ML20080G152
| ML20080G152 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 02/07/1984 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20080G147 | List: |
| References | |
| PROC-840207, NUDOCS 8402130282 | |
| Download: ML20080G152 (19) | |
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.I SEQUOYAH NUCLEAR PLANT ODCM REVISION 8 INSTRUCTION SHEET Remove Insert (front /back) (front /back)
Effective Page Listing Rev. 7 Effective Page Listing Rev. 8 Dates of Revision TOC-1/ TOC-2 TOC-1/ TOC-2
- 7/8 7/8 16/- 16/16a 25/26 25/26 27/28 27/28 29/-
29/- 30 /-
Table 3 1-2 Table 3 1-2 Figure.3.1-3 Figure 31-3 Figure 3 1-6 Figure 3.1-6 Figure 3.1-7 ,
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l 8402130282 840207 PDR ADOCK 05000327 P PDR
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SEQUOYAH NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL EFFECTIVE PAGE LISTING
, REVISION 8 Page Revision
-TOC 1 through TOC 2 Revision 8 1 through 2 Revision 6 3 through 4 Original 5 Revision 3 6 Revision 4 7 Revision 8 8 through 9 Revision 5 10 Original 11 through 13 Revision 5
.14 Revision 7 15 Revision 5 15a Revision 7 16 through 16a Revision 8-Table 1.1 (2 pages) Revision 4
' Table 1.2 (2 pages) Original Table 1.3 (8 pages) Revision 4 Table'1.4 Revision 4 Table 1.4A Revision 5 Table 1.5 Revision 4 Tables-1.6 and 1.7 Revision 5 Table 1.8 Original Figures 1.1 and 1.2 Original f' Figure 1.3 Revision 3 17 Original 18 Revision 2 l~ 19 Revision 7 f 20 Revision 6 12 1 - Rcvision 7 22 Revision 5 23 through 24 Revision 7 25 through 29 Revision 8 Table 2.1 (3 pages) Revision 7 Table 2.2 Revision 5 Table 2.3-(3 pages) Revision 5 Table 2.4 a-c Revision 5 30 Revision 8 Table 3.1-1 (4 pages) Revision 4 Table 3.1-2 Revision 8
- Table ~ 3.1-3. Revision 4 Table 3.2-1 (3 pages) Revision 4 Figure 3.1-1 through 3.1-2 Revision 4 Figure 3.1-3 .
Revision 8 Figure 3.1-4 through 3.1-5 Revision 4 Figure 3.1-6 through 3.1-7 Revision 8
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Sequoyah Nuclear Plant
' Offsite Dose Calculation Manual Dates of Revisions Original ODCM- 2/29/80*
. Revision 1 4/15/80**
.Revisien 2 10/7/80**
Revision 3 11/3/80, 2/10/81 4/8/81 and 6/4/81**
Revision 4 11/22/82 (10/22/81, 11/28/81 and 4/29/82**
. Revision 5- 10/21/82**
Revision 6 1/20/83**
Revision 7 3/23/83**
Revision 8 12/16/83**
- Low: Power license for Sequoyah unit 1
- RARC-Meeting date
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TABLE'OF CONTENTS
. Introduction
- 1. Gaseous Effluents 1.l 51 arm / Trip Setpoint's 1 1.1.1 Release' Rate Limit Me'thodology - Ci/s 1
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Step 1 1 A. Noble Gases 1 B. Iodines and Par'ticulat'es 4 Step 2 10 1.2 Monthly Dose Calculations 10 1.'2.1 Nob'le Gases 11 Step 1 11 Step 2 13 l5 1.-2.2 Iodines and Particula'tes 14 Step 1 14 Ste'p 2 16 5 1.3 Dose Projections 16 1.4 Quarterly and Annual Dose Calculations 16 1 1.5 Gaseous Radwaste Treatment System Operation 16 8 1.5.1 Ejstem Description 16
-1.5.2 Dose Calculations 16a TOC-1
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TABLE'OF' CONTENTS (cont'd)
- 2. . Liquid Effluents. 17 2.1- Concentration 17 2.1.1 RE.TS Requirement 17 2.1.2 Prerelease Analysis 17
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2.1.3 ~ MPC - Sum of the Ratios 18 2.2. Instrument Setpoints 19 2.2.1 Setpoint Determination 19 2.2.2. Post-Release Analysis 20 1
'2.3._ Dose 20 2.3.1 RETS. Requirement 20 2.3.2 ' Monthly Analysis 21 2.3.2.1 -Water Ingestion 21
'2.3.2.2 Fish Ingestion 23
_2.3.2.3 Recreation 23
. I 2.3.2.4 Monthly Summary 25 2.3.2.5= Dose Projections 25 8 2.3.3 Quarterly and Annual Analysis 25 2.3-3.1 . Individual Doses 25
. 2'3.3.2
. Population Doses 28 7 2.4' operability of Liquid Radwaste Equipment 28 5
- 3. ; Radiological Environmental Monitoring. 30 8 3 3.1 Monitoring Program 30 3.2 . Detection. capabilities 30
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- 3. Milk Ingestion For determining the. concentration of any nuclide (except 11-3) in and 8 on vegetation:
7 , (1.7) f9 k 1 DR r [1-exp. (-A Ei t e , CVg = 3,600 k=1 2nx/n , YA y Ei [1-exp (-A B gy f t b)I' PA 1 j I
-where:-
CV concentration of radionuclide i in end on vegetation, g = pCi/kg. . k = stability class. f frequency of this stability class and wind direction k = combination, expressed as a fraction. Qg = average release rate of radionuclide 1, pCi/s. 4 DR = relative deposition rate, m~1 (Figure 1.2). x = downwind distance, m. n = number of sectors, 16. 2nx/n = sector width at point of interest, m. r = fraction of deposited activity retained on vegetation, 0.47 8 (table 1.6). , A effective removal rate constant, A .=A A ,
~i Ei = where A 4 is the radioactive decay Edeffid+ieXt, h ,
5 and A Is a measure of physical loss by weathering (A y =y0.0023 h 1) for particulates and 0.0017 for iodines, t, = period over which deposition occurs, 720 h. 5 Yy = agricultural yield, 1.18 kg/m 2, 1 B gV = transfer factor from soil to vegetation of calionuclide 1 (Table 1.6). Ag u radioactive decay coefficient of radionuclide i, h 1 4 Le t b = 3.07 x 105 time h for (3Syr). buildup of radionuclides on the ground,
- Revision 8
! -P = effective surface density of soil, 240 kg/m 2, 3,600 ='s/h conversion factor.
' For. determining the concentration of H-3 in vegetation:
,. .CVT'
- 1 x 103 )qp (0.75)(0.5/H)
(1.8) where: CVT =: concentration of H-3 in vegetation, pCi/kg.
.XT = air concentration of H-3, pCi/m3 . 4 0.75 = fraction of total plant mass that is water.
0 5 = ratio of tritium concentration in plant water to tritium concentration in atmospheric water.
-H = absolute humidity of the atmosphere, 9 g/m a,
- l'x=103 =. g/kg conversion factor.
For determining the concentration of any nuclide in cow's milk: CMg = CVf FM 1 Qg exp (-A g t g) (1.9) where: CM. = concentration of radionuclide i (including H-3) in 1 cow's milk, pCi/L. CV ;= concentration of radionuclide i in and on f vegetation, pCi/kg. FM.-= 1 transfer ^ factor from feed to' milk for radionuclide
-i, d/L~(Table 1.6). !
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~ .- -Step 2 This-methodology is to be used if the calculations in step 1 yield doses'that exceed applicable limits.
Doses for releases of ~ iodines and particulates shall be calculated using the' methodology in Section 1.1.1, step 1, part B, with the following exceptions:
\[ 1. All measured radionuclide releases will be used.
- 2. LDose will be evaluated at real cow locations and will consider actual grazing ' information.
~The receptor having:the highest total dose is then used to check
. compliance with specification 3.11.2.3.
' Calendar quarter doses are first estimated by summing the doses calculated for each month in that quarter. Calendar year doses are first estimated by summing the doses calculated for each month in that ye ar.~ .However, if the annual doses determined in this manner exceed or approach the specification. limits, doses calculated for previous ,
t . quarters with the methodology of section 1.4 will be used instead of the doses estimated by summing monthly results. 8 f: 1.3- Dose Projections J -In accordance with. specification 3.11.2.4, dose. projections.will be L. performed. This will be done by averaging the calculated dose for-L the most recent month and the= calculated dose for the previous month and assigning that average dose as the projection for the current month.
.1.4 1 Quarterly and Annual Dose Calculations-I! A' complete dose analysis utiliz'ing the total estimated gaseous b' ' releases for each calendar quarter will be performed and-reported as ~
L required in ' Specifications 6.9.1.8 and '6.9.1.9. Methodology for~this analysis is the same as :that described in Section 1.1.1, except that
-real pathways and receptor locations (Table 1.4A) are considered. In addition, meteorological data representative of a ground level release for each corresponding calendar quarter will be used. This
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. ~ analysis will replace the estimates in Section .1.2..
LAt_the end of.the year.an. annual dose analysis will'be-performed by
- calculating the sum.of'the quarterly doses to'the critical receptors.
'l.5" Gaseous Radwaste Treatment System Operation Theg!aseousradwastetreatmentsystem(GRTS)describedbelowshallbe
' maintained and operated to keep releases ALARA.
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-lc$.1 System Description
.A~.flo'w diagram for the GRTS is given in Figure 1.3. The system con'sists of two waste-gas compressor packages, nine gas decay tanks,
;and;the: associated. piping, valves,andinstrumentation. Gaseous
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. wastes are received from the following: degassing of the reactor coolant.and purging of the volume control tank prior to a cold shutdown, displacing of cover gases caused by liquid accumulation in the tanks connected to the vent. header, and boron recycle process operation.
1.5.2I Dose Calculations Doses will be calculated monthly using the methodology described in Section 1.2. These-doses will be used to ensure that the GRTS is operating as designed. t
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The dose equation then becomes D.=k(0.0823Acc-60 + 0.0013-ACo-58 + 0.0218 ACs-134 + (2.18) 0.0356 ACs-137) 2.3.2.4. Monthly' Summary
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' Calendar quarter doses are first: estimated by summing the doses calcu-
-lated for- each month in that ~ quarter. Calendar year. doses are first estimated ~by summing-the doses calculated for each month in that yea'r.
'However, if theLannual doses determined.in this manner exceed or approach 8 the specification limits, doses calculated for previous quarters with the I methodology of section 2.3.3 will be used instead of those quarterly. doses l estimated by summing monthly results. An annual check will be made to ensure.that the monthly dose estimates account for at least 95 percent
'of the dose calculated by the method described in Section 2.3.3. If less
. -than 95 percent of the dose has been estimated, either a new list of 3 principal _ isotopes will be prepared or a new correction factor will be l- used. The latter option will not be used if less-than 90 percent of the~ tota 11 dose is predicted.
2.3.2.5 :DoseiProjections l
.In:accordance:with specification 3.11.1.3, dose projections will L .be performed.: This will be'done by averaging the calculated dose L -
for.the.most recent month.and the calculated dose for the previous 8 month.and assigning that average' dose as the projection for the o current month.
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2.'3.3,-Quarterly and Annual Analysis A complete analysis utilizing the total estimated liquid releases for each calendar quarter will be performed and reported as required in section.6.9 of the: technical specifications. This analysis will replace values ~ calculated using section 2.3.2 methodology and will also
' include an approximation of population doses..
2'3.3.1 ' Individual Doses The dose to the'j th organ of the maximum individual from m nuclides,
.D),-is; described by.
- 5. m HD j= D ijk, rem (2.19) k=1 i=1 a 2 5-
[(IDCF)f).x'lik] + [(RDCF)ijk
- bik Tk $] (2.20)
,1t=-1, ~k = 1 k=3 Revision 8
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.where:
th D = dse'to-tggj organ from the i th radionuclide, ij k via the k exposure pathway, rem.
.j. .= the; organ of interest (bone, G1 tract, thyroid, liver, total body, and skin.)
k- '.=~ . exposure pathway of interest: (1) water ingestion', (2) fish' ingestion, (3) shoreline recreation, (4) above- , water recreation, (5) in-water recreation. th for the j organ from
-(IDCF)tj = ingesggon the 1 radionuclide, rem /pCi.
dose commitment factor For the combination of pathways considered and the nuclide mix expected, the maximum exposed individual will be an adult or child. Table 2.1 is a list of ingestion dose factors for the-two age groups. th radionuclide, the activ
.l ik=viathek{gyingestedof-thei exposure pathway, pCi.
Igg =CVgn (2.21) For the fish pathway 112 = C gg BM (2.22) F
'Cg= concentration of the i th radionuclide in the 5 t Tennessee - River, pCi/mL Cf .= Ag /(Fgd) (2.23)
Ag = activity released of i th radionuclide during the release period, pCi. Fg= total river flow at location 1 during period, mL. t = location of-interest -(for dose to the maximum individual the first down-river exposure point is used. For the. population: dose, various oown-river locations are used to account - for the total . exposed population. Table 2.4a gives the river location of;public water _ supplies; tables 2.4b and 2.4c-give.the boundaries of the'various reaches in which concentrations are calculated.for the fish and recreation pathways.) d'=Jfraction.of rive ~r flow available for dilution (1/5 above Chickamauga Dam, 1 below the dam). V'=caverage rate of water consumption per Regulatory Guide 1.109.
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For maximum-individual:
-Adult - 2000 mL/d Child - 1400 mL/d, 8 Revision 8
L For average individual (population): Adult , 1010 mL/d N.' Child - 710 mL/d n = number'of days during the release period, day. Bi = bioaccumulation factor for the i th radionuclide in fish, pCi/g per pCi/mL, from table 2.2. M = amount of. fish consumed during the period (fraction of year times.the annual consumption rate per Regulatory Guide 1.109.) For maximum individual: Adult - 21 kg/yr Child - 6.9 kg/yr For average individual (population): Adult - 6.9 kg/yr Child - 2.2 kg/yr th
' (RDCF)ijk = recreationt gose commitment factor fgg the j organ from the i radionuclide via the k pathway; mrem /yr per concentration (&ik) in medium; from table 2.3. 5 I ik =.the concentration of the ith radigguclide in the environ-mental medium pertaining to the k pathway.
For above-water-and in-water _ pathways Iik
- I i5 =C 1 (2.24)
For the shoreline pathway, a 15-year buildup in the sediment of-the late is assumed (per Regulatory. Guide 1.109 equation ~A-5). (13 = 100 RHL1C1 W [1-exp (-Ag t)] (2.25) where 100 = transfer constant as defined in Regulatory Guide 1.109. RHLg = radiological hal f-life of the i th isotope, days, from table 2.1. W = shoreline width factor (0.3 for a lake shore, per table A-2 of Regulatory Guide 1.109.)
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A1 = decay constant of the i th radionuclide
= 0.693/RHLt .
t = buildup time in' sediment, assumed 15 years, ~ per Regulatory Guide 1.109.
-27 8 Revision 8 k
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Tk=assumpgexposure'timeofmaximumindividualfor the k pathway
- 3) shoreline 500 h/yr (*10 h/ week) ,
- 4) above-water 1800 h/yr (6 h/d, 300 d/yr)
- 5) in-water 920 h/yr (6 h/d, for five ,
summer months)
$ = fraction of annual exposure for each quarter 1st Quarter Jan.-March 0.1 2nd Quarter April-June 0.3 3rd Quarter July-Sept. 0.4 4th Quarter Oct.-Dec. 0.2 2.3.3.2 Population Doses The total dose from all 5 pathways to the j th organ of the population, Aj, from m nuclides at n locations is described by n 5 m
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^J ijkt (2.26) 5 2=1 k=1 i=1 n 5 m
= D -
P (2.27), ij k1 kt l t-= 1 k=1 i=1 > . where th A ijkt
= dgge to the j organ of tgg total population from the i radionuclide via the k pathway at location 2.
D ij kt. = dose to individual as described in section 2.3.3.1 at location 2. P th kt = number of people exposed via the k pathway at location 1, from table 2.4.a-c. The population is aesumed to consist of 71 percent adults and 29 percent children (from Appendix D, Regulatory Guide 1.109 - the value for children includes-teenagers). 2.4 Operability'of Liquid Radwaste Equipment Specification 3.11.1.3 of the Radiological Ef fluent Technical Specifications requires that the liquid radwaste system shall be used to reduce the radioactive materials in liquid wastes prior to their 8 Revision 8
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discharge.when the projected dose due to liquid effluent releases to unrestricted' areas (see Figure 2.1.1-1) when averaged over 31 days would exceed 0.06 mrem to the total body or 0.21 mrem to any organ. Doses will be projected monthly to assure compliance. 8 Revision 8 i ...i . -- --
3.0 Radiological Environmental Monitoring 3.1 Monitoring Program An environmental radiological monitoring program shall be conducted in accordance with Technical Specification 3.12.1. The monitoring program described in Tables 3.1-1, 3.1-2, and 3.1-3, and in Figures 3.1-1, 3.1-2, 3.1-3, 3.1-4, 3.1-5, 3.1-6, and 3.1-7 shall be conducted. 4 lg Results of this program shall be reported in accordance with Technical Specifications 6.9.1.6 and 6.9.1.7.
.The atmospheric environmental radiological monitoring program shall consist of 12 monitoring stations from which samples of air particulates, atmospheric radioiodine, rainwater, and heavy particle fallout shall be collected.
The terrestrial monitoring program shall consist of the collection of milk, soil, ground water, drinking water, and food crops. In addition, direct gamma radiation levels will be measured in the vicinity of the plant.
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The reservoir sampling program shall consist of the collection of samples of surface water, sediment, and fish. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, sample unavailability or to malfunction of sampling equipment. If the latter, every effort shall be made to complete corrective action prior to the end of the next sampling period. 3.2 Detection capabilities Anslytical techniques shall be such that the detection capabilities listed in Table 3.2-1 are achieved. 8 Revision 8
SNP TABLE 3.1-2 Atmospheric and Terrestrial Monitoring Station Locations Sequoyah Nuclear Plant Location Approximate Distance and Sample Station Direction from Plant LM-1 S 1/4 mile SW LM-2 S 1/4 mile N PM-1 S (Nortliwoods) 10 miles WSW PM-2 S (Hamilton County Park) 3-3/4 miles WSW PM-3 S (Daisy) 5-1/2 miles WNW PM-4 S (Sale Creek) 10-1/2 miles N PM-5 S (Georgetown) 9 miles ENE PM-6 S (Work) 5 miles NE PM-7 S (Harrison Bay) 3-1/2 miles SE PM-8 S (Harrison) 8-1/2 miles SSW RM-1 S (Chattanooga, Riverside) 16 miles WSW RM-2 S (Dayton) 17-1/2 miles NNE (Identical with RM-2 WB, Watts Bar Nuclear Plant) Farm L 2-3/4 miles NNE Fara M 3-1/2 miles NNE Fara J 1-1/4 miles W Fara HW 1-1/4 miles NW
' Farm EM 2-1/2 miles N 4 Farm BR 2-1/4 miles SSW
. Farm LE 3-1/2 miles S Farm SM l-3/4 miles SE 8 Farm SU 3-1/4 miles SSE Farm C (control) 16 miles NE Farm B (control) 43 miles NE Farm S (control) 12 miles NNE Revision 8
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~ 4 Q Air Monitor Scale of Miles a TLD Station Revision 8 i
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e Figure 3.1 - 6 VEGETATION SAMPI,1NG 1.OCATIONS
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