ML20087L174
| ML20087L174 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 03/08/1984 |
| From: | PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20087L167 | List: |
| References | |
| PROC-840308-01, NUDOCS 8403270067 | |
| Download: ML20087L174 (41) | |
Text
,. . _ ,
2840010450 Ottsite Dose Calculation Manual Peach Bottom Atomic Pow >sr Station Units 2 nnd 3 Philadelphia Electric Company Docket Nos. 50-277 6 50-278 3
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Table of Contents 2840010450 I. Purpore II. -Instrument Setpoints III. Liquid Pathway Dose Calculations A. Liquid Radwaste Release Flow Rate Determination B. Surveillance Reguirement 4.8.B.2 C. Surveillance Requirement 4.8.B.4a IV.- Gaseous Pathway Dose Calculations A. Surveillance Requirement 4.8.C.1 B. Surveillance. Requirement 4.8.C.2 C. Surveillance Requirement 4.8.C.3 D. Surveillance Requirement 4.8.C.Sa V. Nuclear Fuel Cycle Dose Assessment - 40 CPR 190 A. Surveillance Requirement 4.8.D VI. Calendar Yea r Dose Calculations A. Unique Reporting Requirement 6 . 9 . 3 .' 2
. VII. Radiological Environmental Monitoring Program A. Surveillance Requirement 4.8.E VIII. Bases O
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Rev. 0 2840010450 1.- Purpose-The purpose of the offsite Dose Calculation Manual is to establish methodologies and. procedures for calculatine doses to individuals in, areas at and beyond_the SITE BOUNDARY due ' to . radioactive ef fluents f ron Peach Bottos Atomic Power Station. The results of these calculations
_are: required to_ determine compliance with. Appendix A to
. ' Operating Licenses DPR-44 and DPR-56, " Technical Specification and Bases for Peach Botton Atomic Power Station Units No. 2 and 3".
II . - Setpoint-Determination for Liquid & Gaseous Monitors iA. Liquid Radwaste Activity Monitor Setpoint Each-tank of radioactive vaste is sampled prior to
- . release. A small liquid volume of this sample is
. analyzed for gross gamma (well count) activity. This analysis'is performed in a NAI well counter. This well counter has a counting efficiency similar to the liquid radwaste discharge aross activity monitor. The well counter and' liquid radwaste discharge gross activity monitor are. calibrated against the same liquid. radioactivity 1 source in the geometry to be used by each detector. An ef ficiency is deterniined f or each radwaste tank to be released. Exceeding the expected responde would indicate that an incorrect sample had been obtained for that release and the release is automatically stopped.
S.P. =: (Net CPM /ml(well) _ X Ef f W/RW) + Background CPS
- S.P.. = Liquid Radwas'te gross activity monitor setpoint in CPS Net CPM /ml(well) = gross gamma activity for the radwaste sample tank determined by the well counter.
EfffW/hW = conversion factor between well counter and
-liquid radwaste gross-activity monitor (CPS (R/W monitor) . CPM /ml (well) ) .
Lackground. CPS = Background reading of the liquid radwaste gross activity monitor
. (CPS).
Rev. 0 2840010450 The alarm and trip pot setooints for the liquid radwaste activity monitor are determined from a calibration curve f or. the alarm pot and trip pot. The alarm pot setting includes a factor of 1.25 to allow for analysis error, pot setting error, instrument error and calibration error. The trip pot setting includes a .f actor of 1.35 to allow for analysis error, pot setting error, instrument error and calibration error. The flow rate determination includes a margin of assurance which includes consideration of these errors such that the instantaneous release limit of 10 CFR 20 is not exceeded.
B. Liouid Radwaste Release Flowrate Setpoint Determination The trip pot setpoint for the liquid radwaste release flowrate is determined by multiplying the liquid radvaste flowrate determined above by 1.2 and using this value on the appropriate calibration curve f or the discharge flow meter to be used. The Peach Bottom radwaste system has two flow monitors (high flow (5 to
'300 gpm) and low flow (0.8 to 15 qpm) ) . The factor of 1.2 allows for pot' setting error and instrument error.
The flow rate determination includes a margin of assurunct which includes consideration of this error such that the instantaneous release limit of 10 CFR 20 is not exceeded.
C. Setpoint Detern.ination f or Gaseous Radwaste The high and high-high alarm setpoints f or the main stack radiation monitor, Unit 2 roof vent radiation monitor and Unit 3 roof vent radiation monitor are determined as follows:
High Alarm - the high alarm setpoint is set at approximately 3 x the normal monitor reading.
High-Hioh Alarm - the high-high alarm setpoint is set at a release rate from this vent of aoproximately 30% of the instantaneous release limit of 10 CPR 20 as specified in Technical Specification 3.8.C.1.a for the most
, restrictive case (skin or total body) on an unidentified basis.
To determine these setpoints 28400104$0 solve the gaseous effluent dose rate equations in section IV.A.
of the ODCM to determine what main stack' release rate and roof vent release rate will produce rate of 150 mrem /yr and a dose rate of 900 mrem /yr to the skin (30% of the limit of 3000 arem/yr) from each release point. Using the smallest (most restrictive) release rate for each release point determine monitor response required to produce this release rate assuming.a normal vent flow rate and pressure correction factor. Set the high-high alarm for approximately this monitor response.
D. Setpoint Determination for Gaseous Radwaste
- Plow Monitorc
- The alarm setpoints for the main stack flow monitor is an followc:
f Low Flow Alarm '10,000 0FM. - This setting insures that the main stack minimum dilution flow as specified in Technical Specification 3.8.C.4.a is maintained.
The alarp.'setpoints for the root vent flow monitors are as f'ollows:
5 Low Flow Alarm - 1.5 x 10 cfm 5
High Flow Alarz - 5.4 x 10 cfm III. Qu id - Pa th wa y Dose Calculations A. Liquid Radtacte Release Flow Hate Determination Peach Bottom Atomic Power Station Units 2 and 3 have The
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one.comc.on discharge point for liquid releases.
.following calculation assures that the radwaste
. - release lisits'are. met.
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Rev. O 2'8'40010450
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The flow rate of liquid radwaste released from the site.to areas at and beyond the SITE BOUNDARY shall be such that.the concentration of-radioactive material
- aft'er dilution shall be limited to the concentration specified in 10 :0FR 20.106 (a) for radionuclides other
- than' noble gases and 2X10E4 uCi/ml total activity i concentration for all. noble gases as specified in Technical Specif', cation 3.8sB.1. Each tank of 3
radioactive vaste is-sampled-prior to. release and is
. guantitatively analyzed for identifiable gamma emitters as specified in Table 4.8.1 of-the Technical: ,
- Specifications. - From.this gamma isotopic analysis the r
- maximum . permissible. release flow rate is determined as follows:
Determine a_ Dilution Factor by:
L . Dilution Factor =
] uCi/ml MPC1 i . i ^ uCi/ml i'= the. activity.of each identified ; gamma emitter in~uci/ml
' MPCi = The MPC specified in 10'CPR 20, Appendix ,
B, Table II, Column 2 for radionuclides
-4 other than noble gases or 2 X 10' uCi/s.1
- tor-_ noble gases.
' Datermine the Maximum Permis.eible Release Rate with this Dilution ~ Factor by:
- i' 5
Release Rate _ (gpn) = A ' Y 2.0- Y 10 . B X Dilution Factor A = The' number of circulating-water pumps running which will provide' dilution 5' 2.0 X'10- -
= the flow rate in opm for each circulating water pump running B = margin of assurance.which includes consideration of the maximum. error in the activity -~setpoint ,: the ma ximum error in -the flow setpoint, . and . possible loss of 5 out of the 6 2*' possible circulating water ~ pumps during'a
. . release. The value used for B is 10.0
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'fr eo seau- % 9 9 ( e4 ys syes'tegei- e-wT ofprii mg gg- ty . wee *.g- ymyeye pqg+ y.-ourge- y g .- g:- gf---i twy-pveT#'=e-etam-"y - p +pM rpy* y y 7 *F'
2840010450 nev. o B. Surveillance Requirement 4.8 B.2 Dose con tributions f rom liqui,d ef fluents released to areas at and beyond the SITE SOUNDAltY shall be calculated using the equation below. This dose
. calculation uses those. appropriate-radionuclides listed in Table III.A.1. These radionuclides account for virtually 100. percent of the total body dose and bone- dose f rom liquid ef fluents.
k r-e
- n bM 4
-k 4
2840010450 Rev- 0 D -= b A j' at C F i ., i 1 = 1- 1 11 1J where: D = the cumulative dose commitment to the total body or any organ,[T", from liquid effluents for the total time period m , in mrem 3E 4t 1= 1 1 4t = the length of the 1th time period over which 1 C and F are averaged for the liquid release, i1 1 in hours. C = The average concentration of radionuclide, i, in 11 undiluted liquid , effluent during time period At from any liquid release, (determined by the effluent sampling analysis program, Technical specification Table 4.8.1) , in uCi/ml. A = the site related incestion dose commitment i factor to the total body or organ,J7', for each radionuclide listed in Table III.A.1, in erem-al per hr-uci. See Site. Specific Data.** P = the near field' average dilution factor f or 1 C during any liquid effluent release. Defined
'il as the ratio of the maximun undiluted liquid waste flow during release to the average flow from the discharge structure to Conowingo Pond.
III.C Surveillance Requirement 4.8.B.4a Projected done contributions from liquid effluents shall be calculated using the methodology described in section III.B. l
* * ~ See - Note 1 in Bases 6- -
. . . Bev. 0 r-284bD10450
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TABLE III.A.1
-M QUID EPFLUENT INGESTION DOSE FACTOkS (Decay Corrected)
A 7 Done Factor (mrem-ml per hr-uci) i Radionuclide Total Body Bone 5 5 Cs-137 3.98x10 4.44x10 5 5 Cs-134 6.74x10 3.47x10 4 5 P-32 5.93x10 3.28x10 4 4 Cs-136 9.83x10 3.45x10 4 4 2n 3.87x10 2. 6 9 x 10 5 5 Sr-90 1.88x10 7.67x10 0 0 11 - 3 2.13x10 2.13x10
- 2 2 Na-24 2.24x10 4.41x10 2 2 1-131 1.86x10 2. 28x 10
, 2 2 Co-60 7.40x10 7. 40x 10
- 2 2 I .133 1.97x10 2.28x10 2 2 Fe-55 1.31x10 8.12x10 2 4 Sr-89 8. 83 x.10 3. 08x 10 3 4 Te-129m 2.01x10 1.27x10
'2 2 ,
Mn-54 9.82x10 9.82x10 2 2 Co-58 2.59x10 2.59x10
- 3 3 Fe-59 1.14x10 1.26x10 2 3 Te-131m 4.57x10 1.12x10 1 2
.. B a - 1.4 0 3.66x10 5.57x10 3 3 Te- 13 2 1'. 4 0x 10 2.29x10
- 2840010450 3,y, o
' NOTE:- The listed.done. factors are for radionuclides that may be detected;in ' liquid ef fluents and have significant dose conrequences. ~ Thece f actors _ are decay:yd f or one day to account for the tis.e between effluent release and ingestion of fish by the maximum exposed individual.
'
- There.is.no bone dose factor given in R.G. 1.109 for these nuclides.
Theref ore,- the whole body dose f actor was used. S e 8-
nov. o 2840010459 IV. Gaseous Pathway Dose Calculations A. Surveillance Reauirement 4.8.C.1 Tne dose rate in areas at and beyond the SITE BOUNDARY due to radioactive materials released in gaseous effluents shall be determined by the expressions below:
- 1. Noble Gases:
The dose rate from radioactive noble gas releases shall be determined by either of two methods. Method (a) , the Gross Release Method, assumes that all noble gases released are the most limitino nuclide - Kr-88 for total body dose'and Kr-87 for skin dose. Method (b) , the Isotopic Analysis Method, utilizes the results af noble gas analyses required by specification 4.8.C.1a. For normal operations, it is expected that method (a) will be used. However, if noble gas releases are close to the limits as calculated by method (a ) , method (b) can be used to allow more operating flexibility by using data that more accurately reflect actual releases.
- a. Gross Release Method D =Vh +K (X/0) b TS NS V NV D =
(L- (X/Q) + 1.1 B) Q + (L + 1.1 M) (X/0) -Q s- s NS NV where: The location is the site boundary, 1097m SSE from the vents. This location results in the highest calculated dose to an individual from noble gas releases. - D = total body dose rate, in aren./yr. TB D = skin dose rate , in crem/yr. s
-9_
c -
2840010450 .
-4 V = 4.72 X 10 mrom/yr per uCi/sec; the constant for Kr-88 accountina-for the gamma radiation trom the elevated'iinite plume. This constant was developed using MARE program with plant specific inputs for PBAPS.
h = the gross release rate of noble gases from the NS stack determined by gross activity stack
. monitors averaged over one hour, in uCi/sec.
4 3 K- = 1.47 X'10 mres/yr per uCi/m ; the total body dose f actor due to camma emissions f or Kr-88 (Reg Guide 1.109, Table B-1) .
-7 3 (X/Q) = 5.33 x 10 sec/m ; the highest calculated v annual avprage relative concentration for any area at or beyond the SITE BOUNDARY for all vent releases.
h = the gross release rate of noble gases in gaseous NV efiluents.from vent releases determined by gross activity vent monitors averaged over one hour, in uci/sec. 3 3 L- = 9.73 x 10 mrem /vr per uCi/m ; the skin dose . factor due to beta emissions for Kr-67. (Reg Guide 1.109, : Ta ble B-1) .
-8 3' (X/Q) = 9.97 x 10 sec/m.; the highest calculated s annual average relative concentration from the stack releases for any area at or beyond the SITE BOUNDARY. ,
4 B = 1.74 x 10 mrad /yr per uCi/sec; the constant for Kr-87 accounting for the gamma radiation trom the elevated ~ finite plume. This constant was ceveloped-using MARE program with plant specific ' inppts for PBAPS. ... 3 3 M = 6.17 x 10 mrad /yr per uCi/m ; the air dose factor due to gamma emissions 1or Kr-87.
.(Reg Guide 1.109, Table B- 1) .
2840010450
- b. Isotopic Analysis Method D =25(V h +K (X/0)
V h) iv TB i i is i D = JE (L (x/0) + 1.1B ) O + (L + 1.1M ) (X/Q) s i a- i s i is i i V where: The location is the site boundary,1097m SSE f rom the vents. This location results in the highest calculated dose to an individual from noble gas releases. D = total body, dose rate, in mrem /yr. TB D = skin dose, in nres/yr. S V = the constant for each identified noble gas i radionuclide for the gamma radiation trot the elevated finite plume. The constants were developed usino the MARE program with plant specific inputs for PBAPS. Values are listed on Table III.A., in mrem /yr per uCi/sec. b = the release rate of noble gar radionuclide, is i, in gaseous effluents from the stack determined by isotopic analysis-averaged over one hour, in uti/sec. K = the total body dose factor due to gamma i emissions for each' identified noble gas radionuclide. Values are listed on Table IV.A., 3 in area /yr per uCi/m .
-7 3' (520) = 5.33 x 10 sec/m ; the highest calculated v annual average relative concentration for any area at or beyond the SITE BOUNDARY for all' vent releases.
O
Rev. O
~
2840010450 . ih = the release rate of noble gas-radionuclide, iv i, in gaseous effluents from all vent releases determined by isotopic analysis averaged over one hour, in-uci/sec. L = the skin dose factor due to beta emissions i for each identified noble gas radionuclide. Values are listed on Table IV.A., in 3 mrem /yr per uCi/m .
-8 3 (X/0) = 9.97 x 10 sec/m ; the highest calculated s annual average ; elative concentration from the stack releases for any area at or beyond the SITE BOUNDARY.
B = the constant for each identified noble gas i radionuclide accounting for the gamma radiation from the. elevated finite plume. The constants were developed using MARE program with plant specific inputs f or-PBAPS. Values are listed on Table IV.A., in-mrad /yr per uti/sec. M = the air dose factor due to gamma emissions i for_each identified noble gas radionuclide. Values are listed on Table IV.A, in trad/yr 3 per uCi/m . 1.1 = unit conversion, converts ai dose to skin dose, mrem / mrad. 4 - > .as 2840010450 aev. O TABLE IV.A - Constants for Isotopic Analysis Method (corrected for decay durina transit) Total Plume-Body Skin Gamma Beta Air Body Plume-Air' Dose Dose Air Dose Dose Dose Dose Factor Factor Factor Factor Factor Factor ~B K L M N Y i i i i i i (m ra d/yr . (arem/yr (ares /yr (trad/yr (mrad /yr (mrad /yr per per per per per per-Radionuclide uCifsec) uCi/m#1 uCi/s 8), uCi/m 31- fuci//) uCi/sec) Kr-87 1.74E-04 5.92E+03 9.73E+03 6.17E+03 1.03E+04 1.66E-04 Kr 3 .15 E- 0 4 1.47E+04 2.37E+03 1.52E+04 2.93E+03 4.72E-04 Xe-133 -1.19E-05 -2.94E+02 3.06E+02 3.53E+02 1.05E+03 1.11E-05 Xe-133m 1.09E-05 2.51E+02 9.94E+02 3.27E+02 1.48E+03 1.01E-05 Xe-135 _6.37E-05 1.61E+03 1.86E+03 1.92E+03 2.46E+03 5.95E-05 Xe-135m 6.61E-05 2.53E+03 5.76E+02 2.72E+03 5.99E+02 6.17E-05 Xe-138- 1.52E-04 7.33E+03 3.43E+03 7.54T+03 3.94E+03 1.46E-04
~
~ ~'h e v o l u e r K , L~, M , and N bre taken from Reg Guide 1.109,
-i i i i Table B-1. The values E and V were develooed using the MARE i i program with plant. specific inputs for PSAPS.
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2840010450 aev. o
- 2. Iodine-131, .Iodire-133, tritium and radioactive materials in particulate form, other than noble gases, with' half-lives areater than eight days:
D = (CP) P W h +W h
; I_ S Is v Ivj where:
The location is the site boundary, 1097m SSE from the vents. D = dose rate to the thyroid, in mrem /yr. T CF = 1.09; the correction factor accounting for the use of iodine-131 in lieu of all radionuclides released in gaseous effluents-including Iodine-133. 7 3 P = 1.484 x 10 ~ arem/yr per uCi/m ; the dose I parameter 1or I-131 via the inhalation
-pathways. The dose f actor is based on the critical individual organ, thyroid, and most restrictive age group, child. All values are-fror Reg. Guide 1.109 (Tables E-S and E-9) .
-7 3 W = 1.03 x 10 sec/m ; the highest calculated S annual average relative concentration f or any area at or beyond the SITE BOUNDARY from stack releases. (SSF boundary) h = the release rate of iodine-131 in gaseous
'IS effluents from the stack determined by the effluent sampling and. analysis program (Technical Specitication Table 4.8.2) in uci/sec.
-8 3 W = 2.31 x 10 sec/m ; the highest calculated v annual average relative concentration f or any area at or beyond the SITE BOUNDARY for <
-all vent releases (SSE boundary) h = the release rate of iodine-131 in gaseous
'. IV effluents froc. all vent releases, determined by'the effluent samplino and analysis procra:. (Technical Specification Tabic 4.8.2) in uCi/sec.
Rev o 2840010450 . IV.B Surveillance Requirement 4.8.C.? The air dose in areas at and beyond the SITE BOUNDARY due to noble gases released in gaseous eftluents shall be determined by the-expressions below. 7he air dose shall be determined by either of two methods. Method (a) , the Gross helease Method, assumes that all noble gases released are the most limiting nuclide - Kr-88 for gamma
-radiation and Kr-87 for beta radiation. Method (b) , the Isotopic Analysis Method, utilizes the results of noble gas analyses required by specification 4.8.C.1a.
~
For normal operations, it is expected that Method (a) will be used. However, it noble gas releases are close to the limits as calculated by Method (a) , Method (b) can be used to allow more onerating flexibility by using data that more accurately reflect actual releases.
- 1. for gamma radiation:
a) Gross T.elease Method
-8 --
___ _ _t D. = 3.17 x 10 (M (X/0) 0 + B0) 1- v v s_ vhere: The location is the SITE BOUNDARY 1097m SSE from the vents. This location results in the hiahest calculated gamaa air dose from noble gas releases. D =-gamma air dose, in mrad.
-8 3.17 x 10 = years per second.
4 3 M = 1.52 x 10 mrad /yr per uci/m ; the air dose factor due to gamma emissions for Kr-88. (Reg Guide 1.109, Table B-1)
-7 3 (X/0) = 5.33 x 10 sec/m : the highest calculated V annual average relative concentration
~from vent releases for any area at or beyond the SITE BOUNDARY.
15 -
2840010450 . 0 = the gross release of noble gas y radionuclides in gaseous effluents from all vents, determined by gross activity vent monitore, in uCi. Releases shall be cumulative over the calendar quarter or year as appropriate.
-4 LB = 3.15 at 10 mrad / year per uCi/sec; the constant for Kr-88 accounting for the gamma radiation trom the elevated finite plume.
The constant was developed using the MARE program with plant specific inputs for PBAPS. 0 = the gross release of noble gas radionuclides in caseous releases f rom the stack determined by gross activity stack monitor in uti. Releases shall be cumulative over the calendar guarter or year as approoriate. b) Isotopic Analysis Method
-8 - ->
= 3.17 x 10-25 n (X/0) 0 +B 0 D[
i i v iv i is J where: The location is the. SITE BOUNDARY, 1097m SSE from the vents. -This location results in the highest calculated gamma air dose from noble gas releases. D = gamma air _ dose, in mrad.
-8 3.17 x 10 = years per second.
M = the air dose factor due to gamma emissions i for.each identified noble gas radionuclide. Values are listed on Table III.A, in mrad /yr 3 per uti/m . S _ . - - , ,, ~,.
Rev 2840010450 0
-7 3 (X/0) = 5.33 x.10 sec/m ; the highest calculated V average relative concentration from vent releases for any area at or beyond the SITE BOUNDARY.
0 = the release of noble gas radionuclides, i, iV in gaseous effluents from all vents as determined by isotopic analysis, in uCi. Releases shall be cumulative over the calendar guarter or year, as appropriate. B = the constant for each identified noble gas i radionuclide accounting for the gamma radiation for the elevated finite plume. The constants were developed using the MARE program with plant specific inputs for PBAPS. Values are listed on Table IV.A, in mrad /yr per uCi/ roc. 0 = the release of noble gas radionuclides, i, ir in gaseous erfluents from the stack determined by isotopic analysis, in uCi. Releases shall be cumulative over the calendar guarter or year, as appropriate.
- 2. f or be t a radiation:
a) Gror.s Release Method
-8 F~ t D = 3.17 x 10 N (X/Q) 0 + (X/Q) 0 sd - y v s s_
where: The location is the SITE BOUNDARY 1097m SSE from the vents. This location results in the hichest calculated gamma air dose from noble gas releases. D = beta air doce, in mrad. g
-8 3.17 x 10 = years per.second.
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~
2840010450 aev o 4 3 N = '1.03 x 10 mrad /yr per uCi/m ; the air dose factor due to beta emissions for Kr-87. (Reg Guide 1.109, Table B-1)
-7 3 (X/0) = 5.33 x 10 sec/m ; the highest calculated y annual average' relative concentration from vent releases for any area at or beyond the 3ITE BOUNDARY.
0 = the gross release of noble gas v radionuclides in caseous effluents from all vents determined by gross activity vent monitors, in uCi. Releases shall be cumulative over the calendar guarter or year, as appropriate.
-8 3 (X/0) = 9.97 x 10 sec/m ; the highest calculated s annual averace relative concentration from the stack releases for any area at or beyond the SITE BOUNDARY.
0 = the gross release of noble cas u radionuclides in caseous releases fror, the stack determined by gross activity stack monitors, in uCi. Releases shall be cumulative over the calendar quarter or year, as appropriate. b) Isotopic Analysis Method
-8 D = 3.17 x 10 2$ N Q + (X/0) 0 d i i L (X/Q) v iv s is ,
-8 '
- . 3.17 x-10 = years per second.
N = the air dose factor due to beta i emissions for each identified noble gas radionuclide. Values are listed 3 on Table IV.A, in mrad /yr per uCi/m . b_
Rev. O
-7 3 2840010450 (X/0) = 5.33 x 10 sec/m ; the highest calculated v annual average relative concentration from vent releases for any area at or beyond the SITE BOUNDARY.
0 = the release of nchle gas radionuclide, i, iv in gaseous effluents from all vents as determined by isotopic analysis, in uCi. Releases shall be cumulative over the calendar guarter or year, as appropriate.
-8 3 (X/0) = 9.97 x 10 sec/m ; the highest calculated s annual average relative concentration from the stack releases for any area at or beyond the SITE BOUNDARY.
0 = the release of noble ggs radionuclide, i, is in gaseous effluents from the stack as determined by isotopic analysis, in uti. Releases shall be cumulative over the calendar quarter or year, as appropriate. I V . ". - Lurvsil..ance Requirement 4.8.C.3 The_ dose to an individual from Iodine-131, Iodine-133, tritium and radioactive materials in particulate form and radionuclides other than noble gases with half-lives creater than eight days in gaseous _etiluents released to areas at and beyond the SIIE DOUNDARY shall be determined by the following expression:
-8 r _ _
D = - 3 .17 x 10 (CF) (0.5) R EO +W0 S IS y IV where: Location is the critical pathway dairy 2103m SSW from vents. D = critical organ dose, thyroid, from all pathways, in mrem.
-8 3.17.x 10 = years'per second.
CF = 1.09; the correction factor accounting for the .use of Iodine-131 in lieu of all radio-nuclides released in gaseous effluents including 19 -
T _ 2840010450 8 - Iodine-133. l~ , O
2840010450 nev- 0 0.5 = fraction of iodine releases which are nonelemental. 11 2 R = 2.61 x 10 m (mrem /yr) per uti/sec; the dose factor for Iodine-131. The dose factor is based on the critical individual organ, thyroid, and most restrictive age group, infant. See site Specific Data.**
-10 -2 W = 4.95 x 10 meters ; (D/Q) for the food s pathway for stack releases.
0 = the release of Iodine-131 from the stack IS determined by the effluent sampling and analysis program (Technical Specification Table 4.8.2) , in uCi. Releases shall be cumulative over the calendar guarter or year, as anpropriate. _ g. -2
.W = 1.14 x 10 met ers ; (D/Q) for the food v- pathway for stack releases.
0 = the release of Iodine-131 determined by the IV effluent samplina and analysis program (Technical Specifica tion Table 4.8.2) , in uci. Releases shall be cumulative over the calendar guarter or year, as appropriate. IV.D S u r v eill a n_ce_ Req ui rem o n t 4.8.C.5a The. projected doses f rom releases of gaseous effluents to areas at and beyond the SITE BOUNDARY shall be calculated in accordance with the following sections of this manual:
- a. gamma air dose - IV .B.1
- b. beta air dose - IV.B.2
- c. - organ dose - IV.C The projected dose calculation shall be based on expected release from plant operation. 7he normal release pathways
.. result 'in the maximum releases f rom the plant. Any alternative release pathways result in lower releases and therefore lower doses.
** Sec Note 2 in basec
- 21 -
sev. 0 2840010450 v.A surveillance heQuirement 4.8.D If the doses as calculated by the equatione in this manual do not exceed the limits given'in Technical Specifications 3.8.B.2, 3.8.C.2, or 3.8.c.3 by more than two times, the conditions of Technical Specification.3.8.D have been met. It the doses as calculated by the equations in this manual exceed the limits given in Technical Specifications 3.8.B.2, 3.8.C.2, or 3.8.C.3 by more than two times, the maximum dose or dose commitraent to a real individual shall be determined
- utilizing the methodology provided in Regulatory Guide 1.109,
" Calculation of Annual Doses to Man f rom Routine Releases of Reactor Ef fluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I", Revision 1, October 1977. Any deviations f rom the methodology provided in Regulatory Guide 1.109 shall be documented in the Special Report to be prepared in'accordance with Technical Specification 3.8.D.
The cum'ulative dose contribution f rom direct radiation from the two reactors at the_ site and from radwaste storage shall be determined by the following methods: Cumulative dose contribution from direct radiation = Total dose at the site of interest (as evaluated by TLD measurement) - Mean of background dose (as evaluated by TLD's at background-sites) - Effluent contribution ~to dose (as evaluated by surveillance requirement 4.8.D) This evaluation is in accordance with ANSI /ANS 6.6.1-1979 ' Section 7. The error using this method is estimated to be approximately 8E. VI.A Unious Reporting Recuirement 6.9.3.h . (3) Dose Calculations for _the Radiation Dose-Assessment Report The. assessment of radiation dosec for the radiation dose assessment report _shall be performed utilizing the methodology. provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Efiluents for the Purpose of Evaluating _ Compliance with 10 CFR Part 50, Appendix
~
I", Revision 1, October 1977. Any deviations from the methodology provided in Regulatory Guide 1.109 shall be documented in the radiation dose assessment report, The meteorological conditions concurrent with the time of release of radioactive materials (as determined by sampling
2$40010450 aev o f requency or . measurement) or approximate methods shall be used as input to the dose model. The Radiation Dose Assessment Report shall be submitted within 120 days after January 1 of each year in order to allow' time for the calculation of radiation doses following publication of radioactive releases in the Radioactive Effluent Release Report. There is a very short turnaround time between the determination of all radioactive releases and publication of the Radioactive Effluent Release Report. This would not allow time for calculation of radiation doses in time for publication in the same report. VII.A Surveillance Requirement 4.8.E The radiological environn. ental monitoring samples shall be collected pursuant to Table VII.A.1 from the locations shown on Figures VII.A.1, VII.A.2 and VII.A.3 and shall be analyzed pursuant to the requirements of Table VII.A.1. 6 S e
+ .
f TABLE VI.A.1 2840010450 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM f Exposure Pathway Number of Samples and ~ Station Location-Direction-and/or Sample Sample Station Name and Distance from Peach Botton Discussion
- 1. Direct Radiation 47 Locations Site Boundary vicintly lA Peach Bottom .On Site, 0.3 miles SE of TLD sites were chosen in accord-WeatherLStation il Units 2 & 3 ance with Peach Bottom Technical Specifications Table 3.12-1, 1B Peach Bottom .
On Site, 0.5 miles NW of item 1. Site Boundary stations , Weather Station 42 Units 2 & 3 all. sectors except several along Conowingo Pond. These sectors are 1C Peach Bottom On Site, 0.9 miles SSR of monitored by stations on the east South Substation Rd. Units 2 & 3 side of Conowingo Pond. The 5 - mile vicinity stations cover ID Peach Botton On Site, 0.7 miles SE of all sectors. 140 Sector Units 2 & 3 Site Boundary The distant and special interest stations, as well as several of 18 Peach Bottom the site boundary and 5 mile 350 Sector Units 2 & 3 vicinity stations provide Site Boundary information in population centers, nearby residences, schools, and IF Peach Botton On Site, 0.6 miles SSW of control 200 Sector Units 2 & 3 locations. Hill n 1G Peach Bottom On Site, 0.7 miles 60nf of North Units 2 & 3 Substation lH Peach Botton On Site, 0.6 miles W of Site 270 Units 2 & 3 Sector II Peach Botton On Site, 0.6 miles SSE of South Units 2 & 3 Substation
. =,
..+ ,
TABr,E vi.A.1- 2840010450
. RADIOLOGICAL ENVIRONMENTAL MONJ'r0 RING PROGRAM Exposure Pathway- Number of Samples and Station Location-Direction and/or Sample Sample Station Name .and Distance from Peach' Bottom Discusnion
_ LT Peach Bottom On Site, 0.7 miles S of Site 180 Units 2 L 3 Sector Hill IL Peach Bottom Located near Unit 3 Unit 3 Intake Structureg 0.2 miles Intake ENE of Units 2 & 3 , 1M Peach Bottom Located near Canal Discharge Canal Discharge structurer 1.0 miles SE of Units 2 & 3 .
. 1NN Peach Bottom On Site, 0.5 miles WSW of Site Units 2.s 3 2 Peach Bottom On Site, 0.9 miles SE of Site 130 Units 2 & 3.
Sector Hill 40 Peach Bottom In Site Area about 1.2 miles Site Area SW of Units 2 & 3 5 Mile. vicinity 3A Delta, PA 3.6 miles SW of Units 2 & 3 Substation 5 Wakefield, PA' At Wakefield, PA 4.6 miles E of Units 2 & 3 6B Holtwood Dam On roof of Hydroelectric Hydroelectric Station, 5.8 miles NW of Station Units 2 & 3 15 Silver Spring 3.6 miles N of Units 2 & 3 near Road Silver Spring Road 1
p , E
.28_400J0450 TART.E VI . A. I '
RADIO!,0GICAL ENVIRONMENTAL MONI M HIMG PROGRAM Exposure Pathway Number of Samples and Station f.ocation-Direction and /or ' Samp] e Sample Station Name and Dintance from Peach Bottom. ' Discussion 17 Riverview 4.0 miles ESE of Units 2 & 3 Road 26 Slab Road .4.2 miles NW of Units 2 &.3 near Slah Road 31 Pilotown Road 4.9 miles SE of Units 2 & 3 near Pilotown Road 42 Muddy Run 4.2 miles NNW of Units 2 & 3 . Environmental, Lab 43 Drumore Township 5.0 miles NNE of Units 2 & 3 School 44 Goshen Hill 5.1 miles NE of Units 2 & 3 Road
' 45 PB .Keeney Line 3.3 miles ENE of Units 2 & 3 46 Broad Creek 4.5 milen SSC of Units 2 & 3 near Flintville Road 47 Broad Creek 4.3 miles S of Units 2 & 3 Scout Camp 48 Macton Substation '5.0 miles SSW of Units 2 & 3 49 PB-Conastone Line 4.1 miles WSW of Units 2 & 3 50 TRANSCO Punping 4.9 miles W of Units 2 & 3 Station 51 Fin Substation 4.0 miles WNW of Units 2 & 3 s.4.-
mAni.e. v r . A.1 - RADIOLOGICAL ENVIRONMENTAT, MONI'"0 RING PROGRAM 2840010450 Exposure. Pathway -Number of Samples and Station Location-Direction and/or Samnle ' Sample Station Name and Distance from Peach liottom Discussion D,istant 12B Phila.,'PA On roof of Radiation 3508 Market Street Management Corp., Phila., PA, 64 miles E of Units 2 & 3 16 Nottingham, PA 12.8 miles E of Units 2 & 3 at
- Substation Nottingham Substation 18 Fawn Grove, PA 10 miles W of Units 2 & 3 at
[ , Fawn Grove, PA 19 Red Lion, PA 20.6 miles WNW of Units 2 & 3
'at Red Lion, PA 20 Bel Air, MD 15.1 miles SSW of Units 2 & 3 Area near Bel Air, MD 21B Lancaster, PA 19 miles NNW of Units 2 & 3 Area near Lancaster, PA 24 Harrisville, MD 10.9 miles ESE of Units 2 & 3 Substation at Harris Substation Special Interest 4K Conowingo Dam On roof of Conowingo Power-Powerhouse Roof house, 8.6 miles SE of Units 2& 3
- 14. Peters Creek 1.9 miles ESE of Units 2 & 3 near the mouth of Peters Creek 22 Eagle' Road 2.4 miles NNE of Units 2 & 3 near Eagle Road Y
l
; , ;l
*- TAtu.E vi.A.1t 2840010450;
- RADIOLOGICAL ENVIRO!:".CJTAT, MONOOk:';G it'GEAM
' Exposure Pathway Number of Samples and St at ion Lce'at ion-Di r ection ar.d/or Sample Samole-Station Name and Distance from Peach 30ttom Discunnion 23 Peach Bottom Off-site Hill 1.0 miles 150 Sector Hill- SSE of Units 2 & 3 Offsite 1
27 N.' Cooper Road 2.6 miles S of Units 2 & 3 near N. Cooper Road . 32 Slate Hill 2.7 miles E:G of Units 2 & 3 Road ,near Slate Hill Road 33A Fulton Main 1.7 miles ENE'of-Units 2 & 3 Weather Station-38 Peach Bottom 3.0 miles E of Units 2 & 3 Road near Peach Bottom Road.
- 2. Airborne Radiciodine &
Particulates 5 Locations lA Peach Bot. tom - . On Site at Weather Station These stations' provide for cover-(1z) Weather Station 1 0.3 miles SE of Units 2 & 3 age of the highest annual average ground level D/Q near the 1B Peach Bottom - On Site at Weather Station 2, site boundary, the community Weather Station 2 0.5 miles N of Units 2 & 3 with the highest annual average D/Q, and a control location. 2 Peach Bottom site - On Site, 0.9 miles SE of For radioiodine samples, station 130 Sector Hill Units 2 & 3 12 is used inctcad of station lA. It is the cane location. Radiolodine 3A Delta, PA 3.6 miles SW of Units 2 & 3 cartridges which have been tested Substation 0.5 miles N of Maryland- for performance by the manufacturer border are used at all times.
mLEv1.A.1 28.40gl0450! RADIOLOGICAL ENVIRONMENTAL' MONT'r0 RING PROGRAM
-Exposure Pathway' , Number of Samples andf Station Location-Direction and/or Sample Sample Station'Name ~ and Distance from Peach Bottom Discussion 120' Philadelphia, PA 62 miles ENE.of-Units.2 & 3 on the roof of 2301 Market Street
- 3. Waterborne
- a. Surface ILL. Peach Bottom Units 2 Continuous Sampler on Site at
& 3 Intake - Composite: Units 2 & 3 Intake, 1200' ENE of Units 2 & 3 DO4 Peach Bottom -~ Continuous Sampler on Site at .
Canal Discharge - Canal Discharge 1.0 miles SE of Composite . Units 2 6 3 , b. Drinking 4L Conowingo Dam - Continuous sampler in the El. 33 (ft.) Conowingo Hydro-Electric-u -Composite Station, about 8.6 miles SE of Units 2 & 3 61'Holtwood Dam - Continuous sampler at'Holtwood Station 6I is_a control lodation
~ Hydro-Electric ..
Hydro-Electric Station intake for both surface and drinking water. Station - composite about 5.8 miles NW of Units 2 & 3 c.' Sediment from 4J Conowingo' Pond Locatedin Conowingo Pond d Shoreline Net Trap.15 about l.4 miles SE of Units 2 & 3. j 4. Ingestion
- a. Milk Four locations.- three Milk samples are taken from several i indicator, one control farms surrounding PBAPS.-These farms.
include those with the highest dose potential, as well as control + locations. However, the location of the frams is not listed herein due to longstanding agreement with the i i j l 1 i i i
~
TAntE VI.A.1 momt.oc.iCu. Ewim:: mTu. mm.w:c. P., a,, 2840010450 Exposure Pathway. !! umber of Samples and Station !r,c.it iron-Dir ection und Dist.ince from Peach nottom' Discussion and/or Samg}e- Sa,mgle Station Name farms involved.'l'n ret .irn for- beinn
~ allowed to sampic and ..nal fze the milk, PECo has agreed not to divulge the f arms' location.
- b. Fish' Two locations 4 Conowingo Pond Station 4-Conowingo Pond fish are.
indicator samples,,while ntation. 6 Iloltwood Pond 6-Iloltwood Pond fish are control 2 species each location, camples.
- if available:. channel catfish and white crappie
- c. Food Products 3 locations 1 Peach Bottom Site Area Site area, 0.9 miles Food products are to be namples.
SE of. Unit 2 &.3 as part of the PBAPS Technical Specification program only if milk-6D 11oltsood , ' PA 5.8 miles 13W of Units nampling is not perforr.ed. The milk 2& 3 near Ecitwood Dam. pathway, which results in a greattr maximum close to humans than the 3 types of broadleaf- vegetation pathway, is monitored vegetation cach location, at locations.near the site, and is a if available. Only be?tter indicator than vegetation if milk sampling is samples. In addition; no crops not performed grown in the vicinity of Peach e Dottom are irrigated with water in-which liquid plant wastes have been discharged. l l l l l I
~
i
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' I' l INTER AFTER RADWASTE ANfL
\___/ pCONTAINMENT ' j
" T'w'4 g-' 8 RADWASTE
- CDNDENSER CONDENSER m _
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\ # FROM UNIT 3, PUMP (2) 3 ARTUP r T HOLDUP FIPE' SEPARATOR
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s ANkL j n n TURB Y, j { SEAL FRCM TURBs' "" ' SEALS (UNIT 2)
" l {GLANDSEAL GLAND SEAL EXHAUSTER(2) u v A CONDENSER (2) p CONTAINMENT CONDENSATE RADWASTE DRAIN TANK I
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V///J tment has of site PHILADELPHTA ELECTRIC 00. pggpg stal Affairs
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i R2v. 0 28A0010459 VIII. BASES _ Site Snecific Data Note 1: Liquid dose factors, A , for section III.S were developed , I i using the f ollowing site specific data. The liquid pathways involved are drinking water and fish. The maximum exposed individual is an. adult. A = (U /D +U x BF ) K x DF x RC i w w T i 0 i
.U = 730 liters per year; maximum adult usage of drinking w water (heg Guide 1.109, Table E-5)
D = 5.4; average annual dilution at Conowingo intake v U = 21 kg per year; maximum adult usage of fish (Reg Guide F 1.10 9, Table E-5) BF = biosecumulation f actor f or nuclide, i, in freshwater i fish, heg Guide 1.109, Table A-1, expect P-32 which uses a value of 3.0E03 pCi/kg per pCi/ liter. 5 6 3 K = 1.14 x 10 (10 p;i/uci x 10 ml/kg x 8760 hr/yr) O units conversion factor. DF = dose conversion factor for nuclide, i, for adults in i total body or bone, as applicable. Reg Guide 1.109, Table E-11, expect P-32 bone which uses a value of <
-5 3.0 x 10 .
RC = 1.16; reconcentration.from PBAPS discharge back through
,PBAPS intake.
The data f or D and RC were derived f rom data published in Peach Bottom Atomic Power Station Units 2 and 3 (Docket Nos. 50-277 and 50-278) Radioactivo Effluent Dose Assessment, ! Enclosure A, September 30, 1976. All other data except P-32 BP and DF were used as given in Rea Guide 1.109, Revision 1, October 1977. The P-32 BP and DF were used in accordance
~
-with infora.ation cupplied in Branagan, E.F., Nichols, C.E., and Willis, C. A., "The Ir.portance of P-32 in Nuclear Reactor i
- Liquid Eifluents", NBC, 6/62.
i
2840010450 Rev. O Note 2 To develop constant h f or section IV.C, the following Fite specific data were use6: HC (D/Q) = K'O (U ) F x r x DFL )a (Fn Cl-F ) -dits i F ap m i s_ e A +A Y i w p 6 K' = 10 pCi/ Ci unit conversion factor 0 = 40 Kg/ day; cow's consumption rate F U = 330 1/yr; yearly milk consumption by an infant ap
-7 -1 j( = 9.97 x 10 sec decay constant for I-131 1
-7 -1
= 5.73 x 10 sec. decay constant for removal of w ectivity in leaf and plant surfaces.
-3 F = 6 . 0 - x. 10 day / liter, the stable element transfer a coef f icient tor I-131.
r = 1.0 fraction of deposited radioiodine retained in cow's feed grass.
-2 DFL = 1.39 x 10 mrem /pci - the thyroid ingestion dose factor for I-131 in the infant.
f = 0.6; the fraction of the year the cow is on pasture p (average of all f arms) f = 0.484; the traction of' cow feed that is stored feed c while the cow is on pasture (average of all f arms) . 2~ - Y = 0.7 Kg/m - the agricultural productivity of pasture i-p feed grass. t = 2 days - the transport ' time f rom pasture to cow, to i milk, to recept or. _ _ _ _ _ _ , _ +
x 5~ 2840010450
;The- pathway ,is the grass-cow-milk incestion pathway. These data were derived iros data published in Peach Bottom Atomic
. Power Station Units 2 and 3 (Docket . Nos. 50-277 and 50-278)-
' Radioactive Effluent Dose Assessment, Enclosure A, September 30,.1976. - All other data were used as given in Reg Guide 4 1.109, Revision 1,- October 1977, jurve'111ance Reouirement 4.8.B.2 Liquid ~ Pathway Dose Calculations The equations for calculating the doses due to the actual release rates of : radioactive materials. in. liquid effluents were developed f rom thefnethodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to ManLfrom Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFh Part 50, Appendix. I",
- Revision 1, October 1977 ;and NUREG-0133 " Preparation of Radioloalcal Ef fluent tTechnical Specifications f or Nuclear Power -Plants", October 1978.'
Surveillance Recuirement 4.8.C.1 i . Dose'Nonle Gaseg lThe equations f or calculating the dosos .due to .the actual release rates of radioactive. noble gases in gaseous effluents were developed
.f rok- the . methodolog y ' provided ini Rooulatory Guide 1.109, "Calculat ion 01-Annual-Loser to' Man'from Routine Releases of Reactor Ettluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I",
Revision'1, October 1977, NUhEG-0133 " Preparation of Radiological Ettluent1 Technical-Specifications for Nuclear Power Plants", August n1976, . and the' ctmospheric dispersion sodel presented in Inf ormation Requested _in-Enclosure 2'to-letter from Goorce Lear to-F. G._Bauer
' dated Februa ry- 17,- 1976, September 30, 1976. . The specified equations
; provide f or determining the . air doses -in areas 'at ~and beyond the! SITE BOUNDARYfbasedEupon;the historical,averaoe atmospheric conditions.
- The' dose' due .to -noble' gas release as calculated by' the Gross Release Method 11s' much more ' conservative than the dose calculated ~ by t he Isotopic Analysis Method. Assuming the release rates given in
- Radioactive Effluent Dose Assonsment, September 30, 1976, the values; calculated by the Gross ReleaFe. Method for total body dose rate and Eskin
- dose rate are : 6.0 times and 5.7 times, respectively, the values
- Ecalculated'by the Isotopic-Analysis Method.'
i LThe: mode 1L Technical specification LCO for all radionuclides and radioactive 'ma terials in particulate f rom and radionuclides other than
; p . noble gases requireso that the instantaneous dose ~ rate be 'less than the equivalent 1of---1500 mrem per year. For the purpose of calculating this
- i i39-
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L 2840010450 instantaneous dose rate, thyroid dose from iodine-131 through the inhalation pathway will be used. Since the operating history to date ind2 cates that iodine-131 releases have had the major dose impact, this approach is appropriate. The value calculated is increased by nine per cent to account for the thyroid dose from all other nuclides. This allows for expedited analysin and calculation of compliance with the LCo. Surveillance Requirement 4.8.C.2 Dose Noble Gases The equations for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents were developed from the methodology provided in Regulatory Guide 1.109, " Calculation of Annun1 Doses to Man fror Routine Releases of Reactor Effluents for the Purpose ot Evaluating Compliance with 10 CPR Part 50, Appendix I", Revision 1, October 1977, NUREG-0133 " Preparation of Radiological Effluent Technical Specifications f or Nuclear Power Plants", August 1976, and the atmospheric dispersion model presented in Information hoquested in Enclosure 2 to letter from George Lear to E. G. Bauer dated February _jl, 1976, September 30, 1976. The specified equations provide f or determining the air doses in areas at and beyond the SITE BOUNDARY based upon the historical average atmospheric conditions. The dose due to noble gas releases as calculated by the Gross Release Method is much more conservative than the dose calculated by the Isotopic Analysis Method. Assumino the release rates given in Radioactive Ef fluent Dose _Ascessment, September 30, 1976, the values calculated by the Gross Release Method for total body dose rate and skin dose rate are 4.3 times and 7.2 times, respectively, the values calculated by the Isotopic Analysis Method. Dose, Iod ine-13J2_ _I od in e-13 3, Tritium, and Radioactive Daterial in Particulate Form The equations for calculating the doses due to the actual release rates of radioiodines, radioactive material in particulate form, and radionuclides other than noble gases with half-lives greater than 8 days were developed using the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases 01 Reactor Effluents.for the-Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I", Revision 1, October 1977, NUREG-0133,
" Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants", October 1978, and the atmospheric dispersion model presented in Information Requested in Enclosure 2 to Letter from Georce Lea r to E. G. Baue'r dated February 17, 1976, September 30, 1976. These equations provide for determining the actual doses based
-unon the historical average atmospheric conditions.
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2840010450
- compliance with the 10 CFR 50 limits for radioiodines, radioactive
. materials in particulate form and radionuclides other than noble gases
' with half lives greater than eight days is to be determined by calculating the thyroid dose irom iodin'e-131 releases. Since the iodine-131 dose accounts for 92 percent of the total dose to the thyroid, the value calculated is increased by nine percent to account for'the dose fror, all other nuclides.
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