ML20053C423
| ML20053C423 | |
| Person / Time | |
|---|---|
| Issue date: | 05/31/1982 |
| From: | Bates E, Grimes B, Ramos S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| To: | |
| References | |
| NUREG-0849, NUREG-0849-DRFT, NUREG-849, NUREG-849-DRFT, NUDOCS 8206020104 | |
| Download: ML20053C423 (37) | |
Text
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i Standard Review Plan for r
g"i the Review and Evaluation of Emergency Plans for Research yi and Test Reactors
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For interim Use and Comment q
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Commission Office of Inspection and Enforcement
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NOTICE Availability of Reference Materials Cited in NRC Publications Most documents cited in NRC publications will be available from one of the following sources:
- 1. The NRC Public Document Room,1717 H Street, N.W.
Washington, DC 20555
- 2. The N RC/GPO Sales Program, U.S. Nuclear Regulatory Commission, Washington, DC 20555
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Referenced documents available for inspection and copying for a fee from the NRC Public Docu-ment Room include NRC correspondence and internal NRC memoranda; NRC Office of Inspection and Enforcement bulletins, circulars, information notices, inspection and investigation notices; l
Licensee Event Reports; vendor reports and correspondence; Commission papers; and applicant and l
licensee documents and correspondence.
l The following documents in the NUREG series are available for purchase from the NRC/GPO Sales Program: formal NRC staff and contractor reports, NRC-sponsored conference proceedings, and N RC booklets and brochures. Also available are Regulatory Guides, NRC regulations in the Code of Federal Regulations, and Nuclear Regulatory Commission Issuances.
t Documents available from the National Technical information Service include NUREG series reports and technical reports prepared by other federal agencies and reports prepared by the Atomic Energy Commission, forerunner agency to the Nuclear Regulatory Commission.
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Single copies of NRC draft reports are available free upon written request to the Division of Tech-nical Information and Document Control, U.S. Nuclear Regulatory Commission, Washington, DC l
20555.
Cop;es of industry codes and standards used in a substantive manner in the NRC regulatory process are maintained at the NRC Library, 7920 Norfolk Avenue, Bethesda, Maryland, and are available there for reference use by the public. Codes and standards are usually copyrighted and may be purchased from the originating organization or, if they are American National Standards, from the l
American National Standards institute,1430 Broadway New York, NY 10018.
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NUREG-0849 r zz :-
Standard Review Plan for the Review and Evaluation of Emergency Plans for Research and Test Reactors For interim Use and Comment
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Manuscript Completed: February 1982 Date Published: May 1982 E. F. Bates, B. K. Grimes, S. L. Ramos Division of Emergency Preparedness Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission l
Washington, D.C. 20555 h
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ABSTRACT This document provides a Standard Review Plan for the guidance of the NRC staff to assure that complete and uniform reviews are made of research and test reactor emergency plans.
The report is organized under ten planning standards which correspond to the guidance criteria in Draft II of ANSI /ANS 15.16 as endorsed by Revision 1 to Regulatory Guide 2.6.
The applicability of the items under each planning standard is indicated by subdivisions of the steady state thermal power levels at which the reactors are licensed to operate.
Strindard emergency classes and example action levels for research and test reactors which should initiate these classes are given in an Appendix.
I iii
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i CONTENTS Page No.
ABSTRACT......................................................
iii C O NT E N T S. 4....................................................
v AC KN 0WL ED G EM E NT S.............................................. v i i INTRODUCTION..................................................
1 AREAS OF REVIEW, PLANNING STANDARDS AND EVALUATION ITEMS
1.0 INTRODUCTION
5 2.0 DEFINITIONS.............................................
6 3.0 ORGANIZATION AND RESP 0NSIBILITIES.......................
7 4.0 EMERGENCY CLASSIF ICATION SYSTEM.........................
10 5.0 EMERGE NCY ACTION L EVELS................................. 11 6.0 EMERGE NCY PLANNI NG Z0N ES................................
12 7.0 EM ERGE NCY RESP 0 NS E......................................
13 8.0 EMERGENCY FACILITIES AND EQUI PMENT......................
16 9.0 REC 0VERY................................................
20 f
10.0 MAINTAINING EMERGENCY PREPAREDNESS......................
21 APPENDIX I DiERGENCY CLASSES AND EXAMPLE EMERGENCY ACTION LEVELS............................................... I-1 APPENDIX II METHOD FOR DETERMINING THE SIZE OF AN EMERGENCY PLAfiN ING Z0NE............................... II-1 y
ACKNOWLEDGEMENTS This report has been prepared with the assistance of the personnel of the Health Physics Technology Section, Radiological Sciences Department, at the Battelle Pacific florthwest Laboratories. The authors wish to I
acknowledge C. D. Corbit, A. E. Desrosiers, S. C. Hawley and J. G. Meyers for their technical contributions to this report.
t l
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i vii
STANDARD REVIEW PLAN FOR THE REVIEW AND EVALUATION OF EMERGENCY PLANS FOR RESEARCH AND TEST REACTORS INTRODUCTION An emergency is a condition which calls for immediate actions beyond the scope of normal operating procedures to avoid or mitigate the consequences of an accident. Many organizations, although capable of handling most industrial situations or accidents, must place additional emphasis on the proper response to situations or accidents involving radioactive materials that could result in unwarranted exposures to radiation.
There can be several limiting factors which will affect the overall ability of the emergency response organizations to take control of the emergency situation.
For example, the absence of dose assessment capability could prevent timely and accurate projections of radiation doses from accidental releases of radionuclides.
Radiological emergencies or incidents can occur at any time or I
place where radioactive materials or radiation-producing devices are
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used, stored, or transported. To cope with emergencies or incidents research and test reactor licensees are required to develop radiological emergency plans and implementing procedures. To be effective, the plans and procedures nust address the establishment of an acceptable state of emergency preparedness.
A well conceived, properly implemented plan j
will minimize the hazards which could jeopardize the health and safety of employees and the public.
Pursuant to 10 CFR 50.54 (r), each licensee who is authorized to possess and/or operate a research or test reactor under a license of the.
type specified in 10 CFR 50.21 (c), shall submit emergency plans, in compliance with the 10 CFR 50, Appendix E requirements to the Director of Nuclear Reactor Regulations. Appendix E of 10 CFR 50, " Emergency Plans for Production and Utilization Facilities," establishes minimum requirements for emergency plans to attain an acceptable state of emer-gency preparedness and to provide reasonable assurance that protective measures can and will be taken to protect the health and safety of workers and the public.
Regulatory Guide 2.6, " Emergency Planning for Research and Test Reactors," which is specified by Appendix E as the guidance to be used to determine the acceptability of research and test reactor emergency response plans, describes a method acceptable to the NRC staff for complying with the Commission's emergency planning regulations.
Revision 1 to Regulatory Guide 2.6 endorses Draft II, dated November 29, 1981, of the American National Standard, ANSI /ANS-15.161978, " Emergency Planning for Research Reactors," which provides specific guidance on emergency planning for research and test reactors.
f This Standard Review Plan (SRP) has been prepared for the guidance of NRC staff reviewers in perfonning reviews and evaluations for the acceptability of research and test reactor emergency plans. The purpose j
of the SRP is to assure that unifonn evaluations and complete reviews are made of each research or test reactor emergency plan.
The report is organized under ten planning standards which correspond to the guidance criteria in Draft II of ANSI /ANS 15.16.
Responsibility for planning and implementing all emergency measures within the site boundaries rests with the licensee.
In this context, the site boundaries should be clearly defined.
Supporting organizations that would augment the licensee's emergency organization, e.g., fire _ -.
department, hospitals, and security organizations, should be specified.
Planning and implementation of measures to cope with reactor-related emergencies beyond the site boundary should be commensurate with and based on the potential consequences of credible accidents or incidents.
The emergency plan should describe this planning basis and the corresponding arrangements and agreements among the licensee and the local, State, or l
Federal agencies expected to respond.
l l
Within the research and test reactor community, the authorized thermal power levels range from 0.1 W to 50 MW.1/ The inventory of I
radionuclides generated in reactor operations and the potential for accidents that result in a degraded core are largely dependent upon power level and operating history.
Hence, the applicability of the planning standards to research and test reactors is also based upon power levels.
Three ranges of power levels (greater than 100 W to less than 100 KW, equal to or greater than 100 KW to less than or equal to 2 MW, and greater than 2 MW) are used in the text, and the applicability of the items under each planning standard to reactors in these three ranges is identified by an "X" in the appropriate columns of the review sections.
Research and test reactors authorized to operate at power levels less than or equal to 100 watts do not need to meet the planning standards. The scope and content of emergency plans for research or test reactors authorized to operate at power levels less than or equal to 100 watts should include, as a minimum, those evaluation items that are marked with an asterisk.
l
-_/ Power level in this document neans authorized steady state thennal 1
power level of the reactor.
It should be noted that the radiation dose levels of the emergency action levels established for the various emergency classes are slightly different from those specified for power reactors.
However, in the judgment of the NRC staff, the radiation dose levels specified are adequate for the credible accidents associated with the operation of research and test reactors, and the specified action levels provide reasonable assurance that protective measures associated with the action levels specified can and will be taken, provided appropriate emphasis is also given to developing emergency action levels that relate directly to facility parameters (e.g., pool water levels and area radiation monitors).
I Four standard emergency classes are defined in Draft II of ANSI /ANS 15.16 and in this document which are generally consistent with those used for power reactors. The classes are Notification of Unusual Events, Alert, Site Area Emergency and General Emergency.
The General Emergency class of accidents as defined in the NRC Regulations and in Appendix 1 to NUREG-0654/ FEMA REP-1 is not credible
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for most research or test reactors as this class is reserved for accidents which could have a significant radiological impact at substantial distances I
from the reactor.
Therefore, most research or test reactors would not include this class as part of their emergency plan.
)
1 Acceptable sizes for Emergency Planning Zones (EPZs) are given in Appendix II as a function of authorized steady state thennal power j
level. These are consistent with those given in Drait II, ANSI /ANS-15.16.
i Small reactors do not require EPZs larger than the operations boundary because of the low potential hazard from these facilities.
The EPZ size will be determined on a case-by-case basis for any research and test reactors with power levels greater than 50 MW. 1
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1.0 INTRODUCTION
PLANNING STANDARD The introduction should provide a general orientation and comon understanding about the reactor facility and the objectives of the emergency plan.
Applicability by Reactor Operating Power Levels
)
~> 100 KW
> 100 W to Evaluation Items
< 100 KW to 12 MW
> 2 MW f
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1.
The emergency plan should include i
the following:
a.
A description of the reactor j
including fuel type, authorized power j
level and associated facilities.*
X X
X I
b.
Identification of the owner /
{'
l operator and the operating license.*
X X
X
)
)
c.
A description of the location of the reactor facility including access routes should be included in an appendix to the plan.*
X X
X d.
Identification of the major functions and utilization of the reactor.
X X
e.
The typical operating frequency (schedule) and average energy output per f
year, e.g., number of megawatt days.
X X
f.
The objective of the emergency l
plan, i.e., its use as a plan of action J
to follow in the event of a radiological I
accident.*
X X
X
- Emergency plans for research and test reactors with authorized power levels less than or equal to 100 W thennal should include as a minimum those items that are marked with an asterisk.
2.0 DEFINITIONS PLANNING STANDARD Words or phrases that have a special meaning when used in the plan or are unique to the reactor facility should be defined in the plan.
Applicability by Reactor Operating Power Levels
> 100 W to
> 100 KW Evaluation Items
< 100 KW to s. 2 MW
> 2 MW 1.
The emergency plan should include definitions of words or phrases with j
meanings specific or unique to the plan or reactor.
X X
X I I
3.0 ORGANIZATION AND RESPONSIBILITIES PLANNING STANDAPD The staffing and responsibilities for emergency event responses, including recovery and maintaining emergency preparedness, are to be documented in energency plans.
Applicability by Reactor Operating Power Leve_ls_
> 100 W to
> 100 KW Evaluation Items
< 100 KW to < 2 MW
> 2 MW 1.
The emergency plan should describe l
the following organizational considerations:
l l
a.
The functions as applicable to emergency planning of Federal, State, and local government agencies and the assistance that they would provide in the event of an emergency.
X X
i b.
Licensee's emergency organi-zation including any augmentation of i
staff for emergency event responses, reentry, recovery and maintaining
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the emergency preparedness program.
X X
c.
Identification of services that will be provided to the licensee by offsite support organizations (e.g., medical, fire and ambulance servic es).*
X X
X d.
A block diagram showing f
the interfaces among the facility's g
emergency organization, offsite I
support organizations, and State and local government agencies where applicable.
X X
- Emergency plans for research and test reactors with authorized power levels less than or equal to 100 W thennal should include as a minimum those items that are marked with an asterisk. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _
Applicability by Reactor Operating Power Levels
> 100 W to
> 100 KW Evaluation Items
< 100 KW to 5 2 MW
> 2 MW e.
Capability for the emergency organization to function around-the-clock for a protracted period following initiation of emergency events that either have or could X
lead to radiological consequences.
2.
The emergency plan should identify responsibilities and authorities for the follogng key positions, by title: -
I a.
Emergency director, with a line of succession, including those responsibilities which may not be delegated (such as notification and protective action decisions).*
X X
X b.
Emergency coordinator, including those. responsibilities for emergency preparedness planning, updating of emergency plans and procedures, and coordination of plans with other applicable
/
X X
X organizations.
c.
Public information officer.
X X
d.
Health physicist, with a line of succession, including
)
responsibilities for onsite and offsite dose assessments and X
X recommending protective actions.
1 j
e.
The individual (s), with a line of succession, in charge of X
X recovery operations.
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E ne or more of these positions may be assigned to the same incumbent.
O
- Emergency plans for research and test reactors with authorized power levels less than or equal to 100 W thennal should include as a mimimum those items that are marked with an asterisk. i I
Applicability by Reactor Operating Power Levels
> 100 W to
> 100 KW Evaluation Items
< 100 KW to < 2 N
> 2 MW 3.
The emergency plan should specify which positions have the following responsibilities and authorities:
a.
Termination of an emergency and initiation of recovery.
X X
X b.
Authorization of volunteer emergency workers to incur radiation exposures in excess of 10 CFR 20 limits.
X X
X
)
c.
Authorization of reentry into a reactor facility (or portion thereof) that l
required evacuation following an accident.
X X
X i
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4.0 EMERGENCY CLASSIFICATION SYSTEM PLANNING STANDARD A standardized emergency classification system will be used by all licensees and (where applicable) State and local agencies, to enhance communications and aid in implementing onsite and offs 1te protective actions.
The system of classification should consist of mutually exclusive groupings that cover the spectrum of credible accidents. Energency classes are:
Notification of Unusual Events, Alert, Site Area Emergency, and General Emergency.
The more severe classes are not appropriate for many research reactors.
Each class should be associated with a set of emergency action levels that include reactor systems indications and effluent parameters.
Applicability by Reactor Operating Power Levels
> 100 W to
> 100 KW l
Evaluation Item
< 100 KW to < 2 MW
> 2 MW 1.
The ;mergency plan should contain:
a.
An emergency classification system consistent with the planning standard above.
X X
X i
2.
Prepare implementing procedures for each class of emergency and list procedures by title in the emergency pl an.
X X
1 3.
A statement that appropriate State and local governmental agencies have adopted identical emergency classes.
X.
5.0 EMERGENCY ACTION LEVELS PLANNING STANDARD The plan should specify Emergency Action Levels (EALs) that are specific to the licensed activity and consistent with Appendix I.
EALs that initiate protective actions for members of the general public onsite shall use values of 1 rem whole body or 5 rem thyroid.
l Applicability by Reactor Operating Power Levels
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> 100 W to
> 100 KW j
Evaluation Items
< 100 KH to 1 2 MW
> 2 MW l
l 1.
Emergency action levels based on actual or potential l
radiological exposures.
Each I
facility's plan should describe f
specific instrument readings, l
observations or judgements that I
will be used to initiate emergency f
measures consistent with Appendix I.
X X
X
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i 6.0 EMERGENCY PLANNING ZONES PLANNING STANDARD The reactor owner / operator of a facility that identifies radiological emergencies which could result in offsite plume exposures exceeding I rem whole body or 5 rem thyroid shall identify an emergency planning zone (EPZ).
For many research reactors, this EPZ need not extend beyond the operations boundary.
Applicability by Reactor Operating Power levels
> 100 W to
> 100 KW Evaluation Items
< 100 VW to 1 2 MW
> 2 MW 1.
The emergency plan shall identify the EPZ.
X X
X 2.
If the EPZ is not consistent with Appendix II, the plan shall include an acceptable basis for the EPZ.
X X
X l
j _ _ _ _ _ _ _ _ - _ _ _ - _ _ _ _ _ _ _ _
7.0 EMERGENCY RESPONSE PLANNING STANDARD Emergency response measures shall be identified for each class of emergency and should be related to specific action levels.
Applicability by Reactor Operating Power Levels
> 100 W to
> 100 KW i
Evaluation Items
< 100 KH to < 2 PW
> 2 MW 1.
The emergency plan should cover the following emergency notification information:
a.
The assurance that emergency notification rosters that would be used to mobilize the emergency organization and supporting agencies are accessible from communication stations.*
X X
X b.
The assurance that notification contacts for licensee support organizations (e.g., fire, medical, ambulance, etc.) can be made any time.*
X X
X 2.
The emergency plan should cover the following assessment considerations:
a.
Identification of any effluent monitoring instruments, calibration frequency and correlation of their readings with quantities of released radionuclides.
X X
b.
The methods used to correlate quantities of actual or projected releases of radionuclides to offsite dose projections (usually by hand calculations).
X X
- Emergency plans for research and test reactors with authorized power levels less than or equal to 100 W thermal should include as a minimum those items that are marked with an asterisk.
Applicability by Reactor Operating Power Levels
> 100 W to
> 100 KW l
Evaluation Items
< 100 KW to 1 2 MW
> 2 MW c.
The identification of fixed and portable instruments and methods used to measure and confirm projected radiation dose rates and contamination levels inside and outside of the reactor facility following an accident.
X X
X d.
The methods used to determine radionuclide release rates if fixed l
assessment instrumentation is either j
inoperable or off scale.
X X
X e.
The method used to determine onsite radiation doses to personnel during an emergency.*
X X
X 3.
The emergency plan should cover the following corrective actions:
l a.
For each emergency class, the type of action that could mitigate or correct the problem.
X X
X i
b.
The requirements and commitments to assure that actions such as fire control, repair and damage control, can be effectively carried out.
X X
X 4.
The emergency plan should cover the following protective actions:
i a.
The capability to account for individuals within the operations boundary i
within 30 minutes after initiation of an emergency event.
X
.X X
i b.
The means used to notify, advise i
and evacuate (if necessary) persons within the operations boundary or within the 1
appropriate EPZ following initiation of an emergency.
X_
X X
Umdrgency plans for research and test reactors _ with authorized power levels less than or equal to 100 W thermal should include as a minimum those items that are marked with an asterisk.
Applicability by Reactor Operating Power Levels
> 100 W to
? 100 KW Evaluation Items
< 100 KW to12MW
> 2 ffW 5.
The emergency plan should include protective action values for each of the following categories:
a.
Allowable emergency exposure levels for:
i (1) rescue of personnel, (lifesaving f
activities)
X X
X (2) taking corrective actions related
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to reactor safety.
X X
X b.
Recommend protective actions for areas outside the Operations Boundary for whole body and thyroid exposures.
X 6.
The emergency plans should include an I
emergency health physics program, including coverage of the following items:
a.
Protective clothing (e.g.,
coveralls, booties, gloves, head covers, etc.)
X X
X i
b.
Respiratory protection.
X X
c.
Dosimeter which would be appropriate for emergency l
conditions.
X X
X f
d.
Dose rate and contamination moni toring.
X X
X e.
Radiation survey records.
X X
X l
i - - - - - - - - -
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8.0 EMERGENCY FACILITIES AND E0VIPMENT PLANNING STANDARD Adequate facilities and equipment for coping with postulated emergency conditions are to be available and maintained.
Applicability by Reactor Operating Power Levels
> 100 W to
> 100 KW Evaluation Items
< 100 KW to < 2 MW
> 2 MW 1.
The emergency plan should designate an energency support cente (ESC) area including provisions for tne following functions / items at or near the ESC:
a.
ESC use as a central point for receipt and evaluation of radiological data, and from which energency control directions will be given.
X X
b.
Timely ESC activation and staffing.
X X
c.
First aid and decontamination supplies in or near the ESC.
X X
2.
The monitoring and sampling equiDment systems to be used for accident assessment, should be described in the emergency plan, and'should include:
a.
Portable and fired radiological moni tors.
X X
X b.
Sampling equipment.
X X
c.
Instrumentation for specific radionuclide identification and analysis.
X, X
d.
Nonradiological monitors or indicators that may provide pertinent system or status information, such as:
(1) reactor coolant temperature, water level, flow, and power le vel.
X X
X Applicability by Reactor Operating Power Levels
> 100 W to
> 100 KW Evaluation Items
< 100 KW to 12 MW
> 2 MW (2) meteorological instruments or source of meteorological data representative of the facility location.
X 3.
The emergency plan shall identify the facilities and methods that will W used to assist contaminated persons or injured persons contaminated by radioactive material, including:
a.
Facilities for decontamination.*
X X
X I
l b.
Methods for handling contaminated l
injured personnel.*
X X
X c.
Transportation of injured personnel.*
X X
X d.
Arrangements for local hospital and medical services.*
X X
X e.
Written agreements with hospitals to assure that raadical services are available and the staff is prepared to handle radiological emergencies.
X X
4.
The emergency plan should describe the communications system that will be used for emergency communications.
The description should include:
a.
The number and locations of phones.
X X
X b.
The use of public address systems (e.g., loud speaker / security car speaker, etc.).
X X
c.
Alternate communication systems that are available for use and their location.
X X
o Dnergency plans for research and test reactors with authorized power levels less than or equal to 100 W thermal should include as a minimum those items that are marked with an asterisk.. _ _ _ _ _ _ _
Applicability by Reactor l
Operating Power Levels
> 100 W to
> 100 KW t
Evaluation Items
< 100 KW to12MW
> 2 M!
d.
The frequency and method (s) of testing communication system operability.
X X
e.
Callback from offsite authorities for verification of initial emergency messages.
X X
5.
The emergency plan should describe the contents of initial and followup emergency messages to the NRC and, if applicable, r
other offsite government agencies. To the extent known, these messages should include the following:
a.
Name, title and telephone number of caller, and the location of the incident.
X X
X b.
Description of emergency event and energency class.
X X
X c.
Date and time of incident initiation.
X X
X d.
Type of expected or actual release (airborne, waterborne, surface spill) with estimated duration times.
X X
X e.
The quantity of radionuclides released or expected to be released.
X X
X f.
Meteorology data, obtained from meteorological stations representative of the facility location, which include:
(1) Wind direction and speed from reactor site.
X i
(2)
Estimate of atmospheric stability f
class.
X I
g.
Projected (usually by hand calculations) or actual dose rates outside of operations boundary.
X X
h.
Impact of releases and recommended offsite emergency actions.
X -
Applicability by Reactor Operating Power Levels 1
> 100 W to
> 100 KW Evaluation Items
< 100 KW to 1 2 MW
> 2 MI 6.
The emergency plan should describe the inventory frequency, general contents and locations of emergency supplies and eauipment.
X X
X t
7.
The emergncy plan should specify that the portable health physics instruments, including dosimeters dedicated for emergency use during an emergency will be inspected and checked for operability quarterly and calibrated i
semiannually.
X X
X i _ _ _ - -
9.0 REC 0VERY PLANNit!G STANDARD General plans for recovery operations are to be established.
Applicability by Reactor Operating Power Levels
> 100 W to
> 100 KW Evaluation Items
< 100 KW to 1 2 MW
> 2 MW 1.
The emergency plan should specify:
a.
That recovery procedures will be written and approved for each operation prior to initiation.
X X
b.
That recovery operations and procedures will include consideration of:
(1) Contamination levels X
X X
(2) Radiation levels X
X X
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- 10. MAINTAINING EMERGENCY PREPAREDNESS PLANNING STANDARD Training programs and provisions for review and update of emergency plan and procedures are to be established for maintaining emergency preparedness.
The plan should include provisions for the conduct of periodic drills and exercises.
Applicability by Reactor Operating Power Levels
> 100 W to
> 100 KW Evaluation Items
< 100 KW to.1 2 MW
> 2 MW 1.
The emergency plan should describe an initial training and biennial retraining program for personnel with emergency response responsibilities, including:
a.
The training program for facility personnel, including l
classroom training and practical drills, to demonstrate their
(
ability to perfonn assigned functions including:
(1) personnel responsible i
for decisionmaking and I
transmitting emergency information and instructions.
X X
(2) personnel responsible for accident assessment.
X X
X (3) radiological monitoring and analysis teams.
X X
X (4) first aid and rescue personnel.
X X
X b.
Site specific programs for offsite emergency response personnel who would provide onsite support during an emergency, including:
(1) medical support personnel.
X X
Applicability by Reactor i
'4 Operating Power Levels
> 100 W to
> 100 KW Evaluation Items
< 100 KW to s 2 MW
> 2 MW (2) police, security, ambulance and fire fighting personnel.
X X
X 2.
The emergency plan should describe provisions r the conduct of exercises 77 and drills that will test the adequacy of the emergency plan, inplementing procedures and emergency equipment and ensure that emergency organization personnel are familiar with their duties.
a.
The emergency plan should provide for developing written accident scenarios to conduct exercises and drills to include:
(1) Medical emergency drills involving a simulated contaminated individual.
Offsite support organizations (i.e., anbulance and medical treatment facilities) should be invited to participate.
X X
X (2) Radiological monitoring including contamination control methods and pro-cedures, dose rate measurements, non-essential personnel evacuation and recordkeeping.
X X
X (3) Communication drills designed to test communication links between the facility and applicable Federal, State and local agencies and offsite support organizations to insure reliability of the system (s) and correct transmission, receipt and understanding of message I
contents.
X X
X i
E An exercise tests the integrated capability and a major portion of the basic elements within emergency plans and organizations.
2_/ A drill, often a component of an exercise, is a supervised instruction period designed to test, develop and maintain skills in a particular operation.
Applicability by Reactor Operating Power Levels
> 100 W to
> 100 KW Evaluation Items
< 100 KW to.1 2 MW
> 2 MW 3.
The emergency plan should establish methods for evaluating observer and participant comments
/
on exercises and drills concerning areas needing improvement, including changes in the emergency plan and procedures.
X X
4.
The emergency plan should provide for a biennial review and update of the emergency plan and implementing procedures and agreements with offsite support organizations and agencies, including:
a.
Modifications resulting from exercises and drills or changes in the facility or environs.
X X
l b.
Reviews and approvals by the l
individuals responsible for emergency planning.*
X X
X c.
provisions for forwarding applicable l
portions of the plan, agreements, and implementing l-procedures to authorized agencies and support
)
o rganiza tions.
X X
d.
Implementing procedures affected by emergency plan changes shall be revised, approved and distributed to authorized recipients within 30 days after revised plans have been issued.
X X
l
- Emergency plans for research and test reactors with authorized power levels less than or equal to 100 W thermal should include as a minimum those items that are marked with an asterisk. l
APPENDIX I EMERGENCY CLASSES AND EXAMPLE EMERGENCY ACTION LEVELS EMERGENCY CLASS EXAMPLE ACTION LEVELS NOTIFICATION OF 1.
Actual or projected radiological effluents UNUSUAL EVENTS at the site boundary exceeding 10 MPC for
)
unrestricted areas when averaged over 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or 1pmrem whole body accumulated l
in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
2.
Report or observation of severe natural phenomenon that are imminent or existing such as:
(1) earthquakes that could adversely affect the reactor safety systems, (2) high or low natural water sources that could adversely affect reactor safety systems and; (3) tornado or hurricane winds that could strike the facility.
3.
Threats to or breaches of security.
4.
Fuel damage accident that could release radio-l nuclides to confinement or containment.
5.
Fire within the facility lasting more than 10 minutes.
l N It should be noted that the radiation dose levels of the emergency action levels established for the various emergency classes are slightly different from those specified for power reactors. However, in the judgment of the NRC staff, the radiation dose levels specified are adequate for the credible accidents associated with the operation of research and test reactors, i.nd the specified action levels provide reasonable assurance that protective measures associated with the action levels specified can and will be taken, provided appropriate emphasis is also given to developing emergency action levels that relate directly to facility parameters (e.g., pool water levels and area radiation monitors).
1-1
i
. Appendix I cont.
EMERGENCY CLASS EXAMPLE ACTION LEVELS ALERT 1.
Actual or projected radiological effluents at the site boundary exceeding 50 MPC for unrestricted areas when averaged over 24 houp or 75 mrem whole body accumulated in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
2.
Radiation levels at the site boundary of 20 mrem /hr for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> whog body or five times this level to the thyroid. -
3.
Abnormal loss of water used for shielding or coolant to irradiated reactor fuel at a rate which either exhausts the initial backup system capacity or exceeds makeup capacity.
4.
Loss of radioactive material control that causes radiation dose rates or airborne radionuclides to increase ambient exposure levels by a factor of 1000 throughout the reactor building.
5.
Fire that may affect any reactor safety system (s).
6.
Other imminent or existing hazards such as (1) missles impacting on the reactor facility, (2) explosion that affects facility operation, and (3) uncontrolled release of toxic or flammable gases into the facility environs.
7.
Radiation dose rates in the reactor building reouiring evacuation of all persennel (e.g.,
100 mrem /hr for one hour throughout the reactor building.
M It should be noted that the radiation dose levels of the emergency action levels established for the various emergency classes are slightly different from those specified for power reactors. However, in the judgment of the NRC staff, the radiation dose levels specified are adequate for the credible accidents associated with the operation of research and test reactors, and the specified action levels provide reasonable assurance that protective measures associated with the action levels specified can and will be taken, provided appropriate emphasis is also given to developing emergency action levels that relate directly to facility parameters (e.g., pool water levels and area radiation monitors).
1-2
I Appendix I cont.
EMERCENCY CLASS EXAMPLE ACTION LEVELS SITE ARtA 1.
Actual or projected radiological effluents EMERGENCY at the site boundary exceeding 250 MPC for unrestricted areas when averaged over ?4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or 375 mrem accumulated in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. yf 2.
Actual or projected radiation levels at the site boundary of 100 mrem /hr for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> whole body or five times this level to the thyroid. I/
3.
Abnormal continuing loss of reactor coolant, to fuel requiring coolant, at a rate the capacity of the backup system (greater than s).
4.
Imminent loss of physical control of the reactor.
5.
Severe natural events being experienced.
Examples include:
1 (a) earthquake that is causing observable damage to the reactor safety equipment within the building.
(b) high or low natural water levels that are affecting the operability of any reactor safety system; and (c) Tornado or hurricane winds that are damaging the reactor structure.
lI It should be noted that the radiation dose levels of the emergency action levels established for the various emergency classes are slightly different from those specified for power reactors.
However, in the judgment of the NRC staff, the radiation dose levels specified are adequate for the credible accidents associated with the operation of research and test reactors, and the specified action levels provide reasonable assurance that protective measures associated with the action levels specified can and will be taken, provided appropriate emphasis is also given to developing emergency action levels that relate directly to facility parameters (e.g., pool water levels and area radiation monitors).
I-3
I
\\
Appendix I cont.
EMERGENCY CLASS EXAMPLE ACTION LEVELS GENERAL 1.
Sustained actual or projected radiation EMERGENCY 2/
levels at the site boundary of 500 mrem /hr.
2.
Actual or projected doses radiation levels at the site boundary in the exposure pathway of I rem whole body or 5 rem thyroid.
3.
Loss of reactor coolant that could lead to fuel melt.
4.
Loss of physical control of the reactor building or reactor control room and areas housing vital equi pmen t.
5.
Events that have caused or will cause massive facility or reactor system damage that could lead to fuel mel t.
1 1
l 2/ Generally not specified for facilities with authorized power levels less than or equal to 2 MW thermal and determined on a case by case basis above the level.
I-4
APPENDIX II METHOD FOR DETERMINING THE SIZE OF AN EPZ Authorized Power Level Acceptable EPZ Size
.Less than or equal to 2 MW Operations Boundary Greater than 2 MW 100 Meters but less than or equal to 10 MW Greater than 10 MW 400 Meters but less than or l
equal to 20 MW Greater than 20 MW 800 Meters but less than or equal to 50 MW Greater than 50 MW Will be determined on a l
case-by-case basis.
I
)
I t
11-1
l U.S. NUCLEAR REOULATORY C(BANNION (7 77)
Bl8LIOGRAPHIC DATA SHEET NUREG-0849 i TITLE AND SusTITLE (Adid vanwne Na. // auprepneel
- 2. (Leave e/m*/
Standard Review Plan for the Review and Evaluation of Emergency Plans for Research and Test Reactors
- 3. RECIPIENT *S ACCESSION NO.
- 7. AUTHORtS)
- 5. DATE REPORT COMPLETED l YEAR MON TH E. F. Bates, B. K. Grimes, S. L. Ramos February 19R2
- 9. PE7 FORMING ORGANIZATION NAME AND MAILING ADDRESS //nclue tip Coel DATE REPORT ISSUED l**^"
Office of Inspection and Enforcement Division of Emergency Preparedness May 1982 U.S. Nuclear Regulatory Commission
- e. (t.v. umas Washington, DC 20555
- 8. (Leave umki
- 12. SPONSORING ORGANIZATION NAME AND MAILING ADORESS (inclue les Co*/
- 10. PROJECT / TASK / WORK UNIT No.
Office of Inspection and Enforcement Division of Emergency Preparedness
- 11. CONTRACT NO.
U.S. Nuclear Regulatory Commission l'
Washington, DC 20555 j
- 13. TYPE (.Y REPORT 9E RioO cove REo finclusive densi Technical
- 15. SUPPLEMENTARY NOTES
- 14. (Leave um*/
- 16. A85TR ACT Q00 words'or less)
This document provides a Standard Review Plan for the guidance of the NRC staff to assure that complete and unifonn reviews are made of research and test reactor emergency plans.
The report is organized under ten planning standards which correspond to the guidance criteria in Draft II of ANSI /ANS 15.16 as endorsed by Revision 1 to Regulatory Guide 2.6.
The applicability of the items under each planning standard is indicated by subdivisions of the steady state thermal power levels at which the reactors are licensed to operate.
(
Standard emergancy classes and example action levels for research and test reactors which should initiate these classes are given in an i
Appendix.
- 17. KEY WORDS AND DOCUMENT AN ALYSIS 17a. DESCRIPTORS h
17b. IDENTIFIE RS/OPEN-EN DE D TE RMS
- 18. AVAILA81LITY STATEMENT
- 19. SECURITY CLASS (This report /
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