ML20129F157
| ML20129F157 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 04/25/1985 |
| From: | Maine Yankee |
| To: | |
| References | |
| PROC-850425-01, NUDOCS 8507170256 | |
| Download: ML20129F157 (60) | |
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s 3 . ., ? l Dept. Head @ Proc. No. 2.50.4
- " PORC W % r d Class. A M00 g/A Rev. No. 10 Issue Date 4-25-85 Review Date 4/87
. 2.50.4 GENERAL EMERGENCY
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l DISCUSSION A General Emergency is defined as actual or imminent substantial core degradation or [j melting, with a potential for loss of containment. Integrity. The events included in a General Emergency category represent actual or potential substantial off-site radioactivity releases requiring immediate implementation of off-site protective actions. Assessment of radiolo protective measures necessary. gical parameters will determine the type of 1 i The decision to make an immediate initial declaration rests with the Emergency Coordinator. Prompt notification is made to the appropriate off-site authorities to jl " assure that sufficient emergency personnel are mobilized and respcnd to the event in accordance with their respective emergency plan arrangements. Public information concerning the event will be provided via appropriate mechanisms. The public will be alerted by the Public Emergency Alert System under this emergency. The State will activate this system, unless plant conditions immediately indicate a General u Emergency condition. Under this circumstance the Plant Snift Superintendent will d authorize activation of this system from the Control Room. 3 Other nuclear industry organizations will be alerted and requested to render assistance as appropriate. Federal agency response will be implemented in accordance with the Federal Master Emergency Plan. All emergency centers are activated following the declaration of a General Emergency. All personnel without emergency assignments are evacuated from the plant Protected Area. The Emergency Operations Facility (EOF) once activated, will provide a centralized meeting location-for representatives from all responding emergency organizations. The following appendices are attached and are to be used as check-off sheets by individuals responsible for implementaticn of this procedure at the various identified center locations: Appendix A Plant Shift Superintendent (Initial Declaration) Pg. 6 Appendix A-1 Plant Shift Superintendent (Escalation to General Emergency) Pg.11 Appendix B Plant Management Pg.17 i Appendix C Emergency Coordinator (Initial Declaration) - Pg.19 Appendix C-1 Emergency Coordinator (Escalation to General Emergency) Pg.26 4 Appendix D Radiological Evaluation Assistant Pg.33 Appendix E Communications Ass?stant Pg.39 Appendix F Manpower and Planning Assistant L Pg.43 i s, Appendix G Coordinator's Assistant
' Pg.44 Appendix H Radiological Habitability Assessment Pg.45 85071702568504j5 ADOCK 050
- PDR PDR F
- 3 Dept. Head q PORC I% [ % #eE((. Class.Proc.A No. 2.'50.10 Q
Rev. No. 8 Issue Date 5-28-85 Review Date 5/87 j 2.50.10 EVALUATION OF RADIOLOGICAL DATA ] 1 ]1 1.0 DISCUSSION l! i This procedure as to be used to assess the off-site radiological hazards due to an abnormal release of radioactive material by evaluating information received from within the plant, off-site monitoring teams, and environmental monitoring i stations. Radiological assessmen- is made to the extent of projecting doses to i the public from each source of data. The dose rate projections produced by j this procedure represent the best estimate possible for each method. If l projections from in-plant parameters are significantly different than those
] measured in the environment, it may be due to specific variations in the plume behavior which cannot. ce pre-determined. The results obtained from this procedure should be carefully analyzed since these may form the basis for l
protective action recommendations to the public. There are two sources from which information will be available for the analysis
! q of radiological hazards; in-plant (stack effluent monitor, containment hi range
) monitor, or other) and off-site field monitoring surveys (air samples and dose rates). From each of these sources, the projection of off-site whole body and thyroid doses are possible with the necessity of employing different techniques at each area. In order tc categorize the different techniques, the procedure has been divided into several appendices.
When the High Range Stack Monitor or the High Range Containment Monitor are indicating measurable levels of radioactivity, Control Room personnel can make early initial estimates of the off-site whole body dose rates by using the computer system in the Control Room (use Appendix A) or the nomograms on the Control Room wall (use Appendix 8). APPENDIX TITLE PAGE A Computer Calculation of whole body dose / dose rate 6 protections at 1/2 mile to 10 miles using in plant parameters. NOTE: When the computer is working use thic method for calculating whole body dose / dose rates for stack and containment releases.
s s Proc. No. 2.50.10
; /m - "
Rev. No. 8
'. Page 2 of 50 APPENDIX TITLE PAGE.
5 8 Nomogram Calculation of whole body dose / dose rate ' 10 projections at 1/2 mile, using in-plant parameters. NOTE: Use the nomogram when the computer is not
.} working or to check computer results.
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- 1. Containment leakage dose calculation.
- 2. Stack release calculation.
j NOTE: For worst case conditions the stack
, monitor must read at least 500 mr/hr f before PAGs are approached at 1/2 j
a mile 3 j 3. Primary Vent Stack release calculation when
, the Victoreen High Range Noble Gas Monitor is i inoperable.
- 4. Steam safety and atmospheric dump valve t calculation.
. C- Thy'roid Dose Assessment from in-plant measurements. 18 NOTE: The assessment of iodine releases should be made as soon as possible.
D Evaluation of Air Particulate Data 23
,; E Whole Body Dose Rate Projections at Distance Greater 30
- Than 1/2 Mile. This Appendix is only needed for expanding the 1/2 mile nomogram dose rate projections.
F Plume Plotting 37 G Population Exposure Estimation 39 H Evaluations of Environmental Station Samples and other i environmental sample media. 47 These appendices should be used in the order that they appear since they are arranged in the order of priority. A description of the appendicies and the interpretation of the results are given below. Each appendix uses the existing meteorology conditions and therefore these parameters should be periodically monitored for significant changes. O G
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- 1 i Proc. No. 2.50.10 Rev. No. 8 Page 3 of 50 Appendix A describes how to use the computer terminals, located in the Control Room and the EOF, to perform whole body dose rate calculations. The program uses the same algorithms used to develop the nomograms along with additional I parameters that allow for the variation of containment leakage with containment j
pressure, the dose at various distances up to 10 miles and the plume arrival l times. A CRT is available at the computer terminal that displays containment
- i absolute pressure, upper wind velocity and lower wind velocity (15 min. avg.)
j and the 195 ft.-33 ft., temperature difference, j Appendix 8 may be used by Control room or Emergency Center personnel to obtain l an estimate of the release rate and/or off-site whole body dose rate at 1/2
' mile due to a high level stack release, a containment leakage release or a 1
release through the main steam system during a loss of coolant accident (LOCA). This appendix uses the Emergency Off-Site Dose Nomogram which requires
, the following inputs: time after plant shutdown, containment hi-range monitor
! dose rate, wind speed, delta temperature (for atmospheric stability class), and j the high range noble gas monitor response. The information obtained from the Nomograms is Total Noble Gas Release Rate and Off-Site Whole Body Dose Rate at 1/2 mile. It must be acknowledged that information obtained from the i Containment Leakage Nomogram is very conservative, since it assumes a containment leakage of 0.1% per day which is the maximum allowed design basis p leakage at peak containment pressure, therefore, a correction for containment t Q pressure is available. Appendix C shuuld be used by the Radiological Data Evaluator to assess the potential off-site thyroid dose to the public by evaluation of the Primary Vent Stack (PVS) charcoal cartridge for halogen release. The appendix describes the method by which the charcoal cartridge at the stack should be analyzed and evaluated to obtain iodine concentations at 1/2 mile. From this result, the Field Sample Thyroid Dose Nomogram may be'used to obtain Adult and Newborn thyroid dose estimates. Appendix 0 describes how to calculate the airborne particulate activity from the field data. The appendix describes the methods to he used to evaluate the results reported by the off-site survey teams from the iodine cartridge field counting and to analyze the sample at the EOF for more accurate radiological estimates. These results are also used in conjunction with the Field Sample Thyroid Dose Nomogram to obtain Adult and Newborn Thyroid Doses. As data comes in from the field, it should be recorded on Data Sheet G. Appendix E describes the method to be used to project the in-plant and field measured estimates of whole body and thyroid doses to distances greater than 1/2 mile. The results of these projections should be compared to the field sample measurement performed by the Off-Site Survey Teams. In the event that these measurements are significantly different, it may indicate one of the following: p a) Containment leakage estimates are in error, or, j O
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/ .i Proc. No. 2'50.10 Rev. No. 8 '.-(m Page 4 of 50 b) Meteorological conditions have changed rapidly, or
'i c) Actual plume dispersion is extremely stochastic (variable). Appendix F describes the manual method to use to plot the path of the airborne radioactivity (plume) as it is dispersed downwind, Appendix G is used to estimate the accumulated dose received by the population ]y living within the Emergency Planning Zone. Appendix H calls attention to the use of the environmental station's samples, i soil and other enviornmental sample media to be used for dose assessment to the public during the later stages of the accident. The analysis of these samples will be made when the Yankee Environmental Lab van arrives or the samples are sent out for analysis. Therefore, this section describes sample collection and
, labeling techniques that should be employed.
2.0 OBJECTIVE 2.1 To assess the off-site radiological hazards associated with an abnormal release of radioactive material from the plant so that appropriate protective actions to the public may be recommended. k-/
3.0 REFERENCES
4.0 PRECAUTIONS 4.1 Meteorological conditions are subject to change and must be closely monitored and recorded during the potential radiological hazard. 4.2 Results of the different dose projection methods must be carefully compared for a complete evaluation of the radiological off-site conditions. 4.3 If the PVS High Range Noble Gas Monitor (RM 3903)is inoperable, the RM-16 monitor (RM-16) must be used for stack noble gas release calculations. The graph in Appendix 8 Section 5 and the ncmogram located in the EOF E-Plan cabinet must be used as these parameters are NOT in the computerized dose calculation program for stack releases. 5.0 PROCEDURE NOTE: At each stage of the procedure, pass the appropriate information to the Emergency Coordinator so that protective actions may be recommended. 5.1 Upon notification of an Emergency condition, complete the steps in Appendix A to determine the off-site whole body dose rate at 1/2 mile. Use Appendix 8 if the computer is inoperable. O
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- Proc. No. 2.'50.10 Rev. No. 8 Page 5 of 50 o
t j 5.2 Check with the Chemistry section to assure that they have implemented i Procedure 7.1.3 " Post Accident Primary Vent Stack Sampling" if the stack ti . radiation monitor indicates a release is occuring. 5.3. Chemistry results should be reported to the Radiological Data Evaluator. 1; I 5.4 Once the Primary Vent Stack charcoal cartridge has been analyzed or off-site iodine samples have been collected, determine the off-site projected thyroid dose as described in Appendix C. If this sample has not been taken, go to a 5.3. 4 3 5.5 As offsite data are available determine offsite air activity using Appendix 3 D. 5.6 'After the 1/2 mile projected doses / dose rates have been determined, go to 7, Appendix E and calculate projected doses at other locations of interest. j
; 5.7 Make periodic estimates of the plume travel using Appendix F.
1 ^ 5.8 Make periodic estimates of the accumulated population dose using the procedure described in Appendix G. 5.9 Under the direction of the Emergency Coordinator, make provisions to collect the air samples at the environmental sample stations and other environmental
- j. samples (soil, water, vegetation, milk, etc.) as outlined in Appendix H.
- 5. ecount for any steam generator blowdown that has been discharged to the
.vironment during a primary to secondary tube leak incident. Have the l
Chemistry section evaluate the release. i 5.11 As updated information becomes available, repeat the steps in each Appendix [ as appropriate. 6.0 FINAL CONDITIONS 6.1 The radiological hazards associated with the plume exposure pathway have been defined by the best means available. h NOTE: When reporting results to the State of Maine C.E.P. use the Data L Reporting Sheets Form 3 Meteorology page 11, Form 4 Projected Doses
- - page 9, Form Y Primary Vent Stack Iodine Analysis page 21 and Form X 1 Off-site Survey Report page 22.
, 6.2 All calculated and measured parameters have been logged on the appropriate data reduction forms and recorded on the EOF status board.
l 6.3 All information and data forms have been given to the Emergency Coordinator. 6.4 Environmental Samples have been taken and analyzed.
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- Proc. No. 2.50.10 Rev. No. 8
, Page 6 of 50 APPENDIX A Computer Whole Body Dose / Dose Rate Projections 1.0 Computer Tecminal Locations lI 1.1 A Decwriter that will call up the off-site dose program is located in the l ,. Control Room.
- l 1.2 A system 34 computer terminal and CRT screen and a Decwriter input terminal
- ! fc; the fbdcomp computer are located in the EOF.
2.0 Computet Operation - System 34 2.1 Turn the computer terminal on. 2.2 Adjust the intensity of the markers that are displayed. O NOTE: If no markers are displayed and varying the intensity knob does not ,. bring uo the markers, call the computer section for help. 2.3 To get the sign on display on screen do the following: i: 2.3.1 Depress and hold the up shift key (arrow pointing up). 2.3.2 Depress the Sys. Reg. key (still holding up shift). 2.3.3 Depress the Enter / Rec. Adv. key (still holding up shift). 2.3.4 Release the up shift key. The sign on display should be on screen. NOTE: If the sign on display does not appear on the screen after 11 several attempts call the Computer Department for help.
. 2.4 Type any one of the following names in the User ID field of the sign on screen:
o Tom, Dick or Harry 2.5 Depress the key on the right marked Field Exit.
. 2.6 Type MYAT in the password field. The password will not be displayed.
2.7 Depress the Enter / Rec. Adv. key. 2.8 A Guest Menu, a display of 24 options that you can choose, will appear on
- i. screen.
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l a j .t i ' Proc. No. 2.'50.10 O Rev. No. 8 ( Page 7 of 50 2.9 Type in the number 21. Depress Enter / Rec. Adv. key. This will get the Off-Site Dose Program. l 2.10 The screen will display the following: i j Maine Yankee Computerized Off-Site Emergency Dose Program a j -- Please note that all numeric inputs except time since shutdown require a decimal point. l
; Please enter the time since shutdown in hours and minutes (hours can be up to 3 digits, so zero-fill as necessary, (e.g., "013:45 for 13:45).
2.11 The instructions to put in a decimal point after each numeric entry (e.g.,
- 12. not 12) must be followed or the computer will not accept the information and will repeat the request for the number. If a decimal point already
; exists in a number, you do not need to add another (1.5, not 1.5.).
2.12 The computer will continue to ask for the input parameters necessary for the
; calculation. Answer the request and depress the Enter / Rec. Adv. key after , each entry.
p) ( 2.13 After the last entry (Containment Absolute Pressure) the computer will print out a list of the inputs, followed by the instruction to " Press Enter Key to view Next Page". 2.14 After pressing the Enter Key you will get the output information. (Dose rate in mr/hr from 0.5 to 10 miles, plume arrival time at each distance, release rates from the stack and containment). Record this information. 2.15 The question Rerun Coed is asked at the end of the output table. If you answer "Y" for yes, you will be returned to the beginning of the program. Do this only if you don't want a print-out at this time. 2.16 If you answer "N" for no to the Rerun Coed question you will be returned to the Guest Menu listing. A print-out of the data input and the results will be produced. To prepare terminal for another calculation, choose option 21, 2.17 Complete Form 4 or attach a copy of the printout and route to the Rad. Evaluation Assistant. 2.18 You can sign off the enmputer by typing the number 24, the " Sign Off" option. 2.19 Never power off the terminal unless you sign off first. i v t 4
i Proc. No. 2.'50.10 Rev. No. 8 0 Page 8 of 50 3.0 Computer Program - Modcomp Deewriter Input 3.1 Turn the Decwriter on. {
! 3.2 If a $ (dollar sign) is on the screen go to Step 3.8.
l 3.3 Press and hold the Control Key and then press the A key. i l 3.4 Release both keys. You then get operator control. i R 3.5 Hit / BAT 001/E,, BM (slash, BAT 001, slash, E, comma, comma, B,M) or at the EOF terminal, hit / BAT 002/E,, BM (slash, BAT 002, slash, E, comma, comma, B, M). 3.6 Hit carriage return. I
, 3.7 You will get a $ (dollar sign) in the screen.
3.8 Type in the program name, COED. 3.9 Hit carriage return and dose program will come up. 3.10 Follow instruction on the screen. i I. .I u l:
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Proc. No. 2.50.10' 9 Rev. No. 8 l Page 9 of 50 FORM 4 - PROJECTED DOSES Info Current at Time /Date d ll Noble gas release rate I j j! Projected Whole Body Gamma Dose Rate (Sector-Averaged) d j Distance Dose Rate Transit Time
- 1/2 Mile mr/hr hrs: min 1 Mile mr/hr hrs: min 2 Miles mr/hr hrs: min 3 Miles mr/hr hrs: min 4 Miles mr/hr hrs: min 5 Miles mr/hr hrs: min 6 Miles mr/hr hrs: min
. 7 Miles mr/hr hrs: min 8 Miles mr/hr hrs: min 9 Miles mr/hr- hrs: min 10 Miles mr/hr hrs: min O)
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- Transit time is the time it takes released material to travel from the release point to the field at the indicated distance.
- 1) Prepared by Radiological Data Evaluator
- 2) Original to Radiological Evaluation Assistant for Approval
- 3) Copies to: Recovery Manager NRC Radiological Evaluation Assistant Radiological Data Evaluator
- 4) Approved original to Emergency Coordinator for Approval
- 5) Emergency Coordinator's Original to Hotline Operator
- 6) Transmitted to State by:
Hotline Operator Date/ Time
- 7) File Original 9
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- Proc. No. 2.50.10'
? Rev. No. 8 g Page 10 of 50 APPENDIX B
. Nomogram Calculations of
- Whole Body Dose / Dose Rate Projections At 1/2 Mile From In-Plant Parameters
( l NOTE: Nomograms are wall mounted in the Control Room (behind Reactor i i Protection System) and in the EOF (at the dose assessor station). j 1.0 Oc termine the value of the following parameters. i
, 1.1 Time after Shutdown, t (I-RS)
(if reactor is operating, set t = 0 HIS) l 1.2 Containment Hi Range Monitor Response, Oc (R/hr) (If applicable) i 1.3 Containment Pressure, Pc (PSIG) i l 1.4 (ange Noble Gas Stack Monitor Response, Os (mr/hr) s .pplicable)
- 1.5 Steam line radiation levels (if applicable) h a
1.5.1 Affected steam line 1.5.2 Main steam pressure (PSIG) or Atmosphere Steam Dump. 1.5.3 Steam line radiation level, DSL (mr/hr) 1.6 Wind Speed (previous 15 minute average), u (mph). Log on Form 3. 1.7 Wind Direction (previous 15 minute average). Log on Form 3. 1.8 Met Tower Delta Temperature,AT (oF). 1.9 Number of Primary Vent Stack (PVS) Fans Operating. 1.10 Estimated Duration of Accident (only if accurate estimate can be established) 2.0 From the following table and the value of AT, determine the atmospheric
- Stability Class and report on Form 3.
DELTA TEMPERATURE PASQUILL ATMOSPHERIC T (oF) STABILITY CLASS T 6 -1.74 A
-1.73 4.T 6 -1.55 8 ,
n -1.54 6.T 6 -1.37 C
') -1.36 6 T +_ -0.46
-0.45 s T 6 +1.36 D
E
+1.37 6 T 6. +3.64 F
+3.65 4.T G
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Proc. No. 2.'50.10 Rev. No. 8 I Page 11 of 50 i FORM 3 - METER 0 LOGY
'l
{l Info Current at Time /Date
-) Delta Temperature (oF) (Upper Minus Lower) 0F 1
l Stability Class - Pasquill 10 Meter Elevation Wind Speed ] mph 10 Meter Elevation Wind Direction (from) degrees
. 30 Meter Elevation Wind Speed mph .i 30 Meter Elevation Wind Direction (from) degrees NOTE: Use with Form #2 " Release Data".
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- 1) Prepared By Radiclogical Data Evaluator
- 2) Copies To: Radiological Evaluation Assistant NRC
- Radiological Data Evaluator i
Original to Emergency Coordinator for Epproval
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- 4) Approved Original to Hotline Operator
. 5) Transmittal to State By: I Hotline Operator l Date/ Time
- 6) File Original
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Rev. No. 8'
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{L J y_ LOCA Determination j* 3.0 From the In-Containment High Range Monitors (RM 6113A & RM 61138), determine the LOCA designation from the following table. - IN-CONT. HIGH RANGE LOCA TYPE MONITOR RESPONSE DESIGNATION OF LOCA 2 R/hr 6 De 6 15 R/hr I Large Primary Coolant Leak 15 R/hr 4 De III Fuel Melt LOCA Containment Leakage
- 4.0 If the In-Containment High Range Monitor response is greater than 2 R/hr, then 11 determine the total noble gas release rate and the 1/2 mile whole body dose D' rate using the Containment Leakage Nomogram as described below. Log these d results on Data Reduction Sheet 8.1. If this monitor is less than 2 R/hr, go y to step 5.0 since off-site doses will be negligible.
- i 9 4.1 Locate the " Time after Shutdown" axis, at the appropriate value of t(hrs),
d draw a vertical line through the curves of parameters J(t) and J(t)/F(t). i: 4.2 At the intersections of this vertical line with the appropriate J(t) and 4
- J(t)/F(t) curves , draw a horizontal line to the right, through the y appropriate diagonal lines of the In-Cont. High range Monitor readings.
41 f 4.3 From the parameter J(t) horizontal line, locate the intersection of the e ' appropriate "In-Cont. High Range Monitor" response and proceed vertically
- downward until you intersect the " Noble Gas Release Rate, Q (uCi/sec) q scale. Record this value on Data Reduction Sheet 8.1 (page 17).
4.4 From the parameter J(t)/F(t) horizontal line, locate the intersection of the ] appropriate "In Containment High Range Monitor" response and procced vertically upward. At the intersection of the appropriate "ATMOSPIERIC y[ STABILITY CLASS", proceed horizontally to the right. At the appropriate a wind speed intersection, use the ground level (10 meter) wind speed, proceed vertically upward and read the value of the "0FF-SITE DOSE RATE" S 1/2 Mile, H mr/hr and record on Sheet B.1 in uncorrected 1/2 mile Dose Rate (mr/hr) column. 1 li 4.5 Record Containment Pressure (Pc) in psig on Sheet 8.1. Calculate K where K j = Pc (psig)/55. n O 4.6 Adjut,t the off-site dose rate for actual containment pressure (Pc),by multiplying by K. RecordthisvalueonDataSheetB.1(page17). If ~ release rates are to be used for any calculations, be sure to correct them i for containment pressure in the same manner. F h 4.7 . Multiply the corrected dose rate at 1/2 mile by the estimated duration of h the release to obtain the projected whole body dose, if applicable. Record {; this value on Data Reduction Sheet A. e i!
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Proc. No. 2.50.10 1 Q Rev. No. 8 i Q Page 13 of 50 Primary Vent Stack Release I 5.0 If the Primary Vent Stack (PVS) normal range noble gas monitor (RM 3902) response is high off-scale and the PVS high range noble gas monitor (RM 3903) reads 0.1 MR/Hr or greater, then determine the total noble gas release rate and the 1/2 mile whole body dose rate using the STACK RELEASE NOMOGRAM as described i below. Log these results on Data Reduction Sheet 8.1 (page 17). NOTE: If the PVS (Victoreen) High Range Noble Gas Monitor is inoperable, go to Step 5.6. NOTE: If neither of the above conditions exist, go to step 6.0.
- 5.1 Locate the " Time After Shutdown" axis on both the release rate function graph J(t) and the dose rate function graph J(t)/F(t), at the appropriate j value of t(HRS), proceed vertically upward.
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! 5.2 At the intersections of the appropriate LOCA designation curve of parameters J(t) and J(t)/F(t), draw horizontal lines to the right, through the "PVS High Range Mon." diagonal lines.
5.3 At the intersection of the horizontal line from parameter J(t) with the x appropriate value.of the "PVS High Range Mon." response, proceed vertically downward until you intersect the appropriate " Noble Gas Release Rate, Q(UCi/sec)" scale for 1 or 2 operating PVS fans. Record this value on Data Reduction Sheet 8.1. 5.4 At the intersection of the horizontal line from parameter J(t)/F(t) with the appropriate value of the "PVS High Range Mon." response, proceed vertically upward to the appropriate " Atmospheric Stability Class" lines. At this intersection point, proceed horizontally to the right. At the intersection with the appropriate " Wind Speed" line, use the elevated level (30 meter) wind speed, proceed vertically upward until you intersect the "0FF-SITE DOSE RATE e 1/2 Mile, mr/hr" scales for 1 or 2 operating PVS fans. Record this value on Data Reduction Sheet 8.1 (page 17). 5.5 Multiply the estimate of the duration of the release by the above result to obtain the projected whole body dose. Record this value on Data Reduction Sheet B.l. I NOTE: Follow Steps 5.6 through 5.13 only if the Victoreen High Range Monitor is inoperable. 5.6 Check to see if the RM-16 is operating. The RM-16 readout is located at the bottom of the center panel of the Radiation Monitoring System Board in the Control Room, fm 5.7 If the RM-16 is not operating check with I & C. (' 5.8 If the RM-16 is working but is not reading and the low range stack monitor is off scale high have Chemistry take a stack gas sample.
l P Proc. No. 2.'50.10 ; fq Rev. No. 8 Page 14 of 50 5.9 Use Fig. 1 Site Boundary Dose Rate Versus PVS Gas Concentration (page 1_6) 6 to estimate site boundary dose rate at the analyzed UCi/cc level. ., NOTE: The graph assumes the worst meteorological conditions. Another i method to use would be to calculate the release rate using the formula: J Release Rate (uci/sec)= gas activity' (uci/cc) X stack flow (CFM) X 470 l cc/sec/CFM With this calculated release rate go to the nomogram (Rev-l edition) and procede to determine the dose rate at 1/2 mile for existing conditions. 5.10 If the RM-16 is reading use the Rev.1 edition of the Containment and PVS Nomogram. This nomogram is located in the EOF emergency storage cabinet. ll 5.11 Use the Rev.1 PVS Nomogram to determine 1/2 mile offsite dose rate for the-4 indicated RM-16 reading in the same manner as described above for the Victoreen High Range Monitor. l' p 5.12 Data may be recorded on Data Reduction Sheet 8.1 (page 17). 5.13 Multiply the estimate of the duration of the release by the above result to obtain the projected whole body dose. Data may be recorded on Data Reduction Sheet 8.1. Steam Line Releases 6.0 If the main steam safety relief valves or the atmospheric steam dumps have been operated, and radiation levels are observed on the Main Steam Line radiation monitors, then determine the noble gas release rate and off-site dose rste at 1/2 mile from the steps below. -If either of the above conditions have not been met, j go to Appendix C and complete those items. NOTE: If Main Steam Line radiation monitors are not operable go to Step 7.0 (next page). 6.1 Use the Emergency Main Steam Line Release Nomogram to determine noble gas release rate and off-site dose rate. 6.2 Locate the " Time After Shutdown" axis, at the approximate value of T (hrs), draw a vertical line through the curves of parameters J(t) (the release rate function) and J(t)/F(t) (the off-site dose rate function). 6.3 At the intersections of the approximate LOCA designation curves of parameters p J(t) and J(t)/F(t), draw horizontal lines to the right, through the ey approximate diagnal line indicating the Main Steam Monitor Response. u, e-- ,--e....
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9 Proc. No. 2.50.10 g; Rev. No. 8 Page 15 of 50 6.4 Draw a vertical line down from the intersection of the J(t) release rate function and the Main Steam Monitor Response through the release rate scales
, for the various pressure set points for the Main Steam Reliefs and the Atmospheric Steam Dump.
6.4.1 Determine if the plant is on Atmospheric Steam Dump or if the steam pressure is at or above any of the relief valve set points indicated on the scales. 6.4.2 If the steam pressure is between two safety setpoint scales, use the lower setpoint scale since the pressure is not enough to lift the higher setpoint. [For example for a steam pressure of 1015 ps.tg use the 1005 psig scale - that scale would account for steam flow through all steam , relief valves that would lift at 1015 psig]. 6.4.3 If the release is via the Atmospheric Steam Dump, use the scale labeled ASD. 6.5 Read the noble gas release rate from the intersection of the vertical line drawn in Step 6.4 and the appropriate scale. 6.6 Draw a vertical line up from the intersection of the J(t)/F(t) (off-site dose rate function) and the main steam line monitor response to the U appropriate " Atmospheric Stability Class" lines. At this intersection proceed horizontally to the right. Where this intersects with the appropriate " Wind Speed" line, use the ground level (10 meter) wind speed, proceed vertically upward through the "Off-Site Whole Body Dose Rate Scales". 6.7 As in Step 6.6 determine the appropriate scale and read the off-site dose rate at 1/2 mile from the intersection of the vertical line and the chosen scale. 7.0 If the Maine Steam Line radiation monitors are not operable use the following steps to determine dose rates at 1/2 mile. 7.1 Send a technician to the location of the main steam radiation monitors and have him take a contact reading, using a PIC 6A, as close to the monitor as possible. 7.2 Record the reading and the Steam Line it applies to. 7.3 Use the readings obtained with the PIC 6A instead of the Main Steam Line Monitor Response for calculating the off-site dose rate from the Emergency Main Steam Line Release Nomogram. (
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! - ~~ APPENDIX 8, FIG. 1 SITE BOUNDARY 00SE RATE VERSUS 2
m=
-r" PVS GAS CONCENTRATION FOR 1 FAN (45,000 CFM) ,'
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Proc. No. 2.'50.10 S Rev. tb. 8 Page 18 of 50 APPENDIX C Thyroid Dose Assessment From Inplant Measurements i 1.0 Inplant Analysis of PVS iodine cartridge v. 1.1 p; Obtain sample according to Chemistry Procedure 7.1.3, " Post Accident Primary Vent Stack Sampling Procedure".
! 1.2 Once the PVS iodine cartridge (silver zeolite) has been analyzed, on the plant GeLi (if available), or the SAM 2 (if plant GeLi is not available) proceed as follows. l l
!; 1.2.1 Determine activity using the computerized analysis program. i 1.2.2 If sample is counted on the plant GeLi, the output information can be either activity (uC1) or concentration (uCi/cc or UCi/ft3) of I-131.
- If " Dose Equivalent Iodine-131 Activity" is provided by the computer, use that in preference to straight I-131 activity.
) 1.2.3 If counted on the SAM 2, calculate the activity' using the following
~
equation: I-131 (uC1) = SAM-2 Sample counts per minute - SAM-2 Background counts per minute SAM-2 Efficiency (cpm /apm) x 2.22 x 106 dpm/uCi NOTE: SAM-2 efficiency is posted on the instrument. 1.3 Determine the I-131 concentration at 1/2 mile offsite as follows. 1.3.1 Calculate the release rate using the computer program if available. 1.3.2 If activity (uC1) is provided, calculate the I-131 release rate, QI -131, (in uCi/sec) as follows. I t QI -131(uC1/sec) = (AF) (FSTACK) (FF ) (t) If sample concentration (C) is provided, calculate the release rate from: QI -131 (uC1/sec)=(C)(FSTACK)(28317 cc/ft3)(1 min /60 sec.)
/"%
_. .. .._ .. .m __ ._
' Proc. No. 2.50.10' Rev. No. 8
(~N Page 19 of 50 where: C= Concentration of sample, uC1/cc A= F Activity on charcoal cartridge, uCi F= F t= Flowratetothecharcoalcartridhe(CFM time since beginning of release t a cartridge was in the sample stream, sec.
! FSTACK= Flow rate out the PVS (CFM) , For 1 Fan, FSTACK = 45,000 CFM 2 Fans, FSTACK= 60,000 CFM I *If flow rate to the cartridge is given in cc/ min., convert to CFM by dividing by 28, 317 cc/CF.
1.3.3 Obtain the 1/2 mile diffusion factor (uX/Q) from Table 8-1 and the Stability Class. . NOTE: If st&bility Class E, F, or G, use value of
, Max. Ground Level uX/Q.
t 1.3.4 Observe the wind speed (u) in mph, convert this to meters /sec as
! follows:
u in m/sec = .447 x (mph). 1.3.5 Determine the value of,X/Q (see m-3) as follows: X/Q (sec m-3) = (u X/Q) u 1.3.6 Calculate the 1/2 mile I-131 concentration as below. C (uCi/cc) = Q I-131(uC1/sec) x X/Q(sec/m3) x 10-6 m3/cc. 1.4 Determine the Projected Adult and Newborn Thyroid Dose as follows. 1.4.1 Estimate the duration of the accident (" Inhalation Time"). NOTE: Use 2 hours if no other value is available. 1.4.2 Using the " Field Sample Thyroid Dose Nomogram" determine the appropriate Projected Doses as follows. a) Locate the "I-131 air concentration, uCi/cc" axis. b) From the appropriate concentration value, proceed vertically upward to the " Inhalation Time (Hours)" value. c) From this intersection proceed horizontally to the right through the Adult and Newborn Thyroid Dose Scales. Log the values of the Adult and/or Newborn Thyroid Doses on Form Y. 1.5 Report Projected Dose Results to the Radiological Evaluation Assistant on Form Y and post on the Status Board. I
i; Proc. No. 2.50.10 Rev No. 8 Page 20 of 50 s TABLE B.1 Diffusion Factors for Elevated Releases, (uX/Q)m-2 Distance Of ., Pasquil 1/2 Mile Max. Ground Level Max. Ground
- Stability Class Value Concentration, Mile Level Value A 6.3 x 10-6 0,5 __
B 2.3 x 10-5 0.5 -- C 4.0 x 10-5 0.5 -- 0 2.9 x 10-5 0.5 -- E 1.0 3.1x10-5 F
- 2.0 2.0x10-5 G 5.0 9.2x10-6
, *Use max. ground level value.
O L 1 O
Proc. No. 2.50.10 Rev. No. 8 . Page 21 of 50 - 1 Info Current At Time /Date FORM Y - PRIMARY VENT STACK IODINE ANALYSIS 1 Time Cartridge Removed AM PM i Sampling Time - Time Cartridge was in Sample Stream Minutes Sample Flow Rate CFM Number of Fans Running - 1 or 2 Results Iodine Analysis From Geli Analysis uCi/cc or
, From Sam II Analysis UCi/cc Calculated 1/2 mile 2 hour thyroid dose Adult, Child j Particulate Analysis From Geli. Analysis i
- 1) Prepared by Radiological Data Evaluator
- 2) Original to Radiological Evaluation Asst. for approval
- 3) Copies to: Recovery Manager NRC Rad Evaluation Asst.
Rad Data Evaluator
- 4) Original to Emergency Coordinator for approval
- 5) Emergency Coordinator's original to Hotline Operator
- 6) Transmitted to State by:
Hotline Operator A U 4 Date/ Time
- 7) File original 4
p -~,~.---+#+g g.y +m--,.,,-3--y-,., -- --- .--,, - - - , - -. , - , . , - . - - , ,
a Proc. No. 2.50.10 Rev. No. 8 PaGe 22 of 50 O " FORM X - 0FFSITE SURVEY REPORT Info Current at Time /Date Survey Point #
- j Distance from Plant Direction Other Descriptive Information 1
Sample Time I. Area gamma, beta-gamma and ground level beta-gamma survey - Dose Rates Waist High Gamma (Beta Window Closed) mr/hr
. Waist High Gamma (Beta Window Opened mr/hr Ground Level Beta-Gamma (Beta Window Opened) mr/hr II. Field Determination of Iodine Concentrations Particulate Filter cpm before purge cpm after purge Iodine Cartridge cpm Idoine Concentration uCi/cc Projected 2 hr thyroid dose III. Laboratory Determination of Iodine Concentration SAMII Counts '
Counting Time Decay Time (hours) (From time sample was taken) Sample Flow Rate CFM OR Iodine Concentration uCi/cc
- 1) Prepared by Radio Operator / Radiological Data Evaluator
- 2) Original to Radiological Evaluation Assistant for Approval.
- 3) Copies to: Radiological Data Evaluator / Radio Operator Recovery Manager NRC Sample Coordinator Radiological Data Evaluator
- 4) Original to Emergency Coordinator for approval.
- 5) Emergency Coordinator forwards original to the Hotline Operator.
- 6) Transmitted to State by:
Hotline Operator
- 7) File Original u
~ _ _ _. ._ _ _ _ . _ - - _
Proc. No. 2.50.10 Rev. No. 8 Page 23 of 50 ! APPENDIX D Evaluation of Air Particulate Data
.l ll 1.0 ANALYSIS OF 0FFSITE AIR SAMPLE RESULTS 1.1 Obtain the following survey team sample results, sample location, sample flow rate (CFM), sample collection time and sample count results. Log them on Data-Sheet G (page 27).
~1.2 Determine the airborne iodine concentration using Fig. 2 and the net iodine cartridge activity from the off-site survey team. Record this value on Data p Sheet G.
1.3 Obtain an estimate of the duration of the accident and log it on Data Sheet
- ,- G.
t NOTE: Use 2 hours if no other value is available. l: 'l.4 ~Using the " Field Sample Thyroid Dose Nomogram" and the above information, determine the Adult and Newborn Thyroid Dose as follows.
- 1.4.1 Locate the "I-131 Concentation (uC1/cc)" axis (lower right quadrant). _
1.4.2 From the appropriate I-131 concentration, proceed vertically to the , estimated " Inhalation Time (hrs)" line. 1.4.3 At this intersection, proceed horizontally to the right through the . Adult and Newborn Thyroid Dose Scales. Read the value of the Adult and Newborn Thyroid Dose and log the results on data Sheet G. L 1.5 If the projected Newborn Thyroid Dose is greater than 10-1 Rem, make a recommendation to the Emergency Coordinator that these samples should be immediately returned to the EOF for further analysis. 1' NOTE: All field samples will be eventually returned to the EOF for further more accurate analysis. 1 1.6 Once samples are returned to the EOF for analysis, make provision to count samples on the SAM-2 in accordance with Procedure 9.321 " Operation and
- - Calibration of the Eberline SAM-2/RD-22".
1.7 Analyze SAM-2 results by converting the count rate to an appropriate concentration by using the following equation.
- I-131 uCi/cc = SAM-2 Counts / Minute (corrected for background)
) (E)(2.22 x 106 dpm/uC1)(F)(T)(28,317 cc/ft>) i ~L Where:- s E = Sam-2 efficiency CPM /dpm F = flow rate of sampler "t3/ min T = sampling time min
1 1 . . Proc. No. 2.50.10
. Rev. No. 8
._ Page 24 of 50 )
i 1.8 Correct the I-131 results for decay if the time between sample collection and sample count is greater than 2 hours. , , 1.9 Report Projected Dose results to the Radiological Evaluation Assistant on Form Y and update the Status Board. 1 i, t i N f1 i! V 3 t 4 1 4 4 4
j Proc. No. 2.50.10 scw som T m oo cost (acu). EPA Mod el i Rev. No. 8 % % % i' Page 25 of 50 L - ' n' m - > vg % i
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- FIELD DATA Survey Team: Date tj tj i Sample Number i 1 1 2 3 'l 4 5 l l 1 I l Time reported (24 hr. clock)
!!. 1 l i l l l l .
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/m Rev. No. 8 Page 30 of 50 APPENDIX E ! Dose / Dose Rate Projections j At Distances Greater Than 1/2 Mile l ! 1.0 WHOLE BOOY DOSE PROJECTIONS j 1.1 Obtain the 1/2 mile whole body dose projections made from in-plant l parameters in Appendix 8.
J j NOTE: For distances up to about 1 mile, whole body gamma doses are
; practically independent of atmospheric stability.
1 j 1.2 Project these dose estimates to other distances of interest by using the
- i. Effective Gamma Dose Diffusion Factors,(uX/Q) listed in Tables C.1 and C.2
] for Elevated and Ground Level releases, respectively. Log these results on i Data Sheet C.
I J. [u(X/Q) ]X Dx = D1/2 x
'"'^~'"'
O
~
1.3 Dose ratas measured by the off-site teams may be projected to other distances by ratioing the UX/Q values at the desired distance to the distance of the measured value. 2.0 THYROID DOSE PROJECTIOhS 2.1 Obtain the 1/2 mile thyroid dose estimate made from in-plant parameters. 2.2 Project these dose estimates to other distances of interest by using the i Concentration Diffusion Factors, u X/Q, listed in Tables C.3 and C.4 for elevated and ground level releases, respectively. Log these results on i Data Sheet C. Dx = D1/2 x Lu(x/W) Juz 2.3 Concentrations o.- dose , measured hv the off-site teams inay be projected to other distances by ratioing the uX/Q value at the desired distance to the ux/Q value at the distance of the measured value. (uX/Q)x n Dx = Dm t (uX/Q)m D) Where m = measured value. 1 4
. - . .-. . . . . - . . . . . - - - . . _ -. . . - . : .. n . . _ .
O O Proc. No. 2.50.10 O.- Rev. No. 8 -. Page 31 of 50 TABLE C.1 MAINE YANKEE EFFECTIVE G/M4A DOSE DIFFUSION FACTORS uX 2 ELEVATED LEVEL RELEASE Q (All values should be multiplied by 10-6) Stability Category 00muind -- Distance Pasquill A Pasquill B Pasquill C Pasquill D Pasquill E Pasquill F Pasquill G 0.5 miles 7.9 16.0 19.0 19.0 18.0 17.0 17.0 . 1.0 ciles 1.2 4.1 8.0 9.9 9.7 8.9 8.6 2.0 miles 0.62 0.67 2.9 4.6 4.9 4.8 4.4 3.0 miles 0.42 0.42 1.5 2.8 3.2 3.3 3.0 4.0 miles 0.31 0.31 0.93 1.9 2.3 2.5 2.3 5.0 miles 0.25 0.25 0.64 1.4- 1.8 2.0 1.9 6.0 miles 0.21 0.21 0.47 1.1 1.4 1.6 1.6 7.0 miles 0.18 0.18 0.36 0.91 1.2 1.4 1.4 8.0 tiles 0.16 0.16 0.29 0.77 1.0 1.2 1.2 9.0 miles 0.14 0.14 0.24 0.66 0.89 1.1 1.1 10.0 miles 0.12 0.12 0.20 0.57 0.78 0.97 0.97
. . . ~ . . - - - - - . . ~ - - - _-. = w_...~ ~a-..- . ., - -w -. n .w. =
Proc. No. 2.50.10 Rev. No. 8 - -. Page 32 of 50 TABLE C.2 MAIPE YANKEE EFFECTIVE GA>NA 00SE OIFFUSION FACTORS uX 2 - GROLNO LEVEL RELEASE Q (All values should be multiplied by 10-6) Stability Category Downsind Distance Pasquill A Pasquill B Pasquill C Pasquill O Pasquill E Pasquill F Pasquill G 0.5 miles 8.3 19.0 26.0 34.0 37.0 41.0 47.0 , 1.0 ciles 1.3 4.3 9.5 14.0 16.0 18.0 20.0 2.0 miles 0.63 0.68 3.1 5.7 6.9 8.3 9.4 3.0 miles 0.42 0.42 1.6 3.3 4.2 5.2 6.0 4.0 miles 0.31 0.31 0.97 2.2 2.9 3.7 4.4 5.0 miles 0.25 0.25 0.66 1.6 2.2 2.9 3.4 6.0 miles 0.21 0.21 0.49 1.3 1.7 2.3 2.8 7.0 alles 0.18 0.18 0.37 1.0 1.4 2.0 2.4 8.0 ciles 0.16 0.16 O.30 0.85 1.2 1.7 2.0 9.0 ciles 0.14 0.14 0.24 0.72 1.0 1.5 1.8 10.0 elles 0.13 0.13 0.20 0.62 0.92 1.3 1.6
! O O . Proc. No. 2.50.10 O.- Rev. No. 8 l Page 33 of 50
.t 1 TABLE C.3 MAIE YANKEE PLtX CENTERLINE EFFLLENT C(NCENTRATION OIFFUSION FACTORS uX W2
, ELEVATED RELEASE Q ' (All values should be multiplied by 10-6) 4 l Stability Category ! Oownind j Distance Pasquill A Pasquill B Pasquill C Pasquill D Pasquill E Pasquill F Pasquill G 0.5 ciles 6.3 23.0 40.0 29.0 9.5 0.03 0.00 1.0 ciles 1.4 4.9 17.0 32.0 31.0 5.8 0.04 ,
~ ; 2.0 ciles 0.77 1.1 5.7 17.0 24.0 20.0 2.2 j 3.0 miles 0.55 0.73 2.9 10.0 17.0 20.0 5.9 t
4.0 miles 0.43 0.56 1.8 6.9 12.0 18.0 8.5 l 5.0 miles 0.36 0.46 1.2 5.1 9.8 15.0 9.2 1 I 6.0 uiles 0.31 0.40 0.92 4.0 8.0 13.0 9.5 7.0 ciles 0.26 0.35 0.72 3.3 6.8 12.0 9.5 8.0 ciles 0.23 0.32 0.58 2.8 5.9 11.0 9.4 , 1 9.0 ciles 0.21 0.29 0.49 2.4 5.1 9.6 9.1 10.0 ciles 0.19 0.26 0.42 2.1 4.5 8.8 8.7 i
_ ._- . .,.z_ . . - - _ .; _m _ ;__--. .-. , . O O Proc. No. 2.50.10 O. Rev. No. 8 -* Page 34 of 50
- TABLE C.4
. MAIE YANKEE i PLUW CENTERLIE EFFLENT CCNCENTRATION OIFFUSION FACTORS uX p2 .- ) CROLNO LEVEL RELEASE Q 1 (All values should be multiplied by 10-6) Stability Category i Down:ind q Oistance Pasquill A Pasquill B Pasquill C Pasquill O Pasquill E Pasquill F Pasquill G 0.5 ciles 6.4 26.0 60.0 160.0 260.0 450.0 920.0 . 1.0 ciles 1.4 4.9 19.0 60.0 11 0.0 210.0 350.0 i 2.0 ciles 0.77 1.1 5.9 21.0 41.0 85.0 170.0 i
- 3.0 ciles 0.55 0.73 3.0 12.0 24.0 52.0 110.0 1
j 4.0 miles 0.43 0.56 1.8 7.6 16.0 38.0 79.0 4 5.0 miles 0.36 0.46 1.2 - 5.5 12.0 29.0 61.0-l ,
! 6.0 tiles 0.31 0.40 0.92 4.3 9.6 23.0 50.0 ,
i l 7.0 ciles 0.26 0.35 0.72 3.5 7.9 20.0 42.0 i ,I 8.0 ciles 0.23 0.32 0.58 3.0 6.7 17.0 36.0
! 9.0 ciles 0.21 0.29 0.49 2.5 5.8 15.0 32.0 I 10.0 ciles 0.19 0.26 0.42 2.2 5.1 13.0 29.0 '
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Proc. No. 2.50.10 7- 3 . Rev. No. 8 ( ) Page 37 of 50 v APPENDIX F Plume Plotting Using the data recorded on Data Sheet E, determine the 15 minute wind vectors
' (direction and distance the plume segment traveled during the 15 minute period). Plot the vectors on the plastic covered map and label each 15 minute vector as Point 1 (P1), Point 2 (P2), etc. For each wind shift begin another vector plot at the proper time and label as above.
By connecting all of the points of equal time period the centerline of the actual plume travel pathway will be approximated. The width of the plume (c y) can be approximated from the width of the colored angles on the stability map for the proper distance or they can be calcuated from the formula: cy = 2K r (plane angle in degrees) 3600 where r = downwind distance (units) at point of interest. cy values can also be estimated from the graph in Fig. 1
-s Keep the Radiological Evaluation Assistant updated as to the progress of the (N- /) plume so that he may have the most. complete information available for directing the offsite teams and for making protective action recommendation.
NOTE: With several wind shifts over a period of time the actual plume path will approximate a mirror image of the wind vectors. s-
- . . . . < . . -. .-~ .--a )
j Proc. No._2.50.10 Rev. No. 8
~
t' - Page 38 of 50 t.
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Proc. No. 2.50.10 Rev. No. 8 Page 39 of 50 D ' APPENDIX C Population Exposure Estimation Total population exposure will be estimated as follows: The sector segment dose rates in the EPZ will be periodically determined using } the method described in procedure 2.50.10 Appendix E or by actual measurements 1 taken by off site surey teams and the sector segment dose for the time increment { of interest will be calculated. The sector segment dose will be multi i the sector segment population to get the segment population exposure. pliedThe by ^; segment exposure will be summed to determine the entire sector population exposure. Population data are given by sector segments for both year round and summer i seasons. The sector segments are at 1 mile radil out to 5 miles, then the i ' segments are at 5 mile radii out to 10 miles. In the southern sector the EPZ extends beyond 10 miles and appropriate data are given for the 10-20 mile segments. A segment beyond 20 miles for sector G is also provided. j Since plume dispersion will not usually fall totally within the sector boundaries, the conservative assumption may be made that if any portion of a segment is exposed the entire population of the segment will be exposed for j purposes of estimating population exposure. The summer population data, table will be employed from Memorial Day through h D Labor Day. The year round population data table will be employed the remainder of the year,. Use table E-1 and Data Sheet E (page 36) to perform and record population exposure estimates. For Xu/Q values at distances greater than 10 miles, an approximation can be made by using 1/r relationship. Hence the Xu/Q values at 20 miles should approximate 1/2 the Xu/Q value at 10 miles. This approximation is very nearly exact for A, 8, 0, E, F, and G stabilities and is conservative for C stability. Similarly for the segment beyond 20 miles be 1/3 the 10 mile Xu/Q value. , (20 to 30 miles) the 30 mile Xu/Q value should SECTOR SEGMENT NOTATION SECTOR (A R)* SECMENT # DISTANCES (in miles) 1 0-1 2 1-2 3 2-3 4 3-4 5 4-5 10 5-10 20 10-20
*with letter I and 0 eliminated so os not to confuse them with numbers 1 and O. \
The segment # identifies the outer radius of the segment. For example, sector segment # C5 means that in sector C, our concern lies with the segment which as an inner radius of 4 miles and an outer radius of 5 miles.
- j. - -
I' . . h Proc. No. 2.50.10 - Rev. No. 8 p Page 40 of 50 ( , TABLE G-1
, YEAR ROUNO POPULATION DISTRIBUTION BASED ON 1980 U.S. CENSUS l
I 1 R A B 5,000 9,267 1170 587 ' Q AA2 \ \ 50 C 3,276 49 2952 3 o 260 931 57 o 131 517 gg7
- ' ~
u 1 s's7i 753 9 108 420 19c0 43 86 gggo l 10 4 52 \6 17 5, gg 43 43 10 4 2 48 4g ', 4g , 18 0 o 13 1 i i 12478 5332 2 61 10 4 76 49 ik37'20 129 2+ S19 658 '{ N 23 og g 15 - Yi 52 (\ 0 go 12 ) 43 22gg 24 71
; 37 39 37 37
? 5877 13 25 739 4,23 3 I6 30 4t9 6 40 's 16 25 F
'\ '
4 47 64 57 eso } 3,258 267 h 400 379 1 4 x { 429 2994 109
) \ I,057 160 @
\s 346 o -
o
; K H '
J. Total Total Total Total Sector Population Sector Population Sector Population Sector Population A 5936 R 1698 J E 1207 N R 18300 l B 4226 F 1308 K 1577 P R 6861 C 4950 G 1577 L 3753 Q R 4294 0 3285 H 3330 M 20317 R R 9835
1
' Proc. No. 2.50.10 r~N '
Rev. No. 8 {). Page 41 of 50 DATA SHEET E l POPULATION EXPOSURE ESTIMATION DATA SHEETS t Date Stability Class { Time Wind Direction - blowing from Wind Speed (upper - for stack releases) Wind Speed (lower - for containment and steam line releases) Directions:
- 1. Use the area map with the plume overlay to determine the sectors exposed to
, the plume.
- 2. Use the entire population of the segment if any portion of the segment is under the plume.
(q V
)
- 3. Use the center line dose rate for all estimates.
- 4. Use the plume arrival time at the inr.er radius (from the computer printout or from a wind speed-distance calculation) for the exposure start time.
. 5. Convert the time to 24 hour tjme for ease of manipulation.
- 6. Use the time of parameter change (i.e. wind direction change, dose rate change, or time of calculation if no changes have occurred) for the end time, i
NOTE: Care should be employed on those releases which have a duration in hours less than the desired time after the release has started so as not to overstate exposure time. Consideration must be given to the trailing edge of the plume after the release is stopped for exposure time.
- 7. For each sector segment number average dose rate by adding the inner radius dose rate to the outer radius dose rate and then dividing this sum by two.
This would approximate the dose rate at the center.of the sector segment. NOTE: For segment No.1, which has a range of 0-1 miles, use the 1/2 mile dose rate as the inner radius dose rate when averaging with the outer radius dose rate at 1 mile.
- 8. Consider wind direction and dose rate remain constant during the calculation period.
(m) v
- 9. Record the time interval as hours and fraction of an hour.
Proc. No. 2.50.10 Rev. No. 8
'0 Page 42 of 50
- 10. To calculate total time of plume exposure for column 5 of the calculation forms use the following steps:
I I I I I I I Seament Number l 1 l 2 l 3 1 4 l 5 l 6 1 7 f Segment Range i I I I l l l i,! beainnina of sea. - end of sea. I 1/2-1 l 1-2 1 2-3 1 3-4 l 4-5 l 5-10 l 10-20 0 I I I I I I I
! Step A Start of release (24 hour time) l l l l l l l u l l l l 1 l l
![ Step B Time to reach beginning of segment l l l l l l l !; distance to beainnina of sea.(miles)l l l l j Wind speed (miles / hour) l l l l l l l l l l l Step C Use one of the following for the stop time. l 1. End of release l l l l l l l use time plant release ends i I i l l l l plus time trailing edge or I l l l l l l
- plume posses beginning of I l l l l l l l
seament. I I l l l l l l l l l l l l l 2. Time of a dose rate chance l l l l l l l l 1 l l l l l
- 3. Time of a wind direction change l l I I l 1 l L l l I I I i l l 4. Time of a desired calculation l l l l l l l period l l l l l l l 1 1 I I I I I Step D Total time exposed to plume l l l l l l l C -(A + B) = Total time l 1 l l l l l l
O L
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( t 5 1 2 2 1 1 P O P R R R R ll l l I l Ii I i I l I l I I II ll l l l l I l I l l 1 l I I 1 I i I I I I LS
)
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) AR h /
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)
)
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) Rh 2 / d M
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) RA 9 D
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) OR 8 I - -
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) A 1 3 2 2 2 1 5 1 1 1 7 3 3 1 1 3 3 0 8 0 2 2 6 5 9 6 6 L 1 8 6 7 4 1 8 4 9 1
( U 2 P O Il P I l l I R I I I i I l I l i i l l l I I I iiI I l l I I I lI i I I I lII LS
) AR 5 TU
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) AR h /
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)
)
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) Rh E 2 / d
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)
1 Rh
/ m E D
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IllllIllll ll Il lllllllllIIIlllI IIIIIlII IIll ME ET
) RA 9 D
( N AO MT Il I l I I I I I I l I I i i I I I l I l I I l II lI l I I I I I I l I I l I SM UE
) OR 8 I - - -
( VN EA RM 0 P 1 ll l l I I I I I I I I I I I I I I l l I I l l II II lI I I I I I l II I I II 0 5 0 ) 5 6 2 8 f M ( E x N o
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) A 1 1 2 6 2 4 2 1 4 6 7 5 3 4 5 2 5 4 3 7 8 6 L 1 2 4 3 3 0 4 2 8 2
( U 1 3 5 4 P 1 O Il P I l 1 I l i I I l I I l I l i i l l l l I l I I lIl l Il l l l I I I I I II
) AR LS 5 TU
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)
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( ER n G S e E O S D Iii ll I 1 l1 II I 1 I l I lI T E g N n Ar l E T P
) Rh G 1 / m E
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) ll
,I ll'l( ll llIllll, lIIll1llllll Il lI!I lIII llllllllIIIlll Illl ME ET
) RA 9 D
( N AO MT ll I l l l I I l I l l I l I i i I I l I I I I l I l l l l I I I I I l II I I l I SM
) OR UE 8 I - - -
( VN EA 0 RM 1 P ll l l l l I I l I I I Il I i i I I l I I I I l I l l l I i I I I I l I I I I i I 0 5 0 ) 5 6 2 8 M ( f E x
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)
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) AR h /
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)
)
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. I I I I 1 ll E
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)
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) Rh G 1 / m E
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' l l
l lI lIl l 1 I l l 1 ll ll lll 1 lI ll R O T C N P Q R E . . S llIlllllllll1IIllllllllIlllllllllllillIlll 1lllll
,l
. Proc. No. 2.50.10 Rev. No. 8 L Page 47 or 50 APPEPOIX H T
l Evaluations of Environmental Station's Samoles,
, 5011 Samples, and Other Environmental Media
'I !ji 1.0 ENVIR0tNENTAL STATION SAMPLES 7 1.1 Make arrangements to collect and remove the filter media and the TLD's at the environmental sample stations. in the downwind direction of the plume (a
- j 908 sector), and in one mile radius circle around the plant.
7 Bailey Farm environmental personnel should be notified by NOTE: Radiological Evaluation Assistant to. report to the E.O.F..for instructions. Dosimetry should be issued and instructions given to environmental personnel before they go to collect samples. 4 j 1.2 At the station record the time of removal, the flow indication on the flow totalizer, the timer indication and the integrity of the system. Log this. l ,, information on Data Sheet D. Label TLD's with time set out and time removed.
- 1.3 Place all filters and TLD's in labeled poly bags for analysis by the Yankee
- Mobil Van and/or other facilities.
1e O 1.4 Calculate the total flow through' the filters since the beginning of the V release as follows and hold this with the filter. Record this on Data Sheet
- - D.
1 j ;, 1.4.1 Divide the total flow indication by the. timer indication to obtain the system flow rate. l.4.2 Multiply this value by the time the system was exposed to the plume (estimate) and convert this value to cm3
,, 1.5 Environmental personnel should return their samples to the Sample i~
Coordinator at the E.0.F. i: 2.0 After the urgency of the accident has subsided, make provisions to collect . snow, soll, vegetation, water and milk samples downwind of the plume under the direction of the Emergency Coordinator. 2.1 Solid samples should be placed in clean poly bags in a manner as to avoid
, cross contamination of samples. .
2.2 Liquid samples should be collected in 1-5 gallon clean plastic bottles. 2.3 Snow samples should be collected as follows: I 2.3.1 Select the area to be sampled from the general location requested that
, has not been subjected to non-meteorological disturbances (plowing, snowmobiles, pedestrians,etc.)
{
i . . Proc. No. 2.50.10 Rev. No. 8 x Page 48 of 50 NOTE: Snow falling at time of interest or snow on ground at time of deposition may have drifted since the time of interest. Melting and freezing and/or rain may mean the snow deposition is fixed in an ice layer and not affected by winds. These possibilities must be considered and existing weather conditions used to determine area to be sampled.
- j 2.3.2 Measure the selected area to be sampled in units of square feet.
'l l 2.3.3 Take up snow to depth sufficient to collect snow of interest. NOTE: If a crust layer may have formed on an earlier snowfall, collect snow from surface to this crust. If snow of interest may be below a crust layer formed later, sweep loose snow away to this crust layer and then sample the crust layer and loose snow to next crust layer.
, NOTE: Sample volume to give meaningful data should exceed 3 liters of melted snow. Loose snow volume is 4 times its liquid volume.
Icy snow is approximately twice its liquid volume. The snow can .., be packed in the collection bag. '! 2.3.4 Estimate depth of snow collected. 2.3.5 Securely close sample bag. It is recommended that all samples be doubly bagged to prevent leakage as snow melts. 2.4 All samples should be labeled as follows: time of collection, location of sample, name of individual. 3.0 Once analysis of samples is complete, results should be sent to the NSD Radiological Engineering Group for further analysis and dose analysis. O
Proc. No. 2.50.10 (m. Rev. No. 8 y) Page 49 of 50 DATA REDUCTION SHEET D ! Evaluations of Environmental Stations Samples,
- Soil Samples and Other Environmental Media 1.0 Environmental Stations Samples i l I i i Flow Through System Location of l Time of Flow l Sample During Plume Passage Environmental l Sample Totalizer . Timer l Flow Station l Removal l Reading l Indication l Rate l (cm3) i I I l l l l l l l 1 1 I I I I I I I I I I I I I l l l l l l l l 1 1 l l l l l
' 1 1 1 1 1 I I I I i i l i I i i l I l l I I I I I l l l l l l 1 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I l l I I I I I I I I l l l l l l 1 I i l I i l l I I I I I I I I I I I I I I I i l l l l l 1 1 1 I I I I I I I I I I I i ^
l l I I i _ l i I I I I I I I I I I I I I I l l l l
Proc. No. 2.50.10 (., Rev. No. 8 ( Page 50 of 50 (Sheet D Can't) 2.0 Other Environmental Samples I 1 Approximate i I I Sample l Type of l Volume of l Time Sample l l Destination Location i Sample l Sample l Taken l Initials 1 of Sample I I i i l l I I l l I I I I I I I l I l i I I I I I I I I I I I I I I l l l i I I I I l l I I I i i i i I i l i I I I I I I _ l l l l l i I I I_ I l l I I I I I I I i i l I l 1 I I I I i l i I I I I I I I I l l l l 1 1 I I I I I I I I I I I I I l l l l l l 1 1 I I I l l l l 1 1 I I I l l l l l I I I I I I i l i i i i i l i I I I I I i i i l I l l l I I I i i l I l l l 1 _ i i i i l I i l i 1 1 I I i l i I I I I I l l l 1
* ~ )
Proc. No. 2.50.14 Rev. No. 5 O Page 2 of 19 O ,_ Guideline action levels for continuous habitability of all emergency centers is presented in Table II. This procedure consists of four parts as follows: 5.0 Search and Rescue of Personnel t 6.0 Emergency On-Site Assistance ] 7.0 Personnel Dosimetry Record-keeping 8.0 Decontamination of Personnel and Equipment The following tables and forms are attached: Personnel Exposure Log pg. 10 Table I Emergency Dose Limits pg. 11 Table II Emergency Center Protective Action Criteria pg. 12 Table III Personnel and Equipment Release Criteria pg. 13 Table IV Summary of Design-Basis Doses for Required Functions pg. 14 Preferred Routes of Travel to Reach Emergency Operating Stations pg. 17
2.0 OBJECTIVE
f To specify emergency worker dose guidelines, including emergency center habitability, preferred routes of travel to minimize personnel exposure, the fs d
)
methods to perform emergency personnel dosimetry, record-keeping, and decontamination of personnel and equipment.
3.0 REFERENCES
i Emergency Procedure 2.50.20 "Prophylatic Administration of Potassium Iodide" Emergency Procedure 2.50.8 " Medical Emergency Plan" Emergency Procedure 2.50.7 " Emergency On-Site Radiation Monitoring Proc." Emergency Procedure 2.50.22 " Actuation of the Alternate Emergency Operations R Facility" H.P. Procedure 9.1.6 " Establishments and Posting Controlled Areas" H.P. Procedure 9.1.7 " Area and Equipment Decontamination" H.P. Procedure 9.1.9 " Personnel Decontamination" tECP 39
4.0 PRECAUTIONS
- 1. During any emergency involving radiological hazards, exposure to personnel should be minimized consistent with the nature of the emergency response required.
- 2. Utilize radiological protective measures and equipment whenever practical.
- 3. Assure that the proper high range instrumentation and dosimetry is used.
NOTE: High range dosimetry is located at the H.P. Check Point and in the h b Emergency Kits for the EOF, TSC, OSC. High range survey equipment is kept at the H.P. Check Point and one meter is in eaca of the Emergency Kits. ,
l Proc. tb. 2.*;0.17 , Rev,th. 10 e * ,- Paje 5 of 11 e faCLEAR SAFETY EtolffER - ErfRCENCY CALL LIST Ireli.sks Nuclear Support Division
, I 1 I I
tRfC Maine Yankee Ntolear SaqTort Div. Yankee Nuclear Saggiort Div. totify tNC for All Energency Classifications 1. Notify for All Energency Classifications. 1. Notify for Alert, Site Area and
. , using tre Red Ptone in the Control Room or Tectnical Support Center. General Energency OttY. .
2 Start at tre top of the list and work duwn antil
' a contact is made, advise of tre ene ency, and 2. Call NSD Security and report
, Orce contact is made tre prune should be kept if it's regJired, instruct him to not fy the rest classification of emergency.
open and manred. The NSE should assign an of the personnel on the list. , l available loowledgeable neater of the plant Telephnne: *
, staf f to man the phone. 3. When a contact is made, make sure that the individt.al reached has a copy of the phone list NOTE: If you have difficulty with
! tote: If the Red Ptnne is inoperable, use any so that notification can te continued if necessary. this numter, you can reach
; of the followiry numters to reach tre tre NSD Security with an NRC Operations Center. PM PAT R NO. PWNE alternate ntruler:
I i 1. '
- 1. Frlzzle, Charles D.
- 2. 2. Wood, Edwin C.
- 3. 3. liehert, James
- 3. For backshifts anit holidays call *
, 4. 4. Brinkle,1, James E. YNSD 24 hour parler siswerinr}
i 5. Lawton, Rotert R. I service, ZIP-C/LL, in Onstrn. .
\ 6. Arnold, .'btn H.
, 7. Evans, Stephen D. Teleptune f I An answering service operator at ZIP-CALL will answer " ZIP-CALL"
*# p and request parler nisnter. Give the ZIP-CALL operator paler nirntwar .
'} -
- 7. .
R@ eat fifteen minutes later. l 'h l l l t
,~, . < ~ -
~ r'- " " - -
, (. , . . - g,
,' jy ~. [, r i_ ( ' , -[ '
,' [fT{rs. . . . "
.g 7
~ ' .
g.jy . t _. , ! ; ~ .' . 4 r . ( -_- -
_ __ an- -
- - - - - - - - - ~ --
3 A Proc. No. 2.*0.17 , Rev. No. 10 Page 9 of 11 e
- MISCELLAtEOUS - EWRCENCY CALL LIST e
- 1. Anerican Nuclear Insurers -
- 5. Off-Site Local Assistance - When Needm1 TOTE: AN! maintains a % t enverage emergericy notification rumher. Dr. Anttony Keating '
, The number i ring normal office injrs (Notify for all hospital cases)
(8:00 a.m. - 4:0) p.m.) this runber will be answered by a receptionist wtio will transfer an incomiry energency call to an Bath Hospital . apprnpriate individual in tte office. Outside of mrmal office Wiscassest Fire Dept, hours this phone line is covered by an answering service. Tie Wiscasset Police Dept. answering service will intercept the call and obtain tre name, Wiscasset Ambulance Service affiliation, and phone runter of the caller. They will than notify a designated ANI staff member who will in tum call back 6. Enerqency Plan Roster by Duties the facility to obtain appropriate information regarding tie ruclear accident. Emerqmcy Coordinator Pagef
- 2. ItPO James Brinkler Thomas Doulette Emergency Call Nun Use this nmber if a management Cary Cochrane decision is made to reque assistance. Patrick Dostle Stephen Evans l 3. Dailey thise - Envirorvia51tal Personnel Geonje Pillsbury
! Donald Stevenson ! Regular Bustress Hours - Ext Leo Croteau ! Phone No. David Sturniolo Of f Duty Hours Radiolrnical Data Evaluators Parjer William Nason Environmental Field Supervisor Cary Cochrane
! Roger O' Clair Environnental T&h. James Iksmer j willian Camtall Environmental Spwlalist Michael Istum i 0111y Nanson Air Quality Specialist Gregory Kapinos George Pillstury
- 4. Newcastle District Office David Sturniolo During working hours: First Ald Paqer i
' Durinq Regular Business Ikurs you will get tie Newcastle Office directly. Louise N range . Tell ttusn who you are and where you are from and that they should prepare Gregory Kapinos 3 for the arrival of Maine Yankee Personnel and Yankee Nbile Emergency Vans, wer Poordinators All ot ter tines: Call ite CH2 Dispatcher Brenda Castongtay Read the followirq nessaje: "This is frnm the Nine Yankee Marylou Larrabee , Plant, please contact tre Duty Supervisor for tie Newcastle District Nancy Leavitt l Office and inform him that he should open the office and prepare for Lee Ann Harpell the arrival nf Maine Yankee Personnel and Yankee Nblie Emergency Vans". Patti Whitten Check to assure ? I
r-
. O
-) Form fo. 2.50.19-2 Rev. :o. 5 Revised Date: 05-29-85 O ._ Page 13 of 13 RELEASE DATA INFO CURRENT AT TIME /DATE i
i TIME SINCE SHJTDOWN WS R CONTAIPMENT HI-RANGE MONITOR (RI 6113A, B) R/m f R PRIMARY VENT STACK HIGH RANGE NOBLE GAS MONITOR (RR 3903) MR/HR l MAIN STEAM LINE MONITORS SGl MR/m SG2 MR/HR SG3 MR/HR MAXIMUM STEAM GENERATOR PRESSURE AT TIME OF SAFETY VALVE LIFT PSIG CONTAIfMENT PRESSURE PSIG Nt.NBER OF FANS RUNNING - 1 or 2 DURATION OF RELEASE (USE 2 HOUR DEFAULT TIME IF UtKNOWN) HOURS CHECK ONE: ESTIMATED OEFAULT
- 1) PREPARED BY TSC COORDINATOR
- 2) COPIES TO: RADIOLOGICAL EVALUATION ASSISTANT RECOVERY MANAGER NRC l TSC COORDINATOR RADIOLOGICAL DATA EVALUATOR
- 3) ORIGINAL TO EMERGENCY COORDINATOR FOR APPROVAL.
- 4) APPROVED ORIGINAL TO HOTLINE OPERATOR
- 5) TRANSMITTED TO STATE BY:
H0TLINE OPERATOR DATE/ TIME
- 6) FILE ORIGINAL f
I n U i I l
r
. . . - ... .:.. . . -.. . . . - - - . = . au . --
,W
,.. .. .. .. . .. . .- .... - . -- -.-~ ...-...- - - - - a.a' a . .- . . - . . - - . ?. -
-126$r l{ . ...--
l 'M - - Form No. 0-05-1-1
.i.
c' l0 R. 0 C . A) d. '7 Rev. No. 2 e l . 56. / '/ Revised 12/18/84 Page 7 of 8 l 1
.l .
I
] MAINE YANXEE CONTROLLED 00CUF_NT REVISION TRANSMITTAL FORM j .
00CUMENT: 2.50 SERIES - IMPLEMENTING PROCEDURES TO THE EMERGENCY PLAN COPY NUMEER: ,h a w.~ , 4 8n 71,/ /M u ]". [1 M,.) ISSUE CATE: May 30, 1985
- 1. Remove existing 2.50 series Implementing Procedures to the Emergency Plan index, and replace with attached.2.50 series index dated 5-30-85, 2 pages.
't l 2. Remove existing page 1 of Proc. No. 2.50.4, . General Emergency,'Rev. No.10, 1
and replace with attached corrected page 1. (Typographical error)
'l
- 3. Remove existing Proc. No. 2.50.10, Evaluation of Radiological Data, Rev. No. 7, j_ and replace with attached Proc. No. 2.50.10, (Same Title), Rev. No. 8, pages 1-50.
1 . i 4. Remove existing page 2 of Proc. No. 2.50.14, Emergency Radiation Exposure p s Control, Rev. No. 5, and replace with attached corrected page 2. (Typographical error) '
)
- 5. Remove existing pages 5 and 9 of Proc. No. 2.50.17, Emergency Notification, Rev. No.10, and replace with attached corrected pages 5 and 9. (Typographical
; errors) i
- 5. Remove existing page 13 of Proc. No. 2.50.19, Technical Support Center, Rev. No. 5, and replace with attached corrected page 13. (Typographical error) 1P f The above listed revision (s)/ change (s) has/have been placed in ycur assigned ccpy.
a
/ .E DATE l' THE UNCERSIGNED ACXNOWLEDCES COMPLETION CF THE FOLLCWING:
Ig R 1. The receipt, review and insertion of the revised material into the s assigned manual / file.
- 2. Assurance that those who use the dccument are aware of the change.
R 3. The destructicn of all superseded pages. SIGNATURE CF HCLCER: / CATE R.eTURN THIS FCRM TO: Ad:inistraticn Office within 10 working days of issue. Maine Yankee Atomic Power Co. w
s' - 2.50 SERIES IMPLEMENTING PR0tED0RES TO THE EMERGENCY PLAN 5-30-85 O N MBER TIRE '
'l CURRENT REVISION h/ l# DATE I'# l DATE ll # DATE [j # lDATE 2.50.0 Declaration & Categorization I 6 8/84 l _
l l of Emergency Condition l } l l 2.50.1 Notification of Unusual 7 6/84 $8 4/85 l ] Event l l l 2.50.2 Alert 7 7/84 l 8 4/85 l' ll l ' l l
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j 2.50.3 Site Area Emergency
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I 9 8/84 [ 10 4/85 ll I [ i 2.50.4 General Emergency l l l l l 2.50.5 Emergency Plan Training l 3 3/85 l' l { l l1 l Il I Emergency Equipment i 21 3/85 .I l t 2.50.6 Readiness Check ' l , l I Emergency On-Site Radiation i 4 3/85 lL l l 2.50.7 Monitoring Procedure l l l l O 2 4/85 l ' ll l 2.50.8 Medical Emergency Plan j g j D Security Force Radiation l5 3/85 l l l 2.50.9 Emergency Plan l l l l l j. Evaluation of Radiological l7 4/85 11 8 5/85 ll ll l 2.50.10 Data g y l l 2.50.11 Plant Entry & Recovery 6 8/84 l l. l-Plan j , l l Emergency Off-Site Radiation !6 1/85 ll l l' 2.50.12 Monitoring Procedure I [ l- l l . 2.50.14 Emergency Radiation Exposure 5 3/85 l l l. l Control l l; I j; l Release of Public Information 2 3/85 h '
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2.50.15 During Emergencies jg g ggg 2*50*16 Protective Action -l 4 '3/85 I j Recommendations l l 2.50.17 Emergency Notification 9 5/84 I;10 4/6 g gp i W W MWW O-
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'5 2.50 SERIES IMPLEMENTIllG PROCEDURES TO THE EMERGEllCY PLAf4 5-30-85
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CURRENT REVISION ( ) flUMBER TITLE l # ilDATE l'# H DATE ll # lDATE [ # l DATE 2.50.18 Operations Support Center 4 11/84 l I I
! l l l: ll 2.50.19 Technical Support Center Propnylactic Aaministration of t 3 3/85l l' i l 2.50.20 Potassium Iodide for Thyroid Blockino l I l l l 2.50.21 Offsite Dosimetry Assistance 11 2/84I l; I l l l 1 l l 2.50.22 Activation of the Alternate 1 0 3/85l 1 l'4/85 ll l Emergency Operations Facility l l- ll l l Emergency Preparedness } 0 4/84 l ll h 2.50.23 Exercises & Drills l -j ll l P I ll l l- 1 i I ~
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'g UNITED STATES l 8' > g NUCLEAR REGULATORY COMMISSION
(, g WASHINGTON, D. C. 20555 p July 9,1985
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50-309 Maine Yankee MEMORANDUM FOR: Chief, Document Management Branch, TIDC i FROM: Director, Division of Rules and Records, ADM
SUBJECT:
REVIEW 0F UTILITY EMERGENCY PLAN DOCUMENTATION The Division of Rules and Records has reviewed the attached document and has determined that it may now be m3de publici . available.
. M. Felton, Director ivision of Rules and Record ' ,/ ,
Office of Administration
Attachment:
As stated i 1 i 6}}