ML20137X164
| ML20137X164 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 03/03/1986 |
| From: | PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | |
| Shared Package | |
| ML20137X157 | List: |
| References | |
| PROC-860303, NUDOCS 8603050226 | |
| Download: ML20137X164 (116) | |
Text
. - . - . . . . - . . . - - - - - . - . .
i J
i i .
SEABROOK STATION OFF-SITE DOSE CALCULATION MANUAL I
NEW HAMPSHIRE YANKEE I
e i
8603050226 860303 PDR ADOCM 05000443 A PDR
--e - . . , - - -- -,-e - --- w ,. --
ny-, ,--,, , y,. . ,--.,, -w..v--g,--wsesege..wa.. p ,,
DISCLAIMER OF RESPONSIBILITY This document was prepared by Yankee Atomic Electric Company on behalf of New Hampshire Yankee. This document is believed to be completely true and accurate to the best of our knowledge and information. It is authorized for use specifically by Yankee Atomic Electric Company, New Hampshire Yankee and/or the appropriate subdivisions within the Nuclear Regulatory Commission only.
With regard to any unauthorized use whatsoever, Yankee Atomic Electric Company, New Hampshire Yankee and their officers, directors, agents and employees assume no liability nor make any warranty or representation with respect to the contents of this document or to its accuracy or completeness.
) l
-iv-
ABSTRACT The Seabrook Station ODCM (Off-Site Dose Calculation Manual) contains approved methods to estimate doses and radionuclide concentrations occurring beyond the boundaries of the station resulting from normal station operation.
With initial approval, and approval of subsequent revisions by the, Station Management (as per the Technical Specifications), this ODCM is suitable to show compliance where referred to by the Station Technical Specifications.
Sufficient documentation of each method is provided to allow an experienced Health Physicist to understand and regenerate the methods with few references to other material. Most of the methods are presented at two levels. The first, Method I, is typically a linear equation which provides an upper bound and the second, Method II, is an in-depth analysis which can provide more realistic estimates.
-V-
TABLE OF CONTENTS Eage REVISION REC0RD.................................................. ii LIST OF EFFECTIVE PAGES....................................,...... iii 4
OISCLAIMER OF RESPONSIBILITY..................................... iv
~
ABSTRACT......................................................... v LIST OF FIEURES.................................................. viii LIST OF TABLES................................................... ix 1.0 INTR 000CTION..................................................... 1 -1 1.1 Summary of Methods, Dose Factors, Limits, Constants, Variables and Definitions.................................. 1-2 2.0 METHOD TO CALCULATE OFF-SITE LIQUID CONCENTRATIONS............... 2-1 E NG 2-1 2.1 and C 2.2 MethodtoDetermineF}NGMethodtoDetermineRdionuc Concentration 2-2 for Ear.h Liquid Effluent Pathway...........................
2.2.1 Waste Test Tanks Pathway........................... 2-2 2.2.2 Turbine Building Sump Pathway...................... 2-3 2.2.3 Steam Generator Blowdown Flash Tank Pathway........ 2-3 3.0 0FF-SITE DOSE CALCULATION METH0DS................................ 3-1 3.1 Introductory Concepts...................................... 3-2 3.2 Method to Calculate Total Body Dose from Liquid Releases................................................... 3-4 3.3 Method to Calculate Maximum Organ Dose from Liquid Releases................................................... 3-6 3.4 Method to Calculate the Total Body Dose Rate from Noble Gases................................................ 3-8 3.5 Method to Calculate the Skin Dose Rate from Noble Gases.... 3-10 3.6 Method to Calculate the Critical Organ Dose Rate from Iodines, Tritium and Particulates with T1/2 Greater Than 8 Days................................................ 3-12 3.7 Method to Calculate the Gamma Air Dose from Noble Gases.... 3-14 3.B Method to Calculate the Beta Air Dose f rom Noble Gases..... 3-16 3.9 Method to Calculate the Critical Organ Dose from Tritium, Iodines and Particulates................................... 3-18 3.10 Method to Calculate Direct Dose from Plant Operation....... 3-20
-vi- ;
I
. _ . .- , . - _ , - - . _ _ ~ . _.
TABLE OF CONTENTS (Continued)
Pace 4.0 ENVIRONMENTAL MONITORING PR0 GRAM................................. 4 -1 5.0 SETPOINT DETERMINATIONS.......................................... 5-1 5.1 Liquid Effluent Instrumentation Setpoints.................. 5-2 5.2 Gaseous Effluent Instrumentation Setpoints................. 5-9 6.0 LIQUID AND GASEOUS EFFLUENT STREAMS, RADIATION MONITORS AND RADWASTE TREATMENT SYSTEMS................................... 6 -1 7.0 BASES FOR DOSE CALCULATION METH0DS............................... 7-1 8.0 BASES FOR LIQUID AND GASEOUS MONITOR SETP0lNTS................... 8-1 REFERENCES....................................................... R-1
-vii-
LIST OF FIGURES i
Number Title Page 4-1 Radiological Environmental Monitoring Locations Within 4 km of Seabrook Station 4-4 4-2 Radiological Environmental Monitoring Locations Betweep 4 km and 12 km from Seabrook Station 4-5 4-3 _ Radiological Environmental Monitoring Locations Outside 12 km of Seabrook Station 4-6
. 44 Direct Radiation Monitoring Locations Within 4 km of Seabrook Station 4-7 4-5 Direct Radiation Monitoring Locations Between 4 km and 12 km from Seabrook Station 4-8 4-6 Direct Radiation Monitoring Locations Outside 12 km ,
of Seabrook Station 4-9 6-1 Liquid Effluent Streams, Radiation Monitors and Radwaste Treatment System at Seabrook Station 6-9 6 -:' Gaseous Effluent Streams, Radiation Monitors and Radwaste Treatment System at Seabrook Station 6-10
-viii-e
LIST OF TABLES Number Title Pane 1.1 -1 Summary of Radiological Effluent' Technical Specifications and Implementing Equations 1-3 I
- 1.1-2 Summary of Method I to Calculate Unrestricted Area Liquid Concentrations 1-6 1.1-3 Summary of Method I to Calculate Off-Site Doses from Liquid Releases 1-7 1.1-4 Summary of Method I to Calculate Dose Rates 1-8 1.1-5 Summary of Method I to Calculate Doses to Air from Noble Gases 1-9 1.1-6 Summary of Method I to Calculate Dose to an Individual from Tritium, Iodine and Particulates 1-10 1.1-7 Summary of Methods for Setpoint Determinations 1-11 1.1-8 Summary of Variables 1-12 1.1-9 Definition of Terms 1-16 1.1-10 Dose Factors Specific for Seabrook Station for Noble Gas 1-17 Releases 1.1-11 Dose Factors Specific for Seabrook Station for Liquid Releases 1-18 e
1.1-12 Dose and Dose Rate Factors Specific for Seabrook Station for Tritium, lodine and Particulate Releases 1-19 1.1-13 Combined Skin Dose Factors Specific for Seabrook Station Special Receptors for Noble Gases 1-20 1.1-14 Dose and Dose Rate Factors Specific for Seabrook Station Special Receptors for lodines, Tritium and Particulates 1-21 4.1 Radiological Environmental Monitoring Stations 4-2
-ix-
LJST OF TABLES (Continued)
Number Title Page 7.1-1 Usage Factors for Various Liquid Pathways at 4 Seabrook Station 7-4
- r.
- 7. 2-1 Environmental Parameters for Gaseous Effluents at Seabrook Station 7-22 7.2-2 Usage Factors for Various Gaseous Pathways at Seabrook Station 7-23
- 7. 3-1 Seabrook Station Dilution Factors 7-27 7.3-2 Seabrook Station Dilution Factors for Special Receptors 7-28
-X-
)
l
1.0 INTRODUCTION
This ODCM (Off-Site Dose Calculation Manual) provides formal and approved methods for the calculation of off-site concentration, off-site doses and effluent monitor setpoints, and indicates the locations of environmental monitoring stations in order to comply with the Seabrook Station : Technical Specifications 3/4.3.3.9, 3/4.3.3.10, 3/4.11 and 3/4.12, hereaf ter ref erred to as the Radiological Effluent Technical Specifications (RETS). The ODCM forms the basis for station procedures which document the off-site doses due to station operation.
Revisions must be reviewed and accepted by SORC (see Technical Specification 6.14). The NRC requires notification of revision, but not prior approval.
The methods contained herein follow accepted NRC guidance, unless otherwise noted in the text. The basis for each method is sufficiently documented to allow regeneration of the methods by an experienced Health Physicist.
1 -1
1.1 Summary af Methods. Dose Factors. Limits. Censtants. Variables and Definitions This section sunenarizes the Method I dose equations which are used as the primary means of demonstrating compliance with RETS. The concentration j and setpoint methods are identified in Table 1.1-2 through Table :1.,1-7. Where more refined dose calculations are needed, the use of Method II dose deteminations are described in Sections 3.2 through 3.9 and 3.11. The dose factors used in the equations are in Tables 1.1-10 through 1.1-14 and the Regulatory Limits are summarized in Table 1.1-1.
The variables and special definitions used in this DCCM are in Tables 1.1-8 and 1.1-9.
1-2 l
TABLE 1.1-1 Summerv of Radiological Effluent Technical Specifications and Imp _lemenli_ng_E_quations 1
Technical (1)
Specification Category Method I limit 3.11.1.1 Liquid Effluent Total Fraction cf Eq. 2-1 5 1.0 Concentration MPC Excluding Noble Gases Total Noble Gas Eq. 2-2 5 2 x 10-4 pCi/ml Concent ration 3.11.1.2 Liquid Effluent Total Body Dose Eq. 3-1 5 1.5 mrem in a qtr Dose S 3.0 mrem in a yr.
Organ Dose Eq. 3-2 5 5 mrem in a qtr.
7 5 10 mrem in a yr.
u 3.11.1.3 Liquid Radwaste Total Body Dose Eq. 3-1 5 0.06 mrem in a mo.
Treatment Operability Organ Dose Eq. 3-2 5 0.2 mrem in a mo.
3.11.2.1 Gaseous Effluents Total Body Dos? Rate Eq. 3-3 5 500 mrem /yr.
Dose Rate from Noble Gases Skin Dose Rate Eq. 3-4 5 3000 mrem /yr.
from Noble Gases i Organ Dose Rate Eq. 3-5 51500 mres/yr.-
f rom I-131, 1-133, .
Tritium and Particulates with T1/2 > 8 Days .
TABLE 1.1-1 (continued)
Sumary of Radiological Ef fluent Technical Specifications i and Implementing E_quations Technical (1)
Specification Category Method I t.imit Gaseous Effluents Gama Air Dose f rom Eq. 3-6 5 5 mrad in a qtr.
3.11.2.2 Dose from Noble Noble Gases Gases 5 10 mrad in a yr.
Beta Air Dose from Eq. 3-7 5 10 mrad in a qtr.
Noble Gases 5 20 mrad in a yr.
Gaseous Effluents Organ Dose from Eq. 3-8 5 7.5 mrem in a qtr.
3.11.2.3 Dose f rom I-131, lodines, Tritium and I-133. Tritium, Particulates with 5 15 mrem in a yr.
g and Particulates 11/2 > 8 Days 3.11.2.4 Ventilation Organ Dose Eq. 3-8 5 0.3 mrem in a mo.
Exhaust Treatment Total Body Dose Footnote (2). 5 25 mrem in a yr.
3.11.4 Total Dose (from All Sources)
Organ Dose 5 25 mrem in a yr.
Thyroid Dose 5 75 mrem in a yr.
.s-i i
1&Bl_E 1.1-1 (continued)
Summary of Radiological Effluent Technical Specifications an_d Implementing E_quations Technical (1)
Specification Category _ Method I Limit 3.3.3.9 Liquid Effluent Monitor Setpoint Liquid Waste Test Alarm Setpoint Eq. 5-1 T.S. 3.11.1.1 Tank Monitor 3.3.3.10 Gaseous Effluent Monitor Setpoint 7 Plant Vent Alarm / Trip Setpoint Eq. 5-9 T.S. 3.11.2.1
'a Wide Range Gas for Total Body Dose (Total Body)
Monitors Rate Alarm / Trip Setpoint Eq. 5-10 T.S. 3.11.2.1 for Skin Dose Rate (Skin)
(1)
More accurate methods may be available (see subsequent chapters).
(2)
Technical Specification 3.11.4.a requires this evaluation only if twice the limit of equations 3-1, 3-2, 3-12, 3-15 or 3-18 is reached. If this occurs a Method II calculation, using actual meteorology and identified pathways for a real individual, shall be made.
i i
TABLE 1.1-2 Summary of Method I Ecuations to Calculate Unrestricted Area Liouid Concentrations Equation Number Category Ecuation 2-1 Total Fraction of MPC in p ENG , i g )
- Liquids, Except Noble Gases 1 MPC g 2-2 Total Activity of Dissolved NG vCi 0 and Entrained Noble Gases C
1 ml)=f~C i4 from all Station Sources < 2E-04 f
9 l
1 1
1-6
TABLE 1 1-3 Summary of Method i Ecuations to Calculate Off-Site Doses from Liouid Re]easeg Equation Number Categorv .
Ecuation 3-1 Total Body Dose Dtb(arem) = Qi DFL itb g
3-2 Maximum Organ Dose D
mo(mrem) = Qi DFL imo 4
l i
{
e 4
a 1-7
TABLE 1.1-4 Summary of Meth.pd_I Ecuations to Calculate Rose Ratel Equation
_ Number __
Category fauation 3-3 Total Body Dose Rate from Noble 6ases j tb g erem)=.43)hDF8 yr i i 4
3-4 Skin Dose Rate fskin (mrem)
)I
=9{ hi i DF' from Noble Gases yr
^
3-5 Critical Organ Dose .
r-Rate from Iodines, DFG gg, i Tritium Og , (*"'r ) " i- i and Particulates with T 1/2 Greater Than Eight Days ,
t t
l h
e 1-8 ,
Tgt,.E_1,1 -5 WS of Methed 1 tauations to Calt.olate Ooses to Air f mni Noble Gases ,
Equation Number Category Equation [
3-6 Gamne Dose to Air T T Qi DF 1 from Noble Eases Dair (mrad) = 2.00-08 g 1
3-7 Beta pose to Air 5 0l W i
) from Noble Gases Dair (2 rad) = 4,4E-08 q a
e l ,
4 d o 1
i 1
a >
s i
l l
l k
k l
4 l !
4 i
l i '
i i
1-9 ,
i I
l
, _..___ ,__ . _ . . . . . - _ ~ . _ _ _ ,. . . , . . . . . _ _ _ . . _ , _ _ _ _ _ _ _ _ _ . _ . , , - .. _.. ,, , . , , . _ _ , . , _ . _ _ , _
TABLE 1.1-6
}ygunary of Method I Equations to Calculate Oose to an Indivitfeci from Tritium. 10 dine arid Particulates Equation Number Category _
Ea> gat _t on _ _ _ _
3-8 Dose to Critical Dg , (wem) = { Og bm,,,
organ from Iodines, j Tritium and Particulates 4
1 v
l 1
4
.j k
i i
i
's 1-10 4
, - - ,- -- ... , - , , . , . , . - , .- , . . - . - - , . - - - - - , - - . , , , , -,---e,- - ,. - .- - , - - - < -
-. ~ . . . . . .. . ... ._ ---__m. .
TABLE 1.1-7 Sewary of Methods for Setooint Determiration a
Equation
+
Number _
Category EQuatior. ,
5-1 Liquid (ffluents:
Liquid Waste Test DF Tank Monitor gsetpoint ( g ) ,DF ain g"
,) i (RM-6509)
Gaseous Effluents:
Plant Vent blide Range Gas Monitors (RM-6528-1, 2, 3) 5-5 Total Body 0 11 Ntb ( M3 }" F DFB c
cm 5-6 Skin R 1 1 skin ( $ )= 3000 i DF' j Cm ,
j e
t f
1-11
(
t J
l I
.. . , . . . . , _ . _ - . . _ - ~ _ . - _ . _ , , . _ , . . , , _ , , - _ ._ - . . _ , , , _ . . , _ _ - ,
J191E 1 1-8 Summarv of Yarlebt.es ,
Variable _
Definftion y,nj,ti C = Concentration at point of discharge cf , >C1/ml ,
dissolved and entrained noble gas "i" in -' -
liquid pathways f rom al) station sacrees E~ s Total actietty of all dissolved ar.d entrained gC_i C
noble gr.ses in liquid pathways froen all mi station sot,rce3 Concentration of radionucMCe "1" at the peint gC_t ,
C,g a
al of liquid discharge Eg = Concentration of radionuclide "i" vCi/cc C
pg
= Concentration, exclusive of noble gases., of E1 C radionuclide "i" from tank 'Q" at point of El discharge C
gg = Concentration of radionuclide "1" in mbttur: Ai/ml i at the monitor 0 = Beta cose to air wrad r
D = Beta dose for cir et Education Center mrad ir E 0
frR
= leta dose to air et "Rs:ks" mrad
)
= GanYnc dose to air mrad Ca fr
= Ganna dose to air it Education Center mrad
$ Ohr E
= 6ansna dose to air at " Rocks" mrad 1
Oj g,,,y mrem D, = Oose to the critical organ C = Direct dose mrem d
8 = &ama d se to air, corrected for finite cloud mrad finite 1-12 i
J
TABLE 1.1-8 (continued [
Sumnary of Variables Definition Units fariable
= Cose to the maximum organ : . arem D,
5 S ~ = Dose to skin from beta and gamma arem O
= Dose to the tetal body erem D
tb
= Dilution factor ratio DF
= Ninimum allowable di'iution factor ratio DF min 'l 3 ;
= Composite skin dose factor mrem-m D F *' pCi-yr DFB = Total body gimmt dose factor for nuclide 'i [r 9
~
OfB = Composite total body dose factor y e
OR = Site-specific, total boJy dose f actor for a meen ite Ci liquid release of nuclide "i" DFL = Site-specific, maximum crgan dose factor for a mrem I" liquid release of nuclide "i" Ci DFG = Site-specific, criticel organ dose f actor for a mrem gaseoas release of nuclide "i" Ci
= Site-spe-ific, critical organ dose rate fe.ctor meer-see 0FG'ci for a gasecos release of nuclide '1" yti-yr 3
mrem-m 1
= Beta SF.in tot e facter f or nuclide "i" pCi-yr
- DFj = Com*aines skin dose factor for nur.lide *1" C r OF} = Gama air dose factor for nuclide "i" C-1-13 e
1
, - . , . - - e n..,, - - - -
TABLE 1.1-8 (continued)
Summary of Variables r
Variable Definition Units CF = Beta air dose factor for nuclide "1" Cy b = Critical orgen dose rate due to iodines C
and particulates b = Skin dose rate due to noble gases r skin i
b = T tal bcdy dose rate due to noble gases tb a
, D/Q = Deposition factor for dry deposition of sec elemental radioicdines and other particuittes ,2 F = Flow rate out cf discharge canal gpm d
F, = Flow rate past liquid waste test tank monitor gpm 1 ,
F = Flow rate past plant vent monitor cc sec F = Total fraction of MPC in liquid pathways fraction (excluding noble gases)
MPC = Maximum permissible concentration for uC1 radionuclide di" (10CFR20, Appendix E, cc Table 2. Column 2) ;
Q$ = Release to the envircoment for curies radionuclide "i" Qg = Release rate to the environnent for scuries/sec radionuclide "i" R = Liquid monitor response for the limiting cps !
setpoint concentration at the point of discharge f
R = Resp nse of the noble gas monitor at the cpm hin limiting skin dose rate R = Response of the noble gas monitor to cpm tb limfting total body dose rate Sp = Shielding factor Ratio 1-14
I TABLE 1.1-8 i
(c ntinued)
Summary of Variables Variable Definition Units
= Detector counting ef ficiency f rom the : .CDm mR/hr S
yC1/cc r pCi/cc I gas monitor calibration
= Detector counting efficiency for noble com mR/hr S -
or pC1/cc I gas "i" Sci /cc
= Detector counting ef ficiency from the cos Sj liquid monitor calibration pC1/mi S jj = Detector counting efficiency for cos radionuclide "i" pC1/ml 5
X/0 = Average undepleted atmospheric dispersion factor m{C 5'C
[X/Q]Y = Effe:tive average gamma atmospheric 3 dispersion factor m
[
1-15 1
,- . - - . . - , - --- .-._-..n. - .- .. -
2 TABLE 1.1-9 l Definition of Terns 3 r 4
Critical Receptor - A hypothetical individual whose location and behavior i
cause him or her to receive a dose greater than any possible real individual.
Egig - As used in Regulatory Guide 1.109, the term " dose." when applied to individuals, is used instead of the more precise term ' dose equivalent," as j defined by the International Commission on Radiological Units and Measurements J (ICRU). When applied to the evaluation of internal deposition or radioactivity, the term " dose," as used here, includes the prospective dose l
! component arising f rom retention in the body beyond the period of environmental exposure, i.e., the dose commitment. The dose commitment is
]
I evalcated over a period of 50 years. The dose is measured in mrem to tissue or mrad to air.
Dose Rate - The rate for a specific averaging time (i.e., exposure period) of l dose accumulation.
4 Licuid Padwaste Treatment System - The components or subsystems which comprise
! the available treat.nent system as shown in Figure 6-1.
! l l
- I i i
I i P
i :
- t 1
l t
i !
i
]
i 1-16 i
i i
i
! F
---.-,,.4- .,.#-- _ . - -, , , , , - - - . . - , . - , ..,.,,y,,-
- - - - . - - . , ,,-mw. ..,_-,,,---,...-....--,---,,,---.,.,..-.m. . ~ , , . .
TABLE 1.1-10 >
Dose Factors Specific for Seabrook Station for hople Gas Releases Gama Total Body Beta Skin Combined Skin Beta Air: ,
Gamma Air Dose Factor Dose Factor Dose Factor Dose Factor' Dose Factor
- Radionuclide DFB 3 (arem-m DFS $(mrem-m)0Fj(arem-sec) DF8 (mrad-m ) DF} I (mrad-m DCi-vr DCi-vr ) DCi-vr uCi-vr $ oCi-vr Ar-41 8.84E-03* 2.69E-03 8.18E-03 3.28E-03 9.30E-03 Kr-83m 7.56E-08 9.26E-06 2.88E-04 1.93E-05 Kr-85m 1.17E-03 1.46E-03 2.61E-03 1.97E-03 1.23E-03 Kr-85 1.61E-05 1.34E-03 1.86E-03 1.95E-03 1.72E-05' Kr-87 5.92E-03 9.73E-03 1.64E-02 1.03E-02 6.17E-03 Kr-88 1.47E-02 2.37E-03 1.06E-02 2.93E-03 1.52E-02 Kr-89 1.66E-02 1.01E-02 2.22E-02 1.06E-02 1.73E-02 Kr-90 1.56E-02 7.29E-03 1.79E-02 7.83E-03 1.63E-02 Xe-131m 9.15E-05 4.76E-04 7.32E-04 1.11E-03 1.56E-04 Xe-133m 2.51E-04 9.94E-04 1.53E-03 1.48E-03 3.27E-04 Xe-133 2.94E-04 3.06E-04 5.92E-04 1.05E-03 3.53E-04 Xe-135m 3.12E-03 7.11E-04 2.59E-03 7.33E-04 3.36E-03 Xe-135 1.81E-03 1.86E-03 3.49E-03 , 2.46E-03 1.92E-03 Xe-137 1.42E-03 1.22E-02 1.76E-02 1.27E-02 1.51E-03 Xe-138 8.83E-03 4.13E-03 1.01E-02 4.75E-03 9.21E-03
- 8.84E-03 = 8.84 x 10-3 1
1-17
TABLE 1 1-11 -
Dose Factors Specific for Seabrook Station for Liouid Releases i
Total Body Maximum Organ Dose Factor Oose Factor OFL Iarem) ORg ,,(arem) uci Radionuclide ith uCi 3.02 E-13 3.02E-13 H-3 1.48E-09 Cr-51 1.83 E-11 5.14E-09 2.68E-08 Mn-54 7.67E-08 Fe-55 1.26E-08 8.74E-08 6.66E-07 Fe-59 1.40E-08 Co-58 2.45E-09 6.14E-09 9.21E-08 Co-60 5.49E-07 2n-65 2.49E-07
- 1. 31 E-14 1.89E-14 Br-83 6.96E-10 Rb-86 4.18E-10 Sr-89 2.17E-10 7 M -03 3.22E-08 1. 31 E-07 sr-90 2.62E-10
'Mo_g 9 3.10E-11 4.95 E-11 7.76E-11 Tc-99m 7.07E-08 1.81E-06 Te-127m 3.50E-10 9 A6E-08
- Te-127 1.54E-07 3.46E-06 Te-129m 6.97E-14 8.22E-14 Te-129 Te-131m 3.16E-08 2.94E-06 i Te-132 9.05E-08 3.80E-06 2.77E-11 3.20E-09 I-130 i 1-131 2.21 E-10 1.00E-07 3.30E-12 4.03E-11 I-132 Il I-133 2.SSE-11 1.15E-08 I-134 1.18E-12 1.40E-12 I-135 8.84E-12 4.39E-10 Cs-134 3.24E-08 3.56E-08 Cs-136 2.46E-Og 3.27E-09 Cs-137 3.58E-08 4.03E-08 Ba-140 1.61 E-10 3.4BE-09 La-140 5.13E-11 4.13E-08 Ce-141 3. 67 E-11 9.31E-09 Ce-144 1.95E-10 6.46E-08 Np-239 4.18E-10 6.96E-10 1-18 e
l
TA8LE 1.1-12 Dose and Dose Rate Factors SDecific for Seabr00k Station for lodines. Tritium and Particulate Releases Critical Organ Critical Organ Dose Factor Dole. Rate Factor arem-sec Radionuclide DG 4c,(mrem) uCi ico I vr-uCi I H-3 2.15E-10 6.78E-03 C-14 1.45E-07 4.57E+00 Mn-54 8.05E-08 2.54E+00 Fe-59 8.83E-08 2.78E+00 Co-58 5.33E-08 1.68E+00 Co-60 3.46E-07 1.09E+01 Zn-65 1.06E-06 3.34E+01 Sr-89 2.97E-06 9.37E+01 Sr-90 1.25E-04 3.94E+03 Mo-99 1.44E-08 4.54E-01 1-130 7.32E-08 2.31E&O0 1-131 2.83E-05 8.93E+02 I-132 7.67E-09 2.42E-01 1-133 2.64E-07 8.33E+00 1-134 2.01E-09 6.34E-02 1-135 3.14E-08 9.90E-01 Cs -134 9.84E-06 3.10E+02 Cs-137 9.28E-06 2.93E+02 Ce-141 3.16E-08 9.97E-01 Ce-144 8.93E-07 2.82E+01 1-19
x 4
TA8LE 1,1-13 Combined Skin Dose Fa'ctors SDecific for Seabrook Station SDecial ReceDtorstlJ for Noble Gas Release
/
Education Center The " Rocks' Combined Skin Combined Skin .
Dose Factor Dose Factor
""~5'C **~5
Radi_onuclide DFjE("uCi-vr) DFjR("vCi-vr )
- 3.2SE-02 1.03E-01 Ar-41 2.99E-05 8.82E-05 Kr-83m 1.17E-02 3.85E-02 Kr-85m 9.02E-03 3.02E-02 Kr-85 7.49E-02 2.47E-01 Kr-87 3.95E-02 1.22E-01 Kr-88 '
9.46E-02 2.92E-01 Kr-89 ,
7.42E-02 2.38E-01 Kr-90 3.44E-03 1.14E-02 Xe-131m Xe-133m 7.18E-03 2.38E-02 g
Xe-133 2.60E-03 8.49E-03 Xe-135m 9.98E-03 3.13E-02 Xe-135 1.55E-03 5.06E-02
- Xe-137 8.42E-02 2.81E-01 Xe-138 3.25E-02 1.35E-01 t
i.
(I) See Seabrook Station Technical Specification Figure 5.1-1.
I u r
\ >
a
%0 6
4 1-20
's m
"~ " - - - _, ,mm ,
1 TABLE 1.11-14 Dose and Dose Rate Factors Specific for Seabrook Station Special Receptorsl U for Iodine.
Tritium and Particulate Releases Education Center The " Rocks".
Critical Organ Critical Organ Critical Organ . Critical Organ Dose Factor Oose Rate Factor Dose Factor Dose Rate Factor mrem-sec OFG ge,g(arem) DFG, cop vti-vr (mrem-sec) icoE Iarem) DFG icoE I g
- Radronuclide DFG Ci vCi-vr J Ci 8.55E-03 9.07E-10 2.86E-02 H-3 2.71E-10 8.07E-01 C-14 7.63E-09 2.41E-01 2.56E-08 1.22E+01 1.29E-06 4.07E+01 Mn-54 3.87E-07 3.13E+01 Fe-59 2.98E-07 9.40E+00 9.93E-07 8.26E+00 8.73E-07 2.75E+01 Co-58 2.62E-07 1.79E+02 Co-60 1.70E-06 5.36E+01 5.67E-06 7.63E-01 8.06E-07 2.54E+00-Zn-65 2.42E-07 1.49E+01 1.57E-06 4.95E+01 Sr-89 4.72E-07 1.02E+02 1.07E-05 3.37E+0?
Sr-90 3.22E-06 1.66E-01 1.75E-07 5.52E-01 Mo-99 5.25E-07 1.14E+01 1.20E-06 3.78E+01 1-130 3.61E-07 3.17E-06 1.00E+02 1.06E-05 3.34E+02 I-131 3.97E+00 1-132 3.78E-08 1.19E+00 1.26E-07 7.51E-07 2.37E+01 2.50E-06 7.89E+01 1-133 1.04E+00 1-134 9.90E-09 3.12E+01 3.29E-08 1.55E-07 4.89E+00 5.15E-07 1.62E+0) 1-135 2.31E+01 Cs-134 2.20E-07 6.94E+00 7.33E-07 5.24E+00 5.51E-07 1.74E+01 Cs-137 1.66E-07 1.20E-07 3.78E-01 3.99E-07 1.26E+00 Ce-141
- 2. 61 E-06 8.23E+00 8.68E-06 2.74E+01 Ce-144 (I) See Seabrook Station Technical Specification Figure 5.1-1.
1-21 1
1
I 2.0 METHOD TO CALCULATE OFF-SITE L10VID CONCENTRATIONS Chapter 2 contains the basis for station proceoures that the station i operator requires to meet Technical Specification 3.11.1.1 which limits the !
total fraction of MPC in liquid pathways, other than noble gases, denoted here as F "0, at the point of discharge f rom the station to the environment NG is limited to less than or equal to one, i.e..
(see Figure 6-1). F F1 "O < l .
The total concentration of all dissolved and entrained noble gases at the point of discharge from the multiport diffuser f rom all station sources combined, denoted C , is limited to 2E-04 pCi/ml, i.e.,
Cf52E-04pCi/ml.
0 Evaluation of F "6 and C is required concurrent with the sampling and analysis program in Technical Specification Table 3.12.1.
b 2.1 Method to Determine F and C First, determine the total fraction of MPC (excluding noble gases), at the point of discharge f rom the station f rom all significant liquid sources denoted F ; and then separately determine the total concentration at the point of discharge of all dissolved and entrained noble gases from all NG station sources, denoted C , as follows:
FENG , p .1 < l .
2-1) 1 MPC 4 $
IuCi/ml) pCi/ml and:
2-1
C = C 1 2E-04 (2-2) 4 ,(pci/ml) (pCi/ml) (pCi/ml) i where:
( .
0 = Total fraction of MPC in liquids, excluding noble F
gases, at the point of discharge from the multiport diffuser Cp ,j = Concentration at point of discharge from the multiport dif fuser of radionuclide "i", except for dissolved.and entrained noble gases, f rom all tanks and other significant sources, p, from which a discharge may be made (includmg the waste test tanks and any other significant source from which a discharge can be made) (pC1/ml)
NFCj = Maximum permissible concentration of radionuclide "i" except for dissolved and entrained noble gases from 10CFR20, Appendix B, Table II, Column 2 (vCi/ml)
= Total concentration at point of discharge of all dissolved i
Cf and entrained noble gases in liquids from all station j sources (pCi/ml)
C = Concentration at point of discharge of dissolved and entrained noble gas "i" in liquids f rom all station sources (vCi/ml) 2.2 Method to Determine Radionuclide Concentration for Each Liouid Effluent Source 2.2.1 Waste Test Tanks i
+
C is determined for each radionuclide above the LLD f rom the activityinaproportionalgrabsgmpleofanyofthewastetesttanksandthe i predicted flow at the point of discharge.
l The batch releases are normally made from two 25,000-gallon capacity waste test tanks. These tanks normally hold liquid waste evaporator 1
distillate. The waste test tanks can also contain other waste such as liquid taken directly from the floor drain tanks when that liquid does not require processing in the evaporator, distillate f rom the boron recovery evaporator when the BRS evaporator is substituting for the waste evaporator, and 2-2 l
l
distillate from the Steam Generater Blowdown System svaporators and flash steam condensers when that system must discharge liquid of f-site.
If testing indicates that purification of the waste test tank contents is required prior to release, the liquid can be circulated through the waste demineralizer and filter. ! .
- The contents of the waste test tank may be reused in the Nuclear System if the sample test meets the purity requirements.
Prior to discnarge, each waste test tank is analyzed for principal gamne emitters.
2.2.2 Turbine Building Sump The Turbine Building sump collects leakage from the Turbine Building floor drains and discharges the liquid unprocessed to the environment.
Sampling of this potential source is done once per week for determining the radioactivity released to the environment.
2.2.3 Steam Generator Blowdown Flash Tank The steam generator blowdown evaporators normally process the liquid f rom the steam generator blowdown flash tank when there is primary to secondary leakage. Distillate from the evaporators is sent to the waste test tanks. When there is no primary'to secondary leakage, flash tank liquid is processed through the condensate demineralizers and returned to the secondary side.
Steam generator blowdown is only subject to sampling and analysis when all or part of the blowdown liquid is being discharged to the environment instead of the normal recycling process.
2-3
3.0 OFF-SITE DOSE CALCULATION METHODS Chapter 3 provides the basis for station procedures required to meet the Radiological Effluent Technical Specifications (RETS) dose o'r dose rate requirements contained in Section 3/4.11 of the station operating Technical Specifications. A simple, conservative method (called Method I) is listed in Tables 1.1-2 to 1.1-7 for each of the requirements of the RETS. Each of the Method I equations is presented in Sections 3.2.
through 3.9. In addition, those sections include more sophisticated methods (called Method II) for use when more refined results are needed. This chapter provides the methods, data, and reference material with which the operator can calculate the needed doses, dose rates and setpoints.
The bases for the dose and dose rate equations are given in Chapter 7.0.
The semiannual radioactive effluent release report to be filed after l January 1 each year requires that meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents, as determined by sampling frequency and measurement, be used for determining the gaseous pathway doses. For continueus release sources (i.e. plant vent, condenser air removal exhaust, and gland steam packing exhauster).
concurrent quarterly average meteorology will be used in the dose calculations along with the quarterly total radioactivity released. For batch releases or identifiable operational actvities (i.e. containment purge, or venting to atmosphere of the waste cas system) concurrent meteorology during the period of release will be used to determine dose if the total noble gas or iodine and particulates released in the batch exceeds 5 percent of the total quarterly radioactivity released from each unit, otherwise quarterly average meteorology will be applied. Quarterly average meteorology will also be applied to batch releases if the hourly met data for the period of batch release is unavailable.
4 3-1 4
3.1 Introductory Crncepts In part, the Radiological Effluent Technical Specifications (RETS) limit dose or dose rate. The term " dose" for ingested or inhaled radioactivity means the dose comitment, measured in mrem, which results f rom the exposure to radioactive materials that, because of uptake and deposition in the body, will continue to expose the body to radiation for some period of time after the source of radioactivity is stopped. The time frame over which the dose comitment is evaluated is 50 years. The phrases " annual dose" or dose in one year" then refers to the 50-year dose comitment resulting from exposure to one year's worth of releases. " Dose in a quarter" similarly means the 50-year dose comitment resulting f rom exposure to one quarter's releases. The term " dose," with respect to external exposures, such as to noble gas clouds, refers only to the doses received during the actual time period of exposure to the radioactivity released from the plant. Once the source of the radioactivity is removed, there is no longer any additional accumulation to the dose commitment.
" Dose rate" is the total dose or dose commitment divided by exposure period. For example, an individual who is exposed via the ingestion of milk for one year to radioactivity f rom plant gaseous effluents and receives a 50-year dose comitment of 10 mrem is said to have been exposed to a dose rate of 10 mrem / year, even though the actual dose received in the year of exposure may be less than 10 mrem.
In addition to limits on dose commitment, gaseous effluents from the station are also controlled so that the maximum or peak dose rates at the site l boundary at any time are limited to the equivalent annual dose limits of 10CFR, Part 20 to unrestricted areas (if it were assumed that the peak dose rates continued for one year). These dose rate limits provide reasonable assurance that members of the public, either inside or outside the site boundary, will not be exposed to annual averaged concentrations exceeding the limits specified in Appendix B, Table II of 10CFR, Part 20 (10CFR20.106(b)).
ThequantitiesADandbareintroducedtoprovidecalculable quantities, related to off-site doses or dose rates that demonstrate compliance with the RETS.
3-2
Delta D, denoted AD, is the quantity calculated by tha Chapter 3 Method I dose equations. It represents the conservative increment in dose.
The AD calculated by Method I equations is not the actual dose received by a real individual, but usually provides an upper bound for a given release because of the conservative margin built into the dose factors and the '
selection and definition of critical receptors. The radionuclide: specific dose factors in each Method I dose equation represent the greatest dose to any organ of any age group. (Organ dose is a function of age because organ mass and intake are functions of age.) The critical receptor assumed by " Method I" equations is then a hypothetical individual whose behavior - in terms of location and intake - results in a dose which is higher than any real individual is likely to receive. Method II allows for a more exact dose calculation for each individual if necessary.
D dot, denoted b, is the quantity calculated in the Chapter 3 dose rate equations. It is calculated using the station's effluent monitoring system reading and an annual average atmospheric dispersion factor. D predicts the maximum of f-site annual dose if the peak observed radioactivity release rate from the plant stack continued for one entire year. Since peak release rates, or resulting dose rates, are usually of short time duration on the order of an hour or less, this approach then assures that 10CFR20.106 limits will be met, with a large conservative margin.
Each of the methods to calculate dose or dose rate are presented in separate sections of Chapter 3, and are summarized in Tables 1.1-1 to 1.1-7.
Each method has two levels of complexity and conservative margin called Method I and Method II. Method I has the greatest margin and is the simplest; generally a linear equation. Method II is a more detailed analysis which allows use of site-specific factor and variable parameter to be selected to best fit the actual release. Guidance is provided, but the appropriate margin and depth of analysis are determined in each instance at the time of analysis under Method II.
3-3
3.2 Meth*d to Calculate the Total Body Dose from Liouid Releases Technical Specification 3.11.1.2 limits the total body dose commitment to a member of the public from radioactive material in liquid effluents to 1.5 arem per quarter and 3 mrem per year per unit. Technical Specification 3.11.1.3 requires liquid radwaste treatment when the total body dos,e estimate exceeds 0.06 mrem in any 31-day period. Technical Specification 3.11.4 limits the. total body dose commitment to any real member of the public from all station sources (including liquids) to 25 mrem in a year.
Use Method I first to calculate the maximum total body dose from a liquid release from the station as it is simpler to execute and more conservative than Method II.
Use Method II if a more refined calculation of total body dose is needed (i.e., Method I indicates the dose might be greater than the Technical Specification limits), or if Method I cannot be applied.
To evaluate tte total body dose, use Equation 3.1 to estimate the dose from the planned release and add this to the total body dose accumulated from prior releases during the month. See Section 7.1.1 for basis.
3.2.1 Method I The increment in total body dose from a liquid release is:
O " Oi 0FL itb (3-1) tb i (mrem) (vCi) ( C I where:
OFlitb = Site-specific total body dose factor (mrem /uti) for a release. It is the highest of the four age groups. See Table 1.1.11.
Qi = Total activity (uti) released for radionuclide "i". (For strontiums, use the most recent measurement available.)
3-4
Equaticn 3-1 can be cpplied under the following ccnditions (otherwise, justify Method I or consider Method II):
- 1. Liquid releases via the multiport diffuser to unrestricted areas (at the edge of the initial mixing or prompt dilution zone), and
- 2. Any continuous or batch release over any time period.
3.2.2 Method II If Method I cannot be applied, or if the Method I dose calculations appear to exceed a Technical Specification limit or if a more exact calculation is required, then Method II should be a'pplied. Method II consists of the models, input data and assumptions in Regulatory Guide 1.109, Rev. 1 (Reference A), except where site-specific models, data or assumptions are more applicable. The general equations and parameters taken from Regulatory Guide 1.109, and used in the derivation of the simplified Method I approach as described in the Bases section, can also be applied to a Method II assessment, which, in addition, incorporates site receptor-specific information which coincides conditions at the time of release, such as identified pathways of exposure.
N i
3-5
3.3 Method to Calculate Maximum Oroan Dose from Licuid Releases Technical Specification 3.11.1.2 limits the maximum organ dose comitment to a Member of the Public f rom radioactive material in liquid effluents to 5 mrem per quarter and 10 mrem per year per unit. Technical Specification 3.11.1.3 requires liquid radwaste treatment when tite snaximum organ dose estimate exceeds 0.2 mrem in any 31 days. Technical Specification 3.1U.4 limits tne maximum organ dose commitment to any real member of the public from all station sources (including liquids) to 25 mrem in a year except for the thyroid, which is limited to 75 mrem in a year. Dose evaluation is required at least once per 31 days.
Use Method I first to calculate the maximum organ dose from a liquid release to unrestricted areas (see Figure 6-1) as it is simpler to execute and more conservative than Method II.
Use Method II if a more refined calculation of organ dose is needed (i.e., Method I indicates the dose may be greater than the limit), or if Method I cannot be applied.
Use Equation 3-2 to estimate the maximum organ dose from individual or combined liquid releases. See Section 7.1.2 for basis.
3.3.1 Method i The increment in maximum organ dose from a liquid release is:
0 = Q DFL (3-2) mo 3
i imo (mrem) (pCi) ( *)
where:
DFl imo - Site-specific maximum organ dose factor (mrem /uti) for a liquid release. It is the highest of the four age groups.
See Table 1.1-11.
Qj = Total activity (pCi) released for radionuclide "i". (For i strontiums, use the most recent measurement available.)
! 3-6
Equati:n 3-2 can be applied under the following conditions (otherwise, justify Method I or consider Method II):
- 1. Liquid releases via the multiport diffuser to unrestricted areas (at the edge of the initial mixing or prompt dilution zone), and t
- 2. Any continuous or batch release over any time period.
3.3.2 Method II If Method I cannot be applied, or if the Method I dose calculations appear to exceed a Technical Specification limit, or if a more exact calculation is required, then Method II should be applied. Method 11 consists f of the models, input data and assumptions in Regulatory Guide 1.109, Rev.1 (Reference A), except where site-specific models, data or assumptions are more applicable. The general equations and parameters taken f rom Regulatory Guide 1.109, and used in the derivation of the simplified Method I approach as
! described in the Bases section, can also be applied to a Method II assessment, which, in addition, incorporates site receptor-specific information which coincides conditions at the time of release, such as identified pathways of exposure.
3-7
3.4 Method to Calculate the Total Body Dose Rate From Noble Gases Ter.hnical Specification 3.11.2.1 limits the dose rate at any time to the total body from noble gases at any location at or beyond the site boundary to 500 mrem / year. The Technical Specification indirectly limits peak release rates by limiting the dose rate that is predicted from continued! release at the peak rate. By limiting D tb to a rate equivalent to no more than 500 mrem / year, we assure that the total body dose accrued in any one year by any member of the general public is less than 500 mrem.
Use Method I first to calculate the Total Body Dose Rate from the peak
) Method I applies at all release release rate via the station vents .
rates.
is desired by the UseMethodIIifamorerefinedcalculationofhtb station (i.e., use of actual meteorology and release-specific X/Qs) or if Method I predicts a dose rate greater than the Technical Specification limit ,
to determine if it had actually been exceeded during a short time interval.
See Section 7.2.1 for basis.
3.4.1 Method I The Total Body Dose Rate due to noble gases can be determined as follows:
b " '43 0FB (3-3) tb 4 i $
3 mrem mrem-m yr y DCi-sec) 3 gCj,)
see gp Ci-yr Ci-m (I) The Turbine Building vent ground level release X/Qs are used in the 00CM Method I equations. This is to conservative'y account for the station vent stack, and, any potential ground level releases.
3-8
wh;re:
0 = Peak release rate at the station vents that is averaged by a 9
time period no longer than one-hour (,uci/sec) for each radionuclide, "i", shown in Table 1.1-10. ,
- 0F8 g = Total body gamma dose factor (see Table 1.1-10).
Equation 3-3 can be applied under the following conditions (otherwise, justify Method I or consider Method II):
- 1. Normal operations (nonemergency event), and
- 2. Noble gas releases via any station vent to the atmosphere.
3.4.2 Method II If Method I cannot be applied, or if the Method I dose exceeds the limit or if a more exact calculation is required, then Method 11 may be applied. Method 11 consists of the models, input data and assumptions in Regulatory Guide 1.109, Rev. 1 (Reference A), except where site-specific models, data or assumptions are more applicable. The general equations and parameters taken f rom Regulatory Guide 1.109, and used in the derivation of the simplified Method I approach as described in the Bases section, can also be applied to a Method II assessment, which, in addition, incorporates site receptor-specific information which coincides conditions at the time of release, such as identified pathways of exposure.
1 3-9
3.5 Method to Calculate the Skin Dose Rate from Noble Gases Technical Specification 3.11.2.1 limits the dose rate at any time to the skin from noble gases at any location at or beyond the site boundary to 3,000 arem/ year. The Technical Specification indirectly limits peak release rates by limiting the dose rate that is predicted from continued)elease at the peak rate. By limiting D skin to a rate equivalent to no more than 3,000 mrem / year, we assure that the skin dose accrued in any one year by any member of the general public is less than 3,000 mrem. Since it can be expected that the peak release rate on which Dskin is derived would not be exceeded without corrective action being taken to lower it, the resultant average release rate over the year is expected to be considerably less than the peak release rate.
Use Method I first to calculate the Skin Dose Rate from the peak release rate via the station ventsI I. Method I applies at all release rates.
is desired by the Use Method 11 if a more refined calculation of Dskin station (i.e., use of actual meteorology and release-specific X/Qs) or if Method I predicts a dose rate greater than the Technical Specification limit to determine if it had actually been exceeded during a short time interval.
See Section 7.2.2 for basis.
3.5.1 Method 1
'T The Skin Dose Rate due to noble gases is:
DFj (3-4)
Dskin " g i
mrem-sec mrem) yr sec pCi-yr y
(1) The Turbine Building vent ground level release X/05 are used in the ODCM Method I equations. This is to conservatively account for the station vent stack, and, any potential ground level releases.
3-10
where:
hg = peak release rate at the station vents that is averaged by a time period no longer than one hour (uCi/sec) for each radionuclide, "i", shown in Table 1.1-10.
OFj
= combined skin dose factor (see Table 1.1-10).
Equation 3-4 can be applied under the following conditions (otherwise,
~
just1fy Method I or consider Method II):
- 1. Normal operations (nonemergency event), and
- 2. Noble gas releases via any station vent to the atmosphere.
3.5.2 Method Il If Method I cannot be applied, or if the Method I dose exceeds the limit or if a more exact calculation is required, then Method II may be applied. Method 11 consists of the models, input data and assumptions in Regulatory Guide 1.109, Rev.1 (Reference A), except where site-specific models, data or assumptions are more applicable. The general equations and paraneters taken from Regulatory Guide 1.109, and used in the derivation of the simplified Method I approach as described in the Bases section, can also be applied to a Method II assessment, which, in addition, incorporates site
. receptor-specific information which coincides conditions at the time of release, such as identified pathways of exposure. .
I 3-11 l
. . . - - - .. . - ~ . -. -- - - - - . - - _ . . - , .-
.i j 3.6 Methed to Caltulate the Critical Orean Oose Rate from fodines. Tritium ed. -
Particulates with T g Ereater Than 8 Days ;
i, ,
Technical Specification 3.11.2.1 limits the dose rate at any time to j any organ f rom 131 3
, 133 g
,y3 and radionoclides in particulate fem with ,
half lives greater than 8 days to 1500 mrem / year to any organ. The, Technical l Specification indirectly limits peak release rates by limiting the dose rate ;
l j
- .thatris predicted from continued release at the peak rate. By limiting Dc , [
to a rate equivalent to no more than 1500 mrem / year, we assure that the ;
critical organ dose accrued in any one year by any member of the general i
public is less than 1500 srem.
).
i Use Method I first to calculate the Critical Organ Ocse Rate from the peak release rate via the Station vents . Mcthod I applies at all release f rates.
! I i
Use Nethod 11 if a more refined calculatior cf hg , is desired by the [
- station (i.e., use of actual meteorology and release-specific 7/0s) or if ,
i Methed I predicts a dose rate greater than the Technical Specification limit ,
f to determine if it had actually been exceeded during a shert time interval. i i
i See Section 7.2.3 for basis. j
! f 1
} 3.6.1 Method i L
i [
I The Critical Organ Dose Rate can be determined es follows: ;
b = bg 0FG gco (3-5) [
co 1
,l j
mrem) uti y mrem-sec y
j yr set vCi-yr t
! where:
1 j OFGy a Site-specific critical organ dote rate factor mrem-sec) pCl-yr for a gaseous release. See Table 1.1-12, d
i i (I) The Turbine Building vent ground level release X/Qs are used in the
~
' 00CM Method I equations. This is to conservatively account for the station vent stack, and, any potential ground level releases. ;
{ 3-12 ;
h-y
= Peak a:tivity roleast rate at the statitn ve.its cf ;
radior.uclide "i" in vC1/sec. For i = Sre9 or $r$0, use the best esticates (such as most recent measurements).
Equation 3-5 can be applied under the followirs conditions (otherwise,
' justify Methe,o ' or consider Method II): ,
- - 1. Normal operations (not emergency event), and
' to the atmosphere. 1 4
{ 3.6.2 Method II ,i If Method I cannot be applied, or if the Methnd I dose exceeds the limit or if a more swact calculation is required, then Method !! may be applied. .
Method 11 consists of the models, input data and assumptions in Regulatory Guide ,
j 1.109. Rev.1 (Reference A), except where site-specific models, data or l assumptions are more applicable. Int general equations and psrameters taken from Regulatory Guide 1.10"t, and used in the d6rivatio1 of the simplified Method 1 approacn as described in the Ba>cs section, can also be applied to a Method II ;
I '
assessment, which, in addition, ir.corporates site receptor-specific infornation which coincides conditions at the time of release, such as identified pathways ;
! of exposure.
a ,
e 9
I 1
t l
i l
l l
3-13 i
,i..,p y, .- p.- - .- -.i9 --
,--:p 7q -.y9 .p e - .-- ._m ,y - .,y-.g- . -- = , --p gy ---, ,
3.7 Metho tolaiculato t_he Gamma _ Air- Oose f rom Noble Gasos Technical Specification 3.11.2.2 limits the genma dose to air f rom f noble gase; at any location at or beyond the site boundary to 5 mrad in any quartar and 10 mrad in any year per unit. Pose evaluation is required at least once per 31 aays. $ e. .
~
lise M.athod I first to calculate the gasma air dcse for the station i vent (l releases dur195 the period.
Use Nethod 11 if a (nere refinef, calculation is reeded (i.e., use of
- actusi meteorology and release-specUic X/Qs), or if Methcd I predicts a dose '
greater thJn the Tecnnical Specification Jimit to determine if it had actually '
teen exceeded. See Section 7.2.4 for basis.
3.7.1 Method i The gam.: air oose f ror, staticn vent releases is:
(3-6)
D ar = 2.0E-G8 1 43 0F}
3 (orad) (E ) (Sci) (grad-m ) !
9Cl-m pti-yr where Q9 - 1*,tal attivity (vCl) teleased to the cteosphere vli station .
vents of eacte ra.11onuclide "1" during the prrrio6 of interest.
See Tatle 1.1-10 of( . guru dose f a: tor to air for radionuclide *i. .
(1) The lurbine Building vent ground level rehase A/Q. are used in the l ODCM Method J equations. This is to cohscrvatively account for the statio,1 vent stact And, any potential ground level releases. :
?
3-t4 ,
i i
Equation 3-6 can be applied unO P the following cor.dittees (etherwise .
justify Method I or consider Method !!): .
i
- 1. hormal operations (nonemergency event), and ,
- 2. Noble gas releases via station vents to the atmosphere.
- 3.7.2 N_ethod 11 If Mett.od I cane.ot be applied, or if the Method I dote exceeds the liott or if a more exact calculation is required, then Method II may be applied. Met %c 11 consists of the models, input data and assumptions in Regulatory Guide 1.109, tev.1 (Reference A), except where site-specific models, data cr assurnptions are mere applicable. The general equations and ;
parameters taken from Regulatory Guide 1.107, and used in the derivation of the sitt.plifled Method I approach as described in the Bases section, can also l'
be applied to a Method Il assessment, which, in addition, incorporates site receptor-specific information whicn coincides conditions at the t!ne of j release, such as ider,tified pathways of exposure.
i s 4
e il i
i k
i 4
J t
! 6 l
l ,
I
't-15 l e
- - - - - . - - . ~ , - . _ . . . _ - , _ _ .
I 3.8 Method to Calculat'> the Bett Air tiose f rom Noble _6cses_ _
1echnical Spec 5fication 3.11.2.2 Ifp11ts the beta dose to air f rom noble gases at any location at or beyond the site boundary to 10 mrad in any quarter ,
I and 20 mrad in any year g,er unit. Do:e evaluation is reqaired at leas t once i per 31 days. },
,_ Use Method I first to calculate the beta air dose for the station vent III stack releases dJring the period. Met 5cc I applies at all dose levels.
2 Use Method 11 if a mors refined calculation is tieeded (i.e., use of I actuel meteorology and release-scecific X/Qs) or if Method I predicts a dcse i greater than the Technical Specific 3 tion limit to determine if it had actually ,
been exceeded. See Section 7.2.5 for basis.
L 3.8.1 hetbec I i
i Tt.e beta air dose from station vent releases is:
0 = 4.4E-08 ( 3-7 )
tr 1
Og DFf (rad) ( ) (pct) ( ')
t where:
GF - beta dose f actor to air f or radionuclide "i". See Table 1.1-10
- Og = tctal activity (uti) released to the attro phere via station vents of each radionuclide "i" during the period of irterest. ,
4 l t
< -(l ) The Turoine Building vent ground level releast X/05 are used in the i 00CM Method I equations. This is to censervatively account fcr the ;
station vent stack, and, any poter,tial ground levt1 releases, 3-% j 4
l
_ . , _ . _ . _ . , . ~ , , , _ . _ _ _ _ , . - . . . , . _ , . _ _ . . _ _ . _ _ , . . , _ . . . _ _ , _ . , _ . _ - - - _ - , , . , , . _ , . _ _ _ , _ . - . , , . _ . . _ , , , , , _
Equati@n 3-7 can be applied under the following cond*tions (otherwise justify Method I or consider Method II):
- 1. Normal operations (nonemergency event), and ,
- 2. Noble gas releases via station sents to the atmosphere.
t 3.3.2 Method if
(
If Method I cannot be applied, or if the Method I dose exceeds the limit or if a more exact calculation is required, than Nethod Il may be applied. Method II consists of the models, input data and assumptions in Regulatory Ovide 1.109, Rev.1 (Ref erence A), except where site-specif'it ,
models, data or assumptions are more applicable. The g:neral equations ano parameters taken from Regulatory Guide 1.709,and used in the derivation of the ,
simplified Method I approach as described in the Baset Section, can also be applied to a Method 11 assessment, which, in addition, incorporates site l
receptor-specific information which coincides conditions at the tima of
- release, such as identified pathways of exposure, i
t d
1 i
k
)
i i e i
e J
1 i
' 3-17 1 i
.vt
-r--- +.,------+--g.re-
,- ----~-.-----e ,c-----~-. - - - . - ~ < - , - -- - ~ - - . - - - - - - , - + ~ - - .--.---m~< -
-3g - -.4. .- -
1 3.9 Pethod to Calculate the Critical Oraan Oose f rom Iodines. Tritium and 9 articulates Technical Specification 3.11.2.3 limits the critical organ dose to a member of the public f rom radioactive iodines, tritium, and particulates with ;
half-lives greater than 8 days in gaseous effluents to 7.5 mrem per; quarter ,
i and 15 crem per year per unit. Technical Specification 3.11.4 limits the total body and organ dose to any real member of the pcblic from all station !
sources (including gaseous effluents) to 25 mrem in a year except for the thyro 10, which is limited to 75 prem in a year.
Use Method I first to calculate the critical or6an dose f rom a vent release as it is simpler to execute and more conservative than Method 11.
4 Use Method 11 if 6 more refined calculation of critical organ dose is needed (i.e., Method I indicates the dese is greater than the limit). See ,
i Section 7.2.6 for basis.
i j 3.9.1 Methoe !
D, =wQ g LFG iro I3-0I <
i i
1 (mrem) (uci) ( )
Og = letal activity (Sci) released to the atnosphere of radionut11de ,
"i" during the period of interest. For strontiums, use the Kost recent measurement.
DFGg, = Site-specific critical organ dose f actor (mrem /pci). For each radionuclide it is the age group and organ with the largest dose factor. See Table 1.1-12.
-7 ,
- Equation 3-8 can be applied under the folicwing conditions (otherwise, justify Method I or consider Method II)
). Normal operations (none.tergency event),
d
- 2. todine, tritium, and particulate releases via station vents to the atmosphere, and 3-18
,_ _ _ _ _ _ . _ - . _ _ . - _ . . - - - . . _ - , _ _ - _ _ _ _ - _ , _ _ . . . - , . _ . - _ _ - _ - , .- _ ._ . - _ - _ . ~ _ _ _
- 3. Any continuous or batch release cver cny time paried.
3.9.2 METHOD IJ, If Method I cannot be applied, or if the Method I dose exceeds the ;
limit or if e more exact calculation is required, than Method !! sh9uld be applied. Method Il consists of the models, input data and assumptions in <
l Regulatcry Guide 1.109 Rev.1 (Reference A), except where site-specific evadels, data or assurptions are more applicable. The general equations and
- parameters taken f rom Pegulatory Guide 1.109, and used in the derivation of i
the simp 11 fled Method I approach as described in the 8ases section, can also i be applied to o Method II assessment, which, in addition, incorporates site I receptor-specific information which coincides conditions at the time of I release, such as identified pathwys of exposure.
i
+
1 6
t e
I
. I l
r I
)
J i
3-19 i f
f i
i
__ ~ . -. _ . . _ . . ..,,,.,_._,,,_3.m, ~. __--...r. r. , --- , . _ _ -~ . , - . . _ . _ . , ._ _ _ - _ , , . _.___,,,,,,,..,,..,,,-.--,-,,,,,,,,...w.r.--
,..,..,,,-..._v , , -,_
l l
' 3.10 Method to Calculste Direct Dose from Plant Operation !
l
) Technical Specification 3.11.4 restricts the dose to the whole body or any organ to any member of the public from all station sources (including direct radiation from the turbine and reactor building) to 25 mrem in a i calendar year (except the thyroid, which is limited to 75 mres). : , ,
I i
r i 3.19.1 Method '
?
l.
The direct dose from the station will be determined by obtaining the l
' dose from the appropriate TLD locations, and subtracting out the dose contribution from background. Alternate methods to calculate the direct dose
! may also be used, such as high pressure ion et.awber measurements, or
{
analytical design calculations.
i
?
J i i I
i 1
i !
i !
1 ;
J !
I i
i 1 .
5 2
t I ;
I t
i i
i
- j. l l 3-20 ,
4 l
i
4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING FROGRAM The radiological environmental monitoring stations are listed in Table 4.1. The locations of the stations with respect to the Seabrook Station are shown on the maps in Figures 4-1 to 4-6. .
m Direct radiation measurements are analyzed at the station. All other radiological analyses for environmental samples are performed at the Yankee Environmental Laboratory. The Laboratory participates in the U.S.
Environmental Protection Agency's Environmental Radioactivity Laboratory Intercomparison Studies Program for all the species and matrices routinely analyzed.
J l
I l
1 l
4 -1 !
J l
j
TABLE 4.1 Radioloaical Environmental Monitorina Stationf a)
Distance From Exposure Pathway Sample Location Unit 1 , Direction Fron and/or Sample and Desionated Code Containment (km) ? 1he Plant
- 1. AIRBORNE (Farticulate and Radiciodine)
AP/CF-01 PSNH Barge 2.7 ESE Landing Area AP/CF-02 Hampton Marina 2.7 E AP/CF-03 SW Boundary 0.8 SW AP/CF-04 W. Boundary 1.0 W AP/CF-05 Winnacunnet H.S. 4.0 NNE AP/CF-06 Georgetown 24.0 SSW Substation (Control)
- 2. WATERBORNE
- a. Surface WS-01 Hampton-Discharge Area 5.3 E WS-51 Ipswich Bay (Control) 16.9 SSE
- c. Sediment SE-02 Hampton-Discharge Area 5.3 E SE-07 Hampton Beach 3.1 E SE-08 Seabrook Beach 3.2 ESE SE-52 Ipswich Bay (Control) 16.9 SSE SE-57 Plum Island Beach 15.9 SSE (Control)
- 3. INGESTION
- a. Milk TM-04 Salisbury, MA 5.2 SW TM-08 Hampton Falls, NH 4.3 NNW TM-10 Hampton Falls, NH 4.0 WNW TM-20 Rowley, MA (Control) 16.3 5
- b. Fish and Invertebrates (b)
FH-03 Hampton - Discharge 4.5 ESE i Area i FH-53 Ipswich Bay (Control) 16.4 SSE HA-04 Hampton - Discharge 5.5 E Area HA-54 Ipswich Bay (Control) 17.2 SSE MU-06 Hampton - Discharge 5.2 E Area MU-09 Hampton Harbor 2.6 E MU-56 Ipswich Bay (Control) 17.4 SSE MU-59 Plum Island (Control) 15.8 SSE 4-2
TABLE 4.1 (c;ntinued)
Radiological Environmental Monitorina Stationf a)
Distance From Exposure Pathway Sample Location Unit 1 Direction From and/or Sample and Desionated Code Containment (km) the Plant
- 4. DIRECT RADIATION TL-1 Brimmer's Lane, 1.1 N Hampton Falls TL-2 Landing Rd., Hampton 3.2 NNE 3.1 TL-3 Glade Path, Hampton NE Beach TL-4 Island Path, Hampton 2.4 ENE Beach TL-5 Harbor Rd., Hampton 2.7 E Beach TL-6 PSNH Barge Landing 2.7 ESE Area TL-7 Cross Rd., Seabrook 2.6 SE Beach TL-8 Farm Lane, Seabrook 1.1 SSE TL-9 Farm Lane, Seabrook 1.1 S T L-10 Site Boundary Fence 1.0 SSW TL-11 Site Boundary Fence 1.0 SW T L-12 Site Boundary Fence 1.0 WSW T L-13 Inside Site Boundary 0.B W TL-14 Trailer Park, Seabrook 1.1 L'NW T L-15 Brimmer's Lane, 1.4 NW Hampton Falls TL-16 Brimmer's Lane, 1.1 NNW Hampton Falls T L-17 South Rd., N. Hampton 7.9 N T L-18 Mill Rd., N. Hampton 7.6 NNE T L-19 Appledore Ave., 7.9 NE N. Hampton TL-20 Ashworth Ave., 3.4 ENE Hampton Beach TL-21 Route 1A, Seabrook 2.7 SE Beach TL-22 Cable Ave., 7.6 SSE Salisbury Beach -
TL-23 Ferry Rd., Salisbury 8.1 S TL-24 Ferry Lots Lane, 7.2 SSW Salisbury TL-25 Elm St., Amesbury 7.6 SW TL-26 Route 107A, Amesbury 8.1 WSW 4-3
r-TABLE 4.1 (continued)
Radiological Environmental Monitorina Stationf a)
Distance From '
Exposure Pathway Sample Location Unit 1 Direction From and/or Sample and Desianated Code Containment (km) - the Plant TL-27 Highland 5t.,
- 7.6 W
_ S. Hampton TL-28 Route 150, Kensington 7.9 WNW TL-29 Frying Pan Lane, 7.4 NW Hampton Falls TL-30 Route 101C, Hampton 7.9 NNW 4.0 TL-31 Alumni Drive, Hampton NNE ,
s TL-32 Seabrook Elementary 1.9 5 - .
School TL-33 Dock Area, Newburyport 9.' S TL-34 Bow 't. , Exeter 12.1 NW TL-35 Lincoln Ackerman 2.4 NNW School TL-36 Route 97, Georgetown 22 SSW (Control)
TL-37 Plaistow, NH (Control) 26 WSW '
TL-38 Hampstead, NH (Control) 29 W TL-39 Epping, NH (Control) 27 NW TL-40 Newmarket, NH (Control) 24 NNW ,
TL-41 Portsmouth, NH 21 NNE 1
(Control) , i TL-42 Ipswich, MA (Control) 27 i SSE -
TL-43 Education Center On-Site TL-44 Rocks Road Landing On-Site (a) Sample locations are shown on Figure 4.1 to 4.6.
(b) Samples will be collected pursuant to Technical Specification Table 3.12-1 Item 4.b. Samples are not required at all stations listed during any sampling interval (FH = Fish; HA = Lobsters; MU = Mussels). y 8
1 1
Y \
i 4
4-4
N l
Ph ?
\ -
l A 5 ,
f WG-04@
e
+
Oly SROL.NS RIVfR N-09 @
WG-06@ EABROOK 1 f Ap.gyg AP-04 @
m2 / , ,Ag;70y gACMR
@ AP 03 A A
Si-Oe e i 5
E k h j
/ 0 500 1000
\* ! U METERS $p j M 5
Figure 4.1 ludiological Environmental Monitoring Locations Within 4 Kilometers of Seabrook Station fl 4-5 l
t
r.- o 5 e
ElinirTl0%
D 8 l_ v V
N
\A RVE SEACH SEE U!AR:ECNT JA FIGvFE 2.1 1M-08 AP-05
.......b....-.
N, '
t TM-10@ l
'.leSE-07
/ HAMPTON BEACH l
SE ASROOK' STATION E '
@ DISCHARGE SITE O .
WS-01 MU-06 l , FH-03 HA-04
.-%~ *
, 5f-02
/
,/ '5l 0 y SEASROCK EEACH
/ .- :
g., r. /.
@ Tw-C:
e SALISButY BEACK D
NERRin c $
P q ATLETIC OCEAu
)
Figure 4.2 Radiological Environmental Monitoring Locations Between 4 Kilometers and 12 Kilometers from Seabrook Station 4-6
, k.
O % !il 1 '.
g_ __ _ i p_. _a k lIINI.Il RS ,
d YOR6 Y.c o L
~
DURHAM e '
s .
'% q
_ NEWMARrET e PORT 5 MOUTH e N, F
uY.0 \
EPPING e g S'
l l Y. \
i e s e EXETER e l N l ;
l SEE EN M CEstEA~ IN r] cup 5 g, g ) l 8
HAMTON e ,
l '
s SEABROOK STATION KINGSTON e l \ #0" ##E e SEABROOKo E a --
N )lO! CHARGE $1TE
.- \---
~',.- '
I e SALISBURY
./ ' AMESBURY e I e PLAISTOW e , ! ; l
, ,, , N. g, ,/ l l ATLAVTIC OCEAN
/ A.qg'gy . ,I NEWBURYPORT e 8
~-)
f i
HAVERHILL e
- l. TM-20 l
l SE-57 PLUM ESLAND FH-53 AP-6@
. LAWRENCE @
IP$WICH SAY IP5WICH e MU-56@
HA-54
- GLOUCESTER Figure 4.3 Radiological Environmental Monitoring Locations Outside 12 Kilometers of Seabrook Station 4-7 l
i
NNW
\ / .- . Tt-2 i /' NE
\
\ i.
._ , . TL-3
$ 1
/
\
l /
TL 5 TL 6\ %
l @ TL-1 ,/ Qp TL-14 @ f W
N TL-13@ #
sunaoor, Q l5 TL-5 @
- '# s
- wrTou max I '
TL-11 @
gTL-C WSW / /@
M
/ / TL-9 TL-8
/ '
ESE TL-7 @
TL-32@
g, 0 500 1000 4, g I gh TL-21 S Sh, Ntitns SSE SE 3
S Figure 4.4 Direct Radiation Monitoring Locations Within 4 Kilometers of Seabrook Station 4-B
x n /
\ c. )/ o 5 bi l
\ *-
NNW
- I Lt#1t it 135
~
k NNE U '
NE NW
~
@ TL-34 /
s i ., d\ >
- g RVE BEACH
,g
, TL-17 ,
TL-30 TL-18 WW sit in AR: s g,,. ,,
xx rzcurt 2.c 7t,3, 7 ENE e TL-28 y' \ TL- NMFTOM BEACH W @ TL-27 N/
stranoon'sTA m e
otstntRGE stTE E
- \
- ~~' k SEABROCK BEACH
/
e TL-26 ,
'.~ pg' d.-
1 . .
N ESE
@ TL-25 SAL!55uty Acg TL 24 g TL 24
/
TL-23 y b
SE RRiw %
SW 7t.33g ArtAurtc OccAx P
g
)
- S Figure 4.5 Direct Radiation Motsitoring Locations Between 4 Kilo:neters and 12 Kilometers f rom Seabrook Station 4-9
h [
N I [
go gg j O $ NNI L llJ M TLit $ ' '
NNv! $ vows ,
NW k '
f DURii *1 e N TL-40
' 'Pc NE
@ /
~
NEWMRKET e PORTS UTil e 9
@ TL-39 TL-41 Q# ' *
, 10 Miles \ ,
EPPING e s
g \-f i
\ ENE WNW N
IETER e N[.AMEMEN* EN ffCU?: 2,$ ,
g a HA PTO e l #
1
/ '
SEABROOK
~
(ARW-K!NGSTONe SEABRO e
.. E W s e
i
,./ - 0 406-U
@ TL-3a '
,' ' MESB e SAL B0 Y \ '
- ' - \
PLAISTOW e , s
' ' ATLMTIC CCEM TL-3T & . '
I
,# . ,Y NE URYPORT e ESE
/ -
.?@ '
WSW I mvERHI e l
PLUM LANO
- ~~~
TL-36@
ffTHUEN e e LAWRENCE IPSwTCn SE IP5WICHe . TL-42 SW SSW SSE Figure 4.6 Direct Radiation Monitoring Locations Outside 12 Kilometers of Seabrook Station 4-10
,w - - ---
5.0 SETPOINT DETERMINATIONS Chapter 5 contains the plant procedures that the plant operator requires to meet the setpoint requirements of the Radioactive Effluent Monitoring Systems Technical Specifications. They are Specification 3.3.3.9 for liquids and Specification 3.3.3.10 for gases. Each outlines'the instrumentation channels and the basis for each setpoint.
k 5-1
5.1 Liouid Effluent Instrumentation Setooints Technical Specification 3.3.3.9 requires that the radioactive liquid effluent instrumentation in Table 3.3-12 of the Technical Specifications have alarm setpoints in order to ensure that Specification 3.11.1.1 is not exceeded. Specification 3.11.1.1 limits the activity concentratibn.in liquid effluents to the appropriate MPCs in 10CFR20 and a total noble gas MPC.
5.1.1 Liauid Waste Test Tank Monitor (RM-6509)
The liquid waste test tank effluent monitor provides alarm and automatic termination of release , ior to exceeding the concentration limits specified in 10CFR20, Appendix B, u ble II, Column 2 to the environment. It is also used to monitor discharges f rom various waste sumps to the environment.
5.1.1.1 Method to Determine the Setpoint of the Liquid Waste Test Tank Monitor (RM-6509)
The instrument response (uCi/ml) for the limiting concentration at the point of discharge is the setpoint, denoted Rsetpoint, and is dete M ned as fcilows:
R setpoint " 0 in "i (uCi/ml) () ( )
where:
DF =
= Dilution factor (dimensionless) (5-2) m F, = Flow rate past monitor (gpm)
F = Flow rate out of discharge tunnel (gpm) d DFmin = M nimum allowable dilution f actor (dimensionless) 5-2 l
%3 l DFoin " P.P
(')
g MPC g = MPC for radionuclide "i" f rom 10CFR20, Appendix B, Table II, Column 2 (yCi/ml)
C ,9
= Activity concentration of radionuclide "i" in sixt'ure at the monitor (yci/ml) 5.1.1. 2 Liouid Waste Test Tank Monitor Setpoint Example The activity concentration of each radionuclide, Cg , in the waste test tank is determined by analysis of a proportional grab sample obtained at the radwaste sample sink. This setpoint example is based on the following data:
i C ,3 (pCi/ml) VNg (ud/ml)
Cs-134 2.15E-05 9E-06 Cs-137 7.48E-05 2E-05 Co-60 2.55E-05 3E-05 Y
LCg = 2.15E-05 + 7.48E-05 + 2.56E-05 i
uti, uCi uti uti I ml l Iml ) Iml ) Iml )
= 1.22E-04 uCi
-(ml )
DF min
=
(5-3) uti-ml I ml pCi I 2.15 E-05 7.48E-05 2.56E-05
" + +
uti-m1 vCi-ml uCi-ml I El pCi I Iol pCi}
(c1 9C1)
DF g =7 The minimum dilution factor, DFmin, needed to discharge the mixture of radionuclides in this example is 7. The release rate of the wast'e test tank is between 10 and 150 gpm. The circulating water discharge flow can vary f rom 10,500 to 412,000 gpm of dilution water. With the dilution flow taken as 41.2,000 gpm and the release rate from the waste test tank taken as 150 gpm, the DF is:
F d
DF =
pm (gpm) (5-4)
(gpm) 412.000 com 150 gpm
= 2750 Under these conditions, the setpoint of the liquid radwaste discharge monitor is:
R setpoint
- D in (cps) () ( )
2750
=
q 1.22E-04 i
() ( )
= 4.79E-02 pCi/ml or pCi/cc
- l 5-4
In this example, the alarm of the liquid radwaste discharge monitor should be set at 4.79E-02 pCi/cc above background.
I 5.1. 2 Turbine Buildina Drains Liouid Ef fluent Monitor (RM-6521)
The Turbine Building drains liquid effluent monitor continuo.usly monitors the Turbine Building sump effluent line. The only sources to the Sump Effluent System are f rom the secondary steam system. Activity is expected in the Turbine Building Sump Effluent System only if a significant primary-to-secondary leak is present. If a primary-to-secondary leak is present, the activity in the sump effluent system would be comprised of only those radionuclides found in the secondary system, with reduced activity from decay and dilution.
The Turbine Building drains liquid effluent monitor provides alarm and automatic termination of release prior to exceeding the concentration limits specified in 10CFR20, Appendix B, Table II, Column 2 to the environment. The alarm setpoint for this monitor will be determined using the same method as that of the liquid waste test tank monitor if the total sump activity is greater than 10 percent of MPC. If the total activity is less than 10 percent of MPC, the setpoints of RM-6521 are calculated as follows:
High Trip Monitor = (DF') (3.0E-07 pCi/ml) (5-21)
Setpoint (pCi/ml) where:
Service water flow rate (apm)
DF' = Flow rate post-monitor (gpm) 3.07E-07 vCi/ml = most restrictive MPC value for those isotopes which could be identified. (I-131 = 3.0E-07 pCi/ml f rom 10CFR20, Appendix B, Note 3b).
5-5
Warning Alarm High Trip (5-22) !
Monitor Setpoint =IMonitor Setpoint) (0.25)
(pCi/ml) 5.1.3 Steam Generator Blowdown Liould Sample Monitor (RM-6519)
The steam generator blowdown liquid sample monitor is used to detect ,
abnormal activity concentrations in the steam generator blowdown: flash tank liquid discharge to the environment.
Nornelly steam generator blowdown liquid is released directly to the environment when no primary-to-secondary leakage exists. Under normal operating conditions, the activity concentrations at the point of discharge from the steam generator blowdown flash tank will never exceed the MFC in 10CFR20, Appendix B Table II, Column 2. The alarm setpoint for the steam generator blowdown liquid sample monitor will be determined using the same approach as the Turbine Building drains liquid effluent monitor.
For any liquid monitor, in the event that no activity is expected to be discharged, or can be measured in the system, the liquid monitor setpoint should be based on the most restrictive MPC for an " unidentified" mixture given in 10CFR20, Appendix B notes.
l 5-6
5.2 Gaseous Effluent Instrumentation Setpoints Technical Spe:ification 3.3.3.10 requires that the radioactive gaseous ef fluent instrumentation in Ta' ale 3.3-13 of the Technical Specifications have their alarm setpoints set to insure that Technical Specification 3.11.2.1 is not exceeded. TechnicalSpe.ification3.ll.2.1.alimitstheacttyyy concentration in off-site gaseous effluents to well below the appropriate MPCs in 10CFR20 by limiting the whole body and skin dose rates to areas at or beyond the site boundary.
5.2.1 Plant Vent Wide-Range Gas Monitors (RM-6528-1.2 and 3)
The plant vent wide-range gas monitors are shown on Figure 6-2.
5.2.1.1 Method to Determine the Setpoint of the Plant Vent Wide Range Gas Monitors (RM-6528-1.2 and 3)
The setpoint for the plant vent wide-range gas monitor readout response in uti/cm is set at limiting the off-site noble gas dose rate to the total body or to the skin is ' denoted R setpoint' setpoint s e esser of:
=
R tb 1150h DFB c
3 set uti/cm3 (mrem uti-m )
yr-pCi-sec Il}I cm DCi-vr) mrem-m 3
and:
R skin
= ,000 h DFl (5-6) uti-pCi/cm 3 gmrem) yr (sec) 3 { mrem secvr )
where:
R = Response of the monitor at the limiting total body dose tb 3
rate (pCi/cm )
5-7
500 1150 = (yr-pci-sec m m-uC E )
(0.7) (1E+06) (6.2E-07) 500 = Limiting total body dose rate (mrem /yr) 0.7 = Attenuation factor that accounts for the dose reduction due to shielding provided by residential structures
_ (dimensionless) 1E+06 = Number of pCi per pCi (pCi/pC1) 6.2E-07 = [X/Q)T, maximum annual average gama atmospheric dispersion factor (sec/m )
F = Appropriate plant vent flow rate (cm /sec) 1 DFB = Composite total body dose factor (mrem-m /pCi-yr) c h$DFB $
= (5-7) b3 i
h$ = The release rate of noble gas "i" in the mixture averaged by the time constant of the measuring system for each noble gas identified in the off-gas (pCi/sec) 3 DFB j = Total body dose factor (see Table 1.1-10) (mrem-m /pci-yr)
R = Response of the monitor at the limitirg skin dose rate skin 3 (pCi/cm )
5-8
._ _ _ . . ~. , .. _ .
3,000 = Liniting skin dose rate (crem/yr)
DF' = Composite skin dose factor (arem-sec/pCi-yr) hi DFj ,
i
= .
(5-8) bg i
l DF' = Combined skin dose factor (see Table 1.1-10)
I (mrem-sec/pci-yr) .
- 5. 2.1. 2 Plant Vent Wide Range Gas Monitor Setpoint Example The following setpoint example for the plant vent wide range gas monitors demonstrates the use of equations 5-5 and 5-6 for determining setpoints.
The nominal plant stack flow is 4.3E+07 cc/sec ((153,200 cfm x 28,300 cc/ft }/60 sec/ min).
This setpoint example is based on the following data (see Table 1.1-10 s e for DFB3 and DFg ):
i l '
Qg DFj
' DFB) 3 s Iuti) sec Imrem-m DCi-vr ) I rnrem-sec uti-vr' )
Xe-138 1.03E+04 8.83E-03 7.76E-03 Kr-87 4.73E+02 5.92E-03 9.5SE-03 Kr-88 2.57E+02 1.47E-02 1.00E-02
! Kr-85m 1.20E+02 1.17E-03 1.61E-03 Xe-135 3.70E+02 1.81E-03 2.25E-03 Xe-133 1.97E+01 2.94E-04 3.90E-04 l l
i 1 l 5-9 l I l l
, i f
- .- = . . - - - .. . - - -
bi 0FB g l
0FB = (5-7) h3 4 i t-h, OFB, = (1.03E+04)(8.83E-03) + (4.73E+02)(5.92E43)
, 1 i .
~
+ (2.57E+02)(1.47E-02) + (1.20E+02)(1.17E-03)
- + (3.70E+02)(1.81E-03) + (1.97E+01)(2.94E-04) s l = 9.83E+01 (uti-mrent-m /sec-pti-yr)
= 1.03E+04 + 4.73E+02 + 2.57EF02 1 , h>.
I f + 1.20E+02 + 3.70E402 + 1.97E+01
= 1.15E+04 pCi/sec '
1 9.83E+01 OFB
, c = 1.15E+04 3
= 8.52E-03 (mrem-m /pCi-yr)
Rtb = 1150 h DF8 c 1
=( 0) (4.3E+07) (8.52E-03) i 3 ;
= 3.14E-03 pCi/cm i
4 i
hg DF{
DF' = . (5-8)
, hg i i ,
E . 1
. /._, Og 0Fj = (1.03E+04)(7 76E-03) + (4.73E+02)(9.59E-03) i i i
i l 5-10
' l l
o (2.57E+02)(1.00E-02) o (1.20E+02)(1.61E-03) ;
+ (3.70E+02)(2.25E-03) + (1.97E+01)(3.90E-04)
= 8.81E+01 (vCi-mrem-sec/sec vci-yr) i , ,
DF'c = 8.81E+01 1.15E+04 .
= 7.66E-03 (mrem-sec/vci-yr) 1 1 Rskin = 3,000 p DF. (5-6) c 1 1
, = { 000) (4.3E+07) (7.66E-03) 3
= 9.11E-03 vC1/cm The setpoint, Rsetpoint, is the lesser of R tb and R skin, r the noble gas mixture in this example R b is less than Rs in, indicating that the total body dose rate is more restrictive. Therefore, in this example the plant vent wide-range gas monitors should each be set at 3.14E-03 vCi/cm above background, or at some administrative f raction of the above value.
In the event that no activity is expected to be teleased, or can be measured in the system to te vented, the gaseous monitor setpoint should be
+
based on Xe-133.
l 6
! i I
i i
5-11 l l n
.ng, -- 4,. - . + - - . - - - , , , ,e - , - -- -r.. y , ,. --,---n.,,,nw,,,,..w-.-
6.0 L10010 AND 64Sf_005 EFF10ENT STREAMT. RADi& TION MON.{JORS AN0 RADWA51t IR{ATMENT_ SYSTEM $
Figure 6-1 shows the liquid effluent streams, radiation meattors and ,
the appropriate liquid Radwaste Treatment System. Figur.e 6-2 shows the gaseous effluent streams, radiation monitors and the .appropriateiGAseous .
Radwaste Treat 9ent System, Tor more detailed information concerning the above, refer to the Seatrock Station Final Safety Analysis , Report, Sections 11.2 (Liquid W3ste System), 11.3 (Gaseous Waste System) and 11.5 (Process and Effluent Radioicgical Monitoring and Sampling System).
The turbine gland seal ccnderser exhaust is an unmonitored release l path. The iodine and particulate gasecus releases will be determined by continueusly sampling the turnine glarid seal condens.er erhaust. The noble gas releases will be determined by the noble gas released via the main condenser air evacuation exhaust and ratioing them to the turbine glar.d seal condenser
~
exhaust by use of the ficw rates.
i i
0-1 )
i l
.- ~ -
- ~% D A-h MAKEDP I MAKEUF STOR Act STORAGE TANK TANK WT 2
" us 7 2 t.iNlf 1 W if 1 g 9, 71 --
Il I , .
y h l l _-[- _ _
i
<F i ~
f i
__ _ _ g _t _ _ _
g J a,
' l >
8 SOACN 9
= f RECOVEMY g- -
$YET EM f' .
l l .
i I ,r o - - . d<
g
~~ .e y - ..& "
t I --
4 ,
I LWeg i TunJp4[
TUA8 TNT l LWPs gg ,
WON M1CYCLI SellW SU8LOsNG i SECYCLE E LOWOOWN Ppf4 TION UNIT 3 SYSTEM w g ,
j ] 1 4l i
4 G_ __" .
i, i - 3' 4.-
g v
\
1 - RM-6521
( M-6510) ,I ~ ' h ~
j s' y k RM*6$09 ) > <
1 9
C19tCULAT140 Y
- - + - = .- - e W ATE R ; .
SYSTEM
[ (2-EM-6321))
PELEASE
" Future" LE6tNG
~ ~ ~ ~ ~ SONDEhSATE LLARA9E h CVCS LETD7NN SOWPMENT CIVER5 OR AIN ACE TON
. = . -S- RECYCLA8if DE AER.4f(D EDULPMEf47 LE AK AGE
AECYCAAELE AERf ATEO ' 'b 'I '8 *
~ NQ4 IEECf CL ASLE 4hD MISC- COPdT AINVE N T SUMP 5
--*-- gTI AM Cf N.8 LOWDOWN LA8044TGAY OF AINO Df CONTAMINAT CN WATge P" Rcdiation Monitor
@ tune:NE stoc suw 9
@ vary:UM. CONTROL . ELEASE h $(COND ARy StDE STI.t.CEn!L E LcWDOny .
9 Figure 6-1 Liquid Ef fluent Streans, Radiation Monitors, and PAdveste -
Treatment Sy. stem at Seabrook Station 6-2 i
= _
i Turbine Gland AM-6528-1,2,3 Seal Condenser M- M -1,2 Exhaus t ,
ccN7AiutEN'T i TM -6333-1,2,3[
BunLCING VE NT IL AT ORS TuntlN{ b k n I
sttAu
- EACTH St4EPATORi
\ su4c.No g --
- TV%s?NE ,* M EGE(4 t
- ygg i ;;*
w i 1 p
SECGNOARy I qgi 4
. -(
s
/ ,
i in3
- y. =
3.
y CCNT AtN8WINT PUFGE A1Re-4 {_ _
J E ]
f e
<P
-Q B LOWDCW*4 W45? E R
b l<
F LA3w TANK 9U40a % f 2
l v sf.T [ f ga ng REAt* foe COOL W N C A SEDUS 4W ASTE #GOCES$ ENC SYSTIM M + 2 F " #R et.1 A A ) , ,
db
' N;D s i TYPlCAL OF S d i i
CUARD i ' "5 V
< SED 1p ', d'? 0, .
' I .
ST gk AFTCR )d
~
NE 8 ' g
' k:-f .
b .141 ' ' -+
')j l -J CHAACCAL86DS PM '%f A R Y DPYEA goggg;gq M80El' TAM j ,.
Auxite4%y [, l AW L3 8% ,
fe
~
j w 'i' l VOLUnli CONTROL 4 1ANK dl i
- i ,
DEC A51ElEM p l
- - - 2-b3w c , ) ,l h- AustisARY
- - -. ,mcutLD.NG : VENT
- Am
_ en -
b LEGE Q c-H - HEPA FILiER C .- CH.A ACC A L F I L T E R gn, 3]
RM + ftadiation Moni:or BUILDING hY ~
Figure 6-2 Gasecus Eff1 cent Streams, Radiation Monitors, and Radasste Treatrent System at Seabrock Station 6-3
T 4
7.0 AASES FOR DO5T CALCLfLATMNJETHODS
') .1 Li. quid Release Oose Calculations This section serves: (1) to document the development and conservative reture of Metho5 I equatiocs to provtie backgrocnd information t'e Method i users, and (2) to idsntify the general equatic;is, parameters and approaches to Method Il-tyoe dose assessments.
M3thod I may be used to shw that the Technical Specifications which limit off-Jite total tody doss from liauids (3,11.1,2 and 3.11.1.3) have been met for releases over the appropriate periods. The quarterly and annual dose limits in Technical Specification 3.11.1.2 are based on the ALARA design oojectives in 10tfR50, Appendix } Subsection II A. The minimum dose values noted th lechnical Specification 3.11.1.3 ar6 " appropriate. fractions," as determined by the NAC, cf the desigre objective to ensure that radsaste equipment is used as required to keep off-site doset ALARA.
Method I was developed such that "the actual exposure of an indiyiccal ... is VM 5kfly to he substanti' llya ur.derestimated" (10CFR50, Appendix J). Ths definition, below, of a single " critical receptor" (a hypot Ntica individual whose behavior results in an unrealistic 31ly hfsh -
dose) prc,vides part of the conservative margin to the calculaticr. of total body dose ir Method I. Method I) allWs that actual individuals, associated with identifiable exposure pathways, be taken into acccunt for any given release. In fat.t. Method I was based on a Method II crialysi; for a critical receptor assur,ing si) principal path.tays present innead pf any real individual. That analysis was called the hase case;' it was tiien re:fuced to form Method I. The geceral equations used in the base case analysis are also esed as the starting point in Methoc 11 evaluations. The base case, the ethod of redcctfon, and the assumptions and data used are presented .below.
"ihe steps perf ormed in the Method I derivatien follow. First, the dose impact to the critical receptor [in -the form of dose f actors DFL (arer/Ci)) for a unit activity release of each radioisotope in liquid efflcents was derived. ine case case analysis uses the general equations, metheds, data and assynctions in Regulatory Cuide 1.109 (Equaticos A-3 and 7-1 .
J I
A-7, R;farenco A). The liquid pathways tentributing to an incividual dose are dur' to consueption of fish end !nvertebrates, shoreline activities, and swimming and .botting near the discharge poiot. A plant discharge flow rate of 318 f t / sac was used with a mixing fatio of 0.10. The mixing ratic of 0.10 correspoods to the pronet dilutico or near-field mixing ione created at the ocean surface by the multiport dif futers. The location of the cr'itical '
receptor is assumed to be the e.1ge of the mixing zone at the ocean surface. P The transit tiae used for the aquatic food pathway was 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> atd for f
shoreline activity 0,0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />. Table 7.1-) outlines the human cor,sumption and environmental parameters used in the analysis. lhe resulting, site-specific, total body dose f actors sc.cear in Table 1.1-11.
i Note that the liquid dose f actors calculated refit:t a one unit operation. Liquid waste f rvo both unitt is processed by a ceremon pr.ocessing facility. In the casa of two-unit operetion, the liquid waste releases .must be apportioned accordin.31 y to . tach coit.
l 7.1.1 00se to the Total Body For any liquid release, during any period, the increment in total bcdy dose f rom radionuclide "i" is:
1 AD *O i 0FL II-I}
tb itt (crem) (uti)(*#f*)
where:
i DFLitb = Site-specific total body dose f actor (eren/vci) for e liquid release. It is the highest of the four age groups.
See Table 1,1.11.
Q1
= Total activity (vC1) released for radionuclide "la. ,
3 Method I is more conservative ttan Method II in the region of the l Technical Specification limits because the dose factors DFlitb Cd 1" Method I were chosen for the base case to be the highest of the four age groups (adult, teen, child and infant) for that radionuclide. In effect each radionuclide is conservatively represented by its own critical age group.
1-2 4
. -, ,y , _ _ r -. ._,v ,w , .--. m.,,-r , .
\
7.1.2 Ocse te the Critical Organ The methods to calculate maximum organ dose parallel to the total body dose methods (see Sect 19n 7.1.1),
for each radionuclide, a dose factor (arem/wCi) was deters,in,ed for each of severi organs and four age groups. The largest of these was chosen to be the jaaximum organ dose factor (DFLj ,,) for that radionuclide. DFL4 ,,
also includes the external dose contribution to the critical organ.
For any liquid release, during any period, the increment in dose from
- radionuclide "1" to the maxin.am organ is:
AD,3 =0 $ DFL imo (7'2)
(mrem) (uti) (*C I where:
OfL imo = Site-specific maximum organ dose factor (mrem /pti) for a liquid release. See Table 1.1.11.
Qi
= Total activity (pCi) released for radionuclide "i".
e s
7-3 i
.L <
O w ^
k N O O O O O. O. O. O.
J N
< m O O O O
% L Z w m
C Z ^ O O O C
- M
- d. Q O.
r > O. .
< N @ N PJ O O E N m O 133 I
- O
^ O O O O
.E
-* Cr. O O. Q. O.
~
g y e E N CD m CD C
- W W N 3 =
c'n M *
+
.O s- 4J W #
Ce O
h W st:
- O O.
O O.
O O. O.
- g f J > < W W O o W \ M # "
O 3 L 4 "O *'
.C <*
- ec c -
Y G Cs M
^
- 6.J > O O O O J cc % O O O O w' { CC w Cd * * * =
y g O O O
< r- w O on!g 33 H< **
gi O3-e=I **\ C " '
> m. u e-l, C-1 C.
~
[N
$OL * ^ O O O O
- = O* O O m
g y , CE >
- c.
- g ,f w N @ C") e- O C J t > d w Z M Wf ,, - w 3 0 O'~
^ O O O O g, _
_ > C. O. . O.
3 A N - 4 @ C f .
glg - C N e i.C
-' 'C; v
v c L c m 2 O O O O
$ W >
$'I~
u < N O. O. O. O.
O
[$ w E
C w
O O O G E c O to k ^
elm D* O O O O M N O. O. O. O.
a cc
- w O O O O E *-
m enJ w
^ CD
>
- cc O O O O O wC > O. O. O, O. e.
<w % e w> C O O O O J d de w
.T e=
3 m C
- CC C C C O h C > O. O. O. O. L w %
O
> C O O O O e*
nd 80 4 w F
& O
- V C CD w e- C - rc &
C 3 b =*= t.- CC
< m s e c y.4
- 4 r v --
7.2 Gaseous Release Dose Calculations 7.2,1 Total Body Dose Rate From Noble Gases This section serves: (1) to document the development of the Method I equation. (2) to provide background information to Method I userr', .and (3) to
. identify the general equations, parameters and approaches to Method II-type dose rate assessments.
j Method I may be used to show that the Technical Specification which limits total body dose rate from ncble gases released to the atmosphere
! (Technical Specification 3.11.2.1) has been met for the peak noble gas release
! rate.
Method I was derived from general equation B-8 in Regulatory Guide
't i 1.109 as follows:
b = lE+06 S p [X/Q) hg CFB (7-3) tb $
3 IpCi) III sec mrem I yr I IvCi) sec Imrem-m pCi-yr )
vCi ,3 ) ;
i where:
S p
= Shielding factor in residential structures = 0.7. l
[X/Q]T = Maximum receptor location long-term average gamma atmospherf c
( dispersion factor.
= 6.2E-07 (sec/m ).
Qg = Release rate to the environment of noble gas "i" (yCi/sec).
)
3 i
DFB 4
= Gawna total body dose f actor, ("C ). See Table 1.1-10. ,
(Regulatory Guide 1.109. Table B-1).
Equation 7-3 reduces to:
" ~#3 OIO tb 3 i i (3-3) 7-5 l
i
'l
)
Crem uCi crem-n.3 I yr I DCi-sec) Isec) Ipci-yr I Ci +3 The selection of critical receptor, outlined in Section 7.3 is inherent in the ,
1 derived Method I, since the maximum expected of f-site long-term average atmospheric dispersion factors were used. All noble gases in Table 1.1-10 must be considered, none are deemed insignificant a priori. i, .
A Method II analysis could include the use of actual concurrent meteorology to assess the dose rates as the result of a specific release.
7.2.2 Skin Dose Rate From Noble Gases This section serves: (1) to document the development of the Method I equation, (2) to provide background information to Method I users, and (3) to identify the general equations parameters and approaches to Method II-type dose rate assessments. The methods to calculate skin dose rate parallel the total body dose rate methods in Section 7.2.1. Only the differences are presented here.
Method I may be used to show that the Technical Specification which limits skin dose rate from noble gases released to the atmosphere (Technical Specification 3.11.2.1) has been met for the peak noble gas release rate.
The annual skin dose limit is 3,000 mrem (from NBS Handbook 69, Reference D, pages 5 and 6, is 30 rem /10). The factor of 10 reduction is to account for nonoccupational dose limits.
It is the skin dose commitment to the critical, or most limiting, off-site receptor assuming long-term site average meteorology and that the release rate reading remains constant over the entire year.
Method I was derived from the general equation B-9 in Regulatory Guide 1.109 as follows:
D = 1.11 S p D ir
+ 3.17E+04 Og [X/Q) DFS 4
(7-4) i 7-6
Ci set I
Frem yr I II IIItrad}yr IDCi-Vr)
Ci-sec F I ,3 frem-m )
) IpCi-yr where:
1.11 = Average ratio of tissue to air absorption coefficients (will -
convert mrad in air to arem in tissue. ,
DFSj = Beta skin dose factor for a semi-infinite cloud of
- radionuclide "i" which includes the attenuation by the outer
" dead" layer of the skin.
T T (7-5)
D = 3.17E+04 Qg [X/Q] DF 3
ir i 3
Ci see '
Imrad) yr IDCi-vr)
Ci-sec IEII ,3 ) mrad-mpCi-yr DF} = radionuclide Gamma air "i". dose f actor for a uniform semi-infinite cloud of Now it is assumed for the definition of (X/Q ) for Reference 8 that:
D
- D [X/Q)T/[X/Q) (7-6) inite air 3
mrad sec m Imrad) yr I yr II,3 ) I sec) and Q9 = 31.54 h4 (7-7)
Cl y y_Cl C
g (Ci-secy y yr pCi-yr sec so: b 1E+06 [X/Q]Y h4 (7-8) skin
- I *II b F DF}
3 sec Imrem}
yr I) I) IDCi)pCi I,3 ) IvCi) sec Imrad-m pci-yr )
+ 1E+06 X/0 h$ DFS g i
set uCi IDCi)
Ci ,3 set Imrem-m pCi-yr )
7-7 i
substituting
[X/Q]Y = 6.2E-07 sec/m3 X/0 = 1.4E-06 sec/m3 SF
= Shielding factor - D.7
+ ' : 7. (7-9) gives b skin = 0.48 1
h' g DF}
+ 1.40 i
hg DFS 3 3 garem) (f_ig mrem-m )
i DCi-sec) guci) gerem-m )
yr (DCi-sec-erem) 3 sec pCi-yr 3 sec pCi-yr 4 i
pCi-m -mrad Ci-m (7-10)
=
i hg [0.48 DF} + 1.40 DFS g
]
define
( 7-11 )
DFj=0.48DF}+1.40DFS g then: h skin
- DFj (3-4) i mrem) yr uti) sec mrem-sec) pCi-yr The selection of critical recepto'r,' outlined in Section 7.3, is inherent in the derived Method I, as it is based on the determined maximum expected off-site atmospheric dispersion factors at the most limiting location. All neble gases in Table 1.1-10 must be considered.
7.2.3 Critical Organ Dose Rate Fror,i iodines. Tritium and particulates With Half-Lives Greater Than Eiont Days I
This section serves: (1) to document tef acu <jment of the Method I equation, (2) to provide background information to Method I users, and (3) to identify the general equation's parameters and approached to Method II type dose rate assessments. The methods to calculate skin dose rate parallel the total body dose rate methods in Section 7.2.1. Only the differences are prasented here.
,' 7-8 9
F
' Meth::d I may be used to show that the Technical Specification which limits organ dose rate from iodines, tritium and radionuclides in particulate form with half lives greater than 8 days released to the atmosphere (Technical Specification 3.11.2.1) has been met for the peak above-mentioned release rates. .
The annual organ dose limit is 1500 mrem (f rom NBS Handbook 69, Reference 0, pages 5 and 6). It is controlled by looking at the critical organ dose coenitment to the most limiting of f-site receptor assuming long-term site average meteorology.
Theequationforb,isderivedbymodifyingEquation3-8from e
Section 3.9 as fgliows:
D cg
= Q$ DFG ico ( -8)
(mrem) (pCi) (*C I applyir.g the conversion factor, 3.154E+07 (sec/yr) and converting Q to hinpCi/secyields
- r. I -I 2)
D cg
=
3.154E+07 L Q DFG ico i
g mrem yr y yyr uti) set mrem) uti Eq. 3-8 is rewritten in the form:
beg = hj DFG
$co (3-5) y
{ mrem) yr sec mrem-sec) pCi-yr where DFG = 3.154E+07 0FG ico (7-13)
$co mrem-sec mrem I pCi-yr I Isee) yr I pCi I 7-9
The selection of critical rsceptor, cutlined in Secticn 7.3 is inherent in Method I, as are the maximum expected off-site atmospheric dispersion factors.
Should Method II be needed, the analysis for critical receptor, critical pathway (s) and annual average atmospheric dispersion facters may be performed with concurrent meteorology and latest land use census ! data to identify existing pathways.
~
Because of the choice of atmospheric dispersion factors and pathways, it is expected that Method I results always will exceed Method 11 calculations. Either method provides adequate margin to ensure that the annual average concentrations based on organ dose from 10CFR20.106(d) are not exceeded and that the derived peak release rates are conservative.
7.2.4 Gamma Dose to Air From Noble Gases This section serves: (1) to document the development and conservative nature of Method I equations to provide background information to Method I users, and (2) to identify the general equations, parameters and approaches to Method II-type dose assessments.
Method I may be used to show that the Technical Specification which limits of f-site gamma air dose f rom gaseous effluents (3.11.2.1) has been met for releases over appropriate periods. This Technical Specification is based on the objective in 10CFR50, Appendix I, Subsection 8.1, which limits the estimated gamma air dose at unrestricted area locations.
For any noble gas release, in any period, the increment in dose is taken f rom Equations B-4 and 8-5 of Regulatory Guide 1.109 with the added T
assumptionthatDfinite =D[X/Qf/[X/QD Qg (7-14)
AD}r a = 3.17E+04 [X/Q)T i DF}
3 d (mrad) (D (d) _p )
C sec) (sec/m )
7-10 J
where:
3.17E+04 = number cf pCi per Ci divided by the numbIr cf seconds per year.
[X/Q]T = maximum annual average gamma atmospheric dispersion factor
= 6.2E-07 (sec/m )
09 = number of curies of noble gas "i" released DF} = Ganna air dose factor for a uniform semi-infinite cloud of radionuclide "1".
which leads to:
= 2.0E-08 (3-6)
D ar Qg DF{
1
~V" "
(mrad) (D ) (pC1) (*C - I pCi-m 3 The major difference between Method I and Method II is that Method II would use actual or concurrent meteorology with a specific noble gas release spectrum to determine [X/Q]T rather than use the most limiting meteorological dispersion value obtained for the years 1979 to 1981.
7.2.5 Beta Dose to Air From Noble Gases This section serves: (1) to document the development and conservattve nature of Method I equations to provide background information to Method I users, and (2) to identify the general equations, parameters and soproaches to Method II-type dose assessments.
Method I may be used to show that the Technical Specification which linits of f-site beta air dose from gaseous ef fluents (3.11.2.1) has been met for releases over appropriate periods. This Technical Specification is based on the Objective in 10CFR50, Appendix I, Subsection B.1, which limits the estimated beta air dose at unrestricted area locations.
For any noble gas release, in any period, the increment in dose is taken f rom Equations B-4 and B-5 of Regulatory Guide 1.109:
7-11
.- =
0 AD = 3.17E+04 X/Q Qg DF (7-15) ir 1
3 mrad-m (mrad) (DCi-vr)
Ci-sec Isec) I" )I pCi-yr I
,3 0
where: DF = Beta air dose factors for a uniform semi-infinite cloud of ~
radionuclide "i".
subs.tituting X/Q = Maximum long-term average undepleted atmospheric dispersion factor 3
= 1.4E-06 sec/m ,
We have 0 0 D = 4.4E-08 09 DF (3-7) air i
(pci-v"3 ) "d (mrad) (pCi) ("C - )
pCi-m 7.2.6 Dose to Critical Organ From Iodines. Tritium and Particulates With Half-Lives Greater Than Eiaht Days This section serves: (1) to document the development and conservative nature of Method I equations to provide background information to Method I users, and (2) to identify the general equations, parameters and approaches to Method II-type dose assessments.
Method I may be used to show that the Technical Specifications which limit of f-site organ dose f rom gases (3.11.2.3 and 3.11.4) have been met for releases over the appropriate periods. Technical Specification 3.11.2.3 is based on the ALARA Objectives in 10CFR50, Appendix I, subsection 11 C.
Technical Specification 3.11.4 is based on Environmental Standards for Uranium Fuel Cycle in 40CFR190, which applies to direct radiation as well as liquid and gaseous effluents. These methods apply only to iodine, tritium, and particulates in gaseous ef fluent contribution.
7-12
Meth:d I was develcped such that "the actual Gxptsure of an individual ... is unlikely to be substantially underestimated" (10CFR50, Appendix I). The use below of a single " critical receptor" provides part of the conservative margin to the calculation of critical organ dose in Method I. Method 11 allows that actual individuals, associated with identifiable exposure pathways, be taken into account for any given relea'se.
In fact, Method I was based on a Method II analysis of a critical receptor assuming all pathways present. That analysis was called the " base case"; it was then reduced to form Method I. The base case, the method of reduction, and the assumptions and data used are presented below.
The steps performed in the Method I derivation follow. First, the dose impact to the critical receptor [in the form of dose factors DFG g (mrem /Ci)) for a unit activity release of each iodine, tritium, and particulate radionuclide with half lives greater than eight days to gaseous effluents was derived. Method I was determined using simplifying and further conservative assumptions. The base case analysis uses the general equations methods, data and assumptions in Regulatory Guide 1.109 (Equations C-2, C-4 and C-13 in Reference A). Tables 7.2-1 and 7.2-2 outline human consumption and environmental parameters used in the analysis. It is conservatively assumed that the critical receptor lives at the " maximum of f-site atmospheric dispersion factor location" as defined in Section 7.3. In addition, the receptor is assumed to be exposed to all pathways (see Section 7.3). The resulting site-specific dose f actors are for the maximum organ which combine the limiting age group with the highest dose factor for any organ with each nuclide. These critical organ, critical age dose factors are given in Table 1.1-12.
For any iodine, tritium, and particulate gas release, during any period, the increment in dose from radionuclide "i" is:
aD = Q DFG g (7-16) where DFG g is the critical dose f actor for radionuclide "i" and Qg is the activity of radionuclide "i" released in curies.
7-13
Because of the assumptions about receptors, envir:nment, and radionuclides and because of the regulations of 10CFR50 and 40CFR190, the lack of immediate restriction on plant operation, and the adherence to 10CFR20 concentrations (which limit public health consequences), a failure of Method I (i.e., the exposure of a real individual being underestimated) is improbable and the consequences of a failure are minimal. : ,
7 . 2.-7 Special Receotor Gaseous Release Dose Calculations Technical Specification 6.9.1.6 requires that the doses to individuals involved in recreational activities within the site boundary are to be determined in the annual Semi-Annual Effluent Report.
The gaseous dose calculations for the special receptors parallel the bases of the gaseous dose rates and doses in Sections 7.2.1 through 7.2.5.
Only the differences are presented here.
4 The special receptor XQs are given in Table 7.3-2.
7.2.7.1 Total Body Dose Rate From Noble Gases Method I was derived f rom Regulatory Guide 1.109 as follows:
DFB (7-3) b = 1E+06 S p [X/Q]T i $
tb General Equation (7-3) is then multiplied by an Occupancy Factor (OF)
! to account for the time an individual will be at the on-site receptor L
locations during the year. For the Education Center, and the " Rocks", the OFs t
are:
5 "
Education Center -
I
- 0.0014 8
i (I)Taken from Seabrook Station Technical Specifications (Figure 5.1-1).
7-14
. ~
+
The ' Ricks" - jr = 0.0076 substituting Sp = 0.7 for the Education Center
= 1.0 for the " Rocks" ,
[X/Q]T = 2.0E-06 sec/m (Education Center)
= 5.9E-06 sec/m3 (The " Rocks")
multiplying by 0F = 0.0014 (Education Center)
= 0.0076 (The " Rocks")
gives
( 7-17) i DFB $(mrem /yr) btbE = 0.0014i DFB (mrem /yr) ( 7-18) i $
btbR = 0.045 i where:
DtbE' and DtbR = Total body dose rates due to noble gases to an individual at the Education Center and the " Rocks" (recreational site), respectively, hj = defined previously DFB 9 and DFB, = defined previously.
'l 7-15
, -- - --.- __ ,_ ,,-_---w. . _ , - , - -. . - _ . _, ., .- _
,._,3m. ,
7.2.7.2 Skin Dose Rate From Noble Gases Method I was derived from Equation (7-8):
+ (7-8) hg bskin " I*II SF1E46 [X/Q)T 1 DF} ,
-t.
1E+06 X/Q i DFS, substituting SF = 0.7 for the Education Center
= 1.0 for the " Rocks"
[X/Q]T = 2.06E-06 sec/m3 (Education Center) 5.9E-06 sec/m3 (The " Rocks")
X/0 = 6.7E-06 sec/m3 (Education Center) 2.3E-05 sec/m3 (The " Rocks")
multiplying by 0F = 0.0014 (Education Center)
= 0.0076 (The " Rocks")
gives
[1.54DF}+6.71DFS](mrem g /yr) bskinE = 0.0014 3,,,_ . 0.e.,, r 6 [6.4, ,,1 .. 5 , , , (m,em,,,,
7-16
- _ _ . _ _ __. _ _ . ~ .
then:
h DF'i II-I9}
iE (arem/yr) bskinE - 0.0014 g DF, (7-20) i 1E (arem/yr) hskinR = 0.0076g
~
where:
skinE andbskinR = the skin dose rate due to noble gases to an b
individual at the Education Center and the " Rocks,"
respectively.
h = defined previously.
4 DF iE and DF'iR = the combined skin dose factors for radionuclide "i"
' for the Education Center, and the " Rocks",
respectively (see . Table 1.1-13.)
j 7.2.7.3 Critical Organ Dose Rate From Iodines. Tritium and Particulates With Half-lives Greater Than Eight Days The equations for Dc , are derived in the same manner as in Section 7.2.2, except that the occupancy factors are also included. Therefore:
r DFG icoE (mrem /yr) (7-21) bcoE = 0.0014 NcoR (mrem /yr) N bcoR = 0.0076 where:
b oE andbcoR = the critical organ dose rates to an individual at the Education Center and the " Rocks", respectively.
h = defined previously.
4 7-17
DF' ccE and DF'iceR = the. critical crgan d:s2 rate fact:rs for radienuclide "i" for th2 Educaticn Ccnter and the "R:cks," respectively (se2 Table 1.1-14.)
7.2.7.4 Gamma Dose to Air From Noble Gases Method I was derived from Equation (7-14):
~ 01 DF} (7-M)
D air
= 3.17E+04 [X/Q]Y substituting
[X/Q]T = 2.0E-06 sec/m3 (Education Center)
= 5.9E-06 sec/m (The " Rocks")
' multiplying by 0F = 0.0014 (Education Center)
= 0.0076 (The " Rocks")
and 1E-06 pCi/Ci
~
gives T Oi DF ( -23)
DairE = 8.88E-ll i (mrad) 01 DF{ I7-24)
DairR = 1.42E-09 (mrad) where:
= the gamma air doses to an individual at the D[ ire and D airR Education Center and the " Rocks," respectively.
Q9 = total activity (pCi) released to the atmosphere via the station vents of each radionuclide "i" during the year.
7-18 1
DF}andDF}=d2finedprevisusly.
7.2.7.5 Beta Dose to Air From Noble Gases Method I was derived f rom Equation (7-15): ,
~
0 01 DF (7-15)
Dair = 3.17E+04 X/Q substituting X/Q = 6.7E-06 sec/m3 (Education Center)
= 2.3E-05 sec/m3 (The " Rocks")
multiplying by 0F = 0.0014 (Education Center)
= 0.0076 (The " Rocks")
and IE-06 pCi/Ci gives 0
DairE = 2.97E-10 7
[O i DF 0
i (mrad)
(7-25) 0 Oi D (7-26)
! (mrad) 0 irR = 5.54E-09 where:
0 B 0 and D aire airR = the beta Center airthe and doses to an respectively.
" Rocks," individual at the Education Og = total activity (pC1) released to the atmosphere via the station vents of each radionuclide "i" during the year.
7-19
0 0 DF and DF = defin d previously.
7.2.7.6 Critical Orean Dose From Iodines. Tritium and Particulates With Half-Lives Greater Than Eiaht Days Method I was derived in the same manner as Equation (3-18); .
~
D,=
c b Nco (3-18) multiplying by 0F = 0.0014 (Education Center)
! = 0.0076 (The " Rocks")
and lE-06 pC1/Ci gives 0 DFG I ~2 )
i icoE (mrem)
DcoE = 0.0014 Oi DFG ( -28)
Dcop = 0.0076 icoR (mrem) l where:
! D and D the critical organ doses of an individual at the to c R.= Education Center and the " Rocks," respectively.
09 = the total activity (pCi) released to the atmosphere of radionuclide "i" during the year.
DFG and DFG icoR = the critical organ dose factors (mrem /pCi) for the icoE Education Center and the " Rocks," respectively for each radionuclide "i". The factors represent j the age group and organ with the largest dose f actor (see Table 1.1-14). 1 The special receptor equations can be applied under the following conditions (otherwise, justify Method I or consider Method II):
I 7-20 t
- 1. _ Normal cperations (nonemergIncy event).
- 2. Applicable radionuclide releases via the station vents to the atmosphere.
If Method I cannot be applied, or if the Method I dose exceeds this limit, or if a more refined calculation is required, then Method II may be applied, i
1 f
d i
f P
i 7-21 ,
I l
l L. -- . . . . _ . . . - . . - , - _ . _ _ - - _ _ - . _ _ _ _ ___ _ _ _ __
I Atil l. 1. ? -l Fnvironmental Parameters f or Gaseous Ef fluents at Seabrook Station (Derived from Reference A)* 1 Vegetables Cow Milk Goat Milk Meat Stored Leafy Pasture Stored Pasture Stored Pasture Stored variable (Kg/M2 ) 2. 2. 0.75 2. 0.75 2. 0.75 2.
(V Agricultural Productivity 240. 240. 240. 240. 240. 240. 240.
> Soil Surface Density (KG/M 2) 240.
- 48. 48. 48. 48. 480. 480.
I 1rc sport Time to User (HRS) 131400. 131400. 131400. 131400. 131400. 131400. 131400. 131400.
IB Soil Exposure Time (HRS) 1440. 1440. 720. 720. 720. 720. 720. 720.
TF Crop Exposure Time (HRS)
Tto Plume 1440. 24. O. 2160. O. 2160. O. 2160.
TH Holdup Af ter Harvest (HRS)
QF Animals Daily Feed (KG/ DAY) 50. 50. 6. 6. 50. 50. g 0.50 0.50 0.50 FP Fr:ction of Year en Pasture
- 1. 1. 1.
FS Fr:ction Pasture whea on Pasture FG Frcction of Stored 0.76 Veg. Grown in Garden FL Frcction of Leafy 0.50 Veg. Grown in Garden .,
FI Fr ction Elemental Iodine = 0.5 H Abs 31ute (gm/M3 )
Humidity = 8.00 o Regnistory Guide 1.109
TABLE 7.2-2 ,
Usage Factors for Various Gaseous Pathways at Seabrook Station (from Reference A,~ Table E-5)*
Maximum Receptor:
Age Leafy Gr9up Vegetables Veaetables Milk Meat Inhalation .
(kg/yr) (kg/yr) (1/yr) (kg/yr) (m3 /yr)
Adult 520.00 64.00 310.00 110.00 8000.00 Teen 630.00 42.00 400.00 65.00 8000.00 Child 520.00 26.00 330.00 41.00 3700.00 Infant 0.00 0.00 330.00 0.00 1400.00 The " Rocks" and Education Center:
Age Leafy Group Vegetables Vegetables Milk Meat Inhalation (kg/yr) (kg/yr) (1/yr) (kg/yr) (m /yr)
Adult 0.00 0.00 0.00 0.00 8000.0 Teen 0.00 0.00 0.00 0.00 8000.0 -
Child 0.00 0.00 0.00 0.00 3700.0 Infant 0.00 0.00 0.00 0.00 1400.0
I 7-23 ,
1
- 1
7.3 Receptor Points ano Averaae Atmospheric DisD7rsion Factors for Important Exposure Pathways The gaseous effluent dose equations (Methaj 1) have been simplif~ied by assuming an individual whose behavior and living habits inevitably lead te a higher dose than anyone else. The following exposure pathways td gaseous-t effluents listed in Regulatory Guide 1,109 (Reference A) have been considered:
- 1. Direct exposure to contaminated air;
- 2. Direct exposure to contaminated ground; 4
- 3. Inhalation cf air;
- 4. Ingestion of vegetables;
- 5. Ingestion of cow's and goat's milk; and
- 6. Ingestion of meat.
Section 7.3.1 details the selection of important off-site and on-site locations and receptors. Section 7.3.2 describes the atmospheric model used to convert meteorological data into atmospheric dispersion factors. Section 7.3.3 preser.ts the maximum atmospheric dispersion factors calculated at each of the off-site receptor locations.
7.3.1 Receptor Locations The most limiting site boundary location in which individuals are, or likely to be located as a place of residence was assumed to be the receptor for all the gaseous pathways considered. This provides a conservative estimate of the dose to an individual from existing and potential gaseous pathways for the Method I analysis.
This point is the N sector, 914 meters from the center of the reactor units.
7-24
Two other locaticns (cn-site) were analyzed for direct gr:und plane 1 exposure and inhalation only. They are the ' Rocks" (recreaticnal site) and 1, the Education Center given in Table 5.1-1 of the Technical Specifications. ,
f l .
-r. r
~
1 i
i 4
1 i
I I
1 1-25 I
r
- , _ . - - , . , - . - , , - - . , , . - . . , . , - - . -n,,e , ,-, r, r
., , , , ~ , ,,.,..--...n
7.3.2 Seabrook Station Atmosoheric Dispersion Model ,
J The time average atmospheric dispersion factors are computed for i
routine (long-ters) ground level releases using the AEOLUS Computer Code.
(Reference B). AEOLUS is based, in pa-t, on the straight-line airflow model j discussed in Regulatory Guide 1.111 (Reference C). f.
l
- AEOLUS produces the following average atmospheric dispersion factors for each location- t
{ ,
Undepleted X/Q dispersion factors for evaluating ground level 4
1.
' concentrations of ncble gases; ,
- 2. Depleted X/Q dispersion factors for evaluating ground level I concentrations of iodines and particulates; i r
- 3. Sama X/Q dispersion f actors for evaluating gama dose rates from a ,
f sector averaged finite noble gas cloud (multiple energy undepleted l P
? source); and s
j 4. D/Q deposition factors for evaluating dry deposition of elemental J
i radiciodines and other particulates.
! Gama dose rate is calculated throughout this ODCM using the finite cloud model presented in " Meteorology and Atomic Energy - 1968" (Reference E, Section 7-5.2.5. Inst model is implemented through the definition of an i
T ef fective ganma at2cspheric dispersion f actor, [X/Q ) (Ref erence 8, Section i
6), and the replacemer,t of X/Q in infinite cloud dose equations by the
] T
', [X/Q ). {'
7.3.3 (gna-Term Averaae Atmosoheric Discersion Factors for Acceptors
{
Actual measured meteorological data for the two-year period,1979 }
- through 1981, were analyzed to determine the locations of the maximm of f-site
! average atmospheric dispersion f actors. Each dose and dose rate calculation incorporates the maximum applicable off-site long-term average atmospheric j dispersion factor. The values used and their locations are sumarized in f
- Tables 7.3-1 and 7.3-2. '
1 1 L 7-26
[
- i
TABLE 7.3-1 Scabrook Station 91lution factory 1
Dose to Critical' Dose Rate M individual - _ Bose to Air _6rgen Total _ Body _, Sk i n_ _ _Cri t ita l _ Organ Gaasna Beta _ Thyroid
- - 4.3E-06 - -
1.3E-06 X/0 dep'eted (5*f) -
X/Q undepleted (5'C) -
1.1E-06 - -
1.4E-96 -
3 a
D/Q ( ) - -
3.ll-09 - -
3.1E-09
? 6.2E-07 6,2E-07 -
6.2E-07 - -
X/QTm(If)
O
- Marth site boundary, 916 meters from Containment Guilding
, 1
.c -l
- 5 i
i 9
.. . _ . _ _ - . . - . . _ _ . _ _ . _ . . . . . . _ _ - - ._ . - . - ~ . - . _ _ .-.. . - -
f TABLE 7.3-2 Scabrook Station ci'lution Factors fo L 5pecial (On-Sittq_ Receptors ,
Dose to Criticei .
Dose Rate to Individual Dete,tG _Alr , A qan Total Bod 1 Skin critital Or_gan Ganu Beta Thyrcid_,
Education _ Center:
(WSW - 335 meters)
X/Q depleted ( EC) - -
6.21-05 - -
6.20-06 3
m xtQ undepleted ( "3 )
C - 6.7E-06 - -
6.7E-06 -
m i D/Q ( )
I . ll# J8 -- - -
m E x/QT (C) 2.CE-06 2.00-06 -
2.GE-06 - -
m
= ::t The ' Rocks" (ENE - 3:11 feeters)
X/Qdepleted(y) - -
2.10-05 - -
2.lE-05 m*
X/Q undepleted ( ) -
2.11-05 - -
2.3r-05 -
L'/Q ( )
- - 5.0E-08 - - -
- i A/QT ( b'3 ) 5.9E-06 5.9f'06 -
5.9E-06 - -
3 m
i
8.0 BASES FOR L10010 AND 6ASEOUS MOWITOR SETPOINTS _
8.1 Basis for the Uauid Waste Test Tank Monitor Setpoint The liquid waste test tank monitor setpoint must ensure that Specification 3.3.3.9 is not exceeded for the appropriate in-plant pathways.
1 The liquid waste test tank monitor is placed upstream of the major source of dilution flow.
The derivation of Equation 5-1 begins with the general equation for the response of a radiation monitor:
R =
C,g S), (8-1) l 1
(cps) ( ) (# )
4 wnere:
- ! = Response of the coalter (cps)
S;3 = Detector coucting ef ficiency for radionuclide "i" (cps /(pCi/mi))
C g = Activity concentri, tion of radionuclide "i" in mixture at the monttor (901/ml) 1tte detector calibration procedure for the liquid waste test tank monitor st Seabrook Station establishes a counting ef fittency by use of a known calibration source standard and a linearity response check. Therefore, i in Eccation 8-1 one may substitute 53for Sj y , where 53 is the detector counting ef ficiency determined from the calibration procedure. Therefore, I (quation 8-1 becomes l
(
R = C g (8-2)
S) ,
, i l (cps) (cos-m1) g ((,C_1,
)
) j j
l 91 1
1h3 MFC for a given radionuc11d2 must n;t be exce:ded at the point of discharge. Den a cixture of radionuclides is present,10CFR20 specifies that the concentratico at tres point of discharge shall be limited as follows:
13 , (8-3) i 1 t. .
di-ml
- Inf vti) where:
C = c y conceo kad n rado,ucWe P b W mMm at di the poir.t of discharge (pCi/ci)
MPC g = MPC f or radionuclide "i" frcm 10CFR20, Appendi,x 8. TaDie 11, Column 2 (pCi/ml)
The activity concentration of radionuclide di" at the point of discharge is related to the activity concentration of radionuclide 81" at the monitor as follows:
F C =
C,3 (6-4 )
di [d (mi ) (ml ) (gpm) where:
C4 , = Activity concentration of radionuclide "1" in the mixture at the point of discharge (pCi/ml)
F, = Flow rate past monitor (gem)
F = Flow rate out of discharge tunnel (gpm) d 6-2
$ubstituting th2 right half Cf [guation 84 ftr Cdi in Equation 8-3 and
- solving for f I m ,V)*1d5 tht minieunt dilution factor needed to comply with d
Equation 8-3:
t . (b-5) .
DFain *-
(gpm) (al-41) where:
1 F = Flow rate out of discharge tunnel (gym) d F, = Flow rate past tronitor (qpm)
= Activity concentration of radionuclide '1" in mixture at the C ,g monitor (uC1/ml)
MPC, = MPC for radionuclide "i" from 10CFR20, Appendix B. Table II, Column 2 (uti/mi) f If F d/F ,is less than DFmin, then the tank may not be discharged until \
either F d I m r both are adjusted such that:
F (8-5) -
y- 2 0F ain (E) gpm usually F,/F ,is greater than DF ,gq (i.e., there is more dilution than necessary to comply with Equation t-3). The response of the liquid waste test tank monitor at the setpoint is therefore:
R
$etpoint
- D in (cps) () ( [) (f) 8-3 *
. . _ _ _ _ - - _ _ _ _._______.__-___________-__--_._____-___._______-________._____-_______-_s
- . - - _ = . - . - ..
The monit ring system is design:d to incorporate the detecter efficiency, S), into its software. This results in an automatic readout in 4 pC1/cc or pCi/mi for the monitor response. Since this procedure for converting cps to pC1/ml is inherently done by the system software, the m nitor response setpoint can be calculated in terms of the total waste test tank activity concentration in pCi/mi determined by the laborator.y analysis.
Therefore, the setpoint calculation for the liquid waste test tank is:
- ($ 1}
"setpoint O in "1
( el) I I I mi) 8.2 Basis for the Plant Vent Wide Ranae Gas Monitor Setpoints The setpoints of the plant vent wide range gas monitors must ensure that Technical Specification 3.1121.a is not exceeded. Sections 3.4 and 3.5 i thow that Equations 3-3 and 3-4 are acceptable methods for determining compliance with that Technical Specification. Which equation (i.e., dose to tot 61 body or skin) is more liciting depends on the noble gas mixture.
1herefore, each equation must be considered separately. The derivations of
, Equatio*s 5+5 and 5,5 begin with the general equation for the response R of a radiation moottor; R = $ C (0~7) i g
gi mi (cpm)
(C]*3-) ( Cm )
where:
- R = Response of the instrument (cpm) 3
- Sg , = Oetector counting efficiency for noble gas "i" (cper/(pti/cm );
l 1
I 8-4
_ . . _ . . _ , _ _ . _ _ . , , . _ _ _ ~ _ _ , . . . _ . , . . _ _ , _ . . , . . . - . _ _ _ _ . . . . . - _ . , , _ _ _ , , . . - . . . _ . . . . ,.
4 C g = Activit.y etnccctration cf n:ble gas *l' in th2 cixture at th2 3
coble gas activity monitre (yCi/ca )
~
C,g, the activity concentration of noble gas "i" at the noble gas activity monitor, may be expressed in terms of Qg by dividing by F, the apprcpriate flow rate. In the case of the plant vent noble gas activity monitors the , t appropriate flow rate is the plant vent flow rate.
C ,g
= hg h (8-8)
(cm3) (*sec) (C ,3) i where:
t hg = The release rate of noble gas "i" in the mixture averaged by the time constant of the measuring system for each noble gas listed in P Table 1.1-10 i F = Appropriate flow rate (cm /sec) i Substituting the right half of Equation 8-8 into Equation 8-7 for C,g yields:
i R - S gg hg h (8-9)
(cpm)
(CD}')(h)(g )
As in the case before, for the liquid waste test -tank froritor, the ,
plant vent wide range gas monitor establishes the detector counting efficiency by use of a calibration source. Therefore, 5 can be substituted for S gg 9
in Equation 8-9, where S is the detector counting ef ficiency determined 9 .
f rom the calibrattori procedure. Therefore. Equation 8-9 becomes: '
a b R =
h h hg (840) 8-5 1
4
, - - - - . - - -, - . , , + - - - - - ---%-_ , , - - - , -
.f.--, . - , - . , , . . ,,,y - , -..,_y,,.- -,~.., .,~-,,-,-e,. .- .. _ . , -
., - -- . . _ , _ - . _x., -- . . - . - ~ - . _ - -- . - . . - . _ - . - . . . . . . . . . -
4 3
] sec IgEj,) '
(cpm) (CDm-c~ipCi II 3 I sec
< cm The total body dose rate due to noble gases is determined with r
! Equation 3-3:
t.
O = 0.43 h, '8F8 (3-3)
- tb i 9
3 ,
erem y {oci-secy (g[j,) (orem-m yr 3 sec pCi-yr ,
Ci-m '
i L
j where: ,
t D = t tal body dose rate (prem/yr) j tb 1 r 3
0.43 = (0.7E+06) x (6.2E-07) (pci-sec/vci-m ) ;
j O.7 = attenuation factor that accounts for the dose reduction due to shielding provided by residential structures )
(dimensionless) .
k 4
1E+06 = number of DCi per pCi (pCi/yCi) j
! i 6.?E-07 = (X/0]T.- maximum annual average garena atmospheric ,
f dispersion factor (sec/m ) f j !
i
+
h, = The release rate of noble gas "i" in the mixture averaged i f
i by the time constant of the measuring system for each noble l gas listed in Table 1,1-10 (yC1/sec) l
- DFB, a total body dose factor (see Table 1.1-10) t 3
(mrem-m /pCi-yr) 1
! A composite total body gama dose f actor, OfB , may be defir.ed such that:
s .
1 4 i f
! 8-6 t
?
) l 1 i i
_ - - _ . . . _ ,. . . _ . , . . _ _ , _ . _ . _ . _ . . _ _ , , _ . . . _ . . . _ _ _ _ . . - _ . ~ . . _ _ . _ . . _ . _ _ . _ _ . . . _ _ . . , , _ _ _ _ . _ _ _
DFB g
i h= g i
hg DFB g (8-11 )
3 3 erem-m guC_i_) guc i) garem-m )
pCi-yr sec sec pCi-yr Solving Equation 8-11 for DFB g yields:
~
h,DFB, DFB = (5-7)
! c .
01 g
Technical Specification 3.11.2.1.a limits the dose rate to the total j
body from noble gases at any location at or beyond the site boundary to 500 arem/yr. By setting D equal to 500 mrem /yr and substitutir.g DFB for DFB g tb *
) in Equation 3-5, one may solve for Qg at the limiting whole body noble gas I
dose rate:
h= 1150 IO-I I ,
g DF8 i C vCi Im em-uti-m ) goCi-vr3 )
I set yr-pCi-set mrem-m i
Substituting this result for [_, h ing Equation 8-11 yields Rtb the response i
of the monitor at the limiting noble gas total body dose rate; R - 1150 S h DFB g IO~ I tb g C Dm-c m seC (cpm) (mrem uti-m ) I II DCi-Vr3 )
yr-pti-sec sci g ,3 mrem-m r
The skin dose rate due to noble gases is detervined with Equation 3-6:
b
- I3~0) skin 9 i Ob mrem) g(i) prem-sec) pCi-yr yr sec '
8-7 J
, , - .----n , . ,4.n~. , , , - . . , - - . , , , - - - - , , . , , . - - - - , - .,n , ,-- v- ~.- - ,, --w -
where:
bskin = Skin dose rate (mrem /yr) h, = The release rate of noble cas "1" in the mixture averaged by the time constant of the measuring system for each noble gas listed in Table 1.1-10 (yci/sec) 4
, i
= Combined skin dose factor (see Table 1.1-10) (mrem-sec/pci-yr) ,
DFj A composite combined skin dose f actor, DF', may be defined such that:
- r. r. (8-14 )
DF' 4._ Qg -L Og DFj i i gi ,
mrem-sec) pCi-yr uti) sec , sec) mrem-sec) pCi-yr Solving Equation 8-14 for DF' yields:
^
hj DFj DF' = (5-8)
Q3 i
Technical Specification 3.11.2.1.a limits the dose rate to the skin from noble gases at any location at or beyond the site boundary to 3,000 mrem /yr. ,
Bysettingb skin equalto3,000 mrem /yrandsubstitutingDF'forDFjin Equation 3-6 one may solve for Q3 at the limiting skin noble gas dose rate:
h = 3,000 (8-15) l 3 DF' i C (gi) (mremy sci-vr y sec yr mrem-sec Substituting this result for hgin Equation 8-11 yields Rskir,, the response of the monitor at the limiting I noble' gas skin dose rate:
8 -8 s'
I R
skin 3,000 5 9 h gp, (8-16) 3 com-cm uCi-vr (cpm) (aremII r pCi IIsec) 3 Imrem-sec) cm As with the liquid monitoring system, the gaseous monitori,ng system is also designed to incorporate the detector efficiency, 95 , into it's "
software. This results in an automatic readout in pC1/cm for the monitor
~
response. Therefore, Equations 8-13 and 8-16 become:
(5-5)
R b
= 1150 h DF8 g gyC_C.1) gerem-uti-m ) see) (DCi-vr 3y 3
cm.
yr-pCi-sec ,3 mrem-m
, R skin = 3000 fh (5-6) pg) mrem) sec) , DCi-vr )
c,3 ,yr ,3 ' mrem-sec l'
8-9
REFERENCES A. Regulatory Guide 1.109, " Calculation of Annual Doses to Man From Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I", U.S. Nuclear Reguldtory Commission, Revision 1, October 1977.
B. Hamawl, J. N., "AEOLUS - A Computer Code for Determining Hosrl,y and ~
Long-Term Atmospheric Dispersion of Power Plant Effluents and for Computing Statistical Distributions of Dose Intensity From Accidental
_ Releases", Yankee Atomic Electric Company, Technical Report, YAEC-1120, January 1977.
C. Regulatory Guide 1.111. " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases From Light-Water Cooled Reactors", U.S. Nuclear Regulatory Commission, March 1976.
D. National Bureau of Standards, ' Maximum Permissible Body Burdens and Maximum Permissible Concentrations of Radionuclides in Air and in Water for Occupational Exposure", Handbook 69, June 5, 1959.
E. Slade, D. H., " Meteorology and Atomic Energy - 1968", USAEC, July 1968, F. Seabrook Station Technical Specifications.
k a
i l
R-1 l
l 1
!