PY-CEI-NRR-0906, Semiannual Radioactive Effluent Release Rept,Jan-June 1988
| ML20153D791 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 06/30/1988 |
| From: | Kaplan A, Kensicki S CLEVELAND ELECTRIC ILLUMINATING CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| PY-CEI-NRR-0906, PY-CEI-NRR-906, NUDOCS 8809060038 | |
| Download: ML20153D791 (202) | |
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THE CLEVELAND ELECTRIC ILLUMINATING COMPANY PERRY NUCLEAR POWER PLANT UNIT 1 SEMIANNUAL RADIOACTIVE EFFLUENT t RELEASE REPORT T
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1988: QUARTERS 1 & 2 l
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Approved By'
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S MA 1m Plant Tecyni' cal Director i
DU , M . 0 GeneTal ManasTf[of OpeTations 8809060030 000630 PDR ADOCK 05000440 R PNV 4
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TABLE OF CONTENTS Page Introduction .......................................... 4 Radiological Impact on Man ............................ 5 Supplemental Information .............................. 7 Liquid Effluents ...................................... 9 Gaseous Effluents .................................... 11 Solid Waste .......................................... 13 Meteorological Data .................................. 13 Abnormal Releases .................................... 13 Appropriate Technical Specification Requirements ... . 14 1
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ATTACHMENTS Attachment 1: Radiological Impact on Man (Dose Summaries)
I Attachment 2: Radiological Impact on Man (Land Based Sectors)
Attachment 3: Technical Specification Limits Attachment 42 Liquid Effluents Attachment 5: Gaseous Effluents Attachment 6: Solia Waste Attachment 7: Meteorological Data
- Attachment 8
- offsite Dose Calculation Manual (ODCM) Changes Attachment 9: 1988 Annual Land Use Census 1
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INTRODUCTION ,
This Semiannual Radioactive Effluent Release Report (SRERR),
covering the period of January 1 through June 30, 1988, is submitted in accordance with Section 6.9.1.7 of Appendix "A" (Technical Specifications) to Perry Nuclear Power Plant ;
(PNPP) License No. NPF-58. It is designed to meet requirements of Regulatory Guide 1.21, as applicable to the '
PNPP Technical Specifications. Portions of the Technical Specifications applicable to this report, Sections 3/4.3.7.9, 3/4.3.7.10, 3/4.11, 3/4.12, 6.13.2, 6.14.2, and 6.15.1, are known as the Radiological Effluent Technical Specifications l' (RETS).
During quetters 1 ar.d 2 the plant produced 3,214,679 Megawatt Hours Electric Gross. The reactor capacity averaged 60 -
percent while the reactor was critical a total of 30C5 hours. !
Liquid and gaseous radioactive effluent releases to the environment during this reporting period were sampled and i analyzed in accordance with the requirements of the Technical Specifications. All radioactive effluent releases were i within the concentration and release limits specified in the j RETS.
Calculations and terms utilized in this report are those outlined in the PNPP Offsite Dose Calculation Manual (ODCM). !
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RADIOLOGICAL IMPACT ON MAN Sampling and analysis of liquid and gaseous effluents were performed in accordance with the frequencies, types of
, analysis, and Lower Limit of Detection (LLD) outlined in the ,
l PNPP Unit 1 Technical Specifications. ;
3 Radioactive material was detected in some of the liquid and gaseous effluent samples analyzed. Dose calculations, using ,
measured effluent flow and meteorological data, resulted in r dose to individuals at levels below 10CFR20 and 10CFR50, !
Appendix I limits. Direct radiation resulting from plant f operation, as measured by environmental thermoluminescent ,
I dosiaeters located around the plant, did not contribute any measurable dose to members of the public for the reporting i i period and, as there are no other nearby fuel cycle sources, 40CFR190 limits were not exceeded.
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Summaries of maximum individual and population doses resulting from liquid and gaseous radioactive effluent releases are given, in Regulatory Guide 1.21 format, in Attachment 1. .
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l Technical Specification 6.9.1.7 requires assessment of l' radiation doses from radioactive liquid and gaseous effluent l to members of the public while onsite. These onsite doses 4 ere assessed relative to offsite dose values, and are i adjusted for appropriate dilution, dispersion, and occupancy ,
j factors.
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ONSITE DOSE FOR LIQUID EFFLUENTS i
- I The onsite liquid effluent pathway of concern for members of !
(f the public is shore exposure while fishing along the Lake i Erie coast. Occupancy is assumed to be 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> per year and
. the dilution factor for the point of exposure is 10.
l Ratioing *.his exposure pathway to doses calculated for l
- offcite locations yields the following onsite dose values.
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Total Body l
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Quarters 1 & 2 2.3 E-04 mism 2.7 E-04 mrem (skin) !
, Quarter 1 1.0 E-04 meem 1.2 E-04 mrem (skin) l i Quarter 2 1.3 E-04 mrem 1.5 E-04 mrem (skin) ;
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t ONSITE DOSE FOR GASEOUS EFFLUENTS Several cases are considered for onsite gaseous effluent #
exposure to members of the public including traversing a public read within the site boundary, shoreline fishing, non-plant related training, car pooling, and job interviews.
The onsite activity with the-highest dose potential, relative to gaseous effluents, is shoreline fishing. Occupancy is again assumed to be 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> per year. Accounting for this and the difference between annual average disgersion values ;
for the onsite point of concern, 6.6 E-05 s/m , (a unity occupancy factor is assumed for this calculation), the following maximum onsite dose values are generated.
Tota! Body Organ Quarters 1 & 2 1.1 E-01 mrem 4.9 E-01 mrem (thyroid) 1 Quarter 1 1.1 E-03 mrem 3.6 E-03 mrem (thyroid) ,
j Quarter 2 1.1 E-01 mrem 4.9 E-01 mrem (thyroid) i AVERAGE INDIVIDUAL TOTAL BODY DOSES
, Average total body dose to individual members of the public is determined for the population that lives within fifty miles of the plant for gaseous effluents (2.42 E+06 persons) and the population that receives drinking water from intakes within fifty miles for liquid effluents (2.37 E+06 persons).
These doses are calculated using the total population dose i figures found in Attachment 1.
Gases Liquids Quarters 1 & 2 9.9 E-05 mrem 3.3 E-05 mrem Quarter 1 1.2 E-07 mrem 1.1 E-05 mrem l 4
Quarter 2 9.9 E-05 mrem 2.2 E-05 mrem ;
- Gaseous cnd Air Dose calculations at the site boundary were 2
performed for two cases. Attachment 1 provides the l calculated maximum site boundary dose values for all sectors 1 including those sectors which are totally over water in which no member of the public resides (These are the W, WNW, NW, 3
NNW, N AND NNE SECTORS). Attachment 2 provides the
{ calculated maximum site boundary dose values for the land
< based sectors in which members of the public reside.
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SUPPLEMENTAL INFORMATION Regulatory Limits Technical Specifications 3/4.11.1 and 3/4.11.2 outline requirements for release of radioactive liquid and gaseous effluents, respectively. Concentration of radioactive i material in liquid effluents and dose or dose commitment ,
resultant thereof are limited in unrestricted areas. Dose :
and dose rate due uo radioactive materials released in I gaseous effluents cre limited in areas at or beyond the site l l boundary. Technical Specification limits are *isted in i Attachment 3.
s Maximum Permissible Concentrations J
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The Maximum Permissibla Concentrations (MPCs) in liquids are ,
those outlined in Technical Specification 3.11.1.1 (10CTR20, t Appendix B, Table II, Column 2, with the lower of the soluble 4
and insoluble MPC being used; for dissolved and entrained i noble gases, concentrations are limited to 2 E-04 vCi/ml). !
PNPP Unit 1 Technical Specifications do not contain a l concentration requirement for gaseous releases, therefore, ;
i MPCs are not used to calculate maximum release rates for 1 radioactive gaseous effluents.
Averace Energy i Average energy requirements for radioactive effluent mixtures do not apply to PNPP Unit 1 Technical Specifications ot Off- '
site Oose Calculation Manual.
i Measurements and Approximations of Total Radioactivity (
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} Analyses of specific radionuclides in effluent samples ats 1
- used with efflu2nt path flow measurements to evaluate the l 1 radioactive composition and concentration of effluents.
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Batch Releases Liquid effluent releases were considered continuous (t Emergency Service Water (ESW) Loops A and B) as well as bate'.
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(Liquid Radwaste (LRW) discharges). Although the ESW t 9 tem a is considered to be a continuous release path when in :
service, it is not run continuously. !
All gaseous effluent releases from Perry Nuclear' Power Plant were considered continuous.
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LIQUID RELEASES t
't January 1 - March 31, 1988 Batch continuous Number of Releases 78 25 f i
Total Time of Releases (min) 1.4 E+04 2.2 E+05* r Minimum Time for a Release (min) 5.0 E+00 1.3 E+01 i Average Time for a Release (min) 1.8 E+02 9.0 E+03 '
Maximum Time for a Release (min) 2.7 E+02 8.6 E+04 l Average Effluent Stream riow 2.3 E+05 2.4 E+05 ;
During Periods of Release (1/ min) i
April 1 - June 30, 1988 {
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Number of Releases 47 43 l Total Time of Releases (min) 8.5 E+03 1.7 E+05, :
Minimum Time for a Release (min) 2.0 E+02 3.7 E+01 !
Average Time for a Release (min) 1.8 E+02 4.0 E+03 Maximum Time for a Release (min) 2.8 E+02 7.1 E+04 l l
Avarage Effluent Stream riow 2.4 E+05 2.2 E+05 !
During Periods of Release (1/ min)
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d LIQUID EFFLUENTS ,
, ror the first quarter of 1988 there were 78 batch and 25
- continuous releases. Batch release total waste volume for the fir-t quarter was 7.3 E+06 liters; total continuous ,
I release waste volume was 7.9 E+09 liters; total plant disclarge during periods of release was 5.3 E+10 liters. ;
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- i. continuous releases. Batch release total waste volume for 4
the second quarter was 4.4 E+06 liters; total continuous
- release weste volume was 6.3 E+09 liters; total plant i
- diseastge during periods of release was 3.8 E+10 liters. !
Sus 3 aries of the radionuclidc total curie activities, average i
, diluted concentrations, and percentage of MFC (in Regulatory ,
! Guide 1.21 format) are included in Attachment 4. '
j If a radionuclide was not detected, zero activity was used for that isotope in dose calculations. A zero activity [
i indicates that the tsdionuclide was not present at a level i j greater than the Lower Level of Detection (LLD) of the 1 instrumentation used. In all cases, these LLDs were less
- than the levels required by Technical Specifications. The i following are typical LLDs. {
8 Co-58 1.9 E-08 '
! Co-60 3.4 E-08 !
- n-55 4.6 E-08 l 4
Mo-99 2.1 E-07 l I-131 2.3 E-08 i
, Cs-134 2.3 E-08
, Cs-137 2.6 E-08 Ce-141 3.2 E-08 '
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Co-144 1.3 E-07 i
J Sr-89 3.0 E-08
! St-90 3.7 E-08 j re-55 5.7 E-09 J H-3 4.6 E-06 j Gross Alpha 6.0 E-08 i
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i Estimates of error associated with sample analysis, discharge volume, and dilution volume follow. Analytical error terms are based on split sample analysis results, the majority of 4 ;
which are confirmatory measurements, the others are inter-laboratory comparison results. Discharge and dilution ,
volume (flow rate instrumentation) error is assessed using loop instrumentation accuracy teriss. -
Gamma Analysis 10% !
- H-3 Analysis 8% ,
Sr-89/90 Analysis 10%
re-55 Analysis 21%
Gross Alpha Analysis 4% !
Service water Volume 31% 7 (Dilution)
Emergency Service water 25%
Volume (Discharge) a Liquid w_swaste volume 1%
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i GASEOUS EFFLUENTS ,
t Summaries of the radionuclide total curie activities, average ;
release rates (in Regulatory Guide 1.21 format) are included l in Attachment 5. j l
l If a radionuclide was not detected, zero activity was used !
j for that isotope in dose calculations. A zero activity !
) indicates that the radionuclide was not present at a level 1 greater than the Lower Level of Detection (LLD) of the instrumentation used. In all cases, these LLos were less than the levels required by Technical Specifications. The
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- Kr-87 1.7 E-08 i
. Kr-88 2.3 E-08 l l Xe-133 1.8 E-08
. Xe-133m 5.3 E-08 Xe-135 6.4 E-09 Xe-138 1.0 E-07 Mn-54 2.7 E-13 '
re-59 5.6 E-13 ;
Co-58 3.2 E-13 i
,, Co-60 4.6 E-13 ?
2n-65 7.7 E-13 !'
- Mo-99 2.1 E-12
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Cs-134 2.1 E-12 Cs-137 3.1 E-13 Ce-141 3.2 E-13 Ce-144 1.5 E-12 I-131 2.8 E-13 !
I-133 4.9 E-13 :
I Sr-89 3.8 E-14 +
St-90 6.8 E-14 l H-3 3.0 E-10 i Gross Alpha 5.4 E-12
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Estimates of error associated with sample analysis,. sample flow rate, and effluent flow rate follow. Analytical error i terms are based on split sample analysis results, the i majority of which are confirmatory measurements, the others are interlaboratory comparison results. riow rate 4 instrumentation error is assessed using loop instrumentation accuracy terms. .
Noble Gas Analysis 1.1%
I Particulate Analysis 9% .
Iodine Analysis 12% i H-3 Analysis 8%
Sr-89/90 Analysis 10% i Gross Alpha Analysis 4%
. Sample riow Rate 10% ,
j Effluent riow Rate 9%
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, SOLID WASTE There were 22 solid radioactive waste shipments transported (
j from PNPP for the period covered by this report. In The 22 r shipments, there were 14 dewatered liners and 11 solidified ;
!. liners. There was no irradiated fuel transported from site. f See Attachment 6 for volume and activity values.
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d METEOROLOGICAL DATA '
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Cumulative joint frequency distribution (JrD) tables of wind l I speed and direction for each stability class, as well as for ;
- all stability classes combined, are given in Attachment 7 for l
, the semiannual period and for each annual quarter of the time period covered by this report. ,
f These JrD tables are the results obtained from the processing l j of hourly average meteorological data collecteo at the PNPP i
- site met tower. It should be noted that the 1-3 mph JrD l i
column includes wind speeds down to 0.1 mph and that hours of i 0 wind speed appear only in the totals columns. The separate l
- tallies of periods of calm include wind speeds from-0.0 to l 2 0.7 mph. Differential temperature (oT 60 - 10 meters) is L generally used for atmospheric stability classification.
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ABNORMAL RELEASES f There were no abnormal liquid or gaseous effluent releases during the reporting period. i J
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APPLICABLE TECHNICAL SPECIFICATION REOUIREMENTS Per PNPP Technical Specifications, certain noncompliance items, changes, and findings are reportable in the Semiannual ,
j Radioactive Effluent Release Report.
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Radioactive Liquid Effluent Monitoring Instrumentation noncompliance (PNPP Technical Specification 3.3.7.9, Action b.): ,
There were four cases in which liquid effluent ,
monitoring instrumentation was not restored to an r
- operable condition within the time period required
- by Technical Specifications.
f The Emergency Service Water-A Loop discharge
! radiation monitor (1D17K604) was declared ,
l inoperable on May 16, 1988. Work on the system
) consisted of replacing carbon steel piping with ,
stainless steel piping to improve flow to the f
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monitor and install a temporary shield to reduce ,
background radiation levels. The monitor was declared operable on August 5, 1988.
The Emergency Service Water-B Loop discharge i radiation monitor (1D17K605) was declared ,
3 inoperable on May 8, 1988. Work on the system l consisted of replacing carbon steel piping with stainless steel piping to improve flow to the i monitor. The system was declared operable on July j 19, 1988.
The service Water (OP41K444) flow monitor was inoperable on November 7, 1987. Work on the system consisted of replacing and calibrating the monitor. 1
! The system was declared operable March 7, 1988. i
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- The Emergency Service Water (1P45K272) flow monitor I was inoperable on November 7. 1987. Work on the i system consisted of replacing and calibrating the
- monitor. The system was declared operable on March 1 6, 1988. On April 25, 1988 the system was declared j inoperable due to a channel check failure. A new 1 calibration curve was developed and as of August
- 26, 1988 the system was declared operable.
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4 i Radioactive Gaseous Effluent Monitoring Instrumentation noncompliance (PNPP Technical Specification 3.3.7.10, ,
Action b.):
t There were no occurrences of inability to restore inoperable radioactive gaseous effluent monitoring :
- instrumentation, listed in Technical Specification l i Table 3.3.7.10-1, to the minimum channels operable t l within the time period specified in the applicable l 1 action note. !
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L i Liquid Holdup Tanks noncompliance (PNPP Technical (
Specification 3.11.1.4, Action a.):
There were no outside temporary tanks containing radioactive liquid on the PNPP site 6uring the I
reporting period, therefore, the applicable Tech-
) nical Specification limit was not exceeded.
j i Radiological Environmental Monitoring Program (REMP) changes (PNPP Technical Specification 3.12.1, i l
Action c.):
Por the reporting period, samples were obtained at i
- their respective locations as required by the spec- !
ified collection frequencies. t l
! The program underwent minor changes during the i reporting period. Milk sampling location 61 was l added so goat milk could be sampled year round. '
Milk sampling location 30 was reinstated. Water sampling locations 59 and 60 were changed to make !
I easy access for personnel.
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Land Use census findings (PNPP Technical Specification 3.12.2, Actions a and b.):
The Land Use census had two minor changes during the reporting period. The first was occupancy of the house at 3121 Center Road and the resident's garden in the S sector. The second was in the WSW sector in regards to the nearest garden, it changed
.o 1.9 miles from 1.2 miles. See attachment 9.
! Process Control Program (PCP) changes (PNPP Technical Specification 6.13.2):
There were no changes made to the Process Control Program during the reporting period.
Offsite Dose Calculation Manual (ODCM) changes (PNPP Technical Specification 6.14.2):
, The Offsite Dose Calculation Manual was revised for the third time and was effective February 24, 1988.
i The scope of the revisi.on was: Incorporation of Temporary Change Notice (TCN)-2 through 8 to l
revision 2; Deletion of atmospheric dispersion and i
deposition parameters for the nearest residence
, with animal and garden locations because this information is available in the Annual Enviromental Operating Report; Incorporate Radiological Environmental Sampling Program changes. Changes to the third revision were made through TCN-1 and 2.
These changes were made to reflect Radiological Environmental Monitoring Program changes.
See Attachment 8.
Page Change 80,87,88,89, REMP location changes and 90 additions. ,
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Major Changes to Radioactive Waste Treatment Systems (PNPP Technical Specification 6.15.1):
There were no major changes to radioactive waste treatment systems during this SRERR period.
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Attachment 1 Radiological Impact on Man (Dose Summaries)
Attachment 1 (Page 1 of 3)
Radiological Impact on Man (Dose Summaries) .
1988: Quarters 1 & 2
SUMMARY
OF MAXIHUM INDIVIDUAL 00hES LIQUID 98 1 1 1-88 43024 GASEQUS 88 1 $ 1-WB 63024 AIR 88 1 1 1-88 63024 APPLICABLE EST! HATED AGE LOCATION % OF L1 HIT EFFLUENT ORGAN DOSE GROUP DIST DIA APPLICA>LE (MREM) (M) (TOWARD) LIMIT (MREM)
LIQUID TOTAL PODY 3 40E-04 TEEN RECEPTOR 1 1.1E-02 3.0E+00 i
LIQUID THYRDID 2.05E-03 CHILD RECEP10R 1 2 1E-02 1.0E+01 NOBLE GAS AIR DOSE 1 70E+00 294. N 1.7Lf01 1 0L401 (GAMMA-MRAD)
NOBLE GAS AIR DOSE 2 39E+00 294. N 1 2Lf01 2.0Lf01 (BETA-MRAD)
NOBLE GAS T. BODY 1.00E+00 ALL 294. N 2.0L+01 b.0L+00 t NOBLE GAS SKIN 2 29E+00 ALL 294. N 1 5E+01 1 5E+01 10DINEL THYR 0!D 4.56Ef00 INFANT 294. N 3.0E+01 1.$E+01 PARTICULATES
SUMMARY
OF POPULATION DOSES I
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) EFFLUENT APPLICABLE ESTIMATED !
ORGAN POPULATION DOSE !
(PERSON-REH) l I
LIQUID TOTAL BODY 7.8E-02 f LIQUID- THYR 0!D 3.0E-01 !
i 6ASE0VS TOTAL BODY 2.4E-01 t j GASEOUS THYR 0!D 1.2E+00
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Attachment 1 (continued - Page 2 of 3)
Radiological. Impact on Man (Dose Summaries) ,
1988: Quarter 1
SUMMARY
OF MAXIMUM INDIVIDUAL DOSES LIGil!D 98 1 1 1-89 33194 GASEOUS 88 1 1 1-80 331.%4 AIR 98 1 1 1-H8 33124 APPLICABLE ESTINATED AGE LOLAT!UN 1 inF LI61T EFFLUENT ORGAN DOSE GROUP DIST DIk AFFLICAblL (MREM) (H) (TOWARD) Llbli ( hf.f is e LIQUID TOTAL BODY 1.43E-04 TEEN RECEPT 0R 1 4.8E-04 3. 0 E + 0 :e L10VID GI-TRACT 5.58L-04 ADULT RECEPT 0k 1 L.6E-03 1.0Ef01 4
NOBLE GAS AIR DOSE 2 26E-03 294. N 2.3E-02 1.0L+01
< (GAMMA-MRAD)
NOBLE GAS AIR DOSE 2.80E-03 294. N 1 4E-02 2 0Ef01 (BETA-MRAD) i NOBLE GAS T. BODY 1 46E-03 ALL 294. N 2.9E-02 5.0E+00 NOBLE GAS SKIN 3.77E-03 ALL 294. N 2.5E-02 1.5E+01 l'
10DINEL THYROID 3 3TT-02 CHILL 280. NNW 2.3E-01 1.5E+01 PARTICULATES
SUMMARY
OF PDFULATION D0SES LIQljlD GB 1 1 1-88 33124
......................E.O.US...... GAS
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1-88 33124
! EFFLUENT APPLICABLE EST! HATED
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ORGAN POPUL ATION '0SE (PERSON-RFn)
LIQUID TOTAL 90DY 2.6E-02 LIQUID THYR 0!D 8.5E-03 6ASE0VS TOTAL PODY 3.0E-04 GA3EOUS THYROID 2.9E-03 i
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Radiological Impact on Man (Dose Summaries) 1988: Quarter 2
SUMMARY
OF MAXIMUH IHDIVIDUAL D0SES b ! h5 hh f f~h! $!hh4 AIR WB 4 1 1-88 63024 t
APPLICABLE EST! HATED AGE LOCATION % OF LIMIT EFFLUENT ORGAN DOSE 6ROUP D151 b!R AFF LICA>LE (MREM) (M) (TOWARD) Lintf (MRENs LIQUID TOTAL 80DY 1.97E-04 TEEN RECEPTOR 1 6.6E-03 3.0E+00 LIQUID THYR 0ID 1.99h-03 CHILD RECEPTOR 1 2 0E-02 1.0Ef01 ,
................................... r NOBLE GAS AIR DOSE 1.70E+00 294. H 1.7E+01 1 0E401 GAMMA-MRAD)
NOBLE GAS (AIR DOSE 2.39E+00 294. N 1 2E401 2 0E+01 (BETA-MRAD)
NOBLE GAS T.90DY 1 00E+00 ALL 294. N 2.0Lf01 5 0E400 NOBLE GAS ShlN 2.29E400 ALL 294. N 1.5E+01 1 5E+01 10 DINE 1 THYROID 4.53E+00 INFANT 294. N 3 0E+01 1.LE+01 PARTICULATES l SUMMAR) 0F POPULATION DOSES LIQUID BB 4 1 1-88 43024 f 88 4 1 ...............................
GASEOUS 1-Bb 63024 EFFLUENT APPLtCABLE ESTIMATED <
ff[kshkREkf '
LIQUID TOTAL PODY 5.2L-02 !
LIQUID THYR 0!D 3.0E-01 '
6ASEOUS TOTAL 90DY 2 4E-01 6ASEQUS THYROID 1.2E+00 L
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Attachment 2 Radiological Impact on Man (Land Based Sectors)
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Attachment 2 (Page 1 of 1)
Radiological Impact on Man (Land Based Sectors) 4 Quarters 1 & 2 APPLICABLE ESTINATED AGE LOCATION 10F LIMIT EFFLUENT ORGAN DOSE 6ROUP DIST DIR APPLICABLE ,
(MREM) (M) (TOWARD) LIMIT (HREM:
NOBLE GAS AIR DOSE 3.07E-01 478. NE 3.1E+00 1.0E+01 (GAMMA-MRAD)
NOBLE GAS AIR DOSE 3.49E-01 1452. SSW 1.7E+00 2.0E+01 (BETA-NRAD)
- NOBLE GAS T.80DY 1.77E-01 ALL 678. NE 3.5E+00 5 0E+00 NOBLE GAS SKIN 3.73E-01 ALL 678. NE 2 3E+00 1.3E+01 I
10 DINE 4 THYR 0!D 3 40E+00 INFANT 900. WSW 2 3E+01 1.3E+0!
PARTICULATES i
Quarter 1 i
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NOBLE GAS AIR DOSE 1.04E-03 678. NE 1 0E-02 1.0E+01 1 (GAMMA-MRAD)
! NOBLE GAS AIR DOSE 6.46E-04 678. NE 3.2E-03 2.0E401 (BETA-MRAD) l NOBLE GAS T. BODY 5.85E-04 ALL 672. NE 1.2E-02 5.0E+00
) NOBLE GAS SKIN 1 14E-03 ALL 676. NE 7 4E-03 1 5E+01 !
10 DINE 1 THYR 0!D 4.08E-03 CHILD 900. WSW 2.7E-02 1 5E+01 PARTICULATES I
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NOBLE GiS AIR DOSE 3.06E-01 478. NE 3 1E+00 1 0E401 (GAMMA-MRAD)
NOBLE GAS AIR DOSE 3.49E-01 1452. S5W 1 7E+00 2.0E+01 (BETA-MRAD)
NOBLE GAS T. BODY 1.77E-01 ALL 678. NE 3.5E+00 L.0E+00 N0BLE GAS SKIN 3.74E-01 ALL 678. NE 2.5E+00 1.3E+01
. 1001NE1 THYR 0!D 3 40E+00 INFAN! 900. W5W 2 3E+01 1.5Et01 1
PARTICULATES l
1
- - - - - - - - - - , - , - - - - + . - , , - ,
i Attachment 3 Technical Specification Limits i
l
t <
l 1 i l
i
' Attachment 3 (Page 1 of 1)
! Technical Splaification Limits.
i i l '
i LIQUID ErrLUENTS:
- Concentration < 10CTR20
- release rate limit ,
Appendix,B, Table II, TS 3.11.1.1 ;
a Column 2 2
- < 1.5 aren total body a quarterly dose limit i i 1 5 atem any organ per TS 3.11.1.2 4
- 1 3 mrem total body
- annual dose limit
- i 10 arem any organ per TS 3.11.1.2 4
)
) GASEOUS EFFLUENTSt i Noble Gases '
1 ;
I * < 500 mrem /yr total body
- dose rate limit j i 3000 mrem /yr any organ per TS 3.11.2.1
! * < 5 mrad air gamma
- auarterly air dose l i 10 mrad air beta ,1 1 mi t per TS l
! 3.11.2.2 j l ,
- < 10 mrad air gamma
- annual air dose i
! 3 20 mrad air beta limit per TS l 1 3.11.2.2 I-131, 1-133, H-3, Particulates with Halflives >8 Days !
.I * < 1500 mrem /yr any organ a dose rate limit per l q
a
- 1 7.5 mrem any organ
- quarterly dose limit 'l j per TS 3.11.2.3 c
! t
!
- 1 15 arem any organ
- annual dose limit j per TS 3.11.2.3
]
4 l !
I
! - Dissolved or ent.ained noble gas concentration !
) is limited to < 2 E-4 vCi/ml. - !,
i i
)
i Attachment 4 Liquid Effluents
.l l
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i i i
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1 l l l
s Attachment 4 (Page 1 of 2)
Liquid Effluents GUARTER 1 1 START DATE 88010101 END DATE 88033124 9UARTER 2 1 START DATE 88040101 END DATE 88063024 t
a LIQUID EFFLUENTS --
! ! UNITS t QUARTER 1 QUARTER I
.........I.... 1......! ............I 3
I 2
- A. FISSION AND ACT!VATION PRODUCTS l ..........................................................
I 1. TOTAL RELEA$E (EXCL.! CI ! 1 72E-02 1 1.42E-02 I i 1RIT.e GASES: ALFHA)! I t t
.....................r.................................... -
i ! 2. AVERAGE DILU1ED IUC!/ML ! 3 25E-10 1 3 75E-10 t
! CONC. DURING PERIOD t t t t t 3. PERCENT OF t % 1 0.00Et00 1 0.00E+00 t i APP I t i
........L.I C A bL E L I M I T......t ................................
B. TRIT!UM I 1. TOTAL RELEASE t Cl i 1 72E+00 1 1.41E+00 !
1 1 2. AVERAGE DILUTED !UCl/ML t 3 24E-08 t 3 70E-08 1 1 CON
. . . . . . . .C......
! 3. PERCENT OF
.DU ...R. I.N.G P E.R I.O.D. . I ....................I I
1
.i ! I i 1 08E-03 1 1 23C-03 1
.1 1 APPLICABLE LIMIT t t t t l
1 l 1
C. DISSOLVED AND ENTRAINED GASES t 8 1. TOTAL RELEASE 5.10 4
1
.........................................L-OS t Cl 1 1 1 00E-02 8 i
! 2. AVERAGE DILU'ED IUCI/hL t 9.62E-13 1 2.64E-10 t CONC. DURING PIRIOD t t t !
! 3. PERCENT OF i 1 1 4.81E-07 1 . 32E 04 I t APFLICABLE LIMIT
..........................................................t t t t '
D. GROSS ALPHA RADICACTIVITY '
i I 1. TOTAL RELEASE I CI t 0.00E+00 1 6.00E
......................................................+.00 ...
t E. VOLUNC WASTE RELEASED ILITER5 t 7.90E+0? I 4 29E+09 I I (PRIOR TO D i U T I O N )I t
. . . . . . . . . . . . . . .! .L.......................................... t t
.......................................................... i t
F. VOLUME DILUTION WATER ILITERS 4 5 300+10 1 3.80E410 t 1 USED DURING PERIOD t I i t !
,! l I
I l
4 1
l
Attachment 4 (Continued - Page 2 of 2)
Liquid affluents L!0U!D EFFLUENTS
........................................... 4.........................
QUARTER 1 i START DATE 68010101 END DATE *?073124 OUARTER 2 i START DATE 88040101 EF* PAIE 88063024 L l
CONT 1NDuus N0bl 941CH MODE I NUCLIDES i UN!'S I QUARYER 1 QUAk1ER 1 QUAR 1LR ! QUARTER 1 2 i 8 RELEASED 8 8 1 1 2 1 1 1 1 I H3 1 1 72E40
........ 0..1 . 1 .41L+00 t
. . . . . . . . . . . . . . . .C.1. . ...1 . 0.
...0 0.E 4 0 0. 1...... 0. 0 0 L.+.0 0. .1 ........
I NA24 i C1 1 0 00E+00 1 0.00L+00 1 1 491-04 1 0 00L400 t
! CR51......1..CI ...I. 4.k
.... . ... 0. 00E+00.
.... .1. 0. 00E+00 1 1.L-03 1.. .. ..S. ......
...... .... 17L-03.1
! MN54 8 C1 1 0 00E+00 1 0 00E400 1 3.62L-03 1 2 76E-03 8
! MN56 i C1 1 0.00E+00 8 0.0CE+00 t 3 93E-04 ! 0 00f400 1 >
8 FE59 t C1 1 0.00E+00 1 0.00E+C0 1 7 93L-04 1 6 10L-04 8 0.00E+00 8
. . . . . . . . .I. .CI
.I. .C058 . . . . .I. .0.00Ef00
. . . . . . . . 1. . . . . . . . . . . . . . . .....
- 2. 9 4 L - 0. .....
3 8 . 1. 0 6. L - 0 3 1
! C060 t C! l 0 00E+00 1 0 00E+00 1 2 06L-03 8 2.b7f-03 I t TC99M I C! l 0 00E+00 1 0 00E400 t 2.02E-05 1 7.51L-Or.
t I AG110M ! C1 1 0.00L+0C ! 0.00E+00 1 2 44L-05 1 2 49E-04 I
.I . .1 13.1. . . . . 1. . .C. !. . . . .l. 0.. 0
...0.E + 0 0. .0. t..00.E400.
.. . 1. 0. 00.E.400 1...... 1 66.E..03
.. .... I I !133 t C1 1 0.00E400 ! 0 00Ef00 1 0 00E400 1 2 07L-OL t t CS137 t CI t 0.00E400 1 0 00E+00 1 0.00L+00 1 2.62[-05 t
! AS76 i C! l 0.00E+00 8 0 00E+00 1 2.02E-04 1 0 00L+00 t 1 SB124 i CI I 0.00E+00 1 0 00E400 1 0 00L+00 t 2.37E-05 t 1 TOTAL FOR 1 i I t I t PERIOD t C1 1 0.00Ef00 1 0 00E+00 1 1 73E+00 1 1.42E+00 t I (AROVE) ! I I I t t t XE133 Cl ! 0.00E+00 t 0.00E+00 1 4 63E-05 t 9.49E-(3 i t XE135 t C1 1 0.00E+00 1 0.00E+00 1 2 72E-06 1 3.13E-04 i t XE135H t CI i 0.00E+00 t 0.00E+00 1 0.00E+00 1 1.36E-04 1 t XE133H t CI I 0 00E+00 8 0 00Et00 1 0 00L+00 t 8.47E-05 i
d Attachment 5 Gaseous Effluents j 4
d
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a t
I
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Attachment 5 (Page 1 of 2)
Gaseous Effluents 2
OUARTER 1 1 START DmTE 800 0101 END DATE 08033124 00ARTER 2 i START DATE 86040101 END DALE 86063024 EFFLUENT AND WASTE DISPOSAL REPORT GASEQUS EFFLUENTS -- SUMMATION OF ALL RLLLASES I UNITS 1 QUARTER I QUARTER 1
! ! 1 8 2 I A. FIS$10N AND ACT!VATION GASES
- 1. TOTAL RELEASE t CI
.....................................................~....
I 8 70E-01 ! 9.97E+02 I
! 2. AVERAGE RELEASE tuC!/ SECT 1 11E-01 1 1.27Et02 1 l
! RATE FOR PERIOD ! I t t 3. PERCENT OF 1ECHNICALI 1 4 0,00E+00 1 0.00E+00 t i SPLCIFICATION LIMIT t t t t j . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , . .
B. 10 DINES 1 ..........................................................
4 I 1. TOTAL 10 DINE-131 1 CI
! 8.43E-04 1 J.37E-02 1 t 2. AVERAGE FELEASE 10C1/SEC1 1.07E-04 8 4.29E-03 1 *
! RATE FOR PERIOD 1 1 1 ! 1 i ........ ............. ................................... '
r
! 3. PER ENT OF TECHN! All 1 1 0 00Ef00 t 0 00Ef00 t <
t t SPL IFICATION LIM T t t t ! !
I C. PARTICULATES 1 1. PAR *!CULATES WITM ! C1 1 1.22E-05 1 3 00E-04 1 !
! WALF-LIVES >t EAYS I ! ! ! I I
I
1 3. PER ENT OF TECHNIC 4Lt % 1 0.00E400 1 0 00Et6a !
, t SPE !FICATION LIMIT I I f 1 i
t 4. GROSS ALPHA ! CI I 2.24E-04 '. 1 43E-03 !
t RA t t t 8 j . . . . . . . .D. 10.A C T !.V ! T Y
... ........................................... i t
D. TRIT!UM
' .......................................................... [
t 1. TOTAL RELEASE I CI ! 3.42E+00 1 0.00E+00 t
, t 2. AVERAGE RELEASE !UC1/ SECT 4 41E-01 1 0.00E+00 t '
t RATE F
, ...........O.R PERI.OD.....
8 1... .......... ................. I I i I 3. PERCENT OF TECHN' Call 1 1 0.00Et00 1 0 00E+00 1
- t SPECIFICATION L!n!T t t t t i
I I
I 5
Attachment 5 (Continued - Page 2 of 2) a Gaseous Effluents .
GASEOUS EFFLUENTS QUARTER 1 1 START DATE 88010101 END DATE 88033124 i QUARTER 2 1 START DATE 88040101 END DATE 88063024 DATE OF REF0k18 AUG. 25, 198k 1 PREFARib BYt CON 11NUQUS Mubt
! NUCLIDES I UNITS I QUARTER 1 QUARTER I I RELEASED t i 1 1 2 1
- 1. FISSION AND ACTIVATION GASES I H3 i C1 2 3.42Et00 t 0.00Et00 t
! AR41 1 CI I 2.24E-02 1 0.00Et00 t
.............................................. i l t KR85M ! CI t 4.44E-01 1
.........................................Et01
! KR87 1 19 1
...........................................0 I KR88 i CI ! 0.00Et00 1 1.57Et0 t
0 00Ef00 t 3.77Et
' ..........................................00 i XE131M C1 1 1 ,
0 00Et00 4 6.96E-0 i ...........................................1 i XE133M I CI t CI t 0.00Et00 t 8
....................................1.39E+C1.4 . . . . . .
t XE133 1 C1
........,.......................... 1 0.00Et00 t 6ss0 .....Et02 ! I
! XE1356 4
...............................0 I
i CI I 0.00Et0 1 1.11Et02 1 i
XE135 t CI i 1.3*.k-01 1 1.92Et
.................02 1
t XE138 t C! i 2.i?E-01 !
3,
....................................2.45Et00 .........
1 J
1 TOTAL FOR t t t t 1
! FERIOD 1 CI t 4.49Et00 t 9 97Et02 1 1 (ABOVE) ! i
..............................................1 I
1
- 2. 10 DINES t 1 C ! 8.43E-04 1 3.
- ...1131.............I ....................37E-02 .......
4 i
I I
8 CI t
. . . .!...! 3 3. . . . . ...........1.3bE-03 1.
1.............79E-02 .......
1 l
i
! 1132 l CI I 0 00Et00 1 4.44
.........................................E-05
! ! 35 t I i
. . . . .!.............I....I t C 0.00Et00 t 4.93E 04 ! ,
i
' t TOTAL FOR I i 1 1 t PERIOD I CI I 2 19E-03 8 5.22E-02 1 l (480VE) i
.............................................1 1 1 1, 1 d
- 3. PARTICULATES
!,' t SR89 t CI i 1 22E-05 4 3.
1 T TA FOR 1
..............................00E-04 .......
1 1 1 1
I P R1 D I CI i 1.22E-05 1 3 00E-04 1 l t (A30VE) t t 4
..............................................t t i
I, I
i 4
Attachment 6 I
Solid Waste i
- l t
?
1 1
I
.I
$ I l
I l
J .
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Attachment 6 (Page 1 of 2)
Solid waste .
Solid. Waste Shipped offsite for Disposal During Period from January 1 to June 30, 1988 WASTE STREAM:
Resins, rilters, & Evap. Bottoms i Waste Cu. Cu. Curies % Error Class reet Meters Shipped (Ci) j A TC 123.0 T 25E+2 + 25%
~
j B 0 0 0 N/A-C 0 0 0 N/A ALL 4345.4 123.0 2.25E+2 + 25%
WASTE STREAM i Dry Active Waste Waste Cu. Cu, Curies % Error
! Class reet Meters Shipped (Ci) d A 0 0 0 N/A I B 0 0 0 N/A j C 0 0 0 N/A ALL 0 0 0 N/A
( WASTE STREAM:
Irradiated Fuel I Waste Cu. Cu. Curies % Error
- , Class reet Meters Shipped (Ci) j A 0 0 0 N/A
- B 0 0 0 N/A 8
C 0 0 0 N/A ALL 0 0 0 N/A
- WASTE STREAM:
Other Waste 1.
I Waste Cu. Cu. Curies % Error l Class reet Meters Shipped (Ci) 1 A 0 0 0 N/A l B 0 0 0 N/A C 0 0 0 N/A ALL 0 0 0 N/A d
l i
i
)
Attachment 5 (Continued - Page 2 of 2)
Solid waste .
Estimates of Major Radionuclides by Waste Type WI,STE TYPE: Resins, Tilters, & Evap. Bottoms Waste Nuclide Percent Class Name Abundance Curies A Cr-S1 45.293 1.02 E+2 Mn-54 22.462 5.05 E+1 Co-58 10.351 2.33 E+1 Co-60 7.965 1.79 E+1 re-55 6.831 1.54 E+1 re-59 1.9C9 4.28 E+0 Pu-241 1.738 3.91 E+0 2n-65 0.786 1.77 E+0 Ag-110m 0.649 1.46 E+0 Ce-244 0.498 1.12 E+0 H-3 0.332 7.47 E-1 Ni-63 0.311 7.00 E-1 Zr-95 0.299 6.73 E-1 Nb-95 0.193 4.35 E-1 Cs-137 0.148 3.32 E-1 Sb-124 0.105 2.!? E-1 Sb-125 0.075 1.69 E-1 Co-57 0.033 7.47 E-2 Ce-141 0.009 2.11 E-2 Cs-134 0.006 1.44 E-2 Ni-59 0.006 1.26 E-2 Sr-90 0.005 1.08 E-2 Tc-99 0.001 1.19 E-3 C-14 0.000 9.80 E-4 Nb-94 0.000 2.60 E-4 1-129 0.000 9.91 E-5 Pu-239/40 0.000 2.80 E-7 Pu-238 0.000 1.31 E-7 i Cm-242 0.000 0.00 E+0 i
Solid Waste Disposal Summary No. of Mode of Shipments Transportation Destination 1
22 Truck Barnwell 0 N/A Richland 0 N/A Beatty 0 N/A Other l
Attachment 7 Meteorological Data T
't
]
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Attachment 7 (Page 1 of 12)
Joint Frequency Distribution Tables - 1988: Quarters 1 & 2 i
HOURS AT EACH WIND SPEED AND DIRECTION PERIO F RECORD
- 88010101-88063024 STA)1 I Y CLAS$1 ALL DT/0Z ELEVA I NI SPEEDISPD10P p! RECT 10NtDIR10P LAFSE1DT30M WIND SPEED (MPH)
DIR!kIf0N 1-3 4-7 8-12 13-1b 19 24 >24 T01AL N 17 66 93 10 0 0 167 ,
4
$$ h6 97 Af 3 0 e
rNE 98 41 0 .14 4i- 65 4 8 n5
) J'
$$E tl48 !!77 l!
54 2{. $
0
- 206ll s 71 132 134 39 5 0 364 ;
lf WSW
$h 28 Nd 74 Nd 136 N
152 k
i 27 0 417 W 19 83 192 175 23 1 493 WNW 21 112 140 37 NW 19 81 93 b' 31$
23*
a NNW 19 77 96 {W
.3 0 215
..OTAL................614 1424 T
..........1534 694 76
.......................*...- ~..
4 4368 PERIODS OF CALM (HOURS) 32
' VARIABLE DLRECTION 0 HOURS OF M;;SSING DATA! 0 ,
i 1 HOURS AT EACH WIND SPEED AND DIRECTION
' PERIOD OF RECORD = 90010101 80063024 STA)!LITY CLASS! A DT/DZ ELEVATION: SPEEDISF D10F DIRECTIONIDlk1OP
........................................ ......LAFSLtDTbOH ..,..............
WIND SFEED(MFH)
DIRfff0N 1-3 47 8-12 13 18 19-24 >24 TOTAL j N 0 6 8 0 0 0 14 '
E ENE h
0 h
2 0
3 2h 3
h 0
h 0
b8 i E O 2 0 0 0 0 2 k
SSE 0
1 0
1 f h h h f 1 0 0 $
S 0 0 3' 1 0 0 3 i IP 8 8 f 3 f 8 i WSW 1 1 0 4 2 0 t i W 0 3 15 19 1 0 38 NU" NNW h I lb 1 h h 12
..................................................0 0 3 3 1 0 7 i .19I S. . . . . . . . . . . . . 2,,,, 33,,,3 3,,, ,33,,,,,3, ,, , ,3,,, 2 33,,,,,
PERIODS OF CALM (HOURS)1 0 VARIABLE DLRECTION 0
- HOURS OF M;;S$1NG DATAt 0 1
J f
i 0
- . - - - _ . - - , .- - ,~ ~-. _ , - _ - - . . . - -
- +
j Attachment 7 (continued - Page 2 of 12)
Joint Frequency Distribution Tables - 1988: Ch2arters 1 & 2 l
HOURS AT EACH WIND SPEED AND DIRECT!0N F F RECORD = 8601110' 08063024 f
I YNtCLASS;PJ ,Dtt5PD10l'iT/ \U RLCT!0NtD
..................'......................I.R10P E I S LAPSEIDT50M WIMD 6FEEDtMPH)
DIR!bYf0N 1-3 4-7 6-12 13-10 19-24 >24 TOTAL N 1 7 0 0 0 0 16 NNE O 9 13 0 0 0 i
NE O 10 15 1 0 0 3'26
[NE O O 5 0 0 9 5 E O 1 1 0 0 0 2
, kh $ $ $ $ $ $ h j $$E o 0 0 2 0 0 2 i i S 0 2 5 2 1 0 10
) $$W 0 3 3 0 g 0 6 SW 1 0 1 1 . 0 5 4
- WSW 1 3 11 0 t W 0 $ 33 17 6' 0 6' 5 WNW 0 14 'O 0 0 6 MW i 4 l.4 I' O O k
NNW D 9 40 3 0 0 ..
i PERIODS OF CALM (H0VRS)1 0 VARIABLE DIRECTION 0 HOURS OF MISSING DATAI 0 1
i HOURS A1 EACH WIND SFEED AND t!RECTION i
) PIRIOD OF RECORD d 86010101-80063024 !
t I'TAPlIITYCLAS$1. I ET/ !?...?"!.... 5!!!!!.!!!!...hiI..!!!!!!"!!!!!?!..'*!: '
W!HD SPEED (MPH)
DIR!bfION 1-3 4-7 6-12 13-10 19-24 >24 101AL .
......... ... ... .... ..... ..... ... ..... t j N 1 9 5 0 1 0 16 NE
[NE d
0 if 3 ff 2 k
0 h
0 h
0 hk 5
l L 0 4 2 0 0 0 6 i
l h h h k h $
j Sit S
b 0 3
f.
6 3 o 0
0 5 -
1 7 0 17 l fB" WSW 8
1 1
3
'l5 13 1 t 2
8 0
14 W
1 6 29 13 2 0 $'41 i
NNW f ff is 1 8 8 18 1
.......................................................17 0 11 5 1 0 0
..OTAL......................106....128 .....................306 T 7 57 8 0 PERIODS OF CALMtHOURS)1 0 VARIABLE DIRECTION 0 HOURS OF MISSING Daft.1 0 i
l C-]
Attachment 7 (Continued - Page 3 of 12)
Joint Frequency Distribution Tables - 1988 Quarters 1&2 HOURS AT EACH WIND SPEED AND DIRECTION
3024 11!!!"kf0Nt9?
ELEVA SPEED! EEllii f"D10P'23191fCTIONIDIR10F P u RE LAPSEID150M WIND SPEED (MPH)
DIEffff0N 1-3 4-7 8-12 13-18 1Y-24
>24 T01AL N 11 33 65 9 0 0 118 NNE 7 37 29 1 0 0 74 NE 13 53 43 9 0 0 118 ENE 8 39 43 5 0 0 95 E 11 28 1 0 0 0 40 kf 55t' f3 f 20 if22 k 8
k 0
h 0
kf 56 5 3 38 31 17 2 0 111 SSd 49 79 47 7 3 187 SW $' 32 80 46 0 0 162 WSW 6 38 10 109 21 0 ;76 W 11 $0 10f' 123 19 411 WNW l 8 81 9 18' NW i f' $"0 53 3'9 6' 145 NNW 11 36 49 17 0 0 133
. .T.O.T.. A L. . . . . . . . . . . .12 3. ...
54
. 5 8 3. . . .8 31 ..........................
.454 4 2072 PERIODS OF CALM (HOURS)! 2 VARIAFLE DIRECTION 0 HOURS Of HISSING DATA! O HOURS Al EACH WIND SPEED AND D1kLCTION FERY D OF RECORD 6 88010101-08063024 (TA) (TTY CLAS$1 E D1/DZ ELEV .1041 SPEEDtSPD10P DIRECT 10NtDIR10P LAPSEIDT50M WIND SFEED(MPH)
DIR ION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 2 10 7 0 0 0 19 NNE J 13 5 0 0 0 '1 NE 9 13 4 0 0 0 36 ENE 11 42 8 0 0 0 61 E 20 17 2 0 0 0 39 ESE 17 11 4 1 0 0 33 SE 7 20 1 0 0 49
$$E 8 28 3't8 8 0 0 7 S 8 54 66 12 2 0 143' SSW 13 79 54 30 O 181 SW 6 52 29 8 6' 0 95 WSW 8 25 26 15 0 0 74 W 6 18 8 3 1 0 36 W f f h h fh NNW 3 17 8 1 0 0 31
..............................273 TOTAL 138 422 80 5 0 921 PERIODS OF CALM (HOURS)1 5 VARIABLE DIRECTION 0 HOUR ,
5 0F MISSING DATA 1 0
Attachment 7 (Continued - Page 4 of 12)
- Joint Frequency Distribution Tables - 1988
- GNarters 1 & 2 i HOURS AT EACH WIND SPEED AND D!kECTION 4
PERI F RECOR3< 8601 10 88063024 l STA> ! Y CLASS F 1/
4 ELEV I Nt 3PEEDtSFD10 RECT!0NtDIR10P LAPSEtDT50M W!HD SPEED (MFH)
DIRkfff0N 1-3 4-7 8-12 13-19 19-24 >24 T01AL N 2 1 0 0 0 0 4 NE h h h h
! ENE 9 7 0 0 0 0 16 j E 22 8 0 0 0 0 30 kh SSE if10 2h 14 h
0 h
0 h
0 h
0 k!
24 S 12 21 4 0 0 0 38 kh f k h h h h fh 4 WSW 5 5 0 0 0 0 19 W 0 0 0 0 0 0 0 WNW 0 ' 0 0 0 3 1
NW 1 [ 0 0 0 0 3 NNW 2 1 1 0 0 0 4 260
..................106..........................................
TOTAL 144 6 0 0 0 ,
PERIODS OF CALM (HOURS)! 5 3
i VARIABLE DIRECTION 0 HOURS OF MIS $1NG DAT At 0 ,
HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD m 86010101-88063024 STAtlLITY CLAS$1 0 DT/DZ ELEVATIONI SFEEDtSPD10F DIRECT!0NtDIR10F LAPSEtDT50M
, WIND SPEED (MFH)
DIR ff0N 1-3 4-7 B-12 13-18 19-24
>24 T01AL
! N 0 0 0 0 0 0 0 [
NE k h h h h h h l l ENE 17 5 0 0 0 0 24 l 1 E 30 5 0 0 0 0 36 ;
KSE 39 6 0 0 0 0 46 :
1E 41 11 0 0 0 0 56 ;
USE 24 14 0 0 0 0 42 i G 47 14 0 0 0 0 6) <
NW h f h h h h WSW 6 0 0 0 0 0 6 W 1 1 0 0 0 0 2 W 0 h h h h f 1 NNW 1 0 0 0 0 0 1
......L............232....47......1.....1.....0.....0....17 TOTA 3 PERIODS OF CALM (HOURS)1 20 VARIABLE DIRECTION 0 HOURS OF MIS $1NG DATA! 0
}
i Attachment 7 (Continued - Page 5 of 12)
Joint Frequency Distribution Tables - 1988 Quarter 1 HOURS A1 EACH WIND SPEED AND DlkECT10N PERI 0F RECORD = 8801010 88033124 STAB ITY CLASSt ALL DT/ Z ELEV 10Nt SPEEDISFD10F IRECTIONtDIR10F LAPSEtDT50M WIND SPEED (HPH) l DIR ION 1-3 47 8-12 13 18 lb 24
>24 TOTAL N to 28 36 3 0 0 77 ll ENE 20 h N45 N
20 f
2 h
0 h
0 N
85 i E 23 3l 2 v 0 0 41 i llE SSE jf 20 29 li 36 20 i I 0 8 0
$3 105
$ 29 73 97 33 4 0 36 il" 22 5 !! 24 8 'f 23 3 {tU 252 WSW 5 27 83 114 0 W 11 25 95 132 23 1 287
! h 3f h 32 fe h 0 0 44 NNW 6 22 4
.............................................................. 1 2
TOTAL 207 594 852 458 67 4 2184 l FERIODS OF CALM (HOURS)! 6 VARIABLE DIRECTION 0 HOURS OF MISSING DATAt 0 HOURS AT EACH WIND SPEED AND DIRECTION FERIOD OF RECORD = 88010101-88033124 STAlllliY CLASS: A DT/DZ ' [LEVATION! SPEEDtSPli10P li! RECT 10NtDIR10F L AF SE ID150M WIN 11 SPEEli(MFH) i 4 DIRf $ ION 13 47 8 12 13-18 19 24
>24 101AL I
N 0 2 1 0 0 0 3 h f h f h h N ENE o 1 1 1 0 0 3
) E O O
[ 0 2 0 0 { E g g g [LE 5 0 1 0 b 1 1 1 0 0 4 2 I h 0 f h h h I
- WSW 0 0 0 3 0 0 3
. W 0 3 4 4 1 0 14 h k f h h h i NNW 0 1 0 0 0 0 1 I
....................0....16.....2....13.....1.....0....72.....
TOTAL 4 i PERIODS OF CALM (HOURS)t 0
- VAR!ABLE DIRECTION 0 HOURS OF MISSING DA)At 0 1
Attachment 7 (Continued - Page 6 of 12) Joint Frequency Distribution Tables - 1988: Chiarter 1 HOURS AT EACH WIND SPEED AND DIRECT!(IN P F RECORD = 8801 10 88033124 S I Y CLASSt 3 T/ E I NI SPEEDlSPD10 RECTIONIDIR10P LAPSE!DT50M WIND SPEED (MPH) DIRffff0N 1-3 4-7 8-12 13-18 19-24
>24 ThiAL N 1 2 1 0 0 0 4 ENE E h O
f 0 k 3 h 0 h 0 h 0 3 E O 1 0 0 0 0 1 h$ $ b h $ $ $ b SSE O O O 2 0 9 2 S 0 1 4 0 0 0 5
$ h f h h WSW 0 1 2 4 0 8 W 0 2 10 7 0 19 WNW 0 11 0 13 NW NNW 1
0 (' 4 0 0 1 6 3 TOTAL 3 17 48 15 1 0 84 PERIODS OF CALM (HOURS)1 0 VARIABLE DIRrCTION 0 HOURS OF MIS $1NG DATAt 0 HOURE AT EACH WIND SFLED AND b!kEC110N PERIOD OF RECORD = 88010101-88033124 kLEhAk0H1 SPEEDtkPD10h'bkRECT!0NtDIR10P LAPSEtDT50h WIND SPEED (MPH) DIRffION 1-3 4-7 8-12 13-18 19-24 >24 T01AL l N 0 4 2 0 0 0 6 . NE O h h h h h h ENE 0 2 0 0 0 0 2 l E 0 2 1 0 0 0 3 L hf h h f h h h f SSE 0 0 0 0 3 :
$ 0 4 L0 i WSW { }1 l1 7 Ls 1
l W 0 1 9 10 3 0 2.{ Ud" NNW 8 0 i 1 { 2 f 1 8 0 h 0
}}
4 .........................33.....53....37 TOTAL 0
.. ....8 ....0...131.....
PERIODS OF CALM (NOURS)! 0 VARIABLE DIRECTION 0 H0JRS OF MISSING DATAt 0 ; i l WJ
Attachment 7 (Continued - Page 7 of 12) Joint Frequency Distribution Tables - 1988 Quarter 1 HOURS Al LACH WIND SPEED AND DIRECT!DN P F RECOR')4 0001 10 08033124 5 I Y CLAll D T/ E i i Nt llPEEDt3PD10 RECTIONIDIR10P LAPSE!DT50M WIND SPEED (MPH) D!Rff'ON 1-3 47 8-12 13-18 19-24
>24 101AL N 7 20 3 3 0 0 2 NE ENE f5 ff 18 h
15 h 1 h 0 h 0 4h 39 E 4 21 1 0 0 0 24 kk k 13 k k h kh
$5E 1 17 15 8 0 0 41 5 0 32 42 lb 2 0 91 WSW i
3 lt 19 tl48 11 et 8 20 8 0 Wt 198 W 5 15 48 107 19 1 2. 5 NNW h 4 ff 16 h0 f5 2 h 0 h 0 b2 TOTAL 51 305 5b2 332 52 4 1296 PER 1 "OgSOFCAM(NOURS)t b5NkkSk DATA 1 0 HOURS AT LACH WIND SPEED AND DIRECTION PERI 0F RECORD a W8010101-It033124 STAB ITY CLASS' E Dt/DZ ELEV 10Nt $PCEDtSF010P DIRECTION:DIR10P LAPSE!DT50M WIND SPEED (MPH) DIRiffk'ON 1-3 4-7 O-12 13-18 19-24 >24 TDIAL N 1 0 0 0 0 0 1 NE f h h h h k ENE 5 14 1 0 0 0 20 E 5 4 0 0 0 0 9 lit I !! 11 f h 8 H 15' l 33 kl 5 t ! 8 L WSW
#4 #12 1 8
0 h 0
'li!
30 W 4 4 16 WNW 3 1 7 NW 4 0 4 NNW 2 0 0 4 T
..O.TAL.............60...155....157
. .. .....0.....5.....0....38 4 4 PERIODS OF CALM (HOURS)1 3 VARIABLE DIRECTION 0 HOURS Of.BISSING DATA 1 0
i Attachment 7 (Continued - Page 8 of 12) Joint Frequency Distribution Tables - 1988: Quarter 1 i HOURS AT EACH WIND SPEED AND DIRECTION PERI 0F REC De 8801 88033124 TAD TY CLA t F ILEV UNt SPEED!$PD10 RECTIONIDIR10F LAPSEtDT50M WIND SPEED (MPH) DlRfff0N 1-3 4-7 8-12 13-18 19-24
>24 TOTAL l
J N 1 0 0 0 0 0 , E $ $ $ $ $ $ 1:NE 1 4 0 0 0 0 5 9 4 13 E 4 4 11 0 0 3' 1E 4 0 0 L3 , S 9 5 0 0 0 0 14 kh f f h h h h $ WSW 0 0 0 0 0 W 0 6' 0 0 0 0 5 4 NU" NNW 8 i 8 0 h 8 8 1 i 0 0 0 0 0 0 i T O.T .. A L. . . . . . . . . . . .. . 4 3. . . . 5 0 ...........0.....0.....0....95..... 0 .: PERIODS OF CALM (HOURS) 0 I VARIABLE DIRECTION 0 j HOURS OF MIS $1NG DATA! 0 i ' HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD e 88010101-88033124 1 kLEhkkbNt hFEEDtkFD10h'hRECTION!DIR10P LAPSElDT50k WlHD $ PEED (MPH) DIRfff0N 1-3 4-7 8-12 13-18 19-24 >24 TOTAL , j N 0 0 0 0 0 0 0 UE' ENE
?
9 I 3 h 0 i 0 h h ! \ i E 5 0 0 1)
- 3 0 0 0 0 s I
$ k
$$E 10 5 f h h h h 2
1 0 0 0 0 11 S 12 4 0 0 0 0 16 kW WSW f h h h h h k 0 0 0 0 0 0 ! W 1 0 0 0 g '
!N h h h 0 h NNW 0 0 0 0 0 i l' TOTA i
. . . . . .L . . . . . . . . . . . . . 4 8.....18.....0.....1.....0.....0....48 ..... l PER S OF CALM (HOURS)! 2 l VAR LE DIRECTION 0 HOURS OF M1551NG DATAt 0 1
l i
Attachment 7 (Continw d - Page 9 of 12) Joint Frequency Distribution Tables - 1988: Quarter 2 l HOURS AT EACH WIND SPEED AND D1kECTION PERIOD OF RECORD d 88040101-88063024 kNNkkNt F EED tbi10 RECTIONIDIR10P iAPSEtDT50M t WIND SPEED (MFH) I D!Rbf0N 1-3 4-7 8-12 13-18 1Y-24
>24 101AL i
J1 , J N 7 38 57 7 9 0 0 10 NNE l' S 48 10 I l NE 8 71 3$ 15 ENE b5 6 41 6 129 i' E 60 29 4 0 0 0 94 k
$$E 4
28 48 1 h h h N
' 18 2 0 9 101 S 42 59 37 6 1 0 146 i
WSW fi23 i? 47 th 53 il 38 1 4 8 0 li: 165 i l W 8 58 97 43 V 0 206
- I N N 5h N ff h h fl$ '
...................13..........................................
NNW 55 64 19 0 0 151 t TOTAL 407 830 682 236 9 0 2184 PERIODS OF CA M(HOURS)1 26 VARIA>LE D RE T!ON 0 . < HOURS OF MSSS NO DATAt 0 l-J l l
- HOURS AT EACH WIND SPEED AND DIRECTION M/ )
kLEVAh!ONtN SF EEDISF A bh ' D10P D RECTIONID!R10P LAPSEID1bOM , i WIND SFEED(MPH) ' N
~
0
. ' . . '.~. .$ k!'. . . .'.~.$ . .$......
4 7 0 0 0 11 NNE NE 0 0 4 4 y
- 4. 21 1 0 0 0 0 2 LI' i ENE 0 '
1 . 2 0 0 $ E O 1 0 0 0 0 1 kk h h h h h h h l SSE 1 0 0 0 0 0 1 l ) S 0 0 1 0 0 0 1 l l
!!" 8 8 8 h f 8 I !' WSW 1 1 0 1 0 5 W 0 0 11 13 6' 0 24 ,
NNW h 0 ! h 1 l l f!. ! I l T
..O.TAL
. ..................................................166 2 1W 95 48 3 0 PERIODS OF CALN(HOURS)! 0 !
VARIABLE DIRECT!ON 0 ' HOURS OF MISSING DATA 1 0 ),
( Attachment 7 (Continued - Page 10 of 12) Joint Frequency Distribution Tables - 1988 Quarter 2 ' HOURS AT EACH WIND SPEED AN!J D!kECTION
, PERIOD OF RECORD = 88040101-88063024
!LEh!Nt kPEEDi$PD10b!RECTIONtDIR10P LAPSE!DT50M V!ND SPEED (MPH) -
DIR N0H 1-3 4-7 8-12 13-18 19-24 >24 T01AL N 0 5 7 0 0 0 12
!E l
- NE h
O if O if 2 f0 h 0 h 0 2 1: 0 0 1 0 0 Q ! 1:SE 0 1 1 0 0 0 2 SE 0 0 2 0 0 2 g i l b 1SW h 0 f f* h 0 k 4 I HW 0 $ $; . 2 l W5W 1 1 1 11 , W 0 3 23 10 0 0 36 '
! 0 1 h h h f!
NNW 0 , 10 2 0 0 19
. .T O.T A L . . . . . . . . . . . . .1. .. . . 51. . . . 8 8.....26
. ... .................0.....
4 0 17 r PERIODS OF CALM (HOURS)! O VARIA6LE DIRECTION 0 ! I HOURS OF MISSIMO DAik 0 i i l HOURS AT EACH WIND SPEED AN11 DIRLCTION - u P LEV i ONt (( sFEEDikPD10P8804g-88063024 D RECT!0NtDIP.10P LAPSEIDT50m
- l ................................................................
i 1 WIND SPEED (MPH) ) D!R NON 1-3 4-7 8-12 13-18 19-24 >24 101AL l 1 N 1 5 3 1 0 0 3 l NNE 1 10 8 b 0 0 ,9 l I NE O 9 5 4 0 0 ,8 i
! E ENE O
O j 2 1 0 6 0 0 0 0 3 3 SSE f0 h h h f
, 0 2 0 0 0 S 1 2 2 2 0 0 I' !
l U" 8 $ $ 8 h 8 I ; WSW 1 2 4 4 0 0 13 W 1 5 20 3 0 0 29
- WNW 0 17 Q 24 .
1 MW 1 5 : 0 17 NNW 0 to u 0 13 i 1 .............................................................. j
......L..............7 ...........5.....................175 TOTA 73 7 20 0 0 i
PER10DS OF CALM (HOURS)! O i 0 VAR:48 HOU(:S g g E g 0NDATA
- O )
l i
Attachment 7 (Continued - Page 11 of 12)
- Joint Frequency Distribution Tables - 1988
- Quarter 2 HOURS A1 EACH WIND SPEED AND b!RIC110N PERIAD OF RECORD = 88040101-80063024 ,
ST ABI'!TY CLAS$1 D UT/DZ l ELEVAl!ON! $PEEDilPD10P DIRECT 10NIDIR10P LAPSEtDT50M WIND SPEED (MFH) DIRfff!'ON 13 4-7 8-12 13-18 19-24 >24 101AL N 4 13 33 6 0 0 56 NE $5 f8 h 8 8 N f Et;E 3 21 28 4 0 0 56 E 7 7 0 0 0 0 14 kh 8 8 k 8 8 h 1 d 155
$$W i 13
! ?
0 i 4 8 1 8 18
- SW I' l 1 1 i 0 I WSW 3 : 9 4 {al B W e : 5 9 6 9e i WNJ 10 P 3 4 $9 II' 4
NW 8 b$ L4 /6
< NNW 7 20 39 15 81 1 ..............................................................
776 T
..O.TAL
. ... ............74....27B....299....122.....2.....0 ...........
!' PERIODS OF CALM (HOURS)1 1 VARIABLE DIRECTION 0
, HOURS OF MIS $1NG DATAt 0 ! I I HOURS AT EACH WIND 5 FLED AND DIRECTION , P 0 F REC k ]-
' 8 1yYCLAg$pa E 88040g D 88063024 ,
E h ION! kPEEDt5PD10F RECTIONIDIR10P LM 4EtDT50h WIND SPEED (MFH) I DIRffkON 1-3 4-7 8-12 13 18 19-24 >24 TD1AL
........;..... ..; ...g lE5 i 'l ! 8 8 8 38
. 1"5 it f? I 8 8 8 il i 1F
$$t
!6 24 l i9 8* 8 0
8 0 11 41
$ 0 24 20 $ 0 6 44 I
f? W5W tA 11 21
'l 14 i 3 8
0 8 0 tl44 , W 1 14 4 1 0 0 20 N NNW h 3 15 h f 8 8 kb ' { 8 1 0 0 27 ! l TOTA
) . . . . . .L . . . . . . . . . . . . . 7 8. . . 2 4 7. ...118......20.....0.....0...483.....
3 PERIODS OF CALM (HOURS)t 2 VARIABLE DIRECTION 0 ): HOURS OF M15$1NG DATAt 0
i i l l l ( Attachment 7 (Continued - Page 12 of 12) Joint Frequency Distribution Tables - 1988: Quarter 2 i HOURS AT EACH W1dit SPEED AND DIRECTION l PERIOD OF RECORD a 98040101-88063024 STABILITY CLASSI F DT/DZ ELEVATION: SPEED!SPD10P DIRECTIONtDIR10P LAPSEtDT50M WIND 3 PEED (MPH) WIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N 1 1 0 0 0 0 3 E h f h 0 h 0 h ENE 8 3 0 0 0 0 !!
E 13 4 0 0 0 0 17 h SSE h 3 if8 h 0 h 0 h 0 h 0 ik 11 S 3 16 4 0 0 0 24 SSW 6 38 0 0 0 0 40 SW 6 7 0 0 0 0 14 WSW 5 3 0 0 0 0 0 W 0 0 0 0 0 0 0 WNW 0 1 1 0 0 0 2 NW 1 0 0 0 0 0 2 NNW 2 1 1 0 0 0 4 TOTAL 61 94 6 0 0 0 165 PERIODS OF CALH(HOURS): 5 VARIABLE DIRECTION O HOURS 0F MISSING DATAt 0 HOURS AT EACH WIND SPEiD AND DIRECTION PERIOD OF RECORD a 8C040101-88063024 STABILITY CLASS 1 0 DT/DZ ELEVATION: SPEED!SPD10P DIRECTIONIDIR10P LAPSEtDT50M WIND SPEED (MPH) DIRkb ON 1-3 4-7 B-12 13-18 19-24 >24 T01AL H 0 0 0 0 0 0 0 NN d f 0 h h h 6 ENE 8 2 0 0 0 0 11 E 25 2 0 0 0 0 2B SSE
}h h h h h h !B 14 13 0 0 0 0 31 S 35 to V 0 0 0 47 SSW 15 8 0 0 0 0 23 SW 4 1 0 0 0 0 5 WSW 6 0 0 0 0 0 6 W 0 1 0 0 0 0 1
$W ? $ b $ h h $
NHW 1 0 0 0 0 0 1 TOTAL 184 49 1 0 0 0 249 PERIODS OF CALM (HOURS)! 18 VARIABLE DIRECTION 0 HOURS OF.MISSINO.DATAl. 0
Attachment 8 Offsite Dose Calculation Manual (ODCM) Changes
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OH12D: ODCH Page : i Rev. : 3 THE CLEVELAND ELECTRIC ILLUMINATING COMPANY PERRY NUCLEAR POVER PLANT OPERATIONS MANUAL TITLE: OFFSITE DOSE CALCULATION MANUAL REVISION: 3 EFFECTIVE DATE:
)w - M- SQ 21- bC3 #W/F8 DATE P R R E PREPARER: Richard M. Cochnar z 1-25-88
- asvisvra
- wwWr' Aw k PORC MEETING NO. g.gg g/is/6%
I V ********************************************************************* N A NOTE: Complete this block only if in-plant validation is desired L ****************************** P I L D APPROVAL FOR - A A VALIDATION: [ T I VALIDATION 0 COMPLETE: N VALIDATION TC'S BY: INCORPORATED: A , / P APPROVEC. F9 R S m n "N, N bAb o.cu.e u.,n.a i AA W p.g , Mas mem :
\
OM12D: ODCH Page : 11 Rev. : 3 Table of Contents Section Title Page
1.0 INTRODUCTION
1 2.0 LIQUID EFFLUENTS 2 2.1 Batch Releases 2 2.1.1 Monitor Alava Setpoint Determination 2 2.1.1.1 Determinati:,n of the Minimum Acceptable 3 Dilution Faxtor 2.1.1.2 Determina'. ion of the Maximum Allovable Radvaste 3 Tank D'.scharge Flow Rate 2.1.1.3 Liquid fadvaste Discharge Flov Monitor Alsrm 4 Setpo nt 2.1.1.4 Liquid Radvaste Discharge Radiation M3nitor 5 Ala'.m/ Trip Setpoint 2.1.2 Comp *iance with 10CFR20 - Liquid Effluent 6 Concentration 2.1.2.1 Pratelease 6 2.1.2.2 Post Release 7 2.2 Continuous Releases 8 2.3 Compliance with 10CFR50 Appendix I - Liquid 11 Effluent Dose 2.3.1 Dose Calculations 11 2.3.2 Cummulation of Doses 13 2.3.3 Projection of Doses 13 2.3.4 Population Dose 14 3.0 GASEOUS EFFLUENTS 29 3.1 Monitor Alarm Setpoint Determination 31 3.1.1 Determination of the "Mix" (Noble Gas Radio- 32 nuclide Composition) of the Gaseous Effluent 3.1.2 Determination of the Maximum Acceptable Total 32 Activity Release Rtte of Noble Gas Radio-nuclides in Gaseous Effluent Bascd on Total Body Dose Rate Limit) l 3.1.3 Determination of the Maximum Acceptable Total 33 Activity Release Rate of Noble Gas Radio-nuclides in Gaseous Effluent Based on Skin Dose Rate Limit) 3.1.4 Determination of the Maximum Acceptable Total 34 Radioactivity Concentration of all Noble Gas Radionuclides in Gaseous Effluent 3.1.5 Determination of the Maximum Acceptable Monitor 34 i Count Rate Above Background Attributed to l Noble Gas Radionuclides l 3.1.5.1 Determination of the Monitor High Alarm Setpoint 35 3.1.5.2 Determination of the Monitor Alert Setpoint 35 l
OM12D: ODCM Page : 111 Rev. : 3 Table of Contents Section Title Page 3.2 Compliance with 10CFR20 - Gaseous Effluent Dose 38 Rate 3.2.1 Noble Cases 38 3.2.2 Radionuclides, Particulates, and Other 38 Radionuclides 3.2.3 Dose Rate Calculatio..is 39 3.3 Compliance with 10CFR50 Appendix I - Gaseous 67 Effluent Dose 3.3.1 Noble Gases 67 3.3.2 Radionuclides, Particulates, and Other 68 Radionuclides 3.3.3 Dose calculations 68 3.3.4 Cumulation of Doses 69 3.3.5 Projection of Doses 70 3.4 Population Duse 70 < 4.0 TOTAL DOSE 72 4.1 Compliance with 40CFR190 - Uranium Fuel Cycle 72 Dose 4.2 Direct Radiation Dose From PNPP 74 4.3 Dose to Members of the Public While On-Site 75 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 76 5.1 Monitoring Program 76 5.2 Land Use Census Program 77 5.3 Inter Laboratory Comparison Program 78 APPENDIX A Atmospheric Dispersion and Deposition Parameters 92 APPENDIX B Lover Limit of Detection 108 REFERENCES 112 l l
OM12D ODCM Page : iv Rev. : 3 List of Tables Table' Title Page 2.3-1 Organs Used for Liquid Effluent Dose Calculations 15 2.3-2 Age Groups Used for Liquid Effluent Dose Calculations 15 2.3-3 Liquid Effluent Dose Pathways 15 2.3-4 Bioaccumulation Factors 16 2.3-5 Ingestion Dose Factors for Adult 17 2.3-6 Ingestion Dose Factors for Teenager 19 2.3-7 Ingestion Dose Factors for Child 21 2.3-0 Ingestion Dose Factors for Infant 23 2.3-9 External Dose Factors for Standing on Contaminated 25 , Ground 2.3-10 Liquid Effluent Dilution Factors (H p) 27 2.3-11 Transit Times Required for Nuclides to Reach the 27 Point of Exposure 2.3-12 Usage Factors (U,p) 28 3.1-1 Total Body and Skin Dose Factors 37 L 3.2-1 Organs Used for Gassous Effluent Dose Calculations 44 3.2-2 Age Groups Used for Gaseous Effluent Dose Calculations 44 3.2-3 Gaseous Effluent Dose Pathvays 45 3.2-4 Dose Factors for Exposure to a Semi-Inifinite Cloud 46 of Noble Cases l 3.2-5 External Dose Factors for Standing on contaminated 47 i Ground 3.2-6 Inhalation Dose Factors for Adult 49 3.2-7 Inhalation Dose Factors for Teenager 51 l 3.2-8 Inhalation Dose Factors for Child 53 a
OM12D: ODCM Page : v l I Rev. : 3 List of Tables (Cont.1 Table Title M 3.2-9 Inhalation Dose Factors for Infant 55 3.2-10 Ingestion Dose Factors for Adult 57 3.2-11 Ingestion Dose Factors for Teenager 59 3.2-12 Ingestion Dose Factors for Child 61 3.2-13 Ingestion Dose Factors for Infant 63 3.2-14 Annual Usage Factors for the Maximum Exposed 65 Individual 3.2-15 Annual Usage Factors for the Average Individual 65 3.3-1 Gamma and Bet Air Dose Factors for Semi-Infinite 71 Plume 5.1-1 PNPP P.adiological Environmental Monitoring Program 79 5.1-2 Reporting Levels for Radioactivity Concentrations 82 in Environmental Samples 5.1-3 Detection Capabilities for Environmental Sample 83 Analysis and Lover Limit of Detection (LLD) 5.1-4 Sample Locations and Media for the Radiological 85 F.nvironmental Monitoring Program A-1 Atmospheric Depletion and Deposition Factors 95 A-2 Site Boundary Atmospheric Dispersion and Deposition 97 Parameters for PNPP Unit 1 A-3 Atmospheric Dispersion (X/0) as a Function of 98 Distance A-4 Atmospheric Deposition (D/0) as a Function of 103 Distance
OM12Di ODCM Page vi Rev. : 3 List of Pigures Table Title Pag ; 2.1-1 Liquid Radioactive Vaste (LRV) Discharge System 10 4 3.0-1 Gaseous Effluent System Flow Diagram 30 3.2-1 PNPP Site Boundary and Unrestricted Area 44 5.1-1 Radiological Environmental Monitoring Program 89 Sampling Locations Approximately 2 Miles from Site 5.1-2 Radiological Environmental Monitoring Program 90 Sampling Locations Approximately 8 Miles from Site 5.1-3 Radiological Environmental Monitoring Program 91 Sampling Locations Control Locations Greater than 10 Miles from Site i i l l 1 i
1 I OH12D: ODCH Page : vii Rev. : 3 10CFR50.59 Applicability Check Yes No Is there a change to the plant as described in the FSAR7 Reason:-71u a u eLu, w /d eL/ rd/ e[dd -/d hdh l l eisafL whsuchVe m km ~ai d wri4>J . 41 4x' i l Is there a change to a procedure / instruction as described in the FSAR7 Reasons -71, Odds, L ,,,/ o ,.ur.ut,\ w sr.$ce/vr
- dd q I g' p t edb,>., tfa n EJ 7,o & 6 efe46 eMan24a. Pfld w tral.h asl J ([s/ tad f, %ftedel.kdescribed in the FSAR7 Is/0IIr.eu eat t or ex driment no l l g*
Reason $ n nf s hat er wiu,ded nd Sehe d.n is. / i hu . dre a dkJ m A M v -rei h d e a k n.r. Is there a ciange to the Technical Specifications? I IW Is there an effect on the environment or change to the Environmental Protection Plan? Reason: W ,<, a u .d<,<x I II< pfled o. Re k.hu n e le a J: /l* TH
/
Ansvers to all q astions are "No", no potential for an Unteviewed I Safety or Environme.?tal Question exists, no further reviev required. p Ansvers to ont or more questions is "Yes", further review reyuired. Safety Evaluation Number Environmental Evaluation Number Prepared /Date evieved/Date Appr wA a -N/ o 2h/n' 55cobved/Datez al
/'
SCOPE OF REVISION: Rev. 3 - 1. TC's from previous revision that were evaluated for incorporation - TCN-002 through TCN-008.
- 2. Deletion of Atmospheric dispersion and deposition parameters for nearest residence with animal and garden locations as this information is subject to change and is available in the Annual Environmental Operating Report.
- 3. Radiological Environmental Sampling Program changest precipitation sampling added to locations 3 and 41 precipitation sampling deleted from locations 1, 44, and 48 revision TLD station 8 location.
- 4. Rewritten to include editorial changes, often too insignificant and too profuse to varrant demarcation.
%t. t 3::Ahc:N*oD W h e Ac.oR8h W %c MW D verse
OH12D: ODCM Page : 1 Rev. : 3
1.0 INTRODUCTION
This Offsite Pose Calculation Manual (ODCM) contains information and methodologies to be used by the Perry Nuclear Power Plant (PNPP), Unit 1, to ensure compliance with PNPP Radiological Effluent Technical Specifications. The Technical Specifications are written to satisfy 10CFR20, 10CFR50.36 and Appendix I, and 40CFR190 requirements. Sections 2 and 3 of this manual deal with liquid and gaseous radiological effluents, respectively. Each of these sections contain alarm setpoint determinatio.a, radiation dose and dose rate calculation methodologies, as well as limits and requirements. Section 4 covers uranium fuel cycle related radiation dose limits including direct dose. Also included in this manual, in Section 5, is information relating to the Radiological Environmental Monitoring Program (REMP). The figures ano tables contained therein designate specific sample types and locations currently used to satisfy the Technical Specification requirements for the REMP as well as sampling reporting and detection capability limits. The sample types and locations are subject to change based on factors including the results of the annual Land Use Census. TheODCMhasbeenprepared,asgenerallykspossible,inorderto minimize future revisions. However, any such changes vill be reviewed and approved as per the Administrative Control Section of the PNPP Technical Specifications. Supplemental information needed to support calculations, both in this document and in the accompanying Radiological Effluent Technical Specifications is contained in the appendices at the end of this manual. Appendix A contains atmospheric dispersion and deposition parameters and Appendix B presents the methodology for determining the lover limit of detection (LLD). i
OM12D: ODCM Page : 2 Rev. 3 2.0 LIQUID EFFLUEIUS 2.1 Batch Releases A batch release is the discharge liquid radioactive vaste of a discrete volume. Batch releases from the liquid radvaste system may occur from any of the following tanks: vaste sample tank, floor drain sample tank, chemical vaste distillate tank, and detergent drain tank. (See Figure 2.1-1). The maximum release rate possible, due to pump capacity, is 200 gallons per minute from all telease taris except the detergent drain tanks, which have a maximum release rate of 50 gallons per minute. All of the above liquid radvaste releases go to the Emergency Service Vater discharge which is then released through the discharge tunnel after mixing with Service Water effluent, and blevdovn from circulating Vatar system if present. The type and frequency of sampling and analysis required by the PNPP Technical Specifications is given in T.S. Table 4.11.1.1.1-1. Prior to sampling for analysis, each batch should be isolated, and c thoroughly mixed to assure representative sampling. For mixing, the contents of the tank are recirt.ulated by isolating the tank and turning on equipment that takes suction from and discharges back into the tank. Recycle lines are provided with one or more mixing . eductors located near the bottom of the tanks to promote better ' mixing as well as reducing recirculation time. This ensures that the water in the tank vill be mixed and vill be representative of the activity in the tank. The minimum recirculation performed is the equivalent of two volumes of the tank contents. Monitor alarm setpoints vill be determined in order to ensure compliance with 10CFR20. The radioactive content of each batch release vill be determired prior to release in accordance with Table 4.11.1.1.1-1 of the PNPP Technical Specifications. Concentrations for tritium and other non-gamma emitting isotopes vill be those most recently determined (previous month / quarter). 2.1.1 Monitor Alarm Setpoint Determination The following methudology is used to calculate the setpoints for the Radvaste Discharge Radiation Monitor - ESV Discharge and Liquid Radvaste Adjustable High Flov Trip Unit to ensure that liquid radvaste effluent releases from the site to unre-i stricted areas are below the concentrations specified in 10CFR20, Appendix B, Table II, Column 2 for radionuclides other than noble gases. An MPC of 2.0E-4 pCi/a1 has been established for dissolved and entrained noble gases. The Radvaste Dis-charge Radiation Monitor - ESV Discharge provides alarm and automatic termination of releases prior to exceeding these limits.
OM12D: ODCM Page : 3 Rev. 3 NOTE: Liquid radvaste discharge flow rate shall be verified at least once per four hours, whenever the flow rate measuring device (s) is inoperable during actual releases. 2.1.1.1 Determination of the Minimum Acceptable Dilution Factor C DF . I (2.1-1) i MPC g Vheres , DF - the minimum acceptable dilution factor determined from analysis of the ifquid effluent to be released: Cg - the concentration of radionuclide "1" in the batch to be released, in WC1/mli MPC g = the limiting maximum permissible concentration of radionuclide "i", from Appendix B. Table II, Column 2 of 10CFR20, in pCi/ml adn (2.0E-4 uCi/ml for noble gases). DF = 10 DF, (2.1-2) Vhere DF = the conservative dilution factor used by PNPP to calculate the maximum release rate prior to releare in order to ensure compliance with 10CFR20 DF, - the minimum acceptable dilution factor, as per equation 2.1-11 10 a factor of ten less than 10CFR20 limits as specified in Appendix B, Table II, Column 21 this factor ! represents an order of magnitude of conservatism for I liquid radvaste releases from PNPP. l l 4 NOTE: If the concentration of a radionuclide is below the i lover lirit of detection the radionuclide shall not be included as a source term in the setpoint calcu-
> 1ation.
2.1.1.2 Determination of the Maximum A11ovable Radvaste Tank Discharge l Flov Rate (0.64)( adf) i f aax - DF (2.1-3) l I ! l
OH120: ODCH Page : 4 Rev. : 3 i Vheres f""* - the maximum allovable radvaste tank discharge ficv rate for the batch to be released, in gps DF - the conservative dilution factor, per equation 2.1-2 adf - the minimum dilution flov - supplied by the Service Vater system, i.e., the lov flov slarm setpoint of the Service Vater Flow Transmitter P41-N443 - 30,000 spel 0.64 an engineering factor to prevent spurious alarms. 2.1.1.3 Liquid R6dvaste Discharge Flow Honitor Alarm Setpoint Monitor alarm setpoints are determined to ensure that the concentration of radionuclides in the liquid radvaste effluent released from PNPP to unrestricted areas does not exceed the limits specified in 10CFR20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. An MPC of 2.0E-4 uCi/ml has been established for noble gases dissolved and entrained in liquid effluents. 1 SPg - (1.25)(fact) (2.1-4) Vhere
- SP g Liquid Radvaste Adjustable High Flov Trip Unit (G50-K805A/B or G50-K926/7) alarm setpoint, in gpm; f act the actual allovable radvaste tank discharge flow rate for the batch to be released, not to exceed the maximum allovable radvaste discharge flow rate (fmax) as defined in equation 2.1-3; 1.25 the engineering safety factor to prevent spurious .
alarms. l The liquid radvaste tank discharge flov should be maintained at { or below this f value by proper regulation of the high ; volumeorlovv8!6medischargethrottlevalves(G50-F153or i l G50-F155). , t I t
OM12D: ODCM Page : 5 Rev. : 3 2.1.1.4 Liquid Radvaste Discharge Radiation Monitor Alarm / Trip Setpoint Monitor alarm / trip setpoints are determined to ensure that the concentration of radionuclides in the liquid radvaste effluent released from FNPP to unrestricted areas does not exceed the limits specified in 10CFR20, Appendix B. Table II, Column 2 for radionuclides other than dissolved or entraAned noble gases. An MPC of 2.0E-4 WCl/ml has been established for noble gases dissolved and entrained in liquid effluents. CR = I (C )(E g g) (2.1-5) i Vhere: CR, = the calculated monitor count rate above background, in epm; Cg = the concentration of radionuclide "i" in the batch to be released, in WCi/ mil Eg = the detector efficiency of the monitor for radionuclide "i" in epm /(uct/ml). 1 0 CR, = (R,)(Fx)I Cg (2.1-6) Vhere: CR* = background, the cross-calibrated in cpm; monitor count rate above F*
= the cross-calibration factor used to ratio the Liquid Radvaste Discharge Radiation Monitor actual response to the Cs-137 calibrated response; ,
R = the response of the Liquid Radvaste Discharge s Radiation Monitor to a Cs-137 calibrated standard, in eps/(uci/ml). SP r
=
(1.25) (feax#Iact) (CRn )
- I2*I~ I Vhere SP' = the Radvaste Discharge Radiation Monitor - ESV Dis-charge (OD17K0606) alarm / trip setpoint, in cpml BG = the background count rate due to internal contami- ;
nation and radiation levels in the area of the monitor ; 9
OM12D: ODCM' Page : 6 Rev. : 3 CR = the monitor net count rate, either CR or CR , as n x per equation 2.1-5 or 2.1-6; 1.25 - the engineering safety factor to prevent spurious alarms; f*** - an adjustment factor (to account for the difference between an actual radvaste discharge flov_ rate to f be used for the discharge and maximum allovable act radvaste discharge flow rate) to allow operational flexibility and to minimize spurious alarms: Where:
- the actual radvaste discharge flow rate; this f*** value must always be less than or equal to I 3 max f*** = the maximum allovable radvaste discharge flov rate, per equation 2.1-3.
i 2.1.2 Compliance with 10CFR20 - Liquid Effluent Concentration In urder to shov compliance with 10CFR20, the concentrations of radionuclides in liquid effluents vill be determined and compared with the limiting maximum permissible concentrations
. (HPC) as defined in Appendix B, Table II, Column 2 of 10CFR20 (2.0E-4 uCi/ml for entrained and dissolved noble gases).
Concentrations of radioactivity in effluents prior to dilution vill be determined. Concentration in diluted effluent vill be calculated using these results prior to each batch release, and folloving each batch release. PNPP has no continuous releases. 2.1.2.1 Concentration of radionuclides in Prerelease I i The radioactivi'y content of each batch release vill be ; determined prior to release. PNPP vill show compliance with 1 10CFR20 in the following manner: ) The concentration of the various radionuclides in batch releases prior to dilution is divided by the minimum dilution
;f flow to obtain the concentration at the unrestricted area.
This calculation is shown in the following equation: 1 l (C3 )(f)
,I Cone g- (2.2-1) ad! ,,---- - - - - - - - - , - _n . , un --- - - ,
s OH12D: ODCH Page : 7 Rev. 3 Where: Conc the concentration of radionuclide "i" at the 3 unrestricted area, in WC1/all Cg the concentration of radionuclide fi" in the batch to be released, in WC1/ mil f - the radvaste tank discharge flow rate for the batch to be released, in spm; adf o the minimum dilution flow, per equation 2.1-3, in spm. The projected radionuclide concentrations in the unrestricted area are compared to the maximum permissible concentrations in I Appendix B, Table II, Column 2 of 10CFR20 (2.0E-4 uCi/ml for ' i dissolved and entrained noble gases) in order to give a final 10CFR20 compliance check, i.e., the following equation must be mets p Cone g (2.2-2)
/. NPC g 5I i
i Vhere: Coneg the concentration of radionuclide "i" at the unrestricted area, in uCi/mli MPCg the limiting maximum permissible concentration of radionuclide "i", from Appendix B. Table II, Column 2 of 10CFR20 (2.0E-4 UCi/ml for dissolved ' and entrained noble gases), in WC1/ml. I 2.1.2.2 Post Release l l The actual radioactivity content of each batch release vill be determined following release to show. final compliance with i 10CFR20.
- The concentration of the various radionuclides in batch releases prior to dilution is divided by the actual dilution to obtain the concentration at the unrestricted area. This calculation is shown in the following equation:
l l (C )(Virt) g l l Coneg = y (2.2-3) ;
- dil ;
d , i
. - _ _ - _ . _ .-- .. - - - - _ . . _ _ _ - _ - _l
OM12D: ODCM Page : 8 Rev. 3 Where: Cone the actual concentration of radionuclide "i" at g = the unrestricted area for the release, in uCi/mli Cg = the concentration of radionuclide "i" in the batch released, '.n pCi/sl; the actual volure of dilution water during the Vdil release (total plant discharge flov, including Service Vater, Emergency Service Vater, and cooling tower blevdown), in. gallons: V irt = the actual volune cf the liquid radvaste tank dis-charged for the batch, in gallons. The concentrations in the unrestricted area are compared to the maximum permissible ccncentrations in Appendix B, Table II, , Column 2 of 10CFR20 (2.0E-4 pCl/ml for dissolved and entrained noble gases). In order to demonstrate final compliance vith 10CFR20, the following equation must be met Conc 3 (2.2-4)
/ . MPC g II i
Vhere: 1 j Coneg = the concentration of radionuclide "i" at the unrestricted area, in pCi/mli MPCg - the limiting maximum permissible concentration of radionuclide "i", from Appendix B, Table II, Column 2 of 10CFR20, in pCi/ml. 2.2 Continuous Releases A continuous release is the discharge of fluid vastes of a non-discrete volume, i.e., from a volume or system that has an input flov during the continuous release. Continuous radioactive releases are not planned for PNPP although the potential does exist for RHR heat exchanger leakage into the Emergency Service Vater system. Potentially contaminated dicharges fron. the ESV are monitored by an installed radiation monitoring system. This system consists of two channels, one for monitoring downstream of equipment in Emergency Service Vater System Loop A and the other for Emergency Service , Vater Loop B. Monitors are set to alarm at three times background i level. If radiation is detected, the affected Emergency Service l Vater line can be manually isolated. The decision of whether to isolate or not is dependent upon other conditions. The PNPP staff vill take appropriate action to limit release.
OM12D ODCM Page : 9 Rev. 3 . The Emergency Service Vater discharged vill be sampled and analyzed in accordance vith PNPP Technical Specification Table 4.11.1.1.1-1. To show compliance with 10CFR20, the sum of the concentrations of radionuclide "i" in unrestricted areas due to both continuous and batch releases divided by that isotope's MPC aust again be less than 1. o N l
Figure 2.1-1 LIQUID RADIOACTIVE WASTE (LRW) DISCHARGE SYSTEM i
.CV 854 2 CHEMICAt W AST E '
S -----V'-~~-~7 ( DISTILLATE TANKS / - i i l if (_g '
$ Cto s'es O N---
LOW sw. oisCn , LOW g- -- ,g j ,C,v 3 l CLOSES ON ! l HIGH R AD. l
~
=
( 2 DETERGENTh
= \ \
g DR AIN TANKS u
. 't z
gg .
= i i g 1r
- i I i
SCW 158 - ( g - ESW
' ~
I 2 ,LOOR DRAIN I l I i
)
l S i s a i i
- ( SAMPLE TANKS ,-
l
= : 'iMPh!"-
r
---- RM
- (o
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) l i -
1
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< = -
[ } = \(.'I
/
> l LIE j 2 WASTE g SAMPLE TANKS I g 'd5 t__________ ___a "
g .
,E
> l C LOW SW. DISCR FLOW s W oisCn O 5 LAKE I
OM12D: ODCH Page : 11 Rev. : 3 2.3 Compliance Vith 10CFR50, Appendix I - Liquid Effluent Dose Doses resulting from liquid effluents vill be calculated at least monthly to show compliance with 10CFR50, Appendix I. A cumulative sumustfora of total body and organ doses for each calendar quarter and calendar year vill be maintained. Additionally, doses due to liquid releases are projected monthly. 2.3.1 Dose Calculations Radiation doses due to liquid radioactive effluents from PNPP , are calculated based on three main dose'pathvays potable water, aquatic foods (namely fresh vater fish ingestion), and exposure to shoreline deposits. Irrigated food pathvays, as - discussed in Regulatory Guide 1.109, vill not be of concern at PNPP as little or no vater from Lake Erie is used for irrigation in the nearby Ohio counties of Lake, Ashtabula, Cuyahoga and Lorain. Nursery businesses and other agricultural activities that require supplemental water generally rely on water drawn from small ponds and streams. Radiation dose to members of the public for liquid radioactive releases from PNPP vill be calculated for the potable water, aquatic food, and shoreline deposit pathways using the following equations:
- 1. Potable Vater U
R,)p 1100 (H p { F) f(O)(D,g))exp(-A g p g tp) (2.3-1)
- 2. Aquatic Foods:
U R,)p = 1100 I5p {F) I (O )(Bg g p)(D,gp)) exp (-A g tp ) (2.3-2) g
- 3. Shoreline Deposits:
(U,,)(V) R,jp - 110,000 (M HF) I (Og )(Tg )(D,gp )) * (2.3-3) g P lexp (-A t )l * [1 - exp (-Ag tb )I gp Vhere R,3p = "the dose to individuals of age group "a" to organ j" from all the radionuclides in pathway "p", in area l i
- - . _ - . _ - . - - , - - .. - - - - - - - - - - - - - , . , . - . . _ _ - _ . - . - , - , - - - - - - _ _ - - , , - . . ~ . - - - . _ - , . -
l I l OM12D: ODCH Page : 12 Rev. 3 1 B 3p the equilibrium biaccumulation factor for radio-nuclide i in pathway p, expressed as the ratio of the concentration in biota (in pCi/kg) to the radionuclide concentration in water (in pCi/1), from Table 2.3-4, in 1/kg; D,gE) the dose factor, specific to a given age group "a", radionuclide "i", pathway "p", and organ "j", which can be used to calculate the radiation dose from an intake of a radionuclide, in arem/pcil or from exposure to a given concentration of a radio-nuclide in sediment, expressed as a ratio of the dose rate, in arem/h, agd the areal radionuclide concentration, in pCi/m , from Tables 2.3-5 through 2.3-9: F - the flow rate of the liquid effluent in ft /s Mp the dilution factor at the midpoint of exposure (or the point of withdrawal of drinking vater or point of harvest of aquatic food), from Table 2.3-10, dimensionless: Og the release of radionuclide "i", in Ci tb - the period of time for which the sediment or 5 soil is exposed to the contaminated water, 1.75 x 10 h (20 years): Tg the halflife of radionuclide "i", in days tp - the average transit time required for radionuclides to reach the point of exposure, from Table 2.3-11 for internal dose, t, is the total time elapsed between release of the radionuclides and the , ingestion of food or vater, in hs U ap the usage factor that specifies the exposure time or ' intake rate for an individual of age group a l associated with pathway "p", from Table 2.3-12, in I h/yr, 1/hr, or kg/hr:
- V - the shoreline width factor. 0.3 (from Regulatory Guide 1
1.109): A g-ther9ioactivedecayconstantofradionuclide"i", d in h~ 3 1100 a factor to convert from (C1/yr)/(ft /s) to pCi/11 l I l
OM12D: ODCH l Page : 13 Rev. : 3 110,000 - a factor to convert from (Ci/yr)/(ft3 /s) to pCi/1 and to account for the prorortionality constant used in the sediment radioactivity model. 2.3.2 Cumulation of Doses The dose contribution from liquid effluents vill be calculated at least monthly. Calculations vill be performed to determine the maximum total body as vel) as the maximum organ dose to an individual. These dose calculations vill be summed for comparison with quarterly and annual limits. These results vill be summed with the doses cumulated from the other months in the quarter of interest and in the year of interest. To assure compliance with the dose limits of 10CFR50, Appendix I the following relationships shall hold: , for the quarters Dose f 1.5 arems total body: Dose f 5 mrems any organg for the calendar year Dose f 3 mrems total body: Dose $ 10 mrems any organ. The quarterly limits given above represent one-half of the I annual design objective. If these quarterly or annual limits are exceeded, a special report vill be submitted to the NRC, in accordance with PNPP Technical Specifications, stating the reason and corrective action to be taken. 2.3.3 Projection of Doses Antit.ipated doses resulting from the release of liquid efflu-ents vill be projected monthly. The doses calculated for the present month vill be used as the projected doses unless information exists indicating that actual releases cotid differ significantly in the next month. If the projected dose, when averaged over 31 days, exceeds 0.06 mrem to the total body or 0.2 ares to any organ, the liquid radveste system vill be used to process vaste. The values for the projected dose impact levels correspond to approximately one forty-eighth of the Appetidix I design objective. If con-tinued at this rate for one year, the projected impact vould correspond to less than one-fourth of the Appendix I limit. l The projected doses vill be calculated using Equations 2.3-1, j 2.3-2, and 2.3-3.
OH12D: ODCH Page : 14 Rev. : 3 In this case, the source term vill be adjusted to reflect this information and the justification for the adjustment noted. This adjustment should account for any radvaste equipment which was operated during the previous month that could be out of service in the coming month. 2.2.4 Population Dose PNPP's Semiannual Radioactive Effluent Release Reports, as required by Regulatory Guide 1.21, vill include total population dose and average individual doses calculated for radioactive effluent releases. The total population dose and average individual doses vill be calculated using average individual transit times and usage factors, Table 2.3-12, (as compared to maximum exposed individual factors used for individual doses). The total population dose vill be calculated by dose pathvay and organ, with pathvay doses being j corrected for the fraction of the population assumed to be in r each age group (adult, teen, child and infant 0.71, 0.11, 0.18, 0.0 respectively), i l
)
OM12D: ODCM Page : 15 Rev. 3 Table 2.3-1 Organs used for Liquid Effluent Dose Calculations i
- 1. Bone
- 2. GI Tract
- 3. Kidney
- 4. Liver
- 5. Lung
- 6. Thyroid
- 7. Total Body 3
- 8. Skin Table 2.3-2
- Age Groups used for Liquid Effluent Dose Calculations j 1. Adult (17 yrs, and older)
- 2. Teen (11 - 17 yrs) t J
l
- 3. Child (1 - 11 yrs) t
- 4. Infant (0 - 1 yr) 1 Table 2.3-3 i Liquid Effluent Dose Fathways
- 1. Vater Ingestion
- 2. Shore Exposure j 3. Fresh Vater Fish Ingestion i,
4 i
OM12D: ODCM Page : 16 Rev. : 3 Table 2.3-4 Bioaccumulation Factors (Bg p ) (pCi/kg per pCi/ liter) Element Fish H 9.0E-01 C 4.6E+03 Na 1.0E+02 P 1.0E+05 Cr 2.0E+02 Mn 4.0E+02 Fe 1.0E+02 Co 5.0E+01 Ni 1.0E+02 Cu 5.0E+01 Zn 2.0E+03 i Br 4.2E+02 i Rb 2.0E+03 Sr 3.0E+01 Y 2.5E+01 Zr 3.3E+00 ; , Nb 3.0E+04 , Mo 1.0E+01 Tc 1.5E+01 Ru 1.0E+01 Rh 1.0E+01
~
Te 4.0E+02 I 1.5Et01 Cs 2.0E+03 Ba 4.0E+00 La 2.5E+01 Ce 1.0E+00 , i Pr 2.5E+01 l l Nd 2.5E+01 ! V 1.2E+03 j Np 1.0E+01 i l ! i l l 1 i ! l i l
OM12D: ODCM Page : 17 Rev. : 3 Table 2.3-5 Ingestion Dose Factors for Adult (ares /pci ingested) i SONE Livet f.m00y Thya010 KIDNtv LUNG GI-LLI NUCL I L'.t...... .......................... ................... .................... H 3 WO DafA 1.05t.07 1. O b t -0 7 1.05t=07 1.05L-07 1 05t-07 1 05t=07 C 14 2.84t*06 S.68t-07 S.68t-07 5.68t-07 5.68t-07 S.68t-87 S.68t-07 NA to 1 70t=06 1 70f=06 8 70t=06 l.f0t=06 1 708-06 1 70t=06 8.70f=06 P 32 1.93t=04 1 20f=0S 7. 46 E -0 6 40 Data NO DATA h0 Data 2.17t-05 CR St NO DafA 40 Cafa 2. 66 t -0 9 1 59t=09 S.86L-10 3 53t=09 6.69t=0F MN $4 40 Data 4.fft-06 8.721-07 NO CATA 1.368-06 NO O&fA 1 40f-05 MN $6 NO O&TA 1.tSC-07 2. 04 E -0 8 NO 0674 1 46t=07 NO Cafa 3.67t-06 ft SS 2.75t-06 1 90F=06 4. 4 s t-0 7 NC Data No cafa 1 06t=06 1.09E 06 F t 19 4.34E=06 1.02t*05 3. 9 8 t.0 6 40 DafA NO DATA 2 858-06 3.401-05 CD 58 NO 04fA 7.4Si=07 8.67t=06 40 Data NO DATA NO Cafa 1 5tE=0S CC 60 NO Cafa 2.14F=06 4.72C-06 NO Cata NO 06f4 NO DATA 4.028-05 i NI 63 1 30E-04 9.011-06 4.36t-06 NO 04f4 NO CafA NO CATA 1 88t.06 NI 65 S.28t=07 6 86t=08 3.13 E -0 8 NO DATA NO DATA ho Data 1.74f-06 ! CU 64 NO DATA 8.33I.00 3.9tt-08 NO DATA 3.10t=07 ho O&fA 7.lCt=06 1 2N 65 4.848-06 1 54I-05 6.968-06 NO CafA l.038-05 NO 04fA 9.70E-06 1 ZN 69 1 05t=08 1.9fE608 1. 3 7 t -0 9 NO 047& 1.288-08 NO DATA 2.96t=09 l 84 83 NO 04'A NO DATA 4.02t=08 NO DATA NO Cata ho 0&fA S.791-08 i 84 84 NO DATA NO C&TA S.218-08 NO CafA NO DATA ho D&TA 4.09E-13 BR SS NO Cafa NO DATA 2.148-09 NO D&f4 NO C&TA h0 DafA LT (=24 R8 86 NO DATA 2.ttt=0S 9.838 06 NO DATA NO DATA NO Cafa 4.16t=06 R8 88 NO Cafa 6.051-08 1.211-08 NO DATA NO 0&TA NO D&fA 8.361-19 : R8 89 NO O&TA 4. Cit-08 2 82t-0 8 NO DATA NO Data NO DAfa 2.33t=21 I 1R 89 3.08t=C4 NO Cafa 8. 84 E -0 6 NO DATA NO 0474 NG O&f4 4.94t=0S SR 90 7.58t-03 NO 04f4 8 861-03 NO DATA No CafA No Data 2.19t=04 2 70E.05 SR 91 S.67t=C6 NO 04f4 2.298-07 40 CATA NO 04f4 NO DATA 3R 92 2.llt-06 NO O&fa 9.30t.00 NO CAf4 NO Data NO 04f4 4.26t-0S Y 90 9.62t-09 NO 04fA 2 58t=10 No DATA NO DATA NO D4TA 1 02t=04 Y 91N 9.098-11 NO 04f4 3. Si t.12 NO 04fA M0 DATA No D&TA 2.674 10 Y 91 1 418-62 40 04f4 3.778-09 NO DATA NO DATA ko 0&f4 7.768-05 Y 92 8 4St=10 NO DATA 2 4f(-11 ho Otf4 NO DATA NO 04fA t.488-05 Y 93 2 68t?O9 h0 Data 7.4 0 t-i l NO 04fA NO 04fA k0 DATA 8.508-05 2R 95 3.04t=05 9.75t-09 6.60t-09 NO O&f4 1 53t 08 NO DATA 3.091 05 2R 97 1 68t=09 1.398 10 1.lltalt NO D&fA S.IIE=le h0 Defa 1.0$t=04 48 99 6 228-09 3 46t=09 1. 8 6 t -0 9 WO CafA 3.428-09 #0 Data 2.10t-05 ND 99 NO Cata 4.311 06 8.201-07 NO DATA 9.768-06 ho 04fA 9.99t=06 FC 99M 2.478-10 6.98t=10 8.898-09 NO 04f4 4 06t=08 3 4d8=10 4.tSt=0? l l l l ll l 1 l
- - - - , ,_- ------_n - - _ - . + - ,+-.4 u , + - y 4 ,n -.. -,,..._- w--,p- ------w-- w--- -
4
OM12D ODCH Page : 18 Rev. 3 I Tablo 2.3 5 (Cont.) Ingestion Dose Factors for Adult (arem/pCi ingested) wuct:0t tomt Livia r.s00v TMea010 al0=tv tvec si.LLI
.............. .....w........... ................- - - ............ - . .
Tctet 2.64t.10 3.66t.te 3.59t.09 90 Data 6.59t.09 t.sfc.10 t.10s.at aut03 1.ste-07 =0 Dafa f . 9 7 t.c e =c Ca f a' f.est.of =0 pafa r.tes.05 autes 1 54t-08 mu cafa 6. 0:t .09 =0 Data t.99t at =0 Data 9. ort-06 aut06 a.75t.06 =0 Data 3. 4 s t .0 7 =0 Data S.sta.06 =0 Data t.78t.04 Act Om t.60t.07 1.48t-07 8. 9t.0 a w0 Dafa 2.9tt.07 wo 0#fa teset-el fetzlm 2 6st.06 9.fts 07 3.5 9C.0 7 s.06t.07 1 09t.05 =0 Data t.0ft.05 T212fm 6.77t=06 3 42C-06 8. 2 9 t .4 7 8.73t.06 2.ftt=05 NO Cata 2.378-05 7t127 1.let.07 3.951-08 F . 3 8 E .0 0 B.llt-OS 4.4tE.07 NO Cafa 8.68E.06 TE129M 1.tSt=0S 4.79t-06 1. a 2 8 -0 6 3.95t=06 4.001-05 NO Dafa S.798-05
! TEt29 ..t4t=08 1 10t.08 7.6st=09 2.418-08 1.32t.07 #0 DafA 2.37E.68 TCt3th 1 73E-06 8.46t=07 7. 0 5 t .0 7 1 34t 06 0.578 06 NO DafA 8.40E-05 ; fit 31 1 978-04 8.23E=09 6. 2 2 t-0 9 1 62t=08 0.635 00 NO DafA 2.798-09 !
i 78132 2.928 06 1 631 06 1.lat 06 1 00E-06 1.57E-05 h0 Cafa 7.711-05 i 130 7.96t.07 2.23t.06 8. 8 0t.0 7 1.09t=04 3.48t.06 NO DAT A 1 92F-06 j i 131 4.168 06 5.95t-04 3.418 06 1 95t-03 1.028-05 NO Cafa 1.lft")4 l I i 132 2.03t-07 5.48t-Of 1. 9 0 t.0 7 t.90t-05 s.65t.07 na Cafa 1 0tt.07 l 1 133 1 4tt=06 2.4ft-06 7.538 07 3.63t=04 4.310-06 ho Oafa 2.Itt-06 I i 134 1 06L-07 2.00;-07 1038 0F 4.99t*06 4.50lp07 NO Dafa I.Stt-it k... I 139 4.43E-07 1.16t.06 4. 2 8 t.0 7 7.65t.05 1.861-06 NO Cafa 1.318 06 C5134 6.22t=0S 1.48t-04 1. I t t -0 4 NO DATA 4.79E.05 * .598 05 2.59t-06 , Clt36 6.ltt-06 2.578-05 8. 0 5 t -0 5 40 Cafa 1 45t.06 t.96t.06 2.928 06 l l C$taf 7.978-05 1 09t=04 7 14 t.0 5 N0 Data 3.701 06 1.25t.09 3.tte.06 ,
) Cll30 5. lit.00 1.C91-07 5. 4 0 f .0 0 NO Cata 3.0tt.00 7.918-09 4.65t.13 84139 9.70t.00 4.94t-tt 2.848 09 M0 Dafa 6.46E-tt 3 928 11 1 72t-07 j '
04140 2.05t=09 Felit.04 1.33te16 NO e&fa 8.674 09 1 46t.00 4.tSt=0S ' nat41 4.7tt-00 9.lst-st 1 19t.0 9 40 DafA 3.318 11 3 03t.11 3.33E t? Dater 2.13t.08 2 198 11 1 14t-0 0 NO Cata 4.sSt-tt t.34t=Lt 1 00E-36 l Lalet 2.60t=09 1.26!.09 A.33C=le 40 Data NO Cata 20 Data 9.tSt.05 ' '! Lal42 1.281-10 5.821-11 1.45t.lt WO DATA N0 DATA 90 Dafa 4elle-07 CEL41 9.36E 09 6.llt.09 F.t tt=l e >0 Data 3.94t.99 h6 DATA 2.4tt-05
.....................3........... ...................... . .... ..... .
5.171-10 20 Data 4.54t.05 Cel43 8 65t.01 t.FJF.06 1. 3 5 t.t t Mc Safa i til44 4.ast.07 2.00t.07 7 62:-00 NO DATA 1.284 07 NO Safa L.65t.04 j Pa143 .20t=09 3 698-09 4.66t.8 0..................,........... 40 DafA 2 135-09 we Safa . 4.03t=0S
< Pal 44 3.08t-il I.tSt.11 4.968 13 to Cafa 7.0SE.12 No Data 4.33t-18 j N0147 6.29t=09 7.D6 09 4.155 10 as DAT4 4.25t.09 40 Data 3.49t=99 N 147 1.052-07 8.4tt.00 3.04t 01 40 DefA .....
NO 047A
#0 Data 3.0ft-05
... ....... - . ...... ... . m NF239 1 198-09 1. tit =10 6.4%E.11 40 Data 3 698-10' NO DATA 3 408-05 1
1 1 l 1 ]
. - - - - . . . - - - - - _ _ _ - . - - ~ _ _ _ _ _ ___ - _ _ . - _ _ _ _ _ __
l OM12D: ODCH Page : 19 Rev. : 3 Table 2.3 6 Ingestion Dose Factors for Teenager (aren/pcl ingested) Ltytt f.800Y TMYACIO RIONtv LUNO GI-LLI NUCL 10f SONE
............w .................. .......... .............................
Il 3 NO Cala 1.06t.07 1. 0e t -0 7 1 06t=07 l.06t=07 t.06t=07 1.061-07 L 14 4.06t=0e v.12t*07 8 121-07 8 12t=07 8.12t-07 8.12t-07 8.82F-07 Na 24 2 301-06 2.301-t6 2. 3 0 E -0 6 2 30E*06 2.304-06 2 10t-06 2 30t=06 P 32 2 76t=04 1.ftC-OS 1.0ft-05 NO 0474 NO DATA 40 DafA 2.32f-OS CR 51 NU CATA NO Cafa 3.601-09 2 00t-09 7.89t=10 S.14t=09 6.05t-07 1 28t-05 PN in NO Cafa 1.70t=0e 1. tit.06 Nn Oafa 1.76t=06 NO Cafa mN 96 NO Data t.Stt.37 2. s t t.0 8 NO CatA 2 00t=07 NO Cafa 1 0st.05 FE lb 3 181-06 2.6Lt.06 6. 2 5 t .0 7 Nn Data Nc nafA 4 70f.06 t.let=06 F t 19 5.878-06 1.Jff=05 5.294-06 NO Cata NO DATA 4.32t-06 3.24t.05 CD 18 NO CafA 9.72t=07 2. 2 4 t.0 6 nu D&TA NO DATA NO D&fa 1.34t-Cl NO DafA 2.811-06 6.33t-06 NO DATA NO Defa NO Cafa 3.66t=0S CD 60 NO Cafa NO D&IA 1 99t-06 NI el 1 778-04 1 25t=0S s . 00 E-0 6 NO DATA 7.491-07 9.571-08 4.361 08 NO D&Ia NO DATA NO Cata 1.19t-06 NI 65 2.9tt-07 NO Cata 8.92t-06 CU 64 NO Cafa 1.15f-07 5.418 08 NO D&fa 8.47E-06 FN 6h 5.76t-06 2.CCE-05 9.13 t -0 6 NO D&fa 1.28t*05 NO Data AN 69 1 471*02 2.60E-08 1 96 t =0 9 NO D&TA 1.a)t*08 NO Cafa 1.16t=08 et 83 NO CafA NO DATA S . 74 t -0 8 NO Cafa NO D AT A - NO DATA Lf E.24 88 On NO DATA NO C&TA 7. 2 2 t -0 8 NO CATA NO CafA NO DafA LT t-24 et On NO DATA N0 CATA 3. Cit =0 9 h0 Data NO Cafa NO CafA LT f=24 at 86 NO Cafa .2.978-05 1 40E-05 NO DATA NO 0414 40 C&fa 4.4tt.06 48 88 NO Dafa 8.52t-08 4.let-08 NO DATA No 04f4 No C&fa 7.30f-Il i at 89 No D&fa S.let-OS 3 891-08 N0 DATA 40 DATA No cafa 8.43f-t? 4.40t=04 NO C&TA 1. 2 6 t .0 5 NO DaIA N0 CATA NO CafA S.24t=0S 14 81 NC OATA NO DATA 2.llt=04 54 90 8 30f=03 NO 04f4 2 0SE-0 3 NO 04fA 8.07t=06 NO D&fA 3.2 t t-0 7 40 Data NO DATA NO Onta 3.66t=0S SR 11 NO Cata SR 92 3.05t-06 NO CatA 1.101-07 No caTA NO 04f4 7. 7 T .'= 0 5 1 37t=08 NO DATA 3.698 10 no 04fa NO D&T A NO DATA 1 13(a04 Y 90 . ... ..... ..................... ... . 4.93E.12 NO Cata he DefA WO 0&fA 6.09t-09 Y eta 1 29t*10 NO DATA No Data 8.24t-GS Y 91 2 018-07 NO 04T4 5. 39t-0 9 NO DafA sec OATA Y 92 3 21t=09 NO D&TA 3.50f =11 NO DATA MQ DATA NO DATA 3.32t-05 3.83t.09' 40 DATA 1.05t.10 NO 0%f A NO DAf4 NO Defa 1 17t.04 T 93 1 9tt=08 40 D&TA 1.005-01
!a 95 4 822-08 1 30t.08 8.94t.09 NO L,afa t.27t=04 ta 97 2 37t-09 4.69t-10 2.16t-10 NO D&f4 7 111-10 NO DAT A wm 95 8 222 09 4.561-09 2. b i t =0 9 40 Defa 4.421-09 40 04f4 1 95t=0$
Po 99 NO DATA 6.03C-04
. . l lt -0 6 NO Cafa 1 381-05 NO Oafa t.08t.0$
8.928-10 9.261 10 4 20t-0 8 NO CafA 3 18t.nd 5.14t 10 4.04t.07 FC 99m
-.. - - ,_.,.,n.,-. _,-- .., __ - - .
l OM12D ODCM Page : 20 Rev. : 3 Table 2.3-6 (Cont.) Ingestion Dose Factors for Teenager (aren/pci ingested) l j l \ l
. I Livan T .600f THva010 alowty Lu%s st.ttl ,
i hvCLIDI s046 TClet 3.60t.60 9 421 10 9. O l t-0 9 no CaTA 9 26t-09 3.12E-10 e.75t-17 9u103 2.lle-07 mu casa t.098 07 =0 Data s.998 07 ho Cafa 2.t3t.05 autel 2.tst.04 no paTa 0. 4 6 t .0 9 go DAfa 2 755 07 WO caTA t.76t 05 nul06 3.921-06 g0 Cafa 4. 94 t -0 7 =0 e4TA 7.56t-04 ho Oafa t.est.04 ActlOa 2.0st.07 t.94t.07 1 18t.07 40 paTA 3.70s.07 h0 caTA 1.45t-05 no paTA Tillna 3.s38-06 1.384 06 S.128-07 1 078-04 =0 Dafs t.13t.05 Tettfm 9.67t-06 3.4st-06 1. t t t -0 6 3 30t-06 1.92t-05 =0 Data 2.6tt-05 til27 t. Set.07 5.ett.Os 3.4 0 s.e s 1 09f.07 6.60t 07 No Cafa 1.22t.05 Titata 1 63t-05 6.0lf-06 2. l e t -0 6 S.26t-06 6. alt.05 mn OaTA 6.12t-05 ft:29 4.6st-08 1 67t.08 1 01t-O s 3.2 0 E-0 8 1.sti.07 he CaTA 2 45E-07 filat> 2.44t=06 *1.ttt-06 9.76t=07 n.F6t 06 1.22E-05 NO DATA 9.39t-05 TEL3L 2.798-08 t.tSt-08 8.728-09 2.llt-00 1 22t=07 NO DATA 2.29t-09 i fin 32 3 49t=06 2 21t-06 2.08t=06 2 33t-06 2 12E-05 20 DATA 27.00E-OS 29[.06 l 1 110 1.03t=06 2 90f=06 1 19t*0 6 2 43t=04 4.59E-06 WO DATA t I 131 5 05t=O6 8.19t=06 4.40t 06 2 39E-03 1 4tt=01 NO DATA 1 62t=06 , l 132 2.798-07 7.30t=07 2.628-07 2 46E-OS 1.tSt-06 NO DATA 2.let-06 3. TIE-07 I 133 2.0tt-06 1.4Lk 06 1. 04 E -0 6 4.76E-04 S.98t-06 NO Defa 1 134 1.46t 07 1.t?t=07 1.291-07 6 451-06 6.104-07 1 10E-09 kJ DATA ~ . ..
.... ... - i i 135 6. tot-07 1.l?t-06 5.82t 07 1 01t-04 2.40t-06 NO DATA 1 74E-06 l C5136 3.37t=05 1 97t-04 9.16 t-0 5 ko OATA 6.26t=05 2.398-05 2 65E-06 C1136 8 59t=06 3 30t-05 2 2 7 t-O S NO 0&TA 1 04t-05 2 90E-06 2.728 06 I
C5137 1 12t=04 4 49t=04 S .19 t -0 5 h0 Data 1.07E-05 1 97t=0S 2.128-06 1 C5138 7.76t 00 1.49t-07 7.458-08 #0 DATA 1.10E-07 1.20f=88 4.76t-tt i j sal 39 n.39t-07 9.7st.it 4.06t 49 =0 esta 9.22t.it 6.74t.11 t.24t.e6 : 64160 2.04t-06 3.44t=08 f . 8 8t *0 6 40 Data 1.*st.00 2.14t.00 4.301-05 r Rat 6i 6.7tt-08 5.ntt it 2.248-99 40 Data 4.65E-il 3443t.nl 1 43t=13 2 99t=08 2.998-11 1 84E49 40 Data 2.536 11 3 99t.tt 9.108 20 > 84142 ,
) Lat40 B.401-09 1.71t-09 4. llt =10 90 04Ta NC DaT4 NO DATA 9.028-08 l Lat42 1.79t-10 7.99E-il 1.9 0t *l t to Dafa N0 DATA h6 DATA 2.42E-06 I Cttel 1 33E-08 0 00t-99 1.028-99 40 Data 4.let 09 ho D&Ta 2 94t-05 (
1 Cit 43 2.35t-09 1 718 06 1.918-10 he Data 7.674-10 NO Data 51 14t=0S 79t-04 i Cit 44 6.96t=07 2.00t.07 3 748-08 WO DATA 1.72t*07 40 DATA pal 43 1 318-08 1.2 3C 09 6.52 t-t e WO DATA 3 64t=09 WO DATA 4.318 05 ; 4.74t 14 4 I Pal 44 4.30E.11 1 768. t l' 2. l t t-12 NO D&!A 1.018-11 he DATA 9.18t-09 1.02t=04 6.118-10 h0 DATA S.99t=09 kn DATA 3.60t-05 l 40147 W 187 8 468-07 1.19t 07 4 178-00 #0 DATA NO DATA h0 DATA 3 221 01 i NP239 1.76t-09 1.66f-10 -9. 2 2 E -11 1ec DATA $.211-10 NO DATA 2 67t=0S ! l l 1 I J l i i 1 I
OM12D ODCH Fage : 21 Rev. : 3 Table 2.3-7 l Ingestion Dose Factors for Child (ares /pCi ingested) i l l f.n cuY Cl-LLI l MUCLlDE 80Nf Livtt
.......... TNT 4010 al0Nt. LU4G l H 3 40 CATA 2.03t.07 2.01t.0 7 2.031-07 f.93t=0? 2.03t=07 2.03t-07 C 14 1 28t-05 2.428 06 2.428 06 2 42t.06 2.428-06 2.42E-66 2.42t-06 Na 24 5.80E-06 S.00t.06 S.00E-06 9.80L.06 5 00L.06 5.00t-06 1.80t.04 P 32 0.25t=O4 3 16t-05 3. l ti-O h 40 04fA NO Cata NO DATA 2.28t=0S CR ll NO DATA NO Cafa 3.908 09 4.94t=09 1.35t-69 9 02t=09 4.72t-07 PN le 40 CafA 1 076-05 2.stE.06 NO Data 3.00C-06 NO DATA 8.988-06 MN $6 (0 Data 3.34t-07 f . 5 4 t -0 0 NO DATA 4.C4t=07 NO Cata 4.848 0%
- l FE lb l.llt-OS 6.10t.06 1 89E-06 NO 0414 No cafa 3 418 06 l.llt=06 i FL 59 1.65t-Cl 2 6ff=09 1 34C-0$ NO CATA NO C&f4 7.748 06 2.788 05 CD $8 NO Cafa 1.40t.06 S.118 06 NO DATA NO Cafa NO C&T A l.05t=0S CO 60 WO DATA S.29f=06 4.961-05 NO Daft NO Dife NO 0414 2.93t.05 NI 63 5.30f-C4 2.IIF-05 ' t . I J t.0 5 NO DATA NO Cafa N0 DATA l.94C.06 NI el 2.22t-06 2.09F=07 1 221 07 No DAT& NO 0674 No CATA 2.96t-05 l CU 64 No Cafa 2.458-07 1.48t-07 NO DATA 5 921-07 NO DATA l.llt-OS 2N 46 1.371 05 3.65t=0D 2 2 f t.0 5 NO CafA 2. lot-05 NO DATA 6.411 06 2N 69 4.388-00 6.s1[-08 S.tSt-09 NO 0&T4 1.048-08 NO DATA 3.99t-06 et 83 40 DATA NO 04f4 1. 7 8 t -0 7 NO DATA NO CafA NO D&fA LT t-24 SR 84 NO DATA NO DATA 1.98(.07 NO DATA A0 DATA NO Caf& LT t-24 AR 89 NO D&T4 NO DATA 9.12 E -0 9 NO DATA MC Data NO Cafa LT t.24 at 86 NO Cafa 6.70t=0$ 4.12 E -0 5 NO 04f4 NO Cata NO D&T4 4.3tF-06 1
Rt 88 NO DATA 1 90t-07 1. 3 2 t -0 7 40 Daft NO 04f4 NO Cata 9.32t=09 4 At 89 WO Cafa 1.172 07 1.04 t-0 7 40 DATA NO 04Ta NO DATA l.02t=09 i la 89 l.32t-03 NO Caft 3.778 0$ 40 DafA 40 D&TA NO DafA S.llt.09
! SR 90 1.70t=02 40 Daft 4. 3 8 t-0 3 NO 04fa N0 Data NO Cafa 2 298-04 S R 91 2 40f.Ol NO D&TA 9.C t S -0 7 NO cefa NO cat 4 NO DATA S.30t.05 5R,92 9.03t=06 NO CafA 3. ?.-0 7 NO 0414 NO Cata NO Data 1.7tE=04 Y 90 4.llt=04 NO 0474 1 10E-09 NO Cafa NO Data NO Defa 1 17t.04 I Y 9tM 3.02t*10 NC 04f4 1 31E-I l NO Sata NO DefA No DATA T.48t=07 Y 9% 6.028-07 NO 04fA 1 61 f-0 8 40 DATA NO D&fa No DafA 8.028-05 Y 92 3.60t=09 NO 04fA l.018-10 NO D&fa NO Data NO DaT4 l.04E-04 T 93 1 14t=08 NO DATA 3.13 t =10 40 DATA 40 Data ho D414 1.T0t-04 '
2R 95 l.let-Of 2.96t.08 2.I T E -0 8 NO 9&TA 3.6SE*00 NO Cata 2.66t-05 2R 97 4.991-09 1 041-09 5 968 10 NO DATA l.41L.09 NO DATA 1.93t.04 46 95 2.252-08 8.76t.09 6.26t=49 40 Data 3.23t.o9 NO DATA 1.628 05 - l MO 99 NO 0414 f.33t-05 3. 2 9t-0 4 No Data 2.048 05 NO 04f4 1 10E-05 TC 998 9.23t=10 1. Bit-09 3.005-04 40 641A 2.6 3 t -64 9.19t-10 1.03t-06 ! a L 1 i b
OM12D: ODCM Page : 22 Rev. : 3 Table 2.3-7 (cont.) Ingestion Dose Factors for Child (aren/pci ingested) , wucL aut sont Livia f.s00v THyn0:0 st04tf tuas st-tL IClet 1.07t.09 1 828 09 1. 42 g.0 s =0 OATA t . 9 t t .Ge s.92t-10 x.56t-09 aults 7.318 07 no CATA 2. s t t-0 7 =0 DATA l.est.06 nn DATA 1.s9t.0% , nul01 6.45t.0e no Cafa 2.14 t -c e =0 DATA 5.678 07 see DATA 4 21a.05 autes t.tte.05 NO DATA 1 4 6 t=4 6 NO DATA 1. Set.05 NO DATA 1 02t=04 Actlen 5.39t-07 3.64t.07 2. 9 t t -0 7 mn DATA 6.7st-07 WO DATA 4.33t-05 rit25n 1.14t.05 3.09t-06 1 5 2 t.0 6 3.20t.06 =0 cATA =0 DATA 1 104 05 feltin 2.89t=0S 7.74t=06 3.4 At =0 6 6.91t-06 8.248 0% NO DATA 2. 48 05 Tell? 4.7tt-07 1 2fF=07 1. 0 t t-4 7 3.26t-07 1 345-06 #0 DATA 1 048-05 TEt29" 4.07t-05 1.36t-05 7.56t.06 1.lff-05 1.438 04 NO DATA S.94t=05 It!29 1 34t-Of 3.74t=08 3.18 E.0 0 9.568-38 3.92t*07 N0 CAfa I.34t-06 tillta 7.20t.06 2.498 06 2. 6 5 t -0 6 S.12E-06 2.418 05 40 CAfi 1.Olt.04 18131 8 30E-08 2.53t-00 2. 47 E-0 8 6.358-05 2.llt-07 NO D AT A 4.36t-07 fila! lacit=0S 4.47t-06 S.408 06 6.lle=06 4.158-05 'ho DATA 4.50t-05 1 130 2692t-06 S.90t.06 3.04t-0 6 6.50E-04 8.82t.06 NO DATA 2 76t=06 I 131 1 72t=0S 1 73C-05 9.BJE 06 5.72t-03 2.84t. 05 WO DATA 1 545-06 l l 132 0.00E-07 1.478-06 6.76t.07 6.82t=05 2.25t.06 Mn D AT.i 1 73t-06 I I 133 S.12t.06 1.32t=06 2. 7 7 t-0 6 1.36t-03 1 22E.06 NO DATA 2.95t*06 j i 134 4.19t=07 7.788-07 3. l g t -0 7 1.79E-05 1 19t=64 ho DATA 1.16t-07 2.40f=06 i I i 135 1.75t.04 3.Ilt-06 1. 4 9 t.0 6 2 79t-04 4.038 06 WO DATA C1834 2.34L.04 3. 0 4 t- 04 0 1 t'.-4 5 NO CATA 1 19t-04 4.!?t-05 2.07t=O6
, Cll36 2.358-05 6.46t-05 4. t s t.0 5 WO DATA 3.448-05 S.13t=06 2.27t=06 1 ................................. ..........................................
] CSI3F 3.2ft-04 3.13t.04 4.62t 0 5 40 l;a t t 1.024-04 3 67t=0S 1 96t=06 J Cllat 2.201-07 3.17t= O7 ' 2.Olt=4 7 NG DATA 2.238-07 2 40t-08 1.46E.07 r B4139 4.14t-07 2 28t-10 120t 08 40 DAT& 4 934-10 1 898-10 2 39t-05 . . . . . . - . . . ; i Ratte 8. Alt.05 7.20t=08 4 05E.96 =0 DATA 2.37t-00 4.34t=08 4.Ilt=0S , talet 2.00t=07 1. l H = l e 6. b i t 4 9 40 DAfa 9.694 11 6.19t=10 !.let-Of ( j Sal 42 8.fot=00 6.291-tt 4.848-4 9..................... 90 DATA S.098-11 3.70t.lt 1 14t-09
> ................o................
Lal40 1.0lt-08 1.llt-09 1 19t-4 9 se0 DAT A WO Dafe 40 DATA 9.d48-05 I l Lal42 S.74t=10 8.6fF-10 6 2 8t=i t 40 DATA 40 DAf4 NO DATA 3.3tt-05 1 Ctl41 3.97t=08 1 98t.00 2 94t.49 WO DATA 8.68E-09 20 DATA 2 478-05 i j ................................. .......... ...... .......... ......... I Cit 4A 6.99t-09' 3.79t=04 S.498-10 20 DATA t.998 09 NO DATA S llt-On I Cit 44 2.00E-06 6.523-07 1 168 07 40 Otra 3 616-07 me DATA l.70t-04 i i P4l43 3.93t=00 1 10%.04 1.91E -09 te0 leaf A 6.196-09 40 DAT A 4 24t=0S l
) ......... ...................... .......... ....... .......... ..... .. i Pal 44 1.29t-10 1.991-11 6.49E 12 40 DATA 2.118 11 WO DATA O.59t-08 l 12480 tec OATA NDl47 2.19 tate 7.26t-SS t.168 09 No DATA 1.ltt.05 i W 187 4.298-07 2.94f-47 1 148-07 eeU OATA M0 DATA NO DAT A 3.17E-05 J
I NP239 5.Ibt-09 3.17t=10 2.6bt-10 aso DATA 1 098 09 h6 OATA 2 791-05 ; I 1 I I l I
)
1 OM12D: ODCM Page : 23 Rev. : 3 1 1 Table 2.)-8 Ingestion Dose Factors far Infant (area /pci ingested) NuCLIDt 00Nr Livge f . 8 0 pf THYt010 al0Ntv LUNG GI-LLI N 3 k0 CATA 3.08t=07 A . 0 8 t -0 7 3.00f=0? 3.08L-07 3.00t-07 3.08t=07 G to 2.3ff.05 S.C&t=06 S . 0 6 C -0 6 1.06t=06 S.06t-06 S.06F 06 5.06C 06 NA 24 1.Olt.05 1. cit =06 1.011-25 l. Cit =0S l.018-05 1 01t-05 1.01E-05
......................................................................... . i P 32 1.70f=03 1 00!=04 6.59t-05 40 Unf& NO Data NO Daft 2.10E-05 C4 in NO Cata NO Cata 1.413 00 1.20t=09 2 0lt=09 1.79t=08 4.111-07 MN 14 NO Cata 1.991 0) 4. 5 t 8 -0 6 NO Daft 4.418 06 NO Cafa f.3tC-06 NN 96 NO Cafa 8.181 07 1 4 t t.0 7 NU OATA 7.014-07 NO D&TA 7.43t=0S ft il 1.391 0% 0.981 06 2 4Ct.06 NO Cafa NO Data 4.19E-06 1.14U-06 Ft 59 3.08t.0% 5.,82-06 2.12 t =0 h NO Cain 40 Data 1.59t-05 2.lff=0S CD 18 NO Otfa 3.601-06 8.98t-06 NO DATA NO Cafa NC *&fa 4.97C-06 CD to NO Data 1.00t.0% 2. ll t-0 5 NO Data NO Cafa No .74 2.lft-05 NI 63 6.14t=04 3.921 0% 2.20t-05 40 DAfa NO Data NL 04f4 1 95t=06
......................r........... . ............... ............ .......
NI 65 A.70t=06 S.32t=07 2 428-07 NO Data NO Cata NO D&fA 4.053-05 CU 66 NO Cata 6.09t-47 2 82t-07 NO Caf4 1.03t.06 A0 D&fA 1 25t=0S IN el 1.14t-05 6. 'a t t- 0 5 2. 91 t *0 5 NO DATA 1.06t-05 NO CaTA S.33t*05 2N 69 9.33f-08 l.ett-Of 1.2 5 t -0 4 NO Cafa 6.988 08 NS Daft 1.377-05 On 83 NO C&T4 NO DATA 3. 6 3 t -0 7 NO 04f6 NO D&TA NO DATA LT t=24 84 84 NO CafA NO DATA J . 0 2 t -0 7 NO CATA NO DATA NO D&T A LT E-24 et In 40 Data NC Data 1. 9 4 t -0 8 NO Cafa NO O&Ta NO Cafa LT E=24 R$ 86 NO DATA l.10R-04 8.4 0 t -0 5 NO 04f4 NO Cata NO 0674 4.35t=06 dB $8 NO D&fa 4.91(.07 2.?)C-07 NO Caft NO 0674 No 047. 4 85t=07 to 89 NO Cafa 2.06t=07 1.9 7 t *1'i NO Dafa 40 Daft NO D&TA 4.74t.08 la 89 2.518 03 NG 04fa 1.20t.05 NO Cafa NO DATA NO CATA S.16t=05 SR 90 1.858-02 NO CatA 4.7 8 t-0 3 40 Defa NO DATA NO Cafa 2.3tt=04 , SR 91 6c00t=0S ND 0.f4 1. Bit-06 NO Caf4 NO Cafa NO 0414 S.92E-05 la 92 1 92C+0S NO Data 7.13t*01 NO DafA NO DATA NO Cafa 2.07t=04 Y 90 8.691-08 ND cafA 2. 3 3 t *0 9 NO Cafa NO Data 40 D&fa 1.202-04 Y 9tm 8.10E-10 NO Data 2.76 tall 20 DATA ho DATA NO C&fA 2.70t.04 Y 91 1.43E-04 NO Cafa 3.011-08 ho OafA WO Cafa no DATA 0.10E-05 Y 92 7.6SE-09 NO DaT4 2.llt-10 h0 DATA k0 Data ho Data 1.46t=04 Y 93 2.43t-08 NO 04TA 6.62t=10 20 Data NO DATA NO 04f4 1.92t.04 Ik 95 2.06t=07 S.02Ff04 3 56E-0 8 MC Cafa 1.415-08 NO Data 2.let-05 I A 97 l.48t=08 2.54C-09 1 16t-0 9 k0 04fA 2.l61 09 NO Daft 1.62t.04 98 95 4.20E-08 8.71t.08 1.031-08 NO D&?4 1.F4t=08 NO D&fa 1.46t=05
=0 99 NO 04fA 1.40t.05 6. 6 3 t .0 6 NO Data 5.08t=0S ho Oafa 1.ltr.05 TC 99m 1 92t=09 3.96t.09 S.10t .0 0 kn Data 4 26t=08 2 078-09 1.15t-06 l
l l _ _ ._ _ __ ___ ~ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ - . _ . . _ _ . _ _ . _ _ _ _ _ _ _ - . _ _ , _ _ _ _ _ . . _ . . _ _ _ _ _ _ _
n Oh12D ODCH Page : 24 Rev. I 3 l l Table 2.3 8 (Cont.) 1 i Ingestion Dose Factors for Infant (st am/pCi ingested) i i wucLIOt 004E Livia T.800v fnyn010 alO=tv Luns st.tLt scles 2.27t-09 2.s6t-09 2.s In -O s =0 Data 3.40s.0e t.96t.09 4.s6t-07 3.0st 06 =0 Data 1. set.05 nul03 1.ast.06 en cafA 4.95t.07 40 DafA aul0S l.36t.07 =0 Data 4.let-Os wo Safa t.00t 06 wn 04fa S.sta.05 aut06 2.4tt 05 =0 Data 3.0 s t -0 6 wo DATA a. alt.05 no Cafa t.elt.04 4Gilem 9i961.07 7.27t=07 4. Bat-07 41 Data 1 04t-06 No tafa 3.?ft-05 fil25m 2.33E-05 7. 7 9 t-06 3 16 t-0 6 7.04t=06 NO 06f4 NO DATA 1. t f ( *0 5 Tet27m 3.tSt-05 1.948 06 7.0st.06 1 69t.05 1.44t 04 he nata 2.36t-05
) 7t127 1.00E-06 3.358-07 2.tSt-07 0 44t-07 2.448-06 NO DATA 2 10t-05 t Ttl21m 1 00E-04 3 43t-0$ t.54t-05 3.84t-05 2.50t-04 he Data 3.9ft-05 ftt29 2.84t=07 9.79t-08 6.63E-08 2.30t=0? 7.071-07 'NO O&fa 2.27t-05 ftt3tr 1 52t-05 6.12E-06 .l.05t-06 1 24t=05 4.Ilt=0S NO D&fA 1.03t.04 TE131 1 76E-07 6.50t=08 4. 94t-0 8 1.978-07 4.50E-07 NO DATA f.11t-06 TEl32 2.00t-05 1.031 05 9. 6 t t -0 6 1 92f=0s 6.44t-05 NO Ca7A 3. tit-05 i
! 130 6.00E-06 1 321-35 S.301-06 1 40t=03 1.45t=05 NO DAfa 2 01t-06 I
i 131 3.59E-05 4.23t-05 4 46E-OS 1.390-02 4.94t-05 40 CATA 1 918-06 i I 132 1 66t-06 1.37t-06 1 2 0 E -0 6 1.581-04 3.76t.06 No cafA 2.73t-06 I 133 1 25t-05 l.02t-05 S.33t-06 3.3tt-03 2. tot =35 NO CafA 3.00t.06 8 134 8.691-07 1 78t.06 6 338-07 4.158 05 1.99t-06 he Data 1 84f-06 . I 135 3.64t=06 7.24t=06 2 64t=06 6.491-04 0.071-06 NO Cafa 2.628-06 Cll34 3.77t-64 7.03t=04 7 8 0 t =0 S NO 04fA 1.Ilt-04 7.42t-05 1.91E-06 Cll36 4.59t-05 1 35E-04 S.04t-05 NO D&TA l.30E-05 1 10E-05 2.05t=06 4 .. ............................. ...................... ................. Cll37 S.22t-04 6. t tt-04 4.13 t -0 5 NO 04f4 1.44t-04 4.448-05 1.9tt-06 Cll30 4.818-07 7.82t=0F 3. 7 9 t -0 7 40 Defa 3.901-07 6.098-08 1.26E-06
- $4139 3.sti.07 S.04t-10 2. 3 5 t -0 8 40 DATA 3.518-10 3.948-10 9.ltt=0S SA140 1.7 t-04 1.71t-07 s . a 18 -06 40 Data 4.048-08 1.05t 07 4.20t-05 i Ratel 4.25t-07 2.911-10 1. 3 4 t .0 0 kn Otfa 1.754-10 8.7ff=10 9.19t-06 i sat 42 1.04E-07 1.llt-10 9.06t-09 WO DATA 8.91t-11 9 26t-il 7.59t-07 i L*l40 2.ltt-00 0.32t-09 2 14 t =09 NO Safa NO DATA NO DATA 9.77t-06 Ent42 8 10E-09 4.04t=10 9.6ft 1 NO 04T4 40 DafA WO Data 6.86t=05 ,
C(848 7.87t-04 4.00f-00 S . 6 t t -0 9 40 Data 1 48E-04 NO D&fA 2.40t=05 ;
................................. ...................................... . i , Ctt43 4 488-00 9.52t-06 1.128-09 40 DATA 2.96t=09 WO Data 3.73t-05 CFl44 2. 9 8 f- D6 1 228 06 l . 6 7 E -0 7 40 04fa 4.93t=01 NO DATA t.7 t-04 j pal 43 0 13t-04 1.04E-00 4.03t-99 40 DATA l.13t-et WO 04f4 4.29t=0S i
Patan 2.14t-10 1.06t=10 1 388 11 40 Data 3.e46 11 h6 DafA 4.9)t-06 Not47 S.53t-01 S . 6 0 E- 04 3. n e t -0 9 NO Cafa 2.19t=06 20 DATA 3.60E-06 W 887 9 03t-07 6.20t=07 2. l f f -0 F 40 04f4 ho 04fA 40 SATA 3.69t*05 t .. ....... ........... ....... ... ..... ......................... .. NP239 1.Itt-05 9.93t-10 S.618-10 40 DafA t.98t=09 #0 04f4 2 078 05 t
I OM12D ODCM Page : 2S Rev. 3 Table 2.3-9 External Dose Factors for Standing on Contaminated Ground (ares /h per pCi/m2 ) g fetal teor 111S N.3 0.0 0.0 C.14 0.0 0.0 hA.24 2.50t.M 2.90t M !
- p.32 0.0 0.0 l Cr.51 2.irot.10 f.60t.10 1 Mm.54 5.80t.09 6.00t.09 Mn.16 1.10t.08 1.30t.08 Fe.ll 0.0 0.0 Fe.it 8.00t.09 9.40t M J
Co.58 7.00t.09 8.10!.M Co.60 1.70t.M t 00t.08 ns.63 0.0 0.0 nr.65 3.70E*M 4.30t*M cv.g4 1.50t.09 1.70t.09 i
- Zn.65 4.00t 09 4.60t.M 1 In.69 0.0 0.0
! Br 83 4.40t.11 9.Mt.11 i Br 84 1.70t.08 1.40t.08 I Br.05 0.0 0.0 Rb.84 6.30t.10 7.70t.10 b.88 3.60t.09 4.00t.09 1 4 89 1.50t.00 1.00t.00
$r.89 5.60t.13 8.Mt.13 ,
Sr.91 7.1M.09 8.30t.09
$r.92 9.00t.09 1.00t.00 f.90 2.20t.12 2.80t.12 f.91M 3.00!.M 4.40t.09 i f.91 3.40t.11 3.7M.11 i f.92 1.60t.09 1.90t.M Y.93 5.70t.10 7.00t.10 fr 95 S.00t M l.00t 09 tr 97 5.Mt.M 6.4M 09 It.95 5.1M.M 6.0M.00 l t.tM 00 Me.99 1.00t.M < It.9M 9.60( 4 0 1.1M.09 (
l ft.101 f.7 M .09 3.00t.09 i kv.103 3.Mt.00 4.70t.09 L kv.105 4.60t.09 h 6.1M.00 i Rv.108 1.60t.09 1.00t.09 i j AS.11tst 1.00t.00 2.1M.05 t fe.12M 3.90t.11 4.00t.11 fe.127M 1.1M.12 1.3M.I t fe.121 1.00t.11 1.1M.11 f e.itM 7.70t.10 9.00t.10 , ' 1e.139 7.15 10 8.4M.10 I j 1e.131M S.aM.M 9.90t.09 i r 1e.131 2.30(.00 2.60t 06 l
.fe.132 1.?H.00 8.00t.nl ,
I l n l l l l
OM12D: ODCM Page : 26 Rev. : 3 Table 2.3-9 (Cont.) Ey,ternal Dose Factors for Standing on Contaminated Ground (ares /h per PC1/m2 ) fetal Beds B,f,g h 1 1 130 1.40t.08 1.700 08 I 131 2.00( 00 3.40t.09 I 132 1.tM.00 2.00(.00 1 133 3.?M.M 4.Mt.0g I.1 H 1.60t.08 1.got.08 I.135 1.tM.00 1.40t.00 Ct.134 1. 2M.00 1. 4M.08 Cs.134 1.60t.00 1.?M.08 Ct.137 4.20t.09 4.901 00 3 C t.138 2.10t.08 2.40t.00 Ba.139 2.40t.09 2 ?M.0g 84 140 2.10t.09 2. 40t.M
, 84 141 4.30t.09 4.90(.09 l 64 142 7.h ; if J.Ori.00 Lt.140 1.50t 08 1.1J.08 La.142 1,50t,.00 1.00t.08 Co.141 5.50t.10 6.tM 10 Co.143 2.20t.09 2.50t.09 Co.144 3.20t.10 3.?N.10 Pr.143 0.0 0.0 l
Pr.144 2.00t.10 2.30C.10 N4 147 1.00t.09 1.70t.09 v.187 3.10t.09 3.60t.09 hp.239 9. lot.10 1.1M.09 j i j i I .i - i l 1 l i
\ ,
I l
I OM12D: ODCM
- Page
- 27 Rev. :
3 Table 2.3-10 , Liquid Effluent Dilution Factors (M ) p Maximum Individual Dilution Factoy l M , P Pathway Location L Potable Vater Ingestion 3.9 mile VSV of alte 31.5 t 4 Fresh Vater Fish Ingestion Near Discharge Structure 10.9 l Shoreline Exposure 0.7 mile ENE of Site 14.5 Population Dose Dilution Factors M , Pathvay E Location Potable Vater Ingestion Popdation Veighted Average 316 Fresh Vater Fish Ingestion Hear Discharge Structure 10.9 I dhoreline Exposure 7.7 mile VSV of site 162
' Table 2.3-11 ; i Transit Times Required for Nuclides to Reach the' I Point ofExposure(ty Maximum Exposed Average Exposed 1
) Individual Individual
- l Eventual transit time for water ingestion 12 h 24 h l l
Eventual transit time for fish ingestion 24 h 168 h l Eventual transit tiee for shore exposure 0h 0h J
*for total population and average individual dose calculations ,
\
l , 1 1 l k 1
OM12D ODCM Page : 28 Rev. 3 Table 2.3-12 Usage Factors (U,pl Maximum Exposed Average Exposed Individual Individual
- l Vater ingestion (1/yr) Adult 730 370 i
i Vater ingestion (1/yr) Teen 510 260 Vater ingestion (1/yr) Child 510 260 , Vater ingestion (1/yr) Infant 330 -- Fresh vater fish ingestion (kg/yr) Adult 21 6.9 1 Fresh water fish ingestion (kg/yr) Teen 16 5.2 Fresh water fish ingestion (kg/yr) Child 6.9 2.2 Fresh water fish ingestion (kg/yr) Infant -- -- Shore exposure (h/yr) Adult 12 8.3 Shore exposure (h/yr) Teen 67 47 Shore exposure (h/yr) Child 14 9.5 a f, Shore exposure (h/yr) Infant -- -- ' l
*for total population and average individual dose calculations ;
l j i . t 1 i 1 l N l 1 ;
OM12D: ODCM Page : 29 i Rev. : 3 i 3.0 GASEOUS EFFLUENTS There are four environmental release points for gaseous effluents ; used for Unit 1 operation of the Perry Nuclear Power Plants Nester : Bay / Turbine Building Vent, Offgas Vent Pipe, Unit i Vent, and Unit 2 Vents. (See Figure 3.0-1). The Unit 1 and Unit 2 Vents are located on the top of the Intermediate Build'r.3, Elevation 753'9". The Heater Bay / Turbine Building Vent is located on the top of the Heater Bay Builidng, Elevation 722'0". The offgas Vent Pipe is located on the top of the Offgas Building, Elevation 723'0". Site ground level ; elevation is 620'0". Radiological releases from each vent are i monitored by a noble gas radiation monitor. : i ' All gaseous effluent releases from PNPP will be continuous releases. ' containment /dryvell purges and vents vill be considered periods of increased radiological release as they are vented through the Unit 1
- Vent concurrent with normal, continuous releases. All releases are considered to be long-term, i.e., greater than 500 hours per year, ;
and ground level. ] 0 Y i i t 0
- r i
! I J l 1 ) ' i I I J t I l t l t ) i l e i i
. ~ ..
A Am.A
.m. x
.. C , I @ @
0
-me
- C - UNIT 1 VENT
!(tikiki.D.
_, (140,000 cfm)
.m .. ; > g< ,
.__g ._ s-a
-ed-o
_a-r- cE-Q s= [1trd qa c
.=.-
m-. m 9 p ..
,~ = n N,W - J)Q' I.'g .:.r'.*]. - a.:. .:= ,:. '
8*
- ' ~ ~
l -.
..~ ~ . .
Wm g .h.. .6% ,t.v22. [ .. _ , .i . . . g ,. ~. .
;' ' l l >G O ~~
m OO e ~. 3 '* io a - 4 -- hE.- l 7
-<Er-@ ia -
J . h_. % a - F T. -.-.ll-j!is : 2.- ;1.:: -(-:i~@
~
l F i ' i~ IA!!altal tal t! MM BS p:g em "t-g p- m.. (.D' (Dl n3 n 5 ti eus e s -, e ti v ., r r i
;. , .e..
;21-fy __]- 1- ~
s-l. --.{- ** l
= _ - -s.- i
._.__...._2.____
. .m ewe . . 54 e .em. "
.= =
. .
- gem
- - + - - - - - - ~ . - . . . . . , _ _ - - -
c,_ .. .-
, OFFGAS VENT PIPE (19,000 cfa) ,
J UNIT 2 VENT j ht i )=. _- (47,000 cfm) p p...
+'**~
-Y _, p SI a7-
~
0 -- APERTURE CARD HEATER BAY / TURBINE BLDG. (400,000/ f... ' M N AVE N Aperture L,ard 220,000 cfa) M [ E 3' 7 rigure 3.0-1 ,' GASEOUS EFFLUENT SYSTEM
,1 TLOW DIAGRAM 'i J
i l ; l o ji i 4 i y .... 3E ,o n, n D I I "s a g 5
,' ' ' l .
I Lyg c-D- ) 49
, yea 1 i E i "YQ::
qqupcGoost-ol , _ _. _ ____- i
OH12D ODCH Page : 31 Rev. 3 3.1 Monitor Alarm Setpoint Determination The following calculation methods provide a means of determining the high alarm setpoint (HSP) and the alert setpoint (ASP) to ensure compliance with 10CPR20 dose rate limits to areas at or beyond the site boundary for the following noble gas monitors:
- 1. Heater Bay / Turbine Building Vent radiaton monitor (1D17K0856)
- 2. Offgas Vent Pipe radiation monitor (1D17K0836)
- 3. Unit 1 Vent radiation monitor (1D17K0786)
- 4. Unit 2 Vent radiation monitor (2D17K0786).
The Unit 2 Vent Radiation Monitor is incit ded for the operation of i Unit 1 of the Perry Nuclear Power Plant because the second train of the Unit 1 Annulus Exhaust and the Control Complex and Intereediate Building ventilations are exhausted through the Unit 2 Vent. The High Alarm Setpoint (HSP) for each release point radiation a monitor vill be set at 70 percent of the 10CFR20 dose rate limits and the Alert Setpoint (ASP) vill be set at 10 percent of these limits. This procedure determines the monitor alarm setpoints that indicate if the dose rate beyond the site boundary due to noble gas radio- l nuclides in gaseous effluent released from the site exceeds 500 l mrem / year to the total body or 3000 arem/ year to the skin. l NOTE: The values of 70 percent for the HSP and 10 percent for I j the ASP are set as fractions of the total activity that l l may be released via the sonitored pathvays to ensure that t the site boundary dose rate limits are not exceeded. Any 1 single ASP can be exceeded without the 10CFR20 limits ! j being exceeded. Upon receipt of an alert alera a sample l from the alarming effluent path vill be obtained and , i analyzed. If two or more monitors exceed the ASP, or any ' one monitor exceeds the NSP, it is possible that the limits have been exceeded. In this case all four effluent paths vill be sampled and analyzed. Appropriate action vill be teken to limit gaseous releases to belov 10CPR20 limits. NOTE: If an RSP or two or more ASP's continue to be exceeded, verification shall be made at least once per 4 hours via ! the gaseous e!!1uent radiation monitors that plant i releases are belov Technical Specification 3.11.2.1 dose i rate limits, and sampling and analysis shall be performed i en the four gaseous effluent release points at least once
! per 12 hours.
4
OM12D: ODCM Page : 32 j Rev. 3 3.1.1 Determination of the "Mix" (Noble cas Radionuclide Composition) ; i of the Caseous Effluent
- a. The gaseous source terms that are representative of the "mix" of the gaseous effluent are determined. Caseous source terms are the concentrations of the noble gas ,
i radionuclides in the effluent as determined by analysis of the various sources of gaseous effluents. During the early period of plant operation, before a suffielent
- operatter.a1 effluent source term data base has been obtained, source terms will be those generated by the CALE !
l, code, Revision 0 for PNPP (FSAR Tables 11.3-9 and ; i 11.3-10).
; b. Determination of the fraction of the total radioactivity i in the gaseous effluent for each nobit
- gas radionuclide in
- the gaseous effluent.
1 ; A i (3.1-1) j S g.
! I ^1 I
1 1 1 Where: l Sg the fraction of the total for radionuelfde "i" in t'.e effluent: Ag . the activity of radionuclide "1" in the gaseous effluent. ? I NOTE: If the activity of a noble gas radionuclide is below the j lover limit of detection the noble gas radionuelide is not j included as a source term in this setpoint calculation. 3.1.2 Determination of the Maximum Acceptable Total Activity Release ! Rate of Noble Gas Radionuclides in Caseous Effluent Based on j Total Body Dose Rate Limit I 1 500 (3.1-2) Ob
- WO) iI (K i )(8 1) r i
b re Ob = the maximum acceptable total activity release rate l of all noble gas radionuclides in the effluent (for ! total body exposure), in pCi/s j Kg the total body dose factor for a semi-infinite f cloud of 2radionuclide "1" (includes the attenuation ; l 1 of5g/ga of tissue) f rom Table 3.1-1, in (aren/yr)/ ' (uci/m ): i 1
. - - - _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ - - - _ _ . _ _ - _ _ _ . - - _ - _ _ _ _ _ - - _ - _ _ _ - - ___-_-__.______A
OM12D ODCM l Fage : 33 Rev. 3 the fraction of the total for radionuclide "i", as S g= per equation 3.1.11 X/0 = the highest annual average relative dispersion facjorforareasatthesiteboundary.5.8x10~6 s/n (from Appendix A, NE direction at the site boundary) NOTE: The dispersion parameters (X/0) used in these calculations are the highest calculated site boundt:y values for any of the land-based sectors only. At FNPF the site boundary locations ir the following sectors are totally over vater: N. NNE, NNV, NV, V, VNV. 500 = the total body dose rate limit, in arem/yr. 3.1.3 Determination of the Maximum Acceptable Total Activity Release Rate of Noble Gas Radionuclides in Gaseous Effluent Based on Skin Dose Rate Limit 3000 (3.1-3) 0, = iT/Q) I (Lg + 1.11 Mg ) (Sg ) i Vhere: Q, the maximum acceptable total activity release rate of all noble gas radionuclides in the effluent (for skin exposure), in WC1/s Ig the beta skin dose factor for a semi-infinite cloud of radionuclide "1" (includes attenuation by the 3 , outer "dead" layer of skin), in (area /yr)/(vCi/m )s Mg the gamma air dose factor for a uniform semi-igfinite i cloud of radionuclide "1", in (arad/yr)/(9C1/n ) Sg the fraction of the total for radionuclide '1", per Equation 3.1.11 X/0 = the highest annua 1 ""$8e relative dispersion factor . 5.8 x 10'6 a/a , per Equation 3.1-2 i 1.11 = the air dose to tissue dose equivalent conversion factor, in ares /arad: 3000 = the skin dose rate limit, in Jres/yr. ! l (L g 4 1.11 Mg ) values are shown in Table 3.1-1. 1 j
OM120: ODCM Page : 34 Rev. : 3 3.1.4 Determination of the Maximum Acceptable Total Radioactivity Concentration of all Noble Gas Radionuclides in the Gaseous Effluent (2.12 x 10'3)(0 ) C t" I*~ l Vhere C the maximum acceptable total radioactivity t = concentration of all noble gas radionuclides in the effluent, in WC1/cci f = the flov rate for the release point f5*th' respective flow rate recorders, in ft / ming i NOTE: Design flov rate may be used in lieu of actual flov rate. These design flov rtte values incorporate a 10% flow rate inaccuracy corr.ection. Release Path Flov Rate (cfm)
- Heater Bay / Turbine Buildia.g Vent 400,000 (sue.mer) ,
220.000 (vinter)
- Offgas Vent Pipe 19.000
- Unit 1 Vent 140,000
- Unit 2 Vent 47,000 O the smaller of O and 0 , calculated in equations t = 3.1-2 and 3.1-3,brespeclively,inWCi/s 2.12 x 10'3 .
th3conversionfactortoconvert(uct/s) ft / min) to WCi/cc. 3.1.5 Determination of the Maximum Acceptable Monitor Count Rate Above Background Attributed to Noble Gas Radionuclides CR, = (0.8) (Ct ) (E,) (3.1-5) Where CR* = the calculated monitor count rate above background attributed to noble gas radionuclides. in epm
OM12D ODCM Page : 35 Rev. : 3 C the maximum acceptable radioactivity concentration, t per equation 3.1-4, in WC17eci r the detector efficiency of the monitor for the "mix" ' E" of noble gas radionuclides in the effluent, in cpa/(uCi/cc):
= the total WCi/cc concentration divided into the net monitor count rate taken at the time the sample was taken during the early period of operation, before a sufficient operational effluent source term data base has been obtained, the value vill be calculated using monitor calibration data:
4 0.8 an engineering safety factor. 3.1.5.1 Determination of the Monitor High Alarm Setpoint f HSP = (0.70)(CR ) + BG (3.1-6) l l Where HSP = the high alarm setpoint (including background), in cpm; BG the background count rate due to internal contamination and radiation levels in the area in which the monitor is installed when the monitor chamber is filled with uncontaminated air, in epm; j CR = the calculated monitor net count rate, per C equation 3.1-5, in epm; a j 0.70 the fraction of the maximum acceptable activity , i that may be released from the vent to ensure that the site boundary dose rate limits are not i
- exceeded during concurrent releases from several
pathways. ; 3.1.5.2 Determination of the Monitor Alert Setpoint ; ASP = (0.10)(CRg ) + BG (3.1-7) Where ; a
; ASP = the alert setpoint (including background), '
l in cpe
- BG = the background count rate due to internal
- contamination and radiation levels in the area I in which the monitor is installed when the monitor chamber is filled with uncontaminated air, in eps:
l
OM12D ODCM Page : 36 Rev. : 3 CR the calculated monitor net count rate, per e equation 3.1-5, in cpe 0.10 the fraction of the maximum acceptable activity that may be released from the vent to ensure that the site boundary dose rate limits are not exceeded during concurrent releases from several pathways. l t i 1 1 r
l OM12D ODCM Page : 37 Rev. t 3 Table 3.1-1 , Total Body and Skin Dose Factors Total Body Total Skin Dose Tsetor Dose Factor (L 1.11 M Radionuclide (Kg )(nren/yr/uct/m 3) (arek+/yr/ucifm)3) l Kr-83m 7.56E-02 2.14E.01 [ Kr-85m 1.17E+03 2.82E+03 Kr-85 1.61E+01 1.36E.03 Kr-87 5.92E.03 1.66E.04 Kr-88 1 47E.04 1.92E.04 Kr-89 1.66E.04 2.93E.04 ! Xe-131m 9.15E.01 6.49E.02 Xe-133m 2.51E.02 1.36E.03 1 , Xe-133 2.94E.02 6.97E.02 7 Xe-135m 3.22E.03 4.44E.03 Xe-135 1.81E.03 3.99E+03 1 Xe-137 1.42E.03 1.39E.04 , j Xe-138 8.83E.03 1.44E+04
- Ar-41 8.84E.03 1.30E.04 ;
i i T h 9 4 P 1 i 1 I 1 : i I i 1 1 I
0H12Di ODCM Page 38 Rev. 3 3.2 Compliance Vith 10CFR20 - Caseous Effluent Dose Rate Dose rates resulting from the release of noble gases, radiolodines, tritium, and radionuclides in particulate form must be calculated to show compliance with 10CFR20. The limits of 10CFR20 are conservatively applied for the release period at the controlling location. 3.2.1 Noble Cases The dose rate in unrestricted areas resulting from noble gas effluents is limited, by PNPP Technical Specifications, to 500 arem/yr to the total body and 3000 arem/yr to the skin. Only the external dose pathway vill be considered for noble gases. Because all gaseous effluent releases from PNPP are considered , ground level, the controlling location for these dose rate limits is the site boundary location (see Pigure 3.2-1) with the highest relative dispersion f actor (X/0). (See Appendix A l for elaboration on atmospheric dispersion.) 1 l The alarm setpoint determinations discussed in the previous section should ensure compliance with these dose rate limits. However, if any one high alarm or two or more alert alarms occur, the dose rates in unrestricted areas resulting from the release of noble gas radionuclides from all vents vill be calculated. The calculations vill be based on the results of analyses obtained pursuant to the PNPP Technical i < Specifications. 3.2.2 Radionuclides, Particulates, and Other Radionuclides 1 The dose rate in unrestricted areas resulting from the release 4 of iodine-13), iodine-133, tritium, and all radionuclides in j particulate form with half-lives greater than eight days is I limited, by FNPP Technical Specifications, to 1500 arem/yr to l any organ. The calculation of dose rate from these radio- ' nuclides vill be performed veekly based on results of analyses i obtained persuant to those Technical Specificatons. The l controlling location for this limit is the location of'the d highest relative deposition (D/0) for the period of release as well as the actual receptor pathway. The receptor pathway > locations vill be reviewed once per year following the performance of the Land Use Census to include consideration of nearest residences, garden, mad farm animal locations in each ! sector. i
\ l I
1 i l
OM12D: ODCM Page : 32 Rev. : 3 3.1.1 Determination of the "Mix" (Noble Ga.s Radionuclide Composition) of the Gaseous Effluent
- a. The gaseous source terms that are representative of the "mix" of the gaseous effluent are determin9d. Gaseous source terms are the concentrations of the noble gas radionuclides in the effluent as determined by analysis of the various sources of gaseous offluents. During the early period of plant operation, before a sufficient operational effluent source term data base has been obtained, source terms vill be those generated by the GALE code, Revision 0 for PNPP (FSAR Tables 11.3-9 and 11.3-10).
- b. Determination of the fraction of the total radioactivity u in the gaseous effluent for each noble
- gas radionuclide in the gaseous effluent.
Ag S g- (3.1-1) ! IA g i vheres Sg = the fraction of the total for radionuclide "1" in the effluents I Ag - the activity of radionuclide "i" in the gaseous q effluent. , j 1 NOTE: If the activity of a noble gas radionuclide is belov the lover limit of detection the noble gas radionuelide is not included as a source term in this setpoint calculation. 3.1.2 Determination of the Maximum Acceptable Total Activity Release Rate of Noble Gas Radionuclides in Gaseous Effluent Based on Total Body Dose Rate Limit 500 (3.1-2) ] Oh = (X/0) I (Kg )($g) j i Vhere Ob = the maximum acceptable total activity release rate of all noble gas radionuclidus in the effluent (for total body exposure), in pCi/s 1 l Kg . the total body dose factor for a semi-infinite I cloud of2 radionuclide "i" (includes the attenuation
- of5g/gm of tissue) from Table 3.1-1, in (aren/yr)/
I (UCi/m )
OM12D: ODCM Page : 33 Rev. i 3 the fraction of the total for radionuclide "i", as , S g= ', per equation 3.1.11 , X/0 = the highest annual average relative dispersion facjorforareasatthesiteboundary-5.8x10~6 , s/n (from Appendix A, NE direction at the site , boundary): i NOTE: The dispersion parameters (X/0) used in these ! calculations are the highest calculated site boundary values for any of the land-based i sectors only. At FNPF the site boundary . loco ions in the following sectors are totally ! over water N, NNE, NNV, NV, V, VNV. 500 . the total body dose rate limit, in aren/yr. [ 3.1.3 Determination of the Maximum Acceptable Total Activity Release ; Rate of Noble Gas Radionuclides in Gaseous Effluent Based on l Skin Dose Rate Limit i 3000 (3.1-3) 0, = (X/0) I (Lg + 1.11 Mg ) (Sg ) ! i l l j Vhere 0, the maximum acceptable tots.1 activity release rate ;
; of all noble gas radionuelides in the effluent (for J skin exposure), in DCi/sl L
3 the beta skin dose factor for a semi-infinite cloud l of radionuclide "i" (includes attenuation by the 3 i outer "dead" layer of skin), in (aren/yr)/(uci/m ): 1 4 Mg cloud of radionuclide "i", in (arad/yr)/(WC1/m ):thesammaairdo; i
- sg the fraction of the total for radionuclide "i", per Equation 3.1.1 l -
X/0.thehighestannua1***'$gerelativedispersion factor . 5.8 x 10'6 s/n , per Equation 3.1 2 . I 1.11 . the air dose to tissue dose equivalent conversion l factor, in aren/aradt I l 3000 the skin dose rate limit, in eres/yr. ) (L g + 1.11 Mg ) values are shown in Table 3.1-1. 1 i
OM12D ODCM Page : 34 Rev. : 3 3.1.4 Determination of the Maximum Acceptable Total Radioactivity i Concentration of all Noble Gas Radionuclides in the Caseous
- Effluent (2.12 x 10'3)(0 )
C t" ('~ f Vhere C the maximum acceptable total radioactivity t concentration of all noble gas radionuclides in the , effluent, in 9Ci/cci the flov rate for the release point f om the f respective flov rate recorders, in it /3min: NOTE: Design flow rate may be used in lieu of actual flow rate. These design flov rate values incorporate a 10% flov ate , inaccuracy corr.eetion. Release Fath Flov Rate (cfm) ,
- Heater Bay / Turbine Butiding Vent 400,000 (summer) i 220,000 (vinter) .
l l
- Offgas Vent Pipe 19,000 l
l - Unit 1 Vent 140,000
- Unit 2 Vent 47,000 j O the smaller of O and 0 , calculated in equations t = 3.1-2 and 3.1-3,brespeclively,inWC1/s i I
2.12 x 10'3 th!"''8"f*ctrt ft / min) to WC1/cc.
"' (SC)
3.1.5 Determination of the Maximum Acceptable Monitor Count Rate Above Background Attributed to Noble cas Radionuclides CR e
- (0.8) (Ct ) (Em) (3.1-5) [ ! Where:
1' CR* = the calculated monitor count rate above background ! q attributed to noble gas radionuclides, in epm; i 4 l I
t i 0M12D ODCM Page : 35 Rev. 3 C the maximum acceptable radioactivity concentration, [ t = per equation 3.1-4, in WC1'/cci E" = the detector efficiency of the monitor for the "mix" of noble gas radionuclides in the effluent, in cps /(uC1/cc):
= the total WC1/cc concentration divided into the net monitor count rate taken at the time the sample was takent during the early period of operation, before a sufficient operational effluent source term data base has been obtained, the value vill be calculated using monitor calibration detal 0.8 = an engineering safety factor.
3.1.5.1 Determination of the Monitor High Alarm Setpoint HSP = (0.70)(CR,) + BG (3.1-6) 1 Vhere: 1 HSP = the high alarm setpoint (including background), in cpm
- BG = the background count rate due to internal contumination and radiation 1cvels in the area in which the monitor is installed when the monitor chamber is filled with uncontaminated air, in cpm i CR = the calculated monitor net count rate, per e
equation 3.1-5, in eps: i j 0.70 = the fraction of the maximum acceptable activity l that may be released from the vent to ensure that i the site boundary dose rate limits are not
; exceeded during concurrent releases from several pathways.
3.1.5.2 Determination of the Monitor Alert Setpoint ASP = (0.10)(CR,) + BG (3.1 7) Where: l ASP = the alert setpoint (including background), in cpal BG = the background count rate due to internal
; contamination and radiation levels in the area l in which the monitor is installed when the l monitor chamber is filled with uncontaminated air, in epm; l
i
r i 0H12D ODCM i Page 36 i Rev. : 3 i CR* = the calculated monitor net count rate, per l equation 3.1-5, in eps: , i , O.10 the fraction of the maximum acceptable activity that may be released from the vent to l ensure that the site boundary dose rate limits l 1 are not exceeded during concurrent releases ; ) from several pathways. t 4 ! r I I t i s I h 1 a d f a >
! i ! l l;
e i i , 1 ! l a I I
?
l
OM12D: ODCM Page : 37 Rev. : 3 Table 3.1-1 Total Body and skin Dose Factors Total Body Total Skin Oose Factor Dose Factor (L 1.11 M Radionuclide (Kg )(nren/yr/uct/m 3) (arek+/yr/ucif m)3)
,.o .
Kr-83m 7.56E-02 2.14E 01 Kr-85m 1.17E+03 2.82E+03 Kr-85 1.61E+01 1.36t+03 Kr-87 5.92E+03 1.f6E+04 Kr-88 1.47E+04 1.92E+04 Kr-89 1.662+04 2.93E+04 Xe-131m 9.15E+01 6.49E+02 Xe-133m 2.51E+0F 1.36E 03 Xe-133 2.94E+02 6.9/E+02 Xe-135m 3.12E+03 4.44E+03 Xe-135 1.81:+03 3.99E+03 Xe-137 1.42E+03 1.39E+04 X4-138 8.83E+03 1.44E+04 Ar-41 8.84E+03 1.30E+04
l l 1 OH12D: ODCH l Page : 38 Rev. : 3 3.2 Compliance Vith 10CFR20 - Gaseous Effluent Dose Rate Dose rates restilting from the release of noble gases, radioiodines, tritium, and radionuclides in particulate form Must be calculated to show compliance with 10CFR20. The limits of 10CFR20 are - conservatively applied for the release period at the controlling location. 3.2.1 Noble Cases The dose rate in unrestricted areas resulting from noble gas effluents is limited, by PNFP Technical Specifications, to 500 arem/yr to the total body and 3000 arem/yr to the skin. Only the external dose pathvay vill be considered for noble gases. Because all gaseous effluent releases from PNPP are considered ground level, the controlling location for these dose rate limits is the site boundary location (see Figure 3.2-1) with the highest relative dispersion factor (X/0). (See Appendix A for elaboration on atmospheric dispersion.) The alarm setpoint determinations discussed in the previous section should ensure compliance with thesu dose rate limits. However, if any one high alarm or two or more alert alarms occur, the dose rates in unrestricted arean resulting from the release of rioble gas radionuclides from all vents vill be calculated. The calculations vill be based on the results of analyses obtained pursuant to the PNPP Technical Specifications. 3.2.2 Radionuclides, Particulates, and Other Radionuclides The dose rate in unrestricted areas resulting from the release of iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than eight days is limited, by PNPP Technical Specifications, to 1500 mrem /yr to any organ. The calculation of dose rcte from these radio-nuclidos vill be performed veekly based on results of analyses obtained persuant to those Technical Specificatons. The controlling location for this limit is the location of the highest relative deposition (D/0) for the period of release as , the actual receptor pathvay. The receptor pathway vel. '.s locttions vill be reviewed once per year following the per!,rmance of the Land Use Cersus to include consideration cf nearest residences, garden, and farm animal locations in each sector.
. _ _ _ _ . _ . _ . .m. _ ., _ _ , , ,
OM12D: CDCM Page : 39 Rev. : 3 3.2.3 Dose Rate Calculations The following is the equation used to calculate the dose rate resultant from the release of radioactive materials in gaseout effluents to areas at or beyond the site boundary for the purpose of shoving compliance with PNPP Technical Specification as related to 10CFR20. 1 D,)p = (3.15 x 10 ) (X/0 or D/0) I (DF,g)p) (Qg ) (3.2-1) Vhere D,)p = "the organ "j" dose "p",rate as a function of age group a" and pathvay in arem/yri DF,g)P ="a", the dose factor for organ type "j", age group pathvay "p" for isotope "i" (see Tables 3.2-1 through 3.2-3): units and equations used (equations 3.2-2 through 3.2-6) are provided later in this sections X/0 or D/0 = the normal or depletgd relative dispersion f(D/0), actorin(X/0)2,in m' at s/m , or relative the receptor distance deposition (see Appendix A): 3.15 x 101 = the s. . version factor to convert (mrem
- uCi}l(Ci
- s) to mrem /yr; O the annual average release rate of isotope "i", in g = uCi/s
- (472)(Cg )(f)
Vhere l Cg = the concentration of radionuclide "i" in the gaseous effluent, in uCi/cci f=thegaseouseffluentflowrateduringthe release, in ft / mini 3 472 - the conversion factor (cc/ft )/(s/ min). The following relationships are used to derive the dose factors (DF for noble gases, tritium, radioiodirais and parikd8)1stesusedinequation3.2-1. l l 1 1
OM12D: ODCH Page : 40 Rev. 3
- s. Total Body Dose Factors from Exposure to a Semi-Inifinite Plume -
T DF g = (SF ) IX i) IDFBg ) (3.2-2) Where T DFg - the total body factor due to immersion in a semi-infigitecloudofradionuclide"1",in (arem
- m )/(Ci
- s):
DFB 3 = the total body gamma dose factor for a semi-infinitecloudofradionuclige"i"which includes the attenuation of 5g/cm of31ssue from Table 3.2-4, in mrem /yr per pCi/m S the attenuation factor that accounts for the F = dose reduction due to the shielding provided by residential structures, optional, dimensionless: maximum exposed individual = 0.7, population dose 0.5 (Regulatory Guide 1.109): I X g="theannualaveragg)concentrationofradionuclide i" in air (pCi/m , for a gnit release (Ci/yr) and3 a unit X/0 (8/m ), in (pCi/m5*** )/ (Ci/yr)(s/m ).
- b. Skin Dose Factors for Exposure to a Semi-Infinite Plume S y DFg = (Xg) ((1.11) (Sp ) (DFg) + (DFSg )) (3.2-3)
Vhere S DFg = the skin doce factor due to immersion in a semi-infigitecloudofradionuclide"i",in (ares
- a )/ (Ci
- s):
Y DF g the gamma air dose factor fer a uniform semi-infinite cloud of radionucigde "i", from Table 3.2-4, in arad/yr per pCi/m i
, DFSg = the beta rkin dose factor for a semi-infinite c.vud of radionuclide "i" (includes attenuation by the outer "dead" layer of skin)3 from Table 3.2-4 in stem /yr per pCi/m
OM12D: ODCt' Page : 41 Rev. 3 Sp the attenuation factor that accounts for the dose reduction due to,the shielding provided by residential structures, optional, dimensionless maximum exposed individual - 0.7, population dose - 0.5 (Kegulatory (,uide 1.109); Xg = "the annual e't&rsag concentration of radionuclide i" in air (pci/m'), foragnitreleaserate
- (Ci/yrg)andaunitXf0(s/m),in (pCi/m /t;Ci/yr)(s/m );
1.11 - the air dose to tissue dose equivalent conversion factor, in ares /arad.
- c. Dose Factors from External Irradiation from Radionuclides Deposited onto the Ground Surface G G ,
I3'2-4) DFg ) - (8760) (Cg ) (DFGg )) (SF ) Vhere G the dose factor for radionuclide "1" to organ DFg ) "j" resulting from exposure to radionuclides deposited2 nto the ground surface, in (mrem
- m )/Cil G
2 Cg = the ground plane concentration (pci/m ) og radionuclide "i" for a unit release rate (Ci/
),
andaunig)D/0,relatiyegoundaeposition in (pci/m /(Ci/yr)(m- ); DFG g ) - the open field ground plane dose conversion f actor for organ "j" f rom radionuclide 2 "I"' ' from Table 3.2-5, in mrum/yr per pCi/m S, the attenuation factor that accounts for the
- dose reduction due to the shielding provided by residential structures, optional, dimension 1t;ssi maximum exposed individual 0.7, population ;
dose - 0.5 (Regulatory Guide 1.109); 8760 the number of hours in a year.
- d. Dose Factors from Inhalation'of Radionuclides in Air l
A DF,g) = (DFA,q) (R,) (Xg) (3.2-5) l
4 OM12D: ODCM Page : 42 Rev. : 3 Where:
~
A s DF g "the dose factor for radionuclide "i" "a"todue organ j" of an individual in age group 3 toinhalation,in(arem*m)/(Ci*sg/s)); [ -- equivalent to (arem/yr)(yr/C1)(m DFA"Id e"i", the organ inhalation "j", and dose factor age groupfor "a"radionuclide (the value for skin is assumed to be 0), from Tables 3.2-6 through 3.2-9, in arem/pcil 18 1" '8* R*=theannuelairintakeforindividu!yri group "a", from Table 3.2-14, in a / Xg "the 1" inannual averag3) air (pci/m concentration of radionuclide
,foragnitreleasegate (Ci/yr) and3a unit X/0 (s/m ), in (pCi/m )/
(C1/yr)(s/m ).
- e. Dose Factors from the Ingestion of Atmospherically Released Radionuclides in Food D F F L L M M DF,g) - DFI,q [(U,) (Cg ) + (U,)(f g)(C g) + (U,)(Cg ) +
V V (U,)(fy)(Cg )] (3.2-6) Vhere: D DF"Id = "the dose factor for radionuclide "i" to organ j" of an individual in age group "a" from the ingestion of meat, leafy vegetables, allk, and produce (non-leafy veggtables, . or in ! fruits, the cases andofgrains) H-3 andinC-14 (arem
- m )/C1,3)/
in (arem *m (Ci
- s):
F L M V C,C,C,Cg g g g "the concentrations of radionucliae i" in seat leafy vegetables, milk, and produce, respectively (pci/kg i or pCi/1) for a unit release rate (C1/yr) and a unit D/ , relative grounddeposition(m'g),orin cases of H-3 and C-14, a unit X/0, I relajiveground-levelconcentgation (s/m),in(pci/kg)(Ci/gr)(m-) or(pCi/kg)/(Ci/yg()s/m)or or (pci/1)/(Ci/yr)(mj/); (pci/1)(yr/C1)(s/n
l OM12D ODCM Page : 43 Rev. : 3 DFI,g) "the ingestion dose factor for radionuclide i", organ "j", and age group "a", from Tables 3.2-10 through 3.2-13, in arem/pCil f,f g y the respective fractions of the ingestion rates of leafy vegetables and produce that are produced in the garden of interest, 1.0 and 0.76 respectively (Regulatory Guide 1.109) F L M V U", U*, U* , U* - the annual intake (usage) of meat, 1eafy vegetables, milk, and produce respectively, for individun1s in ate group "a", from Table 3.2-14, in kg.-yr or 1/yr. l 1 l
OM12D: ODCH Page : 44 Rev. : 3-Table 3.2-1 Organ used for Gaseous Effluent Do'se Calculations s
- 1. Bone x
- 2. GI Tract ,
- 3. Kidney
- 4. Liver
- 5. Lung
- 6. Thyroid
- 7. Total Body
- 8. Skin Table 3.2-2 Age Groups Used for Gaseous Effluent Dose Calculations
- 1. Adult (17 yr and older)
- 2. Teen (11-17 yr)
- 3. Child (1-11 yr)
- 4. Infant (0-1 yr)
I A r I 1 l
'a OM12D ' ODCM
- Page : 45 Rev. s' 3 Table 3.2-3 l
Gaseous Effluent Dose Pathways .
- 1. Plume t
- 2. Ground Shine l t
t
- 3. Vegetables !
t 1
- 4. Heat '
s.
- 5. Cow Milk ;
- 6. Goat Milk
- 7. Inhalation k h j
i s T f I 4 4 r l 4 >
?
I f i
?
I i i t l l J.
- r I i '
1 i i l
. t l
'l 1 [ t I a I
OH12D ODCM Page s' 46 Rev. : 3 Table 3.2-4 Dose Factors for Exposure to a Semi"-Infinite Cloud of Noble Gases Total Body
- Beta Skin Gamma Air **
Nuclide Gamma Dose Dose Factor Dose Factor Factor (DFB1g (DFSg ) (DF[) Kr-83m 7.56E-08 --- 1.93E-05 Kr-85m 1.17E-03 1.46E-03 1.23E-03 Kr-85 1.61E-05 1.34E-03 1.72E-05 Kr-87 5.92E-03 9.73E-03 6.17E-03 Kr-88 1.47E-02 2.37E-03 1.52E-02 Kr-89 1.66E-02 1.01E-02 1.73E-02 Kr-90 1.56E-02 7.29E-03 1.63E-02 Xe-131m 9.15E-05 4.76E-04 1.56E-04 Xe-133m 2.51E-04 9.94E-04 3.27E-04 Xe-133 2.94E-04 3.06E-04 3.53E-04 Xe-135m 3.12E-03 7.11E-04 3.36E-03 Xe-135 1.81E-03 1.86E-03 1.92E-03 Xe-137 1.42E-03 1.22E-02 1.51E-03 Xe-138 8.83E-03 4.13E-03 9.21E-03 Ar-41 8.84E-03 2.69E-03 9.30E-03
- mrem /yr per pCi/m 3
** mrad /yr per pCi/m l
l l l l 4 i i
OM12D: ODCM Page : 47 Rev. 3 Table 3.2-5 External Dose Factors for Standing on Contaminated Ground . 2 (m:es/h pet pCi/m ) h Tout 806 SHn P.3 0.0 0.0 C.14 0.0 0.0 h4 24 1.50E.00 2.90E.00 P.N 0.0 0.0 Cr.51 3.70E.10 2.60E.10 Mn.54 5.80E.M 6.00E 09 Mn.56 1.10E.08 1.30E.08 Fe 55 0.0 0.0 Fe.59 8.00E 09 9.40E.09 Cp.58 7.00E.09 8.20E.09 Co.60 1.70E*08 2.00E.08 N163 0.0 0.0 Nr.65 3.70E-09 4.30E 09 cv.64 1.50E.09 1.70E.05 Zn.65 4.00E.09 4.60E.09 Zn.69 0.0 0.0 Br.83 6.40E.11 9.30E.11 Br 84 1.20E.08 1.40E 08 Br.85 0.0 0.0 Rb.86 6.30E.10 7.20E.10 86 88 3.50E.09 4.00E 09 Ab.89 1.50E.08 1.80E.08
$r 89 $.60E.13 6.5CE.13
$r.91 7.10E 09 8.30E 09 i Sr.92 . 9.00E.09 1.00E.00 f.90 2.20E.12 2.60E.12 f.91M 3.00E.09 4.40E 09 f 91 2.40E.11 2.70E.11 1 92 1.60E.09 1.90E.09 1'-93 5.70E.10 7,80E.10 Zr.95 5.00E M 5.90E.09 Zr.97 5.50E.09 6.40E.09 Mb.95 5.10E 09 4.00E.09 Mo.99 1.90E.09 1.20E 09 I ft.99M 9.60E.10 1.10E.09 Tc.101 2.70E.09 3.00E.w Rs.103 3.80E 00 4.20E.09 Rv.105 4.50E.09 5.10E.09 l Sv.106 1.50E.09 ).80E.09 i A9 110M 1.80E 08 1.10E.08 l Te.125M 3.50E.11 4,80E.11 '
Te.127M 1.10E.12 1.30E.13 Te.127 1.00E.11 1.10E.11 To.12M 7.70E.10 9.00E.10 Te.129 7.10E.10 8.40E.10 Te.131M 8.4M.09 9,90E.09 Te.131 I.20E 09 2.60E.08 To.132 1.70E 09 f.00E.nl
- - - - - - ~ - - , - _ - . _ _ . - - _ - _ , , , . _ ___ _. _ _ _ __ _ _ _ _
OM12Ds ODCM Page : 48 Rev. : 3 Table 3.2-5 (Cont.) External Dose Factors for Standing on Contaminated Ground (e en/h per pCi/a 2- ) LI,ta!gi Total 80dy M I.130 1.40E.08 1.70t.08 I.131 2.80t.09 3.40[.09 1 132 1.70t.08 2.00t 08 I.133 3.70t.09 4.50[.09 I.134 1.60C 08 1.90t.08 I.135 1.20t.08 1.40t.08 Cs.1M 1.20t.08 1.40[.08 Cs.136 1.50E.00 1.70t.00 Cs.137 4.20t.39 4.90t.09 Cs.138 2.10E.08 2.40t.08 Sa.139 2.40t.09 2.70[.09 84 140 2.10t.09 2.40t.09 84 141 4.30[.09 4.90E.09 84 142 7.90E.09 9.00[.09 La.140 1.50E.08 1.70t.08 Le*142 1.50t.08 1.80E.08 Co.141 5.50t.10 6.20t.10 Co.143 2.20C.09 2.50t.09 Co.144 3.20t.10 3.70t.10 Pr.143 0.0 0.0 Pr.144 2.00t.10 2.30t.10 Nd.14 ? 1.00t.09 1.20!.09 W.187 3.10[.09 3.60E.09 Mp.239 9.50C.10 1.10t.09 I l 1 1 l
OM12D8 ODCM Page : 49 Rev. : 3 Inhalation Dose Facto e uit(arem/pCiinhaleQ NUCL10E SONE Livtt T.ROCY TNYA010 K10NEY LUNC St-LLI N 3 NO DATA 1.SBt-07 1.507-07 l.SSE-07 1. Set-07 8.SSE-07 1.58E-07 C 14 2.27t=06 4.26E-07 4. 2 6t-0 T 4.26t=07 4.261-0T 4.26t=07 4.261-07 NA 24 1 28t-04 1.28t=06 1.28606 1.20t=06 1.28t=06 1 288-06 1.20E-06 P 32 1.65E-04 9.64t=06 6. 2 6 t-0 6 NO DATA NO DATA NO DATA 4.00E-05 CR 51 NO DATA NO DATA 1.25t=00 7.44t=09 2.SSE-09 1 00E-06 4.llE-07 MN S4 NO DATA 4.95E-06 T.8 FE-0 T NO DATA 1 231-06 1.TSE-04 9.67t-06 MN 56 NU OATA !.55E-10 2 29E-11 40 DATA 1.63f=10 1.LSE-06 2.93E-06 FE 55 3.0TE-06 2.12t-06 4.91t-07 40 DATA NO DATA 9.0lt-06 T let=07 Ft 59 1.47E-06 9.4TI-Os 1 32 t-0 6 NO DATA N0 DATA 1 27t=04 2.35E-05 CO 58 40 DATA !.90E-07 2. 5 9E -0 7 NO DATA NC OATA 1 16t=04 1.33E-05 CO 60 NO DATA 1.44E-06 1.861-06 NO DATA N0 OATA 7.46t=04 1.56t=05 NI 63 5.40t-05 3.931-06 1 8 t E -06 40 DATA NO DATA 2.238-05 1.67t=06 Ni el 1.92E-10 2.e2C-11 1 14 F-11 NO DATA NO DATA 7.001-07 1.54E-06 CU 64 NO DATA 1.83E-10 T.69E-11 NO DATA 6.78E-10 8.40E-07 6.12E-06 2N el 4.051-06 1.29E-05 S . 8 2 E-0 6 NO DATA 0.62t-06 1 088-04 6.6sE-06 24 69 4.23E-12 0.14t-12 5. 65 t =13 NO DATA S.271-12 1.15E-07 2.04E-09 sk 83 NO DATA NO DATA 3.01E-00 NO DATA NO DATA NO DATA 2.90E-08 SR 84 NO DATA NO CATA 3.9 t t-0 8 NO DATA NO DATA NO DATA 2.05E-13 84 85 NO CATA NO DATA 1. 60 E-0 9 NO DATA NO DATA NO DATA- LT E 48 46 NO CATA 1.69E-05 7.371-06 NO DATA NC OATA NO DATA 2.00t=06 RD 88 NO DATA 4.84t-08 2.41E-00 NO DATA NO DATA NO DATA 4.let-19 R$ 09 ' NO DATA 3.20E=0I 2.12E-Og NO DATA NO DATA NO DATA 1.let-21 54 89 3.SOE-05 NO DATA 1. 0 9 t-0 6 N0 CATA NO DATA 1.75t-04 4.37t=05 SR 90 L.*st-02 N0 DATA 7.62E-04 NO DATA NO DATA 1.20E-03 9.02E-05 SR 91 7.74E-09 NO DATA 3. l 3 t =10 NO DATA NO DATA 4.S6E-06 2.39E-05 SR 92 4.43E-10 NO CATA l.64t-11 NO DATA NO DATA 2.06E-06 5.38t-06 Y 90 2.618-07 NO DATA 7. 01 E -0 9 NO DATA NO DATA 2 12E-05 6.32f-05 Y 91M 3.26E-11 NO DATA 1 27 E-12 NO DATA NO DATA 2.40t=07 1.66E-10 Y 91 S.78E-05 NO DATA 1 5 5 E-0 6 NO DATA NO DATA 2 13t=04 4.815-05 Y 92 1 291-09 NO DATA 3.77t-11 40 DATA NO DATA t.96E-06 9 19E-06 Y 93 1 188-00 NO DATA 3.265-10 NO DATA NO DATA 6.06t=06 S.27E-OS 2R 95 1.34t=05 4.30E-06 2.915-06 NO DATA 4.77E-06 2.Itt-04 1 00E-09 IR 97 1 21t-00 2.4SC-09 1 13E-0 9 NO DATA 3.715-09 9.84E-04 4.54E-05 N B 91 1.76t*06 9.77E-07 5. 2 6t-0 7 40 DATA 9.67E-07 4.3tt 05 1 30E-05 N0 99 NO DATA 1.llE-00 2. S TE-0 9 NO DATA 3.64t=00 1.14t=05 3.10E-Ol' TC 99m 1.29E-13 3.64E-13 4.63E-12 NO DATA S.64E-12 9.llE-00 9.20t-07
- , , , - - - - , , - - - , - - - - , - - - - - - . , , - - - - - - , , - _ , , - - , , .--,-ge--,-----,_,e_ awn- n,--,--------..-.--,---~--~.-m---. -- - -
ON12D3 ODCM Page : 50 Rev. : 3 Table 3.2-6 (Cont.) Inhalation Dose Factors for Adult (ares /pci inhaled) l
\ \
\
NucLl06 DONE Liven 7.sOav TNvn010 ale =Ev tuos st-LLt TCl0! l.22E-Il 7.12E-Il 7.3st-14 NO DATA 7.298-07 6 3tE=0S 1 30E-OS 1.35E-89 4.998-08 E.36E-21 A9105 1 9tt-07 WO 04fA 8. 2 JE -0 8 NO DATA RutOS 9 88E-t! NO 04fA 3.89E-11 NO DATA 1 7?E-te 1 378 06 4402E-06 le6ft-0S t t?E-03 4 84E-04 l tule6 8 64E-06 NO DATA l . 0 PE -0 6 40 DATA AGl10p 1 35E-06 1 2SE-06 7.4 AC-4 7 NO DATA 2 46E-06 S.798-04 3.78t=0S tillE-07 8 95E-06 3.92E-05 8.83E-06 TE!!54 4 27E-07 1 98E-07 S.84E-08 TE127M t.SSE-06 7.2tE-07 1 96E-07 4.11E-07 t.32E-10 6.378-10 S.728-06 81 14t=07 20E-04 7.l?E-06 t.878-05 ' TEl27 1 75E-10 8.031-18 3. 8 7 E -! ! 4.30E-07 4.57E-06 1 4SE-04 4 79E-OS fEt29* 1 22E-06 S.84E-07 L.985-07 4.87E-12 2.14E-11 2 42E-07, l.96E-08 6.22E-12 2 99E-12 L'. ll E -12 6.88E-09 3.86E-08 t.828-05 6 99E=0S TE129 , TE13tM 8.74E-09 5.4SE-09 3 63F-09 1 17E-12 9 46E=lt 1 74E-07 2 30E-09 JE131 1 39E-12 7 44E-13 4.49E-13 TE132 3 2SE-00 2 69E-08 2.02E-08 2 37E-08 1 02E-07 3 60E-05 49.6tE=07 37E-0$ I 130 9 72E-07 1 68E-06 6.60E-07 1 42E-04 2 61E-06 NO DATA 7 8SE-07 I 131 3.19E-06 4.47E-06 2. 56E-0 6 1 49E-03 7.66E-06 ... .. NO. DATA
...... .................... ... ... ... S.08E-08 I 132 1 4SE-07 4 07E-07 1 4 bE-0 7 1 43E-OS 6 40E-07 NO DATA t.!!E-06
' I 13') 1 08E-06 1 8SE-06 S . 6 S E-0 7 2 69E-04 3 23E-06 NO DATA 1 26E-10 l I 134 8 0SE-08 2 16E-07 7.698-08 3.73E-06 3 44E-07 N0 04fA 6.568-07 I 13S 3.35E-07 8 73E-07 3.21E.07 S.60E-0$ 1 39E-06 3.l9E-0$ NO CA?A 1 30E-06 1.22E-0$ CS134 4 66E-05 1 06E-04 9.10E-05 NO DATA 1 07E=0S telOE-06 1 46E-06
- Cll36 4.88E-06 1 83E=0S 1 38E-05 NO 0474 2 78E-0$ ~9.408-06 1 0SE-06 ,
C5137 9.98t=0S 7.76E=0S l . 3 S E -0 5 NO DATA 6.00E-08 6.0ff=09 2 33E-13 C5138 4 14E-08 7.76E=08 4.0l E-0 8 NO DATA 7.78E-14 4.70E-07 1 12E-07 54139 1 17E-10 8 32E-14 3.42E-12 NO DATA
.. .................w..
2 041-09 1.998-04 2 73F=0S 1 RAl40 4.88t=06 6.13E-09 l.2 t E-0 7 NO DATA 8 7SE-fl 2.42E-07 1 41E-17 l nel41 1.25E-11 9.41E-15 4.20E-13 40 Da?A 2 86E=ll 1.49E-07 1 96E-26 malet 3.29E-12 3 3EE-Il 2.078-19 NO DATA I NO 0474 1.10E=0S 5.73E-05 j LA140 4.30E-05 2.l?E 08 5. 73 E.0 9 NO DATA NO DATA 7.91E-07 2.64E-07 L4142 8.54E-Ll 3 88E-11 9.64E-12 NO DATA 7.03E-07 4.12E-OS l.10E=OS CEtel 2.49E-06 t.69E 06 1. 91 E-0 7 M0 DATA 7.60E=09 9.97t=06 2.83E-0$ CEt43 2 33E-04 1 72E 08 1.916-0 9 ND 0476 t.06E-04 9.72E-04 1.02E-04 CE144 4.29E-04 1 79E-04 2. 3 0E-0 5 NO DATA I 2 70E-07 3.51E-05 2.50E-OS rel43 1.17E-06 4.69E-07 S.898-08 20 DATA 3.76E-12 1.16E 12 1 9t t-13 90 OA?A 0.818-13 1.2?E-07 2 69E-te PR144 4.49E-07 2.76E-05 2.16t=0S 40147 6.b9E-07 7 62E=07 4. 56 E-0 8 40 Data 3.63E-06 1 94E-OS NO DATA I W 187 1.06E-09 8.85E-te ... 3 10E-10 NO DATA NP239 3.17E-00 2.928-09 1.llE-09 NO DATA 8.79E-99 4.10E-06 l.49E=0S i i I
<-Mev ee--o--w-w,,- e~,,-e-, ,- m~ ow, w w.,wwwww--~~~m __
, em,---- --o-m- ~
' OM12Ds ODCM Page : 51 Rev. : 3 Table 3.2-7 Inhalation Doze Factors for Teenager (area /pci inhaled)
*UCtt0E DoNE Liven f.000Y TNya010 al0NEY LvNC st-LLI N 3 N0 DATA l.19E-07 1.19E -0 7 1.59E-07 1 99E.07 l.99E-07 1.99E-07 C 14 3.2bE-06 6.C9E-07 6.09E.07 6. 09E -07 6.P9E-07 6.09E-0F 6 09E-07 '
Na 24 1.72E-06 8 72E-06 4 72E-06 8 72E-06 1.72E-06 8 72E-06 1 72E-06 P 32 2 34E-04 8.lfi.09 8. 9 5E-0 6 40 Defa NC DafA NO Data 1.16F-05 EA bl 40 04f4 NO U4f4 8.69F-00 9.37E-09 3.84E-09 2.62E-06 3.7tE-07 MN 14 NO 04fa 4.31F-06 1.03E-06 NO Safe 1.99E-06 2.48E-04 8.35E-04
*N $6 NO Dafa 2.124 10 3.19E-11 40 Data 2.24E-lo 1 90E-06 7.10E-06 FE ll 4.tBE-06 2.90E-06 6. 9 3 E.0 7 NO Data 40 Defa 1.llE-05 7.99E-07 FE %1 1.19E-06 4.62(-06 1.79E-06 NO Data NO DATA l.9tE-04 2.23E-05 CD St NO DATA 2.99E-07 3.47E-07 NO Dafa 40 Daft 1.6tE=04 1.19E-05 CD 60 NO O&fa 1.01E-06 2.48E=06 NO Daf4 NO CATA 1.09E-03 3.24E-05 NI 63 7.2SE-05 9.43E-06 2.4ft-06 NO DAfa No Data 3.84E-09 1.77E-06 Ni eb 2.73E-in 3 66E-It 1.59E.11 NO DATA NO DATA 1 17E-04 4.99E-06 i CU 64 40 DATA 2.54E-10 1.06E-10 NO DATA 5.01E-10 1.19E-06 7.60E-06 LN 65 4.82E-06 1.67E-05 7. 0 0 E -0 6 No cafa 1 08E-Ob I.llE-04 S.03E-06 (N 69 6.04E-12 1.llF-11 8.07E-13 NO Data 7.53E-12 1 94t=07 3.96E-OS At 83 NO 04fA NO DATA 4.30E-08 NO 0474 NO DATA NO OATA L7 E-24 SR 44 NO DATA NO DATA S.4tE-08 40 DefA NO DATA NO DATA L7 E-24 BR 85 NO DATA NO D4TA 2.29E-09 NO DATA NO DATA NO DATA LT E-24 48 86 NO DATA 2.38E-OS 1.05E-05 40 0474 NO DATA NO Dafa 2.2tE-06 RS SI NO DATA 6.02E-04 3.40E-08 NO DATA NO DATA NO DafA 3.65E-Il 28 89 NO O&fA 4.40!=0B 2.91E-03 NO Dafa NO DATA NO Defa 4.22E-17 Sa of 5.43E-05 NO Cafa 1 56E-06 No DATA NO Cata 3.02E-04 4.64t=05 1
SR 93 l'.ilt-02 NO Data 8.3SE-04 NO DATA NO DATA 2.06E-03 9.56E-05 SR 91 1 10E-04 NO DATA 4.19E-10 NO DefA NO Cata 7.99E.06 3.24E-05 54 92 1 19E-09 NO O&fA S.00E-11 NO DafA NO Data 3.43E-06 1 49E-05 Y 90 3.73E-07 NO 04f4 1 00E -0 8 NO DATA NO DATA 3.66E-05 6.99E-OS Y 9tm 4.63E-11 NO 04f4 1.77E=lk NO DATA NO DATA 4. 00 E-0 7 3.77E-09 Y 91 0.26E-05 NO DafA 2.21E.06 NO DATA NO DATA 3.67E-04 S.11E-09 Y 92 1.04E-09 NO DATA ' S.36E-18 NO D&fa NO DATA 3.35E-06 2 06E-05
....................................~.~.-..-t-..
Y 93 1 69E-08 NO DATA 4.65E-10 NO 04f4 NO DATA 1.04t=0S 7.24t=05 IR 99 8.82E-09 9.73E-04 3.94E=46 ISO DATA 0.42E-06 3.36t*04 8.86E-09 1.72E 00 3.40E-09 1 17E 09 a DATA Sel1E 09 1.62E-05 7.00E-05 , it 97
................................. ....t0 .......... ............... - .......
48 96 2 32E-06 1. 29E - 06 7. 08 E-0 7 NO Data 1.29E*06 9.B9E-OS 1 21E-06 1 #0 99' NO DATA 2 11E-00 4. 03 E -0 9 NO Cata S.14E-08 8 92E=OS 1.let-On j IC 99m 1 7AE-13 4.83E-Il 6 24E-12 40 Data 7.20E-12 1 44E 07 7.66E-67 ) i
- 4 k
)
i OM12D ODCM Page : 52 Rev. : 3 I Table 3.2 7 (Cont.) Inhalation Dose Fae10rs for Teenager (ares /pci inhaled) ! i
=vcLIO s0=f Livta t.a0pv fnvR080 s10=tv tugs cl.Ltl TClet 7.40s.it 1.0st.14 1 03 t.13 =0 04fa 1.90s.it s.34t.08 1 09t-16
, RUl03 2.634-07 40 CATA 1.12 t-0 7 NO 04f4 9.291-07 9.79E-05 1.36E-05 aul0S 1.40t*le NO 04fA S.42f-11 ho CATA 1 768-10 2.27E-06 1.13E-05 RUl06 1.23E-05 NO O&TA 1. 9 5 t -0 6 NO DATA 2.388 05 2.018-03 1 20E-04 4ctt0M 1.73t-06 1.64C-06 9.998-07 NO DATA 3 438-06 g.44t=04 3.415-05 TERISP 6.198-07 2.00E-07 8 348-08 8 758-07 40 Daft 6.708-05 9 38E-06 i i TE127m 2.25t-06 1 0ft-06 2.73t-07 S.48t-07 8 178-06 2.07E-04 1.99t=0S i filt? 2.518-10 1 14F-10 5.52C-Il I.778-10 9.10E-10 1 40E-06 1.0lt-05 4 fil29M l.748-06 8.23f=0f 2 0lt-0 7 S.728-07 6.498-04 2.47t=04 1.068-05 !
................................. ......................................... t i ft!!9 0.078-12 4.22t-12 2.20E-12 6.48t-12 3.32f-11 4.128-07 2.028-07 1
fin 31P 1.23E-08 7.51C-09 9.03E-09 9.06t=09 S.49t-00 2.978-05 7.76t=0S final 1.978-12 1.04c-12 6.308-13 1.S5t-12 7.72E-12 2.92t=07 1 898-09 fil32 4.SOE-98 1.e3E-08 2.741-08 3.07t=08 2.448 07 S.618-05 S.79E-05 I 130 7.80E-07 2.24t-06 0.96E-07 l.86t-04 3.441-06 h0 DATA 1 14E-06 I 131 4.438-06 6.148-06 3.308-06 1.838-03 1 058-05 NO DATA 8.!!P-07 ! I 132 1.99t-07 S.478-07 1. 9 7 t-0 7 1.89t=05 8.658-07 h0 DATA 1.59t-07 ; I 133 1.52t=06 2.36E-06 7. 7 8 E -0 7 3.65t-04 4.49E-06 h0 DATA 1.29t-06 1 134 1.118-07 2.90E-07 1. 0l f -0 7 4.948-06 4.501-07 h0 DATA 2 95t=09 t i 135 4.62t=07 1.18t=06 4. 3 6 E -0 7 7.76t=0S 't.86t=06 NO DATA 8.698-07 l C5134 6.28f 05 1.418-04 6.868-05 NO Defa 4.698-05 1.838-05 1 22t=06 ' CS116 6.44E-06 2.42t=0s 1 7 8 E -0 5 NO Oafa 1.3st.05 2 22t=06 1 36t=06 C5137 8.38t=05 1.06t=04 3 4 89 f-0 5 NO Data 3.801-05 1. Sit-05 1.068-06 CS138 S.82E-08 1.078-07 S . 5 8 t -0 8 NO DATA 8.20E-08 9.84t=09 3.38E-Il SA139 1.67t=10 1.188-13 4 87t=12 40 0474 1.118-13 0 08t-07 8.06t=07 sal 40 6.84t-06 8.30E=09 4. 4 0 f-0 7 NO DATA 2.0St=09 2.$48-04 2.06t=0) i sal 41 8.F88-11 1.82f=14 S.9 AE-il NO Cata 1.23t 14 4.llt 07 9.338 14 64142 4.62t-12 4.63t-IS 2.04E-13 ko 04f4 3.928-19 2 39t=07 S.99E-20 Letto 5.99t-08 2.99C-00 7. 8 7 t -0 9 NO Defa NO 04f4 2.688-05 6.09t=05 l L4142 1.20Cale S.3ttall 1.32E-Il WO DATA 40 DATA 1.278 06 1.50t=06 ) Cfl41 3.558-06 2.37C-06 2.788-0 7 WO Da74 1 114 06 7.678 6S 8.lat-On , Ctl43 3. Alt-04 2.428-00 2 70t-09 we 06f4 1.S88-00 1.63t-09 3.l9t=05 l Ctl44 6 11t-04 2.538-04 3. 2 8 t =0 S No cafa t.Sig.04 1 67t=0i 1.00t-04 P9843 1 67t=06 6 64t=07 8.285-04 #n 04f4 3.86E-07 6.045-05 2.674-05 . Patte S.378-12 2.204-12 2.72E-13 40 Defa 1.26t-12 2.19t=07 2.94t-14 40147 9.03E-GF l.078-06 6. 4 8 t =0 B 40 04T4 6 201-07 4.65t=0S 2.20E-OS W 147 8.904-09 1 22 t-09 4.29t-10 WO DATA #0 Data S.928-06 2 218-05 pP239 4.231-00, 3 99E-09 2 288-09 40 O&fA l.251-08 A.188-06 1 65f-0) i 1 J l
OM12D: ODCM Page : 53 Rev. 3 Table 3.2 8 Inhalation Dose Factors for Child (arem/pci inhaled) NutL10E SONE Livte f . 6007 TNYaClO E10Ntv LUNC Cl-LLI H 3 NO DATA 3.04t-07 3.04E-07 3.04f=07 1.04C-07 3.04t=07 1.04E-07 C 14 9.70E-06 8 828-06 1.42E-06 4 82E-06 1 82t=06 8.87t=06 1 82t-06 NA to 4.35C-06 4 35*-06 4.39f-06 4.3%t-06 4.35t-r6 4 35t-06 4.351-06 P 32 f .0 4 t-04 1.f98-06 2.6ft-OS NO DATA NO DATA Mn DATA 1.14t-05 CR St NO DATA ND 04fA A . l f t -0 0 2.31r.08 6.978 09 4.99E-06 2.93t=07 MN b6 '40 D A T A 1.16t-05 2. 5 7 t-0 6 NU OATA 2 78t-06 4.26t.04 6.19f-06 mN 56 40 DATA 4.48f=10 9.438-11 NO DATA 4.52t-10 3.SSt-06 3.33C-05 f t 15 1.28E-06 6.80E-Oe 2.10 t -0 6 NO DATA NO CATA 3.00E-05 f.75f.07 FL St S.99t=06 9.C4t-06 4. Sit-06 NO Data NO DafA 3.43C-04 8.9tE-05 CO 68 NO DATA 4.79t=07 8.S5t-07 NO DATA NO DATA 2.99t=04 9.295-06 CO 60 NO DATA 3.S SE-06
- 6.12 t-0 6 NO DATA NO OsfA l.98t-03 2.60E-05 NI 63 2.22t=04 1.25t=05 7.968-06 NO DATA NO Cafa 7.43E-09 1 7tE-06 NI 65 8.00E-10 7.99E-tl 4.44t-11 No DATA NU CATA 2.218-06 2.27t-05 CU 64 NO DATA S.39t-80 2.90C-10 NO DATA 1.63E-09 2 19t-06 9.92t-06 2h 6b l.15t-05 3.06t-05 1. 90 E -O S NO DATA l.93t.05 2.69t=04 4.41E-06 IN 69 1.8tt-!! 2.68t=11 2.4 t t.12 NO DATA 1 181-11 3.84E-07 2.75t-06 BR 83 NO DATA NO DATA 1. 2 8 E-0 7 NO DATA NO CafA NO DATA LT E.24
< UR 84 NO DATA NU CATA 1. 4 8 E -0 7 40 UATA NO DATA NO CATA LT E-24 84 85 NO CATA NO D&fA 6. 8 4 t-0 9 No CATA NO DATA NO DATA LT E=24 40 86 NO CATA 5.36t-05 3.09t-Ob NO CATA NO DATA NO CafA 2.16t=06 At 88 NO DATA 1.52E-07 9.90E-08 NO DATA NO DATA Nb DATA 4.66t=09 RS 89' NO CafA 9.331-08 7. 8 s t -0 8 NO D&fA NO DATA NO DafA S.llE-10 St 89 1.62t=04 NO 04fA 4. 66 E-0 6 NO DATA NO DATA S.81t=04 4.92t-05 1R 90 2.738-02 NU OATA 1.74t=03 NO DATA NO DATA 3.99C.03 9 28t=05
$P 98 3.288-08 NO DATA l . 2 4 E -0 9 NO DATA NO Data 1 44t.0$ 4 . 7 0 F. = 0 S SR 92 3.t4t=09 NO DATA l.428-10 NO DATA NO DATA 6.49t-06 6.55t=0S T 90 1.l!E-06 NO DATA 2 998-08 NO DATA NO 04fA 7.078-05 7 24t-0S ,
Y 9tP 1 378-10 NO DATA 4.98t=12 40 DATA NO DATA 7.40F=07 4.64t=07 l Y 98 2.478-04 NO DATA 6. 9 9 t =0 6 40 OATA NO DATA 7 10t=04 4.97E-05 Y 92 S.908-09 NO DATA 1.S T E-10 NO DATA NO DATA 4.46t-C6 6.46t-OS Y 91 S.04t-08 40 DATA 1 3 8 t-0 9 NO DA76 NO DATA 2 0lt-05 1.0St=04 l j 24 95 DelAt-OS l.llt=06 1.00t-05 NO DATA 1 6ti=0D 6.03f=04 1.6St=0S ' 2R 97 S.07t=08 7.A4t=09 4 328-09 NO DATA 1 058-08 3 06t-05 9.49t=0S NS 99 4.35t 06 2.48t=06 1.778-06 NO DATA 2.33t=06 8.668-04 1.00t=0S MD 99 NO 04f4 4.668-08 1. l t t-0 8 NO Caft I.06t=07 3.66t-05 1.42t=0S TC 997 4.8tt=ll 9.48t=13 1.56t-11 40 CATA 1 37t.it 2.57t=07 1.30E-06 I l l l l
OM12D: 0DCM Page : 54 Rev. I 3 Table 3.2-4 (Cont.) Inhalation Dose Factors for Child (ares /pci inhaled) aucties sugE tivEn f.so0y THva010 al0gtv Lu*c st-Ltl TClot 2 .19 t = 14, 2.30f=l4 2.911-13 NO DATA 3.9PE-Il 1. bat-of 4.41f-09 ; 20103 7. 4 S k'- 01 NO DATA 7.90f-0 7 NO 04fA 1.904-66 l.79E-04 l.Itt-CS AULOS 4.13f=10 NU OATA 4 908-40 Nn 04f4 3.638-10 4.16t=06 2 69t=0S AU106 3 68E-Ob NU 04f4 4.57f=06 NO DATA 4.97Ea05 3 078-03 8 16t=04 AClier 4.96E-06 3.08t=06 2.47t=06 N0 DATA S.74L-06 1.48f=03 2 71E-05 TE1254 1.82E-06 6.29t=07 2.47f-07 S.205-07 NC DATA 1.298-04 9 83E-06 TE12FM 6.72E-06 2.38t-ce 8.let-07 1.6AE-06 1.724-05 4.00E-04 1.93f=0S fil27 7.49E-10 2.97C-10 1 6 SE-10 S.30E-10 1 916 09 2.7tE=06 1 528-05 18121r 5.19f-C6 1 8tE=06 p.22t-07 l.7tt=06 1.161-05 4.'76t=04 4.9tt-OS fil29 2.64t-11 9.451-12 6.44C-12 1.93E=ll 6.94L-11 7.9tt-07 6.09E-06 TE13tr 1 63t=08 l.60E-00 1.37t-00 2.64E-00 1 001-07 S.56E-05 8.32f-05 fil31 S.87C-12 2.201-12 4.78C-12 4.b9hal2 1 19C-11 S.558-07 3.601-07 TFl32 1.30E-07 7.36t=00 7.12E-08 8.58t-08 4.791-07 1 02E-04 3.721-05 1 130 2.71E-06 4.43f=06 2 2AE-06 4.99t-04 6.618-06 NO DATA 1 38t-06 1 131 1 30E-05 1.30E-05 7. 3 7 f =0 6 4.39t-03 2.13E-05 NO DATA 7.60f-07 8 132 S.72f-07 1.10E-06 S.O f f-0 7 S.2 3E-05 1.69E-06 NO DATA 8.6St=07 1 133 4.48t-06 5.49:-06 2.00E-06 1 04t-03 9.13E-06 NO DATA 1.48t=06 8 134 3.17t=07 5.841-07 2 6)E-07 1.37E-05 S.92E-47 NO DATA 2. Set-07 1 135 1.33E-06 2.l6E-06 1.12 f -0 6 2.14C-04 3.62E-06 NO DATA 1.20E-06 r C$t34 1 76E-04 2.74C-04 4 071-05 NO DefA 4.93E-05 3.27E-05 1.04E-06 ] C$136 1 768-05 4.62t-05 3.14 E -0 5 N0 CATA 2.58E-OS 3.93te ?^ 1 13E-06 i CSl37 2.45t-04 2.235-04 3.47E.05 NO DATA 7.63t=0S 2.BIE-OS 9.78t-07 CS138 1 71E-07 2.27t-07 l.SOE-07 NO DATA 1.6tE-07 1.84t-ce 7.29t-08 84139 4.90E-10 2.66F-13 1.45t=11 NO Cafa 2.33t=13 1 56t=06 1.56t=0S 04140 2 00E=Ob l.751-08 1. l f f *0 6 NO D AT A S.718-09 4.7tt-04 2 75t=0S talet S.29C-11 2.95t=14 1. 7 2 F -12 40 DATA 2.56E-14 7.09E-07 7.44t=00 , 04142 1 35E-il 9.73C-LS 7. 64 t-13 NO DATA 7.87E-15 4.44t=07 7.4tt-10 l 1 L4140 1.74t=07 6.08t-00 2 04 E -O S NO DefA NO DATA 4.94E-05 6.10E-05 i tal42 .3.50E-te 1 11E-10 3.49E-il No 04f4 NO DATA 2.35E-06 2 0$f-05 l Ctl41 1.06t=0b S.20E-06 7. 0 3 t =0 F NO DATA 2 311-06 1.47f-04 1.535-05
................................. .... .... .......... .. ..... l CE143 9.091-04 S.17E.08 7.7 tt-0 9 No DefA 2.266-05 3.12E-OS 3.44E-05 :
C E 14 4 - 1 03t-03 9.72C-04 9.770-0S N0 DATA 3.17E-04 1.23C-03 1.05t-04 1 PRl43 4.99E-06 1 50E-06......................,8.tlk-07 2 47E-07 NO DATA ........ 1 178-04 2.63t=0S , i PR144 1 61[=11 4.99d-II 0.10 E.13 N0 DATA 2 648-12 4.23t=47 S.32t=08 1 ND147 2.92f=06 2. 3 6 E-66 1 04 t =0 7 No 04f4 1 308 06 8.876-05 2.22R-05 l t w 187 4.48E-09 2 6 t t-D9 1 17 F-0 9 No DATA NO DATE 1 11E-0S 2.46E-OS l l NP239 1 26E-07 9.04f=09 6.358-09 NO DATA 2 638-00 1.674-05 1 73t OS l a 1 4 1 i
OM12D: ODCM ' Page : 55 Rev. : 3 Table 3.2-9 Inhalation Dose Factors for Inf ant (aree/pci inhaled) NUCLICE SONE LivtR f.6007 TMYA010 Al0NEY LUNG Cl-LLI N 3 NO DATA 4.62E-07 4.62E-07 4.62F=07 4.62E-07 4.62E-07 4.62E-07 C 14 1.09E-05 3.79C-06 3.79t-06 3.798-06 3.79t=06 3.791-06 3.79t-06 44 24 7. bet-06 7.54C-06 7. 54 C-0 6 7.54t-06 7.14t-06 7.54E.06 7.54E-06 P 32 1.45E-03 0.03E-05 S.SJE-Ob NO DATA NO DATA 40 OATA 1.tSt-05 CR St NO DATA NO DATA 6.39E-08 4.ttt-08 9.45E-04 9.lff-06 2.55E-07 MN S4 NO Cafa 1 8tE-05 3.56C-06 NO DATA 3.56E-06 7.14E-04 5.04E-06 MN 56 NO DATA 1.10 F. = 09 1.5 8 E-10 NO DATA 7.86E-10 0.95t-06 5.12E-05 Pt 55 1.4tt-05 8.89E-06 2.30E-06 NO DATA NO DATA 6.2tt-05 7.821-07 FE 59 9.69E-06 1.68E-05 6. 7 f t -0 6 N0 DATA 40 DATA 7.25E-04 1.77E-05 CD SS NU DafA 8.7tt-07 1.30E-06 NO DATA NO CafA S.95t=04 7.95E-06 CD 60 NO DATA 5.73E=06 8 418-06 NO DATA NO DATA 3.22t=03 2.20E-05 NI 63 2.42E-04 1.46t.05 8. 2 9 E-0 6 40 DATA NO DATA 1.49E-04 1 73t-06 NI e5 1.ftt-09 2.03C-10 8.79E-t! NO DATA NO DATA 1.80E-06 3.58t-05 CU 64 NO DATA 1.34E-09 5.53E-10 NO DATA 2.844-09 6.64E-06 1.0ft-05 24 65 1.38t-05 4.47E-05 2.22E-05 No DATA 2.32E-05 4.62E-04 3.67E-05 2N 69 3.85E-11 6.9tE-t! 5.13E.12 NO DafA 2.87E-il 1.055-06 9.44E-06 3R 83 NO DATA NO DATA 2.72E-07 NO DATA NO DATA NO DATA LT E-24 3R 84 NO DATA NO DATA 2. 86 E-0 7 NO DATA NO DATA NO DATA LT E-24 84 85 NO DATA NO DafA 1 4 6E -0 8 NO DATA NO DATA NO CafA LT.t-24 AB 86 NO DATA 1.36E=04 6.30E-05 NO DATA NO DATA NO DATA 2.17E.06 20 88 MO DATA 3.98E-07 2.035-07 NO D&fA NO O&fA NO DATA 2 42E-07 RS 89 NO DATA 2 29E-07 1.47E-07 NO DATA NO DATA NO DATA 4.87E-08 SR 49 2.84t-04 NO DafA 8.tSC-06 NO DafA NO DATA 1.45t-03 4.57E-05 SR 90 2.92E 02 NU DATA 1. 8 5 t-0 3 NO DATA NO DATA 8.03E-03 9.36E-05 SR 91 6.83t*08 NO DATA 2 4 7 t -0 9 NO Defe NO DATA 3.768-05 5.24E-05 SR 92 7.50E-09 NO DATA 2 79E-10 NO DATA NO DATA 1.70E-05 1 00E-04 Y 90 2.35t=06 NO Data 6. 3 0 E-0 8 NO DATA NO DATA 1.924-04 7.43t-05 Y 9tm 2 918-10 NO DATA 9.90E-12 NO DATA NO DATA 1.99E-06 1.688-06 9 91 4.20t=04 40 DATA 1 12E-05 NO DATA NO DATA 1.75E-03 S.02E-05 Y 92 1 17E-08 NO DATA 3.29t=10 NO DATA NO DATA 1 75E-05 9 04t=05 Y 93 1.07E-07 NO DATA 2 9tt=09 WO DATA NO DATA S.46f-On 1.19t=04 2A 95 0.24E-05 1.998-05 1. 4 9 t -t 4 NO DATA 2.22t-65 1.25E-03 1.S$t-05 14 9 T 1 07E 07 1 83E-08 8. 36 t -0 9 NO DATA ,l.05t-08 7.88E-05 1 00E-04 48 9b 8.l2E-05 4.59t=06 2. 70E -0 6 NO DATA 3.lff=06 3.42t-04 9.05E-06 MO 99 NO 04'A l.18d-07 2. 31 E .0 8 NO DATA 1.R9t=07 9.63E=0S 3.48t=05 TC 99M 9.98f=l) 2.96t=12 2.66E-It NO DafA 2.22t-11 S.79t=07 1.4SE-06 . . - .
----,._,,_-...____,,,,..---,__,-,._-.__-_,,~,,,,p_-._,,,-_ _. - - - , - . . , - , - , . , _ _ , , _ . .
5 OM12Ds ODCM Page : 56 Rev. 3 Table 3.2-9 (Cont.) Inhalation Dose Factors for Infant (art.a/pci inhaled) , wuctlet 00wt Liven f. Door Twvnolo al0Nev LUNc st-LLI l ftlp! 4.654-14 5.90E-14 S.00E-13 NO DATA 6.99E-13 4.17E-07 6.03f=07 Rul03 1.44F=06 NO DATA 4. 8 S E -0 7 NO DATA 3.03t*06 3.94t=04 1.15t-05 kul05 0.74:=:0 NO DATA 2 93E-10 NO 04f4 6.428-10 1.12t-05 3 46E-05 Aul06 6.20E-05 NU OATA 7.77t-06 NO D&fA 7.6tt-05 0.26E-03 1.17t-04 s AG1104 7,335-06 S.16t=06 3.978-06 NO Defa 7.80E-06 2.628-03 2.36t=0S IE125m 3.40E-06 4.42t=06 4.70E-07 1 16E-04 NO DATA 3.19t-04 9.22E-06 TE127m 1.19t-05 4.93f=66 1 48E-06 1.48E-06 2.6BE-OS 9.37f*04 1.95t=0S TEl27 1.99t=09 6.58t=10 3.49t=10 1 32E-09 3.47t=09 7.398-06 8.74E-05 TEl29* lefit-OS 4.3SC-06 1 998-06 1 918-06 2 2?E-05 1.20E-03 4.93E-05 TElI9 S.63t-il 2.40E-11 1 34E-11 4.82E-Il 1.255-10 2.let-06 1.08t-05 ftt3tM 7.62t-08 3.93t=00, 2 99E-00 6.385-00 1 09E-07 1.428-04 8.58E-05 fEt31 1 245-11 S.878-12 3.575-12 1.13E-11 2.451-11 1.47E-06 S.07E-06 7t132 2 66E-07 1.69E-07 1. 26 E-0 7 1 99E-07 7.19E-07 2.438-04 1.llt-OS 1 130 4.S4E-06 9.9tE=06 3.98E-06 1 14E-03 1.09t-05 NO DATA 1.42E-06 l 131 2.71t-05 3 17t-05 1.40E-OS 1 06t-02 3.70E-05 NO DATA 7.56E-07 1 132 1.2tE-06 2.53t-06 8. 99 t-0 7 1.21E-04 2.42t=06 NO DATA 1.36t=06 1 133 9.465-06 1 3fE-05 4.00E-06 2.let-03 1.60E-05 NO DATA 'l.14E-06
- I 134 6.lOE-07 1. 3 4 E- 06 4. 7 9 E-0 7 9.18E-05 1 49t=04 NO 0474 9.218-07 i
1 139 2.76t=06 S.43E-06 1. 90 E-0 6 4.97E-04 6.051-06 NO DATA 1.3tE-06 CS134 2.83t-04 S.02E-04 S.3IE-OS NO DATA 1 36t-04 S.69E-OS 9.53t-07 Cll36 3.45t-05 9.611-05 3.70E-05 NO DATA 4.03E-05 8.49E-06 1.026-06 Cll37 3.92E-04 4.37F-04 3. 2 5 E -0 5 NO DATA 1.231-04 S.09E-05 9 93t-07 CS138 3.68t=07 S.65C-nf 2.84E-07 NO DATA 2.93E-07 4.67E-08 6.26f-07 uA139 1 06E-09 7.03t-13 3 078-11
- NO DATA 4.73E-13 4.2SE-06 3.64f-05 matto 4.00E-05 4.00t-08 2. 07 E-0 6 NO DATA 9.99E-09 1.14E-03 2.74t*05 rel41 1 121-10 7.70f-14 3.558-12 NO DATA 4.641-14 2 128-06 8 39E-06 malet 2.84E-Il 2 365-14 1.40E-12 NO DATA 1.36E-14 1 11t-06 4.99t-07 tal40 3.4tt-07 1.434-07 3.681-04 NO DATA NO Defa 1 20E-04 6.06t-05 LA142 7.36t=10 2.69E=le 6.46E-11 NO DATA NO DATA let?f=66 4.25t=0S CEint 1 188-Ob ,l.19t-05 1. 42 E -0 6 NO D&fA 3.fik-06 3.69E-04 1.14t-05 CE143 2.09t-07 1.40E-07 1. l AE-0 8 No DATA 4.03E-08 8.30t-05 3.llE-05 CE144 2.20E-03 8. elf-04 1.26E -0 4 NO DATA 3.848-04 7.03E-03 1.06E-04 P4143 1 00E=OS 1.74E-06 4.99t-07 NO DATA l.488-06 3.09t=04 2 66E-05
+ PR144 3 42E-11 1.328-11 1. 72 E -12 NU 0474 4.40E-II 1.tlE 06 3.06t-06 N0 te r S.67t=06 1 01F 06 1. 57 E-0 7 NO DATA 2.291-06 2.30E-04 2.23f=0S w 187 9.26t=09 6.44t=09 2 23E-09 NO DATA N0 DAfa 2.83E-05 2 14E-05
..................... .......... ........ ...... ..............~,.. ...
] NP239 2 65t=07 2.378-08 194E 40 NO 041A 4.73t-00 4.2SE-05 1 70E=0S i l
\
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OM12D: ODCM Page : 57 Rev. : 3 Table 3.2 10 s testion Dose Factor for Adult (ares /pCi ingasted) NUCLICE SONE LtvtR T.ROCY THYROl0 KIONEY LUNO Cl-LLI H 3 NO DATA l.05t-07 1. 0 5 t-0 7 1.05t-07 1.05E-07 1 05E-07 1 05E-07 C 14 2.84E-06 5.68t=07 5. 4 8 t -0 7 5.68E-07 5.68E-07 5 68E-07 51.70E-06 68t-07 NA 24 8.70E-06 1.70t=06 l . 70 t -0 6 1.T0E-06 1.70E*06 1 70E-06 P 32 1.9 3 t-04 1.20t-05 7. 4 6 t -0 6 40 DATA NC OATA ho CATA 2 17E-05 CR 58 40 OATA NO DATA 2. 64,E -0 9 1 59E-09 5.86E-10 3 53t-09 6.69E-07 MN 34 40 OATA 4.57t.06 0. 72 E -0 7 NO CATA 1 36E-06 NO DATA 1.40t-05 NN $6 NO DATA 1.15C-07 2.04t-08 NO DATA 1.46t=07 NO O&fA 3.67E-06 ft SS 2.75E-06 1.90F-06 4. 4 )f.0 7 NO DATA NO DATA 1.061-06 1.09E-06 78 59 4.34E-06 1 02t=05 3.9tt-06 40 DATA 40 DATA 2 85E-06 3.40E-05 CD 58 NO DATA 7.45t-07, 1. 6 7 E -0 6 NO DATA NO DATA NO DATA 1.51E-05 CO 60 NO Cafa 2.14f-06 4.72C-06 NO DATA NO DATA NO DATA 4.02E-05 NI 63 1 30t=04 9.01E-06 4. 3 6 t -0 6 NO DATA NO DATA NO DATA 1.88f-06 NI 65 5 28E-07 6.86E-08 1.13 E -0 5 NO DATA NO DATA NO DATA 1.74E-06 CU 64 NO DATA 8.33E-08 3. 91 t =0 8 NO DATA 2.10f-07 WO DATA 7.10E-06 2K 65 4.84t=06 1.54E-05 6. 9 6 E -0 6 NO DATA 1 03t.05 NO DATA 9.70E-06 2N 69 1.03E-08 L.97t-08 1.37t=09 NO DATA 1.28E-08 NO DATA 2.96t-09 SR 83 NO DATA NO DATA 4. 02 t =0 8 NO DATA NO DATA NO DATA 5.79E-08 SR $4 NO DATA NO DATA 5. 21 t -0 8 ho CATA NO DATA NO DATA 4.09E-13 BR 85 NO DATA NO DATA 2.14 E -0 9 NO DATA NO DATA NO DATA LT t-24 RS 86 NO DATA 2 11E-05 9. 8 3 E -0 6 No DATA NO DATA NO DATA 4.16E-06 R$ 88 NO DATA 6 05t=08 1. 2 L E *0 8 NO DATA NO DATA NO DATA 8.36t=19 R8 89 NO DATA 4.01E-0 8
- 2.8 2 t-0 8 NO DATA NO DATA NO DATA 2.33E-21 SR 89 3.08t=04 NO DATA 8. 8 4 E -0 6 NO DATA NO DATA No DATA 4.94E-05 SR 90 7.58t-03 NO DATA 1 86 t-0 3 NO DATA NO DATA NO DATA 2.198-04 SR 91 5.6ft-06 NO DATA 2. 29 E.0 7 40 0'ATA NO DATA NO DATA 2.70E-05 SR 92 2 15t=06 NO DATA 9.301-08 NO DATA NO DATA NO DATA 4 26t=05 Y 90 9.62t-09 NO DATA 2 58E-10 NO DATA NO 04fA NO DATA 1 02t-04 Y 91M 9.09E.11 NO DATA 3 528 12 NO DATA NO DATA No DATA 2.678-10 Y 91 1 41E-02 NO DATA 3.778-09 MQ 04fA NO DATA NO DATA 7.76E-05 Y 92 8.45t-10 NO CATA 2 47E-1 L NO DATA M0 DATA NO DATA 1 48E-05 V 93 2 68tY09 NO DATA 7.40t 11 NO DATA NO DATA NO DATA 8.50E-05 24 95 3.04E-08 9.75E-09 6. 6 0 E-0 9 NO DATA 1.53E-08 NO DATA 3.09E-05 2R 97 1.68E-09 3.392-10 1. 5 5 t-10 NO DATA 5.12E-10 NO DATA 1.05t-04 NS 95 6.22t=09 3.46t=09 8. 86 d -0 9 NC OATA 3.42E.09 NO DATA 2.10t=05 NO 99 NO DATA 4.31E-06 8. 2 0 E-0 7 NO 0474 9.74E-06 NO Data 9 99t-06 fC 99M 2.47t=10 6.98f-10 0. 89 E -0 9 NO DATA t.06E-05 3 42 tale 4 13t=07
_. . , - - ,._ - ,--n,_,n. -
- --..-- , ,--- -- __ _ ,__.-,,_. - - ,._ n .
_--,--...---,,,.-n,-- -,---_--.---,__n , - - - . . - - . , . . - - ,
l l ! OM12D: ODCH Page : 58 Rev. : 3 Table 3.2-10 (Cont.) Ingestion Dose Factor for Adult (area /pCl ingested) NUCLICE SONE LivfA 7.80 DY TMYROID KIDNEY LUNG GI-LLI TClot 2.648-10 3.66E-10 3. 5 9 E -0 9 40 D&fA 6.591-09 1.87t-10 1.10t-21 4U103 1 85E-07 NO DATA 7. 9 7 E -0 8 NO 0474 7.06t-07 NO CafA 2.161-05 Autch 1.54E-08 NU DefA 6. 0 0 E -0 9 NO DATA 1.99f-07 NO Caf a 9.42E-06 AUl06 2.7tE=06 40 OATA 3. 4 8 t -0 7 NO DATA 5.311-06 NO DATA 1.78E-04 ACit0M 1.60E-07 1 48f=07 8. 79 E -0 8 40 DATA 2.9tE=07 NO DATA 6.04E-05 TE125M 2.6tE-04 9.71t-07 3. 51E -0 7 9.061-07 1.096-05 NO DATA l.07E-05 ftL27M 6.77E-06 2.42C-06 8.2 5 E-0 7 8.73E-06 2.75t=05 NO DATA 2 27E-05 TE127 1.80E-07 3.9 5 t=08
- 2.38 E-0 8 0.15t-08 4.40E-07 NO DATA 8.68E-06 ftt29M 1.15E-05 4.29E-06 1. A 2 E -0 6 3.95t-06 4.80E-05 NO DATA 5.79t=05 ftt29 3.lef=08 1 18t=08 7. 6 mi-0 9 2.4tt-08 1.32f-07 NO 06TA 2.37E-08 TCl31M 1 73E-06 8.46!-07 7. 0 5 E -0 7 1.34t=06 8.57E-06 ND'OATA 8.40E-05 TEl31 1.97t-08 8.23E-09 6. 2 2 E-0 9 1 62E-08 8.63E-08 NO DATA 2.79E*09 TE132 2.52E-06 1.63E=06 1. 5 3 E-0 6 1.80E-06 1.57E-05 NO DATA 7.71E-05 1 130 7.56E-07 2.23E-06 8. 0 0 E -0 7 1 09C-04 3.48E-06 NO DATA 1.92E-06 1 131 4.16E-06 5 15t-06 3. 4 t E -0 6 1 95E-03 1.02E-05 NO DATA 1.57E-06 8 132 2.031-07 5.43E-07 1.90E-07 1.90E-05 0.65E-07 NO DATA 1.02E-07 1 133 1 42E-06 2.47t-06 7.53E-07 3.63E-04 4.31E-06 NO DATA 2.22E-06 I 134 1 06E-07 2.88t=07 1.03 E-0 7 4.99E-04 4.58E-07 NO DefA 2.5tE-10 1 135 4.43E-07 1 16f-06 4. 2 0 E -0 7 7.65t-05 1.86E-06 NO DATA t.31E-06 C5134 6.22E-05 1.40E-04 1.2 t E 0 4 NO Def A- 4.79f-05 1.59E-05 2.59E-06 C5136 6.5tt-06 2.57E-05 8. 8 5 E -0 5 NO DATA 1.43E-05 1.96E-06 2.92E-06 CSL37 7.97E-05 1.091-04 7.14 E -0 5 NO DATA 3.70E-05 1.23f-05 2 118-06 CS138 5.52E-08 1.09E-07 5.4 0 E-0 8 NO DATA 8.01E-08 7.91E-09 4.65t-13 BA139 9.70E-08 6.918-l! 2. 8 4 E -0 9 NO DATA 6.46E-11 3.92E-11 1.72E-07 Bal40 2 03C-05 2.551-08 4 3 3 t =0 6 NO DATA 8.67t=09 1 46E-08 4.18t-05 84141 4.flE-08 9.56C-11 1. 5 9 E-0 9 NO Daf4 3.31E-11 2.0!!=11 2.225-17 94142 2 13t=08 2.19E-Il 1 34 E-0 9 NO Defa 1 85E-11 1 24E-11 1.00t-26 Lal40 2. SOL-09 8.262-09 J.3JC-10 NO Cafa NO 04fA N0 DATA 9.25t=05 LA142 4 28t-10 5.821-11 1.45E-11 NO DATA NO DATA 40 OATA 4.25E-07 CEl41 9.36t=09 . 6. 5 3t=09 F.18C-10 NO DATA 2.94t=09 NO CATA 2.42E-05 Ctt43 8 65t=09 1.227-06 1. 3 5 E -10 NO DATA 5.37E-10 NO DATA 4.56t-05 Ctl44 4.48E-07 2 04E=07 2. 6 2 E -0 8 NO DATA 1.21E-07 NO DATA 1 65t=04 PA143 9.20t=09 3 69C-09 4.56t-10 40 04f4 2.13I-09 NO DefA 4.03t-05 Ptl44 3.01E-Il 1.25E-11 1.581-12 40 DefA 7.05t-12 NO DATA 4.338-18 N0147 6.29t=09 7.27E-09 4.358-1 0 NO DATA 4 25E-09 NO Defa 3.49t=05 W 157 1.03E-07 8.618-08 3 0!!a0 8 NO DATA NO DATA NO DATA 2.82t-05 NP239 1 19t-09 1.17t=10 6.4%E-It 40 DATA 3 65E-10 NO DATA 2 40t-05 i l
l l l l l l l l 4
,-,..,__..,___---~,m_,.-_._.,_.. _ . _ _ _ _ _ . _ . , _ _ ~ _ . _ _ _ , _ . _ , _ . , . - ._.,_,.__m . _ _ ._. _ _ . , _ . . ,
OM12D: ODCM Page : 59 Rev. 3 Table 3.2 11 Ingestion Dose Factors for Teenager (ares /pci ingested) NUCL10E SONE liver f.00cf TNYRDIO R10Ntv LUNO Cl-LLI H 3 NO DATA l.06E-07 1 0e f-0 7 1.06t=C7 1.06E-07 1.06t-07 1.061-07 L 16 4.06E-06 0.12F-07 8.12 f -0 7 8.12f=07 8.12E-07 8.128-07 8 12F-07 NA 24 2 30E-06 2.301-96 2 30E-06 2 30E-06 2.30L-06 2.30E-Ot 2.30t-06 P 32 2 76t-04 1.FIC-05 1.07E-05 NO DATA NO DATA NO DATA 2 32E-05 CA St NU OATA NO DATA 3.60t=09 2.00E-09 7.896 10 5 14t-09 6.05t-07 1.28t=05 PN 54 NO DATA 5.90t=0e 1.17 t =0 6 NO DATA 1 76t-06 NO DATA mN 56 No DATA 1.38t-07 2.4tt-08 NO DATA 2 00f-07 NO Data , 1.04E-05 ff 55 3.781-06 2.68F-06 6.2SE-07 No UATA 40 DATA l.70f-06 1 16t=06 FE 59 5.87E-06 1.JFL-05 5.29t 06 N3 OATA NO DATA 4.32E-06 3.24E-05 CD 58 NO DATA 9.72t-Of 2.2 4 f-0 6 NO DATA NO DATA NO DATA 1.34E-05 CU 60 NO DATA 2.8tt-06 6.33E-06 NO DATA NO DATA NO Cafa 3.66E-05 NI 63 1 77E-04 1 25t=05 e . 0 0 E -0 6 NO DATA NO DATA NO DATA 1.99f-06 NI 65 7.491-07 9.5?t=08 4.36t-08 NO DATA NO DATA NO DATA 5.19E-06 CU 64 NO DATA 1 15I-07 5.41E-08 NO 04fA 2.9tt-07 NO DATA 8.92E-06 FN 6b 5.76t=06 2.00E-05 9. 3 3 E-0 6 NO DATA l.285-05 NO DATA 8.47E-06 JN 69 1 471-08 2.50t=08 1 96E-0 9 NO DATA 1. Alt-08 NO DATA 5.16t.00 84 83 NO DATA NO DATA 5.74E-08 NO CATA NO DATA
- NO DATA LT E.24 BR 86 NO DATA NO DATA 7. 22 E -0 8 NO DATA NO DATA NO DATA LT E-24 sk 8% NO DATA NO Data 3 05E *09 'o N DATA NO DATA NO DATA LT t-24 R8 86 NO DATA 2.18t=05 1 40E-05 NO DATA NO DAT A NO DATA 4.415-06 R8 88 NO DATA 8.52E-08 4.54E-08 NO DATA No ptfA NO DATA 7.30E-15 R8 89 NO Cafa 5.50t-08 3 8 9 E-0 5 NO DATA NO DATA NO Data 't.43f=17 54 87 4.40E-04 NO DafA L . 2 6 E -0 5 NO DATA NO DATA NO DATA b.24t=05 54 90 8.30E-03 NO DATA 2 0S E -0 3 No CATA NO DATA No cAf a 2.338-06 i ................................. .......... .. ........ ...............
SR 11 0.07t=06 NO DATA 3 2 8 E-07 NO 0174 NO DATA NO DATA 3.66t-05 SR 92 3.0$E-06 NO CATA 1.30E-07 NO DATA NO DATA NO DATA 7.7?E-05 Y 90 1.37t*08 NO DATA 3.61t-to NO DATA NO DATA NO DATA 1.13E-04
........................................... ..................... ... (
y 91M 1 29t-10 NO DATA 4. 9 3 E.12 No DATA NO DATA NO DATA 6.09E=09 Y 91 2 01E-07 N0 DATA 5. 3 9 E-0 9 NO DATA NO DATA NO D AT A 8.24f=05 Y 92 1.2LE=09 NO DATA 3.10E-11 NO DATA NO DATA NO DATA 3 32E-05 Y 93 3.83t=09 NO DATA 1.05E-10 NO DATA NO DATA NO DafA 1.17E-04
!a 96 4.12E-08 1.30t-08 8.94E-09 NO DATA 1.91E-08 NO DATA 1.006-09 2R 97 2 37t=09 4.69t.10 2.16t=10 NO 04f4 7 11E-10 NO OATA 1 27E-04 NR 95 0.22t=09 4.561 09 2.5tt-09 NO D AT A 4.421-09 NO DafA 1.95f-05 MD 99 NO DATA 6.03C 06 1.15 F -0 6 NO O&fA t.18t-05 NO DATA 1 08t-05 FC 99m 3.42f-10 9.26t=10 1 20t=08 NO DATA 1.38t-08 $.14t=10 6.088-07
OM12D: ODCH i Page : 60 Rev. : 3 i Table 3.2-11 (cont.) ' Ingestion Dose Facter for Teenager (ares /pci ingested) NUCLIDE DONE LivfR t.800f TNv2010 ElDNEY LU44 Ol-LLI IClo! 3.60E.10 5.42E-10 9. 01 E-0 9 No Safa 9.26E-09 3.12E.10 0.75E-17 , tut 03 2.SSE-07 WU OATA 1. 09 E -0 7 WO Defa 8.99E-07 NO DAfa 2 13E=05 [ autel 2 18E-04 NO UATA 8. 46t =0 9 40 0Af4 2 79E-07 No D&fa 1 76E-05 l
................................. ......................................... (
Rul06 3.92E-04 40 DATA 4.94E-07 40 Da7A F.16E-06 NO DATA t.88E-04 ACllom 2 05E-07 1.94E-07 1 18E-0 7 20 04fA 3 70E-07 NO DATA S.4SE-05 TEl264 3 03E-06 1.384-06 S.12 E-0 7 1 07E-04 40 DATA NO DATA t.13E-OS i ffl27M 9 67E-06 3.4st-06 1. t b E-0 6 2.30E-06 1 92k-05 NO DATA 2.4tE-05 fE127 1 58E 07 5.6CE-04 3 40E-08 1.09E-07 6 40E-47 NO DATA 1 22E-05
' TE129m I.63E-05 4.0$E-06 2. 58 E-0 6 S.26E-06 4.RIE-05 Nn DATA 6 12E-OS l TEtte 4.48E-08 1.67E-08 1. 01E -0 8 3.20E-03 1.00E 07 WO DATA 2 4SE-07
- TE131p 2.44E-06 1 17E-04 9.76E-07 1.F6E-06 1.22E-09 WO DATA 9 39E-05 TE131 2.79E-08 1.15E-08 8.72E-09 2.tSE-08 1.22E-07 NO DafA 2.29E TE132 3.49E-06 2.21E-04 2.08E-06 2.33E-06 2 12E-05 NO D&fA 7.00E-05 1 130 1 03E-06 2.98E-06 1 19E-0 6 2.43E-04 4.59E-06 NO DATA 2.29E-06 I 131 S.85E-06 8.19C-06 4. 40E -0 6 3 39E-03 1.4tE-05 No DATA t.62E-06 1 132 2.79E-07 7.30E-07 2. 62 E -0 7 2 46E-05 1.19E-04 NO D&? ~.181-07 I 133 2.0tE-06 1.4th-06 1. 04 E -0 4 4.76E-04 S.98E-06 NO 041. a.58E-06 i i 134 1 46E-07 3.87t=07 1 39E -0 7 6 4SE-06 6 10E-07 NO DATA 5.10E-09 1 135 6.10E-07 1.S7E-06 5 82 f-0 7 1.01E-04 2 48E-06 NO DATA 1.74E-06 C1134 8.37E-06 1.97E-04 9 14 E-0 5 NO Defa 4.26E-05 2.39E-05 2.4SE-06 C5136 0.59E-06 3.38E-05 2. 2 7 E-0 5 WO OATA t.84E-05 2 90E-06 2 72E-06 Cll37 1.12E-04 1.49E-04 5 19E-0 5 No DATA 5.07E-05' t.97E-05 2.12E-06 i C5138 7.76E-08 1.49E-07 7.4SE-08 20 DATA 1 10E-07 1 28E-08 6.76E-11 t 84139 1 39E-07 9.78E-11 4. 0 $ E -0 9 NO DATA 9.22E-Il 6.74E-11 1 24E-04 84140 2.84E-0) 3.4AE-08 1 0 3 E.0 6 90 DATA 1.18E.08 2 14E-08 4.38E-05 A4141 6.71E.00 5.01E-11 2.24E 09 90 DATA 4.65E-It 3.43E-18 1.43E-13 BA142 2 99t-04 2.99E-Il 1 84 E -0 9 90 DafA 2.53t-it 1 99E-11 9.18E-20 i Lat40 3.40E-09 1 71C-09 4.15E-10 40 CATA NC DafA NO DefA 9.82E-05 L At42 t . 7 9 E - 10, 7.95E=ll 1. 9 8 E .1 1 40 Defa 40 DATA h6 OATA 2.42E-06 CLt41 1 33E-08 0.88E=09 1. 02 E -0 9 40 DATA 4.18E 09 NO DATA 2 54E-05 CEt43 2.3SE-09 1.7tE=06 L .9 t E-10 M0 DATA 7.67E-10 NO DATA S.14E-05 CEtte 6.96E-07 2.88E-07 3 74E-0 4 NO DATA 1.72E-07 40 ^*ATA 1 75E-04 PRie) 1 3tt-08 1.23C-09 6. 52 E-10 40 DATA 3 64E-09 h0 DATA 4.31E-05
... 4............................ .........................................
l PA144 4.30E-11 1.76E.11 2.18E-12 NO Dafa 1.018=11 NO DAT4 4.74E=le 40847 9.30E-09 1.02E-04 4.11E-10 NO DefA S.99E-09 NO O&fA 3.68E-05 W 197 1 46E-07 1.19E=07, 4.lFE-08 NO DATA NO DATA NO 04fA 3.22E-05 NP!39 1 16E-09 1.66E-10 9.22E-11 20 Defe 9 28E-10 NO DATA 2 6fE 05 1 i l l I 1 1 i
.n- _nn_---._,-,n---r- ,.---n,-n,-_ _ _ _ _ _ , __,,_n__ ,w_n--.nn.,,newnn,__-
OM12D: ODCM Page : 61 Rev. t 3 Table 3.2-12 Ingestion Dose Factors for Child (ares /pci ingested) NuCLipt DONI Livtt f.nnut TMYa010 al0Ntv LUNO GT-LLI Il 3 NO DATA 2.03t-07 2.Olt-07 2.03t-07 2.e31-07 2.031-07 2.031-07 C 14 1.28t=0$ 2.*2E-06 2.42t.06 2.42f-06 2 42t-06 2.42E-06 2.42t=06 NA 24 b.80E-06 1.80L-06 S.80t=06 5.001-06 S.801-06 5.80t.06 S.80f=06 P 32 8.258-04 3 86t-0$ 3.18E-0> 40 O&fA NO DATA NO CLT A 2 281-05 CR St NO DATA NO Lefa 8.901 09 4.94t=09 l.35t*09 9.02t=09 4.77t*07 FN S4 40 O&fA 1 076-05 2. 8 SE-0 6 NO 04f4 3.00C-06 NO DATA 4.98E-06 3.34t-Of 4.04t-07 NO DATA 4.84f-OS MN 16 40 cafA f.Stt.08 NO Defa FE Sb l.llt-05 6.10E-06 8 89*-06 NO 0414 NO 04f4 3.45E-06 1.llt-06 FE 19 1.63E-05 2 6ff=0) 1 3 8 t-0 5 NO Cata NO Caf4 7.74E-06 2.78E-05 CO 58 NO DATA 1.801-06 5.518-06 NO DATA NO Cafa No cafa 1 05t-on CO 60 NO DATA S.2 9E-06 1.56 E -0 5 NO DATA NO DATA No DafA 2.93t-05 NI 63 S.388-04 2.88F=05 1.8At=05 NO DafA NO DATA NO DATA 1.94C-06 NI 65 2.22E-06 2.09F-07 1 22t-07 NO DATA NO DATA NO DATA 2.56E-05 CU 64 NO DATA 2.45t=07 1.488-07 NO Cata 5.92E-07 NO DATA 1.15t-05 (N 65 1 37t=05 3.658-05 2.2fC-05 NO DATA 2.901-05 No 04f4 6.418-06 2N 69 4.38t-08 6.J3t=08 S.85E-09 NO Data 3.841 08 NO DafA 3.998-06 84 83 NO DATA NO DATA 1.78t-07 NO CafA NO DATA NO D AT A LT t-24 84 84 NO DATA NO DATA 1. 9 8 E-0 7 No DATA NO DATA NO DATA LT t-24 RR 85 NO DATA No cafA 9.12t-09 N0 DATA NO DATA N0 CATA LT E-24 at 86 NO DafA 6.708-05 4 121-05 NO DATA NO 04fA NO DATA 4.3tF-06 RB 88 'NO DATA . 1 90E-07 1 32 f-O f NO 04f4 40 DATA NO 04f4 9.32E-09 R8 89 No DATA l.l?t=07 1. 04 t-0 7 NO DATA NO DATA NO DATA l.02E-09 54 89 1.32E-03 NO CATA 3. 7 7 t =0 5 40 DafA NO 04f4 No Data 5.118-05 SR 90 1.70f-02 No DAfa 4.38f-03 840 Da t a 40 DafA NO Cafa 2 29t-04 SR 91 2.40t=05 MO 04fA 94068-07 NO DATA NO Data NO DATA S.308-05 54 92 9 03t=06 NO Data 3. 62 f -0 7 NO DATA NO CATA NO Defa 1.788-04 Y 90 4 118-08 NO Caft 1 10L-0 9 NO Data NO 04fa NO DATA 1.17t-04 Y 9tN 3.82t=l0 40 DATA l .11 t-i l NO DATA NO DafA NO 0474 F.48t-07 Y 91 6.028-07 40 DATA 1 6 t F-0 8 NO DATA NO 04fA No 0474 8.028105 Y 92 3.60t=09 40 04fA 1 04E-10 NO DATA NO 04fA NO 0474 1.04t=04 Y 93 1 14C-08 NO DafA 3.13 t-10 NO D&fA NO DATA NO 04fA 1.70t=04 2R 95 1.let=07 2.35t-08 2.278-08 NO DATA 3.65t=08 NO DafA 2.66t-05 At 97 6.991-09 1 0!E 01 *t.968-10 NO DATA , 8 411-09 No DefA 1.93t-04 NB tl 2 25t=08 8.768-09 4.268 99 NO DATA 8.231-09 NO DATA l.62t=0S MD 99 NO CafA 1.33f-05 3. 2 9 t -0 6 NO Data 2.84L-05 NO 04fA 1 10t-05 ft 98a 9.23t-10 l.811-09 8. 00 E-0 8 NO CAIA 2 63t=08 9 191-10 1 03t=06 .l l l l l I -- -,_.-_ - . . _ . . - - - - _ _ - - _ - - ,- . _ , _ - . . _ . _
OM12D: ODCM Page : 62 Rev. 3 Table 3.2-12 (Cont.) Ingestion Dose Factors for Child (area /pci ingested) NUCLICE 8098 Livtt f . 80 DY THYR 010 El04tY LUNC GI-LLI TClot 1.07E-09 1.12i=09 1.42t-08 40 DATA 1.911-08 S.92C-10 3.56t=09 Aul03 7.31E-07 NU 04f4 2.818-07 NO DATA 1.84t=06 Nn DATA 1.89E-05 RulOS 6.4SE-08 ND DATA 2 34 E -0 4 40 Defe S.67E-07 NO DAT A 4.IIE-05 Aut06 1.17t-05 NO DATA 1 46 E-0 6 NO DATA !.58E.0S NO DATA 1 82E-04 AG110M 5.39E-07 3.64C-07 2 91t-0 7 NO DATA 6.78t-07 NO DATA 4.33E-OS TE12SM t.let-OS 3.09t-06 1 52 t-4 6 3.20t=06 40 DATA NO DATA 1 10E-05 TE!!FM 2.89E-OS 7.78t-06 3. 4 J t -0 6 6.98t=06 8.248-05 NO DATA 2.34E-05 fil27 4.71E-07 1.27F-Of 1. O l t -0 7 3.26E-07 1.34t=06 NO DATA 1.84E-OS fil29" 4.87E-05 1 36t-05 7. 5 6 t -0 6 1.578 05 1.43t-04 NO DATA S.94t-OS Itt29 1.34t=0F 3.74t-08 3.18E-08 9. 5 6E -08 3.92E-07 NO Cafa 8.34E-06 l TElllM 7.20E-06 2.49E-06 2.6SE-06 S.lti-06 2.41t-05 NO DATA 1.Olt=04 ' ftt31 8.30E-08 2.53E-08 2.471-4 8 6.35E-00 2 51t-07 NO DAfa 4 36t=07 TE132 1.01E-05 4.47t=06 S.40E-04 4.51E-06 4.15 E -05 NO DATA 4.50E-05 8 130 2.92t=06 S.90E-06 3.04E-06 6.50t-04 8.82E-04 40 DATA 2.76E-06 1 131 1 72t-05 1 73C-05 9. 8 J E -0 6 S.72t=03 2.84t-05 40 Data 1 54E-06 8 132 8.00C-07 1.47t-06 6.76t-07 6.02E-05 2.2SE-06 NO D AT A 1.73t=06 1 1 133 S.92E-06 7.32t-06 2.778-06 1.36t-03 1.221-05 NO DATA 2.95E-06 I 134 l 4.19t=07 7.78E-Of 3.588-07 1 798-05 1 19E-06 NO Daft 5.16E-07 1 l I 135 1.75t-06 3.llt=06 1. 4 9 t = 0 6 2.79E-04 4.831-06 NO DATA 2.40t-06 C1134 2.341-04 3.84C-04 8.101-05 N0 DATA 1.19t-04 4.27E-05 2.078-06 CSI)6 2.35t-05 6.46t-05 4. t S t -0 5 NO DATA 3.446-05 S.13t-06 2 278-06 CS13) 3.27t-04 3.13t-04 4.62E-05 40 Data 1.02E-04 3.67E-05 1 96E-06 C$138 2.28E-07 3 17t=07
- 2. Cit-0 7 NO D&fA 2.231-07 2.40E-08 1 46E-07 8A139 4.14t-07 2.28t-10 1. 2 0 E -0 8 40 DafA 1.93E-10 1 305-10 2 39t-05 R4140 8 3tE=0S 7.288-08 4.85t-06 40 O&fa 2.37t-08 4.34t.08 4.218-05 SAlet 2.00E-07 1.122-10 6. b i t -0 9 90 DAfa 9.691-11 4.58t-80 1.14t=0F CA142 0.741-08 6 291-18 4. 8 8 f -0 9 10 D&fA $.09E-11 3.70C-Il t.14E=09 Lal40 1.0tt-08 3.53t-09 1 19t-09 40 Data NO DATA 40 OATA 9.84E-05 LA142 S.74t-10 1.v7E-10 S.23t-l1 NO DATA NC Daft NO DATA 3.3tt-05 CEl41 4.9?C 11 1.d8C-00 2.94t 09 NO DAT4 4.688-09 NO DATA 2.47E-05 CE143 6.99t=09 3.71E-06 S.49t-to NO 04f4 1.59E-09 AD DATA S.S$t-05 CEl44 2.08E-06 6. Sit =07 1. l i t-0 7 NO DATA 3.616-07 NO DATA 1.'Ot=04
. PA143 3.93t-08 1.181-08 4. 9 5 t -0 9 40 Defa 6 194-09 NO DATA 4 24f-05 P4144 1.29t 10 1.91E-Il 6.498-12 40 0474 2.118-11 NO DATA 8.59E-08
, N0l47 2.79E=0A 2.26t-08 8 75E-09 NO DATA l.241-08 NO DATA 3.S8E-05 W IST 4.29E-07 2.54f.01 1 848-07 40 O&fA NO 04fA NO DATA 3.S7E-05 i NP239 S.2)E-09 3.77t-80 2:4bt=10 40 DATA 1.098-09 NO DATA 2.79t-OS i 2 l 4 \ \ , l
---,-- -- , , _ , . , . . , - - - . , ,- ,, ---.,_,.,,w., , . , ._-,_, , _ . _ - , , . , _ . -
.,__g.,_~,n- , - - - , _ , _ _ _ , , . , , . - . , , - -
1 I OM12D: ODCH Page : 63 Rev. : 3 l Table 3.2-13 Ingestion Dose Factors for Inf ant (aren/pci ingested) NUCL IDL SONE L l Wi t f . 8 00Y TMv4Ul0 A10Ntv " UNO Ol-LLI N 3 NO DATA 3.08R 07 8.088-O f 3.0Rf=07 3.081-0f 3 08t=0? 3.08t-07 C le 2.3ff=0S S.06t=06 5. 0 6 C-0 6 S.06t=06 S.066-06 S.068-06 S.06C.06 NA 24 1.01t-05 1 01C-05 1 0 8 t -9 5 1.08t=0S l. cit =0S t.018-0) 8.Olt-05 P 32 8.700-03 1 004-04 6. 5 9t -0 5 NO UAfa NO Data NO DATA 2 501-05 CA il NO DATA NO DATA l.48t-08 1 20E-09 2.0lt=09 8 79t*88 4. tit =0f MN le NO CafA 1.99f.0b 4.518-06 40 DATA 4.48t-06 40 DATA fellt=06 MN $6 40 DATA 8.18t=07 1.4 8 t 0 7 NU 04fA 7.011-07 NO CAfa 7.4 3 f =0 5 ft 55 1.391-05 8.98t=06 2. 4 C E-0 6 NO DATA NO O&fA 4.59t=06 1.14t.06 FT 59 3.00t-05 S.J81-0$ 2.12E-0) 40 CATA NO DATA l.198-05 2.571-05 CO 18 NO DATA 3.60t-06 8.98t-06 NO cAfa 40 DATA NO DATA 4.9 f t 06 CO 60 40 Data 1.088-05 2.951-05 NO UATA NO DATA NO DATA 2.178-05 ' NI 63 6.34f-04 3.92i-05 2.20E-05 NO DATA 40 DATA NO CafA 1.95t-06 e................................ ......................................... NI 66 4.708-06 S.321-Of 2.428-07 No UATA NO DATA NO DATA 4.05t=0S
~U 64 NO DATA 6.09t=0f 2. 82 t =0 7 NO DATA 1.03t-06 N0 Defa 1.25t=0S IN 65 1.34t-05 6.'stt-05 2.9tf*05 NO DATA 3.06t-05 NO DATA S.33t-0$
IN 69 9.33E-08 1.68t-Of 1.25f-08 NO DATA 6.98t.c8 NO DATA 1.378-05 nt 83 NO CafA NO DATA 3. 6 3 t-0 7 NO DATA NO DATA NO CATA LT t 24 SR 84 NO CafA NO DATA 2.828-07 NO DATA NO DATA NO DATA LT t-24 st 83 NO DATA NO Data 1 94 E -0 8 NO DATA NO DATA NO DATA LT t-24 M8 86 NO DATA 1.70!=04 8.4 0 t-0 5 NO DATA NO DATA NO DATA 4.35f-06 48 48 .NO DATA 4.988-07 2.73t=07 NO DATA NO DATA NO DATA 4.85t-07
................................................................. ...... . l R$ 89 NO DATA 2.868-07 1.978-17 NO DATA NO DATA NO DATA 9.748-08 SR 89 2.518-03 NO DATA 7 20E-0$ No DATA NO 04f4 NO DATA l.16t-05 SR 90 1.05t=02 NO DATA 4.718-03 NO DATA NO DATA NO DATA 2 38t=04 SR 91 3.00f=CS NO CATA 1.8tt-06 NO DATA NO DATA NO DATA S.92t=0S 54 92 1.92C 05 NO Cata 7.13 t =0 7 NO DATA NO DATA NO DATA 2.07t=04 <
Y 90 8.691-08 40 DafA 2. 3 s t -0 9 NO DATA NO DATA 40 CATA 1 201-04 l 1 Y 9tm 8.1e8-10 NO DATA 2.76f I t NO 04f4 NO OAV4 NO DATA 2.708 06 Y 91 1 135-06 40 CATA 3.018 08 NO DATA NO DATA NO DATA 8.108-0$
- Y 92 7.65t=09 NO Data 2.15 t-10 ho DATA NO DATA NO DAf4 1.461-04 Y 93 2.438 08 NO DATA 6.62t t e NO DATA NO 04fA NO DATA l.92t-04 2R 95 2.068-07 1.021-88 3.168 48 NO 0474 S.41E 08 WO DATA 2.50F.0$
2A 97 1.44t=08 2.54C=99 1.16 t *0 9 NO DATA 2.561-09 NO DATA l.62t=04 it 95 4.208 04 l.75t=08 1. 0 3 t-0 8 NO DATA 1.74k-08 NO DATA l.46f 05 mo 99 NO DATA S.4C2-pl 6. 6 8 t -0 6 NO DATA S.088-05 NO DATA l.12E-05 fC 99p I.92t-09 3 96t=09 S . l 08 -0 8 NO DATA 4.26t=08 2.0ff=09 l.191-06 1 _ _ _ _ _ _ _ _ __ _ _. _ _ . _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ - , _ - __ . _ _ . _ _ _ _ _ _l
l 1 1 OM12D: ODCM l Page : 64 , Rev. 3 l Table 3.2-13 (Cont.) Ingestion Dose Factors for Infant l NUCLICE SONE LivtR f . 00 DT TMya010 E10Ntv LUNC Cl-LLI ; IClot 2.27E-09 2 86t=09 2.4)t-08 NO DATA 3.408-08 8.l6t=09 4.861-07 j Rut 03 1.48t=06 NO Uafa 4.95E-07 N0 DATA 3.08t=06 NO DATA 1.00t-01 i EU105 1 365-07 NO D&fa 4.68t-08 N0 Daf4 t.00t-06 Mn DATA S.4tt-05 4Ul06 2 4tt-05 ND DATA 3.018-06 kn DATA 2.891-05 NO Daf4 1.83F.04 l AG110m 9t96E-07 7.27t-07 4. S i t-0 7 N0 DATA t.04t=06 NO DafA 3.77t-05 ftt25M 2.33E-05 7.79C-06 3 16 t =0 6 7.84t=06 NO DATA NO DATA 1.llt*05 fil27m 5.85E-OS 1.94t=05 7.00E-06 1.69t=0S 1.44t=04 NO Data 2.36t=09 1.00E-06 3.35t-07 2.llt=07 8.14E-07 2.44t-06 NO DATA 2.10E-OS
- TE127 ft129M l.00E-04 3 43E-05 1.54E-05 3 84E-05 2.50t-04 NO DATA S.97t-05 ftlt9 2.84t=07 9.79t=08 6.61t=08 2.38E-07 7.078-07 ' NO DATA 2 27E-OS ft13tp 1.62t=0S 6.12t=06 S.05t-06 1 24t=0S 4.!!E-05 NO DATA 1.03E-04
- IEl31 1 76E.07 6.50C-08 4.948-08 1 571-07 4.50E-07 No DAfo 7.11t-06 fil32 2.00E-05 1 03t=0S 9.6 t t -0 6 8 52E-05 6.44E-05 NO 0474 3.8tt-05 8 130 6.00t=06 1.328-05 S . 30t -0 6 1.48t=03 1.451 05 NO DATA 2.81E-06 I 131 3.198-05 4.23t-05 1. 46 t -0 5 1 39E-02 4.94E-05 40 DATA 1.518-06 i
i 132 1 66E-06 3.37t=06 1 2 0 E -0 6 1.58t=04 3.76L-06 NO DATA 2.73t-06 8 133 1 25E-05 4 82t=05 S.33t-06 3.3tt-03 2.14E-35 NO CafA 3.088-06 2 I 134 8.69E-07 1 78t.06 6. 3 3 t-0 7 4.198-05 1 99t-06 NO DafA t.84E 06 i i 135 3.64E-06 7.24C-06 2.6 4 t -0 6 6.49t=04 8.071-06 NO DATA 2.621-06 i C5134 3.77E-04 7.032-04 7.101-05 NO DATA 1.811-04 7.42E-05 1.91E=06 4.59E-05 t.35E-04 5 048-05 NO DATA 5.188-05 1 10E-OS 2.09t-06 Cll36 i i C5137 S.24t=04 6.11E 04 4. 3 3 8 -0 $ NO DATA 1.64t=04 6.641-06 1.91E=06 CS134 4.81E-07 7.82t-07 3. 7 9 E -0 7 NO DATA 3.908-07 6.09E-08 1 25t=06 Sal 39 8.88E.07 5.84E-10 2. ll t -0 8 NO DATA 3.llt.10 3.54t-10 9.58t=0S
................................. .................. 3.. ......
8a140 1 7tt-04 1.ftt=07 8. A18 -0 6 40 OATA 4.068-08 1.05t.07 4.20t=01 ' Ral41 4 25t=07 2 91t-li 1. 3 4 t .0 8 Mn DATA l.755-10 1.77E-10 S.198-06 Saint 1 84t.07 1.538-10 9.06t 09 NO O&fA 3 018-11 9.26t-il 7.591-07
.......................... ..... ......................................... i Lat40 2 111-08 8.328 09 2.14 t =0 9 NO DATA MO DATA NO DATA 9.178-05 L A 14 2 1.108-09 4.04t-10 9.6 f t ll Mn DATA N0 Daf4 NO D&7A 6 86f=05 Cttel 7.87f-08 4.001-08 5. 6)t -0 9 NO DATA 1 488 08 NO DATA 2 48t-06 Cit 43 1 48t=08 9.82t=06 1 171-09 N0 CATA 2 46t=09 NO DATA S.73t-05 Ctt44 2 98t=06 1.22t=06 8. 6 7 t-0 7 NO DATA 4.93t-07 NO DATA 1.ftt-04 i pat 43 0.13t=08 3.C41-08 4. 0 3 E -9 9 NO DATA 1 13t-08 NO DATA 4.298-05 i PRl44 2.74C-te 1.068 10 1 38t.11 40 DATA 3.8'd ll NO Defa 4.93t-06 N0l47 S.53t=08 S.68t=08 3.488-99 NO DATA 2.198-08 NO DATA 3.40t-05 k it? 9.031-07 6.286-07 2. l f f =0 ? Mn DATA NO Cafa 40 CATA S.69t=05
................................. ... ..... ...........................o.
i NP239 1 111-08 9.938-10 9.61E 10 N0 Data 1 988-09 NO WATA 2 87t=0S
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OM12D: ODCM l Pace : 65 Rev. : 3 Table 3.2-1'4 Annual Usage Factors for the Maxitum Exposed Individual Pathway Infant Child Teen Adult Fruits, vegetables & ' grain (kg/yr)* -- 520 630 520 Leafy vegetables (kg/yr) -- 26 42 64 Milk (1/yr) 330 330 400 310 i 1 Meat & poultry (kg/yr) -- 41 65 110 3 8000 8000 Inhalation (m /yr) 1400 3700
- Consists of the following (on a mass basis): 22% fruit, 54% vegtables (including leafy vegetables), and 24% grain.
< Table 3.2-15 Annual Usage Factors for the Average Individual,,
Pathvay Child T,een Adult Fruits, vegetables, & grain (kg/yr)* 200 240 190 Milk (llyr) 170 200 110 Heat & poultry (kg/yr) 37 59 95 3 l 4 Inhalation (m /yr) 3700 8000 8000 2
- Consists of the following (on a sans basis): 22% fruit, 54% vegetables (including leafy vegetables), and 24% grain. ,
**For total population and average individual dose calculations. l l
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l OM12D ODCH Page : 67 l Rev. : 3 3.3 Compliance Vith 10CFR50 Appendix I - Gaseous Effluent Dose Doses resulting from the release of noble' gases, radiolodines, tritium and radionuclides in particulais form must be calculated to show compliance with Appendix I of 10CFR50. The calculations vill be performed at least monthly for all gaseous effluents. 3.3.1 Noble Gases Section II.B.1 of Appendix I of 10CFR50 limits the releases of gaseous effluents from each reactor to unrestricted areas such that the estimated annual gamma air dose is limited to 10 millirads and the beta air dose is limited to 20 millirads. The external dose pathvay only vill be considered for noble gases. The controlling location for the above stated dose limits is the site boundary location with the highest relative dispersion factor (X/0) for the period of release. PNPP Technical Specifications limit the dose resulting from the relerse of noble gas radionuclides in gaseous effluents to the following: I
- a. For gamma radiation, during any calendar quarter:
D air f 5 mrads, 1 :
- b. For beta radiation, during any calendar quarter:
D air
$ 10 erads,
- c. For gamma radiation, during any calendar year D
air f 10 mrads,
- d. For beta radiation, during any calendar year ;
D air f 20 mrads. i )
- - - - _ - . - , _ _ _ _ _ _ _ _ - _ _ _ - _ , , - _ _ - - , - . , , _ , - - - - .y - -_ ___
~
i l OM12D ODCM Page : 68 Rev. 3 3.3.2 Radiciodines, Particulates, and Other Radionuclides Section II.C of Appendix I of 10CTR50 limits the release of radioiodines and radioactive materials in particulate form from each reactor such that estimated dose or dose commitment to an individual in an unrestricted area from all pathways of exposure is not in excess of 15 area to any organ. The controlling location for this organ dose limit is the location of the highest relative deposition (D/Q) for the period of release, as well as the actual receptor pathway. Receptor pathway locations vill be reviewed once per year following the performance of the Land Use census to include consideration of , nearest residences, garden, and farm animal locations in each sector. PNPP Technical Specifications limit the dose resultant from the release of iodine-131, iodine-133, tritium, and all radionuelades in particulate form with half-lives greater than eight days to the following
- a. During any calendar quarter:
Dose to Any Organ f 7.5 mrems 1
- b. During any calendar year Dose to Any Organ f 15 arems.
3.3.3 Dose Calculations The following calculations are used to determine gamma and beta , air dorf.s resultant from noble gas release to areas at or I beyond the site boundary for purpose of shoving compliance with j 10CFR50, Appendix I. The equations used to calculate organ i doses resultant from the release of iodine-131, iodine-133, tritium, and radionuclides in particulate form with half-lives greater than eight days are those found in Section 3.2.3. The :
- dose rate obtained is integrated over the appropriate surveillance or sampling time period.
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OM12D: ODCM Page : 69 Rev. : 3
- a. Camma Air Dose from Noble Gas Releases Y g Y Dair - (3.15) (10 ) (X/0) iI (Og ) (Drg ) (3.3-1)
Vhere: Y
. D the annual samma air dose due to noble gas air = radionuclides, in arad/ yrs Y
DFg the gamma air dose factor for a uniform semi-infinitecloudofradionuglide"i",fromTable 3.3-1, in arad/s per C1/m Og the release rate of radionuclide "1", in uCi/s 3 X/0 the normal relative dispersion factor, in s/m : 3.15 x 101 = the conversion factor to convert (mrad
- pC1)/(Ci
- s) to arad/yr.
- b. Beta Air dose from Noble Gas Releases 6 6 3
Dair - (3.15 x 10 ) (X/0) iI (0 )3 (DF g) Vhere: 6 D the annual beta air dose due to noble gas air = radionuclides, in erad/ yrs 6 DF the beta air dose factor for a uniform semi-g=infinitecloudofradionuS'd'"i"*T*bI' 3.3-1, in arad/s per C1/m Og the release rate of radionuclide "i", in pCi/s 3 X/0 the normal relative dispersion factor, in s/m : 3.15 x 10I - the conversion factor to convert (arad
- pC1)/(Ci
- s) to arad/yr.
3.3.4 Cumulation of Doses The dose contribution from gaseous offluents will be calculated at least monthly. Calculations vill be performed to determine the muimua air dose as well as the maximum organ dose to an individual. These dose calculations vill be summed for , comparison with quarterly and annual limits. To assure ; I i
)
OM12D: ODCM Page : 70 Rev. : 3 compliance with 10CFR50, Appendix I, the dose limits for air dose and organ dose are those found in Sections 3.3.1 and 3.3.2, respectively. The quarterly limits specified in those sections represent one half of the annual design objectives. If these limits a o exceeded, a special report vill be submitted to the NRC in accordanec with PNPP Technical Specifications. 3.3.5 Projection of Doses , Anticipated doses resuliing from the release of gaseous effluents will be projected monthly. The doses calculated for the present month will be used as the projected doses unless information exists indicating that actual releases could differ significantly in the next month. In this case the source term i vill be adjusted to reflect this information and the justifica-tion for the adjustment noted. If the sum of the projected doses for the 31-day period exceeds 0.3 stem to any organ, appropriate portions of the ventilation l exhaust treatment system vill be operated to reduce releases. The values for the projected dose impact levels correspond to about one forty-eighth of the Appendix I limits. If continued for a year, these values vould correspond to less than one-fourth of the Appendix I limits. 3.4 Population Dose PNPP's Semiannual Radioactive Effluent Release Reports, as required by Regulatory Guide 1.21, vill include total population dose and average individual doses calculated for all radioactive gaseous effluent releases. The total population dose and average individual i dose vill be computed, taking into account geographical population distribution and pathvay(s) using the equations in Section 3.2. However, the dose factors, DF differt total population and j averageindividualdosesareIkkEu,latedinamannersimilartothat i used for maximum individuals except that Regulatory Guide 1.109, Revision 1 assumptions for average individuals are used rather than for maximum exposed individuals and they are averaged over all age groups after weighting by the fraction of population in each age i group. T r f a l t
I OM12D: ODCM Page : 71 Rev. 3 1 Figure 3.3-1 Gamma and Beta Air Dose Factors for Semi-Infinite Plume (arad/s per C1/m3) Gamma Air Beta Air Dose Factor Dose Factor 0 Nuclide (DF[) (DFg ) Ar-41 2.95 2 1.04+2 Kr-83m 6.12-1 9.13+0 Kr-85m 3.90+1 6.24+1 Kr-85 5.45-1 6.18+1 . I Kr-87 1.96+2 3.27 2 I Kr-88 4.82+2 9.29 1 ! ) Kr-89 5.48+2 3.36+2 i Kr-90 5.14+2 2.48+2 j Xe-131m 4.95+0 3.53+1 ! 4 Xe-133m 1.04+1 4.69>1 j Xe-133 1.12+1 3.33+1 i Xe-135m 1.07+2 2.34+1 i Xe-135 6.09+1 7.80+1 i Xe-137 4.79+1 4.03+2 l Xe-138 2.92+2 1.51+2 , ! I 1 i > ' i i ! 1
)
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OM12D ODCH Page : 72 Rev. t 3 4.0 TOTAL DOSE 4.1 Compliance Vith 40CTR190 - Uranium Tuel Cycle Dose Annual dose contributions from liquid and gaseous effluent releases, as discussed in Sections 2.3.2 and 3.3.4, are summed to evaluate compliance with the 40CTR190 annual limit of 25 aren total body or any organ (except the thyroid, which is 75 arem). PHPP does not intend to exceed 40CTR190 limits during normal operation. However, if such a situation should occur, viel tions would be handed as per Technical Specification 3/4.11.4'.. which requires the following: Vith the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specification 3.11.1.2a., 3.11.1.2b., 3.11.2.2a., 3.11.2.2b., 3.11.2.3a. or 3.11.2.3b., calculations shall be made including direct radiation contributions from the reactor units and from outside storage tanks to determine whether the above limits of Specification 3.11.4 have been exceeded. If such is the case, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent
' recurrence of exceeding the above limits and includes the schedule fcr achieving conformance with the above limits. This Special Report, as defined in 10CFR20.405c, shall include an analysis that estimates the radiation ext.osure (dose) to a MEMBEn OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathvays and i
direct radiation, for the calendar year that includes the release (s) l covered by this report. It shall also describe levels of radiation i and concentratiosn of radioactive material involved, and the cause ; 1 of the exposure livels or concentrations. If the estimated Jose (s) exceeds the above limits, and if the release condition resulting in violation of 40CFR190 has not alredy been corrected, the Special
- Report shall include a request for a variance in accordance with the provisions of 40CTR190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete, j
This Special Report shall contain:
- 1. A determination of which fuel cycle f acilities or operations, in addition to the nuclear power reactor unit (s) at the site, contribute to the annual dose to the. maximum exposed individual. Nuclear fuel facilities over five elles from PNPP need not be considered in this determination.
- 2. A determination of the maximum exposed 17.dividual.
?
OM12D: ODCM Page : 73 Rev. : 3
- 3. A determination of the total annual dose to this person from all existing pathways and sources of radioactive effluents and direct radiation using the methodologies described in this ODCH. Where additional information on pathways and nuclides is needed, the best available information vill be used and documented. ,
- 4. A determination of the dose resulting from direct radiation from the plant and storage facilities. '
l The total body and organ doses resulting from liquid effluents from the PNPP vill be summed with the doses resulting from gaseous i releases of noble gases, radiciodines, tritium, and particulates with half-lines greater than eight days when any of the dose limits , outlined in Sections 2.3.2, 3.3.1 or 3.3.2 are exceeded by a factor l of two. The doses from the PNPP vill be summed with the dose to the i maximum exposed individual contributed from other operations of the
- uranium fuel cycle.
-i t 1 l 4 i I l ! l I 1 i u i I i l
ON120: ODCH Page : 74 Rev. 3 4.2 Direct Radiation Dose From PNPP Potential direct radiation dose to individuals outside PNPP vill arise from (a) skyshine and direct dose from the turbines, (b) direct dose from the external surfaces of buildings, and (c) direct dose from stored radvaste. Coolant activation by high energy neutrons, the 016 (n.p)N16 reaction, is of interest in boiling vatar reactors, like PNPP, because it can result in turbine skyshine and direct dose. The N-16 present in the steam of a direct cycle BVR is carried with the steam into the turbine moisture separators, and associated equipment. Although N-16 has a 7.13 second half-life, its gamma emission can present a radiation dose problem to the site boundary as a result of the high energy gamma seatter from structures and the atmosphere. All external valls of buildings at PNPP have been designed to attenuate radiation sources from within the plant to maximum of 0.5 mrem /h outside, with an expected radiation dose not to exceed 0.25 arem/h. Prcjected direct radiation dose assessment for normal operations was performed, based on 80% load factor and 100% occupancy, for the closest site boundary location (VSV sector). Direct dose from turbine skyshine vas calculated to be 1.3 mrem /yr and direct dose from the surface of buildings 'ias calculated to be 2.2 E-3 mrem /yr. Direct radiation doses at PNPP vill be messured by self-contained dosimeters encircling the site located in the general area of the site boundary. These self-contained dosimeters vill be of the thermoluminescent variety (TLDs) with analyses performed quarterly and annually.
OM12D ODCM Pago : 75 Rev. 3 4.3 Dose to Members of the Public While Onsite PNPP Technical Specification 6.9.1.7 requires "assessment of the radiation doses from radioactive liquid and gaseous effluents to members of the public due to their activities inside the site boundary". This assessment is included in Semiannual Radioactive Effluent Release Reporting. A member of the public is defined in Technical Specifications to include anyone who is not occupationally associated with Also the plant, excluded i.e., not a utility employee, contractor or vendor. from this category is any person who enters the site to service equipment or make deliveries. Maximum dose to member of the public while onsite is conservatively The assessment assessed relative to offsite dose values.
- methodology incorporates use of appropriate dilution, dispersion, and occupancy factors for onsite activities.
The only liquid effluent dose pathway affecting Fishingmembars of the on the Lake Erie public while onsite is shore exposure. Onsite dose shoreline is the assumed activity for this exposure. assessment is made via ratio to the maximum calculated offsite shore exposure dose incorporating adjustments for occupancy factor and liquid effluent dilution. 1 Several cases are considered for gaseous effluent dose assessment traversing a public to member of the public while onsite including: road within the site boundary, lakeshore fishing, non-PNPP related training sessions s't the Training and Education Center, car pooling to the Primary Access Control Point (PACP) parking lot, and job applicant interviews. This evaluation is made using "relative X/0" (atmospheric dispersion) values. "Relative X/0" values are the product of the highest annual average X/0 for the point of concern,A and occupancy factor for the case. i by ratioing this highest onsite "relative X/0" to th0 highest site boundary "relative X/0". (A unity occupancy far'or is used in the determination of the highest site boundary "relative X/0"). Conservative onsite dose determination is made by applying the "relative X/0" adjustment f actor for the highest potential onsite dose activity to the highest calculated gaseous effluent offsite dose. f
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a OM12D: ODCM t Page : 76 3 Rev. : 3 l 4 5.0 RADIOLOGICAL EN m 0NMENTAL MONITORING PROGFAM 4 5.1 Monitoring Program i gnvironmental samples shall be collected and analysed according to . Table 5.1-1 at locations shown in Figures 3 1-1 and 5.1-2. Table 5.1-4 describes sample locations, associated media, and approximate distances and directions from the site. Analytical techniques used
~
1 shall ensure that the detection capabilities in Table 5.1-3 are >
- achieved.
Ground water sampling vill not be conducted as part of FNPP's REMP J because this source is not tapped for drinking or irrigation purposes in the area of the plant and the hydraulic gradient is not suitable for useful groundvater contamination. The position of the ! l plant and the underdrain system with respect to the hydraulic i gradient is such that any leakage or overflow from the underdrain l system vill flow north towards Lake Erie. Local domestic volls ! i outside the exclusion area boundary are up-gradient from the plant. , i As part of the REMP, samples vill be routinely collected from the i j closest potable water intakes on Lake Erie. 3
- The results of the radiological environmental monitoring program are j intended to supplement the results of the radiological effluent ;
1 monitoring by verifying that the measurable concentrations of , l radioactive materials and levels of radiation are not higher than
- expected on the basis of the effluent measurements and modeling of j t the environmental exposure pathvays. Thus, the specified .
) environmental monitoring program provides measurements of radiation ;
and of radioactive materials in those exposure pathways and for ' those radionuclides which lead to the highest potential radiation ! exposures of individuals resulting from the' station operation. The r l initial radiological environmental monitoring program should be l , conducted for the first three years of commercial operations i 2 following this period, program changes may be proposed based on l . operational experience. ' Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hasardous conditions, seasonal j
- unavailability, malfunction of automatic sampling equipment and t other legitimate reasons. If specimens are unobtainable due to l sampling equipment malfunction, every reasonable effort shall be i made to complete corrective action prior to the end of the next 2
sampling period. All deviations from the sampling schedule shall be l documented in the annual report. 4 )
OH12D: ODCH Page : 77
- Rev. : 3 5.2 Land Use Census Program A Land Use Census vill be conducted annually to identify, within a distance of 8 km (5 miles), the location in each .* the meteorological sgetors of the neargst residgnce, the nearest vegetable garden greater than 50m (500 ft ) producing broad leaf vegetation and the nearest milk-producing aniaa1 in each of the 22 1/2' meteorological sectors within a distance of five miles.
If a Land Use Census identifies a location (s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20% greater than at the location from which samples are currently being obtained the nov location (s) vill be added to the radiological environmental monitoring program within 30 days. The sampling location (s), excluding the control station location, having the lovest calculated dose or dose commitment (s), via the same exposure pathvay, may be deleted from this monitoring program after October 31 of the year in which this Land Use Census was conducted. Any location from which milk can no longer be obtained may be dropped fror the surveillance program after notifying the NRC in writing that they are no longer obtainable at that location. The Land Use Census shall be conducted during the groving season at
! least once per 12 months using that information that vill provide the best results, such as by a door-to-door survey, serial survey, general observations, or by consulting local agriculture authorities. The results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report.
i r I l I e 1 I j I l
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d
i OM12D: ODCM Page : 78 Rev. : 3 5.3 Inter Laboratory Comparison Program The laboratories of the licensee and/or licensee's contractors which perform analyses shall participate in the Environmental Protection Agency's (EPA) Environmental Radioactivity Laboratory Intercom-parisons Studies (Crosscheck) Program or equivalent program. This participation shall include all of the determinations (sample medium-radionuclide combinations) that are offered by EPA and that also are included in the monitoring program. The results of analysis of these crosscheck samples shall be included in the Annual Radiological Environmental Operating Report.
- Broad leaf vegetation sampling of at least three different types of vegetation may be performed at the site beundary in each of two different sectors with the highest predicted D/Os in lieu of the garden census. Specifications for broad leaf vegetation sampling in Table 5.1-1 shall be followed, including analysis of control samples.
If the results of a determination in the EPA crcsscheck program (or equivalent program) are outside the specified control limits, the laboratory shall investigate the cause of the problem and take steps to correct it. The results of this investigation and corrective action shall be included in the Annual Radiological Environmental Operating Report. t j i I 1 l 1 - 1
_ __. _ . - . _ . ._ __._m . __ . ___ _ _ _. . - . - ._ __ ._ _ Table 5.1-1 MW'r Radiological Enviremental Monitoring Program Analysis Sample Media locations
- Sampling Frequency Type Frequency 1
Cirborne radiolodine 1, 3, 4, 5, 6, 7, 35 Coritinuous sampler operation Radiolodine Weekly following 1 i and with collection weekly or as I-131 canister change particulates required by dust loading, Particulates Weekly following loading, whichever is more Cross Beta (a) filter change frequent h Composite, by J Isotpic(b) location quarterly 4 Direct Radiation 1 through 24, 35, 36 Continuous sampling, one TID r:a - Dose Quarterly (3 TIDs/ location) 41, 42, 43, 45, exchanged quarterly 53, 54, 55, 56, 58 Continuous sampling, one TID Gasuna Dose Annually exchanged annually Continuous sampling, one TID Gamma Dose Quarterly or exchanged quarterly or under emergency under emergm situations situations j ~ Vaterborne Composite (c) H-3 Composite, by surface 28, 34, 59, 60 location, quarterly drinking (d) 36 Gross Beta Monthly Gamma Isotopic Monthly
! Sediment tram 25, 26, 27, 32 Semiannually - Spring and Gamma Isotopic Semiannually F7@
shoreline Fall as weather permits .TC
?
S011I *) 1, 2, 4, 6, 12, 14, Quarterly Gamma Isotopic Quarterly w 18, 20 Sr-89/90 j x i
! See footnotes at end of table. )
l Table 5.1-1 (Cont.) FNPF Radiological Environmental Monitoring Program ! Analysis l Sample Media tocations* Sampling Frequency Type Frequency l Ingest *g' t'l Milk 29, 30, 31, 47 Monthly when animals are not I-131, Monthly , I !
$1, 52, 57, 61 on pasture Gwena k Isotopic Semimonthly when animals are I-131, Semimonthly
( on pasture Gamma l'2-i Isotopic ,Ngg, 1 i u l Fish 25, 32 Scalancually - Spring and Cassia Semiannually ' y Fall as veather permits Isotopic ,O g ' (edible o portion) N " Food Products j
<-l Human Consumption 38, 39, 49, 50 Annually I-131, Annualy __ _
I Casuna
- l Isotopic o msg N
l 1D Animal Consumption 29, 31, 47, 51, Annually, location determined by I-131, Annually { o 52, 57 annual milk animal and Gwena Isotopic o N
- garden census ' ym g.
J". l g Vegetation 6, 7, 35, 44, 48 Monthly during growing season I-131, Monthly dur,ing Cassia Isotopic growing season 1 PrecipitationI *) 3, 4, 6, 7, 12, 35 Monthly Camuna Isotopic, Monthly l Gross Beta, l Tritium y7@ l .SC __o Sampling locations were selected on the basis of local ecology, meteorology, physical charactizations of the region, and demographic and land use features of the site vicinity. Other factors considered were applicable regulatory 'd guidelines (Appendix I to 10CFR50 Regulatory Guides 4.1, 4.2, and 4.8), population distribution (from environmental x report), ease of access to sampling stations, security, future program Jntegrity (e.g., not placing TID's near areas under construction or where the potential for vandalism is high, and the NRC Radiological Assessment Branch Technical ( Position on radiological environmental monitoring as revised in Revision 1, November 1979 (reference 1). In addition, l certain locations where INPP operations are unlikely to affeet levels of radiation or radioactivity were selected as control locations. l l
Footnotes to Table 5.1-1 (Cont.) (a) Particulate semple filters will be analyzed for gross beta 24 hours or more af ter samplig to allow for radon and thoron daghter decay. (b) Canna isotopic analysis means the identification and quantification of ganan-emittig radionuclides that any be attributable to the effluents from the facility. If gross beta activity in air or water is greater than ten times the mean of control samples for any medium, gamma isotopic analysis vill be performed on the individual samples. (c) Composite sampler will be collected with equipment that is capable of collecting an aliquot at time intervals that are very short (e.g., hourly) relative to the compositing period (e.g., monthly). (d) Biveckly (2 week period) I-131 analysis on each composite is to be performed when the dose calculated from the consumption of water is greater than 1 aren/ year (using ODCM methodology for maximum organ and age group). (e) Not Technical Specification required sample medlun. (f) When milk sampling is not performed, samples of three kinds of broad leaf vegetation grown nearest each of t.9 two different offsite locations of highest predicted annual average ground level D/0 and one sample of each of siellar broad leaf vegetation grown 15 to 30 km distant in the least prevalent wind direction shall be performad. l a l i f2E
- 2 ::;
S' ! wmo 1
~81
i Table 5.1-2 ( Reporting Icels for Radioactivity Concentrations in Environmental Samples l l UAT1!R TE FISR MIIJC FOOD PRODUCTS ANA1.TSIS (pC1/l) AIRBOINtOK GASESFARTIq/m (pCl ) (pCl/kg, wet) (pCl/1) (pC1/kg, wet) E-3 2 x 10'I*I ski-54 1 x 10 3 3 x 10' Fe-59 4 x 102 1 x 10' Co-56 1 x 103 3 x 10' 2 1 x 10' co-60 3 x 10 2 2 x 10' Zn-65 3 x 10 Zr-Mb-95 4 x 102 0 2 I-131 2 x 100 9 x 10-I 3 x 10 1 x 10 Cs-134 3 x 10 I 1 x 10 I 1 x 103 6 x 10 I 1 x 103 Cs-137 5x10 I 2 x 10 I 2 x 10 3 7x10 I 2 x 10 3 2 Ba-la-140 2 x 10 3 x 10 (a) For drinking water samples. The value given is the 40C m141 value. EIS 2 ::
? ~
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Table 5.1-3 - Detection capabilities for Environmental Sanple Analysis and (a) (b) Imuer Limit of Detection (LID) VATER TE FISH NIlJC FOOD PRODUCTS SEDDEBrf ANALYSIS (pCi/1) ADtBONE OR GASESPARTIg/m (pCi ) (pCi/kg, vet) (pCi/1) (pCi/kg, wet) (pC1/kg, dry) 0 Cross Beta 4 x 10 1 x 10' H-3 2 x 10 II 2 Mn-54 1.5 x 10 I 1.3 x 10 2 Fe-59 3 x 10 I 2.6 x 10 C0-58, 60 1.5 x 10I 1.3 x 102 2n-65 3 x 10 I 2.6 x 102 I Mb-95 3 x 10 Zr-95 1.5 x 10 I , 0 I I-131 1 x 10N'I 7 x 10-2 1 x 10 6 x 10 Cs-134 1.5 x 10 I 5 x 10-2 1.3 x 10 2 1.5 x 10 I 6 x 10 I 1.5 x.102 Cs-137 1.8 x 10 I 6 x 10-2 1.5 x 102 1.8 x 10 I 6 x 10 I 1.8 x 102 Ba-140 6 x 10 I 6 x 10 I g g E7E La-140 1.5 x 10 1.5 x 10 f%C
?
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Table 5.1-3 (Cont.) Table Notations "Required detection capabilities for thermoluminescent dosimeters used for environnental measurements shall be in accordance with the recommendations of Regulatory Guide 4.13, except for specification regarding energy dependence. Correction factors shall be provided for energy ranges not meeting the energy dependence specification. hThe methodology for determinig the ilD is contained in Appendix B. C This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.6. For these radionuclides in Tednical , Specification Table 4.12-1 41ch are not detected, the typical llDs for the measurement system will be j separately reported in the annual report. i If no drinking water pathway exists, a value of 3 x 10 pCi/l may be used. l C I If no drinking water pathway exists, a value of 1.5 x 10 pC1/1 may be used. 1 1 1 t ou 1
-g l "N-l r
Table 5.1-4 Seapling Imcations and Media for Favironmental Monitoring Perry Nuclear Power Plant Distance Description (Miles) Direction Media III Rs 3Wt! (Raines Road, North of Vest Diapel Road) 3.4 ENE AFT, AI, TID,
! On pole 3303409; first pole south of first drivevay of left 50 I
2 Site Boundary; Tree line 0.7 E TID, SO Ash tree 1000 feet leaf of second transmission tower from road j 1 %teorological Tower 1.0 SE AFT, AI, TID, PR
, On fence surrounding the equipment shelter j 4 On pole SW79/SFG5-30; inside auxiliary road gate of Parmly Road 0.7 S AFT, AI, TID, FR,
- 50 i S!r+ Boundarye Guincy Substation 0.6 SE AFT, AI, TID on pole 91.1283/9300, east side of substation 6 h icord Service Center (Control) 11.0 SSE AFT, AI, TID, Auburn Road south of Rt. 90; on inside rear fence next to gate FR, 50 VL 7 Site Boundary; tackwood Road Bus turnaround, on the right,100 feet 0.6 NE AFT, AI, TID, VL, par
- the turnaroised on tree with white dot. FR
$ 8 Site Poundary; Tree Line, behind nursery off Antioch Road 0.8 E TID ; 9 Site Boundary; Transmission Line Tower 0.7 ESE TID Third tower from Antioch Road toward the plant 10 South-southeast Corner Security Fence 0.8 SSE TID i on pole at turn in the fence -
11 Transmission Line Tower 0.6 SSU TID on tower at SU corner of Center and Parmly Roads 12 Site Boundary; Transmission Line Tower 0.6 USE TID, PR, SO Access road from N side of Paraly just U of location 95 w .e o
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Table 5.1-4 (Cont.) Sampling Imrations and Media for Environmental Monitoring Perry Nuclear Power Plant location Distance No. Description (Miles) Direction Media I)
! 13 Madison-on-the-take 4.7 DE TfD ! At end of Whitevood Drive, N of Onapel Road, ; NU side of turnaround on pole 3835803 t 14 Rubberd Road (South of North Ridge Road) 4.9 E TID, SO l On pole 928974 on V side of road, S side of McMackin Creek ! 15 Madison Substation (Eagle Street) 5.1 ESE TID On utility pole inside substation fence 16 Dayton Road (North of Interstate 90) 5.0 SE TID On pola 8572203 on lef t af ter dirt driveway which is just after the sharp left on Dayton 17 diadvick Road (Cul de Sac South of Interstate 90) 5.2 SSE TID On pole 9276222/1182011; last pole on left 18 Blair Road 5.0 S TID, 50 en pole on left just af ter road makes 90 degree lef t curve down hill heading towards river 19 Lane Road and South Ridge Road 5.3 SSU TID On pole SPC5648, 100 feet north of intersection 20 Nursery Road at Route 2 overpass 5.3 SU TID, 50 On pole 9628976 across from entrance 'o Route 2 21 Mardy Road at Painesville Township Park 5.1 VSE TID -
On pole 3378345, east of park entrance 22 Pafnesv111e 6.9 SE TID q on S side of Main Street across from Evergreen Cemetery on tree with white dot 60 feet vest of pole DDBPC2% E' 2 E l .2 E'
"3y 2
1 1 _. -_.---_=-. - - - - ._-. ___ .. __ - - - - _ . .-
Table 5.1-4 (cont.) Samplieg tocations and Media for Environmental Monitoring Ferry Muclear Power Plant 5 c I Incation Distance ] e No. Description (Miles) Direction Media (l) g y g 23 Fairport Barbor (Righ Street and Isew Street) 7.9 USE TID on pole en rear substation facing street 24 St. Clair Ave. Substation (Centrol) 15.1 SU TID In Mentocs on rear fence corner near rafirood tracks 25 FMPF Discharge 0.6 300U SED, FSR 26 offshore at Redbird, vicinity of chie Water Service Company Intake 4.2 DIE SED 27 Offshore, vicinity of Fairport b ebor Vater Supply System Intake 7.9 USU SED Ashtabula (Control), MI Generating Station Intake 22.0 EME VIR 28 Milk Farm, Haites residence, Antioch Road, Ferry 1.3 ESE MIK, FS 29 Milk Farm, Nealey residence, Iserth Ridge Road, Ferry 2.3 SSU MtK, FS lTC* 30 Mut, FS 31 Milk Farm, Soffer residence, Antioch Road, Ferry 1.4 15.8 ESE USE FSE, SED { 32 Mentor-en-the-take (Control) . 33 Deleted 34 PMPP Intake 0.7 IIU VIR 35 Site Roundary; north of transmission line, next to transformer, 0.6 E AFT, AI, TID, follow tree line VL,PR Fafnesv111e Water Supply Intake 3.9 USU VTR, TID 36 37 Deleted ^ 38 Seith Farm, 2061 Antioch Road, 1.1 E FD ,,o 0.5 miles from leerth Ridge Road ;g3 39 Goldings Farm Stand 1.8 SSU FD -ag 3515 North Ridge Road uo U
Table 5.1 4 (Cont.) Sampling locations and Media for Environmental Monitoring Perry Nuclear Power Plant location Distance No. Description (Miles) Direction Media 40 Deleted 41 Clark Road 1.1 SU TID one-half mile from Center Road, on pole No. 561%9, south side of road 42 Parmly Poad 0.8 S TID One-half mile from Center Road, located on utility pole No. 582923 near southwest corner of plant fence 43 Parmly Road 1.0 SS' ' TID Approximately 0.6 miles from Center Road next to stream, tree with white dot 50 feet from road, left of stream 44 Parmly Road 1.0 SSE VL 45 Clark Road 0.9 SSV TID Approximately 0.2 miles from Center Road on Pole No. 561960, south side of road 45 Deleted 47 Milk Farm, Zoldak residence, Middle Ridge Road, Madison 6.5 E MIK, FS , , 48 Antioch Road 1.1 ENE VL 3 49 Garden, 4385 lockwood Road 0.8 NE PD M ,g,
'.20 Carden, 13271 Radcliffe Road 10.9 5 PD i 51 Rettger Farm, 13863 Painesville-Varren Road 9.2 S MIK, FS '
pQ 52 Milk Farm, Pollack residence, Wood Rd. 4.5 SE MIK, FS o 1> 53 Netf Perkins, Co., southeast fence corner 0.5 USV TID ' E 54 Hale Rd. School, pole No. 395910, 2nd from corner on tre 4.6 SU TID E 55 Perry School District Offices - on pine in tree line by baseball dianond 2.5 S TID 56 Madison Nigh School, 1st clump of pine trees from library 4.0 ESE TID 57 Butler Residence, 6244 N. Ridge Road 8.5 E MIK, FS 77@ 58 On tree in NU corner of imsely Nursery off Antioch Road. 0.8 DIE TID f%C approximately 100 yards north of location 88 9 59 Lake shoreline at the north end of Green Road 4.0 DIE VfR 60 Lake shoreline at the retired boat launch area in 1.0 VSU VIR 'd$ Perry Park x 61 Milk Farm, Keller residence, Dewey Road, Madison 7.4 SE MIK, FS 'IC L (1) AI - Air Iodine MIX - Milk SI) = Soil APT = Air Particulate PD = Produce TID = Ambient Cammi Dose Rate F5 - Feed / Silage PR = Precipitation VL = Vegetation Fm . Fish SED = Sadimant 1Tm = Vatar
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i OM12Ds ODCH Page : 92 Rev. 3 Appendix A Atmospheric Dispersion and Deposition Parameters 9
OM12D: ODCM Page : 93 Rev. : 3 The atmospheric dispersion and deposition parameters used to calculate gaseous effluent doses vill be calculated using the following equations. Dose calculations vill be performed using hourly meteorological and effluent data. All atmospheric releases at PNPP are considered to be ground-level reler.ses.
- a. Constant Mean Vind Direction Relative Dispersion Factor X/0 = ( .3 ) (T g) (3 3)
(6) (x) (e) l Where X, - she relative dispersion factor at ground level, in s/m 3 T the terrain correction factor, from FSAR Table 2.3-26, g = dimensionless; O = the vind speed (measured at 10m), in m/sl x = the distance of calculation, in m 2.032 - (2/n) u divided by the vidth in radians of a 22.5* sector < 2 2 H % ; c e = the lesser of e, + or (e ,) (3 u) 2n , Vheres H = the building height (44.8m); e e, = the vertical dispersion coefficient, per Regulatory Guide 1.111, in m.
- b. Depleted Relative Dispersion Factor X/Od = (X/0)(DPL))
(A-2) Where X/O d halogens and particulates), in s/a :thedepletedrelativedispersion l
OM12D: ODCH Page : 94 Rev. : 3 DPL) = the ground depletion factor for the "j"th distance, interpolated from Table A-1, dimensionless X/0 = the relative dispersion factor, per equation A-1.
- c. Ground Deposition D/0 = $ (A-3)
(0.3927) (x) Where: D/0-therelativedepositjonperunitarea(forhalogensand particulates), in m~ ; DEP)=thegrounddepositionfactorfortge"j"thdistance, interpolated from Table A-1, in m ; T terrain correction factor, from FSAR Table 2.3-26, g = dimensionless; x = the "j"th distance, in ml 0.3927 - radians per 22.5' sector I
l l 1 Table A-1 i Atmospheric Depletion and Deposition Factors Pasquill Distance (meters)
- Stability i
Class 200 500 1,000 2,000 3,000 6,000 10,000 30,000 50,000 80,000 i All 0.970 0.936 0.930 0.860 0.832 0.770 0.714 0.590 0.517 0.440 Depletion Factors (DFL)) Depositiou Factors (DEF))(a-I) All 1.25E 4 8.0E-5 5.4E-5 3.2E-5 2.6E-5 1.5E-5 9.9E-6 4.5E-6 3.0E-6 2.0E-6 i I i MNO
.g
=
i ) 1
l OH12D: ODCM , Page : 96 ) Rev. : 3 1 The following tables contain annual average atmospheric dispersion and deposition parameters for long-term releases at PNPP. Long-term releases are those that occur greater than 500 hours per year. The highest annual average relative concentration (X/0) value at the site boundary for sectors over land shall be used for radioactive gaseous effluent monitor setpoint calculations. The dispersion model used was X00D00, with PHPP PSAR rite-specific terrain adjustment factors included. Dispersion valuet are based on seven years of meteorological dat6 (May 1, 1972 through April 30, 1974 and September 1, 1977 through August 31, 1982), ground-level releases, sector spread for purge calculations, and twelve vind speed classes.
OM12D: ODCM Pogo : 97 Rev. : 3 Table A-2 l Site Boundary Atmospheric Dispcrsion (X/0) and Deposition Parameters (D/0) for PNPP Unit 1 X/0 D/0 SECTOR DISTANCE (PER 50. METER) (MILES) ( SEC. /. CUE. METER) O.18 5.7E-05 1.6E-07 N 7.9E-08 NNE O.25 1.8E-05 5.8E-06 3.1E-08 NE O.42 1.6E-08 ENE O.67 2.1E-06 O.67 2.2E-06 1.8E-08 1 E 1.3E-OB ESE O.67 1.6E-06 . 1.4E-06 1.1E-08 SE O.79 1.4E-08 SSE O.82 2.2E-06 2.7E-06 1.6E-08 5 0.81 6.8E-09 SSW O.80 1.3E-06 2.3E-06 1.1E-08 SW O.65 1.SE-08 O.56 4,2E-06 WSW 4.6E-08 W O.27 2.5E-05 5.9E-05 8.4E-08 WNW O.18 1.1E-07 NW O.17 6.6E-05 5.9E-05 1.2E-07 ) NNW O.17 l l l l l ) l
- -r , ., -- - - , , _ , - _ . - _
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- -- u, u- g , - - . a . -.
t OM12D: ODCM Page 98 3ev. 3 Table A-3 3 Atmospheric Dispersion (X/Q) as a Function of Distance (s/n ) SECNIR 0. 2 0. 3 . 0. 4 0. 5 0. 6 i (MILES) (MILES) (MILES) (M!LES) (MILES) N 4. 904E-05 2. 453E-05 1. 525E-05 1. 057E-05 7. 918E-06 NNE 2. 656E-05 1. 360E-05 S. 640E-06 6. 082E-06 4. 612E-06 NE 1. 859E-05 9. 760E-06 6. 293E-06 4. 460E-06 3. 383E-06 E4E 1. 327E-Ob 7.129E-06 4. 636E-06 3. 293E-06 2. 490E-06 E 1. 363E-05 7. 362E-06 4. 760E-06 3. 367E-06 2. 530E-06 ,i ESE 1. 025E-05 S. 566E-06 3. 602E-06 2. 54 7E-06 1. 916E-06 , SE 1.113E-05 6. 061E-06 3. 935E-06 2. 788E-06 2.100E-06 ' SSE 1. 894E-05 1. 022E-05 6. 647E-06 4. 718E-06 3. 560E-06 , S 2. 289E-05 1. 227E-05 7. 932E-06 5. 615E-06 4. 238E-06 l SSW 1.142E-05 6. 079E-06 3. 925E-06 2. 777E-06 2. 097E-06 EW 1. 449E-05 7. 663E-06 4. 928E-06 3. 479E-06 2. 622E-06 WSW 2.151E-05 1.111E-05 7. 031E-06 4. 934E-06 3. 733E-06 W 4.184E-05 2. 081 E-05 1. 281 E-05 8. 833E-06 6. 606E-06 WNW 4. 669E-05 2. 298E-05 1.401E-05 9.573E-06 7.093E-06 NW 4.90SE-05 2.423E-05 1.482E-05 1.015E-05 7.521E-06 NNW 4. 580E-05 2. 266E-05 1. 390E-05 9. 541E-06 7. 083E-06 SECTOR 0. 7 0. 8 0. 9 1. 0 1. 1 (MILES) (MILES) (MILES) (MILES) (MILES) ! 6 N 6.138E-06 4. 968E-06 4. 203E-06 3. 636E-06 1. 949E-06 NWE 3. 622E-06 2. 947E-06 2. 481E-06 2.132E-06 1. 278E-06 NE 2. 662E-06 2.165E-06 1. 815E-06 1. 552E-06 9. 269E-07 ENE 1. 957E-06 1. 588E-06 1. 325E-06 1.129E-06 6. 710E-07 E 1. 991E-06 1. 613E-06 1. 343E-06 1.141E-06 6. 768E-07 I ESE 1. 501E-06 1. 21SE-06 1. 010E-06 S. 571E-07 S. 000E-07 SE 1. 647E-06 1. 334E-06 1.108E-06 9. 402E-07 4. 456E-07 SSE 2. 79&E-06 2. 266E-06 1. 885E-06 1. 6012-06 S. 524E-07 5 3. 327E-06 2. 697E-06 2. 247E-06 1. 911E-06 7. 340E-07 ' SSW 1. 646E-06 1. 335E-06 1.114E-06 9. 486E-07 S. 223E-07 SW 2. 053E-06 1. 664E-06 1. 391E-06 1.1SSE-06 S. 667E-07 WSW 2. 927E-06 2. 380E-06 2. 002E-06 1. 719E-06 8. 671E-07 W . 3.110E-06 4.135E-06 3. SO4E-06 3. 036E-06 1. 630E-06 WfdW S. 434E-06 4. 378E-06 3. 719E-06 3. 235E-06 1. 545E-06 NW S. 764E-06 4. 643E-06 3. 941E-06 3. 425E-0$ 1. 952E-06 NNW S. 439E-06 4. 395E-06 3. 720E-06 3. 230E-06 1. 839E-06 I
i l OM12D ODCM Page : 99 Rev. : 3 Table A-3 (Cont.) 3 Atmospheric Dispersion (X/0) as a Function of Distance (s/n ) i I SECTOR 1. 2 1. 3 . 1. 4 1. 5 1. 6 j (MILES) (N!LES) (MILES) (MILES) (MILES) l l N 1.729E-06 1.549E-06 1.399E-06 1.273E-06 1.166E-06 NNE 1.128E-06 1.006E-06 9.050E-07 8.202E-07 7.485E-07 ; NE 8.150E-07 7.243E-07 6.494E-07 5.867E-07 S.340E-07 ENE 3. 878E-07 S.'205E-07 4. 652E-07 4.190E-07 3. 803E-07 i E 5. 917E-07 S. 230E-07 4. 667E-07 4.197E-07 3. 804E-07 ESE 4. 437E-07 3. 919E-07 3. 494E-07 3.140E-07 2. 843E-07 SE 3.891E-07 3.436E-07 3 062E-07 2.751E-07 2.491E-07 ! SSE 4. 829E-07 4. 267E-07 3. 807E-07 3. 423E-07 3.102E-07 5 6. 424E-07 5. 684E-07 5. 076E-07 4. 569E-07 4.145E-07 SSW 4. 576E-07 4. 054E-07 3. 624E-07 3. 266E-07 2. 965E-07 SW 4.976E-07 4.417E-07 3.955E-07 3.570E-07 3.246E-07 WSW 7.648E-07 6.814E-07 6.12SE-07 S.547E-07 S.060E-07 H 1. 44SE-06 1. 299E-06 1.175E-06 1. 070E-06 9. 809E-07 WWW 1.644E-06 1.479E-06 1.341E-06 1.224E-06 1.124E-06 NW 1.739E-06 1.563E-06 1.416E-06 1.292E-06 1.186E-06 NNW 1.637E-06 1.471E-06 1.332E-06 1.214E-06 1.115E-06 l l l SECTOR 1. 7 1. 8 1. 9 2. 0 2. 1 (MILES) (MILES) (MILES) (MILES) (MILES) N 1.074E-06 9.931E-07 9.226E-07 8.604E-07 8.052E-07 NNE 6.067E-07 6'.331E-07 S.864E-07 5.453E-07 S.090E-07 NE 4.036E-07 4.494E-07 4.153E-07 3.854E-07 3.263E-07 ENE 3.471E-07 3.194E-07 2.936E-07 2.718E-07 2.526E-07 E 3.467E-07 3.177E-07 2.925E-07 2.705E-07 2.283E-07 ESE 2. 590E-07 2. 371E-07 2.182E-07 2. 017E-07 1. 871E-07 SE , 2.268E-07 2.076E-07.1.910E-07 1.765E-07 1.637E-07 SEE 2. 927E-07 2. 390E-07 2. 384E-07 2. 205E-07 1. 407E-07 j E 3l78DE-07 3.466E-07 3.194E-07 2.955E-07 1.373E-07 l SSW 2.706E-07 2.494E-07'2.290E-07 2.121E-07 1.409E-07 I SW Q.960C-07 2.727E-07 2.518E-07 2.335E-07 2.173E-07 WEW 4. 439E-07 4. 27SE-07 3. 957E-07 3. 678E-07 3. 303E-07 W 9. 03 7E-07 8. 365E-07 7. 777E-07 7. 258E-07 1.050E-06 WNW 1.038E-06 9.622C-07 8.960E-07 8.375E-07 1.142E-06 NW 1.0T5E-06 1.015E-06 9.445E-07 8.826E-07 8.275E-07 NNW 1. 028E-06 9. 527E-07. 8. 865E-07 8. 281E-07 7. 761E-0,7
OM12DE ODCM Page : 100 Rev. : 3 Table A-3 (Cont.) 3 I Atmospheric Dispersion (X/0) as a Function of Distance (s/n ) ) l l 1 sector 2. 2 2. 3 . 2. 4 2. 5 2. 6 l (MILES) (M!LES) (MILES) (MILES) (MILES) i N 7.560E-07 7.1.8E-07 1 6.720E-07 6.359E-07 6.033E-07 NNE 4. 766E-07 4. 47?C-07 4. 217E-07 3. 982E-07 3. 770E-07 h5 3.050E-07 2.SS9E-07 2.6SSE-07 2.534E.-07 2.395E-07 i ENE 2.356E-07 2.20SE-07. 2.069E-07 1.947E-07 1.837E-07 E 2.127E-07 1.988E-07 1.864E-07 1.752E-07 1.652E-07 ESE 1.743E-07 1.62SE-07 1.32SE-07 1.433E-07 1.351E-07 SE 1.524E-07 1.424E-07 1.334E-07 1.253E-07 1.181E-07 SSE ' 1.311E-07 1.22SE-07 1.149E-07 1.0SOE-07 1.018E-07 l 5 1.2SOE-07 1.197E-07 1.123E-07 1.056E-07 9.963E-OS SSW 1.314E-07 1.230E-07 1.154E-07 1.087E-07 1.02SE-07 SW 2.030E-07 1.902E-07 1.787E-07 1.683E-07 1.590E-07 WSW 4.964E-07 4.661E-07 4.3SSE-07 4.142E-07 3.920E-07 1 W 9.867E-07 9.29hE-07 S.780E-07 8.313E-07 7.891E-07 l WNw 1.075E-06 1.014E-o6 9.SS7E-07 9.0SSE-07 S.636E-07 I NW 7. 782E-07 7. 339E-07 6. 939E-07 6. 576E-07 6. 247E-07 NNW 7.297E-07 6.879E-07 6.502E-07 6.161E-07 S.SS2E-07 SEC70R 2. 7 2. 8 2. 9 3. 0 3.1 (MILES) (M!LES) (MILES) (MILES) (MILES) N S 734E-07 5.460E-07 S.20SE-07 4.976E-07 4.762E-07 NNE q. 576E-07 3. 398E-07 3. 235E-07 3. 086E-07 2. 94SE-07 NC 2.26SE-07 2.152E-07 2.046E-07 1.949E-07 1.859E-07 ENE 1.737E-07 1.64SE-07 1.562E-07 1.4SSE-07 1.415E-07 E 1.560E-07 1.477E-07 1.401E-07 1.331E-07 1.267E-07 ESE 1.275E-07 1.207E-07 1.144E-07 1.087E-07 9.399E-OS SE 1.115E-07 1.054E-07 9.996E-08 9.493E-OS 9.031E-OS SSE 9. 613E-OS 9. 099E-OS 3. 630E-08 8. 200E-08 7. SOSE-OS S 9. 41SE-OS 8. 917E-08 S. 462E-03 S. 044E-08 7. 661E-00 SSW 9. 697E-OS 9.129E-OS 8. 72SE-03 S. 299E-08 7. 907E-03 SW 1.50SE-07 1.428C-07 1.357E-07 1.291E-07 1.231E-07 WSW 3. 716E-07 3. 531E-07 3. 360E-07 3. 204E-07 2. 520E-07 1 W 7.503E-07 7.147E-07 6.820E-07 6.519E-07 S.874E-07 WNW S.220E-07 7.838E-07 7.487E-07 7.164E-07 7.722E-07 , NW S.94SE-07 S.66SE-07 S.413C-07 S.178E-07 S.412E-07 : NNW S.567E-07 S.307E-07.3.067E-07 4.946E-07 4.642E-07 i i i
OM12D ODCH Page : 101 Rev. : 3 Table A-3 (Cont.) 3 Atmospheric Dispersion (X/Q) as a Function of Distance (s/n ) SECTOR 3. 2 3. 3 -
- 3. 4 3. 5 3. 6 (MILES) (MILES) (MILES) (MILES) (MILES)
H 4. 563E-07 4. 379E-07 4. 208E-07 4. 047E-07 3. 899E-07 NNE 2. 820E-07 2. 702E-07 2. 592E-07 2. 489E-07 2 395E-07 NE 1. 77?E-07 1. 700E-07 1.629E-07 1.562E-07 1.501E-07 ENE 1. 350E-07 1, 290E-07 1. 234E-07 1.182E-07 1.135E-07 ) E 1. 203E-07 1.154E-07 1.103E-07 1.056E-07 1.013E-07
.ESE 8. 958E-08 8. 550E-08 8.173E-08 7. 821E-08 7. 499E-08 SE 8. 606E-08 8. 213E-08 7. 849E-08 7. 510E-08 7. 200E-08 SSE 7. 441E-08 7.105E-08 6. 794E-08 6. 503E-08 6. 237E-08 ,
S 7. 307E-08 6. 980E-08 6. 678E-08 6. 395E-08 6.136E-08 j SSN 7. 546E-08 7. 212E-08 6. 902E-08. 6. 613E-08 6. 348E-08 SW 1.176E-07 1.125E-07 1. 07 7E-07 1. 033E-07 9. 922E-08 WSW 2. 410E-07 2. 308E-07 2. 214E-07 2.125E-07 2. 044E-07 W 5. 631E-07 5. 406E-07 5.196E-07 4. 999E-07 4. 818E-07 WNW 7. 409E-07 7.118E-07 6. 848E-07 6. 593E-07 6 359E-07 tr.4 5.192E-07 4. 987E-07 4, 797E-07 4. 618E-07 4. 454E-07 Nf4W 4. 452E-07 4. 276E-07 4.112E-07 3. 958E-07 3. 817E-07 SECTOR 3. 7 3. 8 3, 9 4. 0 4.1 (MILES) (MILES) (MILES) (MILES) (MILES) N 3. 759E-07 3. 628E-07 3. 504E-07 3. 388E-07 2. 981E-07 NNE. 2. 336E-07 2. 222E-07 2.144E-07 2. 070E-07 1. 819E-07 NE 1. 4 4 4E-07 1. 390E-07 1. 339E-07 1. 292E-07 1, 247E-07 ENE 1. 090E-07 1. 048E-07 1. 009E-07 9. 718E-08 9. 373E-08 E 9. 722E-08 9. 342E-08 8. 987E-08 8. 653E-03 8. 341E-08 ESE 7.196E-08 6. 912E-08 6. 647E-08 4. 399E-08 6.166E-08 SE 6. 908C-08 6. 635E-08 6. 380E-08 6.140E-08 5. 378E-08
- SSE 5. 987E-08 5. 753E-08 5. 531E-08 5. 328E-08 5.135E-08 5 5. 892E-08 5. 664E-08 5,451E-08 5. 251E-08 5. 063E-08 SSW 6. 098E-08 5. 865E-08 5. 646E-08 5. 441E-08 5,248E-08 BW 9. 537E-08 9.178E-08 8. 841E-08 8. 325E-08 8. 228E-08 WSW 1. 967E-07 1. 396E-07 1. 828E-07 ' 1. 765E-07 1. 462E-07 W 4. 646E-07 4. 485C-07 4. 334E-07 4.191E-07 3. 043E-07 WNW 6.137E-07 5. 929E-07 5. 733E-07 5. 548E-07 4.180E-07 NW 4. 298E-07 4.151E-07 4. 013E-07 3. 383E-07 3. 761E-07 NNW 3. 482E-07 3. 556E-07 3. 438E-07 3. 326E-07 2. 928E-07
i OM12D: ODCM Page : 102 Rev. : 3 Table A-3 (Cont.) I Atmospheric Dispersion (X/0) as a Function of Distance (s/n ) l 8ECTOR 4. 2 4. 3 -
- 4. 4 4. 5 4, 6 (MILES) (MILES) (MILES) (MILES) (M!LES) l N 2.887E-07 2.798E-07 2.714E-07 2.634E-07 2.559E-07 )
NNE 1.759E-07 1.703E-07 1.4,50E-07 1.599E-07 1.552E-07 ) NE 1.205E-07,1,166E-07 1.128E-07 1.093E-07 1.059E-07 , ENE 9.047E-08 8.740E-08 8.451E-08 8.176E-08 7.921E-08 l E 8.046E-08 7.769E-08 7.508E-08 7.2A0E-08 7.030E-08 i ESE 5. 946E-09 5. 740E-08 5. 54 5E-08 5. 351 E-08 5.189E-08 l SE 5.186E-08 5.005E-08 4.835E-08 4.673E-08 4.523E-08 SSE 4. 954E-08 4. 783E-08 4. 622E-08 4. 469E-08 4. 327E-08 5 4.886E 08 4.719E-08 4.562E-08 4.413E-08 4.274E-08 SSR 5. 067E-08 4. 896E-08 4. 735E-08 4. 581E-08 4. 439E-08 SW 7.94SE-08 7.684E-08 7.435E-08 7.198E-08 6.978E-08 W5W !.413E-07 1.368E-07 1.325E-07 1.284E-07 1.246E-07 ) W 2.948E-07 2.85BE-07 2.773C-07 2.69:E-07 2.616E-07 Wf!H 4.051E-07 3.930E-07 3.815E-07 3.706E-07 3.603E-07 NW 3. 64!E-07 3. 536E-07 3. 432E-07 3. 333E-07 3. 241E-07
- NNW 2. 837E-07 2. 752E-07 2. 671E-07 2. 593E-07 2. 521E-07 SECTOR . 4, 7 4. 8 4. 9 5. 0 (MILES) (MILES) (M!LES) (MILES)
N 2.487E-07 2.419E-07 2.354E-07 2.292E-07 NNE 1.507E-07 1.464E-07 1.423E-07 1.384E-07 NC 1.028E-07 9.975E-08 9.689E-05 9.416E-08 ENE 7. 676E-08 7. 443E-08 7. 223E-08 7. 014E-08 E 6. 809E-08 6. 600E-08 6. 402E-08 6. 214E-08 ESE 5. 025C-08 4. 869E-05 4. 722E-08 4. 582E-08 SE 4. 379E-08 4. 244E-08 4.115E-08 3. 992E-08 4.191E-08 4; 063E-08 3. 941E-08 3 32SE-08 l SSE i 1 5 4.141E-08 4.015E-08 3.896E-08 3.782E-08 l 55W 4.302E-08 4.173E-05 4.05CE-08 3.934E-08 l SW 6.767E-08 6.567E-05 6.377E-08 6.196E-08 i WSW 1.210E-07 1.175E-07 1.142E-07 1.110E-07 N 2.543E-07 2.474E-07 2.403E-07 2.345E-07 WftW 3. 505E-07 3. 411E-07 3. 322E-07 3. 237E-07 NW 3.152C-07 3. 068E-07 2. 987E-07 2. 910E-07 i NNW 2 452E-07 2 386E-07 2.323E-07 2 263E-07 1 4
ON12D: ODQi Pcge : 103 Rev. 3 Table A-4 Atmospheric Dispersion (D/0) as a Function of Distance (m-2)
- 0. 3 0, 4 0. 5 0. 6 SECTOR 0. 2 .
(MILES) (MILES) (M!LES) (MILES) .AILES) , N 1. 396E-07 7. 578E-03 4. 936E-08 3. 383E-03 2. 516E-03 NNE 1.107E-07 6. 008E-08 3. 934E-04 2. 682E-08 1. 995E-05 NE 9.733E-08 5.284E-09 3.372E-08 2.359E-08 1.75?E-08 ENE l'. 067E-07 5. 795E-00 3. 698E-OS 2. 587E-08 1. 924E-08 E 1.184E-07 6.429E-08 4.103E-OS 2.870E-00 2.13SE-OS ESE 3. 56SE-OS 4. 913E-08 3. 071E-03 2.149E-08 1. 598E-05 ' SE 9. 402E-08 S.10SE-08 3.' 258E-05 2. 279E-08 1. 695E-OS SSE 1.338E-07 7.266E-09 4.637E-OS 3.244E-08 2.413E-05 5 1.429E-07 7.757E-08 4.951E-08 3.463E-08 2.576E-08 SSW 6.094E-08 3.309E-OS 2.111E-08 1.477E-05 1.099E-05 7.267E-05 3.94SE-03 2.518E-08 1.761E-08 1.310E-08 SW WSW 7.117E-09 3.864E-08 2.466E-OS 1.72SE-08 1.283E-08 W 7.129E-08 3.870E-08 2.470E-00 1.728C-08 1.28SE-08 WNW 6.970E-08 3.784E-08 2.41SE-08 1.639E-08 1.236E-08 NU S 904E-08 4.834E-09 3.08SE-05 2.158E-09 1.60SE-08 NNW 9.623E-08 S.22SE-08 3.334E-09 2.332E-05 1.735E-05 : I I SICTOR 0. 7 0. 8 0. 9 1. 0 1.1 (MILES) (mil f.S) (MILES) (MILES) (MILES) l N 1.954E-08 1.560E-02 1.277E-09 1.069E-08 5.54SE-09 NNE 1.549E-05 1.237E-08 1.013E-08 8.46SE-09 4.94SE-09 1
- NE 1. 362E-09 1. 088E-08 S. 907E-09 7. 44SE-09 4. 350E-09 ENE 1, 494E-05 1.193E-08 9. 76SE-09 0.164E-09 4. 770E-09 E 1.658E-09 1.323E-09 1.084E-08 9.053E-09 5.292E-09 !
ESE 1.241E-08 9.90SE-09 3.112E-09 6.781E-09 3.961E-09 ' 4 SC " 1.316E-08 1.051E-08 8.60SE-09 7.192E-09 3.361E-09 55E 1. 974E-08 1. 496E-08 1. 22SE-OS 1. 024E-OS 3. 4SOE-09 E 2.000E-09 1.597E-08 1.300E-00'1.093E-08 4.120E-09 i SSW S. 531E-09 6. 810E-09 S. 377E-09 4. 662E-09 2. 521E-09 sW 1. 017E-OS 3.120E-09 6. 651E-09 5. SS9E-09 2. sv8E-09 WSW 9.963E-09 7.933E-09 6.313E-09 5.444E-09 2.678E-09 W 9. 980E-09 7. 966E-09 6. 524E-09 5. 453E-09 2. 832E-09 WNW 9. 757E-09 7. 788E-09 6 379E-09 5. 332E-09 2. 932E-09 NW 1.246E-00 9.949E-09 8.140E-09 6.811E-09 3.74SE-09 NNW 1.347E-05 1.075E-08 3.007E-09 7.361E-09 4.047E-09 I i I
OM12D: ODOi Fage : 104 Rev. : 3 Table A-4 (Cont.) Atmospheric Deposition (D/0) as a Function of Distance (a-2) SECTOR 1. 2 1. 3 . 1. 4 1. 3 1. 6 (MILES) (MILES) (MILES) (MILES) (MILES) N 4. 777E-09 4.163E-09 3. 664E-09 3. 252E-09 2. 910E-09 NNE 4. 260E-09 3. 713C-09 3. 268E-09 2. 900E-09 2. 595E-09 NE 3. 747E-09 3. 26SE-09 2. 874E-09 2. SSIE-09 2. 283E-09 ENE 4.109E-09 3. 581E-09 3.151E-09 2. 797E-09 2. 503E-09 E 4. SS9E-09 3. 973E-09 3. 497E-09 3.104E-09 2. 777E-09 ESE 3. 413E-09 2. 974E-09 2. 617E-09 2. 323E-09 2. 079E-09 SE 2. 896E-09 2. 524E-09 2. 221E-09 1. 971E-09 1. 764E-09 SSE 2. 998E-09 2. 612E-09 2. 299E-09 2. 041E-09 1. 526E-09 5 3. SS6E-09 3. 099E-09 2. 727E-09 2. 421E-09 2.166E-09 SSW 2.172E-09 1. 892E-09 1.666E-09 1. 478E-09 1. 323E-09 SW 2.238E-09 1.930E-09 1. 717E-09 1. 324E-09 1. 363E-09 WSW 2.307E-09 2.011E-09 1. 770E-09 1. 571E-09 1. 406E-09 W 2.440E-09 2.126E-09 1. 871E-09 1. 661E-09 1. 486E-09 WNW 2. 525E-09 2. 201E-09 1.937E-09 1.719E-09 1.538E-09 NW 3. 226E-09 2. 811E-09 2. 474E-09 2.196E-09 1. 965E-09 NNW 3, 487E-09 3. 039E-09 2. 674E-09 2. 374E-09 2.124E-09 SECTOR 2. 0
- 1. 7 1. 9 1. 9 2.1 (MILES) (MILES) (MILES) (MILES) (MILES)
N 2. 619E-09 2. 371E-09 2.1 SBE-09 '1. 973E-09 1. 912E*09 flNE 2. 336E-09 2.115E-09 1. 925E-09 1. 760E-09 1. 61&E-09 NE 2.055E-09 1.860E-09 1. 693E-09 1. 540E-09 1. 292E-09 ENE 2. 253E-09 2. 040E-09 1. SS&E-09 1. 697E-DV 1. 353E-09
. E 2. 500E-09 2. 263E-09 2. 059E-0? 1. 883E-09 1. 572E-09 ESC 1. 871E-09 1. 694E-09 1. 542E-09 1. 410E-09 1. 294E-09 SE 1. 383E-09 1. 437E-09 1. 303E-09 1.196E ,09 1. 098E-09 SSE 1.644E-09 1. 48BE-09 1. 354E-09 1. 238E-b? 7. 316E-10 5
- 1. 930E-09 1. 765E-09 1, 406E-09 1. 469E-09 6. 743E-10 SSW 1.191E-09 1. 078C-09 9. 510E-10 5. 969E-10 S. 983E-10 SW 1. 227E-09 1.111E-09 1.011E-09 9.244E-10 3.488E-10 WSW 1. 265E-09 1.145E-09 1. 042E-09 9. 330E-10 1. 352E-09 W 1. 338E-09 1. 211E-09 1.102E-09 1. 008E-09 1. 430E-09 WNW 1. 385E-09 1. 254E-09 1.141E-09 1. 043E-09 1. 393E-09 NW 1 769E-09' 1. 601E-09 1. 4 37E-09 1.333E-09 1.223E-09 NffW 1. 912E-09 1. 731E-09 1.573E-09 1.440E-09 1.322C-09 i
OM12Ds ODCH Page : 105 Rev. : 3 Table A-4 (Cont.) Atmospheric Deposition (D/Q) as a Function of Distance (a~2) SEGtR 2. 2 2. 3 . 2. 4 2. 5 2. 6 (MILES) (MILES) (MILES) (MILES) (MILES) l
- \
l N 1.670E-09 1.544E-09 1.433E-09 1.334E-09 1.2455-09 1 NNF 1.489E-09 1.377E-09 1.278E-09 1.189E-09 1.110E-09 NC 1.191E-09 1.101E-09 1.022E-09 9.511E-10 S.379E-10 l ENE 1.436E-09 1.32SE-09 1.233E-09 1.147E-09 1.071E-09 ! E 1.44?E-09 1.340E-09 1.243E-09 1.157E-09 1.0SOE-09 CSE 1.193E-09 1.103E-09 1. 024E-09 9. 528E-10 3. 395E-10 SE 1.012E-09 9.362E-10 9.687E-10 3.085E-10 7.548E-10 . SSE 7.204E-10 6.663E-10 6.193E-10 5.754E-10 3.372E-10 5 6.215E-10 5.749E-10 5.334E-10 4.964E-10 4.634E-10 SSW 3.422E-10 5.015E-10 4.653E-10 4.333E-10 4.043E-10 SW 7.323E-10 7.236E-10 6.714E-10 6.249E-10 5.834E-10 WSW 1.246E-09 1.153E-09 1.070E-09 9.956E-10 9.294E-10 W 1.318E-09 1.219E-09 1.133E-09 1.053E-09 9.327E-10 WNW 1.284E-09 1.188E-09 1.102E-09 1.026E-09 9.575E-10 NW 1.128E-09 1.043E-09 9.678E-10 9.007E-10 3.409E-10 NNW 1.219E-09 1.127E-09 1.046E-09 9.735E-10 9.089E-10 1 l 1 SECTOR 2. 7 2. 8 2. 9 3. 0 3.1 I i (MILES) (MILES) (MILES) (MILES) (MILES) l l N 1.165E-09 1.092E-09 1.026E-09 9.666E-10 9.120E-10 NNE 1.039E-09 9.742E-10 9.155E-10 3.621E-10 3.134E-10 l NE 3.307E-10 7.739E-10 7.320E-10 6.393E-10 6.SO4E-10 i < ENT 1.002E-09 9.396E-10 3.330E-10 9.315E-10 7.845E-10 E - 1.011E-09 9.477E-10 S.906E-10 S.387E-10 7.913E-10 ESE 3.322E-10 7.SO4E-10 7.334E-10 6.906E-10 5.923E-10 SE 7.061E-10 6.622E-10 6.223E-10 3.360E-10 S.529E-10 - SSE' 3.026E-10 4.713E-10 4.429E-10 4.171E-10 3.935E-10 5 4.336E-10 4.066E-10 3.821E-10 3.598E-10 3.395E-10 SSW 3.782E-10 3.547E-10 3.333E-10 3.139E-10 2.961E-10
, EW S.453E-10 S.118E-10 4.810E-10 4.529E-10 4.273E-10 WSW 3.hT5E-10 3.154E-10 7.663E-10 7.216E-10 S.607E-10 W 9.194E-10 9.621E-10 3.102C-10 7.630E-10 6.775E-10 WNW 3.95SC-10 9.400E-10 7.894E-10 7.434E-10 7.890E-10 NW 7.367E-10 7.377E-10 6.933E-10 6.52SE-10 6.719E-10 i NUW S.503E-10 7.973E-10 7.493E-10 7.036E-10 6.657E-10 1
I l OM12D: ODCH Page a 106 i Rev. : 3 l { Table A-4 (Cont.) Atmospheric Deposition (D/0) as a Function of Distance (a-2) l SECTOR 3. 2 3. 3 . 3. 4 3, 5 3. & : (MILES) (MILES) (MILES) (MILES) (MILES) l N 8.620E-10 8.161E-10 7.739E-10 7.347E-10 6.991E-10 NNE 7.699E-10 7.279E-10 6.902E-10 6.552E-10 6.235E-10 NE 6.147E-10 5.820E-10 5.518E-10 5.239E-10 4.955E-10 ENE 7.410E-10 7.020E-10 6.657E-10 6.320E-10 6.014E-10 E 7.479E-10 7.081E-10 6.714E-10 6.374E-10 6.066E-10 ESE 5.398E-10 5.300E-10 5.026E-10 4.771E-10 4.541E-10 SE 5. 225E-10 4. 947E-10 4. 691E-10 4. 454E-10 4. 238E-10 SSE 3.719E-10 3.521E-10 3.339E-10 3.170E-10 3.016E-10 S 3. 209E-10 3. 038E-10 2. 880E-10 2. 735E-10 2. 602E-10 SSW 2.799E-10 2.650E-10 2.513E-10 2.386E-10 2.270E-10 SW 4. 039E-10 3. 524E-10 3. 626E-10 3. 4 42E-10 3. 276E-10 WSW 3.299E-10 5.017E-10 4.757E-10 4.514E-10 4.298E-10 W 6.403E-10 4.062E-10 5,749E-10 5.458E-10 5.193E-10 WNW 7.457E-10 7.060E-10 6.695E-10 6.356E-10 6.048E-10 NW 6.351E-10 6.013E-10 5.702E-10 5.413E-10 5.151E-10 NNW 6.272E-10 5.957E-10 5.649E-10 5.363E-10 5.103E-10 SECTOR 3. 7 3. 8 3. 9 4. 0 4.1 ' (MILES) (MILES) (MILES) (MILES) (M!LES) l 1
, N 4. 657E-10 6. 347E-10 6. 059E-10 5. 791E-10 5. 036E-10 NNE 5. 937E-10 5. 661E-10 5. 404E-10 5.165E-10 4. 492E-10 NE '
4.747E-10 4.5265-10 4.321E-10 4.129E-10 3.951E-10 ENE 5. 727E-10 3. 460E-10 5. 212E-10 4. 981E-10 4. 766E-10 E . 3.716E-10 3.507E-10 5.257E-10 5.024E-10 4.807E-10 ESE 4.324E-10 4.122E-10 3.935E-10 3.761E-10 3.598E-10 SE 4. 036E-10 3. 848E-10 3. 673E-10 3. 510E-10 3. 053E-10 SSE 2.372E-10 2.739E-10 2.614E-10 2.498E-10 2.390E-10 E 2. 478E-10 2. 363E-10 2. 255E-10 2.155E-10 2. 062E-10 SSW 2.162C-10 2.061E-10 1.968E-10 1.880E-10 1.799E-10 BW 3.119E-10 2.974E-10 2.339E-10 2.713E-10 2.596E-10 WSW 4.093E-10 3.902E-10 3.725E-10 3.560E-10 2.919E-10 W 4.945E-10 4.715E-10 4.501E-10 4.302E-10 3.087E-10 WNW 3.759E-10 3.491E-10 5.242E-10 5.010E-10 3.728E-10 NW 4.90SE-10 4.477E-10 4.464E-10 4.266E-10 4.082E-10 NNW 4. 859E-10 4. 633E-10 4. 423E-10 4. 227E-10 3. 676E-10
OM12D: ODCM Page : 107 Rev. : 3 Table A-4 (Cont.) Atmospheric Deposition (D/Q) as a Function of Distance (a-2) SECTOR 4. 2 4. 3 . 4. 4 4. 5 4. 6 (MILES) (MILES) (MILES) (MILES) (MILES) N 4.823E-10 4.624E-10 4.437E-10 4.260E-10 4.097E-10 NNE 4. 302E-10 4.124E-10 3. 9 57E-10 3. 800E-10 3. 654E-10 NE 3.784E-10 3.627E-10 3.400E-10 3.342E-10 3.214E-10 ENE 4.564E-10 4.375E-10 4.19EE-10 4.031E-10 3.877E-10 E 4. 603E-10 4. 413E- 10 4. 234E-10 4. 066E-10 3. 910E-10 ESE 3.446E-10 3.4303E-10 3.170E-10 3.044E-10 2.927E-10 ' SE 2.924E-10 2.803E-10 2.690E-10 2.583E-10 2.484E-10 SSE 2.289E-10 2.195E-10 2.106E-10 2.022E-10 1.944E-10 S 1.973E-10 1.893E-10 1.817E-10 1.744E-10 1.677E-10 SSU 1.723E-10 1.652E-10 1.SBSE-10 1.522E-10 1.463E-10 SW 2.486E-10 2.383E-10 2.287E-10 2.196E-10 2.112E-10 WSW 2.796E-10 2.6SOE-10 2.572E-10 2.469E-10 2.375E-10 W 2.956E-10 2.834E-10 2.719E-10 2.611E-10 2.511E-10 WNW 3.570E-10 3.422E-10 3.284E-10 3.133E-10 3.032E-10 NW 3.909E-10 3.747E-10 3.396E-10 3.433E-10 3.320E-10 NMW 3.321E-10 3.373E-10 3.239E-10 3.110E-10 2.991E-10 i l l l SECTOR 4, 7 4. B 4. 9 S. 0 (MILES) (MILES) (MILES) (M!LES) l N 3.941E-10 3.795E-10 3.656E-10 3.525E-10 NNE 3.515E-10 3.384E-10 3.261E-10 3.144E-10 NE 3.092E-10 2.977E-10 2.868E-10 2.76SE-10 ENE 3.729E-10 3.391E-10 3.460E-10 3.336E-10 E 3.762E-10 3.622E-10 3.489E-10 3.364E-10 ESE 2.81&E-10 2.711E-10 2.412E-10 2.519E-10 Sh 2.389E-10 2.300E-10 2.236E-10 2.137E-10 SSE 1.871E-10 1.831E-10 1.735E-10 1.673E-10 5 1.614E-10 1.554E-10 1.497E-10 1.443E-10 SSW 1.408E-10 1.355E-10 1.306E-10 1.259E-10 EW 2. 031E-10 1. 956E-10 1. 884E-10 1. 817E- 10 WSW 2. 28SE-10 2.199E-10 2.119E-10 2. 043C-10 l W 2.415E-10 2.326E-10 2.241E-10 2.160E-10 l WNW 2.917E-10 2.839E-10 2.706E-10 2.609E-10 1
- NW 3.194E-10 3.075E-10 2.963E-10 2.857E-10 l NNW 2.877E-10 2.770E-10 2.669E-10 2.S73E-10 )
i 1 l _ _ _ _ _ _ - _ _ _ . _ _ _ _ _ _ __ _ _ _. _ . __ _ _ _ - _ _ _ _ _ . _ _ _ _ _
OM12D: ODCH Page : 108 Rev. : 3 Appendix B Lover Limit of Detection 1
OM12Da ODCH Page : 109 Rev. : :3 The lover limit of detection (LLD) is the smallest concentration of radioactive material in a sample that vill be detected with a;95 percent probability with a 5 percent probability of falsely concluding that a blank observation represents a "real" signal. For a measurement system (which may include radiochemical separation) based on gross beta, gross alpha, liquid scintillation, or other analyses where a background count determined by a separate measurement with no sample (or blank sample) is subtracted from the gross sample count to obtain a net count due to sample activity: b b 3.3 . (B-1) I g,
's b (C)(E)(V)(Y,) exp (4 ot)
Vhere LLD = the "apriori" lover limit of detection, as defined above; C the conversion factor of transformations per unit time per uCi or pCi; E = the detector efficiency: rb the background count rate in units of transformations per unit time ' t b = the counting time of backgrounds t, - the counting time of the sample V - the sample size, in units of mass or volume Y* - the fract mal radiochemical sample collection or concentrr .m yield (when applicable); at for plant effluents, the elapsed time between the midpoint of sample collection and time of counting for environmental samples, the elapsed time between sample I collection (or and of the sample collection period) and i time of counting: A the radio 3ctive decay constant for thn radionuclide in ! question. 1
y I OM12D: ODCM Page : 110 J Rev. : 3 for the purpose of routine analyses, count times for both the sample (s) and background (s) are equal. This satisfies the given Technical , Specification lover limit of detection definition, as the numerator of equation B-1 simplifies to 4.66 Sg, where S b is the standard deviation of the background count rate or the Eount rate of a blank sample as appropriate. The LLD is defined as an "apriori" (before the fact) limit representing the capability of a measurement system and not as an "a posteriori" (after the fact) lisiit for a particular measurement. For gamma ray spectroscopy analyses (Canberra Spectran - F Version 2): L D exp (0.693 ot/t %) (C)(E)(t)(V)(Y )(Yy) ] e Where LLD = the lover limit of detection, in 901 or pCi per unit mass or volume C = the conversion factor of transformations per unit time per uCi or pCil J E = the detector efficiency for the energy in questions : t = the data collection (counting) time of samples l l t 6 = the half-life of the radionuclide in question: { V = the sample size, in units of mass or volume Y* = the fractional radiochemical, sample collection, or con-centration yield (when applicable): Yy = the yield of the gamma ray in question; at - for plant effluents the elapsed time between midpoint of sample collection and time of counting for environmental samples, the elapsed time between sample collection (or end of the sample collection period) and the tiee of counting: LD = the detection limit
=k 2 + 2k [ (1 + [ ) (8 3+B)+I+e 2
(B-2a) f l
OH12D: ODCM Page : 111 Rev. 3 Where: a n" background channels below the 83 - the peaknumber due toofCompton counts inscattering, etc., determined at the same time a photopeak is seasured; B2 the number of counts in the "n" background channels above the peaks k - an abscissa of the normal distribution corresponding to confidence level,
- 1.645 at a confidence level of 95%
I - the measured value of interference in the photopeak of interest due to environmental background, detector contamination, etc., determined by a separate measurement with no sample N the number of channels in the photopeak of interest n - the number of background channels on each side of the photopeak of interesti ay - the standard deviation of I. Typical values of E, V, Y, and at shall be used in the calculation. In calculating the LLD for a radionuclide determined by gamma-ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples (e.g., potassium-40 in milk samples). Analyses shall be performed in such a manner that the LLD's listed in Tables 4.11.1.1.1-1, 4.11.2.1.2-1, and 4.12.1-1 of the Radiological Effluent Technical Specifications for the Ferry Nuclear Power Plant vill be achieved under routine conditions. Occasionally, background
- fluctuations, unavoidably small sample sizes, the presence of interfering '
nuclides, or other uncontrollable circumstances may render these LLDs i
- l. unachievable. In such cases, the contributing factors vill be identified '
; and described in the Annual Radiological Environmental Operating Report
- or the Semiannual Radioactive Effluent Release Report.
l 4 i l i l
OM12D: ODCH Page : 112 Rev. : 3 REFERENCES
- 1. Title 10 "Energy," Chapter 1, Code of Federal Regulations: Part 20, U.S. Government Printing Office, Washington, C,C. 20402, January 1, 1984.
- 2. Title 10. "Energy," Chapter 1, Code ' Federal Regulations: Part 50; U.S. Government Printing Office, Washington, D.C. 20402, January 1, 1984.
- 3. Title 40, "Protection of Environment," Ohapter 1, Code of Federal Regulations, Part 190, Federal Registet. Vol. 42, Vashington, D.C.
20402, January 13, 1977.
- 4. U.S. Nuclear Regulatory Commission, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," USNRC NUREG-0133, Vashington, D.C. 20555, October, 1981.
- 5. U.S. Nuclear Regulatory Commission, "Draft Radiological Effluent Technical Specifications for PVR's," USNRC NUREG-0473, Revision 2, Vashint'on, D.C. 20555, February, 1980.
- 6. Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Vastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Vater-Cooled Nuclear Power Plants," Revision 1. U.S. Nuclear Regulatory Commission, Vashington, D.C. 20555, June 1974.
- 7. Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1," Revision 0, U.S.
Nuclear Regulatory Commission, Vashington, D.C. 20555, March 1976.
- 8. Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1. U.S.
Nuclear Regulatory Commission, Vashington, D.C. 20555, October 1977.
- 9. Regulatory Guide 1.111. "Methods for Estimating Atmo cheric Transport and Dispersion of Gaseous Effluents in Rou.ine Releases from Light-Vater-cooled Reactors," Revision 1, U.S. Nuclear Regulatory Commission, Vashington, D.C. 20555, July 1977.
- 10. Regulstory Guide 1.113. "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," Revision 1. U.S. Nuclear Regulatory Commission, Vashington, D.C. 20555, April 1977.
9
/
OM12D ODCM Page : 113 - LAST Rev. : 3 REFERENCES (Cont.)
- 11. Regulatory Guide 4.15, douality Assurance for Radiological Monitoring Programs (Normal Operation) - Effluent Streams and the Environment," U.S. Nuclear Regulatory Commission, Vashington, D.C.
20555, February 1979.
- 12. U.S. Nuclear Regulatory Commission, "Branch Technical Position,"
Revision 1, Vashington, D.C. 20555, November 1979.
- 13. Perry Nuclear Power Plant, Unit 1 and 2. "Final Safety Analysis Report," Amendment 14, The Cleveland Electric Illuminating Company, Perry, Ohio 44081, August 1984.
- 14. Perry Nuclear Pover Plant, Units 1 and 2, "Environmental Report, Operating License Stage," Supplement 3 The Cleveland Electric Illuminating Company, Perry, Ohio 44081, November 1981.
- 15. Perry Nuclear Pover Plant, Units 1 and 2 "Radiological Environmental Monitoring Program Manual," The Cleveland Electric Illuminating Company, Perry, Ohio 44081, February 1985.
- 16. "Midas User's Manual, for the Cleveland Electric Illuminating Company, Perry Nuclear Power Plant," Pickard, Love and Garrick, Vashington, D.C. 20036, July 1983.
l
; 17. Kocher, D.C., "Radioactive Decay Data Tables," Technical Information center, U.S. Department of Energy, Springfield, Virginia 22161, September 1985.
b j I e t i i I 1 j
Attachment 9 Annual Land Use Census l l t l l
ANNUAL LAND-USE REPORT 1988 Prepared by: x - 7 4 W hn A. Lepo "/ [Dyte I Reviewed by: &
' Richard R. Bowers A 7!M' 3h Date l
l WN Ray F.CZuckdr WE '/// Date i P I l
\
b THE PERRY NUCLEAR POVER PLANT LAND USE SURVEY 1988 , I. INTRODUCTION The Perry Nuclear Power Plant is a tvin unit BVR plant with a capacity to generate 1205 MVe Net per unit. The as'n condenser circulating vater is cooled by a closed-loop natural draft cooling tower system. The plant is located on Lake Erie, on approximately 1100 acres about thirty-five miles northeast of Cleveland, Ohio. , The Unit I reactor has accumulated 5799.2 GVHr of operating capacity as of June 30th of this year. The construction of Unit 2 is on indefinite hold. All nuclear facilities have the potential of releasing radioactive material to 3 the environment. To assess the impact of this release, it is important to understand site-specific parameters within the communities around the plant. Some of these parameters include residents themselves and food products. The ; people who live, work, and farm within a community have a great influence on t how the land is used. The purpose of the land use survey is to determine the use of land vithin the i vicinity of the plant and to identify any changes. The information obtained i in this survey can be used in future dose pathway assessments. This survey was conducted in accordance with 10 CFR 50 Appendix I, "Domestic Licensing of Production and Utilization Facilities", and the PNPP Technical Specifications, Section 12, "Radiological Environmental Monitoring Program". II. METHODOLOGY t i The procedure for conducting the Land Use Survey is PNPP RENP Instructions 0017, "Land Use Survey For Residence, Gardens and Milk-Producing Animals" Revision O. The 1988 survey was conducted from June 3rd to June 14th. i The land use survey was conducted by traveling over major roads within the five mile radius of the plant. In residential areas (i.e., sub-divisions, small communities, and trailer parks), roads vere selected at random for the survey. . The nearest resident and the nearest garden vere determined by visual inspection. A map with 16 equal sectors (22.5 degrees per sector) vas used to determine the nearest resident and nearest garden by sector. Dairy cows, milking goats, and non-dairy animals were identified by visual roadside inspection, previous years Land Use information and information l obtained from local residents. .- I ] \ 1 l
Agricultural growers vere identified by commercial roadside signs. A visual inspection of the area as well as the description on the roadside advertisement was used to determine the nature of the product grown on the property. This report includes a section covering general observations of the area during the survey. III. RESULTS AND DISCUSSION This survey reports the findings of the nearest resident and nearest garden by sector, as well as dairy animals and non-dairy animals within the five mile radius of the plant. The survey included agricultural grovers within the five mile vicinity of the plant. Figure 1 is a map shoving these locations by symbols. The surveillance of dairy animals, non-dairy animals that consume vegetation, and agricultural grovers vill allow close monitoring of the food-chain pathway. The dispersion and deposition values used in this report are taken from Appendix A of the PNPP Offsite Dose Calculation Manual (ODCM). These values represent the seven year annual average based on the seven year onsite meteorological data base. (REF. 1)
- 1. Nearest Resident The nearest residents are shown in Table 1 which includes direction, address and distance, dispersion value (X/0) and map locator for easy reference to Figure 1.
The resident at 3121 Center Road was identified as having the most restrictive dispersion value (X/0) as a function of distance with respect to other sectors. The historical trend of the nearest residents, by sector, since 1984, shovs that only the residents in the South sector and the Northeast sector have changed.
- 2. Nearest Garden The nearest gardens are shovn in Table 2 which includes direction, addrcss and distance, deposition value (D/0) and map locator for easy reference to Figure 1.
The nearest garden with the highest deposition value as a function of distance with respect to other sectors was 3121 Center Rd. Last year the garden at 3119 Paraly Road had the highest D/0 value. The residence at 3121 vas vacant last year and did not have a garden. ; l I I l
The historical review of PNPP Land Use Surveys since 1984 shows that several gardens have changed over this period. The owners of these gardens have occasionally chosen not to grow a garden during a particular year for personal reasons or the property has been vacant.
- 3. Dairy Animals Dairy animals were confirmed from lass ,, ear's annual land use survey and a search was made within the five mile radius of the plant to identify new locations.
The dairy animals are listed in Table 3 by direction, location, deposition (D/0) value, number / type of animals, map locator, and comments. The ~iocation at 3291 Paraly Rd., N. Perry was identified as having the highest deposition value as a function of distance with respect to other sectors. This location has been contacted for participation in the PNPP Radiological Environmental Monitoring Program for milk sampling on several occasions. The j owners at this residence declined to participate. (Table 3) The locations at map locator 23, 24, and 28 have been the most consistent in the past few years in supplying milk samples. A new location in the SE sector, 7.4 miles from the plant on 5888 Devey Road in Madison was added to the milk sampling program this year.
- 4. Non-Dairy Animals Non-Dairy Animals, such as rabbits, cattle and pigs, are animals that consume vegetation (including pasture grass) as their main staple diet and can be consumed by man. The major food chain pathway is the air-to-pasture grass-to-animal->to-man.
Table 4 shows these animals by direction, location, deposition value, number / type of animal and 'op locator. This table is updated every year to reflect new locations, as well as locations that no longer have their livestock. The number of animals and type of animals change from year-to-year as owners purchase and sull their livestock. ' A total of 24 locations were identified in the 1988 Land Use Survey. This is the same number of locations that vere identified in the 1987 Land Use Survey,
- 5. Agricultural Grovers
! Agricultural growers are commercial businesses that grov erops or plants. These businesses are ideatifiei oy roadside signs within the five mile 1 vicinity of the plant. Ti:e two major pathways are: 1) air-to-crop-to-man and
- 2) air-to-soil-to-crop-to-asn.
The identifica*. ion of agricultural grovers within the vicinity of PNPP vill ', help in determining how the land is being used in the area. , i !
The agricultural grovers are depicted in Ta' ole 5. They r.re listed '- 'ame, address, city, sector / distance, deposition value, type of grover ano . locator. Some agricultural grovers have very large properties. In some cases, this property extends r"gr many acres which crosses into other sectors. Also, the owners have property scattered over the Lake County aret. The deposition value assigned to these locations only represent the point at share the property was identified during the survey. A total of 45 agricultural grovers were identified in this survey. Some of these locations may be owned by the same person or corporation, or may be separate fawily entities (i.e., brother ovnership--see map locator 55 and 84). The majority of these locations are nurseries, vith some nurseries also selling produce or fruit. The number of nurseries in this survey represented 73% of the total agricultural grovers.
- 6. General Observations All major roads within the five mile radius of the plant vere covered during this survey. It should be noted that the land use within this radius varied quite differently in some areas.
l For example, areas between 4 miles and 5 miles in the ENE, VSV, SV, and SSV sectors from the plant, are highly populated residential areas. l The area between 3 miles and 4 miles in the VSV sector is primarily heavy l industrial. The land along Route 20 or N. Ridge Rd. is used mainly for I commercial operations. This area is considered to be moderate to light in land use. The remaining ar'en within the five mile radius of the pleas is rural farm land i vith moderate to lov population density areas. No major residential, commercial or industrial development under construction was observed during this survey. Some single homes in different areas in the process of being j built were observed in this survey, 1 IV. CONCLUSION It can be concluded from this survey that the land within the five mile radius ' of the plant has not changed significantly since 1984. The changes noted in this report can be considered ninor and subject to normal fluctuations in the methodology. The major land use within the area is considered to be commercial nurseries, which includes wholesale and retail.
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i , i LAND USE SURVEY 1988
! REPPJtENCES
! 1. PERRY NUCI, EAR POVER PLANT OPERATIONS MANUAL, OM12D, 0FFSITE DOSE ' CALCUiATION MANUAL, APPENDIE At ATMOSFJERIC DISPERSION AND DEPOSITION M TERS, REV. 3, PC. 92-107.
- 2. KASSER, BELENE L., PERRY NUCLEAR POWER PLANT LAND-USE SURVEY POR 1986, NUS-4739, PREPARED BY NUS CORPC'.ATION FOR THE CLEVELAND ELECTRIC ILLUMINATING COMPANT, NOVEMBER 1986.
- 3. VEBB, J., ll2MORANDUM "E" - 50/2366 FROM J. VEBB TO L.O. BECK: ,
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM, MILK SAMPLES, THE CLEVELAND ELELTRIC ILLUMINATING COMPANY, DECEMBER 27, 1985.
- 4. VEBB, J., PERRY NUCLEAR POVER PLANT LAND-USE SURVEY FOR 1987 1
- 5. RAINES & COMPANY INCORPORATED, CROSS DIRECTORY FOR LAKE AND GEAUGA COUNIIES 4 i f
I ( i 1 i I 5. I J l i .1 1 r p - o i
! l i 1
l J TABLE 1 l $ NEAREST RESIDENT BY SECTOR AND DISFERSION (X'0) VALUE 1 Nearest Rcsident IIII ) X/0 Value Map Direction (Distance / Address) (See/a ) s Locator S 0.9 miles /3121 Center Road 2.25 E-6 1 NE 0.8 miles /4384 Lockwood Road 2.17 E-6 2 SSE 0.9 miles /3111 Paraly Road 1.89 E-6 3 I ENE 1.0 miles /4602 Lockvnod Road 1.13 E-6 4 1 SSV 0.9 miles /3850 Clark Road 1.11 E-6 5 VSV 1.1 ailes/3462 Paraly Road 8.67 E-7 6
- E 1.2 miles /2684 Antioch Road 5.92 E-7 7
\ 1 SV 1.2 miles /3440 Clark Road 4.98 E-7 8 ESE ,1,2 miles /2774 Antioch Road 4.44 E-7 9 SE 1.2 miles /4495 North Ridge Road 3.89 E-7 10 (1) The following sectors extend over water: V, VNV, NV, NNV, N, and NNE. (2) All residents are located in the North Ferry Township. TABLE 2 NEAREST GARDEN BY SECTOR AND DEPOSITION (D/0) VALUE s Nearest Resident (1}I ) D/Q Value Map 1 Direction (Distance / Address) (Per m8) Locator S 0.9 miles /3121 Center Road 1.31 E-8 11 j NE 0.8 miles /4384 Lockwood Road 1.09 E-8 12 l SSE 0.9 miles /3119 Parmly Road 1.23 E-8 13 ENE 1.2 miles /4650 Lockwood Road 4.11 E-9 14 SSV 1.5 miles /3513 North Ridge Road 1.48 E-9 15 ' VSV 1.9 miles / Corner of Blackmore 2.31 E-9 16 and Clark Roads (3) i E 1.1 miles /2674 Antioch Road 5.29 E-9 17 SV 1.2 miles /3440 Clark Road 2.24 E-9 18 ) ESE 1.3 miles /2846 Antioch Road 2.97 E-9 19 , SE 1.2 miles /4521 North Ridge Road 2. 90 E- 9 20 (4) i 1 4 i (1) The following sectors extend over water V, VNV, NV, NNV, N, and NNE. ; j (2) All gardens are located in the North Perry Township. i (3) Cultivated corn field on south side of Clark Roadt no address of ovner of I this field was available. ; (4) This property belongs to Golding's Farm on 3515 North Ridge Road. The property extends north from North Ridge Road and turns vest to Perry Park Road. This property is used for growing produce and fruits for public .. consumption. - 4 l
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TABLE 3 MIIK ANIMAL BY SECTOR AND DEPOSITION (D/Q) VALUE Location D/0 Value Number / Type Map of Animals Locator Comments Direction (Distance / Address) (Fer m ) 8 1.02 E-8 1 Goat 21 Resident declined to participate SSE 1.0 miles / 3291 Farmly Road in milk-sampling program. North Ferry 2.97 E-9 19 Goats 22 Valtes residence (milk samples). ESE 1.3 miles / Antloch Road North Perry 2.62 E-9 8 Coats 23 Bofer residence (milk sampler.J. ESE 1.4 miles / 2897 Antioch Road North Perry SV 2.3 miles / 7.24 E-10 30 Coats 24 Manley residence (milk samples). 3202 North Ridge Road North Perry SE 3.6 miles / 4.24 E-10 4 Dairy Cows 25 Resident declined to participate 5230 South Ridge Road in milk-sampling program. l Perry SE 4.5 miles / 2.58 E-10 2 Dairy Cows 26 Pollack residence (milk samples). 4566 Vood Road Madison l
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i i I Location D/0 Value Number / Type Map of Animals Locator F - ts Direction (Distance / Address) (Fer m ) a 4.1 miles / 2.39 E-10 2 Goats 27 SSE 4676 Elberta Road Ferry 28 Zoldak residence (milk samples). E 6.5 ciles/ (I) 2.07 E-10 15 Goats Middle Ridge Road . Madison SSE 4.6 miles / 1.94 E-10 1 Dairy Cow 29 35d8 River Road Madison III 1.35 E-10 10 Goats 30 Butler residence (milk samples). E 8.5 miles North Ridge Road Geneva l 1.07 E-10 14 Goats 100 Keller residence (milk saeples). SE 7.4 miles II) 588P. Dewey Road l Madison New location i (1) This location is not on aap in Figure 1. l 1 i _9_ a e _,,,,_,_ _ _ , _ _ , _ _ , _ _ _- - -_ _ _ - _ - + - , - - - - - ,, .- - - ,, - , , .
TABLE 4 l NON-DAIRY ANINALS BY SECTOR AND DEFOSITION (D/Q) l Location D/0 Value Number / Type Nap Direction (Distance / Address) (Fer a ) 8 of Amisals Locator 2.97 E-9 3 Cattle 31 ESE 1.3 miles / 2821 Antioch Road 4 Figs North Ferry 2.0 miles / 1.88 E-9 3 Cows 32 E l 2620 Townline Road North Ferry 1.8 miles / 1.77 E-9 1 Bull 33 5 3590 Center Road 2 Steer Ferry E 2.1 miles / 1.57 E-9 1 Goat 34 2541 Townline Road 1 Cow Nadison 350 Rabbits E 2.1 miles / 1.57 E-9 1 Coat 35 2447 Townline Road Madison SSE 2.0 miles / 1.24 E-9 10 Cat!!e 36
%08 Call Road Ferry i - - - - - . -- _ _ _ . - - _ - _ _ , - , - - . ,, -, - _ - , - _ - , .,, . - . , , - - - - ~ , . . - . - - . _ , , , ,
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I m tion D/0 Value Number / Type Map Direction (Distance / Address) (Per m8 ) of Animals _Incator ESE 2.6 miles / 8.90 E-10 18 Cattle 37 3234 McMackin Road Madison l SV 2.2 miles / 7.82 E-10 6 Cattle 38 3340 Blackmore Road North Perry l E 3.7 miles / 5.78 E-10 8 Cattle *9 ! 6008 North Ridge Road l Green Farm, Madison SE 3.1 miles / 5.53 E-10 8 Cattle 40 l 3941 Townline Road Perry SSE 2.8 miles / 4.71 E-10 6 Cows 41 4686 Davis Road Perry SE 3,7 miles / 4.04 E-10 55 Cattle 42 5320 South Ridge Road 4 Dairy Cows Perry E 4.6 miles / 3.91 E-10 49 Cattle 43 6401 Middle Ridge Voodworth Farm, Madison ESE 4.0 miles / 3.76 E-10 B Cattle 44 3587 Dayton Road Madison ESE 4.5 miles / 3.04 E-10 13 Cattle 45 5960 Middle Ridge Madison _ 11 -
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Location D/0 Value Number / Type Map Direction (Distance / Address) (Per m3 ) of Animals Locator SE 4.4 hiles/ 2.69 E-10 2 Cows 46 l 4260 Vood Road Madison 1 SE 4.5 miles / 2.58 E-10 4 Cattle 47 l 4566 Vood Road 1 Dairy Cow Ldison SE 4.6 miles / 2.48 E-10 48 4145 Dayton Road Madison SSE 4.1 miles / 2.39 E-10 12 Cattle 49 4676 Elberta Road 2 Coats Perry SSE 4.6 miles / 1.94 E-10 15 Cattle 50 5278 River Road Madison SSE 4.6 miles / 1.94 E-10 14 Cattle 51 3588 River Road 1 Dairy Cow Perry SSE 4.8 alles/ 1.80 E-10 6 Cattle 52 5551 River Road Madison 5 4.7 miles / 1.61 E-10 30 Cattle 53 3920 River Road Perry
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D/0 Value Number / Type May Location Direction (Distance / Address) 8 (Fer m ) of Animals Locator 1.31 E-10 8 Cattle 54 SSV 4.9 miles / 3082 South Ridge Road Ferry l l l l ! NOTE: The number of livestock may vary from time to time due to sale or slaughter. l l l l l l l i i __ -- _ , - , -.m.-- . .-- ----. - --.. . - -- -, ,- -
__m.____.-- . _ __ _ . _ _ _ _ ___ _ _ _ _ _ . . _ _ _ - _ _._ _ _ _____ __. _ _ . _ _ _ _ _ - f l TARLE 5 ACRICULTtRAL GROUERS VITHIN VICINITY OF FNFP D/0 Nap i Name Address City Sector / Distance (Fer a )8 Type of Crower Locator Losely Nursery Lockwood Road North Ferry NE/0.9 miles S.91 E-9 Nursery 55 ' Antioch Road E/1.0 miles 9.06 E-9 Rutland Fara Raines Road Madison ENE/3.1 miles 7.84 2-10 Strawberry Field 56 [ Twins Creek Farm Maines Road Madison ENE/3.2 miles 7.41 E-10 Strawberry Field 57 Roc-Ner Nerseries Green Road Madison E/3.6 alles 6.07 E-10 Nursery 58 Secor Nursery North Ridge Road Ferry ESE/1.8 miles 1.69 E-9 Nursery / 59 Strawberry Field Rainbow Farms Townline Road Ferry ENE/1.9 miles l'.86 E-9 Strawberry Field 60 Antioch Farm Antioch Road North Ferry ESE/1.4 miles 2.62 E-9 Produce 61 Ridge Manor Nurseries North Ridge koad Nadison E/2.9 miles 8.91 E-10 Nursery 62 Inc. (Reigert Fars) Green Farm North Ridge Road Nadison E/3.7 miles 5.78 E-10 Straw / Ray / Rye 63 i Ridge Manor Nurseries Dubbard Road Nadison ENE/5.0 miles 3.34 E-10 Nursery 64 Inc. (Reigert Farm) Great Lakes Evergreens Dayton Road Nadison ESE/4.0 miles 3.76 E-10 Nursery 65 (Dayton Fara ll) I i
D/0 Nap Address City Sector / Distance (Fer m ) 8 Type of Crower Incator Name Madison E/4.1 miles 4.81 E-10 Nursery 66 Kingwood Nurseries Burns Road Middle Ridge Road Madison E/4.6 miles 3.91 E-10 Froduce 67 Voodworth Fara Middle Ridge Road Madison ESE/3.7 miles 4.32 E-10 Nursery 68 Creat Lakes Evergreen l (Bejduk Fars) i Middle Ridge Road Madison ESE/3.0 miles 6.91 E-10 Nursery 69
) Sunleaf Nursery l
Middle Ridge Road Madison ESE/3.4 miles 5.03 E-10 Nursery 70 1 Lake County k rsery l (Kohanke Fara) D. L. Crawford Middle Ridge Road III Madison ESE/2.6 miles 8.89 E-10 krsery 71 Nursery Inc. Middle Ridge Road Madison ESE/2.7 miles 8.32 E-10 Nursery 72 J. Turkenburg t Norseries i Middle Ridge Road Madison ESE/2.7 miles 8.32 E-10 Nursery 73 Neans Nursery Dugan Nurseries North Ridge Road Perry SSE/1.3 miles 2.61 E-9 Nursery 74 Manchester Road S/1.7 miles 1.95 E-9 Vood Road Madison SE/4.1 miles 3.05 E-10 k rsery 75 Turkenburg Nurseries Middle Ridge Road Perry SE/1.7 miles 1.58 E-9 Nursery 76 The Cottage Gardens l Middle Ridge Road Perry SE/1.9 miles 1.31 E-9 hrsery 77 D. E. Sta11ards/ Daughter Nursery Middle Ridge Road S/1.7 miles 1.95 E-9 Fruits 78 i Brookside Fruit Farm Ferry Green Road S/2.4 miles 5.33 E-10 Nursery 79 Landscape Industries Perry j i , i l
D/0 Nap
"'-- Address City Sector / Distance 8 (Fer m ) Type of Grower Locator Narrows / South Ridge Ferry SSE/3.4 miles 3.34 E-10 Nursery 80 Lake County Nursery Roads South Ridge Road SSE/3.5 miles 3.17 E-10 Turnkey / South Ridge SSE/3.6 miles 3.02 E-10 Roads SSE/2.6 miles 5.37 E-10 Nursery 81 V1110wbend Nursery Davis Road Ferry Madison SE/4.0 miles 3.51 E-10 Froduce 82 Garnett Farm South Ridge Road Madison SSV/4.8 miles 1.35 E-10 Nursery 83 Klyn Nurseries South Ridge Road Ferry SSV/3.8 miles 2.06 E-10 Nursery 84 Berman Losely/ Sons Shepard Road Nurseries Perry SSV/4.3 miles 1.65 E-10 Nursery 85 Ferry Lake Nursery Shepard / Lane Roads Ferry SSV/3.9 miles 1.97 E-10 Nursery 86 Great Lakes Evergreen Maine / Lane Roads North Ridge Road SSV/1.7 miles 1.19 E-9 North Ridge Road Ferry SV/2.8 miles 5.12 E-10 Nursery 87 Norris Garden Center SV/2.7 miles 5.46 E-10 Fruits 88 Vest Orchard Fruit North Ridge Road Ferry Ferry Park / clark SV/1.6 miles 1.36 E-9 Froduce Market Roads North Ridge Road Ferry SV/2.5 miles 6.25 E-10 Nursery 89 Cilson Cardens North Ridge Road Perry SU/2.3 miles 7.24 E-10 Froduce 90 Blackacre Farm North Ridge Road Ferry SSV/1.9 miles 9.31 E-10 Nursery 91 Martin's Nursery Colding Farm North Ridge Road North Ferry SSV/1.7 miles 1.19 E-9 Fcuits 92 Ferry Park Road SV/1.5 miles 1.52 E.9 Froduce
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D/0 Nap Name Address City Sector / Distance (Per m*) Type of Crover Locator Lake County Nursery North Ridge Road North Ferry SSU/1.5 miles 1.48 E-9 Nursery 93 Lake County Nursery Narrows Road Perry SSV/2.4 miles 4.65 E-10 Nursery 94 Inc. Frank Square Nursery Narrows Raad Perry SSV/2.9 miles 3.33 E-10 Nursery 95 Beardslee Nursery Blackmore Road Perry SU/2.2 miles 7.82 E-10 Nursery % Penn-Ohio Gardens Park Avenue Painesville S53/5.0 miles 1.26 E-10 Nursery 97 Ralph T. Norman Park Avenue Painesville SSV/5.0 miles 1.26 E-10 Nursery 98 l Nursery l Lester T. Square Farm Blase-Nemeth Poad Painesville SU/4.0 miles 2.71 E-10 Produce 99 (1) D. L. Crawford Nursery on both N & S sides of road. I l d e L_ - - - - -- __ - _ _ - - _ . . _ - _ - - . _ _ _ _ _ _ _ _ _ _ _ _ _ - _ . , - - - - - - , - ~
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THE CLEVELAND ELECTRIC ILLUMIN ATING COMPANY P.O BOX 97 e PE ARY, OHIO 44081 e TELEPHONE (216) 259 3737 e ADDRESS 10 CENTER ACAD Serving The Best location in the Nation PERRY NUCLEAR POWER PLANT Al Kaplan YCCE PRE SDf MT W cLEAA G80 Vp August 30, 1988 PY-CEI/NRR-0906 L U. S. Nuclear Regulatory Com:sission Document Control Desk Washington, D.C. 20555 Perry Nuclear Power Plant Docket No. 50-440 Semiannual Radioactive Effluent Release Report Centlement We ara hereby submitting the Semiannual Radioactive Effluent Release Report for the Perry Nuclear Power Plant, Unit 1, for the period of January 1 through June 30, 1988. This report meets the requirements of the Regulatory Guide 1.21, as applicable to the Perry Technical Specification, Section 6.9.1.7. All effluent releases were within the concentration and rele:ise limits specified in the Radiological Ef fluent Technical Specifications. If you have any questions, please feel free to call. Very truly yours. Al Kaplan Vice President i Nuclear Group , AKinje ' 1 cc: T. Colburn l K. Connaughton USNRC, Region III ( pt. l / I g i l 1
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