ML20149D485
| ML20149D485 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 03/05/1986 |
| From: | Mayer D, Quinn D POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | |
| Shared Package | |
| ML20149D472 | List: |
| References | |
| PROC-860305, NUDOCS 8802090514 | |
| Download: ML20149D485 (111) | |
Text
indien Point 3 Nuclear Power Plant P.O. Boa 215 Buchanan New wrk 10511 914 739.8200
- > NewYorkPower 4# Authority 0FFSITE DOSE CALCULATION MANAVAL REV. 3 TITLE: _
WRITTEN BY:} Q uinn f . d(Mee
- ' O REVIEWED BY: M PORC REVIEW: i G A4. ., . /s 3/.44 APPROVED BY: .g[/ [/[ e A i[ p, 0002090514 060020 EFFECTIVE DATE:
(
b/ /s
/ /
ppg /
p ADOCK 05000206 '
PDR r
f
)!
O INDIAN POINT 3 0FFSITE DOSE CALCULATION MANUAL Revision 3, February 1986 1
OCCM REV. 3 ODCM TABLE OF CONTENTS PAGE Table of Contents 1 List of Tables 11 List of Figures iv References v Chapter 1.0 INSTRUMENTATION AND CONTROL 1.1 Effluent Monitoring System Description 1 1.2 Set Points 1 1.2.1 Set Points for Gaseous Effluent Monitors 1 1.2.2 Set Points for Liquid Effluent Monitors 2 Chapter 2.0 LIQUID EFFLUENTS 2.1 Liquid Effluent Releases - General Infor1 nation 5 2.2 Liquid Effluent Concentrations 8 2.3 Liquid Effluent Dose Calculation Requirements 9
- a. Calculation of Maximum Permissible Concentrations in Liquid Effluents 10 2.4 Dose Methodology (Computer Calculation) 11 2.5 Backup Dose Methodology (Hand Calculation) 14 Chapter 3.0 GASEOUS EFFLUENTS 3.1 Gaseous Effluents Releases - General Information 20 3.2 Gaseous Effluent Dose Calculation Reouirements 22 3.3 Dose Calculations Methodology 24 (ComputerCalculation)
I. Instantaneous Dose Rates 24 3.3.1 Instantaneous - Noble Gas Releases 24 ,
3.3.2 Instantaneous - Radioiodine and Particulate Releases 26 L i
a ODCM REV. 3 TABLE OF CONTENTS (Continued)
PAGE II. Time Averaged Dose 27 3.3.3 Time Averaged - Noble Gas Releases 27 3.3.4 Time Averaged - Radioiodines and Particulates 29
- a. Inhalation Pathway 31
- b. Ground Plane Pathway 32
- c. Grass - Cow - Milk Pathway 32
- d. Vegetation Pathway 35 3.4 Backup Dose Methodology (Hand Calculation) 37
- 1. Instantaneous - Noble Gas Releases 37 3.4.1 Instantaneous - Noble Gas Releases 37 3.4.2 Instantaneous - Radiofodine and Particulate Release 38 II. Time Averaged Dose 39 3.4.3 Time Averaged - Noble Gas Releases 39 3.4.4 Time Averaged - Radioiodine and Particulate Releases 40 3.5 Calculation of Meteorological Dispersion Factors 42 3.6 Finite Cloud Correction Justification 46 Appendix 3-A Calculation of Allowable Release Rates 68 76 Chapter 4.0 SAMPLE LOCATIONS
i (BCM - REV, 3 LIST OF TABLES PAGE 3
l-1 Effluent Monitoring system Data 2-1 Liquid Effluent Dose Factors 1 3-l a Inhalation Dose Factors for Child 47 3-lb Inhalation Dose Factors for Infant 50 3-2 Ground Plane Dose Factors 53 3-3a Ingestion Dose Factors for Child 54 3-3b Ingestion Dose Factors for Infant 57 3-4 Total Body Dose Factors (Ki) from Noble Gases (Gamma) 60 3-5 Skin Dose Factors (Li) from Noble Gases (Beta) 61 3-6 Air Dose Factors (Mi) from Nable Gases (Gamma) 62 3-7 Air Dose Factors (Ni) from Noble Gases (Beta) 63, 3-8 Skin Dose Factors (Si) from Noble Cases (Beta-Gamma) 64 3-9 Dose Factors for Site Boundary 65 '
3-10 Dose Factors at Site Boundary for Standard Isotype Mixture 66 3-31 Locations of Site Boundary, residence, dairy cows 67 Appendix 3-A , Calculation of Allowable Release Rates 68 4-1 Indian Point Station - Location of Radiological Environmental 11onitoring Sample Points 79 244
C ON2 - MN. 3 4
LIST OF FIGURES PAGE Figure 1-1 Map Defining Unrestricted Areas for Radioactive 4
- Gaseous and Liquid Release Points Figure 2-l' Radioactive Liquid Waste Effluent System Flow Diagram 19 Figure 3-1 Gaseous Waste Effluent System Flow Diagram 75 ,
Figure 4-1 Radiological Environmental Monitoring Sampling i Stations - Near Site 77 Figure 4-2 Radiological Environmental Monitoring Sampling 3 Stations - Away from Site .78 e
l b
t l
i I
iv
GKM-RW,3 REFERENCES
- 1. U.S. Nuclear Regulatory Commission, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants", "USNRC REPORT NUREG-0133", Washington D.C.C 20555, October 1978.
- 2. M.E. Wrenn and J. W. Lentsch, "The Fate of Gamma-Emitting Radionuclides Released into the Hudson River Estuary and an Evaluation of their Environ-mental Significance, New York University Medial Center, Institute of Environmental Medicine, 1974.
- 3. Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I" Revision 1, USNRC Washington D.C. 20555, October 1977.
- 4. "An Evaluation to Demonstrate the Compliance of the Indian Point Reactors with the Design Objectives of 10 CFR 50, Appendix I, "Consolidated Edison Company of New York, Inc. and Power Authority of the State of New York, February, 1977.
- 5. U.S. Nuclear Regulatory Commission, "XOQDOW Program for the Heteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations",
"USNRC REPORT NUREG-0324," Washington D.C. 20555, September, 1977.
- 6. "Semi Annual Report of Radioactivity in Solid Wastes and Releases of Radio-active Materials in Liquid and Gaseous Effluents for Indian Point Three," Power Authority of the State of New York, Jan. 1, 1978 to June 30, 1980.
- 7. "Environmental Technical Specification Requirements for Indian Point Nuclear Generating Unit Number 3, "Power Authority of the State of New York, Dec. 12, 1975.
- 8. U.S. Nuclear Regulatory Commission, "Radiological Effluent Technical
. 20555.
Specification for PWR's, "USNRC REPORT NUREG-0472, Washington D.C.
- 9. Regulatory Guide 1,113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I", Revision 1, USNRC Washington D.C. 20555, October 1977.
- 10. AP-11, Indian Point No. 3 Nuclear Power Plint Administrative Procedere, "Radioactive Wasto Release Permits".
t,
. ~
00CM - REV. 3 1.0 INSTRUMENTATION AND SYSTEM 1.1 Effluent Monitoring System Description Effluent monitor information is provided in Table 1-1, including an
-indication of which monitors use effluent set points. Figures 5-1 and 5-2 show a schematic of the possible radioactive release points with monitor locations for gaseous and liquid pathways respectively.
1.2 Setpoints This section provides equations and methodology used for each alarm and trip set point on each effluent release point according to Specifications 2.1 and 2.2.
1.2.1 Set Points for Gaseous Effluent Monitors Set points for gaseous monitors are based on the permissible discharge rate as calculated in section 3.4 of this 00CM.
The most restrictive set points (based on annual average dose limit) should be used if practical. If not practical and with the concurrence of the Shift Supervisor and/or Superintendent of Power, as appropriate, points man be used.
(per Reference 10, AP-11). All but the computer-generated set points are based on the following permissible discharge rates: ,
Permissible Discharge Rate (Ci/sec)
Basis of Iodir.e/ Noble Gases Limit P_a-'.i c ul a t e*
Annual Average
- 3.3E-8 5.06E-4 .
6.5E-8 1.01E-3 0 Quarterly Average **
Instantanecus (Tech Spec 2.4.1) 2.2E-6 1.63E-2
- Half-lives greater than 8 days.
- These limits are not part of the Tech Spec requirement 2.4.1, but are included for information, as these limits are used for operational control of releases.
The noble gas limits are based on an isotopic mix as described in Table 3.10.
The generic equation for determining an alarm set point is as follows:
S= (D)
(E) (F) (4.72 E-4) 1
WKM - MN. 3 e
Where S = Alarm set point (cpm)
D = permissible discharge rate (Ci/sec) ,
E = Monitor Calibration Factor (uCi/cc)
P = Vent duct flow rate (ft /3 min) 4.72 x 10-4 = conversion factor to convert from uCi Ft3 to Ci/sec '
cc min. .,
The computer-generated set points are determined by calcu-lating the instantaneous dose rates based on the actual nuclide mix. During normal operation without a primary to secondary leak, the only release point is the Unit 3 main plant vent. However, in the event of a leak, the blowdown flash tank and the condenser air ejector would also be release points. In that case, the total ;
discharge rate for all release points must remain less i than the permissible discharge rate. Alarm set points l w'uldo be reduced accordingly, depending on the fraction l of the permissible discharge rate allowed to be released from each release point.
1.2.2 Set Points for Liquid Effluant Mon.itors j I
Liquid Effluent Mohitors R18 and R19 have set points ,
based on limiting the concentrations in the discharge canal to the levels listed in 10 CFR 20 Appendix B, Table i 2, Column 2. The set points are calculated based on the following equations S = (MPCw) (F) .,
Exf S = set points on monitor (cpm)
MPCw = Maximum Permissible Concentration (uci/cc) for isotopic mixture being released per 10 CFR 20, Appendix B, Table 2, Column 2. This will be calculated for each release. ;
F = Available Dilution Flow in Discharge Canal (gpm)
= Release Discharge Rate (gpm) l f
f i
E = Calibration Factor of monitor (uci/ect epm r a
1 J
l
, - wy----,w-rw-y,,, i- ---y 7 .- 9 - -- ----,w - ey - --
gata - gEV. 3 TAR E l-1 DTIINNr NNTIURING SYSITM 1RTA AIMM SET RAN2 UNIROI. RNLTICNS FOINT USI1)
- 01ANPEL MNrlTR DESOtIPIT(N SAWLING IDCATI(NS Cmtairrunt Cas &nitor Sarples drawn frtn Cmtainment 0-106 c;n Cmtalment Ventilation Yes R-12 Isolatim C Fan Coolers I's 32 and 35 0-105 cpm Secures wiste gas tank release. Yes R-14 "lant Vent Radiogas Inglant vent at approximately C Mar.itor 105 elevation 0-10-3 (tCf/ce)
(typical)
Plant Vent Wide-Range In-plant vent 10-7 -1045 None Yes R-27d* (tCf/cc)
C M mitor Condenser Air Ejector In-line detector en the air 0-106 c;m On alarm diverts air ejector No R-15 flow to VC, flash evaporator C M mitor ejector exhaust leader shut downe steam to condense primirg e;xtor flow stqped.
15' PAB - Este Cas Tank 0-105 ni;/hr. None No R-20 W ste Gas Disposal G Systen nmitor A&ninistration Building 4th Floor A kinistration Building 0-10k c;n None Yes R-46 G Vent Radiopps & nitor Monitor Exhaust Plente for Cm trolled Areas Nme Yes R-59 R#6 Building Vent 55' RAE Buildirg Monitor 0-105 cTa
- C Radior,1s Monitor Exhaust Piemm 6 y,, y,,
Service E ter chase across frta 10-10 c},
F-16 or Fan Cooler Service Mini-Contairment R-23 L
Wter Activity 3
6 Isolates Surge Tak Vents Crmpment Cooling 41' PAB in ccmponent cooling witer IO-Id c;n No R-17A or fnm atmosphere.
R-17B Wter Activity header L
Este DL, 11 Liquid 55' PAB Wste Condemate Room 0-106 cpn Stops release on alarm. Yes R-18 L Effluent tor unitors liquid wiste discharge 0-105 cgn Clones blowdown isolation Yes R-19 S/G S.wples BIcudown PAB blowdown trxw monitors stean generator blowdown valve.
L Mmitor
- Alarm se: point used for effluent considerations. N7IE (N RANT OF MNTI0RS:
riaxumm release rate rnat can be detected onscale by the
- If available, (R-14 or R-27 mist be operstfrg). detector (Ci/sec.) is based cri the maxinass readout rarge of the detector, the calibration factor and the voltme flow rate of the discharge.
G= Caseous Ci/sec. (nux) = (anx clu) x (uCi/cc/cpa) x (cfm) x (4.72 FMM) w
~
-d '5
~~ t f., - . v.
e 3
g:y fg f - 'I I E, Y
- / :hf lI 'N ll sj, l b.
IE 9 il l
- l$
'g . s <
kg ' '
k ' .. . . . $ 5l Es i ' r
.1r I ll4 : g!II l
I!i ~~
l
\
] g 3
- a
., .\ s . ,
- .
- .yn : ..- ,
i, 4
.,l- -
5y t*-
..i . 4 ,; i ll ,
i N <
9 . s , ., ,m 'i .,
( kV i .. ,s g>i '-
, 3 t .
L .--% .,l'k
. ! .. .! %g .j .
4 m-
-l.;l-~';
'~
i u- , .d i a j,,
3.,
w &, -
~
. );
4.L .
' f . .'tu.I k n_f-#f l @a
. ~j 5
l n.
8 c
&rMf_ $ 8 -
i,..
,%,./ 3
,.: -y fN f-K 34 g:q,,1l,5
,a -
4= -
- % : g '~
. c. ,- '. lll cg 3 -
'5 "
p5 / N'
. hec'1 i
3 .
c'?eg.( " .- gi y T v <l 3 .
e !.g hN a5 '..f,/, ./ ', ? N-M..E,::-L. .m 4 .'i;a.e.x .s l ), : se i. !!: :g <
gs 4.7 . . -. ' . j g s.J p r 3 .
~ -
._ ll
. 1-
, i f; l ) .'N 3l I* \(. g
.c it .
f'.
\\ l 15
.h / 0 kj' I l;!
h) [gp#
. ?
l l M .
luri
'IIII' r^&wgy . W R N; $. h '
- s. ;
y+ _
l .
4
4 MCM - RDi. 3 4
2.0 LIQUID EFFLUENTS 2.1 Liquid Effluent Releases - General Information 2.1.1 The surveillance and lower limit of detection requirements for liquid radioactive effluents are contained in Section 3.3.1 of the Technical Specifications. For any-and all
' discharges, a minimum dilution flow should be available for IP3NPP to ensure compliance with time average liquid
, release limits.
2.1.2 A completed and properly authorised Liquid Radioactive Waste Permit shall be issued prior to the release of 4 any radioactive waste from an isolated tank to the discharge canal. A permit is required for each tank to be discharged and must be retained for tre life of the plant.
2.1.3 All activity determinations for liquid radioactive affluents *
. will be performed in such a manner as to be representative of the activity released to the river. ;
2.1.4 - The radioactivity in liquid waste shall be continuously monitored during release. If the flowmeter is inoperable, the flow shall be estimated every four hours by difference in tank level or by discharge pump curves. I 2.1.5 Prior to discharge, the tank contents shall be recirculated ,
I for two tank volumes. After this recirculation, and prior to discharge, a sample shall be taken and analyzed for activity with a portion of the sample set aside for composite analysis. The measured activity shall be used for calculating permissible discharge rate and the alarm set point for the liquid waste discharge monitor.
2.1.6 Radioactive releases that are continuous such as steam i generator blowdown during primary-secondary leaks when '
released to the river shall be documented on Liquid Radio-
- ' active Waste Release Permits using data supplied by the l Chemistry technician.
i 2.1.7 Assurance that combined liquid released from unita 2 l l i and 3 do not exceed section 2.3. Limits for the site '
are provided by administrative controls agreed to in l the Memorandum of Understanding (415) between Con Edison I
and the Power Authority concerning liquid discharge and ,
the requirements of this document.
I l
" 2.1.8 The dilution flow from' Unit No. 3 should be used for j
calculating discharge canal concentrations. However, by agreement with Con Editon's IP3NPP Watch Supervisor, l and the Power Authority's IP3NPP Watch Supervisor one l I
t party can reduce or eliminate radioactive liquid waste f discharge for a period of time to allow the other party ;
j to use the full site dilution flow, or a specified portion j
' thereof, for a discharge when necessary. ,
[
r
open - m. 3 2.1.9 Steam generator blowdown activity is determined by samples taken three times per week. This frequency is required by Table 4.1-2 item 6 of Appendix A of the stations operating license. These "grab" samples of the steam generators are collected in a manner to be proportional to the rate of flow of the total steam generator blowdown. These samples are then analysed for the various radionuclides at the frequencies specified in Table 3.3-1B (further flow proportional composites are made where appropriate). (REF NUREG 0472 - REV 3 DRAFT 6 TABLE 4.11-1) 2.1.10 The Discharge Canal flow rate is determined by the use of pump flow characteristics curves. The normal flow for condenser cooling pumps is 140,000 gpm when operating at maximum frequency. During the cold weather months the 3 condenser cooling pumps are operating at reduced frequency this reduced flow is nominally 71,000 gpm (Ref: NUREG 0472-REY. 3 DRAFT 6 3.3-12) 2.1.11 Radioactivity content in outdoor tanks is to be limited to less than ten curies. Compliance with this requirement is demonstrated by limiting the radioactive concentration in these tanks to the value which results in ten curies when the tank is at full liquid capacity except as modified below. The radioactive concentrations for these tanks are:
RWST 6
10 curie _s.x 10 uCi/ curie =7.3 x 10-3 uC1/mi 358,500 gals x 3785 ml/ gal pWST O
10 curies x 106 uCi/ curie =1.6 x 10 uC1/mi 165,000 gals x 3785 ml/gai 31 & 32 mt 6 10 curies x 10 uCi/ curie = 2.2 x 10~1 uCi/mi 11,750 gals. x 3785 ml/ gal Outside Temporary Tanks 6
10 curies x 10 uCi/ curie = uCi/ml Volume in gals. x 3785 ml/ gal.
The refueling water storage tank has the potential to te filled from the reactor cavity with liquid which exceeds the limits stated. Therefore prior to filling the RSWT from the reactor cavity after refueling operations, the reactor cavity (or residual heat removal system) must be sampled for radioactivity and action taken to ensure that the total 3 '
activity in the tank does not exceed 10 curies.
Outside temporary tanks should not be filled with liquid which could exceed the concentration limit calculated.
Therefore prior to transfer to outside tanks the source of liquid shall be sampled for radioactivity if it exceeds the concentration limit calculated. (REF NUREG 0472 REV 3 DRAFT 6,3.11.1.4) 6
MCR - REY. 3 2.1.12 There are no continuous composite samples for steam generator blowdown. The method of determining release concentrations is shown below:
Blowdown flowrate (by flowmeter or by flow curves) multiplied by sample blowdown concentration equals composite activity being released. In addition, R-19 monitors the composite steam generator blowdown released. (REF NUREG 0472 REV 3 DRAFT 6 TABLE 3.3-12) 2.1.13 The service water radioactivity monitor listed in Table
- 3.3-12 is defined as the process radiation monitors which monitor components which discharge into or are cooled by the service water system. These process radiation monitors are component cooling radiation monitor (R-17 A/B), Liquid Waste Release Monitor 1R-18) Steam Generator Blowdown Monitor (R-19), Vapor Containment Fan Coolers, and Vapor Containment FCU Motor Coolers (R-23).
If any of these monitors are taken out of service and the removal of that monitor from service is not specifically addressed in the Radiological Environmental Technical Specification samples shall be taken every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or releases may not continue via this pathway. Sarples may be taken on the affected monitored stream or on the service water system. (REF NUREG 0472 REV 3 DRAFT 6 TABLE 3.3-12) 2.1.14 Liquid Effluent Concentrations are limited to 10CFR20 limits, as calculated under 20,106a. This permits aver-aging of effluent concentrations over one year. This is appropriate since doses from the liquid pathway are the result of total curies released and are not greatly influenced by instantaneous concentrations. In any case, the total dose per quarter and per year must be within the limitations of 2.3.2 of the RETS. (REF NUREG 0472 REV 3 DRAFT 6 3.11.1.'l) 2.1.15 There are no drinking water intakes within 3 miles of the site on the Hudson River. (REF NURFG 0472 REV 3 DRAFT 6 3 11.1.'2 )
2.1.16 A turbine hall drain system which would collect leakage of contaminated secondary plant waters during operation does not exist at IP3. The sumps which are present in the turbine hall five foot elevation receive drains from i areas containing secondary plant components at sub atmos-pheric pressures, these sumps would not meet the intent ,
of the NUREG-0472. I l
l l
l
NCM - KV. 3 The activity released to the environment via this pathway is negligible when steam generator blowdown activity is less than 3 x 10-5 uci/cc. Activity released via this pathway when steam generator activity exceeds 3 x 10-5 uCi/cc is determined by the following method Turbine Hall Drain Feedwater Steam Steam Effluent Activity = 1 Specific i x Plant -
Generator
( Activity J Makeup Blowdown Rate (
(REF NUREQ 0472 REV 3 DRAFT 6 TABLE 3.3-12) 2.2 Liquid Effluent Concentrations 2.2.1 This section provides a description of the means that -
will be used to demonstrate compliance with Technical Specification 2.3.1.
2.2.2 Compliance with the instantaneous limita of 10CFR20 is achieved by observance of discharge limits and monitor set points. Normally, only dilution water from Unit 3 circulators is taken credit fer, except as allowed by the memorandum of understanding between NYPA and Con Edison. A monthly report is issued which summarizes the radioactive releases from the site for the pre, ceding month. This report provides information necessary to comply with quarterly and annual average limitations on discharge.
2.2.3 Each isolated liquid waste tank must be recirculated for two tank volumes prior to sampling in order to obtain a representative sample.
2.2.4 The concentration in liquid effluents prior to dilution in the discharge canal is determined by sampling prior to release, for batch releases. For continuous releases, the concentration is determined by grab sampling or by the following equation:
C=ExR C = concentration of liquid effluent (uci/ce) prior to dilution E = Calibration factor of monitor (uci/ec) cpm R = count rate of monitor (cpm) 2.2.5 The concentration in liquid effluents after dilution in the discharge canal is determined by the following equation:
s
OKM - RW, 3 CD=Cxf F
Co = Diluted concentration of liquid effluent (uci/cc) f = Releass Discharge Rate (gpm)
F = Dilution Flow in Discharge Canal, Unit 3 circu-lators only (gpm) 2.3 Liquid Effluent Dose Calculation Requirements 2.3.1 Section 2.3.2 of the Technical Specification requires that the dose or dose committment above background to an individual in an unrestricted area from radioactive materials in liquid effluents released from each reactor unit shall be limited:
a) During any calendar quarter less than or aqual to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ.
b) During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal ;
t to 10 mrem to any organ, Note: If either of the above limits is exceeded by a factor of two or more, then cumulative dose contributions from direct radiation would be determined by evaluation of existing peri-meter and environmental TLDs per Tech Spec 2.6.B.
2.3.2 Section 2.3.3 of the Technical Specifict.tions requires that appropriate portions of the radwaste treatment system be used to reduce the radioactive material ir. liquid waste prior to their discharge when the projected dose due to liquid effluent from each reactor unit when averaged over 31 days, would exceed 0.06 mrem to the total body or 0.2 mrem to any organ. Doses due to liquid release shall be projected at least once per 31 days.
These doses are projected based on the dose methodology in Section 2.4 or 2.5. The average of previous months' doses is used to project future dose.
2.3.3 Section 2.3.1 of Technical Specifications require that the concentration of radioactive material released from the site shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases (averaged over a calendar quarter). For dissolved '
or entrained noble gases the concentration shall be limited to 2 x 10-4 uCi/ml total activity. ,
i l o
WKM - tDI. 3 2.3.4 calculation of Maximum Permissible Concentrations in Liquid Effluents 2.3.4.1 This section describes the methodology used to meet the requirements of section 2.3.3. The total discharge canal concentration of discharge from all reactor units, both continuous and intermittent, must be maintained at less
~
than the effective maximum permissible concentration for the respective radionuclide mixture exclusive of dissolved noble gases when averaged per 10CFR20.106a.
The dissolved noble gas limit is contained in Section 2.3.4.
2.3.4.2 The following methodology is utilized to meet the require-ments of section 2.3.4.
- a. Record tank identification, time of isolation, volume to be discharged start tank recirculation, recording rate, start time, and end time (later calculated in 2 below).
- b. Assure that at least two tank volumes have been recir-culated as follows:
T = 2V G
where: .
T = minimum recirculation time (minutos) y = volume in tank (gallon)
G = recirculation rate (gpm) end time equal to T plus start time,
- c. Af ter recirculation, have the tank sampled and determine the radioactive concentration and MPCw for the sample.
Record this and the total dilution flow from this unit.
- d. Determine if other liquid radioactive discharges are being made from this unit and obtain the radioactive concentration and discharge rate. If another release is occurring, the available dilution flow must be adjusted. This may be performed by allocation or by calculation. The adjusted dilution flow is calcu-lated as follows:
Dr (A) =E MPCwA
OKA - 801. 3 Where D,r = Current release discharge rate (gpm)
E = Required dilution flow for current release (gpm)
A = Concentration of radioactivity in current release (uci/ec)
MPCw g = Maximum permissible concentration for current release (uci/ce)
' Adjusted' Dilution Flow = Available dilut' ion flow- E.
- e. Calculate the permissible radioactive discharge rate for the irsolated tank as follows:
D = (MPCwr *; n (B)
C where:
D = Maximum permissible discharge rate (gpm)
MPCwT = Maximum permissible concentration for tank release (uci/ce)
B = Adjusted dilution flow available from unit (gpm)
C = Radioactive concentration in tank for discharge (uci/ml). .
2.4 Dose Methodology (Computer Calculation) 2.4.1 NUREG 0133 (Ref. 1, Section 4.3, Pg. 14) states that cumulative dase contributions should consider the dose contribution from the maximum exposed individual's con-sumption of fish, invertebrates and potable water as appropriate. The river at IP3NPP is considered to be fresh water when in reality it is a tidal estuary and never completely fresh. Observed average chlorosity at IP3NPP has ranged as high as 2.5 g/l or about 134 sea water and 87% fresh water. Hence, use of the Hudson River for water supply purposes is precluded south of Chelsea (mile point 65) which is the nearest point of potable water supply. Radionuclide concentration in the nearest water supply have been calculated (Ref.2) to b'e a factor of at least 500 lower than the river water in the Indian Point area. Exposures from ingestion of the drinking water is therefore negligible.
ON 3 - REV. 3 1
l Based on these factors, potable water consumption is not considered to bw a pathway at IP3NTP. Thus, at IP3NPP, the cumulative dose considers only the dose contributions from the maximum exposed individuals consumption of fish and invertebrates. Also, IP3NPP takes the position that the adult is the maximum exposed individual, as recom-mended by NUREG 0133 (Ref. 1, section 4.3, pg. 14).
Subsequently, tables of dose f actors for the adult case were dyveloped in Section 2.4.3.
2.4.2 The relationships and methods that form the calculational base for dose accounting for the liquid effluent pathway are described in this section. These relationships can be used to meet the calculational requirements of Section 2.3.1. The cumulative dose factors (Ai are calculated in Section 2.4.3. The following equati5n)is generally applicable and can be used for any number of isotopes released over any time period.
t m <
D T
=
i lAi IatLCliF8 g, ,
where D = The cumulative dose commitment to the total body T
or any organ, t, from the liquid effluents for the total time period I"4 t i , in mrem.
L"l A
tg= The length of the ith time period over which Cit and F1 are averaged for all liquid releases, in hours.
Ci l= The average concentration of radionuclide, i, in undiluted liquid effluent during time period ati from any liquid release, in uci/ml.
AiT = The site related ingestion dose commitment factor to the total body or any organ for each IP3-NPP identified principal gamma and beta emitter listed in table 2-1, in mrem-m1 per hr - uCi.
Ff = The near field average dilution factor for Cil' .
during any liquid effluent releases. Defined as the ratio of the maximum undiluted liquid waste flow during release to the average flow from the site discharge structure to unrestricted receiving waters.
The term Cil is the composite undiluted concentration of radioactive material in liquid waste at the release point as determined by the radioactive liquid waste sampling and analysis program as contained in the Technical Specifi-cationc. All dilution factors beyond the sampic point are included in the F8 and All terms.
OKJ o RD, 3 f
The term F R is a near field average dilution factor and is determined as follows:
F = Liquid Radioactive Waste Flow
[ Discharge Structure Exit Flow x (Applicable Factor))
The liquid radioactive waste flow is the flow from all continuous and batch radioactive effluent releases specified in Technical Specifications from all liquid radioactive waste management systems. The discharge structure exit flow is the average flow during disposal from the discharge structure release point into the receiving body of water.
As recommended in NUREG-0133 (ref. 1, section 4.3, pg.
- 16) the "Applicable Factor" is set equal to 1 because the plant has a once through cooling system.
In order to accurately determine Fi , it is calculated based on actual operating parameters that exist at the time of releases. This affords a quantitative assess-ment of radiation dose resulting from liquid effluent releases at IP3NPP. The determination and use of Jilution factors is discussed in Section 2.2.
2.4.3 Dose Factor for Liquid Effluent Calculations 2.4.3.1 The equation for dose from liquid effluents requires the use of a dose factor Ait for each nuclide, i, which embodies the dose factors, pathway transfer factor, pathway
, usage factors, and dilution factors for the points of pathway origin. IP3NPP has followed the guidance of NUREG 0133 and has calculated Ait for the total body and critical organ of the maximum exposed individual e.g. the adult. All the factors needed in the equation were obtained from Regulatory Guide 1.109 (ref.3) with
_ the exception of the fish and invertebrate bioaccumulation factors (BFi and BIi) for Cesium. A site specific factor of 150 was used instead of the 2,000 presented in Table A-1 of the Regulatory Guide for fish. Similarly, a factor of 150 was used for invertebrates instead of the Regulator Guide value of 1000. The justification for these substi-tutions is discussed in Section 2.5.3. The summary dose factor is as follows:
Ait = Xo (UpBFi + Ug BIi) CFi a where:
Ai = Composite dose parameter for the total body or critical organ for nuclide, i, for all appropriate pathways, arem/hr per uCi/ml.
Xo
units conversion factor, 1.14F05
i 106 pci/uCJ . x 103 ml/kgtB760 hr/yr.
i Up = 21 kg/yr, adult fish consumption from Table E-5 of Regulatory Guide 1.109.
Si
ODCM - REV, 3 Bioaccumulation factor for nuclide, i, in fish BF4= pCi/kg per pCi/ from Table A-1 of Regulatory Guide 1.109.
U;
= 5 kg/yr, adult invertebrate consumption from Table E-5 of Regulatory Guide 1.109.
Bioaccumulation Factor for nuclide, i, in BI 4= invertebrates, pCi/kg per pCi/l from Table A-1 of Regulatory Guide 1.109.
Dose conversion factor for nuclide, i, for adults DF4=
in pre-selected organs T. in mrem /pci, from Table E-11 of Regulatory Guide 1.109.
For the IN3NPP site, Ai 7 can be expressed as:
Ai 7= 1.14E05 (21 BF 4 + 5 BI4 ) DFi IP3NPP has complied Ai factors for total body and various organs for ,the maximum exposed individual. These are included as Table 2-1, 2.5 Backup Dose Methodology (Hand Calculation) 2.5.1 This method is a simplified version of that presented in Section
-2.4. and is more amenable to manual calculation. However, doses calculated using this method will be used only as a backup to the method of Section 2.4.
2.5.2 This method is identical to that presented in Section 2.4 except that the number of ruclides considered in the dose calculation is reduced to a number that is more manageable for manual calculations. The pathways of concern are fish and invertebrate consumption.
Review of past release data indicates that there are a group of radionuclides that are relcased most frequently and abundantly relative to total activity released. These radionuclides make up 3 at least 90% of the total activity and calculated dose for a .
release. The equation in Section 2.4.2 will be utilized to calculate doses resulting from liquid releases by calculating the dose committment to each organ at and the total body for these major contributors. To ensure a conservative result the result using equation 2.4.2 will be multiplied by a factor of 1.2.
WKM - R0l. 3 2.5.3 As stated in section 2.4.3 the bioaccumulation factor'(BPg ) for cesium in fish is assumed to be 150 instead of the 2000 listed in Regulatory Guide 1.109 (Ref. 3). This is based on the fact that the' Hudson River at IP3NPP is not completely fresh, BF for salt water is 40 (Ref. 2), and that the behavior of ceskum in the Hudson is a complex phenomenon.
Similarly, the bioaccumulation factor for invertebrates is 150.
The NYU study (Ref. 2) shows that cesium concentrations in fish are regulated at a relatively constant value independent of the concentration of cesium in water, and the bioaccumulator factors are thus inversely proportional to the water concentration of cesium. This explains the lower bioaccumulation factor for cesium reported by numerous investigators for salt water fish as opposed to fresh water fish because of the higher stable cesium content of sea water. The NYU report states that water at Indian Point has a dissolved cesium concentration which is much higher than would be expected from simple mixing between sea water and fresh water and postulates that these higher concentrations result from leaching of cesium from bottom sediment by saline water.
Use of the bioaccumulation factors of Regulatory Guide 1.109 for a f resh water site will thus substantially overestimate fish ingestion doses because no account is taken of the phenomena Just discussed. However, radiocesium concentrations in fish may still be estimated through the use of a bioaccumulation factor, provided that this factor is determined from the body of water at interest.
This factor has been estimated (ref. 2, Table IX-5) to be about 150 for the flesh of indigenous fish caught in the Indian Point area. In contrast, the cesium fresh water bioaccumulation factor presented by Regulatory Guide 1.109 for fish is 2000. Fish ingestion doses would therefore be overestimated by a factor of 13 if the Regulatory Guide ,
value were used.
Similarly, for invertebrates, the site specific bioaccumulation factor of 150 is used. This is larger than the value of 25 given in Eeg.
Guide 1.109 for salt water invertebrates. .
N A second conservatism in the NRC model concerns the location at which the concentrations in the river of the discharged cesium are evaluated.
Use of this model implies that these fish have grown directly in such a location prior to being caught, which is unrealistic and adds about a factor of five (ref. 2) in consSrvation. This conservatism remains -
in the calculation, thus the use of the NYU (Ref. 2) bioaccumulation
- factor is justifiable since this remains as a conservative calculation.
In summary, with the exception of the site specific bioaccumulation '
factors discussed above, all remaining factors are as follows: fish factors are for fresh water and invertebrate factors are for salt water.
ODCM - REV 3 THIS PAGE INTENTIONALLY LEFT BLANK J 16
OM2 - REV. 3 Table 2-1 Site Related Incestion Dose Commitment Factor (Freshwater Fish and Saltwater Invertebrate Comsumption) ;
(Alt )
eram/hr per pCi/mi j
ISOTOPE I BONE LIVER I TOT-90DYI THYROID t MIDNEY t LUNG 1 CI-LLI i 1 0.00E-018 2.99E-018 2 99E-018 2.99E-018 2.99E-018 2.99E-018 2.99E-01 l H-3 ;
C-14 8 3.35E 048 6.71E 038 6.71E 038 6.71E 031 6 71E 031 6.71E 038 6.71E 03 i NA-24 1 4.07E 028 4.07E 021 4.07E 028 4.07E 028 8.07E 028 4.07E 021 4.07E 02 P-32 t 4.95E 071 3.08E 068 1.91E 061 0 00E-011 0.00E-011 0 00E-018 5.57E 06 CR-51 1 0.00E-011 0. 00 E- 011 4.31E 008 2.57E 003 9.49E-018 5.72E 001 1.08E 03 MN-54 1 0.00E-01 5.42E 031 1.03E 031 0 00E-011 1 61E 031 0 00E-011 1.66E 04 MN-56 1 0.00E-011 1 36E 023 2.42E 011 0.00E-018 1 73E 028 0.00E-018 4.35E 03 FE-55 t 3.20E 048 2.21E 048 5.16E 038 0.00E-011 0.00E-011 1.22E 04! 1.27E 04 FE-59 I 5.05E 04! 1 19E 051 4 55E 048 0 00E-011 0.00E-011 3 32E 048 3.96E 05 CO-58 1 0 00E-011 5.14E 021 1.15E 038 0.00E-011 0.00E-011 0.00E-018 1 04E 04 CO-60 1 0.00E-018 1.48E 038 3.26E 03! 0.00E-011 0.00E-011 0.00E-011 2 77E 04 NI-63 1 4.97E 041 3.44E 038 1 67E 031 0.00E-011 0.00E-011 0.00E-011 7.18E 02 NI-65 1 2.02E 02t 2.62E 018 1 20E 018 0 00E-011 0.00E-011 0.00E-011 6.65E 02 CU-64 1 0.00E-011 9.07E 011 4.26E 011 0.00E-011 2.29E 021 0.00E-018 7.73E 03 2N-65 t 1.61E 051 5.13E 05! 2.32E 058 0.00E-018 3 43E 058 0.00E-011 3.23E 05 BR-83 1 0.00E-011 0.00E-011 4.05E 018 0.00E-011 0.00E-011 0 00E-011 5.83E 01 BR-84 1 0.00E-011 0.00E-018 5 25E 011 0.00E-011 0.00E-011 0.00E-011 4.12E-04 ER-85 8 0.00E-011 0.00E-018 2.16E 001 0.00E-011 0.00E-011 0.00E-018 1.01E-15 RB-86 1 0.00E-018 1 01E 051 4.72E 041 0 00E-011 0.00E-011 0.00E-018 2.00E 04 RB-88 1 0 00E-011 2 90E 021 1.54E 028 0.00E-011 0.00E-018 0 00E-018 4.01E-09 RB-89 3 0.00E-018 1 92E 028 1 35E 028 0.00E-011 0.00E-011 0.00E-018 1.12E-11 SR-91 ! 4.73E 021 0.00E-011 1 91E 011 0 00E-011 0.00E-011 0.00E-018 2.25E 03 SR-92 1 1 79E 028 0.00E-011 7.76E 001 0.00E-011 0.00E-011 0.00E-011 3.55E 03 Y-91M t 5 73E-021 0.00E-01t 2.22E-031 0.00E-011 0 00E-011 0 00E-011 1.68E-01 Y-92 1 5.32E-011 0.00E-018 1 56E-021 0.00E-011 0 00E-011 0 00E-01t 9.32E 03 Y-93 1 1 69E 003 0 00E-011 4.66E-028 0.00E-011 0.00E-011 0.00E-018 5 34E 04 2R-95 8 1 63E 00 5.23E-011 3 54E-011 0.00E-018 8.21E-011 0.00E-018 1 66E 03 ZR-97 8 9.02E-021 1 82E-028 8.32E-031 0.00E-011 2 75E-023 0 00E-018 5.64E 03 NB-95 t 4.47E 02t 2.49E 028 1 34E 02t 0.00E-011 2 46E 028 0.00E-011 1 51E 06 MD-99 0.00E-018 1.2BE 023 2 44E 011 0.00E-011 2.91E 021 0.00E-011 2.98E 02 TC-99M I 1 60E-02 4.51E-021 5.74E-011 0.00E-018 6.85E-01! 2.21E-022 2 67E 01 TC-101 ! 1.64E-021 2 36E-028 2.32E-011 0 00E-011 4.26E-01! 1 21E-028 7.10E-14 RU-103 ! 1 10E 021 0.00E-018 4.74E 011 0.00E-011 4.19E 028 0.00E-018 1.20E 04 RU-105 8 9.15E 00t 0.00E-011 3 61E 00t 0.00E-011 1.18E 048 0 00E-018 5.60E 03 RU-106 8 1.63E 028 0.00E-018 2 07E 021 0.00E-011 3.15E 03t 0.00E-018 1 06E 05 AG-110M t 3 02E 02t 2 79E 028 1 66E 021 0.00E-018 5 49E 021 0.00E-011 1 14E 05 TE-125M i 2 72E 03t 9.85E 028 3.64E 028 8.18E 021 1 11E 048 0.00E-018 1.09E 04 1E-129 I 3.19E 018 1 20E 013 7.76E COI 2 45E 018 1 34E 028 0 00E-011 2.41E 01 TE-131M i 1 74E 038 8.59E 021 7.15E 028 1 36E 038 8.70E 031 0.00E-011 0.52E 04 TE-131 1 2.00E 01 8.35E 001 6.31E 001 1 64E 018 8.76E 011 0.00E-011 2.83E 00 TE-132 1 2 56E 031 1 65E 031 1 55E 031 1 83E 031 1.59E 048 0.00E-011 7.82E 04 I*t10 i 4.66E 011 1 44E 021 5.68E 011 1 22E 041 2.25E 028 0.00E-011 1 24E 02 I-131 1 2.69E 02t 3.84E 028 2 20E 028 1 26E 058 6.59E 02t 0.00E-011 1.01E 02 I-132 8 1.31E ott 3.51E 011 1 23E 018 1.23E 038 5.59E 011 0.00E-011 6.59E 00 I-133 1 9.17E 011 1.60E 028 4.86E 011 2.34E 048 2 78E 028 0 00E-013 1 43E 02 I-134 1 6.85E 001 1.86E 018 6.65E 001 3.22E 02t 2.96E 011 0.00E-011 1 62E-02 I-135 1 2.86E 011 7.49E 018 2 76E 018 4.94E 038 1 20E 028 0.00E-011 8.46E 01 CS-134 8 2.77E 044 6.58E 048 5.38E 048 0.00E-018 2.13E 0417.07 E 038 1.15E 03 4
O 17
ON3 - ROI. 3 Table 2-1 (Contimed)
..............................................______..............___.......... t CI-LLI.
I SONE I LIVER 1 TOT-80DYt THYRDID t KIDNEY I LUNG ISOTOPE CS-136 3 2.89E 031 1.14E 048 8.23E 03 1 0 00E-018 6.36E 03: 8.71E 02t 1.30E 03 CS-137 t 3.54E 041 4.85E 048 3.18E 041 0 00E-011 1 65E 048 5.47E 038 9.38E 02 CS-138 1 2.04E 013 f.07E 013 2 02E 018 0 00E-01t 2.99E 018 2 95E 008 1 74E-04 BA-139 t 6 47E 002 4.41E-038 1 90E-018 0 00E-011 4 31E-038 2 62E-031 1 15E 01 BA-141 1 3 14E 008 2 38E-032 1.04E-018 0 00E-018 2.21E-03t 1 35E-031 1 48E-09 BA-142 3 1.42E 003 1 4eE-03! 8 94E-021 0 00E-018 1 23E-031 8 20E-041 2.00E-18 LA-140 1 1.58E 001 7 94E-011 2 10E-011 0 00E-011 0.00E-012 0.00E-011 5 83E 04 LA-142 8 8.06E-028 3 47E-028 9 14E-038 0 00E-011 0.00E-011 0 00E-018 2 47E 02 CE-141 1 3.23E 001 2 18E 001 2 47E-011 0.00E-011 1.11E 001 0.00E-012 8 34E 03 CE-143 I 5.69E-018 4.20E 021 4.45E-02% 0.00E-018 1 65E-011 0 00E-018 1 57E 04 CE-144 8 1 68E 028 7 03E 011 9.03E 003 0 00E-011 4.17E 011 0 00E-018 5 49E 04 PR-143 8 5.80E 008 2 32E 008 2 87E-011 0.00E-018 1 34E 003 0 00E-018 2 54E-09 PR-144 1 1 90E-021 7 88E-038 9.44E-048 0.00E-018 4.44E-031 0.00E-Ott 2.73E-09 ND-147 t 3.96E 001 4.58E 001 2.74E-011 0 00E-018 2.48E 003 0 00E-012 2 20E 04 W-187 i 2 98E 02! 2.49E 028 8,70E 011 0.00E-011 0.00E-018 0 00E-018 8.15E 04 NP-239 1 3.55E-021 3 49E-031 0 00E-011 0.00E-011 1.09E-02t 0.00E-011 7.15E 02 e
e 18
l j ll lllll ll I
)!l1 j1 1l lI I ; \1lII\)l! ,
Sf **
.?
r r r r e e e e r v v v v e i i i i v
R R R R i R
~
> - & y >
8 _
1 R .
m e
t r s y
o S t
ik t nn 3 n i
oa 2 e MT R u l
f f
~ ,* g E
eae 1
g 0 t r -
n sg 2 .
miDa-i _
s e ns r we oc g
n e vw u
g do i O i o i .
wr es t s tl F oP se cF l
ac r a .
Be e 0 _
t Wor h t 1 l s g a d P a P im W a IW H r R
- a e -
nl 3 c I d .
OA i i u
9 2 v q _
1 6 r i R R e L S
-" O ; _
i s
r s r g t e o b n i l t n o a p a i o
rn u t l d U _
ew d t l C ._
no) l osi r o* Hk u e r ed4 /nB l o G w( H )
ya o t -.
o 3 e "* ( rT . o o *
} ml d n C M aB t n
. e a u i
n U _
t m h a d a C S
- I A F F g
GKA - RW. 3 i 3.0 CASE 00S EFFLUENTS 3.1 caseous Effluent Releases - General Information 3.1.1 The surveillance and lower limit of detection requirements for gaseous radioactive effluents are contained in section 3.4 of the technical Specifications. All releases at IP3NPP are assumed to be ground level so there are no elevated releases.
3.1.2 A completed and properly authorized Airborne Radioactive Waste Release Permit shall be issued prior to the release of airborne activity from the waste gas holding system, and containment purge.
The unit shall maintain Airborne Radioactive Release Permits for the life of the plant.
3.1.3 One half of the derived Ci/sec. instantaneous limits delineated in section3.2.lare applicable to IP3NPP since it is a two unit site. The time-average limits presented, in 3.2.2, 3.2.3 and 3.2.4 are "per reactor" limits, and the full Ci/ sea limits are applicable to IP3.
3.1.4 During normal operations without a primary to secondary leak, almost all gaseous ground level releases occur ;
through the main plant vent, - with a neglibigle amount released from the Administration Building and the Radio-active Machine Shop. However, in the event of a leak, I the blowdown flash tank vent and condenser air ejector releases shall be added to those from the main plant vent for the purpose of determining if total release criteria are met.
3.1.5 For releases that are expected to continue for periods over two days a new release permit will normally be issued each day. Containment purge release permits may be termi-nated at the discretion of the RESS and be considered as a continuous release until the purge is terminated.
However, when plant conditions change that will cause the activity in containment to significantly change a new permit shall be issued.
3.1.6 Assurance that the cocbined gaseous releases from Units 2& 3 do not exceed section 3.2,.111mits for the site is provided by administrative controls agreed to in the Memor-andum of Understanding (016) between con Edison and the j Power Authority concerning gaseous effluent discharge j and the requirements of the document.
3.1.7 By mutual agreement with Con Edison's IP2NPP >Ntch Super- ;
visor and the Power Authority's I?3NPP Shift Supervisor, one unit can reduce or eliminate discharges for a period of time to allow the other unit to use the full site permis- f sible discharge rate, or a specific portion thereof, for [
a discharge when necessary. l f
s i
00CNoItV.3 t
3.1.8 Conservative release rate limitations have been established to i aid in controlling time average dose limits. The annual average i limit shall be used for calculating limitations on discharge. If this limit restricts eperating flexibility the quarterly average limit may be used by the Shift Supervisor as long as releases for the calendar month stay within the quarterly averagc and the Operations Superintendent is in agreement. The Shift Supervisor may use the instantaneous limit for release if the Superintendent of Power is in agreement. The instantaneous limit should be checked by the Radiological and Environmental Services Department when !
applied.
When the instantaneous limit applies the monitor response should i be averaged over a one hour time interval. ,3 >
3.1.9 Containment Pressure Reliefs Containment pressure reliefs occur on a frequent enough basis to be considered continuous and are sampled as part of the plant -
vent release path. However, to ensure that the release rate will '
not be exceeded, the containment noble gas monitor (R-12) and the expected flow rate are used to calculate a release rate. The effluent noble gas monitor in the plant vent is used to verify these calculations. (REF. NUREG 0472 REV 3 DRAFT 6 TABLE 3.1-13) 3.' 10 Ceeposite Particulate Sanples One of these methods will be used to obtain a composite sample:
- 1. Samples will be taken weekly and intei~ated monthly, or j
- 2. Samples will be taken weekly and counted together once per month. ,
-(REF. NUREG 0472 REV 3 DRAFT 6 TABLE 4.11-12) 3.1.11 Cas Storage Tank Activity Limit The noble gas activity limit of 50,000 Ci in the gas storage tanks was calculated using the equations frem Section 5.6.1 of l NUREG 0133 and the following parameters: ,
Kg = 294 rrem - m 3, Xe-133 equivalent Table B-1 uC1 yr Reg. Guide 1.109 [
~3 s-m"3, Indian Point 3 FSAR X/Q = 1.03 x 10 9 it 7 j 500 arem (3.15 x 10 sec/ year
~
6 10 uCi/Ci(294 arem m ) 1.03 x 10 s,3 uC1 yr e , ,
N it = 52,011 C1-50,000 C1 (
21 ;
WCR-t[V,3 3.1.12 Cas Storace Tank Activity - Surveillance Recuirements There are two methods available to ensure that the activity in the gas storage tank is within the 50,000 Ci, Xe-133 equivalent concentration:
- 1. Cas samples of the tank 5scontents which are less than 430 uci ce"1 will ensure that there are less than 50,000 Ci in the tank.
- 2. The waste gas line monitor R-20 will have an exposure rate
, to activity concentration conversion factor which will also allow for activity determinations. (REF NUREG 0472 REV 3 DRAFT 6 3.11.2.6) 3.1.13 The ventilation flow rate utilized to monitor environmental releases from the Administrative Building Controlled Area and the Radioactive Machine Shop shall be the system's design flow rate. The system design flowrate for the Administration Building and the Radioactive Machine Shop is 12,500 and 33,750 cubic feet per minute respectively.
Using the system design flowrate will result in a con-servative quantification of releases as the flowrate cannot exceed design. (REF NUREG 0472 REV 3 DRAFT 6 TABLE 3.3-13) 3.1.14 The activity released via the bicwdown flash tank vent if determined as follows. The release rate of radioactivity from the steam generator blowdown is determined. The partition factors for the blowdown flash tank vent as listed in Regulatory Guide 1.42 "Interim Licensing Policy On As Low As Practicable for Gaseous Radiciodine Releases from Light Water Cooled Nuclear Power Reactors" are then, applied to determine how much activity is being released via the blowdown flash tank vent. (REF NUREG 0472 REV 3 DRAFT 6 TABLE 3.3-13) 3.2 Caseous Effluent Dose Calculation Requirements 3.2.1 Section 2.4.1 of the Technical Specifications requires that the dose rate due to radioactive materials released in gaseous effluents from the site at or beyond the site boundary shall be limited to the followings a) For noble gases: less than or equal to 500 mrom/yr to the total body and less than or equal to 3000 mrem /yr to the skin, and b) For all radiciodines and for all radioactive materials in particulate form and radionuclides (other than noble gases) with half lives greater than 8 days less than or equal to 1500 mrem /yr to any organ.
The methodologies for performing these calculations are discussed in section 3.3.1 and 3.3.2, respectively.
WCA - RW. 3 3.2.2 Section 2.4.2 of the Technical Specifications requires that the air dose due to noble gases released in gaseous i effluents from each reactor unit at or beyond the site boundary shall be limited to the following: .
e) During any calendar quarter: less than or equal i to 5 mrad for gamma radiation and less than or equal [
to 10 mrad for beta radia*, ion.
I b) During any calendar years less than or equal to
- 1. 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation. :
The methodology for calculating these dose rates is discussed in Section 3.3.3. ,
Note: If either of the above limits is exceeded by a factor of two or more, then cumulative dose contri-butions from direct radiation would be determined ,
- by evaluation of existing perimeter and environmental TLDs per Tech. Spec. 2.6.8.
3.2.3 Section 2.4.3 of the Technical Specifications requires that the dose to a member of the general public from Iodine-131, tritium, and radionuclides in particulate form with half-lives greater than 8 days in gaseous of-fluents released from each reactor unit shall be limited to the followings a) During any calendar quarter: less than or equal to 7.5 mrom to any organ and I b) During any calendar years less than or equal to 15 j mrom to any organ.
Cumulative dose contributions fot the current calendar .
quarter and current calendar year shall be determined at least once every 31 days, i
i The methodology for calculating these dose rates is discussed in section 3.3.4. ,
j Note: If either of the above limits is exceeded by a l i
factor of two or more, then cumulative dose contributions .
from direct radiation would be determined by evaluation I of existing perimeter and environmental TLDs per ;
Tech. Spec. 2.6.5.
I i
i L
I
- __.fl _ . . _ __ __ _ _ _ . , _ _ _ __ _
ON3 - REV. 3 3.2.4 section 2.4.4 of the Technical Specifications requires that for each reactor unit, the appropriate portions of the gaseous radweste treatment system shall be used to reduce radioactive effluents in gaseous waste prior to their discharge when projected gaseous effluent air dose at the site boundary when averaged over 31 days, would exceed 0.2 mrad for gamma radiation. 0.4 mrad for beta radiation. These doses are projected bered on the dose methodology discussed in section 3.3.3 (gas) and 3.3.4 (iodine) and the average previous months' doses are is used to project future doses. The appropriate portions of the ventilation exhaust treatment system shall be
.used to reduce radioactive materials in gaseous releases when the projected doses when averaged over 31 days, would not exceed 0.3 mrem to any organ (at nearest residence).
Dose due to gaseous release from the site shall be cal-culated at least once every 31 days.
3.3 Dose Methodology (Computer Calculation) 3.3.1 Instantaneous Dose Rates - Noble Gas Releases When the instantaneous limit applies the monitor response should be averaged over a one hour time interval. 3 3.3.1.1 The equations developed in this section are used to meet the calculational requirements of paragraph 3.2.1. The magnitude of this pathway is the same for all age groups to there is no critical group. Based on an agceement with Consolidated Edison, IP3NPP utilizes 50% of the site release limit as measured in Ci/see which translates to 63% of the applicable dose rate limit for Noble gas releases. Each unit has different dispersion factors due to their relative positions to the critical sector of the unrestricted area boundary. The conversion from dose rate to Ci/sec was determined with the use of a finite cloud exposure model. The methodology is dis-cussed in Section 3.6 A calculation showing the relationship between Ci/see and dose rates f rom Units 2 and 3 is shown in Appendium 3-A. The equations for calculating the dose rato limi-tations are obtained from NUREG 0133 (Bef. 1 Section
- 5.1). Utilising the above assumptions, these equations reduce to the following:
T (Ki l (X/0) (Oil = 317 mrem /yr whole body .
1 __
1 (Li + 1.1 Mil (X/O (01) = prem/yr skin i
! (sil (x/O (Oil = 2046 mrem /yr to the skin a
24
NCA o ity, 3 i
where Ki = the total body dose factor due to gamma emissions for each identified noble gas radionuclide, in mrom/yr per uci/m3 . (finite cloud correction included)
Li = The skin dose f actor due to beta emissions for each identified noble gas radionuclide, in arem/yr per uci/m3 .
Mi = The air dose factor due to gamma emissions for each identified noble gas radionuclide, in mrad /yr per uCi/m3 (finite. cloud correction included) ;
Ni = The air dose factor due to beta emissions for each identified noble gas radionuclide, in mrad /yr per uCi/m3 .
(Li + 1.1 Mil in prem/yr Si = The total skin dose factor. ;
3 per uci/m .
Qi = The release rate of radionuclides, i, in gaseous effluent for all release points in uCi/sec.
(X/Q) = For all vent roleses, the highest calculated annual average relative concentration for any area at the unrestricted area boundary, 3.0 E-5 sec/m3 in the SW sector at 350 meters.
The Ei, Li, Mi, Ni and Si factors were obtained from Table B-1 of Regulatory Guide 1.109 and are included in this document as Tables 3-4, 3-5, 3-6, 3-7, and 3-8 respectively. The Ei, Mi, and si factors have a finite cloud correction factor included. ,
3.3.1.2 These equations can also be expressed in the following manners E (Qt) = mrem /yr (dose to whole bodg (L + 1.1 H) (Qtv) =
IS) ( Qt) ,= mrem /yr(dose to the skin )
i
Qt = Tue release rate of all noble gases summed together in uCi/sec.
i Qt = I Qi I= (1/Qt) E QL Ei )
Ki = Ki (X/Q) 5~ = (1/Qt) I( Qi LD Ei = Li (X/Q) k = (1/Qt) E(Qi 51) l Mi - Mi (X/Q) 5= (1/Qt T( Qi III) 51 = Ni (X/Q)
'5 = (1/Qt) E( Qi 51 ) .
i being the 51 = Si (X/Q), where the summations are from i to .n ith nuclide.
Th'e- values of 5, 5, 5, 5 and S are listed in Table 3-9 for the unrestricted area boundary.
3.3.2 Instantaneous Dose Rates - Radiciodines and Particulate Releases The equation developed in this section is used to meet the calculational requirements of Paragraph 3.2.1.b.
The critical organ is considered to be the child thyroid i as stated in section 4.0 of the Technical Specifications.
Based on a previous agreement with Consolidated Edison, IP3NPP utilises 50% of the site release limit as measured in Ci/sec which translates to 71% of the applicable dose rate limit. This is a . result of the dif ferent dispersion
' factors for each unit due to their relative positions to the critical sector of the unrestricted area boundary.
A calculation showing the relationship between ci/sec released and dose rates from units 2 and 3 is shown in Appendix 3-A. The equation for calculating the dose I
rate limitation is obtained from NUREG-0133 (Ref. 1, Section 5.2.1, Pg. 25). Utilising the above assumptions ;
this equation reduces to the following: 3
{ Pj (W Q{} <1070 mrom/yr E
NCR RDI 3 where Pi(in) = The dose parameter for radionuclides other than noble gases for the inhalation pathway in mrom/yr per uCi/m3 The dose factors are based on the critical individual organ and most restrictive age group which is the child thyroid.
.i = The release rate of radionuclides, i, in gaseous effluents for all release points in uci/sec.
W = The highest calculated annual average dispersion parameter for estimating the dose to an individual at the controlling location due to all vent releases (see section 3.5).
W(in) =
3.0E-5 sec/m3, for the inhalation pathway release. The location is the unrestricted area boundary in the SW sector. at 350 meters.
3.3.2.a Calculation of Pitin): Inhalation Dose Factor Pi (inhalation) = K' (BR) DFAi (mrem /yr per uCi/m3) where K' = A constant of conversion,106 pCi/uci BR = The breathing rate of the child age group (3700m3/yr) from Table E-5 of Regulatory Guide 1.109.
DFAi = The thyroid inhalation dose f actor for the child age group for the ith radionuclide, in mrem /pci. Taken from Table E of Regulatory Guide 1.109. These values are reproduced in Table 3-la Resolution of units yields:
Pi (inhalation) = 3.7E09 DFAi i
3.3.3 Time Average Dose - Noble Gas Release 3.3.3.1 The equations in this section are used to meet the cal-culational requirements of Paragraphs 3.2.2 and 3.2.4.
t All releases at IP3NPP are assumed to be ground level so there are no elevated releases. The magnitude for this pathway is the same for all age groups so there is no critical group. Dispersion parameters are discussed
- in Section 3.5.
l 3.3.3.2 The equations for calculating the dose limitations are obtained from HUREG 0133 (Ref. 1. Section 5.3). The i
doses are evaluated at the unrestricted area boundary in the worst meteorological section (SW sector at 350 meters). These equations reduce to the following:
ODCM - t(V. 3 l
i a) During any calendar quarter, for gamma radiation:
3.17 x 10-8 iMi ((x/Q) Oi + (x/q qi < $ mrad '
during any calendar quarter for the beta radiations j
((X/Q) Di+(x/q) qi) 110 mrad 3.17x10*8[N i b) during any calendar year for gamma radiation:
((x/O Di + (x/q) qi) 110 mrad 3.17x10-8[M i ,
during any calendar year for beta radiations:
3.17 x 10-8 [Ni ((X/O) '61 e (x/q) qi) < 20 mrad where: !
(x/Q) = The highest calculated annual average l relative concentration for the unrestricted area boundary in the SW sector at 350 I meters for long term releases (greater !
than 500 hrs / years), 3.0 E-5 sec/m3 . !
(x/q) = The relative concentration for the unrestricted area boundary for short term releases (equal to or less than 500 hrs /
year),intheSWsectorat350 meters.
This value is :alculated as per Section 3.5.
Mi
= The air dose factor due to gamma emission
- for each identified noble gas radionuclide .
in nrad/yr per uCi/m 3. i
= the air dose factor due to beta emissions Ni for each identified noble gas radionuclide, in mrad /yr per uC1/m 3.
" = The average release of noble gas radio-f1 nuclides in gaseous effluents, i, for ,
short term releases (equal to or less !
than 500 hrs /yr) from all vents, in ;
uCi. Releases shall be cumulative over the calendar quarter or year as appropriate. [
(,A
= The averags release of noble gas radio- l nuclides in gaseous effluents, i, for long term releases (greater than 500 [
hrs /yr) from all vents, in uct. Releases shall be cumulative over the calendar j quarter or year as appropriate. ;
l
- l i
f
,o !
OKA o 10. 3 3.17 x 10-8 = The inverse of the number of seconds in a year.
The air dose factors Mi and raiiwere obtained from Table 3-1 of Regulatory Guide 1.109 and are listed in Table 3-6 and 3-7 respectively. The M air dose factors are finite . cloud corrected ,
3.3.4 Time Averaeed Dose - Radioiodines and Particulates 3.3.4.1 The equations in this section are used to meet the calculational requirements of Paragraphs 3.2.3 and 3.2.4. All releases at.2P3NPP are assumed to be ground level so there are no elevated releases. Only the infant and child factors are esiculated for the purpose of this manual, since they are the most restrictive age groups, NUREG 0133 (Ref. 1, section 5.3.1, Page 31) 3.3.4.2 The pathways considered in this analysis are inhaletion, ground plane, vegetable ingestion and milk ingestion.
The meat ingestion pathway is not considered because of the high degree of commercial, industrial and resi-dential land usage in the area, and the fact that this pathway was not indicated within ten miles of the plant.
The inhalation, grovad plane and vegetation ingestion pathways only are assumed to exist at the nearest residence in the worst meteorological sector, which is the SSW sector at 1526 meters. Since no real cow exists within 5 miles of the plant, a hypothetical cow has been placed at 5 miles in the worst meteorological sector, which is the SSW. All 4 pathways will be considered at this secondary receptor. Calculated doses for the nearest resident and the secondary receptor will be compared and the higher calculated dose will be reported.
3.3.4.3 The equations for calculating the dose limitations are obtained from NUREG 0133 (Ref. 1, Section 5.3).
These equations reduce to the following:
During any calendar quarter 3.17 x 10*8 I Ri (W Di + w 'qi) 1 7.5 mrem i
During any calendar years 3.17 x 10-8 Igg (w gg 4 w'qi l i 15 mrem i
't SQ
OKA = ttV. 1 j i
where: ;
s og = The plant releases of radiciodines and radioactive i materials in particulate form with half lives !
greater than eight days, for long term releases I greater than 500 hr/yr, in uC1. Releases !
shall be cumulative over the calendar quarter ;
or year as appropriate.
41 = The' plant releases of radiciodines and radioactive ;
materials in particulate form withhalf lives l greater than eight days, for short term releases !
equal to or less than 500 hrs /yr, in uC1.
Releases shall be cumulative over the calendar ;
quarter or year as appropriate. f W = The dispersion or deposition parameter (based ,
on meteorological data defined in Section 3.5) for estimating the dose to an individual ;
at the controlling location for long term ;
releases (greater than 500 hrs /yr):
Wn (in) = The highest calculated annual average dispersion .
parameter for the inhalation pathway for the ;
nearest residence in the unrestricted area e located in the ssW sector at 1526 meters, 2.7 E-6 sec/m3 Wn (dep) = The highest r'alculated annual average deposition ,
parameter for the nearest residence in the ,
unrestricted area located i the S sector ,
at 1279 meters, 8.7 E-9 m W,(in) = The calculated annual average dispersion parameter ,
for the inhalation pathway for the secondary ;
receptor located in the ssW sector at 5 miles, .
2.90-7 sec/m3 W,(dep) = The highest calculated annual average deposition '
parameter for the secondary receptor located in the S5wsector at 5 miles, 4.7E-10 m-2, l l
W = The vent dispersion or deposition parameter L for estinating the dose te an individual at !
the controlling location for short term releases !
(equal or less than 500 hrs /yr) calculated f
+
as in section 3.5.
3.17 x 10*8 = The inverse number of seconds in a year, j i
Rg
= The dose factor for each identified pathway, ,
organ and radionuclide, i, in ma - krem/yr ;
per uCi/see or aren/yr per uCi/m3 These j dose factors are determined as described in l 3ections 3.3.4.5a-d. ,
l
.. I l
l I
mRn - RW. 3 3.3.4.4 Utilizing the assumptions contained in section 3.3.1.2, these equations for the nearest resident and the secondary receptor respectively, reduce.to the following Qg = 3.17E-08 I{ RI I(W n IIDI 91 + "n(in) qi) } +
i i
((RG+RV) (Wn (dep) Di + En (dep) qi)}
i i D
S = 3.17E-08 { R j W (in) Di + ws (in) hi) +
I
{(RG + RchV R ' (W (dep) 61 + ws (dep) hi)}
i 'l s 1 7.5 mrem Quarterly 1 15 mrem Annual Note: The subscript a refers to the secondary receptor and the subscript n refers to the nearest residence.
3.3.4.5 Calculation of Dose Factors
- a. Calculation of RIl (X/0) Inhalation Pathway Factor 3
RiI (X/Q) = K' (BR) a (DFAila (mrem /yr per uCi/m where:
Constant of unit conversion, 106 pCi/uci K' =
(BR)a = Breathing rate of the receptor of age group (d)in M 3 /yr (DFAi)a = The maximum organ inhalation dose factor for the receptor of age group (a) for the ith radionuelide, in mrem /pci. The total body is considered as an organ in the se-
! lection of (DFhi)a' Ostly the child and the infant R factors are needed for the purpose of this manual, since they are the most restrictive groups. The (DFAi)a values are listed in Table 3-la and 3-lb respectively.
1 Breathing rates l
Infant = 1400 (m 3/yr)
- Child = 3700 (m3/yr)
- l The values of (BR), (DFAi) and (DFAi) were obtained from Tables E-5, E-9 and E'10 respectively of Regulatory Guide 1.109.
l
ODCM - RDi. 3 3.3.4.5 b calculation of R G4 (D/0) Ground Plane Pathway Factor RG (D/Q) = K'K" (SP) (DFGi (1-e /Ai)
(m2 x mrem /yr per uCi/sec) where K' = A constant of cor: version, 106 pCi/uci K" = A constant of conversion, 8760 hr/yr Ai = Deca constant for the ith radionuclide sec- .
t = The exposure time, 4.73 x 108 see (15 years)
DFGi = The ground plane dose conversion factor for ith radionuclide (mrem /hr per pCi/m 2)
SF = Shielding factor (dimensionless) = 0.7 from Table E-15 of Regulatory Guide 1.109.
The values of DFGi were obtained from Table E-6 of Regulatory Guide 1.109. These values were used to calculate RG i, which is the same for all age groups and is listed in Table 3-2.
3.3.4.5.c calculation of RC (D/0) - Grass-cow-Milk Pathway Factor RC (D/Q) = K' Q7 (Uap) Pm fr) (DFL4) a x A i +Aw fp fs + (1-f ps f )e A it.h _A (e itf)
Yp Y s
where K' = Constant of conversion, 106 pCi/uci Q7
= Cow's consumption rate, in kg/ day (wet weight)
Uap = Receptor's milk consumption rate for age (a), in liters /yr.
Yp = Agricultural productivity by unit area of pasture grass, in kg/m 2, Y, = Agricultural productivity by unit area of stored feed, in kg/m 2,
= Stable element transfer coefficients, Fm in days / liters.
r = Fraction of deposited activity retained on cow's feed grass.
.99. -
OFJ - RBl. 3 (DFLi la= The maximum organ ingestion dose factor for the ith radionuclides for the receptor in age group (a) in mrem /pci. Values are f rom T. ables E-13 and E-14 of Regulatory Guide 1.109 and are listed in Table 3-3a and 3-3b.
11 = Decay cor.s;ent for the ith radionuclide, in sec-1 Aw = Decay constant for removal of activity on leaf and plant surfaces by weathering, 5.73 x 10-7 sec -1 (corresponding to a 14 day halflife).
tg = The transport time from pasture, to cow, to milk, to receptor in sec.
th = The transport time from pasture, to harvest, to cow, to milk, to receptor,
~
in sec.
fp = Fraction of the year that the cow is on pasture, fs = Fraction of the cow feed that is pasture grass while the cow is on pasture.
The concentration of tritium in milk is based on the airborne concentration rather than the deposition.
Therefore, the RCi is based on X/Q:
R g (X/Q) = K'K'"F O Um F ap(DFLi)a0.75(0.5/H)
(mrem /yr per uCi/m 3) where K'" = A constar.t of unit conversion, 103 gm/kg.
H = Absoluto humidity of the atmosphere, in gm/m3 . -
0.75 = The fraction of total feed that is water.
0.5 = The ratio of the specific activity of the feed grass water to the atmospheric water, and other parameters and values are given above. The value of H may be considered as 8 grams / meter 3, in lieu of site specific information.
- 01 - try, 3 RC Parameters are taken from the following sources:
i Parameter Value Table (R.G. 1.109 r (dimensionless) 1.0 for radioiodine E-15 0.2 for particulates E-15 Fm (days / liter) Each stable element E-1 Uap (liters /yr) a infant 330 E-5
- child 330 E-5
- teen 400 E-5
- adult 310 E-5 (DFL1)a(mrem /pCi) Each radionuclide E-ll to E-14 Yp(kg/m 2) 0.7 E-15 Y s (kg/m 2) 2.0 E-15 tg (seconds) 1.73 x 105 (2 days) E-15 th (seconds) 7.78 x 106 (90 days) E-15 Of (kg/ day) - 50 E-3 fs *
- f sand f are assumed to be unity p
fp Only the RC values for the child and the infant are calculated for the i
purpose of this manual as they are the most restrictive age groups.
Ingestion dose factors for these two age groups are given in Tables 3-3a and 3-3b.
l l
I
~ -~- - - -- , - - . , . , _ _ _ ._, ,
9 ON3-RG.3 3.3.4.5.d Calculation of RiV (D/0) - Vegetation Pathway Factog g ie" i h t
RV (D/Q) = K' (r) (DFL)aUffe-AltL+Usg i t Yy (A i + A w) where:
k' = Constant of conversion, 106 pci/uci UL = Consumption rate of fresh leafy vegetation by the a receptor in age group (a), in kg/yr.
U = Consumotion rate of non-leafy vegetables by the receptor in a age grbup (a), in kg/yr.
ft
= The traction of the annual intake of leafy vege- -
tation grown locally.
fg = The fraction of the annual intake of non-leafy vegetation grown locally, tn = The average time between harvest of leafy vege-tation and its consumption, in seconds.
th = The average time between harvest of stored vege-tation and its consumption, in seconds.
Yy = The vegetation area density, in kg/m2 All other factors are defined in the Calculation of Grass-Cow-Milk Pathway Factor Section 3.3.4.5.c a( this nanual.
4
'e 4
ON3 - RW. 3 I R Parameters Are From The Following Sources:
1 l
Parameter Value Table (R.G. 1.109 r (dimensionless) 1.0 for radioiodines E-15 0.2 for particulates ;
(DFLi )a (mrom/pCi) Each radionuclide E-ll to E-14 UL (kg/yr) - infant 0 E-5 a
- child 26 E-5
- teen 42 E-5
- adult 64 E-5 US (kg/yr) - infant 0 E-5 ,
a
- child 520 E-5
- teen 630 E-5
- adult 520 E-5 L (dimensionless 1.0 E-15 9
fg (dimensionless) 0.76 E-15 8.6 x 104 '( l day ) E-15 tt (seconds) th (seconds 5.18 x 106 (60 days) E-15 Yy (kg/m2 ) 2.0 E-15 The concentration of tritium in vegetation is based on the airborne concentration rather than the deposition. Therefore, the R V is based on X/Q:
i R{ X/Q = K'K"'{ U LfL + U Sf }g(DFL )a1 (0.75(0.5/H)) (mrem /yr per uCi/m3) l where all terms have been defined above and in the grass-cow-milk pathway calculation section of this manual. (DFL1)a for the child are given in Table l
3-3a.
l 8
3.4 Backup-Simplified Dose Methodology The dose calculation' procedures described in this section are intended to serve as a backup only. They will be implemented whenever the computer implemented procedures canr.ot be followed.
3.4.1 Instantaneous Dese Rates - Noble Gas Releases When the instantaneous limit applies the monitor response should be averaged over a one hour time interval. 3 3.4.1.1 This section describes the alternative calculational method to meet the requirements of Paragraph 3.2,1. The purpose of this method is to provide a calculational technique which is readily amendable to hand calculation and yields conservative results.
3.4.1.2 To 6.' ermine an acceptable noble gas instantaneous releasie rate, a standard isotopic mixture of noble gases is assumed. This isotopic mixture was measured for a mixture of isotopes typical of the condenser air ejector with a steam generator tube leak.
This requirement is evaluated at the worst sector of the unrestricted area boundary. Based on this isotopic mixture ,
standard K L M , and S (subscripts denote weighted sum see s
Table 3-107,ca$,bedetermiEedusingthetechniquepresentedin paragraph 3.3.1.2 and Ki, Li, Mi, Ni, and Si values from Table 3-9. The data and results of this calculation are shown in Table 3-10.
3.4.1.3 The isotopic mixture chosen was obtained from a condenser air ejector sample during a past primary to secondary leak. Table 3-10 contains the mixture data and the fractional relative abundance of each isotope.
These standard factors can be used with the equations and limits presented in Section 3.3.1. The instantaneous dose rate equations then reduce to the following:
Dose to whole body; K, x (Qtv) < 317 mrem /yr Dose to skin; l S, x (Qtv) < 2046 mrem /yr 3.4.1.4 Utilizing the equations from Paragraph 3.4.1.3 and the values from Table 3-10, maximum release limits for all noble gases in l
i uC1/see can be calculated as follows:
These equations can be solved to yield a maximum instantaneous l release rate as follows:
l Qtv = 317 = 317 = 1.63 E04 uCi (Whole Body) l i K .0194 See Qtv = 20I6 = 2046 = 3.01 E04 uCi (Skin)
.0679 Sec S,
i 37
" ODCM - REV 3 3.4.2 Instantaneous Dose Rates - Radioiodines and Particulates 3.4.2.1 This section describes the alternative calculational i method to meet the requirements of paragraph 3.2.1.
The purposes of this method is to provide a calculational technique which is readily amendable to hand calculation i and yields conservative results.
3.4.2.2 To determine an acceptable iodine and particulate release rate it is assumed that the limit on these releases shall be met if the total noble gas concentration in the VC is at least a factor of 20,000 more than the concentration
~
of radioiodine and long lived particulates. This has historically been the case and this assures that the noble gas activity will be limiting.
3.4.2.3 The thyroid is the critical organ for gaseous releases of iodine and particulates typical of IP3NPP, based on analysis performed in Reference 4.
3.4.2.4 In performing this analysis only the child thyroid inhalation pathway at the worst annual average X/Q unrestricted area boundary sector is considered.
3.4.2.5 All iodines and particulates detected are assumed to be I-131 for the purpose of these calculations, which is a conservative assumption since this isotope has the highest thyroid dose factor of all iodines and particulates.
3.4.2.6 The assumptions presented in the previous paragraphs can be used with the equation presented in section 3.3.2 to determine the instantaneous dose rate.
D = (P(in) WB(in)Q < 1070 mrem /yr to the child thyroid where D = The dose in prem/yr P(in) = The dose parameter of I-131 for the in-halation pathway, 1.62E07 mrem /yr per uCi/m 3 WB(in) = The highest calculated annual average dis-persion parameter, for the inhalation pathway at the unrestricted area boundary ig the SW sector at 350 meters, 3.0 E-5 seg/m Note: Subscript B refers to site boundary.
O = The total plant relear.e rate of all iodines and particulates summed together in uCi/sec.
38
_ - . _ . _ - _ . _ _ - .=
ON2 - MN. 3 3.4.2.7 These equations.can then be solved to yield an estimate of the maximum allowable release rate as follows:
Qv = D , where (P(in) WB(in))
D = 1070 mrem /yr, and the denominator equals 486 mrem a_(See uCi yr.
Appendix 3-As instantaneous release rate Qv = 1071 = 2.2 uCi/sec 486 3.4.3 Time Averaged Dose - Noble Gas Releases
> 3.4.3.1 This section describes the alternative method of meeting
" the requirements of Paragraphs 3.2.2 and 3.2.4 and the alternative method of implementing the calculation techniques presented in Section 3.3.3.
3.4.3.2 On a monthly basis collect the analytical results of all noble gas samples required by the surveillance requirements for IP3NPP.
3.4.3.3 A value of lit ' I st I5 t* IIt and llt is determined for each release usino the dispersion parameter for the site boundary in the worst sector. The calculation is as follows:
KI = Ki (X/Q) l Li - Li (X/Q)
Mi = Mi (X/QJ l
Ni a Ni (X/Q)
Si = Si (X/Q) f where Ki = The total body dose factor due to gamma emissions for each identified noble gas radionuclide, in mrem /yr per uCi/m 3, (finite cloud correction used)
Li = The skin dose factor due to beta emissions for each identified noble gas radionuclide in mrem /yr per uC1/m3, Mi = The air dose factor due to gamma emissions for each identified noble gas radionuclide, in mrem /yr '
per uCi/m 3. (finite cloud correction used)
Ni = The air dose factor due to beta emissions for each identified noble gas radionuelide, in mrad /yr per uCi/m 3.
l
- __ _ ? - . . _
OKM - RW, 3 Si = The skin dose factor due to beta and gamma emissions for each identified noble gas radionuclide, (Li
+ 1.1 Mi) in mrem /yr per uCi/m 3. (finite cloud corrected M used)
(X/Q) = The highest calculated annual average dispersion parameterforthenoblegasgathwayattheunrestricted area boundary, 3.GE-05 sec/m Determine weighted average d'ose factors as follows:
All values of Ki, Li, Ei, Ei, and Si are shown in Table 3-9 for the unrestricted area boundary.
E Ct = Ci i
Kt = (1/Ct) E Ki Ci i
Lt = (1/Ct) E Li ci i
Mt = fl/Ct) E Hi ci i
Nt = (1/Ct) E Ni C'i i
St = (1/Ct) E Si Ci i
where:
Ci = Concentration of isotope 1 (uci/cc) in analysis, t Ct = Concentration of all noble gas isotopes (uci/cc) for a specific analysis, t Calculate resultant doses and compare with limits:
Considering both the continuous and batch releases, determine the total weighted average M and N factors for the calendar month. Utilizing the highest calculated (X/Q) for the site boundary; add the resulting value of:
3.17 E-8 gr x total uCi released x (M (77Q) t and Wt II7D I' s
to the appropriate values for the current calendar quarte'r or calendar year. Compare these sums to the limits of Section 3.2.2 and 3.2.4.
3.4.4 Time Averaged Dose - Iodines and Particulates 3.4.4.1 This section describes the alternate method of meeting the requirements of Paragraph 3.2.3 and 3.2.4 and of implementing the calculational techniques presented in Section 3.3.4.
40 -. -.
OKR - RD/, 3 3.4.4.2 on a monthly basis collect the analytical results of iodines and particulates samples required by the surveillance requirements, for IP3NPP.
3.4.4.3 The activity of I-131 and particulate released for each weekly sampling period, are summed together to get the total activity released for the month, prorating when time periods overlap the monthly periods. This value is then divided by the time in seconds for the month to find Qt in uCi/sec. the average release rate for the month. To simplify the calculations, all measured iodine and particulate activity (with a half-life greater than 8' days) is assumed to be I-131.
3.4.4.4 Determine the monthly dose and monthly time averaged fraction of the quarterly dose requirements in Paragraph 3.2.3. At the nearest residence the inhalation and vegetation pathways are considered. At the secondary receptor as defined in Section 3.3.4.2 the cow-milk, and inhalation pathways are considered. Because of the cow-milk pathway, the infant is considered the critical age group at the secondary receptor. At the nearest resident the child age group is critical. For both receptors the ground plane pathway is omitted because it is relatively insignificant. Incorporating these assumptions, the equations from section 3.3.4.4 can be simplified as follows:
Child Thyroid Dose at the Nearest Residence, Dn = 'RI W +RV W (dep) Qd 1 year p mrem / month C n(in) c n. i TL2 month'W where:
Dn
= Estimated dose to the nearest resident RI = Child inhalation thyroid dose factor for C I-131 = 1.62 x 10 7 mram per -y uci .
R7 = Child vegetation thyroid dose factor for c I-131 = 4.77 x 1010 m2 mrem per uci year see 3
I WN (in) = X/Q at the nearest residence = 2.7 E-6 s/g WN (dep) = D/Q at the nearest residence = 8.7 E-9 m Infant Thyroid Dose at the Secondary Receptor, C
os= s + L(al+R)wg ,
(aIw(in) . l12 months 41
ON3 - RBI, 3 D3= Estimated dose to the secondary receptor RI= Infant inhalation thyroid dose factor for I-131 I = 1.48 x 107 mrem per uCi yr ~l m
RV = Infant vegetation thyroid dose factor for I-131 = 0 I (no ingestion of vegetables for infant)
RC = Infant cow-milk thyroid dose factor for I-131 I = 1.06 x 1012 m2 mrem per uci yr s W 3 (in)=X/Q at the secondary receptor = 2.9E-7 s/m3 Us(dep)=D/Q at the secondary receptor = -4.7E-10m-2 Substituting the parameters into both equations, Dn= 38.3 Qt mrem / month D' = 41.9 Qt mrem / month The largest of these two dose parameters (Ds) should be used for manual dose calculations.
Compare this thyroid dose to the limits in paragraph 3.2.4. Add this calculated thyroid dose the calculated values for the period time period in the calendar quarter and calendar year. Compare these sums to the limits of paragraph 3.2.3. If the dose is excessive, the calculation will be performed in greater detail, using methodology described in Section 3.3.4.
3.5 Calculation of Meteorological Dispersion Factors 3.5.1 For the purupose of these calculations the site boundary was taken to be the unrestricted area boundary. The distances to the site boundary as measured from the center of IP3NPP containment are shown in Table 3-18 for each of the 16 major compass sectors. The distances to the nearest residence in each of'these sectors is also shown on this table. In the sectors where the Hudson River is the site boundary, the opposite shore is assumed as the boundary of the unrestricted area. This is based on the definition of unrestricted area in NUREG 0133 (ref. 1, section 22, page 6), which states that the unrestricted area boundary does not include areas over bodies of water.
The nearest opposite shore distances is five times that of the closest land restricted area boundary. Therefore, these locations are unimportant when evaluating the maximum unrestricted area boundary concentrations.
NCM - RD). 3 3.5.2 The atmospheric transport and diffusion model used in the evaluation of dispersion and deposition factors is the straight line flow model presented by Sagendorf in NUREG 0324 (ref. 5). All releases were treated as ground level with credit taken for building wake dilution as applicable and no credit was taken for plume depletion or decay during travel time. Values of sigma Y and sigma Z were defined by onsite measurements of temperature differential which determine the atmosphere stability classes of Regulatory Guide 1.23. These measurements were taken from the onsite meteorological towers wind data were taken at the 33 foot elevation and temperature differentials between the 200 foot and 33 foot levels.
Data recovery for the two years used (1978-1979) was 96.3% and 98.2% respectively. Calms were assigned to the lowest windspeed class and to wind directions in proportion to the directional distribution of the lowest windspeed within an atmospheric stability class. Compar-ison of these meteorological data with the previous data in the Indian Point area shows that these data are represen-tative of long term conditions at the IP3NPP site. The program of meteorological monitoring and data acquisition is in accordance with Regulatory Guide 1.23.
3.5.3 To meet the calculational requirements of Paragraph 3.2.1, 3.2.2 and 3.2.4 the annual average dispersion factors were calculated for each compass sector at the site unre-stricted area boundary. The most restrictive X/Q was determined to be 3.0E-05 in the SW sector at 350 meters.
The distances to the site boundary in each sector are listed in Table 3-11.
3.5.4 To meet the calculational requirements of Paragraphs 3.2.3 iodines and particulates, the annual average depo-sition and dispersion parameters were calculated for the nearest residence in each of the compass sectors.
Distance to the nearest residence in each sector are listed in Table 3-11. Because no real dairy exists within 5 miles of the power plant, a hypothetical cow was placed in the worst meteorological sector at 5 miles. Dispersion and deposition parameters for both locations are given below.
Wn(in) = Ths highe'ts calculated annual average dis-persion parameters for the inhalation pathway for the nearest residence in the unrestricted area located in the SSW sector at 1526 meters, 2.7E-6 sec/m3 .
Wn (dep) = The h.ighest calculated annual average de-position parameters for the ground plane and vegetation pathways for the nearest l
residence in the unrestricted area located in the S sector at 1279 meters, 8.7E-9 m -2 For tritium in the vegetation pathway WN (in) is used.
ODu - RDJ, 3 Ws (in) = The calculated annual average dispersion factor for the inhalation pathway for the secondary receptor occurs in the SSW sector at 5 miles , 2.9E-7 sec/m 3, Ws(dep) = The highest calculated annual average deposition factor for the cow-milk vegetation, and ground plane pathways for the secondary receptor occurs in the SSW sector at 5 miles, 4.7 E-10 m-2 For tritium in the cow-milk and vegetation pathways W s(in) is used.
3.5.5 To meet the calculational requirements of Baragraphs 3.2.2, 3.2.3, and 3.2.4 and the calculation methodologies described in Sections 3.3.4 and 3.3.3 short term release dispersion and deposition factors may need to be calculated.
For this document short term release dispersion and deposition factors are determined from the long term annual average parameters. The method utilized is that presented by Sagendorf in NUREG 0324 (ref.5) as recommended by NUREG 0133 (ref. 5 section 3.3, page 8). This short term release calculation assumes that the plume uniformly distributes in the horizontal within a 22h degree sector as recommended in NUREG 0324 (ref. 5, page 22). It is further assumed that all releases are ground level. No credit is taken for plume depletion or decay during plume travel time, and all short term releases are cumulative over the calendar year or quarter as appropriate, NUREG 0133 (ref 1, section 5.3.1., page 29). Utilizing the following equation, a factor (F) is developed for a particular compass sector and distance which is simply multiplied against the annual average for the same sector and distance to develop the short term dispersion or deposition factor:
F. TITOTAL' 8760 where:
F = The non-dimensional correction factor used to convert annual average dispersion or deposition f actors to short term dispersion or deposition factors.
NTOTAL = The total number of hours of intermittent releases.
8760 = The total number of hours in a year.
ANMX = The calculated annual average dispersion (sec/m3 ) or deposition (m-2) factor for the compass sector and distance of interest.
l
4 WKM - RW. 3 F15MX = The short term dispersion (secAn3) or deposition (m-2) factor for the compass sector and distance of interest. This is the 15th percentile value such that worse weather conditions can only exist 15% of the time and better weather. conditions 85% of the time.
M = log ( ANMX/ FISMX) log (8760) 3.5.6 The short term 15th percentile dispersion or deposition factor for use in the equation of the preceeding paragraphs and the simplified F factor equation are as follows:
a.) Nearest Residence Inhalation:
~
F15 MX (1526m, SSW, inhalation) = 3.07E-5 sm 3 ANMX ( " "
) = 2.7E-6 sm F= NTOTAL m; m = log ('. 7E-6/3.07E-5) = -0.27 8760 log (8760)
F= NTOTAI -0. 27 8760 b.) Nearest Residence Deposition:
F15MX (1526m, SSW, Dep.) = 9.89E-8m~2 ANMX (1526m, SSW, Dep.) = 8.7E-9m F= NTOTAL m, .27 m = loc (8. 7E-9/9. 89E-8) =
8760 loh (8760)
~
F= NTOTAL -0. 27 8760 c.) 5 mile Inhalation:
F15MX (5 mi, GSW, inhal.) = 3. 36E-6 sm-3, ANMX (5 mi, SSW, inhal.) = 2. 80E-7 sm -3
~
i F = NTOTA[ m; , loq (2. 80E-7/ 3. 36E ,6,) = -0. 2 7
,8760 ,
log (8760)
F = hiTOTAL -0.27
,8760 ,'
d.) 5 mile Deposition:
l
~
FISHX (5 mi, SSW, Dep) = 5. 64E-9 m, ANMX (5 mi, SSW, Dep) = 4.7E-10 m I F = NTOTAC m; = log (4. 7E-10/5.64E,9) = -0.27 I y 3760, log (8760)
F ='YJTOTA[ -0.27
( - _ _ _
1 l
O EM - ROJ. 3 3.6 Justification for the Use.of the Finite Cloud Assumption for Assessing Site Boundary Dose .
If the dimensions of a homogenous cloud of gamma-emitting material are large compared to the distance that the photons travel, an. equilibrium condition will exist. Under these cond'.tions the rate of energy absorption per unit volume is equal to the rate of energy release per unit volume.
When tha above conditions are satisfied the geometry is referred to as an infinite cloud geometry. In a situation where these conditions are not met (e.g. dimensions of cloud are not large with respect to photon path length) e then a finite cloud geometry is said to exist. Under finite cloud conditions the resultant dose rate from exposure to the cloud will be less than that for an infinite cloud.
This difference can be expressed in the form of a ratio and is a function of both cloud dimension and photon energy.
The site boundaries of the Indian Point power station are in close enough proximity to the reactor units that the conditions of infinite cloud geometry are not met. Using the data and assumptions presented in Meteorology and Atomic Energy, 1968 (TID 24190); nuclide specific finite to infinite dose ratios were developed in order to more accurately assess doses at the site boundary. These ratios were applied to the appropriate Reg. Guide 1.109 dose factors. The results of the finite / infinite dose ratio calculations are on file with IP3 Radiological Engineering. The site boundary finite correcte< dose factors are contained in
~
this ODCM PRabies 3-4, 3-6, 3-8, 3-9).
t
ODut - REv 3 TABLE 3-la INHALATION DOSE FACTORS FOR CHILD (MREM PER PCI INHALED)
Page 1 Of 3 .
TUCL I DE SONE Live 2 T. AODY Thya01D MIONEY LUNG GI-LLI H J NO Defa 3.04E-07 3.04 E-0 T 3.04(-D7 1.04E-07 3.04E-r7 3.04E-07 C 14 9.70E-06 1.82E-06 1.82E-06 8.82E-06 1.821-06 1.12E.06 1.028-06
%a 24 4.35E-06 4.35:-06 4. 3 s E -o s 4.lbt-06 4.35E-r6 4.15E-06 4.154-06 P 32 7.04E-04 1.r9E-05 2. 6 T f -0 5 No DATA NC DATA NO DATA 1.14E-05 CR 51 NO Data NO Data 4.17 E-0 8 2.31r-08 6.57f-09 4.59E-06 2.93E-07 MN 54 NO DATA 1.16!-05 2.57E-06 NO Data 2.7tt-06 4.26E-04 6.19F-06 WN 56 NU Data 4.48E-lo 8.43E-Il NO Data 4.52E-10 3.SSE-06 3.33f-05 f t $5 1.28E.05 6.80E-06 2.10E-06 NO Data NO DATA 3.00E-05 7.75E-07 FE 59 S.htE-06 9.c4E-06 4.51L-06 NO DATA ND Data 3.43E-04 1.9tE-05 CO 58 NO Data 4. TOE-07 8.55E-07 NO DaT4 NC Dafa 2.99E-04 9.29E-06 CO 60 NO Data 3.55E-06 6.12E-06 NO Data NO DATA t.9tE-03 2.60E-05 NI 63 2.22E-04 1.25F-05 7.56E-06 40 DATA NO DATA 7.43E-05 1.71E-06 NI 65 8.'C8E-10 7.99E-Il 4.44E-11 Nn DATA NC DATA 2.2tE-06 2.27E-05 CU 64 NO Data S.J9E-10 2.90E-10 NO Data 1 63E-09 2.59E-06 9.92E-06 2A 6b 1.lSE-05 3.06E-05 1. 90E-0 5 40 DATA 1.93E-05 2.69E-04 4.41E-06 2N 69 -l.01E-11 2.61Eall 2.41E-12 NO DATA 1.SSE-Il 3.84E-07 2.75E-06 et 83 NO CaTA NO pata 1. 2 E E -0 7 NO Defa NO Data NO Data LT E-24 um A4 NO DATA Nu Data 1.4RE-07 No paTa NC 04T4 NO Defa LT E-24 29 85 NO Cafa NO DATA 6.84E-09 NO DATA NO DATA NO Dafa LT E-24 to A6 NO Data S.36E-05 3.09E-DD NO CATA NO Data NO DATA 2 16E-06 RF 88 NO Data 1.52E-0T 9.90E-08 NO Data NO DATA NO DATA 4.665-09 R8 89 NO DATA 9.31!-08 7. 8 st -0 4 NO Data NO Data NO Data 5.llE-10 54 89 1.62E-04 NO DATA 4. 66 E-0 6 NO 04T4 NO DATA 5.81E-04 4.52E-05 58 90 *2.73E-02 NO Data 1.74 E-0 3 NO DATA NC DATA 3.99E-03 9.28E-05 5P 91 3 28E-09 NO DATA 1. 24 E -0 9 NO DATA NO Data 1.44E-05 4.708-05 5R 92 3.94E-09 NO DATA 1 42E-10 NO DATA NO Data 6.49E-06 6.55E-05 Y 90 1.llE-06 NO Data 2 94F-08 WO DATA NO DATA 7.07E-05 7.24E-05 Y 91P 1.1TE-10 NO Data 4.90E-12 NO DATA NO Data 7.60F-07 4.64E-07 i Y 91 2.47E-04 40 Defa 6. 5 9 E -0 6 40 Data NO Defa 7.10E-04 4.97E-05 i V 92 S.50E-09 NO Dafa 1. 5 7 E-10 40 Data NO Data 6.46E-C6 6.46E-05 l
This table was taken from NRC Regulatory Guide 1.109 l
Table E-9 c
l
ODCM - REV. 3 i
TABLE 3-la CONT'D INHALATION DOSE FACTORS FOR CHILD-(MREM PER PCI INHALED)
I Page 2 of 3 SOME liver 7. dO DY THYROID RIONEY LU4G 01-LLI ,
NUCLIDE Y 91 5.04E-os NO DATA 1 38E*09 NO 067 4 NO Data 2.01E-05 1.05E-04 S.lAE-05 1.13E-D5 1 00E-05 NU OATA 1.61i-Ob 6.03E-04 1.65[=05 2R 95 20 97 5.07E-05 7.34E-09 4 32E-09 MO 04T4 1 05E-08 3 06E-05 9.49E-05 NS 95 6.35E-06 2.40E-06 1 77E -0 5 NO DATA 2.33E-06 1.66E-04 1.00E-05 MD 99 NO DATA 4.66E-06 1.lSE-08 NO Daft 1. 0 6 E -t'7 3.66E-05 1.42[-05 4.tlE-Il 9.41L-13 1.56E-il NO DATA 1.37E-Il 2.57E-07 8 30E-06 TC 99P 7Cl01 2 19E-14 2.30E-l* 2 91E-13 NO DATA 3.92E-13 1.5RE-07 4.418-09 7.55E-07 NO DATA 2.90E-07 NO DATA 1.90E-06 1.79E-04 1.21E-C5 .
20103 Rul05 4 13E-10 NU D&TA 1.DCE-!O N0 DATA 3.631-10 4.1oE-06 2.69E-05 . I 3 68E-05 NU 04TA 4.57E-06 NO DATA 4.97E-05 3.87E-03 1 16E-04 Rul06 5.74L-06 1 40E-03 2 71E-05 AGil0* 4.56E-06 3.00E-06 2.47E-06 NO DATA 7E1254 1 82E-06 6.29E-07 2 47E-07 5.20!-07 40 DATA 1.29E-04 9 13E-06 1.93E-05 7El2?M 6.72E-06 2.31E=0e O.loE-07 1 64E-06 1.721 85 4.00E-04 TE127 7.49E-10 2.57E-10 1 65E-10 5.5CE-10 1.91L-09 2c71F-06 1 52E-05 TEl27r 5.19E-C6 1.ObE-06 8.22E-07 1.7tt-06 1.16E-09 4.76E-04 4.91E-05 9.45E-12 6.44[-12 1.93E=ll 6.94L-il 7.91E-07 6.89E-06 TE129 -2.64E-Il 0.32E-05 TE13tr 1 63E-08 1.60E-08 1.37E-05 2.64E-OS 1 08L-07 5.56E-05 1.*,BE-12 4.59t-12 1.59E-!! 5.55E-07 3.60E-07 fil31 5.87E-12 2.28E-12 0.5OE-00 4.79E-07 1.02E-04 3.72E-05 i TE!)2 1.30E-07 7.36E-08 7.12E-Os 1. lee-06
! 130 2 21E-06 4.43!-06 2 28E-06 4.99E-04 6.6tt=0e NO DATA l
- 7. 3 7 E -0 6 4.39E-03 2.13E=05 NO DATA 7.60E-07 t 131 1 30E-05 1 30E-05 1.10!-06 5.0fE-07 5.2SE-05 1.69E-C6 MO DATA 8.65E-07 i I 132 5.72E-07 1.48E-06 ;
1 133 4.48[=06 5.49:-06 2 00E-06 1 04E-03 9.13E-06 NO Defa 2.58E-07 <
I 134 3 17E-07 5.841-07 2 69E-07 1.37E-05 0.92E-07 NO CaTA i i ................................. ............................... ........
1.33E-06 2 16E-06 1 12E-06 2.14[*04 3.62E-06 NO DATA 1 20E-06 i i 135 3.93E-05 3.27E-05 1.04E-06 C5134 1.76E-04 2 74E-04 6 07 E-0 5 40 DATA C5116 1 76E-05 4.62E-05 3.14E-05 NO Da7A 2.5st-05 3.93E-06 1.13E-06 l C5137 2.45t=04 2.23E-04 3.47E-05 NO 04fA 7.63E 05 2.Off=05 9.70E-07 C5138 1.715-07 2.27E-07 1 50E-07 NO DATA 1.69E-07 1.04E 08 7.29E-08 4A139 4.98E-10 2.668-13 1 4SE-Il 40 DAT4 2.13E 13 1 56E-06 1 56E-05
...... ................ ..... e .c.. .. .. .....................
I
'e I l
ONE - REV 3 TABLE 3-la CONT'D INHALATION DOSE FACTORS FOR CHILD (MREM PER PCI INHALED)
Page 3 of 3 7.800f 7MYRO10 EIONEY LUNG Cl-LLI NUCLIUE SUNE LivEA 1 75E-08 1.lff-06 NO DATA 5.71E-09 4.7tE-04 2 75E-05 84140 2.00E-05 2.56E-14 7.09E-07 7.44E-06 Sal 48 S.29E-!! 2.95E-14 1.72F-12 40 DATA 4.44E-07 7.4tF-10 9.73E+15 7.54E-13 NO CATA 7.87E-15 3a142 1.35E-Il 6.08E-00 2 04 E -0 8 NO DAT A NO DATA 4.94E-05 6.10E-05 tal40 1 74E-07 NO DATA 2.35F-06 2.05E-05 3.50E-10 1.llE-10 3.49E-11 NO DATA LA142 2.31E-06 1 47E-04 1 53E-05 CE141 1 06E-Ob 5.20E-06 7. 8 3 E-0 F NO DATA 7.77E-09 NO DATA 2.26E-08 3.IZE-OS 3.44E-05 .
Cele) 9.89E-08 5.37E-08 1.23E-03 1.05E-04 1 83E-03 5.72E-0* 9.77E-05 40 Defa 3.17E-04 Cele 4 3.11t-07 1 17E-04 2.63E-05 PA143 4.99E-06 1 60E-06 2 47E-07 NO DATA PA144 1.6tE-11 4.996-12 0 10E-13 NO DATA 2 64E-12 4.23E-07 S.32E-08 N0147 2.92t-06 2.36E-06 1 047-07 Nn DATA 1 30E-06 8.87E-05 2.22F-05 4.41E-09 2 61E-09 1.lfF-09 Nn DATA NC CATA 1.llE-05 2.46E-05 W 187 1.76E-07 9.04f-09 6.35E-09 NO DATA 2.63E-08 1.57E-05 1 73E-05 NP239 i
i I
{
ODDt - REY. 3 1
)
i TABLE 3-lb INHALATION DOSE FACTORS FOR INFANT :
(MREM PER PCI INAHLED)
Page 1 Of 3 l NUCL I DE SONE LIVER 7.000Y THVROID RIONEY LUNG GI-LLI P 3 NO DATA 4.62E-07 4.62E-07 4.62F-07 4.62E-07 4.62E-07 4.62E-07 1.09E-05 3.79C-06 3.79E-06 3.19E-06 3.79E-06 3.79E-06 3.79E-06 C 14 7.54E-06 7.54E-06 7.54E-06 7.54E-06
% A 24 7.54E.06 7.54E-06 7. 54 E-0 6 P 32 1.45E-03 8.03E-05 5.53E-05 NO DATA NO DATA NO DATA 1.15E-05 CR 51 NO DATA NO DATA 6.31E-08 4.11E-08 9.45t-09 9.17E-06 2.55E-07 MN 54 NO DA1A 1.81E-05 3.56C-06 NO DATA 3.56E-06 7.14E-04 5.04E-0)
MN 56 No DATA 1.10E-09 1 58E-10 NO DATA 7.86E-10 8.95E-06 5.IZE-05 FE 55 1.41E.05 8.39E-06 2 38E.06 NO DATA NO DATA 6.21C-05 7.02E-07 9.69E-06 1.68E-05 6.77E-06 40 DATA 40 DATA 7.25E-04 1.77E-05 FE 59 CD SS NU DATA 8.71E-07 1 30E-06 NO DATA NO DATA 5.55E-04 7.95F-06 CD 60 NO DATA 5.73E-06 8 4tE-06 40 DATA NO DATA 3.22E-03 2.20E-05 NI 63 2.42E-04 1.46E-05 0. 2 9 E.0 6 NO DATA NO DATA 1 49E-04 1.73E _06 NI 65 1.71E-09 2.01C-10 8.79E-11 40 DATA NO DATA 5.80E-06 3.58E-05 .
1.34E-09 5.53E-10 ND DATA 2.84E-09 6.64E-06 1.0TE-05 CU 64 NO CATA 3.67E-05 24 65 1.38E-05 4.47E-05 2.22E-05 NO DATA 2.32E-05 4.62E.04 2.87E-Il 1.0$f-06 9.44E-06 JN 69 3.85E-11 6 91E-11 5.13E-12 NO DATA No DATA NO DATA LT E-24 B4 85 NO DATA NO DATA 2 72E-07 NO DATA LT E-24 NO DATA 2 86E-07 NO DATA NO DATA NO DATA 84 84 40 DATA .......
i NO DATA 1 46E-08 NO DATA NO DATA NO DATA LT E-24 84 82 NO DATA NO DATA 2.17E-06 1.36t=04 6. 30E-0 5 NO DATA NO DATA R$ 86 NO DATA NO DATA NO DATA 2.42E-07 48 88 NO DATA 3.90E-07 2 03E-07 NO DATA ..... -
NO DATA NO DATA 4.8 7 E-08 R$ 89 NO DATA 2.29E=07 1.47E-07 NO DATA 1.45E-03 4.57E-05 8.15 t-0 6 NO DATA NO DATA 54 89 2.84E-04 40 DATA NO DATA 8.03E-03 9.16E-05 SR 90 2.92E-02 NU 0414 1. 8 5 E .0 3 NO DATA 6.83E-08 No DATA 2 4 7 E.0 9 N0 DATA No DATA 3.76E-05 5.24E-05 SR 91 NO DATA 1 70E-05 1 00E-04 54 92 7.50E-09 NO DATA 2 79E-10 NO DATA Y 90 2 35E-06 NO DATA 4.30E-08 NO DATA NO DATA 1 92E-04 7.43f-05 V tir 2 9tE*10 NO DATA 9.90E-12 NO DATA NO DATA 1 99E-06 1 40E-06 Y 91 4.20E-04 NO DATA 1 12E-05 NO DATA NO DATA 1.75E-03 5.02E-05 Y 92 1 178-08 NO DATA 3.29E-10 NO DATA No DATA 1 75E=05 9.04E-05 This table was taken from NRC Regulatory Guide 1.109 Table E-10
DDDI - RW, 3 TABLE 3-lb CONT'D INHALATION DOSE FACTORS FOR INFANT (MREM PER PCI INHALED)
- Page 2 Of 3 SONE liver. T . 80DY THynotD n10NEY LuMG si. Ell NUEL 10E 3 07E-07 NO DATA 2.91E-09 'NO DATA NO DATA 5 46E.05 1.19E.04 V 93 2.22E.n5 1 25E.03 1.55E.05 la 95 8.24E-06 1 19E-05 1 45E.05 NO DATA 7.88E-05 1.00E.04 24 97 1.07E-07 1 83E.08 8. 36 E.0 9 40 DATA 1.85E-08 .. .
48 95 1 12E.0% 4.596-06 2.70E-04 NO DATA 3.37E-06 3.42E.04 9.05E.06 mo 99 NO DATA 1 18i-07 2. 31 E.0 8 NO DATA 1.mtE.07 9.61E-05 3.48E.05 TC 99p 9.90E-13 2 06E-12 2 66E-!! 40 DATA 2.22E.it 5.79E.07 1.45E.06 TC101 4.65E-14 5.98E-14 5.00E-13 NO DATA 6.99E.13 4.17E-07 6.03E-0T 2U103 1 44E.06 NO CAT A 4.85E-07 NO DATA 3.03E.06 3.94E-04 1 15E.05 AU105 8.74E-10 NO DATA 2 91E.10 NO DATA 6.42E-10 1 12E-05 3.46E.05 Rul06 6.20E*05 NU OATA 7.77E.06 NO DATA 7.61E-05 0.26E-03 1 17E.04 AG1104 7,13E-06 5.16E-06 3.57E.06 NO DATA 7.00E-06 2.62E.03 2.36E.05 TE125r 3.4 0 E.0 6- 1 42E.06 4.70E-07 1 16E-06 NO DATA 3.19E.04 9.22E.06 TE127r 1.19E-05 4.93E.06 1 48E.06 3.48E.06 3.47E.09 7.39E-06 1 74E.05 7.68E.05 9.37E.04 1.95E.05 TE127 1.59E-09 6.8tt-10 3 49E-10 1.32E-0V TE129r 1. PIE-05 4. 3 5E.06 1 59E.06 1.9tE-06 2.27E-05 1.20E-03 4.93E-05 TE129 5.63E-Il 2 48E.it 1 34E-11 4.82E-ll 1.25E.10 2.14E-06 1.88E-05 TE13tm 7.62E-08 3 93E-08 2 59E-08 6.38E-08 8 89E-07 1 42E.04 8.51E.05 1 24E.ll 5.87E-12 3 57E-12 1 13E-Il 2.85E-11 1.47E.06 5.a7E.06 -
rE131 TE132 2 66E.07 1.69E.07 1 26E.07 1 99E-07 7.39E-07 2 43E-04 3 1.42E-06 1.09E.05 NO DATA 15E.05 1 130 4.54E.06 9.9tt-06 3 98E-0$ l.14E-03 1.06E.02 3.70E-05 h0 CATA 7.56E-07 i 131 2.7tt-05 3.171 05 1 40E.05.......... .................. .. ....
v................................ 1.36E.06 1 21E.06 2.53E-06 8.99E-07 1.2tE.04 2 82E.06 NO DATA 1 132 1 60E.05 NO DAT4 1.54E.06 1 133 9.46E.06 1 3ff.05 4.00E.06 2.54E-03 1 49E-06 NO DATA 9.21E-07 1 134 6 58E.0T 1 34E.06 4.75E.07 3.18E-05 1.3lE 06 1 135 2 76E.06 5.41E 06 1 9tE.06 4.97E-04 6.05E-06 1 36E.04NO5.69E-05 DATA 9.53E-07 C5134 2.83E.04 5.02E.04 5.32E.05 40 DATA 4.03E.05 8.40E.66 1.02E-06 3 45E.05 9.61E-05 3.78E-05 NO D AT A C5136 3 25E 05 NO DATA 1.23E-04 5.09E.05 9.53E207 C5137 3.92E-04 4.37F-04 C5138 3.61E.07 5 58E-07 2 84E.07 NO DATA 2.93E-07 4.23E-13 4.67E.00 6.26F 07 4.25E-06 3.64E.05 Sal 39 1 06E-09 7.03E.13 3..-... 0TE.it .................-
WO DATA .. ...... ..... ..
- - ~ - . _ - - . . - ~ _ - - = _ , _ . . _. ,_, , _ _ _ ,_,, . _ _ . _ __, __ , __
ODDI - REV. 3 TABLE 3-lb CONT'D
.. INHALATION DOSE FACTORS FOR INFANT (MREM PER PCI INHALED)
Page 3 of 3 NUCLICE SONE LIVER f . 8 0 DY TMYR010 RIONEY LUNG Cl-LLI wanno 4.00E-05 4.00E-08 2.07E-06 NO DATA 9.59E-09 1.44E-03 2.74E-05 val 41 1.12E-10 7.70r-14 3.55E-12 NO DATA 4.64k-14 2.12E-06 3.39F-06 Mal 42 2.04E-!! 2. 3 6 f- 14 1.40E-12 NO O&TA 1.36L-14 1.11E-Da 4.95E-07 L A 14 0 3.61E-07 1.43t-07 3.68E-08 NO 04f4 NO Cafa 1 20E-04 6.06E-05 LA142 7.36E-10 2.69E-10 6.4ef-11 NO CaTA NO DATA 6.87E-06 4.2SE-05 CEl41 1 94E-0) 1.19E-05 1.42E-06 NO O&fA 3.75t-06 3 69F-04 1.54E-05 Cele) 2.09E-07 1 98E-07 1.59E-Os NO DATA 4.03E-00 4.3CE-05 3 5 5E OE144 2.28E-03 8.e5E-04 1.26E-04 NO DATA 3.84E-04 7.03E-03 1.06E-04 v4143 1.00E-05 9.74E-06 4.99E-07 NO Data 1.41E-06 3.09E-04 2 66E-05 PR144 3.42t=11 1.32E-!! !.72E-12 NO DATA 4. ROE-12 1.15E-06 3.06E-06 N0147 5.67E-06 5. 81 F = 0( 5.57E-07 NO DafA 2.25E-06 2.30E-04 2.23E-05 W 887 9.26E-09 6 44E-09 2.23E-09 NO 041A NO Data 2.83E-05 2.54E-05 NP239 2.65E-07 2.37E-00 1 14 E -0 8 NO Data 4.73L-08 4.25E-05 1.70E-05
O E M - REv, 3 TABLE 3-2 GROUND PLANE DOSE FACTOR (MREM /HR PER PCI/M2)
Page 1 of 1 ELEMENT TOTAL BODY ELIMENT TOTAL BODY H-3 0.0 Ru-103 3.60E-09 C-14 0.0 Ru-105 4.50E-09 NA-24 2.50E-08 Ru-106 1.50E-09 P-32 0.0 Ag-llCN 1.80E-08 Cr-51 2. 2E-10 Te-125M 3.50E-ll Mn-54 5.80E-09 Te-127M 1.10E-12 Mn-M 1.10E-08 Te-127 1.00E-11 Fe-55 0.0 Te-129M 7. 70E-10 Fe-59 8.00E-09 Te-129 7.lE-10 Co-58 7.00E-09 Te-131M 8.4E-09 Co-60 1.70E-08 Te-131 2. 2E-09 Ni-63 0.0 Te-132 1.7E-09 N1-65 3.70E-09 l-130 1.4E-08 CD-64 1.50E-09 I-131 2.8E -09 Zn-65 4.00E-09 I-132 1.70E-08 Zn-69 0.0 I-133 3.7E-09 Br-83 6.40E-ll I-134 '
l.60E-08 !
Br-84 1.20E-08 I-135 1. 2E-08 Br-85 0.0 Cs-134 1. 2E-08 Rb-86 6. 30E-10 Cs-lM 1. 5E-08 Rb-88 3.50E-09 Cs-137 4. 2E-09 Rb-89 1.50E-08 Cs-138 2.lE-08 Sr-89 5.60E-13 Ba-139 2.4CE-09 St-91 7.10E-09 Ba-140 2.lE-09 Sr-92 9.00E-09 Ba-141 4. 30E-09 Y-90 2.20E-12 Ba-142 7. 9E-09 Y-91M 3.80E-09 La-140 1.5E-08 Y-91 2.40E-ll La-142 1. 5E Y-92 1.6E -09 Ce-141 5.50E-10 Y-93 5.70E-10 Ce-143 2.2E-09 Zr-95 5.00E-09 Ce-144 3.2E-10 Zr-97 5.50E-09 Pr-143 0.0
%-95 5. lE-09 Pr-144 2.0E -10 Mo-99 1.Por-09 W-147 1.00E-09 Tc-99M 9.60E-10 W-187 3.10E-09 Tc-101 2.70E-09 S-239 9.5E-10 This table was taken from NRC Regulatory Guide 1.109 9able E-6
ODCit - REV. 3 TABLE 3-3a INGESTION DOSE FACTORS FOR INFANT (MREM PER PCI INGESTED)
Page 1 Of 3 WUCLIDE CONF , LIVER T. 80U7 TMYt010 EIONEY LUNG Cl-LLI W 3 ho DATA 3.00E-07 S.00 E-0 7 3.0RE-07 1.00E-07 3.08E-07 3.08E-07 L in 2.37E-05 5.06E-06 5. 0 6 E-0 6 5.06E-06 5.06E-06 5.06F=06 5.06E-06 NA 24 1 0lf-05 1.0lt-05 1.01E-05 1. ORE-05 1 01E-05 1.Olt-Ob 1. ORE-05 P 32 1.70E-03 1.00E-04 6.59E-05 40 DATA NO DATA NO DATA 2.90E-05
, Ca 51 NO DATA h0 DATA 1.41E-08 9.20E-09 2.0lf-09 1.79E-08 4.llE-07 WN 54 40 DATA 1.99E-Ob 4.llE-06 NO DATA 4.4tE-06 NO DATA 7.31E-06 MN 56 40 DATA 8.18E-07 1.4 t E-0 7 N0 DATA 7.0lf-07 40 DATA 7.43F-05 '
FE 55 1.39E-05 8.98E-06 2.40E-06 NO DATA ho DATA 4.19E-06 1.14E-06 ,
FE 59 3.00E-05 5. A SE-03. 2.12E-Ob 40 DATA NO DATA 1.59E-05 2.57E-05 CD 58 NO DATA 3.6cE-06 8. 9 8 E-0 6 NO DATA NO DATA NO DATA 8.97E-06 CD to NO DAIA 1 08E-05 2.55E-05 NO DATA NO DATA NO DATA 2.5TE-05 48 63 6.34E-04. 3.92E-05 2. 2 0 E -0 5 ho DATA 40 DATA NO DATA 1.95E-06
%I 65 4.70E-06 5.32E-07 2.42E-07 No UATA ho DATA NO DATA 4.05E-05 Cu to 40 DATA 6.09E-07 2.82E-07 40 DATA 1 0AE-06 ho DATA 1.25E-05 2N 65 1.54E-05 6.stf-05 2.9tE-03 40 DATA 3.06E-05 NO DATA 5.13E-05, 2h 69 9.33E-08 1.68E-0T 1.25F-08 NO DATA 6.98E-08 kn DATA 1.378-05 '
HA 83 40 DATA fJO DATA 3.63E-07 NO DATA NO DAT A ho DATA LT E-24 hP to 40 DATA NO DATA 3.82E-07 NO DATA ho DATA ha DATA LT E.24 )
WR 83 NO DATA ho DATA 1 94E-08 NU DATA NO DATA NO DATA LT E-24 AP 86 NO DATA 1.70E-04 8.40E-05 ho CATA NO DATA ho DATA 4.35E-06 At 88 ho OATA 4.98E-07 2.73E-07 WD DATA NO DATA NO DATA 4.85F-07 l
40 89 NO DATA 2.86E-07 1 97E-37 NO DATA NO DATA NO DATA 9.74E-08 CR 89 2.51E-03 NG DATA 7.20E-05 40 DATA NO DATA ho DATA 5.16E-05 I 1R 90 1.85E-02 NO DATA 4.71E-03 40 DATA NO DATA ho DATA 2.3tt.04 SR 91 5.00E-05 NO DATA 1. E l f-0 6 NO DATA NO DATA NO DATA 5.92E-05 5A 92 1.92E-05 40 DATA 7.13E-07 NO DATA NO DATA NO DATA 2 07E-04 '
3 Y 90 8.69E-08 seo DATA 2.3st-09 40 DATA NO DATA 40 DATA 1 20E-04
! Y tim 8.10E-10 ND DATA 2.76E-Il k0 DATA NO DATA NO DATA 2.70E-06 l V 91 1 13E-06 NO DATA 3. O l f.0 8 h0 DATA NO DATA NO DATA 4.10E-05 l V 92 7.65E-09 No DATA 2.15E-10 ho DATA NO DATA NO DATA 1 46E-04 l
. . . . - _.. - ............ . . ..... _ ..... - ......... ...... 1 l
I l
I This table was taken from NRC Regulatory Guide 1.109 l Table E-14 i
-- ..,-.-.-_--.,---__.._.-_..___.,,.___SA
ODDI - RW, 3 TABLE 3-3a CONT'D INGESTION DOSE FACTORS FOR INFANT (MREM PER PCI INGESTED)
Page 2 of 3 NUCLICE 809E LivfA 7.00DY THyaOID KIDNEY LUNG GI-LLI Y 93 2.43E-00 NO DATA 6.62E=10 NO DATA NO DATA NO DATA 1.92E-04 2R 95 2.06t=07 S.02E-08 3.56E-08 40 DATA 5.41E-08 NO DATA 2.50F-05 IA 97 1 4 SE-08 '7.54E-09 1 16E-09 NO DATA 2.56E-09 NO DATA 1. 6 2 E-04 98 95 4.20E=dt 1.73E-08 1. 0 0E-0 9 NO DATA 1 74t-03 NO 3ATA 1.46E-05 NO 99 NO DATA 3.4CE-05 6.63E-06 NO DATA 5 00E-05 NO DATA 1 12E-05 TC 99P 1.92E-09 3.96E-09 5.10E -O s Nn DATA 4.26k-08 2.07E-09 1 15E-06 -
TC101 2 27E-09 2 86E-09 2. 0 3 E-0 8 NO DATA 3.40E-08 1.56E-09 4.06E-07 Rul03 1 40E-06 N0 DATA 4.95E-07 NO DATA 3.00E-06 NO DATA 1 80E-05 4Ul05 1 36E-07 NO DATA 4. 5 s t-O s No DATA 1 00E-06 Nn DATA 5.4tE-05 Auto 6 2 41E-05 NO DATA 1. 01 E -0 6 NO DATA 2.ASE-05 NO DATA 1.03F-04 AGl!0m 9.96E-07 7.27E-07 4. 01 E-0 7 NO DATA l.04E-06 40 DATA 3.77E-05 I TE12br 2.33E-05 7.79E-06 3. l > E-0 6 7.84E-06 NO DATA NO Data 1.llE-05 i TE127p 5.05E-05 1 94E-05 7.00E-06 1 69E-05 1 44E-04 NO DATA 2.36E-05 I 7E127 1 00E-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 NO DATA 2.10E-05 7E129M 1 00E-04 3.43E-05 1. 54 E -0 5 3.04E-05 2.50E-04 NO DATA 5.97E-05
- TE129 2 84E-07 9.79E-08 6 61E-08 2.38E-07 7.07E-07 NO DATA 2.27E-05 TEl3tw 1.b2E-05 6.12E-06 5.05E-06 1.24E-05 4.21E-05 NO DATA 1.03E-04 TEl31 1 76E-07 6.50E-08 4.94E-08 1.t?E-07 4.50E-07 Nn DATA 7.llE-06 Til32 2 0BE-05 1 03E-05 9.61E-06 1 52E-05 6.44E-05 NO DATA 3.51E-05 1 130 6.00E-06 1 32E-15 5. 3 0E -0 6 1.40E-03 1 45E-05 NO DATA 2.83E-06 1 131 3.59E-05 4.2 3E-0 5 1.4tE-05 1.39E-02 4.94E-05 NO DATA 1 51E-06 1 132 1 66E-06 3.37E-06 1. 2 0 E -0 6 1. Set-04 3.76E-06 NO DATA 2 73E-06 I 133 1.2bt-05 1.82F-05 5.33E-06 3.3tt-03 2 14E-05 NO DATA 3.00E-06 1 134 0 69E-07 1 78E-06 6. 3 3 E-0 7 4.15E-05 1 99E-06 NO DATA 1.34E-06 .
I 135 3 64E-06 7.24E-06 2.64E-06 6.49E-04 8.07E-06 NO DATA 2.62E-06 1 C5134 3.77E-04 7.03E-04 7.10 E-0 5 NO DATA 1.Ilt-04 7.42E-05 1.9tE-06 C5136 4.59E-05 1 35E-04 5. 04 E -0 5 NO DATA 5.30E-05 1.10E-05 2.05E-06 i C5117 5 22E-04 6.11E-04. 4. 3 3 E -0 5 NO DATA 1.64E-04 6.64E-05 1 9tE-06 i Clltt 4.Olf-07 7.02E-0T 3 79E-0 7 NO DATA 3 90E-07 6.09E-00 1 25E-04 Sal 35 8 81E-07 5.04E-10 2. 5 5 E -0 6 NO DATA 3.llE-10 3.54E-to 5.5BE-05
. .. .... .................... .............. .. ................... i 1
l
OBOL - REY. 3 TABLE 3-3a CONT'D INGESTION DOSE FACTORS FOR INFANT (MREM PER PCI INGESTED)
Page 3 of 3 i
MUELIDE 004E LIVER T.00DY THva010 RIONEY LUNC Cl-LLI SA140 1 71E 1.7tE-07 8.RIE-06 40 DATA 4.06E-Ot 1.0SE-07 4.20E-05 8A141 4.25E-07 2.913-10 1.3*E-08 NO DATA 1.75E-10 1.TTE-10 S.19E-06 84142 1.84E-07 1.53f-10 9. 06 E -0 9 NO DATA 8.81E-Il 9.26E-Il 7.59E-07 Lal40 2.llt-08 8.32f-09 2.14E-09 ND DATA NO Data NO DATA 9.77E-05 L A 14 2 1 10E-09 4 04E-10 9.6ff=11 NO DATA NO DATA NO DATA 6.86F=05 CEl41 7.8TE-08 4.80f-08 5.6SE-09 NO DATA 1.40E-09 NO DATA 2.48E-05 Cele) 1.48E-08 9.82E-06 1 17E-09 40 DATA 2.96f-09 NO DATA S.73E-05 CEl44 2.98f=06 "1.22E-06 4.67E-07 40 DATA 4.93E=07 NO DATA 1.7tE-04 PR14J 8.13E-08 1.04E-08 4.03E-09 NO DATA 1.13E-nt NO DATA 4.29E-05 PRl44 2.74E-10 1.06E-10 1. 3 0 E -! ! MO DATA 3.R4k-ll NO DATA 4.93E-06 N0147 5.b3E-08 5.68E-04 3. 4 8 E -0 9 NO DATA 2.19E-0R NO DATA 3.60E-Ob w 187 9.03E-07 6.28:=Of 2.17 E -0 T Mn DATA NO DATA NO DATA 3.69E-05 NP239 1.llE-08 9.93E-10 S . 61 E -10 40 DATA 1.98E-09 40 DATA 2.87F-05 l
J O
A s - _ _ _. . . . -- - - . - --.
GK3 - RW, 3 l
TABLE 3-3b 1 INGESTION DOSE FACTORS FOR CHILD (MREM PER PCI INGESTED)
Page 1 Of 3 l
l NuCLIDE SONF liver T . 50 pv TMen0ID KIDNEY LUNG GI-LLI H 3 40 DATA 2.03E-07 2.Olf-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 C E4 1.21E-05 2.*21-06 2.42E*06 2.42E-J6 2.42E-06 2.42E-06 2 42E-06 44 24 b.80E-06 5.80E-06 5.00E-06 5.00L-06 5.00E-06 5.80E-06 5 00E-06 9 32 0.2SE-04 3.06t-0$ 3.18E-Ob. 40 DATA 40 DATA 40 0414 2.28E-05 CR 51 NO C4fA NO LATA 8. 9 0E -0 9 4.94E-09 1.35E-09 9.02E-C9 4.72E-07 WN 54 40 DATA 1.07E-05 2. 0 5k -0 6 NO 94f4 3.00C-06 h0 04TA S.98E-06 MN 56 40 DATA 3 34E-02 7.54t-08 43 CafA 4.C4E-07 40 DATA 4.84E-05 FE Sb 1.lbt-05 6.10E-06 1 49?-06 ho Cafa hC Data 3.45E-06 1.13E-06 I FE 59 1.6st-05 2.67E-05 1 3st-05 40 DATA NO DaT4 7.74E-06 2.78E-05 CD le 40 Defa 1 00E-06 5.llE-06 40 DATA NC OATA NO CafA 1.0$E-05 l CD 60 40 Data 5.297-06 1.56E-05 NO DATA 40 DATA NO DAT A 2.93E-05 )
f 1.94C-06 l 41 63 5.30f-C4 2 8tF-05 1.8AE-05 NO cafa NO Cata NO DATA l l
NI 65 2.22E-06 2.09F-07 1 22E-07 NO DATA NO 0474 h6 oaf a 2.56E-05 CU 64 hu DafA ,,2 45E-07 1.40E-01 40 DATA 5.92E-07 ho DATA 1.15E-05 2N 65 1 37E-05 3 65E-03 2 27La05 40 DATA 2.30E-05 nn OaTA 6.4tt-06
/N 69 4.30E-00 6.s3E-08 5.SSE-09 NO Data 3.04E-08 40 DATA 3.99E-06 34 BJ NO Dafa 40 Data 1.71E-07 40 DATA NO DATA NO DATA LT E-24 ta 84 NO DATA 40 DafA 1.9ti-07 ho DATA NO DafA NO DATA LT E-24 RR 85 NO Daft NO DafA 9.12E-09 NO DATA 40 DATA h0 cafa LT E-24 Rb 86 NO DafA 6.70E-05 4.12E-05 NO DATA NO DATA NO 04TA 4.3tF-06 Rt 88 NO Caft 1 90E-07 1 32E-07 WO Defa 40 0414 NO Defa 9.32C-09 Ru 49 WO DATA 1 17E-07 1.04E-07 40 DATA NO 04T4 h0 DATA l.02E-09 1R 89 1.32E-03 NU O&T4 3. 7 7 E -0 5 40 DATA NO DATA NO DATA 5.llE-C5 SR 90 1.70E-02 40 DATA 4.3tf*03 40 Data 40 Data h0 Data 2.29E.c4 SR 91 2 40E-05 NO DATA 9.06E-07 WO DATA ho Data 40 0414 5.30E-05 l
SR 92 9.03E-C6 40 Data 3.62E-07 NO DATA NO DATA NO Data 1.7tE-04 l 1 17E.04 I Y 90 4.!!E-06 NO Dafa 1 10E-09 NO DATA 40 Data NO Data i
Y 9tM 1.82E-10 40 Data 1 39E-!! h0' Data 40 DATA WO Defa 7.40E-07 Y 91 6 02E-07 W0 041A 1 61 F =0 8 40 Data 40 Data Nn 04Ta 8.02E-05 Y 92 3 60E-09 40 DATA 1 0AE-10 NO 0&TA 90 DATA 40 0414 1.04E-04 This table was taken from NRC Regulatory Guide 1.109 Table E-13
,n
DDDI - REV. 3 .
I I
TABLE 3-3b CONT'D INGESTION DOSE FACTORS FOR CHILD (MREM PER PCI INGESTED)
Page 2 Of 3 NUCLICE SOME liver 7.80 pf THYR 010 EIDhtY LUNG GI-LLI y 93 1.14t=08 NO DATA 3.13 C-10 NO DATA NO DATA NO 04f4 1.70E-04 2R 95 1.16E-07 2.35E-05 2.27E-08 NO DATA 3.65E-08 h0 D&fe 2.66E-05 IR 97 6.991-09 1.C11-09 S.96E-10 NO DATA 1 45E-09 NO DATA 1.53t-04 NB 95 2 25f=08 8.76E-09 6.26t=09 NO DATA 8.23E-09 NO Data 1 62f-05 '
MD 99 NO Cata 1.33E-05 3.29E-06 NO DATA 2.84E-05 NO DATA 1 10t-05 TC 99u 9.23E-10 1 81t-09 3.03E-08 40 DATA 2.63E-08 9.19E-10 1 03E-06 -
FCIDI 1 07E-09 1 126-09 1.42t-08 40 CATA 1.911-CR 5.92f-10 3 56t-09 avlo) 7.38t-07 ND DATA 2.8tE=07 NO DATA 1 84t=06 NO DATA 1 89E-05 AU105 6 45E-08 NO DATA 2.34E-08 NO DATA 5.67E-07 NO DATA 4.2tE-05 .
RU106 1 17E-05 NO DATA 1 46f-06 NO DATA 1.58!-05 NO DATA l.82E-04 AG110M 5.39E-07 3.64C-07 2.91f-07 NO DATA 6.78E-07 NO DATA 4.33E-05 TEl25M 1 14E-05 3.09E-06 1. 5 7 t -0 6 3.20t=06 NO DATA NO DATA 1 108-05 fft2FM 2 89E-05 7.18t-06 3.4Jt-06 6.9tE-06 f.24E-05 NO DATA 2 34t-05 fil27 4.71E-07 1 278-07 1. 0 l t -0 7 3.261-07 1.14E-06 NO DATA 1 04E-05 fft29" 4 87E-05 E.s6f=05 7. S e t -0 6 1.551-05 1.43E-04 NO DATA 5.94t ft!29 1 34f=07 3.74E-08 3.18 E-0 8 9.56E-08 3.92E-07 NO DATA 8.34t-06 TE131M 7 201-06 2.49f-06 2 65t-06 5.12E-06 2.4tE-05 NO DATA 1 0lf-04 4 361-07 TElst 8.30E-08 2.53E-00 2.4 7 E-0 8 6.35E-08 2.51E-07 NO DATA 1 01 t-05 "4.4 7 E-Os 5.4 0 E-0 6 6.51E-06 4.15E-05 NO DATA 4.50E-05 TEl32 2 76t=06 l 130 2 92f-06 5.90E-06 3. 04 E -0 6 6.50E-04 8.821-06 NO DATA l 131 1 72E-05 1 7 3C-05 9. 8 J E-0 6 5.72t-03 2.84E-05 NO DATA 1 54E-06 1 132 8 00E-07 1.47t=06 6.76t 07 6.82E-05 2 251-06 NO Caf n 1.73t=06 I 133 5.92E-06 7.'2E-06 J 2.? ? E-0 6 1 36t-03 1 221-05 NO DATA 2 95E-06 1 134 4 191-07 7.78E-07 3.5BE-07 1.71E-05 1 19E-06 NO DAT A 5.16E-07 1.75E-06 3.15E-04 1.49E-06 2 79E-04 4.83E-06 NO DATA 2 40f-06 3 135 C5134 2 34E-04 3.84t=04 8.10E-05 NO DATA 1 19E-04 4.27E-05 2 0ff=06 C5136 2.35E-05 6 46t=05 4.18 E -0 5 NO DATA 3.44E-05 5.13E-06 2 27E-06 C5137 3 27t=04 3.13t=04 4.62E-05 40 O&ta 1.0!E-04 3 67E-05 1 96t-06 C5138 2 28E-07 3.17E-07 2 0lt-07 40 DATA 2.231-07 2 40t=0B l.46E-07 84139 4 14E-07 2.!!E-10 8 2 0t -0 8 40 DATA l.93t-10 1 30f=10 2 39E-05
OK* - RDi, 3 TABLE 3-3b CONT'D INGESTION DOSE FACTORS FOR CHILD (MREM PER PCI INGESTED)
Page 3 Of 3 NUCLlut SONE LivtR ' f . 40CY TMYROID E10%EY LUNG Cl-LLI Ral40 8.J1t-05 7.28E-08 4.05E-06 NO Data 2.37t-08 4.34E-08 4.211-03 SA141 2.00E-07 1.12;-10 6. b l E-0 9 NO Data 9.69E-11 6.Stt-10 1 14E-07 BA142 0.74L-08 6.29E-11 4. 0 8 f -0 9 NO DATA S.09E-11 3.70E-ll 1.let-09 L4140 1.0lf-CP 3.53E-09 1. lit-0 9 40 DaT4 NO CATA NO DATA 9.840-05 Lal42 S.24t-10 1.^1F-10 6.211-11 NO D&TA hn DAT4 NO DATA 3.31E-05 CE141 4.97t-OR I . "- :- 0 8 2.94 t-0 9 kn Dafa e.6Bi-09 ho DATA 2.4TE-05 CE14J 6.99t-09 3.19 E - 06 5.491-10 NO Data I.S9E-09 NO DATA S.SSt-OS Ctl44 2.00E-06 6.521-07 1.Ilf-07 NO DATA 3.616-07 NO DATA 1 70f=04 PRl4) 5.938-08 1.10t-08 1. 9 5 f-0 9 NO DATA 6.196-09 h0 DATA 4.24E-05 PRl44 1.29t-10 1.91E-11 6.49E-12 NO DATA 2.!!E-Il NO Da7a e.19E-04 N0147 2.79E=0A 2.261-08 1. 7 6 t =0 9 NO DATA 1.24L-08 NO DATA 3.58t-05 w 187 4.29E-07 2.54r-07 1.t*E-07 No caTa NO DATA h0 Data 3.57E-05 NP239 5.2bE-09 3.77t-10 2.6tJ-10 NO DATA I.09E-09 NO DATA 2 79E-05 I,
I i
l l
l l l l l l
.so - - _ _ _ _
0006 - Kv, 3 TABLE 3-4 W AL BODY DOSE FACTORS E .
FROM NOBLE GASES (GAMMA)
Finite Cloud **
0 NUCLIDE Y - BODY
- 10 (pci/ Ci) Correction Factor Ki ***
-8 6 Kr-83m 7.56x10 X 10 X 1.0 7.56E-2
~ 6 3.39E+2 Kr-85m 1.17x10 X 10 X 0.29
~ 6 4.19E+0 Kr-85 1.61x10 X 10 X 0.26 Kr-87 5.92x10" X 10 X 0.26 1.54E+3
~
Kr-88 1.47x10 X 10 X 0.22 3.23E+3
~
Kr-89 1.66x10 X 10 X 0.26 4.32E+3 Kr-90 1.56x10" X 10 X 0.26 4.06E+3
~ 6 Xe-131m 9.15x10 ' X 10 X 0.31 2.84E+1
~4 6 7.28E+1 Xe-133m 2.51x10 X 10 X 0.29
~4 6 9.70E+1 Xe-133 2.94x10 X 10 X 0.33
~3 6 8.42E+2 Xe-135m . 3.12x10 X 10 X 0.27
~3 6 0.29 5.2SE+2 Xe-135 1.81x10 X 10 X
~ 6 3.69E+2 Xe-137 1.42x10 X 10 X 0.26
~ 6 2.21E+3 Xe-138 8.83x10 X 10 X 0.25 8.84x10'3 10 X 0.22 1.94E+3 Ar-41 X
- From Regulatory Guide 1.109, Table B-1 (mrem /yr per pCi/m'<)
- The finito cloud correction factor is described in Section 3.6.
- Xi (mrem /yr per pCi/m
OKA - 80, 3 TABLE 3-5 SKIN DOSE FACTORS S
FROM NOBLE GASES (BETA)
NUCLIDE B - SKIN
- 10 (pCi/ Ci) Li **
6 Kr-83m X 10 6
Kr-85m 1.46x10" X 10 1.46x10
~ 6 Kr-85 1.34x10 X 10 1.34x10 6
Kr-87 9.73x10" X 10 9.73x10
~ 6 Kr-88 2.37x10 X 10 2.37x10 6
Kr-89 1.01x10" X 10 1.01x10
~3 0 Kr-90 7.29x10 X 10 - 7.29x10
~4 6 2 Xe-131m 4.76x10 X 10 4.76x10 0
Xe-133m 9.94x10"4 X 10 9.94x10 6 2 Xe-133 3.06x10" X 10 3.06x10
~4 6 2 Xe-135m 7,11x10 X 10 7.11x10
~3 6 3 Xe-135 1.86x10 X 10 1.86x10
-2 6 4 Xe-137 1.22x10 X 10 1.22x10
~3 6 3 Xe-138 4.13x10 X 10 4.13x10
~ 6 Ar-41 2.69x10 X 10 2.69x10
)
- Prom Regulatory Guide 1.109, Table B-1 (mrem /yr per pCi/m )
- Li (mrem /yr per VCi/m )
't 61
(SCA - REY. 3 TABLE 3-6 AIR DOSE FACTORS FROM NOBLE GASES (GAMMk)
Finite Cloud **
NUCLIDE y - Air
- 106 (pCiACi) Correction Factor Mi ***
~
Kr-83m 1.93x10 X 10 X 1.0 1.93E+1
~ 6 0.29 3.57E+2 Kr-85m 1.23x10 X 10 X
~
Kr-85 1.72x10 X 10 X G.26 4.47E+0
~
Kr-87 6.17x10 X 10 X 0.26 1.60E+3
~ 6 3.34E+3 Kr-88 1.52x10 X 10 X 0.22
~
Kr-89 1.73x10 X 10 X 0.26 4.50E+3 Kr-90 1.63x10" X 10 X 0.26 4.24E+3
~4 6 4.84E+1 Xe-131m 1.56x10 X 10 X 0.31 6 9.48E+1 Xe-133m 3.27x10 X 10 X 0.29
~ 6 Xe-133 3.53x10 X 10 X 0.33 1.16E+2
~3 6 9.07E+2 Xe-135m 3._36x10 X 10 X 0.27
~
Xe-135 1.92x10 X 10 X 0.29 5.57E+2
-3 6 Xe-137 1.51x10 X 10 X 0.26 ;3.93E+2 ;
~ 6 2.30E+3 Xe-138 9.21x10 X 10 X 0.25
~
Ar-41 9.30x10 X 10 X 0.22 2.05E+3
- From Regulatory Guide 1.109, Table B-1 (mrad /yr per pCi/m ) P
- The finite cloud correction factor is described in Section 3.6
- " Mi (mrad /yr per pCi/m )
00CR - REV. 3 TABLE 3-7 AIR DOSE FACTORS (Ni) FROM NOBLE GASES (BETA) a
- BETA NUCLIDE AIR 10 (pCi/uci) Ni**
Kr-83m 2.88E-04 10 2.88E02 Kr-85m 1.97E-03 10 1.97E03 Kr-85 1.95E-03 10 1.95s03 6
Kr-87 1.03E-02 10 1.03E04.
6 Kr-88 2.93E-03 10 2.93E03 6
Kr-89 1.062-02 10 1.06E04 6
Kr-90 7.83E-03 10 7.83E03 Xe-131m 1.11E-03 10 1.11E03 Xe-133m 1.48E-03 10 1.48E03 Xe-133 1.05E-03 10 1.05E03 Xe-135m 7.39E-04 10 7.39E02 Xe-135 .
2.46E-03 10 2.46E03 6
Xe-137 1.27E-02 10 1.27E04
. Xe-138 4.75E-03 10 4.75E03 Ar-41 3.28E-03 10 3.28E03
- Prom Regulatory Guide 1.109, Table B-1 (mrad /yr per pCi/m )
- Ni (mrad /yr per uCi/m )
f filk
0006o tu , 3
,, TABLE 3-8 SKIN DOSE FACTORS FROM NOBLE GASES (BETA-CAMMA)
Si = 4(Li+1.1Mi) 1 (M is Finits Cloud Corrected) .
NUCLIDE Li Mi Si = (Li+1.1Mi)
I Kr-83m 1.93E1 2.12E+1 3 1.85E+3 Kr-85m 1.46x10 3.57E+2 Kr-85 1.34x10 4.47E+0 1.34E+3 Kr-87 9.73x10 1.60E+3 1.15E+4 3 6.04E+3 Kr-88 2.37x10 3.34C+3 4 1.60E+4 Kr-89 1.101x10 4.50E+3 Kr-90 7.29x10 4.24E+3 1.20E+4 Xe-131m 4.76x10 4.84E+1 5.29E+2
, Xe-133m 9.94x10 9.4BE+1 1.10E+3 [
Xe-133 3.06x10 1.16E+2 4.34E+2 2 1.71E+3 Xe-135m 7.11x10 9.07E+2 2.47E+3.
i Xe-135 1.86x10 5.57E+2 4 1.27E+4 Xe-137 1.22x10 3.93E+2 Xe-138 4,13x10 2.30E+3 6.66E+3 Ar-41 2.69x10 2.05E+3 4.95E+3
- From Table 3-5 (mrad /yr per pCi/m )
I 3
- From Table 3-6 (mrad /yr per pCi/m ) .
f I
- Si (mrem /yr per UCi/m )
I
(BOI - MV.1 TABLE 3-9 DOSE FACTORS FOR SITE BOUNDARY
- (X, M, S are Finite Cloud Corrected) r Nuclide Ki
- Li
- Mi ** Ni ** SI
- Kr-83m 2.27E-6 0.00E+0 5.79E-4 8.64E-3 6.36E-4 Kr-85m 1.02E-2 4.38E-2 1.07E-2 5.91E-2 5.55c-2 Kr-85 1.26E-4 4.02E-2 1.34E-4 5.85C-2 4.02E-2
- Kr-87 4.62E-2 2.92E-1 4.80E-2 3.09E-1 3.45E-1 9.69E-2 7.11E-2 1.00E-1 8.79E-2 1.81E-1 ,
Kr-88 1.30E-1 3.03E-1 1.35E-1 3.17E-1 4.80E-1 Kr-89 1.22E-1 2.19E-l' l.27E-1 2.36C-1 3.60E-1 Kr-90 8.52E-4 1.43E-2 1.44E-3 3.33E-2 1.59E-2 Xe-131m Xe-133m 2.18E-3 2.98E-2 2.84E-3 4.44E-2 3.3E-2 2.91E-3 9.18E-3 3.48E-3 3.15E-2 1.30E-2 Xe-133 Xe-135m 2.53E-2 2.13E-2 2.72E-2 2.22E-2 5.13E-2 1.58E-2 5.58E-2 1.61C-2 7.38E-2 7.41E-2 Xe-135 1.llE-2 2.61E-1 1.18E-2 3.17E-1 3.81E-1 Xe-137 6.63E-2 1.24E-1 6.9E-2 1.43E-1 2.00E-1 Xe-138 5.82E-2 d.08E-2 6.15E-2 9.84E-2 1.49E-1*
Ar-41 r
(X/Q)v = 3.0E-5 sec/m3 :
i
- Ki, Li, Si, (mrem.sec per uCi. yr) [
I
- Mi, Ni, (mrad.see per uCi. yr) t
00cn - REY. 3 TABLE 3-10 Dose Factors For Site Boundary Using Standard Isotopic Mixtures Instantaneous Release Mixture Relative Nuclide Abundance Weighted Dose Ractors Kr 85m 4.06E-2 E.=1.94E-2(mrem-secperUCi-yr)
Kr 87 4.36E-2 I.=4.54E-2(mrem-secperuCi-yr)
Kr 88 8.25E-2 S=2.05E-2(mrad-seeperuCi-yr)
Xe 131m 1.09E-1 = 6.46E-2 (mrad - sec per UCi-yr)
Xe 133m 1.23E-2 $ = 6.79E-2 (mrem - sec per uCi-yr)
Xe 133 4.11E-1 Xe 135m 2.88E-2 Xe 135 2.21E-1 Xe 138 5.18E-2 Time Averaged Release Mixture Relative Nuclide Abundance Weighted Dose Factors Kr 85 5.33E-5 I( = 5.49E-3 (mrem - sec per uCi-yr) 3 Kr 85m 1.63E-2 i. = 1.88E-2 (mrem - see per uCi-yr)
Xe 131m 4.72E-4 it = 6.15E-3 (mrad - sec per uCi-yr)
Xe 133 7.89E-1 E = 4.01E-2 (mrad - sec per uCi-yr)
Xe 133m 4.46E-4 'S = 2.55E-2 (mrem - sec per uCi-yr)
Xe 135 1.93E-1 M
a SCM o REV. 3 TABLE 3-11 1 LOCATIONS OF SITE BOUNDARY AND NEAREST RESIDENCES Distance
- Nearest Point of Distance
- sector site Boundary Hearest Residence (Meters) (Meters)
N River 1950 NIM River 1740 NW ,, River 1830 WNW River 1830 W River 1890 WSW River 2135 SW 350 2745 SSW 380 1525 S 580 1280
, SSE 595 1220 SE 580 1100 ESE 580 1070 E 625 730 ENE 760 1370 NE 790 1525 NNE River 3050
- Measured from Indian Point 3.
4
- O
( App. 3-A pg. 1 of 7)
IM3 - WN.1 i
APPENDIX 3-A ,
i CALCULATION OF ALLOWABLE RELEASE RATES Primary Assumptions:
- 1. Unit 3 and Unit 2 effective dose factor K,gf._ values are equivalent, ,
- 2. Each,ynit shares 50% of the total allowable release rate. 0, in l' Therefore Q 3 =Q 2 f r instantano us releases.
Ci s .
Givent Location Unit 3 Unit 2 Location W (in) Arnual Average Site -3 -5 B%undary X/Q (SW350m) 3.oE-5 sm 1.2 x 10 (sW579m)
W (gp) Annual Ave. Ground Plane .
-2 i SYteBoundaryDeposition (SSW380m) 7.9E-8 m l
Wy (f) Food Pathway Dispersion -2 Parameter ,,
(SSW5.0ml) 4.7E-10 m ;
Wy (in) Annual Ave X/Q (5 mi) (SSW 5mi) 2.9E-7 sm" W (in) Inhalation Pathway Nearest 3 Residence (SSW1526m) 2.7E-6 sm ,
Wy (gp) Annual Ave. Ground Plane -2 Depos Parameter Nearest Residence (S 1279 m) 8.7E-9 m 3
From Table 3-10 Ks = 1.94E-2 mrem-see 1 yr 1 2.OGE-5 mrem-m K effective i
uCi-yr
- 3.15E7 sNe 3E-5 sec/m " uCi-s 4
(X/Q) f i
a l
I J
I i
l 4 ,
4 I
4
(App. 3-A, pg. 3 of 7) 3(3 - 3 0 . 3 INSTAttrANEOUS RELEASE RATE VS. DOSE RATE UNITS 2 & 3 A.- Instantaneous Dose Rate: Calculation of Allowable Release Rates Noble Gas Release Including Finite Cloud Correction for Site Boundary
- i. Whole Body
[(Eeff)(X/Q)g(Qiv)3 500 mrom yr" (subscript i refers to each I (values'and units of above parameters of the two sites) are given on previous page)
~ ~1 a) 500 mrem yr = 1.585E-5 mrem s
~l b) Let Q 3 =Q = Q in uCi s c) Solve for 00 mem yr Q((Kef f) 3 (X/Q) 3 + (KeW2 I !9' 2) ~
Q ( (2. 06.E-5 ) (3.0 C-5) + (2. 98 E-5) (1. 2E-5 ) ) = 1.585E-5 mrem s
~
Q = 1. 6 3E4 uCi sec = 1.63E-2 Ci/sec
~
d) Dose Committments per site for Q = 2.93E4 uCi sec 3
Unit 3: 1.63 E4 uCi x 2.06 E-5 mrem-m x 3.0 E-5 s,3 x 3.HE7 i = 317 mrem y sen uCi-s m yr 3
Unit 2: 1.63 E4 uci x 2.98 E-5 mrem-m x 1.2E-5 s.3x 3.15E7 s, = 183 mrem yr sec uCi-s m yr Unit 3 has 63% and Unit 2 had 37% of the dose rate limit, ii. Skini f
-I (Lg + 1.1 tig) (X/Q)g(Qgy)5 3000 mrem yr
~ ~
a) 3000 mrem yr b)
=9.51{-5mrems '
Let Q3=Q Solve for g, in c s-c) 3 d) (L3 + 1.1 Mi) for Unit 3 = 7.19E-5 mrad-m , for Unit 2 = 8. 33E-5 mrad-m uCi-s uCi-s Q ( (7.19L-5 ) ( 3. 0E-5 ) + (8. 3 3E-5) (1. 2E-5 ) ) = 9. 51E-5
~
Q = 3.01E+4 uCi sec
- Dose factors for skin 9 site boundary are finite cloud corrected refer to ODCM Section 3.6 for discussion of finite cloud geometry.
~
NOTE: The allowable release rate is 1.63E-2 Ci s as calculated in A above due to the limiting whole body dose rate.
(App. 3-A, pg. 3 of 7)
ODCM R;v. 3 RELEASE RATE LIMITS Quarterly and Annual Average Noble Gas Releases For a Calendar Quarter For a Calendar Year ,
I air dose 35 mrad ~1' air dose $10 mrad A air dose fl0 mrad ja air dose $20 mrad I. ASSUMPTIONS: 1. Doses are delivered to the air 9 the site boundary.
- 2. Finite Cloud geometry is assumed for noble gas releases 9 site boundary.
t X/Q for Unit 3 = 3.0E-5 sm -3 , (Q = release rate uCi s-1 )
3.
- 4. Gamma air dose factor (M), Corrgeted for finite cloud geometry is: M = 2.05E+2 mrad-m uCi-yr
- 5. Betaairdosefactor(N)isunajfectedbyfinitecloud assumption: N = 1.337E+3 mead-m uCi-yr ,
II. Calculation of Allowable Release Rates - Quarterly Limits
~I
' a. for dose:
- b. for dose: (Q)/(M)(X/Q)( 5 mrad /qtr (20 mrad yr(Q)/(H)(X/Q)i10 mrad3/qtr(
~
5 mrad /qtr = 3.30E+3 uCi s'1 = 3.30E-3 Ci s Solve for a. Q =
(M) (X/Q)
-I
- b. = 10 mrad /atr = 1.01E+3 uCi s"1 = 1.01E-3 Ci s Q
(M) (X/Q)
Based on the above analysis the 4 dose is limiting for time average doses ,3 and therefore the allowable quarterly average release rate is 1.01E-3 Ci s III. Allowable Release Rate - Calendar Year Annual Limits are 1/2 the quarterly 11gits, therefore, mgximum allowable annual average release rate is 5.06E+2 uCi s or 5.06E-4 Ci s .
l 70 -- __
-(App. 3-A, pg.-4 of 7) ,
i NOI - EV. 3 ALLOWABLE INSTANTANEOUS RELEASE RATE i IODINES /PARTICULATES (Tl i >0 Days) r Given X/Q for IP3 = 3.0; E-5 sm" G 350m SW X/Q for IP2 = 1.2 E-5 sm @ 579m SW P
nhal. = 1.62 E7 mrem /yr '
Child jg Assumed Pathway: Child Inhalation at Unrestricted Area Boundary solve the following equation for Q:
"#** Y #
OI h (X/Q) Unit 3 # EI '( !E' Unit 2 IP3 QP (X/Q)) = Q l.62E7 mrem yr" 3.0E-5 s_3 = Q 486 mrem yr ,
uCi m-J m uci s-'
-1 -1 IP2 Q P (X/Q)2 = Q l.62E7 mrem yr 1.2E-5 s,3 =
Q1M mem { .
uCi m-J m uci s
{ = 680 Q mrem yr-1 [
uCi s-1 .
t
~
Limit is 1500 mrem yr per sites ;
therefore: 680 Q mrem yr~ 5 1500 mrem yr" "
uCi s-1
~
Q = 2.2 uCi s ,y ,
Q = 2.2 E 6 Ci s per unit i
IP3 Dose Contribution: 2.2 uci x 1.62E7 mrem m x 3.0 E-5 s3 = 1.07E3 mem y[
s yr uCi m IP2 Dose Contribution: 2.2 uCi x 1.62E7 mrem m x 1. 2E-5 s 3= 4. 3 E2 mem yr f s yr uCi m
{-:=c1500mram/yr [
Approximately a 71% - 29% dose split for IP3 and IP2 respectively.
I l
i 8
P P
I
(App. 3-A, pg. 5 of 7) '
, i GNR - EN. 3 ALLOWABLE RELEASE RATES FOR IODINE / PARTICULATE TIME AVERAGE DOSES QUARTERLY AND ANNUAL DOSE LIMITS L
There are two receptor pathways considered; a primary receptor - child at the nearest residence, and a secondary receptor - Infant at 5 miles.
As discussed in the ODCM, both receptors will be considered when evaluating time averaged dose committments. For the purpose of setting an administrative ,
limit on quarterly and time average release rates the secondary receptor was chosen because it proved more limiting (only long term releases were considered, ,
e.g. the possibility of intermittent releases was not considered for the calculation).
Calculations for both receptor locations are included in this attachment for reference.
i r
a 4
f j
e I
l
.p m .- -
P r
(App. 3-A, pg. 6 of 7) !
IODINE TIME AVERAGE
- g g . ggy, )
Primary Receptor Child at the nearest residence Givent** 9 1526m SSW inhalation X/Q = 72.7.E-6 D/Q = 8. E-9 m sm} 9 1279 m Splane deposition f actor ground i R = 1.62E+7 mrem /yr, child inhal. dose factor for I-131 Child uCi/mJ ,
R = 2.1E7 m mrem yr7 l uCi s
2 vegetation path for child C ld = 4.77E10 m mrem /yr[ ,
R uCi sec ,
Calculate the allowable time ave. release rate by solving the following equation for Q:
~
Q R X/Q + R D/Q + R D/Q 5 mrem yr
~
~
- 2. 7 E-6 sm" = Q 43. 7 mrem yr QRfX/Q=Q(1.62E+7)mremyr uCi s~1 uC1 m'd
~ ~ ~
QRGD/Q = Q(2.1E7) m mrem yr 8. 7 E-9 m =Q 0.2 mren yr ~
uCi s*1 uCi s-1 1 ~1 Q R" D/Q = Q (4. 77E10) m mrem yrI 8. 7 E-9 m' = Q 415 mrem yr uCi s"* uCi s-1 mrem yr~ )Q
[ = ( 459 uCi s-1 1
Quarterly Time Ave. (Limit is 7.5 mrem to any organ or 30 mrem /yr)
-1 Solving for Q yields: Q 459 mrem yr~15 30 mrem yr uCi s-1 o
Q = 6.54E-2 uCi s~1 ,
= 6.54E-8 Ci s~1 4
~
Annual Limit is \ Quarterly Limitt 15 mrem to any organ (15 mrem yr )
~
Q = 6,54E-8 = 3.27E-8 Ci s '
2
- All iodines and particulates with half lives greater than 8 days are assumed ,
j to be I-131 for the purposes of this calculation which is a conservative assumption since this nuclide has the highest thyroid dose factor of all iodines and particulates. [
o 1
_. ., . _ _ _ _ . _ _ . , , , . .sa . .- . , _ _
s (App. 3-A pg. 7 of 7) 00CR-ttV.3
- IODINE TIME AVERAGE
~
R = 1.48E7 mrem yr infant inhal. dose factor ,
infant _3
~
R = 2.lE7 mrem yr m ground plant dose factor uCi s-1
= 1.06E12 mrem yr m
~
cow-milk pathway dose factor for infant Rfnf. uCi s-A v
R is not calculated because the infant is assumed to have no intake of inf fresh vegetables. t Calculate the allowable time ave. release rate by solving the following equation for Q: -
Q R X/Q + R D/Q + Pint !E " "#*" Y f
~ ~
QR inf X/Q = Q l.48E7 mrem yr 2. 9 E-7 sm' = Q 4.3 mrem yr uCi m'J uCi s-A ,
QR D/Q = Q 2.lE7 m mrem yr"l_ 4.7E-10 m
~
= Q . 01 mrem yr" uCi s uCi s-1 D/Q = Q .06E12 m mrem yr 4.7 E-10 m =QG8 mnm yr QRfnf uCi s-A uCi s-' f
{(502. 3brem yr!'
Quarterly Limit 7.5 mrem to any organ (or 30 mren/yr) uCi s
i Solve for Q: ,
-1 = 30 mrem yr ~ !
(502.3) Q mrem yr uCi s-1 [
Q= [
5.97E-2uCis{
= 5.97E-8 Ci s !
Annual Limit is in Qtrly Limit: 15 mrem (or 15 mrem /yr) !
Q= 2.99E-8 Ci s
- See note under Primary Receptor Calculation f'
" See note under Primary Receptor Calculation i
f
. SCR-REV.3
~ Release Point Main Condensers [ Release cint
. I I Condenser Air Ejector '
,,,On High I o Alarm I 9
i Containment Building
--)
g
- Primary Aux. Building "
+ Waste Gas Tanks
- R13 Fuel Storaga Building M !
102 :
l Rad. Machine Shop ,,
Releas Point M l 101 l Admin. Building P.adiation Monitor I
t e, Gaseous Radioactive Waste Effluent System Flow Diagram ,
Figure 3-1
)
GNX - REV. 3 4.0 SAMPLE LOCATIONS Figure 4.1 is a map which shows the location of environmental sampling points within 2.5 miles of the Indian Point Plant and Figure 4.2 is a map providing the same information for points at greater distances from the plant. Table 4.1 provides a description of environmental sample locations and the sample types collected at each of these locations.
" The locations listed in Table 4.1 are'the RETS designated locations only. The air sample locations were chosen considering the highest average annual D/Q sectors and the practicality of locating continuous air samples. There are backup sample locations not listed in Table 4.1 that may be maintained to provide the program with additional sup-porting information.
I l
t I
I i
4 l
l I
RADIOLOGICA EINZRONMENTAL MO!1ZTOR2t1G - SAMPL2NG STATIONS (g g . ggy, 3 F?GURE 4-1 V=~ \
m- 1 on.
slan DR1 A3
\/
/s -
Ib I4 Hudson Riv.r 3 b
a
- Indian Poi m ,' h r
p=_I -
@ .- , O
@ DRIC
- A4 J
A .
, 1 Mile ,
d - Wat.rborn. Surf c. Was
==
,, o - otr.es n.41. tion Sampi. toe.ston oR, , ,g ,g , ,
. o - ursorn. Sampi. Ioe. sten Ae
- g - o1.r. n.41. tion m rdorn.
O RADIOLOGICAL DNIRONMENTAL MONITORING - SAMPLING STATIONS 301
- M 3 FIGURE 4-3 *
- r DRW w.
M Beacon-Newburgh Bridge A5 f
6~ f
\== I Dutchess Cobnty y
/"I Qtange, County Putnam County
@ 2 @
Bear Mountain Bridge IU ' Indian Point h Hudson Y 23 h -
- River 2%
Rockland County Westchester County
\
b 5 Miles Tappan Zee /
Bridge 1
- O - otr et a diatiaa 5 et tac tiaa o"-
- Direct Radiation / Airborne Q - Waterborne. Drinking, t l
KEY:
Q - Shoreline Sediment Wet l
78 _ _--_.
Ohm - NN 3 l
Table 4.1 Indian Point Station Environmental Sampling Station Points !
Exposure Pathway / Sample: Direct Radiation ,
l RETS Sample Designation Location Distance DR1 Cortlandt Sanitation Garage 2 mi - N DR2 Old Pemart Ave. 2 mi - NNE DR3 Charles Point 0.8 mi - NE DR4 Lents Cove 0.5 mi - ENE DR$ Broadway and Bleakley 0.4 mi - E DR6 Sector Six Reuter Stokes Pole 0.5 mi - ESE DR7 Water Meter House 0.3 mi - E !
DR8 Service Center Building 0.4 mi - SSE DR9 SE Corner 0.9 mi - SSE 1 mi - $$W DRIO NYU Tower DR11 White Beach ! si - SSW DR12 Gays Hill Road South 1.5 mi - WSW DR13 Gays Hill Road North 1 mi - W DR14 Rt. 9W Pirates Cove 1 mi - WNW DR15 Rt. 9W South of Ayers Road 1 mi - NW DR16 Ayers Road I si - NNW DR17 Rt. 9D Garrison 5 mi - N o DRl8 Gallows Hill Road 5 mi - NNE DR19 Westbrook Drive 5 mi - NE DR20 Pine Road - Cortlandt 5 mi - ENE ,
DR21 Croton Ave. - Cortlandt 5 mi - E DR22 Colabaugh Pond Rd. Cortlandt 5 mi - ESE DR23 Mt. Airy & Windsor Road 5 mi - SE ,
DR24 Croton Point 7.5 mi - SSE DR25 Warren Ave. Haverstraw 5 mi - S DR26 Railroad Ave. & 9W 5 mi - SSW DR27 Willow Grove Road & Birch Drive 5 mi - SW '
DR28 Palisades Parkway-NY/NJ Sign 5 mi - WSW DR29 Palisades Parkway 4 mi - W ,
DR30 Anthony Wayne Park 4.5 mi - WNW l DR31 Palisades Pkwy Lake Welch Exit 5 mi - NW (South)
DR32 Rt. 9W Fort Montgomery 5 mi - NNW !
DR33 Hamilton St. 3 mi - NNE DR34 Furnace Dock 3.5 mi - SE DR35 Highland Ave. & Sprout Brook 3 mi - NNE DR36 Lower South & Bay Street 1.5 mi - NE DR37 Verplantk-Broadway & Sixth St. 1.5 mi - SSW DR38 Montrose Marina 1.5 mi - S .
DR39 Grassy Point 3 mi - S l t DR40 Roseton* 20 mi - N ,
i 96-
'yll #e NCA.ett,3 in is
+ ,
Li:
Table 4.1 (Cont'd)
Exposure Pathway / Sample: Airborne RETS Cesianation Location Distance Al Algonquin cas Line 0.25 mi - SW A2 Standard Brands 0.6 mi - NE A3 Cortlandt Sanitation Carage 2 mi - N AA NYU Tower 1 mi - SW A5 *Roseton- 20~mi - N Exposure Pathway /Samplet Waterborne-Surface (Hudson River Water)
Wat Plant Inlet N/A Wa2 .,
Discharge Canal N/A Exposure Pathway / Sample: Waterborne- Drinking Wbl Camp Field Reservoir 3.5 mi - NE Exposure Pathway /Saaple: Sediment from Shoreline Wel White Beach 0.9 mi - SSW We2
- Manitou Inlet 4.5 mi - N
- Control Station Location Exposure Pathway / Sample Milk
~ ~
There are no milch animals within 8 ka distance of Indian Point therefore, no milk samples are taken.
Exposure Pathway / Sample Ingestion-Pish and Invertebrates The RETS designate two required sample locations labeled Ib1 and Ib2.
The downstream Ib1 location and samples will be chosen where it is likely to be effected by plant discharge. Ib2 will be a locationThe upstream that is not likely to be effected by plant discharge.
following fish species are considered acceptable sample species.
Striped Bass Bluegill Sunfish White Perch Pumpkin Seed Sunfish White Catfish blueback Herring American Eel Crabs 9
_ _ _ _ _ _ . _ _ _ . _ - _ _ _ _ _ _ __y.-
WCR - BEY. 3 t
t i
Table 4.1 (Cont'd) {
i Exposure Pathway / Sample: Ingestion-Pood Products (Broad Leaf Vegetation) i ,
l RETS Desianation Location Distance ,
Icl SW and SSW Sectors N.Y.U. 0 - 1 mile f Ic2 N and NE Sectors Campsaith 1 - 3 miles .
i Ic3 Rosaton (North) 20 miles l l
[
i f
I i
I I
! h I
1 i
~
i l i
~
[
. t i
3 i
i t
(,
- t i
i
- i i ;
i
' l, Corrections to Previously Submitted .
Semi-Annual Effluent Reports The following corrections should be made to previously submitted semi-annual effluent reports. The corrections to the "Average Stream Flow" where the result of identifying an error in calculation. The corrections to the 1984 isotopic activities is the result of a review performed for Brookhaven National Laboratory as requested by your letter dated May 16, 1986.
Average Stream Flow (CFS) i Previous Correct i 1984 First Quarter 67000 9667 [
1984 Second Quarter 126000 14044 ,
1984 Third Quarter 32950 10983
., 1984 Fourth Quarter 37050 12350 1985 First Quarter 60800 20267 1985 Secord Quarter 41550 13850 Table 1.A.B.1 4th Quarter 1984 Total Iodine-131 1.61E-2 2.24E-3 f I
1 l
[
s d
t i
t
Effluent and Waste Disposal Semi-Annual Report January 1 - June 30, 1986 Facility Indian Point 3 Licensee New York Power Authority This information is provided in accordance with the requirements of Regulatory Guide 1.21. The numbered sections of this report reference corresponding sections of the subject Regulatory Guide, pages 1.21-10 to 12.
A. Supplemental Information
- 1. Regulatory Limits Indian Point 3 is presen_ly subject to limits on radioactive waste releases that are set forth in sactions 2.3.1, 2.3.2, 2.3.3, 2.4.1, 2.4.2, 2.4.3 and 2.4.4 of Appendix B to Docket #50-286 entitled "Environmental Technical Specification Requirements Part II Radiological Environmental". The percentages of the technical specification limits reported in Tables 1A and 2A are the percent of the quarterly limits specified in the ETSR. If more than one limit applies to the release the most restrictive limit is applied.
- 2. Maximum Permissible concentration
- a. Fission and Activation Gases The quarterly dose resulting from release of fission and activation gases is calculated in accordance with the methodology stated in the off Site Dose Calculation Manual (ODCM). The specific isotopes listed in Table 1C are used to determine the effective dose factors for the time period.
b&c. Iodines, Tritium and Particulates The quarterly organ dose limit for Iodine 131, tritium and ,
particulates with half-lives greater than eight days is calculated in accordance with the methodology stated in the ODCM.
- d. Liquid Effluents The quarterly dose limit for liquid isotopic releases is calculated in aorrrdance with the methodology stated in the ODCM. The instantaneous concentration limit for noble gases dissolved in liquid releases its calculated based upon a neximum permissible concentration of 2.00E 4 c required by section 2.3.1.A of the ETSR.
- 3. Average Energy The average energies (E) of the radionuclide mixture in releases of fission and activation gases were as follows:
1st Quarter E = 1.55E-1 MeV/ dis E = 6.75E-2 MeV/ dis 2nd Quarter E = 1.46E-1 MeV/ dis E = 5.55E-2 MeV/ dis
- 4. Measurements and Approximations of Total Radioactivity
- a. Fission and Activation Gases Analysis of effluent gases has been performed in compliance with the requirements of Table 3.4-1 of the ETSR. In the case of isolated tanks (batch release) the total activity discharged is based on an isotopic analysis of each batch with the volume of gas in the batch corrected to standard temperature and pressure.
Vapor containment purge discharges have been treated as batch releases and pressure relief discharges have been treated as continuous releases (> 500 hrs / year as defined in NUREG 0133). At least one complete isotopic concentration analysis of containment air is performed monthly. This analysis is used in conjunction with a process monitor to obtain the isotopic mixture and quantification of each pressure relief. Isotopic analyses for each vapor containment purge are taken prior to and during the purge. This information is combined with the volume of air in each discharge to calculate the quantity of activity, from these discharges.
The continuous building discharges are based on weekly samples of ventilation air for isotopic content. This informatien is combined with total air volume discharged and the process radiation monitor readings to determine the quantity of activity from continuous discharges.
b&c. Iodines and Particulates Iodine-131 and particulate releases are quantified by collecting a continuous sample of ventilation air on a TEDA impregnated activated charcoal cartridge and a glass-fiber filtar paper. These samples are changed weekly as required in Table 3.4-1 of the ETSR and the concent-ration of isotopes found by analysis of these samples is combined with the volume or air discharged during the sampling period to calculate ;
the quantity of activity discharged. !
For other iodine isotopes the concentration of each isotope is dete ermined monthly on a 24-hour semple. The concentration of the isotopes found by analysis is combined with the volume of air discharged during the sampling period to calculate the quantity of activity discharged.
I 1
l l
l l
l
v
'd. Liauid Effluents A sample of each batch discharge is taken and an isotopic analysis is perfomed in compliance with requirements specified in Table 3.3-1 of the ETSR. This isotopic concentration data is ceabined with information on volume discharged to determine the amount of each isotope discharged.
Proportional composite samples of continuous discharges are
[
taken and analysed in compliance with Table 3.3-1 of the ETSR.
l This concentration data is combined with the volume discharged to calculate the total activity discharged.
l l
- 5. Batch Releases
- a. Liquid
'1986 let Quarter 2nd Quarter Number of Batch Releases 45 63 Total Time Period Batch Releases (Min.)" 11567 17166 Maximum " " " " " 412 513
" " " " " 257 272 Average "
Minimum " " " " " " 155 120 Average Stream Flow (cfs)
I
- b. Gaseous Number of Batch Releases 1 18 Total Time Period Batch Release (Min.) 75 8858 ;
Maximum
" " " " " 75 5075 l
" " " " " 75 492 l Average Minimum " " " " " 75 30
- 6. Abnormal Releases l
- a. Liquid Mone
- b. Gaseous None
e i
r i
7.0 Radiological Environmental Technical Specifications !
l The Radiological Environmental Technical Specifications regaire reporting '
of prolonged outage of effluent monitoring equipment (Sections 2.1.C and
- 2.2.5) and significant changes in the land use census, Radiological Environmental Monitoring Program or exceeding the total curie content i limitations in outdoor tanks. (Sections 2.8.A 2.8.B, 2.7.C and '
2.3.4.8). During this reporting period no reportable events occurred.
The RETS modified the content and format of the Semi-Annual Effluent Release Report (Section 5.3.3.1). A Section G "Offsite Dose Calculation i Manual Changes", has been included. During this reporting period there l were several changes to the Offsite Dose calculation Manual. There were no changes in the Process Control Program. [
I i
r
?
i 3
1 t
l i
I I
i.
l l
Indian Point 3 EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT B. GASEOUS EFFLUENTS FIRST AND SECOND QUARTER, 1986
- ~
TABLE 1A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1986)
GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES UNIT QUARTER QUARTER EST. TOTAL 3 1st 2nd Error %
A. Fission & Activation Gases
- 1. Total release Ci 5.54E+2 7.35E+2 2.50E+1
- 2. Average release rate for period uCi/sec 7.12E+1 9.35E+1
- 3. Percent of technical specification % 6.41E+0 7.90E+0 limit.
B. Iodines 1.03E-3 2.14E-3 2.50E+1
- 1. Total iodine - 131 C1
- 2. Average release rate for period uCi/sec 1.32E-4 2.72E-4
- 3. Percent of technical specification % 2.19E-1 4.55E-1 limit.
C. Particulates
- 1. Particulates with half-lives >8 1.29E-5 2.50E+1 days Ci 1.13E-5
- 2. Average release rate for period uci/sec 1.45E-6 1.64E-6
- 3. Percent of technical specification limit.
~
% 2.19E-1 4.55E-1
- 4. Gross alpha radioactivity Ci <3.89E-7 <3.86E-7 D. Tritium 9.45E-1 1.16E+0 2.50E+1
- 1. Total release ci 1.48E-1
- 2. Average release rate for period uCi/sec 1.22E-1
- 3. Percent of technical specification % 2.19E-1 4.55E-1 limit.
i l
Page 1 TABLE 1C EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1986)
GASEOUS EFFLUENTS-GROUND RELEASES CONTINUOUS M0DE BATCH MODE Nuclides Released Unit 1st Quarter 2nd Quarter 1st Quarter 2nd Quarter
- 1. Fission Gases Krypton (Kr) 85m Ci 3.04E+0 2.29E+0 9.85E-2
- Krypton (Kr) 85 Ci 1.41E+0 1.12E+0 3.05E+0 Krypton (Kr) 87 Ci 2.06E-3 6.62E-1 Krypton (Kr) 88 Ci 1.32E-2 1.85E-2 4.13E-2 Ci 2.28E+0 8.45E-1 4.01E+0 Xenon (Xe) 131m Ci 3.45E+0 4.56E+0 9.47E-7 8.25E+0 Xenon (Xe) 133m Ci 4.87E+2 3.03E+2 8.33E-5 3.75E+2 Xenon (Xe) 133 Xenon (Xe) 135m Ci 2.39E-4 1.30E-3 Ci 5.72E+1 2.46E+1 7.31.E+0 Xenon (Xe) 135 Xenon (Xe) 138 Ci Argon (Ar) 41 Ci 9.74E-2 4.05E-2 Unidentified Ci Ci 5.54E+2 3.37E+2 8.42E-5 3.97E+2 TOTAL FOR PERIOD
- 2. Iodines iodine (I) 131 Ci 1.03E-3 2.14E-3 iodine (I) 133 Ci iodine (I) 135 Ci TOTAL FOR PERIOD Ci 1.03E-3 2.14E-3 L
Psgn 2 TABLE 1C EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1986)
GASEOUS EFFLUENTS - GROUND RELEASES CONTINUOUS MODE BATCH MODE Nuclides Released Unit 1st Quarter 2nd Quarter 1st Quarter 2nd Quarter
- 3. Particulates Antimony (Sb) 125 Ci Barium (Ba) 133 Ci Cadmium (Cd) 109 Ci 6.08E-6 2.51E-6 Cerium (Ce) 139 C1 Cerium (Ce) 141 Ci 6.96E-8 4.18E-7 Cerium (Ce) 144 Ci 5.62E-7 Cesium (Cs) 134 Ci Cesium (Cs) 137 Ci 6.37E-7 1.96E-6 Cobalt (Co) 57 C1 Cobalt (Co) 58 Ci 2.48E-7 4.34E-6 Cobalt (Co) 60 C1 2.69E-6 Chromium (Cr) 51 C1 1.55E-6 2.24E-6 Iron (Fe) 55 Ci 8.59E-7 Niobium (Nb) 95 Ci Strontium (Sr) 85 Ci Strontium (Sr) 90 Ci Tin (Sn) 113 Ci TOTAL Ci 1.13E-5 1.29E-5
Indian Point 3 EFFLUENT AND WASTE DISPOSAL SEMI-PNNUAL REPORT C. LIQUID EFFLUENTS FIRST AND SECOND QUARTERS, 1986
TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1986)
LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES UNIT QUARTER QUARTER EST. TOTAL 1st 2nd ERROR %
A. Fission and activation products
- 1. Total release (not including tritium, gases, alpha) Ci 3.99E-2 7.90E-2 2.50E+1
- 2. Average diluted concentration during period uCi/ml 1.56E-10 2.94E-10
- 3. Percent of applicable limit % 3.68E-1 9.48E-1 ,
B. Tritium
- 1. Total release Ci 1.95E+2 1.78E+2 2.50E+1
- 2. Average diluted concentration during period uCi/ml 7.64E-7 6.62E-7
- 3. Percent of applicable limit % 3.68E-1 9.48E-1 C. Dissolved and entrained gases
- 1. Total release C1 1.16E+1 4.76E+0 2.50E+1
- 2. Average diluted concentration during period uCi/ml 4.55E-8 1.77E-8
- 3. Percent of applicable limit % 3.68E-1 9.48E-1 D. Gross alpha radioactivity
- 1. Total relense Ci <8.39E-5 <1.47E-4 2.50E+1 E. Volume of waste released (prior to 1.48E+6 2.51E+6 1.00E+1 dilution) liters F. Volume of dilution water used during period liters 2.55E+11 2.69E+11 1.00E+1
PIga 1 TABLE 2B LIQUID EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT CONTINUOUS MODE BATCH MODE Nuclides Released Unit 1st Quarter 2nd Quarter 1st Quarter 2nd Quartor Antinony (Sb) 122 Ci 2.18E-4 Antinony (Sb) 124 Ci 1.17E-4 Antimony (Sb) 125 Ci 8.48E 9.51E-4 Barium. (Ba) 140 Ci 4.39E-5 1.39E-5 Barium (Ba) 133 Ci 8.03E-5 2.24E-5 Cadmium- (Cd) 109 C1 1.93E-4 Cerium (Ce) 139 Ci Cerium (Ce) 141 c4 Cerium (Ce) 144 Ci 4.28E-4 Cesium (Cs) 134 Ci 1.74E-4 Cesium (Cs) 137 Ci 1.20E-4 5.04E-4 Cesium (Cs) 138 Ci 6.84E-6 Chromium (Cr) 51 Ci 3.71E-4 3.12E-3 Cobalt (Co) 57 C1 2.73E-5 3.69E-5 Cobalt (Co) 58 Ci 5.40E-3 2.01E-2 Cobalt (Co) 60 Ci 7.77E-5 8.98E-3 7.74E-3 Iodine (I) 131 Ci 6.67E-3 4.57E-3 Iodine (I) 133 Ci 1.42E-4 1.16E-4 Iodine (I) 134 Ci
-Iodine (I) 135 Ci Iron (Fe) 55 Ci 8.97E-3 2.75E-2 Iron (Fe) 59 Ci 4.27E-4 Lanthanum (La) 140 Ci 1.03E-5 Mercury (Hg) 203 Ci 1.63E-5 5.42E-6
' pig s 2 TABLE 2B CONTINUOUS MODE BATCH MODE Nuclides Unit is Quarter 2nd Quarter 1st Quarter 2nd Quarter Manganese (Mn) 54 Ci 4.77E-4 5.26E-4 Molybdenum (Mo) 99 Ci 6.05E-5 Nickel (Ni) 63 Ci 5.25E-3 2.49E-3 Copper (Cu) 64 Ci 6.97E-4 Niobium (Nb) 94 Ci 2.69E-6 3.35E-4 1.19E-3 Niobium (Nb) 95 Ci
' Yttrium (Y) 88 Ci 1.19E-3 1.83E-4 Rubidium (Rb) 88 Ci 4.48E-5 1.04E-5 Ruthenium (Ru) 103 Ci 3.57E-5 J.58E-5 Ruthenium (Ru) 105 Ci 1.83E-4 Ruthenium (Ru) 106 Ci Silver (Ag)110m C1 3.62E-4 6.71E-3 Sodium (Na) 24 Ci 5.42E-5 5.18E-5 Strontium (Sr) 85 Ci 1.65E-4 2.58E-4 Technetium (Tc) 99m Ci Tin 8.38E-5 6.99E-5 (Sn) 113 Ci 2.02E-6 Tellurium (Te) 132 Ci Tungsten (W) 187 Ci 2.65E-5 1.22E-5 3.08E-5 Zine (Zn) 65 Ci 2.15E-4 4.77E-5 Zirconium (Zr) 95 C1 7.77E-5 3.99E-2 7.90E-2 TOTAL FOR PERIOD
7 Page 3 TABLE 2B CONTINUOUS MODE BATCH MODE Nuclides Unit 1st Quarter 2nd Quarter 1st Quarter 2nd Quarter Ci 1.35E-4 Argon (Ar) 41 Xenon (Xe) 131m Ci 8.63E-2 3.46E-2 1.13E+1 4.53E+0 Xenon (Xe) 133 Ci Xenon (Xe) 133m C1 1.50E-1 7.31E-2 Xenon (Xe) 135 C1 1.34E-1 1.06E-1 Xenon (Xe) 135m Ci 4.91E-4 3.82E-5 Krypton (Kr) 85m Ci 7.75E-4 1.28E-3 Ci 1.22E-2 1.17E-2 Krypton (Kr) 85 Krypton (Kr) 87 Ci 5.45E-5 Ci 1.30E-4 Krypton (Kr) 88 TOTAL DISSOLVED AND ENTRAINED GASES Ci 1.16E+1 4.76E+0
Indian Point 3 EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT D. SOLID WASTE FIRST AND SECOND QUARTERS, 1986 i
1 J
1 TABLE 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT January 1 - June 30, 1986 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)
Unit 6 Month Period Est. Total
- 1. Type of Waste Class A Class B Error, %
- a. Spent Resins, filter m 4.81E+0 0 5.0E+1 sludges, etc. Ci 6.17E+0 0
- b. Dry Compressible, m 0 0 N/A contaminated equip. etc. Ci 0 0 3
- c. Irradiated Components m 0 0 N/A Ci 0 0
- d. Other m 0 0 N/A Ci 0 0
- 2. Estimate of major nuclide composition (by type of waste)
NUCLIDE UNIT CLASS A CLASS B
- 3. Solid Waste Disposition Number of Shipments Mode of Transport Destination 1 Truck Barnwell, So. Carolina
- 4. Containers Shipped .
Class A Class B Container Number Solid. Media Number Solid. Media Steel Liner 1 None N/A N/A
. . .. . . . . __ . ~ _ _
1 m
i T
l f
Indian Point 3 i
EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT !
l E. RADIOLOGICAL IMPACT ON MAN FIRST AND SECOND QUARTER, 1986
- (Not to be submitted during chis reporting period) ,
b j ?
'l f l
1 +
k A
i i
h r
1
- 4 I I
J
N 4
4 i
a k
Indian Point 3 ,
b k
EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT !
F. METEROROLOGICAL DATA ,
FIRST AND SECOND QUARTER, 1986 1
(Not required to submitted during this reporting period) i I
r d
4 0
e L
2 l
i e f
Indian Point 3 EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT G. OFFSITE DOSE CALCULATION MANUAL CHANGES FIRST AND SECOND QUARTERS, 1986
Offsite Dose Calculation Manual (ODCM) Changes Changes have been made to the ODCM since our last submittal. Each change is descr! bed and justified separately. These changes have been reviewed by the Plant Operating Review Conrnittee as required by Section 6.5 of Appendix A to the facility operating license. These changes have been effective since March 5,1986.
Process Control Program (PCP) Changes There have been no revisions to the PCP since our last semi-annual report.
J
)
ODCM Changes Since January 1986
- 1. DESCRIPTION:
Table 1-1 was updated to include the Fan Cooler Service Water and Component Cooling-Water Monitors and their associated data.
JUSTIFICATION:
The monitors associated with these potential liquid release paths were inadvertently left out of the last submittal.
IMPACT:
Results in a more accurate summary of our effluent monitors. There is no impact on dose assessments or set-point determinations.
- 2. DEPCRIPTION:
Section 2.1.10 is updated to reflect the newly installed variable speed pumps for condenser cooling intake.
JUSTIFICATION:
These pumps were installed to meet commitments of the Hudson River Settlement Agreement that required us to have the ability to vary pump flow rate.
IMPACT:
No impact relative to offsite dose assessment.
- 3. DESCRIPTION Section 2.1.11 was modified to allow storage of water in the refueling water storage tank at concentrations in excess of 7.3E-3 uCi/ml. The curie limit imposed by the RETS however remains unchanged.
JUSTIFICATION:
Since the RETS limits the total radioactivity in the tank it is not necessary to control to this value using a maximum activity concentration limit. Therefore we will control the activity by applying appropriate actions to reduce the activity concentration and/or the total allowable tank volume.
IMPACT:
This change will have no impact on set-point determinations or dose assessment.
\
- 4. DESCRIPTION:
The backup dose methodology for liquid effluents (Section 2.5) has been changed to improve calculation accuracy. It is now necessary to account for the top 90% of all radionuclides (based on activity content per release).
JUSTIFICATION:
This method will still allow for manageable hand calculations in the event they should become necessary and will add increased accuracy to the calculations. A multiplicative factor of 1.2 is retained in the equation employed to ensure conservative results.
IMPACT:
This change increases the accuracy of the dose calculations for liquid releases. Set-point determination is not effected by this change.
- 5. DESCRIPTION:
A more representative data set was used to re-calculate allowable time averaged noble gas release rates with the result that the annual and quarterly average release rates are increased. The change effects Section 1.2.1, Table 3-10 and Page 3 of Appendix 3-A.
JUSTIFICATION:
The increased limits were re-calculated after reviewing the radionuclide mixtures from past releases where the time average Ibmit applied. Then after conservatively choosing the representative mixture to use in the calculation, the appropriate weighted dose factors were determined.
Use of these limits will allow increased operational flexibility when pressure relieving the vapor containment building.
IMPACT:
This change will cause set-point limits to be higher but offsite dose commitments will remain unchanged.
- 6. DESCRIPTION:
Time averaging the gaseous activity release. rate over a timeLinterval of one hour. This change will not effect the instantaneous release rate value from our last submittal which was based on the 500 millirem per year limit. This change effects Section 3.1.8, 3.3.1 and 3.4.1.
JUSTIFICATION:
The change allows for a realistic yet conservative dose assessment at the site boundary. There is a finite time required for the instantaneous dose rate limit to be reached from the resultant gas cloud. The time frame of one hour is consistent with 10 CFR 50.72 requirements. This change effectively allows a maximum dose at the site boundary of .06 millirem in a one hour period, based on annual average dispersion.
IMPACT:
Set points would not change; however, the comparison of instrument response (cpm) to the set-point would be averaged over one hour. '
This would allow short-term excursion above the set-point as long as the one hour average was below the set-point.
Dose assessments would not be effected, since the limitations of 5 mrad per quarter and 10 mrad per year must still be complied with.
- 7. DESCRIPTION:
Section 5 has been deleted to make the ducument more readable.
JUSTIFICATION:
The material contained in Section 5, back up information RETS items has been moved into the body of the ODCM in the appropriate sections.
IMPACT:
NONE