ML20237A143
| ML20237A143 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 09/30/1987 |
| From: | SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | |
| Shared Package | |
| ML20237A135 | List: |
| References | |
| PROC-870930, NUDOCS 8712140288 | |
| Download: ML20237A143 (112) | |
Text
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iihjV OnfR j Control Copy No. NON6 l l
i OFFSITE DOSE CALCULATION MANUAL i
FOR SOUTH CAROLINA ELECTRIC AND GAS COMPANY I VIRGIL C. SUMMER NUCLEAR STATION O
REVISION 12 September 1987 r
Approved by the PSRC & x os
~ /s O Revision 12 8712140288 871200 PDR ADOCK 05000395 R DCD
LIST OF EFFECTIVE PAGES Page Revision Page Revision i 12 1.0-1 12 l ii 12 1.0-2 12 iii 12 1.0-3 12 iv 12 1.0-4 12 v 12 1.0-5 12 vi 12 1.0-6 12 vii 12 1.0-7 12 viii 12 1.0-8 12 1.0-9 12 1.0-10 12 1.0-11 12 1.0-12 12 1.0-13 12 1.0-14 12 1.0-15 12 1.0-16 12 .
1.0-17 12 1.0-18 12 1.0-19 12 1.0-20 12 1.0 21 12 1.0-22 12 1.0-23 12 1.0-24 12 1.0-25 12 1.0-26 12 1.0-27 12 1.0-28 12 1.0-29 12 1.0-30 12 1.0-31 12 1.0-32 12 1.0-33 12 1.0-34 12 1.0-35 12 1.0-36 12 1.0-37 12 1.0-38 12 1.0-39 12 1.0-40 12 O
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ODCM, V.C. Summer /SCE&G: Revision 12 (September 1987) ii
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CONTROLLED COPY DISTRIBUTION l
Person Copy #
Director, Nuclear Plant Operations 1 Manager, CHP& EP 2 Manager, Nuclear Licensing 3 Associate Manager, Health Physics 4 Associate Manager, Corporate Health Physics F Associate Manager, Radiological Analytical Services 6 Supervisor, Count Room 7 Manager, Support Services 8 Manager, Operations 9 Associate Manager, Regulatory Compliance 10 V. C. Summer Document Section Manager, ISEG 11 12 g
Associate Manager, Quality Assurance 13 Associate Manager, Environmental Programs 14 Resident NRC Inspector 15 9
ODCM, V.C. Summer /SCEandG: Revision 12 (September 1987) iii
Table of Contents
() List of Effective Pages PAGE i
Controlled Cooy Distribution List iii List of Tables v List of Figures vi References vii introduction viii 1.0 LIQUID EFFLUENTS 1.1 Liquid Effluent Monitor Setpoints 1.0-1 1.1.1 Liquid Radwaste Effluent Line Monitors 1.0-1 1.1.2 Liquid Waste Discharge Via industrial and Sanitary Waste System 1.0-10 1.1.3 Steam Generator Blowdown, Turbine Buildirig Sump and Condensate Demineralized Backwash ,
Effluent Lines 1.0-11 1.2 Dose Calculation for Liquid Effluents 1.0-27 1.3 Definitions of Liquid Effluent Parameters 1.0-35
( ) 1.4 Liquid Radwaste Treatment System 1.0-40 2.0 GASEOUS EFFLUENTS 2.1 Gaseous Effluent Monitor Setpoints 2.0-1 2.1.1 Station Vent Noble Gas Monitors 2.0 1 2.1.2 Waste Gas D 2 cay System 2.0-4 2.1.3 Alternative Methodology for Establishing Conservative Setpoints 2.0 A 2.2 Gaseous Effluent Dose Calculations 2.0-3 2.2.1 Unrestricted Area Boundary Dose 2.0-9 2.2.2 Unrestricted Area Dose to Individual 2.0-10 2.3 Meteorological Model 2.0-40 2.3.1 Atmospheric Pispersion 2.0-40 2.3.2 Deposition 2.0-41 2.4 Definitions of Gaseous Effluents Parameters 2.0-46 2.5 Gaseous Radwaste Treatment System 2.0-51 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING l 3.1 Sampling Locations 3.0-2
(' 3.2 Map of Sampling Locations (Local) 3.0-11 l
3.3 Map of Sampling Locations (Remote) 3.0-12 ODCM, V.C. Su mmer/SCEandG: Revision 12 (September 1987) 69 -- _ - - - - - - - - - - - - - _ -
z LIST OF TABLES ,
Table No. Page No.
1.2-1 Bioaccumulation Factors 1.0-30 1.2-2~ Adult ingestion Dose Factors 1.0-31 1.2-3 Site Related Ingestion Dose Commitment Factor (A,1) 1.0-33 2.1-1 Dose Factors for Exposure to a Semi-infinite Cloud of Noble Gases 2.0-8 2.2-1 Pathway Dose Factors for Section 2.2.1.b (P,) 2.0-13 2.2-2 Pathway Dose Factors for Section 2.2.2.b (R,) 2.0-17 2.2-3 Pathway Dose Factors for TechnicalSpecifica-tions 4.11.2.4.1 and 6.9.1.13 (Infant) 2.0-20 s.
2.2-4 Pathway Dose Factors for Technical Specifica-tions 4.11.2.4.1 and 6.9.1.13 (Child) 2 0-23 2.2-5 Pathway Dose Factors for Technical Specifica-2.2-6 tions 4.11.2.4.1 and 6.9.1.13 (Teenager)
Pathway Dose Factors for Technical Specifica-2.0-26 h.
tions 4.11.2.4.1 and 6.9.1.13 (Adult) 2.0-29 2.2-7 Controlling Receptors, Locations, and Pathways 2.0-33 2.2-8 Atmospheric Dispersion Parameters for Controlling Receptor Locations 2.0-35 2.2.9 Parameters Used in Dose Factor Calculations 2.0-36 3.0-1 Radiological Environmental Sampling Locations 3.0-2 9
ODCM, V.C. Surnmer/SCEandG: Revision 17 (September 1987) v
rs LIST F .i jURES
\s_)
Figure No. Paae No.
1.0-1 Example Calibration Curve for Liquid Effluent Monitor 1.0-26 1.4-1 Liquid Radwaste Treatment System 1.0-40 2.1-1 Sample Noble Gas Monitor Calibration Curve 2.0-3 2.3-1 Plume Depletion Effect for Ground Level Releases (S) 2.0-42 2.3-2 Vertical Standard Deviation of Materialin a Plume (a) 2.0-43 2.3-3 Relative Deposition for Ground Level Releases (D,) 2.0-44 -.
2.3-4 Open Terrain Recirculation Factor (T) 2.0-45 -
2.5-1 Gaseous Radwaste TreatmentSystem 2.0-51
('l 3.0-1 Radiological Environmental Sampling Locations N._/ (Local) 3.0-11 3.0-2. Radiological Environmental Sampling Locations (Remote) 3.0-12 4
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ODCM, V.C. Summer /SCEandG: Revision 12 (September 1987) l
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i REFERENCES This Offsite Dose Calculation Manual was prepared for the Virgil C. Summer i Nuclear Station by Applied Physical Technology based on information communicated directly to APT by South Carolina Electric and Gas Company personnel and the following reference documents:
( 1. Boegli, T.S., R.R. Bellamy, W.L. Britz, and R.L. Waterfield, " Preparation of 3
Radiological Effluent Technical Specifications for Nuclear Power Plants" NUREG-0133 (October 1978).
- 2. " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR 120, Appendix 1", U.S. NRC Regulatory Guide 1.109 (March 1976).
- 3. " Calculation of Annual Doses.to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR 120, Appendix I", U.S. NRC Regulatory Guide 1.109, Rev.1 (October 1977). s.
- 4. " Final Safety Analysis Report", South Carolina Electric and Gas Company, .
Virgil C. Summer Nuclear Station.
- 12. " Operating License Environmental Report", South Carolina Electric and Gas Company, Virgil C. Summer Nuclear Station.
- 6. Wahlig, B.G., " Estimation of the Radioactivity Release Rate /Ecluilibrium Concentration Relationship for the Parr Pumped Storage System , Applied Physical Technology, Inc., February 1981.
- 7. " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light - Water - Cooled Reactors", U.S. NRC Regulatory Guide 1.111 (March 1976).
- 8. " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light - Water - Cooled Reactors", U.S. NRC Regulatory Guide 1.111, Rev.1 (July 1977).
- 9. Slade, D.H., (editor), " Meteorology and Atomic Energy"; U.S. Atomic Energy Commission, AEC TID-24190,1968.
- 10. " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gasenus Effluents from Light-Water-Cooled Nuclear Power Plants", U.S. NRC Regulatory Guide 1.21, Rev.1 (June 1974).
. O O DCM, V.C. Summer /SCEandG: Revision 12 (September 1987) vii
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, s O- INTRODUCTION L
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' The OFFSITE DOSE CALCULATION MANUAL is a supporting document of the RADIOLOGICAL EFFLUENT. TECHNICAL SPECIFICATIONS. As such the ODCM describes the methodology and paramenters to be used in the calculation of offsite -
doses due to radioactive liquid and gaseous effluents and in the calculation of liquid and gaseous effluent monitoring instrumentation alarm / trip setpoints. The ODCM contains a list and graphical description'of the specific sample locations for the radiological environmental monitoring program. Configurations of the liquid and i gaseous radwaste treatment systems are also included.
The ODCM will be maintained at the Station for use as a reference guide and training document of accepted methodologies and calculations. Changes in the calculational methods or parameters will be incorporated into the ODCM in order to .,
assure that the ODCM represents the present methodology in all applicable areas. ,
Computer software to perform the described calculations will be maintained current with this ODCM.
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ODCM, V.C. Summer /SCEandG: Revision 12 (September 1987) viii
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l 1.0 LIOUlO EFFLUENTS l
The Virgil C. Summer Nuclear Station is located on the Monticello Reservoir j which provides supply and discharge for the plant circulating water. This reservoir j i
also provides supply and discharge capacity for the Fairfield Pumped Storage l Facility. The Parr Reservoir located below the pumped storage facility is formed by )
the Parr Dam.
There are two basic release pathways and sources of dilution for liquid effluents: the circulating water discharge canal and the liquid effluent line to the i
penstocks of the pumped storage facility. Allliquid effluent pathways discharge to i either one or the other release point. Generally speaking, very low concentrations of radioactive waste are discharged to the circulating water discharge while generally higher concentrations of radioactive waste are released to the penstocks .. .
of the pumped storage facility during the generation cycle.
1.1 Liquid Effluent Monitor Setpoints The calculated setpoint values will be regarded as upper bounds for O'
the actual setpoint adjustments. That is, setpoint adjustments are not required to be performed if the existing setpoint level corresponds to a lower count rate than the calculated value. Setpoints may be established at values lower than the calculated values if desired.
i 1.1.1 Liquid Radwaste Effluent Line Monitors l (RM-L5, RM-L7, RM-L9)
Liquid Radwaste Effluent Line Monitors provide alarm and auto-matic termination of release functions prior to exceeding the concentration i limits specified in 10CFR 20, Appendix B, Table ll, Column 2 at the release point to the unrestricted area. To meet this specification, the alarm / trip setpoints for liquid effluent monitors and flow measurement devices are set to assure that the following equation is satisfied:
O ODCM, V. C. Summer, SCEandG: Revision 12 (September 1987) 1.0-1 1
(^')
'O cf (1)
C2 F+f where:
C= the effluent concentration limit (Technical Specification 3.11.1.1) implementing 10CFR 20 for the site, corresponding to the specific mix of isotopes in the effluent stream being considered for i discharge, in uCi/ml.
c= the setpoint, in uCi/ml, of the radioactivity monitor measuring the radioactivity concentration in the effluent line prior to dilution and subsequent release; the setpoint, which is inversely proportional to the volumetric flow of the effluent line and proportional to the volumetric flow of the dilution stream plus the effluent stream, represents a value which,if exceeded, would result in concentrations '
exceeding the limits of 10CFR 20 in the unrestricted area. '
g f= the effluent line flow setpoint as determined at tne radiation l
V monitor location,in volume per unit time, but in the same units as F, I below.
F= the dilution water flow setpoint as determined prior to the release point, in volume per unit time.
l At the Virgil C. Summer Nuclear Station the Liquid Waste Processing System (LWPS) and the Nuclear Blowdown System (NBS) both discherge to 4 the penstocks of the Fairfield Pumped Storage (FPS) Facility through a common line. The available dilution water flow (F,) is assumed to be 90 percent of the flow through the FPS penstock (s) to which liquid effluent is being discharged and is dependent upcn operational status of the FPS Station. The waste tank flow rates (f y, f o and fy) and the monitor setpoints (cy ,gc and cc ) re set to meet the condition of equation (1) for a j given effluent concentration, C. The three monitor setpoints are l
l determined in accordance with the monitor system configuration for this l t
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ODCM, V. C. Summer, SCEandG: Revision 12 (September 1987) 1.0-2 l
s discharge pathway. The LWPS discharges through RM-LS, which has setpoint cyfor ' alarm / control functions over releases from either Waste Monitor Tanks 1 or 2. The Nuclear Blowdown discharges through RM-L7, which has setpoint c, for alarm / control functions over releases from the Nuclear Blowdown Monitor Tank. These two release pathways merge into a common line monitored by RM-L9, which has setpoint cc for control '
functions over the common effluent line. Although the piping is arranged so that simultaneous batch releases from the two systems could be practiced, operational releases shall be from only one of the two batch systems at any given time. The method by which their setpoints are determined is as follows:
- 1) The isotopic concentration for a waste tank to be released is obtained from the sum of the measured concentrations as determined by the analysis required in the Radiological Effluent s, Tech nical Specifications Table 4.11-1 :
7,C,=[C,+c,+c,+c,+c, I 9 where:
C, = the concentration of nuclide i as determined by the analysis of the waste sample.
C,* = the concentration of Fe-55 in liquid waste as determined by analysis of the quarterly composite sample.
ECg = the sum of the concentrations C, of each measured gamma 9 emitting nuclide observed by gamma-ray spectroscopy of the waste sample.
C,* = the measured concentrations C, of alpha emitting nuclides observed by gross alpha analysis of the monthly composite sample.
O ODCM, V. C. Summer, SCEandG: Revision 12 (September 1987) 1.0 3
i C,* =
the measured concentrations of Sr-89 and Sr 90 in liquid (j,$s waste as determined by analysis of the quarterly composite sample.
C,* = the measured concentration of H-3 in liquid waste as determined by analysis of the monthly composite sample.
The Cg term will be included in the analysis of each batch; terms for alpha, strontium, Fe-55, and tritium shall be included as appropriate.
Isotopic concentrations for both the Waste Monitor Tanks (WMT) and the Nuclear Blowdown Monitor Tank (NBMT) may be calculated using equation (2).
Prior to being sampled for analysis, the contents of a tank shall be isolated and recirculated. The minimum recirculation time shall be: .
t, = 2V/f, (3) ,
where:
( ) V= the volume of liquid in the tank to be sampled, gal. '
f, = the recirculation flow rate being used to mix the tank gal / min.
This is to ensure that a representative sample will be obtained. Mechanical mixers shall ensure a similar minimum turnover.
- 2) Once isotopic concentrations for either Waste Monitor Tank or the Nuclear Blowdown Monitor Tank have been determined, these values are used to calculate a Dilution Factor, DF, which is the ratio of dilution flow rate to tank flow rate (s) required to assure that the limiting concentration of 10CFR, Part 20, Appendix B, Table 11, Column 2 are met at the point of discharge for whichever tank is having its contents discharged.
Values for these concentrations will be based on most recent available previous composite sample analyses as required by Table 4.11-1 of the Radiological Effluent Technical Specifications.
O ODCM, V. C. Summer, SCEandG: Revision 12 (September 1987) 1.0-4
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l (4)
C DF = [ g ,
+5F (5)
C C C C C MPC MPC, MPC, MPC, MPC, where:
C. = the sum of the ratios of the measured concentration of E'
ypc . nuclide i to its limiting value MPC for the tank whose
' contents are being considered for release. For a WMT, X = M. For the NBMT, X = B.
~
M PC, = MPCg , MPC,, MPC,, MPC,, and MPC, = limiting concen -
trations of the appropriate gamma emitting, alpha -
emitting, and strontium radionuclides, Fe-55, and tritium, respectively, given in 10CFR, Part 20, Appendix B, Table 11, Column 2. For gamma-emitting noble gas radionuclides MPC,is to be set equal to 2 x 104 pCi/ml, according to the Radiological Effluent Technical Speci-fications.
SF e- the safety factor; a conservative factor used to compensate for engineering and measurement uncer-tainties.
= 0.5, corresponding to a 100 percent variation.
- 3) The maximum permissible discharge flow rate, fs , may be calculated for the release of either the WMT or NBMT. First the appropriate Dilution Factor is calculated by applying equation (4), using the appropriate concentration ratio term (i.e. M or B).
O ODCM, V. C. Summer, SCEandG: Revision 12 (September 1987) 1.0-5
. then, i
- ,~ .
- (6)-
F. dp + fdx F t
Jgp yy{
F,, = dilution flow rate to be used in effluent monitor setpoint calculations, based on 90 percent FPS Station expected flow rate, as corrected for any recirculated radioactivity: '
c (7)
F =
dp F t(1- MPC, where:
F, = the flow > rate through .the FPS Station penstock (s) to.which radioactive liquids are. l being discharged. F, should' normally fall ..,
between 2500 and 44800 cfs.
C, = the concentration of radionuclides i in the intake i A of FPS Station (that is, in the Monticello A)
Reservoir). Inclusion of this term will correct for possible long-term buildup of radioactivity due' to recirculation and for the presence of activity recently released to the Monticello Reservoir by l-
~
plant activities. For expected discharges of ;
liquid wastes, the summation will be much less !
than 1.0 and can be ignored (Reference 6).
f, e
= the flow rate of the tank discharge, either f em orfgg.
I f,
e
= flow rate of Nuclear Blowdown Monitor Tank discharge.
l (Conservatively this value will be either zero,if no release is {
1 to be conducted from this system, or the maximum )
measured capacity of the discharge pump if a release is to be conducted.)
ODCM, V. C. Summer, SCEandG: Revision 12 (September 1987)
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f,, = flow rate of Waste Monitor Tank discharge. (Conserva-tively this value will either be zero, if no release is to be conducted from this system, or the maximum measured capacity of the discharge pump if a release is to be conducted.) l DF = the Dilution Factor from Step 2.
If f, a f ,,e the release may be made as planned and the flow rate monitor setpoints should be established as in Step 4 (below). Because F,,is normally very large compared to the maximum discharge pump capacities l for the Waste Monitor Tank and the Nuclear Blowdown Monitor Tank, it is l extremely unlikely that f, < f g,. However, if a situation should arise such !
that f, < f ,,a steps must be taken to assure that equation (1) is satisfied prior ..,
to making the release. These steps may include decreasing f,, by decreasing the flow rate ofe f , or f,,, u&m kmsg F,p. )
When new candidate flow rates are chosen, the calculations of Step 3 should be repeated to verify that they combine to form an acceptable h
release. If they do, the establishment of flow rate monitor setpoints may proceed as in Step 4. If they do not, the choice of candidate flow rates must 1 be repeated until an acceptable set is identified. '
k Note that if DF G 1, the waste tank concentration for which the -
calculation is being performed includes safety factors in Step 2 and meets !
the limits of 10CFR 20 without further dilution. Even though no dilution i 1
would be required, there will be no discharge if minimum dilution flow is 1 not available, since the penstock minimum flow interlock will prevent discharge.
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- 4) The dilution flow rate setpoint*, F,is established at 90 percent of the i expected available dilution flow rate:
F = (0.9) F, (8)
The flow rate monitor setpoint* for the effluent stream shall be set at the selected discharge pump rate (normally the maximum discharge pump rate or zero) fe, or f ,e chosen in Step 3 above.
- 5) The radiation monitor setpoints may now be determined based on the values of ECi, F, and f which were specified to provide compliance with the limits of 10CFR 20, Appendix B, Table 11, Column 2. The monitor response is primarily to gamma radiation, therefore, the actual setpoint is based on E C,.
The setpoint concentration, c, is determined as follows:
(9) cs [C X g A 9
t A= Adjustment factor which will allow the setpoint to be established in a practical manner for convenience and to prevent spurious alarms.
(10)
A=f/f g If A is 1, Calculate c and determine the maximum value for the actual monitor setpoint (cpm) from the monitor calibration graph.
If A < 1, No release may be made. Re-evaluate the alternatives present-ed in Step 3.
l l Set points for flow rates are administrative limits.
ODCM, V. C. Summer, SCEandG: Revision 12 (September 1987)
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s NOTE: if calculated setpoint values are near actual concentrations planned for release, it may be impractical to set the monitor alarm at this value. In this case a new setpoint may be calculated following the remedial methodology presented in Step 3 for the case f, < gf .
Within the limits of the conditions stated above, the specific monitor setpoints for the three liquid radiation monitors RM-L5, RM-L7, and RM-L9 are determined as follows:
RM-L5, Waste Monitor Tank Discharge Line Monitor:
(11)
Cg 5 [ C, y XA 9
NOTE: If no discharge is planned for this pathway or if E Cg = 0, the monitor setpoint should be established as close to .
background as practical to prevent spurious alarms and yet ,
alarm should an inadvertent release occur.
RM-L7, Nuclear Blowdown Monitor Tank Discharge Line Monitor; h Cg s [C B XA 9
9 NOTE: In no case should discharge be made directly from the Nuclear Blowdown Holdup Tank. Its contents should always be processed via the Nuclear Blowdown Monitoring Tank.
NOTE: If no dischcrge is planned for this pathway or if E Cg = 0, the monitor setpoint should be established as close to background as practical to prevent spurious alarms and yet alarm should an inadvertent release occur.
l l RM-L9, Combined Liquid Waste Processing System and Nuclear Blowdown Waste Effluent Discharge Line Monitor O
ODCM, V. C. Summer, SCEandG: Revision 12 (September 1987) 1.0-9
i The monitor setpoint on the common line, c c, should be the same as i}
the setpoint for the monitor on the active individual discharge line (i.e., cy , ,
l or c, as determined above):
(13)
Cc 5 MAX (Cg,Cg)
NOTE: If no discharge is planned for this pathway or if E Cg = 0, the monitor setpoint should be established as close to background as practical to prevent spurious alarms and yet alarm should an inadvertent release occur.
NOTE: In all cases, cy ,a c , and cc are the setpoint values in uCi/ml. '
The actual monitor setpoints (cpm) for RM-L5, RM-L7, and RM-L9 are determined from the calibration graph for the
{
particular monitor. Initially, the calibration curves were . .
determined conservatively from families of response curves 4
supplied by the monitor manufacturers. A sample is shown in Figure 1.0-1. As releases occurred, a historical correla-tion will be prepared and placed in service when sufficient
(]-
data are accumulated.
1.1.2 Liquid Waste Discharge Via industriaf,and Sanitary Waste System f
(RM-LS) )
I in the Virgil C. Summer Nuclear Station liquid waste effluent system design, there exists a mechanism for discharging liquid wastes via the Industrial Sanitary Waste System. The sample point prior to discharge is one of the Waste Monitor Tanks. The analysis requirements are the requirements listed in the Radiological l
Effluent Technical Specifications, Table 4.11-1.
This effluent pathway shall only be used when the following condition is met for all radionuclides,i:
(14)
C, y s C, g k
ODCM, V. C. Summer, SCEandG: Revision 12 (September 1987) 1.0-10
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t, c'y *i
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c' M
= the concentration of radionuclides iin the waste contained within the Waste Monitor Tank serving as the holding facility for -
sampling and analysis prior to discharge. '
q 1 ci
= the Lower Limit of Detection,(LLD) for radio-uD nuclide i in the liquid waste in the Waste Moni- ,
tor Tank as determined by the analysis required u D 1 in the Radiological! Effluent Technical Specifica- fs tion Table 4.11-1.
y v When the condicitora @quation (14) are met [uid waste may be ( l,' '
released via the industrial and Sanitary Waste System pathway. The RM-L5 d l setpoint should be estatfished as close to backgrotind as practical to prevent t spurious alarms ark yet alarm should' an inadvertent high concentration b release occur. ,
O 1.1.3 Steam Generator Blowdown, Turbine'ibildino Sump, and Conden-sate Demineralized Backwash Effluent Lines
- I' (RM-L3, RM-L10, RM-LS, RM-L11) '
s Concentrations of radionuclides in(he lliquid effluent discharges made,via th'e Turbine Building Sump, Steh n Generator Blowdown, and 3)
Conderisate Demineralized Backwash are expected to be very low or ,,
nondetectable. The first two releases are expected to be continuous in nature a' nd the last a batch release. All will be sampled in an appropriate manner as specified in Table 4.11-1 of the RETh The Steam Generator 7
Blowdown Monitors, the Turbine Buildjag %mp Monitor, and the I Condensate Demineralized Backwash Mohitor provide alarm and automatic
- termination of release prior to excheding the concentration limits specified in 10CFR 20, Appendix B, Table 11, Column 2 at the release point to the
(
unrestricted area. .{n reality, all of these effluent pathways utilize the ,
, y G
ODCM, V. C. Summer, SCEandG: Revision 12 (September 1987) e 1.0-11 $
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. p , circulating water as dilution to the effluent stream, with the circulating Gyer rIscharge canal being the p'oint of release into an unrestricted area, y' 'i fiowever, to compensate for uncertainties in the transit times of activity i
discharge to the Industrial and Sanitary Waste System, discharges to that i
system will not be credited with dilution for the purpose of monitor setpoint h calculations.
The steam Generator Blowdown Effluent may be released to the Circulating Water either directly in the Condenser outflow or via the ponds f and sumps of the Industrial and Sanitary Waste System; the latter path is preferred for chemical reasons in the first hours following startup. The Turbine Building Sump and Condensate Demineralized Backwash Effluents enter the Circu:ating Water through the Waste Lagoons.
lt4 For thL sake of clarity, two mutually exclusive setpoint calculation s, processes are obtlinbd below. Section 1.1.3.1 is to be used whenever Steam ,
Generator Blowdown in being released directly to the Circulating Water in the Condenser \cutflow, which is the normal mode. Section 1.1.3.2 is to be
) used whenIever Steam Generator Blowdown is being released to the Industrial and Sanitary Waste System, or diverted to the Nuclear Blowdown Processing System, both of which are alternate modes. Each section covers all four monitors (RM L3, RM-L8, RM-L10 and RM-L11).
NOTE: UN_ hen Circulating Water is unavailable for effluent dilution, releases u 'contairing activity above 1.LD should be discouraged via pathways
'+ which lead to it. Steam Generator Blowdown should be diverted to 1 s
(
[' ? S Ne Nuclear Blowdown Processing System. Condensate t
D3 mineralized Backwash may be diverted to the Turbine Building D6 dump or not'r<. leased. Turbine Building Sump effluent should be diverted [.o the Excess Liquid Waste Processing System. (These steps are to keep the calculated dose to individuals as low as reasonably achi99able.) Furthermore, sampling and analysis of the Industrial and Sanitary Waste System is to be initiated and the measured concenkatiorh'used in the dose calculations of Section 1.2.
~; ,
(. 4 l ODCM, V. C. Summer, SCEandG: Revision 12 (September 1987) 1.0-12 L_ . _ _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
1, f
- = '
s ,;
f
'[ j , . _
1.1.3.1 Stearn Generator Blowdown Effluent bitect to Circulating -o Wat,er_(bicrmal Mode)
Equation (% is again used to assure that effluents are in compliance with the aforernentioned specification: .
! ci (F + f) sc
,,; '< ' \'
where: c, f, F, and C are the same generic terms dis:usd!d in Section j l
' 1 1.1.1.
The available dilution water flow (Fg ,) is dependent upon the mode of operation of the Circulating Water Syst'em. Any change in this value will be accounted for in a recalculation of equation (1).
The Steam Generator Blowdown flow rate (fo ,) aM Ge Meam Generator Blowdown monitor setpoints (c3 , and c33) are set to meet the cc ;cn of ekvation (1). The Turbine Building-Sump and ."
Condensate Dimeneralizer effluents will be limited to concentra-tions less than MPC'without claiming dilution (see below). There '
fore,it is not necessary to consider their flow rates or concentrations in determining the required dilution and monitor setpoints for Steam Generator Blowdown.
g For conservatism, the Turbine Building Sump and Conden-sate Demineralized Backwash monitor setpoints fc1 and co ) will claim f f' no dilution from the Circulating Water, and will be set at the- aopli:
P cable concentration limit. That is:
c5C '
(15) suhere: c and C are the generic terms discussed in Section 1.1.1.
l RM-L8, the TurHne Building Sump monitor alarms and terminates release u.pon es;ceeding the monitor setpiiint (c,). The discharge can then be .mbnually diverted to the Excess Waste <
Processing System. RMii .3, the firi,t roonitor in the Steam Gerierator Blowdown discharge pathway, alarms and terminates release of the
,( stream. The discharge is then a6tomatidilv diverted to the Nuclear
~
( .
{
o e!
ODCM, V. C. Summer, SCEandG: Revision 12 (September 1987)
! ( 1.0-13 )
(
o !
y -.
'l Blowdown' Processing System'. RM-L10,'the last monitor in the Steam Generator Blowdown discharge pathway, alarms and terminates the release. Thus, RM-L10 is redundant to RM-L3 and the setpoint (c33) will be determined in 'the same manner as RM-L3 (cs,). RM-L11, the Condensate Demineralized Backwash monitor, alarms and terminates release upon exceeding the monitor setpoint (co ). The-discharge may then be manually diverted to the Turbine Building-Sump or simply delayed. The method by which the monitor setpoints are determined is as follows:
- 1) . The isotopic concentrations for_ any release source to be or being released are obtained from the sum of the measured concentrations as determined in the Radiological Effluent Technical Specifications Table 4.11-1. Equation (2) is again employed for this calculation: .
[ C, = [ C +g C, + C , + C, + C,
- ' 9 where
EC, = the sum of the measured concentrations as determined by the analysis of the waste sample.
EC, = the sum of the concentrations C, of each measured gamma emitting nuclide observed by gamma-ray spectroscopy of the waste sample.
C, = the measured concentration C, of alpha emitting composite sample.
C, = the measured concentrations of Sr-89 and Sr-90 in liquid waste e determined by analysis of the most recent available quarterly composite sample.
O ODCM, V. C. Summer, SCEandG: Revision 12 (September 1987) 1.0-14
- a. - _ _ . - - -
C, = the measured concentration of H-3 in liquid waste determined by analysis of the monthly composite sample.
C, = the measured concentration of Fe-55 in liquid waste as determined by analysis of the most recent available quarterly composite sample.
Isotopic concentrations for the Steam Generator ;
Blowdown System effluent, the Turbine Building Sump Effluent, and the Condensate Demineralized Backwash effluent may be calculated using equation (2).
- 2) Once isotopic concentrations for the Steam Generator Blowdown .. .
iiave been determined, these values are used to calculate a Dilution Factor, DF, which is the ratio of the total dilution flow rate to effluent stream flow rate required to assure that the limiting concentrations of 10CFR, Part 20, Appendix B, Table 11, Column 2 are met at the point of discharge.
(16)
C DF = +5F p 3 (17)
C C C C C MPC MPC, MPC, MPC, MPC 5 9
where:
C, = C,, C,, C,, C,, and C,; measured concentrations as defined in Step 1. Terms C , C,, C,, and C, will be included in the calculation as appropriate.
I gi ODCM, V. C. Summer, SCEandG: Revision 12 (September 1987) 1.0-15
I i -
C (dO)
' g i MPC '
= the sum of the ratios of the measured concen-S tration of nuclide i to its limiting Value MPC, for the Steam Generator Blowdown effluent.
M PC, =
MPCg , MPC,, MPC,, MPC,, and MPC, are limiting concentrations of the appropriate radionuclides from 10CFR, Part 20, Appendix B Table ll, Column 2 limits. For gamma-emitting noble gas radiortuclides, MPC,is to be set equal to 2 x 10 8 uCi/ml, according to the Radiological Effluent Technical Specifications.
SF = the same generic term as used in Section 1.1.1, Step 2.
= 0.5 .
- 3) The maximum permissible effluent discharge flow rate, fo , may now Q be calculated for a release from the Steam Generator Blowdown.
(18) dc ds dc f*
d DF E dC d5 where:
F dc
= Dilution flow rate for use in effluent monitor setpoint calculations, based on 90 percent of the expected flow rate of the Circulating Water System during the time of release and corrected for any recirculated activity:
(19)
C F = (0.9) dF II -
MPC, !
where:
F, = the flow rate of the Circulating Water System during the time of the release. Fo should normally fall between 1.78 X 105 and 5.34 X 105 gpm.
O V '
ODCM, V C. Summer, SCEandG: Revision 12 (September 1987) 1.0-16
4.
C,, = the concentration of radionuclides i in the g Circulating Water System intake, (that is, in the W Monticello Reservoir). Inclusion of this term will correct for posible long-term buildup of l
radioactivity due to recirculation and for the presence of activity recently released to the Monticello Reservoir by plant activities. For expected discharges of liquid wastes, the summa- j tion will be much less than 1.0 and can be ignored (Reference 6). i f ds = Flow rate of Steam Generator Blowdown discharge.
(This value normally will be either zero, if no release is to be conducted, or the maximum rated capacity of the discharge pump (250 gpm), if a release is to be . .
conducted.) .
DF = the Dilution Factor from Step 2.
O Note that the equation is valid only for DF > 1; for DF fi 1, the effluent concentration meets the limits of 10CFR 20 without dilution as well as being in compliance with the conservatism imposed by the Safety Factor in Step 2.
If f, d f ,,o releases may be made as planned. Because F,,is normally very large compared to the maximum discharge pump capacity of the Steam Generator Blowdown System, it is extremely unlikely that f, < f ,.o However, H a skuadon shod anse such @at f d
< f,,, steps must be taken to assure that equation (1) is staisfied prior to making the release. These steps may include diverting Steam Generator Blowdown to the Nuclear Blowdown Processing System or decreasing the effluent flow rate.
When new candidate flow rates are chosen, the calculations of Step 3 should be repeated to verify that they combine O
ODCM, V. C. Summer, SCEandG: Revision 12 (September 1987) 1.0 17
s to form an acceptable release. If they do, the establishment of flow rate monitor setpoints should proceed as in Step 4, if they do not provide an acceptable release, the choice of candidate flow rates must be repeated until an acceptable set is identified.
- 4) The dilution flow rate setpoint for minimum flow rate, F, is established at 90 percent of the expected available dilution flow rate:
F = (0.9)(Fd) N Flow rate monitor setpoints for the Steam Generator Blowdown effluent stream shall be set as the selected discharge pump rate (normally the maximum discharge pump rate) f,, chosen in Step 3 above.
- 5) The Steam Generator Monitor setpoints may be specified based on the values of E Ci, F,and f which were specified to provide compliance with the limits of 10CFR 20, Appendix B, Table ll, Column 2. The monitor response is primarily to gamma radiation, therefore, the actual setpoint is based on E Cg. The monitor setpoint in cpm which corresponds to the calculated value c is taken from the monitor calibration graph. (See NOTE, page 1.0-10.) The setpoint concentration, c, is determined as follows:
(21) c s [C gXB 9
B = Adjustment factor which will allow the setpoint to be established in a practical manner for convenience and to prevent spurious alarms.
=fNd os M If B i 1, Calculate c and determine the maximum value for the actual monitor setpoint (cpm) from the monitor calibration graph.
O ODCM, V. C. Summer, SCEandG: Revision 12 (September 1987) 1.0-18
It t? < 1, No release may be made. Re-evaluate the alternatives presented in step 3.
i NOTE: If the calculated setpoint value is near actual concen- ;
trations being released or planned for release, it may be impractical to set the monitor alarm at this value. In this case a new setpoint may be calculated following the remedial methodology presented in steps 3 and 4 for the casegf < fos.
Within the limits of the conditions stated above, the specific monitor setpoints for the two Steam Generator Blowdown monitors RM-L3 and RM-L10 are determined as follows:
s, For RM-L3, Steam Generator Blowdown Discharge initial ,
monitor, and for RM-L10, Steam Generator Blowdown Discharge final monitor:
(23) g c3 ,orcsb 5 bC g s XB 9
= the isotopic concentration of the Steam Generator Ecg 9 5 Blowdown effluent as obtained from the sum of the measured concentrations determined by the analysis required in the Radiological Effluents Technical Specifications Table 4.11-1.
NOTE: If no discharge is planned for this pathway or if T., Cg =0, the monitor setpoint should be established as close to background as practical to prevent spurious alarms and yet alarm should an inadvertent release occur.
- 6) The Turbine Building Sump and Condensate Demineralized Backwash monitor setpoints are to be established independently of each other and without crediting dilution. They are to be based on the measured radio-O ODCM, V. C. Summer, SCEa ndG: Revision 12 (September 1987) 1.0-19
I nuclide concentrations of the effluent stream and are to ensure compliance with the limits of 10CFR 20, Appendix B, Table 11, Column 2 prior to discharge.
For each effluent stream, a concentration factor CF must be calculated, measuring the nearness of approach of the undiluted waste stream to the specified limiting condition of the Maximum Permissible Concentration. That is, L (24)
C CF = +5F (25)
C CF7 -= { T
+5F (26)
C CFg = D
+5F O -here:
C
= the sum of the ratios of the measured concentration of
{ MPC, T
nuclide i to its limiting value MPC, for the Turbine Building Sump effluent.
Ci
=
the sum of the measured concentration of nuclide i(in MPC ' o liquid only) to its limiting value MPC, for the Condensate -
Demineralized Backwash effluent.
CF 7 = the concentration factor for the Turbine Building Sump Effluent.
CF o = the concentration factor for the Condensate Demin-eralizer Backwash Effluent.
O ODCM, V. C. Summer, SCEandG: Revision 12 (September 1987) 1.0 20
i 1 <
SF = the generic engineering safety factor used in Section p 1.1.1, Step 2. {
= 0.5 If CF S 1, calculate c and determine the actual monitor setpoint (cpm) from the calibration curve.
If CF > 1, no release may be made via this path. The release must either be delayed or diverted for additional processing.
Because of spurious alarms, these remedial steps may be
/
required if the monitor setpoints are only near the actual concentrations being released.
Within the 'above limitation, setpoints may now be calculated for the two effluent rnonitors. Because they are primarily . .
sensitive to gamma radiation, their setpoints will be based on the concentrations of gamma emitting radionuclides as follows:
Where:
For RM-L8, Turbine Building Sump Discharge Monitor: h (27)
Cr s [C g 7
+ CF 7 9
= The gamma isotopic concentration of the Turbine Building Ec g 1 Sump effluent as obtained from the sum of the measured 9 concentrations determined by the analysis required in the Radiological Effluents Technical Specifications Table 4.11-1.
CF 7 = The Turbine Building Sump Effluent Concentration Factor from equation (25).
NOTE: If no discharge is planned for this pathway or if E C, = 0, the monitor setpoint should be established as close to background as practical to prevent spurious alarms and yet alarm should an inadvertent release occur.
O ODCM, V. C. Summer, SCEandG: Revision 12 (September 1987) 1.0 21
( For RM-L11, Condensate Demineralized Backwash Discharge Moni-tor:
(28)-
cg s [C g g + CF g 9
where:
= The gamma isotopic concentration of the Condensate EC 9 Demineralized Backwash effluent (including solids) as ob-
' tained from the sum of the measured concentrations determined by the analysis required in the Radiological Effluents Tech nical Specification ns Ta ble 4.11-1.
CFo = The Condensate Demineralized Backwash Effluent Concen-tration Factor from equation (26). '
f NOTE: If no discharge is planned for this pathway or if E Cg = 0, the monitor setpoint should be established as close to
[v) background as practical to prevent spurious alarms and yet alarm should an inadvertent release occur.
1.1.3.2 Steam Generator Blowdown Effluent Not Directly to Circulating Water (Alternate Mode)
Equation (15)is again used to assure that effluents are in compliance with the aforementioned specification before dilution in the receiving water:
c5C where c and C are the generic terms discussed in Section 1.1.1.
i Because dilution is not considered in the setpoint calculation,it is not l necessary to calculate maximum permissible discharge flowrates or i anticipated available dilution flow rate.
4
/^\
N ODCM, V. C. Summer, SCEandG: Revision 12 (September 1987) 1.0-22 i
The functions of the four monitors whose setpoints are to be' established are describe in Section 1.1.3.1 above. The method for the determination is as follows:
- 1) If a release is found to be permissible, flow rate monitors for the active effluent streams (Steam Generator Blowdown - fo ,, Turbine Building Sump - fg ,, and l Condensate Demineralized - oof ) may have their setpoints established at any operationally convenient value. Since 10CFR 20 is to be complied with before dilution, the flow rate of discharges is irrelevant. l
- 2) The Concentration Factor of equations (24) - (26) is again used to ensure the permissibility of the release:
C CF = +5F C.
O CF 7
=
7
+5F C
CFg = g +5F C (29)
CF 3= 3
+5F in which all terms are defined in subsection 1.1.3.1 and subscripts T, D, and S refer respectively to the Turbine Building Sump Effluent, the Condensate Demineralized Backwash Effluent, and the Steam Generator Blowdown Effluent.
9 ODCM, V. C. Summer, SCEandG: Revision 12 (September 1987) 1.0-23
If CF 51, calculate c and determine the actual monitor setpoint i (cpm) from the calibration curve.
If CF > 1,no release may be made via this path. The release must either be delayed or diverted for additional processing.
l Because of spurious alarms, these remedial steps may be required if the monitor setpoints are only near tlie actual concentrations being released. !
Within the above limitation, setpoints may now be calculated for the four effluent monitors. Because they are primarily sensitive to gamma radiation, their setpoints will be based on the concentrations of gamma emitting radionuclides as follows:
For RM-L8, Turbine Building Sump Discharge Monitor (using equation (27) . .
above): ,
C 7 si [C g 7
+ CF 7 O where:
= The gamma isotopic concentration of the Turbine Building Sump effluent as obtained from the sum of the measured EC 9 i concentrations determined by the analysis required in the S
Radiological Effluents Technical Specifications Table 4.11-1.
CF 7 = The Turbine Building Sump Effluent Concentration Factor from equation (25).
NOTE: if no discharge is planned for this pathway or if E Cg = 0, the monitor setpoint should be established as close to background as practical to prevent spurious alarms and yet alarm should an inadvertent release occur.
O ODCM, V. C. Summer, SCEandG: Revision 12 (September 1987) 1.0 24
For RM-L11, Condensate Deminersiizer Backwash Discharge Monitor (using equation (28) above): 1 cg 5 [C 9 D + CF g 9
where:
= the gamma isotopic concentration of the Condensate Demin-Ec 9 eralizer Backwash effluent (including solids) as obtained from the sum of the measured concentrations determined by the 9
analysis required in the Radiological Effluents Technical Speci-fications Table 4.11-1.
CF 9 = The Condensate Demineralized Backwash Effluent Concen-tration Factor from equation (26).
NOTE: If no discharge is planned for this pathway or if E Cg = 0, the monitor setpoint should be established as close to background as practical to prevent spurious alarms and yet alarm should an '-
inadvertent release occur.
For RM-L3, Steam Generator Blowdown Discharge initial monitor, and RML-10, Steam Generator Blowdown Discharge final monitor:
(30)
+
c sa " \b ' g s s 9
.vhere:
= The isotopic concentration of the Steam Generator Blow-Ec 9 5 down eHluent as obtained from the sum of the measured i
concentrations determined by the analysis required in the Radiological Effluents Technical Specifications Table 4.11-1.
CF 3 = The Steam Generator Blowdown Effluent Concentration Factor from equation (29).
NOTE: if no discharge is planned for this pathway or if E Cg = 0, the monitor setpoint should be established as c'ose to background as practical to prevent spurious alarms and yet alarm should an inadvertent release occur.
O ODCM, V. C. Summer, SCEandG: Revision 12 (September 1987) 1.0 25
P _
+
FIGURE 1.0-1 EX AMPLE CALIBRATION CURVE FOR LIQUID EFFLUENT MONITOR o ,
% 10 . , ,
r a .g v .'n.
. 1
. . - ,w w s . - . -
- ~ ~ --
iw -e ,ses: 1 ' m.e .i.bmiM # MP ' ~ ,n + -
~"- ~ ~
hl p M "a 4! , - +. ~
-iQ ' e 't ?T '.MSEi 1450YM 'OT.f.5 . ' ' . # f "21 -Q. .I : .;;- ,=
'-M 4 . .C' ;
A.e i!!i ~~-W@#'-
~---
e i.=_1-::- ;. _..; .g
. p_g = ;. ;-
-4 0= C Z 1 ~d_Of-M_: :': =-~ E. .-A=y2s @..W ys q : .s===g __
" " . ,===.
~.7-='-
p'~
g_ ,y - ---
a u. = - > -i a="e 5 W'1 ._ ~~._; c
% w- -; p 1m@4 'T-._M. l s ": 1 ~~ " +,=La.ma - -
--. ;;.;_ J_ -f -c. ? *5.:+ -5. 'A::.11H - "U -E'fFLP85.M ist.*'SMM
- - .Oe 2.aw n rs .rw 2 Y
r .~
.2 :E_
5332Jgsi~1.Ms r"-C72~-Z{ disks.I'if-D'-r*.. : r. @E:4 ~
2-. w-4M a
'i: -Pg
=.;
- =g= .y=.=r=
. . _ .: r u-=-.c 7
m- .
.w : -
j@f 5P - -
- t
- -
'rEiEEf=#@h
--. _ - : .r t-- -
. A _ ::;.::r.-P'< . - . - - - - ^ --
=- -
4; 10-1 3_ + '. . -,-,-. i 5 '
.+-- 17
-%.+
1 -
,".=a~.:
w.*.g.nm.c d p.*..e -s- ~m >.
.p u.
--- n> g. i
~
F
~. .ra +
. , ~.
. . ~v. . t .c e :. :
p.=
'*"""* * .g rv
+ -
r Et y" --*
n m g
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2 .= -,.J - o' t , . maspw ,. g e=sth-a=%=== : = -
em'I -n# w. g .
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. ; p ,,3 .
m - _ . . ,= ; g ng m .. _ .
gz N
-.-.;===-..
, =7*=*
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i-
=~ - . - =. - - e
- -___ m j h_.__#~
.a
. . . , _ . - w 10 z;m e _;
- g q, ;:m :=a
--"TQ [ l4 pa :-r;gce. u ;.w; . .;--;
M.i = Ml ? !
D i"% :G.;G :-- i - ~ ' '~
s
s
== =s-. i-W
._,.= -
._a= =1: &
iseW x ="i ~ N C - = = - := L E s.
a _m E .W_ ~, r.MM u p.. ~. -
y w pa-
- n. mm.
u-
__ = ~-
=
6E :-a m :-
- a s- .+ 9FW_u.m
.n -r n-
+e-w.m . .
QN.
.cb:m=a:
m .
u
.M==mE=t_.=' gy:_. e= .--ik:
.- =
e=-iiW:stm :. .uier~
% 7 w
S 10 3 .-
, : . -. # . ... g <
l.__.
. , m, -
g > 4 to JVjt*"-'".
.. _ 1 ,
. -1J s. --i.. T . ad
,,- - m m =
pg "r gygy-
,,;,- J'. , _"'~_
~.-e- p~i'- T. ].4fM M M L. a. r. .
-hr : ".} 8'T :. ' l.* .
i- .I T ~
}- i * .d
~"
! - d
.wD W1I] gaE h m.,n,j .=,,_.,,-3,.y g[-5 [m-m- .t-,gv.s _, i '
---.= u e pN?=iO ELjg*_ ._ ' -
T ;'Ej T- "
.sr'5=.2 :--
'= =; .I s._. . .:
- t"5 4 Ot:::~:E-M E @f ' ~ .':I LNET;$E.D N ."- -, _ .S:~.
~
-$l' ..
Z- I.-' 7 :.
o u ,=_=,= ---- -
_ .:==m = . __ . _ . _ %_-.
= _._.
i ==. n .__ _=r . - - -
.: ==
._=::4_
,-- +-
_r. _
- ,. . n.;.
10 6 -
- . % + __
- . . _,.. -
p.gu.j .y .. y g g 7 p;- ; g i _ .m
=
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3
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.c- .. N m~ p g-M %= t.m, cn s4 1.
} Q
'-- ?
3.
eo-= = msg = . I- .-
o-d :
F
<_; := =-
-- . _ _ _ , .. == =
- -,-;y
- - ~ ~ gp. , . 4 =~
e 7 _,_ . -
m
., t, 3 i ,
_-m-p
- 3 ~. -~.. ! __ m .
.-u _ .- _
. m e m = =.u'.-._' -%.P
= ,
q;i .. . -.
- _ - - - - --- : a : _ . . . :.
_;=g-;w_-.u sm e sT. - L__ ~ ? E5-R
__ u
. z___ ,_ , ==.as
=_.- -
-} .%.~ ~ ~ l ,"
10,,5 ma .+ - ._
-.__ :: ;;t::a:::f t;::@: -
9<.y i u ,, :::cn
_.- :"U :y : ---- . '
- - - ~~
w ='- 5' =2 .TE- ?-i:?-
'- r_ u_o~ ; ";==
-"- i
.: U:r r"
W w ;;n==,=-
r ,u.am n n .n ---
w -=s_ M*=Tw nmn .g m .
e=.m- "= m
=-~ m' o:
wun.m e n.n
^
d O'I%g@w
_. ,. m.
? m,m_m
-mm mm
~= n-V- ..a=t-@i MD 'dY ~
5-,N f $ .. ' i '3 * * **-
@:C
~
l _.a ,.-- M- '.h.T.J-T-i 8MEM-
" -MTM--TM r - -
r-=raf+tT.M=o=@ d2.M W W *-
GdMf.M 'h ? T U i_
i
_.2
- l _P f505- WJME.WW &=M M9-
+ --e ;Ed- Er~MiM=:=_eii
. . 3 .-.2
- q "p' M dq i" "' . ,
.o
~rN yM M.& rbu a. .
10-' -- "
c c.% ---
r . .:
e@-7N.S..MW ~~~ M *4 = :-
2 10 10' 10' 10' 5 10 1 CountRate(cpm) _ _ - - - - - - - - - - - _ __ _ _ _ _ _ _ _ _ _ _ _ - - - - - - -
1.2 Dose Calculation For Liquid Effluents The method of this section is to be used in all cases for calculating doses to individuals from routine liquid effluents. Four notes at the end of the section confirm the values which certain parameters are to be assigned in some special cases.
The dose contribution from all radionuclides identified in liquid effluents released to unrestricted areas is calculated using the following expression:
(31)
D, = { A [ At, C,, F ,
i k=1 where:
Dr = the cumulative dose commitment to the total body or any . .
organ,I, from the liquid effluents for the total time period ,
E At in k mrem (Reference 1).
At, = the length of the kth time period over which C,, and F, are averaged for allliquid releases,in hours.
C,, = the average concentration of radionuclides, i, in undiluted liquid effluent during time period At, from any liquid release, in uCi/ml.
A,, = the site related ingestion dose commitment factor to the total body or any organ, t, for each identified principal gamma and beta emitter listed in Table 1.2-3 in mrem-ml per hr-uCi.
A,, = Ko( (U,/D,) + U,BF,) DF, (32)
F, = the near field average dilution factor for C,, during any liquid effluent release. Defined as the ratio of the maximum undiluted liquid waste flow during release to the product of the average flow from the discharge structure to unrestricted receiving water times 2.
O DCM, V. C. Su mmer, SCEandG: Revision 12 (September 1987) i .
1.0-27 3
~
l
,e U Fk = (averaae undiluted liauid waste flow)
(average flow from the discharge structure) x (Z) where:
2=1 = applicable factor when no additional dilution is to be considered. (Reference 1; Section 4.3)
K, = units conversion factor 1.14 x 105
= ((106 pCi/uCi) x (103ml/f) + (8760 hr/yr))
I U, = 21 kg/yr, fish consumption (adult). (Reference 3) j J
B F, = Bioaccumulation Factor for nuclide i,in fish, pCi/Kg per pCi/l, .
from Table 1.2-1,(taken from reference 3, Table A-1).
) DF,t = Dose conversion f actor for nuclide i, for adults in preselected organ, t , in mrem /pCi, from Table 1.2-2 (taken from reference 3, Table E-11).
)
I l
U, = 730 f/yr, water consumption (adult). (Reference 3)
D, = Dilution Factor from the near field area within one-quarter mile of the release points to the potable water intake for adult water consumption; for V. C. Summer, D, = 1.
(Reference 1) l NOTE 1: If radioactivity in the Monticello Reservior (C,,) becomes > the LLD specified in Radiological Effluent Technical Specification, Table 4.11-1, that concentration must be included in the Dose determination. For this part of the dose calculation, F, = 1 i and at, = the entire time period for which the dose is being calculated.
O ODCM, V. C. Summer, SCEandG: Revision 12 (September 1987) 1.0-28
i NOTE 2: During periods when the Circulating Water Pumps are not in operation, the possibility of leakage of activity from the industrial Water System will be accounted for as follows.
Sampling of the liquid in the Sanitary and Industrial Waste System will be initiated, and the measured concentrations of '
radionuclides will be used in the dose calculations with F, = 1 and A t, = the entire time period for which the dose is being calcualted.
NOTE 3: During periods when the Circulating Water Pumps are in operation, any releases to the Sanitary and Industrial Waste System a_re to be credited with dilution in Circulating Water for dose calculation purposes, even though such dilution was not claimed in the setpoint calculation. When taken in union s, with the note above, this procedure results in some overestimation of dose to the population because discharges made to the Sanitary and Industrial Waste System just before loss of Circulating Water will be counted twice in the dose calculation process.
h NOTE 4: If radioactivity in the Service Water becomes > LLD as determined by the analysis required by Radiological Effluent Technical Specification, Table 4.11-1, that concentration must be included in the Dose determination. For this part of the dose calculation, F, = 1 and A t, = the entire time since the last Service Water sample was taken.
O ODCM, V. C. Summer, SCEandG: Revision 12 (September 1987) 1.0 29 ,
t
' ~
TABLE 1.2-1 BIOACCUMULATION FACTORS
- l
. (pCi/kg per pCi/ liter)
ELEMENT FRESHWATER -
FlSH H 9.0E-01 C 4.6E 03 Na 1.0E 02 P 1.0E 05 Cr 2.0E 02.
Mn 4.0E 02 Fe 1.0E 02 Co 5.0E 01 Ni . 1.0E 02 Cu 5.0E 01 l Zn 2.0E 03 Br 4.2E 02 .
Rb 2.0E 03 Sr 3.0E 01 Y 2.5E 01
, Zr 3.3E 00 l Nb 3.0E 04 i
Mo 1.0E 01 Tc 1.5E 01 Ru 1.0E 01 Rh 1.0E 01 Te 4.0E 02
- I 1.5E 01 Cs 2.0E 03 Ba 4.0E 00
, La 2.5E 01 Ce 1.0E 00 Pr 2.5E 01 Nd 2.5E 01 W 1.2 E 03 ,
Np 1.0E 01 '
i
- Values in Table 1.2-1 are taken from Reference 3 Table A-1.
i ODCM, V.C. Summer, SCEandG: Revision 12 (September 1987) l
(
)
1.0-30
TABL E 1. 2-2 1 Page 1 of 2
\
ADULT INGESTION DOSE FACTORS *
(mrem /pCi ingested) .
l l
l NUCLILE BONE LtvE4 T.80CY THYR 010 K10NEY LUNG GI-LLI H 1 NO DATA 1 05E-07 1. 0 5 E-0 7 1.05E-07 1.05E-07 1.05E-07 1.05E-07 C 14 2.84E-06 5.68E-07 5 6 8 E-0 7 5.68E-07 5.68E-07 5.68E-07 5.68E-07 N A. 24 1.70E-06 1.70E-06 1 70E-0 6 1. TOE-06 1.70E-06 1.70E-06 1.70E-06 P 32 1.93E-04 1.20E-05 7.46E-06 NO DATA NC OATA NO DATA 2.17E-05 CR 51 NC OATA NO DATA 2.6oE-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 NN 56 NO DATA 4.57E-06 8 72E-0 7 NO DATA 1.36E-06 NO DATA 1.40E-05 MN 56 NO DATA 1.15E-07 2 04 E-0 8 NO DATA 1.46E-07 NO DATA 3.67E-06 rf 55 2.75E-06 1.90E-06 4.4 J E-0 7 NO DATA NO DATA 1.06E-06 1.09E-06 FE 59 4.34E-06 1.02E-05 3.91E-06 NO DATA NO DATA 2.85E-06 3.40E-05 CO 58 NO DATA 7.45d-07 1.67E-06 NO DATA NO DATA NO DATA 1.51E-05 CO 60 NO DATA 2.14F-06 4. 72 E-0 6 NO DATA NO DATA NO DATA 4.02E-05 NI 63 1.30E-04 9.01E-06 4.36E-06 NO DATA NO DATA NO DATA 1.88E-06 NI 65 5.28E-07 6.86E-08 3.13E-08 NO DATA
NO DATA NO DATA 1.74E-06 CU 64 NO DATA 8.33E-08 3. 91 E-0 8 NO DATA 2.10E-07 NO DATA 7.10E-06 ZN 65 4.84E-06 1.54E-05 6. 96 E-0 6 NO DATA 1 03E-05 NO DATA 9.70E-06 '
ZN 69 1.03E-08 1,97E-08 1. 3 7 E-0 9 NO DATA 1.28E-08 NO DATA 2.96E-09 BR 83 NO DATA NO DATA 4. 02 E-0 8 NO DATA NO DATA NO DATA 5.79E-08 BR 84 NO DATA NO DATA 5.21E-08 NO DATA NO DATA NO DATA 4.09E-13
( BR 85 NO DATA NO DATA 2.14 E-0 9 NO DATA NO DATA NO DATA LT E-24 R8 86 NO DATA 2.11E-05 9. 8 3 E-0 6 NO DATA NO DATA NO DATA 4.16E-06 RB 88 NO DATA 6.05E-08 1. 21 E-0 8 NO DATA NO DATA NO DATA 8.36E-19 A8 89 NO DATA 4.01E-08 2. 82 E-0 8 NO DATA NO DATA NO DATA 2.33E-21 5R 89 3.08E-04 NO DATA 5.84E-06 NO DATA NO DATA NO DATA 4.94E-05 SR 90 7.58E-03 NO DATA 1. 8 6 E-0 3 NO DATA NO DATA NO DATA 2.19E-04 SR 91 5.67E-06 NO DATA 2. 29E-0 7 NO DATA NO DATA NO DATA 2.70E-05 54 92 2.15E-06 NO DATA 9.30E-08 NO DATA NO DATA NO DATA 4.26E-05 Y 90 9.62E-09 NO DATA 2. 5 8 E-10 NO DATA NO DATA NO DAT4 1.0ZE-04 Y 9tM 9.09E-11 NO DATA 3.52E-12 NO DATA NO DATA NO DATA 2.67E-10 Y 91 1.41E-0J NO DATA 3.77E-09 NO DATA NO DATA NO DATA 7.76E-05 Y 92 8.45E-10 NO DATA 2.47E-11 NO DATA NO DA TA NO DATA 1.48E-05 Y 93 2.68E-C1 NO DATA 7.40E-11 NO DATA NO DATA NO DATA 8.50E-05 IR 95 3.04E-08 9.75E-09 6.60E*09 NO DA TA 1.53E-08 NO DATA 3.09E-05 2R 97 1.68E-09 3.39E-10 1.55E-10 NO DATA 5 12E-10 NO DATA 1.05E-04 NS 95 6.22E-09 3.46E-09 1. 86E-0 9 NO DATA 3.42E-09 NO DATA 2.10E-05 MO 99 NO DATA 4.31E-06 8. 2 0 E-0 7 NO DATA 9.76E-06 No DATA 9.99E-06 TC 99M 2.47E-10 6.98E-10 8.89E-09 NO DATA 1.06E-08 3.42E-10 4.13E-07 TC101 2.54E-10 3.66E-10 3. 5 9 E -0 9 NO DATA 6.59E-09 1.87E-10 1.10E-21 RU103 1.85E-07 NO DATA 7.97E-08 No DATA 7.06E-07 NO DATA 2 16E-05 Rul0S 1.54E-08 NU OATA 6.08E-09 NO DATA 1.99E-07 No DATA 9.42E-06
/
t
- Values in Table 1.2-2 are taken from Reference 3, Table E_11
- "N S ""* " ' 5 "' "* " * " " " * " * " " ' * " "" ' ~"
,_ ---___ _m_______. 7.-----_- . . - . _ _ _ _ . - - - , _ _ _ _ _ _ - - _ _ _ _ _ _
-,__.7__.---- _ . _ _ _ - -. - - - . . _ . - . - . . _ _ . - _ _ . . - . . _ - - - - _ _ - _ _ . - - - . . _ _ . -
i I TABLE 1.2-2 (Continued)
L I,2)J:
g Page 2 Of 2
- l hbCL80E !ONE LIvit f . 6 0 CY THvt0!C K10NEY Lu$G G1-LLI FUIC6 2.7SE-06 NO DATA 3.48E-07 NO DATA 5.31E-06 NO DATA 1.78E-06 a;110w 1.o0E-07 1 48E-07 8.79E-08 NO DATA 2.91E-07 NO DATA 6.04E-05 TE125* 2.65E-06 9.71E-07 3. 5 9 E-0 7 8.06E-07 1.09E-05 NO DATA 1.07E-05 TE127= 6.77E-06 2.42C-06 8. 2 5 E-0 7 1.73E 2.75E-05 NO DATA 2.27E-05
, TE127 1.10E-0F 3.95E-08 2. 3 8 E-0 8 8.15E-08 4.48E NO DATA 8.68E-06 l TE129* 1.15E-05 4.29E-06 1. 82 E-0 6 3.95E-06 4.80E-05 NO DATA 5.79E-05 TE129 3.14E-08 1.18E-08 7.63E-09 2.41E-08 1.32E-07 NO DATA 2.37E-08 TE131M 1.73E-06 8.465-07 .7. 0 5 E-0 7 1.34E-06 8.57E-06 NO DATA 8.40E-05 s.- TE131 1.97E-08 8.23E-09 6. 22 E-0 9 1.62E-08 S.63E-08 NO DATA 2.79E-09 TE132 2.52E-06 1.6 3E-06 1.53E-06 1.80E-06 1.57E-05 No DATA 7.71E-05 l" 1 130 7.56E-07 2.2 3E-06 8.80E-07 1.89E-04 3.48E-06 NO DATA 1.92E-06 1 131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 NO DATA 1.57E-06
~~'
1 132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 NO DATA 1.02E-07 i 133 1.42E-06 2.47E 7. 5 3 E-0 7 3.63E-04 4.31E-06 NO DATA 2.22E-06 I 134 1.06E-07 2.88E-07 1. 0 3 E-0 7 4.99E-06 4.58E-07 NO DATA 2.515-10 1 135 ' 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 NO DATA 1.31E-06 C5134 6.22E-05 1.48E 1.21E-04 NO DATA 4.79E-05 1.59E-05 2.59E-06, C5136 6.51E-06 2.57E-05 1. 85 E-0 5 NO DATA 1.43E-05 1.96E-06 2.92E-06
' C5137 7.97E-05 1.09E-04 7.14 E-0 5 NO DATA 3.70E-05 1.23E-05 2.11E-06 C5138 5.52E-08 1.09E-07 5.40E-08 NO DATA 8.01E-08 7.91E-09 4.65E-13 k SA139 9.70E-08 6.91E-11 2. 8 4 E-0 9 NO DATA 6.46E-11 3.92E-11 1.72E-07 OA140 2.03E-05 2.55E-08 1. 3 3 E-0 6 40 DATA 8.67E-09 1.46E-08 4.18E-05 RA141 4.71E-08 1.56E-11 1. 5 9 E-0 9 NO DATA 3.31E-11 2.02E-11 2.22E-17 94142 2.13E-08 '2.19E-11 1. 3 4 E-0 9 NO DATA 1.85E-11 1.24E-11 1.00E-26 LA140 . 2.50E-09 1.26E-09 J.33E-10 NO DATA NO DATA NO DATA 9.25E-05 LA142 1.28E-10 5.82E-11 1. 4 5 E-11 NO DATA NO DATA NO DATA 4.25E-07 CE141 ' 9.36E-09 6.33E-09 7.18E-10 NO DATA 2.94E-09 NO DATA 2.42E-05 CE143 1.65E-09 1.22E-06 1.35E-10 NO DATA 5.37E-10 NO DATA 4.56E-05 CE144 4.A8E-07 2.04E-07 2.62E-08 No DATA 1.21E-07 NO DATA 1.65E-04 PR143 9.20E-09 3.69E-09 4. 5 6 E-10 NO DATA 2.13E-09 NO DATA 4.03E-05 PRl44 3.01E-11 1.25E-11 1.51E-12 NO DATA 7.05E-12 NO DATA 4.33E-18 i N0147 6.29E-09 7.27E-09 4. 3 5 E-10 NO DATA 4.25E-09 No DATA 3.49E-05 l w 117 1.03E-07 8.61E-08 3. 01 E-0 8 NO DATA NO DATA NO DATA 2.82E-05 NP239 1.19E-09 1.17C-10 6. 4 5 E-1 1 NO DATA 3.65E-10 NO DATA 2.40E-05 ll l
1 t ODCM, V.C. Summer, SCEandG: Revision 12 (September 1987) 1.0-32
- ; &. ? ! .,
. ?? y % -
. i s
~ *
? TASGE "L2-3 '
i
.~
SITE RELATED DdDT3DN DDIE IDMITrftiT FACTOR, A
- h ,
(mrem /hr per di/ml) .
muCLSDC: SONC : LIUCD : T.BOIT : 7Mvp0!D: NIDNCY t LUNG : 63-LLI :
N : M-3 :8. 20C + CO
- 9. 96C
- 00 : 5. 96C
- 0@ 3. 96C*te:8.96C+ 00 ? S.96C +00:8.96C + 50 :
- * ~~
- J C-1* l3 15t*04:6. 3 0C + 0 3 : 6. 3 0C a t a : 6. 39C
- 0 3 : 6. 30C + 0 3 : 6. 3 0C + 3 3 : 6. 3 5C+ 0 3 :
. No-24 3 5. d t t + C2 : 5. d S C + 02 : 5. 4 8t
- C2 : 5. d 8C + 82 : 5.49t + 82 :5. 4 8t+ 0 2 : 5. d eC + 02 :
i . . P-32 : 4. 62 C + 0 * : 2. 0 ? C + 06 : 1. 7 9C + 06 : 9. 2 0C + 00 : 9. 80C+89 : 3. 9 8t + 0 9 : 5.2 SE
- S6 :
~
- : Cr-91 : e . 00C- 0 D . C. D CC + 00.1. 4 9C + CO : 8. 9 dC-t t : 3. 29C-01 :1. 9 BC+88 : 3. 7 6C + 82 :
- 0.0CC+CO4.
- 6 C + 0 3 : 9. 08 C + C2 : 0. S tC+ 08 : 1. 4 2C+33 : 8. 9 0C + 0 0 : 1. 4 6C o g d :
- Mn-Se
- Mn-56 : 0. 0cC + c0 :1. 2 0C + C2 : 2.12C + 3 3 : e . BOC+se : 3. 52C+ 52 : 9. 88C* S8 : 3. 82C + 03 : l
- : Fe-!S : 8. t ?C + 02 : 6.13C + 02 : 1. d 3C +S2 : 5. 00C + 00 : 9. 99C+S8 :3.42C+02:3.52C+52: I I
.- : re-19 21. 40C + 0 3 : 3. 2 9C + S 3 :1. 2 &C+ 93 : 9. BSC+ 08 : 3. peC +38 t g.19C+ 02 :1 3 3C+ 34 :
2 : Co-se : e . e a C + 00 : 1. 5 : C + 02 : 3. 39 C + C2 : e. s eC + ee : e. seC+ es : e . seC + es : 3. e 6C + a 3 : l t Co-69 30.00C*tt:4 3 d C + 02 : 9. 59C + 02 : 9. 00C+ 00 ! O. teC+ 08 : 0. 0 0C* SS ! B.16C + 5 3 : l 9 : Na-63 d.39C+04:2. 9 t t + 0 3 : 5. 4 3 C+ 0 .
N.-69 : 1.7 e C + 02 : 2. 2 :C* e t : 1. e : C +.3 : 3. teC+:....C+
ite.0.C+..:...et.. 03 : 9. seC+
0:5.61C. es.:2: 8. 90C + 80 6. 97C + 02 : I
! Cu-64 10. 0 0C + 08 : 3. 6 9C a st : 7. 9 3C + 08 : 8. SSC +39:4.26C+0119.90C+00:1.adC+S3: l
- 2n-65 22.36C+04:7.SeC+ed 3.39C+04:3.00C+se:5.82C+04:8.00C+DO4.73C+04:
- 2n,69 35.02C+tt:9.6CC+0126.67
. .,-t3 : .. 0C +.. : 0. 0C
- 0e . 3.C + f 8 : 3. 03C+ 09 : 6.2.dC+ 01 8. 80C +85 : 1. d dC + 01 C+.S.. 0.C+..:.. .C.O B**Se 2 9. 90 C + 8 8 : 8. 8 0C -t B ! S. 67C + 81 : 0. 99C+98 ; 8.0BC+ DS : 8. StC +9 0 :4.d5C-04:
'9--t! 18. 00C + CC : C . CCC + 0 0 : 2. 3 3 C + 88 : 5. 80C +CD : 5. 90C+ 00 : 8. 80C + 89 : 1. 0 9C-15 !
- Re-94 8.00C+00*8.83C+05:4.79C+84:3.SSC+39:8.SGC+08:3.33C*st:2.33C+34:
RD*te : 0. r eC + 00 : 2. 95t
- er : 1. 5 6t
- B2 : 8. 80C +08 : 9. DeC+ 00 : 8. stC + tt :4.57C-39:
_ ! Rt-69 l 0. FCC
- 0C
- 1. 9 5C + 02 : 1. 3 7 C
- 02 : 3. 98C +89 : 3. 00C + tt : 3. DeC + S8 : 1.13C-t s
- C.teL* Ct:2. 00C + t!:t. SSC+99:3..eC+.0:8.seC+se:7'. . ....C...:3...C+..: 66C+ sa:
Sr=91 : 8. ? 9C + C2 : C . t 3C + CC : 3. 55C + 01 : 2. DOC + 00 : C. 08C+38 : 8. seC+ 38 : 4.19t + 3 3 :
- 5*=92 : 3. 3 2C + 02 : C . e t t + 0 0 : 1. d d C + 81 : 8. 0 0C + 88 : 8. Ott + 99 : 9. 99C + 89 : 6. 68C + 53 : ..
- v=98 11 3 6C +t e : 0. 00C a OS . 3. 6 91-02 ; t . 80C+98 :3.90C+00 : 9. 00C+ 00 :1. 46C +S A :
- Y-93* *l.3CC-02*t.0DC+rC*f.edC 04:3.0tt+00:8.89C*te:8.etC+00:3.82C-82:
-O' : v-91 l 2. 92C + 01. C . t DC + te ' 5. 3 9 C -8 8 : 8.DeC + 88 : 3. 04C+00 : 8. 00C+ S8 :3.11 C + 04 :
T-92 : 1. 21 C -01 ; t . CCC + CP ' 3. 5 3C = C3 : 8. eaC +00 : 8. StC+S8 : 8. 80C + 08 : 2.12C + 8 3 :
- Y-91 '3.0)C-C1.C.00C-90:1.86C-02:3.90C+00 f.StC+98:8.9BC+S8it.22C*Se:
. 2r-tf :2. 77t+ CC . S. TIC-S S : 6. 81 C 91 : 8. 00C+ 08 : 8.39t+08 ;S.80C+0tl2. 82C+ 03 :
2r-?? :1 53C+C1.3. tit-02.8.41C-02:9.Stt+tt:4. 67C-t 2 : 8. B BC + 3 8 : 9. 57t + 0 3 :
- MS*$f Id.d*C+02:2.dSCofl.a.3dC*02:9. sac +38:2.46t*S2:3.08C+88:1.51C+06:
- 0. CCC + CO ' d. 61C + C2 t.?9t+ 01 : 8. SCC +90 :1.25C+ 03 :8.80C+ 08 :1.07C *S3 ;
(. : Mo-99
? ft-99m
- ft-:t1
- 2. 9 d C -02 : 9. 32 C a t t : 1. 0& C + 2 0 : 8. 8 0C + 88 :1. 26C +SS:4.97C-82:4.92C+S8:
- 3.P2C-02:4.3fC-E2:4 3C-82:1.3tC-Rv=103 .5dC.Ce.. i:
i R*-105 11 99 C + 8 8 :9. eet.ee . 2 GC =C1 : 0.00Ce tC f 7.SSC-Ot
- 1. 6 f C + 20 : 0. 00C-ee 6. ...C+C3:2.i3C.. 5 2C.. . .. e.C...:... 7. 57t+.i C...: :.. .sic *t3:
e v-le6 : 2. 95 C + 02 : 9. O OC + 00. 3.7 3C + 9 8 : 9. 9tt + SS
- 5.69C+ 82 : 3. 00C +0 8 :1. 91 C + 0 4 :
- 80
- 1 t os !1. 4 2C + C1 :1. 31 C + 01 : 7. 0 0C + 00 : 5. 00C+ 00 : 2.50C +e t : 5. s eC + se : 5. 36C + s 3 :l i Te-125a.Z.79C+83:1.21C+83:3.7dC+02:8.39C+02:1+13C+94:3.S$C+SS 1.13C+Sd:
7e- 3 2 ? s : 7. c5C + c 3 : 2.52C + t 3 : 8. 5 9C + 32 :1. 80C+ 03 :2. 06t+ 84 :3.80C+00:2.36C*Sd:
- 7e-32' !1.3dC+C2:4 11C+01:2.40C+01:8.dBC+ta:4. 65C+ 02 : 3. 8 0C+ 08 : 9. 8 3C+ 0 3 :
. Te=329s.t.2CC+04:4.d?C-03:1.99C+t3:4.11C+t3:3.SeC+S4:8.00C+88:6.83C+B4:
- 7e-129 2 3.27t +01:1.C3C* 01:7.96C+ 0C
- 2.51C+31:1.37C+02:9.80C+88:2.47C +01:
T e = 3 31e: 1. scc + t) . 0.81C + 02 :7.3 dC+ st : 3.3 9C+ 93 : 8.92C+0 3 :5.00C*es:5.7dC+Bd 7e-131 : 2. C S C + C 1 : 8. !'C
- CC : 6. 4 7C + 00 : 1. 69C+0118. 99t+ 3 8 : 0. 58C
- SS : 2. 90C + 88 :
- 7e-132 2 62C+t3:1.*CC+03:1.C9t+83:1.37C+s3:3.63C+84:8.88C+00:0.82C+S4:
- 1-138
- !=131 9. 01 C + 01 : 2. 6:.
ld.96C+tt:7.e,C.e2 4C + 0 2:2.32C+ts 06t+e2 : 1. 8 ? C+ 0 2 : 2.3:25C+
- 1.22C. 0 d !d 7C+.2:
, C+..:1. .15C+ 02 : 8. 00.C+95 : 2. 29:* S2
- 1-132 12. 4 2 C + 0 3 : 6. d ? C
- C 1 : 2. 2 6T + 01 : 2. 26t+ 03 :1.8 3C+ 02 : 3. 98C+ 00 ! t .22C+ 01 :
- 1-333 : 1. 6 9 C+ 02 : 2. t d C
- t2 : 8. 9 7 C+ 01 :4.32C+84:5.13C+82:5.00C+98:2.6dC+er:
2-134 11. 2 6C + 0 8 : 3. 4 3C + 01 : 1. 2 3C + 5 8 : 5.9 dC+ st :5.46t+e s :8. 88t* es : 2. 9 9C-st :
1 L-135 :5,20C* t111 e 3f C+Cri5. 8 9C+ 01:9 llc +93!2.22C* 02:9.99C+ BS: 3.56C+st :
- rs-334 : 3 0 3C+ ts :7. 21 C*tS : 5. 5 9t + t5 : 9. eeC+88 :2.33C+95 :7.75C+Cd :1.26t+S4 :
- Cs-136 3.l?C+04:1.25Catf 9.01C+04:8 BBC*00:6.97C+84:9.55C+83 1.42C+04:
! Cs-137 13. S SC
- Cf
- f . 31C + 05 : 3. 4 0C
- t5 : 3.99C*te :1.99C+ kS:5. 95C+ 94 :1.83C+84:
Cs-SSB : 2. 6 9C + 22 : 5. 31 C + ct : 2. 6 3 C + s t . t . Setete :3. 90C+ 3 2 :3. 8 5C + e t :2.2?C-83:
- B a- 3 39
- S. 00C + 00. 6. e t t-0 3. 2. 6 dC-91
- 0. 00C+ 50 :5.99C-03 :3. 64C-9 3 :1. 68C+01
- 3 a-14 9 1. S SC* C 3
- 2. 37t + te:1. 2 3C + S2 : 8. e0C + 00 : 5 /0*C-81 :1. 3 5C+ 88 : 3. S SC + 3 3 :
- 34-143 d. 37C
- re: 3
- 39C-0 3 :1.4 0C 9119. 80C+99: 3.8?C-93:1. 57 Cat 3 :2.t EC=89 :
3 4-142 11. 9 9C + 60 : 2. 8 3C = 0 3 : 1. 2 d C-0 8 : 3. t SC + 00 :1.72C-9 3 :1.15C-0 3 : 2. 7 8C-18 :
- Ls=1dc :3.58C*tt:8.tCC-et:4. 7 6C a t2 : 9. 8cC
- rt : 5. 8tC+ 98 : 8. 8 0C + 0 0 :1. 32 C + 8 4 :
- La-182 !1. 0 3C *02 : 9 3 3C-0 3 : 2 0?C-0 3 : 9. 00C+ tt . S. SDt+D8 : 8. 00C+00 :6.SSC+38:
! Ce-let 18.21C-et:5.42C-91:6.15C-02:9. B BC + 80 : 2. 52C-51 8. S SC+ 0 8 : 2. 0 ?C+ 0 3 :
Ce 14 3 11. d 1 C-O l : 1. P 8 C
- 0 2 : 1.16C-02 : 0. 0 0C + 88 :4. 60C-8 2 : 9. t 0C + 0 0 : 3. 9eC + 0 3 :
. Ce. led 4. s g C + 01 : 1. 7 5 C + 01 : 2. 2 d r
- e t : 5. 80C+ 00 : 1. sd C + 01 : 8. 99t + 09 : 1. d t t + S d :
. pr-343 : 3. 32 C + Ce
- g . 2 0 C-01 : 6.52E-82 : 8. stt+ se :3.tSC-SI 8. 90C* SO :5.77t + 03:
. Pr-idd :d.31C-03:1. 7 9 C -0 3 : 2. 3 9 C-0 4 :3.00C*SS:1.03C-83:D.teC+08:6.19C-10:
. No-147 19.80C-Ot:1.edC*ee:6.22C 92:9.00C+88:6.80C-OS 0.SS 4.99C+03:
- w le? : 3.edC* t2 :2. C+C2.s.90C* e s :0.stt+e0:e.seC+es:5.0 C+88:
C+es:0.3dC*sd:
. ~6-239 :1.2st-ci .25C 02:6.9 6-e3:0.e0C+e0:3.9:C-s2:9.eeC+ee:2.57C+S3:
- Calculated using equation (32 ) and Tables 1+2-1 arri 1+2-2.
00CM, V.C. Summer, SCE&G: Revisio 12 (September 1987) 1.0-33
I 1.3 Definitions of Effluent Parameters (continued Term Definition Section of Initial Use !
A" = the site related ingestion dose commitment 1.2 factor to the total body or any organ t, for each identified principal gamma and beta emitter listed in Table 1.2-3 in mrem-ml per br-uCi.
B = adjustment factor which will allow the set- 1.1.3.1 point to be established in a convenient manner and to prevent spurious alarms.
BF * = Bioaccumulation Factor for nuclide i,in fish, 1.2 PCi/Kg per pCi/l, from Table 1.2-1.
C = the effluent concentration limit (Specifica- 1.1.1 tion 3.11.1.1) implementing 10CFR 20 for the site, in uCi/mi.
i C*
= the effluent concentration of alpha 1.1.1 l emitting nuclides observed by gross alpha -
analysis of the monthly composite sample. ,
C, = the measured concentration of Fe-55 in 1.1.1 liquid waste as determined by analysis of the most recent available quarterly com-O nesitesemn'e-C 8
= the effluent concentration of a gamma 1.1.1 emitting nuclide, g, observed by gamma-ray spectroscopy of the waste sample.
C' = the concentration of nuclide,i, as 1.1.1 determined by the analysis of the waste sample.
C, = the average concentration of radionuclides, 1.2 i,in undiluted liquid effluent during time period At, from any liquid released,in uCi/ml.
C" = the concentration of radionuclides iin the 1.1.1 Monticello Reservoir.
C, = the concentration of Sr-89 or Sr-90 in liquid 1.1.1 wastes as determined by analysis of the quarterly composite sample.
ODCM, V.C. Summer, SCEandG: Revision 12 (September 1987)
Page 1.0-34
1.3 Definitions of Effluent Parameters (continued i
Term Definition bC nit Use O
C, = the measured concentration of H-3 in liquid 1.1.1 waste as determined by analysis of the monthly composite.
c = the setpoint,in uCi/ml, of the radioactivity 1.1.1 monitor measuring the radioactivity con-centration in the effluent line prior to dilu-tion and subsequent release.
c, = the monitor setpoint for RM-L7, the 1.1.1 Nuclear Blowdown Monitor Tank discharge line monitor.
c c
= the monitor setpoint for RM-L9, the com- 1.1.1 bined Liquid Waste Processing System and Nuclear Blowdown System effluent discharge line monitor.
co = the monitor setpoint for RM-L11, the Con- 1.1.3.1 densate Demineralized Backwash discharge line monitor.
cy = the monitor setpoint for RM L5, the Waste 1.1.1 c,s
=
MonitorTank discharge line monitor.
the monitor setpoint for RM-L3, the initial 1.1.3.1 g
Steam Generator Blowdown Effluent line monitor, c s3 = the monitor setpoint for RM-L10, the final 1.1.3.1 Steam Generator Blowdown Effluent line monitor.
c7 = the monitor setpoint for RM-L8, the Tur- 1.1.3.1 bine Building Sump Effluent line monitor.
CF o = the Condensate Demineralize Backwash 1.1.3.1 Effluent Concentration Factor.
CF 3 = the Steam Generator Blowdown Effluent 1.1.3.2 Concentration Factor.
CF 7 = the Turbine Building Sump EHluent Con- 1.1.3.1 centration Factor.
ODCM, V.C. Summer, SCEandG: Revision 12 (September 1987)
Page 1.0-35 g
r ... -
l l1.3 Definitions of Effluent Parameters (continued x,
Term Definition Section of initial Use L
.DF = the dilution factor, which is the ratio of the 1.1.1' total dilution flow rate to the effluent stream flow rate (s)
DF" = a dose conversion factor for nuclide, i, for 1.2 adults in preselected organ,T,in mrem /pCi
, found in Table 1.2-2.
D' = the cumulative dose commitment to the 1.2 total body or any organ, t , from the liquid effluents for the total time period.
D* = Dilution Factor from the near field area 1.2 within one-quarter mile 'of the release i points to the potable water intake for adult water consumption; for V. C. Summer, D,
='1.
F = the dilution water flow setpoint as deter- 1.it1 mined prior to the release,in volume per ,
unit time.
F, = the flow rate of the Circulating Water 1.1.3.1 the time of release of the O System Terei"e 8""<durinfing 5 mp and/ rthe Steam Generator Blowdown.
F d
= the dilution flow rate of the Circulating 1.1.3.1 Water System upon which the setpoint is based, as corrected for any recirculated radioactivity.
F, = the flow rate of water through the Fairfield 1.1.1 ,
Pumped Storage Station penstock (s) to which radioactive liquids are being dis-charged during the period of effluent re- >
lease.This flow rate is dependent upon operational status of Fairfield Pumped Storage Station.
f = the flow setpoint as determined for the 1.1.1 radiation monitor location.
fo = the maximum permissible discharge flow- 1.1.3.1 rate for releases to the circulating Water.
ODCM, V.C. Summer, SCEandG: Revision 12 (September 1987)
Page 1.0 36
1.3 Definitions of Effluent Parameters (continued
'C "
Term Definition it Use
- f. = the flow rate of the Nuclear Blowdown 1.1.1 Monitor Tank discharge.
f, e
= the flow rate of a Waste Monitor Tank dis- 1.1.1 charge.
f' d
= the flow rate of the Steam Generator Blow-down discharge.
1.1.3.1 f' = the recirculation flow rate used to mix the 1.1.1 contents of a tank.
f, = the maximum permissible discharge flow 1.1.1 rate for batch releases to the penstocks.
F og = the dilution flow rate through the pen- 1.1.1 stock (s) receiving the radioactive liquid re-lease upon which the effluent monitor set-point is based, as corrected for any recircu- ^-
lated radioactivity.
F, = the near field average dilution factor for C a 1.2 during any liquid effluent release.
K, = 1.14 x 105, units conversion factor. 1.2 g M PC, = MPC , MPC,, MPC,, MPC,, and MPC, = the 1.1.1 !
limitfng concentrations of the appropriate gamma emitting, alpha emitting, and l strontium radionuclides, Fe-55, and tritium, .'
respectively, from 10CFR, Part 20, Appendix B, Table 11, Column 2. For gamma emitting noble gas radionuclides, MPC = 2 x 10 4 uCi/ml, according to the Radiological Efflu-ent Technical Specifications.
SF = the safety factor, a conservative factor used 1.1.1 to compensate for engineering and measurement uncertainties. SF = 0.5, corresponding to a 100 percent variation.
[E Ci]s = the sum of the measur.:d radionuclides 1.1.1 concentrations of the Nuclear Blowdown Monitor Tank.
ODCM, V.C. Summer, SCEandG: Revision 12 (September 1987)
Page 1.0 37 g
i 1.3 Definitions of Effluent Parameters (continued
_ l l
- m. .
l Term Definition " '
k't Use
[ Ci]t,g = the Lower Limit of Detection, LLD, for 1.1.2 radionuclides i in liquid waste in the Waste (
Monitor Tank, as determined by Technical Specifications, Table 4.11-1.
[E Ci]y = the sum of the measured radionuclides 1.1.1 }
concentrations for a Waste Monitor Tank.
{
= the sum of the measured radionuclides
[E Ci]3 1.1.3.1 concentrations for the Steam Generator Blowdown l
= the sum of the measured radionuclides
[E Ci]o 1.1.3.1 l concentrations for the Condensate Demineralized Backwash.
=
[ECi]r the sum of the measured radionuclides 1.1.3.1 concentrations for the Turbine Building Sump. .'
i
[E (C;/MPC i )]3 = the sum of the ratios of the measured 1.1 '.1 concentration of nuclideito itslimiting value MPC for the Nuclear Blowdown
,, .s Monitor Tdnk.
(,) [E (Ci/ MPCi)]y = the sum of the ratios of the measured 1.1.1 concentration of nuclide i to its limiting for the Waste Monitor Tank value MPC,idered for release.
being cons
[E (Ci /MPCi)]3 = the sum of the ratios of the measured 1.1.3.1 concentration of nuclide i to its limiting value MPC, for the Steam Generator Blowdown Effluent.
[E (Ci /MPCi)]3 = the sum of the ratios of the measured 1 1.3.1 concentration of nuclide i to its limiting value MPC for the Condensate Demineralized Backwash.
[E (Ci/ MPCi)]r = the sum of the ratios of the measured 1.1.3.1 concentration of nuclide i to its limiting value MPC, for the Turbine Building Sump Effluent.
t, = the minimum time for recirculating the 1.1.1 contents of a tank prior to sampling.
ODCM, V.C. Summer, SCEandG: Revision 12 (September 1937)
(q) Page 1.0-38
- o. ;
1.3 Definitions of Effluent Parameters (cortinued Term Definition Section of ,
initial Use '
Atk = the length in hours of a time period over '
1.2 which concentrerons and flow rates are .Y averaged for dose calculations. S ,"
d ;y U, = 21 kg/yr, fisp conitg'ption (adult). g 1.2 s no additional dilution is to be considered; 2 = 1.
I
\ )
?
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O
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% /,
n /' ,
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( 3, f
e
<,% q a
l ODCM, V.C. Summer, SCEandG: Resion 12 (September 1987) )
Page 1.0-39 v
\
i
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w" %
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I 3
2.0 GASEOUS EFFLUENTS ,
?
J l 2,1 _ Gaseous Effluent Monitor Setpoints i l '
The calculated setpoint values will be regsroed as upper bot.nds for j the actbal setpoint adjustments. That is, setpoint adjustrnent's are not I required to be performed if the existing setpoint level corresponds to j a lower count rate than the calculated value.
i i i 2.1.1 5tation Vent Nghle Gas Monitors '
For the purpose of implement 3fion of section 3.3.3.9 of the b '
. Technical 5 specifications, the MarnY setpoint level icr the station v
j i i ' Ant noble gas monitors will be calculated as followN:
ws ,
5,, = l count rate of helplant vegt noble gas monitor (= s
/ ' 5; for RM A3)'or the con @nment purge noble gas t
,, ,- menitor (= 5, for RM;Aiy,at the alarm setpoint 1
1piel. ..
h ,'
3, 1
.i '0.25 x, R x Oh ~ / (33) i '
J' 5 the lesser of 4 or 0.25 x R, x D 33 .
(34) 0.25 = the safety factor applied to eads vf the two vent noble gas monitors (plant vent anki containment -
purge) to arsure that the sum o'. dvd releases has a
]
combined safdty factor of OJ wh!6 allows a 10C, g percent margin for cumulative unce' dainties of ' i measurements. '
t j
w; e Du = . Dore _ rate limit to the total body of an ina'ividual t
= 100 r'nrern/yr
( R, = ; c vt;nt rate per mrern/yr to the total body t
i ODCM, V.C. Summer, SCE&G: Revision 12 (September 1937) 2.0-1
[
l t
(T%).
= C, / ((XTQ) x F, x E K,X,,)
t (35)
X,, = the measured concentration of noble gas radionuclides i in the last grab sample analyzed for vent v, pCi/ml.
., (For the plant venti grab samples are taken at least monthly. For the 6" and 36" containment purge lines,
~ the sample is taken just prior to the release and also monthly,if the release is continuous.) '
F, = the flow rate in vent v, cc/sec. (1 cc/sec = 0.002119 cfm) .
C, = - count rate of the monitor on station vent v cor--
1 responding to grab sample noble gas concentrations, X,,, as determined from the monitor's calibration '-
curve. (Initial calibration curves of the type shown in .
Figure 2.1-1 have been determined conservatively from families of response curves supplied by the g
. ..h monitor manufacturers. As releases occur, a historical _!
correlation will be prepared and placed in service when sufficient data are accumulated.)
l 4
X7/ = the highest annual average relative concentration in any sector, at the site boundary.
= 5.3 x 104sec/m 3in the SE sector
- j i
K, = total body dose factor due to gamma emissions from '
isotope i (mrem /yr per pCi/m3) from Table 2.1-1. 1 i
D ss = Dose rate limit to the skin of the body of an individual
, in an unrestricted area
= 3000 mrem / year.
Reference 4, Section 11.3.8 states that this is the annual average relative dispersion at the point on the exclusion boundary where highest concentra-tions may be expected.
ODCM, V.C. Summer, SCE&G: Revision 12 (September 1987) 2.0-2 l
_. ,$ i l
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_ : r r = c = = 1 n =: =. = r _ iig .Mb _ _ _ ____g r - - : :== : = = r 1 = r ;
)-- .
jgi.C --. :: * ------=_==a-
.=.4_==.._r_.=.=:=-==-_====g=.====-J=d:....,.,."
- r- , C . 2'.8.D.C... = =
C .". - _"- y,.=cd.*.E '- 2 0..C_ :-....=====--=.;==_2- .~__~.~_":~.
eme-i:s:~... ===.==g=.=...=.=.....=.. 4..ll;.".===. .. =.=.. .::=.".'. =.=..=... =-,=...=. =.~. ."".C. .=.=...:.:.=-
4 . . . . .
=""*.'2
.. 7-10-5 ~ . === . .=... .n . .m , =. .- . . .=m=-----
Mg (*70g%
MB34etillilJ p - fil4. .! m=- en=.
'f~*,'e *t J, ' .* ....v.....J'.
be
=:=.===..= :=:r:===::::m==.
. i *
- I f ' ' 'i :' 88 '*5'a
'8'**'
.~..n..~ .
OJ8 ' *I'
- I4846.l*" J ' . fl.lMt.L ** J II
= . . . . . . . . . . . . . . ~ ... . . .
8, ' Il l'"'
- l'
- ki. le'd ,4 - ' . . ? ' ' . 't > t tri m' :.:k,;;;. c., .".'..li'..- 3 i
O *!f 5 8690s.h k vAe54 aid $ ' '
WI.
' .ak.m1grint.Ci. ' '.L..'.Jf- ".').'..1J8W.
- * +: - '%
- J.. N .7 . ..
- k. f' . '4 % el$
Mt Tg, J , : ; ;j s t. .. '. '
, . ;, / . - _ , < e i . C"". 'j'My @,& , ' 7 . t .W*1' . MG
,,. p . f gr- y#,$E ,
d isd E.?.M:-M, masa m.a :9 m .r _:M!=2E,fi" .w tRMM,e f@ua:is.WhadaMAEWRE auassnr a _i,,"M _Wc i * == =2= ==#=J 595
-- - * ; : ee .- m. . :,a , : w _s..w . - .ns .n.m,v w su . .u.... m .m n, ._ : r.
.. .. ~.n .
,c.
- mMEEPHEiEHiiEiERREMgngil511155RIBUMigggggggggg n .w w - - = ~ ~ n : - n _ _..a.<r>ma E a
- " " . NE".:. -
10,10EERIERHill!E!!OREHERilEEERMHilli!!!iiiMHRHilMEMEE 3 10 10 5 10" 10 10 CountRate(cpm) _ _ _ _ __ __ _ _ _ -
(^'.;
-V: O R, = count rate per mrem /yr to the skin
=
Cv + [RTQ x Fv x lC (Li + 1.1M i) Xiv) (36)
L, = skin dose. factor due to beta emissions from isotope i (mrem /yr per pCi/m )3 from_ Table 2.1-1.
= mrem skin dose per mrad air dose 1.1 M, = air dose factor due to gamma emissions from isotope i (mrad /yr per pCi/m3 ) from Table 2.1-1.
NOTE: If two simultaneous releases out of the main plant vent should occur, calculate the setpoint for each type of release and use lowest setpoint obtained. At plant startups when no grab sample analysis is available for the-continuous 4 releases, the Alternate Methodology of Section 2.1.3 must ,'
be used.
'i 2.1.2 ' Waste Gas Decay System ;
The permissible conditions for discharge through the waste gas ;
decay system monitor (RM-A10) will be calculated in a manner i
~
similar to tha't for the plant vent noble gas monitor. In the case of 1
the waste gas system, however, the discharge flow rate is co'n-
{
tinuously controllable by valve HCV-014 and permissible release I conditions are theref.,re defined in terms of both flow rate and concentration. Whereas, RMA-10 is used only to insure that a '
representative sample was obtained.
l l
l ODCM, V.C. Summer SCE&G: Revision 12 (September 1987) 2.0-4 l
l
For operational convenience, (to prevent spurious alarms due to fluctuations in background) the setpoint level will be established at 1.5 times the measured waste concentration.
The maximum permissible flow rate will be set on the same basis but include the engineering safety factor of 0.5. The RM-A10 setpointlevelSoisdefined as:
Sg < 1.5c (37) where:
c = count rate of the waste gas decay system monitor corresponding to the measured concentration (pCi/ml).
The maximum permissible waste gas flowrate f, (cc/sec) is ,
calculated from the maximum permissible dose rates at the site boundary according to:
f,5 the lesser of f, or f, (38) where:
f, = the maximum permissible discharge rate based on total body dose rate.
= 0.2 5 x Da / [XTQ x 1.5 E X,g y @)
I f, = the maximum permissible discharge rate based on skin dose rate.
= 0.25 x Ds3/[X/Q x 1.5 X,g (L, + 1.1 M,)] (40)
Xid = the concentration of noble gas radionuclides iin the waste gas decay tank whose contents are to be discharged, as corrected to the pressure of the discharge stream at the point of the flowrate measurement. The maximum discharge pressure as governed by the diaphragm valve, 7896, is 30 psia.
O ODCM, V.C. Summer, SCE&G: Revision 12 (September 1987) 2.0 5
=
NOTE: The factor of 1.5 in the denominators of equations (39) and (40) places f, on the same basis as So .
When a discharge is to be conducted, valve HCV-014 is to be opened until (a) the waste gas discharge flowrate reaches 0.9 x f, or (b) the count rate of the plant vent noble gas monitor RM-A3 approaches its setpoint, whichever of the above conditions is reached first.
When no discharges are being made from the Waste Gas Decay System, the RM-A10 setpoint should be established as near background as practical to prevent spurious alarms and yet alarm in the event of an inadvertent release. 1 2.1.3 Alternative Methodoloav for Establishing Conservative Setpoints !
A more conservative setpoint may be calculated to minimize requirements for adjustment of the monitor as follows: h' For a plant vent:
R,' = conservative count rate per mrem /yr to the total body (Xe-133 detection, Kr-89 dose).
= C,' + [X/O x K x ,.3, x X,' x F,], M1) where:
X,' = a concentration of Xe-133 chosen to be in the operating range of the monitor on vent v, pCi/cc.
C,' = the count rate of the monitor on vent v corresponding to X,' pCi/cc of Xe-133.
K x, . ,, = tod Mdy de kdm 6 bM, & mu mWde isotope from Table 2.1-1.
O ODCM, V.C. Summer, SCE&G: Revision 12 (September 1987) 2.0-6
R,' = count rate per mrem /yr to the skin.
= C,' + [7TQ x (LKr-89
- 1 *1 Ki-89
- v* v 1
where:
Lx ,.39 = skin dose factor for Kr-89, the most restrictive isotope from Table 2.1-1.
j M x ,.,9 = air dose factor for Kr-89, the most restrictive isotope, from Table 2.1-1.
For the waste gas decay system:
f,' =
the conservative maximum permissible discharge rate .,
based on Kr-89 total body dose rate.
= 0.25 x Die + [X/Q x 1.5 x XgN Kx,.,g] (43) f,' = the conservative maximum permissible discharge rate based on Kr-89 skin dose rate.
~
= 0.25 x D 33 + [X/O x 1.5 x Xo'x (L x ,.,9 + 1.W K r-89 X' o
= the total concentration of noble gas radionuclides in the waste gas decay tank whose contents are to be discharged, as corrected to the pressure of the discharge stream at the point of the flow measurement.
c' = count rate of the waste gas decay system monitor corresponding to X,' pCi/cc of Kr-85.
O ODCM, V.C. Summer, SCE&G: Revision 12 (September 1987) 2.0-7
O TABLE 2.1-1 DOSE FACTORS FOR EXPOSURE TO A SEMI-tNFINITE CLOUD OF NOBLE GASES,*
i Nuclide y Bodv* * * (K) 6-Skin * * * (L) y-Air * *(M) B-Air * *(N)
Kr-85m 1.17 E + 03 * * *
- 1.46E + 03 1.23E + 03 1.97E + 03 Kr-85 1.61 E + 01 1.34E + 03 1.72E + 01 1.95E + 03 Kr-87 5.92E + 03 9.73E + 03 6.17E + 03 1.03E + 04 Kr-88 1.47E + 04 2.37E + 03 1.52E + 04 2.93E + 03 Kr-89 1.66E + 04 1.01E + 04 1.73E + 04 1.06E + 04 Kr-90 1.56E + 04 7.29E + 03 1.63E + 04 7.83E + 03 4 Xe-131m 9.15E + 01 4.76E + 02 1.56E + 02 1.11 E + 03 Xe-133m 2.51 E + 02 9.94E + 02 3.27E + 02 1.48E + 03 Xe-133 2.94E + 02 3.06E + 02 3.53E + 02 1.05E + 03 Xe-135m . 3.12E + 03 7.11E + 02 3.36E + 03 7.39E + O2 Xe-135 1.81E + 03 1.86E + 03 1.92E + 03 2.46E + 03 Xe-137 1.42 E + 03 1.22 E + 04 1.51E + 03 1.27E + 04 Xe-138 8.83E + 03 4.13E + 03 9.21E + 03 4.75E + 03 Ar-41 8.84E + 03 2.69E + 03 9.30E + 03 3.28E + 03
- Values taken from Reference 3, Table B-1
- m rad-m3 pCi-yr
- *
- mrem-m3 pCi-yr
- * *
- 1.17E + 03 = 1.17 x 103 O
ODCM, V.C. Summer, SCE&G: Revision 12 (September 1987) 2.0 8
O 2.2 Gaseous Effluent Dose Calculations 2.2.1 Unrestricted Area Boundary Dose 2.2.1.a For the purpose of implementation of section 3.11.2.1a of the Technical Specifications, the dose at the unrestricted area boundary due to noble gases shall be calculated as follows:
D, = current total body dose rate (mrem /yr)
~
= X/Q K, d, (45) i D3 = current skin dose rate (mrem /yr)
= X/Q (L, + 1.1 M,) Q, (46) 1 where:
Q, = the release rate of noble gas radionuclides i as determined from the concentration measured in the analysis of the appropriate sample required by Radiological Effluent Technical Specification Table 4.11-2 (pCi/sec.).
~
X/Q = the highest annual average relative concen-tration in any sector, at the site boundary (for value, see Section 2.1.1).
2.2.1.b Organ doses due to radiciodines and all radioactive materials in particulate form and radionuclides (other than noble gases) with half-lives greater than eight days, will be calculated for the purpose of implementation of Technical Specification section 3.11.2.1.b as follows:
l D, = current organ dose rate (mrem /yr)
O ODCM, V.C. Summer, SCE&G: Revision 12 (September 1987) 2.0-9 l
1 i
~
= E X/Q P, I
, (47) G where:
1 X/Q = the highest annual average relative concentration in any sector, at the site boundary (for value, see Section 2.1.1)
P, = dose parameter for radionuclides i, (mrem /yr per pCi/m3) for inhalation, from Table 2.2-1.
Q,' = the release rate of non-noble gas radionuclides i as determined from the concentrations measured in the analysis of the appropriate -
sample required by Radiological Effluent j Technical Specification Table 4.11-2 (pCi/sec).
O 2.2.2 Unrestricted Area Dose to Individual 2.2.2.a For the purpose of sections 3.11.2.2 and 3.11.2.4 of the Technical Specifications, the air dose in unrestricted areas shall be determined as follows:
Dy = air dose due to gamma emissions from noble gas radionuclides i(mrad) u
= 3.17 x 10~8 E M, X/O Q, (48) i where:
3.17 x 10* = the fraction of one year per one second Q, = cumulative release of noble gas radionuclides i over the period of interest (pCi).
O ODCM, V.C. Summer, SCE&G: Revision 12 (September 1987) 2.0-10
O. Dp = air due to beta emissions from noble gas radionuclides i (mrad).
= 3.17 x 10 8 E N, X/Q% (49) i where:
N, = air dose factor due to beta emissions from noble gas radionuclides i (mrad /yr per pCi/m3 ) frorn Table 2.1-1.
l 2.2.2.b Dose to an individual from radioiodines and radioactive materials in particulate form and radionuclides (other than l noble gases), with half-lives greater than eight (8) days will be calculated for the purpose of implementation of section i 3.11.2.3 of the Technical Specifications as follows:
D"
= dose to an individ'ual from radioiodines and O <ea'eeec'>aes>e nert'< 'e1e form. ~i16 hei<-iives greater than eight days (mrem)
= 3.17 x 10 8 I R,, W,, '%', (50) y where:
W,,' = relative concentration or relative deposition for the maximum exposed individual, as appropriate for exposure pathway j and radionuclides i.
~
X/Q' for inhalation and all tritium pathways
= 2.2 x 104sec/m3
= <
FQ' for other pathways and non-tritium radio-nuclides
= 8.4 x 104 nr 2 s
O O DCM, V.C. Su mme r, SCE &G: Revision 12 (September 1987)
(See the notes to Table 2.2-7 and 2.2-8 for the origin of these factors.)
R ,, = dose factor for radionuclides i and pathway j, (mrem /yr per pCi/m3 ) or (m2- mrem /yr per I pCi/sec) from Table 2.2-2.
s k' = Cumulative release of non-noble gas radionuclides i (required by Technical Specification 3.11.2.3) over the period of interest (pCi).
2.2.2.c For the purpose of initial assessments of the impact of unplanned gaseous releases required by Section 6.9.1.13 of .
the RETS, dose calculations for the critical receptor in each affected sector may be performed using the above equations as follows. For each location, X/Q' and D/Q' will be calculated according to the methods of Section 2.3 of this ODCM, using the measured meteorological parameters h
for the period of the unplanned release. The location of the critical receptors and the pathways j which should be analyzed for each are shown in Table 2.2-7. (For very
~
rough calculations, the annual average X/Q and DTQ for each receptor are shown in Table 2.2 8.) The R,, for the appropriate exposure pathways and age groups will be selected from Tables 2.2-3 through 2.2-6.
O ODCM, V.C. Summer, SCE&G: Revision 12 (September 1987) 2.0-12
1 i
4 1
. .. . y 1
1 1
)
Tab ?e 2.2-1 i h-s./- PATHAY DOSE FACTOR S FOR SECT IONj 2.2.1.b (P )*
1 i
N ,,
Page 1 of. 3 ,
AGE GROUP ( CHILD )
l.ISOTOPEI INHALAT
____________________ ION ____- 1 IH 3 1 1.125E+0 l i
__________..__________3___' 1 l IC 14 1 3.589E+04 \
________________________1 !
INA 24 1 1.610E+04 j
____________________1 IP-32 1 2.605E+06
________________________I ICR 51 1 1.698E+04
________________________l .
IMN-54 1 1.576E+06 I 1
.___..____________________ l IMN 56 1 1.232E+0
____________________5____ I IFE i 1.iiOE+05 I
____-55 ____________________ Y IFE-59 I i.269E+0 I
______________ ______6___ l ICD-58 I i'.10 6E + 0 6 1 5Cb255~~~I~~fI55fE+55~~
g- ________________________i INI-63
.n .
l 8.214E+05 q
\ ________________________I
, INI-65 l 8.399E+04
_________'_______________I ;
ICU-64 1 3.670E+04 I q Iis65-~~I~~i!ii3E~ii-~I -~ ,
Tis si'~~I-~iT5iiE!i4
________________________i IBR 83 1 4.736E+0 I
_____________________2 ___ I IBR 84 1 5.476E+0 1
____________________2____
IBR-85 1 2.531E+01 1 iR5555~~~I~~iI9555
____________________05~~i ____
5.624E+02 I 1
I R B __88 IRB-89 1 3.452E+02
_______________________i 15R-89 1 2.157E+06
_______________________i ISR-90 1 1.010E+08 1 ISR-91 1 1.739E+05 1 See note, page 2. 0-16 x .
Units _ mrem /yr per pCi/m a g
me nn - ^^
Taole 2.2-1 (Continued)
- l PATHmY 00SE FACTORS FOR SECTION 2.2.1.b (Pj )
Page 2 of 3 AGE GROUP ( CHILD )
l ISOTOPEI INHALATION I i iSR-92~~~I~~2IIbkE 55~ I lY 90 l 2.679E+05 l lY 91M i 2.812E+03 1 lY 91 1 2.627E+06 i lY-92 1 2.390E+05 1
\ lY 93 1 3.885E+05 i IZR-95 1 2.231E+06 i 13R-97 I 3.511E+05 I IUiS9 5~~~i"~6II45EIii~~i ~
IE6~ii~~~I~~i?iiii~ii~~I ITC 99M I 4.810E+03 1 ITC 101 1 5.846E+02 I IRU-103 1 6.623E+05 1 IRU55hi~~i~~95955k hk'~i IRU-106 I i.432E+07 i IAG-iiOM i 5.476E+06 I Iii Iiis I-~i!ii.iiiii~~I ITE-127M i 1.480E+06 i ITE 127 1 5.624E+04 I (TE 129M i 1.761E+06 i ITE 129 1 2.549E+04 i ITE 131M i 3.078E+05 i ITE 131 1 2.054E+03 i ITE 132 l 3.774E+05 i II 130 1 1.846E+06 I Units - mrem /yr per uCi/m ODCM, V.C. Summr, SCLindG: Revision 12 (September 1987) 2.0-14
_ _ . - - - - ~ - - - ' - - - - ' - - _
- s. -'. . 1 1
p: Table 2.2-1 (Continued) l f
PATH @Y 00SE FACTORS FOR SECTION 2.2.1.b j (P )
Page 3 of _3
)
AGE GROUP ( CHI )
__________________LD ______
l ISOTOPEl INHALATI I
____________'________ON ____
11 131 l 1.624E+0
_____________________7 ___ i 11 132 I i.935E+ )
____________________05____ i II-133 3.84GE+0 .
_____________________6 ___ .I 1
II 134 1 5.069E+0
_____________________4.___ l.
11 135 I 7.918E+0 1
_____________________5 _ , , _ !
ICS f.34 1 1.014E+ .,
____________________06____ 1.
ICS-136 l i.709E+0
___..___ ____________5____ 1 ICS 137 l 9.065E+
____________________05____ i ICS 138 l- 8.399E+
____________________02____ I IBA 139 1. 5.772E+0
____________________4____ 1 IBA 140- 1 1.743E+
________________06____ I IBA 141 1 2.919E+ 1 c ____________________03 ____ .
- IBA 142 l- i 643E+
____________________03; I
+ ____
ILA-140- l 2.257E+ i
____________________05 ____ !
ILA 142 I 7.585E+ 1 3
________'____________04 ICE_ 141 1 5.439E+
________________05____ 1 ICE 143 -l 1.273E+05 1
________________________ 1 ICE 144 1 1.195E+07 !
________________________1 l IPR 143 1 4.329E+0
________________5____ i IPR 144 1 1.565E+03 1 IND 147 1 3.282E+05
________________________1 IW 187 4
I 9.iO2E+04 i 1 INP-239' I 6.401E+04 1 s' y e __
Units. _ mrem /yr per uCi/m3
__ _ m m _ _ _ _ _ _
_ ohW ^ hM CS # D' " #*' ^^^-
i NOTE: The P, values of Table 2.2-1 were calculated according to the methods of ,
Reference 1, Section 5.2.1, for children. The values used for the various parameters and the origins of those values are given below in Table 2.2-9 and its notes.
-s O
I O
ODCM, V. C. Summer, SCEandG: Revision 12 (September,1987) 2.0-16 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
l l ~
Table 2.2-2 I
PATHWAY DOSE FACTORS FOR SECTION 2.2.2.b (R j )*
(For [bse Calculations Required by TS 3.11.2.3)
I Page 1 of 3 -
AGE GROUP ( CHILD ) ( N.A. ) ( CHILD )
l ISOTOPEl INHALATION I GROUND PLANEl VEGETATION I lH-3 1 1.125E+03 1 0.000E+00 1 3.627E+03 i IC 14 1 3.589E+04 1 0.000E+00 1 8.894E+08 I INA 24 I i.610E+04 1 1.385E+07 1 3.729E+05 i IP-32 1 2.605E+06 1 0.000E+00 1 3.366E+09 i ICR Si i 1.698E+04 1 5.506E+06 1 6.213E+06 i l lMN 54 1 1.576E+06 I i 625E+09 I 6.648E+08 i IMN 56 1 1.232E+05~ l 1.068E+06 1 2.723E+03 I IFE-55 I i.iiOE+05 1 0.000E+00 1 8.012E+08 1 3 IFE-59 I i.269E+06 1 3.204E+08 I 6.693E+08 i ICO 58 1 1.106E+06 1 4.464E+08 1 3.771E+08 I ICO-60 1 7.067E+06 1 2.532E+10 l 2.095E+09 i INI 63 1 8.214E+05 1 0.000E+00 1 3.949E+10
( ____________________________________________________
I INI-65 1 8.399E+04 1 3.451E+05 I i.2iiE+03 i ICU-64 1 3.670E+04 1 6.876E+05 I 5.iS9E+05 I IZd~65~~~I~~9I9535+05~~I~~5I5555+~55~~I~~5Ii64k+09~~i IZN-69 l 1.018E+04 1 0.000E+00 1 9.893E I
______________________________________________-04 ______
IBR 83 1 4.736E+02 I 7.079E+03 1 5.369E+00 1 IBR 84 1 5.476E+02 1 2.363E+05 1 3.822E ii i IBR 85 1 2.531E+0i 1 0.000E+00 1 0.000E+00 1 IRB 86 l 1.983E+05 1 1.035E+07 I 4.584E+08 I IRB 88 1 5.624E+02 1 3.779E+04 1 4.374E 22 I IRB-89 I 3.452E+02 1 1.452E+05 1 1.642E 26 i ISR 89 1 2.157E+06 I 2.509E+04 1 3.593E+10 1 ISR 90 1 1.010E+08 1 0.000E+00 1 1.243E+12 1 ISR
___-91 1 1.739E+05 1 2.511E+06 I i.157E+06 i See note, page 2.0-31 Units:
Inhalation and all tritium - mrem /yr per uC1/m3 Others -m 2
- mrem /vr per uCi/sec ODCM, V.C. Summr, SCEhndG: Revision Ip (Seoter^er 1987) 2.0- D
Table 2.2-2 (Continued)
PATHWAY DOSE FACTORS FOR SECTION 2.2.2.b (Rg )
Page 2 of 3 AGE GROUP ( CHILD ) ( ) ( CHILD )
______________________________N.A. ______________________
l ISOTOPEl INHALATION I GROUND VEGETATION I
________________________________PLANEl ____________________
i ISR-92 1 2.424E+05 I 8.631E+ l 1.378E+04 i
_________________________________.05 ___________________
lY 90 l 2.679E+05 I 5.308E+
_______________________________03__________________ 1 6.569E+07 i lY 91M i 2.812E+03 1 1.161
_______________________________E+05 1 1.737E-05 1 lY 91 1 2.627E+06 1 1.207 ;
____________________________E+06 I 2.484E+09 i lY 92 l 2.390E+05 1 2.142E+ 1 4.576E+04 1
__________________________________05__________________ {
lY 93 l 3.885E+05 1 2.534 >
________________________________E+05 1 4.482E+06 I s IIR 95 1 2.231E+06 1 2.837
____-___________________________E+08 I 8.843E+08 i
~lZR-97 3.511E+05 1 3.44 1
_______________________________5E+06 I i.248E+07 I '
- t INB 1 6.142E+05 I i.605E+08 1
____-95 _____________________________________2.949E+08 i IMO 99 1 1.354E+05 1 4.6
______________________________26E+06 I i.647E+07 I .
i ITC 99M i 4.810E+03 1 2.iO9 1 5.255E+03 i
____________________..__________E+05 __________________-__
ITC-ioi 1 5.846E+02 1 2.277 1 4.123E-29 I
________________________________E+04 _________..__________ i IRUJiO3 i 6.623E+05 I i ,
____________________________.265E+08 I 3.971E+08 l I IRU 105 I 9.953E+04 1 7 5.981E+04 l
____________________________.212E+05 1
________________________ l IRU 106 1 1.432E+07 1 5
________________________.049E+08 I 1.159E+10 1 IAG tiOM i 5.476E+06 1 4.01 1 2.581E+09 L
___________________________..___9E+09 ITE 125M i 4.773E+05 1 2.1 ___.._________________ 1 3.506E+08 1
_--__-________________________20E+06 ______________________
ITE-127M i 1.480E+06 1 1.083E+0 1 3.769E+09 I
__________________________________5__________________
ITE 127 I 5.624E+04 1 3.293E+0 1 3.903E+05 I
___________________________________3 _________________
ITE 129M i 1.761E+06 1 2.305 1 2.460E+09 i
_______________________________E+07 _____________________
ITE-129 1 2.549E+04 1 3.076E+0 1 7.204E-02 1
___________________________________4 _________________
ITE-131M i 3.078E+05 i 9.459E+0 I 2.163E+07 i
__________________________________6__________________
ITE-131 1 2.054E+03 1 3.450E+0 1 1.349E-14 i
__-_______________________________7 ITE-132 1 3.774E+05 1 4.968E+0 __________________ I 3.iiiE+07 I
_____________-_____________________6 ________________-
11 130 1 1.846E+06 I 6.692 1 1.370E+08 I
________________________________E+06 ____________________
l Units: Inhalation - mrem /yr per pCi/m 3 Others -m 2
- mrem /yr per uCi/sec
_ __ - . - - - _ _ _ -m _
' ~
Table 2.2-2 (Continued) i PATHWAY DOSE FACTORS FOR SECTION 2.2.2.bg (R )
Page 3 of 3 AGE GROUP ( CHILD ) H.A. )
_ ___ __ ___ __ ________( ( CHILD )
l______
ISOTOPEI INHALATION I _ ___ ______________ ____
VEGETATION II 131 ________1 1.624E+07 ________ 1 GROUND PLANEl________________________._I
_______ _ ___ ___ _____2.089E+07__ ____.__
I 4.754E+10 1 II 132 1 1.935E+0 1 1.452E+06
___ ____ ___ __5____ ______ 1 7.314 II 133 . __ __E+03 1 1 3.848E+06 1 I 8.ii3E+08 .
II-134 1 5.069E+04
__.2.981E+06.______.____________.1- .
1
____5.305E+05_________________.I 1 6.622E 03 II 135 1 7.918E+05 1 2.947E+06 I 9.973E+06 i l ICS-134 1 1.014E+06 I __ _ . _____
_______ _____ _ ____ __8.007E+09 __ ___ ____
l 2.631E+10 l l
ICS 136 l 1.709E+05 1 _____ _
______ ___ _________ . _1.702E+08 _____
1 2.247E+08 1 ICS 137 I 9.065E+05 1 _ ____ ____
______ ___ ____ __1.20iE+10 1 2.392E+10 t IC5 138 I 8.399E+02 1 4 l
~
___ _ ______ ___ _____.iO2E+05 _____ ______
9.133E ii i IBA-139 I 5.772E+04 1 _ _ ___ _
_ _ __ ___ ___ _ _________1.194E+05 ___ . ___ __
1 2.950E+00 1 IBA 140 1 1.743E+06 1 ______ .
____ ___ ____ 1 2.767E+08 i IBA 141 1 2.919E+03 ___.2.346E+07.___ ____ _____ _
1
_ ___4.734E+04 1 1.605E 21 1 IBA 142 l i.643E+03 1
______ __ ___ _ __ __ 5.064E+04.__ ___ I 4.105E 39 __1 ILA 140 1 2.257E+05 1 _______ _ __
_________ ___ ___ ___.2.iB0E+07. ___ ___ 1 3.166E+07 ILA 142 l 7.585E+04 I _____ ___ __i
___ _ ____.'.__ ___________ _8.886E+05 l 1.582E+0i I ICE-141 1 5.439E+05 1 _____ __
__ _ _ __ . __ ____ __.1.540E+07 .__ _ __ ______
1 4.082E+08 i ICE-143 1 1.273E+03 1 _ ___
___ __ . ___ __ _2.627E+06 1 1.364E+07 i ICE 144 1 1.195E+07 I
__ ___ . _______ _8.032E+07 1
1.039E+10 I IPR 143 1 4.329E+05 1
________0.000E+00_ ____._____
1 1.575E+08
____ _ ____i IPR 144 1 1.565E+03 1 I 3.829E i IND-147 1 3.282E+05 I 2.ii2E+03._ ____ ___ . ___ _ _ _ _-23
___ ________ _ ______ __ _i.009E+07 _ .
i 9.197E+07 1
IW-187 l 9.102E+04 1
___ _ _.2.740E+06 .__ _ _
I 5.380E+06 i INP 239 I 6.401E+04 1 __________ _____
_ __________ ___ _ _______1.976E+06 _ _____ .
I i.357E+07 1 Uni ts : Inhalation _ mrem /yr per pCi/m Others _m 2 . mrem /yr per uCi/sec ODm, V.C. Sumer, SCEand;: Revision 12 (September 1987) 2.0-19
___-.a - - ~ - ~ " " ' ' " " ' " ' ' ' ' ' ' ' ' ' ____ - _______ -
.i i
1
. l
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Ta ble 2. 2-3 .i l PATHWAY 00SE FACTORS FOR SECTION 2.2.2.c (R )* i (For Dose Calculations Required by TS 6.9.1.13)
Page 1 of 3
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See note, page 2.0-32 Units: Inhalation and all tritium - mrem /yr per pCi/m 3 g Other pathways for all other radionuclides - m
- mrem /yr per pCi/sec ODCM, V.C. Strmer, SCEandG: Revision 12 (September 1987) 2.0-20
__ __-_______A
+
Table 2+ 2-3 (Continued)
PATHWAY 00SE FACTORS FOR SECTION 2+ 2.2+c (Rg )*
Page 2 of 3 a I
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---=
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. . 1..6 40.st..+.44.
. i (PASTURE) (PASTURE) (FEED) (PASTURE)
Units : Inhalation and all tritium - mrem /yr per p Ci/m 3 Other pathways for all other radionuclides - m2
- mrem /yr per uCi/sec ODW, V.C. Summr, SCEhndG: Revision 72 (September 1987) 2 + 0-21
_ _ _ _ _ _ , . , _ _ _ ___m_ _ _ _ _ _ _ _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - __ _
Table 2.2-3 (Continued) . i PAT HWA Y DO SE FA CTOR S FOR SE CT IO N 2. 2 + 2. c ( R )
- Page 3 of 3 1
1
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t.t...t . 6 ..9 4.t.t..+ .t....t..4 .S.t.4 E*4.9...I ...t .l.t.e
.. . E.+.0 4...i
.I W .10. . 7....a..3 .9 62.E.*.0 4..4..1 .... 7 4 t E.*.0 6. I..t. .l.t.t . t.+.6 6 6..0 0 .0 0.E.*..4 4 1. 5..275.E. t t.e.t E..* s.t. I...a 0 .0.B E..* e.8..8
......23.,..5. 5 ,. ... .i .G .E.+ ...i i.4t.?.6E.. 4 .6...i. 9 4..-4 0 E.0 4. i..4 s.t.tt 9 6 4 4E...t..1..0
+.4 9...i. . . .4 ..i .S .s.t.9E*06.
i 0 000E.+.00
. .... . . .i (PASTURE) (PASTURE) (FEED) (PASTURE)
Units: Inhalation and all tritium -
mremlyr per u Ci/m 3 Other pathways for all other radionuclides - m2
- mrem /yr per u Ci /sec ODCM, V.C. Sumer, SCEandG: Revision 12 (SeDtembe' r 1987) 2.b22
l.
Table 2. 2-4
~
PATH @Y DOSE FACTORS FOR SE CTION 2+ 2+2.cg(R )*
(For Oose Calculatuns Required by TS 6.9*1.13)
Page 1 of 3
( N.A. D '4----CHILD
.)....t -CHILD = = = = =l ....i CMILD --- - 3 .-
6 CHILD
=
1--- -
( -CMILD - = _ -n..
.aC..E .C.s ou..P.. 4..CM l L D )- _ _ _ _ =CR 0uMD P L ANE l .C A
.I .15...
.N.3 010P.E.I...I...N MAL. A..f.! 0.N i i.itst. 3 0 0.000E+00 - -e- i.
i
. . tie *43 . i 2.iitt+04_ i ...Ittet3 i 2.54tt+61 i y.627E.ty iC.ie l 3. Stet.04 i ..ettE.00 i t.itSE+0, i 3.334E+0s i 4.lett+6e i 4.40tt+07 i ...,4E*t.
i IN 8 8.053E+46 t
. ..A .2 4... .I .. .t .610.E.+.4 4..1..1 .385.E.+.07 7 .775E+10
- 1. 7tSE.4
-- - 3..1...t .. 32.t
- - -t.37
- . 4. 3. 8 .7--0C.0 4..1. .3 72 9.E.+.4 . 5...I i .tP. 32....1. 2. .605E.+.06..4. .. 0.060C+04 6 1
- - _ _ _ .. 7 4.t .i.E.+ . .0 ?...I--3.44tE+98...i a....
- -. ~ - - S.893E*tt...i. 3.366t+49...I 51...1..8 .698Eete I --
i .sc. . . _..
4
--5.586E+06. 4. 5 373C.+.06..6- 4. 6 6 t E + 4 5 .I ...t t.t.s.t.+05..6
- 1. 57 &,C + 4 6 i B.625E*t9 $ t.. t?7t+07 . ..
1 .193E.+44...I.
. ~ 6..It3E*06==.t 1 .e MN.e l.e... i 6.640E+
$ . 01.-:1+ -=_ 0 6 . 0. 6. e .t tt+ 0 6 . 8. 9. 6.3.E..+.8 5...l- :_ t.t. 4 I
.i ..nN.. 5 6... 6. 1. 2 3tt.e . t.l...I. l . 0 6e E + 4 6..1. 1. s 6 5 E.+.t .e...I.2. .4 37E.=51
.l 4 000E.+.44...$. t ft.4E. 52..1. .. 2 723E+t.3...I
_.-1.818E+45 I t et0E+48 ...
.t r.. E .. 5 5. .. =4 = = = - _ - . _ _ __ - - - - _ - - _.I .t i .t SE *. t .0...$ 4 57 t E + 4 9 . 8. 3. 6 73 - - -
E+ 4. .. 7...I . . 1 4 8 6t.+.0 . ...7....$ . t t.tt.t* 4 8. l 8 2..6. 9E.+.4 6. 3.204E+00 _8 2...
.I F.C .. .S.t....t I -
.f.t1.E.*.0
. 0..1 6 3.3 0.E.*.0 0 1 4 7..4 f E.+.4 7 1. 7. 6 0=-_$E_=* 0 7 6 6.6934+00 t 4 C..D.-l.e....i . ..1.15 __ -6.. E ._
+ 0 6 6..4 . -4 _- 6 4_E
- 0 0 '.l - -7._ 0_ 8.___ t E
- t 7...I t S..f.6.E.+.0 7.. 0..1. 0..3tt.+.0 7...I ..1 15t t * .t 7 I . 3 77..t 3 830E*00
. t.+.4. 9...4
.I C.O. . 6 0...1..7 .... 0 67 -E..t i .2 e 53tE.*.10..8 2 391E+18__.1 ..l. .....
I
. .. .. - .. 4 163E.+.47 6. 4.645E+47...I. -___ -- t,etSE.+.09 .$
.M .. I. .6 3... 6.. 4 I.l . .4.E.*.0 5...I .t e.t.t . ...t + 4 9...I ..t . 9 6 4 E + t .t 4. 2. 9.t
.. tt..+.10..1..1 .. .
0 3 6.E.+.t8 .B...l .. ... 3..4 95.C .+..4 9...I . 3 9 4 t.t.e t.s ...t
.I M I .6 5.....I ..t.. 3 9 9C..+.6 4.. 4..3., .4.5.t .
E.4 0 5. 6 1.__=.. f t 9 C.*.0 6...l ..4, 0 6 t t.51- $ 0,$0$t+$6 4,373E.52 l 1,gitt+03 l I....
.C.u. 6 4. ... 4..3 4 7 0 E..+.t . e...t ..6 9. 7. 6.E.* .0 5.. 1. 3 . 5 4 tE
- t 6 8 1.393E.05...I..? t.t.tE. 46 1 1.67tt 46
.$ 5.15fE+45..8 B t . . . ... - __. . -
. .... I N - 6 5. . .. .I... .... 953E.+91..1. 0.583E+tt 8 1.19 t t+ t t IZN.69
_ ____= ..I ...t .0 0 0.E.+.0 9.. 4 2 9 .05.E.+.t..I ? ...l I..t.t.... t+ 0 0...$ . t t..4 4 C.+.4 9 4 8 t,tt0E+84 1 0,$ttt+4$ $ t.it3C.99 I t,8$0E*te. 4 0,068t+49 8 8.088E+08 0 9.093C.04 I IDA.83 1 4.736t+02 1 ~
7.479E+03= = 4 4.3t?E.et $ t.5ttE.57 4 4.tt4E+tt _ _.t...t .14tt -
.. . 57....t. 5. 3 ... 6 ?E.+ 4 4.4
.It.a-s.e.. ... i. 1. 476C.+.42.. ... I 2.363.E+05.
___=. ... 4. 6. Stat 23 I ..t .s.t.e
... E+ t.t..1..0 0 0 0 E+ 0 e
..I ..s . 0 0 0 E + 0 s .1 .3 s.ttE..... ..i.t _4 164 85 ..6..2.53tt.+.01. t 0 . 0 0=_=0 E.*.0 6..1. 0 ._0 :8 6_=E + 0 0- 1 0.040E+tt I t.040E*00-_ 1 4.sett+08
. _ _ I t.40$C+44
=. - .L 1.983E*85 I t.114E+40 6 6.97tE+07 $
18 . .0.-0 6.. =6_: =__:_ - =.I...t 4 35.E.+ 0 7.. 0. 0. 0 0 4 E+ 4I9__= 5.816t+49
. . 64 186 08 4 5.at4E+tt 1 3.779E,.. 1 7.tSSE.45 I 8. tele +48 4 0.000E+80 t === 4 - .--=5 0 4 E + 4 9...I 6.ettE*60 1 4.374E.tt I ltD.09 8 3.45tt+02 I t.452E+45 l 1.715E.53 1 0.000E*00 0 0.048E*00 l 6.600E+49 I t.44tt.16 I
.i .s t 8 9....I..t. __157E*06_____=2.50fE+44 5 1 6.6tSE*09 6 4.015E+49 4 6. 7 3 4 E* 0 5
..l. 1 5 77.t.E.+. 0 7.. --- -3 . 5___.
_ __ ._== 9 3 E + 10...t
.I .II . 9 0....t...t .8.t.e.E.*.t.s 1 0 0 0. 0.E.*.0 0._1 1 117E+ 11. 8-..1 .4_4 4 E.+.19.I 3 . 0 87t + t t...I ..t.240E.+49 I i l t .,.i l i.73,E.tl 9 2.51tE+46 I t. 7.E+05 i 5.2,tt.it t . 2 43E +.t.t...$
i 4.tett.et i 6.35tt.it i i.il7E+06 8 (PASTURE) (PASTURE) (FEED) (PASTURE)
See note, page 2.0-32 Unit s : Inhalation and all tritium - mrem /yr per u Ci/m Other pathways for all other radionuclides - m2
- mrem /yr per pCi/sec ODC4, V.C. Sumer, SCEanch Revision 512 (SeDtember 1987) 2*0-23
+ .
Table 2.2-4 (Continued) . I PAT HWA Y OO SE FA CTOR S FO R SE CT IO N$2. 2. 2. c ( R ) * -
Page 2 of 3 i
1
.a. C.. ..E.C t .0U.P . . .t ..C.M..I L.S..I A . ..
. 6. ...(....(
..N.
..C.H. .I L.D..1... i-- CHILD -- . - ..-
) 4 CH
.t .15010P E (HMALn110N
- l. I L S.1. .. ..( ..C.H..I L.D...I . ....( ..CH f L% % ..
I Ca0U D PL. - --- ... . .
.i..s 2 t . ,. . i .. .......
- 2. 24E+05 . .... ........N.
i . . .. AM.E..l .C t.i S3./C OW/M.IL.E . .. . .l . .C.i
. ... .t./C.O.W./.M.E.A.f . .. . .l .C .a t / C.O
. 63st+05...i. 4.i3+E*41 4,tt. 4.....i..4 8 8 t E..+ t .t.. .i . .-4 -49 . t t t E..
.iv.,.............,.................
2 67.E.+..t1...i... 5. 0.....i. . i ,.17 E+05 - - - _ _
i 4.07tE*05
= .1...i 3 7 0 E.+.0 4...i i .. . i
. 3--4-6E - + 4 3 2.277E.45
.I .V flM i . .. -
5.e55E+04...i.
.. 6.51,C+07
- _i 2 0.t tE..*.0
. 3...1..1 .16..L E..+ 4 5..6. 5 199E.16 .4. 4. 0 0 0 E
- 0 6
.i.v,..........
.1..-_i 2 _=. 6 tv..E.+.8 6...i ...i.t.t.t
.I. t . 6 -.
0 0 E
- 0 0__..1. 0.000E*06_
=- - -- - -8 1.737E.45 t
. t.+.9 6...i .. 5 i ..,.,E.+ .. 6...i . 2. 4 0 0 E + 0.
69 i. 6 ..
26..E.*
.. t 5...1. 2. t.:.0 . .. E.+ 4 7....i . 2. _4. 0 4 E.+ .8 9 .i 92....1..2 .39 3.S$5E*t5 tE.*.0 l5.. 6..2 . . 14 t.E.*.8 5.. 6..7 3.t e.E.+.4 4 8 6 9 5t E.35
.. .- 4..0 0 9 8 E.+.0
... . e .. 4..0.,35.0..E.3 6...1.
.t .v 9 3 1 2.534E+05 4 57 .. 6 ~ . t+ 4 4.. 4
_.0..1 .5 73E..+.0 4...I...t.,1.47E t..?
.120 .t.5... 4 ==- - - _ .
.. .I . 9. 13
.-- 4 E.61.= _ - l 1.057E.08...8.
__.. 4.48tE+46 ..I
......................--t .. 2. 3 t C+ 4 6...78. 6. 2 8 37.t .t.&E.*.0 t +. 4 s9 .1..0
.l ..at.*f 7 1 3.sttE*ts t 6t.*.t.5...t..6., . ...1 16.t E+ 0 5. ..... 6 -7.3tSE*t?.I..0 .043E*t.t
... .I 3 4 45.E.+.9 6..4..4 .19.tt.+.4 4 1..7 015.E 41 4 4 7 --_ 0 3E.35-_ _ 8 3. 4 t ._...
et.8 8
.IMS ................. ...... 95....4..6
- 1. 1 240E*47
. ... - I 142E.*.45...l...L 695E+99..4. 2.297E+490. 2.229E.+09
.I...l 346E.*tt
- 1. 2 673E..*.00..1. .2. 94tE+44 7
.IM.O . .. f t. .i..1 . .
.I.T..C. 9 9 M...i ...35.4E.+.45.. 4..4 636.E.+.44..1..1 734.E+ 0 0..1..2 456t+ .. .. 05 .i S1.647E.*.67 S.i tt.63..8. 2 947t.+
. . . . . .. - . . .... 8 I
-4 e.l .e EI..t. + 0 3.......
t t tg+0 5. l 1 474E..*.t.4..4..6 915.E .t e
. . . 1..4 0 4 s t+0 4. ...1..0 2.98.E . .. 19..1 5 255.E..+.03. 0 17C...191..1.
. . .1.. 0 .44E.+.02...I...t.,277C+4
-_ .__ 4..4.1. .. . 593..E.58. .- 4 0 e tit +s t ..i ..9 t 8 9 ...
... 0E.+ 0 9 0 0 0 0 0.E.*.t.0.
- 4. 4 i.t.3E.t.t
.I n U.. t.t 3.. 6..6 623.E..*.t5..
. .. . .. . ... . 4..1 26 5.E.+.18..1..1 .18..8 .E.+.0 5. 4 4 0.-0 f E + 0 9
- 1. n..9. 19 5... 6..9.. 953E.e.8 4. t.i.t.t. ..+ 4 5 1..2 4 .9.3E.*.0 8. 7. t.S.2.E.*.t 3..1..4 01.t E.+.0.e...t .97..tt+.4
.. . . ..3 9. 4
. t..7 . 0. g 5. .. s.g5.E 35 1 0.000E.+.09..8 1 5.901E+04 4 7 861.E
. : 26 .
6 8 U 10 6.. 8..1 4 3tE.*.0 7. 6 .5 .4 4.tE.+.4 8...I ...t
.l .a C .
.4 .3 7E.+.t.6.. 4. 6. f t tE +10- .1..4 -
243E.+.tl...1 8 I.t.t.t.+.tt
... . . i- 1.15tC*te 1
. .. . . .t. 1. 678E+14. 6..6 7.4t.t.+.0 0 4 4. 576t+ 49 8 8 4 9.t.E.+.87
-.. .i.t.e.n.1. 5 474.E.*.0 6. 5 4 I t 9E*tt =
0? I ITE*125M..i..4 773E*05 1 _ .
8 2 501.E+
.. i 1.48tE+46._ L 2.120.E.+.06.. ...t 7 ..
.- ~ .
.BTE
.. 127M 377.E.+.t .
?....I . 5.. 69 tE
- t et 8_ 482E.+.06..1. .-
6 ..
026.E+07.
.. 4. 3. 586E.*.t.8 8_
127 6 t .. 4. 6_ -3 ___. E + 61.. 0. 1.., .9 3.t.t.+.4 9...l 5., .0 6.t. E.+.4 9 .l ..1 .. .
17.t E.*.0 0.. l 17.E................-5.624E*te 8. t t 3E t ..
6 0 73E..*.0 0..0.. 3..76.tE.*.0
.. . 90
___.* t 3..1..1 .. t t.t..t.+.tl .I . 4. 6 0 ?E..t e 1 6 000E.+88
.a.ft. ...............
..i.t.tM..i...t .. . ....- . . ....
_ . - _ .0..1 .f.t.tC..*.0. 9 1. 3 9 0 3 E
- 4 I5.
76.t t.*.4 6...l . 3 3 9 5E+ t.?...l . 7 9 6.t t..+.0 8.. 3 5 2 4 5.E+
.B..T E..t. t.t...i--2.549E+04 _.4 3 . ...476E.+.44...l..6 166E .. 48 8..4 000.E*06
. .. . .. .. .. .. 0.?.. .I . 4 3 2 8'
. - 0..0 .000.E.+.t.t..5..0 .000E.*.00..1. . 7..204E..S.t. i 4.T ...
E.13..t M...i. . 3. 4 .. 78.E..+ .t1...l 4 .5.t. E..+.4 ..f. 6..1... 2 3. 4 4 E.+.4..I7 . t . 015E+ 0 3 8..1 6.t..t E..
15... 4..1 . 17.0
. E.+.4 3...t
.. .... . 2 16 3C* t? 4
.I .T E. 4 31.. 6.
.. .. 2.. . 4 5 4E.*.0 . 3.. 0..3 . 41..0 5.0a... E..*
s t.E 0
.. 32. 7.. 4..0., .0 0 0 E.+ 0 4
.S.TE... 132..1..3 77.4E.+.t.l
.- 8 0 000E..+00..0..0
. . 088E.*.44
. . .I...t .34tE.14....
4
.I ..4...,2E960E.*.0 6._I .4. 5 t- E+0
- - 78. 9 32. 5E.+.46 . . 8. 7. 27tt.4 - - 2 .I.
.i .i .i.3 6....i...i .84. 6t.+.6. i.. .6.. .0 6...i 3 0. 4 5E.+.0...I..6 .. t i t9E+ 46. 4 3 l.t.tE.+.t.? .I 750.E 8. _i3 i.25.E . 45 1... . i.t.t.E .45 .i. i 37. 0.E t.e .
(PASTURE) (PASTURE) (FEED) (PASTURE)
Units: Inhalation and all tritium - mrem /yr per uCi/m Other pathways for all other radionuclides - m2
- mrem /yr per u Ci/sec
_ -- __ n . . . _ - -.
+
- Table 2.2-4 (Continued)
PAT HWA Y DO SE F A CTOR S FO R SE CT IO N 2. 2.g 2. c ( R )
- Page 3 of 3
\ -
i k
A
. . C. E. . C.s. oup. ... . .4 .. . .'CM. .I LD . 5.....t..N A. .
..1...--( CHILD 3 - i CHILS 1 ---
___ - t .CMILS t --
i CHILD l
. . = - - - - -
4
= .C.H..I L.D...l ..
.I41 ..I .SO..T C.P E..t ...I NM AL. AT.IO.N..I-Ca0UND PLAMCI -
CA.S/ .
COW . /MILEl CR S/CCW/mC AT I Ca t/C.0.J./.n..tL.E
.4 333t*tt--- t 5.5 8 3t.+ 0 9 .I. 6. 4 4 8t + 4 7..1. 6.
889E+07 1 ..-- - ---
.131...4...t 624t*07._ .8..2
. -6 0 4- E-+= ~
8 -.754E+10 I 4 - -: .t 41 1 2 - .
132...1..1 935C+es 1 1. 4 5 2 E.*.t.6.. 9 5 .12 9t + 61 -. . 4 2 tE.57 . 8..8 9 0 8 t.+.42.8..
.. . . . =====-- --- -m ... . . ... 4.. 8..8. 7 3.t 4E.+.g 3. I 915.E..5 11 ....
133...4. 3 848t..+.46..1. 2. 901E+e6 - 8 3.945E+0? 1.384E+et i t 7.29tE.23 L.564E+tt. i 8 113E+00 t 4
11 13 4....e . 5 ... . 8 5.385t*e5 .= - -
_ 3.624C.10 t.400E+00
. 0 6.t.C.+.6
.. = 4 - -
4 I 4 0.080E+00 1 8.800E+40 t 6.622E 63-. i
.t.1.... I 135...1. 7. 910E.+.45..1.
. . 2.947t.+86..
. 6. 8.687t+86 _ - - --t . 4 3tt.14...s. _. 4 s.e..t t..+.s.e .t...L 2.47E.15. -. .I . 9. 973E + 0 6 s
\
t
.IC.S . ..134.. 6..1 . 914t.+.46
. . 4..8 t.I.7.E+t.9.
. .. 6 3 715.t+10...I.
. t . 513E.+.4
~. 9 4 1 197t+ 4 _. 4 .I ~t 816t+ 08..1..3 631C+10 - t I
.C..S .. 4 36.. 8.= 1. 7 0 9 ._E=+ 4 .I..=1.
5- _ ==7 8 2 E + =4 8 1 _
2.773E+09 8 4.426tet7 4 s.276C+t6 1 5.3ttE*06 5 2.247E+tt a 8 C..S.-13 7 8 .9 565C+45_ .4..~1. 2 0.t .E.*.16.
9
- 3. 22 4 t.*18 1 1.334E+tt. I t..1 122E.+.10
... . 0.1. 6 0 8 E*4 3 8 2.--
392E+14 ._ :-_
0.399C+02
.I C.S...13 0. = I 184 139
__ 1.-4.tett+tl I
5.528t.=.23. - _ I..t.-008t+49 _
I
_ 0 t.e.tt+.0
. 8..1 - 0.000E*60..8. .. 9 133C.tE t'
= ..I = 5.772E*44. 1-1.19 4E.*.e.5 * .I. t . .-- 23 tc.4 5 .4 0 0. 0. 0 E.+4 9 t. 0 s.t.eE.+.4
. .. 9 0..0 8 .8.t . E.+.e.t...I -
t.958t+0s t
.t .h.a.14 00 1.743E.*.46 4 2.346t+07 6 1.17tt+et t
.= __.
.t 4 384.E 47 1 E 104 141 4
.. . 3.114E+ 45... 0 5 26 t t + t6..1.n 76 7.t.+0e
... --- _.2.919t+43..6-
-- _ _ 4.734E+84. 4. 1.210E.45. 1 8 000E.+39
. . -8 0.000E+68. __. 1 .0.008C+48..1 -
1 60$.C..t.t i
5.064t+64 . ..
1
.I .6 4..14 2.. 4..1 .. 6 4--3.E
- 0 3 ... . -
4
- 0. s t eE+e.s...I s 0 0 8t+4 9
.. 6. 0 0 4 . 0.E.+.9 9..0 0 0.0 .0E.+.4.4.4 4.18%4 -
-_ 39. 4
.I L. A...t. .e t...i ..-- 2 . -- 257 :== t *.0 5 1 .2.100C+47 ._ I t.st4C+t1 1 ..
5.49ttest t 4.196t.62 .. 1 .6.590E+01 l 3.166L+47 4 I
.L. A...14 . 2..1..7. 5 =__ 0$E__= +44 6 0.006E*85 l 2.904E.06 8.48tE*00. t..4 800E+0g 0
.__- .1. 0 s.t.tE*e9..I
. .... - ___ _t.582t+41_
_ _ .I
.t C.E..t
.e.t ...t ..5. 4 3 t.E..+.t 5....e . 1. 5 4 8 t1.+ 3t ?. .._ - --
6 t It_.+ 4 7 1 1 3 82E+ 4 7
. . . - 4. 6.t ....
e c t.+.s 5 _6_.8.65tE.+46..1. 4 st.2E+te... - .4.
tCE.143 5 1.273E*ts 1 2.627t+86 . _
- 8. 1 488t.+.t.6 .... 1. 2.516t.+.02- .l. 1.806E.14..1..3 :_ - -
428t.+t.1..1.
. .. 1.364E*e7. 8
.I C.E. .. 14 4..1..1 .195C.*.t.?..
1 6...S .8 32.E.+.0 7. 1. 32 6t + 0 0 0 1 893C+ 4 9.. 6 3. 72 .7E 3.t.t-__ent
- t 7 . 0 2. 2. 7.t .. t.+ s 7... 6..1 . 8 .. t
.i P.e. ..6 4 3.. 6..4 .. 3 2.tE..*.0 5...4..0 S t B E+ 4 8 1 7.754E+45_ 8 3.68tE+s7 4 3.73st+s3 1 4.334t+s6 1 1.575E.98 t 174. 144. ...4..1 .565E.*.43..9..2 .
412E*03
.__ ._ .1..2 .04.t.E.*.50. 0 0.640E+00 .1 0 000E+40 .- ..t..0 000E+49__.8.
- _ 3..829C .... 23. 0 -
.I n.D..=.t ... 4 7 . 6..3 .. 2 82..E.+.4 5...1..1 .8 .. 8 9E.+.47....I . . ..5 7..t at.+.0 5... 6 1.5tSE+47...4 6 864E+82__
. i L.885C+s6 I t.ht2E+44 6 2 748E+46 a . 9. 19 . 7.E..+. .s ?...I
.i W. i t ? 1. 2. .. 2.799t+tt 3 348E-0
.. 4
- i. 5.tt3E.22 .1 . ..
_ .. i..3 67.,.E 2.1i.1.i5.380E+46...a
- i. , 420E.+.06 4...i...i 976t+.6
.i ............=
. .. .4..6 -.. 239 t_ . 336E.9.
..41.E.+. ....... i.3 t.+.6 4. 9 2.232t.63
. . . 357t 47 i (PASTURE) (PASTURE) (FEED) (PASTURE) 1 1
1
! Units: Inhalation and all tritium - mrem /yr per u Ci/m 3 Other pathways for all other radionuclides - m2
- mrem /yr per uCi/sec ODCM, V.C. Surmer, SCEhndG: Revision 12 { September 1987) 2.0-25
_ _ __ _m_ _ - - - - - - - - - ~ ^ - - - - - - - - ' - - - - - - _
i
.i Table 2.2-5 .
PA T HM Y DO SE FA CTOR S FO R SE CT IO N 2. 2. 2. c ( gR ) *
.(For Dose Calculations Required by TS 6.9.1.13)
Page 1 of 3 i
(
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=
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- = .-_
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_- c.._.. _ .-
(PASTURE) (PASTURE) (FEED) (PASTURE)
- See note, page 2.0-32 Units : Inhalation and all tritium - mrem /yr per p Ci/m 3 Other pathways for all other radionuclides - m2
- mrem /yr per p Ci /sec l __ __ _ _ _ _ ~am__ m ~ 1 - 9W
T i
. ?
l
+: * .~
qu r t a o
) h
.\
Table 2.2-5 (Continued) s!
h*
i e PATHWAY DOSE FACTORS FOR SECTION 2.2+2+c
.L Page 2 of 3 \
a t
m .+ e S t h.9 p
I s
a
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u.a....i....e tEtr acte.i...
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8..IS0. .
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= = - .ttE.ta11.Du..a .
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=
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.n........ . ..i ...s s.u.t.+ 4 5 - 3.9tE+43...4 s 74E+46. i. 7.47tE.45.. i 2.666E -- 45. -.i, +.e-5E+44. i --1.425E+49
. .. .... - .. - - i
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. ..<c . 83...e...i .i.e.:E+45 i
_ . it9E.~ie
- .... .i. s.st.eE+44.-i ir let.
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.~ --
4 iteE+0e.. n .*.r .t.+.t.t .i.
t.20SE.
... 97 - <
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2 142.E*45 . . -
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4.426E.36
.~~
8 3
- t..t3E+t.f ~.
i ent.364E+64. 3
- 11. .
t .................93.....e..5 79tE..*.s5...6.
. . - . 2.53 4E+15. 600E.47
.. ... 9u 1 .t 317tt+4 7 62.SE.6 L4..1...t
.I 2 4 2.W. te . I.N d., .793E.+.34. 3
.it.. 95. .. .a..2 6DDE*46 6
-- _ _ _ = 3 8 37.E.*.0 0 t t I.t.t E*.06... 4..1 4 ..
. . . 9tt..+.tt .I...l 50.S.E*t5. .l 1 3.16.E.+.49
. ~
8.1 253E+et a
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12 9 .
97.... 4..6., 30 .. 4E..+.4 5. l ..3 441E+ t 6 0 I t.ittE.91 is 4 7.5L2C*tl i
. --. 4 225E+.44..4.
... . 9. 13tt.tt t 4. 7.8t.t...35.
. -- .. 3 S 673E.+97 4-
...t.-95 1.684t*08. i 5.tttt+03 e 4,55tE+42 ,4
- 4. 3. 330.E.*t
. . .. t 4 - 4.25 tt+t.t. 4 963E.+t.
. . <t
.in.0. ................... -99... 6.. 2. 6
... 00E.*.t5... 1
~ 823E*t.0...t 4 4 ht 6E 1 99tE+45*t48
. .. 4 5 9530....?...I I
s t .
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.I.T.C 99M 11C ....... .... .......
8 2 i..t9C*l5..8.
.. . $ 853.E.+.44.
.. 8 6 47.t.E..se . . i..f 6...4 8E. +.c t i. 7 766E.=~st 8 5.ettt+03 ....4
. .i.t.t...t. 6 672.E+.02 8 2 277t+44 4 3.297E 58.ii 6.004;E+0.0. 0 9.6881.+88...(...t leu ss3 6 7.832E+44- . .
.i. 3. 227029 4 I c-
.~ _ . . . 46.tE.*tt
. +. .
El t.265E..+.#.8. 8. 8 513.E.+.05. .. . 4. 7.163E..+09..
8 8 7364+44 i..S 595.&.+.98. 4 5 786E.+48.4
+ _
.S t.u. ....195...I. 9 ..8...4 6E+4 4.1 7 tl2.E.4.95 4. 3.263E*J.4..4 I 3 94..tt...25 I t .0 69E* G.G 1..4 694E
. . .. 26 1. 4 0 3. 9t.+.0 .- 4 14 0...18 6...I..1 .. 6 4 0E..+.47m .4 5 949.E.*.09..9. 3.799E*86.c I .8 4 3 0 E.+
t
. .tt t 5 312E.+.45....t.
.. . 1..356E+
_ _ t t...i..1. 4 p aE.+.t. e...t
.a.G..L ... i t.M. .i.. 6..,752.E.+..t b. n .4. 4 49E.+..)9
-1
. . . I. 2. 559E.+ t .t
.i . 4- . ._ 3 45. t..+t f....( . 6. 98.tE.+49 ..I ..I
. .. L 614E.+..tt.
. .t . 4---. 0 3---__
t t + 99_ -
- N ... ... ..
41.C..t
' .i .f E.*.tt?M 1.n 1.
.....i..1 5 3 6 0E..+.05... 4 4 .t.t.BE..*.t6.. 6..3 963E+.0 7. 4 3 9.a.t.E.*.64..
07
. . 3E.*.0
. 5...4..443715.E.+44. 45.t.E..+
. 4. 4 7..1..1
. 6 5. 6E.*.t.h.. 4..1., .9 2.J.E.+.0 5.. 8..3
.. . 4 2 8.E.+.t.8._'
__3 .1S.t A.C.+.69 i . 6.753C..+.t ? ..t.
. ... _ 4 5.6.t..E + 4 4 . 4. 2. 2. 3 6.E.+.9 9 4 ;
' .o ....f.C..t !7..1. 0. 0.. 00E..+.4 4...t. 3. 393.E . +.43....l 9 57tt..+.04.
. 1 1 69.,9E. .. . 99....I..6 .0 0 0 E..+.4 4.. 82. 517E..
. . .. 09 . 6..4 8..8.B E.+ 4%.6
- li.t.. it.t.n..s...t
. . 976.E..*
.. . 46...6 .3 .. 3 9 5.E..+.47...I . . 4 64 tt.+ 49.....4 3
-.f.66E..+.4 9..8..2 5 8 .t.E..+.47. 4. 4. 759E.+.tt s 8
. . . .. i..1 5 6.... SE.+.s9.
' .s .f E.*.t 29.m e.3.
. .... 29 6E.+.4 ... t3...l
?61 ,,.* ..3 2 t e...i - 196.E.49..4. .... 6 st.eE..+t.t
. . . . .t 6 09 ... 4.+
.ETE.
. 63tm i e tOSC*t5 4 9 459.E.+.t6. 0 2.529.E* . ... 47...4..1 447E..+.te 4 1 027E.4 ..15. 4.. 6..3_. 4 9.tte e.t...t. 3 4.stE*5 3. 8 l..1 736E+t3. a. 3 .t.e.s.tes.T.e ...
.e.ft . 131..6. ..... ... ..........
f 336.E.*.43..1 3 8-45..t
.. . E.+.47....I t. . 79E.32 4..6 e ... s tE.+ .. st....I .t 4...4 0E.*
. 4 4. 1. ..0 tt.t.t.+..e t- .t 6 e.t.tE. ..15 6
.i.TE. ...132...I..4 63tt+tl 4.960E+96 4 s.sett+t?- I . /
.i.t ..i38. .i...t . ..... .. ........... . 0.742.E.......,. 2.348E+s7..8
..tE+.46. i 6 6_9t.E.* 6.
. . 4 37..tC .e..t. . 4. 2..769t 06..4. . 7.etSE+s?.._I 4 .45.E ._ - 4 5 5.4i6.E 45 i 4966E95 i sc
. . . . i
. . .. S!?.6E+.47 (PASTURE) (PASTURE) (FEED) (PASTURE) ( Y t
,i i.
tg g j- i i
y A i +- h.
t i
( Unit s : Inhalation and all tritium -
mrem /yr per uCi/m 3 Other pathways for all other radionuclides - mf '* mrem /yr per uCi/sec , .
k' I^ {
ODCM, V*C+ Surrrner, SCEhrd3: Revision 12 (Seotember 198g f*0-27
t
'n * >
,, >( '3 Table 2.2-5. (Continued)
PAT HWA Y OO SE F A CTOR S FO R SE CT IO N 2. 2+ 2. c$( R )
- Page 3 of 3 i
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9
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( TEENaCE4.~5
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- :- -- : .... s tE E N ACE t .t
.I 15 . 010.P E. .I ...I ....Nw aL a..T.wo..a .C.a .0V.MS.P.L. A.NE.l . . .. C A .S /Cets .. /m.!
. . .LE .l .C.t f.,/.CCWM.C.A .T.I . .Ca..l/ Lit./n .== -t L t .l .C.a.s /.C.O.T/.m.E.A.f t wtCE Tn 41..8 31.... 6..1 . . . t 3.264t*t?:==I e i 4 6.4t.*.8 7. 8__-_2. t e - _f _E - .* 0 7 .1..2 t., b'4 /.e t t
. -_ _.- 3.645E+49.. ... 1 = --_.375E.*tt. - - - - =3.14s= = = .E.* . .t .t . t
' .a .! .t. .32....i ..1 .5 .8.2.E.*.0 5.. 4..1. 4...5.2 E
- t.6
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- t.t 1..1 6 67E.50.. 9. 4 . 2.:-6 2 E + 4 3...I --
.41..13..3... 8..2 92.t..E..*.B .6.
1 2.981E+66..0 i 41 952E+te
=. 6 674E.*.09..8 .7 .234E.*.81.
.. . . . . 6. 3.496E.2.3
- -- . .4.=8.68tE+tt......
- ==-- 4 . 5 8 7 E.**0 6.
8
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_ ==- - - 0. 3. -- = =
.-.854E.93. -
8 41... 135...e-
. 6.208E95. 1. 2. 9 4. .7.t.*.9 4..1. .3 777.E.*.t.6.t*>.m 1...... .
9632 15....I..4 .000E.+.t..s. 1. 7..156C. .. 16...I. 5. 832.E+t.t.
. . .. t a
- 2. 310 E+ t t
?
.C .. E.*.t
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--- 7, 4. 4...
3 E + t.t.. .t. 1 477E*.0
.. 4.... 0..1 671E..+.10.
. t
- ). .I C.S..... 136.. 8....Nn.. 7, E.*.0 5..1. 1 7. 0. 2.t* .. 4 4.. 4..6 7. 5.tt + 4 9.. A,n.3. 67..t . . E.*.6 7... 8 5 2 4 tE+4 6..1..4 .4 ....
( f' .ICS.. 837 8 8 . 4 8 t E..+.0 5 1.20tt+10 .0 8
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. .- 4 5E+ 8 6....I ...t 7.4 6.E.+.4
. 8 I
8 6 19 7.t..+.t 9...I ..t .15 6 E+ t t i 1.3. 4. 8.t.+.t.t.
(s) . 838 I
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. 4. 0 0 .0 .0E.* . 6 8. 8 8. 4 6 0.. E+0 8..8.
. ...6 93 .. 5E. 11..8 .
a
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l t.4E.+4
. .. 5...l. 7. 7.4.t. E.. 6 7. . t b. 0 0 E+ 8 9.. 0 0 8..0 S E..+.0 3 -
6 . 0., .0 0...0 g* t.t...t .. ..2 4 72E.61 I t .
.t.A.14. - 4 . 6..2 9 .32.E.+ . . . 9 6...s .2.t.3 4 6.G.+.47....I. . 7_.. 4... 83.E + 0 7.... 8.'.4 .6 . 63. . E.+.47 9. 1. t.t.t.t.+.4 5. 4. 4.3. 9...6.E.* 0 6.. 8 - 2.136t.+49. -
i
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4 922.E.446..1..0 008t.+.08..0..8 40$E.*.00. t. 4.088t+tt..1. 0. .-699E.22. 8 9.4...= 142 1 ". 4 912 . . . E.*.t.3..
. 4... 5 2 6 4E *.0 4..1..9 .e.t.e.E.+.t.t .t. 6 6 . 8 81.+.8 8 4 .4 G.l.8 . . E.*.4 0 1 -_ _ -- 1 2.26?E-39 I
=0.000E+09
.t L.a. ..t e.t...a --- =-.
4.s72E+s5 l 1..2 18.tE+07 . . . . - 2. 29.t.t+...
. 85 .t..t .- 68tE __ -- +4 2 1. 5. 9---6 0E.4 2 8 ..1 ...
943.E.*.82 1. 5. 194E*47 . - 0 y .It. A...4 4 2...I...t 2 =8 __ 0 E* 0 4 1 S . 0 06E *t5 ____,_.2. 1
- 3. 0.,06tE+49 i.
-==
0 57.4E.. 67. . --- ..I 4 098t.+.49
. . . .4. 4. 880E.+.44...6.
. . .1 868t+08 4
{
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- 1. 54.0.E.+.t.7..1. 4 7 8 3E+ 0 6 8 5. 4 6 4 r.+ 0 s t 1 6 tee + 0 7.. 5. 2 2 52E+ 0 7. w. .8 7 4 t t + 6 % ..i=_..2
_. . . - .+
) .I C.E. . . 8 4 3...I. 2. 552E+05
- -- - .1. 2.627E.*.t6. e
- 1. -67 _..t t +4 6. 8..3 6.t.SE.+.0 2.. 8. 1. t _M. ._ t e..1. 4 4 3 4 E
- 01 ..l . 2 .9 -4 5 E + 0 7 .I fp #
.C.E. 14 4. ... .I. . .t... 3 3.6E..+.t I e 032E+s7.
? . .... I 1 655.E.+08 4
-3. e___.. ttt+0 S 8 3. 7 8 6E* t 7 0
. .. 4.65
_-. 8 t.+.47...8 _
- 8. 1. 326E.*l.t
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- t. g. 9.553(+gg g g,g
.t.7.(+g?.
... g) g gg,g + o .g..... .... 1.
.j .'/ 4 7. .4 E.* .........t.g l 3..t g E..+.0 g l 178 2.112E+4%. 1.23tE.53
.. 844..8..8 skD-147 4 752 tat 3 .4 --_
.e- -
.1 . =-- -- .1. 6. .-009E*06 I t.SteE+00 t e.94tt+00 1 3.097E.26 I s
-.3 7.20E+tt=
-. i 1. 0 ___
0 9E.*
.. t 7..1. 7 . .. l t .6.E.*.t
. 5 .t . 2. 4.... 5 2E.+ .t ?. .t ..0 5 52.E.+.4 2..1. 2. 9 4 2E
- 8 6.. 6..1 . .. 4 2.4 E.e t e....t dk.
. 4 4.787E.81 2.748E+06 2.646E+46 4 3 9.0.tt.+.t t..1 5.579E.22 1
.18 7...,.I..t. ...760E..+05____
1 4 7.83tE*l6 6
.............i 23, 320E
. . 05m........... .t. ,765 8....... ...
- 4. 066t*t5 .
.. I..i. . 3.3 7t.+.03 . . .. .. 3E.
. .... .. 07.. ..4 0 6.4
.. E.*.t 2... 8. 2...0,7.E. . l?.. i 4
[ (PASTURE) (PASTURE) (FEED) (PASTURE) e ,
)
s 1
3 , !
s (j ' K
.\ i
\s '
s l; i
1
\ i i
s l
f Unit s : Inhalatio,n arg all tritium )
- mrem /yr per u Ci /m 3 l
/f Other pathwayfior all other radionuclides - m2
- mrem /yr per pCi/sec 1 l l
\
\
ODc4, V.C+ Sumer, SCEandG: Revision 12 (September 1987) 2J-M j
s s ;,
. , s 3 > .
4 c . T.able 2.2-6 \
r (_~ "3
- <.PATHMY DOSE FACTORS, zo FOR SECT DN 2.2.2.c (R1 )* '
i i
>4 'A ,1.Nr Jose Q1culaticos Required by TS 5.9.1,.1,3) y .f ,
.ne ' -
Paga l ,'of 3 / .
i > . i -
t q
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, , ll.
r
/
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t (. t 1 a i sW,
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, I
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..................-..~..x...................................................y......u.< < amt i: . ..ar . . ..x , , ; j , uu o t, 350lo,C: ....................
8 8** 4 G.0WeV PLhac: G.!ve@u/M Lut Ga &ec pwac.11 W54 0 Wen:Lu i s aleOMeeur: W
. . . . . . . . . . . . . . .'*.6 a f l GN......................... --..u -.c....n~ ............................ .......... -...CGCT r:On. . . . . . . . . . . . ' .
- .., i . e..c .u 4. .uc.= , .. : .. .ac.n -
..,..c.=
............................s............_................................................un.na
- c... 1 ...i.c... . .....c... : e.. .c... : n . . . .c .. . ..ri,c.., i 3.un.n,i
....rc..,
. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , . . . . . ......................... :........... ..,1.c... .
- ..:. i.nu.u r,. uc.n : i . u u.u : . . .uc.n -
....................................t.
i . nu..r n.on.a . i.mu t. .
4
- ,. n : i . nv.* . . .uc.= . i.n
.......-.................,......................G.:...umn : 1. s su.c : s.urc.u : i...u.n u..e i 1
- c.m. . i . un.n 4 - r. suc.u r. .re.= i /s.rnc.u 3 ..............~.....................-.a............-......................................auc.n
. . . .....c... ...asc... : a.svec.., a..irc..e a.un.n : a . u r c.n : i
........'-...........- - ................ ......-.: .....-..................----....r. . c... : 3.arsc.
. .....: ...sc.
i
- .u . e.nu.o i . . u.c.u :,i.nu.u . . u u.n i ....w.= : s.un.n i s.nu.n : .
s ac.n : 7. : ..uu.a : ' a. n ic.n : a . n u... . . n .c.a i 3. sin. n
.m. .s. . . ... .. i.... n. u.... . . . e: n3.ruc... c . u.........................................-..-................-.....-......e..uc.i
- a. nu.= : z. .uc.n
. : a. u.n 2 c.nue i . nse... :
.................... ........ .-........-................ ~ ... ......... . .-.... . . - . . . t
- co.n . .. sue.n : . . .uc . = ,. uu.n : 3.n u. ~i ..n.c.n
- .............-...............................................-........................suc.
- co... i s....c... : e.sarc.i. : a...zc... : . . . :c .. 1 i....c... :
x . . u n.n n
- ,l i...sc... i
...... .............. ...................... ............................ .... ...... . s.as.c...
i s
,o s
- =i.o . ..nu.n i . . u.c . = ..nu.n i s . un. n . a.uic.
..................-..-........................-.......................................uun,i : a.auc.n i n :
- iu : i . a nc.n : 3. nic.n : 3. n u.= a r . .nc .n : . . ..u..( : . . wa.n i e. .uc.=
~
.=.~.............................................-..
- cu
- . . m t.u : .. v ..s u..uc.u
-. ...-.......... w _....... ...-. .-.... .
- a. wc.n :
. ..a
. . .- :u..........................u................................................_.ua.n
. . u n.n
. . u n . ..
..na. e i m. n u.u u r i
.. un.n : i. inc.n : . . . u . .. : i . n u... i s . .nc.n !
...........-....................................-...-........ ............ .......... - ........ 1
- , .o . ..suc.n i ...uc.a s.un.n : . . .uc . = ....u.a : ..=.c.4. : i i....: i ....c.. v..r.c... : i.a.,c..a
................. -..... ............................... enc..:
i .....c.., ,
i.
1
...nu.
........:: ...i....c..r .. .....:.
.....c... . .rsc... : 1
[ ..................................... . ~ ................ ... . . . <
zu.= . 3. un.n : e.un.n : i.un u i .. nu. i . .,c.u
................................- i n.nu.n '
- n.u , ......................... . _.......... ...................- -. ,
- i. nc.n : .....c. i .. u.= ....u.= i . . .nc .. : ...vu.= . . .n c . .
.......................,......,...._........ . _ ......... .. .. - .... . I
- n.u n.n u..s . . i. u n n < : s. mr..n
..-..............................._...............................n m.= 3. .nc.= i 3. nu.u i n.ww..: i . . nu.
.. v u. : 3.un.n i
- . . uu .
- s. un.
. . . =u .
i
- s. i uc.
3.u n.as :
1 l
........................ ........... . ~.......- ................. .. ............. . ....
- n.n : a. nu.= i n. m c : : 4. c cc.n . . uu . : .. u.=
......................................-...-...........................................useu
- u.n i . .nc .* i s . nu.u : i. m c..o 3. n u.a
- . . ..u .
- i . nu.=
- i l
i s.un.n : . . w a.n i 1
- n.n .. nu.n i . . ww . : ..un.i. i .auc.i. : i.uu.i. : i . mc.n : . . .nc.a i
- u.n : i . n u.n : n. soc.m i s.nn.n : r. n u.i. : .. u.= i .. u.n : i . n a.* i
.................... .............. ...........~............. .............
(nstut) (nstut) (nto) (nstr--)
1 l l l
- See note, page 2.0-32 l
l Units : Inhalation and all tritium - mrem /yr per pCi/m 3 Other pathways for all other radionuclides - m2
- mrem /yr per u Ci /sec l
Table 2.2-6 (Continued \ .
PA THWA Y DO SE FA CTOR S FOR SE CT IO N 2. 2. $2* c ( R )
- Page 2 of 3
. a.C. E. . C. 4 0.uP . . .l . . 4.DU.L..T . .Ia........t . .u. .. A.DU.L.T =t- A9 ULT I t
.. 3.....E . 3
- -- ;--- =.- a...DU.L.T. 3.....i - -ADULT -
3 4 at>ut.T 3
.l .15 010.P E.I ...I NM AL. A f.t DN..I .G.R.OU.ND.P.L.
. .. . .. .. .. ... =- =- -
A.NE.t0 ...C .-
tttt+40 B= .5./.CC.W/M.IL.E.
. .. . = .. 8 Ce $/ COW /ME..A.f t- CB 15..0 .9 2... 6. .4 ...3 .0 4t.*.0 4..1...S .6 3.t t..+.0 5.. 6.=- 9. 675 E + t t.. 4. -2.. .3_ 3. 4 C.4 5...1. ..l . 2.0. 0.t t.... 4 9. 0 (r
0.452E*t3..4
=.
.lY... 98.....I. .5 ....... 956C+05..1. 5.38 tees 3 .1.:7.litt+05
.1- - -1.14tt+06..8-
- -- t . 8 65E.05 -
..I...t 36... 9E.+0
=- 5 a t. 4--.tee *49
..I 8
.I..T
- 9..t M... ..i ..1 ... 9 2 ..0 E.* t 3....I . 1.16= -t t.*= 0 5 1.743E.. .19..=9 _ I
- 0. 0 0 0 E.+.t . 8.. 0. 0. e t 0 E
- 4 9 -
_..0 040E+tt...i.
. .... 1. 527E.00..8 19...91.... 6..1 7 8 4.E.+.4 6... I t.. _2_ 9- 7E.* t 6 4.726E+te t 6. 23 t t+ 0 0 8 i
.. =.- 0.: 5. 6 9 t E* t 5.. 5. 7. 4 7--7E+ 4= 7. 8.= --
17
_=
- 2. 314E* .. s t...t j 2 .......
87
. .. 92....1. 7 =____
8 352E+te_ ___= 142E*t5...t..9.772E.01- 4 -
- 2. 657.E 3.5.. 8 =6. =- e t st + t t..1. 3. .t .. t.t.E.= 34....I...t 6 9 3E..*.0 4.L
.. 93....6. 4 216E..+.05..5 2.13
.. --- -:4E + t3...1. 7. 0- SE.*.t.3..1..2 .0 7 5E.0 7.. 4. 4 . 2 .9 0 E.6.1.. 4 .. 2 ... 4 9 0 E. 0 0..1. 5. 5.17 E* t e...I - .
a 12a .95.....i..1 .. 76 0 E..*.t 6.. 0. .. 2... 0 37.E.e
==. .. s t..t 9.587E.+.05...I. 1 993E+tf ' I 1 2.65.E.+.0 5.. 8. 2 . 2 8 4 E + 4 19 0...I 4 E..1
.. = - - - --
+ 6 9...I
.t..r ..e 9 7....t ..5 .2.3. 2 E.*.t 5.. 6. 3. 4 4 5E
- t 6 2 747.t.+.44..8 1 1.292E+44
. - _ _ . .4. 3.032E....35 .I..1 550E.41 1. 2. 109E.+.07...I
.I M..D..95....1..5 .0 .... 4 S E + 0 5... 6..1 6 0 5E
- -_-- - + 06. 4 2 . 7 8 6E
- 0 0.. 8 7. 7 40E.*.t.9...I..1 6 39.E.+.0 7.. 8. 9 297t.+ 0g I
. .. . .4= . 79 ..... 0 E+ 0 e...I 3
.a..---
m0-9 9 1
-_2460E.*.05...4..4
.. . 6.26t.+.44..4.
... 5. .74.tE..+47..1.
.. = 2.3tBE+051. 2..-813E.03 .1. 2.7stt+44 - - l. 1.426E.*07..6 I
.I .f. C..9
. 9.n..1.. .4. 16.0 E.+.0 3....0..2 l .t 9E..+.e.l.. _ _ . = _ 8. _5 . .s __ _ 5 53E+
. 7. 4 39E-t -
t 3 __ e a
4.848E*tt...i. 8.92?E.19 ___ __:.=
I 5.tS7E*t3 I
.i .f ..C..i.t.t...a .. 3. 992E.+.0
. . . 2.. .8.... 2 277E.* s.e..4.013E t. .. .. 50...I 4.000E+0s -- _- 6..4 000.E.+.s.t...I..t
. . a.s.tE 40...t. 3.582E.29..4 1..1 265t* 88 ----1 i). .
10.u. ...l e.3..1. 5 4 4 8.E.*.t5 9
199E+05 .t 1.229E*18..8 '
8.537E.+.03..5..1 475E+49 .I S.577E*tS .i
.I t.u. .. t.e.l...I. .4 .016.t..+.0 4..8. 7 212 E+ 0 5 t 1 _ _ . _
. . ___ _ ____ 2.44E. 0.%..8. 3.533E.25_ _ _.1..0 .. 0 0 0 C.+.0 0.. 0. _4 . 239E.2 6 _ _3.294
. 3
_ _ _ ..E. ..
- t .e . . .i 10.U. .. 10 6...I ..9... 3 6 8 E..+.4 6..1..5 1. 32 0 E
- 6 6 i
. . .e.4
.. 9E.+.4 0.. 8- - --
..I ...t .e.t.L E..+ .. 11.. 4_-3.09st+05...1. _ .. 2.173E+18 9. 1.247E*te...I
.t a.C. ...o.l l .e.m.8..4 .. 632.E.*
. . 0 6... 4..4 619 E
- 4 9. -----. 12.19 .. 0.E.+.t .t. 1. 2. 523E.+.t
. ... . f.. 8. 5 . 9 9 6E -_
- 4 9...1. 3 9. 29.f..+ .. 4 9.. 6.. 3 . 979 E.* t t....i i, I. .125 n.. ....i ..3.136.E.*.t.5..1..2 12
.T.E . 8 E..+.0 6..1. 6. 6 2 6E* t ? I
.__ 1 46tE+49..4. 7 906E*06..4.
1 75..LE.+.0S....I i
... . 3
. .. 927.E*08
.I..T .- E..12.. _ 7M : . i 9 . 6 0 0 E.*.t.5..
1
... 8..1 f.t3E.+.0 ..5... 8..1 486.t.E+ 53 t t+. 4090...1.
. 8..3.67.t . . t.+.0. 7.. 8. .5. 4 37t..+.18... 8..1 410 E..+ t t...i . ..
81E.*.l27..1.
. . 5. .736E*te 2 . 29 3.E.+.8 3.. 4.= 5. 27 8E+ 42.4_=-_=
.. ... ___.8.
034E..se 1..8 t.t.tt.+.$$
4
. .. 2.44tt 09.. I 4 . 5 3 2E
- s.5...I
.B .T .E. . .12
. 9m..I ...t16 0.E.+.4
.. . 6..1..2 3 . 0 SE
- t 7...I ..3 .0. 2.8 t.+.0.B...f ..56 _.
..... tE
- 4 9...I ...t .6 .4. 5E.+.9 6.839E+05 7.. 4- 1 1.-__ 2 6.t E..*.t . t...t
.I .T E. 12 9.. ..1..1.9.3 6E.*.8 3.. 8..3 0 76.E.*.0 4..1._9.167E.i St...i. 0 0 0 E+ 9 8
.. __ - . _ __ . 0 8 8 E+
. 0 6..4..0 . 8 0 0 E.*.0.0 1. 2. 8=-9 6C
- t 3 I
_ = ..I . 9 ..
6.T E...13.t n .a.
. .. . .- 5 56 4E* 45 _ .0.= 9.=-4 _==_= 59E* 0 6 4..1 75.3E.+.-- 07 8 2 19.0. .E.+.0 4.. 4..1. 2 6 6E.15 . 8. 2 .= 6 2 SE + 0 3 _
.1. 4
. ...4 2 0 E.+ 0 7 I
.I .T .E. 131. . 4... .4 39 2E.*.0 3..1..3 . . 4 5.&E.*.4 6._ 57eE.32.. 7.. 6
.... I t . 8 0 0E* 0 6 8 0. 8 0 0E* 0 0 ..t. ..
0 0 0 0 E.*.0 .. 0..8. 6. 575.E 15....I
.I T.E.132.. 6. 5. 896E..e
.. .. . t$... 4.. 4..9 .. 68.E.+9 6..1. 7. 32 4E+8 7 2.87t.*.4 1..4 . 7.. 8 1 17.t . .... E 91 1. 5 4 .4.... 4 E+ 9 6..8..1 3.12E.*.0 0 .I
.l .i .i.3 9....i.....i r..E.* . 6...i..6 .. 6 92.E
.. 8 6...i i . 0 5.E... .. .i. 1. 272.E .. .. 9 ..0 535E.44...i. .... 6..326E .. 05...i......,......E. 07..1 (PASTURE) (PASTURE) (FEED) (PASTURE)
/ Uni t s : Inhalation and all tritium - mrem /yr per u Ci/m Other pathways for all other radionuclides - m2
- mrem /yr per u Ci /sec 1
)
i I
ODCM, V.C. Sumer, SCEandG: Revision U (2:etembet 1987) 2.0-30 l
n Table 2.2-6 (Continued)
+
PATHWAY OOSE FACTORS FOR SE CTION 2.2* 2.ci(R ) *
- /r*
- i. ..
Page 3 of 3 l'
l
.a.c...t .C .. a.O.UP . . .a ...a . pu.(. T. .p. .....t..u. a. ..3....-(_ a DULT t -
3.....i ...A.D.UL.T l - ;_.. ---A DULT .1.....( .. A ..
0u.t.,.T . 3 .....t a.D
.. U.L.T. ..I .
t . . ...
i i
- n. 131
..I .15010.P t 1.lT2E*07. E. .t 0. . 2.I0m .. .
.0 ....
a.a L a...110.N..t . - == ==_ _:-
9E + 4 7.. 4..1 3 8 SE.+.11.. 3. 5. 0 3 4 E + 9 9
.C.R.O.U.N.D.P t.a.N.E .l ..C S.$. ...
9
.. ;__ -__2 . .. / C.Q W./ M I L t l
.it ........................132....
- 2. 0 .:-
65t.*.e.7....I . 6. 9 4 0E.+.t.t....t . 3. 7 8 5.E.*.t.4..6
~
14 eE..*.4 5....I6..1
. ... =__ 5 2E
- t8 6 -
.. t ._4-_.____.-
- 1. 3 4 2E + 01...I . 1. :. e t 6E.57... 0. 0 . 0 0 0 E .+.. 4 4..1..2 43
. .. 533...1..2 152E.*.06 . .. =
17.9 C.59....I ... . 5 .016 E.*..t 3...I e .2 94.LE.*.06..8.
9.09tt+ee..1. 9.336E*01...I...l. .03.OE.
... 23...t..1 lt.eE.*01
. . ... 6. 5 . ---33tt+tt...t 1....
1 8 3 4.....e . 2.... 9 0. 4 E..* s .e..1.
- 5. 3.8 ..5.E.* t 5....I . = 9 . 4 91 E ... = l l.. 8..8 4 0 06 E.+.4 E.*4..1..9
.6..t.. .0 0.. 4 . 0. 0 4.8 t.*.t..t...I 5..44. 4..C. 8 3...I 11 135...1.. 4 4 ..0 0.E.+.4 5.. 8..2
. . 9 4 7.E.*.t.e...i 2 217.E.+.0
.. 6..1. 7. 6 4 4E.15.--I 9.80SE*06 8 9.172.E.8 6. 8. 6.7.31 E.+.8
- . ... . 6...1 t E.S.
. .. 13.4.. 4. 0..
- t.0 E..+.0 5...4. 0 0 0 7E.+.s 9.8..1 34 5E+ 10 - .I ..1 56 5C* t t .1. 4 . 33:---.
3 E + e 9...I ..1 0.. 7 0E.+.0 8..1..1. 110 E..*.10
. .I
.I C.S. . 134 ..e ..1., .46 4 E
- t 5 8 1 7 0 2E.+ 0 s t ..4 i
j
. - - - . . . .. .. 4 36E.+.t.f.. 4...4 72 4E.+.t.?...t..3
.. . . 9 9 3C*
..- __ t 6..1. 5. 6 6 9 E + 4 8 6..1 475.E.+.6 . . . 86 I.C.$. ..
137.. . 6. 6.. ..2.t B.E.* t 5....t -- - . 1._=2 2 8 t E
- t.ee...i ..1
.t t.t + 10-....4.6 .19 -- --
3E. + 8 9..8. 3.513.E.*.e . . 9... 8..1 431. .. E.+ 0 S..I ..O. 49 6.E.+ 4 9...u.n
.I .C.S l.3.e...i..6 20 8.E.*.0 2.4..4 102E+05 0 0 0E+ t t...I 4 s.t.tE* t.t...t..4 e t tE* t t _ t..7 .73.tt..l.t.
0..1 786E*23..1..6 r
I
.Ita
.. ...13 9...t... .3. 76..a E.*10 3..1
. .. t.
19.4
. E..+.0. .. 5 t ..8 . 322.E.t
... e....t ..9 t .O.G E..+
a s.t.e.s.oE.*.4
_ ..t .. 8...e...es .t.e E..+.t.t...t.5. .225E
.I .D....a.. t a e ...I...t2.72C..*.se....i
. . .. 4 2...
. 2 3 .4 6E.+.8 7...t ~. . 1. 53 5.E+ ..t ?....l .1..1. 5. .- 49.17.t.+
7 2t+ 05...t.
47 7. l .t .lE..+.0 6 6 2. 6...4 6E..* .e e....I ,
.ita.146...a.
.... . 1.936E*t3..1 184 342 s 6.192E*s3 4 4 734.E+04..8. 2.677E.46..6. 0.666t+04. 8. .8.--steE*48 4..0 000E.*t.0...t.
==_ .. .. -___
9.. 3.tSE.22 6
.s. -
(.. 0.000E+44 .6. 4.steE*00. e. 8.astE*00..1..0 5 46.4E.*04..6.
000E*40 4 g .L.a ....................
..14 0..1..4 5. 4 4 E..+.t1.. .
. --- __. 2 463.E.
. .. ... 39 4
. Im ) . . . ..
- 6. 2 19 8 E + 0 7 . 9..1 6 72.E..+.0. . 38 5E..+.45...I 3 ...l
.l.. 4 4. .5 .. 9 E. 12.. 6..1 . .6. 6 2E.*.8 2.. . .6..7 327 E.*.t.?...I 9, .I L. .. A.6 42...1. 6. 320.E ... ...+ s 3..1. 8 st.6 .. .E.*.0 5..1 3.543E.80..1.
. -_ _ - 9.000E+00 i ...S .I s.t I . ..t.+0 8... 8. ..0. 4 8 4.E.+.4.9..8 ... 4. 99 9.E..S.t ..4
.C.E. ... 8 41. .1..3.616 .E.*.t . 5.. 4..1 5. 4 ..4. E.+ 4 7 ..l I 2 53.E..+ ..
4 7.. 6..3 6.32E..+.4 7.. 6. 6 4 2 4 E..*.t.t...i
. . .. . . .t ...5.4 4.. 35..eC..+.4 97.C.*
... t .. s. t . 4
.I C.E. . .. .t e s...a . 2. 2 6..* E..*.t 2. 5...1.
- 6. 2 7.E.*.t. e..I ...t . ..
14 9.E.*.t 6. 1. 5. .5.4 7.E..e s t....t . 7. 7 6.e.t.e . ... t.s...1.
. 6. 6 5 6E e t..t ...i . 2
.C .. E ...8 4 4.. 6. 7 776.E..*.t e....t I
-- -. 0. -_ 9 __ 3 2E+ 0 1 27...t 8 9E.+.0 g
... . ....I..4 .920E.+t.g. . ...i .. 3 3.... 9 0 .E
- t 7.. 4. 5. 914E..+.4. . 7...I .t i ..t 2.C *.t .t...t ,
19 5.. .. l. .4 3...e ..2.s.t 9E*t5 2 4 4 5.E.+ t 3 I
..=---
-1 l.st6E*t3 e:.. t.e .e .E..+.0 8...I ..6. _...9 2 3E+ 0 5..1..9 2 .t8 4E..+.47 . .- .
-t .10 4 E.+.e ?...I .. 2 7.4 0.E..+ e s... -
t.e. a. 14 4 8 2.112E+03 t -__ . . ..
6 716E .. 5 4...I .t t.t.s.t.+.t.s...a ...t .t.t.tt..+.t.t...t ..4 .s.t.I.E
.th..D ..................................... .
.. + t.t. i . .3... 3 0 3E..2 .1- 6.
.147....1..2 2 0 0E
- t 5
.r 4.. 6 4 0 9 f.+.8 7...I ..5 2.3.t t.+.0 5..1..3 9 3 5E.+.4 7... 6..6 2.1..4 8.6E..+.t 7 22 E2
. . . 4
+ 0 6-BW .. . --- -
_ ..1 0 5 3 E..+.t .e.
..t S.7.,....I ..1 552.C..+.9 5.. 8. 2 7 4 8 E + 4 6.. 4..1 7 9 6 t.*.4 6..
.... ... .t. 4. ..7..
3 587.E 912E..*.t.t
.22...1. 7. 4.9 4E..6.%...l ...L0 4 6.t.+.4 7...4
.i . ..2 3....I ...s .a.9 2C.*.t.5. i...i ,76E* t.
.. .. 4 3 .i. 7 5 4 5E. 4 ...i.... 6 i 2E..+.4 2 i 2 ...72E. .4 7...i
- i. 7 3 5.E 9. . . ...i. 5. il.2.E . . .
1 (PASTURE). (PASTURE) (FEED) (PASTURE) 1
)
i i
i 1
l, i
i I
i l
[V Units: Inhalation and all tritium -
mrem /yr per uCi/m Other pathways for all other radionuclides - m2
- mrem /yr per uCi/sec ODm, V.C. Sumer, SCEandG: Revision 12 (SeDtember 1987) 2.0 4
NOTE: The P, values of Table 2.2-2 through 2.2-6 were calculated in O
accordance with the methods of Section 5.3.1 of Reference 1.
Columns in those tables marked " Pasture" are for freely-grazing animals (fp = f,= 1). Columns marked " Feed" are for animals fed l
solely locally-grown stored feed (f,= f,= 0). The values used for each parameter and the origins of the values are given below in Table 2.2-9 and its notes.
O' i
O' ODCM, V.C. Summer, SCEandG: Revision 12 (September 1987) ,
l 2.0-32 j i
(
e Table 2.2-7 CONTROLUNG RECEPTORS, LOCATIONS, AND PATHWAYS
- DISTANCE AGE ORIGIN SECTOR (METERS) PATHWAY GROUP (FOR INFORMATION ONLY)
N** 6,400 Vegetation Child -Vegetable Garden NNE 5,800 Vegetation Child -Vegetable Garden 5,300- Grass / Cow / Meat -Grazing Beef Cattle NE 4,700 Vegetation Child -Vegetable Garden 4,700 Grass / Cow / Meat -Grazing Beef Cattle ENE 2,400 Vegetation Child -Vegetable Garden E 5,000 Vegetation . Child -Vegetable Garden ESE 1,800 Vegetation Child -Vegetable Garden -
SE 2,400 Vegetation - Child - -Vegetable Garden SSE 4,300 Vegetation Child -Vegetable Garden S** 6,300 Vegetation Child -Vegetable Garden (m SSW*
- 5,500 Vegetation Child -Vegetable Garden
\ SW 5,300 Vegetation Child -Vegetable Garden WSW 5,300 Vegetation Child -Vegetable Garden W 4,300 Vegetation Child -Vegetable Garden 3,400 Grass / Cow / Meat -Grazing Beef Cattle WNW*
- 7,200 Vegetation Child -Vegetable Garden 7,200 Grass / Cow / Meat -Grazing Beef Cattle NW 6,600 Vegetation Child -Vegetable Garden 6,600 Grass / Cow / Meat -Grazing Beef Cattle NNW- 4,800 Vegetation Child -Vegetable Garden 4,800 Grass / Cow / Meat -Grazing Beef Cattle See note on the following page for the method of choice of these controlling receptors.
If a cow were located at 5.0 miles (8,000 meters) in this sector, an infant consuming only its milk would receive a greater total radiation dose than would the real receptor listed. Such an infant would not be the Maximum Exposed Individual for the site.
I 00CM, V.C. Summer, SCEandG: Revision 12 (September 1987) 2.0-33
NOTE: The controlling receptor in each sector was identified in the following way. Receptor locations and associated pathways were obtained from the August 1987 field survey. A child was assumed at each location, except that where a milk cow was listed, an infant was assumed. XTO' for each candidate receptor was obtained by interpolation of values in Table 6.1-10 of Reference 5; DTQ' for each candidate receptor was obtained by interpolation of values in Table 6.1-13 of Reference 5. Expected annual releases of each nuclide were taken from Table 5.2-2 of Reference 5. The pathway dose factors given above in Tables 2.2-3 and 2.2-4 were then used with the referenced values in the methodology of i Section 5.3 of Reference 1 to compute total annual doses at each candidate receptor site for the pathways existing at that site. The controlling receptor for each sector was then chosen as the ,
candidate receptor with the highest total annual dose of e.ny candidate receptor in the given sector. All listed pathways are in addition to inhalation and ground plane exposure.
O O
ODCM, V.C. Summer, SCEandG: Revision 12 (September 1987) 2.0-34
1 l
Table 2.2-8 ATMOSPHERIC DISPERSION PARAMETERS FOR CONTROLLING RECEPTOR LOCATIONS
- _ .__ DISTANCE SECTOR X/O' D/O' (l\/IlLES/ METERS)
N 1.4 E-07 6.2 E-10 4.0/6,400 NNE 2.5 E-07 1.1 E-09 3.3/5,300 NE 3.4 E-07 1.7 E-09 2.9/4,700 I ENE 1.2 E-06 6.8 E-09 1.5/2,400 E 2.4 E-06 9.6 E-10 3.1/5,000 f ESE 2.2 E-06 8.4 E-09 1.1/1,800 SE 1.6 E-06 5.8 E-09 1.5/2,400 ..
SSE 3.0 E-07 1.0 E-09 2.7/4,300 5 1.7 E-07 3.7 E-10 3.9/6,300 SSW 2.0 E-07 6.4 E-10 3.4/5,500 SW 2.6 E-07 1.0 E-09 3.3/5,300 WSW 2.0 E-07 8.7 E-10 3.3/5,300 W 3.6 E-07 1.7 E-09 2.1/3,400 WNW 6.6 E-07 2.5 E-10 4.5/7,200 N5N 9.7 E-08 4.1 E-10 4.1/6,600 NNW 1.8 E-07 9.7 E-10 3.0/4,800 Annual average relative dispersion and deposition values for the receptor locations in Table 2.2-7. Values were obtained by interpolation in Tables 6.1-10 and 6.1-14 of Reference 5. Those tables are based on one year (1975) of meteorological readings and the FSAR dispersion model (ground-level release, sector-averaged model, with open terrain recirculation factors, dry depletion by Figure 2.3-1, and using decay with a half-life of 8.0 days). As a result of the analysis described in the note to Table 2.2-7, the location of the maximum exposed individual for the site was identified as being the vegetable garden at 1.1 miles in the ESE sector. Therefore, the site X/Q' and UTQ'(Section 2.2.2.b and following) are those from this table for that location.
O ODCM, V.C. Summer, SCEandG: Revision 12 (September 1987) 2.0-35
a 1
- i Table 2.2 9 G'
Page 1 of 4 !
PARAMETERS USED IN DOSE FACTOR CALCULATIONS I Origin of Value l l
Parameter Value 5 ion f g, R.G.1.109 SD'CII'C 0133
- *
- Fo r P;* *
- I DFA, Each radionuclides E-9 Note 2 BR 3700 m3 /yr E-5 '
I
- **For Ri (Vegetation)* * * -
r Each element type E-1 Y, 2.0 kg/m 2 ..
E 15 Aw 5.73 E-7 sec ' p 5.3.1.3 h
DFL, Each age group and radio- E-11 thru Note 2 nuclide E-14 Ua' Each age group E-5 f t 1.0 5.3.1.5 t
o 8.6 E + 4 seconds E-15 5
Ua Each age group E-5 fy 0.76 5.3.1.5 t
n 5.18 E + 6 seconds E-15 H 8.84 gm/m 3 Note 1
- * *For Ri (Inhalation)* *
- BR Each age group E5 DFA, Each age group and nuclide E-7 thru Note 2 E-10 e'
ODCM, V.C. Summer, SCEandG: Revision 12 (September 1987) 2.0-36
l Table 2.2-9 f^)
c i Paae 2 of 4 l
1 PARAMETERS USED IN DOSE FACTOR CALCULATIONS l
I Oriain of Value Parameter Value Table in Section of Site-R.G.1.109 NUREG-Specific
]
- **For R Plane)*
- g(Ground ,
SF 0.7 E-15
(
DFG, Each radionuclides E-6
t 4.73 E + 8 sec 5.3.1.2 o ***For Ri (Grass / Animal / Meat)* *
- Q, (Cow) 50 kg/ day E-3 Q, (Goat) 6 kg/ day E-3 U,, Each age group E-5 Aw 5.73 E-7 sec-' 5.3.1.3 F, (Both) Each element E-1 3
r Each element type E-15 DFL, Each age group and nuclide E-11 thru Note 2 1 E-14
]
f, 1.0 Note 3 f, 1.0 Note 3 l Y, 0.7 kg/m 3 E-15 l tn 7.78 E + 6 sec E-15 Y, 2.0 kg/m 2 E-15 tf 1.73 E + 6 sec E-15 H 8.84 gm/m 3 Note 1 l
1 ODCM, V.C. Su mmer, SCEand G: Revision 12 (September 1987) l ]
l j 2.0-37 l
l j
{
,i Table 2.2-9 g' l Page 3 of 4 PARAMETERS USED IN DOSE FACTOR cat.CULATIONS
)
Oriain of Value Parameter Value Section of Table .in Site-RE R.G.1.109 Specific 333
- * *For R Note 4 (Grass /Co; w/ Milk)* *
- QF 50 kg/ day E-3 U,, Each age group E-5 Aw 5.73 E-7 sec-' 5.3.1.3 F, Each element E-1 r
DFL, Each element type Each age group and E-15 E-11 thru Note 2 g
nuclide E-14 Y, 0.7 kg/m 2 E-15 i
n 7.78 E + 6 sec E-15 Y, 2.0 kg/m 2 E-15 t, 1.73 E + 5 sec E-15 f, 1.0 Note 5 f, 1.0 Note 5 f, 0.0 Note 5 i f, 0.0 Note 5 H 8.84 gm/m 3 Note 1 O
ODCM, V.C. Summer, SCEandG: Revision 12 (September 1987) 2.0-38
Table 2.2-9 (Continued)
Page 4 of 4 NOTES
- 1. Site-specific annual average absolute humidity. For each month, an average I absolute humidity was calculated from the 7 years of monthly average temperatures in Table 2.3-49 of Reference 4 and the 5 years of monthly average dewpoints in Table 2.3-64 of Reference 4. The 12 monthly values were averaged to obtain the annual average of 8.84 gm/m 3 (Section 5.2.1.3 of Reference 1 gives a default value of 8 gm/m 3.)
)
- 2. Inhalation and ingestion dose factors were taken from the indicated source.
For each age group, for each nuclide, the organ dose factor used was the highest dose factor for that nuclide and age group in the referenced table.
- 3. Typically beef cattle are raised all year on pasture. Annual land surveys have indicated that the small number of goats raised within 5 miles typically are used for grass control and not food or milk. Nevertheless, the goats were ~
O treeted es fe'i m eet seerces w 8ere preseet. desnite 18e fec1 thet t8eir numbers cannot sustain the meat consumption rates of Table E-5 of Reference 3.
- 4. According to the August 1987 land use census, no cows or goats are kept for milk within 5 miles of the Station. These values are included for reference only.
- 5. Two columns of R,'s were calculated - one for cows kept exclusively on local pasture (fp = f,= 1), and one for cows kept exclusively on locally grown stored feed (f p= f, = 0). See the note on page 2.0-32.
O ODCM, V.C. Summer, SCEandG: Revision 12 (September 1987)
i 2.3 Meteorological Model 2.3.1 Atmospheric dispersion for all releases is calculated using a ground-level, wake corrected form of the straight line flow model.
X/O = the sector-averaged annual average relative ,
concentration at any distance in the given sector (sec/m 3) n (51)
=
2.032 ST { Nru,[y
)
where:
2.032 = (2/n)i.2 divided by the width in radians of a 22 " sector (0.3927 radians).
8= plume depletion factor at distance r for the appropriate '-
stability class from Figure 2.3-1.
.t i = windspeed class. The windspeed classes are given in Table g 4A of Reference 10 as 1-3,4-7,8-12,13-18,19 24, and > 24 W miles per hour.
n, = number of hours meteorological conditions are observed to be in a given wind direction, windspeed class i, and atmospheric stability class j.
N = total hours of valid meteorological data.
r = distance from the containment building to location of interest (m) u, = wind speed (midpoint of windspeed class i) at ground level (m/sec).
, (52)
Eg = the lese of (o 2 + b2/2n)' or (V3ay O
ODCM, V.C. Summer, SCEandG: Revision 12 (Septernber 1987) 2.0 40
where:
f}
'~
o, = vertical standard deviation of the plume (in m) at distance r for ground level releases under the stability category indicated by AT/ AZ, from Figure 2.3-2.
T = terrain recirculation factor, from Figure 2.3-4 n = 3.1416 b = height of the containment building (50.9m)
AT/AZ = temperature differential with vertical separation i
( K/100m).
2.3.2 Relative deposition per unit area for all releases is calculated for a g round-level release.
D/Q = the sector-averaged annual average relative deposi-tion at any distance in a given sector (m-2),
10 V -- 2.55 Dgn (53) rN where, Dg = deposition rate for ground-level releases relative to distance (r) from the containment building (from Figure 2.3-3).
2.55 =
the inverse of the number of radiansin a 22.5 sector 1
(22.5 )(0.0175 Radians / )
n = number of hours wind is in given direction (sector).
N = total hours of valid meteorological data.
O b
ODCM, V.C. Summer, SCEandG. Revision 12 (September 1987) 2.0-41
1 Figure 2.3-1 .
Plume Depletion Effect for Ground Level Releues (4)
(All Atmospheric Stability Classes)
Graph taken from Reference 8 Figure 2 ,
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i
. (1 Figure 2.3-2 k/ Vertical Standard Daviation of Material in a Plume ( z) l (Letters denote Pasquill Stability Class) i Graph taken from Reference 8, Figure 1 I a /
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0.1 1.0 10 100 PLUME TRAVEL DISTANCE (KILOMETERS)
Temperature Otange Pasquill Stability with Height AT/aZ (*K/100n) Ca tegories Cl ossification
< -1. 9 A Extremely Unstable
-1.9 to -1.7 8 Moderately Unstable
-1. 7 t o -1. 5 C Slightly Unstable
-1. 5 t o -0. 5 0 Neutral
-0. 5 t o 1.5 E Slightly Stable C( 1.5 to 4.0 F Moderately Stable
> 4.0 G Extremely Stable ODCM, V.C. Stamer, SCEandG: Revision 12 (September 1987) 2.0-43
l ..
I i i j
.+
/ Figure 2.3-3
( Relative Deposition for Ground-Level Releases (D )
g
/ ( All Atmospheric Stability Classes) j
/
Graph taken from Reference 8, Figure 6 l 10 , ,
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PLUME TRAVEL DISTANCE (KILOMETERS)
- - __,n- nn s,- nne a n oc
/
Figure 2.3-4 Open Terrain Recirculation Factor Graph taken from Reference 7, Figure 2 p ,
8
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/ o O o - 8 5 CORRECTION FACTOR ODCM, V.C. Sumer, SCEandG: Revision 12 (September 1987) 2.0-45
. _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - ~ - - - - _ . - _ __ -- - - - - - - - - -
~ .
~
l 2.4 Definitions of Gaseous Effluent Parameters Section of Term Definition Initial Use b = height of the containment building. (2.3.1) l C, = count rate of a station vent monitor (2.1.1) corresponding to grab sample radio-nuclide concentrations. '
C*' = the count rate of the monitor on vent v (2.1.3) corresponding to X,' uCi/cc of Xe-133.
c = count rate of the gas decay system (2.1.2) monitor for measured radionuclides concentrations corrected to discharge pressure.
c' = the count rate of the waste gas decay "
(2.1.3) system monitor corresponding to the total noble gas concentration.
D = deposition rate for ground-level re- (2.3.2) 9 leases relative to the distance from the containment building (from g
Figure 2.3-3).
D, = average organ dose rate in the current (2.2.1.b) year (mrem /yr).
D"
= dose to an individual from radioiodine (2.2.2.b) and radionuclides in particulate form and radionuclides (other than noble gases), with half-lives greater than eight days (mrem).
D, = average skin dose rate in current year (2.2.1.a)
(mrem / year).
D 33 = limiting dose rate to the skin (3000 (2.1.1) mrem / year).
D, = average total body dose rate in the (2.2.1.a) current year (mrem /yr).
Da= limiting dose rate to the total body (2.1.1)
(500 mrem / year).
Op = air dose due to beta emissions from (2.2.2.a) l noble gas radionuclides (mrad).
I ODCM, V.C. Summer, SCEandG: Revision 12 (September 1987) l 2.0-46 1
A l
Section of
. Term Definition Initial Use V
Q Dy = air dose due to gamma emissions from noble gas radionuclides (mrad).
(2.2.2.a) !
l D/O = . the sector averaged annual average (2.3.2) relative deposition for any distance in a given sector (m.2),
l D/Q' = annual average relative deposition (2.2.2.b) at the location occupied by the maxi-mum exposed individual.
6 = plume depletion factor at distance r (2.3.1) for the appropriate stability class ,
from Figure 2.3-1.
j F, =
the flow rate in vent v (cc/sec). (2.1.1) !
f, = the maximum permissible waste gas (2.1.2) discharge rate, based on the actual radionuclides mix and skin dose rate.
f, = the maximum permissible waste gas (2.1.2) discharge rate, based on the actual ,
i radionuclides mix and total body dose rate.
'f * = the maximum permissible waste as (2.1.2) discharge rate, the lesser of f, an f,.
f,' = the conservative maximum per- (2.1.3) missible waste gas discharge rate based on Kr-89 skin dose rate.
f,' = the conservative maximum permissible (2.1.3) waste gas discharge rate based on Kr-89 total body dose rate.
K, = total body dose factor due to gamma (2.1.1) emissions from isotope i (mrem / year per uCi/m 3) from Table 2.1-1.
Kk r-89 = total body dose factor for Kr-89, the (2.1.2) most restrictive isotope from Table 2.1-1.
=
i L, Skin dose factor due to beta emissions (2.1.1) from isotope i(mrem /yr per uCi/m 3) from Table 2.1-1.
Lg, .g, = Skin dose factor for Kr-89, the most (2.1.2) restrictive isotope, from Table 2.1-1.
M, = air dose factor due to gamma emissions O from isotope i(mrad /yr per uCi/m3 ) from Table 2.1-1.
(2.1.1)
ODCM, V.C. Su mmer, SCEandG: Revision 12 (September 1987) 2.0-47
'l Section of l Term Definition initial Use -
)
)
MKr-89 = a r dose factor for Kr-89, the most restrictive isotope, from Table 2.1-1.
(2.1.2) 9 )
i N, = air dose factor due to beta emissions (2.2.2.a) from noble gas radionuclides i(mrad per uCi/m 3) from Table 2.1-1.
{
l N,' = number of hours meteorological (2.3.1) l conditions are observed to be in a !
given wind direction, windspeed class i, and atmospheric stability class j.
1 N = total hours of valid meteorological (2.3.1) l data.
P, = dose parameter for radionuclides i, (2.2.l.b) {
(mrem /yr per uCi/m3 ) for inhalation, l from Table 2.2-1.
O, = the release rate of noble gas radio- (2.2.1.a) .
nuclide i as determined from the con-centrations measured in the analysis {i of the appropriate sample required by Radiological Effluent Technical Speci-fication Table 4.11-2 (uCi/sec).
=
Q = the release rate of non-noble gas radionuclides i as determined from (2.2.1.b) 0 -
the concentrations measured in the analysis of the appropriate sample required by Radiological Effluent Technical Specification Table 4.11 2 (uCi/sec).
%= cumulative release of noble gas radio-nuclide i over the period of interest (uCi)
(2.2.2.a)
Q,' = cumulative release of radionuclides i (2.2.2.b) of iodine or material in particulate form over the period of interest (uCi).
R
= dose factor for radionuclides i and (2.2.2.b) pathway j,(mrem /yr per uCi/m3 ) or (m 2-mrem /yr per uCi/sec) from Tables 2.2 2 through 2.2-6.
R, = count rate per mrem /yr to the skin. (2.1.1)
R, = count rate per mrem /yr to the total (2.1.1) body.
r = distance from the containment building (2.3.1) to the location of interest for dispersion calculations (m).
ODCM, V.C. Summer, SCEandG: Revision 12 (September 1987) 2.0-48
., , ; y <
Section of
,, Term. Definition Initial Use
- /
\ R ,' - = conservative count rate per mrem to (2.1.3) the skin (Xe-133 detection, Kr 89 dose).
R ,' = conservative count rate per mrem to (2.1.3) the total body (Xe-133 detection, Kr-89 dose).
Sg = wm rate M h wane gas decay Q.1.0 l system noble gas monitor at the alarm setpoint.
5, = count rate of a station vent noble gas (2.1.1) monitor at the alarm setpoint.
]
Sy , count rate of the containment purge (2.1.1) noble gas monitor at the alarm setpoint.
.S , = coun,t rate of the plant vent noble gas (2.1.1) monitor at the alarm setpoint.
Y )
E, = vertical standard deviation of the (2.3.1) plume, with building wake correction !
applied. I o, = vertical standard deviation of the plume (2.3.1) l
-(in m), at distance r for ground level j
~'s -
releases under the stability category indicated by AT/ AZ, from Figure 2.3-2.
AT/AZ n temperature differential with vertical (2.3.1) separation ( K/100m).
T = terrain recirculation factor, Figure (2.3.1) 2.3-4.
u, = wind speed (midpoint of windspeed (2.3.1) class i) at ground level (m/sec).
W, = controlling sector annual atmospheric (2.2.1.b) dis aersion at the site boundary, as rac ionuclide i.
W'= ,' relative dispersion for the maximum (2.2.2.b) exposed individual, as appropriate for his exposure pathway j and radionuclides i.
]
Xg = the concentration of noble gas radio- (2.1.2) nuclide i in a waste gas decay tank, as corrected to the pressure of the discharge stream at the point of its i
flow measurement. '
X,, = the measured concentration of noble (2.1.1)
ODCM, V.C. Summer, SCEand G: Revision 12 (September 1987) 2.0-49 r
~ ,
i Section of Term Definition Initial Use -
gas radionuclides iin the last grab j sample analyzed for vent v (uCi/cc).
X' a
= % total noNe gas cowwa& b a W1.M waste gas decay tank, as corrected to the pressure of the discharge stream at the point of its flow measurement.
X' y = a concentration of Xe-133 chosen to be (2.1.3) in the operating range of the monitor on vent v (uCi/cc).
X/O = the highest annual average relative (2.3.1) concentration at any distance in a given sector. (sec/m ).
X/Q = the highest annual average relative (2.1.1) concentration in any sector, at the site boundary.
XTQ' = relative concentration for the location (2.2.2.b) ,
occupied by the maximum exposed individual.
O O
1 ODCM, V.C. Summer, SCEandG: Revision 12 (September 1987) 2.0-50 4
1
< 1
'l 2.5 Gaseous Radwaste Treatment System Figure 2.5-1 12 a! : I
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ODCM, V. C. Summer, SCEandG: Revision 12 (September 1987) 2.0-51
~ .
O 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING 1
Sampling locations as required in section 3/4.12.1 of the Radiological Effluent Technical Specifications are described in Table 3.0-1 and shown on the maps in Figures 3.0-1 and 3.0-2. As indicated by the ditto (") marks in the table, entries in the sampling frequency and analysis frequency columns apply to all samples below the entry until a new entry appears.
-u O
O ODCM, V.C. Summer, SCEandG: Revision 12 (September 1987) 3.0 1
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