ML20030B723

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Standard Format and Content for Radiological Contingency Plans for Fuel Cycle and Materials Facilities
ML20030B723
Person / Time
Issue date: 07/31/1981
From:
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
References
NUREG-0762, NUREG-762, NUDOCS 8108240044
Download: ML20030B723 (30)
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Text

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NUREG-0762 . L _ _ -- - = Standard Format and Content for Radiological Contingency P ans for Fuel Cycle and Materials Facilities f Manuscript Completed: January 1981 Date Published: July 1981 Division of Fuel Cycle and Material Safety Office of Nuclear Material Safety and Safeguards U.S. Nuclear Reguin'ory Commission W1.shington, D.C. 20555 g,o ste, e ~~ i 5 I

trsu o w (b TABLE OF CONTENTS ? Page jss INTRODUCTION..................................................... iii

1. 0 GENERAL DESCRIPTION OF THE PLANT / LICENSED ACTIVITY..........

1-1 n h[ 1.1 Licensed Activity Description.......................... 1-1 1.2 Site and Facility Description.......................... 1-1 1.3 Process Description............................ 1-2 2.0 ENGINEERED PROVISIONS FOR ABNORMAL OPERATIONS............. 2-1 2.1 Criteria for Accommodation of Abnormal Operations...... 2-1 2.1.1 Process Sy3tems.......................... 2-1 2.1.2 Alarm Systems and Release Prevention.. 2-1 2.1. 3 Support Systems................ 2-1 2.1.4 Control Operations................... 2-2 l 2.2 Demonstration of Engineered Provisions for l Ab no rma l Ope ra ci o n.................................... 2-2 2.2.1 Process Systems............................. 2-2 2.2.2 Alarm Systems and Release Prevention Capability. 2-2 2.2.3 Support Systems.............................. 2-2 2.2.4 Control Operations.............................. 2-2 3.0 CLASSES OF RADIOLOGICli CONTINGENCIES..... 3-1 3.1 Classification System............ 3-1 3.2 Recommended Classification Scheme........ 3-2 3.3 Range of Postulated Accidents.......................... 3-6 4.0 ORGANIZATION FOR CONTROL OF RADIOLOGICAL CONTINGENCIES...... 4-1 4.1 Normal Plant Organization.................. 4-1 4.2 Onsite Radiological Contingency Response Organization.. 4-1 4.2.1 Direction and Coordination........... 4-1 4.2.2 Plant Staff Radiological Contingency Assignments 4-1 4.3 Offsite Assistance to Facility......................... 4-2 4.4 Coordination with Participating Government Agencies.... 4-2 5.0 RADIOLOGICAL CONTINGENCY MEASURES......................... 5-1 5.1 Activation of Radiological Contingency Response Organization................................. 5-1 l i l

i i TABLE OF CONTENTS (Continued) Page 5.2 Assessment Actions..................................... 5-1 5.3 Corrective Actions.................... 5-1 5.4 Protective Actions..................................... 5-1 5.4.1 Personnel Evacuation from Site and Accountability.................................. 5-1 5.4.2 Use of Protective Equipment and Supplies........ 5-2 5.4.3 Contamina'.!on Control Measures.................. 5-2 5.5 Exposure Control in Radiological Contingencies......... 5-2 5.5.1 Emergency Exposure Control Program.............. 5-2 5.5.2 Decontamination of Personnel.................... 5-3 5.6 Medical Transportation................................. 5-3 5.7 Medical Treatment....................... 5-4 6.0 EQUIPMENT AND FACILITIES............................. 6-1 6.1 Control Point...................................... 6-1 6.2 Communicc tions Equipment............................. 6-1 6.3 Facility for Assessment Teams........................ 6-1 6.4 Onsite Medical Facilities.............................. 6-1 6.5 Emergency Monitoring Equipment............ 6-1

7. 0 MAINTENANCE OF RADIOLOGICAL CONTINGENCY PREPAREDNESS CAPABILITY....................

7-1 7.1 Written Procedures..................................... 7-1 7.2 Tre.ining............................... 7-1 7.3 Tests and Dri11s....................................... 7-1 7.4 Review and Updating of the Plan and Procedures......... 7-1 7.5 Maintenance and Inventory of Radiological Emergency Equipment, Instrumentation, and Supplies............... 7-1 8.0 RECORDS AND REP 0RTS.......................... 8-1 8.1 Records of Incidents................................... S-1 8.2 Records of Preparedness Assurance..................... 8-1 8.3 Reporting Arrangements................................. 8-1 9.0 REC 0VERY................. 9-1 9.1 Reentry........................................ 9-1 9.2 Plant Restoration...................................... 9-1 9.3 Resumption o f Operations............................. 9-1 ii

INTRODUCTION NRC has initiated an extensive program to reevaluate and upgrade the j requirements for emergency prepareoness planning of its fuel cycle and ma o In advance of that comprehensive regulatory program f i to which includes rulemaking, a pressing need is believed by the Commiss on materials licensees. promptly require radiological contingency planning of those licensed fue I cycle and major materials facilities exhibiting the potential for anidents (i) offsite radiation doses exceeding 1 rem to the d s whole body, 5 rems to the thyroid, or 3 rems to to other which could result in: i tially serious radiation overexposures of workers from a nuclear critical tyR incident or release of radioactive materials. Guides whole body and 5. ems to the thyroid are the lWest Pro The protective action in public areas following a radi: tion accide l only to onsite planning. Radiological contingency planning is that part of emergency response preparedness contributed by plant operators to assure i i exposures in the event of an accident, (2) that a capability exists for i measuring and assessing the significance of accidental releases of radioact v ided materials, (3) that appropriate emergency equipmer.. and t d following an accident, (4) that notification; are promptly made offsite to Federai, State, and local government agencies, and (5) that necessary recovery ition actions are taken in a tirely fashion to return a plant to a safe condO following an accident. sufficiently encompassing to meet the following objectives: Confinement systems for radioactive material pro 1 tc detect accidental releases, and apprcpriate means exist for limiting accidental releases. The responsibilities of the various supporting organizations are specifically ectablished, and a requisite number of s 2. emergency that might occur. On-shif t licensee responsibilities for amergency response are unambiguously defined, adequate staffing is x ovided to assure that 3. key functional areas will continuously operate, and the interfaces among -3rious onsite response activities and any offsite support an response activities are specified. Arrangements are made for requesting and effectively using assistanc d esources, and other organizations capable of augmenting the planne 4. response are identified. ii'

\\ 5. A standard emergency classification and action level scheme is in use by the licensee. '6. Procedures ha e been established for notification of State and local response organizations and for notification of emergency personnel by the. licensee and for assuring that messages concerning emergencies are unambiguously communicated to these individuals. 7. Provisions exist for prompt communications to State and local response organizations, to other organizations, and to emergency personnel. -8. Adequate emergency facilities'and equipment to support the emergency response are provided and maintained. 9. Adequate methods, systems, and equipment for assessing and monitoring actual or potential offsite releases of radioactive materials are in use. 10. Means for controlling radiological exposures, in an emergency, are established for emergency workers.

11. Arrangenents are made for medical services for injured individuals-who are contaminated.
12. General plans for recovery and reentry are developed.

13. Periodic exercises are conducted to evaluate major portions of ) emergency response capabilities, pc-iodic drills are conducted to ] develop and maintain key skills, ana deficiencies identified as a result of exercises and drill are corrected. 14. Radiological emergency response training is provided to those who may be called on to assist in an emergency. { 15. Responsibilities for plan development and review and for distribution of plans are establishea, and the planners are properly trained. Licensees who are required to prepare radiological contingeacy plans must submit them to the Director, Division of Fuel Cycle and Material Safety, NMSS, Nuclear Regulatory Commission, Washington, D.C. 20555, for review and approval. NRC will assess and evaluate the licensee's proposed response and recovery actions and will use the information provided to plan NRC's response activi*- tics. For completeness, the plan must include descriptions of (1) facilities, (ii) chemical and physical processes, (iii) types, forms and quantities of radioactive and other hazardous materials, (iv) distribution of radioactive material inventories, (v) specifications of structures, systems, and components important to safety, and (vi) the elements of emergency planning. Purpose and Applicability This Standard Format has been prepared to help assure uniformity and completeness in the preparation and review of Radiological Contingency Plans. iv

The licensee is encouraged to prepare his Radiological Contingency Plan in accordance with the Standard Format and to provide all information to support the coaclusion that his plan is adequate and capable of implementation. The information specified in the Standard Format is the minimum for a Radiological Contingency Plan. Although strict conformance with the Standard Format is not mandatory, presentation of an equivalent level of information is necessary. Additional information mcy be required for completion of the staff review of a particular plan. The information provided should be up-to-date with respect to the licensee's current radiological contingency planning and should reflect current awareness of the need for preplanning for abnormal occurrences and current state of the art and technology for emergency management. Information requirementa which are deemed by the licensee to be not applicable should be explicitly so designated and justificatan provided unlen the nonapplicabilty is obvious. Page Numbering Pages should be numbered by chapter and sequentially within the chapter, e.g., the first page of Chapter 3 would be 3-1, etc. Do not number the entire report sequentially. Format References References in the application to this Standard Format should be by chapter, section number, and subsection number. Procedures for Updating or Revising Pages The updating or revising of data and text should be on a replacement page l basis. Each changed or revised portion of a page should be highlighted by a vertical line. The line should be on the margin rpposite the binding margin at each line changed or added. All pages submitted to update, revise, or add pages to the report should show the date of change. The transmittal letter should include an index page that lists' the pages to be inserted and the pages to be removed. Where major changes or additions are made, pages for a revised Table of Contents should be provided. l l tjumberofCopies The licensee should submit six copies of his Radiological Contingency Plan. Compatibility The licensee should ensure that the Radiological Contingency Plan is compatible with the other sections of his license or license application. Upon receipt of the prepared plan, the Regulatory staff will perform a preliminary review to determine if the plan provides a reasonably complete presentation of the informatica needed. The Standard Format will be used by v

'2 Paper Stock and Ink Suitable quality in substance, paper color, and ink density for handling and for reproduction by microfilming. 3. Page Margins No less than one inch on the top, bottom, and binding side of all pages submitted. 4. Printing Composition: text pages should 59 single spaced. Type face and style: suitable for microfilming. Reproduction: may be. mechanically or photographically reproduced. All pages of the text may be printed on both sides with the image printed head to head. 5. -Binding Pages should be punched for looseleaf ring binding. e i 4 4 s vii 1 i w

o 1-1 1.0 GENERAL DESCRIPTION OF THE PLANT / LICENSED ACTIVITY The information in this section is to provi e perspective about the p unt and the licensed activity such that the adequacy and appropriateness of the. licensee's contingency planning, emergency organization, and emergency equip-F ment can be evaluated. Where this information duplicates information provided elsewhere in the licensee's various applications, it is recommended that it also be repeated here; however, it can be referenced instead if specific sections, paragraphs, and page numbers are cited. j 1.1 Licensed Activity Description Present briefh the principal aspects of the overall licensed activity. The f3110 wing should be included: a general description of licensed and other activities conducted at the plant site; the location of the plant; the type, form, and quantities (possession limits) of radioactive materials; the types of product; and the wntes produced. 1.2 Site and Facility Description Include a description of the principal characteristics of the site at which l licensee activities are conducted. Indicate the site on a general area map (approximately 10-mile radius) and upon a United States Geographical Survey 7.5' topographical map (s). Provide a site plan or aerial photograph indicating onsite,tructures and near-site structures (about 1-mile rad' :s). On this photograph or site plan, include the following: (1) location of population centers (office buildings, schools, arenas, stadiums, etc.), (2) the location of facilities which could present potential evacuation problems (prit.ons, nursing homes, and hospitals), (3) identification of primary routes for access of emergerry equipment or for evacuation as well as potential impediments to traffic flow (rivers, drawbridges, railroad grade crossings, one-way streets, etc.), (4) location of any emergency facilities (fire station, police station, hospital with capability for handling radioactive contamination, etc.), (5) the sites of potential emergency significance (LPG terminals, pipelines, filling j stations,etc.). Indicate approximate populations, both commuters and residents, associated with onsite and near-site structures. Provide a detailed site plan and a concise description of the facilities. The description should include a discussion of the principal design criteria; descriptions of process or manu-facturing systems; confinement systems for handling and storage of radioactive and other hazardous materials, the release of which could impact adversely on the safety of licensed operations; auxiliary systems such as ventilation; radioactive waste management system (s); alarms to detect accidental releases; i and means for limiting accidental release when detected. Provide equipment, piping, and instrumentation diagrams of sys ims pertinent to the processing or confinement of radioactive materials to fu.n.ner des cibe the functions and interactions of plant systems. The arrangement of structures and major equip-ment items should be indicated on plan and elevation drawings in sufficient number and detail to provide a reasonable understanding of the general layout of the plant. Any additional features of the plant likely to be of special interest because of their relationship to safety should be identified.

J 1-2 i i

1. 3 Process Description Descriptions of the process (es) used in the facility should be included.

Identify reactants, products, and waste streams. Provide sufficient detail, 1 including process flow diagrams, in the discussion to praside an understanding of the processes involved. J i 2 b i O i' 1 n l 4 4 ,9 9 -m e e-, e -w r---- +

2-1 2.0 ENGINEERED PROVISIONS FOR ABNORMAL OPERATIONS The impacts of radiological contingencies are affected by the nature-of a partiedlar event; design of plant facilities, processes, and control operations which contribute to limiting radiation exposures or releases of radioactive materials; implementation of emergency response actions; and recovery actions taken. In this section describe those facility process and control measures which contribute to: (1) promptly aetecting accidental releases of radioactive materials and effecting corrective or niitigating responses; (2) limiting releases of radioactive materials and potentially dangerous nonradioactive materials which could adversely affect the safety of licensed operations; and (3) permitting safe and prompt recovery actions to be taken in the event of abnormal operations. 2.1 Criteria for Accommodation of Abnormal Operations In this section, describe the desiga criteria for performance of facility sistems during abnormal operations and conditions. 2.1.1 Process Systems Describe the perfcrmance criteria for response of process systems to abnormal conditions resulting from operator error or malfunction of process and control equipment. 2.1.2 Alarm Systems and Release Prevention Specify criteria for detectors and alarms provided to detect and alert operators to accidental releases of radioactive materials and describe the response anticipated to effectively limit accidental releases and to mitigate the consequences of such releases. 2.1. 3 Support Systems Describe the performance criteria for response of support systems to abnormal conditions such as operator error, malfunctions of equipment or controls, accidents, and severe natural phenomena. Those should include but are not necessarily limited to: 2.1.3.1 Structural Performance vs. Site Environmental Factors 2.1.3.1.1 Severe Natural Phenomena 2.1.3.1.2 Accidents at Neighboring Activities 2.1.3.2 Confinement Barriers and Systems 2.1.3.3 Access and Egress of Operating Personnel and Emergency Response Teams 2.1.3.3.1 Onsite 2.1.3.3.2 Near site

2-2 q 2.1.3.4 Fire and Exp1nsion Resistance and Suppression 2.1.3.5 Shielding 2.1.4 Control Operations Describe the criteria for controlling and maintaining the capabilities of plant engineered systems to respond as planned to abnormal conditions. 2.2 Demonstration of Engineered Provisions for l Abnormal Operation In this section describe facility systems important to safety and demonstrate that their anticipated performance (regarding the detection and sounding of an alarm for accidental releases of radioactive materials or potentially hazardous nonradioactive materials, which could adversely affect radiological safety, end limiting releases of radioactive materials and exposure of persons to radiation) during and following an abnormal operation or condition are in accordance with the criteria of Section 2.1. 2.2.1 Process Systems Describe the anticipated performances of process systems under abnormal conditions caused by such things as operator error or malfunctions of process equipment and controls. 2.2.2 Alarm Systems and Release Prevention Capability Describe detectors, alarms, and other components and the anticipated performance i of all effluent alarm systems under abnomal conditions and describe the strengths l and weaknesses of the methods planned for limiting releases when such releases are detected. 2.2.3 Support Systems l Describe the anticipated behavior of support systems during abnormal conditions such as malfunctions of equipment or controls, operator error, accidents, and severe natural phenomena. 2.2.4 Control Operations Describe in t iis subsection a safety assurance program which includes provisions for monitoring and auditing plant equipment and procedures for continued safety, for detecting deteriorating safety performance, and for identifying where improvements are needed.

3-1 3.0 CLASSES OF-RADIOLOGICAL CONTINGENCIES 3.1 Classification System -The radiological contingency plan should characterize several classes of emergency situations and relate them to response levels. The system of classification used should consist of largely mutually exclusive groupings, and it should cover the entire range or credible emergency situations. Each defined class should be associated with a particular set of immediate response actions that are to be taken to cope with the situations. Specific implementing procedures should be prepared for each identified class of radiological contingency. A recommended classification scheme is described in Section 3.2. In it, emergency' situations are classified into the four categories specified in Section IV of Appendix E of 10 CFR Part 50, i.e., Notification of Unusual Event, Alert, Site Area Emergency, General Emergency. The rationale for the notification and alert classes is to provide early and prompt notification of minor events which could lead to more serious censequences given operator error or equipment failure or which might be indicative of more serious conditions which are not yet fully realized. A gradation is provided to assure fuller response preparations for more serious indicators. The site area emergency class reflects conditions where some significant releases are likely or are occurring but where an uncontrolled release situation is not indicated based on current information. In this situation, full mobilization of emergency personnel in the near site environs is indicated as well as dispatch of monitoring teams and associated communications. The general emergency class involves actual or imminent uncontrolled releases of large inventories. l l t O

3-2 3.2 Recommended Classification Scheme-I Class NOTIFICATION OF UNUSUAL EVENT l m Class Description Licensee Actions Unusual events are in process or 1. Promptly inform State and/or local have occurred which indicate a offsite authorities of nature of potential degradation of the level unusual condition as soon as of safety of the plant. No discovered. ' leases of radioactive material requiring offsite response or 2. Augment on shift resources as' monitoring are expected unless needed. s further degradation of safety l systems. occurs. 3. Assess and respond. Purpose 4. Escalate to a more severe class, if appropriate. 4 Purpose of offsite notification i .is to (1). assure that the first~ or step in any response later found to be necessary has been' carried 5. Close out with verbal summary to out, (2) bring the operating offsite authorities, followed by staff to a state of' readiness.- written summary wthin 24 hours. and (3) provide systematic handling of unusual events 4

information and decisionmaking.

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ll 3-3 Class ALERT Class Description Licensee Actions Events are in process or have 1. Promptly. inform State and/or local occurred which involve an authorities of alert status'and actual or potential substantial reason for alert as soon as degradation of the level of safety discovered. of the plant. Any releases are expected to be limited to 2. Augment resources and activate small fractions of the EPA Pro-onsite operational support tective Action Guideline exposure emergency facilities and equipment. levels. Bring key emergency personnel to standby status. Purpose 3. Assess and respond. Purpose of offsite alert is 4. Dispatch onsite monitoring teams to (1) assure that emergency and associated communications. personnel are readily available to respond if situation 5. Provide periodic plant status becomes more serious'or to updates to offsite authorities. perform confirmatory radiation monitoring if required and 6. Provide periodic 2eteorological (2) provide offsite authorities assessments to offsite authorities current status information. and, if any releases are occurring, dose estimates for actual releases. 7. Escalate to a rore severe class,- if appropriate. 9E 8. Close out or recommend reduction in emergency class by veri:al summary to offsite authorities followed by written summary within 8 hours. t e

3-4 Class SITE AREA EMERGENCY Class Description Licensee Actions Events are in process or have 1. Promptly inform State and/or local occurred which involve actual offsite authorities of site area or likely major failures of emergency status and reason for plant functions needed for emergency as soon as discovered. protection of the public. Offsite releases are not 2. Augment resources by activating expected to exceed EPA Pro-onsite emergency response tective Action Guideline organization. exposure levels except near site boundary. 3. Assess and respond. 4. Dispatch onsite and offsite Purpose monitving teams and associated communications. Purpose of the site area emergency declaration is to 5. Dedicate an individual for plant (1) assure that response status updates to offsite centers are manned, (2) assuie authorities. that monitoring tc ws are dispatched, (3) anure that 6. Make senior technical and management personnel required for staff available onsite for consulta-evacuation of site areas tation with liRC and State on a are at duty stations periodic basis. if situation becomes more serious, (4) provide 7. Provide met.eorological and dose consultation with offsite estimates te offsite authorities for authorities, and (5) orovide actual releases via a dedicated updates for the public individual or automated data through offsite authorities, traasmission. 8. Drovide release and dose projections t,ased on available plant condition Information and foreseeable contingencies. 9. Escalate to general emergency class, if appropriate. EE 10. Close out or recommend reduction in emergency class by briefing of affsite authorities followed by written summary within 8 hours of closeout or class reduction.

3-S Class GENERAL EMERGENCY Class Description Licensee' Actions - Events are in process or have-1. Promptly inform State and local o'ffsite occurred which involve actual authorities of general emergency status or imminent loss of confinement and reason for emergency as soon as integrity. Releases can be discovered (Parallel notification of reasonably expected to exceed State / local). EPA Protective Action Guideline exposure levels offsite for more 2. Augment resources by activating onsite than the immediate site area. emergency response organization. Purpose 3. Assess ar.d respond. 4. Dispatch onsite and offsite monitoring Purpose of the general emergency teams and associated corynunications. declaration is to (1) initiate predetermined protective actions 5. Dedicate an individual for plant status for the public, (2) provide updates to offsite authorities. continuous assessment of infor-mation from licensae and offsite 6. Make senior technical and management organization measurements, staff available onsite for conudta-(3) initiate additional measures tion with NRC and State perscenel as indicated by actual or on a periodic basis. potential releases, (4) provide consultation with offsite autneri-7. Provide t.eteorological and dose ities, and (5) provide updates estimates to offsite authorities for for the public tnrough offsite actual celeases via a dedicated authorities. individual or automated cata transmission. 8. Provide release and dose pojections based on available plant condition information and foreseeable contingencies. E f 9. Close out or recommend reduction of emergency class by briefing of offsite authorities followed by written summary within 8 hours of closeout or class reduction.

3-6 ) 3.3 liange of Postulated Accidents Emergency planning is concerned with individual and organizational responses to the continuum of potential accident situations including those accidents that have been hycothesized but have a very low probability of occurrer.ce. . The radiological contingency plan should demonstrate how the postulated accidents are encompassed within emergency characterization classes. This section of the plan shoula describe how the postulated accidents are covered by the plan and should provide a summary analysis of their implication for emergency planning, including assessment of offsite impact, instrumentation capability for prompt detection and continued assessment, and manpower needs in relation to the anticipated sequence and timing of events. i l i

4-1 4.0 ORGANIZATION FOR CONTROL OF RADIOLOGICAL CONTINGENCIES In this chapter, describe the radiological contingency organization to be activated for the possible events onsite and its augmentation and support offsite. Delineate the acthorities and responsibilities of key individuals and groups, and identify the communication chain for notifying, alerting, and mobilizing the necessary personnel. 4.1 Normal Plant Organization Provide a brief description of the plant organization and identify those individuals that have the responsibility and authority to declare an emergeacy and to initiatc the appropriate radiological contingency response. 4.2 Onsite Radiolo g al Contingency Response Orgeization Describe the onsite radiological contingency organization for controlling each class of emergency including the times when normal operations are not being ) conducted. As appropriate, use organization charts and tables. 4.2.1 Direction and Coordination Designate the position of the person and his alte nate(s) who have the overall responsibility for implementing and directing the radiological contingency procedures. Discuss his duties and authority including control of the situa-tion, termination or the emergency conditier., and coordination with the staff and offsite personnel who augment the staff or require information concerning the event. 4.2.2 Plant Staff Radiological Contingency Assignments Specify the organizational group or groups which are assigned to the following functional areas of emergency activity inclucing the personnel arsynment raticaale for working and nonworking hours. For each group describe their duties, authority, and interface with other groups and outside assistance. The functional groups should provide capability in the following areas: Plant Systems Operations Radiological Survey and Assessment Fire Control Rescue Operations First Aid / Decontamination of Personnel Plant Security and Access Control Repair and Damage Control Recordkeeping Personnel Accountabilty Facility Decontamination Commt.aications Post-Event Assessment

I 4-2 4.3.0ffsite Assistance to facility Describe provisions and arrangements for assistance to onsite personnel during and after a radiological emergency. Identify the services to be performed, means of communcation and notification, and type of agreements that are in place for: Medical Treatment Facilities First Aid Personnel and Ambulance Service Services of other Medical Personnel Or Site Firefighting Backup Police Assistance Other l 4.4 Coordhiation with P,3rticipating Government Agencies Identify the principal state agency and other government (local, county, state, and federal) agencies or organizations having action responsiblities for radiological emergencies in the area of the facility. Icc each agency and-j organization describe: Its authority and responsibility in a radiological emergency and its interface with others, if any. l l Its specific response capabilities in terms of personnel and resources l available. Its~ location with respect to the facility. Typical agencies to be included are law enforcement, departments of health or i environmental protection, emergency / disaster control agencies, and the Regional Coordinating Offices for Radiological Assistance of the U.S. Department of j Energy. 6

T[ 5-1 s

5. 0 RADIOLOGICAL C3NTINGENCY MEASURES L

Specific radiological r itingency response measures should be identified for each radiological cont gency~ class and related to action levels or criteria that specify when the measures are to be implemented. ~ Response measures include assessment actions, corrective actions, protective actions, exposure ' control, and aid to injured persons. 5.1 Activation of Radiological Contingency Response Organization Describe the means to activate the radiological contingency response personnel for each class of radiological contingency as defined in Section 3.1, including a general description of the message authentication scheme. Identify the action levels selected and relate them to the responsibilitias identified in Chapter 4.0. In this section and subsequent secticus, attach the specific i written procedures to be used. 5.2 Assessment Actions For each class of emergency discuss the actions to be caken to determine the extent of the problem and te decide what corrective actions may be required. 5.3 Corrective Actions Discuss the response actions that will be taken for the. events idactified in Chapter 3.0. 5.4 Protective Actions i The nature of protective actions, the criteria for implementing those actions, the area involved, and the notification procedures to onsite persons should be described in the plan. In order to prevent or minimize exposure to radiation j and radioactive materials, the plan should provide for timely relocation of onsite persons, effective use of protective equipment and supplies, and use of appropriate c.ontamination control measures. t 5.4.1 frerson ul Evacuation from Site and Accountability This segment of the radiological contingency plan should include the following items: a. Action criteria, b. The means and the time required to notify persons involved, c. Evacuation routes, transportation of personnel, and reassembly areas, d. Missing persons check, e. Radiological monitoring of evacuees and decontamination and selection for medical attention, if required. ki

5-2 5.4.2 Use of Protective Equipment and Supplies Effective'use of protective equipment and supp'ies, including the proper .onsite distribution of special equipment, is an important measure for miniaizing the effect of radiological exposures or contamination problems. Measures that should be. considered include: 1. Individual respirator protection and .0. Use of protective clothing. l l For each measure that might be used, a description should be given of: l l 1. Criteria for issuance, 2. Locations of items, 3. Means of distribution. 5.4.3 Contamination Control Measures Describe provisions for preventing fu.ther spread of radioactive materials and for mininizing radiation exposures from radioactive materia?t unshielded or released by abncrmal conditions. Onsite protective actions should be described and should include the following items: 1. Isolation and area access control, l 2. Criteria for permitting return to normal use. l Action criteria and responsiblity for implementation af the measures planned should be described. 5.5 Exposure Control in Radiological Contingencies Describe means for controlling radiological exposures, in an emergency, for emergency workers. The means for controlling radiological exposures should include exposure guidelines consistent with EPA Emergency Worker and Lifesaving Activity Protective Action Guides, EPA 520/1-75/001, viz. less than 75 rems planned whole body exposures for lifesaving action and less than 25 rems where l it is desirable to enter a hazardous area in order to protect facilities, eliminate further escape of effluents, or to control fires. 5.5.1 Emergency Exposure Control Program 5.5.1.1 Exposure Guidelines j Specify onsite exposure guidelines consistent with EPA Emergency Worker and Lifesaving Activity Protective Actions Guides (EPA 520/1-75/001) for i l j

5-3 a. removal of injured persons; b. undertaking corrective actions; c. performing assessment actions; d. providing first aid; e. performing personnel decontamination; f. providing ambulance service; and 9 providing medical treatment services. 5.5.1.2 Radiation Protection Program Describe an onsite radiation protection program to be implemented during emergencies, including methc,ds to implement exposure guidelines. Identi fy individt:als(s), by position or title, who can authorize workers to receive emergency doses. Procedures shall be worked out in advar.ce for permitting j onsite volunteers to receive radiation doses in the course of carrying out lifesaving and other emergency activities. Procedures should provide for expeditious decisionmaking and a reasonable consideration of relative risks. 5.5.1.3 Monitoring Describe provisions for 24-hour per-day capability to determine the doses and dose commitments from any internally deposited radioisotopes received by i emergency personnel involved in any nuclear accident, including volunteers. Include provisions for distribution of dosimeters, Doth self-reading and permanent record devices and means for assessing inhalation exposures. Describe provisions for assuring that dose and dose commitment records are maintained for emergency workers involved in any nuclear accident. 5.5.2 Decontamination of Personnel Specify action levels for determining the need for personnel decontamination. Describe the means for radiological decontamination of emergency personntl, wounds, supplies, instruments, and equipment, and the means for collecting and l handling radioactive wastes. Describe provisions for decontaminating relocated onsite personnel, including provisions for extra clnthing and decantaminants suitable for the type of contamination expected. 5.6 Medical Transportation 1 Specify arrangemants for transporting injured persennel, who may also be radiologically contaminated, to medical treatment facilities.

f 5-4 5.7 Medici; Treatment Describe arrangements made for local and backup hospital and medical services and their capabilities for the' evaluation and treatment of radiation exposure and uptake. For'both hospital and medical services,~the plan should incorporate assurance not only that the required services are available, but also that j persons providing the services are prepared and qualified to handle radiological L emergencies. ~' L I f [ e i 5 e k

6-1 6.0 EQUIPMENT AND FACILITIES. In this chapter, describe the licensee's equipment and facilities designated for use during a radiological emergency. Provide sufficient detail to allow the NRC staff to determine the adequacy of the equipment to perform its function during an emergency. 6.1 Control Point Describe the principal an', if provided for, alternate onsite location from d which emergency control is exercised. 6.2 Communications Equipment Describe the onsite communication systems that would be required to perform vital functions in t.ransmitting and receiving information throughout the course of an emergency and subsequent recovery. 6.3 Facility for Assessment Teams Describe the facilities designated for use by staff performing post-accident and recovery assessment and protective action functions. 6.4 Onsite Medical Facilities Describe t'ie-facilities and medical supplies at the site designated for emergency first aid treatment and decontamination of onsite individuals. 6.5 Emergency Monitoring Equipment List and describe the emergency equipment that will be available for personnel and area monitoring as well as that for assessing the release of radioactive materials to the environment. The description should include the purpose to be served and the capability of the. equipment to function properly during an emergency. Operational data for the instrumentation such as sensitivity, range, backup power, calibration frequency as well as any alarm function and associated set point should be included. The location for all monitoring equipment should be described. Include similar descriptions of effluent monitors and meteorological measurement systems. Describe how those are to be u:,ed 'to timely assess the magnitude and likely dispersion of releases. l-l l e e

7-1 7.0 MAINTENANCE CF RADIOLOGICAL CONTINGENCY PREPAREDNESS CAPABILITY 7.1 Writter f acedures l Identify the means for assuring that implementing written procedures clearly state the duties, responsibilities, action levels, and actions to be taken by each group or individual in responding to &n emergency condition. Discuss provisions for approval of the procedures and their periodic review fo* adequacy. 7.2 Training Describe the programs and procedures used to train the onsite radiological emergency staff and the support offsite personnel. Specify the training afforded to those personnel who prepare, maintain, and implement Radiological Contingency Plans. Include schedules, training lesson plans, and the frequency of retraining and the estimated number of hours of training that will be provided. l 7.3 Tests and Drills Describe provisions for the conduct of periodic drills and exercises to test the adequacy of timing and content of implementing proceaures, to test emergency equipment and instrumentation, and to ensure that the radiological emergency personnel are familiar with their duties. Preplanned descriptions of accidents i_ should be used to prepare scenarios appropriate to the objectives of each I drill and exercise. When applicable, those exercises should contain provisions for coordination with offsite assistance organization, includirg testing of procedures and equipment for communication and notification of local and state agencies. The procedures should include a requirement for the use of observers during drills ar:d exercises to evaluate the effectivess of the personnel, the procedures, anc the readiness of equipment and instrumentation and to recomirend l needed changes. It is recommended that drills and exercises be held by the l licensee annually with involvement of outside observers and support agencies at least once every five yars. 7.4 Review and Updating of the Plan and Procedures Discuss the pre; ram to be used to annually review the radiological contingency plans and procedures to assure that they are adequate. In addition to the input obtained from the evaluation of tests and drills above, consideration should be given to a defined periodic review time as well as a review whenever changes occur in processes, kinds of material or inventory at risk, and plant organization. 7.5 Maintenance and Inventory of Radiological Emergency Equi 9 ment, Instrumentation, and Supplies Describe the plans for assuring that the equipment and instrumentation are in a working condition and that the stock of supplies is maintained. Provision should be made for periodic checking that the specified inventory is intact I and in operating condition, including instrumentation operation and calibration, l demand respirators, supplemental lighting, and communications equipment. The l procedures should include corrective action to be taken when deficiencies are l found during these checks. i

~. 8-1 8.0 RECORDS AND REPORTS 6.1 Recoros of Incsdents In this section provide a detailed description of the records that will be kept of radiological contingencies according to the following classification: (1) notification of unusual event, (2) alert, (3) site area emergency, and (4) general emergency. The records should include the cause of the incideat, personnel and/or equipment involved, extent of injury and/or damage resulting from the incident, corrective actions taken to terminate the emergency, and the action taken or planned to prevent a recurrence of the incident. The records should also include the onsite and offsite support assistance requested and received for recovery action. The title (s) of the personnel responsible for maintaining the records should be identified. The minimum retention time for each type record should be specified. Those records unique to a radio- ~ logical contingency, not covered by existing Commission regulations or license conditions, should be retained until the license is terminated. 8.2 Records of Preparedness Assurance In this section provide a description of the records that will be kept to confirm the maintenance of preparedness to respond to radiological contingen-cies. These records include (1) training and retraining, (2) drills, exercises, and related critiques, (3) inventory and locations of emergency equipment and supplies, (4) maintenance, surveillance, and testing of emergency eqvip:nent and supplies, (5) agreements with offsite support organizations, and (6) reviews and updates of the radiological contingency plan and notification of all personnr;l and offsite agencies affected by an update of the plan and procedures. 8.3 Reporting Arrangements In this section describe the arrangements for reporting accidents and related information offsite. These reports are needed to keep lccal, state, and federal agencies, corporate management, and the public informed on (1) the occurrence of an emergency condition, (2) its effect on the health and safety of operating personnel, the pubMc and the environment, (3) progress on its control, and (4) recovery from the emergency condition. Responsiblity for reporting information should be specified. l l-

~ 9-1 9.0 REC 0VER) 9.1 Reentry This section should discuss the criteria for reentry. Radiological criteria should be as described in Section 5.5.1 of this standard format. Reentry is-the first step in recovery after an emergency. 9.2 Plant Restoration (his section should describe the plans for restoring the facility to a safe status. Although it is not possible to detail specific plans for every type of incident, the plans should include the general requirements for (1) assessing the damage to and the status of the facility's capabilities to contain radioactivity, (2) determining the actions necessary to reduce any ongoing releases of radio-active or other hazardous material and preventing further incidents, and (3) accomplishing the tasks to c et any required restoration action. Specifically, the plans should include the requirements for checking and restoring to normal operations all safety-related equipment involved in the incident (e.g., criticality alarms, radiation monitoring instruments, respiratory masks, air filters). During any plant restoration operations, personnel exposures to radiation must be maintained within 10'CFR Part 20 limits and as low as can be reasonably achieved. 9.3 Resumption of Operations This section should describe the criteria for resumption of operations. Operations should not be resumed until normal facility conditions have been restored, investigation has determined the cause of the incident, and necessary corrective actions have been taken. Any problems identified in the investigation should be resolved prior to resumption of operations. 4

T ~_ f,",f,';"" 338 u.s. NUCLEAR CEIULATORY COMMISSION BIBLIOGRAPHIC DATA SHEET NUREG-0762

4. TETLE AND $U8TlTLE LAdd Vdume No.,ifepropruani 2.(Leave M m kl STANDARD FORMAT AND CONTENT FOR RADIOLOGICAL CONTINGENCY PLANS FOR FUEL CYCLE AND MATERIALS FACILITIES
3. REOlPIENT'S ACCESSION NO.

F. AUTHOR $)

5. DATE REPORT COMPLETED MONTH l YE AR ENVIRONMENTAL RADIATION AND EMERCENCY SUPPOR7 SECTION January 1981
9. PERFORMING ORGANIZATION NAME AND MAILING ADDRESS flacevae Zip Codel CATE REPORT ISSUED

-Divisiori of Fuel Cycle and Material. Safety [ MONTH l YEAR Office of Nuclear Material Safety and Safeguards Julv 1981 U.S. Nuclear Regulatory %Cominission v

s. Ite, e maa*/

Washington, DC 20555 7

8. (Leave Nankl
12. SPONSORIN G '

TION NAME AND MAILING ADDRESS (lactuo' Zip Codel' 1o. PROJECT / TASK / WORK UNIT NO. Division o. ei Cycle and Material Safety ?",. Office of Nuclear Material Safety and Safeguards ii. CONTRACT NO. A,, U.S. Nuclear Regulatory Commission Washington, DC 20555

13., TYPE OF REPORT FERICOCO E ME O finclusove dans)

Regulatory '15. SUPPLEMENTARY NOTES

14. (Leave Nek/
16. ASSTR ACT 000 wores or sessi This report is issued as guidance to those fuel cycle and major materials licensees who are required by the NRC to prepare and submit a radiological contingency plan.

This Standard Format has been prepared to help assure uniformity and completeness in the preparation of those plans. i 4

17. KEY WOROS AND DOCUMENT ANALYSIS 17a DESCRIPTORs radiological emergency emergency preparedness radiological contingency radiological contingency planning radiological contingency plans 17o. IDENTIFIE RSIOPEN-ENDED TERMS

~ IS. AVAILABILtTY STATEMENT

19. SECURITY CLAGS (Thss reporff s 21. NO. OF P AGES Unclassified i

Unlimitad-

20. SEcuRiTv ctAsS iTa,s o,xl
22. PRICE Uncla s si fied

- s N f**C # 0 AM 335 (1773

a. i 1 4 UNITE 3 STATES NUCLE A3 FiEEULAT30Y COMMISSISN F ] W A!MINOTON, O. C. 20696 Post Aos ANO rats paso u S. NUCLE AR Rggut.ATORY comusseeoM =- ('g OFFICI AL SUSINESg

FEN ALTY Pon PaivATE usE,8300 x

L J m OI 6uOi g, i NH .>z O>. a r,, n m: 4 O c' mEL a c, y. i 2 -4 m)- I CZ' i mO rn' i no t <Z 1 OH rm' m2 ) -1 I Zm' OO: E 3; y 2. -4 > l mO.

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