ML20237C545
| ML20237C545 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 10/28/1987 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20237C477 | List: |
| References | |
| PROC-871028, NUDOCS 8712210373 | |
| Download: ML20237C545 (95) | |
Text
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OFFSITE DOSE CALCULATION MANUAL CHANGES REVISION NO. 17 e
8712210373 071215 PDR ADOCK 05000327 PDR R
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. 0FFSITE DOSE CALCULATION MANUAL REVISION 17
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INSTRUCTIONS ,
I Replace pages.
enclosed the following pages of the Offsite Dose Calculation Manual with the The revised pages are identified by revision number. i Remove (front /back) Insert
[ front /back)
EPL-1 / Dates of Revisions All EPL-1 / Dates of Revisions All i
All pages associated with the 1
Process Control Program (PCP) ee l
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SEQUOYAH l NUCLEAR <
PLANT ;
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OFFSITE DOSE CALCULATION MANUAL O .
I TENNESSEE VALLEY AUTHORITY c
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SEQUOYAH NUCLEAR PLANT O 0FFSITE DOSE CALCULATION MANUAL EFFECTIVE PAGE LISTING REVISION 17 t
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Pace i Revision Listing of Dates of Revisions i Revision 17 Table of Contents Page 1 through 4 Revision 17 1 through 85 Revision 17 O
EPL-1 c.
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j "'s, SEOUOYAH NUCLEAR PLANT l 1 0FFSITE DOSE CALCULATION MANUAL
\s_ / DATES OF REVISIONS Original ODCM 02/29/80*
Revision 1 04/15/80**
Revision 2 10/07/80**
Revision 3 11/03/80, 02/10/81 04/08/81, 06/04/81**
Revision 4 11/22/82 (10/22/81, 11/28/81, 04/29/82**)
Revision 5 10/21/82**
Revision 6 01/20/83**
Revision 7 03/23/83**
Revision 8 12/16/83**
Revision 9 03/07/84**
Revision 10 04/24/84**
Revision 11 08/21/84**
Revision 12 02/19/85**
Revision 13 .. 12/02/85 Revision 14 04/14/86 Revision 15 11/05/86***
Revision 16 01/16/87**
Revision 17 10/28/87**
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Approved by - DateII'l9[87
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RARC airmt Approved by > (04 M Dateff (Nanager,RADCON c
- Low Power license for Sequoyah unit 1
- RARC Meetin6 date
- Date approved by RARC Chairman i
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I SEOUOYAH NUCLEAR PLANT
[m} OFFSITE DOSE CALCULATION MANUAL
.() TABLE OF CONTENTS f j
l REVISION 17 1 page I 1.0 Gaseous Effluents i 1.1 Alarm / Trip Setpoints 1 1.1.1 Release Rate Limit Methodology - pCi/s 1 Step 1 - Design Source Term Dose Rate 1 A. Noble Gases - Dose Rates 1 Assumptions 1 Equations 3
Air Concentration 3 Total Body Dose Rate 3 Skin Dose Rate 4 B. Iodines and Particulate - Dose Rates 4 Assumptions 4 Equations 5
Inhalation - Thyroid Dose Rate 5 p Ground Contamination - Thyroid Dose Rate 6
\ Milk Ingestion - Thyroid Dose Rate 7 Total Thyroid Dose Rete 10 Step 2a - Initial Setpoints 10 Step 2b - Release Mix Specific Setpoints , 11 1.2 Monthly Dose Calculations 12 1.2.1 Noble Gases 13 1.2.2 Iodines and Particulate 17 1.3 Dose Projections 20 1.4 Quarterly and Annual Dose Calculations 21 1.5 Gaseous Radwaste Treatment System Operation 21 1.5.1 System Description 21 1.5.2 Dose Calculations 21 i
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TOC - 1 '
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I SEOUOYAH NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL gw TABLE OF CONTENTS (CONTINUED)
\ REVISION 17 page 2.0 Liquid Effluents 2.1 Concentration 2.1.1 RETS Requirement 22 2.1.2 Prerelease Analysis 22 2.1.3 MPC - Sum of the Ratios 23 2.2 Instrument Setpoints 24 2.2.1 Setpoint Determination 24 2.2.2 Post-Release Analysis 24 2.3 Dose 2.3.1 RETS Requirement 25 2.3.2 Monthly Analysis 25 2.3.2.1 Water Ingestion ~
26 2.3.2.2 Fish Ingestion 27 2.3.2.3 Recreation 28 2.3.2.4 Monthly Summary 29 7- ,s 2.3.2.5 Dose Projections 30 2.3.3 Quarterly and Annual Analysis 30 2.3.3.1 Individual Doses 30 2.3.3.2 Population Doses 33 2.4 Operability of Liquid Radwaste Equipment 34 3.0 Radiological Environmental Monitoring 3.1 Monitoring Program 35 3.2 Detection Capabilities 35 3.3 Interlaboratory Comparison Program 35 3.4 Land Use Census 36 4.0 Annual Maximum Individual Doses - Total 37 c'
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( SEOUOYAH NUCLEAR PLANT Offj,1TE DOSE CALCULATION MANUAL
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LIST OF TABLES
, REVISION 17 Page 1.1 EXPECTED ANNUAL ROUTINE GASEOUS RELEASES FROM ONE UNIT AT SEQUOYAH NUCLEAR PLANT 38 1.2 BASIC RADIONUCLIDES DATA- 39 1.3 JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED FOR DIFFERENT STABILITY CLASSES 41 1.4 SQN - 0FFSITE RECEPTOR LOCATION DATA 49 1.5 DOSE FACTORS FOR SUSMERSION IN NOBLE GASES 50 1.6 NUCLIDE SPECIFIC TRANSFER DATA 51 1.7 INTERNAL DOSE FACTORS - INFANT THYROID 53 j 1.8 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND 54 2.1 INGESTION DOSE FACTORS 56 i
, 2.2 FISH CONCENTRATION FACTORS 60 2.3 RECREATION DOSE FACTORS 62 2.4 PUBLIC WATER SUPPLY INFORMATION 66 2.5 FISH HARVEST DATA .
67 2.6 RECREATION USAGE DATA ~ 68 3.1 RADIOLOGICAL ENVIRONMENTAL MONITORNG PROGRAM 69 3.2 ATMOSPHERIC AND TERRESTRIAL MONITORING STATION LOCATIONS 73 3.3 PUBLIC WATER SUPPLIES SAMPLED IN ENVIRONMENTAL MONITORING PROGRAM 74 3.4 MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD) 75 c.
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eN SEOUOYAH NUCLEAR PLANT f 0FFSITE DOSE CALCULATION MANUAL
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LIST OF FIGURES REVISION 17 Page 1.1 PLUME DEPLETION EFFECT FOR GROUND LEVEL RELEASES 77 1.2 RELATIVE DEPOSITION FOR GROUND LEVEL RELEASES 78 1.3 GASEOUS RADWASTE TREATNINT SYSTEM 79 3.1 ATMOSPHERIC AND TERRESTRIAL MONITORING NETWORK 80 3.2 SITE MONITORING STATIONS 81 3.3 LOCAL MONITORING STATIONS 82 i
3.4 RRSERVIOR MONITORING NETWORK 83 3.5 SQN TLD STATIONS 84 3.6 MILK AND VEGETABLE SAMPLING LOCATIONS 85
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1.0 Gaseous _ Effluents 1.1 Alarm / Trio Setooints Specification 3.11.2.1 requires that the dose rate in unrestricted areas due to gaseous effluents from the site shall be limited at all times to the following values:
- 1. 500 mrem /y to the total body and 3,000 mrem /y to the skin from noble gases.
- 2. 1,500 mrem /y to any organ from radioiodines and particulate.
Specification 3.3.3.10 requires gaseous effluent monitors to have j alarm / trip setpoints to ensure that the above dose rates are not exceeded. This section of the ODCM describes the methodology that will be used to determine these setpoints.
~ i The methodology for determining alarm / trip setpoints is divided into two major parts. The first consists of backcalculating from a dose rate to a release rate limit, in pCi/s, for each nuclide and release point.
The second consists of using the release rate limits to determine the physical settings on the monitors.
1.1.1 Release Rate. Limit Methodology - uCi/s Sten 1 - Release Rate Limit Methodology - Dose Rates The first step involves calculating a dose rate based on the design objective source term mix used in the licensing of the plant,. Doses are determined for (1) noble gases and (2) lodines and particulate.
Depending on the pathway involved, either air concentrations or ground concentrations are calculated.
A. Release Rate Limit Methodology - Noble Gas Dose Rates Release Rate Limit Methodology - Noble Gas Dose Rates - Assumptions:
- 1. Doses to be calculated are total body and skin.
- 2. Exposure pathway is submersion within a cloud of noble gases.
c
- 3. Noble gas radionuclides mix is based on the design objective source term given in Table 1.1.
f
- 4. Basic radionuclides data are given in Table 1.2.
- 5. All releases are treated as ground level.
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(~} Revision 17 Y )
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- 6. Meteorological data are expressed as a joint-frequency distribution of wind speed, wind direction, and atmospheric stability for the period January 1972 to December 1975 .
(Table 1.3).
- 7. Raw meteorological data consist of wind speed and direction measurements at 10m and temperature measurements at 9m and 46m.
- 8. Dose is to be evaluated at the offsite exposure point where maximum concentrations are expected to exist.
- 9. Potential maximum-exposure points considered are the nearest land site boundary points (Table 1.4) in each sector.
- 10. A semi-infinite cloud model is used.
- 11. No credit is taken for shielding by residence.
- 12. Plume depletion and radioactive decay are considered.
- 13. Building wake effects on effluent dispersion are considered.
- 14. A sector-average dispersion equation is used.
- 15. The wind speed classes that are used are as follows:
Humber RanRe (m/s) Midpoint (m/s) 1 <0.3 0.12 2 0.3-0.6 0.45 3 0.7-1.5 1.10 4 1.6-2.4 1.99 5 2.5-3.3 2.88 6 3.4-5.5 4.45 7 5.6-8.2 6.91 8 8.3-10.9 9.59 9 >10.9 10.95
- 16. The stability classes that will be used are the standard A through G classifications. The stability classes 1-7 will correspond to A=1, B=2, ..., G=7. c
- 17. Terrain effects are not considered. i
- 18. Environmental transfer data is consistent with NUREG/CR-1004. I O 1157c
/ Revision 17 Release Rate Limit Methodology - Noble Gas Dose Rates Equations To calculate the dose for any one of the 16 potential maximum-exposure points, the following equations are used.
Belease Rate Limit Methodology - Noble Gas Dose Rates - Eauations Air Concentration 9 7 fjk Qi P Xi = } } (2/w)1/2 E zk ud (2rx/n) exp(-Ai x/uj) (1.1) j=1 k=1 where Xi = air concentration of radionuclides i, pCi/m8.
fjk = joint relative frequency of occurrence of winds in windspeed class j, stability class k, blowing toward this exposure point, expressed as a fraction.
Qi = average release rate of radionuclides i, pCi/s.
/ p = fraction of radionuclides remaining in plume (Figure 1.1).
N'- '
Izk = vertical dispersion coefficient for utability class k which includes a building /2 wake adjustment, Izk * (O zk + cA/w)1 , where o z k is the vertical dispersion coefficient for stability class k (m), c is a building shape factor (c=0.5), and A is the minimum building cross-sectional area (1800 m 2 ),-
uj = midpoint value of wind speed class interval j, m/s.
x = downwind distance, m.
n = number of sectors, 16.
11 = radioactive decay coefficient of radionuclides i, s-1 2rx/n = sector width at point of interest, m.
1 c
Release Rate Limit Methodology - Noble Gas Dose Rates - Eauations Total Body Dose Rate DTB = 2 Xi DFBi (1.2) i
\
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~ ~ - - - - _ - - _ _ - _ _ _ _ - _ _ - _ - _ _ _-
N
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t Revision 17 where DTB = total body dose rate, mrem /y.
Xi = air concentration of radionuclides i, pCi/m8 .
DFBI = total body dose factor due to gamma radiation, mrem /y per pCi/m3 (Table 1.5).
Release Rate Limit Methodoloav - Noble Gas Dose Rates - Eauations Ekin Dose Rate Da= Xi (DFSi + 1.11 DFyi) (1,3) where Ds = skin dose rate, mrem /y.
Xi = air concentration of radionuclides i, pCi/m8 .
DFSi = skin dose factor due to beta radiation, mrem /y per
~g pCi/m8 (Table 1.5).
Nm _- 3.11 = the av'erage ratio of tissue to air energy absorption coefficients, mrem / mrad.
DFy1 = gamma-to-air dose factor for radionuclides i, mrad /y per pCi/m3 (Table 1.5).
B. Release Rate Limit Methodology - Iodines and Particulate Dose Rates Release Rate Limit Methodoloav - Iodines.and Particulate Dose Rates Assumptions:
- 1. . Dose is to be calculated for the critical organ, thyroid, and the critical age group, infant.
- 2. Exposure pathways from iodines and particulate are milk -
ingestion, grzound contamination, and inhalation. '
- 3. The radioiodine and particulate mix is based on the design objective source term given in Table 1.1.
- 4. Basic radionuclides data are given in Table 1.2.
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SQN ODCM Page 5 of 85 fs Revision 17
- 5. All releases are treated as ground-level.
- 6. Meteorological data are expressed as joint-frequency distributions (JFD's) of wind speed, wind direction, and atmospheric stability for the period January 1972 to December 1975 (Table 1.3).
- 7. Raw meteorological data for ground-level releases consist of wind speed and direction measurements at 10m and temperature measurements at 9m and 46m.
- 8. Dose is to be evaluated at the potential offsite exposure point where maximum concentrations are expected to exist.
- 9. Real cow locations are not considered.
- 10. Potential maximum exposure points considered are the nearest land site boundary points (Table 1.4) in each sector.
- 11. Terrain effects are not considered.
- 12. Building wake effects on effluent dispersion are considered.
- 13. Plume depletion and radioactive decay are considered for air-concentration calculations.
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14 Radioactive decay is considered for ground-concentration calculations.
- 15. Deposition is calculated based on the curves given in Figure 1.2.
- 16. A milk cow obtains 100 percent of her food from pasture grass.
- 17. No credit is taken for shielding by residence.
Release Rate Limit Methodology - Iodines and Particulate Dose Rates Equations:
To calculate the dose for any one of the potential maximum-exposure points, the following equations are used:
c Release Rate Limit Methodoloav - Iodings and Particulate - Inhalation -
Thyroid Dose Rates The equation for calculating air concentration, X, is the same as in the Noble Gas Section, 1.1.1.A, Equation 1.1.
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('~'N Revision 17 N.)
For determining the inhalation thyroid dose rate:
DTHI = 10-' 2 Xi DFIi (1.4) i where:
DTHI = thyroid dose rate due to inhalation, mrem /y.
Xi = air concentration of radionuclides i, pCi/ma ,
DFIl = infant inhalation dose factor, mrem /yr per pCi/cm3 ,
(Table 1.7).
10-6 = m8/cm3 conversion factor.
Release Rate Limit Methodology - Iodines and Particulate - Ground Contamination - Thyroid Dose _Eates For determining the ground concentration of any nuclide:
,T'N i fk Qi DR
\s s') Gi = 3.15x107 { { 1-exp-(Attb) ] (1.5) k=1 (2rx/n)Ai where:
Gi = ground concentration of radionuclides i, pCi/m2 , ,
k = stability class.
ik = joint relative frequency of occurrence of winds in stability class k blowing toward this exposure point, expressed as a fraction.
Qi .= average release rate of radionuclides i, pCi/s.
DR = relative deposition rate, m-1 (Figure 1.2).
x = downwind distance, m.
c n = number of sectors, 16, 2rx/n = sector width at point of interest, m.
Ai = radioactive decay coefficient of radionuclides i, yr-1
- f ~s t
V) 1157c L _ _ - _____ __-__-__-_ ___ _ . - - -
SQN ODCM Page 7 of 85 f'~'s Revision 17 iv) tb = time for buildup of radionuclides on the ground, 35yr.
3.15x107 = s/y conversion factor.
For determining the thyroid dose rate from ground contamination:
DTHC = (8,760) 10' 1G1 DFGi (1.6) i where:
DTHG = thyroid dose rate due to ground contamination, mrem /yr. ,
4 Gi = ground concentration of radionuclides i, pCi/m ,
2 DFGi = dose factor for starding on contaminated ground, mrem /h per pCi/m2 (Table 1.8).
8,760 = occupation time, h/yr.
10' = pCi/pci conversion factor.
s
\s - Release Rate Limit Methodology - Iodines and Particulate - Milk Innestion - Thyroid Dose Rates l
For determining the concentration of any nuclide (except H-3) in and on vegetation:
7 CVi = 3,600 { fk Qi DR r(1-exp (-AEi te)) Bl y(1-exp (-11 t (2vx/n)
[ + b)) ] (1.7) k=1 yay Ei P11 T
where:
CVi = concentration of radionuclides i in and on vegetation, pCi/kg.
k = stability class.
c fk = frequency of this stability class and wind direction combination, expressed as a fraction.
Qi = average release rate of radionuclides i, pCi/s.
DR = relative deposition rate, m-1 (Figure 1.2).
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Revision 17
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x = downwind distance, m.
n = number of sectors,16.
2irx/n = sector width'at point.of interest, m.
r
= fraction of deposited activity retained on vegetation, 0.47 (Table 1.6).
AEi = effective removal rate constant, AEi " Ai+Ave where li is the radioactive decay coefficient, h-1, and 1 , is a measure of physical loss by weathering (1 ,= 0.0023 h-1 for particulate and 0.0017 for iodines).
te = period over which deposition occurs, 720 h.
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Yy = agricultural yield, 1.18 kg/m2, l Biy =
transfer factor from soil to vegetation of radionuclides i
.(Table 1.6).
11 = radioactive decay coefficient of radionuclides i, h-1
'[ tb
'~ = time for buildup of radionuclides on the ground, l
3.07x105 h (35 yr).
l P
- l. = effective surface density of soil, 240 kg/m2, 3,600
= s/h conversion factor.
For determining the concentration of H-3 in vegetation:
CVT = 10s XT (0.75)(0.5/H)
(1.8) where:
CVT = concentration of H-3 in vegetation, pCi/kg.
XT = air concentration of H-3, pCi/m8 .
0.75 = fraction of total plant mass that is water. c' O.5 = ratio of tritium concentration in plant water to tritium concentration in atmospheric water.
H = absolute humidity of the atmosphere, 9 g/ma ,
103 = g/kg conversion factor.
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SQN ODCM l Page 9 of 85 f'~N Revision 17 For deterrtining the concentration of any nuclide in cow's milk:
CM1 = CVi FMiQf exp(-11 tr) (1.9) where:
CMi = concentration of radionuclides i (including H-3) in cow's milk, pCi/L.
CVi = concentration of radionuclides i in and on vegetation, pCi/kg.
FMi = transfer factor from feed to milk for radionuclides i, d/L (Table 1.6).
Qf = amount of feed consumed by the cow per day, kg/d.
Ai = radioactive decay coefficient of radionuclides i, d-1 tg = transport time of activity from feed to milk to receptor, 1 day.
For determining the thyroid dose rate from ingestion of cow's milk:
6 DTHM = 10 [ CMI DFING1 UM (1.10) i where:
DTl'y = thyroid dose rate due to milk ingestion, mrem /yr.
CMi = concentration of radionuclides i in cow's milk, pC1/L.
DFINGi = infant ingestion dose factor, mrem /pC1, (Regulatory Guide 1.109).
UM = infant ingestion rate for milk, 330 L/yr.
106 = pCi/pc1 conversion factor.
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,('~'} Revision 17
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Release Rate Limit Methodoloav - Iodines and Particulate -
Total Thyroid Dose Rate For determining the total thyroid dose rate from iodines and particulate:
DTH = DTHI + DTHG + DTHM (1all) where:
DTH = total thyroid dose rate, mrem /yr.
1 DTH1 = thyroid dose rate due to inhalation, mrem /yr.
DTHG = thyroid dose rate due to ground contamination, mrem /yr.
DTEM = thyroid dose rate due to milk ingestion, mrem /yr.
The maximum total thyroid dose rate calculated in this step will be used in step 2.
Sten 2a (Initial Setooints)
\s- The dose rate limits of interest (Specification 3.11.2.1) are:
Total Body = 500 mrem /yr Skin = 3000 mrem /yr Maximum Organ = 1500 mrem /yr For the determination of initial setpoints, the above limits are divided by the appropriate dose calculated in step 1 yielding, Dose limit
=R Dose step 1 i l
This ratio, R, represents how far above or below the guidelines this step 1 calculation was. Multiplying the original source term by R will give release rates that should correspond to the dose limits given above.
Appropriate release rate limits in pCi/s for each nuclide and release point will be provided to plant personnel for use in establishing monitor C
setpoints. The setpoint for each gaseous effluent monitor will be established using plant instructions.
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[ Revision 17
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The general equation used by plant personnel in establishing setpoints in cpm from release rate. limits in pCi/s is as follows:
C=
Q x e x s x 60 v x 28320 (1.12) where:
C = monitor setpoint, cpm.
Q = release rate limit, pCi/s.
e = detector efficiency, cpm /pC1/cc. ;
s =
safety factor; 0.2 for systems without automatic isolation; 0.5 for systems with automatic isolation, )
j 60 = s/ min.
28320 = cc/fta, V = flow rate past the detector, cfm.
Sten 2b (Release Mix Specific Setooints)
When release mixes are known, setpoints are based on the dose methodology given in Step 1, disregarding the design source term mix. Using a
-s normalized source term (qi) for each nuclide, nuclide specific dose
[\s_,) \
rates (D i) are determined independently for each nuclide using Step 1 methodology. Dividing the appropriate dose rate limit above by the nuclide specific dose rate, D i, yields:
Dose Rate limit
= ri Di ,
This ratio, ri represents how far above or below the guidelines the nuclide specific dose rate (D i) is. Multiplying the normalized source term (gi) by ri vill give the maximum allowable release rate R i for nuclide i.
Ri for each nuclide is also calculated by an alternative methodology using the reporting requirements of 10 CFR 50.73 (2 times the 10 CFR 20 Appendix B, Table II air concentrations). Release rate limits, Ri for each nuclide are calculated using this methodology as given below:
(2)(MPC1 )
Ri= (1.13)
(5.12x10-6)(10-6) g
= 3.91x1011 where MPCi = the 10 CFR 20, Appendix B. Table II, air concentration, pCi/cc.
[ 5.12x10-6 o worst land site boundary X/Q, s/m3 (Table 1.4).
V) 10-6 = conversion factor, m 8/cc.
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/\ Revision 17 The release rate limit, Ri , for each nuclide will be the most restrictive one calculated using both methodologies.
For a known mixture of n nuclides the release rates must be such that:
n Qi I <1 i=1 Ri Appropriate release rate limits in pCi/s for each nuclide and release point will be provided to plant personnel for use in establishing monitor setpoints. The setpoint in counts per minute for each gaseous effluent monitor will be established using plant instructions. The general equation used by plant personnel in establishing setpoints in epm from release rate limits in pCi/s is the same as that used in Step 2a, Equation 1.12. -
1.2 Monthly Dose Calculations Dose calculations will be performed monthly to determine compliance with
- [,, specifications 3.11.2.2 and 3.11.2.3. These specifications require that i
the dose rate in unrestricted areas due to gaseous effluents from each reactor at the site shall be limited to the following:
For noble gases,
- 1. During any calendar quarter, 5 mrad to air for gamma radiation and 10 mrad to air for beta radiation.
- 2. During any calendar year, 10 mrad to air for gamma radiation and 20 mrad to air for beta radiation.
For iodines and particulate,
- 1. During any calendar quarter, 7.5 mrem to any organ.
- 2. During any calendar year, 15 mrem to any organ.
This section of the ODCM describes the methodology that will be used to .
perform these monthly calculations. '
Doses will first be calculated by a simplified conservative approach (step 1). If these exceed 50 percent of the specification limits, a more realistic calculation will be performed (step 2).
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{g Revision 17 l 1.2.1 ILoble Gases Slep 1 Monthly Noble Gas Dose (simplified conservative accroach) !
Doses will be calculated using the methodology described in this step, j
1 If 50 percent of any limits are exceeded, step 2 will be performed. j l
Assumptions and equations for calculating doses from releases of noble l
gases are as follows:
Sten 1 Monthly Noble Cases Dose Assumptions
- 1. Doses to be calculated are gamma and beta air doses.
- 2. The highest annual-average X/Q based on licensing meteorology for ground level releases for any offsite location will be used.
- 3. No credit is taken for radioactive decay.
- 4. For gamma and beta doses, releases of Ar-41, Kr-85m, Kr-85, Kr-87, Kr-88, Xe-131m, Xe-133m, Xe-133, Xe-135m, Xe-135, and Xe-138 are considered.
~p 5. Dose factors are calculated using data from TVA's nuclide library.-
- 6. The calculations extrapolate doses assuming that only 90 percent of total dose was contributed.
- 7. A semi-infinite cloud model is used. ,
- 8. Building wake effects on effluent dispersion are considered.
Sten 1 Monthly Noble Gas Dose Ecuations Sten 1 Monthly Noble Gas Dose Eauations - Ga.mma Dose to Air D (
Y= 2 Qi DFyi (1.14) 0.9 3.15x107 i where: ,
t.
Dy = gamma dose to air, mrad.
X/Q .= highest annual-average relative concentration, 5.12x10-6 s/m3 .
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Revision 17
\%sl 0.9 = fraction of total gamma dose expected to be contributed by these nuclides.
106 = pCi/Ci conversion factor.
3.15x107 = . s/yr conversion factor.
Qi = monthly release of radionuclides i, Ci.
DFyi = gamma-to-air dose factor for radionuclides i, mrad /yr per pCi/m3 (Table 1.5). For Kr-88 and Xe-138, the dose factors for Kr-88+D and Xe-138+D are used to account for daughter buildup.
This equation then reduces to Dy = 1.81x10-7 { Qi DFyi -
i Step 1 Monthly Noble Gas Dose Ecuations - Beta Dose to Air 3
O)
(s,,/ De =
(X/Q) 0.9 10' 3.15x107 1 Qi DFgi (1.15) 1 where:
i De = beta dose to air, mrad.
X/Q = highest annual-average relative concentration, 5.12x10-6 s/m8 .
0.9 = fraction of total beta dose expected to be contributed by these nuclides.
106 = pCi/Ci conversion factor.
3.15x107 = s/yr conversion factor.
Qi = monthly release of radionuclides 1, C1.
DFBI = beta-to-air dose factor for radionuclides i, mrad /yr per C pCi/m3 (Table 1.5). For Kr-88 and Xe-138, the dose factors for Kr-88+D and Xe-138+D are used to account for daughter buildup.
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-('~'\, Revision 17 This equation then reduces to:
Da = 1.81x10-7' I Qi DFgi I i
Sten 2 - Monthly Noble Gas Dose (realistic aooroach)
This methodology is to be used if the calculations in Step 1 yield doses that exceed 50 percent of the applicable limits.
Equations and assumptions for calculating doses to air from releases of noble gases are as follows: ,
Steo 2 Monthly Noble Gas Dose Assumptions
- 1. Doses to be calculated are gamma and beta air doses.
2.
Dose is to be evaluated at the nearest land site boundary point in each sector.
'3. Historical onsite meteorological data from the period 1972-1975 s will be used.
s/
m 4. All meas'ured radionuclides releases are considered.
- 5. A semi-infinite cloud model is used.
- 6. Radioactive decay is considered.
- 7. Building wake effects on effluent dispersion are considered.
- 8. Dose factors are calculated using data from TVA's radionuclides library.
Sten 2 Monthly Noble Gas Dose Ecuations The equation for calculating air concentration, X, is the same as in Section 1.1.1, Step 1, Equation 1.1. Air concentrations are calculated for the site boundary in each sector.
Sten 2 Monthly Noble Gas Dose - Gamma Dose to Air . i L
Dyn = tm 2 Xni DFyi (1.16) i
./'
\
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where:
D yn
= gamma dose to air for sector n, mrad.
Xni = air concentration of radionuclides i in sector n, pCi/ma ,
DFyi
= gamma-to-air dose factor for radionuclides i, mrad /yr per pCi/m8 (Table 1.5).
tm
= time period considered, yr.
Steo 2 Monthly Noble Gas Dose - Beta Dose to Air DBn = tm I Xni DFai (1.17) i
~~
where:
)
DBn = beta dose to air for sector n, mrad.
Xni = air concentration of radionuclides i in sector n, pCi/ms ,
~'s DFgi = beta 8to air dose factor for radionuclides i, mrad /yr per v) f
- pCi/m .
tm = time period considered, yr.
The sector having the highest total dose is then used to check compliance with specification 3.11.2.2.
- i e
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1.2.2 Iodines. Particulate. and Tritium Sten 1 Monthly Iodines. Particulate. and Tritium Dose Doses will be calculated using the methodology described in this step.
If 50 percent of the applicable limits are exceeded, step 2 will be performed.
Equations and assumptions for calculating doses from releases of iodines, particulate, and tritium are as follows:
Sten 1 Monthly Iodines. Particulate. and Tritium Dose Assumptions
- 1. Doses are to be calculated for the infant thyroid from milk ingestion and for the child bone and teen g.i. tract from vegetable ingestion.
2.
Real cow locations are considered for the milk pathway and nearest resident-locations with home-use gardens are considered for the vegetable pathway.
- 3. The highest annual-average X/Q and D/Q based on 1972-1975 meteorological data for ground level releases will be used for
,-_ ingestion pathway doses.
_, 4. No credit is taken for radioactive decay.
- 5. Releases of H-3, I-131, and I-133 are considered for the milk pathway. H-3, Sr-89, Sr-90, Cs-134, and Cs-137 releases are considered for the vegetable pathway to the child bone. H-3, Co-58, and Co-60 releases are considered for the vegetable pathway to the teen g.i. tract.
- 6. The calculations extrapolate doses assuming that only 90 percent of the total dose was contributed.
7.
The cow is assumed to graze on pasture grass for the whole year.
j Sten 1 Monthly Iodines. Particulate. and Tritium Dose Eauations Sten 1 Monthly _Ihyroid Dose from Milk Innestion (Qi DFi ) D/Q 106 + (QT DFT ) X/Q DTH - --
(1.18) 0.9 x 3.15x107 l
where:
.s DTH = thyroid dose from H-3, I-131, and I-133, mrem.
Il57c
SQN ODCM Page 18 of 85 y'~%g Revision 17 Qi = monthly release of iodine nuclide i, C1.
QT = monthly release of H-3, C1.
DFi = nuclide i milk ingestion dose factor to infant, 7.24x1011 mrem /yr per pCi/m2
-s for I-131 and 1.52x1010 mrem /yr per pCi/ma -s for I-133.*
DFT = H-3 milk ingestion dose factor, 3.53x10 8 mrem /yr per pCi/cc.*
D/Q = relative deposition rate, 2.96x19-'m-2, X/Q = relative air concentration, 1.76x10-6 s/m3 .
0.9
= fraction of dose expected to be contributed by I-131 and I-133.
3.15x107 = s/yr.
10' = pCi/Ci.
Equation 1.18 then reduces to:
-~s
( p) DTH = 1.04x10-10 Qi DFi + 2.19x10-4 QT Sten 1 Monthly Bone Dose from Venetable Innestion 1
I DBCi = -i (Qi DFi ) D/Q 108 + QT DFT X/Q (1.19) 0.9 x 3.15x107 where:
DBC1 = bone dose to child, mrem.
Qi = monthly release of Sr or Cs nuclide i, C1.
QT = monthly release of H-3, Ci.
DFi = Vegetable ingestion dose factor to child, 2.25x1011, '
1.36x1018, 1.59x1011, and 2.58x1011 mrem /yr per pCi/m2-s for Sr-89, Sr-90, Cs-134, and Cs-137, respectively.*
'~'}
- As per Regulatory Guide 1.109 and NUREG/CR-1004 methodologies.
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(
DFT = vegetable ingestion dose factor for H-3, 4.53x10 8 mrem /yr per pCi/cc.*
D/Q = relative rieposition rate, 7.10x10-8 m-2, X/Q = relative air concentration, 2.98x10-' s/ma ,
3.15x107 = s/yr.
10' = pCi/C1.
l 0.9
= fraction of total bone dose expected to be contributed by H-3, Sr-89, Sr-90, Cs-134, and Cs-137.
l Equation 1.19 then reduces to DBCi = 2.50x10-10 l Qi DFi + 4.76x10-8 QT i
Sten 1 Monthly Gastrointestinal (R.i.) Tract Dose from Venetable Incestion E
,O DGI T = --~i (Qi DFi ) D/Q 106+ (QT DFT ) X/Q
( ,)g _ 0.9 x 3.15x107 (1.20) where:
DGIT = teen g.i tract dose from H-3, Co-58, and Co-60, mrem.
Qi = monthly release of cobalt nuclide i, C1.
QT = monthly release of H-3, C1.
DFi = Vegetable ingestion dose factor for the teen g.i. tract, 3.87x105 mrem /yr per pCi/ma -s for Co-58 and 3.31x1010 mrem /yr per pCi/m2-s for Co-60.*
DFT = vegetable ingestion dose factor for H-3, 2.92x108 mrem /yr per pCi/cc.*
D/Q = relative deposition rate, 7.10x10-8 m-2 2
X/Q = relative air concentration, 2.98x10-' s/m ,a 3.15x107 = s/yr. i i
h
~
- As per Regulatory Guide 1.109 and NUREG/CR-1004 methodologies.
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l
= pCi/C1.
106 0.9 = fraction of total g.i. tract dose expected to be contributed by H-3, Co-58, and Co-60.
Equation 1.20 then reduces to DGIT = 2.50x10-10 I Qi DFi + 3.07x10-4 QT i
Step 2 This methodology is to be used if the calculations in step 1 yield doses that exceed 50 percent of the applicable limits.
Doses for releases of iodines and particulate shall be calculated using the methodology in Section 1.1.1, step 1, part B, with the following exceptions:
- 1. All measured radionuclides re aes will be used.
C
, ( 2. Dose will be evaluated at real cow locations and will consider
'- actual g'azing r 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 I calculated for each month in that quarter. Calendar year doses are first estimated by summing the doses calculated for each month in that year.
However, if the annual doses determined in this manner exceed or approach the specification limits, doses calculated for previous quarters with the methodology of section 1.4 will be used instead of the dosea estimated by summing monthly results.
1.3 Dose Projections In accordance with specification 3.11.2.4, dose projections will be .
performed. This will be done by averaging the calculated dose for the '
most recent month and the calculated dose for the previous month and assigning that average dose as the projection for the current month.
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1.4 Qyarteriv and Annual Dose Calculations A complete dose analysis utilizing the total estimated gaseous releases for each calendar quarter will be performed and reported as required in j 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 1.4) are considered. In addition, meteorological data representative of a ground level release for each corresponding calendar quarter will be used. This analysis will replace the estimates in Section 1.2.
At the end of the year an annual dose analysis will be performed by calculating the sum of the quarterly doses to the critical receptcrs.
1.5 Gaseous Radwaste Treatment System Ongration The gaseous radvaste treatment system (GRTS) described below shall be maintained and operated to keep releases ALARA.
1.5.1 Rystem Description A flow diagram for the GRTS is given in Figure 1.3. The system consists of two waste-gas compressor packages, nine gas decay tanks, and the associated piping, valves, and instrumentation. Gaseous vastes 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. .
1.5.2 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.
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\v} l 2.0 Liauld Effluents 2.1 Concentration 4 2.1.1 RETS Requirement Specification 3.11.1.1 of the Radiological Effluent Technical Specifications (RETS) requires that the concentration of radioactive material released at any time from the site to unrestricted areas shall be limited to the Maximum Permissible Concentration (MPC) specified in 10 CFR 20, Appendix B, Table II, Column 2 for nuclides other than dissolved cc entrained noble gases. For dissolved or entrained noble gases, t'ne concentration shall be limited to 2x10-4 pCi/mL total activity. To ensure compliance, the following approach will be used for each release.
2.1.2'?Igrelease Ana,1ysis Most tanks will be recirculated through two volume changes prior to sampling to ensure that a representative sample is obtained. Because of the.Ti size, the high crud tanks, non-reclaimable waste tank, and cask decontamination tank will not necessarily be reticulated through two volumes. An appropria?.d recirculation time for these tanks will be 7_ determined by a ont time test. The tank will be recirculated and l j periodically samphed for suspended particulate during the test. The
( _ ,/ appropriate recirestatica time will be the time that the suspended particulate concentration reaches steady state. The condensate
~
deminersitier vaste evaperator blowdown tank cannot be recirculated.
However the coni?nts of the tuJ , will be under administrative control and could'be c.rgnsihrred 'to the distfilate tanks prior to release.
Prior to : release a grab sample vill be analyzed for each release point for, the concentration of each radionuclides, rf Ci=}Ci 'at (2.1) where:
Gj = Total concentration in the liquid effluent at release point j, pC1/mL.
Cg = concentration of radionuclides i, pCl/nb. '
O l
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SQN ODCM g 1 - Page 23 of 85 Revision 17 l [mV} ;
i
{
2.1.3 MPC-Sum of the Ratios There are two possible release points into the river, the turbine building sump and the cooling tower blowdown. The cooling tower blowdown is further subdivided into four separate liquid release paths as chown below.
Radwaste ft )
1 p Condensate Demineralized fz a {
1 Steam Generator Blowdown ^
Es Cooling Tower Blowdown F
Steam Cenerator Blowdown f4 V
The sum of the ratios (Rj) for each release point will be calculated by ,
i the following relationship.
)
Ci RJ=1 (2.2) g MPCi where:
f Rj = the sum of the ratios for release point J.
Ci = effluent concentration of radionuclides i, pCi/mL. For the turbine building sump, this will be the diluted concentration determined by daily grab sampling. For releases into the f cooling tower blowdown, this will be the undiluted concentration in the tank as determined in Section 2.1.2.
l MPCi = the MPC of radionuclides i, as specified in Section 2.1.1, pCi/mL.
For releases into the cooling tower blowdown, the sum of the MFC ratios must be 1 1 due to the releases from any or all of the four release paths shown above. The following relationship will assure this criterion is met:
f1R1 + f2R2 + f3Rs + f4R4 1 (2.3)
F where: i c
ft,f2,fs,f4 = the effluent flow rate at the respective release point as determined by plant personnel, gallons / minute.
R1,R2,Rs,R4 = the sum of the ratios of the respective release points as determined by Equation 2.2.
[ F = minimum dilution flow rate for prerelease analysis (cooling
( tower blowdown) = 15,000 gallons per minute.
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2.2 Instrument Setooints 2.2.1 Setooint Determination The setpoint for each liquid effluent monitor will be established using plant instructions. Concentration, flow rate, dilution, principal gamma emitter, geometry, and detector efficiency are combined to give an equivalent setpoint in counts per minute (cpm). The physical and technical description location and identification number for each liquid effluent radiation detector is contained in plant documentation.
The respective alarm / trip setpoints at each release point will be set such that the sum of the ratios (Rj) for all points, as calculated by Equation 2.3, will not exceed 1. The RJ is directly related to the tatal concentration calculated by Equation 2.1. An increase in the concentration would indicate an increase in the respective Rj. A large increase would cause the limits specified in Section 2.1.1 to be exceeded. The minimum alarm / trip setpoint value is equal to the release concentration, but for ease of operation it may be desired that the setpoint(s) be set above the effluent concentration (Cj). That is, Sj = bj (Cj + B) (2.4) im \
( where
\ -
Sj = desired alarm / trip setpoint at release point J.
bj = scaling factor to prevent alarms / trips due to variations in the effluent concentrations at release point J.
Gj = monitor response based on the total concentration in the liquid effluent at release point j specified by Equation 2.1, pCi/mL.
B = monitor background prior to release.
2.2.2 Post-Release Analysis l
A post-release analysis will be done using actual release data to ensure that the limits specified in Section 2.1.1 were not exceeded.
A composite list of concentrations (C 1), by isotope, will be used with C
the actual liquid radwaste (f) and dilution (F) flow rates (or volumes) during the release. The data will be substituted into Equation 2.3 to demonstrate complience with the limits in Section 2.1.1. This data and setpoints will be recorded in auditable records by plant personnel.
/)
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I SQN ODCM Page 25 of 85 i f') Revision 17
)
2.3 Eg_sg 2.3.1 BETS Requirements Specification 3.11.1.2 of the Radiological Effluent Technical Specification (RETS) requires that the dose or dose commitment to an individual from radioactive materials in liquid effluents released to unrestricted areas from each reactor shall be limited:
- 1. During any calendar quarter to 1 1.5 mrem to the total body and to I 5 mrem to any organ, and
- 2. During any calendar year to 1 3 mrem to the total body and to 1 10 mrem to any organ.
To ensure compliance, cumulative dose calculations will be performed at least once per month according to the following methodology.
2.3.2 Monthly Analysis Principal radionuclides will be used to con;ervatively estimate the monthly contribution to the cumulative dose. If the projected dose f-- exceeds the above limits, the methodology in Section 2.3.3 will be l
implemented.
\
- The 20 nuclides (listed below) contribute more than 95 percent of the dose to the total body and the most critical organs for each pathway.
The critical organs considered for water and fish ingestion are the gastrointestinal tract (GIT), bone, thyroid and liver.
H-3 Na-24 Cr-51 Mn-54 Fe-55 Fe-59 Co-58 Co-60 Zn-65 Sr-89 Sr-90 Zr/Nb-95 Mo/Tc-99m Ag-110m Sb-124 I-131 I-133 Cs-134 Cs-136 Cs-137 A conservative calculation of the monthly dose will be done according to the following procedure. First, the monthly release data will be obtained and the activities released of each of the above 20 radionuclides, if identified, will be noted. This information will then be used in the following calculations. ,
\
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l SQN ODCM ON Page 26 of 85 Revision 17 2.3.2.1 Water Ingestion The dose to an individual from ingestion of water is described by the following equation.
1 y 20 (4k = { DCFi jk lik (2.5) 0.95 g,y ;
where:
Djk = dose for the jth organ from 20 radionuclides, rem.
J = the organ of interest (bone, GI tract, liver, thyroid and total body).
k = the age group being considdred, adult or child.
0.95 = conservative correction factor, considering only 20 radionuclides.
DCFi jk = critical ingestion dose commitment factor for the ith p radionuclides for the jth organ for the kth age group,
- rem /pC1, (Table 2.1).
Gj ,
Iik = monthly activity ingested of the ith radionuclides by the kth age group, pC1. ;
Igj is described by
. 1 At Vk (30)
Iik = (2.6)
F d (7.34x1010) where:
Ag = activity released of the ith radionuclides during the month, pCi. j l
Vk = maximum individual's water consumption rate corresponding to the kth age group selected for the critical DCF ijk above (
(Adult: 2000 mL/d, Child: 1400 mL/d; Regulatory Guide 1.109). .
c 30 = days per month.
F = average river flow at Chickamauga Dam for the month (cubic feet per second).
d = fraction of river flow available for dilution (1/5).
( 7.34x1010 = converts cubic feet per second to milliliters per month.
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('~~ Revision 17
=t t
s.,
Considering the conversion factor from rem to mrrm, the dose equation
, then becomes:
1 20 Djk " 2.15x10-6 1Yk DCF jk Ai i (2*7}
F i.
i=1 l
2.3.2.2 Fish Inzestion The dose to an individual from the consumption of fish is described by j Equation 2.11. In this case the activity ingested of the ith radionuclides (Ii y) is described by lik = .. (2.8)
F d (7.34x1010) where Ai = activity released of ith radionuclides during the month, pCi.
/*
i Bi = effective fish concentration factor for the ith radionuclides pCi/g per pCi/mL (Table 2.2).
Mk = amount of fish eaten monthly by maximum individual corresponding to the kth age group selected for the critical DCFi k above (Adult: 1750g, Child: 5,75g ;
Regulatory Gu de 1.109). J F = average river flow at Chickamauga Dam for month (cubic feet per second),
d t
= fraction of river flow available for dilution (1/5).
7.34x1010 = converts from cubic feet per second to milliliters per month.
Considering the conversion factor from rem to mrem, the dose equation then becomes
- c 20 7.17x10-a Djk
- 1Al Bi Mk DCF jk i (2.9)
F g,1 s
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/ 3 Revision 17 )
s_-
Recreation i' The total body dose to an individual via the shoreline recreation pathway is described by the following equatien. For this calculation, the total !
dose is estimated based on a calculation for Co-58, Co-60, Cs-134, and Cs-137. These four nuclides are expected to contribute over 95 percent of the recreation dose. ;
0.1 D= 1 RCDFi (i 67 0.95 g,y 8760 (2.10) where D
= shoreline recreation dose to the total body from plant releases, mrem.
1 0.95 = c nserva ive c rrect n actor, considering only 4 radionuclides.
RDCri = shoreline recreation dose commitment factor for the ith radionuclides, mrem /yr per pCi/cm2 (Table 2.3). i
, (Note: For Cs-137, the dose commitment factor for its
[ daughter, Ba-137m, is assumed.)
\
- 67
= assumed monthly exposure time for maximum individual, h.
= 500 h/ year x 0.4 (fractional exposure for worst quarter)
+ 3 (months / quarter).
8760 = conversion from year to hours. .
j 0.1 = conversion factor combining conversions for m2/cm2 and mL/L.
1 (i = concentration of ith radionuclides in shoreline sediment (pCi/cm2 ), as described by the following equation (based on equation A-5 in Regulatory Guide 1.109).
= 100 RHLi Ci W [1-exp (-11 t)] (2.11) uhere:
100 = transfer2 constant defined in Regulatory Guide 1.109, '
L per m -day.
RHLi = radiological half-life of the ith radioisotope, days, from Table 2.1.
W = shoreline width factor (0.3 for a lake shore, per Table
[ A-2 of Regulatory Guide 1.109).
t 1157c
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Xi = decay constant of the ith radionuclides
= 0.693/RIILi .
t
= buildup time in sediment, assumed 15 years, per Regulatory l Guide 1.109.
Ci = concentration of ith radionuclides in the Tennessee River, pCi/mL.
= Ai /(F d 7.34x1010) where A1 = activity released of ith radionuclides during the month, pCi.
F
= average river flow at Chickamauga Dam for the month, cubic feet per second.
d
= fraction-of river flow available for dilution (1/5).
7.34x1010 = cubic feet per second to milliliters per month.
1he dose equation then becomes f .
D=
(0.00692 A1 + 0.00012 A2 + 0.00206 A3 + 0.00342 A4 ) (2.12) where A1, A2, A3, A4 = the activities of Co-60, Co-58, Cs-134 and Us-137 respectively.
2.3.2.4 Monthly Summary 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 year.
Ilowever, if the annual doses determined in this manner exceed or approach the specification limits, doses caelulated for previous quarters with the methodology of section 2.3.3 will be used instead of those quarterly doses 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 principal isotopes will be prepared or a new correction factor will be used. The latter option will not be used if less than 90 percent of the total dose is predicted.
/
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- ) Revision 17 2.3.2.5 Dose Projections In accordance with specification 3.11.1.3, dose projections.will be performed. This will be done by averaging the calculated dose for the most recent month and the calculated dose for the previous month and assigning that average dose as the projection for the current month.
b 2.3.3 Ouarteriv and Annual Analysis A complete analysis utilizing the total estimated liquid releases for
~
each calendar quarter will be performed and reported as required in !
l 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.
l 1
2.3.3.1 Individual Doses The. dose, Djke.to the maximum individual from n nuclides is described by:
i 5 n
,~ , Djk = } } ' D ijkm (2.13)
/ m=1 i=1 i
n' 2 5 Dj k = 2 { [DCF i jk Iikm) + 1 [RDCFi jm Elm Tm 9] (2.14) i=1 m=1 m=3 where:
l Di jkm = dose to the jth organ for the kth age group from the ith radionuclides via the mth exposure path, j = the organ of interest (bone, GI tract, thyroid, liver, total body and skin).
k = the age group being considered: adult and child for the ingestion pathways; adult for the recreation pathways, m = exposure pathway of interest:
- 1. water ingestion, .
- 2. fish ingestion, L
- 3. shoreline recreation,
- 4. above water recreation, and
- 5. in-vater recreation.
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'N,_,):
(LCF)ijk = ingestion oose commitment factor for the jth organ from the ith radionuclides for the kth age group, rem /pCi (Table 2.1).
(RDCF)ijm = recreation dose commitment factor for the jth organ t from the ith radionuclides via the mth pathway; mrem /yr per pCi/cm2, (Table 2.3).
Tm = assumed exposure time of maximum individual for the mht 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).
9 = Fraction of annual recreation exposure for each quarter 1st Quarter January-March 0.1 2nd Quarter April-June 0.3 3rd Quarter July-September 0.4 4th Quarter October-December 0.2.
Iikm = The activity ingested of the i h tradionuclides, via the mh t exposure pathway for the kth age group, pC1.
=Ci Vk N for the water ingestion pathway (2.14) r- =Ci Bi Mk for the fish ingestion pathway (2.15)
( .
where:
l
= water consumption for the kth age group, per Vk Regulatory Guide 1.109 for maximum individual:
l adult - 2000 mL/d ,.
child - 1400 mL/d for average individual (population):
adult - 1010 mL/d child - 710 mL/d.
N = number of days during the releas:e period, da/.
Bi = bioaccumulation factor for the ith radionuclides in fish, pC1/g per pCi/mL (Table 2.2).
Mk = amount of fish consumed during the period for the k t h age group (fraction of year times the annual consumption rate per Regulatory Guide 1.109) c' for maximum individual:
adult - 21 kg/yr l
child - 6.9 kg/yr for average individual (population):
adult - 6.9 kg/yr child - 2.2 kg/yr.
t 1157c l
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\ Revision 17 Ci = concentration of the ith radionuclides during the release period, pCi/mL
= Ai /(Fgd).
1 where:
Ai = Activity released of ith redionuclide during the release period, pC1.
Fg = Total river flow at location 1 during period, mL.
E
= Location of interest (For dose to the maximum individual the first down-river exposure point is used. For the population dose, various down-river locations are used to account for the total exposed population. Table 2.4 gives the river location of public water supplies; Tables 2.5 and 2.6 give the boundaries of the various reaches in which concentrations are calculated for the fish and recreation pathways).
\
[ d
( '
= fraction of river flow available for dilution (0.20 above Chickamauga Dam, 1 below the dam).
(im = the concentration of the ith radionuclides in the environmental medium pertaining to mth pathway.
= (15 = C1 , for above-water and in-water -
recreation pathways;
= 100 FHLi Ci W [1-exp(-li t)], for the shoreline recreation pathway; .
where:
j 100 = transfer constant as defined in Regulatory Guide 1.109 'i equation A-4, L per m2-day.
RHLi = radiological half-life of the ith isotope, days, (Table 2.1).
Ci = concentration of the ith nuclide in water, pCi/mL. '
W = shoreline width factor (0.3 for a lake shore, per Table A-2 of Regulatory Guide 1.109).
,r x
(
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[ Revision 17 Q]/ .
Ai = decay constant of the ith radionuclides
= 0.693/RHLi .
t
= buildup time in sediment, assumed 15 years, per Regulatory Guide 1.109.
l 2.3.3.2 Population Doses l
l The. total population dose, aj, from all 5 pathways to the jth organ of the population from n nuclides at p locations is described by:
p 5 n Oj" 1 2 1 O ljmle (2.17) 1=1 m=1 i=1 l .
p 5 n Oj= 1 2 2 D ijm1 Pm1, 1=1 m=1 i=1 (2.18) where:
aj = total population dose to the Tennessee River Valley population, man-rem.
aijm1 = dose to the jth organ of the total population from the ith radionuclides via the mth pathway at location 1.
- Di jm1 = dose to individual (as described in Section 2.3.3.1) at location 1.
Pi = number of people at location 1 (Tables 2.4, 2.5 !
and 2.6). The population is assumed to consist of 71-percent adults and 29-percent children (from Appendix D, Regulatory Guide 1.109, the value for children includes teenagers).
c I
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._ / . Revision 17 t
2.4 Operability of Liould Radwaste Eouinment Specification 3.11.1.3 of the Radiological Effluent Technical Specification requires that the liquid radwaste system shall be used to reduce the radioactive materials in liquid wastes prior.to their discharge when the projected dose due to liquid effluent releases to unrestricted areas when averaged over 31 days would exceed 0.06 mrem to the total body of 0.21 mrem to any organ. -Doses will be projected monthly to assure compliance.
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s Revision 17 U) 3.0 Ra_dlolozical q Eh!,c p!.ynental Monitorina i
3.1 MqniLqtinn Pronrara An environmental radiological monitoring program shall be conducted in_accordance with Technical Specification 3.12.1. The monitoring i program described in Tables 3.1, 3.2, and 3.3, and in Figures 3.1, 3.2, 3.3, 3.4, 3.5, and 3.6 shall be conducted. 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 monitoring stations from which samples of air particulate and atmospheric radiciodine 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 Vill 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 f'. 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 .
Analytical techniques shall be such that the detection capabilities listed in Table 3.4 are achieved.
3.3 Interlaboratory Comparison Pronram Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program which has been approved by the NRC. A summary of the results obtained in the intercomparison shall be included in the Annual Radiological Environmental Operating Report (or the EPA program code designation .
may be provided). L If analyses are not performed as required corrective actions taken to prevent a recurrence shall be reported in the Annual Radiological Environmental Operating Report.
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3.4 Land Use Census A land use survey shall be conducted in accordance with SQN Technical Specification 3/4.12.2. The results of the survey shall be reported in the Annual Radiological Environmental Operating Report, i
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SQN ODCM Page 37 of 8S f'"% Revision 17
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4.0 Annual Maximum Individual Doses - Total 1 To determine compliance with 40 CFR 190, the annual dose contributions to the maximum individual from SQN radioactive j effluents and all other nearby uranium fuel cycle sources will be considered. The annual dose to the maximum individual will '
be conservatively estimated by first, summing the quarterly total body air submersion dose, the quarterly critical organ j dose from gaseous effluents, the quarterly total body dose from liquid effluents, the quarterly critical organ dose from liquid effluents, and the direct radiation monitoring program, and then taking the sum for each quarter and summing over the four quarters.
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( l Revision 17 Table 1.1-EXPECTED ANNUAL ROUTINE GASEOUS RELEASES FROM ONE UNIT AT SEQUOYAH NUCLEAR PLANT Curies / year AUXILt.\RY TURBINE NUCLIDE BUILDINJ SERVICE CONTAINMENT BUILDING Kr-85m 2.2E-00 BUILDING 2.3E-00 1.5E-00 6.0E-02 Kr-85 2.0E-00 5.1E-02 Kr-87 1.2E 5.1E-00 1.2E-00 8.1E-01 8.2E-01 Kr-88 4.1E-00 2.8E-02 3.6E-00 2.7E-00 1.0E-01 Kr-89 2.7E-02 8.3E-03 Xe-131m 6.4E-02 9.0E-04 1.7E+00 2.6E+01 1.1E+00 Xe-133m 3.7E+00 2.9E-01 1.6E+01 2.4E+00 2.2E-01 Xe-133 2.9E+02 2.4E+03 Xe-135m 1.8E+02 2.9E+01 1.8E+01 7.8E-02 2.0E-01 Xe-135 6.8E+00 1.8E-01 9.9E+00 4.4E+00 2.lE-01 Xe-137 5.6E-02 1.8E-02 -
Xe-138. 1.2E-01 1.9E-03 5.9E-01 2.4E-01 6.2E-01 Br-84 3.5E 1.5E-02 4.9E-06 1.7E-05 3.7E-06 B r-85 1.2E-05 1.3E-07 I-131 2.4E-07 1.2E-07 4.5E-02 1.2E-02 9.2E-03 I-132 1.7E-02 6.6E-04
' 3.7E-04 2.6E-03 2.0E-04 I-133 6.5E-02 3.3E-03 I-134 1.4E-02 8.2E-04 7.1E-03 1.1E-04 5.0E-04 i 'I-135 3.3E-02 7.7E-05 9.0E-04 5.4E-03 3.9E-04 Rb-88 1.6E+00 2.1E-02 Cs-134 1.0E-04 1.6E-02 5.5E-05 1.1E-05 6.4E-05 Cs-136 2.9E-05 1.3E-06 2.6E-06 3.6E-05 6.8E-07 Cs-137 '4.0E-05 7.8E-06 Cr-51 5.3E-05 1.0E-06 2.0E-06 2.6E-07 3.6E-07 Mn-54 1.6E-06 2.6E-08 3.1E-07 4.5E-07 2.4E-08 Fe-59 2.lE-06' 3.2E-07 Co-58 5.4E-07 3.0E-08 5.3E-07 8.8E-08 9.0E-06 Co-60 1.6E-06 9.6E-08 3.1E-07 2.7E-07 2.2E-08 Sr-89 7.6E-07 1.2E-07 Sr-90 1.6E-07 1.0E-08 2.2E-08 4.3E-09 8.4E-09 Sr-91 1.5E-06 3.5E-10 1.2E-08 8.9E-08 1.6E-08 Y-90 3.8E-08 4.7E-09 Y-91m 8.2E-09 5.1E-10 9.1E-07 7.4E-09 4.13-08 Y-91 4.4E-06 9.6E-09 7.0E-07 1.9E-06 7.0E-08 Y-93 3.0E-07 2.4E-09 3.6E-08 Zr-95 1.3E-07 3.4E-09 2.1E-08 8.4E-08 2.4E-09 Nb-95 1.1E-07 2.2E-08 8.4E-08
. t Mo-99 9.9E-04 2.2E-09 '
3.0E-05 1.4E-04 1.2E-05 Tc-99m 8.9E-04 2.8E-05 1.0E-04 Ru-106 1.0E-05 2.2E-08 4.1E-09 8.4E-09 Te-132 3.5E-10 6.0E-05 2.0E-06 2.1E-05 Ba-140 8.3E-07 4.8E-07 4.4E-08 2.lE-07 7.3E-09 La-140 3.4E-07 4.6E-08 1.4E-07 Ce-144 5.3E-09 7.2E-08 1.4E-08 4.2E-08 1.3E-09 Pr-143 1.1E-07 1.1E-08 4.2E-08
\ Pr-144 1.6E-09 7.7E-08 1.4E-08 2.8E-08 1.2E-09 Np-239 2.7E-06 7.0E-08 1.2E-06 4.0E-08 i l
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_ Revision 17 :
a Table 1.2 (1 of 2)
BASIC RADIONUCLIDES DATA
\
Half-Live LAMBDA BETA GAMMA Nuclide (Days) (1/s) (MeV/ DIS) (MeV/ DIS)
H-3 4.49E+03 1.79E-09 5.68E-03 0.0 3 C-14 2.09E+06 3.84E-12 5.17E-02 0.0 N-13 6.94E-03 1.16E-03 4.91E-01 1.02E+00 0-19 3.36E-04 2.39E-02 1.02E+00 1.05E+00 P-18 7.62E-02 1.05E-04 2.41E-01 9.88E-01 Na-24 6.33E-01 1.27E-05 5.55E-01 4.12E+00 P-32 1.43E+01 5.61E-07 6.95E-01 0.0 Ar-41 7.63E-02 1.05E-04 3.63E-01 1.28E+00 Cr-51 2.78E+01 2.89E-07 3.75E-03 3.28E-02 Mn-54 3.03E+02 2.65E-08 4.17E-03 8.36E-01 Mn-56 1.07E-01 7.50E-05 7.93E-01 1.76E+00 !
Fe-59 4.50E+01 1.78E-07 -
1.18E-01 1.19E+00 Co-58 7.13E-01 1.12E-07 2.05E-01 9.76E-01 Co-60 1.92E-03 4.18E-09 9.68E-02 2.50E+00 Zn-69m 5.75E-01 1.39E-05 0.0 4.15E+00 Zn-69 3.96E-02 2.03E-04 3.19E-01 0.0 Br-84 2.21E-02 3.63E-04 1.28E+00 1.68E+00 Br-85 2.08E-03 3.86E-03 1.04E+00 8.40E-01 f
Kr-85m 1.83E-01 4.38E-05 2.53E-01 1.59E-01
\s Kr-85 3.93E+03 2.04E-09 2.51E-01 2.21E-03 Kr-87 5.28E-02 1.52E-04 1.32E+00 7.93E-01 Kr-88 1.17E-01 6.86E-05 3.75E-01 1.96E+00 Kr-89 2.21E-03 3.63E-01 1.23E+00 2.08E+00 Rb-88 1.24E-02 6.47E-04 2.06E+00 6.86E-01 Rb-89 1.07E-02 7.50E-04 0.0 2.40E+00 Sr-89 5.20E+01 1.54E-07 5.73E-01 1.36E-04 Sr-90 1.03E+04 7.79E-10 1.96E-01 0.0 l
Sr-91 4.03E-01 1.99E-05 6.50E-01 6.95E-01 Sr-92 1.13E-01 7.10E-05 1.95E-01 1.34E+00 Sr-93 5.56E-03 1.44E-03 1.61E+00 6.28E-01 Y-90 2.67E+00 3.00E-06 9.36E-01 0.0 Y-91m 3.47E-02 2.31E-04 0.0 5.56E-01 Y-91 5.88E+01 1.36E-07 6.06E-01 3.61E-03 Y-92 1.47E-01 5.46E-05 1.44E+00 2.50E-01 Y-93 4.29E-01 1.87E-05 1.17E+00 8.94E-02 Zr-95 6.50E+01 1.23E-07 1.20E-01 7.35E-01 Nb-95m 3.75E+00 2.14E-06 2.85E-01 5.87E-02 .
Nb-95 3.50E+01 2.29E-07 4.50E-02 7.64E-01 '
Mo-99 2.79E+00 2.87E-06 3.96E-01 1.62E-01 Tc-99m 2.50E-01 3.21E-05 4.85E-03 1.43E-01 Tc-99 7.74E+07 1.04E-13 8.38E-02 0.0 Tc-104 1.25E-02 6.42E-04 0.0 0.0 !
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Page 40 of 85 y'~'N, Revision 17 i
V)
Table 1.2 (2 of 2)
BASIC RADIONUCLIDES DATA Half-Live LAMBDA BETA GAMMA Nuclide (Days) (1/s) (MeV/ DIS) (MeV/ DIS)
Ru-106 3.67E+02 2.19E-08 1.01E-02 0.0 Te-132 3.24E+00 2.48E-06 1.00E-01 I-129 2.05E-01 6.21E+09 1.29E-15 4.20E-02 3.77E-03 I-131 8.08E+00 9.96E-07 1.94E-01 MI-131 3.81E-01 l 8.05E+00 9.96E-07 1.94E-01 3.81E-01 1-132 9.58E-02 8.37E-05 5.14E-01 2.33E+00 MI-132 9.58E-02 8.37E-02 5.14E-01 2.33E+00 I-133 8.75E-01 9.17E-06 4.08E-01 6.10E-01 MI-133 8.75E-01 9.17E-06 4.082-01 1-134 6.10E-01 3.61E-02 2.22E-04 6.10E-01 2.59E+00 MI-134 3.61E-02 2.22E-04 6.10E-01 2.59E+00 I-135 2.79E-01 2.87E-05 "
3.68E-01 1.58E+00 MI-135 2.79E-01 2.87E-05 3.68E-01 1.58E+00 Xe-131m 1.18E+01 6.80E-07 1.43E-01 2.01E-02 Xe-133m 2.26E+00 3.55E-06 1.90E-01 4.16E-02 Xe-133 5.27E+00 1.52E-06 1.35E-01 4.54E-02 Xe-135m 1.08E-02 7.43E-04 9.50E-02 4.32E-01
,, ~s Xe-135 3.83E-01 2.09E-05 3.17E-01
/ 2.47E-01 j Xe-137 2.71E-03 2.96E-03 1.64E+00 1.94E-01
( ,/ Xe-138 1.18Ew02 6.80E-04 6.06E-01 1.18E+00 Cs-134 7.48E+02 1.07E-08 1.57E-01 1.04E+00 Cs-135 1.10E+09 7.29E-15 5.74E-02 0.0 Cs-136 1.30E+01 6.17E-07 1.01E-01 2.20E+00 Cs-137 1.10E+04 7.29E-10 2.52E-01 5.97E-01 Cs-183 2.24E-02 3.58E-04 1.23E+00 2s30E+00 Ba-139 5.76E-02 1.39E-04 6.54E-02 5.05E-02 Ba-140 1.28E+01 6.27E-07 3.15E-01 1.95E-01 La-140 1.68E+00 4.77E-06 5.40E-01 2.31E+00 Ce-144 2.84E+02 2.82E-08 9.13E-02 3.29E-02 Pr-143 1.36E+01 5.90E-07 3.14E-01 0.0 Pr-144 1.20E-02 6.68E-04 1.23E+00 3.10E-01 Np-239 2.35E+00 3.41E-06 1.24E-01 2.08E+00 c'
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Table 1.4 l
SQN - 0FFSITE RECEPT 0R LOCATION DATA l DIST ELEV X/Q D/Q POINT SECTOR (m) l 1 Land Site Boundary (m) (s/m 3
) (1/m23 N 950 -6. 5.12E-06 2 Land Site Boundary 1.29E-08 NNE 2250 -6 1.93E-06 5.2BE-09 3 Land Site Boundary NE 1910 -6. 2.32E-06 4, Land Site Boundary 6.33E-09 ENE 1680 -6. 1.12E-06 2.64E-09 5 Land Site Boundary E 1510 -6. 7.10E-07 6 Land Site Boundary 1.46E-09 ESE 1460 -6. 7.91E-07 1.58E-09 7 Land Site Boundary SE 1460 9.14E-07 8 Land Site Boundary
-6. 2.41E-09 SSE 1550 -6. 1.34E-06 3.23E-09 9 Land Site Boundary S 1570 -6. 2.37E-06 10 Land Site Boundary 4.18E-09 ,
SSW 1840 -6, 4.51E-06 11 Land Site Boundary SW 9.26E-09 2470 -6. 1.38E-06 2.63E-09 12 Land Site Boundary VSW 910 -6, 2.93E-06 13 Land Site Boundary 3.86E-09 W 670 -6 3.63E-06 14 Land Site Boundary 3.74E-09 WNW 66&- -6. 2.49E-06 15 Land Site Boundary 2.44E IN 660 -6. 2.25E-06 16 Land Site Douadiry 3.67E-09 NNW 730 -6. 3.95E-06 17 Resident, Sardin' 6.59E-09 N 1370- O. 2.93E-06 7.10E-09 18 Resident
- NNE 2710" 0.
19 Resident, Garden 1.49E-06 3.88E-09 NE 3430 15. 1.01E-06 2.33E-09 20 Resident ENE 2290 0.
21 Resident 7.13E-07 1.57E-09 E 1790 i. 5.85E 1.18E-09 22 Resident ESE 1790 46.'
3.86E-07 1.14E-09 23 Resident SE 1680, 24 Resident, Garden O. 7.42E.d7 1.92E-09 SSE 2210 45 7.99E-07 1.74E-09 25 Resident S 2020 b. 1.65E 06 26 Resident, Garden 2.75E-09 SSW 2670. O. 2.66E-06 ,A ,9 '.E-09 27 Resident SW 3010 0. 1.04E-06 II 28 Resident, Garden d.83E WSW 1140 8. 2.09E-06
! 29 Resident, Garden 2.67E-09 W 1750 47. 8.53E rt' 30 Resident, Garden 7.32TA 0
. WNil 1750 12. 5.71E~07 "y 31 Resident NW 1140 11. 1.25E-06 #<# 4.98E-10 '
32 Resident NIN /,. 1.50E-09
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NEL*3 1.28E-06 K24EJ09 34 Carden E -
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IN 1180 11 1.19E-06 41 Garden b.A2E E09 * '
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- -1 i Te.ble 1.5 .
Ik' DOSE TACIORS FOR SUBMERSION IN MGELE GASE3 '
,, jlfB"_ D?Sa __
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Kr-85 ' l . 6'J.+ 01 1,69E+01 l 1.34E+03 3.83E+03 Kr-87 f. 9 2h'+ 0 3 - 6.05E+03 9.73E+03 2.01E+04
'Tr-86 ! LATDd4 ' 1.50E+04' 2.37E+03 5.72E+03 Kr-8HiD -- - 2.02E+04, ---
3.72E+04 Kr-89 1.6 Gi$5- 1.59E+/J4$. 1.01E+04 1.88E+04 Xe-131m 9.15E+01 1.53E+02'.' 4.76E+02 2.18E+03 Xe-133m 2.51E402~ 3.17E+02 9.94E+02 2.90E+03 Xe-133 2.94E+02 3.46E+02 3.06E+02 2.06E+03 Xe-135m- 3.12E+03 '
3.30E+03 7.11E+02 1.45E+03 Xe-135 1.81E+03 1.88E+03 1.86E+03 4.34E+03
( Xe -137. -
Xe-138 '-
1.42E+03 8.83r+03 1.48E+03 9.00E+03 -
1.22E+04 4.13E+03
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Xe-1384 'i . . - - 2.65E+04 ---
2.81E+04
'I j Ar-41 8.i,41.503 9.76E+03 2.69E+03 5.54E+03 t-A.
a mres/yr per pCi/m 8 ,
& D mrad /yr per pCi/m 8 (y U.,,1.17E+03 = 1.17 X 108 .
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1157c
'l Revision 17
(
Table 1.6 (1 of 2)
NUCLIDE SPECIPIC TRANSFER DATA
- l NUCLIDE RETENTION
- By(fff{}
i U
FMi (g) 1 Tritium 4.70E-01 4.80E+00 1.30E-02 2 C-14 4.70E-01 5.50E+00 1.20E-02 3 N-13 4.70E-01 7.50E+00 2.20E-02 4 0-19 4.70E-01 1.60E+00 2.00E-02 5 F-18 4.70E-01 6.50E-04 1.40E-02 6 Na-24 .4.70E-01 5.20E-02 4.00E-02 1 7 P-32 4.70E-01 1.10E+00 2.50E-02 8 Ar-41 4.70E-01 6.00E-01 2.00E-02 9 Cr-51 4.70E-01 2.50E-04 2.20E-03 10 Mn-54 4.70E-01 2.90E-02 2.50E-04 11 Mn-56 4.70E-01 2.90E-02 2.50E-04 12 Fe-59 4.70E-01 6.60E-04 1.20E-03 13 Co-58 4.70E-01 9.40E-03 1.00E-03 14 Co-60 4.70E-01 9.40E-03 1.00E-03 15 Zn-69m 4.70E-01 4.00E-01 3.90E-02 16 Zn-69 4.70E-01 4.00E-01 3.90E-02 17 -Br-84 4.70E-01 7.60E-01 5.00E-02
-~ 18 Br-85 4.70E-01 7.60E-01 5.00E-02 fN, 19 20 Kr-85m Kr-85 4.70E-01 3.00E+00 2.00E-02 4.70E-01 3.00E-00 2.00E-02 21 Kr-87 4.70E-01 3.00E-00 2.00E-02 22 Kr-88 4.70E-01 3.00E-00 2.00E-02 23 Kr-89 4.70E-01 3.00E-00 2.00E-02 24 Rb-88 4.70E-01 1.30E-01 3.00E-02 25 Rb-89 4.70E-01 1.30E-01 3.00E-02 26 Sr-89 4.70E-01 1.70E-02 1.40E-03 27 Sr-90 4.70E-01 1.70E-02 1.40E-03 28 Sr-91 4.70E-01 1.70E-02 1.40E-03 29 Sr-92 4.70E-01 1.70E-02 1.40E-03 30 Sr-93 4.70E-01 1.70E-02 1.40E-03 31 Y-90 4.70E-01 2.60E-03 1.00E-05 32 Y-91m 4.70E-01 2.60E-03 1.00E-05 33 Y-91 4.70E-01 2.60E-03 1.00E-05 34 Y-92 4.70E-01 2.60E-03 1.00E-05 35 Y-93 4.70E-01 2.60E-03 1.00E-05 36 Zr-95 4.70E-01 1.70E-04 5.00E-06 37 Nb-95m 4.70E-01 9.40E-03 2.50E-03 ,
38 Nb-95 4.70E-01 9.40E-03 2.50E-03 C 39 Mo-99 4.70E-01 1.20E-01 7.50E-03 40 Tc-99m 4.70E-01 2.50E-01 2.50E-02 41 Tc-99 4.70E-01 2.50E-01 2.50E-02 42 Tc-104 4.70E-01 2.50E-01 2.50E-02 43 Ru-106 4.70E-01 5.00E-02 1.00E-06 44 Te-132 4.70E-01 1.30E+00 1.00E-03 45 I-129 4.70E-01 2.00E-02 1.20E-02
/ 46 I-131 4.70E-01 2.00E-02 1.20E-02 47 MI-131 4.70E-01 2.00E-02 1.20E-02 1157c
(
[' 'T 1 Revision 17 Ns_ '
Table 1.6 (2 of 2)
NUCLIDE SPECIFIC TRANSFER DATA
- NUCLIDE RETENTION
- B iy(fff*) FM(f) i 48 I-132 4.70E-01 2.00E-02 1.20E-02 49 MI-132 4.70E-01 2.00E-02 1.20E-02 50 I-133 4.70E-01 2.00E-02 1.20E-02 51 MI-133 4.70E-01 2.00E-02 1.20E-02 52 I-134 4.70E-01 2.00E-02 1.20E-02 53 MI-134 4.70E-01 2.00E-02 1.20E-02 54 I-135 4.70E-01 2.00E-02 1.20E-02 55 MI-135 4.70E-01 2.00E-02 1.20E-02 56 Xe-131m 4.70E-01 1.00E+01 2.00E-02 57 Xe-133m 4.70E-01 1.00E+01 2.00E-02 58 Xe-133 4.70E-01 1.00E+01 2.00E-02 l 59 Xe-135m 4.70E-01 1.00E+01 2.00E-02 60 Xe-135 4.70E-01 1.00E+01 2.00E-02 61 Xe-137 4.70E-01 1.00E+01 2.00E-02 62 Xe-138 4.70E-01 1.00E+01 2.00E-02 63 Cs-134 4.70E-01 1.00E-02 8.00E-03 64 Cs-135 4.70E-01 1.00E-02 8.00E-03
,s 65 Cs-136 4.70E-01 1.00E-02 8.00E-03 j 66 Cs-137 4.70E-01 1.00E-02 8.00E-03
\ 67 .
Cs-138 4.70E-01 1.00E-02 8.00E-03 68 Ba-139 4.70E-01 5.00E-03 4.00E-04 69 Ba-140 4.70E-01 5.00E-03 4.00E-04 70 La-140 4.70E-01 2.50E-03 5.00E-06 71 Ce-144 4.70E-01 2.50E-03 1.00E-04 72 Pr-143 4.70E-01 2.50E-03 3.00E-06 73 Pr-144 4.70E-01 2.50E-03 5.00E-06 74 Np-239 4.70E-01 2.50E-03 5.00E-06
Reference:
Reference:
Reference:
NUREG/CR-1004 for Iodine, Strontium, and Cesium; R.G. 1.109 for all other nuclides.
c' im
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1157c
( Revision 17 D
Table 1.7 INTERNAL DOSE FACTORS 1 - INFANT THYROID Inhalation 1 Cow Milk Ingestion 2 mrem-cm 8 mrem-m2 _y Radionucligg vr-uCi vr-uCi H-3 6.47E+08 3.53E+09*
Te-132 2.79E+08 3.50E+07 I-131 1.48E+13 7.24E+11 I-133 3.56E+12 1.52E+10
- Unit for H-3 is mrem /yr per pC1/cm 3. -
- 1. Based on Regulatory Guide 1.109 methodology with an infant breathing rate of 1400 m 8 /yr.
- 2. Based on Regulatory Guide 1.109 and NUREG/CR-1004
,r- dose methodologies.
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- Page 54 of 85
[gj Revision 17 Table 1.8 (1 of 2)
EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND (mrem /h per pCi/m2)
Element Total Body (DFG i
') Skin H-3 0.0 0.0 C-14 0.0 0.0 Na-24 2.50E-08 2.90E-08 P-32 0.0 0.0 Cr 2.20E-10 2.60E-10 Mn-54 5.80E-09 6.80E-09 Mn-56 1.10E-08 1.30E-08 Fe-55 0.0 0.0 Fe-59 8.00E-09 9.40E-09 Co-58 7.00E-09 8.20E-09 Co-60 1.70E-08 2.00E-08 N1-63 0.0 **
0.0 Ni-65 3.70E-09 4.30E-09 Cu-64 1.50E-09 1.70E-09 Zn-65 4.00E-09 4.60E-09 Zn-69 0.0 0.0 Br-83 6.40E-ll 9.30E-11 O Br-84 1.20E-08 1.40E-08 i Br-85 0.0 0.0
\- Rb-86 6.30E-10 7.20E-10 Rb-88 3.50E-09 4.00E-09 Rb-89 1.50E-08 1.80E-08 Sr-89 5.60E-13 6.50E-13 Sr-91 7.10E-09 8.30E-09 Sr-92 9.00E-09 -
1.00E-03 Y-90 2.20E-12 2.60E-12 Y-91M 3.80E-09 4.40E-09 Y-91 2.40E-11 2.70E-Il Y-92 1.60E-09 1.90E-09 Y-93 5.70E-10 7.80E-10 Zr-95 5.00E-09 5.80E-09 >
Zr-97 5.50E-09 6.40E-09 Nb-95 5.10E-09 6.00E-09 Mo-99 1.90E-09 2.20E-09 Tc-99M 9.60E-10 1.10E-09 Tc-101 2.70E-09 3.00E-09 Ru-103 3.60E-09 4.20E-09 .
Ru-105 4.50E-09 5.10E-09 Ru-106 1.50E-09 1.80E-09 Ag-110M 1.80E-08 2.10E-08 Te-125M 3.50E-11 4.80E-11 Te-127M 1.10E-12 1.30E-12 l Te-127 1.00E-ll 1.10E-11 Te-129M 7.70E-10 9.00E-10
[q . Te-129 7.10E-10 8.40E-10
\ Te-131M 8.40E-09 9.90E-09 Te-131 2.20E-09 2.60E-06 1157c L ------------.---------------_--_--i
/- Page 55 of 85 Revision 17 Table 1.8 (2 of 2)
EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND (mrem /h per pCi/m2 )
Element Total Body (DFG i ) Skin Te-132 1.70E-09 I-130 2.00E-09 1.40E-08 1.70E-08 I-131 2.80E-09 I-132 3.40E-09 1.70E-08 2.00E-08 I-133 3.70E-09 I-134 4.50E-09 l 1.60E-08 1.90E-08 l I-135 1.20E-08 Cs-134, 1.40E-08 l
' 1.20E-08 1.40E-08 Cs-136 1.50E-08 Cs-137 1.70E-08 4.20E-09 4.90E-09 Cs-138 2.10E-08 Ba-139 2.40E-08 2.40E-09 "
2.70E-09 Ba-140 2.10E-09 Ba-141 2.40E-09 4.30E-09 4.90E-09 Ba-142 7.90E-09 9.00E-09 La-140 1.50E-08 1.70E-08 La-142 1.50E-08 1.80E-08 Ce-141 5.50E-10 6.20E-10 Ce-143 2.20E-09 k 2.50E-09 Ce-144 3.20E-10 3.70E-10 Pr-143 0.0 0.0 Pr-144 2.00E-10 2.30E-10 Nd-147 1.00E-09 1.20E-09 W-187 3.10E-09 3.60E-09
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,, Page 60 of 85 Revision 17 s
Table 2.2 (1 of 2) {
FISH CONCENTRATION FACTORS
- I NUCLIDE NUCLIDE NUCLIDE H-3 9.00E-01 Tc-99m 1.50E+01 Ce-144 1.00E+00 C-14 4.60E+03 Ru-103 1.00E+01 Pr-143 2.50E+01 Na-22 1.00E+02 Ru-105 1.00E+01 Pr-144 2.50E+01 Na-24 1.00E+02 Ru-106 1.00E+01 Pr-144m 2.50E+01
- P-32 3.00E+03 Rh-103m 1.00E+01 Nd-147 l 2.50E+01 Cr-51 2.00E+02 Rh-105 1.00E+01 Pm-147 2.50E+01 Mn-54 4.00E+02 Rh-105m 1.00E+01 Pm-149 2.50E+01 Mn-56 4.00E+02 Rh-106 1.00E+01 Sm-147 2.50E+01 Fe-55 1.00E+02 Ag-110m 2.31E+00 Sm-151 2.50E401 !
Fe-59 1.00E+02 Ag-111 2.31E+00 Sm-153 2.50E+01 !
Co-57 5.00E+01 Sb-122 1.00E+00 Eu-155 2.50E+01 I Co-58 5.00E+01 Sb-124 1.00E+00 Ta-182 3.00E+04 Co-60 5.00E+01 Sb-127 Iv00E+00 W-187 1.20E+03 I Ni-63 1.00E+02 Te-125m 4.00E+02 Pr-210 3.00E+02 Ni-65 1.00E+02 Te-127 f
4.00E+02' Pb-212 3.00E+02 f Cu-64 5.00E+01 Te-127m 4.00E+02 Pb-214 3.00E-02 !
Zn-65 2.00E+03 Te-129 4.00E+02 Bi-212 1.50E+01 l Zn-69 2.00E+03 Te-129m 4.00E+02 Bi-214 1.50E+01 As-74 1.00E+02 Te-131 4.00E+02 Po-212 5.00E+01
/ \ As-76 1.00E+02 Te-131m 4.00E+02 Po-214 5.00E+01 k_,I s Br-83 4.20E+02 Te-132 4.00E+02 Po-216 5.00E+01 Br-84 4.20E+02 I-129 1.50E+01 Po-218 5.00E+01 Br-85 4.20E+02 1-130 1.50E+01 Ra-224 5.00E+01 Kr-83m 1.00E+00 I-131 1.50E+01 Ra-226 5.00E+01 Kr-85m 1.00E+00 I-132 1.50E+01 Ra-228 5.00E+01 Kr-85 1.00E+00 I-133 1.50E+01 Ac-228 . 2.50E+01 Rb-86 2.00E+03 I-134 1.50E+01 Th-228 3.00E+01 Rb-88 2.00E+03 I-135 1.50E+01 Th-230 3.00E+01 Rb-89 2.00E+03 Xe-133m 1.00E+00 Th-232 3.00E+01 Sr-89 3.00E+01 Xe-133 1.00E+00 Th-234 3.00E+01 Sr-90 3.00E+01 Xe-135m 1,00E+00 Pa-234 1.10E+01 Sr-91 3.00E+01 Xe-135 1.00E+00 U-234 1.00E+01 Sr-92 3.00E+01 Cs-134 2.00E+03 U-238 1.00E+01 Y-90 2.50E+01 Cs-135 2.00E+03 Np-238 1.00E+01 Y-91 2.50E+01 Cs-136 2.00E+03 Np-239 1.00E+01 (
Y-91m 2.50E+01 Cs-137 2.00E+03 Pu-238 3.50E+02 Y-92 2.50E+01 Cs-138 l 2.00E+03 Pu-239 3.50E+02 Y-93 2.50E+01 Ba-137m 4.00E+00 Pu-240 3.50E+02 ,
Zr-95 3.33E+00 Ba-139 4.00E+00 Pu-241 3.50E+02 ? i, Zr-97 3.33E+00 Ba-140 4.00E+00 Pu-242 3.50E+02 Nb-95 3.00E+04 Ba-141 4.00E+00 Am-241 2.50E+01 Nb-95m 3.00E+04 Ba-142 4.00E+00 Am-247 2.50E+01 Nb-97 3.00E+04 La-140 2.50E+01 Am-243 2.50E+01 '
\
1157c
SQN ODCM Page 61 of 85 Revision 17
\
Table 2.2 (2 of 2)
FISH CONCENTRATION FACTORS
- NUCLIDE NUCLIDE NUCLIDE Nb-97m 3.00E+04 La-142 2.50E+01 'Cm-242 2.50E+01 Mo-99 1.00E+01 Ce-141 1.00E+00 Cm-243 2.50E+01 Tc-99 1.50E+01 Ce-143 1.00E+00 cm-244 2.50E+01
- The source for the fish concentration factors, given in order of preference is:
NUREG/CR-1336, "The Bioaccumulation Factor for Phosphorus-32 in Edible Fish Tissue," B. Kahn and K. S. Turgeon, Georgia Institute of Technology, March 1980.
Regulatory Guide 1.109, October 1977.
UCRL-50564, " Concentration Factors of Chemical Elements in Edible Aquatic Organisms," S. E. Thompson, et al.; Lawrence Livermore Laboratory, October 1972.
UCRL-50163, " Prediction of the Maximum Dosage to Man from the Fallout of Nuclear Devices: IV. Handbook for Estimating the Maximum Internal Dose from Radionuclides Released to the Biosphere," Y. C. Ng, et al.; Lawrence Livermore Laboratory, May 1968.
Regulatory Guide 1.109, Draft, Marcy 1976.
TVA generated numbers for noble gases.
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[ Revision 17
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Table 2.4 PUBLIC WATER SUPPLY INFORMATION*
2020 IEM POPULATION WATER SUPPLY 484.5 Sequoyah Nuclear Plant 473.0 2000 ICI America Inc.
473.0 900 C. F. Industries 470.5 4000 E. I. duPont, Co.
465.3 610700- Chattanooga 418.0 4400 South Pittsburg 413.6 3400 Bridgeport 407.6 500 Widows Creek Steam Plant 405.2 500 Mead Paper Board 392.0 Bellefonte Nuclear Plant 385.8 38700 Scottsboro 382.1 18600 Sand Mountain Water Authority 368.2 125 Christian Youth Camp 358.0 14900 Guntersville 334.5 4500 NE Morgan County Water and Fire 334.2 168600 Huntsville I 330.2 10000 Redstone Arsenal 324.2 Redstone Arsenal 306.0 84600 Decatur '
294.0 Browns Ferry Nuclear Plant O 283.0 274.9 259.6 500 50 14,100 U. S. Plywood-Champion Paper Wheeler Dam Muscle Shoals 259.5 2,700 TVA-NFDC 254.3 21,100 Sheffield 245.0 520 Colbert Steam Plant 239.3 3,900 Cherokee .
238.7 350 U.S. Steel Agri-Chemicals, Inc.
217.4 1 Yellow Creek Nuclear Plant 206.8 2,400 Hardin Co. Water District 193.5 1,900 Tri-County Utility District 158.0 1,100 Clifton 101.9 170 Foote Mineral Co.
100.5 6,100 New Johnsonville 100.4 13,300 Camden 100.0 375 Johnsonville Steam Plant 98.5 900 E. I. Dupont Company 95.5 700 Consolidated Aluminum Corporation 94.5 250 Inland Container Corporation ,
79.5 120 Bass Bay Resort c 39.3 4,300 Jonathan Creek Water District 28.5 9,100 North Marshall Water District 23.6 650 Grand Rivers 17.8 600 B. F. Goodrich Chemical Co.
17.4 106 Airco Carbide 16.8 592 Airco Alloys r 16.7 510 Air Products and Chemicals )
1.1 69,800 Paducah
- From TVA Water Quality Branch, updated December 1979 1157c )
SQN ODCM Page 67 of 85 Revision 17 Table 2.5 FISH 11ARVEST DATA RIVER SPAN NAME OF REACII _ FISH HARVEST (LBS/YR)
(TRM) SPORT
- COMMERCIAL **
484.5 - 471.0 Chickamauga Lake below SQN 5.4E+05 2.0E+05 471.0 - 452.0 Nickajack Lake (Part 1 of 2) 1.2E+05 4.6E+04 452.0 - 424.7 Nickajack Lake (Part 2 of 2) 2.9E+05 1.lE+05 424.7 - 417.5 Guntersville Lake (Part 1 of 4) 2.6E+05 9.5E+04 417.5 - 392.0 Guntersville Lake above BLN 5.2E+05 1.9E+05 l 392.0 - 373.0 Guntersville Lakebelow BLH 7.8E+05 2.9E+05 l
373.0 - 349.0 Guntersville Lake (Part 4 of 4) 1.0E+06 3.8E+05 l 349.0 - 294.0 Wheeler Lake above BFN 1.0E+06 3.8E+05 l 294.0 - 274.9 Wheeler Lake below BFN 1.5E406 5.7E+05 274.9 - 259.4 Wilson Lake 5.9E+05 2.2E405 259.4 - 217.4 Pickwick Lake above YCN 1.3E+06 4.9E+05 217.4 - 206.7 Pickwick Lake below YCN 3.3E+05 1.2E+05 206.7 - 165.0 Kentucky Lake (Part l'of 4) 6.lE+05 2.3E+05 165.0 - 121.0 Kentucky Lake (Part 2 of 4) 6.lE+05 2.3E+05 121.0 - 76.0 Kentucky Lake (Part 3 of 4) 1.8E+06 6.8E+05 76.0 - 22.4 Kentucky Lake (Part 4 of 4) 3.lE+06 1.lE+06
- Derived from " Situation Assessment and Planning Assumptions," Division of Forestry, Fisheries, and Wildlife, TVA, December 1978.
l l
c ll57c
,A Revision 17 Table 2.6 RECREATION USAGE DATA
- RIVER SPAN NAME OF REACH HOURS OF USAGE PER YEAR (TRM) SHORELINE ABOVE-WATER IN-WATER 484.5 - 471.0 Chickamauga Lake below SQN 5.5E+06 1.0E+06 4.9E406 471.0 - 452.0 Nickajack Lake (Part 1 of 2) 1.2E+05 2.5E+04 1.lE+05 452.0 - 424.7 Nickajack Lake (Part 2 of 2) 2.0E+05 4.0E+04 1.8E+05 424.7 - 417.5 Guntersville Lake (Part 1 of 4) 7.0E+04 1.5E+04 6.0E+04 417.5 - 392.0 Gun:ersville Lake above BLN 5.2E+05 1.0E+05 4.7E+05 392.0 - 373.0 Guntersville Lake below BLN 4.7E+06 8.9E+05 4.2E+06 373.0 - 349.0 Guntersville Lake (Part 4 of 4) 1.lE+07 2.lE+06 9.8E+06 349.0 - 294.0 Wheeler Lake above BFN 4.0E+06 7.6E+05 3.6E+06-294.0 - 274.9 Wheeler Lake below BFN 5.2E+06 1.0E+06 4.7E+04 274.9 - 259.4 Wilson Lake 3.9E+06 7.4E+05 3.5E+06 259.4 - 217.4 Pickwick Lake above YCN 2.0E+06 3.5E+05 2.0E+06 217.4 - 206.7 Pickwick Lake below YCN 2.0E+06 4.0E+05 1.8E+06 206.7 - 165.0 Kentucky Lake (Part 1 of 4) 6.0E+05 1.2E+05 5.4E+05 165.0 - 121.0 Kentucky Lake (Part 2 of 4) 1.2E+06 2.3E+05 1.lE+06 121.0 - 76.0 Kentucky Lake (Part 3 of 4) 2.4E+06 4.7E+05 2.2E+06 76.0 - 22.4 Kentucky Lake (Part 4 of 4) 2.6E+07 4.9E+06 2.3E+07 5
- Based on " Extent of Recreation development and Use of TVA Lake Frontage
\ Property;" (unpublished data from 1974 Annual Recreation Survey); and Observations of Recreation Use of TVA Reservoirs, Division of Reservoir Properties, Recreation Resources Branch, TVA, 1975.
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\
Table 3.2
-ATMOSPHERIC AND TERRESTRIAL MONITORING STATION LOCATIONS Location Reference _
Approximate Distance and Number Samole Station Direction from Plant 2 LM-2 SQ 0.8 mile N 3 LM-3 SQ l.3 miles SSW 4 LM-4 SQ l.5 miles NE .
5 LM-5 SQ l.7 miles NNE 7 PM-2 SQ (Chester Frost Park) 3.8 miles SW 8 PM-3 SQ (Daisy) 5.6 miles W 9 PM-8 SQ (Harrison) 8.7 miles SSW 10 PM-9 SQ (Lakeside) - 2.7 miles WSW 11 RM-1 SQ (Chattanooga, Riverside) <16.7 miles SW 12 RM-2 SQ 17.5 miles NNE 13 RM-3 (Cleveland) 11.3 miles ESE 14 RM-4 (Dunlap) 19.5 miles WNW
) 18 Farm J 1.3 miles IN
\j 19 Farm HW l.3 miles W 20 Farm EM 2.5 miles N 21 Farm BR 2.3 miles SSW 25 Farm B (control) 43.0 miles.NE 26 Farm C (control) 16.0 miles NE 27 Farm S (control) 12.0 miles ENE 48 Farm H 4.3 miles NE i
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Table 3.3 PUBLIC WATER SUPPLIES SAMPLED IN ENVIRONMENTAL MONITORING PROGRAM Reference Distance Sampling Number Water Sucolv from Site Sgurce Freauency IRM 31 C. F. Industries 11.5 Tennessee River Monthlya 473.0 32 E. I. duPont and Co 14.0 Tennessee River Monthly 470.5 33 Chattanooga 19.0 Tennessee River Monthly 465.3 34 b 12.5 Tennessee River ' Monthly 497.0 35 Dayton 19.3 Tennessee River Monthlya 503.8 a Sample collected by an automatic sequential-type water sampler with composite sample taken monthly.
gsg b Sample collected at 473.0 is taken from raw water supply; therefore, the
, upstream surface water sample at 497.0 will be considered a control sample for drinking water.
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SQN ODCM Page 75 of 85 O Revision 17
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Table 3.4 (1 of 2)
MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)a,e Airborne Particulate Analysis Water or Gas Fish Milk Food Products Sediment (pCi/L) (pCi/L) (pC1/m3 ) (pCi/kg, vet) (pCi/L) (pCi/kg, vet) (pCi/kg, dry) gross. beta 4 1 X 10-2 N.A. N.A. N.A. N.A.
H-3 2000 N.A. N.A. N.A. N.A. N.A.
Mn-54 15 N.A. 130 N.A. N.A. N.A.
Fe-59 30 N.A. 260 N.A. N.A. N.A.
Co-58,60 15 N.A. 130- N.A. N.A. N.A.
Zn-65 30 N.A. 260 N.A. N.A. N.A.
Zr-95 30 N.A. N.A. N.A. N.A. N.A. .
'Nb-95 15 N.A. N.A. N.A. N.A. N.A. l l
I-131 lb 7 x 10-2 N.A. 1 60 N.A.
Cs-134 15 5 X 10-2 130 15 60 150 Cs-137 18 6 X 10-2 150 18 80 180 Ba-140 60 N.A. N.A. 60 N.A. N.A.
.La-140 15 N.A. N.A. 15 N.A. N.A.
l TABLE NOTATION a The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5% probability i,
of falsely concluding that a blank observation represents a "real" signal. ,
r.
For a particular measurement system (which may include radiochemical separation):
LLD = 4.66 sb E V 2.22 Y exp(-Mt )
l 1157c 1
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[ Revision 17
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Table 3.4 (1 of 2)
MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)a,e TABLE NOTATION (continued)
Where:
LLD is the "a priori" lower limit of detection as defined above (picoeurie per unit mass or volume),
sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute),
E is the counting efficiency (counts per transformation),
V is the sample size (units of mass or volume),
2.22 is the number of transformations per minute per picoeurie, Y is the fractional radiochemical yield (when applicable),
1 is the radioactive decay constant for the particular fs radionuclides, and
(
Ns at is the elapsed time between sample collection (or end of'cbe sample collection period) and time of counting (for environmental samples, not plant effluent samples).
The value of s3 used in the calculation of the LLD for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically ,
predicted variance. In calculating the LLD for a radionuclides j determined by gamma-ray spectrometry, the background shall include '
the typical contributions of other radionuclides norma 11) present in the samples (e.g. , potassium-40 in milk samples). Typice!. values of E V, Y, and at shall be used in the calculations.
b The LLD for analysis of drinking water and surface water samples shall be performed by gamma spectroscopy at approximately 15 pCi/L.
If levels greater than 15 pCi/L are identified in surface water samples downstream from the plant, or in the event of an . !
unanticipated release of I-131, drinking water samples will be '
analyzed at a LLD of 1.0 pCi/L for I-131.
c Other peaks which are measurable and identifiable, together with the radionuclides in Table 4.12-1, shall be identified and reported.
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,/~N Revision 17 Figure 1.3 GASEOUS RADWASTE TREATMENT SYSTEM CVCS VCT \
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SQN ODCM Page 85 of 85 Revision 1.7 Figure 3.6 MILK AND VEGETABLE SAMPLING LOCATIONS
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