ML20040E329

Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures SC-1.3A Re Site Emergency (Shift Supervisor & Control Room) & SC-1.13 Re Estimating Offsite Doses

ML20040E329
Person / Time
Site:	Ginna
Issue date:	01/16/1982
From:	Bodine J ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17258A499	List: ML20040E327 ML20040E329
References
PROC-820116-01, NUDOCS 8202040189
Download: ML20040E329 (36)

Text

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CONTROLLED COPY NUMBER ] ij"'".ic .

PROCEDURE NO. SC-1.3A REV. NO. 19 SITE EMERGENCY (SHIFT SUPERVISOR AND CONTROL ROOM)

IECHNICAL REVIEW PORC REVIEW DATE /~/8- 82

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QC REVIEW PLANT SUPERINTENDENT

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3 EFFECTIVE DATE QA ( _NON-QA CATEGORY 1.0 REVIEWED BY:

THIS PROCEDURE CONTAINS 11 PAGES I : Z~CCC? :Z;2

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8202040189 820201 PDR ADOCK 05000244

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SC-1.3A:1 f

i SC-1.3A i

SITE EMERGENCY

! (SHIPr SUPERVISOR AND CORTROL ROOM) i

! 1.0 PURPOSE:

[ 1.1 To establish the duties performed and the actione required by the on-duty

1. Shif t Supervisor and Operators and Health Physics Technicians for a Site Eme rgency. .

A site emergency is defined as a emergency condition whose consequences affect pe rsonnel on-site, and possibly of f-sit e.

2.0 REFERINCES

2.1 SC-1, Radiation Emergency Plan, step 3.2.

2.2 SC-1.lA.

3.0 INSTRUCTIONS :

3.1 Any Ginna Station NRC Licensed Reactor Operator shall initiate a Site Emergency by sounding the PIME EVACUATION ALARM when the evaluation of conditions as outlined in SC-1.lA Ginna Station Event ~ Evaluation and Classification indicates a severity of the emergency to require plant evacuation.

3.1.1 Operator jud,gement shall, however, prevail so that this procedure may be initiated without total dependence on instruments or alarms. Licensed Control Room Personnel may in their judgement initiate a Site Emergency at less severe conditions or other parameters.

3.2 All on-duty Operators, Shift Supervisor and Duty MP Technicians shall report to the Control Room.

3.3 The SHIFT SUPERVISOR shall assume the responsibility for the Radiation Emergency Plan until relieved by the first staff arrival (nights and weekends) or arrival of plant Supe rint endent in Technical Support Center.

3.3.1 Evaluate plant conditions by checking status of control and safeguards systems and radiation monitors and ensure appropriate Emergency Procedures are being followed. (Dete rmine class of emergency using E-1. lA.)

3.3.2 Delegate the communications assistant to commence the Immediate Call List (SC-1.12A) and continue until relieved by Technical Support Center.

SC-1.3A:2 3.3.3 Designate an Auxiliary Operator (see step 3.8) to complete the Equipment Evaluation Form, Attachment I of this procedure to determine what safeguards actuation has occured, and to fill in the Initial Notification Sheet, Attachment III.

3.3.4 Dispatch in-plant Survey Team to conduct plant and radiation survey (refer to SC-1.9) as needed.

, 3.3.5 Communicate with the Emergency Coordinator when he contacts Control Room and relay information as required.

3.3.6 Within one hour notify NRC Operations Of ficer using the Red Phone and assign an individual to maintain continuous communications. If the Red Phone is not worxing, use the alternative notification methods identified in Attachment 3.

3.4 The SHIFT TECHNICAL ADVISOR shall cbserve Control Board parameters and analyze the event with the Shift Supe rviso r.

3.5 , The HEAD CONIROL OPERATOR shall take appropriate actions per applicable Emergency Procedures.

3.6 The CONTROL ROOM OPERATOR shall perform the following:

3.6.1 Secure Control Room ventilation dampers from outside to inside air and turn on charcoal filter fan by operating the check source on R-1, Control Room Area Monitor. Check output pressure on override control at 0 psig (located in C.R. kitchen). Do not reset R-1 alarm until further orders.

3.6.2 Ensure emergency radio switch is in the local position and plug in intercom for communicatiens with Emergency Survey Center.

3.6.3 Answer radio calls from plant guards as they report status to Control Room.

3.6.4 Assist Head Control Operator.

3.7 The DUTY HP TECHNICIAN shall perform the following:

3.7.1 Prepare radiation emergency equipment for use. Start lapel sampler for

' Iodine in air concentration. Use Procedure SC-1.7B.

3.7.2 Account for all operating and health physics personnel remaining in Control Room. Re port names to Emergency Coordinator.

3.7.3 Check lake for boaters. Notify Emergency Coordinator if any are in plant vicinity.

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SC-1.3A:3

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) 3.7.4 Assist in plant Survey Team conduct a plant equipment and radiation survey.

3.7.5 Standby for instructions from Shif t Supervisor.

3.8 A PdSIGNATED AUXILIARY OPERATOR shall perform the following:

i j 3.8.1 Fill in the Evaluation Form. Attachment I and Initial Notification Sheet, i Attachment III. Ic main weather tower information is unavailable obtain j weather readings from the Nationi Weather Service (71-9-328-7633).

1 i 3.8.2 Attachment II may be used to estimate dose levels based upon type of I accident and safety equipment in operation. This estimate should be used to determine the need for protective actions on the Immediate Notification Sheet. When the Bureau of Radiological P.ealth calls back the estimated dose should be reported along with other information requested. ,

3.8.3 At tachment 11 may be used to estimate dose levels based upon type of accident and safety equipment in operation. This estimate should be reported to the Bureau of Radiological Health when they call back, along with other information requested.

, 3.9 Communications Assistant shall do the following:

3.9.1 Start Immediate Call List (SC-1.12A).

3.9.2 Make calls to Stats and Counties using Initial Notification Sheet, Attachment III.

3.9.3 Note that the Bureau of Radiological Health has verified the information supplied via the Control Room Emergency Phone.

3.10 Of f Site Dose Assessment may be made Utilizing the Plant Vent concentration (See SC-1.13 for State Protective Action Guides).

3.10.1 Determine the plant vent gas concentration from the R-14 monitor and S-14.2.

3.10.1.1 If the plant vent gas monitor (R-14) is off scale, the gas concentration being released can be obtained from the SPING-4 monitor (PC-23.5) or from the TMI interim fix monitor installed in the Intermediate Building near the vent line (PC-23.3).

3.10.2 After obtaining the plant vent gas concentration from S-14.2, PC-23.5, or PC-23.3, the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> whole body dose at the site boundary can be est imated using the following equation:

2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> W.B. Dose (site boundary) = (pCi/cc gas in vent) (15 Rem per pCi/cc)

NOTE: The following assumptions were made for these calculations:

X/Q = 5.3 x 10-4 sec/m3 ( from AEC Docket #50-244 proposed change to Op. License).

SC-1.3A:4

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This value assumes meteorological conditions which are 100 times more conservative than annual average meteorology.

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[ Plant vent flow = 65,000 CFM (or 3.1 x 10 7 cc/sec). 15 Rem /uCi/cc is based on EPA-520 whole body dose curve at 0 time af ter shutdown.

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S C-1. 3 A:5 f

1 ATTACKMENT I Refer to SC-1.3A EQUIPMENT EVALUATION FORM for Instructions Complete the following checklist and evaluate each safeguard group for proper operation. Report any problems to the Shift Supervisor and/or the Shif t Technical

! Advisor. If less than 2 SIS pumps or less than 2 CS pumps, or less than 2 post accident charcoal filters are .in service, or no RHR pumps, refer to SC-1.4 General Emergency.

S SAFETY INJECTION SYSTEM Operating Flow Pressur e 1-A Pump Yes No Loop A FI-925 g pm PI-923 psi 1-B Pump Yes No Loop B FI-924 gpm PI-92 2 psi 1-C Pump Yes No PR-420 psi (Bus 14 or 16)

NOTE: There may not be flow to the RCS unless PR-420 is less than 1,500 psi.

91 Pumps operating properly? YES If not, note problem:

ACCUMULATORS

, Level (Narrow Range Only) Pres s ure 1-A Accumulator LI-938  % PI-940 psi PR-420 psi 1-B Accumulator LI-934  % PI-936 psi NUIE: There may not be delivery to the RCS unless PR-420 is or has been less than 700 psi.

Accumulators operating properly? YES If not, note problem:

RESIDUAL HEAT REMOVAL SYSTEM Operating Flow '

Pressure 1-A Pump Yes No FI-626 gpm PR-420 osi 1-B Pump Yes No NOTE : There may not be flow to the RCS unless PR-420 is less than 150 psi.

RHR pumps operating properly? YES If not, note problem:

SC-1.3A:6 i

ATTACHMENT I Refer to SC-1.3A EQUIPMENT EVALUATION FORM (Cont'd) for Inst ructions CONTAINMENT SPRAY SYSTEM

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Operating Flow Valves 1-A Pump Yes No FI-930 gpm A0V-836A Open Closed 1-B Pump Yes ,

No NaOH Tank Level LI  % ADV-836B Open Closed Containment Vessel Pressure -

Average of PI-945 PI-947 and PI-949 Average psi NOTE: CS Pumps will not start unless CV pressure is or has been > 28 psi.

CS Pumps operating properly or not called for? YES If not, note problem:

SERVICE WATER SYSTEM Ope rat ing 1-A Pump Yes No 1-B Pump Yes No 1-C Pump Yes No 1-D Pump Yes No Number of Puwps in Service Any problem? If so, note:

CONTAINMENT VESSEL FANS AND FILTERS Operating 1-A Recire. Fan Yes No 1-B Recire. Fan Yes No 1-C Recire. Fan Yes No 1-D Recire. Fan Yes No Total Running

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SC-1.3A:7 i

1 ATTACHMENT I Refer to SC-1.3A EQUIPMENT EVALUATION FORM (Cont'd) for Instructions

.f CHARCOAL FILTERS 1-A Damper - Green Lite Out Yes ______ No Annunciator l

' > l-B Damper - Green Lite Out Yes No C-9 On Yes No NUIE: If damper lights are out and no alarm on C-9, the filters should be in service.

Number in service:

AUXILIARY FEEDWATER PUMPS Operating 1-A Pump Yes No 1-B Pump Yes No Turbine Pump Yes No 1-C Pump Yes No l 1-D Pump Yes No Numbar in service:

EMERGENCY DIESEL GENERATORS operating i

l l-A D/G Yes No 1-B D/G Yes No Number in service:

CONIAINMENT RADIATION l

Containment High Range Monitor mR/hr Monitor R-1 __ mR/h r .

1 i Other Notes:

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SC-1.3A:8

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ATTACHMENT II Refer to SC-1.3A

' for Instructions ESTIMATED DOSE LEVELS c

TWO HOUR DOSE OFFSITE EST IMAIED (AT 1500' RADIUS FROM QUANTITIES REAGIOR) RELEASED 3

WHOLE T HYROID NOBLE BODY INMALATION GASES I-131 (REM) (REM)

No Spray Pumps, and 2 fans **

on after proper safety injection core cooling 89 2 Ci/ day 1 Spray Pump + 1 Fan on**

after proper safety .

injection core cooling 29 .7 Ci/ day 2 Spray Pumos on af ter **

proper safety injection core cooling 20 .5 Ci/ day

" Design Basis Loss of

• Coolant Accident with Iodine removal by Spray &

Filter" and no breach of containment. 0.6 15.5 35 Ci/ day .35Ci/ day Gas Decay Tank Rupture (Puff)* 0.3 < 10 150 Ci Control Rod Ejection

• 0.19 5.0 Steam Line Rupture Outside

• C.V. - with tube leak negl. 1,8 5 Ci .004 Ci

- no tube leak Refueling Incident with

• Charcoal System On 0.17 1.7 1.96x10 2.7 Ci Steam Line Rupture in C.V.* 0.1 1.2 .005 'Ji .00lmCi Steam Gen. Tube Rupture

• 0.003 0.15 3 Ci .5 mci

• AEC Safety Evaluation (for siting) values reduced by tactor of 10.

• • 0peration of 1 Accumulator and 1 RHR Pump and 2 SI Pumps: FSAR

SC-1.3A:9 ATTACHMENT III Refer to SC-1.3A

" INITIAL NOTIFICATION SHEET" for Instructions

1. Call the New York State Warning Point (9-1-518-457-2200 or 457-6811). Relay to the person answering the information in steps 4.1 thru 4.10. They should be able to take the information quickly and accurately if given the letter and corresponding words.

2. Call the Wayne County Of fice of Disaster Preparedness (9-1-946-4878 or 946-9711). Relay to the person answering the information from items 4.1 through 4.4 and 4.9 and that further information will come from the State Bureau of Radiological Health.

3. Call Monroe County Of fice of Emergency Preparedness (71-9-473-0710 or 428-7200) .

Relay to the person answering thct a Site Emergency exists at Ginna Station and that further information will come from the State Bureau fo Radiological Health.

4.1 Nuclear Facility providing this report.

ICl Ginna Station 4.2 Thisl Al is or f5) is not an exercise.

4.3 Emergency Classification A) Unusual Event B) Alert C) Site Emergency D) General Emergency E) Transportation Incident F) Other (Describe) 4.4 Reported By:

Name Title 4.5 There l A l has l B l has not been a release of radioactivity to the l C l atmosphere l Dl ground (spill only)I El Lake Ontario on Deer Creek.

f 6.6 ThereleaselAl is continuing.

l B l ha. terminated.

l Cl not applicable.

4.7 Protectiva Action l A l None needed outside the site boundary, notified for information only.

lBl There is need for offsite protective action. Af fected areas include sectors or ERPA's.

SC-1.3A:10

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!! 4.8 . Recommended Protective Actions i:

ti A) Not Applicable B) Shelter within miles j

C) Evacuate within miles I

D) Other or additional information 4.9 A) Wind speed miles per hour B) Direction (from) degrees C) General weather conditions 4.10 Verification or additional information phone number (315) 524-4891, i

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l ATTACHMENT 4 l i

ALTERNATE NRC NOTIFICATION METHODS PRIMARY NOTIFICATION METHOD:

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! Emergency Notification System to NRC Operations Center. (Lift receiver from

! cradle on RED phone).

l ALTERNATE NRC NOTIFICATION METHODS:

TELEPHONE SYSTEM TELEPHONE NUMBER

1. Commercial Telephone System to 301/492-8111 NRC Operations Center (via Bethesda Central Office)

2. Commercial Telephone System to 301/427-4056 NRC Operations Center (via Silver Spring Central Of fice)

3. Health Physics Network to *22 NRC Operations Center

4. Commercial Telephone System to 301/492-7000 NRC Operator (via Bethesda Central Of fice)

NOTE: The Health Physics Network phone will not have a dial tone, nor will there be any indication of a ring. A high pitched tone indicates the syst em is in use and the next alternative method should be used.

NGrE: For any change check procedure 0-9.3 & SC-1.12C also.,

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CONTROLLED COPY NUMBER PROCEDURE NO. SC-1.13 REV. NO. 9 ESTIMATING OFF-SITE DOSES TECHNICAL REVIEW PORC REVIEW DATE /- /d ~8 2

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QC REVIEW PLANT SifPERINTE$ DENT i

r x - \ .f,, - *? , O.m sc EFFECTIVE DATE QA / NON-QA CATEGORY 1.0 REVIEWED BY:

THIS PROCEDURE CONTAINS 23 PAGES

SC-1.13:1 i

'i SC-1.13 ESTIMATING OFF-SITE DOSES _

I.0 PURPOSE:

1.1 The purpose of this procedure is to provide estimates of the post accident dose in the areas around the plant and guidance for the selection of sampling locations. Information is needed early to decide what action be taken to limit the exposure of the general public. Steps must be t aken to define the affected areas, assess the extent and significance of the release and provide data on which appropriate protective actions can be based.

2.0 REFERENCES

2.1 Radiation Emergency Plan, SC-1 2.2 N.Y.S. Radiological Emergency Preparedness Plan 2.3 SC-1.lA, SC-1.3A, SC-1.7C, SC-1.8 2.4 PC-23.3, PC-23.4, PC-23.5 and S-14.2 2.5 EPA-520, Manual of Protective Action Guides and Protective Actions for Nuclear Incidents (Feb. 1980).

2.6 Regulatory Guide 1.109 3.0 INSTRUCTIONS-3.1 The following equipment is available for use in estimating doses 3 1.1 Xu/Q Isopleths, and Xu/Q tabulated values (Table 1).

3.1.2 Map of surrounding area, U.S. Geological Survey (1 inch: 24000 inch scale) 3 1.3 Control Room wind and temperature indicators 3.1.4 Control Room Radiation Monitor System 3 1.5 Back-up wind speed and direction indicators . - Station 13A, and National k'eather Service.

3.2 Preliminarv Radiological Estimates and Ever c_ ssification

- SC-1.13

2 i-3.2.1 For initial notification purposes, a first-cut estimate of potential of fsite doses and releases may be obtained by the Control Room using SC-1,3A, Attachment II. Levels are provided for various accidents evaluated in the Ginna FSAR and in previous AEC Safety Evaluations 6ar Ginna plant siting and design.

3.2.2 It is preferable to base of fsite estimates upon measured release values.

Vent activity concentrations and release rates can be determined from curves in Procedure S-14.2, and from Procedure PC-23.5. Should vent monitors be inoperable, procedures PC-23.3 and PC-23.4 should be used estimating plant and steam vent releases, respect ive1f .

3 2.3 An estimate of the 0-2 hr site boundary whole body dose from plant vent noble gas concentration, obtained from S-14.2 (low range monitor), PC-23.5 (hi range monitor) or PC-23.3 (back-up monitor), may be obtained using the following equation:

Plant vent (uci/cc) x 15 Rem = 0-2 hr whole body dose (Rem) uCi/cc at site boundary NOTE: The following assumptions were made for these calculations:

X/Q = 5.3 x 10-4 sec/m3 (def ault value in lieu of actual meteorology data: assuming downwind mixing conditions 100 times more conservative than annual average conditions).

Plant vent flow = 65,000 cfm (3.1 x 10 7 cc/sec)

EPA-520 whole body dose curve (t = Ohr) 3.2.4 Determine the classification of the emergency with respect to plant releases and site boundary doses from the following criteria ( from SC-1.lA):

RADIOLOGICAL ESTIMATE CLASSIFICATION Radiological ef fluent Technical Unusual Event Specification limits exceeded (T.S.3.9)

Radiological effluent greater than Alert

! 10 times Technical Specification limits.

Site Emergency Effluent monitors indicate levels corresponding to greater than 50 mrem /hr whole body or 0-2 hr. thyroid dose greater than 500 mrem at the site boundary.

Or these doses projected based upon plant parameters, or actual of f site measurements.

SC-1.13:3 l

L Ef fluent monitors show levels corresponding General Emergency to 500 mrem /hr whole body or a 0-2 hr.

thyroid dose greater than 1 rem. Or these doses indicated by offsite measurements.

3.2.5 Any preliminary dose estimates used as a basis for emergency classification or protective action recanmendations should be refined as follows using release measurements and actual meteorological and field sampling data as they become available. -

3.3 Use of Meteorlogical and Release Data with EPA Curves to Project Doses 3.3.1 Obtain the temperature at 33' and 250' from the " Status Report Form",

Control Room, TSC or Computer Terminal. From the 33' temperatures subtract the 250' temperature. If readings from the main weather tower are unavailable , proceed to step 3.3.2.1.

- T33'

-T25 0 ' _

1 T' 3 3.2 If 6. T is 2.0 or greater condition is unstable (lapse).

If o. T is between 0.5 and 2, condition is neutral .

If 25 T is less than .5 or is negative (T250' > T33'). condition is stable (inversion).

Condition is 3 3.2.1 In the event that meteorological data are unavailable from the main weather tower, the Emerger.cy Coor d inator should direct an individual to proceed to the back-up westher inst rument recorder inside the Station 13A control building. The recorder is located next to the communications desk on the north wall.

i 3.3.2.2 If the primary tower temperature sen: ors are not available to determine

! stability, the individual t aking the readings should note wind speed (mph)

! wind direction (degrees) and approximate fluctuation in wind direction (degrees) averaged over the last hour. The wind direction fluctuation is determined by eyeballing or by drawing 2 average lines through the last hour's wind direction extremes, and subtracting the dif ference.

3.3.2.3 Station 13-A wind speed, wind direction and wind direction fluctuation readings are reported to the Technical Support Center by phone (ext. 500 through 507) or by the plant P.A. The individual at Station 13A should request for further instructions from the Emergency Coordinator.

3.3.2.4 To determine atmospheric stability from wind fluctuacion, use the following table:

SC-1.13:4 i

f Wind Fluctuation Stability

< 45 ' anyt ine st able (inversion) i > 45' night t ime neutral 45 *-7 5* d ayt ime neutral

> 75* dayt ime unstable (lapse)

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3 3.3 Select the Xu/Q plastic overlay matching the condition determined in 3.3.2 and attach to the area map. (Also rabulated Xu/Q values are given in the attached Table 1).

3.3.4 Obtain wind speed and direction data from the " Status Report Form", the Control Room, TSC, Computer Terminal or alternatively from Station 13A. The direction given will be that from which the wind is blowing.

Wind Speed (mph)

Wind Direction (degrees)

NOTE: Supplemental' weather information is also available from the National Weather Service Of fices in Rochester (716-328-7633) or Buffalo (716-632-2223), if necessary.

3.3.5 Align the centerline of the overlay in the downwind direction. The mark on the centerline at the bottom of the overlay should be aligned on a compass point on the map 180 degrees from the degrees given in 3.3.4 To determine this point, do one of the following:

If the degrees given in step 3.3.4 is between 180 and 360, subtract 180.

If the degrees given in step 3.3.4 is between 0 and 180, add 180.

Degrees wind is blowing from Degrees

! +or ___180 D egree s Align mark on centerline of overlay (at bottom) at D egree s 3.3.6 The Xu/Q plastic overlays and Table 1 values have, for convenience been calculated based upon a wind speed of 1 mph. Thus, in order to determine X/Qsec},it is necessary to divide the isopleth value by the actual wind m')

l speed, in mph.

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, SC-1.13:5 t

3.3.7 To calculate the downwind concentration of noble gas, particulates or radioiodine, multiply the release rate of radioactivity (Ci/sec) from the plant times the X/Q (sec/m3 ) dispersion coefficient determined in step 3.3.6. The resultant concentratica will be in Ci/m3 or uCi/cc. Pe rfo rm t

these calculations on Attachment 1 .

3.3.8 Obtain an initial estimate of release duration from the Emergency Coordinator or Recovery Manager. If this estimate is unavailable, use an initial release duration estimate of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for dose projection purposes.

3.3.9 Whole body gamma dose is then estimated using Figures 1 through 7, according to the approximate time after shutdown. To estimate gamma dose rate for a given noble gas downwind concentration (right vertical scale) find the corresponding whole body dose rate (mrem /hr) along the lef t vertical scale.

3.3.10 To estimate whole body gamma dose, find the point on the graph where the noble gas concentration line intersects the projected exposure t ime. Th e integrated whole body dose is then found along the diagonal lines on the graph.

3.3.11 To estimate child and adult thyroid dose, find the point on the Figure 8 graph where the downwind radioiodine concentration line intersects the projected exposure time. The integrated thyroid doses for the adult and child are indicated along the diagonal lines (the child dose being twice the adult's).

3.3.12 Correct thyroid dose estimates for time after shutdown, by multiplying by-the appropriate factor indicated in Figure 9.

3.4 Survey Team Data 3.4.1 Note the sample locations on the map that are covered by the Xu/Q overlay.

The initial sample taken should be in a high concentration area and on a

! first stage survey route. Using the attached list of samole locations and teams, notify proper teams where to take samples. When results are received, mark results on appropriate map and status board.

3 4.2 When the initial field sampling results are received, assign a Xu/Q vslue i

to the sample results using the Xu/Q value for the line closest to the l sample location. For the plastic overlays, all points along a given line are assumed to have the same concentration as the initial sample. Th e concentration at any other point of interest can be estimated by multiplying the sample concentration by the ratio of the respective Xu/Q values.

EXAMPLE: A sample taken on a Xu/Q line of 5 x 10-6 indicat ed an iodine concentration of 5 x 10-7 uCi/cc and dose rate of 100 mrem /hr. Determine the concentration and dose rate expected at a Xu/Q value of 2 x 10-7?

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SOLUTION:

Iodine at 2 x 10-7 = 2 x 10-7 x 5 x 10-7 uci 2x10-8(uCi 5 x 10-6 g (ec Dose Rate at 2 x 10~7 = 2 x 1077 x 100 (mrem /hr) = 4(mrem /hr) 5 x 10-0 3.4.3 Compare measured dose rates and air concentrations to predicted values, and adjust dose projections accordingly.

3.4.4 Notify the survey team to continue surveying the af fected area looking for high concentration areas and hot s pot s .

3.4.5 If the wind direction changes, realign overlay using 3.3.5. Sample new locations indicated by the overlay.

3.4.6 If the wind speed change s, recalibrate the overlay by dividing the original speed by the new wind speed and multiply by the concentration or dose. Resample to check new overlay calibration.

3.4.7 For puf f type releases multiply wind speed by elapsed time to find distance radioactive cloud has traveled.

3.4.8 Environmental TLD's, (SC-1.7C) and Post Accident Environmental Samples, (SC-1.8) may be used to give better values for of f-site doses.

3.5 Protective Action Guides 3.5.1 Recommend the appropriate measures to be followed with respect to the general

, pub lic . Table 2 , 3 and 4 give the projected vbole body and thyroid dose levels which warrant given protective actions (e.g. shelt ering ,

evacuation) indicated.

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sc-1.13:7 l TABLE I j

GINNA SITE VALUES OF E3 AS A FUNCTION -

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OF STABILITY AND DISTANCE (ce 'uted by Pickard, Lowe & Garrick 1/82)

DOWNWIND DISTANCE UNSTABLE NEUTRAL STABLE METERS FEET MILES 200 660 0.1 2.42 E-4 1.17 E-3 2.06 E-3 400 1,310 0.2 1.06 E-4 6.33 E-4 1.42 E-3 600 1,970 0.4 5.88 E-5 4.02 E-4 1.10 E-3 800 2,620 0.5 3.71 E-5 2.80 E-4 8.78 E-4 1,000 3,280 0.6 2.34 E-5 2.13 E-4 7.17 E-4 1,200 3,940 0.7 1.62 E-5 1.68 E-4 5.97 E-4 1,400 4,590 0.9 1.19 E-5 1.36 E-4 5.05 E-4 1,600 5,250 1.0 9.13 E-6 1.12 E-4 4.42 E-4 1,800 -5,910 1.1 7.18 E-6 9.45 E-5 3.91 E-4 2,000 -

6,560 1.2 5.20 E-6 8.22 E-5 3.48 E-4 2,500 8,200 1.6 2.83 E-6 6.02 E-5 2.70 E-4 3,000 9,840 1.9 1.99 E-6 4.67 E-5 2.23 E-4 3,500 11,500 2.2 1.69 E-6 3.76 E-5 1.88 E-4 4,000 13,100 2.5 1.46 E-6 3.10 E-5 1.61 E-4 4,500 14,800 2.8 1.27 E-6 2.60 E-5 1.39 E-4 5,000 16,400 3.1 1.12 E-6 2.21 E-5 1.22 E-4 5,500 18,000 3.4 9.99 E-7 1,91 E-5 1.08 E-4 6,000 19,700 3.7 9.11 E-7 1.68 E-5 9.78 E-5 6,500 21,300 4.0 8.53 E-7 1.52 E-5 8.89 E-5 7,000 23,000 4.3 8.03 E-74p 1.38 E-5 8.12 E-5 7,500 24,600 4.7 7.58 E-7 1.25 E-5 7.45 E-5 8,000 26,200 5.0 7.18 E-7 1.15 E-5 6.86 E-5 8,500 27,900 5.3 '

6.82 E-7 1.05 E-5 6.34 E-5 9,000 29,500 5.6 6.49 E-7 9.72 E-6 5.88 E-5 9,500 31,200 5.9 6.19 E-7 8.99 E-6 5.49 E-5 10,000 32,800 6.2 5.94 E-7 8.40 E-6 5.24 E-5 11,000 36,100 6.8 5.53 E-7 7.50 E-6 4.79 E-5 12,000 39,400 7.5 5.18 E-7 6.74 E-6 4.40 E-5 13,000 42,700 8.1 4.86 E-7 6.09 E-6 4.06 E-5 14,000 45,900 8.7 4.59 E-7 5.54 E-6 3.76 E-5 15,000 49,200 9.3 4.34 E-7 5.50 E-6 3.49 E-5 16,000 52,500 10.0 4.12 E-7 4.63 E-6 3.26 E-5 NOTE: VALUES ARE BASED ON 1 MPH WINDS

. . 3C-l.13:8 j

t .

[

TABLE II - \

. PROTECTIVE ACTION GUIDES FOR VHOLE BODY EXPOSURE TO AIRBORNE RADI0 ACTIVE MATERIALS l

l PROJECTED WHOLE BODY l POPULATION AT RISK GAMMA DOSE (REM l

l GENERAL POPULATION 1 TO SCA)

EMERGENCY WORKERS 25 LIFESAVIllG ACTIVITIES 75 A WHENRANdESARESHOWN,THELOWESTVALUESHOULDBE l

i l ~~

USED IF THERE ARE'NO MAJOR LOCAL CONSTRAINTS I'N PROVIDING PROTECTION AT THAT LEVEL, ESPECIALLY TO SENSITIVE POPULA-IIONS. LOCAL CONSTRAINTS MAY MAKE LOWER VALUES IMPRACTICAL TO USE, BUT IN NO CASE SHOULD THE HIGHER VALUE 3E EXCEEDED IN DETERMINING THE NEED FOR PROTECTIVE ACTION.

j

.SC-1.13:9

'e TABLE III PROTECTIVE ACTION GUIDES FOR THYROID DOSE

^

DUE TO INHALATION FROM A PASSING PLUME PROJECTED THYROID DOSE POPULATION AT RISK REM GENERAL POPULATION 5 - 25 c EMERGENCY WORKERS 125 LIFESAVIliG ACTIVITIES (A) ,

A)NO SPECIEIC UPPER LIMIT IS GIVEN FOR THYROID EXPOSURE SINCE IN THE EXTREME CASE COMPLETE THYROID LOSS ,

MIGHT BE AN ACCEPTABLE PENALTY FOR A LIFE SAVED. HOWEVER, T,HIS SHOULD NOT BE NECESSARY IF RESPIRATORS AND/OR THYRUID PROTECTION FOR RESCUE PERSONNEL ARE AVAILABLE AS THE RESULT OF ADEQUATE PLANNING.

3) 3 -

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i ii  !

<lI i l li

SC-1.13:11 ATTACHMENT I t

RELEASE VENT:

1 TIME /DATE-POST-SHUTDOWN TIME: (hr)

EFFLUENT ENITOR READINCS:

uCi/cc Gas (Monitor No. )

uCi/cc Particulate (Monitor No. )

uCi/cc Radioiodine (Monitor No. )

CFM Vent Flow '

(1) To convert CFM to cc/sec CFM x 2.83 x 104 cc/CFM x 1 min /60 sec = cc/sec NOBLE CAS:

(2) To calculate release RATE in Ci/sec from monitors uCi/cc x cc/sec x 10-6Ci/uci = Ci/sec (3)- To predict downwind concentration see-mph x Ci/sec x 1/( ) mph = uCi/cc ar (Xu/Q) m3 (windspeed) (distance) 1 PARTICULATE:

(4) To calculate release RATE in Ci/see from monitors l

l uCi/cc x cc/see x 10-6Ci/uci = Ci/sec l (5) To predict downwind concentration i

see-mph x Ci/sec x 1/( ) mph = uCi/cc at (Xu/Q) mJ (windspeed) (distance)

RADIOIODINE:

! (6) To calculate release RATE in Ci/see from monitors uCi/cc x cc/sec x 10-6Ci/uci = Ci/sec (7) To predict downwind concentration see-moh x Ci/see x 1/( ) mph = uCi/cc at j (Xu/Q) mJ (windspeed) (distance)

3C-1.13:12

i il

! . l 0 ECURS .E .x S*r-*ut0W 4-

\ i\ l I IIIIIl

{1.0

.;' *O USE T*A?S CU FM _

\ l lll t iIIl l

3 Flot the point representing gan=a -

2 N radiation exposure rata (mA/hr) and -

-4 N projected duration of exposure (hrs). .

\ _t

,g , .N't\

\ Leimate the projected whole body dose

<\ h s . -

fr=a potat.

che curves above and below the .

-2 s s s , ,-'

7 .

x. s x .

.x..x_ . . . . . . . . . . . . . ...

x x iN , i.w_w. . .i,.. , i i i 4 g, N e!e = 1 -

i N I NJ #N ii s sL N e _ i e 6 Isei e i I i iti -

\l 1 f\{lk l  ? N Ma,i '

l.Illi l i l I

'I Z "I 2- '

~"

~'

l 104 _

\N \\is -

s x s.

,. , ,s W ,*.

-2 3

. s , , s a 7_ s s .

s.

x ....s_..

s .s s .=,

~

O N .y, s .x. , ,m..v . . . . . . . ,

. . . . + N N .s; ...x, N g~l\ . . . . . . . .

1\ l N l i i ! ! \"4 l\ l\l N l i I f\ \l 2

- 10 2 g 1 \l 1 l IN iill I I I l Ili 8

\l \ N INil \hi I i lill Z -7 g g,

~4

,! 102 -

NN.lN s l N N%U^\\( .N i N M^ -

1

. 7, s.

m s

~,

-2  !

=

E s .

u x

e v i . i s3 -

., . x x;

x .

ix,..N

..x..

s . .

s

.s N N .N e . .X

.x

-v .

.m m

=> 4- f\ l (\ l i I e i N.T 3

l\ l t\ t t I IIl\ t\ t\l N ili U 3o I M i Milli \S l 4 i (N lill \l i N l'k11 -

-7 =

111 liYl . 1 11 INI K l Wil 2_ l -

~- -.

N N lI N s s N Ig.

i N

\< K .s 102 -

.\ A. l '\ -

-2 t s .

7 . ss s s_, , s s ., .

. . .. si s . .%.. x .

. . . . . . . . x. .x, x.

. . . .y g_ i4 6 . 11i1e /N Is i e i I e f\ (N i

.x, a

s#

.,,.y eai C

-. to-4 I i i i lilll ~ '*I iN I N illl \ f M l N ili -

2- l lllll l l\ l \ l\lN, - -

4xic-5

' gl t s

\ N  :

10 ls ' N i i i . . . . .

. . .' IA i 0.1 .2 4 .7 4 7 10 . .  ;

• 1 - 2 2.0 40 70 100 i

rcJected exoosure duration (hour s) l

?! E 1 Projected =nole body gasma dose as a func*1on of galtria exoosure race and ;rojec:eo duration of exoasure f

i 4 ( ' ) 3

... ~ .

l ~

5C-1.13:13 O

1.'S HOURS AFTER SHUTDOW =.-1.0

4. .

\Nl l l l 'l o Usr nts cupit

[ -7 4ex i Plot the point representing stina 2- \

radiation exposure rate (=Jt/ht-) and

' N .

_ _4

'N projected duration of exposure (hrs).

\'\ \ \ Istimate the proj ected whole body dose

~

\ N e

g5. - f rom the curves above and below the s s. i .s, , point. - -

-2 x n .x. .s.  ;

7 . , , , ,

o

, x 'x. x ...i .

x_ . . . ... .

x x 6N eiss e_ w . , ,

.g 4- \ '

\ ' N '\ ' ' D\' - II E

\l \ Ni h iM'N o,1 .I ll _- -7 2- ' '

s% 's %

-4

'N N -

104 - '- - \ Z x

s s

x.

s. .s-- s , s u

-2 $

v 7_ . ,, s, x _s s . x . ...y x .xx. 3 . . m .

T . . . . . . .

y .x,,...s, y y e x_. . .~. v x . . u C - \ i\ l N Itill W IN INI N lli N \1 I i i f 118 = 2 ;

! 1 \l 4 l Mll I \l 1 N I N I' N h_ l l I t ill Z -7  ;

w 2-N x ', s s s N w

-4 i.

\ N

• N N

~

3 \ \

?. 10 -'. x

' ~

e

's . - is . s v , ,

s-

-2 o v

t 7, s . .s , m x. . . ,_ ,

s .x y .

, x x . .

. , . x . s ...x. x .

t g .x. y .%. g

x. e x. . ..s - y e xi I . eiN N N .w . e . s i 4, ts 4 (N s i l l %r is i .steset N IX iN Nie, g 3 I N l Nlll l

\% l 4 i N llll \ l 1 N l'k11 -- -7 a 2- -

-4 N 'p -

N N N N N

\IA ^

g kA \\ \ N

~

102 -

s s N N - -2 s i 7, , , ,

... % x s_. . x . s. . . ., .i

. . . . . . . , ss . x . ..%.. x . . . ..x.6

, , . . . . . . . y. . x , , . . .x , x. ,y,,...N j g i i e i i t lll N I t\ t i Iilr\

10-8

/\ t Ni e I ill -

i i l I i lili i NJ l N iill \ l M I N lil '

-- 7 2-l I

l N'

lN \l\ Nl b- w

~

4x10-5 l

l 10

\ ' '

\' h '

i i i . . . . . . . . .

0.1 .2 4 * .7 1 2 4 7 10 2.0 40 70 ICO

, projected exposure duration (heurs)

,#2

' 2 Projected whole body garrr a dose as a function of garma esposure rate and projected duration of exposure l

C s.

i

':C- 1.13 : 14 i]

' 4.

.\ i\ l I ililll 2.5 HOURS .VTER SHUTDOW c Usr ats curit .

= ' - 1. 0

\ t . %xli ll l Flot the point espresenting gamma -

7 2 radiation exposure race (za/hr) and -

.\

NN ,\

N N N

\

projected duration of exposure (hrs).

Est = ace the projected whole body dose

-4 105 from the mes awe and helcn, the s s - point. ,

7, s x.x.

- s , .x.

x . ..u,x.

m , . , . ..

-2 N 4 eN eii% _Nm e . . ,

4 ,, N i \ I N IN I s e it. N I . # leei#

t iieti I e 6I -

1

\l \ N lhll 3 N'o) l Ill ( illl

~

Wilt 'N T4y ' _

7 2

hs\.ys,1 N .,

l 4 l 'l Z N l' v. - i\ N 4n s

g g4, _

7 s

s s

1 .

s

-1 1

.< _ ,ss s

1N 4 .c

-2

$2 x .

....y. x.x. . . ~.s . n. s-v T y .~ x i . . .~, y 3

.y . ..u x

l5 4 \ i\ l N i 111  % IN INJ N l i i f\ \l 3

$ i I I I I fl - 2 =

\l 1 I NIll \l 1 N INil \ s I ' l illi --

2

_7 3w ' 2-s N s N w s -

~

-g 0

\ \ \IN \ \,N g h

=

? 103 - 's -

N .\ '

VN O I

~ ,

e- -s s .s . m s. .

s . , ,

-2 ,5

, x . s . . s s n .x ,

3 . s . s . ..s., x .x e x. eu...w w i s. . . . w -y N

-s .s.  ;

1 .N i .t a.

i 4_ rs i N etiIN# f\ l N t I lil\ IN #N N I 8: = ,- 10-3 =

1 \{ l Milli %l M i N llll \l 1 N INI _7 2- l \ N!lf -

\ls \ ~

\l.\

g \y A s

\sm \ -

102 -

\ N 7 . m s. .

x . s s

x. .

-2

. v s . .%.. s . . . . . .,.

. . . . . . . x, .N. . s . .t. y .x,

,...w 4 8 I I a 66tt .N .N l l e s (N ts l N_# : e,s -

10-4 I I I IIIil i N4 i N I!! ' \ l N( i 'N l l i E

_ 7 2 I l lll l\ N h 1 Nl1 NlN Z

- 4 x10-3 10

\C I

\ \l \- ^ 3 J

. s . . . . . . . . . .

0.1 .2 . 4 '. 7 1 2 4 7 10 2.0 40 i ,

70 100

rcJected exposure duration (hours) nm 3 Projected =nole body ganna dose as a function of ganna excesure este and projec

ea curacien of exposure

.) .

-.,n -

i . .. . . 3c-1.13:15 i

4 4 3.5 sctms A.=m sarcow

\bI \

l llllll TO UsE

• MIS c2APM *

\ \ l Flot the point represasting ga=sa ~

2 -y 2 .

I radiation azposure rata (s2/hr) and -

% N projected duration of exposure (hrs). . ~

\ \

4 3

105 .\ N s s s

\ N

,s, Estimate the projected whole body dose f rom the curves above and below the point. .

~ ~

3-7 s n x , . v.

% iN. x . ..x..x_ . i,...

-2 N

4 N ee, uw

,N 4 \ I N i s) IN i il L N1 I e ' e is I i:

\l 1 fM IMl M Mo,l i ll t

l ll l i il I lli 3 ~ 10'

z. K 's K t 's T ie i..e x, .x, .,;j e i .N3 N. .s. ....%

4, i i e ieeil a N t Ne e iiits tN e Ne ie a

l l l l llll ~

1N l IN lill \l M l IN ll! -

,. I I II I I 'il ylM ' KIN IM Z -'

- s N, N

s

- 4:10-5 gg a i y s, ls.N l 0.'1 .2 4 .7 l 2 4 7 l'0 2.'O 4d 7'O 100

rojected ex

osurt duration (hours) 8 "" 4 Projected =nole bocy garma dose as a func:1:n of ga.ma exposure rate ana ;rcJectec duration of exposure l

G l

l

_-_ _y.

. . 3c-1.13:15 i

i I

i 4.5 EOURS .WTIR SEUT::0W

\ l\ l l .I l l l f l TO USE TM!! CRAP' 1.0 ll Flat the potat representing gn=ma Z 2\  %

q lI radiacion exposura rata (sA/hr) and projected duration of exposure (hrs).

-7

\

10 *

$ NN N N

\ Escinate the projected whole body dose fna the cusns abm and beb the point.

4 i

7-x x

s n

x x.

x 1

1,

..t . , . . ...,7

, , x.x. x . . ,1. , x _ . . . . . . . . ..4 .. -

x N .N e , i N, w e i . 4,is e 6 ee'is -2

~

A t \ I NJ IM i l - 'L \ _ i t i I f il 4 I I I Ill

\l 1 lN{ lM I '

N }\a,l l l l l ll l l I lll! -

1

• - -7 Nx 'sy N

.,.y s x%l  :

ic4 -

,_ x x .A ..

, .. . ~ , , ,_ -

x n x t s >s x .N -

e 7- x, x ,.,,t., x.x. , . . .w . x . . . - -

s y .y . .,%,  % N .N . ..u x + * ' . . . ' '

-2 3 v

h, .

1. ~ \ l\ i f\J l i t i lN(*< l\ l\J N lllN \ l I I I Ill

(

1 \l \l Mill! \l \ N I N il \ )h I I l llll

-to-2 %

2-

's \l \ ls,i't{ . '}\ s W!k s Ul \ -

llll 5 -7 -

5

\ a 0

3

\g s

\

'I i \. l\ k \

N

\

\\ \ -4 t

3 .

g-' 2. 10 - < nx x- -

2 g 's y 's, ,

y ,

y .s x (

x w u 7 ,, 3,, x . x . .s.. x .x. N - N .' - -g a j xi -y i ieQ, N i \t ie eiN N N '\1 \

• 5 tg s (N i e i i e IN/ i\ q l\ t i I I I l\ l\ l\l N IIl O

• #~

l N{ l Milli N% l X l f\{ l l l l \l N N INI 3 '..

2-I lll lM .

T l1 3lhd 1 s I NDS s 5-7 3,

i

\is s N N' N

.s \ ~

_ _4 jl ,%' \ l\ t, %

icz. .

, '( g s 's . s x. .w 7-y., ,

, , 1 . . , '

-2

. . . . . . . . x. .si e i . ,1e y x. e i s.%

4 i e ie eiiai- N rN I i 16if\ f\ t 'N i i i I l i I I ilill -

I N I N Illi \ l 4 l N ill -

-7 xg\

Nl.s 3l l ,% - 4x10-5 -

. 10 , , e e s e . -."

s , , , e 0.1 .2 4 .7 1 2 4 7 10 2.0 40 70 100 projec.ed ex;2sure duration (hours)

Pmjected =ncle body carma dose as a functicn of garma ce CURE 5 execsure rate ana arcaicted curatien of execsure o .

~

_ . _ - - - , - - . - - - - - - - - - - w - - . . , - __ -+ Q - , - y

s CC-1.13:l/

4- 6.5 HCGS AFU.R ScTm:CW O -

\ l\ l i lIiliI

~

to ust wts curw

\ . 4,\ l Illl II I l Plot the point representing ga==.a .

2 radiation exposura race (=A/hr) and

• g, \A NN\ \

N N s projected duracima of exposure (hrs).

Esti=ata the proj ected whole body dose

., ='*1.0

[ ,7

(

s ,

from the curves above and below the point.

\ s x s

-4 7* x. s.

. v. , . .

- x x s, y. ,,ti.x_ ,%#,

,_ x es ist isinis xi ,iiiin i

iiiin -

NI N N iMil Nt Mo.I I I t i 11 1

-2

,_ K s K'Ns s.s, ftt. M4 I I I Illi I I lil' = t N s ',< \x s xmJ -

-7 3g, N N. s %.. -

s .

. . . ~.=

7- s_ s

-4 s . s. . ...,.-.,-

. , ,i s .s s ,

s, s

,s.

. . . . . . . .w _

. . . . ~ ~.s. -

...s. s . _.-.

t N IN I N ll11 % IN l\l N l i i f\ \1 . . . . . . .

1 \l 1 I iM Il11 1 I Iiitt -

-2 5

\l \ IN I N Il \hi I l lIil 2- \ ls h lIN -s h l sM Ms lDN s 11l l l lll =. 2 e s ,

a N 4 N N '

N'4s '

-7 e 10 - x 3

s. .s s

\ .

~

-4

g 7

s . . . . . . . .

. ... s. , 4

... . . .s . ,- e

. s, . . s . . . . . . y 3, .s ,

,s, ,,,,s,_ s, ,s. ,,,,~

s

,s.~..s.

s ..m...s

,_ s, i , , , s, ,s , s , , , , , , s ,s i s , ~ , , , -

-2 x

iN i INilll 41 N i N llll \l % N INI l

e 2- l\ lM- l\l l \l l O' ~ l"~

s y s x s x

1,2 .s -

e, xs s, s

N Ny  : _7 e-i s i,s -

-4 7- .

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- s . . . . . , . . . . ~. , 1. -

. . . . . . . . s. .s, . ...s, s, .s. ....x

-s , s,,,,,s s, y,,,, -

-2 l l l l l 1 l11 IN l IN I III \ l N - i .N l I l; 2- Ill lll l l\ ' l \ x!\ IN = 4 y

Nxlis 10 , hs e s s -

0.1 .2 .4 .7 2 4

- . 10-5 1 7 to 2. 0 40 70 1C L projected ex;osure duration (bcurs)

,G3:

ce . 5 . P sjected whole bocy gan a cose as a function of ga na ex:esure rate ane ;ro:ec:eo curatien of emoesure

• .)

1 J

,00-1.13:18 i

) \ ?\ l I llIlli

12. 5 "OURS Az a.s sc.u wC'JN To Usr 'Is c u PM Plot the point representing gan=a

.i 2- \ radiation exposure rate (=A/hr) and -.

NN\.

projected duration of exposure (hrs). J Estisate the projected whole body dose o 105

\ l\ l N free the cvrares above and below the .=> - 1. 0 N y 1 . s potat. .

7-s x s v. . . . . . .

. . . .g . .

7 xe x. x. . .i.x_ . . . . . ... . . . . .e.

N X eN , e e N. e_ w e e 6 e iet i e e es**

!o \ $\ L\j IN(lli b \ 1_ ~ ~

4, l i i i iil l l l I ill

\l \ N lM N Mo.1 l l l ll ll l l lll ~

W

?

l 2- K s s s ht M4 -

s l l l l l'

-z o

74 l\ l As /.'

• N A.! $ ,= - 10*1 7"

s s

s s

.v,,> s s.

s s

,c

.- 7 x e s ....K.e xe s .w ..cv.ey s; . . . . . . . .

7 e \s e e ..Ne se N e s; *sess x +

e e e e.e d

e l

• - \ l\ l sj lllll N l\ l \l 4N I l i f\ \l l l I i lIl

~ ~

1 NI 1 I IN illi NI \ N INil \ A I I I lill -

! w 2- 1 ylh lM s

. h l Qk 3 Ql lllll

' g ,

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0

\s N t

\s\l \s E i

g, 103 - m 1 N li\ N A .s =--10-2 **

s -

x . ~

l,., u s

s s .

7 s s y .. x .s s. .- . s s .s

~

i

-7 C

, x . t ....w .. s . X .s. s

.s,,,,,u, .x e

+N . .N. #

, s, ~ ,s....,~ ,,,,

N . , x. , e . s

, si s, , ,1, n ,x l s,ll..is ~,s i x i ~ , 3 . _ _,  :

3 l Nl %llll \% l Nl IN l lli \l N N INI ~~

J z- l l'Li l NL . 'k I 'kJ I N' s' ., s s.

'k sl 'kfKit -

-z  !

=

2 s

% N\ N "i b

\'\ si+f _ _1c 3 : '* ~

s , 3

- -7 e 7- .

.. ,.s

v. t .

s _.

y..

.s g .

s

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. , , , . . . . , .x, si , i . ct, u .s. ...es_ ,4 1 i t i e f 1ii PN I f\ t 6 I i 6 (\ sI \l i e iI i I I i Illit i \1 i N_ l i ll N I N I 'N i ll '"-

2- l l l lll l lNls M 1 sl1llN s

~2

\i%i \ A i s

.N g. c-4

. . . ., . . . . . . . e 70 10d~ _ 7 i

0.1 .2 4 .7 1 2 4 7 10 2.0 40 projected exposure duration (heurs) -

l -

- 4:1c-5 FIE 7 . Projected whole body gama dose as a function of gama ex=csure rate and projected curatien of ex;csure a

l 9 ..

)

.SC-1.13:19 Ie . a, 7- 3 's d6 x .s , , . . . . . . . _

I t i t6e14 4

\l N 6 I I t t il

~

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_-ic s ss s' s.

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10 3-

- i s . s . s. - s. . ....

r- m . s-. . ~ .. s. s . . .... . --s

,i... e N N 6 is '

e .w u . x . . _ ,

4. N i \1 6 N t t i e'? N A6 6ta it- I s N N I Nil 4 l'N i Ki l i li en11d l --:

A IN N lih. 'k N NJ ,ll :".T

\x i,.

. ~ s s _ ,,4 x 2 s

\s s s-N s

+

\s\ x xs

~

A

-r J

i 4 10 -

~ -

. - _ a s ~

~

~.

~

• ~ 1 s --6

- 7- s . x.., .m s s m 3

- x .x . s , . s . . . s.c .s. .x....us. s _ a

\l NJ

~

\~*. ! \ t I \lii1 N \ g S g, m f f\ l i N. I N h_ I N i N 16 % N I % i i Ni 76 \  ;

i -- :

. ! 2-

. N sllMllM Nl \ l NlllN. '

N ,x I\ '

= lc5 ;*

a! ., o: - s s

\s N

's %gNN se s ~# . \ "r y -

- o x-  % W x

7- s s -,.s, ,. s s s

s. .v .s --s  ;

. . .x , . . . N . v. . x. i s . .N . . ss . x _ g

\e 6%iiN. Na E i e e N tin.. N i i i i ixo s.rxixiimrw N -: l' i

, I I I I t ilfN. K N NJ I(M.N '

\ \ 7 10 10, a N -

M .N. Y C7-

's -6 7-

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...y

, s

s. s. _

e ie i e i iis

'- . ......i. . . . . . 4; NJ y ,

. . TU USE 3!3 OIAP1 4 Flot thepointrepresentisttheexpasrell l\

2- . rate or concancracias and azoosure 12e 10 7

and estas. ace the projected anyroid dose 7 by 1starvolation.

. . . . . . . . . . . . .' l [

-6z 10 4

1, . .

- c.1 .: 6 pocascTro 7 1.0 sucsues Na ecuas: x J. 1 to* - :o 30

~

?!GLRE 8 Projec:ed thyroid de:;e as a function of either gamma expc:ure rate, or radioicdine concentration in air and the projected exposura tima.

x k

3C-1.13:20 s ( i

. .n.u.! %j . . r

.  :: '. ' a .- .=. h_tu fr.t./'

E. t:a ~ q : jp=::.m. .. r::r

. q ~'

t=,. H. ._3. .. .-

bry : **-?%. -~ i+3.4 M... [ % -"F +L%

i Il .- .

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73 ?.:.e=i 4

t?$

1

[=m . p.gm:--- ._-+ ,,_

e

=- .

~

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~

/ 9

, =. . 7

~

~

,=

---

• 1,=- - -

t 5

>=

f o ..

< 1.0 -

m  ;'

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(

i:

a r=t--- : -

y a o.3 -

=

C u

g3 _.

a.:

i 0.6 '

1 2 3 4 5 6 7 8 9 to 11 12 TIME (HRI AFTER CHUTCCWN '

FIGURE 9 CURRECTIUM FACTORS FdR THY 20!D IMHALAT10M C03E AS A FUNCTION OF TIME AFTER REACTOR SHUTUOWN THAT HA01010 DINE CCHCINTRATION 13 MEASURED.

. ,___ .. _ -.,. ,_ . ..-,.---.r- . - - - - - - - - - - - - - - - - - - - - - - - - - - - -

Pr:p. Rev. SC-1.13:21 i

9/9/71 KEY FACILITIES LOCATED ABOUT CINNA SITE Company and Product Distance from Site Direction from Site Duf fy-Mott Co. , Inc. Williamson 8-1/2 mi. Southeast Baby Foods

The Waterman Food Products Co.

4 Food Processing 3-4 miles South Ontario Kraut Corp.

7 Railroad Ave.

Food Processing 3-4 miles South SW Victor Preserving Co.

Food Procccsing 3-4 miles South Ontario Cold Storage Food Processing 3-4 miles South SW Waterman Fruit Products Co.

Food Processing 3-4 miles South SW Ontario Food Products 3-4 miles South SW Food Processing 7

Lyndan Products Co.

Food Processing 3-4 miles South SW Ontario Water District 1.1 mile East Williamson Water District Sh miles East Ontario Fire Department Ontario Center Fire Department Union 11111 Fire Department Ontario Town llall 110USES IN AND AEOUT CINNA SITE Ilouse on Lake Rd. directly south of p' int Beebee 1,500 ft. South Ilouse on S.W. corner of Lake Rd. and Ontario Center Rd. Loomis g- llouse on North side of Lake Rd.

S.E. of Science Center access Rd.Taillee llouse on private road north of above house 2,000 ft. S.W.

SC-1.13:22 EMERGENCY OFF-SITE SAMPLE POINTS I

z $ z $

z $

c U $ c d c $

SAMPLE POINT y g g ggg fg g f NUMBER LOCATION TEAM STAGE STAGE 1 Lake & Knickerbocker X X X X X X y 2 Brick Church & Knickerbocker X X 3 Brick Church & Ontario Center X X 4 Brick Church & Slocum X X 5 Lake & Slocum X X X X X X X 6 Bear Creek Harbor X X X X 7 Putman & Furnace X X 8 Trimble & Furnace X X 9 Knickerbocker & Kenyon y 7 10 Ontario Center Rd. & Kenyon X X X X 11 Slocum & Kenyon X X 12 RT-104 & Ontario Center X X X X (3 RT-104 & Knickerbocker X X j

14 RT-104 & Lakeside X X 15 Berg & Lakeside X X 16 Boston & Lakeside X X L7 Lake & Lakeside X X X X 13 Ontario-on-the-Lake X

19 Shepherd & Fisher X X 20 Trimble & Fisher X X X

21 RT-104 & Fisher X X 22 Trummonds & Arbor X X 23 Tru=monds & Walworth-Ontario X X 24 RT-350 & Paddy Lane X X 25 RT-350 & RT-286 X X 26 WALWORTH X X l 27 Stony Lonesome & Lake X X 28 PULTNEYVILLE X X X X 29 Salmon Creek & Eaton X X l - . _ . tl

.' SC-1.13:23

, EMERGENCY OFF-SITE SAMPLE P0'INTS z $ = $ z $

a = 4 m a j = = 5 SAMPLE LOCATION

$ $ $ $ b O $

POINT NUMBER OND TEAM STAGE STAGE 30 Salmon Creek & RT-104 x x 31 RT-21 & RT-104 X X 32 MARION (RG6E Sub-Station ) X X 33 Plank Road & Lincoln X X 34 County Line & Lake X x X

_X___

35 County Line & Boston y y 36 County Line & Berg y y 37 County Line & RT-104 X X 38 RT-250 & State X X 39 Salt & Plank X

_ _ X 40 Eastern Monroe Serv.-Cent. (Plank Rd) X X Al PENFIELD X X 42 Salt & Schlegel X X 43 Salt & Woodward X X 44 "

Klem & Whiting X X 45 Lake Road & Route 250 X

.- X 46 County Line & Plank y y 47 RT-21 & Farnsworth X X 48 RT-21 & Pound X X 49 Furnace & Kenyon X X 50 RT-350 & Plank X X 51 Plank & Five Mile Line X X l

t

- - -