency on the public. 3.1.3 Emergency Asse
33、ssment. The evaluation of the past, present, and potential future physical plant status and external conditions. This assessment guides emergency response personnel in their efforts to mitigate the emergency and formulate protective action recommendations, 3.1.4 Recommendation of Protective Actions.
34、 The actions taken to determine or develop a Protective Action Recommendation (PAR) for the public and to communicate or provide the PAR to the responsible government or offsite agencies for implementation. 3.2 Support Functions. Support functions are those activities performed to ensure that the ba
35、sic functions can be adequately fulfilled. The extent to which the support functions are implemented is dependent upon the nature of the emergency and the emergency classification level. The plants Plan shall address the scope, responsibility, and facilities for each support American National Standa
36、rd ANSUANS-3.8.1- 1995 function. Implementation of support functions will depend upon organizational structure, and the size, design, and location of the plant. Requirements for each of the support functions are specified below: 3.2.1 Technical Support. Technical sup- port shall be provided to advis
37、e on the present status of the plant during the emergency and to predict possible future conditions. Guidance should be provided by these technical support personnel (e.g., licensing, nuclear steam supply system vendor, plant architectlengineer, Nu- clear Regulatory Commission, and licensee cor- por
38、ate engineering functions) to management and operations on mid- to long range de- cisionmaking for plant operations to mitigate the emergency, to stabilize the event, and to maintain or return the plant to a safe condition. 3.2.2 Communications. Communications support shall be provided to maintain c
39、ontrol of the emergency organization and to allow effec- tive communications among key individuals. American National Standard Criteria for Func- tional and Physical Characteristics of Radio- logical Emergency Response Facilities, ANSI/ ANS-3.8.2-1995 31, shall be evaluated for additional guidance i
40、n the design of a commu- nications system that meets the needs of the organization described in this document. 3.2.3 Notifications. Notification methods shall be established to support emergency management and to provide recommendations for protective actions. Equipment, personnel, and procedures sh
41、all be available to ensure that licensee and government emergency response organizations are properly activated and informed of changes in emergency classifications. 3.2.4 Data Distribution. Relevant plant and environmental data shall be provided on a timely basis to support the response effort. Sel
42、ected data shall be displayed and critical parameters shall be trended so that the plant status can be rapidly evaluated. 3.2.5 Administration and Logistics. Ap- propriate transportation, meals, accommoda- tions, purchasing, finance, insurance, legal 3 COPYRIGHT American Nuclear Society (ANS) Licens
43、ed by Information Handling Services COPYRIGHT American Nuclear Society (ANS) Licensed by Information Handling Services ANS 3.8.31 95 I 07248318 0202443.705 I American National Standard ANSUANS-3. 1-1995 Table 1 Function vs. Emergency Classification Functions NUE Alert Site Area General Emergency Eme
44、rgency Basic Functions: Emergency Management Plant Operations Emergency Assessment Recommendation of Protective Actions X X X X X X X X X X X X X Support Functions: Technical Support Communications Notifications Data Distribution X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X
45、X X X X X Administration radiation and contamination sur- veys; and airborne activity detection and as- sessment. Exposures shall be controlled as low as reasonably achievable (ALARA). This func- tion shall include actions to control the spread of contamination, provide decontamination of personnel
46、and vehicles, and support ambulance and medical personnel in the treatment of contaminated injured workers and their trans- portation to offsite medical facilities. 3.2.15 Radiological Assessment. A radio- logical assessment function shall be available to provide assessment and recommendations for a
47、ctions to protect personnel and to estimate onsite and offsite radiological impacts, taking into account current and forecast meteorology. 3.2.16 Core Physics and Thermal Hy- draulics. Reactor engineering and nuclear fuels expertise shall be available to analyze core parameters and to develop guidan
48、ce for plant operations personnel on protection of the core. This function shall include the ability to perform analyses of core parameters to deter- mine an assessment of core damage for consid- eration in PAR decisions. Proposed plant Oper- ations should be reviewed with respect to the effect on c
49、ore conditions, and recommendations should be developed for plant operations that would provide safer core conditions. 3.2.17 Chemical Analysis Support. Chemical analysis support shall be available to coordinate sampling and analysis of the reactor coolant, ventilation, and containment systems. This function should include the direction of the actual sampling and analysis work used to evaluate the mid- to long term actions to be taken for chemical addition, calculation of ra- dionuclide concentrations in the reactor coolant and containment, and estimation of core dam- 7 COPYRIGHT Americ
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