ML20090B041
| ML20090B041 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 07/08/1991 |
| From: | Leland W, Linville J, Moody D PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | |
| Shared Package | |
| ML20090B010 | List: |
| References | |
| PROC-910708, NUDOCS 9203030172 | |
| Download: ML20090B041 (134) | |
Text
RMD CONTROL COPY #
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- STATION *
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- 1. Does this manual / manual revisions
- a. Make changes in the facility as described in the FSARf Y" N"
- b. Mak changes in procedures as described in the
- c. Involve tests or experiments not described in !
the FSARf Ova Exo
- d. Involve changes to the existing Operating License or require additional license requirements? Ova -- Nuo :
- 2. If any of the above questions.are answered yes, a safety evaluation per i NHY Procedure 11210 is required.- t-PREPARED BY: .J T. LINVILLE, CHEMISTRY DEPARTMENT SUPERVISOR SUBMITTED BY N' L /
W. B. LELAND. CHEMISTRY AND HEALTH PHYSICS MANAGER DATE SORC REVIEV COMPLETED DURING MEETING NUMBER: 9l"fDb DATE: 1 i APPROVED BY E 1 i b!E , 91 E. ROODY 'TATION MANAGER DATE
. APPROVED BY: k '
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1.4. RIDGE ECUTIVE DIRECTOR -
RODUCTION
//DATE !
REVISION 8 -- EFFECTIVE: 07-15-91 DATE OF LAST PERIODIC REVIEV 2/5/91 DATE NEXT PERIODIC REVIEW DUE: 2/5/93 9203030172 920226 Sl]PERSEDED :
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p M LAj MTR ,0J__ RESPONSIBILITY. r this document was prepared by Yankee Atomic T.lectric Conpany (*Yarkee'). The '
use of information contained in this document by anyone other than Yankee, or the Organization for which the document was prepared under centract, is not .
- authorized and. with restect to any unauthorized use, neither Yankee nor its officers, directors, agents. or empicyees assume any obligation, responsibility, :
or liability or make any warranty er representation as to the accuracy or completeness of the material contained in this document.
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-The Station Offsite Dose Calculation Manual (ODCM) is divided .into two parts: (3) the in-plant Radiological Ef fluent Monitoring Program requirements j for liquid snd gas sanpling and analysis, along with the Radiological i Environmental Monitoring Program requirements (Part A): and (2) approved methods l to determine effluent monitor setpojnt values and estimates of doses and i radionuclide concentrations occurring beyond the boundaries of Seabrook Station l i
resulting from normal Station operation (Part B).
j The sampling and analysis programs in Part A provide the inputs for the models of Part B in order to calculate offsite doses and radionuclide '
concentrations necessary to determine compliance with the dose and concentration requirements of the Station Technical Specification 3/4.11. The Radiological
-Environmental Monitoring Program required by Technical Specification 3/4.12 and outlined within this manual provides the means to determine that measurable con
- centrations of radioactive nateriala released as a result of the operation of ;
Seabrook Station are not significantly higher than expected.
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j JAB E OF CONTENTS i
1 jlG1 CONTFNI l PART As RADIOLOGICAL EFFLUENT HONITORING PROGRAHL f A.1 '; ;
1.0 INTR 000CTION A.2-1 >
2.0 RESPONSI.BILITIES FOR PART A A.3-1 3.0 LIQUID EFFLUENT SAMPLIN0 AND ANALYSIS TR00 RAM 4.0 CASE 0VS EFFLUENT SAMPLINO AND ANALYSIS PROGRAM A.4-1 8 A.5-1 50 RADIOLOGICAL ENVIRONMENTAL MONITORING 5.1 SAMPLING AND ANALYSIS PROGRAM A.5 1 A,$-2 5.2 LAND USE CENSUS RADIOLOGICAL CALCULATIONAL MET 110DS AND PARAMETERS j PART B B.1-1
1.0 INTRODUCTION
1.2 RESPONSIBILITIES FOR PART B B.1 1
.1.2
SUMMARY
OF METHODS. DOSE FACTORS. LIMITS, CONSTANTS.
VARIABLES AND DEFINITIONS B.1 2 2.0 METHOD TO CALCULATE OFF. SITE LIQUID CONCENTRATIONS B.2 1 2.1 METHOD TO DETERMINE Fg EM AND C " B.2-1 ,
2.2 METHOD TO DETERMINE RADIONUCLIDE CONCENTRATION FOR EACH LIQUID EFFLUENT SOURCE B.2-2 2.2.1 Waste Test Tanks B.2 2 2.2.2 ' Turbine Building Sump B.2 3 2.2.3 Steam Generator Blowdown Flash Tank B.2-3 2.2.4 Primary Component Cooling Vater (PCCV) System B-2.4 3.0 0FF-SITE DOSE CALCULATION METHODS B.3-1 3.1 INTRODUCTORY CONCEPTS B.3-3 3.2 METHOD TO CALCVLATE TOTAL BODY DOSE FROM LIQUID RELEASES B.3-5
- 3.3 HETHOD TO CALCULATE MAXIMUM ORGAN DOSE FROM LIQUID RELEASES B.3-7
'3.4 METHOD TO CALCULATE THE TOTAL BODY DOSE RATE FROM NOBLE GASES B.3 9
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Page 1 ODCM Rev. 8 l.
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1 TABLE OF CONTENTS l Eb91 i UOldLT.
PA!!T B RADIOLOGICAL. CALCUIATIONAl. METil0DS AND PARAMETTRS 3.0. OPT + SITE DOSE CALCU!ATION HETil0D5 B.3-12 l 3.5 HETl10D TO CALCULATE THE $RIN DOSE RATE FRCH NOBLE CASES t
36 HETHOD TO CALCU! ATE THE CRITICAL ORGAN DOSE RATE FROM 10DINFS.
B.3 1$ {
TRITIUM AND PARTICULATES VITH T m OREATER THAN 8 DAYS B.3 18 3.7 METHOD TO CALCUIATE Tile CAMMA AIR DOSE FROM NOBLE GASES t B.3-20 3.8 METHOD TO CALCULATE T!!E BETA AIR DOSE FROM NOBLE CASES 3.9 HETHOD TO CALCULATE THE CRITICAL ORGAN DOSE FROM 10DIi1ES.
TRITIUM AND PARTICULATES B.3 22 B.3-24 3.10 METHOD TO CALCULATE DIRECT DOSE FROM PLANT OPERATION B.3 25 3.11 DOSE PROJECTIONS i B.4-I 4.0- RADIOLOG1 CAL ENVIRONMENTAL MONITORING PROGRAM 5.0 SETPOINT DETERMINATI0H5 B.5-I B.5-P :
5.1. LIQUID EFFLUENT INSTRUMENTATION SETPOINTS B.5-9 5.2 CASE 0US EFFLUENT INSTRUMENTATION SETPOINTS 6.0 LIQUID AND CASEOUS EFFLUENT STREAMS, RADIATION HONITORS AND RADWASTE TREATMENT SYSTEMS B.6 1 .
a B.7-1 7.0 BASES FOR DOSE CALCULATION HETHODS B.8 1 8.0 BASES FOR LIQUID AND GASEOUS HONITOR SETPOINTS R-1 REFERENCES APPENDIX As- DOSE CONVERSIL1 FACTORS A-I-f t
Page 2 ODCH Rev. 8
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MST OF FICtTRQ lilLE LU3 i LQi!.R !
i PART S B.4 1 ' Radiological Environmental Monitoring Locations kithin R
. 4-5 4 kilometers of Seabrook Station B.4-2 Radiological Environmental Monitoring Locations Between '
5.4-6 4 kilometers and 12 kilometers from Seabrook Station ,
B.4-3 Radiological Ervironmental Monitoring Locatiens outside 5.4-7 12 kilometers of Seabrock Statien
- B.4 4 Direct Radiation Monitoring Locations Vithin 4 kilometers B.4-8 of Seabrook Station _
B.4-5 Direct Radiation Monitoring Locations Between 4 kilometers '
B.4 9
- and--12 kilometers from Seabrook Station.
B.4 Direct Radiation Monitoring Locations outside 12 kilometers B.4+10 ,
of Seabrook Station J
B.6 1 Liquid Effluent Streams, Radiation Monitors, and Radvaste B.5-2 Treatment System at Seabrook Station B.6-2 Gaseous Effluent Streams, Radiation Monitors, and Radwaste Treatment System at Seabrook Station B.6 3 5
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LIST OF TABLIS fit' E
, ffMJi NLHP ER PART A Radioactive Liquid Vasto $smpling and Analysis Program A.3 2 A.3 1 Radioactive Gaseous Waste Sampling and Analysis Program A.4-2 A.4 1 A.5 3 A.5-1 Radiological Environmental Honitoring Program Detection Capabilities for Envitcnmental Sample Analysis A.5 7 A.5 2 A.5 3 Reporting Levels for Radioactivity concentration in A.$ 10 Environmental samples PART B 3.1 1 Summary of~ Radiological Effluent Technical Specifications 3.1-3 and Implementing Equations B.1 2 Summary of Method I Equations.to Calculate Unrestricted B.1-5 Area Liquid Concentrations B.1-3 Summary of Hethod 1 Equations to Calculate Off-Site Doses 3.1-7 from Liquid Releases -
B.1 8 B.1 4 Summary of Hethod I Equations to Calculate Dose Rates B.1-5 Summary of Method I Equations to Calculate Doses to Air B.1-9 from Noble Gases B.1-6 Su. mary of Method I Equations to Calculate Dose to an Individual from Tritium, iodine, and Particulates B.1 10 B.1-11
.B.1-7 Sur:r.ary of Hethods for Setpoint Determinations ,
L B.1 12- i u ry <f Variables.
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B .14 ' ,
B.1-15 ,
-B.1.) :riginition of Terms B.1-10 Dose Factors Specific for Seabrook-Station for Noble Gas 3.1 17 Releases B.1-11 Dose Factors Specific for'Seabrook Station for Liquid-B.1-15 Reletro Page 1 of 2 CDCM Rev. S
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LIST OF 7APLES fAEE EdiEl . TIT 1 E PART B (Centinued) !
B.1 12 Lose and Dose Rate Factorr Specific for Seabroak station l for Iodines. Tritium and Particulate Releases B.1 19 ,
t 8.1-13 Combined Skin Dose Factoro Specific for Seabrook Station Special Receptors for Noble Gas Release B.1-20
-t B.1-14 Dose and Dose Rate Factors Specific for Seabrook Station Special Receptors for Iodine. Tritium, and Particulate B.1 21 Releases B.1-15 Vent Stack Elevation to Ground level Release Point correction Factor B.1 22 Radiological Environmental Monitoring Stations B.4 2 B.4-1 Usage Factors for Various Liquid Pathways at Seabrook B.7-8 ;
B.7 1 Station ;
B.7 2 Environmental Parameters for Gaseous Effluents at Seabrook Station B.7-30 B.7-3 -Usage Factors for Various Gaseous Pathways at Seabrook Station B.7-32 Seabrook Station Dilution Factors Primary Vent Stack B.7-38 B74 t B.7-5 Seabrook_ Station Dilution Factors for Special (on-Site) ,
Receptors Primary Vent Stack B.7 39 ;
B.7-6 ,Seabrook Station' Atmospheric Diffusion and Deposition Factors Ground-Level Release Pathway B.7 40 t
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D.1 10 7 List of Figures 8 B.1-11 7 }
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- SEABROCK STATION 00CM PART 8 1
RADIOLOGICAL CALCULAT10NA1. METH005 AND PARAMETERS ,
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1.0 INTRODUCTION
' Part B of the 00CM (Off-Site Oose Calculation Manua'.) provides formal and approved methods for the calculation of off-site concentration, off-site doses and effluent monitor setpoints, and ladicates the locations of environmental monitoring sthtions in order to comply witn the Seabrook Station ;
Radiological Effluent Technical Specifications (RETS), Sections 3/4.3.3.9, 3/4.3.3.10, and 3/4.11, as well as the REMP detailed in Part A of the manual.
The 00CH forms the basis for station procedures which document the off-site doses due to station operation which are used to show compliance with the '
numerical guides for design objectives of Section II of Appendix I to 10CFR Part 50. The methods contained herein follow accepted NRC guidance, utiless otherwise noted in the text.
1.1 Responsibilities for Part B All changes to Part 8 of the 00CM shall be reviewed and approved by the Station Operations Review Committee (SORC) in accordance with Technical '
Specification 6.13 prior to implementation. Changes made to Part B shall be submitted to the Commission for their information in the Semiannual Radioactive Effluent Release Report for the period in which the change (s) was made effective, it shall-be the responsibility of the Station Manager to ensure that the 00CM is used in the performance of in-plant surveillance requirements and administrative controls of the appropriate portions of the Technical'
-Specifications and Effluent Control Program detailed in Part A of the manual. The Production Services Manager shall be responsible to ensure that the Radiological Environmental Monitoring Prc3 ram described in Section 4 of Part B is implemented in accordance with Technical Specification 3/4.12 and Part A of this manual.
4 6.1-1 oDCH Rev. 8 8683R-e,,r. -~----.<ewr.,,e..-,<-erw ,--m..- ,,,,n-- y.w,,--,,, w-,,y-r,,-*,w-yr.w,,--een, r ..-.%y e,-c--.- y-'+r'**'t=W'"Y *
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12 Summary of Methods. Dose factors, Limits, Constants, Variables and Definitions
~This section summarizes the Method I dose equations which are used as the primary means of demonstrating-compliance with RETS. The concentration and setpoint methods .are identified in Table 6.1-2 through Table B.1-7. Where more refined dose calculations are needed, the use of Method II dose determinations are described in. Sections 3.2 through 3.9 and 3.11. The dose
-factors used in the equations are in Tables B.1-10 through 8.1-14 and the ;
Regulatory Limits are summarized in Table B.1-1. e The variables and special definitions used in'this'00CM, Part 8, are in Tables B.1.8 and 8.1-9.
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' TABLE B.1-1 (Continuedi ,
i Summary of' Radiological: Effluent:Tect;*r ucifications and Implementing Equations .
. a I
(1)
Technical Specification Catenc y Method I Limit- t 3.3.3.10 Gaseous Effluent- :
i Monitor Setpoint '!
Plant Vent Alarn/ Trip Setpoint Eq. 5-9 T.S. 3.11.2.1 '
Wide Range Gas .for Tot.' Rody Dose (Total Body)
Monitors ' Rate Alarm / Trip.Setpoint Eq. 5-10 T.S. 3.11.2.1 i
'for Skin Dose Rate (Skin) :!
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-f (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 release point i parameters with annual average or concurrent' meteorology and identified pathways for a raal indivluual, shall lu2 niade.
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TABLE B'.1-2 Summary of Method I Equations to Calculate Unrestricted Area Llauid Concentrations Equation Catecery Ecuation Number 2-1 Total Fraction of MPC in Liquids, Except Noble Gases pENG ,
1
[{C p g MFCg -
2-2 Total Activity of Dissolved C NG- ,
and Entrained-Noble Gases C"1O($)* ml i
- from all Station Sources -
< 2 -M 1
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-B.1-6 ODCM Rev. 8
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TABLE B.1-8 (continued)
' Summary of Variables Definition Units Variab1_e
- Dose to the maximum organ mrem D
g S - Dose to skin frcm beta and gamma mrem D
. Dose to the total body mrem D
tb c DF - Dilution factor ratio DF - Minimum allcwable dilution factor ratio h min
- Composite skin dose factor mrem-set DF' pri-yr 3
mrem-m
- Total body gamma dose factor for nuclide "1" pCi-yr DFB' (Table B.1-10)
DFB - Composite total body dose factor c
DFl - S te-specific, total body dose factor for a trem itb liquid release of nuclide "i" (Table B.1-11) pC1
- Site-specific, maximum organ dose factor for a mrem DFl imo liquid release of nuclide "1" (Table 6.1-11) pct _
= Site-specific, critical organ dose factor for a mrem DFG jg gaseous release of nuclide "1" (Table B.1-12) pCi
- Site-specific, critical organ dose rate factor mrem-sec DFGjco pCi-yr for a gaseous release of nuclide "1" (Table B.1-12)
- '*~*3 DFS - Beta skin dose factor for nuclide "1" p -yr I
(Table B.1-10) 5C DF' - Combined skin dose factor for nuclide "1" *f!*~y'r p -
' (Table B.1-10) 3 mrad-m Y - Gamma air dose factor for nuclide "1" pCi-yr DF' (Table B.1-10)
B.1-13 B683R
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TABLE B.1-8 t.
(continued) -i Summary of Variables Definition Units
-Variable 3
mrad-m DF 0 - Beta air dose factor for nuclide "1" pCi-yr I
(Table B.1-10) mrem b - Critical organ dose rate due to tedines FT CO and particulates ,
b - Skin dose rate due to noble gases skin b - Total--body dose rate due to noble gases r tb D/Q Deposition factor for dry. deposition of 1 elemental radioiodines and-other particulates ,2
- Elevation release point (R) correction factor Dimensionless EL(RL
- Flow rate out of discharge tunnel gpm or
-F d
f t 3/sec
- Flow rate past liquid waste test tank monitor gpm F,
- Flow rate past plant vent monitor cc F
seC Dimensionless f;f j I3 iI 4 - Fraction of total MFC associated with 2 Paths 1, 2, 3, and 4
- Total fraction of MPC in 11guld pathways Dimensionless F
(excluding noble gases)
- Maximum permissible-concentration for gCi
-MPC g cc
' radionuclide "1" (10CFR20, Appendix:6, Table 2, Column 2).
~
curies, or
- Release to the environment for Qg pcuries radionuclids."1" pC1/ set h-3 - Release rat'e to the' environment for radionuclide "1" 8.1-14
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oDCM Rev. 8 8683R
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TABLE B.1-14 Dose and Dase Rate factors Specific-for Seabrook Station Scecial Receptorstit for Iodine,
' Tritium, and Particulate Releases Education Center _
The " Rocks" Critical Organ Critical Organ Critical Organ Critical Organ Dose factor Dose Rate-factor Dose factor Dose Rate factor DFG DFG,, egg (mrem-sec) Ofugegg(mrem) C7- DFG,coR(mrem-sec' i pCi-yr Radionuclide lcoE(mrem) uCl C1-yr 2.03E-03 6.85E-10 2.16E-02 H-3 6.45E-11 2.12E-01 2.68E-08 1.07E+00e Cr-51 4.98E-09 6.24E+01 5.84E-06 2.55E+02 Mn-54 1.39E-06 1.29E+01 1.74E-06 6.78E+01-Fe-59 3.09E-07 3.89E-07 1.72E+01 2.01E-06 8 llE+01 Co-58 3.97E+03 Co-60 2.17E-05 9.78E+02 8.83E-05 3.31E401 3.23E-06 1.37E+02 Zn-65 7.34E-07 3.63E+00 1.23E-06 3.88E+01-Sr-89 11.15E 1.62E+02 5.48E-05 1.73E+03 Sr-90 5.14E-06 1.35E+01 2.22E-06 8.14E+01 Zr-95 3.38E-07 6.43E+00- 8.59E-07 3.37E+01 Nb-95 1.53E-07 5.58E-01 1.50E-07 4.92E+00 Mo-99 1.62E-08 5.33E+00 7.74E-07 2.95E+01 Ru-103 1.30E-07 1.55E+02 1.54E 6.47E+02 Ag-110m 3.43E-06 2.89E+01 4.04E-06 1.56E+02 Sb-124 6.96E-07 2.47E+01 8.27E-06 2.61E+02-I-131 7.79E-07 5.83E+00 1.95E-06 6.18E+01 I-133 1.84E-07 3.08E+02 2.78E-05 1.25E+03 Cs-134 6.83E-06 4.64E+02 4.19E-07 1.89E+03 Cs-137 1.03E-05 3.85E+00 1.10E-06 3.56E+01 Sa-140 1.14E-07 1.45E+00 3.59E-07 1.20E+01 Ce-141- -4.09E-08 2.25E+02-6.95E-07 2.27E+01 7.02E-06 Ce-144 -4.16E+02 Other' 2.26E-06 1.02E+02 9.56E-06 ,
- Dose factors to be used in Method-I calculations for any "other" detected gamma emitting radionuclide which is not included in the above list.
l (l) See Seabrcok Station Unit I l Technical Specification-Figure 5.1-1.
6.1-21
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ODCM Rev. 7 8683R i
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TABLE B.1-15 Vent Stack Elevation to Ground level
~ Release Point Correction factortU-
Correction factor (2)
Release Type EL(GRD)
Receotor Point (R) 12,1
- 1. Maximum Off-Site a. Noble Gases Receptor
- 2. 'The " Rocks" a. Noble Gases 9.4
- b. Iodine, Trituim, 9.4 and Particulates The " Education a. Noble Gases 14.3
- 3. '
Center"
(1) The' sum of doses from both plant vent stack (EL(R) - 1,0) and ground level release (EL(R) " values from Table B.1-15") must be considered for determination of Technical Specification compliance.
(2) . See Section 7.2.6 for a description of how the EL(GRD) were derived.
~
B.1-22
- ODCM Rev. 8 8683R L
l 2.0 METh00 TO CALCULATE OFF-SITE LIQUID CONCENTRATIONS I
Chapter 2 contains the basis for station procedures used to demonstrate compliance with Technical Specification 3.11.1.1, which limits the total fraction of MPC in liquid pathways, other than ncble gases (denoted here as Ff0) at the point of discharge from the statien to the environment (see ENG is limited to less than or equal to one, i.e.,
Figure B.6-1). F FENG < ), -
1 The total concentration of all dissolved and entrained noble gases at the point of discharge frcm the multiport diffuser frcm all station sources combined, denoted Cf is limited to 2E-04 pCi/ml, i.e.,
Cf<2E-04pC)/ml.
0 2.1 Method to Determine F andCf First, determine the total fraction of HPC (excluding noble gases), at the point of discharge from the station from all significant liquid sources denotedFfG;andthenseparatelydeterminethetotalconcentrationat the point of discharge of all dissolved and entrained noble gases from all station sources, denoted Cf as follows:
(2-1)
F ENG , [ [~ MPCpl < 1' 1
"p i i -
(pCl/ml) pCl/ml and:
B.2-1 ODCM Rev. 8 8683R
- . . . - . - - - - . - . . - . - _ . ~ . - - . - _ . . - _ . . - . . - . . -
(2-2)
-Cf
. C 's 2E-04 (pC1/ml) (pCl/ml) -(pCl/mi) where:
= Total fraction of MPC in liquids, excluding noble Ff gases, at the point of discharge from the multiport diffuser j
i Cj - Concentration at point of discharge from the multiport )
p diffuser of radionuclide "1", except for dissolved and J entrained noble gases, from all tanks and other significant l sources, p,.from which a discharge may be made (including the' l waste test tanks and any other significant source from which a discharge can be made). Ct p is determined by dividing the product _of the measured radionuclide concentration in 11guld waste test tanks, PCCW, steam generator blowdown, or other effluent streams times their discharge flow rate by the total available dilution water flow rate of circulating and 7 service water at the time of release (pC1/ml).
HPC)
= Maximum permissible concentration of radionuclide "1" except for dissolved and entrained noble gases from 10CFR20, Appendix B Table II, Column 2 (pC1/ml)
- Total concentration at point of' discharge of all dissolved Cf and entrained noble gases in liquids from all station sources (pC1/ml)
- Concentration at point of discharge of dissolved and entrained Ch noble gas "1" in liquids from all station sources (pCl/ml) 2.2. Method to Oetermine Radionuclide Concentration for Each Liquid Effluent' Source 2.2.1 Waste Test Tanks-C is determined for each radionuclide detected frcm the activity in pg a representative grab sample of any of the waste test tanks and the predicted flow at the point of discharge.
The batch releases are normally made from two 25,000-gallon capacity waste test tanks. These tanks normally hold liquid waste evaporator B.2-2 ODCM Rev. 8
-8683R
~-.._ ~ ~ _ ___
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 from the boron recovery evaporator when the BRS evaporator is substituting for the waste evaporator, and distillate frcm the Steam Generator Blowdown System evaporators and flash steam condensers when that system must discharge Itquid off-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 discharge, each waste' test tank is analyzed for principal gamma emitters in accordance with the' liquid sample and analysis program outlined in Part A to the 00CM.
2.2.2 Turbine Building Sumo The Turbine Building sump collects leakage from the Turbine Su11 ding floor drains and discharges the liquid unprocessed to the circulating water system.
Sampling of this potential source is normally done once per week for determining the radioactivity released to the environment (see Table A.3-1). ,
I 2.2.3 - Steam Generator Blowdown Flash Tank The steam generator blowdown evaporators normally process the 11guld
.from the steam generator blo down flash tank when there is primary to secondary leakage. Distillate from the evaporators can be sent to the waste test tanks or recycled to the condensate system. When there is no primary to secondary leakage, flash tank liquid is processed through the steam generator blowdown demineralizers and returned to the secondary side.
B.2-3 ODCM Rev. 7 8683R-o g ,3 -
f Steam generator blowdown is only subject to sampilng and analysi's when all'or-part of the blowdown'llquid is being discharged to the environment '
Iinstead of.the normal recycling process (see Table A.3-1).
J2.2.4 PrlmaryComponentCoolingWater(PCCW) System The PCCH System is used to cool selected pri_ mary components.
The system is normally sampled weekly to determine if there is any radwaste in leakage. If leakage has been determined, the Service Water System is sampled to determine if any release to the environment has occurred.
S l _.
L i
1 :-
\l l
l-B.2-4
~
8683R- ODCM -Rev. 8 i
i i
...m ... - . . , _ . . . _ . . _ .________ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _
_-._m .._ _ _ _ _ _ _ .-._ _ _ ._ .___ _ .__ _.___._ _.___.
~ 3.0 OFF-SITE DOSE CALCULATION METH005 Chapter 3-provides the basis for station procedures required _to meet-the Radiological Effluent Technical Specifications (RETS) dose and dose rate requirements contained in Section 3/4.11 of the station cperating Technical Specifications. A simple, conservative method (called Method I) is listed in Tables B.1-2 to B.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_refercnce material with which the operator can calculate the needed
. doses, dose rates ant' setpoints. The bases for the dose and dose rate equations are given in Chapter 7.0.
The Semiannual _ Radioactive Eff'luent Release Report, to be filed af ter January 1 each year per Technical Specification 6.8.1.4, requires that meteoro l ogi cal conditions concurrent with the time of release of radioactive materials in gaseous effluents, as determined by sarpilng frequency and measurement, be used for determining the gaseous pathway doses. For continuous 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 Jr identifiable operational activities (i.e., containment purge or venting to atmosphere of the Waste Ga, l
l- 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 five percent of the total quarterly radioactivity released from the unit; otherwise quarterly average metecrology will be applied.
Quarterly average meteorology wil.;also 1 be applied to batch releases if.the-hourly met data for the pericd of batch release is unavailable.
Dose assessment reports prepared in accordance with the requirements of
-the ODCM will include-a statement indicating that the appropriate portions of:
, Regulatory Guide 1.109 (as identified in the individual subsections-of the
~
6.3-1 ODCM Rev. 8 8654R ,
00CM for each class of effluent exposure) have been used to determino dose
?
Impact from station releases. Any deviation from the methodology,
-- -assumptions, or parame t ers~ gi ven in Regulatory Guide 1.i.s, and not-already identified inlthe bases of the 00CM, will be explicitly described in the effluent report, along with'the' bases for the deviation. --
?
A 9
.t I
1 B.3-2 ODCM Rev. 8 8684R~ _
. -- . . - - - . . - . - . - . - . ~ - -. .. - . . ~. - - _-. - - . _ ~ .~ - .
i 3.1 Introductory Concepts-
-In_ part, the Radiological Effluent Technical Specifications (RETS) limit dose or dose rate. The term " dose" for ingested or Inhaled
- radioactivity means the dose commitment, measured in mrem, which results from ,
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 radioa.ctivity is stopped. The time frame over which the dose commitment is evaluated is 50 years. The phrases " annual dose" or dose in one year" then refers to the 50-year dose commitment resulting frcm i exposure to one year's worth of releases. " Dose in a quarter" similarly means the 50-year dose commitment resulting trem exposure to one quarter's releases. The term " dose," with respect to external exposures, such as to noble gas-cicuds, refers only to-the doses received during the actual time ,
period of exposure to the radioactivit'y released from the plant. Once the scurce 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 from plant ga_secus effluents and receives a 50-year dose commitment 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 miem.
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
- 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
. assuranc, that members of the public, either inside or outside the site L boundary, will not be exposed to annual averaged concentrations exceeding the-limits specified in Appendix B, Table II of 10CFR, Part 20 (10CFR20.106(a)). _
- B.3-3 8684R oDCM Rev. 8 f- "- +- g.v--*-e-te-+-- r, w. 3._-., ..a .,_,__r, y g ._
I ThequantitlesADandbareintroducedto-providecalculable ,
quantitles, related to off-site doses or dose rates that demonstrate compliance with'the RETS.
Delta D. denoted AD, is the quantity calculated by the Chapter 3, .
' Method I-dose equations. It represents the conservative increment in dose.
The 40 calculated by Method I equations is not necessarily 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 generally 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. ,
Ddot-denotedb,isthequantitycalculatedintheChapter3doserate equations, It is calculated using the station's effluent monitoring system reading and an annual or long-term average atmospheric dispersion factor, b
- predicts the maximum off-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 provides assurance that
-10CFR20.106 limits will be1 met.
Each of the methods to calculate dose or dose rate are presented in
-separate-subsections of_ Chapter 3, and are summarized in Tables B.1-1 to
- B 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 i
simplest; generally aillnear equation. Method II_is a more detailed analysis which allows'use of site-specific factors and variable parameters to be-selected to-best fit -the actual release. Guidance is provided, but the a ppropriate margin and depth of analysis are determined in each instance at -
).
the time of analysis under Method II, t -
B.3-4
- ODCM Rev. B r^ - -
3.2' Method to Calculate-the Total Body-Dose from Liquid Releases ,
Technical Specification 3.11.1.2 limits the total-bod'y dose commitment
~
to a member of the public from radioactive material in liquid effluents to 1.5 mrem per quarter and 3: mrem per year per unit. Technical-Specification 3.11.1.3 requires liquid radwaste treatment when the total body dose estimate exceeds 0.06 mrem in any 31-day period, Technical Specification 3.11.4 limits the. total body dose ccmmitment 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.
To evaluate-the total body dose, use Equation 3.1 to estimate the dose from the planned release and add this to the total body dose accumulated frcm prior releases during the month. See Section 7.1.I for basis. .
3.2.1 Hethod I
. The increment in total body dose frem a liquid release is:
~
.D "
01 Dhitb-tb i (mrem)
=()(Cl)(]')
where:
- DFLitb: - Site-specific total body dose factor (mrem /pCl) for a liquid release. It is the highest of the four age groups.
See Table B.1-11.
B.3-5 oDCM Rev. 8 8684R _
i l
j
_. _ _ _ _ _ _ _ . _ __ _ . ~ . _ _ _ . _ . . _ . _ _ . _ _ . _ . _ _ _
Qi
- Total activity (pCl) released for radionuclide "1". (For strontiums, use the most recent measurement available.)
K _. 918/Fd ; where Fd is the average (typically monthly-average) dilutic flow of the Circulating' Hater System at the-point of distnarge frcm the multiport-diffuser (in 3 For normal operations with a. cooling water flow ft /sec).3 of 918 f t /sec, K is equal to 1.
Equation 3-1 can be applied under the following conditions (otherwise, justify Method I or consider Method II):
l
- 1. Liquid releases via the multipor't diffuser to unrestricted areas (at the-edge of the initial mixing or prompt dilution zone that corresponds to a factor of 10 dilution), and ,
2, Any continuous or batch release over any time period.
3.2.2- Method II .
Method'II consists of the models, input data and assumptions
-(bicaccumulation factors, shore-width factor, dose conversion factors, and transport and. buildup times) in Regulatory Guide 1.109, Rev. 1 (Reference A),
except'where site-specific data or assumptions have been identified in the ODCM. The general equations (A-3 and A-7) taken from Regulatory Guide-1.109, '
and used in the derivation of the simplified Method _I approach as described in
~
the Bases section, are also applied to Method II assessments, except that doses calculated to the whole body from radioactive effluents are evaluated for_ each of the four age groups to determine the-maximum whole body dose of an age-dependent indivi_ dual via all existing exposure pathways. Table 8.7-1 lists the usage factors of Method II-calculations. As noted in Section B.7.1, the mixing ratio associated with'the edge of the 1 F surface isotherm above the multiport diffuser may be used in Method II calculations.
~
B.3-6 oDCM Rev 8 8684R _
_-_._.-.___._____...-.__._.________7 I
l 3.3 Method to Calculate Maximum Organ Dose from liquid Releases- ,
Technical Specification 3.11.1.2 limits the maximum organ dose commitment to a Member of the Public from radioactive material in liquid effluents to ", mrem per quarter and 10 mrem per year per unit. Technical Specification 3.11.1.3 requires liquid radwa:te treatment when the maximum organ dose projected exceeds 0.2 mrem in any 31 days (see Subsection 3.11_for dose projections). Technical Specification 3.11.4 limits the maximum organ dose commitment to any real member of the public from all station sources
-(including 11gulds) to 25 mrem in a year except for the thyroid, which is ,
limited to 75 mrem in a year.
Use Method I first to calculate the maximum organ dose frcm a 11guld release to unrestricted areas (see figure 8.6-1) 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.
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 relelse is:
O =k DFL gg (3-2) mo Qj 1
(mrem) = ( ) (pCl)-( *)
L where:
DFLjmo- . Site-specific maximum organ dose factor (mrem /pci) for a liquid release. -It is the highest of.the four age groups.
See Table B.1-ll.
- Total activity (pCl) released for radlonuclide "i". (For 01 strontiums, use the most recent measurement available.)
~
S.3-7 l oDCM Rev. 8
-8684R- ,
-. ._. - _ _ - - ~ _ _ _ . _ . _. - _ __ .__ _ __
. -- , . .- -. - .., - - - - - . - .. - - - . - . ..~ .... .-.. - .. _
-K~ = 918/Fd ;_where-Fd is the average (typically monthly.
average) dilution flow of the Circulating Water System at-thg point of discharge frcm the multiport diffuser (in ftJ/sec). 'For normal operations with a cooling water flow _
of 918 ft 3/sec, K is equal to 1.
Equation'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 that corresponds to a factor of 10 dilution), and
-2. Any continuous or batch release'over any time period.
3.3.2 Method II -
Method II consists of the models, input data and assumptions (bloaccumulation factors,. shore-width factor, dose conversion factors, and g
transpo, and buildup times) in Regulatory Guide 1.109, Rey, 1 (Reference A),
except where site-specific data or assumptions have'been identified in the 00CM. The general equations (A-3 and A-7) taken from Regulatory Guide 1.109, and 'used-in the derivation of the_ simplified. Method I approach as described in sthe. Bases section, are also applied to Method II assessments, except that
. doses-calculated to critical organs from radioactive effluents'are evaluated for each of the fourLage groups to determine the maximum critical organ cf an age-dependent individual via-all existing _ exposure pathways. Table B.7-1
-11sts the-usage. factors for Method-II calculations. As noted in Section 0
- B.7.1, the mixing ratio associated with the edge of the
- 1 F surface isotherm above the_multiport diffuser may be used in Method II calculations.
~
B.3-8 oDCM Rev. 8 8684R _
-- _ . - - - ~ .-
_ 3.4 Method to Calculate the Total Body Dose Rate from Noble Gases Technical 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 b 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 W . -Method I applies at all release release rate via the station vents rates.
Use Method II if a more refine'd calculation of O tb is desired by the station (i.e., use of actual release point parameters with annual of actual meteorology to obtain 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 interv'a1. See Section 7.2.1 for basis.
Compliance with the dose rate limits for noble gases are continuously demonstrated when effluent release rates are below the plant vent noble gas activity l monitor alarm setpoint by virtue of the' fact that the alarm setpoint _
is based on a value which corresponds- to the off-site dose rate limit, or a value below it. Determinations-of dose rate for compliance with Technical Specifications are performed when the effluent monitor alarm setpoint is exceeded, or as required by the Action Statement (Technical Specification 3.3.3.10, Table 3.3-10) when the monitor is inoperable. .
p The primary vent stack-mix mode release X/Qs are assumed in the 00CM
~
L (I)
Method I equations when-the correction factor for release point elevation, EL(R), is set-at 1.0.
8684R cDCM Rev. 8 19- a. ~-r e. - y w,+r,.- y , . . , _ -w-,.,-
&-m 4 , , . - , , . _ , , , .y- ,.,-, ,m, , ,,ur,,_w,y n,+--..,3- ,--,.-,,---v y. --.a , w---w e,
3.4,1- Method I The. Total-. Body Dose Rate due~to noble gases'can be determined as follows:
b = 0.85
- EL(R)
- hg DFB g (3-3) tb 1 3
C y_CI Imrem' " DCi-set mrem-m Ci-yr )
yr Cl-m 3 sec where: ,
EL(R) - Elevation Release Point (R) correction factor (dimensionless). For primary vent stack releases, EL(STACX) equals 1.0.. For ground level releases, EL(GRD) equals 12.1 for the maximum off-s'ite receptor, as shown on Table 8.1-15.
hg - The release rate at the station vents (uC1/sec), for each noble gas radionuclide, "1", shown !n Table B.1-10.
DFB,
= Total body gamma dose factor (see Table B.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 Method II consists of the model and input _ data (whole body dose factors) in: Regulatory Guide 1.109, Rev.1 (Reference A), except where site-specific data or assumptions have been identified.in the ODCH. The general equation-(B-8) taken from Regulatory Guide 1.109, and used in the derivation of the simpilfled Method I approach as described in-the Bases section, is also applied to a Method II assessment. No credit for-a shleiding
~
B.3-10 ODCM Rev. 8 8684R- _
_ - . . _ _ ._ . . < . _ . _ . _ . _ . _ . _ ~ . _ _ _ . _ __ _ _ _ ,. _. _ _ . _ .. _ ._ . _ _ ._ _ . _
Concurrent factor (Sp) associated with residential structures is assumed.
-; meteorology with the release period may be. utilized for the gamma atmospheric dispersion- factor:1dentified in 00CM Equaticn 7-3 (Section 7.2.1), and ,
-determined 'as indicated in Section 7.3.2 for the release point (either ground level or vent-stack)-from which recorded effluents have been discharged.
4
~
B.3-11 ODCM- Rev. 8 8684R _
- =, ~, :, . _ . _ . _ . - , _ , __ . ___,_ . . _ . . . _ _
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 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 Oskin 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 r te via the station vents 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 release point parameters with annual or actual meteorology'to obtain release-specific X/Osi 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.
Ccmpliance with the dose rate limits for noble gases are continuously demonstrated when effluent release rates are below the plant vent noble gas activity monitor alarm setpoint by-virtue of the fact that the alarm setpoint is~ based on a value which corresponds to the off-site dose rate limit, or a value below it. _ Determinations of dose rate for compliance with Technical
' Specification's are per_ formed when the effluent monitor _ alarm setpoint is exceeded.
(l) The primary vent' stack mix mode release X/Qs are assumed in the
-ODCM Method I equations when the correction factor for release point evaluation, EL(R), is set equal to 1.0.
8.3-12 ODCM- Rev. 8 8684R
-~_.-,- . - _ , , , .__ ,-_.--._.-_m-,, m., , , . - , . . _ . , - - , - , - ---. c--~ ,
F i
3.5.1 Method I The Skin Dose Rate due to noble gases is:
(3-4)
O skin EL(R)L* T Q j DFj zmrem) ,-( ) (pg) (mrem-sec) yr- sec .pCi-yr where; EL(R) = Elevation Release Point (R) correction factor (dimensionless).
For primary vent stack releases, EL(STACK) equals 1.0. For ground level relt.ases, EL(GRD) equals 12.1 for the maximum off-site receptor, as-shown on Table 8.1-15.
Q, - The release rate at the static.n vents (pCi/sec) for each radionuclide, "1", shown ir, Table B.1-10.
DFj . combined skin dose factor (see Table B.1-10).
Equation _3-4 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 iny station vent to the atmosphere.
. 3.5.2 Method'II
- Hethod -II consists-of the medel and input data (skin dose factors) in Regulatory Guide _1.109, Rev.1 (Reference A), except where site-specific data or assumptions-have been identified in the 00CM. The-general equation (B-9) taken from Regulatory Guide 1.109, and used in the-derivation of the j
_ simplified Method I approach as described in the Bases section, is also applied to a Method II assessment, no credit for a shielding factor (SF }
L I
B.3-13 ODcM Rev. 8 8684R _
i,
associated with residential structures is assumed; Concurrent meteorology with the release period may be utilized for~tha gamma atmospheric dispersion i factor and 'undepleted atmosptiric dispersion factor-identified in 00CM Equation 7-8_(Section 7.2.2), and determined as indicted in Sections 7.3.2 and-7,3.3 for the release point (either ground level or vent stack) from which recorded eff.luents have been discharged.
4 4
L i
l
\
1
~
B 3-14 ODCM Rev. 8 8684R _ _
w -w w- --+e--9f =rw m-F e e sm469 w w 'y fFm-er tw-*w-yo-Mw-e p-hw-T4- g meWT w -& y-e4gwm.=swri-+%p7Tw.y y ry--yws- r-d'*v a y 'w g- -w-ygq 'T-'g-T- ' ' - - P f
u_ _ _ _ _ _ . _ _ _ _ . _ _ _ _ . _ _ . _ . _ _ - . . - . _ _ . _ . _ _ _ . _ _ _ . _ _ _ . .
3.6 Method to Calculate the Critical Organ Dose Rate from Iodines, Tritium and l Particulates with Tl/2 Greater.Than 8 Days-
- Technical Specificatt'on 3.11.2.1 limits the dose rate at any time to ,
any organ from I3I I, 1337, 3H and-radionuclides in particulate form with half lives greater than 8 days to 1500 mrem /." ear to any organ. The Technical Specification indirectly limits peak release rates by limiting the dose rate-that is predicted from continuud release at the peak rate. Bylimitingb eg 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 ,
public is less than 1500 mrem.
Use Method I first to calculate the Critical Organ Dose Rate from the W Method I applies at all release peak-release rate via the station vents .
rates.
is desired by the Use Method II if a more refined calculation of O cg station (i.e., use of actual release point parameters with annual or actual meteorology to obtain release-specific X/Qs) or l'f 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 7.2.3 for basis. .
3.6.1- Method I The Critical Organ Dose Rate can be determined as folicws:
= MRF
- hg DN gg, M I beg_
i (pC1) (mrem-sec)
(mremyr g (). sec pCi-yr I
!- (I) The primary vent stack mix mode release X/Qs are assumed in the 00CM Method-I equations when the correction factor for release point elevation, EL(R), is set equal to 1.0.
B.3-15 ODc.M Rev. 8 8684R -
i
- l. l l
l- ~ ~ - . . , - . - - _ _ _ _ _ _ _ _ _
where:
El.(R) - Elevation Release Point (R) correction factor (dimensionless). ^
-for primary vent stack releases, EL(STACK) equals 1.0. For ground level releases, EL(GRD) equals 12.5 for the maximum off-site receptor, as shown on Tabic B.I.15.
DFGje,-Site-specificcriticalorgandoseratefactor< mrem-sec) pCi-yr for a gaseous release. See Table B.1-12.
h, = The activity release rate at the station vents of ,
-radionuclide "1" in pC1/ set (i.e., total activity measured of radionuclide "1" averaged over the time period for which the filter / charcoal sample collector was in the effluent stream). For 1 - Sr89 or Sr90, use the best estimates (such as most recent measurements).
-Equatio'n 3-5 can be-applied under the following conditions (otherwise, ju tify Method I'or consider-Method II):
- 1. Normal-operations (not emergency event), and
- 2. Tritium, 1-131 and particulate releases via monitored station vents to the atmosphere.
'3.6.2 Hethod:II:
Method II consists of the models, input data and assumptions in Appendix C of. Regulatory Guide 1.109, Rev. 1 (Reference A), except where site-specific data or' assumptions have been identified in the 00CM (see
- Tables B.7-2_and B.7-3). The critical organ dose rate will be determined
[
based on the location (site boundary, nearest resident, or farm) of receptor by
_-pathways'.as--Identified-in the most recent annual land use census, or conservatively assuming the existence of all pathways (ground plane, '
inhalation, ingestion of stored and leafy vegetables, milk, and meat) at an off-site: location of maximum potential dose. Concurrent meteorology with the release period may be utilized for determination of atmospheric dispersion
- factors in accordance with Sectichs 7.3.2 and 7.3.3 for the release point B.3-16 ODcM Rey, a l _8684R _
r .
_ _o l
, . .. - ... -. _ - . . ~ . .- . ..
(etther ground level or-vent-stack) from which recorded effluents have been discharged. The maximum critical organ dose rates will consider the four age-groups independently, and take no credit for a shielding factor (Sp)
. associated.with residential structures.
e Y
l l
ll lL i B.3-17 -l ODCM Rev. 8 8684R- -
l L
i j
3.7 Method to Calculate the Gamma Air Dose from Noble Gases '
1 Technical Specification 3.11.2.2 limits the gamma dose to air from ;
r noble gases at any location at c. beyond the site boundary to 5 mrad in any quarter and 10 mrad in any y*ar per unit. Dose evaluation is required at f least once per 31 days.
Use Method I first to calculate the gamma air dose for the statten f UI releases during the period. ;
vent I
Use Method 11 if a nere refined calculation is needed (i.e., use ef j actual release point p(reeter with annual or actual meteorology to obtain release-specific X/Qs), er if Method I predicts a dose greater than the Technical Specification limit to determine-If it had actually been exceeded.
See Section 7.2.4 for basis. ,
3.7.1 Method 1 The gamma air dose from station vent releases is:
l (3-6) 0,Jr - 2.7E-08
- EL(R)
- Og DF{
1 3
(mrad) (pci- )( ) ( Cl) (mrad-m ) -
pCl-m pCl-yr where:
i Og
- total activity (pC1) released to the atmosphere via station.
vents of each radionuclide "1" during the period of interest.
- gamma' dose factor to air for radionuclide "1". See Table B.1-10 Of}
EL(R) Elevation. Release Point (R) correction factor (dimensionless),
for primary vent stack releases, EL(STACK) equals 1.0. For ground level releases, EL(GRE equals 12.1 for-the maximum
-off-site receptor, as shown'on Table B.1-15.
(I) The primary vent stack mix mode release X/Q: are assumed in the
-0DCM Method I equations when the correction factor for release point elevation, EL(R). 15 set equal to 1.0.
a B.3-18 oDCM Rev. 8 ;
B684P.
Equation 3-6 can be applied under the following conditions (otherwise justify Method I cr consider Methcd 11):
- 1. Normal operations (nonemergency event), and
- 2. Noble gas releases via staticn vents to the atmosphere.
3.7.2 Methed 11 Method 11 consists of the models, input data (dose factors) and assumptions in Regulatory Guide 1.109, Rev. 1 (Reference A), except where ,
site-specific data or bstumpt'ons have been identified in the 00CM. The general equations (B-4 and B-5) taken frcm Regulatory Guide 1.109, and used in the derivation of the simplified Method I approach as described in the Bases Section 7.2.4 are also applied to Method 11 assessments. Concurrent meteorology with the release period may be utilized for the gamma atmospheric dispers'.on factor identified in 00CM Equation 7-14, and determined as indicated in Section 7.3.2 for the release point (either gr.und level or vent stack) from which recorded effluents have been discharged.
S.3-19 oDcM Rev. 8 8684R _
l l
3.8 Method to Calcultite the Beta Air Oose from Noble Gases Technical Specification 3.11.2.2 limits the beta dose to air from noble [
l gases at any location at or beyond the $lte boundary to 10 mrad in any quarter and 20 mrad in any year per unit. Oose evaluation is required at least once ,
i per 31 days. !
Use Method I first to calculate the beta air dose for the station vent stack releases during the period. Method I applies at all dose levels. <
i i
Use Method II if a more refined calculation is needed (i.e., use of actual release point parameters with annual or actual meteorology to obtain i
release-specific X/Qs) or if Method I predicts a dose greater than the Technical Specification limit to deter'mine if it had actually been exceeded.
See Section 7.2.5 for basis.
3.8.l .Hethod I The beta air dose from station vent releases is:
0 DF 0 (3-7)
D . 2.6E-08
- EL(R)
- Qg alr (mrad) --(cci- ) (- ) ( C1) (* *)
- y. ,
pCl-m l.
d ere:
"1" (see Table B.1-10).
DFf Beta dose factor to air for radionuclide Oi
- Total activity (pci) released to the atmosphere via station E
vents of each radionuclide "i" during the period of interest.
_ l (I) Tne primary vent stack mix mode release X/Qs are assumed in the 00CM Method-I equations when the corrective factor for release point elevation, EL(R). is set equal to 1.0.
' 6.3-20 oDCM Rev. B 8684R i
- . - . , . . _ . _ _ _ . ~ . , . _ . _ . . . . _ . . . , , . , _ . . . _ _ _ _ _ . _ . . . , _ . _ . , ~ _ - _ , _ _ . . - , ; ., m ,. _., . . , _ . . _ . - , _ , . , , .
l EL(R) Elevatten Release Point (R) correction factor (dimensionless).
for primary vent stack releases. EL(STACK) equals 1,0. For
-ground level releases, EL(GRD) equals 12.1 for the maximum off-site receptor, as shown on Table B.1-15.
Equation 3-7 can be applied under the following conditions (otherwise justify Hethod I or consider Method II):
l
- 1. Normal operations (nonemergency event), and
- 2. Noble gas releases via station vents to the atmosphere.
3.8.2. Method II Method 11 consists of the models, input data (dose-factors) and assumptions in Regulatory Guide 1.109, Rev. 1 (Reference A), except where site-specific data or assumptions have beer, identif'ed in the 00CM. The general equations (B-4 and B-5) taken from Regulatory Guide 1.109, and used in the derivation of the simplified Method I approach as described in the Bases Section 7.2.5, are abo applied to Method II assessments. C.ncurrent meteorology with the >;1 ease period may be utilired foJ the. atmospheric dispersion factor identified in 00CM Equation 7-15, and determined, as l
Indicated in Sections 7.3.2 and 7.3.3 for the release point (either grour.1 level or vent stack) from which recorded effluents have been discharged.
B.3-21 ODcM Rev. 8 8684R _
1
_ . , _ _ . - ,---.,-..,..-.__...,,_.__.....-.;_._-._.,_.._;_.___._.__.-___._.._-._._m_.. ; ..--__,._-._.__a
l 3.9 Method to Calculate the__ Critical Organ Oose from__ Iodines. Tritium and j Particulates Technical Specification 3.11.2.3 limits the critical organ dose to a member of the public from radioactive lodines, tritium, and particulates with half-lives greater than 8 days in gaseous effluents to 7.5 mrem per quarter and 15 mrem per year per unit. Technical Specification 3.11.4 limits the total body and organ dose to any real member of the pubile from all station sources (including gaseous effluents) to 25 mrem in a year except for the thyroid, which is limited to 75 mrem in a year. ,
Use Method I first to calculate the critical organ dose from a vent release as it is simpler to execute and more conservative than Method II.
Use Method II if a more refined calculation of critical organ dose is needed (i.e., Method I indicates the dose is greater than the limit). See Section 7.2.6 for basis.
3.9.1 Method I
. EL(R)
- Q3 OfG ygg _( 3-8)
O co 1 (mrem) = ( ) (pC1) ( *)
Q3 - Total activity (pCl) released to the atmosphere of radionuclide "i" during the period of interest. For strontiums. use the most recent measurement.
for each OFG jeg - Site-specific critical organ dose factor (mrem /pC)).
radionuclide it is the age group-and organ with the largest dose factor. See Table B.1-12.
EL(R) Elevation Release Point (R) correction factor (dimensionless'.
For primary vent stack releases, EL(STACK) equals 1.0. For ground level releases, EL(GRO) equals 12.5 for the maximum off-site receptor, as shown on Table B.1-15.
~
B.3-22 oDCM Rev. 8 8684R ,
Equation 3-8 can be applieu under the following conditions (othcrwise, justify Method I or consider Method II):
- 1. Normal operations (nonemergency event),
- 3. Any continuous or batch release over any time period.
t 3.9.2 METHOD II d assumptions in Method 11 consists of the model. m r), except where Appendix C of Regulatory Guide 1.109, R,e 1 W i' 'H% ,
$1te-speelfic data or assumptions have been u ;iffe:! In the ODCH (see Tables B.7-2 and B.7-3). The-crit! cal' organ do o will be determined based on the location (site boundary, nearest resident, cr farm) of receptor pathways, as identified in the most recent annual land use census, or by conservatively assuming the existence of all pathways (ground plane, inhalation, ingestion of stored and leafy vegetables, milk and meat) at an off-site location of maximum potential dose. Concurrent meteorology with the release period may be utilized for determination of atmospheric dispersion factors in accordance !
with Sections 7.3.2 and 7.3.3 for the release point (ulther ground level or I
vent stack) from'which recorded effluents have been discharged. The maximum l
critical organ dose will consider the four age groups independently, and use a shleiding factor (SF ) of 0.7 associated with residential structures. ,
I s
l, .
L 6.3-23 oDCM Rev 8 8684R _
1 l
I 3.10 Method to Calculate Direct Dose from Plant Operation I
a t
Technical Specification 3.11.4 restricts the dose to the whole body or any organ to any member of the public from all uranium fuel cycle sources (including direct radiation from station facilities) to 25 mrem in a calendar year (except the thyrold, which is limited to 75 mrem). It should be noted that since there are no uranium fuel cycle facilities within 5 miles of the station, only station sources need be considered for determining compliance with Technical Specification 3.11.4 .
4 3.10.) Hethod The direct dose f rom the station will be determined by obtaining the dose from TLD Iccations situated on-site near potential sources of direct radiation, as well as those TLDs near'the site boundary which are part of the environmental monitoring program, and'$ubtracting out the dose contribution from background. Additional methods to calculate the direct dose may also be
-used to supplement the TLD information, such as high pressure ion chamber measurements, or analytical design cal cu al tions of direct dose from identified sources (such as solid waste storage facilities).
The dose determined from direct measurements or calculations will be related to the nearest real. person off-site, as well as those ir.div1Juals on-site involved in activities at either the Education Center or the Rocks boat landing, to assess the contribution of direct radiation to the total dose limits of Technical Specification 3.11.4 in conjunction with liquid and gaseous effluents.
~
B.3-24 ODCM Rev 8 8684R i
. = _ - - - _ .
3.11 Date Prolections Technical Specifications 3.11.1.3 and 3.11.2.4 require that appropriate portions of liquid and gaseous radwaste treatment systems, respectively, be used to reduce radioactive effluents when it is projected that the resulting cose(s) would exceed limits which represent small fractions of the "as low as reasonably achievable" criteria of Appendix 1 to 10CFR Part 50. The surveillance requirements of these Technical Specific.iticas state that dose projections be performed at least ence per 31 days when the liquid radwaste treatment systems or gaseous radwaste treatment systems are not being fully utilized. _
Since dote assessments are reutinely performed at least once per 31 days to account for actual releases, the projected doses shall be determined by comparing the calculated dose from the last (typical of expected verations) completed 31-day period to the appropriate dote limit for use of radwaste equipment, adjusted if appropriate for known or expected differences between past operational parameters and those anticipated for the next 31 days.
3.11.1 Qquid Dose Projecticns The 31-day liquid dose projections are calculated by the following:
(a) Determine the total body D tb and organ dose Dg (Equations 3-1 and 3-2, respectively) for the last typical completed 31-day period. The last typical 31-day period should be one without significant identified operational differences from the period being projected to, such as full power operaticn vs. periods when the plant is shut dOwn.
(b) Calculate the ratio (R)) of the total estimated volume of batch releases expected to be released for the projected period to that actually released in tne reference period.
B.3-25 cDCM Rev. 8 8684R _
l (c) Calculate the ratio (R )y of the estimated gross primary coolant activity for the projected period to the average value in the reference period. Use the most recent value of primary coolant activity as the projected value if no trend in decreasing or increasing levels can be determined.
(d) Determine the projected dose from:
Total Body: Dtb pr Otb
- N1.R2 l,
Max. Organ: D mo pr = 0,g . R3.R2 i l
3.11.2 Gaseous Dose Projections-for the gaseous radwaste-treatment system, the 31-day dose projections are calculated by the following:-
i (a) Determine the gamma air dose Da r (Equation 3-6), and the beta air doseDjr(Equation 3-7)fromthelasttypical31-dayoperating ,
period.
(b) Calculate the ratio (R ) of anticipated number of curies of noble 3 ,
gas to be released from the hydrogen surge tank to the atmosphere over the next-31 days to the number of curies released in the reference period on which the gamma and beta air doses are based.
If no differences between the reference period and the next 31 days :
?
can be identified, set R3 to 1.
(c) Determine the projected dose from:
Gamma Air: D a r pr- .Da r..
R3 Beta Air: O r pr - O r.R3 ,
ooca Rev. 8-8684R ,
4 .
For the ventilation exhaust treatment system, the critical organ dose from lodines, tritium, and particulates are projected for the next 31 days by the following:
(a) Determine the critical organ dose Den (Equation 3 8) from the last typical 31-day operating period.
(b) Calculate the ratto.(R 4) cf anticipated primary coo 4nt dose equivalent I-131 for the next 31 days to the_ average dose equivalent I-131 level during the reference period. Use the most ,
current determination of DE I-131 as the projected value if no trend can be determined.
(c) Calculate the ratio-(R ) of anticipated primary system leakage 5
rate to the average leakage rate during the reference period. Use the current value of the system leakage as an estimate of the anticipated rate for the next 31 days if no trend can be determined.
(d) Determine-the projected dose from:
Critical O_rgan: D o pr " Oco ' N4.R5
- f B.3-27 ODCM Rev. 8 8684R ,
i
~
f 4.0 RA010 LOGICAL ENVIRONMENTAL MONI,TORING PROGRAM The radiological environmental monitoring stations are listed in Table B'.4-1. The locations of the stations with respect to the Seabrook Station are shown on the maps in figures B.4-1 to B.4-6.
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 Envi enmental Radioactivity Laboratory Intercomparison Studies Program for all the species and matrices routinely analyzed.
Pursuant to Technical Specification 4.12.2, the land use census will be conducted "during the growing season" at least once per 12 months. The ,
growing season is defined, for the purposes of the land use census, as the period from-June I to 0ctober 1. The method to be used for conducting the census will consist of one or more of the following, as appropriate:
door-to-door survey, visual inspection from roadside, aerial survey, or consulting with local agricultural authorities.
l Technical Specification 6.8.1.3 requires that the results of the Radiological Environmental Monitoring Program be summarized in the Annual Radiological Environmental-Operating Report "in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1,1979." The general table format will be used with one exception and one clarification, as follows. The mean and range values will be based not upon detectable measurements only, as specified in the NRC Branch Technical. Position, but upon all measurements. This will prevent'the positive bias associated with the calculation of the mean and range based upon detectable measurements only.
Secondly, the Lower Limit of _ Detection column will specify the LLO required by 00CM Table A.5-2 'or that radionuclide and sample medium.
- B.4-1 oDCM Rev. 5 8685R L
TABLE B.4 1 Radiological Environmental Monitoring Stations (a) 4 Olstance from Exposure Pathway Sample Location Unit 1 Ofrection from and/or Sample and Designated Code Containment (km) . __,the Plant 2
- 1. AIRBORNE (Particulate and Radiolodine)
AP/CF-01 PSNH Barge 2.7 ESE Landing Area i AP/CF-02 Hampton Marina 2.7 E AP/CF-03 SH Boundary 0.8 SW AP/CF-04 W. Boundary 1.0 W AP/CF-05 Winnacunnet H.S.(b) 4.0 NNE AP/Cf-06 Georgetown 24.0 SSW '
Substation (Control)
- 2. HATERSORNE
- a. Surface WS-01 Hampton-Dis' charge Area 5.3 E
-HS-51 Ipswich Bay.(Control) 16.9 SSE 1
- b. Sediment SE-02 Hampton-Discharge Area (b) 5.3 E i
SE-07 3.1 E Hampton Beach (b) 3.2 ESE SE-08 Seabrook Beach SE-52 Ipswich Bay (Control)(b) 16.9 SSE 15.9 SSE SE-57 Plum' Island Beach (Control)(b) ,
t
, 3. INGESTION
- a. Hilk TM-04 Salisbury, MA 5.2 SW Hampton Falls, NH 4.3 NNH TM-08 ,
Hampton falls, NH 4.8 WNH TM-10 16.3 5 TM-20 Rowley,.MA (Control)
- b. Fish and Invertebrates (C) &
TH-03 Hampton - Olscharge 4.5 ESE Area FH-53 'Ipswich Bay (Control) 16.4 SSE HA-04 Hampton - Discharge 5.5 E Area HA-54 Ipswich Bay (Control) 17.2- SSE 5.2 E-MU-06 Hampton - Discharge l
Area Ipswich Bay (Control)- 17.4 SSE
_MV-56 lI I
B.4-2 ODCM Rev. 5 6685R
4 e l
l TABLE B.4-1 (continued) i a) j Radio 1_o_gical Environmental Monitoring Stations .
Distance from Exposure Pathway Sample Location Unit 1 Direction from and/or Sample _ and Designated 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 TL-3 Glade Path, Hampton 3.1 NE ,
Beach TL-4 Island Path. Hampton 2.4 ENE Beach TL-5 Harbor Rd., Hampton 2.7 E f
> Beach TL-6 PSNH Barge, Landing 2.7 ESE Area TL-7 Cross Rd.,.Seabrook 2.6 SE Beach Farm Lane, Seabrock 1.1 SSE TL-8 -
Farm Lane, Seabrook 1.1 5 TL-9 TL-10 Site Boundary Fence 1.0 SSW TL-Il Site Boundary Fence 1.0 SW ,
TL-12 Site Boundary Fence 1.0 WSW TL-13 Inside Site Boundary 0.8 W Trailer Park, Seabrook 1.1 WNW TL-14 Brimmer's Lane, 1. 4 - NW TL-15 Hampton Falls Brtmmer's Lane, 1.1 NNW TL-16 Hampton Falls TL-17 South Rd., N. Hampton 7.s- N i
TL-18 Mill Rd., N. Hampton' 7.6 NNE TL-19 Appledore Ave., 7.9 NE N. Hampton TL-20 Ashworth Ave., 3.4 ENE Hampton Beach TL-21 Route IA, 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 Rcute 107A, Amesbury 8.1 WSW TL-26 ODCM Rev. 4
'8685R-(
m,..nw-- ,-----o-a,
TABLE B.4-1 (continuedi Radiological Environmental Monitoring Stations (a)
Distance from
- Exposure Pathway Sample Location Unit 1 Direction from
_and/or Sample _, and Designated Code Containment (kml the Plant TL-27 Highland St., 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 TL Alumni Ortve. Hampton 4.0 NNE ,
TL-32 Seabrook Elementary School- 1.9 5 TL-33 Dock Area, Newburyport 9.7 5 TL-34' Bow St., Exeter 12.1 NW TL-35 Lincoln Ackerman School 2.4 NNW 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 (Control)(b)
TL-42 Ipswich, MA (Control)(b) 27 SSE (a) Sample locations are shown on figures B.4-1 to B.4-6.
(b) This sample location is not required by monitoring program defined in Part A of ODCM; program requirements specified in Part A do not apply to samples taken at this location.
(c) Samples will be collected pursuant to 00CM Table A.5-1. Samples are not-required from all stations listed during any sampling interval (FH . Fish; HA = Lobsters; MU Mussels). Table'A.5-1 specifies that "one sample of three commercially and recreationally important species" be collected in the vicinity of the plant discharge area, with similar species being collected at a control E location. (This wording is consistent with the NRC final Environmental Statement for Seabrock Station.) Since the discharge area is off-shore, there is a. great number of fish species that could be considered commercially or recreationally important. Some are migratory (such as striped bass), making them less desirable as an-indicator of- plant-related radioactivity. Some
- pelagic species (such as herring and mackerel) tend to school and wander throughout a large area, sometimes making catches of significant si7e difficult to obtain, _S_ince.the collection'of all species would be-difficult or "
impossible, and would provide unnecessary redundancy in terms of monitoring-important pathways to man, three' fish and invertebrate species have been specified as a minimum requirement. Samples may include marine fauna such as lobsters, clams, mussels, and bottom-dwelling fish, such as flounder or hake.
Several similar species may be grouped together into one sample if sufficient
-sample mass for. a single species is not available after a reasonable effort has
- been made (e.g.,-yellowtail flounder and winter flounder).
~
B.4-4 ODCM Rev. 4 8685R
FIGURE B.4 1 IM101021 CAL ENV110t:11EllIllJtJITOPING L0 fail 0R5 ELT1[IN 4 ULQMETERS OF SEJJiEQQJ'dIAllfi{
%y N ( /))/ y/
k3
(
g~
-.- /"' }Q ( lk ft Jh N
y /emp>r/ Q,;4 fk
/3
/
OW RIV
$E B K2 _
)
/)(v
.1
~
AP/CF-04 A HAMPTCH HARECR AP/CF-03 A % s FU IST y p-,
REEX AF/CF-01 A N
(y SE-03 A 1 [ f 1 au5E
[,
/
0 500 1000 L
U u
.h
) , , $'.g. .
5 METERS Q f .7
! / \
B.4 5 ODCM Pev. B
FictTRE B,4 2 FADlfL0fqlO1_CillEQ2iIRIll MOH112ElEilDCAll0Il2 -
LEriLEN 4 ElLQBLI1ES.ll!D_l'MQJ4ETEE5 II.011_5fAEFf2CE_iTAllD11 "h
0 5 X c: . a=: - .=s
% KILCMETERS 0
o O
m
(
N' RYE BEACH
%d TM-09 A T
SEE ENLARGEMENT IN FIGURE B.4-1 % A AP/CF-05 i - -. - - .
\
8 l w.t
TM-10 A l l
' HAMPTON BEACH
' lA$E-07
$EABR00K 5 ATION " A*
h3 6
WS-01
~ DISCHARGE SITE i SE-02 80-06
- . . , i V I FH-03 HA-04 g5
- hg$5@k ,N. .d
'i % SEABRC0K BEACH t
l 's -
- i
,#*'. 1 l - - .s 4f---- .
>\
~~
TM-04 A SALISBURY EEACH D
^
e J hippgp;( psfG O ATLANTIC CCEAN
/S' B.4-6 ODCM Rev. B
- - . - - - -. - ~ _ . . - __~ _ - . =
TICL'RE B.4 3 l'IDT0 LOGICAL Er{ylRot: MENTAL MONITORING 1.OCAT10f4 OUTSIDE 12 KILMilEES OF SEMROOK. STATIQjj f_._ ._ _ -._. .N KILCMETERS e YORK 4 e "Y
CURHAM e %
~
Q sg NV l NEWMARKEi e ORTSMOUTHe .
, EPPING \
O /, 'g 1,\,i'
, , yi I I SEE ENLARGEMENT IN FIGURE l '
B.4-2 J 8 I HAMPTON I
i e i l l -
l KINGSTON e l SEAER00K STATICN ),
- HAMPTON HAREOR
" ' '~
SEABRC0K e N. O!$ CHARGE $1TE
^
l .- .
/ MESEURY e 34 .
ATLANTIC CCEAN
- 4) ____I I
HAVERHILLo (I
- A SE-57 1
.. 1, PLUM ISLAND TM-20 FH-53 METHUEN , AP/CF-05 A A S E-52 A W$-51
- LAWRENCE
[ gps.jgcq ggy, f A MU-5 6 IP5WICH e .
HA-54 o GLOUCESTER, ODCM Rey, 8 E.4 7
TICURE B.4 4 DIRECT PADI ATION MONITORING LQfATIONS WITHIl{
4 KILCMETERS OF SEAPPOOV STATION N
' A it-2 NE gy /
w}>p JN i
tf" } } } }A TL-3 /
~
L 7
- TL-14 A
] m @ A VERp/ s q - tRo '
susRcoK 1 qv N f stABRo0x 2 ,
O E
W TL-13 a k4 'y-d ~ TL-5 4 k
K L A ESE
/y g ATL-7 SW TL-32 a l C %~
fgg g $ b' t
p 0 (CO 1000 i
i D TL 21
/ HETERS
[
}/ ssw s ssE
,m sE g
8 ODCM Rev. B
TICURE B.4 5 DIRECT RADIATION MONITQRING 1.OCATIONS PETVEEN t._P11.OMETERS AND 12 MILOMETERS PROM EEAEROOK STATIOtt a lb4W N' NNE 5
a, 0
r- _ . - . - - .
KILCMETERS g ,
b NW T y NE t
N A TL-34
! Miles A RYE BEACH A' 7 ~ ~ TL-17 A
/
% TL-30 TL-18 A TL-19 A TL-29\ ENE WNW \ \
SEE ENLAR EMENT IN FIGURE B.4-4 A TL-26 \ ~g,g~/' ~ 'e k ~~^~
A E
--i w ON "
y A TL-2 y N.' , i #--- SEABROCK BEAC TL-26 l'\. , l q ' - - - N, - -Gh ' / ESE WsW }\ b $AL' SEURY . BEACH TL-22 TL-24 A A\
b A m REARIMAc- ON SE
\
~
A .O ATLANTIC OCEAN SW \
~
i B.4 9 ODCH Rev. 8
TICURE B,4 6 DIRECT PADIATION MONITORING 1_0CATIOMS 0.!!111DE 12_ntOMETrRS OF SEAPPOOV. STell.Cl{
NNW N ! .P' NNE O 5 10 it sw k.= - .
gy K1LOMEi[RS i e cuRHAM e q
v Qv s. g NE TL 40 A - t 0 TL-39 NEWMARKET e A
FORTIMOUTHe A
b/
RAYMCND
. uR1NG f a ,,,/ 1L-41 \x WNW --
s g------ -- ,l ?e\'$' gyg
-"I ENLARGEMENT IN FIGURE F B.4-5 h N HAM TCN
/ 8[ '
//
g KINGSTCN*
lSEABROOKSTATIONNk SEA!R00K e E
, I T
g i l TL-28 A # . .-
XJ4 DISCHARGE SITE
,/* SALISEURY %
PLAIsiCW e ,
ig/ .
, ) * -
NEVEU ,
ATLANTIC CCEA i
_ _ . , _ ' _ . _ _l WSW [ sAv[asitt. / /
/
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. ~ , , 1 PLUM ISLAND
.ETHUEH , TL-36 A
[
- LAWRENCE PSWICH EAY IPSWICH e SE
, m. 3 it .t SW
~
ODCH RW, 8 3,4,79
I fj .
1 - (f2+I 3
- I 4} I *h"' II i s the fraction of the total contribution of MPC at the discharge point to be
' associated with the test tank effluent pathway and, (2' I3 '
and f are the sir'lar fractions for Turbine Building sump, 4
steam generator bit s wn, and primary component ccoling pathways, respectively: (f) + f2*I3*I 4 1 I}'
(5-3) 0Fmin " fi g
[
MPC for radionuclide "1" from 10CFR20, Appendix B, Table !!,
= l HPC, Column 2 (pCi/ml). In the event that no activity _15 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.
C,9
- Activity concentration of radionuclide "1" in mixture at the 1 monitor (pC1/ml) 2 5.1.1.2 Liquid Waste Test Tank Monitor Setpoint Example _
The activity cenrentration of each radionuclide, C ,g, in the waste '
test tank-is determined by analysis of a representative grab sample obtained at the.-radwaste sample sink. This setpoint example is based on the following data: ,
1 C,g (pC1/ml) MPCg (pCi/ml)
Cs-134 2.15E-05 9E-06' Cs-137 '7.48E-05 2E-05 Co-60 2.56E-05 3E-05
- . 1;22E-04
__, C ,9 - 2.15E-05 + 7.48E-05 + 2.56E-05 1
(h) (",f ) (yh) ($f)
B.5-3
- ODCM Rev. 8 8686R ce r w we -y -e-- +--w .er sw e -- -r ws arwe e-: * *, e-%ws ww-~,--e e, - m re , wwww we er-- v eww +er-w .y-e me c=-em t+ .mw=vw w yw w irese-,w =p.rtw-vem wwey-nm~ -_ireeg--w--m-- gw -' ' '
(5-3)
Of
- min t i
(pCl-m1) mi-pCl o
2.15E-05
- 7.48E-05 2.56E-05 * '
-g pC1-ml y pCi-ml gpCi-ml) mi-pCl gml-pC)) ml-pC1 4
DFmin " 7
'The minimum dilution factor, Ofmin, needed to discharge the mixture of radionucildes in this example is 7. The release rate of the waste test tank is between 10 and 150 gpm. The circulating water discharge flow can vary from 10,500 to'412,000 gpm of dilution water, With the dilution flow taken as.
412,000 gpm and the release rate from the waste test tank taken as 150 gpm, the DF is:
OF - ' = .
m .
(gem) (5-4)
~( g pm) 412,000 gym
-150 gpm
--2750
. B.5-4 ODCM Rev. 4 8686R
Under these conditions, and with the fraction fg of total MPC to be '
associated with the test tank selected as 0.6, the setpoint of the liquid
- radwaste discharge monitor is: >
R$etpoint
- Il 6 in
- I h ( )( ) (h) 1.22E-04 f
0.6
() ( ) (h)
- 2.C,i-02 pCl/mi or pCl/cc In this example, the alarm of the liquid radwaste discharge monitor should be set at 2.87E-02 pC1/cc above background.
5.1.2 Turbine Building Drains Liquid Effluent Monitor (RM-6521)
The Turbine Building drains 11guld effluent monitor continuously monitors the Turbine Building sump effluent line. The only sources to the Sump Effluent System are from 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 l 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 HPC, the setpoints of RM-6521 are calculated as follows:
~
B.5-5 oDen Rev. 7 8686R.
High Trip Monitor fj(DF') (1.0E-07 pC1/ml) (5-21)
Setpoint (pCl/ml)
I
)
where:' 1 Circulating water flow rate (gem) 0F' -
Flew rate pass monitor (gpm) !
1.0E-07 pC1/ml most re'strictive HPC value for an unidentified mixture given in 10CFR20, Appendix B. Note 3b. ;
a e
f2 =1- (f1+f 3 + f 4); where the f values are described above.
Warning Alarm High Trip (5-22)
Honitor Setpoint .gMonitor Setpoint) (^*25)
(pC1/ml) -
5.1.3 Steam Generator Blowdown t.iould Sample Monitor (RM-6519) l The steam generator blowdown liquid sample monitor is.used to detect abnormal activtty concentrations in the steam generator blowdown flash tank 11guld discharge.
1 The_ alarm setpoint_for the. steam generator blowdown liquid sample monitor, when liquid is to be discharged from the_. site, will be determined using the same approach as the Turbine Building dra. ins liqu.id effluent monitor.
For ai equid monitor, in the event that no acti vity is expected to be discharg'ed, or can be measured in the system, the liquid monitor setpoint L
L should be based on the most restrictive MPC for an Punidentifled" mixture given in 10CFR20, Appendix B notes.
I 5.1.4 -PCCW Head Tank Rate-of-Change Alarm Seteoint-A rate-of-change alarm on the liquid level in the Primary Component Cooling Water (PCCW) head tank will work in conjunction with:the PCCW Tradiation monitor to alert the operator in the Main Control Room of a leak to B.5-6 ODcH. Rev. 8 8686R
the Service Water System from the PCCW System, for the rate-of-change alarm, !
a setpoint is selected based on detection of an activity level equivalent to ,
10-8 pCl/ml in the discharge of the Service Water System. The activity in the PCCW is determined in accordance with the liquid sampling and analysts program described in Part A. Table A.3-1 of the OOCH and is used to determine the setpoint.
The rate-of-change alarm setpoint is calculated from:
2 RC set lx10~0 SWF h (5-23) ,
(g_a.1,) ,, (pCl) (gal) hr mT h r- (mlT)
R where: -
RC - The setpoint for the PCCW head tank rate-of-change set alarm (in gallons per hour),
~
1x10~8 - The minimum detectable activ1ty-level in the Service Water System due to a PCCW to $WS leak (pC1/ml).
SHF - Service Water System flow rate (in gallons per hour).
PCC = Primary Component Cooling Water measured (decay---
corrected) gross radioactivity. level (pCl/ml),
As an example, assume a PCCW activity concentration of 1x10-5 C1/ml with a service water flew rate of only 80 percent of the normal flow of 21,000 gpm. -The rate-of-change-setpoint is then: . ,
RCset - 1x10 h g
1.0x106 gph (1/1x10-5 )
RCset - 1000 gph
. 0.5-7 oDCM Rev. 7 8686R -
m wr
=-wr-w - e- - . - e,-.w-w em-.e+- -e ,,.n,,-=,r-we.,.ww_, woe..,.pg.,i, .gy-py,.,,,-e--p-,-,,.y,,,y- g,..%,_.,,,. .,M. .,w ,.g'-m* e se garr e- e s g s -+s-eernw pt 9 w *m -- esr - .r
As a result, for other PCCW activities, the RCset which would also relate to a detection of a minimum service water concentration of 1x10~8 pCl/ml can be found from:
' '" D (5-24)
RCset "
5.1.5 PCCW Radiation Monitor The PCCW radiation monitor will alert the operator in the Main Control Room of a leak to the PCCW System-from a radioactively contaminated system.
The PCCW radiation monitor alarm is based on a trend of radiation levels in the PCCW System. The background radiation of the PCCW 15 determined The alert alarm by evaluating the radiation levels over a finite time period. -
setpoint is set at 1.5 x background, and the high alarm setpoint is set at
.2 x background, per Technical Specification Table 3.3-6.
i
. B.5-8 ODCM Rev. 8 8686R
)
i 6.0 LIOUID AND GASEOUS-EFFLUENT STREAMS, RADI ATION MONITORS AND RADWARE l TREATMENT SYSTEMS !
Figure B.6-1 shows the liquid effluent streams, radiation monitors and the appropriate Liquid Radwaste Treatment Systern. Figure 8.6-2 shows the f gaseous effluent streams, radiation monitors and the appropriate Gaseous j
Radwaste Treatment System. !
For more detailed information concerning the above, refer to the i Seabrook Station Final Safety Analysis Report, Sections 11.2 (Liquid Waste #
System), 11.3 (Gaseous Waste System) and 11.5 (Process and Effluent l Radiological Monitoring-and Sampling System).
.The turbine gland seal condenser exhaust is an unmonitored release path. The iodine and particulate gaseous releases will be determined by
-i continuously sampling the turbine gland seal condenser exhaust. The noble gas i
releases will be determined by the noble gas released via the main condenser air evacuation exhaust and ratioing them to the turbine gland seal condenser
~
exhaust by use of the flow rates. .
L i 1
1 i
B.6-1 8687R ,.
oDcM Rev. 4 i
.2 , , . , _ , _ . - _2._ _ . _ . _ - _ _ , . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ _
I i
lAAKEUP 11tJIT STORAGE TANK PAB g l
Y
. t ti 4 /y b '
s'v5?N" O '
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- 1 I
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- st wt
- aseveu smwo a:arew SVsit M ! pg,t t6C 4 l
i I I4 4
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i g x r -
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6t aira- REl. EASE ,w ,sn
<e: cts.s .... s ru' gavsvu Ccefmot Attt.58 vCS Mo*4 0 vgegce
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t*:':'..u.'
n :..
='a,t.:. ..n.
Q s~~ ua w Q .a, . n. e,n.
, ~ . - . . , ~
1 FIGURE B.6-1 Licuid Effluent Streams, Radiation Monitors, and Radwaste Treatment System at Seabrook Station oocM Rev. 8 8687g.
e- .. . '
(DU%h4 HOGGING COf4TAlf! MENT . ISII' *** "0C' CNk" BUILDING ..
VENTUTORE
+
TURO Nt ' t t t vacGuu Sull 02*G l ] l PyMP f,'E ty y,cyyy U f LUf NT PLtCTCM GL%1t(TOI:
WasAt CONct*itR
" ~ 2 o '
4 V b CONTAihMENT
' ], I sw PJACE A:R -- .
e j
=0 Stow 00WN FLASH TANK CASE 0VS WASTE NCCisSihG SY1Ttu ]
C00 A T ~ "
TVMAL Cr TbPt! y,q ,g[ f M.U '
W
' thf M -
QUARD i
f , l BED ,,
C00t,id} .q l DRYER -
CHARCOALBtOS ' l
_ i e COMPP(550R l e
PH;MAAY pp3uAny l WNT AUX 1LIARY _
mm ) ese STACK ButLDit.O f " ":S '
~
futL
. va,we
$7 BUILOtNG ~b7
( _/ V I U
su .
AUX 1LIAAY BUILDlho VENT AIR * -d LEGEND H HEPA F;LitR C . CHARCOAL FILTER
((
- RA0tATlON MCNITCR FIGURE E.6-2 Gaseous Effluent Streams, Radiation Monitors, and Radwaste Treatment System at Seabrock Station l_
I l
' - B.6-3 ODCM Rey, 8 8687R
~
t 7O BASES FOR DOSE CALCULATIOW METHODS' Liquid Release Dose Calculations
~
7.1-
-This section serves: _ (1) to document the development and conservative nature of Method I equations to provide background information to Met'":o T users, and (2) to identify the general equations, parameters and appt .,a3, to ;
Method II-type dose' assessments. .
Method I-may be used to show that the Technical Spetifications which limit off-site total body dose from liquids (3.11.1.2 and 3.11.1.3) have been '
met for releases over the appropriate periods, The quarterly and annual dese-limits in Technical Specification 3.11.1.2 are based on the ALARA design objectives in 10CFR50, Appendix 1 Subsection II A. The minimum dose salues noted in Technical Specification 3.11'.1.3 are " appropriate fractions," as determined by the NRC, of the design objective to ensure that radwaste equipment is used as required to keep off-site doses ALARA.
Method I was devel .,d such that "the actual exposure of an individual ... is unlikely to be substantially underestimated" (10CFR50, Appendix I). The definition, below, of a-single " critical receptor" (a hypothetical or real -individual whose behavior results in a maximum potential dose) .provides part of the conservative margin to the calculation of total body dose in Method I. Method II allows that actual individuals, associated with identifiable exposure pathways, be taken Into account for any given release, In-fact, Method I was based on a Method II analysis:for a critical receptor assuming all principal pathways present instead of any real individual. That analysis was called the " base case;" it was then reduced to
' form Method 1. -The general equations used in the base case analysis are also The base case, the used as the starting point-in Method II evaluations.
method of reduction,- and _ the assumptions and data used are presented below.
First, the dose The steps performed in-the Method I derivation follow.
impact to the critical receptor (in the form of dose factors DFl itb (mrem /pCl)] for a unit activity' release of each radioisotope in liquid The base case analysis uses the general equations,
- . effluents was derived.
methods; data and assumptions in Regulatory Guide 1.109 (Equations A-3 and B.7-1 oDCM Rev. 4 ,
8688R h
7 A-7, Reference A), .The liquid pathways contributing'to on. individual dose are.
due to consumption of fish and invertebrates, shoreline activities, and.
swimming.and boating near the discharge point. A normal operating plant discharge flow rate-of 918 ft 3/sec was.used with a mixing ratto of 0.10.
The mixing ratio of 0.10 corresponds to the minimum expected prompt dilution or near-field mixing zone' created at the ocean surface directly above the multiport diffusers. (Credit for additional dilution to the outer edge of the 0
prompt mixing zone which corresponds to the 1 F surface isotherm (mixing ratio .025) can be applied in the Method II calculation. The edge of this isotherm typically does not rear' ' 7 shoreline rece[. tor points during the
-tidal cycle.) The~ location of the critical receptor is assumed to be the edge
- of the mixing zone at the ocean surface.
The requirements for the determination of radiological impacts resultingfrcmreleasesinliquideffiuent: is derived frcm 10CFR50, Appendix I.Section III.A.2 of Appendix I indicates that in making the assessment of
-doses to hypothetical receptors, "The Applicant may take account of any real phenomenon or factors actually affecting the estimate of radiation. exposure, including the characteristics of the plant, modes, of discharge of radioactive materials, physical processes tending to attentuate the quantity of radioactive material to which an individual would be exposed, and the effects of averaging. exposures over time during which determining factors may fluctuate." In accessing the liquid exposure pathways that characterize Seabrook Station, the design and physical location of the Circulating-Water Discharge Systemn .eeds.to be considered within the scope of Appendix I.
Seabrcok utilizes an offshore submerged multiport diffuser discharger
'for rapid dissipation and mixing of thermal effluents in the ocean environment. The 22-port diffuser section of the Discharge System is located in approximately 50 to 60 feet of water with each nozzle 7 to-10 feet above the sea ~ floor. Water is discharged in a generally eastward direction away from the shcrelins nrough tne multiport diffuser, beginning at a -location
- B.7-2 oDCM Rev. 8 8688R _
-- aa-,-. .- - . - -. - . _ . _
lover one mile due east of Hampton Harbor inlet. This arrangement effectively '
prevents _the discharge plume (at-least to the 1 degree cr 40 to 1 dilution isopleth) from impacting the shoreline 'over the tidal cycle.
Eleven riser shafts with two diffuser nozzles each form the diffuser and are spaced about 100 feet apart over a distance of about 1,000 feet. The
~
diffusers are designed to maintain a high exit velocity of about 7.5 feet per second during power operations. Each nozzle is angled approximately These high 20 degrees up from the horizontal plane to prevent bottom scour.
velocity _ jets passively entrain about ten volumes of fresh ocean water into ' >
the near field jet mixing region before the plume reaches the water surface.
This factor of 10 mixing occurs in a very narrow zone of less than 300 feet from the diffuser by the time the thermally buoyant plume reaches the ocean surface. This high rate of dilution occurs within about 70 seconds of discharge from the diffuser nozzles. '
l The design of--the multiport diffuser to achieve a 10 to 1 dilution in the near field jet plume, and a 40 to 1 dilution in the near mixing zone '
associated;with the 1 degree isotherm, has been verified by physical model tests (reference " Hydrothermal Studies of Bifurcated Olffuser Nozzles and Thermal;Backwashing - Seabrook Station," Alden Research Laboratories, July 1977).
Ouring shutdown. periods, when the plant only requires service water cooling flow, the high velocity jet mixing created by the normal' circulating However, mixing within the water flow at the diffuser nozzles is_ reduced.
discharge:tunn'el water volume is significantly increased (factor of about 5) due to the long transit time (approximate _ly 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />) for batch waste j
discharged from the_ plant-to travel _the three miles through the 19-foot
! diameter tunnels to the diffuser n_ozzles. Additional mixing of the thermally j
buoyant effluent in the near field mixing-zo 4 assures that an equivalent
! overall 10 to 1 dilution occurs by the time the plume reaches the ocean
-surface.-
i
- 8.7-3 oDCM Rev. 8 8688R ,
L l
=. - . - , , - . - . , . . - . . . .
_ . _ _ . _ . . _ _ _ _ - - - _ _ _ _ - _ . _ _ _ _ _ _ _ _ ~ _ ____
The dose assessment models utilized in the ODCM are taken frcm NRC Regulatory Guide 1.109. The liquid pathway equations include a parameter
-(M ) to account for the mixing ratio (reciprocal of the dilution factory of p
effluents in the environment-at the point of exposure. Table 1, in Regulatory Guide 1,109 --defines the point of exposure to be the location that is anticipated to be-occupied during plant lifetiine, or have potential land and water usage and food pathways as could actually exist during the term of plant operation. For Seabrook,-the potable water and land irrigation pathways do not exist since saltwater is used as the receiving water body for the circulating water discharge. The three pathways that have been factored into the assessment models are shoreline _ exposures, ingestion of invertebrates, and' fish ingestion.
'With respect to shoreline exposures, both the mixing rat w -? 0.1 and 0.025 are extremely conservative sinc'e the effluent plume which is discharged over one mile offshore never reaches the beach where this type of exposure could occur. Similarly, bottom dwelling invertebrates, either taken from mud flats near-the shoreline or from the area of diffuser, are not exposed to the undiluted _ effluent plume. The shore area is beyond the reach of the surface plume of the discharge, and the design of the upward directed discharge nozzles along with the thermal buoyancy of the effluent, force the plume to quickly rise to the surface without affecting bottom organisms.
Consequentially, the only assumed exposure pathway which might be impacted by the near field plume of the circulating water discharge is-finfish. However, the mixing ratio of 0.1 is very conservative because fish will avoid both the high exit velccity provided-by the discharge nozzles and the high thermal temperature difference between the water discharged from the diffuser and the ambient water temperature in the near field. In addition, I the dilution factor of 10 is achieved within 70 seconds of discharge and confined to a very small area, thus prohibiting any significant quantity of fish from reaching equilibrium conditions with radioactivity concentrations created in the water environment, l'
- B.7-4 ODCM Rev. 8 8688R _
l
. . - - .-. -. - - - - - -.-..-. ..- -. - .- -.- - - -.~.~ - -
The mixing ratio of 0.025, which corresponds to the 1 degree thermal near field mix!ng zone, is a more realistic assessment of the dilution to
,which finfish might be exposed. Howesar, even this dilution credit is conservative since it neglects the plant's cperational design which discharges radioactivity by batch mode. Batch discharges are on the order of only a few hours in duration several times per week and, thus, the maximum discharge concentrations are not maintained in the environment long enough to allow fish to reach equilibrium uptake concentrations as assumed in the dose assessment modeling. When dose impacts from the fish pathway are then added to the very conservative dose impacts derived for shoreline exposures and invertebrate ingestions, the total calculated dose is very unlikely to have underestimated the-exposure to any real individual.
The recommended value for dilution of 1.0 given in NUREG-0133 is a simplistic assumption provided so that'a single model could be used with any plant design and physical discharge arrangement. For p_ l ants that utilize a surface canal-type discharge structure where little entrainment mixing-in the environment occurs, a dilution factor of 1.0 is a reasonable assumption.
However, in keeping with the guidance provided in, Appendix I to 10CFR50, Seabrook has determli.e site-specific mixing ratios which factor in its plant design.
The transit time 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 />, and for shoreline activity 0.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />. Table B.7-1 outlines the human consumption and use factors used in the analysis. The resulting, site-specific, total body dose factors l appear in Table B.1-ll. Appendix A_provides an example of the development of a Method I 11guld dose conversion factor for site-specific conditions at Seabrock'.
7.1.l' Dose to the Total Body For-any 11guld release, during any period, the increment in total body dose from radionuclide "1" is:
- oDCM Rev. 8 8688R
=
.~-.pe-, w ,-r- e ,w +v --VT
~
80 =.k Qg DFl tk .
itb' (mrem) ( ) (pCl) ( _
- )
where:
DFLitb = Site-specific total body dose factor (mrem /pC)) for a liquid release. It is the highest of the four age groups.
See Table B.1-11.
Qt - Total activity (pC1) released for radionuclide "i".
K = 918/Fd (dimensionless); where Fd is the average dilution flow of the Circulating Water System at the goint of ,
discharge from the multiport diffuser (in ftJ/sec). ,
Method I is more conservative than Method II in the regicn of the Technical Specification limits because the dose factors DFlitb used in 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 rich '
radionuclide is conservatively represented by its own critical age group.
7.1.2 Dose to the Critical Organ The methods to calculate maximum organ dose parallel to the total body dose methods (see Section 7.1.1).
l-l ~ For each radionuclide, a dose factor (mrem /pC1) was determined for each Lof seven organs and four age groups. The largest of these was chosen to be OFl the maximum organ dose factor (0FLg ) for that radionuclide. imo 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 maximum organ is:
L DFL g (7-2)
AD, = k- Qg (mrem)'( ) (pC1) ("]*)
B.7-6 oDCM Rev. 8 8688R
~m -~ e ~
. .- - . - . .. - . _ - . .. .~ . ..-. - . . - - - - . . - _ . . . - . . - . . . . .
e where.:
DFl imo = Site-specific maximum organ dose factor (mrem /pCl) for a liquid release. See Table B.1-11.
Qt
= Total activity (pCl) released for radlonuclide "1".
K = 918/Fd (dimensionless); where Fd i s the average dilution
- ficw of the Circulating Water System at the3 point of discharge frcm the multiport diffuser (in ft /sec),
B.7-7 ODCM Rev. 8 8688R
. , . --------w-,-+em e, , ..,m% . , . .,-, c y..y.,,.-,-+_.y...-w%.w, ., - .-y,yy-,.,, , -p,,.,,,,qyy,,,y..ywyy, ,- .#w-fy ,,y,- w n r4 ,i. -r
TABLE B.7-1 lisage factors for Various Liquid Pathways at Seabrook Station (from Reference A.. Table E-5*, except as noted. Zero where no pathway exists)
FISH INVERT. POTABLE Sil0 RELINE SHIMMING *** BOATING ***
AGE VEG. LEAFY HILK HEAT VEG. HATER (KG/YR) (KG/YR) (KG/YR) (LITER /YR) (llR/YR) (HR/YR) (HR/YR)
(KG/YR) (KG/YR) (LITER /YR) 0.00 0.00 21.00 5.00 0.00 334.00** 8.00 52.00 Adult 0.00 0.00 !
0.00 0.00 16.00 3.80 0.00 67.00 45.00 52.00 0.00 Teen 0.00 0.00 0.00 6.90 1.70 0.00 14.00 28.00 29.00 l Child 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 '0.00 In'fant 0.00 0.00 i
- Regional shoreline use associated with mudflats - Maine Yankee Atomic Power Station Environmental Report
' *** llERMES; "A Digital Computer Code for Estimating Regional Radiological Effects from Nuclear Power Industry,"
llEDL, December.1971. Note, for Method II analyses, these pathways need not be evaluated since they represent only a small fraction of the total dose contribution associated with tiie other pathways.
B.7-8 oDCM Rev. 8 8688R
-7.2 G_aseous Release Oose Calculations 7.2.1 Total Body Dose Rate From Noble Cases 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. ,
Method I may be used to show that the Technical Specification which limits total body _ 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.
Method I was derived from general equation B-8 in Regulatory Guide
-.l.109 as follon: .
, y7 .
(7-3)
D tb
= 1E+06 (X/Q) L. Og DFB g i .
3 (mrem) , (pCl)(sec) (gC l.) (mram-m )
yr pCi ,3 sec pCi-yr where:
CX/Q)Y = Maximum off-site receptor location long-term average gamma atmospheric dispersion factor.
3
. 8.5E-07 (sec/m ),-
hg_ = Release rate to the environment of noble gas "1" (pCl/sec).
~*3 0FB p = Gamma total body dose factor, ( y
). See Table B.1-10.
(Regulatory Guide 1.109, Table B-1).
Equation 7-3 reduces to:
b = 0.85
- EL(R) hg 0FS g (3_3) tb i 3
mrem - uCl mrem-m fyr}*(pCl-see Cl-m 3 p -yr oDCM RW.8 8688R
The selection of critical receptor, outlined in Section 7-3 is inherent 'in the: .
derived Method I, since the maximum expect $d off-site long-term average atmospheric dispersion factors were used for a primary vent stack release.
The EL(R) term is added to the~above equation as a dimensionless correction factor to be applied when calculating the impact frcm ground level release points. For primary vent stack releases, this correction factor is equal to 1.0 since the dose conversion factors are based on meteorological dispersion parameters derived for this release point. For release points other than the primary. vent stack, the correction factor reflects the difference between ground level dispersion and that associated with the primary vent stack. The sum of doses from both plant vent stack (EL(R) < 1.0) and ground level releases (EL(R) " values from Table B.1-15") must be considered for determination of Technical Specification compliance. All noble gases in Table B.1-10 should be considered. ,
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 Cases ,
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 nchle 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 (frcm NBS Handbook 69, Reference 0, pages 5 and 6, is- 30 rem /10). The factor of 10 reduction is to-account for nonoccupational-dose limits.
~
oDCM Rev. 8 8688R -
re-., - , --,vr r ..,,-. .- -m ~ --v. c
-- - - - ~ . _ _ _
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.
Me', hod I was derived from the general equation 8-9 in Regulatory Guide 1.109 as follows:
3
- 1.11 D + 3.17E+04 DFS g (7-4) 0 tr 03 (X/Q) i 3
IpCl-yr) see (mrem' yr
- Imrem) mrad (mrad) yr Cl-sec C1 y7 (, T } (mrem-m pCi-yr '
where:
1.11 - Average ratio of tissue to air absorption coefficients (will convert mrad in air to' mrem in tissue).
DFSt - Beta skin dose factor for a semi-infinite cloud of radionuclide "1" which includes the attenuation by the outer
" dead" layer of the skin.
- 3.17E+04 Q3 [X/Q) DFj Y (7-5)
D tr 1
3 (mrad)-
pCi-yr (Cl) (sg ) mrad-m yr (Cl-sec) yr ,3 pCi-yr DFJ - Gamma air dose factor for a uniform semi-infinite cloud of radionuclide "i".
Now it is assumed for the definition of (X/QY) from Reference B that:
( -6)
Ofinite" O alr ( /Q /(X/Q)
( ) =( r} ( } ( }
B.7-11
' ODCM Rev. 7 8686R
-~. - - - - . . , - . , ,-,
j
- (7-7)
.and - Qg
- 31.54 hg (C_1.) , (Cl-sec)-(pC1) yr pCl-yr sec (7-8) so: 1.11- 1E+06 [X/Q)Y h DF{:
bs kin 1- 1 3
(tzr em) , (mrem) (pCl) gc) c (pp) (mrad-m )
pCi-yr pCl ,3 sec ,
yr mrad .
+ 1E+06 X/Q hg_ DFS g 1
3 (pC.1 ) sec pg m_
__sec (mrem-pCi-yr )
pCl ,3 4
substituting 3
[X/Q)Y - 8.5E-07 sec/m 3
X/Q - 8.2E-07-sec/m (7-9)
-0.82 hg 0F5g-gives b skin - 0.94 hg 0F{+ 1 1-3 3-(mremy , (DCI-sec-mrem)(pC1)gmrem-m sec pCi-yr 3)(pCi-sec)(gC1)(mrem-m sec pCl-yr )
yr 3 Cl-m -mrad Cl-m (7-10)-
- l_ h [0.94.0F{
3 + 0.82 0FS 3 g I
define
-.(7-11)
DFj_-0.94DF{+0.82DFS g B.7-12 ODCM Rev. 8
__8688R -
-r-y'"e-yvyw7--,w ,,,---m.c,- g -r-yw,.rci- ---n--- , ..-,4 --*.7--y a ge-,y e y g p9--~ 9 p--#-y.c! e
then: b skin - EL(R)
- hg DFj (3-4)
(mremy,( ) (pC_i ) gmrem-sec) pCi-yr yr sec The EL(R) term is a dimensionless correction factor that is applied when calculating the dose impact from a ground level release point. For primary vent stack releases, this correction factor is equal to 1.0 since the dose conversion factors derived for all Method I applications are based on-meteorological dispersion parameters calculated for this mixed mode elevation release height. For release points other than the primary vent stack, the EL(R) correction factor reflects the difference between ground level disitersion and that associated with the primary vent stack. This is done so that the same list of mixed mode (primary vent stack) Dose Conversion factors (DCFs) can be used for eicher ground -level or vent stack releases. The EL(GRD) correction factors are derived by calculating all the specific nuclide dose conversion factors in the same way as was done for the vent stack release point (see Appendix A for example calculation of a vent stack release point DCF), but substituting in the equivalent ground level release point dispersion factors for each critical receptor point.- Then, for each radionuclide, a
- ratio between the ground level DCF und the vent stack DCF was calculated, with the largest ratio for each release type selected to represent the correction factor for use with the Method I dose equations. Table B 1-15 lists the correction factors calculated in this way for each release type.
The selection of critical receptor, 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. All noble gases in Table B.1-10 must be considered, t
. B.7-13 oDCM Rev. 8 8688R
-m- w. ...i-,v. .,-. w..e,,,s .r.-- +e -i,..w,3,py.---r,--,..,c-,.- m.c3..., e..,,-,--,,pwm ,---_.-.-mm9my- =. - -w-,. , .-. - , , w --
y- ---=p-g- ,- + e --
l
' I Critical Organ Dose Rate from Iodines, Tritium and Particulates With ]
7 . 7. 3
. Half-Lives Greater Than Eight Days This section serves: (1) to document the development of the Method I to
- equation, (2) to provide background information to Method I users, and (3) 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.
Method 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 (from NBS Handbook 69, Reference D, pages 5 and 6). It is evaluated by looking at the critical organ ,
dose commitment to the most limiting off-site receptor assuming long-term site average meteorology.
Theequationforb co is derived by modify 1'ng Equation 3-8 frem Section 3.9 as follows:
- (3-8)
D - EL(R) Qg 0FG i co co 1
-(mrem) l( ) (pC1) ( *)
applying the conversion factor, 3.154E+07 (sec/yr) and converting Q to hinpC1/secyields hy 0FG gcg 0-12) b - 3.154E+07
- EL(R) co
.L sec ) gull,) (mrem)
(mremy
-yr , (yr ) (
sec pC1 I
B.7-14
' oDCM Rev. 8 8688R
-Tvy r- m arr-+fT-^^PS"- ****-z'am- - - - e- o- - +* --
Eq 3-8 is rewritten in the form:
O gg - EUO
- 0FG gco (3-5)
Qg (mrem) ( ) (pC1) (mrem-sec) yr sec pC1-yr where
- 3.154E+07 0FG gco (7-13)
DFGjco (mrem-sec) , (sec) (mrem) pCl-yr yr pCi In the case of the dose rate conversion factor (DFGgen), the dose conversion factors for iodine and particulate exposure pathways (DFGico) are derived
- with the Shielding Factor (SF) for ground plane exposure set equal to 1.0.
For accumulated doses over extended periods, the DFGjeg are calculated with SF - 0.7, as referenced in Regulatory Guide 1.109.
The selection of critical receptor, outlined in Section 7.3 is inherent in Method I, as are the maximum expected off-site atmospheric dispersion factors.
In accordance with the Basis Statement 3/4.11.2.1 in NUREG-0472, and the' base's section for the-orv an-dose rate limit given for Technical
-Specification 3.11.2.1, a Method II dose rate calculation, for compliance purposes, can be based on restricting the inhalation pathway to a child's thyroid to less than or equal to 1,500 mrem /yr. Concurrent meteorology with time of release may also be used to assess compliance for a Method II l
calculation.
S 7.2.4 - Gamma-Dose to Air Frem Noble Gases This section serves: (1)'to document the development and conservative nature of Method I equations to provide background information to Method I
- B.7-15 oDcn Rev. 8 8688R.
l
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 3.11.2.1 which limits off-site gamma air dose from gaseous effluents has been met for releases over appropriate periods. This Technical Specification is based on the objective in 10CFR50, Appendix 1, Subsection B.1, which limits the estimated gamma air dose in off-site unrestricted areas.
For any noble gas release, in any period, the increment in dose is #
taken from Equations B-4 and B-5 of Regulatory Guide 1.109 with the added assumption that Dfinite=OD/QF/(X/QD OFY j (7_14)
AD = 3.17E+04 [X/Q)Y Q ar 1 3
(mrad) - ( -[r)(sec/m)
(C1) ( *y )
where: -
3.17E+04 - Number of pC1 per Cl divided by the number of seconds per year.
[X/Q]Y - Maximum off-site long-term average gamma atmospheric dispersion factor for the primary vent stack release point.
3^
3
- 8.5E-07 (sec/m )
Q-9 - Number of curies o_f noble gas "1"_ released.
. Gamma air dose factor for a uniform semi-infinite cloud of DF{
radionuclide "1".
which leads to:
- (3-5)
D - 2.7E-08
- EL(R) Qg DF{
ar i i
f B.7-16 oDCM Rev. 8 l
8688R
_ ,.. _ - . _ _ _ _ . _ . _ _ . . _ _ _ . . _ _ _ _ _ _ - . . _ _ . . . _ . - _ _ . . . . ~ _
3 (mrad) (pCl-yr ) ( -
) ( Cl) (mrad-m pC1-yr )
3 pCl-m
- As done above, the EL(R) correction factor has been added to allow for-the determination of dose linpacts from ground level release points utilizing the same dose equation as used for the primary vent _ stack.
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/Qf rather than use the site's long-term average o meteorological' dispersion-values.
7.2.5 Beta 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 Technical Specification 3.11.2.1, _
which limits off-site beta air dose from gaseous effluents, has been met for l-releases over appropriate' periods. This Technical Specification is based on the_ objective'in_10CFR50, Appendix I, Subsection B.1, which limits the j
. estimated beta' air dose in off-site unrestricted area locations.
I f-i For any noble gas release, in any period, the increment in dose is taken from Equations B-4 and B-5 of Regulatory Guide 1.109:
0 (7-15) 0F f 60 fir - 3.17E-02 X/Q 1 Qg 3
I
'(mrad) = (pCl-yr )_ gg) ( Cl) (mrad pCi-yrin )
pCl-sec m 3
B.7-17 ODc:-: Rev. 8 8688R
,-3-,--. -m --.w- +._ .---,----.~mm.a.-
. -.-,a--,- - - - , _ ,-e- .-w.
e - - . . . .- ~ ~ y v ,, r,-
+
where: Off-Betaairdosefactorsfora'uniformsemi-infinitecloudof )
radionuclide "1". .l
~
substituting X/Q = Maximum off-site long-term average undepleted atmospheric dispersion factor for the primary vent stack release point.
- 8.2E-07 sec/m3 ,
l l
We have (3-7)
Ofir
= 2.6E-08
- EL(R)
- Qg Off 1
(mrad) = (pCI- )( ) ,( Ci) ( )
pCl-m As done above, the EL(R) correction factor has been added to allow for the determination of dose impacts from ground level release points utilizing the same dose equation as used for the primary vent stack.
17.2.6 Dose to Critical Organ From Iodines, Tritium and Particulates With Half-Lives-Greater-Than Eloht 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 off-site organ dose from 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 II C.
Technical Specification 3.11.4 is based on Environmental Standards for Uranium L
l-B.7-18 oDcM Rev. B 8688R' ,
' ' *Viv' w w w w n , .,wm,. ,,g,,.
,. . - . - - . . _ . -- - -_. - ..- - .~. - .-.. -. - - - - . - - - .
-- 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-i_n' gaseous effluent contribution.
Hethod I was developed such that "the acttal exposure of an individual ... is unlikely to be substantially underestimated" (10CFR50, f 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 II allows that actual individuals, associated with
- identifiable exposure pathways, be taken into account for any given release. #
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.
First, the dose The steps performed in the Method I derivation follow.
impact to the critical receptor [in the form of dose factors DFG 1co (mrem /pC1)] for' a unit activity release of each todine, tritium, and
-particulate radionuclide with half lives greater-.than eight days to gaseous effluents was derived.- Six exposure pathways (ground plane, inhalation, stored vegetables, leafy vegetables, milk, and meat ingestion) were assumed to exist at the. site boundary (not over water or marsh areas) which exhibited the highest long-term X/Q. Doses were then calculated to six organs (bone, liver, kidney, lung, GI-LLI, and thyroid), as well as for_the whole body and skin for four age groups (adult, teenager, child, and infant) due to the-seven-combined-exposure pathways. For each radionuclide, the highest-dose per unit activity release for any organ (or whole body) and age group was then selected to The base case, or Method I
.become_the-Method I site-specific dose factors.
analy. sis,,uses the general equations methods,_. data, and assumptions in Regulatory Guide _1.109 (Equation C-2 for doses resulting from direct exposure
'to contaminated ground plane; Equation C-4 for doses associated with inhalation-of'all radionuclides to different organs of Individtals of
(
different age-groups; and-Equation C-13 for doses to organs of individuals'in l
different age groups resulting from ingestion of radionuclic'es in produce,
- B.7-19 oDCM Rev. 8 8688R ,
e- n ,,wn,.my-.,- - - , - . . c.,,-,v,,-w,--e-ww., ~,.ps,,,--., .- ,~,ag,,-.s,,,w..,,n,,,,, . . - . , , , ,,,n.g. ...,, .,n-,,, --,,.m,..,.,,,.,m-,,..-, .n y .n. , , - - , . , g
- - - . - - - . . . - _ - - - . - - - . _ . . . . - - . - . - . . - . . . . . ~ . - . .
milk,- meat, and leafy vegetables in Reference A). Tables B 7-2 and B.7-3 outline human consumption and environmental parameters used in the analysis. '
It'15 conservatively assumed that the critical receptor lives et the " maximum off-site' atmospheric dispersion factor location" as defined in Section 7.3.
The resulting site-specific dose factors 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 B.1-12. Appendix A provides an example of the development of Method I gaseous dose conversion factor for site-specific conditions at <
Seabrook.
For any lodine, tritium, and particulate gas release, during any period, the increment in dose from radionuclide "1" is:
- U-W 60lco " 9 DFG3c3 1 is where DFG jeg is the critical dose factor for radionuclide "1" and Qg the activity of radionuclide "1" released in microcuries.
7.2.7- Special Receptor Gaseous Release Dose Calculations Technical Specification 6.8.1.4 requires that the doses to individuals involved in recreational activities within the site boundary are to be
-determined and reported in the annual Semiannual 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. The special receptor XQs are given in-Table.B.7-S.
7.2.7.1 Total Body Dose Rate Frem Noble' Gases Method I was derived from Regulatory Guide 1.109 as follows:
r B.7-20 ODCM Rev. 8 l- 8688R AAi: A-n.., ,,;.__ _ ,
l l
~
OI0 i l btb - IE+06 [X/Q)Y 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 locations during the year. There are two special receptor locations on-site.
The " Rocks" is a boat landing area which provides access to Browns River and Hampton Harbor. The Seabrook FSAR, Chaoter 2.1, indicates little boating activity in either Browns River or nearby Hunts Island Creek has been observed upon which to determine maximum or conservative usage factors for this on-site shoreline location. As a result, a default value for shoreline activity as -
provided in Regulatory Guide 1.109, Table E-5, for maximum individuals was utilized for determining the " Rocks" occupancy factor. The 67 hours7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br /> / year corresponds to the usage factor for a teenager involved in shoreline recreation. This is the highest usage factor of all four age groups listed in Regulatory Guide 1.109, and has been used in the 00CM to reflect the maximum usage level irrespective of age.
Regulatory Guide 1.109 does not provide a maximum individual usage factor for activities similar to those which would be associated with the Seabrook Education Center. Therefore, the usage factor used in the 00CM for the Education Center reflects the observed usage patterns of visitors to the facility. Individuals in the public who walk in to look at the exhibits on display and pick up available information stay approximately 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> each.
Tour groups who schedule visits to the facility stay approximately 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.
For conservatism, it was assumed that an individual in a tour group would return five times in a year, and stay 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> on each visit. These assumptions, when multiplied together, provide the occupancy factor of 12.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> / year used in the 00CM for public activities asscciated witn the Educatien Center.
~
B.7-21 oDCM Rev. 8 8688R _
. l l
For the Education Center, and the " Rocks", the Ofs are:
}
5 s Education _ Center.- h j ,/p - 0.0014 h
The " Rocks" - = 0.0076 60 r substituting (X/Q3Y - 1.lE-06 sec/m3 (Education Center) for primary vent stack ,
releases.
- 5.0E-06 sec/m3 (The " Rocks") for primary vent stack releases.
multiplying by OF - 0.0014 (Education Center)
- 0.0076 (The " Rocks") ,
and adding the release point correction factor EL(R) gives:
(mrem /yr) (7-17) btbE - 010015
- EL(R)1
- hg 0FB g (mrem /yr) (7-18) ,
'hg DFB, htbR - 0.038
- EL(R)i * '
t where:
btbE,andbtbR - Total body dose rates due to noble gases to an individual:at the Education Center and the " Rocks" (recreational site), respectively.
(l}Taken_ from Seabrook Station Technical Specifications (Figure 5,1-1).
- B.7-22 ODCM Rev. 8 ;
8688R -
)
hi - Defined previously. .
I DFB;
- Defined previously.
EL(R) .
Defined previously.
7.2.7.2' Skin Dose Rate From Noble Gases Method I was derived from Equation (7-8): ,
(~'
hg DF{ +
bskin - 1.11 lE+06 [X/Q]Y 1 1 DFS'g lE+06 X/Q. .1 substituting.
[X/Q)Y - 1.lE-06 sec/m3 -(Education Center) for primary vent stack releases.
- 5.0E-06 sec/m3 (The " Rocks") for primary vent stack releases.
X/0 = 1.6E-06 sec/m3 (Education Center) for primary vent stack releases.
= 1.7E-05 sec/m3 (The " Rocks") for primary vent stack releases.
multiplylng by-0F.= 0.0014 (Education Center)
= 0.0076 (The " Rocks")
1 l-B.7-23 ODCM Rev. 8 8688R _
_ _ . _ _ _ _ . . -_ _ . . _ _ . _ - . m-._ . _ . - _ __. .._ . _ _ . .
~
gives.
bskinE_. 0.0014 'h g (1.22 DF} + 1.60 DFS g] (mrem /yr) hg [5.55 0FJ + 17.0 0FS g] (mrem /yr) bskinR = 0.0076 and with the addition of the release point correction factor EL(R), the equations can be written: ,
hg DF 1E (mrem /yr) bskinE - 0.0014
- EL(R) bskinR = 0.0076
- EL(R) .hg DF5R-(mrem /yr) where:
skinE andbskinR = The skin dose rate due to noble gases to an b
Individual at the Education Center and the " Rocks,-
l respectively, hj - Defined previously.
'EL(R) = Defined previously.
"f" DF'iE and DF'gg - The. combined skin dose factors for radionuclide for the Education Center, and the " Rocks",
respectively (see Table B.1-13).
I L
t t
B,7-24 oDcM Rev. 8 8688R
- _ . . _ - _ - - - _ ~
- 7.2.7.3 Critical Organ Dose Rate From lodines, Tritium and Particulates With
-Half-Lives Greater Than Eight Days The equations for be,are derived in the same manner as in Section 7.'2.2, except that the occupancy factors are also included. Therefore:
( -21) bcoE - 0.0014
- EL(R)
- hg 0FGjcoE(mrem /yr) begg - 0.0076
- EU R) hg 0FG{coR (mrem /yr) (~
where:
baoE ""dcoR - The critical organ dose rates to an individual at the Education Center and the " Rocks", respectively.
-h j - =_ Defined previously.
EL(R) - Defined previously.
DF'icoE and 0F'icoR - The critical organ dose rate factors for radionuclide "1" for the Education Center and the " Rocks," respectively-(see Table B.1-14).
, 7.2.7.4 Gamma-Dose to Air From Noble Gases Method I was derived from Equation (7-14):
(7-I4)
Oj Dff D h = 3.17E+04 (X/Q]Y
~
B.7-25
- ODCM Rev. 8 8688R
. - - . . . - - =. . .
-substituting
[X/QlT =.1,l'E-06 sec/m3 (Education Center) for primary vent stack releases.
- 5,0E-06 sec/m3 (The " Rocks") for primary vent stack releases, multiplying by 0F = 0,0014 (Education Center) 4
- 0.0076 (The " Rocks")
and IE-06 C1/pCl, plus adding the-rele,ase point correction factor EL(R) gives Qg DF
( -23)
DalrE - 4.88E-11
- EL(R) * (mrad)-
1 Qg_DF{ (7-24}
D trR = 1,20E-09
- EL(R) * (mrad) 1 where:
0 ire andD{lrR = The gamma air doses to an individual at the Education Center and the " Rocks," respectively.
LQ j
--Total activity-(pCl) released to the atmosphere via the station vents of each radionuclide "1".
OFj,DF{,andEL(R)=Oefinedpreviously.
~
B.7-26 oDCM Rev, 8 8688R . ,
i * - - - - - - - - - - - _ _ . _ - _ _ _ - _ _ _ _ - - _ _ _ _ _ - - _ - _ _ _ _ _
I
.7.2.7.5 Beta Dose-to Air From Noble Gases Method I'was derived from Equation (7-15): ,
l G-15) 6 0DFf 1
0 air - 3.17E+04 X/Q i substituting X/0 - 1.6E-06 sec/m3 (Education Center) for primary vent stack releases.
i
- 1.7E-05 sec/m3 (The " Rocks") for primary vent stack releases.
-multiplying by .
Of = 0.0014 (Education Center)
= 0.0076 (The " Rocks")
and IE-06 C1/pCl, plus adding the. release point correction factor EL(R) gives Og Off (7-25)
D 1rE - 7.1E-11
- EL(R) (mrad) 1
- ~
4.1E-09
- EL(R) Qg DFf (mrad)-
D 1rR 1 B.7-27 oDCM Rev. 8 8688R l
where:
0 trE and OfirR
- ihe beta air doses to an individual at the Education Center and the " Rocks " respectively.
Qg - Total activity (pCl) released to the atmosphere via the station vents of eacn radienuclide "1".
DF,Off,andEL(R) . Defined previously.
7.2.7.6 Critical Organ Dose f ,m lodines. Tritium and Parti _culates_Hith Half-Lives Great g_Than Eight Days Method I was derived in the same manner as Equation (3-8):
D co
- Oi O lco (3-8) i multiplying by:
Of - 0.00 ' Education Center)
- 0.0076 (The " Rocks")
und IE-06 Ci/pCl; plus substituting the lo;ation specific DFGs gives Q DFG ( *" * ' ( ~ '
DcoE - 0. W 4
- EL(R)
- g icoE i
Qg 0FG icoR (*"* '
Degg . 0.0076
- EL(R) i I
I,
)
. B.7-28 ODCH Rev. 8 8688R
where:
i O and D egg - The critical organ doses of an individual at the coE Education Center and the "Rockt," rispectively.
The total activity (pCl) released to the Qg atnesphere of radionuclide "1".
DFG and DFG gggq - The critical organ dose factors (mrem /pC1) for the 1coE Education Center and the " Rocks," respectively for each radionuclide "1". The factors represent the age group and organ with the largest dose f actor (see Table B.1-14).
EL(R) - Defined previously.
The special receptor equations can be applied under the following conditions (otherwise, justify Method I or consider Methal II):
- 1. Normal operati.,s (nonemergency 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.
l l
B.7-29 oDCH Rev 8 B688R _
r{ !l!t t[j .i { f ;If !f !f[ j>()i[i t ; I[(! Ii[lt!!
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ri uv f t r r o
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o uc S p E Eu p l i si oiG iG i e ui cu s l u a t at t t t n ld a l pP d m cP c n c . c . ci oi l id ro l
l n
a l o l i a a e ag ag ad sm u g
oro o n r n rh re re ro bu AP STorSCt H A F oF wFV FV FI gr e R AH 8 R -
8
- 6 V BF H F P S G L I 8
T Q F' F F F F H Y P T TT
- i 1!* 1 j j l jl
- l
TABLE B.7-2 (Continued)
Notes:
(1) For Method II dose / dose rate analyses cf identified radioactivity releases of less that one year, the soll exposure time far that release may be set at 8760 hours0.101 days <br />2.433 hours <br />0.0145 weeks <br />0.00333 months <br /> (1 year) for all pathways.
(2) For Method II dose / dose rate analyses performed for releases occurring during the first or fourth calendar For the second quarters, the fraction of time animals are asse.ned to be on pasttire is zero (nongrowing FP season).
may also be adjusted and third calendar quarters, the fraction of time on pasture (FP) will be set at 1.0.
for specific farm locations if this information is so identified cnd reported as part of the land use census.
.. for specific (3) for Eathod II analyses, the fraction of pasture feed while on pasture may be set to less th.- . 1 farm locations if this information is so identified and reported.as part of the land use cer. !
i 3 l (4) For all Method II analyses, an absolute htmidity value equal to 5.6 (gm/m ) shall be used to reflect conditions In the Northeast (
Reference:
Health Physics Journal, Vol. 39 (August), 1980; Page 318-320. Pergammon Press).
1 B.7-31 cocM Rev. s 8688R
, L
unimill TABLE B.7-3 Usage Factors for Various Gaseous Pathways at Seabrock _ Station (frcm Reference A, Table E-5)*
Maximum Receptor:
/,g e Leafy Vegetables Vegetables Milk Meat Inhalation Group _
(kglyr) (kg/yr) (1/yr) (kg/yr) (m3 /yr) <
64.00 310.00 110.00 8000.00 Adult 520.00 42,00 400.00 65.00 8000.00 Teen 630.00 26.00 330.00 41.00 3700.00 Chlid 520.00 '
0.00 330.00 0.00 1400.00 Infant 0.00 The " Rocks" and Education Center:
Age Leafy Vegetables Vjgetables Milk Meat inhalation GrouJ (kg/yr) (kglyr) (ilyr) (kglyr) (m3 /yr) 0.00 0.00 0.00 8000.0 Adult 0.00 0.00 0.00 0.00 8000.0 Teen 0.00 0.00 0.00 0.00 3700.0 Child 0.00 0.00 0 00 0.00 1400.0 Infant 0.00
- Regulatory Guide 1.109 B.7-32 ODcM Rev. 8 86S8R
-- _ . _ _ _ .._ _ ._.___._ _ _ _ .- _ ~_. - _ _
h 7.3 Receptor Points and_ Ave g e Atmospheric Olspersion factors for l Important Exposure Pathways ;
The gasecus effluent dose equations (Method I) have been simplified by assuming an individual whose behavior and living habits inevitably lead to a higher dose than anyone else. The following exposure pathways to gaseous effluents listed in Regulatory Guide 1.109 (Reference A) have been considered:
- 1. Direct exposure to contaminated air; 9
- 2. Direct exposure to contaminated ground;
- 3. Inhalation of air; l
- 4. Ingestion of-vegetables; i
S. Ingestion of goat's milk; and i
- 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 presents 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.
B.7-33 l-opcM Rev. 8 86SSR -
- . . - - - - _ _ . - . - _ . _ _ _ - - - . _ - - - _ - - - . - - _ - . _ _ ~ - .- -
This point is the west sector, 974 meters from the center of the reactor units for undepleted, depleted, and gamma X/Q calculations, and the northwest section, 914 meters for calculations with 0/0 the dispersion parameter.
The site boundary in the NNE through SE sectors is Jocated over tidal marsh (e.g.. over water), and consequently are not used as locations for determining maximum off-site receptors (Reference NUREG 0133).
Two other locations (on-site) were analyzed for direct ground plane t exposure and inhalation only. They are the " Rocks" (recreational site) and the Education Center shown.on Figure 5.1-1 of the Technical Specifications. ,
e f
I i
i I
l B.7-34 oDcn Rev. 8 .)
8688R i
w+-----, ~ , , . ...,<[.<,s.
,. .,.--,,-,e~..,,.,. + ,.,mc...._,__,.,-.,, .,~,.w.,_ . . ,, . . . .,.m.mm.....,._,,y. . , . - . _ , . . . . , ..,,y,.4,e.-
7.3.2 Seab_ rock Stattu Atmospheric Olspersion Model The time average atmospheric dispersion factors fo'r use in both Method I and Method 11 are computed for routine releases using the AEOLUS-2
- Computer Code (Reference B).
AEOLUS-2 produces the following average atmospheric dispersion factors for each location:
- 1. Undepleted X/Q dispersion factors for evaluating ground level concentrations of noble gases;
- 2. Depleted X/Q dispersion factors for evaluating ground level concentrations of iodines and particulates;
- 3. Gamma X/Q dispersion factor's for evaluating gamma dose rates from a
-sector averaged finite noble gas clouu (multiple energy undepleted source); and
- 4. 0/Q_ deposition factors for evaluating dry deposition of elemental radiolodines and other particulates.
Gamma dose rate is calculated throughout this 00CM using the finite cloud model presented in " Meteorology and Atomic Energy - 1968" (Reference E, Section 7-5.2.5. That model is implemented through the definition of an Y
effective gamma atmospheric dispersion factor, CX/Q ] (Reference B, Section 6), and the replacement of X/Q in W inite cloud dose equations by the
[X/QY ).
7.3.3 Average Atmospheric Dispersion factors for'Reccetrs The calculation of Method I and Method II atmospheric diffusion factors (undepleted CHI /Q, depleted CHI /Q, 0/Q,-and gamma CHI /Q values) utilize a methodology generally consistent with US NRC Regulatory Guide 1.111 (Revision 1) criteria and the methodology for calculating routine release diffusion factors as represented by the XOQDOQ computer code (NUREG/CR-2919).-
B.7-35
~
oDCM Rev. 8 8688R l
gh6km .
i i
The primary vent stack is treated as a " mixed-mode" release, as defined in
- Regulatory Guide 1.111. Effluents are considered to be part-time ground level /part-time elevated releases depending on the ratio of the primary vent stack effluent exist velocity relative to the speed of the prevailing wind.
All other releate points (e.g., Turbine Building and Chemistry lab hoods) are considered ground-level releases.
In addition, Regulatory Guide 1.111 discusses the concept that constant !
mean wind direction models like AEOLUS-2 do not describe spatial and temporal l
variations in airflow such as the recirculation of airflow which can occur <
during prolonged periods of ct mspheric stagnation. For sites near large l l
bodies of water like Seabrook, the onset and decay of sea breeces can also results in airflow reversals and curved trajectories. Consequently, ,
Regulatory Guide 1.111 states that adjustments to constant mean wind direction model outputs may be necessary to account for such spatial and temporal L variations-in air flow trajectories. ' Recirculation correction factors have been applied to the diffusion factors. The recirculation correction factors >
used are compatible to the " default open tarrain" recirculation correction ,
factors used by the )TQDCQ computer code. .
The relative deposition rates, D/Q values, were_ derived using the relative deposition rate curves presented in Regulatory Guide 1.111 (Revision 1). These curves provide estimates of deposition rates as a function'of plume height, stability class, and plume travel distance.
Receptor Locations for ground-level releases, the downwind location of "The. Rocks" (244m NE/ENE) and the Ed Center (40Em SW) were taken as the distance from the nearest point on the Unit 1 Administrative Building / Turbine Building complex.
For the site boundary, the minimum distances from the nearest point on the Administration Building / Turbine-Building complex to the site boundary within a 45-degree sector centered on the ccmpass direction of interest as measured from FSAR Figure 2.1 4A were used (with the exception that the -
NNE-NE-ENE-E-ESE-SE site boundary sectors were not evaluated because of their over-water locations).
B.7-36 oDCH Rev. 8 8688R
-_x_ . . _ _ . _ _ _ . . _ . _ _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ . .,_,2,__ ,_ _
t!
For primary vent stack releases, the distances from the Unit 1 primary
, vent stack to "The Rocks" (244m NE) and the Ed Center (488w SW) as measured from'a recent site aerial photograph were used. For the site boundary, the minimum' distances from the Unit 1 primary vent stack to the site boundary within a 45-degree sector centered en the compass direction of interest as measured from FSAR Figure 2.1-4A were used (with the exception that the NNE-NE-ENE-E-ESE-SE site boundary sectors were not evaluated because of their over-water locations),
i Meteorological Data Bases for "The Rocks" and Ed Center receptors, the diffuslen factors j represent six-year averages during the time period January 1980 through December 1983 and January 1987 thrcugh December 1988 (with the exception that, l because of low data recovery, April 1979 and May 1979 were substituted for April 1980 and May 1980). For the site boundary receptors, both six-year average growing season (April through September) and year-round (January through December) diffusion factors were generated, with the higher of the two chosen to represent the site boundary.
The meteorological diffusion factor used in the development of the ODCM Method 1 dose models are summarized on Tables B.7-4 through B.7-6, t
B.7-37 oDCM Rev, 8 8688R _
._ . . _ , ._.2. _ ._ . . _ . . _ _ . _ _ _ . _ . . _ _ _ . _ _ _ . _ . . _ ,_,_, _ . , _ _. - _ . _ _ _ _
l i
4 TABl.E B.7-4 1: [
j Seabrook Station Dilution Factors
- t
- j. Primary Vent Stack I:
s *
!(
) Dose to !
Critical l l' Dose Rate to Individual Dose to Air Organ !
j Total Body Skin Critical Organ Gamma Beta Thyroid ,
i
~
X/Qdepleted(y) - -
7.5E-07 - -
7.5E-07 m l 2 i X/Q undepleted (5'C) -
8.2E-07 - -
8.2E-07 -
5 i,
1.5E-08** 1.5E-08 D/Q (h)
- m i-X/QY (Se )' 8.5E-07 8.5E-07 -
8.5E-07 - -
3
- -m ,
i . j i i j-
- West site boundary. 974 meters from Containment Building f
['; ** Northwest site boundary, 914 meters from Containment Building i i
l l
r I !
4 l B.7-38 8688R ODCM Rev. 8 i t
i i
o.
I:
)' r 1
TABl.E B.7-5 i
1 Seabrook Station Dilution Factors for Special (On-Site) Receptors ;
i Primary Vent Stack
. Dose to Critical !'
Dose Rate to Individual Dose to Air Organ Total Body. Skin Critical Organ Gamma Beta Thyroid Education Center:
(SH - 488 meters).. !
s .X/Q depleted ( )' - -
1.5E-06 - -
1.5E-06' m i t
X/Q undepleted (S"C) -
1 6E-06 - -
- 1. 6E-06 -
m3 l
'D/0 ( ) - 2.7E-08 -
f.
- m X/0Y (Se ) 1.1 -06 1.1E-06 - 1.lE-06' - -
3 m
The " Rocks" j
. (E!1E - 244 meters)
X/Q depleted (5'3) - -
1.6E-05 - -
1.6E-05 m ,
X/Q undepleted (S'3) - 1.7E-05 - -
1.7E-05 - ,
[! '
m ;
D/0 ( ) - -
1.lE-07 - - -
i
- i I
j X/0Y (5_e ) 5.0E-06 5.0E-06 -
5.0E-06 - -
l 3
m '
t 0- oDCM Rev. 8 j 8688R k
L. - . .. .
t
TABLE B.7-6 Seabrock Station Atmoy heric Diffusion a_nd Deposition Factors Ground-Level ReTease Pathway RECEPT 0R (a) 01, fusion Factor lhe Rocks Ed Center Site Ecundarv 2.3 x 10-5 1,ox 10-5 Undepleted CHI /Q, sec/m3 1.6 x 10-4 (244m ENE) (406m SW) (823m W) 1.5 x 10-4 2.1 x 10-5 g,4 x 10-6 Depleted CHI /Q, sec/m3 (244m ENE) (406m SW) (823m W)
D/Q, m-2 5.1 x 10-7 1.0 x 10-7 5.1 x 10-8 (244m ENE) (406m SW) (823m W) 2.6 x 10-5 5.3 x 10-6 3,4 x 10-6 Gamma CHI /Q, sec/m3 (244m ENE) (406m SW) (823m W) f (a) The highest' site beundary diffusion and deposition factors occurred during the April through September growing season. Note that for the primary vent Stack release pathway, none of the off-site receptor diffusion and deposition f actors (located at 0.25-mile increments beyond the site boundary) exceeded the site boundary diffusion and deposition factors.
B.7-40 ODCM Rev. 8 8688R _
l l
Substituting the right half of Equation 8-4 for Cdl in Equation 8-3 and solving for F /I yields the minimum dilution factor needed to comply with d m Equation 8-3:
OFmin i m (9Em) (gCl-m1) gpm mi-pCl where:
F Flow rate out of discharge tunnel (gpm) d F, - Flow rate past monitor,(gpm)
C ,g
Activi,ty concentration'of radionuclide "1" in mixture at the monitor (pCl/ml)
MPCj
- MPC for radionuclide "i" from 10CFR20, Appendix B, Table II, Column 2 (pC1/ml)
If F dF ,is less than DFmin, then the tank may not be discharged until either F d r F ,or both are adjusted such that:
F d
DF (8-5) 7-m 1 min (gpm) ,
Usually FdF m 5 greater than OFmin (i.e., there is more dilution than necessary to comply with Equation 8-3). The response of the liquid waste test tank monitor at the setpoint is therefore:
S C ng (8-6)
R setpoint " I l 0 min 1
i pCi ,( ) () ( as-ml) (pg)
- ml pCl ml
~
B.8-3 oDCM Rev. 4 8689R
where f; 15 equal to the fraction of the total contribution of 14PC at the discharge point to the environment to be associated with the test tank 1
effluent pathway, such that the total sum of the fractions for the four liquid discharge pathways is equal to or less than one (f3+f2+I+I 3 4 I II' The monitoring system is designed to incorporate the detector efficiency, 5 3, into its software. This results in an automatic readout in pCi/cc or pC1/ml for the monitor response. Since this procedure for converting cps to pC1/ml is inherently done by the system software, the monitor response setpoint can be calculated in terms of the total waste test ,
tank activity concentration in pC1/ml determined by the laboratory analysis.
Tierefore, the setpoint calculation for the liquid waste test tank is:
t r--
(5-1) ;
N setpoint
- I l0 b C,'g ;
min !
(" ) ( )( )
(P-h) :
8.2 Basis for the Plant Vent Wide Range Gas 14cnitor Setpoints The setpoints of the plant vent, wide range gas monitors must ensure that Technical Specification-3.11.2.1.a is not ext.eeded. Sections 3.4 and 3.5 show that Equations 3-3 and 3-4 are acceptable methods for determining compilance with that Technical Specification. Which equation (i.e., dose to total body or skin) i s more limiting depends on the noble gas mixture.
-Therefore, each equation must be considered separately. The derivations of W tions 5-5 and 5-6 begin with the general equation for th, response R of a radiation monitor:
(8-7)- ;
R = S gg C,g (cpm) - (C )( )
Cm ,
-- .B.8-4 oDCM Rev. 8 8689R ,
-w-.,-,.e..a w %,e.r_,.E . - w -.w, .-..-%,,,y ,_-.mm-%,c .c ,.-y .i%,,,gn-,,,,,,,,,,_,s,,
m.c , ,w y nn . my r g e, y g.-,p.p ,. %,c w w. -w w m,me wp.-ww 3,
APPENDIX A DOSE CONVERSION FACTORS A-1 ODCM Rev. 8 6
_ _ _ _ _ _ _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ - . ...=_J
._ _ - - ~ -..___-.-_ _ _ -
APPDIDIX A Dose Conversion Factors .
I. Liquid Pathways - Seabrook Sito Specific DCF's l
resulting from The models used to assess doses '
offluents into liquids is derived from Appendix A ef Reg.
Guide 1.109. Since Seabrook is a salt water site, the .i assumed pathways of exposure taken from Reg Guide 1.109 are i Aquatic foods - fish; Aquatic foods -invertebratest and !
dose from shoreline deposits (direct dose). No drinking water or irrigation pathways exist because of the salt water environment. In addition, exposures resulting from i
. I boating and swimming activities have been included for key radionuclides even though Reg. Guide 1.109 identifies these '
pathways as not contributing any significant contribution to the total dose, and therefore dcas not provido dose equations for them. For co=pleteness, the swiraing and boating pathways have been includes using the dose models from the 1ERMES code -(IEDL-TME-71-168, Dec. 1971), section G, Water Immersion.
The Method I dose conversion factors are derived by ,
calculating the dose impact to individuals via the site
. specific pathways for a unit activity release (1 curie per nuclide). For each pathway, doses by radienuclide are calculated for each of the 7 organs (including whole body) for each of the four age groups (adult, teen, child,isand then infant) . The Method I dose factor for each nuclide selected by taking the highest factor for any organ in any of the age groups for all the exposure pathways combined.
The list of dose factors in the ODCM then represents a combination of-different limiting organs and age groups which, when used to calculate a dose impact from a mix of radionuclides released in liquid effluents, gives a conservative dose since it combines the exposure to different. organs and age groups as if there was a single critical organ-age group.
As an example of how the liquid dose conversion factors are developed, the following calculation for co-60 is shown.
The critical organ / age group is selected based on the full assessment of all organs and age groups.
Factor for fish Ingestion The general equation for ingestion doses in RG 1.109 is eq A-3.
U 'M -1 t ap p p
' 1119.7* -
QB D c F
i ip alpj The full assessment for the ODCM dose f actors indicated that for i = co-60, the maximum dose (nrem/yr) is to the GI-LLI of an adult as the target organ and age group, therefore: ODCM Rev. 8 A-2
U := 21 kg/yr adult usage factor for fich ap M := 0.1 mixing ratio for near field dilution p provided by submerged multiport diffuser.
F := 918 cu. ft./sec effluent flow rate for circulating water system Q := 1.0 curies / year relased of C0-60 i assumed l
B := 100 equilibrium bicaccumulation factor ip for co-60 in salt water fish, in liters /kg
-5 D := 4.02 10 nrem/pci, adult GI-LLI alpj ingestion dose factor from RG-1.109, table E-11.
-5 1 := 1.501+10 decay constant for CO-60 in 1/ hrs.
t := '4 time between release and p ingestion, in hrs.
1119.7 is the factor to convert from Ci/yr per f t3/sce to pci/ liter. note .
that RG 1.109 uses 1100 as a rounded approximation.
Therefore the dose from fish to adult GI-LLI is (mrem /yr) :
U M -1 t ap p p B D e = 0.0103 1119.7- -
Q F i ip alpj Factor for invertabrate ingestion:
Next, the dose from invertebrates to the adult GI-LLI is given by the same general equation but with the following variables changed:
as iii n e i esu mine mmim a
l l
l U := 5 kg/yr usage factor ap B := 1000 1/kg bicaccumulation factor ip all other variables the same as above therefore the dose frcm invertebrates is (nrem/yr):
U M -1 t ;
ap p p
-Q D D o a 0.0245 1119.7-F i ip alpj Factor for shoreline direct-dose:
The general equation for direct dose frca shoreline deposits is taken frcm equation A-7 in RG-1.109 as (mrom/yr):
W ~1 t -1 t U H b ap p p Q TD e -
~1-e '
111970-F 1 alpj i
It is assumed that all internal organ doses also receive exposure from direct external sources, therefore each organ dose due to ingestion must have and exte nal component added. For the above equation, the site specific variables for an adult exposure to a 1 curio per year release of co-60 are:
U := 334 hrs / year usage factor used for ap assumed shoreline activities at Seabrook.
M := .1 mixing ratio for near field p dilution provided by the subccrged multiport diffuser and assume to be extended to the beach continuously.
W := 0.5 shorevidth factor for ocean sites, dimensionless A-4 ODCH Rev. 8
- _ - _ _ - _ _ _ _ _ ___ _ _ _ _ _ __ _ - - - - - - - - - ~ - . - . _ . _ _ _ _ . . _ _ , _ _ _ _ _
4 3
T = 1.923 10 radioactivo half life in days for CO-60 .
-8 D t= 1.70 10 done factor for CO-60 due alpj to deposits in se diments, ,
r units of (mram/hr)/(pci/m2) t =-O. transit time to point of p exposure, hrs t = 131400 period that sediment is b
assumed to be exposed to water contamination for 16ng term buildup, set at 15 ,
< l years for Method I DCF's Q := 1.0 curies per year, Co-60 i assumed 111970 conversion factor to convert
'p(Ci/yr)/(f t3/sec) toci/ liter and account for
,the proporcionality constant used in sediment model Therefore the dose to the whole body and each organ due to direct exposure to the shoreline (mren/yr) ins
-X t -1 t ,
U H W b ap p p
= 0.0573
-Q TD e -
1-e '
111970 - ~
F i alpj Direct dose due to Swimming:
The dose due to immersion in water (swimming) is.taken from the HERMES computer code. The original ODCM calculation was based on some preliminary dilution assumptions which gave a near field Forprompt single dilution unit factor for the multiport diffuser of 8.
operation with both service water and circulating water flow (412,000 gpm), a value on 10 is more realistic.
This surface area of-the plume is restricted to a small area over the diffuser and does not touch the shoreline approx. 1 mile away. Since'the over all impact from swi= ming is small when compared to the.other exposure pathways, the original conservatism on dilution are kept here.
l' ODCH Rev. 8 A-5 1: .
1.
- - --- _. *i _. ,, .. ., _ _ _ _
~
. 7 The dose from swimming is given by the following equations i
U 12 p 1.0 10 - - -
Q DF (mrom/yr)
F ' i in a i where:
U := 45 hrs /yr, usage factor for ,
p swimming for maximum age <
group (tecn) from HERFIS.
11 F := 6.56*10 liters /yr, estimated annual a dilution effluent flow in multiport diffuser Q := 1.0 Curies /yr, assumed release i rate of nuclide 1.
-6 DF := 4.6 10 mrem-liters per hrs-pci, dose im factor for Co-50 for water immersion tahr.n from IER!ES.
12 1.0 10 constant for pCi/Ci Therefore the swimming dose for a 1 curie release of co-60 is (mrem /yr):
M 12 p -5 1.0 10 U *
-Q DF = 3.155 10 p F i im a
As can be seen, the contribution of the swimming dose is only about one 30000ths of the total of the RG 1.109 pathways, and can be ignored in the case of co-60. Similarly, the boating dose as given in
.- HERMES is taken as half of the swimming dose,(and A-6 ODCM Rev. 8
i corrected for change in usage assumptions). The resulting dose is'found to be less than the swimming dose and can also therefore be discounted in this case.
Total liquid Pathway dose:
The sum of the above 11guld pathway doses can now bc '
added to give the total maximum individual dose to the critical organ (adult-GI-LLI) for Co-60. This ;
gives 0.0103 + 0.0245 + 0.0573 = 0.0921 mrem /yr Since the internal doses'given by the RG-1.109 methods actually are 50 yr dose commitments '
resulting from onc year exposure to the quantity of activity araumed to be released into the water, and the direct dose represents the dose received for the period assumed to be exposed to the pathway, and the activity release was taken as a unit quantity (i.e. Q= 1 Ci), the above total liquid pathway dose can be stated as site specific committed dose factor in mrem /Ci released. For Method I in the ODCM, the critical organ dose factor is seen to be 0.0921 mrem /ci, as shown above. The value reported on Table B.1-11 (9.22 E-08 mrem /uci) was generated by a computational routine which gives rise to the round-off difference between it and the above example. The whole body site specific dose factor for the CDCM was calculated in the same way treating the whole body as a separate organ.
9
- A-7 ODCH Rev. 8
- i--r -+v - , , . , , . _ , .
II. Gaseous Pathways - Seabrook site Specific DCF's The models used to' assess doses resulting from gaseous effluents in the form of iodines, tritium, and particulates For Seabrook, are derived from Appendix C of Reg. Guide 1.109.
it is assumed that at the of f site location which exhibits minimum atmospheric dilution for plant releases the following )
exposure pathways exist: inhalation, ground pinne, ingestion of goats milk, meat, stored vegetables, and leafy vegetables.
The Method I dose and dose rate factors are derived by calculating the dose impact to all age group individuals via the site specific pathways for a unit activity release (1 curie per ,
nuclide). For each pathway, doses by nuclide are calculated for cach of 7 organs ( including the whole body) for each of the 4 age,,
groups. The Method I dose factor for each nuclide is then selected by taking the highest factor for any organ in any of the age groups for all exposure pathways combined. The list of dose factors in the ODOi then represents a combination of different ;
limiting organs and age groups which, when used to calculate the done impact from a mix of radionuclides released into the atmosphere, gives a conservative dose since it combines the exposure to different organs and age groups as if they were for all the same critical organ-age group. ,
As an example of how the gaseous particulate dose factors are developed, the following calculation for Mn-54 is shown. The !
critical organ / age group for Mn-54 was selected gaced on a full assessment of all organ and age group combinations. For elevated releases from the plant vent stack to the maximum site boundary (max. dose point due to meteorology), the critical organ and age group for Mn-54 was determined to be the GI-LLI for the adult.
PART At Inhalation Dose Contibution:
The general equations for inhalation doses in RG 1.109 are eg, c-3, and C-4 which together give:
3.17 10 R- -
Q DFA =D a ,Q,
' i ija ja i
Where for the case of Mn-54 releases, the variabics above are defined as:
4 i
3.17*10 is the number of pCi/Ci divided by the number of second per year-1 -
A-8 ODCM Rev. 8 I
- , - . . .. _.,_,_..,__-__._._-..;...._._,_._..-. , . _ _ . _ . . . . . _ , _ , _ _ . - , . _ , _ ,._._c,,_,_-,
R := 8000 the breathing *rato for aga group a o (adults) in n 3 /yr.
X - 7
- = 7.5 10 the long torn average depleted Q atmospheric dispersion factor, in sec/m*3, at the maximum exposure point off site (S.B.)
Q := 1 the release rate of nuclide i to the i atmosphere in C1/yr
-6 DFA := 9.67*10 the inhalation dose factor for lja nuclide 1 (Mn-54), organ j (GI-LLI) , t and age group a (adult) taken from' ,
RG 1.109, table E-7, in mrem /pci inhaled.
Therefore, the inhalation dose to the maximum potential off site individual is given ass ,
4 'X' 3.17 10 + R - -
-Q DFA = 0.00184 mrem /yr per C1 -i a ,0, 1 ija PART D Ground Plane Direct Dose Contribution:
The general equations for ground plane external direct dose in RG 1.109 are equations C-1 and C-2 which together give the dose DG ast
-1 t i b ,
12 "D' 1-e -
DFG 8760+1.0'10 +S - - -
Q -
ij F ,Q, i X i i
%ere for the case of Mn-54 releases, the variables in the above equation are defined as:-
A-9 ODCM Rev. 8 i
ww .4-, w w-r 4. - , -y- .m-,,.y..p._w..ra m., ,me.
i,%., -c e ..e2--,--. -- __,emm.,e,--...,.ry.,:.3~,-. ~,r-,---.,-4 .py iy. p. -e -ww,-e,y,,,,, ,r y y -v-w
12 1.0 10 is the number of pCi per Ci ,
S := 0.7 the shielding factor provided by i F- residential structures (dimensionless) ;
for use in calculation accumulated doses over time. Note that for determination of dose rate factors (i.e. Instantaneous dose rates) the shielding factor is set equal to 1.0, or in affect no credit for dose reduction is taken for determination of dose rates at points in time.
D -8
- = 1.5 10 the long term average relative i Q deposition factor at the maximum site boundary location, in 1/m*2 <
1 := 0.8105 -is the radiological decay constant for i Mn-54 (nuclide i in this case) in 1/yr.
t := 15 is the time in years over which b accumulation is evaluated ( approx.
midpoint of plant operating life) t
~9 DFG := 5.80 10 external dose factor to the whole ij or any internal organ , for body,ing on contaminated ground stand from Mn-54 (RG 1.109 Table E-6) in arcm/hr per pCi/m*2 Q := 1.0 is the unit release p antity assumed i for each nuclide 1, in C1/yr.
8760 is the number of hours in a year Therefore, the contribution to the total done made by exposure to
.the ground plane at the maximum off site exposure location for ,
Mn-54 is given as:
-1 <t i b 12 'II l'- e mrem 8760 1.0 10 S - -
-Q - DFG = 0.655 1 ij per F .Q, i i
yr per ci ODCM Rev. 8 A.10
. I PART C Ing stion Dose contribution:
As an initial step to determining the doce contribution from ingestion of milk, meat, stored vegetables, and leafy vegetables, we must first calculate the radionuclido concentration in forage, produce, and leafy vegetables resulting from atmospheric tranfers of the activity to theFor surface all of the vegetation and onto the soil for root uptake.
radiciodines and particulate nuclides (except tritium and C-14),
the concentration of nuclide i in and on the vegetation at a point of interest can be calculated using R.G. 1.109 cquations C-5 and C-6, which combined gives:
' i
)
r -1 .t -1 +t Ei e i b -1 t 1-e 1-e i h 8 'D'
+B e 1.14 10 - -
-Q +
r- -
Q i Y 1 iv P1 y' Ei i .
PART C.1: Concentration in Produce (sto' red vegetables)
For the case of Mn-54 released in air emissions to the maximum site boundary, the concentration of Mn in produce grown in the hypothetical garden at that location can be calculated from the above equation where the variables are defined as:
8 1.14 10 is the number of pCi per Ci divided by the number of hours in a year (r*"^).
D -8
- = 1.5 10 is the relative deposition factor, in Q 1/m2, at the maximum exposure point off site (S. B.)
Q := 1 the release rate of nuclide i to the i atmosphere in C1/yr r := 0.2 fraction of deposited activity retained '
on crops, leafy vegetables, or pasture grass (1.0 for lodines)
ODCH Rev. 8 A.11
- l. -
1 := 0.00219 effective removal rate constant for l El Mn-54 from crops due to decay and weathering, in hr-1 t := 131400. soil exposure time to deposition, in b (equal to 15 yrs, or mid plant life)
Y := 2.0 agricultural productivity (yeild) for v produce, in kg/m-2
-2 B := 2.9 10 concentration factor for uptake of iv Mn-54 from ; oil by edible parts of crops in pCi/kg (vet weight) per pCi/kg dry sofi :
-5 1 := 9.252 10 radioactive decay constant for Mn-54, i in hrs-1 P := 240. of fec,tive surf ace density of soil. in kg/m2 t := 1440. crop holdup time after harvest and h before ingestion, in hrs t := 1440, crop cxposure time to plume, in hrs e
Therefore, the concentration of Mn-54 in stored vegetables produced at the location of maximum deposition for a unit activity release is given as:
-1 t -1 *t Ei e i b -1 t 1-e i h 8 'D' 1-e = 67.379
+B - *e 1.14 10 - -
-Q -
r-P1
,0, i Y 1 iv y Ei i ,
pCi/kg PART C.2: Leafy Vegetable Concentration:
For leafy vegetables, the above equation is repeated with the value for t.h, crop holdup time af ter harvest is changed from 1440 hrs to 24 hru, i.e.:
ODCM Rev 8 j
_ A-12
1 I
l t := 24 crop holdup time after harvest, in hrs.
I h Therefore the concentration of Mn-54 in leafy vegetables at the maximum deposition point due to a unit activity release is given as:
~
_1 .t -l *t Ei e i b -1 t 1-e i h 8 ' D' 1-e e = 76.011 1.14 10 - -
-Q -
r- +B -
,Q i Y +1 iv P1
~
Y Ei i ~
pCi/kg PART C.3.a: Animal Feed concentratien (pasture): C P
liext, we can repeat the above calciulation to determine the concentration of Mn-54 in pasture grass used as animal feed. This vill allow for the determination of dose contribution from milk and meat.
For pasture grass, all the above variables remain the same execpt ,
for :
Y := 0.70 for agricultural productivity of pasture v grasses, kg/m2 t := 720. for grass exposure time to plume, hrs e
t := 0.0 for holdup time after harvest h
Using these variables in the above equation gives the concentratien in pasture grass as:
~
-1 t -1 t Ei e i b -1 t 1-e 1-e i h B ' D'
+B e = 179.227 1.14 10 - -
-Q -
r- -
,Q i Y 1 iv P1 v Ei i ,
pCi/kg
. a A-13 CDCM Rev. B
. _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ ____ _ _ _ _ _ _ _ _ __ _ _ __ _ _ _ ---------_.--_2__ _ . _ _ _ _ _ _ _ _ _ _
C PART C.3.b: Animal Feed Concentration (stored feed): s For stored feed that would be given to goats, or meat animals, the average concentration would be calculated by changing the following variables in the above calculation to:
Y := 2.0 apicultural productivity for stored feed V
i t := 1440. feed crop exposure time to plume in hrs -
f i
e t := 2160. feed crop holdup time after harvest, hrs h
Putting these values back into the above equation gives the concentration in stored animal feed (goat and meat animal) of Mn-54 for a unit activity release to the maximum exposure point.
~
~
_1 .t -1 t Ei e i b -1 t 1-e i h 8 ' D' 1-e e = 63.037 1.14 10 - -
-Q -
r- +B -
,Q. i Y 1 iv P1 y Ei i .
pCi/kg Concentration in Goat's Milk: C PART C.3.c.: m The Mn-54 concentration in milk is dependent on the amountThe and contamination level of the feed consumed by the animal.
radionuclide concentration in milk is estimated from RG 1.109 general equation C-10 as:
-1 t a i f e m conc. in milk, pCi/ liter F C -Q n v F A-14 ODCM Rev. 8
C
-PART C.3.b:- Animal Feed Concentration (stored feed) s l
For stored feed that would be given to goats, or meat animals, the average concentration would be calculated by changing the following variables in the above calculation to; Y := 2.0 agricultural productivity for stored feed ,
l v
t := 1440, feed crop exposure time to plume in hrs <
l l
e t := 2160. feed crop holdup time after harvest, hrs h
Putting th9se values back into the above equation gives the concentr.ition in stored animal feed (goat and meat animal) of Mn-54 for a unit activity release to the maximum exposure point.
-l t -l *t Ei e i b -1 t 1-e i h 8 'O' 1-e = 63.037
+B - e 1.14 10 - -
-Q -
r-
,Q, i Y *1 iv P1 v Ei i ,
pCi/kg Concentration in Goat's Milk: C PART C.3.c.: m The Mn-54 concentration in milk is dependent on the amountThe and contamination level of the feed consumed by the animal.
radionuclide concCntration-in milk is estimated from RG 1.109 general equation C-10 as:
-1 t 1 f F C- -Q e a conc. in milk, pCi/ liter n ~v F l .
l-A-14 ODCM Rev. 8 ,
I where the variables aro defined as:-
-4 F := 2.5 10 average fraction of animal's daily m-intake of Mn-54 which appears in each' liter of milk', in days / liter Q := 6.0 amount of feed consumed by a goat F- per day, in kg/ day ~(50 kg/d for meat) t := 2.0 average transport time of activity f_
from feed into milk and to receptor,,
I in days.
~3 1- := 2.22 10 decay constant of Mn-54 ,in days-1 i
In addition, the C.v term for the concentration of a nuclide in the animal's feed is given frca RG 1.109 general equation C-11 as:
~
C = f f C + 'l - f
~
C +f -
'l-f C p p, s p s, s v p s ,
where the following equals:
f := 0.5 fraction of the year that animals p graze on pasture f := 1.0 fraction of daily feed that is s pasture grass when the animal grazes on pasture C := 179.227 concentration of Mn-54 in pasture p grass as calculated from above, pCi/kg C := 63.037 concentration of Mn-54 in stored-s feed as calculated from above, in pCi/kg Therefore, the concentration in the total animal's feed is estimated to be :
A-15 ODCM Rev. 8
+ +f 'l - f C = 121.132
+f C -
f C 'l - f p s p ,
p, s p ,
c, s pCi/kg Khen this value of 121.132 is put back into the above general equation for nuclido concentration in milk, we get:
[C := 121.132 pCi/kg )
v and
-1 t ,
'e i f F C -Q e = 0.181 pCi/ liter of m v F Mn-54 in goats milk PART C 3.d. : Concentration in Heat: C f
Similar to milk, the concentration of the nuclide in animal meat is calculated. RG 1.109 general equation C-12 is given as:
-1 t i s C = F C -Q e f f v F Here the variables are set as:
-4 F := 8.0 10 fraction of animals daily intake of f Mn-54 which appears in each kg of flesh, in days /kg Q := 50.0 animal's daily feed intake, in F kg/ day t := 20.0 average time from slaughter to s consumption, in days C := 121.132 concentration on Mn-54 in animal's v feed, same as calculated above for goat, in pCi/kg Therefore, the concentration of Mn-54 in animal reat is calculated to be:
ODM W.B A-16 M
.where the variables are defined as:
-4 F := 2.5 10 average fraction of animal's daily a intake of Mn-54 which appears in each-liter of milk', in days / liter Q := 6.0 amount of-feed consumed by a goat F per day, in kg/ day (50 kg/d for meat) t := 2.0 average transport time of activity f from feed into milk and to receptor,, i in days.
i
-3 1 := 2.22 10 decay constant of Mn-54 ,in days-1 i
In addition, the C v term for.the concentration of a nuclide in the anistal's feed is given from RG 1.109 general equation C-11-as:
I C = f - f C + ~1 - t C. . +f * ~1-f C s p p, s p s. .s v p ,
where the following equals:
.f := 0.5 fraction of the year that animals p graze on pasture f :=-1.0 fraction of daily feed that is s pasture grass when the animal gra::es.
on pasture C :=-179.227. concentration of Mn-54 in pasture p grass as-calculated from above, pCi/kg-C := 63.037 concentration of Mn-54 in stored s feed as calculated from above, in pCi/kg Therefore, the concentration in the total animal's feed is estimated to be :
A-15 ODCM Rev. 8
2 2 +C + ~1 f ~C- +f - ll - f C a 131.133 s P P.. s P s, s P .
Pci/kg When this value of 121.132 is put back into the above general equation for nuclide concentration in milk, we get
(-C := 121.132 pCi/kg -)
v and
-1 t i i F C -Q e = 0.181 pCi/ liter of a v F Mn-54 in goats milk PART C.3.d. : Concentration in Meat: C f
Similar to milk, the concentration of the nuclide in animal meat is calculated. RG 1.109 general equation C-12 is given ts: -l
-1 t' i s C = F C Q e f f v F i
Here the variables are set as:
-4 F := 8.0 10 fraction of animals daily intake of f Mn-54 which appears in each kg of flesh, in days /kg
-Q := 50.0 animal's daily feed intake, in F kg/ day t := 20.0 average time from slaughter to s consumption, in days C := 121.132 concentration on Mn-54 in animal's v feed, same as calculated above for goat, in pCi/kg l
i Therefore, the concentration of Mn-54 in animal meat is calculated to be:
ODCH Rev. B A.16 m gM4 ,+---wey
-1 t i e F C -Q e = 4.635 pCi/kg in meat f v F for Kn-54 PleT D: DDSE FROM INGESTION OF FOODS PRODUCED AT MAXIEM IDCATION Now that we have calculated the cet centration of Mn-54 in milk, meat, leafy vegetables, and stored vegetables produced at a location of maximum air depcsition, the resulting dose to any organ j and age group a can be calculated from the following J general equation C-13 taken from RG 1.109:
F+
~
C +U C +U C +U f C DFI 'U f Ia 1 L,
' ija ,, va g y ma m Fa f ty ,
e i
%f or Mn-54 set equal to 1, we find that from the evaluation of all organs for all age groups for combination of all exposure pathways, the adults GI-LIl is the critical age group / organ.
Therefore, the variables in the above dose equation can be defined as:
l
-5 t
DFI := 1.40 10 ingestion dose factor for ija adults /GI-LLI for Mn-54, in tren/pci ingested (RG 1.109, Table E-ll)
U := 520.0 vegetable ingestion rates for va adults, kg/yr f := 0.76 fraction of stored vegetables g grown in the garden f := 1.0 fraction of leafy vegetables 1 grown in the garden l U :e 310.0 milk ingestion rate for ma adults, liter /yr ODCM Rev. B A-17
U := 110.0 meat ' ingestion rate for l adults, kg/yr Fa U := 64.0 leafy. Vegetable ingestion La rate for adults, kg/yr C := 67.379 concentration of Mn-54 in y stored vegetables, in pCi/kg (from above)
C := 0.181 concentration of Mn-54 in m milk, in pCi/ liter (from above)
C := 4.635 concentration of Mn-54 in f meat, in pCi/kg (from above) ,p C := 76.Bil concentration of Mn-54 in L '
leafy vegetables, in pCi/kg (from above)
The dose from the combination of ingestion pathways for this example is calculated by substituting the above listed variables back into the ingestion dose equation: ,
C +U C +U C +U f C = 0.4495 DFI -
'U f ija , va g v ma m Fa f La 1 L, nrem-
/Y per ~
ci By breaking the above dose equation down into the different '
pathways which combine to give the total ingestion dose, we can see the individual dose contribution made by each exposure pathway.
Therefore, we have:
Dose for ingestion DFI U f C = 0.373 of stored vegetables ija va g v Dese for ingestion -4 of goat's milk DFI U C = 7.855 10 ija ma m A-18 ODCM Rev. 8
_ - - _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - - - ~ - - - - . _ - - _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _
Dose for ingestion DFI U C = 0.00714 of meat ija Fa. f Dose _for ingestion DFI U f C == 0. 068 8 of leafy vegetables ija la 1 L-PART E: TOTAL DOSE FROM ALL EXPOSURE PATHWAY The total dose from all exposure pathways assumed to be present at the maximum receptor location can be found by simply adding the individual pathway doses calculated above.. Since all the calculations above assumed a unit activity release from the plant vent stack, the combined dose can be stated as dose factor per unit activity released. This then demonstrates the development of the Seabrook ODCM Method I dose factors for gaseous release of particulates from the vent stack.
Inhalation dose (Part A) 0.00184 mres/yr per Ci Ground plane dose (Part B) 0.658 mrem /yr per Ci Ingestion dose total (Part D)- 0.449 mrem /yr per Ci Total dose all pathways 1.11 mrem /yr per Ci-(critical' organ is GI-LLI '
of an adult for Mn-54)
A-19 ODCM Rev. 8
..