ML20004D051

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Offsite Dose Calculation Manual
ML20004D051
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 05/31/1981
From:
APPLIED PHYSICAL TECHNOLOGY, INC.
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Shared Package
ML20004D050 List:
References
PROC-810531, NUDOCS 8106080264
Download: ML20004D051 (125)


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{{#Wiki_filter:. _ _ I* I I 0FFSITE DOSE CALCULATION MANUAL FOR SOUTH CAROLINA ELECTRIC AND GAS COMPANY VIRGIL C. SUMMER NUCLEAR STATION r I I May 1981 I I ! I ' I I l I l l

TABLE OF CONTENTS PAGE List of Taoles.......................................................... 11 List of Figures......................................................... iii References.............................................................. iv Introduction............................................................ v 1.0 LIQUID EFFLUENTS 1.1 Liqu id Ef fl uent Moni tor Setpoints.......................... 1.0-1 1.1.1 Liquid Radwaste Effluent Line Monitors............... 1.0-1 1.1.2 Detergent Waste Discharge Via Sanitary Waste System.. 1.0-10 1.1.3 Steam Generator Blowdown and Turbine Building Sump E f f I u e n t L i n e s................'.......................1. 0-11 1.2 Dose Calculation for 1.iquid Effluents....................... 1.0-20 1.3 Definitions of Liquid Effluent Parameters................... 1.0-26 1.4 Liquid Radwaste Treatment System............................ 1.0-31 2.0 GASEQUS EFFLUENTS 2.1 Gaseous Effluent Monitor Setpoints.......................... 2.0-1 2.1.1 Station Vent NoDl e Gas Mon i tors...................... 2.0-1 2.1.2 Waste Gas Decay System............................... 2.0-3 2.1.3 Alternative Methodologies for Establishing Conservative Setpoints............................... 2.0-5 2.2 Gaseous Effluent Dose Calculations 2.2.1 Unrestr i cted Area Boundary Dose...................... 2.0-9 2.2.2 Unrestricted Area Dose to Individual................. 2.0-10 2.3 Metecrological Model 2.3.1 Atmospheric Dispersion.........,..................... 2.0-32 2.3.2 Deposition........................................... 2.0-33 2.4 Definitions of Gaseous Effluents Parameters................. 2.0-38 I 2.5 Gaseous Radwaste Treatment System........................... 2.0-44 3.0 RADIOLOGICAL ENV IRONMENTAL MONITORING............................ 3.0-1 3.1 S amp l i n g L oc a t i o n s..........................................

3. 0-2 3.2 Map of Sampl ing Locations (Local)........................... 3.0-12 3.3 Map of Sampling Locations (Remote).......................... 3.0-13 ODCM, V C Summer, SOUTH CAROLINA ELECTRIC AND GAS CO.

i

LIST OF TABLES Taole No. Page No. 1.2-1 Bioaccumulation Factors 1.0-22 1.2-2 Adult Ingestion Dose Factors 1.0-23 1.2-3 Site Related Ingestion Dose Comitment Factor (Ajr) 1.G-? S 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 (Pj) 2.0-13 2.2-2 Pathway Dose Factors for Section 2._2.2.b (Rj) 2.0-16 2.2-3 Pathway Dose Factors for Technical Specifications 4.11.2.4.1 and 6.9.1.13 (Infant) 2.0-19 2.2-4 Pathway Dose Factors for Technical Specifications 4.11.2.4.1 and 6.9.1.13 (Child) 2.0-22 2.2-5 Pathway Dose Factors for Technical Specifications 4.11.2.4.1 and 6.9.1.13 (Teenager) 2 ')-25 2.2-6 Pathway Dose Factors for Technical Specifications 4.11.2.4.1 and 6.9.1.13 (Adult) 2.0-27 2.2-7 Controlling Receptors, locations, and Pathways 2.0-30 2.2-8 Atmospheric Dispersion Parameters for Controlling Receptor Locations 2.0-31 3.0-1 Radiological Environmental i,ampling Locations 3.0-2 i ODCM, V C Sumer, SOUTH CAROLINA ELECTRIC AND GAS CO. ii l

LIST OF FIGURES Figqre No. Page No. I 1.0-1 Example Crlibration Curve for Liquid Effluent Monitor 1.0-19 1.4-1 Minimum OPERABLE Liquid Radwaste Treatment System 1.0-31 2.3-1 Plume Depletion Effect for Gound Level Releases (6) 2.0-34 2.3-2 Vertical Standard Deviation of Material in a Plume (a ) 2.0-35 z 2.3-3 Relative Deposition for Ground Level Releases (0 ) 2.0-36 9 2.3-4 Open Terrain Recirculation Factor (T) 2.0-37 2.5-1 Minimum OPERABLE Gaseous Radwaste Tre'atment System 2.0-44 3.0-1 Radiological Environmental Sampling Locations (Local) 3.0-12 3.0-2 Radiological Environmental Sampling Locations (Remote) 3.0-13 I 00CM, V C Sumer, SOUTH CAROLLIA ELECTRIC AND GAS CO. iii

REFERENCES This Offsite Dose Calculation Manual was prepared for the Virgil C. Summer 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 Radiological Effluent Technical Specifications for Nuclear Power Plants", NUREG-0133 (October 1978). j 2. " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR 50, Appendix I", 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 50, Appendix I", U. S. NRC Regulatory Guide 1.109, Rev. 1 (October 1977). 4. ' Final Safety Analysis Report", South Carolina Electric and Gas Company, Virgil C. Summer Nuclear Station. 5. " 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 / Equilibrium Concentration Relationship for the Parr Pumped Storage System", Applied Physical Technology, Inc., February 1981. 7. " Methods for Estimating Atmospheric Transport and Dispersion of Faseous Effluents in Routine Releases from _ight - Water - Cooled Reactors", U.S. NRC Regulatory Guide 1.111 (March 1976). 8. "Methoo; 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. I I ODCM, V C Summer, SOUTH CAROLINA ELECTRIC AND GAS LO. iv

INTRODUCTION The OFFSITE DOSE CALCULAT %. MANUAL is a supporting document of the RADIOLOGICAL EFFLUENT TECHNICAL SFECIFICATIONS. As such the ODCM describes the methodology and pa . ers 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 instrumen,tation alarm / trip setpoints. The ODCM contains a list and graphical descript' ion of the specific sample locations for the radiological environmental monitoring program. Minimum OPERABLE configurations of the liquid and 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 00CM represents the present methodology in all applicable areas. Computer software to perform the described calculations will be maintained current with this ODCM. I l l I I l l l ODCM, V C Summer, SOUTH CAROLINA ELECTRIC AND GAS CO. v I

1.0 LIQUID EFFLUENTS The Virgil C. Summer Nuclear Station is located on the Monticello Reservoir which provides supply and discharge for the plant circulating water. This reservoir also provides supply and discharge capacity for the Fairfield Pumped Storage Facility. The Parr Reservoir located below the pumped storage facility is located above the Parr Dam. There are two basic release nithways and sources of dilution for liquid effluents: the circulating water discharge canal and the liquid effluent line to the penstocks of the pumped storage facility. All liquid effluent pathways discharge to 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 p imped storage f acility during the generation cycle. 1.1 Liouid Effluent lionitor Setpoints The calculated setpoint values will be regarded as upper bounds for ' e actual setpoint adjustments. That is, setpoint adjustments are not required to be performed if the existing setpoint level corresponds to a lower count l rate than the calculated value. Setpoints may be established at values lower i than the calculated valuC3 if desired. 1.1.1 Liouid Radwaste Effluent Line Monitors l (RM-L5, RM-L7, RM-L9) l Liquid Radwaste Effluent Line Monitors provide alarm and automatic termination of release functions prior to exceeding the concentration limits specified in 10CFR 20, Appendix B, Table II, Column 2 at the release point to the unrestricted area. To meet I l l 00CM, V C Summer, SOUTH CAROLINA ELECTRIC AND GAS CO. 1.0-1

1.1.1 Liouid Cadwaste Effluent Line Monitors (Continued) s this specification, the alarm / trip setpoints for liquid effluent monitors and flow measurement devices are set to assure that the following equation is satisfied: h <_ C x RF (1) where: C the effluent concentration limit (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 discharge, in uCi/ml. RF = the recirculation factor, determined by' system equilibrium calculations, used to assure that concentrations of effluents at the outfall do not exceed the effluent concentration limit, C. RF - 0.5. (Reference 6) the setpoint, in pCi/ml, of the radioactivity monitor measuring c - the radioactivity concentration in the effluent line prior to dilutien 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 l stream plus the effluent stream, represents a value which, if exceeded, would result in concentrations exceeding the limits of l 10CFR 20 in the unrestricted area. l l f the flow setpoint as determined at the radiation monitor = location, in volume per unit time, but in the same units as F, below. the dilution water flow retpoint as determined prior to the F = releMe point, in volume per unit time. ODCM, V C Summer, SOUTH CAROLINA ELECTRIC AND GAS CO. 1.0-2

At the Virgil C. Summer Nuclear Station the Liquid Waste Processing System and the Nuclear Blowdown System both discharge to the penstocks of the Fairfield Pumped Storage Facility through a common line. The available dilution water flow (Fdp) is assumed to be 90 percent of the flow through the Fairfield Pumped Storage Station penstock (s) to which liquid effluent is being.11scharged and is dependent upon operational status of the Fairfield Pumped Storage Station. The viaste tank flow rat,es (fdn' Idb and foc) and the monitor setpoints (c, c and c ) are set to meet the condition g B C of eouation (1) for a given effluent concentration, C. The three monitor I set;aints are indicative of the monitor system configuration for this discharge pathway. The LWDS discharges through RM-LS, which has setpoint cg for alarm / control functions over releases from either Waste Monitor Tanks 1 or 2. The Nuclear Blowdown discharges through RM-L7, which also has setpoint. cB for alann/ control functions over releases from the Nuclear Blowdown Tank. These two relear.e pathways merge into a common line monitored by RM-L9, which has setpoint c for control functions over the cor:non effluent line'. C The method by which this is accomplished is as follows: I 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 Technical Specifications Table 4.11-1: l EC$=IC +C +C +C (2) g a s t i g l where: C 4 the concentration of nuclide i as determined by the = analysis of the waste sample. ODCM, V C Summer, SOUTH CAROLINA ELECTRIC AND GAS CO. 1.0-3

C the sum of the concentrations C of eacn measured gamma g g emitting nuclide observed by gamma-ray spectroscopy of the waste sample. C* the measured concentrations C of olpha emitting nuclides = a a observed by gross alpha analysis of the monthly composite sample. I C* th? measured concentrations of Sr-39 and Sr-90 in liquid s waste as determined by analysis of the quarterly composite sample. I C* the measured concentration of H-3 in liquid waste as t determined by analysis of the monthly composite. The C term will be included in the analysis cf each batch; g terms for alpha, strontium, and tritium may be included as appropriate.. Isotopic concentrations for both the Waste Monitor Tanks and the Nuclear Blowdown Monitor Tank may be calculated using equation (2). 2) Once isotopic concentrations for either Waste Monitor Tank and/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 II, Column 2 are met at the point of discharge. Values for these concentrations will be based on previous coa.cosite sample analyses as required by Table 4.11-1 of the Radiological Effluent Technical Specifications. ODCM, V C Sumer, SOUTH CAROLINA ELECTRIC AND GAS CO. 1.0-4

DF = 5 I - -E C'. C + + SF x RF or (3) g -i MPC; 1 MPC .y -g_. ~' C C C C ~' ~ C C C C a

  • MPC + MPC + Mp

+ DF = + gpC + MPC P g g gp a s a s I + [SF x RF] (4) where: g C; the sum of the ratios of the mea,sured concentration of i MPC., nuclide i to its limiting value MPC; for the waste monitor ~ tank being considered fur release. I ~ C; - the sum of the ratios of the measured concentration of g i MPC j nuclide i to its limiting value MPC; for the Nuclear Blowdown -B Monitor Tank. MPC MPC, MPC, MPC, and MPCt - limiting concentrations j g a 3 of the appropriate gamma emitting, alpha emitting, and strontium radionuclides, and tritium, respectively, from 10CFR, Part 20, Appendix B, Table II, Column 2. SF the safety factor; a conservative factor used to compensate = l for statistical fluctuations and errors of measurements. 0.5, corresponding to a 100 percent variation. i 3) The maximum permissible discharge flow rate, f, may be calculated t for the release of either the WMT or NBMT or for the release of both tanks simultaneously. First the appropriate Dilution Factor is calculated by E E applying equation (3). If only one tank is being considered for discharge, calculate DF using the appropriate concentration ratio term I 1 (i.e. M or B) with the other concentration ratio term set equal to zero. If both tanks are to be discharged simultaneously, calculate DF with both concentration ratio terms included in equation (3). i 00CM, V C Sumner, SOUTH CAROLIriA ELECTRIC Afl0 GAS CO. 1.0-5 I

then do + Idm + Idb do F For Fdp " #dm' #db (5) t DF DF I where: F dilution flow rate based on Fairfield Pumped Storage Station dp operational status. The minimum dilution flow alarm setpoint (as described later in Step (4)) is established at 90 percent of expected dilution flow, F. T,herefore t I Fdp - (0.9) F (0) t I where F the flow rate through the Fairfield Pumped t Storage Statian penstock (s) to which radioactive liquids are being discharged. fdb flow rate of Nuclear Blowdown Monitor Tank discharge. (This = value normally will be either zero, if no release is to be conducted from this system, or the maximum rated capacity of the discharge pump (250 gpm) if a release is to be conducted.) fdm flow rate of Waste Monitor Tank discharge. (This value normally will either be zero, if no release is to be conducted from this system, or the maximum rated capacity of the discharge pump (100 gpm) if a release is to be conducted.) dilution flow rate from equation (6). F = dp ll l DF the Dilution Factor from Step 2. llI If ft>Idm + Idb, the release may be made as planned. Because F is normally very large compared to the maximum discharge pump dp capacities for the Waste Monitor Tank and the Nuclear Blowdown Monitor l l Tank, it is extremely unlikely that ft<Idm db. + However, H a situation should arise such that f # t dm db, steps must be taken to assure that equation (1) is satisfied prior to making the release. ODCM, V C Su rner, SOUTH CAROLINA ELECTRIC AND GAS CO. 1.0-6

These steps may include decreasing f by limiting the release dm db to one tank if both had been considered; by decreasing the flow rate of f rf or both; or by increasing F dm db dp' I Note that if DF < 1, the waste tank (s) concentration (s) for which the calculation is being performed includes safety factors in Step 2 and meet (s) the limits of 10CFR 20 without further dilution. I 4) Tne dilution flow rate setpoint for minimum flow rate, F, is established at 90 percent of the. expected dilution flow rate: (7) F= Fop - (0.9) F t Flow rate monitor setpoints for effluent streams may be set at the selected discharge pump rate (normally the maximum discharge pump rate or zero) for the case ft>Idm db. +I For the case ft<Idm db' the setpoint for the flow rate monitor under consideration n..st be determined from dp (8) f t DF applied for the alternative selected from the possibilities discussed above. 5) The radiation monitor setpoint may now be determined based on the I values of C,F and f which were specified to provide compliance with 4 I the limits of 10CFR 20, Appendix B, Table II, Column 2. The monitor response is primarily to gamma radiation, therefore, the actual setpoint is based on C. The monitor setpoint in cpm which corresponds to the g g particular setpoint concentration, c, is taken from the monitor calibration graph. (Example of monitor calibration graph is shown in Figure 1.0-1.) ODCM, V C Summer, SOUTH CAROLINA ELECTRIC AND GAS CO. 1.0-7

The setpoint concentration, c, is determined as follows: E g xA (9) c = g _ml _, Adfustment factor which will allow the setpoint to be A = established in a practical manner for convenience and to prevent spurious alarms, f a t (10) = fdm, db If A > 1, Calculate c and determine the m3ximum value for the actual monitor setpoint (cpm) from the monitor calibration graph. If A<1, No release may be made. Re-evaluate the alternatives presented in Steps 3 and 4. 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'setpcint may be calculated following the methodology presented in Steps 3 and 4 l for the case ft<Idm db'

  • I I

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: g x A (11) Cg-g -M ODCM, V C Summer, SOUTH CAROLINA ELECTRIC AND GAS CO. 1.0-P

NOTE: If no discharge is planned for this pathway, 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: B-g x A (12) C I -B NOTE: If no discharge is planned for this pathway, 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-L9, Combined Liquid Waste Processing System and Nuclear Blowdown Waste Effluent Discharge Line Monitor If a discharge is made from only one system, the monitor setpoint on the common line, c, should be the same as the setpoint for the c monitor on the individual discharge line (i.e., c, rc as M B determined above). If simultaneous discharges are made, c iS c determined as follows: -IC -. -EC -. - f g , f g dm _g _,g db.9 .B x A (13) cc" f + f dm db I NOTE: In all cases, c, c, and c are the setpoint values in g B c uCi/ml. The actual monitor setpoints (com) for RM-L5, RM-L7, and RM-L9 are determined from the calibration graph for the ( particular monitor. l l ODCM, V C Summer, SOUTH CAROLINA ELECTRIC AND GAS CO. 1.0-9 l

l 1.1.2 Detergent Waste Discharge Via Sanitary Waste System (RM-L5) In the Virgil C. Sum.er Nuclear Station liquid wasta effluent system design, there exists a mechanism for discharging detergent l wastes via the sanitary waste system. The sample point prior t.o l discha is normally Waste Monitor Tank No. 2. The analysis requirements are the requirements listed in the Radiological Effluent Technical Specifications, Table 4.11-1. This effluent pathway shall on'ly be used when the following condition is met: I 1 i (14) D - LLD where: -EC ~ the isotopic concentration of the detergent waste contained = 9 -D within the Waste Monitor Tank serving as the holding facility for sampling and analysis prior to discharge. the Lower Limit of Detection, (LLD), for the isotopic l E C. = I l i l - LLD concentrations of the Waste Monitor Tank as determined by the analysis required in the Radiological Effluent Technical Specifications, Table 4.11-1. When the conditions of equation (14) are met, the detergent \\ waste may be released via the Senitary Waste System pathway. There is no requirement to perform the Steps 2, 3, 4, or 5 of Section 1.1.1 if the conditions of equation (14) are met. 00CM, V C Summer, SOUTH CAROLINA ELECTRIC AND GAS CO. 1.0-10

f l l.1.3 Steam Generator Blowdown and Turbine Building Sump Effluent Lines (RM-L3,RM-L10,RM-L8) Concentrations of radionuclides in the liquid effluent discharges made via the Turbine Building Sump and Steam Generator Blowdown are expected to be very low or nondetectable. These releases are expected to be continuous in nature ano thus will be sampled in an appropriate manner as specified in Table 4.11-1 of the RETS. TheSteamGeneratorBlow$ownMonitorsandtheTurbine Building Sump Monitor provide alarm and automatic termination of release prior to exceeding'the concentration limits specified in 10CFR 20, Appendix B, Table II, Columri 2 at the release point to the unrestricted area. Both of these effluent pathways utilize the circulating water as dilution to the effluent stream with the circulating water discharge canal being the point of release into an unrestricted area. Equation (1) is again used to assure that effluents are in compliance with the aforementioned specification:

5. C x RF f

where c, f, F, C, and RF are the same generic terms discusseo in Section 1.1.1. l The common usage of the Circulating Water System for dilution of both the Steam Generator Blowdown and the Turbine Building Sump effluents is similar to the release mechanism utilized by the higher activity effluents in Section 1.1.1. The basic difference is that the two pathways do not merge into a single discharge line. Therefore, only individual pathways are monitored. I ODCM, V C Summer, SOUTH CAROLINA ELECTRIC AND GAS CO. 1.0-11

The available dilution water flow (Fdc) is dependent upon the mode of operation of the Circulating Water System. Any change in this value will be accounted for in a recalculation of equation (1). The Stean. Generator Blowdown flow rate (fds), the Turbine Building Sump flow rate (fdt), and the monitor setpoints (cSa' cSb, and c ) are also set to meet the condition of ecuation T (1). The three monitor setpoints corr,espond to the methodology of the two release pathways. RM-L8, the' Turbine Building Sump monitor alarms and terminates release upon exceeding the monitcr setpoint (c ). RM-L3, the first monitor in the Steam Generator Blowdown T discharge pathway, alarms and terminates release of the stream. The discharge is then manually diverted to the Nuclear Blowdown Processing System. RM-L10, the last monitor in the Steam Generator Blowdown discharge pathway, alarms and terminates the release. Thus, RM-L10 is basically redundant to RM-L3 and the setpoint (cSb) will be determined in the'same manner as RM-L3 (cSa). The r1: hod by which the monitor setpoints are determined is as fullows: I 1) The isotopic concentrations for either 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. Ecuation (2) is again employed for this calculation: ICg=EC +C +C +C g a s t 1 9 I ODCM, V C Summer, SOUTH CAROLINA ELECTRIC AND GAS CO. 1.0-12

where: fi 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 9 = g g emitting nuc1ide observed by gamma-ray spectroscopy of the waste sample. I the measured concentrations C of alpha emitting nuclides C 3 a observed by gross alpha analysis of the monthly composite sample. l C themeasuredconcentrationsohSr-89adSr-90inliquid s waste as determined by analysis of the quarterly ccaposite sample. C the measured concentration of H-3 in liquid waste as t determined by analysis of the monthly composite sample. Isotopic concentrations for both the Steam Generator Blowdown System effluent and the Turbine Bu11dir.g Sump effluent may be calculated using equation (2). i 2) Once isotopic concentratiens for either the Steam Generator Blowdown or the Turbine Building Sump have been determined, these values are used 1 to calculate a Dilution Factor, DF, which is the ratio of the total dilution flow rete to effluent stream flow rate (s) required to assure l that the limiting concentration of 10CFR, Part 20, Appendix 8, Table II, Column 2 are met at the coint of discharge. I -fgpf -fMP - C C DF = + SF x RF or (15) i ms 1-T_ C C C C ~ C C C C -' 9 a t I g a,"s ,"t g MPC + MPC,"s ,MPC 9 MPC ~ MPC i DF = -S g a s t g a 5 t -T_ + [SF x RF] (16) ODCM, V C Summer, SOUTH CAROLINA ELECTRIC AND GAS CO. 1.0-13

I wnere: C,C C, and C ; measured concentrations as defined in C g g a s t Step 1. Terms C, C, and C will be included in the a s t calculation as appropriate. ~ C ~ the sum of the ratios of the measured concentration of nuclide i g j i MPC for the Steam Generator Blowdown ~ j to its limiting value MPC$ effluent. e ~ C ~ the sum of the ratios of the measured concentration of nuclide i g j i MPC I j to its limiting value MPCj for the Turbine Building Sump -T effluent. MPC, MPC, MPC, and MPC are limWng concenkadons MPC 4 g a s t of the appropriate radionuclide from 10CFR, Part 20, Appendix B, Table II, Column 2 limits. the same generic term as used in Section 1.1.1, Step 2. SF 3) The maximum permissible effluent discharge flow rate, f, may be d calculated for a release from either the Turbine Building Sump or the Steam Generator Elowdown or releases via both pathways simultaneously. First the appropriate Dilution factor is calculated by applying equation is (J). For discharges via only one patnway, calculate DF using the I appropriate concentration ratio term (i.e. T or S) with the other concentration ratio term sat equal to zero. For simultaneous discharges, os calculate DF with both concentration ratio terms included in equation (/). I F dc

  • Idt
  • ds de dc " Ids ' #dt (17)

UI

  1. d' DF

~ ?7~ i l where: l F Dilution flow rate based on 90 percent of the expected flow rate dc l of the Circulating Water System during the time of release: - (0.9) Fg l l ODCM, V C Summer, SOUTH CAROLIt4A ELECTRIC Af4D GAS CO. 1.0-14 1

I f Flow rate of the Steam Generator Blowdown discharge. (This ds value normally will either be zero, if no release is conducted concurrently, or the maximum rated capacity of the discharge pump, if a release is conducted concurrently.) I dt Flow rate of the Turbine Building Sump discharge. (This value f normally will be either zero, if no release is being conducteo concurrently, or the maximum rated capacity of the discharge pump, if a release is being conduc,ted concurrently.) the Dilution Factor from Step 2. DF Note that the equation is valid only for DF > 1; for DF < 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 fd>fds + fdt, releases may be made as planned. Because F is n rmally very large compared to the maximum discharge pump dc capacities for the Turbine Building Sump and the Steam Generator Blowdown System, it is extremely unlikely that fd< Ids dt. +I However, if a situation should arise such that.fd<#s+ dt, steps must be d taken to assure that ecuation (1) is satisfied prior to making the release. These steps may include diverting Nuclear Blowdown to the Nuclear Blowdown Processing System, diverting the Turbine Building Sun.p output to the Excess Waste Holdup Tank or both. I 4) The dilution flow rate setpoint for minimum flow rate, F, is established at 90 percent of the expected dilution flow rate: I F=Fdc - (0.9) (F ) ( } d ODCM, V C Summer, SOUTH CAROLINA ELECTRIC AND GAS CO. 1.0-15

Flow rate monitor setpoints for effluent streams may be set at the selected discharge pump rate (normally the maximum discharge pump rate or zera) for the case fd> ds dt. For the case fd< Ids dt'

  • I the setpoint for the flow rate monitor under consideration must be determined from:

F fd"D (19) a-applied for the alternative selected to satisfy equation (1). 5) The inonitor setpoint may now be specified based on the values of I C, F, and f which were specified to provide compliance with the j 1 limits of 10CFR 20, Appendix B, Table II, Column 2. The monitor response is primarily to gamma radiation, therefore, the actual setpoint is based on IC. The monitor setpoint in com which corresponds to the g 9 calculated value c is taken from the monitor calibration graph. where: c= C xB (20) g Adjustment factor which will allow the setpoint to be B = j established in a practical manner for convenience and to prevent spurious alarms. f I ff (21) = fds dt i 1 ~ Calculate c and determine the maximum value for the actual If B > 1 monitor setpoint (com) from the monitor calibration graph. l If B < 1 No release may be made. Re-evaluate the alternatives presented [ in steps 3 and 4 I ODCM, V C Summer, SOUTH CAROLINA ELECTRIC AND GAS CO. 1.0-16

NOTE: If calculated setpoint values are near actual concentrations being released or planned for releass, it may te impractical'to set the monitor alarm at this value. In this case a new setpoint may be a calculated following the methodology presented in steps 3 and 4 for the case fd< Ids dt*

  • I I

Within the limits of the conditions st,ated above, the specific monitorsetpointsforthethreeliquidradiationmonitorsRM-L3,RM-L10, and RM-L8 are determined as follows: For RM-L3, Steam Generator Blowdown Discharge initial nonitor, and for RM-L10, Steam Generator Blowdown Discharge final monitor: Sa g xB (22) c or cSb " g -S Where -EC -' the isotopic concentration of the Steam Generator = g 9 Blowdown effluent as obtained from i.he sum of the -S measured concentrations determined by the analysis required in the Radiological Effluents Technical Specifications Table 4.11-1. I NOTE: If no discharge is planned for this pathway, the monitor setpoint should be established as close to background as i practical to prevent spurious alarms and yet alarm should an inadvertent release occur. ODCM, V C Summer, SOUTH CAROLINA ELECTRIC AND GAS CO. 1.0-17

For RM-L8, Turbine Guilding Sump Discharge Monitor: c

  • 9 T

g -T Where ~IC ~ The gamma isotopic concentration of the Turbine Building = g _9 _. T Sump effluent as obtained from the sum of the measured concentrations determined by the analysis required in I the Radiological Effluent's Technical Specifications Table 4.11-1. NOTE: If no discharge i planned for this pathway, the monitor setpoint should be established as close to background as practical to pravc.;t spurious alarms,and yet alarm should an inadvertent release occur. I I l { l oocs, v c Summer, Sour.9 caaounA Etmarc Ano cAS co. l.o_la

Figure 1.0-1 Example Calibration Curve for Liquid Effluent Monitor I I ! I ' j h1-E=wd h e !. M. +h.L i,, .._m ,. - rs_i btt 1 hi _

  • t.. _ T C_&p _~ e_ Y qp- - p gg -

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1 --.

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- w-~ .c m~ rin;m m m u = m '=' m p~= y h:n x*-.cu.

h h,.+ m r3

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q== =:=f=_^--'=' 'l; :,-~'H ~--

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. =p c 3

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  • '=h

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  • a e U 3 -, i 0

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  • r=--23---

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  • c -c ' -, ' - - -

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  • I q' I " '

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  • $'- - !# 5-((]-= N

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  • ITI-t # l-WM 'F-it LEE 4 f-Vl-

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  • T u a 7;- -.E4. i, = r_

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  • t I 4 E'LE-k =E V =-i- ^^tMLEE~. _4 M i f -WE N- =-Ni^M g,

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  • =,r c "" ' UM*T t -"

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p.._ u. m,_.v L.,

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  • r4 !' -
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.;ad..._i r-F brl-+l.rs#' - s4

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~r r

. :: r r-H ---. . __. -i -Y, h.T 172rd -' M_.. _" l -tm. M,.jQ M MiiI_h j JfW a ...2---q h _- t. " rf L: -i ~ k - z. t.' q1i a - : I". -. a. l'y- - + 75M iill-.42-{_. s- _ r r _. ?t j u. $ . J2'[, ,. - -- :m--y ; r - m --- : -. 1 M i, - -t.1 -F L-f{ J {.- 7_ ~ rT 3 2; 41 l 7.. l,1; :}.j Q. g.d,71 f u.. _..._, /.;."mq.7.1_.l.T S. p. -r.. .; n. .. 3 Id ._ __-... I'; [ -..{._[. .j_..__:n:- % ;_.ja._. r...d._7_i t. ' j _* 1 '***~ ': t. .. j. .f

  • T.

_ t.: -1 1 a.;;; m_:..._. { _._., _.m .u-;i.... t ,] T. l,' J I l' *G ! 4 ]*. C* U *.i.'~' l' 3 - #" ~{1.; ; ?.~T9'[17q" ' a,- -. ~ ~ .{...- -]..g 7.j +l-'. ~.e t 'A."..~: nl :. '..^l. !**Q '4' C.'. _4 UAT 1C i

  • 1*

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  • A.

om,- ^ ~ i..a e e a . 6....

TTr1, a...

,m a ' a a 1 10 10 10 1[ l ~ PD:R OR 8 NL CD3, V C Sumer, SOUTH CAROLINA ELECTRIC AND GA5 CO. 1.0-19

I 1.2 Dose Calculation For Liauid Effluents The dose contribution from all radionuclides identified in liquid effluents released to unrestricted areas is calculated asing the following expression: ~' m D =E A E At C F (24) i _ j7 g 9g g t=1 Where: D The cumulative dose commitment to the total body or any = organ, T, from the liquid effluents for the total time m period E at, in mrem (Reference 1). g E=1 the length of the Ith time period over which C and F are at = g $g g averaged for all licJid releases, in hours. C the average concentration of radionuclide, i, in undiluted $g liquid effluent during time period at from any licuid g release, in uCi/ml. the site related ingestion dose commitment factor to the total A = j 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. A =Kg ((U /D ) + UF 4 BF ) DF (25) I g g F the near field average dilution factor for C during any g jg 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 Z. (average undiluted liauid waste flow) (average flow 1 rom the disci.arge structure) x (Z) where: Z=1 aoplicable factor when no additional dilution is to be = considered. (Reference 1; Section 4.3) ODCM, V C Summer, SOUTH CAROL?NA ELECTRIC AfiD GAS CO. 1.0-20

I 0 units conversion factor 1.14 x 10 K g ((105 h) 3 x (10 ) + (8760 )) = F 21 kg/yr, fish consumption (adult). (Reference 3) U BF Bioaccumulation Factor for nuclide, i, in fish, pCi/Kg per pCi/1, from Table 1.2-1, (taken from reference 3, Table A-1). I DFj Dose conversion factor for nuclide, i, for adults in preselected organ, in mrem /pCi, from Table 1.2-2 (taken from reference 3, Table E-11). I U, 730 kg/yr, water consumption (adult). (Reference 3) e I 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) I I I ODCM, V C Summer, SOUTH CAROLINA ELECTRIC AND GAS CO. 1.0-21

I l TABLE 1.2-1 BI0 ACCUMULATION FACTORS (pCi/kg per pCi/ liter)* ELEMENT FRESHWATER FISH H 9.0E 01 C 4.6E 03 NA 1.0E 02 P 1.0E 05 CR 2.0E 02 MN 4.0E 02 l 1 FE 1.0E 02 C0 5.0E 01 NI 1.0E 02 CU 5.0E 01 ZN 2.0E 03 BR 4.2E 02 RB 2.0E 03 SR 3.0E 01 I Y 2.5E 01 ZR 3.3E 00 NB 3.0E 04 MO 1.0E 01 TC 1.5E 01 RU 1.0E 01 RH 1.0E 01 TE 4.0E 02 I 1.5E 01 l CS 2.0E 03 BA 4.0E 00 LA 2.5E 01 i CE 1.0E 00 PR 2.5E 01 ND 2.5E 01 W 1.2E 03 NF 1.0E 01

  • Values in Table 1.2-1 are taken from Reference 3, Table A-1.

I ODCM, V C Sumer, SOUTH CAROLINA ELECTRIC AND GAS CO. 1.0-22 I

TABLE 1.2-2 I Page 1 of 2 ADULT INGESTION DOSE FACTORS (mrem /pCi ingested) NUCLICE BONE LIVER T.80CY THYROID KIDNEY LUNG GI-LLI --=== - _==.........------ _ - - - - = H 3 NO DATA 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 C 14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.6eE-07 5.68E-07 NA 24 1.70E-06 1.70E-06

1. 70 E-0 6 1.70E-06 1.70E-06 1.70E-06 1.70E-06

__..- --___== -- =-- _ =.._ =..... P 32 1.93E-04 1.20E-05 7.46E-06 NO DATA NO DATA NO DATA 2.17E-05 CR 51 NO DATA NO DATA 2.66E-09 t,59E-09 5.86E-10 3.53E-09 6.69E-07 NN 54 NO DATA 4.57E-06

8. 72 E -0 7 NO DATA 1.36E-06 NO DATA 1

SE-05 = =_ -

==== ----. I MN 56 NO DATA 1.15E-07

2. 04 E-0 8 NO DATA 1.46E-07 NO DATA 3.67E-06 FE 55 2.75E-06 1 90E-06
4. 4 3 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

= -- - -._=_ _==- =.----- = CD 58 NO DATA 7.456-07 1.67E-06 NO DATA NO DATA NO DATA 1.51E-05 I CO 60 NO DATA 2.14F-06 4.72E-06 NO DATA NO DATA NO DATA 4.02E-05 N1 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-Od 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 1.546-05
6. 96 E-0 6 NO DATA 1 03E-05 NO DATA 9.70E-06

===. ---...... --= .==___ 2N 69 1.03E-08 1.97E-08 1.37E-09 NO DATA 1.28E-08 NO DATA 2.96E-09 BR 83 NO DATA NO DATA

4. 0 2 E-0 8 NO DATA NO DATA NO DATA 5.79E-08 BR 84 NO DATA NO DATA
5. 21 E -0 8 NO DATA NO DATA NO DATA 4.09E-13 NbDAT NO DATA LT E-24 BR 85 NO DATA NO DATA 2.14E-09 NO DATA RB 86 NO DATA 2.11E-05
9. 8 3 E -0 6 NO DATA NO DATA NO DATA 4.16E-06 I

R8 88 NO DATA 6.05E-08

3. 21 E-0 8 NO DATA NO DATA NO DATA 8.36E-19

_-.g. =_ RB 89 NO DATA 4.01E-08 2.82E-08 NO DATA NO DATA NO DATA 2.33E-21 SR 89 3.08E-04 NO DATA 8.84E-06 NO DATA NO DATA NO DATA 4.94E-05 SR 90 7.58E-03 NO DATA 1.86E-03 NO DATA NO DATA NO DATA 2.19E-04 I __ --=__ .=-

== - =---- ____ = -- SR 91 5.67E-06 NO DATA

2. 2 9E-0 7 NO DATA NO DATA NO DATA 2.70E-05 SR 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 2.58E-10 NO DATA NO DATA NO 04TA 1 02E-04 l

E Y 91N 9.09E-11 NO DATA

3. 52 T-12 NO DATA NO DATA NO DATA 2.67E-10 Y 91 1.41E-CJ 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 DATA NO DATA 1.48E-05 I

= Y 93 2.68E-09 NO DATA 7.40E-11 NO DATA NO DATA NO DATA 8.50E-05 ZR 95' 3.04E-08 9.75E-09 6.60E-09 NO DATA 1.53E-08 NO DATA 3.09E-05 ZR 97 1.68E-09 3.39E-10 1.55E-10 NO DATA 5.12E-10 NO DATA 1.05E-04 --== =- ..=__._ _ ----......-- ---.--- I NB 95 6.22E-09 3.46E-09

1. 86 E-0 9 NO DATA 3.42E-09 NO DATA 2.10E-05 MO 99 "' NO DATA 4.31E-06
8. 2 0E-0 7 NO DATA 9.76E-06 NO DATA 9.99E-06 TC 99m 2.47E-10 6.98E 8.89E-09 NO DATA 1.06E-08 3.42E-10 4.13E-07

... _==.---.-_....... --_-10-- =-... TC101 2.54E-10 3.66E-10

3. 5 9 E -0 9 NO DATA 6.59E-99 1.87E-10 1.10E-21 4U103 1.65E-07 NO DATA 7.97E-08 NO DATA 7.06E-C7 NO DATA 2.16E-05 RU105 1.54E-08 NU DATA'
4. 08 E-0 9 NO DATA 1.99E-07 NO DATA 9.42E-06
  • Values in Table 1.2-2 are taken from Reference 3, Table E-11.

I ODCM, V C Summer, SOUTH CAROLINA ELECTRIC AND GAS CO. 1.0-23

I TABLE 1.2-2 Pa0e 2 Of 2 ADULT INGESTION DOSE FACTORS (mrem /DCi ingested) l NUCLICE BONE LIVER T.800Y THY 90!O KIONEY LUNG GI-LLI I RU106 2.75E-06 NO DATA

3. 48 E-0 7 NO DATA 5.31E-06 NO LATA 1.78E-04 AG110M 1.60E-07 1 48E-07 8.79E-08 NO DATA 2.91E-07 NO JATA 6.04E-05 TE125M 2.69E-06 9.71E-07
3. 59 E-0 7 8.06E-07 1.09E-05 NC OATA 1.07E-05

__- -= TE127M 6.77E-06 2.42E-06

8. 25 E-0 7 1.73E-06 2.75E-05 P,0 DATA 2 27E-05 TE127 1.10E-07 3.95E-08
2. 3 8 E-0 8 8.15E-08 4.48E-07 NO DATA 8.68E-06 TE129M 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 7.6SE-09 -2.41E-08 1.32E-07 NO DATA 2.37E-08 I TE131M 1.73E-06 8.46E-07 7.0 5 E-0 7 1.34E-06 8.57E-06 NO DATA 8.40E-05 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 1.63E-06 1.5JE-06 1.8CE-06 1.57E-05 NO DATA 7.71E-05 1 130 7.56E-07 2.23E-06

8. 80E-0 7 1.89E-04 3.48E-06 NO DATA 1.92E-06 I 131 4.16E-06 5.95E-06
3. 41 E-0 6 1.95E-03 1.02E-05 NO DATA 1.57E-06

==-- _.... I 132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 NO DATA 1.02E-07 1 133 1.42E-06 2.47E-06

7. 53 E-0 7 3.63E-04 4.31E-06 NO DATA 2.22E-06 I

I 134 1.06E-07 2.88E-07 1.03 E-0 7 4.99E-06 4.58E-07 NO DATA 2.51E-10 1 135 4.43E-07 1.16E-06 4.2 SE-0 7 7.65E-05 1.86E-06 NO DATA 1.31E-06 CS134 6.22E-05 1.48E-04

1. 21 E-0 4 NO DATA 4.79E-05 1.59E-05 2.59E-06 CS136 6.51E-06 2.57E-05
1. 85 E-0 5 NO DATA 1.43E-05 1.96E-06 2.92E-06 I

CS137 7.97E-05 1.09E-04 7.14 E-0 5 NO DATA 3.70E-05 1 23E-05 2.11E-06 CS138 5.52E-08 1.09E-07

5. 40 E-0 8 NO DATA 8.01E-08 7.91E-09 4.65E-13 BA139 9.70E-08 6.91E-11
2. 8 4 E-0 9 NO )ATA 6.46E-11 3.92E-11 1.72E-07 I

==

SA140 2.03E-05 2.55E-08

1. 3 3 E-0 6 N0 DATA 8.67E-09 1.46E-08 4.18E-05 BA141
4. 71 E-08 3.56E-11 1.59E-09 NO DATA 3.31E-11 2.02E-11 2.22E-17 BA142 2.13E-08 2.19E-11
1. 34 E -0 9 NO DATA 1.85E-11 1.24E-11 3.00E-26 I

=- _=-- LA140 2.50E-09 1.262-09 3 33E-10 NO DATA NO DATA NO DATA 9.25E-05 LA142 1.28E-10 5.82E-11 1.45E-11 NO DATA NO DATA NO DATA 4.25E-07 CE141 9.36E-09 6.33E-09 7.18 E-10 NO DATA 2.94E-09 NO DATA 2.42E-05 I = - - _ __.___.-- = CE143 1.65E-09 1 22E-06

1. 35 E-10 NO DATA 5.37E-10 NO DATA 4.56E-05 CE144 4.A8E-07 2.04E-07
2. 62 E-0 8 NO DATA 1.21E-07 NO OATA 1.65E-04 PR143 9.20E-09 3.69E-09 4 56E-10 NO DATA 2.13E-09 NO DATA 4.03E-05

___.____________.= _- i = PR144 3.01E-11 1.255-11

1. 5 5E-12 NO DATA 7.05E-12 NO DATA 4.33E-18 N0147 6.29E-09 7.27E-09
4. 35E-10 NO DATA 4.25E-09 NO DATA 3.49E-05 4 197 1.03E-07 8.61E-08 3.01 E-0 8 NO DATA NO DATA NO DATA 2.82E-05 7

=- .= _=-===-

==- _= - _ _... = _ _ _=_... NP239 1.19E-09 1.17E-10

6. 4 5 E-1 1 NO DATA 3.65E-10 NO DATA 2.40E-05 11 l

l ODCM, V C Summer, SOUTH CAROLINA ELECTRIC AMD GAS CO. 1.0-24

TABLE 1.2-3 SITE RELATED INGESTION DOSE COMMITMENT FACTOR,# Ag, in mrem /hr per pCi/ml.

NUCL1DC: SONE : LIVER :

T. BODY : THYROID: MIDNCY : LUNG ! GI-LLI : N-3 l0.00E+00:8.96E+00:8.96C+00:8.96C+00:8.96C+00 9.96C+00:1.96C+00:

C-14
3.15E+04:6.30C+03:6.30E+03:6.30C+03:6.30C+03:6.20E+03:6.30C+03:
Na-24
5.48C+02:5.48E+02:5.48C+02:5.48C+02:5.48E+02:5.48C+02:5.48C+02:

P-32

4.62C+07:2.87C+C6:1.79C+06:0.00C+00:0.00E+00:0.00E+00:5.20E+06:

Cr-51 l0.00C+00:0.00Ct00:1.49C+00:8.94C-01:3.29C-#1:1.98C+00:3.76E+02: I . Mn-54 10.00E+00:4.76E+03:9.00E+02:0.00E+00:1.42C+03:0.00C+00:1.46E+04:

Mn-56 l0.00C+00:1.20C+02:2.12E+01:8.00E+es:1.52C+02:0.00E+00:3.82C+03:
Fe-55
8.87C+02:4.13E+02:1.43C+02:0.00C+00:0.00E+00:3.42C+02:3.52E+02:
Fe-59 l1.40C+03:3.29E+03:1.26E+03:0.00C+00:0.00C+P9:9.19E+02:1.10C+04:
Co-58 l0.00E+00:1.51C+02:3.39C+02:0.00E+00:0.00E+2h 0.00C+00:3.06E+03:

Co-60 10.00C+00:4.34C+02:9.56C+02:0.00C+00:0.00C+00:0.03C+00:8.16C+03:

Ni-63 14.19E+04:2.91C+03:1.41E+03:0.00C+00:0.00C+00:0.00C+00:6.07C+02:
Nt-65
1.70E+02:2.21E+01:1.01E+01:0.90C+00:0.00C+00:0.09C+90:5.61C+02:
Cu-64 10.00C+C0
1.69C+01:7.93C+00:0.00C+00:4.26E+01:0.00C400:1.44C+03:

2n-65 l2.36E+04:7.50C+04:3.39E+04:0.00C+00:5.02C+04:0.00C+00:4.73C+04: 2n-69 15.02C+01:9.60C+01'6.67C+00:0.00C+00:6.24C+01:8.00C+00:1.44C+01:

Br-83 l0.00C+00:0.00C+00:4.57C+01:0.00C+00:0.00C+00:8.00C+00:6.30C+01:

BP-84 l0.00C+00:0.00C+00:5.67C+01:0.00L+00:0.00E+00:0.00E+00:4.45E-04: Be-05 l0.00C+00:0.00E+00:2.33E+00:0,00C+00:0.00C+00:0.00C+00:1.09E-15:

RD-86 l0.00C+00:1.03C+05:4.79E+04:0.00C+00:0.00C+00:8.00C+00:2.03E+04:

Ro-88 l0.00C+00:2.95C+02:1.56C+02:0.00C+00:0.00C+00:0.00E+00:4.07C-09:

R3-39 l0.00C+00:1.95C+02:1.37C+02:0.00C+00:0.00C+e0:0.00C+00:1.13C-11:
SP-89
4.78C+04:0.00C+00:1.37E+03:0.0PI+00:0.00C+00:0.00C+00:7.66E+03:

SP-90 l1.18C+06:0.00C+00:2.88C+05:0.00C+00:0.00E+00:0.00C+00:3.40E+04: SP-91 8.79E+02:0.00C+00:3,55C+01:0.00C+00:0.00E+00:0.00C+00:4.19t+93: I

Sr-92
3.33E+02:0.00C+00:1.44E+01:0.00E+e0:0.00Ee00:0.00E+EQ:6.60E+03:

Y-90

1.30C+00:0.00E+00:3.69C-02:0.00E+00:0.00Et00:0.00C+00:1.46C+04:

Y-91m

1.30E-02:0.00C+00:5.04C-04:0.00C+00:9.00E+00:0.00C+00:3.82E-02:
Y-91
2.02C+01:9.00C+00:5.39E-01:0.T2E+00:0.00E+00:0.00C+00:1.11C+04:
Y-92
1.21C-01:0.00C+00:3.53C-03:0.6JC+00:3.00C+00:0.00E+00:2.12C+03:
Y-93
3.83C-01:0.00C+00:1.06C-02:0.00C+00:0.00C+00:0.00C+00:t.22C+04:

2r-95 12.77E+00:8.88C-01:6.01E-01:0.00E+00:1.39C+00:0.00E+00:2.62C+03: 2r-97

1.53C-01:3.09C-02:1.41C-02:0.00E+00:4.67C-02:0.00C+00:9.57E+03:
hn-95 14.47C+02:2.49C+02:1.34C+02:0.00C+00:2.46E+02:0.00E+00:1.51C+06:
No-99 l0.00E+00:4.62C+02:8.79C+01:0.00C+00:1.05C+03:0.00C+00:1.07C+03:

Tc-99s :2.94C-02:8.32E-02:1.0CC+00:0.00C+00:1.26C+00:4.07C-02:4.92C+01:

Tc-101 13.03E-02:4.36E-02:4.20C-01:0.00C+00:7.85C-01:2.23C-02:1.31C-13:

Ru-103 11.90C+01:0.00C+00:8.54C+00:0.00C+00:7.57C+01:0.00E+00:2.31E+03:

Ru-105 1.65C+00:0,00C+00:6.52C-01:0.00E+00:2.13C+01:0.00C+00:1.01E+03:

Ru-106 2.95C+02:0.00C+00:3.73C+01:0.00C+00:5.69C+02:0.00E+00:1.91C+04: Ag-110m:8.82E+00:1.23C+01:7.32C+00:0.00C+00:2.42E+01:0.00C+00:5.03C+03:

Te-125m:2.79C+03:1.01E+03:3.74C+02:8.39C+02*1.13E+04:0.00C+00:1.11C+04:

7e-127m:7.05E+03:2.52C+03:8.59C+02:1.80C+03:2.86C+04:0.00C+00:2.36E+04: Te-127 11.14C+02:4.11E+0*:2.48E+01:8.40C+01:4.66C+02:0.02C+00:9.03C+03:

Te-129m:1.20C+04:4.47C+03:1.89C+03:4.11C+03:5.00C+04:0.00E+00:6.03C+04:

Te-129 3.27E+01:1.23E+01:7.96E+00:2.51C+01:1.37t+02:9.00E+00:2,4/E+01:

Te-131m:1.80E+C3:8.81C+02:7.34C+02:1.39C*e3:8.92C+03:0.00E+00:8.F4C+04:
.Ye-131 :2.05E+01:8.57C+es:6.47C+00:1.69E+0118.98C+01:0.00C+00:2.90C+00:

Te-132 l2.62C+03:1.70C+03:1.59C+03:1.87C+03:1.63C+04:0.00C+00:8.02C+04: I 1 1-130 19.01E+01:2.66C+02:1.05E+02:2.25E+04:4.15E+02:0.00C+00:2.29C+02: I-131

4.96C+02:7.09C+02:4.06C+02:2.32E+05:1.22C+03:0.00C+00:1.87C+02:

I-132 l2.42C+01:6.47C+01:2.26E+E1:2.26E+03:1.03C+02:0.00E+00:1.22C+01: I-133 11.69E+02:2.94E+02:8.57C+01:4.32E+04:5.13C+02:0.00C+00:2.64C+01. I-134

1.26E+01:3.*3C+01:1.23C+01:5.94C+02:5.46E+01:0.00E+00:2.99C-02:

I-135 15.20C+01:1.30E+02:5.10C+01:9.11C+03:2.22C+02:0.00C+00:1.56C+02: l l Cs-134 13.03E+05:7.21E+05:5.89C+L5:0.00C+00:2.33C+05:7.75E+04: 1.26E+04: i

Cs-136 : 3.1 'E + 04 : 1.25C+05:9.0:C+04:8.00E+00:6.97C+04:9.55E+03:1.42C+04:

) Cs-137 3.89E+05:5.31E+05:3.48C+05:0.00E+00:1.00E+05:5.99E+04: 1.03C+04:

Cs-138 :2.6dJ'02:5.31E+02:2.63E+02:0.00C+00:3.90E+02:3.85C+01:2.27C-03:

Ba-139 9.00E+00:6.41E-03:2.6(E-01:0.00C+00:5.99E-03:3.64C-03:1.60C+01: Ba-140 l1.88E+03:2.37E+00:1.23E+02:0.00C+00:8.05E-01:1.35C+00:3.80C+03: Ba-141 l4.37E+00:3.30C-03:1.48E-01:0.00E+00:3.37E-03:1.07C-03:2.06C-09: Ba-142 11. 9 BC+ 00 : 2. 03C-03 : 1. ?4 C- 01 : 0. 0 0E+00 : 1. 7 2C-0 3 : 1.15 E-03 : 2. 7eC-t e : . I La-140 13.5BC-01:1.80E-01:4.76C-02:3.00C+65:0.00C+00:0.00E+00:1.32C+04: La-142 :1.83C-02:8.33C-03:2.07E-03:0.00E+00:0.00E+00:3.00C+00:6.0GC+01 l Ce-141 :8.01E-01:5.42C-01:6.15C-02:0.POC+00:2.52C-01:0.00C+00:2.07C+03:

Cd-143 :1.41C-01:1,04C+02:1.16C-02:0.0-T+00:4.60C-02:3.00E+00:3.90E+03:

Ce-144 :4.18C+01:1.75E+01:2.24C+00:0.00J+00:1.04E+01:0.00C+00:1.41C+04: I Pr-143 1.32C+00:5.28C-01:6.52E-02:0.00C+00:3.05C-01:0.00C+00:5.77E+03: Pr-144 ;4.31E-03:1.79E-03:2.19E-04:0.00C+00:1.01C-03:0.00C+00:6.19E-10; Ha-147 l9.00C-01:1.04E+00:6.22C-02:0.00E+00; 00E-01'0.00C+00:4.99C+03:

W-187
3.04E+02:2.55C+02:9.90E+01:0.00C+00:.00C+00:0.00E+00:8.34C+04:

I 10-239'l1.20C-01:1.25C-02:6.91C-03:0.00C+00:3.91E-02:3.00E+00:2.57E+03: {

  • Calculated using equation (25).

r ODCM, V C Summer, SOUTH CAROLINA ELECTRIC AND GAS CO. 1.0-25 P00R OR GINAL

I 1.3 Definitions of Liquid Effluent Parameters Term Definition Section of Initial Use j7 the site related ingestion dose commitment factor to the 1.2 A total body or any organ T for each identified principal gama and beta emitter listed in Table 1.2-3 in mrem-ml per br-uCi. 8 Bioaccumulation Factor for nuclide i, in fish, 1.2 74 pCi/Kg per pCi/1, from Table 1.2-1. the effluent concen'.-ation limit (Specification 3.11.1.1) 1.1.1 C implementing 10CFR 20 for the site, in uCi/ml. the effluent concentration of alpha emitting nuclides 1.1.1 C a observed by gross alpha analysis of the monthly composite sample. C,y the effluent concentration of a gamma emitting nuclide, g, 1.1.1 observed by gamma-ray spectroscopy of the waste sample. Cj the concentration of nuclide, i, as determined by the 1.1.1 analysis of the waste sample. Cjg the average concentration of radionuclide, 1, in 1.2 undiluted liauid effluent during time periosi at g from any liquid release, in uCi/ml. C the concentration of Sr-89 or Sr oD in liquid wastes 1.1.1 l s = as determined by analysis of the quarterly composite sample. l C the measured cor. centration of H-3 in liquid waste 1.1.1 t as determined by analysis of the monthly composite. ) i I ODCM, V C Summer, SOUTH CAROLINA ELECTRIC AND GAS C0. 1.0-26

Term Definition Section of Initial Use the setpoint, in uCi/ml, of the radioactivity moniter 1.1.1 c = measuring the radioactivity concentration in the effltant line prior to dilution and subsequent release. the monitor setpoint for RN-L7, tha Nuclear Blowdown 1.1.1 c = B Monitor Tank discharge line monitor. the monitor setpoint for RM-L9, the coa.bined Liquid Waste 1.1.1 cC = Processing System and Nuclear Blowdown System effluent discharge line monitor. the monitor setpoint for RM-L5, the Waste Monitor Tank 1.1.1 c = I M discharge line monitor. the monitor setpoint for RM-L3, the initial Steam 1.1.3 c = 33 Generator Blowdown Effluent line monitor. the monitor setpoint for RM-L10, the final Steam Generator 1.1.3 c3g Blowdown Effluent line monitor. I the monitor setpoint for RM-L8, the Turbine Building Sump 1.1.3 c = T Effluent line monitor. DF a dose conversion factor for nuclide, i, for adults in 1.2 = j preselecteo organ, T, in mrem /pCi found in Table 1.2-2. the cumulative dose commitment to the total body or any 1.2 D = organ, T, from the liquid effluents for the total time period. DF the dilution f actor, which is the ratio of the total 1.1.1 = dilution flow rate to the effluent stream flow rate (s) required to assure that the limiting concentration of 10CFR, Part 20, Appendix B, Table II, Column 2 are met at the point of discharge. 00CM, V C Sumer, SOUTH CAROLINA ELECTRIC AND GAS C0. 1.0-27

l l Term Definition Section of Initial Use Dilution Factor from the near field area within one-quarter 1.2 D, mile of the release points to the potable water intake for adult water consumption; for V. C. Summer, D, - 1. the dilution water flow setpoint as determined prior to 1.1.1 F the release point, in glume per unit time. the flow rate of the Circulating Water System during the 1.1.3 F d time of release of the Turbine Building Sump and/or the Steam Generator Blowdown. F the dilution flow rate of the Circulating Water System upon 1.1.3 dc which the setpoint is 'aased: 90 percent of F *d the flow rate of water through the Fairfield Pumped St ge 1.1.1 F t Station penstock (s) to which radioactive liquids are being discharged during the period of effluent release. This flow rate is dependent upon operational status of Fairfield Pumped Storage Station. f the flow setpoint as determined for the radiation monitor 1.1.1 location. i F the dilution f low rate (through the penstock (s) receiving 1.1.1 dp the radioactive licuid release) upon which the setpoint is based: 90 percent of F

  • t F

the near field average dilution factor for C g jg during 1.2 any liauid effluent release. i f the flow rate of the \\oclear Blowdown Monitor Tank 1.1.1 db discharge, f the flow rate of the combined Waste Monitor Tank and 1.1.1 dc Nuclear Blowdown Monitor Tank discharge. I \\ ODCM, V C dummer, SOUTH CAROLINA ELECTRIC AND GAS CO. 1.0-28

Term Definition Section of Initial Use dm the flow rate of a waste monitor tank discharge 1.1.1 t f the flow rate of the Steam Generator Blowdown discharge. 1.1.3 ds f the flow rate of the Turbine Building Sump discharge. 1.1.3 = dt 5 k 1.14 x 10, units conversion factor. 1.2 g MPC MPC, MPC, MPC, and MPCt - the '.imiting concen-1.1.1 j g 3 s trations of the appropriate gamma Nitting, alpha emitting, and strontium radionuclides and tritium, respectively, from 10CFR, Part 20, Aopendix B, Table II, Column 2. RF the recirculation factor, determined by system 1.1.1 = equilibrium calculations, used to assure that concentrations of effluents at the outfall do not exceed the effluent concentration limit, C. RF - 0.5. SF the safety factor, a conservative factor used to 1.1.1 = compensate for statistical fluctuations and errorr of measurements. SF - 0.5, corresponding to a 100 percent variation. -EC -' the sum of the measured radionuclide concentrations 1.1.1 9 -i -B of the Nuclear Blowdown Monitor Tank. -EC ~ g the sum of the measured radionuclide concentrations 1.1.2 = -i -D of the detergent waste in a Waste Monitor Tank to be dis-chargui via the Sanitary Waste System. EC the sum of the Lower Limits of Detection, LLD, for 1.1.2 j = 1 -LLD the isotopic concentrations of the Waste Monitor Tank as determined by the analysis required in the Radiological Effluent Technical Specifications, Table 4.11-1. ODCM, V C Summer, SOUTH CAROLINA ELECTRIC AND GAS CO. 1.0-29

Term Definiticn Section of Initial Use C-the sum of the measured radionuclide concentrations 1.1.1 -M 'or a Waste Monitor Tank. -I C.' the sum of the measured radionuclide concentrations 1.1.3 I -I -i -S for the Steam Generator Blowdown. -IC-the sum of the. measured radionuc,lide concentrations 1.1.3 4 -T for the Turbine Building Sump.- I -E i-the sum of tne ratios of the measured concentration 1.1.1 i MPCi of nuclide i to its 1imiting value MPC for the j Nuclear Blowdown ilonitor Tank. -E C -' the sum of the ratios of the measured concentration 1.1.1 4 I MPC of nuclide i to its limiting value MPC$ for the j-" Waste Monitor Tank being considered for release. -E C - the sum of the ratios of the measured concentration 1.1.3 4 I MPC of nuclide i tc its limiting value MPC for the I j -S Steam Generator Blowdown Effluent. [I-C - the sum of the ratios of the measured concentration 1.1.3 4 i MPC of nuclide i to its limiting value MPC for the 4-Turbine Building Sump Effluent. g 21 kg/yr, fish consumption (adult). 1.2 U p applicable f actor when no additional dilution is to be Z be considered; Z - 1. 1.2 730 kg/yr, water consumption (adult). 1.2 U, ODCM, V C Summer, SOUTH CAROLINA ELECTRIC AND GAS CO. 1.0-30

1.4 Liquid Radwaste Treatment Systen. Figure 1.4-1 Minimum OPERABLE Liquid Radwaste Treatment System a l'2gs; 28?: 22 := ld? Si gjl! 5555o si 7 1813 4 151* .:s; s:gs: 2 g e, 5i! !!A 4 l= 3 ii i 3 !!= = &;= s= a a s 3%

S ;= c;
= ;e "e c

a 3 =cg; si = a g g-c a-i M.,.> 1 =! 3 -4' t j', a l ir a .a -#s: gE -(c =P r E -s; -): -so 1 a-

==.2 533:s ={t teI ja: = g* =* =2 g: e

== I g. ag e r--- j.--r-,1 l=---l [ ~ - <R l =----l !! l ,.y

ssa

" L _ _. I ess: sem-a. s i $l"S 4 -33 sim g 7 1 k 3 s s 4,* 4,* s"3, R, a-c- g g = = s d i i T I l ,I I l 1 i I g a a a a a aE a a u8 s a !!R 2 ij E i3 33

B

=

g-1o
5
5 ca.

ca. c cg c= _z = =

==

s. a-

= = I = = = u = I T i ~ l .____a l l

a.. -- __ __ _ J

+ .r... l.--r--l 1.--r--l 1 .c--l 5 g [. --,1 = T

  • -+

I ,__J 1P 9P J 9P l I

g?

e a l 23

22 s2

-o l "om = o:: m "o'o l , w aa t;" !?

ng
2

=5 I i k, i2 e n*, ~, i 3 9 7 i = A ce"8 a

=Eg

= a I 2-i si. 1.0-31 g ~ 1 I

i 2.0 GASE0US EFFI'JENTS 2.1 04seous Effluent Monitor Setpoints The calculated setpoint values will be regarded as upper bounds for 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. 2.1.1 Station Vent Noble Gas Monitors For the purpose of implementation of section 3.3.3.9 of the Technical Specifications, tne alarm setpoint level for the station vent noble gas monitors will be calculated as follows: S count rate of the plant vent noble gas monitor = y l (S = RM-A3) or the containment purge noble gas yp monitor (Svc - RM-A4) at the alarm setpoint level count rate. 0.25 x RtxDTB (1) - the lesser of < or s x Dss (2) 0.25 x R the safety factor applied to each of the two vent 0.25 noble gas monitors (plant vent and containment purge) to assure that the sum of the releases has a I combined safety factor of 0.5 which allows a 100 percent margin for cumulative uncertainties of measurements. Dose rate limit to the total body of an individual D = TB in an unrestricted area required to limit dose to 500 mrem in one year. 500-F[(X/Q)fK li ] (3) = j (1-F) ODCM, V C Summer, SOUTH CAROLINA ELECTRIC AND GAS CO. 2.0-1

R count rate per mrem /yr to the total body C+((X/Q)fKjQ) (4) 4 count rate of a station vent monitor corresponding C to grab sample radionuclide concentrations. (For tha plant vent the sample is taken concurrently with the release, For the containment purge, the sample is taken prior to the release and the count rate cor:.sgcading to the measured concentration is determined from the monitor calibration curve.) 3 5.3 x 10 sec/m in the SE sector

  • X/Q total body dose factor due to gamma emissions from K

j 3 isotope i (mrem /yr per uCi/m ) from Table 2.1-1. I Q rate of release of noble gas radionuclide 1 = 4 (uCi/sec) fraction of current year elapsed at the time of the F = calculation. average rate of release of noble gas radionuclide i Qj for the elapsed fraction of the year, F, (uCi/sec). I Dose rate limit to the skin of the body of an O ss i indheidual in an unrestricted area required to limit dose to 3000 mrem in one year. 3000-F[(X/Q)f(Lj + 1.1 M ) Q$] = j (5) '.1 - F ) il I R count rate per mrem /yr to the skin = s

  • Reference 4, Section 11.3.8.

ODCM, V C Summer, SOUTH CAROLINA ELECTRIC AND GAS CO. 2.0-2

I ~ X/Qf(Lj + 1.1 M ) Q4 (6) C+ = j I L skin dose factor due to beta emissions from isotope = j i (mrem /yr per uCi/m ) from Table 2.1-1. 1.1 mrem skin dose per mrad air dose j air dose factor due to gama emissions from isotope M = 3' 1 (mrad /yr per uC1/m ) from Table 2.1-1. 2.1.2 Waste Gas Decay System The setpoint level for discharge through the waste gas decay system monitor (Sd - RM-A10) will be calculated in a corresponding manner: 0.25 x rt x D'TB (7) the lesser of < Sd or 0.25 x r s x D'ss (8) D'TB 500-(F(X/Q)fK q) = j j [g) (1-F) c + (X/Q f Kj gj) (10) r = t count rate of the waste gas decay system monitor c for radionuclide concentrations to be discharged. rate of release of noble gas radionuclide 1 gj (uCi/sec) from the waste gas decay system. ii average rate of release of noble gas radionuclide i j from the waste gas decay system for the elapsed fraction of the year, F, (uCi/sec). ODCM, V C Summer, SOUTH CAROLINA ELECTRIC AND GAS C0. 2.0-3

R u D'ss 3000 - F [(X/Q) f (Lj+].]M)%] = j (1-F) { c + [ X/Q f (Lj + 1.1 M ) g ] (12) r = j j s NOTE: For planned releases from the waste gas decay system, calculations may first be performed assuming maximum flow from the system. If this calculation results in an unacceptable release rate,q must be controlled by limiting the flow rate trom the system. Due to the 0.25 safety factor in equations (1) and (2), the release rate also must be controlled such that the ratio of dose rate limit (D'TB U" D'ss) to the dose rate which would result from the planned release (X/Q f K q$ ) or,[ X/Q f (L; + 1.1 M ) g ] j j j is greater than four (4). Also, a setpoint calculation should be performed for the plant vent monitor (RM-A3) incorporating the waste gas decay system planned relase rates with the existing plant vent release rates to determine whether the plant vent monitor setpoint should be adjusted. When no discharges are being made from the Waste Gas Decay System, the monitor setpoint should be E.stablished as near background as practical to prevent spurious alarms yet l alarm in the event of an inadvertent release. ODCM, V C Sommer, SOUTH CAROLINA EI.ECTRIC AND GAS CO. 2.0-4

2.1.3 Alternative Methodologies for Establishing Conservative Setooints: Alternate 1: For ease of implementation, the count rate setpoints may be calculated by applying the methodologies presented in sections 2.1.1 and 2.1.2 with the more restrictive assumption of continuous release at the limiting rate for a year as follows: 500 mrein/ year (13) DTB D"TB 3000 mrem / year (14) D D"ss ss Alternate 2: A more conservative setpoint may be calculated to minimize requirements for adjustment of the monitor as follows: 500 mrem / year (15) DTB D"TB 3000 mrem / year (16) D D"ss ss conservative count rate per mrem to the total body R t (Xe-133 detection, Kr-89 dose). C' + [XTQ x K x Q"], where (17) = Kr-89 Assigned value of, for example,1.0 uCi/sec, Xe-133; Q" or, if necessary, i more practical value. (See definition of C' below.) l l ODCM, V C Summer, SOUTH CAROLINA ELECTRIC AND GAS C0. 2.0-5

C' count rate of the vent monitor for an effluent concentration of Xe-133 corresponding to a 1.0 uCi/sec release rate of Xe-133. [ Note: Calculate the related concentration based on dilution flow.] If the concentration corresponding to a release rate of 1.0 pCi/sec of Xe-133 is not compatible with the calibration curve for the particular monitor, a compatible release rate may be selected. Kr total body dose factor for Kr-89, the most K restrictive isotope from Table 2.1-1. I conservativecountratepermremIyrtotheskin. R's = C' [XTQx(LKr-89 + 1*1 NKr-89) x Q"] (18) where: LKr skin dose factor for Kr-89, the most restrictive isotope, from Table 2.1-1. MKr air dose factor for Kr-89, the most restrictive isotope, from Table 2.1-1. Similarly for the waste gas decay system: conservative count rate per mrem /yr to the total r' t body for the waste gas decay system only. c' + [FQ x K x q"], where (19) Kr-89 Count rate of the waste gas decay system monito.- c' corresponding to, for example, a 1.0 uCi/ml concentra-tion of Kr-85. If this concentration is incompatible with the calibration curve for the particular monitor, a compatible concentration may be selected. l release rate from the waste gas decay system (may q" be determined for maximum flow from the system and the concentration selected for c' above). ODCM, V C Summer, SOUTH CAROLINA ELECTRIC AND GAS CO. 2.0-6 l

r' conservative count rate per mrem /yr to the skin for s waste gas decay system only. c' + [I/-Q x (LKr-89 + 1*1 MKr-89) x q"] (20) / r* I I ODCM, V C Summer, SOUTH CAROLINA ELECTRIC AND GAS CO. 2.0-7

TABLE 2.1-1 DOSE FACTORS FOR EXPOSURE TO A SEMI-INFINITE CLOUD OF N0BLE GASES,*

Nuclide, y-Body *** (K) 8-Skin ***(L) y-Air **(M) 8-Air **(N)

Kr-85m 1.17E+03+*** 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+01 1.34E+03 1.72D01 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 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11E+03 Xe-133m 2.51E+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+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 Xe-138 8.83t'+03 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03 1 I l

  • Values taken from Reference 3, Table B-1
    • mrad-m3 l

uCi-yr

      • mrem-m3 uCi-yr
        • 1.17E+03 - 1.17 x 103 ODCM, V C Summer, SOUTH CAROLINA ELECTRIC AND GAS CO.

2.0-8

2.2 Gaseous Effluent Dose Calculations 2.2.1 Unrestricted Area Boundary Dose 2.2.1.a For the purpose of implementation of section 3.11.2.1.a of the Technical Specifications, the dose at the unrestricted area boundary due to noble gases shall be calculated as follows: average total body dose rate in the current year D t (mrem /yr) fK Q (21) X/Q = 9 9 average skin dose rate in current year (mrem /yr) D = s X/Qf(L9+1.1M)79 (22) = 9 2.2.1.b Organ doses due to radioiodines 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 section 3.11.2.1.b as follows: average organ dose rate in the current year (mrem /yr) D g WfP Q ', where (23) = 9 9 l l controlling sector annual average atmospheric W dispersion at the site boundary for the appropriate pathway. ' FQ for inhalation and all tritium pathways (Section 2.1.1) (24) l

  • i D/Q-2.0 x 10-8
  • for other pathways in the NE sector (25)
  • Value based on Reference 5, Table 6.1-13.

ODCM, V C Sumer, SOUTH CAROLINA ELECTRIC AND GAS CO. 2.0-9

P dose parameter for radionuclide i, (mrem /yr per 3 2 uCi/m ) for inhalation and (m -mrem /yr per uCi/sec) for other pathways, from Table 2.2-1 average release rate of radionuclide 1 (required by Qj' = Technical Specification 3.11.2.1.b) in the current year (uCi/sec). 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: I air dose due to gamma emissions from noble gas D radionuclide 1 (mrad) 3.17 x 10-8 M X/Q' Q (26) = g

where, 3.17 x 10 the fraction of one year per one second E' -

relative concentration for unrestricted areas for long term releases 3* 2.8 x 10 sec/m, in the ESE sector cumulatfie release of noble gas radionuclide i over Q the period of interest (uCl). air dose due to beta emissions from noble gas O g radionuclide 1 (mrad).

  • Values based on Reference 4, Table 2.3-119; Reference 5, Table 6.1-10.

ODCM, V C Summer, SOUTH CAROLINA ELECTRIC AND GAS CO. 2.0-10

3.17x10-0fN X/Q'hj,where (27) = 9 air dose factor due to beta emissions from noble gas N g radionuclide 1 (mrad /yr per uCi/m from Table 2.1-1.) 2.2.2.b Dose to an individual from radioiodines and radioactive materials in particulate form,and radionuclides (other than no'olegases) with half-lives greater than eight (8) days will be calculated for the purpose of implementation of section 3.11.2.3 of the Technical Specifications as folitas: dose to an individua'l from radiciodines and D, radionuclides in particulate fonn, and radionuclides (other than noble gases) with half-lives greater than eight (8) days (mrem). W' h, where (28) 3.17 x 10-8 R = 9 4 W' relative concentration or relative deposition for unrestricted areas. i (2.8 x 10-6)*sec/m3 for inhalation (29) X/Q' = and all tritium pathways. (8.8 x 10-9)*m-2 for other pathways (30) D/Q' in the ESE sector. IT/U' relative deposition for unrestricted areas = per unit area (n.2)-1, for long term releases. 3 j dose factor for radionuclide i, (mrem /yr per uCi/m ) or R = 2 l (m - mrem /yr per uCi/sec) from Table 2.2-2.

  • Values based on Reference 4, Table 2.3-119; Reference 5, Table 6.1-10.

ODCM, V C Summer, SOUTH CAROLINA ELECTRIC AND GAS CO. 2.0-11

Q' Cumulative release of radionuclide 1 (required by 4 Technical Specification 3.11.2.3) over the period of interest (uCi). 2.2.2.c For the purpose of implementing section 6.9.1.13 of the Technical Specifications, dose calculations will be performed using the above equations with the substitution of average meteorological parameters for the period of the report. Values for R$ may be found in Tables 2.2-3 through 2.2-6. I I I I ODCM, V C Summer, SOUTH CAROLINA ELECTRIC AND GAS CO. 2.0-12 - _.... ~. -,_...

TABLE 2.2-1 ' E PATHWAY DOSE FACTORS FOR SECTION 2.2.1.b (P )0 E (For Dose Calculation Required by TS 3.11.2.g ) 1 Pane 1 of 3 AGE GROUP t INFANT $ ( H.A. ) ( INFANT )

ISOTOPE:

INHALATIONb' GROUND PLAN F00h l I lH-3 6.468E+02 0.000E+00 2.430E+03 I lC-14 2.646E+04 0.000E+00 l 2.340E+09 INA-24 1.056E+04 l 1.979E+07 1.542E+07 P-32 2.030E+06 0.BOBE+00 1.602E+11 lCR-51 1.284E+04 7.864E+06 4.700E+06 I MH-54 9.996E+05 1.287E+09 3.900E+07 l-I lMN-56 7.tG8E+04 l 1.525E+06 2.862E+00 lFE-55 8.G94E+04 0.000E+00 l 1.351E+08 lFE-59 l 1.015E+06 4.562E+08 3.919E+08

CO-58 7.770E&C3 6.194E+08 6.055E+07 I
CO-60 4.508E+06 5.172E+09 l

2.098E+08 l-I 'NI-63 3.388E+05 0.000E+00 3.493E+10 NI-65 5.012E+04 4.930E+05 3.020E+01 l lCU-64 l 1.498E+04 9.823E+0S 3.807E+06 5

ZN-65 6.468E+05 7.907E+08 l

1.904E+10 I

2N-59 1.322E+04 0.000E+06 3.C55E-09 i

lBR-93 3.808E+02 1.011E+04 9.339E-01 I BR-84 4.004E+02 3.376E+05 1.256E-22 E.

BR-85 l

2.044E+01 0.000E+00 0.000E+00 RB-86 1.904E+05 1.478E+07 l 2.234E+10 I lRB-88 5.572E+02 5.399E+04 1.874E-44 RB-89 3.206E+02 2.075E+05 4.193E-53 i

SR-89 2.030E+06 3.560E+04 1.258E+10 1

I lSR-90 4.088E+07 0.000E+00 1.216E+11 lSR-91 7.336E+04 3.587E+26 3.215E+05 l l Values based on Reference 1, Section 5.2.1 assumptions unless otNrwise indicated. o G - mrem /yr ner pCi/m' i @-m 2 nren/yr oer uCi/sec ODCM, V C Sumer, SOUTH CAROLINA ELECTRIC AND GAS C0. 2.0-13

TABLE 2.2-1 (Continued) PATHWAY DOSE FACTORS FOR SECTION 2.2.1.b (Pj) Page 2 of 3 I AGE GROUP C INF' ANT ) ( N.A. ) ( INFANT )

ISOTOPE:

INHALATION 4: GROUND PLANc.. I __._ FOOD

SR-92 1.400E+05 1.233E+06 5.

.005E+01

Y-90 2.688E+05 7.583E+03 l

I _ __9.406E+05

Y-91M 2.786E+03 1.658E+05 1.8

____ _ 76E-15 I _ _1E+06 c-91 2.450E+06 1.702E+06 5.25 Y-92 1.266E+05 3.060E+05 L ____1.026E+01 Y-93 1.666E+05 3.620E+05 1.7 1 76E+04 12R-95 1.750E+06 3.975E+08 ' O.25 I 7E+05

ZR-97 l

1.400E+05 4.921E+06 __4.446E+04 I __.__62E+08 lNB-95 4.788E+05 l 2.291E+08 l 2.0 MO-99 1.348E+05 6.608E+06 3.108 ____E+08 I lTC-99M 2.030E+03 3.013E+05 1 _ ___ ____ __ __ ___.646E+04 lTC-101 8.442E+02 l 3.253E+04 1.423 I _____ __E-S6 RU-103 5.516E+05 1.804E+08 1.055E+0 ______ _ 5 I ____ 204E+00 lRU-105 4.844E+04 1.030E+06 3 RU-106 1.156E+07 3.590E+08 1.445 _______;______________________________________E+06 AG-110M : 3.668E+06 3.649E+09 1.461E+ ____10

TE-125M :

4.466E+05 3.001E+06 1. I _.508E+08

TE-127M :

1.312E+06 1.395E+05 1.037E+09 TE-127 2.436E+04 4.704E+03 1.359E+LS

TE-129M :

1.680E+06 3.290E+07 l 1.39 ___ ___ _2E+09 I lTE-129 l 2.632E+04 4.395E+04 1.678E-07 lTE-131M : 1.988E+05 1.351E+07 2.280E+07 I TE-131 8.218E+03 4.929E+07 l 1.3 _____ _ __ __ ___ __ _ _ __ _..__ _ __ _84E-30

TE-132 3.402E+05 7.098E+06 6.513E+07 I-130 1.596E+06 9.560E+06 8.754E+08 I

w' - mrem /yr per pCi/m 3 @-m2 mrem /yr oer uCi/sec I CDC!1, V C Summer, SOUTH CAROLIfiA ELECTRIC AtlD GAS CO. 2.0-14

E TABLE 2.2-1 (Continued) E PATHWAY DOSE FACTORS FOR SECT 10tl 2.2.1.b (Pj) P. age 3 of 3 I AGE GROUP ( INFANT ) ( N.A. ) ( INFANT.) ____________________.__g g___: l ISOTOPE: INHALATION GROUND PLAN FOOD I lI-131 1.484E+07 l 2.985E+07 l 1.053E+12 I lI 132 1.694E+05 2.075E+06 1.188E+02

I-133 3.556E+06 4.259E+06 9.601E+09 I 134 4.452E+04 7.578E+05 8.402E-10 I-135 6.958E+05 4.210E+06 l

2.002E+07 I i

CS-134 7.028E+0S 3.2822+09 6.801E+10

~ 5Cb-ibb 1I34bk+0h UI4bbk+08 b3bbk+09

CS-137 6.118E+05 1.337E+09 6.024E+10
CS 138 8.764E+02 5.860E+05 2.180E-22 lBA-139 5.096E+04 1.705E+05 2.874E-05 I

lBA-140 l 1.596E+06 3.352E+07 2.410E+09 lBA-141 4.746E+03 6.762E+04 3.141E-41 .I = lBA-142 1.554E+03 7.234E+04 0.000E+00 I lLA 140 l 1.680E+05 3.114E+07 l 1.880E+05 lLA-142.: 5.950E+04 l 1.269E+06 6.019E-06 I

CE-141 5.166E+05 2.199E+07 1.366E+e7 lCE-143 1.162E+05 3.753E+06 1.536E+0L lI f

lCE-144 9.842E+06 6.761E+07 1.334E+08 _____________________________r. I

PR-143 4.326E+05 0.000E+00 7.845E+05

_______________________._________t

PR-144 4.204E+03 3.017E+03 1.171E-48 I

HD-147 3.220E+05 1.441E+07 5.743E+05 lW-187 3.962E+04 3.915E+06 l 2.501E+0F lNP-239 5.950E+04 2.823E+0S 9.400E+04 E G - nren/yr per uci/m' t E @-m 2 mrem /yr per uCi/sec I ODCM, V C Summer. SOUTH CAROLIf1A ELECTRIC At!D GAS CO. 2.0_15 I

I Table 2.2-2 PATHWAY 00SE FACTORS FOR SECTION 2.2.2.b (R )* (For Dose Calculations Required by TS 3.11.?.3) Page 1 of 3 AGE..ROUP ( CHILD 3 ( H.A. ) ( Crt!LD ) ...,............................=__

ISOTOPE: INHALATION : CROUND PLiNE: UEGET4 TION :

!H-3 1.125C+03 0.000E+00 j 4.000E+03 ll _ =..,. _ = I lC-14 3.509E+04 0.000E+0a l 8.894C+08 INA-24 1.610E+04 1.385E+07 1 3.fr9E+05

P-32 2.605C+06 0.000c+00 3.366E+09 I

CR-51 1.698E+04 5.506E+06 l 6.2f7 +06 ........ _ _ = - -.. _.. _... - - - - ___

== . - = !MN-54 1.576C+06 1.625E+09 6.648E+08 I lMH-56 1.232E+05 1.068E+06 l 2.723E+03 - - _ - - = =.......... _ _. - =-- -_... FE-55 1.110E+05 0.000E+00 8.012E+08 !FE-59 1.269E+06 3.204E+08 6.693E+0S _4..__._.__..__.

==.............__.__...____._

CO-58 1.106E+06 4.464E+03 3.771C+09

....__..__....-_.__.................J...__._....... 3CO 7.067E+06 2.532E+10 h 2.095E+09 3, ...-60 _ _ _ _........ = - - -

HI-63 8.214E+C5 0.000E+0.

3.949E+10 ..__............=== - = _ - !HI-65 8.399E+04 3.451E+05 1.211E+03 .._== . T. '. '159 E + 0 5 - - ' ~ ' ' I lCU-64 3.670E+04 6.876E+05 5 _.....y___...... ..'d-65 -.___..;_.........__.J: I 9.953E+05 8.583E+0B 1 2.164E+09 .-__..___.. _-__.__.== 9.893C-04 3'

ZH-63 1.018E+04 0.000E+00 d

BR-83 4.736E.02 7.079E+03 $._5.369E+00 t, ........ _ _. _ _............. _ _ - - = - - - - -

BR-84 5.476E+02 2.363E+05 3.822E-11

_=__=..._.. I lBR-85 2.531E+01 0.000E+00 1 0.000E+00 _J-lRB-86 1.983C+05 1.035E+07 d 4.584E+08 .............._.______..____.....____4......._____.. lRB-88 5.624E+02 3.779E+04 4.374E-22 I ______..___________________J._.... RS-89 3.452C+02 1.452E+05 1.642E-26 ....__...................._____.__...J._............' iSR-89 2.157E+06 2.509E+04 3.593E+10 l' ____...._._..J_.______._____ I SR-90 1.01EE+08 0.000E+00 1.243E+12

SR-91 1.739E+05 2.511E+06 1.157E+06 Values based on Reference 1, Section 5.3.1 assumptions unless otherwise indicated.

I 2 Uni ts : Inhalation - mrem /yr per pCi/m nnnn anlpIRI p rrem/yr per uC1/sec f 2 Others - m 00CM, V C Summer, SOUTH CAROLINA ELECTRIC AND GAS CO. 2.0-16

Table 2.2-2 (Continued) PATHWAY DOSE FACTORS FOR SECTION 2.2.2.b (R )j Page 2 of 3 ACE GROUP t CHILD 3 ( N.A. ) ( CHILD 3 ISOTOPE: INHALATION : GROUNU PLANE: UEGETATION ! _..====


===_.___.,e 2.424E+05 8.631E+05 1.378E+04 l

SM-92

---___..__........_.7....__........'

Y-90 2.679E+05 5.309E+03 6.569E+07 I

- =__- Y-91M 2.812E+03 1.161C+05

i_ _.1. 7 37 E-05

...................q: Y-91 2.627E+06 1.207C+06 I -.__...._....._.....J,_.2.484E+09 -__.i. 4.5761+04 Y-92 2,390E+05 2.14.7E+05 _.._........._ ____...._....== Y-93 3.085C+05 2.534E+05 4.482E+06 !ZR-95 1 2.231E+06 l 2.937E+00 ^ 9.043E+08 _____a________...

l 1.240E+07 12R-97 3.511E+05 3.445E+06

___........__......................_.q:__2.949E+09 ..____.__.___....___.._......_____..J_........-...: !N8-95 6.142E+05 1.605E+09 IMO-99 1.354E+05 4.626E*06 1.647E+07 1 TC-99n : 4.910E+03 2.109E+05

I 5.255E+03

_..__.......____....___....__________q:,.____...._....y I TC-121 5.846E+02 2.277E+04 4.123E-29 _ _ _.._ _._ _ _. q:i..... _..... 7 1.265E+08 3.971E+09 RU 103 6.623E+05 t !RU 105 : 9.953E+04 7.212E+05 5.981E+04 _________.........J:.. -.q!! I I . RU-106 1.432E+07 5.049E+08 l4 1.159E+10 ....__..__....______....__.__..._._..__._____.___3 IAG-110n : 5.476E+06 4.019E+09 2.501E+09 __.___...__.__.,'...._____....______.__.___....___5:[ TE-125n : 4.7.1E+05 2.128E+06 3.506E+08 TE

1. 4 01E + 06 1.093E+05 lI 3.769E+09

._ -127M ......W-__....____... 1

TE-127 :

5.624E+04 3.293E+03

\\

3.903E+05

I I -

I I ITE-129n : 1.761E+06 2.305E+07 3' 2.460E+09

TE-129 2."49E+04 3.076E+04 7.204E-02

.a-I ..) .....t. 2.163E*07..__......._i TE-131n : 3.078E+05 9.459E+06 l

TE-131 2.054E+03 3.450E+07 l

1.349E-14

TE-132 :

3.774E+05 4.960C+06 3.111E+07 .1-13e 1.946E*06 6.692E+06 1.370E+09 l I 3 Units: Inhalation - m em/yr per tici/m l Others -m mrem /yr per uCi/sec 1 1 00CM, V C Summer, SOUTH CAROLINA ELECTRIC AND GAS CO. 2.0-17 1 l

Table 2.2-2 (Continued) PATHWAY OOSE FACTORS FOR SECTION 2.2.2.b (R )j Page 3 of 3

  • t AGE GROUP

( CHILD 1 ( H.A. 3 ( CHILD ) - __ = ISOTOPE: INHALA710H : GROUND PLANE: UEGETATICH : I -.......... -_ _ - - _ = - _ - _ lI-131 1.624E+07 2.089E+07 4.754E+10 -_...._........_....L- __a II-132 1.935E+05 1.452E+06 7.314E+03 . - - - _ = - -.


=.....

..n. !!-133 3.848E+06 2.961E+26 8.113E+08 -- =- =_ 81-134 5.069E+04 5.305E+05 6.622E-03 ll 9.973E+06 1-135 7.918E+05 2.947E+06 7-..

CS-134 :

1.014E+06 8.007E+09

, 2.631E+10 ICS-136 1.709E+05 1.702E+08 2.247C+08

- - - _ _ _ - _ = = - -..... CS-137 9.065E+05 1.201E+10 2.392E+10 .._..._............_--- ----= -_._.- _ -_== _.

CS-138 :

9.399E+02 4.102E+05 l 9.133E 11 : IBA-139 5.772E+94 1.194E+05 2.950E+00 . - _ - - - - - = -

DA-140 :

1.743E+06 2.346E+07 I 2.767E+00 = J39-141 2.919E+03 4.734E+04 ll 1.605E-21___......_.-- 184-142 1.643E+03 5.064E+04 li 4.105E-39 i ..-........__..=__ lLA 2.257E+05 2.180E+07 lLA 142 : 7.585E+04 8.886E+05

I _=

..._-140 - _._______..........____ _1.3.166E+07 1.582E+01 4.082E+08

CE-141 5.43?E+05 1.540E+07 CE-1C
s 273E+05 l

2.627E+06 1.364E+07 if

CE-144 : 1 (95E+07 8.032E+07 l

1.039E+10

PR-143 :

4.329E+05 0.000E+00 l' 1.575E+08 l =.__....

PR-144 1.565E+03 l

2.112E+03 3.029E-23 ....... ____-.___....-=- IND-147 3.282E+05 1.009E+07 9.197E+07 !W-107 9.102E+04 2.740E+06 5.300E+06 1 lNP-239 6.401E+04 1.976C+06 1.357E+07 1 1 1 1 I l 3 Units: Inhalction - mrem /yr per uCi/m Others -m mrem /yr per uCi/sec ODCM, V C Summer, SOUTH CAROLINA ELECTRIC AND GAS C0. 2.0-18

Table 2.2-3 PATHWAY DOSE FACTORS FOR SECTION 2.2.2.c (R )* j Page 1 of 3 AGE Group ( INFANT 3 ( N.A. 3 ( INFAN7 3 3 ( INrANT 3 .-................-...........-....................(.. INFANT

ISOTOPE:

INMALATION : GROUND PLANE: GRS/CGWenILK: GRs/CowenEAT! VEGETATION l ........................----- _==_ .__.- = =----- _........._

H.3 6.468C+02 0.000E+30 2.43aE+03 0.000E+00 8

.................................................... 0.000E+00

C-14 2.646E+04 0.020E+ea 2.340E+as 0.000E+00 0.003E+aa l

...... = =- l ..----.---..................--....................:.0.00aE+0a =-..........--.................................. =- lNA 24 1.056E*04 1.385E*07 1.542E+a7 0.000E+00 ..........................i

P-32 2.040E*06 0.000E+00

.602E+11 0.000E+aa_------__..........! 0.000E+03 -=- - _

CR-51 1.284E+ad 5.546C+86 4.700E+06 0.000E+00

=.....--.........--............... 0.000C+00 ....................-.=--.

MH-54 9.996E+0 1.625C+09 3.900E+07 1

0.000E+00 ..........................--........--..........:. 0.000E+00 lMN.56 7.168E+04 1.C68C+06 2.062E+00 0.000C+0a 0.000C+00 _..... - -......... = - _ - ,=--....--.-...--....

FE-55 0.694E+04 0.000E+00 1.351E+0e 8.00aE+00 0.000

......................................E+00 .... = _ _ -. - -......... - = - lFC-59 1.015E+06 3.204E+09 3.919E*00 0.000E+00 0.000C+00 ................... - -................. - -... = _=.........--............ a

CO-Sa l

7.770E+05 4.464E+39 6.055E*07 0.00eE+00 .........................---..--..................... 0.000E+0? CO-60 4.50SE+06 l 2.532E+10 2.OS8E+08 ........--... ---.......--............. -----...:..0.000E+0a 9.000E+00 lNI.63 3.389E+05 0.00aE+00 1 3.493E*10 0.00aE+aa 0.000E+0a .---.................=- -- =4-

==- _ -- ---- lNI-65 5.012E+04 3.45tE+05 3.020E+01 0.000t+0a .-.......--........_.......---.............------..0.040E+00 CU-64 1.499E+04 6.076E+05 3.007 0.00aE+00 1 0.000E+00 ... --.............--............--.........E+06 ?2N-65 6.460C+05 0.503C+00 1.904C+10 0.003E+0a ...................-...-......---.......--.........:-.0.0aaE+00

ZN-69 1.322E+04 1

0.000E+0a 3.855E-09 0.200E+00 .................................~........-..-..---.0.000E+00 38R-93 3.809E+02 7.079E+03 9.339E-01 0.000E+00 0.000E+00 =......- =. -.....__..- =- =_.....--.................--......... lBR-84 4.004E+02 2.363E+05 1.256E-22 1 0.000E+00 ......--.......--............--............--..--... 0.000E+0a BR-85 2.044E+01 0.000E+00

0. 000E* 00 1 0.000E*00

.--._-.--.....---------..................-..--...0.000E+0a I RS-86 1.904E+05 1.035E+07 2.234E+10 ........--...........--..........--..--------...... 0.000E+00 0.000E+00 lRB-89 5.572E+D2 3.779E+04 1.874E-44 0.000E+aa ....--....-- -..--...........---................--... 0.000E*00 .-_ =.............--..-- lRB.89 3.206E+02 1.452Cs05 4.193E-53 0.000E+00 ..................---........................--... 0.000E+0a SR.89 2.030E+06 2.509E+04 1.256C+ 0.000E+00 0.000E+00 .............---..........--------..... -....10.----....-..................... ISR-30 4.088E+07 0.000C+0a 1.216I+11 .............--.........--....--.........--..... - 0.00aE+00 0.002C+03

SR.91 7.336E+04 3

2.511E+06 3.215E+05 0.00aE+00 __..._.._. ____ -.......-....._....--........._------.0.000E+00 Values based on Reference 1, Section 5.3.1 assumptions unless otherwise indicated. 3 Units: Inhalation - mrem /yr per uCi/m Others -m mrem /yr per uCi/sec ODCM, V C Summer, SOUTH CAROLINA ELECTRIC AND GAS CO. 2.0-19

I Table 2.2-3 (Continued) PATHWAY DOSE FACTORS FOR SECTION 2.2.2.c (R )* j I Page 2 of 3 I AGE GROUP ( INFANT 3 ( H.A. 3 ( INFANT 3 ( INFAN7 ) ( IHfANT I ISOTOPE: INHALATION : GROUND PLANE: CRS/ COW / MILK: CHS/COWenEAT UEGETATICM :i I -==- SR-92 1.400E*05 8.631E+05 5.005C+01 0.000E+00 0.000E+00 t.i ........... - _ = _ - _..........................................-=_ ....e Y.90 2.688E+05 5.308E+03 9.406E+05 0.000E+00 0.000E+00 1 =--....___.._.- _.= ____....q Y.91N 2.786E+03 1.161E+05 1sB76E-15 : 0.000E+ee 0.000C+00 J

Y-91 2.450C+06 1.207E*05 5.251E+06

'. 000C+0 0 0.000C+.90 ............ = -- _... Y.92 1.266E+05 1 2.142E+05 1.026E+01 0.000E+00 0.000C+00 24 I _==_................................-4

Y.93 1.666E+05 l

2.534E+05 1.776E+04 0.000E+00 0.000 ---_-...._............_------..._-...---...._..-_.........--....E+00 .--__.4

2R 95 1.750E+06 2.037E+08 8.257E+05 0.000E+00

.........._....--................--..........................:_.0.000E+00 I,

2R-97 1.400E+0?

3.445E+06 4.446E+04 0.000E+0 ........--........~.....--...... --......._-__........ --.0 0.000E+00 .-_............+.

H9 95 4.700E+05 1.605E+09 2.062E+09 0.000E+00 0

.___...........-..........--........--..._................-__..._... 000E+00 I .....--.........._...----........................................ 000E+00 lMO-99 1.349E+05 1 4.626E+06 3.100E+09 0.000E+00

0
TC-99N 2.030E+03 2.109E+05 1.646E+04 0.000E+00 3.000E+00

=__.-------..--...--.-_........................

TC-101 0.442E+02 2.277E+04
1. 423 E-56 0.000C+00 0.000E+00 RU-103 5.516E+05 1.265E+08 1.055E+05 0.000E+00
0

..............-_..............--_.._....----..............--..... 000E*00 TRU-105 4.844E+04 7.212E+05 3.204E+00 0.000E+00 .......................__._--.............--...--...........-...:. 0.000E+00 I ...---..--.....--..___......--......--....__.--...---............0.000E+00 lRU-106 1.156E+07 5.049E+08 1.445E+06 0.000E+00 1AO-110n : 3.668E+06 4.019E+09 1.461E+10 0.000E+00

0

...............------.........----.... --....._........_......... 000E+00 TE-125n : 4.466C+05 2.128E+06 1.508E+00 0.000E+0 I ._.----.........--.................----_..0 0.000C+00

TE. ?7N :

1.312E+06 1.083E+05 1.037C+09 0.000E+00

0

..-_.--...-..........................--_--..--.-....._--.--.. 000E+00

TE-127 :

2.436E+04 3.293E+03 3 1.359E+05 0.000E+00 0 .--...-_-----..........--.~.-_.. _-. --..__........ _......--.._:.--.000E+00 I

TE-129n :

1.680E+06 2.305E+07 1.392E+09 0.000E+00 i .....__..........................-----......--._....-_.-_..-_.....0.000E+00 TE.129 2.632E+04 3.076E+04 1.678E-07 0.000E+00 ....._..........--......--......--..-_-_--...._.....---.__........0.e00C+00

TE-131M :

1.988E+05 9.459E+06 2.298E+07 0.000E+00 0 .......... --_..---............--.. _-.___--.............--........ 000E+00 D

TE.131 8.218E*03 3.450E+07 1.384E-30 0.0000+00 0.000E+00 1

.---_........_.-....--..-....................-_-.._.--.-------._1 l

TE-132 3.402E+05 4.968E+06 6.513E+07 0.000E+00
0

......-.._.__.. _..._.........__-----------.__......-_.._..-..... 000C+00 i 11 130 1.596E+06 6.692E+06 0.75dE+08 0.000E+00

0

...-_.. __...-------..... __--..._..-........-_--_......_...-...._ 000E+00 I Units: Inhalation - mrem /yr per uCi/m Others -m mrem /yr per uCi/sec ODCM, V C Summer, SOUTH CAROLINA ELECTRIC AND GAS CO. 2.0-20

Table 2.2-J (Continued) PATHWAY DOSE FACTORS FOR SECTION 2.2.2.c (R )* j Page 3 of 3 I AGE GROUP C INFAN7 ) ( H.A. 3 ( INFAN7 ) ( INFANT 3 ( INFANT 3 + ..........__ =- - = = = =.. - = _=- --... __-=-== = ISOTCPE: INNALATION : GROUND PLANE: GRS/ COW / MILK: GRS/ cower 1 EAT: VEGETATION I, ......... =__ -_..- =- _=....- !!-131 1.484E+97 l 2.089E+07 1.053E+12 0.000E+00 0.000E+03 lI _ _ _ _ _ = - = = - - - - - - _ - _ = !-132 1.694C+05 1.452E*2% 1.188E+02 0.00dE+00 0.300E+00 l1-133 3.556C+06 I.981E+04 9.601E+09 0.000C+00 1 0.000E+00

==__ _-===_..__=-==-- !!-134 4.452E+04 5.305E+05 8.402E-10 0.000E+00 0.000E+0a - =_.....____- _= _-......__..... !!-135 6.950E+0? 2.947E+06 2.002E+07 e.000E+00 0.00eE+00 'CS-134 7.028C+a5 8.007E+09 6.801E+10 0.000E+0a 0.003E+00 I ...___.___.s.__.___.....

CS-136
1. ~J 4 ? r + 3 5 :

1.702C+08 5.795E+09 0.000E+00 0.00aE+00 _,. = -

CS-137 :

6.118C+05 1.201E+10 6.024E+10 0.000E+00 1 0.000E+00 .... _ _...... _ _ _. _ _ _. _ _ _.......... = - - - -

CS-138 :

8.764E+02 4.102E+05 2.1808 ?2 0.000E+00 8.000E+00 =

= _ - _ _. - - - - _...._

BA.139 5.095E+04 1.194E+05 l

2.874E 05 : 0.00eE+ce 0.000E+00 ... _....... _.... = = = - ..--- ____=........_.__....._...__........_____...

BA-140 1.596E+0S 2.346E+07 2.41eE+0B 0.000E+e0 0.000E+90

_._._____....__.____==---- -._==

BA-141 4.746E+03 4.734E+04 3.141E-44 0.000E+03 0.000E+23

_____.-- _....__.....___....._- _=- =- IBA-142 1.554E+03 5.064E+04 0.000E+0a 0.000E+0a 0.000E+00 LA-140 1.680E+05 2.18aE+07 1.880C+05 0.00aE+00 1 0.000E+00 LA-142 5.950E+04 8.886E+05 6.019E-06 0.020E+00 0.000E+0a CE-141 5.166E+05 1.540E+07 1.366E+37 0.00eE+aa 0.000E+00 2, ......___.....__=--

CE-143 :

1.162E+05 2.627E+06 1.536E+06 0.BeeE+00 0.000E+00 ..... __.............._...- ---- ---- -=.. _ -

CC-144 9.842E+36 0.032E+07 1.334E+09 0.000E+00 0.000E+20
PR-143 4.326E+05 0.000E+00 7.845E+05 0.000E+0a 0.000E+00

____.....__..........=- = _ _ _ _...... _......... _ _ _ _ _ _.....,

PR 144 4.284E+03 l

2.112E+03 1.171E-48 0.000E+08 0.00aE+30 _=-__.._......____................... I lND 147 3.220E+05 1.009E+07 5.743E+a5 0.030E+0a 0.000E+00 lW-187 3.962E+04 l 2.740E+06 l 2.501E+06 0.083E+00 0.000E+00

==..._ ....-239 lNP 5.953E+04 1.976C+06 9.400E+04 0.020E+20 0.0 ace +00 I 3 Units: Inhalation - mrem /yr per uCi/m 2

  • mrem /yr per uCi/sec Others

-m 00CM, V C Summer, SOUTH CAROLINA ELECTRIC AND GAS CO. 2.0-21

Table 2.2-4 PATHWAY DOSE FACTORS FOR SECTION 2.2.2.c (R )* Page 1 of 3 feGE GROUP ( CHILD ) ( H.A. 3 ( CHILD 3 ( CHILD 3 ( CHILD 3 l m........--....y ....... -....................... - - _ _ = _ _ - - - - - - - - - _ -

ISw!0PE: INHALATION : GROUND P ANE: GRS/ COW / MILK: GRS/ COW / MEAT: UEGETATION :

H-3 1.125E*03 P.000C+00 1.601E+03 l 2.341C+02 4.000E+03 _=.....---._ .=.........y

C-te 3.589E+04 0.000E+00 1.195E+39
3. 834f -08 8.894E+08

=... = = - -. __= = = =- INA-24

1. G O E+ 0 4 1.385E+07 8.853E+06 1.725E.03 3.729E+05
P-32 2.605E+06 0.000E+00 7.7~hi+10 7.411E+09 3.756E+09

-.................__.....=__ . --.........-......=- =-

CR 51 1.696E+04 5.506E+06
% 398E+06 4.661E+05 6.213E+06
j

. = _ _3ll lMM-54 1.576E+06 1.625E+09 2.097E+07

b 011E+e6 :

6.648f-t9 4 g ...y ..............--.n.....---..... 2.7s.. 3 : MN-56 1.232E+05 1.068E+06 1.865E se : 2.417E-51 =.--- =_..............--......... lFC-55 1.110E+05 U.000E+00 1.118E+08 4.571E+08 8.012C+08 --.......----.....-----..=

FE-59 1.269E+06 3.204E+09 2.025E+ea 6.338E+08 6.693E+08

..... _ = Co-50 1.106C+06 4.464E+08 7.000E+07 9.595E+07 3.771E+08 -= ---- lCo-60 7.067E+06 2.532E+13 2.391E+09 3.038t+08 2.095E+09 .. = _ = _ - - - - = - - = = _ = _ -....... - -...... - -............. - -. - -...... - -.............

HI-63 8.214E+05 0.000E+00 2.964E+10 2.912E+10 3.949E+10 i

= NI-65 8.399E+04 3.451E+05 1.909E+01 4.061E-51 1.211C+03 .------ :=_.----- l lCU-64 3.670E+04 6.876E+05 3.502E+06 1.395E-05 5.159E+05 9.953E+05 8.583E+08 1.101E+10 1.000E+09 2.164E+09 ."ZN-65 t f

ZN-69 1.018E+04 0.000E+00 1.123E-09 0.000E+00 9.893E-04 lBR-83 4.736E+02 7.079E+03 4.399E-et 9.519E-57 5.369E+00

- - - - - - = - - - - - - - - l lBR-84 5.476E+02 2.363E+05 6.500E-23 0.000E+0a 3.822E-11 l 1 lBR-85 2.531E+01 0.000C+00 0.000E+00 0.000E+00 0.000E+00 l l

RS-86 1.983E+05 1.035E+07 8.804C*09
5 816E+08 4.584E+0B lR8-80 5.624C+02 3.779E+04 7.150E-45 0.000E+C0 4.374E-22 lI lR8-89 3.452E+02 1.452E+05 1.715E-53 0.000E+ea 1.642E-26 ISR-89 2.157E+06 2.509E+04 6.619E+09 4.015E+08 3.593E+10
SR-90 1.010E+08 0.000E+00 1.117E+11 1.04cE+10 1.243E+12 l
SR-91 1.739E+05 2.511E+06 2.878E+05 5.292E-10 1.157E+06 l

I 1 Values based on Reference 1, Section 5.3.1 assumptions unless otherwise indicated. Units: Inhalation - mrem /yr per uCi/m p Others -m mrem /yr per uCi/sec b I ODCM, V C Summer, SOUTH CAROLINA ELECTRIC AND GAS CO. 2.0-22

I Table 2.2-4 (Continued) PATHWAY DOSE FACTORS FOR SECTION 2.2.2.c (R )* j Page 2 of 3 9 AGE GROUP ( CHILD 3 ( H.A. 3 ( CHILD D ( CHILD 3 ( CHILD 3 l .....= _ = _ - - = _......... - = -. I

ISOTOPE: INHALATION : GROUND PLANE: GRS/ COW / MILK GR5/ COW / NEAT: UEGETATION :

lSR-92 2.424E+35 3.631E+05 4.134C+01 3.492E-48 1.378E+04 ...m ..=-_ --............... -..==_- =- = _..................- _ _ _ - - - - Y.93 l 2.679E+05 5.308Et03 2 9.171E+05 i 4.379E+05 6.569E+07 ( ---__ - = =......... - -..... - -. - -...... _ _ _ - .Y.91M 2.812E+a3 1.161E+05 5.198E-16 0.00aE+0a 1.737E-05 --=----

Y.91 2.627E+06 1.207E+06 5.199E+04 2.400E+09 2.484C+09 l

-.. - - -........ -.................. = _ - - - - - - - - - - - - - -.. - -............. - -............ - I Y.92 2.390E+05 l 2.142E+05 7.310E+00 6.959E.35 4.576t+04 ll ...............--.........----..................--+.....---.--...........---...- Y.93 3.885E+05 2.534E+95 1.573E+a4 1.547C-07 4.482F+06

ZR.95 l

2.231E+06 2.837C+08 8.786C+05 6.106E+03 8.843C+06 1 I 4

ZR.97 3.511E+05 3.445E+w6 4.199E+04 7.015C-01 1.248E+07

_- =......---.... -.............--..... =.......----................=---_ HB.95 6.142E+05 1.605"+08 2.297E+09 2.220E+09 2.949E+08 lMO-95 1.354E+05 4.E26C+04 1.730E+29 2.456E+05 1.647E+07

TC-99n :

4.810E+03 2.199E+05 1.474E+04 6.915E-18 5.255E+03 - - =. -.... - z--...-............-....-..--.-...

TC-101 5.846E+02 2.277E+04 5.593E-58 0.000E+0D 4.123E.29 1

lRu.103 6.623E+05 1.265E+08 1.108E+05 4.009E+09 3.971E+08 1RU-105 9.953E+04 7.212E+05 l 2.493E+00 5.885E-25 5.991C+04 I lRU-106 1.432E+07 5.049E+0a 1.437E+06 6.90?C+10 1,159E+10

== ---. . - -. - - -. - - - - -................ - - - - -..... -....... - - - - -..... - - - - - - - - _ - = - AG-110M : 5.476E+06 4.019E+09 1.678E+10 6.742E+08 2.581E+09 - _ -. - - -. - -.... - -..... - -....... - - - + -. - -.. - - - -... - -. - - -. - - - - - - - - - - - - - - - - - - - - - - T~-125M : 4.773E+a5 2.128E+06 7.377E+07 5.69aE*00 3.506E+09

TE-127N :

1.480E+06 1.083E+05 5.932E+08 5.06aE+as 3.769E+09 .a-

TE.127 :

5.624E+04 3.293E+03 1.111E*a5 1.607E-08 3.903E+05 TE-129n : 1.761E+06 2.305E+0 ' : 7.9617+h9 5.245E+09 2.460E+09 l

TE-129 ;

2.549E+04 3.076E+0A 6.166E-23 0.000E+00 7.204E-02 l

TE-131M :

3.078E+05 9.459E+06 2.244E+07 9.815E+03 2.163C+07 l

TE-131 2.054E+03 3.d50E+07 9.489E.32 0.030E+aa 1.949E-14

( l

TE.137 3.774E+05 4.960E+06 4.551E+07 9.325E+06 3.111C+07

= = - - - - - -.... - - - - - -........ - - - - -... - lI-130 1.846E+0S 6.692E+06 3.845E+09 6.75aE-04 1.370E+03 l I 3 Units: Inhalation - mrem /yr per uCi/m Others -m mrem /yr per uCi/sec ODCM, V C Summer, SOUTH CAROLINA ELECTRIC AND GAS CO. 2.0-23

Tabic 2.2-4 (Continued) PATHWAY 00SE FACTORS FOR SECTION 2.2.2.c (R )* j Page 3 of 3 AGE group ( CHILD 3 ( H.A. 3 ( CH 11.D 3 ( CHILD ) C CHILD 3 l =-- ---- - _ - = _ _ = _ ISO 70PE: INHALA7ICH : GROUND PLANE: GRS/ COW / MILK G4S/ COW / NEAT: UEGETATION : =- _=-..... 11-131 1.624E+07 2.089E+07 4.333E+11 5.503E*09 4.754E+10 _ _.... = = - - - =- _A .... 3 21-132 1.935E+05 1.452E+06 5,129E+01 2.429E-57 7.314E+03 1, _ _ _ _..... _.. = = - - _ _ - - =- -- _=_.................__.- II-133 3.648E+06 1 2.981E+06 3.945E+09 1.304E+02 8.113C+09 a n.. lI-134 5.069E+04 5.345C+05 3.624E-10 0.000E+00 6.622C-03 _ _. - - = = - - - _........._- II-135 7.910E+05 2.947C+06 8.607E+06 1.039E-14 9.973C+05 ..___._-......_......__.-- -_=_ - - - - - -

CS-134 1.014E+0s 8.007E+03 3.715E+10 1.513E+09 2.63tE+10 I

_ =................ _. _ = _ - lCS-136 1.709E+05 1.702E+0e 2.773E+09 4.426C+07 2.247E+29 =...... _==..__.._..._-.....-_................

CS-137 9.065E+05 1.201E+10 3.224E+10 1.334E+09 2.392E+10

- -.................... ~ - _ _ _=_........__........_ - _ - _ ___..... lCS-130 8.399E+02 4.102E+05 5.528E-23 0.000E+00 9.133E-11 I s..... 1B4-139 5.772E+C4 1.194E+05 1.231E-05 0.000E+00 2.9 ---....._..............__.___.....-_.._._.........._..._...50E+0W 184-140 1.743L*06 2.346E+07 1.171E+09 4,304 __......_..............................___........_.....E+07 2.767E+0S I BA-141 2.919E+03 4.734E+04 1.210E-45 0.000E+00 1.605C-21

BA-142 1.643E+03 5.064E+04 0.000Ee00 0.ee0C+00 4.105E-39 I

.._.___............._..........-...........___._-...... 492E+02 lLA-140 l 2.257E+05 2.180E+07 1.894E+05

5 3.166C+07 LA-142 7.585E+04 0.896E+05 2.904E-06 0.000E+00 1.502E+01

...s-

CE-141 5.439E+05 1.540E+07 1.361E+07 1.382E+07 4.082E+09 I

=....................__.._._...._... _......_............._.. CE-143 1.273E+05 2.627C+06 1.4SSE+26 2.5 1.364E+07 ....__.......___........ ~........__..........__.__ 16t+02

CE-144 1.195C+07 9 a3*E+07 1.326C+09 1.893E+09 1.039E+10 I
PR-143 4.329E+05 0.000E+00 7.754E+05 3.609E+07 l

1.575E+09

PR.144 1.565E+03 2.112E+03 2.04eE-50 0.000E+0a

.......___...__......_...._____.......:___3.829E-23 IND-147 3.282E+05 1.009E+07 5.712E+05 1.505 9.197C+07 .................______......... __......_._ _._.... ____E+07

W-187 9.10ZE+04 2.740C+06 2.420E+06 2.790E+00

............_..........................__...__....._..___...:.5.30eE+06 I [ NP-239 6.401E+04 1.976E+06 9.139E+04 2.2 1.357E+07 _.......-.....___.-_._.._...___.-_....__. _ _........- _32E+03 I I Units: Inhalation - mrem /yr per uCi/m p 9l Others -m mrem /yr per uCi/sec Q j' 1 I ODCM, V C Summer, SOUTH CAROLINA ELECTRIC AND GAS CO. 2.0-24

Table 2.2 5 PfTHWAY DOSE FACTORS FOR SECTION 2.2.2.c (R )* j Page 1 of 3 I AGE GAOUP (TEENAGER) ( N.A. 3 (TEENAGER) (TEENAGER) (TEENAGER 3 l =_-__........ = _- - i ISOTOPE: IMHALATION : GROUND PLANE: GRS/ COW / MILK: GRS/ COW / MEAT: UEGE7ATION t, ..... _.. _ _. _ = - - --==...._...- _ ._.i _ _ _-3 lH 1.272E+03 0.000E+00 1.014E+03 1.930E+02 2.588E+03 I _=......._...-- lC-14 2.600E+04 0.000C+00 4.859E+0e 2.040E+0s 3.69eE+09 ... __ - _==-- -_a NA.24 1.376E+04 1.385E+07 4.255C+e6 1.084E-03 2.389E+05 3'

_.....__..........e

. _ _ _ = - _ .__.....y

P-32 1.8SSE+06 0.000E+00 3.153E+10 3.931E+09 1.608E+09

=-- = __....=- _=___._..._J

CR-51 2.096E*01 5.506E+06 8.387C+e6 9.471E+05 1.037E+07

..=-- : .= MM-54 1.984E+06 1.625E+09 2.875E+07 1.436E+07 9.320E+08 .......... = - -_..._.............= =........) lNN-56 5.744E+04 1.068E+&S 4.856E-0 8.302E-52 9.451E+02 ............................._................1 ifE-55 1.240E+05 0.000E+00

==.......- . - - = _ = - - 4.454E+07 2.382E+08 3.259C+08 ___...... 4 !FE-59 1.528E+06 3.204E+0e 2.861E+08 1.171E+09 9.895E+00

CO-58 1.344E+06 4.464E+09 1.095Er03 1.942E+03 6.034E+09
Co-60 8.720E+06 2.532E+10 3.6 7.60aE+09 3.239E+09

.........__.............._..........._.. 21E+0a

HI.63 5.800E+05 0.000E+00 1.182E+10 1.519E+10 1.606E+10

.................. =- _ _

HI-65 3.672E+04 3.451E+05 4.692E+00 1.305C-51 1

3.966E+02

CU-64 6.144E+04 6.876E+05 3.293E+e6 1.713E-05 6.465E+05

..._.................___......=

ZH-65 1.240E+06 8.583E+08 7.315E+0 8.68SE+09 1.471E*09 l

{ ........._..___............................... 9...... _.....___......_..__..... 32N-69 1.584E+03 0.00FE+00 1.760E-11 0.000E+00 2.067C-05 =__-_.....--- BR-93 3.440E+02 7.079E+03 1.790E-01 5.066E-57 2.911E+00 __........c .=................_....

BR-84 4.32SE+02 2.363E+05 2.877E-23 9.000E+00 2.251C-11 m-....

.............m..... IBR-85 1.832E+01 0.000E+00 0.000E+ 1 0.000E+00 0.000E+00 ................ _............. _......_..... 00 RS-86 1.904E+05 1.035E+07 4.746E+09 4.101E+0a 2.772E+09 lRa-88 5.456E+02 3.779E+04 3.886E-0.000E+00 3.16aE-22 .....___...................................... 45 _=-.._ RS-89 3.520E+02 1.452E+05 9.774E-54 9.00 1.247E-26 .._........._.._._.. _._........._......_..0E+00

SR-99 2.416E+26 2.509E+04 2.674

....._........_........._....... _....._.....E+09 2.545E+29 1.513E+10

SR-90 1.080E+0a 0.000C+00 6.612E+10
8 7.507E+11

=_............_......................_. _.049E+09 SR-91 2.592E+05 2.511E+06 l 2.409E+0 5.794E-10 1.291E+06 _...._._.......__..........._.. ___...._...... 5....__........_...__..... _. __. l i Values based on Reference 1, Section 5.3.1 assumptions unless otherwise l Indicated. l Units: Inhalation - mrem /yr per uCi/m D ADIElM ll Others - m mrem /yr per uCi/sec [ ,, U n ] U ] l 0 1 L ODCM, V C Summer, SOUTH CAROLINA ELECTRIC AND GAS C0. 2.0-25

I Table 2.2-5 (Continued) PATHWAY DOSE FACT 095 FOR SECTION 2.2.2.c (R )* Page 2 of 3 AGE group (TECNAGER) t N.A. 3 (TEENAGER) (TEENA _- _=_...... ...............--......GER) (TELNAGER) i

ISOTOPE:

INNAL ATION ! GROUNO PLANC: GRS/COM/MILM: GRS/ COW / MEAT: ....--.y - - _ -............. - = - - ISR-92 1.192E+05 8.631E+05 1 2.277E+01 2.516E-48 1.012E+04 =............---..J ---s-...-----

Y-90 5.592E+05 5.30SE+03 1.074E+s6 7.470E+05 1.025E+08

=.---- __ -_- -_

Y-9 t ti 3.200E+03 1.161E+05 5.129E-18 9.000E+00
.2.285E-07

_................. = - Y-91 2.936E+06 1.207E+06 6.475E+06 3 3.910E+0e _ _=--.......... -=. -__-................. --..-:,=3.212E+09 ._.............. _ =

Y-92 1.648E+05 2.142E+05 2.828C+

3.522E-35 2.360 _.......--.....--.....--00....--......--. .........E+04

Y-93 5.792E+05 2.534E 1.312E+04 1.688E-0 4.983E+06

..................--.. --........t05..--................----....7 2R-95 2.68aE+06 2.837C+08 1.201E+06 __---.....--...--........--. --.--.-- -.1.092E+09 1.253E+39 12R-97 6.304E+05 3.44 4.225E+94

9 1.673E+07

..--...--...........--..5C+96..-- --............... 231E-01 ItB-95 7.512E+05 1.605E+08 ...'.....--..---...............--..:..3.338E*09 4.251E+09 4.55t .....--.................--....E+09 1M0-39 2.688E+e5 4,626E+0 .................................-6 1.023E+03 1 1.892E+05 .....................--...-..:.-1.293C+D7 !TC-93n : 6.12eC+03 2.10 1.055E+04 6.4 5.et1C+03 .--...-........--............9E+05........---...........--.71E-18

Tc-131 6.672C+02 2.277E+

3.287E-58 0.000 3.229E-29 .--.--.........--...............04............--,......... E+00 RU-103 7.832C+05 1.265E+ 1.513E+05 7.162E+09 .............-................08....................-.-. -.....:.- 5.7D6E+08 lRU-105 9.040E+04 7.21 1.263E+00 3.900 ..---..........---.......---.2C+05......--.....--.......--...E-25

4. 0 39 E+ 0 4
RU-106 1.608E+07 5.049E+D8

...........--........--.---.........1.799E+0S-..........--.....--.------....C+10 1.130E+11 1.484 AG-lien : 6.752E+06 4.019E+09 ........--...--......---....-.....---:--.2.559E*10--....--...........--...........E+09 1.345E+09 4.031

TC-125n :

5.360E+05 2.128 8.863E+07 8.941 4.375E+08 -....d ...--.----.......E+06.....--.....--.............E+09

TE-127M :

1.656E+06 1.083E+0 3.420E+08 3.816E+09 --.----.........--...--..........5........--...........---....:-.2.236E+03 I

TE-12' 8.000E+04 3.293E+03 9.572E+04.--.....--.........-.........

180E+05 1.689E.08 4

TE-129M :

1.976E+0S 2.305 4.602E+08 3.966 -...---..............-......--E+07-........----..........--...E+39 1.500C+09 l TE-129 3.296C+03 3.076E+04 ....................--........-------.. 2.195E-09... --...-....------..........18E-03 0.000E+00 3.4

TE-131M :

6.208E+05 9.459E+06 l ..-~.....................-----....-. 2.529E+07---........-....-........---..-8E+07 1 1.447E+04 3.24

TE-131 2.336E+03 3.450E+

2.879E-32 0.000 6.099C-15 ............................----.07----------........-------..E+00

  • TE-132 4.632C+05 4.96aE+06

...---............---- -----.---......: -8.581E+07...------...---...---...... --.18E+07 2.300E+07 7.8 I 31-13e 1.488E+06 6.692E+06 ---............--......--..-...-......:.-.1.742E*09...........----


....--.6E+07 4.003E-04 8.27 3

Units: Inhalation - mrem /yr per uCi/m 2. mrem /yr per uCi/sec l U U H,, U H E U R n i 1 b Others -m ODCM, V C Summer, SOUTH CAROLINA ELECTRIC AND GAS CO. 2.0-26

Table 2.2-5 (Continued) PATHWAY DOSE FACTORS FOR SECTI0tl 2.2.2.c (R ) Page 3 of 3 AGE GRouA (TECHAGER) C N.A. 3 (TEENAGER) (TEENAGER) (TEENAGER) l I ............... -- -==-... =. ._=.--.3 15070PE: INHALA7 ION : GROUND PLAME: GRS/ COW / MILK: GRS/ COW /nEA7: UEGETATION : .... =- _ =,

f 31-131 1.464E+07 2.099E+07
,2.1956:?8 3.645E+09 3.140E+10

.-..==-- =_................. =.


=q:

I 11-132 1.512E+05 1.452C+06 3 2.242E+01

1. 389 E -57 4.262E+03 21-133 2.920E*05 2.991E+06 1.674E+09 7.234E+01 4.587E+00
I-134 3.952E+04

.305E+05 1.583E-10 0.000E+00 3.854E-03 I _== - - I 135 6.209E+05 2.947E+06 3.777E+06 5.953C-15 5.832E+06

CS-134 :

1.128E+06 8.007E+09 2.310E+10 1.231E+a9 1.671E+10 _=.-.-. I = --..---- lCS-136 1.936E+05 1.702C+08 1.759E+09 3.671E+07 1.709E+09 -=:- -..- _- - - -. - - - -.. = = - =...... --....--..----- lCS-137 8.480E+05 1.201E+10 1 1.781E+10 9.634E+09 1.348E+10 I= CS-138 8.553E+02 4.102E+05 3.149E-23 0.000E+00 6.935E-11 ......-- - _......---.... --= l34-139 6.464E+03 1.194E+05 7.741 0.002E+00 2.472E-01 ...........--.....------.........-...------..E-07 2B4-140 2.032C+06 2.346E+07 7.483 3.653E+07 2.130E+09 ..........---............--..........--_- -..E+07....-......----.---...--........g

BA-141 3.280E+03 4.734E+04 4.922E-46 8.699E-22

..........---..............--..............--......:- 0.0aaE+00

8A.142 1.912E+03 5.064E+04 0.000E+00 0.000E+00 2.253E-39 I

LA.140 4.872E+03 2.100E+07 2.291E+05 8.639E+02 5.104E+07 __-....- _= =.....---- lLA-142 1.20dE+34 8.886E+05 2.574E.07 0.022E+00 1.869E+03 CC-141 6.136E+05 1.5/0E+07 1.696E+07 2.252E+07 5.404E+0a I lCE-143 2.552E+05 2.627t+06

1

...........-........ 671E+06 3.695E+02 2.040E+07 lCE-144 1.336E+07 8.032E+07 1.655E+29 1.32SE+10


.----..........---...---.........--.--...3.009E+0s I

PR-143 4.832E+05 0.000E+00 9.553E+05 5.817C+07 2.310E+ea
PR-144 1.752E+03 2.112E+03 1.230E-53 3

0.000E+00 3.097E-26 I HD-147 3.720E+05 1.039E+07 7.116E+05 2.452C+07 1.424E+09 lW-187 1.'6aE+a5 2.740E+06 2.646E+e6 7.939E+05 .-... -..........--...............---.........-:. 3.989E*00 'NP-239 1.320E+05 1.976E+06 1.053 3.397C+03 2.097E*07 ....--..--..----...E+03 I Units: Inhalation - mrem /yr ner pCi/m 3 Others - c,2 nrer/yr ner UCi/sec I ODCM, V C Summer, SOUTH CAROLIflA ELECTRIC AND GAS CO. 2.0-26a I g P00R ORIGINAL

I Table 2.2-6 PATHWAY OOSE FACTORS FOR SECTION 2.2.2.c (R )* j Page 1 of 3 I AGE GROUP ( ADULT 3 ( H.A. 3 ( ADULT ) ( ADULT 3 ( ADULT 3 .==_. -.._=- -

15070PE:

INHALATION : GROUND PLANE: GRS/ COW / MILK! GAS / COW / NEAT: UEGETATION : I H-3 1.264E+03 0.000E+00 7.781E+02 3.248E+02 2.260E+03

[

. = = = _ = _ - =_. = _q lC-14 1.816E+04 0.00aE+00 1 2.634C+08 2.414E+08 2.276C+09 ...._..._____= thA.24 1.024E+04 1.385E+07 2.438C+06 1.356C-03 2.690E+05 = - -

P-32 1.320E+05 0.000E+00 1.709E+10 4.651E+09 1.403E+03

.....== I _ = - = lCR-51 1.440E+04 5.506E+06 7.187E+06 1.772E+06 1.168E+07 ........... _ _......... = - - _ - =-_==............._.. --_-_.....-_. _ _. _=_. NN-54 1.400E+06 1.625E+09 2.57BE+07 2.812E+07 9.585E+08 =............___- ._=....

NN-56 2.024E+04 1.068E+06 1.32SE-01 4.958r-52 5.082E+02

_=_ lFE-55 7.200E+04 0.000E+00 2.511E+07 2.933E+03 2.095E+08 lFE-59 1.016E+06 3.204E+08 2.326E+08 2.083E+09 9.875E+08 I _=====--. _ _ _ - -

CO-59 9.280E+35 4.464E+08 9.565E+07 3.7035+D8 6.252E+09

==_.._...............

CO-60 5.969E+e6 l

2.532E*10 3.092E+09 1.413E+39 3.139E+03 --.......___.___..__.._...... __._ _ _ - = - - _ - -.... =.......... lHI-63 4.320E+05 0.000E+00 6.729E+09 1.sest+10 1.040E+10 t I .. _ _ - _ = __ - - - - -. _.... _ - _ - _ _........ _ _ _... _ _ _......

HI-65 1.232E+04 3.451E+05 1.219E+00 7.405C-52 2.026t+02

.__.=- =_ -- ___.._J ____-64 lCU 4.896E+04 6.876E+05 6.000E+04 6.825E-07

*2.31?C+04 1,

I - =. -_.__.._.....---_._...._-_..

2N-65 8.640E+05 8.593E+08 4.36SE+09 1.132E+09 1.009E+09

______.__-_.__,....__....____.......________....___....__.____..__......._.4

2N-69 9.200E+02 0.000E+00 5.207E-12 0.002E+00 1.202E-05 I
BR-83 2.400E+02 7.0?*E+03 9.716E-02 6.004E-57 3.107E+00 BR-84 3.129E+02 2.363E+05 1.609E-23 0.000E+00 2.475E-11

..__.....____.___.........= - ___......_-_== _ lBR-85 2.280E+01 0.000E+00 0.000C+00 0.000E+00 0.000E+00 I ___............s.. ......._............=- lRB-86 1.352E+05 1.035E+07 2.604E+09 4.914E+08 2.217E+08 ........ ___......-_.....__...._=_-==- lRB-89 3.872E+02 3.779E+04 l 2.139E-45 0.000E+00 3.429E-22 I R3-89 2.560C+a2 1.452C+05 5.523E-54 0.0aaE+as 1.385E-25

SR-03 1.4e0E+06 2.509E+04 1.451E+09 3.014E+39 9.961E+09
SR-90 9.920E+07 0.000E+00 4.680E+10 1.244E+10 6.046E+11 I
SR-31 1.9:2E+05 1

2.511E+06 1.377E+05 7.233E-10 1.451E+36 Values based on Reference 1, Section 5.3.1 assurr " ions unless otherwise indicated. 3 Units: Inhalation - mrem /yr per uCi/m } Others - m mrem /yr ser uCi/sec j 00CM, V C Summer, SOUTH CAROLINA ELECTRIC AND GAS CO. 2.0-27

Table 2.2-6 (Continued) PATHWAY DOSE FACTORS FOR SECTION 2.2.2.c (R )* j I Page 2 of 3 AGE CROUP ( ADULT 3 ( H.A. 3 ( ADULT 3 ( ADULT 3 ( ADULT 3 l I =-- =--....-- _____==--

ISOTOPE; INHALATICN : CROUND PLANE: GRS/ COW / MILK: GRS/ COW / NEAT: VEGETATION T lSR-92 4.304E+04 8.631E+05 9.675E+00 2.334E.49 8.452E+03
Y-98 5.056E+05 5.308E+03 7.511E+05 1.141E+06 1.410C+08
f I

r- -__===_ Y-Sin 1.920E+03 1.161E+05 1.743E-19 0.000E+00 1.527E-08

====.....- = =.. -. ---..l Y-91 1.7P4E*06 1.207E+0S 4.726E+06 6.231E+08 2.814E+09 I _...e =.......- -

==_......-

Y-92 7.352E+04 2.142C+05 9.772E-01 2.657E 35 :

1.603E+04

Y-93 4.216C+05 2.534E+05 7.389L+03 2.075E-J7 5.517C+06 I

... = = _ - - _ - - =........... - - -. l2R-95 1.76eE+06 2.837E+08 9.587E+05 1.903E+09 1.194E+09 t, l2R-97 5.232E+05 3.445E+06 2.707E+04 1.292C+00 l 2.108E+07 ...........m ___.......== =-- ----_=..--..--- HB-95 5.048E+05 1.605E+09 2.786E+08 7.748E+09 4.798E+08 I


:TC-9hn:

4.160E+03 2.109E+05 5.553E+03 7.439E-18 5.187C+03 _=- -_=..................................................--.- IMO-99 2.490E+DS 4.62SE+06 5.741E+07 2.318E+05 1.426E+07 --..........................--......-........--..........'.......--..m I

TC.101 3.992E+02 2.277%+04 1.813E-50 0.002E+00 3.502E-29 2,f

.......__.--...............--...................................= lRU-103 5.048E+05 l 1.265E+09 1.159E+05 1.229E+10 5.577C+08 -=-......._..-.........-.-................--.- lRU-105 4.816C+04 7.212E+05 5.240E-01 2 3.533E-25 3.294E+04 5 ...............--.......- -- -....-..-.--...--...........--.............----l lRU-106 9.360E+06 5.049E+08 1.320C+06 1.811E+11 1.247E+10 ............... --.......--.---........_....--_....-_----- = IAG-110M : 4.632E+06 4.019E+09 2.190E+10 2.523E+09 3.979E+09 TE-125M : 3.136E+05 2.120E+06 6.626E+07 l 1.460E+09 3.927E+F9 i t ...... - -..................... -............. - - _. -.... - -.......... - = TE-127M : 9.600E+05 1.083E+05 1.860E+0S 4.531C+03 1.418E+09 I lTC-127 5.736E+04 3.293E+03 5.278E+04 2.034E.Os 4.532E+05

TE.129M :

1.160E+e6 2.305C+07 3.028E+03 5.693E+09 1.261E+09 ---_ - __..=----

TE-129 1.936E+03 3.076E+04 9.167E-10 0.000E+00 2.80SE-03 I
TE-131M :

5.560E+05 9.459E+06 1.753E+07 2.190E+04 4.429E+07 l l

TE 131 :

1.392E+03 3.450E+07 1.578E-32 0.030E+e0 6.575E-15 l l lTC-132 5.096E+05 4.96GE+06 7.324E+07 4.297E+07 l 1.312E+09 l

!-130 1.136E+06 6.692E+06 1.050E+09 5.272E-04 9.809E+07 I

3 Units: Inhalation - mrem /yr per uCi/m 2. mrem /yr per uCi/sec Others -m l ODCM, V C Summer, SOUTH CAROLINA ELECTRIC AND GAS CO. 2.0-28 I

Table 2.2-6 (Continued) PATHWAY DOSE FACTORS FOR SECTION 2.2.2.c (R )* j Page 3 of 3 AGE GROUP ( ADULT 3 ( H. F., ) ( ADULT 3 ( ADULT ) ( ADULT ) I =._. . =.

ISOTCPE: INHALATION : GROUND PLANE: GRS/ COW /NILK: GRS/COV/ MEAT: UEGETATICH :

21-131 1.192C+07 2.009E+07 1.388E+11 5.034E+09 3.785E+10 .. _ _. _ _...... _ _. - - = - - _..____....__.......__- =__ ___ !.132 1.144E+05 1.452E+06 1.342E*01 1.816E-57 5.016E+03 I ......i ..=_ -- =....- - __-- =_-__.--- .....a II-133 2.152E+06 2.981E+06 9.891E+28 9.336E+01 5.331E+09 !-134 2.984E+04 5.305E+05 9.491E-11 0.003E+0a 4.544E-03 I i

I-135 4.480E+05 2.947E+06 2.217E+06 7.644C-15 6.731E+CS

__- =___ ___ _ _.--- =___

CS-134 :

8.480E+05 9.007E+09 1.345E+10 1.555E+a9 1.110E*10

CS-136 :

1.464E+05 1.702E+08 1.036E+09 4.724E+07 1.075C+09 305-137 : 6.208E+05 1.201E*10 1.010E+10 1.193E+09 8.696E+09 __..._-__= =.._..- .=- +.............. - lCS-130 6.209E+02 4.102E+05 1.786E-23 0.003E+00 7.733E-11 _ _............... _ _ _ _ _ _---==_.....__._....__..

BA-139 :

3.76aE+03 1.194E+05 8.322E-00 8.00aE+is 5.225C-02

BA.140 1.272E+06 2.346E+07 5.535E+07 5.917E+07 2.646C+03 I

===- lBA-141 1.936E+03 4.734E+04 2.677E-45 0.00aE+3e 9.305E-22 lBA-142 1.192E+03 5.064E+04 0.cadE+0a 0.000E+00 2.463C-39 ._......._._.....n w......._. LA-140 4.584E+05 2.18aE+07 1.672E+05 1.385E+03 7.327E+07

LA-142 :

6.328E+a3 8.88sE+35 3.503E-Da 0.0aaE+ea 4.999E-01 _s_.____............

CE.141 3.616E+25 1.54aE+07 l

1.253C+07 3.632E+07 5.097E+08 - =......_. _......-_..... _.... , I lCE-143 2.264E*05 2.627C+06 1.149E+06 5.547E+02 2.759E+0? l l lCE-144 7.776C+an 8.032E+07 l 1.209E+03 4.929E+09 1.112E+10

PR-143 2.80SE+05 0.003E+00 6.923E+D5 9.704E+07 2.74eE+08 I
PR-144 1.016E+03 2.112E+03 6.716E-54 0.000E+0a 3.303C-26

- - =....._.________. __ - ND 147 : 2.203E+05 1.009E+07 5.231E+05 3.935E+07 1.853E+08 l l W-187 1.552E+05 2.740E*06 1.796E+25 5.912E+aa 1.046E+07 ...... =

NP 1.192E+25 1.976E+05 7.385E+a4 5.152E+03 2.872C+07

-_.-239 l I 1 I l l l t t 3 i Units: Inhalation - mrem /yr per uCi/m Others - m mrem /yr per uCi/sec 1 1 l 1 00CM, V C Summer, SOUTH CAROLINA ELECTRIC AND GAS CO. 2.0-29 l ~ l

Table 2.2-7 CONTROLLING RECEPT 0RS, LOCATIONS, AND PATHWAYS

  • I DISTANCE

_ METERS) PATHWAY AGE GROUP ORIGIN (FOR INFORMATION ONLY) ( SECTOR N 6,196 Vegetation Child -Vegetable Garden NNE 4,748 Vegetation Child -Vegetable Garden NE 2,414 Vegetation Child -Vegetable Garden ENE 2,237 Vegetation Child -Vegetable Garden E 2,446 Vegetation Child -Vegetable Garden I ESE 1,770 Vegetation Child -Vegetable Garden SE 2,173 Vegetation Child -Vegetable Garden SSE 2,494 Grass / Cow] Meat Child -Nearest Cow S 6,360 Vegetation Child -Vegetable Garden SSW 5,472 Vegetation Child -Vegetable Garden SW 4,909 Vegetation Child -Vegetable Garden WSW 2, t.46 Grass / Cow / Meat Child -Nearest C.: W 4,458 Vegetation Cnild -Vege' table Garden WNW 4,023 Grass / Cow / Meat Child -Nearest Cow NW 6,437 Grass / Cow / Milk Infant -Nearest Milk Cow NNW 4,506 Vegetation Child -Vegetable. Garden

  • Table based on Reference 5, Table 2.1-7; and Reference 1, Section 5.3 l I I

!I I ODCM, V C Sumer, SOUTH CAROLINA ELECTRIC AND GAS CO. 2.0-30

Table 2.2-8 ATMOSPHERIC DISPERSION PARAMETERS FOR CONTROLLING RECEPT 0R LOCATIONS

  • _ SECTOR X/Q D/Q DISTANCE (MILES)

N 2.35E-7 6.80E-10 3.85 I NNE 4.40E-7 1.55E-9 2.95 NE 1.90E-6 7.50E-9 1.50 ENE 1.90E-6 7.90E-9 1.39 E 1.40E-6 5.40E-9 1.52 ESE 2.80E-6 8.80E-9 1.10 SE 2.50E-6 6.80E-9 1.35 SSE 1.30E-6 4.20E-9 1.55 I. S 2.40E-7 3.60E-10 3.95 SSW 3.00E-7 6.50E-10 3.40 t SW 4.40E-7 1.25E-9 3.05 WSW 1.30E-6 5.50E-9 1.52 W 3.00E-7 8.50E-10 2.77 WNW 3.00E-7 9.10E-10 2.50 NW 1.60E-7 4.20E-10 4.00 NNW 3.10E-7 1.15E-9 2.80 I I Table based on Reference 4, Table 2.3-119; and Reference 5, Tables 6.1-10 l through 6.1-14. l I I l I 00CM, V C Summer, SOUTH CAROLINA ELECTRIC AND GAS CO. 2.0-31

2.3 Meteorological Model 2.3.1 Atmospheric dispersion for all releases is calculated using a ground-level, wake-split form of the straight line flow model. 3 atmospheric dispersion (sec/m ) X/Q = 3 average atmospheric dispersion (sec/m ) for a given X/Q = wind direction (sector). 2.0326T (31) = ij NrU 2.032 (2/w)1/2 divided by the width in radians of a 22.5* = sector (0.3927 radians). plume depletion factor at distance r for the appropriate 6 stability class from Figure 2.3-1; (radio;odines and particulates). number of hours meteorological conditions are observed n = gj to be in a given wind direction, windspeed class i, and atmospheric stability class J. total hours of valid meteorological data. N = distance from the containment building to location of r interest (m) wind speed (midpoint of windspeed class 1) at ground u = j level (m/sec). 2 b /2n)I/2 (32) 2 (o + z the lesser of 4 I = z 9, /3 07) whe re, (33) I sertical standard deviation of the plume (in m) at o = z distance r for ground level releases under the stability category indicated by i, from Figure 2.3-2. IlI ODCM, V C Summer, SOUTH CAROLINA ELECTRIC AND GAS C0. 2.0-32

terrain recirculation factor, from Figure 2.3-4 T 3.1416 2 height of the containment building (50.9M) b = temperature differential with vertical separation T (*k/100M). 2.3.2 Relative deposition per unit area for all releases is calculated for a ground-level release. relative deposition per unit area (m-2) D/Q relative deposition per unit area (m-2), for a given D/Q wind direction. 2.55 On n

where, (34) rN D

deposition rate for ground-level releases relative to g distance (r) from the containment building (from Figure 2.3-3). I 2.55 the inverse of the number of radians in a 22.5* sector ( 1 (22.5*)(0.0175 Radians /*)y number of hours wind is in given direction (sector). n total hours of valid meteorological data. N I I I ODCM, V C Summer, SOUTH CAROLINA ELECTRIC AND GAS CO. 2.0-33

Figure 2.3-1 Pluma Deoletion Effect for Ground Level Releases (6) (All Atmospheric Stability Classes) - - - Graph taken from Reference 8, Figure 2 o 8 A o. 8 l / / / l / /. I / A E Ww Y ob l l

  • ew I

~ / 8 lI / 5 / b; o ll / .5# I E g w !a 6, 1 I i i i 1 1 'l / a 6 9 9 A w n N + s o o o o o-6 o o' d-3 Wold NI DNINIVW38 NOllOVHd ODCM, V C Summer, SOUTH CAROLINA ELECTRIC AND GAS CO. 2.0-34

Figure 2.3-2 Vertical Standard Deviation of M2terial in a Plume (o ) (tetters denote Pasquill Stability Class) Z Graph taken from Reference 8, Figure 1 1000 i r I / j r A s / / / '~ / / / l / / f ) / / 1l r r / / / / / / [ I A / / / / / i 3ng / i B ; / / / r / ,f / / / j / / / / / /~ i / ? / / n f,l // / / j D l /// /?/ / / // / // r/,/ ' y G 10 , j j / l / / / / ~ / / / / ~ / / '/ l / f / l / l / 1'O.1 1.0 10 100 3 PLUME TRAVEL DISTANCE (KILOMETERS) Temoerature Channe Pasquill Stability with Heicht (T)(UK/100m) Cateaories Classification <-1.9 A Extremely unstable -1.9 to -1.7 8 Moderately unstable -1.7 to -1.5 C Slightly unstable -1.5 to -0.5 0 fleutral -0.5 to 1.5 E Slightly stable 1.5 to 4.0 F Moderately stable > 4.0 G Extremely stable ODCli, V C Summer, SOUTH CAROLIrlA ELECTRIC ATID GAS C0. 2.0-35 I

l I Figure 2.3-3 Relative Deposition for Ground-Level Releases (D ) (All Atmospheric Stability Classes) 9 Graph taken from Reference 8, Figure 6 10,3 I I 10-4 A N E l N N i N !g h e a h \\ w Q N \\ e $ la-5 ( I A \\ N 1 S X l O \\ \\ E \\ ' d s e 104 I \\ I 10-7 ~ i ~ 0.1 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS) ODCM, V C Summer, S0llTH CAROLIf1A ELECTRIC Afl0 GAS C0. 2.0-36 I

Figure 2.3-4 l Open Terrain Recirculation Factor Graph taken from Reference 7, Figure 2 8 g i ,Y s o I / / E l / y / i ( / 3 / E / Ez l l / E \\ o l l d C 4 O e 6 801DVd NOl103HUO3 l ODCM, V C Surrrner, SOUTH CAROLINA ELECTRIC AND GAS C0. 2.0-37

2.4 Definitions of Gaseous Effluents Parameters Term Definition Section of Initial Use height of the containment building. (2.3.1) b count rate of a station vent monitor corresponding (2.1.1) C to grab sample radionuclide concentrations. count rate of the gas decay system monitor for (2.1.2) c = radionuclioe concentrations to be discharged. deposition rate for ground-level releases relative (2.3.2) O g to the distance from the containment building (from Figure 2.3-3). O average organ dose rate in the current year (mrem /yr) (2.2.1.b) g dose to an individual from radioiodines and radio-(2.2.2.b) D, nuclides in particulate form,and radio nuclides l (other than noble gases) with half-lives greater than eight days (mrem). average skin dose rate in current year (mrem /yr) (2.2.1.a) D 3 average total body dose rate in the current year (2.2.1.a) D t l (mrem /yr) 1 air dose due to beta emissions from noble gas (2.2.2.a) D g radionuclide i (mrad) air dose due to gamma emissions from noble gas (2.2.2.a) D radionuclide i (mrad) relative deposition per unit area (m-) (2.3.2) D/Q l l ODCM, V C Summer, SOUTH CAROLINA ELECTRIC AND GAS C0. 2.0-38 l

I 2.4 Definitions of Gaseous Effluents Parameters (Continued) Term Definition Section of Initial Use sector annual average relative deposition (m )-1 (2.3.2) 2 D/Q based on X/Q. specific value at unrestricted area boundary. (2.2.1.b) relative deposition for unrestr.icted areas per unit (2.2.2.b) D/Q' = area (m )-I for long term releases. plume depletion factor at distance r for the (2.3.1) 6 appropriate stability class from Figure 2.3-1; (radiciodines and particulates). Fraction of current year elapsed at the time of (2.1.1) F l calculation. total body dose f actor due to gamma emissions from (2.1.1) K j 3 isotope i (mrem / year per uCi/m ) from Table 2.1-1. total body d7se factor for Kr-89, the most restric-(2.1.2) K = Kr-89 tive isotcpe from Table 2.1-1. Skin dose factor due to beta emissions from isotope (2.1.1) L j 3 i (mrem /yr per uCi/m ) from Table 2.1-1 Skin dose f actor for Kr-89, the most restrictive (2.1.2) L I Kr-89 isotope, from Table 2.1-1 g air dose factor due to gamma emissions from isotope (2.1.1) M = 3 i (mradlyr per uCi/m ) from Table 2.1-1. air dose f actor for Kr-89, the most restrictive (2.1.2) M Kr-89 isotope, from Taule 2.1-1 I ODCM, V C Summer, SOUTH CAROLINA ELECTRIC AND GAS CO. 2.0-39

I 2.4 Definitions of Gaseous Effluents Parameters (Continued) Term Definition Section of Initial Use air dose factor due to beta emissions from (2.2.2.a) N 3 noble gas radionuclide 1 (mrad per uC1/m ) from Table 2.1-1. s r) number of hours meteorological conditions are (2.3.1) j observed to be in a given wind direction, wind-speed class i, and atmospheric stability class j. total hours of valid meteorological data. (2.3.1) N dose parameter for radionuclide i, (mrem /yr (2.2.1.b) P 3 per uCi/m ) for inhalation and all tritium 2 pathways; and (m -mrem /yr per uCi/sec) for other pathways, from Table 2.2-1. rate of release of noble gas radionuclide 1 (2.1.1) Q$ = (uCi/sec) average rate of release of noble gas radionuclide 1 (2.1.1) Qj for the elapsed fraction of the year, F, (uCi/sec). average release rate of isotope i of radiciodine or (2.2.1.b) Qg' other radionuclides in particulate form and radio-nuclides (other than noble gases), with a half-life I. greater than eight (8) days, in the current year (uCi/sec) cumulative release of noble gas radionuclide i (2.2.2.a) Q = over the period of interest (uCi). cumulative release of radionuclide i of iodine or (2.2.2.b) Q' material in particulate form over the period of interest (uCi). ODCM, V C Summer, 50VTH CAROLINA ELECTRIC AND GAS CO. 2.0-40

2.4 Definitions of Gaseous Effluents Parameters (Continued) Term Definition Section of Initial Use gj rate of release of noble gas radionuclide 1 (2.1.2) = (uCi/sec) from the waste gas decay system. iij average rate of release of noble gas radionuclide (2.1.2) = i from the waste gas decay system for the elapsed fraction of the year, F, (uCi/sec) I R dose factor for radi.onuclide i, (mrem /yr per (2.2.2.b) = uCi/m ) or (m -mrem /yr per uCi/sec) from i Tables 2.2-2 throught 2.2-6. I R count rate per mrem /yr to the skin. (2.1.1) = 3 R t count rate per mrem /yr to the total body. (2.1.1) = DTB limiting dose rate to the total body based on (2.1.1) = the limit cf 500 mrem in one year. l D limiting dose rate to the skin cased on the (2.1.1) = ss limit of 3000 mrem in one year. distance from the containment building to the loca-(2.3.1) I r tion of interest fr.r dispersion calculations (m). 1 count rate per mrem /yr to the skin for the waste (2.1.2) r = s gas decay system monitor only. l I t count rate per mrem /yr to the total body for the (2.1.2) r = waste gas decay system monitor only. D'TB limiting dose rate to the total body based on the (2.1.2) = I limit of 500 mrem in one year (waste gas decay system). I ODCM, V C Summer, SOUTH CAROLINA ELECTRIC AND GAS CO. 2.0-41

2.4 Definitions of Gaseous Effluents Parametert (Continued) Term Definition Section of Initial Use D' limiting dose rate to the skin based on the (2.1.2) I s limit of 3000 mrem in one year (waste gas decay system). R' conservative count rate per mrem,to the skin (2.1.3) = (Xe-133 detection, Kr-89 dose).' conservative count rate per mrem to the total (2.1.3) R' = t body (Xe-133 detection, Kr-89 dosel. conservative count rate per mrem to the skin (2.1.3) r' = s for the waste gas decay system only. conservative count rate per mrem to the total (2.1.3) rt' = I body for the waste gas decay system only. liiniting dose rate to the total body based on (2.1.3) D"TB = the conservative dose rate of 500 mrem / yea.. limiting dose rate to the skin based on the (2.1.3) 0"ss = conservative dose rate of 3000 mrem / year. count rate of the waste gas decay system noble (2.1.2) l S = d gas monitor at the alarm setpoint. count rate of a station vent noble gas monitor (2.1.1) S I y at the alarm setpoint. l count rate of the containment purge noble gas (2.1.1) S = vc monitor at the alarm setpoint. count rate of the plant vent noble gas monitor (2.1.1) S = yp at the alarm setpoint. ODCM, V C Summer, SOUTH CAROLINA ELECTRIC AND GAS C0. 2.0-42

I 2.4 Definitions of Gaseous Effluents Parameters (Continued) Term Definition Section of Initial Use t vertical standard deviation of the plume with (2.3.1) I = i building wake correction. vertical s'andard deviation of the plume (in m.), (2.3.1) a = z at distance r for ground level releases under ( the stability category indicated by I, from Figure 2.3-2. i temperature differential with vertical separation (2.3.1) = (*K/100m). l T terrain recirculation f actor, Figure 2.3-4. (2.3.1) = Ii wind speed (midpoint of windspeed class i) at (2.3.1) = j ground level (r./sec). controlling sector annual atmospheric dispersion (2.2.1.b) W = j at the site boundary for the appropriate pathway. W' relative dispersion for unrestricted areas. (2.2.2.b) = atmospheric dispersion (sec/m ). (2.3.1) X/Q = l [ X/Q sector annual average atmospheric dispersion (2.3.1) I = 3 (sec/m ), specific value at unrestricted area boundary (2.1.1) relative concentrati~on for unrestricted areas (2.2.2.a) X/Q' = 3 (seclm ) for long term releases. I ODCM, V C Sumer, SOUTH CAROLINA ELECTRIC AND GAS CO. 2.0-43

Nen Q0nWO3m g0V36M h FLg Mh h s fe f ff [U3 f N=ngM E CeEaE O.CLh MJJ 0m Mg 13 bDO u,h p hm E i - L f 8 1a a 1 J DG tV WCF RSmW H9RC SP( E N N E EML E A A A T0C W OR C C F OE U N NEOCS S S R C Uf AT T MOY T T T EO DS RN R NS E US SI RCEE E JN CC IF t' T S L n C L R A i E A T EI E LN R M W H LF TAD E H E CRI A SLP E i F I A I R OL R VO V TE N N )E T u A NA AO A E A OC K N AS N R M LDI V PD P AL R C ]R Y T G T T D Y ORNA O O CA T I E LN ,( llI O O LI UO LN A n C A P RU R BR AI Ta A N FK R A P H N T T [ LE t tPO G r N N A F M L T T OT O L D-C A O RA R W

  • I E

t N R CU u GA S K N C w T P Jt f D e N R U N R N "$a E A L t D I O D OP L O A C t I C N t I L D A L N L T F H C N N S W G E A I C C T .R R I E G I R' A T V T C b p O E A hllll T EO u ut N t A -(llg E RA L L S L D T R s D A E N N R G NI N A TA En G R S CY C V IF H w JT N OD d .M R O D i Ik IO MR L E t V S,, " G BO T P h f E A M NE t G N E R T EN E R N R g l ] DW T f b AEA CS 4 N R AT N YE S T tau R t T EC arf M O R _h NTD If O N B D I N - O W E N UW A PN L N E DW e,_ _- S T EA E A tl B CS SR NAT Y U M S YE S H SA I TAU T I L T R ART E D NTD s i M I N h 4O G PW DW N T sl EA w, A CS N AT N VE A T I U X DW LI w,_ e" EA tl A CS A N AT A YE R K T S Y E B G U A I D# S L TAEA D CS wy S I NAT Y N KTE S G T E M DW T w,_ EA fl A CS N AT N YE = y 1 "m "m pp I U I O O R p R R F0 F U F O f U F L G L G L G t U T N T M T H LG E I E T H R N N' E I E I G R N G R G R N G eF H F p F t E I f t E I H H F L L T P T F LE E A E T N T P A R R E E A R R C C F H 4 A tF H C L R I H A F R A T C T C L R E O E O TC R A RA EO L L RAL F t F H F e ( E I E I M L f P T P LE t A E A T P R R E A R "m gg V M E g A N I gg T N g y N.O Y I ' i ;i i r

  1. l

3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING 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. I I l l 00Ca, v c Summer, SOUTH CAROLINA ELECTRIC AND GAS C0. 3.0-1

TABLE "3.0-1 1 RADIOLOGICAL ENVIP.ONMENTAL MONITORING PROGRAM VIRGIL C. SUMMER NUCLEAR STATION Page 1 of.10 Sample Locations Exposure Pathway Criteria for Selection of Sampling and Loca-Type and Frequency of and/or Sampic Sample Number and Location Collection Frequency tion (l) Hi/Dir Analysis AIRBORNE I. Particulates A 3 Indicator samples to Continuous sampler 2 1.1 SW Gross beta following be taken at locations operation with 5 1.3 SE filter change; Monthly (in different sectors) weekly collection. 10 2.4 NNE composite (by location) beyond but as close to for gamma isotopic, the exclusion boundary as practicable where the highest offsite. sectoral ground level concentrations are anticipated.(2) B 1 Indicator sample to be 6

1. l ESE taken in the sector be-yond but as close to the exclusion boundary as practicable correspond-ing to the residence having the highest anticipated offsite ground level concentration or dose. 2) t C 1 Indicator sample to be 14(4) 5.2 W 4

l teken nt the location of 1 oneofthedairiesmosg} } likely to be affected. F ? ~

E c s s / TABLE 3'0-1 (Continued) Page 2 of 10 Sample Locations Exposure Pathway Criteria for Selection of Sampling and Loca7 ) Type and Frequency of and/or Sample Sample Number and Location Collection Frequency tion Mi/Dir Analysis

AIRBORNE, D 2 Control samples to be 17 24.7 SE (continued) taken at locations at least 10 air miles from 16 28.0 W the site and not in the i

most prevalent wind directions.(2) II. Radiciodine A 3 Indicator samples to Continuous sampler 2 1.1 SW Camma isotopic screening be taken at two loca-operation with weekly 5 1.3 SE of all five indicators 4 tions as given in I.A canaister collection. 10 2.4 NNE with conjunctive screen-above. ing of the two controls. If screening is positive, each sample will be sub-jected to isotopic analysis for iodine. B 1 Indicator sample to 6

1. i 'ESE be taken at the lo-cation as given in 4

I.B above. i C 1 Indidator sample to be 14 5.2 W 4 taken at the location as 1 given in I.C above. 1 D 2 Control samples to be 17 24.7 SE taken at locations similar in nature to A-C 16 28.0 W l l above. i F ? w )

m M j TABLE 3.0-1 (Continued) Page 3 of 10 Exposure Pathway Criteria for Selection of Sampling and Sample Locations Type and Frequency of and/or Sample Sample Number and Location Collection Frequency Location Mi/Dir Analysis

AIRBORNE, (continued)

III. Direct A. 5 Indicator samples to Monthly exchange.(5)

  1. 's 2, 5, 6, 10, Gamma dose monthly (5) be taken at the loca-Two or more dosi-and 14 i

tions as given in I.A meters at each l through D above. location. B. 3 Additional indicator 1 1.3 S. samples to be taken in 4

1. 2 NW sectors different from 8

1.3 ENE III.A above, beyond but as close to the exclu-i I sion boundary as prac ticable. 1 C. Control samples to be 16 28.0 W l tdken at the locations 17 24.7 SE 'l as given at I.D above. j D. 1 Additional control 18 16.5 S sample to be taken at a location as set forth in I.D above l E. Additional Sites 3 .8 WSW'

i 7

1.7 E 9 2.6 NE t i 11 3.6 NNE l 12 4.3 N i i 13 2.9 NNW !l 15 2.3 SSW l 19 17.9 ESE 4 20 22.0 NW i F. Accident Evaluation . Quarterly exchange. (5) 41 3.7 S Gamma dose quarterly. Quarterly Exchange (7) Two or more dosi-42 3.6 SSW I Program meters at each 43 4.7 SW w 'o location. 44 2.3 WSW i k 45 5.4 WSW l 46 3.7 WNW r 47 1.0 NW t t l t 8

M W M i TABLE 3.021 (Continued) Page 4 of 10 Exposure Pathway Criteria for Selection of Sampling and Sample Locations' Type and Frequency of and/or Sample Sample Number and Location Collection Frequency Location Hi/Dir Analysis

AIRBORNE, (Continued)

III. Direct F. (Continued) 48 2.4 NW 49 4.6 NNW 50 5.6 N 51 5.6 N s 52 4.3 NNE l 53 3.6 NE 54 2.2 ENE 55 3.2 E 56 2.0 ESE 57 2.7 SE 58 2.4 SSE 59 2.1 SSE 60 5.7 WSW / WATERBORNE l IV. Surface A. 1 Indicator sample to Time composite samples.. 21(3)(6)2.7 SSE Gamma isotopic with Water be taken at a location. with collection every quarterly composite (by which allows for mixing month (corresponds to location) to be analyzed for tritium.(7) and dilution in the USG'co fnuoussampling ultimate receiving site). - river. I y) i <n

[ ) l TABLE-3.0-1 Wontinued) Page:s of 10 Sample Locations Type and Frequency of Exposure Pathway Criteria for Selection of Sampling and Loca- ) Hi/Dir tion (l Analysis and/or Sample Sample Number and Location Collection Frequency 22(3) 12-15 NNW 1 WATERB010lE, B 1 Control aample to be (continued) taken at a location on the receiving river, suffi-l ciently far upstream such that no effects of pumped storage operation are anticipated. I C 1 Indicator sample from 17 24.7 S 5 I location immediately l upstream of the nearest ] downstream municipl water supply 1 D 1 Indicator sample to be Grab sam ling 23(3) <1 E As in V above. / ) taken in the upper reser-monthly 5) 1 4 l voir of the pumped storage facility. ~ 24(3) 4,7 y l E 1 Indicator sample to be taken in the upper reser-voir's non-fluctuating recreational area. 18(3) 16.5 S y F 1 Control sample to be I taken at a location on a j separated unaffected watershed reservoir. 4 grab 26 Onsite Gamma isotopic and V. Ground Water A 2 Indicator samples to Quarterly (7) be taken within the ex-sampling 27 Onsite tritium analyses 1 4 quarterly.(7) clusion boundary and in the direction of poten-lw tiall,y affected ground water supplies. ' * *a I:n l l l t I

S S i C TABLE 3.0-1 A sntinued) Page 6 of 10 i Sample Locations Exposure Pathuay Criteria for Selection of Sampling and Loca-Type and Frequency of and/or Sataple Sample Ntuaber and 1.ocation Collection Frequency tion (I) Hi/Dir Analysis 1 WATEltDoluiE, B 1 Control sample from an l (continued) unaffected location.- 16 28.0 W VI. Drinking A 1 Indicator sample from Monthly 1}rab Honthly(5) gag,,, 1,otopic 4 Wter nearby public ground samplingt5) 28 1.3 ESE water. supply source. and gross Bet nalyacs and quarterly tritium 4 j analyses I B 1 Indicator (finished Monthly Brab 17-24.7 S 2 water) sample from the sampling (5) 5 i nearest downstream I water supply. INCESTI0tt t Vll.'MilkIS) A 1 Indicator sample to Semi-monthly when 14I4) 5.2 W Gamma isotopic and I-be taken at the location animals on analysis semi-monthly 1 of one of the dairies

pasture, monthly when animals are(o 4

5 other times. (5) pastur4* monthly at l most likely tn be affected.(2) (5) other times 16 28.0 W B 1 Control sample to be j 1 taken at the location of { a dairy 10-20 miles dis-- tant and not in the most prevalent wind direction.(2) ~ C 1 Indicator grass (for-Monthly when available(5) 6 1.1 ESE Gamma Isotopic 1 4 age)aample to be taken at one of the locations beyond but as close to the exclusion boundary as practicable where the F highest offsite sectoral i ? ground level concentra-tione are anticipated.(2)

\\ ) ) ( TABLis 3.0-1 (continued) Page 7 of 10 Sample Locations Exposure Pathway Criteria for Selection of Sampling and Loca g Type and Frequency of and/or Sample Sample Number and Location Collection Frequency tion Mi/Dir Analysis INGESTION, D 1 Indicator grass (for-14(4) 5.2 W 4 (continued) age) sample to be asken at the location of VIII.A above when animals are on pasture. E 1 Control grass (forage) sample to be taken at the location of VIII.B above. 16 28.0 W VIII. Food A 1 Indicator sample to be Annually at the 6 1.1 ESE Gamma isotopic on edible Products taken at a nearby garden approximate median portion. Radioiodine on 1 likely to be affected. harvest t;ime for green leafy vegetables. the area. Samples, if available, will i include: green leafy, fruit, and grain. 4 .i B 1 Control sample for the 18( } 16.5 S j same foods taken at a 8 location at least 10 miles distant and not in the 'most prevalent wind di-rection. IX. Fish A 1 Indicator sample to be Semi-annual } collec-23( 0.3-5 Camma isotopic on edible 1 taken at a location in tion of the following portions semi-annually 4 the upper reservoir. specie types if available : bass, bream, crappie; catfish, carp; forage fish (shad). ?m

\\ i J TABLE.3.0-1 (Continued) Page 8 of 10 1 Sample Locations Exposure Pathway Criteria for Selection of Sampling and Loca77) Type and Frequency of and/or Sample Sample Number and Location Collection Frequency tion Hi/Dir Analysis INCESTION, B 1 Indicator sample to be 21( } 1-3 1 (continued) taken at a location in the lower reservoir 4 C 1 Indicator sample to be 24( } 4-5 N 1 taken at a location in the upper reservoir's non-fluctuating recreational area. 1 4 ^ 1 Control sample to be 22( ) 12-15 NNW l D taken at a location on the receiving river, sufficiently far up-stream such that no effects of pumped storage operation are anticipated. l AQUATIC X. Sediment A l' Indicator sample to be Semi-annual grab 23(3) 0.3-4 Gamma isotopic (3) 1 taken at a location in sample (9) the upper reservoir. 4 m t

I [ Page 9 of 10 TABLE 3.0-1 -(Continued) Sample Locations E>.posure Pathway Criteria for Selection of Sampling and Loca g Type and Frequency of and/or Sample Sample Number and Location Collection Frequency tion Hi/Dir Analysis AQUATIC B 1 Indicator sample to be 24( ) 4-5 N 1 (continued) taken in the upper reser-voir's non-fluctuatin, s recreational area. C 1 Indicator sample to be 21 1-3 y taken on the shoreline of i the lowe reservoir. I3) D 1 Control sample to be 22 12-15 1 taken in receiving river, sufficiently far upstream such that no effects of pumped storage operation are anticipated. ,, a s ~ l 4 Location numbers refer to Figures 3.0-1 and 3.0-2 ( ) Sample site locations are based on the meteorological analysis for.the period of record as pres'ented in Chapters 5 and 6.(Reference 5) ( } Though generalized areas are noted'for simplicity of sample site enumeration, airborne, water and sediment l1 sampling is done at the same location whereas biological sampling sites are generalized areas in order to i reasonably assure availability of samples. F i ? Es e

5M M M M M M M M TABLE 3.0-1 (continued) l Page 10 of 10 ( } Milking animal and garden survey results will be analyzed annually.' Should the survey indicate new dairying activity of a significant nature (5 or more cows milking) in a quadrant (s) other than.W or NW and closer than 4 5-7 miles, the owners shall be contacted with regard to a contract for supplying sufficient samples. If contractural arrangements can be made, the site (s) will be added for additional milk sampling. ( } Not to exceed 35 days. (6) Time composite samples are samples which are collected with equipment capable of collecting an aliquot at s time intervals which are short (e.g. hourly) relative to the compositing period. ( } At least once per 100 days. ( } At least once per 18 days. ( ) At least once per 200 days. i 4 NOTE: Deviations from this sampling ochedule may occasionally be necessary if sample media are unobtainable due to hazardous conditions, seaconal unavailability, insufficient sample size, malfunctions of auto-matic sampling or analysis equipment and other legitimate reasons. If specimens are unobtainable due f to sampling equipment malfunction, every effort shall be made to complete corrective action prior to the end of the next sampling period. Deviations from sampling-analyses schedule will be described in the annual report, t 0 8 e 7

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