Regulatory Guide 1.101: Difference between revisions

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{{Adams
{{Adams
| number = ML13350A291
| number = ML13038A097
| issue date = 11/30/1975
| issue date = 10/31/1981
| title = Emergency Planning for Nuclear Power Plants.
| title = Emergency Planning and Preparedness for Nuclear Power Reactors
| author name =  
| author name =  
| author affiliation = NRC/OSD
| author affiliation = NRC/RES
| addressee name =  
| addressee name =  
| addressee affiliation =  
| addressee affiliation =  
Line 10: Line 10:
| license number =  
| license number =  
| contact person =  
| contact person =  
| document report number = RG-1.101
| document report number = RG-1.101, Rev. 2
| document type = Regulatory Guide
| document type = Regulatory Guide
| page count = 15
| page count = 2
}}
}}
{{#Wiki_filter:U.S. NUCLEAR REGULATORY  
{{#Wiki_filter:October 1981 Revision 2 U.S. NUCLEAR REGULATORY  
COMMISSION
COMMISSION
November 1975 REGULATORY  
.REGULATORY  
GUIDE OFFICE OF STANDARDS
GUIDE OFFICE OF NUCLEAR REGULATORY
DEVELOPMENT
RESEARCH REGULATORY  
REGULATORY  
GUIDE 1.101 EMERGENCY  
GUIDE 1.101 EMERGENCY  
PLANNING FOR NUCLEAR POWER PLANTS
PLANNING AND PREPAREDNESS
FOR NUCLEAR POWER REACTORS


==A. INTRODUCTION==
==A. INTRODUCTION==
create a high order of preparedness and ensure an orderly and timely decision-making process at times of Section 50.34, "Contents of Applications;
On August 19, 1980, the Commission published amend-ments to its regulations in 10 CFR Part 50, "Domestic Licensing of Production and Utilization Facilities," to upgrade its emergency planning requirements
Technical stress, as well as the availability of necessary equipment.
(45 FR 55402).Paragraph (a)(1) of § 50.47, "Emergency Plans," of 10 CFR Part 50 states that no operating license for a nuclear power reactor will be issued unless a finding is made by NRC that the state of onsite and offsite emergency prepared-ness provides reasonable assurance that adequate protective measures can and will be taken in the event of a radiological emergency.


* Information." of I0 CFR Part 50, "Licensing of supplies, and services.Production and Utilization Facilities," requires that each application for a license to operate a facility A iptt.. o planning for An imlportant element of emergency`,:'p.lanning fur include in a Final Safety Analysis Report (FSAR), along nuflear uwe ..... is t.. "m -with other information, thc applicant's plans for coping lrepare to cope with a ier" bya ti6onrum of potential pin, ... prpr tocp wtv v with emergencies.
For operating power reactors, paragraph (s)(2)of § 50.4 requires that the licensee, State, and local emer-gency response plans shall be implemented by April 1, 1981, except as provided in Section IV.D.3 of Appendix E to Part 50. If, after April 1, 1981, the NRC finds that the state of emergency preparedness does not provide reason-able assurance that adequate protective measures can and-"will be taken in the event of a radiological emergency, the Commission will determine whether the reactor must be shut down until such deficiencies are remedied or whether other enforcement action is appropriate.


including the itemns specified in consequences.
In both cases, the NRC will base its finding on a review of the Federal Emer-gency Management Agency (FEMA) findings and determina- tions as to whether State and local emergency plans are adequate and capable of being implemented, and on the NRC assessment as to whether the licensee's emergency plans are adequate and capable of being implemented.


Federal $tHIeý1`"aIdW5'Vagencics, as well Appendix E, "Emergency Plans for Production and as the licensee, have r ..l,'-ýes to play in both. t.e Utilization Facilities," to 10 CFR Part 50. Appendix E planning and the.
Section 50.47 also establishes standards that must be met by the onsite and offsite emergency response plans in order for the staff to make a positive finding that there is reasonable assurance that adequate protective measures can and will be taken in the event of a radiological emer-gency.This regulatory guide provides guidance to licensees and applicants on methods acceptable to the NRC staff for complying with the Commission's regulations for emer-gency response plans and preparedness at nuclear power reactors.


of emergency preo refers to a document entitled "Guide to the Preparation paredness procedif''s
==B. DISCUSSION==
'redcrfl interagenc y responsibili- of Emergency Plans for Production and Utilization ties for nuclear'lniAzc-t
Revision I to NUREG-0654/FEMA-REP-1, "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants," was published in November 1980 to provide specific acceptance criteria for complying with the standards set forth in § 50.47 of 10 CFR Part 50. These criteria provide a basis for NRC licensees and State and local governments to develop acceptable radiological emergency.
'pInning were set fortli by the Facilities,"'
which wa', developed to help applicants Of.c o, re. , r edness i a F.D. RA. R.G-*~~~~f ic .....
teparedness in a FDR=U.AL.


REGt.-establish adequate plans for coping with emergencies.
plans and improve emergency preparedness.


0STI ." F o I 36 us .January 24 .S" ST Knol; " 3a F,..I 2356) publishled January 24, 1973J.This regulatory guide provides more complete guidance To 9iii '- e these respn are diecedto* indeveloping emergency plans for nuclear power plants..r ,,ard ~et"Od nation of efforts to provide assistance to It describes a miethod acceptable to the NRC staff for r -01oc,' gove n i ip n.. Thi re-.. ... ., " a t coal governm ents in their planning.
NUREG-0654/
FEMA-REP-l is the product of the joint FEMA/NRC Steering Committee established to coordinate the agencies'work in emergency preparedness associated with nuclear power plants.The staff is not publishing this Revision 2 to Regulatory Guide 1.101 for public comment because of the unique developmental process used for NUREG-0654/FEMA-REP-l.


Th is complying with the Commission's regulations with -ased on the recognition that State and local gard to adequate content of emergency plans for nuel~t..,,-
The interim version of NUREG-0654/FEMA-REP-1 was published for interim use in January 1980, and public comment was invited in a notice published in the Federal Register on February 13, 1980 (44 FR 9768). Almost 100 comment letters were received, reviewed, and evaluated prior to the development of a final version of the document.The staff's evaluation of the comments is contained in NUREG-0742/FEMA-REP-4.
.,,...rtctne p f go nments have the necessary authority to implement power plants, primarily in the FSAR stage measures in their jurisdictions.


Although B '. DISCUSSION
The interim version was also reviewed by the Advisory Committee on Reactor Safeguards and, the Commission in the course of the rulemaking that resulted in the emergency preparedness amendments cited above. Comments were also received from the Interorgani- zational Advisory Committee (made up of State and local representatives)
',, 'ederal agencies can and will respond to emergencies
and from other State officials later at a September
"., arising from nuclear power plant activities if necessary, The Commission's interest in cergen jian g is :;uch response should be regarded primarily as supportive focused primarilyions intuaet ions teamergyn
1980 workshop sponsored by FEMA specifically to review and discuss the interim version of NUREG-0654/
.'-r may of, and not as a substitute for, responsible action by focused primarily on situations that may c ay licensees and State and local governments.
FEMA-REP-
1.Based on all the comments received, a final version of NUREG-0654/FEMA-REP-1 was published in November 1980 as Revision 1. Therefore, because this Revision 2 of Regulatory Guide 1.101 endorses Revision 1 of NUREG-0654/
FEMA-REP-1, the staff believes that a formal public com-ment period is not warranted.


threaten to cause radiological hazards affecting the health and safety of workers' ie public or resulting in damage to property.
USNRC REGULATORY
GUIDES Regulatory Guides are issued to describe and make available to the public methods acceptable to the NRC staff of implementing specific parts of the Commission's regulations, to delineate tech-niques used by the staff in evaluating specific problems or postu-lated accidents or to provide guidance to applicants.


Em nc I ns should be directed In the preparation or an emergency plan for a specific toward mitigating the con ni of emergencies and nuclear power plant, the applicant should be guided by should provide r ' le rance that appropriate the following criteria to clarify the scope, content, and measures can an, will talk to protect health and purpose of the document that describes the plan.safety and ,mag o property in the event of an emergency thd.oj u not practicable to develop a I. Although considered a part or the Final Safety completely iiled plan encompassing every conceiv- Analysis Report, the plan should be prepared as a able type of ,gency situation, advance planning can separate document.ICopies may be obtained by request to the U.S. Nuclear Rcgulatory Commission, Washington, D.C. 20555, Attention:
Regulatory Guides are no? substitutes for. regulations, and compliance with them is not required.
2. The plan should be an expression of the overall Director, Office of Nuclear Rcaclor Regulation. "concept of operation" that describes the essential USNRC REGULATORY
GUIDES Comments should be sent to the Secretary of the Commission.


U S Nuclear Rngulatoty Guides are issued to describe and minke available to the P Regular'e Commisson.
Methods and solutions different from those set out in the guides will be acceptable if they provide a basis for the findings requisite to the issuance or continuance of a permit or license by the Commission.


Washington.
This guide was issued after consideration of comments received from the public. Comments and suggestions for improvements in these guides are encouraged at all times, and guides will be revised, as aPoropriate, to accommodate comments and to reflect new informa-tior. Gr ?xnerience.


DC. 205%. Attention.
Comments should be sent to the Secretary of the Commission, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, Attention:
Docketing and Service Branch.The guides are issued in the following ten broad divisions:
1. Power Reactors 6. Products 2. Research and Test Reactors


OockSteng and methods acceptable to the NRC stalf of imptlernrtling specific Stce Section.Comamnssion's tequaltolt.
===7. Transportation===
3. Fuels and Materials Facilities
8. Occupational Health 4. Environmental and Siting 9. Antitrust and Financial Review 5. Materials and Plant Protection
10. General Copies of issued guides may be purchased at the current Government Printing Office price. A subscription service for future guides in spe-cific divisions is available through the Government Printing Office.Information on the subscription service and current GPO prices may be obtained by writing the U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, Attention:
Publications Sales Manager.


to delineate techntiques used be the stall in evalu "he guides ate issued in the following ten broad divisions atInq specil.c problenms a postulated accidents.
C. REGULATORY  
 
POSITION  
at to provide guidance to appl, cant" Regulatory Guides are not substitute%
for regulations.
 
and co,,opliance I Powet Reactors 6 Products with them is oit required Methnds and sotutions difterent from those %et out in 2 Research and Test Reactors 7 Transporitaton the guides wilt be a,c.eplthltt if they provide a basis tor the Indinga requisite to .3. Fuels and Matetials Factlities B. Occupational Health the~tsunefat, ton.tintidlit!OfA(Permit Of license by the Commnission..
.4. Environiental and Siting 9 Antitust Review Comn.rnt%
and %uqqentiaon lot improveaie.,lt It1 these guides ate encouraged r, Materials and Plant Protection
10 General at alt times. ad guides wlt rlr ,evised. an aptpropriate.
 
to accommodate cam.Imenit and to fellect new Inte- or elpaetir.nr.
 
However. cmrnments an Copies of published guides may be obtained by written request indicating the this guide, it ,ectved w-tlri ..t.. ut two ntnnths After its issuance.
 
will be par divisions dr.%tred to the U.S Nuclear Regulatoty Comnmlision, Washinglon.
 
D C.ltcularlt usetul it, ewdluahiJ
the on..d rot an eatly
20555, Attention Ditectot.
 
Otlice of Standards Development.
 
elements of advance planning that have been considered and the provisions that have been made to cope with emergency situations.
 
The plan should incorporate infor-mation about the emergency response roles of support-ing organizations and agencies.
 
That information should be sufficient tO enable a determination of the interface and coordination required among the supporting groups and between them and the licensee.3. Details that can reasonably be expected t, change froml time to time, 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, should not be incorporated into the plan.4. The plait should not, by itself, be considered a primary working document to be used during an emergency.
 
Detailed procedures that will ensure timely and effective implementation of various aspects of the emergency plan should be prepared.
 
These procedures, however, should not be incorporated into iie document.C. REGULATORY  
POSITION I. Each applicant's emergency plan should !iclude provisions for coping with emergencies, both within the boundary of the plant site and in the environs of the site. Responsibility for planning and implementing all emergency measures within the site boundaries rests with the licensee.
 
Planning and implementation of measures to cope with plant.related emergencies outside the site boundary should be a coordinated effort involving the licensee and local, county, State, and Federal agencies having emergency responsibilities.
 
The emergency plan should describe this coordination, that is. the arrangements and agreements between the licensee and these supporting agencies.2. The scope and content of a nuclear powei plant emergency plan should be substantially equivalent to that recommended in Annex A to this guide. "Organiza- tion and Content of Emmergency Plans for Nuclear Power Plants." Provision should be made for an annual review of the emlergency plan and for updating and improving procedures based on training, drills, and changes onsitc or in the environs.3. Features and candidate subjects that should be considered in the preparation of specific procedures for implementing the emergency plan are described in Annex B to this guide. "Implementing Procedures for E-mergency Plans." Implementing procedures should not be incorporated into the plan and are not required to he submi:ted as part of the Final Salety Analysis Report to the Commission.
 
These procedures should, however, be available for review by the Oflfice of Inspection and Enforcement during its prelicensing and routine inspec-tions.


==D. IMPLEMENTATION==
==D. IMPLEMENTATION==
The purpose of this seclion is to pi'ovide infoimation to applicants and licensees regarding the NRC staff's plans fot utilizing this regulatory guide.With the exception.
The criteria and recommendations contained in Revi-sion 1 of NUREG-0654/FEMA-REP-1 are considered by the NRC staff to be generally acceptable methods for com-plying with the standards in § 50.47 of 10 CFR Part 50 that must be met in onsite and off site emergency response plans. Furthermore, FEMA, NRC, and other involved Federal agencies intend to use the guidance contained in Revision 1 of NUREG-0654/FEMA-REP-l in their indi-vidual and joint reviews of the radiological emergency response plans and preparedness of State and local govern-ments and the plans and preparedness of applicants for and holders of a license to operate a nuclear power reactor.UNITED STATES NUCLEAR REGULATORY
COMMISSION
WASHINGTON, 0. C, 20555 OFFICIAL BUSINESS PENALTY FOR PRIVATE USE, $300 The purpose of this section is to provide information to applicants and licensees regarding the NRC staff's plans for using this regulatory guide. This guide reflects current NRC staff practice.


of Annex B, this guide reflects current Nuclear Regulatory Comttmissiot practice iLs outlined in the USNRC Standard Review Plan. Except in those cases in which the applicant proposes an accept-able alternative metlhod for complying with specified portions of the Comnmission's regulations, the method described in Annex A is being and will continue to be used in the evaluation of Final Safety Analysis Reports until this guide is revised as a result of suggestions fromn the public or additional staff" review.Annex B is being published now for comment and review; it may be revised as a result of suggestions from the public or additional staff review.1.101-2 ANNEX A ORGANIZATION
Except in those cases in which the applicant or licensee proposes acceptable alternative practices or methods for complying with specified portions of the Commission's regulations, the practices or methods described herein will be used as a basis for evaluating the adequacy of the emergency plans and preparedness of applicants for a license to operate a nuclear power reactor as well as the plans and preparedness at currently operating plants.POSTAGE AND FEES PAID U.S. NUCLEAR REGULATORY
AND CONTENT OF EMERGENCY
COMMISSION
PLANS FOR NUCLEAR POWER PLANTS I. DEFINITIONS
I -~1.101-2}}
This section should provide definitions of any terms (hat are unique to the power plant under consideration or are given conrotations that differ from normally ucceptcd usage. Listed below are some terms used in this guide along with the definitions that should be applied to these terms when they are used in emergency plans.I. Assessment actions -those actions taken during or after an accident which are collectively necessary to make decisions to implement specific emergency mea-Sures.2. Corrective actions -those emergency measures taken to ameliorate or terminate an emergency situation at or near the source of the problem.3. Protective actions -those ."mergency measures taken after an uncontrolled release of radioactive mate-rial has occurred for the purpose of preventing or minimizing radiological exposures to persons that would be likely to occur if the actions were not taken.4. Popula:ion at risk -those persons for whom protective actions are or would be taken.5. Affected persons -individuals who have been.radiologically exposed or physically injured as a result of an accident to a degree requiring special attention, e.g., decontamination, first aid, or medical services.6. Recovery actions -those actions taken after the eniergeney to restore the playi .ts nearly as possible to its preemergency condition.
 
7. Protective action guides -projected radiological dose or dose commitment values to individuals in the general population that warrant protective action follow-ing a release of radioactive material.8. Emergency action levels -radiological dose rates; specific contamination levels of airborne, water-borne, or surface-deposited concentrations of radio-activity;
or specific .instrument readings that may be used as thresholds for initiating specific emergency measures.2. SCOPE AND APPLICABILITY
This section of the plan should define the unit, plant, station, or area to which the plan is applicable and present a summary of the plan's interrelationships with (I) its implementing procedures, (2) plant operating, radiological control, and industrial security procedures, (3) other emergency plans of the company (e.g., an overall corporate plan I, and (4) emergency plans of other participating agencies, particularly the responsible State agency or other governmental authority having emergency planning responsibilitics in the immediate offsite area.3. SUMMARY OF EMERGENCY
PLAN This section should describe the key elements of overall emergency planning logic, incorporating graded emergency classifications of increasing severity and their relationship to the participating status of onsite and offsite personnel and agencies.
 
===4. EMERGENCY ===
CONDITIONS
4.1 Classification System An emergency plan should characterize several classes of emergency situations.
 
The system of classifica- tion employed should consist of mutually exclusive groupings (to avoid ambiguity)
but should cover the entire spectrum of possible situations.
 
Succinct verbal rather than numerical or alphabetical classification desig-nations are recommended to give better immediate information to personnel as to the scope and character of the situation.
 
The plan should describe the limiting scope consid-ered for each identified class of emergency, that is, the area and/or persons affected by the consequences.
 
The plan should also describe, for each class, the preliminary actions to be taken to cope with the situation, the authority or title of the individual responsible for initiating these actions, and the organizations and agencies that would be alerted and mobilized.
 
Specific implementing procedures slhuld be pre-pared for each identified class of emergency (see Annex B).An acceptable classification scheme is described in qualitative terms in Sections 4.1.1 through 4.1.5. This part of the emergency plan should describe the criteria for recognizing and declaring each class, including specific emergency action levels for the last three classes.4.1.1 Personnel Emergency This class involves accidents or occurrences onsite in which emergency treatment of one or more individuals is required.
 
It includes those situations that 1.101-3 ANNEX A ORGANIZATION
AND CONTENT OF EMERGENCY
PLANS FOR NUCLEAR POWER PLANTS I. DEFINITIONS
This section should provide definitions of any ternis that arc unique to the power plant under consideration or are given conr.otations that differ from normally accepted usage. Listed below are some terms used in this guide along with the definitions that should be applied to these lerms when they are used in emergency plans.I. Assessment actions -those actions taken during or after an accident which are collectively necessary to Make decisions to implement specific emergency mea-sures.2. Corrective actions -those emergency measures taken to ameliorate or terminate an emergency situation at or near the source of the problem.3. Protective actions -those ,'mergency measures taken after an uncontrolled release of radioactive mate-rial has occurred for the purpose of preventing or minimizing radiological exposures to persons that would be likely to occur if the actions were not taken.4. Popula:ion at risk -those persons for whom protective actions are or would be taken.5. Affected persons -individuals who have been radiologically exposed or physically injured as a result of an accident to a degree requiring special attention.
 
e.g., decontainination, first aid, or medical services.6. Recovery actions -tthose actions taken after the emergency to restore the pla!I i ,s nearly as possible to its preemergency condition.
 
7. Protective action guides -projected radiological dose or dose commitment values to individuals in the general population that warrant protective action follow-ing a release of radioactive material.8. Emergency action levels -radiological dose rates; specific contamination levels of. airborne, water-borne, or surface.deposited concentrations of radio-activity;
or specific instrument readings that may be used as thresholds for initiating specific emergency measures.2. SCOPE AND APPLICABILITY
This section of the plan should define the unit, plant, station, or area to which the plan is applicable and present a summary of the plan's interrelationships with (1) its implementing procedures, (2) plant operating, radiological control, and industrial security procedures, (3) other emergency plans of the company (e.g., an overall corporate plan), and (4) emergency plans of other participating agencies, particularly, the responsible State agency or other governmental authority having emergency planning responsibilities in the immediate offsite area.3. SUMMARY OF EMERGENCY
PLAN This section should describe the key elements of overall emergency planning logic, incorporating graded emergency classifications of increasing severity and their relationship to the participating status of onsite and offsite personnel and agencies.
 
===4. EMERGENCY ===
CONDITIONS
4.1 Classification System An emergency plan should characterize several classes of emergency situations.
 
The system of classifica- tion employed should consist of mutually exclusive groupings (to avoid ambiguity)
but should cover the entire spectrum of possible situations.
 
Succinct verbal rather than numerical or alphabetical classification desig-nations are recommended to give better immediate information to personnel as to the scope and character of the situation.
 
The plan should describe the limiting scope consid-ered for each identified class of emergency, that is, the area and/or persons affected by the consequences.
 
The plan should also describe, for each class, the preliminary actions to be taken to cope with the situation, the authority or title of the individual responsible for initiating these actions, and the organizations and agencies that would be alerted and mobilized.
 
Specific implementing procedures should be pre-pared for each identified class of emergency (see Annex B).An acceptable classification scheme is described in qualitative terms in Sections 4.1.1 through 4.1.5. This part of the emergency plan should describe the criteria for recognizing and declaring each class, including specific emergency action levels for the last three classes.4.1.1 Personnel Emergency This class involves accidents or occurrences onsite in which emergency treatment of one or more individuals is required.
 
It includes those situations that 1.101-3 have no potential for escalation to morc severe emer-gency conditions.
 
There may be no effect on thie plant, and immediate operator action to alter plant status is not necessarily required.
 
A Personnel Emergency does not activate the entire emergency organization but may activate such teams as thc first aid team. It may also require special local services such as ambulance and medical.hmplemcnting procedures for the handling of this class of' emergency may also be incorporated in the plant's radiation protection procedures and general industrial safety procedures.
 
Included in this class are injuries that may be complicated by contamination problems or excessive radiation exposures t) onsite personnel.
 
The recognition of this class of emergency is primarily a judgment matter for plant supervisory or management personnel.
 
Its importance as part of the classification scheme rests to some extent on its "nega-tive'" information content, viz, that the incident giving rise to the emergency is restricted in its scope of involvement.
 
This section of the plan should designate the classification criteria and should enumerate discrete accident situations that could give rise to this class.4.1.2 Emergency Alert This class involves specific situations that.can be recognized as creating a hazard potential that was previously nonexistent or latent. The situation has not yet caused damage to the plant or harm to personnel and does not, necessarily require an immediate change in plant operating status. Inherently, however, this is a situation in which time is available to take precautionary and constructive steps to prevent an accident and to mitigate the consequences should it occur. An Emer-gency Alert situation may be brought on by either man-made or natural phenomena.
 
Emergency Alert conditions imply a rapid transition to a state of readiness by the plant personnel, the possible cessation of certain routine functions or activities within the plant that are not immediately essential, and possible precautionary actions that a specific situation may require. Examples of situations that might be placed in this class are threats to or breaches of plant security measures such as bomb threats or civil disturbance, severe natural phenomena in the plant environment such as floods, earthquakes, tsunami, hurricanes, or tornadoes;
emergency situations such as fires at adjacent locations;
or release of a toxic or noxious gas in or near the plant. This section of the emergency plan should identify specific candidate situa-tions for Emergency Alerts and the quantitative criteria that would guide the decision to implement each.Qualitative criteria should he added for other candidate situations to guide the decisions of onsite supervisory personnel.
 
4.1.3 Plant (Unit) Emergency This class includes physical occurrences within the plant requiring full plant staff emergency organization response.
 
The initial information and assess-ment indicates that it is very unlikely that an offsitc hazard will be created. Hlowever, substantial modifica-tion of plant operating status is a highly probable corrective action if this has not already taken place by the actions of automatic protective systems. Although it is judged that the emergency situation can be corrected and controlled by the plant staff. nolification of corporate headquarters staff' to put them on an alert status is prudent. Notification of appropriate offsite agencies as to the nature and extent of the incident is also advisable.
 
Evacuation of the plant is not anticipated in this class of emergency, although protective evacua-tions or isolations of certain plant areas may be necessary.
 
Examples of situations that might fall into this class are those accidents analyzed in the FSAR as events that are predicted to have no radiological conse-quences offsite. Fires, explosions or explosive gas re-leases, or in-plant flooding conditions may fall into this class.Activation levels for declaring Plant Emergen-cies should be based on the recognition of an immediate need to implement in-plant emergency measures to protect or provide aid to affected persons in the plant or to mitigate the consequences of damage to plant equipment, coupled with a positive observation that (I)effluent and other radiological monitors do not indicate the possibility of a Site Emergency and (2) there is no apparent breach of any fuel cladding, primary system boundary, or containment.
 
This section should describe the alarm conditions or combinations of alarm condi-tions and the emergency action levels for initiating a Plant Emergency.
 
4.1.4 Site (Station)
Emergency This class involves an uncontrolled relcase of radioactive materials into the air, water, or ground to an extent that initial information and assessment indicate protective actions offsite may be desirable.
 
Mobilization and readiness of offsite emeigency organizations is prudent. Protective actions are likely to include evacua-tion of plant areas other than control rooms and emergency stations and should include the evacuation of construction personnel when additional units are under construction on the same site. Assessment actions will include monitoring of the environment.
 
101-4 IJ
MEM Situations likely to fall into this class include those accidents analyzed in the FSAR that are predicted to have small to moderate releases at the exclusion radius. It should be anticipated that Site Emergencies would not normally be preceded by a Plant Emergency, although the possibility of this evolution should not be excluded.Emergency action levels for declaring a Site Emergency should be defined in terms of instrument readings or alarms in the control room, including indications from effluent monitors.
 
To avoid false alarms or to minimize their frequency of occurrence, the levels may be defined so as to require corroborating evidence from two independent sources that provide input to the control room. Site Emergencies should also be declared on the basis of evidence of apparent breaches in fuel cladding, primary system bound4Wl,':, or containment.
 
The bases and criteria used to divf= the instrument alarm levels should be described.
 
Suitable criteria would be protective action guide values at a security fence, exclusion area, or site boundary, and the bases would show how the effluent monitor readings relate to such values. Federal agency guidance'
2 is available to assist in the selection of acceptable protective action guides.4.1.5 General Emergency This is an occurrence characterized by conse-quences lequiring that protective actions be taken in offsite areas as a matter of prudence or necessity.
 
Evacuation of the site may also be necessary under extreme circumstances.
 
Action levels for declaring the General Emer-gency case should be defined. The action levels should recognize bo.li short-term and long-term hazards. The selection of action levels for the former should be guided by direct radiation hazards and inhalation hazards that may be presented by the passage of a cloud of radioactive material released from the plant. The selec-tion of action levels for the long-term hazards should be guided by contamination hazards that could result from fallout or deposition of radioactive materials released from the plant.Protective actions should be planned and implemented at the prescribed action levels. Action levels for severe short-term situations requiring rapid implementation of protective actions should be defined in terms of readily available information such as readings of effluent monitors or other onsite monitor indications.
 
Implementation of protective actions may also be based on confirmatory measurements taken in the field to the extent it can be shown that field measurements can be"Background Material for the Development of Radiation Pro-tection Standards," Federal Radiation Council, Report No. 5, July 1964, and Report No. 7, May 1965.2"Emergency Response Protective Action Guides-Airborne Releases from Fixed Nuclear Facilities," Office of Radiation Programs, U.S. Environmental Protection Agency, January 1975.taken and evaluated rapidly enough to permit adequate time for the protective actions to be accomplished.
 
In either event, the bases and criteria used to define the action levels should be described in the plan.4.2 Spectrum of Postulated Accidents Accident analysis scclions of Safety Analysis Re-ports are primarily concerned with the dcsign responses of a plant to postulated malfunctions or equipment failure and include estimates of the radiological conse-quences of discrete accidents.
 
By contrast, emergency planning is concerned with individual and organizational responses to the continuum of potential accident situa-tions, including those discrete accidents that have been hypothesi7ied.
 
This section of the emergency plan should show that each postulated accident is encompassed within the emergency characterization classes and should provide a summary analysis of their implications for emergency planning.
 
Implications to be considered should :-'Jiude: I. Instrumentation capability for prompt detection and continued assessment, including functional applica-bility, range, response time, locations of sensing and readout elements (including alarms), and backup or redundant capability;
2. Manpower requirements for assessment, includ-ing recordkeeping;
for corrective actions- for protective actions, including communications requirements;
and for aid to affected persons; and 3. The timing of and the time required for the implementation of each emergency measure that may be brought into play.S. ORGANIZATIONAL
CONTROL OF EMERGEN-CIES Starting with the normal operating organization as a base, this section of the plan should describe the emergency organization that would be activated on the site and its augmentation and extension offsitc. Authori-ties and responsibilities of key individuals and groups should be delineated.
 
The communication links estab-lished for notifying, alerting, and mobilizing emergency personnel should be identified.
 
5.1 Normal Plant Organization Both day and night shift staffs (crews) should be described, indicating clearly who is in the immediate onsite position of responsibility for the plant or station (normally a shift supervisor)
and his authority and responsibility for declaring an emergency.
 
5.2 Onsite Emergency Organization This section should describe the mobilization billets of plant staff personnel for controlling each class of emergency for both day and night shift situations.
 
1.101-5
5.2.1 Direction and Coordination The' position title of utat person who is designated to take charge of onsite emergency control measures should be clearly identified.
 
A specific line of succession for this authority should also be given. A policy statement describing the scope of authority and responsibility vested in that role by the company (applicant)
should be included.
 
Functional responsibili- ties assigned to this individual should be described and should include a summary of those preliminary assess-ment procedures that would be followed to prescribe or guide his decision to classify and declare an emergency.
 
5.2.2 Plant Staff Emergency Assignments The plan should specify the iunctional areas of emergency activity to which members of the plant staff are assigned, including an indication of how the assignments are made for both day and night shifts and for plant staff members both onsite and away from the site. Functional areas should include: 1.. Plant systems operations, 2. Radiological survey and monitoring, 3. Firefighting, 4. Rescue operations, 5. First aid, 6. Decontamination, 7. Security of plant and access control, 8. Repair and damage control, 9. Personnel accountability, 10. Recordkeeping, 11. Communications.
 
5.3 Augmentation of Onsite Emergency Organization This section should describe two categories of offsite support assistance to the plant staff emergency organization.
 
These can be either directed, authorized, or requested by the company management to perform special emergency assistance functions.
 
5.3.1 Licensee Headquarters Support Headquarters management, administrative, and technical personnel should be prepared to augment the plant staff, both in emergency planning and in the performance of certain functions required to cope with an; emergency.
 
The following special functions are considered appropriate for headquarters support and should be incorporated in the overall plan, although company policy and organizational features may dictate variations in modes of assigning responsibilities for these functions among headquarters personnel, plant staff personnel, and outside support organizations:
I. Environs monitoring, 2. Logistics support for emergency person-nel, e.g., transportation, temporary quarters, food and water, sanitary facilities in the field, and special equip.ment and supplies procurement, 3. Technical support for planning and reentry/recovery operations, 4. Notification of governmental authorities, and 5. Public relations and information release, coordinated with governmental authorities, including steps taken to inform visitors to the plant, site, or information center and occupants in the environs of the site how the emergency plans provide for notification to them and how they can expect to be advised what to do.The emergency organization status of sup.porting headquarters personnel should be specified, relative particularly to the person directing the plant emergency organization.
 
In some instances, companies may provide for certain emergency supporting services to their plants by contracts with private organizations.
 
Where this is the case, the nature and scope of the support services should be characterized here. (The Commission may find it necessary to request evidence of the qualifications of such contractors.)
Specific services by contractors should be identified at the appropriate places in the emergency plan.5.3.2 Local Services Support This section should identify the extension of the organizational capability for handling emergencies to be provided by ambulance, medical, hospital, fire, and police organizations.
 
Evidence of the arrangements and agreements reached with such organizations should be included in an appendix.
 
This section should contain references to that appendix and to thio parts of the plan in which the functions of these *,rganizations are described.
 
5.4 Coordination with Participating Agencies This section should identify the principal State agency (designated state authority)
and other govern-mental agencies (local, county, State, and Federal)1.101-6 having planning or action responsibilities for emergen-cies, particularly for radiological emergencies, in the area in which the plant is located. If the boundary linec between two political chtilies, e.g., counties or states, passes within the low-population zone or within appioxi-mately fciir miles of the site, agencies from both governmental entities should bc included.
 
Subsections for each such agency should include: I. The identity of the agency.2. A summary of tlhe written agreement wiltl the agency that clearly defines the authority and icsponsi-bility of the agency for emergency preparedness plan-ning and for emergency response, particularly in relation to those of" the licensee and to those of other agencies.Copies of such agreements should be included in an appendix, along with a copy or summary of relevant parts of that agency's "minergency plan.3. Activation uf the agency function.
 
including titles and alternates for both ends of the communication links, and primary and alternative means of communica- lion.4. The designation and location of the Emergency Operations Center of each agency.5. Support of the agency function that may be provided by the company emergency organization, which may include (a) information on plant status, monitoring results, dose predictions, (b) recommenda- tions or requests for specific actions, and (c) logistics support.Typical agencies to be included here are law enforcement agencies not included above (e.g., State Police/Highway Patrol), departments of health or envi-ronmental protection, civil defense or emergency/
disaster control agencies, and the Regional Coordinating Offices of USERDA's Radiological Assistance Program.
 
===6. EMERGENCY ===
MEASURES Specific emergency measures should be identified in this section and related to action levels or criteria that specify when the measures are to be implemented.
 
They should be organized with respect to each emergency classification.
 
Preplanned action levels and criteria should be designed to assist and guide, or in some cases specify, the decision-making functions.
 
The planning represented by this section should lead to more detailed emergency procedures and assignments for executing tasks by appropriate members of the total emergency organization.
 
Emergency measures begin with the activation of an emergency class and its associated emergency organization.
 
The additional measures may be organized into assessment actions, corrective actions, protective actions, and aid to affected persons.6.1 Activation of Emergency Organization The emergency conditions classified in Section 4.1 involve the alerting or activation of progressively larger segments of the total emergency organization.
 
This section should describe how the necessary communica- lion steps are taken to alert or activate emergency personnel under each class of emergency.
 
including, in.particular, action levels for oolification of offsite agen-cies.6.2 Assessment Actions FEffective and direction of all elements of the emergency organization require continuing assess-ment throughout the duration of art emergency situa-lion. Assessinent functions should be incorporated in explicit p,,)cedures for each emergency classification.
 
They should be identified in this section and may include the following:
1. Surveillance of control room instruments and emergency control center, radiological and nmctcorolomri- cal monitors.2. Surveillance of containment integrity.
 
3. in.plant radiological surveys.4. Site and site boundary surveys.5. Environs surveys and monitoring.
 
a. Plume and other effluent surveillance for short-term assessment.
 
Planning should consider type of'data sought- instrument and equipment requirements:
Iransportation facilities for monitoring team (e.g.. air-craft, boats, other vehicles):
methods and accuracy of plume location:
and potential use of fixed offsite monitoring facilities.
 
b. Contamination surveillance.
 
Planning should consider the tinting, frequency, and types of samples to he collected, such as soil, vegetation, food, milk, and water supplies, and potential locations for reconcenira- lion, e.g., in air intake filters.6. Data reporting, reduction, and analysis.7. Interviewing of evacuees or other witnesses of the accident.8. Notification of assessment results for modifica-tion of emergency measures in progress, if necessary.
 
6.3 Corrective Actions Many emergency situations involve actions that can be taken to correct or mitigate the situation at or near the source of the problem. This section should identify 1.101-7 those actions, e.g., fire control,.
repair, and damage control, that would be implemented when necessary..
Emergency exposure criteria for personnel undertaking corrective actions should be included.d. The means and the time required to notify the persons involved and their expected response.These should include: (1) Adjacent businesses, property owners, and tenants, 6.4 Protective Actions This section should describe the nat:-j'e of protective actions that the plan contemplates, the emergency action. levels, the area involved, and the means of notification to the population at risk. Protective actions to be taken offsite by other agencies should be dc-scribed.6.4.1 Protective Cover, Evacuation, Personnel Ac-countability The emergency plan should provide for timely relocation of persons to prevent or minimize exposure to radioactivity.
 
The following items should be included: 1. Plant Site a. Action criteria.b. The means and the time required to notify persons involved.
 
These should include: (2) Nearby schools or recreational facilities, (3) General public in the environs.6.4.2 Use of Protective Equipment and Supplies Additional protective actions that should be considered in emergency planning include measures for minimizing the effects of radiological exposures or contamination problems by the distribution of special equipment or supplies.
 
Measures that should be consid-ered include: I. Individual respiratory protection.
 
2. Use of protective clothing.3. Use of radioprotective drugs, e.g., indi-vidual thyroid protection.
 
For each measure that might be used, a description should be given of: 1. Criteria for issuance, 2. Locations of items, and 3. Means of distribution to onsite and offsite assignments, (1) Employees not having emergency (2) Working and nonworking visitors, (3) Contractor and construction per-sonnel.persons.c. Control of public access areas on or passing through the site or within the exclusion area.d. Evacuation routes, transportation of personnel, and reassembly areas, including alternatives for inclement weather and high traffic density.e. Missing persons check.f. Radiological monitoring of evacuees.6.4.3 Contamination Control Measures Provisions should be made for preventing or minimizing exposure to radioactive materials.
 
Control of in-plant contamination should be described in specific radiological protection procedures and need not be repeated here. Measures for the protection of offsite persons and onsite persons outside of fenced security areas should include: 9. Offsite Areas 1. Isolation or quarantine and area access control.a. Action criteria, including inclement weather alternatives.
 
organization.
 
b. Responsibilities of company emergency c. Agency responsibilities.
 
2. Control of the distribution of affected commercial agricultural products.3. Control of public water supplies.4. Means for providing advisory information regarding the use of potentially affected home food and water supplies.1.101-8
5. Criteria fur permitting return to normal use.Action levels and responsibility for execution of each mcasure contemplated should be described.
 
6.S Aid to Affected Personnel This section of the emergency plan should describe measures thai will be used to provide necessary assist-ancc to persons injured or exposed to radioactivity.
 
The following mat lers should bc included: 6.5.1 Emergency Personnel Exposure Criteria This should specify exposure limits for entry or reentry to areas to remove injured persons and limits for emergency personnel who may provide first aid, decontamination, ambulance, or medical treatment serv.ices to injured persons. An individual or authority should be designated it) autlhorize or approve the acceptancc of emergency radiation exposure for life-saving purpo,:es.
 
6.5.2 Decontamination and First Aid Capabilities for dccontaminating personnel for their own protection and to prevent or minimize fuirther spread of contamination should be included.along with a brief description of first aid training and capabilities of appropriate members of the emergency organization.
 
6.5.3 Medical Transportation Arrangements for transporting injured person-nel, who may also be radiologically contaminated, to medical treatment facilities should be specified.
 
6.5.4 Medical Treatment Arrangements made for local and backup hospital atid medical services and the capability for the evaluation of radiation exposure and uptake should be described.
 
For both hospital and medical services, the plan should incorporate assurance not only that the required services are available, but also that persons providing them are prepared and qualified to handle radiological emergencies.
 
Written agreements with re-spect to arrangements made by the applicant, which should be included in the appendix.
 
would facilitate this determination.
 
===7. EMERGENCY ===
FACILITIES
AND EQUIPMENT This section of the emergency plan should identify, describe briefly, and give the locations of the items identified below. Where appropriate, references may be made to applicable.
 
sections of the Safety Analysis Report for additional oetail.7.1 Emergency Control Centers This should include the principal and, if provided for, alternative onsite locations from which effective emergency control direction is given, One alternative offsite location under the jurisdiction of the applicant should also be de:cribed.
 
Their locations should be related to the reactors, prevailing wind direction, and evacuation routes.7.2 Communications Systems This should give brief descriptions of both oisite and offsitc communications systems, including redun-dant power sources that would be required to perform vital functions in transmitting and receiving information throughout the course of an emergency.
 
7.3 Assessment Facilities Many of the emergency measures described in Section 6 wiil depend on the availability of monitori;ig instruments and laboratory facilities.
 
This section should list monitoring systems that are to be used to initiate emergency measures, as well as those to be used for continuing assessment.
 
The listing should be organized as follows: 7.3.1 Onsite Systems and Equipment 1. Natural phenomena monitors, e.g.. mete-orological, hydrologic, seismic.2. Radiological monitors, e.g.. process. area.emergency, effluent, and portable monitors and sam-pling equipment.
 
3. Nonradiological monitors, e.g., reactor coolant system pressure and temperature.
 
containment pressure and temperature, liquid levels, flow rates, status or lineup of equipment components.
 
4. Fire detection devices.7.3.2 Facilities and Equipment for Offsite Monitor-ing I. Natural phenomena monitors.2. Radiological monitors.3. Laboratory facilities, fixed and mobile.I0 1.101-9
7.4 Protective Facilities
.8.1.2 Drills* Specific facilities that are intended to serve a protective function should bedcscribed with emphasis on those features of each facility that ensure its"j adequacy with respect to capacity for accommodating the number of. persons expected and with respect to shielding, ventilation, and inventory of supplies.
 
Such facilities might include fallout shelters or similar areas and reassembly points. If design details have been provided elsewhere in the Safety Analysis Report, only a brief summary need be given here, along with a reference to the detailed information.
 
7.5 First Aid and Medical Facilities A summary description of onsite facilities should be provided. (Offsite medical facilities should be described in the appendix, along with the agreements providing for their use.)*
 
===8. MAINTAINING ===
EMERGENCY
PREPAREDNESS
This section of the plan should describe the means to be employed to ensure that the plan will continuc to be effective throughout the lifetime of the nuclear facility.8.1 Organizational Preparedness
8.1.1 Training This should include a description of periodic training programs to be given to all categories of emergency personnel.
 
Specialized training for the follow-ing categories should be included: I. Directors or coordinators of the plant emergency.
 
organization.
 
2. Personnel responsible for accident assess-ment, including control room shift personnel.
 
3. Radiological monitoring teams.Periodic (at least annual) announced drills should be incorporated in the emergency plan. These should be preplanncd simulations of accidents to test the adequacy of tinting and content of specific implement- ing procedures and to test cmergency equipment.
 
Ar--angem...1ts should be made for critiques of the drills.Coordinating drills should be held with participating agencies at least annually;
as a mininimum, the communi-cations links and notificafion procedures with those agencies should be tested. An initial coordinated drill with participating agencies should be planned and carried out prior to fuel loading of the first unit at'any site.8.2 Review and Updating of the Plan and Procedures Provision should be made for aai annual review of tile emergency plan and for updating and improving procedures to incorporate results of training and drills and to account for changes onsite or in the environs.Means for maintaining all coordinate elements of the total emergency organization informed of revisions to the plan or relevant procedures should be described.
 
8.3 Emergency Equipment and Supplies The operational readiness of all items of emergency equipment and supplies should be ensured. The plans and schedules for performing maintenance, surveillance testing, and inventory on emergency equipment and supplies should be described.
 
9. RECOVERY This section should describe general plans, including applicable criteria, for restoring the plant as nearly as may be possible to its preemergcncy status.10. APPENDIX The appendix should include the following items: 1. Copies of agency agreement letters and copies or summaries of interfacing emergency plans.2. Plots of calculated time.distance.dose for the most serious design basis accident.
 
as called for in the latest revision of Regulatory Guide 1.70, "Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants." 3. Listings, by title, of written procedures that implement the plan.4. Listings, by general category, of emergency kits, protective equipment, and supplies that are stored and 4. Fire control and repair and damage con.trol teams.5. First aid and rescue team members.6. Local services personnel.
 
7. Medical support personnel.
 
8. Licensee's headquarters support personnel.
 
1.101-10
maintained for emergency purposes.
 
A detailed catalog of individual items should not be included in the plan.The written procedures themselves and a detailed catalog of protective equipment and supplies should be available at the plant site for inspection at any time by a representative of the Commission's Office of Inspection and Enforcement.
 
1.101-11 ANNEX B IMPLEMENTING
PROCEDURES
FOR EMERGENCY
PLANS.This annex provides guidance regarding the prepa tion and content of procedures that implement t emergency plan.1. CONTENT AND FORMAT OF PROCEDURES
This section describes desirable features that shot be incorporated, where appropriate, into individt implementing procedures.
 
1.1 Organization and Responsibilities Wherever appropriate, each procedure shot specify the individual or organizational element havi the authority and responsibility for performing speci critical tasks covered by the procedure.
 
1.2 Action Levels Emergency action levels and protective actii guides should be specified in procedures, along with t emcrgency actions or protective actions required and t individuals or organizational units responsible for thi implementation.
 
1.3 Actions by Support Agencies The specific actions to be performed by suppt groups should .be identified in the procedures deali with their activities.
 
If the emergency actions perform by these groups require coordination with other e ments of the emergency organization, the particulars a requirements of this coordination should be specified the controlling procedure.
 
1.4 Procedure Format A rigid format for implementing procedures is n suggested in this guide. An acceptable format shot display the action steps so the user of the procedure c clearly understand his duties. The format of procedu!that specify immediate actions to be taken has spec significance because the user needs brief and expli instructions that can be followed easily and quickly.1.4.1 Title and Purpose Eacth procedure should have a title that descriptive of its purpose. The purpose of the procedt should be stated separately, however, if the title is r sufficiently descriptive.
 
1.4.2 Conditions and Prerequisites Each procedure should specify the prereq sites and conditions that should exist before the spe ra- fled actions or operations are performed.
 
These should he be in the form of action levels or protective action guides.1.4.3 Actions and Limitations ild Procedures should present the required jal actions in a succinct and concise manner and in step-by-step order and logical sequence.
 
The instructions should be sufficiently detailed for a qualified individual to perform the required actions without supervision but need not provide a completely detailed description of ild the actions, methods, or processes.
 
ng fic If the user is given the latitude to exercise judgment in implementing specific actions or parts of the procedure, guidelines should be provided in the procedure to aid the user in making decisions.
 
on 1.4.4 Cautions and Precautions he he Important steps or precautions should be eir noted or highlighted within the procedure.
 
1.4.5 References When procedural steps require other func-)rt tions or jobs to be performed, the controlling procedure ng should contain the reference to other applicable proce-ed dures.le-nd 1.4.6 Signoff Sheets and Checklists in Complex or lengthy controlling procedures should have provisions for signoff sheets or checklists to document the fact that required actions havy been taken or have been completed.
 
Examples include notification iot call lists and personnel accountability checks.mid an res 2. SCOPE OF IMPLEMENTING
PROCEDURES
ial cit 2.1 Immediate Action Procedures There should be a separate procedure for each identified class of emergency to specify and implement is the preplanned response actions required for that emer-ire gency condition.
 
Each procedure should (I) clearly lot identify the action level, the protective action guide, or the conditions for declaring the emergency condition, (2) list the individuals and elements of the emergency organization that are to be notified and mobilized, and (3) specify the emergency actions that are to be taken ui- by designated individuals and elements of the emergency'ci- organization.
 
1.101-12
2.2 Emergency Action Procedures The following sections list subjects that should be covered by written procedures.
 
The titles (f specific procedures, as well as their contents, may vary among licensees, but the actions or subjects described below should be covered within the group of procedures that implement the emergency plan.2.2.1 Notifications Call lists to alert and mobilize the emergency organization and. supporting agencies should be specified for each identified class of emergency.
 
If call lists are not too lengthy or complex, they should be incorporated into the immediate action procedure.
 
2.2.2 Radiological Surveys Procedures should specify the methods, and preplanned locations if feasible, for emergency radio-logical surveys in the plant and in the environs of the plant. The rocedures should include or refer to require-ments for 'oviding collected data and information to the individual or organizational element responsible for emergency assessment functions.
 
2.2.3 Personnel Monitoring and Decontamination The procedures should require monitoring of individuals leaving restricted areas or other areas known or suspected to be contaminated.
 
The procedures should specify contamination levels that require decontamina- tion actions. They should also include or refer to decontamination procedures for various types and levels of radioactive contamination.
 
2.2.4 Evacuation of Oasite Areas Procedures for evacuation should include the action levels that require evacuation of specified areas, buildings, and the site. Primary and secondary evacua-tion routes and assembly areas should be designated.
 
These procedures should be related to or refer to those procedures for personnel accountability and personnel monitoring.
 
2.2.5 Personnel Accountability A method of personnel accountability should be specified in procedures to ensure that, at all times, all individuals within the site confines and areas and buildings within the site are warned of imminent threats or hazardous conditions and evacuated from affected areas if required.The procedures should designate individuals having the responsibility of accounting for persons within areas and buildings within the site. The proce-dures should contain appropriate checksheets and sign-offs and should provide for reporting of information to the central authority in charge of the emergency response actions.2.2.6 Asse.,sment Actions Procedures should describe the system for gathering information and data on which to base decisions to escalate or deescalate emergency response actions. They should identify the types and sources of information available such as control room radiological and meteorological instruments and radiation and con-tamination levels as defined by in-plant, site boundary, and onsite and offsitr. surveys The procedures should specify action levels, protective action guides, and other guidelines as a basis for decisions to initiate emergency measures and actions or to terminate or otherwise modify emergency actions in progress.
 
The procedures should assign responsibilities for gathering and using assessment data and information.
 
2.2.7 First Aid and Medical Care The procedures that specify the methods and instructions for receiving, transporting, handling, and: providing medical treatment of injured persons should specifically include the prezautions and special handling required for contaminated paticnts.
 
The proce-dures should cover separately the provisions for, and use of, medical treatment facilities in both onsite and offsite areas.2.2.8 Firefighting The procedures should cover precautions for fighting fires involving radioactive materials and for situations where firefighters may otherwise be exposed to radiation.
 
They should cover the responsibilities and capabilities of both' in-house and offsite firefigh!ing teams and equipment.
 
They should include specific instructions for monitoring the exposure to radiation of offsite personnel involved in firefighting.
 
2.2.9 Reentry Procedures and guidelines should be devel-oped for reentry to previously evacuated areas for the purposes of saving lives, search and rescue of missing and injured persons, or manipulation, repair, or recovery of critical equipment or systems. Specific guidelines should be included in these procedures for maximum emer-gency radiation exposures for reentry and rescue person-nel. The procedures should designate the individual or authority having the responsibility for approving the voluntary acceptance of emergency exposures.
 
1.101-13
2.2.10 Plant Security 2.3.3 Equipment and Instrumentation The normal plant security proceduwes should powidC f'o security and access control during emergency co il d ior ls.2.2.1 Recovery Actioln lovels .autd guidClines should be devel-op.d I'M restoring operations and propierty as nearly as possible to their preenmergency status. The less complex tpcr:ations such as personnel enlergencics and emergency al-ius should require only brief recovery action proce-dures. The more complex emergency operations, how-ever I(site .and geoeral emergencies I'or eample). will gene.rally require !urrvspondingly conmphlex recovery:ictions.
 
It is not practicable to plan detailed recovery actL ionS for all conceivable situations, but procedures that include at least the initial planning considerations fOr recovering.
 
repairing, de,:ontaininating.
 
etc. poten-tiaily affIected portions of the facility should be devel-During recovery operations, personnel cx-posures to radiation should be maintained within 10 C(FR Part 20 limits.2.3 Supplemental Procedures This section lists subjects for procedures that supplement those covering emergency resl'onse actions.rhc specific titles and contents may vary, but the described subjects should be covered in the licensee's proccedural system.2.3.1 Communications Procedures should be available for activating, operating.
 
testing, and maintaining the emergency com-umnlications svsye ins.2.3.2 Documentation and Records Procedures should include requirements for iecording the implementation and completion or termi-nation of emergency response actions, logging assess-nenl data, reports of personnel accountability, and maintenance of required ;ecords and log.Operating instructions for equipment and ins!rumentation should be prepared and stored with the equipment.
 
Procedures should include inventory lists of kits, equmipment, and ittstrumnents and provisions ftor periodic inventory, inspection, calibration, and nainlten-arict.2.3.4 Training The training program for thec cnergency organization should be documented in the form of schedules and lesson plans or lesson outlines.
 
The program should include training for licensee employees and for offsite organizations and personnel who are to provide support in the emergency response.2.3.5 Tests and Drills Procedures should provide for practice drills to test the state of preparedness of the emergency organization.
 
The procedures should include guidance for the development oft detailed scenarios to test both specific procedures and implementation of the major aspects of the emergency plan. The scenarios should be preplanned simulations of emergency situations, arid they should be approved by plant management after they have been reviewed for scope and adequacy.The procedures should consider t(le utility of testing on both an announced and unannounced basis.They should require the use of an observer staff during tie conduct of test drills and should contain provisions for appropriate checklists or critique sheets to be used by the observer staff.The procedur6s for practice drills should include coordinatiun with offsite support organizations.
 
Communications drills with support organizations are sufficient to test the licensee's notification procedures.
 
3. REVIEW AND APPROVAL OF PROCEDURES
The procedural system used by licensees should contain written rules and instructions- governing the writing, revising, and updating of implementing proce-dures. The instructions should specify the methods to be used to ensure that procedures, revisions, and changes are reviewed for adequacy, approved for use, and distributed to user organizations and individuals having the responsibility for implementing the procedures.
 
@1 S 1.101-14}}


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Revision as of 21:14, 17 September 2018

Emergency Planning and Preparedness for Nuclear Power Reactors
ML13038A097
Person / Time
Issue date: 10/31/1981
From:
Office of Nuclear Regulatory Research
To:
References
RG-1.101, Rev. 2
Download: ML13038A097 (2)
v • d • e


October 1981 Revision 2 U.S. NUCLEAR REGULATORY

COMMISSION

.REGULATORY

GUIDE OFFICE OF NUCLEAR REGULATORY

RESEARCH REGULATORY

GUIDE 1.101 EMERGENCY

PLANNING AND PREPAREDNESS

FOR NUCLEAR POWER REACTORS

A. INTRODUCTION

On August 19, 1980, the Commission published amend-ments to its regulations in 10 CFR Part 50, "Domestic Licensing of Production and Utilization Facilities," to upgrade its emergency planning requirements

(45 FR 55402).Paragraph (a)(1) of § 50.47, "Emergency Plans," of 10 CFR Part 50 states that no operating license for a nuclear power reactor will be issued unless a finding is made by NRC that the state of onsite and offsite emergency prepared-ness provides reasonable assurance that adequate protective measures can and will be taken in the event of a radiological emergency.

For operating power reactors, paragraph (s)(2)of § 50.4 requires that the licensee, State, and local emer-gency response plans shall be implemented by April 1, 1981, except as provided in Section IV.D.3 of Appendix E to Part 50. If, after April 1, 1981, the NRC finds that the state of emergency preparedness does not provide reason-able assurance that adequate protective measures can and-"will be taken in the event of a radiological emergency, the Commission will determine whether the reactor must be shut down until such deficiencies are remedied or whether other enforcement action is appropriate.

In both cases, the NRC will base its finding on a review of the Federal Emer-gency Management Agency (FEMA) findings and determina- tions as to whether State and local emergency plans are adequate and capable of being implemented, and on the NRC assessment as to whether the licensee's emergency plans are adequate and capable of being implemented.

Section 50.47 also establishes standards that must be met by the onsite and offsite emergency response plans in order for the staff to make a positive finding that there is reasonable assurance that adequate protective measures can and will be taken in the event of a radiological emer-gency.This regulatory guide provides guidance to licensees and applicants on methods acceptable to the NRC staff for complying with the Commission's regulations for emer-gency response plans and preparedness at nuclear power reactors.

B. DISCUSSION

Revision I to NUREG-0654/FEMA-REP-1, "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants," was published in November 1980 to provide specific acceptance criteria for complying with the standards set forth in § 50.47 of 10 CFR Part 50. These criteria provide a basis for NRC licensees and State and local governments to develop acceptable radiological emergency.

plans and improve emergency preparedness.

NUREG-0654/

FEMA-REP-l is the product of the joint FEMA/NRC Steering Committee established to coordinate the agencies'work in emergency preparedness associated with nuclear power plants.The staff is not publishing this Revision 2 to Regulatory Guide 1.101 for public comment because of the unique developmental process used for NUREG-0654/FEMA-REP-l.

The interim version of NUREG-0654/FEMA-REP-1 was published for interim use in January 1980, and public comment was invited in a notice published in the Federal Register on February 13, 1980 (44 FR 9768). Almost 100 comment letters were received, reviewed, and evaluated prior to the development of a final version of the document.The staff's evaluation of the comments is contained in NUREG-0742/FEMA-REP-4.

The interim version was also reviewed by the Advisory Committee on Reactor Safeguards and, the Commission in the course of the rulemaking that resulted in the emergency preparedness amendments cited above. Comments were also received from the Interorgani- zational Advisory Committee (made up of State and local representatives)

and from other State officials later at a September

1980 workshop sponsored by FEMA specifically to review and discuss the interim version of NUREG-0654/

FEMA-REP-

1.Based on all the comments received, a final version of NUREG-0654/FEMA-REP-1 was published in November 1980 as Revision 1. Therefore, because this Revision 2 of Regulatory Guide 1.101 endorses Revision 1 of NUREG-0654/

FEMA-REP-1, the staff believes that a formal public com-ment period is not warranted.

USNRC REGULATORY

GUIDES Regulatory Guides are issued to describe and make available to the public methods acceptable to the NRC staff of implementing specific parts of the Commission's regulations, to delineate tech-niques used by the staff in evaluating specific problems or postu-lated accidents or to provide guidance to applicants.

Regulatory Guides are no? substitutes for. regulations, and compliance with them is not required.

Methods and solutions different from those set out in the guides will be acceptable if they provide a basis for the findings requisite to the issuance or continuance of a permit or license by the Commission.

This guide was issued after consideration of comments received from the public. Comments and suggestions for improvements in these guides are encouraged at all times, and guides will be revised, as aPoropriate, to accommodate comments and to reflect new informa-tior. Gr ?xnerience.

Comments should be sent to the Secretary of the Commission, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, Attention:

Docketing and Service Branch.The guides are issued in the following ten broad divisions:

1. Power Reactors 6. Products 2. Research and Test Reactors

7. Transportation

3. Fuels and Materials Facilities

8. Occupational Health 4. Environmental and Siting 9. Antitrust and Financial Review 5. Materials and Plant Protection

10. General Copies of issued guides may be purchased at the current Government Printing Office price. A subscription service for future guides in spe-cific divisions is available through the Government Printing Office.Information on the subscription service and current GPO prices may be obtained by writing the U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, Attention:

Publications Sales Manager.

C. REGULATORY

POSITION

D. IMPLEMENTATION

The criteria and recommendations contained in Revi-sion 1 of NUREG-0654/FEMA-REP-1 are considered by the NRC staff to be generally acceptable methods for com-plying with the standards in § 50.47 of 10 CFR Part 50 that must be met in onsite and off site emergency response plans. Furthermore, FEMA, NRC, and other involved Federal agencies intend to use the guidance contained in Revision 1 of NUREG-0654/FEMA-REP-l in their indi-vidual and joint reviews of the radiological emergency response plans and preparedness of State and local govern-ments and the plans and preparedness of applicants for and holders of a license to operate a nuclear power reactor.UNITED STATES NUCLEAR REGULATORY

COMMISSION

WASHINGTON, 0. C, 20555 OFFICIAL BUSINESS PENALTY FOR PRIVATE USE, $300 The purpose of this section is to provide information to applicants and licensees regarding the NRC staff's plans for using this regulatory guide. This guide reflects current NRC staff practice.

Except in those cases in which the applicant or licensee proposes acceptable alternative practices or methods for complying with specified portions of the Commission's regulations, the practices or methods described herein will be used as a basis for evaluating the adequacy of the emergency plans and preparedness of applicants for a license to operate a nuclear power reactor as well as the plans and preparedness at currently operating plants.POSTAGE AND FEES PAID U.S. NUCLEAR REGULATORY

COMMISSION

I -~1.101-2


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