ML20065A490
| ML20065A490 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 01/10/1983 |
| From: | Coy S DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML16162A429 | List: |
| References | |
| PROC-830110-01, NUDOCS 8302220059 | |
| Download: ML20065A490 (72) | |
Text
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I Page 2 Table of Contents (Implementina Procedures - Continued) , CP/0/B/2003/02 Estimate of Failed Fuel Based on I-131 Concentration (12/15/82)- CP/1&2/A/2002/05 Post Accident Caustic Injection into the Low Pressure ! Injection System (01 26-81)
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CP/3/A/2002/05 Post Accident Caustic Injection into the Low Pressure Injections System (01-26-81) CP/2/A/2002/04B Post Accident Liquid Sampling of the Low Pressure Injection System (12/01/81) CP/3/A/2002/04B Post Accident Liquid Sampling of the Low Pressure Injection System (12/01/81) CP/0/A/2004/2E Post Accident Determination of Boron Concentration Using Carminic Acid (07/09/82)
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CP/0/A/2004/3C Post Accident Determination of Chloride by Specific Ion Electrode Using Beckman 4500 Meter - (07/09/82) CP/0/A/2005/2D Post Accident Determination of Gamma Isotopic Activity (07/09/82) CP/0/B/4003/01 - Procedure for Environmental Survelllance Fol" awing a Large Unplanned Release of Gaseous Radioactivity - (12/09/82) ll CP/0/B/4003/02 The Determination of Plume Direction and Sector (s) to be Monitored Following a Large Unplanned Release of Gaseous Activity - (10/15/82) HP/0/B/1009/09 Procedure for Determining the Inplant Airborne Radiciodine Concentration During Accident i Conditions - (07/09/81) HP/0/B/1009/10 Procedure for Quantifying Gaseous Releases t Through Steam Relief Valves Under Post-Accident Conditions - (05/06/82)
- . HP/0/B/1009/11 Projection of Offsite Dose from the Uncon-trolled Release of Radioactive Materials Through a Unit Vent - (12/23/82)
HP/0/B/1009/12 Distribution of Potassium Iodide Tablets in the Event of a Radioiodine Release - (08/13/82) 1 Revision 83-1 Janua ry 10, 1983 i -
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8 * . Page 3 Table of Contents (Implementing Procedures - Continued) - HP/0/B/1009/13 Procedure for Implementation and Verification for the Availability of a Back-Up Source of Meteorological Data - (04/23/82) HP/0/B/1009/14 Project Offsite Dose from Releases other than Through a Vent - (12/20/82) l HP/0/B/1009/15 Procedure for Sampling and Quantifying High Level Gaseous Radioiodine and Particulate Radioactivity - (07/15/82) HP/0/B/1009/16 Procedure for Emergency Decontamination of Personnel and Vehicles on-site and from Off-site Remote Assembly Area - (9/16/82) IP/0/B/1601/03 Environmental Equipment Checks - (12/08/82) l l 1 I Revision 83-1 Janua ry 10, 1983 O
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Form 34731 (10-81) (Formerly SPD 1002-1) C {Q a.a*_ DUKE POWER COMPANY (1) ID No: CP/0/3/2003/02 PROCEDURE PREPARATION Change (s) O to
- PROCESS RECORD 1 Incorporate (
(2) STATION: Oconee Nuclear Station l3) '.?ROCEDURE TITLE: Esti:nate of Failed Fuel Based on I-131 Concentration (4) PREPAREDY: B ,dIc, e A dm DATE: /2-AfL (5) REVIEWED-BY: DATE: / A f i. Cross-Disciplinary Review By: N/R: (6) TEMPORGY APPROVAL (IF NECESSARY): By: (SRO) Date:
, 7 By: m _
Date: (7) APPROVED 3Y: u U.w Date: b (8) MISCELLuiEOUS: -
/ Approved By: . o Date: / .2. 9 u V d //
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7.- 1 . - . _ - v CP/0/B/2003/02 DUKE POWER COMPANY OCONEE NUCLEAR STATION ESTIMATE OF FAILED FUEL BASED ON I-131 CONCENTRATION 1.0 Purpose This procedure describes the method for calculating the number of failed fuel pins and the percent failed fuel for four fuel conditions using the I-131 concentration (in pCi/ml) in the Reactor Coolant System (RCS). 2.0 Limits and Precautions e 2.1 The numbers obtained by using this procedure are at best, estimates only. 2.2 All formulas quoted are based upon equilibrium full power core iodine. If fuel damage is suspected to have occurred during times of -s reduced power or near the time of significant power change, the core -)
/_
' I-131 inventory must be adjusted by using. Enclosure 10.2. This is -- the correction factor Y. .
- 2.3 All' values given are normalized to volumes of coolant at normal reactor coolant system pressure and temperature. To correct for other RCS system temperatures or RCS sample temperatures, use Enclosure 10.1. This is the correction factor X.
h 2.4 The decay of Te-131 to I-131 has been neglected as insignificant in
- , this analysis.
, i 2.5 Iodine spiking may occur after a shutdown or significant power i change. Data from other nuclear power plants have-shown that the 4 iodine spiking process has been observed to occur during a period of cj 1 to 3 days after the change or shutdown. However, the spike seems ,- to peak during the period from 4 to 8 hours after the change. I-131 !' - concentrations can increase by a factor of 2 to 25 above the equilibriun levels during these times, although an increase over a factor of 10
] ,; is unusual and would only be seen at a shutdown. Increases by a factor of 2 to 3 are typical for a significant power decrease (i.e.,
[ 100% to 50% power). Do not misinterpret this temporary change for j j fuel failure if there is no other evidence of fuel damage. Other i avidence of fuel damage can be constituted by any indication of
-i - inadequate core cooling, loose parts indication, high incere thermo-l couple indication, etc.
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r ( i 2.6 If estimates for fuel failure-are needed for fuel conditions other
\ than those covered by the four cases described below, or if more accurate fuel failure data is needed, see Section 7.0 of this pro-cedure.
2.7 The following four cases cover a very board range of core conditions. Choose the one that best suits the existing conditions. 2.8. Follow up as necessary with Babcock and Wilcox site managers depending on the plant situation. 3.0 case I - Normal Operation 3.1 Initial Conditions 3.1.1 The conditions which pertain to Case I - Normal operation are as follows: 3.1.1.1 Normal reactor operation at any power or snutdown with no unusual conditions-prior to shutdown. Adequate core cooling has been maintained. 3.2 Procedure 3.2.1 If 3.1.1 describes the core conditions, use the following
/ S! formulas to calculate the range of failed fuel values.
V Evaluate correction factors X and Y by using Enclosures 10.1 and 10.2. 3.2.1.1 (Measured I-131 concentration uCi/ml)(X)(Y) = 3.5 x 103 pCi/mi .
= Number of failed pins (Max. expected-ind best estimate) 3.2.1.2 (Measured I-131 concentration uCi/ml)(X)(Y) =
- 4.9 x 10~3 pCi/ml i
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= Number of failed pins (Min, expected)
- 3.2.1.3 (Measured I-131 concentration uCi/ml)(X)(Y) =
l 1.8 pCi/ml
= Percent failed fuel (Max. expected and best estimate)
L 3.2.1.4 (Measured I-131 concentration uCi/ml)(X)(Y) =
; 2.5 pCi/ml
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= Percent failed fuei (Min. expected) 4
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o . . 3- - NOTE: Values for I-131 concentration in pCi/ml for Oconee at normal operating conditions are between 1.0 x 10 3 and 5.0 x 10~1 pCi/ml. 4.0 Case II - Macroscopic Clad Damage 4.1 Initial Conditions 4.1.1 The conditions which pe'tain r to Case II - Macroscopic clad damage are as follows: 4.1.1.1 Normal reactor operation at any power, or shutdown where some mechanical clad failure (i.e., a loose part monitor indication) or a flow induced failure is suspected. The core has adequate cooling and no significant fuel overtemperature . is observed. 4.2 Procedure 4.2.1 If 4.1.1 best describes the core conditions, use the following formulas to calculate the range of failed fuel values. Evaluate correction factors X and Y by using Enclosure 10.1 and 10.2. s t 1 4.2.1.1 -(Measured I-131 concentration uCi/ml)(X)(T) = - 5.5 x 102 pCi/ml
= Number of failed pins (Max. expected) 4.2.1.2 =
(Measured I'-131 concentration uCi/ml)(X)(Y)
. 16.5 x 10~2 pCi/ml 4 = Number of failed pins (3est estimate) 4.2.1.3 ,( Measured I-131 concentration uCi/ml)(X)(Y) =
27.4 x 10~2 pCi/ml j = Number of failed pins (Min. expected) 4.2.1.4 = (Measured I-131 concentration uCi/ml)(X)(Y) i j 27.9 pCi/ml
= Percent failed fuel (Max. expected)
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= Percent failed fuel (Best estimate) . 4.2.1.6 (Measured I-131 concentration uCi/ml)(X)(Y) =
139.5 pCi/ml
= Percent failed fuel (Min expected) 5.0 Case III - Severe Fuel Overtemperature 5.? Initial Conditions 5.1.1 The conditions which pertain to Case III - Severe Fuel Overtemperature are as follows:
5.1.1.1 TMI type accident where there has been an abnormal shutdown and it is suspected that the fuel has been at least partially uncovered for a period of time greater than a few minutes. Voiding in the core is detected by high incore thennoccuple
, . . readings and loss of margin to saturation. Fuel
( ~f clad' oxidation is detected by excess hydrogen in ( the containment or in the reactor coolant sample; however, no fuel melting is suspected. 5.2 Procedure 5.2.1 If 5.1.1 best describes the core conditions, u'se the following values. formulas to calculate the range of failed fuel Evaluate correction factors X and Y by using Enclosures 10.1 and 10.2. . 5.2.1.1 (Measured I-131 concentration uci/ml)(X)(Y)= l' 2.4 pCi/ml
- = Number of failed pins (Max. expected) i 5.2.1.2 l
(Measured I-131 concentration uCi/ml)(X)(Y)= 2.9 pCi/ml
= Number of failed pins (Best estimate) 5.2.1.3 (Measured I-131 concentration uci/ml)(X)(Y) =
,, 3.2 pCi/ml 4
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= Percent failed fuel '(Max. expected) 5.2.1.5 (Measured I-131 concentration uCi/ml)(X)(Y) =
1535 pCi/ml
= Percent failed fuel (Best estimate) 5.2.1.6 (Measured I-131 concentration uCi/ml)(X)(Y) =
1675 pCi/ml Percent failed fuel (Min. expected) 6.0 Case IV - Fuel Melting 6.1 Initial Conditions 6.1.1 The conditions which pertain to Case IV - Fuel Melting, are as follows: 6.1.1.1 Severe accident where there has been an abnormal ,,
* - shutdown and the core is uncovered for a long period of time.
Incore thermocouple temperature readings are above 2300*F for a long period of time. Fuel melting is suspected (i.e., fuel temp-erature exceeds 5000*F) and is verified by the in-ability to operate the incore instrumentation system properly. 6.2 Procedure
' 6.2.1 If 6.1.1 best describes the core conditions, use the following formulas to caluclate the failed fuel values.
"s Evaluate correction factors X and Y by using Enclosures 10.1. and 10.2. 6.2.1.1 (Measured I-131 concentration uCi/ml)(X)(Y) =
- t t 5.5 pCi/ml
=
5 Number of failed pins (Best estimate) 6.2.1.2 l ' (Measured I-131 concentration uCi/ml)(X)(T) = 2790 pCi/mi ,
- =
s' Percent of failed fuel (3est estimate)
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7.0 Case V - Other Fuel Conditions 7.1 If fuel conditions other than those described above exist, or if a more detailed failed fuel estimation is desired for either emergency or normal operation, contact the appropriate B&W Site Managers or the Crisis Management Center for assistance. 8.0 Data Disposition 8.1 When plant conditions dictate that the Technical Support Center (TSC) is not necessary to the Safe Operation of ONS: , 8.1.1 Deliver Enclosures 10.4 - 10.7 to the Station Chemist in the Technical Services Building. Deliver a copy to the Primary Chemistry Supervisor. S.2 When plant conditions, addressed in the Emergency Plan, dictate that the TSC be manned: 8.2.1 Deliver Enclosures 10.4 - 10.7 to the Station Chemist in the TSC. Deliver a copy of Enclosures 10.4 - 10.7 to the Power Chemistry Supervisor in the Operational Support Center (OSC).
- f. 8.3 After completing failed fuel calculations, compare data with the guide-lines given in Enclosure 10.8 to determine appropriate Station Emergency
( ' Action Level (EAL). Appropriate EAL and supporting data should be recorded in comments section of Enclosures 10.4 - 10.7 and delivered in accordance utch S.1.1 and 8.1.2. 9.0 References 9.1 Letter of 4/14/82 from R. Michael Glover to C. C. Jennings,
Subject:
" Failed Fuel Estimating" ,
j, 9.2 ONS Emergency Plan, Section-II.D 9.3 MNS Administrative Procedure AP/0/A/5500/33 l 9.4 ONS FSAR l 10.0 Enclosures lj 10.1 De sity Correction Factor, (X) i! l' 10.2 Core I-131 Inventory Correction Factor, (Y) 10.3 Examples 10.4 Failed Fuel Calculations - Case I a s,, .[ 10.5 Failed Fuel Calculations - Case II s . l. l
a E 9.. - - . 7 , 10.6 Failed Fuel Calculations - Case III , 10.7 Failed Fuel Calculations - Case IV 10.8 F.mergency Action Levels 909 & h4 l
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~fS ENCLOSURE 10.1 DENSITY CORRECTION FACTOR (X)
-Find the appropriate RC System temperature at the time of accident. Find the approximate temperature at which the RC samples are taken. The intersection .
of both numbers is the density correction factor, I. NOTE: Normal RC System sample temperature is approximately 90*F. Use this temperature if.no other information is available. RCS Sample Temperature *F 80 90 100 100 .996 .998 1 (- I ,e
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s . 150 .983 .985 .987 200 .966 .968 .970 250 .945 .947 .949 300 .921 .923 .924 RCS Temperature 350 .894 .895 .897 F 400 .862 .864 .865 450 .827 .828 .830 500 .787 .788 .790 550 .739 .740 .741 4
.728 560 .729 .731
. l 570 .717 .718 .719 580 .706 .708 .708 ! I w 590 .693 .694 .695 l 3 v' 600 .680 .681 .683
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Page 1 of 1 ' ENCLOSURE 10.2 . CORE I-131 INVENTORY CORRECTION FACTOR (Y) 10.2.1 Situation 1: Use the following equation to calculate (Y) at power operation (except 0%) where the power level has not changed more than i 10% within the last 22 days. Eq. 10.2.1.1 Y = 100 pg Where: Y = the Core I-131 inventory correction factor. PL = the power level, in *., at the suspected time of fuel failure. 10.2.2 Situation 2: Use the following equatica to calculate (Y) at times other than covered . by Situation 1 above. 100 Eq. 10.2.2.1 Y= (PLg )(e"^') + (PL )(1-e-AE) , g
. Where: Y = the core I-131 inventory correction factor.
PLg = the initial power level before the power change. PL the final power level before/at the suspected time g = of fusi failure , A. = the decay constant for I-131, 0.084 day 1 4 { t =tt+t2 tt = the median time, in days, to make the power change from PLg to PL g. . [ t2 = the time, in days, after the final power level (PL,) is reached that the fuel failure is suspected to have 'Jf - occurred. 3 d _v'
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s ENCLOSURE 10.3 l EXAMPLES j Problem 1
. . a. Power level has been decreased from 85% to 50%.
- b. This power change took four hours and occurred bet.cen 1200 and 1600. Tgyg at 50%.is 570*F.
- c. At 1800 a loose part monitor alarm goes off indicating a loose object in the core. The reactor is not tripped.
- d. A Chemistry team is immediately dispatched to take a sample RC System as failed fuel is suspected.
- e. Chemistry sample indicates I-131 concentration is 10.0 pCi/ml.
Part 1. Determine the best estimate of the number of failed pins. Part 2. Determine tne best estimate of percent failed fuel. Solution This is Case II, Section 4.0 4 Use equation 4.2.1.2 for Part 1 Use equation 4.2.1.5 for Part 2 Measured I-131 concentration pCi/ml (X)(Y) = Number of failed pins Part 1. , 16.5 x 10 , pCi/ml
< Determine X: Enclosure 10.1 T 4yg is 570'E at 50%.
- Assume RCS Sample Temperature is 90*F Therefore, X = .713 Determine Y: Enclosure 10.2 1
A7 = .0864 day t = (4) + (2) = 4 hours 2 Remember, t is the median time to make a power change plus the difference between the time when the damage is suspected and the tice the new power level is reached. 1 day - Convert t to days t = 4 hours x 24 hrs. ** # #I' 4
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i ENCLOS1,PI 10.3 EXAMPLES 100 (85)e
- (.08o4 day ') (.107 day) + (50) 1-e - ( .08% day *) (.107 day; 100 Y = (85)(.9857) + (50)(.0143) = 1.183 Part 1. 10 uCi/ml 16.5 x 10 ,pCi/ml (.718) (1.183) = 51.5 3 52 failed pins
- Answer 1
Part 2. .!easured I-131 Concentration uCi/mi 83.7 pC1/ml (X)(Y) = . failed tuel 10 uCi/ml
- 83. 7 pC1/ml (.718) (1.133) = 0.1*.' failed fuel Answer f
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Page 3 of 8 , O ENCI.05URE 10.3 EXAFJI.ES Problem 2
- a. The reactor has just tripped instantly from 100". power due to a mal-functioning instrument. There were no unusual conditions prior to the trip.
- b. Tgyg is now 557*F at 0*. power.,
- c. The operator, while having no reason to suspect failed fuel, is curious about the amount of failed fuel present now following the trip.
- d. A Chemistry team is sent to take an RC sample 12 hours after the trip.
- e. The Chemistry sample gives an I-131 concentration of 2.0 x 10~2 pCi/ml.
(A typical value for a normally operating planc. See Note under Case I, Section 3.0)
- f. Chemistry personnel also indicate that RC sample temperature is 100*F.
Part 1. Determine the maximum expected number of failed fuel pins. Part 2. Determine the maximum expected percent. failed fuel in the core. Solution This is Case I, Section 3.0 Use equation 3.2.1.1 for Part 1 Use equation 3.2.1.3 for Part 2 p Measured I-131 concentration uCi/ml (X)(Y) = Number of failed pins 3.5 x 10 a pCi/ml Determine X: Enclosure 10.1 K:: Temperature is 557*F at 0*. RC sample temperature is 100*F Therefore, X 3 .732 4 4 N
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Page i of 3 l l ENCLOSURE 10.3 -
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EXAMPLES Determine Y: Enclosure 10.2 1 dav Situation 2: t = 12 hours x = .5 davs 24 hrs. 100 (100) e (.0860 (.5) + (0) 1-e -( .0864) (.5) 4 Y = 1.044 NOTE: If t = 0 or a sample was taken immediately, Y = 1.0. 1 2 Part 1. '" 0 x 10 uCi/ml (.732)(1.044) = 4.4 ' 3.5 x 10~3 pCi/ml
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or ~ 4 to 5 failed pins Answer
-i Part 2. Measured I-131 Concentration uCi/ml (I)(Y) *- , ,alled fuel .
1.8 pCi/ml - 1i 9
0-x 10 ~2
_- 1.3 pCi/mi uCi/ml (.732) (1.044) = .0085 ". failed fuel i t i The above numbers are indicative of normal operation.
.1 .l Answer 4
i NOTE: I-131 spiking may be a problem here. See Section 2.5.
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[ - ENCLOSURE'10.3 EXAMPLES Problem 3
- a. Power level has been between 50% and 65% for the last 30 days and is pre-sently at 60% at 1800.
- b. T is 3 575*F at 60% power.
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- c. It is desired to see if any significant failed fuel exists in the core even though no abnormal occurrences have taken place.
- d. At 2200 the same day, a Chemistry sample is taken of the RC system.
- e. The Chemistry sample indicates I-131 concentration is 3.9 x 10~2 pCi/ml.
Part 1. Determine the best estimate of the number of failed pins. Part 2. Determine the best estimate of the % failed fuel. . Solution m. This is Case I, Section 3.0 , Use , equation 3.2.1.1 for Part 1 Use eque. tion 3.2.1.3 for Part 2 p, g, Measured I-131 concentration uCi/ml (X)(Y) = Number of failed pins 3.5 x 10 a pCi/ml Determine X: Enclosure'10.1 T is 575*F at 60% power A$VGsure RCS sample temp. of 90*F i Therefore, X = .713 Determine Y: Enclosure 10.2 Situation 1 Y = 100 9
= 1.67 i ?
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ENCLOSURE 10.3 ' EXAMPLES Part 1. 3.9 x 102 uC1/ml (.713)(1.67) = 13.27 3.3 x 10
- pCi/ml 3 14 failed pins Answer d
-m 3a r .,. a. Measured I-131 Concentration uCi/ml (X)(Y) = . talled :.uel j; ;)
1.8 Ci/ml ..i 2 3.9 x 10 Answer 1.3 pCi/ml uCi/ml (.713)(1.67) = .026". failed fuel The above numbers are acceptable for a normally operating plant. 1 4 J f s
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l Pt.ga 7 of 8 : l x~ ENCLOSURE 10.3 EXAMPLES j Problem a
- a. The unit has been at 97". power for a month when a depressurization of the RC system occurs.
- b. The reactor trips.
- c. Heavy vibration is observed in the RC pumps.
- d. Thermocouple temperatures over 1000*F are indicated in the core.
High Pressure Injection was delayed and it is suspected the core was un-e. covered between 30 and 60 minutes before sufficient reactor vessel water level was regained.
- f. The incere instrumentation system is still operable.
- g. The RC sample indicates an I-131 concentration of 3800 pCi/ml.
- h. A Chemistry sample is taken immediately (within the hour) after the trip.
Part 1. Determine the maximum expected number of failed pins. Part 2. Determine the maximum expected *. of failed fuel. Solution This is Case III, Section 5.0 Use equation 5.2.1.1 for Part 1 Use equation 5.2.1.4 for Part 2 Determine X: Enclosure 10.1 g at 0% power u H M RCTemp.T[g Assume samp e temperature of 90*F Therefore, X E .730 Determine T: Enclosure 10.2 Y=103=1.03 9s
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' ENCLOSURE 10.3 EXXIPLES .;'
Part 1. , 00 uCi/ml . (,'730)(1.03) = 1190.5
. 4 pCi/ml 4 3 1191 number failed pins ~, max. expected Answer 4
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ENCLOSURE 10.4 FAIIID FUEL CALCUI.ATIONS CASE I UNIT DATE/ TIME BY X= Y= I-131 pCi/ml Maximum Number of Failed Fuel Pins (Best Estimate): 3.2 c-3
.- ( )( )=
Minimum Number of Failed Fuel Pins:
-. 9 c-3 ( )( ) =
Maximum *. Failed Fuel (Best Estimate): p -
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1,3 ( )( )_ - Minimum ". Failed Fuel: 2.5 ( )( ) *
- COMMENTS:
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ENCLOSURE 10.5
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FAILED FUEL CALCULATIONS CASE II UNIT DATE/ TIME BY X= Y= I-131 pCi/ml Maximum Number of Failed Fuel Pins: s.s r -2 ( ) () = Best Estimate of Failed fuel Pins:
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( ) ( ) 1.o5 E-1 - Minimum Number of Failed Fuel Pins: _
, - . ( ) ( ) = . .., :-t Maximum ?. Failed Fuel:
( ) ( ) = 7. g,9 1 4 .l Best Estimate Failed Fuel: -; s ~ .{ j : s., o ( ) ( )' = % i~
- i. Minimum ?. Failed Fuel:
I ( ) ( ) = %
-; 139.s-j COMME'.iTS :
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** ' Paga 1 of 1 A ENCLOSUPI 10.6 FAILED FUEL CALCULATIONS CASE III UNIT DATE/ TIME BY X= Y= I-131 pCi/ml Maximum Number of Failed Fuel Pins:
( ) ( ) =
.-.2 Best Estimate of Failed Fuel Pins:
( ) ( -) . 2.9
.. h Minimum Number of Failed Fuel Pins: -
( ;; . ( ) ( ) = . 3.., Maximum ". Failed Fuel: ( ) ( )
- 1255 Best Estimate Failed Fue::
- ( ) ( ) = %
1532
- Minimum ". Failed Fuel:
= "
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ENCLOSURE 10.7 \
?
FAILED FUEL CALCULATIONS CASE IV UNIT DATE/ TIME BY
, g. ; .. . . .
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--7:= I-131 pCi/ml Best Estimate of' Failed Fuel Pins:
( ) ( )_ -- s.a Best Estimate of *. Failed Fuel: ( ) ( )
- 2790 ".
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ENCLOS1. T E 10.8 EMERGENCY ACTION LEVELS (EAL)
- Following reactor coolant sampling and completion of the failed' fuel calculations, compare I-131 concentrations or percent failed fuel with the following guide-lines to determine the appropriate Station Emergency Action Level. Appropriate action level should be highest applicable EAL.
1.0 Unusual Event-1.1 Initial indicator is high reactor coolant activity;- total activity > 224 . 5 1.2 Suspected damage mechanism is mechanical clad failure or flow induced failure. 1.2.1 I-131 concentration in reactor coolant in range of 70 pCi/mi to 350 pCi/ml.
; 2.0 Alert
(. - 2.1 Initial indic'ator is very high reactor coo-lant activity; total activity >> 224 . 5 2.2 Suspected damage mechanism is mechanical clad failure or flow induced failure. 2.2.1 Total failed fuel exceeds 5%, but less than 25%. 2.2.2 I-131 concentration between 350 and 1770 pCi/ml. l 3.0 Site Area Emergency 3.1 Initially suspected degraded core with possible loss'of coolable geometrf. 3.2 Substantial mechanical clad failure or flow induced failure with total failed fuel > 25%. 3.2.1 I-131 concentration from 1770 to 7000 pCi/ml (7000 pCi/ml equivalent to 100% failure under this damage mechanism). 3.3 Substantial damage to clad from severe fuel over temperature (fuel clad oxidation evident from excess hydrogen in containment or reactor coolant, no fuel melt suspected). 3.3.1 I-131 coccentration from 1300 to 13,000 Ci/ml (1". to 10%
.c/ fuel failure under this damage mechanism).
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u w_. _ Page 2 of 2 o s s 3.4 Substantial damage to fuel and clad from fuel melt conditions (incore ' thermocouple > 2300*F for period of time; fuel temperature > 5000 F). 3.4.1 I-131 concentration from 1180 to 11,800 pCi/ml (0.5% to 5% failed fuel under this damage mechanism). 4.0 General Emergency , 4.1 Initially loss of cladding and primary coolant boundary with potential loss of containment. 4.2 Substantial damage to clad from severe fuel overtemperature (fuel clad I oxidation evident from excess hydrogen in containment or reactor coolant, no fuel melt suspected). 4.2.1 I-131 concentration > 13,000 pCi/ml (> 10% fuel failure under this mechanism). 4 __ 4.3 Substantial damage to fuel and clad from fuel melt (severe accident where core is uncovered for a period of time and incore temperature j , , , ,
> 2300*F for long period; fuel melt suspected by fuel temperature ,
> 5000*F and verified by inoperable incore instrumentation.
4.3.1 I-131 concentration > 11,800 pCi/mi, for this damage mechanism failed fuel > 5%. -N
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, PROCEDURE PREPARATION Change (s) 2 to PROCESS RECORD N/A Incorporated (2) STATION: Oconee (3) PROCEDURE TITLE: Projection of.0ffsite Dose From Releases Other Than Threugh The Unic Vent (4) PREPARED BY: brkf\ _
DATE: \3 -l b~ k s (5) REVIEWED 3Y: d.T ,9 V /btbao.l.m DATE: I 2. - / 7 - B 2_ Cross-Disciplinary Review By: N/R: (6) TEMPORARY APPROVAL (17 NECESSARY): (- By: (SRO) Date: V - - - - . Sy- Date: (7) APPROVED SY: 4 Date: S b i (8) MISCEIL WEQUS: . Reviewed / Approved 3y: Date: . Reviewed / Approved By: Date: t a f
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HP/0/3/1009/14 DUKE POWER COMPANY OCONEE NUCLEAR STATION PROJECTION OF OFF-SITE DOSE FROM REI. EASES OTHER THAN THROUGH THE UNIT VENT 1.0 Purpose This procedure should be used for projecting dose commitment from a noble gas or iodine release, other than a unit vent release, during an emergency. 2.0 References
; 2.1 Reg Guide 1.109 2.2 Reg Guide 1.4 2.3 HP/0/3/1009/13, Procedure for Implementation and Verification for the Availability of a Backup Source of Meteorological Data.
s 3.0 Limits and Precautions -
- - U}
3.1 It is assuded that a small percentage of the total containment inventory of iodine is released. The' iodine whole body dose from a release is very small compared to the iodine thyroid dose. Thus, iodine whole body dose is not c.onsidered tiere. 3.2 This procedure applies to releases made from Oconee Nuclear Station only. Many of the values contained in this procedure are site specific.
, 3.3 This procedure considers all releases to be ground level releases.
) 3.4 Enclosure 5.6 should be done in conjuction with the Field Monitoring Coordinator.
3.5 Meteorology data needed to calculate offsite dose should be obtained j as required by Enclosure 5.1. Data not available from the primary l* source should be obtained from the backup source. The order of preference for each data point is listed each place meteorolo'gical
'l data is required. All meteorology dsta ootained from the tower or 1 river must be a 15 minute average. National Weather Service (NWS)
,j data is a standard observation and is not a 15 minute average. i
! 3.5.1 Every 15 minutes the wind direction and wind speed will '! be rechecked in accordance with Enclosure 5.1 to ensure '
additional sectors have not been affected. Once a sector I
._ _ _ _ _ . _ . _ _ ., a ,_.._ . _ , .. ,. _._.
~
2 (. has been determined to be affected, it cannot be removed from the list of affected sectors. 3.5.2 The following are conversion formulas for the meteorological data obtained from the National Weather Service: sph -- 1.15 (knots)
'F = (9/5 *C) + 32 4.0 Procedure 4.1 Acquire the following information and record on Enclosure 5.1.
NOTE: The sources of meteorological data are listed in order of preference on Enclosure 5.1. 4.1.1 Reactor Unit, date and time of reactor trip. 4.1.2 Wind speed (mph). 4.1.3 - Wind direction in degrees from North (North = 0').
=4.1.4 Temperature gradient (ST*F).
4.1.5 Radiation Monitor reading (R/hr) calculated per Enclo-sure 5.2. t 4.1.6 Present date and time. 4.1.7 Time meteorology data determined. 4.2 Determine the Containment Bui? ding leakage rate (LR) and record it on Enclosure 5.1. 4.2.1 LR is the total leak rate for the containment which is: I a) a "best guess" assumption, b) assumed to be the design leak rate (see note below), or c) the measured leak rate where suitable means are available. Record the leak rate onto Enclosure 5.1. NOTE: The design leakage rate (LRDLR) is determined by, LR n a ament ume - es gn es nstant DLR = (5.38 x 10 10 ml) ( 0.0025 irz day )
= - ,
, i
- l* hr
= 5.6 x 108 ml/hr
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4.3 Determine the X/Q values for each point of interest downwind. . If no points have been requested, use the 1, 2, 5 and 10 mile values. 4.3.1 Locate the relative two-hour downwind concentration value (CH) for each point from Enclosure 5.3 and record onto Enclosure 5.1. 4.3.2 Convert these values to X/Q by, gjq , CH (MPH-Sec/m3 ) Wind Speed (MPH) Record X/Q values onto Enclosure 5.1. 4.4. Determine the potential whole body dose from submersion in a cloud of noble gas. 4.4.1 Calculate the whole body two (2) hour dose commitment, 9* M' D ' WB NG Where, DWB = Whole body two (2) hour dose commitment [' DR 3 = Monitor dose rate (see Encl. ,5.2) DC = Average Decay constant for noble gases = pCi MeV hr 2 1.5 448E-2 ml d R (see Encl. 5.4) LR = containment leakage rate in ml/hr-X/Q = dispersion factor in sec/m 3 _ (3.74d/sec uci)(1.6E-6erts/MeV) _ NG 2 (100 ergs / g-rad)(1.2E-3g/ cm4)(IE6cm ef m") d m3 rad ' ~ 2.5E ,/ l sec pCi MeV-l l Record results on Enclosure 5.1 L6
.: 4.5 Determine the potential thyroid dose from uptake of radiciodine.
l' 4.5.1 Locate the time plus one (1) hour after trip on Enclo-sure 5.5 and record the corresponding Decay Constant l i on Enclosure 5.1 l l
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. . . . '. 4 4.5.2 Calculate a child's thyroid two (2) hour dose commitment using time plus one (1) hour, DRT = D g DC LR X/Q UI Where, DR = thyroid two (2) hour dose commitment T
DR 3 = monitor dose rate (see Encl. 5.2) pCi mrem hr2 DC = Decay Constant in f r time plus al pCi R one (1) hour (see Enclosure 5.5) LR = Leak rate in ml/hr X/Q = dispersion in sec/m 3 UI = breathing rate for child ' 3 # ~"** (1.17E-Am /sec)(1E3 pCi-mrem )= 1.17E-1
^-
h Record results on Enclosure 5.1
/
( , . 4.6 Calculate an adult's thyroid dose by dividing the child's dose by two (2). Report results of all calculations on Enclosure 5.7. 4.7 Determine the potentially affected area using Enclosure 5.6. Re-cord sectors on Enclosure 5.7. . 4.3 Complete Enclosure 5.7 with.infoemation from Encl.osure 5.1 and submit it to the Offsite Radiological Coordinator or his designee. Include any comments pertinent to the evaluation of offsite hazards. 5.0 Enclosures 5.1 Projected offsite Dose Released from Containment 5.2 Survey Instrument Correlation I i 5.3 Table of Two Hour Relative Concentration Factors 5.4 Table of Noble Decay Constant (DC) 5.5 Table of Iodine and Noble Decay Constant (DC) 5.6 Evaluation of Plume Location 5.7 Dose Assessment Report _/ s .
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, Page 1 of a ENCLOSL*RE 5.1 HP/0/3/1009/14 Proposed PROJECTED OFFSITE DOSE RELEASED FRCM CONTAINFJ.NT Date/ Time Now /
i Uni's Date/ Time o'f Incident / METEOROI.0GICAL DATA (All data is 15 min. average, excapt NWS) A. Daytime - 1000-1600 hrs. (Circle source of data for each point)
- 15 min. period ending time
- Wind Direction (degrees)
Sources 1) Tower (T)
- 2) River (R) .
- 3) NWS (N)
T T T T
.. R R R R N ; N ; N : N , 7%
. n (*y) "~
~
Sources 1) Tower (T)
- 2) Assume (A) -0.4*?
T A 1
- Wind Speed (mph)
Sources 1) Tower (T) -
- 2) River (R)
- 3) NWS *
(N) l T T T T 4 R
- R- R R t
N ; N ; N ; N
- 3. Nightime - 1600-1000 hrs. (Circle source of data for each point)
['
- 15 min. period ending time 1
e' . - t ; River Wind Direction (If river wind direction is unavailable assume
.0* - 210*)
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. Page 2 of J.
,m ENCI.CSURE 5.1 HP/0/B/1009/14 Proposed PROJECTED OFTSITE DOSE REI. EASED FROM CONTAINMENT
- 1. River Wind Direction is between 210* - 70*
- Wind Direction (degrees)
Sources 1) Tower (T)
- 2) Assume (A) between 0 - 360*
T T T T A ; A ; A ; A
- 2 (*T)
Sources 1) Tower (T)
- 2) Assume (A) +1.0*T T
A
- Wind Speed (mph)
Sources 1) Tower (T)
- 2) Assume (A) - 1 mph _
T T T T A ; A ; A ; A
- 2. River wind direction is between 70* - 210* (Sources below are based
, on experiment)
- Wind Direction (degrees) .
Source 1) 3etween 0* - 360* (I) E ; E ; E ; E
- E (*T)
Source 1) +1.0*Y (E) . I i
- Wind Speed (mph) i Source 1) 1 mph (E)
E ; E ; E ; I BUII. DING DOSE RATE
- 1) Deter: sine DR, by completing eit.her step a or b.
-> A) Containment high range monitor - RIA 4 DRa = R/hr
- 3) Survey instrwnent 1 a) reading R/hr b) correlacion *ralue (Enclosure 5.2) c) CRm = R;hr C) Data / time of sample /
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l j Page 3 of A ENCI05URE 5.1 HP/0/B/1009/14 Proposed PROJEL...:,D OFFSITE DOSE RELEASED FROM CONTAINMENT DOSE CALCULATION
- 1) IR al/hr (Design basis LR = 5.6E6 al/hr] .
- 2) G@ mi.. = , X/Q = sec/m3 G@ mi.. = , X/Q = sec/m3 G@ mi.. = , X/Q = sec/m3 G@ mi = _ _, X/Q = sec/m 3 A. Wole Body 2 hr. dose projection frere sable gasest i
by D,4 = D 1.5448E-2 LR X/Q 2.5E-7,
*4 Miles out 1
, .]
~
- 3. Thyroid 2 hr. dose projection from iodine:
.- - DC (for e + 1 hr.) by D L = D DC LR X/Q - (1.17E-1), 1
?
l-DR., 2 hr Dose Commitment Miles Out ., j l
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- Page a of .
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- 1 ENCLOSURE 3.1 HP/0/3/1009/14 Proposed PROJECTED OFFSITE COSE REIS.ASED FRCM CONTA12RTC DEFINITIONS Dg - whole body 2 hour dose commitment DR - thyroid 2 he dose commitment from iodina T
LR - containment leakage este g - Design leak rate (5.6 E6ml/hr) X/Q " Chi over Q" is downwind concentration correction factor CH - 2 hr. relative downwind concentration - MPH (X/Q MPH) DC - Decay constant
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- Page 1 of 2 ENCI.05URE 5.2 HP/0/3/1009/14 Proposed SURVEY INSTRL?SNT CORREI.ATION Presently, Ocones does not have a high range rnonitor installed to evaluate the conditions of an airbocne release inside the containment. Therefore, the l
following equation shotuld be used to detemine the dose rate: I l DR . = DR survey Correlation Value monitor where: The correlacion value is deter:nised by using the graph on the following page. DR' is taken free the 6th floor inside the Auxiliary Building, survey 1 foot from the re: actor wall and 4 feet from -he floor.
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Page 1 of 5 Mw ENCLOSURE 5.6 EP/0/B/1009/14 Proposed EVALUATION OF PLUME LCCATICN
- 1. Acquire the following information from Enclosure 5.1 and record en Enclosure 5.7.
a) Meteorological Data - identify for each point whether data is assumed (A), exper ment (Z), or measured (T, R or N). b) Thyroid and whole body dose
- 2. Protective action guides submitted to the Offsite Radiological Coordi-
- sator are to be made based on the calculated dose on Enclosure 5.1 and the following information.
, A) For doses: i
> 5 Rem Whole 3ody or,
> 25 Rem Thyroid Recommend Evacuation of Population La Affected Area.
i
- 3) For doses:
4 1-5 Rem Whole 3ody or, 4 5-15 Rem Thyroid Recommend evacuatjec of children and pregnant women, and sheltering of remainder of personnel in the affectec area. C) For doses:
< 1 Rem Whole 3ody or, i
j 1
< 5 Rem Thyroid Recommend no action.
- 3. To determine sectors affected, complete one of the options ander A or 3 asing meterological data from Enclosure 5.1. Record the sectors affected an Inclosure 5.7.
A. Daytime (1000-1600 hrs.)
- i) Wind speed > 5 mph for tower or river wind direct on, use Table 1.
l e, - - -, e s .
,,mc-,- ---- ,- v--- - - -
. Page 2 of 5 F.NCLOSURE 5.6 HP/0/3/1009/14 Preposed EVALUATION OF PLI.F LOCATION i.
- 2) Wind speed 3, 5 mph fo-. .WS wind direction, use Table 2.
- 3) Wind speed < 5 alph for tower or river wind direction, assume sector: A1, 31, C1, D1, E1, and F1 are affected. Then use Table 1 to deter:nine additional sectors affected.
- 4. Wind speed < 5 mph for NVS wind direction, assume all sectors are affected (Al through F1, A2 througn F2).
- 3. Nightime (1600 - 1000 hrs.)
(If river wind direction is unavailabla, assume 70* - 210*) .
- 1) If river wind directics is between 210' - 70* , use Option A (Daytime).
- 2) If river wind direction is between 70* - 210*, assume all sectors affected (Al through F1, A2 through F2) . AD I j
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5 ElCLOSURE 5.6 EP/0/3/1009/14 Proposed CVALUATION OF PLL*ME LOCATION TABLE 1
'Jind Direction Sectors Affected 14*-27' C1, C2, D1, D2, El, E2 27*-42' C1, D1, D2, El, E2 42*-66* D1, D2, El, E2 668-85* DI, D2, El, Z2, F2 35*-104* D1, 02, II, E2, F1, F2 10'*-129' El, E2, F1, F2 129*-156* A1, A2, Ei, E2, F1, F2 I i
)
1
- 156*-175* 51,A2,Ei,F1,F2 1
175*-131* A1, A2, F1, F2 131*-219' A1, A2, 31, 32, ?!, F2 1 - 219*-255" A1, A2, 31, 32 255*-271* A1, A2, 31, S2, C1, C2 271*-297* 31, 32, C1, C2 297*-312' 31, 32, C1, C2, D2 312*-345' 31, 32, C1, C2, 21. 32 3 t.5 * - 14
- C1, C2, D1, D2
* ' - - * * *m ag.. . - . . . . - , . . , ,,
, _ . _ _ _ y__ .,
~ '
I .-
= , ;
a Page ; of 5 m'.i ENC 20SURE 5.6 HP/0/3/1009/14 Proposed EVALUATION OF PL12fE LOCATION TABLE 2 Wind Direction Sectors Affected 1*-39' 31, 32. C1, C2, El, E2, FI, F2 A1 through F1, A2 nrough F2 4 3 39*-75* 75*-91* A1, A2, C1, C2, D1, D2, El, E2, F1, F2 91*-117' Al through FI, A2 through F2 117*-132* A1, A2, 31, 32, C1, DI, D2, El, E2, Fl, F2 132*-165* A1, A2, 31, 32,- D1, D2, Ei, Z2, 71, F2
- s 165*-194* Al through F1, A2 through F2
) 4 194*-207* A1, A2, 31, 32, C1, C2, El, E2, F1, F2 -g j )
! 207*-222* A1, A2, 31, 32, C1, C2, D2, Ei, E2, F1, F2 ,-
4 j f 222*-2a6* Al through F1, A2 through F2 246*-265* A1, A2, 31, 30, C1, C2, D1, D2, El, II, F2 4 2658-234' Al,A2,31,32,C1,C2,,DI,'D5,F1,F2 234**309* Al through F1, A2 through F2 i . 309*+3368 A1, A2, 31, 32, C1, C2, 01, D2, E1, 22 J 336*-355* A1, A2, 31, 32. C1, C2, D1, D2, Ei, E2, F2 355*-1* A1 through F1, A2 througn 72 l
=
d i g E I t
'l .
W -- p
. Pago 5 of 5 ENCLOSURE 5.6 HP/0/B/1009/14 Proposed l
EVALUATION OF PLUE LOCATION 4 Deter: sine Stability Class by completing step (a) below and record on Enclosure 5.7. a) .1T Stabilitr Class
-3 to-1.3 A
-1.2 to -1.0 C
. -0.9 to -0.4 D
-0.3 to +0.9 E i +1.0 to +8 F
.f 4
~
i l e I I I f e 4
, i
._ . .. . - n. . - . . . . . , - - - - - . - . . +'. s - -
\
', - Page 1 o f *.
i 1 DiCI.0SURE 5.7 a i COSE ASSESSMENT REPORT i,
; EP/0/3/1009/14 Proposed f
DATE: l; TIME: 00SE ASSESSOR: ? . WUD DIRECTION SOURCE ) WIND SPEED MPH SCURCE l i r *F/120 ft SCURCE j STABII.I""? C'AS > ~
'3?ROID/ADUI.T "'HYROID/ CHID WROLE 30DY CCMME'ITS
; DISTANCE i .5 mi. .a m j
~
, 1 mi.
i . r 2 si. . 3 11 ._ , , i :. m . }: 5 mi. 5 "li . i ti . 3 ni . 7 n. 10 mi. l' l l Sectors Affected i i l
)
*s t
i e
- -. v 4 6 =e* WS - Mpe m. m s,._..m e w,e w _. +.a..e. en ,,%,4, ,_ , , , . , , , , , , , , , , , _ , , , , , ,
O r 7 0h f f 'a -:- l
' a< %-l a L e a u
@'w
= )
) c.ijuil Jnt t:n l je ' '
im CONTROL COPY r = s'o-too2-t ggginT!M ONU DUKE POWER COMPANY (1) ID No: HP/0/3/1009/11 PROCEDURE PREPARATION Change (s) 3 to.
- PROCESS RECORD N/A Incorporated (2) STATION: Oconee .
(3) PROCEDURE TITLE: Projection of Offsite Dose from the Uncentrolled Re-lease of Radioactive Materials Through a Unit Vent (4) PREPARED 3Y: bhAab b b DATE: N '\b- D
~ (5) REVILTED 3Y: fT Vge.ua /DL6 DATE: /2 - /5- R 7 -
Cress-Disciplinary Review By: N/R: _ (6) TEf?ORARY APPROVAL (IF NECESSARY): 3y: (SRO) Date: i 3y: - .- Date: (7) APPRCVED 3Y: l C Date: ll (3) MISCELLUTEOUS : . Reviewed / Approved By: Date: Reviewed / Approved By: Date:, 1 i
- 6
--w.
. . _~
4 t < 1 HP/0/3/1009/11 E DUKE POWER COMPANY OCONEE NUCI. EAR STATION PROJECTION OF OFFSITE DOSE FROM THE UNCONTROI.I.ED REI. EASE OF RADIOACTIVE MATERIAI.S THROUGH A UNIT VE.VI l 1.0 Purnose This procedure describes the method for calculating the potential offsite dose following an uncontrolled release of radioactive materials through the unit vent. 2.0 References 2.1 EPA-520/1-75-001, Manual of Protective Action Guides and Protective Actions for Nuclear Incidents 2.2 PT/0/A/230/01, Radiation Monitor Check - 3.0 Limits and Precautions . 3.1 Use actual sample data when possible. Radiation monitor readings are susceptible to several sources of error. When radiation monitor
- l. readings are used for downwind concentrations, note this in the report of offsite dose assessment. .
l 3.2 Environmental data should be collected and analyzed to verify these calculations. This procedure considers all releases to be ground level releases. 3.3 Use the computer code ODCAR2 when possible. It is faster, applies a more accurate conversion factor when changing count rate to concentra-tion, and it generates a more concise report. CECAR2 integrates dose from the initial release and makes two-hour projections from the time of latest data entry.
; 3.4 Use the manual calculations for times when ODCAR2 is unavailable and
, if more than oae unit is affected.
i 3 . '5 This procedure applies to releases made from Oconee Nuclear Station only. Many of the values contained in this procedure are site specific. 3.6 Enclosure 5.7 should be done in conjenetion with the Field Monitor ng Coordinator. s i e s/ a i* - -
--' . e w- - - -g -. __,.7
-+
- 2 l
3.7 Vent releases can occur through more than one unit at a time. Check unit vent monitors-on all 3 units during a vent release. 3.3 When using this procedure in conjunction with
- dP/0/3/1009/10, "Proce-dure for Quantifying Gaseous Releases through Steam Relief Valves and Post-Accident Conditions", ensure that the correct time is used in Steps 4.4.3 and 4.4.4 3.9 Meteorology data needed to calculate offsite dose should be obtained as required by Enclosure 5.1. Data not available from the primary source should be obtained from the back up vource. The order of preference for each data poznt is listed each place meteorological data is required. 'All meteorology data obtained from the tower or river must be a 15 minute average. National Weather Service (NWS) data is a standard observation and is not a 15 minute average.
k
. 3.9.1 Every 15 minutes the wind direction and wind speed will be rechecked in accordance with Enclosure 5.1 to ensure additional sectors have not been affected. Once a sector has been determined to be affected it es.nnot be removed .
from the list of affected sectors.
' 3.2 The following are c nversion formulas for the meterological data obtained from the National Weather Service.
A
/
mph = 1.15 (Knots)
}
. 'E = (9/5 *C) + 32 .
4.0 Procedure d 4.1 Obtain the following meteorological information f rom one of the designated sources and record it on Enclosure 5.1. The sources of data are listed in order of preference on Enclosure 5.1. I 4.1.1 Time of reactor trip. 4.1.2 Wind speed in MPH. 4 4.1.3 Direction frem'which the wind is blowing in degrees from North. l 4.1.4 Temperature gradient (2T*F).
! 4.1.5 Time meteorology data taken.
t
; 4.2 Obtain results of vent sample analysis and vent flow rate in cfm and
. record on Enclosure 5.1 for each affected unit. l l 4.2.1 Date/t ae of sample. a.2.2 3ross gas concentration in pCi/ml.
.m., , m. . . . - , , . - , - . . . . . -
. - - - -,.. . .m ,
2 m.
'T 4.2.3 -Iodine equivalent concentration (or data for calculation).
4.2.4 Gamma E bar value in 02v/ dis (or data for calculation). NOTE: Actual sample results may not be available due to adverse plant conditions. If sample results are not available, obtain vent radiation monitor readings from the gas and iodine monitors on the unit involved. Record the date/ time of data collection and the monitor readings on Enclosure 5.1 Calculate discharge concentration as shawn on Enclosure 5.1. NOTE: The iodine monitor response is time dependent. Allow sufficient time to elapse between readings in order to obtain adequate change in monitor response. , 4.3 Project the impact of the release on the downwind population by using the computer code CDCAR2. . NOTE: In the event that CDCAR2 cannot be used, manually calculate the potential dose by the methods outlined in Steps 4.4 thru 4.6. NOTE: ODCAR will only calculate for one unit at a time.
]
4.3.1 Using Enclosures 5.1 and 5.2, run ODCAR2 for the unit on which the highest activity is found and obtain a printout of the downwind dose assessment. Then manually calculate potential dose (Step 4.4) from any other affe,cted unit. Add these results onto che printout from CDCAR. 4.3.2 C mplete Steps 4.5 thru 4.6 of this peccedure. 4.4 Project the impact of the release on the downwind population by using tne manual calculations outlined below. i
- 4.4.1 Cetermine the X/Q values for each point of iaterest downwind.
l. NOTE: If no points have been requested, use the 1, 2, 5 and 10 mile values. j 4.4.1.1 Locate the relative two hour concentration value j (CH) for each point from Enclosure 5.3 and record onto Enclosure 5.4 , i
.4.1.2 Convert these values to X/Q b/,
l. l ; ! . 3 i X/Q = ~CH(MPH-Sec/M 4ind Speed (MPH) 1 i t i
}.
1
- 4- . -
e , 3 l l Record results on Enclosure 5.4. 4.4.2 Calculate the downwind concentrations for gas and x, dine at 1, 2, 5 and 10 mile points by completing Steps 4.4.2.1 and 4.4.2.2. 4
= Unit 1 (Coney Fy) + Unit 2 (Coney 4.4.2.1 ConcT Fy) + Unit 3 (Coney F) y where, ConcT = total concentration in unit vents (pCi/ml cfs) i Coney = vent discharge concentration (pCi/ml)
Fy = vent discharge flow rate (CFM) . 4.4.2.2 X/Q U ConcDW = ConcT DWC 1 where, 4 Conc = dennwind concentration (pCi/ml) ! DW Conc a t tal concentration in unit vents l T ! (pct /ml cfm) 3 X/Q = dispersion factor in sec/m , U = unit conversi ns derived from (2.832E-2m 3/ft 3), DWC 'j (0.017 min /sec) = 4.7E-4 Enclosure 5.4 provides work space for this calculation. . 1 , 4.4.3 Determine the potential whole body gamma dose downwind j using the gas concentrations calculated above and the equation, I"* G' D "*DW WB l where, t D = whole body gamma dose due to submersion in a WB cloud of radioactive gas (rem) 1 Ug = unit conversion derived from, i (2.22E6/ dis /pci min), (cc/1.293E-3g), i I i
.e.,. -
-,p,., -. - .,..-.,-.*-w.. , m. ., p, ,
..wew.w-_ - , 1 5 s ) 1 (60 min /hr.), (1.602E-o erg /mev), (g rem /100 ergs), di'*~# (1.1' Pt/P a
) 1/2 = 9.00E2 pCi-ar-dev Conc = downwind concentration (pCi/ml)
DW
~
Time = projected duration of exposure (hrs); use 2 hours unless calculating a release from a steam relief valve. 5 = average gasna energy per disintegration (Mev/ dis) NOTE: If 5 cannot be obtained from the sample results, the following values can be used:
- Hours from Trip 5 (Mev/ dis) 0-12 0.40 .
12-48 0.00 48-* 0.10 Record results on Et.rlosure 5.4. y 4.4.3.1 Use E,nelosure 5.5 as an alternate means of wnole . _J '
- body exposure approximation.
a.4.4 Determine the potential thyroid dose downwind using the iodine concentrations calculated above and the equation.
=U Conc,W Time Dt dY I u -
where. D THY = yhyroid dose due to uptake of radioactive
. todi;e (rem) _ , U = constants derived from a child's breaching rate
.' 7 (1.17E2 cc/sec.), I-131 dase conversion factor (4.39 E-3 mrem /pCi), and conversion of pCi to
~3 pCi(108 ), mrem to rem (10CC), and hrs. to sec (3600 sec/hr) = 1.86 E6 pei hr Conegg = downwind concentration of iodine (pci/ml)
Time a projected exposure time (hrs); use 2 hours unless calculating a release from a steam i relief valve. 1 Record results on Enclosure 5.a.
-d h
s N .
-.w..,., -. - . . ,, -- _.-
.' . :' \
.f.
4.4.4.1 Use Enclosure 5.6 as an alternate means of . thyroid. exposure approximation. i.5 Calculate an adult's thyroid dose by dividing the child's dose by two (2) . Record results of all cal;ulations on Enclosure 5.3. 4.6 Determine the potentially affected area using the method outlined in Enclosure 5.7. Record sectors on Enclosure 5.3. 4.7 Ccqelete Enclosure 5.8 with information from Enclosure 5.1 and submit it to the Offsite Radiological Coodinator or his designee. Include any comments and information pertinent to the evaluation of offsite haza rds . 4 NOTE: Maintain a file of all worksheets and printouts used in dose calculations. i 5.0 Enclosures 5.1 Vent Release Data Sheet 5.2 CDCAR2 User's Guide l Appendix A: Sample Run of ODCAR J' 5.3 Table of Two Hor Relative Concentration Factors 5.4 Manual Calculation Worksheet i 5.5 Graph of Noble Gas Concentration vs. Whole Body Dose 5.6 Graph of I-131 Concentration vs. Thyroid Dose 1 5.7 Evaluation of Plume Location , 5.3 Dose Assessment Report 4 l l i 4 l 5 4 1 e m e
/
*- Page 1 of 4 S
ENCLOSURE 5.1 HP/0/B/1009/11 VENT RELEASE I.aTA SIEET Date/ time / Unit Date/ time of Rx trip f METEOROLOGICAI., DATA (All data is 15 min average except WS) A) Daytime-1000-1600 hrs (Circle source of data for each point)
-15 min. period ending time
-wind direction (degrees)
Sources 1) Tower (T)
- 2) River (R) -
- 3) WS (N)
T T T ! R R R R N ; N ; N ; N
-iT (*F) ""
Sources 1) Tcwer (T)
- 2) Assume (A) - -0..*F T ,
A
-wind' speed (mpn)
~
Sources 1) Tower (T) .
- 2) River (R)
- 3) WS (N)
T T T T R R R R 3 ; N : N ; N _
- 3) Night. time-1600-1000 hrs (circle source of data for each point)
-15 min. period ending time
'i
- 4
}j River '4ind Direction (If river wind direction is ur.available assume 70*- i 210*) i' Using the river wind .tirection above comolete 41 or r:2 below I 1 i
~' 1 j .
s .
sS b Page 2 of 4 ENCLOSURE 5.1 ifP/0/3/1009/11 , 1 P
- 1) River wind direction is between 210*r70*
-wind direction (degrees)
Sources 1) Tower (T)
- 2) Assume (A) - between 0-3@0*
T T T T A ; A _, ; A ; A I
-2T (*F)
Sources 1) Tower (T)
- 2) Assume (A) - +1.0*F T
A ;
-.ind speed (mph)
Sources 1) Tower (T)
- 2) Assume (A) -1 mph
- l T T T T A ; A ; A : A
- 2) River wind direction is between 70*-;t108 (Sources below are based on experiment)
-wind direction (degrees)
Source 1) 3etween 0-360* (E) . E ; E ; E ; .E
-AT (*F)
- Source 1) +1.0*F (E) i g
-wind speed (mph)
Source 1) 1 mph (E) E ; E ; E ; E VENT SAMPLE ANALYSIS i 1) Total Gas pCi/ml - Unit 1 l pCi/ml - Unit 2 , pCi/mi - Unit 3
./
l s . s= =e ** __ , . _ , , e, ..e , - -e- . % - -
1 Page 3 of 4 m 1 i - } j ENCI.0SURE 3.1 HP/0/3/1009/i1 2A. - HT. -. t ~
- 2) I-131 Equiv. pCi/ml - Unit 1 I=.
I- 13 1 pCi/mi - Enit 2 pCi/ml - Unit 3
- 3) Gas 5 Mev/ dis (Gamma) - Unit 1 Mev/ dis (Gamma) - Unit 2 Mev/ dis (Gamma) - Unit 3 Samole Results Qlculated Hours from Trio / 5
, [25 g A]
g 0-12 .a - E = 12-48 . 2 A t 48 4 . 1 VENT MONITOR DATA , ], a R1A 45 (lo range) CPM - Unit . 1) CPM - Unit 2 CPM - Unit 3
- 2) RIA 16 (hi range) _ CPM - Unit 1 .
CPM - Unit 2. CPM - Unit 3
- 3) ARIA a- (iodine) CPM; at min - Unit 1 CPM; at min - Unit 2 CPM; at min - Unit 3 i) RIA So (hi range) mr/hr - Unit 1 ar/hr - Unit 2 k mr/hr - Unit 3
. .J h
i 1 4 i . l. v w - - - - w - e -- -- r-,-y - - , , .- - m
- Paga 1 cf 4 .
~,y ENCLOSURE 5.2 HP/0/B/1009/11 ODCAR2 USER GUIDE 1.0 Introduction The complete code ODCAR2 was designed to calculate offsite dose from gaseous releases through the unit vent. This guide is to aid the user -
in running ODCAR2 on VAX. In this guide, comouter resoonses will be shown inside double bold lines. User resconses will be shown underlined. The mark signifies a carriage return. ODCAR will only calculate for one unit at a cine. If more than one unit is affected, use ODCAR for the unit showing the highest activity. Any e other unit will be calculated manually and added to the ODCAR results. 2.0 Procedure 2.1 Complete VAX LOGON procedure outlined below. 2.1.1 Depress parity and duplex keys.
~
2.1. 2 - Pick up receiver and diak._ _ g 'When tone is heard, '.. depress data key and return to phon _e_, cradle.
. 2.1.3 Type in a carriage return ( ) .
2.1.a The computer will request: user name: Answer with: ODC7310 2.1.5- The computer will then request: Password: Respond by typing: DOSE 2.2 Computer will hesitate for a few seconds to load program and read the initial data file. 1 2.3 Computer will then respond with: INITIALIZE (TES OR NO) t i Answer YES for first run of the program to initialize data files and history files.
- Answer No for subsequent runs of the program to allow the computer to
-l account for past history of the release.
] 2.3.1 If initiali:ed, computer will type: ENTER TIME OF TRIP _. ' Enter the date and time of the reactor trip.
I , j ._- l t .I l * *
, -n, ,-,.--a,, - - - - , - - - - - - , - , . , , . - - - - ,
Piga 4 of 4 I ENCLOSURE 5.1 HP/0/3/1009/11 CALCUI.ATED DISCHARGE CONCEeVTRATION
- 1) Gas - (Use RIA 56 if on scale; if not on scale, use RIA 45 or RIA 46.
RIA-46 is considered on scale at > 10 cpm) Coney = {RIA-56 3*23,, mr/hr)
= pG/ml, Unit 1
, pCi/ml, Unit 2 . pCi/il, Unit 3 Cone y 5 cem)
= (RIA *
= Ci/ml, Unit I
; pCi/ml, Unit 2
_ pci/ml, Unit 3 Cones = (RIA-46 com)
= pCi/ml, Unit 1 "3 pCi/ml, Unit 2 uCi/ml, Unit 3
- 2) Iodine pCi/ml, Unit 1 Conc.. .- I = (ARIA 44 CPM) (1.0E-9) =
At pCi/ml, Unit 2
, --I
\ uCi/ml, Unit 3 O
4 l I e g .
,, p. .e. a =, w .e emeoe e M .me * . *
- 4- --- , e . - - , , ,, -. -~ ,_w. , . - - - ,
- a
,
- r .
*- Page 2 of 4 ENCLOSURE 5.2 HP/0/B/1009/11 Format: month, day, year, ti=e Example: 11.10.30.0945 2.4 Computer will type: ENTER WIND SPEED tMPM)
Enter the wind speed in miles per nout.
' Example: 12.0 2.5 Computer will type: ENTER WIND DIRECTION (*FROM NORTH)
Enter wind direction Example: 127.0 NOTE: At night when wind direction is 0*-360*. enter 360* into
! the computer.
2.6 Computer will type: E5 ITER TEMP DIFTERENTIAL (DEG.F) Enter the tseperature differential using degrees Fahrenheit.
, \ Example: -1.6 2.7 Computer will type: INPUT RELEASE RATE IN CFM Enter the release flow race (unit vent flow rate) in cubic feet per minute. .
1 Example: 1.3E3 . NOTE: Exponential notation may be used, but does not have to be. 2.3 Computer will type: ENTER TIME DATA WAS TAKEN Enter the time of day (approximately) that aX of the data being entered was collected. Example: 11.10.30.0945 2.9 Comouter will type: RELEASE CONC. IS :00WN (K) CR CVKNOWN (U) i If release concentration is known, use case (A) below. If the release concentration is not known, skip down to Case (3). (A) 2nter a :$ if the release concentration is known (such as fr:m uni. vent sample results.) i l .
.*%+, . . - . e , .
en,, , - -. ,, _,7 - ,
. . ~ - .....r- - ..
- Page 3 of 4-O
}
ENCLOSURE 5.2 HP/0/B/1009/11 2.9.1 Computer will type: ' ENTER GROSS NOBLE GAS CONC. Example: 1.3 E-2 Use units of microcuries per cubic centimeter. 2.9.2 Computer will type: ENTER I-131 EOUIV. CONC. Example: Same as 2.9.1 2.9.3 Computer will type: ENTER GAS E-BAR Example: 0.27 NOTE: This E-Bar number'can be obtained from sample resulta. , (B) Enter a U if the release concentration is unknown (processs monitor information). 2.9.4 Computer will type: ENTER GAS LOW RANGE CPM iRIA *5) T
}
/
Enter the counts per minute reading from the RIA-45 display. Example: 1.2 E 4 NOTE: RIA 45 goes offscale at IE6 cym. Enter 1E6 if I RIA-46 is > 100 cym. ,
'- 2.9.5 Computer will type: ENTER GAS HI-RANGE CPM tRIA-uoa il Enter counts per minute from RIA-46.
l Example: 1.2 E 3 ' i. l' NOTE: ODCAR does not consider RIA-46 on scale until
> 100 cpm.
l
+ .-
2.9.6 Computer will type: INTER IODINE CHANGE IN CP'.; 'RIA - i lj Enter the change in counts per minute observed on RIA-44 over fi 1 a measured period of time. Example: LaE4 s ,] 2.9.7 Computer will type: ENTER TIME tMINUTES1 0F CHANGE 's l: nter the time in minutes over which the change in RIA-44 took ll place. Example: 10.0 _j i, 4 . s
, e Pag 2 4 of 4 ENCLOSt~tE 5.2 HP/0/B/1009/11 .
2.10 Computer will now calculate, and update histor/ files: Computer will type: WHEN READY FCR PRINTOUT, ADVANCE TO TOP OF PAGE AND ENTER NL?iBER 9 i . Ex mple: 9 2.11 Computer will print, program will end, and the' computer logs off. 2.12 Wen computer has signed off. hang up the phone or start at Step 2.1.3 and continue data entr/. Release the paone line at the end of the session (when logged off) by depressing the LOC.U./ TALK key. 1 9 d 2 f I I
'~ * * ' * * * *
- w mwe . m i
Page 1 of 2
~
ENCLOSURE 5.2, APPENDIX A
. HP/0/3/1009/11 SAMPLE RUN OF ODCAR2 a.
Username: ODC7310 Password: Welcome to VAX/VMS Version 72.3 on node _0CO:: INITIALIZE? (YES OR NO) YES ENTER TIME OF TRIP 11 12 SO 0900 ENTER T0kT.R WIND SPEED (.*2H) 2.2 ENTER TokT.R WIND DIRECTION (DEGREES FROM NORTH) 148 j ENTER TEMP DIFFERENTIAL (DEG F)
-1.6 INPUT RELEASE FLOJ RATE (CIM) 12000 ENTER TIME DATA WAS TAKEN 11 12 30 1000 ,.
RELEASE CONC. IS KN0kW(K) 0F UVICIOkW(U) U c'TTER GAS LOW RANGE CPM (RIA-45) 1.3E6 - ENTER GAS HI RANGE C?M (RIA-46)
- 1. '.E4 E2TER IODINE CHANGE IN C?M (RIA-44) ,
1.5E5 ENTER TIME (MINUTES) 0F CHANGE , 2.0
; b1IEN READY FOR PRINTCUr, j ADVANCE TO TOP OF PAGE
{ AND E. VIER NUMBER 9. 1 O I i A)
=m. og e op.m -m _ w. __ ==M**. =+we - *=wy* + .ys giw6 -
. o-
- 6 Page 2 of 2 i
s ENCLOSURE 5.2, APPENDIX A HP/0/B/1009/11 SAMPLE RUN OF ODCAR2 P'LL7fE DIRECTION: 3.2SE+02 DEGREES RELEASE FLOW RATE: 1.20E+04 CFM WINDSPEED: 2.2 MPH DEI.fA TDfP: -1.6 DEG F NOBLE GAS RELEASE CONC: 2.82E+01 UCL/ML IODINE RELEASE CONC.: 3.62E-04 UCI/ML TIME OF TRIP- 11/12/80 900 TIME OF SAMPLE: 11/12/80 1000 CfERGENCY LEVEL SITE EMERGENCY DISTANCE SUBMERSION SU3MERSION SUBMER; ION PRESENT COWNWIND COSE RATE DOSE-TOTAL DOSE-TOTAL + 2 HOURS CONCENTR4 TION
- (MILES) (REM /HR) (REM) (REM) (UCI/ML) 1 4.081E-01 4.081E-01 1.224E+00 9.3SSE-04 2 2.951E-02 2 951E-02 S.853E-02 6.788E-05 3 1.695E-02 1.695E-02 5.085E-02 3.900E-05 4 1.256E-02 1.2561-02 3.767E-02 2.389E-05 i 5 1.067E-02 1.067E-02 3.202E-02 2.455E-05 6 9.104E-03 9.104E-03 2.731E-02 2.094E-05 7 7.343E-03 7.848E-03 a.354E-02 1.305E-05 l
3 6.906E-03 6.?C6E-03 2.072E-02 1.539E-05 9 6.273E-03 6.278E-03 1.384E-02 '1.444E-05
.0 5.651E-03 5.651E-03 1.695E-02 . 1.300E-05 1
TRTROID T'iYROID PRESENT DOSE-TOTAL DOSE-TOTAL + 2 HOURS CONCENTRATION (REM) (REi) (UCI/ML) 1 2.244E-02 6.733E-02 1.206E-08 2 1.623E-03 4.368E-03 S.719E-10 3 9.323E-04 2.797E-03 5.009E-10 4 6.906E-04 2.072E-03 3.710E-10 5 5.370E-04 1.761E-03 3.154E-10 6 5.007E-04 1.50?E-03 2.690E-10 7 4.316E-04 1.295E-03 2.319E-10 3 3.79dE-04 1.139E-03 2.041E-10 9 3.453E-04 1.036E-03 1.355E-10 10 3.108E-04 9.323E-04 1.670E-10 FORTRAN STCP OCC7310 logged out at 18-ACG-1981 07:59:40.30 d - * **
, , , . , , .,_ .,e- .. .+__,-e v
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t i nc l o:.s S3 lalite of lou-llour lie 14 Live Concentration Iacturs I _ louiperature Distance (Hiles) Diffe.cuce i Al"f 2 3 4 S 6 7 8 9 10 1
-25.0 to -1.3 l.SE-6 9.4E-7 5.4E-7 4.0E-7 3.4E-7 2.9E-7 2.SE-7 2.2E-7 2.0E-7 1.8E-7 C~
n no
-1.2 to -1.0 S.8E-S 1.6E-S 8.lE-6 4.9E-6 3.4E-6 2.SE-6 1.9E-6 1.SE-6 1.2E-6 1.0E-6 S .'x5' "Ykt
"' 9 = S 5'
3 C&o3 'G
-0.9 to -0.4 l.SE-4
;'1 Di
- S.6E-S 3.lE-S 2.lE-S I.SE-S 1.2E-S 7.6E-6 7.8E-6 6.7E-6 S.8E-6 o, a, -~ w o a.
3 ". < a
-0.) to th.S 2.9E-4 1.2E-4 6.7f-S 4.9E-S 3.4E-S 2.7E-S 2.2E-S 1.9E-S l.6E-S 1.42-5 el.0 to e25.0 6.4E-4 ?.lE-4 1.8E-4 1.'3E-4 9.SE-S 7.3E-S 6.lE-S S.0E-S 4.3E-S 3.6E-S M
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Page 1 of 2 ENC;0FURE 5.4 HP/0/B/1009/11
.WUAL CALCULATION '40RKSHEET
- 1) Discharge Concentration (Coney ).
Gas = pCi/ml U-1; pCi/ml U-2; pCi/ml U-3 Iodine = pC1/ml U-1; __ pCi/ml U-2; pCi/ml U-3
- 2) Vent Discharge Flow Rate:
Fy= CFM U-1; CFM U-2; CFM U-3
- 3) '4ind Speed MPH (Enclosure 5.1) a) Total Concentration: ConcT = U-1 (Cone,,, F.,,) + U-2 (Conc.1 F.,,) + U-3 (Cone y
- 1 3.)
Gas = pCi/ml cfm
-- Iodine = pCi/ml cfm
- 5) Two !{our Relative Cone. Factors (CH) = sec-mph /m3 X/Q - CH/ mph = secim3)
CH @ Mi = ; X/Q = Secim3 CH @ Mi = ; X/Q = Sec/m3 CH @ Mi = ; X/Q = Sec/m3 CH @' Mi = ; X/Q = Sec/m3
- 6) Downwind Concenetrations: Conc.,k. u = Cone e X/Q - (4.7E-4)
?
A)' Gas Conegg. = uCi/mi @ Mi Conc,%. pCi/ml @ Mi u = 1 Conegg. = pCi/mi @ Mi
, Conegg = uCi/ml @ Mi f ,
\ :
4
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=
s ,
. Pap 2 of 2 i
J ENCLOSURE 5.4 HP/0/3/1009/11 MANUAL CALCULATION WORKSHEET
- 3) Iodine Conegg = pCi/al @ Mi !
pCi/mi @ Mi ConcDW = Conegg = pCi/ml @ Mi Cone gy a pCi/ml @ Mi
- 7) Potential Whole Body Gamma Dose: DVB = (9.00 E2) Cone gg 5 Time 5= Mev/ dis Time = hours
- D.,.B Rem @ Mi D.,.B Rem @ Mi D., g Rem @ Mi D., B R** @ Hi
- 3) Potential Thyroid Dose: D7g = (1.36E6) Cone gg Time ,
Time : hours
- D Rem @ Mi .
7q Rem @ Mi . D 'EtT. - Dg Rem @ Mi 4~ Rem @ Mi
. DT*H
- Ensure correct time is used for steam relief valve release.
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Page 1 00 3 ENCLOSURE 5.7 RP/0/B/1009/11 EVALUATION OF PLCME LOCATION
- 1. Acquire the following information from Enclosure 5.1 and record on i Enclosure 5.8. .
a) Meteorological Data - identify for each point whether data is assumed (A), experiment (E) or measured (T, R or N). b) thyroid and whole body doses
- 2. Protective action guides submitted to the Offsite RadioJogical Coordinator are to be made b-sed on the calculated dose on Enclosure 5.1 and the follow-ing. info rmation.
a) For doses:
> 3 Rem Whole Body or,
>25 Rem Thyroid Recommend Evacuation of Population in Affected Area.
b) For doses: 1-5 Rem Whole Sody or. 5-25 Rem Thyroid Recommend evacustion af children and pregnant women, an_d sneltering of remainder of personnel in the affected area. c) For doses:
< 1 Rem Vhole 3ody or,
< 5 Rem Thyroid Recommend no action.
- 3. Determine Stability Class by completing step a below and record on Enclosure 5.3.
i 1
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'Page 2 of 3 l
~
ENCLUSURE 5.7 HP/0/B/1009/11 .! EVALUATION OF PLC:E LOCATION a) AT Stability Class
-8 to-1.3 A
-1.2 to -1.0 C
-0.9 to -0.4 D
-0.3 to +0.9 E
+1.0 to +8 7 4 To determine the sectors affected, complete one of she options under A Record the sectorc affected on Enclosure 5.3.
or 3. I A) Daytime (1000-1600 hrs)
- 1) wind speed 15 mph for tower or river wind direction, use Table 1.
') wind speed 1 5 :ph for NWS wind direction, use Table 2.
- 3) wind speed < 5 mph for tower or river wind direction, assume sectors
- A1, 31, C1, D1, El, and F1 are affected. Then use Table 1 to i determine additional sectors affected.
i' 4) wind speed < 5 mph NWS wind direction, assume all sectors affected (Al througn F1, A2 through F2). j' - TABLF. 1 , l Wind Direction Sectors Affected 1, 4 14*-27* C1. C2. DI. D2. E1. E2 4 27*-a2* C1. DI. D2, E1. E2 42*-6o* DI D2, El. E2 co*-85* DI D2. E1. E2. F2 I 35*-10e* DI. 02. E1. E2, 71. F2
; 10A*-129' El . E2, F1. F2 1 129*-156* A1. A2. E1, E2, F1. F2
] 15o*-175* A1. A2. E1. F1. F2 1 175*-131* A1. A2. F1. F2 j 131*-219' A1. A2. 31. 22. F1. F2 '. 219'-255* A1. A2. 31. 32 I 2558-271* A1. A2. 31, 32. C1. C2
, 271*-297* 31. 32. C1 C2 1
297*-312' 31. 32. C1. C2, 02 312*-345* ,
- 31. 32. C1, C2 DI. 02
. 345*-1A* C1. C2. DI. D2 i i [ .* f
}
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' ENC 20SURE 5,7 KP/0/3/1009/11 EVALUATION OF PLUME LOCATIG'l EVALUATION OF PLUME LOCATION TABLO 2 Wind Direction Sectors Affected
~
1*-39* B1, 32, C1, C2, 81, E2, F1, F2 39*-75* Al through F1, A2 through F2 75*-91* A1, A2, C1, C2, D1, D2, E1, E2, F1, F2 91*-117* Al through F1, A2 through F2 117*-132* A1, A2, B1, 32, C1, Di, D2, El, E2, F1, F2 132*-165* A1, A2, 31, 32, D1, D2, E1, E2, F1, F2 1658-194* Al through FI, A2 through F2 154*-207* A1, A2, 31, 32,.C1, C2, E1, E2, F1, F2 207*-222* A1, A2, B1,. 32 C1, C2, C2, El, E2, F1, F2
- 222*-246' . Al through F1, A2 througn F2 246*-263* A1, A2, 31, B2, C1, C2, D1, D2, Ei, 71, F2 2658-234' A1, A2, Bl. 32. C1, C2, DI, D2, F1. F2 2Sa*-309* Al through F1, A2 through F2 309*-336* A1, A2,.31, 32, 01, C2, D1, D2, Ei, E2 336*-355* A1, A2, 31, 32, C1, 02, D1, D2, Ei, E2, F2 3558-1* Al through F1, 22 through F2 1 3) Nighttime (1600-1000 hrs)
(If river wind direction is unavailable, assume 70*-210*.)
- 1) If river wind direction is between 210*-70*, use Option A (Daytime).
- 2) If river wind direction 1 2etween 70*-210*, assume all sectors affected (Al through F1, A2 througn F2).
1 4
? l 1
)
- r ,o, is e
Page 1 of 1 ENCLOSURE 5.S-DOSE ASSEST, MENT REPORT EP/0/3/1009/11 DATE: TIME: DOSE ASSESSOR:
'4IND DIRECTION SOURCE
'4IND SPEED MPH SOURCE
.17 *F/120ft SOURCE STABILITY CLASS DISTANCE THYROID / ADULT THYROID / CHID WOLE BODY COMMENTS
.5 mi.
I mi. _ 3 2 mi. - 3 mi. a mi. 3 mi. 5 ni .
- mi. .
3 mi. 9 mt. 10 mi. i Sectors Affected i e 4 M [ l l 4 I 4
. - ~ .
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