ML20128A075
| ML20128A075 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 05/31/1985 |
| From: | TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | |
| Shared Package | |
| ML20128A054 | List: |
| References | |
| PROC-850531, NUDOCS 8507020560 | |
| Download: ML20128A075 (102) | |
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OFFSITE DOSE CALCULATION MANUAL FOR TEXAS UTILITIES GENERATING COMPANY COMANCHE PEAK STEAM ELECTRIC STATION MAY 1985 i
i B507020560 850627 PDR ADOCK 05000445 A PDR
TABLE OF CONTENTS
- 8. age List of Tables iv List of Figures v Cross Reference.to Technical Specifications vi References viii Introduction ix
. I 1.0 LIQUID EFFLUENTS 1-1 1.1 General Methodology for Determining Liquid 1-1 Effluent Monitor Setpoints 1.1.1 Isotopic Concentration of the Waste Tank 1-2 1.1.2 Maximum Effluent Flow Rate (f) 1-3 1.1.3 Dilution of Liquid Effluents Due to 1-3 Circulating Water Flow (F) 1.1.4 Actual Dilution Factor (ADF) 1-4 1.1.5 Required Dilution Factor (RDF) 1-4 1.1.6 Upper Setpoint Limit for 1-6 Detector XRE-5253 1.2 Dose Calculation for Liquid Effluents 1-8 1.2.1 Calculation of Dose Due to a Batch Release 1-9 1.2.2 Calculation of Dose Due to Radionuclide 1-11 Buildup in the Lake 1.3 Dose Projections for Liquid Effluents 1-12 1.4 Service Water Effluent Radiation 1-15 Monitors 1RE-4269/4270 1
1.5 Turbine B211 ding Sump Effluent Radiation 1-16 Monitor 1RE-5100 1.6 Definitions of Common Liquid Effluent Parameters 1-17 i
TABLE OF CONTENTS Page 2.0 GASEOUS EFFLUENTS 2-1 2.1 Gaseous Effluent Monitor Setpoints 2-1 2.1.1 Dose Rates Due to Noble Gases 2-2 2.1.2 Plant Vent Stack Noble Gas 2-5 Monitors XRE-5570A/B and XRE-5567A/B 2.1.3 Plant Vent Flow Monitors 2-7 2.1.4 Auxiliary Building Ventilation Exhaust 2-8 Monitor XRE-5701 2.1.5 Containment Atmosphere Caseous 2-11 Monitor 1RE-5503 2.1.6 Dose Rates Due to Radioiodines, 2-13 Tritium, and Particulates 2.1.7 Plant Vent Stack Iodine Monitors 2-14 XRE-5575A/B 2.1.8 Plant Vent Stack Particulate 2-15 Monitors XRE-5568A/B 2.2 Gaseous Effluent Dose Calculations 2-17 2.2.1 Air Dose in Unrestricted Areas 2-17 2.2.2 Dose to an Individual 2-18 2.2.3 Dose Projections for Gaseous Effluents 2-20 2.2.4 Dose Calculations to Support Other 2-21 Technical Specifications 2.3 Meteorological Model 2-40 l 2.3.1 Dispersion Calculations 2-40 2.3.2 Deposition calculations 2-42 2.3.3 Collection and Processing of Real 2-42 Time Meteorological Data i 2.4 Definition of Gaseous Effluent Parameters 2-44 t
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TABLE OF CONTENTS, CONT.
M 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING 3-1 3.1 Sampling Locations 3-1 3.2 Interlaboratory Comparison Program 3-1 APPENDIX A. Pathway Dose Factor (Pg ) Determination A-1 B. InhalationPathwayFactor(Rf,,) Determination B-1 C. Ground Plane Pathway Factor (R ,) Determination C-1 D. Grass, Cow-Milk Pathway Factor (R ,,) Determination D-1 E. Cow-Meat Pathway Factor (R ,) Determination E-1 F. Vegetation Pathway Factor (R ,,) Determination F-1 d
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Cross Reference to Technical Specifications Technical Specification No. Requirement ODCM Section 3.11.1.1 Liquid effluent concentration 1.1 3.11.1.2 Dose due to liquid effluents 1.2 3.11.1.3 Dose projections for liquid releases 1.3 3.11.2.1.a Dose rate due to noble gases 2.1.1 3.11.2.1.b Dose rate due to iodine, tritium, and 2.1.6 particulates with half lives greater than eight days 3.11.2.2 Air dose due to noble gases 2.2.1 3.11.2.3 Doses due to iodines, tritium, and 2.2.2 particulates with half-lives greater than eight days 3.11.2.4 Dose projections for gaseous releases 2.2.3 3.11.4 Total dose due to releases of radioactivity 2.2.4 and direct radiation 3.12.1 Description of radiological environmental 3.1 sampling locations 3.12.2 Dose calculations for identifying changes 2.2.4 to environmental sampling locations 3.12.3 Description of the Interlaboratory 3.2 Comparison Program 3.3.3.10 Radioactive liquid effluent monitoring channels alarm / trip setpoints o liquid waste monitor (XRE-5253) 1.1.6 o turbine building sump monitor (1RE-5100) 1.5 o service water monitor (1RE-4269/4270) 1.4 vi ,
List of Figures Figure Title Pajya 1.1 Liquid Effluent Discharge Pathways 1-20 1.2 Example Calibration Curve for Liquid 1-21 Effluent Monitors 1.3 Circulating Water Pump Curves 1-22 1.4 Simplified Liquid Waste Processing System 1-23 2.1 Simplified Gaseous Waste Processing System 2-48 2.2 Plume Depletion Effect for Ground Level 2-49 Releases 2.3 Vertical Standard Deviation of Material 2-50 in Plume 2.4 Relative Deposition for Ground-Level 2-51 Releases 2.5 Open Terrain Recirculation Factor 2-52 3.1 Environmental Sampling Locations 3-7 4
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Cross Reference to Technical Specifications Technical Specification No. Requirement ODCM Section 3.11.1.1 Liquid effluent concentration 1.1 3.11.1.2 Dose due to liquid effluents 1.2 3.11.1.3 Dose projections for liquid releases 1.3 3.11.2.1.a Dose rate due to noble gases 2.1.1 3.11.2.1.b Dose rate due to iodine, tritium, and 2.1.5 particulates with half lives greater than eight days 3.11.2.2 Air dose due to noble gases 2.2.1 3.11.2.3 Doses due to iodines, tritium, and 2.2.2 i
particulates with half-lives greater than eight days
- 3.11.2.4 Dose projections for gaseous releases 2.2.3 3.11.4 Total dose due to releases of radioactivity 2.2.4 and direct radiation 3.12.1 Description of radiological environmental 3.1 sampling locations 3.12.2 Dose calculations for identifying changes 2.2.4 to environmental sampling locations a
3.12.3 Description of the Interlaboratory 3.2 Comparison Program 3.3.3.10 Radioactive liquid effluent monitoring channels alarm / trip setpoints o liquid waste monitor (XRE-5253) 1.1.6 o turbine building sump monitor (IRE-5100) 1.5 o service water monitor (1RE-4269/4270) 1.4 vi
Cross Reference to Technical Specifications, continued Technical Specification No. Requirement ODCM Section Q
3.3.3.11 Radioactive gaseous effluent monitoring channels alarm / trip setpoints o noble gas monitors 2.1.2 XRE-5570A/PVG-084 and XRE-5570B/PVG-085 XRE-5567A/PVG-384 and XRE-5567B/PVG-385 o iodine monitors 2.1.7 XRE-5575A/PVI-094 and XRE-5575B/PVI-096 o particulate monitors 2.1.8 XRE-5568A/PVP-093 and XRE-5568B/PVP-095 o flow rate monitor 2.1.3 XRE-5570A/PVF-684 and XRE-5570B/PVF-685 o waste gas holdup system monitor 2.1.4 (auxiliary building vent monitor)
XRE-5701 o sampler flow rate monitor XFT-5570A4/B4 2.1.3 3.3.3.1 Radiation monitoring channels alarm / trip
, setpoint o Containment atmosphere gaseous 2.1.5 monitor (containment vent monitor) 1RE-5503 6.9.1.7 Assessment of radiation doses due to liquid 2.2.4 and gaseous effluents released during the previous year 6.9.1.7 Assessment of doses to members of the 2.2.4 public inside the site boundary 6.9.1.7 Assessment of doses to the most likely 2.2.4 exposed member of the public from reactor releases and direct radiation vii ,
REFERENCES
- 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).
- 2. Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I. U. S. NRC Regulatory Guide 1.109, Rev. 1 (October 1977).
- 3. " Environmental Report," Texas Utilities Generating Company, Comanche Peak Steam Electric Station.
4 " Final Safety Analysis Report," Texas Utilities Generating Company, Comanche Peak Steam Electric Station.
- 5. Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors, U.S. NRC Regulatory Guide 1.111 (March 1976)
- 6. Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Release from Light - Water - Cooled Reactors, U. S. NRC Regulatory Guide 1.111, Rev. 1 (July 1977).
- 7. Meteorology and Atomic Energy; Edited by Slade, D. H.; U. S.
Department of Commerce (July 1968).
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INTRODUCTION The OFFSITE DOSE CALCULATION MANUAL (ODCM) is a supporting document of the RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS. As such the ODCM describes the methodology and parameters to be 'ised in the calculation of offsite doses due to radioactive liquid and gaseous affluents and in the calculation of liquid and gaseous affluent monitoring instrumentation :
alarm / trip setpoints. The ODCM contains a list and graphical description of the specific sample locations for the radiological environmental monitoring program. Liquid and Gaseous Rsdweste Treatment System configurations are shown in Figures 1.4 and 2.1.
The ODCM will be maintained at the plant for use as a reference guide and training document of accepted methodologies and calculations. Changes in the calculation methods or parameters will be incorporated into the ODCM in order to assure that the ODCM represents the present methodology in all applicable areas. Licensee initiated changes in the ODCM will be implemented in accordance with Section 6.14.2 of the Technical Specifications.
Offsite dose calculations utilized to implement the RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS 3.11.1.2 (dose due to liquid releases), 3.11.2.2 (air dose due to noble gases), 3.11.2.3 (dose due to iodines, tritium and particulates in gaseous releases), and 3.11.4 (total dose) may be performed using either the GA Technologies RM-21 Report Processing Computer or the methodology given in this manual. For gaseous effluent dose calculations, ix
l the basic equations used by the RM-21 to perform these calculations are the same as those given in this manual. However, in lieu of annual average dispersion parameters, computed hourly sector-averaged dispersion parameters are used with concurrent radiological release data as input in these equations. For liquid effluent dose calculations, the methodology used by the RM-21 is similar to that given in Regulatory Guide 1.109. The RM-21 methodology differs from that in this manual in that it includes a correction for the decay of isotopes for the period between the time of the release and consumption by the receptor. This correction will be negligible for long lived isotopes, but will result in a difference in the doses due to isotopes with relatively short half-lives. Otherwise the methodologies used by the RM-21 are the same as those described in this
, manual.
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SECTION 1.0 LIQUID EFFLUENTS The Comanche Peak Steam Electric Station, Units 1 and 2, is located on the Squaw Creek Reservoir which serves as the point of supply and discharge for the plant circulating water. Liquid releases are made via the Circulating Water Discharge Canal. Discharge pathways for the liquid radwaste sources are shown in Figure 1.1. Although no significant releases of radioactivity are expec.ted from the General Service Water System, this effluent pathway is monitored as a precautionary measure.
1.1 GENERAL METHODOLOGY FOR DETERMINING LIQUID EFFLUENT MONITOR SETPOINTS Normal liquid releases from the radwaste system will be batch type releases and will originate from the laundry holdup tanks and waste monitor tanks and terminate in Squaw Creek Reservoir. To ensure such discharges do not exceed the limits of 10CFR20, Appendix B.
Table II, Column 2 at the release point to the unrestricted area, as specified in Technical Specification 3.11.1.1, an in-line radiation detector (XRE-5253) monitors discharges to the circulating water discharge canal. XRV-5253 is the isolation valve controlled by detector XRE-5253. The isolation valve shuts automatically if the detector alarms or is placed out of service. The methodology for determining the setpoint for detector XRE-5253 is given in the following sections. It should be noted that the liquid effluent monitor setpoint values as determined using the methodology from the following sections will be regarded as upper bounds for the actual setpoint adjustments. That is, setpoint adjustments are not required if the existing setpoint level corresponds to a lower value 1-1
than the calculated value. Setpoints may be established at values lower than the calculated values, if desired. Further, if the calculated value should exceed the maximum range of the monitor, the setpoint shall be adjusted to a value that falls within the normal operating range of the monitor.
1.1.1 Isotopic Concentration of the Waste Tank Determine the isotopic concentration of the waste tank to be released:
[Cg= {C +
(C,+ C, + Ct + Cp ,)
i g Where: [C f= Sum of the concentrations of each radionuclide, i, 1
in the waste tank (uCi/ml)
[C = Sum of the concentrations of each measured gamma 8
8 emitter, g, (uCi/ml) as required by Surveillance Requirement 4.I1.1.1.1.
C, = concentration of alpha emitters as measured in the monthly composite sample (uci/ml) required by Surveillance Requirement 4.11.1.1.1. (Sample analyzed for gross alpha only)
C, = concentration of O'Sr and 90 Sr as measured in the quarterly composite sample (uC1/ml) required by Surveillance Requirement 4.I1.1.1.1.
Cg = concentration of 'H as measured in the monthly composite sample (uci/ml) required by Surveillance Requirement 4.I1.1.1.1.
1-2
55 C = concentration of Fe Fe as measured in the quarterly composite sample (uCi/ml) required by Surveillance Requirement 4.11.1.1.1.
1.1.2 Maximum Effluent Flow Rate (f)
The effluent disci.arge rate is determined from the number of radwaste system pumps running and their capacity. The radwaste system pumps that can be utilized to discharge liquid effluents to the circulating water discharge canal consist of the following:
Laundry Holdup and Monitor Tank Pump - 100 gpm Waste Monitor Tank Pump #1 - 100 gpm Waste Monitor Tank Pump #2 - 100 gpm i
Normally, only one. waste tank will be discharged at a time.
XRE-5253'isanin-linep$cessmonitorwhich,duetophysicalflow restric'tions, allows a maximum flow rate of 46 gps. As a worst case s
c:mdition, the effluent flow rate}(f) will be determined based on s^
the capacity of one tiank\being ;iumped (100 gpm). This built in 6, t ~7,4 ' .
t safety factor.of 2.2 ensures that tt.e effluent flow rate is not
, i i .m being underestimated. This maximum effluent flow rate of 100 gpm willbeuse(.inthecalculationofdilutionfactorforallliquid radwaste system haEch discharges.
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1.1.3, Dilution ob Liquid Ef fluents Due. to Circulatir.g Parer F'lcu (F)
. ~ t Snc'eIiqld' Affluent from the,'radvaste tredtment stem is mixed
, i'9 .
, ;)
x with circulNing 3, watw prior to bel.pg y -
d!.schseted to Squaw Creek-
, , 1
(
g ^
Reservoir, khe setpoint for detector XRE-5253 is a function of trie
- circulating water flow rate. The maximum circulating water flow
,\-
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y ,
~Q % o i - - .; i >-
4,, ,
i 1- 3 e g k * \
3 s . -
4 rate per plant is 1.1 million gpm. This is determined from the Ingersoll-Rand pump curves (Fig. 1.3) which indicate a flow rate per pump of 275,000 gpm. The actual circulating water dilution flow is given by:
F(diluting flow) = (275,000 gpm/ pump) x (# of pumps) x SF Where: SF = Safety Factor of (.9). '
This coupensates for flow fluctuations from the rate predicted by the circulating water pump curves (Fig. 1.3).
1.1.4 Actual Dilution Factor (ADF)
ADF is the ratio of the effluent flow rate plus the circulating water flow rate divided by the effluent flow rate.
~~
ADF = (f + F)/f Where: f = 100 gpm F = (275,000 gpm/ pump) x (# of pumps) x SF NOTE: If radioactivity is detected in the Reservoir, an adjusted circulating water flow rate, F', shall be used in place of F in the calculation of ADF. See section 1.1.6 for the calculation of F'.
1.1.5 Required Dilution Factor (RDF)
The required dilution f ctor ensures that the maximum permissible concentrations expressed in 10CFR20, Appendix B, Table II, Column 2*
are not exceeded during'a discharge.
- MPCs listed in 10CFR20 give values for each isotope in both a soluble and insoluble form. The lowest value for each isotope should be used.
1-4
t RDF=(7,(C/MPC))
g i
=();(C/MPC)+(C,/MPC,+C,/MPC g + C /MPC t
8
+CFe/MPC p ,))
Where: MPC = Maximum Permissible Concentration of Radionuclide i All other variables and subscripts are previously defined.
NOTE: If RDF is less than 1, the tank effluent meets discharge limits without dilution. For conservatism, set RFD equal to 1.0. The maximum value for the high alarm setpoint for detector XRE-5253 would then be calculated in accordance with the equation for C y in the following section.
- see footnote on page 1-4.
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1.1.6 Upper Setpoint Limit for Detector X-RE-5253 Cy , = (ADF/RDF) x C Where: Cy ,= The liquid waste effluent monitor ale.rm setpoint.
This corresponds to the gamma concentration in the undiluted waste stream which after dilution would result in MPC-level releases (uCi/ml).
All other variables are as previously defined.
As a further considsration, the reservoir into which the diluted radwaste flows may build up a concentration of radioactive isotopes.
It is therefore necessary to account for recirculation of previously discharged radionuclides. This is accomplished as follows:
F' = F (1 - (C{/MPC))
f Where: F' = Adjusted Circulating Water Flow Rate C{ = Concentration of radionuclide i in the Reservoir (uCi/ml) as measured in the analysis of the monthly j sample of the Reservoir required by Surveillance i
, Requirement 4.12.1.
[
MPC = Maximum Permissible Concentration of Radionuclide i l F = (275,000 gpm/ pump) x (# of pumps) x SF NOTE: If C{ is less than LLD then F' = F and no adjusted flow
\
rate need be considered in the calculation of ADF. LLD is the smallest concentration of radioactive material in l a sample that will be detected with a 95% probability.
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- see footnote on page 1-4 1-6 i
When considering the mixture of nuclides in the liquid effluent stream in terms of detector sensitivity, the most probable nuclides present would be those referenced in Technical Specification 3/4.11.1.1. Figure 1.2 is a representative energy spectrum response for the RD-33 type detector used in XRE-5253. This curve illustrates that for any given mixture of the most probable gamma emitting nuclides present, the conversion factor between counts per minute and microcuries per milliliter remains relatively constant..
60 In fact between Cs and Co, the total change in sensitivity is approximately 7%. Because this is well within the accuracy of measurement, there is no need to change the software sensitivity for given varied effluent concentrations. However, should the concentration of previously unexpected nuclides become significant. '
further evaluation weuld be required.
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l.2 Dose Calculation for Liquid Effluents For implementation of Technical Specification 3.11.1.2, the dose commitment from the release of liquid effluents will be calculated once per 31 days and a cumulative summation of the total body and organ dose commitments will be maintained for each calendar quarter and each calendar year. The cumulative dose over the desired time period (e.g., the sum of all doses due to releases during a 31 day period, calendar quarter, or a calendar year) will be calculated using the following equation:
DT = ][D k + ][D(lake) k m Where: DT = the dose commitment to the total body or any organ due to all releases during the desired time interval (mrem).
Dk = the dose commitment received by the total body or any organ during the duration of batch release
, k (mrem). The equation for calculating D is given k
in Section 1.2.1.
D(lake) = the dose commitment received by the total body or any organ during a 31 day period, m, due to the buildup in the lake of previously discharged radionuclides. The equation for calculating D(lake) ,is given in Section 1.2.2.
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1.2.1 Calculation of Dose Due to a Batch Release The dose commitment to the total body or any organ due to a batch release will be calculated using the following equation:
D k
= A t C F gT k ik k Where: t k = the time duration of'the batch release k, in ,
hours C
k = the isotopic concentration (uCi/ml) of radionuclide i found in the pre-release sample for batch release k. Concentrations are determined primarily from gamma isotopic analysis of the liquid effluent sample.
For Sr, Sr, H, 55Fe and alpha emitters, the last measured value will be used in the dose calculation.
Fk = the near field average dilution factor during a liquid effluent release. This is defined as the ratio of the average undiluted liquid effluent flow rate to the average circulating water flow rate during the release. The average liquid effluent flow rate is based on the actual flow past the monitor into the circulating water.
F = average undiluted liquid effluent flow rate k
circulating water low rate a
?
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A = the site related ingestion dose commitment factor for the total body or any organ, T, for each identified gamma or beta emitter (mrem /hr per uCi/ml). A is calculated as follows:
l A = 1.14x10 5 (U,/D + Uf BFg ) DF g 5
Where: 1.14x10 = unit conversion factor, U,= adult water consumption, 730 liters /yr Ug = adult fish consumption, 21 kg/yr BFg = bioaccumulation factor for
, radionuclide, i, from Table A-1, Ref. 2 (pCi/kg per pCi/1)
DFf = adult dose conversion factor for radionuclide, i, from Table E-11, Ref. 2 (mrem /pCi ingested)
D = Dilution factor from the near field area within k mile of the release point to the potable water intake for the adult water consumption, 1.0 for CPSES, (unitiess)
Calculated values for A are given in Table 1.1. .
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1.2.2 Calculation of Dose Due to Radionuclide Buildup in the Lake The dose contribution due to buildup of previously discharged radionuclides in the lake must be considered in the committed dose calculation only if they are detected in the water of Squaw Creek Reservoir. Tlie contribution to the total dose due to this buildup is determined as follows:
(A)ifC{islessthanorequaltoLLD, D(lake) ,= 0 (B)ifC{isgreaterthanLLD, D(lake) ,= A tC{
Where: t = 744 hours0.00861 days <br />0.207 hours <br />0.00123 weeks <br />2.83092e-4 months <br /> (31 days) or other time period of interest C[=concentrationofradionuclideiinthe reservoir
. All other variables are previously defined.
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1.3 DOSE PROJECTIONS FOR LIQUID EFFLUENTS Dose projections required to fulfill the requirements of Technical Specification 3.11.1.3 shall be performed using the methodology in Section 1.2. If required, doses shall be projected for the whole ,
body and for any organ in a 31 day period using conservative effluent and dilution flow rates. This 31 day period shall be that period ending on the day of the anticipated release.
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TABLE 1.1 SITE RELATED INGESTION DOSE COMMITMENT FACTOR A (mrem /hr per uCi/ml) I ISOTOPE BONE LIVER T-BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E+00 8.96E+00 8.96E+00 8.96E+00 8.96E+00 8.96E+00 8.96E+00 C-14 3.15E+04 6.30E+03 6.30E+03 6.30E+03 6.30E+03 6.30E+03 6.30E+03 P-32 4.62E+07 2.87E+C6 1.79E+06 0.00E+00 0.00E+00 0.00E+00 5.20E+06 Cr-51 0.00E+00 0.00E+00 1.49E+00 8.94E-01 3.29E-01 1.98E+00 3.76E+02 Mn-54 0.00E+00 4.76E+03 9.08E+02 0.00E+00 1.42E+03 0.00E+00 1.46E+04 Fe-55 8.87E+02 6.13E+02 1.43E+02 0.00E+00 0.00E+00 3.42E+02 3.52E+02 Fe-59 1.40E+03 3.29E+03 1.26E+03 0.00E+00 0.00E+00 9.19E+02 1.10E+04 Co-58 0.00E+00 1.51E+02 3.39E+02 0.00E+00 0.00E+00 0.00E+00 3.06E+03 Co-60 0.00E+00 4.34E+02 9.58E+02 0.00E+00 0.00E+00 0.00E+00 8.16E+03 Ni-63 4.19E+04 2.91E+03 1.41E+03 0.00E+00 0.00E+00 0.00E+00 6.07E+02 Zn-65 2.36E+04 7.50E+04 3.39E+04 0.00E+00 5.02E+04 0.00E+00 4.73E+04 Rb-86 0.00E+00 1.03E+05 4.79E+04 0.00E+00 0.00E+00 0.00E+00 2.03E+04 Sr-89 4.78E+04 0.00E+00 1.37E+03 0.00E+00 0.00E+00 0.00E+00 7.66E+03 Sr-90 1.18E+06 0.00E+00 2.88E+05 0.00E+00 0.00E+00 0.00E+00 3.40E+04 Y-91m 1.30E-02 0.00E+00 5.04E-04 0.00E+00 0.00E+00 0.00E+00 3.82,E-02 Y-91 2.02E+01 0.00E+00 5.39E-01 0.00E+00 0.00E+00 0.00E+00 1.11E+04 Zr-95 2.77E+00 8.88E-01 6.01E-01 0.00E+00 1.39E+00 0.00E+00 2.82E+03 Nb-95 4.47E+02 2.49E+02 1.34E+02 0.00E+00 2.46E+02 0.00E+00 1.51E+06 Tc-99m 2.94E-02 8.32E-02 1.06E+00 0.00E+00 1.26E+00 4.07E-02 4.92E+01 Ru-103 1.98E+01 0.00E+00 8.54E+00 0.00E+00 7.57E+01 0.00E+00 2.31E+03 Ru-106 2.95E+02 0.00E+00 3.73E+01 0.00E+00 5.69E+02 0.00E+00 1.91E+04 Ag-110m 1.42E+01 1.31E+01 7.80E+00 0.00E+00 2.58E+01 0.00E+00 5.36E+03 Te-125m 2.79E+03 1.01E+03 3.74E+02 8.39E+02 1.13E+04 0.00E+00 1.11E+04 1-13
TABLE 1.1 SITE RELATED INGESTION DOSE COMMITMENT FACTOR A (mrem /hr per uCi/ml) Y ISOTOPE BONE LIVER T-BODY THYROID KIDNEY LUNG GI-LLI Te-127m 7.05E+03 2.52E+03 8.59E+02 1.80E+03 2.86E+04 0.00E+00 2.36E+04 Te-127 1.14E+02 4.11E+01 2.48E+01 8.48E+01 4.66E+02 0.00E+00 9.03E+03 Te-129m 1.20E+04 4.47E+03 1.89E+03 4.11E+03 5.00E+04 0.00E+00 6.03E+04 Te-129 3.27E+01 1.23E+01 7.96E+00 2.51E+01
. 1.37E+02 0.00E+00 2.47E+01 I-131 4.96E+02 7.09E+02 4.06E+02 2.32E+05 1.22E+03 0.00E+00 1.87E+02 Cs-134 3.03E+05 7.21E+05 5.89E+05 0.00E+00 2.33E+05 7.75E+04 1.26E+04 Cs-136 3.17E+04 1.25E+05 9.01E+04 0.00E+00 6.97E+04 9.55E+03 1.42E+04 Cs-137 3.88E+05 5.31E+05 3.48E+05 0.00E+00 1.80E+05 5.99E+04 1.03E+04 Ba-140 1.88E+03 2.37E+00 1.23E+02 0.00E+00 8.05E+01 1.35E+00 3.88E+03 Ce-144 4.18E+01 1.75E+01 2.24E+00 0.00E+00 1.04E+01 0.00E+00 1.41E+04 Pr-143 1.32E+00 5.28E-01 6.52E-02 0.00E+00 3.05E-01 0.00E+00 5.77E+03 Nd-147 9.00E-01 1.04E+00 6.22E-02 0.00E+00 6.08E-01 0.00E+00 4.99E+03 W-187 3.04E+02 2.55E+02 8.90E+01 0.00E+00 0.00E+00 0.00E+00 8.34E+04 Np-239 1.28E-01 1.25E-02 6.91E-03 0.00E+00 3.91E-02 0.00E&00 2.57E+03 1-14
1.4 SERVICE WATER EFFLUENT RADIATION MONITORS 1RE-4269/4270 Concentration of radioactive material in the service water effluent line normally is expected to be insignificant. Therefore, the monitor alert alarm setpoint should be established as close to background as practical to prevent spurious alarms and yet alarm should 'an inadvertent release occur. To this end, the alert alarm setpoint will be initially established at three (3) times background until further data can be collected. If this effluent stream should become contaminated, radionuclide concentrations should be determined from grab samples and a radiation monitor alarm setpoint determined as follows:
C, =(][Cg
) + DF Where C sw = the Service Water effluent monitor alarm setpoint.
C = the concentration of each measured gamma emitter ,g, observed in the effluent (uCi/ml)
DF = (C /MPC ) = the dilution factor required to ensure maximum permissible concentrations are not exceeded.
For this release pathway no additional dilution is available.
Therefore, if the calculated DF is greater than 1.0 any releases occurring via this pathway will result in a violation of Technical Specification 3.11.1.1. In this case, ensure that the requirements of all applicable Technical Specifications are met.
If radioactivity is detected in this release stream, doses due to releases from this stream shall be calculated in accordance with the methodology given in Section 1.2, with the near field average dilution factor, F , equal t k 1.0.
1-15
~ , - , - , * - - -
1.5 Turbine Building Sump Effluent Radiation Monitor 1RE-5100 The purpose of the turbine building sump monitor (IRE-5100) is to monitor turbine building sump discharges and, if radioactive, divert this discharge from the Low Volume Retention Pond to the Waste Water Holdup Tanks. Because the only sources of water to the turbine building sump are from the secondary steam system, activity is I
expected only if a significant primary-to-secondary leak is present.
Since only non-radioactive turbine building sump water is allowed to go to the Low Volume Retention Pond, the monitor setpoint should be established as close to background as practical to prevent spurious alarms and yet alarm should an inadvertent radioactive release occur. To this end, the setpoint will be initially established at three (3) times background until further data can be collected.
Then, if this setpoint is exceeded, 1RE-5100 will direct valves 1RV-5100A and B to divert discharges from the turbine building sumps to the Waste Water Holdup Tanks where the effluent can then be sampled and released to Squaw Creek Reservoir in accordance with Technical Specification 3.11.1.1. If a radioactive release is made from the waste water holdup tank, doses due to this release shall be calculated in accordance with the methodology given in Section 1.2.
1-16
1.6 DEFINITIONS OF COMMON LIQUID EFFLUENT PARAMETERS SECTION OF TERM DEFINITION INITIAL USE ADF Actual Dilution Factor (unitiess'). This is defined 1.1.4 as the ratio of the effluent flow rate plus the circulating water flow rate divided by the effluent flow rate.
A The sfce related ingestion dose commitment factor 1.2.1 I to the total body or any organ,T, for each identified gamma or beta emitter, i.
(mrem /hr per uCi/ml)
BF g Bioaccumulation factor for radionuclide, i, from Reg. 1.2.1 Guide 1.109. (pCi/kg per pCi/1)
C, The concentration of alpha emitters in liquid waste 1.1.1 as measured in the analysis of the monthly composite sample required by Surveillance Requirement 4.11.1.1.1.
(uCi/ml) 55 C
The concentration of Fe in liquid waste as 1.1.1 measured in the analysis of the quasterly composite sample required by Surveillance Requirement 4.11.1.1.1. (uci/ml)
C Sum of the concentrations of each measured gamma 1.1.1 8 emitter, g, in the waste tank as measured in the analysis of the sample of each batch as required by Surveillance Requirement 4.11.1.1.1. (uCi/ml)
C f
The concentrations of radionuclide, 1, in the 1.1.1 waste tank (uCi/ml).
C{
The concentration of radionuclide i in the 1.1.6 Reservoir as measured in the analysis of the monthly sample of the Reservoir required by Surveillance Requirement 4.12.1. (uci/ml).
C ik The isotopic concentration of radionuclide i 1.2.1 found in the pre-release sample for batch release k.
Concentrations are determined primarily from gamma isotggic agglysis of ghe liquid pffluent sample.
For Sr, Sr, 'H, 5 Fe and alpha emitters, the last measured value will be used. (uCi/ml)
C 1" The liquid waste effluent monitor alarm setpoint. 1.1.6 This corresponds to the gamma concentration in the undiluted waste stream which after dilution would result in MPC-level releases. (uCi/ml) 1-17
SECTION OF TERM DEFINITION INITIAL USE C
The concentration of 'Sr and 90 S h Md aste LL1 as measured in the analysis of the quarterly
- composite sample required by Surveillance i
Requirement 4.11.1.1.1. (uci/ml)
C sw The Service Water effluent monitor alarm setpoint. 1.4 (uci/ml)
C t
The concentration of sH in liquid waste as measured 1.1.1 in the analysis of the monthly composite sample required by Surveillance Requirement 4.11.1.1.1.
(uci/ml)
DF I
Adult dose conversion factor for radionuclide, i, 1.2.1 from Reg. Guide 1.109 (arem/pci ingested)
D k The dose commitment received by the total body 1.2 or any organ during the duration of batch release k of liquid effluents. (mrem) i D(lake)* The dose commitment received by the total body or 1.2 any organ during a 31 day period, m, due to the buildup
.; in the lake of previously discharged radionuclides. (mrem)
D T The total dose commitment to the total body or any 1.2 1
organ due to all releases of liquid effluents
! during a desired time interval. (mrem)
D Dilution factor, from the near field area within 1.2.1 i Is mile of the release point to the potable water intake l for adult water consumption,1.0 for CPSES (unitiess) f Effluent flow rate. (gpm) 1.1.2 4
F Circulating water flow rate (or dilution flow rate). 1.1.3 l (gpm)
. F' Adjusted circulating water flow rate to account for 1.1.4 buildup of radionuclides in the circulating
, water due to previous releases. (gpm)
F k The near field average dilution factor during a 1.2.1 liquid effluent release (unitless). This is defined as the ratio of the average undiluted liquid waste flow to the average circulating water l flow during the release.
l-18
r SECTION OF TERM DEFINITION INITIAL USE MPC Maximum Permissible Concentration
- of a mixture 1.1.5 of unidentified alpha emitters. (uCi/ml) 55 l MPCp , Maximum Permissible Concentration
- of Fe. (uci/ml) 1.1.5 MPC Maximum Permissible Concentration
- of each 1.1.5
'8 identified gamma emitter, g. (uCi/.ml) f MPC i
Maximum Permissible' Concentration
- of 1.1.5 radionuclide, 1. (uci/ml)
MPC, MaxggumPermggsibleConcentration*ofamixture 1.1.5 of Sr and Sr. (uCi/ml)
MPC*
Maximum Permissible Concentration
- of 1.1.5 tritium. (8H) (uCi/ml)
- SF Safety Factor of 0.9. This compensates for flow 1.1.3 fluctuations from the rate predicted by the circulating l
water pump curves.
RDF Required Dilution Factor (unitiess). This is defined 1.1.5 l
,as the dilution factor that ensures the maximum permissible isotopic concentrations expressed in 10CFR20, Appendix B, Table II, Column 2, are not I
exceeded during a discharge.
l t
k The time duration of batch release k. (hours) 1.2.1 U
f Adult fish consumption. (kg/yr) 1.2.1 U, Adult water consumption. (liters /yr) 1.2.1 i
! *MPCs are given in 10CFR20 Appendix B. Table II, Column 2. Values are given for each isotope in both a soluble and insoluble form. The most conservative (lowest) value for each isotope should be used.
l 1
i i
l 1-19 I
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u,u wa.i.
Psec essins sresem see Fie. s.4 LIQUID EFFLUENT xRE-52s3 DISCHARGE PATHWAYS FIGURE 1.1 waste wate Outrais 101 -
Holdup Tank k L Clac. Water L
(~ _ _ v v v Outf all 201 l , Dischette l Tunnel ,
1 l 15,000 G AL. E A.
- I 200 GPM EA.
+
,_ _ _ _ , _ _ _ _4 _ _ _ _ , u .sP.w._ Recovety g
l l Tank e Unit 1 g
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l 1RE-5100 2b 4 \. /
Loi .elume Retention Pond Caa. I 1975 GAL. IbO GPM) Reacta-Pac j L No. 2 19 20 GAL. (300 GPM ) g Eackwash 1 Sump Unit 2 I Turbine Tus bane Bulld6ng Mutadang Semipe h 300 GPM Chemical J L Sump 2RE-5100 No. 4 1820 GAL. 6300 GPM) 7242 GAL.
No. 51976 GAL. (50 GPM) 150 GPM J L KEV:
J L J L J L JL NORMAL FLOW PATil Unitt thnet 2 Unit 1 Unet 2 Availlas y Diesel Gen. OlseelGen CCW Drain CCW Drain _ _ _ _ _ _ _ FL OW PA TH IF tasaldene HADIOACTivlTY 85 Susnpo Sumpe Tank Tank Sump DETECTED.
98 0. 1 & 2 No. 3 4 No.Il 13 5 G AL. E A. 135 GAL. E A. 2300 GAL. 2300 GAL. 135 GAL SO GPM. EA. 50 GPM EA. 40 GPM 40 GPM GOGPM
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LIOUID WASTE PROCESSING SYSTEM FNWas 1.4 g
I I Waste Holdup N"*"I * *
- Floor Drains Lab Laundry & Hot I j -+ . Sample Room g Floor Drain a Hot 6.-- < Rinse Water Shower Tank H
! Sinks Accumulator g l Shower Building Sumps l Drains l
Drainage g 6
g g :
i r g---
g g J L s , 8 Floor Drain Waste l , e l Waste l Evaporator i Reverse Osmosis Epafcgr ase ' Package l Package J ~
- I M h l M
} g } l Laundry Holdup l Waste Evaporator I Waste Monitor * "N l
l Condensate Tank
- Dominerallaer l l l Dominerallaer l l
'k '
k
, m w-c<: ,i c xo :
(une ass g
l Waste Monitor g Waste Evaporator l Tanks l Condensate Tank Laundry Head l l Tank l X g 7
% l (8) l , r tal l (une-sasah l (une-sasa mav-sasa lRWSTl l xav-sas -
Y l g Circulating Water l Condensate Discharge Storage Tanka l
^ g I
l l DRAIN CHANNEL A DRAIN CHANNEL B O DRAIN CHANNEL C (1)l#-Rad. signals close valves to the Condensate Storage Tank (XRE-5252) or the Laundry Head Tank (XRE-55251)
(2) Valve to Circulating Water Discharge closes on Hi-Rad. circuit failure, loss of flow and channel out of service indications from the monitor.
I,
SECTION 2.0 GASEOUS EFFLUENTS 2.1 GASEOUS EFFLUENT MONITOR SETPOINTS The gaseous monitor setpoint values as determined using the methodology in the following sections will be regarded as upper bounds for the actual setpoint adjustments. That is, setpoint l .
adjustments are not required if the existing setpoint level J
, corresponds to a lower value than the calculated value. Setpoints t
may be established at values lower than the calculated values if i
l desired. Further, if the calculated value should exceed the maximum !
t l
range of the monitor, the setpoint shall be adjusted to a value that l falls within the normal operating range of the monitor.
i If a calculated setpoint is less than the monitor reading associated ,
with the particular release pathway, no release may be made. Under such circumstances, contributing source terms shall be reduced and
$ the setpoint recalculated.
j At CPSES, all gaseous effluents are released to the atmosphere through the two Plant Vent Stacks (Figure 2.1). Setpoint ,
methodologies for the effluent monitors associated with the plant vent are addressed in the following sections. I t
f i
4 2-1 l
2.1.1 DOSE RATES DUE TO NOBLE GASES For implementation of Technical Specification 3.11.2.1.a. the dose rate to the total body and skin of an individual at the unrestricted area boundary due to noble gases shall be calculated as follows:
A. Calculate the total body dose rate due to noble gases D =(5) [ KQ (noble gases)
, Where: D = the total body dose rate at the site boundary due to noble gases (mrem /yr)
(X/Q) = the highest annual average relative concentration at the site boundary = 3.3 x 10 -6 sec/m in the NNW sector *.
1 Kg = total body dose factor due to gamma emissions from noble gas radionuclide i from Table 2.1 (mrem /yr per uCi/m3)
Qg = the release rate of radionuclide i from the plant i
vent stack (uCi/sec) l '
(See C below for calculation of Qg )
B. Calculate the skin dose rate due to noble gases D, = (X/Q) ][ (Lg + 1.1 M g) Qg i (noble gases)
Where: D, = the skin dose rate at the site boundary due to noble gases (mrem /yr)
Lg= the skin dose factor due to beta emissions from noble gas radionuclide i from Table 2.1 (mrem /yr per uCi/m8 )
2-2
1.1 = conversion factor of mrem skin dose per mrad air dose.
4
- Mg = air dose factor due to gamma emissions from noble i i
- gas radionuclide i from Table 2.1 (mrad /yr per uCi/m8 )
- All other terms are as previously defined. !
, C. Calculation of the Qg term Qg is defined as the release rate (uCi/sec) of radionuclide i from the plant vent stack. Q is given by:
1 91" iv Fy Where: X1 , = the concentration of radionuclide i present at the plant vent (uCi/cm 8)
Fy = the flowrate at the plant vent (cm 3/sec)
The concentration of radionuclide i present at the plant vent l stack monitor due to all release sources (e.g., continuous and batch sources), X fy, is calculated using the following equation:
X
= ic Fe
- iB B F, + FB l Where: X ic = The concentration of radionuclide i in the i
continuous release stream as sampled in accordance 8
1 with RETS Table 4.11-2. (uci/cm ) '
1 4
F, = the continuous flow rate contribution of the plant !
ventilation system (cm 8/sec) l 5
iB = the concentration of radionuclide i in the batch X
I release stream as sampled in accordance with RETS f 8
j Table 4.11-2 (uci/cm ) -
I i
2-3 l i-
- -- - . , - . , ---_---,___.n- - . - . _ - -.--..-,,_ ,,,. _ .,, .,. - - - . - - - - , - - . - , -,
.i FB = the flow rate contribution associated with the release of a batch source (cm8 /sec)
, NOTE: If there is no batch release source, F and X
, B iB are zero, and X fy =X g.
The flow rate at the plant vent, F , is given by:
F =F +F v c B NOTE: If there is no batch release source, F is zero, B
and F =F.c v
j f
i i.
k i
, i O
t i
2-4 t
)
2.1.2 PLANT VENT STACK NOBLE GAS MONITORS XRE-5570 A/B AND XRE-5567 A/B For implementation of Technical Specification 3.3.3.11, the alarm setpoint level for the plant vent noble gas monitors will be calculated as follows:
Xgy 500 x SF x AF = 125 Xgy D
t t C = e esser of <
G X
gy 3000 x SF x AF = 750 Xgy s D, s
Where: Cg = The plant vent noble gas monitor alarm setpoint (uCi/cm3 )
GV " (noble gases) iv
= the concentration of noble gases present at the plant vent due to the combined sources as calculated from the radionuclide concentrations determined from the analysis of the appropriate samples taken in accordance with RETS Table 4.11-2 (uci/cm3 )
500 = the technical specification dose rate limit to the total body of an individual in an unrestricted area due to noble gases. (mrem /yr) 3000 = the technical specification dose rate limit to the skin of the body of an individual in an unrestricted area due to noble gases. (mrem /yr)
SF = Safety Factor of 0.5 applied to compensate for statistical fluctuations and errors of measurement (unitiess).
2-5
t i
i i 1
i AF = Allocation Factor of 0.5 applied to account for releases from both plant stacks simultaneously (unitiess).
ii .
, All other variables are as pre'viously defined.
i i
I s
i 2
4
}
i I
A 4
i i
I-I 3
I t i.'
l I
i l
J t
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---,- -_ - --- . m .--I
2.1.3 PLANT VENT FLOW MONITORS A. Plant Vent Stack Flow Rate (Release Rate) Monitors XRE-5570 A/B (PVF-684/685)
Channels PVF-684 and PVF 685 monitor the release rate of radioactive materials from the plant vent stack by combining inputs from a stack noble gas concentration (uCi/cm 3) indication and a stack flow rate (cm8 /sec) indication to yield a release rate (uCi/sec).
If an alarm setpoint is established for this monitor, an increase in either concentration or flow rate could cause an alarm trip.
The setpoius for the plant vent flow rate monitor will be calculated as follows:
Cg =C g Fy where: Cf = The plant vent flow rate monitor alarm setpoint (uCi/sec)
All other terms are previously defined.
B. Sampler Flow Rate Monitors.XFT-5570A2/B2 The sampler flow rate monitors are designed such that if there is a loss of sam'ple flow, the release is terminated. The loss of sample flow alarm setpoint is established permanently in accordance with vendor specifications.
2-7 1
v' . . . . . . . _
-4 -
+, ;, b,
.m s (g .~ u,,x '
4- -
w\
w
,[- ' .s 4 '. : .
s t 1/ . -
, \ ,) l 2.1.4 thUXILIdY BUILDIh'GjVENTILATIdN EXHAUST MONITOR XRE- 5701 s
! For impleme,ntation of Technical Specification 3.3.3.11, the alarm h
setpoint for,..the Auxiliary Builoing Ventilation Erhaust Monitor will w:, s
- e ,, .
,\* fbe calculated,using.the following' methodology. The alarm setpoint
- :1 < _ ,
] ' calculation is Based on tia following assumptions:
Ul '(1)' ,a vaste gas fecay, tank purge operation is the only batch
~ f. ,' t
- , releasiloccurring' (i.Y., a containment purge or vent is not a% \ >
q ~;s
^^ occurring at .,the same time).
, 1 (2) the source contribution due'to other sources in the auxiliary building are negligible rei tive'to the" source contribution due to the rele.ase of the wgn.e gas decay tank.
yl %
The concentradon at the\auxhliary building vent monitor during a
,s M g
waste gas decay t'ar.k rrle$sQ ik calculated as follows:
i X iaur,;- i iGDT GDT + iABY ABV t
S 3GDT , 7ABF
' ?
.{. n Ftom assumption (2) above,'(XNDTFGDT ' AiABV ABV}'
- _ this equation can be reduced to
r
" X =X F 1 iaux iGDT GDT F
aux -
g
- I c' Where) e concentra&n of nome gas radionuclMe 1 Y[GDI g 3 i
. (uci/cm3) in the waste gas decay tank as sampled t
, . in accordance with RETS Table 4.11-2.
{
- F GDT
= the flow rate contributions associated wi'ch'the t ' release of thrt waste gas decay tank (cm8 /sec)
Y a t.
s'., **e ,
d*, *'t k e
- s. 2-8 .
- .> ~.:#
s\: c. r .
- j_
8
X gy = the concentration of noble gas radionuclide 1 8
(uCi/cm ) in the auxiliary building ventilation stream due to sources other than the waste gas decay tanks (see assumption (2), above)
Fgy = the flow rate contribution associated with sources in the auxiliary building other than the waste gas d'ecay tanks.
F, =_the total flow rate at the auxiliary building ventilation monitor during the release of a waste gas decay tank = FGDT + ABV Xf , x = the concentration of noble gas radionuclide i at the auxiliary building ventilation monitor during a waste gas decay tank release.
From Section 2.1.2:
iv v" ic c
+
iB B For this case of a batch release of a waste gas decay tank, make the following substitution into this equation (see assumption (1),
above):
~
iB B iaux aux Therefore, iv v" ic c
+
iaux aux Now, assuming that the source contribution from the auxiliary building vent (due to the release of the waste gas decay tank),
X iaux Faux, is much greater than the source contribution due to all other continuous sources to the plant vent, X ic F' c "" F iv y is approximately equal to X f , , F, 2-9
X F =X F iv v iaux aux At the alarm setpoint concentration at the plant vent monitor, X fy
=
C.
G Also, the Auxiliary Building Ventilation monitor alarm *
-setpoint, C, , corresponds to the noble gas concentration, Xg , ,
that would result in the alarm setpoint concentration at the plant vent monitor. Therefore, C F =C F G v aux aux Solving for C, yields:
= G yF C,
aux Where: C, = the Auxiliary Building ventilation exhaust monitor __
alarm setpoint (uCi/cm 3)
All other variables are previously defined.
\,
o O
2-10
2.1.5 CONTAINMENT ATMOSPHERE GASEOUS MONITOR 1RE-5503 For implementation of Technical Specification 3.3.3.1, the alarm setpoint for the Containment Atmosphere Gaseous Monitor will be calculated using the following methodology. The alarm setpoint calculation is based on the following assumptions:
(1) a containment purge or vent operation is the only batch release i
occurring (i.e., a waste gas decay tank purge operation is not occurring at the same time).
(2) the source contributions due to all other continuous sources to the plant vent are negligible relative to the source contribution from containment building purge or vent operation.
From Section 2.1.2, iv yF =X
- ic c iB B For this case of a batch release due to a containment purge or vent operation, make the following substitution into this equation (see assumption (1), above) iB B" icont cont Where: X = the concentration of noble gas radionuclide 1 (uci/cms ) in the containment release stream as sampled in accordance with RETS Table 4.11-2.
F cont = the flow rate contribution associated with the release of the containment atmosphere (cm8 /sec)
Therefore, iv yF =X F
- F ic e icont cont 2-11
Now, assuming that the source contribution from the containment purge or vent, X g F
o t, is much greater than the source contribution due to all other continuous sources to the plant vent, X F , then X y F is approximately equal to X g F
cont' X
iv v F =X F icont cont At the alarm setpoint concentration at the plant vent monitor, X
fy =C.g Also, the Auxiliary Building Ventilation monitor alarm setpoint, C g , corresponds to the noble gas concentration, Z icont' that would result in the alarm setpoint concentration at the plant vent monitor. Therefore, CG Fv =C F cont cont Solving for C yields:
cont C = G v cont p cont Where: C, = the containment atmosphere gaseous monitor alarm setpoint (uCi/cm 3)
All other variables are previously defined.
l 2-12
l 1
2.1.6 DOSE RATES DUE TO RADIOIODINES, TRITIUM, AND PARTICULATES Organ dose rates due to radiciodines, tritium, and all radioactive materials in particulate form with half-lives greater than eight days will be calculated to implement the requirements of Technical Specification 3.11.2.1.b as follows:
D9 = (X/Q) ][ PQ IP&T Where: D = the total organ dose rate due to radioiodines, particulates with half-lives greater than eight days, and tritium. (mrem /yr)
Pg = dose parameter factor for radionuclide, i, (for radiciodines, particulates, and tritium) for the inhalation pathway in mrem /yr per uCi/m8 * (Table 2.2)
IP&T = Iodines, particulates with half-lives greater than eight days, and tritium. These are the isotopes over which the summation function is to be performed.
All other variables are.previously defined.
- *The latest NRC guidance has deleted the requirement to determine P g for the ground plane and food pathways. In addition, the critical age group has been changed from infant to child. The methodology used for determining values of Pg is given in Appendix A.
2-13 t
2.1.7 PLANT VENT STACK IODINE MONITORS XRE-5575A/B The setpoint for the Plant Vent Stack Iodine Monitors should be established to ensure compliance with Technical Specification 3.11.2.lb. The methodology used performs dose rate calculations in accordance with Section 2.1.6 and compares them with the Technical Specification dose rate limit of 1500 mrem /yr to any organ for compliance. An allocation factor (AF) and safety factor (SF)
, are also utilized for this determination. The equation for calculating the Plant Vent Iodine Monitor Setpoint, C 7, is:
C 7
= X 79 1500 x AF x SF = 5 X79) o o Where: C 7
= Plant Vent Iodine Monitor Setpoint (uCi/cm8)
IV " (iod nes) iv
=
the concentration of radioiodines present at the plant vent due to the combined sources as calculated from the radionuclide concentrations determined from the analysis of the appropriate samples taken in accordance with RETS Table 4.11-2 (uci/cm3 ). .
1500 = the technical specification dose rate limit to any organ due to iodines, tritium and particulates (mrem /yr)
All other variables are previously defined.
2-14
m 2.1.8 PLANT VENT STACK PARTICULATE MONITORS XRE-5568A/B The setpoint for the Plant Vent Stack Particulate Monitors should be established to ensure compliance with Technical Specification 3.11.2.1.b. The methodology used performs dose rate calculations in accordance with Section 2.1.6 and compares them with the technical specification dose rate limit of 1500 mrem /yr to any organ for compliance. An allocation factor (AF) and safety factor (SF) are also utilized for this determination. The equation for calculating the Plant Vent Particulate Monitor Setpoint, C p
, is:
Cp = Xpy 1500 x AF x SF = 375 (Xpy)
D, D o
Where: Cp = Plant Vent Particulate Monitor Setpoint (uCi/cm8 )
bV"(particlates) iv
= the concentration of particulates present at the plant vent due to the combined sources as calculated from the radionuclide concentrations determined from the analysis of the appropriate samples taken in accordance with RETS Table 4.11-2 (uCi/cm8 )
All other variables are previously defined.
4 2-15 L_
TABLE 2.1 DOSE FACTORS FOR EXPOSURE TO A SEMI-INFINITE CLOUD OF NOBLE GASES,*
Isotope '/-Body ***(K) /3-Skin ***(L) '/-Air **(M) /3-Air **(N)
Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 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 8.83E+03 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03
- Values taken from Reference 2. Table B-1 l
l ** mrad-m8 l uCi-yr l *** mrem-m3 uC1-yr 2-16
2.2 GASEOUS EFFLUENT DOSE CALCULATIONS 2.2.1 AIR DOSE IN UNRESTRICTED AREAS For implementation of Technical Specification 3.11.2.2, the cumulative air dose due to noble gases to areas at and beyond the site boundary will be calculated once per 31 days and a cumulative summation of thu air doses will be maintained for each calendar quarter and each calendar year. The air dose over the desired time period will be calcG ated as follows:
D = air dose due to gamma emissions from noble gas radionuclides (mrad)
Dy = 3.17 x 10-8 (gjq) y, g q
( (noble gases)
-8 Where: 3.17 x 10 = the fraction of a year represented by one second Q{ = the cumulative release of radionuclide i for the 31 days, calendar quarter or year as appropriate. (uci)(Q{=Q1 (uci/sec) x release duration (sec))
All other variables are previously defined.
D = air dose due to beta emissions from noble gas radionuclides (mrad) o = 3.17 x 10-0 (X/Q) (nobleN{g Qgases)
D g
N
\
2-17
Where: N g = the air dose factor due to beta emissions from noble gas radionuclide i i
from Table 2.1 (mrad /yr per uCi/m3 ).
All other variables are previously defined.
i Note: If the methodology in this section is used in determining dose to an individual rather than air dose due to noble gases, substitute K for M g, (L 1 + 1.1 Mg ) for N , and X/Q for I7Q.
2.2.2 DOSE TO AN INDIVIDUAL For implementation of Technical Specification 3.11.2.3, the cumulative dose to any organ of an individual from radioiodines, tritium, and particulates with half-lives greater than 8 days will be calculated once per 31 days and a cumulative summation of these doses will be maintained for each calendar quarter and each calendar year. The dose over the desired period will be calculated as follows:
D = dose to any organ of an individual from radioiodine.
p tritium, and radionuclides in particulate form with
] half-lives greater than eight days (mrem).
I ~0 h
' p D
p
=
[ 3.17 x 10 W' }l R PATHS ( IP&T i'"qsi) 4 Where: W' = the dispersion parameter for estimating the dose to an individual at the location where the combination of
- existing pathways and receptor age groups indicates the maximum potential exposures. Locations of interest are listed in Table 2.8. '
i 2-18
_ . . . _ _ _ . - . _ _ _ _ . _ _ _ _ . r, --
W' =
X/Q for the inhalation pathway in sec/m 8
. X/Q is the annual average relative concentration at the location of interest. Values for X/Q are listed in Table 2.7.
. If desired, X/Q (3.3 x 10-6 ,,,j ,3) may be used.
~
W' =
D/Q for the food and groundplane pathways in m . D/Q
,. is the annual average deposition at the location of interest. Values for D/Q are listed in Table 2.7.
If desired, D M (3.2 x 10 -9 m-2) may be used.
NOTE: for tritium, the dispersion parameter, W', is taken as X/Q for all pathways.
h{,=dosefactorforradionuclidei,pathwayp,andage group a, in mrem /yr per uCi/m 8 for the inhalation pathway and m8 (mrem /yr) per uCi/m 8 for food and groundplane pathways. The controlling values for R ,
for each pathway, radionuclide, and age group are listed in Tables 2.3 - 2.6.* The values in these tables reflect the value for the critical organ for each pathway and radionuclide.
Q'g = cumulative release of radionuclide, i, (uC1)~
IP&T = Iodines, particulates with half-lives greater than eight days, and tritium. These are the isotopes over which the summation function is to be performed.
PATHS = the real pathways of exposure to individuals at the locations of interest as indicated in Table 2.8.
- P The methodologies used for determining values of R1,, for ,sach pathway are given in Appendicies B through F.
2-19
2.2.3 DOSE PROJECTIONS FOR GASEOUS EFFLUENTS Dose projections required to fulfill the requirements of Technical Specification 3.11.2.4 shall be performed using the methodologies in Section 2.2.1 for air dose determinations and Section 2.2.2 for the determination of the dose to any organ of an individual. 5 or 5 , as appropriate, should be used for the dispersion parameter, W', when projecting the dose to any organ of an individual. If required, air dose due to noble gases and the dose to any organ from iodines, tritium, and particulates with half-lives greater than eight days in a 31 day period shall be projected. This 31 day period shall be that period ending on the day of the anticipated release.
8 2-20
2.2.4 DOSE CALCULATIONS TO SUPPORT OTHER TECHNICAL SPECIFICATIONS For the purpose of implementing the requirements of Technical Specification 6.9.1.7, the Semiannual Radioactive Effluent Release Report shall include an assessment of the radiation doses due to radioactive liquid and gaseous effluents from the station during the previous calendar year. 'This assessment shall be a summary of the doses determined in accordance with Section 1.2 for doses due to liquid effluents, Section 2.2.1 for air doses due to noble gases, and Section 2.2.2 for doses due to iodines, tritium, and particulates. This same report shall also include an assessment of the radiation doses from radioactive liquid and gaseous e'ffluents to members of the public due to their activities inside the site boundary. This assessment shall be performed in accordance with the methodologies in Sections 1.2, 2.2.1, and 2.2.2, using dispersion and deposition parameters for the locations of interest concurrent with the time of release, and taking into account occupancy factors. All assumptions and factors used in the determination shall be included in the report.
For the purpose of implementing Technical Specification 3.12.2 dose calculations shall be performed using the methodology in Section 2.2.2. substituting the appropriate pathway receptor dose factors and dispersion parameters for the location (s) of interest. Annual average oispersion parameters may be used for these calculations.
2-21
For the purpose of implementing Technical Specifications 3.11.4 and 6.9.1.7, the total annual dose to any member of the public due to releases of radioactivity and to radiation from uranium fuel cycle sources may be determined by combining the annual doses determined for a member of the public in accordance with Sections 1.2, 2.2.1, and 2.2.2 with the direct radiation dose contributions from the units and from outside storage tanks to the particular member of the public. This assessment must be performed once per year for inclusion in the Semiannual Radioactive Effluent Release Report to be submitted 60 days after January 1 of each year (Tech Spec 6.9.1.7), and in the event calculated doses exceed twice the limits of Specifications 3.11.1.2, 3.11.2.2, or 3.11.2.3 (Tech Spec 3.11.4).
The dose component due to direct radiation may be determined by calculation or actual measurement (e.g., thermoluminescent dosimeters, micro-R meter, etc.). The calculation or actual measurement of direct radiation shall be documented in the Special Report that must be submitted if this determination is required.
2-22
TABLE 2.2 PATHWAY DOSE FACTOR g (P )*
NUCLIDE INHALATION NUCLIDE INHALATION ,
H-3 1.125E+03 Nb-95 6.142E+05 P-32 2.605E+06 Ru-103 6.623E+05 Cr-51 1.702E+04 Ru-106 1.432E+07 Mn-54 1.576E+06 As-110 5.476E+06 Fe-55 1.110E+05 Te-125 4.773E+05 Fe-59 1.269E+06 Te-127 1.480E+06 Co-58 1.110E+06 Te-129 1.761E+06 Co-60 7.067E+06 I-131 1.628E+07 Ni-63 8.214E+05 I-133 3.848E+06 Zn-65 9.953E+05 Cs-134 1.014E+06 Rb-86 1.983E+05 Cs-136 1.709E+05 Sr-89 2.157E+06 Cs-137 9.065E+05 Sr-90 1.010E+08 Ba-140 1.743E+06 l
Y-91 2.627E+06 Ce-141 5.439E+05 (
Zr-95 2.231E+06 Ce-143 1.273E+05 i
- reference Appendix A
- ares /yr per uCi/ms ,
l 2-23 i
l l
TABLE 2.2 PATHWAY DOSE FACTOR (Pg )
NUCLIDE INHALATION
, Ce-144 1.195E+07 Pr-143 4.329E+05 Nd-147 3.282E+05 Np-239 6.401E+04
- reference Appendix A
- mrom/yr per uC1/m 3 2-24
TABLE 2.3 PATHWAY DOSE FACTOR (Rg )
INFANT R (D/Q)
Rf(X/Q) GROUND ( !O} ( !O} ( 0} 0}
NUCLIDE INHALATION PLANE COW / MILK COW / MEAT VEGETATION
- COAT 3 K, H-3 6.468E+02 0.000E+00 2.382E+03 O'.000E+00 0.000E+00 4.860E+03 4
P-32 2.030E+06 0.000E+00 1.603E+11 0.000E+00 0.000E+00 1.924E+11 Cr-51 1.284E+04 5.517E+06 4.692E+06 0.000E+00 0.000E+00 5.631E+05 Mn-54 9.996E+05 1.629E+09 3.920E+07 0.000E+00 0.000E+00 4.704E+06 Fe-55 8.694E+04 0.000E+00 1.351E+08 0.000E+00 0.000E+00 1.757E+06 Fe-59 1.015E+06 3.238E+08 3.930E+08 0.000E+00 0.000E+00 5.109E+06 Co-58 7.770E+05 4.490E+08 6.062E+07 0.000E+00 0.000E+00 7.274E+06 Co-60 4.508E+06 2.528E+10 2.098E+08 0.000E+00 0.000E+00 2.517E+07 Ni-63 3.388E+05 0.000E+00 3.493E+10 0.000E+00 0.000E+00 4.192E+09 Zn-65 6.538E+05 8.574E+08 1.904E+10 0.000E+00 0.000E+00 2.285E+09 Rb-86 1.904E+05 1.029E+07 2.228E+10 0.000E+00 0.000E+00 2.673E+09 Sr-89 2.030E+06 2.523E+04 1.255E+10 0.000E+00 0.000E+00 2.636E+10
$r-90 4.088E+07 0.000E+00 1.216E+11 0.000E+00 0.000E+00 2.553E+11
- mrea/yr per uC1/m'
- m' (arem/yr) per uC1/sec
- units for H-3 conversion factors are mrom/yr per uCi/m3 for all pathways 2-25
TABLE 2.3 PATHWAY DOSE FACTOR (Rg )
INFANT RC (D/Q)
Rf(X/Q)
- CROUND (D/Q) (D/Q) R (D/Q) R D/Q)
NUCLIDE INHALATION PLANE COW / MILK COW / MEAT VECETATION GOAT MILK Y-91 2.450E+06 1.217E+06 5.261E+06 0.000E+00 0.000E+00 6.313E+05 Zr-95 1.750E+06 2.915E+08 8.302E+05 0.000E+00 0.000E+00 9.962E+04 Nb-95 4.788E+05 1.610E+08 2.064E+08 0.000E+00 0.000E+00 2.476E+07 Ru-103 5.516E+05 1.226E+08 1.059E+05 0.000E+00 0.000E+00 1.271E+04 Ru-106 1.156E+07 5.063E+08 1.445E+06 0.000E+00 0.000E+00 1.734E+05 Ag-110m 3.668E+06 4.062E+09 1.462E+10 0.000E+00 0.000E+00 1.754E+09 Te-125m 4.480E+05 2.133E+06 1.502E+08 0.000E+00 0.000E+00 1.802E+07 Te-127m 1.312E+06 1.083E+05 1.037E+09 0.000E+00 0.000E+00 1.244E+08 Te-129m 1.680E+06 2.348E+07 1.401E+09 0.000E+00 0.000E+00 1.681E+08 I-131 1.484E+07 2.095E+07 1.055E+12 0.0'00E+00 0.000E+00 1.267E+12 I-133 3.556E+06 2.983E+06 9.590E+09 0.000E+00 0.0D0E+00 1.151E+10 Cs-134 7.028E+05 7.972E+09 6.801E+10 0.000E+00 0.000E+00 2.040E+11 Cc-136 1.344E+05 1.690E+08 5.768E+09 0.000E+00 0.000E+00 1.730E+10
- arem/yr per uC1/m8 co m8 (ares /yr) per uC1/sec 2-26
TABLE 2.3 PATHWAY DOSE FACTOR (Rg )
INFANT R (D/Q)
Rg (X/Q) GROUND i( Q) ** R (D/Q)
R (D/Q)
R (D/Q)
NUCLIDE INHALATION PLANE COW / MILK COW / MEAT VEGETATION GOAT MILK Cs-137 6.118E+05 1.203E+10 6.024E+10 0.000E+00 0.000E+00 1.807E+11 Ba-140 1.596E+06 2.351E+07 2.413E+08 0.000E+00 0.000E+00 2.896E+07 Ce-141 5.166E+05' 1.539E+07 1.366E+07 0.000E+00 0.000E+00 1.639E+06 Co-144 9.842E+06 8.046E+07 1.334E+08 0.000E+00 0.000E+00 1.601E+07 Pr-143 4.326E+05 0.000E+00 7.843E+05 0.000E+00 0.000E+00 9.412E+04 Nd-147 3.220E+05 -
1.015E+07 5.767E+05 0.000E+00 0.000E+00 6.920E+04 Np-239 5.950E+04 1.978E+06 9.416E+04 0.000E+00 0.000E+00 1.130E+04
- mrem /yr per uCi/m 8
- m8 (mres/yr) per uC1/sec 2-27
TABLE 2.4 PATHWAY DOSE FACTOR (Rg )
CHILD R (D/Q)
Rf(X/Q) CROUND (D Q) (D/Q) ( /Q) (D/Q)
NUCLIDE INHALATION PLANE COW / MILK COW / MEAT VECETATION COAT MILK H-3 1.125E+03 0.000E+00 1.570E+03 2.341E+02 4.008E+03 3.203E+03 P-32 2.605E+06 0.000E+00 7.781E+10 7.427E+09 3.375E+09 9.337E+10 Cr-51 1.702E+04 5.517E+06 5.402E+06 4.669E+05 6.232E+06 6.482E+05 Hn-54 1.576E+06 1.629E+09 2.097E+07 8.013E+06 6.651E+08 2.517E+0fi Fe-55 1.110E+05 0.000E+00 1.110t*08 4.571E+08 8.012E+08 1.453E+06 Fe-59 1.269E+06 3.238E+08 2.031E+08 6.374E+08 6.766E+08 2.640E+06 Co-58 1.110E+06 4.490E+08 7.088E+07 9.616E+07 3.786E+08 8.505E+06 Co-60 7.067E+06 2.528E+10 2.391E+08 3.837E+08 2.095E+09 2.870E+07 Ni-63 8.214E+05 0.000E+00 2.965E+10 2.913E+10 3.949E+10 3.557E+09 Zn-65 9.953E+05 8.574E+08 1.101E+10 1.000E+09 2.164E+09 1.322E+09 Rb-86 1.983E+05 1.029E+07 8.780E+09 5.780E+08 4.539E+08 1.054E+09 Sr-89 2.157E+06 2.523E+04 6.627E+09 4.82HE+08 3.611E+10 1.392E+10 Sr-90 1.010E+08 0.000E+00 1.117E+11 1.040E+10 1.243E+12 2.346E+11
- mrem /yr por uci/m 3
- ma (mrem /yr) por uCi/anc 0** units for 11-3 convernion f actors arn nrom/yr por uC1/m' for all pattwayn 2-28
t i
l TABLE 2.4 PATHWAY DOSE FACTOR (Rg )
CHILD i R (D/Q)
Rf(X/Q) (D Q) (D/Q) R (D/Q) R (D/Q)
GROUND ** * ** **
- NUCLIDE INHALATION PLANE COW / MILK COW / MEAT VEGETATION COAT MILK !
Y-91 2.627E+06 1.217E+06 5.209E+06 2.409E+08 2.501E+09 6.250E+05 l Zr-95 2.231E+06 2.915E+08 8.833E+05 6.172E+08 9.025E+08 1.060E+05 Nb-95 6.142E+05 1.610E+08 2.290E+08 2.232E+09 2.961E+08 2.748E+07 Ru-103 6.623E+05 1.226E+08 1.118E+05 4.062E+09 4.052E+08 1.341E+04 Ru-106 1.432E+07 5.063E+08 1.437E+06 6.903E+10 1.160E+10 1.724E+05 Ag-110m 5.476E+06 4.062E+09 1.679E+10 6.749E+08 2.587E+09 2.014E+09 Te-125m 4.773E+05 2.133E+06 7.380E+07 5.695E+08 3.512E+08 8.857E+06 Te-127m 1.480E+06 1.083E+05 5.932E+08 5.060E+09 3.769E+09 7.118E+07 Te-129m 1.761E+06 2.348E+07 8.011E+08 5.315E+09 2.521E+09 9.613E+07
!-131 1.628E+07 2.095E+07 4.343E+11 5.540E+09 4.770E+10 5.212E+11 1-133 3.848E+06 2.983E+06 3.952E+09 1.320E+02 8.124E+08 4.743E+09 Cc-134 1.014E+06 7.972E+09 3.715E+10 1.513E+09 2.631E+10 1.114E+11
- mrem /yr per uC1/m'
- m8 (mres/yr) per uC1/see 2-29
1 TABLE 2.4 PATHWAY DOSE FACTOR (Rg ) >
CHILD j RU (D/Q)
} Rf(X/Q) ( /Q) ( /Q) (D/Q) R (D/Q)
GROUND * * **
- 7
! NUCLIDE INHALATION PLANE COW / MILK COW / MEAT VECETATION COAT MILK I
I~
i j Cs-136 1.709E+05 1.690E+08 2.760E+09 4.374E+07 2.216E+08 8.280E+09 !
i .!
) ,
Cs-137 9.065E+05, 1.203E+10 3.224E+10 1.334E+09 2.392E+10 9.672E+10 ,!
l i
- Ba-140 1.743E+06 2.351E+07 1.173E+08 4.398E+07 2.777E+08 1.407E+07 f
Ce-141 5.439E+05 1.539E+07 1.361E+07 1.381E+07 4.078E+08 1.633E+06 ;
- [
Ce-144 1.195E+07 8.046E+07 1.327E+08 1.893E+08 1.039E+10 1.592E+07 !
i Pr-143 4.329E+05 0.000E+00 7.752E+05 3.607E+07 1.574E+08 9.302E+04 1 Nd-147 3.282E+05 1.015E+07 5.735E+05 1.521E+07 9.287E+07 6.882E+04 I
Np-239 6.401E+04 1.978E+06 9.153E+04 2.249E+03 1.358E+07 1.098E+04 1 !
l
- ares /yr per uCi/m3 C* ma (ares /yr) per uCi/sec l
I l
i
! t f
i i !
I I
I i j 2-30 f
TABLE 2.5 PATilWAY DOSE FACTOR (Rg )
TEENAGER R (D/Q)
Rf(X/Q) GROUND ( 0} ( !O}
NUCLIDE IN1IALATION PLANE COW / MILK COW / MEAT VEGETATION GOAT MILK H-3 1.272E+03 0.000E+00 9.938E+02 1.938E+02 2.588E+03 2.027E+03 P-32 1.888E+06 0.000E+00 3.155E+10 3.939E+09 1.611E+09 3.786E+10 Cr-51 2.096E+04 5.517E+06 8.393E+06 9.487E+05 1.040E+07 1.007E+06 Mn-54 1.984E+06 1.629E+09 2.875E+07 1.437E+07 9.324E+08 3.450E+06 Fe-55 1.240E+05 0.000E+00 4.454E+07 2.382E+08 3.259E+08 5.790E+05 Fe-59 1.520E+06 3.238E+08 2.869E+08 1.178E+09 1.000E+09 3.729E+06 Co-58 1.344E+06 4.490E+08 1.096E+08 1.945E+08 6.057t+08 1.316E+07 Co-60 8.800E+06 2.528E+10 3.621E+08 7.600E+08 3.237E+09 4.345E+07 Ni-63 5.800E+05 0.000E+00 1.182E+10 1.519E+10 1.607E+10 1.419E+09 Zn-65 1.240E+06 8.574E+08 7.314E+09 8.687E+08 1.471E+09 8.777E+08 Rb-86 1.904E+05 1.029E+07 4.734E+09 4.076E+08 2.747E+08 5.680E+08 Sr-89 2.416E+06 2.523E+04 2.677E+09 2.551E+08 1.521E+10 5.623E+09 Sr-90 1.080E+08 0.000E*00 6.612K+10 8.049E+09 7.507E+11 1.389E+11 mrem /yr por uC1/m' m8 (mren/yr) por uC1/nce c4 units for 11-3 convernion factorn are mrem /yr por uCi/m' for all pathwayn 2-31
) !
) 4 I
- TABLE 2.5 !
! PATHWAY DOSE FACTOR (Rg ) :
- TEENAGER i RU (D/Q) l Rf(X/Q) D/Q) (D/Q) R (D/Q) RhD/Q)
CROUND* * **
NUCLIDE INHALATION PLANE COW / MILK COW / MEAT VECETATION COAT MILK
- i Y-91 2.960E+06 1.217E+06 6.487E+06 3.923E+08 3.233E+09 7.784E+05 l Zr-95 2.688E+06 2.915E+08 1.208E+06 1.103E+09 1.278E+09 1.449E+05
)
Nb-95 7.512E+05 1.610E+08 3.341E+08 4.260E+09 4.568E+08 4.009E+07 i i
l l Ru-103 7.832E+05 1.226E+08 1.519E+05 7.219E+09 5.788E+08 1.823E+04
\
Ru-106 1.608E+07 5.063E+08 1.818E+06 1.143E+11 1.500E+10 2.182E+05 i \
Ag-110m 6.752E+06 4.062E+09 2.561E+10 1.347E+09 4.039E+09 3.073E+09 '
i i Te-125m 5.360E+05 2.133E+06 8.868E+07 8.950E+08 4.383E+08 1.064E+07 1 Te-127m 1.656E+06 1.083E+05 3.420E+08 3.816E+09 2.236E+09 4.105E+07 1
4 Te-129s 1.976E+06 2.348E+07 4.631E+08 4.019E+09 1.544E+09 5.557t+07 l l
- r I-131
} 1.464E+07 2.095E+07 2.209E+11 3.685E+09 3.162E+10 2.651E+11 4
1-133 2.920E+06 2.983E+06 1.677E+09 7.324E+01 4.593E+08 2.012E+09 l l
l' Cs-134 1.128E+06 7.972E+09 2.310E+10 1.231E+09 1.670E+10 6.930E+10 :
i t
!
- ares /yr per uC1/m' C* m8 (ares /yr) per uC1/sec i l l I
i ;
I 1
- 2-32 L l
i j
I i TABLE 2.5 i PATHWAY DOSE FACTOR (Rg ) !
TEENAGER t
- Rg (D/Q)
Rf(X/Q) GROUND R (D/Q) R (D/Q) R (D/Q) Rf(D/Q) i NUCLIDE INHALATION PLANE COW / MILK COW / MEAT VEGETATION COAT MILK ;
f Cs-136 1.936E+05 1.690E+08 1.761E+09 3.650E+07 1.698E+08 5.282E+09 l 1 '
] Cs-137 8.480E+05 1.203E+10 1.781E+10 9.634E+08 1.348E+10 5.342E+10 l' Ba-140 2.032E+06 2.351E+07 7.493E+07 3.675E+07 2.137E+08 8.991E+06 1
1 l Co-141 6.136E+05 1.539E+07 1.696E+07 2.251E+07 5.399E+08 2.035E+06 l
! i Ce-144 1.336E+07 8.046E+07 1.655E+08 3.089E+08 1.326E+10 1.986E+07 f
j .
] Pr-143 4.832E+05 0.000E+00 9.551E+05 5.813E+07 2.308t+08 1.146E+05 :
l i
j Nd-147 3.720E+05 1.015E+07 7.146E+05 2.478E+07 1.436E+08 8.575E+04 j Np-239 1.320E+05 1.978E+06 1.062E+05 3.413E+03 2.100E+07 1.274E+04 .
l
- mres/yr per uC1/m8 <
on ms (ares /yr) per uCi/sec :
i
- I
! [
1
- I l l-i I
I
(
j 2-33 !
4 TABLE 2.6 PATHWAY DOSE FACTOR (Rg )
ADULT
~
Rf(D/Q)
Rf(X/Q) (D/Q) R (D/Q) Rg (D/Q) Rg (D/Q)
- GROUND * * ** **
- NUCLIDE INHALATION PLANE COW / MILK COW / MEAT VEGETATION GOAT MILK H-3 1.264E+03 0.000E+00 7.629E+02 3.248E+02 2.260E+03 1.556E+03 4 l P-32 1.320E+06 0.000E+00 1.710E+10 4.661E+09 1.406E+09 2.052E+10 Cr-51 1.440E+04 5.517E+06 7.203E+06 1.778E+06 1.173E+07 8.644E+05 4
i j Mn-54 1.400E+06 1.629E+09 2.578E+07 2.813E+07 9.589E+08 3.094E+06 1
^
Fe-55 7.208E+04 0.0007.+00 2.511E+07 2.933E+08 ,2.096E+08 3.265E+05 Fe-59 1.016E+06 3.2361.+0B 2.333E+08 2.091E+09 9.969E+08 3.033E+06
- Co-58 9.280E+05 4.490E+08 9.575E+07 3.710E+08 6.274E+08 1.149E+07 Co-60 5.968E+06 2.528E+10 3.082E+08 1.413E+09 3.139E+09 3.699E+07 Ni-63 4.320E+05 0.000E+00 6.729E+09 1.888E+10 1.041E+10 8.075E+08 4
Zn-65 8.640E+05 -
8.574E+08 4.365E+09 1.132E+09 1.009E+09 5.238E+08 i
i
! Rb-86 1.360E+05 1.029E+07 2.598E+09 4.884E+08 2.201E+08 3.117E+08
- Sr-89 1.400E+06 2.523E+04 1.452E+09 3.023E+08 1.001E+10 3.050E+09 I i
- Sr-90 9.920E+07 0.000K+00 4.680E+10 1. ?.44 E+ 10 6.046E+11 9.828E+10 l
- mrem /yr per uC1/m8
{ C* m8 (arem/yr) per uCi/sec j cc* units for H-3 conversion factors are mrem /yr per uC1/ms for all pathways 2-34
TABLE 2.6 PATHWAY DOSE FACTOR (R )
ADULT R (D/Q)
Rf(X/Q) (! (
- GROUND ** ** **
NUCLIDE INHALATION PLANE COW / MILK COW / MEAT VEGETATION GOAT MILK Y-91 1.704E+06 1.217E+06 4.734E+06 6.253E+08 2.831E+09 5.681E+05 Zr-95 1.768E+06 2.915E+08 9.639E+05 1.923E+09 1.216E+09 1.15,7E+05 Nb-95 5.048E+05 1.610E+08 2.788E+08 7.764E+09 4.814E+08 3.346E+07 Ru-103 5.048E+05 1.226E+08 1.194E+05 1.239E+10 5.649E+08 1.432E+04 1
Ru-106 9.360E+06 5.063E+08 1.320E+06 1.811E+11 1.248E+10 1.584E+05 Ag-110m 4.632E+06 4.062E+09 2.200E+10 2.526E+09 3.987E+09 2.640E+09 Te-125m 3.120E+05 2.133E+06 6.690E+07 1.474E+09 3.970E+08 8.028E+06 Te-127m 9.600E+05 1.083E+05 1.860E+08 4.531E+09 1.418E+09 2.232E+07 Te-129m 1.160E+06 2.348E+07 3.047E+08 5.774E+09 1.288E+09 3.656E+07 I-131 1.200E+07 2.095E+07 1.391E+11 5.067E+09 3.795E+10 1.669E+11 I-133 2.160E+06 2.983E+06 9.910E+08 9.452E+01 5.337E+08 1.189E+09 Cs-134 8.480E+05 7.972E+09 1.345E+10 1.565E+09 1.110E+10 4.035E+10 C:-136 1.464E+05 1.690E+08 1.032E+09 4.668E+07 1.660E+08 3.095E+09 e arem/yr per uCi/m 3 00 m8 (mrem /yr) por uCi/sec 2-35
.s
, (d '
i ,
~
\
TABLE 2.6 3 PAT WAY DOSE FACTOR (R )
t '
ADULT '
+
'R (E /Q).
Rf(X/Q) ( ( 0} !O} !O}
- GROUNii* ** ** * **
NUCLIDE INHALATION PLANE COW / MILK COW /1 EAT VECETATION GOAT MILK Cs-137 6.208E+05 1.20.]E+10 1.010E+10 1.193E+09 8.696E+09 3.029E+10 Ba-140 1.272E+06 2.351E+0{; 5.i42E+07 5.936E+07 2.652E+08 5 6.650E+06 Ce-141 3.616E+05 L539E407 1.252E+07 3.630E+0F 5.094E+08 1.503E+06 Ce-144 7.776E+06 8'.046E+07 1.210E+08 4,929E+08 1.112E+10, l 451E+07 Pr-143 2.808E+05 0.000E+00 6.921E+05 9.198E+07 2.747E+08 8.305E+04 Nd-147 2.208E+05 1.015E+0[ 5.252E+05 3.978E+07 , 1.865E+08 6.302E+04 Np-239 1.192E+05 1.978E+06 7.397E+04' 5.191E+03 2.876E+07 8.876E+03
- mrem /yr per uCi/m 8 ',
i ** m2 (mrem /yr) per uCi/sec I
r i A s
~ &
/
4 f
L 4
2-36 -
TABLE 2.7 ATMOSPHERIC DISPERSION PARAMETERS FOR TECHNICAL SPECIFICATIONS 3.11.2.3 and 3.11.2.4 Sector Miles X/Q D/Q N 4.5 2.4E-07 1.0E-09 NNE 2.4 4.7E-07 2.3E-09 NE 2.4 3.2E-07 1.1E-09 ENE 2.6 2.2E-07 4.1E-10 E 3.5 1.5E-07 2.7E-10 ESE 2.3 3.7E-07 9.0E-10 SE 3.6 2.4E-07 7.0E-10 SSE 2.0 5.8E-07 3.2E-09 S 4.8 1.0E-07 3.6E-10 SSW 4.3 9.2E-08 2.9E-10 SW 3.5 1.2E-07 3.3E-10 WSW 1.5 6.9E-07 2.2E-09 i
W 1.7 6.5E-07 2.2E-09 l WNW 3.0 3.7E-07 1.0E-09 NW 5.0 2.2E-07 5.3E-10 NNW 3.4 4.9E-07 1.9E-09
- sec/m 2
- m l
i 2-37
t TABLE 2.8 CONTROLLING RECEPTORS, LOCATIONS, AND PATHWAYS (For Dose Calculations required by Technical Specifications 3.11.2.3 and 3.11.2.4) ,
DISTANCE ,,
SECTOR (MILES) PATHWAY AGE GROUP N 4.5 Vegetation Child NNE 2.4 Vegetation Child NE 2.4 Vegetation Child ENE 2.6 Vegetation Child E 3.5 Vegetation Child ESE 2.3 Vegetation Child SE 3.6 Vegetation Child SSE 2.0 Vegetation Ch,ild S 4.8 Cow / Milk Infant
[
SSW 4.3 Vegetation Child SW 3.5 Vegetation Child WSW 1.5 Vegetation Child W 1.7 Vegetation Child WNW 3.0 Vegetation Child NW* - -- -
NNW 3.4 Vegetation Child
- No pathway currently exists in this sector.
- In addition to the ;tthways shown, the plume, inhalation, and ground plane pathways are present at each receptor location.
2-38
2.3 METEOROLOGICAL MODEL 2.3.1 DISPERSION CALCULATIONS Atmospheric dispersion for gaseous releases are calculated using a straight line flow Gausian model similar to the Constant Mean Wind Direction model given in Regulatory Guide 1.111. Section C l.c. The method given here is modified by including factors to account for plume depletion and effects of the terrain. The average relative concentration is given by the following equation:
f \
=2.0326K 1 j,k Nra jk {j(r)
Where: 2.032 = (2/ff)b divided by the width in radians of a 22.5* sector.
6 = plume depletion factor at distance r for the applicable stability class (Figure 2.2).
Normally, a value of 1.0 is assumed when undepleted X/Q values are to be used in dose calculations.
i K = terrain correction factor (Figure 2.5) n = the number of hours meteorological conditions are jk observed to be in a given wind direction, wind speed class, k, and atmospheric stability I
class,j.
l 2-39 l
L_
N = total hours of valid meteorological data throughout the period of release.
NOTE: If hourly meteorological data are used, all k and N are variable subscripts are dropped, n set equal to I and the hourly averaged meteorological variables are used in the model.
r = downwind distance from the release point to the location of interest (meters) u k = the average windspeed (midpoint of windspeed class, k) measured at the 10 meter level during stability class J. (met.ers /sec)
[ (r) = the vertical plume spread with a volumetric correction for a release within the building wake cavity, at a distance, r, for stability class, J.
The equation for calculating 2 (r) is:
f~
2 (g2 + 0.5 b f77)b
{(r)=thelesserof<
Where:
g=theveriticalstandarddeviationofmaterialsin the plume at distance, r, for atmospheric stability class, j. (Figure 2.3) 0.5 = the building wake shape factor, b = the vertical height of the reactor containment structure (79.4 meters) 2-40
2.3.2 DEPOSITION CALCULATIONS The relative deposition per unit is calculated as follows:
KDzg D,
Q 0.3927 r Where: D = relative deposition rate for a ground level release (m- ) (Figure 2.4) z = the fraction of time the wind blows to the sector of interest.
Note: If hourly meteorological data are used, z is set equal to one.
0.3927 = the width in radians of a 22.5* sector.
Other variables are as previously defined.
2.3.3 COLLECTION AND PROCESSING OF REAL TIME METEOROLOGICAL DATA Several real time meteorological parameters are collected from the onsite meteorological tower by the RM-21 Computer.
Instantaneous data readings for wind speed (10 and 60 meter),
wind direction (10 and 60 meter), ambient temperature (10 and 60 meter), and 50 meter delta temperature are collected by the RM-21 at 5 second intervals and every other reading is recorded in a 10 second data file. This file contains one hour's worth l
of unprocessed meteorological data values that have been collected at 10 second intervals. Data in this file are stored by parameter. Every hour, data in this file are processed to produce an hourly meteorological data file which contains hourly averaged values for each parameter.
i 2-41
The RM-21 uses the hourly averaged meteorological data to compute atmospheric relative concentration, depletion, and deposition. Specifically, delta temperature values are used for determining atmospheric stability classifications and wind speed and direction values are used for calculating dispersion.
The equations used by the RM-21 in performing dispersion and depletion calculations are the same as those shown in Sections 2.3.1 and 2.3.2. If desired, these hourly dispersion factors can be used in conjunction with concurrent radiological release data to perform routine dose calculations.
2-42
2.4 DEFINITIONS OF GASEOUS EFFLUENTS PARAMETERS Section of Term Definition Initial Use AF = Allocation Factor of 0.5 applied to account for releases from both stacks siniultaneously. 2.1.2 b = vertical height of the reactor containment structure. 2.3.1 Cg = the plant vent noble gas monitor alarm 2.1.2 setpoint. (uCi/cm 8)
C f
= the plant vent flow rate monitor alarm setpoint. 2.1.3 (uCi/sec)
C
= the Auxiliary Building Ventilation Exhaust 2.1.4 monitor alarm setpoint. (uCi/cm 8)
C e nt
= the Containment Atmosphere Gaseous monitor 2.1.5 alarm setpoint. (uCi/cm )
C 7
= the plant vent iodine monitor alarm setpoint. 2.1.7 (uC1/cm8 )
Cp = the plant vent particulate monitor alarm setpoint. 2.1.8 (uCi/cm8 )
D = relative deposition rate'for a ground-level 2.3.2 8 ~
release (m )
D = the total organ dose rate due to tritium, iodines, 2.1.6 and particulates in gaseous releases. (mrem /yr)
D = dose to any organ of an individual from 2.2.2 P radioiodines, tritium and radionuclides in particulate from with. half-lifes greater than eight days. (mrem)
( D s
= skin dose rate at the unrestricted area 2.1.1 l boundary due to noble gases. (mrem /yr) f D E
= total body dose rate at the unrestricted 2.1.1 l
area boundary due to noble gases. (mrem /yr)
Do =airdoseduetobetaemissionyfromnoblegases. 2.2.1 P (mrad) ;
Dy = air dose due to gamma emissions from noble gases. 2.2.1 E (mrad)
D/Q = the annual average relatiye deposition at the 2.2.2 location of interest. (m- )
e l 2-43 I
i
Section of
- Term Definition Initial Use D/Q = the highest annual average relative deposition at 2.2.2 the locatgn f the maximum exposed individual.
(3.2 x 10 m in the SSE sector) 6 = plume depletion factor at distance r for the 2.3.1 appropriate stability class (radioiodines and particulates),
i F
B
= the flow rate contribution associated with the 2.1.1 release rate of the batch source. (cm8/sec)
F
" = the continuous flow rate contribution of the plant 2.1.1 ventilation system. (cm 8/sec) j F y = the flow rate at the plant vent. (cm /sec) 8 2.1.1 l
Fg = the flow rate contribution associated with the 2.1.4 i sources in the auxiliary building other than the l waste gas decay tanks. (cm8 /sec)
F
""* = the total flow rate at the auxiliary building 2.1.4
, ventilation monitor during the release of a Waste Gas Decay Tanks. (cm8 /sec)
F
- "" = the flow rate contribution associated with the 2.1.5 release of the Containment Atmosphere. (cm8 /sec)
F = the flow rate contribution associated with the 2.1.4 release of a waste gas decay tank. (cm8/sec)
K =
terrain recirculation factor. (unitiess) 2.3.1 Kg = total body dose factor due to gamma emissions from 2.1.1 noble gas radionuclide i. (mrem /yr per uC1/m8)
L'
= skin dose factor due to beta emissions from noble 2.1.1 gas radionuclide 1. (mrem /yr per uC1/m8 )
Mg = air dose factor due to gamma emissions from noble 2.1.1 gas radionuclide 1. (mrad /yr per uCi/m8 )
] N = air dose factor due to beta emissions from noble gas 2.2.1 radionuclide 1. (mrad /yr per uCi/m8) n k
=
number of hours meteorological conditions are 2.3.1
. observed to be in a given wind direction, wind-speed class k, and atmospheric stability class j.
2-44 J
~ - - - e e-- n, -, .--..,
, . , . - - - - . - - -s , - . , ,.-,,,.,,--,._,,,,n.
Section of Term Definition Initial Use N = total hours of valid meteorological data. 2.3.1 P = dose parameter for radionuclide 1, (other than 2.1.6 noble gases) for the inhalation pathway, in mrem /yr per uCi/m8 .
Q[ = rate of release radionuclide i from the Plant Vent 2.1.1 Stack. (uCi/sec) ,
Q{ = cumulative release of radionuclide i for 2.2.1 31 days, calendar quarter or year as appropriate. (uC1)
R{'"' = dose factor for radionuclide 1, pathway p, and age 2.2.2 group a. (mrem /yr per uCi/m8 ) or (m -mrem 2
/yr per uCi/sec) r = distance from the point of release to the location 2.3.1 of interest for dispersion calculations. (meters).
SF = Safety Factor of 0.5 applied to compensate for 2.1.2 statistical fluctuations and errors of measurement.
(r) ,= vertical plume spread with a volumetric correction 2.3.1 for a release within the building wake cavity, at a distance, r, for stability class, J.
g = vertical standard deviation of the plume concentration 2.3.1 (in meters), at distance, r, for stability category j.
k = wind speed (midpoint of windspeed class k) at ground 2.3.1 level (m/sec) during atmospheric stability class j.
W' = the dispersion parameter for estimating the dose to 2.2.2 an individual at the location where the combination of existing pathways and receptor age groups indicates the maximum exposures.
X/Q = the annual average relative concentration at 2.2.2 the location of interest. (sec/m8)
X/Q = the highest annual average relative concentration 2.1.1 8
attheageboundary. 8 (sec/m )
= 3.3 x 10 sec/m in the NNW sector X
I
= the concentration of noble gas radionuclide i in the 2.1.1 batch release stream (uCi/cm ) as sampled in accordance with RETS Table 4.11-2.
2-45
4 l
i I
Section of I~ Tera Definition Initial Use
, X
= the concentration of radionuclide i in the continuous 2.1.1 ,
3 release stream (uC1/cm ) as sampled in accordance '
f with RETS Table 4.11-2.
X = the concentration of radianuclide i present at the iv plant vent. (uCi/cm )3 2.1.1 X
GV
= the concentration of noble gases present at the 2.1.2
- plant vent due to the combined sources as calculated l from the radionuclide concentrations determined from the analysis of the appropriate samples taken j in accordance with RETS Table 4.11-2. (uci/cm3 )
X 7y = the concentration of radioiodines present at the 2.1.7 plant vent due to the combined sources as calculated i
, from the radionuclide concentration determined from i
! the analysis of the appropriate samples taken in j accordance with RETS Table 4.11-2. (uC1/cm3 )
4 j X gy = the concentration of noble gas radionuclide i in the 2.1.4 i auxiliary building ventilation stream due t'o sources
. other than the waste gas decay tanks. (uci/cm ) 3 l X
= the concentration of noble gas radionuclide i at the 2.1.4
, auxiliary building ventilation monitor during a i waste gas decay tank release. (uci/cm )3 1
)
i X icont
= the concentration of noble gas radionuclide 1 in 2.1.5
- the containment release stream as sampled in j accordance with RETS Table 4.11-2. (uC1/cm3 ). ,
^
- X iGDT
= the concentration of noble gas radionuclide i in 2.1.4
- thewastegasdecaytankassamgledinaccordaace .
i with RETS Table 4.Il-2. (uCi/cm )
Xpy = The concentration of particulates present at the 2.1.8 plant vent due to the combined sources as calculated from the radionuclide concentrations f determined from the analysis of the appropriate samples taken in accordance with RETS Table 11.4-2.
l (uci/cm3 )
I z = the fraction of time the wind blows to the sector of 2.3.2
- interest l 1.1 = conversion factor of mrem skin dose per mrad air dose. 2.1.1
! 500 = the technical specification dose rate limit to the 2.1.2 l total body of an individual in an unrestricted area
[ due to noble gases. (mrem /yr) i I
2-46 l
l
- . _ - . . = . .. --- . . .=_ _ .- _ - -__ . --. . . . . _ _
"e ,
Section of Term Definition Initial Use 3000 = the technical specification dose rate limit to the 2.1.2 skin of the body of an individual in an unrestricted area due to iodines, tritium, and particulates.
(mrem /yr) 1500 = the technical specification dose rate limit to any 2.1.7 organ due to iodines, tritium, and particulates.
(mrem /yr)
)
2-47
d
[
DISCHARGE TO Af tSOSPHERE DISCMARGE TO Aft 00SPteERE J L JL (1,8,el X mE-SS 7 Mas-SS70 A (1,8,8)
SAtsPLE Sus
- GASEOUS WASTE PROCESSMG SYSTEM SAasPLE Suso l
P.Su= t
( .> = =- S = = x=-un A i.i i
(8,,=.. ,68 ==-uru t.i
=a,:a,,*;=, = . - - ,. -- , A i.
PESSWATER d Pase0ARY PLANT EENAUST Alft PLE00Utd h l l lai JLJLJ LJ LJ LJ LJ LJ LJ LJ LJ L J L J LJ LJLJ LJ LJ L i
. = - o.. s ,,
'a'",,g w, I ,,
j (.i .--u n l ,,,,.,,,, I.,l1ag-m:-
i f.,
,,, e(=>
UseIT a UsseT s l ; (2 )
SAPseUAnot ; COe0TAleda8ENT f3I Au g LIAfty If SUeLeesse HvAC UNIT 1 l g,3 CONTAlstasENT N a 1 ..E.S... ..,
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FEESWAMA A=A IPrimerNy from Velema (S) la addellen te HI-Red, etteelt felture, less of counts, less of flew or channel eut of service will l Centeel Tank) eastsete the sectres fumettee.
(4) FIItere are presamt between the AsIt BffAuf PLSegund AND EMMAUST AIR PLE00Uet. There are sixteen banke ;
{ t) Wide flenge Gee RSerJter, Hi-fled Indication sleets walve HCV-014 et #11 tere divided Into TRAIII A and TRA8BI S. Rech henk eenetete of a serben filter, 2HEPA flIter, e corben i (Weste See Release) and In6tietes sentrol room emergency restreutellen. fester, and a DEPA flIter In eerles.
l (3) MS-Red indteetten by menMer sleese selve. (7) A8eatter MRE-SSSO leested on 868'G* tevel In Ass. Side.
(S) M6-Red indeoetten Snetlelee sentelament leetettee. (4) aseettere ERESSFSA, 22888705 NMTA/GSA/7sA MIIE-SSSTS/688/788 l
(4) Eleht seeeems dessy tenho ese be IndivideeSy purged (There are tes 3RESO98 are leested ee SFS*S* tevet of Aes. Sede. l edditlemet tente for shutdown). (9) RSeattere 1988487 end SAESGSF ere leseted on level SSR*S* et the Aus. 314g.
, (tel asenteer NRES700 Is leested on 944* 8evel of Ass. Beds.
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! 0.1 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANOE (KILOMETERS) j Plume Depletion Effect for Ground-Level, Releases (All Atniospheric Stability Classes) t Figure 2.2
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1 0.1 1.0 10 100 PLUME TRAVEL DISTANCE (KILOMETERS)
Vertical Standard Devienon of Materialin a Plume (Letters denote Pasquill Stability Class)
NOTE: THESE ARE STANDARD RELATIONSHIPS AND MAY HAVE TO BE MOOlFIED FOR CERTAIN TYPES OF TERRAIN AND/OR CLIMATIC CONDITIONS (E.G., VALLEY, DESERT, OVER WATER).
Figure 2.3 2-50
10-3 , r ;
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Relative Deposition for Ground Level Releases (All Atmospheric Stability Classee)
Figure 2.4 2-51 t
l
. . - __ .-__ . ~. . - . . .- . - .
_ . . - - _ - - _ - .. . .. . - - . - _. .__ .~.
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.; Open Terrain Correction Factor Figure 2.5 t i
__ _ _ __. _ _ . _ - _ _ . -. _ ____._________J
SECTION 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING 3.1 SAMPLING LOCATIONS Sampling locations as required in Technical Specification 3/4.12.1 are described in Table 3.1 and shown on the map in Figure 3.1.
NOTE: For the purpose of implementing Technical Specification 3.12.2, sampling locations will be modified as required to reflect the findings of the Land Use Census. Dose calculations used in making this determination will be performed as specified in Section 2.2.4.
3.2 INTERLABORATORY COMPARISON PROGRAM For the purpose of implementing Technical Specification 3.12.3, TUGC0 has contracted Teledyne Isotopes Midwest Laboratory to perform the Interlaboratory Comparison Program. The program is operated by agencies which supply environmental-type samples (e.g., milk or water) containing concentrations of radionuclides known to the issuing agency but not to the participant laboratories. The purpose of the program is to provide an independent check on the laboratory's analytical procedures and to alert it to any possible problems. Participant laboratories measure the concentrations of specified radionuclides and report them to the issuing agency. Several months later, the agency reports the known values to the participant laboratories and specifies control limits. Results consistently higher or lower than the known values or outside the control limits indicate a need to check the instruments or procedures used. Teledyne participates in the 3-1
f i
l environmental sample crosscheck program for milk and water samples !
conducted by the U.S. Environmental Protection Agency Intercomparison and Calibration Section. Quality Assurance Branch, Environmental Monitoring and Support Laboratory, Las Vegas, Nevada. The results of the program are included in the Annual Radiological Environmental Operating Report.
b l
4 9
3-2
J i
Table 3.1
, Environmental Sampling Locations Sampling Location Sample 4
Point (Sector - Miles) Type
- i
~
1 E-0.5 A 2 N-2.2 A
) 3 W-2.0 A i 4 NNW-4.6 A 5 E-3.5 A i
i 6 SE-3.85 A 1
7 SSE-4.5 A i 6 8 N-9.4 A ,
9 SW-12.3
] A l 10 N-1.2 R 11 N-4.4 R 12 N-6.5 R 13 N-9.4 R i
i 14 NNE-1.1 R i 15 NNE-5.65 R 1 16 NE-1.7 R 17 NE-4.8 R l
18 ENE-2.5 R t
19 ENE-5.0 R i
20 E-0.5 R e
i i
3-3 i
- - - - - . - - _ . . - . - - - - - - - - _ - - - = - _ . - - _ - - - _ . . _ _ - - - . - _ _
Table 3.1 (Continued)
Environmental Sampling Locations, continued ,
Sampling Location Sample Point (Sector - Miles) Type
._ 29 SSE-1.3 R 30 SSE-4.4 R 31 SSE-4.5 R 32 S-1.5 R 33 S-4.2 R '
I 34 SSW-1.0 R 35 SSW-4.4 R 36 SW-0.9 R 37 SW-4.8 R 4
38 SW-12.3 R t 39 WSW-1.0 R l 40 WSW-5.35 R 4
4 f
3-4
Table 3.1 (Continued) t' Environmental Sampling Locations
- Sampling Location Sample Point (Sector - Miles) Type
- 41 WSW-7.0 R i i
42 W-1.0 R 43 W-2.0 R 44 W-5.5 R 45 WNW-1.0 R 1 46 WNW-5.0 R r
47 WNW-6.7 R 48 NW-1.0 R 49 NW-5.7 R 50 NW-9.9 R 51 NNW-1.35 R l
52 NNW-4.6 R 53 NNW-0.1 SW i 54 N-9.9 SW 4
55 N-19.3 SW i
56 W-1.2 CW l 57 WSW-0.1 CW 58 SSE-4.5 CW I 59 N-10.0 GW
, 60 NNE-1,.0 SS l
l 61 N-9.9 SS ,
l l
- 3-5
. . - . - - _ _ _ - _ . - . - . , _ , . _ _ . - , ~ _ .. _
Table 3.1 (Continued)
Environmental Sampling Locations Sampling Location Sample Point (Sector - Miles) Type
- 62 S-4.8 M 63 SW-13.5 M 64 ENE-2.0 F 65 NNE-8.0 F 66 E-4.2 V 67 SW-13.5 V
- Types: A - Air Sample, R - Direct Radiation, SW - Surface Water, GW - Ground Water, SS - Shoreline Sediment, M - Milk F - Fish; V - Vegetation.
- Due to the current availability of milk sampling locations, milk samples are taken at only two locations. If additional milk sampling locations are identified in future land'use census, the radiological environmental a
monitoring program will be revised to include up to a maximum of 3 samples and one control, as indicated in TS 3.12.1, Table 3.12, 3-6
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i l
i APPENDIX A Calculation of Pg (Inhalation)
Pg (inhalation) = K' (BR) DFA where:
l P
g = the dose parameter for radionuclide, i. (other than noble gases) for the inhalation pathway, in mrem /yr per s
microcurie /m . .The dose factors are based on the critical individual organ for the child age group.
k' = conversion factor, 106pCi/ microcurie 8
BR = 3700 m /yr, breathing rate for child (Ref. 2, Table E-5)
DFA g - the maximum organ inhalation dose factor for the child age l group for the ich radionuclide (mrem /pCi). Values are taken i
from Table E-9, Reg. Guide 1.109 (Ref. 2) l Resolution of the units yields:
l 9 Pg (inhalation) = 3.7 x 10 DFAg (mrem /yr per uCi/ms )
l The latest NRC Guidance has deleted the requirement to determine Pg (ground plane) and Pg (food). In addition, the critical age group has been changed
! from infant to child.
l l
l A-1 l
l
APPENDIX B Inhalation Pathway Factor, R Ig,, (X/Q) i Rf,(X/Q)=k'(BR)(DFAg ,) (arem/yr per microcurie /m8 )
where k' = conversion' factor, 100 pCi/ microcurie BR = breathing rate, 1400, 3700, 8000, 80008 m /yr for infant, child, teenager, and adult age groups, respectively. (Ref. 2, Table E-5)
DFA g,, = the maximum organ inhalation dose factor for the receptor of a given age group, a, and for the ich radionuclide, in mrem /pCi.
- The total body is considered as an organ in the selection of DFA g ,, Values are taken from Tables E-7 through E-10, Reg.
Guide 1.109 (Ref.2) l l
l r
i 9
l I
l l
B-1 a
APPENDIX C Ground Plan Pathway Factor, R (D/Q)
R (D/Q) = k' k" (SF) DFG 1 [(1-e t)j j where 0
k' = conversion factor, 10 pCi/
microcurie k" = Conversion factor, 8760 hr/yr
-I gg = Decay constant for the ith radionuclide, sec t = the exposure time (this calculation assumes that decay is the 8
only operating removal mechanism) 4.73 x 10 sec. (15 yrs)
DFG = the ground plane dose conversion factor for the ich radionuclide (mrem /hr per pCi/m2 ). Values are taken from Table E-6, Reg. Guide 1.109 (Ref. 2)
SF = 0.7, shielding factor, from Table E-15 Reg. Guide 1.109 (Ref. 2) l C-1 1
P
<t APPENLIX D Grass-Cow-Milk Pathway Factor, R *
(D/Q) ,
R a(D/Q) = k' [(QF*UAP !
w} *(m * ( .
i,a
[((fp x f s)/ Y p )",+ ((1-f p-xf)e--
s i th)/Ys ] e- if where:
, k' = conrersica factor, 106picoeurie/ microcurie-(pCi/uci)
QF = c w consumption rate, 50 kg,/ day, (R.G. 1.109$
Ug. = Receptor's milk consumption ratei; 330, 330, 400, 310 liters /yr
, for infant, child, teenager, and adultJ> age groups, respectively (R.G. 1 109) r s.
t
- 1 <
Y p = agricultural productivity by unit area of pasture feed grass.
0.7 kg/m 2(NUREG-0133)
~
Y, q = agricultural productivity by unit area of-stored feed, 2.0 kg/m 2, (NUREG-0133) .:
f..
= stable element transfer' coefficient (Table E-1, P..C. 1.109)
F, r = fraction of depocited activity retained on cow's feed g ss, i -
0.2 for partic'ulates,1.0 for rzdiciodine (Table E-15, l
R.G. 1.109) '
DFL
, = cfre uaximum organ ingestion dose factor for the ith radionuclide for each respective age group, a (Tables E-11' to E-14, R.G. 1.109) k = decay constant for the ich radionuclide,.sec~
Ay = decay constant for veathering, 5.73 xt10 -7 see -1 (NUREG-0?33) .
5 t
g = > 1. 71 x 10 sec, the transport time from pasture to cow to milk to reccptor (Table E-15, R.G. 1.109) /, ,
/, s >
I i D-1
\
APPENDIX D (CONTINUED) 6 t
h = 7.78 x 10 sec, the transport time from pasture to harvest to cow to milk to receptor (Table E-15, R.G. 1.109) f = 1.0, the fraction of the year that the cow is on pasture.
f, = 1.0, the fraction of the cow feed that is pasture grass while the cow is on pasture.
The concentration of tritium in milk is based on the airborne concentration rather than the deposition. Therefore R is based on (X/Q):
R t,a(X/Q) = k'k F,Q p U AP t,a (.75 (.5/H))
where:
k = 108 grams /kg 8
H = 8 grams /m , absolute humidity of the atmosphere
.75 = fraction of total feed grass mass that is water
.5 = ratio of the specific activity of the feed grass water to the atmospheric water. (NUREG-0133)
DFL
= the maximum organ ingestion dose factor for tritium for each respective age group, a (Tables E-11 to E-14, R.G. 1.109)
All other parameters and values are as given above.
NOTE: Goat-milk pathway factor, R (D/Q) will be computed using the cow-milk pathway factor equation. F factor for goat-milk will be from Table E-2 R.G. 1.109.
D-2
APPENDIX E COW-MEAT PATHWAY FACTOR Ri,a (D/Q)
R g,,(D/O = P Qpx UAP
- w} * ( f} * (# *( i,a
(((f x f 8)/Y ) + ((1 - f f ) e P P Ps ih)/Y]xekf t
s where:
6 k' = conversion factor, 10 picoeurie/ microcurie Qp = cow consumption rate, 50 kg/ day (R.G. 1.109)
U AP
- receptor's meat consumption rate; 0, 41, 65, 110 kg/yr for infant, child, teenager, and adult age groups, respectively. (R.G. 1.109)
Fg = the stable element transfer coefficients, days /kg.
(Table E-1, R.G. 1.109) r = fra'ction of deposited activity retained on cow's feed grass, 0.2 for particulates, 1.0 for radiciodine (Table E-15, R.G. 1.109)
DFL , = the maximum organ ingestion dose factor for the ich radionuclide for each respective age group, a (Tables E-11 to E-14. R.G. 1.109)
Ag = decay constant for radionuclide i, sec
-7 Ay = decay constant for weathering, 5.73 x 10 sec -I (NUREG-0133) 6 t
g = 1,73 x 10 sec, the transport time from pasture to receptor (NUREG-0133) t h
= 7.78 x 100 eac, the transport time from crop field to receptor (NUREG-0133)
E-1
APPENDIX E, CONTINUED COW-MEAT PATHWAY FACTOR R1.a (D/Q)
Y = agricultural productivity by unit area of pasture feed grass, 0.7 kg/m ,2 NUREG-0133)
Y, = agricultural productivity by unit area of stored feed, 2.0 kg/m2 (NUREG-0133) f p = 1.0, the fraction of the year that the cow is on pasture f, = 1.0, the fraction of the cow feed that is pasture grass while cow is on pasture The concentration of tritium in meat is based on its airborne concentration rather than the deposition. Therefore, R is based on (X/Q):
R ,,(X/Q) = k'k Ff Q pUAP ( t,a) x 0.75 x (0.5/H) where:
All terms are as defined above and in Appendix D.
3 s
4 E-2
l APPENDIX F Vegetation Pathway Factor, R (D/Q)
.a R ,(D/Q) = k' x [r/ (Yy (k gd,))] x (DR1,a} * ( } L*
~
U
+U f e A g i h]
where:
k' = 106picocurie / microcurie
[A = the consumption rate of fresh leafy vegetation, 0, 26, 42, 64 kg/yr for infant, child, teen, or adult age groups, respectively. (R.G. 1.109)
U = the consumption rate of stored vegetation, 0, 520, 630, 520 kg/yr for infant, child, teen, or adult age groups, respectively. (R.G. 1.109) f t = the fraction of the annual intake of fresh leafy vegetation grown locally, 1.0 (NUREG-0133) f = the fraction of the stored vegetation grown locally
.76 (NUREG-0133) t g = the average time between harvest of leafy vegetation and its 4
consumption, 8.6 x 10 seconds (Table E-15, R.G. 1.109 (24 hrs))
t h = the average time between harvest of stored vegetation and its 6
consumption, 5.18 x 10 seconds (Table E-15, R.G.1.109 (60 days))
Y y = the vegetation areal density, 2.0 kg/m (Table 2
E-15, R.G.I.109)
All other parameters are as previously defined F-1
The concentration of tritium in vegetation is based on the airborne concen-tration rather than the deposition. Therefore, R is based on (X/Q)
R ,,(X/Q) = k'k [U ft+U f]g (DFLt a) (.75 (.5/H))
where:
All terms are as defined above and in Appendix D.
4 F-2
{ -.
Log # TXX-4499 TEXAS UTILITIES GENERATING COMPANY MKYWAY TOW EH
- 400 NORTH OLIVE MTHEET, L.B. M1 ' DALLAM, TEXAM 73201 June 27, 1985
'1"."J.US*
Director of Nuclear Reactor Regulation Attention: Mr. Vince S. Noonan, Director Comanche Peak Project Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C. 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION DOCKET NOS. 50-445 AND 50-446 0FFSITE DOSE CALCULATION MANUAL REF: NRC letter from V. S. Noonan to M. D. Spence dated 5/7/85
Dear Mr. Noonan:
Please find enclosed the proposed final draft of the CPSES Offsite Dose Calculation Manual (00CM). Comments forwarded in your letter of May 1985 have been resolved and the results incorporated into the manual. A description of the resolution of each of these comments is included as Attachment A.
Further revisions to the ODCM were made to incorporate certain textual changes and to reflect current methodology used in performing various calculations. A description of all changes made to the ODCM is included as Attachment B to assist in the review of the manual.
If you have any questions, please call Steven D. Karpyak at (214) 979-8227.
Sincerely, Og .es. k ohn W. Beck SDK/grr Attachments Enclosure f
(Ldho A URVINDON OF TEXAN l'TELETIEN ELECTNic COMi%NY
._