Text

Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures IP-1003 Re Obtaining Meteorological Data & IP-1011 Re Offsite Monitoring Team.One Oversize Drawing Encl.Aperture Card Available in PDR
	ML20040E055
Person / Time
Site:	Indian Point
Issue date:	01/18/1982
From:	; POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	;
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ML093450231	List: ML093450232; ML20040E055;
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	PROC-820118-01, NUDOCS 8202030045
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{{#Wiki_filter:POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN POINT NO. 3 NUCLEAR POWER PLANT ~ P. O. box 215 BUCH AN AN. N. Y.10511 TELEPHONES 914.739 8200 9 TO: NRC CONTROL COPY NO.: NRC FROM:, LINDA M. LOMONACO DATE: January 15, 1982

SUBJECT:

INDIAN POINT NO. 3 NUCLEAR PCWER PLANT EMERGENCY PLAN AND PROCEDURES DOCUMENT The enclosed sheets are the revised pages to your Emergency Plan (assigned controlled copy) Document. Please discard the old sheets, insert the attached sheets, initial and date this routing sheet and return it to the Radiological and Environmental Services Department; Attention: Linda M. Lomonaco Section Pages Date Initials Remove old and replace with: Table of Contents -- iii, iv 1& 2

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. Procedures Index.. ~ . QE{'..;,. .;_.y _ all 'IP-1001 m_. I 5.IP-1002 all .1 t I IP-1003 all IP-1004 all II-1005 all IP-1010 all IP-1011 all IP-1015 all CANCEL : IP-1016 CANCEL IP-1017 all I I l IP-1021 all 8202030045 820126 PDR ADOCK 05000286 F PDR

1 r-CONTOLLED COPY NO.: SECTION PAGES DATE INITIALS _ IP-1025 all IP-lO27 all IP-1030 all TP-1040 all IP-1041 all IP-1045 all IP-1047 all IP-lO50 all IP-1054 all IP-1056 all IP-1058 all IP-1060 all IP-1063 ,11 IP-1065 all IP-1085 all . s..,, 3, -

EMERGENCY PI.AN PROCEDURES TABLE OF CONTENTS Procedure # Procedure Title l IP-1001 Discussion of Determination of the-Magnitude of Release IP-1002 Determination of the Magnitude Release IP-1003 Obtaining Meteorological Data IP-1004 Midas Computer System, Dose Assessment Models IP-1005 . Planned Discharge of Containment Atmosphere During Accident Conditions Environmental Monitoring IP-1010 In-Plant / Site Perimeter Survey I l IP-1011 Offsite Monitoring Team IP-1015 Airborne Iodine-131 Determination using SAM-2/RD-22 or RM-14/HP-210 IP-1017 Recommendation of Protective Actions for Offsite Population IP-1018 Post Accident Environmental Sampling and Counting Personnel Injury s IP-1021 Radiological Medical Emergency (Containment Injured Individual) ~ Transport of Contaminated Injured Personnel Between IP-1022 Unit 3 and 1 Damage Assessment IP-1025 Repair and Corrective Action Teams IP-1027 Emergency Personnel Exposure Notification and Communication IP-1030 Emergency Notification and Communications and Staffing IP-1034 Notification and Recommendation to U.S.C.G. and Rail Roads IP-1038 Use of the Emergency Communications Systems (Initial Notification Fact Sheet, County Hot Line & NAWAS) lii

EMERGENCY PLAN PROCEDURES TABLE OF CONTENTS Procedure # Procedure Title Emergency Operation Facilities IP-1040 Habitability for the Emergency Facilities IP-1041 Personnel Monitoring Devices for EOF, TSC and OSC Personnel IP-1045 Technical Support Center IP-1047 Operations Support Center Accountability and Evacuation IP-1050 Accountability IP-1053 Evacuation of Site IP-1054 Search and Rescue Teams Non-Radiological Emergencies IP-1055 Fire Emergency IP-1056 Directing Fire Fighting Personnel in Controlled Area 3-1057 Tornado (Hurricane) Emergency 3-1058 Earthquake .P-1059 Air Raid Emergency HP Release Surveys and Decontamination IP-1060 Personnel Radiological Check and Decontamination IP-1063 Vehicle Radiological Check and Decontamination P-1065 Use of SAM-2/RD-22 to Determine Thyroid Burdens mergency Equipment and Maintenance IP-1070 Periodic Check of Emergency Preparedness Equipment IP-1075 Periodic Check of Indian Point Emergency Communication Equipment IP-1076 Beepers IP-1079 Issuance and Use of Radiological Equipment Stored in the Command Guard House Exercises, Drills and Training l IP-1080 Conduct of Emergency Drills IP-1085 Emergency Response Training o iv

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EMERGENCY PLAN PROCEDURES INDEX REV. 9 Procedure # Procedure Title Rev. # IP-1001 Discussion of Determination of the Magnitude of Release 2 IP-1002 Determination of the Magnitude Release 3 IP-1003 Obtaining Meteorological Data 2 IP-1004 Midas Computer System, Dose Assessmer,t Models 1 IP-1005 Planned Discharge of Containment Atmosphere During Accident Conditions 2 Environmental Monitoring IP-1010 In-Plant / Site Perimeter Survey 2 IP-1011 Offsite Monitoring Team 2 -IP-1015 Airborne Iodine-131 Determination using SAM-2/RD-22 or RM-14/HP-210 2 IP-1017 Recommendation of Protective Actions for Offsite Population 2 IP-1018 Post Accident Environmental Sampling and Counting 1 Personnel Injury IP-1021 Radiological Medical Emergency (Containment Injured li Indiv4.aal) 4 IP-1022 Transport of Contaminated Injured Personnel Between Unit 3 and 1 0 Damage Assessment IP-1025 Repair and Corrective Action Teams 2 IP-1027 Emergency Personnel Exposure 1 3 Notification and Communication lS IP-1030 Emergency Notification and Communications and Staffing 4 IP-1034 Notification and Recommendation to U.S.C.G. and Rail Roads 2 IP-1038 Use of the Emergency Communications Systems 2 (Initial Notification Fact Sheet, County Hot Line & NAWAS) i Procedure Index 9 Page 1 y -t ...--.m---r--- .- - e..,... : -- g--- r w.m.:_ - - l -r - m-q. ,.7 ~~:. --, -..,,

EMERGENCY PLAN PROCEDURES INDEX REV. 9 (PAGE 2) Procedure # Procedure Title Rev. # l l Emergency Operation Facilities IP-1040 Habitability for the Emergency Facilities 3 IP-1041 Personnel Monitoring Devices for EOF, TSC and OSC Personnel 3 IP-1045 Technical Support Center 3 IP-1047 Operations Support Center 3 Accountability and Evacuation IP-1050 Accountability 3 3 JP-1053 Evacuation of Site 1 [1 IP-1054 Search and Rescue Teams 1 Non-Radiological Emergencies IP-1055 Fire Emergency 1 IP-1056 Directing Fire Fighting Personnel in Controlled Area 1 1, 7 -1057 Tornado (Hurricane) Emergency 0 -1058 Earthquake 2 1, .i--1059 Air Raid Emergency 0 HP Release Surveys and Decontamination IP-1060 Personnel Radiological Check and Decontamination 2 IP-1063 Vehicle Radiological Check and Decontamination 2 IP-1065 Use of SAM-2/RD-22 to Determine Thyroid Burdens 1 i ergency Equipment and Maintenance IP-1070 Periodic Check of Emergency Preparedness Equipment-3 IP-1075 Periodic Check of Indian Point Emergency Communication Equipment 2 IP-1076 Beepers 3 IP-1079 Issuance and Use of Radiological Equipment Stored in the Command Guard House 1 Exercises, Drills and Training IP-1080 Conduct of Emergency Drills 2 IP-1085 Emergency Response Training 1 Procedure Index o Page 2 y-- g,, ~. m .r,- --, -, ~.,, n -- 7.-- e.---- --r,

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F POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN POINT NO. 3 NUCLEAR POWER PLANT P. O. 50X 215 8UCHAN AN N. Y,10511 TELEPMc 9 8200 EMERGENCY PLAN PROCEDUPIS r PROCEDUPI NO. IP-1001 REV. 2 TITLE: DISCUSSION OF TEE DEE PMINATION OF THE MAGNITUDF OF RELEASE emp REVIEWED BY: ,', /[# m-s# PORO REVIEW et CA~I /5/PL STE I[/ 3! APPROVED BY: W Q EFFEcT!vE DA I - \\ 1s 'a l / / /

IP-1001/2 IP-1001 DISCUSSION OF THE DETERMINATION OF THE MAGNITUDE OF RELEASE 1.0 NEED FOR EARLY ASSESSMENT In the event of an accidental release of radioactive material to the en-vironment, it is important for the Shift Supervisor to assess the accident as soon as possible and to determine the exposure to the off-site population. The exposure may be only to the whole body due to fields created by the noble gas cloud or it may include exposures to the thyroid from the radio-iodines when they are present. It is important to make this early assessment of potential exposure and have it available for the State and County Officials. This information will assist them in their decisions regarding protective actions for the public and in the most extreme case, to give guidance on the movement of the offsite population from the effected areas. This information will also be used by the onsite Emergency Director for establishing protective actions far onsite personnel. 2.0 TYPES OF ACCIDENTS Monitor Response a. LOCA with no core damage -R-10, spike response with rapid decrease reactor coolant system -R-13/R-14 shows increase only (RCS) activity only if VC isolation was not held -R-2/R-7 spike response with rapid decrease b. Clad failure - up to the entire -R-14 off scale if releasing gap activity could be released to -R-10 shows increase to 65 mR/hr VC (iodines and noble gases) -R-2/R-7 read high (long lived gases) -High Range Containment Monitor l2 reads high -VJ Iodine Monitor shows increase c. Fuel melt in addition to Clad -R-14 offseale due to high failure background through VC wall (iodines, noble gases, bromines -R-10 increase to 15 R/hr and o,ther moderately volatile -R-2/R-7 off scale nuclides; Sr-89, Ru-106, CS-137, -HighRangegentainmentMonitor Ce-144, Ba-140, Tellurium-132) reads up 10 R/hr -VC/ Plant Vent Iodine Monitors may show increase increase in direction of plume d. Fuel element damage in FSB -R-14 off scale due to high ("long-lived" isotopes, as in background through FSB wall clad failures, but on a smaller -Magnitude of release and scale) isotopic mix depend on decay time of fuel since its removal from the core -FSB/ Plant Vent Iodine Monitor may show increase -FSB APD shows increase Page 1 of 12

IP-1001/2 e. Gas release from tank rupture in -R-14 off scale PAB (gas decay tank, VCT CVCS tanks) -PAB APD may show increase f. fuel melt, containment integrity -R-14 off scale does not hold -R-10 off scale > 1000R/hr -HighRangeCongainmentMonitor reads up to 10 R/hr 7 3.0 RADIOLOGICAL ASSESSMENT 3.1 Approximate Time of Monitor Monitors and Surveys and Assessment Availability Immediate R-10 R-14 (low) 4 5.0 x 10 'uci/cc ~ APD's and Iodine Monitors High Range Containment Monitor l1 15 minutes stackmonitor (R-16 in PAB) 4 7.5 -+ 7.5x10 uCi/cc 20-30 minutes Ludlum gamma detectors in the environment 25 minutes plantveng(HPtechrgading) 1.0 x 10 -+ 3. 0 x 10 uCi/cc 30-45 minutes A (readings at site boundary 30-45 minutes isotope analysis (chem. sample of stack air) 1 1/2 hr. iodine sample in field 3.2 Initial Steps For Assessment (

Reference:

IP-1002) 1. R-14 on scale; estimate offsite dose from reading on R-14. a. Send chemist for sample of stack (normal) 2. R-14 off scale: a. Send HP Tech to plant vent to obtain uCi/cc and release rate per HPI-12.4. b. Send chemist for stack sample (emergency method, RS-CS-042), count total iodine first, then noble gases and particulates. c. Send HP to site boundary sample point. (IP-1010) d. Send offsite monitoring teams to do offsite surveys. (IP-10ll) c. Request Ludlum monitors results. (IP-1011) i 3. When chemist has results (2b) develop the ratio of Total Iodines to Noble Gas. (Total I ) NG Page 2 of 12

IP-1001/2 4.0 METHOD OF ASSESSMENT In order to determine what the actual or potential offsite exposure to the population is, it is necessary to evaluate the accident relative to the source term, release rate (actual or potential), meteorological conditions (wind speed, wind direction, and Pasquill Stability Category), concentration (noble gas and radiciodines) at the environmental point of interest (site boundary, etc.) and the relationship of the concentration to whole body and thyroid exposure in mrem./hr. These basic steps followed in IP-1002 to accomplish the radiological assessment are: a. Determine Release Rate o. Determine the Site Boundary Concentration c. Determine the Site Boundary Dose: Whole Body and Thyroid I d. Determine Point of Interest Dose: Whole Body and Thyroid NOTE: An estimate of tha duration of the release should be obtained from the Emergcccv Director. If unavailable use 4 hours as the first estimate. 1 5.0 10 MILE AREA AND SECTOR MAP The 10 mile area sector map is to be used in conjunction with the " Indian Point Station Radioactive Release Overlays". The maps center point is the Indian Point superheater stack, and it extends from there out to 10 miles. The map is radially sectioned off into 16 equal sections, each of 22 1/2. Each of the 16 sectors is further subdivided into 10 more sections by 1 through 10 mile concentric rings with the origin at the superheater stack. This results in a total of 160 " mile zone / sectors" which will be used when identifying areas for recommending protective actions. Within each sector are: Sites with dose integrating devices (TLD's) (located on the map a. by red dots). ~~ ~ b. Emergency sampling sites (located ~on the map by' yellow dots) t'hese are predetermined locations for the offsite monitoring teams to sample at. c. Fixed air sampling sites with continuously running samples (located on the map by green dots). Charcoal and millipore filters are changed weekly. d. Ludlum gamma dose rate instruments at police stations, fire-houses, etc; dose rates available by phone (IP-1011) (located on the map by black dots) Reuter Stokes instruments, gamma exposure, real time readings e. or accumulated dose. (located on the map by blue dots) 1 1 Page 3 of 12

IP-1001/2 6.0 OVERLAY DESCRIPTION 6.1 The diffusion overlays are in the file " Indian Point Station Radio-active Release Overlays", and were prepared for the Indian Point site using data collected from an NYU study which calculated dispersions patterns for the Indian Point area of the Hudson Valley. Indian Point is situated in an area which is significantly influenced by topo-graphic features which create a channeling effect for the air along the river valley with low wind speeds; the channeling effect is negated for high wind speeds. () 4m/sec) 6.2 The overlays have isopleths of normalized concentration Xu/Q, where Xu/Q is a relative measurement of how the plume is spreading in the horizontal and vertical directions with a given itmospheric stability. 3 X = concentration Ci/m or uCi/cc u = windspeed m/see Q = source strength (release rate) Ci/sec Normalized concentration means that the effects of windspeed and source strength have been assumed to be 1; to get an actual concentration, you must multiply Xu times 9 - X Q u 7.0 OVERI.AY PLACEMENT 7.1 Meteorological data: wind speed, wind direction, and the pasquill category is obtained from the Control Room meteorological display panel, or in backup methods as outlined in IP-1003. Using this data in conjunction with Figure 1, Flowchart for Overlay Section and Place-ment, the proper diffusion overlay can be found. Ex. 1. - windspeed 3m/sec, wind direction 110, Pasquill C: Overlay is yellow C. Ex. 2. - windspeed Sm/sec, wind direction 200, Pasquill B: Overlay is red B. 7.2 The position of this overlay is described here as well as in Figure 1. 1. For downvalley flow (blue) or upvalley flow (yellow), allign the E-W, N-S positions parallel to those on the map orientation point. Downvalley (blue) overlay should be placed so as the plume a. is traveling south, b. Upvalley (yellow) overlays should be placed so as the plume is traveling north. 2. For crossvalley flow (red), align the overlay origin so that the plume is traveling in the direction of the wind. The placement of the overlay on the 10 mile area map, a.) indicates the plume travel direction; b.) normalized concentrations Xu/Q, within the area of the plume. Page 4 of 12

IP-1001/1 FIGUPI 1 READ METEOROLOGICAL DISPLAY PANEL PICORD WIND DIRECTION RECORD WIND SPEED RECORD PASQUILL CATEGORY WIND SPEED 6 4 m/s WIND SPEED > 4 m/s WIND DIRECTION 339 210 209 l l USE BLUE USE YELLOW USE RED DOWINALLEY UPVALLEY CROSSVALLEY OVERLAY CTIERLAY OVERLAY GROUND OR ELEV. GROUND OR ELEV. GROUND OR ELEV. (Plume Travels in the (Plume Directed ~ South) (Plume Directed ~ North) Direction of the Wind) Place overlay over Place overlay over Center over plant plant orientation point plant orientation point orientation point with i Align E-W & N-S lines Align E-W & N-S lines plume centerline aligned Parallel to those on along wind direction. parallel to those on th e map. Plume will follow the map. Plume will valley contours. fellew valley cente m, 5 of 12

IP-1001/2 l NOTE: Wind direction is always from (180 = wind from the south). 7.3 Table 1, IP-1002 has been compiled in a similar way as the diffusion curves. Using site meteorology, the user is able to determine the dispersion factor (Xu/Q) for the site boundary. This table acts in place of choosing the site boundary location from the 10 mile area sector map and picking the dispersion factor off the overlay. Table I will also give guidance to the Emergency Director as to where to deploy the onsite monitoring teams. 8.0 DOSE ASSESSMENT This section briefly outlines radiological dose assessment: the onsite and offsite field surveys and how to use their results in determining the projected dose to onsite and offsite individuals. 8.1 Gamma Assessment ( I) (Whole Body exposure) Gamma measurements are indicative of whole body exposures received from a radiological release. 8.1.1 Using gamma survey instruments: a. Portable gamma instrumentation: I 3'mR/hr will give the Whole Body exposure rate at the survey location. Multiplying mR/hr by the duration of stay will give the Whole Body exposure in mR. b. Ludlum monitors: (IP-10ll) ./ Gamma readout is in mR/hr. Multiplying 2 mR/hr by i the duration of stay will give the Whole Body exposure in mR. c. Reuter Stokes I'R/hr by the Gamma readout .s in mR/hr. Multiplying m duration of stay will give the whole body exposure in mR. i 8.1.2 TLD Sites Within the 5 mile radius surrounding the Indian Point site there ate IP designated TLD Sites which integrate (' dose, and these are changed monthly. In the event of an radiological accident these must be collected and sent for processing. TLD's may provide estimates of whole body exposure. Page 6 of 12

IP-1001/2 8.1.3 Whole Body exposure guidelines as per EPA PAG's are: Projected Dose (Rem) to Recommended Actions the Population Whole Body 4 1 . No protective action required . State may issue an advisory to seek shelter and await further instructions or to voluntarily evacuate. . Monitor environmental radiation levels. ,Whole Body 1 to < 5 . Seek shelter and wait further instructions . Consider evacuation particularly for children and pregnant women . Monitor environmental radiation

levels, l

. Control Access. Whole Body > 5 and above . Conduct mandatory evacuation of populations in the predetermined area . Monitor environmental radiation levels and adjust area for mandatory evacuation based on these levels. . Control Access. l i i I l 6 i Page 7 of 12

IP-1001/2 8.2 Beta Assessment ( /3) Beta surveys are helpful in assessing the location of the plume or plume deposition. If you are in the plume, a f3 - J' survey instrument will indicate a significant jG reading; however, if you were not in the plume or near a contaminated surface the beta reading will be low or nil. (Beta's are short range emmitting particles (several meters in air)) 8.2.1 Beta gamma readings taken in the environment may be affected by various sources. The following table describes the effects on the open window / closed window (OW/CW) ratio when using a beta gamma survey instrument (e.g. R0-2, E-530) Sources of Radiation OW/CW ratio (675'/ 6')*

a. Contained source of activity 1.0 or slightly greater (e.g. radioactive gases in V.C.)

than 1.0

b. Plume (reading taken near plume 1.0 or slightly greater but not in plume) than 1.0

c. Plume (Reading taken in plume) at least 2.0

d. Deposition on ground from

- Near ground, at least 2.0 particulates in plume - Above ground, instrument pointed upward, ratio lower that at ground level. The ratios given above are approximate and can be affected by a combination of sources. 8.2.2 Protective actions for beta exposure would be to remove persons from the plume by sheltering or evacuation. Sheltering is effective because beta particles are not penetrating and will not travel through walls. Page 8 of 12

IP-1001/2 8.3 Iodine Assessment Radioiodines released as a result of a radiological emergency are thyroid " seekers". These iodines whether ingested or breathed travel to the thyroid gland and remain there as any other iodine would. The radioactive properties of the radioiodines would cause damage to the thyroid gland. As the mass of the thyroid decreases, the doses from radioactive iodine increase. Consequently for infant or child thyroid the dose is greater than would be for an adult breathing the same air. It is for,this reason that the child becomes the limiting case, and protective actions for the general population are determined from child thyroid doses. Taking breathing rates into consideration it is estimated the child thyroid dose from inhalation is greater than the adult dose by a factor of two. 8.3.1 Field Samples: (CR, TSC, EOF, Site Boundary, Fixed and emergency offsite monitoring locations and/or requested locations both in plant and offsite) a) Charcoal and millipore filters or silver zeolite cartridges analyzed by the SAM-2 to determine I-131 activity (uCi/ce) I-131 (uci/ce) X 1.6 X 109 = child thyroid dose rate (mR/hr breathed) I b) Concentrations taken in Field using an HP-210 probe j (counts total Iodines) Concentration x DCF = Dose rate child thyroid uCih u_Ci x mrem C cc hr l _, _ _ ce l j. NOTE: multiplying the child thyroid dose rate by hours breatned will give the Iodine dose received to the child thyroid. NOTE: Dose Conversion Factors (DCF) can be found in Table 3 c of IP-1002 j 8.3.2 Gamma Dose Rate to Thyroid Dose Coversion The gamma dose rate (mR/hr) can be used to make an initial estimate of thyroid dose rate due to radiciodines (this method can be used prior to the counting of iodine sampling filters) a. Assuming on (Total I/NG) ratio of 10 : '[ mR/hr x.15 = Child thyroid dose rate (mR/hr breathed) Page 9 of 12

IP-1001/2 b. If an actual (Total I/NG) ratio is available the thyroid dose rate would be calculated using the following equation: actual (Total I/NG) ratio x.15 x OImR/hr = mR/hr breathed 10-4 child thyroid Multiplying the thyroid dose rate obtained in a or b by the actual hours breathed will give an estimated iodine received to the child thyroid. 8.3.3 Thyroid exposure guidelines as per EPA PAG's: Projected Thyroid Dose Recommended Actions (Rem) to the Population Thyroid (5 No protective action required State may issue an advisory to seek shelter and await further instructions or to voluntarily evacuate. Monitor environmental radiation levels. Consider issuance of KI to workers if 1 rem Thyroid < 5 to ( 25 Seek shelter and wait further instructions . Consider evacuation particularly for children and pregnant women Monitor environmental radiation levels. Control access. Issue KI to workers l Thyroid = 25 and above Conduct mandatory evacuation of populations in the predetermined area. Monitor environmental radiation levels and adjust area for mandatory evacuation based on these levels. Control access. Issue KI to workers. The recommendations above should be token only if there is a good probability of preventing a substantial portion of the l projected dose. For example, evacuation would probably not be recommended for a projected thyroid dose of <,25 Rem for a puf f (short-term) release. i { l 1. Page 10 of 12

IP-1001/2 9.0 THYROID BLOCKING USING POTASSIUM IODIDE (KI) The National Council on Radiation Protection and Measurements (NCRP) in Report No. 65 recommends that " individuals who have had an accidental occupational exposure to radioiodine, regardless of the route of exposure should immediately be given a 300 mg potassium iodide or sodium iodide tablet. Daily administration of 300 mg potassium iodide tablet should be continued for 7 to 14 days. The purpose of using potassium iodide (KI) is to saturate the thyroid gland with stable iodine so the radioactive iodine will be " blocked". Studies indicate that iodine has approximately a 6 hour half time of uptake, so the stable KI can be given up to several hours after exposure to radioiodine and it will still have some thyroid blocking effect. Preferably, KI should be given prior to exposure to radioiodine. 9.1 When an indication arises that workers will potentially receive a thyroid dose due to radiciodine exposure of 5 Rem or greater, the Emergency Director or appropriate designee shall authorize the issue of KI to those workers. Consideration should be given to issninee of KI at lower projected doses. (about 1 Remthyroid). 9.2 KI is located in the emergency lockers of the Control Room, Technical Support Center, Operations Support Center, Emergency Operation Facility and the Alternate Emergency Operation f'acility. Emergency Directors I have been issued bottles of KI, and there is a well stocked supply 4 of KI at the Con Ed Service Center building. ~ 9.3 The following page is the insert as well as new instructions for KI at Indian Point. 9.4 Instructions for use, as recommended by the NCRP are: Take 2 tablets per day for 7 to 14 days. 10.0 SITE PROTECTIVE ACTIONS For a Site Area or General Emergency sheltering for site personnel is accomplished by assembly in designated areas. For releases with iodine doses to the site population issuance of potassium iodide maybe considered. (Sheltering would also reduce the dose received from radioiodines). For a General Emergency with radiological consequences issuance of KI to site personnel should be considered. The decision to evacuate the site should be based on the estimated or actual release time, expected outdoors exposures and weighed against the fact that evacuation may cause more harm by personnel being outside as well as the confusion of an evacuation rather than to remain indoors with proper sheltering. Pace 11 of 12

IP-1001/1 Patient Package insert For HOW POTASSIUM IODIDE WORKS Certam forms of iodine help your thyroid gland work right, hiost people get the iodine they teed from foods like iodized salt or fish. The thyroid can " store" or hold only a certain amount of THYRO BLOCK" iodia*- In a radiation emergency. radioactive iodine rney be released in (POTAS$1UM IODIDE) the air. This material may be breathed or swallowed. It may (pronounced ooe-TASS +vm EYEch.oyed) enter the thyroid gland and damage it. The damage would pro-(abbreviated: KI) bably not show itself for years. Children are most likely to have TABLETS and SOLUTION U.S.P. thyroid damage. If you take potassium iodide. It will fill-up your thyroid gland. This reduces the chance that harmful radioactive iodme will enter the thyroid gland. TAKE POTASSIUM IODIDE ONLY WHEN PUBLIC HEALTH OFFICIALS TELL YOU. IN A RADIATION WHO SHOULD NOT TAKE POTASSIUM IODIDE EhtERGENCY. RADIOACTIVE IODINE COULD BE The only people who should not take potassium iodide are people RELEASED INTO THE AIR. POTASSIUh1 IODIDE (A FORht OF IODINE) CAN HELP PROTECT YOU. who know they are allergic to iodide. You may take potassium iodide even if you are taking medicines for a thyroid problem (for example, a thyroid hormone or antithyroid drugt. Pregnant and IF YOU ARE TOLD TO TAKE THIS 51EDICINE.TAKE IT nursing women and babies and children may also take this drug. ONE TIhtE EVERY 24 HOURS. DO NOT TAKE IT 510RE OFTEN. htORE WILL NOT HELP YOU AND h!AY IN-HOW AND WHEN TO TAKE POTASSIUM IODIDE CREASE THE RISK OF SIDE EFFECTS. DO NOT TAKE Potassium Iodide should be taken as soon as possible a(ter THIS DRUG IF YOU KNOW YOU ARE ALLERGIC TO public health officials tell you. You should take one dose every 24 IODIDE. (SEE SIDE EFFECTS BELOW.) hours. 51 ore will not help you because the thyroid can " hold" on-ly limited amounts of iodine. Larger doses will increase the risk of side effects. You will probably be told not to take the drug for more than 10 days. INDICATIONS SIDE EFFECTS THYROID BLOCKING IN A RADIATION Eh!ERGENCY Usually, side effects of potassium iodide happen when people ONLY. take higher doses for a long time. You should be careful not to take more than the recommended dose or take it for longer than DIRECTIONS FOR USE you are to'1 Side effects are unlikely because of the low dose and Use only as directed by State or local public health authorities in the short time you will be taking the drug. the event of a ramtion emergency. Possible side effects include skin rashes. swelling of the salivary DOSE glands, and " iodism"(metallic tsste. burning mouth and throat, sore teeth and gums. symptoms of a head cold, and sometimes stomach upset and diarrhea). A few people have an allergic reaction with more serious symp-coms. These could be fever and joint pains. or swelling of parts of the face and body and at times severe shortness of breath requir-DOSAGE: TWO (2) TABLETS ing immediate medical attention. DAILY FOR SEVEN (7) TO Taking iodide may rarely cause overactivity of the thyroid FOURTEEM (14) DAYS. gland. underactivity of the thyroid gland. or enlargement of the thyroid gland tgoiter). WHAT TO DO IF SIDE EFFECTS OCCUR If the side effecta are severe or if you have an allergic reaction, stop taking potassium lodide. Then, if possible call a doctor or Store at controlled room temperature between 15* and 30*C 159' to 86*F). Keep container tightly closed and protect from light. HOW SUPPLIED Do not use the solution if it appears brownish in the nor.zle of the THYRO-BLOCKTM TABLETS (Potassium lodide. U.S.PJ bot-bottle. ties of 14 tablets (NDC 0037 0472 20J Each white, round, scored tablet contains 130 mg potassium iodide. WARNING Potassium iodide should not be used by people allergic to iodidr. Keep out of the reach of children. In case of overdose or. allergic maction, contact a physician or the public health authority. DESCRIPTION Each THYRO BLOCKTM TABLET contains 130 ccg of potassium iodide. Pace 12 of 12

POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN POINT NO. 3 NUCLEAR POWER PLANT P. O. BOX 215 BUCH ANAN, N. Y.10511 TsLerwoNC 914 739 8200 EMERGENCY PLAN PROCEDURES PRDCEDUPI NO. IP-1002 REV. 3 f TITLE: DETERMINATION OF MAGNITUDE OF RELEASE G REVIEWED sY d : G i,- / PORC REVIEW A p/ , DATE ///'/?I-APPROVED BY: DATE p /o /T1 () EFFECTIVE DA7E I-\\9-91 l l

IP-1002/3 l l IP-1002 DETERMINATION OF MAGNITUDE Ci REI. EASE l

1.0 INTENT

To describe various methods of estimating the whole lody doce due to radioactive noble gas and the thyroid dose due to radioactive Iodine for the off-site population.

2.0 DISCUSSION

At this time there are two methods for estimating offsite do.se. The Primary method is to use the readings directly from the plant vent monitors R-14 or RM-16 high range plant vent monitor or to monitor the f plant vent directly using a Teletector of other suitable radiation detection equipment. The secondary method involves the offsite sampling team who will take air samples at locations under the plume. Knowing the release rate, the sample readings and the concentration of nuclides in the release, the dose rate can be determined. For the same iodine concentration a child receives twice the dose that an adult receives, therfore, the child is used as the limiting case and all offsite estimates are calculated for the child. Inside the site boundary the adult dose should be used. This is done by dividing the child dose by 2. (Flow chart values are the dose for the child and it is this thyroid dose which is divided by 2.) Using the meteorological conditions along with the concentration, the dose rate can be calculated for any point, specifically for the site boundary and 2, 5, and 10 miles out from the plant in the area under the plume. 3.0 PROCEDURE 3.1 Follow the flow chart, EP-Form #1 keeping in mind the basic l' steps: 1. determine the release rate 2. determine the site boundary concentration 3. determine the site boundary dose 4. determine the point of interest dose 3.2 Use graphs and tables on pages 4 & 5 in conjunction with the flow chart, EP-Form #1 as well as IP-1001, section 7 & (Figure 1) on the choice and placement of the meteorological overlays to determine the site boundary dose projections and the point of interest dose projections. 3.3 Along with these calculations, a) The on site monitoring team is to be sent to the site boundary (IP-1010) for actual radiological readings. b) The offsite team is to be called in and sent to areas the plume is expected to pass over. (The overlays are to be used as guidance for plume path and IP-1011 as guidance for the offsite team). Page of 7

[ IP-1002/3 c) The chem tech. shall be directed to take a sample of the activity in the Plant Vent if the radiological conditions prove safe to do so. The chemist should be instructed to remove and count the normal weekly iodine plant charcoal cartridge. (Will determine how much iodine has been released) NOTE: Total Iodines 3 Sample the Noble Gases currently in the Plant Vent by taking a gaseous Marinelli sample. (Until the chem sample is obtained and analysed a total Iodine 4 to Noble gas ratio of 10 is assumed. This may prove to be overly conservative, or an underestimate, all dependent i on plant conditions. Therefore it is necessary to have a chem sample as soon as possible and use the new value-(Total I/NG) in the dose projection calculations when making any~ decisions on' protective actions.) 3 If initial dose projections are done using the estimated (Total I/NG) ratio of 10 one should state to offsite authorities.it is only a rough estimate, ?nd we will be providing more ac urate information by direct' sampling shortly. This should be conside red when taking or recommending protective actions based on project ed thyroid exposure. f 3.4 When an actual chemistry sample is available, the dose projections are i corrected by the following: (Total I/NG) chem samole X estimated Iodine = corrected Iodine 10 dose dose 3.5 An estimate of the duration of the release should be obtained from the Emergency Director. If it is unknown use 4 hours as a first estimate. 3 3.6 Implementation Procedure IP-1017 offers assistance on the i recommendations which can be made to offsite authorities regarding offsite protective actions for the public. 3.7 Table 3, includes the projected thyroid dose as a function of the individual iodine isotopes concentrations in air and the projected exposure time. This can be used to more exactly corvert radiciodine concentration field measurement to exposure if the isotopic mix is known. 3 i i Pace 2 of 7

IP-1002/3 3.8 If on or off-site sampling teams have reported a gamma (8) mR/hr reading an initial estimate of thyroid exposure can be obtained by multiplying the gamma dose rate (mR/hr) by.15. gamma thyroid dose rate dose rate Multiplying the thyroid dose rate by hours breathed will give you the approximate iodine dose to an individual at that location. NOTE: The direct gamma (Y) reading (mR/hr) is primarily the dose rate from the Noble Gases in the plume. Page 3 of 7

4 i DOCUV ENT PAGE 3J _ _E J AN O.,nozo8oovr NO. OF PAGES REASON O PAGE ILLEGIBl. O HARD COPY FILED AT. PDR CF OTHER 1 3 O SETTER con esoVESTED ON _ 'g100 LARGE TO RLM.- -., - c V OTHER FILMED ON APERTURE CARD NO RO

5 IP-1002/3 4- ~ TABLE 1 CONVERSION FACTORS uCi/cc i mR/hr Column A Column B Column C f Time Post RM-16 High Range Contact With 6 Ft. From Release Plant Vent Monitor Plant Vent Plant Vent

~

0-2 hr. 0.487 6 x 10 2.5 x 10 ~3 -3 2-4 hr. 0.830 1.2 x'10 3.8 x 10 ~3 ~3 4-6 hr. 1.2 1.6 x 10 5.5 x 10 -3 ~3 6-12 1.95 2.8 x 10 9.5 x 10 -3 -2 l 12 hrs.-24 hrs. 3.5 5.5 x 10 1.6 x 10 -3 -2 24 hrs.-2 wks. 4.7 6.5 x 10 2.0 x 10 -3 -2 ( 2 weeks 5.3 7.3 x 10 2.3 x 10 i 1 3 Page 5 of 7

IP-1002/3 l THE 1 SITE BOUNDARY ISOPLETH VALUES BY WIND DIRECTION AND PASQUILL STABILITY CATEGORY Pasquill A B C D E F G Wind Boundary Direction Sample Boundary Boundary Boundary Boundary Boundary Boundary Boundary (from)* Point X u/Q X u/Q X u/Q X u/Q X u/Q X n/Q X u/Q 0 10 --c> 12 2.2 E-6 3.4 E-6 2.8 E-5 1.7 E-4 1.2 E-4 4.0 E-4 1.2 E-3 10 12 --c> 13 2.1 E-6 2.7 E-6 2.5 E-5 8.5 E-5 1.0 E-4 3.6 E-4 1.1 E-3 20 13 --C> 14 2.2 E-6 3.4 E-6 2.8 E-5 1.7 E-4 1.2 E-4 4.0 E-4 1.2 E-3 30 14 --C> 17 5.8 E-6 7.4 E-6 6.1 E-5 1.8 E-5 2.3 E-4 7.6 E-4 2.3 E-3 P 40 18 1.3 E-5 1.6 E-5 1.1 E-4 3.9 E-4 4.4 E-4 1.5 E-3 4.5 E-3 50 18 --C 19 1.5 E-5 1.8 E-5 1.3 E-4 4.3 E-4 4.8 E-4 1.6 E-3 4.8 E-3 60 19 1.8 E-5 2.1 E-5 1.5 E-5 5.1 E-4 5.3 E-4 1.8 E-3 5.4 E-3 70 19 --c> 20 3.1 E-5 3.5 E-5 2.5 E-4 7.5 E-4 8.0 E-4 2.9 E-3 8.7 E-3 80 20 -C 21 5.7 E-5 6.2 E-5 4.0 E-4 1.1 E-3 1.3 E-3 4.8 E-3 1.4 E-2 90 21 8.0 E-5 8.5 E-5 5.1 E-4 1.5 E-3 1.8 E-3 6.3 E-3 1.9 E-2 100 21 9.7 E-5 1.0 E-4 6.0 E-4 1.7 E-3 2.1 E-3 7.4 E-3 2.2 E-2 110 22 1.1 E-4 1.1 E-4 6.5 E-4 1.9 E-3 2.3 E-3 8.0 E-3 2.4 E-2 120 22 1.4 E-4 1.4 E-4 8.0 E-4 2.3 E-3 2.8 E-3 9.9 E-3 3.0 E-2 130 22 1.4 E-4 1.4 E-4 8.0 E-4 2.3 E-3 2.8 E-3 9.9 E-3 3.0 E-2 140 22 1.4 E-4 1.4 E-4 8.0 E-4 2.3 E-3 2.8 E-3 9.9 E-3 3.0 E-2 150 22 1.0 E-4 1.1 E-4 6.3 E-4 1.8 E-3 2.2 E-3 7.8 E-3 2.3 E-2 160 22 8.6 E-5 9.2 E-5 5.5 E-4 1.6 E-3 1.9 E-3 6.7 E-3 2.0 E-2 170 Water 9.0 E-5 9.5 E-5 5.6 E-4 1.6 E-3 2.0 E-3 6.9 E-3 2.1 E-2 180 Water 6.0 E-5 6.5 E-5 4.1 E-4 1.2 E-3 1.4 E-3 5.0 E-3 1.5 E-2 190 Water 3.6 E-5 4.0 E-5 2.8 E-4 8.1 E-4 9.0 E-4 3.3 E-3 1.0 E-2 200 Water 2.0 E-6 2.4 E-6

1. 8 E-4 5.8 E-4 5.8 E-4 2.0 E-3 6.0 E-3 210 Water 9.4 E-6 1.2 E-5 8.4 E-5 2.8 E-4 3.3 E-4 1.1 E-3 3.3 E-3 220 Water 5.4 E-6 7.0 E-6 5.8 E-5 1.8 E-4 2.2 E-4 7.3 E-4 2.2 E-3 230 1

5.0 E-6 6.4 E-6 5.4 E-5 1.7 E-4 2.1 E-4 6.8 E-4 7.0 E-3 240 1 --C> 2 5.9 E-6 7.4 E-6 6.2 E-5 1.8 E-4 2.3 E-4 7.7 E-4 2.3 E-3 250 2 --C> 3 6.5 E-6 8.3 E-6 6.6 E-5 2.0 E-4 2.5 E-4 8.3 E-4 2.5 E-3 260 3 --c, 4 5.1 E-6 6.6 E-6 5.5 E-5 1.7 E-4 2.1 E-4 7.0 E-4 2.1 E-3 270 4 --c> 5 5.7 E-6 7.3 E-6 6.0 E-5 1.8 E-4 2.3 E-4 7.6 E-4 2.3 E-3 280 5 7.5 E-6 9.7 E-6 7.2 E-5 2.3 E-4 2.8 E-4 9.2 E-4 2.8 E-3 290 5 --c> 6 8.6 E-6 1.1 E-5 7.8 E-5 2.( E-4 3.1 E-4 1.0 E-3 3.0 E-3 300 6 9.6 E-6 1.2 E-5 8.6 E-5 2.9 E-4 3.4 E-4 1.1 E-3 3.3 E-3 310 6 --c-7 9.6 E-6 1.2 E-5 8.6 E-5 2.9 E-4 3.4 E-4 1.1 E-3 3.3 E-3 320 7 8.9 E-6 1.2 E-5 8.1 E-5 2.7 E-4 3.2 E-4 1.1 E-3 3.3 E-3 330 7 -c> 8 7.5 E-6 1.0 E-5 7.4 E-5 2.4 E-4 2.9 E-4 9.6 E-4 2.9 E-3 340 8 --c> 9 6.1 E-6 7.7 E-6 6.3 E-5 1.9 E-4 2.4 E-4 7.9 E-4 2.4 E-3 350 9 -c> 10 4.5 E-6 5.9 E-6 5.0 E-5 1.6 E-4 1.9 E-4 6.3 E-4 1.9 E-3

The wind direction is + 5 of table value (i.e.: 5 15 )

Pace 6 of 7 _-____-____________-__-_____-_-___a

IP-1002/3 TABLE 3 TOTAL INHALATION DOSE CONVERSION FACTORS L. P DOSE CONVERSION FACTOR 1 i mrem / g _ ISOTOPES hr ce 9 l I-131 1.6 x 10 7 1-132 7.9 x 10 I 8 I-133 5.4 x 10 1 7 l I-134 4.0 x 10 f 8 I-135 1.6 x 10 Iodine Mix 6.7 x 10 l' (post accident) i i i NOTE: If the Iodine mix is not known and it is within 24 hours of shutdgwn, 1 use the Post Accident Iodine Mix dose conversion factor (6.7 x 10 ). After 24 hours, use the I-131 dose conversion factor.

Concentration x Dose Conversion Factor = Dose Rate i

r (uCi/cc) x mrem / uCi = mrem /hr hr cc i

Concentration can be determined by calculation or by field samples.

i 1 l Field Samples: SAM use I-131 DCT (1.6 x 10') 8 EP-210 use Iodine Mix DCF (6.7 x 10 ) . 3 l. 4 } j I i i l l Page 7 of 7

POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN PotNT NO. 3 NUCLEAR POWER PLANT P. C. SCX 213 BUCH AN AN. N. Y.10S11 TELA pwoN E: $147394100 EMERGENCY PLAN PROCEDUPIS 2 i PROCEDUPI NO. IP. 1003

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IP-1003/2 IP-1003 OBTAINING METEOROLOGICAL DATA 1.0 INTENT This procedure describes the available means to obtain meteorological i data for IP-3. 2.0 DISCUSSION Meteorological data is necessary in determining the impact of accidental or planned releases to the environment. There are several methods to obtain the required meteorological data at the IP-3 site. This procedure states the primary methods and subsequent backup methods to obtain meteorological data. 1) Control Room Digital Display of Meteorological Parameters. 2) Telephone Data line direct to towers using ASKII terminal in the Control Room. (The same information can be obtained by going to the tower locations directly: 122m or 10m) 3) Telephone Data line to MIDAS using the ASCII rerminal in the Control Room. 4) 122m Meteorological Tower, existing instruments. 5) 122m Meteorological Tower, Portable Wind Instruments & Emergency Wind Set. There are two meteorological towers and systems on the Indian Point site. The primary tower is.a 122 meter tower located on PASNY property south of the PASNY acce,ss road. Measurements for windspeed and wind direction are available at 3 levels (10m, 60m, 122m). Pasquill Category is determined from a delta temperature using the ground (10m) as the control level (60-10, 122-10). See Figure 1 for stability class conversion. For redundency in determining the stability class, sigma theta, which is a measurement of atmospheric stability, is measured at the 122m level and converted to a Pasquill Category. (In the event there is a loss of electrical power, a backup diesel generator would supply power for the 122m tower systems.) The backup meteorological tower is located on the Con Ed Service Center building and records wind speed and wind direction at 10 meters. The Pasquill class is determined from sigma theta or by visual means using Figure 2. The data is sent to a Climatronics Data Acquisition System IMP /801 which is located in the MIDAS computer room of the EOF and includes a two pen Esterline Angus recorder and a Texas Instrument (TI) Silent 700 Electronic Data Terminal. NOTE: The units for wind speed vary from methed to method. I m/sec = 2.2 mi/br. 0.45 m/sec = 1 mi/hr Therefore: If you have mi/hr multiply by.45 to get m/sec If you have m/sec multiply by 2.2 to get mi/hr Page 1 of 12

2P-1003/3 NOTE: All wind direction is interpreted as the direction from which the wind is blowing. NOTE: The determination of the magnitude of release calculations require ground level (10m) meteorological data. NOTE: All time is EST. 1 3.0 PROCEDURE 3.1 A panel containing a digital display of meteorological parameters is located in the Control Rcom. This data is transmitted from the 122m tower and has both ground (10m) and elevated (122m) meteor-slogical parameters. 3.1.1 Windspeed is in m/sec and is read directly. 3.1.2 Wind direction is read directly. 3.1.2 Pasquill Category can be read directly. IF THE DIGITAL DISPLAY PANEL IS NOT FUNCTIONING IN THE CONTROL ROOM 3.2 Use the Dec Writer ASCII computer terminal in the Control Room to telephone the primary or backup meteorological towers and obtain the meteorological parameter via a telephone data link. NOTE: The same data is available by going to the tower locations directly: Both locations read out on TI silent 7000 terminals. (See examples 1 & 2 for printouts) NOTE: Time is always EST. a) Turn ASCII "on", 300 baud line. b) Telephone: i) (122m tower) if the Control Room displays are not working. chances are this line will not transmit data. ii) (backup tower) c) Listen for high pitched tone. NOTE: If the telephone rings more than 4 times, the data link is not connected. Try the other telephone number. d) Place telephone hand piece in ASCII cradle with the mouth piece on right. e) Wait for red light to go on. It is located on the right hand side of the ASCII terminal. 2 of 12

IP-1003/2 f) Push the "H" button on the terminal keyboard fo'. lowed by a " RETURN". This will print a previous hours 15 minute average. (Up to six hours of fifteen minute averages can be retrieved by typing an "H" with a number from 1-6 following it (i.e. H5). The average at the end of the hourly summary will be that of the current hour). NOTE: If you are at the tower locations using the TI silent 700 terminals: Turn on, and begin with commands in (f). g) When it finishes printing, the link can be closed by hanging up the phone. h) Turn off ASCII terminal. 3.2.1 Ground level wind direction is read from the WD1 column. (Example 1 & 2) 3.2.2 Ground level windspeed is read from the WS1 column. (Example 1 & 2) This is in mi/hr. Multiply this number by 0.45 to obtain the m/see windspeed. 3.2.3 Pasquill stability class: 1) Primary tower See example 1 Use the DT1 column, and use' Figure 1 to transcribe this ground level (60-10) T value to a stability class letter. (Note: the last WD3 column is the 122m level stability as derived from sigma theta, and if used will be very conservative in assessing ground level concentrations.) ii) Backup tower See example 2 Use the right most WD1 column to read the Pasquill category letter directly, or use Figure 2 and determine by visual means. (For this tower, Pasquill is determined from sigma theta) l l l ') 3 of 12

IP-1003/2 Example (1) 122m tower (3 wind measurement levels) M w ua w,us.nc c im:/*4 giu. c.t o w (.u Ac-.e 2 6.rv26) (du u s s vi Q c.4 L i- :.p~e:v !?tiis;! 11 1! !! !!I C"* E!!!

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11,15 !! C;r. Erl: r. A. ; r.. Cr.;t.NEL ree-! E: On og l C r <.o g. r ec.".E W ggv

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. ;.1 a l l 1:.. ~2 :, g 's - N Nbu 11:$b h i4 (( g. l 12:4! 1 12 .1 c W M* tT y 13: 00 0 6.T C 4An 12: 1! 3!. 12 T. F 0 12 : N

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\\ .,> c - - : =..... 4... 1. l l l l -~ ~ w.% -Je g g 0 s c.a c.n c, a b / w e-) l i l l NOTE: Scan the data to make sure it makes sense. (i.e. Pasquill classes are A-G, wind direction o will not exceed 360 on ti.e printouts) l 4 of 12 1 I I

IP-1003/3 FINAL MITHOD TO OBTAIN MITEOROLOGICAL DATA WHILE LOCATED IN CONTROL ROOM 3.3 Use the Dec Writer ASCII computer terminal in the Control Room to telephone the MIDAS computer system which has up-to-date meteor-ological information. a) Turn ASCIL "on", 300 baud line b) Telephone: c) Listen for high pitched tone NOTE: If the telephone rings more than 4 times, the data link is not connected. Try the other telephone numbers. d) Place telephone hand piece in ASCII cradle with mouthpiece on the right. e) Wait for red light to go on. It is located on the right hand side of the ASCII terminal. f) Terminal Prompts Operator Response Please enter your ID " RET" Please enter your password " RET" NUM, UNIT, NAME ,NRCMET " RET" Enter Start and End Dates (99 = Last 6 hours) 99, " RET" Or YYMMDDHHMM YYMMDDHHMM (Calendar) Or YYJJJHHMM YYJJJHHMM (Julian) NOTE': Time is EST NOTE: An option of using calendar, Julian, or past six hocrs is user selectable. For emergency operation it is recommended that only "99" by used for expediency. g) It will begin printing met data in 15 minute intervals. h) NRCMIT output headings are as follows: YYJJJHHMM - Year, Julian Date, hour, minute (EST) WDU, WDI, WDL - wind direction for upper (122M), intermediate (60M) and lower (10M) sensor heights (degrees). WSU, WSI, WSL - wind speed (meters /second) for 122, 60 and 10M. STU, STI, STL - standard deviation of the horizontal wind direction, 122, 60 and 10M. DTUL, STUI, STIL - temperature differential presented in 'C/100M for UL (122-10M), UI (122-60M), and IL (60-10M). TAL - ambient temperature ('C) for 10 meters. TDL - dew point temperature ('C) for 10 meters. PCP percipitation total (MM) at ground level. S - Pasquill stability indicator (A=1, B=2, C=3.. G=7). i) Message of VRCMET DONI - completes the program. 5 of 12

... ~ IP-1003/2 i 1 1 Example (3): MIDAS Meteorological printout. l CCCL: LATE: ELI: t* C:: Cr t*Y - FC+E8 Avi6C:ITY Cr T-E : TATE CF NEW iCh e IrtLI Are sC!r*T revCLE A: GErEEATIb? TATIC9 C 1::Ti til METC8 !C+i2 L AT-C D. LCN-C C, ELEv-le:E 41.i!FFF T 3. :-!001 116. T h.IrtL T:-v.1,L DT1-9 tit-L LTi-U LTI-I 072-1 Lf! w i f"'S 08' FCF 112.0 60.0 10.0 121.0 10.0 111.0 +0.0 c c. 0 19. 0 10.9 10. V 1.0 NCTEsLATITUEE ard LONGITU:E FC8 If101'N 3CIbf 01TE v;E*, OL&EE-tAits ;T-Cr m; tri sEFEsENCE 8CINT ;;; CCe3TAtha+ENT LATE:T C&LIIE ATID* F-2 0-il 3 yyJs --na i-Lv wLI i4 L w*v w"I w"L :TU TIITL LT'.'t Divl LTIL Tw TIL AC8 I 212!2111! 24 15. 3.5 1.9 1.3 11 to 19 -1.0 -1.1 .? -32.4 i:.5 's. O 4 i13?i1120 41, 20, 14 ".T

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3.3.1 WDL co'.umns is wind direction for ground level. 3.3.2 WSL is wind speed for ground level in m/sec. l2 3.3.3 The Pasquill stability class is determined by using the column DTIL and Figure 1 which will transcribe this ground level (60-10) T value to ground level stability class. (NOTE: the right most "S" column can be used to i determine the stability class by converting the numbers to letters as follows 1 = A, 2 = B, 3 = C, 4 = D, 5 = E, 6 = F, 7 = G). NOTE! If the primary tower is not transmitting data to MIDAS the backup tower will be used as a default and its data will print out. l 6 of 12

IP-1003/2 3.4 At this point decisions must be made whether to send a member of the watchforce to the primary tower or back up tower. Back-up tower: to read the TI silent 700 terminal (3.2 and example 2) Primary tower: to read the TI silent 700 terminal (3.2 and example 1) or section 3.5 IF THE CONTROL ROOM READOUTS AND THE BACKUP TOWER SYSTEM ARE NOT FUNCTIONING 3.5 The Emergency Director directs a member of the Watch force to the Meteorological Trailer located at the base of the 122m tower. (The key to this trailer is located in the Control Room key locker.) If it is an electrical outage, (i.e. wind instruments still functioning) he will use the " Emergency Wind Set 10m Speed and Direction Kit. If the power is out and the meteorological instru-ments are not functioning, he will set up the portable wind system. NOTE: Figure 3 is the instrument layout for the 122m tower. 3.5.1 Using the 10m winds and " Emergency Wind Set 10m Speed and Direction" kit. a) At the rear of the instrument console near the south wall of the trailer is an instrument line plugged into the rear of the panel marked "10 meter emergency winds". This cable is connected directly to the 10m level winds on the tower. b) Unplug the connector and attach it to the " Emergency Wind Set 10m Speed and Direction" kit so marked. It is plugged into the connector labled "F460" marked "in trailer", c) Turn on kit power, select "F460" and check for a proper trace on chart paper. Write on trace paper start date and time. (trace will run at 1 inch /hr) i) Wind speed is in m/sec. ii) Wind direction is read directly from strip chart. iii) Pasquill Category is determined by visual means. (Figure 2,) 3.5.2 If all other methods of obtaining meteorological data, the Portable Wind System must be used. a) Remove portable wind translators and arm from the east end of the trailer, and mount it on the tripod in any open available area. 7 of 12

IP-1003/2 l b) Disconnect the battery cable from the " Emergency Wind Set 10m Speed and Direction" kit. c) Bring kit within reach of the portable instrument, plug the transmitters into the connector marked "WM1". d) The system must now be oriented. Using the siting compass (located in the trailer on the NE shelf), align the cross arm in an east-west direction with the direction sensor at the western end. (Site thru the i l compass mirror and site along the crossarm (E-W). NOTE: Site the (E-W) crossarm along 102 or 282 for a true north alignment. (at this latitude we are 12" west of north) e) Turn on the Emergency Recorder and select WM1. l f) Check to make sura that when the direction vane is l pointed along the axis of the arm towards west, the recorder reads 270. If not readjust the arm so that when the vane points west, the recorder reads 270. t l 3.5.3 Wind speed is in m/sec. 3.5.4 Windspeed is read from the strip chart l 3.5.5 Pasquill Category is determined by visual means (Figure 2,) NOTE: This instrument should be left recording until another source of meteorological data is functioning. Lid should be closed for l this continued usage. 4.0 0FFSITE METEOROLOGICAL MONITORING l 2 4.1 Meteorological data for the surrounding area can be obtained by telephaning the following air stations. Information includes wind l speec, wind direction, cloud cover and percipitation. l l National Weather Service Stations: l Site Telephone No. Central Park, Manhattan, NY La Guardia Airport, Queens, NY J.F. Kennedy Airport, Queens, NY i l Newark Airport, Newark, NJ Dutchess County Airport, Poughkeepsie, NY Westchester County Airport, t White Plains, NY MacArther Airport, Islip, NY l 8 of 12 l

IP-1003/2 Stewart Field, Newburgh, NT Sikorsky Mem. Field, Bridgeport, Conn. Teterboro Airport, Teterboro, NJ Alletentown Airport, Allentown, PA WilkesBarre-Scranton Airport WilkesBarre, PA

Albany County Airport, Albany, NY 6
Atlantic City Airport, Atlantic City, NJ
Wind data for upper air are only available from Albany and I

Atlantic City stations. 4,2 Forcasts can be c',tained by calling ACCU-Weather Forcast Service Ask for the N.Y.C. Meteorologist. Inform them you work for Pt.SNY (we have a contract with them) and request the forcast for this area. 4.3 For remotely accessed tower data at adjacent Bowline Point: Telephone Number 300 Baud Line Half Duplex Type in upper case only a) Dial 6 when a high pitch tone is heard insert phone into ASCII acustic coupler. A complete link is verified by the indicator light on the terminal. b) Sign on Procedure: The system will ask for the password, type ORU and then depress the space bar. System response will be "0 RANGE-ROCKLAND UTILITIES-- ". When the word " READY" appears hourly data can be accessed. f For the past hour type H space EU and press the " RETURN" I key. Data will automatically printout. Sensor heights are in meters. B-100= Bowline Tower 100 meter level. A " READY" l message appears after the data is printed. If dxta from a previous hour, up to 12 hours, is required type LnEU and the " RETURN" key, where hh is the hour of interest. After all inquires are complete press down on the "CNTL" key and type z to disconnect from the system. 9 of 12

IP-1003/2 FIGURE 1 aT CONVERSION TO STABILITY CLASS GROUND LEVEL (60m-10m) Stability Class 4T Temperature in *F A -1.74 B -1.74 to ( -1.56 C -1.56 to j -1.37 D -1.37 to < -0.46 7 -0.46 to ( +1.37 F +1.37 to ( +3.66 G h +3.66 10 Of 12

IP-1003/2 FIGURE 2 Estimation of Pasquill Category A stability classification (Pasquill) was developed to differentiate the dispersive capacities of the atmosphere. The vertical temperature difference of the atmosphere ranges from very unstable (Category A) to extremely stable (Category G) conditions. Alphabetic characters (A,B,C,D,E,F, or G) are used to define the prevailing thermal structure. A listing of the categories is as follows: PASQUILL CATEGORY STATE OF THE ATMOSPHERE A Extremely unstable B Moderately unstable C Slightly unstable D Neutral E Slightly stable F Moderately stable G Extremely stable The appropriate Pasquill category is derived from vertical temperature measurements. However, in the absence of specific onsite temperature measurements, stability categories can be estimated by visual techniques. A methodology for determining the Pasquill category from observations of cloud cover, wind speed and time of day, (solar radiation) is illustrated in the-following table. DAYTIME NIGHTTIME Clear Partly Over-Partly cloudy Clear sky Surface Windspeed (m/s) Sky Cloudy cast to Overcast partly cloudy 0-2 A A-B B E-F G 2-3 A-B B C E F 4-5 B B-C C D E 6 C C-D D D D >6 C D D D D General Definitions 1. Daytime is considered as one hour after sunrise to one hour before sunset. 2. (a) Clear sky - less than 20 percent of cloud cover (b) Partly cloudy - 20 to 80 percent of cloud cover (c) Overcast - 80 to 100 percent of cloud cover NOTE: This procedure should be used only in the event of onsite instrument failure. NOTE: If there is a doubt concerning which category is applicable, select the alphabetic character furthest from A. This decision will be more conservative is assessing ground level concentrations. 11 of 12

INSTRUMENT IAYOUT 122 m Meteorological Tower PWR H H H WR g g gg Supply o$ oO mO 8 ll E lupply Hy HQ gy nQ *$ 4 M 30 m WIND RECORDER o o H d 3 y y I o WD l WS I l 60 m WIND RECORDER I WD 'l WS l 10 m WIND RECORDER 122 m WIND RITORDER I i a 0 WD l WS WD l WS I C N v' I I m r* I l C TEMPERATURE RECORDER PRECIP. R1. 10 m Temp. RECORDER 82. 60 - 10 m aT Wind Speed is recorded in mi/hr. 53, 122 - 10 m AT B5, 10 m Dew Point (.45 x mi/hr = m/sec.) IWR H f 2 SulPD E4 'N hb O (* h 3

POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN POINT NO. 3 NUCLEAR POWER PLANT P. O. BOX 215 5UCHANAN N. Y.10511 TELs P=o w s 914 739 8200 8 EMERGENCY PLAN PROCEDURES PROCEDUPI NO. IP-1004 REV. 1 TITLE: ff!DAS COMJUTER SYSTEM: DOSE ASSESSMENT MODELS WRI CEN BY:,. / f/NfcMAt8 REVIEWED BY Mh w - DATE 52/fL PORC REVIEW "'d, APPRCVED BY: J-DATES /rh1'2-EFFECTIVED7w}_ l l - ) 'R - R 1

l IP-1004/1 IP-1004 MIDAS COMPUTER SYSTEM: DOSE ASSESSMENT MODELS 1.0 DISCUSSION The MIDAS Computer System has 2 computer models available to assess the real time values of radiological releases, both are available for use during emergency conditions. The Class A Model a gaussian straight line plume simulator, provides relative concentration output within a few minutes. The Class B Model produces refined l estimates of the transport and diffusion of particulates incorporating terrain, j time and space variations within 5 minu es. I 2.0 PROCEDURE 2.1 These programs can be accessed and run remotely by using an ASCII Terminal, 300 Baud line with an acoustic coupler. 2.1.1 Telephone numbers to remotely access the MIDAS System Are: l i 2.1.2 Enter Your ID, type PASNY 2.1.3 Enter Your Password, type LINDA 2.2. Class A Mod'el (Gaussian Model) Prompt from Machine Operator Response NUM, UNIT, Name M,, NRCRRC " RET" Enter Unit (U2 or U3) U3 " RET" Enter Start and End Dates (99=Last 6 hours) 99, " RET" or YYMMDDHHMM YYMMDDHHMM or YYJJJ1DCIM YYJJJHHMM The system will now calculate a Class A Gaussian model at downwind distances of 3218, 8047 a 2d 16093 meters (2,5 and 10 miles) fo3 the time requested. All distances are in meters, X/Q has dimensions of sec/m Message of NRCRRC DONE - completes program. 2.3 Class B Model (Potential Flow) Prompt from Machine Tvoe Kev O M,,peration NUM, UNIT, NAME NRCCLB " RET" Enter Unit #2 or #3 U3 " RET" ll Enter Start Date - YYMMDDHHMM YYMMDDHIDei "REI" or (YR=99 is current time) or 99 " RET" Enter Type of Release (GRND, ELEV) GRND or ELEV " RET" Page 1 of 2

IP-1004/1 The systens will now print out data representing the spatial increments of the plume. At the completion of the first table, the screen message will state - " TYPE C TO CONTINUE TO PRINT". Type C and carriage return (" RET"). The second table will permit a plot of the plume segments (trapezoids) to be made from output using an x-y coordinate system. Messa,. of NRCCLB DONE completes program. 4 Pace 2 of 2

POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN POINT NO. 3 NUC'. EAR POWER PLANT P. O. BOX 215 SUCH AN AN. N. Y.10511 TELapwoNc: 914 739-8200 EMERGENCY PLAN PROCEDURES PROCEDURE NO. IP-1005 REV. 2 TITLE: PLANNED DISCHARGE OF CCh7AINMELT ATMOSPHERE DURING ACCIDENT CONDITIONS -- E:,, ff o cuo= ,c;= -I w!&.J. A E a.n= l APPROVED BY: L DATE /.//MD - EFFECTIVE D E i - ) % - 4 "L w. y

IP-1005/3 IP-1005 PI.ANNED DISCHARGE OF CONTAINMENT ATMOSPHERE DURING ACCIDENT CONDITIONS

1.0 INTENT

To describe the method used during accident conditions to estimate the thyroid exposure to an individual off-site from a planned containment release and to determine whether or not the release should take place.

2.0 DISCUSSION

A Chemistry Tech. will obtain a sample from ccatainment to obtain a (Total Iodine / Noble Gas) ratio. In the event a chem sample is unavailable, and until an actual Chemistry sample can be drawn from 4 containment, use a (Total Iodine / Noble Gas) ratio of 10 to calculate the proposed release rate. The proposed dose rate can be calculated from the release rate and meteorological condition. The Emergency Director will determine whether or not the release is to take place. Calculations using the dose rate and estimated release time will be used as guidance.

3.0 REFERENCES

3.1 RE-CS-042 Sampling Various Plant Systems During Accident Conditions. 3.2 IP-1002, Determination of the Magnitude of Release

4.0 PROCEDURE

4.1 Use Flowchart, EP-Form #1 in IP-1002 for guidance on determining site I boundary and offsite doses. ( 4.2 Determine the significance of the additional expected exposure to the exposure the population may have already received. 4.3 Obtain the latest weather report relative to the next eight (8) hours by calling: 1

1) National Weather Service h which gives the forecast for Westchester County and is updated hourly to see if any significant weather events will occurr i.e. front in wind direction, precipitation.

2) ACCU Weather, ask for the N.Y.C. area meteorological and request the forecast information for this area.

g Page 1 of 2

IP-LOOS /2 i t I-4.4 The decision if the release will take place should be based upon the following: 4 I a) Plant safety related to the need for the release b) Ability to wait for a more favorable time due to weather conditions. c) Exposure already received by the population. f d) Expected population exposure from the proposed release i e) Expected exposure rate changes in the next few hours due to plant performance, f) Discussions with Senior Corporate Officials. 4.5 Should the release take place, instruct the Chem. Tech. to sample the vent to determine the actual Iodine-131 specific activity. 4.6 Flow charts, calculations, and any check off lists or data sheets used in RE-CS-042 should be given to the Chemistry Team Leader or the Emergency Director for retention. j i i I i l l i i Pace 2 of 2 l

POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN POINT NO. 3 NUCLEAR POWER PLANT P. O. 8CX 215 BUCHANAN.N.Y.10511 TsLapwont, 914 739 4200 J EMERGENCr PLAN PROCEDURES PROCEDURE NO. IP-1010 Rri. 2 ] T!TLE: IN-FIANT / SITE PERIMETER SURVEYS 1 Y= h W / bw,/D. aEvIEwED sy: PORC REVIEW N

DATE '//s/f'7
t dr e o cm a0,=

m ac m er ErrECTIvEad 1-s s.u i 1

IP-1010/2 1 P l IP-1010 IN-PLANT / SITE PERIMETER SURVEYS 1.L INTENT To describe the actions of Control Room Personnel and Health Physics and/or Chemistry Technicians in accomplishing in-plant surveys or analysis and site perimeter radiological survys. 2.0 DISCUSSION In-plant surveys and analyses may be taken during any one of the four emergency classes, particularly the Radiological Alert, Site Ares & General emergencies. The Watch H.P. and Chemist should be available for the in plant surveys. Directions for requesting their assistance and instructing them on survey locations as well as overviews of radiological precautions to be observed are found in this procedure. Survey and analysis ] procedures which would be followed by the H.P. and Chemist can be found in RE-HPI-12.4 and RE-CS-042 respectively. The Health Physics surveying may help to determine release rates from the Plant Vent and determine radiological conditions in specified areas of the plant. Chemistry analysis will help to determine the isotopic mixture of the release and the extent of core damage. Site perimeter surveys may be requested during a Radiological Alert, Site Area or General emergencies. Health Physics personnel would be available for site perimeter surveys, or other so designated individuals. Directions for requesting there assistance and instructing them on which site perimeter locations to survey as well as an overview on radiological precautions to be observed are found in this procedure. These surveys are performed to verify exposure rates that have been calculated using measured Plant Vent acticities. These surveys may indicate the maximum exposure rate at that specific point in time, that members of the offsite population in the vicinity of the site are experiencing. 3.0 PROCEDURE FOR IN-PLANT SURVEYS 3.1 CONTROL ROOM ACTIONS: t i A. No sounding of the Site Radiation Evacuation Alarm-I 1. Telephone of page the Watch H.P. and/or Chemist. 4 2. Instruct them to report to the Control Room for instructions or give them survey / analysis instructions over the telephone. B. Sounding of the Site Radiation Evacuation Alarm: 1 1. The Watch H.P. & Chemist will report directly to the Control Room. C. Instruct technicians to do surveys / samples j A Page 1 of 7 1

IP-1010/2 D. Radiological Precautions: 1. Require use of film badges, dosimeters, protective clothing I and other REA requirements as necessary. 2. DO NOT send them to areas which may be radiologically hazardous without these precautions. a. Check Radiation Monitors b. Assess need for KI c. Assess need for respirators /SCBA 1 3. Require use of KI, Respirators or SCBA as necessary l 4. If it is expected that NRC limits may be exceeded refer to IP-1027. 1 J E. Ready themselves to receive survey / analysis results: l The watch HP and Chemist will report their results to the l Control Room. The survey and analysis results should be j forwarded to the appropriate individuals. I i HP Chemistrv j Control Room Control Room RATL in EOF TSC OSC for R&CA preparation OSC RATL in EOF 3.2 HEALTH PHYSICS / CHEMISTRY TECHNICIAN ACTIO,NS: A. No Sounding of the Site Radiation Evacuation Alarm: 1. If paged or telephoned by the Control Room report to the Control Room or perform surveys / analysis as requested. B. Sounding of the Site Radiation Evacuation Alarm: l. The Watch H.P. and Chemistry technician upon hearing the Site Radiation Evacuation Alarm should report directly to the Control Room for instructions. C. Radiological Precautions: 1. Wear film badges, dosimeters, protective clothing and other REA requirements as necessary. 2. Assess Radiological Conditions in any survey / analysis area prior to entering. 3. Take KI as discussed with the Control Room 4. Put on respiratirs or SCBA as required. 5. If it is expected that NRC limits may be exceeded refer to IP-1027. 3.3 Surveys & Analysis may include: (when R-14 is offscale) A. H.P.: Reading the RM-16 High Range Plant Vent Monitor (near clothing drop point in PAB) 'l Page 2 of 7 a

= _. - . =. IP-1010/2 B. H.P.: Taking a teletector reading at the Plant Vent 1. 6' from vent if less than 1000 mR/hr 2. take a reading on contact with plant vent C. H.P.: H.P. surveys for access. D. Chemist: Take Gaseous Marinelli E. Chemist: Plant Vent Charcoal (if expected Iodine problem) F. Chemist: Post Accident Sampling of RSC/ Containment Air / Plant Vent 3.4 Reporting Survey & Analysis Results Using walkie talkies, wound power phones, or telephones as appropriate. A. Technicians should report results to the: [ 1. Control Room, who would forward results to appropriate individuals. 4.0 PROCEDURE FOR SITE PERIMETER SURVEYS i I' 4.1 CONTROL ROOM ACTIONS: A. No sounding of the Site Radiation Evacuation Alarm: 1. Telepbone the H.P. Supervisor and request H.P. techs. to perform site perimeter surveys. Have them report to the Control Room for instructions. B. Sounding of the Site Evacuation Alarm: i 1. Page H.P. Tech (s) to the Control Room for site perimeter surveys. Call operations support center for H.P.'s to report to the Control Room to do site perimeter surveys. C. Review the site map: 1 1. Using wind direction as guidance, choose the site perimeter sector (s) which maybe affected by the phone. NOTE: If sectors 1-8 or 22 are affected, you can request Con Edison technicians to perform these surveys. a. Call the Unit 2 Watch Foreman b. Request H.P. 's to do site perimeter surveys (j3 & 6 ) c. Give sector numbers d. Inform results should be reported to the Unit 3 Control Room. NATF.: For the water front areas (no sector #'s assigned) request a boat from the Con Ed NEM group to perform j surveys. i l Page 3 of 7

- _ _ ~ l IP-1010/2 I D. Radiological Precautions I i 1. Instruct H.P.'s to wear film badges & dosimeters i 2. Assess Radiological Conditions t a. Assess need for protective clothing I b. Assess need for KI I c. Assess need for Respirators l I 3. Require use of protective clothing, KI & respirators as j necessary. E. Direct H.P.'s to affected sectors, giving them site perimeter map & data sheet, EP-Form #2. F. Ready yourselves to receive survey results via the con Edison radio frejuency. Radiological Assessment Team Leader should also be receiving data). 4.2 HEALTH PHYSICS TECHNICIANS ACTIONS: A. No sounding of the Site Radiation Evacuation Alarm i 1. As indicated by the H.P.. Supervisor or Operations Support Center Supervisor report to the Control Room with survey instruments (j3, f) for site perimeter surveys. i B. Sounding of the Site Radiation Evacuation Alarm 1. Proceed to your assembly area, taking with your survey instruments (f3, f) (availaMe at the Health Physics Control Point locker) 2. If paged to the Control Room to do site perimeter surveys assure your assembly area is aware of yo'ur wearabouts a. b. report to the Control Room with survey instruments (available at Control Point Health Physics Locker) C. Review site perimeter map with the Control Room to determine which l sectors to survey D. Obtain from Control Room site survey map and data sheet, EP-Form #2. E. Radiological Precautions: i 1. Wear film badges and dosimeters i 2. Assess Radiological Conditions i 3. Wear Protective Clothing as required 4. Take K2 as discussed with Control Room 5. Wear respirators as discussed with Control Room l F. Pick up a Ccn Edison frequency portable radio upon exiting the l protected area (Command Guard House) G. Proceed to site perimeter sectors, taking beta and gamma readings along the way, h Page 4 of 7 l i

IP-1010/2 1. Report any significant readings to the Control Koom and if manned the EOF Radiological Assessment Team Leader (both can be contacted via the portable radio) 2. Record readings for data submittal to the Radiological Assessment Team Leader on EP-Form #2. H. When arriving at site perimeter location (denoted by orange signs with blue sector numbers) take gamma field readings at enough locations to identify the approximate width of the plume and its centerline. I I. Take a beta field reading at the location of the plume center line. i J. The monitoring team shall interpret rising beta field indications as rising radioactive airborne concentrations. I 4.3 Monitoring Guidelines: A. Gamma and beta field readings will normally be highest at the center of the plume. B. Beta field readings are determined by taking field measurements with the survey instrument detector window shielded (gamma), and unshielded (gamma & beta). Subtract the shielded reading from the unshielded reading to obtain the beta dose rate. C. Traversing the plume from one side to the other would result in readings that start at zero, buildup to a maximum and then decrease to zero again. The point where the highest gamma reading is obtained is the plume centerline. { i 4.4 Reporting Survey Results I A. Use con Edison frequency portable radio l i B. On the way to site perimeter report any significant readings to the Control Room and/or Radiological Assessment Team Leader via the radi:. C. Report site boundary survey results to the Radiologcial Assessment Team Leader l D. Give data sheet EP-Form J2 to Radiological Assessment Team Leader 4.4 Radiological Assessment using Survey Results 4 A. Refer to IP-1001, Discussi us of the Magnitude of the Release. B. Consult the Radiological Assessment Team. y l Fage 5 of 7

IP-1010/2 i EP-Form #2 MONITORING TEM 1 FIELD SURVEY Instrument Model No. Serial Number Individuals Name Date i Survey Location or Site B +I / [(B + I)- Y]4 Perimeter Sector Number Time mR/hr mR/hr mrad /hr Remarks i i 1 3 4 Page 6 of 7

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POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN POINT NO. 3 NUCLEAR POWER PLANT P. O. BOX 215 BUCH AN AN, N. Y.10511 Tztr awoN E: 914 739 8200 EMERGENCY PLAN PROCEDUPIS PROCEDUPI NO. IP-1011

Prf, 2

TITLE: OFFSITE MONITORING o WRITTEN BY: e _)/ jffryz& ~ REVIEWE O dan //aA> PORC PIVIEW 1/ e,t <. f b DATF, /./r, /f 2. APPROVED BY:g EFFECTIVE DA=:. \\-) % -R1 i 1

IP-1011/2 IP-10ll 0FFSITE MONITORING l 1.0 INTENT This procedure addresses the various methods of offsite monitoring which are available within the plume exposure pathway. 2.0 DISCUSSION A combination of these methods of offsite mcnitoring should give at idea of the radiological conditions of the environment within a 10 mile radius of Indian Point. Various methods of offsite monitoring are: 2.1 Offsite monitoring teams: A, [ surveys: A. 1. Survey results 2. TLD's B. Air Sampling (Iodine & Particulate): 1. Continuous Sampling 2. Emergency Locations 2.2 Reuter Stokes: A. '[ monitoring B. meteorological monitoring (wind speed & direction) 2.3 Ludlum Gamma Radiation Monitors: f A. [ monitoring 3.0 PROCEDURE FOR OFFSITE MONITORING TEAM MONITORING l 3.1 Offsite monitoring locations have been predetermined and locations are listed on Table 1 of this procedure. To determine which locations should be monitored use the overlays, 10 mile sector map and Table 1. The types of monitoring would include: j A. Iodine Sampling: 1. From fixed sample locations (continuous air sampling) 2. Emergency Sampling Sites B. Whole Body dose: 1. TLD's at Fixed Locations l 3.2 Members of the offsite monitoring teams are Con Edison NEM personnel, 2 i i Pige 1 of 13

IP-1011/2 3.3 CONTROL ROOM ACTIONS: A. Control Room personnel should request offsite monitoring team assistance immediately upon declaration of a Site Area or General Emergency, and in certain cases during a Radiological Alert. I B. The IP-3 Control Room personnel should telephone the Unit No. 2 Watch Foreman: 1. Request offsite monitoring team assistance 2. Direct the teams to the Emergency Operation Facility (EOF) C. Ready yourselves to receive information via the Con Edison frequency radio, using EP-Form #2 and EP-Form #3. 3.4 0FFSITE MONITORING TEAM: 1 A. Are made up from Con Edison NEM personnel j B. Are to follow the Con Edison Procedure IP-1015 3.5 RADIOLOGICAL ASSESSMENT TEAM: 5 A. Determine which offsite monitoring locations the offsite teams I should be sent to. I I 1. Using overlays 2. Using Table 1 of this procedure I 1 4 B. Instruct the offsite monitoring team (s) to appropriate sample l locations-i 1. Fixed Sample Locations j 2. Continuous Air Sampling Locations i 3. TLD sites 1 } C. Discuss the need for KI with the Emergency Director and Monitoring Teams, issue if appropriate. l D. Receive information via the radio: i t I 1. NEM Location (s) l 2. Sampling results (Using forms EP-Form #2, EP-Form 2a and j 1 EP-Form #3) a) Beta and gamma field readings obtained while proceeding to the site. b) Beta gamma field readings obtained at the sample point. c) Concentration of radioactivity on the particulate filters. AlsoreportthesampleCPM,tgeinstrument .2 background CPM, the sample volume in ft, and the counter efficiency. .Paa?r, pf 13 2

IP-10ll/2 d) Concentration of Iodines on the charcoal or silver zeolite filter. Also report the sample CPM, the in3trument background CPM and the sample volume in ft and the counter efficiency. 4.0 PROCEDURE FOR REUTER STOKES INTERPRETATION 4.1 Reuter Stokes monitors are located in each of the 16 sectors within 2 or 3 mile radius of Indian Point. Real time Whole Body dose rates ( [) and meteorological (wind speed & direction) information can be remotely interrogated using the Reuter Stokes Sentrii 1100 System and the MIDAS computer. 4.2 Radiological Assessment Team: A. Using MIDAS, obtain Reuter Stokes data. 5.0 PROCEDURE FOR LUDLUM RESULTS 5.1 Ludlum monitors are a gamma field measuring instrument. These have been deployed to various locations around the Indian Point site, which are manned 24 hours per day. 5.2 RADIOLOGICAL ASSESSMENT TEAM: 1. To determine which Ludlum monitor locations to query. ~ a. use overlays b. 10 mile sector map c. Table 1 of this procedure 2. Choose Ludlum monitor locations to query using mile & sector as guidance. 3. Telephone Ludlum locations. a. Request readout of monitor (It is a digital readout) record on EP-Form #4 on page 8 of this procedure. b. Request each location called to record readings every 5 minutes (time & reading) and await for further information & instructions. 4. Expand Ludlum monitor query as necessary using existing readings, calculations, and wind direction as guidance. 5.3 Using Ludlum Readings for Assessment: 1. Whole Body & Gamma Dose: a. A Ludlum reading of 1 mrem /hr is equivalent to a whole body dose of 1 mrem /hr. I i. IS Pace 3 of 13

4 j IP-1011/2 2. Radioiodine Dose: a. A first estimate of radiciodine dose would be: a Ludlum I reading of 1 mrem /hr is approximately equivalent to c.2 { mrem thyroid per one hour of breathing. 6.0 RECORD RENTENTION 6.1 The Radiological Assessment Team Leader is responsible for retaining all data sheets, forms, and plots pertaining to offsite Radiological Assessment. 2 4 1 l 1 i Page 4 of 13 ~ _ _ _ _ _ _.,, -., _ _. _, _ _.

( q t a f %) table I IDCATION NAHE SFCT HILE CAS FAS N/S TI.Il IDnLAHS/I'llONF. NUHlWHS Roa Ifook Rd. - Sanatation Carage 1 I CAS EAS Tf.D (Cortlandt) Hear Hist. HJ. near Old Stone on flu.fson i 2.0 N/S Hie. 9D Carrison I 5 ll El Rte. 911 St. Francis Retreat (Carrison) I F EAS y Hec, 9n Desta C m s Hd. (Coly pgng) I lo EAS gu Canopus Hollow R.I. & Dell llollow R.I. 2 10 EAS 'h old Pamast Ave. (Peckskllt) 2 2 EAS TfD Ann.wille Carcle. Texaco Station 2 2.5 N/S Ui Troup K St. Police, Annsville Cara;le 2 3 O Highlasul Ave. & Sprout Drook Rd. 2 3 FAS "n f.alluws Ilill RJ. 2 5 llD F-4 Canopus Hollw Hel. & Old Alleany Post HJ. 2 6 .EAS W Putnam, Va l l ey. I'ol i ce ficp t. 2 9 I.UDIA Nortl East Cosner (site) 3 .5

TlD, 1.ontsa St. & H.R. Bridge 3

I EAS l.ower Souti St. & Boy St. 3 1.5 TID Pechshill Gas Holder 3 2 CAS Ilulson St. & kN Street (Peekskill) 3 2 "A R/S (Ca s t,ones Rest. ) HamiIton St. 3 3 TI.D Hillcrest Sc t.oa t (Peekskill) 3 3 EAS fire gun Hon.1 Sul.st at lan 3 4 CAS Westlerrok Delve 3 5 Tlu useson Corners (Putssam Valley) 3 6 EAS Hol.csan F.ll. - Lake Hohegan (Ilead.paar tes s) 3 7 Ltful.lR1 Peckskill llollow H.l. & Tinker till! Rd. 3 10 EAS 1.ent a Cove 4 .5 Tih I.ower Soutti St. & Louisa St. 4 1.5 ll.D Standarel Bianels 4 I CAS 1113 Old Dump 4 1 TLla 1.ower Soutti St., Hearl Corp. (Peekskill) 4 i EAS 1.ower S. St. near West. Ison 4 1.0 R/S Perkskill Police Dept. 4 3 LUDI.UH Cent ennial flouse F. D. 4 3 1.UplIt Haple Ave. Entrance to Ht. Florence Sclinal 4 3 F.AS

T I f r.1wrr ' DI yt.E PAGE 2 of 5 5.OCATION NATIE SECT Hil.E CAS EAS R/S llD 1.UDIAttS/PflONE NttillERS l'ine RJ. 4 5 TI.11 I.csington Ave. & Townsend Rd. (Co r t l an.it ) 4 6 EAS Hohegan F.D. - Jefferson Valley 4 9 LUDI.lti Sam.rston Rl. & Carol Ct. (Yoshtawn) 4 to EAS ~ liti Dicakicy & Broa.tway 5 .5 1.uwer S. St. near By Pass Diner 5 1.0 R/S Welaher Ave. & lickincly Se hool Playgsound 5 1.5 TfD Nd a nely St. & W-leher Ave. (Peckskill) 5 2 FAS Haple Ave. E furnare Woods Rd. ( Co r t l an.it ) 5 4 EAS Centon Ave. 5 5 T I.8) flolecg:en F.D. - Fus nac e Doc k 5 6 LUDI.lti fluiat re terock Rd. e CoAs. Sta.f571 (Yorktown) 5 7 EAS Yorktown Police Dept. 5 9 Ltlut.UH Hasc=4n,Rd d St. Patricks School _(Yoshtown) 5 ID EAS Simulator flu l l eli n g 6 .5 Tib IIrnailway, between Bleakley & Service Center 6 .5 R/S 'O Tennalite Corp. Rt. 9A (Buchanan) 6 I EAS factory Street 6 1.5 TfD .c Watch flill R4 & Nt. Stile Trall (Cortlan tt) 6 3 EAS Calatiangh Pond Rd. 6 5 TfD Rte. 129 e llunIerbrook Drldge (Yorktown) 6 7 EAS 'O rai l lwena s,1,. Sta. 6 to Ltlnt.tal Hte. 100 & Rtc. 114 6 10 EAS n.w iiEa n l'ol ice Dept. ) i~~ '~ LUDLtti Wat er Heter llouse 7 .5 Ti ti lir e a.tway, at Service Center Cate 7 .5 R/S Dnthanan Village llall 7 I CAS TfD Serv. Ctr. Guard Ilse. 7 I f.UDI.tAl Westrnester Ave. & First St. (Itur hanan) 7 I EAS Inrnate Dock 7 4 CAS TfD Wate-li 11111 Rd. & Westminister Dr. (Cortlandt) 7 4 EAS tit. Alry & Winner R.I. 7 5 TID Crot on Police Dept. 7 6 LUDI.l#1 Clevelan.1 Dr. & llughes St. (Croton) 7 6 EAS Ossining Paltre Dept. 7 9 1.UDI.lP Nor tle St at e Rd. & Ryder Ave. 7 10 EAS I HO H H\\N .....,. ~. -. . ~ ~.....

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Table I 10Cff'D) Page 4 of 5 litATION NAME SECT lill E CAS EAS R/S Tib LUDLAllS/PilONE WIRtRERS Trap Rock at end of 9 Ave. (White Beach) Il I R/S Cilmore Dr. & Adame Dr. (Stony Pt.) Il 3 EAS Willow Grave Rd. & Birth Dr. Il 5 TLD Willow Grove RJ. & Rnspp Rd. (llaverstraw) II 6 F.AS llaverstraw Rd.,(Rte. 202) & Wilder _Rd. Il to F.AS Cays Ilill Rd. (south end) & Rte. 9W 12 2 F.AS R/S TfD levelt Plant 12 2 CAS I.tmLIRl/9 84-786-3310, X2533 Franrk Rd. & Rutson Town Rd. (Stony Pt.) 12 4 F.AS Palisades Pkwy. (sign going So., NY & NJ) 12 5 TfD 1.ahe Welch Pkwy. & Sewage Plant (lla r ri son) 12 7 FAS Lake Welch I' hwy. & 7 Lakes Pkwy. (Harrison) 12 10 EAS Cays Blill' Rd. (north end) & Rte. 9W 11 2 EAS R/S tlh flot t Farm R.I P Ent rance to Camp A.idison s3 3 EAS Royce (Tusedo) Palisa. Ice Pkwy. (So. of Cas Statlon) 13 5 TIR Arden V, alley & I.ake Cohasset 13 9 EAS Rtc. 9W at Pireles Cove Rest. (Stony Pt.) 14 2 FAS R/S TID Anthony Wayne Park 14 5 TfD y 0, Rte. 6 I mi. West of PaliseJes 14wy. 14 6 EAS y County Rte. 9 @ Thruway (Woodbury) 14 10 F.AS 00 lit e. 9til 5Iw Eo7 5onument lSi~eny'Pt.) ' ' ~ ~14 11 LirDLtRl/9 84-7R2-8311 Orange County M.T.S. Police,tionroe, N.Y. 15 " ' ~ ~ ~ l F.AS R/S O Rte. 9W Sa. of Ayers Rd. 15 1 Tin F4 9W & 202 (Pole f NYT #255) 15 2.0 R/S g Front F.et rante Bear tit. Inn 15 4 EAS ta8 Palisades Pkwy. (Lake Welch Exit going So.) 15 5 TIS tl6 ne Hel. & Weynant s Ril. (Highland) 15 6 EAS tlineral Spf ngs Rd. & County Rtc. 34 15 10 EAS i Ayers Ril., Jones Point (Stony Pt.) 16 I EAS R/S II.li Ibek 16 .5 TfD Rear Ht. Br6dge West Envi 16 4 EAS Fort Plan t gome r y 16 5 TfD 0.4 mi. West. Junction Res. 9V & 21R 16 6 EAS Rt e. 9W f. Rt e. 293 (Highland) 16 9 F.AS IHOH t* tJ l h i I t

t. ( i ? i i i, TABLE 1 (CONT'D) Page 5 of 5 SECT: Sector I CAS: Continuous Air Sampling Site (Green dots) EAS: Emergency Air Sampling Site (Yellow dots) f. R/S: Reuter Stokes (Blue dots) \\ 'O* ?' TID: TLD (Red dots) i8 1 LUDLUM: Location & phone # of Ludlum Sites (black dots) ) O th H i W Miles determinations are made in this mannor: I Miles are determined by the mile sector which encompasses it. i ex: if between sector 1 & 2 it will be refered to as mile 2. l 4 4 tilI HO 3 -s tJ 4 1 + -

IP-10ll/2 EP-Form 42 i 1 MONITORING TEAM FIELD SURVEY Instrument Model No. Serial Number Individuals Name Date [(B + [)- 2f]4 Survey Location or Site B +T 3' Perimeter Sector Number Time mR/hr mR/hr mrad /hr Remarks i. i l i .l Page 10 of 13

IP-10ll/2 2 EP-Form 42a i ENVIRONMENTAL TLD AND AIR SAMPLE READOUT Prior to Discharge C After Discharge C Sample Pickup - Date Time Indiv. Sample Process - Date Time Indiv. TLD AIR SAMPLE Sector Sector Iodine uCi Thy. Mile Zone mrem Mile Zone Part. Char. Rem * ,\\ I i 1 I 1 I l 1 1 4 A

Note:

1 uCi of Iodine on filter (Part. or char.) is approximately equal to 1 Rem exposure to the adult thyroid. Page 11 of 13 }

IP-1011/2 IP-Ferm u3 CON EDISON FORM e 21 RM-14/HP-210 DETERMINATION OF RADIOACTIVE AIRBORNE CO N C E NT RA T IO N S l Samole l Samoling w/Sendix lSamoline W/HD28 or D.C. Sampleri ~ IStar: 1 End I Gas Meter l l l ITime ITime l I i l Elapse l l i I l Star: lend ISample i Time lRotometer or Flow ra:e i I i l I I IIndic. Iscar: i ene lavs.isa ptai l-1 I I I I I l i I I l Hrs. I Hrs. I Ft1 iFed l F:1 lMins l CFM lCFM lCFM I F:1 1 I i 1 I i i l i i i I I I i l I i l i i i i l l l I l l i i l i 1 -l- . l-- -i i i I i i i I i l l Sample C o u n:in;; RM-14 EP-210 Serial No. ,1 l 13600 Tes C?M lSutton Source 5:a:ec C?M l I lau::en Source Coun: CPM I I I I .1 l 3 ample 1 3kgd 1 l 1 Samole l CPM l CP= l uCi/ca I l l l l Particulate i I l l l 1 l l ICharcoal l l l 1 i l i i i ISilver Zeolite l l 1 l i I i r I 10-11) l (Sample CPM-EKGD CPM) (6.4 x l Particulate uti/cc = ~ I F:d l i I l i 1 l i (Sample CPM-SRCD CPM) (4.6 x 10 2.1 l l Charcoal uCi/cc = l Silver Zeolite FTJ l i I I l .I I I I I I I I I I I l l l Return this form to the Radiological Assessment Team Leader. Page 12 of :.3

IP-1011/2 EP-Form #4 LUDLUM ENVIRONMENTAL RADIATION MONITORING F"TWORK i 1 Plume Monitor Involved Location Monitor Location i Time Sectors Sector Zone mR/hr Xu/Q i I I, Page.13 of 13 l

POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN POINT NC. 3 NUCLEAR POWER PLANT P. O. BOX 215 BUCH AN AN. N. Y.10511 TELEPm o N E: 914 736 8200 .~ EMERGENCY PI.AN PROCEDURES PROCEOUPI NO. IP-1015 REV. 2 TITLE: AIRBORNE I-131 DETERMINATION USING SAM-2/RD-22 OR RM-14/HP-210 WRITTEN BY:. 4 m,f 7 .E/IEWED BY dhd i PORC REVIEW 7/dhut DATE N 9?;- a. APPROVID BY: M-DATEJ.hsb. g EFTECTIVE DATJ \\-\\t-81 l

IP-1015/2-IP-1015 AIRBORNE 10 DINE-131 DETERMINATION USING SAM-2/RD-22 OR RM-14/HP-210 1.0 INTENT To describe the procedure used to sample air and count the sample to determine a specific activity of Iodine-131 during a Site Area or General Emergency. 2.0 DISCUSSION This procedure describes the method to obtain specific air samples and count the samples at various sampler locations during an emergency condition. Samples drawn at the EOF or in Con Edison Offsite Monitoring Vehicles will require utilization of the equipment provided by Con Edison and shall follow the procedure described in section 3.1. Samples drawn at other locations will utilize PASNY sampling equip-ment provided in that particular sample area, ie. Control Room, Technical Support Center. 3.0 PROCEDURE 3.1 SAMPLING AT THE EOF 3.1.1 SAMPLING WITH RADECO HD28 (REF: FIGURE 1) NOTE: Use EP-Form #3 a) Place a glass fiber 0.8 u particulate filter in the outer section (gold) of the filter escembly, b) Place charcoal or silver zeolite cartridge in the . inner section (blue) of the filter assembly. c) Set the elapsed time indicator with the manual reset. d) Record the starting time on EP-Form #3. Start the pump and record the flow rate as indicated on the rotometer (0.5 to 3.0 CFM). e) Run sampler for at least hour, record final flow-rate, turn off pump and record elapsed time. f) Remove the filters from their respective holders. Replace with new ones, reset elapsed time recorder and restart the pump when a second sample is required. Note: If the a P PAPER gauge reading is 1 the PUMP HEAD gauge reading the filters must be changed. Page 1 of 16

IP-1015/2 3.1.2 SAMPLE COUNTING USING THE SAM-2/RD-22 (REF: FIGURES 3/7) DISCUS 9 ION The SAM-2/RD-22 is a two channel gamma spectrometer that has been calibrated to count the gamma photons emitted from Iodine 131 having a peak of 0.364 MeV and to reject the gamma photons coming from other isotopes. a) Connect the RD-22 detector, using the coaxial cable, to the lower right hand corner terminal on the face of the SAM-2 marked detector. (The RD-22 detector is contained within the RD-15u). b) Connect the SAM-2 to a 120 VAC supply using the power cord which connects at the back of the instrument chassis. c) Energize the instrument by placing the power switch located on the back to the "0N" position. d) Allow the instrument to warm up for at least 10 minutes. e) Set CH 1 Switch to "+" and CH 1 window to "IN". Set CH 2 Switch to "0FF" and CH 2 window to "IN". f) Check to determine that the five (5) ten (10) turn pot settings are as recorded on the cali-bration sticker for the 0.02 window. These settings are the proper ones for determining the Iodine-131 contribution on the filters. When Barium-133 button source (used to check oper-ability of instrument) is counted in subsequent steps, it will be necessary to lower the CH 1 threshold setting by 0.008 which is the differ-ence between the Iodine-131 peak at 0.364 and Barium-133 peak at 0.356. After adjustments to the threshold pot, lock it in place by moving the little lever on the pot to the down position (clockwise). Note: Each complete turn of the pot is equivalent to 0.100. I g) Set the count time to 2 and X1 Set count to " Timed". Page 2 of 16

IP-1015/2 h) Press the " start" button to start the 2 minute back-ground count. Divide the count by 2 and record the count rate in CPM on EP-Form #3. This background may g be used when checking the Ba-133 source or when counting the filters for Iodine-131. 1) Adjust the CH 1 threshold pot to a value 0.008 lower than is called for on the calibration sticker. Place the Ba-133 button source (located in the container mounted to the chassis) on the top shelf position of the sample holder using the appropriate plate. The source name plate must face the detector. j) Press the " Start" button to start the 2 minute source count. Divide the count by 2, subtract BCPM and re-cord the count rate in CPM on EP-Form #3. 2 k) The source minus the background BCPM should be as labeled on the back of the source times the decay factor. The decay factor is obtained by determining the number of months since the source date and find-ing the decay factor corresponding to those months on the curve found on page 9 of this procedure. Proceed to step (m) if the source check is okay, if not proceed to step (1). 1) If the check source count rate is outside the limits as specified, the threshold pot must be varied, up or down, until the peak is identified on the count rate meter. Perform a two minute count of the check source and proceed as in Section (k) above. This is the new Ba-133 threshold setting. Add 0.008 to obtain the new I-131 threshold setting. m) Adjust the CH 1 threshold pot to the value specified on the calibration sticker or to the value just arrived at in step (1). Remove the Ba-133 check source and shelf from the sample holder. Using the other shelf (large hole in center) place charcoal or silver zeolite cartridge on the middle shelf position making sure the filter is positioned right unde :- the detector. Press the " Start" button and I count for 2 minutes. Record the count rate in CPM g l on EP-Form #3. n) Remove the' charcoal or silver zeolite cartridge and shelf from the sample holder. Place the particulate filter on the shelf and place the shelf in the top j position making sure the filter is positioned right under the detector. Press the " Start" and count for 2 minutes. Record the count rate in CPM on EP-Form #3. 2 Page 3 of 16 l

IP-1015/2. o) Calculate the Iodine-131 activity for each filter or cartridge using the following equation and the appropriate efficiency (E) obtained from the cali-bration sticker. uCi/cc = (sample CPM-Bkgd CPM) (6.2x10 0) (E)(V)(Ft ) 3 p) Perform background and source checks approxi-mately every hour-or at the filter counting periods. GCPM = Gross Counts Per Minute of Sample BCPM = Background Counts Per Minute E = Efficiency Posted 3" V = Sample Volume (Ft ) 3.2 SAMPLING AT THE CONTROL E00M, ISC, Osc NOTE: Use EP-Form #5 or EP-Form #6 3.2.1 AIR' SAMPLING (RADECO HD-28B)(REF: FIGL"1E 2) a) Assemble the air sample equipment at the desired location. Connect the HD-28B to a 120 VAC supply. b) Load a glass fiber 0.8 u particulate filter and a charcoal of silver zeolite cartridge into the sample head, place sample head into the quick-connect fitting on the front face of the HD-28B sampler. c) Reset the elapsed sample time recorder to zero. j Ensure the sample head is inplace, start the sampler and record the' start time on EP-Form #5 or #6. Obtain a flow rate of 1.0 CFM by adjusting j the flow adjust knob on the front of the HD-28B i sampler. Record the flow rate. Run the sampler for at least \\ hour when obtaining samples of l the Control Room, TSC, and OSC. d) Turn off the sampler; record the elapsed time and the l sample time on EP-Form #5 or #6. Multiply the flow rate 2 by the elapsed time to obtain the sample volume. l e) Remove the sample head, reset elapsed time recorder and replace with a new one in the event additional samples are required. 3.2.2 SET UP OF MS-2/ SPA-3 FOR SAMPLE COUNTING (REF: FIGURE 4/6) DISCUSSION The MS-2/ SPA-3 is a single-channel spectrometer that is calibrated to count the gamma photons emitted from Iodine-131 having a peak of 0.364 MeV and to reject all other gamma photons. Page 4 of 16

IP-1015/2 a) Connect the SPA-3 detector, using the coaxial cable, to the lower right hand corner terminal on the face of the MS-2 marked detector. b) Connect the MS-2 to a 120 VAC supply. c) On the back, place the power switch to the "0N" position to energize. d) Let the instrument warm up for 10 minutes. e) Set CH 1 switch to "+" and CH 1 window to "IN". f) Set the three (3) ten (10) " turn pot" dials to the setting indicated on the calibration sticker on top of the MS-2. Each full turn is equivalent to 0.1. g) Set the count time to 2 and XI. Set the count to " Timed".

Background

h) Set the detector / sample holder up utilizing RD-15u radiation shield shown in Figure 5 on page 15, in a low background area. If the gama fields are greater than 10 mR/hr, move to a location with fields as,. low as practical before setting up equipment. i) Press the reset / start button to start the two minute background count. Divide the total counts by two to obtain the CPM. Record all data on EP-Form #5. 3 Source check 1 j) Place the Ba-133 source in shelf No. 2 position. k) Press the reset / start button to start the two minute source count. Divide by two and subtract the background BCPM to obtain the sources CPM, record all data on EP-Form #5. 2 1) The source CPM should be within 110% of the Ba-133 source value posted on the MS-2. m) If the source CPM does not agree within the specified 110% of the posted source value, the source check procedure shall be repeated 2 ad-ditional times. If this source CPM is not with-in the specified tolerence following the two additional counts, the treshold adjustment must be varied up or down in increments of 0.02 until a satisfactory source CPM is obtained. This is the new threshold value for all future counts until a re-calibration is performed on the instrument. Page 5 of 16

IP-1015/2 3.2.3 SAMPLE COUNTING USING THE MS-2/ SPA-3 g NOTE: Use EP-Form #5 DISCUSSION Initial samples obtained should be counted using the MS-2/ SPA-3 assuming all the activity is I-131, both particulate and gaseous. This is performed by seperately counting the charcoal or silver zeolite cartridge and the particulate filter. Utilizing the MS-2/ SPA-3 which is set up to analyze gamma rays at the specific energy equal to Iodine-131. The SPA-3 detector is contained within the RD-15u. CHARCOAL CARTRIDGES a) Place the charcoal cartridge in the shelf No. 2 position of the counting assembly. Ensure the cartridge is directly under the detector and count for two minutes to obtain GCPM. Divide by two and subtract the back-ground BCPM to obtain the sample (NCPM). Record all data on EP-Form #5. b) To calculate the Gaseous Iodine-131 concentration, use the following equation and the appropriate efficiency obtained from the calibration sticker. j ", Record all information on EP-Form #5. (Sample GCPM-BCPM) = uC1/cc (6.2X1010)(E)(V) c) Remove the charcoal cartridge from the counting shelf and mark the date, sample location, sample volume, and sample activity for future analysis. PARTICULATE FILTER I d) Replace the particulate filter in the shelf No. 2 position of the counting assembly. Ensure the filter is directly under the detector and count for two minutes. Divide the total counts by two and subtract the background (CPM) to obtain the sample (CPM). Record data on EP-Form #5. 2 e) To calculate the particulate activity, use the following equation and the appropriate efficiency obtained from the calibration sticker. (GCPM-BCPM) _ gj (6.2X1010)(E)(V) f) Remove the particulate filter from the counting l shelf and mark date, sample time, saspl-location, sample volume and sample activity for tuture analysis. Page 6 of 16

IP-1015/2 g) Perform background and source checks approximately every hour at filter counting periods as described in section 3.2.2 " Background and Source Check". 3.3 SAMPLE COUNTING USING THE RM-14/HP-210 (REF: FIGURES 8/9) NOTE: Use EP-Form #6 DISCUSSION The RM-14/HP-210 is a gross beta counter which may be used to obtain a gross beta activity of the particulate filter and charcoal cartridge. a) Connect the HP-210 detector to the lower right corner 4 face of the RM-14 marked " Detector". b) Connect the RM-14 to a 120 VAC supply. c) To energize, place the five position rotary switch on one of the counting ranges (X1,X10,X100), d) To check the battery, place the rotary switch on "Batt" and ensure the needle is reading in the " Battery OK" position. i e) Place the rotary switch to X10 and place the test toggle switch to "On". Make sure the indication on the meter reads 3600 CPM (t10%) above background and then turn off the toggle switch.

Background

j f) Place the detector on the sample holder and check for background. Record the background CPM on EP-Form #6 (Use lead bricks to shield as appropriate). 7 Source Check g) Place the CS-137 check source in the counting chamber. Record the source CPM above background. Compare this to the count rate labeled on the source. Record data on EP-Form #6. I Sample Counting h) Place the particulate filter in the counting chambers to be counted. 1) Read and record the total counts (GCPM) j) To calculate the particulate activity: (GCPM-BCPM) = uCi/cc 3 10 (.15)KFt ) 7 (6.2X10 X Page 7 of 16

IP-1015/2 k) Place the charcoal cartridge in the counting chamber in the cavity created by removing the sample holder slide. 1) Read and record the sample CPM. m) Calculate the Iodine activity as follows, Record all data on EP-Form #6 (Page 12 of this procedure). (GCPM-BCPM) = uCi 0 (V) x (7.9x10 ) cc 7 5 The factor (f.9x10 ) takes into account the conver-sion from Ft to cc and the efficiency (ccpm/uci) of the KP-210 for counting iodine cartridges. n) Perform background and source checks approximately every hour at filter counting periods as described in section 3.2 " Background and Source Check". 0) All samples shall be marked with date, sample time, sample location, sample volume, and sample activity for future analysis and identification. GCPM = Gross Counts Per Minute of Sample BCPM = Background Counts Per Minutes E=EfficiencyPostedgnInstrument V = Sample Volumes (Ft ) Page 8 of 16

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IP-1015/2 r.P-Form v3 CON EDISON FORM # 21 RM-14/HP-210 DETERMINATION OF RADICACTIVE AIRBORNE CONCENTRATIONS l Sample i Sampling w/Bendix lSamoling W/HD28 or D.C. Samplert l Start 'l End i Gas Meter i l l l Time ITime l i i lElapse l l l l l Start lend ISample l Time (Rotometer or Flow rate i i l l l I IIndic. lStart idad lavg.15 amp 14i l i l i I I i l I i i lMrs. I Hrs. I Ft1 lFt1 i Ft1 1 Mins l CFM lCFM lCFM l Ft1 l l i l i i l i i i i l i i i l I i l i I I i 1 1 1 1 1 1 I I I I T i I I i i l i i l l l I Serial No. _l RM-14[HP-210 l Sample Counting 13600 Test CPM 1 13utton Source Stated CPM i 13uccon Source Count CPM l 1 l I I .1 i Sample 1 3kgd l I l Samole l CPM l cpm i uCi/cc l i i l i l Particulate l I l i l i I l l Charcoal l l l l l t i i ISilver Zeolite l l l l I i i l Il Particulate uCi/cc = (Samole CPM-BKGD CPM) (6.4,x 10-111 l i Fed l I l g g I i i i i t iCharcoal uCi/cc = (Sample CPM-BKGD CPM) (4.6 x 10-9_1 l ISilver Zeolite FTJ l I i I .I I I I I I I I I I I I I Return this form to the Radiological Assessment Team Leader. Pace 10 of 16

~ _ -. EP-rom 05 'IP-1015/2 MS-2/ SPA-3 i DETE!?!INATION OF PADICACTIVE AIRBORNE CCtCtrFATIONS i a BACKGROLh"J (BCPM) Background Total Background Counts = 2 SOO M CHECK Total Source Counts - (BCPM) = (SCPM) Source 2 CPM Labeled Source Value IDIE: 'Ihe source (CPM) should be within t 10% of the Labeled source value 4 SAMPLE TYPE SAMPLE P-PART START S'IOP EIAPSED FILM SAMPE SM4PE '

ACTIVITY LOCATION I-IODINE TDE TDE TEE PATE VOLUME GCPM BCPM EFF uCi/cc I

{ i r I 1 l l I I l l l l l i l l l l 1 I l l I I I I I j' I I I N M TICN T N W

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Backgrourd Counts per Minute VCL = Sample Volume in Cubic Feet Page 11 of 16

.-,u~ ~ IP-1015/2 EF-Form 06 ? PM-14/EP-210 DETEPMINATION OF RADIOACTIVE AIRBOP!E COhmTrPATIONS BACKGROUND BCPM SOURCE CHECK Total Source Cbithts - (BCPM) = (SCPM) Scurce CPM Labeled Source Value SAMPLE TYPE. SAMPLE P-PART START STOP _EIAPSED EIfW SAMPLE SAMPLE _ BCPM ACTIVITY II) CATION I-IODINE TIME TIME TIME RATE.VOIR E GCPM UCi/cc t CAICJIATION OF ACTIVITY

GCPM = Gross Counts Per h ute Sanple PARTICUIATE:

SCPM = BacRgrov.d Counts Per Minute W ec = GCPM-BCPM i 6.2 X 10 u X.15 X VOL (fta) TEL = Sarple Voltec in Cubic Feet IODINE: GCPM-BCPM NCO " 3 (7.9 X 105) X VUL l:t ) Page I2 of 16 + n

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POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN POINT No. 3 NUCLEAR POWER PLANT P. C. BOX 213 RUCHANAN.N.Y.10511 TELapuc N E 914 739 8200 EMERGENCY PLAN PROCEDURES PROCEDURE NO. IP-IP-1017 Prl. 2 TITLE: RECCMMENDATICN OF PROTECTIVE ACTIONS FOR THE OFF SITE POPULATION /2tq2e n/ WPlTTEN BY: s aEv: EXED 3( f E b O [/ 1.f #s[e.., II....DA3 r/, Al' S m / / PORC REVIEN APPROVED SY: h h b - DATE l /Ok2. EFFECTIVEDAlAE l \\ \\ % - 91

IP-1017/2 IP-1017 4 RECOMMENDATION OF PROTECTIVE ACTIONS FOR THE OFFSITE POPULATION 1.0 INTENT This procedure describes the methods to be used by the Shift Supervisor / Emergency Director to determine the protective actions to recommend to the offsite authorities (State and County) whenever there is an accident or condition at Indian Point that may have offsite Radiological consequences. I 2.0 DISCUSSION l I 2.1 Recommendations for protective actions to offsite agencies are found in the " Initiating Condition and Emergency Action Levels" Table. a) Initiating conditions have been appropriately corresponded to recommended protective actions. b) Where no protective action recommendations have been made it implies there is no need to take any immediate prctective actions. Standing by for any changes may be appropriate. REMINDER: When protective action recommendations are made for offsite action, appropriate steps should be taken for onsite personnel. 2.2 The decision to make protective action recommendations to the offsite population should be made by the Emergency Director (Shift Supervisor during the initial stages of an emergency). l 2.3 During the initial motification process (IP-1030) and using EP-Form #8, protective action recommendations should be relayed to offsite agencies. 2.4 To provide more detailed protective action recommendations refer to: a) Section 3.0 for Actual Releases b) Section 4.0, Based on Plant Parameters c) Sectica 5.0, Recommendations for the Food Pathway NOTE: When protective action recommendations have been made for the offsite population, the food pathway should be given consideration. 2.5 After the EOF is staffed, the decisions to make protective action recommendations to offsite agencies should be made by the Emergency Director, with input from the Radiological Assessment Team Leader. STATEMENT: The Power Authority shall make recommendations to the State on protective actions based on in-plant assessments and plant j parameters, however, the decision to initiate the recommended j protective actions is the responsibility of the State and Local authorities. i 1 i 1 of 3

IP-1017/2 3.0 ACTUAL RELEASE PROTECTIVE ACTION RECOMMENDATIONS 3.1 Do dose calculations in IP-1002 within 15 minutes. i NOTE: Dose calculations within the first 15 minutes will be based on:

1) Assumed I/NG ratio

2) Actual meteorology j

3) Actual or estimated duration of release i

i Protective actions may be based on this initial calculation (duration of the release should be actual or realistic). The calculation should be repeated when a chem sample is obtained, and protective actions reconsidered on that basis. l 3.2 Assess dose at the site boundary and recommend protective actions based on the following: - - - ~ ~' Dose at Siti Boundary I ~ (REM) Protective Actions

a)

Less than 1 Rem Whole Body No immediate action Less than 5 Rem Thyroid necessary b) 1-5 Rem Whole Body Shelter to 5 miles 5-25 Rem Thyroid Consider evacuation out to 2 miles, particularly for children and pregnant women. c) Greater than 5 Rem Whole Body Evacuate to 2 miles, and Greater than 25 Rem Thyroid evacuate affected sectors out to the. point the dose is less than 5 Rem Whole Body and 25 Rem Thyroid. Shelter affected sectors out to the point where the dose is less than 1 Rem Whole Body, 5 Rem Thyroid. Consider evacuation of children and pregnant women in this area.

3.3 When deciding to evacuate consider and weigh the following:

a) Duration of release b) Time it would take to evacuate c) Exposure persons would receive during the evacuation If it would not offer a substantial benefit to evacuate, sheltering should be continued. 1 2 of 3

2P-1017/3 4.0 BASED ON PLANT PARAMETERS: RECOMMEND PROTECTIVE ACTIONS 4.1 Protective Action recommendations made on the basis of plant parameters (no release) should be made if the following are both applicable: a) Fuel Damage and j b) Anticipated loss of Containment integrity. 5.0 FOOD PATHWAY PROTECTIVE ACTIONS i

5.1 Pasture

a) Removal-of lactating dairy animals from contaminated pasture and substitution of uncontaminated stored feed. b) Substitute source of uncontaminated water. 5.2 Milk: a) Withhold milk from market to allow radioactive decay of short lived radionuclides. l b) Prolonged milk storage at reduced temperatures following ultra-j high temperature pasturation. l l c) Diversion of fluid milk for production of dry whole milk, non-fat dry milk, butter or evaporated milk. 5.3 Fruits and Vegetables: a) Washing, brushing, scrubbing or peeling to remove surface contamination. b) Preservation by canning, freezing and dehydration or stcrage to permit radioactive decay of short lived radionuclides. 1 l

5.4 Grains

a) Milling b) Polishing 5.5 Meat & Meat Products: Consider on a case by case basis. 5.6 Other Food Products: i Process to remove surface contamination. 1 3 of 3

POWER AUTHORITY OF THE STATE OF NEW YORK INotAN POINT NO. 3 NUCLEAR POWER PLANT P. O. SCX 215 8UCH A N AN. N. Y.1 C511 TEL EPMO N E4 914 739 8200 8 EMERGENCY PLAN PROCEDURIS REv. 4 PRCCEDU?2 NO. IP-in93 TITLE: RADIOLOGICAL MEDICAL EMERGENCY j, ,A #,T W / -

4RITTEN SY:

PIVIEWED 3 w/ PCRC REVIIW If Auc - <0 ATE +5'/N APPRCVED BY: ) k b CATE /lt?){y // ~ EFFECTIVE OATE \\ -) 9 -91

IP-1021/4 IP-lu21 RADIOLOGICAL MEDICAL EMERGENCY i 1. INTENT To describe the procedure to be followed when an individual is injured and contaminated. 2. DISCUSSION I This procedure is to be used as guidance when an individual is injured and contaminated at IP-3. In all such instances, it should be the guiding rule that required medical attention must take precedence over decontamination whenever the injured's life is considered to be endangered. i. In such instances, the prompt treatment of the injury must take first consideration, however, when contamination does occur, radiological hazards cannot be ignored and should be dealt with as is feasible while the medical condition is being treated. j Rescue teams should make every attempt to stabilize the patient. If the patient is stabilized and there is no threat to life, the patient should be decontaminated (to the level normally allowed for release, with maximum 200 cpm above background) prior to transporting to a hospital. If the patient is not stabilized or his medical condition warrants immediate transportation to the hospital, initial attempts must be made at decon, or at a minimum to remove the contaminated -protective clothing and/or wrap him in a blanket to minimize the spread of contamination. NOTE: The transportation of a contaminated injured individual to the l hospital requires notification as per the Emergency Plan class-ification, Notifica*. ion of Unusual Event. Reportable as per IP-1030, i.e. within 15 minutes af ter the declaration of the Emergency Class. NOTE: Applicable telephone numbers are found on the last page of this procedure. 3.0 PROCEDURE 3.1 An employee arriving at the scene of the accident will: a) Immediately render lifesaving aid to the best of his ability to the injured individual. b) Notify (or cause to be notified) the Control Room. c) The patient should not be moved until a first aider arrives, unless conditions in the area jeopardize the patient's life. d) The time the patient is left alone should be minimized until the first aider (s) arrive. Page 1 of 11

IP-1021/4 3.2 The Control Room Operator: a) Will page and have report to the accident scene: 1. Nurse (Normal Work Hours) 2. First Aider 3. H.P. Technician 4. Shif t Supervisor 5. NPO Rever b) Will Call IP-3 security: i) Give the location of the accident. ii) Be on stand-by to escort ambulance to closest access point to patient. Be on stand-by to bring protective clothing package to ambulance workers (found in the Security Emergency Locker). c) Will call the Radiological & Environmental Services Superintendent to advise of the situation. 3.3 At the accident scene: a) The Nurse /First Aider will render life saving aid to the patient, making every effort to stabilize the patient. b) The Health Physics Technician will: i) Immediatelyestablishthesafetyoftheareaandass[st the Nurse /First Aider. ii) Respond with the Decontamination kit and continue with its use until arriving at the hespital (if required). c) All non-essential personnel in the immediate area should be in-structed to leave. d) The Shif t Supervisor should be in frequent contact with the Control Room, and coordinate the Medical Emergency Response from the accident scene. 1) If there is a possibility that the patient may require trans-portation to the Unit 1 decon facility, arrangements for this should be set in progress (IP-1022). 3.4 The patient's condition will determine one of the following: a) The need to transport directly to the hospital with initial attempts at decon. b) If a stretcher will be required for transportation to Unit 1 Decon Suite. c) The need to decontaminate at the Unit 3 decon room. Page 2 of 11

IP-1021/4 l i 3.5 If and when transportation to the hospital is required. The Control Room shall: a') Call the Verplanck Ambulance b) Call Peekskill Hospital to alert them of the ambulance arrival of a contaminated or possibly contaminated individual. t c) Call Security: i) Notify IP-3 (or Unit 2) Security of the ambulance's need for access. ii) Instruct security to direct the ambulance to the closest vehicle access to the injured individual. iii) Instruct to bring protective clothing packages for ambulance -attendents use-(found-in Security Emergency Locker) l d) In any case where transportation to the hospital is required for an injured-contaminated individual i) A Medical Respresentative should be notified as to the patientsconditionandneedtotransporttoggehospital. (If the patients life is at risk transport i nd)and make notification to the Medical Representative 2 ii) The IP-3 staff shall bring the patient to the ambulance. iii) Ambulance attendents should be provided with protective clothing & dosimetry. iv) Ambulance driver should not touch patient and should be given dosimetry. Protective clothing is not required. v) An H.P. Technician will accompany the injured to the hospital with a dosimeter charger and dosimeters for Ambulance and hospital personnel. The Decon kit should be used in transport to the hospitsi if warrented. He will remain with the patient surveying and monitoring as required. He will monitor Hospital Room before and af ter the patients arrival, and advise hospital personnel of the necessary H.P precautions. 3.6 The Control Room is to be notified by Security as soon as the patient has left for the hospital. 3.7 If the decision is made to transport the patient to a facility other l than the Peekskill Community Hospital, the Medical Support Staff and Radiological and Environmental Services Superintendent will decide l the mode of transportation to be used, and will make the necessary arrangements. 3.8 An injured contaminated individual being transported to the hospital requires notification under the Emergency Action Level Notification of Unusual Event, within 15 minutes after the Ambalance leaves the site. Page 3 cf 11

IP-1021/4 3.9 General Instructions on pages 5-9 are provided for the following personnel a. Control Room b. Nurse c. First Aid d. Health Physics e. Security Page 4 of 11

IP-1031/4 RESPONSIBILITY OF CONTROL ROOM CENERAL INSTRUCTIONS 1. Page Nurse First Aider, H.P., N.P.O. Rover & S.S. to accident scene. 2. Call RESS to advise of situation. 3. If necessary, arrange for the Unit 3 - Unit 1 transportation routes to be open (IP-1022). 4. Call Ambulance and Hospital advising them of patients possible contamin-ated condition. 5. Call Security and advise them of the ambulance's arrival, and have Security direct the ambulance to the closest vehicle access to the patient. Have Security bring protective clothing package to ambulance attendents. 6. Call Medical Representative for IP-3 to notify of the transport of a contaminated individual off-site. 7. Call the Radiological and Environmental Services Superintendent to advise of the situation. 8. Make required, Emergency Plan Notifications under Notification of Unusual Event. Page 5 of 11

&#19eM9'O RESPONSIBILITY OF NURSE GENERAL INSTRUCTIONS 1. Respond to the Control Rooms call to report to the accident scene with emergency bag. 2. Put on protective clothing and dosimetry which are necessary for Controlled Area entry. 3. Report to the accident scene or Decontamination Room per instructions of page from the Control Room. 4. Evaluate the patients condition and render emergency care as necessary. 5. Provide gross decontamination. 6. Remove the patient to the Decontamination Room Unit 3 or Unit I following the route approved by the H.P. and Shift Supervisor. 7. In the Decontamination Room, evaluate the patients condition so that you can describe findings to a consulting physician. 8. Start medical decontamination procedure. 9. If considered necessary; collect all urine, stool, vomitus, etc. and label. 10. If necessary; draw I tube blood for CBC (lavender top) mixing well, I full clot tube (red top) for chemistries, being careful to obtain from non-contaminated area. Specimens should be drawn prior to starting any I.V. fluids. 11. Start I.V. as medically indiested. 12. In the event of mass casualties initiate Triage procedure. 13. When the patient is stabilized and decontaminated as much as possible, decontaminate self and prepare to go with the patient to the hospital, maintaining life support as required. 14. Provide medical report form - radiation casuality and accompany patient to the hospital, retain duplicate copies. Page 6 of 11

IP-1021/4 RESPONSIBILITY OF THE FIRST AID TEAM GENERAL INSTRUCTIONS 1. Respond to call of Control Room to designated location with a first aid kit (and stretcher). 2. Obtain emergency equipment and Anti-C clothing from the emergen'cy cabinet in the Control Room or from the normal supply at the Control Point. Don coveralls before entering the Controlled Area. 3. Render immediate care under Health Physics direction. (Move victim from highly contaminated area - or away from source caly when it is definite that this will not create any further injury). 4. If necessary move the victim to the Unit 3 Decon Room or the Unit 1 ~~~ Decontamination Room. 5. Assist in decontamination of the victim. 6. Decontaminate self, if necessary. 7. Assist with the delivery of victim to ambulance. 8. Assist transfer of victim from ambulance to hospital. 9. Assist Hospital Radiation Casualty team as needed. i Page 7 of 11

IP-1021/4 RESPONSIBILITY OF HEALTH PHYSICS PERSONNEL GENERAL INSTRUCTIONS 1. Specify Anti-C Clothing and monitoring equipment for team members. As a minimum, all personnel responding to a First Aid call in the Controlled Area, shall don coveralls before entering. 2. Respond to scene with proper survey instruments. 3. Direct all non-injured to safe area. 4. Measure and evaluate fields. 5. Identify contaminated areas on victim and mark them. 6. Direct initial decontaminated procedures. 7. Restrict access to area as necessary. 8. Discuss with the RESS, or Shift Supervisor or Medical Representative the route to Decontamination Area, either on or offsite. Use IP-1022 for specific requirements, to transport to IP-2 Decon Room. 9. Accompany the injured to Decontamination Room and remain with him including his transportation and decontamination at the hospital or until relieved by another H.P. 10. Respond with Decontamination Kit and continue using this kit while in transit to the hospital. 11. Follow procedures as outlined for First Aid Team. 12. The H.P. will be responsible to advise hedical personnel as long as any radiation hazard exists to rescue personnel. The H.P. will monitor and advise of allowable working time exposure limits and shielding. l 13. Accompany the patient to hospital providing dosimeters for the drivers (the ambulance driver should remain behind the wheel and not come in contact with the patient. (Dosimeter charger should be brought). Provide dosi-meters for hospital personnel. 14. Survey hospital room prior and after victim is treated. Assure all unnecessary major hospital equipment out of room. (The Power Authority is responsible for all contaminated equipment replacement). 15. Inventory and bag all hospital equipment for further pick up and disposal. Page 8 cf 11

.m... 4 IP-lO21/4 SECURITY RESPONSIBILITY i GENERAL INSTRUCTIONS: 1. Direct the ambulance to closest vehicle access point to injured. f 2. Bring protective clothing package for ambulance attendents use, i 3. Notify the Control Room wl.en the ambulance leaves the site. 1 I e Ji e i ) i i 1 i i l e I 1 1 1 l i r i t i 1 i Page 9 of 11 -. ~. -

IP-1021/4 FIRST AID SUPPLIES Locations of First Aid lockers and/or kits: a) 33' elevation First Aid Room b) Security Building c) S.S. Office d) H.P. Control Point e) Outside Nuclear NPO Office l1 Locations of Stretchers: a) Outside H.P. Control Point b) Decon Room c) 33' Elevation First Aid Room d) Outside Nuclear NPO Office I 1 Locations of oxygen: a) S.S. Office b) Security Building (Security Shif t Coordinators offices) c) Security Vehicle d) H.P. Control Point l1 - -- e ) Outside Nuclear NPO Office Resuscitator: a) In the Safety & Security Super-visors possession Medical Response Kit: a) In the Safety & Security Super-visors possession Page 10 of 11

IP-1021/4 MEDICAL TRANSPORTATICN Verplanck Ar2ulance 6 HOSPITAL Peekskill Hospital Ask for Emergency Roo:n & ( Head Nurse Brookhaven Nation Request Medical Consultation ( Laboratory MEDICAL SUPPORT Patr la Russell, R.N. Indian Point No. 3 1 --ee MEDICAL REPRESENTATIVES Dr. Donald Kent 1185 Avenue of the Americas Life Extn. Institute Nes York, New York 10036 lY Dr. Jack Bratton Life Extn. Ins titute i ogic ar nvironmental Services Supt. l l l l l l l t i Page 11 of 11

POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN POINT NO. 3 NUCLEAR POWER PLANT P. C. B O Y. O t BUCH AN AN. N. Y.10511 Takspw o m st 914 739 8200 8 EMERGENCY PLAN PROCEOUPIS PRCCEOURE NO. IP-1025 FIV. 2 TITLE: REPAIR AND CORRECT!VE ACTICt! TEAMS ./ mm, ,Y. sm_- ./ / (u C s b REVIEWED BY: PCRC REV $'I y/17 CATE//d/Id 4. M 1 m -C::vE cA:E i - W - u.

IP-1025/3 IP-1025 REPAIR & CORRECTIVE ACTION TEAMS (R&CA) 1.0 INTENT To outline the procedure that a Repair and Corrective Action Team shall use to provide themselves with task briefings and with radiological l1 protection while repairing or performing corrective action on plant equipment during an emergency. This procedure should be used as guidance and the applicable REA followed. t

2.0 REFERENCES

l 2.1 RE-HPP-2.1, Radiation Exposure Authorizations 2.2 RE-HPP-3.4 Emergency HP Monitoring and Sampling 2.3 AP-4, Procedure Adherence and Use f I 2.4 IP-1047 Operations Support Center i 3.0 PERSONNEL 3.1 Repair and Corrective Action Teams should consist of at least three individuals, one of which is a Health Physics Technician. 4.0 BRIEFINGS 4.1 Task & mission briefings should be accomplished i.. the OSC or other appropriate area prior to entering hazerdous area. I a. most direct route b. proper tools c. task understanding i d. visual aids as available (maps) e. simulations i 4.2 Briefings should be lead by the OSC Supervisor or appropriate team leader. 4.3 The OSC Supervisor, Plant Operations Manager and Emergency Director should be cognizant of all Repair and Corrective action team efforts. 4.4 Obtain Shif t Supervisor approval before directing the performance of any work on safety related items. 4.5 Obtain TSC guidance for engineering rep $1r work. 4.6 Perform tasks in accordance with established procedures or follow requirements as defined in AP-4: "In the event of an Emergency not covered by an approved procedure, personnel shall take action so as to minimize personnel injury and damage to the facility and to protect health and safety". i 2. Page 1 of 2 I

IP-1025/2 5.0 RADIOLOGICAL PRECAUTIONS: 5.1 Require use of film badges, dosimeters protective clothing and other REA requirements as necessary. 5.2 Assess need for KI. 5.3 Assess need for respirators /SCBA. 5.4 Require use of KI, respirators or SCBA as necessary. 5.5 If NRC limits for exposure are expected to be exceeded refer to IP-1027. 5.6 ALARA concepts will be adhered to 5.7 Health Physics procedures RE-HPP-3.4 & RE-HPP-2.1 with respect to Emergency HP Monitoring and Sampling, and REA's will be adhered to. Standard Radiological Survey Log sheets should be used. 6.0 REPORTING REQUIREMENTS / RECORD RETENTION 6.1 Teams should maintain contact with the Operations Support Center. Sound power phones, walkie-talkies or telephones are available for this communication. 6.2 HP Survey Sheets pertaining to accident conditions should be directed to the HP Team Leader in the OSC. Page 2 of 2

POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN PolNT NO. 3 NUCLEAR POWER PLANT P. C. SCX 215 SUCH AN AN. N. Y. !C511 T at.s amo

s. 914 739 8200 0

EMERGENCY PLAN PROCEDURES PPCCEDO.M NO. IP-1027 RIV. 1 TITLE: E:tERGENCY Pt;RSONNEL EXPOSURE / / p h'/ .,,w, WRITTEM SY: ._p REVII' FED BY v PCRC REVIEW '// .' CA*E '!/'/5 APPROVED BY: dM_(*'d CA~E //e/Y1 // EFFECTIVE DA'0E l - \\ 'R - 81

IP-1027/1 IP-1027 EMERGENCY PERSONNEL EXPOSURE 1.0 INTENT This procedure describes the guidelines for emergency personnel exposure limits and authorization for exceeding the 10CFR20 criteria during emergencies. 2.0 DISCUSSION During emergency situations as classified by the Emergency Plan, it becomes necessary to have guidelines for exposure control for emergency workers as well as the line of authority for authorizing those exposures exceeding administrative and 10CER20 guidelines. The exposure levels promulgated in 10CFR20 will be adhered to under most circumstances. However, under extreme conditions authorization can be given to approve exposures to volunteers within the EPA & NCRP guidelines (below). In certain cases it is recognized extreme measures may have to be taken to protect the health and safety of the public or to save a life. The maximum levels of exposure that may be authorized are as follows: Protect Public Health & Safety: Whole Body 25 Rem Thyroid

125 Rem Life Saving:

Whole Body 100 Rem Thyroid

No Limit 2.1 In instances where prior planning time is available the Emergency Director should sign the Authorization to Receive Emergency Personnel Exposures.

2.2 In cases such as an immediate need for life saving or circumventing substantial immediate exposures to population groups, the Emergency Director should be notified and his approval for the life saving mission be granted and documented. 2.3 In extreme life saving circumstances the rescuer should be norified of the fields in the area prior to his entry, Health Physics shall determine the projected personnel dose. Authorization to enter the area may be granted by the Emergency Director, Plant Operations Manager j or the most Senior H.P. available. The Emergency Director should be j notified as soon as possible. i

KI when administered prior to exposure and during subsequent days would preclude the individual from receiving this exposure.

3.0 GENERAL GUIDELINES FOR OCCUPATIONAL EXPOSURES UNDER EMERGENCY CONDITIONS The following recommendations are given in NCRP Report No. 29, Basic Radiation Protection Criteria. These actions abould be reviewed and incorporated at appropriate times into the decisions regarding planned exposures under emergency conditions. 1 of 4

IP-1027/1 Planned Occupational Exposures Under I Emergency Conditions It is compatible with the risk concept to accept exposures leading to doses considerably in excess of those appropriate for lifetime use when recovery from an accident or major operational difficulty is necessary. Saving of life, measures to circumvent substantial exposures to population groups or even preservation of valuable installations may all be sufficient cause for accepting above-normal exposures. Dose limits cannot be specified. They should be commensurate with the significance of the objective, and held to the lowest practicable level that the emergency permits. The following is offered as general guidance. Life Saving Actions This applies to search for and removal of injured persons, or entry to prevent conditions that would probably injure numbers of people. 1. Rescue personnel should be volunteers or professional rescue personnel (e.g. firemen who " volunteer" by choice of employment). 2. Rescue personnel should be broadly familiar with the consequences of exposure. 3. Women capable of reproduction should not take part in these actions. 4. Other things being equal, volunteers above the age of 45 should be selected. 5. Planned dose to the whole body shall not exceed 100 rems. 6. Hands and forearms may receive additional dose of up to 200 rems (i.e. a total of 300 rems). 7. Internal exposure should be minimized by the use of the best available respiratory protection, and contamination should be controlled by the use of available protective clothing. 8. Normally, exposure under these conditions shall be limited to once in a lifetime. i j 9. Persons receiving exposures as indicated above, should avoid procreation for a period up to a few months. The purpose of this limit is to avoid unnecessary genetic effects whenever possible. With quality factors used in ordinary circumstances, this dose equivalent could represent exposure risk considerably above 20 times that for 5 rems spread over a year because the recovery inherent in low dose and low dose rate for the low-LET components may not be applicable. On the other hand, the risk may be considerably less than 20 times as great because the normal QF values do not apply to large acute exposures. Actions in Less Urgent Emergencies This applies under less stressful circumstances where it is still desirable to enter a hazardous area to protect facilities, eliminate further escape of effluents, or to control fires. 1. Persons performing the planned actions should be volunteers broadly familiar with exposure consequences. 2. Women capable of reproduction shall not take part. 3. Planned whole body dose shall not exceed 25 rems. 1 i Page 2 of 4

IP-1027/1 4. Planned dose of hands and forearms shall not exceed 100 rems (including the whole body component). 5. Internal exposure shall be minimized by respiratory protection and contamination controlled by the use of protective clothing. 6.' Normally, if the actual dose from these actions is a substantial fraction of the recommended limits, the actions should be limited to once in a lifetime. 4.0 PROCEDURE t 4.1 Emergency actions which would result in a persons receiving exposures in excess of NRC limits should be brought to the attentien of the Emergency Director for his prior authorization.(NOTE: See 4.6) a) NR_C-l i j i Whole Body 3.0 Rem /Qtr.:with Form 4 i 1.25 Rem /Qtr. No form 4 _{ Extremities 18.75 Rem /Qtr. i t I Skin of Whole Body 7.5 Rem /Qtr. b) Under extreme circumstances the following limits will apply: Protect Public Health & Safety: Whole Body 25 Rem Thyroid

125 Rem Life Saving:

Whole Body 100 Rem Thyroid

No Limit 4.2 Mission routes and allowable exposures shall be planned in advance.

4.3 Protective equipment such as repiratory protection and protective clothing will be' used as needed and appropriate to the mission. 4.4 Potassium Iodide may be determined necessary. 4.5 The Emergency Director will evaluate or reject the request using NRC and NCRP guidelines and the given mission. 4.6 Authorization from " Authorization to Receive Emergency Personnel N Exposures", EP-Form'#7 should be completed and signed by the emergency workers and the Emergency Director. (Except for immediate necessary responses when the Plant Operations Manager or Sr. H.P. available 'may give verbal authorization. } 4.7 The Radiological and Environmental Services Superintendent shall be made aware of this authorization in a timely manner. 4.8 The Emergency Director will document his decision in his log. 4.9 The authorization form shall be sent to, and filed by H.P. Records. I Page 3 of 4

IP-1027/1 POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN POINT No. 3 NUCLEAR POWER A'_ ANT P,0. 80X 215 SUCHANAN.N.Y.105f1 TaLapwoN as 914 739 82oo EP-Form #7 AUTHORIZATION TO RECEIVE EMERGENCY PERSONNEL EXPOSURES , SOCIAL SECURITY # IS AUTHORIZED TO RECEIVE AN EXPOSURE GREATER THAN NRC LIMITS. (IP-1027) Prior Exposure of Above Named Individual is: mrem - Recorded Prior Exposure This Quarter mrem - Current Dosimeter mrem - Total Exposure This Qtr. mrem - Total Exposure This Year REASON FOR EXPOSURE IN EXCESS OF GUIDE LIMIT'S. APPROVALS: DATE EMPLOYEE'S SIGNATLTE EMERGENCY DIRECTOR Page 4 of 4

POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN POINT NO. 3 NUCLEAR POWER PLANT P. O. BOX 215 BUCHAN AN. N. Y.10511 T EL E PMO N E: 5'4 739 8200 4-y EMERGENCY PDl! PROCEDURES PROCEOURE NC. IP-1030 REV. 4 TITI.E: E'4FPGENCY NOTIFICATION, COMMUNICATION & STAFFING { \\ Y/ f_ l 9 6 Eu:/ ou REv:reo sE.

CRC aEv: Zw -(A cS I..'cA= d e s fdM[L_,cATE / in_

APPRovZo av: ErrECTIvE [dE i-m-u s 1 4 2* -

-~ IP-1030/4 i IP-1030 EMERGENCY NOTIFICATION, COMMUNICATION AND STAFFING 1.0 INTENT To describe the process for the notification and associated communications required when any of the four Emergency classes is declared, as well as the methods which will mobilize the IP-3 Emergency Response Organization. 2.0 DISCUSSION Af ter the declaration of an Emergency (Notification of Unusual Event, Alert, Site Area or General) the Shift Supervisor (Emergency Director) will initiate and insure this procedure is implemented until he is relieved from the responsibility of Emergency Director. Persons who should may be notified of an Emergency Condition include: PASNY NR OFFSITE** J

Resident Manager
Resident Inspector
Con Edison
Superintendent of Power.
Headquarters
Westchester County
Information Officer
City of Peekskill
N.Y.O. Duty Officer
Rockland County Emergency Response Personnel
0 range County
Putnam County
N.Y.

State Dept. of Health U.S. Coast Guard Con Rail Corporation

Persons or agencies who must always be notified (NUE, Alert, Site Area, General)

Those not

are notified under the appropriate circumstances as per procedure.
- 0ffsite Agencies should be notified within 15 minutes of the declaration of an emergency classification. PASNY and Nhc notifications should be made simultanously or directly following offsite notifications.

PASNY maintains staffing consiatant with the NRC requirements for onshift, minimum (30-60 minutes) and additional support staffing during emergency conditions. Personnel required on saift are supplied by members of the Watch Organization with additional personnel available through t.he Con Edison Sr. Watch Supervisor. Emergency Personnel off-hours minimum staffing (30 to 60 minutes) shall be accomplished as follows: Alert Site Area General Personnel as Personnel on Personnel on Emergency Director Roster III Roster III determines necessary Immediate and minimum staffing should be directed by the Shift Supervisor. Off-hours call in of Emergency Personnel will be done by Security. i 1 of 16 1

IP-1030/4 3.0 PROCEDURE - NORMAL k'ORK HOURS 3.1 Notification of Unusual Event /Non-Radiological Alert (Use EP-Form #10) T 3.1.1 Shift Supervisor a) Designates a communicator b) Determines which support centers should be activated 3.1.2 Communicator a) Fill out the Initial Notification Fact Sheet, EP-Form #8. b) Call the Resident Manager's Secretary and request her to notify the Resident Manager, Superintendent of Power, Information Officer and the NYO Duty Officer using the Initial Notification Fact Sheet (EP-Form #8) and Roster #1 (EP-Form #9). l9 c) Call the con Edison Unit 2 Control Room and alert them of IP-3 conditions. d) Notify offsite agencies within 15 minutes of a declaration of an emergency using the Hot Line Telephone and the lY Initial Notification Fact Sheet (EP-Form #8). e) Notify NRC Headquarters using the direct line telephone, f) Notify the USNRC Resident Inspector. g) Keep offsite authorities (b,c,d,e,&f) informed of significent changes (approximately every 30 minutes) using the Follow-up Notification Fact Sheet (E?-Form #12) as necessary. h) Notify authorities (b,c,d,e & f) of a reduction of escalation in the Emergency Classification.

1 i) Closeout to offsite authorities (b,c,d,e,&f).

3.1.3 Personnel or Support Center Activation 3.1.3.1 Technical Assistance alone is required, use PA to announce: a) "All Technical Support Center personnel report to to the Technical Support Center" b) " Shift Technical Advisor Report to the Control Room" Page 2 of 16

IP-1030/4 or 3.1.3.2 Operational and Technical Assistance is required: Use the PA to announce: a) "All Technical Support Center personnel report to the Technical Support Center" b) " Shift Technical Advisor report to the Control Room" c) " Operations Support Center Personnel Report to the Operations Support Center" 3 or 3.1.3.3 If all Support Centers are to be activated: Use the PA to announce: a) " Emergency Directors and Radiological Assessment Team report to the Emergency Operations Facility" b) "All Technical Support Center personnel report to the Technical Support Center" c) " Shift Technical Advisor report to the Control Room" I d) " Operations Support Center Personnel Report to the Operations Support Center" lq e)""All other personnel carry on with your normal duties" I 3.2 Radiological Alert / Site Area / General (use EP-Form #11) l '1 3.2.1 Shif t Supervisor: a) Designates a communicator b) Initiate sounding site evacuation alarm and supoort center activation. l l c) Initiate calculations for dose projection I 1 l l l' l Page 3 of 16 I

IP-1030/4 3.2.2 Communicator a) Fill out the Initial Notification Fact Sheet, EP-Form #8 b) Call IP-3 Security:

i. Alert them of emergency status 11.

Direct them to restrict access to the site c) Call the Resident Manager's Secretary and request her to notify the Resident Manager, Superintendent of Power, Information Officer and NYO Duty Officer using the Initial Notification Fact Sheet (EP-Form #8) and Roster I (EP-Form #9). d) Call Con Edison Unit 2 Control Room: 1. Alert them to IP-3 conditions ii. Request offsite monitoring teams to report to the Emergency Operation Facility. e) Notify offsite agencies within 15 minutes of declaration of the emergency using the Hot Line Telephone and the Initial Notification Fact Sheet, (EP-Form #8). f> Notify NRC Headquarters using direct line telephone, g) Notify the USNRC Resident Inspector. b) Notify the U.S. Coast Guard if emergency is Radiological in nature and will impact Hudson River Traffic. i) Notify Con Rail if emergency is Radiological in nat'ure and will impact Railroad Traffic. j) Keep offsite authorities (c,d,e,f,g,h,&i) informed of significant changes (approximately every 30 minutes) using the Follow-up Notification Fact Sheet (EP-Form #12) as necessary. k) Keep authorities (a,d,e,f,g,h,&i) informed of a reduction or escalation in the Emergency Classification. t

1) Closecut to offsite authorities (c,d,e,f,g,h,&i).

3.2.3 Evacuation Alarm and Support Center Activation 3.2.3.1 Sounding Site Evacuation Alarm results in: Emergency Director & Assessment Team will report to the Emergency Operation Facility . Technical Support Center personnel will report to the Technical Support Center Page 4 of 16

IP-1030/4 . Operations Support Center personnel will report to the Operations Support Center. q l Shift Technical Advisor will report to the Control Room . Watch H.P. and Chemist will report to the Control Room unless otherwise notified 3.2.3.2 Announce over PA: a) "A emergency has been declared, all non-watch personnel report to your Assembly Area". (repeat) 3.2.4 Dose Projection Calculations: a) Refer to IP-1002 4.0 PROCEDURE - NON NORMAL WORK HOURS 4.1 Notification of Unusual Event /Non-Radiological Alert (use EP-Form #10) 1 4.1.1 Shif t Supervisor a) Designates a communicator b) Determine which support centers should be activated, and initiates the call-in of Emergency Response Personnel as necessary. 4.1.2 Communicator a) Fill out the Initial Notification Fact Sheet, EP-Fo rm #8. b) Call security and request them to notify the Resident Manager, Superintedent of Power, Information Officer and the NY0 Duty Officer using the Initial Notification Fact Sheet (EP-Form #8) and Roster I (EP-Form #9) c) Call Con Edison Unit 2 Control Room: 1. Alert them to IP-3 conditions

11. Request 1 RO immediately and if needed HP, Chem, I&C or Maintenance Techs. to report to the IP-3 Control Room, d) Notify offsite agencies within 15 minutes of declaration of the emergency using the Hot Line Telephone and the Initirl Notification Fact Sheet (EP-Form #8).

I e) Notify NRC Headqtarters using the direct line telephone f) Notify the USNRC Resident Inspector g) Keep offsite authorities (o,c,d,e,&f) informed of significant changes (approximately every 30 minutes) using the Follow-up Notification Fact Sheet (EP-Form #12) as necessary. 1 PAge 5 of 16

IP-1030/4 h) Notify authorities (b,c,d,e&f) of a reduction or escalation in the Emergency Classification i i) Closeout to offsite authorities (b,c,d,e,&f). 4.1.3 Support Center Activation & Staffing (initiated by the Shift Supervisor) 4.1.3.1 Use the PA: a) Shift Technical Advisor report to the Control Room 4.1.3.2 Technical Assistance alone is requested: a) Instruct Security.(Command Post) to call-in Technical Support Center Personnel; Appendix A, Roster II. - '~ or' 4.1.3.3 Operational and Technical Assistance required: a) Determine which support areas are needed. b) Instruct Security (Command Post) to call-in as needed from the Off Hours Personnel Call-in List, Appendix A, Roster III sections A & B.

i. HP

11. Chem iii. Technical Support iv. Operations v.

Maintance vi. I&C l l or 4.1.3.4 All Support Centers to be activated: i a) Instruct Security to call-in all personnel on the off-hours Personnel Call-in List, Appendix A, Roster III sections A & B. 4.2 Radiological Alert / Site Area / General (use EP-Form #11) 1 4.2.1 Shift Supervisor a) Designates a communicator b) Initiates sounding site evacuation alarm and support center activation. c) Initiates calculations for dose projection Page 6 of 16

IP-1030/4 4.2.2 Communicator a) Fill out the Initial Notification Fact Sheeet, EP-Form #8. r b) Call IP-3 Security: 1. Alert them of emergency status 11. Direct hem to restrict access to the site iii. Call Security (Command Post) and request them to notify the Resident Manager, Superintendent of Power, Information Officer and the NYO Duty Officer using the Initial Notification Fact Sheet (EP-Form #8) and Roster I (EP-Form #9) 1 c) Call Con Edison Unit 2 Control Room: 1. Alert them to IP-3 conditions ~- ii. Request offsite monitoring teams to report to the Emergency Operation Facility. iii. Request 1 RO immediately and if needed H..P.,

Chem, I&C or Maintenance Techs. to' report to the IP-3 Control Room.

d) Notify offsite agencies within 15 minutes of declaration of the emergency using the Hot Line Telephone and the Initial Notification Fact Sheet (EP-Fo rm #8). l1 [ e) Notify NRC Headquartes using the direct line telephone f) Notify the USNRC Resident Inspector g) Notify the U.S. Coast Guard if emergency is Radiological in nature and will impact Hudson River Traffic, h) Notify Con Rail if emergency is Radiological in nature and will Unpact Railroad Traffic.

1) Keep offsite authorities (b,d,e,f,g&h) informed of significant changes (approximately every 30 minutes) using the Follow-up Notification Fact Sheet (EP-Form #12) as necessary, j) Notify authorities (b,c,d,e,f,g,&h) of a reduction or escalation in the Emergency Classification 1

k) Closecut to offsite authorities (b,c,d,e f,g,h,&i). 4.2.3 Evacuation Alarm and Support Center Activation: 4.2.3.1 Sounding Site Evacuation Alarm results in: . Shift Technical Advisor sill report to the Control Room . Watch H.P. and Chemist will report to the Control Room unless notified to the contrary Page 7 of 16

IP-1030/4 4.2.3.2 Announce over PA: a) "A emergency has been declared, all non watch personnel report to your Assembly Area". (repeat) 4.2.3.3 Support Center Activation: a) Instruct Security to call-in personnel from the Off-hours Personnel Call-in List, Appendix A, Roster III sections A & B. b) If the Emergency Director determines additional staffing is required a listing of PASNY personnel by department can be found in Appendix A, Roster IV. j c) If the Emergency Director determines additional staffing other than PASNY personnel is necessary, he may request Con Edison personnel by calling the Unit 2 Watch Supervisor. 4.2.4 Dose Projection Calculations a) Refer to IP-1002 NOTE: There are 4 call-in rosters: Roster I, PASNY Notificat.on Telephone Numbers is a listing of those people to be called (notified) in the event of any Emergency Plan Emergency. This should be used in conjunction with the Initial Notification Fact Sheet. Roster II is the Technical Support Center staff and call-in listing. Roster III, sections A & B is the minimum staff personnel required within 30-60 minutes of the declaration of Emergency. This Roster contains Department Heads, HP, Chem., Rad. Assessment, Technical Support Center, Emergency Operations Facility, Operations, Maintenance and I&C personnel. Roster IV is a listing of PASNY personnel by department available for Call-in. Roster III should be initiated if it is a Unit 2 emergency is declared and the Con Edison Watch Supervisor requests additional n'on-watch personnel from the PASNY Shift Supervisor. (This does not include those PASNY watch personnel who will be sent to Unit 2 inmediately upon request; 1 R0, 1 Maintenance person, 1 I&C Tech, 1 HP or Chem. Tech.). Page 8 of 16

IP-1030/4 EP-Form # 8 Data & Tim 2 of Massage Wistchester Peekskill Rockland INITIAL NOTIFICATICN FACT SHEET Orange Putnam 1. NUCLEAR FACILITY PROVIDING THE INITIAL REPORT: NY State W.7 Indian Point Unit 2 @ Nine Mile Point Unit 1 Indian Point Unit 3 @ Fitzpatrick Plant PR Sec. or Securit @ Ginna Station @ Other py, SCP 2. THIS is is not AN EXERCISE. IO 3. EMERGENCY CLASSIFICATION: BA Unusual Event Site Area Emergency @ Transportation Incident B Alert General Emergency Other (Describe) Message: 4. REPORTED BY ~ Name Title 5. THERE @ has has not BEEN A RELEASE CF RADIOACTIVITY TO THE atmosphere @ ground (spill only) @ body of water 6. THE REIJ.ASE is continuing @ has terminated @ not applicable. 7. NEED FOR PROTECTIVE ACTICN: @ For information Only. There is no need for protective actions outside the Site Boundary. @ There is need for Protective Action. (If applicable, affectec areas include sectors or ERPAs) 8. RECCMMENDED PROTECTIVE ACTICNS: Not Applicable @ Evacuation within miles Shelter within miles @ Cther (or for additional information) 9. @ WIND SPEED miles per hour or meters per second, and @ DIRECTICN (from) degrees. @ GENERAL WEATHER CONDITICNS (sunny, rainy, etc. ) 10. MEANS OF CCMMUNICATICN CCNTACT, 7ERIFICATICN AND/CR ADDITICNAL INFCPRATICH IF DIFFERENT FRCM PPS-ARRANCED CCMMUNICAT!CNS CHANNELS. Telephone Number or Method Page 9 of 13

IP-1030/4 EP-Form # 9 ROSTER I PASNY NOTIFICATION TELEPHONE NUMBERS (For use by Resident Managers Secretary and Security) The personnel below shall be called and given the details of the Emergency as listed on the Initial Notification Fact Sheet. This notification to these people is mandatory and contact should be made under all circumstances. l Contacted or Work Ext. Home Phone # Beeper # Returned Call A. Resident Manager, J. Brons M B. Supt. of Power, V. Josiger g C. Info rmation Of ficer, 1ter a C. Spieler D. N.Y.0. Duty Officer ** During normal work hours, if the Resident Manaears Secretary uses any beeper number, she should call Security, to tell them a beeper was used and she should leave the message for their call-in to Security. During normal work hours it is appropriate to call the Senior Vice President l Nuclear Generation and notify him of the emergency occurrence. NOTE: When contacted by beeper these persons will call back Security and I the appropriate information should be relayed to them. The SS/ED should be notified if the above people can not be contacted. l l l 1 Page 10 of 16

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IP-lO30/4 EP-FCRM 012 j FOLLOW-UP NOTIFICATION FACT SHEET. '.. s.r 3 Westchester Peekskill The following data represent the,most current and accurate Rec and information projections and/or prognosis available at this time. Orange " U"* Time Date New York State i By Title Con Edison (IP-2) l Telephone Number Coast Guard ? ? Railroad ? 1. Location of Emergency: NRC If other comm. l I NYO paths have A Indian Point Unit 2 D Nine Mile Point Unit 1 not been est-B Indian Point Unit 3 E Fitzpatrick Plant ablished j C Ginna Station F Other 2. Emergency declared at am on (Time) pm (Date) 3. Emergency Classification: i Unusual Event Site Area Emergency Alert General Emergency l 4. Description of Initiating Event (s) : i j i i 1 5. Current Plant Ccnditions: 6. Prcgnosis for Worsening or Termination of Emergency: i 7. Emergency Response Actions Underway: 1 i I i 8. Request for Offsite Support: i i l 1 i I Page 13 of 16 1

IP-1030/4 EP-Form #12 (Cont'd)et 1.r 3 9. Type of actual or projected release and estimated duration and impact times: a) Atmospheric Release Actual Projected Date and Time Release Started Duration of Release hrs hrs Release Rate cc/sec cc/sec Noble Gas Release Rate Ci/sec Ci/sec-Radioiodine Release Rate Ci/sec C1/sec Release Height ft ft Chemical and Physical Form Meteorology Data Wind Speed MPH Wind Direction (From) Temperature Stability Class Precipitation Time of Impact (Offsite) Sectors Affected b) Waterborne Release Date and Time Release Started Duration of Release hrs hrs Volume of Release gal gal Radioactivity Concentration uci/ml uci/ml Total Radioactivity Released ci ci Radio Nuclides in Release i Chemical or Physical Form Meteorology Data Wind Speed MPH Wind Direction (From) Time of Impact (Offsite) Sectors Affected c) Surface Release (Spill) Date and Time Release Occurred I Volume of Release l Radicactivity Concentration Total Radioactivity Released Radionuclides in Release Chemical or Phycical Form Sectors Affected Page 14 of 16

IP-1030/4 l EP-Form 012 (Cont'd) 3.r 3 p3 10. Dose Measurements and Projections a) Site Boundary Actual Projected Whole Body Dose Rate mr/hr mr/hr Rem Woole Body Dose mr/hr Thyroid Dose Rate mr/hr l Thyroid Dose Rem Highest Sectors b) Projected Offsite 1 2 Miles 5 Miles 10 Miles l I Whole Body Dose Rate (mr/hr) 4 Whole Body Dose (Rem) Thyroid Dose Rate (mr/hr) Thyroid Dose (Rem) ERPA's Affected i 11. Recommended Protective Actions: I 0 / Date Time i .I I l l Page 15 of 16 4 ,,.,mv,rm, w a n-,- v ---,-e n,, -- ~- --_e,-e -~, --*-m e

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IP-lO30/4 l l OFFSITE NOTIFICATION & CCPMUNICATICN PROCEDtJRE TELEPHCNE NUM3ERS l Work Ext. Home Phone USNRC Inspector, g i l U.S. Coast Guard Port Safety Officer N Cor.solidated Rail Corp. (Conrail Chief Train Dispatcher) W IF THE HOT LINE AND NAWAS ARE NOT WORKING call, Westchester County Warning Point Putnam County Warning Point .__6________ Rockland County Warning Point Orange County Warning Point City of Peekskill Police Ccenissioner l N.Y. State Narning Point If phone lines are down, radio the State Police by means of the Security Plectron device. Request the State Police to contact the State Police in Albany and make contact with Westchester, Rockland, Orange & Putnam Counties & the City of Peekskill. IF THE NRC DIRECT LINE IS NOT OPERATIONAL, call 1. NRC Operations Center (via Bethesda Central O'fficer) 2. NRC Operations Center (via Silver Spring Central Officer) 3. Health Physics Network Line (to NRC Operations Center) g 4. NRC Cperator (via Bethesda Central Office) PAge 16 of 16

POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN POINT NO. 3 NUCLEAR POWER PLANT P, C. 80X 215 9UCHAN AN. N. Y.10511 TELsPMc N s4 914.739-8200 EMERGENCY PLAN PROCEDURES PROCEOURE NO. I?- 1040 REV. 3 TITLE: HABITABILITY CF THE CMERGENCY FACILITIES WRITTEN SY: _ . *.o . / /' i A.a O RE7:EWED BY: 74)$M cATE %v/'- l 2 CRC aEvrEw mRevEs sY: hil1~ cATE /nie. n ErrECT:vE cATE \\-s ? - %

IP-1040/3 IP-1040 HABITABILITY FOR THE EMERGENCY FACILITIES 1.0 INTENT To describe the necessary checks to determine if the radiological conditions I of the Emergency Operations Facility (EOF), the T-chnical Support Center (TSC) and Operations Support Center (OSC) are such that a move to its alternate is required. 3 2.0 PROCEDURE FOR THE EOF: l 2.1 The Emergency Director, or the Rao;ological Assistant Team Leader upon arrival at the EOF will immediately call the Unit No. 3 Control Room to confer with the Shif t Supervisor l on whether or not the EOF has been involved in the plume since the start of the emergency, and if so for how long. 3 2.2 Interrogate the Meteoclogical system at the EOF to determine if the meteorological conditions have prevailed for the past hour. 2.3 Follow guidance in section 3.0. 2.4 The EOF will be considered tenable after careful consideration of the following: 2.4.1 Fields inside and outside the EOF. 2.4.2 Meteorological Conditions at the time a) Plume direction b) Atmospheric Stability c) Weather forecast obtained from the National Weather Service at l 2\\ 5 If the decision is to move to the AEOF, notify the Control Room of the \\ decision and proceed to the AEOF. l l 2.6 Perform the same surveys of the AEOF upon arrival. 1 ~, l 3.0 PROCEDURE FOR TEE EOF, TSC, AND OSC 3.1 The. Emergency Locker should be unlocked. 3.2 If the emergency is one where radiological conditions are expected, the radiation monitoring equipment should be put in use immediatly. I 3.3 An initial survey should be made for beta and gamma fields, record results in the log book. 3.4 If at the EOF perform beta and gazma surveys outside the building. Record readings in log book. 3 Page 1 of 3

YP-1040/3 3.5 After the initial survey, an H.P. technician may be contacted (through the OSC) to discuss and/or set up further monitoring equipment. 3.6 The results of the radiation surveys are to be analyzed, and an evaluation of potential radiation hazard is to be made by Radiological Assessment personnel, Health Physics personnel or the Facility supervisor. 3.7 Upon declaration of a high radiation level or potential, the staffs upon direction of the Plant Operation Manager or Emergency Director, would procede immediatly to the Control Room, AEOF or another l designated facility. j 3.8 Check Radiological conditions frequently and record all readings ( in log book. 3.9 Monitoring for personnel should be in accordance with IP-1041. 3 4.0 HABITABILITY GUIDANCE Various factors and conditions must be considered when deciding on the Habitability of the Operation Facilities and Centers. Whole Body, beta and Iodine doses must be measured and evaluated along with the accident conditions and circumstances. The basic factor to consider is whether or not the accident is under control: is the radiological release terminated? or will stop shortly? or, if the release is expected to continue for hours or days. This time of expected release along with advantages and disadvantages of moving must be considered. Below is offered as general guidance: 4.1 Whole Body and Beta Doses Maximum acceptable total dose Fields Considerations WB~ release for a 10 hr. /3

10 mR/hr move if feasible 100 mR 300 mR 100 mR/hr move if at all possible 1000mR 3000mR 500 mR/hr move 5000 mR 15000 mR
/3 = 3 x k8 rather than 6 x WB because the lens of the eye has been factored into the calculation.

4.2 Iodine Doses From the Iodine sample taken the concentration of I-131 can be determined and from this the dose of I-131 is determined. 6 Dose = Concentration x 1.5 x 10 x hr breathed = Rem thyroid If the dose is 1 R or greater distribution of KI should be considered. If the dose is > 5 -+ 25R KI shoulu be given. Page 2 of 3

IP-1040/3 If doses are greater than 25R give KI and re-evaluate the dose to the thyroid on that basis and then make the determination of whether or not to evacuate the facility or center and relocate. 4.3 The Radiological Assessment Team should be consulted for recommendations and dose projections prior to any relocation of the Operation Facilities. i i I i 4 j l 2 Page 3 of 3

4 POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN POINT No. 3 NUCLEAR POWER PLANT P. C. 5CX 215 BUCH AN AN, N. Y.10511 Ta'.CPMo n t. 914.739 8200 R EMERGENCY PLAN PROCEDURES PROCEDURE NO. IP-indi REV. 1 TITLE: eroen.n er vesiv o v'r. er ene. tec. vin cec eepgemier. 7 i WRITTEN BY:, p.. / f <'cM.c 7 /' [ '/ REVIEWED BY: U' Ih PCRC REVIEW k 4%f A DA~E 'I 'I APPRCVED 3Y: w.b[h DATE / 3/*., c e t0 i rr.CTIVE DATE 1-t V - y1 l l l

IP-1041/3 IP-1041 PERSONNEL MONITORING FOR EOF, TSC, AND OSC PERSONNEL 1.0 INTENT To describe the procedure to be used for personnel monitoring of the support forces located in the Emergency Operation Facility (AEOF), Technical Support Center and the Operations Support Center. 2.0 DISCUSSION In the event of a Radiological Release at Indian Point it becomes necessary to staff the Emergency Operation Facility, Technical Support Center and the Operations Support Center. Technical Support Center,0perations Support Center and Emergency Operation Facility personnel shall be monitored as follows: ,3 3.0 PROCEDURE 3.1 Periodic gamma and beta field measurements shall be made (RO-2, E-530 or equivalent). These measurements are to be logged in the Emergency Log Book (See IP-1040, " Habitability of the Emergency Facility for habitability criteria). 3.2 One dosimeter and one film badge will be used to monitor the Emergency Operations Facility background and one dosimeter and one film badge l will be used to monitor the Technical Support Center background and j one dosimeter film badge will be used to monitor the Operations Support ? Center background.. 3 3.3 A control point and frisker station should be set up in order to control contamination. 3.4 An exposure record system shall be set up in a Personnel Log Book. This book shall also'b,e used as a " sign in" and " sign out" record of Technical Support Center, Operations Support Center and Emergency i Operations Faciltiy pers,onnel. >3 \\ 3.5 Personnel who leave the protected areas of the Technical Support Center, Operations Support Center and Emergency Operations Facility shall be j issued dosimetry from the Emergency Locker Stock and shall " log out" '3 and " log in" of the Personnel Log Sook. 3.6 Environmental Monitoring Teams shall obtain their own dosimeter and film badge from the stock in the emergency vehicles. 3.7 All dosimetry records will be appropriately logged in the PASNY exposure record system. 1 of 1

POWER AUTHORITY OF THE STATE OF NEW YORK lNOlAN POINT NO. 3 NUCLEAR POWER PLANT P. O. 80X 215 SUCH A N AN. N. Y.105 t 1 TsbsPMoN s2 914.739 8200 r" EMERGENCY PLAN PROCEDURES 1045 3 PRCCIOURE NO. IP-

ggy, TECHNICAL SUPPORT CENTER

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2 IP-1045/3 l IP-1045 TECHNICAL SUPPORT CENTER 1.0 INTENT To establish a procedure for the activation and operation of the l Technical Support Center. The Technical Support Center (TSC) may be } activated for an Alert Emergency and will be activated in the event of a Site Area or General Emergency.' 1 2.0 DISCUSSION The Technical Support Center serves as the facility where technical, engineering and operations personnel evaluate plant operating and accident conditions. The present TSC is the Conference Room on the 3rd floor of the Administration Building. The Technical Support Center Supervisor directs the activities of the TSC, and reports directly to the Plant Operations Manager.

3.0 REFERENCES

l 2.1 P-250 Operators Console Reference Manual for Nuclear Power Plant Supervision (Westinghouse TP044-P), Appendix A. I 2.2 IP-1040, Habitability of the Emergency Facilities 2.3 IP-1041, Personnel Monitoring for EOF, TSC and OSC Personnel 2.4 IP-1070, Periodic Check of Emergency Preparedness Equipment 4.0 INITIAL CONDITIONS l 1 4.1 The location of the Technical Support Center is the Conference Room on the 3rd floor of the PASNY Administration l' Building i 4.2 TSC STAFFING i A. No sounding of the Site Radiation Evacuation Alarm and/or off-hours: I 1. Await call or page to report to, and staff the TSC. B. Sounding of the Site Radiation Evacuation Alarm i 1. TSC personnel as designated by Roster II report to the TSC if they are inside the plant or close to the TSC, i otherwise they will report to the nearest assembly area as an "other". They then should inform the accountability officer that he/she must report to the TSC as soon as a safe route to get there is established. C. Documents, HP, and Administrative Support may be required during the course of the emergency. 3 '3 i 1. Request support from OSC. i Page 1 of 4

ZP-1045/3 2. Request support from Assembly Areas. 3. Request support from Department Supervisors. j i D. The on-duty STA will report to the Control Room and remain there as the liasion to the TSC. E. TSC Supervisor Heirarchy: f Technical Services Superintendent 3 Reactor Analyst Technical Services Electrical Engineer Technical Services Mechnical Engineer Performance & Reliability Supervisor Off-duty Shift Technical Advisor l 4.3 Communication Equipment: A. Telephones l B. Security Radio i j C. Walkie talkies 4.4 TSC Emergency locker: A. An Emergency Locker is located in the TSC. Equipment 4 available is listed in IP-1070. An equipment check of this locker is performed in accordance with 3PT-M40. 5.0 TECHNICAL SUPPORT CENTER SUPERVISOR ACTIONS 5.1 The TSC Supervisor reports to the Plant Operation Manager i 5.2 Assign Duties: A. Accountability Officer i B. Check of Radiological Conditions in TSC (IP.1040, 1041) N C. Communicator / log books N \\ D. If other personnel or expertise (documents, clerical. or HP) are required, request their assistance. E. Persons with combination to the documents' vault are so noted on a list located inside the TSC locker F. Person to access Plant Computer. 5.3 Notify the: Plant Operation Manager l Control Room (STA) Emergency Director when the TSC is staffed 3 2 of 4 4 i

I' IP-1045/3 m 5.4 Notify Wastioghouse of Emergency Condition 5.5 Notify UE&C of emergency condition if applicable 5.6 TheTSCsupervisorisresponsibleteassurehSCactivitiesare reported to appropriate individuals. This transfer of information may be assigned to the communicator. 5.7 CommunicatewithNRCofficiallocatedinTechnicasSupportCenter 5.8 The TSC is to remain operational throughout the emergency. 6.0 TSC FUNCTIONS 6.1 RADIOLOGICAL CONDITIONS: A. Follow guidanc.e in IP-1040 and IP-1041 l l

6.2 COMMUNICATOR

A. Test Communication Fquipment i 1. Telephones: a. PASNY Extensions b. Direct line telephones 3 c. Outside lines 2. Radio's ~ B. Maintain frequent contact with the Control Room via the STA. C. Report TSC activities to appropriate individuals. D. Keep log book of TSC Activities 6.3 PLANT COMPUTER: s ~ A. See Attachment 1 for instructions on accessing.*.he P-250, Plant Computer e B. See Reference 2.1 for additional information on.th'e P-230 4 7.0 REPORTING REQUIREMENTS: 'h 7.1 Plant Operation Manager 7.2 Operation Support Center ^ 7.3 Control Room through STA l l 5 7.4 Emergency Director i 7.5 NRC offical located in the TSC I 8.0 RECORD RETENTION: ( i 8.1 A log of all activities in the TSC should be kept. ,' y Page 3 of 4

I?-1045/3 ACCESS TO P-250 AND TRENDING BLOCKS The plant P-250 process computer is accessible by way of the CRT terminal and modem which are kept in the TSC. Both units are to be connected to the electrical outlet, and the modem is attached to the CRT by way of a twenty pin connection which plugs into its reverse side. a) To access the computer, turn both units to "0N". b) Dial one of the following numbers. on the direct outside line. When the carrier tone is heard, insert the receiver into the modem. c) While holding the "CNTRL" key down, type "X" This will produce a " SERVICE" request to which the user should respond by typing "0N" and then pressing the " RETURN" key. d) When the user number and password are requested type 18,TSSC and press the " RETURN" key. e) Request the computer's attention by holding tb ." key down and typing "D". The computer will respond with. question mark and a prompt signal (?) _). f) To start a Visual Trend of Block N, type "VT,,N" and press the " RETURN" key. g) To start a new Visual Trend of Block M, request the computer's attention (Step e) and type "VT,,M". Press the " RETURN" key. h) To sign off the computer, request the computer's attention but hit the " RETURN" key when you get the prompt signal. This should result in an "0PCON ERROR" message. Then, while holding the "CNTRL" key down, type "X". When the computer responds with a " SERVICE" request, type "BfE" and press the " RETURN" key. Upon receiving a j sign-off message, hang up phone and turn off equipment. l l NOTE: Blocks 21 through 40 are reserved exclusively for use by the TSC. NOTE: Information on " Visual Trend" and available blocks for trending may be four.d in the manual entitled "STA Computer Info" in ;he TSC. l 4 of 4

POWER AUTHORITY OF THE STATE OF NEW YORK INolAN POINT NO. 3 NUCLEAR POWER PLANT r

p. O. SCX 2 8 5 f *JCH AN AN. N. Y.10511 Tsi.s pmo N s4 914 739 4200

'EMERGEMCY PLAN PRCCICURES PRCCECURE 110. IP-1047

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OPEPAT10:TJ SUPPCRT CENTER (OSC) N % N je<>fh./ - WRITTEN SY: T /,- Pr/IEWED BY: sCA h> w I PCRC REVIEW I'bY%.h CATE //it/ M. APPROVED SY: ft[1 CATII//1/e, // EFEICTIVE OATE l-i 7-92 r

i IP-1047/3 I IP-1047 OPERATIONS SUPPORT CENTER (OSC) 1.0 INTENT To establish a procedure for the activation and operation of the Operations Support Center (OSC). The OSC may be activated for an Alert emergency and at all times in the event of a Site Area or General Emergency. The OSC has been designed to provide services such that personnel designated to assist in bef.nginS the emergency under physical cor. trol may be expeditiously contacted and disptached. 2.0 DISCUSSION l The Operations Support Center (OSC) is the central point from which j personnel are assigned and scheduled to accomplish a varity of 1 emergency tasks. The location of the OSC is the Maintenance Office, on the 1st floor of the Administration Building. The OSC Supervisor directs the activity of the Health Physics Team Leader, the Repair and Corrective Action Team Leader, the Chemistry / Radiochemistry Team Leader and the Administrative Support Team Leader, and coordinates these activities with the other emergency functions. The activities of each of these groups is detailed below.

3.0 REFERENCES

3.1 IP-1040, Habitability of the Emergency Facilities 3.2 IP-1041, Personnel Monitoring for EOF, TSC and OSC Personnel 3.3 IP-1025, Repair and Corrective Action Teams 3.4 IP-1070, "eriodic Check of Emergency Preparedness Equipment 3.5 IP-1027, Emergency Personnel Exposure I 4.0 INITIAL CONDITIONS 4.1 The location of the Operations Support Center is the Maintance Office. 4.2 OSC STAFFING A. No sounding of the Site Radiation Evacuation Alarm and/or off hours: 1. Await call or page to report to, and staff the OSC. B. Sounding of Site Radiation Evacuation Alarm 1. OSC Personnel as designated on Roster III, shall procede to the OSC if they are inside the plant or close to the OSC, otherwise they will report to the nearest assembly area as an "other". Then they should report to the accountability officer that he/she must report to the OSC as soon as a safe route to get there is established. 1 of 5

i IP-1047/3 { C. Personnel other than on Roster III can be requested i 4 to report to the OSC. Request this support from the Lead i Accountibility Officer. l D. OSC Supervisor Heirarchy: I i Maintance Superintendent I&C Superintendent Assistant Maintance Superintendent Maintance Contract Engineer Maintance Engineers l f If one of the above are not available to serve in this i position, the Plant Operatica Manager or Emergency Director l will designate a suitable member of the plant staff to be the OSC Supervisor. f 4.3 Communication Equipment: A. Telephones i B. Walkie Talkies l, C. Plant Paging System j D. Sound Power Phones where available l 4.4 OSC Emergency Locker: l A. An Emergency Locker is located in the OSC. Equipment available is listed in IP-1070. An equipment check of this locker is performed in accordance with 3PT-M40. 5.0 OPERATIONS SUPPORT CENTER SUPERVISOR ACTIONS 5.1 The OSC Supervisor reperts to the Plant Operations Manager. 5.2 Assign Duties: 4 A. Accountability Officer B. Check of Radiological Conditions in OSC .i C. Communicator / Log book D. Team Leaders 1. Health Physics Team Leader 2. Rapair & Corrective Action Team Leader l 3. Chemistry / Radiochemistry Team Leader 4 Administrative Team Leader (call-in) 5.3 Notify the: Plant Operations Manger Control Room Emergency Director when the OSC is staffed. 7 i Page 2 of 5

IP-1047/3 i 5.4 The OSC Supervisor is responsible to assure OSC activities are reported to appropriate individuals. This transfer of information task may be assigned to the communicator. l t 5.5 If other personnel or expertise, including clerical staff, are needed in the OSC, telephone or page them to report to the OSC or locate them through the Lead Accountability Officer. 5.6 Dispatch teams under the guidance of the Plant Operations Manager and IP-1025, Repair and Corrective Action Teams. l 5.7 The OSC is to remain operational throughout the emergency. j 6.0 OSC FUNCTIONS

6.1 COMMUNICATOR

l A. Test Communication Equipment i a. Telephones b. Plant Paging l c. Walkie Talkies B. A log of all activities in the OSC should be kept. C. Assuring appropriate personnel are kept abreast of plant conditions, survey results, and team results 5 using the following as guidance: 1. Health Physics Results Emergency Director & Radiological Assessment Team Leader in the Emergency Operations Facility Plant Operations Manager & Shift Supv. in the Control Room EP Team Leader Watch HP Repair & Corrective Action Teams Operations Support Center 2. Chemistry Results Emergency Director in Emergency Operation Facility Plant Operations Manager & Shift Supv. in the Control Room Chemistry Team Leader Watch Chemist Technical Support Center Operations Support Center 3. Repair and Corrective Action Team Results I Emergency Director in Emergency Operation Facility l Plant Operations Manager & Shift Supv. in the Control Room Technical Support Center Operations Support Center 6.2 RADIOLOGICAL CONDITIONS: A. Follow guidance in IP-1040 and IP-1041. .) Page 3 of 5 i y r-, w ,__.,__-,,,_,,__,m_ .w-

.. - _ - _ __~ - -__-- - ~.=__ _=.- - _--- _. t IP-1047/3 J I I 7.0 TEAM LEADERS 7.1 Senice members of the HP, Chemistry, Maintance and Administrative Support Groups shall be designated as Team Leaders. i t I I 7.2 Health Physics Team Leader directs the following functions: l A. OSC Support: 1. Monitoring OSC habitability 2. Provides dosimetry for the OSC & OSC Personnel i 3. Radiologically controlling the OSC area is required. i B. Radiological Support: 1. Radiation & Contamination Surveys (in-plant & on the plant site) 3 2. Issuance of radiation monitoring instrumentation and dosimetry devices 3. Support of ist aid, fire fighting and repair & corrective i action teams. 4. Dispatches Decon teams, survey teams and instrument teams (TSC, CR, EOF) 5. Works with the Radiological Assessment Tear Leader on i 1 mission dose estimation. 6. Works with the Radiological Assessment Team Leader on in-plant status updates on radiological conditions. 7. If it is expected that NRC exposure limits may be exceeded, refer to IP-1027. l l C. Reporting Requirements: l 1. Reports to OSC Supervisor 2. Plant Survey Information should be relayed to as the OSC Supervisor, and he incurn should assure the appropriate people are kept informed. NOTE: The watch HP reports to the Shif t Supervisor but should maintain contact with the H.P. Team Leader. 4 3. Personnel. overexposure should be reported to the OSC Supervisor, Emergency Director and the Radiological Assessment Team Leader. 4 Communicate with NRC H.P. official in Operations Support Center i D. Record Retention: 1. Radiological Survey Leg Sheets l l 2. Personnel dosimetry records 3. Over exposure information (EP-Form #7) 4. Personnel Contamination Check (EP-Form #14) 5. Skin Decontamination Record (EP-Form #15) k a Page 4 of 5 1 1 m .,m..- ..,...,,,_,-m.

IP-1047/3 7.3 Repair and Corrective Action Team Leader directs the following functions: A. Pre-mission briefings B. Assures compliance with IP-1025 C. Repair & Corrective Actions: 1. Obtain and provide supplies, tools and equipment to repair / corrective action / maintenance teams. 2. Accomplishment of repairs of physically accessible systems as directed by the Operations Support Center i Supervisor. 3. Accomplishment of corrective actions to, or maintenance i of, equipment as needed to mitigate or improve the i emergency conditions. 4. Assessment or verification of plant damage to accessible equipment. E. Reporting Requirements: 1. ' Reports to OSC Supervisor 2. Report Repairs & Corrective action team results to the OSC Supervisor. F. Record Retention-t 7.4 Chemistry / Radiochemistry Team Leader directs the following functions: A. Sampling of plant fluid systems B. Analysis of plant fluids j C. Analysis of radiological samples D. Reporting Requirements: 1. Reports to OSC Supervisor 2. Reports Chemistry / Radiochemistry team results to the OSC Supervisor. i NOTE: The watch chemist reports directly to the j shift Supervisor but should maintain contact with the chemistry team leader. l E. Record Retention: A. Chemistry data sheets 7.5 Administrative Support Team Leader directs the following, functions: l A. Clerical support including typing, word processing and i reproduction, which may require the use of offsite facilities. B. Wa'rehousing operations including cataloging, retrieval and supply i. of material to emergency response operations j C. Provision of human factors requirements such as food, rest areas and janitorial services. l l i i t l l Page 5 of 5

.= _. .= 9 POWER AUTHOR!TY OF THE STATE OF NEW YORK INDIAN POINT NO. 3 NUCLEAR POWER PLANT P. C. SOX 215 SUCH AN AN. N. Y,10511 TsLapwows: 914 739 4200 8 EMERGENCY PLAN PROCEOUFIS PROCEDUPI NO. IP-1050 PIV. 3 TITLE: ACCOUNTABILITY / WRITTEM SY:. n-e & a r # REVIEWED B h' PCRC REVIEW '[I

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Si:3-aL- __;L .u-wa+ -L --.w+ b-4 2 4 IP-1050/3 IP-1050 ACCOUNTABILITY 1.0 INTENT This procedure is used during an emergency to assure IP-3 personnel are accounted for. 2.0 DISCUSSION When the evacuation alarm sounds all non-watch personnel will report to their assigned assembly areas. A list of all persons missing and/or at an' assembly area other than their' assigned one will be given to the Lead Accountability Officer and these lists will be cross checked to determine who is actually missing. The Emergency Director and Lead Accountability Officer will discuss Search and Rescue Team mobilization. NOTE: Evacuation Route Maps are posted throughout the site. These maps denote evacuation routes as well as identify assembly areas. 3.0 WATCH & NON-WATCH PERSONNEL PROCEDURE 3.1 All non-watch personnel will report to their assembly areas or to the nearest assembly area when the Radiation Emergency Evacuation Alarm sounds. Assembly Area locations are denoted by large orange signs with blue letters reading " ASSEMBLY AREA". The larger assembly areas have been further subdivided into department sections and personnel shall report to their respective sub areast (The switch board should be trans-ferred temporarily to Security when the operator goes to her Assembly Area, then reopened when appropriate.) 3.2 The PASNY assembly areas and who reports to them are as follows: (See page 6 for the site map with PASNY assembly arts locations) (L) Training Trailer (Office Area): Training per31nnel, personnel who are in Training classes, Onsite ?eview Committee, or persons in the immediate vicinity. (K) Admin. Service Bldg. (2nd Floor Lunch Room) Admin. Building Personnel, floors 2, 3 & 4. (C) Machine Shop (15' Elevation): All non-watch, maintenance and f construction personnel within the security fence. First floor (maintecance) personnel should use this as their assembly area. s (G) Construction Conference Trailer: PASNY Construction personnel, contractor personnel and all other personnel in the immediate area and outside the security fence. (J) Warehouse: (Office Area) Warehouse personnel and personnel in immediate vicinity. Page 1 of 6

IP-1050/3 (H) Con Edison Service Center, West Storeroom Area: All personnel will eventually assemble here if evacuation of the site is necessary. t 3.3. Each unit Watch or Shift Supervisor shall account for their personnel. 3.4 Security shall account for their own personnel. 3.5 Technical Support Center (Roster II) personnel should report to the TSC and it is their assembly area. If a TSC person is at another Assembly Area they should report in, and then go directly to the TSC. One individual will assume responsibility for accountability in the TSC. Missing individuals shall be reported to the Lead Accountability Officer when she/he calls. 3.6 Designated Operation Support Center personnel (as designated on Roster III) shall report to the Operations Support Center, it is their assembly area. If-an-0SC designated individual is at another assembly area they should report to that area and then go directly to the OSC. One individual will assume responsibility for accountability in the OSC. Missing individuals shall be reported to the Lead Accountability Officer when he/she calls. OSC personnel who are on watch shall remain on watch and not report directly to the OSC. 3 3.7 For accountability purposes, persons reporting to the EOF shall notify their secretaries that they are going to the EOF. 4.0 AREA ACCOUNTABILITY OFFICERS 4.1 Each assembly area has a designated Area Accountability Officer and l alternate. i 4.2 The Area Accountability Officer shall survey the assembly area with an ionization chamber instrument, readings above 10 mR/hr shall be { reported to the OSC Supervisor, and an H.P. will be dispatched to l that area for more extensive surveys, and relocation of those i' persons in that Assembly Area shall be assessed. 4.3 The Area Accountability Officer has a master list of personnel by department who should be reporting to each designated assembly area. i 4.4 To assist the Area Accountability Officer in accounting for personnel, First Line Supervisors will account for their personnel and report any missing individuals to the Area Accountability Officer. i 4.5 Construction has assigned, where appropriate, Accountability Officers j for their personnel. The Construction Accountability Officers should j report any missing individuals to the Area Accountability Officer. I 4.6 On the master list of personnel, the Area Accountability Officer should l note whether or not an individual is present or missing or an extra. i a Page 2 of 6 .l

IP-1050/3 NOTE: Persons should only be accounted for if: 1. is visibally present 2. on vacation 3. is on travel or not onsite that day 4. on another shif t If the person is " thought" to be out to lunch it should be so noted. 4.7 After the Area Accountability process is complete the Area Accountability Officer in charge should receive a phone call from the Lead Accountability Officer. At that time those persons missing and extra should be reported. " Lunch" persons should also be reported as such. i 4.8 Area Accountability Officers should report any " late reporters" as soon { as possible to prevent unnecessary search & rescue team efforts. t 4.9 For Accountability problems that need immediate attention the Area I Accountability Officer should phone the Lead Accountability Officer. 5.0 LEAD ACCOUNTABILITY OFFICER 5.1 The Lead Accountability Officer has a master list of all personnel by Accountability Area and by Department located on the Officer Managers Book Shelves. 5.2 The Lead Accountability Officer shall call each of the Assembly Areas to obtain their respective missing and extra lists. (5 PASNY Assembly Areas, TSC, OSC, Security, Watch) 5.3 The Lead Accountability Officer shall make a cross check of missing and extra personnel. I 5.4 A final call should be made to each assembly area to see if there are l any " late reporters". 5.5 A final missing persons list is developed. 5.6 If persons on the missing list are considered to be actually missing within the plant, those names should be given to Security to have a badge i check run on them to determine if they are indeed in the plant. 1 5.7 The Lead Accountability Officer must discuss Search & Rescue Operations with the Emergency Director. It is only the Emergency Director who may authorize a Search & Rescue effort. t NOTE: The Con Edison Chief Accountability Officer should be called. l This is to check if PASNY pecple are at Con Ed or to report I any Con Ed people reported as extras at PASNY. l t 5.8 If necessary the Emergency Director shall discuss Evacuation Routes with the Lead Accountability Officer and the LA0 will transmit that information to all the assembly areas. 5.9 If evacuation is to the con Ed Service Center Building, a re-accounting of personnel should be performed in arrival. i l Page 3 cf 6

IP-1050/3 6.0 0FF HOURS g I 6.1 Upon hearing the Evacuation alarm all non-watch personnel should j assemble at the nearest assembly area. 6.2 The Security Shift Coordinator is the Lead Accountability Officer during off-hours. 6.3 Responsibility for Assembly Area habitability surveys shall be assumed t by the Shift Supervisor and the Watch Health Physics technician or other l designated responsibilities. I 6.4 The Lead Accountability Officer should call each Assembly Area to i gather a list of persons on-site. (Esch Assembly Area, Control Room, OSC, TSC, for Watch Personnel, and assure Security personnel are ,1 accounted for). 6.5 If persons are thought to be missing a Security Badge check should be run to determine if they are indeed in the plant. 7.0 SEARCH & RESCUE 7.1 A Search and Rescue effort must be discussed with the Emergency Director I (the Shift Supervisor is the Emergency Director during the initial stages of an emergency). It is only the Emergency Director who can authorize a i Search and Rescue Effort. i 8.0 PERSONNEL CONTAMINATION CHECK (IP-1060) 8.1 Persons leaving restricted area or those areas suspected to be 3 contaminated should be checked for contamination. 8.2 Prior to leaving the re-assembly area at the Con Edison Service Center building, personnel should be checked for contamination. '.) i 1 Page 4 of 6 1 I

f IP-3 ASSENDI.Y AltEA r. INACUATION ROUTES ^ ' ' ' ' 8N'OAD h/A Y m P .i Ma/n l \\ } ~ Dire,4/K/* COA! ED ([ PASA/V FN TR'ANCE (gif. SEPV/CE S G EK k m,_,_a_ -> p.f.s j C; A 1*E \\ .-g _n-n.-.9. q-, y9 J ,g - n--,s - n-- w-x-n - K-n 4 ( o -TAM /t/Ts [44*--4;.h,.1 V DasEt's'Antw F BiR s' BLOQ. { f) f Ws~rg., p- .a S MUL A rOit 5 / f " Conry. rcron-D=' r au.sg h as / ~ e / ( \\ s o UN F _l YAMS P - Pue,<isc A aeas A [\\ U# IIP"I I ' ' ) \\, som.g em_a.,_ x-x-x-Fe ncisa m3a un k. "*M6 ( WM frem bw) 3, gECURITY UNIT I 2 l o PASNY V k $%EmBCY _f ) ru ' /NE TVA*L5/NE ADHw / .? A -~. $. :- g@ + n m susu ~ ~ ~ ~ ~ ~ ~ me y(1g ~"* E vseo.t. J Recy. S b4< (ul d . S j (P~ f< %'"x i ufuse s-w .s < _ _ <__< INDIAN POI NT C Machine Shop, IS' elev. SITE PLAN tp HUDSON RlVE R J Warehmse Office K 2nd Ploor Cafeteria I, Training Trailer G Hurnu & Roe Conference Trailer D hi con Edison Service Center Building

IP-1050/3 ACCOUNTABILITY AREA TELEPHONE NUMBERS C. Machine Shop 15' Elevation l G. Construction Conference Trailer M J. Warehouse M K. Administration Service Building g (2nd Floor, Lunch Room) L. Training Trailer Complex Control Room M Technical Support Center t Operations Support Center g Emergency Operations Facility t Security Seargant M H. Con Edison Service Center, West Storeroom Area M Lead Accountability Officer: Ext. rmal working hours Ext. non-normal working hours Con Edison Lead /.ccountability Officer: l l Additional Facility Telephone Numbers can be found in Appendix B. l \\ l l l Page 6 of 6

POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN POINT No. 3 NUCLEAR POWER PLANT P. C. SCX 215 SUCH AN AN, N. Y.10511 TaksemoN ei 914 739 4200 8 EMERGENCY PLAN PROCECURES PROCEDUaS NO. IP. 1054 gy, 1 TITLE: SEARCH & RESCUE TEAMS ?. ) />x n. > - uR nzu s1:y I,~y Oa J azv::ata av: PcRC azv::a 7M(u.I. ex:rda/n JdJs/3_.ex:si/[iln m RevEm av ll Ertze::vz ca:E t-a-u

--_-. - ~ IP-1054/1 i IP-1054 SEARCH AND RESCUE TEAMS 2 1.0 INTENT l 4 l To outline the procedure that search and rescue teams shall use for radiological protection when dispatched for immediate access into j controlled areas to search for individuals who have not been accounted l for in the early stages of an emergency. 2.0 DISCUSSION i Search and rescue teams would be dispatched under the direction of the Emergency Director. This team is made up of at least two individuals, one of whom is an HP or trained in the use of radiatior. survey instruments. It is assumed search and rescue teams would be needed in the early stages of an emergency, perhaps to enter radiologically controlled and hazardous i, portions of the plant. Radiological precautions at all times should be j observed. If radiological coaditions are unkn;wn, assume and provide t for the worst. This procedure gives basic guidance as to radiological r precautions which search and rescue teams should follow. i

3.0 REFERENCES

3.1 IP-1050, Accountability 3.2 IP-1027, Emergency Personnel Exposure f 3.3 RE-HPP-2.1, Radiation Exposure Authorization 4.0 PROCEDURE 4.1 The Emergency Director would authorize a search and rescue team effort after: A. Confering with the Lead Accountability Officer 1. cross check of areas j 2. security badge check 3. last time & place individual was seen i B. Reviewing overexposure potential for search and rescue j team members. 4.2 If NRC overexposure limits for lifesaving (100 R Whole Body, no limit for Iodine) are expected to be required refer to IP-1327. 4.3 Each search and rescue team shall be made up of at least two individuals, one of whom is an EP or an individual trained in the use of radiation survey instruments. I 1 of 2 .-----,s.,.-., - - - -. ,,_._.-,,,.,--_y ,--.m .yy w

IP-1054/1 I 4.4 RADIOLOGICAL PRECAUTIONS i 4.4.1 If radiological conditions are known dress in accordance with the existing REA. 4.4.2 If radiclogical conditions are unknown, consider the worst I and wear as a minimum: 2 pairs coveralls, plastic outside double shoe covers 2 pairs gloves, plastte outside full hood SCBA

4.4.3 Dosimetry

0-5 R 0-200 R film badge /TLD 4.4.4 Survey instruments: high range ion chamber measure for beta and gamma j 4.4.5 Consider the need for: j KI extremity dosimetry I additional whole body dosimetry additional eye protection for high energy betas ( i 4.5 The search and rescue team should maintain contact with the i Emergency Director. Sound power phones, radio or telephone. i 4.6 The HP should be the first one through to survey the area. 'N 4.7 Notify the Emergency Director when the person (s) or accident victim is located and/or removed from a'high radiation area. If the person is injured, do not move himsunless fire or other conditions jeopardize his safety or if the vic' tim could receive a whole body dose of 1 Rem or more before Medical assistance arrives. If there is an j obvious indication that movement of the victim would jeopardize his 5 life, he should not be moved unless he could receive a whole body }* dose of 200 Rem or greater. I i i Page 2 of 2

POWER AUTHORITY OF THE STATE OF NEW YORK INQlAN PolNT NO. 3 NUCLEAR POWER PLANT P. O. SCX 215 EUCHANAN.N.Y.10511 ?Ekspwomta 914 739 8200 DIERGENCY PLAN PROCEOURES PROCECURE NO. IP-1056

p2y, 1

TITLE: DIRECTING FIRE FIGHTING PERSCNNEL IN CONTROLLED AREAS 9 7 V/ W f/, $ , S9 s i, WR! m N BY: (,f u hw~ ./ / n REVIEWED BY: ~ PORC PIV!EW 7/ _.>t. CATE 1// $/17-APPROVED 3Y: ,[ DA3 /[3/syr / IFFECTIVE CATE \\ -n 4 t L T

IP-1056/1 IP-1056 DIRECTING FIRE FIGHTING PERSONNEL IN CONTROLLED AREA 1.0 INTENT To provide a procedure that describes the duties of the H.P. Technicians and the Security Force for handling Fire Department personnel who respond to a fire in the Coatrolled Area. 2.0 PRECAUTIONS AND LIMITATIONS 2.1 Fire Department personnel are not required to wear our Anti-C clothing when they fight a fire in the Controlled Area. 2.2 All Fire Department personnel who enter the Controlled Area will be provided with a dosimeter and film badge by a member of the Security Force-or the H.P. Department. Dosimeters and badges may be obtained from the supply kept at the Command Guard House. KI may be issued if directed by the ED or RESS. 2.3 All Fire Department personnel entering the Controlled Area are re-quired to have their person, clothing and equipment checked for con-tamination betore they leave the Controlled Area for the last time. Repeated exits from the Controlled Area without frisking are permitted in order to prevent interference with fire fighting efforts. If possible, the outside area surrounding fire fighting equipment should be roped off for contamination control. 2.4 All clothing and equipment not permitted to be removed from the Con-trolled Area, due to contamination, is to be inventoried for compensation. 2.5 Every effort will be made to keep exposures to Fire Department personnel As Low As Reasonably Achievable. 2.6 If it became necessary for the personnel fighting the fire to exceed the Power Authority radiation exposure limits, (300 mrem per quarter for whole body exposure or the 40 hour M.P.C. amount) the H.P. Tech. shall notify the Radiological & Environmental Services Superintendent (RESS). 2.7 Do not enter heavy smoke areas without a self contained breathing apparatus (SCBA). 3.0 PROCEDURE 3.1 Security Force a. Direct firemen to fire area. l 8 b. Bring dosimeters and film badges from the supply at the Command guard House, to the entrance point where the firemen are being admitted to the Controlled Area. 1 of 4

IP-1056/1 c. Issue a dosimeter and film badge to each fireman with instructions to wear them underneath his raincoat to protect them from water damage. NOTE: The name of the individual and his film hadge number shall be recorded by the H.P. after the fire has been extinguished on EP-Form #13. I d. Issue a KI tablet to each fireman entering the controlled area if directed by the ED or RESS. e. It is allowable for the firemen to enter the Controlled Area without wearing anti-C clothing. 3.2 H.P. Technician (he should issue dosimetry & possibly KI if security has not already done so). a. Make field measurements at the fire scene and notify the officer in charge of any restrictions you are imposing on his personnel. b. Set up an air sampler (particulate and iodine) as close as practical to the firemen. If a CAM is available or may be obtained without detracting from your duties at the fire scene set it up to alarm at M.P.C. levels (9X10-9 uCi/cc). c. Evaluate the potential for the spread of high levels of radio-active contamination from the use of water by the firemen. 3. Shot 1d airborne activity, as seen by the CAM, read 9E-9 uCi/cc request isotopic analysis from the Chem. Tech. on the particulate and iodine filters:

1. Notify the officer in charge of any re-strictions you are imposing on his personnel due to the airborne activity.

2. Instruct all personnel to wear respiratory protective devices (i.e.: Self Contained Breathing Apparatus (SCBA), Chemox or respirator) depending on their proximity to the fire and their duties. SCBA, would be used for 02 deficient atmospheres, e.

When personnel have been involved in an airborne atmosphere, where they reached or exceeded the 40 hour M.P.C. amount as determined from counting the air sampler filters, and disre-garding any protective device they have worn:

1. Check the areas of the eyes, ears, nose and mouth with an RM14/HP-210 or equivalent G.M. survey instrument. This check should be performed in a background of 300 cpm or less.

2. Any reading 200 cpm or (in 1 above) greater above background should be further investigated by means of smears.

3. These individuals should then be referred for whole body counting.

4. The RESS shall be notified, and take the necessary action.

2 of 4

..m____.__._..____.____..____..._ t l l IP-1056/1 i I I i f. Check all fire Dept. personnel, their clothing and their equip-l l ment for contamination befote they leave the Controlled Area. l 4 t j g. Record individuals nar.e, and film badge / number upon exiting the fire scene using EP-Form #13. j i I h. Check the fire truck and outside areas for contamination. i i. Assist and supervise the decontamination of any fireman and/or personnel that becomes necessary. Refer to liPI-6.41 for decon-tamination instruct. ions. I I j. Supervise the decontamination of any equipment or protective t gear. Make a list of all items you are not allowing to leave the Controlled Area as well as the items you have checked okay. t l i { k. If CAM was used remove the. chart and incorporate with the job REA { data. Indicate instrument range, if appropriate, on the chart. I 4.0 REPORTS 4.1 Health Physics shall log the events of the fire from a radiological l standpoint for filing with the REA related to the job. 4.2 Record exposures on EP-Form #13. i \\ I 4.3 List all confiscated materials and radiation levels. i i i t I i l l l 4 i t 1 i a i 4 1 i i l l 1 1 i I i c l i I t. I f 3 of 4

IP-1056/1 EP-Form #13 FIREMEN EXPOSURE RECORD DATE H.P. TECH. FII.M DOS BADGE READ INDIV. NAME SOC. SEC. NO. NUMBER MREM REMARKS i [ 4 of 4

POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN POINT NO. 3 NUCLEAR POWER PLANT P. C. SOX 215 BUCH AN AN. N. Y.10511 TELepwoM E: 914 739 8200 8 EMERGENCY PLA:I PROCEDURES PROCEDURE NO. IP-1058 REV. 2 TI"7 E EARTHQUAKE EMERGENCY .... ~- 7 ~ WRITTIN BY-9 .z _, F / Vp' ~ Fr/IEWED BY: Yl./M Cm PCRC REVIEW r./. -? - CATE/ APPRCVED 3Y:' b b[ b s DATE /fi3 ff /f EFFECTIVE CA!" '-ih*-<1 I l

IP-1058/2 f IP-1058 EARTHQUAKE EMERGENCY l.0 INTENT & DISCUSSION This procedure highlights the actions which atould be followed in the event of an earthquake near or at the Indian Point site. Whether or not the seismic event is actually felt at Indian Point or if reported in the local area (within range of the microseismic monitoring network, approximately the 4 county area), it falls under the offsite reporting requirement of the Emergency Plan (within 15 minutes of the event or notification of the event). Plant personnel actions are only taken when an actual seismic d event is experienced at the site. Emergency Procedure PEP-S-1, Seismic Monitoring Equipment Actuation specifies minimum assessment aad responsive action requirements in the event of a seismic monitoring equipment actuation. It is not the intent of this procedure to substitute for the Radiological Emergency Procedures if the consequences of an earthquake create a radio-i logical hazard. Applicable procedures for that type of radiological emergency should be followed in addition to those contained in this procedure.

2.0 ASSESSMENT

EQUIPMENT Unit 3 is equipped with a seismic monitoring system that records a. l vibrations caused by strong local earthquakes or similar events. Use of the data received from the system enables operating personnel to determine what course of action to take following an alarm or earthquake. J Briefly, the system consists of two SMA-2 Strong Motion Accelerographs located on the 46 foot and 100 foot elevations in the Vapor Containment, three Peak Shock Recorders located on the 46 foot elevation and Peak Recording t.ccelerographs installed on

31 RCP,
31 SG and the Pressurizer.

1' The Unit 3 Control Room is equipped with the appropriate alarm panel and recording devices. b. In addition to the installed monitoring system, the National Warning System (NAWAS) telephone installation in the Unit 3 Control Room can, also provide earthquake warning information and verifications, c. If the earthquake is not strong enough to record on site monitoring equipment, the Control Room should be notified by Unit 2 Control Room, NAWAS, Woodward Clyde or another source as to the magnitude and location of the event. The Control Room, should make the required off-site notifications within 15 minutes. 4 l Page 1 of 2 I

IP-1058/2 i 3.0 PROCEDURE 3.1 If the earthquake is strong enough to be recorded on seismic monitoring equipment: a. See PEP-S-1, Seismic Monitoring Equipment Actuation i b. Make appropriate Emergency plan notifications as per IP-1030 c. Assure Con Edison Unit 2 is notified of the magnitude as recorded on IP-3 equipment. 1 3.2 If the earthquake is experienced in the general area, but not strong enough to record on site monitoring equipment: a. The Control Room would be notified via the Seismic Consultant (Woodward Clyde), Unit 2 Control Room, NAWAS or some other source. b. Confirm the notification of an earthquake event by calling Woodward Clyde or the Unit 2 Control Room if the message came from a source other than them. ) c. If confirmed, make the appropriate Emergency Plan Notifications under Notification of Unusual Event as per IP-1030. NOTE: The Seismic Consultant Woodward Clyde. (Appendix B) l 1 i i 1 i i i 4 j Page 2 of 2 1 - - =, - -

POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN POINT NO. 3 NUCLEAR POWER PLANT P. O. SOX 215 EUCH AN AN. N. Y.10511 T EL E PM c N r. 914 739 4200 8 EMERGENCY PLAN PROCEDURES PRCCEDURE NO. IP-1060 REV. 2 TITLE: PEFSCtMEL RADIOLOGICAL CHECK AND DECON*Pf4TMATIOM / // WRIT *EN SY:. /c M. c /'t/ ) Fr/IINED BY: J.a DATZ /da/f t-PCRC Pr/IEW Il e a c ut l t i APPROVED BY: '[ DATE /// v/y2 /\\ ~~ EFTECTIVE DATE \\-t<RL I i

IP-1060/2 IP-1060 PERSONNEL RADIOLOGICAL CHECK AND DECONTAMINATION 1.0 INTENT To describe the emergency condition methods of checking personnel for contamination and their subsequent decontamination when required. 2.0 DISCUSSION Determination of personnel contamination levels, supervision of personnel decontamination and subsequent checkout will be performed by members the Health Physics staff. Resolution of problem cases will be handled by the Radiological Assessment Team Leader (RATL). 3.0 DECONTAMINATION FACILITIES 3.1 Decontamination facilities available include: 1. Health Physics Control Point l 2. Decon facility on the 4th floor of the Admin. Building 3. Con Edison Service Center Building i 3.2 Decontamination supplies are available to each location. a 4.0 PRECAUTIONS 4.1 Decontamination will be performed in accordance with RE-HPI-6.41 4.2 Chemical decontamnation should only be performed with medical supervision or under direction of a knowledgeable individual. 4.3 Clean is considered less than 200 cpm above background. 5.0 PROCEDURE 5.1 Personnel will be monitored for contamination: a. when leaving restricted areas b. when leaving areas suspected to be contaminated c. assembly areas if suspected of contaminated. d. re-assembly areas t 5.2 Records of personnel monitoring will be maintained on the Personnal Contamination Check form, EP-Form. #14. L Page 1 of 4

= IP-1060/2 5.3 Records of personnel decontamination will be maintain'ed on the Skia Decantamination Record form, EP-Form //15. 5.4 Documentation of all monitoring and ~ decontamination activities will be directed to the Health Physics Team Leader in the OSC for eval,tation and retention. i 5.5 H.P. Control Point decontamination and Decon Facility decontamination will be performed in accordance with RE-HPI-6.41. I i 5.6 Decontamination at the Con Edison Service Center: I; 5.6.1 Determine the contamination level category by using a frisker with an HP-210 G.M. tube to check the individual. The categories are as follows: Clean - less than 200 cpm above background a. b. Low level - less than 10,000 CPM above background l c. High level - 10,000 CPM above background or greater 5.6.2 For individuals contaminated in the Low Level category use the Service Center locker room shower. This amount will not exceed the limits specified in 10CFR ?0.303 for discharge into a sanitary sewage system. a. Shower using non-alkaline soap, such as phisoderm, if available and lukewarm water. Keep contamination away from non-contaminated parts of the body. If practical wash off high levels of contamination first. J b. Recheck individual after shower. Level: less than 200 cpm above background are considered uncontaminated. c. If the levels are still greater than 200 cpm above I background have the individual re-shower and then re-check. d. If the individual remains contaminated after (3) showers (over 200 cpm above background) consult the Radiological Assessment Team Leader. 5.6.3 For individuals contaminated in the High Level category use the portable Radioisotope Decontamination list located in the Medical Bureau Office at the Service Center. Included with the list are the instructions for its use. The key is located with the Service Center Guard. i 5.6.4 When an individual is decontaminated to a level less than 10,000 cpm above background using a "frisker" with an HP-210 G.M. tube, he may be referred to the shower room where further decontamination may be continued. Page 2 of 4

IP-1060/2 EP-Form #14 j PERSONNEL CONTAMINATION CllECK DATE INSTR. MODEL H.P. INSTR. SER. NO. I MAXIMUM l I l FRISKER I DESCRIPTION OF AREA I DISPOSITION INDIV. NAME l CPM j WITH READING > 200 CP:t l OF INDIV. i I I I I l-I I i i I l I I ._ _g l l I l 1 1 1 1 1 I I I i 1 i 1 i l I I I I I I I 1 I I i 1 1 I I I I I I l I I I I I i i i i l I I I i l i I I I I I I I I I I I i i i l 1 1 I l i I I i I i l I I i I I I I I I i I I I l 1 I I i NOTE: All personnel leaving restricted areas or other areas suspected to. i be contaminated should be surveyed. Record en this form whether contaminated or not. Return this form to the H.P. team leader in the CSC. ? Page 3 of 4

EP-Form #15 IP-1060/2 + SKIN DECONTAMINATION RECORD i Name: (Last) (First) (Initial) (Social Security Number) (Date) (Time of Contamination.) H.P. Tech. How & where it occurred Max. Initial Contam. Levels - With Anti-C Without Anti-C Body Orifices - Swabs or Smears - Counting Instr. Used/StJ 1 2 -3 4 5 l Time l CPM l Time l CPM i Time i CPM l Time l CPM i Time i CPM l Eye l l l l l l l l l 1 l l l l l 1 l I l l l l Ear I l l l l l l l l l l l l 1 I I I-1 I I I I Nose l i i i i i l I i i l i I I i I I I I I I I 4 Mouth l I I I I I I I ( l i 1 I I I I I I I I I I I Other i l l l 1 l l l 1 l l l 1 I I I I I I I I I l Time i 1 i Contamination l I IDecontamination l Skin Area l Decontamination l Level After l Skin [ ! Step Begins i Concerned l Agents Used l Decontamination! Condition I I i l i i l d I i l i I I I I i i i l I I I I I i 1 I i i i I I I I I I I 4 i 1 T I I I I I I i i i l i i i i i l I i i i l' f 1 I i i i I I I I I I I I I i 1 I l l 13 I i 1 -l I i-1 i i l I l-1 I I I I i l i 1 1 I I I I I I 'l i l i i I I I I I I I i i i i i l I I I I I [ } Time Decontamination Completed: l Decontamination Done by: l I I I I i i i Page 4 of 4 4 Return this form to the H.P. team leader in the CSC. ..w ~-

POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN POINT No. 3 NUCLEAR POWER PLANT P. C. SCX 215 9UCH AN AN. N. Y.1 C511 Tal. EPM Q N E4 $14 739 8200 EMERGENCY PLAN PROCIOURES PROCEDURE NO. I? - 1061 RIV. 2 TITLI: VrNIctE/EOUI?ME':T PADIOLOGICAL CFECK & DECONTAMINATION i l l . /k 8,~r?r2:n ! WiCTTEN SY ' f Fr/!EiED 3Y: hw Ow l 'A~]//-ela' cA r '//vTc_ PCRC Rzv:re t i APPRCVID BY: -Md. f CATE i;// 7 f r w rnzC :v: =As i-a u

IP-1063/2 IP-1063 VEHICLE /EQUITMENT RADIOLOGICAL CHECK AND DECONTAMINATION 1.0 INTENT To describe the methods of checking vehicles and equipment for contamination and their subsequent decontamination at the Service Centar when required. 2.0 DISCUSSION During a Site Area or General Emergency vehicle access to, or departure from, the Indian Point Site is stopped with the exception of emergency vehicles. Permissions for vehicles or equipment to leave the Site is obtained from the Emergency Director af ter evaluation of contamination (potential or actual). The responsibility for performing contamination checks and supervision of any decontamination is the Onsite Monitoring Team which is made up of Health Physics personnel. Vehicle and equipment decontamination will be performed at the Service Center parking area (or other designated area) which will be accessed through the southgate located near the gasoline pumps. This gate will be opened by a member of the Security Force. No vehicles will be allowed to leave the Broadway entrance unless authorized by the Emergency Director. 3.0 PROCEDURE 3.1 Check for removable (loose) contamination by making smear checks (guage pads and paper disks). A gauze pad smear is made up of the major surface area of the outside of the car and tires. The pad is then paced against an RM-14/HP-210 pro'ue, less than 200 cpm above background is constoered uncontaminated. A papeg disk smear is made of a number of representative areas, 100 cm' in size, and counted with a G.M. or proportional counter or the RM-14/HP-210. Tobeconsidereduncontaminatedtgeremovablecontamination must be less than 1000 dpm/100 cm 3.2 Check for fixed contaminscion by slowly passing the RM-14/HP-210 probe as close as possible to the surface. To be considered un-contaminated the fixed contamination as seen by the instrument must be less than 200 cpm above background. 3.3 If the vehicle or equipment does not check qut uncontaminated, have it moved to the decontamination location in tce N-rtheast corner of 1 Service Center North Parking Lot. t 1 of 4

IP-1063/2 3.4 Position the vehicle or large equipment close to the corner water run l,_ off opening. This will allow contamination to run off into a small depression where it will be contained and concentrated by the land contour. Isolate and post the run off area, as necessary. 3.5 Using hoses, hooked up to the nearest fire hydrant or utilizing a Fire Deparment pumper, wash the vehicle or equipment with the g detergent and water. L 3.6 If the vehicle or equipment is still contaminated, rewash and recheck l until it checks out uncontaminated. L 3.7 Record all contamination checks and washes along with the vehicle license plate number on EP-Form #16 and equipment information on ( EP-Form #17. i_r 3.8 Vehicles (not including environmental monitoring vehicles) that are i contaminated will not be permitted to leave the site. i 1 l 2 of 4

IP-1063/2 EP-Fem 016 7. VEHICLE CONTAMINATION CHECK DATE COUNTER SER. NO. H.P. FRISKER SER. NO. CALIBRATION DUE DATE LOOSECONJAM. FIXED CONTAM. DESCRIP. OF AREA DISPOSITION VEH. LIC. NO. DPM/100CM CPM > BKGD CONTAMINATED OF VEHICLE I i e i i I_ i I. k f f i e T 1 4 i s l. 1 s k 4' S 4 l j i + I i l 3 of 4

IP-1063/2 EP-Form #17 I EQUIPMENT CONTAMINATION CHECK DATE COUNTER SER. NO. F. P. FRISKER SER. NO. CALIBRATION DUE DATE EQUIPMENT LOOSECONjAM. FIXED CONTAM. LOCATION OF DISPOSITION DESCRIPTION DPM/100CM CPM > BKGD CONTAMINATION OF EQUIPMENT i 9 E l I l i i i. i i I t i i I 4 t 2 i 5 i l r I i i i i i l 4 of 4

POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN POINT NO. 3 NUCLEAR POWER Pt. ANT P. O. 3CX 215 SUCH AN AN. N. Y.10511 TaLapwo es s 914 739 8200 EMERGENCY PLAN PROCEDURES 1 1065 gg,y, PROCEDURE NO. IP-USE CF SAM-2/RD-22 TO DETERMINE THYROID BURDENS TITLE: N ' ;sm rA NRITTEN SY: A. / U Fr/IENED BY: hhhe-9 / * / PCRC Pr/IEN

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hb% CATIib3h APPRC'/ED 3Y: /f EFFECTI'/E DA"E 1 -t < -R L

IP-1065/1 IP-1065 USE OF SAM-2/RD-22 TO DETERMINE THYROID BURDENS 1.0 INTENT To describe the use of the SAM-2/RD-22 dual channel analyzer to determine the approximate thyroid Iodine-131 burdens. 2.0 DISCUSSION In the event of a significant radioactive gaseous release to the environ-ment it might become necessary to determine thyroid Iodine-131 burdens of individuals who had been involved with the plume. Thyroid counting should be performed approximately two (2) days from the time the inhala-tion occurred which is the point of peak concentration in the gland. If the number to be thyroid counted were large it would tax the existing facilities at Indian Point and the N.Y.U. facility at Sterling Forest, Tuxedo, New York. Therefore it becomes necessary to screen candidates before sending them to the above mentioned facilities. The individuals who become candidates for the more sophisticated thyroid count are the ones whose thyroid burden as seen by the SAM-2/RD-22 is greater that 0.07 uCi which is 10% of the allowable thyroid burden. This equates to approx-imately 1000 cpm above background on the SAM-2/RD-22. The screening would be accomplished by the Health Physics or Nuclear Environmental Monitoring organization as directed by the Emergency Director or Radiological Assessment Team Leader and would only take approximately three minutes per scan. Data would be kept which would allow assessments to be made on individuals, who are not counted promptly at the facilities, by comparing SAM-2 burdens vs facility burdens os a number of individuals and applying this factor to all SAM-2 scans. 3.0 PROCEDURE 3.1 Set up the SAM-2/RD-22 as described in IP-1015, allow for one (1) hour wa rmup. 3.2 After the threshold dial is set the instrument is ready to be used as a thyroid counter. NOTE: Background readings should be repeated periodically and recorded on EP-Form #18. 3.3 Using the data sheet record the time, name and identifying information for each individual counted. 3.4 Place the detector against the individual's neck. 3.5 Press the " start" button and count for 2 minutes. 3.6 Record the count on the data sheet. 1 of 3

IP-1065/1 3.7 Calculate the Iodine-131 thyroid burden using the following equation. Thy. Burden uCi Thy. Sean CPM - Bkgd CPM = (2.22 x 10") x (EFF) x (K) 0 Where 2.22 x 10 = DPM/uCi EFF = Record on SAM-2 calib sticker for 0.02 window - particalate K = 0.26 factor to convert efficiency to make it compatible for use of SAM-2 as thyroid counter. 3.8 Calculate approximate thyroid exposure using the following relationship. I uCi = 5000 meads. 3.9 If the thyroid count is.07 uCi (1000 CPM above background on 1 SAM-2/RD-22) refer to the Radiological and Environmental Services Superintendent. i l i l l l 2 of 3

IP-1065/1-EP-Form #18 DATA SHEET THYROID SANS USING THE SAM-2/RD-22 TIME NAME IDENTIFYING INFORMATION 2 Min. BKGD EQUIV. APPR. (br) Soc. Sec. # Address SCAN (CPM) (uci) THYR. (CPM) EXPOS (mR) 1700 John Doe 001-00-0101 20 Elm St. Peekskill 1400 350 0.025 115 4 'l 3 of 3 v m - -,y .n -.--n-- -m ~-~

POWER AUTHORITY OF THE STATE OF NEW YORK INO!AN POINT NO. 3 NUCLEAR POWER PLANT P. O. 8CX 215 SUCH ANAN. N. Y.10511 Ts'.tewoN sa 914.739-8200 8 EMERGENCY PLAN PRCCEDURES PROCEDURE MO. I?- _ _1 o c e REV. TITI,E : EMERGENCY REPONSE TRAINING 1 1 /* / WRITTEN SY: n / h4 Afr/i7 's !/ ' ['/w bm REVIEWED 5'l: e 6 U.tuIn OATE '/' '/. - Jf PORC REVIEW APPROVED BY: !r h, ___DA2 k 2 EFFECTIVE CA.E I i9-e t .r-.

IP-1085/1 IP-1085 EMERGENCY RESPONSE TRAINING I.0 OBJECTIVE To provide guidelines for the training of Power Authority employees in their specific responsibilities in Emergency Response at IP-3. 2.0 DISCUSSION 4 2.1 In order to ensure that site personnel assigned specific emergency response duties respond in the most efficier.t manner, specific emergency response training is required. 2.2 To facilitate this training section 3.0, of this document, has been developed for general guidance as to the content and structure of Emergency Response Training. Lesson plans are maintained by the Emergency-Preparedness Analyst. These lesson plans are consistent with the content of the Emergency Plan and Procedures. 2.3 In addition to the lesson plans various sections of Emergency Response Training require Facility tours and practical demonstrations and " hands-on" experience where applicable. 2.4 Instructor selection is accomplished by the Radiological and Environmental Services Department. Instructor qualifications are reviewed by the-Radiological and Environmental Services Department. Instructors will be members of the plant staff familiar with Emergency Planning or contractors suitably prepared to conduct Emergency Plan training. i 2.5 Emergency response training shall be accomplished annually, within + 3 months. 2.6 When changes to the Emergency Procedures are made they are routed to the controlled copy holders of the Emergency Plan Procedures document. If significant changes to the Plcn or Procedures are made, re-training will be conducted for those personnel the plan or procedure changes would impact on. If necessary re-training would be a formal classroom session, a facility tour, or accomplished by a procedure rout ng sign-off method. i 2.7 The Emergency Plan Coordinator maintains documentation on attendance for Emergency Response Training. Training Attendence sheet ITP-15.3, w'ill be used for attendence varification. The "Secpe of Training" section shall be filled out in accordance with lesson plan wording. i The Training Coordinator maintains training attendance records and associated results for each individual's training file. The Training Coordinator is responsible for maintaining all documentation regarding General Employee, and first aid training. A minimum of 90% of IP-3 site personnel shall maintain current training qualifications in assigned emergency responsibilities. i 2.8 Written tests are administered to personnel who are assigned specific Emergency Response responsibilities. A passing grade is considered to be 70% and above. Paga 1 of 6

IP-1085/1 t 2.9 All Emergency Plan related training, accomplished by Con Edison for their personnel, that relates in any manner to the Power Authority Emergency Plan, can be audited in accordance with MOU #28. f 3.0 PROCEDURE The purpose of Emergency Response training is to accomplish specialized individual and team training in methods / techniques for emergency } response / recovery steps in order to respond to an accident at the j IP-3 Nuclear Power Plant. All personnel who may be required to perform emergency duties in any of the following areas will be trained in those emergency plan responsibilities that are not a part of their normal duties. Various lesson plans and presentations have been formulated. The following list is a break down by job and which topics should be covered during their training for that j-s. 3.1 Emergency Directors

3.1.1. Topics

A. Emergency Director Responsibilities B. Dose Calculations C. Set-up, Operation and Concept of an Emergency l Operation Facilitiy D. Off Site Monitoring E. Computer Systems F. Accountability G. General Organization H. Communications Equipment I. Technical Support Center i J. Operations Support Center K. Administrative Support 3.1.2. Overviews Topics: A. Security B. Health Physics Responsibilities l C. Chemistry Responsibilities D. Control Room E. R0 and SRO Responsibilities { 3.2 Plant Operation Manager I 3.2.1. Topics-A. Plant Operation Manager Responsibilities B. R0 and SRO Responsibilities C. Control Room l D. All topics for Emergency Directors j l 3.3 Radiological Assessment Team 1 I l

3.3.1 Topics

A. Radiation Assessment Team Leader Responsibilities B. Dose Calculations l C. Operations Support Center i D. Technical Support Center i il Page 2 of 6

IP-1085/1 2.9 All Emergency Plan related training, accomplished by Con Edison for their personnel, that relates in any manner to the Power Authority Emergency Plan, can be audited in accordance with MOU #28. 3.0 PROCEDURE The purpose of Emergency Response training is to accomplish specialized individual and team training in methods / techniques for emergency response / recovery steps in order to respond to an as -ident at the i IP-3 Nuclear Power Plant. All personnel who may be required to l perform emergency duties in any of the following areas will be j trained in those emergency plan responsibilities that are not a part of their normal duties. Various lesson plans and presentations have been formulated. The following list is a break down by job and which topics should be covered during their training for that job. 3.1 Emergency Directors

3.1.1. Topics

A. Emergency Director Responsibilities l B. Dose Calculations l C. Set-up, Operation and Concept of an Emerge'tcy Operation Facilitiy D. Off Site Monitoring E. Computer Systems F. Accountability G. General Organization H. Communications Equipment I. Technical Support Center i J. Operations Support Center l K. Administrative Support 3.1.2. Overviews Topics: A. Security B. Health Physics Responsibilities C. Chemistry Responsibilities D. Control Room E. R0 and SRO Responsibilities { 3.2 Plant Operation Manager

3.2.1. Topics

l A. Plant Operation Manager Responsibilities l B. R0 and SR0 Responsibilities C. Control Room D. All topics for Emergency Directors l 1 3.3 Radiological Assessment Team l t i

3.3.1 Topics

A. Radiation Assessment Team Leader Responsibilities B. Dose Calculations C. Operations Support Center D. Technical Support Center 11 Page 2 of 6

IP-1085/1 2.9 All Emergency Plan related training, accomplished by Con Edison for their personnel, that relates in any manner to the Power Authority Emergency Plan, can be audited in accordance with MOU #28. 3.0 PROCEDURE The purpose of Emergency Response training is to accomplish specialized individual and team training in methods / techniques for emergency response / recovery steps in order to respond to an accident at the j IP-3 Nuclear Power Plant. All personnel who may be required to perform emergency duties in any of the following areas will be j trained in those emergency plan responsibilities that are not a part of their normal duties. Various lesson plans and presentations have been formulated. The following list is a break down by job and which topics should be covered during their training for that job. 3.1 Emergency Directors

3.1.1. Topics

A. Emergency Director Responsibilities l B. Dose Calculations C. Set-up, Operation and Concept of an Emergency l Operation Facilitiy D. Off Site Monitoring E. Computer Systems F. Accountability G. General Organization H. Communications Equipment l I. Technical Support Center i J. Operations Support Center K. Administrative Support 3.1.2. Overviews Topics: 1 A. Security B. Health Physics Responsibilities j l C. Chemistry Responsibilities D. Control Room E. R0 and SRO Responsibilities i I I l 3.2 Plant Operation Manager I l

3.2.1. Topics

l A. Plant Operation Manager Responsibilities l B. R0 and SRO Responsibilities C. Control Room D. All topics for Emergency Directors 3.3 Radiological Assessment Team

3.3.1 Topics

A. Radiation Assessment Team Leader Responsibil ties l B. Dose Calculations C. Operations Support Center i D. Technical Support Center j i1 Page 2 of 6

IP-1085/1 I. E. Health Physics Responsibilities F. Chemistry Responsibilities G. Communication Equipment H. General Organization I. Computer Systems J. Set-up, Operation and Concept of an EOF K. Off-Site Monitoring i 3.3.2. Overview Topics: A. Accountability B. Control Support C. Administrative Support 3.4 Emergency Operation Facility Communicators

3.4.1 Topics

A. Communication Equipment B. Set-up, Operation and Concept of an EOF C. General Organization 3.5 ' Technical Support Center Personnel

3.5.1. Topics

A. Technical Support Center B. Technical Support Center Manager C. Communication Equipment D. General Organization E. Radiation Monitoring Equipment 3.6 Operations Support Center Personnel

3.6.1 Topics

A. Operations Support Center 0. Operations Support Center Supervisor C. Communication Equipment D. General Organization E. Accountability F. Radiation Monitoring Equipment G. Administrative Support H. Repair & Corrective Actions 3.6.2 Overview Topics A. Health Physics Responsibilities B. Health Physics Team Leader C. Chemistry Responsibilities D. Chemistry Team Leader 3.7 Shift Supervisors

3.7.1 Topics

A. Dose Calculations B. Emergency Director Responsibilities C. Operations Support Center D. Technical Support Center E. Communication Equipment F. General Organization G. Accountability H. Computer Systems Page 3 of 6

1 IP-1085/1 I. Set-up, Operation and Concept of an EOF J. Off-Site Monitoring K. Control Room L. RO & SRO Responsibilities M. Radiation Monitoring Equipment N. Administrative Equipment 3.7.2 Overview Topics: A. Security B. Health physics Responsibilities C. Chemistry Responsibilities 3.8 Accountability Officers

3.8.1 Topics

A. Accountability B. General Organization 3.9 Security

3.9.1 Topics

A. Security B. Communication Equipment C. General Organization 3.9.2 Note: Security Shift Coordinators will recieve in addition to the above topics A. Accountability 3.10 Health Physics Technicians 3.10.1 Topics: A. Operations Support Center B. Health Physics Responsibilities C. Communication Equipment D. General Organization E. Off-Site Monitoring 3.10.2 Note: Health Physics supervisors will receive in addition to the above topics A. Health Physics Team Leader B. OSC Supervisor 3.11 Chemistry Technicians 3.11.1 Topics: A. Operations Support Center B. Chemistry Responsibilities C. Communication Equipment D. General Organization E. Post Accident Sampling I Page 4 of 6

IP-1085/1 3.11.2 Note: Chemistry Supervisors will receive in addition to the above topics A. Chemistry Team Leader B. OSC Supervisor 3.12 Senior Reactor Operators and Reactor Operators 3.12.1 Topics: A. Dose Calculation B. Emergency Director Responsiblities C. Communication Equipment D. General Organization E. Computer Systems F. Control Room G. RO & SRO Responsibilities H. Radiation Monitoring Equipment 3.12.2 Overview Topics: A. Security B. Health Physics Responsibilities C. Chemistry Responsibilities D. Off-Site Monitoring 3.13 Shift Technical Advisor 3.13.1 Topics: A. Technical Support Center B. Technical Support Center Manager C. General Organization D. Control Room 3.14 Nuclear Plant Operators 3.14.1 Topics: A. Operations Support Center B. Communication Equipment C. General Organization D. Control Room E. Radiation Monitoring Equipment 3.15 Emergency Operation Facility Technical Assistants 3.15'.1 Topics: A. Set-up, Operation and Concept of an EOF B. Communications Equipment C. General Organization 3.16 Administrative Support 3.16.1 Topics: A. Operations Support Center B. General Organization C. Administrative Support i page 5 of 6

3 IP-1085/1 3.17 General Employee 3.17.1 Topics: A. Film on Emergency Plan, Site Assembly Procedures and Site Alarms 3.18 Medical Emergency Training 3.18.1 Topics: A. On-Site; Conducted as per consultant training program. l E. Offsite; Conducted as per cons'sitant training program. l 1. Hospital Personnel 2. Ambulan:e Personnel 3.19 Fire Response 3.19.1 Verplanck Fire; Conducted by Sr.fety & Security Department 3.20 First Aid 3.20.1 First Aid training will be performed equivalent to Red Cross Multimedia standards. Provisions will be made to have at least one member of the watch trained in first aid. 1 i I l l t Page 6 of 6 .}}

ML20040E055

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SUBJECT:

Reference:

1.0 INTENT

2.0 DISCUSSION

1.0 INTENT

2.0 DISCUSSION

3.0 REFERENCES

4.0 PROCEDURE

Background

Background

5.1 Pasture

5.4 Grains

2.0 REFERENCES

3.0 REFERENCES

6.2 COMMUNICATOR

3.0 REFERENCES

6.1 COMMUNICATOR

3.0 REFERENCES

4.4.3 Dosimetry

2.0 ASSESSMENT

3.1.1. Topics

3.3.1 Topics

3.1.1. Topics

3.2.1. Topics

3.3.1 Topics

3.1.1. Topics

3.2.1. Topics

3.3.1 Topics

3.4.1 Topics

3.5.1. Topics

3.6.1 Topics

3.7.1 Topics

3.8.1 Topics

3.9.1 Topics

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