ML20055G303

Rev 3 to State of Me Ingestion Pathway Plan (Mipp) for Seabrook Station

ML20055G303
Person / Time
Site:	Seabrook
Issue date:	06/14/1990
From:	David Brown PUBLIC SERVICE CO. OF NEW HAMPSHIRE
To:
Shared Package
ML20055G297	List: ML20055G303
References
PROC-900614-01, NUDOCS 9007230022
Download: ML20055G303 (301)

Text

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9 RMD CONTROL COPY d 1 O

STATE OF MAINE INCESTION PATHWAY PLAN (MIPP)

FOR SEABROOL STATION ,

SEABROOK NEW RAMPSHIRE O

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APPROVED:

gkgG David D. Brown. Director C

• DATE:

1 Maine Emergency Management Agency REVISION: 03 ETFECTIVE DATE: 06/18/90 MIPP Rev. 3 rassue8@

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CHANGE IN8TRUCTIONS STATE OF MAINE INGESTION PATHWAY PIAN POR SEABROOK STATION REMOVE INSERT ENTIRE CONTENTS INSERT CONTENTS INCLUDING TABS REV. 3 O

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l-TABLE OF CONTENTS O]

Section ligg 1131 1.0 PURPOSE 1-1 2.0 BASIS 21 2.1 EMERGENCY PLANNING IONES 2-1 j 2.2 PROTECTIVE ACTION GUIDES 2-1 3.0 CONCEPT OF OPERATIONS 3-1  !

3.1 DESCRIPTION

3-1 3.2 AGENCY ROLES AND RESPONSIBILITIES 3-4 3.2.1 -

Comunon Responsibilities 3-4 3.2.2 Agency Roles 3-5 i

3.2.3 Role Description for State Agencies 3-5 j q 4.0 PROTECTIVE RESPONSE 4-1  !

4.1 ENVIRONMENTAL SAMPLING COLLECTION 4-1 ,

4.2 LABORATORIES 4-2 4.3 MILK CONTROL 4-3 4.4 WATER CONTROL 4-4 ,

4.5 FOOD CONTROL 4-4 4.6 DECISION PROCESS FOR SELECTION OF PROTECTIVE 4-5 ACTIONS FOR INGESTION PATNWAY EXPOSURES 4.7 PROTECTIVE ACTIONS 47 e

4.7.1 Precautionary Protective Actions 4-8 4.7.2 Preventive Protective Actions 4-9 4.7.3 Dnergency Protective Actions 4-10 MIPP Rev. 3

TABLE OF CONTENT 8 O (Continued) it.s3d.921 Ilu.t Iair.

4.8 RECOVERY 4-11 4.8.1 Recovery from Food and Water Control 4-12 5.0 PUBLIC INFORMATION 5-1 5.1 PUBLIC INFORMATION POLICIES 5-1 5.1.1 Rumor Control 5-2 5.1.2 Brochures 5-2 5.1.3 Radio /TV 5-2 6.0 FACILITIES 6-1 6.1 STATE EMERGENCY OPL" RATIONS CENTER 6-1 6.2 YORK COUNTY EMERGENCY OPERATIONS CENTER 6-1 6.3 INCIDENT FIELD OFFICE / EMERGENCY OPERATIONS 6-1 O FACILITY 6.4 PUBLIC HEALTH LABORATORY 62 6.5 MEDIA CENTER 6-2 6.6 MAINE MEDIA CENTER 6-3 7.0 AUTHORITIES 7-1 8.0 EMERGENCY RESPONSE SUPPORT 8-1 8.1 PURPOSE 8-1 8.2 COORDINATION WITH OTHER STATE AND FEDERAL 8-1 RADIOLOGICAL HEALTH OFFICIALS 8.3 NEW ENGLAND COMPACT 8-3 8.4 RESPONSE BY FEDERAL AGENCIES UNDER HASTER PLAN 8-4 8.4.1 Federal Emergency Management Agency (FD1A) 8-4 MIPP Rev. 3

TABLE OF CONTENTS

{~T (Continued) section h Iggg 8.4.2 Nuclear Regulatory Couunission (NRC) 8-5 8.4.3 Department of Energy (DOE) 8-6 8.4.4 Department of Agriculture (USDA) 8-7 4.4.5 Department of Comunerce (DOC) 8-8 >

8.4.6 Department of Defense (D0D) 8-9 8.4.7 Department of Health and Human Services (HHS) 8-9 8.4.8 Department of Transportation (DOT) 8-10 8.4.9 -

Environmental Protection Agency (EPA) 8-10 8.4.10 National Consnunications System (NC$) 8-11 APPENDICES

, A GLOSSARY. ABBREVIATIONS AND ACRONYMS,

', AND REFERENCES t

l B NEW ENGLAND COMPACT l

C NEW ENGLAND INTERSTATE RADIATION ASSISTANCE PLAN D DIVISION OF HEALTH ENGINEERING PROCEDURES E MAINE PUBLIC HEALTH LABORATORY PROCEDURES F STATE OF HAINE CHECKLIST PROCEDURES FOR THE INGESTION PATHWAY PLAN FOR SEABROOK STATION ATTACHMENTS 1 LAND USE DATA 2 EMERGENCY RESPONSE TEAM / DISASTER RESPONSE TEAM 3 FARMER NOTIFICATION PERSONNEL

- lii - MIPP Rev. 3

l LIST OF TABLIES O

L' action M Iggg 2.2-1 PAGs for Direct Exposure 2-3 2.2-2 PAGs for ingestion Pathway 2-4 3.1-1 Radiation Evaluation Equipment 3 11 3.1-2 Laboratory Analysis Capability 3-13 4.6-1 Derived Response Levels for the Milk Pathway 4-13 Preventative PAGs 4.6 2 Derived Response Levels for the Milk Pathway 4 14 Emergency PAGs 4.6-3 Long-term Derived Preventive Response Levels 4 15 for Drinking Vater 4.64 Long-term Derived Preventive Response Levels 4-17 for Vegetable Foodstuffs 4.7-1 Actions Applicable to the Pasture-Milk-Han 4 19 O Pathway 4.7 2 Percent Reduction in Radioactive Contamination 4 21 of Fruits and Vegetables by Processing 4.7 3 Actions Applicable to Soil 4-22 4.7-4 Average Daily Consumption of Specific Foods 4-23 for the General Population 5.1-1 State of Maine Comunercial Broadcast Stations - 54 Cumberland and York Counties 8.4 1 Airports in Vicinity of Seabrook Station IPZ 8-12

- iv - MIPP Rev. 3 4

I LIST OF FIGURES Section M g 1-1 Seabrook Station Ingestion Zone 1-2 3.1 1 Organisation Chart for State of Maine Response 3-10 to a Seabrook Station Accident 4.6-1 Decision Criteria for Recommended Ingestion 4 24 Pathway Protective Actions 8.4-1 Federal Emergency Response Support Organisation 8-13 0

v -V - MIPP Rev. 3

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D LIST OF EFFECTIVE PAGE8 i

= m Cover 3 1-v 3 i L0EP-1 3 1-1 and 1-2 3 2-1 to 2-4 3 3-1 to 3-13 3 4 1 to 4-24 3 5-1 to 5-4 3 6-1 and 6-2 3 7 1 and 7-2 3 I

8 1 to 8-13 3 O Annendices J l

A-1 to A-7 3 B-1 to B-51 3  !

C-1 to C-11 3 l

l D-1 to D-72 3 l E-1 to E-23 3  ;

F-1 to F-61 3 i

Attachments _

Attachment 1 3 Attachment 2 3 ,

J Attachment 3 3 l

L0EP-1 MIPP Rev. 3 t

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( SECTION 1 1.0 PRPOSE I The purpose of this plan is to describe the means by which the general public in l'theStateofMainewillbeprotectedfromthedepositienofradioactivematerial which might be released from an accident at Seabrook station. In order to protect the public, two emergency planning zones (EPZs) have been designated around osch nuclear power plant in the United States. They have been defined and are codified in Maine Public 'aw, title 375, Chapter 17, Section 960. The first zone, which contains the atto within a 10-mile radius of the plant, is called the Plume Planning Zone. This is defined in Chapter 17 as the emergency planning zone. Within this area, detailed planning, to protect the public from radiation received by inhalation of and inanersion in radioactive effluents is made. No part of Maine is included within the Plume Planning Zone for Seabrook Station. A second zone, the ingestion Planning Zone (IPZ), contains the area surrounding the power plant within 50 miles. In this sone, detailed planning is I done to mitigate effects of radioactive releases on the food chain. A portion s

of York County, Maine (refer to F15ure 1-1) is contained in the ingestion j planning zone for Seabrook Station, located in Seabrook, New Hampshire, and I operatet oy New Hampshire Yankee. I l

l Ingestion planning includes consideration of protective actions to prevent or  !

! mitigate radioactive contamination of water, allk, or food that is consumed directly or indirectly by man. Thus, animal feed for farm animals whose milk or l swat is consumed by man is also of concern. Emphasis is placed on preventing  ;

l contamination of food in preference to protective actions following i l contamination.

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Berwick Old Orchard Beach

,. , . Biddeford Saco

! ' Dayton Sanford

\., N , , , , , Eliot Shapleigh Kennebunk South Berwick N .'\ Kennebunkport Waterboro

, Kittery . . Wells inaus Lebanon York i

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SECTI0II 2

-2.0 BASIS 2.1 EMERGENCY PL&lOIING SONES The. basis for emergency planning for light water nuclear power plants is found in NUREG-0654, FEMA-REP-1. Criteria for Preparation and Evaluation of.

Radiological Emergency Respcnse Plans and Preparedness in Support of Nuclear Power Plants. This document describes the plans, personnel, facilities, and equipment which must be in place to develop a satisfactory emergency response plan. NUREG-0654, in turn, was based on earlier studies, including the Reactor Sefety Study, WASH 1400, and Planning Basis for the Development of State and Local Government Radiological Emergency Response Plans in Support of Light: Water

. Nuclear Power Plants, NUREG-0396 EPA 520/1-78 016. NUREG-0396 defines and describes the basis for the 10 mile Plume Planning Zone and the 50 mile IP2.

2.2 PROTECTIVE ACTIOF GUIDES Protect. < action Guides (PAGs) are projected dose commitment levels which warrint procactive action. The US EPA defined these levels as well as the basis for ve.a in tF e 'nual of Protective Action Guides-for Nuclear Incidents EPA 520/' M ,'

"'te guides are defined in terms of the projected dose that would occt ei ,e

. vts ve action were taken in response to a radiological incident.

No cm

• h ra er. :s prior doses is taken into account in defining them. PAGs for direec q,usure, as defined by EPA are given in Table 2.2-1.

The Food and Drug Administration of the U.S. Department of Health and Human Services has developed PAGs for use in protecting the public from radiation exposure via the Ingestion Pathway (47 FR 47073). These guides are for exposures to radionuclides such as Iodine-131, Cesium-134. Cesium-137 Strontium-90, and Strontium-89 which can be deposited on pastures, food crops, and orchards, or on meats and produce ready for sale in retail markets. Of special importance is contaminetion of milk, either directly, or through the 2-1 MIPP Rev. 3

-. .. .~ . . -.. .- . .. - - -

pasture-animal-allk pathway. The PAGs have been developed for whole body and s

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. thyroid exposures. Whole body exposure guides include consideration of the effects of radiation on bone marrow and other organs. As with the PAGs-established for direct exposure, these PAGs are defined'in terms of projected dose and no prior dose is teken into account. These PAGs are listed in Table 2.2-2. it.a basis for the ingestion pathway PAGs isLdescribed in Background for Pr9tdlrtion Action Rwcommendations: Accidental Radioactive Contamination of Food Land Animal Feeds. HHS Pr?dtem?,lon FDA 82-8196.

Protective actions at the emergency protection action guide level may include bans on harvest and embargo or destruction of food, milk or water supplies.

Protective actions would be ordered by the Governor as advised by the Division of Health Engineering (DHE), the Department of Agriculture (DOA), and the Department of Environmental Protection (DEP).

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TABLE 2.2-1

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PAGs FOR DIRECT EIPOSURE (Projected Dose in reums) ,

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Ponulation at Risk Whole-Body ( G=== ) '

M =I General Population 15 5-25 Emergency Workers 25 .125 l.

Lifesaving Activities 75 (a)~ >

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EQJI: (a) (;o sp,cific upper limit is given for thyroid exposure.  ;

' References EPA 520/1 75-001 r

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TABLE 2.2-2 l

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PAGe FOR IBGESTION PATEWAY (Projected Dose in rems) 1 Pooulation at Risk Whole-Body g Preventive Actions 0.5 1.5 Emergency Actions 5 15

Reference:

47 FR 47073-i I

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ft SECTION 3 3.0 CONCEPT OF OPERATIONS

3.1 DESCRIPTION

This section describes the Maine State agencies and organizations that would respond to a radiological release from Seabrook Station that might impact the lStateofMaine. The role of each agency and the management structure by which ltheyarecoordinatedaredescribed. An accident at Seabrook Station could impact the ingestion pathway within the State of Maine. The organizational

. structure is directed toward protection of the public frca radiation received from the ingestion of water, milk, and other food. The organizations that would 4 respond would include, but not be restricted to:

Governor's Office Maine Emergency Management Agency Maine Bureau of Health Maine Department of Agriculture Maine Department of Marine Resources Maine Department of Inland Fisheries and Wildlife l-In the-event of an accident at Seabrook Station that has the potential of affecting the State of Maine, the plant operators will notify the New Hampshire

[StatePolicewhichnotifiestheNewHampshireOfficeofEmergencyManagement which,' in turn, notifies the Maine State Police. The Maine State Police lnotifiestheMaineEmergencyManagementAgency(MEMA), the Division of Health

-Engineering (DHE) of the Bureau of Health, and the Governor's Office. MEMA would notify additional State response organizations following activation of the State Emergency Operations Center (EOC).

The State EOC is located within the offices of MEMA in Augusta, Maine. Upon notification that a response to an accident at Seabrook Station may be required, the EOC will be activated and staffed with personnel from State response 3-1 MIPP Rev. 3 l

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l lagenciesandorganizations. In addition to the Governor's office, MEMA, DHE,

.-l the Department of Agriculture (DOA), the Department of Marine Resources (DMR),

. l' and the Department of Inland Fisheries and Wildlife (IF&W) will be represented lontheEmergencyResponseTeam(ERT)attheStateEOCforingestionpathway l response. Checklists for DHE, DOA, DMR and IF&W responders having a direct role

'l in the ingestion pathway response are contained in Appendix F to this plan.

The agencies represented at the EOC are presented on Figure 3.1-1.

In addition to staffing the State EOC, personnel from DHE MDIA and State Police will .be dispatched to the Incident Field Office / Emergency operations Facility-(IF0/ EOF) in Newington, New Hampshire: the Governor's Office would dispatch personnel to the Media Center in Augusta a Maine Public Affairs Officer will proceed to the Media Center in Newington, NH and sampling teams will be dispatched to,the York County EOC in Alfred, Maine to take samples within the IPZ.

Radiological surveys and sampling will be conducted in accordance with.the DHE Procedures, Appendix D of this plan. DHE teams will collect field samples for radiological assessment within the ingestion pathway. Personnel from DMR and

-lDOAmaybeusedtosupplementDHEpersonnel,ifneeded. These samples may include the following:

-l o fruits and vegetables o maat and meat products o eggs o soil o grass and forage o milk o: drinking water o surface water l o fish and shellfish 3-2 MIPP Rev. 3 l

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.lSampleanalysiswillbeperformedatthePublicHealthLaboratory(PHL)in l accordance with standard laboratory procedures Appendix E to this plan.

Radiological evaluation equipment and laboratory capabilities are tabulated in Tables 3.1-1 and 3.1 2, respectively.  !

Protective action decisions will be made by the Governor's Office based on l reconsnendations from State agencies at the EOC. The DHE Radiological Health Specialist at the IF0/ EOF will coordinate ingestion pathway decisions for Maine lwithaccidentassessmentpersonnelofNewHampshire, Massachusetts,andtheNew lHampshireYankeeEmergencyResponseOrganization(ERO)andOffsiteResponse

[ Organization (ORO). This coordination will ensure consistency of actions among the states and will ensure effective utilization of Federal and interstate l assistance. The Radiological Health Specialist at the IF0/ EOF will keep in l l constant comunication with the Radiological Health Coordinator and the Division 1 Director of DHE at the State E00 and DHE offices to ensure that response actions are consistent with other needs within the State. 1 l

Farmers and food processing facilities within the IPZ will be contacted by I I i personnel from the University of Maine Cooperative Extension Service and Maine Department of Agriculture. They will distribute informational brochures and give farmers advice and reconsnendations as to prevention or mitigation of radioactive contamination of food products. The York County Coor.erative l

Extension Service and the USDA Food and Agriculture Council will have personnel available to provide information to= farmers who call the York County EOC.

Additional information will be transmitted to the public via News Releases on radio and television. I t

In the recovery stage, when plant conditions have stabilized, general '

information will be transmitted by News Releases and specific reconsnendations lwillbemadetheGovernor'sOfficethroughMEMAbyDEEandDOA. Based on analysis of biota samples, restrictions on shellfish harvesting or on fishing and hunting may be lifted by Department of Marine Resources and Department of Inland Fisheries and Wildlife respectively. With passage of time, weathering, and decontamination efforts, it may be possible to release food products to the 3-3 MIPP Rev. 3

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l If-it is not feasible to store, process, or treat food products, the

( )- DOA may direct that they be deotroyed.

l 3.2 -AGENCY ROLES AND RESPONSIgILITIES' 3.2.1 Common Responsibilities '

l Each agency in the Maine Emergency Response Organization has the j following responsibilities:

1. Maintain an adequate emergency response capability by i

ensuring that the agency can be notified and mobilised.- l

2. Ensure the agency can support the emergency response effort on a 24-hour basis (two 12. hour shif ts)-for the duration of a protracted emergency period.

3. Staff the State's emergency response facilities as described in Section 4.0 of this plan.

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Keep the operations telephone directory current by reporting emergency response personnel and telephone number changes as soon as-they occur to HEMA. y

5. Ensure that each member of the agency assigned to participate -

in emergency response is knowledguable of both agency and individual responsibilities as well as with agene**

implementation procedures. Each assigned individual also should be generally familiar with the plan.

6. Ensure that a copy of the complete Ingestion Pathway Plans .

including-local government plans are accessible to emergency response personnel.

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/" ' . '7.- Participate in emergency response drills and exercises. An ingestion pathway exercise will be held at least once every-six years. This exercise will be critiqued by Federal and State observers / evaluators.

3.2.2 -Agency Roles The Governor's Office, MEMA, and DHE play a primary role in response to a radiological accident impacting the. ingestion '

pathway. They comprise the team that has the decision making authority to implement emergency response' actions. DHZ, DOA and l DMR will provida personnel for sampling teams who will collect samples of soil, water, adlk, crops, forage and other biota. The methodology used is found in the DEE Procedures which the three 1

organizations keep current. Lists of personnel who form the teams j also are found in the DHE Procedures (Appendix D).

l If conditions warrant, the Department of Agriculture may embargo or destroy milk or other food products. The Department of Marine Resources may' prohibit fishing or shellfish harvesting from offshore water _or destroy ocean-fish or shellfish. The Department of Inland Fisheries and Wildlife have similar authority _regarding l wildlife or. fish harvested from inland waterways. The Bureau of Health has authority to impound, quarantine, treat or otherwise control water supplies.

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3.2. 3 - Role Description for State Agencies

1. Governor's Office - The Governor commands and controls emergency response operations through the MEMA and other State agencies. The Governor makes final decisions on protective measures based on recommendations by DHE. A i representative of the Governor's Office will be at the State EOC and another representative will go to the Media Center in Augusta in the event of an accident at Seabrook-Station which

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.g hasithe potential of having an impact on the State of Maine. '

\ If Federal assistance is required, the Governor or his representative at the EOC will request it through DOE-RAP for radiological assistance or through FEMA for non-technical assistanco. The Governor is-in charge of all activities of this office.. .

2. Maine Emeraency Manaaement Amency - Maine Emergency Management Agency (MEMA) coordinates. emergency response actions on the Governor's behalf. MEMA prepares emergency response plans, provides training, and maintains the State EOC. MEMA coordinates recovery efforts af ter ti e emergency has ended. Upon a declared State of Emergency, HEMA has authority to direct all emergency response activities. The l director of MEMA is in charge of all operations of MEMA.

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3. - Bureau of Health - The Division of Health Engineering'(DHE) of the Bureau of Health (part of the Department of Human _

Services) provides technical advice and reconsnends protective actions and recovery actions. As needed, the DHE would reconsnand to the Governor that assistance be requested from adjoining states through the New England Compact or from Federal agencies through FRERP.. In the case of the New

-England Compact, the authority to request aid has been delegated to the Coasaissioner of Human Services and then to the Director of DHE. In the event of an accident at the Seabrook Station with the potential of impacting' the State of l Maine, the Director of DHE or designee-will perform the role l of Radiological Health Coordinator at the State EOC.

l. Personnel from the Radiation Control Program will perform the

.l ' role of Radiological Health Specialist at the State EOC, at j the IF0/ EOF in Newington, New Hampshire, and at the York l County EOC in Alfred. Maine. The radiological sampling teams will be directed by the Radiological Health Coordinator after l conferring with the Radiological Health Specialist at the i

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IF0/ EOF. These teams consist of at least two persons. The G Public Health Laboratory will provide support to the monitoring teams, including providir.g cnd reading Thermoluminescent Dosimeters (TLDs) and sauple analysis. The Director of DHE is in charge of all operations of DHE. The l

Director of the Laboratory directs all PEL activities.

4. Maine Deoartment of Agriculture - DOA will dispatch the Milk Technician to the State EOC and personnel to staff sampling teams. The Director of Regulations or his designee will oversee all DOA activities, and will direct embargo of consumables as needed. DOA has authority to embargo all food products within the State of Maine.

5. Deoartment of Environmental Protection - DEP will provide l support service and technical reconuendations at the request of MEMA.

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6. Deoartment of Marine Resources - The Department of Marine Resources is a law enforcement agency and is authorized to enforce any State law. They are authorised to close taking of marine mollusks or any other marine food source and have the right to embargo or destroy food taken from the sea. In the event of a Seabrook Station accident, the Division Commander in Portland is notified, and the Division 1 Connander (Lieutenant) would report to the York County EOC.

The Deputy Chief of Marine Patrol would go to the State EOC in the event of an accident which could affect marine food sources.

7. Denartment of Inland Fisheries and Wildlife - The Department of Inland Fisheries and Wildlife is a law enforcement agency and is autbt.12ed to enforce any State law. In the event of an accident at Seabrook Station the Division A (Gray Region)

Lieutenant would (if not already there) proceed to the Gray 3-7 MIPP Rev. 3

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, N. , Regional Headquarters. If a contamination risk occurs,.

hunting and fishing can be interdicted. Inland Fisheries and Wildlife could use land vehicles and aircraft to notify 1 y rsons on public land of the need-to take protective.

, actions. j

8. .Univer'sity of Maine Coonerative Extension Service - Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of an incident at Seabrook Station, the University of Maine Cooperative Extension Service,' assisted by.the Food and  ;

Agriculture Council, the Agriculture Stabilisation and j conservation Services, the Soil Conservation Service, and the Farmers Home Administration, will notify farmers and other  !

food producers and processors within the IPZ of the need for protective actions. They maintain: lists of farmers and food producers within the IPZ of Seabrook Station. They maintain a supply of public information brochures for farmers and food processing facilities.

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9. Maine Denartment of Transnortation - The Haine Department of I 1

Transportation would deliver barricades to traffic control  !

points.  !

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10. Maine State Police - The Maine State Police would receive '

'l notification of an accident at Seabrook Station from the New l Hampshire Office of Emergency Management and would notify MEHA, DHE and the Governor's Office. They establish and L

staff traffic control points and provide law enforcement.

The Supervisor of Planning and Research directs State Police response activities. The State Police dispatcher receives notification.

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,O A chart of the Emergency Response organisation for the State of Maine.in response to an accident at seabrook Station is.

shown on Figure 3.1-1. Additional agencies may be called upon on an as-needed basis. On a long-term basis, not all agencies may be represented in the State EOC but communications would be available to enable conferencing and

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decision making.

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FIGURE 3.1-1 ORGANIZATION CHART FOR STATE OF MAINE RESPONSE TO A SEABROOK STATION ACCIDENT '

GOVERNOR l _

MAINE EMERGENCY i MANAGEMENT AGENCY ,

i COORDINATION -

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l l l l BUREAU l DEPARTMENT DEPARTMENT

! 0F MAINE DEPARTMENT OF OF INLAND

! STATE OF MARINE HEALTH AGRICULTURE TRANSPORTATION FISH AND POLICE RESOURCES WILDLIFE DIVISION OF .

HEALTH YORK COUNTY '

l ENGINEERING __________________________________________ ,

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' FARMER NOTIFICATION TEAMS I i

FIELD MONITORING TEAMS '

i O 9 0 CES ASCS SCS FanHA '

l DHE DOA DMR FARMERS HOME '

l ~ DEPARTMENT OF MARINE RESOURCES ADMINISTRATION DEPAR1 MENT OF AGRICULTURE SOIL CONSERVATION SERVICE .

DIVISION OF HEALTH ENGINEERING AGRICULTURE STABILIZATION AND CONSERVATION SERVICE i

COOPERATIVE ERTENSION SERVICE 3-10 MIPP Rev. 3-

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TABLE 3.1-1 RADIATICW ETALD& TION BQUIFIE3IT (State of Maine)

Radiation Evaluated Micro-Model # Lab Beta. 'X-Ray '

Quantity TIge* Manufacturer Pield Alpha Gammaa Neutron wave 5 Air Sampler .Radeco HD-28B X (120 VAC) 2 Air Sampler. Gelman -X (120 VAC) 250 TLD Panasonic UD-814AQ 1 1 mR-1000R-Badges I TLR-5 1 mR LLD 1 TLD Reader (1) Eberline X 1 TLD Reader Panasonic UD-702E X 1 TLD Calibrator Panasonic Mark IV X 1 mR LLD Model G 1 Liquid Scint. Beckman 7000 X X X l

1 PHA 8000 Canberra Series X Channel 8000 1 PHA 1000 Canberra Series X Channel 8100 1 PHA 8000 Nuclear Data NO-66 X Channel 1 GeLi (5I) Canberra X X 1 GeLi (202) Canberra- X X 1 3x3 Na1 Harshaw- I' X-3-11' MIPP Rev. 3

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' (Contitioed )

Radiation Evaluated' Micro-Quantity Type *- ' Manufacturer Model # Lab Field Alpha Beta Gaauna ~X-Ray Neutron wave 1 4x4-NaI Harshaw X I

1 Silicon Canberra X X 1 Beta Counter Nuclear 8100 X Chicago 1 Proportional Nuclear DSIB X X Counter Measurements 1 Proportional Nuclear PCI X X X Counter Measurements 3 Proportionni Nuclear PC3A X X X Counter Measurements 1 Proportional Nuclear PC-5 X Counter Measurements 1 Alpha / Beta Canberra 2404F X X X Counter NOTE:

The Series 8000 Multichannel' Analyzer has an~_8K microcomputer with a library of' 65 fission products for auto analysis.

The GeLi and Silicon scintillator spectroscopic detectors are all connected to the Series 8000. There are additional MCA's available and 2 bard copy printers._ The 3x3 Mal is connected to the Series 8100 MCA.

'3-12 MIPP Rev. 3

..-g a

/

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,r-t.>

TABLE 3.1-2 LABORATORY. ANALYSIS' CAPABILITY ,

(state of mine)

-Medium Analysis State Involved in Fmermency State Not Involved in Emeraency.

_ Analysis Time (Hrs.) .8-Hour Day 24-Hour' Day 8-Hour Day 24-Bour Der Milk.or Ganuma Scan 1.67 - Normal vegetation'or .4 12 (100 min. count) water

.33 - hergency. 24 72

-(20 min. count)

Water or Gross Alpha 4 - Normal (1 1) 2 precipitation Cross Beta 1.75 - Baergency 6 30 120 (25 1)

Wzter or H-3 1.5 - Normal precipitation 5 15 1

.5 - Beergency . 16 48 i

Air filter or Gross Alpha 1 67 - Normal dry deposition Gross Beta 5- 15

.23 - hergency 24 72 TLD Chip External- 200 600 200 Ganssa 600 NOTES:

Assumption cenditions. is made that contaminated samples will not need as long a counting time as under normal, non-emergency Total sample capability for gross alpha and gross beta is included under water or precipitation.

3-13 MIPP Rev. 3-

.u- . . , . _

l SECTION 4

(

4.0 PROTECTIVE RESPONSE I

lRadiologicalassessmentactivitieswillbedirectedbytheRadiologicalHealth lCoordinatorattheStateEOC. The Radiological Health Coordinator will be l lAssistedintheassessmentoftheingestionpathwaybythreeRadiologicalHealth l Specialists,onelocatedintheStateE00,onelocatedintheIF0/EOFin

)

l Newington, NH, and one located at +,he York County EOC in Alfred Maine.

lNotificationofradiologicalasseosmentpersonnelwillbeperformedin accordance with DHE Procedure No. 2.01 contai?,ed'in Appendix D of this plan.

l4.1 ENVIROIOENTAL SAMPLE COLLECTION I

lEnvironmentalsamplingwillbeperformedifaSiteAreaEmergencyinvolvinga l radioactive release or a General Emergency is declared by Seabrook dtatiorn or

'luponrequestbytheRadiologicalHealthCoordinatorattheStateE0C.

OilUpondeclarationofaSiteAreaEmergency,theRadiologicalHealthCoordinator lwillnotifyenvirontentalsamplingpersonnelusingDivisionofHealth  !

lEngineeringProcedureNo.2.01, ' Radiological Monitoring Team Notification.'

Following notification, envir.eprental stspling personnel will report to the Division of Health Engineering, 157 Capital Street, where they will receive a

_lbriefingandbeissuedpersonneldosimetryandequipment,asdescribedin lDivisionofHealthEngineeringProcedureNo.2.05S.

1 lThefirstpersonnotifiedbytheRECwillserveasthemonitoringteam l organizer who will brief the teams and issue personnel dosimetry and equipment.

I lTheRadiologicalHealthCoordinatorwilldeterminesamplingstrategiessuchas

-lthelocationswhereenvironmentalsamplesaretobeobtained,typesofsamples l most needed, and the prioritization of sample analyses. Input to the

,ldeterminationofsamplingstrategieswillconsistofadvisoriesfromthe b l Radiological Health Specialist at the State EOC, the Radiological Health

'v 4-1 MIPP Rev. 3

i

. Specialist at the IF0/ EOF and'the Department of Agriculture Representstive at

, the State E0C. The Radiological Health Coordinator will also consider '

l meteorological data, field measurement data, and projected deposition levels l.providedbyutilityaccidentassessmentpersonnel. Environmental Sampling Teams lwillbedispatchedfromandreturnsamplestotheYorkCountyEOCatAlfredas ldeterminedbytheRadiologicalHealthCoordinator. Upon determination of

-lsamplinglocations,theRadiologicalHealthCoordinatorwillnotifytheteam  ;

l organizer,whowillbrieftheteams. I The RHC will also notify the Public Health Laboratory and other laboratories providing sample analysis of the prioritization of sample analyses.. .-

I lTheenvironmentalsamplingkitscontainsurveyinstrumentswhichwillallowthe U lteamstoperformradiationsurveysoftheareasthattheyareassignedto sample, thereby extending the ability of environmental sampling teams to identify, define, and. assess the extent of radioactive contamination, t: ,

'lDirectradiationmeasurementswillbecorrelatedwithenvironmentalsample j analysis results wher. results become available. This correlation will expedite 7 the identification of affected areas in the ingestion pathway.

m

-All. samples-will be esilected in accordance with Division of Health Engineering l 4

lProcedureNo.211F.

l .

ll4.2 LABOR /20EIES The Public Health Laboratory in Augusta, Maine will serve as the central point  ;

l for receipt of all environmental and food samples collected by the Sample l l1CollectionTeams. Analyses will'be performed in accordance with the standard l-laboratoryprocedurescontainedinAppendixEofthisplan.'MainePublic

.lHealthLaboratoryProceduresfortheRadiochemistryLaboratoryDuringaNuclear l Emergency *. Table 3.1-2 of this plan shows the sample analysis capacities of l'thePublicHealthLaboratory. If needed.; additional laboratory support can be

' l?obtained.throughheactivationoftheFederalRadiologicalEmergencyResponse )

LOl Plan (FRERP)andthroughactivationoftheNewEnglandIn 4-2 x1PP Rev. 3 1

1 1

N 4

lAssistancePlan. The Food and Drug Administration Laboratory in Winchester, l' Massachusetts,andBrookhavenNationalLaboratoryinNewYorkwouldbetwoof lthefederallaboratoriesavailablethroughtheactivationofFRERP. These llaboratoriescanprovideadditionalcapabilitiesfortheanalysosofsoil, l forage, milk, water,andairsamples. The New England Interstate Radiation lAssistancePlan,whichhasbeendevelopedinaccordancewithArticleIIIofthe lNewEnglandCompactonRadiologicalHealthProtection,isprovidedasAppendixC lofthisplan. The New England Interstate Radiation Assistance Plan outlines the lmannerinwhichinterstatemutualaidandassistanceandexchangeofpersonnel lcanbeaccomplished. It includes, among other things, the availability of equipment, the laboratory capabilities of the New England states, and the procedure for requesting assista'nce from the participating states. If ladditionallaboratorycapabilitiesareneeded,theRadiologicalHealth lCoordinatorattheStateEOCwillcoordinatetheactivationoftheNewEngland l Compact. Laboratory capabilities of the New England Compact states are listed linAppendix5ofthisplan. The Radiological Health Coordinator will coordinate lneededresources,thetrackingofsamples,andsamplingstrategies.

~

4.3 MILE CONTROL Preventing contamination of milh is an important element of the Ingestion Pathway protective actions. Actions for controlling consumption of contaminated milk are classified as preventive or emergency protective actions. Preventive protective actions include two approaches. One involves protecting animal feed and ordering dairy farmers to use only stored feed rather than graaing the herd on contaminated pasture. In Maine contamination of dairy feed is not likely to be a significant problem since most feed is stored.

The second preventive protective action is applied to contaminated milk. It involves delaying ite release to market or diverting it to other uses. In addition to the above, emergency protective actions may require condemning and destroying milk supplies to prevent distribution to the market.

4-3 MIPP Rev. 3 l

1 l

i fs As recommended by DHE control of milk will be implemented by the Maine DOA by direct contact with the dairy farm owners / operators. ' Lists of consnercial dairy operations within the Seabrook Station IPZ are maintained by the Cooperative Extension Service and at the State E00.

4.4 IfATER COIITROL

, Water supplies that receive a major portion of their water from the surrounding watershed will be the focus of protective actions for water contro?. The soil may have been contaminated and- run-off may concentrate radioactivo materials ~ in the water supply. Reservoirs that are filled by pumping from flowing streams can be protected by prohibiting pumping when run-off causes an increase in contamination. As necessary, the Manager Drinking Water Program of the Division of Health Engineering will direct the control of use of water from

-potentially contaminated public surface water. supplies within the IPZ. Public surface. water supplies can be quarantined until testing for radioactivity levels-can be undertaken to confirm or refute the need for control. Wells and groundwater sources are not likely to be contaminated but'may be tested if they are muddy or otherwise suspected of having received runoff from contaminated soils.

4.5- FOOD CONTROL Field and orchard crops or other foods may be contaminated by deposition from the radioactive plume. These foods may be stored until the radioactivity has decayed or has been treated. Emergency protective actions will be used only if crops have been so heavily contaminated the preventive measures are ineffective.

Emergency actions will prevent food from entering the market place.

The DOA will implement control of harvesting, sale of crops, and, if necessary, condemnation of contaminated foods. '

Lists of the commercial agricultural facilities within the IPZ are located-at the University of Maine Cooperative Extension Service, the State EOC, and the

.IF0/ EOF.

4-4 MIPP Rev. 3

j y, _ _ _ _ _ . .

Deposition of particulates on the ground, paved surfaces, and other surfaces may increase background levels and contaminate soil. The long-term effects of this increase in background levels will be determined and actions taken as appropriate. Recovery actions are designed to address these longer term lproblemsandarediscussedinSection4.8.

Haps for recording Ingestion Pathway data, including locations of key land use, agricultural facilities, water supply location and related information, are kept at the State EOC, York County E0C, and at the IF0/ EOF. These maps, which are too large_to be included in this plan, are used to identify areas and facilities where protective actions may be necessary and for recording survey and monitoring data.

4.6 DECISION PROCESS FOR SELECTION OF PROTECTIVE ACTIONS FOR INGESTION PATHELY EXPOSURES lTofacilitaterapiddecisionmakingforingestionpathwayprotectiveactica reconsnendations, assessment personnel will use a predetermined radioactivity

=

level, or derived response level.-that corresponds to the PAG for a particular ingestion pathway. The derived response level is the amount of radiation in food, water, or animal feed that would ultimately result in exceeding the PAG if it were allowed to pass up through the food chain to the human consumers. For l example,ifthelevelofIodine-131inamilksourceexceedsthepredetermined radioactivity level the human dose-resulting from the milk pathway would exceed the PAG if preventative actions for milk were not taken. This radioactivity-level-to-PAG-dose-conversion-calculation has been described by the Food and Drug Administration of the US Department of Health and Human Services (FDA/HHS) in l43FR58790. Predetermined derived response levels for specific pathways are lcontainedinTables 4.6-1, 4.6 2, 4.6-3 and 4.6-4. Total dose consnitment from all pathways and for all nuclides taken together will be calculated in ldeterminingwhetherpreventiveoremergencyPAGshavebeenexceeded. The ratios l- of nuclides contributing to whole body dose will be sununed separately from those lcontributingtothyroiddose.

O 4-5 MIPP Rev. 3

4 u

[ ]TheRadiologicalHealthCoordinatorwillcomparethemeasuredresultsofsample h L :l analyses to the derived response levels in the assessment of the radiological

! l consequences via the ingestion pathway. The checklist for the Radiological lHealthSpecialistattheE0CcontainedinAppendixFofthisplanincludes ll lworksheetsforcalculatingtheratiosofmeasuredactivitylevelstoderived

_ response levels for contributing radionuclides for each pathway of concern.

During the time when sampling analyses are not available to confirm deposition, L easily implemented precautionary actions, e.g., removing milk producing animals from pastures or washing garden vegetables and fruits, may be recommended.

[ Preventive or emergency protective action recommendations will be issued if sample analyses indicate that the amount of radioactive material in milk, food, lorwaterexceedthePAG.

l . The following discussion traces the decision process for recossaending ingestion lpathwayprotectiveactions. To facilitate understanding Figure 4.61 describes this procedure by means of a flow chart. The term ' response level' refers to lthepredeterminedradioactlyltylevels. ..

Block #1 - Determine whether an ingestion pathway may be exposed to radiation.

l lThisdeterminationentailsuseofdataprovidedbytheutility,includingplant

! .l status,accidentprognosis,projecteddepositionlevels, meteorology (wind lspeedanddirection,precipitationandforecasts)andfieldmeasurements. These l data will be used to determine whether precautionary actions should be l implemented.

t u

Precautionary actions will include sheltering milk producing animals, putting

-lthemonstoredfeed,andissuingnewsreleasesadvisingagainstconsumptionof l" llocallygrownproduceuntilmeasurementsofradioactivitycanbemade. ,

l

(

ll .lIfprojecteddepositionlevelsexceedcheFDApreventiveresponselevelslisted in Tables 4.6-1, 4.6-3 and 4.6-4, precautionary actions will be implemented, j Upon implementing precautionary actions, proceed to the second decision step.

li l ' Block #2 - Determine whether any preventive PAGs have been exceeded for one or This 1 Olmoreofthethreeingestionpathwaysbasedonresultsofsam 4-e ze, ev. >

l

lentailsusingthederivedresponselevelslistedinTables 4.6-1, 4.6-3 and

'O- 'l4.6-4formilk,waterandotherfoodstodeterminewhetherthepreventivePAGs l'havebeenexceeded. If the answer is negative, no protective action is required l'andprecautionaryactionsmayberevisedappropriately. If the answer is lpositivefortheingestionpathways,theGovernorwillbeadvisedbythe lRadiologicalHealthCoordinatortoorderpreventiveprotectiveactionsforthe l area (s)ofconcern. Figure 4.6 1 presents the actions for the three ingestion pathways. Each involves procedures for handling ingestion materials by the appropriate State agencies followed by field testing to accurately determine the _

level of contamination. For example, the Department of Marine Resources has the authority to prohibit or restrict shellfish harvesting and may control access to harvesting areas if contamination is suspected. Collection of field samples is ldescribedintheDHEProceduresatAttachment1ofthisplan. Upon implementing preventive actions, proceed to the third decision step. l l Block #3-DeterminewhetheremergencyPAGshavebeenexceeded. This entails ldeterminingifthederivedresponselevelslistedinTable4.6-2havebeen lexceededoriftheresponselevelslistedinTables4.6-3and4.6-4havebeen exceeded by a factor of 10. If an emergency PAG has been exceeded, the Governor i will be advised by the Radiological Health Coordinator to order emergency 4 protective actions for the area (s) of concern.

4.7 PROTECTIVE ACTIONS Actions are appropriate when the health benefit associated with the achievable reduction in dose outweighs the undesirable health, economic, and social factors. It is the intent of this section to outline protective actions which should.be considered for implementation in order to reduce the consequences in the ingestion pathway if the preventative or emergency PAGs are exceeded.

Several of the actions listed below are easily implemented, and may be considered for implementation as precautionary measures during the time period when post-plume data are being evaluated, or when it is reasonable to assume from early field data that the level of radioactive material in the environment is likely to approach or exceed the PAGs. It is recommended that once protective actions are initiated, they continue for a time period sufficient to 4-7 MIPP Rev. 3 1

lmitigatetheradiologicalconsequencesviatheingestionpathway. Tables 4.7 1, l4.72and4'.7-3giveadditionalinformationconcerningcertainprotective actions.

lTofacilitateprotectiveactiondecisionmaking,copiesof'Guidanceonoffsite lEmergencyRadiationMeasurementSystems-Phase 2: The Milk Pathway,'

. l FEMA REP-12 and " Phase 3: ' Water and Non-Dairy Food Pathway,' FEMA REP-13 will be maintained at the State E00 and utilized as needed. A copy of HHS Publication FDA 82-8196 also will be maintained at the State EOC as a further lprotectiveactiondecisionmakingguide. Tables 4.7-1, 4.7-2 and 4.7-3 are excerpted from the latter publication and provide additional information concerning certain protective actions. These tables are intended for the lRadiologicalHealthCoordinatorinassessingtherelativemeritsofprotective actions that are available.

4.7.1 Precautionary Protective Actions For Pasture Removal of lactating animals from possible contaminated pastures and substitution of stored feed.

For Milk: Withholding of possibly contaminated milk from the market to allow sampling or field testing.

l For Fruit and Venetables: Avoid consumption of locally grown

-l produce until field data area analyzed. Wash garden vegetables and fruit.

l For Drinking Vater Avoid use of surface water (streams, lakes, ponds) for human and animal consumption.

Limit ingestion of potable water until field testing and source has been approved.

For Other Foods: Process to remove possible surface contamination.

4-8 MIPP Rev. 3

- . . _ - . . - ~. - ~ - . . - . . . . . ,

.

0 ,

For Fish and Shellfish: The Department of Marine Resources any-

~N_,/. suspend fishing operations of commercial fish firms, prohibit or 1 a

restrict. shellfish harvesting and may control access' to harvesting l areas.

4.7.2 Preventive Protective Actions  !

i For Pasture Removal of lactating animals from contaminats?

pastures ano substitution of uncontaminated stored feed.

Substitute source of covered uncontaminated water. Do not u6e surface waters.

I For Milk: Withholding of contaminated milk from the market to allow radioactive decay of short-lived radionuclides. This may be achieved by storage of frozen fresh milk, frozen concentrated-allk, or frozen concentrated. milk products..

( )~ Storage for prolonged times at reduced temperatures also is feasible provided ultrahlgh temperatures pasteurization-techniques are employed for processing. '

For Fruits and Venetables: Washing, brushing, scrubbing, or peeling to remove surface contamination. .

Preservation by canning, freezing, and dehydration of storage to permit radioactive decay of short-lived radionuclides.

For Grains: Milling and polishing, i

For Drinkinn Water: Avoid use of surface water (streams, lakes, ponds) for human and animal consumption.

Limit ingestion of potable water until source has been approved for consumption.

) 4-9 HIPP Rev. 3

_1___

-I'.

+

l Use bottled water- and canned beverages and juices as water

, sources.

For Other Food Products: Process to remove surface contamination.

For Meat and Meat Products Intake of Cesium-134 and Cesium-137 by an adult via the meat pathwey may exceed that of the milk pathway: therefore, levels of cesium in milk which approach the

' response level' should cause surveillance and protective actions for meat, as appropriate.

For Anhnal Feed Other Than Pasture: Action should be on a case-by-case basis taking into consideration the relationship between the radionuclide concentration in the animal feed and the concentration of the radionuclide in human food.

For Fish and Shellfish: Suspend fishing operations of- comunercial fish fims and charter fishing boats until resumption is recomunended. Identify fishing operations of coaunercial fish firins and charter fishing boats within the affected area, including estuarine waters, and implement sampling several days after the l release.

4.7.3 Dnergency Protective Actions o

Responsible officials should isolate food containing radioactive material to prevent its introduction into comunerce and determine whether condesmation or another disposition is appropriate.

Before taking this action, the following factors should be considered:

, o .The availability of other possible protective actions, o The relative proportion of the total diet by weight represented by the item in question.

4-10 MIPP Rev. 3 1

l o The importance of the particular food in nutrition and the availability of uncontaminated food or substitutes having the

]

same nutritional properties.  !

o the relative contribution of other foods and other  !

radionuclides to the total projected dose. 1 o the time and effort required to implement corrective action.

4.8 RECOURY i

When it has been determined that plant conditions have stabilised and/or are improving with no chance of worsening, the Governor or his designee se advised by ths' Division of Health Enginee,ing, shall direct recovery operations to {

?

begin. In addition, the assistance cf Federal Agencies. Including EPA. and FDA.

will be utilized, as needed.

Following the initiation of recovery operations by the Governor, the Operations officer of MINA or his designee will confer with the heads of each of the 1 agencies or departments within the State EOC to deterinine the requirements to return the affected areas to norral operations. Items to be considered include, i

but are not restricted to, the followings t

o coordinating area radiological surveys and evaluating datas o

mobilizing necessary resources, manpower. and equipments o determining traffic control requirements:

o determining cossnunication nee's o determining the need for Federal assistance: and o coordinating with other states. '

Positions established during emergency risponse will initially remain active during the recovery phase. As the recovery phase progresses, the Governor may allow selected positions of the emergency response organization to return to their non-emergency mode of operation.

h l

[\

4 11 MIPP Rev. 3 o

II

i I

4.8.1 Recovery from Food and Water Control Restrictions on food and water will be lifted when DHE has determined that levels of radioactive material found in food and water supplies have decreased below the PAGs for preventive l' actions shown in Table 2.2 2. Use will be restricted until the levels of radiation associated with the nuclear power plant j estrgency have fallen below the preventive PAG 1evels.  !

l l

t O

O 4 12 MIPP Rev. 3 i

I i

TARLE 4.6 1 N 1' DERIVED RESPONIE 1.IVELS FOR TER MIIK PATEWAY PREYWTIVE PAGs 1

Infant at Critical Seament of Pooulation(a) {

M (0) Cs-13fiCJ Cs-137(CJ jId M ]

Initial Deposition 0.13 2 3 0.5 8 I (microcurielsquare meter)

Forage Concentration (d) 0.05 0.8 1.3 0.18 3  !

(microcurie / kilogram) i i

Peak Milk Intake 0.015 0.15 0.24 0.009 0.14 (microcurielliter)

Total Intake 0.09 4 7 0.2 2.6 (microcurie) la) Nebborn infant includes fetus (pregnant woman) as critical segment of population for Iodine-131. Por other radionuclides ' infant' refers to .

child less than one year of age.

( ) (b) From fallout. Iodine-131 le the only radiciodine of significance with respect to milk contamination beyond the first day. In case of a reactor acciusnt, the cumulative intake of Iodine-133 via milk is about 22 of Iodine-131 assuming equivalent deposition.

(c) Intake of Cesium via the meat-person pathway for adults may exceed that of the milk pathways therefore, such levels in milk should cause surveillance and protective actions for meat as appropriate. If other Cesium-134 and Cesium-137 are equally present, as might be expected for reactor ac:idents, the response levels should be reduced by a factor of two.  !

(d) Fresh weight.

i

(

Reference:

47 FR 47073, October 22, 1982) l I

1 l

l I

i

\. 4-13 MIPP Rev. 3 1

. l 1

~

O O O TABLE 4.6-2 DERIVED RESPONSE LEVELS FOR THE MItX PATBUAY EMERCENCY PAGs I-131ta) Cs-134(b) Cs-137(b) Sr-90 Sr-89 Infant (C) Adult InfantIdI Adult InfantICI Adult InfantIC) Adult InfantICI Adult Initial Deposition (microcurle/ square meter) 1.3 18 20 40 30 50 3 20 80 1.600 Forage Concentrationi'I (microcurie / kilogram) 0.5 7 8 17 13 19 1.8 8 30 700 Peak Milk Intake (microcurie / liter) 0.15 2 1.5 3 2.4 4 0.09 0.4 1.4 30 Total Intake (microcurie) 0.9 10 40 70 70 80 2 7 l 26 400

(*) From fallout. Iodine-131 is the only radiolodine of significance with respect to allk contamination beyond the first day. In case of a reactor accident, the cuawilative intake of Iodine-133 via allk is about 21 of Iodine-131 assuming equivalent deposition.

(b)

Intake of cesium via the meat-person pathway for adults may exceed that of the ullk pathways therefore, such levels in allk should cause surveillance and protective sctions for : seat as appropriate. If both Cesium-134 and Cesium-137 are equally present, as might be expected for reactor accidents, the response levels should be reduced by a factor of two.

(C) i Newborn infant includes fetus (pregnant women) se critical segs.ent of population for Iodine-131.

(d) . Infant- refers to child less than one year of age.

(OI Fresh weight.

(

Reference:

47 FR 47073. October 22. 1982) 4-14 MIPF Rev. 3

h(% TAB 1.E 4.6-3 LONG-TERN DEEIVED PREVENTIVE RESPONSE LEVELS POR marraG WATER" (ONE YEAR INGESTION PERIOD)

)

Adultd Teenager d Childd Infantd I Nuclide gggggC fucilliter) fucilliter) fucilliter) f uC1/11'mer ) I I.131 Th 6.3E.28 5.7E-2 2.4E.2 1.3E-2 I I.132 Th 1.2E+1 1.4E+1 4.9E+0 3.5E.1 1 1 133 Th 2.4E+0 2.6E+0 9.1E-1 -5.85-1 1 Rb-86 Lv 6.4E.1 1.4E+0 4.7E-1 1.8E.1 I Cs.134 Lv 1.2E-2 5.8E.3 3.0E.3 1.5E-2 I Cs-136 Lv 7.6E-1 8.2E-1 4.3E-1 3.2E-1 l Cs.137 Lv 1.A7 2 6.6E.3 3.0E-3 2.28 2 I To.127m Ed 8 . 5 E. .' 8.5E.2 4.0E-2 3.6E 2 Te.229 Kd 4.0E+4 3.1E+4 9.1E+2 5.2E+2 ]

i Te.131m GI 2.4E+0 3.1E+0 2.9E+0 4.'E+0 Ts.132 31 1.0E+0 1.6E+0 2.5E+0 2.7E+C ] !

Sb.127f GI 9.8E-1 1.5E+0 2.4E+0 4.4E+0 l St-89 Bo 4.1E.1 1.6E-2 5.3E.3 5.6E-7 l Sr.90 Bo 9.9E-4 1.2E.4 5.CE.5 0.2E-4 <

Bs.140 GI 4.7E.1 6.5E-1 3.4E.1 2.6E.1 l Ho.99 Kd 9.1E+0 9.4E+0 4.6E+0 5.9E*0 -

Ru.103 GI 3.0E.1 4.3E.1 4.9E.1 7.0E.1 rO

.( /

Ru.106 Ru 105f GI GI 5.2E.3 1.2E+1 6.9E.3 7.2E.3 1.1E-2 1.8E+1 2.9E+1 5.4E+1 Co.58 GI 2.4E.1 3.8E.1 4.9E.1 8.4E-1 Co-60 GI 3.8E.2 2.8E.2 3.6E-2 6.3E.2 Y.90 GI 6.AE.3 6.8E 3 8.5E-3 1.3E.2 l Y-91 GI 5.5E.2 7.5E-2 7.7E.2 1.2E.1 I Zr.95 GI 1.3E-1 1.9E.1 2.1E.1 3 5E-1 tr.97 GI 3.4E+0 4.0E+0 3.3E+0 4.9E+0 La.14 0 GI 2.1E-1 2.9E-1 2.9E.1 4.5E.1 i Co-141 GI 3.2E-1 4.4E.1 4.5E-1 7.0E-1 ,

Co.143 GI 4.0E+0 5.1E+0 4.7E+0 7.1E+0 Co.144 GI 5.9E-3 7.9E 3 8.2E-3 1.3E.2 1 Pr-143 GI 4.6E-1 6.1E-1 6.2E-1 9.6E-1 Nd.147 GI 6.5E.1 8.9E 1 9.1E-1 1.4E+0 Np-239 GI 4.5E+0 5.8E+0 5.5E+0 8.4E+0 Pu-238f Bo 1.0E.4 1.4E.4 6.5E-5 9.6E-5 i

l Pu-239f Bo 8.8E.5 1.2E-4 5.4E.5 8.0E.5  ;

Pu-240f Bo 8.8E.5 1.2E-4 5.4E-5 8.0E.5 Pu-241f Bo 4.4E-3 5.6E.3 2.8E-3 4.0E-3 Am-241f Bo 1.7E-5 2.2E-5 1.1E-5 1.5E-5 Cm 242f Bo 2.1E.3 2.7E-3 1.3E-3 1.8E-3 Ca.244f Bo 3.5E-5 4.5E-5 2.2E-5 3.2E-5 1

0 4-15 MIPP Rev. 3

l TABl.n. 4.6-3 LONG TERN DEEIVID PREVENTIVE RESP 06?SE LEVELS FOR DaTiertiaG WATERa (ONE TEAR INGEST 13 PERIOD)

(Continuet)

Initial Water concentration Equivalent to the Preventive PAC Innestion Dose C^-4 *mantD Adultd Teenager d Childd Infantd Nuclide M C fuC1/11ter) faci /11ter) faci /11ter) fuC1/11ter)  !

l I

a Assumes a contaminated water ingestion period equivalent to the shorter time interval of the radionuclide mean lifetime or 365 days (see Appendix A).

Water is ingested at the rates given in Reference 9 for the maximum exposed individual, b

The derived response level for each radionuclide is capable of producing the preventive PAG dose. Therefore. if more than one radionuclide is present in the sample the sum of ratios technique must be used to estimmte the i 1

individual radionuclide concentrations that are permissible, e.g..

_ Cone A _ +,,,+ Conc X . g 1, Response Level A j

, Response Level X j

(- c Th= thyroid. Lv= liver, Kd= kidney. Bo= bone. Vb=whole body. GI=gastro- l intestinal track. These are critical organs for the corresponding 1

l radionuclides.

d I calculated concentrations may vary if calculation assumptions concerning l ingestion rates and done conversion factors are different from those I presented in Reference 9.

i 6.3E-2 = 6.3x10-2 = 0.063.

f Adult dose conversion factors (DCF's) were obtained from ICRP-30 10.11.12 dose conversion factors for other age groops were estimated by multiplying these adult DCF's by DCF ratios (other age group / adult) presented in Reference 9 for other nuclides having similar critical organs and retention times.

O 4-16 MIPP Rev. 3 l

j

, _ - - - . .- -- . .- -- ~- . _ .

()_

TABLE 4.6 4 LONG-TERM DEEIVED PREVENVIVE RESPONSE LEVELS FOR YEGITABLE FOODSTUFFSa,b l

i AdultC Teenc ChildC ProduceQ Leafy' Produce Leafy Produce Leafy Mggligt uC1/ko uC1/km uC1/km uCf/km uC1/ka uC1/km  ;

I-131 8.9E-2f 7.02 1 4.6E-2 6.6E-1 2.3E-2 4.7E-1  !

I-132 1.7E+1 1.4E+2 1.1E+1 1.6E+2 4.8E+0 9.8E+1 I-133 {

3.4E+0 2.7E+1 2.1E+0 3.0E+1 9.0E 1 1.8E+1 Rb-86 9.1E-1 7.1E+0 1.1E+0 1.1E+0 4.6E-1 9.4E+0 Co-134 1.7E 2 1.3E-1 4.7E 3 6.8E-2 2.9E-3 5.9E.2 Ca 136 1.1E+0 8.4E+0 6.7E 1 9.6E+0 4.3E 1 8.6E+0 Co-137 1.6E-2 1.3E-1 5.4E-3 7.7E 2 3.0E-3 6.1E-2 Te-127m 1.2E-1 9.4E-1 6.9E-2 9.9E 1 4.0E-2 8.1E-1 Te-131 3.4E+0 2.7E+1 2.5E+0 3.6E+1 2.8E+0 5.7E+1  !

Te-132 1.4E+0 1.1E+1 1.3E+0 1.9E+1 2.4E+0 5.0E+1 l Sb.1278 1.4E+0 1.1E-1 1.2E+0 1.8E+1 2.4E+0 4.8E+1 Sr-89 5.7E-1 4.5E+0 1.3E-2 1.8E-1 5.2E 3 1.1E-1 Sr-90 1.4E-3 1.1E-2 9.6E-5 1.4E-8 5.7E 5 1.2E 3 Bs 140 6.73-1 5.3E+0 5.3E 1 7.5E+0 3.4E-1 6.SE+0 Mo.99 1.3E+1 1.9E+2 7.6E+0 1.1E+2 4.5E+0 9.1E+1

, Ru-103 4.2E-1 3.3E+0 3.5E-1 5.0E+0 4.8E 1 9.7E+0

\

Ru 106 7.2E-3 5.7E-2 5.6E-3 8.1E-2 7.1E 3 1.4E 1 Rh 1058 1.7E+1 1.3E+2 1.5E+1 2.2E+2 2.9E+1 5.9E+2 Co.58 3.3E-1 2.6E+0 3.1E.1 4.4E+0 4.;E 1 9.7E+0 Co-60 2 . f> E- 2 2.0E-1 2.3E-2 3.3E-1 3.3E-2 7.1E 1 Y-90 9.6E-3 7.5E-2 7.1E-3 1.0E-1 8.3E-3 1.7E 1 Y-91 7.8E-2 6.2E-1 6.0E 2 8.7E 1 7.6E-2 1.5E+0 2r-95 1.8E-1 1.4E+0 1.5E 1 2.2E+0 2.1E-1 4.2E+0 Zr-97 4.8E+0 3.8E+1 3.3E+0 4.7E+1 3.3E+0 6.7E+1 Nb-95 4.9E-1 3.8E+0 4.3E-1 6.2E+0 6.3E-1 1.3E+1 La-140 3.0E 1 2.4E+0 2.3E-1 3.4E+0 2.8E-1 5.8E+0 Co.141 4.6E-1 3.6E+0 3.6E 1 5.2E+0 4.5E 1 9.1E+0 Ce-143 5.7E+0 4.5E+1 4.1E+0 6.0E+1 4.7E+0 9.5E+1 ,

Co-144 8.3E-3 6.5E-2 6.4E-3 9.3E-2 8.0E-3 1.6E-1 Pr-143 6.5E-1 5.1E+0 5.0E-1 7.2E-1 6.2E-1 1.2E+1 Nd-147 9.2E-1 7.3E+0 7.2E-1 1.0E+1 9.0E 1 1.8E+1 Np.239 6.3E+0 5.0E+1 4.7E+0 6.7E+1 5.5E+0 1.1E+2

-Pu-2388 1.4E-4 1.1E 3 1.1E-4 1.6E-3 6.4E-5 1.3E-3 Pu-2398 1.2E-4 9.8E-4 9.3E-5 1.3E 3 5.4E 5 1.1E-3 Pu-2408 1.2E-4 9.8E 4 9.3E-5 1.3E-3 5.4E.5 1.1E-3 Pu 2413 6.2E-3 4.8E-2 4.5E-3 6.5E-2 2.7E-3 5.6E-2 Am-2418 2.4E-5 1.9E-4 1.8E-5 2.6E-4 1.1E-5 2.2E-4 Cm-2428 2.9E 3 2.3E-2 2.2E-3 3.1E-2 1.3E-3 2.6E-2 Cm-2448 4.9E-5 3.9E-4 3.7E-5 5.3E-4 2.2E-5 4.4E-4 4-17 MIPP Rev. 3

G TABLE 4.6-4 I t

LONG-TEBt DERIVED FREYWrfIVE RESPON8E LEVELS FOR YEGETABLE FOODSTUFFSa,b (Continued)

AdultC TeenC ChildC i 1

ProduceQ Leafy' Produce Leafy Produce Leafy Nuclide utilka ac'llko nC1/ko uC1/ko uC1/km nCilke l

a Assumes an ingestion period equivalent to the shorter time interval of the radionuclide mean lifetime or 365 days (see Appendix A). Leafy vegetables and other produce are ingested at the rates given in Reference 9 for the maximum exposed individual. Also, assumes that the produce and leafy vegetables are harvested shortly after a contaminating event.

b The derived respense level for each radionuclide is capable of producing the preventive PAG dose. Therefore, if more than one radionuclide is present in the sample, the sum of ration technique must be used to estimate the individual radionuclide concentrations that are permissible, e.g.. '

Cone A 4,,,+ Cone X _ . g 1, Response Level A Response Level X C

/'

' Calculated concentrations may vary if calculation aestunptions concerning ingestion rates and dose conversion factors are different from those presented b Iteferance 9.

d Produce = Non-liafy vegetables, fruits and grains.

• Leafy = Leaty vegetables, f 8. 9E-2 = 8. 9x10E = 0. 00 9.

8 Adult dose conversion factors (DCF's) were obtained from ICRP 30 10.11.12 dose conversion factors for other age groups were estimated by multiplying these adult DCF's by DCF ratios (other age group / adult) presented in Reference 9 for other nuclides having similar critical organs and retention times. ,

O 4-18 MIPP Rev. 3 I

.i i. . ..

I TABLE 4.?-1 ACTIONS AFFLICASLE TO TSE PASTME-MILE-MAN PATEMY Radionuclide(s) for which Protective , Practically Action is Applicable Effectiveness Safety " Effort teomired)

Applicable to Cattle Provide Alternate Source I-131. Sr-90. Sr-8* Cs-137 (+)(a) (+) (+) Good of Uncontaminated Animal Feed -

Add Stable Iodine to I-131 Marginal (D) Some Bazard (+)

Cattle Ration Add Stable Calcium to Sr-89. Sr-90 Marginal Some Hazard (+)

Cattle Ration Add Binders to Cattle Ration Cs-137. Sr-89, Sr-90 Marginal Questionable (+)

Substitute Sources of Cs-137. Sr-89. Sr-90 (+) (+) (+)ICI Uncontaminated Water Applicable to Milk Condesmation of Milk I-131. Sr-89. Sr-90. Cs-137 (+) (+) ( + )(d ) M Divert Fresh Milk to I-131. Sr-89 (+) (+) (+) Good Processed Milk Products Process Fresh - Store Sr-90. Cs-137 Marginal Questionable (+)

Process Fresh - Store I-131 (+) (+) (+) Good 4-19 MIPP Rev. 3

f^Q-TABLE 4.7-1 ACTIONS APPLIC&BIA TO TM PASTRE-MIIK-MM PAM i

(Continued) j Radionuclide(s) for l Which Protective Action is Applicable Practically Effectiveness Safety (Effort Reanired)

Applicable to Milk Remove Radionuclides from I-131. Sr-89. Sr-90. Cs-137 Milk (+) (+) (+)(') Good i

(a) (+): 90Z effective (b) Marginal: Less than 901 effective.

(c) Depends on availability.

(d) Somewhat dependent on volume. *

(*) No processing plant presently available.

(

Reference:

HHS Publication FDA E2-8196) s 1

4-20 MIPP Rev. 3

~ . ..

- _. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ - _ - - _ _ _ _ . . _ _ _ _ . - -_ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ . _ _ _ _ _ _ _ . . _ _ _ _ _ . _ _ _ _ ~ _ _ . _ _._.~ _.__ _

- - - = _

fD TABLE 4.7-2 PERCENT REDUCTION IN RADIOACTIVE CONTANDI4710W OF FRUITS AND VBGETABLES ET PROCESSING Study 1 (60)

Study 2 (61) Study 3 (62)

Normal Food Preparation for Freezina. Cannina or Dchydration Canning Home Preostation External Contamination (a) Internal Combination (a)

Sr-90 Cs-137 Sr-90 Cs-137 Sr-90 Sr-90 Spinach 92 95 64 Snap Beans -

88 22 -

Carrots - -

62 -

Tomatces -

19 19 65 -

21 Broccoli 94 92 28 72 89 Peaches 100 100 100 Onions -

100 50 -

.i Potatoes -

37 Cabbage - -

24 Green Beans -

55 36 (a) l Contamination on surface is referred to as external contamination. Internal contamination is contamination of fleshy portion of product from surface deptsaltion of radionuclide.

i 4

(

Reference:

BBS Publication FDA 82-8196) l 4-Il MIPP Rev. 3

_ _ _ . _ _ . __ _ . _ _ _ _ _ _ _ _ _ _ _ . . . _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _._ - . __ _. _ = . .

.g TABLE 4.7-3 ACTIONS APPLICABLE TO SOIL i Radionuclide(s) for Action Which Protective Action is Applicable Practically

$ Effectiveness Safety _(E# fort Requiredl(D)

Applicable to Soil l

Soil Management - Minimum Tillage: Sr-90(a) j Deep Plowing with Root Inhibition Foor to Fair Not Applicable Good Sr -90 Good to Fair Not Applicable Irrigation and Leaching Sr-90 Poor Poor Liming and Fertilizing Sr-90 Poor to Fair Not Applicable Good Not Applicable Good Removing Contaminated Surface Crops Sr-90 Most Poor Not Applicable Poor to Fair Removal of Soil Surface Contamination:

Warm Weather with Vegetation Cover 'Sr-90 Good to Fair Not Applicable Poor i

Cold Weather with No Cover Sr-90 Good to Poor Not Applicable Good to Poor i

(83 Rating for reducing Sr-90:

Good - 95Z reduction.

Fair 95Z reduction.  !

Poor - 75Z reduction.

(b) Rating for effort required: l Good - Not significantly more than normal field practice.

Fair - Extra equipment or labor required.

Poor - Very great requirement of equipment, materials and labor.  !

(

Reference:

HHS Publication FDA 32-8196) l i.

Y 4-22 MIPP Rev. 3 '

_ - - - _ _ . . _ . . -_ _ . - __ -_ --_ _ _m -

[^')

QJ TABLE 4.7-4 ,

AVERAGE MILY CON 8tBtPTION OF SPECIFIC FOOD FOR TEE CENERAL P0FDIATION Average Consumption 122d fkilomramiday)

Milk. cream, cheese, ice cream (s)........................... .570 Fats o11s..................................................

Flour, cerea

.055 1............................................... .091 Bakery products............................................. .150 '

Heat........................................................ .220 Poultry..................................................... .055 i Fish and she11 fish.......................................... .025 Eggs........................................................ .055 Sugar syrups honey, molasses, etc......................... .075 Potatoes. sweet potatoes.................................... .105 Vegetables, fresh (excluding potatoes)...................... .145 Vegetables, canned, frozen, dried........................... l

.077 Vegetables, juice (single strength)......................... .009 Fruit, fresh................................................

Fruit, canned, frerwn, dried................................

.165

.056 Fruit. juice (single attength).............................. .045 Other beverages (soft drinks, coffee, alcoholic)............ .180 m Soup and gravies (mostly condensed)......................... .056

/

- Nut s a nd peanut bu t t e r . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .009 l T0TAL.......................................................

I 2.099 if a mixture of radionuclides is present, the sum of all the ratios of the projected total intake of each specific radionuclide to its specific response level for total intake should be less than one.

(a) Expressed as calcium equivalent, that is, the quantity of whole fluid allk to which dairy products are equivalent in calcium content.

(Referencen 47 FR 205. October 22, 1982) i' 4-23 MIPP Rev. 3

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l

SECTION 5 O

5.0 FUELIC INFCE RTION i

5.1 PUBLIC INFCE RTION POLICIES i

Procedures and policies facilitating access to and timely dissemination of information must be established and known by all concerned. The following general policies apply:

• i All news releases addressing state polt.cy decisions as well as releases '

not of an innediate life-saving nature shall emanate from the Governor's Office or be approved by that office for release. I New Haapanire Yankee will maintain responsibility for the release of infortantion to the news media regarding onsite conditions ,and other j corporate information. Information concerning New Hampshire Yankee emnloyees will be released by the company as it deems appropriate.

The' Governor's Director of cosaunications will be assisted by a Public 1 Affairs Officer in processing all news in a timely and accurate manner.

The Public Affairs Officer will be available to provide information for release at both the State House complex and at the Media Center.

All organisations with emergency responsibilities in this plan will refrain from making statements to the news media and will direct requests for information to the appropriate Public Affairs Officer

( located at the State House complex or the Media Center in Augusta, when i

established.

[ ,

A Maine Public Information Officer will be dispatched to the Media Center in Newington, NH to facilitate coordination of public information releases.

5-1 HIPP Rev. 3

I State agencies or individuals who desire to release any official public O information will submit the release to the closest Public Affairs officer.

All information prepared for release must be accompanied by appropriate data documents or other substantiating information as appropriate.

5.1.1 Rumor Control A rumor control telephone number (1800 452-8735), which can be reached throughout the State of Haine, will be made public in i

order to respond to public concerns and provide information and )

, emergency instructions, a

5.1.2 Brochures )

j Printed information on the effects of radiation and met. nods for 1 preventing radiological contamination of food products will be distributed to farmers and food processing facilities within the Maine pertion of the IP2 by the University of Maine Cooperative Extension Service and the Maine Department of Agriculture.

5.1.3 Radio /TV ,

5 In the event of an accident at Seabrook Station. News Releases will be the primary means of providing the public with information and instructions. If needed, the Emergency Broadcast System (ESS) will also be utilized.

News Releases and Protective Action Recosamendations for the ingestion pathway will be formulated in the State E0C in Augusta and coordinated with other states at the IF0/E0F. Once the message is prepared it will be reviewed by MEHA and the Governor's representative at the State E00 before release.

5-2 HIPP Rev. 3 -

.. . ~_ . - _ _ . - .. . . . .- - . . .-.- . - . - - . . - - . . .

l A list of Comunercial Broadcast stations in Cumberland and York Counties which can be called upon to provide public notification j and information is included as Table 5.1 1.

Information also will be provided by National Oceanic and Atmospheric Agency Weather Radio Stations.

l 1

l l

O l

~l l

l l

1 0 >-> "" "" > l

_ _ _ _ _ _ _ - _ -__-______ - _ -_- - - - - - - - - - - - - - - -- - - - - - - - - - - -- - - - - - - ' - - ~ - - - -

- - ~ ~

q-TABLE 5.1-1 STATE OF MILINE CUfGERCIAL BROADCAST STATIONS CfgerntAND AND TORE COGNTIES Location Call Frecuencv Monitorina Assianment Ph9ee Portland WTHT-FM 102.9 MHz WKCG, AIN'/WBZ. BOS Portland WTHT-AM 797-9330 560 kHz WTNT-FM Portland WGME-TV 797-9330 Channel 13 WTHT FM 797-6480 Portland WCSH-TV Channel 6 UTET-FM 772-0181 Portland WJBQ-FM 97.9 MHz '

WTHT-FM 775-6321 Portland WLOB-AM 1310 kHz WTET-FM 775-1310 Portland WMGX-FM 93.1 MHz WTET-FM 774-4561 Portland WPOR-FM 101.9 99fz j WTNT-FM 772-4248 Portland WPOR-AM 1490 kHz WTHT-FM 772-4248 l Portland WMEA-FM 90.1 MHz WTNT-FM 866-4493 l Portland / Poland WMTV-TV Channel 8 WTHT-FM Portland / Poland WHOM-FM 998-4311 ,

94.9 MHz WTNT-FM Gorham WDCI-AM 773-0209 '

1590 kHz WTRT-FM Sanford WNCT-FM 883-9539 91.1 Mffz WTET-FM

! Sanford WSME-FM 324-7021 92.1 MHz WTNT-FM t

WSIE-AM 324-7271 1220 kHz WTET-FM 324-2464 l Scarborough WDCS-FM 106.3 MHz WTNT-FM 883-9539 Westbrook WMEK-AM 1440 kHz WTNT-FM 775-6321 Biddeford WBSF-FM 91.7 IGft WTHT-FM 282-1515 Biddeford WBTC-FM 94.3 Pflz WTHT-FM 282-3121 WIDE-AM 1400 kHz WTET-FM Biddeford (Orono) ~iFiEG-77 282-5121 s

Channel 26 WTNT-FM 866-4493 Brunswick WBOR-FM 91.1 MHz L*TET-FM 725-8731 Brunswick WKXA-FM 98.9 MHz WTNT-FM 725-5507 Brunswick WKXA-AM 900 kHz WTNT-FM Portland WTNZ-FM 725-5507

-100.9 Pelz WTET-FM 772-9791 Portland WTNZ-AM 970 kHz WTNT-FM 772-9791 Seco WPIG-FM 95.9 Pfiz

, WTNT-FM 283-1235 5-4 MIPP Rev. 3

___ _ __________m - - --- - - - - - - -- - - - - - - - " ^^~ ' ' ' - - - ~ ~ - - - - - ' '

~ ~ ~ ~ -

._ . __ . _ - _ ~ . - - _ _ _ _

l l

l 1

SECTION 6 l

l 6.0 FACILITIES l I

Emergency Response Facilities utilised in the event of an accident at Seabrook l Station that has the potential of impacting the State of Maine are described in  !

l this section.

6.1 STATE BIERSENCY OFERAT10Its CENTER 1

i The State E0C is located in the State office Building in Augusta. Maine within the office of MEMA. In the event of a Seabrook Station accident, representatives of the State agencies shown in Figure 3.1 1 would proceed to the

{

State EOC. Emergency response is directed from the State E00. The primary I means of comanunication with the other emergency response facilities is by telephone. Two-way radio is a back-up means of comununication. The Public i

Health Laboratory is within easy walking distance. The Maine Media Center is  !

located in the same building as the State E00.

6.2 TORK COUNTY EstERGENCY OPERATIONS CENTER I

J The York County EOC is located in the York County Courthouse in Alfred. Maine.

Personnel from York County response agencies would proceed to the County E0C in the event of an accident at' Seabrook Station. The York County EOC will be used as a State Field EOC. and field teams will be dispatched from there.

6.3 INCIDENT FIELD OFFICE / EMERGENCY OPERATIONS FACILITY t

i The Incident Field Office / Emergency Operations Facility (IF0/ EOF) is located in Hewington, New Hampshire. The IF0/ EOF is operated by New Hampshire Yankee (NEY) and will be staffed by representatives from NNY. Federal agencies and State i lagenciesfromNewHampshire.MassachusettsandMaine. The Radiological Health {

i o S.,

Mm ,ev. ,

i

specialist of DHE and representatives of HEMA and Maine State Police will O_, s proceed to the IF0/80F in the event of an accident at Seabrook Station that has the potential of impacting the State of Haine.

6.4 FUBLIC EEALTE LABORATOET The Public Health Laboratory within the Division of Health Engineering will receive samples of food, milk, water, vegetation soil, etc., collected in the field in accordance with DHE Procedures. Samples will be processed in t accordance with priorities established by DUE accident assessment personnel.

Testing of samples will be performed at the Public Health Laboratory. If the volume of skaples exceeds the capacity of the Laboratory, samples will be dispatched to nearby laboratories available through the New England Compact or the Federal Radiological Emergency Response Plan.

6.5 HEDIA CENTER

() The Media Center is located at the Newington Town Hall in Newington, New Hampshire. This facility is utilized to prepare and distribute news releases and to permit exchanges of information among the designated spokespersons for New Hampshire Yankee State agencies and Federal agencies. News releases prepared by one of the designated spokespersons will be reviewed with his counterparts before release to the news media. A Haine Public Affairs Officer will proceed to the Media Center in the event of an accident at Seabrook Station.

• 6.6 MAINE MEDIA CENTER

• The Haine Media Center is located on the ground floor of the State Office Building in Augusta. This facility is used to distribute news releases to ths prsse from the State of Haine. A member of the Governor's Press Office will proceed to the Maine Media Center in the event of an accident at Seabrook Station.

6-2 HIPP Rev. 3

l SECTION 7 i 7.0 AUT30EITIES  !

I Title 25, Section 31 of Maine Public Law authorizes the Governor of his designee to enter into agreements and develop plans to protect the public from heaards or  !

dangers ' arising from the peaceful use of nuclear or atomic materials.'

Title 25, MRSA Section 50 Radiation Hazards, authorizes and directs the  !

Department of Human Servicco, which includes the Bureau of Health and its Division of Health Engineering, to advise the Governor on the nature of a radiation incident and to recomunend protect!ve action guidelines. l 1

1 The Radiation Protection Act, Chapter 160, revises and consolidates earlier Maine regulations in the area of radiation. It states the role of State i agencies, including the Department of Human Eervices and the Department of l Environmental Protection, in this area, Maine Public Law, Title 375, Section 783, identifies the need for disaster l

emergency plans and directs 'esch municipal, interjurisdictional, county and .

regional agency, in consultation with the bureau * (HEMA) to prepare and keep current a disaster emergency plan. Part 960 defines an ' Emergency Planning Zone' as the approximately 10 mile radius around a nuclear power plant for which  !

plans must be prepared to protect the public from the inhalation exposure pathway. This zone is frequently referred to as thn Plume Planning Zone in the industry.

The Ingestion Planning Zone is defined in Part 960 as being the approximately 50-mile radius around the nuclear plant for which plans must be made to protect the public from radiation by means of the food chain. l

-The Maine Food Law, Title 22 Chapter 551, states the authority of the Maine Department of Agriculture to sample food (Section 2164), detain, embargo or condemn food which has been misbranded or adulterated (Section 2159).

l 7-1 HIPP Rev. 3 I i l

Maine ,ublic Law. Title 12. Sections 701-725, comprise the State of Maine Inland Fisheries and Wildlife Laws which govern the practices of the Maine Department of Inland Fisheries and Wildlife.

Maine ,ublic Law. Title 12. Sections 601 62,. governs the practices of the Maine

. Department of Marine Resources.

Copies of pertinent statutes and laws are maintained at the MDM offices.

O O ,., n ,, ,ev. ,

l

_ua u u SECTION 8 O

8.0 ENERGENCY RESPONSE SUFFORT 8.1 PURPOSE This section ertablishes the arrangements for requesting and effectively utiliaing resources from other states through the New England Compact on Radiological Health Protection and from the Federal Radiological Emergency Responte Plan (FRERP).

8.2 C00BLINATION WITE OTEER STATE AND FEDERAL RADIOLOGICAL REALTR OFFICIALS Other states will be conductir.g field monitoring and dispersion calculations for their portions of the IP2. 'he IF0/E0F accident assessment staff will periodically exchange inforvation and jointly review protective action reconsnendations with the radiological health specialists of these states.

During the course of an accident. NRC staff may be stationed at the EOF and the EOC. The observations and information obtained from these Federal officials will be of value to the IF0/ EOF accident assessment staff and the decision

• makers at the E00.

Further, during the course of an accident, DHE may have a need to supplement its resources for accident assessment tasks. Two readily available sources are Federal Radiological Monitoring and Assessment Plan and the New England Compact on Radiological Health Protection. The need for additional support will be coordinated by the Radiological Health Specialist at the IF0/E0F with other response organisations. Recomunendations for assistance must be approved by the Director of DHE at the EOC and actual requests for assistance will be authorized by the Governor's representative at the E00. Needs will be determined sufficiently in advance to allow for travel delays. The needs may be based on anticipated events and a possible accident course that may not occur.

8-1 MIPP Rev. 3

l The specific needs for FRER.P and Compact resources cannct be determined in O advance of an accident and itemiaod. The State of Haine considers that it has sufficient personnel and equipment to carry out a complete response to most accident scenarios and to cover the initial response to all accidents.

Instances that may require additional support include the following:

Accidents taking place over a protracted period may require augmenting monitoring and accident assessment staff to ensure reasonable workloads and a thorough response.

Accidents that result in establishing large exclusion areas may require special equi}eent, and personnel with appropriate training, to carry out monitoring and environmental sampling within the arer..

The contamination of available equipment, or breakdowns of one-of-a-kind items may require securing replacements in order to continue monitoring, environmental sampling activities and laboratory analysis.

Prolonged exposure of personnel to high levels of radiation may reqtire supplemental personnel for monitoring and environmental sampling activities.

Recovery and reentry activities in the wake of an accident that produced widespread contamination or a high level of contamination, may require additional personnel and equipment for a prolonged period of monitoring, sampling and clean-up.

Requests for Federal assistance will b,e coordinated with the state governments lofNewHampshireandMassachusettsandwithNNYpersonnelattheIF0/E0 Fin lNewington,NH.

When requests are approved by the Director of DHE, the f.overnor or his representative will make the request for assistance from the DOE-Brookhaven facility or from FEMA Region I. For Compact-related support, the Director of DHE will complete the activation process specified in the New England Interstate 82 MIPP Rev. 3

Radiological Assistance Plan. Specific teeds will be provided by the Manager, y Radiation control Program, who will also confirm arrival times and arrange for specific pre-arrival support requested. Specific needs will be described and arrangements for support will be made.

Once the requested support has arrived and/or laboratory facilities have been arranged for, control and coordination of all technical assistance will rest with the Manager, Radiation Control Program. Upon establishment of the Federal Radiological Monitoring and Assessment Center, the Radiological Health Specialist at the IF0/ EOF will consnunicate with the Federal Offsite Technical Director to obtain radiological monitoring and assessment information.

Logistical support will be provided by MECEP.

8.3 NEW ENGLAND COMPACT The New England Compact on Radiological Health Protection (.he Compact) was adopted by the six New England states by means of legislative action and provides the means for obtaining assistance from other states. Appendix B provides detailed information about the compact. The New England Interstate Radiation Assistance Plan. Appendix C, was developed in accordance with Article III of the Compact.

~

The Plan outlines the manner in which the interstate mutual aid and assistance, and exchange of personnel, will be accomplished. It includes specific information on the channels of comununication among the states, the availability of equipment, the laboratory capabilities of the states, the procedures for requesting assistance from the party states, and the notification of party states of radiological incidents. Also, it provides clarification of the procedures for loan of personnel and e.quipment and for the coverage of financial obligations resulting form the provision of assistance.

Authority to seek assistance by means of the Compact has been delegated to the I

Consnissioner of Human Services and then to the DHE. Control of Compact resources is maintained by the States s.nd coordinated by the Compact.

8-3 HIPP Rev. 3 I

i L , . - - - -

4.4  !

D RESPONSE BY FEDERAL AGENCIES UNDER H& STER PLAN The Federal agencies and the support they may provide are identified in the

)

\

FRERP $0 FR 46542 (November 8,1985) and described below (refer to Figure 8.41 for organization of Federal support), i 8.4.1 Federal Emergency Management Agency (FEMA) i

)

i

1. Serves as the primary point of contact for requests for Federal assistance from State and local officials and other Federal agencies.

2.

Provides a lead official to coordinate and ensure the provision of appropriate nontechnical assistance including }

telecommunications support, requested by Federal, State and I local agencies.

3. Serves as the primary point of contact and coordination

• between the NRC and other Federal agencies for nontechnical response activities.

I

4. Coordinates the dissemination of all public information

('

concerning Federal nontecnnical emergency response activities and ensures that public information releases are l coordinated with State / local authorities and the NRC.

1 Establishes an interagency public affairs group.

1

5. Develops procedures to facilitate reimbursement of Federal agencies for resources expended in responding to a radiological accident.

6. Reviews and integrates all Federal agency implementation plans to ensure that all required actions and interfaces are adequately addressed.

8-4 MIPP Rev. 3

o~

8.4.2 Nuclear Regulatory Commission (NRC)

.V

1. Coordinates the technical response activities of the licensee. DOS and other Federal agencies.

2. Provides technical advice to State / local agencies.

3. Develops, for State and local agencies, a Federal technical recomunendation on protective measures which reflects all substantive dissenting views of other Federal agencies and the licensee. Participates with the lead FDM official in discussing Federal recomunendations for protective measures with appropriate State / local officials, except in situations i

, of inuainent peril to the public health and safety where the NRC may be required to make direct contact with the appropriate State / local officials regarding recomunendations >

l for protective measures. ,

4. Ensures that its radiological sonitoring act.ivities are coordinated with the Offsite Technical Director of DOE.

l

5. Coordinates the release of public information concerning the Federal technical response. Including the status of the j reactor, radiological monitoring activities, and other

! Federal technical support, and ensures that such releases are coordinated with the State (s). FDIA and the licensee.

6. Assesses the nature and extent of the radiological accident and the potential offsite consequences to the health and -

safety of the public.

1 8-5 MIPP Rev. 3 4

L, , - _ , - , ,

4.4.3 Department of Energy (Dot)

1. Coordinates the offsite radiological monitoring assessment, evaluation and reporting activities of all Federal agencies during the initial ases of an accident, and maintains a technical liaison with State and local agencies with similar responsibilities.

Ensures the orderly transfer of responsibility for coordinating the intermediate and long-term radiological monitoring function to EPA after the initial phases of the emergency at a mutually agreeable time.

2. Provides the personnel, including the Offsite Technical Director, and equipment required to coordinate and perform the offsite radiological monitoring and evaluation activitiet.

3. Assists the NRC in assessing the accident potential and in developing technical recommendations on protective measures.

4. Maintains a comenon set of all off site radiological monitoring data and provides these data and interpretation to the NRC and to appropriate State and local agencies requiring direct knowledge of radiological conditions.

5. Provides consultation and support services to all other entities (e.g., private contractors) having radiological monitoring functions and capabilities.

6. Assists the Department of Health and Human Services (HHS) and other Federal. State and local agencies by providing technical and medical advice concerning treatment of radiological contamination.

8-6 MIPP Rev. 3

. . . - - - . -- - - - - -~ -- - -.--c-ni a.

i

7. Provides telecommunications support and interface with

(. Nuclear-Emergency Search Team capabilities as provided for by existing NRC/ DOE agreement.

8. Assists other Federal agencies in developing and establishing guidelines on effective systems of emergency radiation:

detection and measurement, including instrumentation.

9.. Reviews and integrates agency radiological monitoring plans into.the Federal Radiological Monitoring and Assessment Plan.-

8.4.4 Department of Agriculture (USDA) i

1. Assists the NRC, in coordination with HHS, in developing technical recommendations for State and local officials regarding protective measures related to food and animal feed.

() 2. Assists State sai local officials, in coordination with HHS, on the impiamer.i . tion of protective measures to minimize contamination through food ingestion.

'3. Estimates and provides advice to State and local officials on .

how to minimize losses to agricultural resources from radiation effects.

4. Monitors emergency production, processing and distribution of }

food resources during a radiological accident.

5. Ensures the safety and wholesomeness of agricultural products in establishments under Federal inspection and agricultural commodities and products owned by the Commodity Credit Corporation /USDA.

-r

>t $

' 8-7 HIPP Rev. 3 1

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r, '6. Assists:in the provision of animal feed to replace j contaminated feed and pasture.

l

7. Provides advice on and assists State / local officials in the disposition of food animals affected by radiation in coordination with the EPA and HHS.

8. Provides a representative to State agricultural agencies to keep State / local officials informed of Federal efforts, l i

9. Provides a representative to HHS to facilitate cooperation between,USDA and HHS. '

I

,10. Provides emergency food coupon' assistance in the event that comunercial channels of food distribution have been disrupted.

8.4.5 Department of Conuserce (DOC)

1. Estimates the damage to industrial resources and recosusende  !

measures to desl with problems in the industrial sector.

2. Provides current and forecast meteorological information about wind direction and. speed, boundary layer mixing, precipitation and any other meteorological and hydrological i parameters affecting radiological contamination.

3. Provides gamma radiation level readings from National Weather Service offices as requested by DOE.

4. Provides a representative to both the onsite and offsite l-radiological monitoring agencies as required (i.e., DOE and l

NRC) to coordinate meteorological operations, provide meteorological and hydrological information and arrange for

l. supplemental meteorological measurements.

l

% 8-8 MIPP Rev. 3

i i

8.4.6 Department of Defense (D0D) l Provides military assistance in the form of manpower, technical )

and logistical support, including airlift services and l teleconsnunications support, as requested by FEMA.

8. 4. 7 - Department of Health and Human Services (HHS)

1. Coordinates the Federal health service response. l

2. Assists the NRC, in coordination with USDA, in developing technical recomunendations for State and local officials  ;

regarding protective measures related to food and animal feed.

3. Provides assistance to State and local government officials on the use of prophylactic drugs to minimize the radiation n doses of affected persons, U 4. Provides advice and guidance to State and local officials in assessing the impact of the offsite consequences of radiological accidents on the health of persons in the

.affected areas.

5. Provides advice to medical care personnel regarding proper medical treatment of people exposed to or contaminated by'.

radioactive macerial.

6. Ensures the capability of Public Health' Service Hospitals to respond to radiological accidents.

7. Provides resources, in coordination with the USDA, to ensure that food and animal feeds are safe for consumption.

8-9 HIPP Rev. 3

8.4.81 Department of Transportation (DOT)

1. Coordinates the Federal transportation response in support of transportation plans and actions of State and local authorities.

2. .Provides, through Regional Emergency Transportation ,

Coordinators, representation to State and local

• transportation authorities. '

3. Directs air traffic ir. and around the affected area. I 8.4.9 Environmental Protection Agency (EPA)

1. Provides resources including personnel, equipment and ,

laboratory support to assist DOE in monitoring radioactivity levels in the environment.

2. Assists the NRC, in coordination with HHS, in developing i

technical rectussendations regarding measures to protect the public health and safety, i

3. Assumes responsibility from DOE, at a mutually agreeable time, for coordinating the intermediate and long-term i N radiological monitoring function after the initial phases of the emergency.

4. Provides guidance to Federal agencies and State and local '

governments, in coordination with DOE and HHS, on acceptable emergency levels of radioactivity and radiation in the environment.

5. Assesses the nature and extent of the environmental radiation hasard.

8-10 MIPP Rev. 3

8.4.10 National Communications System-(NCS) l 1. Provides and coordinates, in response to a FDM request, the necessary coannunications for the Federal Government response in accordance with the National Plan for Comununications Support in Emergencies and Major Disasters. Is prepared to provide this support prior to a formal declaration of an emergency or major disaster.

2. Provides technical representation to appropriate State agencies to assist in meeting their comununications requirements.

New Hampshire Yankee will notify Federal agencies of an accident at Seabrook Station. Upon notification, NRC will decide whether or not to activate its organization to support onsite activities. If the onsite organization is activated. NRC will notify FEHA and DOE to prepare to support the affected States under FEMA's coordination.

. All requests for Federal assistance to the State of Maine will be authorized by the Governor or his representative. Requests will be made to FEMA Region I for

. nontechnical support and to DOE-Brookhaven for technical support. In accordance with the:FRERP, FEMA will inform other Federal agencies of State needs.

Airports in the vicinity of Seabrook Station which may _ be utilized by federal agencies are listed in Table 8.4 1.

8-11 MIPP Rev. 3

T l'

' TABLE 8.4 1 AIRPORTS IN VICINITY OF SEABROOK STATION IPZ l

Concord Municinal AirDort - Concord. NH A. Runways:

Three runways - asphalt t l

Runway 3-21 3999 ft. long x 150 ft, wide Runway 12-30 3499 ft. long x 150 ft, wide Runway 17-35 6009 ft. long x 150 ft. wide L

B. Instrumentation: i Instrument approach is possible on Runway 17 using:

Visual Omni Range Visual Omni Range / Distance Measuring Equipment C. Mainly for smaller aircraft.

1 Portland International Jetnort - Portland. ME l A. -Runways - 1 l

y Two runways - asphalt Runway 11-29 6800 ft. long x 150.ft. wide Runway 18-36 5000 ft. long x 150 ft, vide B. Instrument' approach is.possible on' Runway 11-29 using Instrument Landing System  !

C. Will accommodate Boeing 727 or comparable aircraf t.

l ll 1 Pease Air Force Base - Newinnton. NH (Seabrook Station EPZ Access)

~

A. : Runways:

One runway - asphalt

-Runway 16-34 11,320 ft. long x 300 ft. wide B. Instrumentation:

L All instrumentation capabilities are available.

C. Will accommodate any type and size aircraft.

() 8-12 MIPP Rev. 3 l

1

)

FIGURE 8.4-1 FEDesat. EMERGENCY RESPONSE SUPPORT OncANIZATION NRC/ FEMA JOINT

. Federal Technical Support COORDINATION Federal Nontechnical Support i

e NRC FDfA HQ NRC DOE 1 i

NCS '

HHS ONSITE ACCIDENT OFFSITE RADIOLOGICAL ' '

Assessment Monitoring i i DOD '

j FDIA Regional i

t i UTILITY NRC/ UTILITY s . i DOC ' '

EPA E . .

EPA s . .

USDA '

l DOT l HHS t .

DOI B ,

USDA i

8 l DOC 1

5 DOE ,

I DOD 5

901

(

Reference:

44 CFR Part 351) 8-13 MIPP Rev. 3

, . ~ , ... - - - .. .- . - , .

i APPEBIDIX A GLOSSARY Access Control The prevention of unauthorized people from entering a specific area. Road barriers and traffic control may be used to effect access control in the event of an accident at Seabrook Station.

-Agricultural Any building or tract of land used to grow crops or raise Facility livestock for production or food storage and food processing operations.

ALERT An ALERT is the second lowest level of emergency classification. Declaration of-an ALERT indicates events are in progress which involve an actual or potential substantial degradation of the level of safety at the nuclear power plant. Any radioactive release associated with this level'is expected to be limited to small fractions of the EPA Protective Action Guideline exposure levels.

Emergency Network of radio station which provides direct link between Broadcast responsible public officials and the public. EBS stations System (EBS) broadcast instructions about what steps the public should take.

Emergency The level at which an incident at a' nuclear power plant has Classification; been classified by the plant operator. The levels, listed in Level increasing severity, are UNUSUAL EVENT, ALERT, SITE AREA EMERGENCY, and GENERAL EMERGENCY.

,:s A-1 MIPP Rev. 3 i

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4 I

l Emergency Locations designated by the State and local Emergency Operations Response Organisations as assembly areas for their respective-Centers staffs. These facilities are the central command and control points for their respective Emergency Response Organisations.

Emergency A center established to coordinate the flow of technical Operations information from the onsite to the offsite Emergency Response Facility (E0F) Organisation. It is in the EOF that accident assessment activities are coordinated among Federal State, local, and utility personnel. State of Maine officials will be represented at the New Hampshire Yankee EOF in the event of an emergency at Seabrook Station.

Emergency The area covered by the Radiological Emergency kesponse Plan.

Planning The Ingestion Pathway EFZ is the area contained within 50 Zones (EPZs) miles of the plant. The boundary of the Plume Exposure EPZ is chosen to accommodate practical planning considerations and to conform as closely as possible to a 10-mile radius.

O Emergency The combination of Federal, State, local and private agencies Response designed specifically'to provide offsite capability to organisation implement emergency response.

GENERAL The most severe of the Emergency Classifications. It may EMERGENCY insolve substantial degradation or melting of the reactor's radioactive core with potential for loss of containment integrity. Release may exceed the EPA Protective Action-Guideline exposure levels beyond the power plant site boundary area.

Incident Field The IFO is the location in close proximity to the Plume Office (IFO)' Exposure EPZ at which representatives from the plant and from Federal, State and local emergency response organisations-will coordinate with each other.

A-2 MIPP Rev. 3 1

g . Ingestion The pathway through which persons may take up radioactive lj Exposure material and receive a radiation dose from internally.

Pathway deposited radioactive materials.(e.g., from ingestion of contaminated water, food, or milk).

Media Center The location where news media representatives obtain news information concerning an emergency at's nuclear power plant.

The Public Information Representatives at the Media Center will gather, coordinate, and release information as it i becomes available.

Plume An elongated and usually open and mobile mass of material that is dispersing through the atmosphere. In the case of a nuclear power plant, the material consists of radioactive particles and gases.

Plume Exposure The pathway through which persons may be exposed to Pathway radioactive material due to (a) whole-body external exposure'

[ - due to gansna radiation from the plume and-from deposited 1 material, and'(b) inhalation of radioactive particles or ,

gases such as radioactive iodine, xenon, or krypton from the passing radioactive plume.

I

-Protective Emergency measures to be taken by the public to mitigate the Action consequences of an accident by minimizing the radiological-exposures that would likely occur if such actions were not undertaken. '

l Protective The numerically projected dose level criteria of radiation Action- which act as trigger points for initiating protective Guidelines response actions.

Site The property owned by the utility in the insnediate area of the nuclear power plant site.

A-3 MIPP Rev. 3

__m ____-- -___-_--._-___________-_.-m__--..---______....__________-_____.____--_m_. _ _ _ _ . _ - _ - _ . - . . _ _ _ _ _ _ _ _ . _ _ _ _ _ _

SITE AREA- An incident which' involves actual or likely major failures of .

I

) EMERGENCY plant functions needed for the protection of the public. EPA Protective Action Guideline exposure levels except near the site boundary.

UNUSUAL EVENT The least severe of the emergency classifications.

Declaration at this level-indicates that an incident which has taken place may lead to a potential degradation of the level-of safety at the nuclear power plant.

~

i

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() A-4 MIPP Rev. 3

r 1

ABBREVIATIONS AND ACRONYMS S)

B0H (Maine) Bureau of Health I

CPCS-1 Common' Program Control Station - 1 DHS Division of Human Services DOA (Maine) Department of Agriculture DOC (U.S.) Department of Commerce DOD '(U.S.) Department of Defense DOE (U.S. ) Department of Energy DOT (U.S.). Department of Transportation DEP (Maine) Department of Environmental Protection DHE (Maine) Division of Health Engineering EBS Emergency Broadcast System -

ECL Emergency Classification Level  ;

.hY o EOC Emergency. Operations Center EOF Emergency Operations Facility EPA (U.S.) Environmental Protection Agency EPZ Emergency Planning Zone FDA Food and Drug Administration-FEMA Federal-Emergency Management Agency

.FRERP. Federal Radiological Emergency Response Plan FRMAP Federal Radiological Monitoring and Assessment Plan HHS (U.S. Department of) Health and Human Services IFO Incident Field Office

'MEMA Maine Emergency Management Agency NHY. New Hampshire Yankee

( ) A-5 HIPP Rev. 3 i

i NOAA. National' Oceanic and'Atn.ospheric Administration (of the U.S.

Departaent of Comuneree)

NRC . Nuclear Regulatory Comunission

. PAG' Prctective Action Guidelines (Proralgated by EPA)

PHL Public Health Laboratory RERP. Radiological Emergency Response Plan RHC Radiation Health Chemists SS Seabrook Station USAF U.S. Air Force USCG U.S. Coast Guard USDA U.S. Department of Agriculture O

A-6 MIPP Rev. 3

REFERENCES O

1. U.S. Department of Health and Human Services. Background for Protective Action Reconmendations: Accidental Radioactive Contamination of Food and Animal Feeds. HHS Publication, FDA 82-8196, August 1982.

-l2. Guidance on Offsite Emergency Radiation Measurement Systems. Phase 2 The l Milk Pathway, FEMA REP-12 September, 1987.

-l 3. Guidance on offsite Emergency Radiation Measuremert Systems. Phase 3 l Water and Non-Dairy Food Pathway. FEMA REP-13 September 1989.

l 4. FDIA Guidance Memorandum IN-1. The Ingestion Pathway, February, 1988.

5. U.S. Government Printing Office. Accidental Radioactive Contamination of Human Food and Animal Feeds and Reconnendations for State and Local Governments. Federal Register 47073-47083, Octobef 22, 1982.

O l6. U.S. Nuclear Regulatory Cosmission. Criteria for Preparation and-Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants. NUREG-0654/ FEMA-REP-1.

7. U.S. Nuclear Regulatory Conmission. Planning Basis for the Development of State and Local Government Radiolcgical Emergency Response Plans in Support of Light Water Nuclear Power Plants. HUREG-0396/ EPA 520/1-78-016.

8. U.S. Nuclear Regulatory Conmission. The Reactor Safety Study. WASH 1400.

9. Environmental Protection Agency. Manual of Protective Action Guides for l ~ Nuclear Incidents. EPA 520/1-'75-001-A, January 1990.

A-7 MIPP Rev. 3 i

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APPENDIX B NEW ENGLAND CGfPACT B-1 MIPP Rev. 3

l 1

l 1

TABLE OF CONTENTS

~r r

~ Document Title Iggg, New England Compact Appendix II Inventory of Radiation Evaluation B-3 Equipment New England Compact Appendix III Inventory of Laboratory Analysis B-22 Capability .

New England Compact Appendix IV Radiological Incident Reporting System B-29 Instruction Sheet for New England Compact Form RIA-1 B-31 Appendix 1 to Instruction Sheet for Form RIA-1 B-33 l

New England Compact Radiological Incident Advisory (New England B-43 Compact Form RIA-1)

Instruction Sheet for New England Compact Form RIA-2 B-44 'l New England Compact Radiological Incident Heteorological and Release B-46 l Data ' (New England Compact Form RIA-2) l Instruction Sheet for New England Compact Form RIA-3 B-48 New Engle.nd Compact Radiological Incident - Sampling Data B-49

\ (New England Compact Form RIA-3)

New England Compact Request for Radiological Assistance (New England B-50 I Compact Form RIA-4) 1 i :.

' lk B-2 HIPP Rev. 3 Q

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NEW ENGLAND COMPACT 1

1 APPENDIX II

]

INVENTORY OF RADIATION EVALUATION EQUIPMENT l

1 1

1

-1

-I l'

I lI J

L s

B-3 MIPP Rev. 3 I

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l. l l: 1

._-_.s-

g RADIATION ETALIRTION EQUIPIEIN Page 1 of 4-STATE CO M ICUT Date 12/80 Qty.

Radiation Evaluated Type Manufacturer Model,# Lab. Field Alpha Beta Gamma X-ray Neutron 4 GM Microwave Eberline E-530 X

+

a. 4 HP-270 probe l b.1 HP-260 probe 24 K 200 200 cpm ar/hr ar/hr '

1 GM Eberline E-120 X 50 50 15 0 mr/hr ar/hr ar/hr

! 5 Ion Chamber I Victoreen 470A X

a. Will also detect 1000 1000 1000 high energy alpha. R/hr R/hr R/hr '

4 GM Baird Atomic 420 X  !

100 100 100 mr/hr ar/hr ar/hr 1 GM/ Scintillation Eberline- RM-19 X X j

a. 1 Eberline SPA-3 X 1.2 Meg X i

scintillation probe cpm per i

assembly,'a 2x2 NaI ar/hr Xtal C5-137

b. The RM-19 can be used with a GM probe and other alpha, beta, gamma.

probes.

3 Scintillation Eberline PAC-1 S X 2 Meg AGA cpm

'I 1 Ion Chamber MDB Indus. HDH X 999R 999R l  !

l l

B-4  !

HIPP Rev. 3 '

I

C k

RADIATION ETALE& TION RtBIPMENT Page 2 of 4 STATE COMECTICUT (Continued) Date 12180 i

~

Radiation Evaluated Qty. Type Manufacturer Model i Lab. Field Alpha Beta Gasma X-ray Neutron Microwave 12

• Dosimeter Bendix CDV-138 X 200 nr 1 12 Dosimeter Landsverk L-50 X- 200 mr X '

9

• Dosimeter Landsverk CDV-730 X 20 R i 12 Dosimeter Bendix 622 .X 20 R 15

• Dosimeter Landsverk CDV-742 X 200 R 3 Dosimeter Capintec PHY-SEQ X 6

500 mr 500 mr 1 Dosimeter Bendix 1200-st X 200 nr 200 mr 1 Dosimeter Nuclear 050 X-Assoc. 5R 5R t 4

• Dosimeter Bendix CDV-742 X 200 R 2 Dosimeter Charger .Nrdan CDB-750 X i 2 Dosimeter Charger Bendix X 1

• Dosimeter Charger Victoreen CDV-750 X 1 Dosimeter Charger Bendix 906-5 K 1 Dosimeter Charger Capintec CAT 6 X ,

N192 I

• Additional equiptent of this type available on short notice.

B-5 MIPP Rev. 3

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~ RADIATION ETALU& TION EQUIPMENT Page 3 of 4 STATE COIMBCTICUT (Continued) Date 12180 Qty.

Radiation Evaluated

' Type l Manufacturer Model # Lab. Field Alpha Beta l Canuta X-ray Neutron Microwave 1 RF Narda 8100- X 200 mw/cm2 1 RF 915 MHz or Narda 8600 X 2450 Pfiz'

a. *E' Field and 'H" 20 sM/cm2 l' Field 10 MHz to

b. 8616 metering unit 18 GHz 3 Air Samplers, fixed X X X X j 1 Pressurized Ionization

! X Chamber with chart X recorder and e.larm setpoint 1 Liquid Scintillation Packard 3003 X Automatic, Capacity: 106 cp, 200 Samples Low Energy 1 Ganana Spectrometer Tracor TN1700 X System (Na I) Northern X 1 Canana Spectrometer Canberri S-80 I System (Ga-LI) X 1 Radon Gas Counting Johnson LLRC-2 'I I System (Kovar Cell) 1 Proportional Counter Beckman Wide X 106 cpm 106 cp, (PC) Beta 11 f

B-6 MIPP Rev. 3

= . - _ _ - - _ _ _ _ - _ _ - _ _ _ _ _ _ - _ - _ . _ _ _ _ _ _ - - _ _ _ _ - _ - _ .- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ ~ - . __. .- __ _ - _ _ _ _ - , _ _ - . .:

l ,y

~ RADIATION ETAIJIATION MUIPMENT Page 4 of 4 STATE COsmBucTICUT (Continued) Date _12/80 -[

Qty.

Radiation Evaluated Type Manufacturer Model i Lab. Field Alpha i Beta Gasuna 1

X-ray Neutron Microwave Windowless Internal Tracerlab FC-180 X Proportional Counter 106 c p, (IPC) 1 Window Type Beta Tracerlab 339 K Counter (Low Bkg)(LBBC) 106 c p, 1 Beta Counting System Eberline E-120 X (Modified Pancake 50 K I X Probe / Holder) cpm

-l k

i t

i i

1 B-7 MIPP Rev. 3

g $ C)

RADIATION ETAIR&TIog gygggy Page 1 of 1 EST- '2 STATE MgIgg Date 12128182 Radiation Evaluated Qty. Type Manufacturer Model # Lab. Field Alpha Beta Gamma X-ray Neutron Microwave

'l ZnS Eberline PAC-15A X 2 R/hr 1 Ion Chamber Victoreen CDV-700 X 30.000 Cpal -

2 Cutie Pie Ion Chamber Technical TAC X 5.000 Associates mRfhr 4 Ion Chamber CDV- X 0-500 R 715/720 2 Ion Chamber gog 1015 y 2ut-999R 1 Condenser R Victoreen 570 OmR-10R 1 Condenser R Landsverk L-64 I OmR-1000R 1 G.M. Thinwall Victoreen CDV-700 I 50mR/hr 1 2x2 Nai microR Johnson C P 2A X 2-20eRf hr 4 Air Sampler (120 VAC) Radeco HD-28B X 2 Air Sampler (120 VAC) Gelman y B-8 MIPP- Rev. 3

. . =

~

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RADIATIOd ETALE& TION RlUIPMENT Page 1 of.3-STATE M&S N ETTS Rev. 1 Date 12128182 Qty.

Radiation Evaluated Type .

Manufacturer Model # Lab. Field Alpha . Beta - Gasana 1B X-ray Neutron Microwave Windowless Gas Flow Nuclear 1 Proportional Counter X X X Measurements Corp.

1B Thin Window Gas-Flow Nuclear X ,

Proportional Counter Chicago X X Spectro Shield IB Liquid Scintillation Packard 3300 X Counter X 1B GeLi MCA System w/DEC Canberra 8100 X 1104 X i

^

2 TLD Reader Victoreen 2600 X X

181 CaF2 (Mn) Vacuum Tube ' Victoreen 2600-2 X Dosimeters X 1 Furnace Thermolyne Type X 10500 1AC L B Beta System Tracerlab I X X 1AC Proportional Counter NMC PCC11A X X X 2 Regulated Air Samplers Eberline RAS 1 X  !

2 Pulse Rate Meters with Eberline PRM6 H210 Probe Eberline HP210 X 5x105 5x105 cpm cpm B-9  !

MIPP Rev. 3

~

f RADIATION EVALE& TION EQUIPMENT Page 2 of 3 STATE M&S N ETTS Rev. 1 (Continued) Date 12/28182-

. Radiation Evaluated '

Qty. Type Manufaeturer Model # Lab. Field Alpha Beta Gasma X-ray Neutreon Microwave 1 Gamma Detector Victoreen 498 X 10R/hr 10R/hr 2 Alpha Meter Eberline PACI X 2m cpai SAG 2R/hr 9 Ganana Detector - Precision Drill X Radiation 20mR/hr Hole Instrument 1 Survey Heter Ludluni 3 X 2 Frobe Ludluni 44-3 X 2

0-200 al:/hr low energy gasuna probe Probe Ludlum 44-2 X I 0-200 mi:/hr high energy gasuna probe '

1 Ganana Detector Eberline E-120 X 50mR/hr 2 Juno Model.7 X 1mR/hr= 25R/hr 25R/hr 1000dpa alpha ,

1 Jordan Model AGB-10k I 10kR/hr i Victoreen Model 444 X 1000R/

hr 1 Ion Chamber Victoreen 440 X 300mR/

he 10 GH Victoreen CDV-770 X 50mR/hr 50mR/hr t B-10 MIPP Rev. 3  !

~

. _ _ _ _ _ _ . - - _ _ _ _ _ . - _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ - _ _ _ _ _ _ . _ + _ _ _ _ _ . _ _ _ _ _ _ _ . - _ _ _ . _ _ . - _ . . _ _ _ _ . - _ , . - _ _ . . . - _ . . , . _._

RADIATION Eva12aaYION MIGIPBENT Page 3 of 3' STATE M&Sta= _ _-m Rev. 1 (Continued) Date 12/28182-Radiation Evaluated Qty. Type Manufacturer Model # Lab. Field Alpha Beta Gamma X-ray Neutron Microwave 10 Ion Chamber Victoreen CDV-715 X 500Rlhr 10 Alpha Meter Victoreen CDV-700 X 50mR/hr 5 Ion Chamber Hud X 12R/hr 5 Cutie Pie Victoreen X 10kR/hr 10kR/hr 10 Dosimeter Charger IEHC Sb X 60 Dosimeter ,

Landsverk CDV-742 X 200mR 20 Dosimeter Landsverk X 1R 1 RM Meter Narda H616 X 10,000 Mw/cm2

(  :.

il t

3  !

B-11 MIPP Rev. 3 '

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___ _ _ _ ________-.._________-___ _ _ _ _ _ . . _ - . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ - . - - - - _ _ _ _ . . . _ _ _ _ _ _ . _ _ _ - . . _ . _ _ _ _ _ _ _ _ _ -. _. _ _ , _ _ _ _ _ _ . _ _ _ _ . , .. _ _ _ . . ._ __ . ~ . . _ _

e ei o RADIATION ETAIR&TICE W PHERT Page 1 of 3 Rev. 3

-STATE NEW BAMPSEIRE Date 11/07/85 Radiation Evaluated Qty. Type Manufacturer Model # Lab. Field Alpha Beta Gamma X-ray Neutron Microwave 1 Proportional Counter Tennelec LB-1000 X 107 cpm 107 cpm 1 TLD Reader Victoreen 2810- X 6x108 R 6x108 R 1 HCA [Ge(L1)] Nuclear Data 6620 X N/A 1 Ion Chamber Victoreen 592B X 1R 1R 3 GM Eberline E-510 X 200 200 200 mR/hr mR/hr mR/hr 3 GM Various CDW700 X 50mR/hr 50mR/hr Makes GP-200 X 20mR/hr 20mR/hr 2 Scintillation Eber11ne PAC-15A X 2x106 cpm 1 Scintillation Eberline SPA-1 X 2x106 cpm 1 Scintillation Eberline X 200mRI Mw/cm2 hr 1 Proportional Counter Eberline PAC-3G I 105 ep, 1 Scintillation Wm. B. BSP-2A I 5x100 Johnson cpm

~

MIPP Rev. 3

- _ - _ _ _ mu

RADIATION ETarmaaTICM MpfIPMENT Page 2 of_3

-STATE MEN BMfSEIRE 'Rev. 3 (Continued) Date 11/07185 Qty. Radiation Evaluated-Type Manufacturer Model # Lab. Field Alpha Beta Gamme .X-ray Neutron Microwave 2 Pressurized Ion Nuclear X Chambers 300uR/

Measurement Lab. hr

'l Scintillation Wm. B. FNSP-2A X Johnson 5x10' cpm 1 Ion Chamber Victoreen 70- X 2 Ion Chamber Victoreen 570 X (0.25 R - 100R) 2 Power Density Narda 8100 X ,

63 Dosimeter 20mW/cm2 Various CDV-138 X Makes 200 mR 1 Ion Chamber MDB 1015 I 999 R 1 Air Sampler MGD Pneu-41-3202 X 66 m3 /

matics Inc. 768 66 m3 /

hr hr 1 Liquid Scintillation NEI LSC-2 X Counter 106 Mw/cm2 3 Ion Chamber Eberline PIC-6A X 1000R/ 1000R/

hr hr 3 G-M Ratemeter Eberline RM-14 X' 3x105 3 Air Sampler Radeco H-809C X (2.5 cfa)

B-13 MIPP Rev. 3

t a "

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RADI& TIM ETALMTION MlWINEDIT Page 1'of 4 STATE REDGE ISM Rev. 2 Date 12128182 Radiation Evaluated Qty. Type Manufertuter Model #l La* hield Alpha Beta Gamma X-ray Neutron 1 Microueve Scintillation Counter 'Ludlume 60 X 3x196 CPut 1 . Beta Survey (not GM) Nuclear 2650 I

Chicago 100 mRfhr -

1 Ga m Survey Victoreen 470A X 1 R/hr 1000Rf hr 1 (8) Geiger Counter Ludlues 3 X 200 arf hr 3x105 cpan 1 Micro-R Meter Ludlum 12 S X  !

3 mR/hr 1 Geiger Cov.ater Ludlum 2 X 30mRfhr 50mRfhr 1 (1) GM Eberline E-120 X 50mRfhr 50aRfhr 1 GM (thin well) Victoreen CDV-700 X 50mR/hr 50mR/hr 2 lon Chamber Victoreen CDV-715 X 500R1hr 2 (2) Condenser R Meter Victoreen 570 I (2) 3 RAD TAD Eberline RT-1A X X X 6 Dosimeter Bendix CDV-742 X 200aK X B-15 MIFF Rev. 3

_ . _ _ _ _ ~~

o O Om RADIATION ETamaTION MlWIPRENT Page 2 of 4 STATE REDEE ISEAMP Rev. 2 (Continued) Date 12/28182 Radiation Evaluated Qty. Type Manufacturer Model i Lab. Field Alphe 1

l Beta Gamme X-ray Neutron Microwave i

1 Dosimeter Capintec PHY-SEQ X 2R 6 X 1 Dosimeter Capintec PHY-SEQ X 6 200 mR X 1 Dosimeter Landsverk L-50 X 200 as X 1 Dosimeter Nuclear 012 X 1.2 R Assoc. I 2 Dosimeter Nuclear 050- X Assoc. 5R X e

1 Dosimeter Dosimeter 1200 X Corp. 200 mm X 1 Dosimeter Dosimeter 002 X Corp. 200 mR X 1 Proportional Counter IG9C Corp. PCC 11T I I X IDS-1T 1 Low Background Beta Tracerlab OMNI- X X System Guard  ;

1 NaI/MCA (3) System TMC 400 X X Channel 3 (4) Ion Chamber les 1015 I 999 R 999 R B-16 MIPP Rev. 3

2 8 2 ) 2 3 4

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RADIAT10B E94EakTION MlWIF9BNT Page 4 of 4 Rev. 2 STATE REDBE ISIJJB Date 12/28/82 (Continued)

NOTES andfor C009ENTS:

1) Calibrated with both geiger and HP 270 probes.

2) One unit has 2.5R, 5R, 10R. and 25R chambers. The other unit has 2.5R and 25R chambers.

3) . System has 3 x 3 NaI coupled to 400 channel MCA. Output is channel by channel teletype or X-Y plot.

4) lu x 5-6 and 10 x 5-180 probes on 2 units, 10 x 5-6 probe only on 1 unit.

5) RF shielded for CRT and TV measurements. This unit is on loan from BRH.

6) One unit with two probes. This unit is on loan froer BRH.

7) Probe is for use with Narda Model 8616 meter.

8) Unit is calibrated for Ludlum Model 44-3 (Iow energy) Probe, although it will detect other gesunas.

l B-18 MIPP Rev. 3

O g O RADIATION EVARR&TIce HQqrIPgameT Page 1 of 3 Rev. 2 STATE Tusseneff Date J218f;;

Radiation Evaluated Qty. Type Manufacturer Model i Lab. Field Alpha Beta Gasman X-ray Neutron Kicrowave 1 BF3 Eberline PNC-4 I 5x105 cpm 2 Ion Chamber Victoreen 570 X 0.25 1 G.25 K to 100R to 100R 1 Ion Chamber M.H.D. 1015 I 999 R 999 R 2 Pressurized Ion Chamber Reuter- RSS-111 X 500 500 Stokes uR/hr uR/hr 1 GM Eberline E-120 I 3x10' 5x10' 3x10' cpm cpm cpm 3 Ion Chamber Victoreen 471 X 300R/hr 300R/hr

(<1mR to 300mR .ntegrate) 2 GM Eberline FRM-6A X 2x105 2x103 cpm cpm 1 GM to Scintillation Na1 Victoreen Thyac I 8x10 3 8x105 III cpm cpm 1 Silicon Barrier Herac IV I 1x10 5 counts 1 Scintillation Eberline PAC- X 2x10 6 2 R/hr 15AG cpm B-19 MIFF Rev. 3

o p

p O U RADIATION ETALRATION EQUIFIWIT Fage 2 of 3 STATE TFEMnFf Rev. 2 (Continued) .Date 12/28102_

Radiation Evaluated Qty. Type Manufacturer Model i Lab. Field Alpha Beta Casma X-ray Neutron Microwave  !

1 Diode Holiday HI-1500 X (2.54 GHz) 100ms/cm2 1 Diode Holiday 3002 I  !

E- robe 0.5 PElz to 6 CHz. I 10 v2fn2 Fs.

H-Prober 5 Mz to 300 telz, 1 Diode Narda 100 A /M2 73, 2 ,

8616 X Probe 10KHz to 220 Mfiz. 300 V/M Narda 8621 X 20aN/cm2 300 telt-4 26 GHz Ion Chamber Victoreen V715 I 500R/hr 2 GM Victoreen V700 X 3x105 50mR/hr cpm

1 Ion Chamber Nuclear Strad I 103 R/hr 103R/hr Assoc.

1 Quartz Fiber DCA 015 X 1.5 R 1.5 R 1 Quartz Fiber DCA 050 X 5.0 R 5.0 1 3 Quartz Fiber Capintec SEQ-6 X 0.5 1 0.5 R 2 TLD Reader Victoreen 2810 X 103 R 203 1 1 Gas Flow Proportional ISIC PCC-117 I Counter 5:197 5x107

& DS-1T cpm cpm B-20 MIFP Rev. 3

~. . _ _ . __ -_, _ ~_. - - _ _ .

O O O RADIATION ETAR M TI M BQUIF9 err Page 3 of 3 STATE N Rev. 2 Date 12128182 l

Radiation Evaluated Qty. Type

( Manufacturer Model # La b. Fleid Alpha Beta Gesuma 1

X-ray Neutron Microwave 100 mgalem8 Uindoor Gas Canberra 220S X Flow Counter 1 Ge-Li Gammaa Swctro- Canberra Series I meter 80 Mod.

8623 1 Liquid Scintillation Packard X

I l

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NEW ENGLAND COMPACT l

I l APPENDIX III '

L l INTENTORY j OF LABORATORY ANALYSIS CAPABILITY l

{

l l

B-22 MIPP Rev. 3 L

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LABORATURY AB&LTSIS CAPABILITY Page 1 of 1 STATE ItATME Date 1011180 Analyses Per Day State State Not Analysis Time Involved in Beerzency Involved in Emernency Meditan Analysis (hrs) 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> day 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> day 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> day 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> day Milk or Vegeta- Gamen Scan 16.7 0 45 15 45 tion Water or Gross Alpha & .7 0 30 30 100 Precipitation Gross Beta Water or H3 30 5 16 5 16 Precipitation Air Filter or Gross Alp 5a & .7 (2) (2) (2) (2)

Dry Deposition Gross Beta TLD Chip External Gamma 100 300 200 600 s

(1) Assumptica is made that conta=Insted samples may require shorter sample counting times.

(2) Total sample capability for gross alpha beta is included under water or precipitation.

B-24 MIPP Rev. 3

/ h

%J IABORATURY ANALYSIS CAPABILITY Page 1 of 1 STATE M&SSACEUSETTS Date 12/28/82 Analyses Per Day State State Not Analysis Time Involved in Emermency Medium Analysis Involved in Emermency (hrs) 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> day 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> day 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> day 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> day i

i NOTE:

THE ITEMS ON THE :'NVENTORY WITH SUPERSCRIPT *B* ARE INSTALLED AT THE STnTE LABORATORIES INSTITUTE BUILDING, JAMAICA PLAIN MASSACHUSETTS. EACH PIECE OF EQUIPMENT IS READY POR CALIBRATION.

THIS EQUIPME1T IS SCHEDULED TO BE. OPERATIONAL IN JANUARY. 1983. .

i i

i B-25 MIPP Rev. 3

f,s '

O._ O_ U i

IADDEATURY amaLYSIS CAPABILITY Page 1 of 1 STATE NEW EAMPSBIRE Date 11/07I85 Analyses Per Day State State Not Analysis Time involved in Emermency Medium Analysis Involved in Emntmency i

(hrs) 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> day 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> day 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> day 124 hour0.00144 days <br />0.0344 hours <br />2.050265e-4 weeks <br />4.7182e-5 months <br /> day

! Milk. Water or Gesana Scan 4.0 l Vegetation 2 5 2 5 i

Water or Gross Alpha & 0.7 l Precipitation (2) Gross Beta 2 (3) 8 (3) 6 (3) 24 (3) i

! Water or Tritium (H-3) 3.0 Precipitation 1 3 2 l 8 Air Filter or Gross Alpha & 0.7 4 Dry Deposition (2) Gross Beta 11 11 34 I

TLD (bulb or External Gesana 0.1 27 chip) 80 80 240 l

(1)

(2) This schedule can be maintained for a relatively short period of time (e.g., 1-5 days).

Instrumentation not available to do both analyses simultaneously.

(3) Preparation time included.

(4) This presupposes the availability of personnel.

(3) For any other NERCH members.

B-26 MIPP Rev. 3

- , ~..

. - - . . - - , . _ _ - - - - - . . - _ - ~ - _ - - _ _ - - _ - .

O O O IABORATORY AH& LYSIS CAPABILITY (I) (2) Page 1 of 1 STATE EBODE 10 ABD Dete 09/09180 Analyses Per Day State State Not Analysis Time Involved in Emergency Involved In Beersency Meditua Analysis (hrs) 8 hr. day 24 hr. day 8 hr. day 24 hr. day  !

No

• Wet i Gross Alpha Chemistry" caps- 5 (3) 10 '

bility in the Gross Beta laboratory. 10 (3) 20 Gassaa Spectra 2-3 (3) 5-6 I

l I

(1)

The Rhode Island Radiation Program has no direct control over the state laboratory doing the analysis. Any

' assistance would have to be negotiated on a case-by-case basis depending on work load in the lab at that time.

(2) The (3) estimate of total samples per working day was provided by the laboratory superviser.

Represents an approximate 50-50 split between extended in state and emergency out-of-state sampling. ,

B-27 MIPP Rev. 3

.fw 1

O O U IABORATURY AEALYSIS CAPABILITY Page 1 of 1 STATE VERIWNT Date 10101/80 Analyses Per Day State State Not Analysis Time Involved in Ehmermency Medium Analysis Involved in Baermency (hrs) 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> day 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> day 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> day 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> day Air Filter Gross Alpha / Beta 0.5 5 20 10 20 i

Water Gross Alpha / Beta 8.0 5 5 5 10 Tritium 4.0 5 20 10 20 Gasmia Scan 2.0 2 4 3 6 Milk Gasman Scan 2.0 2 4 3 6 Vegetation Fish Gammaa Scan 8.0 1 2

Earth, etc. 2 4 TLD Read Out Dose 0.1 25 50 50 100 l

(1) Sample preparation time included in all time estimates.

(2) One-person lab staff assumed for all time estimates.

(3) Analyses estimate times are mutually exclusive; i.e.

be accomplished. not al'. analyses can be done sinaltaneously but each can

l l B-28 MIPP Rev. 3

.*.- . . . . _ o_ _____-_ __ _ _ _ __ _____a

O NW ENGLAND COMPACT APPENDIX IV RADIOLOGICAL INCIDENT REPOILTING SYSTEM O

O B-29 MIPP Rev. 3

1 APPENDIX IV The purpose of Appendix IV is to provide a uniform system to be used to request assistance and exchange of data during radiological incidents occurring in the New England Compact states.

NUREG-0654/ FEMA-REP-1 was used as the reference document to construct the standard forms in order to acconsnodate the manner in which information will be available at the site of a radiological incident occurring at a nuclear power facility.

A complete set of forms and instructions has been included in this Appendix. I However, a brief summary of the intended use of these forms follows.

Form RIA-4 is used to request aid or assistance from any of the other members of the Compact. It is not necessary to use this form to request assistance.

[ However, all of the information required by RIA-4 should be contained in a request for assistance.

I 1

Form RIA-1 is used to notify other members of the Compact of a radiological incident in progress. The notice can be used, in conjunction with RIA-4. to request assistance (Item 7A/B) or to inform the other states.

1 Form RIA-2 is used to report meteorological and/or release data at the site of a I radiological incident. This form should also be used to update meteorological data as new information becomes available.

I Form RIA-3 is used to report sampling and/or monitoring data collected at the i site of a radiological incident. This data should be updated as necessary.

I r

l l B-30 MIPP Rev. 3 l

l 1 L i 1 .. .

l Q INSTRUCTION SEEET FOR NEW ENGLAND COMPACT FORM EIA-1 i

11AEL 1,1, and I are self-explanatory.

Item 4: a. Should indicate the reactor site involved. If there is more than one reactor at the site, the problem reactor should be identified (e.g.,

Millstone f2).

If the incident is a transportation accident, a quick geographic description should be given (e.g., Newton, MA, at the intersection of Route 128 and Mass.

Pike).

If the incident is at some other nuclear facility such as a reprocessing plant or navy yard, the gevgraphic location and site name should be given with a short description of the problem entered in #10 (comments).

() b. Enter the date and time the incident was initiated or reported.

Item 5: Items A, B, C and D are defined in NUREG-0654 and the degree of the emergency should be identified by the reactor when the information is made available to the State Radiation Contro1' Agency. Circle whichever letter applies.

Item E should be circled for an accident involving transportation of radioactive  ;

naterials.

Item F should be circled for any other type of incident such as a navy yard or reprocessing plant. Any additional data should be entered in $10 (comments).

• Item 6: NUREG-0654 defines several example initiating conditions for each of the emergency categories specified in Items 4A, B C and D. Each of these conditions is identified by number, and this number or numbers should be entered on this line. If more space is needed, use Item fl0 (comments). These *

('~ conditions and numbers are reproduced in Appendix 1 to this instruction sheet.

U B-31 MIPP Rev. 3

r^

(]N NB: The numerical code which identifans the problem should be provided by the nuclear plant. If it is not furnishet., as's for it before hanging up.

Itama 7 and 8: If you are requesting assistance, Circle 7A and circle the agency (s) that you are requesting assistar.ce from in Item 8.

If the data is for information only (e.g., no assistance needed now but may need help later), circle 7B and make no entry in Item 8.

If some other agency assistance or only e. specific type of assistance is needed, i circle Item 80 and explain in Item #10 (comments).

Item 9: Self-explanatory if the answer is yes, then Item #10 (consnents) should have a statement to the effect that New England Compact form (s) will follow inanediately.

Item 10: Enter any additional information not covered in previous items, but keep it brief and to the point.

l

)

I

\/

B-32 MIPP Rev. 3

s APPENDIX 1 TO INSTRUCTION SHEET FOR FORM 12A-1 EIAMPLE INITIATING CONDITIONS: NOTIFIC& TION OF UNUSUAL EVENT

1. ECCS initiated. .

2. Radiological effluent technical specificating limits exceeded.

3. Fuel damage indication. Examples:

a. High offgas at BWR air ejector monitor (greater than 500,00 uci/ sect corresponding to 16 isotopes decayed to 30 minutest or an increase of 100.00 uci/see within a 30-minute time period).

b. High coolant activity sample (e.g., exceeding coolant technical specification for iodine spike).

O c. Failed fuel monitor (PWR) indicates increase greater than 0.12 equivalent fuel failurse within 10 minutes.

4. Abnormal coolant temperature and/or pressure or abnormal fuel temperatures.

, 5. Exceeding either primary / secondary leak rate technical specification or primary system leak rate technical specification.

6. Failure of a safety or relief valve to close.

7. Loss of offsite power or loss of onsite AC power capability.

8. Loss of containment integrity r"Nuiring shutdown by technical specifications.

O B-33 MIPP Rev. 3 1

i

9. Loss of engineered safety feature or fire protection system function requiring shutdown by technical specifications (e.g., because of malfunction, personnel error, or procedural inadequacy).

10. Fire lasting more than 10 minutes.

11. Indications or alarms on process or effluent parameters not functional in control room to an extent requiring plant shutdown or other significant loss of assessment or communication capability (e.g. plant computer, all meteorological instrumentation).

12. Security threat or attempted entry or attempted sabotage.

13. Natural phenomenon being experienced or projected beyond usual levels

a. any earthquake

b. 50 year flood or low water, tsunami, hurricane surge, seiche

c. any tornado near site

d. any hurricane

14. Other hasards be k.; experienced or projected:

a. aire. raft crash onsite or unusual aircraft activity over facility

b. train derailment onsite

c. near or onsite explosion

d. near or onsite toxic or flammable gas release

e. turbine failure O B- 3 t* HIPP Rev. 3

15. Other plant conditions exist that warrant increased awareness on the part of state and/or local offsite authorities or require plant 6hutdown under technical specification requirements or involve other than normal controlled shutdown (e.g.. cooldown rate exceedin5 technical specification limits, pipe cracking found during operation).

16. Transportation of contaminated injured individual from site to offsite hospital.

17. Rapid depressuriaation of PWR secondary side.

O O B-35 MIPP Rev. 3

I i

l L I A

l )

EIAMPLE INITIATING CollDITIOlis ALEET i I l

i

1. Severe loss of fuel cladding.

a. High offgas at BWR air ejector monitor (greater than 5 ci/ sect corresponding to 16 isotopes decayed to 30 minutes). *

)

l i

b. Very high coolant activity sample (e.g., 300 uct/cc equivalent of l 1 131).

c. Failed fuel monitor (PWR) indicates increase greater than II fuel i failures within 30 minutes or $2 total fuel failures.

I 1

2. Rapid gross failute of one steam generator tube with loss of offsite power.

3. Rapid failure of more than 10 steam generator tubes (e.g., several hundred spm primary to secondary leak rate).  !

l l

4 Steam line break with significant (e.g. . greater than 10 gpm) primary to l

secondary leak rate or MSIV malfunction.

S. Primary coolant leak rate greater than 50 gpm.

l

6. High radiation levels or high airborne contamination which indicates a severe degradation in the control of radioactive materials (e.g., increase of factor of 1000 in dirset radiation readings).

1 l

7. Loss of offsite power And loss of all onsite AC power.

8. Loss of all onsite DC power.  !

l 9, Coolant pump seiaure leading to fuel failure.

0 1 0 1 B-36 MIPP Rev. 3 1

l

10. Loss of functions needed for plant cold shutdown.

11. Failure of the reactor protection system to initiate and complete a scram which brings the reactor suberitical.

12. Fuel damage accident with release of radioactivity to containment or fuel handling building.

13. Fire potentially affecting safety systems.

14. All alarms (annunciators) lost.

15. Radiological effluents greater than 10 times technical specification instantaneous limits (an instantaneous rate which, if continued over 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, would result in about 1 mR at the site boundary under average meteorological conditions).

16. Ongoing security compromise.

17. Severe natural phenomenon being experienced or projected:

a. earthquake greater thar. OBE levels

b. flood.' low water, tsunami, hurricane surge, seiche no.r design levels

c. any tornado striking facility

d. hurricane winds near design basis level

18. Other hazards being experienced or projected:

a. aircraft crash on facility

b. missile impacts from whatever source on facility O B-37 MIPP Rev. 3

i c. taow explosion damage to facility affecting plant operation

d. entry into facility environs of toxic or fJammable gasta

e. turbine failure causing casing penetration

19. Other plant contitions exist that warrant precautionary activation of technical support center and near-site emergency operations center.

20. Evacuation of contro room anticipated or required with control of shutdown systems established from local station.

l O B-38 MIPP Rev. 3 1

I l

l

(N i

EIAMPLE INITIATING CONDITIONS: SITE BIERGENCY j I

l 1

l

1. Known loss of coolant accident greater than makeup pump capacity.

l l l

2. Degraded core with possible loss of coolable geometry (indicators should i l

l include instrumentation to detect inadequate core cooling, coolant activity, and/or containment radioactivity levels). i 4

l l 3. Rapid failure of more than 10 steam generstor tubes with loss of offsite 1 i

power.

1

4. BWR steam line break outside containment without isolation. l

5. PWR steam line break with greater than 50 gpm primary to secondary leakage and indication of fuel damage.

()

\~ >

6. Loss of offsite power and loss of onsite AC power for more than 15 minutes. i

7. Loss of all vital onsite DC power for more than 15 minutes.

{

8. Loss of functions needed for plant hot shutdown.

9. Major damage to spent fuel in containment or fuel handling building (e.g.,

large object damage fuel or water loss below fuel level).

1 1

10. Fire affecting safety systems. I l

l I

11. All alarms (annunciators) lost for more than 15 minutes and plant is not in cold shutdown or plant transient initiated while all alarms lost.

1 i

B-39 HIPP Rev. 3 l

(,n) 12. a. Effluent monitors detect levels corresponding to greater than 50 mR/hr i

v l for h hour ,qr, greater than 500 mR/hr W.B. for two minutes (or five times these levels to the thyroid) a the site boundary for adverse meteorolony,

b. These dose rates are projected based on other plant parameters (e.g., I radiation level in containment with lead rate appropriate for existing I containment pressure) or are measured in the environs.

13. Isuninent loss of physical control of the plant.  !

14. Severe natural phenomena being experienced or projected with plant not in l'

cold shutdown. l l

1

a. eari.. quake greater than SSE levels

b. flood, low water, tsunami, hurricane surge, seiche greater than design levels or failure of protection of vital equipment at lower levels .

c. winds in excess of design levels I 15. Other hasards being experienced or projected with plant not in cold shutdowns

a. aircraft crash affect'ing vital structures by impact or fire

b. severe damage to safe shutdown equipment from missile or explosion

c. entry to toxic or flammable gases into vital areas

16. Other plant conditions exist that warrant activation of emergency centers and monitoring teams and a precautionary public notification.

17. Evacuation of control room and control of shutdown systems not established i p from local stations in 15 minutes.

B-40 MIPP Rev. 3

()

EIAMPLE INITIATING C00tDITI0088: GENERAL ENERGBICY

1. a. Effluent monitors detect levels corresponding to i rem /hr W.B. or 5 i

rea/hr thyroid at the site boundary under actual meteorolonfeal conditions.

l b. These dose rates are projected based on other plant parameters (e.g.,

{

t radiation levels in containment with leak rate appropriate for existing containment pressure with some confirmation from effluent monitors) or i

are measured in the envirotas.

i NOTE:

Consider evacuation only within about 2 miles of the site boundary unless these levels are exceeded by a factor of 10 projected to '

continue for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.

2. Loss of 2 or 3 fission product barriers with a potential loss of 3rd t

barrier (e.g., loss of core geometry and primary coolant boundary and high potential for loss of containment).

NOTE: Consider 2-mile precautionary evacuation. If more than gap activity released, extend this to 5 miles downwind.

3. Loss of physical control of the facility.

NOTE: Consider 2-mile precautionary evacuation.

4. Other plant conditions exist, from whatever source, that make release of 1

large amounts of radioactivity in a short time period pessible, e.g., any I core melt situation. See the specific PWR and BWR sequences.

l

\

l NOTES: a. For sequences where significant releases are not yet taking

! place and large amounts of fission products are not yet in the containment atmosphere, consider 2-mile precautionary O evacuation. Consider 5-mile downwind evacuation (45' to 90' O

B-41 MIPP Rev. 3

sector) if large amounts of fission products are in the containment atmosphere. Recommend sheltering in other parts of the plume exposure Emergency Planning Zone under this circumstance.

b. For sequences where significant releases are not yet taking place and containment failure leading to a direct atmospheric release is likely in the sequence..but not imminent, and large amounto of fission products, in addition to noble gas, are in the conttinment atmosphere, consider precautionary evacuation to 5 miles and 10 miles downwind evacuation (45' to 90' sector).

c. For sequences where large amounts of fission products other noble gases are in the containment atmosphere and containment failure is judged imuninent, recomunend shelter for those areas where evacuation cannot be completed before transport of activity to that location.

O d. As release information becomes available, adjust these actions in accordance with dose projections, time available to .vacuate, and estimated evacuation times given current conditions.

6 B-42 MIPP Rev. 3

t .

o O o

l l- NEW ENGramp CINEACT

j. RADIOfACICAL INCIBENT ADTISORY t

1. Information Received by: 2. Information sent by: i Agency: Agency:

Date: Time: Date: __ _ Time:

For TWX: Send to: FDA , Region I. Boston MA 3. Phone (incPde area code):

l ATTN: BRH Representative i

4. - Incident

- - - - - - -Site:

- - - - - a.

7. a. Request assistance (indicate agency (s) in'#8)

Date: b. Timer c. b. Information only

5. a. Notification of Unusual Event 8. Indicate agency (s) that you are requesting b.

assistance from:

Alert c. Site Bnergency a. Connecticut c. Massachusetts e. Rhode Island

d. General Emergency e. Transportation Incident b. Maine d. New Hampshire f. Vermont

f. Other (specify in #10) . g. Other (specify in #10)

6. Initiating condition (s) based on NRC NUREG-0654 9. Meteorological, release, or other data available7

a. Tes (specify in #10 and submit appropriate RIA forms as soon as possible).

b. No

10. Comments:

i l

t l New England Compact Form RIA-1 B-43 MIPP Rev. 3

(

INSTRUCTION SHEET FOR Rf.V ENGI.AND COMPACT FORM RIA-2 ILgat 1, 1, and j,are self-explanatory.

Item 4: is identical to Item 4 on form RIA-1.

1 Item 5: is identical to Item 8 on form RIA-1.

Item 6: Items A B C and D are typical of what would be rzpected from a l

reactor incident. This information should be available from the nuclear plant.

If the exact composition of the release is known, or if another isotope is involved (such as U-235 from a reprocessing plant), enter this isotope in Item E

-l and enter any additional explanatory material in Item #15. l l

Item 7: The source term of the release (curies /second) should be obtained from tl.e nuclear plant and entered in Item A. If the exact source term is unknown, the nuclear plant should at least be able to provide their total inventory of all radionuclides and the approximate leak rate into the environment. Enter. l this data in Item B.

JtemJ Enter the release height in meters. This should be available from the plant. If release height is unknown, assume that release was at ground level.

Item-9: It is important to know if there is any type of inversion layer

.present, If one is present, circle yes in Item A and enter height of inven ion layer in Item B. If the height of the layer is not exai:tly known, enter your best guess,-but put an

• after the value and explain in Item #10 how this guess was made.

l Item'10: Wind direction at time of release -- be sure to indicate direction i wind-is blowing fromt!

l l

Item 11: Enter wind speed in meters /sscond. For purposes of approximation, 1 l ineter/second - 2 mph. \

B-44 MIPP Rev. 3 l l

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h Item 12: The atmospheric stability class data should be available from the nuclear facility. They should have ' downwind concentration' charts available for all wind speed and stability classes.

Item 13: Enter the best guess as to how long present meteorological conditions will last.

Item 14: Use the same' codes established in Items 9-13 to establish the project new meteorological data.

Item 15: Use this section to report any items.not fully explained in previous sections. Also use this space to briefly identify any special or unique site-geographic or topographical factors. Keep all information brief and to the ,

point.

1 e

B-45 MIPP Rev. 3

_ \

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NEW ENGIAND COMPACT Page 1 of 2 RADIOLOGICAL INCIDENT METBOROIAGICAL AND REIJtARE DATA

1. Information received by: 2. Information sent by:

Agency: Agency: .

Date: Time: Date: Time:

For TWX: Send to: FDA - Region I, Boston, MA 3. Phone (include area code):

ATIN: BRH Representative

4. Incident Site: a. 9. Lid or inversion layer present?

Date: b. a. Yes Su; No

5. Indicate the agency (s) that this information should be b. If yes, height 'f layer (meters):

routed to:

10. Wind direction at time of release (wind blowing

a. Connecticut c. Massachusetts e. Rhode Island from):

b. Maine d. New Hampshire f. Vermont a. N (0*/360') 1. S (130')

b. NNE (22.5') J. SSW (202.5')

g. Other (specify in #15) c. NE (45') k. SW (225')

d. ENE (67.5') 1. WSW (247.5')

6. Type (s) or radio-isotopes involved in the release e. E (90') m. W (270')

f. ESE (112.5') n. WNW (292.5')

a. Primarily I_131 g. SE (135') o. NW (315')

b. Mixed radio _lodines h. SSE (157.5') p. NNW (337.5')

c. Primarily noble gases

d. Mixture of noble gases and radio-lodines 11. Vind speed (meters /second) at time of releases

e. Other (specify):

7. a. Enter the source term (s) (curies /second) for (isotopes) of interest. 12. Atmospheric stability class at thee of releases

b. If source term is not known exactly, enter total a. Class A d. Class D g. Class G inventory (curies) and best guess at release rate b. Class B e. Class E environment. c. Class C f. Class F

8. Release Height (meters):

New England Compact Fonn RIA 2 (Page One) B_46 MIPP Rev. 3

O O O

" "# NE Page 2 of.'2

-RADIGIAGICAL-INCIDENT DETEDROIAGICAI, AND RNE MTA (Continued)

13. How long are these conditions expected ~to last (hours)7

14. Give a brief description of the anticipated meteorological conditions at the end of this period (use the letter codes found in Items 9-13).

a. Wind direction: b. Wind Speed:

c. Stability class d. Projected Durations

e. Inversion layer present YES or NO f. If Item a. was yes, height of layers -

15. Conunents (include any special topographical or site specific data):

New England Conrpact Form RIA-2 (Page Two) B-47 MIPP Rev. 3

TESTRUCTION SHE?T FOR NEW ENGLAND COMPACT FORN RIA-3 Item 1: is self-explanatory.

P Item 2 is same as Item 4.A on frot RIA-1.

Item 3: Enter total number of pages it this report.

Item 4: a. Enter consecutive sample nutber for this report.

b. Enter the type of sample (food, sir, water, etc.) and any sample ID i that has been assigned locally. (This is to help identify a particular sample if problems occur at a later date.)

c. Enter;the instrumentation used to make the measurement (i.e., field GH, ' cutie pie,' NaI gamma spec., etc.).

O d. Enter the magnitude of the reading and the units used (i.e.,

mR/ hour, pCi/ meter3 , uCi/ gram, etc.).

e. Enter the location'of sample, including direction and distance from source,

f. Enter date an.d time _ sample taken.

g. Enter the agency / personnel that was/were responsible for taking the sample and/or measuring the sample.

-Item 5: Enter any other facts that are special or unique about the sample. Key these conunents to the sample i assigned in Item 4.a.

Use as many sheets as necessary to report each batch of sample results.

B-48 MIPP Rev. 3

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NEW ENGLAND COMPACT Page 1 of 2 i

REQUEST FOR RADIOLOGICAL ASSISTANCE

1. I (we) request the following radiological aseistance from under the provisions of the New England Compact.

2. Agency requesting assistance

3. Authorised requestor:

4.- Phone (include area code):

5. Describe type and quantities of assistance requested:

a. Equipments

b. Hanpower:

O

c. Support Services:

6. a. Where is the assistance needed

b. Where should equipment and/or personnel report (be specific):

c. When is the requested assistance needed:

d. Estimated duration of assistance:

O New England Compact Form RIA-4 (Page One) B-50 MIPP Rev. 3

M ENG M COMPACT Page 2 of 2 REQUEST FOR BADIOLOGICAL ASSISTANCE (Continued)

e. Contact person for requested assistance -- specify location and phone number (include area code):

7. Other Consnents:

J aG Signature of Authorized Requestor:

- Date:

=.

O. New England Compact Form RIA-4 (Page two) B-51 MIPP Rev. 3

APPENDIX C O NEW ENGLAND INTERSTATE RADIATION ASSISTANCE PLAN ARTICLE I - AUTHORITY This plan is authorized by the New England Compact on Radiological Health Protection, as approved by_the Legislatures and Governors of the several party States. The Act was first passed in the State of Maine on March 1, 1957, and subsequently passed by the State of Vermont on March 14, 1967 Rhode Island on April 5, 1967. New Hampshire on July 18, 1967 Massachusetts on December 20, 1967, and Connecticut on May 24, 1969. The Compact became official with the passage of the Second Cooperating State. The Compact, as signed into law in-each of the states, followed essentially the same format as developed by the New England Radiological Health Conunittee (NERHC). The NEREC is composed of the six New England Radiation Control Program Directors, the FDA Regional Radiological Health Representative and the EPA Regicnal Radiation Representative. The compact also allows that any state not mentioned above which is contiguous to any party state may become a party to this Compact by enacting the same.

ARTICLE II - PURPOSE The purpose of this plan is to delineate the manner in which the New England Compact on Radiological Health Protection will be implemented. The purpose of the New England Compact is to (a) promote the Radiological Health Protection of the public, and individuals within party states, (b) provide mutual aid and assistance in radiological health matters including, but not limited to, radiation incidents, and (c) encourage and facilitate the efficient use of personnel and equipment by furthering the orderly acquisition and sharing of resources useful for programs of radiation protection. This plan outlines the manner in which this interstate mutual aid and assistance and exchange of personnel will be accomplished. This plan includes specific information on the channels of conunanication among the states, the availability of equipment, and laboratory capabilities, the procedures for requesting assistance from the party C-1 MIPP Rev. 3

1

.1 states ano notifying party states of radiological incidents, as well as ~I

clarification of the procedures of the loan of ' personnel and equipment and financial obligations encountered.

1 ARTICLE III - DELEGATION OF AUTHORITY The Compact Administrator or designee for each party state shall notify the Secretary of the NERHC of the identity of any subordinate or subordinates-to whom his authority as Compact Administratot nas been delegated. (See Appendix I.)

ARTICLE'IV - COMMUNICATIONS AND EXCHANGE OF PLANS Each Compact Administrator or Designee shall provide the home and office telephone nuinber of himself or herself and/or such staff members as he or she

~

may designate as emergency contacts. In addition, he or she shall provide a j second channel of consnunication such as the State Police which will be operative.

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a day for .seven days a week, and shall arrange within his or her state .;

. O, g - for emergency consnunications to reach a responsible staff member. Each Compact

. Administrator shall notify the Secretary of the above designations and this information shall be updated at least annually in Appendix I of this plan.

ARTICLE V -. LISTING OF EQUIPMENT AND LABORATORY CAPABILITIES

'Each Compact Administrator shall transmit to the Secretary a listing of available field survey equipment including range, other emergency equipment, and a listing of available laboratory capabilities by type of analysis (i.e., gross alpha, gross beta, gamma, spectroscopy, etc.).

~

Such listings shall be updated annually or more often if conditions warrant. (See Appendix II and Appendix III.)

ARTICLE VI - REQUEST FOR ASSISTANCE a) Upon determination by a Compact Administrator or Delegate that a radiation

-incident has taken place within his/her state of a magnitude sufficient to C-2 MIPP Rev. 3

require additional personnel or equipment, the Compact Administrator or Delegate should contact the Secretary to request such aid as he/she deems t necessary. The Secretary shall contact such other party state / states to request aid as he/she judged to be best able to assist under the circumstances. The state / states receiving such a request should respond with personnel and/or equipment to the best of their ability, while maintaining sufficient capability for the protection of the public health within their own state. At the time of the request, said personnel should be advised of their assigned tasks and of the location and individual to 1

which they are to report. Provisions for further briefing, when necessary. '

may also be arranged at the time of such request.

b) Any' state responding to a request for aid under this plan shall operate while in a party state, in accordance with the radiation incident plan of that state.- i c)' Reimbursement by the state receiving aid or assistance under this Article for-any loss or damage to, or expense incurred in the operation of any equipment; for cost of all materials, transportation and maintenance of oificers, employees, and equipment; and for any compensation or benefits for injuries or death incurred by officers or employees =or an aiding state shall be in accordance with Article X. i ARTICLE VII - NOTIFICATION The notification to other party states under this plan shall be made directly by the Compact Administrator or Designee and such notification shall also be made to the Secretary, New England Radiolol;ical Health Conmittee.

ARTICLE VIII - LOAN OF FACILITIES AND EQUIPMENTi LABORATORY ANALYSIS AND EXCHANGE OF DATA

.a) Facilities and equipment specified in Article V of this plan may be-loaned in accordance with either of the two following situations; (1) one in which the requested state is not affected by the incident in question; and, (2)

C-3 MIPP Rev. 3

i I

one in which th's requested state is or could possibly be affected by the t incident in question. (See Appendix II and Appendix III.) The requesting state shall reimburse the lending state in accordance with Article X.

b)- Laboratory analyses may be performed by the requested state under conditions:specified in paragraph (a) above. (See Appendix III.)

c) Requests for assistance, exchange of data or other pertinent information may be accomplished utillaing forms in Appendix IV-through the Secretary of the HERHC. Transmission shall be by the most expeditious means of communication available.

ARTICLE IX - LOAN OF PERSONNEL

-Professional or technical personnel having special skills or training related to radiation protection may be made available to a party state upon request. Such requests should be transmitted through the NERHC Secretary and have approval of the respective Compact Administrators or Designees. The requesting state shall l

[. \.f b reimburse the lending state in accordance with Article X.

l ARTICl,J., X - CHARGES FOR EOUIPMENT AND PERSONNEL a) The state receiving aid or assistance shall reimburse the state rendering j aid or assistance for any loss or damage incurred in the operation of any l equipment. -

\I l

! l

.b) The state receiving aid or assistance shall pay for the cost of

)

transporting and maintaining all officers and employees of the state l-rendering aid in accordance with the rendering state's Rules and L Regulations, cr those of the state receiving aid -- whichever is greater, c)- The party state borrowing personnel shall reimburse the state loaning the personnel at the same annual rate as the personnel are receiving in their own state. The borrowing state shall pay for the cost of maintaining such l personnel in accordance with Article X. Section (b).

C-4 MIPP Rev. 3 l

l l

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.. .- - .. . .~ - - . - . _ _ - - - . -

. l d)' Nothing contained herein in Article X shall prevent any assisting party state from assuming the costs incurred under Sections (a), (b), and (c) of f Article X.

ARTICLE XI - UPDATES AND REVISIONS The Secretary of the NERHC shall be responsible for updating Ap;w7 dices I and II on an annual basis and the remaining appendices when appropriate. In addition, the members of the NERHC shall notify the Secretary of changing situations that may affect any of the items covered under this compact. If needed, the Secretary can form a subconmittee to rewrite appropriate sections of the plan.

Revised appendices will be forwarded to all plan holders at the beginning of each calendar year. '

l l

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'( C-5 MIPP Rev. 3

i

. p, l 4

y APPERDIK.I f}.

.V CONNECTICUT-Compact Administrator Conmissioner of Environmental Protection Business Tel.: 203-566-2110 Person to Whom Authority is Kevin T. A. McCarthy Delegated Business Tel.: 203-566-5668 or 5134 Home Tel.: 203-487-0305 Other Emergency Contacts Donald Karn (in order of priority) Business Tel.: 203-566-5668 I Home Tel.: 203-288-1214 l

'l Jesse Tucker '

Business Tel.: 203-566-5626 Home Tel.: 203-529-5063

- 8:30 to-4:30 Contact Radiation Control Office l Hartford, CT I I

24-Hour-A-Day Contact Connecticut State Police j (Ask for Executive Officer)

J h

e i C-6 MIPP Rev. 3

4

~

i O  : Compact Administrator Commissioner, Department of Human Services H. Rollin Ives Business Tel.: 207-289-2736 Person to Whom Authority Donald Hoxie is Delegated. Busivass Tel.: 207-289-3826 Home Tel.:

Other Emergency Contacts Clough Toppan (In nrder of priority) Business Tel.: 207-289-5676 Home Tel.: 207-582-7850 Wallace Hinckley Business Tel.: 207-289-3826 Home Tel.: 207-377-8834 Robert Schell Business Tel.: 207-289-5676 Home Tel.: 207 395-4602 24-Hour-A-Day Contact Maine State Police Business Hourst 8:00 - 5:00 0

C.7 .1,, ee.. ,

til>

M&BSACBUSETTS

. Compact Administrator Cossnit sioner, Department of Public .'ealth Businenw Tel.: 617-727-2700 Person to Whom Authority Robert M. Hallisey-is Delegated Business Tel.: 617-727-6214, 6246 Home Tel.: 617-729-5728

~

Other Emergency Contacts George Swible

, (In' order of priority) Business Tel.: 617-727-6214, 6246 Home Tel.: 617-387-7768 Robert Watkins Business Tel.: 617-727-6214, 6246 Home Tel.: 617-832-3378 William Bell Business Tel.: 413-586-7525 Home Tel.: 413-773-7858 24-Hour-A-Day Contact Hassachusetts State Police O

O c-- "~ >

n.- -. - _-- .. ~_ . .~ . - . - .

, 4 i

j i

NEW EAMPSEIRE '

f% - ,

LL-)y ~f Compact Administrator n Chief,' Bureau of Environmental Health '

John R. Stanton Business Tel.: 603-271-4587 Home Tel.: 603-623-4743 lPersontoWhomAuthority Dian Tefft is Delegated Business Tel.: 603-271-4588 Home Tel.: 603-524-3358 Donald E., Halle Business Tel.: 603-271-4585 Home Tel.: 603-622-9618 -

24LHour-A-Day Contact New Hampshire State Police REODE ISLAND Compact Administrator Director, Department of Health Joseph E. Cannon. H.D. .

Business Tel.: 401-277-2231 l

[\s_- -~

Person to Whom Authority is Delegated James E. Hickey.

Business Tel.: 401-277-2438 .

Home Tel.: 401-884-4732 l

- Other Emergency Contacts Charles McMahon

'(In order of priority) Business Tel.: 4 01~-2 77-24 38 Home'Tel.:- 401-949-3138 f Roger Marinelli i Business Tel.: 401-277-2438

,. Home Tel.: 401-467-4008 24-Hour-A-Day Contact Rhode Island State Police e

<llp C-, H1PP me 3 I

VEID10NT O compact Administrator commissioner, State Health Department Lloyd F. Novick, M.D.

Business Tel.: 802-862-5701 Person to Whom Authority Raymond.N. McCandless

'is. Delegated Business Tel.: 802-828-2886 Home Tel.: 802-223-5075 Other Emergency Contacts Paul Clemons (In order of priority) Business Tel.: 802-828-2886 Home Tel.: 802 592-3534 Deborah Voland Business Tel.: 802-257-1750 Home Tel.: 802-388-3536 24-Hour-A-Day Contact Vermont State Police 9

(

lh C-10 HIPP Rev. 3

i Fune AT. CONTACT LISTING O - - - - - -

Primary Contact Byron Keene Office of Radiation and Noise Business Tel.: 617-22s-46,5' Home Tel.: 617-729 8356

-Other Emergency Contact Paul Bedrosian Business Tel.: 617-223-1591 Home Tel.: 617-475-2558 24-Hour-A-Day Contact 011 & Nazardous Materials Duty Officer 617-223-7265 FOOD AND DRUG AIBGNISTRATION

. Primary Contact Warren Church Business Tel.: 617-223-3178 Home Tel.: 617-664-5307 Other Emergency Contacts Edward Baratta Business Tel.: 617 729-5700 O (In order of priority)

Home Tel.:

Paul Bolin Business Tel.: 617-729-5700 Home Tel.: 603-434-0596 C-11 MIPP Rev. 3 1

- --s - - - - - - y euw - nmummun i k

e APPENDIX D DIVISION OF HEALTH ENGINEERING PROCEDURES O

THIS DOC 2Eff CONTAINS PROCEDURES TO BE USED BY DBE PERSONNEL TO RESPOND TO A RADIOLOGICAL ACCIDENT D-1 MIPP Rev. 3 1

t.

[

, DIVISita OF NEALTE ENGINEERING PROCEDURES I

{. / CONTENTS AND REVISION STATUS i' jbyghgr h Procedure Title fagg 2.01 3 Radiological Monitoring Team Notification D-3 2.0$S 2 Personnel Dosimetry D-10 2.06S 2 Decontamination of Emergency Workers, D-20 Equipment and Vehicles

• L 2.11S 4 Environmental Sample Collection D-36 2.12S 1 Air Sampling Procedure D-66 l.

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$a D-2 MIPP Rev. 3 f-i ';

Proc. 2.01 Date 6/90 Rev. 3 RADIOLOGICAL MONITORING TEAM NOTIFICATION

1. Obiective To provide a system for prompt notification of personnel in the event of a radiological accident.

2. Discussion In the event of an accident involving a nuclear power plant or radioactive-material, the Division of Health Engineering (DHE) is notified by the Stata Police. The individual notified is designated the Radiological Health Coordinator (RHC). The RBC will report to the State Emergency Operations Center-(E00) located in the basement of the State Office Building. From there the RHC will. initiate the notification of Radiological Health Specialists.and monitoring team members.

3. Notification Procedure A. Initial Notification Requirements:

Rad.

Soecialist Mon. Team Lab Nuclear Power Plant: Unusual Event Alert X Site Area X X X General X X X Portsmouth Naval Shipyard X Rad. Materials Incident B. Notification of personnel will follow the order of the call lists (Attachments 1, 2 and 3). The following format should be used (see Attachment 4):

1. State your name.

2. Ask to speak to person called.

3. State the type of accident and request that personnel report to the following location

a. Radiological Health Specialists - State EOC

b. Monitoring Teams - First report to State EOC

- All others to DHE. 157 Capitol Street

c. Lab Personnel - Public Health Lab D-3 MIPP Rev. 3 l

1; 1

L, '

I., .. Proc. 2.01 l p g- Date 6/90

\j: Rev. 3 c

4. . Ask for confirmation that you are understood and request an estimated response time.

5. Record time notified on the call list.

f O

O

4 Proc. 2.01 Date 6/90 O Rev. 3 ATTACIB(ENT 1 DIVISION OF HEALTE ENGINEERING PRIMARY CALL LIST l

Name/ Address Home Phone Business Phone Time Contacted Donald Hoxie 622-7445 289-5686 18 Greenwood Street Augusta. > kine W. Clough Toppan 582-7850 289-5698 RFD #3. Bowman Street Box 5700 Farmingdale, Maine Patrick Dostie 622-9472 882-6321 53 Windy Street Augusta , > hine Robert Schell. 933-4413 289-5696 Box 1773 Wilson' Pond Road No. Honnmouth, Maine David Breau 622-0260 289 5673' 8 School Street Augusta, hkine Wallace Hinckley- 377-8834 289-5685 Fire Road X2 Off Route 135 Winthrop. Maine Jay Hyland- 293-2647 289-5677 Watson Pond Road Rome Maine Linda Plusquellic 547-3109 289-5677 buddle Road Sidney.-> hine D-5 HIPP Rev. 3

I 1

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Proc. 2.01'

[__) L Date 6/90

-N/ Rev. 3 ATTAC8HENT 2 HONITORING TEAM CALL LIST l l

Name/ Address Home Phone Business Phone Time Contacted Robert Peterson 626 5525 289-5693 i

PO Box $643 '

Augusta. Maine Ron McDougal 622-5880 289-5691 46 Pearl Street ___

Augusta Maine Kerwin Keller 622-7712 289-5688 243 Eastern Avenue

. Augusta, Maine Francis Drake 784-9614 289-5680 302 Central Avenue '

Lewiston, Maine Jay Hardcastle O\ 28 High Street 626 0068 289-5684 Hallowell, Maine

-Carlton Gardner 782-2214 289-5682

'48 Gamage Avenue Auburn, Maine:

JJeff'Jenks -685-9086 289-5669 Wayne Village

' Wayne, Maine.

Ken Meyer 549-5741 289-5678 PO Box 64 North Whitefield, Maine Steve Zayszly 224-8267 289-5692-PO Box 560 _

.Torrey Hill _ Road North Turner Maine D-6 HIPP Rev. 3 l

\

(

Proc. 2.01 Date 6/90 Rev. 3 ATTACIDEElff 2 MOBIITORING TEAM CALL LIST (Continued)

MAREllddress Home Phone Business Phone Time contacted Eleanor King- 582-8073 289-3826 17 Beech Street Gardiner, Maine Dean Jackson 78!-4500 596-4297 Box 544, Conunon Road Union, Maine Carl Witham 225-2474 289-3826 Route.117 Turner, Maine Edmund Wurpel 495-2187 775-6054 Box 244 Hulin Road Belgrade, Maine

.Jeffrey Folger. 622-3482 289-3826

-Middle Road iAugusta. Maine:

Sharron Hinckley 377-8834 289-3826 iLoon Cove Road _

. Fire Road X2 Winthrop, Maine D-7 MIPP Rev. 3 O-

Proc. 2.01

> Date 6/90 Rev. 3 ATTACIINENT 3 LABORATORY PERSONNEL

- Name/ Address Home Phone Business Phone Time Contacted Cheryl Baker 445-2956 289-2727 RFD 6. Box 377 Augusta, ME- 04330 Dr. Philip V. Haines 923-3391 289-2727 RFD #1 '943-3394)

Vassalboro, ME 04989 (camp)

Jack Krueger 845-2482 289-2727 RFD fl. Box 2310 South Liberty, ME 04949 Thomas Dwyer 622-6202 289-2727 RFD #5, Box 530 Augusta ME 04330 Richard French 622-3876 289-2727 --

RFD #7, Box 507 Augusta, ME 04330 Theresa Zibura 445-2817 289-2727 RFD 6 Augusta, ME 04330 s

D-8 MIPP Rev. 3

d i

I Proc. 2.01 '

^ Date 6/90 l Rev. 3 1

)

l ATTACIMENT 4 }

i l

SAMPLE NOTIFICATION l

Hello. My name is clounh Toonan. May I speak to Dave Breauf l

Hello. My name is Clounh Toonan frort the Division of Health Er,gineering.

1 am calling to report the occurrence of R & y,1 at Maine Yr.nkee Power connany or Seabrook Station.

The situatien at this time is as follows:

There has been a reactor coolant system rupture to the steam generator.

A stear line radiation monitor is reading high.

You are to report to the State EOC in the basement of the State Office Building.

When can you arrive at the EOC7 Do you understand these instructions?

f

( (Note time individual was notified.) i 6

Y h

D-9 MIPP Rev. 3 d ,

1

I l

o Proc. 2.05$

Date 6/90 Rev. 2 Direct-reading dosimeters are sensitive to shock and may give a false reading if dropped or bounced repeatedly. Also, DRDs may slowly discharge or ' leak' which will lead to false readings.

Thermoluminesce.it Dosimeters. TLDs, are used to provide a permanent record of worker exposure to stama radiation. The TLD records total exposure from the tixe it is 'aeroed' to the time it is read. Unlike the DRDs, the TLDs require a device commonly called a ' reader' to provide a r iadout of the accumulated gamma exposure. TLD badges must be collected and taken to a lab to be read.

TLD bauges must not be switched between workers. Once issued to an individual worker, the badge must be used only by that worker.

IV. POTASSIUM 10DIDE Potassium Iodide (KI) is used to block the uptake of radioactive iodine by the thyroid gland.

Potassium Iodide (KI), in tablet form, will be available for administration to Emergency Workers upon order of the Commissioner of the Department of Human Services or his designated representatives.

Ol NOTE: Administration of KI would not apply to personnel collecting samples in the ingestion exposure pathway beyond the plume exposure pathway EP2.

The following criteria will be considered prior to an order for administration

1. Following a xnown release, or if a release is imminent, of radioactive 8as of unknown composition (! radioiodides):

2. Following a known release, or if a release is imminent, of radioactive gas of known composition such that an individual could receive a dose to the thyroid which exceeds 25 rems.

D-11 MIPP Rev. 3 l

i

-- - - - ~

i Proc. 2.055 Date 6/90 f Rev. 2 Dosage will be as follows:

1. 130 mg (one tablet) daily for e maximum of 10 days, unless otherwise recommended by the Director of the Bureau of Health.

I CONTRAINDICATIONS: KI is contraindicated for individuals with known lodine allergies.

IF All BIERGENCY WOREME REPORTS ANY SIDE EFFECTS OR REACTIONS FRobt II. INSTRUCT TER WOREER TO DISCONTINUE ITS USE AND TO LEAVE TEE AFFECTED AREA.

V. INSTRUCTIONS FOR DISTRIBUTIO4 A. Each designated Emergency Worker (Local and State Police. Sheriff's Deputies DOT workers, etc.) will be issued the following personnel dosimetry devices and informations h Ouantity TLD badge / card 1 High Range Dosimeter 1 Low Range Dosimeter 1 Individus1 Radiation Exposure 1 Card (white card)

Instructions to Emergency Workers i l

B. Sign-Out Procedure

1. Sign out the TLD badge / card

a. Using the ' Personnel Dosimetry Log,' enter the following information:

1. Individual's name

2. Date

3. Time out (time TLD card issued)

4. TLD card number

b. The TLD should be clipped securely to the individual's clothing on the front of the body in the area between the neck and waist. If possible, the card should be placed inside a shirt pocket and the pocket buttoned. The TLD will record any exposure to gasuna radiation even if covered by clothing.

c. In no case should the TLD be used by or reissued to another person.

D-12 HIPP Rev. 3 O-

~

j Proc. 2.05S Date 6/90 O Rev. 2

d. TLD badges / cards marked as ' CONTROL' are not to be issued.

These TLDs should be kept by the supervisor and returned with the worker's TLD badges to be read.

. Direct-Reading Desimeters

a. One high and one low range DRD will be issued to each individual. These should oe 'seroed' by the individual worker at the time of issue.

b. The DRDs should be clipped securely to the individual's clothing in proximity to the TLD (in the breast pocket if possible).

c. Unless otherwise directed, individuals should check pocket dosimeter every 15 minutes and record the time and exposure on the Individual Exposure Record.

d. An individual's DRD readings should be in the same range as other worker's readings if they are located in the same area,

e. A substitute worker should be available so that a worker could be rotated out of the arsa.

f. If the increase on the low-range DRD is greater than or equal to 100 mR, the individual should notify the supervisor.

g. If the reading on the high-range DRD is greater than or equal to 1R. the Division of Health Engineering should be notified.

DHE will require the following informations

a. individual's location (i.e., traffic control point)

b. time worker has been at that location

c. other workers DRD readings co-located with or near the individual

d. availability of substitute so that worker could be rotated out of the area.

DEE contact - Augustas (207) 289 4080

- Newington: (603) 433 1449

3. If the Division of Health Engineering representative cannot be reached the individual worker exposure should be limited to no more than 3 R as indicated on the DRD.

D-13 MIPP Rev. 3 4

/ Proc. 2.0$$

k Date 6/90 Rev. 2 4 i Emergency Workers may exceed the dose limits if required for lifesaving activity. The recommended limit for lifesaving activity is 25 R.  ;

VI. CQ1.11011M ,

At the end of each shif t all personnel dosimetry devices will be returned to the staff supervisor.  !

A. The TLDs will be returned to the shift supervisor. The shift supervisor should contact the Maine Division of Health Engineering or the New Hampshire Incident Field Office (IFO) to request additional TLDs and to request analysis for those used.

B. DRDs will be returned. The DRDs will be read and the time and reading entered on the exposure record. The DRD can be re-seroed and reissued.

The next entry line on the exposure record should be lined out to indicate a ' break' in the exposure history.

C. Personnel Dosimetry Log entry will be completed for each individual.

Next to the individual's name the time in (returned from the field) and  ;

the final reading of the direct reading dosimeters will be entered.

l ' The Personnel Dosimetry Log will be turned in to the Division of Health  ;

l Engineering with the TLD cards.

D. Any exposures should be reported to the Maine Division of Health Engineering representative, i

l l

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Proc. 2.055 Date 6/90 Rev. 2 INSTRUCTIONS TO VORE2ES - DDSIMETRY OPERATION AND USE OF DIRECT-READING DOSIMETER AND CHARGER A. teroint Dos 4==ter

1. Point a dosimeter towards a light source (see Figure 1). Rotate the dosimeter so the word ' Roentgens' or 'M1111 roentgens' appears right.

side up.

2. Read the position of the hairline on the scale. If the hairline is visible and positioned between zero and the first mark, record the reading on the Individual Radiation Exposure Card as the ' initial reading.' Otherwise, re-tero the dosimeter using a dosimeter charger.

3. If batteries have not been previously installed in the charger to be used, loosen the thumbscrew ir. the top or bottom center of the charger with a coin and remove the case bottom cover. Install battery (observing + and - markings) and reassemble charger.

4. Position the charger on a flat surface. Unscrew the cap on the charging contact and place the end of the dosimeter opposite the pocket clip and eye piece on the charging contact (see Figure 2).

5. Applying firm downward pressure, a light will come on and the internal dosimeter scale and a hairline should be visible.

6. If the hairline is not visible, rotate the control knob (Figure 2) until the hairline appears.

7. Set the hairline on zero.

8. Remove the dosimeter from the charger and point towards a light source. If the hairline is between zero and the first mark on the scale, the dosimeter is ready for use. Otherwise, use the charger to properly position the hairline. Install the charging contact cap.

B. Usina Dosimeters

1. Record ' initial' reading on Individual Radiation Exposure Card.

2. To read a dosimeter at any time, point it towards a light source and read the position of the hairline on the scale (Figure 3 is 25 mR and Figure 4 is 10 R). Accumulated exposure is this number minus the initial reading recorded on the Individual Radiation Exposure Card.

O D-16 MIPP Rev. 3 l'

I

[v Proc. 2.0$$

Date 6/90 Rev. 2 3.

Vear direct reading dosimeters (and TLD) on the front of the body in j the area between the neck and waist, in a pocket af possible.

4. Do not permit anyone else to wear your Josimetry.

5.

Complete all parts of your Individual Radiation Exposure Card except columns for ' final' readings. )

)

6. Keep the Individual Radiation Exposure Card in your possession at all t

times.

C. Radiation Ernosure Control

1. Unless otherwise directed, read your direct reading dosimeter every 15  ?

minutes and record the time and exposure on the Individual Radiation 1 Exposure Card.

2. If the reading on the 200 mR direct-reading dosimeter is greater than 1

or equal to 100 mR (half-scale), notify your supervisor. Take all further readings on your 20 R direct reaoing dosimeter.

3. If t.he reading on the 20 R direct-reading dosimeter is greater than or '

equal to 1 R, notify your supervisor.

4. If the reading on the 20 R direct reading dosimeter is greater than or equal to 3 R. notify your supervisor who will rotate you out of the area.

D. Termination of Assinnment At the end of your assignment, report back to the location designated by

.your supervisor. Record the final reading of your dosimeter on the Individual Radiation Exposure Card. Subtract the initial reading from the final reading to obtain Total Exposure. This will be recorded in the Personnel Dosimetry Log, maintained by Division of Health Engineering.

If you are being relieved of your assignment by another individual, then:

o turn over all logs, procedures, and equipment except dosimetry to your relief o notify your supervisor of the turnovers and

o. report to the location designated by your supervisor.

D-17 MIPP Rev. 3

l i

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Proc. 2.058 i Date 6/90 l Rev. 2 I 1

t OPERATICII 0F DIRECT-READING DOSIMITER MED CEARGM 6.isn. ,

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Reading equals 25 Milli centgens Reading equais 10 Reentgens l l PLACE CHARGER HERE I

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D-18 MIPP Rev. 3 t

/ '

\~-) Proc. 2.05S Date 6/90 Rev. 2 INDIVIDUAL RADIATION EKPOSURE CARD Names Date:

Town or Agency:

Assignment Direct Reading Dosimeter Numbers High Range (0-20 R) Low Range (0-200 mR)

TLD Badge Number Road the dosimeter every 15 minutes unless otherwise directed. Record the readings on the reverse side of this card.

Notify your supervisor ife 200 mR DRD reaches 100 mR

- 0 20 R DRD reaches 1 R or 3 R

- DRD becomes lost, damaged or DRD goes off scale i Ingest KI only when directed by your supervisor via dispatcher.

Record date and time Report anyfacility.

assigned adverse side effects to your dispatcher or upon arrival to your (Back)

Direct Reading Dosimeter Record TIME 0-20 R 0-200 mR TIME 0-20 R 0-200 mR TIME 0-20 R 0-200 mR I

Potassium Iodide Record Date: Times g Date Times i Date Time:

D-19 MIPP Rev. 3 l

(-

l

I (s

Proc. 2.06S

\ Date 6/90 Rev. 2 DECONTAMINATION OF EMERGENCY WORKERS, EQUIPMENT AND VENICI.ES Decontamination is the process of removing radioactive materials from persons or objects in order to minia':: r-diation exposure to individuals.

The following equipment will be required: '

1.

Survey instruments: Survey meter (e.g. , RM-14. E.140$') with GM pancake

• probe (e.g., HP-210)

2. Plastic bags ,

3. Signs, tape, rope 4 Towels S. Cleaning agents (see Tables 1 and 2)

Vehicle and personnel monitoring will be conducted in the parking lot at the rear of the York County Courthouse, adjacent to the York County E00, according to the layout depicted in Figure 1.

O D-20 J MIPP Rev. 3

i l

I i

Proc. 2.06S g Date 6/90 Rev. 2 VERICLE DECONTAKDIATION Vehicles suspected of radioactive contamination should be surveyed using the specified survey instrument, or equivalent, and a pancake probe. If readings in excess of 100 cpm above background are observed, the vehicle should be washed and resurveyed.

If contamination is still present, the vehicle should be washed again until no further reduction in contamination is found. If contamination cannot be removed, the vehicle should be placed in an area designated as

' contaminated parkingg' l ' clean parking or can be used again.'if Figure clean, it2 should bediagram is a flow placed in ofan thisarea designated as process.

In surveying the vehicle, special attention should be given to under sides of l fenders,theradiator,theairfilter,thetiresandthedoorhandles. The interior should also be surveyed, especially the seats and the floor. If contamination is found inside the vehicle, the vehicle may be vacuumed with a vacuum cleaner that exhausts through a high efficiency particulate air filter.

If vacuuming to the vehicle wash portions does not remove the contamination, it may be necessary of the vehicle.

If a vehicle interior or exterior cannot be decontaminated to acceptable levels, the vehicle will be impounded for further evaluation.

The occupants of the vehicle should then be surveyed and decontaminated, as I needed, as described under ' Personnel Decontamination.'

Vehicle and driver identification and results of vehicle monitoring and decontamination will be recorded on Figure 3. Vehicle Monitoring Report Form.

l O

O D-21 MIPP Rev. 3

l G Proc. 2.06S kj Date 6/90 Rev. 2 PERSONNEL DECONTAMINATION InCividuals who have been potentially contaminated must be surveyed. A ' hot j line' should be established at a convenient location, so thst contaminated individuals do not spread contamination.

The hot line should be clearly identified through signs, tape and rope, and should be staffed when field personnel are reporting.

i l Figure 4isaflowdiagramforpersonnelmonitoringanddecontamination. Note that clean and unclean areas must be established.

j The individual responsible for'actually monitoring the incoming workers must l remain on the clean side of the line. The monitor should follow the procedure outlined below 1.

Hold probe about one inch from the person's body. Be careful not to come in direct contact with the person being scanned.

Beginning at the head and without touching the person, survey the entire l2. body including the soles of shoes. (See Figure S.) I p 3.

( Iloid probe increase in on either side of the neck just below the ear and note any reading.

4.

A sustained reading of 100 cpm above background on skin or clothing will be considered evidence of contamination.

5.

Direct contaminated individuals to the decontamination area for washing.

6.

Direct uncontaminated individuals to the record keeping area.

Remove clothing with areas exceeding 100 cpm above background and place in a garbage bag clearly marked as containing radioactive materials. Re-survey and if individual is found clean, provide new clothing and allow the individual to cross the ' hot line.'

Individuals before with contamination crossing the ' hot line.' on their skin should remove the contamination Table 1 lists the procedures, in order of preference, for decontaminating skin and clothing.

If an individual receives an exposure in excess of 5 R or if an individual's hair or skin surface remains contaminated after three attempts at decontamination, perform the following:

1.

Complete two copies of the Personnel Contamination Report (Figure 6) and one copy of the Radiological Screening Program Tracking Sheet (Figure 7).

D-22 MIPP Rev. 3

~ 1 Proc. 2.06S Date 6/90 O' -

Rev. 2

2. Give the individual one copy of the Personnel Contamination Report and file the other forms alphabetically.

3. Inform the Radiological Health Coordinator and provide him with information necessary for entry into the Radiological Screening Program.

Additional guidance can be found in NCRP65, 'Hanagement of Persons Accidently Contaminated with Radionuclides.'

O D-23 MIPP Rev. 3

'l l

rw Proc. 2.06S

( Date 6/90 l

..ev. 2 EQUIPMENT DECONTAMINATION l

Equipment that is suspected of being contaminated, such as instrument probes us*d in the field, should be surveyed. If contamination is found, the equipnent i shoulo be -leanad with an oil-impregnated rag (Masslinn type). The persons l performing the decontamination should wear gloves to prevent further spread of contamination. If contamination still exists, use a wet soapy towel.

Be careful that contamination is not spread. Use a minimum amount of water, for example, wipe down digging instruments instead of hosing down. Be careful not )

(

to damage electrical equipment. Table 2 describes methods for equipment '

decontamination.

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[ Proc. 2.068  ;

Date 6/90  !

Rev. 2 TABLE 1 PERSONNEL DECONTANIMATION METNODS A9))LT, '

PROCEDURE i

SEIN AND BANDS '

1. Kild soap and water or detergent and water. If Wash 2-3 minutes using tepid water and monitor. Do not repeat more than necessary follow by soft brush, 3 times. Use light pressure with heavy lather and tepid water. heavy lather. Use care not to )

Lava soap and water may also be scratch or erode skin. Apply used, if necessary. lanolin or hand cream to prevent chapping.

2. A mixture of: Make into a paste. Use with additional water and a mild 50! TIDE (Powdered Soap) scrubbing action. Use care not to 50! Cornmeal scratch or erode skin.

O 3. A 52 water solution of a mixture oft Use with tepid water. Rub for one minute and rinse.

I 301 TIDE 652 Liquid Soap 52 CARBOSE (Carboxy-methyl Cellulose) .

4. A preparation oft Use without additional water. Rub 82 CARBOSE for one minute and wipe off. Follow l 32 Powdered Soap with lanolin or hand cream.

12 VERSENE 861 VATER Homogenised into a cream.

EYES, EARS, NOSE AND MOUTH

1. Running tap water. Roll back the eyelids, flush with large amounts of tepid water. Use Isotonic irrigants if available.

D-25 MIPP Rev. 3

I Proc. 2.065

(( Date 6/90 ,

1 Rev. 2 TABLE 1 PERSONNEL DECONTANINATION METHODS (Continued) i A9. Ell 1 fl9.GLM ,

aan

1. First use shampoo. If shampoo Wash hair using tepid rater. Rinse is not effective. Tide (Powered thoroughly and repeat if necessary.

Soap) or other detergent.

VOUNDS

1. Running tap water. Report to medical personnel as soon as Wash with large volumes of running, possible. tepid water only. Spread the edges of the wound to aid flushing action.

CLOTHING

1. Wash Use standard laundering procedures.

32 Versene or Citric Acid may be Os kdded to washwater.

2. Store If contamination is short lived, allows for decay to background levels.

3. Disposal Treat as Low Level Radioactive Waste. '

o 4

D-26 HIPP Re '. 3

e a -.

./ [G t {m J -

r- - -

Proc. 2.065 TABLE 2 Date 6/90 Rev. 2 EQUIPMENT DSCONTaNDIATION MTEODS Begin with the first listed method and then p m und -*=p by step to the more severe methods. Be sure to monitor equipment after each step.

l Method Surface Action Technique Advantages Disadvantages Vacuum Dry entfaces Removes Use conventienal vac*.aum Good on dry, porous All dust must be cleaning contaminated technique with j

dust by surfaces. Avoids water filtered out of efficient filter. reactions.

suction. exhaust. Machine is contaminated.

Water All nonporous Dissolves For larme surfaces All water equipment may Drainage must be surfaces and erodes. Hose with high pressure be utilized. Allows (metal, controlled. Not water at an optimum operation to be carried suitable for porous painted, distance of 15 to 20 out from a distance. materials. Oiled plastic. feet. Spray vertical

! contamination may be surfaces cannot be etc.). surfaces at an angle of reduced by 50%. ' Water incidence of 30' to decontaminated. Not equipment may be used applicable on dry 40*: work from top to for solutions of other contaminated surfaces bottom to avoid decontaminating agents. (use vacuum): not recontamination. Work applicable on porous upwind to avoid spray.

Determine cleaning rate surfaces such as wood.

concrete, canvas, etc.

experimentally, if Spray will be possible; otherwise use contaminated.

a rate of 4 sq. feet per minute.

All surfaces Dissolves For semil surfaces Extremely effective if and erodes. Blot up liquid and Of little value in the

' done immediately after decontamination of handwipe with water and spill and on nonporous large areas, long erpropriate commercial surfaces.

detergent.

standing contaminants and porous surfaces.

D-27 MIPP Rev. 3

, _ - - .,m ____m

. f \

r

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Proc. 2.065. _

TABLE 2 Date 6/90 Rev. 2 squirnser DecouranimaTIon nrrnons I

(Continued)

Method Surface Action Technique t

Advantages Disadvantages Steam Nonporous Dissolves surfaces Work from top to botton Contamination may be Steam subject to same and erodes. and from upwind. Clean reduced approximately l (especially surface at a rate of limitations as water.

902 on painted Spray hazard makes the l painted or oiled 4 sq. ft. per minute. surfaces. wearing of waterproof The cleaning efficiency surfaces). of steam will be outfits necessary.

l greatly increased by using detergents.

Detergents Nonporous Baulsifies kub surface 1 minute Dissolves industrial May require personal surfaces contaminant with a rag moistened film and other (metal, and with detergent solution contact with surface. I l

painted increases materials which hold May not be efficient then wipe with dry rag; contamination. on long standing i

glass, wetting use clean surface of Contaminstion may be contamination.

plastic, power of the rag for each  !

reduced by 90Z.

etc.). water and application. Use a cleaning power rotary brush with efficiency pressure feed for more of steam. efficient cleaning.

Apply solution from a distance with a pressure feed for more i

efficient cleaning.  ;

Apply solution from a distance with a '

pressure proportioner.  :

Do not allow solution i to drip onto other surfaces. Mist application is all that is necessary. r D-28 MIPP Rew. 3

O _ . . _ _ _ _ . . . . .

Proc. 2.06S Date 6/90 Rev. 2 F10t!EE 1 YERICLE AllD PERS000tEL NoltITORING L&YOUT ac5$$_"'_._. . ._. . .* 5'tt"Ta % ._.,

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CLEAN CONTAMINAT[D YEMICLES VEHICLES .I l.

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l l AREA sNN)

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YORK COUNTY CONTAMINATED k\s\

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! PERs0NNEL ENTRANCE j l - .

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ENTRANCE j ,

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vont ccEHaust E N I' A inant CONE w nrE seRnmRs D-29 HIPP Rev. 3 ,

I eroc. 2.065 4

-( Date 6/90 Rev. 2 FIGURE 2 FLOW DIAGRAN FOR '

YERICLE DECONTANIMATION i Access Road and Driveway 9

Vehicle Passengers Scan Area .If Clean

(<100 cpm)

If Contaminated (>100 cpm)  !

if Wash g Wash Water

( Area l

1F 1P i ,

Rescan Clean l

Area - If Clean 4 Parking i

(<100 cpm) l If Still contaminated (>100 cpm)

Dr\

ivery qp y Personnel Contaminated Monitoring Parking Driver > Center Entrance l

l O o->0 xI , e. 2 l

l 1

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( ,)

'- Proc. 2.06S  ;

Date 6/90 Rev. 2 j FIGURE 3 ,

VEHICLE MONITORING REPORT FORM 120K '

DATE:

I VEHICLE AREAS TIME /DATE REGISTRATION CONTAMINATED INITIALS DECONTAMINATION INITIALS

-s E91K Take all contamination surveys with beta window open.

Decontamination required when contamination levels are greater than 100 cpm above background.

D-31 HIPP Rev. 3

. - - _ -_. . . _ - _ _ .- . . _ . - . . . - . . -- . . . _ . . . - . _ - - . _ . . . ~._.... .._..- __.--__

l l

l l- Proc. 2.068 Date 6/90 Rev. 2 FIGURE 4 FLOW DIAGRAM FOR PERSONNEL MORITORING AND DECONTAMINATION Boundary of F...................

Clean Area Entrance To Personnel l Monitoring

i. Center 1F '

Initial j Scan If Clean Area (<100 cpm)

If Contamin ted (>100 cpm) i Waste i

Storage For Sink And > Registration Contaminated (-- Shower If Clean And Dose Clothing, Area (<100 cpm) Records 3

Towels, Etc.

1F l

' If Contaminated (>100 cpm) Separate l

Exit 1 1F i Refer to Followup I 1 Program 1 T

Registration And Dose Records

_ W Separate I

Exit clean  !

.\ potentially contaminated area D-32 MIPP Rev. 3 l

w ww-____

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Proc. 2.068 Date 6/90 Rev. 2 FIGURE 5 PERSOM EL MOIIITOEING START

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I 1 \-5

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Survey Guides

.f k

1. Hold f ace of probe within'1' of surface but do not touch.

2. Survey at about l' per second.

3. Survey entire surface of body from top of head to bottom of feet.

4. Hold probe on either side of neck just below ear and note any increase in reading.

5. 100 cpoi above background indicates contamination.

D.33 MIPP Rev. 3

_4

Proc. 2.068 Date 6/90 Rev. 2 FIGtIRE 6 PERS0IMEL CONTAMINATIDIl REPORT tote ttee

• ~

(Leets (Fatsti intes4. tatts

3. age 3. som sale tonale 4. Fregnat.t Tee ne

5. tone nedtese

4. City t. state 4. Itp Cese

9. telopnene paneet iNomei f , _ _1 * ,,,,,,,,_ _ _ _ _

10. telopnene sunset (Businesel f_ ,,,,,,,,) ,,,_ _ . _ _ _ _

11. settet soeurity Nummet . -

12. Wee Desteetty Centeatnoted Yee no

13. CAD Reedtage 0-300 mA 210 0-102 #At _

Ottefly Doetitte tout vnetoessets and Activittee. :nclude Assunt of *tse spent at !sta Leestnen Leestion loceste/outdoets itse spent Aestetty tote.)

1.

1. _

3. ,

4. ,

1.

Cententnotes Ctett.ing Onty _tes_Me Ctetatat Lett gtt lesentestnetten _Yes_

Article of Clothing Ceamente Seteetoe CeWat Reto esa Cletatng Steenteatnetoe _ toe _ ao Beengtouns tem Servey Metet settel No.

inttlea Counts Wlaua Baetettuae Counts annes esengreene lDecentamtmatten Metnoef Aftet Deeentaminatten . sedel hmale Seev etub e93 9 Raad/ShouleeF8 i 885 ' . east '

poet '

sua i ese t kansa #ER f eBS '

Cheet Appropetete fine! Aetten

netvtede Setentoaineted i

l Instvidual Sent to Rosette Dee to continued Whole.tody Centeatnetten ql y Greater then 190 cpe Aseve 94catteunc 011mstate _

- . . .. twetmeALs cort sort sa as art D-34 MIPP Rev. 3

d 1

j

[%d ') Proc. 2.06S Date 6/90 "

i Rev. 2 1

FIGURE 7 RADIOLOGICAL SCREENING PROGRAM TnA mTuG SEEET l

Date: - Times t i Individual Names Social Security Number: )

Address: l Telephone I

Actions Required Reason for RSP Adm. i l' (check applicable (check applicable one) one) Actions Taken* ]

Status / Remarks 2 l

exposure greater continue than $ rem whole- tracking body )

O thyroid

_ blood analysis 1

contamination bionssay

_ internal contamination thyroid count

_ other (explain) whole-body count >

other (explain) l

• Specify action and date Radiological Health Specialist (Signature)

,O-.

V D-35 MIPP Rev. 3

1 i

[;

Proc. 2.116 Date 6/90 V Rev. 4 INGESTION PATBWAY E3&IROBIENTAL SAMPLE COLLECTION I. PURPOSE The purpose of this procedure is to provide guidance for environmental sample collection following a release of radioactive material from a nuclear power plant and contamination of the environment. Samples j collected will be analyzed in the field and/or lab and the results will be used: to assess the extent of the contamination (area and levels), to i

determine appropriate preventive and emergency protective actions, and as a basis for planning reentry / recovery actions.

II. DISCUSSION A release of radioactive material to the environment can present two pathways for radiation exposure to individuals.

One pathway is called the Plume Exposure Pathway. Radiation exposure to individuals results from direct exposure to radioactive material in the 1 O

l passing plume, inhalation of radioactive material in the plume, and/or direct exposure to radioactive material deposited from the plume.

The other pathway is called the Ingestion Exposure Pathway. Radiation exposure to individuals results from the ingestion of milk, water, and non-dairy foodstuffs (such as vegetables and fruits) contaminated by radioactive material deposited from the passing plume. The primary pathway of immediate concern for the ingestion of radioactive material '

from milk ist air - pasture - cow - milk - man. For potable water, the pathway is air - water - man. And for non-dairy foodstuffs, the pathway is air - foodstuffs - man.

III. PRECAUTIONS i

In general, the risk of direct exposure due to ground contamination is small. However, there may be isolated ' hot spots.'

A. Protect yourself and your radiation survey equipment from contamination. Wear gloves when collecting the samples and shoe covers when walking over contaminated ground. Use a plastic bag as a clean ground sheet to set equipment on. Dispose gloves, shoe covers '

and plastic sheeting as Low Level Radioactive Waste.

B. Obtain and use dosimetry equipment as described in Attachment 6.

D-36 MIPP Rev. 3 l

,_s Proc. 2.115 (s_/ ) ' Date 6/90 Rev. 4 i l

I

V. PROCEDURE

l A. Team Ormaniter

1. The first person contacted by the Radiological Health Coordinator (RHC) will serve as the monitoring team organiser. The team organimer wills ]

i a.

assist the RHC in notification of team members:

b. obtain mobile radios from the MEHA communications center and i transport to the Division of Health Engineering (DME): l s

c. be briefed by the RHC on the current plant status and 1 i

d. obtain a key or contact Capitol Security to open DHE (after hours). i J

2. At DHE the team organiser will

a. remove environmental sampling kits from storage (kits are  ;

stored in downstairs storage area): *

b. issue dosimetrys

c. log in/out all team members

d. assist team members in comuleting checkoff list contained in

• this procedures

e. provide briefing about current plant status (provide ,

information required on plant status form): and

f. deploy teams upon instruction by the RHC.

i L

() D-37 MIPP Rev. 3

y>

Proc. 2.139 0, Date 6/90 Rev. 4 NOTE For a response to an event at New Hampshire Yankee (Seabrook), teams will be formed in Augusta at DHE and y dispatched to the York County EOF in Alfred. A Radio-logical Health Specialist will.be assigned to the York County EOF to serve as a coordinator for the field teams..

Environmental sampling kits are maintained at-the York County EOF. Teams dispatched from Augusta will obtain equipment there. Equ1Fient checklists will be completed at the York County EOF.

B.-

Environmental Samole Collection Team Memb2Il (General Instructions)

1. Team members will report to the Division of Health Engineering, 157 Capitol Street, following notification.' Team members wills.

a. assist the team organizer in removing monitoring kits from storage:

b. complete pre-deployment checklists:

c. complete h e ingestion pathway-monitoring team checklist:

d. deploy to area as directed by the team organizer or to pre-designated points as instructed.

2. Team members are issued TLDs and direct-reading dosimeters.

Refer to Attachment 6 for instructions.

l-

3. Radio communication will be through the Maine EOC or as directed by the team organizer.

4. Team member en route should have the low range survey meter on.

5. Team members should contact the assigned EOF by radio as soon as possible after deployment from Augusta to verify instructions and plant status. Contact points will be provided in the initial briefing.

6. While in the field, team members will follow the attached procedures for air and environmental sample collection.

D-38 MIPP Rev. 3

-)

Proc. 2.11$

Date 6/90 Rev. 4 7.- Team members-returning to Augusta will turn in all samples at the Public Health Lab, following the check-in procedure in Attachment

4. Public Health Lab - Sample Handling Procedure, then proceed to DHE for out briefing by the team organizer. All dosimetry and exposure records will be turned in to the team organiser.

Vi DHE INGESTION PATHWAY SAMPLING TEAM OUT CHECKLIST A. Samnlinn Kits

1. Open sampling kits and review the equipment list.

Items listed as missing should be replaced now.

If no' equipment list is present, inventory the kit

.using the attached list (see pg. 10). Report any missing items to the team organizer.

2. Perform operational checks on Radiation Monitoring Equipment.

a. Operational Check of E-140N Instrument with HP-210 Probe

1) Verify instrument calibration sticker is-valid.

2) Check window of probe for damage.

3) Turn range switch to BATTERY CHECK position and verify the n.ater reads within the BATT OK region.

Replace the batteries if necessary.

4) Ensure the response knob is rotated to the SLOW position.

5) Turn the external speaker on.

6) Turn range switch to the low scale and verify meter response with the

] gamma check source.

7) Turn the instrument speaker off until ready to use.

8) Return faulty equipmant to the team organizer.

D-39 MIPP Rev. 3

4.

Proc. 2.11S O Date 6/90 Rev. 4

b. Operational Check - Eberline Model R0-2 Survey Instrument

1) Verify instrument calibration etickar is valid.

2) Turn the function switch to the LBAT 1 position. The meter should read within the BATT OK region.

3) Turn the function switch to the BAT 2 position. The meter should read within the BATT OK region.

Replace the batteries. if necessary.

'4) Turn the function switch to the ZERO position. Set the meter to read zero by rotating the ZERO knob.

5) Turn the function switch to low scale and verify meter response

l. with a gamma check source.

'6) Turn off the instrument until ready to use.

7) Ensure that beta shield opens.

The beta shield should slide open to expose the detector. Close the beta shield to protect detector.

8) = Return faulty equipment to the team organizer,

c. CDV-700/715 Survey Instrument (backup use

'only - not for air sampling)

1) Remove CDV-700 and CDV-715 from box.

2) Vertfy instrument calibration sticker is valid within one year.

3) Check instrument for any obvious physical damage.

() D-40 MIPP Rev. 3

i I h

r .

Proc. 2.11S O Date 6l90 Rev. 4

4) Release spring clips on ends of case and lift chassis from case.

5) Install batteries.

6) Replace chassis in case and fasten spring clips.

7) The CDV-715 has a battery or circuit test position. Turn the select knob to that position. The needle will deflect to an indicator mark on the meter scale.

8) If there is not deflection $

- Check for proper battery installation and retest

- Replace batteries and retest

- Replace instrument and repeat the process.

3. Repisce all equipment in kits and place in O vehicle. Place two plastic bags outside of the

. kit for contaminated trash.

B. ELLLg

1. Perform operational checksi.

a.: Red light comes on when transmitting.

b. Contact the dispatching EOC for radio check message format " Unit to dispatching EOC for a radio check."

c. If not operating, check:

1) battery connections

2) antenna leads

3) repeat Step t,

-C. Personnel Dosimetry

1. Zero 0-200 mR, 0-20 R (low and high range)

(instructions are in. Attachment 6).

() D-41 MIPP Rev. 3

,--....,___.4,

I Proc.-2.11S Date 6/90 Rev. 4

2. Record TLD number, 0-200 mR. and 0 20 R DRD numbers on DHE Individuci Radiation Exposure Card and on sheet provided by R!ic.

D. Receive briefinn from RHC on:

1. Plant status

2. Communication contacts O

1 g k

,)

D 42 MIPP Rev. 3 u

1 i

\ l' Proc. 2.11S O Date 6/90 Rev. 4 ENVIRollMENTAL SAMPLING KIT INVEhTORY NORM. QTY. OPER.

I21lE! 1922 .T.Dl_

ENVIRONMENTAL SAMPLING KIT CONTAINING:

1. Dept of Health Engineer Proc. 2.11S with map

2. Air Sampling Equipment (KIT 1 only) o RADECO Air Sampler o Particulate Filters (box) 1 1

0 o Sample Heads: 2 o Silver Zeolite Cartridge 20 o Stop-Vatch 1 o Charcoal Cartridge (Training only) 10 o Eberline E140N with HP-210 probe l: o Glassine Envelopes (1 pkg.)

1 1

0

3. Radiation Monitoring Equipment

'l . :o Eberline E140N with HP-210 or 210 AL probe 1 0 o Planchettes 20 o RO-2 1 o D Size Batteries O 8

o 9-Volt Batteries 6 l- o ' Sample. Holder 1

4. Protactive Equipment

l. o Disposable Coveralls (Tyvek XL) 2 o Ditposable Gloves (box) 1 o Disposable Booties (pair) 20 o Masking Tape-(roll) 2 s

D-43 MIPP Rev. 3

1 o Proc. 2.11S Date 6/90 Rev. 4 ENVIROI9tENTAL SAMPLIllC KIT INVENTORY (Continued)

NORM. QTY. OPER.

M M ZEE 1_

ENVIRONMENTAL SAMPLING KIT CONTAINING:

'5. Sample Collection o Folding Shovel 2 o Grass Clippers. 1 o Scissors 1 o Garden Trowel 1 o 6' Funnel 5 o Ziplock Bag _(13' x 18' or equivalent) 50

o. Plastic Bags (32 gallon or equivalent) 10 o' Plastic Bottles (1 gallon) 4 o Plastic Bottles (1 quart) 4 l- o Cubitainers'(1 gallon) and Boxes 15 o Bucket (2% gallon) 1 o Rope-(feet) 25

.o -Cooler 1

o Smears (box) 1 o Ziplock Bags'(4' x-7' or equivelent) 50

'6.- . Miscellaneous Equipment o Tape Measure (6' or-equivalent) 1 o Ruler (18')- 1 o4 Waterproof Marker 2 o Pens (black). 4 o Sample Labels' (pkg) or equiulent l 1

-o Duct Tape (2' roll) 1 <

o> Masslinn Cloth 25 l .o Radiac-Vash-( gal.)- 1 o Clipboard 1 o ' Paper (8 x 11 pad) .

1 ll o Fuses for Mobile Radio and Air Sampler 2 o Reflective Vests 2

-l: o Flashlight 1

-o Utility Knife 1 o Laydown Plastic 1 o Rain Suit 2 o Squirt Bottle for Radiac Wash l 1 D-44 MIPP Rev. 3

4

{

Proc. 2.11S-Date 6/90 Rev. 4 ATTACilHENT 1 C0bORINICATION PROCEDURES Environmental sampling teams dispatched from Augusta will be equipped with lmobileradios. These radios operate on the long wave low frequency CEP frequency. Consnunications are possible with the Maine EOC, County EOFs, Maine Yankee EOF,-New Hampshire Yankee Incident Field Office-(IFO) and car to car.

A. Radio coeration

1. To turn the radio on, rotate the OFF volume control knob clockwise until-a click is heard. The green ON indicator light will illuminate.

2. Turn the squelch control counterclockwise until noise is heard. Adjust the volume control for a comfortable listening level. Turn the squelch control clockwise until noise just stops.

3. Press the microphone button and the transmit indicator will illuminate.

The radio is now ready for use.

B. Radio Consnunication with EOF

1. . Keep car running.

2. Do not panic when you pick up mike.

3. Make sure mike button is depressed when speaking and released when not speaking.

4. Stay back 1 to 3 inches from the mike.

5. Check audio quality with your units.

6. Speak in a regular talking voice.

7. Speak slowly and clearly.

8. Write out messages.

9. When transmitting information to the various units, remember the receiving party is writing this information down - so do not rush.

10. Use plain language - no 10 signals, etc., only exception is "over."

11. Repeat 'THIS IS A DRILL,' if applicable, at end of each conversation.

D-45 HIPP Rev. 3

i

. , , , j l

t r

, Proc. 2.11S~

ft Date 6/90 Rev. 4 12.- When mobile unit is in a bad location, move or relay conununications -

through another mobile unit.

s NOTE 1

,- l If you are relaying messages, be sure to inform the receivers that  !

you are serving as a relay and identify the party for whom you are relaying meesages.

1 I

i l

)

(a /

, . t 1

l l- i h

l 1  ;

1 l

l -1 i

1 D-46 MIPP Rev. 3 l

P tl i

Proc. 2.11S E

Date 6/90 Rev. 4 ATTACIBGENT 2 SAMPLE COLLECTION PROCEDURE k

5 NOTE i^ -

After the use of tools such as grass clippers'and shovels, the tool should be surveyed kept for contamination, in a plastic bag betweenwiped uses, with a Masslinn cloth if necesserf, and i

Perform a beta-gassa survey at each sampling location and record on the Environmental Sample Record I

a.

Monitorclosed, window the radiation level at waist level using the RO-2 with the beta b.

Monitoropen.

window the radiation level at waist level using the RO-2 with the beta Li c.

With the beta window closed, check the radiation levels 2' above the ground.

Scan approximately one square meter of ground in an area away from trees, buildings, etc. Record highest reading.

d. Repeat Step c.-with the beta window open. l NOTE Samples other Statesuch as fin fish,-shell fish.,and wild game vill be collected by agencies.

A. Surface Water 1~. -  !

Select stream samples from midstream, if possible, and reservoir samples from the larnest oossible portion of the reservoir.

2.

Use a 1-gallon plastic container, and collect the samples by submerging of the water.the neck of the container 3 to 6 inches below the surface 3..

Complete container. sample label as directed in Attachment 3 and affix to sample D-47 MIPP Rev. 3

Proc. 2.11S

f] '

Date 6/90 V- Rev. 4

4. Screw the container cap on tightly, seal with tape, and check for l leaks. Double bag the sample container as protection against leaks.

5. Enter information on the Environmental Sample Record, indicating if the sample is from a moving stream or still body of water.

B. Drinkinn Water

1. Choose a sample site of the tap that is known to be cont ected to the desired water system, frequently used, and not, treated with water

,,.. softeners, filters, etc..

2. Use a 1-gallon plastic container to collect water samples.

j. 3. Complete sample label as directed. in Attachment 3 and affix to sample

[- container.

4. Open the cold water faucet and allow it to flow about 2 minutes before collecting a sample. Fill' container to within 2 centimeters of the top, j i

V

\

5. Screw the container cap on tightly seal with tapes and check for leaks. l l 6. Enter informatica on the Environmental Sample Record.

C. KL1h

1. Use a.1-gallon plastic container. Collect the sample from the i

freshest milk source. Note time of last milking. Pay for'the milk' sample (usually $2,00), obtain a~ signed receipt form, and include on your expense account.

NOTE: If drawn from a storage tank, indicate last milking, date of tank emptying and if milk has been added prior to the contaminating event. i

2. Complete sample label as directed in Attachment 3 and affix to sample container.

3. Enter information on the Environmental Sample Record.

D-48 HIPP Rev. 3 m

.___________w -

~

_ _ . = . ..

k Proc. 2.11S O Date 6/90 Rev. 4 D. Hggt and Meat Prodacts

1. Ensure animal was sisughtered within the time specified by the Radiological Health Coordinator and the sampling plan. Indicate on-sample label if the animal was fed stored feed and water and if the animal was sheltered.

2. Collect approximately 500 gm of a specific type of meat product (muscle, liver, thyroid, etc.) and place in plastic bag 18" x 18' and tie neck of bag.

3. Complete sample label as directed in Attachment 3 and affix to sample container.

4. Place in second bag and tie it.

5. Enter information on the Environmental Sample Record. Indicate where animal was raised, date of slaughter and type of feed given to animal.

E. Venetables

1. Collect 1 kg of the edible portion of cabbage or other leafy vegetables in season. Place in the provided plastic bag. Pay for the vegetables and obtain a signed receipt form and include on'your expense account.

2. Complete. sample label as directed in Attachment 3 and affix to sample container.

3. Enter information on the Environmental Sample Record.

F. Hav. Plants. Etc.

1. Using the grass clippers or shears, collect the vegetation from i square meter. Place material in a provided plastic bag. Cut at 1 to 2 cm above ground level, taking care not to contaminate the sample with soil. Do not uproot the vegetation.

2. Complete sample-label as directed in Attachment 3 and affix to sample container.

3. Enter information on the Environmental Sample Record.

G. 1211

1. Choose an open area that is easily sampled, is not sheltered by trees or-building, and is free of large stones and heavy vegetation.

( D-49 MIPP Rev. 3

i

-r~ Proc. 2.11S i . Date 6/90 Rev. 4

2. Remove vegetation, stones larger than l' in diameter, and any debris from the area.

3.- Insert the shovel straight 'down into :he ground and dig away the soil to create a sloping trench with one ;erpendicular wall. Collect one l inch of soll from a.one square foot :rea from the surface at the edge 'l of the wall.

l

'l 4. Place the sample in a double plastic bag or covered container.

5. Complete sample label as directed in Attachment 3 and affix to sample container.

l: 6. Enter information on the Environmental Sample Record.

H. Seaweed Alnae '

1. Fill a large plastic bag full of seaweed with at least 3.5 kg (over 10 lb.).

2. Complete sample label as directed in Attachment 3 and affix to sample L

i 14.O

\\ )-

container. l 3.- Enter information on the Environmental Sample Record.

I. Seawater

1. Use a 1-gallon plastic container to collect water samples.: Submerge the neck of < the container 3 to 6 inches below the surface of the water.

2. Screw the container cap on tightly, seal with tape, and check- for leaks.

3. Complete sample label as directed in Attachment 3 and offix to sample container.

,3 4 . :- Enter information on the Environmental Sar:ple Record.

J. Iggi 1

1. Collect enough eggs, directly from farm if possible, to nearly fill a one-quart plastic bottle.

2. Break eggs and drop contents into bottle using a funnel. I D-50 MIPP Rev. 3

Proc. 2.11S G Date 6/90 Rev. 4

3. Place shells in plastic bag (12' x 12') rnd seal bag.

4. Screw bottle cap on tightly and sen1 with tape.

5. Complete sample label as directed in Attachment 3 and affix to sample container.

6. Enter information on the Environmental Sample Record.

K. Field Meagg ement Field measurements of collected samples may be performed at the directiin of the team organizer. Field measurement does not replace laboratory analysis. All samples should be retained for analysis by the Public Health Laboratory.

1. Dry Sample (Vegetation, forage, food crops, seaweed)

a. Collect sample as directed in this procedure for the media sampled.

Double bag the sample. Perform a wipe survey of the outer surface of the sample bag to ensure a clear outer surface.

O b. On the Environmental Sample Record, record the background count rate.

c. Flatten the plastic bag containing the sample. Place the probe in the center and wrap the bag (and sample) around the probe. Record the sample count rate on the Environmental Senple Record. If using pancake probe, place probe face directly on surface of bag,

d. Indicate on the label if a field measurement was done and give background and sample count rate. (For example, background equals 20 cpm, sample count rate is 30 cpm: Write this on the label as Field Measurement or 'FM" - 20/30).

e. The sample will be screened according to Public Health Laboratory Procedure 130 ER. Dry samples with field counts greater than 500 ene should be separated from other samples.

D-51 l MIPP Rev. 3

4 Proc. 2.11S Date 6/90 Rev. 4 L. Environmental TLD Collection Environmental TLDs will be collected and exchanged in accordance with the Maine Department of Health Engineering Procedure 5.10. Environmental Monitoring, upon direction by the Radiological Health Officer. 'TLD Route Directions-for York County,' Attachment 7 and the ' Surveillance Report -

Checkoff List,' Attachment 8, provide directions to the*TLDs. Take RO-2 readings at 2' and 30" above the ground and complete the information requested.

9 O

D-52 MIPP Rev. 3

. . . .. - .r}

~,_,;

~

i ..' Proc. ' 2.11S 2 Date 6/90 Rev. 4 Dates EINIROIBIENTAL SAMPLE RECORD l

t

! Sausple Background Sample Type Sample. Time 1-Walst Level, WC (altthr)

Count Location Count '

Number Rate Rate 2-Waist Level. WO (mit/hr) 3-2* WC (mR/hr)

(cpm) -(cpm). 4-2". WO (mR/hr) -

1- ,

2-l 3-4-

1-2-

3-l 4-l 1-2-

3-l 4-

! 1-2-

3-4-

Collected by: ~

R:: corded by: **

• Other team ===hers:

Serial number of instrument (s):

D-53 HIPP Rev. 3 I

o

~'- - -"

_ - _ _ _ - . _ _ - - _ _ - - _ - . - - _ _ . . . _ . - _ . _ . - . . - . . - - -- u+, - . . , , . -

I f

Proc. 2.118

{

4f Date 6/90 Rev. 4-ATTACIMENT 3 LARELING INSTRUCTIONS fiff --

Four digit sample number, Date x Time Location --

Describe location by nearest landmark. If at a preselected point give the i.

1 Collector _

Enter team designation.

Material --

Enter type of sample. If milk, include time since last milking, source of feed, if animal was on stored feed and time the milk was in a holding tank. Indicate amount of milk added to the holding tank after the contaminating event if known.

.-(Use this space 1

/ -for additional .

'k information.)

e FM Sckgd/ Sample --

Indicate in lower right hand corner if a field

' measurement was.done. Give background (Bckgd) '

.and sample count.

. The back of the label f'orm may be used if.more space is needed to describe the sample or the sample location, y

1. Complete label for each sample collected. Use a ball point pen and write on a hard surface to ensure writing is legible on all copies.

2. = When completed the label will be affixed to the sample.

3. Remove the second label-and keep with the Field-Heasurement Record.

4.

ALL samples will be returned to the Public Health Lab and logged in using the PHL sampleLhandling procedure.

5. The Field Measurement Record and the label copies will be turned into the team organizer upon return from the field, gh D-54 HIPP Rev. 3

. Q/ .

'-"' ' ' ' ' ' ' ~ ' '

l l

Proc. 2.11S O Date 6/90 Rev. 4 ATTACHMENT 4 PUBLIC REALTH LAB - SAMPLE HANDLING PROCEDURE Sample collectors must keep a record of pertinent information en all samplec.

Pertinent information includes the time and location of sample collection and any other information that will help to identify the source of the sample at a later date. All samples must be labeled with a tag which includes a sample number and other identifying information.

To drop off a sample at the Public Health Lab

1. During the working hours (7:00 a.m. - 5:00 p.m., Monday - Friday)

a. Leave labeled sample on loading dock,

b. Enter building and notify radiological personnel that a sample is on the dock,

c. Assist lab personnel in filling out log sheet.

2. After working hours:

a. If possible, notify lab personnel that sample is on the way to the lab.

b. Leave labeled sample on the loading dock.

NOTE: The a:aaples will be Screened according to Public Health Laboratory Procedure 130 ER. Dry samples with field counts greater than 500 cpm should be separated from other samples.

c. If it is not possible to enter the building from the loading dock area, enter building from the main entrance on State Street. Use security phone to call the lab at 1714 or 2727. If no one is in the lab, have security call the Director or Assistant Director at home.

They will contact lab personnel.

d. If possible, collector should wait for lab personnel to arrive in order to fill out log sheet. If it is not possible for collector to wait, he should leave all pertinent information concerning the sample attached to the sample on the loading dock.

D-55 MIPP Rev. 3

Proc. 2.11S Date 6/90 Rev. 4 ATTACHMENT 5 FIELD TEAM PLANT STATUS 1.- DATE: TIME:

2. CLASSIFICATION LEVEL:

[ Unusual Event [SiteAreaEmergency Alert- _ General Emergency

3. METEOROLOGICAL CONDITIONS:

Wind Speed' mph Stability Class Wind Direction FROM Precipitation 4 RADIOACTIVITY:

~

~ "

Airborne Has been released Water Has not been' released [SurfaceSpill O- Time commenced:

Release terminated: [] Yes []No Time terminated:

Anticipated or known duration of release hours.

Projected dose rate and doses:

Arrival Dose Rate (Rem /hr)

Time Whole Body Thyroid

Site. Boundary 2 miles 5 miles 10 miles 5.:'SPECIAL' INSTRUCTIONS:

6. COMMUNICATIONS:

A. Radio:

B. Telephone: DHE/ Team Organiser 800-452-1914 MEMA/ Rad Health Coordinator 800-452-8735 York County EOF - 324-3521  !

O. Newington IFO D-56 MIPP Rev. 3 4

y-t Proc. 2.11S Date 6/90 Rev. 4 ATTACHMENT 6 INSTRUCTIONS TO WORKERS - DOSIMETRY OPERATION AND USE OF DIRECT-READING DOSIMETER AND CHARGER A. Zeroinn Dosimeter

1. Point a dosimeter towards a light source (see Figure 1). Rotate the dosimeter so the word " Roentgens' or 'Milliroentgens' appears right-side up.

2. Read the position of the hairline on the scale. If the hairline is visible and positioned between zero and the first mark, record the reading on the Individual Radiation Exposure Card as the ' initial reading.' otherwise, resero the' dosimeter using a dosimeter charger.

3. If batteries have not been previously installed in the charger to be used, loosen the thumbscrew in the top or bottom center of the charger with a coin and remove the case bottom cover. Install battery O (observing + and - markings) and reassemble charger.

4. Position the charger on a flat surface. Unscrew the cap on the charging contact and place the end of the dosimeter opposite the pocket clip and eye' piece on the charging contact (see Figure 2).

5. Applying firm downward pressure, a light will come on and the internal dosimeter scale and a hairline should be visible..

6. If the hairline is not visible, rotate the control knob (Figure 2) until the hairline appears.

7. Set the hairline on zero.

8. Remove the dosimeter from the charger and point towards a light source.

If the hairline is between zero and the first mark on the scale, the dosimeter is ready for use. Otherwise, use the charger to properly position the hairl. A Install the charging contact cap.

B.. Usinn Dosimeters

1. Record ' initial" reading on Individual Radiation Exposure Card.

O D-57 MIPP Rev. 3 l

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Proc. 2.11S Date 6/90-  ;

Rev. 4

2. To read a dosimeter at any time, point it towards a light source and  ;

read the position of the hairline on the scale (Figure 3 is 25 mR and '

Figure 4 is 10 R). Accumulated exposure is this number minus the initial reading recorded on the Individual Radiation Exposure Card. j i

3. Wear direct-reading dosimeters (and TLD) on the front of the body in  !

the area between the neck and waist, in a pocket if possible. j

4. Do not permit anyone else to wear your dosimetry.

5. Complete all parts of your Individual Radiation Exposure Card except columns for ' final" readings.

'6. Keep the Individual Radiation Exposure Card in your possession at all  !

times.

C. Radiation Ernosure Control g '. 1. Unless otherwise directed, read your direct-reading dosimeter every 15

-minutes and record the time and exposure on the Individual' Radiation j Exposure Card, r k '

2. If the reading on the 200 mR direct-reading dosimeter is greater than -j or equal to 100 mR (half-scale). notify your supervisor. Take all j further readings on your 20 R direct-reading dosimeter.

-l 3.- If-the reading on the 20 R direct-reading dosimeter is greater than or equal.to 1 R, notify your supervisor.

4. If the reading on the 20 R direct-reading dosimeter.is greater than or equal to 3 R, notify your supervisor who will rotate you out of the-area. .

{

D.' Termination of Assinnment

~

At the end of your assignment, report back to the location designated by i Jyour supervisor. Record the final reading of yaur dosimeter on the Individual Radiation Exposure Card. Subtract the initial reading from the 11DA.l. reading to obtain Total Exposure. This will'be recorded in the

-Personnel Dosimetry Log, meintained by Division of' Health Engineering (DHE).

O D-58 MIPP Rev. 3

n .

1 .

1 s  !

L{Vj Proc. 2.11S-Date 6/90 l Rev. 4 If you are being relieved of your assignment by another individual, theni o turn over all logs, procedures, and equipment except dosimetry to your reliefs o notify your supervisor of the turnovers and o report to the location designated by your supervisor.

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( Proc. 2.11s Date 6/90-

?.ev. 4 OPERATION OF DIRECT-READING DOSIMETER AND CHARGER pochet stie

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!- ? (* 9 9 9-9 needing equals 25 kilitroenteens - Readi:.4 equals 10 Roentgen"i l

PIACE CHARGER HERE t

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l D-60 MIPP- Rev. 3 L

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{

O. Proc. 2.11S Date 6/90 Rev. 4 INDIVIDUAL RADIATION EKPOSURE CARD Name: Date:

Town or Agency: _._

Assignment:

Direct Reading Dosimeter Numbers High Range (0-20 R) Low Range (0-200 mR)

TLD Badge Number Read the dosimeter every 15 minutes unless otherwise directed. Record the readings on the reverse side of this card.

Notify your supervisor if 200 mR DRD reaches 100 mR 20 R DRD reaches 1 R or 3 R

- DRD becomes lost, damaged or DRD goes off scale Ingest KI only when directed by your supervisor via dispatcher.

O-Record date and time

-Report any adverse side effects to your dispatcher or upon arrival to your assigned-facility.

(Back)

Direct Reading Dosimeter Record TIME 0-20 R 0-200 mR TIME 0-20 R 0-200 mR TIME 0-20 R 0 200 mR

.5 Potassium Iodide Record Jate: Time Date Times O_. Dates' Time:

D-61 MIPP Rev. 3

O. Proc. 2.11S Date 6/90 Rev. 4 ATTACHMENT 7 TLD ROUTE DIRECTIONS FOR YORK COUNTY 4

1. -Biddeford Drive south from Augusta on the Maine Turnpike and take Exit 4 (Biddeford). Turn left onto Route 111E and drive 1.3 miles. Turn right onto Route 1 South and drive another 1.3 miles. TLD is located on the third telephone pole- (NET

1. 131) after the Biddeford Hotel, on the right side of the road.

2. Arundel Continue on Route 1 South for 4.6 miles. TLD is located on the telephone pole (NET #161-61) next to Mann Memorial Clinic for Animals on the left side of the road.

3. -Kennebunk Continue 1.5 miles on Route 1 South. Turn left onto Routes 9A East and 35 South and drive 0.7 mile. TLD is located on telephone pole (NET #38) in front of a large blue house with white trim (Bibber).

()_4. Kennebunkport continue 2.9 miles on Routes 9A East and-35 South and turn right onto Route 9 West. Drive 0.95 mile to an intersection' with Fairview Drive. TLD is located on the telephone pole

-(CMP $47) across from Fairview Drive on the right side of the road, at Grant Farm.

5. Wells Continue 3.2 miles on Route 9 West and turn left onto Route

-1 South. DriveEl.8 miles, to Wells Post Office on the left.-

TLD is located on Telephone Pole #J1 on the left side of the Post Office.

Wells Beach Continue 2.7 miles to a large ' Wells Beach" (Seaweed 2H O) sign. Turn left onto Eldredge Drive and drive 1.0 mile.

Turn right and park along the cement wall. Take seaweed and-water sample.

6. Ogunquit Go back to Route 1 and turn lef t. Drive 3.0 miles on Route 1 South through the village. turn left on School Street and go to the Police Station. TLD is located on the telephone pole (CMP #2) next to the police station.

D-62 MIPP Rev. 3

1 k

Proc. 2.11S Date 6/90 Rev. 4 ATTACBHENT 7 TLD ROUTE DIRECTIONS FOR YORK COUNTY (Continued)

7. York Go back to Route 1 and turn left. Drive 5.3 miles on Route 1 South just past ' Blueberry Hill Child Development-Center.'

TLD is located on the telephone pole (#29D) about 100 yards past this on the right side of the road, slightly farther away from the road than usual.

Bellamy Wharf Continue on Route 1 South for 6.8 miles and (Seaweed, 2H O) turn left beyond Watt's Factory onto Haley Road. Continue 3.0 miles and bear right on Route 103 at fire station.

Drive 0.4 mile and turn left across from the Kittery Point Post Office to Bellamy Wharf. Take seaweed and water semple.

Go back to Route 1 and turn left. Drive 0.7 mile to Mrs.

8. . ,Kittery and Me Restaurant'on the right. TLD is located on the

-.. telephone pole at the north corner of the restaurant parking lot, next to the sign.

9. Eliot Continue on Route 1 South to Route 236 North. Drive 6.3 miles on Route 236 North and turn left onto Route 101 North.

Go 0.1 mile to Old Field Road. TLD is on the telephone pole (CMP #1, NET #149) across from this road.

10. .-South Berwick -Go back tc P.oute 236 and turn left. Continue 4.4 miles and bear right, still on Route 236 North. Drive 0.3 mile to a Getty filling station. TLD is located on telephone pole (CMP #33) across from the filling station on the right side of the road.

?ll. Berwick Continue 3.6 miles on Route 236 North and turn right onto Route 9 East. Drive 0.6 mile just past a Mobil filling station. TLD is located on the second telephone pole (NET iS4-30S) past the filling station on the right side of the road.

12. North Berwick Continue 6.5 miles and turn left onto 4 North. Drive 1.0 mile to the water tower. TLD is located on telephone pole (NET #87-29) on the right side of the road.

O D-63 MIPP Rev. 3

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/~'s I

) ' Proc. 2.11S Date 6/90 '

-Rev. 4 ATTACEMENT 7 TLD ROUTE DIRECTIONS FOR YORK COUNTY-(Continued) 13 . . Sanford Continue 7.3 miles on Route 4 North to Route 4A intersection. Drive straight across, still on Route 4 North and continue for 1.8 miles. TLD is located on the second telephone pole (NET #111-9) past ' Cozy Corner Store" on the right side of the road.

14. Alfred Continue 2.7 miles on Route 4 North _and turn right onto Route 111 East and drive 1.0 mile. TLD is located on the telephone pole (NET #321, CHP #J16) on the right side of the road across from G.R. Roberts Inc.

15. Lyman Continue 5.2 miles on Route 111 East, just past an intersection with a flashing light. TLD is located on the-telephone pole (CMP fJ310 NET #477) on the'right side of

. g ~c the road. 0.1 mile past the light.

i, P

D-64 HIPP iev. 3 l

F A i

4 Proc. 2.11S

[. Date 6/90 i

\

Rev. 4 ATTACBMENT 8 SURVEILLANCE REPORT - CHECKOFF LIST DATE

TLD Qty '

Seawater M1y Seawater M1y Fresh Water M1y

1. 1 Biddeford Just prat Biddeford Hotel

1. 2 -Arundel At Hann Memorial Clinic i

1. 3 Kennebunk In front of the Bibber residence

1. 4 Kennebunkport Across from Fairview Drive

1. 5 Wells Left side of Post Office

-f l C -

iSA .Hoody Point At Moody Point (Wells Beach)

1. 6 .0gunquit At police' station

1. 7: York Just:past Blueberry Hill Child Dev. Center >

1. 8A Bellamy Wharf At Bellamy Wharf'(Pepperrell Cove)

1. 8 Kittery, At Mrs. and Me Restaurant g

1. 9 Eliot Intersection Route 111 and Old Field Road

1. 10 South Berwick Across from Getty-filling station ill Berwick Just past Mobil filling station l 'il2 North Berwick Near water tower i

1. 13 Sanford. Just past Cozy Corner Store i: ,

l- $14 Alfred Across from G.R. Roberts. Inc.

il5 Lyman Just past Route 111 and 35 intersection

( D-65. MIPP Rev. 3

_ ._ __ ._ ~_ _ _ _ - _ _ . . . . _ _ _ _ . . . _ . _ . __ _ _ _ _ . . _ . _ . .

1 Proc. 2.128 I Ox Date 6/90 Rev. 1 I

l AIR SAMPLING PROCEDURE l

I. PURPOSE i I

The purpose of this procedure is to provide guidance for the collection of air samples.

II. DISCUS $10N l L

Airborne plumes will disperse by expansion and dilution. Be%use of this, concentrations of radioactivity will be highest towards the center, at the  !

so called ' centerline.' The centerline can be determined by passing through a plume and observing the rise and fall of counts on a radiation detector. Once the centerline is determined an air sample is drawn through a particulate filter for airborne solids and a cartridge filter for collection of radiciodine.

l l

A

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l g g lume Concentratien

- Plume Dose Rate i'

Plume Cantarlir.e l

It should agi be expected that, in traversing across the plume, a rapid increase and uecrease in dose rate would be observed. Rather, a long '

plateau region of gradually increasing, steady, and then decreasing rates is expected to be observed. The sampling location should be chosen as the ,

• best estimate' of the center of this dose rate plateau, l

Radiation readings using a betalgansna probe will be taken while the air  ;

sample is be bg collected. These readings will include open and closed '

! shield read. tags at vaist and ground level.

1 After the sample is collected, a field count will be performed on the particulate and canister filter.

These retdings,and the waist and ground level readings are reported to the E0C.

D-66 MIPP Rev. 3

. ~ - . - . _. . _ - - . - . - - . _ , . - .

' Proc. 2.128  !

k',) Date 6/90 Rev. 1 Locations for air sampling will be determined based on fis1d radiation measurements or as recosur. ended by Division of Health Engineering (DHE) personnel and relayed through the Radiological Health Coordinator (REC). l A. Onorational Cheeks - Radeco - Air Sanrg C&UTIOh j

ENSURE ENGINE IS RtDGtIlhJ BEFORE CONNECTING AIR SAMPLEE TO MTTERY.

1. Check that a filter is incialled in the air sampler.

I

2. Connect the ORANGE clamp from the air sampler unit I power cable to the positive (+) terminal of a 12-volt battery.

3. Connect the BLACK clamp from the air sampler unit power cable to a grounded part of the chassis or engine block away from the battery.

4. Turn on the unit.

5. Allow the rotameter to stabilize and observe a positive air flow indication.

6. Turn off the unit. , - - - .,

7. Disconnect the air sampler unit ;cwer cables from the vehicle, grounded cable firet.

8. Return faulty equipment to the team organiser. ,_

B. Air Samnlina Location by Field R Qi1_ tion MeasuNtqfD1

'JOTE If high plume dose rates are expected, the air sampler filter holder should be loaded prior to entering the high dess tato areas.

_-= i D-67 MIPP Rev. 3 ,

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Proc. 2.12S

.(N/ ) Date 6/90 Rev. 1

1. While driving to air sampling locations, continuously monitor radiation levels en route using the E.140N with the HP-210 probe on the dashboard against the windshield. If the count rate exceeds 5000 cpm, energize the R0-2 and monitor dose rates.

2. If the'RO-2 shows an increase in radiation levels, report '

readings to the York County E00 I M . Note the location of the change and continue driving until you have gone completely through the plume (i.e., radiation readings have reached a high level and then returned to a background level). Note the locations of the high level and low level readings. If a dose rate of 500 mR/hr or greater 16 measured, obtain approval from '

the Radiological Health Coordinator before proceeding further or exit the plume and await further instructions.

NOTE If it is not possible to drive completely through the plume due to road access limitations, then proceed to Step 3.

, 3. Choose a sampling location tht, represents the center of a dose

\

rate plateau across the plume or the highast readira across the plume. Do not spend greater than 5 minutes locatin:. a sampling

location within a plume.

4. Lumediately report the specific sampling location . hat has been chosen and the sample area dose rates to the E0F and, complete the steps in Section D.

C. Recr - nded Samnlina Points i

1. The RHC may direct the field team to a location most likely to be passed over by a plume. Personnel should locate the location on l

.the map, proceed to it, then collect an air sample as directed in Steps D-1 and D-10. ,

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() D-68 MIPP Rev. 3 k

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,- s Proc. 2.128

( ) Date 6/90 i A/

Rev. 1 l t

D. AIR SAMPLING AND BETA-GAMMA SURVEY p

NOTE o Take all precautions necessary to avoid contaminating yourself and your equipment when taking surveys outside the vehicle.

o If you have touched any outside surfaces, e.g., car door or hood, then put on a fresh pair of gloves before handling ,

filters.

o Ensure instrume.nt + robes do not become contaminated.

o Use the R0-2 for area radiation surveys. '

1. At each air sample location, take the following surveys using the R0-2 and report the dose rates IMHEDIATELY. Once reported, set up the air sampler. Record the highest dose rate readings on the Field Radiological Survey Record (attached).

NOTE For direct radiation readings, the range should be selected to -

keep the needle in the area between 25t and 752 of the meter jscale,

s. Monitor the radiation level at waist level using the R0-2 with the beta window closed.

b. Monitor the radiation level at waist level using the R0-2 with the beta window open.

c. With the beta window closed, check the radiation levels 2' above the ground. Sean approximately one square meter of  ;

ground in an area away from trees, buildings, etc. Record highest reading.

d. Repeat Step D.ic with the beta window open.

2. Load the air sampler with both a particulate filter and silver teolite cartridge. Show the flow direction on the side of the cartridge. Place particulate filter in the filter holder with fuzzy side out.

3. Collect air samples in open areas away from trees, buildings, etc.

D-69 MIPP Rev. 3

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Proc. 2.126

\ ('~\ Date 6/90 V Rev. 1 l

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4. Place the air sampler on the vehicle in a stable position (e.g., l hood, f ender, etc.) and on an uncontaminated surface. The 3

g sampler should not be placed on the ground. ,

5. During wet weather, place the air sampler on the air cleaner of i the vehicle when taking an air sample.  !

6. Clip the cables to the battery terminals of the vehicle, start i air sampler, and record time started.

L 7. Record the initial flow rate (should be about 2 cfm or $71pe).

l l

! 8. Run the air sampler until an approximate 15 ft3 (or 4281) sample )

is collected (about 7.5 minutes).

9. After the air sample has run for the specified time, record the

, final flow rate and turn the sampler off.

10. Disconnect sampler and move to an area with low background count (less than 300 cpm) for sample counting.

E. Samnle Counting I

[~

1

1. Once outside the plume area, reconnect the air samp16r to the I battery and let the sampler run about 30 seconds to purge noble gases from the cartridge. Take a background count using the E.

140N with the HP-210 (pancake) probe. Record this on the survey form.

2. Remove the sample head and separate the filter holder from the cartridge holder.

3. Hold the HP.210 probe with the window centered against the filter holder and count the filter.

1

4. Record the results.

5. Write the date, time, sample location, sampling time and flow rate (CFM) on'the stickers provided in the kit. Attach a sticker i j

to a plastic bag. Remove the retaining ring and, using tweezers, remove the filter from the head and place it in the bag.

6. Remove the retaining ring which holds the cartridge in the sample head, l

D.70 MIPP Rev. 3 4

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Proc. 2.12S O Date 6/90 Rev. 1 NOTE The radioactive iodine results you obtain from the silver aeolite count are very important in determining the protective actions that should be recost. snded for public protection.

These samples should be carefully handled, accurately analysed and promptly reported.

l 7. Hold the HP-210 window centered within a half inch of the filter and count the cartridge. Record the results.

8. Using gloves, reaove the cartridge from the holder and place it in a plastic bag- Attach a sticker (Step 5).

9. Be certain that all filters and cartridges are properly bagged, labeled, and set aside for analysis at the EOF.

10. Report the results to the York County E00. Road the information on the survey form exactly is written.

11. Calculations of air activity will be done at the EOC.

12. If additional samples are requested by the EOC, then go to the location designated and repeat Steps D.1 through E.12. Complete another survey form and call in results as in Step E.10.

13. When directed, returr. to the York County E0C for monitoring.

14. Before returning to the E0C, survey your vehicle and yourself for contamination and check your direct-reading dosimeters. If contamination is found, call the team organiser.

15. Unless otherwise instructed, return all ;amples to the York County E00. Turn in your Individual Radiation Exposure Cards to the team organiser.

16. Await further assignments or, if instructed, recheck your survey kit and prepare it for further use or return it to storage.

D-71 MIPP Rev. 3

.. .i ,i ,,,,iii<iin ,e i 6

O O O Proc. 2.12S Date 6/90 Rev. 4 j FIEIA RADIGIACICAL SMTRY REDED Team Members:

Date:

Action 1 2 3 4 5 6 Current Time AM/FM Waist Level: 3 Ft. - window closed, mR/hr Waist Level: 3 ft. - window open, mRlhr 2* above ground - window closed, mR/hr 2" above ground - window open, mR/hr Air sample start time Initial flow rate CPM or LPM Final flow rate CPM or LPM Air sample stop time Total air sampling time A. Background count rate, CPM B. Silver Zeolite cartridge reading, CPM C. Particulate filter reading, CPM Net particulate count rate (C-A), CPM Net radiciodine count rate (B-A), CPM Wind direction (if known)

Wind Speed (may be descriptive)

Approximate Location t

i D-72 MIFF Rev. 3 t

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APPENDIX E 1 i

1 1

i 1

h MAINE PUBLIC REALTE LABORATORY 1

PROCEDURES FOR THE RADIOCHEMISTRY LABORATORY '

\

DURING A NUCf2AR EMERGENCY l

l l

E-1 MIPP Rev. 3

MAINE PUBLIC IIALTE 1ABORATORY PROCEDURES CONTEf?S AND REVISION STATUS EugdttL AgL, Procedure Title g 120 ER 0 Notification of Personnel During a Nuclear E-3 Emergency 125 ER 1 Preparation of Laboratory for Response to E-5 Emergencies at Nuclear Facilities 130 ER 0 Receipt and Screening of Potentially E-10 Contaminated Samples 320 ER 1 Sample Preparation and Prioritisation E-13

$20 ER 1 Analysis of Samples Under Emergency E-16 Conditions 620 ER 0 Reporting Sample Data E-23 O

E-2 MIPP Rev. 3

i Proc. 120 ER Date 8/88

{O) Rev. O MAINE PUBLIC BALYH LABORATORY NOTIFICATION OF PERSONNEL DURING A NUCLEAR ENERGENCY PROCEDURE:

(1) The Laboratory Director or Assistant Director will be notified by the Commissioner or designated person that laboratory services are needed for processing samples. The Director will then contact laboratory personnel and direct them to report to the laboratory or alert them that they are on standby status.

(2) It is highly desirable to provide at least two people for each shif t being scheduled. Each team should include one chemist familiar with equipment and methods of calt 11ation.

(3) Appendix A contains telephone numbers for laboratory personnel. Other personnel may be contacted if needed.

O  !

E-3 MIFP Rev. 3

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Proc. 120 ER I

[( /.') Date 8/88 Rev. O j

APPENDIX A

! (

LABORATO W PERS03DIEL j Address Home Phone Business Phone Dr. Philip Haines 923-3391 RFD fl 289-2727 923-3394 (camp)

Vassalboro, Maine )'

Jack Kruegar 845-2482 RFD #1, Box 2310 289-2727 S. Liberty, Maine Thomas Dwyer 622 6202 i RFD #5, Box S30 289-2727 J Augusta. Maine '

'Cheryl Baker 445-2956 289-2727 RFD #6 Box 377 Augusta Maine

()

Theresa Zibura

-RFD #6 445-2817 289-2727 Augusta. Maine Jeanine Thayer 623-8052 289-2727 4 Middle Street Hallowell Maine L Richard French 622-3876 RFD #7, Box 507, 289-2727 "

Augusta. Maine 1

E-4 MIPP Rev. 3

Proc. 125 ER f Date 10/89 l

Rev. 1 MAINE PUBLIC HEALTH LABORAff,RY PREPARATION OF LABORATORY FOR RESPONSE TO EMERGENCIES AT NUCLEAR FACILU IES PRINCIPLE OF THE HETHOD:

This procedure describes the actions for laboratory personnel to take to prepare <

the laboratory for processing samples taken during a nuclear power plant emergency. This proc 63ure lists steps necessary to ready key instruments for counting of vipes and samples, to assemble materials necessary for screening of samples, and to ready the sample preparat!on area for handling of potentially contaminated samples. >

PROCEDURE: '

(1) First person to arrive at the laboratory shall unlock doors to Chemistry (Room 172), Chemistry Office (Room 171), and Counting Room Annex (Room 184).

(2) Turn on Panasonic UD-702E TLD reader and printer. Adjust date to correct digits. After allowing at least 15 minutes for warmup, anneal sufficient f- g personnel badges for laboratory personnel. Assign a TLD badge to every '

(j laboratory worker and record the appropriate information on Form RADLAB ER2. i I

(3) a.

Te rminatt. collection of data on both the GeLi and the Ge detectors.

Obtain printout of data accumulated to date.

b. Should the system not be in operation, refer to the Users' Manual for the Carberra Series 80 MCA for system setup. Memory for this instrut.ent is 16K and should be divided into 4 PHA+ inputs. Group (2 ordinarily collects data from the 20Z GeLi and Group #4 from the 242 GeLi.

c.-

Run the Cs-137 Tracerlab F-324 standard for 100 sec. on each detector record results in ' Daily Stds. Gamma' book and verify that each instrument is operating correctly.

(4) a. Terminate collection of data on Canberra 2404F low background beta counter. Restack samples, remove sample holder tube, and label data sheet with proper sample identification. Insure that thw supply of P-10 gas is adequate and'that the detector tray is in the proper position.

b.

If P-10 gas has run out, replace tank and initiate a long purge. This requires one hour.

E-5 MIPP Rev. 3

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-s Proc. 125 ER i T Date 10/89

[O Rev. 1 l

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c. If system controller is off, refer to Users' Manual for setup procedure. Set Program #1 parameters as follows: DISC 7308 VOLTAGE 1530: " TART SAMPLE Os END SAMPLE 30: TIME 2 minutes. j

d. Run a background planchet at the beta voltage for a minimum of 20 l

{

minutes and the Sr90 'F005' standard planchet for 10 minutes. Record '

values in Canberra book and insure that they are in the proper range for instrument operation.

(5) a.

Terminate printout of collection of data data collected to on both 3*x3' Na1 detectors. Obtain date.

1 b.

Should the ND66 be off, set system up according to the following parameters

)

I IH 4.0.0.0 GR 1,4 CH 1,2048 DE S1 '

Group #2 ordinarily collects data from the large shield, and Group $3 collects from the small shield. Set correct date and time. Refer to 7-~ instrument manual for any questions regarding operation.

]

c. For each detector, run the Cs-137 Tracerlab F-324 standard for 60 seconds. If necessary, adjust the fine gain of the appropriate amplifier so that the maximum of the Cs-137 peak falls in the range of  !

Channel Numbers 656-671. Record result of standard in ' Gamma Daily Stds.' book and verify that the values obtained indicate acceptable instrument operation.

(6) a. Obtain the two carts used in Chemistry and remove all objects from them. One cart (A) will be used for supplies necessary for screening samples: the other cart (B) will be used for transportation of samples, b.

Cover both top and bottom shelf of each cart with disposable plastic.

This will need to be taped in place.

c. Place a strip of tape across the center of the top of Cart As this will divide the clean area from the contaminated area.

d. Place the large white enameled tray on the clean side of the top of '

Cart At this will serve to protect the CDV-700 meter from possible spills.

E-6 MIPP Rev. 3 t ,

d

r{

4 .

iV I[ Proc. 125 ER Date 10/89 Rev. 1

e. Obtain the CDV-700 meter from Room 184, turn the selection dial to the X1 scale, and, with open window, obtain a background reading. This should be less than 0.1 mr/ hour. Place the probe against the check source on the side of the meters the reading should be approximately 1 mr/ hour (you will need to switch to X10 range). Turn meter off and place in white tray on Cart A.

f. Check ' Emergency Screening Supplies' box located in Room 184 and verify that all materials listed in Appendix A are in the box. Place box on bottom shelf of Cart A. Take any available vastebasket with clean liner and place on bottom shelf of Cart A. Wheel Cart A and B to the area inside the loading dock door.

(7) Remove hot plate, heat lamp, and all materials possible from hood in-radiation section'and from bench adjacent to hood. Place layer of disposable plastic in bottom of hood. Place double pan balance (normally located on radiochemistry bench) in hood and cover pans with plastic.

Place plastic over bench and tape in place.

(8) Place warning signs on tha outside of shipping room doors to prevent people not-involved with sample screening from entering the area.

(9) Tape plastic over an area of the shipping room floor where screening will O be done and place Cart A on this. Place plastic over an area of the floor in a remote section where rejected samples may be placed. Finally, place plastic on a shelf door table top where samples awaiting transport to the laboratory will be placed.

E-7 MIPP Rev. 3 l

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Proc. 125 ER i Date 10/89 Rev. 1 APPENDIX A SUPPLIES PN '2CEEENING CONTAMINATED SAMPLES  !

1. Supply of wipes and envelopes

2. Planchets

3. Roll of red tape

4. Roll of yellow tape for labeling samples

5. Pens, pencils, markers, scissors

6. Box of terri. wipes

7. Box of disposable gloves

8. Radiation hasard signs

9. Box of trash can liners r~

10. Notebook with RADLAB-1ER fonns l

I t

E-8 MIPP Rev. 3  ;

R _

E - -

9 2 3 58 R .

2/ E .

~. E_ 1 0 - v 1 1 B e A

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ce . L ot v D rae A P .

PDR R P _

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Proc. 130 ER l Date 6/88 j Rev. 0 '

NAINE PUBLIC HEALTH LABORATORY RECEIPT AND SCREEKING OF POTENTIALLY CONTAMINATED SAMPLES PRINCIPLE OF THE HETHOD:

It is necessary for laboratory personnel handling potentially contaminated i

samples to wear appropriate protective clothing and to carefully screen samples before bringing them into the laboratory. This procedure details the method t developed for sample screening and sets limits above which samples will not routinely be analysed. l i

PROCEDURE:

(1) Laboratory personnel will be informed by sampling teams that samples have or will be arriving at the Laboratory loading dock. If possible, check to  ;

verify that all samples have been labeled with necessary information before sample team leaves. I (2) It is highly desirable to have two people available to carry out the 1 sample screening procedure. One person (A) shall physically screen the ,

l O

O samples, assist person andA.

the other (B) will record sample information and generally i

1 (3) The laboratory personnel will don appropriate protective clothing. A minimum of a laboratory coat and two pairs of disposable gloves should be worn. All gloves will be leak tested before use. Inner gloves will be taped securely to the lab coat sleeve and should not need to be changed. 1 Outer gloves should be checked frequently throughout this procedure using '

the CDV-700 meter and changed when necessary to prevent cross-contamination of samples. Additional clothing may be worn at the discretion of personnel. A pre-annealed dositaeter will be worn on the '

outer layer of clothing.

(4) In order to obtain a general indication of the level of contamination of the samples, person A will pass the CDV-700 survey meter (window open) slowly over the box (es) of samples at a distance of approximately 3 inches.

(5) a. Place each sample in turn on the clean side of cart A and screen as described in Step 4. Record necessary information on Form RADLAB-ER1.

b.

If reading is a 500 CPH. the sample is rejected. placed in a clean plastic bag and set aside in a remote area reserved for highly contaminated samples. These samples will only be analyzed at the request of the Radiological Health Coordinator or the Chief Chemist.

p E-10 MIPP Rev. 3

i h

l Proc. 130 ER Date 8/88 Rev. O

c. If reading is < 500 CPM, the sample is swiped twice, being certain to include all sides of the geometry. The swipes are screened using the CDV-700 meter. If the swipes read background, the sample is assigned a chemistry identification number and set aside, later to be brought into the laboratory. The chemistry number will be written on yellow tape and attached to the sample in at least two places. One copy of the sample label vill be removed and attached to the log sheet, and all necessary information will be recorded on the log sheet,

d. If the initial swipes read above background, the sample container must be decontaminated using an appropriate cloth. The sample is then reswiped and the swipe rechecked. This process is repeated until a background reading is obtained on the swipes. The sample is then assigned a chemistry identification number as in Step $c.

(6) After all samples have been screened, Cart A and involved areas of the shipping room are screened and decontaminated if necessary. Laboratory personnel will then screen one another, removing any contaminated clothing.

(7) Person A will place rejected tamples onto Cart B and transport them to Room B-15 where they will be stored until testing or transfer to another laboratory.

a (8)

Person B will transport the swipes to the counting room and place them on the Canberra 2404 low background beta counter. Each wipe will be counted for 2 minutes at the appropriate beta voltage. Any reading < 1000 CPM (which corresponds to approximately 2000 picoeuries) is acceptable and the corresponding samples will be brought into the laboratory. If a vipe reads 2 1000 CPM, the corresponding sample is again decontaminated using an appropriate cloth and then reswiped until a count of < 1000 CPM on thm swipe is obtained.

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[N Proc. 320 ER Date 10/89 )

Rev. 1 MAINE PUBLIC REALTE LABORATORY SAMPLE PREPARATION AND PRIOEITIt& TION j

PRINCIPLE OF THE HETHOD:

All samples must be placed in a geometry for which the counting instruments are calibrated. This procedure describes available geometrics and the one most likely to be used for various types of samples. Sample priorities are i established for use in the event they are not given by the Radiological Health Coordinator.

PROCEDURE:

(1) All samples will be preserved promptly after screening as follows: '

1331d1 Preservative milk (1 gal.)

20 ml. 372 formalin 70-100 mg. methimaaolo

( sea water (1 gal.) 80 ml. conc. hcl, 100 mg. NaHS03

\ freshwater vegetation, meat, eggs, approx. 5 ml. formalin per 500 g.

fruit, etc.

sample Preservative is added directly to original sample container. Notation of preservative added will be mad. directly on the sample tag.

(2) Both the 20! GeLi detector and the 242 Ge detector are currently calibrated for 5 geometries: '

l. 130 ml. plastic jar

2. small marinelli beaker

3. large marinelli beaker i

4. freeser carton l 5. planchet i

All samples must be placed in one of these geometries for counting.

i (3) Sample preparation is to be carried out in the radiochemistry section hood.

Marinelli beakers and freener cartons will be lined with disposable plastic liners to prevent contamination of the container. Since it is important to process these samples quickly, no attempt will be made to dry any of the samples. Samples will be packed 'as is' in suitable containers.

E-13 MIPP Rev. 3

a n - -

( Proc. 320 ER O Date 10/89 Rev. 1 (4) Listed below are the most desirable geometries for various sample types and the amount of sample necessary.

imag13, h container milk 3500 ml. small marinelli fresh water, sea water 3500 ml. small marinelli vegetation, meat, eggs, 500 g. freezer carton fruit, etc.

seaweed 2500 g. large marinelli charcoal cartridge entire 130 ud, plastic jar contents air filter planchet (5) The above sample weights and container types may be altered at the discretion of the analyst. If the weights listed are not used for the corresponding geometry, the weight actually used must be recorded on the data sheet for that sample. Variations in geometry from the preferred O geometry must also be recorded on the data sheet.

(6) Once in appropriate containers, a previously assigned chemistry log number will be affixed to each container using tape. The prepared samples are then taken into the counting room for analysis or set aside in designated area to await analysis.

(7) Samples will be analyss 3 accordance with priorities established by the Radiological Health Coct stor. Samples awaiting analysis will be clearly labeled with priority by placing a number on the sample tag or other affixed tag. Numbers 1-3 will be used with 1 indicating highest priority.

(8)- If no priorities have been communicated to laboratory personnel, the following priorities will exist:

1. charcoal cartridges

2. particulate filters

3. milk 4 drinking water

5. fruits and vegetables

6. meat and fish

7. vegetation and feed

8. soil and sediment E-14 HIPP Rev. 3 l

__....__.._____.__._____.m . ., _ __ ___ _. _ _ _ _ _ __ _ __ ____ _._ __ _

, roc. 320 ER bate 10/89 Rev. 1 (9) If regional priorities only have been established by the RHC, the samples for each given region will be prioritized as in Step 8.

o -u m ,, ,ev. ,

R Proc. 520 ER i

/~N Date 10/89 Rev. 1 l k-  ;

MAINE PUBLIC HEALTH LABORATORY '

ARALYSIS OF SAMPLES UNDER EMERGENCY CONDITIONS PRINCIPLE OF THE METHOD:

When screening samples for the high levels of contamination which might exist '

during an emergency situation, it is desirable to adjust counting times to accommodate a large number of samples. This procedure provides guidance as to '

appropriate changes in standard counting procedures and details the method used to obtain numerical results.

PROCEDURE:

(1) The principal means of sample analysis to be used la gamma spectroscopy.

Caram scans are to be performed using either the Ge or GeLi detector.

Ordinarily data from both detectors is acquirett through the Canberra l Series 80 multichannel-analyzer.

(2) Further analyses (for example, Sr or gross beta) may be performed as requested by the Radiological Health Coordinator. These would be done according to standard methods corJsined in the ' Procedures' manual.

() (3) Ganna counting time is determined by the detection level which must be achieved and sample load. In general, the minimum count time for any sample would be 10 minutes. Although this is more than sufficient to '

detect the levels listed in the Preventive PAG (see Appendix A), it allows the analyst reasonable time to perform calculations during sample counting. Appendix B lists approximate detection limits which can be achieved for various counting times using the 202 GeLi. Detection limits ,

would be slightly lower on the ce detector. These figures have been calculated using Equation 1-1.

(1-1) MDA = 4.65 Rfbe) x 1 T 2.22 x I x E I = gamma intensity ( /m/dpm)

E = efficiency, taken from appropriate graph units vary R(bg) = count rate of background for region of interest 7 = count time This equation assumes that the half-life of the isotope is long compared to the count time.

E-16

[G') MIPP Rev. 3

+

l '

Proc. 520 ER Date 10/89 i

O Rev. 1 (4) An attempt will be made to quantitate all isotopes present in each spectrum. However, since examination of the spectra and calculations are at this time not computerized. It may become necessary to limit the number of isotopes examined. Should this become necessary. Appendix C lists those isotopes which will be quantitated.

(5) Calculations will b's done as follows. Refer to the section in the

' Efficiency Graphs' book corresponding to the detector and geometry used for the sample. If a factor is listed for conversion of net cpm to picoeuries/ liter (or kg.) for a particular isotope, use it s shown in (1-2) to determine the activity of that isotope in the sample.

(1-2) $ (picoeuries/ liter) = N x F x e-(In2)t/T S = activity, pCilkg (or 1)

N = not counts per minute for sample F = conversion factor epm to picoctries/ liter T = half-life of isotope t = time between sample collection and counting (6) If a conversion factor is not listed in the book, one may be calculated using the appropriate graph of efficiency vs. energy. Road the efficiency directly from the graph, er calculate it using the equation given for the O line on the graph. Calculate the conversion factor using Equation (1-3).

(1-3) F= 1 2.22 x E x I E = efficiency from graph-I = intensity of gamma Proceed as in Step 5 to calculate isotope activity.

(7) If the normal weight or volume for a particular geometry has not been used, correction must be made for this fact. The correction factor (Cf) =

Normal volume (or weight)/ Actual volume (or weight).

S (corrected) = S (uncc:..ected) x Cf (8) 'Since concentration on e charcoal filter or air particulate filter is normally expressed in picoeuries/M3 the analyst must be informed of the volume of air which has passed through the filter or the flow rate and sampling time.

E-17 MIPP Rev. 3 4

1 Proc. 520 ER ex Date 10/89

)

Rev. 1 (v) i (9) All results are to be reported with an error band of two standard I deviations. This value is listed for each region on the Canberra Series 80 printout as a 2 error.

The error band, due to counting statistics '

only, for the sample activity can be calculated from Equation (1-4).

(1-4) s = E x S/100 s = 2 standard deviations of sample activity E = 2 error given on printorit

• S = 2 x rx 100 (1-5) f=GGrosscounts+(N/2k)Backgroundcounts k = number of channels averaged to determine Bg.

N = number of channels in peak (10) All results are reported as S +/- s. Activity units to be used are picoeuries. All values will be reported in exponential form with one place to the right of the decimal.

O I

E-18 MIPP Rev. 3

.. - - .- . . . - ..- .-.. ._ - - ~-. . . -_._- - .. . -.

L l l'

Proc. 520 ER f_ Date 10/89 Rev. 1 APPENDIX A RESPONSE 1.EVELS FOR PREVENTIVE PAG  ;

l Infant as Critical Segment of Population

(

! nn nui min u an Forage Concentration 0.05 0.8 1.3 0.18 3.0 (microcuries/ kilogram)

I l Peak Milk Intake 0.015 0.15 0.24 0.009 0.14 l

1 (microcuries/ liter)

)

1 1

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Proc. 520 ER O Date 10/89 APPENDIX B MINDDI DETECTABLE ACTIVITIES FOR 201 GELI (1) _ GEOMETRY = 130 ml. plastic jar h Isotope M

8 hr.

1 hr. 6.5 picoeuries 10 min. 18.4 picoeuries 45.2 picoeuries (2)

GEOMETRY = Small marinelli beaker. 3 liters sample h Isotope 21111 M & alii (picoeuries/ liter)

B hr. 8.3 1 hr. 6.6 37.4 23.6 18.6 10 min. 57.8 105.7 45.4 258.9 (3)

GEOKETRY = Large marinelli beaker, 3 liters sample D Isotope Elll?. M (picoctries/ liter) Sillti 8 hr. 9.8 1 hr. 7.7 44.2 27.6 21.8 10 min. 67.7 125.1 53.5 306.5 (4)

GEOMETRY = Freezer carton, 500 grams sample D Isotope E111?. M Silii (picoeuries/ liter) 8 hr. 48.6 1 hr. 49.4 278.5 137.5 139.8 10 min. 336.8 787.8 342.4 1929.8 E-20 MIPP Rev. 3  !

i l

Proc. 520 ER Date 10/89 Rev. 1 (5) GEOMETRY = Planchet Isotope UlBf. . Gile .11M .Q.1111 (picoeuries/ liter) 8 hr. 4.9 4.3 24.2 l 1 hr. 13.9 12.0 68.4 i 10 min. 33.9 29.5 167.5  :

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Proc. 520'ER

' Date 10/89

,, Rev. 1 APPENDIX C

' -2 Key Gammas.

Isotone Half-Life Energy (kev) Abundance (!)

1131 8.04 d 364.51 81.2 284.3 6.05 I132 2.30 h 667.7 98.5 772.6 76.2 1133 .20.lB h 529.9 86.3 875.3 4.5 I135 6.6 h 1260.4 28.6 1131.5 22.5 Cs134 2,06 y 604.7 97.6 I

795.8 85.4 Cs136 13.2 d 818.5 l

99.7 1048.1 79.6

'Cs137

~

30.17 y  !

661.6 85.1 Ba140 12.79 d 537.3 25.0 i

I t

[~'h E-22 MIPP Rev. 3

v.

Proc. 620 ER Date 8/88 Rev. 0 MAINE PUBLIC HEALTH LABORATORY s EEPORTING SAMPLE DATA PROCEDURE:

(1) All sample results are reported to the Radiological Health Coordinator by commercial telephone lines. The RHC can be reached at 289-4080. The analyst will identify him or herself and relay sample results. The Radiclogicci Health Coordinator will be requested to repeat the results to ir. .ure accurat.y. An EOC communications log will be established and the following information will be recorded for all data reported: sample number, time, date, name of analyst, name of person to whom data was reported.

(2) The EOC is located in the basement of the State Office Building. Written reports can be hand carried to the RHC if necessary or as time allows.

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'[V E-23 MIPP Rev. 3

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4 1

APPENDIX F STATE OF MAINE CEECKLIST FROCEDURES FOR THE IBGESTION PATHWAY PLAN FOR SEABROOK STATION t

O P-1 x m .... ,

4 I ....

STATE OF MAINE CBBCELIST PROCEDURES POR THE IBGESTION PATEWAY PLAN FOR SEABROOK STATION-Number h Procedure Title g 1 0_ _ Radiological Health Coordinator at the State F-3 E0C'- Check-Off List 2- 0 Radiological Health Specialist at the State F-22 EOC - Check-Off List 3 0 Radiological Health Specialist at the F-52 Seabrook Station IF0/ EOF - Check-Off List

~ 4" 0- Environmental Sampling Team Organiser - F-54 Check-Off List 5 0 Radiological Health Specialist at Alfred - F-56 Check-Off List 6 0 Department of Agriculture Representative F-57 at the State EOC - Check-Off List 7 0 Division of Health Engineering Representative F-59

-at'the State EOC - Check-Off List 8 0 Department of Marine Resources Representative F-60 at the. State EOC - Check-Off List 9 0 Department of Inland Fisheries and Wildlife F-61 Representative at the State EOC - Check-off List F-2 MIPP Rev. 3 l

p ,

Proc. 1 Date 6/90 Rev. O RADIOLOGICAL BEALTH COORDINATOR AT THE STATE EOC CHECK-OFF LIST TIME INITIALS AlsEl

1. Receive notification from State Police or Operations Officer.

2. Report to the State EOC in Augusta Maine.

3. Obtain briefing from' Operations Officer. ,

4. Notify Radiological Health Specialists using DHE Procedure No. 2.01, Attachment 1.

5. Asaign a Radiological Health Specialist to the State EOC a1d to the IF0/ EOF in Newington, NH.

SITE AREA EMERGENCY

1. Direct the Radiological Health Specialist assigned to the IF0/ EOF at Newington, NH to report to that location.

2.' Direct the Radiological Health Specialist assigned to the' State EOC to report.

-3. Notify the Environmental Sampling Teams using DHE Procedure No. 2.01 Attachment 2.

4. Determine if a radioactive release has occurred or is underway by consulting with the Radiological Health Specialist at the IF0/ EOF.

5. . Assign a Radiological Health Specialist to the York County EOC in Alfred, ME to oversee sample collection, personnel monitoring and decontamination activities. Dispatch to Alfred with the Environmental Sampling Teams.

6. Brief the Environmental Sampling Team Organizer and the Radiological Health Specialist assigned to the York County EOC on the initial accident assessment.

F-3 HIPP Rev. 3

h I

s Proc. 1 Date 6/90 Rev. 0-TIME INITIALS GENERAL EMERGENCY OR RADI0 ACTIVE RELF-ASE

1. Utilize Figure 4.4-1 of the Ingestion Pathway Plan for Seabrook Station, Decision Criteria for 6 -Recommended Ingestion Pathway Protective Actions.

I V.

2. Inform the Department of Agriculture representat T of the need to disseminate public information e ingestion pathway protective actions.

3. Determine whether precautionary protectivo actiwns are needed by consulting with the Radiological

-Health Specialist at the IF0/ EOF on projected deposition levels, the magnitude of the release, status of plant conditions, and accident prognosis. _

~4. If precautionary protective actions are required, inform the Governor's Office of the need for a news release and assist in.the preparation of a news release. Obtain authorization from the Governor or his designee prior to issuance of the news release.

5. Oversee the coordination-of Field Monitoring Teams by maintaining contact with the Radiological Health Specialist at the York County EOC.

6. Develop a sampling strategy plan utilizing input from the Department of Agriculture representative at the EOC and the Radiological Health Specialist at ,

the IF0/ EOF concerning the types of samples needed, the prioritization for analysis, and the locations  ;

where sampling is most needed. '

i'

'7. Assess the need for additional support in obtaining environmental samples and the analysis of samples by considering activation of the New England Compact, If not already activated (see Appendices A and B to the Plan) and the notification of FEMA. if not already notified (see'Section 8.0 or' the Plan,

' Emergency Response Support').

8. Notify the Environmental Sampling Team Organizer of sampling strategies to be followed.

F-4 MIPP Rev. 3 l

Proc. 1 Date 6/90

.{ Rev. 0 TIME INITIALS

9. Ensure that the Public Health Laboratory is notified t

of the sample analysis prioritization to be L performed using DHE Prondure No. 2.01. Attachment 3.

10. Obtain environmental sample analysis results from the Public Health Laboratory.

11. Compare sample analysis results with the 1

preventative and emergency derived response levels contained in Attachments 1 through 4 of the check-off list for the Radiological Health Specialist.

Consult with the Radiological Health Specialist at the EOC on this comparison.

1 L '12. Utilize Attachment 1 of this procedure to assess protective actions for contaminated milk.

L 13. If sample analysis risults equal or exceed the derived response levels, then advise the Governor or

!.A his designee to imple ment the appropriate protective Q- actions as detailed in Attachment 2 of this procedure.

i

14. . Inform the appropriate agency responsible for the

!' affected~ pathway of the need for protective actions )

as required.

15. Develop news releases in coordination with other

-state agencies as appropriate. *

! 16. If sample analysis resu'lts do not indicate the presence of radioactive depnsition, then consider the lifting of precautionary protective actions. _ ,

17. Continue the assessment of the appropriateness of protective. actions.

-18. Monitor the effectiveness of protective actions for the milk and other food pathways by monitoring at the market level.

19. . A'ssess the need for federal assistance in monitoring the milk pathway at the market level, b

V F-5 HIPP Rev. 3

.x, Proc. 1 Date 6/90 Rev. 0 TIME INITIALS 20.= Assess the need for feder01 assistance in monitoring the other food pathway.

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't Proc. 1 O Date 6l90 Rev. O RADIOLOGICAL HEALTH COORDINATOR AT THE STATE E0C ATTACEMENT 1 FLOW CHAR'T OF DECISION. MAKING RELATIONSHIPS REGARDING THE USE OF POTENTIALLY CONTAMINATED MILK ontaminating Event t

Potentially Contaminated Milk I

O.K.Ior -< g.3 31 Field y g 333 Normal Fluid - Monitoring of Milk use Preventive . For All Use-g Milk Emergenc Response Level ,

[ Response Level

> l 131 Preventive > Preventive And <l.131 Emergepcy Response Levels Response Level Store For I-131 only ~

/ Qualitative and Other Long. Lived uantitative Analyse Radionuc!! des

< Preventive Response Level Olvert for Use -

7 in Manufactured Milk Products '

, ICPP.S.10827 O ,

F-7 MIPP Rev. 3'

3- y i

~

. Proc. 1 Date 6/90 Rev.-O r

RADIOLOGICAL HEALTH COORDINATOR AT THE STATE EOC ATTACHMENT 2 SAMPLE TYPE: Pasture Grass or Milk PAR TYPE: Preventive

-. RESPONSIBLE AGENCY: Department of Agriculture AREA 0F IMPACT: Farms PROTECTIVE ~ ACTION TO ENFORCE: 'l. Remove the lactating dairy animals from contaminated pasturage, move the animals indoors, and provide uncontaminated feed (i.e.. that which had been stored indoors or covered out-of-doors).

2. Provide animals with uncontaminated water. Sources may be covered wells, covered cisterns, and closed storage tanks. Do not use surface water such as st ',ams, ponds, or open reservoirs.

3. individual milkings cannot be stored in separate tanks, take a representative one-gallon sample from each milking, affix identification, and refrigerate.

Samples will be picked up by a survey team.

Reference:

Food and Drug Administration, Federal Register, Volume 47, No. 205, October ~22, 1982.

F-8 MIPP Rev. 3

Proc. 1-Date 6/90

} Rev. 0 RADIOLOGICAL HEALTH C00RDIMATOR AT THE STATE E0C ATTACIDEENT 2 (Continued)

SAMPLE TYPE ' Pasture Grass-or Milk i

. PAR _ TYPE: Emergency c o

RESPONSIBLE AGENCY: Department of Agriculture AREA 0F IMPACT: -Processor PROTECTIVE ACTION "

l. TO ENFORCE: 1. Consider condemnation if emergency DRLs are exceeded. J~

Continue condemnation until radiolodine levels drop _

below emergency DRLs. Furcher consideration should be given to diversion'of milk.

L

2. Withhold contaminated milk from the market to allow i.

" radioactive decay'of short-lived radionuclide. This may be achieved by storing frozen fresh milk, frozen <

'T concentrated milk, or frozen concentrated milk products.

3. Store milk.for a prolonged period of time-at a reduced temperature'in conjunction with a-special  ;

pasteurization process using ultra-high temperatures.

l' 4. Divert the_ production of fluid milk for the j

' production of dry whole milk, nonfat dry milk, butter, or evaporated milk.

5. Attempt.to store all incoming shipments in separate t

L tanks and segregate milk not originating in the Ingestion Pathway EPZ.

6. _Take a one-gallon representative-sample of each i incoming shipment, affix identif1' cation (source, date/ time of arrival, carrier, volume, in-plant '

storage tank, etc.), and refrigerate. Samples will be picked up by a survey team.

I'

Reference:

Food and Drug Administration Federal Register, Vslume 47, No. 205, October- 22, 1982.

F-9 MIPP Rev. 3

(, ,

. Proc. I

g. Date 6/90.

, i Rev. 0--

RADIOLOGICAL REALTH COORDINATOR AT THE STATE EOC

. ATTACHMENT 2 (Continued).

SAMPLE TYPE: Pasture Grass-or. Milk-

. PAR TYPE: Emergency RESPONSIBLE AGENCY: . . Department of Agriculture AREA 0F IMPACT: Public PROTECTIVE ACTION TO ENFORCE:

1. - Advisory that fresh milk on hand prior to the

. advisory and stored in closed containers may be used.

2. Advisory that dry or canned milk in closed containers-1 may be used. '

O l' I i

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m

Reference:

Food and Drug Administration. Federal Register, Volume 47, No. 205, October 22, 1982.

F-10 MIPP Rev. 3 l

I I

Proc. 1 Date 6/90 Rev. O P

RADIOLOGICAL BEALTE C00RDIMATOR AT THE STATE EOC

-ATTACHMENT 2 (Continued)

. SAMPLE TYPE: Pasture Grass or Milk PAR TYPE: Emergency

. RESPONSIBLE AGENCY: Department of Agriculture AREA 0F IMPACT: Farms

- PROTECTIVE ACTION TO'LNFORCE: 1. Consider condemnation ~if emergency DRLs are exceeded.

Continue condemnation until radioiodine levels drop below emergency DRLs. Further consideration should' be given to diversion of milk.

2. Prevent introduction of milk supplies into commerce.

3. Provide animals with uncontaminated feed stored indoors or protected.

4. Provide animals with uncontaminated waters i.e.,

stored in covered or closed tanks or from a deep well.

5. If the individual milkings cannot be stored:in separate tanks, take a representative one-gallon sample from each milking, affix identification, and refrigerate. Samples will be pickad up by a survey team.

References . Food and Drug Administration, Federal Register, Volume 47, No. 205; October 22, 1982.

F-11 MIPP Rev. 3'

'T -

i<

l~

Proc. 1 Date 6/90 Rev. 0 RADIOLOGICAL HEALTH COORDINATOR AT THE STATE EOC ATTACBIENT 2 (Continued).

SAMPLE TYPE: Fresh Fruits and Vegetables PAR TYPE: Preventive

, RESPONSIBLE AGENCY: Department of Agriculture AREA 0F IMPACT: Comunerce .

PROTECTIVE ACTION TO ENFORCE: 1. Remove surface contamination by washing, brushing, scrubbing and peeling.

2.- Food in sealed packages, cans, cartons, barrels, etc., needs no treatment.

O

-)

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t

Reference:

Food and Drug Administration, Federal Register, Volume 47, No. 205, October 22,'1982.

F-12 HIPP Rev. 3

i

!l' Proc.-1 Date 6/90 Rev. O RADIOLOGICAL HEALTP POORDIEATOR AT THE STATE BOC ATTACIDGNT 2 (Continued)

SAMPLE-TYPE: Fresh Fruits and Vegetables

' PAR TYPE: Preventive ,

RESPONSIBLE AGENCY: Department of Agriculture  !

AREA 0F IMPACT: .Public PROTECTIVE ACTION TO ENFORCE: 1. If stored in the open, remove surface contamination -

by washing, brushing, scrubbing or peeling.

2. Food in sealed packages, in refrigerators, or closets is otherwise protec*,ed and needs no treatment..

O i

i

\

Reference:

Food and Drug Administration, Federal Register, Velume 47, No. 205, October 22, 1982.

F-13 MIPP Rev. 3

WA Proc. 1-Date 6/90 0t Rey, 0

-RADIOLOGICAL HEALTH COORDINATOR AT THE STATE EOC ATTAC8HERT 2 (Continued)-

SAMPLE TYPES. Finfish and Shellfish' s

PAR TYPE: Preventive

' RESPONSIBLE AGENCY: Department of Inland Fisheries and Wildlife

' AREA 0F IMPACT ' Commercial Fishing Firms PROTECTIVE ACTION TO ENFORCE: 1.- Suspend fishing operations until resumption is recommended.

2. Check the catch made on the day of the advisory.

e  :

3. Keep catch covered until transported outside the area of possible contamination.

4. Develop sampling plan to ensure that uptakel O contamination doss not occur.

Reference . Food and Drug Administration Federal Register Volume 47, No. 205, October' 22, 1982.

F-14 MIPP Rev. 3 1

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- ' ~ - - - -- -- - - - - -

Proc. 1 Date 6/90 Rev. O RADIOLOGICAL BEALTH COORDINATOR AT THE STATE EOC ATTAcatENT 2 (Continued)

SAMPLE TYPE:' Animal Feed PAR TYPE: Preventive RESPONSIBLE N3ENCY: Department of Agriculture AREA'0F.IMPACf:- Datry Farms Poultry Farms PROTECTIVE ACTION

>TO ENFORCES' 1. Use feed that has been stored indoors..

. 2. Develop sampling plan to ensure that uptake /

contamination does not occur..

D

Reference:

Food and Drug Administration, Federal Register, Volume 47, No. 205, October 22.-1982.

F-15 MIPP Rev. 3 i

1

-u l0,

\ _ti Proc. 1 l

Date 6/90 l Rev. O RADIOLOGICAL REALTH COORDINATOR AT THE STATE BOC ATTACBERT 2 (Continued)

SAMPLE TYPE: Other Food (Including Honey, Eggs and Haple Syrup)

PAR TYPE: Preventive RESPONSIBLE AGENCY: Department of Agriculture AREA 0F IMPACT: .Public PROTECTIVE ACTION TO ENFORCE: 1. Preserved food (canned, frozen and dehydrated before contamination) may be used.

2. Store food to permit radioactive decay of short-lived radionuclides.

O References ~ Food and Drug Administration, Federal Register, Volume 47, No. 205, October 22, 1982.

F-16 MIPP Rev. 3 l

?

Proc. 1 Date 6/90 Rev. O RADIOLOGICAL HEALTH COORDINATOR AT THE STATE EOC ATTACHMENT 2 (Continued)

-SAMPLE TYPE: Other Foods (Including Honey, Eggs and Maple Syrup)

PAR TYPES. Emergency RESPONSIBLE AGENCY: Department of Agriculture, or Department of Inland Fisheries and Wildlife, or Department of Marine Resources AREA 0F IMPACT: Public PROTECTIVE ACTION TO ENFORCE: 1. Restrict diet to foods stored in closed containers prior to the advisory or packaged, sealed foods.

2. Fresh fruits and vegetables should be thoroughly washed, brushed, scrubbed or peeled.

3. Restrict diet to foods not identified as contaminated O or originating outside the Ingestion Pathway EP2.

4. Stay alert for public infonmation bulletins..

Reference:

Food and Drug Administration Federal Register, Volume 47, No. 205, October 22, 1982.

F-18 f) MIPP Rev. 3 i

, - . _ _ _ . _ . . _ . . . _ . . _ _.m . ____ _._. _ _ _ _ , _ _ _ _ - - __

I Proc. 1

[ '

Date 6/90 Rev.,0 N

RADIOLOGICAL REALTH COORDINATOR AT THE STATE EOC ATTACIDENT 2 (Continued).

SAMPLE TYPE: Other Food-(Including Honey, Eggs and Haple Syrup)

. PAR TYPE: Preventive r

, . RESPONSIBLE AGENCY: Department of Agriculture

' AREA 0F-IMPACT: Public PROTECTIVE ACTION

-TO ENFORCES. 1. Preserved food (canned, frozen and dehydrated before contamination) may be used.

2. Store food to permit radioactive decay of short-lived-radionuclides.

I l . ,

lf -

Reference:

Food and Drug Administration. Federal Register, Volume 47, No. 205,

October 22, 1982.

F-16 MIPP Rev. 3 4

I__:___-___---------------------------^ - ~ ~

Proc. 1 Date 6/90 Rev. O RADIOLOGICAL HEALTH COORDINATOR AT THE STATE EOC ATTACBHENT 2 (Continued)

SAMPLE TYPE: Other Foods (Including Honey, Eggs and Haple Syrup)

PAR TYPE: Emergency RESPONSIBLE AGENCY: Department'of Agriculture, or Department'of Inland Fisheries and Wildlife, or Department of Marine Resources AREA 0F IMPACT: Conunerce PROTECTIVE ACTION TO ENFORCE: -

1. Prevent introducing a food type into consnerce if it has been identified as contaminated.

2.- Consider other sources of foed originating outside the Ingestion Pathway EP2.

3. Do not process or vend unpackaged food if the

.9_ Operations Area is contaminated.

Reference:

Food and Drug Administration, Federal Register, Volume 47 No. 205 October 22, 1982.

F-17 MIPP Rev. 3

t I

i Proc. 1 Date 6/90 Rev. O F

RADIOLOGICAL HEALTH COORDIKATOR AT THE STATE EOC ATTACBMENT 2 (Continued) -

SAMPLE-TYPE:

Other Foods (Including Honey, Eggs and Maple Syrup) y PAR TYPE: Emergency '

L f RESPONSIBLE AGENCY: Department of Agriculture, or

• r Department of Inland Fisheries and Wildlife, or Department of Marine Resources AREA 0F IMPACT: Public PROTECTIVE ACTION

TO ENFORCE: 1. Restrict diet to foods stored in closed containers i

' prior to the advisory or packaged, sealed foods,

2. Fresh fruits and vegetables should be thoroughly  ;

washed, brushed, scrubbed or peeled.

L f- 3. Restrict diet to foods not. identified as contaminated

~( S'

• ~-) or originating outside the Ingestion Pathway EP2.

4. Stay alert for public information bulletins.

l' i

Reference:

Food and Drug Administration, Federal Register, Volume 47, No. 205, October 22, 1982.

{ F-18 MIPP Rev. 3

- - =

.f.-

t l

4. Proc. '

Date 6/90 Rev. 0-RADIOLOGICAL HEALTH COORDINATOR AT THE STATE EOC ATTACHMENT 2 (Continued)

SAMPLE'TYPEi- Drinking Water

.y PAR TYPE: Preventive RESPONSIBLE AGENCY: Division of Health Engineering 1 AREA 0F IMPACT: Public PROTECTIVE ACTION 70 ENFORCE: 1. Secure outlets of wells for water identified as-contaminated. Do not use' reservoir water identified as contaminated. Do not use water for consumption-that has not been checked. If approved, this water may be used for sanitary purposes.

2. Use alternate' sources of liquid such as water drawn and stored in closed containers prior to the

. advisory, bottled water, bottled / canned-beverages and y g juices, and water provided by emergency organizations

' such as the American Red Crose ind the. National =

Guard. -

3. Arrange for alternate water supplies outside the affected area to be transported into areas requiring them.

i r

References. Food and Drug Administration, Federal Register Volume 47 No. 205, October 22, 1982.

) F-19 MIPP Rev. 3 v

i

.1

J

,1 Proc. 1 s

Date 6/90 Rev. O RADIOLOGICAL HEALTH C00RDIEATOR AT THE STATE E0C-ATTACEMENT 2-(Continued)

SAMPLE TYPE: Drinking Water 5 PAR TYPE: Preventive RESPONSIBLE AGENCY: Division of Health Engineering and.

Department of Agriculture AREA 0F IMPACT: Farms i

PROTECTIVE ACTION TO ENFORCE: 1. Do not use surface water for human or animal consumption. Surface water may be used for sanitary and nonconsumption purposes.

2. Other water sources identified as contaminated should not be consumed.

3. Water stored in closed tanks or vessels prior to the advisory may be consumed.

s

Reference:

Food and Drug Administration. Federal Register, Volume 47, No. 205, October 22, 1982.

F-20 MIPP Rev. 3 m

b Proc. 1.

' Date 6/90 Rev. 0 RADIOLOGICAL HEALTH COORDINATOR AT THE STATE EOC ATTACHMENT 2 I

.(Continued) '

SAMPLE TYPE: Drinking Water

' PAR TYPE: Preventive RESPONSIBLE AGENCY: Division of Health Engineering and Department of Agriculture-AREA OF IMPACT: Consnerce '

1 PROTECTIVE ACTION TO ENFORCE: 1. Water identified as contaminated should not be used for processing materials (consumables, containers) which will enter the food chain. 4

2. Contaminated water may be used for other industrial and commercial operations if so advised.

i-.,.  :

'r 1

l I

i l

4

Reference:

Food and Drug Administration, Federal Register, Volume 47, No. 205, l October 22, 1982.

F-21 MIPP Rev. 3

Proc. 2 Date 6/90 Rev. O RADIOLOGICAL HEALTH SPECIALIST AT THE STATE EOC CHECK-OFF LIST l

TIME INITIALS l

SITE AREA / GENERAL EMERGENCY

1. Advise the Radiological Health Coordinator on establishing a sampling program based upon consideration of the tables contained in Attachments 8 and 9 of this procedure.

2. Obtain the laboratory analyses results of samples.

3. Determine if the measured levels of radioactive material in milk, drinking water, and other food samples exceed the preventive or emergency derived response levels contained in Attachments 1 through 4 of this procedure.

I:

n 4. Complete Attachments 5, 6 and 7 of this procedure -

( Protective Action Worksheets for milk, water, and leafy food stuffs.

5. Advise the Radiological Health Coordinator on the results of ingestion pathway dose assessment L calculations. ,

l

6. Ensure that ingestion pathway sample collection continues until sample analysis indicates.that the levels of radioactive material found in food items

, have decreased to acceptable lindts.

7. Notify the Radiological Health Coordinator when sample analyses indicate that protective actions can be lifted.

F-22 MIPP Rev. 3 l

l

-R Proc. 2 Date 6/90-Rev. 0 ATTacIBGET 1 DERITED RESPONSE LETELS FUE THE MIIK PATHE&Y A. Response Levels for Preventive Protective Actions (Infant as Critical Segment of Population)'

Sample Type I-131(a) Cs-134(b) Cs-137(b) Sr-90 Sr-89.

Area Deposition 0.13 2.0 3.0 . 0.5 8.0 (microcuries/ square meter)

Forage Concentration (c) 0.05 0.8' 1.3 0.18 3.0 (microcuries/ kilogram)

Peak Milk Activity 0.015 0.15 0.24 0.009 0.14 (microcuries/ kilogram)

Total Inteke (microcuries) 0.09 4.0 7.0 0.2 I 2.6 B. Response Level for Emeraency Protective Actions i

Sample Type I-131(a) Cs-134(b)

Cs-137(b) Sr-90 St-89 Infant (*) Adult Infant (*) Adult Infant (*) Adult Area Deposition .

Infant (*) Adult Infant (*) Adult  !

(microcuries/ square meter) 1.3 18 -20 40. 30 50 5 20 80 1,600 i Forage Concentration (c) i (microcuries/ kilogram) 0.5 7 8 17 13 19 1.8 8 30 700  !

Peak Milk Activity (microcuries/ liter) 0.15 2 1.5 3 2.4 4 0.09 0.4 1.4- 30 Total Intake (microcuries) 0.9 10 40 70 70 80 2 2 26 400 Source: Food and Drug Administration. Federal Register, Volume 47. No. 205, October 22, 1982.

F-23

. 'MIPP Rev. 3 {

.-- ~ s

- - w - -,e, ,m- , , .u. +, --yn

., g4 .s- -o~.,

e Proc. 2 Date 6/90 O ,,,,,, ,, ,

DERIVED RESPONSE LEVELS FOR THE MILE PATHWAY (Continued)

E21Ef.8

(*) From fallout. Iodine-131 is the only radioiodine of significance with respect to milk contamination beyond the first day. In case of a reactor.

accident, the cumulative intake of Iodine-133 via milk is about 2 percent of Iodine-131 assuming equivalent deposition.

.(b) Intake of cesium via the meat-person pathway for adults may exceed that of the milk pathways therefore, such levels in milk should cause surveillance and protective actions for meat as appropriate. If both Cesium-134 and Cesium-137 are equally present, as might be expected for reactor accidents, the response levels should be reduced by a factor of 2.

(c) Forage concentration assumes fresh weight.

(d) Newborn infant includes fetus (pregnant women) as critical segment of population for. Iodine-131. ,

l

(') " Infant' refers to child less than one year of age.  !

i

\

F-24 MIPP Rev. 3

b Proc. 2 Date 6/90 Rev. O ATTACIINENT 2 LONG-TERN DERIVED PREVENTIVE 1ESPONSE LEVELS FOR DRINKING WATER" g

(Ob*t YEAR INGESTION PERIOD)

Initial Water Concentration Equivalent totge Preventive PAG Inte8 tion Dose Commitment Adult 0 Teenager 0 Child 0 lafant G I Nuclide Orlan c fucilliter) ptcilliter) (ucilliter) (ucilliter)

I-131 Th 6.3E-2' 5.7E-2 2.4E-2 1.3E-2

- I-132 Th 1.2E+1 1.4E+1 4.9E+0 3.5E-1

=

I-133 Th 2.4E+0 2.6E+0 9.1E-1 5.8E-1 Rb 96 Lv 6.4E-1 1.4E+0 4.7E-1 1.8E-1 Cs-134 Lv 1.2E-2 5.8E-3 3.0E-3 1.5E-2 r 3.2E-1 g' Cs.136 Lv 7.6E-1 8.2E-1 4.3E-1 Cs-137 Lv 1.1E-2 6.6E-3 3.0E-3 2.2E-2 Te-127m Kd 8.5E-2 8.5E-2 4.0E-2 3.6E-2 Te-129 Kd 4.0E+4 3.1E+4 9.1E+2 5.2E+2 Te-131m GI 2.4E+0 3.1E+0 2.9E+0 4.4E+0 Te-132 GI 1.0E+0 1.6E+0 2.5E+0 2.7E+0 Sb-127 f G1 9.8E-1 1.5E+0 2.4E+0 4.4E+0 Sr-89 Bo 4.1E-1 1.6E-2 5.3E-3 5.61 2 St-90 Bo 9.9E-4 1.2E-4 5.8E-5 6.2E-4 9 Ba-140 Mo-94 Ru-103 GI Kd CI 4.7E-1 9.1E+0 3.0E-1 6.5E-1 9.4E+0 4.3E-1 3.4E-1 4.6E+0 4.9E-1 2.6E-1 5.9E+0 7.9E-1 Ru-106 GI 5.1E-3 6.9E-3 7.2E-3 1.1E-2 Ru-105f GI 1.2E+1 1.8E+1 2 9E+1 5.4E+1 Co-58 GI 2. 4 E- 1 3.8E-1 4.9E-1 8.8E-1 Co-60 GI 1.8E-2 2.8E 2 3.6E-2 6.3E-2 Y-90 GI 6.8E-3 8.8E-3 8.5E-3 1.3E-2 Y-91 GI 5.5E-2 7.5E-2 7.7E-2 1.2E-1 Zr-95 GI 1.3E-1 1.9E-1 2.1E-1 3.5E-1 Zr-97 GI 3.4E+0 4.0E+0 3.3E+0 4.9E+0 La-140 GI 2.1E-1 2.9E-1 2.9E-1 4.5E-1 Ce-141 GI 3.2E 1 4.4E-1 4.5E-1 7.0E-1 Ce-143 GI 4.CE+0 5.1E+0 4.7E+0 7.1E+0

_ Co-144 GI 5.9E-3 7.9E-3 8.2E-3 1.3E-2 Pr-143 GI 4.6E-1 6.1E-1 6.2E-1 9.6E-1 Nd-147 GI 6.5E-1 8.9E-1 9.1E-1 1.4E+0 Np-239 GI 4.5E+0 5.6E+0 5.5E+0 8.4E+0 Pu-23Bf Bo 1.0E-4 1.4E-4 6.5E-5 9.6E-5 Pu-239f Bo 8.8E-5 1.2E-4 5.4E-5 8.0E-5 Pu-240f Bo 8.8E-5 1.2E-4 5.4E-5 8.0E-5 6 Pu-241f Bo 4.4E-3 5.6E-3 2.8E-3 4.0E-3 Am-241 f Bo 1.7E-5 2.2E-5 1.1E-5 1.5E-5 Cm-242f Bo 2.1E-3 2.7E-3 1.3E-3 1.8E-3 Cm-244f Bo 3.5E-5 4.5E-5 2.2E-5 3.2E-5 F-25 MIPP Rev. 3

^ "

Proc. 2  !

[~T Date 6/90 Rev. O ATTACIDEENT 2 LONG-TERN DELIVED PREVENTIVE RESPONSE LEVELS FOR D N mG WATERa (ONE YEAR INGESTION PERIOD)

(Continued)

InitialWaterConcentrationEquivalenttotge Preventive PAG Innestion Dore Cn==4 tment Adultd Teenager d Childd Infantd Nuclide pgggg C faci /11ter) fuci/ liter) fucilliter) fucilliter)

Assumas a contaminated water ingestion period equivalent to the shorter time interval of the radionuclide mean lifetinae or 365 days (see Appendix A).

Water is ingested at the rates given in Reference 9 for the maximum exposed individual.

l b The derived response level for each radionuclide is capable of producing the preventive PAG dose. Therefore, if more than one radionuclide is present in the sample, the sum of ratios technique must be used to estimate the individual radionuclide concentrations that are permissible, e.g.,

7-- Cone A +,,,4 Cone X . g 1, i (,9J. Response Level A Response Level X 1

c Th= thyroid, Lv= liver, Kd= kidney, Bo-bone, Wb=whole bcdy, GI=gastro-intestinal track. These are critical organs for the corresponding radionuclides.

d Calculated concentrations may vary if calculation aesumptions concerning ingestion rates and dose conversion factors are different from those

, presented in Reference 9.

1 6.3E.2 = 6.3x10*2 = 0.06..

f Adult dose conversion factors (DCF's) were obtained from ICRP-30:10,11,12 dose conversion factors for other age groups were estimated by multiplying these adult DCF's by DCF ratios (other age groups / adult) presented in Reference 9 for other nuclides having similar critical organs and retention times.

F-26 MIPP Rev. 3

(}

. - ., wi..',,- -

Proc. 2 Date 6/90 3

Rev. O ATTACStENT 3 LONG-TERM DERIVED PREVENTIVE RESNNSE LEVELS FOR VEGETABLE F00DSTUFF' 4 a,b AdultC Teene ChildC i ProduceC Leafy' Produce Leafy Produce Leafy Nuclide uC1/km uC1/km uCilko uCilko uC1/ko uCilko 1-131 8.9E-2f 7.0E-1 4.6E.2 6.6E-1 2.3E-2 4.7E-1 1-132 1.7E+1 1.4E+2 1.1E+1 1.6E+2 4.8E+0 9.8E+1 1-133 3.4E+0 2.7E+1 2.1E+0 3.0E+1 9.0E-1 1.8E+1 Rb-86 9.1E-1 7.1E+0 1.1E+0 1.6E+1 4.6E-1 9.4E+0 Cs-134 1.7E-2 1.3E-1 4.7E-3 6.8E-2 2.9E-3 5.9E-2 Cs-136 1.1E+0 8.4E+0 6.7E-1 9.6E+0 4.3E-1 8.6E+0 g' Cs-137 1.6E-2 1.3E-1 5.4E-3 7.7E-2 3.0E-3 6.1E-2 Te-127m 1.2E-1 9.4E-1 6.9E-2 9.9E-1 4.0E-2 8.1E 1 Te-131 3.4E+0 2.7E+1 2.CE+0 3.6E+1 2.8E+0 5.7E+1 Te-132 1.4E+0 1.1E+1 1.3E+0 1.9E+1 2.4E+0 5.0E+1 Sb 1278 1.4E+0 1.1E-1 1.2E+0 1.8E+1 2.4E+0 4.8E+1 Sr-89 5.7E-1 4.5E+0 1.3E-2 1.8E-1 5.2E-3 1.1E-1 Sr 90 1.4E-3 1.1E-2 9.6E-5 1.4E-8 5.7E-5 1.2E-3 Ba-140 6.7E-1 5.3E+0 5.2E 1 7.5E+0 3.4E-1 6.8E+0 Mo-99 1.3E+1 1.0E+2 7.6E+0 1.1E+2 4.5E+0 9.1E+1 Ru-103 4.2E-1 3.3E+0 3.5E-1 5.0E+0 4.8E-1 9.7E+0

_ Ru-106 7.24-3 5.7E-2 5.6E-3 8.1E-2 7.1E-3 1.4E 1 Rh-1058 1.7E+1 1.3E+2 1.5E+1 2.2E+2 2.9E+1 5.9E+2 Co-58 3.3E-1 2.6E+0 3.1E-1

{ Co-60 2.6E-2 2.0E-1 2.3E-2 4.4E+0 4.8E 1 9.7E+0 3.3E-1

=

3.5E-2 7.1E-1 Y-90 9.6E-3 7.5E-2 7.1E-3 1.0E-1 8.3E-3 1.7E-1 Y-91 7.8E 2 6.2E-1 6.0E 2 8.7E-1 7.6E-2 1.5E+0 2r-95 1.8E-1 1.4E+0 1.5E-1 2.2E+0 2.1E 1 4.2E+0 Zr-97 4.8E+0 3.8E+1 3.3E+0 4.7E+1 3.3E+0 6.7E+1 NB-95 4.9E 1 3.8E+0 4.3E 1 6.2E+0 6.3E-1 1.3E+1 La-140 3.0E-1 2.4E+0 2.3E-1 3.4E+0 2.8E 1 5.8E+0 Ce 141 4.6E-1 3.6E+0 3.6E-1 5.2E+0 4.5E-1 9.1E+0 m Co-143 5.7E+0 4.5E+1 4.1E+0 6.0E+1 4.7E+0 9.5E+1 Co-144 8.3E-3 6.5E-2 6.4E-3 9.3E-2 8.0E-3 1.6E 1 Pr-143 6.5E-1 5.1E+0 5.0E-1 7.2E-1 6.2E-1 1.2E+1 Nd-147 9.2E-1 7.3E+0 7.2E-1 1.0E+1 9.0E-1 1.8E+1 Np-239 6.3E+0 5.0E+1 4.7E+0 6.7E+1 5.5E+0 1.1E+2 Pu-2388 1.4E-4 1.1E-3 1.1E-4 1.6E-3 6.4E-5 1.3E-3 Pu-2398 1.2E-4 9.8E-4 9.3E-5 1.3E-3 5.4E-5 1.1E-3 Pu-2408 1.2E-4 9.8E-4 9.3E-5 1.3E-3 5.4E-5 1.1E-3 Pu-2418 6.2E-3 4.8E-2 4.5E-3 6.5E-2 2.7E-3 5.6E 2

- Am-2418 2.4E-5 1.9E-4 1.8E-5 2.6E-4 1.1E-5 2.2E 4 Cm-2428 2.9E-3 2.3E-2 2.2E-3 3.1E-2 1.3E-3 2.6E-2 Cm-2448 4.9E-5 3.9E-4 3.7E-5 5.3E-4 2.2E-5 4.4E 4 F-27 MIPP Rev. 3

P Proc. 2

,[' Date 6/90 Rev. O ATTACIDENT 3 LONG-TERM DERIVED FREVENTIVE RESPONSE LEVELS FOR VEGETABLE FOODSTUFF $a.b (Continued) '

_ AdultC 'fe enc ChildC Produce 0 Leafy' Produce Leafy Produce Leafy Jiuelide acilko Mg acilko uCllko uC1/ka hG M ,

8 Assumes an ingestion period equivalent to the shorter time interval of the radionuclide mean lifetime or 365 days (see Appendix A). Leafy vegetables [

and other' produce are inges'.ed et the rates given in Reference 9 for the maximum exposed individual. Also, assumes that the produce and leafy vegetables are harvested short1; after a contaminating event.

b The derived response level for each radionuclide is capable of praducing the I preventive PAG dose. Therefore, if more than one radionuclide is present in the sample, the sum of ratios technique must be used to estimate the individual radionuclide concentrations that are permissible, e.g.,

l:

Cone A +,,3 Cone X . g 1, Response Level A Response Level X .

\ c Calculated concentrations may vary if calculation assumptions concerning Ingestion rates and dose conve'esion factors are different from those .

i presented in Reference 9.

d Produce = Non-leafy vegetables, fruits and grains.

• Leafy - Leafy vegetables. -

f 8,9E-2 = 8,,9x10*2 = 0.089.

E

' Adult dose conversion factors (DCF's) were obtained from ICRP-30410.11.12 dose conversion factors for other age groups were estimated by multiplying these adult DCF's by DCF ratios (other age group / adult) presented in Reference 9 for other nuclides having similar critical organs and retention l

times.

• F-28 MIPP Rev. 3

l U. i Proc. 2 I Date 6/90 Rev. O ATTACEMENT 4 1ANG-TERM DEEIVED VEGETATION SURFACE CONTAMINATION CONCENTRATIONS VEICE M&Y PRODUCE INGESTION DOSE C00MITHENTS AT THE PREFENTIVE PAG LEVEL" Adult Teen Child Produce D *C Produce Leafy Nuclide uC1/m2 Leafy"2 Produce Leafy l uC1/m ggg,fm 2 uCilm2 uC1/m2 uC1/m2 i I-131 1.8E-l' 1.4E+0 9.2E-2 1.3E+0 l

1-132 4.6E-2 9.4E-1 3.4E+1 2.8E+2 2.2E+1 3.2E+2 9.6E+0 1-133 1.9E42 6.8E+0 . 4E+1 4.2E+0 6.0E+1 1.8Et0 Rb-86 3.6E+1 1.8E+0 1.4E+1 2.2E+0 3.2E+1 9.2E-1 Cs-134 1.9E+1 3.4E-2 2.6E-1 9.4E-3 1.4E-1 5.8E-3

-Cs-136 2.2E+0 1.2E-1 1.7E+1 1.3E+0 1.9E+1 8.6E 1 1.7E+1 Cs-137 3.2E-2 2.6E 1 1.1E-2  ;

1.5E-1 6.0E-3 1.2E-1 Te-127m 2.4E-1 1.9E+0 1.4E 1 2.0E+0 8.0E 2 1.6E+0 Te-131m 6.8E+0 5.4E+1 5.0E+0 7.2E+1 5.6E+0 1.1E+2 Te-132 2.8E+0 2.2E+1 2.6E+0 3.8E+1 Sb-127 4.8E+0 1.0E+2 2.8E+0 2.2E+1 2.4E+0 3.6E+1 Sr-89 4.8E+0 9.6E+1 1.1E+0 9.0E+0 2.6E-2 3.6E-1 Sr-90 1.0E-2 2.2E-1 2.8E-3 2.2E-2 1.9E-4 2.8E-8 1.1E-4 Ba 140 1.3E+0 2.4E 3 1.1E+1 1.0E+0 1.5E+1 6.8E 1 1.4E+1 f-~s Mo-99 2.6E+1 2.0E+2 1.5E+1 2.2E+2

() Ru-103 Ru-106 8.4E-1 1.4E-2 6.6E+0 1.1E-1 7.0E+0 1.2E-2 1.0E+1 9.0E+0 9.6E-1 1.8E+2 1.9E+1 1.6E-1 1.4E-2 2.8E-1 Rh-10$f 3.4E+1 2.6E+2 3.0E+1 4.4E+2 5.8E+1 1.2E+3 i

Co-58 6.6E-1 5.2E+0 6.2E-1 8.8E+0 9.6E-1 1.9E+1 Co-60 5.2E-2 4.0E-1 4.6E-2 6.6E 1 7.0E-2 1.4E+0 Y-90 1.9E 1 1.5E+0 1.4E-1 2.0E-1 1.7E-2 3.4E 1 Y-91 1.6E-1 1.2E+0 1.2E-1 1.7E+0 Zr-95 1.5E-1 3.0E+0 3.6E-1 2.8E+0 3.0E 1 4.4E+0 4.2E-1 8.4E+0 Zr-97 9.6E+0' 7.6E+1 6.6E+0 9.4E+1 NB-95 6.6E+0 1.3E+2 9.8E-1 7.6E+0 8.6E-1 1.2E+1 1.3E+0 La-140 2.6E+1 6.0E-1 4.8E+0 4.6E-1 6.8E+0 5.6E 1 1.2E+1 Co 141 9.2E-1 7.2E+0 7.2E-1 1.0E+1 9.0E-1 1.8E+1 Ce-143 1.1E+1 9.0E+1 8.2E+0 1.2E+2- 9.4E+0 1.9E+2 Ce-144 1.7E-2 1.3E-1 1.3E-2 1.9E 1 1.6E-2 3.2E-1 i

Pr-143 1.3E+0 1.0E+1 1.0E+0 1.4E+1 i

Nd-147 1.2E+0 2.4E+1 1.8E+0 1.5E+1 1.4E+0 2.0E+1 1.8E+0 Np-239 3.6E+1 1.3E+1 1.0E+0 9.4E+0 1.3E+2 1.1E+1 Pu-23Sf 2.2E+2 2.8E 4 2.2E 3 2.2E-4 3.2E-3 1.3E-4 I

Pu-239f 2.6E-3 2.4E 4 1.9E 3 1.9E-4 2.6E-3 1.1E-4 Pu-240f 2.4E-4 2.2E-3 1.9E-3 1.9E-4 2.6E 3 1.1E-4 2.2E-3

Pa-241f 1.2E 2 9.6E-2 9.0E-3 1.3E-1

/m-241f 5.4E-3 1.1E-1 4.8E-5 3.8E-4 3.6E-5 5.2E-4 2.2E-5 4.4E-4 Jm-242f 5.8E-3 4.6E-2 4.4E-3 6.2E-2 2.6E-3 5.2E-2

( Cm-244f 9.8E-5 7.8E-4 7.4E-5 1.1E-3 4.4E-5 8.8E-4 I

( F-29 FIPP Rev. 3

. _ - - - - . - - - - - - - - - _ - - - - . . . _ _ - - _ , __ - - - - -, ,- - e, . - - , ,-

Proc. 2 N Date 6/90 Rev. O ATTACIBEENT 4 LONG-TERM DERIVED YEGETATION SURFACE CONTAMINATION CONCENTRATIONS ,

WEICE MAY PRODUCE INGESTION DOSE Cole (ITNENTS AT TEE PRETENTIVE PAG LITELa 1 (Continued)

Adult Teen Child ProduceD 'CLeafy G Produce Leafy Produce Leafy Nuclide uCilm2 uC1/m2 uC1/m2 uC1/m2 uC1/m2 uCilm2 Based on an assumed ingestion period equivalent to the shorter time interval  ;

of the radionuclide mean lifetime or 365 days (see Appendix A). Ingestion rates for both vegetation types are given in Reference 9 for the maximum ,

exposed individual. Produce and leafy vegetables are assumed to be harvested, fresh frozen, canned, or stored shortly after contaminating event.

b Produce - vegetables, fruits and grains.

C The agricultural productivity by unit area of 2 kg/m 2, used in these calculations, is an average value. Actual values should be taken into account when they are known for a specific geographic area. Also, the fraction of the plant area that is edible must be taken into account. This fraction was assumed to be 1.0 for these calculations. The areal activities i' in this Table do not apply to root crops if the harver* is not in progress and the produce is not on the ground surface during the accidental release of radioactivity. The areal activities in this Table are not equivalent to the initial deposition activity on the ground or other flat surfaces. In order  !

to estimate the initial deposition activity, the values in this table should be multiplied by a factor of 2 account for the 0.5 retention factor 9 for deposition on vegetation. ,

d Leafy = Leafy vegetables.

1.8E-1 = 1.8x10'l = 0.18.

f Adult dose conversion factors (DCF's) were obtained from ICRP-30:10,11,12 dose conversion factors for other age groups were estimated by multiplying these adult DCF's by DCF ratios (other age group / adult) presented in Reference 9 for other nuclides having similar critical organs and retention times.

F-30 MIPP Rev. 3

Proc. 2 i Date 6/90 Rev. O i V

ATTACBENT 5 MILE PROTECTIVE ACTION WORESEEET Worksheet i Time Date: Sample Locations ,_..;

Prepared by:

A. Preventive Protective Action Criteria Determination

1. Enter the Measured Activity Level (MAL) for each nuclide listed in Step 3 which is identified. (See Note 1.)

2. Calculate the ratio of the Peasured Activity Level to the appropriate Derived Response Level (DPl.) (see Note 2) activity for each nuclide as follows:

Measured Activity Level (MAL) of Nue11de 'A' Derived Response Level (DRL) of Nuclide 'A'

3. Sum the ratios for all listed nuclides which are identified by adding the results of the individual nuclide ratios as follows:

MAL 'A' + MAL 'B' + MAL 'C'  :

+ ,,,,,+ MAL 'X' = Sum DRL 'A' DRL 'B' DRL 'C' DRL 'X' EL'1142 AA.112.

a. 1-131 ( utill) =

l 1.5E-2 uCill

b. Cs-134 ( uC1/1) =

1 1.5E-1 uCill

c. Cs-137 ( uCill) =

2.4E-1 uCill Sum F-31 MIPP Rev. 3

Proc. 2 Date 6/90 Rev. O ATTACBSNT 5 MILE PROTECTIVE ACTION WORKSHEET (Continued)

Worksheet i

4. If the sum exceeds unity (1), refer to Attachment 5 for determination of appropriate preventive protective actions.

NOTES (1) If a nuclide not listed on this worksheet is identified, it can be considered by referring to the appropriate table in Attachment 1. If the nuclide is listed in that document, the appropriate ratio can be calculated and summed with the ratios identified in the worksheet.

(2) These DRLs assume the infant as the critical receptor per FDM-REP-12.

l I

l F-32 MIPP Rev. 3 L .

L

i i l

Proc. 2 Date 6/90  !

Rev. O ATTAca st? 5 i

MILE PROTECTIVE ACTIOII WORESEEET (Continued)

Worksheet i Times Date: Sample Location:

Prepared by:

i B. Emernency Protective Action Criteria Determination 1.

Enter the Measured Activity Level (MAL) for each nuclide listed in Step 3 which is identified. (See Note 1.)

2.

Calculate the ratio of the Measured Activity Level to the appropriate Derived Response Level (DRL) (see Note 2) activity for each nuclide as follows:  :

Measured Activity Level (MAL) of Nuclide 'A' Derived Response Lovel (DRL) of Nuclide 'A' 3.

Sum the ratios for all listed nuclides which are identified by adding the results of the individual nuclide ratios as follows:

MAL 'A' + MAL *B' + MAL 'C'

+ ,,,,,4 MAL 'X' = Sum DRL 'A' DRL 'B' DRL 'C' DRL 'X' .!

Nuclide M

a. I-131 ( uCill) =

1.5E-1 uCill l

b. Cs-134 ( uC1/1) =

1.5E+0 uCill

c. Cs-137 ( uCill) =

2.4E+0 uCill Sum F-33 MIPP Rev. 3

I Proc. 2 Date 6/90 Rev. 0 ATTACBENT 5 MIIK PROTECTIVE ACTION WORKSHEET (Continued)

Worksheet #

4. If the Sum exceeds unity (1), refer to Attachment 6 for determination of appropriate emergency protective actions.

NOTES (1) If a nucliue not listed on this worksheet is identified, it can be considered by referring to the appropriate table in Attachment 1. If the nuclide is listed in that document, the appropriate ratio can be calculated and sunned with the ratios identified in the worksheet.

(2) These DRLs assume the infant as the critical receptor per FEMA-REP-12.

O G

F-34 MIPP Rev. 3

Proc. 2 Date 6/90 Rev. O ATTACBIENT 6 Damrms wArgR PROTECTIVE ACTION WORKSHEET Worksheet i Time: Date: Sample Location:

Prepared by:

-A. Preventive Protective Action Criteris Determination

1. Enter the Measured Activity Level (HAL) for each nuclide listed in Step 3 which is identified. (See Note 1.)

2. Calculate the ratio of the Measured Activity Level to the appropriate Derived Response Level (DRL) (see Note 2) activity for each nuclide as follows:

Measured Activity Level (MAL) of Nuclide 'A' Derived Response Level (DRL) of Nuclide 'A'

3. Sum the ratios for all listed nuclides which are identified by adding the restilts of the individual nuclide ratios as follows:

MAL *A' + iiAL ' B' + }415 'C' + ,,,,,+ MAL 'X'

= Sum DRL 'A' DK1 'B' & ,'C' DRL 'Y.'

Nuclide g

a. I-131 ( uCill) =

2.5E-2 uCill

b. 1-132 ( uC1/1) =

3.5E-1 uCill

c. I-133 ( ucill) =

5.8E-1 uCill

d. Co-134 ( uCill) =

9.4E.1 uCill

e. CB-137 ( uCill) =

1.6E+0 uCill F MIPP Rev. 3 l

l 1

l Proc. 2 L' Date 6/90 Rev. O ATTACIBtENT 6 Da m nG WATER PROTECTIVE ACTION WORKSEEET (Continued)

Worksheet i I Nuclide ] Latin

f. Ru-106 ( uC1/1) = i j

6.1E-1 uCi/.* '

g. Ce-144 ( uCill) =

6.5E-1 uCi/1 'I

h. Te-132 ( uCill) =

1

)

2.7E+0 uC1/1 l .

Sum g

,m

)

4.

E If the Sum exceeds unity (1), rt fer to Attachment 5 for determination of 1 appropriate emergency protective ctions. (See Note 3.)

NOTES (1) If a nuclide not listed on this worksheet is identified, it can be )

considered by referring to the appropriate table in Attachmt.nt 1. If the i nuclide is listed in that document, the approprise ratio can be calculated l

and suunned with the other ratios calculatad on 9.'.= worksheet. i

.l (2) These DRLs assume the infant as the criticci receptor per FEMA-REP-13.

'(3) These calculations use DRLs which assume a maximum 5-day ingestion period.

If it is necessary to evaluate the long term usability of a water supply,. j refer to FEMA-REP-13 for appropriate DRLs.

i l

1 i

1 F-36 MIPP Rev. 3 1

1

)

i i

Proc. 2 l Date 6/90 NJ Rev. 0 ,

ATTACIMEET 6 neNw- W.TER PROTECTIVE ACTION WORKSHIET (Continued)

Worksheet i _ '

Times Date:

,_, Sample Location:

Prepared by:

-B. Emernancy Protective Action Criteria Determination (See Note 1) 1.

Enter the Measured Activity Level (MAL) for each nuclide listed in step 3 which is identified. (See Note 2.)

2.

Calculate the ratio of the Measured Activity Level to the appropriate Derived Response Level (DRL) (see Note 3) activity indicated for each nuclide as follows:

Measured Activity Level (HAL) of Nuclide 'A' Derived Response Level (DRL) of Nuclide 'A' eO 3.

Sum the ratios for all listed nuclides which are identified by adding the results of the individual nuclide ratios as follows:

MAL 'A' + MAL 'B'

+ MAL."C'_ 4 ,,,,,+ MAL 'X' = Sum DRL 'A' DRL 'B" DRL 'C' DRL 'X' Nuclide g .-

a. I-131 ( uCill) =

2.5E 1 uCill

b. I-132 (. uC1/1) =

3.5E+0 uCill

^

c. I-133 ( uCill) =

5.8E+0 uCill

d. Co-134 (. ucill) =

9.4E+0 uCill . - - -

e. Cs-137 (. uCill) =

1.6E+1 uCill

() F-37 MIPP Rev. 3

Proc. 2 Date 6/90 Rev. O ATTACBENT 6 M N EG VATER PROTECTIVE ACTION WORESEEET (Continued)

Worksheet f Nuclide M

f. Ru-106 ( uC1/1) =

6.1E+0 uCill L g. Ce-144 ( utill) =

6.5E+0 uCill

h. Te-132 ( uci/1) =

2.7E+1 uCill Sum

4. If the Sum exceeds unity (1), refer to Attachment 6 for' determitiation of appropriate emergency protective actions. (See Note 4.)

NOTES s

(1) FEMA-REP-13 water.

does not list DRLs for Emernenev Protective Actions for drinking The DRLs listed on this worksheet were calculated by multiplying the Preventive Protective Action DRLs for drinking water by a factor of 10.

(2) If a nuclide not listed on this worksheet is identified, it can be considered by referring to the appropriate table in Attachment 1. If the nuclide is listed in that document, the appropriate ratio can be calculated and summed with the ratios identified in the worksheet.

(3) These DRLs assume the infant as the critical receptor per FEMA-REP-13.

-(4) These calculations use DRLs which assume a maximum 5-day ingestion period.

-If it is necessary to evaluate the long term usability of a water supply, refer te FEMA-REP-13 for appropriate DRLs.

F-38 MIPP Rev. 3 l.

4

? roc. 2  ;

7,s Date 6/90 1

( Rev. 0 N )

ATTACB ERT 7 PRODUCE PROTECTIVE ACTION VDEKSEEET (See k .e 1)

Worksheet i Type of Produce:

Tiew s Date: Sample Locations Prepared by i A.

Preventive Protective Action Criteria Detenmination 1.

Enter the Heasured Activity Level (MAL) for each nuclide listed in Step 3 which is identified. (See Note 2.)

2.

Calculate the ratio of the Measured Activity Level *to the apprcpriate Derived Response Level (DRL) (see Note 3) activity indicated for each nuclide as follows:

Measured Activity Level fMAL) of Nuclide *A*

Derived Response Level (DRL) of Nuclide

()

'A' 3.

Sum the ratios for all listed nuclides which are identified by adding the results of the individual nuclide ratios as follows:

MAL 'A' 4 MAL 'B' t 4 MAL 'C' + ,,,,,+ MAL 'X' = Sum l DRL 'A' DRL 'B' DRL 'C' DRL 'X' ,

Nuclide m '

a. 1-131 ( uC1/kn) =

}

3.3E-2 uCi/kg

b. I-132 ( uC1/km) =

5.6E+0 uC1/kg

c. I-133 (. ucilka) =

9.4E-1 uC1/kg '

d. Cs-134 ( uci/ka) =

4.7E-2 uCi/kg.

e. Co-137 ( uCilka) =

5.4E-2 uCi/kg

() F 39 MIPP Rev. 3

1 Proc. 2 (

. ,O Date 6/90 '

\j Rev. O L

ATTACBtENT 7 r

PRODUCE PROTECTIVE ACTION WORKSEEET (See Note 1)

(C( r ?inued)

Worksheet i >

t Nucilde M

f. Ru-106 ( uC1/km) =

1.0E-1 uCi/kg l

+

g. Co-144 ( uCi/km) =

1.1E-0 uCi/kg

h. Te-132 ( uCilka) =

2.9E+0 uCi/kg t

Sum O 4. 'If the Sum exceeds unity (1), refer to Attachment 5 for determination of appropriate emergency protective actions. (See Note 4.)

NOTES (1) Produce (non leafy foodstuffs) refers to items such as frcits, grains and non-leafy vegetables (tomatoes, squash, etc.). ,

(2) If a nuclide not listed on this worksheet is identified, it can be .

considered by referring to the appropriate table in Attachment 1. If the nuclide is listed in that document, the appropriate ratio can be calculated and susuned with the ratios identified in the worksheet.

'(3) These DRLs assume the child as the critical receptor per FEMA-REP-13.

! (4) These calculations use a 30-day ingestion period. If it is necessary to evaluate the long term usability of foodstuffs, refer to FEMA-REP-13 for appropriate DRLs.

F-40 MIPP Rev. 3 l

i-l-

t-

iL f

Proc. 2 Date 6/90 O ATTACIDEDIT 7 Rev. O PRO M E PROTECTIVE ACTION WORKSEEET (See Note 1)

(Continued)

Worksheet f Type of Produces Time Date: Sample Location:

Prepared by:

B. h rnency Protective Action Criterit Determination (See Note 2.)

1. Enter the Measured Activity Level (MAL) f7r each nuclide listed in Step 3 which is identified. (See Note 3.)

2. Calculate the, ratio of the Measured Activity Level to the appropriate Derived Pesponse Level (DRL) (see Note 4) activity indicated for each nuclide as follows:

Measured Activity Level (MAL) of Nuclide '$1 Derived Response Level (DRL) of Nuclide 'A'

3. Sum the ratios for all listed nuclides which are identified by adding the results of the individual nuclide ratios as follows:

M + MAL 'B' + MAL *C' + ,,,,,+ MAL 'X' = Sum

' SAL 'A' DRL 'B' DRL 'C' DRL 'X' Nuclide g

a. 1-131 ( uC1/ka) =

3.3E-1 uCi/kg

b. I-132 ( uci/ka) =

5.6E+1 uC1/kg

c. I-133 ( uC1/ka) =

9.4E+0 uCi/kg

d. Co-134 ( utilka) =

4.7E-1 uCilkg

e. Cs-137 ( uCilke) =

5.4E-1 uC1/kg F-41 MIPP Rev. 3

i[ ')

1 Proc. 2 'I Date 6/90 j Rev. O ATTACBGINT 7 i PRODUCE PROTECTIVE ACTION WDRESEEET (See Note 1)

(Continued)

)

Vo:ksheet i Nuclide M

f. Ru-106 ( uCilka) =

i 1.0E+0 uCilkg

g. Ce-144 ( uC1/ka) =

1.1E+0 uCilkg

h. Te-132 ( uCilka) =

2.9E+1 uCi/kg i

L

! Sum l-

4. If the Sum exceeds unity (1), refer to Attachment 6 for determination of appropriate emergency protective actions. (See Note 5.)

L l NOTES I

(1) Produce (non-leafy foodstuffs) refers to items such as fruits, grains and non-leafy vegetables (tomatoes, squash, etc.).

i (2) FEMA-REP-13 does not list DRLs for Emernency Protective Actions for

l. foodstuffs. The DRLs listed on this worksheet were calculated by multiplying the Preventive Protective Action DRL for non-leafy foodstuffs by a factor of 10.

(3) If a nuclide not listed on this worksheet is identified, it can be considered by referring to the appropriate table in Attachment 1. If the nuclide is listed in that document, th appropriate ratio can be calculated and summed with the ratios identified on this worksheet.

(4) These DRLs assume the child as the critical receptor per FEMA-REP-13.

(5) These calculations use c 30-day ingestion period. If it is necessary to evaluate the long term usability of foodstuffs, refer to FEMA-REP-13 for appropriate DRLs. i F-42 MIPP Rev. 3

l

! Proc. 2

( Date 6/90 Rev. 0 l ATTACIMENT 7

}.

l 1.EAFY FOODSTUFFS FROTBCTIVE ACTION WORESEEET (See Ilote 1)

(Continued) i l Worksheet J Type of Foodstuffs l

i

. Times Date Sample Location:- i Prepared by:

l l

A.

Preventive Protective Action Criteria Determination 1.

Enter the Measured Activity Level (MAL) for each nuclide listed in Step 3 which is identified. (See Note 2.)

2.

Calculate the ratio of the Measured Activity Level to the appropriate Derived Response Level (DRL) (see Note 3) activity indicated for each nuclide as follows: 1 Measured Activity Level (MAL? of Nuclide 'A' Derived Response Level (DRL) of Nuclide 'A' l

C 3.

Sum the ratios for all listed nuclides which are identified by adding the results of the individual nuclide ratios as follows:

MAL *A' 4 MAL 'B'

+ MAL 'C' 4 ,,,,,4 MAL 'X' = Sum DRL 'A' DRL 'B' DRL 'C' DRL 'X' I

Ruelide Eglig,

s. I-131 ( uCi/ka) =

6.7E-1 uCilkg

b. 1-132 ( ucilka) =

1.1E+2 uCilkg

c. I-133 ( uCilka) =

1.9E+1 uCilkg

d. Co-134 ( uCilka) =

9.5E-1 uCilkg

+

e. Cs-137 ( uCilka) =

1.1E+0 uCilkg F-43 MIPP Rev. 3

iiii Proc. 2 Date 6/90 Rev. O ATTACB ERT 7 PRODUCE PROTECTIVE ACTION WORESEEET (See Note 1)

(Continued)

Worksheet #

• Nuclide 13.112

f. Ru-106 ( uC1/km) =

2.1E+0 uCi/kg 3 Co.144 ( uCilka) =

2.2E+0 uC1/kg

h. Te-132 ( uci/ka) -

5.8E+1 uC1/kg Sum O 4. If the Sum exceeds unity (1), refer to Attachment 5 for determination of appropriate preventive protective actions. (See Note 4.)

'A0TES i

(1) Leafy foodstuffs refer to leafy vera. tables such as lettuce, cabbage, etc.

(2) If a nuclide not listed on this w ssheet is identified, it can be considered by referring to the appropriate table in Attachment 1. If the nuclide is listed in that document, the appropriate ratio can be calculated and summed with the ratios identified on this worksheet.

(3) These DRLs assume the child as the critical receptor per FEMA-REP-13.

(4) These calculations use DRLs which assume a maximum 30. day ingestion period.

If it is necessary to evaluate the long term usability of foodstuffs, refer to FEMA-REP 13 for appropriate DRLs.

F-44 MIPP Rev. 3 I,

Proc. 2 Date 6/90 O ATTACBGBIT 7 Rev. O LEAFY FOODSTUFFS PROTECTIVE ACTION WORESEEIT (See Note 1)

(Continued)

Worksheet i Type of Foodstuff:

Time Date: Sample Location:

Prepared by:

B. N rnancy Protective Action Criteria Determination (See Note 2)

1. Enter the Measured Activity Level (MAL) for each nuclide listed in Step 3 which is identified. (See Note 3.)

2. Calculate the ratio of the Measured Activity Level to the appropriate Derived Response Level (DRL) (see Note 4) activity for each nuclide as follows:

Measured Activity Level (MAL) of Nuclide 'A' Derived Response Level (DRL) of Nuclide 'A'

3. Sum the ratios for all listed nuclides which are identified by adding.

the results of the individual nuclide ratios as follows:

M L' E + MAL 'B' + MAL 'C' + ,,,,,+ MAL 'X' = Sum DRL 'A' DRL 'R' DRL 'C' DRL 'X*

Nuclide g

a. I-131 ( ucilka) =

6.7E+0 uCi/kg

b. I-132 (

a uh) =

1.1E+3 uCi/kg

c. I-133 ( ucilka) =

1.9E+2 uC1/kg

-2

d. Co-134 ( ucilka) =

9.5E+0 uCi/kg

e. Cs-137 ( uCilka) =

1.1E+1 uC1/kg F-45 MIPP Rev. 3 l

l

. . ~ . . - . . - - - - . . . . - - - - -.. . _- - . - . .

Proc. 2 i

(' Date 6/90 Rev. O

\~

ATTACIMENT 7 PRODUCE PROTECTIVE ACTION WORKSEEET (See Note 1) 4 (Continued)

Worksheet i Nuclide Eglig

f. Ru-106 ( uci/km) =

2.1E+1 uCilkg I

g. Co-144 (_ qE11kg) =

l 2.2E+1 uCilkg

h. Te-132 ( ucilka) =

5.8E+2 uci/kg I i

Sum

4. If the Sum exceeds unity (1), refer to Attachment 6 for determination of appropriate emergency protective actions. (See Note 5.)

NOTES

( -(1) Leafy foof. stuffs refer to leafy vegetables such as lettuce, cabbage, etc.

)

(2) FE4A-REP-13 does not list DRLs for Emeraency Protective Actions for foodstuffs. The DRLs listed on this worksheet were calculated by J i

multiplying factor of 10. the Preventive Protective Action DRLs leafy foodstuffs by a j (3) If a nuclide.not listed on this worksheet is identified, it can be considered by referring to the appropriate table in Attachment 1. If the nuclice is listed in that document, the appropriate ratio can be calculated q j

and summed with the other ratios on this worksheet.

l (4) These DRLs assume the child as the critical receptor per FEMA-REP-13. '

(5) These calculations use DRLs which assume a maximum 30-day ingestion period.

If it is necessary to evaluate the long term usability of foodstuffs, refer to FEHA-REP-13 for appropriate DRLs.

.I ) F-46 MIPP Rev. 3 ,

L j

O O O Proc. 2 Date 6190 Rev. 0 10-0 ATTN 3  ;

. 4 t

L 10 ~

. t o -

o o  ;

_a - - -

I-131

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j 10 . . '

i i e i i i i i e i i i i i i iiiiiie i i g i i i i i 24 48 72 96 120 144 16s 192 e i i I 216 248 264 298 312 3JS 360 384 400 432  ;

{ l Milk Concentration of I-131, 1-133 and I-135, Normalized to Unit Deposition, from a Single Contaminating Event. ,

I  !

! r-47 ni,, ,,,, 3 1

i

L Proc. 2 l Date 6/90' Rev. O AttM s (Continued) 10-1 .

_- CS-134 CS-137 2

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Milk Cancentration of co-134 and Co-137. Igormalized'to thalt Depooltion, from a Slagle Contdaating Event. i F-48 MIpp g,,, 3 l i

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O O O Proc. 2 Date 6/99 Rev. O ATT M E 9 RADICEAGICAL BALF-LITES DEAN LIFETIBES EFFR:TIVE BALF-LITES DE TBCE11 TION.

AND MEAN EFFECTIVE LIFETIME ON VEGETATION FOR TTFICAL RADIONUCLIDES FOUIS IN A NUCLEAR REACTUR CORE .

Effective Balf-Life 14ean Effective Lifetime Mean Lifetime Radiological on Yemetation (days) on Yemetation (days) (days) Balf-Life (days)

Radionuclide Cobalt-58 11.69 16.84 102.24 71.00 Cobalt-60 13.90 20.01 2.674.80 1.920 Rubidium-86 8.01 11.53 26.93 18.70 Strontium-89 11.03 15.89- 75.82 52.10 Strontium-90 13.98 20.13 15.880 11.030 0.39 0.56 0.58 0.40 Strontium-91 3.23 3.84 2.67 Yttrium-90a 2.24 Yttrium-91 11.32 16.29 84.96 59.00 Zirconiun-95 11.53 16.60 93.89 65.20 0.68 0.97 1.02 0.71 Zirconium-97 Niobium-95 10.00 14.40 50.40 35.00 2.33 3.36 4.03 2.80 Molybdenum-99 0.35 0.36 0.25 Technetium-99m 0.24 Ruthenium-103 10.34 14.88 56.88 39.50 0.26 0.27 0.18 Ruthenium-105 0.18 Ruthenium-106 13.48 19.42 527 366 1.95 2.16 1.50 Rhodium-105 1.36 0.38 0.55 0.56 0.39 Tellurium-127 Tellurium-127m 12.41 17.87 157 109 2 0.05 0.07 0.07 0.05 Tellurium-129 0.48 0.49 0.34 Tellurium-129m 0.33 1.65 1.80 1.25 Tellurium-131m 1.15 2.64 3.80 4.68 3.25 Tellurium-132 3.04 4.38 5.59 3.88 Antimony-127 0.25 0.25 0.18 Antimony-129 0.18 7.36 11.59 8.05 Iodine-131 5.11 Iodine-132 b 0.09 0.14 0.14 0.09 0.82 1.19 1.26 0.88 Iodine-133 0.04 0.05 0.05 0.04 Iodine-134 0.27 0.39 0.40 0.28 Iodine-135 F-50 MIFF Rev. O

o O O Froc. 2 Date 6/90 attar 2nENT 9 Rev. O MacIOtacicAL a&W-LIVES, DEEAN LIFETDEES. EFFECTIVE BAU-LIVB5 ON TEGETATION, AND MEAN EFFECTIVE LIFETDet ON (Continued)

TEGETATION FOR TYFIC&L BADIONOCLIDES FOUND Effective Balf-Life Mean Effective Lifetime Radionucline on Venetation (days) Mean Lifetime Radiological on Venetation (days) (days) Balf-Life idays)

Ceslun-134 13.74 Cesium-136 19.79 1080 6.74 750 '

Cesium-137 9.71 18.72 13.98 20.13 , 13.00 i

Barium-140 6.59 15,840 11.000 Lanthanum-140 9.63 18.43 1.49 2.15 12.S0 Cerlun-141 9.77 2.40 1.67 Cerium-143 14.06 46.51 1.26 32.30 Ccrium-144 1.81 1.99 13.34 19.21 1.38 l Praseodymium-143 6.92 409 284 Neodymium-147 9.97 19.73

} 6.19 8.92 13.70 Neptunium-239 15.98 2.01 2.90 11.10 Plutonitsm-238 13.99 3.38 2.35 I

Plutonitan-239 20.15 46,800 32,500 14.00 20.16 Plutonium-240 14.00 1.2 x 107 8.9 x 106 j Plutonium-241 20.16 3.& x 106 13.96 20.11 2.4 x 106 Americium-241 7,704 14.00 20.16 5.350

, Crrium-242 12.89 2.16 x 105 1.5 x 105 Curium-244 18.57 235 13.97 163 20.12 9.547 6,630 '

4 I

e I If Strontium-90 is present in an airborne release to the environment. Yttritan-90 will appear to have an i

effective half-life and mean effective lifetime un vegetation which corresponds to that of Strontium-90.

b If Tellurium-132 is present in an airborne release to the environment. 41ne-132 will appear to have an effective half-life and mean effective lifetime on vegetation which corresponds to that of Tellarium-132.

1 i

i F-51 i

MIFF Rev. 3 i

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_ _ _ _ _ _ _ _ _ _ _ _ _ _ ~_ -_ _ _ __ --

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Proc. 3 Date 6/90

'(] V Rev. 0 RADIOLOGICAL REALTR SPECIALIST AT THE SEABROOK STATION IF0/ EOF CEECK-OFF LIST TIME INITIALS ,

SITE AREAIGENERAL DMtGENCY

1. Receive direction from the Radiological Health Coordinator to report to the Seabrook Station 3 IF0/ EOF. )

2, Uputs arrival at the Seabrook Station IF0/ EOF, call l the State E00.

3. Provide ' input to the Radiological Health Coordinator in the determination of precautionary protective actions based upon the magnitude of the release, status of plant conditions, and accident prognosis.

4. Assist the RHC in determining sampling strategies and location assignments of the Division of Health O

Engineering field teams. l 3.

Review data received from NHY ORO and State of New Hampshire field teams. Review meteorology and projected deposition levels received from NHY ERO accident assessment personnel.

6. Brief the Radiological Health Coordinator on field team survey results, meteorology and projected deposition levels. )

)

7. Participate in briefing updates of plant cos.ditions and projected actions that could affect the off-site safety and health.

l

8. Coordinate sample collection strategies and 1 allocation of sample collection assistance resources with the NHY ERO, NHY OR0. and the State of New  !

Hampshire.

i l 9. Participate in decision making for ingestion pathway t protective actions.

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_Date 6/90 Rev. 0 TIME INITIALS

' 10. Report any supplemental information to the RHC at the State EOC.

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Proc. 4 Date 6/90 Rev. 0 ENVIR00 MENTAL SAMPLING TEAM ORGANIEEE CERCK-OFF LIST TIME _ IRITIALS SITE AREA / GENERAL EMERGENCY

1. Receive notification from the Radiological Health coordinator.

2.- Assist the RHC in notification of sample team members.

3. Obtain key to open DHE office from RHC (after hours). .

4. Obtain mobile radios from the MEMA cc:amunications center and transport to the Division of Health Engineering.

5. Upon arrival at DHE determine vehicle availability and' check vehicles (stset, fuel, oil, tires).

Notify the RHC 4 ==diately of any eroblems.

.6. . Place mobile radios in vehicles.

'7. Obtain dosimetry from P.adiation Control Program

' cabinet in basement.

8. Log in/out all team members and issue dosimetry as they. arrive usine DEE Procedure 2.05S.

9. Assign teams and vehicles. Designate one team member as team leeder for each team.

10. . Notify the RBC when teams are ready. Brief teams on current plkit status using the Field Team Plant

' Status form.

11 ~. Teams-will proceed to the' York County Courthouse in Alfred and repcrt to the York County Emergency Management Agencf 30C in the basement of the courthouse.

F-54 MIPP Rev. 3

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Proc. 4 Date 6/90 Rev. O TIME INITIALS

12. ' The Sample Team Organizer will accompany the teams to Alfred and assist the Radiological Health specialist assigned to the Alfred EOC.

13. Upon arrival, check into the York County EOC.

14. Resave environmental sampling kits from storage and assist = field teams in completing a complete inventory of equipment. (Replace any missing items from stock in cabinet.- Any items which can not be replaced should be noted and a determination made as to the need for that item.) ..

15. Dispatch teams as directed.

16. Coordinate setup of sample receipt area and-decontamination area with the Radiological Health Specialist.

17. Maintain consnunications with the , field teams.

s 18. Periodically brief the Radiological Health Specialist on the team status.

19. Obtain periodic updates of plant status and notify field teams of any pertinent information.-

20. Coordinate team activities with utility or federal teams as direc;ted.

21. Assist the Radiological Haalth Specialist as needed. ,

F-55 MIPP Rev. 3 z

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4 Proc. 5 Date 6/90-key. O RADIOLOGICAL HEALTH SPECIALIST AT ALFRED CHECK-OFF LIST TIME INITIALS SITE AREA / GENERAL EMERGENCY l

1. Receive notification from the Radiological Health coordinator. -

2. Assist Sample Team Organizer at DHE and coordinate transportation to Alfred.

3. Proceed to the York County Courthouse in Alfred.

4. Upon arrival, check in to the York County EOC and notify the County EKA Director of your arrival.

5. Establish communications with the State EOC and notify the RHC of your arrival.

h 6. Obtain briefing.from the RHC and instructions for the field teams.

7. Obtain keys-to "Seabrook Cabinets' from the-key locker. Do a quick inventory check using the equipment list maintained in the cabinets.

8. -Log in all field team members as they arrive. ___

-9.- Notity the RHC when field teams have-arrived, have completed all equipment checks and are ready to be dispatched.

'10 . -Brief the Team Organizer and team members on the current plant status and instruct the teams on the sampling. strategy to be followed. __

11. Assist the County EMA as needed.

12. Maintain communications with the RHC.

13. Coordinate parking lot setup with the County EMA, the-Sample Team Organizer and the Sheriff.

lh F-56 MIPP Rev. 3 1

Proc. 6 Date 6/90 Rev. O DEPARTMENT OF AGRICULTURE REPRESENTATIVE AT THE STATE EOC CHECK-OFF LIST TIME INITIALS I

SITE AREA /CENERAL EMERGENCY-

1. Receive notification from. State Police or the Operations Officer.

2. Report.to the State EOC in Augusta. Maine. __

3. Obtain briefing from the Radiological Health Coordinator.

4. Contact Field Inspector Supervisors using the Division of Regulations Telephone Numbers List.

5. Contact the DOA Division of Regulations Office to obtain the-most recent copy of Land Use Data.

6. Upon direction by the Radiological Health coordinator, ensure that public information on.

ingestion pathway protective actions is disseminated.

7. . Upon direction by the Radiological Health coordinator, ensure that all dairy animals within ten miles of Maine Yankee are sheltered and placed on stored feed.

8. . Develop sampling strategies with the Radiological Health Coordinator concerning the types of samples needed, the prioritization for analysis, and the locations where sampling is most needed.

9.  : Direct Inspector Supervisors to implement the collection of food and water at pre-estsblished sample points within affected areas. __

10. Assist in the development of protective action

. decisions with the Radiological Health Coordinator based upon environmental sample analysis results.

F-57 MIPP Rev. 3 l

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I Proc. 6 Date 6/90 Rev. O i i

TIME gg

'11. Upon determination that protective actions are warranted, ensure that-all affected dairies, farms, food processing, and other establishments are notified.

12. If situation tsrminates, notify Field Inspector Supervisors and ensure that Field Inspectors are notified of situation termination.

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A F-58 MIPP Rev. 3 I

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Proc.17-i Date 6/90 Rev. O DIVISION OF REALTH ENGINEERING REPRESENTATIVE AT THE STATE EOC CHECK-OFF LIST TIME INITIALS SITE AREA / GEN 8'D Af- EMERGENCY

1. Receive notification from State Police or the Operations officer.

2.- Report to the State EOC in Augusta. Maine.

3. Obtain briefing from the Radiological Health '

Coordinator.  ; u._

4. Develop protective action decisions with the Radiological Health Coordinator based upon environmental sample analysis results.

5; Upon determination that protective actions are warranted,-constrict the use of public and private O water-supplies.-as appropriate.

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Proc. 8 y Date'6/90 Rev. 0

, n?.

DEPARTHENT OF HARINE RESOURCES REPRESENTATIVE AT THE STATE EOC l-CHECK-OFF LIST TIME INITIALS ,

-t SITE AREA / GENERAL EMERGENCY

r l 1. Receive notification from State Police or the

.i operations Officer.

2. ' Report to theLState EOC in Augusta, Maine. _.

3. Obtain briefing from the Radiological Health >

Coordinator.

-_ 4 . - Develop protective action decisions with the 1 Radiological Health coordinator based upon l environmental sample analysis results. ,_

5. .Upon determination that protective actions are warranted,-utilize the land use data in the i

attachment to-ensure that all affected fish and J l

shellfish dealers are notified of restrictions as appropriate.

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) MIPP Rev. 0

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t Proc. 9 Date 6/90 Rev. O DEPARTMENT OF INLAND FISHERIES AND WILDLIFE REPRESENT & TITE AT TEE STATE BOC CHP~ OFF LIST T'un INITIALS SITE AREA / GENERAL EMERGENCY

1. Receive notification from State Police or the Operations officer.

2. Report to the State EOC.in Augusta Maine.

3. Obtain briefing from the Radiological Health Coordinator.

4. Develop protective action decisions with the Radiological Health Coer:dinator based upon radiological projections, field measurements, and/or environmental sample analysis results.

5. Upon' determination that protective actions are warranted. : ensure . that hunting and fishing seasons:

are suspended and waterways closed as appropriate.-

5 d't if -

r F-61 MIPP Rev. 3 l

3 -

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O

- l- ATTACHMENT 1 LAND USE DATA O

THIS DOCUMENT IS MAINTAINED UNDER SEPARATE COVER AT THE STATE EHERGENCY OPERATIONS CENTER IT CONTAINS NAMES AND ADDRESSES OF FOOD PRODUCERS AND PROCESSORS WITHIN THE STATE OF MAINE IN THE. INGESTION PATHWAY ZONE OF SEABROOK STATION P

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ATTACHMENT 2 BBERG13CY RESPONSE TEAM /

DISASYER RESPONSE TEAM THIS DOCUMENT IS MAINTAINED UNDER SEPARATE COVER AT THE STATE EMERGENCY OPERATIONS CFNTER IT CONTAINS NAMES AND TELEPHONE NtMBERS OF EMERGENCY EESPONSE PEESONNEL WBO CAN ASSIST IN PERFORMDIG ENVIRONMENTAL HONITORING OR OTHER ACTIVITIES IN.TER EVENT OF AN ACCIDENT AT SEABROOK STATION MIPP Rev. 3 f5

O.

l. ATTACEMENT 3 FARMER NOTIFICATION PERSONNEL THIS DOCUMENT IS MAINTAINED UNDER SEPARATE COTER AT THE STATE ENERGENCY OPERATIONS CENTER IT'CONTAINS NAMES AND TELEPHONE NIMBERS OF ENERGENCY RESPONSE FERSONNEL WBO CAN ASSIST IN' NOTIFICATION OF FARMERS IN THE EVENT OF AN ACCIDENT AT SEABROOK STATION I t e; a ,, E... ,

4  ?

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