ML20153G055
| ML20153G055 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 06/28/1988 |
| From: | Cotton J PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20153G049 | List: |
| References | |
| PROC-880628, NUDOCS 8809080025 | |
| Download: ML20153G055 (50) | |
Text
. .
O' ,
4 2880089940 i
i Offsite Dose Calculation Manual Revision 2 i
L I
Peach Bottom Atomic Power Station Units 2 and 3 1
i i
i
' Philadelphia Electric Company Docket Nos. 50-277 & 50-278 1
PORC Approval : CV--/$.
' PORC Chairman N 4/2 5/
Date b f
{
I PORC Meetlng # : N "" /O/ 0/bf!86
[ Date r
L
[
r 0809080025 G80929 PDR R ADOCK 05000277 L PDC f-
R3v. 2 Table of Contents I. Purpose 0089940 II. Instrument Setpoints Liquid Pathway Dose Calculations III.
l A. Liquid Radwaste Release Flow Rate Datermination B. Surveillance Requirement 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 E. Surveillance Requirement 4.8.C.6b V. Nuclear Fuel Cycle Dose Assessment - 40 CFR 190
)
A. Surveillance Requirement 4.8.D VI. Calendar Year Dose Calculations I
A. Unique Reporting Requirement 6.9.2.h VII. Radiological Environmental Monitoring Program A. Surveillance Requirement 4.8.E VIII. Bases C. .
Rev. 2 1, ,,,,,,,
2880089940 The purpose of the Offsite Dose Calculation Manual is to establish methodologies and procedures for calculating doses to individuals in areas at and beyond the SITE l BOUNDARY due to radioactive effluents from Peach Bottom 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 Bottom Atomic Power Station Units No. 2 and 3".
II. Setpoint Determination for Liquid & Gaseous Monitors A. Liquid Radwaste Activity Monitor Setpoint Each tank of radioactive waste is sampled prior to release. A small liquid /olume 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 gross activity monitor. The well counter and liquid radwaste discharge gross activity monitor are calibrated against the same liquid radioactivity source in the geometry to be used by each detector. An efficiency is determined for I each radwaste tank to be released. Exceeding the expected response would indicate that an incorrect sample had been obtained for that release and the release is automatically stopped.
i S.P. = (Net CPM /ml(well) X Eff W/RW) + Background CPS S.P. = Liquid Radwaste gross activity monitor setpoint in CPS Net CPM /ml(well) = gross gamma activity for the radwaste sample tank determined by the well counter.
Eff W/RW = conversion factor between well counter and ,
liquid radwaste gross activity monitor (CPS (R/W monitor) - CPM /m1(well)). !
Background CPS = Background reading of the liquid radwaste gross activity monitor
)
(CPS). ,
1 1
I
Rcv. 2 2880089940 The alarm and trip pot setpoints for the liquid radwaste activity monitor are determined from a calibration curve for 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 includec a factor of 1.35 to allow for analysis error, pot setting error, instrument error and calibration error. The flow rate determination includes a margin t
of assurance which includes consideration of these errors such that the instantaneous release limit of 10 CFR 20 is not exceeded.
B. Liquid Radwaste Release Flowrate Setpoint Determination The trip pot setpoint for the liquid radwaste release flowrate is determined by multiplying the liquid radwaste flowrate determined above by 1.2 and using this-value on the appropriate calibration curve for 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 gpm)). The factor of
\ 1.2 allows for pot setting error and instrument error.
The flow rate determination includes a margin of assurance which includes consideration of this error such that the instantaneous release limit of 10 CFR 20 is not exceeded.
C. Se_tpoint Determination for Gaseous Radwaste i
The high and high-high alarm setpoints for the main stack radiation monitor, Unit 2 roof vent radiation i monitor and Unit 3 roof vent radiation monitor aru determined as follows:
High Alarm - the high alarm setpoint is set at
> spproximately 3 x the normal monitor reading.
High-High Alarm - the high-high alarm setpoint is set at a release rate LMom this vent of approximately 30% of the instantaneous release limit of 10 CFR 20 as specified in Technical Specification 3.8.C.l.a for the most restrictive case (skin or total body) on an unidentified basis.
To determine these setpoints 1 l
1 I
1 I ,
l
)
}
RGV. 2 H I
)
~ 2880089940 solve _the gaseous effluent dose rate equations 11 section IV.A-of the ODCM to determine what' main stack release rate and-roof vent release rate will produce a dose rate of 150 mrem /yr to the total body and a dose rate of 900 mrem /yr to the skin (30% of the limit of 3000 mrem /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 l
Flow Monitors The alarm setpoints for the main stack flow monitor is
- I as follows
Low Flow Alarm - 10,000 CFM. - This setting insures j that the main stack minimum dilution flow as specified in Technical Specification 3.8.C.4.a is maintained.
I The alarm setpoints for the roof vent flow monitors are as follows:
5 i
Low Flow Alarm - 1.5 x 10 cfm 5
High Flow Alarm - 5.4 x 10 cfm III. Li'."i,id Pathway Dose Calculations j A. Licuid Radwaste Release Flow Rate Determination I Peach Bottom Atomic Power Station Units 2 and 3 have one common discharge point for liquid releases. The following calculation assures that the radwaste release limits are met.
t 4
{ :
i
}
R2v. 2 2880089940-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 after dilution shall be limited to the concentration specified in 10 CFR 20.106(a) for radionuclides other than noble gases and 2E-4 uCi/ml total activity concentration for all noble gases as specified in Technical Specification 3.8.B.l. Each tank of radioactive waste is sampled prior to release and is
( quantitatively analyzed for ider.tifiable gamma emitters as specified in Table 4.8.1 of the Technical Specifications. From this gamma isotopic analysis the maximum permissible release flow rate is determined as follows:
Determine a Dilution Factor by:
Dilution Factor = uC1/ml i MPCi i
uCi/ml i = the activity of each identified
) gamma emitter in uCi/ml MPCi = The MPC specified in 10 CFR 20, Appendix 1 B, Table II, Column 2 for radionuclides
! -4 other than noble gases or 2 X 10 uCi/ml for noble gases.
l Determine the Maximum Permissible Release Rate with this Dilution Factor by:
5 Release Rate (gpm) = A X 2.0 X 10 3 X Diliation Factot I
A = The number of circulating water pumps running which will p! ovide dilution 5
2.0 X 10 = the flow rate in gpm for each circulating water pump 'unning i
B = margin of assurance which includes consideration of the maximum error in the activity setpoint, the maximum error in the flow setpoint, and possible loss of 5 out of the 6 possible circulating water pumps during a release. The value used for B is 10.0 l
l _
~-
Rav. 2 2880089940 B. Surveillance Requirement 4.8.B.2 Dose contributions from liquid effluents released to areas at and beyond the SITE BOUNDARY shall be calculated using the equation below. This dose calculation uses those appropriate radionuclides listed in Table III.A.l. These radionuclides account for virtually 100 percent of the total body dose and bone dose from liquid effluents.
h
\
l i .
- "' 2 2880089940 ,
T
- D- = /___ A T C F
< 1 1 1{=1[_\1t il 1 l
where:
D = the cumulative dose commitment to the total l body or any organ, , from liquid effluents for the total time period , in mrem 1=1 1 8t = the length of the 1th time period over which 1 C and F are averaged for the liquid release, il 1 in hours.
C = The average concentration of radionuclide, i, in 11 undiluted liquid effluent during time period A t I from any liquid release, (determined by the effluent sampling analysis program, Technical Specification Table 4.8.1), in uCi/ml.
f A7 = the site related ingestion dose commitment i factor to the total body ot organ, T , for each radionuclide listed in Table III.A.1, in mrem-ml per br-uCi. See Site Specific Data.**
F = the near field average dilution factor for 1 C during any liquid effluent release. Defined il as the ratio of the maximum undiluted liquid waste flow during release to the average flow from the discharge structure to Conowingo Pond.
III.C Surveillance Recuirement 4.8.B.4a Projected dose contributions from liquid effluents shall be calculated using the methodology described in section III.B.
l
- See Note 1 in Bases 1
2880089940 TABLE III.A.1 i
LIQUID EFPLUENT INGESTION DOSE PACTORS (Decay Corrected)
A T Dose 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 2.38x10 4 4 Cs-136 9.83x10 3.45x10 4 4
) Zn-65 3.87x10 2.69x10 5 5 Sr-90 1.88x10 7.67x10 0 0
) H-3 2.13x10 2.13x10 *
- 1 1 I-133 1.97x10 3.72x10 l 2 2
) Fo-55 1.31x10 8.12x10 2 4 Sr-89 8.83x10 3.08x10 3 4 To-129m 2.0lx10 1.27x10 2 2 Mn-54 9.82x10 9.82x10
- 2 2 Co-58 2.59x10 2.59x10
- 3 3 Fo-59 1.14x10 1.26x10 2 3 To-131m 4.57x10 1.12x10 1 2 B0-140 3.66x10 5.57x10 3 3 To-132 1.40x10 2.29x10 l
Rev. 2 2880089940 NOTE: The listed dose factors are for radionuclides that may be detected in liquid effluents and have significant dose consequences. These factors are decayed for one day to account for the time retween effluent release and ingestion of fish by the maxfmum exposed individual.
k
- There is no bone dose factor given in R.G. 1.109 for these nucijdes.
Therefore, the whole body dose factor was used.
(
(
RGv. 2 2880089940 IV. Gaseous Pathway Dose Calculations A. Surveillance Requirement-4.8.C.1 The 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 nobl'e 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 limiting nuclide - Kr-88 for total body dose and Kr-87 for skin dose Method (b), the Isotopic Analysis Method, utilizet the results of noble gas analyses required by specification 4.8 C.la.
6 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 f flexibility by using data that more accurately reflect actual releases.
- a. Gross Release Method f D =Vh +K (X/Q) h TB NS V NV
) D = (L (X/Q) + 1.1B)h + (L + 1.lM) (X/Q) h s s NS V NV l
where: 1 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 mrem /yr.
TB D = skin dose rate , in mrem /yr.
s I
-4 V = 4.72 X 10 mrem /yr per uCi/ sect the constant
[
for Kr-88 accounting for the gamma radiation t from the elevated finite plume. This constant was developed using MARE program with plant
(
l l -
[
specific inputs for PBAPS.
i
) '
i 1
~-
{ Rev. 2 2880089940 h = the gross release rate of noble gases from the NS stack determined by gross activity stack monitors averaged over one hour, !.n uCi/sec.
t 4 3
/ K = 1.47 X 10 mrem /yr per uCi/m ; the total body 1 dose factor due to gamma emissions for Kr-88 (Reg. Guide 1.109, Table B-1).
-7 3 (X/Q) = 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, b = the gross release rate of noble gases in gaseous NV effluents from vent releases determined by gross activity vent monitors averaged over one hour.
in ,i/sec.
3 3 l L = 9.73 x 10 mrem /yr per uCi/m ; the skin dose factor due to beta emissions for Kr-87. (Reg.
Guide 1.109, Table 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 from the elevated finite plume. This constant was developed using MARE program with plant specific
( inputs for PBAPS.
3 3
( M = 6.17 x 10 mead /yr per uCi/m ; the air dose factor due to gamma emissions for Kr-87.
(Reg Guide 1.109, Table B-1).
l l
2880089940
- b. Isotopic Analysis Method
/ . .
D
=[~(V 0 is
+K (X/0) 0 )
o TB 1 i i v iv
( D =2~_ (L (X/0) + 1.1B ) h + (L & l.lM ) (X/0) (b )
s i i s i is i i V iv J
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 mrem /yr.
, D = skin dose, in mrem /yr.
S i V = the constant for each ideatified noble gas I i radionuclide for the gamma radiation from the elevated finite plume. The constants were developed using the RARE program with l plant specific inputs for PBAPS. Values are listed on Table IV.A.1, la mrem /yr per uCi/sec.
b = the release rate of noble gas radionuclide, is 1, in gaseous effluents from the stack
) determined by isotopic analysis averaged over one hour, in uCi/sec.
K = the total body dca, factor due to gamna i emissions for caca tuentified noble gas radionuclide. Values are listed on Table IV.A.1, 3
in mrem /yr per uC1/m .
-7 3
~ l) = 5.33 x 10 sec/m ; the highest calculatuJ v annual average relative concentration for any area at or beyond the SITE BOUNDARY for all vent releases.
RG Y. Rov. 2
[ ,
2880089940 0 = the release rate at noble gas radionuclide, iv 1. in gaseous effluents from all vent releases determined by isotopic analysis f' averaged over one hour, in uCi/sec.
L = the skiri dose factor due to beta emissions i for each .dentified noble gas radionuclide.
Values are listed on Table IV.A.1, in
) 3 mrere/yr per uCi/m'.
-8 3 (X/Q) = 9.97 x 10 sec/m I the higtest calculated s annual a547 age relative concentration from the . stack releases for any area at or beyond the SITE BOUNDARY.
j B = the constant for each identified noble gas
> i radt nuclide accounting for the gamma
- radiat'aon f rcu the elevated finite plume.
The constants were developed using MARE prograr with r.lant specific inputs for PBA'S. Values are lir.ted on Table IV.A.1, in mrac/yr per uCi/sec.
M ' the air dose factor due to gamma emissions i fo. each identified noble gas radionuclide.
Values are listed on Table IV.A.1, in mrad /yr 4 3
) per uCi/m .
1.1 = unit conversion, converts air dose to skin l do.3e, mrem / mrad.
?
k- - -
[
RGV. 2 2880089940 TABLE IV.A.1 - Constants for (sotopic Analysis Method l (corrected for decay during 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 V i i i i i i (mrad /yr (mrem /yr (mrem /yr (mrad /yr (mrad /yr (mrem /yr per per per per per per 3 3 3 3 R9dionuclido uCl/sec) uC1/m ) uCi/m ) uC1/m ) (uCi/m ) uCi/sec)
Kr-85m 4.025-05 1.17E+03 1.46E+03 1.23E+03 1.97E+03 3.76E-05 l Kr-87 1.74E-04 5.92E+03 9.73E+03 6.17E+03 1.03E+04 1.66E-04 Kr-88 4.00E-04 1.47E+04 2.37E+03 1.52E+04 2.93E+03 4.72E-04 l Xe-133 1.19E-05 2.94E+02 3.06E+02 3.53E+02 1.05E+03 1.llE-05 Xe-133m 1.09E-05 2.51Ft02 9.94E+02 3.27E+02 1.tBE+03 1.01E-05 Xe-135 6.37E-05 1.81E+03 1.86E+03 1.92E+03 2.46E+03 5.955-05 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 7.34E+03 3.94E+03 1.4GE-04
) The values K , L,M, and N are taken from Reg. Guide 1.109, i i i i Table B-1. The values B and V were developed using the MARE i i progrcm with plant specific inputt for PBAPS.
l e
9 I
m _ ~ . - -
[
aav 2 2880089940
- 2. - Iodine-131, iodine-133, tritium and'. radioactive-materials in particulate form,-other than noble gases,
! with half-lives greater than eight days.
The dose rate shall be determined by either of two j' methods. Method (a), the Iodine-131 Method, uses the lodine-131 releases and a correction factor to calculate the dose rate from all nuclides released.
tiethod (b), the Isotopic Analycis Method, utilizes all applicable nuclides.
For normal operations, it is expected that Method (a) will be used since iodine-131 dominates the critical pathway - thyroid. However, in the event iodine-131 releases are minimal (e.g., during long term shutdown)
Method (b) will be used to provide accurate calculations. In the absence of iodine-131 releases, the lung is the critical organ.
- a. Iodine-131 Method
~
r D = (CF) P W h +W h T I S IS V IV
- ~
where:
The location is the site boundary, 1097m SSE from the vents.
D = dose rate to the thyroid, in mrem /yr.
T .
I CF = 1.09: the correction factor accounting for the use of iodine-131 in lieu of all radionuclides released in caseous effluents including iodine-133.
7 3 l P = 1.624 x 10 mrem /yr per uCi/m 3 the dose I parameter for I-131 via the inhalation pathways. The cose factor is based on the a itical individual organ, thyreid, and most
.estrictive age group, child. All values are from Reg. Guide 1.109 (Tables E-5 and E-9).
-7 3 W = 1.03 x 10 sec/m the highest calculated S annual average relative concentration for.any area at or beyond th1 SITE BOUNDARY from stack releases. (SSE boundary) h = the releais rate of iodine-131 in gaseous IS effluents from the stack determined by the L _ _ .
2880089940 effluent sampling and analysis program (Technical Specification Table 4.8.2) in uC1/sec.
-7 3 W = 4.78 x 10 sec/m i the highc;t calculated v annual average relative concentration for any area at or beyond the SITE BOUNDARY for all vent releases (SSE boundary) b = the release rate of iodine-131 in gaseous IV effluents from al'. vent releases, determined by the effluent sampling and analysis program (Technical Specification Table 4.8.2) in uCi/sec.
- b. Isotopic Analysis Method l
I D
L
=[P i W
S h
IS
+ W V
h iv where:
The location is the site boundary, 1097m SSE from the vents. I D = dose rate to the lung, in mrem /yr.
L !
l l P = the dose parameter for radionuclides other i than noble gases for the inhalation pathway.
The dose factors are based on the critical individual organ-lung, and most restrictive ,
) age group-child. All values are f!om Reg. !
Guide 1.109 (Tables E-5 and L-9). Values j are listed on Table IV.A.2, in mrem /yr per l 3
uCi/m .
-7 3 W = 1.03 x 10 sec/m i the highest calculated S annual average relative concentration for any area at or beyond the SITE BOUNDARY from stack releases. (SSE boundary) h = the release rate of radionuclies; i, in gaseous is effluents from the stack determined by the effluent sampling and analysis progrtn ' Technical Specification Table 4.8.2) in uCi/sec. {
( -7 3
( W = 4.78 x 10 sec/m ; the highest calculated
, v annual average relative concentration fer any l
L
Rov. 2 2880089940 area at or beyond the SITC BOUNDARY for all vent releases. (SSE boundary) b = the release rate of radionuclides, 1, in gaseous iv effluents from all vent releases, determined by the effluent sampling and analysis. program (Technical Specification Table 4.8.2) in uCi/sec.-
i f
(
)
1 l ___ _
2380089940 TABLE IV.A.2 - CONSTANTS FOR ISOTOPIC-ANALYSIS METHOD 3
(msem/yr. per~uci/m )
PI - Inhalation Radionuclide Lung Dose Factor Mr-54 '1.58x10 4-Cr-51 1.70x10 6
Co-58 1.11x10 6
Co-60 7.07x10 5
2n-65 9.95x10 l 6 l St-89 2.16x10 7
Sr-90 1.48x10 l 5 l Ce-141 5.44x10 5
Cs-134 1.21x10 5
Cs-137 1.04x10 6
Ba-140 1.74x10
[
2880089940 IV.B Surveillance Requirement 4.8.C.2 l The air dose in areas at and beyond the SITE BOUNDARY dut to I noble gases released in gaseous effluents shall be determined by the expressions below.
The air dose shall be determined by either of two methods.
Method (a), the Gross Release Method, assumes that all noble gases released are the most limiting nuclide - Kr-88 for gamma radiation and Kr-87 for bets radiation. Method (b), the Isotopic Analysis Method, utilizes the results of noble gas analyses required by specification 4.8.C.la.
For normal operations, it is expected that Method (a) will be used. Jowes'r, 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.
- 1. for gamma radiations a) Gross Release Method
~ ~
-8 De = 3.17 x 10 (M (X/Q) 6 + B6) v v s where The location is the SITE BOUNDARY 1097m SSE from the vents.
This location results in the highest calculated gan.ma air dose from noble gas releases.
D y = gamma air dose, in mrad.
-8 3.17 x 10 = years per second.
4 J 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-A)
-7 3 (X/Q) = 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.
I u
i
RGv. 2 2880089940 6 = the gross release of noble gas v radionuclides in gaseous effluents from all vents, determined by gross activity -
{ vent monitors, in uC1. Releases shall be cumulative over the calendar quarter or year as appropriate.
-4 B = 3.15 x 10 mead / year per uCi/ sect the
- constant for Kr-88 accounting for the gamma radiation from the elevated finite plume.
The constant was developed using the KARE program with plant specific inputs for PBAPS. ;
6 = the gross release of noble gas S radionuclides in gaseous releases from the stack determined by gross activity i stack monitor in uCi. Releases shall be ;
cumulative over the calendar quarter or !
year as appropriate. j b) Isotopic Analysis Method j
~ ~
I Dy = 3.17 x 10 -82 [ M (X/Q) O +B Q ;
i i v iv i is i
- . l 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.
Dy = 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 IV.A.l. in mrad /yr l 3
per uCi/m . l l
l l
1 l
l l
l 1
Rav. 2 2880089940
-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.
O = 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 quarter 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.1, in mrad /yr per uC1/sec.
6 = the release of noble gas radionuclides, i, is in gaseous effluents from the stack determined bf isotopic analysis, in uCi. Releases shall be cumulative over the calendar quarter or year, as appropriate.
- 2. for beta radiations a) Gross Release Method
-8 D
p
= 3.17 x 10 N (X/Q) 6 + (X/Q) 6 v v s s
~
where The location is the SITE BOUNDARY 1097m SSE from the vents.
This location rasults in the highest calculated gamma air dose from noble gas releases.
Op
= beta air dose, in mrad.
-8 3.17 x 10 = years per second.
4
< R:v. 2 2880089940 4 3 N = 1.03 x 10 mead /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/Q) = 5.33 x 10 sec/m ; the highest calculated v annual average relative concentration from vent releases for any area at or be)Snd the SITE BOUNDARY.
6 = the gross release of noble gas v radionuclides in gaseous effluents from all vents determined by gross activity ,
vent monitors, in uCi. Releases shall be [
cumulative over the calendar quarter or year, as appropriate.
-8 3 (X/Q) = 9.97 x 10 sec/m i the highest calculated s annual average relative concentration from the sta,< releases for any area at or beyond the SITE BOUNDARY.
6 = the gross release of noble gas s radionuclides in gaseous releases from the stack determined by gross activity stack monitors, in uC1. Releases shall be cumulative over the calendar quarter or year, as appropriate.
b) Isotopic Analysis Method
~
-8~ l D = 3.17 x 10 2_N (X/Q) 6 + (X/Q) 6 i i 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 i gas radionuclide. Values are listed 3
on Table IV.A.1, in mrad /yr per uCi/m .
\
l l.
i i
p.
Rov. 2 2880089940
-7 3 (E7D) = 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.
6 = the release of noble gas radionuclide, i, iv in gaseous effluents from a*1 vents as determined by isotopic analysis, in uCi.
Releases shall be cumulative over the calendar quarter or year, as appropriate.
-8 3 (27D) = 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.
6 = the release of noble gas radionuclide, i, is in gaseous effluents from the stack as determined by isotopic analysis, in uCi.
Releases shall be cumulative over the calendar quarter or year, as appropriate.
IV.C Surveillance Requir? ment 4.8.C.3 The dose to an individua2 from iodine-131, iodine-133, tritium and radioactive materials in particulate form and radioauclides other than noble gases witt half-lives greater than eignt days in gaseous effluents releastd to areas at and beyond the SITE BOUNDARY.
The dose shall be determined by one of two methods. Method (a),
the Iodine-13.1 Method, uses the iodine-131 releases and a correction factor to calculate the dose from all nuclides released. Method (b), the Isotopic Analysis Method, utilizes all applicable nuclides.
For normal operation, it is expected that Method (a) will be used since icdine-131 dominates the critical nathway - thyroid.
However, in the event iodine-131 releases are mi.nimal (e.g.
during long term shutdown) Method (b) will be used to provide accurate calculations. In the absence of iodine-131 releases, the liver is the critical organ,
- c. Iodine - 131 Method
-o -
- D = 3.17 x 10 (CF) (0.5) R W6 +W6 T S IS y IV
" ~
where:
2880089940 L Location .s the critical pathway dairy .2103m SSW f rom vents.
D = critical organ dose, thyroid, from all T pathways, in mrem.
-8 3.11 x 10 = years per second.
CP = 1.09; the correction factor accounting for the use of Iodine-131 in lieu of all radio-nuclides released in gaseous effluents including Iodine-133. l ;
0.5. = fraction of iodine releases which are nonelemental.
l .
11 2 R = 3.08 x 10 m (mrem /yr) per uC1/sec; the I dose factor for lodine-131. The dose factor is i based on the critical individual organ, thyroid, i 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.
6 = the release of iodine-131 from the stack l IS determined by the effluent sampling and
- analysis program (Technical Specification ,
Table 4.8.2), in uC1. Releases shall be 3
cumulative over the calendar quarter or i 3
year, as appropriate. j s
-9 -2 !
- W = 1.14 x 10 meters (D/0) for the food t j v 'thway for vent releases.
l l 6 = the release of iodine-131 from the vent !
IV determined by the effluent sampling and !
analysis program (Technical Specification l Table 4.8.2), in uCi. Releases shall be
- cumulative over the calendar quarter or year, j as appropriate.
- See Note 2 in Bases. i
- b. Isotopic Analysis Method ,
- D = 3.17 x 10 __
R WG +WD j 1 i S is v iV i
. ~ ,
I r
i
l Rov. 2 1
2880089940 i Location is the critical pathway dairy 2103m SSW from vents.
i :
D = critical organ dose, liver, from all j c
pathways, in mrem. i i
-8 >
3.17 x 10 = yea s per second. i R = the dose factor for each identified i radionuclide, i, based on the critical individual organ, liver and most restrictive age group, infant. !
i 2 values are listed on Table IV.C.1, in M (mrem /yr) per uci/sec. j 3 -10 -2 i W = 4.95 x 10 meters ; (575) for the food l j s pathway for stack releases. !
i !
l 6 = the release of radionuclides, 1, in gaseous [
l is et'fluents f rom the vents determined by the l
- ef fluent s ampling (Technical Specification ;
i Table 4.8.2), in uCi. Releases shall be l cumulativer over the calendar quarter or i year, as appropriate. !
l 1 -9 -2 i l W = 1.14 x 10 meters : (57D) for the food !
- y for vent releases.
- t i
6 = the release of radionuclides, i, in gaseous i iv effluents from the vents determined by the i effluent sampling and analysis program (Technical ;
j Specification Table 4.8.2) in uCi. Release t
- shall be cumulative over the calendar quarter !
j or year, as appropriate. j 3
4 4
l l
l l i I r
l 4 i I
] !
l i
] !
i
RGv. 2 )
( '
2880089940 TABLE IV.C.1 - CONSTANTS FOR ISOTOPIC ANALYSIS METHOD 2
(m (mrem /yr) per uC1/sec)
RSdionuclide RI 7
Mr-54 1.14x10 4
Cr-51 4.72x10
- 7' Co-58 2.13x10
, 7 -
Co-60 2.58x10 9
Zn-65 5.56x10 8
Sr-89 1.06x10
- 9 Sr-90 9.06x10
- 3 Co-141 7.73x10 10 Cs-134 1.99x10 10 Cs-137 1.76x10 4
Ba-140 ,
7.04x10
- Thore is no liver dose factor given in R.G.1.109 for theh2 nuclides. Therefore, the whole body does factor was used.
i l
{
l
[
r
"'av . 2 ;
' 2880089940 ;
V.D. Surveillance Requirement 4.8.C.Sa i
The projected doses from releases of gaseous effluents to areas f at and beyond the SITE BOUNDARY shall be calculated in ;
! accordance with the following sections of this manual:
' t i a. gamma air dose - IV.B.1 [
l 1 l b. beta air dose -
IV.B.2 i i d c. organ dose -
IV.C !
- I The projected dose calculation shall be based on expected ,
release from plant operation. Thn normal release pathways ;
- result in the maximum releases from the plant. Any alternative r release pathways result in lower releases and therefore lower !
- doses. j I
1 t !
I I
'l l j r L
I l l N i i i i 4
! i
! t i
1 l
i i i !
1 1
1 i
i
(
r L
I I
I- aw. 2 i 2880089940 IV.E Surveillance Requ.rement 4.8.C.6.b
- 1. The three types of recombiner hydrogen analyzers used at Peach Bottom ares l a. Hays Thermal Conductivity type (Analyzers 20S192L, 20S192H, 20S222, 20S223, 305192L, 30S192H, 30S222, 30S223) +
l
- b. Scott Helium-Immume type (Analyzers 30S222 and 30S223) l
- c. Exosensor Helium Immume (20S192L and 20S222).
- 2. The calibration gases for the two types are:
- a. Hays Analyzers and Exosensor Analyzers l Zero Gas - Air Calibration Gas - 4% Hydrogen, Balance Nitrogen it Hydrogen, Salance Nitrogen
- b. Scott Analyzers
( 2ero Gas - Air Calibration Gas - 21 Hydrogen, Balance Air 1
I l
l e
Rov. 2 2880089940 V.A Surveillance Requirement 4.8.D If the doses as calculated by the equations 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.
If 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 commitment to a real individual shall be determined utilizing the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CPR Part 50, Appendix I", Revision 1, October 1977. Any deviations from 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 cumulative dose contribut!on from 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 i 1 approximately 81.
l VI.A Unicue Reportino Recuirement 6.9.2.h.(3) Dose Calculations for l the Radiation Dose Assessment Report The assessment of radiation doses for the radiation dose assessment report shall be performed utilizing the methodology previoed i.' Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the
) Purpose of Evaluating Compliance with 10 CPR 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.
4 The meteorological conditions concurrent with the time of release of radioactive materials (as determined by sampling frequency of measurement) or approximate methods shall be used as input to the dose model.
A2 mocaggo The Radiation Dose Assessment Report shall be submitted within 120 days after January 1 of each year in order to allow time for i
the calculation of radiation doses following publication of l 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 l 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 environmental monitoring samples shall be collected pursuant to Table VII.A.1 from t,he 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.
f I
l i l i
4 l
_ . - . . . 4 _
e
-n ,
f f i
h T
9 * * '
6 = Sk e . b 0 i
te Cee et 49 I %W 6 90 C e* eC.Oe @ b CGC ,
wC4ee6 e b
.e S=
=t e eA t w4 *e 40 w e w M . m .O s. & > C6* ;
+e5w >9
- e E D ( *-
- t C .e . en b eC w & Oe00
. .eeee* > 0
=ed**O Se D.sB I
N e >04d e 9 9 8 w e, -
C .( 4 ea$
C W#C ba $$
aee43 I
t . =t k4.95.4 i
y e . L b es 3 C .e D 8 Op. no me6e6 I O w > $ .e =4 COGid =*
\ s v * .G O D4 9 l 4wd o ee C3 G
- C (
b e( 0 . *
- C 9
4 9 e .9 c.a
- e.
- 6 h 0 .h
- e e .ee C
W e (e *0 0
- 6 ea 4e.e 4 W 9v.C6 e W O
.e d*
- e
- e . .W 6w .
w aC e 4e e
3 w
's .e*=ee s
- EWE e8*
ee>e
- O4 e .4 4 D.eC6A**
- E>=-
- O6ee
.b . 4 +
t e w a
Ove.e.
aC k mod =sw
=
t==
ele gD .e a wo w a n o . s C sCO C .e (7 ,
l-M r
% i o -
O C .0 e . .
- f
@ E
=
- z 9
9 0
- 9 O
O )
g* . Ww S4 W
mA 9 W 44 6,
N .
.ed l e a e !
E *
- e e e e e ,
. C. e o e e
-o e
- Co .e. .o. - l k g e6 .- .- . . - - *
- E E E E E E E 9
_E . ,
a et M @ . k h . '. 8 ;
C wv *M *M eM *M M P em .M =M [
> 0C O O O O O O O
= e4 e '. e6 e8 el d d e6 4 J .e e e e e e s s i
= 6N 6N 6N eN N N eN eH !
1.* .e. N a -e 6 -.
i.
- s. .y . . . . . -
E 5 3 .1 &E is && && 1 & 65 45 && i w
I
.d
. a 1
,1 :
.C . >
a w . N. :
.s .a
> I ;
t 1
. .1. 1 , .i . .i .i. 1
.i. ,
8 8
3.i .
E . .1 .! .!
p . . .
I 1 a . . ,
- s. e a s sww .
- s. w C - sO a,, -
. w ws W ww w . W . .
..= ., . . ,. . . .. . . N. . .
/<
t.
1 a
O
. +.z .e .
w a.
a . 2v .
...C. ..,..
.8 . o_ af 1,3
, . , .~2 .
I i-S 4 1
- I .
.i .
4 % W 4 b as -
g% C Gd
- l l
u a
.E i '
.1 o
o air os s Ch i co : . t : o
[
CD .is 2 2't . ;
o a.
. e ow
. ~
. .o .. .
W o. o.
, i
. ~. s
.s a
e3 ::
- ed a: g a -
- y :
cv ! ? : . . " 1: : : 5
%: ji .
- f. 1.g. :r. !" 18 : : }"a
.. . :" :: a ~
. s .a a w o. e e
.n
,.. e. s .
a gy ~. a s.V s. . .. .
. .a z..a .
O s.
2:~E 2.. *
- . : . 2" %*. 3 1; ;~
1 au 5 2
~5 2
. . . 1..nn . .
1'n8.. 6 31! :*;!:. *: su 4 i1 *: at *: **
. *) 't: 2 I E 3.7 $$ E $$ $5 l' 4 "w $35 43
. y
- t. 5 a
~ -
a
~
- . .: .I 8 l.g i ! .t g 1 .
t -
F
- : :n ;
- i
. s
+
t
- s. e.. a. .
a .* z z e a. oz s.
> 1. 1.
se
- X.2.z6.6 V.a %*
.! . 60 % :% :1.1- r2.,
- 6. .
g ..1 . . 2...i.*
,:s a$.i w -ae .
3.
9 .i* ':t o nea e e a e
zw .a h
z.
Ib.
L.'
W
. =
cow. 2 2880089940 -
icCtt VII.a. l maplotoG3ral ENvlootmef wiat mon 3 toa3NG Ppoceans E posure Pathway es.wr of samples and Statten Locat*en-Directten me.d/or Sample }a.ple Stenen Na and Destense from Peach Botto= Discussion 17 #4we'wle= 4.0 m49es ESE of Units 2& 3 A ce,9 26 Stab Seed 4. 2 me s es few of Units 2& 3 near Slab Road 3t Ptlete=re Road 4.9 moles $E of t**s t t s 2& 3 near Peleteen Road 42 esu ddy Run 4.2 e+1les 9eNw of Untta 2& 3 Envtrenmental Lab l
43 Dev=e<e fe=nship 5. 0 m ' I es Ne#E of L*n t t s 2&3 it hoe t de Goshen fette 5.8 m49es NE of untts 2 & 3 R oset 45 P9 - seeney L l e.e 3.3 ot tes ENE of Unsts 2& 3 46 B r enet free 6 4.% ettes SSE of 18a t t a 2& 3 near FttatwiIle Psa1 47 Broad Cree + 4.3 m49es 5 of tentts 2& 3 Stout (emp as macten soh tatto- 5.o meses 5sw of Untes 2& 3 1 49 P9-Cenestene Line 4.1 attes w%w of t)ntts 2 & 3 50 TmANSCO Pvas.tne 4.9 miles = of tsatts 2& 3 Stateen 59 fin 5.*statten 4,0 estes wtew of Units 2&3 1
l
4
==
)
l l
l I
N 9
O C
i e
e 3
v C
C 6
m :
e M M M
. M M i D w M e et d M d aw O (.
se es m to N el N 4 e eC et a
d e t3 mo N O a .: N d e e.
e N e o
&. ek e
e e wv
- e e4 e N *
- e e e ww
- 4 em *.
b'd b e (5 e e
- e. C
- e e
3 C
3 C e
{(
3e e
@w Ce C
& O * - C e.
- Ce =
,C e 36 3
& e t . .* . . . 3& . a. e 4 (4 e 5M 3 e. e C e GO 4e oe t*
- d a -G t e 3 e 3 . . es ee et 9 2 = .4 t . 9 ed o e B& B es wa -e k e M
== m 4 e se =& 2 w*
- e4 *
- w we
.e w3 g
ee IT sw N w e ea 3e ee se
- e. a*
C e+-
e e e a
vg
.e e.
we Iae *
- s e. e &- e4 a e- e
-e .e a- e e-I
. E Ce o-e .5 t
a eo e6
-a
-s et se
-e el ee
-s
-6 4
.e 9 .
e* e0
-e
-w
- e. -o eee. - - e - e eeM e s s . 6 e-
- e. m. ECs d. a .we E6 a. t *e 6
.o.
e ea C-o e et e ge e *
- Il CeI Ne Q= #e Se Ow CE e. 4 .e
> 2 e e4 C 3 & mi *2 C
= .e Ne =& *C ee O4h -* NE w
w g
b w a O
s= *e s T.
a ee Il .
o e e e 1
e w -
=
a C ew 4
6 e
& O
- e e
e a.
a Oe 4
o Ee &H f
- e. 3 4 -
- e e D ,
$ e- 3 -
.e .- e es . a w
s o o.
o
- . .e Oe
..e fi 3 e
8 e
e ei e.
fe
.c. -e e
.e C eN
- 6 ** e ** e 4 e e Y e e a ww C g. e -
a o s, C 4E
- e 4 0 - 6 e e
- 9 e =i) e & Gw e e s Ge
- w e e i
.e a eee We w E
i I
=l el GQ
- l C4 Nd
- M
@ 2e 4
s-C6 Ne Se Ne e 4e
. 9 N
w y
W 9&
ae B
9 m
N l
m e
- l. e e
er .:
e+
36 e.
Os w ..
i ter. >
2880089940
.. m .. ....
..osoincit. .wenarm.r=,.o .muo,o. =c eeoc... l l
i
_ , .. s s,...<............
l ..., ,., . . .s . . ..- . , a..s...
.- . ,o.u . . ,, ...< .... .... .. ,
,,... ~ ....
,so s.<,., ....
sse ., ... , .,.....
, o,.....
t l
,,..e-,.., s.. ..... ,., ... , ,
.. .. c ,...,
i o.
,, s ... .... ,.. ..... ... ., .. 2 . ,
...., ., s,..........,
I i
... .. .., ,., ..... . e . .. 2 . ,
...,~,s,....
,. ..~ .... ... ..... . ., . . . . ,., ,
- 2. ... .
..... ..... u .. . . . -.
,.., ,. , -. .,~
. . ., . . s,...
..- , o.,s o.,
..... .. ..se -.. , . ...
s,...
....,,-....,o,o...-
.. ...< .... - - s... .. .... , s,... 2 .... _ ,.. . . ~ ..,
....., s,... , .. ..... . ., .... , . , ...~ ,, . . . .
.... o, . ,. _ ,,..
,... ... - s,.. o.,s.... o.,..... se .. . . , . . . . . . .
3 s..... .... .- . ... . . . . . - ,
..., .. ,.6 ..le. sw .f ,s . t . ,.3 c ., t r e. ope. .es ..h ,s.v. . .. , t e . . , j
- 3. -
- a. . . . . . o.s ..... . ., .,,.. e.,,,.,e..,,,,,,.c.,...
tp.ed., .. . as. . t . . t. ..
l
- 33
99w. 2 u 2880089940
~
TAGLE Vit.A.3 l RADIOLOG1 Cat Euvlenweetsstat esosetTOstle#G PROGames Espesure Path =sy esumerer cf Saagnies anss Statten Locattem-Directten nadrer 5.-,3 se-e s , >iestsa amme e o oestance fr - *esch se tte pu tussten 120 8'htladelp443 Pa 52 elles Estt of ten t t s 2 & 3 en the reef of 2303 tearbet Street t
3, 49eter p reme
- e. $ws f.st e ILt 8'es.c ts 9ettem tant t s 2 fee.4Gnwows %empler en $6te at
& 3 Intame - Coaciestte t>=les 2 & 3 tatste. 12fso Evet of t> sits 2 & 3 i teas Peath Settem - Cent 4nwows Sampler en Site at l Coast Olscharge -
(maal Discheroe 4.0 atles SE of Congres t t e the t t o 2&3 i
ts . Ortaking di Cone =taga Dam - Centenwows sempler ln the l E9 33 (f4.) Cone =lape Hydro-Etecer4c I Competite Statten, etseet 0.6 miles
! SE et 4)atts 2 & 3 l
6s Holt eed Dam - Centinweve saaoler et **e t t eed itetten 65 es a centrol t oda t t o,-
e*ydem-E8ectric t*ydre-ftectric Stattea intene for aset h sur f ac e e, +r+4r'
_ em i e w e- -wm - - - --e-m-& -ww-e ea
v f
I 1 . -
4 .
l l
.t !, .
it
.. .e 2.g2, .. .....f..t..
I ', .l l i 5 s
, a .l -.
. z .. .
c..
.f .c.4.
...c . 8v..,. . .c. ...,. ,
ist {2! 2 t i t ,, g . ! ! *. : : .,
. 7 ,. .
. 2. ," .#1..: c, :1.. . . . .
i
.c..5
-.s t 'f ' i. .t1.e .: t .g :.f.t....s..it i
.f..: ;
.aI}...
il; * *t*1 ,
3 :*. [Pl w:'
.l
- .gtt.I[3: 1-23 1
1
!! 3't !,si. 3h ...i. fhs ,. .t . f - - t .a t.
.e t. L......... .. ..,
1 . 1.
- -- #. *- I'
.l32' " -
1*t .
3[J:t:((:.gy..g. 35 J,
c.
c
. . .a 1.f.l
. . . .. . a. 3 i v '
i m
CD 1 o : !
O !!
I C = , i
- co - ,3 N $ :tg: :
- lE.
4 o.1 se i
- 4 .g
- ea .: ; i j
g 1. d~ gl . j
- gr ,
- s. . ... .
I
- l i.~
.a
.a 55
- I en
- . ** (
i, ::> = .31 ## ,~ ,
4 t
1 2~I ( : 1 3 1 V y . :
E .g %I: . . . I'
- a .. t
- t : 22:-
3 :*
- E. s. & .t l
.I ,Et..l 1 .1 1,
. 8 .,4 i
.. . 1.... .
.t. ..
.i..... t. .
.i 3 ... . .t. ...
i..
1 1
o.
-g -
[ :. *t .t-4e = 1.*. f 13.t: 1 (
v 3 v...
- j . S .!::I j i f t
4, b i s !
b.
- b. -
l 2 1 4 .o 3 3 1 3.
i- i J t ,
l
.a E. t I
4 i
a - _ - _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ - . - . .
1 F
2880089940
'N-= ., I,s/s//)' t /'
%7 ]?'r \ _ .. .. s.,,. ., _ .y ;
- s. s ,, s \
i
, ' ) ..) ....../ /'"' h.
', ..:, = q'i(_____ \..
/
\
s -- -
/ . . . . . .* .. /.
of.,/
N. -
,/ , ,,- ) ,s '-
/ ... ...
.x.,
i.efe****e'
, , ,, N )
- I 4.'; g -. ....: [ = ,
( .
iL M .,
- \./. h
..>., u
. ,/ -
.&8 - .
y,,
,s'%q\g\
, %?
r' /)fY)..... 1...
>S."d..k ,, .
N \ . NN g/a
( N .4.A 'JW Y jM.,. f ki'rf,,e
\
[
n
/ x,, p s .h@%7M' .. . ../'C,u Ws s
'. $ ' ,iS
...T- /A,p' ( c . 4F..:.o . -
., 25 . _ j( h i
,. ,,. ,, mM~ .. w x8 ! w. . .. , . ,8 ,
t
. -. v y~w a ,
x.. .,. ~ m ! n .:. ~:-~~. ,. - - . -- ,-.-~
- ~
W. 4,'i . m -i s
,.J \/ 1
\x %.::... ' ~, ~ %
. _ .} Q '.> j ,< ~..'n=-- - .c2.&w. '=' ~,= '=~ - sp -' - ' ^\-j s
1
.,h
)
[c /? Q,t ~ '
v
- j%
\ , .,;
,\p-y, Nj, lI.h : ...
\ \ . . (' l.' !
/, . ./
,,./ \ *. ,-
'\,/,'\/:. / ,/
/ .-s .A . t - u ?. ,
[ .
o .
. s. / , =.
'\
f
.--.. f~:.'E '.,(
r s' *
.\/ r P Y,4 \ /
\f
-('f,.*/ f/ ^\ a f^ l ?. ', hy 9 l
& . +/
\ '- - ( .,' ' . . . . ,. . . > l- -
/ w,/ y ' ,
.e . s . %)w'.,"
v- -
~
/
~~. -
t ENVI RON','ENT AL S Av? LING ST ATIONS AT INTER','E01 ATE DISTANCES FROM PEACH SOTTCM SIT :.
? I GURE \' ! . A.2
[ .
- - ,. :. .s -u .x q :;..
. . - - --+-- 2 [._.- ~ _:. , .
~).
~
- m. h- s=M m- ',,/m h e k - :v ._ b ,+ h' . v 1. :,- . ~ r y s, . __m_.,:_.r.~. . _ -.x . u.
( .'.y , n w/ , -.=_=~:+.<.,.geyf. Q.m n e . .,3
__. ,..y-) x. s u. , _.\
.s. 3- -
. ,, c- / __ .
. _ - w _.:. --
"'_N
.s.
e . - , ,, _..r.,=.~...,e.,,
w, -
. r. ~
\
p sr .= ( *
% ,/ , ~..~..
._,J' ]. .-A /--%~f=.*/-.r
,, %v , v - ~_ . ,. .
N /"x /N-
\<'~A. #s.~1N.*
,,:r -e
\
d,-r~
N
,/ .-
.W:::;; . .. "
W,~. *;; c0 eN b .f *wl's.a *. s..= .,<.:' .'
\-^.' .~ . '% J, .p-m~.~, :s\ -.s / .
\ -
/ ., . --- .a.
\ .:=,' **S.
- . yT -=N-T*"A*/ . "" g
~ ~
y .,,,,. \ .# /
- w.c2-
),,,a """* >\ - --- - s".
g-
. C:)
-(, A .--
_ t -;. e/ q) kA.,.s R_5 s s .s.-._...,.--
" (M' -1,-- s - so e.'<., ,, r: ,e - .
~. -
s-
.= _.\-. p~.-
- . _ g= 4.g
.- . ~9. ,s w.p=.p<<-
., ,. .u.
.a
, - ,,i_ ~i'.
c
.Hs:= s ,,c.,~.w o ~ A.
.).-- ~ -.. _. ,
\.T.F r.--
s::>+.,~n%. . >.,
s
=
x-r~: m_,..,.s~.
. ud-.:..s.=, . s. .
'_&r._~%p_ ,.
I,._ %,
"~
t . .-w:. -
) . -.
- =L5-,1.
s?,"Wi
_ / = --w. E _ 7d.,p;;. G.-=E.p =J . ,g)q.' :,-h.I- -7 - - -= -c..w.-=
r;. t=)
3 -M ;-
v',t:- -f, sif.x,... ==.c= 'V'"4e#,-~ -
.-- %~ r _-l.__\
h._gfs-E. .
f3..= ._ g. .:::..sc.
- c. ~<A%n y_.4Wb v n.r.
. = _ . _ = .v--t Z__v' q.=vs,_s. s <. =,o +:a= :.c w :_.*
. -w.m g s, =g __ -
s .
. = ,
.\ - ,_s __.
_ _ 9 :-=,,_ ,,--. e' p-_
- \s . -, ;_.,::n.
1 t ..=v=A~a =. ,-k, c. . . .s,~
. = w--D. .3 w.
d.b x'b' . J>. LiN_,< =x= ~ ~ .
A.:=.i,
\ .;~- ,T;ou-T i g -- %- <N...- .s.s. u. -n 's, w.
(
- . y.
_c-- ~ --A m. .
m...:.,_
.v .. ,.. - . y. . s->. r. e.;
._ u.
.. = _w,=
.3 pm,;;=w.
. .:':n x'-W==: , , . -.
\e -
-s
.=. \n =%._--3 .2=.::.e.=;m -/ # p=<c as ~ . .=-:=r
- m a c ~.*
.=. . ,:::-- ./ . -s-, . <
.,1_,
e -.
1_:.gsM. -. /' u -_. =,. a s : .s...2:=.
. e
.=
v _:
.-y, ., - c-.u c -
__. - t / v: _. .--'
_\s1_--M e, ._ , ,r--- - s.r -T _ (,,. A%o , aw ~_s=:f.'_- .<
. t . , _-
c, --X. m- %, _ >'.3~.. _
. 7x.u. -
.~___ s.. -
.c.
s . .
'. s .
.j. v fk.=.1
,: - T
,,..-.. i .-. . h.
. c. _ g ~. s__
.=_ s-
.-_ N A
. f .
- I v :e w r. . _ .
.s
-v. - :.q. ._
n = ,..._e - .;.,, .,.:..
s
.N , / \., ,-qg -
,c -v.g._.._c, ' .
e -
. ..- N
~ . . : _.
. s_,; ,- .s ,:
r ,_:._./ . .
s ... t, .
. s. u r =s.t--- -.
. r. w....-(.
)
..o. .- u) , &.8.~.
, u i.
> ,:- =. .:_ i 1 >. .
r . .q? / . % c.f-.a
'\
) g , .o;
...,r.
. .- Q s, ,e ,. s- +
. = - l.
ws- w, v'-=^
1 :., -
- e'. . ...g; -. /g.. .,e n- ,;- _- :
,m - t=i , . .:
n :r. m
<.~-..-
% . + =. /. _.
_i., .
. g.1,,. -
. s. ,/ =w ,7, r' .
- I. ,5
,,r' . .:s.,;2.,.:
m _y> 4- v..a9:
- y . ...
vc . . s-. "'~
t
. * . . -re . .-
/
t
-G
) s,_ ._ _ e= ._ - \ ,tm . ,
1 . .s . '
,/- 8, _- :r.. -1 ? ,
~
-s ,\
% M..[3.M. :
yc . q. .- w M z.:n.,.,p- / x:
. .; ~;;:.: 1
.,... y. .,
w - -
8 (~.- ; . ..s- .i
.c. .w,. -ra
~ r,~ ,. .
- ., _ s.. ,.:
-sc-- , = ) %.
~_
\/
, ._..x . _, .
. ~., .. ~. .
,./. _ ,
--s -~...
t,. .
. / *.all%,ms_.s.
.u s p. - m-.-<-*- -<
- ~.A'.r .,, . .w -8 ts.'-. . ~v a.,. Q ,-
% . s- .
_.R :."
y, i ,
. . _ _ . . . . _ = . , . a.,-
o .
y , '
. .w. . ._
mv y s. p { ,
C z'?d_.y\
i< _
.,4.
W,n,. . W
.. .n . . , . .
"z .
l
~ %.c.k G . tQ i NSE '
- ai mu,e c.:m ,. e n. p$ 5 V. : g = .., g; m, . g,. ,
9 i 4'~~-Q-W +c
._ :. f ,,. - _t 57 m.
s
~
. .. . m. . i m n
. s.
u,i
, . - - . . . .. ' < a- -
.-.% g,- .N
n na m,t ,,' 7.- ~t- ' - "
';.' ~N u m ue. .. .-q ' ENYlRONFENTAL SAWPLING ST ATIONS ~~~~'
' " -P5ATREWOTEOlSTAN0ESFROWPEACHBOTTOWSITE' Ei t[I:'$i h"!'m u .mmim. . ..nm m. FlGURE vi! .A.3
~
e a... ,
kI _?________- n
(~g wE ECs m .- c=<~
- . c ( Y ,.:e_smC :2=un cmw-
- u. - a =
i /O J I
I. . .r j.Aw 3 .r 1 -
J e
u c.- <<
M>3 c.
o.
=
6.s 9 3 m o
4 . .e g i y L 4 - i r y k k --
O \ CM am
)'==
'n v %e_ c
. mm
.< =
L -
e
~w w,
=
o m -- ---
ew c, <a
<e w.c
--rA, ir u. - ::' m
~<
o u.
- ; u. a u. a 5
- C h.cJ I U ou>".' C3 o M C 6- . gg T C {
. 3C w N
CC C uJ c N Vm< / b l
.a c
- <17. OW
~
w(
C.
n-.c, p
C M g
[c c~ >"">",.4 p.4 c C= c
- C a = =
, 2 e. =
/
w (r J j-mo CJ D C
.a -
Q g .
m c= c ='
t w=
-' n. 6 i l l s g N T / a T / s% / g% / :
Ch .' c3 J e.< e< e-<
C == = == ==
A- \= <j \ <j % <j
- )
~~
c:- %
g UJ . .
+
"3 ~
~
) .
>"'8
=
e
= G m w~ -
g 7s o U
=M f J-Q W <"* . <c
- WC ww m-
=C M p----.
c3 O e C
r - - - - - -> cp
=< .
g { <I g
<=
Jy l c= c= i . ew a W< -
I m e. lI i <w a e umn .
1 I - w '
i =a -
w= -
Pw N
- wo -
.s <=
C s
I I
' .JN I M u <-
m e - i w c=
A e
C o CO I y2 C- Mw
,3 M y p l w l 4 w
=w m c_
J i <w , w= - n u =-, =w wv 2 i -w s ,- <e e i w N ~
== . ae
= = FTLAD:L.:TA
, , - :':CI'i'
- r- ~ -
-+ t _.N.] '= =
-=
C i, ,A - ,;,egG m a r:aPS A
' UNITS 2 1 S I
s
. -_a s>< ,
T L - - - -> y a ~=
~CO e--
Ew_" 5%
=
0.:FGA" RADWASTE
%r f
5*,E,- TREATMENT SYSTEM
) =d C-e=q
$ mw w
em
\ x<dm u.s = = m_ =ws =< -0, w e,
, -=
= .,_a
2880089940 l'
REFUELING, FLOOR EXH'
( r V(3)
REA0 TOR , f -
" i 00 "' 2) h:. h ?/ . L i : 'J( r. a AT REACTOR BLDG EQUIP CELL EXH '
s
- %^-~ (2)
( _ _ _
~
i ;
(2) a.E H I G H n A h.
e:-
5 (2) 2) 5 A
RECOMBINER , 6~
x 'f BLOG EXH y ",
n=
TUREINE BLDG, K_
1l AREA EXH '
(3) 5 L EH' I " ^
E (2) 2)
- _a hPAPi!CULfi FILTERS I I TURBINE OPERATING g /_ r ' E FLOOR EXH U (3) '"
c: _
RA0 WASTE , C a
=
5 5 AREA EXB'
- 2) N jE
. W
' =
E (2) 2)
EXH E ' [/
U 2)
LAB AND , C r TOILET EXH' Q (2)
FUM 000l -% ,
g,q 3 PHILADELPHIA ELECTRIC CC PSAPS EX ST
' pp FILTER UNITS 2 & 3 l YENTILATION EXHAUST
} '
WASTE TREATMENT l SYSTEM l
1
. ..., , ._ . . .: - . ;; r .
1 1
N _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
I I ~
(, u~ ' ,e" [
Rl U
I AA IN A
~n -
y )
C R
I I
D C
)
W C
C g
E C gN2 I O nI(
YAK A " R S
gRH N F
)
3OA E O t 2 I
( DE T NG OA E CR L
_ I O
0T U 1S O
( .
Y R RN E DI o T
NA L UR u I - )
AD F L '
2
- (
(^
R E
NK T EE K TGl l Sl iA
{EE L( )2 -
IN AA R A
W 0 AU I T
S P K RT E 4[ WS A MN WA A O
E T
A E
C 0
88 9 S T RL W I 1 8
9 OP V "
OM E R-8 LA C E
- f 0 FS I S i
f V
0 T .
R R E I
O 8 E N -
E E R I 8 I I T S U I
~~ S M A S 1 2 -
A E W Y S 1
Q WD -
C E E N R 'l
, C E P i f
_' I G 1
- V R 1 1 Q R E 0 D R E M 1 l
- R RN E S E 1 i
T E E I 1
T T
_ S L A I I OA LR L I
FD WF F
. N K I
A N -
I R TA y - ' . .
[ D R E 0 GR
- 0. U '
(
y l
F S
, ?> "
N
- O ,
,;S su W _3 I K . ox
. >- Se ; 5 -".> , f T N N '
u I A usa" C .
_ E A T =Um ,,
LK R R LN O O OA -
,1,
' c 5 '$ ge" -
O E E O L a 7r >; 5,x ~ m m ~ E' t
T L S F LO A y" '
W C .
1l
[ .
Rov. 2
{ . vrzt. BASES 2880089940 Site Specific Data Note 1: Liquid dose factors, A , for section III.B were developed i
using the following 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 Dr x RC i w w F i O i U = 730 liters per year; maximum adult usage of drinking w water (Reg. Guide 1.109, Table E-5)
D = 5.4 average annual dilution at Conowingo intake U = 21 kg per years maximum adult usage of fish (Reg. Guide F 1.109, Table E-5)
BF = bicaccumulation factor for nuclide, i, in freshwater i fish. Reg, Guide 1.109, Table A-1, except P-32 which l uses a value of 3.0E03 pCi/kg per pCi/ liter.
5 6 3 K = 1.14 x 10=(10 pCi/uci x 10 ml/kg 8760 hr/yr) l 0 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, except P-32 bone which uses a value of l
-5 3.0 x 10 .
RC = 1.16: reconcentration from PBAPS discharge back through PBAPS intake.
The data for D and RC were derived from 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 otner data except P-32 BT and DF were used as given in Reg. Guide 1.109, Revision 1, October 1977. The P-32 BF and DF were used in accordance with information supplied in Branagan, E.F., Nichols, C.R., and Willis, C. A., "The Importance of P-32 in Nuclear Reactor Liquid Effluents", NRC, 6/82.
Rev. 2 -
2ee008994o I Noto 2 To develop constant R for section IV.C, the following site specific data were used:
RC (D/Q) = K'Q (U ) F x r x DFL )a f (1-f ) -h t i F ap m i p s e if
). + A Y i w p 6
K' = 10 pC1/uci unit conversion factor 0 = 50 Kg/ day; cow's consumption rate F
U n 330 1/yr; yearly milk consumption by an infant ap
-7 -1 h
= 9.97 x 10 sec decay constant for I-131
-7 -l yw = 5.73 x 10 sec decay constant for removal of activity in leaf and plant surfaces.
-3 P = 6.0 x 10 day / liter, the stable element transfer m coefficient for I-131.
r = 1.0 fraction of deposited radiciodine 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 en pasture p (average of all farms) f = 0.513; the fraction of cow feed that is stored feed s while the cow is on pasture (average of all farms).
2 Y = 0.7 Kg/m - the agricultural productivity of pasture p feed grass.
t = 2 days - the transport time from pasture to cow, to f milk, to receptor.
L Rov. 2 1 r
2880089940
[ The p3thway is tho grass-cow-milk ing3stion pathway. Th2s3 data were derived from 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 I 30, 1976. All other data were used as given in Reg. Guide 1.109, Revision 1, October 1977.
f Surveillance Requirement 4.8.B.2 Liquid Pathway Dose Calculations Tho cquations for calculating the doses due to the actual release rotos of radioactive materials in liquid effluents were developed from tho methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I",
Revision 1, October 1977 and NUREG-0133 "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants",,0ctober 1978.
Survoillance Requirement 4.8.C.1 Dose Noble Gases Tho equations for calculating the doses due to the actual release retos of radioactive noble gases in gaseous effluents vere developed from the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CPR Part 50, Appendix I",
Rovision 1, October 1977, NUREG-0133 "Preparation of Radiological Effluent Technical Specificktions for Nuclear Power Plants", August 1978, and the atmospheric dispersion model presented in Information Rcquosted in Enclosure 2 to letter from Georoe Lear to E. G. Bauer dotGd February 17, 1976, September 30, 1976. The specified equations provide for determining the air doses in areas at and beyond the SITE BOUNDARY based upon the historical average atmospheric conditions.
Tho dose due to noble gas release as calculated by the Gross Release Mothod is much more conservative than the dose calculated by the Isotopic Analysis Method. Assuming the release rates given in Radioactive Effluent Dose Assessment, September 30, 1976, the values calculated by the Gross Release Method for total body dose rate and skin dose rate are 6.0 times and 5.7 times, respectively, the values coiculated by the Isotopic Analysis Method.
Tho model Technical specification LCO for all radionuclides and radioactive materials in particulate from and radionuclides other than noblo gases recuires that the instantaneous dose rate be less than the cquivalent of 1500 mram per year. For the purpose of calculating this
2880089940 i
, instantencous dose rate, thyroid dose from iodine-131 through the inholation pathway will be used. Since the operating history to date indicates that iodine-131 releases have had the major dose impact, '
this approach is appropriate. The value calculated is increased by i nino per cent to account for the thyroid dose from all other nuclides.
This allows for expedited analysis and calculation of compliance with
( tho LCO.
1 In the event that the plant is shutdown long enough so that iodine-131 is no longer present in gaseous effluents, an Isotopic Analysis Method
} is available. Since no' iodines are present, the critical organ j chcnges from the thyroid is the lung.
l Surveillance Requirement 4.8.C.2 Deso Noble Gases Tho equations for calculating the doses due to the actual release rotos of radioactive noble gases in gaseous effluents were developed from the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for tho Purpose of Evaluating Compliance with 10 CPR Part 50, Appendix I",
Rovision 1, October 1977, NUREG-0133 "Preparation of Radiologica'.
Effluent Technical Specifications for Nuclear Power Plants", August 1978, and the atmospheric dispersion model presented in Information Roquested in Enclosure 2 to letter from George Lear to E. G. Bauer dctGd February 17, 1976, September 30, 1976. The specified equations provide for letermining the air doses in areas at and beyond the SITC BOUNDARY based upon the historical average atmospheric conditions.
The dose due to r.oble gas releases as calculated by the Gross Release Method is much more conservative than the dose calculated by the Isotopic Analysis Method. Assuming the release rates given in l
Radioactive Effluent Dose Assessment, 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 Methed.
Survaillance Requirement 4.8.C.3 Dose, Iodine-131, Iodine-133, Tritium, and Radioactive Material in Pnrticulate Form The cquations for calculating the doses due to the actual release rotos of radioi.odines, radioactive material in particulate form, and rcdionuclides other than noble gases with half-lives greater than 8 days were developed using tne methodology provided in Regulatory Guide l 1.109, "Calculation of Annual Doses to Man from Routine Releases of l
Rocctor Effluents for the Purpose of Evaluating Compliance with 10 CPR Port 50, Appendix I", Revision 1, October 1977, NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants", October 1978, and the atmospheric di!persion
Rev. 2 2880089940 model presented in Information Requested in Enclosure 2 to Lette.' frorg George Lear to E. C. Bauer dated Feoruary 17, 1976, Septemoer 30, 1976. Tnese equations provide for deterc.ining tne actual doses based upon the historical average atmospheric conditionc.
Compliance with the 10 CFR 50 limits for radioiodines, radioactive i materials in particulate form and radionuclides other than noble gases with hal" lives greater than eight days is to be determined by calculat.ng the thyroid dose from iodine-131 releases. Since the i iodine-?31 dose accounts for 92 percent of the total dose to the i thyroid the value calculated is increased by nine percent to account l for the dose from all other nuclidec.
In the event that the plant is shutdown long enough so that iodine-131 is no longer present in gaseous effluents, an Isotopic Analysis Method is available. Since no iodines are present, the critical organ changes from the thyroid to the liver.
l