ML20083J703
| ML20083J703 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 12/12/1983 |
| From: | Brons J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | |
| Shared Package | |
| ML093450579 | List: |
| References | |
| PROC-831212-01, NUDOCS 8401050374 | |
| Download: ML20083J703 (37) | |
Text
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. EMERGENCY P2.AN 1FROCEDURES CONTETES Procedure # , Procedure Title Dose Assessment ,
IP-1001 Discussion of the DMR l IP-1002 Determination of the Magnitude of Release IP-1003 Obtaining Meteorological Data IP-1004 Midas Computer System-Dose Assessment Models IP-1005 Planned Disch. of Cont. Atmos. During Accident Conditions Environmental Monitoring IP-1010 In-Plant / Site Perimeter Surveys
. IP-1011 Offsite Monitoring
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IP.-1017 Rec. Protective Actions for Offsite Population IP-1018 Post Accident Environmental Sampling and Counting Personnel Injury l
IP-1021' Radiological Medical Emergency IP-1022 Transport of Contam. Injured Personnel Between Unit 3 & 1 IP-1023 Use and Set-up of Unit 3 Personnel Decon Suite Damage Assessment IP-1025 Repair and Corrective Action Teams IP-1027 Emergency Personnel Exposure IP-1028 Core Damage Assessment Notification and Consnunication IP-1030 Control Room Emergency Notif., Communication & Staffing IP-1031 Procedure for EOF Emergency Notification & Communications IP-1038 Use of the Emergency Conusunications Systems Emergenev Operation Facilities l
IP-1040 Habitability of the Emergency Facilities IP-1041 Personnel Monitoring of EOF, TSC and OSC Personnel IP-1045 Technical Support Center '
IP-1047 Operations Support Center Accountabiliev and Evacuation IP-1050 Accountability Evacuation of Site IP-1053 IP-1054 Search and Rescue Teams Non-Radiological Emergencies
< % IP-1055 Fire Emergency I
8401050374 831228 !
EMERGENCY PLAN PROCEDURES CONTENTS Procedure # Procedure Title IP-1056 Directing Fire Fighting Personnel in Controlled Areas IP-1057 Tornado (Hurricane) Emergency IP-1058 Earthquake Emergency IP-1059 Air Raid Alert HP Release Survevs and Decontamination IP-1060 Personnel Radiological Check and Decontamination IP-1063 Vehicle / Equipment Radiological Check and Decontamination Emergency Equ'ipment and Maintenance IP-1070 Periodic Check of Emergency Preparedness Equipment IP-1076 Beepers Exercises, Drills and Training IP-1080 Conduct of Emergency Exercises and Drills IP-1.085 Emergency Response Training C
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4 EMERGENCY PLAN PROCEDURES INDEX REV. 21 (PAGE 1 )
Procedure # Procedure Title Rev. # Date Dose Assessment IP-1001 Discussion of the DMR 4 10/83 IP-1002 Determination of the Magnitude of Release 5 12/83 l IP-1003 Obtaining Meteorological Data 4 11/82 IP-1004 Midas Computer System-Dose Assessment Models 3 11/82 IP-1005- Planned Disch. of Cont. Atmos. During Accident Conditions 2 1/82 Environmental Monitoring IP-1010 In-Plant / Site Perimeter Surveys 4 8/83
_ IP-1011 Offsite Monitoring 5 12/83l IP-1017 Rec. Protective Actions for Offsite Population 2 1/82 IP-1018 Post Accident Environmental Sampling and Counting 2 11/82
< Personnel Injury IP-1021 Radiological Medical Emergency 8 10/83 IP-1022 Transport of Contam. Injured Personnel Between Unit 3 & 1 1 11/82 IP-1023 Use and Set-up of Unit 3 Personnel Decon Suite 0 11/82
. Damage Assessment
{
IP-1025 Repair and Corrective Action Teams ~
3 8/83 IP-1027 Emergency Personnel Exposure 2 8/83 IP-1028 Core Damage Assessment 0 11/83i Notification and Communication IP-1030 Control Room Emergency Notif., Communication & Staffing 9 10/83 IP-1031 Procedure for EOF Emergency Notification & Communications 1 10/83 IP-1038 Use of the Emergency Communications Systems 5 8/83 Emergency Operation Facilities IP-1040 Habitability of the Emergency Facilities 5 12/82 IP-1041 Personnel Monitoring of EOF, TSC and OSC Personnel 4 7/82 -
IP-1045 Technical Support Center 5 8/83 i IP-1047 Operations Support Center 6 10/83 Accountability and Evacuation IP-1050 Accountability 6 8/83 ;'
IP-1053 Evacuation of Site 2 10/83 IP-1054 Search and Rescue Teams 2 8/83 Non-Radiological Emergencies
- - IP-1055 Fire Emergency 2 2/83 i
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l EMERGENCY PLAN PROCEDURES INDEX REV. 21 (PAGE 2 )
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Procedure f Procedure Title Rev. # Date IP-1056 Directing Fire Fighting Personnel in Controlled Areas 1 1/82 IP-1057 Tornado (Hurricane) Emergency 1 10/83 IP-1058 Earthquake Emergency 5 5/83 IP-1059 Air Raid Alert 1 10/83 HP Release Surveys and Decontamination IP-1060 Personnel Radiological Check and Decontamination 2 1/82 IP-1063 Vehicle / Equipment Radiological Check and Decontamination 2 1/82
. Emergency Equipment and Maintenance
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IP-1070 Periodic Check of Emergency Preparedness Equipment 8 7/83 IP-1076 Beepers 4 10/83 Exercises, Drills and Training IP-1080 Conduct of Emergency Exercises and Drills - 5 5/83 IP-1085 Emergency Response Training 3 11/82 e- .
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<$ Authority EMERGENCY PLAN PROCEDURES PROCEDURE NO IP- 1002 REV. 5 TITLE" DETERMINATION OF THE MAGNITUDE OF RELEASE n
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7 ErrECTIVE DATE- s: /ra/33 !
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IP-1002 i I
DETERMINATION OF THE MAGNITUDE OF RELEASE
1.0 INTENT
.To describe various methods of estimating the whole body dose due to radioactive noble ge: end the thyroid dcce due te radicactive Iodine for the offsite population.
2.0 DISCUSSION
There ars two primary methods of estimating offsite dose. One method is to I use plant instrumentation to determine a release rate, and using dispersion I factors based on meteorology, project offsite dose. '
The second method involves taking radiation readings and samples offsite, then using ratios of dispersion factors to estimate the dose at various
.. offsite locations. The offsite readings would be taken by mobile survey .
teams and by installed offsite instrumentation (Reuter Stokes monitors).
Both of these methods should be used to verify accuracy.
When thyroid doses are calculated in this procedure (including flowchart),
the child thyroid dose is conservatively used, since the child thyroid .
dose is approximately two times the adult thyroid dose for iodine inhalation. This is appropriate for offsite dose projections, but onsite.
(. dose projections should use the adult thyroid dose (Adult thyroid dose =
child thyroid dose divided by 2) .
3.0 PROCEDURE .
3.1 Follow the flow charts, EP-Flowchart #'s la & lb keeping in mind these basic steps:
- 1. determine the release rate
- 2. determine the site boundary concentration
- 3. determine the site boundary dose
- 4. determine the point of interest dose 3.2 Use graphs and tables on pages 6 - 8 in conjunction with the !:
flow charts, (EP-Flowchart #'s la & lb) as well as IP-1001, (section'7
& Figure 1) on the choice and placement of the meteorological overlays to determine the site boundary dose projections and the point of interest dose projections.
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3.3 Along with 'these calculations, j.
I:
a) The on site monitoring team is to be sent to the site boundary (IP-1010) for actual radiological readings. l.
b) The offsite team is to be called in and sent to areas the plume
- is expected to pass over. (The overlays are en be used as guidance for plume path and IP-10ll as guidance fc.- che offsite team).
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IP-LOO 2/5 c) The chem. tech, shall be directed to take a sample of the activity in the Plant Vent if the radiological conditions prove safe to do so.
The chemist should be instructed to remove and count the normal weekly iodine plant charcoal cartridge. (This will determine how much iodine has been released)
NOTE: Total Iodines ,
I
. Sample the Noble Gases currently in the Plant Vent by taking a gaseous Marinelli sample.
(Until the chem sample is.obtained and analyzed, a total Iodine to Noble gas ratio of 10 " is assumed. This may prove to be overly conservative, or an underestimate, all apendent on plant conditions. Therefore, it 'is necessary +3 have
__ a chem sample as soon as possible and use the new .alue (Total I/NG) in the dose projection calculations when making any decisions on protective actions.)
If initial dgse projections are done using the estimated (Total I/NG) ratio of 10- , one should state to offsite authorities it is only a rough estimate, and we will be providing more accurate information by direct sampling shortly. This should be considered when taking or recommending protective actions based on projected thyroid exposure.
3.4 When an actual chemistry sample is available, the dose projections are corrected by the following:
(Total I/NG) chem sample
-0 X estimated Iodine = corrected Iodine 10 dose dose l 3.5 An estimate of the duration of the release should be obtained from the Emergency Director. If it is unknown, use 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> as a first estimate. <
1 3.6 Implementation Procedure IP-1017 offers assistance on the recommendations which can be made to offsite authorities ,
regarding offsite protective actions for the public.
3.7 Table 3 includes the projected thyroid dose as a function of the individual iodine isotope concentrations in air and the projected l exposure time. This can be used to more exactly convert radiciodine concentration field measurement to exposure if the isotopic mix is known.
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3.9 If on or offsite sampling +,aams have reported a gamma mR/hr reading, an initial estimate of thyroid exposure can be obtained by multiplying the gamma dose rate (mR/hr) by .15.
gemma thyroid x .15 =
dose rats dose rate Multiplying the thyroid dose rate by hours breathed will give you the approximate iodine dose to an individual at that location.
NOTE: The direct gamma reading (mR/hr) is primarily the dose rate from the Noble Gases in the plume.
3.9 All offsite dose projections should be considered estimates until verification from measurements in the field are obtained.
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4.0 ATTACHMENTS 4.1 Flow Chart for Determining Release Rate' 4.2 Flow Chart for Determining Dose 4.3 Conversion Factors 4.4 Site Boundary Isopleth Values by Wind Direction and Pasquill
- g-. Stability Category (2'
4.5 Total Inhalation Dose Conversion Factors e
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EP Flowchart #1a. I - 002 dee 5'I4MCMART FOR DETERMINING REEASE RA'"E A ac h nt 4.1 Time READ R-14 (CPM)
ONSCALE OFFSCALE Primars READ R-27 Backup 'r ! **
R-24 and 24A High Range v Plant Vent i Monito g g ,
Noble Gas ONSCALE OFFSCALE LOW uCi -6 Ci sec x 10 =-
p g sec.
VENT .(mR/hr)
R-14 (HP TECH) x QCC g_24,2 4A ,,,,,,,, x CF g=
C= uCi/cc C
- uCi/cc B or C CFA see TABLE 1 C= uCi/cc
, cp ... n ur, y a or
~4 C x 4.72 x 10 x PVF =
l PVF = Plant Vent Flow r C = Concentration of gas RELEASE RATE rate (CFM) 4 3 in Plant Vent being FOR NOBLE GASES 4.72 x 10 =m min
, released Ci/see QCC = R-14 Quarterly ft x sec NO CHEM. SAMPLE CHEM. SAMPLE C / M i
~4 10 x Release Rate NG o Total I Rg =
x I
ESTIMATED RELEASE RATE RELEASE RATE FOR IODQp FOR IODINE
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Iodine = Total Ci/sec y Iodines Send Chemist for a .
Chem sample as DETERMINATION l
l soon as possible to obtain actual j RELEASE RATE (RR)
(Ci/sec)
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IP-1002 Attachment 4.3 TABLE 1 CONVERSION FACTORS uCi/cc mR/hr
. Column A Column B Column C Time After R-24,24A High Range Contact With 6 Ft. From Reactor Shutdown Plant Vent Monitor Plant Vent Plant Vent 2.5 x 10 -3
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0-2 hr. 0.487 6 x 10 '
2-4 hr. 0.830 1.2 x 10 ~3 3.8 x 10-3
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~3 4-6 hr.' 1.2 1.6 x 10 5.5 x 10
~3 6-12 hrs. 1.95 2.8 x 10 ~3 9.5 x 10 5.5 x 10 -3
-2 12 - 24 hrs. 3.5 1.6 x 10
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-2 24 hrs.-2 wks. 4.7 6.5 x 10 2.0 x 10 7.3 x 10 ~3
-2 more than 2 wks. 5.3 2.3 x 10 j
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IP-1002 TABl.E 2 Attachment 4.4 1 SITE BOUNDARY ISOPLETH VALUES BY WIND DIRECTION AND PASQUILL STABILITY CATEGORY Pasquill A B C D E F G Wind Boundary Direction Sample Boundary Boundary Boundary Boundary Boundary Boundary Boundary (from)* Point X u/Q X u/Q X u/O I u/Q X u/Q X u/0 X u/Q 0* 10 --c> 12 2.2 E-6 3.4 E-6 2.8 E-5 1.7 E-4 1.2 E-4 4.0 E-4 1.2 E-3 10' 12 --C> 13 2.1 E-6 2.7 E-6 2.5 E-5 8.5 E-5 1.0 E-4 3.6 E-4 1.1 E-3 20 13 --C> 14 2.2 E-6 3.4 E-6 2.8 E-5 1.7 E-4 1.2 E-4 4.0 E-4 1.2 E-3 l 30* ~ 14 --C> 17 5.8 E-6 7.4 E-6 6.1 E-5 1.8 E-5 2.3 E-4 7.6 E-4 2.3 E-3 l 40 18 1.3 E-5 1.6 E-5 1.1 E-4 3.9 E-4 4.4 E-4 1.5 E-3 4.5 E-3 50* 13 --c> 19 1.5 E-5 1.8 E-5 1.3 E-4 4.3 E-4 4.8 E-4 1.6 E-3 4.8 E-3 60' 19 1.8 E-5 2.1 E-5 1.5 E-5 5.1 E-4 5.3 E-4 1.8 E*3 5.4 E-3 70 19 --c> 20 3.1 E-5 3.5 E-5 2.5 E-4 7.5 E-4 8.0 E-4 2.9 E-3 8.7 E-3
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80" 20 --C> 21 5.7 E-5 6.2 E-5 4.0 E-4 1.1 E-3 1.3 E-3 4.8 E-3 1.4 E-2 90 ' 21 8.0 E-5 8.5 E-5 5.1 E-4 1.5 E-3 1.8 E-3 6.3 E-3 1.9 E-2 . 100' 21 9.7 E-5 1.0 E-4 6.0 E-4 1.7 E-3 2.1 E-3 7.4 E-3 2.2 E-2 l
.. 110* 22 1.1 E-4 1.1 E-4 6.5 E-4 1.9 E-3 2.3 E-3 8.0 E-3 2.4 E-2 120" 22 1.4 E-4 1.4 E-4 8.0 E-4 2.3 E-3 2.8 E-3 9.9 E-3 3.0 E-2 130' 22 1.4 E-4 1.4 E-4 8.0 E-4 2.3 E-3 2.8 E-3 9.9 E-3 3.0 E-2 140' 22 1.4 E-4 1.4 E-4 8.0 E-4 2.3 E-3 2.8 E-3 9.9 E-3 3.0 E-2 l 150' 22 1.0 E-4 1.1 E-4 6.3 E-4 1.8 E-3 2.2 E-3 7.8 E-3 2.3 E-2 160* 22 8.6 E-5 9.2 E-5 5.5 E-4 1.6 E-3 1.9 E-3 6.7 E-3 2.0 E-2
(' 170 180" Water Water 9.0 E-5 6.0 E-5 9.5 E-5 6.5 E-5 5.6 E-4 4.1 E-4 1.6 E-3 1.2 E-3 2.0 E-3 1.4 E-3 6.9 E-3 5.0 E-3 2.1 E-2 1.5 E-2 190' Water 3.6 E-5 4.0 E-5 2.8 E-4 8.1 E-4 9.0 E-4 3.3 E-3 1.0 E-2 200 Water 2.0 E-6 2.4 E-6 1.8 E-4 5.8 E-4 5.8 E-4 2.0 E-3 6.0 E-3 210 Water 9.4 E-6 1.2 E-5 8.4 E-5 2.8 E-4 3.3 E-4 1.1 E-3 3.3 E-3 220 Water 5.4 E-6 7.0 E-6 5.8 E-5 1.8 E-4 2.2 E-4 7.3 E-4 2.2 E-3 t 230 1 5.0 E-6 6.4 E-6 5.4 E-5 1.7 E-4 2.1 E-4 6.8 E-4 7.0 E-3 240* 1 --c > 2 5.9 E-6 7.4 E-6 6.2 E-5 1.8 E-4 2.3 E-4 7.7 E-4 2.3 E-3 i 250 2+3 6.5 E-6 8.3 E-6 6.6 E-5 2.0 E-4 2.5 E-4 8.3 E-4 2.5 E-3 260 3 --C> 4 5.1 E-6 6.6 E-6 5.5 E-5 1.7 E-4 2.1 E-4 7. 0 E-4 2.1 E-3 270 4 -C> 5 _ S . 7 E-6 7.3 E-6 6.0 E-5 1.8 E-4 2.3 E-4 7.6 E-4 2.3 E-3 280 5 7.5 E-6 9.7 E-6 7.2 E-5 2.3 E-4 2.8 E-4 9.2 E-4 2.8 E-3 290 5+6 8.6 E-6 1.1 E-5 7.8 E-5 2.6 E-4 3.1 E-4 1.0 E-3 3.0 E-3
- 300 6 9.6 E-6 1.2 E-5 8.6 E-5 2.9 E-4 3.4 E-4 1.1 E-3 3.3 E-3 I 310 6 --c> 7 9.6 E-6 1.2 E-5 8.6 E-5 2.9 E-4 3.4 E-4 1.1 E-3 3.3 E-3 320* 7 E.9 E-6 1.2 E-5 8.1 E-5 2.7 E-4 3.2 E-4 1.1 E-3 3.3 E-3 330' 7 --C> S 7.5 E-6 1.0 E-5 7.4 E-5 2.4 E-4 2.9 E-4 9.6 E-4 2.9 E-3 l' 340 8 --C> 9 6.1 E-6 7.7 E-6 6.3 E-5 1.9 E-4 2.4 E-4 7.9 E-4 2.4 E-3
- 350 9 -C> 10 4.5 E-6 5.9 E-6 5.0 E-5 1.6 E-4 1.9 E-4 6.3 E-4 1.9 E-3
- The wind direction is + 5 of table value (i.e.: 5 15 )
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IP-1002 AttachmInt 4.5 l TABLE 3 TOTAL INHALATION DOSE CONVERSION FACTORS DOSE CONVERSION FACTOR mrem / uCi ISOTOPES hr ec 9 I-131 1.6 x 10 I-132 7.9 x 10 7 I-133 5.4 x 10 8 I-134 4.0 x 10 7
'0 I-135 1.6 x l0 Iodine Mix 6.7 x 10 (post accident)
C - NOTE: If the Iodine' mix is not known and it is within 24 hours of shutdgwn, use the Post: Accident Iodine Mix dose conversion factor (6.7 x 10 ). After 24 hours, use the I-131 dose conversion factor.
- Concentration x Dose Conversion Factor = Dose Rate (uCi/cc) x mrem / uCi = mrem /hr hr cc
- Concentration can be determined by calculation or by field sanples.
Field Samples: SAM - use I-131 DCF (1.6 x 10') 8 HP-210 - use Iodine Mix DCF (6.7 x 10 ) e i 4 4
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EMI31GENCY PIAN PROCEDURES PROCEDURE NO IP- 1011 REV. 5 TITLE" OFFSITE MONITORING H mes s 1 a
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WRITTEN SY: REVIEWED BY: u, , , . # i/[ . , PORC REVIEW: -l , DATE APPROVED BY: [w /b,w3 DATE iMi/84 ErrECTIvE DA i2.1 E9 : ! E s' a
IP-1011 OFFSITE MONITORING 1.0 INTENT This procedure addresses the various methods of offsite monitoring ? which are available within the plume exposure pathway. > 2.0 DISCUSSION A combination of these methods of offsite monitoring should give an idea of the radiological conditions of the environment within a 10 mile radius of Indian Point.
. Various methods of offsite monitoring are: ~~
2.1 Offsite monitoring teams: A. Beta and Gamma surveys:
- 1. Survey results
- 2. TLD's B. Air Sampling (Iodine & Particulate):
- l. Continuous Sampling C' . 2. Ewergency Locations 2.2 Reuter Stokes:
A. Gamma monitoring B. Meteorological monitoring (wind speed & direction) 3.0 PROCEDURE FOR OFFSITE MONITORING TEAM MONITORING , 3.1 Offsite monitoring locations have been predetermined and locations are listed on Attachment 6.1 of this procedure. To determine which locations should be monitored, use the overlays, 10 mile sector map and Attachment 6.1. The types of monitoring would include: - A. Iodine Sampling:
- 1. From fixed sample locations (continuous air sampling)
- 2. Emergency Sampling Sites B. k' hole Body dose:
- 1. TLD's at Fixed Locations 3.2 Members of the offsite monitoring teams are Con Edison NEM personnel.
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2P-10ll/5 3.3 CONTROL ROOM ACTIONS: A. Control Room personnel should request offsite monitoring team assistance immediately upon declaration of a Site Area or General Emergency, and in certain cases during an Alert (radiological in nature). B. The IP-3 Control Room personnel should telephone the Unit No. 2 Watch Foreman:
- 1. Request offsite monitoring team assistance
- 2. Direct the teams to the Emergency Operation Facility (EOF) ,
C. Ready yourselves to receive information via the Con Edison
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frequency radio, using EP-Form #4 and EP-Form #5. 3.4 0FFSITE MONITORING TEAM: A. Are made up from Con Edison NEM personnel ' B. Are to follow the Con Edison Procedure IP-1015 3.5 RADIOLOGICAL ASSESSMENT TEAM: A. Determine which offsite monitoring locations the offsite teams should be sent to. n (c 1.. Using overlays
- 2. Using Table 1 of this procedure B. Instruct the offsite monitoring team (s) to appropriate sample locations:
- 1. Predetermined Emergency Sampling Locations
- 2. Continuous Air Sampling Locations
- 3. TLD sites C. Discuss the need for KI with the Emergency Director and Monitoring Teams. Issue if appropriate.
D. Receive information via the radio:
- 1. Monitoring team location (s) !
- 2. Sampling results (Using forms EP-Form #4, and EP-Form #5) a) . Beta and gamma field r'eadings obtained while proceeding to the site, g b) Beta-gamma field readings obtained at the sample l
point. { c) Concentration of radioactivity on the particulate ; r* filters. Also report thesampleCPM,tgeinstrument j t_ . background CPM, the sample volume in ft , and the i counter efficiency. l l-2 of 3
- ~ . - _ . - ~ . - - - - - - - - - 8 l
. IP-1011/5 d) Concentration of Iodines on the charcoal or silver zeolite filter. AJso report the sample CPM, the ingtrument background CPM and the sample volume in ft , and the counter efficiency. ,
4.0 PROCEDURE FOR REUTER STOKES INTERPRETATION 4.1 Reuter Stokes monitors are located in each of the 16 sectors within a 3 mile radius of Indian Point. Real time Whole body dose rates, integrated dose, (Gamma) and meteorological (wind speed & direction) information can be remotely interrogated usir. the Reuter Stokes Sentrii 1011 System and the MIDAS computer. 4.2 RADIOLOGICAL ASSESSMENT TEAM: . A. Using MIDAS, obtain Reuter Stokes data. 5.0 RECORD RENTENTION 5.1 The Radiological Communicator is responsible for retaining all data sheets, forms, and plots pertaining to offsite Radiological Assessment. 6.0 ATTACHMENTS r-~, 6.1 Offsite Monitoring Locations
\.
6.2 Monitoring Team Field Survey 6.3 Environmental TLD and Air Sample Readout 8 l. t I t 1 3 of 3
IP-1011 , OFFSITE MONITORING LOCATIONS LOCATION NAME SECT MILE CAS EAS R/S TLD Roa. Hook Rd. - Sanatation Garage 1 2 CAS EAS TLD (Cortlandt) Bear Mtn. Rd. near Old Stone on Hudson 1 2 R/S Rte. 9D Garrison 1 5 TLD Rte. 9D St. Francis Retreat (Garrison) 1 7 EAS St. Basils Academy 1 9 TLD Rte. 9D Derham Cross Rd. (Cold Spring) 1 10 EAS Old Pemart Ave. (Peekskill) 2 2 EAS TLD Annsv111e Circle, Texaco Station 2 2.5 R/S I Highland Ave. & Sprout Brook Rd. 2 3 EAS Gallows Hill Rd. 2 6 TLD Canopus Hollow Rd. & Old Albany Post Rd 2 6 EAS ;
. Canopus Hollow Rd. & Bell Hollow Rd. 2 10 EAS TLD North East Corner (site) 3 .5 TLD Louisa St. & R.R. Bridge 3 1 EAS Lower Scuth St. & Bay St. 3 1.5 TLD Peekskill Gas Holder 3 2 CAS Hudson St. & RR Street (Peekskill) 3 2 R/S (Carbones Rest.)
Hamilton St. 3 3 TLD Hillcrest School (Peekskill) 3 3 EAS l r Oregon Road Substation 3 4 CAS Westbrook Dr. 3 6 TLD Oregon Corners (Putnam Valley) 3 6 EAS i Peekskill Hollow Rd. & Tinker Hill Rd. 3 10 EAS TLD Lents Cove 4 .5 TLD Standard Brands 4 1 CAS TLD Old Dump 4 1 TLD _ Lower South St., Merle Corp.(Peekskill) 4 1 EAS Lower South St. near West. Iron 4 1 R/S Lower South St. & Louisa St. 4 1.5 TLD Maple Ave. Entrance to Mt. Florence 4 3 EAS School - Pine Rd. 4 5 TLD Lexington Ave. & Townsend Rd. 4 6 EAS (Cortlandt)
- Somerston Rd. & Carol Ct. (Yorktown) 4 10 EAS TLD Bleakley & Broadway S .5 CAS TLD Lower S. St. near By Pass Diner 5 1 R/S Welcher Ave. & McKinely School 5 1.5 TLD Playground McKinley St. & Welcher Ave.(Peekskill) 5 2 EAS Maple Ave, & Furnace Woods Rd. 5 4 EAS
- (Cortlandt) I Croton Ave. 5 6 TLD Hunterbrook Rd. @ Coax Sta. #571 5 7 EAS (Yorktown) , ,
Moseman Rd. & St. Patricks School 5 10 EAS TLD l (Yorktown)
~ _ _ _ . . _ . - _ _ _ _ . . . _ . _ . . -
I . IP-10ll Attachment 6.1 Pg. 2 LOCATION NAME SECT MILE CAS EAS R/S TLD Simulator Building 6 .5 TLD Broadway, between Pleakley & Service 6 .5 R/S Center
- Tensolite Corp. Rt. 9A (Buchanan) 6 1 EAS Factory St. 6 1.5 TLD Watch Hill Rd & Mt. Side Trail 6 3 EAS (Cortlandt)
Colabaugh Pond Rd. 6 6 TLD Rte. 129 @ Hunterbrook Bridge (Yorktown) 6 7 EAS g Ree. 100 & Ree. 134 6 10 EAS TLD Water Meter House 7 .5 TLD
- Broadway, at Service Center Gate 7 .5 R/S l Buchanan Village Hall 7 1 CAS TLD Westchester Ave. & First St. (Buchanan) 7 1 EAS Furnace Dock 7 4 CAS TLD Watch Hill Rd. & Westminister Dr. 7 4 EAS (Cortlandt)
Mt. Airy & Winsor Rd 7 5 TLD Cleveland Dr. & Hughes St. (Croton) 7 6 EAS l. North State Rd. & Ryder Ave. 7 10 EAS TLD Environmental Lab 8 .5 CAS TLD . C. Service Building 8 .5 CAS TLD Broadway, S.W. of Sub Station 8 .5 R/S . Westchester Ave. & School Exit 8 1 EAS (Buchanan) - Tate Ave. 8 1.5 TLD Crugers R.R. Station (Cortlandt) 8 3 EAS Croton Point & Sample Site 8 7 CAS EAS TLD Liberty St. & Hudson St. (Ossining) 8 10 EAS TLD I South East Corner (site) 9 1 TLD 14th St. Between Broadway & Wes:. Ave. 9 1 EAS Broadway at St. Mary's Cemetary 9 1 R/S Montrose Marina 9 2 TLD Montrose Pt. Rd. (Cortlandt) 9 3 .EAS Warren Ave. Haverstraw 9 5 TLD , Rte. 9W & So.Mt.Rd. (Short Cove) 9 7 EAS (Clarkstown) Kings Highway & Old Mill Rd. 9 10 EAS TLD (Clarkstown) 4
L - IP-10ll Atttchmint 6.1 Pg. 3 LOCATION NAME SECT MILE CAS EAS R/S TLD l k Onsite Pole 10 .5 TLD N.Y.U. Tower 10 1 CAS TLD lith St. & Highland Ave. (Verplanck) 10 1 EAS lith St. & Highland (Con Ed Property) 10 1 R/S I Verplanck 10 l '. 5 TLD Grassy Point 10 4 CAS TLD Beach Rd. & Grassy Pt. Rd. (Stony Pt.) 10 4 EAS , Railroad Ave. & Ree. 9W 10 5 TLD Little Tor Rd. & South Mt. Rd. 10 7 EAS (Clarkstown) : West Clarkstown Rd. & Palisades Pkwy. 10 10 EAS TLD Overpass (Clarkstown) White Beach' Texas Inst. (Verplanck) 11 1 EAS Algonquin Gas Line Crossing 11 1 CAS TLD Trap Rock at end of 9th Ave. 11 1 R/S (White Beach) i Gilmore Dr. & Adams Dr. (Stony Pt.) 11 3 EAS Willow Grove Rd. & Birch Dr. 11 5 TLD Willow Grove Rd. & Knapp Rd.(Haverstraw)11 6 EAS Haverstraw Rd. (Ree. 202) & Wilder Rd. 11 10 EAS TLD Gays Hill Rd. (south end) & Rte. 9W 12 2 EAS R/S TLD {. Lovett Plant 12 2 CAS Frank Rd. & Bulson Town Rd. (Stony Pt.) 12 4 EAS Palisades Pkwy. (sign going So.,NY&NJ) 12 5 TLD Lake Welch Pkwy. & Sewage Plant 12 7 EAS (Harrison) Lake Welch Pkwy. & 7 Lakes Pkwy. 12 10 EAS TLD (Harrison) Gays Hill Rd. (north end) & Rte. 9W 13 2 EAS R/S TLD Mott Farm Rd. @ Entrance to Camp 13 3 EAS Addison Boyce (Tuxedo) Palisades Pkwy. (So. of Gas Station) 13 5 TLD Arden Valley & Lake Cohasset 13 9 EAS TLD Dock (Onsite) 14 .5 TLD Ree. 3W at Pirates Cove Rest.(Stony Pt.)14 2 EAS R/S TLD Anthony Wayne Park - 14 5 TLD Rte. 6, 1 mi. West of Palisades Pkwy. 14 6 EAS County Rte. 9 @ Thruway (Woodbury) 14 10 EAS TLD ., 1 Ree. 9W & Anchor Monument (Stony Pt.) 15 1 EAS Rte. 9W So. of Ayers Rd. 15 1 TLD 9W & 202 (Pole # NYT #225) e 15 1 R/S Front Entrance Bear Mt. Inn 15 4 EAS Palisades Pkwy. (Lake Welch Exit 15 5 TLD going South) ; Mine Rd. & Weynants Rd. (Highland) i 15 6 EAS Mineral Springs Rd. & County Ree. 34 15 10 EAS TLD
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. l IP-1011 Attachment 6.1 i I
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LOCATION NAME SECT MILE CAS EAS R/S TLD Ayers Rd., Jones Point (Stony Pt.) 16 1 EAS R/S TLD Bear Mt. Bridge West End 16 4 EAS Fort Montgomery 16 5 TLD 0.4 mi West. Junction Res. 9W & 218 16 6 EAS Rte. 9W & Rte. 293 (highland) 16 9 EAS TLD l SECT: Sector CAS: Continuous Air Sampling Site (Green dots) EAS: Emergency Air Sampling Site (Yellow dots) R/S: Reuter Stokes (Blue dots) TLD: , TLD (Red dots) Mile determinations are made in this manner: Miles are determined by the mile sector which encompasses it. Example: If site is between sector 1 & 2, it will be referred to as mile 2. ( .- t l l l ..,, _ . . . _ _ . . . _ _ . . - -- -- -- -
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IP-10ll Attachment 6.2 EP-Form 4 4 MONITORING TEMi TIEI.D SURVEY Instrument Model No. Serial Number Individuals Name Date Survey Location or Site B+I / [(B + I)- T]4 Perimeter Sector Number Time mR/hr mR/hr mrad /hr Remarks
*eW-G 9
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EP-Form 4 5 IP-1011 Attachmrnt 6.3 ENVIRONMENTAL TLD AND AIR SAMPLE READOUT Prior to Discharge C ~ After Discharge C Sample Pickup - Date Time Indiv. Sample Process - Date Time Indiv. TLD AIR SAMPLE Sector Sector Iodine uCi Thy. Mile Zone mrem Mile Zone Part. Char. Rem
- 4 w
r k 3 d Note: 1 uCi of Iodine on filter (Part. or char.) is approximately equal to 1 Rem exposure to the adult thyroid. 1 b
Indian Point 3
. Nuclear Power Plant PD. Box 319 Buchanan, New Wet 10911 914 739.8200
#> NemiYorkPowe-Taff Authority EMERGENCY PLAN PROCEDURES PROCEDURE NO IP- 1028 REV. O TITLE" Core Damage Assessment M
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REvzEwED sr. PORC REVIEW: .s . DATE/>>/', i APPROVED BY: % DATE/k//7% ErrEcTIvr DATE: .'s i 4 i 1 _ .-. . . , - - - - . . . _ _ _ _ _ - . . . - . . _ _ . . _ _ . . l
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. IP-lO28/O
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CORE DAMAGE ASSESSMENT PROCEDURE l l 1.0 PURPOSE To provide a methodology to determine the extent of core damage following a postulated accident based on radionuclide concen-trations in reactor coolant (RCS) and containment atmosphere (VC) samples as well as other plant indications and parameters. 2.0 DATA PREREQUISITES The information described in the following paragraphs will be utilized in assessing the core damage condition. Where infor-mation (other than measured concentrations) is not fully available
, _ _ and cannot be obtained in a timely manner, attempts should be made to conservatively estimate those values, with the use of such estimates noted in all discussions and evaluations of results.
2.1 RCS and VC samples have been taken and analyzed (with appropriate isotopic breakdown) in accordance with established post accident sampling procedures. The appropriate source of the liquid sample will depend on the particular accident scenario. 2.2 The following additional information has been obtained: 2.2.1 The reactor coolant temperature at the time the sample is taken. 2.2.2 Temperature of the RCS sample. 2.2.3 Pressure and temperature of both the containment atmosphere (at time of sampling) and the correspond-ing sample. 2.2.4 The volume of emergency core cooling water injected into the primary system. 2.2.5 The amount of dilution performed by the chemist during the sampling process. 4 l Page 1 of 13
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IP-1028/0 1 2.2.6 The elapsed time from reactor shutdown to sample analysis. 2.2.7 Power history data for current cycle and Effective . Full Power Pays (EFPD) for two previous cycles. 3.0 QUALITATIVE ASSESSMENT OF CORE DAMAGE Where plant parameters indicate an abnormal plant shutdown has occurred with core cooling jeopardized or interrupted and possible core damage, a preliminary determination of the extent of core damage can be made by qualitatively reviewing the analyzed sample and evaluating it together with other plant parameters and operating data. Based on the following indicators, a general core damage assessment can be made: 3.1 Cladding Damage Indicators 3.1.1 The appearance of noble gases (xenons, kryptons). iodines and possibly small amounts of cesium in the reactor coolant without the presence of other fission products is a fair indication that damage is
, limited to clad failure and possibly, a limited degree of fuel overheat.
3.1.2 Additional indicators of ci,ad damage include: ( 3.1.2.1 Core exit thermocouple temperature readings higher than 650 (for LOCA with normal Engin-eered S,afeguards response, the maximum expected
. core exit temperatures with natural circulation should be about 620 - 650 F);
I NOTE. Thermocouple readings as confirmatory infor-mation for. core. conditions beyond clad damage
- must be used with caution since coolant con-
. ditions (i.e., steaming) can significantly affect thermocouple accuracy. Those readings should therefore be evaluated carefully before i use. A review of any available thermocouple l trends (log, computer, etc.) will be useful in this evaluation.
3.1.2.2 High Range Containment Monitors (when conditions indicate release to containment) , 100%clagdamagemayindicateupto ! 2.7 x 10 rad /hr on R-25 and R-26 ! i L Page 2 of 13
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IP-1023/O 3.2 Overtemperature Indicators 3.2.1 The presence of an appreciable cesium concentration will be indicative of at least a fuel overheat situation since no substantial quantity of cesiums should be found if core temperatures remain below 2370 F or if the core has not been at least partially uncovered for some extended period of time. In addition, strontium and barium may be present. 3.2.2 High Range Containment Monitors: (When conditions indicate releage to containment) R25/R26 would read up to 3.0 x 10 rad /hr for 100% overheat / melt.
, . 3.2.3 Reactor Vessel Level Indicating System (if avail-able) indicates core uncovery for an extended period of time.
3.2.4 Significant releases (e.g. greater than 100 uCi/cc) of tellurium, ruthenium and more refractory materials will occur only if the temperature approaches the fuel melting point (%,4500 - 5000 F). The presence of ruthenium and tellurium does not
" prove" melting, but their absence is a good -
indicator that melt has not occurred.
) 3.3 Fuel Melt Indicators 3.3.1 Presence of cerium and lanthanum in fluid samples are generally indicative of fuel melt. Ruthenium and tellurium must also be present (although as stated in 3.2.4, their presence does not prove melt).
3.3.2 High Range Containment Monitors: (when conditions indicate releage to containment) R25/R26 would read up to 3.0 x 10 rad /hr for 100% fuel overheat / melt. 4.0 ASSESSMENT OF CLAD DAMAGE FROM HYDROGEN GENERATION FROM ZIRCONIUM WATER REACTION The percent of the zirconium cladding reacting with water car be { estimated using the graph in Figure 1. This assumes that there has been no substantial loss of Hydrogen due to Hydrogen recombiner use. . I 5.0 ASSESSMENT OF THE CORE DAMAGE FROM SAMPLE ANALYSIS ., The following procedural steps address more detailed character-ization of core damage based on results of sampling and analysis of RCS and VC samples. The calculations are based on characteristics -l
- of a reference sample corrected for actual saepling conditions.
q_ Containment atmosphere sampling is of importance only for "line-break" type accidents. Page 3 of 13 y , , --- g - -- e-= -e . r - # ----- .-,-.
,g IP-1028/0 5.1 Application and Determination of Correction Factors l 1
The " reference sample" assumes the following characteristics: o A core average burnup of 1050 effective full power days (EFPD) - EOL conditions. .q o D,ilution of the liquid source term in Reactor Coolant , System volume only (non-line break accident), o Noadditionaldilutionduringthesamplingandanalysis process. o The RCS sample at RCS temperature and pressure (and therefore density) o The VC sample at containment temperature and pressure o Samples taken at time of shutdown To correct for deviations from the above assumptions under ( specific sampling conditions, the following correction factors should be applied as appropriate to the measured activity. The correction factors should be used for both the RCS and VC samp?*s unless otherwise indicated. 5.1.1 Operating Time Correction Factor (P) v Long Lived Isotopes (See Table 2) This correction factor is applied to correct long lived nuclides for operation for less than EOL conditions assumed in the formulation of the j reference " maximum concentration" (MX) values shown } in Table 2. L 1-e -1050Ai p . ) ~ T (1-e 1 0) +N/193(ey ibl)(1-e i1))+N/193{e 2 i 2) (1-e i2)) where: T = operating time,for' current cycle (EFFD) t = time since end.of last cycle (days) T g = operating tima'for last cycle (EFPD) , t = time since end of cycle before last (days) l 2 T ! A 2 "= decay codetantperatingtimeforcyclebeforelast{EFPD) for isotope "i" (days" ) l
. Nf=Numberofassembliesfromthelastcycle {
currently in core j N = Number of assemblies from cycle 1efere last l 2 cycle currently in corn. i f L. Page 4 of 13 gii-gq__ -- W h er Wr-e egi .4-@'d'- m a yG, w r*- * =
. IP-1028/0 Short Lived Isotopes For short lived isotopes (See Table 2), the operating time correction factor (P) must be cal-culated for each isotope 1:
P= 100
)[ P . (1-e ^i j)
~
e ~^i j where: P = steady reactor power in period j (percent) T '= duration of period j (days) t = time from end of period j to react 6r shutdown d (days) NOTE: This calculation should be made over a period starting from at least five half-lives prior to the present shutdown and ending at the time of the present shutdown. Table 3 is included as a worksheet, if necessary. One sheet should be used for each short-lived isotope. (7 s- 5.1.2 Correction for Additional Dilution Provided by Emergency Core Cooling System (ECCS) Volume (ED) For accidents involving injection of emergency core cooling water'into the primary system, the assumed dilution volume for the RCS sample must be corrected. The volumes which may need to be added will depend on the specific accident scenario and may typically include the accumulators, boron injection tank and Refueling Water Storage Tank. The actual volumes can be determined from ' appropriate level and flow instrumentation. ED = 91,600 + ECCS Volume Injected (gallons) 91,600 l i r"
%ee Page 5 of 13
IP-1028/0 l l
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5.1.3 Correction for Dilution During Sampling Process (SD) l l The " reference sample" is an undiluted sample. A l Sampling Dilution (SD) correction factor must be , applied if the chemist further dilutes the drawn !' sample. SD = Dilution Ratio (e.g., SD = 1000 for a 1000: I dilution) 5.1.4 Density Cortection Factor (R) This a straightforward correction if the density of the sample differs from that of the RCS or Containment. The correction factor (R) is taken
;. from Table 1 for the RCS sample. Temperature of the RCS Sample is assumed to be 80 F.
For the Containment atmosphere sample this factor ! I - can be determined by: ! R = (Pve) Ts Ps (Tve) I where: Pvc = Containment Pressure (psia) Ps = Sample pressure (psia) during c analysis ( Tvc = Containment temperature ( R) Ts = Sample temperature ( R) during analysis - Sample temperature is assumed to be equal to the VC temperature. Sample pressure is assumed to be atmospheric. 5.1.5 Decay Correction' Factor i This corrects the measured fission product concen-tration (MC) to account for decay from reactor' shut-down to the time of analysis. This calculation must be performed for each appropriate isotope. MC, = MC (e * *) where: MC, = decay corrected measured concen-
. tration MC = uncorrected measured concentration !
t
= time (hrs) from shutdown to analy"ais A = decay constant (See Table 2)(days )
.0417 = conversion factor (hours to days)
NOTE: The gamma spectrometry computer may be used to back calculate these values. i. Page 6 of 13
ZP-lO28/0 5.2 Determination of " Adjusted" Measured Concentration Having determined and calculated all appropriate correction factors, the " adjusted" measured concentration AC is given by: ACg = (MC ,* P
- ED . SD + R)RCS (MC,' P
- SD + R)VC " "**
(RCS volume) where: AC;= Adjusted total measured concentration for isotope
- 1. This includes both RCS and VC concentration and will be compared to the " reference" sample concentrations (MX's)
- - - RCS = Adjusted Reactor Coolant System concentration VC = Adjusteo C-'t.sanment atmosphere concentration i
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(VC volume) = This term adjusts the containment atmosphere (RCS volume) concentration to allow it to be directly added to the RCS concentration. This concentration should be determined for each of the isotopes Table 2 (or as many as f^ possible). These adjusted concentrations should then be compared to the reference concentrations (MX values) given in Table 2 as follows: NOTE: A different calculation must be performed for each isotope, and it is expected that different fractions will be calculated. Engineering judgement must be used on the aggregate results, to resolve any discrepancies. 5.3 Clad Damage Estimate To estimate the fraction of clad failure damage: 5.3.1 Determine the maximum clad failure concentration, fro MX[ isb ope"mTable2,ColumnIforeachselected i". i
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Page 7 of 13
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IP-1028/0 5.3.2 Calculate a Clad Failure Fraction (CFF for each appropriate isotope) CFF = ACi CFi where Ac t
= adjusted concentration for isotope "i" 5.3.3 Criterion for Cladding Failure If CFF ( .01 there is little or no cladding damage.
Verify that MC is within normal concentration measurements. If .01s CFF il.0 there is some degree of clad damage. To estimate percentage of damage, multiply CFF by 100. If CFF >1.0 proceed to next paragraph to estimate damage. 5.4 Fuel Overtemperature Estimate To estimate the degree of fuel overtemperature: 5.4.1 Determine the maximum fuel overtemperature concen-l (' tration, MXp fr - ( \_ selectedisokope"omTable2.ColumnIIforeach i". 5.4.2 Calculate a Iuel Overtemperature Fraction (F0F): F0F = ACi F01 where AC = adjusted concentration for isotope "1" 5.4.3 To estimate the percentage of the core in an over-temperature conditions, multiply F0F by 100. If F0F is greater than 1.0, proceed to the next paragraph to evaluate for fuel melt. 5.5 Fuel Melt Estimate To estimate the fraction of the core which may have experienc-ed core melt: 5.5.1 Determine the maximum fuel melt concentration, MX fro isbYope"mTable2,ColumnIIIforeachselected 1". , (" i 1 Page 8 of 13
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.. IP-1028/0 5.5.2 Calculate f Fuel Melt Fraction (FMF):
FMF = ACi i where AC g adjusted concentration for isotope "i" 5.5.3 To estimate the percentage of fuel melt, multiply FMF by 100. Note the presence of ruthenium and tellurium as per 3.3.1. 6.0 CAUTIONS AND RECOMMENDATIONS If conflicting data exists based on criteria guidance given in Sections 3 and 4, reanalyze all indications. For example; the
. analysis yields results which indicate' core melt. The core ~~
thermocouple readings show the core is not hot enough to have melted. The sample analysis should therefore be re-examined to determine if the isotopics chosen are appropriate. It should also be noted that the above evaluations address an assumed uniform distribution of core damage. Since the degree of damage is likely to vary within the core, calculations for CFF, F0F and FMF should all be performed to provide a better understanding and perspective with regard to the potential existence of a mixture of fuel damage conditions. Variations in core exit thermocouple readings may supply additional supporting information. Finally it should also be noted that the results determined using this procedure are subject to inaccuracies related to physical processes occurring in the RCS and VC in the post accident condition. These processes, including among others, adsorption, sedimentation and plateout, may remove a significant amount of source term from both the atmosphere and fluid from which the sample is drawn. Although inclusion of these processes is beyond the scope of this. evaluation, their potential effect should be borne in mind.
7.0 REFERENCES
7.1 Reactor Safety Study (WASH-1400) I - 7.2 Three Mile Island - Report to the Commissioners and to the Public ("Rogovin Report") 7.3 W Mitigating Core Damage Training Manual, Sections 6 & 8 7.4 Westinghouse Radiation Analysis Design Manual 7.5 ORIGEN (Isotope generation and depletion code) t r w. i Page 9 of 13 1
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* . IP-1028/0 TABLE 1 DENSITY CORRECTION FACTORS (R)
RCS Sample Temperature ( F) 70 80 90 100 100 .995 .996 .998 1.0 150 .982 .983 .985 .987 200 .965 .966 .968 .970 __ 250 .944 .945 .947 .949 300 .920 .921 .923 .924 350 .892 .894 .895 .897 400 .861 .862 .864 .865 450 .826 .827 .828 .830 I RCS Tem- 500 .787 .788 .789 .791 ( perature at time 550 .737 .738 .739 .742 of sample ("F) 560 .726 .727 .728 .730 570 .716 .717 .718 .720 580 .704 .705 .706 .707 590 .692 .693 .694 .695 600 .680 .681 .682 .683 620 .650 .651 .652 .653 640 .617 .618 .619 .620
, 660 .579 .580 .582 .582 i 680 .528 .529 .530 .531 700 .438 .438 .439 .441 ,
t 4 l Page 10 of 13
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IP-1028/0 TABLE 2 t Short Lived Isotopes I II III MX-CF MX-F0 MX-FM Isotope Halflife A(day ~) (C1/cc) (Ci/ce) (Ci/cc) Mo-99 66.0h .252 N/A 4.8E-3 1.4E-2 I-131 8.04d .0862 4.7E-3 1.4E-1 2.5E-1 { I-133 20.8h .800 8.6E-3 2.5E-1 4.5E-1 Xe-133 5.25d .132 1.5E-2 2.5E-1 4.5E-1 Te-132 78.2h .213 N/A 1.9E-2 5.7E-2 Ru-105 4.44h 3.75 N/A 3.3E-5 1.0E-3 Ba-140 12.79d .0542 N/A 9.0E-3 4.5E-2 La-140 40.2'2h .414 N/A N/A 1.4E-3 l (' Long Lived Isotopes (. Kr-85 10.72y 1.77E-4 9.3E-5 1.5E-3 2.8E-3 Cs-137 30.17y 6.09E-5 1.6E-3 1.3E-2 2.6E-2 Ce-141 32.5d 2.13E-2 N/A N/A 1.2E-3 Sr-89 50.6d 1.37E-2 N/A 3.6E-3 1.8E-2 Sr-90 28.6y
- 6.64E-5 N/A 4.2E-4 2.1E-3 Ru-103 39.4d 1.76E-2 N/A 3.7E-5 1.1E-3 Ru-106 368d 1.88E-3 N/A 1.9E-5 5.5E-4 Ce-144 284d 2.44E-3 N/A N/A 9.3E-4 i
N/A = Not Applicable h l i'w, Page 11 of 13
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