ML20012B033
| ML20012B033 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 12/20/1989 |
| From: | POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | |
| Shared Package | |
| ML20012A931 | List: |
| References | |
| PROC-891220, NUDOCS 9003130320 | |
| Download: ML20012B033 (226) | |
Text
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I NEW YDRK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT CERTIFICATES, DOCUMENTS AND PERMITS 1
0FFSITE DOSE CALCULATION MANUAL
- CDP-15 PORC Review No./Date Meeting No. N-M Date /A./40/F9
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Approved By: .
Resident Manager -
f .;
Approved By: hN ?/
Radiological and Envirorpfntal services Superintendent V Page No.t 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 Rev. No.: 7 7 7 7 6 7 7 7 2 2 7 7 5 7 7 .
Page No.: 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30
- Rev. No.: 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 '
Page No.: 31 32 33 34 35 36 37 36 39 40 41 42 43 44 45 Rev. No.: 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 Page No.: 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 Rev. No.: 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 Page No.: 61 62 63 64 A-1 A-2 A-3 A-4 A-5 A-6 A-7 A-8 A-9 A-10 Rev. No.: 7 7 7 2 2 5 4 2 2 2 2 2 2 2 Page No.: A-11 A-12 A-13 A-14 A-15 A-16 A-17 A-18 A-19 A-20 A-21 A-22 Rev. No.: 2 2 2 2 2 2 2 2 2 2 2 2 Page No.: A-23 A-24 A-25 A-26 A-27 A-28 A-29 A-30 A-31 A-32 A-33 A-34 I Rev. No.: 2 2 2 2 2 2 2 2 2 2 2 2 Page No.: A-35 A-36 A-37 A-38 A-39 A-40 A-41 A-42 A-43 A-44 A-45 A-46 Rev. No.: 2 2 2 2 2 2 2 2 2 2 2 2 Page No.: A-47 A-48 A-49 A-50 A-51 A-52 A-53 A-54 A-55 A-56 A-57 A-58 Rev. No.: 2 2 2 2 2 2 2 2 2 2 2 2 Page No.: A-59 A-60 A-61 A-62 A-63 A-64 A-65 A-66 A-67 A-68 A-69 A-70 l Rev. No.: 2 2 2 2 2 2 2 2 2 2 2 2
.Page No.: A-71 A-72 A-73 A-74 A-75 A-76 A-77 A-78 A-79 A-80 A-81 A-82 Rev. No.: 2 2 2 2 2 2 2 2 2 2 2 2 l Page No.: A-83 A-84 A-85 A-86 A-87 A-88 A-89 A-90 A-91 A-92 A-93 A-94 i
Rev. .
No.: 2 2 2 5 5 5 5 5 2 2 2 5 L Page No.: A-95 A-96 A-97 A-98 A-99 B-1 B-2 B-3 B-4 B-5 B-6 B-7 B-8 i
Rev. No.: 5 5 2 2 2 2 5 2 2 2 4 4 4 Page No.: B-9 B-10 B-11 B-12 B-13 B-14 B-15 B-16 B-17 B-18 B-19 B-20 Rev. No.: 4 2 2 2 2 2 4 2 2 2 2 2 Page No.: B-21 B-22 B-23 B-24 B-25 B-26 B-27 B-28 B-29 B-30 Rev. No.: 2 2 2 2 2 2 2 2 2 2
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NEN YORK PONER AUTHORITY ,
JAMES A. FIT 2PATRICE NUCLEAR POWER PLANT l CERTIFICATES, DOCUMENTS AND PERMITS b
0FFSITB DOSB CALCULkTION MANUAL
- CDP-15 s
PORC Review No./Date - Meeting No. F9- 91 Date /2 /.to/f9 [
Approved By: /N / -
T Residerit Manager A,
@ s=- h. _I J Approved By: 1 c-e -
Radiological and Envi ental .
Services Superintenden @f ,
i Page No.: B-31 B-32 B-23 B-34 B-35 B-36 B-37 B-38 B 'Je B-40 B-41 8-42 Rev. No.: 2 2 2 2 2 2 2 2 2 7 2 2 Page No.: B-43 B-44 5-45 B-46 B-47 B-48 B-49 B-50 B-51 B-52 B'-53 B-54 i Rev. No.: 2 2 2 2 2 2 .
2 2 2 2 2 2 ,
Page No.: B-55 B-56 B-57 B-56 3-59 B-60 B-61 B-62 B-63 B-64 B-65 B-36 i
Rev. No, 2 2 2 2 2 2 2 2 2 2 2 2 L
Page No.: B-67 B-68 B-69 B-70 B-71 B-72 5-73 B-74 B-75 B-76 8-77 B-78 Rev. No.: 2 2 2 2 2 2 2 2 2 2 2 2 Page No.: B-70 B-bo B-81 B-82 B-83 B-84 B-85 B-86 B-87 B-88 B-89 B-90 Rev. No.: 2 2 2 2 2 2 2 2 2 2 2 5 Page No.: D-91 B-92 B-93 B-94 B-95 B-96 5-97 B-98 B-99 B-100 B-101 Rev. No.: 5 5 5 5 5 5 5 2 2 2 2 l Page No.: B-102 E-103 B-104 B-105 B-106 B-107 C-1 C-2 C-3 C-4 C-5 C-6 l Rev. No.: 2 2 2 2 2 2 5 6 6 6 6 6 l Page No.: C-7 C-8 C-9 C-10 D-1 D-2 Do3 D-4 D-5 D-6 D-7 E-1 E-2 E-3 E-4 .,
Rev. No.: 6 6 6 6 2 2 2 2 2 2 2 5 2 2 2 Page No.: E-5 E-6 E-7 E-8 E-9 E-10 E-11 E-12 F-1 F-2 F-3 F-4 F-5 F-6 Rev. No.: 2 2 2 2 2 2 2 2 2 5 2 4 4 2 Page No.: F-7 F-8 F-9 F-10 G-1 G-2 G-3 H-1-H-2 H-3 H-4 H-5 H-6 Rev. No.: 5 2 2 2 2 5 2 2 5 4 4 4 4 Page No.: H-7 H-8 H-9 H-10 I-1 I-2 I-3 I-4 I-5 I-6 I-7 I-8 I-9 I-10 Rev. No.: 4 4 4 2 2 5 2 2 2 2 2 2 2 2 Rev No. 7 lu,o y
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e, OFFsITs 008a-CALCULATION M&NUAL (ODCN)*
Table of Centants EASA
1.0 INTRODUCTION
2 1.1- Purpose' 2 1.2~ _ Methodologies _and Parameters- 2 2.O GLOSS &RY OF' TERMS 3 3.O LIQUID EFFLUENT MBTBODOLOGY 7 3.1 Applicable Site Characteristics 7 3.2 10 CPR 20, MPC Limits-Determination of Fraction (F )6 of Release Limits and Minimum Required Dilution 7 3.3 Determination of Set Points for Radioactive Liquid Effluent Monitors 11
' 3.4 Dose Determination for Radioactive Liquid Effluents 15 3.5 Dose Projections-Determination of Need to operate Liquid Radwasto Treatment System 21 4.O GA83008 BFFLURNT METHODOIDGY 27 4.1 Gaseous Waste Streams 27 4.2 ' Data Requirements for Gaseous Effluent Calculations 27 14 . 3 Instantaneous Release Rate and Set Point Determination 28 4.4 Dose Determination for Radioactive Gaseous Effluents 42 4.5 Dose Projection-Determination of Need to operate offgas Radwaste Treatment System 59 5.0 40 CFR 190 D085 EVALUATION 61 5.1 Evaluation Bases 61 5.2 1 Doses'from Liquid Releases 61 5.3 Doses from Atmospheric Releases , 62 5.4 Doses from Direct Radiation 62'
6.0 REFERENCES
63 6.1 Background References 63 6.2 Essential References / Controlled Documents 63 7.0 APPENDICES 64 Rev. No. 7 Page 1 of ODCM ,
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4 CDP-15 0FFSITE DOSE CALWTION MANUhL (ODCM)
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1.0 INTRODUCTION
1.l' Purpose ,
This manual provides the methodology to calculate radiation doses to individuals in the vicinity of the James A. Fitz- ,
, Patrick Nuclear Power Plant. It also provides methodology :
for calculating' effluent monitor set points and allowable release rates-to ensure compliance with the Technical Spec-ifications, Appendix B, of the New York Power Authority, James A. FitzPatrick Nuclear Power Plant, Docket Number 50- ,
333, and 10 CFR 20 release criteria. ;
1.2 Nethodologies and Parameters-The ODCM follows the methodology and models suggested by the
" Guidance Manual For Preparation of Radiological Effluent-Technical Specifications for Nuclear Power Plants"'(NUREG-0133 October 1978) and-" Calculation of Annual Doses to Man
' from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR'50, Appendix I" (Regu-latory. Guide 1.109, Revision 1. dated October 1977). Simpli-fying assumptions have been made and justified where ap-plicable to provide a more workable document for imple- -t menting the Technical Specifications, Appendix B, require- '
mer.ts. Alternate calculating methods to those presented here may be used provided the gsnaral. methodology is simila-r, well documented and the results are.more precise.
Additionally, as available, the most up-to-date revision of
- the Regulatory Guide 1.109 dose conversion factors and site specific environmental transfer factors may be substituted-t for those currently-included and used in this document.
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2.O GLOSS &M OF TERMS Age Groups Infants, children, teens and adults are age groups evaluated by this CDCM. -
t Beta A beta particle (electron). ,
Beta Dose ,
The dose component to skin dose due to beta-amit-ting radionuclides in air.
cc Cubic contimeter.
Ci . Curie. A unit of radioactivity equal to 3.7E+10 disintegrations per second. See also microcurie (sci). ,
L , [
C, Activity or concentration of a nuclide in the re- ;
lease source. Units of pCi, pCi/ce, or sci /ml.
CFR Code of Federal Regulations. :
Dose A measure of the radiation energy deposited per unit mass (in arem. or arad), that the organ or the individual receives from exposure to radioactive
. effluents dispersed in the environment.
Dose Commitment The total dose delivered to the organ or total body over a 50-year period resulting from uptake of radioactive material.
Dose Factor Normally, a factor that converts the effect of ingesting or inhaling radioactive material into the body, to dose to a specific organ. Body elimination, radioactive decay, and organ uptake are some of.the factors that determine a dose factor for a given nuclide.
Dose Pathway A specific path that radioactive material physi-cally travels through in the environment prior to exposing an individual to its emitted radiation.
The grass / cow / milk food chain is a dose pathway.
Rev. No. 7 Page 3 of ODCM
- a. (
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l Dose Rate
. The dose received per unit time. i H
(D/Q) A long term relative deposition coefficient. A
! factor with units of 1/m8 which describes the .
deposition of particulate matter from a plume at a point downrange from the source. It can be
'> thought of as the part of the cloud that will fall out and deposit over one square meter of ground.
L -Gamma A gamma photon.
\.
Gamma Dose I l
The dose component to skin or total body dose due ;
to gamma-emitting radionuclides in air. ;
Ground Plane Radioactive material deposited uniformly over the ]
ground emits radiation that produces an exposure pathway when an individual is present in the area..
It is assumed that an adult receives the same exposure as an infant, regardless of the physical height differences, only the total body and skin is cc %iered for the purpose of the ODCM.
H-3 Hydy4 vro .
or tritium. An isotope of hydrogen tbst 25 ow-energy beta emitter.
I&8DP Radioiodines and'particulates with half-lives greater than eight days (includes H-3 where :
applicable).
LLD Lower Limit of Detection. The smallest concentra-tion of radioactive material in a sample that will yield a not count, above systems background 1that will be detected with 95 percent probability with only 5 percent probability of falsely concluding-that a blank observation represents a "real" sig-nal.
l-LCO Limiting Conditions for Operation in Technical Specifications,-Appendix B.
I m* Cubic meters, m8 square meters.
I MPC Maximum Permissible Concentration.
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Nuclide For the purpose of the CDCM, a radioactive iso-tope. Nuclide (i) signifies a specific nuclide, the first, second, third, etc. one under consider-ation. If nuclide (i) is I-131, than the M. (dose <
factor) under consideration should be M i .m, for example.
Organ For the purpose of the ODCM, either the-bone, e
- liver, thyroid, kidney, lung, GI-LLI, skin or~the e T. Body (Total Body). T. Body is considered an organ for consistency with the ODCM nomenclature.
Q. Q, (dotted) denotes a release rate in ci/see for nuclide (1). ,
Q, Denotes C, of nuclide (i) released over a specifi-ed time interval.
Receptor The individual receiving radiaticn exposure from effluent. releases at JAFNPP at c given location, or who ingests food products contained with trace amounts of-radioactive materials.. A receptor can receive dose from one or more dose pathways.
Release Source A subsystem, tank, vent or stack where radioactive material can be released independently of other radioactive release points.
Restricted Area An area within the site boundary to which access is controlled by NYPA for purposes of protection of individuals from exposure to radiation and radioactive materials.
Technical Specifications, Appendix B The-JAFNPP Radiological Effluent Technical Speci- .
fications (RETS).
pCi Microcuries. 1 Ci = 1E+6 pCuries. The pCi is the standard unit of radioactivity for all dose calcu-lations in the JAFNPP ODCM.
(X/Q) A long term relativa atmospheric dispersion coefficient. It describes-the physical dispersion characteristics of a semi-infinite cloud of noble gases as the cloud travels downwind from the release point.
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. = . -- .
r as, ,
t.O-(X76)y .A long term relative atmospheric dispersion coefficient. It. describes the physical dispersion characteristics of a finite cloud of noble gases as the cloud-travels downwind from the release' point.
Unrestricted Area- i An unrestricted area shall be any. area at or c beyond the site boundary where access is not i
. controlled by NYRA for. purposes of protection of individuals from exposure to radiation and radioa- ;
etive materials, or any area within the site boundary used for residential quartsrs or for industrial,' commercial, institutional, and/or-recreational purposes. (Refer to Technical Specif- ,
ications, Appendix B, section 1.0 for an expanded definition).
Vent Building ventilation air exhausts via four separa-tely monitored roof top ducts.
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! 3.0 LIQUID BFFLUENT METEODOLOGY
? 3.1 Applicable Site Characteristics L
L The JAFNPP Final Safety Analysis Report (FSAR) contains the official description of the site characteristics. The '
description that follows is a brief summary.for dose cal- t culation purposes..
l The James A. FitzPatrick Nuclear Power Plant is located on
? the eastern portion of the Nine Mile Point promontory on
-Lake Ontario in oswego County, NY. The-site-is approximate-l: ly seven miles northeast of the city of oswego. Radioactive E
- ' liquid releases normally enter Lake Ontario where the Circu-lating Water Discharge Tunnel' terminates on the lake bottom approximately 1,400 feet from the shoreline.
3.2 10 CFR 20, MPC Limits-Determination of the. Fraction (F ) of Release Limits and Minimum Required Dilution 3 L
3.2.1 Requirements In accordance with Technical Specifications, Appendix B, Section 2.2, the. concentration of liquid radioactive material' released to unrestricted areas (Appendix G) shall.
not exceed the concentrations specified in 10 CFR 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. The concentra-tion of radionuclides in liquid waste is determined by sampling and analyses in accordance with Technical Spec-ificaticns, Appendix B, Section 2.2.
In accordance with Technical Specifications, Appendix B, >
Section 2.2 for dissolved or entrained noble gases, the concentration shall be limited to 2E-4 pCi/ml.
3.2.2 Methodology This section presents the calculating method to be used for determining Ft , the fraction of 10 CFR 20 limits, of release concentrations of liquid radioactive affluents,
- a. General Approach This method addresses the calculation for a specific release source. Administrative controls are applied to assure that the summation of F6 values for each release source does not exceed the 10 CFR 20 limit.
4 Rev. No. 7 Page 7 of ODCM
3-Normally,-all potentially radioactive liquid effluents are released to-the unrestricted area through a single monitored release path as indicated in Appendix F. .
However, the service water system presents a potential release point for radioactive liquid effluents. To e
-assure the combined releases do not exceed 10 CFR 20 o
limits, the alarm set point, as determined in section 3.3-include a conservation multiplicator factor of 0.5. ,
The basic equation which determines the fraction (F )'g of.the 10 CFR 20 MPC limits ist C C
'f 1 ,=g FILTRATE g- 4 FILTER i Eq. 3-1 7 ,
f-2 1*1 ("#CI SOL (MPC)ygggg i 1 Where:
Ft = The fraction of 10 CFR-20 MPC limits re-sulting from the release source being discharged,(dimensionless).
f3 = The undiluted release rate of the l release-source as measured at the liquid effluent monitor location, in gym.
fi
= The discharge structure exit flow in gym. (Summation of circulating water pump and service water pump discharge flow; minus the. flow redirected for ;
tempering.)
C FILTRATEg =
The undiluted concentration of nuclide (i) in gCi/ml from filtrate sample assay. When a radionuclide concentration is below the LLD for the analysis, it is 1 not reported as being present in the sample.
(MPC) SOLg=
Soluble Maximum Permissible Concentra-tion of nuclide (i) from Appendix A, in pCi/al.
j FILTER g =
The undiluted concentration of nuclide (i) in sci /ml from filter sample assay.
When a radionuclide concentration is below the LLD for the analysis, it is not reported as being present in the sample.
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^(MPC)INSOLg =
Insoluble Maximum Permissible Concentra- "
tion of nuclide (i) = from Appendix A, in pCi/al.
Using the general approach, the fraction of the 10 CFR-20 MPC limit may be determined using a nuclide-by-nuclide evaluation,
- b. Simplified Approach For purposes of simplifying the calculation, the value
- of 3E-8 gCi/ml (unidentified 10 CFR~20 MPC value) should be substituted for (NPC), in the equation 3-1 and the cumulative concentration (Coui = num of all identified radionuclide concentrations) or the gross beta-gamma concentration should be substituted for C,.
- c. Approach selection criteria As long as the diluted concentration (Coui x f v4f,) is >
less than or equal to 3E-8 pCi/ml, the nuclide-by--
nuclide calculation is not required to demonstrate '
compliance with the 10 CPR 20, MPC limit.
3.2.3 Calculating Process for Determining fdf .
~
The following section provides a procedure for determining
! the minimum required dilution factor (fuhf) to ensure i L that Ft = 1 during the actual release. With F6 = 1, the minimum required dilution factor can be expressed as:
g
- n Ci 9* ~
2_ . I f
l min i=1 (MPC)g ;
a, obtain (C,), the undiluted assay value of nuclide (i),
in pCi/al. If a. gross activity determination (simpli-fled approach) is used, the cumulative concentration (Coui) is used.
- b. From Appendix A, Table A-1, obtain the corresponding (MPC) for nuclide (i) in pCi/ml. The value.of 3E-8 gCi/ml should be used for the gross activity method,
- c. Divide C, by (MPC) .
-Rev. No. 2 Page 9 of ODCM
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- d. If' determining the NPC fraction using the nuclide-by-nuclide evaluation, repeat. steps b and c above for each nuclide and sua the totals.
- e. IfLthe gross activity method is used, then g
1 Total /3E-8 is given by C 7-1 ,
min ,.
- f. Enter the total activity (C) and the minimum required dilution factor (fu'f )ain mit.
i on the' liquid release per-(
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3.3 Determination of Setpoints for Radioactive Liquid Effluent
-Monitors 3.3.1 Requirements Technical Specifications, Appendix B, Section 2.1.a re- ,
quires that the radioactive liquid effluent monitor be operable and set to initiate an alarm and/or trip in the event that the limits of Technical Specifications, Appen-dix B, Section 2.2 are. approached. The1 alarm.and/or trip set points shall be determined and adjusted by the method-ology which follows. . The set point values should be applied above normal background. levels.
The alarm set point for the liquid effluent radiation mon-i itor is derived-from the concentration limit provided in l 10 CFR 20, Appendix B, Table II' Column 2 applied at the unrestricted area boundary where the discharge tunnel flows into Lake ontario.
3.3.2 Methodology i
L' The alarm set points do not consider dilution, dispersion, l
or decay of radioactive material beyond-the unrestricted area boundary (i.e., the alarm setpoints are based on a concentration limit at the and of the discharge tunnel).
-3.3.3 Radwaste Liquid Effluent Monitor
- a. A sample of each batch of liquid radwaste is analyzed for I-131 and other principal-gamma emitters prior to release. The fraction Ft of 10 CFR 20, MPC limits and the minimum required dilution factor to achieve Ft = 1 is determined in accordance with the preceding section for the activity to be released. For cases other than minimum dilution calculation Fu <0.5.
- b. A conservative alarm and/or trip setpoint (gCi/ml) is determined in accordance with the following equation.
S = 0.5 x C_ Eq. 3-3 Ft Where:
Ft = <0.5 S = The alarm and/or trip set point above background corresponding to the limiting concentration of undiluted liquid effluent (pci/ml).
0.5 = Conservatism factor to account for releases from multiple points, and to allow for nuclides not detected by the monitor.
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C = Total gamma isotopic or gross activity concentra-tion (sci /al) of sample as determined in the labo-
. ratory.
F5 = The fraction of 10 CFR 20, MPC limits for unre-stricted areas resulting from the release source being discharged. .
3.3.3.1 Calculating Process The following section provides a procedure for determin- i
-ing the radwaste liquid affluent monitor set point. l Typical parameter values-are used for illustration.
- a. Determine C from laboratory analysis of the liquid effluent sample. For the purpose of this example, assume a value of 3E-5 pCi/ml in a gross beta-gamma-activity _ analysis,
- b. Determine f from pump curves and current plant oper-ating configur,ation. A typical value is 3.78E+5 gpa.
- c. Determine the minimum required dilution factor in ac-cordance with equation 3-2.
I
,a C1
, E
.ft . min i=1 (MPC)g For a gross activity determination, the unidentified MPC of 3E-8 pCi/ml is used. Therefore A = 3E-5/3E-8 = 1,000 t 1 min
- d. Determine or calculate the required f1 at the liquid '
affluent monitor location. A typical value is 100 gym.
- e. A typical value of the dilution factor from current plant operating conditions is:
(3.78E+5 gpa)/100 gym = 3,780, which is
>1,000. Therefore the release can be made at the current release rates and concentrations maintained within the 10 CFR 20 limits.
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f._ Determine F , the fraction of- 10 CFR 20 MPC liEits
~
t
-resulting:from the release source being-discharged at-a dilution-factor _of 3,780, in accordance with_equa-tion 3-1.
n .
C1 F g, [1 g I
,f 2- i=1 (NPC)g
= (100/3.78E+5) x (3E-5/3E-8)
= (2.65E-4) x 1,000
= 0.265
- g. The liquid effluent monitor set point, S in pci/al, from equation 3-3 is:
S = 0.5 x g_ Eq. 3-3.a Ft
= 0.5 x ((3E-5)/(0.265)] t
= 5.66E-5 gCi/al
- h. Appropriate calibration factors are applied to this limiting concentration determined in step 3.3.3.g to determine an effluent monitor alarm potentiometer' set
. point.
3.3.4 service Water Liquid Effluent Monitor a'. A conservative alara setpoint (cps) for the service water liquid effluent monitor is determined in accor-dance with the following methodology:-
DF=_[2 Eq. 3-3.b 1
where: -
DF = the dilution factor which results from the flow rate in the discharge structure in gpa divided by the undiluted release rate of the effluent release source.
fi = the undiluted release rate of the affluent source naasured at the service water liquid effluent monitor (gpa).
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f, .= the discharge structure flow rate in gpa (summation of circulating water pumps minus ;
the: flow redirected for tempering, in'gpa).- ]
SP = set point of liquid effluent monitor in cps. )
0.5 = conservatism factor to account for releases-from multiple points.or a reduction in the DF value due to changes in discharge canal flow, ,
and to' allow for nuclides not detected by the monitor. j h MPC.= maximum permissibic concentration for isotop- l ic mixture being released in service water ;
per 10 CFR 20, Appendix B, Table 2, Column 2 '
(Section b below).
Eff = efficiency ~of the liquid affluent monitor in
- Ci/al/cys.
Bkg = normal monitor background (cys).
- b. Those nuclides present in previous batch releases from the liquid radwasta effluent system, nuclides present in historical semi-annual Radioactive Ef-fluent Release Reports or those nuclides present in the service water system may be used to calculate the MPC, value. Other values for NPC, may be used based on plant conditions (i.e. in the event of known leakage into the RBCLC' system).
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3.4 Dose Determination for Radioactive Liquid Effluents
- 3. 4 - 1
. Annual Dose Assessment-Radioactive Effluent Release Re-port submittal a.. Requirements 1 1
Technical Specifications, Appendix B, Section 7.3 re-quires a semi-annual Radioactive Effluent Release J Report to be submitted that includes an assessment of ,
the radiation doses-to.the public due to the radio-active liquid and gaseous effluents released from the unit during the previous calendar year. The dose .
assessment required by this report is due annually 90 days after January first of each year.
- b. ~ Methodology This section provides the methodology to calculate the doses to all age groups and organs from all '
radionuclides identified in the liquid effluents.
The' method is based on the methodology suggested by NUREG-0133, October 1978, Sections 4.3 and 4.3.1 and Regulatory Guide 1.109. The determination of viable .
. liquid. dose pathways is described in Appendix A, i
~ Table A-4.3.
The site-related dose factors for all viable pathways are listed in Appendix A, Tables A-2 and A-3. Table A-3 dose factors are compiled by age groups, for all organs and radionuclides common-to a i Boiling Water Reactors (BWR).
The following equation provides for a doseLcalcula-tion to the total body or any organ for a given age group based on actual release conditions during a calendar. year for radioactive liquid releases. The equation for Da is to be summed over all i nuclides:
= A ir A 1 011 Eq.3-4a ,
D l
if (DF)y 1
n Eq.3-4b Dr = I Dir l
i=1 l
l 1
^
L 1
Rev. No. 7 Page 15 of ODCM t
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-Where !
U Dr = Total dose commitment for organ f of an age group. .
D., = ' Dose commitment in aram received by organ f {
of age group (to be specified) resulting from '
releases during time interval At for nuclide ->
(1). i A, =
The site-related dose commitment factor to ,
' the total body or any organ , for each iden-L
" tified radionuclide (1) . The A, values listed in Appendix A, Tables A-2 and~A-3 are site specific, in area /hr per #Ci/ml.- Dose commitment factors are compiled by age groups, for organs and radionuclides common to a BWR environment. The derivation of A,,
values is described in Appendix A, Table A- ,
!= 4.1.
At: = The number of hours in the calendar year.
Q,3 = The total quantity of nuclide (i) released during the time' period Ats, in #Ci.
(DF) = The total volume of dilution' released during At: (i.e., summation of' circulating water pump and service water pump discharge flow; minus the flow redirected for-tempering).
By entering'the appropriate annual parameter values onto a form similar to that shown in Table 3.4.2, to-tal body or organ' doses.may be calculated as outlined in step 3.4.2.c.
In addition, more realistic assumptions may be made concerning the dilution and ingestion of fish and potable water by individuals who livs and fish in the area.
3.4.2 Monthly Dose Assessment - Verification of Compliance with 10 CFR 50, Appendix I Limits
- a. Requirements Technical Specification, Appendix B, Section 2.3 re-quires an assessment to be performed at least once every month in any quarter in which radioactive affluent is discharged, to verify that radioactive liquid affluents from the plant do not result in a cumulative dose in excess of 1.5 area to the total body and 5 mrem to any organ in a calendar quarter, and to verify that radioactive liquid effluents from the plant do not result in a cumulative dose in -
excess of 3.0 mram to the whole body and 10 mram to any organ during a calendar year.
Rev. No. 7 Page 16 of ODCM
l
- b. Methodology- )
l This section presents the calculating method to be )
used for the 10 CFR 50 Appendix I compliance verifi- :
cation. The method is based on the models suggested 1 by NUREG-0133 October 1978 Sections 4.3-and 4.3.1 and ,l Regulatory Guide 1.109. :
'l
- 1. General Approach The general approach used is similar to that
,, described for use in calculations for the Annual. <
, Dose Assessment Report. The liquid effluent dose pathways = considered are fresh water fish, potable water and lake shoreline deposits (Appendix D).
These pathways need to be considered for verify-ing compliance with the. requirements specified above.
l The site-specific dose factors for the' fresh- ,
l water fish, potable water and shoreline pathways are provided in-Appendix A, Tables A-2 and A-3.
t For JAFNPP, both the adult and teenager are L normally the most limiting age groups (Appendix /'
! D), but the dose for child and infant may also be
! calculated by-this method using the appropriate dose factors from Appendix A, Table A-3.
D The following equation is used to determine a dose to'the total body or any organ for a.given age group based on actual release conditions duringia specified time interval for radioactive '
liquid releases. The equation for Da is to be summed over all i'nuclides:
D D
ir
if 1 11 Eq.3-5a (DF)y l
E n Eq.3-5b
=
Dr I Dir i=1 Where:
Dr = Dose commitment for organ r of an age group.
Dw = Dose commitment in arem received by or-u gan r of age group (to be specified) from
., release time interval ati for nuclide (1).
Rev. No. 7 Page 17 of ODCM
. t l
}
s A,, = The dose factor for the fresh water fish, ,
potable water lake shoreline deposits o pathways for nuclide (i) for organ r of age group (to be specified).- (Appendix A,
. Tables A-2 and A-3 for A.,,, A,,,, and- A,,,) .
= The number of hours in' the - reporting J At i period.
Q,i = The total quantity of nuclide (i) released during.the time period Ati in pCi.
(DF): = The total volume.of dilution released l
-during At (i.e., the circulating water .
flow multiplied by the time) in all-liliters.
b 2. Limited Analysis Approach Based on the radionuclide distribution typical in radioactive affluents at JAFNPP, the calculated '
dose to. individuals.are dominated by the radionu-
.clides, Cs-134, Cs-137, 2n-65, Kn-54 and co-60.
From 1980 through 1987, these nuclides, in the
. fresh water fish and potable water pathways,
. contributed at least 92 percent of the adult's- r total body dose and at least 81 percent of the teenager's liver dose, which is the critical organ. Therefore, the dose commitment due to radioactivity in lipid effluents may be reason-ably evaluated by-limiting the dose calculating-process to these radionuclides for the adult's total body and the teenager's liver dose. To allow for.any unexpected variability inuthe
-radionuclide distribution, a conservatisa-factor of 0.8'is-introduced into the equation. After calculating the dose based on these'five nu-clides, the cumulative dose should therefore be divided by 0.8.- (Refer to Appendix D for a detailed evaluation and explanation of this limited analysis. approach).
If the limited analysis approach is used, the calculation should be limited to the adult's to-tal body dose and teenager's liver dose from the l '
fish and potable water pathways.: only the five-previously specified nuclides need be evaluated.
L 3. Approach Selection criteria The limited analysis approach fully satisfies.the i
requirements and can thus be used at all times.
The more general approach may be used for more I
refined calculations.
i Rev. No. 7 Page 18 of ODCM l
LT 1
k r-4 t.
L i
. c. Calculating Method .
The methodology that follows is a step-by-step break-down to calculate doses based on equation 3-5. If
- l. the limited analysis approach is used, the calcula-tion should-be limited to the adult total body dose l and teenager's liver dose fron the fish and potable ,
water pathways. Only the five previously specified i radionuclides need to be evaluated for-the limited ;
approach.
NOTE: Table 3.4.2 provides a convenient form for compiling the dose accounting information.
- 1. Determine ( Ati ) the number of hours of the -
reporting period.
- 2. Obtain (DF) for'the time period At for the re- i lease source (s) of interest. DF is the total i volume of dilution, (i.e. the circulating water flow multiplied by the time) in milliliters.
3.- Obtain Qu (MC1) for nuclide (i) for the time period At. i
- 4. Obtain An from the appropriate Liquid Dose-Factor Table: Appendix A, Table A-2 for the fish and potable water pathwayst Appendix A, Table A-3 l for all other pathways.
- 5. Solve for Dose (i)
A lf x At 1 x Qi1 Eq. 3.6a D ,
if (DF)g
- 6. Repeat steps 3 through 5 above for each nuclideL reported and each organ required. If the limited analysis.nethod is.used, limit the radionuclides to Co-60, Mn-54, 2n-65, Cs-134 and Cs-137 and determine the adult's total body dose and the teenager's liver dose.
- 7. . Sun the-De values to obtain the total dose. If .
the limited analysis method is being used, divide the cumulativa dose by a conservatism factor of 0.8 to account for any unexpected variability in radionuclide distribution and any contribution from the lake shoreline deposits pathway.
n Dr = I Dn Eq.3.6.b i=1 (0.8*) *When limited approach is used Rev. No., 7 Page 19 of ODCM
l TABLE 3.4.3 j FISH PATHWAY l 1
TIME /DATE START: TIME /DATE STOP: at: hours TOTAL DILUTION VOLUME (DF) als AGE GROUP: ORGAN: DOSE FACTOR TABLE No.
Nuclide- (i) Qti(pci) Ar i Dose (i) aren 1 Ma-54 l Co-60 2n-65 cs-134 Cs-137 others: ,
l i
l Total Dose f a aren Eq. 3.6.a If based on limited analysis + 0.8 mrom I
,Rev. No. 7 Page 20 of ODCM
. . t Y
4 L. - 3.5 Dose Projections - Determination of Weed to operate Liquid '
Radwaste Treatment system g 3.5.1 Requirements '
L Technical Specifications, Appendix B, Section 2.4 re-p quires that appropriate subsystems of the liquid radwaste treatment' system be used to reduce radioactive material
, in untreated liquid effluents when the projected monthly dose due to liquid releases to unrestricted areas, aver-aged over 31 days, would exceed 0.06 area to the total i'
body or 0.2 area to any organ. Doses are to be projected ,
at least once per month.
3.5.2 Calculating Methodology The method is based on total body dose and limiting organ I' l dose-(liver) as calculated for the Monthly Dose Assess-ment. The adult is normally the limiting age group to be used for the dose projection to the total body. The teen t is normally.the limiting age group to be used for the dose projection to the liver. .Other age groups and/or limiting organs may be used if previous dose calculations indicate that the adult and teen are not the limiting age u groups and the liver is not the limiting organ.
The following calculating methodology is provided for performing this dose projection. 1
- a. Monthly Dose Projectica Each month the expected dose to man shall be pro-L jected.- Projections shall be based on historical or h prior month dose / curie and historical or prior month concentration conversion factors. The historical factors are calculated from historical release data.
l for both a refuel outage-year and a non-refuel outage year. The current historical factors are on file within-the RES Department.
- 1. Each month make an estimate of the volume of i liquid radwaste to be discharged during that >
aonth. The following variables should be con-sidered in estimating radwaste volumes to be l
released:
(a) Projected plant operational status (run, shut-down, refuel, etc.).
(b) Status of radwaste treatment equipment.
Equipment which is inoperable, such as the waste concentrator, should be factored into the source term or volume of liquid waste to be discharged from the plant.
Rev. No. 7 Page 21 of ODCM
l t
I (c) Additional factors indicating that actual liquid releases could differ significantly in the next month.
(d) Historical liquid waste discharge volumes.
j; 2. Determine which dose /Ci and Ci/ gal conversion .
factors should be used. Historical conversion factors can be ucsd. Prior month conversion i factors may be used if they are more represen-tative of current release conditions. In the event that there was no release of liquid radwaste during the prior month, then the historical con-version factors can be used if liquid releases-are expected during the projection month. t (a) The prior month dose /Ci conversion factors-are ,
calculated by obtaining the results of the prior. month adult total body and teen liver dose calculation.
(b) Divids the doses by the total number of Curies released from the plant during this same time-period. This calculation yields a dose per l
Curie conversion factor for the adult total body and teen liver for the most recent prior calendar month. !
(c) The prior month Ci/ gal concentration factor is calculated by. obtaining the total number of Curies released from the plant during the _,
. prior month.. Divide the Curie-total by the total number of: gallons of waste discharged during this same time period. This calcu-p lation yields the Ci/ gal concentration conver-
, sion factor for the most recent month.
l
- 3. Multiply the estimated volume of liquid radwaste to be discharged, by the historical or prior month ~
dose /Ci and Ci/ gal conversion factors. This I
calculation yields a dose estimate to the adult total body and teen liver for the projected month.
L (a) T , x C , x D ,.. = TD,. (Adult Total Body Dose)
(b) T x C , x D ,i = TD, (Teen Liver Dose)
Where:
T, = Total volume of radwaste to be discharged during the month in gallons (estimated)
C, = Curies per gallon conversion factor (histor-ical or prior month)
Rev. No. 7 Page 22 of ODCM
- - . - - . .. . ._ _____-__________-___-____2
A D,. = Dose per Curies adult total body (his-torical or prior month) in aren TDa- = Total-dose for adult total body in arem D. , = Dose per Curies teen liver (historical or ;
prior month) in aren .
TD = Total dose for teen liver in aren ,
If the calculated doses are greater than'0.06 arem ,
to the total body or 0.2 area to the liver, the ap-propriate subsystems of the liquid radwaste system
'shall be used to reduce the radioactivity levels prior to release.
- b. Batch Dose Projections
'The projected dose due to release of each batch can be made prior to the release of the batch. The~projec-tion of~the dose related to each batch allows for an accurate method of estimating the dose from each batch prior'to release and confirms the need-to operate the ,
subsystems'of the radwaste system. The projection.of dose based on each batch release helps to eliminate.
any inaccuracies as a result of using historical or estimated values in the monthly projection. The use of this dose projection on a. batch release basis is not required by the technical specification and is used at the discretion of the Radiological and En-vironmental Services Management.
The method is based on total body dose and limiting organ dose-(liver) as calculated.in step 3.4.2. The L adult'is the limiting age group for projecting dose to ;
l the total body and the toen is the limiting age. group L, for projecting dose to the liver.
The following calculating methodology is provided for i performing this dose projection:
- 1. Obtain the latest result of the monthly calcula-tion of the adult total body and teen liver dose u (step 3.4.2).
l:
- 2. Divide the doses by the total number of Curies re-leased from the plant during the month. This yields a dose per Curie conversion factor for the adult total body and teen liver for the most recent calendar month.
Rev. No. 7 Page 23 of ODCM L
l
V ,
)
i
- 3. Maintain a running total of the Curies released i during'the-past 30 days. Add.to this the Curie l
-content of the-current batch.to be released'(31 i day. total).
p 4.. Multiply the.31 day total from step (3), above by
- the dose per curie. conversion factors calculated .
in step-(2), above.. This. yields the 31 day, total body and liver doses projected for tha. release of-the current batch.
- 5. If the calculated doses are greater than 0.06 arem q
- - to the total body or 0.2 aren to the liver, the ,
appropriate subsystems of the liquid radwaste system shall.be used to. reduce the radioactivity levels prior to release.
- c. coatinuous Liquid Release Dese Projections Each month that a continuous liquid release is in progress,.or is anticipated, the expected dose to man can be projected. The projection shall be based on ,
historical, prior month or current dose / curie and r nuclide concentration (Curie / gallon)' conversion fac- [
The historical conversion factors.are calcu-
~
tors.
1ated from prior releases. The prior month conver-sion-factors are calculated from the prior. month t
continuous liquid releases if such releases-occurred.
Current conversion factors are calculated from. .
samples obtained at or near.the beginning of the dose l projection month. ,
t
- 1. Determine which dose /Ci and Ci/ gal conversion factors should be used. Historical conversion
. factors can be used. Prior month or current l l
conversion factors should be used-if they are more representative of current release conditions.- J (a) The. current month Ci/ gal concentration is calculated by using current sample results for radionuclide concentration and converting the results to Ci/ gal.
(b) The current month estimated curies released is calculated by sultiplying the concentration by the known or expected flow rates for the affluent pathway times the period of release.
(c) Using the dose assessment methodology speci-fled in section 3.4, calculate the adult total body and teen liver doses using known or estimated flow rates and dilution factors.,
Rev. No. 7 Page 24 of ODCM
m (d) Divide the doses calculated in section (c) above'by the estimated number of curies to be released. - This calculation yields a dose per-Curie conversion factor for the current release parameters.
(a) The prior month dose /Ci conversion factors are calculated by obtaining the results of the prior month adult total body and teen liver dose calculations.
(f) Divide the, doses by the total number of curies
. ~ released from the plant via continuous releas-es during this same time period. This calcula-tion yields a dose per Curie conversion factor for the adult total body and teen liver for the most recent prior calendar month.
(g) .The prior month Ci/ gal concentration factor is
' calculated by obtaining the total. number of Curies released from the plant via= continuous releases during the prior month. Divide the-Curie total by the total number of gallons of, waste discharged during this same time period.
- This calculation yields the ci/ gal concen-tration conversion factor for the most recent month.
- 2. Multiply the estimated volume of continuous liquid affluent to be discharged by the historical, prior month or current dose /Ci and Ci/ gal conversion factors. This-calculation yields dose estimates to the. adult total body and teen liver for the projected month.
(a) T, x C, x Dn. = TDu . (Adult Total Body Dose)
(b) T, x C, x D,i = TDi (Teen Liver Dose)
Where:
T, = . Total volume of radwaste to be discharged during the month in gallons.(estimated)
C, =- Curies per gallon conversion factor (hi-storical, prior month, or current)
Dn. = Dose per Curies adult total body (his-torical, prior month, or current) in aren TDw= Total dose for adult total body in aren 1
Rev. No. 7 Page 25 of ODCM
y, .
~
l:l l
D,i- = Dose per CurieJ teen liver-(historical, prior month, or current) in area I-TD i
= Total dose for teen' liver in area T
If the calculated doses are greater than 0.06 area to the total body or 0.2 area to the; liver or other critical organ, efforts should be made to reduce the= effluent release rate or concentration.
The dose contribution from liquid batch releases (projected) should be evaluated in addition to continuous release dose.
r Rev. No. 7 Page 26 of ODCM
r .
. s
't t
i 4.O GASEOUS EFFLUENT METEODOLOGY 4.1 Gaseous Waste Streams James A. FitzPatrick Nuclear Power Plant discharges gaseous effluents through a stack, and discharges ventilation air -
from the reactor building, turbine building, radwaste build-ing, and refuel floor through separately monitored vent re- ,
lease points. There are three vent release locations. The refuel floor and reactor building vent is a combined release y point. Normal gaseous effluent streams, and effluent dis-charge points are tabu 3ated in Appendix F, Table F-1. ,
For the purpose of estimating offsite radionuclide concen-trations and radiation doses, radionuclide concentrations ,
are first measured,in gaseous effluents and ventilation air i exhausted from the plant. Technical Specifications, Appen-dix B, Table 3.2-1-identifies the specific radionuclides in gaseous discharges for which sampling and analysis is done.
' When a radionuclide concentration is below the LLD for the analysis, it is not reported as being present in tha sample.
4.2 Data-Requirements for Gaseous Effluent Calculations Dose calculations to demonstrate compliance with Technical Specifications, Appendix B, Sections 3.2.a, 3.3.a and 3.4.a are normally performed using historical meteorological data and receptor location (s) which yield calculated doses no i lower than those received by real receptor (s).. Historical L meteorological-data for.use in performing dose calculations are provided in Appendix C. Dose calculations to show con- ;
'formance with Technical' Specifications, Appendix B dose lim- -
L its may be performed using real meteorological data, real receptor locations, and sector. wind frequency distribution if desired.
Historical meteorological data factors are calculated and used in dose calculations for the semi-annual Radioactive Effluent Release Report. The report-is submitted 60 days after January 1 of each year. The dose assessment sections of this report are submitted 90 days after January 1 of each ,
year as on addendum to the Semi-annual Radioactive Effluent Release Report. Historical information and conservative receptor assumptions, are also used for ease of Technical Specifications, Appendix B, Limiting Conditions for Operat-ion (LCO) dose limit calculations. JAFNPP uses an elevated '
L release model for stack discharges and vent release model for reactor, turbine, radwaste and refuel floor vents. l Those radionuclides that appear in the gaseous effluent dose )
factor tables are representative of BWR isotopes that may be !
considered in dose calculations.
l l
Rev. No. 7 Page 27 of , ODCM i
4'. 3 Instantaneous Release Rate and Set Point Determination I
4.3. 11 Determining Instantaneous Noble sas Release Rates l
1
- a. Requirements Technical Specifications, Appendix B, Section 3.2.a.1 limits the instantaneous. dose rate from noble gases in airborne releases from the plant to <500Laram/yr - I total body, and <3,000 area /yr - skin. I The results of the sampling and analysis program of R Technical Specifications, Apper. dix B, Table 3.2-1 are used to demonstrate compliance with these limits. j]
- b. Methodology The instantaneous dose rates to the total. body and skin from noble gases are evaluated to determine gas-aous effluent release rates and alarm and/or trip set points, i
The following calculating method is provided for de-L termining the. instantaneous.aose rates to the total ~
l body and skin from noble gases,in all airborne release l -paths from JAFNPP. The conservatism factors in the l instantaneous release rate equations are adequate to
!, account for simultaneous releases from the NMP stack L and vent. James A. FitzPatrick Nuclear Power Plant discharges gaseous affluents through a stack, and discharges ventilation air from the reactor building, turbine building, radwaste building, and refuel floor through monitored vent release points.
The calculating methods are in accordance with NUREG-0133, October 1978, Section 5.1 and 5.2.
The' equations for computing instantaneous dose rates i are:
Total sody Dose Rate vent n .
DR TB " i=1 i* II/0)
- Oi Eq. 4-la The equation for DR s a summed over all vent TB release sources.
Elevated Stack n ___ .
DR Eq. 4-lb TB " gf 3 i* I /0)y *O i Rev. No. 7 Page 28 of ODCM
_ _ _ _=_ .
L mm--
skia Dose Rate _
Vest gg k n .
2 gggy = i=1 (Lg + 1.1 Mg ) (X/Q) xQ g DR E Eq. 4-2a r
The equation for DR EKIN is to be summed over all vent -i
[
release sources.
L tievated Stack SKIN "g g I i IX/9)
- l'1 Ni DR I Il*
y i Eq. 4-2b
- where
- _fE DRn = Total body dose rate from noble gases in L, airborne releases, in aren/sec.
DRui, = Skin dose rate fron noble gases in airborne .
m releases in aren/sec.
K, = The total body dose factor due to gammh
- emissions for each noble gas nuclide (i) reported in ths release source, in aram-n*/gCi-sec. ;
L, = The skin dose factor due to beta emissions for each noble gas nuclide (i) reported in the _
assay of the release source in arem-m*/gCi-see.
F Jr M, = The air dose factor due to gamma emissions for up each noble gas nuclide (i) reported in the ~
't assay of the release source. The constant 1.1 r converts 'arad' to 'aras' since the units of '-
M, are in: (arad-m'/gCi-sec)
(X/Q) = For vent or elavated stsek releases, the highest annual average, concentration X/Q, '~-
, calculated using long tern historic meteoro-logical data, for any land sector, at or
- bayond the site boundary, in sec/m' (Appendix ?
t{
C, Table C-1).
(X/Q)y= For elevated stack releases, the highest *^
- annual average, finite cloud X/Q, calculated _
T using long tern historic meteorological data, for any land sector, at or beyond the site boundary, in sec/m' (Appendix C Table C-2).
7
=
Rev. No. 7 Page 29 of ODCM ,
e ,
o: !
4 !
Q, = The release rate of noble gas nuclide (i) from the release source of interest, in l
.uci/sec.
- 1. Limited naalysis Approash - Imattataneous Noble j sas Release nate .
The above methodology can be simplified to provide i
for a rapid determination of cumulative noble gas release limits based on the requirements specified ,
above. For ease of calculation and without unduly ,
i reducing the conservation of the calculations, all j releases may be treated as if discharged from two release points, an elevated stack and the reactor vent. The reactor vent is used to represent the ;
combined discharge of the reactor building, turbine building, radwaste building, and refuel t floor vents. Beginning with equatLons 4-la and 4- !
'ib, the simplification proceeds as follows.
From an evaluation of past releases, an effective !
total body dose factor (F n) can be derived. This -
dose factor is, in effect, a weighted average total body dose factor (i.e., ws:,ghted by the ;
radionuclide distribution typical of past opera- ,
tion). See Appendix E for a detailed explanation ,
and evaluation of PLn. The value of K.n has been derived from the radioactive noble gas effluents ,
I for the years 1980, 1981, and 1982 for the plant.
The value ist F n = '7.G8E-5 (area-m'/pci-sec) .
(Vent Releases) -
K.n = 1.26E-4 (aram-m8/gCi-sec)
(Elevated Stack Releases) {
i i Either of these values, as appropriate, may be used in conjunction with the total noble gas release rate (EQi) to verify that the instanta-neous dose rate is within the allowable limits.
To compensate for any unexpected variability in the radionuclide distribution a conservatism factor of 0.8 is introduced into the calculation.
The simplified equations are ,
a Vent n .
DRTB = K,ff x (X/Q) E Qg Eq. 4-3a
- 1 0.8 4
Rev. No. 7 Page 30 of ODCM
= _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ . _ _ _ _ _ _ , _ _ , _ . _ , _ _ .
Blevated staek n .
DRTB "
K aff X (X/Q), g[1 Qi Eq. 4-3b 0.8 Wheret DR,. = Tctal body dose rate from noble gases in airborne releases, in area /sec.
(X/Q)= For vent releases, the highest annual
. average reactor vent concentration X/Q, calculated using long ters historic meteo-rological data, for any land sector, at or beyond the site boundary, in sec/a8 (Appendix C, Table C-1)
(X/Q)1= For elevated stack releases, the highest annual average finite cloud X/Q, calcu-lated using long torn historic meteorolo-gical data, for any land sector, at or beyond the site boundary, in sec/a*.
(Appendix C, Table C-2) n.
E Q. = The total release rate of all noble gas i=1 nuclides from the release source of inter-est, in sci /sec A single cumulative (or gross) noble gas release rate limit for elevated stack releases and vent releases may be derived by rearranging equations 4-3a and 4-3b.
Release Rate Limit DRTB x (0.8) for Vent Releases = Eq. 4-4a K,gg x (X/Q)
Release Rate Limit DR TB x (0.8) for Elevated Stack = Eq. 4-4b Releases X,gg x (X/Q)
These limits any be determined by taking the highest calculated annual average (X/Q)3, for elevated stack releases and the highest calcu-lated annual average reactor vent (X/Q) for vent releases, at any of the land based sectors, at or beyond the site boundary. From Appendix C Tables C-1 and C-2 these values are:
4 Rev. No. 7 Page 31 of __QDCE _
g l
1 l
?
= 1.44E-7 Bap (Stack Reisases) _f (X/Q), --
m
= 4.83-7 Bay (Reactor Vent Releases) ,
(X/Q) a 5
l Also, the dose limit of 500 ares /yr = 1.585E-5
- di aram/sec may be substituted for DRyg in equations ]
4-4a and 4-4b. _
In addition, f on a review of gaseous affluent releases as reported in the JAFKPP semi-annual --
Effluent Release Reports for the years 1980, 1981 and 1982, it was determined that, on the average, approximately 90 percent of the annual total body dose from noble gases was due to elevated stack -
releases. These data are presented in Appendix ,
E. In ace'ordance with this, the release limit is a split as fcilows. ;;
90% - Elevated Stack Release __
10% - Vent Release )
Making these substitutions in equations 4-4a and 4-4b yields the following cumulative (or gross) ;
noble gas release rate limits:
Elevated Stack Release J Rate Limit = 6.29E+5 pCi/sec
}_
Vent Release Rate Limit = 3.42E+4 gCi/sec As long as the noble gas release rates do not ex- j coed these values (6.29E+5 gCi/see for elevated
~
stack releases, and 3.42E+4 pCi/sec for vent releases) no additional dose rate calculations y are needed to verify compliance with instantan- g oous release rate limits of Technical Specifica- w tions, Appendix B, Section 3.2.a.1. i
- 2. General Approach - Total Body and Skin Nuclide-Specific Instantaneous Release Rate Calculations The mothods described herein may be used for more i refined calculations or used if the actual releases exceed the values oft ,
a Elevated Stack 3 Release = 6.29E+5 pCi/sec i Vent Release = 3.42E+4 pCi/see
]
Rev. No. _ 7 Page 32 of ODCM _ ;
. , . , , , , , ,, , , . , , ~ ,,, , , . ,, ., , ,, .. . $
.l l
- Total Body Dese Rate
. Eq. 4-5a vent n .
DR i
- IX/0I
- S TB " i=1 i j
The equation for DN gis to be summed over all vent release sources. ;
Eq. 4-5b Elevated staek n . I DR #1 x (X/Q), x Qg j TS " i=1 ;
Where j DR,, = Dose rate to the total body due to ganaa emissions from all noble gas nuclides, aren/sec. i
- K. = The total body dose factor due to gamma L~
emissions from noble gas radionuclide (i), -
l in area-m*/gCiesec (see Appendix B, Table B-2).
(i76) = For vent releases, the highest annual '
average ccncentration X/Q, calculated '
using long term historic meteorological l<
L data, for any land sector, at or beyond L the site boundary, in sec/m* -(Appendix C, l Table C-1). .
(X/Q)T= For elevated stack releamos, the highest '
annual average finite cloud X/Q, calcu- '
lated using long term historic meteorolo-gical data, for any land sector, at or beyond the site boundary, in sec/a* (Appe-
- l. ndix C, Table C-2).
l Stack (X/Q)v = 1.44E-7 sec/2 8 l ..
Vent (X7Q) = (.83E-7 sec/m' 1;
Qi = Release rate of the 1" nuclide from the :
release source of interest, in pci/sec.
Rev. No. 7 Page ___2) of ODCM
l l
Skin Dese Rate 9 ,,g Eq. 4-6a n .
gggy = i=1 (Lg + 1.1 Mg )(X/Q) xQg DR E The equation for DR is to be summed over all vent release sourceEKIN Eq. 4-6b Elevated staek n .
DRgggy= E (Lg (X/Q) + 1.1 Mg (X/Q),) x Qg i=1 Where:
DR . = Dose rate to skin due to beta and gamma radiation from all noble gas nuclides (area / sec).
In = The skin dose factor due to beta emissions from noble gas nuclide (1), in-area-m' /gCi/sec ( Appendix B, Table B-2) .
M. = The air dose factor due to gamma emissions from noble gas nuclide (1), in arad-m*/gCi sec (Appendix B, Table B-3).
1.1 = Conversion factor for M, from arad to trem.
X/Q = For vent or elevated stack releases, the highest annual average concentration X/Q, calculated using long term historic meteorological data, for any land sector, at or beyond the site boundary, in sec/m' (Appendix C, Table C-1).
(X/Q), = For elevated stack releases, the highest annual average finite cloud X/Q, calcu-lated using long term meteorological data, for any land sector, at or beyond the site boundary, in sec/m* (Appendix C, Table C-2).
Q. = Release rate of the 1" nuclide from the release source of interest in pCi/sec.
l l
Rev. No. 7 Page 34 of ODCM__,
L c. calculating Process The fallowing outline provides a step-by-step ex-planation of how the total body and skin dose rates are calculated on a nuclide-by-nuclide basis to evaluate compliance with Technical specifications, Appendix B, Section 3.2.a.1. This adthod is used for more refined calculations or if the actual releases exceed the value specified in the Limited Analysis Approach - Instantaneous Noble Gas Release Rate.
[
- 1. For a vent, the X/Q value = , sec/t' and is the most lialting land sector at k or beyond the site boundary.
For an elevated stack release, the (X/Q) value .
= sec/a* and is the most limiting L land sector at or beyond the site boundary and the (X/Q), value = sec/a' and is the most limiting land sector at or beyond the site boundary.
- 2. Enter the release rate in ft'/ min of the release
=
source and convert it to cc/ sect
= ( ift' x 2.8317E+4 cc x min min ft' 60 eac
= cc/sec volume release rate
- 3. Determine Q for nuclide (i) by obtaining the uci/cc sasay value of the release snurce and multiplying it by the release rate computed in the previous steps.
h, = ( inci x ( iec
- cc see
- h,= pCi/sec for nuclide (i)
- 4. To evaluate the total oody dose rate, obtain the K, value for nuclide (i) from Appenuix B, Table B-2.
- 5. Solve f or DR,,,:
vent E
DR TBi " i
- IX/0)
- i" #Ci-sac E88 1
- n'M
- sec N
- m
Blevated staek DETBi= kg x (X/Q4 x hg = aram-mi xBasX M pci-sec a' see DR = Total body dose rate from nuclide TBi (i) for the specified release source in area /sec
- 6. To evaluate the skin dose rate obtain the L, and N, values from Appendix B Table B-2 for nuclide (1).
- 7. Solve for DA ..:
Vent DN , = ( L. + 1.1 N,) (X/Q) x Q, Elevated Stack DNr. , = (L. (X/Q) + 1.1 M (X/Q),) x d, DN:., =
Skin dose rate from nuclide (i) for the specified release source, in ares /sec
- 8. Repeat steps 1 through 7 above for each noble gas nuclide (i) reported in the assay of the release source.
- 9. The dose rate to the. total body from radioactive noble gas gamma radiation from the specified release source ist n
DR, = E DR,,,
i=1
- 10. The dose rate to the skin due to noble gas radia-tion from the specified release source is:
n DA: = E DA . ,
i=1 The dose rate contribution of this release source shall be added to all other gaseous relsase sources that are in progress at the time of interest.
Rev. No. 7 Page 36 of ODCM 1l N W
i i
Technical Specifications, Appendix B, Section 3.2.a.1 reqaires the following.
DRn $500 area /yr (1.585E-5 area /sec) -
DRun $3,000 aren/yr (9.513E-5 ares /sec)
Wheret DRn = The sum of the total body dose rate con-tributions (aren/sec) from all noble gas nuclides from all concurrent releases.
Drum = The sua of skin dose rate contributions (area /sec) from all noble gas nuclides from all concurrent releases.
4.3.2 set Point Determination
- a. Requirassats To-comply with Technical specifications, Appendix B, section 3.1, the alarm / trip set points are establish-ed to ensure that the noble gas releases do not exceed the appropriate cumulative (or. gross) noble gas release rate limit specified in Limited Analysis Approach - Instantaneous Noble Gas Release Rate.
- b. Methodology This section describes the methodology for determin-ing alarm / trip set points for the stack and vent gaseous release pathways. To allow for multiple sources of releases from different or common release points, the allowable operating set points will be administratively controlled to allocate a percentage of the total allowable release to each of the release sources. The cumulative noble gas release rate limit for a stack (elevated) release (6.29E+5 pCi/sec) is based on allocating 90 percent of the total body dose limit to the stack release point. The individual release rate limits for the other gaseous release points (assumed to be vent releases), are based upon an allocated percentage of the cumulative vent re-lease rate limit (3.42E+4 pCi/sec).
The method that follows establishes a procedure for determining set points.
- 1. Determine the maximum volume release rate po-tential for the release source under considera-tion.
Rev..No. 7 Page 37 __ o f ODCM
_ _ __ . _ .._ ____ .. _ _ _ . . _ _ _ _ . _ ~ _ _ . _ . _ _ _ . . . _ _
I i
i l
L !
- t i
- 2. Based upon that release rate (ft*/ min or other i units of vol/ time) determine the equivalent ac- !
- tivity concentration in (gCi/ce) that would {
produce a release of 6.29E+5 pCi/sec - Elevated Stack Release l 3.42E+4 pCi/sec - Vent Release ;
- 3. Referring to the calibration factor (gCi/cc vs. l l CPM or CPS) for the release source's gaseous ;
r effluent monitor, determine the CPM or CPS value I (C) corresponding to the value of activity !
concentration determined in step 2 above.
- 4. For an elevated stack release, the set point is equal to the CPS value as follows. l SP = (C) CPS Eq. 4-7
- 5. For a vent release, (C) corresponds to 100 percent of the vent. release rate limit assuming :
no other vent release sources at the time. To ;
obtain an operational set point value SP, take (C) in (CPN) and multiply it by the allocated fraction for a specific vent.
fraction ;
allocated for SP = (C) CPM x a particular Eq. 4-8 vent release A typical allocation may be as follows-(example .
only).
Turbine Vent - 0.61 Reactor Vent - 0.14 Refuel Floor - 0.17 Radwaste Vent - 0.08 The total body dose is more limiting than the calculated skin dose. Therefore, the skin dose rate calculations are not required if the simpli-fled dose rate calculation is used (i.e., using K.,, to determine release rate limits) .
l Rev. No. 7 Page 38 of ODCM
The calculating processes of step 4.3.1.c are to be used if the actual releases of noble gases exceed the predetermined, limits of 6.29E+5 pCi/sec for elevated stack releases or 3.42E+4 pCi/sec for vent releases.
Unde:- these conditions, a nuclide-by-nuclide evaluation is required to evaluate compliance with the dose rate limits of Technical Specifica-
'tions, Appendix B, section 3.2.a.1.
i Rev. No. 7 Page 39 of ODCM
-____-___-__--_-___-___________--__-_--________-----__w
4.3.3 Determining the Radisiedime, Tritium, and Eight Day Particulate Instantaneous Release Rates
- a. Requirements !
Technical Specifications, Appendix B, Section 3.2.a.2 i limits the instantaneous dose rate from I-131, I-133, tritium, and particulates with half-lives greater than eight days released from the plant to 1,500 ,
I aren/yr to any organ, from the inhalation pathway only. The limiting age group is the child, and the limiting organ is the thyroid, per Table 3-7.5, Appendix B.
- b. Methodology The following calculating method is provided for de-termining the dose rate from radiciodines, tritium, and particulates. It is based on NUREG-0133, October 1978, Sections 5.2.1 and 5.2.1.1.
Actual concentrations of Iodine-131, Iodine-133, and radionuclides in particulate form with half-life .,
greater than 8 days released from the plant in j gaseous affluents shall be determined using gamma isotopic analysis. Tritium and strontium are deter- i mined by offsite analysis. Sampling and analysis shall be performed in accordance with frequency g specified in Table 3.2-1 of the RETS.
Based on an analysis of doses to various organs and age groups for the inhalation pathway, the child was verified as being the controlling age group and the thyroid as being the limiting organ. This pathway is the only one that need be considered for instanta -
neous releases. The long term sector average con-centration (X/Q) values are based on historical meteorological data. Dose factors for nuclides listed in Appendix B, Table B-4 will be used.
Inhalation Pathway The equation for DRI&8DP is to be summed over all f
release sources (s).
a n .
DR
- Eq. 4-9 I&8DP 7 s=1 i=1 'i r
II/OI s* O is Where:
7 = The organ of interest for the age group of interest (thyroid, child). ;
- 6. = Total release rate of nuclide (i), (gci/
see) for each release source (s).
l l Rev. No. 7 Page 40 of ODCM'
- *-1r-"4- =ww'- pw. =we e-+-.. , , -sw.-, .veg.gvp-.-,.-g.3.v---- _, _ _ _ _ . , - -__m -
a __- ,r___ . _ , , _ _ . , _ _ . _ _ . _ _ . , _ _ _ _ _ , _ _ , _
l j
Dram,f = Total dose rate to the child thyroid from l iodines, tritium, and eight day particu- ;
lates via the inhalation pathway (aren/yr) j for all release points p.
l (X/Q). = The long term sector average concentration ,i X/Q value based on historical meteorologi- ;
cal data in (sec/a*) for release source s i (Appendix c). l P., = The dose factor for the inhalation pathway i in (area /yr per sci /m* ) - for nuclide (i) i (Appendix B, Table B-4). The derivation of P, values is given in Appendix B, Table B-7.1.
a = The number of release sources of interest.
The maximum allowable release rate of all radicio- '
dines, tritfua, and particulates, summed together, is determined by the following relationshipt Eq.4-10 Q7 = ""1
( (Frac), DRThyroid
] x'0.8 .
l (X/Q), #i(Thyroid) '
Where DRn, .. = Dose rate to the child's thyroid from the inhalation pathway set equal to the Technical Specific-ations, Appendix B, section 3.2.a.2 limit of 1,500 aren/ year. ,
Puny,,,o = The dose factor of I-131 for the inhalation pathway, 1.62E+7 mram/yr per sci /m* (Appendix B, Table B-4).
(X/Q). = The long term sector average con-centration X/Q value for any land l sector value based on historical meteorological data in (sec/a*) for release source s (Appendix c).
Q = Maximum allowable release rate of all radiciodines, tritium, and particulates summed together in sci /sec.
(Frac). = Fraction of 1500 area /yr limit allo-cated to release source s, such that I(Frac) . = 1. 0.
Rev. No. 7 , Page 41 of ODCM
l 4.4 Dese Determinaties for Radioactive Saseous Effluents l 4.4.1 Annual Dese Assessment - Radioactive Effluent Release Re- i port submittal i
- a. Requirements 1 Technical specifications, Appendix 3, section 7.3.C requires a semi-annual Radioactive Effluent Release ,
Report be submitted 60 days after January 1 of each "
year. Technical specifications also requires that l this-report includes an assessment of the radiation doses to the public'due to the radioactive liquid and gaseous effluents released from the unit during the ,
previous calendar year. The dose assessment sections !
of this report are submitted 90 days after January 1 of each. year as an addendum to the semi-annual
. Radioactive Eftluent Release Report.
I
- b. Methodelegy The section provides the methodology to calculate the doses to.all age groups and organs from radionuclides identified in the gaseous effluents.
The method is based on the methodology suggested by l [
i NUREG-0133, October 1978, sections 5.3 and 5.3.1.
The determination of viable gaseous dose pathways is ,
described.in Table B-7.4. The site related dose i factors for viable pathways are listed in Appendix B. >
Dose factors are compiled by age groups, for organs :
and radionuclides common to a BWR environment. !
Normally calculated annual long term historical at-mospheric diapersion factors are used to perform the annual dose assessment. Actual meteorological data and sector wind frequency distributions for the year !
of interest may be used in lieu of.the annual long ,
term historical factors. 40 CFR 190 dose assesments, when required, will be made using actual meteorologi- ;
cal data and frequency distribution data for the year covered by the evaluation.
I The following equations provide for a dose calcula-tion to the total body or any organ for a given age group based on actual releases during a specific time interval for radioactive gaseous release sources:
(1) Annual Air Dese Due to Noble Gases Eq. 4-11a Vent n
D x Gamma-Air " i=1 "i x (X/Q) Qg l Rev. No. 7 ,
Page 42 of ODCM
i The equation for D Gam l Vent release sources.ma-Air is to be summed over all Elevated staek d
Eq. 4-11b n
Gamma-Air"g[g "i X (X/Q), x D Qg where D ..., = The gamma air dose from radioactive noble j gases, in arad. j
, M. = The gamma air dose factor for radioactive j noble gas nuclide 'i', in arad-m*/pci-sec (Appe,ndix B, Table B-3).
l (X/Q) = The long tern historical atmospheric !
dispersion factors for vent releases l (annual average) for the location of inter- :
est. Actual meteorological data and sector >
wind frequency distributions may be used to -
determine annual X/Q for the year of interest in sec/a*.
l-(X/Q), = The long term historical atmospheric dispers:,on factor for elevated stack releases (annual average) for the location of interest based on the finite cloud methodology. Actual meteorological data and sector wind frequency distributions may ;
be used to determine annual X/Q for the !
year of interest in sec/a*.
Q, = The number of pCi of nuclide 'i' released L during the year of interest from the >
release source of interest.
Eq.4-12 n
D E Ng x (X/Q) x Qg Beta-Air = i=1 l The equation for DBeta-Air is to be summed over all I
vent and elevated stack release sources, i
+
L Rev. No. 7 Page 43 of ODCM 1
._ _.~. _ _ _ . . .
i l
I Where:
Dm . .. . , = Beta air dose from radioactive noble gases in arad. !
1 N. = The beta air dose factor for radioactive noble gas nuclide (i) in arad-a*/pci-sec (see Appendix B, Table B-3).
(X/Q) = The long term historical atmospheric dispersion factors for vent or elevated stack releases (annual average) for the location of interest. Actual meteorolog-ical data and sector wind frequency dis-tributions may be used to determine annual j X/Q for the year of interest in sec/a'. ;
1 Q. = The number of #Ci of nuclide 'i' released I during the year of interest from the !
release source of interest. J (2) hanual Total Body Dese Due to Noble esses l, Eq. 4-12a Vent P
n DR TB"gfy i* IX/0)
- Oi l
The equation for DRTB is to be summed over all vent release sources.
Elevated Staek ,
n DR x x TB"g[g ki (X/Q), Qg (3) Annual Total skia Dose Due to Noble esses Eq. 4-12c >
L Vent I
n DR z SKIN " i=1 Ibi + 1'1 Ni) (X/Q) xQi 9
The equation for DRSKIN is to be summed over all vent release sources.
Rev. No. 7 Page 44 of ODCM sw~ m ,-., .- ,..,.v .-
, .r__ ,_
Blavated stack n
DR gggy = i 1 (Lt (X/Q) + 1.1 Mg (X/Q),) x Qg Wheret DRn = Total body dose from noble gases in air-borne releases, in area.
DRua = Skin dose from noble gases in airborna releases in area. ,
K, = The total body dose factor due to gamma
- emissions for each noble gas nuclide (1) reported in the release source, in aren-a*/pci-sec (Appendix B, Table B-2). .
In = The skin dose factor due to beta emis-sions for each noble gas nuclide (1) reported in the assay of the release source in arem-s* /pci/sec (Appendix B, ,
- Table B-2).
M, = The air dose factor due to gamma emis-i sions for each noble gas nuclide (i) ?
-reported in the assay of the release i sourca. The constant 1.1 converts 'arad' to ' ares' since the units of M, are in i arad-s*/gCi-sec (Appendix B, Table B-2).
(X/Q) = The long tera historical atmospheric dispersion factors for vent or elevated stack releases (annual average) for the location of interest. Actual meteor-ological data and sector wind frequency distributions may be used to determine annual X/Q for the year of interest in .
sec/a'. 4 (X/Q), = The long tera historical atmospheric dispersion factor for elevated stack i releases (annual average) for the loca-tion of interest based on the finite cloud methodology. Actual meterorologi-cal data and sector wind frequency distributions may be used to determine annual X/Q for the year of interest in sec/a'.
Q. = The number of microcuries for each noble gas nuclide (i) released during the year '
of interest from the release source of interest.
Rev. No. 7 Page 45 of oDcM
(4) Amaual Dese Due to Radiciodines, Tritium, ame Eight Day Particulates Zahalation Pathways Eq.4-13 D = (3.1 E-8) E Rg x (D/Q) x Qg I&8DP,f i=1 e around Plane Deposition Pathway Eq.4-14 n
D = (3. E-8) E Rg x (D/Q) x Qi I48DP ,f i=1 f cow's Milk Pathway Eq.4-15 D = (3.17E-8) E Rg x (D/Q) x Qg I&8DP,f i=1 f Goat's Milk Pathway Eq.4-16 D = (3.17E-8) E Rg x (D/Q) x Qg I&8DP i=1 f
,f I
Meats Eq.4-17 n
D =
(3.17E-8) E Rg x (D/Q) x Qg e I&8DP r i=1 r i
vegetation Eq.4-18 n
D =
(3.17E-8) E Rg x (D/Q) x Qg I&8DP ,r i=1 r
, g Rev. No. 7 Page 46 of ODCM 9
- ~ - - - , -,e. -- ,-,n ,e -- --_ _ ~_. , -- ,,~ne- ,-
I 1
l l
l For tritium, the dose is calculated by substituting X76 and RH-3' in equations 4-15 to 4-18.
, ]
Total haaual Dese From Release Seuree of Interest Eq.4-19a p !
D =E D !
fa ,,3 , I&8DP, f
a ,
Total Amaual Dese Eq.4-19b D =E D
' #8 s=1 - * ,
Wherst f = The organ of interest for the age group of interest.
I s = The release source of interest. j z = Pathway of interest.
p -
The number of pathways of interest.
m = Number of release sources of interest.
L (DI&4DP)7
= Annual dose to the organ.f for the age group of interest from l
iodines, tritium, and eight day par-ticulates via the pathway of inter-est in (area).
3.17E-8 = The inverse of the number of seconds per year in (years /sec).
D,, = '?otal annual dose to organ f from all applicable pathways for the age group of '
interest and for the release source of interest in (area). *
! D, = Total annual dose to organ f from all ap-plicable pathways for the age group of interest and for all release sources of interest in (area). ,
L Rev. No. 7 Page 47 of ODCM
. -_ _ _ _ _ _ _._.. ___ _ _ _ _.. . 1_ _ _ . . - . . _ . _ _ ._ . . _ . _ _ _ _ _ . . _ .
L. , o l
i: i Q, = The number of sci of nuclide 'i' released !
during the year of interest from the I release source of interest. l !
l I
Ro = The dose factor for nuclide (i) for organ f for the pathway specified, units vary with pathway. The derivation of Ra values is given in Appendix B, Table B-7.2.
(D/Q) = The long term historical annual average relative deposition values for elevated stack cr vent releases for the ground ,
plane deposition pathway. For the seat, cow, goat, and vegetable pathways, the long term historical grasing average deposition values for elevated stack and vent releases are used (Appendix C). A 1 factor with units of a 8 which describes
,the deposition of particulate matter from a plume at a point downrange from the source. Actual meteorological data and esctor wind frequency distribution may be used to determine annual average D/Q for the year of interest. D/Q is not used to l calculate doses associated with H-3 releases.
(X/Q) = The long term historical annual average atmospheric dispersion factors for vent or elevated stack releases for the loca-tion of interest (Appendix C). Actual ,
meteorological data and sector wind fre-quency distributions may be used to determine annual X/Q for the year of interest in sec/a*. The X/Q is used to ;
determine doses for H-3 releases.
4.4.2 Monthly Dese Assessment - Verifiention of Complianos with 10 CFR 80, AppendiE I J
- a. Determining the Gamma Air Dose for Radioactive Noble Gas Release souroe(s)
L (1) Requirement Technical Specifications, Appendix B, Section 3.3.a limits the air dose from gamma radiation due j to noble gases released from the plant in the
- l gaseous effluent slo mrad during any calendar L year, and 5 mrad in any calendar quarter. ,
Rev. No. 7 ,
Page 48 of ODCM l
..- . . - . - - _ .- - -- . . _ . - , . . . ~ . . - . . . _ _ - . . - . - . . , _ - - - - - - . - . _ - . . , - .
- - . _ ~ . . . - - . - - - . . . . . . - . . . - . . _ . - - . . - - _ . - _ - - - -
L i
i Technical specifications, Appendix 3, surveillance l Requirement, Section 3.3.a, requires that cumula- I tive air dose contributions from noble gases be ,
calculated at least monthly for the current calen- i dar quarter and current calendar year. l (2) Methodelegy 1 The following calculation method is provided for .
determining the noble gas gamma air dose and is based on NUREG-0133 October 1978 Section 5.3.1. ,
The dose calculation is independent of age group. -
The equation may be used for Technical specifica- '
tions, Appendix 5 dose calculations, the dose cal- ,
culation for the annual report, or for projecting dose, provided that the appropriate value of (X/Q) is used. The equation for gamma air dose is:
I :
Eq. 4-20a l D -
D * *O Gamma-Air kNi* I*/0) i The equation for D is to be summed over all vent release s88P58sAir Eq. 4-20b ,
Elevated Stack n
D "
Gamma-Air g,g "i
- IX/0)7 *Oi where l
Dm.m = The gamma air dose from radioactive noble gases in arad.
M, = The gamma air dose factor for radioactive noble gas nuclide 'i',
in arad-s*/pci-sec (Appendix B, Table B-3).
(X/Q) = The highest long ters annual average atmospheric dispersion factors for vent releases for any land sector, in sec/a8 (Appendix C, Table C-1).
L Rev. No. 7 Page 49 of ODCM L
i-(X/Q), = The highest long ters annual average l atmospheric dispersion factor for g
elevated stack releases for any land sector based on the finite cloud methodology, in sec/m' (Appendix C, i Table C-2).
1 Q. = The number.of pCi of nuclide 'i' ,
released (or projected) during the dose calculation exposure period i (e.g. , month, quarter, or year) from the release source of interest. >
(a) Limited natlysis approach The following limited analysis approach l any be used to establish monthly release objectives (sci / month) that will ensure compliance with 10 CFR 50, Appendix I gamma dose limits.
From an evaluation of past releases, a single effective gamma air dose factor
()(n) has been derived, which is represen-tative of the radionuclide abundances and !
corresponding dose contributions typical ,
of past operation (Appendix E has a -
detailed explanation and evaluation of N n) . The value of M n has been derived from the radioactive ncble gas affluents for the years 1980, 1981, and 1982. The value is ,
Mn= 8.17E-5 mrad-s*/gCi-sec (Vent Release)
P(n = 1.31E-4 arad-s*/gCi-sec (Elevated Stack Release) -
The effective gamma air dose factor may be used in conjunction with the total noble gas release (EQ.) to simplify the dose evaluation and to verify that the cumula-tive gamma air dose is within the equiva-lance of the limits of Technical specifi-cation 3.3.a.2. To compensate for any unexpected variability in the radionu-clides distribution, a conservatism factor of 0.8 is introduced into the calculation. .
The simplified equation for elevated stack releases is: .
Rev. No. 7 Page 50 of ODcM
I U
I Eq. 4-21 DGamma-Air = 0.8 i=1 Qi For purposes of calculations the appropri-ate meteorological dispersion (X/Q) should be used.
I Solving equation 4-21 for the monthly ]
release objectives yields the following:
Eq. 4-22a-Daa-- -Air v to.a) i Ventilation "
Release Objective (M n) x (X/Q) 1 Eq. 4-22b
]
Daa-- -Air x fo.a)
Elevated Stack "
Release Objective
- gg,n) , (yfg) 7 .
I Technical Specifications, Appendix B, Sec- ,
tion 3.3.a states that the doses must be evaluated'once per month. The yearly dose '
limit is 10.arads, which corresponds to a monthly allotment of 0.83 mrads. If the !
0.83 mrads is substituted fer D .u, in equations 4-22a and 4-22b, a cumulative noble gas monthly release objective can be ,
calculated for elevated stack and vent re-leases. As described in section 4.3, 90 percent of the dose will be allocated to elevated stack releases and 10 percent to vent releases in accordance with release source terms for the year 1980, 1981, and 1982 (Appendix E). Thus (X/Q) values of 4.83E-7 sec/m' for vent releases and 1.44E-? sec/m8 for elevated stack releases ,
can be used, along with the corresponding.
NLu values, to calculate the following cumulative noble gas monthly release ob-jectives.
Q (vent release) = 1.68E+9 pCi/ month Q (elevated stack release) = 3.16E+10 pCi/ month Rev. No. 7 Page 51 of ODCM
l As long as these values are not exceeded i during any month, compliance with the i quarterly and annue.1 noble gas release l limits of Technical specifications, Appen-dix B, section 3.3.a is demonstrated.
When the limited approach method is used, ,
the calculations of 4.4.2.a(2) must be performed monthly as a minimum. 9 The gamma air dose limit does not cause the beta air dose limit to be exceeded when the limited analysis approach of this section is used. .
- b. Determining the Beta Air Dese for Radioactive Noble eas Release Seuroes The beta air dose calculations of this step is re- ,
quired to be performed when the radionuclide specific dose analysis of Gamma Air Dose is performed. The radionuclide specific dose analysis is performed at least monthly in accordance with Appendix B of the Technical Specifications, i (1) Requirement Technical specifications, Appendix B, section l 3.3.a limits the air dose from beta radiation, due to noble gases released from the plant in the gaseous effluents, to less than or equal to
! 20 mrad during any calendar year and less than l or equal to 10 mrad in any calendar quarter.
Technical Specifications, Appendix B, survalli-ance Requirement, Section 3.3.a, requires that -
cumulative air dose contributions from noble "
gases released from the plant be calculated at least monthly for the current calendar quarter
- and current calendar. year.
When the nuclide. specific dose calculation is used to evaluate compliance with the gamma air '
dose limits, the beta air dose shall be evalua-ted on a nuclide specific basis using the methodology presented below.
Rev. No. 7 Page 52 of __ODCM
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ . _ _ _ . _ _ . . _ _ . _ _ _ . _ , ~ . _ . , - _ . _ . .
t (2) Methodology The following calculating method is provided for determining the beta air dose and is based on .
NUREG-0133, October 1978, Section 5.3.1.- The dose calculation is independent of any age ;
group. The equation may be used for dose cal- l culations for Appendix B of the Technical specifications, semi-annual Radiological Ef- :
fluent Release Reports, or for projecting dese, !
provided that the appropriate value of (X/Q) is used.
The equation for beta air dose is Eq.4-23 n
D Beta-Air
= N i
X (X/Q) x Qg i=1 The equation for D *ta-Air is to be summed over all release sourceI Where Dm..u , = Beta sir dose from radioactive noble '
gases in (arad).
N. = The beta air dose factor for radioac-tive noble gas nuclide 'i' in arad-m8/pci-sec (Appendix B, Table B-3).
(X/Q) = For vert or elevated stack releases, the highest annual average, X/Q, calcu-lated using long term historic meteor-ological data, for any land sector, at or beyond the site boundary, in sec/m*
(Appendix C).
Q, = T.te number of #Ci of nuclide 'i' released (or projected) during the dose calculation exposure period from the r
release source of interest.
Rev. No. 7 Page 53 -of ODcM
- c. Determining the Radisiedine, Tritium, and Bight Day Particulate Dese to any orgaa frea cumulative Releases (1) Requirement Technical specifications, Appendix B, 3.4.a.1, limits the dose to the total body or any organ resulting from the release of radiciodines, tritium, and particulates with half-lives greater than eight days released from the plant to less than 7.5 area / quarter and less than 15 .
area /yr to any organ.
- Technical specifications, Appendix B, survaill-ence Requirement, section 3.4.a, requires that cumulative dose contributions be calculated at least monthly for the current calendar quarter and current calendar year.
(2) Methodology The following calculating method is provided for determining the organ dose due to releases of radiciodines (I-131, I-133), tritium, and par-ticulates with half-lives greater than 8 days.
It is based on NUREG-0133, October 1978, Section 5.3.1. The equations can be used for any age group provided that the appropriate dose facters are used and the total dose reflects only those pathways that are applicable to the age group and the receptor location. The dispersion factor, (D/Q), represents the rate of fallout from the cloud that affects a square meter of ground at variot3s distances from the site. The total dose to an organ can then be determined by summing the pathways that apply to the receptor in the sector. The equations are:
Inhalaties Pathway Eq.4-24 D
I&8DP
= (3.17E-4) E Rg x (D/Q) x Qt 7
Grenad Plane Pathway Eq.4-25 f n D
I&8DP
= (3. E-8) E Rg x (D/Q) x Qg
, Jr i=1 f Rev. No. 7 Page 54 of ODCM
E c
cow's Wilk Pathway b
Eq.4-26a n
D = (3.17E-8) E Rg x (D/Q) x Qt
- I&8DP i=1 r
, ,f P eoat's Milk Pathway Eq.4-26b n
= (3. x x D
I&8DP ,e E-8) E Rg (D/Q) Qg t ,
i=1 f
=
E Meats Eq.4-26c n .
' x x D
I&8DP * (3.17E-8) E Rg (D/Q) Qi
,r i=1 f Vegetation a Eq.4-26d C
n D
I&8DP " I 'l7 ~8} Z i
- (!} i 7 , ,f i=1 r E For tritium, the dose is calculated by substitutir' X/Q and g 3 in equations 4-26a to 4-26d.
C Total Dose Pros a Release source 5 for Applicable pathways Eq.4-2?a
, D =I D '.
, fa ,,y , I68DP,g og
, Rev. No. _ 7 Page 55 ODcM
Total Amaual Dese From All Release Sources of Interest Eq.4-27b D =E D s=1 - <
Wheret
- f. = The organ of interest in a specified age group.
s = The release source of interest.
- = The pathway of interest.
p- = The number of pathways of interest.
a = The number of release sources of interest.
Dose in area to the organ f of a (DI&sDP) r=specified age group from radiciodines, tritium, and 8 day particulates due to a particular pathway.
I Dr. = Total dose to organ f from all ap-plicable pathways for a specified age s_ group for the release source of inter-est in (area).
Dr = Total dose to organ r from all ap-plicable pathways for a specified age group and for a11' release sources of interest in (area).
3.17E-8 = The inverse of the number of seconds per year in (years /sec).
R,, = The dose factor for nuclide (1) organ f of the specified age group. The units are either area-m'/yr-#Ci for pathways using (X/Q), or aren- ad-sec/yr-sci for pathways using (D/Q) (Appendix 8, 4
Tables 3-5 and B-6).
(X/Q) = The concentration (X/Q) value for a specific location where the receptor is located. The units are (sec/a8) (Appa-ndix C). The X/Q is used to determine doses for H-3 releases.
Rev..No. 7 Page 56 of __ODCM I
m _
n (D/Q) = The deposition value for a specific location where the receptor is located.
The units are (m 8 ) (Appendix C). D/Q is not used to calculate doses as-sociated with H-3 releases.
Q, = The number of microcuries of nuclide (i) released (or projected) during the ll dose calculation exposure period from the release source of interest.
(a) Limited Analysis Approach Based on an analysis of doses to all or-gans from all atmospheric release pathways and age groups, the milk pathway has been identified as the most limiting pathway.
The infant's thyroid has been identified as being the most limiting organ and age group. This pathway contributes, on l average, over 91 per cent of the total dose received by infant's thyroid and the radioiodines contribute essentially all of this dose. Therefore, it is possible to demonstrate compliance with the dose limit of Technical Specifications, Appendix B, Section 3.4.a for radiciodines, tritium, and particulates with half-lives greater than 8 days by only evaluating the in-fant's thyroid dose due to the release of radiciodines via the milk pathway.
The calculating method to be used includes a conservatism factor of 0.7 which assures that the calculated dose is always greater than or equal to the actual dose despite possible atypical distributions of radio-nuclides in the gaseous affluent. The simplified dose equation reduces to:
Eq.4-28a D ,, = (3.17E-8 (D/Q)s iod nas ir* Sis) / 0.7
, Eq.4-28b D = I D f s=1 fa Rev. No. 7 Page 57 of ODCM
7_ _. _ _ _ _ . . . _
1 l
i I
Where: -
P., = Dose in area to the infant's thyroid due to the release of_radiciodines.via the ailk pathway for the release source of interest..
Dr = Total dose in area to the infant's thyroid -,
due to the release of radiciodines via the 1 milk pathway for all release sources of j interest. -
H -l s = The release source of interest, j m = The number of release sources of interest.
Q,, -= For elevated stack releases, Q,, is the total number of microcuries of nuclides released from the stack during the dose calculation exposure period. For vent releases, Q,, is the total number of j microcuries of nuclide i released from the E four vents during the dose calculation >
period.
D/Q, = The deposition value for a specific location where the, receptor is located in (ad ). For elevated stack releases the D/Q for the stack will be used. For vent releases, the D/Q for the reactor vent will be used.
(b) Approach selection criteria The limited analysis may be used in all cases to demonstrate compliance with the dose limit of Technical specifications, Appendix B, section. 3.4.a (7.5 arem/qtr and 15 aren/yr) for radiciodinate, tritium- ,
and particulates.
However, for the dose' assessment included in the semi-annual Radioactive Effluent Release Report, doses will be evaluated for designated age groups and organs _via designated pathways from radiciodines, tritium, and particulates measured in the gaseous affluents according to sampling e and analyses required by Technical speci-fication.
J Rev. No. 7 Page 58 of ODcM t ay, --- * -
---g - w, ,, - _ -
____i . . _ _ . . . . . . _ . , _ _ . . . , , , , , ,
, 4 .' 5 Dose Projections - Determination of Need to operate Offgas Radwaste-Treatment System 4.5.1- = Requirement ~j Surveillance Requirements 3.6.a of Appendix B to the Technical Specifications requires that doses to gaseous releases from the site be projected at least-monthly if the charcoal beds are not in service when offgas treat-ment system operation is required.
4.5.2 Methodology The rollowing calculation method is provided for deter-mining the projected doses.
PD, = H x D, X 1.2 Eq. 4-29 X
PD, =
H x Da x 1.2 Eq. 4-30 X
PDi , = n x D,i x 1.2 Eq. 4-31 X
Where:
PD, = Projected air dose due to noble gas gamma radi-ation during the current month?(arad) frola all routine affluent pathways PDs = Projected air dose due to noble-gas beta radia-tion during the current month (armd) from all routine affluent pathways PD , = . Projected dose to any organ due to Tritium Iodine-131, Iodine-133 and. particulate with half-lives greater than 8 days (area) 31 = Time period for projection (days)
X .= Number of days to date during sample period used to project the doses 0, = Air dose due to noble gas gamma radiation cor-
-resocnding to the time peried X (urad)
Ds
= Air dose due to noble gas beta radiation cor-responding to the time period X (arad)
-D,i
= organ dose due to Iodines, Tritium and Particu-lates corresponding to the time period X (arem) 1.2 = Conservatism factor to provide a margin for changes in mixture and operational line up, etc.
Rev. No. -. 7 Page 59 of CDCM _
_ _ - ' ' 'WL-'. - - -- 6.---.6i-.i-.6-..i6.J.-- u---...i...u ....si . w s. .i ii .u .- - i s' 6... .... 1. i ..-..i..i* iiila i i . i . .nm .i.im.
A formal dose projeccion would be based on the most
? appropriate results of the monthly calculations of tne
- yamma air ?.ose, the beta air dose, and che organ dose due i to Tritium, Iodinas and particulats greater than a days.
The doses calculated will be divided by the number of g days in the sample period determined to be most ap-propriate for projecting doses. An appLopriate period to
~
base projection on should reflect similar radioactive
~~
release rates effective at the time of the projection.
The per-day doess will be multiplied by 31 days, i.e.,
the time period for projection. The product is the projected dose for the coming 31 day period. Its value ray be adjusted to account for any changes in operating conditicas that could significantly alter the sctual s rolesses, such as failed fuel.
The calculated projected doses, PD,, P4, and PDw will be
- compared to the following Technical specifications, g Appendix B, Section 3.6.b limits
1 0.2 mrad for gamma radiation, f 0.4 mrad for beta radiation, or 0.3 mram to any organ.
i 7 If any doses exceed the above limits, tht, offgas charcoal m beds will be used whenever the operation of the offgas i ;
treatment system is required during the projected time period.
- a. Limited Analysis Approach and Selection Criteria A simpler approach, a linear extrapolation of the most recent threa-month dose for the ccming month, could be 3
used as long as the limits of Technical Specifica-tions, Appendix B, Section 3.6.b are not reached, end that releases of radioactive material have not changes significantly during the tima period used for projec-tion.
I n
V
=
m i
Rev. No. 7 Page 60
[" __ of ODCM
. - - - - - - _ - . --- - - _ - - - - - - - . . - . - . - - - . - ~ - - _- -
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7 2
5.0 ~4 0 CFR 190'0085 EVALUATION J Technical specifications, Appendix B, Sectica 5.1.a requires f .that the annual (calendar year) dose cr dose-commitment to any member of the public from uranium fuel cycle sources be 1 H limited to'525 area to the total body or any organ (except the thyroid which is limited to $75 area). The following epproach should be used to demonstrate compliance with these '
4 dose limits.
5.1 Evaluation Bases Dose evaluation to demonstrate compliance with the 40 CFR -
- 190 dose limits need only be -performed if the quarterly or
. annual doses calculated in stepe 3.4.1, 3.4.2, 4.4.1, and 4.4.2 exceed twice the dose limits of Technical Specifica-l tions, Appendix B, Sections 2.3.a, 3.3.a or 3.4.a~respec--
- tively. . Quarterly doses exceeding 3 area to the total body (liquid releases), 10 area to any organ (liquid releases),
10 mrads equivalent ganna air dose, 20 mrads equivalent beta air dose, or.15 area to the thyroid or any organ from '
radiciodines and particulates (atmospheric releases) and
-annual doses exceeding 6 area to the total body (liquid releases), 20 arem to any organ (liquid releases), 20 mrads ,
equivalent gamma air. dose, 40 mrada equivalent beta air desu, or 30 area to the tnyroid.or any organ from radio-iodines and particulates (atmospheric releases) would-
' require 40 CFR 190 evaluation. The dose evaluation includes dose contributions to a maximally exposed real individual from the calendar quarter in which the. quarterly or annual limits were exceeded in addition to plant offsite dose con- ,,
tributions during the balance of the current calendar year.
For purposes of the evaluation, if required, it may be as--
sumed.that the dose commitment to the maximally exposed real l individual from other uranium fuel cycle sources is neglig-ible. However, dose' contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered.
5.2 Coses From Liquid Releases For the evaluation of doses to real individuals from liquid releases, the same calculating method an employed for Liquid Effluents Annual Dose Assessment will be used. However,
- acre realistic assumptions and any current field data or updated estimates may be uued, if available, concerning the dilution and ingestion of fish and potable water by in-dividuals who live and fish in the area. Also, the results of the Radiological Environaantal Monitoring Program will be included in determining more refined estimates of doses to real individuals by providing data on actual measured levels of plant-related radionuclides in the environment.
Rev. No. 7 Page 61 of __QDgM__
5.0 Doses From Atmospheric Releases
- For the evaluation of doses to real individuals from the at-mospheric releases, the same calculating methods as employed for Gaseous Effluent Annual Dose Assessment will be used except that the gamma and beta air doses are not er.lculated.
Otherwise the same calculating sequence applies. However,
- any current field data or updated estimates may be usad, if available, concerning the actual location of real individu-als, the meteorological conditions, ar A the consumption of food (e.g., milk, meat and vegetation). Data obtained from the latest land use census (Technical Specifications, Appen-dix B, Section 6 2) should be used to determine locations for ovaluating doses. Also, the results of the Radiological Envirenaental Monitoring Program will be included in deter-mining more refined dose estimates to real individuals by providing data on actual measured levels of radioactivity and radiation at 1ccations of interest.
5.4 Doses From Direct Radiation Because 40 CFR 190 requirements include consideration of the offsite dose contribution from direct radiation, an estimate
=
must ta provided in the evaluation. Direct raciation dose
= contribution from turbine shine and from outdoor facilities containing radicactive material, if applicable, maf be esti-mated by shielding calculations or from the results of the environmental annitoring program for direct radiation.
2
=
l Rev. No. 7 .
Page 62 __ of ODCM uns - assamm m
.n
6.0 REFERENCES
6.1 Regulatory Guide 1.109, Rev. 1, October 1977.
6.2 NUREG-0133, October 1978.
6.3 Deleted 6.4 Technical Specifications, Appendix B.
6.5 James A. FitzPatrick Nuclear Power Plant, Docket 50-333, Compliance with 10 CFR 50, Appendix I.
6.6 Final Environmental Impact Statement Related to operation of James A. FitzPatrick Nuclear Power Plant, New York Power Authority, Docket No. 50-333, March 1973.
6.7 Environmental Report, Operating License Stage, James A.
FitzPatrick Plant, New York Power Authority, May 1971.
6.7.1 Supplement Environa' ental Report, Operating License Stage,-
November 1971.
6.7.2 Supplement #2 Environmental Report, Benefit / Cost Analysi-s, May 1972.
6.7.3 Supplement #3 Environmental Report, Answers to Atomic Energy Commission-Questions, August 1982.
6.8 Final Safety Analysis Report,. Tames A. FitzPatrick Plant, New York Power Authority, Docket No. 50-333, operating License No. DPR-59.
s 6.9 New York Power Authority, Internal Memorandum from D.
Dunning to G. Re, September 20, 1988.
Rev. No. 7 . Page 63 of ODCM
L 7.0 ATTACEMENTS
& 7 .' i Appendix A, Liquid Dose Calculation Data 7.2' Appendix B, Gaseous Dose Calculated Data 7.3 Appendix C,. Meteorological-Data 5 7.4 Appendix D, Limited Analysis Dose Assessment for Liquid Ra-dioactive Effluents b
7.5 Appendix E, Technical Bases for Effective Dose Factors 7.6 Appendix F, Effluent Monitor Sampling Locations'and Descrip-tions 7.7 Appendix G, Unrestricted Area Map f 7.8 Appendix H, Environmental Sample Locations 7.9 Appendix I, Summary Tables b
=
Eb
[-
V Rev. No. 2 Page _ 64 of oDcM i
APPENDIX A LIQUID DOSE CALCULATION DATA Jg(E TITLE PAGE A-1 Unrestricted Area MPC's A-3 1
A-2 Dose Factors, Limited Analysis Approach A-4 A-3 Dose Factors, All Remaining Pathways- A-9
-A-4 Dose Factor Derivatio'n A-18 Rev. No. 7 Page A-1 of ODCM
1 T
TABLE A-1 -j MAXIMUM PERMISSIBLE CONCENTRATIONS IN WATER IN UNRESTRICTED AREAS NUCLIDEl : MPC NUCLIDE MPC (Insol.)(uCi/ml)
(So l.) (Insol .)(uCi /ml)(Sol . )
H-3 3 E-3 3 E-3 Ru-103 8 E-5 8 E-5
'Na-24 3 E-5 2 E-4 Ru-105 1 E-4 1 E-4 i P-32 2 E-5 2 E-5 Ru-106 1 E-5 1 E-5 i Cr-51 2 E-3 2 E-3 Ag-110m 3 E-5 3 E-5 ;
Mn-54 1 E-4 1 E-4 Sn-113 8 E-5 9 E-5 L Mn-56 1-E-4 1 E-4 In-113m 1 E-3 1 E-3
. Fe-55 2 E-3 8 E-4 Sb-122 3 E-5 3 E-5 Fe-59 5 E-5 6 E-5 Sb-124 2 E-5 2 E-5 Co-57 4 E-4 5 E-4 Sb-125 1 E-4 1 E-4 .
Co-58 9 E-5 1 E-4 Te-125m 1 E-4 2 E-4 1 Co-60 3 E-5 5 E-5 Te-127m 5 E-5 6 E-5 Ni-65 1 E-4 1 E-4 Te-127 2 E-4 3 E-4 Cu-64 2 E-4 3 E-4 Te-129m 2 E-5 3 E-5 Zn-65 2 E-4 1 E-4 Te-129 8 E-4 8 E-4 Zn-69 2 E-3 2 E-3 Te-131m 4 E-5 6 E-5
-Br-82 4 E-5 3 E-4 Te-131 None None Br-83 3 E-6 3 E-6 Te-132 2 E-5 3 E-5 Br-84 None4 None I-130 3 E-6 3 E-6 Br-85 None None I-131 6 E-5 3 E-7 Rb-86 2 E-5 7 E-5 I-132 2 E-4 8 E-6 Rb-88 None None I-133 4 E-5 1 E-6 i t
Rb-89 'None None I-134 6 E-4 2 E-5 Sr-89 3 E-5 3 E-6 I-135 7 E-5 4 E-6 Sr-90 4 E-5 3 E-7 Cs-134 4 E-5 9 E-6 Sr-91 5 E-5 7 E-5 Cs-136 6 E-5 9 E-5 Sr-92 6 E-5 7 E-5 Cs-137 4 E-5 2 E-5 Y-90 2 E-5 2 E-5 Cs-138 None None Y-91m 3 E-3 3 E-3 Ba-139 None None Y 3 E-5 3 E-5 Ba-140 2 E-5 3 E-5 '
Y-92 6 E-5 6 E-5 Ba-141 None None.
Y-93 3 E-5 3 E-5 Ba-142 None None Zr-95 6 E-5 6 E-5 La-140 2 E-5 2 E-5 Zr-97 2 E-5 2 E-5 La-142 None None Nb-95 1 E-4 1 E-4 Ce-141 9 E-5 9 E-5 Nb-97 9 E-4 9 E-4 Ce-143 4 E-5 4 E-5 Mo-99 4 E-5 2 E-4 Ce-144 1 E-5 1 E-5 Tc-99m 3 E-3 6'E-3 Pr-144 None None '
Tc-101 None None W-187 6 E-5 7 E-5 Np-239 1 E-4 1 E-4 (1) If a nuclide is not listed, refer to 10 CFR 20, Appendix B, and use the most conservative insoluble / soluble MPC where they are given in Table II, Column 2. All MPC values are taken from 10 CFR 20, Revised as of January 1, 1984.
(2) None - Appendix B) No MPC limit for any single r(As per 10 CFR 20,adionuclide not listed above with decay mode oth alpha emission or spontaneous fission and with radioactive half-life of less than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
Rev. No. 7 Page _&-1 of ODCM
t ' i,
. TABLE A-2
. DOSE CONVERSION' FACTORS FOR LIQUID DISCHARGES Limited Analysis Approach A P_AJE Freshwater Fish' (Aitf)'- Adult A-5 0 Potable Water (Aitw) - Adult A-6 Freshwater Fish (Aitf) Teenager- A-7 1
Potable Water (Aitw). - Teenager A ..
s 9
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Aitsh VALUES - LAKE SHORELINE DEPOSITS - TEENAGER z .
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" KIDNEY LUNG GI-LLI SKIN T. 800Y NUCLIDE BONE LIVER THYROID 1
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6.31E 00 6.31E 00 6.31E 00- 6.31E 00 6.31E 00 6.31E 00 7.39E 00 6.31E'00 Co-58 3.58E 02 4.21E 02 3.58E 02 Co-60 3.58E 02 3.58E 02 3.58E 02 3.58E 02- 3.58E 02 Cu-64 1.01E-02 1.01E-02 1.01E-02 1.01E-02 1.01E-02 1.01E-02 1.14E-02 1.01E-02 ;
Zn-65 1.24E 01 1.24E 01 1.24E 01 1.24E 01 1.24E 01 1.24E 01 1.43E 01 1.24E 01 i Sr-89 3.61E-04 3.61E-04 3.61E-04 3.61E-04 3.61E-04 3.61E-04 4.18E-04 3.61E-04 0 0 0 . 0 0 0 0 0 Sr-90 2.28E 00 2.28E 00 2.68E 00 2.28E 00 Mb-95 2.28E 00 2.28E 00 2.28E 00 2.28E 00 4.07E 00 4.07E 00 4.07E 00 4.07E 00 4.07E 00 4.07E 00 4.72E 00 4.07E 00 l Zr-95 6.38E-02 6.38E-02 2.21E 00 6.38E-02 i As-76 6.38E-02 6.38E-02 6.38E-02 6.38E-02 '
Nb-95m 3.27E-02 3.27E-02 3.27E-02 3.27E-02 3.27E-02 3.27E-02 2.05E 01- 3.27E-02 Zr-97 4.90E-02 4.90E-02 4.90E-02 4.90E-02 4.90E-02 4.90E-02 5.70E-02 4.90E-02 ,
Mo-99 6.65E-02 6.65E-02 6.65E-02 6.65E-02 6.65E-02 6.65E-02 7.70E-02 6.65E-02 Tc-99m 3.05E-03 3.05E-03 3.05E-03 3.05E-03 3.05E-03 3.05E 3.50E-03' 3.05E-03 Ag-110m 5.73E 01 5.73E 01 5.73E 01 5.73E 01 5.73E 01 5.73E 01 6.68E Ol' 5.73E 01 U Sb-124 9.96E 00 9.96E 00 9.96E 00 9.96E 00 9.96E 00 9.96E 00 1.15E 01 9.96E 00 2.87E-01 2.87E-01 2.87 E-01: 2.87E-01 2.87E-01 2.87E-01 3.48E-01 2.87E-01
$ I-131 4.09E-02 4.98E-02 4.09E-02 1-133 4.09E-02 4.09E-02 4.09E-02 4.09E-02 4.09E-02 1 4.28E-02 4.28E-02 4.28E-02 4.28E-02 _4.28E-02 4.28E '4.99E-02 4.28E-02 ,
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La-140 3.24E-01 3.24E-01 3.24E-01 3.24E-01 3.24E-01 3.24E-01 3.67E-01 3.24E-01 S 2.28E-01 2.28E-01 2.56E-01 2.28E-01 Ce-141 2.28E-01 2.28E-01 2.28E-01 -2.28E-01 ,
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1 TABLE A-4 DERIVATION OF LIQUID DOSE FACTOR $
.Tabl e PJLSA A-4.1' Dose Factor (Ait) Derivation A 19 l A-4.2 Parameters for the Liquid Effluent Pathway A-23 f
'A-4.3 Justification for Liquid Pathways Used to. A-25 '
Assess Dose to Man i
i J
Rev. No. 7 Page A-18 of ODOM 6
x TABLE A-4.1 7 LIQUID DOSE FACTOR (Ait) DERIVATION various receptor age groupsFor purposes of calculating the dose cont used for each radionuclide I.a composite dose factor, Ait may be the sum- of the freshwater fish, AThe composite dose factor,,Ait, is
[ shoreline deposits pathway, Ai h,it1, pathway transfer parameters potable water, Ait and cose factors.
Ait em5'odies pathway usage factors, organ . !) . , bioaccumulation factors),
- cose conversion factors dilution factors between the release point and assumed
. exposure pathway. pointand of
.The composite dose factor may be expressed as:
Ait " (Xo (Uw/Dw) + Ko Uf 8Fi /Df )DFj + (Ko Z W Tj Ush/Dch) (1-e
)DEj it Where:
Ait = is the composite dose parameter for the total body or organ an age gr 2 af for mrem/hr per uCi/ml.radionuclide,for all i,
appropriate pathways, oup
- =
g Ko is a unit conversion factor,1.14E5 yr-pCi-m1 per uCi-br-1 (NUREG-0133).
L 'Uw =
= water consumotion rate for age group of interest (Table A-4.2).
I i hgag, ish consumption rate for age group of interest 6 Ush =
duration of time an individual is located on the beach (Table A-4.2).
E Dw
=
L m_
of rble&3e A-4.2), to the nearest potable rwater intake (Table Df
' =- dilution factor which refIects the dilution from the po fish catch (Table A-4.2).
" Dsh =
dilution factor which reflects the dilution from the point L_ of release deposit to the (Table nearest point assumed for shoreline A-4.2).
E 7 BFj =
bioaccumulation fish factor for r&dionuclide i, in freshwater 1.106.pCi/kg per pCi/1, from Table A-1 of Regulatory Guide E
b Rev'. No. 7 Page A-19 of ODCM
=
W dtX
'1 TABLE A-4.1 (CoNU NUED)
LIQUID DOSE FACTOR (Ait) DERIVATION
= is the radiological half-life of radionuclide,. i, in' days.
Ti Ai = is t sec-ge-radiologicaldecayconstantforradionuclide,1,in
=
W = is the shoreline width factor (Table A-4.2).
- Tb
= 'the period of time for which sediment-or soil is exposed to the contaminated water (Table A-4.2).
Kc
= assumed transfer constant from water to sediment, .in liters /kg per hr as defined in Z.
MS = mass of' sediment, in,kg/m2 of surface as defined in Z.
Z = Kc x Ms x (24/.693), in 1 per m2-day (Table A-4.2).
d DFj = dose conversion factor for radionuclide, i, for organ and
- age group of interest. Used to calculate the- radiation i dose from an intake of a radionuclide, mrem /pCi
- (Regulatory Guide 1.109, Tables E-11 to E-14).
DEj = dose conversion factor for radionuclide, i, for organ and age group' of interest. Used to calculate the radiation-
- dose-fro an external- exposure of a radionuclide, mrem /hr-a per pCi/m (Regulatory. Guide 1.109, Table _ E-6) .
- Examole Calculation
1 1. Potable Water The pota'ule water pathway dose-factor, Aitw, is calculated from Equation A-4.1 by setting- the usage. factors for
- freshwater fish and shoreline deposits equal .to zero.
- Equation A-4.1 reduces to the following
Aitw = Ko (Uw/Dw) DF1 the total body dose factor for an adult due to For Co-60, ion of potable water is:
the ingest 3
DFi = 4.72E-06 mrem /pCi Uw = 730 liters /yr Ow = 165 Rev. No. 7 Page A-2o of ODCM
~
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1
-TABLE A-4,1 (CONTINUED)
LIQUID DOSE FACTOR (Ait) DERIVATION Ko = 1.14E5 yr-pCi-ml per uCi-br-1 These values yield an At i factor of 2.38 mrem /hr per uCi/mi'as listed in Table AU of this appendix, l
- 11. freshwater Fish The freshwater fish pathway dose factor, A i tf, is calculated from Equation A-4.1 by setting the usage factors for potable water' and shoreline deposits equal to zero.
Equation A-4.1 reduces to tne following:
Aitf " Ko (Uf BFj/D f) 0Fi
' ' For the Co-60, ingest ion of freshwater fish is:the total body dose factor for an adult due to OFi = 4.72E-06 mrem /pci Uf = 21 kg/yr Df = 12 BFi = 50 pCi/kg.per pCi/1-Ko .= 1.14E5 yr-pCi-ml per uCi-hr-1 These values yield an Aitf factor of 47.1 mrem /hr per uCi/ml as listed in Table A-2 of this appendix.
III. Lake Shoreline Deoosits The ' shoreline deposits pathway dose factor, Ait h iS calculated from Equation A-4.1 settint the usage fac, tors for otable water and freshw ter fisn equal to zero.
Equat on A-4.1 reduces to the following:
c Aitsh " (Ko Z W Tj Ush/Dsh) (1-e ) DEj the total body dose factor for an adult from For Co-60, deposits is:
shoreline Ush = 12 hrs /yr Dsh = 18 Rev. No. 7 Page A-21 of oDCM
s,-.
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)
TABLE A-4.1 (CONTINUED) r LIQUID DOSE' FACTOR (Ai t) DERIVATION W = 0.30 Ti a 1.92E3 days Tb = 15 years or 4.73E8 see Ko = 1.14E5 yr-pCi-mi per uCi-br-1 .]
Z = 100 1 per m2-day !
Ai = 4.2E-9 see-1 i
DEj = Table E-6)1.70E-8 mrem /hr per pCi/m2 (Regulatory Guid' These values will yield and Aitch factor of 64.2 mrem /hr per uCi/mi as listed in Table A-3 of Ws appendix.
i i
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Rev. No. 7 Page A-22 of ODCM 4
~ , , _ _, , ,. ,,_y
TABLE A-4.2 PARAMETER FOR THE LIQUID EFFLUENT PATHWAY PARAMETER VALUE _ REFERENCE TABLE l
I Uw (liters /yr)-Potable Water / l
- infant 330 R.G. 1.109 E-5 i
- child 510 R.G. 1.109 E-5 1
- teen 510 R.G. 1.109 E-5
- adult 730 R.G. 1.109 E-5 .
I Uf (kg/yr)-Freshwater Fish /
- infant 0 R.G. 1.109 E-5 1
- child 6.9 R.G. 1.109 E-5 )
- teen 16 R.G. 1.109 E-5
- adult 21 R.G. 1.109 E-5 Ush (hr/yr)-Lake Shoreline Deposits /
- infant G R.G. 1,109 E-5
- child 14 R.G. 1.109 E-5 -
- teen 67 R.G. 1.109 E-5
- adult 12 R.G. 1.109 E-5 :
BFj (pCi/kg per pCi/1)- Each R.G. 1.109 A-1 Freshwater Fish Radionuclide Dw 165 Site Specific W(dimensionless)-Potable ater (JAF FSAR Fig.16.1-19)
Df (dimensionless)-Freshwater 12 Site Specific Fich (JAF FSAR Fig.16.1-19)
Dsh Shoreline (dimensionless)-Lake 18 Site Spe:ific Deposits (JAFFSARFig.16.1-19)
DFj - Potable Water / Freshwater Each R.G. 1.109 E-11 to Fish (mrem /pCi) Radionuclide E-14 DEj-LakeShorelineDep0 Each R.G. 1.109 E-6 (mrem /hr per pCi/m sits Radionuclide Rev. No, 7 Page _A-2,1 of ODCM
- . , - , , + - . , . _ , . , . . . - - - . - - , - . . . . . . ,
l TABLE A-4.2 (Comnwuro) l PARAMETER FOR THE LIQUID EFFLUENT PATHWAY l PARAMETER VALUE . REFEREEE TABLE Z (1 per m2-d&y Lake 100 R.G. 1.109 pg 1.109-14 Shoreline Depo) sits j
W (dimensionless Lake 0.3 R.G. 1.109 A-2 Shoreline Depos)its Tb Isec Lake Shoreline 4.73E8 R.G. 1.109 E-15 6epos)its .
- l Transit Time (hours)- 31 Site Specific Potable Water (Based on a current I
speed of 0.4 ft./sec 1 JAF FSAR Fig.16.1-19)
- Site Spectfic 0 ,
Transit Freshwater Time Fis (hhours)- (JAF FSAR Fig.16.1-19) :
Consumption >
Transit Time (hours)- 2.9 Site Specific Lake Shoreline Deposits (JAF FSAR Fig.16.1-19) l
- Location of maximally exposed individual for potable water is l Oswego 8.5 miles west of JAF discharge. Location of maximally exposed individual for freshwater fish consumption ,
is the JAF discharge vicinity. Location of maximally exposed individual for lake shoreline ceposits is Sunset Bay, 0.8 ,
miles east of JAF discharge.
i a
Rev. No. 7 Page A-24 of ODCM
-, .--v . - - - . . ~ . . _ . _ ~ . _ _ _ _ , . _ _ _
L TABLE A-4.3 ,
JUSTIFICATION FOR LIQUID PATHWAYS USED TO ASSESS DOSE TO MAN PATHWAY JUSTIFICATION FOR ONJ5510N OR INCLUSION
- 1. POTABLE WATER This pathway is considered for all required analysis.
- 2. FRESHWATER FISH This pathway is considered for all -
required analysis.
- 3. FRESHWATER SHELL This pathway was not considered for the annual dose calculations and the '
40CFR190 dose analysis. Reference .
6.1.9 states that direct incestion of aquatic invertebrates from Lake Ontario :
is not a common practice. '
- 4. FRESHWATER PLANTS No known pathway exists for the J. A.
FitzPatrick plant ard none is included in the dose analysis of References 6.5 through 6.8. Regulator
- Appendix E, Section 2, ypage Guide 1.109, 1.109-36, states " Ingestion of aquatic material is not normally assumed." plant S. SALTWATER FISH Not applicable to a freshwater site.
- 6. SALTWATER SHELL Not applicable to a freshwater site.
FISH
~
- 7. SALTWATER PLANTS Not applicable to a freshwater site.
- 8. DISCHARGE CANAL This pathway is not applicable since SH0 RELINE the J. A. FitzPatrick Plant discharges through a tunnel to a diffuser offshore, 9, RIVER SHORELINE Not applicable to a Great Lake site.
DEPOSITS
- 10. LAKE SHORELINE This pathway is not necessary to DEPOSITS demonstrate compliance with 10CFR20 and 10CFR50 as specified in Sections 4.2, and 4.3.1 of NUREG-0133. This pathway is considered for the annual dose the 40CFR190 dose cal cul aand analysis, ti ons $ection 3.4.2.b (1) .
- 11. OCEAN SHORELINE Not applicable to a Great Lake Site.
DEPOSITS P
Rev. No. 7 Page A-25 of ODCM
o ,
i TABLE A-4.3 (ConTrnute) :
JUSTIFICATION FOR LIQUID PATRWAYS USED TO ASSES 5 DOSE TO MAN i PATHWAY JUSTIE1 CATION _FOREISSI0lLOR INCLUSION t
- 12. TIDAL BASIN Not applicable to a Great Lake site.
DEPOSITS
- 13. SWIMMING This pathway is not necescary to i demonstrate compliance with 10CFR20 and r 10CFR50 as specified in Sections 4.2, and 4.3.1 of NUREG-0133. This pathway .
is not used in the ODCM since its dose contribution is very small (Appendix D, '
Table D-8),
- 14. BOATING This pathway is not necessary to demnnstrate compliance with 10CFR20 and
~
10CFR50 as specified in - Sections 4.2, and 4.3.1 of NUREG-0133. This pathway is not used in the ODCM since its dose .
contribution is ver small (See ;
Appendix D, Table D-8). y
- 15. STORED FRUITS There are two possible methods of AND VEGETABLES establishing this by using water from the lake for irr pathway
- igation or using well water for irrigation, which may have become contaminated through discharges to the lake. References 6.6 and 6.7 document that a limited '
irrigation pathway exists; however, Reference 6.5 states that recent surveys indicate that the irrigation I pathways discussed in the other l documents ro longer use lake water for .
irrigation. Since Reference 6.5 is the most recent document it is :
l- concluded tht.t the irrigation pathway does not exist and need not be considered in any dose analysis, l References 6.5 through 6.8 state that the possibility of groundwater '
contamination is extremely remote and no impact on groundwater is expected.
- 16. FRESH FRUITS This pathway need not be considered.
AND VEGETABLES See justification for pathway 15.
- 17. MEAT (CONTAMI- This pathway need not be ccasidered.
NATED FORAGE) See justification for pathway 15.
Rev . No . __L. Page A-26 of oCCM
l l
t TABLE A-4.3 (CONTINUED) l JUSTIFICATION FOR LIQUID PATHWAYS USED TO ASSESS DOSE TO MAN PATHWAY JUSTIFICATION FOR OMISSION OR. INCLUSION
- 18. MEAT (CONTAMI- This pathway need not be considered.
NATED FEEO) See Justification for pathway 15. *
- 19. CONTAMI- This pathway is not necessary to MEAT NATED (WATER) demonstrate compliance with 10CFP.20 and 10CFR50 as specified in Section 4.2 and i, 4.3.1 of NUREG-0133. The dose calculations shown in References 6.5 through 6.8 do not consider this ,
pathway as a part of the- analysis; :
hence, it is concluded that this '
pathway is insignificant and need not be considered for annual and 40CFR190 dose calculations.
- 20. COWS MIt.K This pathway need not be considered.
(CONTAMINATED See justification for pathway 15. '
FORAGE)
- 21. COWS MILK This pathway need not be considered. 1 (CONTAMINATED See justification for pathway 15.
FEED)
- 22. COWS MILK This pathway need not be considered.
l (CONTAMINATED Vee justification for pathway 19.
WATER)
- 23. GOATS MILK This pathway need not be considered. ,
(CONTAMINATED See justification for pathway 15. i FORAGE)
- 24. GOATS MILK This pathway need not be considered.
(CONTAMINATED See justification for pathway 15.
l FEED)
- 25. GOATS MILK This pathway need not be considered. l (CONTAMINATED See justification for pathway 19. 1 WATER) j Rev. No. 7 Page A-27 of ODCM
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I APPENDIX B GASE0US DOSE CALCULATION CATA l
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APPENDIX B GASEOUS DO5E CALCULATIUN DATA TABLE TITLE P_&gg B-1 Unrestricted Area MPC's B-3 B-2 Noble Gas Data Transfer Factors (K i , Lj) B-4 B-3 Air Dose Transfer F6ctors (Mi , Nj) B-5 B-4 Inhalation Environmental Pathway Dose B-6 Conversion Factors (Pj) - Instantaneous B-5 Child Limited Analysis Approach - Gaseous B-7 Discharge Environmental Pathway Dose Conversion Factors (Rj)
B-6 Environmental Pathway Dose Conversion B-9 Factors (R1) for All Remaining Pathways B-7 Derivation of Gaseous Dose Factors B-31 Rev, No. 7 Page _B-2 of ODCM
I i
TABLE B-1 MAXIMM PERMISSIBLE CONCENTRATIONS IN AIR IN UNRESTRICTED AREA NUCLIDEI MPC ucr/cc NUCLIDEI WC uCx/cc Ar-41 4 E-8 Y-91 1 E-9 3 E-8 Zr-95 1 E-9 Kr-83m Kr-85m 1 E-7 Nb-95 3 E-9 Kr-85 3 E-7 Ru-103 3 E-9 Kr-87 2 E-8 Ru-106 2 E-10 Kr-88 2 E-8 Ag-110m 3 E-10 Kr-89 3 E-8 Sn-113 2 E-9 Kr-90 3 E-8 In-113m 2 E-7 Xe-131m 4 E-7 . Sn-123 1 E-10 Xe-133m 3 E-7 Sn-126 1 E-10 Xe-133 3 E-7 Sb-124 7 E-10 Xe-135m 3 E-8 Sb-125 9 E-10 Xe-135 1 E-7 Te-125m 4 E-9 Xe-137 3 E-8 Te-127m 1 E-9 i Xe-138 3 E-8 Te-129m 1 E-9 H-3 2 E-7 I-130 1 E-10 P-32 2 E-9 I-131 1 E-10 Cr-51 8 E-8 I-132 3 E-9 Mn-54 1 E-9 I-133 4 E-10 Fe-59 2 E-9 I-134 6 E-9 Co-57 6 E-9 I-135 1 E-9 i Co-58 2 E-9 Cs-134 4 E-10 Co-60 3 E-10 Cs-136 6 E-9 Zn-65 2 E-9 Cs-137 5 E-10 Rb-86 2 E-9 Ba-140 1 E-9 Sr-89 3 E-10 La-140 4 E-9 Sr-90 3 E-11 Ce-141 5 E-9 Rb-88 3 E-8 Ce-144 2 E-10
,mummmmmmmmmmmmmmme .
(1) Appendix If B, a and nuclide is not listed, refer use the most conservative insoluble /soto 10 CFR 20,luble MPC where they are given in Table II, Column 1.
Ref. 10 CFR Part 20, Appendix 8, Table II, Column 1.
Fn%Th _2_ POgn _B-1 Gf ODCM ..
TABLE B-2 TRANSFER FACTORS FOR MAXIMUM DOSE TO A PERSON 0FFSITE DUE TO RADI0 ACTIVE N0BLE GASES 1
Dose Transfer Factors Y
i GAMA B ETA GAW4A + BE"A Ki .i (L + 1.1 M?i RADIONUCLIDE are are arm uCi sec/m3 uCi sec/m3 uCi sec/m3 Kr-83m 2,4E-9 --
6.7E-7 Kr-85m 3.7E-5 4.6E-5 8.9E-5 Kr-85 5,1E-7 4.2E-5 4.3E-5 Kr-87 1.9E-4 3.1E-4 5.3E-4 Kr-88 4.7E-4 7,5E-5 6.0E-4 '
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o j TABER B-6 (Contimased) fh mi VAIBES -- VBGETATION - TERMAGER lE m2 ,,,,f,,
pci/sec h l M ISE BW LIWR INTMIS KIM LIMi GI-tLI SKIN T. 80Dr N-3*. 0 2.59E 03 2.59E 03 2.59E 03 2.59E 03 2.59E 03 0 2.59E 03 Cr-51 0 0 3.42E 04 1.35E 04 8.79E 04 1.03E 07 0 6.16E 04 !
Mn-54 0 4.54E 08 0 1.36E 08 0 9.32E 08 0 9.01E 07 Fe-55 3.26E 08 2.31E 08 0 0 1.47E 08 1.00E 08 0 5.39E 07 Fe-59 1.79E 08 4.18E 08 0 0 1.32E 08 9.89E 08 0 1.61E 08 Co-57 0 1.79E 07 0 0 0 3.34E 08 0 3.00E 07 Co-58 0 4.37E 07 0 0 0 6.02E 08 0 1.01E 08 Co-60 0 2.49E 08 0 0 0 3.24E 09 0 5.60E 08 i Zn-65 4.24E 08 1.47E 09 0 9.41E 08 0 6.23E 08 0 6.86E 08 Sr-89 1.51E 10 0 0 0 0 1.80E 09 0 4.33E 08 Sr-90 7.51E 11 0 0 0 0 2.llE 10 0 1.85E 11 Zr-95 1.72E 06 5.44E 05 0 7.99E 05 0 1.26E 09 0 3.74E 05 Nb-95 1.92E 05 1.07E 05 0 1.03E 05 0 4.56E 08 0 5.86E 04 No-99 0 5.64E 06 0 1.29E 07 0 1.01E 07 0 1.08E 06 Ag-110m 1.52E 07 1.44E 07 0 2.74E 07 0 4.03E 09 0 8.73E 06 :
Sb-124 i 1.55E 08 2.85E 06 3.51E 05 0 3.35E 08 3.12E 09 0 6.03E 07 1-131 7.68E 07 1.08E 08 3.14E 10 1.85E 08 0 2.13E 07 0 5.78E 07 g 1-133 1.95E 06 3.32E 06 4.63E 08 5.81E 06 0 2.51E 06 0 1.01E 06 !
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? Cs-137 1.01E 10 1.35E 10 0 4.59E 09 1.78E 09 1.92E 08 0 4.69E 09
- Sa-140 1.38E 08 1.69E 05 0 5.74E 04 1.14E 05 2.13E 08
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TABLE B-6 (CONnNUED) g
? Ri VALUES -- COW MEAT - CHILO f 32-ares /vr uCi/sec-a NUCLIDE 80ME v QWER TNVRDIS KIDNEY LUNG GI-LLI SKIN T. 800[ I H-3* 0 2.33E 02 2.33E 02 2.33E 02 2.33E 02 2.33E 02 0 2.33E 02 Cr-51 0 0- 2.53E 03 6.90E 02 4.61E 03 2.41E 05 0 4.55E 03- '
Mn-54 0 5.15E 06 0 1.44E 06 0 4.32E 06 0 1.37E 06' Fe-55 3.04E 08 1.61E 08 0 0 9.llE 07 2.98E 07 0 4.99E 07 Fe-59 2.04E 08 3.30E 08 0 0 9.58E 07 3.44E 08 0 1.65E 08 i Co-57 0 3.78E-06 0 0 .0 3.10E 07 0 7.66E.06 Co-58 0 9.41E 06 '
0 0 0 5.49E 07 0 2.88E 07 Co-60 0 4.64E 07 '
O O 0 2.57E 08 0- 1.37E 08 -
Zn-65 2.39E 08 6.35E 08 0 4.00E 08 0 1.12E 08 0 3.95E 08 Sr-89 2.65E 08 0 0 0 0 1.03E 07 0 7.57E 06 -
Sr-90 7.01E 09 0. 0 0 0 9.44E 07 0 1.78E 09 Zr-95 1.51E 06 3.32E 05 0 4.75E 05 0 3.46E 08 0 2.95E 05 Mb-95 1.64E 06 6.38E 05 0 6.00E 05 0 1.18E 09 0- 4.56E 05 No-99 0 5.71E 04- 0 1.22E 05 0 4.72E 04 0 1.41E-04 4.29E 08 2.88E 06 Ag-110m 5.34E 06 3.61E 06 0 6.72E 06- 0 0 Sb-124 1.65E 07 2.13E 05 3.63E 04 0 9.13E 06 1.03E 08 0 5.77E 06 1-131 8.27E 05 8.32E 06 2.75E 09 1.37E 07 0 7.41E 05 0 4.73E 06 1-133 3.09E-01 3.82E-01 7.10E 01 6.37E-01 0 1.54E-01 0 1.45E-01 1-135 3.43E-17 6.17E-17' 5.46E-15 9.46E-17 0 4.70E-17 0 2.92E-17 Cs-134 6.10E 08 1.00E 09 0 3.10E 08 1.IIE 08 5.39E 06 0 2.llE 08 7.85E 05 1.45E 07 Cs-136 8.12E 06 2.23E 07 0 1.19E 07 1.77E 06 0 Cs-137 8.99E 08 8.60E 08 0 2.80E 08 1.01E 08 5.39E 06 0 1.27E 08 8a-140 2.20E 07 1.93E 04 0 6.27E 03 1.15E 04 1.11E 07 0 1.28E 06
.- 3.34E-03 e- La-140 2.83E-02 9.90E-03 0 0 0 2.76E 02 0 Ce-141 1.17E 04 5.82E 03 0 2.55E 03 0 7.25E 06. 0 8.64E 02 Ce-144 'I.48E 06 4.65E 05 0 2.57E 05 0 1.21E 08- 0 '7.92E 04 1
- ares /vr oCi/m3
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p r . TABLE B-6 (Courrusso)
Ri VALUES --COW MILK - CHILD 4'
E2 -arem/vr uCi/sec l
NUCLIDE SONE LNER TNYROID KIONEY LUNG GI-U I '
SKIN T. BODY H-3* O' 't.57E 03 1.57E 93 ' .l.57E 03 .l.57E 03 .l.57Ef03 0 1.57E'03 Cr-51 0 0 2.93E 04 8.00E 03 .5.34E 04 2.80E 06 0. 5.27E 04 - '
Mn-54 0 1.35E 07 0 3.78E 06 0 1.13E 07 0 '3.59E 06 Fe-55 7.43E 07 3.94E 07 0 0 2.23E 07 7:30E 06 0 1.22E 07 Fe-59 6.53E 07 1.06E 08 0 0 3.06E 07 1;IDE 08 0 5.26E 07 Co-57 0 2.45E'06 0 0 0 2.01E 07 0 4.96E 06 Co-58 0 6.95E'06. 0 0 0 4.05E 07 0 2.13E 07 Co-60 1 0 2.89E 07 ~0 0 0 1.60E 08 0 8.52E-07 Zn-65 2.63E 09 7.00E 09 0 4.41E 09 0 1.23E 09 0 4.35E 09 Sr-89 3.64E 09 0 0 0 0 1.41E 08 0 1.04E 08- '
Sr-90 7.53E 10 0 0 0 0 1.01E 09 -0 -1.91E 10 Zr-95 2.17E 03 '4.77E 02 0 6.83E 02 0 4.98E 05 0 4.25E'02 !
I Nb-95 1.68E 05 6.55E 04 0 '6.15E 04 0 1.21E 08 0 4.68E 04 t Mo-99 0 4.06E 07 0 8.67E 07 0 3.36E 07 0 1.00E 07 :
Ag-110m 1.33E 08 8.98E 07 . 0 1.67E 08- 0 1.07E 10 0 7.18E 07 Sh-124 6.11E 07 7.92E 05 1.35E 05 0 3.39E 07 3.82E 08 0 .2.14E 07-I-131 6.52E 08 6.55E 08 2.17E 11. 1.08E 09 0 5.83E 07 0 3.72E 08-1-133 8.70E 06 1.08E 07. 2.00E 09 1.79E 07 0 4.33E 06 0 4.07E 06 2.72E 04 4.89E 04 1-135 4;33E 06 7.49E 04 .0 3.72E 04 0 2.31E 04
/ Cs-134 1.50E 10 2.46E 10 0 7.61E 09 2.73E 09 1.32E 08 0- 5.18E 09 ;
Cs-136 5.07E 08 1.39E 09 0 7.42E 08 1.11E 08. 4.90E 07 0 9.02E 08 '
Cs-137 2.17E 10 2.08E 10 0 6.78E 09 2.44E 09 1.30E 08 -
0 3.07E 09
- 5.87E 07 5.15E 04
~
Ba-140 0 1.68E 04 3.07E 04 2.98E 07 0 3.43E 06 i La-140 9.73E 00 3.40E 00 0 0 0 9.48E 04 0 1.15E 00 1 Ce-141 1.15E 04 5.73E 03 0 .2.51E 03- 0 7.15E 06 0 8.51E 02 i Ce-144 1.04E 06 3.26E 05 0 1.80E 05 0 8.50E 07 0 5.55E 04 l
- mrem /vr uCi/m3 i
i
~ -
^
v
~
' TABLE B-6 iCourneuro) -
Ri VALUES - GGAT MILK - CHILD h 2g g
uCi/sec WCLIOE -
00K LIVE INVRDID .KIONE7 l uME GI-LLI --
SKIN T. BODY -
H-3* O 3.20E 03 3.20E 03 3.20E 03 3.20E 03 3.20E 03 0 3.20E-03 Cr-51 0 0 3.51E 03' 9.60E 02 6.41E 03 3.36E~05 0- , 6.33E -
Mn-54 0 1.62E 06 0 4.54E 05 0 1.36E 06 0 ' 4.31E 05 l A Fe-55 9.65E 05 5.12E 05 0 0 2.90E 05 9.49E 04 G 1.59E 05 Fe-59 8.48E 05 1.37E 06 0 0 3.98E 05 1.43E 06 0 6.84E 05 Co-57 0 2.94E 05 0 0 0 2.41E 06 0 5.96E 05 l* l Co-58 0' 8.34E 05 0 0 0 4.86E 06 0 2.55E 06 l Co-60 0 3.47E 06 0 0 0 .l.92E 07 0 1,02E 07 "
Zn-65 3.15E 08 8.40E 08 0 5.29E 08 0 1.47E 08 0 5.22E 08 Sr-89 7.65E 09 0 0 0 0 2.96E 08 0 2.19E 08 i Sr-90 1.58E 11 0 0 0 0 2.13E 09 0 4.01E 10 Zr-95 2.60E 02 5.73E 01 0 8.20E 01 0 5.97E 04 0 5.10E 01 Mb-95 2.02E 04 7.86E 03 0 7.39E 03 0 1.45E 07 0 :5.62E 03 Mo-99 0 4.87E 06 0 1.04E 07 0 4.03E 06 0 1.21E 06 Ag-110m 1.59E 07 1.08E 07 0 2.01E 07 0 1.28E 09 0 8.61E 06 .
Sb-124 7.33E 06 9.15E 04 1.62E 04 0 4.07E 06 .4.58E 07 0~ 2.57E 06
~
l-131 7.82E 08 7.86E'08 2.60E 11 1.29E 09 0- 7.00E 07 - 0 4.47E 08
- I-133 1.04E 07 1.29E 07. 2.40E 09 2.15E 07 0 5.20E 06~ 0 4.88E 06 i
I-135 3.26E 04' 5.87E 04 5.19E 06 8.99E 04 0 4.47E 04 0 2.77E 04 i Cs-134 4.49E 10 7.37E 10 0 2.28E 10 8.19E 09 3.97E 08 0 1.55E'10 1 Cs-136 1.52E 09 4.18E 09 0 2.23E 09 3.32E 08 1.47E 08 0 2.71E 09 't Cs-137 6.52E 10 .6.24E~10 0 2.03E.10 7.32E 09 3.91E 08 0 9.21E 09 1
. 8a-140 -7.05E 06 6.17E 03 0 2.01E 03 3.68E 03 3.57E 06 0 4.llE 05 La-140 1.17E 00 4.08E-01 0 0 '0 1.14E 04 0 1.38E-01 Ce-141 1.38E 03 6.88E 02 0 3.02E 02 0 8.58E 05 0 1.02E.02
, Ce-144 1.25E 05 3.91E 04- 0 2.17E 04 - 0 1.02E 07 0 6.66E 03
~
~
l
- mres/vr i
uCi/m3
_m.. . . _ _ . . _ _ . . . - . . _ _ - _ _ _ _ . - _-..,__ _ .,.l. _ _ _ . . _ . . . _ _ . . _ _
_ 1 ._ _ , , _, . , . . -_ _ _ _ , _ _ _ _ _ _ _ .m x ,,
9 g TA8LE 8-6 (Com1rsmuto)
Ri VALUES - GROUND PLANE - INFANT f 32-area /vr.
uC1Isec e
IWCLIDE BONE 4.85ER TNVRDID KIDNEY Lime GI-LLI- SKIN T. B00Y l H-3 0 0 0~ 0 0 0 0 0 Cr-51 -4.65E 06 4 36 4.65E 06 4.65E 06 4.65E 06 4.65E 06 5.50E 06 .4.65E 06 Mn-54 1.38E 09 1...m 69 1.38E 09 1.38E 09 1.38E 09 1.38E 09 1.62E 09 1.38E 09 Fe-55 0 -0 0 0 0 0 0 0 Fe-59 2.73E 08 2.73E 08 2.73E 08 2.73E 08 2.73E 08- 2.73E 08- 3.20E 08- 2.73E 08 Co-57 1.88E 08 1.88E 08 1.88E 08 1.88E 08 1.88E 08 1.88E 08 2.07E 08 1.88E 08 Co-58 3.80E 08 3.80E 08 3.80E 08 3.80E 08 3.80E 08 3.80E 08 4.45E 08 3.80E 08 Co-60 2.15E 10 2.15E 10 2.15E 10 2.15E 10 2.15E 10 2.15E 10 2.53E 10 2.15E 10 Zn-65 7.46E 08 7.46E 08 7.46E 08 7.46E 08 7.46E 08 7.46E 08 8.57E 08 7.46E 08 Sr-89 2.16E 04 2.16E 04 2.16E 04 2.16E 04 2.16E 04 2.16E 04 2.51E 04 2.16E 04 Sr-90 0 0 0 0 0 0 0 . 0 Zr-95 2.45E 08 2.45E 08 2.45E 08 2.45E 08 2.45E 08 2.45E 08 2.85E 08 2.45E 08 Nb-95 1.37E 08 1.37E 08 1.37E 08 1.37E 08 1.37E 08 1.37E 08' l.61E.08 1.37E 08 Mo-99 3.99E 06 3.99E 06 3.99E.06 3.99E 06 3.99E 06 3.99E 06 4.62E 06 3.99E 06 3.45E-09 , 3.45E 09 3.45E 09 Ag-llom 3.45E 09 3.45E 09 3.45E 09 3.45E 09 4.02E 09 Sb-124 5.99E 08 5.99E 08 5.99E 08 5.99E 08 5.99E 08 5.99E 08 6.92E 08 5.99E 08 l-131 1.72E 07 1.72E 07 1.72E 07 1.72E 07 1.72E 07 1.72E 07 2.09E 07 1.72E 07 1-133 2.46E 06 2.46E 06 2.46E 06 2.46E 06 2.46E 06 2.46E 06 3.00E 06 2.46E 06 1-135 2.53E 06 2.53E'06 2.53E 06 2.53E 06 2.53E 06 2.53E 06 2.95E G6 -2.53E 06 N Cs-134 6.90E 09 6.90E 09 6.90E 09 6.90E 09 6.90E 09 6.90E 09 8.05E 09 6.90E 09 Cs-136 1.51E 08 1.51E 08 1.51E 08 1.51E 08 1.51E 08 1.51E 08 1.71E 08 1.51E 08
@ 1.03E 10 'l.03E 10 1.03E lo 1.03E 10 1.03E 10 1.03E 10 1.20E 10 1.03E 10-Cs-137 2.05E 07-
'.. Ba-140 2.05E 07 2.05E 07 2.05E 07 2.05E 07. 2.05E 07 2.05E 07 2.35E 07
- La-140 1.92E 07 1.92E 07 1.92E 07 1.92E 07 1.92E 07 1.92E 07 2.18E 07 1.92E 07 Ce-141 1.37E 07 1.37E 07- 1.37E~07 1.37E 07 1.37E 07 1.37E 07: 1.54E 07 1.37E 07 Ce-144 6.96E 07 6.96E 07 6.96E 07 6.96E 07 :6.96E 07 6.96E 07 -8.05E~07 6.96E 07 2
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22_ ____1_Rev.__:No._ 1 _ . _ _ _ _ _ _ _ Boc.70 M e@ @M .
i TABLE B-7 DERIVATION OF GASEOUS DOSE FACTORS ,
Table Pagg B-7.1 Derivation of (Pj) Values B-32 B-7.2 Derivation of Gaseous Dose Factors-(Rj) B-33 B-7.3 Parameters for the Gaseous. Effluent Pathway B-42 B-7.4- Justification for Gaseous Pathways Used to B-45
- . Assess Dose B-7.5 Organ Doses for Gaseous Releases - Inhalation B-47 Pathway ,
t I
l Rev. No. 7 Page B-31 of ODCM
TABLE B-7.1 DERIVATION OF (Pi) VALUES The pathway dose particulates factor, transport includes Pi, for radioiodines,f the oith nuclide, tritium, and 8-day parameters
. the receptor usage rate of tie pathway media, and the appropriate dose. conversion factor. For the inhalation pathway, the value of Pi is calculated as follows:
Pi = K' (BR) DFAj (mrem /yr per uCi/m3)
Where:
K' = a constant of unit conversion, 106 pCi/uCi.
! (BR) = the breating rate of the a /yr (Table E-5 of Regulatory Guide 1.109)ge group, in m3 .
DFAj. = the maximum organ inhalation dose factor for the appro riate age group for the ith radionuclide, in mrem / C1 (Tables E-7 to E-10 of -Regulatory Guide 1.109 .
Example Calculation: '
For the I-131 child thyroid dose factor for exposure from inhalation:
DFAi
= 4.39E-03 :nrem/pCi BR = 3700 m5/yr These values will yield a Pi factor of 1.62E7 mrem /yr per uCi/m3 as listed in Table B-4 of this appendix.
Rev. No. 7 Page B-32 of ODCM
i TABLE B-7.2 DERIVATION OF GASEOUS DOSE FACTORS (Ri)
The lathway dose-part'.culates includefactor Ri forparameters transport radioiodines,fo tritium,h the itnuclide,and 8 day the receptor usage rate of the pathwa media, and the appropriate dose conversion factor. In develo eg potential the Ri values se pathw,ays.parate expressions-are written for each of I. INHALATION For the inhalation pathway, the value of Ri is calculated as follows:
Ri = K' (BR)a (DFAi )a (mrem /yr per uCi/m3)
Where:
K' = a constant of unit conversion, 106 pCi/uCi.
(BR)a rate of the receptor of age group
= the (a) brebthing(Table in m /yr B-7.3).
(DFA 1 )a = the organ inhalation for the receptor of age . dose actorthe
)f for ith radionuclide,ide 1.109 .in mrem es E-7pCirou to E-10 p(Ta of Regulatory Gu Examole Calculation:.
For the Co-60 child total body dose factor from exposure due to inhalation:
(DFA1 )a = 6.12E-6 mrem /pCi (BR)a = 3700 m3/yr These values yield a Ri factor of 2.26E4 mrem /yr per uCi/m3 as listed in Table B-6 of this appendix.
II. GROUND platig For the ground plane pathway, the value of Ri is calculated as follows:
Ri = K' K" (SF) DFGi [(1-e )/11]
(m2-mrem /yr per uCi/sec)
Rev. No. 7 Page B-33 of.ODCM
r y ,
_ f ?.
u TABLE B-7.2 (Con 1rznuto)
- g. DERIVATION OF GASEOUS DOSE FACTORS (Ri)
Where:
K'- = a constant of: unit conversion, 106 pCi/uC1.
K" = a constant of unit conversion, 8760 hr/yr.
Ai ~= the decay constant for the ith radionuclide, sec-1
- t. = the exposure time, 4.73E8 sec (Table B-7.3).
OFGi = the ground plane dose conversi0n factor for the ith
-Regulatory radionuclide,ide mrem /hr 1.109)per- pCi/m . (See Table E-6 of Gu .
SF = the shielding factor, 0.7, dimensionless (Table B-7.3).
Examole Calculation:
For the Co-60 child total body dose factor from. exposure due to the ground plane:
Ai = 4.20E-9 sec-1 DFGi = 1.70E-8 mrem /hr per pCi/m2 These values yield a Ri uCi/sec as listed in Table B-6 factorof . this of 2.15E10 appendix..m2-mrem /yr per III. VEGETATION A. Radiciodines And Eiaht Dav Particulates For the vegetation pathway, Ri, is calculated as follows:
L s ~^i th Ri = K. Jr) (DFLj)a [Va fLe ~^itt+ Ua gef 3 Yv LAi + Aw)
(m2-mrem /yr per uCi/sec)
Where:
K' = a Constant of unit conversion, 106 pCi/uci.
L Ua =-the consumption rate of fresh leafy vegetation ;
by- the rece in age group (a), in kg/yr I (Table B-7.3) .ptor l
'Rev._No. '7 Page B-34 of ODCM
1 n;
TABLE B-7.2 (Courtuvan)
-DERIVATION OF GASEOUS DOSE FACTORS (Ri)
Va
= the consumption rate of stored vegetation by -the receptor in age group (a), in kg/yr (Table B-7.3),
ft
= the fraction of. the annual intake of fresh leafy vegetation grown locally (Table B-7.3).
f 9
= the fraction of the annual intake of stored vegetation grown locally (Table B-7.3).
tl = the . average time between harvest of leafy-vegetation and its consumption, in seconds (Table B-7.3),
th = the average time between harvest of stored'
-vegetation and its consumption, in seconds (Table.
B-7.3).
Yy = the vegetation areal density, in kg/m2 (Table B-7.3).
r = fraction of deposited activity retained on vegetation (Table B-7.3).
Ai = .the decay constant for the ith radionuclide, in
. SeC~1
? Aw = the decay constant for removal of activity on leaf a plant surfaces by weatherino ~5.73E-7 sec-1 (ndcorresponding to- a 14 day half-life) .
(DFLj)a = the maximum organ ingestion dose factor for the ith radionuclide for the receptor in age group (a , in mrem /pCi Tables E-11 to E-14 of Reg)ulatory Guide 1.109() .
Examnie Calculation:
For the Co-60 child total body dose factor from exposure due to ingestion of vegetation:
Ua = u, 4g/yr Ua = 520 kg/yr fl "I fg = 0.76 Rev. No. 7 Page B-35 of ODCM
y ,
j
- , J l
r !
TABLE B-7.21ConTxwuso)
DERIVATION OF GASEOUS DOSE FACTORS (Ri) m "
l tt = 8.6E4 see th. = 5.18E6 sec
- .g Yy =-2 kg/m2 r -= 0.2 A i- = 4.2E-9'sec-1 ,
- - Aw = 5.73E-7 sec-1 (DFLj)a = 1.56E-5 mrem /pci ield an Ri factor of These uCi/secvaluesas lis (ed in Table B-6 of this appendix.1.1259 m2-mrem /y B. - Tri ti um The- concentration of tritium in vegetation 'is based- on the airborne concentration rather than the - deposition. 'Ri is calculated as follows:
R'i =_K' K (Ua f L + Ua fg)_(DFLj)a [0.75- (0.5/H)] "
(mrem /yr per uCi/m3)
Where: .
K' = unit conversion constant, 106 pCi/uti.
K = unit conversion constant, 103 gm/kg.
L 0.75 = the fraction of vegetation which is water (NUREG-
- 0133).
0.50 = the ratio of the specific activity of the vegetation l<; that is water to the atmospheric water (NUREG-0133).
L H = absolute atmospheric humidity, in gm/m3 -
,' (Table B-7.3).
w All other parameters are as previously defined above.
Rev. No.
7 Page B-36.of ODcM
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t F
TABLE B-7.2 (ConTzuuto) ,
a DERIVATION OF GASEOUS DOSE FACTORS (Ri)
Examole Calculation For the H-3 child total body dose factor from exposure due !
to ingestion of vegetation: ;
- VI. = 26 kg/yr !
Ua = 520'kg/yr- .
ft =-1 fg = 0.76 l (DFLj)a = 2.03E-7 mrem /pCi .,
H = 8 gm/ .(NUREG-0133) 3 These values yield a Ri factor of 4.01E3 mrem /yr per uCi/m3 as-listed in Table B-6 of this appendix.
IV. ti[Al A. Radiciodines And Eiaht Dav Particulates
-Ajth -Ajtf Ri = K' Qp(Vap) Ff (r) (DFLj)a [fpfs + (1-fp fs) e
. 3e ,
(Ai +A1) Yp Ys (m2-mrem /yr per uCi/sec)
.Where:
Uap = the receptor's meat consumption rate for age- (a), in :
kg/yr (Table.B-7.3).
Ff -= the stable element transfer coefficients, in days /kg
-(Table E-1 of Regulatory Guide 1.109) .
tf' = the transport time from pasture to. receptor, in sec (Table B-7.3).
th = the transport time from crop field to receptor, in sec (Table B-7.3).
R e v ..: N o .
7 Page B-37 of ODCM
k ~
'-j ,I l TABLE B-7.2 (Counnuto)
DERIVATION OF GASEOUS DOSE FACTORS-(Ri)
Yp r
=theagriculturalp/mgductivitbbyunitareaofpasture feed grass, in kg (Table- 7.3).
Ys = the feed,agricultuEal in kg/m (Table productivity B-7.3), by unit- area' of stored fp = fraction of the year that the cow is on pasture (Table _B-7.3).
fs = fraction of the cow feed that is pasture -grass while the cow is on pasture (Table B-7.3).
Qf = the cow's consumption rate, in' kg/ day (wet weight).
See Table B-7.3).
All other parameters were defined previously.
Examole Calculation:
For the Co-60 child total body dose factor from exposure due to ingestion of meat:
Uap- = 41 kg/yr Ff = 1.3E-2 days /kg th = 7.78E6 see tf- = 1.73E6 sec fp = 6/12 = 0.5 fs "1 (DFLj)a " l 56E-5 mrem /pCi Yp = 0.7 kg/m2 Ys = 2.0 kg/m2 QF = 50 kg/ day These values yield a Ri factor of 1.37E8 m2-mrem /yr per uCi/sec as listed in Table B-6 of this appendix.
B. Tritium The concentration of tritium in meat is based on the 1
- Rev. No. 7 Page B-38 of ODCM
.. .m-__ _ . _ _ . _ _ . _ _ . _ . - _ . _ . _-m_._._m__--1_..____. - _ . . _ . . _ _ _ _ _ __.mm . _ _ _ . _ . _
- [ l TABLE B-7.2 (CONTINUED) I DERIVATION OF GASEOUS DOSE FACTORS (Ri) .
E I
airborne concentration rather than the deposition. Ri is calculated as-follows: ,
Ri = . K ' K' ' ' Ff QF Uap (DFLj)a [0.75(0.5/H)] l (mrem /yr/peruCi/m3)
Examole Calculation:
All parameters have been defined in the previous sections for the H-3 child total bod dose factor from exposure due .
to incestion of meat. . ubstituting values into the preceding equati results in a Ri factor of 2.33E2
. mrem /yrperuCi/m3n,as listed in Table B-6 of this appendix, f
V. COW'S MILK A.- Radiciodines and Eiaht Day Particulates For the cow's milk pathway, Ri is calculated. as follows: (
Ri = K' QF(Vap) Fm (r) (DFLj)a p[f fs + (1-fp fs) e l' e '
-(Aj + Aj ) Yp Ys (m2-mrem /yr per uCi/sec)
Where:
Uap = the receptor's milk consumption rate for age (a), in liters /yr (Table B-7.3). <
tf = the trans sort time from pasture to cow, to milk, to receptor <n sec (Table B-7.3).
Fm = the stable element transfer coefficients in days /11ter (from Regulatory Guide-1.109, Table E'-1).
All other parameters were defined previously.
Examole Calculation:
~
For the Co-60 total body dose factor from exposure due to ingestion of cow's milk:
tf = 1.73E5 sec Vap = 330 1/yr Rev. No. 7 Page B-39 of ODCM
1 J
1:
]
TABLE B-7.2 (CONTINUED)- j DERIVATION OF GASEOUS DOSE FACTORS (Ri) )
)'
Fm =1.0E-3 days /1
, , These values yield a Ri factor of 8.52E7 m2-mrem /yr per i uCi/sec as. listed in Table B-6 of this appendix. ;
. B.1 Tritium i
The ' concentration of tritium 'in ' cow's milk is based on the airborne concentration rather than the; deposition. Ri is calculated as follows:
Ri = K' K Fm QF Uap (DFL i )a [0.75(0.5/H)]
(mrem /yrperuCi/m3)
Examole Calculation:
All ' parameters 'have been defined in the previous sections for the H-3 child total body dose factor from exposure due to ingestion of cow's milk. Substituting values into the preceding equati results in a Ri 1 actor of 1.57E3 mrem /yrperuCi/mbn,as listed in Table B-6 of this appendix. t
- VI. GOATS MILK A. Radiciodines and Eicht Dav Particulates For the goat's milk pathway, Ri is calculated as-follows
(
Ri . K' Qp(Vap) Fm (r) (DFLj)a [fp fs + (1-fpfs) e-Aith] e-Ai tf (Aj +Aj) Yp Ys (m2-mrem /yrperuCi/sec)
I: Where:
l' tf = the transport. time from pasture to . goat, to milk, to L
receptor in sec (Table B-7.3)..
L Fm = the stable element transfer coefficients. For the radionuclide Guide 1.109.in question, If the ionuclide rad is not listed inuse Table E-2 of Regu Table E-2, use Table E-1 (i.e., the same value used for the cow's milk pathway).
i: All other parameters were defined previously.
Rev. No.- 7 Page B-4o of ODCM
(
1 TABLE 8-7.2 (CONTINUED) i DERIVATION OF GASEOUS DOSE FACTORS (Ri) ,
- Examole Calculation: I For the Co-60 total body dose f actor :from exposure -due to-ingestion of goat's. milk:
p ;
gm=6kg/
= 1.0E-3 day (wetweight) days /1 tf = 1.73E5 see These values ' yield a Ri factor of 1.02E7 m2-rarem/yr per uC1/sec as listed in Table B-6 of this appendix. ;
- B. Tritium, The concentration of tritium in goat's milk is based on the- '
airborne concentration rather1than the deposition. Ri is calculated as follows:
Ri = K' K Fm QF Uap (DFLj)a [0.75(0.5/H)]
(mrem /yr per uCi/m3) -
Examole Calculation:
t All parameters have been defined in the previous sections for the H-3 child total body dose factor from exposure.due:
to ingestion of goat's milk. Substituting values into the-result in a Ri factor of 3.20E3 mrem /yr preceding per uCi/m3-as liste in Table B-6 of this appendix.
equation,d '
l l'
l..
l L
.Rev. No. '7 Page B-41 of ODCM
- _ = _ _ _ _ _ _ _ - _ _ - - - _ _ _ _ _ _ _ - _ _ - - -.. ._. - -.
TABLE B-7.3 PARAMETER FOR THE GASEOUS EFFLUENT PATHWAY PARAMETERS VALUE REFERENCE TABLE Vap (liters /yr)-cow's milk /
- infant 330 R.G. 1.109 E-5
- child 330 R.G, 1.109 E-5
- teen 400 R.G. 1.109 E-5
- adult 310 R.G. 1.109 E-5 Vap (liters /yr)-goat's milk /
- infant 330 R.G. 1.109 E-5
- child 330 R.G. 1.109 E-5
- teen 400 R.G. 1.109 E-5
- adult 310 R.G. 1.109 E-S Ua (kg/yr)-vegetation /
- infant 0 R.G. 1.109 E-5
- child 26 R.G. 1.109 E-5
- teen 42 R.G. 1.109 E-5
- adult 64 R.G. 1.109 E-5 Ua (kg/yr)-vegetation /
--infant 0' R.G.-1.109- E-5
- child 520 R.G. 1.109 E-5
- teen 630 R.G. 1.109 E-5
- adult 520 R.G. 1.109 E-5 Uap (kg/yr)-meat /
- infant 0 R.G. 1.109 E-5
- child 41 R.G. 1.109 E-5
- teen 65 R.G. 1.109 E - adult 110 R.G. 1.109 E (BR)a (m3/yr)-inhalation /
- infant 1400 R.G. 1.109 E-5
- child 3700 R.G. 1.109 E-5
- teen 8000 R.G. 1.109 E-5
- adult 8000 R.G. 1.109 E-5 l
l Rev. No. 7 Page B-42 of ODCM
m l
l TABLE B-7.3 (CONTINUED)
PARAMETER FOR THE GASE00S' EFFLUENT PATHWAY ,
i PARAMETERS VALUE REFERENCE TABLE r -(dimensionless) 1.0 for R.G. 1.109 E-15 Radioiodine 0.2 for- R.G. 1.109 E-15 Particulates f1 (dimensionless) 1.0 R.G. 1.109 E .
fg (dimensionless) 0.76 R.G. 1.109 E-15 tl (sec)-vegetation 8.6E4 R.G. 1.109 E-15 th~ (sec)-vegetation 5.18E6 R.G. 1.109 E-15
- (DFAj)ajmrem/Ci)- Each R.G. 1.109 E-7 to nhala ion Radionuclide E-10 L- DFGi (mrem /hr per pCi/m2)- Each R.G. 1.109 E-6 ground plane Radionuclide ,
SF (dimensionless) 0.7 R.G. 1.109 E-15 t (sec)-ground plane 4.73E8 R.G. 1.109 E-15 '
L QF (kg/ day)-cowmilk 50 R.G. 1.~109 E-3 QF (kg/ day)-goat milk 6 R.G. 1.109 E-3 Yp (kg/m2) 0.7- R.G. 1.109 E-15 Ys (kg/m2) 2.0 R.G. 1.109 E-15 (DFLj)a (mrem /pCi)-meat / Each R.G. 1.109 E-11.to -
milk / vegetation Radionuclide E-14 i w (sec-1) 5.73E-7 R.G. 1.109 E-15 tf (sec)-cow milk / 1.73E5 R.G. 1.109 E-15 goat milk th (sec)-cow milk / 7.78E6 R.G. 1.109 E-15 goat milk Yy (kg/m2) 2.0 R.G. 1.109 E-15 fp (dimensionless) 0.5 site specific fs (dimensionless) 1.0 NUREG-0133 page 33 Rev. No. 7 Page B-43 of ODCM l~
L
x .# ,
j l ..: 1 y _
l, 7.
TABLE B-7.3 (ConTruuto)-
PARAMETER FOR THE GASEOUS EFFLUENT PATitiAY PARAMETERS- VALUE REFERENCE TABLE ,
Fm (days / liter) Each R. G. 1.109 E-1 Radionuclide :
r L Ff (days /kg) Each R.G. 1,109 E-1 .;
- . ' Stable :
Element p -tf (sec)-meat 1.73E6 R.G. 1.109 E-15 th (sec)-meat 7.78E6 R.G. 1.109 E-15
. H- (gm/m3) 8.0 NUREG-0133 page 34 l'
i i.
J, i
e 1
i Rev. No. 7 Page B-44 of ODCM
s Is TABLE B-7.4 JUSTIFICATION FOR GASEOUS-PATHWAYS USED TO ASSESS DOSE AT THE J. A. FITZPATRICK NUCLEAR POWER PLANT ,
PATHWAY JUSTIFICATION FOR USAGE- *
- 1. NOBLE GAS EXPOSURE
, (GAMMA)
- a. Total Body This oathway is used in the ODCM to calculate dose rates only. This pathway is required by the Technical Specifications and NUREG-0133.
- b. Gamma Air This pathway is used in the ODCM. This pathway is required by the Technical Specifications and NUREG-0133,
- 2. NOBLE GAS EXPOSURE (BETA) .
a, Skin- This pathway is used in the ODCM to calculate dose rates only. This pathway is required by the Technical Specifications and NUREG-0133.
- b. Beta Air This pathway is used in the ODCM. - This pathway is required by the Technical Specif1 cations and NUREG-0133.
- 3. GROUND PLANE This pathway is used in-the ODCM to DEPOSITION calculate dose only. It is not used to calculate -dose rates. This pathway is required for use in dose calculation by the. . Technical Specifications. The Technical Specifications do not cequire it to- be used for dose rate calculations.
- 4. INHALATION This pathway is used in the ODCM to calculate dose and dose rates. This pathway is required for use in dose and dose rate calculations by the Technical Specifications and NUREG-0133.
- 5. VEGETATION This pathway is used in the ODCM to calculate dose only. It is not used to calculate dose rates. This pathway is required for use in dose calculations by NUREG-0133. The Technical specifications and NUREG-0133 do not Rev. No. 7 . Page B-45 of ODCM
TABLE B-7.4 (CONTINUED)
D" JUSTIFICATION FOR GASEOUS PATHWAYS USED TO ASSESS DOSE AT.THE J. A. FITZPATRICK NUCLEAR POWER PLANT PA1HWAY JUSTIFICATION FOR USAGE require it to be used for -dose rate calculations. The calculation of dose factors for stored fruit and vegetables and fresh fruit- and vegetables is combined in one equation in both the ODCM and NUREG-0133.
- 6. MEAT .This pathway is used in the ODCM to-calculate dose only. It is not used to calculate dose rates. This pathwav is required- for use in dose calculat' ions by NUREG-0133. The Technical Specifications do not require it to be-used for dose rate calculations. The calculation of dose factors for Meat Contaminated Feed and Meat Contaminated Forage is combined in one e both the ODCM and NUREG-0133.quation in
- 7. COW'S MILK This pathway is used in the ODCM to c61culate dose only. It is not used to calculate dose rates. .This pathway is required for use in dose calculations by ~NUREG-0133. The Technical Specifications do not require it to be used for dose rate calculations. The calculation of dose factors for Milk Contaminated Feed and Milk Contaminated Forage is. combined in one equation in both.the ODCM and NUREG-0133.
8.- GOAT'S MILK This pathway is used in the ODCM to
. calculate dose only. It is not used to calculate dose rates. This pathway is required for use in dose calculations by NUREG-0133. The Technical Specifications and NUREG-0133 do not require it to be used for dose rate calculations. The calculation of dose factors for Milk Contaminated Feed and Milk Contaminated Forage is combined in one equation in both the ODCM and NUREG-0133.
Rev. No. 7 Page B-46 of ODCM
__=_______--___-_-_______-__--____-________-_ _ - - _ _ _ _ _ - _ - .
_____---___--L-.
s..
(. -)
. j L
w TABLE B-7.5 o i 4
ORGAN DOSES FOR GASEGUS RELEASES (II81ALATION PAINWAYS) ;
messaamaammesemme-w e+<~
I
- 3 BOIE LIVER TIlVRDID KIDEEY VEAR (area)
LUIIG GI-LLI T. BODY 'I (ares) (ares) (ares) (arem) (aren) (ares) ;
1980 5.6E-05 6.0E-05 1.1E-02 -:
8.2E-05 1.6E-03 1.2E-04 3.5E-05
- 1981 8.6E-05 5.2E-05 1.1E-02 7.6E-05 8.4E-04 1.4E-04 1982 1.6E-04 9.5E-05 1.7E-02 1.5E-04 3.3E-05 ;
, 7.8E-04 1.8E-04 4.8E-05 i y
5 R M FlE5hiW 5 4 eisssRe!??Pi8estie n s e 9i R 3011E -
LIVER TIfYRDI KIDNEY YEAR (ares)
' LIIIIG GI-LLI T. BODY (ares) (aren ' (ares) (arem) (inrem) -(arem) .
1980 7.4E-05 8.0E-05 1.4E-02 1.lE-04 2.2E-03 1.2E-04 1981 1.2E-04 6.8E-05 1.4E-02 7.7E-05 1.0E-04 1.3E-03 1.5E-04 9.3E-05 1982 2.lE-04 -1.3E-04 2.2E-02 2.0E 1.2E-03 .. 1.9E-04 i
7.2E ,
I I ;
s@#!# Psf lFdifmestfRR##!MFe#8#!!@#iB?SeiEDRt* iW:'# ~ # : ~ ' "" !
SONE LIVER TIIYRDIO KIDIIEY VEAR (aren)
LIMIG GI-LLI 1. 800Y-(ares) (area) (ares) (ares) (ares) (aren)
.o 1980 9.7E-05 7.7E 2.1E-02 1.0E-04 1.9E-03 4.8E-05 a 1981 1.6E-04 '6.6E-05 1.6E-02 4.2E-05
$ 9.5E-05 1.lE-03 6.8E-05 4.0E-05 i 1982 2.9E-04 .l.3E-04 2.6E-02 1.9E-04 1.lE-03
' 8.8E-05 6.lE-05 ,
, i .!
1.. -
L M ;stygg gg g g f% y pp;4; g y %$y g}yy g g fnp ; 39 '; g yy~,
-4 ,,
o BOIIE LIVER TNVROID YEAR I[IDNEY LUNG GI-LLI 1. 80DY (arem) (arem) (area) (ares) (ares)
O (area) (ares) j 6.5E-05 8 1980 6.6E-05 1.5E-02 1.4E-04 1.lE-03 1.8E-05 2.8E-05 !
- c 1981 1.lE-04 5.8E-05 1.5E-02 7.0E-05 8.2E-04 2.7E-05 2.7E-05 1982 1.9E-04 1.2E-04 2.4E-02. 1.3E-04 8.5E-04. 3.4E-05 4.2E-05
tt 1
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s .
m . , .n. . !
K 1.', ,
r f
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e.
\ f .*
, -t r
I f)
^
s b.
+
APPENDIX C METEOROLOGICAL INDEX u
5 L
f
.' ' i i
- t. t I
r_
l
\
l' I
.- 3 .
pi l
t l!
I r.
I' 1-1
,Rev. No. 1 Page c-1 of occM-w e , - - . - , w - ,-
l
.1 APPENDIX.C- -l a
METEOROLOGICAL-DATA 1
Five l
sevenyears (heric stabil; ty1978 categories to 19821 of wind were speed andas ' direction joint data for atmosp compiled frequency distributions. The data were obtained at the 10 meter -I
. level and the 61 meter ' level on the meteorological tower at Nine J Mile ' Point. A five year annual average ;oint frequency 1 distribution was compiled for the 10 meter elevatton and also for the 61 meter elevation. For the turbine, ibution,srefuel . reactor, and radwaste vents, the joint frequency distr for the ~10 meter elevation were used. For the stack, the joint frequency distributions for the 61 meter elevation were used.
, oint frequency distributions were used as i
Thepathways.
grazing five input for generating D Goat year j/Q The annual values average five year- for the Garden, Meat, f req,uencyjoint Cow and-I- distributions were used as input for generatin X/0 and D/Q o
values for the Noble Gas, Ground Plane Deposition,gand Inhalation pathways, t
(>
l:
i Rev. No. 7 Page E of ODCM
L f
APPENDIX C ;
METEOROLOGICAL' DATA TABLE TITLE PAGE ,
C-l' Concentration X/Q Values for Site Boundary C-4 C-2 Finite Cloud Gamma X/Q Values-for Site Boundary C-5
!C-3 Depc:ition D/Q Values for Site Boundary C-6 '
'C-4 Reactor Vent - Annual Average Release C-7 Meteorological Data C-5: Refuel Floor Vent - Annual Average Release C-9 Meteorological Data C-6 Turbin2 Vent - Annual Average' Release C-11 Meteorological Data C-7 Radwaste Vent - Annual Average Release '
C-13 ,
Meteorological Data C-8 Elevated Release - Annual Average Meteorological C-15 Data C-9 Reactor Vent - Grazing Release Meteorological C Data C-10 Refuel Floor Vent - Grazing Meteorological Data C-20 C-11 Turbine Vent - Grazing Meteorological Data C-22 C-12 Radwaste Vent - Grazing Meteorological Data C-24 C-13 Elevated Release - Grazing Meteorological Data C-26 H C-14 Critical Receptor Dispersion Parameters for Vent C-29 and Elevated Releases l
I l
l l
l-L _Rev. No. _1_ Page _C-1 of ODCM
TABLE C-1 CONCENTRATION X/0 VALUES FOR SITE BOUNDARY DETERMINED F1t0M 1978 TO 1982 NETE0R0 LOGICAL DATA Sector Average Concentration X/Q (Sec/m3) i Turbine setual Redwaste Reactor canonitored Distance 3149 Floor Eld. Eld. Ground Level <
nirmetion (m) steek vant vant vant vant maiamma l
N w 225 1.072-09 3.095-06 4.093-04 4.943-06 4.093-04 3.75E-05 NNE w 225 2.405-10 1.38E-06 1.43E-06 2.223-04 1.833-06 1.492-05 ;
NE w 354 1.513-09 6.943-07 9.233-07 1.245-04 9.233-07 5.83E-06 !
l ENE w 563 1.673-08 7.46Ee07 1.00E-06 1.535-04 1.005-04 4.143-06 .
E 1 950 2:.223-08 3.962-07 4.833-07 7.473-07 4.833-07 1.83E-04 L ESE 1 1030 1.64E-04 2.30E-07 2.783-07 4.32E-07 2.78E-07 1.043-06 SE 1 1110 1.712-04 1.52E-07 1.893-07 3.3SE-Cf 1.495-07 9.20E-07 i SSE 1 1754 9.733-09 4.54E-08 4.995-08 1.06E-07 4.59E-08 3.513-07 l
i s 1 2205 1.135-08 4.762-04 4.835-08' 1.05E-07 4.833-08 3.262-07 l
L SSW 1 2269 1.22E-08 5 085-08 5.143-08 1.10E-07 5.143-08 2.88E-07 SW 1 2382 1.04E-08 4.105-08 4.223-08 1.365-07'4.222-08 3.77E-07 l'
WSW w 1847 4.32E-09 3.323-04 3.343-08 1.07E-07 3.343-04 5.131-07 W W 644 3.603-09 1.293-07 1.465-07 2.47E-07 1.663-07 6.113-06 WW w 370 4.23E=09 8.43E-07 1.12E-06 1.50E-04 1.12E-06 1.81E-05 NW w 304 6.95E-09 1.923-06 2.59E-04 3.213-06 2.59E-06 3.032-05 L- NNW w 241 2.213-09 2.29E-04 3.01E-04 3.643-04 3.012-06 3.42E-05
.1 = land v = water
}
Rev. No. _1 _Page M of CDCM.
TABLE C-2 FINITE CLOUD GAlmA X/0 VALUES FOR SITE BOUNDARY DETERMINED FROM 1978 TO 1982 METEOROLOGICAL DATA Finite Cloud Gama X/Q (Sec/m3)
Distance Direction rei g N W 225 1.62E-07 WWE w 228 1.04E-07 WE w 354 1.10E=07 ENE w 543 1.873-07 E 1 950 1.44E-07 ESE 1 1020 7.81E=08 8E 1 1110 6.28E-08 SSR 1 1734 2.86E-08 8 1 agog 2.64E-08 S8W 1 2269 2.772-08 SW 1 3333 2.54E-08 W8W w 1867 2.38E-08 W w 644 7.56E-08 HNW w 370 s.12E-08 NW w 306 1.37E-07 NNW w 241 ' 1.35E-07 1 = land w = water Rev. No. & Page E of ODCM
TABLE C-3 DEPOSITION D/0 VALUE5 FOR SITE BOUNDARY DETERMINED FROM 1978 TO 1982 NETEOROLOGICAL DATA DEPOSITION D/G (1/MI)
Turbine Refuel Radwasta Reacter Unmenitored-Distance 51dg. Floor tid. Bld, cround Level Sirection fa) Stack Vant Vant Vant Vant Relamaa N w 225 4.32E-10 2.18E-04 2.91E-08 3.81E-08 2.91E-08 1.22I-07 NNE w 225 1.23E-10 1.02E-08 1.37E-04 1.76E-08 1.37E-08 5.52E-04 NE w 354 1.47E-10 8.12EuC9 1.05E-04 1.34E-08 1.0$E-04 3.05E-08
~
ENE w 563 1.61E-09 1.45E-08 1.76E-08 2.26E-08 1.76E-08 3.49E-08 .
I 1 950 1.93E-09 8.93E-09 9.99E-09 1.212-08 9.99E-09 1.54E-08 ESE 1 1030 1.63E-09 6.21E-09 6.87E-09 8.16E-09 6.87E-09 1.01E-08 SE 1 1116 1.57E-09 4.05E-09 4.53E-09 5.80E-09 4.53E-09 7.71E-09 SSE 1 1754 6.19E-10 0.02E-10 8.47E-10 1.06E-09 8.47E-10 1.70E-09 8 1 2205 4.29E-10 9.06E-10 9.18E-10 1.06E-09 9.18E-10 1.68E-09 SSW 1 2269 4.26E-10 5.86E-10 5.94E-10 7.59E-10 5.942-10 1.21E-09
-SW 1 2382 2. 515-10 5.3 3E-10 5.46E-10 7.18E-10 5. 46E-10 1. 29E-09 W8W w 1867 1.10E-10 2.35E-10 2.42E-10 3.48E-10 2.42E-10 1.10E-09 W w 644 1.63E-10 1.14E-09 1.38E-09 2.26E-09 1.38E-09 1.26E-08 WNW w 370 2.87E-10 4.89E-09 9.22E-09 1.28E-08 9.22E-09 4.92E-08 NW w 306 5.66E-10 1.50E-08 2.05E-08 2.75E-08 2.05E-08 8.84E-08
-NNW w 241 4.93E-10 1.52E-08 2.04E-08 2.73E-08 2.04E-08 9.35E-08 1 = land w = water
=-- u- = . maan e-A ar.ancu
. TABLE C-4 REACTOR VENT - l ANNUAL AVERAGE METEOROLOGICAL DATA i Sector Average Concentration X/Q (sec/m3)
SEGMENT BOUNDARIES IN MILES Direc-tiSD
.5 .75 1.0 1.5 2.5 3.5 N 5.15E-07 3.04E-07 2.215-07 1.475-07 8.81E-08 6.16E-08 NNE 2.34E-07 1.415-07 1.05E-07 7.075-08 4.25E-08 2.95E-08 NE 2.68E-07 1.61E-07 1.175-07 7.70E-08 4.475-08 3.05E-08 ENE 6.10E-07 3.60E-07 2.55E-07 1.585-07 8.50E-08 5.57E-08 E 6.07E-07 3.53E-07 2.465-07 1.495-07 7.95E-08 5.19E-08 ESE 3.913-07 2.263-07 1.573-07 9.495-08 5.035-08 3.272-04 SE 3.898-07 1.713-07 1.248-07 7.88E-04 4.383-08 2.91E-08 SSE 1.15E-07 6.943-08 5.353-08 3.853-08 2.435-08 1.725-04 8 1.183-07 7.143-08 5.85E-08 4.555-08 3.063-08 2.22E-08 SSW 1.16E-07 7.65E-08 6.325-08 4.933-09 3.253-08 2.313-08 SW 1.40E-07 9.37E-08 7.773-08 6.175-04 4.173-08 2.995-04 WSW 5.81E-08 3.85E-08 3.423-08 3.205-08 2.553-08 1.975-06 W 1.22E-07 7.85E-08 6.588-08 5.663-08 4.365-08 3.38E-0'8 WNW 3.45E-07 2.10E-07 1.583-07 1.11E-07 7.065-08 5.06E-08 NW 5.61E-07 3.312-07 2.415-07 1.60E-07 9.60E-08 6.73E-08 NNW 4.24E-07 2 47E 1.79E-07 1.19E-07 7.20E-08 5.09E-08 4.5 7.5 15.0 25.0 35.0 45.0 N 4.67E-08 2.62E-08 1.182-08 6.61E-09 4.52E-09 3.41E-09 NNE 2.22E-08 1.22E-08 5.30E-09 2.88E-09 1.94E-09 1.49E-09 NE 2.27E-08 1.22E-08 5.17E-09 2.76E-09 1.84E-09 1.37E-09 ENE 4.04E-08 2.10E-08 8.54E-09 4.47E-09 2.96E-09 2.17E-09 E 3.75E-08 1.95E-08 7.915-09 4.15E-09 2.75E-09 2.02E-09 ESE 2.36E-08 1.22E-08 4.89E-09 2.563-09 1.49E-09 1.24E-09 SE 2.125-08 -1.125-08 4.575-09 2.433-09 1.61E-09 1.19E-09 SSE 1.305-08 7.23E-09 '3.15E-09 1.735-09 1.17E-09 8.78E-10 5 1.71E=08 9.59E-09 4.215-09 2.31E-09 1.575-09 1.17E-09 SSW 1.74E-08 9.49E-09 3.95E-09 2.095-09 1.39E=09 1.02E-09 SW 2.285-08 1.265-08 5.33E-09 2.845-09 1.89E-09 1.40E-09 WSW 1.57E-08 9.24E-09 4.25E-09 2.385-09 1.63E-09 1.27E-09 W 2.73E-08 1.67E-08 8.27E-09 4.883-09 3.43E-09 2.64E-09 WNW 3.90E-08 2.26E-08 1.075-08 6.17E-09 4.30E-09 3.29E-09 NW 5.12E-08 2.91E-08 1.36E-08 7.805-09 5.43E-09 4.14E-09 NNW 3.89E-08 2.22E-08 1.04E-08 5.98E-09 4.16E-09 3.17E-09 I
Rev. No. 7 Page _G-1 of ODCM
TABLE C-4 (Courzuuto) i REACTOR VENT -
L ANNUAL AVERAGE METEOROLOGICAL DATA (D/Q) Sector Average Deposition (1/m2) By D0wnwind Sectors 4
SEGMENT BOUNDARIES IN MILES )
i Direc-
.5 .75 1.0 1.5 2.5 3.5 N 5.253-09 2.96E-09 1.975-09 1.085-09 4.79E-10 2.76E-10 L NNE 2.385-09 1.373-09 9.30E-10 5.17E-10 2.345-10 1.35E-10 l NE 3.253-09 1.83E-09 1.225-09 6.445-10 2.93E-10 1.67E-10 ENE 1.06E-08 5.855-09 3.825-09 2.04E-09 8.885-10 5.04E-10 t E 1.283-08 6.98E-09 4.513-09 2.38E-09 1.035-09 5.79E-10 ,
ESE 9.88E-09 5.39E-09 3.473-09 1.C35-09 7.31E-10 4.41E-10 i SE 7.103-09 4.03E-09 2.653-09 1.435-09 6.275-10 3.54E-10 ;
SSE 2.40E-09 1.412-09 9.573-10 5.275-10 2.415-10 1.415-10 '
3 8 3.87E-09 2.223-09 1.485-09 7.953-10 3.613-10 2.12E-10 SSW 2.123-09 1.32E-09 9.453-10 5.433-10 2.595-10 1.545-10 SW 1.933-09 1.24E-09 9.125-10 5.363-10 2.593-10 1.555 ,10 ,
WSW 6.23E-10 3.943-10 2.913-10 1.712-10 8.61E-11 5.27E111 W 1.05E-09 6.643-10 4.89E-10 2.925-10 1.453-10 8.743-11 ,
WNW 3.26E-09 1.92E-09 1.335-09 7.475-10 3.433-10 2.005-10 i NW 5.48E-09 3.08E-09 2.043-09 1.11E-09 4.945-10 2.84E-10
- NNW 4.13E-09 2.32E-09 1.533-09 8.30E-10 3.695-10 2.13E-10 4.5 7.5 15.0 25.0 35.0 45.0 :
N 1.80E-10 7.495-11 2.375-11 1.01E-11 5.75E-12 3.77E-12 NNE 8.85E-11 3.645-11 1.153-11 4.84E-12 2.725-12 1.77E-12 '
. NE 1.093-10 4.495-11 1.395-11 5.79E-12 3.225-12 2.07E-12 ENE 3.275-10 1.353-10 4.243-11 1.785-11 9.963-12 6.43E-12 >
E 3.75E-10 1.545-10 4.873-11 2.045-11 1.145-11 7.31E-12 .
ESE 2.843-10 1.185-10 3.735-11 1.575-11 8.76E-12 5.61E-12 SE 2.345-10 9.74E-11 3.113-11 1.355-11 7.72E-12 5.04E-12 SSE 9.32E-11 3.975-11 1.305-11 5.853-12 3.483-12 2.32E-12 8 1.415-10 6.043-11 2.053-11 9.425-12 5.89E-12 4.00E-12 SSW 1.03E-10 4.405-11 1.43E-11 6.425-12 3.80E-12 2.53E-12 SW 1.033-10 4.423-11 1.425-11 6.253-12 3.65E-12 2.41E-12 WSW- 3.54E-11 1.545-11 5.143-12 2.31E-12 1.373-12 8.99E-13 W 5.84E-11 2.495-11 8.045-13 3.50E-12 2.02E-12 1.32E-12 WNW 1.31E-10 5.495-11 1.725-11 7.325-12 4.155-12 2.71E-12 NW 1.86E-10 7.72E-11 2.453-11 1.04E-11 5.94E-12 3.89E-12 NNW 1.39E-10 5.80E-11 1.85E-11 7.98E-12 4.58E-12 3.01E-12
-_. ~ . _ - - - - . - - - - . - __ -- -- ._
i i
l TABLE C-5 REFUEL FLOOR VENT ANNUAL AVERAGE METEOROLOGICAL DATA Sector Aver 8ge Concentration X/Q (sec/m3)
SEGMENT BOUNDARIES IN MILES i
Direction
.50 .75 1.00 1.50 2.50 3.50 I N 5.15E-07 3.04E-07 2.21E-07 1.47E-07 8.81E-08 NNE 2.342-07 1.41E-07 1.05E-07 6.16E-08 7.07E-08 4.25E-08 2.95E-08 NE 2.68E-07 1.61E-07 1.17E-07 7.70E-04 4.47E-08 i
ENE 6.10E-07 3.60E-07 2.55E-07 3.05E-08 1.58E-07 8.50E-08 5.57E-08 l E 6.07E-07 3.53E-07 2.46E-07 1.49E-07 7.94E-08 ESE 3.91E-07 2.26E-07 1.57E-07 5.19E-08 !
9.49E-08 5.03E-08 3.27E-08 SE 2.89E-07 1.71E-07 1.24E-07 7.88E-04 4.38E-08 SSE 1.14E-07 6.94E-08 5.35E-04 2.90E-08 8 3.85E-08 2.43E-08 1.72E-08 1.18E-07 7.14E-08 5.85E-08 4.55E-08 3.06E-08 SSW 1.16E-07 7.65E-08 6.32E-08 2.22E-08 SW 4.93E-04 3.2SE-04 2.31E-08 1.40E-07 9.37E-08 7.77E-08 6.17E-04 4.17E-04 WSW 5.81E-08 3.85E-08 3.42E-08 2.99E-08 W 3.20E-04 2.55E-08 1.97E-08 1.22E-07 7.85E-04 6.58E-04 5.66E-08 4.36E-04 WNW 3.45E-07 2.10E-07 1.58E-07 3.38E-08 1.11E-07 4
NW 5.61E-07 3.31E-07 7.06E-08 5.06E-08 -
2.41E-07 1.60E-07 9.60E-08 6.73E-08 NNW 4.24E-07 2.47E-07 1.79E-07 1.19E-07 7.20E-08 i 5.09E-08 i 1
4.50 7.50 15.00 25.00 35.00 45.00 N 4.67E-08 2.62E-08 1.18E-08 6.61E-09 4.52E-09 NNE 2.22E-08 1.22E-08 5.30E-09 2.88E-09 3.41E-09 NE 2.27E-08 1.22E-08 5.17E-09 2.76E-09 1.94E-09 1.45E-09 ENE 4.04E-08 2.10E-04 8.54E-09 4.47E-09 1.84E-09 1.37E-09
- E 3.75E-08 1.95E-08 7.91E-09 4.15E-09 2.96E-09 2.17E-09 ESE 2.36E-08 1.22E-08 4.49E-09 2.56E-09 2.75E-09 2.02E-09 SE 2.12E-08 1.123-08 4.57E-09 2.42E-09 1.69E-09 1.24E-09 SSE 1.30E-04 7.23E-09 3.15E-09 1.73E-09 1.61E-09 1.19E-09 S 1.71E-08 9.59E-09 4.21E-09 2.31E-09 1.17E-09 8.78E-10 L SSW 1.74E-04 9.49E-09 3.95E-09 2.095-09 1.57E-09 1.17E-09 i
SW 2.283-08 1.26E-08 5.33E-09 2.84E-09 1.39E-09 1.02E-09 WSW 1.57E-08 9.24E-09 4.25E-09 2.38E-09 1.89E-09 1.40E-09 W 2.72E-08 1.67E-08 8.27E-09 4.88E-09 1.63E-09 1.23E-09 WNW 3.90E-08 2.26E-08 1.07E-08 6.17E-09 3.43E-09 2.64E-09 NW 5.12E-08 2.91E-04 1.36E-04 7.80E-09 4.30E-09 3.29E-09 NNW 3.89E-08 2.22E-08 1.04E-08 5.98E-09 5.43E-09 4.14E-09 4.16E-09 3.17E-09 i
L l
l .
l Rev. No. 7 Page _C-1 of ODCM-
. - .~.
TABLE C-5 (Courzwuto)
REFUEL FLOOR VENT -
ANNUAL AVERAGE NETEOR0 LOGICAL DATA 3 (D/Q) Sector Average Deposition (1/m2) By D0wnwind Sectors SEGMENT BOUNDARIES IN MILES l l
Direction !
.50 75 1.00 1.50 2.50 3.50 i N 5.25E-09 2.96E-09 1.97E-09 1.08E-09 4.79E-10 2.76E-10 NNE 2.38E-09 1.37E-09 9.30E-10 5.17E-10 2.34E-10 1.35E-10 NE 3.25E-09 1.83E-09 1.22E-09 6.63E-10 2.93E-10 1.67E-10 ENE 1.05E-04 5.85E-09 3.82E-09 2.04E-09 8.88E-10 5.04E-10 E 1.28E-04 6.98E-09 4.51E-09 2.38E-09 1.02E-09 5.79E-10 ESE 9.88E-09 5.39E-09 3.47E-09 1.82E-09 7.81E-10 4.41E-10 SE 7.10E-09 4.02E-09 2.65E-09 1.43E-09 6.27E-10 3.58E-10 SSE 2.40E-09 1.41E-09 9.57E-10 5.27E-10 2.41E-10 1.41E-10 S 3.87E-09 2.22E-09 1.48E-09 7.95E-10 3.61E-10 2.12E-10 SSW 2.12E-09 1.32E-09 9.45E-10 5.43E-10 2.59E-10 1.54E-10 SW 1.93E-09 1.24E-09 9.12E-10 5.36E-10 2.59E-10 1.55E-10 '
WSW 6.23E-10 3.96E-10 2.91E-10 1.71E-10 8.61E-11 5.27E-11 ,
W 1.05E-09 6.64E-10 4.89E-10 2.92E-10 1.453-10 8.74E-11 '
WNW 3.26E-09 1.92E-09 1.32E-09 7.47E-10 3.43E-10 2.00E-10 i
NW 5.44E-09 3.08E-09 2.04E-09 1.11E-09 4.945-10 2.84E-10 NNW 4.13E-09 2.32E-09 1.533-09 8.30E-10 3.69E-10 2.13E-10
. t 4.50 7.50 15.00 25.00 35.00 45.00 N 1.80E-10 7.49E-11 2.375-11 1.015-11 5.75E-12 3.77E-12 NNE 8.85E-11 3.68E-11 1.15E-11 4.84E-12 2.72E-12 1.77E-12 NE 1.09E-10 4.49E-11 1.39E-11 5.79E-12 3.22E-12 2.07E-12 ENE 3.27E-10 1.35E-10 4.23E-11 1.78E-11 9.96E-12 6.43E-12 E 3.75E-10 1.545-10 4.87E-11 2.04E-11 1.14E-11 7.31E-12 ESE 2.46E-10 1.185-10 3.73E-11 1.573-11 8.763-12 5.61E-12 SE 2.34E-10 9.763-11 3.11E-11 1.345-11 7.72E-12 5.04E-12 SSE 9.32E-11 3.96E-11 1.30E-11 5.85E-12 3.48E-12 2.32E-12 8 1.41E-10 6.06E-11 2.05E-11 9.62E-12 5.89E-12 4.00E-12 SSW 1.03E-10 4.40E-11 1.435-11 6.42E-12 3.80E-12 2.53E-12 SW 1.03E-10 4.42E-11 1.425-11 6.253-12 3.65E-12 2.41E-12 WSW 3.54E-11 1.54E-11 5.14E-12 2.31E-12 1.37E-12 8.993-13 W 5.84E-11 2.49E-11 8.04E-12 3.50E-12 2.02E-12 1.32E-12 WNW 1.31E-10 5.49E-11 1.72E-11 7.32E-12 4.15E-12 2.71E-12 >
NW 1.86E-10 7.72E-11 2.45E-11 1.04E-11 5.94E-12 3.89E-12 NNW 1.39E-10' 5.40E-11 1.85E-11 7.9sE-12 4.54E-12 3.01E-12 ,
Rev. No. 7 Page C-10 of ODCM ,/
l l
i TABLE C-6 TURBINE VENT - '
ANNUAL AVERAGE METEOROLOGICAL DATA .
Sector Average Concentration X/Q (sec/m3) r SEGMENT BOUNDARIES IN MILES '
Direction
.50 .75 1.00 1.50 2.50 3.50 N 3.96E-07 2.43E-07 1.85E-07 1.30E-07 8.10E-08 5.75E-08 '
NNE 1.79E-07 1.13E-07 8.78E-08 6.30E-08 3.94E-08 2.77E-08 i NE 2.05E-07 1.29E-07 9.80E-08 6.81E-08 4.12E-08 2.45E-08 ,
ENE 4.65E-07 2.87E-07 2.11E-07 1.37E-07 7.64E-04 5.07E-08 ;
E 4.90E-07 2.96E-07 2.14E-07 1.35E-07 7.38E-08 4.47E-08 E8E 3.15E-07 1.90E-07 1.37E-07 8.63E-08 4.72E-08 3.10E-04 SE 2.21E-07 1.40E-07 1.06E-07 7.135-04 4.10E-04 2.75E-08 SSE 9.40E-08 6.00E-05 4.85E-08 3.65E-08 2.36E-08 1.68E-08 S 1.05E-07 6.56E-08 5.59E-08 4.51E-08 3.063-04 2.22E-08 '
58W 9.96E-04 7.01E-04 6.05E-04 4.89E-08 3.26E-08 2.31E-08 SW 1.16E-07 8.33E-08 7.29E-08 6.06E-04 4.15E-08 2.98E-08 WSW 4.95E-08 3.49E-08 3.31E-04 3.'24E-08 W' 2.60E-04 2.00E-04 5.64E-08 6.65E-08 W.98E-08 5.50E-08 4.33E-04 3.34E-04 >
WWW 2.64E-07 1.69E-07 1.34E-07 1.01E-07 NW 6.65E-08 4.83E-08 2.59E-07 4.21E-07 1.97E-07 1.39E-07 4.76E-08 6.24E-08 NNW 3.28E-07 1.98E-07 1.49E-07 1.05E-07 6.43E-08 4.75E-04 4.30 7.50 15.00 25.00 35.00 45.00 N 4.39E-08 2.49E-08 1.14E-08 6.38E-09 4.37E-09 3.30E-09 NNE 2.10E-08 1.16E-08 5.08E-09 2.7(E-09 1.87E-09 1.40E-09 NE 2'13E-08
. 1.15E-08 4.93E-09 2.64E-09 1.77E-09 1.31E-09 ENE 3.70E-08 1.943-08 7.96E-09 4.19E-09 2.78E-09 2.04E-09 E 3.54E-04 1.45E-08 7.54E-09 3.98E-09 2.64E-09 1.94E-09 ESE 2.253-04 1.17E-08 4.72E-09 2.47E-09 1.64E-09 1.20E-09 SE 2.02E-08 1.07E-08 4.40E-09 2.34E-09 1.565-09 1.15E-09 SSE- 1.28E-08 7.095-09 3.103-09 1.70E-09 1.16E-09 8.67E-10 3 1.70E-04 9.57E-09 4.19E-09 2.30E-09 1.56E-09 1.17E-09 SSW 1.74E-08 9.46E-09 3.935-09 2.08E-09 1.38E-09 1.02E-09 SW 2.27E-04 1.25E-08 5.293-09 2.82E-09 1.84E-09 1.39E-09 WSW 1.595-04 9.323-09 4.27E-09 2.393-09 1.64E-09 1.23E-09 W 2.72E-08 1.68E-08 8.30E-09 4.905-09 3.45E-09 2.65E-09 WWW 3.75E-04 2.19E-08 1.04E-08 6.073-09 4.24E-09 3.25E-09 Int 4.80E-04 2.76E108 1.313-08 7.57E-09 S.27E-09 4.03E-09 NNW 3.66E-08 2.12E-08 1.01E-08 5.41E 4.05E-09 3.09E-09 Rev. No. 7 Page C-11 of ODCM
_.i__._.,_--_._-
TABLE C-6 (Contzwuro) !
1 TURBINE VENT - i ANNUAL AVERAGE METEOROLOGICAL DATA !
(D/Q) Sector Average Deposition (1/m2) By D0wnwind Sectors j SEGMENT BOUNDARIES IN MILES Direction
.50 .75 1.00 1.50 2.50 3.50 N 4.31E-09 2.50E-09 1.70E-09 9.47E-10 4.27E-10 2.47E-10 NNE 1.92E-09 1.15E-09 8.03E 10 4.58E-10 2.10E-10 NE 2.65E-09 1.55E-09 1.22E-10 1.06E-09 5.91E-10 2.65E-10 1.52E-10 ENE 8.98E-09 5.14E-09 3.43E-09 1.87E-09 4.25E-10 E 1.13E-08 6.34E-09 4,17E-09 4.71E-10 ESE 2.25E-09 9.79E-10 5.57E-10 8.78E-09 4.92E-09 .'s.23E-09 1.73E-09 7.52E-10 4.27E-10 SE 6.18E-09 3.62E-09 3.44E-09 SSE 1.34E-09 5.99E-10 3.45E-10 2.19E-09 1.31E-09 U.03E-10 5.04E-10 2.32E-10 1.36E-10 S 3.78E-09 2.18E-09 1.45E-09 7.86E-10 3.58E-10 SSW 2.01E-09 1.28E-09 2.10E-10 9.23E-10 5.37E-10 2.56E-10 1.53E-10 SW 1.76E-09 1.17E-09 8.75E-10 5.23E-10 2.54E-10 1.52E-10 WSW 5.75E-10 3.76E-10 2.81E-10 1.68E-10 8.46E-11 W 8.97E-10 5.93E-10 5.17E-11 4.50E-10 2.75E-10 1.37E-10 8.32E-11 WNW 2.62E-09 1.61E-09 1.14E-09 NW 6.61E-10 3.04E-10 1.40E-10 4.33E-09 2.51E-09 1.71E-09 9.49E-10 4.29E-10 2.48E-10 NNW 3.39E-09 1.95E-09 1.32E-09 7.27E-10 3.28E-10 1.90E-10 4.50 7.50 15.00 25.00 35.00 45.00 N 1.62E-10 6.76E-11 2.13E-11 9.16E-12 5.27E-12 3.48E-12 NNE 8.02E-11 3.34E-11 1.04E-11 4.38E-12 2.49E-12 1.63E-12 NE 9.93E-11 4.11E-11 1.26E-11 5.26E-12 2.94E-12 1.91E-12 ENE 3.07E-10 1. 27E-10 3 96E-11 1.67E-11 9.45E-12 6.15E-12 E 3.62E-10 1.49E 4.68E-11 1.98E-11 1.11E-11 7.17E-12 ESE 2.78E-10 1.15E-10 3.61E-11 1.53E-11 8.43E-12 5.58E-12 SE 2.24E-10 9.49E-11 3.02E-11 1.32E-11 7.68E-12 5.08Z-12 SSE 9.05E-11 3.86E-11 1.27E-11 5.76E-12 3.45E-12 2.33E-12 S 1.39E-10 6.00E-11 2.03E-11 9.55E-12 5.86E-12 3.99E-12 SSW 1.02E-10 4.36E-11 1.41E-11 6.35E-12 3.77E-12 2.51E-12
~SW 1.01E-10 4.33E-11 1.38E-11 6.10E-12 3.57E-12 2.362-12 WSW 3.48E-11 1.51E-11 5.002-12 2.24E-12 1.33E-12 8.76E-13 W 5.57E-11 2.38E-11 7.612-12 3.32E-12 1.92E-12 1.26E-12 WNW 1.19E-10 4.98E-11 1.55E-11 6.63E-12 3.79E-12 2.49E-12 NW 1.63E-10 6.80E-11 2.15E-11 9.24E-12 5.32E-12 3.52E-12 NNW 1.25E-10 5.21E-11 1.66E-11 7.21E-12 i
4.18E-12 2.78E-12 l
Rev. No. 7 Page ._C-11 of ODCM
- -____ - __________ _ - _ _ __ ____ -. . --- . - . . ~ _ .- .-. --
i 1
TABLE C-7 l RADWASTE VENT -
ANNUAL AVERAGE METEOROLOGICAL DATA Sector Average Concentration X/Q (sec/m3)
SEGMENT BOUNDARIES IN MILES Direction
.50 .75 1.00 1.50 2.50 3.50 N 8.39E-07 5.51E-07 4.13E-07 2.69E-07 1.52E-07 1.03E-07 NNE 3.97E-07 2.66E-07 2.01E-07 1.29E-07 7.11E-04 4.72E-08 I NE 4.43E-07 2.48E-07 2.12E-07 1.33E-07 7.12E-08 4.65E-08 1 ENE 9.75E-07 5.90E-07 4.13E-07 2.43E-07 1.23E-07 7.78E-08 !
E 9.26E-07 5.50E-07 3.82E-07 2.24E-07 1.14E-07 7.21E-08 ESE 5.99E-07 3.52E-07 2.44E-07 1.42E-07 SE 7.17E-08 4.53E-08 4.99E-07 3.03E-07 2.15E-07 1.29E-07 6.61E-08 SSE 2.18E-07 1.49E-07 4.22E-04 1.15E-07 7.54E-04 4.20E-08 2.80E-08 5 2.44E-07 1.75E-07 1.41E-07 1
9.612-08 5.47E-04 3.66E-08 i SSW 2.57E-07 1.94E-07 1.54E-07 1."ofE-07 5.59E-08 3.63E-08 SW 3.11E-07 2.42E-07 1.96E-07 1.3dE-07 7.46E-08 4.90E-08 i
WSW 1.36E-07 i 1.28E-07 1.16E-07 8.89E-08 5.49E-08 3.80E-08 W 2.54E-07 2.23E-07 1.97E-07 1.52E-07 1.00E-07 7.27E-04 WNW 6.05E-07 4.23E-07 3.29E-07 2.23E-07 1.33E-07 9.37E-08 NW 9.19E-07 6.03E-07 4.52E-07 2.94E-07 1.70E-07 1.18E-07 !
NNW 6.77E-07 4.44E-07 3.36E-07 2.22E-07 1.29E-07 9.01E-08 4.50 7.5d 15.00 25.00 35.00 45.00 N 7.68E-08 4.17E-08 1.82E-08 9.86E-09 6.63E-09 4.91E-09 NNE 3.45E-08 1.82E-08 7.65E-09 4.06E-09 2.70E-09 1.99E-09 L NE 3.35E-08 1.73E-08 7.11E-09 3.722-09 2.46E-09 1.80E-09 l ENE 5.53E-08 2.80E-08 1.12E-08 5.7EE-09 3.79E-09 2.77E-09 E 5.13E-08 2.60E-08 1.04E-08 5.39'E-09 3.54E-09 2.58E-09 ESE 3.21E-08 1.62E-04 6.40E-09 3.30E-09 2.16E-09 1.58E-09 i SE 3.02E-08 1.54E-04 6.17E-09 3.22E-09 2.12E-09 1.55E-09 SSE 2.06E-08 1.10E-04 4.63E-09 2.48E-09 1.66E-09 1.23E-09 5 2.69E-08 1.43E-08 5.98E-09 3.20E-09 2.14E-09 1.58E-09 SSW 2.61E-04 1.34E-08 5.34E-09 2.77E-09 1.81E-09 1.32E-09 SW' 3.55E-08 1.83E-08 7.44E-09 3.87E-09 2.55E-09 1.46E-09 WSW 2.84E-08 1.55E-08 6.73E-09 3.632-09 2.43E-09 1.80E-09 W 5.62E-08 3.25E-08 1.51E-08 8.43E-09 5.75E-09 4.30E-09 WNW 7.13E-08 4.04E-08 1.84E-08 1.02k-08 6.96E-09 5.20E-09 NW 4.95E-04 5.03E-08 2.28E-08 1.275-08 8.60E-09 6.43E-09 NNW 6.81E-08 3.83E-08 1.73E-08 9.57E-09 6.50E-09 4.85E-09 l
l Rev. No. 7 Page .C-13 of ODCM
TABLE C-7 (CouTxmuto)
RADWASTE VENT -
ANNUAL AVERAGE METEOROLOGICAL DATA (D/Q) Sector Average Deposition (1/m2) By Downwind Sectors SEGMENT BOUNDARIES IN MILES Direction
.50 .75 1.00 1.50 2.50 3.50 N 7.23E-09 3.98E-09 2.52E-09 1.312-09 5.49E-10 3.05E-10 NNE 3.42E-09 1.92E-09 1.23E-09 6.45E-10 2.71E-10 1.51E-10 NE 4.42E-09 2.43E-09 1.54E-09 7.95E-10 3.31E-10 1.94E ENE 1.36E-08 7.32E-09 4.58E-09 2.35E-09 9.75E-10 5.39E-10 E 1.56E-04 8.30E-09 5.17E-09 2.64E-09 1.09E-09 6.06E-10 ESE 1.19E-08 6.31E-09 3.93E-09 2.00E-09 4.30E-10 4.60E-10 SE 9.42E-09 5.08E-09 3.18E-09 1.64E-09 6.83E-10 3.798-10 SSE 3.43E-09 1.90E-09 1.21E-09 6.36E-10 2.70E-10 1.515-10 5 5.22E-09 2.80E-09 1.76E-09 9.16E-10 3.91E-10 2.218-10 SSW 3.34E-09 1.95E-09 1.27E-09 6.88E-10 2.96E-10 1.67E-10 SW 3.25E-09 1.95E-09 1.29E-09 7.03E-10 3.03E-10 1.71E-10 WSW 1.02E-09 6.27E-10 4.27E-10 2.39E-10 1.05E-10 6.01E-11 W 1.78E-09 1.09E-09 7.33E-10 4.06E-10 1.76E-10 9.97E-11 WNW 4.89E-09 2.79E-09 1.80E-09 9.52E-10 4.02E-10 2.24E-10 NW 7.58E-09 4.16E-09 2.64E-09 1.37E-09 5.75E-10 3.20E-10 NNW 5.63E-09 3.08E-09 1.94E-09 1.01E-09 4.24E-10 2.36E-10 4.50 7.50 15.00 25.00 35.00 45.00 N 1.96E-10 8.35E-11 9.38E-11 2.45E-10 3.32E-10 3.31E-10 NNE 9.65E-11 4.08E-11 4.04E-11 9.95E-11 1.34E-10 1.33E-10 NE 1.17E-10 4.92E-11 4.01E-11 8.81E-11 1.16E-10 1.15E-10 ENE 3.45E-10 1.43E-10 7.87E-11 1.19E-10 1.43E-10 1.37E-10 E 3.88E-10 1.59E-10 7.20E-11 9.36E-11 1.13E-10 1.09E-10 ESE 2.94E-10 1.20E-10 4.76E-11 4.93E-11 5.70E-11 5.50E-11
'SE 2.43E-10 1.00E-10 4.17E-11 4.93E-11 5.93E-11 5.79E-11 SSE 9.80E-11 4.09E-11 2.19E-11 3.92E-11 5.24E-11 5.30E-11 S 1.44E-10 6.09E-11 2.90E-11 4.61E-11 6.18E-11 6.30E-11 SSW 1.08E-10 4.49E-11 2.24E-11 4.02E-11 5.47E-11 5.58E-11 SW 1.10E-10 4.60E-11 2.93E-11 6.5(E-11 9.23E-11 9.45E-11 WSW 3.92E-11 1.66E-11 1.69E-11 5.45E-11 8.33E-11 8.84E-11 W 6.46E-11 2.75E-11 3.64E-11 1.26E-10 1.92E-10 2.03E-10 WNW 1.44E-10 6.13E-11 7.39E-11 2.11E-10 2.97E-10 3.02E-10 NW 2.05E-10 8.81E-11 1.08E-10 2.90E-10 3.98E-10 3.98E-10 NNW 1.52E-10 6.51E-11 8.02E-11 2.20E-10 3.03E-10 3.04E-10 1
l Rev. No. 7 Page C-14 of ODCM
TABLE C-8 ELEVATED RELEASE - METEOROLOGICAL DATA - ANNUAL AVERAGE Sector Average Concentration X/Q (sec/m3)
SEGMENT BOUNDARIES IN MILES Diree-1128
.5 .75 1.0 1.9 2.5 3.5 N 1.27E-08 1.01E-08' 1.163-08 1.87E-08 1.913-08 1.70E-08 NNE 4.085-09 4.173-09 5.765-09 1.13E-08 1.193-08 1.07E-08 MB 2.37E-09 2.80E-09 4.575-09 1.04E-08 1.113-08 1.02E-08 ENE 1.53E=08 1.305-08 1.835-08 2.31E-08 2.283-08 1.96E-08 E 2.32E-08 2.155-08 2.423 08 3.16E-08 *3.013-08 2.50E-08 ESE 1.823-08 1.295-08 1.705-08 1.97E-08 1.833-08 1.48E-08 SE 2.223-08 1.655-08 1.61E-08 1.67E-08 1.533-08 1.233-08 885 1.755-08 1.035-08 9.443-09 1.05E-08 9.933-09 8.31E-09 8 1.77E-08 1.115-08 1.065-04 1.15E-08 1.093-08 9.12E-09
$8W 1.59E-04 1.108-08 1.108-08 1.27E-08 1.213-08 1.01E-08 SW 9.005-09 6.613-09 7.655-09 1.12E-08 1.105-08 9.338-99 W8W 4.20E-09 3.35E-09 3.775-09 6.13E-09 8.353-09 5.705-99 W 3.20E-09 2.943-09 3.93E-09 7.14E-09 7.415-09 6.863-09 WWW 4.84E-09 4.605-09 5.863-09 9.70E-09 9.748-09 8.47E-09 NW 9.675-09 7.435-09 9.235-09 1.65E-08 1.713-08 1.53E-08 NWW 1.17E-08 8.73E-09 9.815-09 1.54E-08 1.595-08 1.42E-08 4.5 7.5 15.0 15.0 35.0 45.0 N 1.475-08 9.605-09 4.735-09 2.755-09 1.923-09 1.483-09 NNE 9.338-09 6.21E-09 3.105-09 1.825-09 1.283-09 9.89E-10 NE 8.988-09 6.143-09 3.195-09 1.938-09 1.373-09 1.07E ENE 1.663-08 1.058-08 5.053-09 2.908-09 2.015-09 1.54E-09 E 2.06E-08 1.263-08 5.753-09 3.198-09 2.175-09 1.643-09 ESE 1.20E-08 7.213-09 3.333-09 1.785-09 1.205-09 9.048-10 SE 9.913-09 5.905-09 2.653-09 1.475-09 1.005-09 7.54E-10 SSE 4.915-09 4.305-09 2.025-09 1.143-09 7.875-10 5.98E-10 8 7.615-09 4.783-09 2.285-09 1.305-09 9.025-10 6.88E-10 58W 8.38E-09 5.155-09 2.375-09 1.335-09 9.113-10 6.905-10 SW 7.788-09 4.863-09 2.295-09 1.303-09 8.995-10 4.87E-10 WSW 4.955-09 3.315-09 '1.488-09 1.013-09 7.183-10 5.42E-10 W' 5.798-09 3.865-09 1.968-09 1.185-09 8.433-10 6.625-10 WWW 7.185-09 4.605-09 2.225-09 1.285-09 8.973-10 6.92E-10 NW 1.32E-08 8.45E-09 4.235-09 2.433-09 1.685-09 1.28E-09 NNW 1.23E-08 8.11E-09 4.025-09 2.343-09 1.633-09 1.2SE-09 Rev. No. 7 Page _S-11 of ODCM
i l
l l
TABLE C-8 (CouTxmuso) i ELEVATED RELEASE - METEOROLOGICAL DATA - ANNUAL AVERAGE Sector Average Finite Cloud Gamma X/Q (sec/m3) l SEGMENT BOUNDARIES IN MILES l l
I Direc- '
113D
.5 .75 1.0 1.5 2.5 3.5 N 1.333-07 9. ore-08 7.00E-04 4.963-04 3.213-08 2.37E-04 NNE 4.643-04 5.933-08 4.592-04 3.273-08 2.135-08 1.57E-08 NE 9.073-08 6.21R-04 4.81E-08 3.433-04 2.223-04 1.643-08 ENE 1.465-07 9.943-08 7.723-08 5.475-08 3.533-08 2.583-08 E 1.643-07 1.153-07 8.983-08 6.375-04 4.083-08 2.943-08 ESE 9.905-08 4.74E-04 5.243-08 3.705-04 2.353-04 1.693-08 i
SE 8.70E-08 5.80E-08 4.483-04 3.125-08 1.975-08 1.42E-04 SSE 4.20E-08 4.013-08
- 3.095-08 2.16E-08 1.385-08 1.013-08 S' 6.913-04 4.51E-08 3.485-08 2.445-08 1.563-08 1.14E-08 l SSW 7.285-08 4.84E-04 3.743-04 2.635-04 1.685-04 1.223-08 SW 6.403-08 4.59E-04 3.575-08 2.543-08 1.643-08 1.203-09 WSW 5.183-08 3.523-04 2.713-08 1.913-08 1.235-04 9.073-09 W 6.163-08 4.20E-08 3.25E"08 2.305-08 1.493-08 1.095-08 WWW 6.593-04 4.513-08 3.50E-08 2.495-04 1.613-04 1.183-08 NW 1.095-07 7.43E-08 5.783-04 4.125-08 2.695-08 1.99E-08 1.09E-07 7.36E-04 NNW 5.70E-08 4.04E-08 2.633-08 1.94E-04 4.5 7.5 15.0 25.0 35.0 45.0 N 1.843-04 1.113-04 5.235-09 2.98E-09 2.065-09 1.543-09 -
NNE 1.245-08 7.40E-09 3.525-09 2.025-09 1.40M-09 1.04E-09 L
NE 1.303-08 7.843-09 3.793-09 2.20E-09 1.535-09 1.17E-09 ENE 2.023 1.195-04 5.523-09 3.123-09 2.143-09 1.623-09 E 2.293-08 1.335-04 5.983-09 3.308-09 2.245-09 1.683-09 ESE 1.313-08 7.473-09 3.333-09 1.835-09 1.245-09 9.253-10 SE 1.095-08 4.253-09 2.80E-09 1.553-09 1.053-09 7.90E-10 SSE 7.495-09 4.615-09 2.123-09 1.193-09 8.145-10 4.133-10 8 8.463-09 5.193-09 2.403-09 1.355-09 9.285-10 7.015-10 SSW 9.503-09 5.533-09 2.523-09 1.415-09 9.595-10 7.222-10 SW 9.353-09 5.485-09 2.535-09 1.425-09 9.713-10 7.333-10 WSW 7.153-09 4.293-09 2.065-09 1.193-09 8.313-10 6.363-10 L W 8.423-09 5.185-09 2.493-09 1.445-09 1.013-09 7.735-10 WNW 9.233-09 5.443a05 2.543-09 1.453-09 1.005-09 7.405-10 NW 1.545-08 9.3ks-09 4.343-09 2.443-09 1.695-09 1.283-09 i NNN 1.52E-04 9.095-09 4.30E-09 2.453-09 1.695-09 1.283-09 Rev. No. 7 Page c-16 of ODCM
TABLE C-8 (CouTxmuso) 4 1 \
ELEVATED RELEASE - METEOROLOGICAL DATA - ANNUAL AVERAGE (D/Q) Sector Average Deposition (1/m2) By Downwind Sectors SEGMENT BOUNDARIES IN MILES Direc-115tB
.5 .75 1.0 1.5 2.5 3.5 N 9.53E-10 7.72Eo10 6.503-10 4.145-10 2.43E-10 1.59E-10 ,
NNE 2.903 2.68E-10 2.585-10 1.86E-10 1.193-10 7.95E-11 NE 1.853-10 2.043-10 2.265-10 1.403-10 1.223-10 8.253-11 ENE 1.41E-09 1.20L-09 1.053-09 7.093-10 4.313-10 2.833-10 i E 2.08E-09 1.735-09 1.513-09 9.913-10 5.945-10 3.893-10 l ESE 1.48E-09 1.482-09 1.20E-09 7.353-10 4.173-10 2.69E-10 .
SE 1.94E-09 1.44E-09 1.16E-09 6.793-10 3.713-10 2.375-10 ;
SSE 1.24E-09 9.213-10 6.935-10 3.865-10 2.035-10 1.27E-10 ;
3 1.15E-09 8.67E-10 6.413-10 3.743-10 1.983-10 1.253-10 ,
ssW 1.063-09 8.213-10 6.543-10 3.933-10 2.195-10 -1.403-10 SW 4.853-10 4.15E-10 3.691-10 2.443-10 1.513-10 9.983-41 WSW 1.62E-10 1.40E-10 1.265-10 0.523-11 5.375-11 3.493i11 W 1.51E-10 1.358-10 1.25E+10 8.753-11 5.523-11 3.683-11 2.745-10 WNW 3.095-10 2.605-10 1.843-10 1.142-10 7.72E-11 NW 7.40E-10 6.253-10 5.503-10 3.443-10 2.205-10 1.46E-10 NNW 9.30E-10 7.295-10 5.898-10 3.59E-10 2.035-10 1.312-10 4.5 7.5 15.0 25.0 35.0 45.0 N 1.095-10 4.925-11 1.713-11 7.90E-12 4.753-12 3.175-12 NNE 5.495-11 3.46E-11 8.483-12 3.813-12 2.243-12 1.48E-12 i NE 5.713-11 2.553-11 8.715-13 3.853-13 2.233-12 1.465-12 l ENE 1.953-10 0.785-11 3.033-11 1.383-11 8.223 5.443-12 l E- 2.685-10 1.213-10 4.175-11 1.913-11 1.143-11 7.593-12 ESE 1.85E-10 6.363-11 2.913-11 1.363-11 8.225-12 5.503-12 SE 1.623-10. 7.353-11 2.573-11 1.223-11 7.453-12 5.013-12 SSE 8.663-11 3.943-11 1.395-11 6.495-12 4.163-12 2.812-12 S 4.588-11 3.903-11 1.375-11 6.573-12 4.063-12 2.745-12 SSW 9.635-11 4.36E-11 1.523-11 7.155-12 4.363-12 2.935-12 EN 6.485-11 3.103-13 1.073-11 4.495-12 2.913-12 1.935-12 Wsw 2.413-11 1.09R-11 3.743-12 1.713-12 1.035-12 6.753-13 W 2.545-11 1.153-11 3.975-12 1.793-12 1.063-13 7.013-13 WNW 5.33E-11 2.395-11 4.253-12 3.723-12 2.195-12 1.453-12
- NW 1.01E-10 4.535-11 1.573-11 7.155-12 4.263-12 2.83E-12 NNW 9.01E-11 4.085-11 1.433-11 6.653-12 4.035-12 2e70E-12 4
Rev. No. 7 Page c-17 of ODCM
--e.- w-wo w,<w-- w. - w - - -*mwn,e .,e--
w-m-- w--
i i
t TABLE C-9 f REACTOR VENT - METEOROLOGICAL DATA - GRAZING Sector Average Concentration X/Q (sec/m3)
SEGMENT BOUNDARIES IN MILES Direction !
.50 .75 1.00 1.50 2.50 3.50 I N 5.69E-07 3.34E-07 2.42E-07 1.59E-07 9.47E-08 6.62E-08 NNE 2.53E-07 1.51E-07 1.11E-07 7.46E-08 4.51E-08 3.16E-08 NE 2.69E-07 1.61E-07 1.18E-07 7.77E-04 4.55E-08 3.11E-08 ENE 6.48E-07 3.84E-07 2.73E-07 1.69E-07 9.10E-08 5.96E-08 E 6.19E-07 3.61E-07 2.53E-07 1.55E-07 8.35E-08 5.48E-08 ESE 3.30E-07 1.92E-07 1.34E-07 8.30E-08 4.53E-08 2.99E-08 SE 2.46E-07 1.45E-07 1.0$E-07 6.77E-08 3.85E-08 2.60E-08 SSE 9.35E-08 5.60E-08 4.27E-08 3.08E-08 1.99E-08 1.43E-08 S 1.18E-07 6.78E-08 5.44E-08 4.17E-08 2.81E-08 2.05E-08 SSW 1.08E-07 7.03E-08 5.79E-08 4.57E-08 3.08E-08 2.21E-08 SW 1.26E-07 8.48E-08 7.04E-08 5.64E-08 3.87E-08 2.81E-08 WSW 6.02E-08 3.91E-08 3.43E-08 3.19E-04 2.55E-08 1.98E-08 W 1.22E-07 7.66E-08 6.34E-08 5.39E-08 4.16E-08 3.25E-08 F WNW 3.47E-07 2.10E-07 1.58E-07 1.11E-07 7.02E-08 5.05E-08 NW 5.46E-07 3.22E-07 2.35E-07 1.56E-07 9.44E-08 6.65E-08 NNW 4.61E-07 2.68E-07 1.94E-07 1.28E-07 s
7.74E-08 5.46E-08 4.50 7.50 15.00 25.00 35.00 45.00 N 5.02E-08 2.83E-08 1.29E-08 7.27E-09 4.99E-09 3.77E-09 NNE 2.38E-08 1.32E-08 5.84E-09 3.20E-09 2.17E-09 1.62E-09 NE 2.32E-08 1.25E-08 5.35E-09 2.88E-09 1.92E-09 1.43E-09 ENE 4.31E-04 2.23E-08 9.08E-09 4.75E-09 3.14E-09 2.31E-09 E 3.98E-04 2.08E-08 8.53E-09 4.50E-09 2.99E-09 2.20E-09 ESE 2.18E-08 1.15E-08 4.71E-09 2.49E-09 1.66E-09 1.22E-09 '
SE 1.92E-08 1.03E-08 4.35E-09 2.35E-09 1.58E-09 1.17E-09 SSE 1.09E-08 6.20E-09 2.73E-09 1.56E-09 1.07E-09 8.06E-10 S- 1.59E-08 9.05E-09 4.06E-09 2.26E-09 1.55E-09 1.17E-09 SSW 1.69E-08 9.29E-09 3.93E-09 2.06E-09 1.40E-09 1.03E-09 r
SW 2.15E-08 1.20E-08 5.16E-09. 2.77E-09 1.86E-09 1.38E-09 WSW 1.58E-08 9.38E-09 4.36E-09 2.46E-09 1.69E-09 1.27E-09 W 2.64E-08 1.64E-08 8.28E-09 4.94E-09 3.49E-09 2.70E-09 WNW 3.90E-08 2.27E-08 1.09E-08 6.36E-09 4.45E-09 3.42E-09 NW 5.07E-08 2.91E-08 1.38E-08 8.00E-09 5.59E-09 4.28E-09 NNW 4.17E-08 2.39E-08 1.13E-08 6.49E-09 4.51E-09 3.45E-09 Rev. No. 7 Page C-18 of ODCM
- - _ _ - - - - .. . .- . - -~___----.-._- -_
l I
i TABLE C-9 (CONTINUED) !
REACTOR VENT - METEOROLOGICAL DATA - GRAZING (D/Q) Sector Average Deposition (1/m2) By Downwind Sectors ,
SEGMENT BOUNDARIES IN MILES ,
I Direction i
.50 .75 1.00 1.50 2.50 3.50 )
l N 5.80E-09 3.26E-09 2.16E-09 1.17E-09 5.20E-10 2.99E-10 l NNE 2.44E-09 1.38E-09 9.24E-10 5.08E-10 2.28E-10 1.32E-10 i NE 2.96E-09 1.64E-09 1.12E-09 6.15E-10 2.72E-10 1.56E-10 ENE 1.07E-08 6.00E-09 3.95E-09 2.12E-09 9.28E-10 5.28E-10 E 1.24E-08 6.81E-09 4.42E-09 2.34E-09 1.01E-09 5.74E-10 ESE 8.02E-09 4.41E-09 2.85E-09 1.50E-09 6.50E-10 3.69E-10 SE 6.04E-09 3.42E-09 2.26E-09 1.21E-09 5.33E-10 3.06E-10 SSE 2.04E-09 1.17E-09 7.84E-10 4.29E-10 1.95E-10 1.14E-10 S 4.36E-09 2.45E-09 1.60E-09 8.44E-10 3.78E-10 2.20E-10 SSW 1.22E-09 1.99E-09 8.61E-10 4.86E-10 2.30E-10 1.37E-10 i i
SW 1.71E-09 1.07E-09 7.75E-10 4.51E-10 2.17E-10 1.30E-10 WSW 6.50E-10 4.01E-10 2.88E-10 1.66E-10 8.26E-11 5.02E-11 ;
W 1.03E-09 6.41E-10 4.66E-10 2.75E-10 1.35E-10 8.10E-11 WNW 3.13E-09 1.84E-09 1.27E-09 7.17E-10 3.29E-10 1.92E-10 NW 5.20E-09 2.94E-09 1.96E-09 1.07E-09 4.79E-10 2.76E-10 '
NNW 4.48E-09 2.51E-09 1.67E-09 9.02E-10 4.02E-10 2.31E-10 4.50 7.50 15.00 25.00 35.00 45.00 N 1.95E-10 8.11E-11 2.57E-11 .1.10E-11 6.26E-12 4.11E-12 NNE 8.62E-11 3.58E-11 1.13E-11 4.74E-12 2.67E-12 1.73E-12 NE 1.02E-10 4.19E-11 1.30E-11 5.39E-12 3.00E-12 1.93E-12 ENE 3.44E-10 1.42E-10 4.46E-11 1.88E-11 1.06E-11 6.87E-12 E 3.72E-10 1.54E-10 4.86E-11 1.15E-11 2.05E-11 7.41E-12 ESE 2.39E-10 9.91E-11 3.15E-11 1.34E-11 7.56E-12 4.88E-12 SE 2.00E 8.37E-11 2.69E-11 1.17E-11 6.80E-12 4.46E-12 SSE 7.53E-11 3.20E-11 1.05E-11 4.72E-12 2.79E-12 1.87E-12 S 1.46E-10 6.31E-11 2.17E-11 1.03E-11 6.33E-12 4.32E-12 SSW 9.13E-11 3.93E-11 1.295-11 '5.83E-12 3.47E-12 2.31E-12 SW 8.65E-11 3.70E-11 1.19E-11 5.26E-12 3.07E-12 2.03E-12 WSW 3.37E-11 1.46E-11 4.87E-12 2.18E-12 1.28E-12 8.46E-13 W 5.40E-11 2.30E-11 7.42E-12 3.23E-12' 1.86E-12 1.22E-12 WNW 1.26E-10 5.2SE-11 1.66E-11 7.05E-12 4.00E-12 2.62E-12 NW 1.81E-10 7.52E-11 2.39E-11 1.02E-11 5.81E-12 3.81E-12 NNW 1.51E-10 6.31E-11 2.02E-11 8.68E-12 4.98E-12 3.28E-12
_ - _ _ __ Mn]% - k-- .-. - - - - - - - - - - - -
i TABLE C-10 REFUEL FLOOR VENT - NETEOR0 LOGICAL DATA - GRAZING Sector Average Concentration X/Q (sec/m3) i SEGMENT BOUNDARIES IN MILES )
Direction
.50 .75 1.00 1.50 2.50 3.50 N 5.69E-07 3.34E-07 2.42E-07 1.59E-07 9.47E-08 6.62E-08 NNE 2.53E-07 1.51E-07 1.11E-07 7.46E-08 4.51E-08 3.16E-08 NE 2.69E-07 1.61E-07 1.18E-07 7.77E-08 4.55E-08 3.11E-08 ENE 6.48E-07 3.84E-07 2.73E-07 1.69E-07 9.10E-08 5.96E-08 E 6.19E-07 3.61E-07 2.53E-07 1.55E-07 8.35E-08 5.48E-08 ESE 3.30E-07 1.92E-07 1.34E-07 8.302-08 4.53E-08 2.99E-08 SE 2.46E-07 1.45E-07 1.05E-07 6.77E-08 3.85E-08 2.60E-08 SSE 9.35E-08 5.60E-08 4.27E-08 3.08E-08 1.99E-08 1.43E-08 l
S 1.18E-07 6.78E-08 5.44E-08 4.17E-08 2.81E-08 2.05E-08 SSW 1.08E-07 7.03E-08 5.79E-08 4.57E-08 3.08E-08 2.21E-08 SW 1.26E-07 8.48E-08 7.04E-08 5.64E-08 3.87E-08 2.81E-08 WSW- 6.02E-08 3.91E-08 3.43E-08 3.19E-08 2.55E-08 1.98E-08 L W 1.22E-07 7.66E-08 6.34E-08 5.39E-08 4.16E-08 3.25E-08 WNW 3.47E-07 2.10E-07 1.58E-07 1.11E-07 7.02E-08 5.05E-08 NW 5.46E-07 3.22E-07 2.35E-07 1.56E-07 9.44E-08 6.65E-08 NNW 4.61E-07 2.68E-07 1.94E-07 1.28E-07 7.74E-08 5.46E-08 4
4.50 7.50 15.00 25.00 35.00 45.00 l N 5.02E-08 2.83E-08 1.29E-08 7.27E-09 4.99E-09 3.77E-09 NNE 2.38E-08 1.32E-04 5.84E-09 3.20E-09 2.17E-09 1.62E-09 NE 2.32E-08 1.25E-08 5.35E-09 2.88E-09 1.92E-09 1.43E-09 ENE 4.31E-08 2.23E-08 9.08E-09 4.75E-09 3.14E-09 2.31E-09 '
E 3.98E-04 2.08E-08 8.53E-09 4.50E-09 2.99E-09 2.20E-09 ESE 2.18E-08 1.15E-08 4.71E-09 2.49E-09 1.66E-09 1.22E-09 SE 1.92E 1.03E-04 4.35E-09 2.35E-09 1.58E-09 1.17E-09 SSE 1.09E-08 6.20E-09 2.79E-09 1.56E-09 1.07E-09 8.06E-10 S 1.59E-04 9.05E-09 4.06E-09 2.26E-09 1.55E-09 1.17E-09 l SSW 1.69E-08 9.29E-09 3.93E-09 2.09E-09 1.40E-09 1.03E-09 SW 2.15E-08 1.20E-08 5.16E-09 2.77E-09 1.86E-09 1.38E-09 WSW 1.58E-08 9.38E-09 4.36E-09 2.46E-09 1.69E-09 1.27E-09 W 2.64E-08 1.64E-08 8.28E-09 4.94E-09 3.49E-09 2.70E-09 WNW 3.90E-08 2.27E-08 1.09E-08 6.36E-09 NW 4.45E-09 3.42E-09 5.07E-08 2.91E-08 1.38E-08 8.00E-09 5.59E-09 4.28E-09 NNW 4.17E-08 2.39E-08 1.13E-08 6.49E-09 4.51E-09 3.45E-09
_ _______ __Juh3h_ _5L ___ ---- -
I TABLE C-10 (CONTINUED)
REFUEL FLOOR VENT - METEOROLOGICAL DATA - GRAZING (D/Q) Sector Average Deposition (1/m2) By Downwind Sectors i SEGNENT BOUNDARIES IN MILES Direction i
.50 .75 1.00 1.50 2.50 3.50 N 5.80E-09 3.26E-09 2.16E-09 1.17E-09 5.20E-10 2.99E-10 NNE 2.44E-09 1.38E-09 9.24E-10 5.08E-10 2.28E-10 1.32E-10 NE 2.96E-09 1.68E-09 1.12E-09 6.15E-10 2.72E-10 1.56E-10 ENE 1.07E-08 6.00E-09 3.95E-09 2.12E-09 9.28E-10 5.28E-10 E 1.24E-08 6.81E-09 4.42E-09 2.34E-09 1.01E-09 5.74E-10 ESE 8.02E-09 4.41E-09 2.85E-09 1.50E-09 6.50E-10 3.69E-10 SE 6.04E-09 3.42E-09 2.26E-09 1.21E-09 5.33E-10 3.06E-10 SSE 2.04E-09 1.17E-09 7.84E-10 4.29E-10 1.95E-10 1.14E-10 S :
4.36E-09 2.45E-09 1.60E-09 8.44E-10 3.78E-10 2.20E-10 SSW 1.99E-09 1.22E-09 8.61E-10 4.86E-10 2.30E-10 1.37E-10 SW 1.71E-09 1.07E-09 7.75E-10 4.51E-10 2.17E-10 1.30E-10 WSW 6.50E-10 4.01E-10 2.88E-10 1.66E-10 8.26E-11 5.02E-11 W 1.03E-09 6.41E-10 4.66E-10 2.75E-10 1.35E-10 8.10E-11 WNW 3.13E-09 1.84E-09 1.27E-09 7.17E-10 3.29E-10 NW 5.20E-09 1.92E-10 2.94E-09 1.96E-09 1.07E-09 4.79E-10 2.76E-10 NNW 4.48E-09 2.51E-09 1.67E-09 9.02E-10 4.02E-10 2.31E-10 4.50 7.50 15.00 25.00 -35.00 45.00 N 1.95E-10 8.11E-11 2.57E-11 1.10E-11 6.26E-12 4.11E-12 NNE 8.62E-11 3.58E-11 1.13E-11 4.74E-12 2.67E-12 1.73E-12 NE 1.02E-10 4.19E-11 1.30E-11 5.39E-12 3.00E-12 1.93E-12 ENE 3.44E-10 1.42E-10 4.46E-11 1.88E-11 1.06E-11 6.87E-12 E 3.72E-10 1.54E-10 4.86E-11 2.05E-11 1.15E-11 7.41E-12 ESE 2.39E-10 9.91E-11 3.15E-11 1.34E-11 7.56E-12 4.88E-12 SE 2.00E-10 8.37E-11 2.69E-11 1.17E-11 6.80E-12 4.46E-12 SSE 7.53E-11 3.20E-11 1.05E-11 4.72E-12 2.79E-12 1.87E-12 S 1.46E-10 6.31E-11 2.17E-11 1.03E-11 6.33E-12 4.32E-12 SSW 9.13E-11 i 3.93E-11 1.29E-11 5.43E-12 3.47E-12 2.31E-12 SW 8.65E-11 3.70E-11 1.19E-11 5.26E-12 3.07E-12 2.03E-12 WSW 3.37E-11 1.46E-11 4.87E 2.18E-12 1.28E-12 8.46E-13 W 5.40E-11 2.30E-11 7.42E-12 3.23E-12 1.86E-12 1.22E-12 WNW 1.26E-10 5.28E-11 1.66E-11 7.05E-12 4.00E-12 2.62E-12
'NW 1.81E-10 7.52E-11 2.39E-11 1.02E-11 5.81E-12 3.81E-12 NNW 1.51E-10 6.31E-11 2.02E-11 8.68E-12 4.98E-12 3.28E-12 Rev. No. 7 Page C-21 of ODCM
i i
I TABLE C-11 j TURBINE VENT - METEOROLOGICAL DATA - GRAZING Sector Aver 8ge Concentration X/Q (sec/m3) l SEGMENT BOUNDARIES IN MILES l l
Direction
.50 .75 1.00 1.50 2.50 3.50 N 4.34E-07 2.64E-07 1.99E-07 1.39E-07 8.64E-08 6.14E-08 NNE 1.96E-07 1.22E-07 9.33E-08 6.65E-08 4.18E-08 2.96E-08 NE 2.04E-07 1.28E-07 9.40E-08 6.86E-08 4.17E-08 2.89E-08 ENE 4.85E-07 3.01E-07 2.23E-07 1.45E-07 8.12E-08 5.38E-08 E 4.94E-07 3.01E-07 2.18E-07 1.39E-07 7.73E-08 5.13E-08 ESE 2.65E-07 1.61E-07 1.17E-07 7.57E-08 4.26E-08 2.85E-08 SE 1.93E-07 1.20E-07 9.12E-08 6.19E-08 3.64E-08 2.48E-08 SSE 7.79E-08 4.90E-08 3.91E-08 2.95E-08 1.95E-08 1.40E-08 S 1.06E-07 6.26E-08 S.21E-08 4.12E-08 2.80E-08 2.05E-08 j SSW 9.36E-08 6.43E-08 5.55E-08 4.55E-08 3.09E-08 2.22E-08 <
SW 1.04E-07 7.51E-08 6.59E-08 5.54E-08 3.86E-08 2.80E-08 !
WSW 5.13E-08 3.53E-08 3.30E-04 3.22E-04 2.59E-08 2.01E-08 W !
9.54E-08 6.43E-08 5.70E-08 5.19E-08 4.12E-08 3.24E-08 WNW 2.64E-07 1.68E-07 1.33E-07 9.96E-08 6.59E-08 4.80E-08 NW 4.12E-07 2.53E-07 1.93E-07 1.37E-07 8.64E-08 6.19E-08 NNW 3.59E-07 2.16E-07 1.62E-07 1.13E-07 7.12E-08 5.10E-08 4.50 7.50 15.00 25.00 35.00 45.00 N 4.70E-08 2.68E-08 1.24E-08 7.00Er09 4.82E-09 3.64E-09 NNE 2.25E-08 1.26E-08 5.61E-09 3.09E-09 2.09E-09 1.56E-09 NE 2.17E-08 1.18E-08 5.09E-09 2.75E-09 1.84E-09 1.37E-09 ENE 3.92E-04 2.053-08 8.41E-09 2.93E-09 4.42E-09 2.16E-09 E 3.75E-08 1.98E-08 8.14E-09 4.31E-09 2.87E-09 2.12E-09 ESE 2.09E-08 1.11E-08 4.56E-09 2.42E-09 1.61E-09 -1.19E-09 SE 1.85E-08 9.98E-09 4.23E-09 2.29E-09 1.54E-09 1.15E-09 SSE 1.08E-08 6.11E-09 2.75E 1.54E-09 1.06E-09 7.99E-10 S 1.59E-08 9.03E-09 4.05E-09 2.26E-09 1.54E-09 1.16E-09 SSW 1.69E-08 9.27E-09 3.91E-09 2.08E-09 1.39E-09 1.02E-09 SW 2.14E-08 1.19E-08 5.13E-09 2.76E-09 1.84E-09 1.37E-09 WSW 1.60E-08 9.45E-09 4.38E-09 2.47E-09 1.69E-09 1.28E-09 .
W 2.63E-08 1.64E-08 8.30E-09 4.96E-09 3.51E-09 2.70E-09 WNW 3.74E-08 2.20E-08 1.07E-08 6.26E-09 4.39E-09 3.37E-09 NW 4.77E-08 2.78E-08 1.33E-08 7.78E-09 5.45E-09 4.18E-09 NNW 3.93E-06 2.28E-08 1.09E-08 6.30E-09 4.40E-09 3.36E-09 f1 Rev.-No. 7 Page c-22 of ODCM y
J i
l i
TABLE C-11 (CONTINUED) j 1
TURBINE VENT - METEOROLOGICAL DATA - GRAZING
]
(D/Q) Sector Average Concentration (1/m2) By Downwind Sectors SEGMENT BOUNDARIES IN MILES Direction
.50 .75 1.00 1.50 2.50 3.50 N 4.72E-09 2.73E-09 1.85E-09 1.02E-09 4.60E-10 2.66E-10 NNE 1.99E-09 1.16E-09 7.95E-10 4.46E-10 2.03E-10 1.18E-10 NE 2.38E-09 1.41E-09 9.672-10 5.43E-10 2.44E-10 ENE 1.41E-10 9.02E-09 5.22E-09 3.512-09 1.93E-09 8.57E-10 4.91E-10 E 1.08E-08 6.15E-09 4.07E-09 2.20E-09 9.65E-10 5.50E-10 ESE 7.11E-09 4.02E-09 2.65E-09 1.43E-09 6.25E-10 3.57E-10 .
SE 5.32E-09 3.11E-09 2.10E-09 1.15E-09 5.13E-10 2.96E-10 SSE 1.87E-09 1.09E-09 7.42E-10 4.11E-10 1.89E-10 1.11E-10 S 4.28E 2.41E-09 1.58E-09 8.34E-10 3.74E-10 2.18E-10 l SSW 1.89E-09 1.18E-09 8.38E-10 4.79E-10 2.28E-10 1.36E-10 SW 1.55E-09 1.00E-09 7.39E-10 2.12E-10 4.38E-10 1.27E-10 ,
WSW 5.97E-10 3.78E-10 2.76E-10 1.62E-10 8.07E-11 4.91E-11 W 8.75E-10 5.64E-10 4.24E-10 WNW 2.49E-09 2.56E-10 1.27E-10 7.65E-11
{ 1.53E-09 1.09E-09 6.29E-10 2.93E-10 1.72E-10 i NW 4.12E-09 2.41E-09 1.65E-09 NNW 9.20E-10 4.18E-10 2.42E-10 3.69E-09 2.13E-09 1.44E-09 7.94E-10 3.58E-10 2.07E-10 l 4.50 7.50 15.00 25.00 35.00 45.00 N 1.74E-10 7.28E-11 2.30E-11 9.90E-12 5.71E-12 3.79E NNE 7.74E-11 3.22E-11 1.01E-11 4.27E-12 2.42E-12 1.58E-12 NE 9.18E-11 3.80E-11 1.17E-11 4.87E-12 2.73E-12 1.77E-12' i ENE 3.21E-10 1.33E-10 4.14E-11 1.76E-11 1.00E-11 6.56E-12 i E 3.58E-10 1.48E-10 4.66E-11 1.98E-11 1.12E-11 7.26E-12 ESE 2.32E-10 9.65E-11 3.05E-11 1.31E-11 7.45E-12 4.84E-12 SE 1.94E-10 8.17E-11 2.62E-11 1.16E-11 6.77E-12 4.49E-12 SSE 7.33E-11 3.12E-11 1.03E-11 4.64E-12 2.80E-12 1.89E-12 S 1.453-10 6.26E-11 2.15E-11 1.02E-11 6.30E-12 4.32E-12 9.04E-11 SSW 3.88E-11 1.27E-11 5.77E-12 3.45E-12~ 2.31E-12 l SW 8.47E-11 3.62E-11 1.16E-11 5.12E-12 3.00E-12 1.99E-12
! WSW 3.29E-11 1.42E-11 4.71E-12 2.11E-12 1.24E-12 8.22E-13 W 5.11E-11 2.18E-11 6.98E-12 3.04E-12 1.76E-12 1.16E-12 i
WNW 1.14E-10 4.76E-11 1.49E-11 6.35E-12 3.64E-12 2.40E-12 NW 1.59E-10 6.66E-11 2.10E-11 9.06E-12 5.23E-12 3.47E-12 l
NNW 1.36E-10 5.70E-11 1.82E-11 7.88E-12 4.57E-12 3.04E-12 l
Rev. No. 7 Page C-23 of ODCM
l i
TABLE C-12 ,
RADWASTE VENT - METEOROLOGICAL DATA - GRAZING Sector Average' Concentration X/Q (sec/m3) !
SEGMENT BOUNDARIES IN MILES J
Direction
.50 .75 1.00 1.50 2.50 3.50 N 9.18E-07 5.95E-07 4.45E-07 2.89E-07 1.64E-07 1.12E-07 NNE 4.17E-07 2.80E-07 2.12E-07 1.38E-07 7.70E-08 5.15E-08 NE 4.45E-07 2.91E-07 2.16E-07 1.36E-07 7.31E-08 4.79E-08 ENE 1.05E-06 6.37E-07 4.45E-07 2.61E-07 1.31E-07 8.29E-08 E 9.60E-07 5.75E-07 4.02E-07 2.38E-07 1.22E-07 7.77E-08 E8E 5.18E-07 3.11E-07 2.19E-07 1.31E-07 6.76E-08 4.33E-08 SE 4.23E-07 2.60E-07 1.87E-07 1.15E-07 6.08E-08 3.95E-08 SSE 1.73E-07 1.20E-07 9.37E-08 6.30E-08 3.63E-08 2.47E-08 S 2.29E-07 1.59E-07 1.28E-07 8.78E-08 5.09E-08 3.45E-08 SSW 2.37E-07 1.80E-07 1.45E-07 9.83E-08 5.45E-08 3.57E-08 SW 2.82E-07 2.23E-07 1.83E-07 1.26E-07 7.14E-08 4.73E-08
- WSW 1.35E-07 1.27E-07 1.15E-07 8.92E-08 5.57E-08 3.89E-08 i W 2.47E-07 2.11E-07 1.87E-07 1.47E-07 9.83E-08 7.22E-08 WNW 6.04E-07 4.20E-07 3.27E-07 2.22E-07 1.34E-07 9.52E-08 ,
NW 8.96E-07 5.89E-07 4.44E-07 2.91E-07 1.70E-07 1.20E-07 NNW 7.33E-07 4.78E-07 3.61E-07 2.38E-07 1.39E-07 9.70E-08 '
4.50 7.50 15.00 25.00 35.00 45.00 ,
e N 8.38E-08 4.59E-08 2.02E-08 1.10E-08 7.39E-09 5.49E-09 NNE 3.78E-08 2.01E-08 8.53E-09 4.55E-09 3.04E-09 2.24E-09
, NE 3.47E-08 1.80E-08 7.44E-09 3.91E-09 2.58E-09 1.90E-09 i4 ENE 5.89E-08 2.98E-08 1.19E-08 6.13E-09 4.02E-09 2.93E-09 E 5.54E-08 2.83E-08 1.14E-08 5.91E-09 3.89E-09 2.84E-09 ESE 3.10E-08 1.59E-08 6.36E-09 3.31E-09 2.18E-09 1.60E-09 SE 2.86E-08 1.49E-08 6.10E-09 3.22E-09 2.14E-09 1.57E-09 4
-SSE 1.84E-08 1.00E-08 4.33E-09 2.35E-09 1.58E-09 1.17E-09 S -2.56E-08 1.38E-08 5.88E-09 3.18E-09 2.14E-09 1.59E-09 SSW 2.58E-08 1.33E-08 5.35E-09 2.78E-09 1.83E-09 1.34E-09 l SW 3.44E-08 1.79E-08 7.32E-09 3.83E-09 2.53E-09 1.85E-09 WSW 2.92E-08 1.60E-08 6.99E-09 3.78E-09 2.54E-09 1.88E-09 W 5.63E-08 3.30E*08 1.54E-08 8.68E-09 5.93E-09 4.45E-09 i.s WNW 7.29E-08 4.17E-08 1.92E-08 1.07E-08 7.32E-09 5.48E-09 L
NW 9.11E-08 5.18E-08 2.37E-08 1.32E-08 9.00E-09 6.73E-09 NNW 7.36E-08 4.15E-08 1.88E-08 1.04E-08 7.10E-09 5.30E-09 Rev. No. 7 Page C-24 of ODCM
.. . .~ __ _ _ _ . _ . _ . _ _ _. _. ___ _ _
l TABLE C-12 (CONTINUED) l RADWASTE VENT - METEOROLOGICAL DATA - GRAZING (D/Q) Sector Average Deposition (1/m2) By Downwind Sectors SEGMENT BOUNDARIES IN MILES i
Direction 1
.50 .75 1.00 1.50 2.50 3.50 N 7.94E-09 4.35E-09 2.75E-09 1.43E-09 5.97E-10 3.31E-10 NNE 3.38E-09 1.88E-09 1.20E-09 6.30E-10 2.65E-10 1.47E-10 NE 4.10E-09 2.27E-09 1.44E-09 7.45E-10 3.11E-10 1.72E-10 ENE 1.42E-08 7.67E-09 4.81E-09 2.47E-09 1.03E-09 5.68E-10 l E 1.54E-08 8.22E-09 5.13E-09 2.62E-09 1.09E-09 6.04E-10 ESE ]
9.85E-09 5.24E-09 3.27E-09 1.67E-09 6.95E-10 3.85E-10 SE 8.00E-09 4.30E-09 2.70E-09 1.39E-09 5.80E-10 3.23E-10 SSE 2.81E-09 1.54E-09 9.80E-10 5.14E-10 2.18E-10 1.22E-10 l S 5.63E-09 2.95E-09 1.84E-09 9.47E-10 4.04E-10 2.29E-10 l SSW 3.03E-09 1.74E-09 1.14E-09 6.11E-10 2.63E-10 1.49E-10 1 SW 2.77E-09 1.64E-09 1.08E-09 5.89E-10 2.54E-10 1.43E-10 WSW 1.01E-09 6.08E-10 4.11E-10 2.28E-10 1.00E-10 5.73E-11 W 1.69E-09 1.02E-09 6.85E-10 3.77E-10 1.64E-10 9.24E-11 i WNW 4.72E-09 2.69E-09 1.74E-09 9.19E-10 3.88E-10 2.16E-10 NW 7.29E-09 4.01E-09 2.55E-09 1.33E-09 5.57E-10 3.10E-10 NNW 6.11E-09 3.34E-09 2.11E-09 1.10E-09 4.60E-10 2.56E-10 4.50 7.50 15.00 25.00 35.00 45.00 N 2.13E-10 9.09E-11 1.04E-10 2.71E-10 3.67E-10 3.66E-10 NNE 9.46E-11 4.02E-11 4.39E-11 1.13E-10 1.53E-10 1.52E-10 NE 1.10E-10 4.63E-11 4.18E-11 9.69E-11 1.29E-10 1.28E-10 ENE 3.64E-10 1.51E-10 8.52E-11 1.29E-10 1.55E-10 1.47E-10 E 3.86E-10 1.59E-10 7.59E-11 1.07E-10 1.31E-10 1.28E-10 ESE 2.47E-10 1.01E-10 4.22E-11 5.03E-11 6.12E-11 6.03E-11 SE 2.07E-10 8.55E-11 3.71E-11 4.95E-11 6.24E-11 6.21E-11 SSE 7.91E-11 3.30E-11 1.87E-11 3.72E-11 5.13E-11 5.24E-11 S 1.49E-10 6.33E-11 3.03E-11 4.75E-11 6.33E-11 6.43E-11 SSW 9.65E-11 4.03E-11 2.19E-11 4.34E-11 6.02E-11 6.17E-11 SW 9.26E-11 3.87E-11 2.77E-11 6.85E-11 9.78E-11 1.01E-10 WSW 3.74E-11 1.59E-11 1.74E-11 5.77E-11 8.87E-11 9.44E-11 W 5.98E-11 2.55E-11 3.65E-11 1.29E-10 1.98E-10 2.10E-10 WNW 1.39E-10 5.94E-11 7.59E-11 2.21E-10 3.12E-10 3.18E-10 NW 1.99E-10 8.56E-11 1.08E-10 2.99E-10 4.12E-10 4.15E-10 NNW 1.65E-10 7.06E-11 8.73E-11 2.41E-10 3.33E-10 3.34E-10 Rev. No. 7 Page C-25 of ODCM
TABLE C-13 ELEVATED RELEASE - METEOROLOGICAL DATA - GRAZING Sector Aver 8ge Concentr8 tion X/Q (sec/m3)
SEGMENT BOUNDARIES IN MILES Direction
.50 .75 1.00 1.50 2.50 3.50 -
N 1.38E-08 1.10E-08 1.27E-08 1.80E-08 2.05E-08 1.81E-04 NNE 4.03E-09 4.36E-09 5.99E-09 9.92E-09 1.22E-08 1.11E-08 NE 2.68E-09 2.98E-09 4.53E-09 8.31E-09 1.07E-08 9.94E-09 ENE 1.76E-08 1.49E-08 1.73E-08 2.37E-08 2.54E-08 2.19E-08 E 2.47E-08 2.30E-08 2.57E-04 3.19E-08 3.13E-04 2.61E-08 ESE 1.72E-08 1.47E-08 1.57E-08 1.01E-08 1.69E-08 1.39E-08 l SE 2.29E-04 1.62E-08 1.52E-08 1.54E-08 1.35E-08 1.04E-04 SSE 1.90E-08 1.07E-08 9.69E-09 9.82E-09 9.12E-09 7.63E-09 S 1.93E-04 1.16E-08 1.08E-08 1.11E-08 1.05E-08 8.88E-09 SSW 1.63E-08 1.10E-08 1.04E-08 1.15E-08 1.10E-08 9.23E-09 SW 9.49E-09 7.11E-09 7.60E-09 9.58E-09 9.93E-09 8.48E-09 WSW 3.60E-09 2.93E-09 3.26E-09 4.65E-09 5.55E-09 5.05E-09 W 2.41E-09 1.94E-09 2.83E-09 4.96E-09 6.26E-09 5.74E-09 5.40E-09 WNW 4.41E-09 4.48E-09 7.71E-09 8.50E-09 7.37E-09 NW 9.43E-09 7.72E-09 9.54E-09 1.45E-08 1.70E-08 1.51E-08 4 NNW 1.28E-08 9.34E-09 1.04E-08 1.43E-08 1.63E-08 1.46E-08 4.50 7.50 15.00 25.00 35.00 45.00 N 1.56E-04 1.02E-08 5.01E-09 2.92E-09 2.04E-09 1.57E-09 NNE 9.71E-09 6.52E-09 3.30E-09 1.96E-09 1.39E-09 1.08E-09 NE 8.83E-09 6.11E-09 3.24E-09 1.98E-09 1.43E-09 1.12E-09 ENE 1.85E-04 1.18E-04 5.68E-09 3.28E-09 2.28E-09 1.75E-09 E 2.15E-08 1.32E-04 6.07E-09 3.39E-09 2.32E-09 1.76E-09 ESE 1.13E-08 6.83E-09 3.10E-09 1.72E-09 1.17E-09 8.83E-10 '
SE 8.78E-09 5.28E-09 2.42E-09 1.36E-09 9.41E-10 7.17E-10 SSE 4.37E-09 4.00E-09 1.92E-09 1.11E-09 7.74E-10 5.93E-10 5 7.45E-09 4.73E-09 2.29E-09 1.33E-09 9.28E-10 7.12E-10 SSW 7.68E-09 4.79E-09 2.25E-09 1.28E-09 8.84E-10 6.75E-10 SW 7.13E-09 4.52E-09 2.18E-09 1.27E-09 8.94E-10 6.94E-10 WSW 4.44E-09 3.02E-09 1.57E-09 9.56E-10 6.88E-10 5.43E-10 W 5.05E-09 3.43E-09 1.78E-09 1.09E-09 7.87E-10 6.24E-10 +
WNW 6.25E-09 4.01E-09 1.95E-09 1.14E-09 8.03E-10 6.24E-10 NW 1.30E-08 8.55E-09 4.18E-09 2.41E-09 1.67E-09 1.28E-09 NNW 1.26E-08 8.30E-09 4.11E-09 2.39E-09 1.67E-09 1.28E-09 Rev. No. 7 Page _A-21 of CDCM
i l
TABLE C-13 (CouT2Nuto) f ELEVATED RELEASE - METEOROLOGICAL DATA - GRAZING Sector Average Finite Cloud Gammt X/Q (sec/m3) t SEGMENT BOUNDARIES IN MILES i Direction
.50 .75 1.00 1.50 2.50 3.50 ;
N 1.43E-07 9.72E-08 7.52E-08 5.33E-08 3.45E-04 2.53E-08 NNE 9.35E-04 6.41E-04 4.97E-08 3.53E-08 2.29E-08 1. 6 9 T.-0 4 NE 9.50E-08 6.49E-08 5.02E-08 3.55E-08 2.30E-08 1.70H-08 '
ENE 1.67E-07 1.14E-07 8.80E-08 6.23E-08 4.01E-08 2.93E-08 E 1.80E-07 1.24E-07 9.61E-08 6.81E-08 4.35E-08 3.11t-08 ESE 5.03E-04 3.55E-08 9.53E-08 6.47E-08 2.25E-08 1.63t-08 i SE 8.22E-08 5.42E-08 4.17E-08 2.89E-08 1.81E-08 1.31E-08 :
SSE 6.142-08 3.91E-08 3.01E-08 2.09E-08 1.33E-08 9.74E-09 8 7.10E-08 4.59E'04 3.54E-08 2.47E-08 1.57E-08 1.15E-08 l SSW 7.11E-08 4.70E-08 3.62E-0E 2.53E-08 1.61E-08 1.17E-08 SW 7.04E-08 4.73E-08 3.65E-08 2.57E-08 1.65E-08 1.21E-08 ,
WSW 5.00E-08 3.39E-08 2.61E-04 1.83E-04 1.18E-04 8.68E-09 i W 5.78E-08 3.93E-08 3.03E-08 2.14E-04 1.39E-08 1.02E-08 WNW 6.11E-Ca 4.19E-08 3.24E-08 7 29E-08 1.47E-08 1.08E-08 NW 1.11E-07 7.53E-08 5.85E-08 4.17E-08 2.72E-04 2.00E-08 NNW 1.13E-07 7.61E-08 5.90E-08 4.18E-04 2.71E-04 2.00E-04 ,
4.50 7.50 *15.00 25.00 35.00 45.00 N 1.99E-04 1.19E-08 5.60E 3.13E-09 2.21E-09 1.68E-09 NNE 1.33E-08 8.00E-09 3.83E-09 2.21E-09 1.53E-09 1.17E-09 NE 1.35E-04 8.16E-09 3.97E-09 2.32E-09 1.62E-09 1.25E-09 ENE 2.29E-04 1.35E-08 6.31E-09 3.57E-09 2.46E-09 1.86E-09 E 2.45E-04 1.42E-08 6.42E-09 3.57E-09 2.43E-09 1.83E-09 ESE 1.26E-04 7.23E-09 3.25E-09 1.80E-09 1.22E-09 9.16E-10 SE 1.01E-08 5.81E-09 2.64E-09 1.48E-09 1.01E-09 7.62E-10 SSE 7.62E-09 4.48E-09 2.08E-09 1.18E-09 4.15E-10 6.18E-10
, S 8.99E-09 5.30E-09 2.47E-09 1.40E-09 9.69E-10 7.35E-10 SSW 9.13E-09 5.34E-09 2.46E-09 1.39E-09 9.55E-10 7.22E-10 SW 9.43E-09 5.57E-09 2.61E-09 1.49E-09 1.03E-09 7.88E-10 WSW 6.86E-09 4.14E-09 2.01E-09 1.17E-09 8.23E-10 6.32E-10 W 8.08E-09 4.89E-09 2.38E-09 1.39E-09 9.76E-10 7.51E-10 WNW 8.44E-09 5.00E-09 2.36E-09 1.35E-09 9.35E-10 7.12E-10
, NW 1.57E-08 9.36E-09 4.39E-09 2.49E-09 1.71E-09 1.29E-09 NNW 1.57E-04 9.37E-09 4.43E-09 2.52E-09 1.74E-09 1.32E-09 l
l l Rev. No. 7 Page ,G-11 of'ODCM
1 TABLE C-13 (Cour muso)
ELEVATED RELEASE - METEOROLOGICAL DATA - GRAZING (D/Q) Sector Average Deposition (1/m2) By Downwind Sectors SEGMENT BOUNDARIES IN MILES l
i Direction
.50 .75 1.00 1.50 2.50 3.50 .
N 1.09E-09 8.76E-10 7.29E-10 4.59E-10 2.67E-10 1.74E-10 i NME 3.10E-10 2.77E-10 2.59E-10 1.83E-10 1.15E-10 7.68E-11 l NE 1.82E-10 1.91E-10 2.03E-10 1.57E-10 1.05E-10 7.10E-11 !
ENE 1.55E-09 1.31E-09 1.15E-09 7.66E-10 4.64E-10 3.05E-10 E 2. 08E-09
- 1. 7 3E-09 1.50E-09 9.82E-10 5.88E-10 3.85E-10 ESE 1.54E-09 1.22E-09 1.00E-09 6.22E-10 3.57E-10 2.31E-10 1 SE 1.81E-09 1.37E-09 1.06E-09 6.12E-10 3.30E-10 2.09E-10 SSE 1,32E-09 9.71E-10 7.16E-10 3.48E-10 1.97E-10 1.22E-10 S 1.23E-09 9.14E-10 6.82E-10 3.76E-10 1.94E-10 1.21E-10 SSW 1.02E-09 7.80E-10 6.07E-10 3.53E-10 1.92E-10 1.22E-10 SW 4.75E-10 3.89E-10 3.30E-10 2.112-10 1.25E-10 8.16E-11 WSW 1.41E-10 1.21E-10 1.07E-10 7.21E-11 4.42E-11 2.92E-11
. W 1.29E-10 1.14E-10 1.04E-10 7.25E-11 4.55E-11 3.03E-11 WNW 2.81E-10 2.50E-10 2.31E-10 1.61E-10 1.01E-10 6.72E-11 NW 7.93E-10 6.62E-10 5.77E-10 3.81E-10 2.29E-10 1.50E-10 NNW 1.02E-09 7.95E-10 6.37E-10 3.85E-10 2.16E-10 1.39E-10 l
4.50 7.50 15.00 25.00 35.00 45.00 i N 1.19E-10 5.39E-11 1.87E-11 8.67E-12 5.23E-12 3.49E-12 NNE 5.30E-11 2.38E-11 8.21E-12 3.70E-12 2.18E-12 1.44E-12 NE 4.91E-11 2.20E-11 7.52E-12 3.34E-12 1.94E-12 1.27E ENE 2.10E-10 9.45E-11 3.26E-11 1.49E-11 8.87E-12 5.89E-12 E 2.65E-10 1.19E-10 4.13E-11 1.89E-11 1.13E-11 7.52E-12 .
ESE 1.59E-10 7.16E-11 2.49E-11 1.16E-11 7.00E-12 4.68E-12 SE 1.43E-10 6.51E-11 2.28E-11 1.00E-11 6.67E-12 4.49E-12 SSE 8.35E-11 3.81E-11 1.35E-11 6.57E-12 4.11E-12 2.79E-12 5 8.29E-11 3.78E-11 1.34E-11 6.46E-12 4.02E-12 2.72E-12 SSW 8.38E-11 3.80E-11 1.33E-11 6.32E-12 3.88E-12 2.61E-12 SW 5.62E-11 2.54E-11 8.82E-12 4.07E-12 2.44E-12 1.63E-12 WSW 2.02E-11 9.09E-12 3.15E-12 1.44E-12 8.56E-13 5.68E-13 W 2.09E-11 9.42E-12 3.26E-12 1.48E-12 8.75E-13 5.79E-13 ,
WNW 4.64E-11 2.09E-11 7.19E-12 3.25E-12 1.92E-12 1.27E-12 NW 1.04E-10 4.66E-11 1.61E-11 7.39E-12 4.41E-12 2.93E-12 NNW 9.55E-11 4.32E-11 1.51E-11 7.07E-12 4.30E-12 2.89E-12 '
Rev. No. 7 Page c-28 of ODCM
7 i
l TABLE C-14 RECEPTOR DISPERSION PARAMETERS FOR VENT AND ELEVATED RELEASES .
DISPERSION PARAMETER DESCRIPTION RECEPT 0R Annual Average X
-- Total ' Stack Site Boundary Skin;Bodyk Annual Average X Stac Site Boundary
- Annual Average X Stack Site Boundary
- Annual Average X - Gamma Air; Stack Site Boundary Annual Average X -- Beta Air;l.
Dep. Inha Resident Annual Average 0 - GPD; Stack ; Stack Resident Grazing - SFV & FFV' Stack Garden Grazing -Cow; Stack Milk Animal Grazing - Goat: Stack Milk Animal -
Grazing - Me ; Stack Meat Animal ,
Annual Average X - Total Body; Vent Site Boundary Annual Average X - Skin; Vent Site Boundary .
Annual Average X Vent Site Boundary Annual Average X - Gamma Air; Vent Site Boundary Annual Average X -- Dep Beta Air;l Inha .; Vent Resident !
Annual Ave age D - GPD; Vent Resident Grazing - SFV & FFV; Vent Garden -
Grazing - Cow; Vent Milk Animal Grazing - Goat; Vent Milk Animal Grazing - Meat; Vent Meat Animal
- The highest X/Q is located beyond the site boundary, ;
Rev.-No. 7 Page C-29 of ODCM
i APPElWIX 0 ,
$ b LIMITED ANALYSIS APPROACH DOSE ASSESSMENT FOR LIQUID itADI0 ACTIVE EFFLUENTS P
{
ev. No. 7 Page L.1 of ODCM
I APPENDIX D ,
LIMITED ANALYSIS APPROACH l DOSE ASSESSMENT FOR LIQUID RADI0 ACTIVE EFFLUENTS l l
IMLg TITLE ggg ;
D-1 Calculation of Total Ci/yr Releases for Liquids D-5 :
D-2 Organ Doses For Liquid Releases D-6 0-3 Dose Contribution to the Adult's Total Body From the D-8 !
Freshwater Fish Pathway l D-4 Dose Contribution to the Teenager's Liver from the D-9 l Freshwater Fish Pathway ,
D-5 Dose Contribution to the Adult's. Total Body from the D-10 l Potable Water Pathway 0-6 Dose Contribution to the Teenager's Liver from the D-11 Potable Water Pathway :
D-7 Dose Contribution to the Adult's Total Body and to 0-12 4
the Teenager's Liver from the Lake Shoreline Deposits Pathway D-8 Dose Contribution to the Adult's Total Body and to 0-13 the Teenager's Liver from the Swimming and Boating Pathways t
l l
l Rev. No 1 Page _jL.1 of ODCM
, ~ . _ _
1 I N LIMITED ANALY N APPROACH DOSE ASSESSMENT FOR LI0' D .lADI0 ACTIVE EFFLUENTS The radioactive- liquid effluents for. the years 1980 through 1987 ;
.(from the- JAFNPP. Semi-Annual Effluent release reports) were evaluated and nuclides to determine the criticaltopathways, which contributed environme l doses.
ita organs, ape he groups, liquid release nuclide distribution used in this analysis is shown in !
. Table D-1. This analysis was performed to develop a limited dose "
analysis for determination of liquid effluent environmental doses.
Limiting the dose calculation to a few selected nuclides that contribute the majority of the dose, along with the application of :
an appropriate conservatism factor to compensate for variations in isotopic mi>tures arovides a- simplified method of determining compliance with th,e cose limits of Technical Specification 2.3.
, Tables D-2 through D-8 show the results of this evaluation. Table L D-2 presents the dose for 8 organs and 4 age groups from all J available pathways. The adult's total body and teenager's -age l
K groups liver, (adult,kidney, teenager, thyroid, child, lung and infant)GI-LLI) skin and .and all The organs (bone, dominant l' pathway contribution to these, doses ,is freshwater fish in estion.
Table D-3 presents- the percent of the adult's total b dose-contribution bv the major -radionuclides through the d inant pathway, ingestion of freshwater fish. Table D-4 presents the same data for the teenager's liver dose. The data in Tables D-3 and D-4
- show that the fish pathway contributes at least 92% to the adult's total body dose and at Teast 80.9% to the: teenager's liver dose from all pathways considered. The data- in the tables also show )
~
that during 1980-1987 the radionuclides Cs-134, Cs-137, Zn-65, Co- :
- t. 60, and Mn-54 contributed over 91% of the total dose to the total 1 l -body and over 80%'of the total liver dose via the freshwater fish ingestion pathway.
. The data- in Tables' D-5 and D-6 show that the potable water pathway i contributed no.more than 1% to the adult's total body dose and no !
more than 0.0% to the teenager's liver dose. This pathway is :
, necessary .to demonstrate compliance with 10CFR50 as specified in 4 Sections 4.-2-and 4.3.1 of.NUREG-0133. As mentioned in Appendix A, Table A-4.3, this pathway is considered for all required analysis.
Table D-7 shows that 17.9% of the teenager's dose to the liver in I 1984 was from the lake shoreline deposits pathway. The lake I shoreline pathway contributed 5.7% of the- adult's total body dose l in 1984. This pathway contributed 9.3% of the teenager's liver dose in 1986 and 2.8% of the adult's total body dose in 1986. The lake shoreline deposits pathway is second to the freshwater fish I l pathway when the concentrations of Cs-134, Cs-137, 2n-65, Co-60, i
and Mn-54 are low as in 1984 and 1986.
l
%. 1 Rev. No 7 Page __Q-2 of oDCM
r
- g LIMITED ANALYSIS APPROACH (Courzmuro)
DOSE ASSESSMENT FOR LIQUID RADI0 ACTIVE EFFLUENTS Table 0-8 shows that the swimmino and boating pathwa s, combined, contribute no more than 1.5% to the adult's total bo dose and no more than 0.8% to the teenager's liver dose from 0 to 1987.
The swimming and boating pathways are not used in the ODCM since their dose contributions are very small.
A conservatism factor of 0.8 is introduced into the equation
' (i.e. calculated doses using this approach should be divided by O.8) ,to compensate for any unexpected variability in nuclide and pathway dose contribution. Therefore, the dose commitment to the adult's total body and. teenager's liver due ~ to radioactive material in liquid effluents can be reasonably estimated by limiting the dose calculation to these b nuclides and the fish and potable water pathways, which cumulatively contribute the bulk of the total dose calculated by accounting for all nuclides and all pathways.
l
-Rev. No 7 Page E of ODCM
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i Rev. No. 7 Page .Q ),of ODcM
,w
~
- E
- a' TABLE D-2 o .
'." ORGAll DOSES FOR LIQUIS RELEASES (ALL PATIIWAYS)-
%E p._
g? w$$MW9?fdp M iUFsi M 7 M his ss M M % $y
??N cs l'( SKIN- BOK I,IVER . T. 9007 TIJYRDIS '. KIDIIEY LINIG GI-LLI YEAR (ares) L(ares) (area)' (aren) (assa) ~ (scree) (area) -(ares) 1980 8.85E-04 7.11E- 02 1.24E-01 9.04E-02 3.25E-03 4.26E-02 1.4)E-02 -1.63E-03 1981 -- 1. 44E-03 7.99E-02 1.38E-01 1.00E-01 5.18E-03 4.81E-02 1.61E-02 1.98E-03 1982 4.09E-04 4.76E-02 8.37E-02 6.17E-02 5.12E-04 2.82E-02 9.46E-03 5.66E-03 1983 5.22E 4.91E-02' 8.42E 6.16E-0? 7.22E-04 2.84E-02 9.67E 6.82E 1984 3.60E-05 4.63E-04 7.97E-04 5.38E-04 4.63E-05 3.21E-04 1.10E-04 7.12E-04 1985 1.16E-04 9.05E-03 1.59E-02 1.15E-02 1.29E-04 5.53E-03 1.79E-03 1.93E-03 1986 1.47E-05 4.47E-04 6.69E-04 4.47E-04 1.97E-05 2.56E-04 8.58E-05 1.58E-04
- 1987 1.32E-04 9.38E-03 1.44E-02 9.98E-03 1.46E-04 4.97E-03 1.71E-03 1.85E , kk k . bi b 3
~'
SKIN .BoWE LIVER T. BODY TIfYROIS KIDIIEY: LifMG . GI-LLJ l YEAR (eres) :(ares) (ares) (ares) (area)- (aren). (aren) (ares) 1 l
4.94E-03 7.82E-02 1.31E-01 5.58E-02' 6.52E-03 4.67E-02 2.00E-02 1.50E-02 i 1980 1981 8.05E-03 8.97E-02 1.48E-01 6.43E-02' 1.05E-02 5.45E-02 2.44E-02 1.97E-02 I 1982 2.28E-03 5.17E-02 8.75E-02 3.71E-02 2.10E-03 3.03E-02 1.27E-02 5.67E-03 i 1983 2.92E-03 5.37E-02 8.86E-02 3.74E-02 2.74E-03 3.10E-02 1.34E-02 6.94E-03 ?
! 1984 2.01E-04 6.08E-04 9.56E-04 4.94E-04 1.86E-04 4.64E-04 2.63E-04 6.44E-04 '
e 1985 6.46E-04 9.98E-03 1.68E-02 7.18E-03 5.79E-04 6.07E-03 2.55E-03 1.82E-03 1986 8.21E-05 5.31E-04 7.48E-04 3.29E-04 7.58E-05 3.17E-04 1.56E-04 1.71E-04 I 1987 7.35E-04 1.05E-02 1.54E-02 6.24E-03 6.57E 5.62E-03 2.54E-03' l.83E-03 o
A ,I a
8 9
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Rev. No. 7 Page D-7 of ODCM
1
\'.
TABLE D-3 i 2 DOSE CONTRIBUTION TO THE ADULT'S TOTAL BODY FROM THE l
FRESHWATER FISH PATHWAY (PERCENT) 150T0PE 1980 1981 1982 1983. 1984 1985 1986 1987 :
Cs-134 52.7 50.3. 56.5 52.2 25.2 52.1 9.2 26.8 Cs-137 45.2 46.8 42.4- 46.8. 59.7 44.9 82.5 71.5 Zn-65 1.3 1.7 0.6 0.3 8.5 2.1 5.7 0.5 Co-60 0.6 0.9 0.4 0.5 4.5 0.6 2.1 0.8 Mn-54 :0.2 0.3 0.1 0.2 1.7- 0.2 0.1 0.4 1 The % 100 100 100 100 99.6 99.9 99.6 100 .
oft $ercentagee total bo y) -
dose from five nuclides in the fish pathway The percentage (%) 98.8 98.3 99.2 98.9 92.0 98.8 95.6 98.4 of the total dose to the. adult's total body from the fish pathway
~The percentage (%) 98.8 98.3 99.2 98.9 91.6 98.7 95.2 98.4 of the total dose to-the adult's a total ~ body from the-five nuclides .
t in the fish
- pathway Rev. No. 7 Page ,_Q-1 of ODCM
i L i g .
} .
TABLE D-4 DOSE CONTRIBUTION TO THE-TEENAGER'S LIVER FROM THE !
FRESHWATER FISH PATHWAY (PERCENT) 1 IS0 TOPE 1980 1981 1982 1983 1984 1985 1986 1987 l Cs-134 46.2 43.8 50.2 45.9 20.0 45.5 7,3 22.0 Cs-137 50.8 52.2 48.4 52.9 60.9 50.2 83.5 75.5 Zn-65 2.0 2.5 0.9 0.5 11.9 3.3 8.0 0.7 Co-60 0.2 0.3 0.1 0.2 1.3 0.2 0. 6- 0.2-l Mn-54 0.8 1.1 0.4 0.6 5.6 0.9 0.5 1.4 The percentage-(% 100 99.9 100 100 99.7 100 99.9 99.8 of the liver dose)-
- from five nuclides in the fish path-way -
The percentage % 96.5 95.0 97.6 97.0 80.9 96.4 89.9 95.6 of the total dos (e) to the teen's c liver from the fish pathway.
The percentage (%) 96.5 94.9 97.6 97.0 80.7 96.4 89.8 95.4 of the total dose.
to the' teen's liver from the five nuclides in the fish. pathway t
2, L
' Rev. No. 7 Page _R::1 of ODCM E- ____________m_________-________-_.v -- -g ea
.,, , .. .a. - . +. . . - . . . . . . . , a . - - ~ . . < . _ .a..a - , - . . . -,-<a _ _ _ . . .
i I
TA8LE D-5 DOSE CONTRIBUTION TO THE ADULT'S TOTAL B0DY FROM THE P0 TABLE WATER PATHWAY (PERCENT)
IS0T0PE 1980 1981 1982 1983 1984* 1985 1986 1987 ,
Cs-134 41.5 35.7 47.5 41.9 3.29 35.7 1.18 15.5 i Cs-137 35.6 23.2 35.7 37.6 7.82 30.7 10.5 41.5 Zn-65 1.01 1.2 0.5 0.25 1.11 1.44 0.73 0.28 Co 17.8 24.4 12.4 15.5 23.4 15.9 10.8 17.8 Mn-54 0.86 1.1 0.4 0.61 1.10 0.84 0.09 1.22 '
The percentage (%) '96.8 95.6 96.5 95.9 36.7 84.6 23.3 76.3 of.the total body dose from the nuclides from the potable water pathway The percentage (%) 0.16 0.18 0.15 0.15 0.89 0.18 0.94 0.21 the total dose to the adult's total body from the
, potable water l
pathway The percentage (% 0.15 0.17 0.14 0.14 0.33 0.15 0.22 0.16 L of the total dose) .
of the adult's total body from -
the five nuclides
.in the potable water pathway l'
L i
- Tritium was the major contributor to the potable water pathway for 1984.
Rev. No. 7 Page D-12 of ODCM ,
l N
1 I
l l
TABLE 0-6 DOSE CONTRIBUTION TO THE-TEENAGER'S LIVER FROM THE POTABLE WATER PATHWAY (PERCENT)
IS0 TOPE 1980 1981 1982 1983 1984* 1985 1986 1987
-1 Cs-134 40.9 37.0 47.0 41.7 4.87 36.9 1.74 16.1 45.0 44.2 Cs-137 45.3 48.0 14.8 40.8- 19.9 55.3 '
'Zn-65 1.8 2.14 0.85 0.44 2.90 2.63 1.90 0.52 l Co-60 6.43 9.25 4.49 5.66 12.7 6.03 5.8 6.77 Mn-54 3.5 4.76 1.73 2.54 6.77 3.62 0.57 5.24 The percentage (% 97.6 97.4 99.4 98.3 42.0 90.0 29.9 83.9 oftheliverdose) from the nuclides from the' potable water pathway The percentage (% 0.12 0.13 0.12 0.12 0.38 0.14 0.44 0.15 of the total dose) to the teen's liver'from the potable water pathway '
The' percentage % 0.11 0.12 0.11 0.11 0.16 0.13 0.13 0.12 of the total dos (e)
L to-the teen's liver from the five nuclides in the potable water pathway l
u
(
l
- Tritium was the major contributor to the potable waer pathway for 1984 p Rev. No. 7 Page D-11 of ODCM
4 i
TABLE D-7 DOSE CONTRIBUTION TO THE ADULT'S TOTAL BODY AND-TEENAGER'S LIVER FROM THE LAKE SHORELINE DEPOSITS PATHWAY 1980 1981 1982 1983 1984- 1985 1986 1987 The percentage (%) 0.83 1.22. 0.56 0.72 5.68. 0.85 2.79 1.12 of the total dose
,. to the adult's ,
total body from the lake shoreline deposits pathway 1
Maximum percentage from 1980 to 1987 - 5.68%
Aver. age percentage from 1980 to 1987 - 1.72% ,
L The percentage (%) 3.22 4.62 2.22 2.80 17.91 3.27 9.33 4.04 of the total dose to the teenager's liver from the lake shoreline deposits pathway Maximum percentage p from 1980-to 1987 - 17.9%
1 Averaa percentage from I 80-to 1987 - 5.93%
l l'
Rev. No.. 7 Page D-12 of ODCM
TABLE D-8 DOSE CONTRIBUTION TO THE ADULT'S TOTAL BODY AND TEENAGER'S LIVER FROM THE SWIMMING AND BOATING PATHWAYS 1980. 1981 1982 1983 1984 1985 1986 1987 0.21 0.31 0.13 0.17 1.39 0.20 0.62 0.27 Percentake(%)of the tota dose to the Adult's total body from the swimming and boating pathways Maximum percentage from 1980 to 1987 - 1.39%
Averace percentage from 1980 to 1987 - 0.41%
Percentage (%)of 0.14 0.21- 0.09 0.12 0.78 0.14 0.37. 0.18 the tota dose to
-the teenager's
. liver from the swimming and boating pathways Maximum pert.entage from 1980 to 1987 - 0.78%
Average percentage from 1980 to 1987 - 0.25%
Rev. No. 7 Page D-13 of ODCM
tai siis i i '- _'
i s 4 3 1
APPENDIX E TECHNICAL BASES FOR EFFECTIVE DOSE FACTORS
('
i
6
. 1 l
.1 l
I
, APPENDIX E I 1
TECHNICAL BASES FOR EFFECTIVE DOSE FACTORS ~
l IARE TITLE EASE l !
E-1 Effective Dose Factors for Noble Gases - Total Body E-6 1
Effective Dose (Keff)
E-2 Effective Dose Factors for Noble Gases - Air Doses E-7 (Meff and Neff)
E-3 Effective Dose Factors-for Noble Gases - Skin E-8 o
Effective Dose (L + 1.1 Meff)
E-4 Tables of Source Terms Used for Development of E-9 Effective Dose Transfer Factors (Elevated Release) o E-5 Tables of Source Terms Used for Development'of E-10 b
Effective Dose Transfer Factors (Vent Release)
E-6 Radionuclide Distribution of Vent and Elevated E-11 Releases E
l l
1 l
L 1
Rev No. 7 Page _E-1 of ODCM
l l
TECHNICAL BASES FOR EFFECTIVE DOSE FACTORS )
~
The evaluation of doses due to releases of radioactive material to the atmosphere can be simplified by the use of effective dose transfer factors instead of using dose factors which are radionuclide specific. These effective factors, which are based on the typical radionuclide distribution in the releases, can be applied to the total radioactiv: released to approximate the dose in the environment, i.e. , stead of having to sum the isotopic distribution multi lie'd by he isotope specific dose factor, only a single- multi lication eff, Leff, eff or N fg times the total quantity of radioactive material re eased, w6u be needed. This approach provides a reasonable estimate of the actual dose while eliminating the need for a detailed calculating technique.
Determination of Effective Dose Factors The effective dose transfer factors are based on past operating data. The radioactive effluent distribution for the past years can be used to derive -single effective factors by. the following equations, n-Keff = i=1 IKi -
fi E-1 Where:
[
L
.Keff = the effective total body dose factor due to gamma l emissions from all noble gases released.
t Ki = the total body dose factor due to gamma emissions from i each noble gas radionuclide 'i' released. -
fi = the fractional abundance of noble gas radionuclide 'i' is of the total noble gas radionuclides.
A Keff is calculated for elevated releases and -also for vent releases, n
Leff = i=1 ILifi
- - Where
Leff = the effective all noble gases skin dose factor due to beta emissions from released.
Li = the skin dose factor due to the beta emissions from each noble gas radionuclide 'i' released.
For ease of-calculation L f and (L + 1.1M)eff is calcuTa<1 is vent
- ed for calculated releases. for elevated releases Re v' . No. 7 Page _E-1 of ODCM
1 1
b l:
TECHNICAL BASES FOR EFFECTIVE DOSE FACTORS (CONTINUED) l l h n I fi '
r E-2 L
(L + 1.1 M)eff = i=1 (Li + 1.1 Mj)
L Where:
(L + 1.1 M)eff = the effective skin dose factor due to beta and gamma emissions from all noble gases released ,
from the vents.
J (Li +'1.1 Mj) = the skin dose factor due to beta and. gamma .
emissions from each noble gas radionuclide 'i' l.
-released-from the vents.
!. n L.
Meff = i=1 r Mifi E-3 Where:-
'Meff'= the effective air dose factor due to gamma emissions from all. noble gases released.
Mi = the air dose factor due to gamma emissions from each noble gas radionuclide 'i' released.
A.Heff releases.
is calculced for' elevated releases and also for vent n
Neff = ,z Nifi E-4 1=1 7
L Where: ,
Neff = the effective air dose factor due to beta emissions from all noble gases released.
Nj = the air dose factor due to beta emissions from each noble gas radionuclide 'i' released.
l A . Neff .'is calculated for elevated releases and also for vent releases.
!?
l To determine the appropriate effective factors to be used and to o evaluate the degree of variability, the atmospheric radioactive L ' effluents for the years 1980, 1981 1982- have been evaluated.
L Tables E-1, E-2, and E-3 present the,results of this evaluatic.n.
L
!' E
! As- can befactors transfer seen from varyTables littleE-1' f rom-2, year and E-3, the to year, effective dose particularly in L the case of elevated releases which contribute the majority of i released noble gas activity and offsite dose.
Rev. No. 7- Page _,E-i of ODCM
E TECHNICAL BASES FOR EFFECTIVE DOSE FACTORS-(CONTINUED)
-To provide an additional' degree of conservatism, a factor of 0.8 is introduced into the dose calculation process when the
' effective dose transfer factor is used. This added conservatism provides additional assurance that the evaluation of doses by the '
use of a single effective factor will not significantly underestimate any actual doses-in the environment.
i i
4
-N_-
) -
.'. fi r
x :
i t
TABLE E-1 JAMES A. FITZPATRICK NUCLEAR POWER PLANT OFFSITE DOSE CALCULATION MANUAL (ODCM)
EFFECTIVE DOSE FACTORS FOR NOBLE GASES -
TOTAL BODY EFFECTIVE DOSE
[Keff]
hs. sb .hfhi$he n 35 Osh- h!!N)b $$. b $ $fd ammmmme
[ mrem /sec per uCi/m3], [ mrem /sec per uCi/m3]
L Total Body. Effective- Total Body Effective-Dose Factor Keff Dose Factor Keff o 1980- li16E-04 1.18E-04 1981 6.89E-05 1.21E-04 1982 4.55E-05 1.38E-04 AVG. 7.68E-05 1.26E-04 ll L
M_ 9 . MM
TABLE E-2 JAMES A. FITZPATRICK-NUCLEAR POWER PLANT OFF5ITE DOSE-CALCULATION MANUAL (00CM)
EFFECTIVE DOSE FACTORS FOR NOBLE GASES - :
AIR-DOSES
[Meff & Neff] .
m . . . . .
41 ERA ;$$FW $$$$55W RELEASER 9 dj& yfSt ELEVATEDiRELEASE E mamm-mrad /sec per uCi/m3- mrad /sec per uCi/m3 Gamma-Air Beta-Air Gamma-Ai r Beta-Ai r Effective Effective Effective Effective Dose Factor' Dose Factor Dose Factor- Dose Factor
-Meff Neff Meff Neff ;
~
1980 8.03E-05 1.21E-04 8.70E-05 1981 7.44E-05 5.57E-05 1.25E-04 8.74E-05 1982 4.96E-05 4.54E-05 1.44E-04 1.00E-04 AVG. -8.17E-05 6.05E-05 1.31E-04 9.14E-05 .
i
- -i _ -_ _ _ . _ _ _ . . _ _ _ _ _ . _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ _ _ _ _ _ _
.i.
TABLE E-3 JAMES A. FITZPATRICK NUCLEAR POWER Pt. ANT OFFSITE DOSE CALCULATION MANUAL (00CM)
- ~
EFFECTIVE DOSE FACTORS FOR NOBLE GASES -
SKIN EFFECTIVE DOSE A? lY .' ?W .
[ mrem /see per uCi/m3] [ mrem /sec per uCi/m3]
. Total Skin Effective Skin Effective Dose Factor Dose Factor (L + 1.1 M)eff Leff 1980 1.94E-04 6.79E-05 1981- 1.22E-04 6.84E-05 1982 8.24E-05 8.15E-05 AVG.- 1.33E-04 7.26E-05 i
_9
i
, ." J
?.
TABLE E-4 JAMES'A. FITZPATRICK NUCLEAR POWER PLANT 1
0FFSITE DOSE CALCULATION MANUAL (ODCM)L [
- l TABLES OF SOURCE TERMS USED FOR DEVELOPMENT OF EFFECTIVE I DOSE TRANSFER FACTORS t
(8ased on Semi-Annual Effluent Data Reports for the years 1980, 1981, 1982) .
)
l ELEVATED RELEASE (Curies)
ISOTOPE 1980 -
1981 1982.
N-13 . 1.22E 03 8.41E 03 2.53E 03
-Ar-41 2.17E 02 2.21E 02 3.19E 02 Kr-85m 5.17E 03 1.23E 04 1.15E 04 -i l Kr-87 6.02E 03 1.49E 04 1.93E 04 Kr-88 9.58E 03 2.48E 04 2.38E 04 Xe-131m 1.10E 04 3.28E.04 2.85E 04
, Xe-133 1.48E 04 3.18E 04 1.83E 04 i
Xe-133m 1.52E 02 5.49E 02 4.22E 02 Xe-135- 2.03E 04 5.18E 04 5.90E 04 Xe-135m 2.22E 03 5.53E 03 8.74E~03 Xe-138 5.01E 03- 1.44E 04 2.53E 04 I-131 2.99E-02 6.37E-02 4.03E-01 1 I-133 6.32E-02 2.02E-01 1.69E 00
- I-135 4.05E-02 2.91E-01 2.03E.00 Mn-54 2.47E-04 3.52E-04 1.31E Co-58 2.07E-05 1.05E-05 1.71E-05 :
Co-60 1.10E-04 2.81E-05 2.34E-05 y Zr-Nb-95 --
3.92E-06 7.19E-04
.Sr-89 1.53E-03 1.37E-01 2.75E-01 Sr-90' 3.61E-05 1.29E-04 3.05E-04 Cs-137 1.14E-04 6.58E-04 3.55E-03 Bo-La-140 6.73E-04 1.13E-02 2.40E-03 :
Cr-51 4.26E-05 --
3.97E-05 i Ce-141 -- --
8.57E-07 H-3 4.393 6.649 5.26 i
l l
l Rev. No.- 7 Page _E-1 of ODCM l
. - . .-____--_--____-___--_____------___--___-_____-___1
j s
r 1
, TABLE E-5
' JAMES A. FITZPATRICK NUCLEAR POWER PLANT OFFSITE DOSE CALCULATION MANUAL (0DCM) H H
TABLES OF SOURCE TERMS USED FOR DEVELOPMENT OF EFFECTIVE DOSE TRANSFER-FACTORS-L- (Based on Semi-Annual Effluent Data Reports for-the years 1980, 1981, 1982) ,
r VENT RELEASE (Curies) ,
I .1 - - - - - - - -
s L
N-13 8.90E 01 3.84E'02 4.26E 01 E
Kr 4.72E 01 '3.08E 01 1.51E 01-
.Kr-85m 5.59E 01 -- --
Kr-88 :9.15E 01 2.75E 01 --
T Xe-133 3.95E 02 5.88E 02 1.94E103 -
Xe-135 2.23E 02 4.66E 02 7.19E 02 Xe-135m 5.38E 01 4.21E 02 6.50E 02
- Xe-138 1.49E 02 8.18E 01 1.06E 02 ;
I-131 -4.68E-02 5.12E-02 3.15E '
u~ I-133.~ 7.07E-02 3.52E-02 1.60E-01 3
'I-135 4.24E-02 .3.97E-02 2.14E-01 Cr-51 1.76E-02 -1.35E-03 2.30E-03 Mn-54 3.58E-03 6.37E-04 4.14E-04
'Co-58 3.33E-03 4.96E-04 5.41E-05:
Co-60 1.45E-02 5.49E-03 3.79E-03 Sr-89 8.85E-04 3.57E-03 7 '~ 88 E-04 u- Sr-90 2.15E-05 3.92E-06 1.63E-05 Zr-Nb-95 1.67E-05 .5.27E-05 2.56E-06 ,
Cs-134 3.21E-04 1.73E-04 4.51E-04 L Cs-137 3.05E-04 2.04E-04 4.64E-04 l Ba-La-140 1.48E-03 3.92E-03 3.64E-03 Ce-141 2.30E-05 2.29E-05 4.83E-05 Zn-65 4.04E-04 -4.97E-05 2.98E-05 N
1 k
~ -_ _ _ - - _ _ _ _ - - _ - _ - .__-.---___.-.--__-___r
l l
l TABLE E-6 j JAMES A. FITZPATRICK NUCLEAR POWER PLANT OFFSITE DOSE CALCULATION NANUAL.(00CM)
RADIONUCLIDE DISTRIBUTION OF VENT AND ELEVATED RELEASES )
RARIGIUCLIDE ggV~n ?,~;ggjay" FRACTION;WiTOTAL? RELEASE 51 '- l aamswasagasa -
VENT ELEVATED 1980 1981 1982 1980 1981 1982 ;
Ar-41 -- -- --
.003 .001 .002 Kr-85m .055 -- --
.069 .065 .059 Kr-87 .046 .019 .004 .081 .079 .099 Kr-88 .090 .011 --
.129 .131 .122 Xe-131m -- -- --
.148 .174 .146 Xe-133m -- -- --
.002 .003 .002 Xe-133 .309 .366 .566 .199 .168 .094 i Xe-135m .053 .262 .189- .030 .029 .045-l L
Xe-135 .220 .290 .210 .272 .274 .302 Xe-138 .147 .051 .031 .067 .076 .130 1
-l
.m erm_rm-
, i
'i e
,, i
- 1..
,1 S i
I APPENDIX F !
EFFLUENT MONITOR SAMPUNG LOCATIONS AND DESCRIPTIONS' -
j i
r
.',\'
Rev.-No.
7~
Page F-1 .of ODCM
I sj. _j u
! ! t l
l l
APPENDIX F-L EFFLUENT MONITOR SAMPUNG LOCATIONS AND DESCRIPTIONS TABLE TITLE PAGE F-1 Atmospheric Gaseous Release Point Data F-3 F-2 Effluent Monitoring System Data F-4 l FIGURE l
F-1 Gaseous. Release Points Building Elevations F-5 F-2 Gaseous Release Points Plant Yard Layout F-6 F Liquid Release Point F-8 F-4 Gaseous Effluent Release Paths F-9 F-5 Liquid Effluent Release Paths F-10 F-6 Solid Radwaste Treatment System F-11 F-7 Standby Gas Treatment System F-12 1
Rev. No.- 7 Page F-2 of ODCM
~
.z
-y' _
2:
o T&BLE F-1
- y JAMES A. FITBr& TRICE MBCIA&R POWER PL&MT '
OFFBITE DOSE CALCWIATION MBEREL (ODCM) !
l r ATMOSPHERIC GASEOUS REIRASE POINT DATA 1 .
= l
,, RELEASE REACTUR* TURBINE * .RADWASTE* REFUEL * '!
POINT STACE BUILDING BUILDING BUILDING FIDOR r
?
Height Above 385 172 172 111 172 !
, Grade (feet)
- i i
i Release Mode Elevated Roof Top Vent Roof Top Vent Roof Top Vent Roof Top Vent
.3 Effluent Turbine Gland Secondary Turbine Maste Disposal Refuel Floor I source Seal Condenser and Auxiliary Building Building Exhaust 1
! Games Nechen- Building Exhaust Ventilation Ventilation ical. Vacuum Exhaust Ventilation i Pump Building j t
pl Exhaust Steam da Jet Air Ejector o Exhaust Y
w .j l,
O '
"
- The Refuel Floor and Reactor Building vent is a combined release point.
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. i z orrsITE pose cALcoLaTrou ummenL (occup
.o EFFIRENT MOIIITORING SYSTEBE DATA -
IIDIIITOR SaleLIIIC DETECTOR RAIICE CGISTROL ALAmpt REpsatsett BESCRIPT1001 RACATICII TYPE FIIIICTIGIIS SETFOIstT CALIBRATIces
.S S C. -
Itate steam Located meer 4-gamma 0-50 mm/br Direct acram, Yes victoreen C6 line monitor the main steam sensitive contanteetles, lines douestream samme dose rate tem chambers isolatten source of the outboard (closure of IISIw's, l IISIV's in the !
recirc feetattee ,
steam tumeel valves, vacuum 'l pump line valve) !
i off-gas Turbine 252' 2-gamme 0-10 mR/br Initinte closure Yes radiation weet ces sample sensitive of off-gae system .'
counted on monitoring ies chambers isolaties valwee cystem Ce(Lt) i
-f sup ;
Off-gas pipe Stack 6 'I
'h8
, Scintillation 0-10 CPS Indicate and record Yes Gas vent -[
O (Stack) detectore . rate of release of merleelli monitor radiomettwo material .
cometed .e :
y .
to the eewireement Ge(LI) .
I O Process liquid Bad Weste - Scintillation 6 '
le -10 Ilsetter for leake Yee
" radietton SW 272* detectore llepresentative CPS of closed systene. Ig g sd sample i O somitore Service Ily 0 peonttor normal re- counted on lease of radio- ce(s.5 )
Ileater may 252' acatwo meteriet to time envireement i
_ _ _ . - - . _ _ _ _ - - _ - ~ _ _ - . _ - _ --
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EFFIDEIIT IICIIITOItIIIG SYSTERI DATA e
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- 4 o
IIGIllTom Saget.IMG DhTECTom aAIIGE LaIReef. AsAaII asymmmmer SESCRIPTIGII IACATISE TYPE FUNCTIGIIS SETFORIff
" Cat.IERATIces uSgs emanere Plant stack & Turbine - CII betectors 9-18 CPII Provide Seelettee Yes Cao .,
went noble IIG Set 300' of poteattalIy serineiIi- !
gas monitors Reactor - contaminated cometed osa RX 344' systems -ce(Ls)
Refuel -
~
RE 369' Radweste - Scleti!Iation 9-10 CPS EB 272' Betector Stack ,
Erywell Beactor 300*- Scintillation 8-30 CFII Ilmetter airborne Yes Ces continuous month side detectore radiometivity in eersnelli
, cir moottor -
Brywell during cometed on a l normat operettee i Ce(Li)
.,, Contalement Stywell 2-tosi closeber 0-80 S/hr Accident contre! Yee Victoteen fa high range penetrations detectore and initiatem _Co-137 gamme
,8 monitors Ell 8C and testation dose rate E8888 source 1
I t Cigh range Stack. .2-ion cleamber 8-10 t/hr Accident control Yes Victoreen O GIII"ent Turbine, detectors- and lettistes co-137 gamma es esagtors Radweete feelaties donc este O ***rce d
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UIRESTRICTED AREA MAP l'
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I APPENDIX H j i
ENVIRONMENTAL SAMPLE LOCATIONS l TABLE TITLE PAGE l H-1 Radiation Environmental Monitoring H-3 4 Sampling Locations s H-2 Liquid Effluent P'athway - Water Intake Points H-13 Description and Pumpage ,
P FIGURE >
H-1 Environmental Sampling Location Map H-10 ;
H-2 Environmental Sampling Location Map H-11 H-3 Liquid Effluent Pathway - Water Intake Points H-12 i
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Rev.-No. i. Page M-2 of ODCM
JAMES A. FIT 3 PATRICK NUCLEAR POWER PLANT OFFSITE DOSE CALCULATION XhMUAL (CDCM)
ENVIRCMMENTAL SAMPLING LOCATIONS 1.0 ENVIROMMENTAL MONITORING PROGRAM 1.1 sampling stations l l
The current sampling locations are specified in Table !
H-1 and Figures H-1, M-2. The Radiological Environmental-Monitoring Program is a joint effort ,
between the Niagara Mohawk Power Corporation and the New York Power Authority, the owners and operators of the Nine Mile Point Unit 1 and the James A. FitzPatrick :
l Nuclear Power Plant, respectively. Sampling locations are chosen on the basis of historical average l dispersion or deposition parameters from both units.
?
The average dispersion and deposition parameters for ;
the two units have been calculated for a five (5) year period, 1978 through 1982. The calculated dispersion or deposition parameters will be compared to the results of the annual land use census. If it is determined that a milk sampling location exists at a location that yields a significantly higher (e.g. 50%)
calculated D/Q rate, the new milk sampling location ;
will be added to the monitoring program within 30 days.
If a new location is added, the old location that yields the lowest calculated D/Q may be dropped from the program after october 31 of that year.
1.2 Interlaboratory Comparison Program ,
Analyses shall be performed on samples containing known quantities of radioactive material that are supplied as part of a Commission approved or sponsored Interlaboratory Comparison Program, such as the EPA Cross-check Program. Participation shall be only for
! those media, (e.g. air, milk, water, etc. ) , that are
! included in the Nine Mile Point Environmental Monitoring Program and for which cross check samples L are available. The actual Quality control sample results shall be reported in the Annual Radiological Environmental operating Report so that the Commission staff may evaluate the results. ,
specific sample media for which EPA Cross check Program samples are available include the following:
o gross beta in air particulate filters o gamma emitters in air particulate filters o I-131 in milk Rev. No. 4 Page M-3 of ODCM
i h
I i
o gamma emitters in milk i o gamma emitters in food product
- o. gamma emitters in water o tritium in water ;
o I-131 in water j 1.3 Thermoluminescent Dosimeters Used for Environmental
, Measurements ,
Thermoluminscent Dosimeters (TLDs) are placed in an inner ring of stations in the general area of the site boundary (TLDs 7, 18, 23, 75-87), and in an outer ring 's in the 4 to 5 mile range from the site (TLDs 8, 88-95).
There are 16 land based sectors in the inner ring and 8 land based sectors in the outer ring. TLDs are also placed in special interest areas such as population centers, nearby residences, schools, and control locations (TLDs 14, 15, 18, 49, 56,96-101).
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t Rev. No. 4 Page M-4 of ODCM
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i TABLE H-1 -
JAMES A. FITZPATRICK NUCLEAR POWER PLANT 0FFSITE DOSE CALCULATION MANUAL (ODCM)
RADIATION ENVIRONMENTAL MONITORING SAMPLING LOCATIONS l
P TYPE OF MAP
- SMFLE LOCATION COLLECTION SITE LOCATION ;
Radioiodine and 1 Nine Mile Point Road 1.8 mi 0 88* E i Particulates (air) North (R-1) l Radioiodine and 2 Co Rt. 29 & Lake Road (R-2) 1.1 mi 0 104* ESE Particulates (air)
Radioiodine and 3 Co.Rt.29(R-3) 1.5 mi 0 132' SE ,
.Particulates (air)
Radioiodine and 4 VillageofLycoming,NY(R-4) 1.8 mi 0 143' SE :
Particulates (air) .
Radioiodine and 5 hontario Point Road (R-5) 16.4 mi 0 42' NE Particulates (air)
Direct Radiation (TLD) 6 NorthShorelineArea(75) 0.1 mi 0 5' N DirectRadiation(TLD) 7 North Shomline Area (76) 0.1 mi 0 25' NNE Direct Radiation (TLD) 8 North Shoreline Area (77) 0.2 mi 0 45' NE L Dimct Radiation (TLD) 9 NorthShorelineArea(23) 0.8 mi 9.70' ENE Direct Radiation (TLD) 10 JAF East Boundary (78) 1.0 mi 0 90' E Direct Radiation (TLD) 11 Rt.29(79) 1.1 mi 0 115' ES DirectRadiation(TLD) 12 Rt.29(80) 1.4 mi-0 133' SE Dimet Radiation (TLD) 13 Miner Road (81) 1.6 mi 0 159'_SS DirectRadiation(TLD) 14 Miner Road (82) 1.6 mi 0 181' S Direct Radiation (TLD)' 15 LakeviewRoad(83) 1.2 mi 0 200* SS Direct Radiation (TLD) 16 LakeviewRoad(84) 1.1 mi 0 225' SW
- See Figums H-1 and H-2 for map locations
.Rev. No. 7 Page y of ODCM
TABLE H-1 (CONTINUED)
JAMES A. FITZPATRICK NUCLEAR POWER PLANT OFFSITE DOSE CALCULATION MANUAL (ODCM) ,
RADIATION ENVIRONMENTAL MONITORING SAMPLING LOCATIONS !
TYPE OF !%P*
, $#fLE LOCATION COLLECTION SITE LOCATION Direct Radiation (TLD) 17 SiteMeteorologicalTower(7) 0.7 mi 0 250' WSW ,
Direct Rcdiation (TLD) 18 Energy Information Center (18) 0.4 mi @ 265' W Direct Radiation (TLD) 19 NorthShorelineArea(85) 0.2 mi 0 294* WNW q DirectRadiation(TLD) 20 North Shoreline Area (86) 0.1 mi 0 315' NW DirectRadiation(TLD) 21 NorthShorelineArea(87) 0.1 mi 0 341' NNW l ,
DirectRadiation(TLD) 22 Hickory Grove (88) 4.5 mi 9 97* E Direct Radiation (TLD) 23 LeavittRoad(89) 4.1 mi 0 111' ESE DirectRadiation(TLD) 24 Rt.104(90) 4.2 mi 9 135' SE .
Direct Radiation (TLD) 25 Rt.51A(91) 4.8 mi 9 156' SSE Direct Radiation (TLD) 26 MaidenLaneRoad(92) 4.4 mi 0 183* S DirectRadiation(TLD) 27 Rt.53(93) 4.4 mi @ 205' SSW Direct Radiation (TLD) 28 Co.Rt.1(94) 4.7 mi @ 223' SW I
Direct Radiation (TLD) 29 LakeShoreline(95) 4.1 mi 0 237' WSW l
DirectRadiation(TLD) 30 Phoenix, NY Control (49) 19.8 mi 9 170' S-SSE DirectRadiation(TLD) 31 SWOswegoControl(14) 12.6 mi 0 226' SW ,
DirectRadiation(TLD) 32 Scriba, NY(%) 3.6 ml 9 199' SSW l
l' DirectRadiation(TLD) 33 Alcan Altsnintsn, Rt.1A(58) 3.1 mi 9 220' SW Direct Radiation (TLD) 34 Lyccming,NY(97) 1.8 mi 0 143' SE i Direct Radiation (TlD) 35 NewHaven,NY(56) 5.3 mi 9 123' ESE
- See Figures H-1 and H-2 for map locations L
Rev. No. 7 Page .3-ft of ODCM
TABLE H-1 (CONTINUED)
JAMES A. FITZPATRICK NUCLEAR POWER PLANT OFFSITE DOSE CALCULATION MANUAL (0DCM)
RADIATION ENVIRONMENTAL MONITORING SAMPLING LOCATIONS TYPE OF MAP
- SMFLE LOCATION COLLECTION SITE LOCATION DimetRadiation(TLD) 36 W. Boundary, Bible Canp(15) 0.9 mi 9 237' S Dimet Radiation (TLD)- 37 Lake Roac'(98) 1.2 mi @ 101* E-ESE Surface Water 38 OSS Inlet Canal (M) 7.6 mi @ 235' SW-WS Surface Water 39 JAFNPP Inlet Canal (NA) 0.5 mi 9 70' ENE l
Shoreline Sediment 40 Sunset Bay Shomline(NA) 1.5 mi @ 80' E Fish 41 NMP Site Discharge Area (NA) 0.3 mi 9 315' W and/or i Fish 42 NMP Site Dischame Area (NA) 0.6 mi 9 55' NE Fish 43 Oswego Harbor Area (M) 6.2 mi @ 235' WSW l
Milk 44 Milk Location #50(NA) 9.3 mi @ 93* SE Milk 45 Milk Location #7(NA) 5.5 mi 0 107' ESE Milk 46 Milk Location #16(NA) 5.9 mi 0 190* S ,
Milk -47 Milk Location #65(NA) 17.0 mi 9 220' SW t
~
Food Pmductst 48 Critical Garden #1(78) 1.5 mi 0 83' E (Bmad Leaf Cary Vegetation) l 49 Initially left Blank Food Pmductst 50 Critical Garden #2(79) 1.6 mi 0 84' E (Bmad Leaf Nerewski l
f Vegetation)
- See Figures H-1 and H-2 for map it. cations t Food product sanples need not be sspled frun each location listed.
Two onsite samples will be collec'ed from the location with the tation highest calculated is available. One average controlD/Q value sample from wi0 be which bmad collected leaf vyocation at a i listed from which bmad leaf vegetation 1; available.
Rev. No. 7- Page .3-2 of oDCM
i TABLE H-1 (CONTINUED)
JAMES A. FITZPATRICK NUCLEAR POWER PLANT OFFSITE DOSE CALCULATION MANUAL (0DCM) .
RADIATION ENVIRONMENTAL MONITORING SAMPLING LOCATIONS TYPE OF MAP
- SM9LE LOCATION COLLECTION SITE LOCATION ,
Food Pmductst 51 Garden #3(134) 1.7 mi 0 84* E (BroadLecf Kronenbitter Vegetation)
Food Pmductst 52 Garden #4(133) 1.1.mi @ 84* E (BroadLeaf Culeton Vegetation)
FoodProductst 53 Ganien #5 1.7 mi 9 82* E (BroadLeaf Dickenson Vegetation)
FoodProductst 54 Garden #6 1.9 mi @ 101' E (BroadLeaf Vitullo Vegetation)
Food Pmductst 55 Garden #7(76) 1.9 mi 0 103* ES' (BroadLeaf Johnson Vegetation)
FoodProductst 56 Garden #8(59) 1.5 mi 0 115' ES (BroadLeaf C. S. Parkhurst Vegetation)
FoodProductst 58 Garden #10(143) 1.6 mi 0 137' SE (Broad Leaf NM #541/2
-Vegetation)
Food Productst 57 Garden #9(142) 1.7 mi @ 142' SE ,
NM #49 (BroadLeaf)
Vegetation ,
See Figures H-1 and H-2 for map locations t Food product sam)les need not be sampled frun each location listed.
Two onsite sanpLes will be collected from the location with the highest calculated average D/Q value from which broad leaf veetation is available. One contml sample will be collected at a location listed frun which broad leaf vegetation is available.
, .Rev. No. 7 Page _E-1 of CDCM
l 1
i TABLE H-1 (CONTINUED)
JAME$ A. FITZPATRICK NUCLEAR POWER PLANT OFFSITE DOSE CALCULATION MANUAL (ODCM) j RADIATION ENVIRONMENTAL MONITORING SAMPLING LOCATIONS I
l TYPE OF MAP
- S#FLE LOCATION COLLECTION SITE LOCATION FoodProductst 59 Control #1(NA) 15.0 mi 9 223' SW Broad Leaf Md4111en (Vegetation)
Food Productst 60 Control #2(NA) 12.6 mi 9 225' SW Broad Leaf Derman (Vegetation) ,
Food Productst 61 Control #3(NA) 15.6 mi 9 220' SW t (BroadLeaf Flack Vegetation)
- See Figures H-1 and H-2 for map locations t Food product emples need not be sampled from each location listed. '
Two onsite samp;es will be collected from -the location with the highest calculated average 0/Q value from which broad leaf vegetation is available. One control samle will be collected at a location -
listed frem which broad leaf vegetation is available.
s Rev. No. 7 Page .jl-1 of ODcM
i a ,
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i FIGURE R-1 JAMES A. FIT 3 PATRICK NUCLEAR POWER PLANT ,
OFFSITE DOSE CALCULATION MANUAL (CDCN)
ENVIRONMENTAL SAMPLING IOCATION MAP i
i i
l- i l
FIGURE H 1 IS OVERSIZED AND IS LOCATED IN A FOLDER q AT THE BACK OF THIS DOCUMENT. i l i l
l 1 I 8
l Rev. No. 4 Page M-10 of ODCM
. . . . . . ~ . .. . - . - - - . . . _ . - . - - - - . - - - - - - - . . . . . _ - - _ . .
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i FIGURE I-2 ;
JAMES A. FIT 5PATRICE NUCLEAR POWER PLANT '
L-E orrsITE cost cALeULATIow unNUAL (opeu) ;
1 1
ENVIRONMENTAL SAMPLING IOCATION MAP i; l
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Rev. No. _,A Page J 11,, of ODCM
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l FIGURE I-3 l l
JAMES A. FIT 3PATRICE NUCLEAR POWER PLhMT l
OFFSITE DOBE CALCULATION MANUAL (CDCN) !
- l. LIQUID EFFLUENT PATHWAY - WATER INTAKE POINTS o
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Rev. No. 4 Page H-12 of ODCM
TABLE 5-2 JAMES A. FIT 3 PATRICK NUCLPAR POWER PLANT OFF8ITE D083 CALCULATION MANUAL (CDCM)
LIQUID EFFLUENT PATHWAY - 11ATER INTAKE POINTS DESCRIPTION AND PUMPAGE Location of Water Intake Averaae Water Pumnaae
~
Milllons of Gallons '
- 1. At a point between Dennison Creek and Beer Creek at a site north of the intersection of lake and Knickerbocker Roads 0.80
- 2. At Pultneyville 1.0
- 3. At a point north of the village of Sodus near the intersection of Shore Road and an extension of Maple Avenue 1.0
- 4. In Sodus Point Village on Lake Road 0.133
- 5. At east of Port Bay 0.095
- 6. In the western part of the City of Oswego between Sixth and Sheldon Avenues and north of West Schuyler Street 20.0
- 7. At east of the Village of Sacketa Harbor 0.30
- 8. In Sawmill Bay at a location on Independence Point approximately 0.5 miles south of Chaumont Village's southerly limit 0.04
- 9. Cape Vincent 0.246
- 10. Township of Pittsburg (Milton) 0.015
- 11. Township of Pittsburg (Glen Lawrence) 0.015
- 12. City of 60ngston (2 Intakes) 9.72
- 13. Township of Kingston (Pt. Pleasant) 0.705
- 14. Township of Kingston (Queen's Acres) 0.037
- 15. Township of Ernestown (Amherstylew) 0.270
- 16. Village of Bath 0.150
- 17. Town of Picton 0.679 Rev. No. 7 Page H-13 of-0DCM
y a n , , ...a.n ---- - - - - - >..a.s~a.n.---
e.a+. -. n .. _ .nu...a4..s n
i APPENDIX I 00CM SLMUUtY TABLES
l
]
APPENDIX I !
M SLNeuRY TABLES l l
IABLE TITLE active Effluent Release Limits Summary fa I-2 ODCM Summary I-4 I t
t 1 i TAKE I-1 '
l BASISKTIVE EFFLMNT anrm LEET 5 - SWOMEV TAKE '
bi i m M M assal F ANV IAWLE
~3.
SM SKIN M BWV SKIN MEAN 50BY ANV immest (anas) M SKIN OREAll (suusel (manol (unen) (senesol (mens) (messen Plant plember of Lieutd (2) the Public Effluents 0.06 Ilone 0.2 1.5 Ilone 5 3 Ilone 10 Plant -
flamber of Gaseous (2) the Pubitc Effluents lione Ilone None 5* 10* 7.5 1C* 20* 15 Plant At or Beyond Gaseous (3)
Site soundary Effluents Ilone Ilone Ilone IIone Ilone Hone 500 3000 1500 Uranium (4) flember of Fuel Cycle the Pub 1ic (Site) None None None 11one Ilone Hone 2S None 25(5) ,
(1) Equipment operability re (Liquid) and 3.6 (Gaseous)quirements for projected exposures.
Refer to Specifications 2.4 (2) Plant Liquid and Gaseous release limitations in accordance with Appendix I to 10 CFR 50.
Refer to 5pectitcations 2.3 (Liquids), 3.3 (Iloble Gases) and 3.4 (ledines and Particulates).
(3) Plant Gaseous release limitations in accordance with 10 CFR 20. Refer to Specification 3.2.
(4) Site Gaseous release limitations in accordance with 40 CFR 190. Refer to Specification 5.0.
(5) Limits to any organ except the thyroid whi ^ shall be limited to 75 mrem.
- mrad air dose.
_ . , . . . ~... _ _ . . . _ . _ _ _ _ _ _ -
F i
taste t-2 SoCm SENISAGT
< 56 t) e PeteefESCY TECS. SPEC. CoeeESpeSoleS SOCm tePet E F fitfEs t PeePOSE Of Of #EtetA* Set APPfeDES e 19mtT8ee sete Eeeettee esta eEPeefses CALCtft A T Ice CALCetafSee eEesteEmEef eteeleEGEst ettets SEdites essett eteegeteEsts eEestetagets WISCEtiewtews
% PAtewAT O.
fractlen of Each batch 18Cte20.19 Section 2.2 10 Cie 20 Section 3-1 . Seecaeree meteese mer ,se e (20U80
,a MPC, f g reteeee (c) MPCte) or, 3.2.2 structwee permit e6.peef6ee to Cia 28 for nebte eett flow epproacn of appendis e, gesee, . Deste t ent esta section Table 2, 2a 10 reteeee 3.2.2 Cotwen 2 wCl/et rete e
. S.e.ie C)*3 t
c.ncenir.- iesgtien.e i .
teens 10' vCe/ml LloulD minleve Each batch 10Cta20.10 Sect 6en 2.2 10 Cta 20 Section 3-2 . Semple Seteese required reteeee (e) MPCtes er, 3.2.3 c onc en t r e - permit dituttee it CFR 29, for dissolved tiene factor appendia 8, noble ggees, 2 ' 1s f 2#It *0"* I*"I' 2 Cetwen 2 wC6/et tieU40 Seteralne- Each botch 10CfR20.10 Sectlen fg less then Sectlen 3-3 . fg la pu t to tien of retenee (e) 2.1.e er equel to 1 3.3.2 . Seepte operettene efftwent 19 CFR 20 when calcule- c onc en t r e - i senIter appendia 8, ting einleve tiens eet-pointe fette 2, diletten flew Cetwen 2 Lieuse annuel Deee Cetender useeC Reg- Sectlen T.3 e/A s ec t l en 3-Se . Site annwet assessment year tetery 3.4.1 3-4b opecific Redleective Guide 1.21 deee Effluent comelt- Report teent fectore
. Pr eelewe yeer's retenee q, eetweee g, ond curies wQ Si te spec-() ,
Ific dite-tien in.estS.en 1r m.
(19989 monthly Cetender 10 Cia 30 Section 2.3 whole sedy Section 3-Se . Ceepeelte e/a mer use seee month Appendia I dose - 1.$ 3.4.2 3-Sb dese teme*ed O areorgtr. . eurotion enetyses assessment
"" 3 aree/yr of epareech Or gon dose - release of 00Cm
() $ eree/gtr. . Cortes section ty
() 18 meee/yr reteesed 3.4.2 J
- C . volwee of dilutlen
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tattE t-2 (Coctinuedt y eete sessner
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FREesEeCT TECO. SPEC. CemetePeseleS SOCe foret EFFiefst Peepest of et efeetates? APP (Sete e Etelftet este Geestges DATA etPee t te6 -
PAfeW67 CALCtfLAtleft CALCeLS7935 CE9e!PfmEst eteeleGmEst TeteES 3EC5995 Seeste seesseemsets seestateEsts e:SCEttaeEcos
, tieve9 Deze pre- Prior to e/A Section 2.4 whete body Sectlen 9/A . Swaber of If non-i jectlen - retenee of dose - 9.94 1.5 botch comPilence, determine- watreeted eree/menth reteeees, 30-der set t l tien of fleefs creen dose - preegeme re por t +
1 need to efftwents .2 oree/menth month l eperate . Projected I
i4qwtd nemmer of redwesto releeees l'
erstems current j eenth t
Caseows Determining Calender 19CFE23.165 Sectlen whste Body Sectlen 4-1 to . siehest sta ney wee e instanten- week 3.2.e.1 dose - Se8 4.3.1 46 ennwel e..eted !
ese; nebte erem/yr eversee enes,se, ges retcase Skin cose -
s/0 for appreecn ,
rotse 3000 ores /yr went end of Octa '
' eteweted Secteen 4.3.1 releases to detereine
. total nebte ses body, reteese rete ;
skin. end timets elr dose !
tectore (
. seble see i
release rete i (wCl/sec)
. Effectlee !
dose transfer tector
%s for eene 14 reteeeee'ef fractien e.eese a rete llelt F4 I
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tacit C-2 (Continued) eeCa spesett M
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4 fetoweect stCs. sPet. Coseesteesses seen soeuf EFftwEnf PuePOSE ff GF ret.#LAleef APPfeetN f LIslIIe6 SeCe EeWelles eel % etP@eIte&
2; PatewAf CALCWtaffee CALLWLAf3ec eteeleffetet efetPfeffuEtt waters SECffee someEc eteegegegets 6C es t eE M s ti ail s tt t t eet oes O
GASEOUS Detsreine- Calender 14CFR29.se$ Section Eteented section 6-7 . eenieve lepet to
-J tien of Jenth st 3.1 Seteese ,' 4.3.2 48 vetwee iperettene effluent open eejer 6.29 m It r e t e eee monttor operettenet wCl/sec eewrce set pef *As tremetente vent . Cellbre-tion cwrwe tl.e..
power level eelesse J.42 e 19
' (wC4/cc we i cSenses and vC4/sec Ces) for Setted fuell spec 4 fled effluent men t t et
. 8er presad ;
f evet releoses, ?
frostlen e? '
relewee rete F4ett i
etteceted to specified rete. .
peint i sasEous ceteretnine Calender 16Cte28.195 section thee aree/yr. sectlen 4-9 . tens-ters e/a radiolodine, weet 3.t.o.2 say *reen 4.3.3 4-10 eector i felttua eversee end 8 day c onc ent r e-particutete tien instanten- 1/#
eene (Ap.9ndle Cl i release ,
tees-term rates relative t degee f t lee 3 I we?ve gf (feble M 1, Appendfm C) d3 L) . eese facters ter oppliceble H4 enviren-j, mentet pothways i (7ebles e-4
() throweh P% e-6) sedene.
Telttwo
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ty - end 8 der
() porticklote DC reteese !
rete t wC 4 / l seep l
l
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M FetteESCT C99eESPeeD696 99CS 99PWI
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m e. S.PEC. e. . 5 = C. 4f..e .ef. M ,Getto.
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i PAfswAT CALC 9 tat 80s CALCWLAllSe SteWfeERGet MewtMMeV V4tWES MCffS5 eme efesteEmEsts eEest eent ets etSCEttsofous I
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tfSett Section 7.3 m/A Section 4-11 to . ,revleus Annwel-GASEOUS Annuet Dese Calender Assessment fear segulatory 4.4.1 4-19 year's medieecesse y ennwel Eff8 vent Gu6de 1.21 l< everage e e por t S/S end l n/e .
. Activity l
reteoced (wCl/yr.)
for the previeve peer iroo vent end i elevated releeees sonthly Celender SS CFR Se, Section seeme ett sectlen 4-20 . Gemme Air GASEOUS 4.4.2 6 23 Seee 9ese month Appendia 3 3.3.e Dese -
j $ ered/gtr. facters, e Assessment . Sete Air
- Geese ofr to ered/yr.
Sete ett Sese facter, Seee G
- Sete air Deee -
IS ered/gtr. . elpheet Dese enneet 20 ered/yr.
eversee s/e for went end eteweted releasee
. sette See cories eeieseed dwring the eenth
- Q 10 CFe 50 Sectlen Any orgen - Section 4-26 to e/A ney age GASEOUS nonthly Celender senth APPendte 8 3.4.e.1 T.5 oree/qtr. 4.&.2 4-2T tietted o Dose
- redle- 15 etee/ye. enetysts opproach of dedine, 00Cn See-I tritlee and $= day tien 4.4.2.c 3 4 portico-
- late et O
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TA3LE I-f (Centissued) eeCst semeAef M sets fseef O reteWEetf fECe. SPEC. Ceestspeesees REPeefles
< 99 DE8stAf987 APPfeefR e LlelffoS seC# E8eATtes DATA steelegeEefs GEcoteEREst s etSCEttmefoes
- E F F LtpE sf PtseresE of WAteEs SECitee Seeste g PAfewAT CALCtetaffte CALCOLAftee REeWieE9EST SteeleESEst O . Somme end If non- ner use o
. Sectlen 0.2 ored Section 4-28 Deee Prler to e/A 6-31 sete ele ceerstence, towitee snee.
GASEOUS 3.A somoe 4.5 projectlen retenee of 0.4 ered dose end 30 der met yees oppreech
'3 Deterelne- empreceased bete portice- report of Octm Sec.
tien of poseeee tote, le- teen 4.5.7 9.3 stem need to effluente orgen dine, and operate tritive off goe *reen dose treatment dertng the eretoe guerter to dote
, sweeer of days the plent is pr o j ec t ed
. to be operationet durtes the coeing month whole Sedy er Section 3-4 . Actuel Seeenetrate Celender 49 CfE 190 Sectlen 5.2 ditwtien Lieult 5.1.e eny ergen comra lence year if lageotten with annwet 46gmid (escept fettere reteseos thyreld) -
feet / cycle 25 meee/yr (fleh end dose comelt- escoed 3 thyreld -
potette ment timite aree, tetet T3 oree/yr weter) body, or 19 . Sedle-eres, any logical ergen Enotron-mentet menttering progree T reewtte CD 4Q O
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Teett I-2 (Continwed) geCe Sesoset
-N O TECo. seEC. Ceeefseososes sete seper 4' seeoutoCy oATA- efPORFtes SEtetAfeef APPESoff e LlettleS SOCe - EGeefles
- ' g y ptegget poePOSE et of WatetS eECT9ee amense ageogegegegg ageotegeGeis m8SCEt teetest
% PAfet8AT CALCetAtlee CALCeLAff00 SEGe8efeEST SEGe8eGeEST O
e unete body ee sectlen Esgwetten Current 30 der set Swest6tute SAStetsS Seeenetrete Cetender 49 Cta 190 Sectlen sectlen dete, seport the toget-5.1.e eny eroen 5.3 comptfence year, if 4.4 lecteding: body dose y with enneet seseges (eacept- sector teep
', thyroid) - octeet fwet cycle retenoes tecetten of ter en, go e 25 meee/yr.
dose comett- escoed 19 thyreld - reel ele oes, fee.
sent tielte erede seems 75 aree/yr. Individeote, ter tat s -
ele deoe, meteore-15 eroe logicot thyreld condtttone, er any end conswep-ernen of feed te.e.,
ettt, meet, and vegetetten) -l Whete medy - Sectlen N/A . Shieiding sirect gemenstrate Celender 40 CfE 198 Section catcotettene 5.1.e 25 ereotyr. 5.4 medie- complience year, if . fte reewits tien with ennwet tietwide or free environ-fuel cycle gases esceed mentet ,
I dose comit- dose Ilotte pr ogr ee teent lleits indicated obeve O
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