ML17212B603
| ML17212B603 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 05/13/1982 |
| From: | FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17212B604 | List: |
| References | |
| C-200, NUDOCS 8205180473 | |
| Download: ML17212B603 (132) | |
Text
FLORIDA POWER & LIGHT COMPANY ST ~ LUCIE PLANT CHEMISTRY OPERATING PROCEDURE C 200 REVISION 0 OFFSITE DOSE CALCULATION MANUAL
Page 1 of TABLE OF CONTENTS
~Pa e Title St. Lucie Plant Offsite Dose Calculation Manual Introduc tion Glossary 1.0 Radioactive Releases of Liquid Effluents 1.1 Liquid Effluent Model Assumptions 1.2 Determining the Fraction (F) of 10CFR20 MPC Limits for Radioactive Liquid Releases 1.3 Determining Setpoints for Radioactive Liquid Effluent Monitors 1.4 Determining the Dose from Radioactive Liquid Effluents 11 1.5 Projecting Dose for Radioactive Liquid Effluents 16 2.0 Radioactive Releases of Gaseous Effluents 2.1 .Gaseous Effluent Model Assumptions 17 2.2 Determining the Total Body and Skin Dose Rates for Noble Gas Releases and Establishing Setpoints for Effluent Monitors- 18 2.3 Determining the Radioiodine and Particulate Dose Rate To Any Organ From Instantaneous Gaseous Re1eases--------- 23 DISCUSSION 23
- 2. 3.1 Inhalation 25
- 2. 3.2 Ground Plane 26
- 2. 3.3 Milk 28
- 2. 3.4 Tritium 29
- 2. 3.5 Total Dose Rate by Release Source 31
- 2. 4 Determining the Gamma Air Dose for Radioactive Noble Gase Releases 32
- 2. 5 Determining the Beta Air Dose for Noble Gase Releases 'adioactive 34
- 2. 6 Determining the Radioiodine and Particulate Dose To Any Organ From Cumulative Releases DISCUSSION 37 ST LUCIE UNIT NO 1-ODCM
Page 2 of TABLE OF CONTENTS cont 2.6 (cont) 2.6.1 Inhalation 39 2.6.2 Ground Plane 40 2.6.3 Milk
- 2. 6. 4 Tritium dose (~<ll Pathways) 4241 2.6.5 Total Organ Dose 43 2.7 Projecting Dose For Radioactive Gaseous Zff. 44 3.0 40 CFR 190 Dose Evaluation 45 4.0 Semiannual Report Format 46 Appendix A- MPC, Dose Factor and Historical Meteorological Tables 57 Appendix B- Limited Analysis Dose Assessment for Liquid. Radioactive Effluents 8i Appendix C- Technical Bases for Effective Do s e Factors 8+
Appendix D- Technical Bases for Eliminating Curie Inventory Limit for Gaseous Y/aste Storage Tanks 89 Appendix E- Current R.E.M. Sample Point Location Map for Sts-A 3/4.12 92 ST LUCIE UNIT NO 1-ODCM
Page 3 of INTRODUCTION This manual provides the methodology to calculate radiation dose, to individuals in the vicinity of the St. Lucie site, from radio-active gaseous and liquid effluents. It also provides methodology for calculating effluent monitor setpoints and allowable release rates to ensure compliance with the STS and 10CFR20 release criteria.
The in-plant procedures specify what sections of the ODCN should be completed to calculate the dose to an individual.
The ODCi~l follows the methodology and models suggested by NUREG-0133 (Nov 1978) and Regulatory Guide 1.109. Simplifying assumptions have been applied where applicable to provide a more workable document for implementing the Technical Specification requirements.
Alternate calculation methods may be used from those presented as long as the overall methodology does not change or as long as the alternative methods provide results that are more limiting.
Also, as available, the most up-to-date revision of the Regulatory Guide 1.109 dose conversion factors and environmental transfer factors may be substituted for those currently included and used in this document.
ST LUCIE UNIT NO 1-ODCH
GLOSSARY OF COKION TERMS dose (dose rate) from Beta radiation CC cubic centimeter Ci Curies - a unit of radioactivity see pCi C
i
~ activity'."or concentration of a nuclide in the release source.
Uni.ts of pCi., pCi/cc, or pCi/ml CFR Code of Federal Regulations Dose The exposure, in mrem or mrad, the organ or the individual receives romf radioac tive ef fluents.
Dose Factor - Normally, a factor that converts the effect of ingesting radioactive material into the body, to dose to a specific
'rgan. Body elimination, radioactive decay, and organ uptake are some of the factors that determine a dose factor'or a given nuclide.
Dose Pathway A specific path that radioactive material physically travels through prior to<< exposing an individual to radiation. The Grass-Cow-Milk-Infant is a dose path-way.
Dose, Rate - The dose received per unit time.
(D/Q) a long term D over Q a factor with units of l/M which describes the deposition of particulate matter from a plume at a point downrange from the source. It can be thought of as what part of the cloud is going to fallout and deposit over one square meter of ground.
Gamma f a gamma photon the dose from Gammas in air etc.
Ground Plane Radioactive material deposited uniformly over the ground emits radiation that produces an exposure. pathway when an individual is standing, sitting, etc. in the area. It is assumed that an adult receives the same exposure as an infant, regardless of the physical height differences. Only the total body is considered for the ODCM.
H-3 Hydrogen-3, or Tritium, a weak Beta emitter.
I68DP Radioiodines and particulates with half-lives greater than 8 days LCO Limiting, condition for operation in STS m cubic meters m square meters ST. LUCIE UNIT 1 ODCM
Page 5 of MPC Maximum Permissible Concentration nuclide for the purposes of this manual, a radioactive isotope.
nuclide (i) signifies a specific nuclide> the 1st> 2nd, 3rd one under consideration. If nuclide (i) is 1-131, then the
~ Mi (dose factor) under consideration should be MI 131 for
'xample.
Organ .- For the ODCM either th'e bone, liver, thyroid, kidney, lung, GI-LLI, or the T. Body. T. Body (Total Body) is considered an organ for ease of writing the methodology in the ODCM.
Qi dotted Denotes a release rate in yCi/sec for nuclide(c)
Qi Denotes pCi of nuclide (i) released over a specified time interval.
Receptor The individual receiving the exposure in a given location or who ingests food products from a animal for example.
A receptor can receive dose from one or more pathways.
Release Source(s) A subsystem, tank, or vent where radioactive material can be released independently of other radioactive release points STS The St. Lucie Unit 1 Standard Technical Specifications gCi micro-Curies. 1 pCi = 10 Curies. The pCi is the standard unit of radioactivity for all dose calculations in the ODCM.
(X/Q) a long term Chi over Q. It describes the physical dispersion characteristics of a semi-infinite cloud of noble gases as the cloud traverses downrange from the release point. Since Noble Gases are inert, they do not tend to settle out on the ground.
(X/Q)D a long term Depleted Chi over Q. It describes the physical dispersion characteristics of a semi-infinite cloud of radioactive iodines and particulates as the cloud travels
.downrange. Since Iodines and particulates tend to settle out (fallout of the cloud) on the ground, the ~X )D represents what physically remains of the cloud and its dispersion qualities at a given location downrange from the release point.
1.0 L I U I D' E L.E A S E S METHODOLOGY
Page 6 of Radioactive Li uid Effluent Model Assum tions The FSAR contains the official'description of the site char-acte 'istics. The description that follows is a brief summary for dose calculation purposes:
The St. Lucie Plant is, located on an island surrounded on two sides by the Atlantic Ocean and the Indian River, an estuary of the Atlantic Ocean. Normally, all radioactive liquid re-leases enter the Atlantic Ocean where the Circulating Water Discharge Pipe terminates on the ocean floor at a point approx-imately 1200 feet offshore. No .credit is taken for subsequent mixing of the discharge flume with the ocean. The "diffusion of radioactive material into the ocean is dependent on the conditions of tide, wind, and some eddy currents caused by the Gulf Stream. The conditions are sufficiently random enough to distribute the discharges over a wide area and no concentrating effects are assumed.
There are no direct discharge paths for liquid effluents to either of the north or south private property boundary lines.
The Big Mud Creek (part of the Indian River) does connect to a normally locked shut dam, that is intended to provide an emergency supply of circulating water to the Intake Cooling Water Canal in the event a Hurricane causes blockage of the Intake Canal. No radioactive water could be discharged di-rectly into the Intake Cooling Water Canal because all plant piping is routed to the discharge canal and no back flow can occur. Consult the FSAR for a detailed description of char-acteristics of the water bodies surrounding the plant site.
Only those nuclides that appear in the Liquid Dose Factor Tables will be considered for dose calculation.
1.2 Determinin the Fraction F of 10CFR20 MPC Limits for A Li uid Release Source Discussion - Technical Specification 3.11.1.1 requires that the sampling and analysis results of liquid waste (prior to discharge) be used with calculation methods in the in-plant procedures to assure that the concentration of liquid radioactive material in the unrestricted areas will not exceed the concentrations specified in 10 CFR 20, Appendix B> Table II. This section presents the calculation method to be used for this determination.
This method only addresses the calculation for a specific release source. The in-plant procedures will provide instructions for determining that the summation of each release source's F values do not exceed the site's 10 CFR 20 MPC limit. The values for release rate> dilution rate, etc will also have to be obt'ained from in-plant procedures. The basic equation is:
ST LUCIE UNIT NO 1-ODCM
Page 7 of 1.2 (cont)
Hhere:
F = the fraction of 10CFR20 ?PC that would result if the release source was discharged under the conditions specified.
R = The undiluted release rate in gpm of the release source.
D = The dilution flow in gpm of Intake Cooling Hater or Circulating Mater Pumps i
C. = The undiluted concentration of nuclide (i) in pCi/ml from sample assay.
(MPC). = The maximum i permissible concentration of nuclide (i) ~
in pCi/ml from Table L-1. For dissolved or entrained noble gases the MPC value is 2 x 10 pCi/ml fo1'he sum of all. gases.
The fraction of the 10 CFR 20 MPC limit may be determined by a nuclide-by-nuclide evaluation or for purposes of simplifying the calculation by a cumulative activity evalua)ion. If the simplified method is used, the value of 3 x 10 pCi/ml (unidentified MPC value) should be substituted for (MPC), i and the cumulative concentration (sum of all i'dentified radionuclide concentrations) or the gross concentration should be substituLI,ed for C.. As long as-8 the diluted concentration (C i D) is less than 3 x 10 pCi/ml, 1
the nuclide-by-nuclide caicuxation is not required to demonstrate compliance with the 10 CFR 20 MPC limit. The following section provides a step4y-step procedure for determining the MPC fraction.
- 1. 2. 1 Calculation Process for $ oi j Qs 1.2.1.1 Obtain from the in-plant procedures, the release rate value (R) in gpm for the release source.
1,2. 1.2 Obtain from the in-plant procedures, the dilution rate (D) in gpm. No credit is taken for any dilution beyond the discharge canal flow.
1.2.1.3 Obtain (C.), the undiluted assay value of nuclide (i), in phi/ml. If the simplified method i,s used," the cumulative concentration (C )
is use4. total 1.2. 1.4 From Table L-l~ obtain the corresponding (MPC).
for nuclide (i) in pCi/ml. The value of 3 x 10 pCi/ml should be used for the simplified method.
1.2.1.5 Divide C. by (MPC)i and write down the quotient.
ST LUCIE UNIT NO 1-ODCM
Page 8 of
- 1. 2 (cont) 1.2.1 (cont) 1.2.1.6 If, the simplified method is used, proceed to the next step. If determining the MPC fraction by the nuclide-by-nuclide evalu'ation, repeat steps 1.2.1.3 through 1.2.1.5 for each nuclide reported in the assay.
1.2.1.7 Add each C./(MPC). i quotient from step 1.2.1.5 and solve for F F; =
D F
L
= a unit-less value where'.
The value of F could be ~ 1 or )1. The pur-pose of the calculation -is to determine what the initial value of F is for a given set of release conditions. Xi F is )1, administrative steps are taken to ensure that the actual Telease conditions for dilution will ensure that F is
~ 1 during the actual release. FL is cal ed
'the fraction of 10CFR20 HPC because it should never be allowed to be ) l.
1.2.2 Calculation Process for Gases in Liquid 1.2.1.1 Sum the uCi/ml of each noble ga's activity reported in the release.
1.2. 1.2 The values of R and D from 1.2. 1 above shall be used in the calculations below:
( sum o f 1. 2. 1. 1) uCi/ml R 1 D 1.2.1. 5 7 shall be less than 2 x 10 uCi/ml .for the site for all releases in progress. 'Each release point will be admininstratively controlled. Consult 'in-plant procedures for "instructions. h ST LUCIE UNIT NO 1" ODCM
1.3 Determinin Set pints for Radioactive Li used Effluent Monitors Discussion - Technical Specification 3.3.3.8 requires that the liquid effluent monitoring instrumentation alarm/trip setpoints be set to initiate an alarm or trip so that the radioactivity concentration in water in the unrestricted area does not exceed the concentration 6f;;10 CFR 20> Appendix B, Table II as a result of radioactivity in liquid effluents, CTechnical Specification 3.11.1.1). This section presents the method to be used for determining the instrumentation setpoints.
Gross cpm vs total liquid activity curves are available for Liquid Effluent Monitors based on a composite of real release data. A direct correlation between gross cpm and the concentrations that would achieve 10 CFR 20 MPC levels in the discharge canal can be estimated. The 1978 liquid release data from semiannual reports was used to determine the average undiluted release concentration. These concentrations were then projected to a diluted concentration in the discharge canal assuming a 1 gpm release rate and a constant dilution flow of 121,000 gpm from 1 circ water pump. This diluted activity was divided by the nuclide's respective 10CFR20 MPC value (Table L-1) to obtain the Mi column on the table that follows.
Table 1.3 1978 M
NUCLIDE UNDILUTED 1 SYMBOL ~ci/mli (no units)
I-131 4.43 E-5 1. 22 E-3 I-132 2.23 E-7 2.30 E-7 I-133 3.17 E-6 2 '2 E-5 I-135 1.31 E-6 2.71 E-6 Na-24 1.72 E-7 4.74 E-8 Cr-51 2.51 E-5 1.04 E-7 Mn-54 5.64 E-6 4.66 E-7 Mn-56 1.11 E-9 9.17 E-11 Co-57 3.69 E-7 7.62 E-9 Co-58 E-4 39 E-5 Fe-59'.512.92 E-6 1 ~
4.83 E-7 ST LUCIE UNIT NO 1"ODCH
Pagel0 of Table 1.3 (cont) 1978 NUCLIDE UNDILUTED .
(no iunits)
M.
S'BfBOL ~Ci/ml Co-60 3.66 E-5 1.00 E-5 Zn-65 4.55 E-7'.23 Ni-65 E-7 6.80 E-8 Ag-110m 1.96 E-6 5.40 E-7 I
Sn-113 i 5.75 E-7 5.94 E-8 Sb-122 !
! 2.16 E-6 5 '5 E-7 I
Sb-124 8.40 E-6 3.47 E-6 M-187 3.51 E-6 4.83 E-7 Np-239 1.57 E-7 1.30 E-8 Br-82 3.64 E-7 7.52 E-8 Zr-95 2.82 E-5 3.88 E-6 Zr-97 4.05 E-6 1.67 E-6 Mo-99 3.24 E-6 6.70 E-7 RU-103 3.84 E-8 4.00 E-9 Sb-125 2'.26 E-6 1.87 E-7 Cs-134 2.14 E-5 1.96 E-5 Cs-136 7.82 E-7 1.08 E-7 Cs-137 4.85 E-5 2.00 E-5 Ba-140 6.44 E-7 2.66 E-8 Ce-141 3.04 E-8 2.80 E-9 Ce-144 2 '7 E-6 1.96 E-6 4.01 E-4 M
Total = 1.33 E-3 (1) 1978 Undiluted Release Volume = 7 E 9 mls.
(2) ."f. = 1978 Undil. Act Nuclide (i) X 1 m (release rate) i MPC. (from Table L-1) 121000 gpm (dil rate)
ST LUCIE UNIT NO 1-0DCM,
Page ll of 1.3 (cont)
A Tot is the total average pCi/ml concentration of the reference mixture and MT Tot. is the fraction of the MPC of all nuclides for the release conaitions specified. Dividing ATot by M. Tot yie1ds which is the maximum total activity concentration equivalent to tne MPC limit for the nuclide distribution typichl of radwaste ax.'ischarges.
A-,. 4.oi E-4 p
'he assumption that the mixture does not change is only used for calculatioral purposes.
1.3.1 The (C ) value in cpm should be obtained for the A (0.302 @%i/m1) from the release sources radioactive liquid effluent monitor curve of cpm vs pCi/ml.
NOTE: This setpoint is for a specified release of 1 gpm into 121000 gpm dilution flow.
1.3.2 For establishing the setpoint prior to liquid radwaste d'ischarges, the (C max ) will be adjusted as needed to account for actual release conditions (ie> actual liquid discharge flow rate and dilution flow).
1.4 Determinin the Dose for Radioactive Li uid Releases Discussion - Technical Specification 3.11.1.2 requires calculations.
be performed at least once per 31 days to verify that cumulative radioactive liquid effluents do not cause a dose in excess of 1.5 mrem to the total body and 5 mrem to any organ.
This section presents the calculational method to be used for this verification.
The method is based on the methodology suggested by sections 4.3 and 4.3.1 of NUREG-0133 Rev 1 Nov 1978. The dose factors are a composite of both the fish and shellfish pathways so that the fish-shellfish pathway is the only pathway for which dose will be calculated. For St. Lucie Unit 1> the adult is the most limiting age group> but the dose for child, and teenager can also be calculated by this method provided that their appropriate dose factors are available for the organ of interest.
Only those nuclides that appear in the Tables of this manual will be considered.
Page 12 of 1.4 (cont) 1.4.1 This method provides for a dose calculation to the total body or any organ for a given age group based on real release conditions during a specified time, interval for radioactive liquid release sources. The equation is Dl Ag rhtl~i 1
where:
D =. dose commitment in mrem,received by organ of age group (to be specified) during the release time interval Qtl.
i'r = the composite dose factor for the fish-shellfish A..
pathway for nuclide (i) for organ v of age group (to be specified). The A.iT values listed in the Tables in this manual are indepenaent of any site specific information and have the units mrem-ml pCi-hr I
At> = I the number of hours that the release occurs.
Q = The, 'total quantity of nuclide (i) released during
~t (pCi)
(DF) 1 = The total volume of dilution that occurred during the release time period 0 tl (ie, the circulating .-
water flow times time)
The doses associated with each release may then be summed to provide the cumulative dose over a desired time period (eg sum all doses for release during a 31 day period, calander quarter or a year).
D D total + 1
+
where:
= the total dose commitment to organ+ due to all T
T releases during the desired time interval (mrem)
ST LUCEE UNIT NO 1" ODCa~f
Page 13 of 1.4 (cont) 1.4.1 (cont)
Based on the radionuclide distribution typical. in radioactive effluents, the calculated doses to individuals are dominated by the radionuclides, Fe-59> Co-58> Co-60, Zn-65, Nb-95, Cs-134 and Cs-137. These nuclides typically contribute over 95% of the total body dose and over 90% of the GI-LLI dose, which is the critical organ. Therefore, the dose commitment due to radioactivity in liquid effluents may be reasonably evaluated by limiting the dose calculation process to these radionuclides for the adult total'ody and adult GI-LLI. To allow for any unexpected variability in the radionuclide distribution> a conservatism factor of 0.8 is introduced into the e'quation. After calculating the dose based on these 7 nuclides, the cumulative dose should be djvided by 0.8 the conservatism factor.
(ie> Dy .Y
= Refer to Appendix B for a detailed 0.8'88).explanation evaluation ance of this limited analysis approach.
The methodology that follows is a step-by-step breakdown to calculate doses based on the above equation. Refer to the in-plant procedures to determine the applicable organs, age groups, and pathway factors. If the limited analysis approach is used, the calculation should be limited to the Adult total body'ose and Adult GI-LLI dose from the fish and shellfish pathways. Only the 7 previously specified radionuclides should be evaluated. For the dose calculations to be included in ski.-annual reports> the doses to all age groups and all organs should be evaluated for .all radionuclides identified in the liquid effluents.
NOTE: Table 1.4 provides a convenient form for'compiling the dose accounting.
1.4.1.1 Determine the time interval At that the release R
took place. The in-plant procedures shall describe the procedure for calculating At for official release purposes.
1.4.1.2 Obtain (DF)< for the time period At from Liquid Haste >fanagement Records for the release source(s) of interest.
1.4.1.3 Obtain Q ~
for nuclide (i) for the time period At from khe Liquid Maste Hanagement Records.
1.4.1.4 Obtain A. from the appropriate Liquid Dose Factor Table.
Page 14 of 80 TABLE 1.4 FISH 6 SHELLFISH PATHWAY TL~fE/DATE START: TINE/DATE STOP: hours TOTAL DILUTION VOLUiiE: ~ mls AGE GROUP: ORGAN: DOSE FACTOR TABLE ij Nuclide (i) A.iY Dose (i) mrem Fe-59 Co-58 Co-60 Zn-65 Nb-95 Cs-134 Cs-137 Others:
Total Dose T
mrem If based on limited analysis+ 0.8 mrem ST LUCIE UNIT NO 1-ODCii1
Wage l5 of 1.4 (cont) 1.4.1 (cont) 1.4. 1.5 Solve for Dose (i)
Dose (i) =
Qil + 'tl A.
(DF) 1.4.1.6 Repeat steps 1.4.1.3 through 1.4.1.5 for each nuclide reported and each organ required.
If the limited anaiysi.s method is used, limit the radionuclides to Fe-59, Co-58, Co-60, Zn-65~ Nb-95, Cs-134> and Cs-137 and determine the adult total body dose and the adult GI-LLI dose ~
1.4.1.7 Sum the Dose (i) values to obtain the total dose to organ m from the fish-shellfish pathway. If the limited analysis method is being used, divide the cumulative dose by a conservatism factor of 0.8 to account for any unexpected variability in radionuclide distribution.
ST LUCIE UNIT NO 1-ODCi~f
Page 16 of 1.5 Pro'ecting Dose for Radioactive Li uid Effluents Discussion Technical Specification 3. 11. 1. 3 requires that appropriate subsystems of the liquid radwaste treat-ment system be used to reduce radioactive material in liquid effluents when the projected monthly dose due to liquid releases to unrestricted areas whd'n averaged over 31 days would. exceed 0.12 mrem to the total body or 0.4 mrem to any organ. Doses are to be projected at least once per 31 days. The following calculation method is provided for performing this dose projection, The method is based on dose as calculated in section 1.4 with the adult as the bases for projecting.
1.5.1 Obtain the latest result of the monthly calculation of the adult total body dose and the adult's highest organ dose. These doses can be obtained from the in-plant logs.
1.5.2 Divide each dose by the number of days the reactor plant was operational during the month.
1 ~ 5 3 Multiply the quetient of each dose by the number of
~
days the reactor plant is projected to be operational during the next month. The products are the projected dose for the next month. These values should be ad-justed as needed to account for any changes in failed fuel or other identifiable operating conditions that could significantly alter the actual releases.
I 5 4 Xf the projected
~ ~ dose is greater than 0.12 mrem to the total body or greater than 0.4 mrem to the adults highest exposed organ, the appropriate subsystems of the liquid radwaste system shall be used to reduce "the radioactivity levels prior to release.
ST LUCXE UNIT NO 1-ODCM
2.0 GASEOU S RELEASE S METHODOLOGY
page 17 of 2.1 Gaseous Effluent Model Assum tions Descri tion of Site (The. FSAR contains the official description of the site characteristics. The description that follows is a brief'ummary for dose calculation purposes only). The St. Lucie Plant is located on an island surrounded on two sides by the Atlantic Ocean and the Indian River, an estuary of the Atlantic Ocean. Private property adjoins the plant site in the north and south directions. A meterological tower is located north of the plant near the site property line. There 0 are 16 sectors, for dose calculation purposes, divided into 22.5 each. The met tower is calibrated such that a zero degree bearing coincides with TRUE NORTH. A bearing of zero degrees dissects the north sector such that bearings of 348.75 and 11.25 define the boundaries of the north sector. The nearest distance to private property occurs in the north sector at approximately 0.97 miles.
For ease of calculation, this 0.97 mile radius is assumed in all directions, although the real Unrestricted Area Boundary is de-fined in Figure 3.11-1 of the STS. Doses calculated over water areas do not apply to the STS LCO's or the annual report and may be listed as O.W. (over water) in lieu of performing calculations.
The 0.97 mile range in the NH sector is O.M., but it was chosen as the worst sector for conservative dose calculations using the historical met data.
Historical Met Data Met data, between September 1, 1976 and August 31, 1978, from the St. Lucie Met Tower was analyzed by Dames & Moore of Mashington, D.C. The methodology used by Dames
& Moore was consistant with methods suggested by Regulatory Guide 1 111 Rev 1
~ ~ R'ecirculation correction factors were also calculated for the St. Lucie Site, and are incorporated into the historical met tables..'(Tables M5> M6, and M7) ~in Appendix.A of this manual.
Dose Calculations - Dose calculations for Technical Specification dose limits are normally calculated using historical met data and receptor location(s) which yield calculated doses no lower than the real location(s) experiencing the most exposure. Real met data factors are calculated and used in dose calculations for the Seniannoal R.garkt i Live met data and hour-by-hour dose calculations are beyond the scope of this manual. Historical information and conservative receptor locations etc., are only used for ease of STS LCO dose limit calculations. Dose calculations for STS dose limits may be performed using real met data, real receptor locations> and sector wind frequency distribution if desired. Any dose calculations performed with real data should note the source of the data in the annual report. Real met data reduction should be performed in accordance with Regulatory Guide 1.111 Rev 1 and should incorporate Recirculation Correction Factors from Table M-4 of this manual. The St. Lucie site uses the long term ground release model for all gaseous effluents. Only those radionuclidcs that appear in the gaseous effluent dose factor tables will be considered in any dose calculations. Land Census information will apply to the calendar year following the year that the census was taken in to avoid splitting quarters etc.
ST LUCIE UNIT NO 1-ODCM
0 0
Page 18 of 2.2 Determinin the Total Bod and Skin Dose Rates for Noble Gas Releases and Establishin Set pints for Effluent Monitors Discussion - Technical Specification 3.11.2.1 limits the instantaneous dose rate from noble gaseous in airborne releases to less than 500 mrem/yr total body and less than 3000 mrem/yr-skin. Technical Specification 3.3.3.9 requires that the gaseous radioactive effluent monitoring instrumentation be operable with alarm/trip setpoints set to ensure that these dose rate limits are not exceeded. The results of the sampling and analysis program of Technical Specification Table 4.11-2 are used to demonstrate compliance with these limits.
The following calculation method is provided for determining the instantaneous dose rates to the total body and skin from noble gaseous in airborne releases. The alarm/trip setpoints are based on the dose rate calculations. The Technical Specification LCOs apply to all airborne releases on the site but all releases may be treated as if discharged from a single release point. Only those noble gases appearing in Table G-2 will be considered. The calculation methods are based on Sections 5.1 and 5.2 of NUREG-0133, Nov 1978.
The equations are:
For Total Bod Dose Rate n
DR K (X/Q) Q.
For Skin Dose Rate DR skin where:
DR = total body dose rate from noble gases in airborne releases (mrem/yr)
DR skin skin dose rate from noble gases in airborne releases (mrem/yr) a mathematical symbol to signify the operations to the right of the symbol are to be performed for. each noble gas nuclide (i) through (n), and the individual nuclide doses are summed to arrive at the total dose rate for the release source.
K. = the i total body dose factor due to gamma emissions for eac) noble gas nuclide reported in the release source mrem-m $
pCi-yr ST LUCIE UNIT NO 1-ODCM
Page 19 of 2.2 (cont)
L.i= The skin dose factor'due to beta emissions for each noble gas nuclide fi) re~artsd in the assay of the release source fmrem m-q abaci-yr j M. =
i The air dose factor due to gamma emissions for each noble gas nuclide (i) reported in the assay of the release source. The constant 1.1,converts mrad to mrem since the units of M . are in mrad-m 3 1
PC i-yr (X/Q) = For ground level> the highest calcula'ted annual long term historic relative concentration foi any of the 16 sectors, at or beyond the exclusion area boundar y . ( sec /m )
Q = The release rate of noble gas nuclide (i) in pCi/sec from the release source of interest.
2.2.1 Simplified Total Body Dose Rate Calculation From an evaluation of past releases> an effective total body dose factor (K f) can be derived. This dose factor is in effect a weigfi ed average total body dose factor>
eff.'ff ie, weighted by the radionuclide distribution typical of past operation. (Refer to Appendix C for a d'etailed explanation and evaluation of K ff). The value of K ff has been derived from the radioactive noble gas effluents for the years 1978> 1979> and 1980. The value is 10 2 K
ff = 6.8 eff x . mrem-m pCi-yr l This value may be used in conjunction with the total noble gas release rate ( ZQi) to verify that the instantaneous dose rate is within the allowable limits.
To allow for any unexpected variability in the radionuclide distribution> a conservatism factor of 0.8 is introduced into the calculation. The simplified equation is DR = K (X/Q) eff Q 0.8 ST LUG IE UNIT NO 1-ODCM
Sl Page 20 of 2.2 (cont) 2.2.1 (cont)
To further simplify the determination> tQe hisfgrical annual'average meteorological X/Q of l.6 x 10 .sec/m (from Table M-1) may be substituted into the equation.
Also, the dose limit of 500 mrem/yr may be substituted for DR . Making these substitutions yields a single cumulaPive (or gross) noble gas release rate limit. This value is Noble gas release rate limit = 3.5 x 10 5 pCi/sec As long as the noble gas release rates do not exceed this value (9.5 x 10 pCi/sec)> no additional dose rate calculations are needed to verify compliance with Technical Specification 3.11.2.1.
2.'2.2 Setpoint Determination To comply with Technical Specification 3.3.3.9> the alarm/trip setpoints are established to ensure that thy noble gas releases do not exceed the value of 6.5 x Q.O pCi/sec> which corresponds to a total body dose rate of 500 mrem/yr. The method that follows is a step-by-step ~
procedure for establishing the setpoints. To allow for multiple sources of releases from different or common release points, the allowable operating setpoints be controlled administratively by allocating a percentage of the total allowable release to each of the release sources.
2.2.2. 1 Determine (V) the maximum volume release rate potential from the in-plant procedures for the release source under consideration. The units of (V) are ft /min.
2.2.2.2 Solve for A, the activity concentration in pCi/cc that would produce the Y dose rate LCO 3
sec (V) ft3 '.8x>0 cc min A = pCi/cc
- 2. 2.2.3 Refer to the pCi/cc vs cpm curve for the Release Source's Gaseous Effluent Monitor cpm value (C),
corresponding to the value of A above.
2.2.2.4 C is the 100% setpoint, assuming that there are no other release sources on the site.
ST LUCIE UNIT No 1-G])(,'g
Page 21 of
- 2. 2 (cont)
- 2. 2. 2 (cont),
2.2.2.5 Obtain the current % allocated t;o this release source from the gaseous waste management logs.
2.2.2.6 The Operating setpoint SP SP = (C) cpm x % allotted b in- lant rocedures 100%
s The total body dose is more limiting than the calculated skin dose. (Refer to Appendix C for a detailed evaluation.) Therefore, the skin dose rate calculations are not required if the simplified dose rate calculation is used (ie, use of .Keff to determine release rate limits).
The calculation process of the following Section (2.2.3) are to be used .if actual releases of noble gases exceed, the. above limit oi 3.5 x 10 pCi./sec.
Under these conditions, a nuclide-by-nuclide evaluation is required to evaluate compliance with the dose rate limits of Technical Specification 3.11.2.1.
2.2.3 Total Body and Skin Nuclide Specific Dose Rate Calculations The folloQing outline'provides a step-by-step explanation of how the total body dose rate is calculated on a nuclide-by-nuclide bases to evaluate compliance with Technical Specification 3.11.2.1. This method is only used if the actual releases exceed the value of 3.5 x 10 pCi/sec.
3 2.2.3.1 The (X/Q) value = sec/m and is the most limiting sector at the exclusion area.
2.2.3.2 Enter the release rate in ft3 /min of the release source and convert it to
) ft 3 4 x 2. 8317x10 cc x min min ft3 60 sec cc/sec volume release rate 2.2.3.3 Solve for Q. for nuclide (i) by obtaining the pCi/cc assay1 value of the release source and multiplying it by the product of 2.4.2 above Q. = (nuclide(i))
~(assa~)Ci x ( 2.4.2 value) cc CC sec Q pCi/sec for nuclide ( i)
ST LUCIE UNIT NO 1-ODCM
Page 22 of 2.2 (cont) 2.2.3 (cont) 2.2.3.4 To evaluate the total body dose rate obtain the K. i value for nuclide (i) from Table G-2.
2.2. 3. 5 Solve for TBi.
DRTB
= = mrem-ra 3 x sec x pCi DR TBi.
i K.(X/Q)Q. i jLCi-yr m3 sec mrem total body dose yr from nuclide (i) for the specified release source 2.2.3.6 To evaluate the skin dose rate obtain the L. and i H values from Table G-2 for nuclide ( i).
2-2.3.7 Solve for DR ki skin i DR ..i skin
= CL. +
gi 1.1 H.l
~i (X/Q) Q.
DR k.
skin
= mrem skin dose from nuclide (i) for yr the specified release source 2.2.3.8 Repeat steps 2.2.3.4 through 2.2.3.7 for each noble gas nuclide (i) reported in the assay of the release source.
2.2.3.9'he Dose Rate to the Total Body from radioactive noble gas gamma radiation from the specified release source is n
DRTB DRTBi 1
2.2.3.10 'The Dose Rate to the Skin from noble gas radiation from the specified release 'source is DR .
skin
= ~
~
n DR skin i The dose rate contribution of this release source shall'e added to all other gaseous release sources that are in progress at the time of interest. Refer to in-plant procedures and logs to determine the Total Dose Rate to the Total Body and Skin from noble gas effluents.
Page 23 of 2.3 Determinin the Radioiodine & Particulate Dose Rate o Ane ~or an From Instantaneous Gaseous Releases Discussion - Technical Specification 3. 11. 2. 1 limits the dose rate from radioiodines and particulates with half lives greater than eight days to ( 1500 mrem/yr to any organ. The following calculation method, is provided for determining the dose rate from radioiodines and particulates and is based on Section 5.2.1 and 5.2.1.1 through 5.2.1.3 in NUREG-0133'ov 1978.. The Infant is the controlling age group in the inhalation> ground plane, and cow/goat milk pathways, which are the only pathways con-sidered for instantaneous releases. The long term (XTQ)
(depleted) and (DTQ) values are based on historical met grata prior to implementing Appendix I; Only those nuclides that appear on Table G-5 vill be considered. The equations are For Inhalation Pathwa (excludin H-3):
Zg 8DP
~x) j.
For Ground Plane:
For Grass-Cow/Goat-Milk:
DR z g8DP C
For Tritium Releases (Inhalation & Grass-Cow/Goat-Milk):
For Total Dose Rate from I & 8DP and H-3 To an Infant Or an v:
DR + DR H-3 ST LUCIE UNIT NO 1" ODCM
Page24 of 2 ' (cont) where:.
v = The organ of interest for the infant age group.
z = The applicable pathways DR IQDP = Dose Rate in mrem/yr to the organ v from iodines and 8 day particulates DR H-3 = Dose Rate in mrem/yr to organ v. from Tritium 7
DR v = Total Dose Rate in mrem/yr to organ v from all pathways under consideration n
= A mathematical symbol to signify,the operations to the right of the symbol are to be performed for each nuclide (i) through (n), and the individual nuclide dose rates are summed to arrive at the tota1 dose rate from the pathway.
= A mathematical symbol to indicate that the tota1 dose rate D to organ v is the sum of each of the pathways dose rates i
R, = The dose factor 'for nuclide (i) for organ v for the pathway specified (units vary by pathway).
P i= The dose factor fog instantaneous ground plane pathway in units of mrem-m sec pCi-yr From an evaluation of the radioactive releases and environmental pathways, the grass-cow/goat-milk pathway has been identified as the most limiting pathway with the infant's thyroid being the critical organ. This pathway typically contributes greater than 90% of the total dose received by the infant's thyroid and the radioiodine contribute essentially all of this dose. Therefore, it is possible to demonstrate compliance with the release rate limit of Technical Specification 3.11.2.1 for radioiodines and particulates by only evaluating the infant's thyroid dose for the release of radioiodines via the grass-cow/goat-milk pathway.
The calculation method of Section 2. 3.3 is used for this determination. If this limited analysis approach is used> the dose calculations for other radioactive particulate matter and other pathways need not be performed. Only the calculations of Section 2.3.3 for the radioiodines need be performed to demonstrate compliance with the Technical Specification dose rate limit.
ST LUCIE UNIT NQ 1-QD;M
Page 25 of
- 2. 3 ( cont)
The calculations of 'Sections 2.3.1, 2.3.2> 2.3.4> and 2.3.5 may be omitted. The dose rate calculations as specified in these sections are included for completeness and are to be used only for evaluating unusual circumstances where releases, of particulate materials other than radioiodines in airborne releases are abnormally high. The calculations of Sections 2.3. 1, 2.3. 2, 2.3.4, and 2.3.5 will typically be used to demonstrate compliance with the dose rate limit of Technical Specification3.11.2.1 for radioiodines and particulates when the measured releases of particulate material (other than radioiodines and with half lives greater than eight days) are greater than ten (10) times the measured releases of radioiodines.
2.3.1 The Instantaneous Inhalation Dose Rate Method:
/
NOTE: The H-3 dose is calculated as per 2.3.4 2.3.1.1 The controlling location is assumed to be an Infant located in the sector at the mile range. Thy (X~Q)D for this locations is sec/m . This value is common to all nuclides.
2.3.1.2 Enter the release rate in ft3 /min of the release source and convert to cc/sec.
ft3 .: 2.8317x10 4 cc min
/
min ft 60 sec 2.3.1.3 Solve for Q for nuclide(i) by obtaining the pCi/cc assay value of the release source activity and multiplying above.
it by the product of 2.3.1.2 devalue i
Q. = (nuclide(i)assa CC
) Ci (Value 2.5.1.2) sec cc pCi/sec for nuclide(i) 2.3.1.4 Obtain the R.- from Table G-5 for the organ v.
ST LUCIE UNIT NO 1-ODCM
Page 26 of 2.3 (cont) 2.3.'1 (cont) 2.3.1.5 Solve for DR.
i DR. = R. (X/Q)D Q. = mrem-m pCi-yr m sec DR. mrem r ix the Dose Rate to organ from nuclide(i)
- 2. 3.1.6'epeat steps 2. 3.1.3 through 2. 3.1.5 for each nuclide(i) reported in the assay of the release source.
2.3.1.7 The Instantaneous Dose Rate to the Infants organ T from the Inhalation Pathway is DR inhalation = DR 1
+ DR 2
+ + DRn for all nuclides except H-3. This dose rate shall be added to the other pathways as per 2.3.5 Total Organ Dose.
NOTE: Steps 2. 3.1.3 through 2. 3.1.7 need to be completed for each organ v of the Infant.
'2.3.2 The Instantaneous Ground Plane Dose Rate Hethod:
NOTE: Tritium dose via the ground plane is zero.
2.3.2.1 The controlling location is assumed to be an Infant located in the sector at the ran~e. The (D/Q) for this location is 1/m . This value is common to all nuclides.
Enter the 'release rate in ft /min 3
- 2. 3.2.2 of the release source and convert to cc/sec.
ft3 2.8317x10 4 cc min
/
min ft 60sec.
ST LUCIE UNIT NO 1" ODCH
Page 27 of 2.3 (cont) 2.3.2 (cont)
- 2. 3.2.3 Solve for Q. for nuclide(i) by obtaining the pCi/cc assay value from the release source activity and multiplying it by the product of 2.3.2.2 above.
Q
= (nuclide(i)assa ) Ci X (Value 2.3.2.2)cc CC sec Q pCi/sec for nuclide(i) 2.3.2.4 Obtain the PC value from Table G-3 2.3.2.5 Solve for i DR. I 2
-sec DR. = P. (D~Q) Q. mrem-m pCi-yr X ~
m 1
X
~Ci sec DR.
i the Dose Rate to organ from nuclide(i) x'rem 2.3.2.6 Repeat steps 2.3.2.3 through 2.3.2.5 for each nuclide(i) reported in the assay of the release source I 2.3.2.7 The Instantaneous Dose Rate to the Infant's Total body from the Ground Plane Pathway is DR Gr Pl
= DR,+DR 1' + -+DRn for all nuclides. This dose rate shall be added to the other pathways as per 2.3.5 ST LUCIE UNIT NO 1" ODCH
Page28 of
- 2. 3 (cont) 2.3.3 The Instantaneous Grass-Cow/Goat-~ililk Dose Rate Hethod:
NOTE: H-3 dose is calculated as per 2.3.4 2.3.3.1 The controlling animal was established as a located in the sector at miles. The (D~Q) for this location 3.S 1/m . This value is common to all nuclides.
2.3.3.2 Enter the anticipated release rate in ft3 /min of the release source and convert to cc/sec.
ft3 .
2.8317X10 cc 4
min cc/sec min 2.3 .3.3- Solve for Q. for nuclide(i) by obtaining the pCi/cc assay value of the release source activity and multiplying it by the product of 2.3.3.2 above.
i Q. = (nuclide(i)assa CC
) Ci X (value 2.3;3.2)cc sec Q
3.
pCi/sec for nuclide(i) 2.3.3. 4 Obtain the R. value from Table G-6(7)
.i the controlling animal, goat/cow, (whichever is for infant).
If. the limited analysis approach is being used, limit the calculation to the infant thyroid.
2.3.3.5 Solve fox DR.
3.T DR. 2 iT = R.
iT i (D/Q) Q. = mrem-m pCi-yr
-sec N
~
Z m-1 X
pCi sec DR mrem/yr the Dose Rate to organ T from nuclide(i) 2.3.3.6 Repeat steps 2.3.3.3 through 2.3.3.5 for each nuclide(i) reported in the assay of the release source.
Only the radioiodines need to be included limited analysis approach is being used.
if the ST LUCIE UNIT NO 1" ODCN
Page 29 of 2.3 (cont) 2.3.3 (cont)
,'2.3.3.7 The Instantaneous Dose Rate to the Infant's organ v from Grass- -Milk pathway is DR Grass- -Milk = DR 1
+ DR.
2
+ + DRn for all nuclides. This dose rate shall be added to the other pathways as per 2. 3.5 Total Organ dose.
NOTE: Steps 2.3.3.3 through 2.3.3.7 need to be comp'leted
~ for each organ of the Infant. Limit the calculation to the infant thyroid if the limited analysis approach is being used.
- 2. 3.4 The Instantaneous H-3 Dose Rate Method:
- 2. 3.4.1 The controlling locations and their (X7Q)D values for each pathway are:
Inhalation Infant at .range in the>
sector. (X~Q) sec/m Ground Plane Does not apply to H-3:
'Grass-Cow/Goat-Milk located in the sector at miles with an Infant at the exclusion area in the sector drinking the milk. The (X~Q)D for the 3 location is (X~Q) = sec/m 2.3.4.2 Enter the anticipated release rate in ft3 / min of the release source and convert it'to cc/sec ft3 2.8317x10 cc min min X f X cc/sec volume release rate ST LUCIE UNIT NO 1-ODCM
Page 30 of 2.3 (cont) 2.3.4 (cont) 2.3 .4.3 Solve for Q for Tritium, by obtaining the pCi/cc assay value of the release source, and multiplying it by the product of 2.3.4.2 above Q
= ~(H-3) Ci (2.3.4.2 value)cc CC sec pCi/sec activity release rate 2.3.4.4 Obtain the Tritium dose organ r from i) for Infant factor (R.)
Path Table $
r'nhalation Grass- -Milk G-6(7) 2.3.4.5 Solve for'H 3 T (Inhalation) using the (XTQ) D for inhalation from 2.3.4.1 and R (Inhalation) from 2.3.4.4 H-3 Inh =
Inh mrem/yr from H-3 Infant Instantaneous Inhalation for organ v 2.3.4.6 Solve for D 3 (Grass- -Milk) using the (X/Q)D for 9rass- -Milk from 2.3.4.1 and
-3 (Grass- -Milk) fr om 2. 3. 4 . 4
'H-3, M (VQ),
MT 3G mrem/yr from H-3 Infant 7 Instantaneous G- -Milk for organ v ST LUCIE UNIT NO 1-ODCM
Page 31 of 2;3 (cont) 2.3.4 (cont) 2.3.4.7 Repeat steps 2.3.4.4 through 2.3.4.6 for each Infant organ v of interest.
2.3.4. 8 The individual organ dose rates from H-3 shall be added to the other organ pathway dose rates as per 2.3.5.
2.3 .5 Determinin the Total Or an Dose Rate from Iodines, 8D-Particulates, and H-3 from Instantaneous Release Source(s) 2.3 .5.1 The following table describes all the pathways that must be summed to arrive at the total dose rate to an organ v:.
Pathway Dose Rate ~
Step 8 Ref Inhalation(I&8DP) 2.3.1.7 Ground Pl.(I&8DP) (T.Body only) .2.3".2. 7 Gr- -Milk(I&SDP) 2. 3'.3.7 Inhalation (H-3) 2. 3.4.5 Gr- -Milk(H-3) 2. 3.4.6 DR.
T (sum of above) 2.3.5.2 Repeat the above summation for each Infant organ x.
2.3.5.3 The DR above shall be added to all other release sources that will be in progress at any instant.
Refer to in-plant procedures and logs to determine the Total DR v to each organ.
ST LUCIE UNIT NO 1-ODCM
Page 32 of 2.4 Determinin the Gamma Air Dose for Radioactive Noble Gas Release Source(s)
Discussion - TechnicaL Specification 3.11.2.2 limits the quarterly air dose due to noble gases in gaseous effluents to less than 5 mrads for gamma radiation. The following calculation . method, is provided for determining the noble gas gamma air dose and is based on sections 5.3.1 of NUREG-0133~ Nov 1978. The dose calculation is independent of any age group. The equation may be used for STS dose calculation, the dose calculation for the annual report or for projecting dose, provided that the appropriate'alue of (X/Q) is used as outlined in the detailed explanation that fo11ows. The equation for gamma air dose is D
y-air = 3. 1'7x10 H. (X7Q) Q.
where:
D
"(-air gamma air dose in mrad from radioactive noble gases.
a mathematical symbol to signify the operations to the right side of the symbol are to be performed for each nuclide(i) through (n), and summed to arrive at the total dose, from all nuclides reported during the in-terval. No units apply.
3.17xlO
-8 = The inverse of the number of seconds per year with units of year/sec.
The gamma air dose factor for3radioactive noble gas nuclide(i) in units of mrad-m pCi-yr.
(X/Q) The long term atmospheric dispersion factor for ground level releases in units of sec/m . The value of (~X 0) is the same for. all nuclides(i) in the dose calculation, but the value of (X~Q) does vary depending on the Limiting Sector the L.C.O. is based on etc.
The number of micro-curies of nuclide(i) released (or projected) duiing the dose calculation exposure period.
(eg. month> quarter> or year)
ST LUCIE UNIT NO 1-ODCH
Page 33 of
- 2. 4 ( cont)
From an evaluation of past releases> a single effective gamma air dose factor'M eff ff) has been derived, which is representative of the radionuclide abundances and corresponding'ose contributions typical of past operation. (Refer to Appendix C for a detailed explanation and evaluation of M f'.) The value of M eff ff has been derived from the radioactive noffe gas effluents for tne years 1978> 1979> and 1980. The value is 2
M ff = 7.4 x 10 mrad/ r pCi/m This value may be used in conjunction with the total noble gas releases ( ~; Q.) to simplify the dose evaluation "and, to verify that the cumulative gamma air dose is within the limits of Specification 3.11.2.2. To allow for any unexpected variability in the radionuclide distribution> a conservatism factor of 0.8 in int'roduced into the calculation. The simplified equation is
=
i i D
o-air. 3.17 x 10 M eff X/Q 0 8 For purposes of calculations> the appropriate meteorological dispersion (X/Q) from Table M-1 should be used. Technical Specification 3.11.2.2 requires that the doses be evaluated once per 31 days, (ie, monthly). The quarterly dose limit is 5 mrads, which corresponds to a monthly allotment of 1.7 mrads. If the 1.7 mrads is substituted for D $ - air, a cumulative noble gas monthly release objective can be calculated. This value is 64,000 Ci/month> noble gases.
As long as this value is not exceeded in any month, no additional calculations are needed to verify compliance with the quarterly noble gas release limits of Specification 3.11.2. 2. Also, the gamma air dose is more limiting th'an the beta air dose. Therefore>
the beta air dose does not need to be calculated per Section 2.5" if the M ff dose factor is used to determine the gamma air dose.
Refer to eff appendix C for a detailed evaluation and explanation.
The calculations of Section 2.5 may be omitted when this limited analysis approach is used but should be performed if the radio-radio-nuclide specific dose analysis is performed. Also> the nuclide specific calculations will be performed for inclusion in s~i-annual mpo~'tX.
ST LUCIE UNIT NO 1-ODCH
Page 34 of 2.4 (cont)
The following steps provide a detailed explanation of how the radionuclide specific dose is calculated. This method is used to evaluate quarterly doses in accordance with Technical Specification 3.11.2.2 if the releases of noble gase 8 during any month of the quarter exceed 64 000 .Ci 2.4.1 To determine the applicable (X~Q) refer to Table M-1 to obtain the value for the type of dose calculation being performed. ie Quarterly L.C.O. or Dose Projection for examples. This value of (X~Q) applies to each nuclide(i).
2.4. 2 Determine (M.) thei gamma air dose factor for nuclide(i) from Table G-2.
2.4.3 Obtain the micro-Curies of nuclide(i) from the in-plant radioactive gaseous waste management logs for the sources under consideration during the time interval.
2.4.4 Solve for D. as follows:
-8 i x N.mrad-m 3 x (X/Q)sec x D. = 3.17x10 yr sec i
pCi-yr m i pCi Q.
1 i
D. = mrad = the dose fr om nuclide(i) 2.4.5 Perform steps 2.4.2 through 2.4.4 for each nuclide(i) reported during the time interval in the source.
2.4 .6 The total gamma air dose for the pathway is determined by summing the D, dose of each nuclide(i) to obtain D -air dose.
i 7 D
Y-air
. =D +D 1 2
+ -+Dn =mrad NOTE: Compliance with a 1/31 day LCO, Quarterly LCO, yearly or,12 consecutive months LCO can be demonstrated by the limited analysis approach using M . Using this method only requires that steps 2.4.2 through 2.4.5 be performed one time, remembering that the dose must be divided by 0.8, the conservatism factor.
2.4.7 Refer to in-plant procedures for comparing the calculated dose to any applicable limits that might apply.
2.5 Determinin the Beta Air Dose for Radioactive Noble Gas eleases Discussion - Technical Specification 3.11.2.2 limits the quarterly air dose due to beta radiation from noble gases in gaseous effluents to less than 10 mrads. The following calculation ST LUCXE UNIT NO 1-ODCM
Page 35 of 2.5 (cont) method is provided for determining the beta air dose and is based on Sections 5.3.1 of NUREG-0133, Nov 1978. The dose
- calculation is independent of any age group. The equation may be used. for STS dose'calculation> dose calculation for annual reports, or for~rojecting dose> provided that the appropriate value of (X/Q) is used as outlined in the detailed explanation that follows.
The equation for beta air dose is D
9-air '.17x10 N.(X/Q)Q.
i i where:
D g-air
. = beta air dose in mrad rom radioactive noble gases.
= a mathematical symbol to signify the operations to the right side of the symbol are to be performed for each nuclide(i) through (n), and summed to arrive at the total dose, from all nuclides reported during the interval.
No units apply.
-8 3.17xl0 = The inverse of the number of seconds per year with units of year/sec.
N. = The beta air dose factor for radioactive noble gas nuclide(i) in units of mrad-m3 pCi-yr (X/Q) ; The long term atmospheric dispersion factor for ground" level releases in units of sec/m The value of
. (X~Q) is the same for all nuclides(i) in the dose calculation, but the value of (X~Q) does vary depending on the Limiting Sector the LCO is based on etc.
Q. = the number of micro-Curies of nuclide(i) released (or projected) during the dose calculation exposure period.
ST LUCIH UNIT NO 1" ODCH
Page 36 of 2.5 (cont)
The beta'ir dose does not have to be evaluated if the noble gas gamma air dose is evaluated by the use of the effective gamma air dose factor (M f ). However, if the nuclide specific dose calculation is users ko evaluate compliance with the quarterly gamma air dose limits (Section 2.4)> the beta air dose should also be evaluated as outlined below for the purpose'f evaluating compliance with the quarterly beta air dose limits of Technical Specification 3.11.2.2.. The following steps provide a detailed explanation of how the dose is calculated.
- 2. 5.1 To determine the applicable (X/Q) refer to Table M-1 to obtain the value for the type of dose calculation being performed (ie Quarterly LCO or Dose Projection for examples). This value of (X~Q) applies to each nuclide(i).
2.5 .2 'etermine (N.) i the beta air dose factor for nuclide(i) from Table G-2.
2.5. 3 Obtain the micro-Curies of nuclide(i) from the in-plant radioactive gaseous waste management logs for the source under consideration during the time interval.
2.5.4 Solve for i-8 D. as follows:
3 i x 1 x ~<" I )
x i
~ .p sec pCi-yr m 1 D.
i mrad = the dose from nuclide(i)
- 2. 5.5 Perform steps 2.5.2 through 2.5.4 for each nuclide (i) reported during the time interval in the release source.
2.5.6 The total beta air dose for the pathway is determined by i
summing the D. dose of each nuclide(i) to obtain D g-air
. dose D
Bair. =D +D 1 2
+ -+Dn = mrad 2.5 .7 Refer Ref e to in-plant procedures for comparing the calculated
'dose to any 'applicable limits that might apply.
ST LUCIE UNIT NO 1-ODCM
Page 37 of 2.6 Determinin the Radioiodine and Particulate Dose To An Or an From Cumulative Releases Discussion - Technical Body Specification. 3.11.2.3 limits the dose to the total body or any organ resulting from the release of radioiodines and particulates with half-lives greater than 8 days to less than 7.5 mrem/quarter. The following calculation method is provided for determining the critical organ dose due to releases of radioiodines and particulates and is based on Section 5.3.1 of NUREG-0133 Nov 1978. The equation can be used for any age group provided that the appropriate dose factors are used and the total dose reflects only those pathways that are applicable to the age group. The (X/Q)D symbol represents a DEPLETED-(X/Q) which is different from the Noble Gas (XTQ) in that (X/Q)D takes into account the loss of I&8DP and H-3 from the plume as the semi-infinite cloud travels over a given distance. The (D~Q) dispersion factor represents the rate of fallout from the cloud that affects a square meter of ground at various distances from the site. The I&8DP and H-3 notations refer to Radioiodine and Particulates having half-lives5 8 days, and Tritium. Tritium calculations are always based on (X~Q) . The first step is to calcluate the I&8DP and H-3 dose for each pathway that applies to a given age group. The total dose to an organ can then be determined by summing the pathways that apply to the receptor in the sector.
The equations are:
For Inhalation Pathway (excluding H-3):
Yl I&8DP =
Q 3.17xlo R. (xTQ) Q For Ground Plane or Grass-Cow/Goat-gi].k DI&8DP 3. 17x R. (D~Q) Q.
C For each pathway above (excluding Ground Plane) for Tritium:
D H-3 3.17x10 R.(X7tQ)DQ.
T For Total Dose from Particulate Gaseous effluent to organ v of a specified age group:
I&8DP H-3 ST LUCIE UNIT NO 1-ODCRf
Page 38 of 2.6 (cont) where:
v = the organ of interest of a specified age group z = the applicable pathways for the age group bf interest D
@8 p Dose in 'rem to the organ T of a specif ied age group from radioiodines and 8D Particulates.
D 3
= Dose in mrem to the organ v of a specified age group from Tritium.
D Total Dose in mrem to the organ v of a specified age group T
from Gaseous Particulate Effluents.
A mathematical symbol to signify the operations to the right of the symbol are to be performed for each nuclide(i) through (n), and the individual nuclide doses are summed to arrive the total dose from the pathway of interest to ogran v'.
't
= A mathematical symbol to indicate that the total dose D to organ v is the sum of each of the pathway doses of I&8DP and H-3 from gaseous particulate effluents.
-8 3.17x10 = The inverse of the number of seconds per year with units of year/sec.
i R. = The dose factor for nuclide(i) (or H-3) for pathway+ to organ r of the specified age group. Tha unit~ are either mr em mg- mrem-m -sec yr-pti for pathways using (X/Q), or yr-gati for pathways using (D/Q)
(X~Q) D = The depleted-(X~Q) value for a specific location where the recep)or is located (see discussion). The units are sec/m (D~Q) = The deposition value for a specific location where the receptor is located (see discussion). The units are 1/m where m = meters.
The number of micro-Curies of nuclide(i) released (or projected) during the dose calculation exposure period.
Q H-3 = The number of micro-Curies of H-3 released (or projected) during the dose calculation exposure period.
ST LUCIE UNIT NO 1"ODCH
Page 39 of 2.6 (cont)
As discussed in Section 2.5> the grass-cow/goat-milk Pathway has been identified as the most limiting pathway with the infant's thyroid being the critical organ. This pathway typically contributes greater than 90% of the t'otal dose received by the infant's thyroid and the radioiodine contribute essentially all of this dose. Therefore, it is possible to demonstrate compliance with the dose limit of Technical Specification 3.11.2.3.for radioiodines and particulates by only evaluating the infant's thyroid dose due to the release of radioiodines via the grass-cow/goat-milk pathway. The calculation method of Section 2.6.3 is used for this determination. The dose determined by Section 2.6.3 should be divided by a conservatism factor of 0.8. This added conservat ism provides assurance that the dose determined by this limited analysis approach will be less than the dose that would be determined by evaluating all radionuclides and all pathways.
If this limited analysis approach is used> the dose calculations for other radioactive particulate matter and other pathways need not be performed. Only the calculations of 'Section 2.6.3 for the radioiodines are required to demonstrate compliance with the Technical Specification dose limit. However, for the dose assessment included in Sem< Annual Reports>
doses will be evaluated for all designated age groups and organs via all designated pathways from radio-and particulates measured in the gaseous effluents 'odines according to the sampling and analyses required in Technical Specification Table 4.11-2. The following steps provide a detailed explanation of how the dose is calculated for the given pathways:
2.6.1 The Inhalation Dose Pathwa Method:
NOTE: The H-3 dose should be calculated as per'2.6.4.
2.6.1.1 Determine the applicable (X/Q)D from Table M-2 for the location where the receptor is located.
This value is common to each nuclide( i).
ST LUCIE UNIT NO 1-ODCM
Page40 of 2.6 (cont) 2.6.1 (cont) 2.6.1.2 Determine the R. factor of nuclide(i) i for the organ v and age group from Table G-3.
2.6.1.3 Obtain the micro-Curies (Q-') of nuclide (i) from the radioactive gas waste management clogs for C
the release source(s) under consideration during the time interval.
2.6.1.4 Solve for D.
D. ~ 3.17xl0 Ri(X/Q)DQ'.
mrem from nuclide(i) 2.6.1.5 Perform steps 2. 6.1.2 through 2. .1.4 for each nuclide(i) reported during the time interval for each organ.
2.6.1.6 The Inhalation dose to organ v of the specified age group is determined by summing the D. Dose of each nuclide(i)
D Inhalation D + D + + D mrem (Age Group) 1 2 n Refer to 2. 6.5 to determine the total dose to organ v from radioiodines & SD Particulates.
2.6.2 The Ground Plane Dose Pathwa Method:
NOTE: Tritium dose via the ground plane is zero. The Total Body is the only organ considered for the Ground Plane pathway dose.
2.6.2.1 Determine the applicable (DTQ) from Table M-2 for the location where the receptor is located.
This (D/Q) value is common to each nuclide(i).
2.6.2.2 Determine the Ri factor of nuclide(i) for the total body from Table G-4. The ground plane pathway dose is the same for all age groups.
2-6 '.3 Obtain the micro-Curies (Q.) of nuclide(i) from the radioactive gas waste management logs for the source under consideration.
ST LUCIE UNIT NO 1-ODCM
Page 41of
- 2. 6 (cont)
- 2. 6. 2 (cont)
- 2. 6.2.4 Solve for i D.
D. = 3.17x10 R (D~Q)Q.
D.
i mrem for nuclide(i)
- 2. 6.2.5 Perform steps 2. 6.2.2 through 2. 6.2.4 for each nuclide(i) reported during the time interval.
2.6.2.6 The Ground Plane dose to the total body is determined by summing the Di dose of each nuclide(i) mrem Gr.Pl.-TBody 1 2 Refer to step 2.6.5 to calculate total organ dose.
2.6.3 The Grass-Cow/Goat-Milk Dose Pathwa Method:
NOTE: Tritium does is calculated as per 2. 6.4
- 2. 6.3.1 A cow, or a goat, will be the controlling animal; ie. dose will not be the sum of each animal, as the human receptor is assumed to drink milk from only the most restrictive animal. Refer to Table M-3 to determine which animal is controlling based on its (D~Q).
- 2. 6.3.2 Determine the dose factor R.
l for nuclide(i), for organ v, from
- 2. 6. 3. 2. 1 Prom Table G-5 for a cow, or;
- 2. 6.3.2.2 Prom Table G-6 for a goat.
If the limited analysis approach is being used, limit the calculation to the infant thyroid.
- 2. 6.3.3 Obtain the micro-Curies (Q.) of nuclide(i) from the radioactive gas waste management logs for C
the release source under consideration during the time interval.
ST LUCIE UNIT NO 1-ODCM
Page42 of 2.6 (cont) 2.6.3 (cont)
- 2. 6. 3. 4 Solve for D."
D. = 3.17xlO R.(D~Q)Q.
mrem from nuclide(i) 2.6.3.5 Perform steps 2.6.3.2 through 2.6.3.4 for each nuclide(i) reported during the time interval.
Only the radioiodines need to be included if the limited analysis approach is used.
- 2. 6.3. 6'he I
Grass-Cow-Milk (or Grass-Goat-Milk) pathway dose to organ v is determined by summing the Di dose of each nuclide(i).
G-C-M( G-G-M)
+ D2 + + mrem 1
The dose to each organ should'be calculated in the same manner with steps 2.6.3.2 through 2.6.3.6.
Refer to step 2.6.5 to determine the total dose to organ v from radioiodinesg 8D Particulates.
If the limited analysis approach is being used the infant thyroid dose via the grass-cow(goat)-
milk pathway is the only dose that needs to be
'determined. Section 2.6.5 can be omitted.
2.6.4 The Gaseous Tritium Dose (Each Pathwa ) Method:
2.6,4.1 The controlling locations for the pathway(s) has already been determined by:
Inhalation as 'per 2; 6.1.1 Ground Plane not applicable for H-3 Grass-Cow/Goat-Milk as per 2.6.3.1 2.6.4.2 Tritium dose calculations use the depleted (VQ)D instead (D~Q). Table M-2 describes where the (Xg) value should be obtained from.
2.6.4.3 Determine the Pathway Tritium dose factor (R 3
for the organ v of interest from the Table specified below.
MILK AGE INHALATION CON GOAT Infant G-6 ST LUCIE UNIT NO 1-ODCM
Page 43 of 2.6 (cont) 2.6.4 (cont)
- 2. 6.4.4 Obtain the micro-Curies (Q) of Tritium from the radioactive gas waste management logs (for pro-jected doses - the micro-Curies'f nuclide('i) to be projected) for'he release souice(s) under consideration during. the time interval. The dose can be calculated from a single release, source, but the total dose for S.T.S. limits or quarterly reports shall be from all gaseous release sources.
2.6.4.5 Solve for DH 3 D = 3.17x10 R 3(X/Q) Q 3
H-3 mrem from Tritium in the specified pathway for ogran v of the specified age group.
2.6.5 Determinin the Total Or an Dose from Iodines 8D-Particulates, and H-3 from Cumulative Gaseous Releases NOTE: STS LCO dose limits for Ig8DP shall consider dose from all release sources from St. Lucie Unit l.
- 2. 6.5.1 The following pathways shall be summed to arrive at the total dose to organ v from a release source, or if applicable to STS, from all release sources:
PATEJAY DOSE(mrem) Step 8'ef.
Inhalation (Ig8DP) 2. 6.1.6 Ground Plane- (Ig8DP) (T.Body only) 2. 6.2.6 Grass- -Milk (Ig8DP) 2. 6.3.7 Inhalation (H-3) 2. 6.4.5 Grass- -Milk(H-3) 2. 6.4.5 Dose T
Sum of above ST LUCIE UNIT NO 1" ODCM
Page 44 of 2.6 (cont) 2.6.5 (cont) 2.6.5.2 The dose to each of the INFANT's ORGANS shall be calculated:
BONE, LIVER, THYROID, KIDNEY, LUNG, TOTAL BODY g'I-LLI The INFANT organ receiving the highest 'exposure to its STS Limit is the most critical "'elative organ for the radioiodine g 8D Particulates gaseous effluents.
2.7 Pro'ectin Dose for Radioactive Gaseous Effluents Discussion - Technical Specification 3.11.2.4 requires that the gaseous radwaste treatment system be used to reduce radioactive materials in waste prior to discharge when the projected dose due to gaseous effluents would exceed 0.4 mrad for gamma radiation and 0.8 mrad for beta radiation. The following calculation.-
method is provided for determining the projected doses. This method is based on using the results of the calculations performed in Sections 2.4 and 2.5.
2.7.1 Obtain the latest results of the monthly calculations
.of the gamma air dose (Section 2.4) and the beta air dose if performed (Section 2.5). These doses can be obtained for the in-plant logs.
2.7. 2 Divide these doses by the number of days the plant was operational during the month.
- 2. 7.3 Multiply the quotient by the number of days the plant is projected to be operational during the next month.
The product is the projected dose for the next month.
The. value should be adjusted as needed to account for any changes in failed-fuel or other identifiable operating conditions that could significantly alter the actual releases.
2.7.4 If the projected dose are greater than 0.4 mrads gamma air dose or (0.8 mrads beta air dose), the appropriate subsystems of the gaseous radwaste system shall be used to reduce the radioactivity levels prior to release.
ST LUCIE UNIT ';kl-ODC~ai
Page 45 of 3.0 40 CFR 190 Dose Evaluation Dxscussion Dose or dose commitment to a real individual from all uranium fuel cycle sources be limited to A 25 mrem to the total body or any organ (except thyroid> which is limited to C 75 mrem) over a period of 12 consecutive months. The following approach be used to demonstrate compliance with these dose limits. 'hould This approach is based on NUREG-0133> Section 3.8.
3.0. 1 Evaluation Bases Dose evaluations to demonstrate compliance with the above
'dose limits need only be performed if the quarterly doses calculated in Sections 1.4, 2.4 and 2.6 exceed twice the dose limits of Technical Specifications 3.11.1.2.a, 3.11.2.2a, and 3.11.2.3a, respectively> ie> quarterly doses exceeding 3 mrem'to the total body (liquid releases)>
10 mrem to any organ (liquid releases), 10 mrads gamma air dose, 20 mrads beta air dose, or 1.5 mrem to the thyroid or any organ from radioiodines and particulates (atmospheric releases). Otherwise, no evaluations are required and the remainder of this section can be omitted.
3.0. 2 Doses From Li uid Releases For the evaluation of doses to real individuals from liquid releases> the same calculation. method as employed in Section 1.4 will be used. However> more realistic assumptions will be made concerning the dilution and ingestion of fish arid shellfish by individuals who live and fish in the area.
Also, the results of the Radiological Environmental Monitoring program will be included in determining more realistic dose to these real people by providing data on actual measured levels of plant related radionuclides in the environment.
3.0.3 Doses From Atmos heric Releases For the evaluation of doses to real individuals from the atmospheric releases> the same calculation methods as employed in Section 2.4 and 2.6- will be used. In Section 2.4, the total body dose factor {K.) should be substituted for the gamma air dose factor (M .) to determine the total i
body dose. Otherwise the same calculation sequence applies. However> more realistic assumptions will be made concerning the actual location of real individuals> the meteorological conditions, and the consumption of food (eg, milk). Data obtained from the latest land use census
{Technical Specif ication 3. 12. 2) should be used to determine locations for evaluating doses. Also> the results of the Radiological Environmental Monitoring program will be included in determining more realistic doses to these real people by providing data on actual measured levels of radioactivity and r'adiation at locations of interest.
ST. LUCIE UNIT fP1-ODCM
Page 46 of
$. 0 SEMIANNUAL RADIOACTIVE EFFLUENT REPORT Discussion The information contained-in a semiannual report shall not apply to any STS LCO. The reported values are based on real release=- conditions instead of historical conditions that the STS LCO dose calculations are based on. The STS LCO dose limits are therefore included in item 1, of the report, for information only. The MPC's in item 2, of the report, shall be those listed in Tables L-1 and G-1 of this manual. The average energy in item 3, of the report, is not applicable to the St. Lucie Plant. An unplanned release is defined as an abnormal release in Reg Guide 1.21 Rev. 1 which is I
an unplanned or uncontrolled release of radioactive material from the site boundary.i The format, order of nuclides, and any values shown as an example in Tables 3.3 through 3.8, are samples only. Other formats are acceptable if they contain equivalent information. A table of contents should also accompany the report. The following format should be used:
RADIOACTIVE EFFLUENTS SUPPLEMENTAL INFORMATION
- 1. Regulatory Limits:
1.1 For Radioactive liquid waste effluents:
a) The once diluted concentration of radioactive material released from the site to unrestricted areas (see Figure 3.11-1 in STS-A) shall be limited to the concentrations specified in 10CFR20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases The once diluted concentration for total dissolved or entrained noble gases shall be limited to 2 x 10 "p.Ci/mk.
b) The dose or dose commitment to an individual from radio- .
active materials in liquid effluents released to unrestricted areas (see Figure 3.11-1 in STS-A) shall be limited during any calendar quarter to < 1.5 mrem to the total body and to < 5 mrem to any organ.
1.2 For. Radioactive Gaseous Waste Effluents:
a) The instantaneous dose rate in unrestricted areas (see Figure 3.11-1 in the STS-A) due to radioactive materials released in gaseous effluents from the site shall be limited to the following values:
The dose rate limit for noble gases shall be < 500 mrem/yr to the total body and < 3000 mrem/yr to the skin, and The dose rate limit for the INHALATION pathway from I-151, Tritium, and with half-lives greater than 8 days particulates shall be less than 1500 mrem/yr to any organ.
Page 47
-OX'ADIOACTIVE EFFLUENTS SUPPLEMENTAL INF019iATION (cont)
- 1. Regulatory Limits: (cont) 1.2 For Radioactive Gaseous Waste Effluents: (cont) b) The dose in unrestricted areas (see Figure 3.11-1 in the STS-A) due to noble gases released in gaseous effluents shall be limited to the following:
During any calendar quarter, to < 5 mrad for gamma radiation and < 10 mrad for beta radiation; c) The dose to an individual from radioiodines, radioactive materials in particulate form, and radionuclides other than noble gases with half-lives greater than.8 days in gaseous effluents released to unrestricted areas (see Figure 3.11-1 in the STS-A) shall be limited to the following:
During any calendar quarter to < 7.5 mrem to
- 2. Maximum Permissible Concentrations.
Air as per attached Table G -l.
Water as per attached Table L-l.
- 3. Average energy of fission and activation gases in gaseous effluents is not applicable to the St. Lucie Plant.
- 4. Measurements and Approximations of Total Radioactivity.
A summary of liquid effluent accounting methods is described in Table 3.1.
A summary of ga'seous effluent accounting methods is described in Table 3.2.
Page 48 of RADIOACTIVE EFFLUENTS SUPPLEMENTAL INFOI&fATION (cont)
- 4. Measurements and Approximations of Total Radioactivity (c5nt)
Estimate of Errors (a) Sampling Error The error associated with volume measurement devices, flow measuring devices, etc. based on calibration data and design tolerances has been conservatively estimated collectively to be less than +
(b) Analytical Error for Nuclides
~Avere e % Maximum %
Liquid Gaseous
'able 3.1
, Radioactive Liquid Effluent Sampling and Analysis E OD F SA'KIPLING FRE UENCY TYPE OF ANALYSIS NONITOR EACH BATCH PRINCIPAL GAiftM CRITTERS p.h.a.'.S.
TAhY Tritium MONTHLY COMPOSITE Gross Al ha RELEASES G.F.P.
UARTERLY COMPOSITE Sr-89 Sr-90 C.S.& L.S ~
STEAM WEEKLY Principal Gamma Emitters GENERATOR and Dissolved Gases p.h.a.
'LOWDOWN "
MONTHLY COMPOSITE Tritium L.S.
RELEASES QUARTERLY COMPOSITE .Sr-89, Sr-90 C.S.&L.S.
TABLE NOTATION:
Boric Acid Evaporator condensate is normally recovered to the Primary Water Storage Tank for recycling into the reactor coolant system and does not con-tribute to liquid waste effluent totals.
p.h.a. gamma spectrum pulse height analysis using Lithium Germanium detectors. All peaks are identified and quantified.
L.S. Liquid Scintillation counting C. S. Chemical Separation G.F.P. Gas 'Flow Proportional Counting ST. LUCIE UNIT 81 ODCM
Page 49 of RADIOACTIVE EFFLUENTS SUPPLEMENTAL INFOEfATION (cont)
- 4. Measurements and Approximations of Total Radioactivity (cont)
(b) Analytical Error for Nuclides (cont)
Table 3.2 Radioact ive Gaseous Waste Sam lin and Anal sis Gaseous Sampling Type of Method of Source Fre uenc Anal sis Anal sis Waste Gas Decay Princi al Gamma Emitters (G C P) .h.a.
Tank Each Tank Releases H-3 L.S.
Contain-ment Princi al Gamma Emitters G C P .h.a.
Purge Each Purge Releases H-3 L.S.
Plant Weekly Princi al Gamma Emitters G C P) .h a.
Vent H-3 L.S.
Monthly Composite Gross Alpha P G.F.P.
(Particulates)
Quarterly Sr-90, 89 C.S. 6 L.S.
Composite (Particulates)
G Gaseous Grab Sample C Charcoal Filter Sample P Particulate Filter Sample L.S. Liquid Scintillation Counting C.S. Chemical Separation p.h.a. Gamma spectrum pulse height analysis using Lithium Germanium detectors. All peaks are identified and quantified.
G.F.P. Gas Flow Proportional Counting ST. LUCIE UNIT //1 ODCM
Page 50 of RADIOACTIVE EFFLUENTS - SUPPLVKNTAL INFORMATION (cont)
- 5. Batch Releases A. Liquid
- 1. Number of batch releases:
2~ Total time period of batch releases: Minutes 3~ Maximum time period for a batch release: Minutes
- 4. Average time period for a batch release: Minutes
- 5. Minimum time period for a batch release: Minutes
- 6. Average stream flow during periods of release of effluent into a flowing stream: GPM All liquid releases are summarized in tables B. Gaseous
- l. Number of batch releases:
- 2. Total time period for batch releases: Minutes
- 3. Maximum time period'or a batch release: Minutes
- 4. Average time period for batch releases: Minutes
- 5. Minimum time period for a batch release: Minutes All gaseous waste releases are summarized in tables
- 6. Unplanned Releases A. Liquid.
- 1. Number of releases:
- 2. Total activity releases: Curies B. Gaseous
- 1. Number of releases:
- 2. Total activity released: Curies I
C. See attachments (if applicable) for:
- l. A description of the event and equipment involved.
- 2. 'ause(s) for the unplanned'elease.
- 3. Actions taken to prevent a recurrence.
- 4. Consequences of the unplanned release.
- 7. Description of dose assessment of radiation dose from radioactive effluents to the general public due to their a'ctivities inside the unrestricted area (see figure 3.11-1 in STS-A) during the report-ing period:
PaS'e 51 of FLORIDA POllER 4 LIGHT COHPRtlY ST. LUCIE UNIT tti SENIAtlNUAL REPORT JULY ii 1978 THROUGH DECEt1BER 31> 1978 TABLE 3.3: LIQUID EFFLUEHT5 SUt'tNRTION OF RLL RELEASES
'HIT mtRRTERtt QURRTERtt R. FI55IOH FIND RCTIVRTION PRODUCTS TOTAL RELEASE-NOT ItlCLUDItlG TRITIUt'ti GASESr ALPHFI) CI 2. 379 E -1 9. 819 E -1
- 2. AVERRGE DILUTED CONCEN-TRATION DURING PERIOD UCIr't'tL 1. 9S3 E -8 7. 439 E -S B. TRIT IUt't TOTRL RELERSE CI 2.G29 E 1 4.509 E i.
- 2. RVERRGE DILUTED CONCEN-TRATION DURING PERIOD UCIr'thL 1. 691 E -6 3. 416 E -6
. C. DISSOLVED RND ENTRRItlED GASES TOTAL RELERSE CI 7. 379 E -1 2. 919 E -1 2.. AVERAGE DILUTED CONCEtl-TRRTIOtl DURING PERIOD UCIPHL 6. 15G E -8 2. 212 E -S D. GR055 RLPHR RRDIORCTIVITY TOTAL .RELEASE CI .GGG E 0 E. VOLUt1E OF WASTE RELERSED CPRIOR TO DILUTIOW) LITERS 1. 189 E 6 1. 559 E 6 VOLUtCE OF DILUTION llRTEP. USED DURING PERIOD L'ITERS 1. 199 E iG 1. 319 E 1G ST. LUCIE UNIT Irl ODCM
Page 52 FLORIDA F'OWER 6 LIGHT COt'1PANY
.ST. LUCIE UNIT tti SEttIRWHURL REPORT JULY ii 1978 THROUGH DECEt'1BER 31 J 19 7S TRBLE 3.4.: LIQUID EFFLUEtfTS COtlTIHUOUS t'lODE BFITCH tiODE tlUCLIDES RELEASED UNIT QURRTERtt QU RRTEP.N QURRTERtt QUAPTE I-131 CI . 609 E 8 .Gee E 6 1. 559 E i. 769 E I-133 CI . 888 E 8 .888 E 8 8. 886 E 7. 428 E -3 I-135 CI . 898 E 8 888 E 4. 178 E 5. 669 E HFI- 24 CI . 660 E 8 8 1. 639 E 3. 968 E -5 CR- 51 CI . 888 E 8 .808 E 7. 728 E -3 6. 379 E -2 tlH- 54 CI . 808 E .889 E 9. 479 E -3 i. 628 E -2 CO- 57 CI . 888 E .068 E 4. 278 E 7 ->9 E 4 CO- 58 CI . 898 E . 888 E 7. 539 E ?'v9 E FE- 59 CI . 688 E . 980 2. 219 E -3 4. 279 E -3 CO- 68 CI . 880 E 8 . 898 E 6. 199 -2 1. 269 E ZH- 65 CI . 698 E 8 . 666 260 E'.
F -4 1. 339 E -3 WI- 65 CI . 868 E .808 E 4. 118 E 1. 818 E RG-iiot1 CI . 680 E .888 E 8 9. 999 E 4 5. 978 E -4 5W-113 CI . 889 E . 898 E G. 9. 838 E 1. 788 E 58-122 CI 699 E ~99 E 3. 889 E -4 4. 439 E SB-124 CI
. 896 E
. 868 E O
8 5. 429 E 4 3. 319 E -r W-187 CI .609 E '8 . 898 E 0 1. 238 E -3 7. 868 E NP-239 CI . 890 E 7. 699 E -5 3. 578 E -4 ZR- 95 CI . eerie E . 009 E 9 4. 839 E 2 n Ori9 t10- 99 CI . 888 E 0 . 889 E 8 2. 689 E -5 84+ E -2 RU-193 CI 886 E . 888 E 8 .869 E 8 1. 436 E CS-134 CI . 866 E . 860 E 9 4. 599 E -3 5. 228 E -2 CS-136 CI . 898 E . 968 E 8 3. G49 E -4 3. 668 E p CS-137 CI . 898 E . 806 E 8 9. 149 E -3 8. ?89 E -2 BFI-148 CI . 888 E : 898 E 8 4. 619 E 5 i. 368 E CE-141 CI . 980 E . 689 E 6 2. 599 E -5 1. 869 E BR- 82 CI . 690 E . 898 E 6 . 698 E 8 5. 980 E 4 ZR- 97 CI .898 E . 909 E 6 1. 578 E -3 9. 849 E -3 58-125 CI . 688 E 9 9. 289 E 4. r78 E -3 CE-144 CI . 898 E 0 . 868'E. 6 1. 6S9 E 6. 219 E 3 5R- S9 CI . 989 E 6 . 860 E 6 SR- 98 CI 0 .698 E 6 6. 599 E -8 UW IDEtlTIFI ED CI . 096 E 8 .689 E 8 . 808 E Q . 880 TOTAL FOR PEP IOD (ABOVE) CI ~ 880 6 . 898 0 2. 375 9.
RR- 41 CI . QQG E 0 . 908 0 1. 398 -4 1. 3SG E VR- 85 CI . GQO E 9 . 609 8 6. 689 -4 1. 719 E -3 FACE-131t't CI . GOQ E Q . 890 0 C'7C'8 -5 1r 9 E CI . 009 E 0 . Geo 0 7. 349 -1 2 759 E -1 i<E-133t1 CI . 960 E 0 , 800 9 2. 450 6. 6r9 E -4
~E-135 CI . 800 E 0 . 960 8 6. 860 -5 4. 689 E -4 ST. LUCIE UNIT 81 ODCi1
Page 53 of FLORIDA POWER & LIGHT COMPANY St. Lucie Unit f31 Table 3.5 Li uid Effluents Dose Summation Age Group: Adult Location: Any Adult Exposure Interval: From through uarter fr'arter 8 Fish & Shellfish DOSE DOSE Pathway to ORGAN mrem mrem BONE LIVER THYROID KIDNEY LUNG GI-LLI T. BODY ST. LUCIE UNIT '/1 ODCM
Page 54 of FLORIDA POWER P LIGHT COt'tPANY ST. LUCIE UttITtt1, SENIANNUAL PEPORT JULY 1w 1978 THROUGH DECEt'tBER '1@ 1978 TABLE 3 ~ 6: GFISEOUS EFFLUEttT5 - SUttt'tATIOt< OF FlLL RELEA5E5 UN IT QUARTERtt QUARTERtt A. FISSION AND ACTIVATIOtt GASES TOTAL PELEASE CI 7.877 E 3 9.759 E 3
- 2. AVERAGE PELEA5E RATE FOR PERIOD UCI)SEC 8. 976 E 2 1. 238 E 3 B IODIt<ES
- 1. TOTAL IOD DIE-131 CI 1. 976 E -2 4. 668 E -2 C
- 2. AVERAGE RELEASE RATE FOR PERIOD UCIr'SEC 2. 587 E -3 5. 9"..1 E -3 C. PARTICULATES
- 1. PFlRTICULATE5 T-1/2 > 8 DAYS CI 1 976 E -'2 4. 661 E -2
- 2. AVERAGE RELLASE RATE FOR PEl?KOD UCIr'SEC 2. 587 E -3 5. 911 E -3 GR055 ALPHA RADIOACTIVITIY CI .688 E 8 .888 E 6 D. TR IT IUt'1
- 1. TOTAL RELEA=E CI 1..261 E 2 2. 526 E 2
- 2. AVERAGE RELEASE RATE FOR PERIOD UCIrSEC 1 688 E 1 3. 203 E ST. LUCIE UNIT I/1 ODC:"I
4 Page 55 of'LORIDA PONER 8 LIGHT COMPANY ST. LUCIE UttIT ¹1 SEt'1 IRt tNURL REPORT 'ULY iz 1978 THROUGH DECEt'1BER 31'978 TABLE 3.7: GRSEOU5 EFFLUEt(TS
'ONTINUOUS tIODE BATCH tIODE ttUCLIDES RELEASED UNIT QUARTER¹ QUARTER¹ QUFIRTER¹ QURRTER¹ FISSIOtt GASES AR- 41 CI . GGG E 8 .GGG E 0 3. 429 E 0 ~
- 3. 179 E 8 t&- 85 CI . 888 E 8 .GGG E 8 1. 939 E 1 2. 899 E 1 t(R- SSN CI . GGG E 8 1.419 E 8 3. 459 E 2 9. 819 E KR- 87 CI .088 E 8 .OGG E 8 7. 479 E 1 3. 899 E KR- 88 CI . 888 E 8 2.739 E 8 4. 139 E 2 369 E 2 XE-131t'1 CI .888 E .0 .GGG E '8 4. 889 E 1 '3. 559 E 2 XE-133 CI 7.899 E 2 4.189 E 3 5. 839 E 3 4. 699 E 3 XE-133 t't CI 3.569 E 8 4.399 E 1 2. 849 E 1 3. 789 E
-135 CI 3.669 E 1 1.G89 E 2 1. 849 E 2 4. 939 E XE-135t'1 CI .GGO E 0 .888 E 8 2. 439 E 1 2. 119 E 8 XE-138 CI .GGO E 8 .888 E 8 1. 459 E 2 5. 179 E UNIDENTIFIED CI . GGG E 8 .GGG E 8 . 880 E 8 888 E 8 TOTAL FOR PERIOD CRBOVE) CI 8.382 E 2 4.267 E 3 6.249 E 3 5.494 E 3
- 2. IODIt(ES I-131 CI i. 229 E -2=- 2. 849 E -2 7. 468 E -3 2. 689 E -2 I-133 CI 4. 379 E -1 2. 279 E -1 -
- 4. 578 E -6 8. 438 E -5 I-135 CI . 880 E 8 . Goo E 8 . GGG E 8 1. 128 E -S TOTAL FOR
'ERIOD <ABOVE> CI 4. S82 E -1 2. 484 E -1 ?. 464 E -3 2. 619 E -2
- 3. PARTICULATES Sn CI .GGO E 0 3.489 E -6 .008 E 8 .800 E 0 5R- 89 CI 4. -80 E -6 . OOG E 8 . OGG E O . OOG E 8 5R- 90 CI 8. 228 E '-6 : 008 E 8 . GGG E 0 . 888 E '8 I
0 ST ~ LUCIE UNIT Nl ODCH
FLORIDA POWER & LIGHT C011PANY St. Lucie Unit 81 Table 3.8 Gaseous Effluents Dose Summation Quarter//
Age Group: Infant Exposure Interval: From through Pathway BONE LIUER THYROID KIDNEY LUNG GI-LII T. BODY mrem) mrem (mrem) mrem mrem) (mrem) mrem)
Ground Plane Grass- -Milk Inhalation Total Sector: Range: miles Cow/Goat Sector: Range: mile Noble Gases Quarter Calendar Year (Above time interval) (mrad) mrad Gamma Air Dose Beta Air Dose Sector: Ran e: 0.97 miles 1 The dose values below were. calculated using real meteorological data during the specified time interval with met data reduced as per Reg. Guide 1.111, March 1976.
APPENDIX A MPC, DOSE FACTOR, HISTORICAL METEOROLOGICAL TABL ES ST. LUCIE UNIT i'll ODCH
Page 57 of TABLE L-1 Maximum Permissible Concentrations in Water in Unrestricted Areas uclide 1
MPC (pCi/ml) Nuclide i MPC(uCi/ml) Nuclide l MP C (uCi/ml)
H-3 3 E-3 Y-90 2 E-5 Te-129 8 E-4 Na-24 3 E-5 Y-91m 3 E-3 Te-133JI1 4 E-5 P-32 2 E-5 Y-91 3 E-5 Te-131 None Cr-51 2 E-3 Y-92 6 E-5 Te-132 2 E-5 Mn-54 1 E-4 Y-93 3 E-5 I-130 3 E-6 M -56 1 E-4 Zr-'95 6 E-5 I-131 3 E-7 Fe-55 8 E-4 Zr-97 2 E-5 I-132 8 E-6 Fe-59 5 E-5 Nb-95 1 E-4 I-133 1 E-6 Co-57 4 E-4 Nb-97 9 E-4 I-134 2 E-5 Co-58 9 E-5, Mo-99 '4 E-5 I'-135 4 E-6 Co-60 3 E-5 TC-99m '3 E-3 Cs-134 9 E-6 Ni-65 1 E-4 Tc-101 None Cs-136 6 E-5 Cu-64 2 E-4 Ru-103 8 E-5 Cs-137 2 E-5
'Zn-65 1 E-4 RQ-105 1 E-4 Cs-138 None Zn-69 2 E-3 Ru-106 1 E-5 Ba-139 None Br-82 4 E-5 Ag-110m 3 E-5 Ba-140 2 E-5 Br-83 3 E-6 Sn-113 8 E-5 Ba-141 None Br-84 None2 In-113m 1 E-3 Ba-142 None
' I Br-85 None Sb-122 3 E-5 La-140 2 E-5 QRb-86 2 E-5 Sb-124 2 E-5 La-142 None None 'b-125 1 E-4 Ce-141 9 E-5 None Te-125M 1 E-4 Ce-143 4 E-5 Sr-89 3 E-6 Te-127m 5 E-5 Ce-144 1 E-5 Sr-90 3 E-7 Te-127 2 E-4 Pr-144 None Sr-91 5 E-5 Te-129m 2 E-5 W-187 6 E-5 Sr-92 '6 E-5 Np-239 1 E-4 (1) If a nuclide is not listed, refer to 10 CFR 20, Appendix B, and use the most conservative insoluble/soluble MPC where they are given in Table II, Column 2.
(2) None-(As per 10 CFR 20, Appendix B) No MPC limit for any single radionuclide not listed above with decay mode other than apha emission or spontaneous fission and with radioactive half'-life less than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
TABLE -2 ENVIPON .ENTAL FATHt(AY-OOSE CONY RSiON FACTORS FOR LiOVIO OISCHARGES PA HHAY " SALT MATER FISH A'30 SHELLFiSH AGE GROUP - ACVLT t JCLiOE ORGAN 0 OS i FACTOR t HREH/H?. P R UCI/HL )
GGNE L~VEP (HY'.CIO KiattCY LUNG Gi LLI SKIN TO)AL BODY G 3~ 605-01 3r60E-01 3 ~ 59E 01 3r 60E-01 3 69 i-01 0 ~ 3 '0c 01 NA 24 SrQOE-Ci 6 ~ 08E-01 6-oai-01 Sroai-Ci S.Oei-ai 6 'SE-01 C ~ 6~ 53i-91 F i. S724G7 ).r 05=+GS 0 ~ 0 ~ 0 ~
'2c499 irSSE+06 ir41E403 9 ~ 6 ATE+95 c9"+09 CR"-51 9 ~ 9 ~ 3 '4E+GO 1. 23-+09 7 0 ~ cd 0~ 7 ~ 076493. Qr 2riOE+03 9 ~ 2 17i+04 0 ~ ir35i+C3 5c \' 1 ~ 786402 6 ~ 2 ~ ZSE+92 3 ~ 5rSOc+03 0 ~ 3 ~ 17F491 I
~ ~
r c+av 5 195+05 9 ~ 0 ~ S.O1 +05 2.03E+05 0 ~ 1 '6i465 nc 8 082404 1 ~ 92c+05 Gr 0 ~ 5 '2E404 6r 33E 405 0 ~ T ~ 29ic404 CJ--~7 lj r 1 r 426+ 02 0 ~ 0 ~ 3 ~ 3 SC" +03 0 2 '6E+OZ C"--58 Gr 6 ~ ') 5E462 0 ~ 0 ~ Q~ ir22i+04 0 ~ 1 ~ 35c 403 C"--"'0 G 1 ~ 74i+03 0 ~ Or 9 ~ 3 '56404 (3 r 3 '3E>03 t::--65 Zruii402 2r53i+Gl 0 ~ 0 ~ 0 ~ 6 ~ 65E4O2 0 ~ 1~ ZCEr 01 C J"-54 C ~ 2~ lr J ~ 5 41c+GZ 0 ~ 1~ 83c+u4 0 ~ ir Qli+02
- 1. SZE+95 5r 136+ G5 0 ~ .3.43E+65 Or 3 23c4G5 0 ~ 2. 32C+05 TN --59 3. 43E+92 S.EQE402 9 ~ 4 27E462 0 ~ 9rSTE+01 0 ~ 4 ~ 57i 401
)) n 0 ~ 4 ~ ~SE 400 0 ~ 4 ~ GSE > 00 9~ G ~ C ~
13 I u ~ h ~ J ur 0 ~ lr05c-Gi or Tr 266-02 r . Qr 9 ~ 0 ~ 0r 9 ~ 7 ~ 38 E-OT 0 ~ 9. 426-02
)) 5 Q~ 6 ~ 0 ~ 0 ~ or 0 ~ 3r Soc-03 t 8--86 Q~ 255402 0 ~ Qr 0 ~ ir23E+GZ 0 ~ 2r 91i 492 FO--83 Qr ]rT c+uo 6 ~ 0 ~ 0 ~ 0 ~ 0 ~ 9. 506-01 Q3 C. 1 ~ 19E409 0 ~ 0 ~ 0 0 ~ 0 ~ 8 38E-Gl
~
S Sa 5 01E403 0 ~ Qr 0 ~ 0 ~ 8 ~ Qii+02 Or 1.445+a2 1 ~ 23iro5 9 ~ 0 ~ 0 ~ 0 ~ 1 ~ 65ic403 0 ~ 3 '26404 ck--9'> c ~ ))3E+31 V~ Or 0 ~ 0 ~ 4 '5=402 0 ~ 4 ~ 15 400 556461 9 ~ 0 ~ G 0 ~ 6.91E402 0 ~ 1. 51=4ao Y---aa ST 07c+09 9 ~ 0 ~ Qr 0 ~ 6 '3i+04 0 ~ 1~ 63i-al 9 ~,r 5.74c"CZ 0 ~ C ~ 0 ~ Qr 1 Soc-Jl 0 ~ 2 '36-03 Y---al S. 89E+0' 0 Or 0 ~ 0~ 4 '96494 0 ~ Zr 33E+GG Y- ~ 34i-al Cr 0 ~ 0 ~ 0 ~ 9 ~ 33E+ 93 0 ~ ir 56E-QZ 03 S~ +90 Or Q ~ 0 ~ 0~ 5r 3SE 494 Q ~ 4. 676-02 i-;--95 ' 63=<51 5 13i+ 00 Or 8 '9E+60 9r 1 ~ 59E+94 0 ~ 3 '7i490 7%"-a7 8 ~ 8Z="91 irTSE-01 0~ Z. 696-01 0 ~ 5 51c 404 0 ~ 8 '9E-QZ t"') --9c 4~4 i i 4C2 2 '9=4i02 0 ~ ~ ) ic+02 Or lr 51c4G6 Or 9 '9c(01 tt~--oT 3r7Eiroa 9rvoc-01 9 ~ 1~ 11=+GO Or 3 ~ 51i 4u3 Or 3 '7=-01 H'--a9 ur 1.286+62 2.90c+62 2 ~ 97i+02 0 ~ 2 '3E+01 TC-a 3tt 1 ~ 39E-02 3 '7 "G2 0 ~
0 ~ 5 '7i-01 Q ~
1.80E-DZ Zr17">01 0 ~ 4 ~ 67i-01 aAS=O ON 1 VCI/SEC RELEASE RATE OF EACH ISOTOPE it( OiSCHARGE FLOW OF 1 CC/SEC H?TH NO ADCITIGNAL DILVTICN
TABLE L-2 (con')
EHVIRONHcttTAL PATHMAY-OOSc CONV RSION FACTORS FOR LIOUIO OISCHARGiS
~
PATHMAY - SALT MATER FISH AHO SHcLLFISH AG E GROUP - A CULT t<UCLIOi 0 R G A H 0 0 S FACTOP. .(HREH/HR PER UCX/HL) 80t;i LIVEP. THYRGI KXOt'iY LUttG GI- LLI SKIN TOTAL QOOY I
TC 32-92 1-93i-02 0 ~ 3.4TE-O} 9~ 82E" 03 0 ~ 0 ~ 1~ 69c 01 RU -103 1 0 76+CZ 0 ~ 0 ~ 4 '9c+GZ 0 ~ 1 ~ 25E+ 04 C ~ 61E+01 FJ-1'5 $ .9 Oi<<00 3 ~ 0 ~ l>>156+02 D~ 5 '4E+D3 0. 3 ~ 5} 6+00
." J-lu6 95+ G3 G~ 0>>
j 3>>QSc +03 0 ~ 1 ~ 038+05 0 ~ 2~ Gli+02
'>>5 Ti+C3 45i+Q3 0 ~ 2 '5c+C3 0 ~ 5 ~ 92E<<05 0 ~ 8~ 62E+02 S5 12Z Q>> 0 0 0~
71i gf/
0 ~ 0 ~ 0 0 ~ ~ ~
c8-}Z>> 2>>7 Sc<<GZ 5>> 23 6+00 6 0 ~ 2 15E+02 7 ~ 85c <<03 0>> 1 ~ 106+02 2~ 2 2.37 c<<GQ 1 95E" 01 0 ~ 2.30E<<G 1 ~ 95E+G3 C ~ 4 '2c+01 1 Tc+C2 7 89E+01 6 '>>c+01 8 ~ 83E+02 0 ~ 8 ~ 67E+02 0>> 2>>9ii+01 7= }271 5 r. 0=+02 1.92c+02 1 ~ 40c<<02 Z ~ 23c +G3 0 ~ 1 c4c+03 0 ~ 6>>708+01 1 27 8 ~ o Zi+GQ 3.20c<<00 F 61=<<00 3 63i<<01 0>> 7 '4E<<02 0 ~ 1>>93E+00
) i -'o i29't 0 ~ 3 ZituZ 3 ~ 496<<02 3>>ZOE <<02 3 '9:+G3 0 ~ 4 ~ o96+03 0>>- 1 ~ 49c+32 2 ~ 5i<<GG 9. 65i-01 1 ~ 95i<<00 1>>07c+01 0 ~ 1 92E+DO 0 ~ 6 '1E-01
}>>4 1"<<02 6 d76+01 1>>09i <<OZ 6>>95i+DZ 0 ~ 6>> 8}i+03 0 ~ 5>>72i<<01 T= -'.31 }>>6 0=+00 6 68c-Gl 1 ~ 31E <<00 7 '0c+00 0~ 2>>39c 0 f 0>> 5 ~ Q4E 01 T=-'32 2 ~ J 5E>> 03 1. 33 i+02 1.46c+CZ 1F 296<<53 Oe 6 '56<<03 0 ~ 1 ~ 246+02 I }30 o ~ o 3c>> Qf 1>>}SE+02 1 ~ 53E <<0>> 1>> 83i <<02 0~ 1-01E<<02 0>> 4~ 63E <<31
--1~}
7, I--}33
) )
Z~ 1 1>> ?E<<01 di<<GZ 3-13c<<C2 656+01 1 ~ 02=<<G5 3 ~ 7oi <<03 5>>35" 4 '56+Gi
+QZ 0 0
~
~
8 5
~ Z>>c+ vi
'oE<<GO 0>>
0 ~
1~
1~
- 7. c+OZ 0}6+01 7>>5 'i<<Ci 1>>306+"2 2>>5}i <<u4 2.27c+02 0 ~ 1 ~ 15c <<02 G ~ 3 '86+Q1 I-"}34 5>>5 72+00 1 ~ 5}c<<01 1>>9o"<<03 2 ~ w}E <<Of 0 ~ 1>> 3ZE" 02 0 ~ 5 '}i+00 I"-135 2 ~ 3 36<<C1 6. }~E<<01 8 G3E+03 9 TTE+Gi 0>> 6 ~ 8$ " <<Cf 0 ~, 2 25-+01 6 8 5.+03 1 63=<<04 0. 5>> 29E <<03 f i75E <<03 2 85c <<G2 G ~ 1>> 33c<<04 135 Tc<<CZ 33 <<03 1 ~ 58i <<03 Z. 16c <<02 22= <<32 046+ 03 CS C- -'7 7,>> 1 S>>T 96<<03
?
206+ 04 0>>
0 ~ 4 ~ 09c+03 1 36E<<G3 3
2
~
'}i<<02 Q ~
0>>
2~
7 ~ 886+ 03 C= -133 6 ' di+00 1.2GE+df 0 ~ 8 ~ 84E+03 8 ~ 73E-G} '5 '2="05 0 ~ 5>>96E<<00 EA-}?9 7 ~ 7i<<GQ 5>>616"03 0 ~ 5>>24 E-Q3 3. 18i-03 1 ~ 39E<<C} 0 ~ 2~ 30c-01 E 4U r 56<<63 Z~ 07=+GO -0 ~ 7>>34E-ui 1~ }SE <<30 3 '9c<<v3 0 ~ 1~ 09 +02 E - <}
~
G. 2 '96-03 D ~ Z>>6SE-03 1 ~ 6+i-03 1 ~ 606-09 0 ~ 1~ Z9E 0}.
54-1>>2 } ~ 7 3=+CO 1 ~ 786 03 0 ~ 1 ~ 50 i-03 1 ~ 0}i"03 0 ~ 0 ~ 1~ 095-01 L<-140 }>> 5 Si<<GQ 7>>956-01 0 ~ 0~ 0 ~ 5 ~ 83i+G4 0 ~ 2>> }16-01 L'-'.-2 8.0 76-C'2 3.676-32 0 ~ D>> 3 ~ 2 ~ 68E <<02 0 ~ 9~ 15i-03
"=-1>>1 3>>~ 35<<00 Z~ 326+DC 0 ~ 1 ~ 08c +00 0 ~ 8>> 876+03 0 ~ 2>>63i-Qf 6 ~ c 56-01 4~ 'E<<02 0 ~ 1 ~ 97c-Gl 0 ~ 1 ~ 6Ti+04 0 ~ 4 '5E-02 Ci-'44 1 ~ 7 c<<02 7. 48 6+ C 1 0 ~ 43c+Gl C ~ 6 ~ C5" +04 Q. 9 'CE+GG PR-1 4 , l>>9}i-GZ 7 $ $ c 03 0 ~ 4 45E-03 0 ~ 2 '3E-09 0 ~ 9 '5E-04
)t--}")7 9 ~ 17i<<00 7>>58E<<QC 0 ~ n. 0 ~ 2>>5}i+03 0 ~ 2~ 69i << "0 Y>-239 3 ~ 5bc 02 3.53E-03 0 ~ 1>>OSi-02 0 ~ 7 12i+02 0 ~ 1>> 92i" 03 EA=cC OH UCI/ScC RELEASE RATE OF iACH ISOTOPE IH OISCHARGE FLOM .OF 1 CC/SEC 'MXTH HO AOOXTIOHAL OI'TION
TABLE G-1 Haximum Permissible Concentrations in Air in Unrestricted Areas Nuclide .HPC gCi/cc Nuclide HPC ~Ci/cc Ar-41 4 E-8 Y-91 1 E-9 Kr-83m 3 E-8 Zr-95 1 E-9 Kr-85m 1 E-7 Nb-95 3 E-9 Kr-85 3 E-7 Ru-103 3 E-9 Kr-87 2 E-8 RU-106 2 E-10 Kr-88 2 E-8 Ag-110m 3 E-10 Kr-89 3 E-8 Sn-113 2 E-9 Kr-90 3 E-8 In-113m 2 E-7 Xe-131m 4 E-7 Sn-123 1 E-10 Xe-133m 3 E-7 Sn-126 1 E-10 Xe-133 E-7 Sb-124 7 E-10 Xe-135m 3 E-8 Sb-125 9 E-10 Xe-135 1 E-7 Te-125m 4 E-9 Xe-137 3 E-8 Te-127m 1 E-9 Xe-138 E-8 Te-129m 1 E-9 H-3 E-7 I-130 1 E-10 P-32 E-9 I-131 1 E-10 Cr-51 E-8 I-132 3 E-9 Hn-54 1 E-9 I-133 4 E-10 Fe-59 2 E-9 I-134 6 E-9 Co-57 6 E-9 I-135 1 E-9 Co-58 2 E-9 Cs-134 4 E-10 Co-60 3 E-10 Cs-136 6 E-9 Zn-65 2 E-9 Cs-137 . 5 E-10 Rb-86 2 E-9 Ba-140 1 E-9 Sr-89 3 E-10 La-140 4 E-9 Sr-90 3 E-ll Ce-141 5 E-9 Rb-88 E-8 Ce-144 2 E-10 (1) If a nuclide is not listed, refer to 10 CFR 20, Appendix B, and use the most conservative insoluble/soluble HPC where they are given in Table II, Column l.
ST. LUCIE UNIT NO 1-ODCH
TABLE G-2 DOSE FACTORS FOR NOBLE GASES<
Total Body Gamma Air Beta Air Dose Factor Skin Dose Factor Dose Factor Dose Factor Ki Li Hi Ni Radionuclide (mrem/yr per HCi/m ) (mrem/yr per HCi/m ) (mrad/yr per HCi/m ) (mrad/yr per HCi/m Kr-83m 7.56E-02"-A 1.93E+01 2.88E+02 Kr-85m 1.17E+03 1.46E+03 1.23K+03 1.97E+03 Kr-85 1.61E+Ol 1.34E+03 1.72E+Ol 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 l. 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+Ol 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 l. 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 '4E+03 2.69E+03 9.30E+03 3.28E+03 "The listed dose factors are for radionuclides that may be detected in gaseous effluents.
": 7 56E-02 = 7.56 x 10
TABLE G-3 EttViROtiYEHTAL PATHttAY OOSE COtlVEFSION FACTOFS P { I) FOR GASEOUS OISCHAFGES O'THhAY GFQUtt0 pLAitE 0 posiTioN Instantaneous AGE GROUP INFANT IN JCL,O= 0 R G A H 0 0 S F A O'T 0 P, S {SO ~ HET R HREH/YR P R UCI/SEC)
ECt'E LIVER THYRCiu KIOHEY LUttG Gi" LLI SKIN TOTAL BOOY '
P <<3 ~
<<---72 0 ~
6~68c+06 ioiOE+09 3 9ZEq08 C"--"7 it 6424.08 5 Z7C+08 CG ct0 < ~ 40E>09 Z 07 6.87E+08 i;'g it 296+07
- 3. 07E+04 c ~ 94c y05 Y- C] i. ~ 53-+ 36 ZR 77 6.94E>08
~~ 95 it 95Eq08 U ~ i 03 1. 57&+08 RU <<u 2 '9E+08
<<0 3. 18E+09 E<<S 0 O.'t 1 UCi/SEC REL ASE PATE GF EACH iSOTOFE IN AHO A VALUE OF 1 ~ FOR X/Qi OEPL TEO X/0 At<0 RFLATIVE 0 POSITION
t~
TABLE 0-3 (cont t) t>VIRCNHi itTAL FATHHAY OOSE COhVERSI ON FACTORS P ( I) FOR GAS OUS OI SCHARGE S pATHHAY - cRouho pLahE 0EFcsITION Instantaneous AGE GROUP - INFAiNT tiiJCLIO 0 R G A N 9 0 S E F A C T 0 R S (SQ ~ Hi TcR HPEH/YR PER UCI/SEC)
G~rrE LIVER THYRCIO KIONcY LUNG GI"LLI SKIN TOTAL 900Y ~
l4 SN"'23 0.
0 g~ ~
Q <<.eoE+o9 S=-12<< 8 '2c+GS I SG-122 7o 56E+08 o 2. 19E~05
~
%7q 1 ~ 15E>06
- 129" " ~ 4cc+07
~ 3hii 7.905r 06
~ ~ 2 '6"+07 I2 1~ 786+06
--'3 3 54E+06
'3cr
~--13< 6 05 3o 666+06 2~ 82c+09 C> 139 2 '35+08 CS -137 i- 156+09.
i t 2. 33c+08 C-- 1 ~ 95Er07 C=-iic 9 '2cq07
~ 7
'EO 0:r 1 UCI/ScC ";,=LEAS= FATc OF El CH ISC OPE IN AN0 A VALrJE OF i FOR X/0 0 PLcTEO X/0 AtlO RELATIV OEPOSITIOtr
TABLE G-4 cNV RONHciliAL PATHWAY-OOSE CONVEPSION FACTORS R(i) FOP. GASEOUS OISCHAFGES P A HHAY - GROUNC PLANE OEFOSITIOl' CIRSLATIVE AGE GROUP CHILD TEEN - ADULT
& INFANT tlUCL Oc ~ 0 'R G A N 0 0 S E F A C T 0 R S (SOPH TER VIREH/YR F R UCI/S C)
GCtlE LiVcR THYRCIO KIONEY LU'iG Gi-LLi SKIN TOTAL BOOY H I 0 ~
3 1 I 0 ~
C-; 4 ~ 60E+06 V I~ 1 ~ 38E+09 Fc --=3 2 '5E~08 C" 57 io89E>08 CO J3 3e 80E ~08 CA 2 ~ 15c+ 10 7'l 7 '32+08 F.9 c6 9s01E+06 2, 17EP04 30 5 '56>06 Y---9 ~ 1 '8E<06 Z=.
5iGic+"8 ie 36E+03 F,U -103 1 ~ 10E ~08 PU -1.'6 4 ~ 19E+08
-Av 'I ~ V 3~ 53ct 09 EASEO 0:l 1 UCi/SEC RELEAS-"I RATE CF EACH ISCTOPE IN Ai'lO A VALUE OF li FOR X/Q~ OcPl.ETcg X/0 ANO ?ELATIVE 0EPOSITiON
TABLE G-4 (con't)
ENVIPCN..Et;TAL FATH)tAY-DOSE CONVERSION FACTOPS P(I) FOR GASEOUS OISCHARGES PATHNAY - GROUNO PLANE OEPOSITION C%)ULATIVE AGE GP.OUP - CPILD THEN ADULT 6 INFANT
'.>UC L Oc i 0 R G A N 0 0 S F A C.T 0 P S (SQ ~ HcT R HPEH/YP Pc% UCI/Sco)
Ca LIVER THYROIO YIOt:EY LUNG GI-LLI S'K I t] TOTAL BOGY cN-1>3 0 ~
SN ~ >6 5o 16E>10
- 5. 986+ 08 c> 1)5 2o 306+09 Ti) cccy06 a
- '+ 8 '9= >05
~ W c !e
.~ 3 '5i+07 I"-1 30 5 '35+06 I--131 1 ~ 725+07
~ 3P 1 ~ 25c+06 133 2 ~ QBE+06 t 505~05
~ "-'5 2
~
'6E+06 6~ 99" <09 C
-'6
-13'S 1-;9cq68 Cs -137 1 v3E+10 l! '! 1 ~ 0 6)E>08 0=-
C=-1
- ii 1m io 37E+07 io 13ii08 R>SEO 0't 1 UCI/S C FELEASE FATc OF cACH ISOTOPE IN ANC A VALUE OF 1 ~ FOR X/Qq OEPLETco X/0 Atto RELATIVE OcPOSITION
TABLE G-5 NVIRONH t(TAL FATHHAY OOS CONVEF SION FACTORS R( I) FOR GASEOUS OISCHAFGES PATHHAY - It!HALATION AGE GRGUP - INFANT t'U CL IOE 0 R G A N 0 0 S c F A C T 0 R S (HRcH/YR PER UCI/CiJr HETEF)
BONE LIVER THYRCi 9 KIOttEY LUNG Cr-LLI SKIN TOTAL BOOY P-- 3 U~ 4 '0E+02 4 'OE+CZ fr 886+62 4 '6c+02 4r306+G2 0 ~ 4 ~ 30E+02 F 42 Z~ 3'+05 1 ~ 35E+04 G ~ 0 ~ 0 ~ ir Sf E(64 6 ~ 78EP03 C ( ~
0~ Q~ 1 '4E+Di 3.99c+00 2 'ZE+03 5 81E+GZ
~ 0., f ~ 75c+01 Fc--c9 4~ 6. 93<<+03 G ~ ?Zc+63 2 45E+65 ir 35c+64 0 ~ iri6 +03 E+G3 wr66E+66 0 ~ 0 ~ 1 ~ 765~05 3r 295+64 6 ~ ~ 1,85Ei03 C3--c? Or 1.2fE+02 Or 0~ 6r4?c+04 5 '3E>63 0 ~ 1 ~ 185+62 (0
<<0 '3 0~ 1 1 8E>02 8.46E+02 Or 0 ~
0 0.
~ 8.79E+05 5 '?c+06 1 ~ 21c+04 3r28E+04 0 ~
0 ~ 1 EQE+ C2 f?Ei 03 7N c5 >rc?E>63 1 ~ O'+04 Or 1 21E+04 1 ~ 53E+05 9 '56+03 Gr 8r 15EqC3 6~ 2 '?6+04 0. -Or 0 ~ 2 '16+03 0 ~ ir 03E<04 Sc--3c 4 ~ 31Er 04 0 ~ 0 ~ U ~ 2 '1E+66 6 ~ 805+ 04 0 ~ 1,24cr03
- 1. 3Zc+07 0 ~ 0 ~ 0 ~ 1 53Ei07 1 39EPOS 0 ~ 8 06cl05 5 '85r64 Za63E~66 7v 1?cy04 Or fr60E+63 7=.--() 5 t.5 --95 1
1
~
~
08"+04 28E >03 G ~
Z~ 73E+03 Sr?5E~OZ 0
Or
~
0 ~
0~
9 48E+03 ir35E.D>
f r81 E~06 A ??E>05 ir41E+04 1 ~ 21E404 0 ~
0 ~
1 '5 +03
- 3. 3?E+OZ "iJ 1 ~3 1 ~ 69 r02 0~ Or 1 ~ OZE~03 5r 66Er GS 1 586+04 0 ~ c ~ 65 F61
".iJ 125 0 ~ U ~ 2 '4-+04 1.506+07 1 ~ 76E+05 0 ~ f ~ f4E+03 A ~ 116't re SC r63 1. 75=+ 03 0 ~ 3 ~ 44E+63 8r f ZE+65 5 '96+04 Q ~ fr046)03 B<<53 0't 1 UCI/SCC RcL=ASE PATc CF EACH ISOTOPE IN At(0 A VALUE OF ir FCR X/Cg OEPLET D X/0 ANO RELATIVE OEPOSITION
TABL'E G-5 con')
Et'ViROHH=HTAL FATH)tAY OOSE CONVcRSXON FACTORS R'tX) FOR GASEOUS OISCHARG S PATHHAY XH tALATIOH AGE GROUP It1FAHT HJCLiGE 0 R G A H O O S E F A C T 0 R S (ttREH/ R 'PcR UCI/CUBI".ETrP)
LIVER THYRCXC KIOttEY LUNG Gi"LLI SKXti'OTAL OOOY S't-123 S.t-- Zo 3 1'+64 Z. 21=+-'5 6 ~ 45E+02 5i 85E+03 6
1~
'572c+03
~02 0 0 ~
3~ 61E+Oo 1.64c+06 5 ~ 99E+04 2 ~ 23E+04 0
Oo
' 1~
8~
C2c+03 40E+03 S3-12>> o ~ 4c +03 1~ 03c+GZ 32E401 e. 4.34E+05 7 ~ 11E+04 0 ~ 2 ~ 17E+03 1~ 1 ec Cc
~
1 25=+02 1 ~ 03c>01 0 ~ 3 '5E+05 76E+04 0 ~ 2 ~ 325 >03
~
2 4 ~ 54c+02 1 ~ 95c+02 1 ~ 535>02 2~ 17c+03 4.96E+05 io 36E~G4 0 ~ eo 16c+01 t c ~ . ~ 215+"3 9. 83c+C2 5i75E i02 8 01E+03 1 ~ 68E+05 2 ~ ezE+04 0 ~ 2 ~ 74E+02 ov 1- 32=+G3 o ~ SGE+GZ 5 08c+G2 6 ~ 40E+03 1 ~ 83E~06 7 ~ 32c<04 0 ~ 20 06c+02 130 c ~ CZE+GZ 2 ~ 355+03 3 ~ 05 +65 3+656+03 1. 352+C3 Oo 9 ~ 255+02 1 31 635+04
'3603'2 4 ~ Z7=+G4 1 ~ 4 c F07
~
7.67c+e4 1 ~ 0 7 +0'4 9 '9c+02 3
V
~
~ ii07-+03 1'+01 0 ~ 2 ~ 51c+04 2 ~ 03E+az 2 o ~ 70=+ 02 0 ~ 7 ~ 0 ~
ll3 1 ~ 3>> >04 io 93r.+04 4 ~ eoE >05 4.55E+C3 0 ~ 2 ~ 286+03 0 ~ 51' 87E+03 3<< i ~ - oc 3 ~ GZE~02 4 ~ 02E >0<< 4 '26+02
'56+03 0 ~ 76E-01 0 ~ ~ ceE Dz I 135 4.70ciez 1 ~ 226+03 ii64E>05 1 0 ~ 9 ~ 18c+02 0 ~ 4 ~ 51E+02 C) 13% <<.802+05 8 ~ 25 4+ G5 0 ~ 5 '<<E+G4 ioG1E+05 11 37E%03 0 ~ 70 326+04 CS-'o 5 '5E~Q3 2+ 56E+04 Oe io50c+C4 Ze iec >03 2 ~ C<<E+03 0 ~ ie 95E>04 CS-137 6.".6->u5 7~ +Or 0 ~ 3 '9E +04 9 ~ 45cq04 32E+03 0 ~ 4 ~ 41Et04 5 'ac~03 >> ~ 27c+00 0 Ze93E+00 1 ~ 64c+05 ) ~ 88E+03 0 ~ 2 ~ 955<02 CE-)' =Pc+03 f,o 5 +03 a. '0--+03 5 ~ >4Eie5 20 CozyC4 0 ~ 1 ~ 81E~OZ ii 1 ~
Cc-1~4 v ~ r )cgar Bzc~05 0 ~ 1 48E+05 1 27c 1.0 1 616 q05 Oo 2e 49o+0'4 EO OH 1 UCI/SEC RELEASE PATc GF EACH ISOTOF iH AHO A VALUc OF 1 ~ FOR X/t) OEPLETcO X/O AHO RELATIVE OEPOSiTIOt'
TABLE'G-6 Et'VIROttHENTAL PATHHAY-OOSE CONVERSION FACTORS R(I) FOR GASEOUS OI SCHARGES PATHHAY - CO:tS HiILK (COt<TAHINATEO FORAGE) AGE GROUP - It'FAttT t' IC'I T 0 0 P, G A N 0 0 S E F A C 7 0 R,S (SO+HETER-HiREH/YR PcR UCI/SEC)
ECt:i LIVER THi YROI 0 KIONEY LUNG GI LLI SKIN TOTAL oOOY P--- 3 2~ 37E403 Z~ 37c403 1,04c 40 2 ~ 37 E+03 2.37c+03 0 ~ 2 '7c+03 I 1 32241 i+ 1 09 0 ~ 0 ~ 9 ~ 2 ~ 05i+39 0~ 7 05c408 Co 0 ~ i>>8224G4 6~ t Zc4U3 4 '4E404 7 eec406 0 ~ 3.05E+04 0~ 8>>9 6640e 0 ~ 2 ~ 67c 40o 0 2 ~ 74i 4i}7 Oi 1 '1"4C6 F=-- 9 3 '7E40 'ti 26+ G7 0 ~ 0 ~ 2~ 09c+07 2 '8E+08 0>> 2 '6c+07 03--57 Oo 1 ~ 3 6" 406 Oo 0 ~ 0~ 3 '6c407 0 ~ 2~ 27E+06 CO--53 O. 2 5 5c+07 Oi 0 ~ 0 e.sGE.07 0 ~ 6~ 24i 407 C GO i)i a.7 Si+07 0 ~ 0 ~ 0 ~ 2 ~ 16E408 0 ~ 2 ~ 09E+
68)
--"5 iicsc40 656+ 09 lj 3>>11E409 0 ~ 2 '35409 0 ~ 2 l OE+69 o Ol>> 2>> 77c+09 0 ~ 0 ~ 0 ~ 5 '56468 0 ~ 1 ~ 296"09 c 1 ~ 47c41 >> 0>> 0 ~ Oi 0 ~ 2 75c+Ga 0 ~ 4 '2E408 1 ~ 65641 1 0 ~ 0 ~ 0 ~ 0~ 1 ~ eii+09 0 ~ 4.21c 10 9l a. 12=40 4 6 ~ Q ~ 0 Oo 5.37c+Ue o ~ 2 16i+ 03 7>> Zoi?c40 5 9.4ic+04 0 ~ 1 86i+04 0~ 7 '7E+07 0 ~ 5 ~ 5oi434
- t. 3--95 5 ~ 9549 2 475495 3>> 84=+04 0 ~' 1 i 986+08 0 ~ 1.45=495
-"J -193 8 30640 3 9 ~ 0>> 4.16'3 ~ 1 04c+35 0 ~ 2 aei+03
'o=494
.=.J -1 35 01=+ C 5 F 236404 1>>
'55oi +1006 9 2
~ =
2 U ~ 0 ~ 0 ~ ~
o ~ 2ic+C I 5 ~ 75F+G7 0 ~ 1 136408 *~
V 2 0 ~ 3 '2E+07 oAS 0 ON 1 UC I/S C 9-"' ' PAT E OF EACH ISOTOFc IN A ttO A VALUE OF 1 FOR XIQ4 0" PL iTEO X/0 ANO RELAT IV"= Oi POSITIOtt
.':CTE - THE UNITS FC.-; C-"-14 ANO H--"-3 ARE ( ~ cEH/YR PER UCI/CU ~ .'l TcP)
TABLE G-6 con't 0
EhVIPOWHcHTAL FATHHAY-COSc COttVcFSIOH FACTORS R(I) FOP GASEOUS OISCHAFGES PA ~ HHAY COl 5 t'iLK (COtlTAYIHATEO FOrAGE t AG c GROUP IhF AHT e ~
0j 0 F G A H 0 0 S E F A C 'T 0 R S (SO ~ H TcR HREH/YR FcP, UCI/SEC)
CGI ~ LIVER THYRO.D KIOHEY L U tt r Gi-LLI SKIt' TOTAL BCOY
~ o3 0 ~ 0~ 0 ~ 0 ~ 0 ~ G ~ ~ 4~
'.75=+09 3 ~ 48c ~ ur C1E+67 0 ~ 4.97E+O5 1.16c+O9 0 ~ re 25F 5 nor
".6 Z.rrE Or woe9 +65 6 '4E<Gw 0 Zei3Enor 7 ~ 76c+08 6 ~ 1.6oEn07 "12'5-125 oeo9c+67 57En68 3
5
'730cnor c+66 2 '3cn96 5 ~ 1SEnG7
~
3e9oE+06 7e05En67 2
0 ~
83E+09 2e43En08 7 '7E+07 0
0
~
~
6 '2E+06
- 2. 10E+ 07 I c rc~ ~ ~ 5 ~ 54cn67 ae'935+07 1.79En07 2eOOE+08 0 ~ 3 '46+08 0 ~ 7. 38En 96 I '2JH 2.025+08. 2 21Enoo ZerGE+G8 9 ~ 3 '4E+68 0 ~ 8 ~ 95E n 07 4 '4-+CS 35EnGS 1 ~ 71=+08 Zeu9E nG6 p. a.as=.+66 0 ~ 5~ 29E+05 I 2 o +69 3.6oE+09 9 94cn11 7 '4E+06 0 ieiSc+06 0 ~ 1 ~ 81cn99
'6 -61
~ ~
I--132 1 4erSE-Gi 6 '5cnoi 7 'SE"Gi 0 ~ 8 '3E"02 0 ~ ie 69E-01 I"-1 33 je rsi <07 485+07 1 39E+ao 1,29E nor 0 9 '4E+9S 0 ~ ie 66E+07 6~ 0 ~ ie05= -39 0 ~ 0 ~ 0 ~ 0 e 0 ~
135 1 ~ 49" +'34 3.94En04 5 ~ 15 +Co 6.26E"04 8 07E-02 4 '1E+04 0 ~ 1 ~ 445+04 C'13>> 4 ~ '<<,3 =+ 1 6 ?e97 +10 Ge 4 '5En09 9 12E+09 1 90E+06 0 ~ 6 '5E+09 CS-1 .5 2 'SEeCS 1 ~ ki +6 9 ~ 6eiir.+08 be37E+07 1.Z5E+CG 0 ~ 7 '0cn08 Co 37 6 44">1" 7~ 215+ 16 0 ~ 3 ~ 65c+09 8 ~ 69En09 ie86c+06 0 ~ 4 '4EnG9 9A-1<9 2.45=noa 2 '7in65 0 ~ ae22cnu4 ie51En95 6 135+06 C ~ 1e 27En07 f c-1-'c-ai~
2e 6="nos a ~ 52Enos 0 ~ 9 '26+93 0 ~ 7 ~ Src n G7 0 ~ 1 90E n94 2 'Gi+67 yocnGS C ~ se'o/E+C5 0 ~ 8 666 nio 0 ~ 1. 13E+ 65 8aoI 0 ~ 8 '6E+68 C=-"= j 0 ~ Z~ 19E 463 8+67E+GZ 85c>63 9 '9=+05 C ~ 3 '6E+G3
~ i ~
5 0 1.08E+06 0 ~ 3 ZOE+05 0 ~ 3 '9c~06 .a. 2 '56)05 59 122>05 9 '86+05 6 ~ Gi 2 72Ei05 3 '3c <06 U ~ 3 '2E~05 C"--c7 6 g ~ c64 r+ Q5 0 ~ 0~ 0 ~ . 4 ~ 15E+06 0 ~ 2+72E+05 C"--53 0~ 3 '6c+06 0 ~ Qo 0 ~ 7 i 9Zc+C6 0 ~ 7 '9c+06 Ca--60 0~ 1~ rc56+67 0 ~ 0~ 0 ~ 2+59E>07 0 ~ 2 ~ 51"- >07 ZiN--65 1 7c 5+a B 5.57m+08 Oo 3 73" +08 0 ~ 3 ~ 51E t 08 0 ~ 2 52Et 08 FS--36 3 SZE+08 0 ~ Q 0~ 6i 54E+G7 Q 1o 55E+08 c 3 '9C+io 0 ~ 0 ~ 0 ~ 0~ 5 77c+06 0~ 8~ 87c +08 3 462+11 3' 0 ~ 0 ~ 0~ 3 '55+09 0 ~ 6~ 83E+10 Y---oi 9 ~ 74c+63 0 ~ 0 ~ 6 ~ 0~ 6 '5E+05 0 ~ 2 '0c+02 7~--95 2 '4E+64 1.13 E+ a4 0 ~ 2 '3C+03 0~ 8 '5Epa a. 6i67E+03 6+596+G-' 97E+64 5~81E<63 37E+07 ii75Et04
'-1"
~ 1 3 ~ ccE+GZ 2
0~
0 0
~
~ 4 996+02 a~
0~
Z 1~
~
24Ey04 0 ~
Oe 3+43E+02 FU-166 2 ~ <<1= 04 Oo 0 ~ 5 04c+G3 0~ 1. ~ 67E>05 0 ~ 2~ 96Eta3 AG ilrYi 7i45 66 ~ 6i 9Gc+66 as lo36EPD7 FI 2 '1E+09 0 ~ 4 '0E106
.'EO 0 'CI/S cC RELEASc RAT C CF EACH ISOTOPE TH AiMO A VALUE OF 1 o FOR X'/O q OEPL c TEO X/0 AHO RELATIVE OcPOSITIOii ttOTE THE UtiiTS FGFi C 14 AtiO H 3 ARE ("REH/Yg PER UCI/CU ~ H TER)
TABLE G-7 Con't)
Et;VIRON .ENTAL FATHHAY-OOSE COtlVEFSION FACTORS
~ R(i) FGP. GASEOUS OISCHACGES PATH "AY GOATS tlILK ICONTA'IINATEO FOFAG" ) AGE GROUP - IttFAtti t(VCL GE G P, G A N O 0 S E F A C T 0 R S IS/ ~ l TFR HF, H/YR PER UCI/SEC)
GCt>>c I.IVE?. THYRGIO KIONEY LUllG Gei LI.I SKiN TOTAL BOGY S'I-123 0~ Oe 0 ~ 0 ~ 0 ~ 0 ~ Oe 0 ~
2>> 10=498 4>>17c+96 1.ZZE 06 5 97F+05 ie406498 0 ~ 6 ~ 30E+06 C>>.'4 3 30E 496 o ~ ZZc+64 7 97E+03 0
C ~
~
2 '6c+06 9.33E+97 0 ~ le 30E+96
- 7. 94c+
73 7 31 +65 3 ~ O'Zc+ 95 3 '2c+05 76" <<05 3 40c468 2.92E+07 0 ~ 05 TE '5'I
~ ~
1 e 896497 6.36"+05 6 'ic466 8 ~ ~5E+96 0 ~ 9 69i+Go 0 ~ 2e52c+96 T>>Z(tI ": ~ o42 496 Z~ 316465 2.15E 405 2 ~ 40 "4G7 0. 3>>83c407 G ~ 8 ~ S5c 407 I voc4U7 Z ~ 42c+07 2 '5E407 3>>23c+07 0 4 '5=+67 0 ~ 1 ~ 07E+07
--130 5 56405 1 ~ 61E405 2.05E468 2 51E406 Oe 1 386495 0 ~ 6 '5E405 I--131 3.11=409 3 ~ 70F409 1 '9E+1Z 9 ~ ZQE 468 0 ~ 1. ~ 39E+98 0 ~ 2 '7E+09 i 132 2 13c"91 447 5 71c-0>>
- 6. 57 c+ C7 7 '1c401
<< ~ 55E 419 9 '0i Gi ie55-467 0
Oe
~ 1 1
~ C7i-91 176+07 0 ~
0 ~
2 1
'36-01
~ 99E+07 4eOI ~
9 1 275-99 Q ~ G ~ D ~ 0~
~
37 0
1~
~
(a +" 4 4
~
'22+94 6 '8 +Oo G ~
7 ~ 51c+64 2 42E-91 5 ~ 29E+04 5 '9c40S 0 ~ ie73E+C4 2 ~ C2E 410 C= -13>> 1.33ctli 2.39c411 G ~ I. 39E+19 2>>7g c410 0 ~
CS -156 Se 3-'+98 3>>29c40'9 Oe 1.83c+G9 2 '1E+05 3 '4E+08 0 ~ Z~ 376+09 CS-137 ~ 936411 2~ 16 4<<1 G ~ i. 47E+03 166+1G Z~ 61E+10 ie 81E+64 5 '9"4CS 0 ~ 1e 24r. + 10 5224C6 3A ~ Q 2.956+Q7 2. 95 "404 0 ~ 1~ 9 7OE405 0 ~ 1~
Ci-1<<1 3-175 4G4 1 '5E+04 0 ~ 1~ 176+03 0 ~ 9.44E466 0 ~ 2 '8E+C3 C>> 4 2 ~ "2:-4 5 c ~ or.E465 0 ~ 6>>80 +64 0 ~ 64c408 0 ~ 1 36c495 9'S"9 ON 1 VCi/SEC RELEASE RATE OF EACH ISOTOPE iN ANO A VALVc GF 1 ~ FOR X/04 O=PLETEO X/0 AtlO PELATIVE OEPOSITION NOTE - THc VtlITS r G? C-'-"14 AIIO H-"--3 A..c IH?cH/YR PcR UCI/CV ~ HFTER)
Page 72 of TABLE ?I-l Selectin the-Ao ro riate Lon Term X for Dose Calculations Involvin Noble Gases for:
Total body dose from instantaneous releases
(
(2) Skin dose from instantaneous releases (3) Gamma air dose (cumulative)
.(4) Beta air dose (cumulative)
Type of Dose Limiting Limiting (X/Q) Value Calculation Range (miles) Sector sec/m3
-6 Instantaneous-LCO 0.97 N 1.6 x 10
-6 1/31 da s-LCO 0.97 1. Normally (X/Q) =1 4< IO sec/m Quarterly-LCO 0.97 2. A (X/@, using a wind sector frequency calculation to deter-12 consecutive mine the avg of the 16 sectors, 0.97 ma be used in lieu of 1 above.
Annual Report 0.97 (NA) Note-1 Note-1 The (X/Q) has to be calculated based on real meteorological data that occurred during the period of interest. The sector of interest is NA because the limiting X/Q will be determined from the actual meterological data.
0.97 miles Corresponds to the minimum site boundary distance in the north direction and 0.97 miles was chosen for all other sectors for ease of calculations when the averaging is done for quarterly reports.
ST LUCIE UNIT NO 1-ODCII
TABLE M-2 Selecting the Appropriate Long Term (X/Q)D or (D/Q) for Dose Calculations Involving Radioiodines & 8 D Particulates for:
(1) Inhalation, (2) Tritium (All gas pathways), (3) Ground Plane Limiting Limiting Type of Dose Range Sector Calculation Miles (OL) (X/Q)D sec/m (D/Q) 1/m2 Instantaneous LCO 0.97 Nw j,S >c lO 8,2.x lo Quarterly for 0.97 Semiannual Reports 0.97 A 1/31 days LCO, 0.97 NN/ l,3 x)O Qtr yearly LCO, 12 consecutive -9 month LCO. 0.97 - WMW ,2. x lO (OL) Over land areas only A. To be determined by reduction of real met data occurring during each quarter with freq. dist averaged in i.e. 16 q D Avg
~(=i fraq factor (X/Q) D rea] (y)
= 16 (D/Q) Avg freq factor x (D/Q) real(i) i=1
Page74 of TABLE H-3 Selectin the A ro riate Lon Term D for Dose Calculations Involvin Radioiodines & 8 D Particulates for Grass-Cow-Hilk or Grass-Goat-llilk:
Type of Dose Limiting Limiting (D/Q) value Calculation Range Sector 1/m2 Release Rate-LCO A A 1/31 days-LCO B Quarterly-yearly LCO B 12 consecutive month LCO Sevn<<nagual Rkpod A The worst cow or goat as per locations from land census. If no milk animal in any sector, assume a cow. at 4.5 miles in the highest (D/Q) sector over land.
B The historical (D/Q) is to be a historical wind distribution frequency weighted average (see Table lf-8) of all land sectors with the ~orst cow or goat from each sector as reported in the Land Census. A 4.5 mile cow should be a'ssumed in the worst sector when no milk animal is reported.
C - The (D/Q) is to be a wind frequency weighted average of all land sectors as reported in the Land Census. Real met data should be used for the reporting period. A 4.5 mile cow should be assumed in land sectors where no milk animal was reported.
A wind frequency weighted average is defined for land sectors(only)as (D/Q) avg = ~ (Freq Dis factor) (D/Q)i where ST LUCIE UNIT NO 1-ODCH
TABLE H-3 (con't) Page 75 of (D/Q) avg = the wind frequency weighted (D/Q) for all land sectors in 1/m . The infant is assumed to drink milk from each animal for the wind distribution frequency.
Freq, Dis Factor The %/100% fraction of time the wind was blowing into the sector. It is a historical determination for B above, and real for C above.
(D/Q)i = The historical or real (D/Q) calculated for the sector over the time interval.
The historical wind frequency fractions for each sector are listed in Table M-S.
ST LUCIE UNIT 4'0 1" ODCH
TABLE N-4 TERRAIN CORRECTION FACTORS FLORIDA POWER ANO LIGHT CO ~
ST<<LUCIE UNIT 1 HUTCHINSON ISLAND<<FLORCDA DAHES ANI) HOORE JOO t$ 0 ~: 4598 - 112 TERRaIN CORRECTIOti FaCIORS tt (GAFF r sTRaIGHT LINEt PERIOD OF RECORD t or29r77 TO nr31I78 BASE DISTANCE Itt HILES r KILOHETEtts AFTD DESIGN SECT DIST HI
~ 2S
.40
.75 1 ~ 21 1 25 F 01 '27S 1 ~
2 2<<25 3 '2 2 4
'5
'2 3 5
'5
'3 3,7S 6 '3 4 <<25 6 F 84 4<<75 7 64 NNE 0 ~ 1.906 I 5/6 465 1 ~ 404 I ~ 338 1 ~ 318 1 ~ 334 I ~ 386 1 <<346 l<<338 HF 0 ~ I ~ 88'I 1.581 1,461 1.391 1<<310 1 ~ 259 1,164 1 ~ 128 1 ~ 1nl 1.116 EtiE 0 ~ 1.452 1.230 1. 12? 1 ~ nisi 1 ~ 047 1.033 ~ 941 <<941 ~ 906 .902 E 0<< 1<<h62 1 '2S 1.27'I I 193 1 ~ 151 l<<123 l<<097 I ~ 1?1 1 ~ 123 1 ~ 1?2 ESE o. 1 ~ 690 1<<483 l. 388 1.?ho 1.?46 1 ~ 190 I ~ 134 I ~ 094 1.032 .968 SF 0<< I ~ 818 I ~ 691 1.47o I <<427 1.435 1 ~ 361 1 ~ 366 1 ~ 331 1.279 1.239 ssE o. I ~ 812 1 ~ Snh I ~ 370 I <<30? 1 ~ 2 IO 1 <<263 1.229 I ~ 193 I ~ 171 I ~ 151 S 0<< 1 ~ 398 1<<3?.l 1.12S I ~ 083 I'.loe 1.127 I.o73 1 ~ 063 1<<047 1 ~ 024 S5M 0 ~ 1 <<534 1<<411 1<<?96 1.192 1<<205 l<<132 F 135 l<<116 l<<077 l.nho SW 0 ~ I ~ 685 1,492
'I t3 l<<?94 1 '33 l<<?00 1 ~ 222 1<<160 I ~ 160 1,198 1.196 usw n. 1,620 1 ~ 1.21n 1<<173 1.082 I ~ 091 1 099 1 F 056 1 ~ 034 l.nn4 W 0~ 1.6&I I 415 290 I ~ 218 1<<154 1.099 1,081 1 ~ 06I I ~ 093 l<<083 WNW 0~ 1 ~ I20 I ~ 4'30 l<<267 I ~ 185 1 150 I <<133 I<<125 I ~ 085 1 ~ 033 I.n45 Hw 0 I ~ 681 I <<407 1.257 1.173 1.119 I ~ 078 I.oo3 .995 ~ 998 ~ 978 NNW 0 ~ 1.739 1 ~ 488 1,3)6 1.? 1? 1 ~ 172 I ~ 122 1 ~ 135 1 F 080 I ~ 099 I.o91 N 0~ 1 ~ 816 1. S?4 ~
1 ~ 3A9 I ~ 285 1 <<257 1 ~ 263 1,285 1 ~ 267 l<<231 l<<213
TABLP. M-5 HISTORICAL LONG TERM (X/ )
TEARAIN / RFCIRCULATION AOJUSTfO PAOGltAH AttNXO09 VERSION - 11/18/76 FLORIOA POWER ANO LIGttT CO ~
5 T ~ LUC IF. Uth I T HUTCHINSON. I SI.ANO ~ FLORIDA OAHES ANO HOORE JOB NO ~ t 4598 112 AVERAGE ANNUAL RELATIVE CONCENTRATION ISEC ~ /CUBIC HETERI PERIOO OF RCCORO t 9/ 1/76 TO 8/31/78 BASE OISTANCE IN HILES / KILOHE.TERS AFTD OESIGN SECT DIST Hl
~
~
25 40
~
lo21 75 lo25 F 01 lo75 2o82 2o25 3 '2 2o75 4 '2 5 3o25
'3 3 6
'5
'3 4 ~ 2S F 84 4oTS 7 '4 ttNE 0 I ~ I E-05 loTE-06 l BF.-07 4 ~ SF.-OT 3 ~ IE-07 2 'E"07 I o TE'-07 5E-07 1 ~ 2E-07 l~Of-07 NF. 0
~
~ 1 o3C-05 2.1E-06 Bo9E-07 5 'E-07 3 'E-07 2o4C-07 I ~ 7E-07 1 ~
lo4E-07 I ~ IE 07 9 'f-08 fttE 0. 9 'E"06 1.4E-Oe 6.2E-OT 3.7E-OT USE"07 I ~GABE 9E"07 lo3E-07 lolE-07 Boof-08 USE-ott E 0 ~ 9 'E,"06 I o6F.-06 6 ~ SF.-07 3 TE-ol 2 'C-07
~ I ~ Of"07 I ~ 4E-07 I ~ 2E"07 9,9E-OO 8 'E-Ott ESE oo 1 ~ ZE-05 I ~ VE-06 8 ~ IE,-07 4oBE-ol 3 'E-OT 2 ~ 4C-07 l~BE-07 I ~ 4E"07 I ~ IE-07 9 'E-OB.
SE oo I ~ 4E-05 2 ~ 4f.-06 9o TF."07 So7F.-07 4 'E-07 Zo9E-07 2,3E 07 1 ~ 9f-07 lo4E FAZE-0707 I o2E-ol SSE 0 ~ I ~ lf.-05 1 e TF-06 To3F.-OT 4e3E"07 2.9E-07 2 elf-07 1 ~ 6E-07 I ~ 3E-07 1 ~ lf-07 '9 ~ 1 f"08 5 0 ~ 6.28-06 1 ~ OF.-06 4o2F.-07 2 ~ SE-07 1 ~ 8E-07 loAE-07 1 ~ OE-07 8 ~ OE"08 e.6E-oB USE-08 SSW 0 ~ 5 'E-06 9 'F 07 o ~ Of 07 2e3t'7 I e6E-0 l loIC-07 8 'E"08 7 ~ OE"08 5 'E"08 4 'f-08 SW 0 ~ 6. IE-06 9o4E-ol 3 'E-07 Ze?E-07 lo6E>>07 lolf-07 8 ~ 6E-08 7 ~ OE-08 6 'E-08 5 I E-08
~
'WSW 0 ~ .7o3E-06 1 o IF.-06 4e6F.-OT 2oTE-07 le7E-07 lo3E-07 1,0E-07 Boof 08 6o5E-08 5 'E"08 0, 7oeE-o6 1 ~ 2f-06 5o2E-07 Z ~ 9f-07 2ooE-07 1.3E-07 1.0E-OT 8 'E-08 7 'E-08 6 1E "08 ~
WNW 0 ~ I ~ 4f-05 2 'E"06 9 lE-07 5 'E-07 3o4E-07 2.6E 07 2 'f-07 1 ~ 5E-07 1 l,of-07 NW 0 ~ 1 ~ 6E-05 2 o 4F.-06 I ~ OE-06 5 ~ 9C -0 7 3 'E"07 2 'E-07 2. I E-07 I ~ 7E-07 1 ~ 4E 07 Io2E-07 NNW 0 ~ USE-05 2.2E-06 9.ef-o7 S.SE-ol 3o6E-07 2 'E-07 2 ~ OE,-07 le6E-07 lo3E-07 I ~ 2E-07 t$ Oe 9o lf-06 1 ~ 4F 06 6 ~ 3E Ol 3 ~ 6E 07 Zo4E-07 I 07 1 ~ 4E-07 1 o2E"'07 9 'E-08 7,9E-OB NIIHHEA OF VALID OBSERVATIONS = 17135 NttHHEtt OF lttVALIO OBSERVATIONS = 385 CALHS.LOWER LFVEL = 95 ttltHIIEA ttttHIIER OF OF CALHS'UPPEA LEVEL = '
,0 TABLE M-6 HISTORICAL LONG TERM DEPLETED (X/Q)D
~ y O
Tf<<<<AIN r <<ECIRCULAT ION AOJUS)tO 0 P<<UGRaH ANNxoa9 vfllslON - 1 lr 18r76 FI.ORIOA 'POWER Atlo LIGHT CO ~
ST ~ LUCIE UNIT, 1 HUTCHltlSON I SLA)lO ~ F'l.oil lf)A OAHES ANO HOORE JOH NO ~ t 459ll - 112 avf)taGE aNNUaL <<ELATIvE CONCENTRaTION OEPLETEO ISECrCUHIC HETE<<)
pE<<loo oF <<Eco<<0 : 9r lr76 To ur3lr/8 elf BASE OISTANCE IN HILES r KILOHtTE<> 1.2L-OS Iedf-Ob 6 ~ OC-01 :).9F.-07 2 8 6 08 SE 0 ~ le3I-05 2.of-o6 8 ~ ?E-07 4o7F.-07 3 'E"07 2 ~ 3E" 01 I.HE-07 1 ~ 3E-Ol 1 ~ If-07 9 Of-OH SSC 0 ~ I "05 loBE-06 6 'C-07 3 'E-07 2 'E-07 loHE-07 1.4E"07 leoE-07 8 ~ 2E-OH 6 ~ BF.-OH S 0 ~ Se9C-06 9.1E-07 3 't-07 2olf-07 1.4E"07 lolf-0) 7. 1E-OH 6.2E-OB 5 'E-08 'C-ott 4
SSW 0 ~ 5 'E-06 8 ~ Ot-07 3 4F-07 le9C-07 1 ~ 3F-07 8.9E-OB 6 'E-08 5 'E-OH 4 'E-OB 3.6E-OB SW Oe 5 7t-06 8 'E-OI 3 'E-07 lo8E-07 1.2E-07 9.2t-oH 6,7E-OU 5 'E-08 4.6F-OU 3 ~ BF.-OB WSW 0~ 7 'E-06 9 'E-07 4oof-07 2 'E-07 1.4E-07 I.OE-07 8 ~ OE-08 6 'E-08 5eoE-08 4.0E-OU 0~ 7.3f-on I lf-06 4 4E"07 2o4f-07 I-6E-07 lolE-07 e 8.2E-OB 6 'E-08 S ~ Sf-08 4o4E-OU WNW 0~ I 3E-OS 1.9E-o6 'I ')F.-07 4 'E-07 2o9E-OI 2.0E-07
~ ~ 1.6E,-O I 1 ~ 2E-07 9e3E-08 leaf-OH tlW 0~ I Sf-oS 2 ~ lf-ob 8 ~ ') C-O'I 4o9E"0) 3.]E-01 2 ~ 3f.-o 1 1.7t-ol 1.3t-ol I.OE-07 HASE-Ot) ttl.lW 0~ 1.4F-05 2. If-06 U ~ 3E-07 4.5l;-01 ? Uf.-ol 2. Of'.-07 1.6E-07 I 2E-01 I.nf-07 Hoof-OH N 0~ 8 ~ )F-06 I ~ tf -06 be4f-O'I 3 ~ OE-01 2ooE"07 1.4E-07 lolF.-07 8 9E-OH 7 'E-OB SeHE-OH to)H)tf<<OF VAL IO OUSt'<<VAT IONS 11135 Nl)HUE<<OF'thVALIO llUStltVATIUtlS 385 wu<<llf<< OF caLHs LowE<< LfvFL = 95 NUHUER 0F CaLHs vppfh LFvfL = 0
0 TABLE M-7 HISTORICAL LONG TERM (D P4 0
I o
A Z
TERRAIN / HFCIHCULAIION AOJUSTEtt PROGHAH AttNX009 VEHSION 11/18/76 FLORIDA POWER ANO LIGHT CO ~
ST. LUCIE UNIT 1 HttTCttINSON ISLANOo FLOHIOA OAHES AND Hooitf JOB Noot 4598 - 112 AVERAGE ANNUAL RELATIVE OFPOSITION RATE ISOUAHE HETER -1 I PERIOD OF RECORD : 9/ 1/76 TO 8/31/78 BASE OISTANCF IN HILFS / KILOHETEHS AFTD DESIGN SECT DIST HI
~
~
25 40 1
~ 75 i21 I ~ 25 2ool I ~ 75 2oe2 2 25 3 62 2 75 4 '2 53 '3 '5 63o'f5 '3 4o25 6.84 4
7 '475
~
NNE NE' 0 ~
~
b SE-08 9 't-09 3 ~ 7F-09 2 IE-09 I ~ 3E-09 6.0E-QB 8 ~ 9E-09 3.5E-09 1 o 9E-09 lo2E-09
'9 'f-lo 6 Bt-10 UolE-10
~ SoSE" 10 6E-10 4o3E-10 4~ 3f-l 0 3 ~ 3E-10 3.5E-IO 2.8E-10 ST ENE Q. 3o2E-08 4ottf-09 lo9F.-09 looE-09 6 'E-10 4 ~ 6E'-10 3 ~ 2E-10 2o4E-10 I ~ 9E-10 1 ~ SE-10 E 0 ~ 3iot-08 4.6E-09 l.ef-09 9.5E-lv 6oOE-10 4 ~ 2E-10 3,1E-IQ USE-10 2.0E-10 1 ohf" lo ESE 0~ 3o7E-08 S.ttf-09 2 'E-09 I ~ 2E-09 8 ~ OE-10 So4t-10 3 ~ 9E-10 3 'E-10 2i2E-lo 1.7E-10 sf o. 6o4E-08 .loof-08 4oof-09 2 ~ lE-09 lo4E-09 9o7E-10 7 ~ 2f-lo 5 ~ 6F.-10 4o3E-10 3.5E-IQ SSt 0 ~ 6.2E-QB 9oSf-09 3 'F.-09 2 QE"09 lo2E-09 BoTE-10 6 'E-10 4o9E 10 3 ~ 9E-10 3olE-10 5 Q ~ 4o2f-08 7.0E-09 2o6E-09 1 ~ 4E-09 9.5E-IQ 6.9t-lO 4.9E-IO 3 'E-10 3.0f-lo 2 Sf-10
~
SSW 0 ~ 3.4E-QB 5,4E-09 2o2E-09 I'1E-09 7o5E-10 5oof-10 3 'E-lo 2 ~ 9E" 10 2 3f" 10 1, BE-10
~
SW 0. 4 5E-QB 7 Qf-09 2 6E-09 USE-09 9ooE-lo 6o6E-10 4 'E-10 3 'E-10 3 'E-10 2 Sk-I 0
~
'WSW 0 ~ 5.3E-ne 7.7f-O9 3.OE-09 1.6E-Q9 looE-09 7 'E-10 USE-10 4o IE-10 3.3f-l 0 2 'E-10 W 0 ~ 5 'f-08 7oSE-09 3.0f-o') 1.6E-09 9oBE-10 6 'E-10 5 'E-10 3 'E-10 3 ~ 2f-10 2o6E"10 WNW 0 ~ 8oBE-08 lo3E"08 4o9E"09 2o6f "09 1 ~ 7E-09 lolE-09 8 'E-10 bo6E-10 5~lE-10 4i2E-10 ttw 0~ 8 ~ 2E-08 I ?E'-08 4 'E-09 2 5E-O9 1 ~ 6E-09
~ lolE-09 7 'E-10 5 'E-10 4. 7E-I o 3. BF.-10 ttllw 0 ~ 8.?E-QB 1.2f-ott 4,6E-O') 2.4E-Oe) loSE-09 1 ~ lf-09 8 IE-10
~ 5 'E-10 4 'E-10 4 ~ Qf-10 tt Oo S.IE-OB 7.3F.-O9. 2.9E-OV 1.5E-09 9oBE"10 7.1E" lo 5.4f-lo 4 'E-10 3o2f-lo 2o TE-10 tHtHBEH OF VALID OUSFHVAT IONS 17135 tatHttER OF IN V AL 10 OU St ft VA I I ON 5 385 ttttHI<ER OF CALHS LowfH LEVEL 95 NUHBER OF CALHS UPPER LEVEL 0
Page80 of TABLE hf-8 JOINT 'ZINO FPEOUENCY DISTRIBUTION DaTA PERIOD: SEPTEMB R I 197b - AUGUST 3) ~ 1978 aLL WINOS ST ~ LUCIE UNIT 2 DATA SOURCE:'N>-SITE HUTCHINSON ISLAND FLORIDA vINO SEr~SOr TABLE GENERATED:
HEIGHT: 10.00 12/05/78 '7 '2+]8 METERS
~
FLORIDA POWER AND LiGHT CO DAMES AND ~OO~E JOB NO: 4598 - 112 - 27 wlND SECTOR 0 0-1.5 1 ~ 5-3 ' 3 '-5 wIND SPEED CATEGORIES <METERS PER SECOND)
P 5 P-7 5 7 '-lP 0 >]0 ~ 0 TOTAL MEAN SPEED NNE F
71 43 206
]>25 318
]+92 ~
71 43 >02 3
'0 0 00 669 4+05 3 '2 62
~ 38 292 I ~ 77 2 '3 385 128
~ 77 0+00 0
0 F 0
00 5 '5 867 3 43
~
ep 36 334 F 02 505 F 06 158
~ 96 0
0 F 00 0 F 0
00 1057 6040 3 '1 69
+42 355 2 ~ .15 3 '9 510 76
.4e 0 F 0
00 0
0 F 00 1010 eel] 3 '5 684 744 115
~ 70 4 ~ 14 4>50 ~
72 44 ~
I 01 0
0 ~ 00 9 '8 1616 3 04 183 1 ~ 11 3 '9 eep 749 4>53 ~
28
]7 0 F 0
00 0
0 F 00 1620 F 81 F 88
])9 579 F 50 3 '7 ese 93
+56 F 01 I
0 F 0
00 1458 8 ~ 82 3>]0 S
F 72 44 310
]>88 4pj 2 '6 99
'60 F 8
05 ~
I Ol 5 '3 897 3 '6 84 446 SS>W e5] 2 '5 372 2 '0 105
~ 64 33
~ 20 ~
4 02 1044 6 ~ 32 3+48
)06 ]4 3o]0 2 '6 44p 335 Sv 129
~ 78 2e03 ~ 64 F 08 0 F 0
00 6 '0 1025 155 320 186 29 695 2+59
~ 94 ]>94 1>13 ~ ]8 ~
5 03 0 F 0
00 4 '1 174
]F05 267
]ob2
])9 ~
37 22 ~
2 Ol 0
0 F 00 3 599
'3 2.43 203
]+23 304
]oe4 172
]+04 F 17 10 0 F 0
00 0 F 0
00 695 4+2]
2 '4 2 '5 NV 143 4 87 3 '<
518 424 2>57 ~
50 30 0 F 0
00 0 F 0
00
)135 e.aj
'70 N>Jx
~
85
- 5) 2 '9 379 3 '4 535
~ 42 >0]
1 0 F 0
00 6 '8 1070 3 22
~
91 Ss
]94
]o]7 3 '1 531 ]48
.90 ~
5 03 0 F 0
00 959 5 F 86 3 '9 CALM 95 95 CALM
~ 57 ~ 57 62]4 7023 16 ~522 3. ) 0 TOTAL 1920 1]+62 37+el 42 '1 I'9 1287
~
73 44 ~
5 03 ]00+00 NUMREp OF VALID OBSERVATIONS ]6522 - 94 '0 PCT ~
NUMBER OF I:VVALID OBSERVATIONS 998 5 70 PCS TOTaL NUMEE OF OBSERVATIONS 17520 100 ~ 00 PCS
>>:EY >XX NU>>Ec'P OF OCCURPENCES XX>. PERCENT OCCURRENCES 1 Totals below are given in hours percent for wind frequency by sectors.
g, ST LUCRE UNIT NO 1-ODCH
APPENDIX B Limited Analysis Dose Assessment for Liquid Radioactive Effluents The radioactive liquid effluents for the years 1978, 1979> and 1980 were evaluated to determine the dose contribution of the radionuclide distribution. This analysis was performed to evaluate the use of a limited dose analysis for determining environmental doses. Limiting the dose calculation to a few selected radionuclides that contribute the majority of the dose provides a simplified method of determining compliance with the dose limits of Technical Specification 3.11.1.2.
Tables B-l and 8-2 present the results of this evaluation.
Table B-1 presents the fraction of the adult total body dose contributed by the major radionuclides. Table B-2 presents the same data for the Adult GI-LLI dose. The adult total body and adult GI-LLI were determined to be the limiting doses based on an evaluation of all age groups (adult, teenager, child, and infant) and all organs (bone>
liver, kidney, lung> and GI-LLI). As the data in the tables show, the radionuclides Fe-59, Co-58> Co 60> Zn 65> Cs 134> and Cs-137 dominate the total body dose; the radionuclides, Fe-59> Co-58, Co-60> Zn-65> and Nb-95 dominate the GI-LLI 'dose. In all but one case (1979 fish, GI-LLI dose) these radionuclides contribute 901 or more of the total dose. If for 1979 the fish and shellfish pathways are combined as is done to determine the total dose> the contribution from these nuclides is 84% of the total GI-LLI dose.
Therefore> the dose commitment due to radioactive material in liquid effluents can be reasonably estimated by limiting the dose calculation to the radionuclides, Fe-59, Co-58, Co-60> Zn-65> Nb-95>
Cs-134> a6d Cs-137, which cumulatively contribute the majority of the total dose calculated by using'll radionuclides detected. This limited analysis dose assessment method is a simplified calculation that provides a reasonable evaluation of doses due to liquid radioactive effluents.
ST LUCRE UNlT NO 1-ODCM
Page 82 of Tritium is not included in the limited analysis dose assessment for liquid releases because the potential d'ose resulting from normal reactor releases is negligible and is essentially independent of radwaste system operation. The amount of tritium releases annually is about 300 curies. At St. Lucie, 300 Ci/yr releases to the Atlantic
-7 Ocean produces a calculated whole body dose of 5 x 10 mrem/yr via the fish and shellfish pathways. This amounts to less than 0.001%
of the design objective dose of 3 mrem/yr. Furthermore> the release of tritium is a function of operating time and power level and is essentially unrelated to radwaste system operation.
ST LUCIE UNIT NO .1-ODCM
Page M of Table B-l Adult Total Body Dose Contr.ibutions t f Fr ac ion o To ta1 1978 1979 1980 Radionuclide Fish Shellfish Fish Shellfish Fish Shellfish Co-58 0. 08 0. 27 0;06 0. 28 0. 02 0.05 Co-60 0.05 0. 19 0. 03 0. 15 0. 20 0.44 Fe-59 0. 10 0.25 0. 04 0. 13 0. 15 0.22 Zn-65 0.01 0. 10 0.02 0. 19 0.04 0.20 Cs-134 0.31 0. 07 0.46 0. 14 0.27 0.04 Cs-137 0.42 0. 10 0.38 0. 11 0.30 0.04 Total 0.97 0. 98 0.99 1. 00 0.98 0.99 Table 8-2 Adult GI-LLI Dose Contribution Fraction of Total Rad ionuc 1 ide'978 Fish She 1lfish Fish 1979 Shellfish Fish 1980 Shellfish Co-58 0. 03 0.36 0. 25 0.44 0. Ol 0. 07
,Co-60 0.02 0.23 0. 12 0.22 0.05 0.57 Fe-59 0.03 0.31 0. 16 0. 19 0.04 0. 29 Zn-65 0.01 0. 02 0. 01 0. 05 0. 01 0. 04 Nb-95 0. 89 0.01 0. 21 0. Ol 0. 88 0. 01 Total 0.98 0.92 0. 75 0. 90 0. 97 ,0. 97 ST LUG IE UNIT NO 1-03CVi
Page 8+ of APPENDIX C Technical Bases for Effective Dose Factors Overview The evaluation of doses due to releases of radioactive material to the atmosphere can be simplified by the use of effective dose transfer factors instead of using dose factors which are radianuclide specific. These effective factors, which are based on the typical L
radionuclide distribution in the releases, can be applied to the total radioactivity released to approximate the dose in the environment, ie, instead of having to sum the isotopic distribution multiplied by the isotope specific dose factor only a single multiplication (K f, M ff or N f) times the total quantity of radioactive material released) would be needed. This approach provides a reasonable estimate of the actual dose while eliminating the need for a detailed calculational technique.
Determination of Effective Dose Factors The effective dose transfer factors are based on past operating data. The radioactive effluent distribution for the past years can be used to derive single effective factors by the following equations.
K ff = K. . f.
where K ff =
eff the effective total body dose factor due to gamma emissions from all noble gases released i
K. the total body dose factor due to gamma emissions from each noble gas radionuclide i released the fractional abundance of noble gas radionuclide i is of the total noble gas radionuclides ST LUCIE UNIT NO 1-ODCM
Page ~ of (L + 1.1 M) eff (L. + 1.1 H.)
~
i .
~ f.i i
where (L + 1.1 M) eff = the ff effective skin dose factor due to beta and gamma emissions from all noble gases released (L + 1.1 M i.) = the skin dose factor due to beta and gamma emissions from each noble gas radionuclide i released eff ) M.. i f.i i
where M ff =
eff the effective air dose factor due to gamma emissions from all noble gases released M.
i = the air dose factor due to gamma emissions from each noble gas radionuclide i released
= (C-4)
N P N.
where N ff =
eff the effective air dose factor due to beta emissions from all noble gases released N.
i = the air dose factor due to beta emissions from each noble gas radionuclide i To determine the appropriate effective factors to be used and to evaluate the degree of variability, the atmospheric radioactive effluents for the past 3 years have been. evaluated. Tables C-1 and, C-2 present the results of this evaluation.
As can be seen from Tables C-1 and C-2i the effective dose transfer factors v'aries little from year to,year. The variability from the average value is 18%. This maximum'bserved variability is minor considering other areas of uncertainty and conservatism inherent in the environmental dose calculation models.
ST LUCIE UNIT NO 1-ODCN
Page86 of To provide an additional degree of conservatism, a factor of 0.8 is introduced into the dose calculation . process when the effective dose transfer factor is used. This added conservatism provides additional assurance that the evaluation of doses by the use of a single effective factor will not significantly underestimate any actual doses in the environment.
Reevaluation The doses due to the gaseous effluents are evaluated by the more detailed calculation methods (ie, use of nuclide specific dose factors) on a yearly bases. At this time a comparison can be made between the simplified method and the detailed method to assure the overall reasonableness of this limited analy'sis approach. If this comparison indicates that the radionuclide distribution has changed significantly causing the simplified method to underestimate the doses by more than 20%> the value of the effective factors will need to be reexamined to assure the overall acceptability of this approach. However> this reexamination will only be needed if the doses as calculated by the detailed analysis exceed 50% of the design bases doses ( ie> greater than 5 'mrads gamma air dose or 10 mrads beta.air dose).
In any case> the appropriateness of the Aeff value will be periodically evaluated to assume the applicability of a single effective dose factor. for evaluating environmental doses.
ST LUCIE UNIT NO 1-ODCM
Page 8~ of Table C-l Effective Dose Factors Noble Gases Total Body and Skin Doses Year .Total Body Effective Skin Effective Dose Factor Dose Factor eff (L+l. 1M) eff 3 3 mrem-m mrem-m Ci- r QCi- r 2 3 1978 7.3 x 10 1.4 x 10 2 3 1979 7.4 x 10 1.4 x 10 2 3 1980 5.6 x 10 1.2 x 10 2 3 Avg 6.8 x 10 1.3 x 10 ST LUClZ UNIT NO 1-ODCN
Table C-2 Effective Dose Factors Noble Gases Air Doses Year Gamma Air Effective Beta Air Effective Factor-M eff Dose Factor-N
, Dose ff ff eff mrad-m mrad-m Ci- r Ci- r 1978 8.0 x 10 2
1.2 x 10 3 1979 8.0 x 10 2
1.2 x 10 3 1980 6.2 x 10 2
1.2 x 10 3 Avg 7.4 x 10 2
1.2 x. 10 3 ST LUCIZ UNIT NO 1-ODCM
APPENDIX D Technical Bases for Eliminating Curie Inventory Limit for Gaseous Waste Storage Tanks The NRC Standard Technical Specifications include a limit for the amount of radioactivity that can be stored in a single waste gas storage tank. This curie inventory limit is established to assure that in the event of a tank failure releasing the radioactivity to the environment the resulting total body dose at the site boundary would not exceed 0.5 rem.
For St. Lucie, the inventory limit in the waste gas storage tank has been determined to be approximately 285,000 curies (Xe-133, equivalent). An allowable primary coolant radioactivity concentration is established by the Appendix A Technical Specifications which limits the primary coolant radioactivity concentrations to 100/E with E being the average energy of the radioactivity in Mev. This equation yields an upper primary coolant gross activity limit of about 160 pCi/ml. By applying this activity concentration limit to the total liquid volume of the primary system, a total activity limit can be determined. For St. Lucie the primary system volume is about 70> 000 gallons, which yields a limiting total inventory of approximately 43>000 Ci.
By assuming a typical radionuclide distribution an equivalent Xe-133 inventory can be determined. Table D-1 provides the typical radionuclide (noble gases) distribution and the Xe-133'quivalent Concentration. The equivalent 'concentration is determined by multiplying the radionuclide concentration by the ratio of the nuclide total body dose factor to the Xe-133 total body dose factor.
Summing all the individual radionuclide equivalent concentrations provides the overall reactor coolant Xe-133 equivalent concentration.
The data show that the equivalent concentration is a factor of 2 larger than the gross concentration (ie, 24 pCi/gm total versus 47 pCi/gm equivalent. The resulting Xe-133 equivalent curie inventory of the reactor coolant system is approximately 86,000 Ci.
ST LUCIE UNIT NO 1-OICM
1>
Page 90 of Therefore, even if the total primary system at the maximum Tech Spec allowable concentration was degassed to a single waste gas decay tank> the tank cur'ie inventory would be well below the 285> 000 Ci limit. Based on this evaluation, the curie inventory limit on a single wastegas storage tank 'nas not'een j.QcluQed. 8S a Tecgnicai Specification requirement.
ST IUCIE UNIT NO.I-ODCM
II
'0 '
I
~y i Page 91 o f Table D-1 Reactor Coolant Xe-1.33 Effective Concentration Radionuclide Reactor Coolant+ Reg Guide 1.109 Ratio Xe-133 Concentration 'i'Zotal .Body DP. 'TB DP Effective
. (pCi/gm) mreml . X.e-133 DP. 'oncentration
( Cil ra Kr-85m 0. 19 1.2 x 10 4.1 0.78 Kr-85 0. 83 1.6 x 10 "0;06 0. 05 Kr-87. 0. 16 5.9 x 10 20. 3.2 Kr-88 0. 31 ~ 1.5 x 10 16.
Xe-131m 8.8 9.2 x 10 0. 32 2.8 Xe-133m 0.20 2.5 x 10 0.86 0 17 Xe-133 12 2.9 x 10 1.0 12.
Xe-135m 0. 11 3.1 x 10 1.2 Xe-135 1.2 1.8 x 10 '.2 Xe-137 0. 02 1.4 x 10 4.8 Xe-138 O. 12 8.8 x 10 30. 3.6 Total 24. : 47 k
Data adapted from the NRC GALE Code ST LUClE UNIT NO 1-ODCM