ML20062L190

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Public Version of Rev 6 to State of Me Ingestion Pathway Plan for Seabrook Station
ML20062L190
Person / Time
Site: Seabrook  NextEra Energy icon.png
Issue date: 09/15/1993
From: David Brown
MAINE, STATE OF
To:
Shared Package
ML20062L183 List:
References
PROC-930915-01, NUDOCS 9312290226
Download: ML20062L190 (52)


Text

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b RMD CONTROL COPY # [h[h ,.

STATE OF MAINE INGESTION PATHWAY PLAN (MIPP)

FOR SEABROOK STATION SEABROOK NEW HAMPSHIRE 1

APPROVED: DATE: 9 /5 98 DavidT5. Brown, Director /

Maine Emergency Management Agency .

i REVISION: 6 i EFFECTIVE DATE: 10/08/93 MIPP Rev. 6 9312290226 931018 PDR ADOCK 05000443 F PDR ,

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LIST OF EFFECTIVE PAGES j Pane Rev.

Cover 6 i-v 3 LOEP-1 and LOEP-2 6 1-1 and 1-2 3 ,

2-1 to 2-4 3 ,

3-1 to 3-2 3 3-3 6 3-4 to 3-13 3 4-1 to 4-5 3 4-6 6 4-7 to 4-24 3 5-1 to 5-4 3 ,

6-1 and 6-2 6  :

e 7-1 and 7-2 3 8-1 3 8-2 6 -i

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8-3 to 8-10 3 8-11 to 8-12 6 8-13 3  !

Appendices A-1 3 A-2 6 A-3 to A-4 3 A-5 6

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LOEP-1 MIPP Rev. 6

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A-6 to A-7 3 B-1 to B-51 3 [

C-1 to C-11 3 ,

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D-1 to D-2 6 .I D-3 to D-9 6  ;

D-10 3 i r

D-11 to D-14 6 l r

D-15 to D-16 3 D-17 6 h D-18 to D-19 3 i D-20 to D-24 6 .!

I D-25 to D-29 3  ;.

i D-30 to D-32 6  !

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D-34 to D-35 6 D-36 to D-66 -3 ,

i D-67 to D-79 6 I I

E-1 to E-24 5 F-1 to F-2 6 F-3 to F-51 3 F-52 6 l i

F-53 to F-61 3 l

~f Attachments >

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, ' Attachment 1 3 Attachment 2 3 Attachment 3. 3 I

LOEP-2 MIPP Rev. 6 i

Sample analysis will be performed at the Public Health Laboratory (PHL) in accordance with standard laboratory procedures Appendix E to this plan. 4 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 recommendations from State agencies at the EOC. The DHE Radiological Health Specialist at the IF0/ EOF will coordinate ingestion pathway decisions for Maine l with accident assessment personnel of the State of New Hampshire, the l Commonwealth of Massachusetts, and the Seabrook Station Emergency Response  ;

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

Farmers and food processing facilities within the IPZ will be contacted by  :

t personnel from the University of Maine Cooperative Extension Service and Maine Department of Agriculture. They will distribute informational brochures and give farmers advice and recommendations as to prevention or mitigation of radioactive contamination of food products. The York County Cooperative 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 I radio and television.

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In the recovery stage, when plant conditions have stabilized, general information will be transmitted by News Releases and specific recommendations will be made the Governor's Office through MEMA by DHE and DOA. 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 j Inland Fisheries and Wildlife respectively. With passage of time, weathering. ,

and decontamination efforts, it may be possible to release food' products to the lt L

3-3 MIPP Rev. 6 [

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t The Radiological Health Coordinator will compare the measured results of sample j analyses to the derived response levels in the assessment of the radiological l consequences via the ingestion pathway. The checklist for the Radiological Health Specialist at the EOC contained in Appendix F of this plan includes

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vorksheets for calculating the ratios of measured activity levels to derived response levels for contributing radionuclides for each pathway of concern.

During the time when sampling analyses are not available to confirm deposition, i l easily Onplemented precautionary actions or preventive actions, e.g., removing l milk producing animals from pastures or washing garden vegetables and fruits, l may be recommended. Emergency protective action recommendations will be issued if sample analyses indicate that the amount of radioactive material in milk, i food, or water exceed the PAG.

  • The following discussion traces the decision process for recommending ingestion pathway protective actions. To facilitate understanding Figure 4.6-1 describes this procedure by means of a flow chart. The term " response level
  • refers to i the predetermined radioactivity levels.  !

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

t This determination entails use of data provided by the utility, including plant l

status, accident prognosis, projected deposition levels, meteorology (wind speed l and direction, precipitation and forecasts) and field measurements. These data will be used to determine whether precautionary actions should be implemented.  ;

Precautionary ac*. ions will include sheltering milk producing animals, putting them on stored feed, and issuing news releases advising against consumption of  ;

i locally grown produce until measurements of radioactivity can be made. l If projected deposition levels exceed the FDA preventive response levels listed  !

in Tables 4.6-1, 4.6-3 and 4.6-4, precautionary actions will be implemented.

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Upon implementing precautionary actions, proceed to the second decision step, i

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Block 12 - Determine whether any preventive PAGs have been exceeded for one or '

more of the three ingestion pathways based on results of sample analyses. This j

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l 4-6 MIPP Rev. 6 l

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r SECTION 6 i

6.0 FACILITIES Emergency Response Facilities utilized in the event of an accident at Seabrook Station that has the potential of impacting the State of Maine are described in e

this section.

6.1 STATE EMERGENCY OPERATIONS CENTER The State EOC 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 EOC. The primary means of communication with the other emergency response facilities is by telephone. Two-way radio is a back-up means of communication. The Public Health Laboratory is within easy walking distance. The Maine Media Center is j located in the same building as the State EOC. .

6.2 YORK COUNTY EMERGENCY OPERATIONS CENTER i 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 EOC 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. l 6.3 INCIDENT FIELD OFFICE / EMERGENCY OPERATIONS FACILITY .

The incident Field Office / Emergency Operations Facility (IF0/ EOF) is located in l Newington._New Hampshire. The IF0/ EOF is operated by Seabrook Station and will ,

l be staffed by representatives from Seabrook Station, Federal agencies and State agencies from New Hampshire. Massachusetts and Maine. The Radiological Ecalth  !

6-1 MIPP Rev. 6

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Specialist of DHE and representatives of MEHA and Maine State Police will proceed to the IF0/ EOF in the event of an accident at Seabrook Station that has  !

the potential of impacting the State of Maine.  ;

6.4 PUBLIC HEALTH LABORATORY The Public Health Laboratory within the Division of Health Engineering will receive samples of food, milk, water, vegetation, soil, etc., collected in the i field in accordance with DHE Procedures. Samples will be processed in 4

accordance with priorities established by DHE accident assessn>ent personnel.

Testing of samples will be performed at the Public Health Laboratory. If the f volume of samples exceeds the capacity of the Laboratory, samples will be .l

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dispatched to nearby laboratories available through the New England Compact or  !

the Federal Radiological Emergency Response Plan.  ;

4 6.5 MEDIA CENTEE The Media Center is located at the Newington Town Hall in Newington, New ,

Hampshire. This facility is utiliced to prepare and distribute news releases and to permit exchanges of information among~the designated spokespersons for l North Atlantic Energy Service Corporation, State agencies and Federal agencies. l News releases prepared by one of the designated spokespersons will be reviewed with his counterparts before release to the news media. A Maine Public Affairs Officer will proceed to the Media Center in the event of an accident at Seabrook Station. ,

6.6 MAINE MEDIA CENTER i i

The Maine Media Center is~ located on the ground floor of the State Office

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Building in Augusta. This. facility is used to distribute news releases to the -j press from the State of Maine. 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 MIPP Rev. 6

4 The specific needs for FRERP and Compact resources cannot be determined in advance of an accident and itemized. The State of Maine 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 f augmenting monitoring and accident assessment staff to ensure reasonable workloads and a thorough response. .

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Accidents that result in establishing large exclusion areas may  !

require special equipment, and personnel with appropriate training, f to carry out monitoring and environmental sampling within the area.

The contamination of available equipment, or breakdowns of one-of-  !

a-kind items may require securing replacements in order to continue f monitoring, environmental sampling activities and laboratory l l analysis. [

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Prolonged exposure of personnel to high levels of radiation may require 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 j period of monitoring, sampling and clean-up.

Requests for Federal assistance will be coordinated with the state governments l of New Hampshire and Massachusetts and with Seabrook Station ERO personnel at l l the IFO/ EOF in Newington, NH. ~l l

t When requests are approved by the Director of DHE the Governor 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 i

DHE will complete the activation process specified in the New England Interstate l

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i 8.4.10 National Communications System (NCS)

1. Providea.and coordinates, in response to a FEMA J request, the necessary communications for the Federal Government response in accordance'with the National- l Plan for Communications Support in Emergencies and  ;

Majot Disasters. Is prepared to provide. this support prio' to a formal declaration of an emergency or major ,

disaster. 4 I

2. Provides technical representation to appropriate State ,

agencies to assist in meeting their communications requiremente. l l Seabrook Station ERO personnel will notify the Nuclear Regulatory Commission 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 FEMA and DOE to prepare to support the affected States under FEMA's coordination. .

I 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 h nontechnical support and to DOE-Brookhaven for technical support. In accordance with the FRERP, FEMA will inform other Federal agencies of State needs. l Airports in the vicinity of Seabrook Station which may be utilized by federal agencies are listed in Table 8.4-1.  ;

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' t TABLE 8.4-1 AIRPORTS IN VICINITY OF SEABROOK STATION IPZ  !

Concord Municipal Airport - Concord. NH A. Runways:  !

t Three runways - asphalt ,

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 B. Instrumentation:

Instrument approach is possible on Runway 17 using: i Visual Omni Range [

Visual Omni Range / Distance Measuring Equipment  !

C. Mainly for smaller aircraft.  ;

Portland International Jeteort - Portland. ME  ;

A. Runways:

Two runways - asphalt i Runway 11-29 6800 ft, long x 150 ft wide Runway 18-36 5000 ft. long x 150 ft. wide

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B. Instrument approach is possible on Runway 11-29 using: .:

Instrument Landing System C. Will accommodate Boeing 727 or comparable aircraft. I j Pease International Tradeport - Newincton. NH (Seabrook Station EPZ Access)

A. Runways: t l

One runway - asphalt l

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

-j All instrumentation capabilities are available. [

C. Will accommodate any type and size aircraft. -i 8-12 MIPP Rev. 6 L L

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

points for their respective Emergency Response Organizations.

Emergency A center established to coordinate the flow of technical Operations information from the onsite to the offsite Emergency Response l

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Facility (EOF) Organization. It is in the EOF that accident assessment'  !

activities are coordinated among Federal, State, local, and utility personnel. State of Maine officials will be

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l represented at the EOF in Newington, NH in the event of an  !

, emergency at Seabrook Station.

Emergency The area covered by the Radiological Emergency Response Plan.  !

r Planning The Ingestion Pathway EPZ is the area contained within 50  ;

2ones (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.  ;

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

GENERAL The most severe of the Emergency Classifications. It may-EMERGENCY involve substantial degradation or melting of the reactor's radioactive core with potential for loss of containment  ;

integrity. Release may exceed the EPA Protective Action t

Guideline exposure levels beyond the power plant site  !

boundary area. f i

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

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-A-2 MIPP Rev. 6 l I

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'It ABBREVIATIONS AND AC'10NYMS i

BOH (Maine) Bureau of Health  !

CPCS-1 Common Program Control Stat!.on - 1

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DHS Division of Human Services DOA (Maine) Department of Agriculture  !

DOC (U.S.) Department of Commerce D0D (U.S.) Department of Defense _'

i DOE (U.S.) Department of Energy  ;

DOT (U.S.) Department of Transportation DEP (Maine) Department of Env > tal Protection ,

DHE (Maine) Division of Health Engineering EBS Emergency Broadcast System ECL Emergency Classification Level  ;

EOC Emergency Operations Center EOF Emergency Operations Facility EPA (U.S.) Environmental Protection Agency -'

EPZ Emergency Planning Zone Food and Drug Administration FDA 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 .f IFO Incident Field Office MEMA Maine Emergency Management Agency l

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t APPENDII D i

DIVISION OF HEALTH ENGINEERING ,

PROCEDURES t

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THIS DOCUMENT CONTAINS PROCEDURES TO BE USED  ;

BY DHE PERSONNEL TO RESPOND TO A RADIOLOGICAL ACCIDENT h

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i D-1 MIPP Rev. 6  ;

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- r DIVISION OF HEALTH ENGINEERING PROCEDUPTS r

CONTENTS AND REVISION STATUS Number Rev. Procedure Title Pace s

2.01 6 Radiological Monitoring Team Notification D-3 2.05S 3 Personnel Dosimetry D-10 2.06S S Monitoring and Decontamination of D-20 '{

Emergency Workers, Equipment and Vehicles ,

2.lls 4 Ingestion Pathway Environmental Sample D-36 ,

Collection 2.12S 2 Air Sampling Procedure D-66 ,

2.20 0 Radiological Screening Program D-76 f l

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- Proc. 2.01 Date 9/93  ;

Rev. 6 RADICIDGICAL MONITORING TEAM NOTIFICATION L

I. Purpose l To provide a system for prompt notification of personnel in the event of ,

a radiological accident.  ;

II. Discussion In the event of an accident involving a nuclear power plant or l radioactive material, the Division of Health Engineering (DHE) is notified by the State Police. The State Police will notify DHE primary call list personnel (Attachment 1) by initiating an all call via pager.

A designated Radiological Health Coordinator (RHC) will report to the State Emergency Operations Center (EOC) located in the basement of the  !

State Office Building at an Alert or higher ECL. From there, the RHC ,

will initiate the notification of monitoring temo members and laboratory l personnel at a Site Area Emergency or higher ECL.

III. Notification Procedure t

A. Initial Notification Requirements: ,

Rad. l Specialist Mon. Team Lab Nuclear Power Plant: Unusual Event X  ;

Alert X Site Area X X X l General X X X Portsmouth Naval Shipyard X i

l Rad. Materials Incident X B. The Division Director and Radiation Control Program personnel may be >

notified by pager. Pagers are alphanumeric. Page may be either all call or individual. ,

1. All Calls (Verbal Message)
a. Dial 1-800-639-77s7
b. Specify group as Health Engineering
c. Request all to operator ,
d. Give message, include return phone number for confirmation, l time and date of call.  ;
2. Individuals (Verbal Message)
a. Dial 1-800-639-7707
b. Specify group as Health Engineering ,
c. Request desired individual  ;

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Date 9/93

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d. Give message, include return phone number for confirmation,  :

l time and date of call.

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3. Individuals (Number only) l t
a. TROM TOUCHTONE PHONE ONLY, dial number indicated on the call  !

list. l

b. After recorded message, key in return phone number.

1 C. Notification of personnJ1 will follow the order of the call lists (Attachments 1, 2 and 3). The following format should be used:  !

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1. State your name.

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2. Ask to speak to person called.

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3. State the type of accident and request that personnel report'to I the following location:
a. Radiological Health Specialists - State _EOC  !
b. Monitoring Teams - First report to State EOC t

- All others to DHE, 157 Capitol Street  ;

c. Lab Personnel - Health and Environmental Testing Lab i i
4. Ask for confirmation that you are understood and request an .f estimated response time. [
5. Record' time notified on the call list.

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D-4 MI?P'-Rev. 6 l v

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. Proc. 2.01 Date 9/93 Rev. 6 j ATTACIDGENT 1 DIVISION OF HEALTH ENGINEERING PRIMARY Q 1L LIST i

Name/ Address Home Phone Business Phone Time Contacted 1 Donald Hoxie M"4 287-5686

  • M i

i l W. Clough Toppan M 287-5698 .

M *W f M  :

I Patrick Dostie MW 882-6321 ,

6 *M  ;

maammmmmmmmme Robert Schell N 287-5696 '

> man.

Jay Hyland M 287-5677 monummunspues mange  :

maammmmum I

Linda Plusquellic W 287-5673 eM H

legasunadam  ;

l David Breau M S -5295 l N ,

EM i Wallace Hinckley N 287-5690

  • denotes numeric pager; must be called from a touchtone phone.

D-5 MIPP Rev. 6 l

Proc. 2.01 Date 9/93 Rev. 6

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ATTACEDoutT 2 MONITURING TEAM CALL LIST '

Name/Addre7g Home Phone Busineer Phuy Time Contacted Robert Peterson M 287-5693 ,

w Ron McDougal N 287-5691 ,

I!LN9115  ;

l Kerwin Keller MM 287-5687 NNW  !

t1lugETJK3ii1Bmm*

Francis Drake -

287-5680 muummummums l Jay Hardcastle eMRAEAEF 287-5688 i

l Ken Meyer N 287-5684 maammmuunnamens Steve Zayssly E. M 287-5692 m

$8nImunumminutur l Mary coor N 287-5682 N'DM MfM David Braley hNg 287-3194 ammmmmmmmmum i

D-6 HIPP Rev. 6

+ Proc. 2.01 Date 9/93 Rev. 6 ATTACHMENT 2  !

l MONITORING TEAM CALL LIST (Continued) j i

Name/Addres3, Home Phone Business Phone Time Contacted l Richard Smith 6 287-5695 I l Carl Witham M 287-5671 M

N i l Jeffrey Folger M 287-5671 M .

i sumner clazier M 287-5671 l l

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Robert Stilwell M 287-5743 -l l

Scott Davis 324-9427 l M

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Michael Murray N 774-4581  !

X 314 N ,

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C Proc. 2.01 '

Date 9/93 Rev. 6 i i

ATTACHMENT 3 .i LABORATORY PERSONNEL  ;

I Name/ Address Mcnne Phone Dusiness Phone Time contacted Cheryl Baker M 287-2727 m.n.an -mass ,

Dr. Philip W. Haines M 287-2727  ;

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' Jack Krueger M 287-2727 Jtehst f"akhlInglrt6 M,WLM Thomas Dwyer malamansuussanus 287-2727 Richard French M 287-2727 +

alumummumammuner i Pat Boudreau M 287-2727 IRWaumusummeraums Jean Thayer M 287-2727 i b

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Proc. 2.01 i Date 9/93 Rev. 6 A1TACHMENT 4 STATE POLICE CALL LIST Division of Health Engineering j Radiation Control Program ,

call List For Incidents Involving Radioactive Materials

1. Group Page (All Incidents)
a. Dial Page New England, 1-800-639-7000
b. Request Health Engineering, Croup Page
c. Give message, include return phone number, date and time.
2. Individual Page Individuals may be called directly at home, paged through the operator at Page New England, or paged directly from any touchtone phone. Numbers are listed below.-

1 Page through operators

a. Dial Page New England, 1-800-639-7000
b. Request Health Engineering and specify individual ,
c. Give message, include return phone number, date and time.

Direct pages (direct pages must be done through a touchtone phone)  ;

a. Dial individual pager number desired from list below. ,
b. After answering message, enter the return phone number.  !

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3. Individual Information Name Title Pacer # Home Phone Donald Hoxie Director, DHE @ M Clough Toppan Manager, Radiation M 6M Control Program Patrick Dostie State Nuclear Safety Inspector Robert Schell Nuclear Engineering  %

specialist i Jay Hyland Assistant Engineer M M i

Linda Plusquellic Engineering Tech 4 N N D-9 MIPP Rev. 6

Proc. 2.05S Date 9/93  !

Rev. 3 ,

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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.

Thermoluminescent DosLmeters (TLDs) are used to provide a permanent record of worker exposure to gamma radiation. The TLD records total exposure from the time it is " zeroed" to the time it is read. Unlike the DRDs, the TLDs require a device commonly called a " reader" to provide a readout of the accumulated gamma exposure. TLD badges must be collected and taken to a lab to be read.

TLD badges must not be switched between workers. Once issued to an individual worker, the badge must be used only by that worker. ,

IV. Exposure Limits i

Exposure limits for field monitoring teams are expressed in terms of i exposure rate and cumulative exposure. The limits are: .

Turn back values: 1 R/hr exposure rate 3 R cumulative exposure ALARA value: 1 R cumulative exposure Turn back values are those levels of exposure at which the emergency  !

worker should leave the area immediately without consultation or direction.

NOTE: Life saving activities and activities which are required for the protection of public health and safety (e.g., manning a roadblock during evacuation of the public) should be continued regardless of turnback i values. Emergency workers involved in these activities should notify their supervisors and request inuw41 ate relief.

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ALARA values are intended to limit exposure to emergency workers. If greater than 1 R of cumulative exposure is observed, notify the Radiological Health Coordinator / Specialist.  ;

V. POTASSIUM IODTDE 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.

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Proc. 2.05S !

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NOTE: Administration of KI would not apply to personnel collecting samples in the ingestion exposure pathway beyond the plume exposure l pathway EPZ.  ;

The following criteria will be considered prior to an order for administration: ,

1. Following a known release, or if a release is Lmminent, of l radioactive gas of unknown composition (% radiciodides);
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.

Dosage will be as follows:  ;

1. 130 mg (one tablet) daily for a maximum of 10 days, unless otherwise -

recommended by the Director of the Bureau of Health.

CONTRAINDICATIONS: KI is contraindicated for individuals with known iodine allergies.

IF AN EMERGENCY WORKER REPORTS ANT SIDE EFFECTS OR REACTIONS FROM KI, INSTRUCT THE WORKER TO DISCONTINUE ITS USE AND TO i LEAVE THE AFTECTED AREA.

i V. INSTRUCTIONS FOR DISTRIBUTION A. Each designated Emergency Worker (Local and State Police, Sheriff's  :

Deputies, DOT workers, etc.) will be issued the following personnel dosimetry devices and information: ,

Item Ouantity TLD badge / card 1 High Range Dosimeter 1 Low Range Dosimeter 1 Individual Radiation Exposure 1 Card (white card) ,

Instructions to Emergency Workers 1 B. Sign-Out Procedure

1. Sign out the TLD badge / card
a. Using the " Personnel Dosimetry Log," enter the following information:

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Proc. 2.05S Date 9/93 Rev. 3

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 TL3 will record any exposure to gamma radiation even if covered by clothing.

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c. In no case should the TLD be used by or reissued to another person,
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.

2. Direct-Reading Dosimeters
a. One high and one low range DRD will be issued to each individual. These should be "zerced" by the individual worker I 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 worket thould be available so that a worker could be rotated out of th area.
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 D-13 MIPP Rev. 6

7 Proc.' 2.05S Date 9/93 Rev. 3

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.

DHE 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.
4. Emergency Workers may exceed the dose limits if required for lifesaving activity. The recommended limit for lifesaving activity is 25 R.

VI. COLLECTION At the end of each shift 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 Of fice (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-zeroed and reissued.

The next entry line on the exposure record should be lined out to indicate a " break" in the exposure history.

C. Personnel Donimetry 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.

The Personnel Dosimetry Log will be turned in to the Division of Health Engineering with the TLD cards.

D. Any exposures should be reported to the Maine Division of Health Engineering representative.

D-34 MIPP Rev. 6

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

  • I Proc. 2.05S

-Date 9/93 j Rev. 3 l b

l

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. -(
4. Do not permit anyone else to wear your dosimetry. ,
5. Complete all parts of your Individual Radiation Exposure Card except l columns for " final" readings.

t

6. Keep the Individual Radiation Exposure Card in your possession at all f t ime s .  ;

C. Radiation Exoosure Control

1. Unless otherwise directed, read your direct-reading dosimeter every 15 minutes and record the time and exposure on the Individual Radiation {

Exposure Card. [

2. If the reading on the 200 mR direct-reading dosimeter is greater than }

or equal to 100 mR (half-scale), notify your supervisor. Take all further readings on your 20 R direct-reading dosimeter.

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 and leave the immediate area. _,

f NOTE: Life saving activities and activities which are required for the protection of public health and safety (e.g. , manning a roadblock-during evacuation of the public) should be continued. In these cases,  ;

you should notify your supervisor and request immediate relief. ->

D. Termination of Assionment .i I

At the end of your assignment, report back to the location designated by 3 your supervisor. Record the final reading of your dosimeter on the ,

i Individual Radiation Exposure Card. Subtract the in111al 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 turnover;;and t

o report to the location designated by your supervisor.

l D-17 MIPP Rev. 6  !

h i

i Proc. 2.06S Date 9/93 Rev. 3 MONITORING AND DECONTAMINATION OF EMERGENCY WORKERS, EQUIPMENT AND VEHICLES I. Pu rpose To provide instruct: ions on the proper methods for monitoring and decontamination of emergency vehicles, personnel and equipment.

II. Discussion Monitoring and decontamination is the process of detecting and removing radioactive materials from persons or objects in order to minimize radiation exposure to individuals.

T The following equipment will be required:

1. Survey instruments: Survey meter (e.g., RM-14, E-140N) with GM pancake probe (e.g., HP-210)
2. Plastic bage
3. Signs, tape, rope
4. Towels
5. Cleaning agents (see Tables 1 and 2)

Monitoring and decontamination of vehicles, personnel and equipment will be conducted according to the procedures described in Section III. ,

vehicle and personnel monitoring will be conducted in the parking lot at the rear of the York County Courthouse, adjacent to the York County EOC, according to the layout depicted in Figure 1.  !

l I

i l D-20 MIPP Rev. 6

4 Proc. 2.06s ,

Date 9/93 j Rev. 3 ,

P III. Procedures A. Vehicle Decontamination .

Vehicles suspected of radioactive contamination should be surveyed using the specified survey instrument, or equivalent, and a pancake l' l probe. If readings in excess of 300 cpm 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  ;

parking;" if clean, it should be placed in an area designated as

" clean parking or can be used again." Figure 2 is a flow diagram of this process.  ;

In surveying the vehicle, special attention should be given to under sides of fenders, the radiator, the air filter, the tires and the door handles. 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 the vehicle does l not remove the contamination, it may be necessary to wash portions of the vehicle. l If a vehicle interior or exterior cannot be decontaminated to )

acceptable levels, the vehicle will be impounded for further i evaluation.

The occupants of the vehicle should then be surveyed and decontaminated, as 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 i Report Form. ,

)

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D-21 HIPP Rev. 6

+

i i

Proc. 2.06S Date 9/93 -

Rev. 3 l B. Personnel Decontamination Individuals who have been potentially contaminated must be surveyed.

A " hot line" should be established at a convenient location, so that- ,

contaminated individuals do not spread contamination. The hot line should be clearly identified through signs, tape and rope, and should i be staffed when field personnel are reporting.

Figure 4 is a flow diagram for personnel monitoring and l decontamination. Note that clean'and unclean areas must be established.

2 The individual responsible for actually monitoring the incoming workers must 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, j

2. Beginning at the head and without touching the person, survey the  ;

entire body including the soles of shoes. (See Figure S.) i

3. Hold probe on either side of the neck just below the ear and note any increase in reading.  ;

i l 4. A sustained reading of 300 epm on skin or clothing will be [

considered evidence of contamination.

i

5. Direct contaminated individuals to the decontamination area for washing.
6. Direct uncontaminated individuals to the record keeping area.

l Remove clothing with areas exceeding 300 epm 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." l i

Individuals with contamination on their skin snould remove the I contamination before crossing the " hot line." Table 1 lists the I procedures, in order of preference, for decontaminating skin and l clothing.  !

l l

D-22 MIPP Rev. 6 1

')

. . . . . , . . - ~ _

-)

e Proc. 2.06S I Date 9/93 [

Rev. 3 1 f

If an individual receives an exposure in excess of 5 R or if an i 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). i

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, " Management of Persons Accidently Contaminated with Radionuclides." -

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F t

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D-23 MIPP Rev. 6 l

l i

l Proc. 2.06S Date 9/93 Rev. 3 l C. Equipment Decontamination Equipment that is suspected of being contaminated, such as instrument probes used in the field, should be surveyed. If contamination is found, the equipment should be cleaned with an oil-impregnated rag

'(Masslinn type). The rgrsons 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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1 i

I D-24 HIPP Rev. 6 i

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1 i

4 Proc. 2.06S Date 9/93 l' Rev. 3 FIGURE 2 FIAMt DTanmW FUE l YERICLE DECONTAMIERTION i Access Road and Driveway  ;

I t vehicle Passengers scan Area If Clean l (<300 cpm) l l If Cont ==inated (>300 cpm) l Wash ,

Wash -

Area '

Water Rescan clean  ;

Area - If Clean Parking  ;

l (<300 cpe) i If St;11- Driver ,

l Con +==Insted (>300 cpm) l Personnel l Monitoring  !

Contaminated Driver Center l Parking Entrance i

1 i.

)

+

.6 i

f D-30 MIPP Rev. 6 I

t

+

-= --- .* ,

4 Proc. 2.06S Date 9/93 Rev. 3 FIGURE 3 VEHICLE MONITORING REPORT FORM 120K DATE VEHICLE AREAS TIME /DATE REGISTRATION CONTAMINATED INITIALS DECONTAMINATION INITIALS I

i t

i NOTE ,

Take all contamination surveys with beta window open.

Decontamination required when contamination levels are l greater than 300 cpm.

D-31 MIPP Rev. 6

- Proc. 2.06S !

Date 9/93 Rev. 3 FIGURE 4 FLOW DIAGRAK FOR PERSOmrRL MOKITORING AND DECO 3rTAKDULTION Bonnetary of

. Clean Area Entrance To j ,

Personnel l Monitoring l Center  !

I I

i i Initial l Scan If Clean l Area (<300 cpm)

I l  !

l If Contmainnted (>300 cpe) j Waste l

  • Storage For Sink And l Registration Contaminated shower If Clean And Dose l Clothing, Area (<300 cpm) Records Towels, Etc.  !

l l If Cont ==lnated (>300 cpm) [ Separate

! Exit .

Refer to l Followup l Program l l

1 Registration l And Dose l Records j i

Separate l Exit l clean potentially contaminated area ,

i i

I l

D-32 MIPP Rev. 6 i

j Proc. 2.06S 5 Date 9/93  ;

Rev. 3  ;

f FIGURE 6 .

FriiratieremY. pgCONTEMTERTION REPORT l I

I

~ peruc nuMean i am eomss m ,

TM AMfvED- ,

en swa y m gy l I

"****"' DECONTAaENATED BY; w ** BUPSUVSOR:

emceo mau SURVEY AND DECONTAMINATION INFORMATION CONTAMINATED a 300 CPM OR MIGHER -

f et ommeC r7EW CoM REMOVED 1 NAT. CAP Y H r v)

?.' /

COAT. JACKET Y N

(

  • SHIRT. BLOUSE Y N /e r i I TROUSERS. SLACKS UNDERCLOTHING Y N V N f.

g g

SOCKS, HOSE Y N ,l  ;

I SHOES, BOOTS Y N ,,

,4 N m** Y N t t

TMvRO D SCAN, CPM, RIGHT .LEFT:

y N

'f soor cow oscow, occoN t occON S COMMENT 5 .[

HEAD, NECK ,

SHOULDERS HANDS AND ARMS  :

chest, a ACK

,F LECS l

"" I DISPOSmON l

1. No Comammaton present, ressened to rogstration.
2. ComemLwoon toes unen 300 CPM, reseened to regteireuon. .

1 Decomammened to nees then 300 CPM, rWeemed to registrauorL ,

t

4. Comammenon gmmer than 300 CPM remems anor 3 anampts to cocomammme, Recented to regtetretton Hood for evemanon Dr4E FORM 900 i

D-34 MIPP Rev. 6  ;

i

4 Proc. 2.06S Date 9/93 Rev. 3 FIGURE 7 RADIOLOGICAL SCREENING PROGRAM - EXPOSURE EVAL *JATION 1

1. Names Age Address:

Home Phone Work Phone

2. Nearest Relative (alternative contact)

Names Address:

Home Phone '

Work Phone

3. Present Location (if different from 1 or 2)

Address:

Home Phone:

Work Phones Exposure Evaluation: Emergency Worker Narrative (include dates, times and activities) i Dose Assessment: By Date Dosimeter Readings:

Method (include instruments, analysis, computer model, etc.)

Determined Dose: Whole Bcdy: Rem EDE Specific organ Dose: Rem Rem Rem >

Rem Attach any supporting documents to this form l 1

i D-35 MIPP Rev. 6 1

. . . _ . . -_ . .. . m . _ _ _ . . . . - _- . . . _ . . . _

.h Proc. 2.12S j Date 9/93  ;

i Rev. 2 Locations for air sampling will be determined based on field radiation measurements or as recommended by Division of Health' Engineering (DHE) personnel and relayed through the Radiological Health coordinator  :[

(RHC).- [

Air sampling will be conducted according to the procedures described f in Section IV. )

III. Precautions A. Monitor your radiation exposure Read your direct reading dosimeters every 15 minutes.

Record the reading on your Individual Radiation Exposure i Record card. i If greater than 1 R of cumulative exposure is observed, s notify the Radiological Sampling Coordinator. -j 1 R/hr is the ' turn back' value. You should not enter or remain in areas with dose rates of 1 R/hr or greater.

i B. Use common sense and good radiation protection practices:

1. Minimize your time in the plume by:- l, Reviewing procedures and assigning tasks before entering the .[

f plume for air sampling.

I Do as much preparation outside of the plume as possible.

Get sample forms out and load filters into the' air sampler. .

Before entering the plume for sampling, determine which [

direction you will go to leave the plume. l I

C. Protect all survey instruments from becoming contaminstod.

D. Air filters may contain concentrated contamination. Use poly gloves and tweezers to handle the filters. .

E. Change gloves often to prevent cross-contamination. f F. Check equipment for contamination af ter each use. Use the maslin cloths and decontamination solution to clean equipment.

D-67 MIPP Rev. 6- i l

I i

_ . _ _ __m __ ._ __ _ _ _ . _ _ _

b d

Proc. 2.125 Date 9/93 l Rev. 2 l IV. Procedures A. Operational Checks - Radeco - Air Sampler I

1. Remove air sampling kits from storage and inventory the contents against the Air Sampling Equipment list in Proc. 2.11S, page D-43. Kits are stored at the York County Emergency Management f Agency, basement of the York County Court House,.

Alfred. ,

2. Drivers should check vehicles (e.g., oil, gas, e tires) while the assistant completes the air sampler-  ;

operability check, steps 3-10. [

CAUTION L ENSURE ENGINE IS RUNNING BEFORE CONNECTING AIR SAMPLER TO BATTERY.

3. Check that a filter is installed in the air {

sampler.

~;

4. Connect the ORANGE clamp from the air sampler t unit power cable to the positive (+) terminal  ;

of a 12-volt battery. )

5. Connect the BLACK clamp from the air sampler l unit power cable to a grounded part of the i chassis or engine block away from the battery. (

l 6. Turn on the unit.

7. Allow the rotameter to stabilize and observe a positive air flow indication. )

l 8. Turn off the unit.

r

9. Disconnect the air sampler unit power' cables ,

from the vehicle, grounded cable first.

l 10. Return f aulty equipment to the team organizer.

B. Air Sampling Location By Field Radiation Measurement NOTE: It should not be expected that, in traversing across the  ;

plume, a rapid increase and decrease in dose rate would be j observed. Rather, a long plateau region of gradually increasing, D-68 MIPP Rev. 6  ;

I

4 L

Proc. 2.12S >

Date 9/93 e Rev. 2 i L

steady, and then decreasi.ng rates are expected to be observed.

The sampling location should be chosen as the "best estimate" of the center of this dose rate plateau.

Exposure Rate for Plume Edges 1 mR/hr {

Exposure Rate for Sampling Location: 100 mR/hr  ;

r If the exposure rate does not exceed 100 mR/hr, collect air sample at the highest rate location.

t NOTE If high plume dose rates are expected, the air sampler filter holder should be loaded prior to entering the high dose rate areas.  ;

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 RO-2 and monitor dose rates.
2. If the RO-2 shows an increase in radiation levels, report readings to the York County EOC IMMEDIATELY.. 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 is 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 urive completely through the plume due to road access limitations, then proceed to Step 3.

3. Choose a sampling location that represents the center of a dose rate plateau across the plume or the highest reading ,

across the plume. Do not spend greater than 5 minutes locating a sampling location within a plume.

4. Immediately report the specific sampling location that has been chosen and the sample area done rates to the EOF and complete the steps in section D.

D-69 MIPP Rev. 6

P i

  • Proc. 2.12s Date 9/93 f Rev. 2  !

Y C. ' Recommended Sampling Points

l. The RHC.may direct the field team to & location most likely i to be passed over by a plume. Personnel should locate the location on the map, proceed to it, then collect an air sample as directed in Steps D-1 and D-10.

D. Air Sampling and Bota-Camma Survey  ;

-t NOTE I

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 i.

hood, then put on a fresh pair of gloves befose handling l filters. l o Ensure instrument probes do not become contaminated.  !

I o Use the RO-2 for area radiation surveys.

1. At each air semple location, take the following surveys  ;

using the RO-2 and report the dose rates IMMEDIATELY. Once reported, set up the air sampler. Record the highest dose i rate readings on the Field Radiological Survey Record (attached).  ;

i.

I NOTE i

I For direct radiation readings, the range should be selected to keep the needle in the area between 25% and 75% of the meter scale. j l

a. Honitor the radiation level at waist level using the l RO-2 with the beta window closed. j
b. Monitor the radiation level at waist level ur*ng the ~!

Ro-2 with the beta window open. P I

c. W,'th 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 D.lc with the beta window open.

i

2. Load the air sampler with both a particulate filter and-silver zeolite cartridge. Show the flow direction on tho' i D-70 MIPP Rev.'6 i f

i I

~?

+< g Proc. 2.12S Date 9/93 Rev. 2 i

side of the cartridge. Place particulate filter in the filter holder with fuzzy side out, j

3. Collect air samples in open areas away from trees,  !

buildings, etc. ,

i

4. Place the air sampler on the vehicle in a stable position (e.g., hood, fender, etc.) and on an uncontaminated surface.
  • The sampler should not be placed on the ground.
5. During wet weather, place the air sampler on the air cleaner .

of the vehicle when taking an air sample.

6. Clip the cables to the battery t'erminals of the vehicle, start air sampler, and record time started. [
7. Record the initial flow rate (should be about 2 cfm or I

57 1pm).

8. Run the air rampler until an approximate 15 ft3 (or 428 1) ,

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 backgrour.1 count (less than 300 cpm) far sample counting.

E. Sample Counting ,

1. Once outside the plume area, reconnect the air sampler to [

the 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 HD-210 probe with the window centered against the {

filter heiaer and count the filter. I

4. Record the results. i
5. Write the date, time, sample location, sampling time and flow rate (CFM) on the stickors provided in the kit. Attach .i '

a sticker to a plastic bag. Remove the retaining ring and, using tweezers, remove the filter from the head and place it ,

in the bag. )

i D-71 MIPP ' Rev. 6 l

_ .__ _ __ _ _ . . - _ . . - _.m .

I l

Proc. 2.12S 'l Date 9/93  !

Rev. 2

6. Remove the retaining ring which holds the cartridge in the  !

4 sample head.  :

i

" j The radioactive lodine resulta you obtain from the silver . -j zeolite count are very important in determining the protective actions that should be recommended for public protection. l These samples should be carefully handled, accurately analyzed I and promptly reported. .

i

?

7. Hold the HP-210 window centered within a half inch of the -

filter and count the cartridge. Record the results. >

8. Using gloves, remove the cartridge from the holder and place  !

it in a plastic bag. Attach a sticker (Step 5). l

9. Be certain that all filters and cartridges are properly f bagged, labeled, and set aside for analysis at the EOF.  !

i

10. Report the results to the York County EOC. Read the .;

information on the survey form exactly as written.  ;

f

11. Calculations of air activity will be done at the EOC. ,
12. If additional samples are requestad 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 l E.10. [

{

13. When directed, return to the York County EOC for monitoring.

l i

14. Before returning to the EOC, survey your vehicle and f

yourself for contamination and check your direct-reading '

dosimeters. If contamination is found, call the team i organizer.

f 3- 15. Unless otherwise instructed, return all samples to the York  !

County EOC. Turn in your Individual Radiation Exposure i Cards to the team organizer.

l

16. Await further assignments or,-if instructed, recheck your survey kit and prepare it for further use or return it to i storage.

t D-72 MIPP Rev. 6 t

-w . - - , . , . , - , ,

l Proc.2.12S l' Date 9/93 l Rev. 5 1 -

l FIELD RADIOLOGICAL SURVEY RECORD I

l Team Members: Date I

i 1

1 Action 1 2 3 4- 5 6 Current Time AM/PM-Waist Levels 3 Ft. - window closed, mR/hr Waist Level: 3 ft..- window open, mR/hr 2" above ground - window closed, mR/hr.

2' above ground - window open, mR/hr Air sample statt time.

Initial flow rate, CFM or LPM Final flow rate CFM or LPH Air sample stop time Total air sampling time A. Background count rate, CPM B. Silver Zeolite cartridge reading, CPM t

C. Particulate filter reading, CPM Net particulate count rate (C-A), CPM Net radiolodine count rate (B-A), CPM Wind direction-(if known)

Wind Speed (may be descriptive)

Approximate Location D-73 M1PP Rev. 6

Proc. 2.12S

, Date 9/93 I Rev. 2 l f

FIELD TEAM PLANT STATUS

SUMMARY

[

1. DATE TIME .  ;

TEAM MEMBERS: .

l f

  • t

(

ASSIGNMENTS:. .  !

\

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2. CLASSIFICATION LEVEL:

( ) UNUSUAL EVENT ( ) SITE AREA EMERGENCY 6

~!

( ) ALERT ( ) GENERAL EMERGENCY i

3. METEOROLOGICAL CONDITIONS:

Wind Speed oph.

Wind Direction FROM degrees.  ;

Stability Class .

Precipitation .

1

4. RADIOACTIVITY

( ) has been released. ( ) Airborne  ;

( ) has not been released. ( ) Wr.ter ,

t

( ) Surface spill i i

Time commenced: .

Relerse terminated: ( ) Yes ( ) No }

Time terminated: .

l Anticipated or known duration of release hours.  !

Projected dose rate and dose:  ;

i Arrival Dose Rate (Rem /hr) Integrated Dose (Rem)

Whole Body Thyroid Time Whole Body Thyroid Site Boundary j 2 miles .

5 miles l l 10 miles 1

D-74 MIPP Rev. 6 l

~

Pgoc. 3.12S ,

, Date 9/93  !

Rev. 2 (

AIR SAMPLING EQUIPMENT LIST ITEM QUANTIY ,

1. RADECO Air Sampler- 1  !
2. Particulate Filters (box) 1 ,

i

3. Sample Heads 2 -!
4. Silver Zeolite Cartridge 20 ~ f
5. Stop Watch 1 ,
6. Charcoal Cartridge (Training only) 10
7. Eberline E140N with HP-210 probe 1
8. Glassine Envelopes (1 pkg.) 1 i

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k D-75 MIPP Rev. 6 ,

_. ..#._. , - - - _ ,,y ,-. ,- , y -

=- -

1.

l

  • Proc. 2.20 .

Date 9/93-Rev. O RADIOLOGICAL SCREENING PROGRAM I

I. Pu rnose  !

i To provide guidance for the disposition and follow-up of radioactively l contaminated or exposed individuals. I II. Discussion Individuals may be exposed to radiation or become radioactively contaminated as the result of an accident involving nuclear materials '

or a nuclear power plant.- Disposition of individuals contaminated by or exposed to radioactive materials as the result of a power plant accident will be treated in accordance with federal guidelines.

The U. S. Nuclear Regulatory Commission directs that medical services be available for contaminated, injured individuals. Contaminated, injured individuals include those who have suffered a physical trauma and are radioactively contaminated and individuals who have received a {

dangerous exposure to ionizing radiation, such that prompt medical i treatment would be required. Individuals who may experience a lesser .

exposure may require medical follow-up and treatment, but not of the [

same immediate need as the previously cited cases.- For these ,

individuals, disposition will be determined on an ad hoc basis at the time of the accident.  ;

The following procedure provides instructions for implementing these r

guidelines.

i III. Procedure  ;

i A. Contaminated, Injured Individuals

=t Excepting minor injury or illness, contaminated, injured individuals  !

, will be taken to the designated primary hospital. The contamination  !

should not impede transport or necessary medical treatment to sustain  !

-life or limb. Individuals in this category may bypass reception'  ;

centers. Individuals ( , iginating at Reception Centers may also bypass ,

decontamination ef forth if those efforts will impede the prompt 4 transport and treatment of the individual, q

Additional hospitals which can accommodate a contaminated, injured  !

individual are listed in the State of Maine Radiological Incident  !

Plan, Vol. 1, Table 5-1.  !

I i

D-76 MIPP Rev. 6 i

6

+ i

o. Proc. 2.20 Date 9/93 Rev. O B. Individuals Exposed to High Levels of Radiation Individuals who have or are suspected to have received radiation doses or contamination equal to or exceeding the following guidelines will be referred for medical evaluation and treatment as soon as possible.

Whole Body (TEDE) 25 Rem c Thyroid (CDE) 125 Rem l

Skin Surface > 10,000 cpm on a CDV-700 or i Contamination or similar instrument l Precedence should be given those individuals with the highest exposures or those individuals exhibiting signs and symptoms of acute radiation syndrome.

C. Low Level Exposure

[

Generally, immediate medical evaluation or care will not be required for individuals receiving a low level radiation exposure, either by direct irradiation or contamination. ,

1. Total Effective Dose Equivalent (TEDE) < 2 5 Rem A TEDE below 25 rem is not expected to produce any outward symptoms of acute radiation syndrome; therefore, prompt medical care is generally not required. A medical evaluation will be performed to document the exposure and the individual's health at the time.

Implementation of an evaluation program for all individuals in this category will be coordinated through participating hospitals (Radiological Incident Plan, Vol. 1, Table 5-1).

A record will be established to document the individual's exposure history.

2. Skin Surf ace Contamination >1000 CPM & < 10,000 CPM and ,

Unremoved Contamination Surface contamination greater that 1000 cpm (CDV-700) is not ~t expected to require prompt medical evaluation or care. An evaluation will be performed to determine skin and whole  ;

body dose due to the surface contamination and to determine {

any uptake by the body. A whole body count will be used to determine uptake.

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' Proc. 2.20 Date 9/93 i Rev.'O Determination of skin dose will require that the radioactive isotopes be identified and that the contamination be  ;

quantified.

Assistance will be requested from local experts (radiation '

physicists), the federal government and the utility to' 1 perform this assessment.

t Implementation of an evaluetion program will be coordinated through participating hospitals and other agencies at the l time of the accident. .

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i D-78 MIPP Rev. 6  ;

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Proc. 2.20  ;

Date.9/93 Rev. O FIGURE 1 RADIOLOGICAL SCREENING PROGRAM - EXPOSURE EVALUATION

1. Names Age:

Address:

Home Phone:

Work Phones i

2. Nearest Relative (alternative contact)

Name:

Address:

Home Phone:

Work Phone:  :

3. Present Location (if different from 1 or 2) ,

Address:

Home Phone:

Work Phones Exposure Evaluation: Emergency Worker Narrative (include dates, times and activities) l 1

i Dose Assessment: By Date f Dosimeter Readings-I Method (include instruments, analysis, computer model, etc.) i i

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l Determined Dose Whole Body: Rem EDE Specific Organ: Dose: Rem Rem Rem-Rem Attach any supporting documents to this form 1

D-79 MIPP Rev. 6 i

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APPENDIX F STATE OF MAINE CHECKLIST PROCEDURES FOR THE t

INGESTION PATHWAY PIAN FOR SEABROOK STATION .2 i

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.f STATE OF MAINE CHECKLIST PROCEDURES FOR.THE INGESTION PATHWAY PLAN FOR SEABROOK STATION Number Rev. Procedure Title Page i

1 0 Radiological Health Coordinator at the State F-3 EOC - Check-Off List ,

2 0 Radiological Health Specialist at the State F-22 EOC - Check-Off List ,

! 3 1 Radiological Health Specialist at the .F-52 Seabrook Station IF0/ EOF - Check-Off List 4 0 Environmental Sampling Team Organizer - 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 i at the State EOC - Check-Off List 7 0 Division of Health Engineering Represer.tative F-59 .i at the State EOC - Check-Off List  ;

i 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  ;

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O Proc. 3 Date 9/93 Rev. 1 RADIOLOGICAL HEALTH SPECIALIST AT THE SEABROOK STATION IF0/ EOF CHECK-OFF LIST TIME INITIALS SITE AREA / GENERAL EMERGENCY

1. Receive direction from the Radiological Health Coordinator to report to the Seabrook Station IF0/ EOF.
2. Upon arrival at the Seabrook Station IF0/ EOF, call the State EOC.
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 Engineering field teams, j 5. Review data received from Massachusetts and State l of New Hampshire field teams. Review meteorology and projected deposition levels received from i Seabrook 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 conditions and projected actions that could affect the off-site safety and health.
8. Coordinate sample collection strategies and allocation of sample collection assistance l resources with the Seabrook ERO, Massachusetts, and the State of New Hampshire.
9. Participate in decision making for ingestion pathway protective actions.

F-52 MIPP Rev. 6