Text

Annual Radioactive Effluent Release Rept 1994:Quarter 1-4
	ML20082R192
Person / Time
Site:
Issue date:	12/31/1994
From:	Shelton D; CENTERIOR ENERGY
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	PY-CEI-NRR-1948, NUDOCS 9505020001
	Download: ML20082R192 (217)
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CENTEENOR ENERGY PERRY NUCLEAR POWER PLANT Mail Address: Donald C. Shelton 10 CENTER ROAD RR , O 10 44081 SENIOR VICE PRESIDENT PERRY, OHIO 44081 NUCLEAR (216) 259-3737 April 27, 1995 PY-CEI/NRR-1948L United States Nuclear Regulatory Commission Document Control Desk Vashington, D.C. 20555 Perry Nuclear Power Plant Docket No. 50-440 Annual Radioactive Effluent Release Report Gentlemen Attached is the Annual Radioactive Effluent Release Report for the Perry Nuclear Power Plant, Unit 1, for the period January 1, 1994 to f December 31, 1994. This report meets the requirements of Regulatory Guide 1.21, as applicable to the Perry Technical Specification 6.9.1.7.

All effluent releases were within the concentration and release limite specified in the Radiological Effluent Technical Specifications.

If you have questions or require additional information, please contact Mr. James D. Kloosterman, Manager - Regulatory Affairs at (216) 280-5833.

Very truly yours, h' 'n

\i GMN sc Attachment cc NRC Project Manager NRC Resident Inspector Office NRC Region III S. Focht - ANI 9505020001 941231 PDR ADOCK 05000440 R PDR

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THE CLEVELAND ELECTRIC ILLUMINATING COMPANY !

PERRY NUCLEAR POWER PLANT !

UNIT 1 .

t ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT ,

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i 1994: QUARTERS 1 thru 4 :

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Approved By: 3 2

M= a A n A '5 7 Direct 6r, Perry Nuclear Engineering Department r

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Genet &l nager, Perry Nuclear @ower Slant i

INTRODUCTION This Annual Radioactive Effluent Release Report (ARERR),

covering the period of January 1 through December 31, 1994, 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 (RETS).

During the calendar year 1994, the plant produced 4,824,754 Megawatt Hours Electric Gross. The net reactor capacity averaged 45.0 percent. The reactor was critical a total of 4399.0 hours0 days 0 hours 0 weeks 0 months .

Liquid and gaseous radioactive effluent releases to the environment during this reporting period were sampled and analyzed in accordance with the requirements of the Technical Specifications. All radioactive releases were within the concentration and release limits specified in the RETS.

Calculations and terms utilized in this report are those outlined in the PNPP Offsite Dose Calculation Manual (ODCM).

l TABLE OF CONTENTS ,

Page Introduction ................................... 4 Radiological Impact on Man ..................... 5 Supplemental Information ....................... 7 Liquid Effluents ............................... 10 Gaseous Effluents .............................. 12 Solid Waste .................................... 13 Meteorological Data ............................. 13 Abnormal Releases .............................. 14 Applicable Technical Specification Requirements. 15 l

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ATTACHMENTS : Radiological Impact on Man (Dose Summaries) : Radiological Impact on Man (Land Based Sectors) : Technical Specification Limits : Liquid Effluents : Gaseous Effluents : Solid Waste : Meteorological Data : 1994 Annual Land Use Census : Abnormal Release 0: Process Control Program 1: Offsite Dose Calculation Manual i

i RADIOLOGICAL IMPACT ON MAN Sampling and analysis of liquid and gaseous effluents were performed in accordance with the frequencies, types of analyses, and Lower Limits of Detection (LLD) outlined in the PNPP Unit 1 Technical Specifications.

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 dose to individuals at levels below 10CFR20 and 10CFR50, Appendix I limits. Direct radiation resulting from plant operation, as measured by environmental thermoluminescent dosimeters located around the plant, did not contribute any measurable dose to members of the public for the reporting period and, as there are no other nearby fuel cycle sources, 40CFR190 limits were not exceeded.

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.

Technical Specification 6.9.1.7 requires assessment of radiation doses from radioactive liquid and gaseous effluents to members of the public while onsite. These onsite doses are assessed relative to offsite dose values, and are adjusted for appropriate dilution, dispersion, and occupancy factors.

ONSITE DOSE FOR LIQUID EFFLUENTS The onsite liquid effluent pathway of concern for members of the public is shore exposure while fishing along the Lake Erie coast. Occupancy is assumed to be 60 hours6.944444e-4 days 0.0167 hours 9.920635e-5 weeks 2.283e-5 months per year and the dilution factor for the point of exposure is 10. Ratioing this exposure pathway to doses calculated for offsite locations yields the following onsite dose values:

Total Body Organ Year 1994 5.22 E-03 mrem 6.16 E-03 mrem Quarter 1 1.60 E-03 mrem 1.86 E-03 mrem Quarter 2 2.61 E-03 mrem 3.12 E-03 mrem Quarter 3 8.70 E-04 mrem 1.02 E-03 mrem Quarter 4 1.82 E-04 mrem 2.11 E-04 mrem l

ONSITE DOSE FOR GASEOUS EFFLUENTS Several cases are considered for onsite gaseous effluent exposure to members of the public including traversing a public road within the site boundary, shoreline fishing, non-plant i 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 i be 60 hours6.944444e-4 days 0.0167 hours 9.920635e-5 weeks 2.283e-5 months per year. Accounting for this and the difference between annual average dispersion values for the onsite point of concern, 6.6 E-05 s/m3, the following maximum onsite dose values are generated. The maximum onsite doses for gaseous effluents for the four quarters may not be cumulative. l Total Body Organ Year 1994 1.47 E-01 mrem 3.41 E-01 mrem Quarter 1 6.48 E-03 mrem 2.86 E-02 mrem Quarter 2 1.50 E-06 mrem 9.88 E-05 mrem i Quarter 3 1.20 E-01 mrem 2.55 E-01 mrem Quarter 4 2.93 E-02 mrem 7.96 E-02 mrem ;

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 (1.82 E+06 persons). These ,

doses are calculated using the total population dose figures found in Attachment 1. 3 Gases Liquids Year 1994 1.1 E-05 mrem 3.5 E-03 mrem l

Quarter 1 3.4 E-06 mrem 1.8 E-03 mrem Quarter 2 1.5 E-09 mrem 1.2 E-03 mrem Quarter 3 4.6 E-06 mrem 4.2 E-04 mrem ,

Quarter 4 2.6 E-06 mrem 5.3 E-05 mrem Gaseous and Air Dose calculations at the site boundary were performed for two cases. Attachment 1 provides the calculated ,

maximum site boundary dose values for all sectors including those sectors which are totally over water in which no member of the public resides (These are the W, WNW, NW, 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.

SUPPLEMENTAL INFORMATION Regulatory Limits Technical Specifications 3/4.11.1 and 3/4.11.2 outline ;

requirements for release of radioactive liquid and gaseous l effluents, respectively. Concentration of radioactive material in liquid effluents and dose or dose commitment resultant thereof are limited in unrestricted areas. Dose and' dose rate due to radioactive materials released in gaseous effluents are limited in areas at or beyond the site boundary. Technical Specification limits are listed in Attachment 3.

Maximum Permissible Concentrations The Maximum Permissible Concentrations (MPC's) in liquids are those outlined in Technical Specification 3.11.1.1 (10CFR20, Appendix B, Table II, Column 2, with the lower of the soluble and insoluble MPC being used; for dissolved and entrained noble gases, concentrations are limited to 2 E-04 pCi/ml). PNPP Unit 1 Technical Specifications do not contain a concentration requirement for gaseous releases, therefore, MPCs are not used to calculate maximum release rates for radioactive gaseous effluents.

Average Energy Average energy requirements for radioactive effluent mixtures do not apply to PNPP Unit 1 Technical Specifications or offsite Dose Calculation Manual.

Measurements and Approximations of Total Radioactivity Analyses of specific radionuclides in effluent samples are used with effluent path flow measurements to evaluate the radioactive composition and concentration of effluents.

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i Batch Releases Liquid effluent releases were considered continuous (runs of Emergency Service Water [ESW) loops A and B) as well as batch (Liquid Radwaste [LRW] discharges). Although the ESW system 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 l were considered continuous. ;

LIQUID RELEASES January 1 - March 31, 1994 l l

Batch continuous Number of Releases 36 42 Total Time of Releases (min) 1.1 E+04 1.1 E+05*

Minimum Time for a Release (min) 2.0 E+00 1.3 E+01 Average Time for a Release (min) 3.1 E+02 2.6 E+03 Maximum Time for a Release (min) 1.7 E+03 5.6 E+04 Average Effluent Stream Flow during 1.4 E+05 2.0 E+04 periods of release (1/ min)

The total of ESW Loop A (3.4 E+04 min) and ESW Loop B (7.4 E+04 min)

April 1 - June 30, 1994 Batch Continuous Number of Releases 31 49 Total Time of Releases (min) 6.9 E+03 1.2 E+05*

Minimum Time for a Release (min) 2.1 E+02 7.9 E+01 Average Time for a Release (min) 2.2 E+02 2.4 E+03 Maximum Time for a Release (min) 2.5 E+02 4.5 E+04 Average Effluent Stream Flow during 4.7 E+04 3.9 E+04 periods of release (1/ min)

The total of ESW Loop A (8.4 E+04 min) and ESW Loop B (3.6 E+04 min) i i

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LIQUID RELEASES (cont.)

July 1 - September 30, 1994 Batch continuous Number of Releases 42 73 Total Time of Releases (min) 9.2 E+03 9.3 E+04*

Minimum Time for a Release (min) 2.0 E+02 3.0 E+00 Average Time for a Release (min) 2.2 E+02 1.3 E+03 Maximum Time for a Release (min) 2.4 E+02 2.7 E+04 Average Effluent Stream Flow during 1.6 E+05 4.6 E+04 periods of release (1/ min)

The total of ESW Loop A (5.2 E+04 min) and ESW Loop B (4.1 E+04 min)

October 1 - December 31, 1994 Batch Continuous Number of Releases 22 55 Total Time of Releases (min) 4.8 E+03 1.9 E+04*

Minimum Time for a Release (min) 1.9 E+02 1.8 E+01 Average Time for a Release (min) 2.2 E+02 3.5 E+02 Maximum Time for a Release (min) 2.4 E+02 2.6 E+03 Average Effluent Stream Flow during 2.3 E+05 4.3 E+04 periods of release (1/ min)

The total of ESW Loop A (1.2 E+04 min) and ESW Loop B (7.2 E+03 min)

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l LIQUID EFFLUENTS j For the first quarter of 1994 there were 36 batch and 42 I continuous releases. Batch release total waste volume for the first quarter was 4.34 E+06 liters; total continuous release !

waste volume was 2.1 E+09 liters; total plant discharge during periods of release was 1.48 E+10 liters. l For the second quarter of 1994 there were 31 batch and 49 continuous releases. Batch release total waste volume for the ;

second quarter was 4.01 E+06 liters; total continuous release waste volume was 4.7 E+09 liters; total plant discharge during periods of release was 1.16 E+10 liters. ,

For the third quarter of 1994 there were 42 batch and 73 continuous releases. Batch release total waste volume for the third quarter was 5.43 E+06 liters; total continuous release -

waste volume was 4.3 E+09 liters; total plant discharge during periods of release was 1.78 E+10 liters.

For the fourth quarter of 1994 there were 22 batch and 55 continuous releases. Batch release total waste volume for the fourth quarter was 2.79 E+06 liters; total continuous release waste volume was 8.1 E+08 liters; total plant discharge during periods of release was 2.01 E+10 liters.

Summaries of the radionuclide total curie activities, average diluted concentrations, and percentage of MFC (in Regulatory Guide 1.21 format) are included in Attachment 4.

If a radionuclide was not detected, zero activity was used for that isotope in dose calculations. A zero activity indicates that the radionuclide was not present at a level greater than i the Lower Level of Detection (LLD) of the instrumentation used.

In all cases, these LLD's were less than the levels required by i Technical Specifications. The following are typical LLD's:

Radionuclide LLD Ci/ml Radionuclide LLD Ci/ml Mn-54 3.6 E-08 Cs-134 2.5 E-08 Fe-59 4.8 E-08 Cs-137 3.1 E-08 Co-58 2.9 E-08 Ce-141 3.8 E-08 '

Co-60 3.8 E-08 Ce-144 1.6 E-07 Zn-65 3.0 E-07 Sr-89 3.0 E-08 (

Mo-99 1.9 E-07 Sr-90 3.7 E-08 ,

I-131 2.4 E-08 Fe-55 5.7 E-09 H-3 4.6 E-06 Gross Alpha 6.0 E-08 ;

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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 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 terms.

Gamma Analysis 10% l 11-3 Analysis 8% ;

Sr-89/90 Analysis 10% i i

Fe-55 Analysis 10% ;

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Gross Alpha Analysis 10%

Service Water Volume (Dilution) 31%

Emergency Service Water 25%

Volume (Discharge) ,

Liquid Radwaste Volume 1%

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GASEOUS EFFLUENTS Summaries of the radionuclide total curie activities, average I release rates (in Regulatory Guide 1.21 format) are included in ! .

If a radionuclide was not detected, zero activity was used for that isotope in dose calculations. A zero activity indicates that the radionuclide was not present at a level greater than the Lower Level of Detection (LLD) of the instrumentation used.

In all cases, these LLD's were less than the levels required by Technical Specifications. The following are typical LLD's:

Radionuclide LLD (yCi/ml)

Kr-87 2.7 E-08 Kr-88 3.0 E-08 Xe-133 2.0 E-08 Xe-133m 5.3 E-08 Xe-135 8.1 E-09 Xe-138 2.8 E-07 Mn-54 6.5 E-13 Fe-59 1.2 E-12 Co-58 6.7 E-13 Co-60 6.7 E-13 Zn-65 1.8 E-12 Mo-99 4.4 E-12 Cs-134 5.3 E-13 Cs-137 7.1 E-13 Ce-141 6.3 E-13 Ce-144 2.5 E-12 I-131 6.1 E-13 I-133 8.1 E-13 Sr-89 3.8 E-14 Sr-90 6.8 E-14 H-3 3.0 E-10 Gross Alpha 5.4 E-12 Estimates of error associated with sample analysis, sample flow rate, and effluent flow rate follow. Analytical error terms are based on split sample analysis results, the majority of which are confirmatory measurements, the others are interlaboratory comparison results. Flow rate instrumentation error is assessed using loop instrumentation accuracy terms.

Noble Gas Analysis 11%

Particulate Analysis 9% :

Iodine Analysis 12% i H-3 Analysis 8% i Sr-89/90 Analysis 10% '

Gross Alpha Analysis 10%

Sample Flow Rate 4% .

l Effluent Flow Rate 4%

SOLID WASTE There were 37 radioactive waste shipments transported from PNPP for the period covered in this report. Twenty-three shipments of dry active waste were sent for volume reduction prior to burial or 48640.0 cubic feet. There were 14 HIC's (1752.2 cubic feet), which were sent in 11 separate shipments. There were 2 separate shipments of compacted radioactive waste for direct '

burial (1536 cubic feet). There was no irradiated fuel transported from site. See Attachment 6 for volume and activity values.

r METEOROLOGICAL DATA Cumulative joint frequency distribution (JFD) tables of wind speed and direction for each stability class, as well as for all stability classes combined, are given in Attachment 7 for the annual and for each quarter of the annual period covered by'.this report.

These JFD tables are the results obtained from the processing of i hourly average meteorological data collected at the PNPP site i met tower. It should be noted that the 1-3 mph JFD column I includes wind speeds down to 0.1 mph and that hours of 0 wind ,

speed appear only in the totals columns. The separate tallies ,

of periods of calm include wind speeds'from 0.0 to <0.7 mph.

Differential temperature (AT 60-10 meters) is generally used for s atmospheric stability classification, i

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ABNORMAL RELEASES There was one abnormal release during the reporting period.

On 8/21/94, an abnormal release occurred through the containment vacuum breakers. The vacuum breakers were inadvertently opened to atmosphere for approximately 37 seconds during SVI-M17-T2002 testing. The release times, isotopic concentrations, flow rate and dose for this event is described below.

Release Period: 8/21/94 @ 1259 , 37 second duration Isotopic Concentrations: (in containment at purge time)

Xe-133 : 4.38E-06 Xe-135 : 6.55E-06 Xe-135m: 8.33E-08 Flow Rate: 1.81E+04 cfm Dose Rate: 2.00 E-02 mrem /yr (Total Body) 5.28 E-02 mrem /yr (Skin)

Dose: 3.57 E-06 mrad (gamma) 5.15 E-06 mrad (beta) 2.28 E-06 mrem (Total Body)

NOTE: Dose based on a 1 minute release averaged over 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months due to software constraints.

See Attachment 9 for Joint Frequency Distribution tables and curie releases for this event.

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APPLICABLE TECHNICAL SPECIFICATION REQUIREMENTS l Per PNPP Technical Specifications, certain noncompliance items, changes, and findings are reportable in the Annual Radioactive Effluent Release Report.

Radioactive Liquid Effluent Monitoring Instrument Inoperability for greater than 30 days. (PNPP Technical Specification 3.3.7.9, ;

Action b.):

There were four incidents where Liquid Effluent Monitoring Instruments were inoperable for greater than 30 days during the. reporting period.

Radwaste low flow discharge header monitor (0G50-R454) was '

declared inoperable on 11/16/92 per Technical Specification 3.3.7.9. The flow monitor was calibrated and declared operable on 11/23/94.

On 2/25/94, the Radwaste to Emergency Service Water Radiation Monitor (0D17-K0606) was declared inoperable.

The inoperability was due to an increase in background levels from the plateout of activity on the detector liner. i The liner was replaced and the radiation monitor was declared operable on 12/19/94.

On 3/10/94, the Service Water Discharge Flow Monitor was declared inoperable. The monitor was declared inoperable during Refuel Outage 4 for a Service Water outage that included draining the system. After the system was .

refilled, tested and all necessary flow monitor calibrations performed, the monitor was declared operable on 8/23/94. ,

on 5/5/94, the Emergency Service Water Flow Monitor was declared inoperable. A difference of >3000 gpm between individual load flow readings and the recorder reading for total flow was observed. The recorder was repaired and all applicable SVI's performed satisfactorily. The monitor was declared operable on 9/19/94.

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Radioactive Gaseous Effluent Monitoring Instrument Inoperability

for greater than 30 days (PNPP Technical Specification 3.3.7.10, Action b.):

There were.no Gaseous Effluent Monitoring Instrument inoperabilities for greater than 30 days during the reporting period.

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 during the reporting >

period. -

Radiological Environmental Monitoring Program (REMP) changes (PNPP Technical Specification 3.12.1, Action c.):

For the reporting period, samples were obtained at their respective locations as required by the specified collection frequencies.

t During the reporting period, Table 5.1-1 (Radiological Environmental Monitoring Program) of the ODCM was replaced l with Table 3.12.1-1 from PNPP Technical Specifications, i Table 5.1-4 was also deleted from the ODCM. This table did ,

not reflect sample points required by Technical Specifications.

t Land Use Census findings (PNPP rechnical Specification 3.12.2, Actions a. and b.):

The 1994 Land Use Census was conducted from July 14, 1994 to July 18, 1994 in accordance with 10CFR50 Appendix I and the PNPP Technical Specifications,.Section 3/4.12.2. See Attachment 8.

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Process Control Program (PCP) changes (PNPP Technical Specification ;

E.13.2): i There were two changes made to the Process Control Program ,

during the reporting period. 5 on 5/3/94, a Temporary change (TCN) was generated to: ,

- Correct a statement concerning the Radwaste Building ;

Heating System.

- Ensure dewatering of waste was provided as an option in all sections of the PCP. -

- Permitted the use of processing techniques not specifically discussed in the PCP, with approved PNPP or vendor procedures. ,

- Permitted the use of the Special Transport Container for processing in the Radwaste truck bay.

- Allow for processed wet solid radwaste to be transferred to the on-site Storage Area for storage.

- Expanded the description of waste preconditioning to '

include the process of treating dewatered waste streams to eliminate or reduce bacterial activity. ;

on 10/28/94, a TCN was generated to: ;

- Clarify the definition of a " Filter Cartridge" ;

- Delete the use of the Centerior Energy Special Transport i container and specify the use of a High Integrity Container.

Note: Between 5/3/94 and 10/28/94, the Special Transport Container was not used for processing waste.

Offsite Dose Calculation Manual (ODCM) changes (PNPP Technical [

Specification 6.14.2): ;

on 8/12/94, a revision was performed to:

- Incorporate previous TCN's

- Replaced Table 5.1-1 PNPP Radiological Environmental Monitoring Program with PNPP Radiological Environmental Monitoring Program Table 3.12.1-1 from Tech Specs.

- Delete Table 5.1-4.

- Move note on sampling. .

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- Minor editorial changes where the text referenced Tables 5.1-1 and 5.1-4.

Major changes to Radioactive Waste Treatment Systems (PNPP i Technical Specification 6.15.1): ;

There were no major changes to the Radioactive Waste ;

Treatment Systems during this reporting period. '

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i Attachment 1 Radiological Impact on Man (Dose Summaries) m Attachment 1 (Page 1 of 5)

Radiological Impact on Man (Dose Summaries) 1994: Quarter 1

SUMMARY

OF MAXIMUM INDIVIDUAL DOSES LAST ACCUMULATIONS FOR PERIODS:

LIQUID 94 1 1 1-94 33024 GASEOUS 94.1 1 1-94 33024 AIR 94 1 1 1-94 33024 APPLICABLE ESTIMATED AGE LOCATION % OF LIMIT EFFLUENT ORGAN DOSE GROUP DIST DIR APPLICABLE (MREM)

(M) (TOWARD) LIMIT (MREM)

LIQUID TOTAL BODY 5.07E-02 CHILD RECEPTOR 1 1.7E+00 3.0E+00 LIQUID BONE 2.70E-01 CHILD RECEPTOR 1 2.7E+00 1.0E+01 NOBLE GAS AIR DOSE 9.76E-02 273. NW 9.8E-01 1.0E+01 (GAMMA-MRAD)

NOBLE GAS AIR DOSE 1.19E-01 273. NW 6.0E-01 2.0E+01 (BETA-MRAD)

NOBLE GAS T. BODY 5.97E-02 ALL 273. NW 1.2E+00 5.0E+00 NOBLE GAS SKIN 1.35E-01 ALL 273. NW 9.0E-01 1.5E+01 IODINE & THYROID 1.31E-01 CHILD 273. NW 8.7E-01 1.5E+01 PARTICULATES

SUMMARY

OF POPULATION DOSES !

LAST ACCUMULATIONS FOR PERIODS: -

LIQUID 94 1 1 1-94 33024 GASEOUS 94 1 1 1-94 33024 j EFFLUENT APPLICABLE ESTIMATED ORGAN POPULATION DOSE ;

(PERSON REM) l LIQUID TOTAL BODY 3.3E+00 l LIQUID THYROID 5.5E-02 GASEOUS TOTAL BODY 8.2E-03 GASEOUS THYROID 3.4E-02 -

i NOTE: The dose limits appearing on this page are annual 1 limits. The quarterly limits are listed on page 29 of this report. .

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Attachment 1 (Page 2 of 5)

Radiological Impact on Man (Dose Summaries) 1994: Quarter 2

SUMMARY

OF MAXIMUM INDIVIDUAL DOSES LAST ACCUMULATIONS FOR PERIODS:

LIQUID 94 4 1 1-94 63024 GASEOUS 94 4 1 1-94 63024 AIR 94 4 1 1-94 63024 APPLICABLE ESTIMATED AGE LOCATION % OF LIMIT EFFLUENT ORGAN DOSE GROUP DIST DIR APPLICABLE (MREM) (M) (TOWARD) LIMIT (MREM)

LIQUID TOTAL BODY 3.60E-02 CHILD RECEPTOR 1 1.2E+00 3.0E+00 LIQUID BONE 2.35E-01 CHILD RECEPTOR 1 2.3E+00 1.0E+01 NOBLE GAS AIR DOSE 0.00E+00 273. N 0.0E+00 1.0E+01 (GAMMA-MRAD) 0.0E+00 2.0E+01 NOBLE GAS AIR DOSE 0.00E+00 273. N (BETA-MRAD)

NOBLE GAS T. BODY 0.00E+00 ALL 0. 0.0E+00 5.0E+00 NOBLE GAS SKIN 0.00E+00 ALL 0. 0.0E+00 1.5E+01 IDDINE& THYROID 9.19E-04 CHILD 280. NNW 6.1E-03 1.5E401 PARTICULATES

SUMMARY

OF POPULATION DOSES LAST ACCUMULATIONS FOR PERIODS:

LIOUID 94 4 1 1-94 63024 GASEOUS 94 4 1 1-94 63024 EFFLUENT APPLICABLE ESTIMATED ORGAN POPULATION DOSE (PERSON-REM)

LIQUID TOTAL BODY 2.2E+00 LIQUID THYROID 7.8E-02 GASEOUS TOTAL BODY 3.5E-06 GASEOUS THYROID 1.0E-04 NOTE: The dose limits appearing on this page are annual limits. The quarterly limits are listed on page 29 of this report.

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Attachment 1 (Page 3 of 5)

Radiological Impact on Man (Dose Summaries) '

1994: Quarter 3

SUMMARY

OF MAXIMUM INDIVIDUAL DOSES LAST ACCUMULATIONS FOR PERIODS:

LIQUID 94 7 1 1-94 93024

GASEOUS 94 7 1 1-94 93024 AIR 94 7 1 1-94 93024 APPLICABLE ESTIMATED AGE LOCATION % OF . LIMIT EFFLUENT ORGAN DOSE GROUP DIST DIR APPLICABLE (MREM)

(M) (TOWARD) LIMIT (MREM)

LIQUID TOTAL BODY 1.29E-02 CHILD RECEPTOR 1 4.3E-01 3.0E+00 LIQUID BONE 8.64E-02 CHILD RECEPTOR 1 8.6E-01 1.0E+01 NOBLE GAS AIR DOSE 2.33E+00 273. NW 2.3E+01 1.0E+01 (GAMMA-MRAD)

NOBLE GAS AIR DOSE 1.87E+00 273. NW 9.4E+00 2.0E+01 (BETA-MRAD)

NOBLE GAS T. BODY 1.1'. E + 0 0 ALL 273. NW 2.2E+01 5.0E+00 NOBLE GAS SKIN 2.17E+00 ALL 273. NW 1. 4 E + 01 1.5E+01 IUDINE& THYROID 2.04E-01 CHILD 283. WNW 1.4E+00 1.5E+01 PARTICULATES

SUMMARY

OF POPULATION DOSES LAST ACCUMULATIONS FOR PERIODS:

LIOUID 94 7 1 1-94 93024 GASEOUS 94 7 1 1-94 93024 EFFLUENT APPLICABLE ESTIMATED ORGAN POPULATION DOSE (PERSON-REM)

LIQUID TOTAL BODY 7.6E-01 LIQUID THYROID 6.4E-02 GASEOUS TOTAL BODY 1.1E-02 GASEOUS THYROID 7.9E-02 NOTE: The dose limits appearing on this page are annual limits.- The quarterly limits are listed on page 29 of this report.

Attachment 1 (Page 4 of 5) l Radiological Impact on Man (Dose Summaries) {

1994: Quarter 4

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SUMMARY

OF MAXIMUM INDIVIDUAL DOSES LAST ACCUMULATIONS FOR PERIODS: l LIOUID 9410 1 1-94123124 i GASEOUS 9410 1 1-94123124 '

AIR 9410 1 1-94123124 i 3

t APPLICABLE ESTIMATED AGE LOCATION % OF LIMIT i EFFLUENT ORGAN DOSE GROUP DIST DIR APPLICABLE (MREM) (M) (TOWARD) LIMIT (MREM)

LIQUID TOTAL BODY 1.39E-03 ADULT RECEPTOR 1 4.6E-02 3.0E+00 l'9uID_ _ _ BgNy , _ _ _ _1.385 02_ Cs13D_ _ R3C3eTOR 1

__ _ _ _ 1.0e+01

_ _1.4e_01 _ _ l NOBLE GAS AIR DOSE 4.99E-01 283. WNW 5.0E+00 1.0E+01 (GAMMA-MRAD) 2.0E+01 NOBLE GAS AIR DOSE 2.33E-01 283. WNW 1.2E+00 i (BETA-MRAD) t NOBLE GAS T. BODY 2.72E-01 ALL 283. WNW 5.4E+00 5.0E+00 NOBLE GAS SKIN 4.89E-01 ALL 283. WNW 3.3E+00 1.5E+01 f IODINE & THYROID 2.51E-01 CHILD 283. WNW 1.7E+00 1.5E+01 :

PARTICULATES l

SUMMARY

OF POPULATION DOSES r LAST ACCUMULATIONS FOR PERIODS:

LIQUID 9410 1 1-94123124 GASEOUS 9410 1 1-94123124 ,

EFFLUENT APPLICABLE ESTIMATED .

ORGAN POPULATION DOSE (PERSON REM)

LIQUID TOTAL BODY 9.7E-02 LIQUID THYROID 3.0E-02 GASEOUS TOTAL BODY 6.3E-03 GASEOUS THYROID 6.1E-02 3 NOTE: The dose limits appearing on this page are annual ;

limits. The quarterly limits are listed on page 29 of this report.

1

Attachment 1 (Page 5 of 5)

Radiological Impact on Man (Dose Summaries)

Year 1994

SUMMARY

OF MAXIMUM INDIVIDUAL DOSES LAST-ACCUMULATIONS FOR PERIODS:

LIOUID 94 1 1 1-94123124 GASEOUS 94 1 1 1-94123124 AIR 94 1 1 1-94123124 APPLICABLE ESTIMATED AGE LOCATION % OF LIMIT EFFLUENT ORGAN DOSE GROUP DIST DIR APPLICABLE (MREM) (M) (TOWARD) LIMIT (MREM)

LIQUID TOTAL BODY 1.01E-01 CHILD RECEPTOR 1 3.4 E+ 00 3.0E+00 LIQUID BONE 6.05E 01 CHILD RECEPTOR 1 6.1E+00 1.0E+01 NOBLE GAS AIR DOSE 2.77E+00 273. NW 2.8E+01 1.0E+01 (GAMMA-MRAD) .

NOBLE GAS AIR DOSE 2.16E+00 273. NW 1.1E+01 2.0E+01 (BETA-MRAD)

NOBLE GAS T. BODY 1.37E+00 ALL 273. NW 2.7E+01 5.0E+00 NOBLE GAS SKIN 2.65E+00 ALL 273. NW 1.8E+01 1.5E+01 IODINE & THYROID 5.19E-01 CHILD 283. WNW 3.5E+00 1.5E+01 PARTICULATES

SUMMARY

OF POPULATION DOSES LAST ACCUMULATIONS FOR PERIODS:

LIQUID 94 1 1 1-94123124 GASEOUS 94 1 1 1-94123124 EFFLUENT APPLICABLE ESTIMATED ORGAN POPULATION DOSE (PERSON-REM)

LIQUID TOTAL BODY ~

6.3E+00 LIQUID THYROID 2.3E-01 GASEOUS TOTAL BODY 2.6E-02 GASEOUS THYROID 1.7E-01 NOTE: The dose limits appearing on this page'are annual' limits. The quarterly limits are listed on page 29 of this report.

t Attachment 2 Radiological Impact on Man (Land Based Sectors) i e

l l

l 1

j

i Attachment 2 (Page 1 of 3)

I Radiological Impact on Man (Land Based Sectors)

Quarter 1

SUMMARY

OF MAXIMUM INDIVIDUAL DOSES !

LAST ACCUMULATIONS FOR PERIODS: !

LIOUID 94 1 1 1-94123124 GASEOUS 94 1 1 1-94 33124 AIR 94 1 1 1-94 33124 APPLICABLE ESTIMATED AGE LOCATION % OF LIMIT !

EFFLUENT ORGAN DOSE GROUP. DIST DIR APPLICABLE (MREM) (M) (TOWARD) LIMIT (MREM)

LIQUID TOTAL BODY 1.01E-01 CHILD RECEPTOR 1 3.4E+00 3.0E+00 LIQUID BONE 6.05E CHILD RECEPTOR 1 6.1E+00 1.0E+01

. . _ _ _ _ _ _ _ _ _ _ _ _ _-01_

NOBLE GAS AIR DOSE 2.43E_02 678. NE 2.4E-01 1.0E+01 (GAMMA-MRAD)

NOBLE GAS AIR DOSE 1.70E-02 678. NE 8.5E-02 2.0E+01 i

(BETA-MRAD)

NOBLE GAS T. BODY 1.39E-02 ALL 678. NE 2.BE-01 5.0E+00 NOBLE GAS SKIN 2.70E-02 ALL 678. NE 1.8E 01 1.5E+01 IODINF& THYROID 2.84E-02 CHILD 678. NE 1.9E-01 1.5E+01 ,

PARTICULATES f

Quarter 2 i'

SUMMARY

OF MAXIMUM INDIVIDUAL DOSES '

LAST ACCUMULATIONS FOR PERIODS

LIQUID 94 1 1 1-94123124 ;

GASEOUS 94 4 1 1-94 63024 AIR 94 4 1 1-94 63024 4

APPLICABLE ESTIMATED AGE LOCATION % OF LIMIT :

EFFLUENT ORGAN DOSE GROUP DIST DIR APPLICABLE ,

(MREM) (M) (TOWARD) LIMIT (MREM) ;

LIQUID TOTAL BODY 1.01E-01 CHILD RECEPTOR ? 3.4E+00 3.0E+00 LIQUID BONE 6.05E-01 CHILD RECEPTOR 1 6.1E+00 1.0E+01 I NOBLE GAS AIR DOSE 0.00E+00 273. N 0.0E+00 1.0E+01 .

(GAMMA-MRAD) 2.0E+01 NOBLE GAS AIR DOSE 0.00E+00 273. N 0.0E+00 L (BETA-MRAD) ;

NOBLE GAS T. BODY 0.00E+00 ALL 0. 0.0E+00 5.0E+00 I NOBLE GAS SKIN 0.00E+00 ALL 0. 0.0E+00 1.5E+01 IODINE & BONE 2.40E-04 CHILD 678. NE 1.6E-03 1.5E+01 PARTICULATES - -

NOTE: The dose limits appearing on this page are annual limits. The quarterly limits are listed on page 29

( of this report.

i l ,

I Attachment 2 (Page 2 of 3)

Radiological Impact on Man (Land Based Sectors)

Quarter 3 3

SUMMARY

OF MAXIMUM INDIVIDUAL DOSES LAST ACCUMULATIONS FOR PERIODS:

LIOUID 94 1 1 1-94123124 GASEOUS 94 7 1 1-94 93024 AIR 94 7 1 1-94 93024 APPLICABLE ESTIMATED AGE LOCATION % OF LIMIT-EFFLUENT ORGAN DOSE GROUP DIST DIR APPLICABLE (MREM) (M) (TOWARD) LIMIT (MREM)

LIQUID TOTAL BODY 1.01E-01 CHILD RECEPTOR 1 3.4E+00 3.0E+00 ;

LIQUID BONE 6.05E-01 CHILD RECEPTOR 1 6.1E+00 1.0E+01 l

NOBLE GAS AIR DOSE 9.78E-02 678. NE 9.8E-01 1.0E+01 (GAMMA-MRAD)

NOBLE GAS AIR DOSE 5.11E-02 678. NE 2.6E-01 2.0E+01-(BETA-MRAD) i NOBLE GAS T. BODY 3.71E-02 ALL 678. NE 7.4E-01 5.0E+00 ,

NOBLE GAS SKIN 7.06E-02 ALL 678. NE 4.7E-01 1.5E+01 !

IODINE & THYROID 2.69E-02 CHILD 678. NE 1.8E-01 1.5E+01 PARTICULATES Quarter 4 :

i

SUMMARY

OF MAXIMUM INDIVIDUAL DOSES ,

LAST ACCUMULATIONS FOR PERIODS: '

LIQUID 94 1 1 1-94123124 GASEOUS 9410 1 1-94123124 '

AIR 9410 1 1-94123124 APPLICABLE ESTIMATED AGE LOCATION % OF LIMIT ,

EFFLUENT ORGAN DOSE GROUP DIST DIR APPLICABLE (MREM) (M) (TOWARD) LIMIT (MREM) ,

LIQUID TOTAL BODY 1.01E-01 CHILD RECEPTOR 1 3.4 E+00 3.0E+00 LIQUID BONE 6.05E-01 CHILD RECEPTOR 1 6.1E+00 1.0E+01 NOBLE GAS AIR DOSE 3.53E-02 900. WSW 3.5E-01 1.0E+01 (GAMMA-NRAD) 6.6E-02 2.0E+01 NOBLE GAS AIR DOSE 1.33E-02 900. WSW (BETA-MRAD) j NOBLE GAS T. BODY 1.57E-02 ALL 678. NE 3.1E-01 5.0E+00 NOBLE GAS SKIN 2.79E-02 ALL 678. NE 1.9E-01 1.5E+01 IODINE & THYROID 2.48E-02 CHILD 678. NE 1.7E-01 1.5E+01 PARTICULATES NOTE: The dose limits appearing on this page are annual k limits. The quarterly limits are listed on page 29 of this report.

Attachment 2 (Page 3 of 3)

Radiological Impact on Man (Land Based Sectors)

Year 1994

SUMMARY

OF MAXIMUM INDIVIDUAL DOSES LAST ACCUMULATIONS FOR PERIODS:

LIQUID 94 1 1 1-94123124 GASEOUS 94 1 1 1-94123124 AIR 94 1 1 1-94123124 APPLICABLE ESTIMATED AGE LOCATION % OF LIMIT-EFFLUENT ORGAN DOSE GROUP DIST DIR APPLICABLE (MREM) (M) (TOWARD) LIMIT (MREM)

LIQUID TOTAL BODY 1.01E-01 CHILO RECEPTOR 1 3.4 E+ 00 3.0E+00 LIQUID BONE 6.05E-01 CHILD RECEPTOR 1 6.1E+00 1.0E+01' NOBLE GAS AIR DOSE 1.53E-01 678. NE 1.5E+00 1.0E+01 (GAMMA-MRAD)

NOBLE GAS AIR DOSE 8.12E-02 678. NE 4.1E-01 2.0E+01 (BETA-MRAD)

N,OBLE GAS T. BODY 6.67E-02 ALL 678. NE 1.3E+00 5.0E+00 NOBLE GAS SKIN 1.26E-01 ALL 678. NE 8.4E-01 1.5E+01 IODINE & THYROID 7.99E-02 CHILD 678. NE 5.3E-01 1.5E+01 PARTICULATES

1

1 l

Attachment 3 Technical Specification Limits t

I

f l

Attachment 3 (Page 1 of 1) ;

i Technical Specification Limits

' i.IQUID EFFLUENTS: ,

+ Concentration < 10CFR 20 + release rate limit ,

Appendix,B, TaEle II TS 3.11.1.1 ,

Column 2 4 $ 1.5 mrem Total Body + quarterly dose limit 1 5 mrem any Organ per TS 3.11.1.2

+ 1 3 mrem Total Body + annual dose limit 5 10 mrem any organ per TS 3.11.1.2 Dissolved or entrained noble gas concentration is limited to 1 2 E-04 pCi/ml !

GASEOUS EFFLUENTS: !

Noble Gases ;

+ $ 500 mrem /yr Total Body 4 dose rate limit 1 3000 mrem /yr any organ per TS 3.11.2.1

. 6

+ 1 5 mrad air gamma + quarterly air dose 1 10 mrad air beta limit per TS 3.11.2.2

+ < 10 mrad air gamma + annual air dose 3 20 mrad air beta limit per TS 3.11.2.2 I-131, I-133, H-3, Particulates w/ halflives > 8 days

+ 1 1500 mrem /yr any organ + dose rate limit per TS 3.11.2.1 :

+ $ 7.5 mrem any organ + quarterly dose limit per TS 3.11.2.3

1 15 mrem any organ 4 annual dose limit per TS 3.11.2.3 ;

l i

I h

Attachment 4 Liquid Effluents I

i l

l l

I

)

1

Attachment 4 (Page 1 of 4)

Liquid Effluents e

1 -

OUARTER 1 : START DATE 94010101 END DATE 94033124 QUARTER 2 : START DATE 94040101 END DATE 94063024 EFFLUENT AND WASTE DISPOSAL REPORT LIQUID EFFLUENTS -- SUMMATION OF ALL RELEASES

UNITS : QUARTER : QUARTER :

: 1 : 2 :

A. FISSION AND ACTIVATION PRODUCTS

1. TOTAL RELEASE (EXCL.: CI : 5.75E+00 : 3.12E+00 :

TRIT.. GASES. ALPHA): : : :

2. AVERAGE DILUTED :UCI/ML : 3.89E-07 : 2.68E-07 :

CONC. DURING PERIOD : : : :

3. PERCENT OF : % : 0.00E+00 : 0.00E+00 :

APPLICABLE LIMIT : : : :

B. TRITIUM

1. TOTAL RELEASE : CI : 3.54E+00 : 1.52E+00 :

2. AVERAGE DILUTED :UCI/ML : 2.40E-07 : 1.31E-07 :

CONC. DURING PERIOD : : : :

3. PERCENT OF : % : 7.99E-03 : 4.37E-03 :

APPLICABLE LIMIT : : : :

C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE : CI : 5.09E-03 : 0.00E+00 :

2. AVERAGE DILUTED :UCI/ML : 3.44E-10 0.00E+00 :

CONC. DURING PERIOD : : : :

3. PERCENT OF : % : 1.72E-04 : 0.p0E+00 :

APPLICABLE LIMIT : : : :

D. GROSS ALPHA RADIOACTIVITY

1. TOTAL RELEASE : CI : 0.00E+00 2 0.00E+00 :

E. VOLUME WASTE RELEASED : LITERS : 2.12E+09 : 4.69E+09 :

(PRIOR TO DILUTION) : : : .

F. VOLUME DILUTION WATER : LITERS : 1.48E+10 : 1.16E+10 :

USED DURING PERIOD : : : :

F L

1 i

i k

5 Attachment 4 (Page 2 of 4) l Liquid Effluents ,

OUARTER 1 : START DATE 94010101 END DATE 94033124 i OUARTER 2 : START DATE 94040101 END DATE 94063024 !

DATE OF REPORT: MAR. 15. 1995 PREPARED BY:

CONTINUOUS MODE BATCH MODE ,

NUCLIDES UNITS : QUARTER : QUARTER : QUARTER : QUARTER : s

RELEASED : : 1 2 : 1 : 2 : i 3.54E+00 : 1.52E+00 :

H3 : CI : -------- : -- :

3.58E-05 :

a CRS1 : CI

.....__....3 7.62E-0

........... ......CI......................_-- ___ 5.64E+00 ............_.........

1.65E-03 : 1.65E-03 : '

a MN54 : CI : -------- : ----- : t

FESS : : -.--- : -------- : : 3.05E*00 : !

FE59 : : : : 3.39E-05 : 0.00E+00 :

a CI 2.76E 04 : 1.27E-05 : !

C058 : CI : ------ -------- 2 a CO60 : CI : : -------- : 9.84E-03 : 1.14E 02 : !

ZN65 : CI : - : ---- 1. 84 E-02 : 9.60E 03 : !

5

SR89 : CI : --- --.. - --- : 6.91E-02 : 4.90E-02 : }

SR90 : CI : : . - : 5. 4 5 E-03 0.00E+00 : 4

i 2R95 : CI : . -..--- ------- 1.18E-04 : 0.00E+00 : .

. NB95 : CI : - --- : ..----- : 1.76E-04 : 0.00E+00 :

TC99M : CI : ------.- : ---.---- 1.62E-04 0.00E+00 :

2.52E-05 : 0.00E+00 :

. _ _ . . . . . . . .: . . .CI

, . . . TC101 . . . . . :. . . . . . . . . . . . _ _ _ _ _ _ _ - ....................

RU103 : CI : ----- -- -------- 1.33E-03 3 0.00E+00 :

e........__...._____...___...__..-__......___..._........._-__........

AG110M : 61 : ----- : ------- 2.74E 04 8.45E-05 : l

1131 : CI : -------- : 6.26E-05 0.00E+00 :

. ._-... ........_.....__....___... , m ......_ ..__.................-

2 1133 : CI : -----.-- - ------ .1.55E 05 0.00E+00 -

i

._............_.........--. ........_.. .... ... ..____..... ...._.... h CS134 : CI : 4.75E : 5.84E !

...__05 a CS137 : CI : -------- ------ - : 7.66E-05 : 1.89E-04 : l LA140 : CI : -------- 2 ----- 1.61E 03 3 0.00E+00 :

CE141 : CI : ------- .--- -- : 2.75E 04 : 4.24E-05 :

CE144 : CI : - --- ------- 7.69E-05 0.00E+00 : I NP239 : CI : ----- - -- 1.78E-05 : 0.00E+00 : ,

3 TOTAL FOR : : : : : )

PERIOD : CI : ..---- - -.----.. : 9.30E+00 : 4. 65 E+ 00 : !

(ABOVE) : : : : : l

....v... vim m: w__e..______. . ............_--..__ ... __.....-- ... ;

NUCLIDES : UNITS : QUARTER : QUARTER : QUARTER : QUARTER : !

RELEASED : : 1 : 2 : 1 2 : l

...... .____....................... .....--...........____............ i

= XE133 : CI : .- ----- : .--.---- 3.25E-03 : 0.00E+00 :

- XE135 : CI : -------- -------- 1.84E 3 0.00E+00 : !

3

.___-03 __...__ .. __.__ >

I L

t

Attachment 4 (Page 3 of 4)

Liquid Effluents OUARTER 3 : START DATE 94070101 END DATE 94093024 OUARTER 4 : START DATE 94100101 END DATE 94123124 EFFLUENT AND WASTE DISPOSAL REPORT ,

LIOUID EFFLUENTS -- SUMMATION OF ALL RELEASES

UNITS : OUARTER : QUARTER :

: 3 : 4 :

A. FISSION AND ACTIVATION PRODUCTS

1. TOTAL RELEASE (EXCL.: CI : 2.30E+00 : 3.03E-01 :

TRIT., GASES, ALPHA): : : :

2. AVERAGE DILUTED :UCI/ML : 1.29E-07 : 1.51E-08 :

CONC. DURING PERIOD : : : :

3. PERCENT OF : % : 0.00E+00 : 0.00E+00 :

APPLICABLE LIMIT : : : :

B. TRITIUM

1. TOTAL. RELEASE : CI : 2.34E+00 : 1.88E+00 :

2. AVERAGE DILUTED :UCI/ML : 1.32E-07 : 9.36E-08 :

' : CONC. DURING PERIOD : : : :

3. PERCENT OF : % : 4.39E-03 : 3.12E-03 :

APPLICABLE LIMIT : : :

C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE : CI : 4.89E 03 : 1.16E-02 :

2. AVERAGE DILUTED :UCI/ML : 2.75E-10 : 5.76E-10 :

CONC. DURING PERIOD : : :

3. PERCENT OF : % : 1.38E-04 : 2.88E-04 :

APPLICABLE LIMIT : : : :

D. GROSS ALPHA RADIOACTIVITY

1. TOTAL RELEASE : CI : 4.44E-05 : 0.00E+00 :

E. VOLUME WASTE RELEASED : LITERS : 4.27E+09 : 8.06E+08 :

(PRIOR TO DILUTION)

F. VOLUME DILUTION WATER : LITERS : 1.78E+10 : 2.01E+10 :

USED DURING PERIOD : : : :

I I

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4 l

l L

D I

l r

Attachment 4 (Page 4 of 4)

Liquid Effluents OUARTER 3 : START DATE 94070101 END DATE 94093024 OUARTER 4 : START DATE 94100101 END DATE 94123124 DATE OF REPORT: MAR. 15. 1995 PREPARED BY:

CONTINUOUS MODE BATCH MODE

NUCLIDES : UNITS : OUARTER : OUARTER : QUARTER : OUARTER :

RELEASED : : 3 : 4 : 3 : 4 :

H3 : CI - ---

-- : --- --- : 2.34E+00 : 1.88E+00 :

CRS1 : CI : - --

----- : 6.62E 05 : 2. 4 4 E-04 :

MN54 : CI : - - --

- : 9.69E 04 : 5.04E-04 :

MN56 : CI : -------- : -------- : 0.00E+00 : 5.55E 05 :

FESS : CI : -------- : -------- : 2.25E+00 : 2.66E-01 :

CO60 : CI : -------- : ---- --- : 7.26E-03 : 3.75E-03 :

ZN65 : CI : -------- : -------- : 5.06E-03 : 1.69E 03 :

SR89 : CI : -------- : -------- : 2.92E-02 : 2.84E-02 :

Y93 : CI : -------- : -

: 2.63E-05 : 0.00E+00 :

TC99M : CI : -------- : --------

6.45E-06 : 5.31E-05 :

1131 : CI : -------- : -------- : 4.73E-04 : 3.92E-04 :

1133 : CI : -------- : --_-----

1.30E-04 : 3.57E-05 :

1134 : CI : -------- : ------ - : 0.00E+00 : 9.32E-05 :

CS134 : CI : - - : --

--- : 7.74E-05 : 4.70E 05 :

CS137 : CI : - : --

--- : 2.71E-04 : 1.55E-04 :

CS138 : CI : --------

-------- : 7.16E-05 : 4.31E-05 :

BA139 : CI : - ----

0.00E+00 : 4.08E-05 :

LA140 : CI : -------- : --------

1.16E-04 : 9.97E-04 :

CE141 : CI : --------

0.00E+00 : 2.94E-05 :

SB124 : CI : --------

0.00E+00 : 6.18E-06 :

- SB125 : CI : - ------ : -------- : 1.17E-04 : 2.93E-04 :

TOTAL FOR : : : : : :

PERIOD : CI : -------- : --------

4.64E+00 : 2.18E+00 :

(ABOVE) : : : : : :

NUCLIDES : UNITS : QUARTER : QUARTER : QUARTER : QUARTER :

RELEASED : : 3 : 4 : 3 : 4 :

= XE133 : CI : -------- : -------- : 4.36E-03 : 1.00E-02 :

= XE135 : CI : -------- : --------

4.28E-04 : 1.37E-03 :

XE133M : CI : -------- : -------

1.07E-04 : 1.65E-04 :

P i

Attachment 5 h Gaseous Effluents t

0 6

I 6

Attachment 5 (Page 1 of 6)

Gaseous Effluents OUARTER 1 : START DATE 94010101 END DATE 94033124 QUARTER 2 : START DATE 94040101 END DATE 94063024 1

EFFLUENT AND WASTE DISPOSAL REPORT GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES

UNITS : OUARTER : QUARTER :

: 1 : 2 :

A. FISSION AND ACTIVATION GASES

1. TOTAL RELEASE : CI : 7.15E+01 : 0.00E+00 :

2. AVERAGE RELEASE :UCI/SEC: 9.20E+00 : 0.00E+00 :

RATE FOR PERIOD : : : :

3. PERCENT OF TECHNICAL: % : 0.00E+00 : 0.00E+00 :

SPECIFICATION LIMIT : : : :

B. IODINES

1. TOTAL IODINE-131 : CI : 8.05E 03 : 3.36E-05 :

2. AVERAGE RELEASE :UCI/SEC: 1.04E-03 : 4.27E-06 :

RATE FOR PERIOD : : : :

3. PERCENT OF TECHNICAL: % : 0.00E+00 : 0.00E+00 :

SPECIFICATION LIMIT : : : :

C. PARTICULATES

1. PARTICULATES WITH : CI : 2.13E-02 : 7.31E.06 :

HALF _ LIVES >8 DAYS : : : :

2. AVERAGE RELEASE :UCI/SEC: 2.74E-03 : 9.30E-07 :

RATE FOR PERIOD : : : :

3. PERCENT OF TECHNICAL: % : 0.00E+00 : 0.00E+00 :

SPECIFICATION LIMIT : : : :

4. GROSS ALPHA : CI : 3.57E-05 : 4*12E-05 ::

RADIOACTIVITY : : :

D. TRITIUM

1. TOTAL RELEASE : CI : 0.00E+00 : 0.00E+00 :

2. AVERAGE RELEASE :UCI/SEC: 0.00E+00 : 0.00E+00 :

RATE FOR PERIOD : : : :

I

3. PERCENT OF TECHNICAL: % : 0.00E+00 : 0.00E+00 :

SPECIFICATION LIMIT : : : :

i 1

Attachment 5 (Page 2 of 6)

Gaseous Effluents OUARTER 1 : START DATE 94010101 END DATE 94033124 OUARTER 2 : START DATE 94040101 END D' E 94063024 DATE OF REPORT: MAR. 15, 1995 PREPARED BY:

CONTINUOUS rN;DJ BATCH MODE

NUCLIDES : UNITS : QUARTER : QLWn . R : QUARTER : QUARTER :

RELEASED : : 1 : : 1 : 2 :

1. FISSION AND ACTIVATION GASES ... ...______.._________ ...-____.

KR85M : CI : 4.34E 01 : 0.COE+00 . : --

KR87 : CI : 4.79E-03 : 9.0GEs00 : ------

KR88 : CI : 3.10E 01 : 0.]uE+)0 : : -

XE131M : CI : 7.47E 02 : 0.L9E+00 : --

XE133M : CI : 4.46E 01 : 0.00E+00 : : --- - :

XE133 : CI : 2.64E+01 : 0.00E+00 : -----

XE135M : CI : 2.56E+01 : 0.00E+00 : --- : :

XE135 : CI : 1.82E+01 : 0.00E+00 : --

TOTAL FOR : : : : : :

PERIOD : CI : 7.15E+01 : 0.00E+00 : -------- : --------

': (ABOVE) : : : : : :

2. IODINES

1131 : CI : 8.05E 03 3.36E 05 : ---- - : - ------ :

1133 : CI : 1.27E-02 : 0.00E+00 -------- : -------- :

= 1132 : CI : 1.21E-03 : 0.00E+00 : -------- : -------- :

1135 : CI : 8.93E-03 : 0.00E+00 : : ------- :

1134 : CI : 1.50E 03 : 0.00E+00 : ---- : - -

TOTAL FOR : : : : : :

PERIOD : CI : 3.24E-02 : 3.36E-05 : -------- : -------- :

(ABOVE) : : : : :

j

Attachment 5 (Page 3 of 6)

Gaseous Effluents l OUARTER 1 : START DATE 94010101 END DATE 94033124 OUARTER 2 : START DATE 94040101 END DATE 94063024 DATE OF REPORT: MAR. 15. 1995 .

PREPARED BY:

CONTINUOUS MODE BATCH MODE NUCLIDES : UNITS : QUARTER : QUARTER : QUARTER : QUARTER :

RELEASED : : 1 : 2 : 1 : 2 :

3. PARTICULATES SR89 : CI : 2.69E-04 : 7.29E-06 : -------- : --------

SR50 : CI : 1.93E-06 : 1.59E-08 : -------- : --------

BA140 : CI : 9.60E-04 : 0.00E+00 : -------- : -------- :

- CS138 : CI : 6.35E-03 : 0.00E+00 : -------- * --------

= BA139 : CI : 1.04E-02 : 0.00E+00 : --------

s'a SR91 : CI : 2.02E-03 0.00E+00 : --------

LA140 : CI : 7.65E-04 : 0.00E+00 : --------

= TC99M : CI : 1.28E-04 : 0.00E+00 : --------

SR92 : CI : 4.83E-04 : 0.00E+00 : --------

TOTAL FOR : : : : : :

PERIOD : CI : 2.13E-02 : 7.31E-06 : -------- : --------

(ABOVE) : : : : : :

t I

t l

1 l

i I

Attachment 5 (Page 4 of 6)

Gaseous Effluents OUARTER 3 : START DrTE 94070101 END DATE 94093024 QUARTER 4 : START DATE 94100101 END DATE 94123124 EFFLUENT AND WASTE DISPOSAL REPORT GASEOUS EFFLUENTS -- SUMMATION OF ALL RELEASES

UNITS : QUARTER : QUARTER :

: 3 : 4 :

A. FISSION AND ACTIVATION GASES

1. TOTAL RELEASE : CI : 9.01E+01 : 7.33E+01 :

2. AVERAGE RELEASE :UCI/SEC: 1.13E+01 :: 9.22E+00 ::

RATE FOR PERIOD : :

3. PERCENT OF TECHNICAL: % : 0.00E+00 : 0.00E+00 :

SPECIFICATION LIMIT :

B. IODINES

1. TOTAL IODINE-131 : CI : 1.61E 03 : 3.27E-03 :

2. AVERAGE RELEASE :UCI/SEC: 2.02E-04 :: 4.12E-04 ::

RATE FOR PERIOD : :

' : 3. PERCENT OF TECHNICAL: % : 0.00E+00 : 0.00E+00 :

SPECIFICATION LIMIT : :

C. PARTICULATES

1. PARTICULATES WITH : CI : 2.74E-02 : 2.20E-02 :

HALF LIVES >8 DAYS : :

2. AVERAGE RELEASE :UCI/SEC: 3.45E-03 :: 2.77E-03 ::

RATE FOR PERIOD : :

3. PERCENT OF TECHNICAL: % : 0.00E+00 2 0.00E+00 :

SPECIFICATION LIMIT : : :

CI : :

4. GROSS ALPHA RADIOACTIVITY :

5*27E-05 : 1*81E-05 :

D. TRITIUM

1. TOTAL RELEASE : CI : 0.00E+00 : 0.00E+00 :

2. AVERAGE RELEASE :UCI/SEC: 0.00E+00 : 0.00E+00 : :

RATE FOR PERIOD : : :

3. PERCENT OF TECHNICAL: % : 0.00E+00 : 0.00E+00 :

SPECIFICATION LIMIT : : : :

1 0 j i

i

Attachment 5 (Page 5 of 6)

Gaseous Effluents OUARTER 3 : START DATE 94070101 END DATE 94093024 OUARTER 4 : START DATE 94100101 END DATE 94123124 DATE OF REPORT: MAR. 15. 1995 PREPARED BY:

I CONTINUOUS MODE DATCH MODE NUCLIDES : UNITS : QUARTER : QUARTER : QUARTER : QUARTER :

RELEASED : : 3 : 4 : 3 : 4 :

1. FISSION AND ACTIVATION GASES AR41 : CI : 2.97E-01 : 0.00E+00 : -

KR85M : CI : 5.71E 01 : 3.07E 02 : -

KR87 : CI : 1.89E+00 : 1.78E 01 : -

KR88 : CI : 1.58E+00 : 1.10E-01 : - : -- - :

XE133M : CI : 1.28E-01 : 1.18E+00 : -- -

XE133 : CI : 8.90E+00 : 1.14E+01 : --- ----- :

XE135M : CI : 3.31E+01 : 4.07E+01 : -

XE135 : CI : 1.64E+01 : 1.79E+01 : -

XE137 : CI : 4.05E+00 : 2.54E 01 : ----

XE138 : CI : 2.32E+01 : 1.50E+00 : - -

TOTAL FOR : : : : : :

PERIOD : CI : 9.01E+01 : 7.33E+01 : --------

(ABOVE) : : : : :

2. IODINES 1131 : CI : 1.61E-03 : 3.27E 03 : -- : --- :

1133 : CI : 3.46E-03 : 9.00E-03 : -------- -------- :

I132 : CI : 3.00E 04 : 1.11E 03 : -

_=___. .__________________________.._______.___________- ..

- 1135 : CI : 2.09E-03 : 6.82E-03 : -------- -------- :

= 1134 : CI : 3.92E-04 : 2.06E-03 : -------- : -------- :

TOTAL FOR : : : : : :

PERIOD : CI : 7.85E-03 : 2.23E-02 : -------- : -------- :

(ABOVE) : : : : : i

__-..____.____..___.._..._______...____..___.__..___ ____._____..____. i 1

i Attachment 5 (Page 6 of 6)

Gaseous Effluents QUARTER 3 : START DATE 94070101 END DATE 94093024 OUARTER 4 : START DATE 94100101 END DATE 94123124 DATE OF REPORT: MAR. 15. 1995 PREPARED BY:

CONTINUOUS MODE BATCH MODE

NUCLIDES : UNITS : QUARTER : QUARTER : QUARTER : QUARTER :

RELEASED : : 3 : 4 : 3 : 4 :

3. PARTICULATES

SR89 : 1.73E-04 : 4.58E-04 :

CI : ----- -------

SR90 : CI : 4.13E-07 : 1.26E-06 : --------

BA140 : CI : 3.02E-04 : 5.94E-04 : -------- : -------- :

= CS138 : CI : 1.41E-02 : 8.26E-03 : -------- : --------

- AG110M : CI : 5.43E-05 : 3.33E-05 : --------

BA139 : CI : 7.60E-03 : 9.80E-03 : --------

SR91 : CI : 4.24E-04 : 9.99E-04 : --------

,* Y91M : CI : 0.00E+00 : 4.22E-04 : --------

- LA140 : CI : 2.53E-04 : 4.12E-04 : --------

RB88 : CI : 2.00E-03 : 0.00E+00 : --------

Y88 : CI : 1.52E-04 : 0.00E+00 : -------- : -------- :

RB89 : CI : 2.24E-03 : 1.86E-04 : -------- : -------- :

MN56 : CI : 1.75E-04 : 4.80E-04 : ---- ---

SR92 : CI : 0.OOE+00 : 1.59E-04 : -------- : -------- :

- NB95 : CI : 5.42E-06 : 0.00E+00 : -- ----

RU106 : CI : 0.00E+00 : 1.72E-04 : -------- : --------

TOTAL FOR : : : : : :

PERIOD : CI : 2.74E-02 : 2.20E-02 : --------

(ABOVE) : : : : : :

b L

Attachment 6 Solid Waste Attachment 6 (Page 1 of 4)

Solid Waste Solid Waste shipped offsite for disposal during period from January 1 to December 31, 1994 WASTE STREAM:

Resins, Filters, and Evaporator Bottoms Waste Cubic Cubic Curies % Error Class Feet Meters Shipped (Ci)

A 1689.5 44.1 2.79E+03 + 25 B 132.4 3.7 2.08E+03 T 25 C 0.0 0.0 0.00 R/A All 1821.9 47.8 4.87E+03 + 25 WASTE STREAM:

Dry Active Waste Waste Cubic Cubic Curies % Error Class Feet Meters Shipped (Ci)

A 50368.0 1429.2 3.70E+00 + 25 B 284.9 8.1 9.51E+01 7 25 C 0.0 0.0 0.00 H/A All 50652.9 1437.2 9.88E+01 + 25 WASTE STREAM:

Irradiated Fuel Waste Cubic Cubic Curies % Error Class Feet Meters Shipped (Ci)

A 0 0 0 N/A B 0 0 0 N/A C 0 0 0 N/A All 0 0 0 N/A WASTE STREAM:

Other Waste Waste Cubic Cubic Curies % Error Class Feet Meters Shipped (Ci)

A 0 0 0 N/A B 0 0 0 N/A C 0 0 0 N/A ,

All 0 0 0 N/A l l

1 1

I Attachment 6 (Page 2 of 4)

Solid Waste l

Estimates of major radionuclides by Waste type.

WASTE TYPE: i Resins, Filters, and Evaporator Bottoms t

Waste Nuclide Percent Curies Class Name Abundance A Zn-65 63.093% 1.14E+02 Fe-55 19.666% 3.54E+01 Co-60 11.976% 2.16E+01 Cs-137 2.083% 3.75E+00 ,

Mn-54 1.642% 2.96E+00 Cs-134 1.058% 1.90E+00 Ni-63 .178% 3.21E-01 C-14 .080% 1.45E-01 H-3 .028% 5.02E-02 Sr-90 .023% 4.05E-02 Pu-241 .002% 3.04E-03 Cm-242 .000% 2.02E-04 I-129 <LLD> 0.00E+00 Tc-99 <LLD> 0.00E+00

.I est

}

Attachment 6 (Page 3 of 4)

Solid Waste WASTE TYPE:

Resins,_ Filters, and Evaporator Bottoms Waste Nuclide Percent Curies Class Name Abundance B Zn-65 52.404% 1.09E+03 Fe-55 22.644% 4.71E+02 Co-60 11.731% 2.44E+02 Cr-51 8.606% 1.79E+02 Mn-54 1.904% 3.96E+01 Co-58 1.404% 2.92E+01 Cs-137 .222% 4.61E+00 Ni-63 .154% 3.20E+00 C-14 .030% 6.16E-01 Sr-90 .014% 2.90E-01 H-3 .001% 1.17E-02 I-129 <LLD> 0.00E+00 Tc-99 <LLD> 0.00E+00 t

m i

l Attachment 6 (Page 4 of 4)

Solid Waste WASTE TYPE:

Dry Active Waste Waste Nuclide Percent Curies :

Class Name Abundance I A Fe-55 66.060% 6.82E401 Co-60 23.758% 2.45E+01 Zn-65 6.366% 6.57E+00 Mn-54 3.311% 3.42E+00 Ni-63 .364% 3.76E-01 Cs-137 .078% 8.02E-02 Pu-241 .011% 1.15E-02 H-3 .006% 5.88E-03 Ni-59 .004% 4.54E-03 Cm-242 .001% 1.21E-03 Nb-94 .001% 6.00E-04 C-14 .001% 5.57E-04 -

I-129 <LLD> 0.00E+00 Tc-99 <LLD> 0.00E+00 Waste Nuclide Percent curies Class Name Abundance :

B 39.506%

Fe-55 3.76E+01 !

Zn-65 29.232% 2.78E+01 i Co-60 16.309% 1.55E+01 Cr-51 6.036% 5.74E+00 Mn-54 [

5.026% 4.78E+00 Cs-137 1.308% 1.24E+00 Sr-90 .429% 4.08E-01 Ni-63 .276% 2.63E-01 Pu-241 .013% 1.28E-02 H-3 .013% 1.21E-02 ,

Cm-242 .002% 1.53E-03 C-14 .001% 9.11E-04 Ni-59 .000% 2.50E-04 Tc-99 .000% 7.92E-06 I-129 <LLD> 0.00E+00 Solid Waste Disposal Summary Number of Mode of Shipments Transportation Destination 14 Truck Barnwell 23 Truck SEG j

l I

I l

T Attachment 7 i

Meteorological Data e

i e

w 1

l l

l i

l Attachment 7 (Page 1 of 20) i Joint Frequency Distribution Tables - 1994: Quarter 1 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 94010101-94033124 STABILITY CLASS: A DT/DZ ELEVATION: SPEED:SPD10P DIRECTION:DIR10P LAPSE:DT50M WIND SPEED (MPH)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N O O O O O O O NNE O O 2 0 0 0 2 NE O O O O O O O ENE O O O O O O O E 1 0 0 0 0 0 1 ESE O O O O O O O ,

SE O 1 0 0 0 0 1 SSE O O O O O O O S 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 0 SW 1 0 0 0 0 0 1 WSW 0 0 0 1 0 0 1 W 0 0 1 0 0 0 1 WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0 TOTAL 2 1 3 1 0 0 7 PERIODS OF CALM (HOURS): O VARIABLE DIRECTION O HOURS OF MISSING DATA: 0 t

ENTER: [ RETURN) CONTINUE. [SO) START OVER. [EX) TO EXIT SITE: PERRY UNIT: UNIT 1 03/15/95 13:17 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 94010101-94033124 STABILITY CLASS: B DT/DZ ELEVATION: SPEED:SPD10P DIRECTION:DIR10P LAPSE:DT50M WIND SPEED (MPH)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N O O 2 0 0 0 2 NNE O 1 3 0 0 0 - 4 NE O O 3 0 0 0 3 ENE O O O O O O O E O O O O O O O ESE O O O O O O O SE O O O O O O O SSE O O O O O O O S 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 0 SW D 0 0 0 0 0 0 WSW 0 0 0 6 0 0 6 W D 0 6 6 0 0 12 WNW O O 3 0 0 0 3 NW D 0 0 0 0 0 0 NNW O O O O O O O TOTAL 0 1 17 12 0 0 30 PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION O HOURS OF MISSING DATA: 0

-__ ..~ > .. - _ ._. .. . .

4 Attachment 7 (Page 2 of 20)

Joint Frequency Distribution Tables - 1994: Quarter 1 HOURS AT'EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 94010101-94033124 .

STABILITY CLASS: C DT/DZ !

ELEVATION: SPEED:SPD10P DIRECTION:DIR10P LAPSE:DT50M i WIND SPEED (MPH) !

WIND !

DIRECTION 1 4-7 >24 TOTAL +

________. _ _- 3_ __. 8-12 _13-18 19-24 N- 0 0 1 0 0 0 1 NNE O 1 9 0 0 0 10 ;

NE O O 9 0 0 0 9 ,

ENE O O 2 4 0 0 6 E O 1 0 0 0 0 1 !

ESE O O 1 1 0 0 2 l' SE O O 1 0 0 0 1 SSE O O O 2 0 0 2 ;

S 0 0 0 0 0 0 0 '

SSW 0 2 0 0 0 0 2 SW 0 0 0 3 0 0 3 WSW 0 0 0 8 0 0 8 ';

W 0 1 11 6 0 0 18 WNW 0 1 10 5 0 0 16 NW 1 0 1 0 0 0 2 NNW 0 1 0 0 0 0 1 !

TOTAL 1 7 45 29 0 0 82 PERIODS OF CALM (HOURS): 0 {

VARIABLE DIRECTION O l HOURS OF MISSING DATA: 0 3 ENTER: [ RETURN] CONTINUE, [SO) START OVER, [EX) TO EXIT t

SITE: PERRY UNIT: UNIT 1 03/15/95 13:18 !

HOURS AT EACH WIND SPEED AND DIRECTION i PERIOD OF RECORD = 94010101-94033124 STABILITY CLASS: D DT/DZ

ELEVATION: SPEED:SPD10P DIRECTION:DIR10P LAPSE:DT50M ;

WIND SPEED (MPH)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL l

_________ ___ ___ ___. _____ ___.. ___ _____ t N 5 32 17 4 0 0 58 '

NNE 6 36 18 4 0 0 . 64 T NE 6 30 52 17 7 0 112 -

ENE 4 27 59 26 2 0 118 E 11 24 8 0 0 0 43 ESE 2 16 15 0 0 0 33 -

SE 5 14 20 22 0 0 61 i SSE 4 11 14 10 1 0 40 S 5 13 28 16 0 0 62 SSW 4 18 51 24 0 0 97 SW 5 23 70 27 1 0 126 WSW 4 40 103 87 18 0 252 '

W 2 42 91 36 2 0 173 WNW 5 53 40 22 0 0 120 i NW 2 32 32 13 2 0 81 NNW 5 38 30 6 0 0 79 l

..__ .________.____________.........______________.._____.____ i TOTAL 75 449 648 314 33 0 1519 i PERIODS OF CALM (HOURS): 0 !

VARIABLE DIRECTION O !

HOURS OF MISSING DATA: 0 t

I

{

~# - .r_ = _

?

Attachment 7 (Page 3 of 20) {

Joint Frequency Distribution Tables - 1994: Quarter 1 HOURS AT EACH WIND SPEED AND DIRECTION i PERIOD O' RECORD = 94010101-94033124 STABILITY CLASS: E DT/DZ ,

ELEVATION: SPEED SPD10P DIRECTION:DIR10P LAPSE:DT50M !

WIND SPEED (MPH)

WIND '

DIRECTION 1-3 4-7 8-12 13 19 >24' TOTAL !

... ____. ___ _.. .... ___-18 ___-24 N 5 2 0 0 0 0 7 .

NNE 3 1 0 0 0 0 4 i NE 3 3 0 0 0 0 6 i ENE 5 23 3 0 0 0 31 :

E 11 7 1 0 0 0 19 ?

ESE 1 3 1 0 0 0 5 >

SE 2 8 2 1 0 0 13 SSE 7 7 10 0 0 0 24 !

S 4 .5 28 16 0 0 64 :

SSW 8 40 32 5 0 0 85 !

SW 8 24 10 2 0 0 44 WSW 6 13 21 1 0 0 41 :

W 2 8 3 0 0 0 13 [

WNW 10 0 0 0 12 2 0 NW 1 2 0 0 0 0 3 NNW 2 0 0 0 0 0 2 f

____________.________ _________._________.. ______________..__ [

TOTAL 70 167 111 25 0 0 373 !

PERIODS OF CALM (HOURS): 0 !

VARIABLE DIRECTION O f HOURS OF MISSING DATA: O ENTER: [ RETURN) CONTINUE, [SO) START'OVER, [EX) TO EXIT j SITE: PERRY UNIT: UNIT 1 03/15/95 13:19 ,

i HOURS AT EACH WIND SPEED AND DIRECTION '

PERIOD OF RECORD = 94010101-94033124 ,

STABILITY CLASS: F DT/DZ !

ELEVATION: SPEED SPD10P DIRECTION:DIR10P LAPSE:DT50M WIND SPEED (MPH)

WIND e DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL NNE O O O O O O _ 0 i NE 1 0 0 0 0 0 1 ENE 5 3 0 0 0 0 8 E 7 1 0 0 0 0 8 :

ESE 6 3 0 0 0 0 9 i SE 5 4 0 0 0 0 9 SSE 2 8 0 0 0 0 10 i S 5 9 2 0 0 0 16 ;

SSW 8 2 0 0 0 0 10 ,

SW 1 3 0 0 0 0 4 i WSW 0 0 0 0 0 0 0 l W 1 0 0 0 0 0 1 WNW 0 2 0 0 0 0 2 NW 1 1 0 0 0 0 2 NNW 0 0 0 0 0 0 0 ,

TOTAL 42 36 2 0 0 0 80 I

_ _______.._________. ___ ....._____________.__ ...._______... )

' PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION O HOURS OF MISSING DATA: 0

.- . - - - . _- . . , .~ - . .

1 l

i Attachment 7 (Page 4 of 20) l Joint Frequency Distribution Tables - 1994: Quarter 1 1

HOURS AT EACH WIND SPEED AND DIRECTION ;

-PERIOD OF RECORD = 94010101-94033124 -!

STABILITY CLASS: G DT/DZ j ELEVATION: SPEED SPD10P DIRECTION: DIR10P LAPSE DT50M WIND SPEED (MPH) .

WIND l i

DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N O O 1 0 0 0 1 NNE 1 0 0 0 0 0 1 NE O O O O O O O i ENE 2 0 0 0 0 0 2 ;

E 2 1 0 0 0 0 3 ,

ESE 4 0 0 0 0 0 4 t SE 18 4 0 0 0 0 22 SSE 11 1 0 0 0 0 12 '

S 5 1 0 0 0 0 6 SSW 9 3 0 0 0 0 12 SW 4 0 0 0 0 0 4 i WSW 0 0 0 0 0 0 0 W 1 0 0 0 0 0 1 -

i WNW 1 0 0 0 0 0 1 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0 TOTAL 58 10 1 0 0 0 69 ,

PERIODS OF CALM (HOURS): 0 I VARIA8LE DIRECTION O i HOURS OF MISSING DATA: 0 ENTER: [ RETURN] CONTINUE, [SO) START OVER. [EX] TO EXIT !

i e

SITE: PERRY UNIT: UNIT l' 03/15/95 13:15 HOURS AT EACH WIND SPEED AND DIRECTION i PERIOD OF RECORD = 94010101-94033124 l STABILITY CLASS: ALL DT/DZ ELEVATION: SPEED:SPD10P DIRECTION DIR10P LAPSE DT50M WIND SPEED (MPH)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL ;

NNE 10 39 32 4 0 0 85 ;

NE 10 33 64 17 7 0 ~131 ENE 16 53 64 30 2 0 165 E 32 34 9 0 0 0 75 ;

53 ;

ESE 13 22 17 1 0' .0 SE 30 31 23 23 0 0 107 .

SSE 24 27 24 12 1 0 88 !

S 19 39 58 32 0 0 148 SSW 29 65 83 29 0 0 206 i SW 19 50 80 32 1 0 182 WSW 10 53 124 103 18 -0 308 i W -6 51 112 48 2 0 219 -

WNW 8 66 53 27 0 0 154 i NW 5 35 33 13 2 0 88 i NNW 7 39 30 6 0 0 82 ,

TOTAL 248 671 827 381 33 0 2160 PERIODS OF CALM (HOURS): 0 !

VARIABLE DIRECTION O HOURS OF MISSING DATA: 0 -

l

Attachment 7 (Page.5 of 20)

Joint Frequency Distribution Tablos - 1994: Quarter 2 HOURS AT EACH WIND' SPEED AND DIRECTION PERIOD OF RECORD = 94040101-94063024 STABILITY. CLASS: A DT/DZ i ELEVATION: SPEED:SPD10P DIRECTION:DIR10P LAPSE:DT50M l

__.. ....__ _______..___.. .___..__.___....________...__.....__. i WIND SPEED (MPH) l WIND .

DIRECTION 1-3 4-7 8-12 13 19-24 >24 TOTAL

_....____ ... __. .... .._-18_. _____ ... ..___ ;

N O O 1 0 0 0 1 i NNE O O 3 0 0 0 3 :

NE O 2 11 0 0 0 13 !

ENE O O O O O O O !

E O O O O O O O h ESE ,0 0 0 0 0 0 0 .

SE O O 1 0 0 0 1 SSE O O O O O O O ;

S 0 0 0 0 0 0 0 l SSW 0 0 0 2 0 0 2 SW 1 0 0 0 0 0 1 '

WSW 0 1 0 0 0 0 1 )

W D 1 13 7 0 0 21 l WNW O O 4 0 0 0 4 I

NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0 '

TOTAL 1 4 33 9 0 0 47 I PERIODS OF CALM (HOURS): 0 ,

VARIABLE DIRECTION O i HOURS OF MISSING DATA: 5 ENTER: [ RETURN) CONTINUE, [SO) START OVER. [EX) TO EXIT ;

e r SITE: PERRY UNIT: UNIT 1 03/15/95 13:22 .

HOURS AT EACH WIND SPEED AND DIRECTION I PERIOD OF RECORD = 94040101-94063024 i STABILITY CLASS: B DT/DZ !

ELEVATION: SPEED SPD10P DIRECTION:DIR10P LAPSE DT50M l WIND SPEED (MPH) ;

WIND DIRECTION 1 4-7 8-12 13-18 19-24 >24 TOTAL

___.... . _-3__ ... ..._ ..... _____ __. .....

N O 2 3 0 0 0 5

I NNE O 3 4 0 0 0 .- 7 NE O 3 15 1 0 0 19 !

ENE O O 2 0 0 0 2 !

E 0 0 2 O 1 1 0 ESE O O O O O O O SE O O 3 0 0 0 3 i SSE O O O O O O O S 0 1 0 0 0 0 1 )

SSW 0 1 0 4 0 0 5 i SW 0 0 0 2 0 0- 2 ,

WSW 0 1 2 5 1 0 9 W 0 3 27 5 0 0 35 ;

.WNW 0 0 13 0 0 0 13 NW 0 1 2 0 0 0 3 NNW 0 4 0 0 0 0 4 TOTAL 0 20 72 17 1 0 110 PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION O .

HOURS OF MISSING DATA: 5 !

l l

)

1 1

r Attachment 7 (Page 6 of 20) >

Joint Frequency Distribution Tables - 1994: Quarter 2 HOURS AT EACH WIND SPEED AND DIRECTION '

PERIOD OF RECORD = 94040101-94063024 ;

STABILITY CLASS: C DT/DZ !

ELEVATION: SPEED:SPD10P DIRECTION:DIR10P LAPSE:DTSOM !

WIND SPEED (MPH) i WIND ;

DIRECTION 1-3 4-7 >24 TOTAL

_._...... ... ... 8-12 13 _18 19-24 N O 14 1 1 0 0 16

NNE O 12 4 0 0 0 16 ,

NE 1 1 13 2 0 0 17 ENE 1 1 3 0 0 0 5 ?

E O 2 0 0 0 0 2 .

ESE O O 5 0 0 0 5 +

SE O 2 5 0 0 0 7 SSE O O O O O O O i S 0 0 2 1 1 0 4 !

SSW 0 0 4 3 1 0 8 SW 0 2 3 0 1 0 6 i WSW 0 1 6 8 3 0 18 ,

W 0 5 20 7 1 0 33 7 WNW 0 5 18 1 0 0 24 NW 0 4 11 0 0 0 15 e NNW 0 8 8 2 0 0 18 TOTAL 2 57 103 25 7 0 194 PERIODS OF CALM (HOURS): 0 !

VARIABLE DIRECTION O HOURS OF MISSING DATA: 5

ENTER: [ RETURN] CONTINUE. [SO) START OVER. [EX) TO EXIT SITE: PERRY UNIT: UNIT 1 03/15/95 13:22 HOURS AT EACH WIND SPEED AND DIRECTION ,

PERIOD OF RECORD = 94040101-94063024 STABILITY CLASS: D DT/DZ l ELEVATION: SPEED:SPD10P DIRECTION DIR10P LAPSE:DT50M ?

WIND SPEED (MPH) !

WIND DIRECTION 1-3 47 8-12 13 18 19 >24 TOTAL I

......__. ... __. .... . ___ __-24 N 4 45 11 1 0 0 61 ,

NNE 6 22 17 0 0 0- 45 i NE 5 14 36 1 0' O 56 i ENE 3 14 20 1 0 0 38 E 1 14 2 0 0 0 17 ESE 1 7 8 0 0 0 16 i SE 3 8 4 0 0 0 15 '

SSE 1 12 5 4 1 0 23 S 2 8 17 4 1 0 32 !

SSW 2 20 38 17 0 0 77 SW 2 20 29 14 0 0 65 WSW 5 24 36 31 5 0 101 W 6 36 44 10 0 0 96 WNW 3 56 21 3 0 0 83 ;

NW 3 58 33 13 0 0 107 -

NNW 6 45 31 4- 0 0 86 i TOTAL 53 403 352 103 7 0 918 PERIODS OF CALM (HOURS): 0 '

VARIABLE DIRECTION O HOURS OF MISSING DATA: 5 *

)

Attachment 7 (Page 7 of'20)

Joint Frequency Distribution Tables - 1994: Quarter 2 HOURS AT ~ EACH WIND SPEED AND DIRECTION .

PERIOD OF RECORD = 94040101-94063024 i STABILITY CLASS: E DT/DZ !

ELEVATION: SPEED:SPD10P DIRECTION:DIR10P LAPSE:DT50M j WIND SPEED (MPH) :)

WIND i DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL j

...... __ ... ... .. . ..... _____ ___ _____ t N 3 9 1 0 0 0 13 NNE 2 12 1 0 0 0 15 NE 2 7 1 0 0 0 10 i ENE 3 13 1 0 0 0 17

E 9 5 1 0 0 0 15 ,

ESE 8 9 0 0 0 0 17 i SE 5 12 6 0 0 0 23 !

SSE 6 24 10 2 0 0 42 i S 7 45 35 6 0 0 93 f SSW 9 50 25 5 0 0 89 s SW 17 33 25 6 0 0 81 WSW 8 15 19 8 0 0 50 W 7 6 11 2 0 0 26 WNW 2 1 3 0 0 0 6 t NW 0 3 3 1 0 0 7 ;

NNW 3 3 1 0 0 0 7

. b__. ..... ....b_____ ... ___. __ _____ ..___ __.. b___..

PERIODS OF CALM (HOURS): 0 l VARIABLE DIRECTION O HOURS OF MISSING DATA: 5 i ENTER: [ RETURN] CONTINUE, [SO] START OVER. [EX] TO EXIT i SITE: PERRY UNIT: UNIT 1 03/15/95 13:22 ;

HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 94040101-94063024 ;

STABILITY CLASS: . F DT/DZ i ELEVATION: SPEED:SPD10P DIRECTION:DIR10P- LAPSE:DT50M j

_..___.......____. ......_._______...__..__...______.._____. ... 3

~

WIND SPEED (MPH)

WIND ,

DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL l t

N 3 0 0 0 0 0 3 NNE 2 0 0 0 0 0 -- 2 NE 3 0 0 0 0 0 3 ENE 6 4 0 0 0 0 10 E 11 2 0 0 0 0 13 '

ESE 7 9 0 0 0 0 16 SE 6 2 0 0 0 0 8 SSE 8 7 0 0 0 0- 15 S 15 8 0 0 0 0 23 SSW 5 10 0 0 0 0 15 i SW 11 1 0 0 0 0 12 :

WSW 3 2 0 0 0 0 5 W 2 1 0 0 0 0 3 WNW 2 1 0 0 0 0 3 ;

NW 1 2 0 0 0 0 3 NNW O O O O O O O ,

TOTAL 85 49 0 0 0 0 134 PERIODS OF CALM (HOURS): 2 VARIABLE DIRECTION O ,

HOURS OF MISSING DATA: 5 ,

1

i i

i Attachment 7 (Page 8 of 20) l Joint Frequency Distribution Tables - 1994: Quarter 2 HOURS AT EACH WIND SPEED AND DIRECTION ,

PERIOD OF RECORD - 94040101-94063024 STABILITY CLASS: G DT/DZ ELEVATION: SPEED:SPD10P DIRECTION:DIR10P LAPSE:DT50M-WIND SPEED (MPH)

WIND .

DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL 3 0 0 0 0 0 3 N 1 NNE 1 0 0 0 0 0 4 1 0 0 0 0 5 NE 15 15 0 0 0 0 0 ENE 0 38 ;

38 0 0 0 0 E

50 4 0 0 0 0 55 ESE 0 0 48 SE 44 4 0 0 39 3 0 0 0 0 42 !

SSE 0 32 S 29 3 0 0 0 9 1 0 0 0 0 10 SSW 0 0 0 9 SW 9 0 0 '

3 0 0 0 0 0 3 WSW 3 0 0 0 0 0 3 W 0 0 0 WNW 0 0 0 0 -

0 0 0 0 0 0 0 NW 0 0 1 NNW 1 0 0 0 TOTAL 248 16 0 0 0 0 265 PERIODS OF CALM (HOURS): 5 VARIABLE DIRECTION O HOURS OF MISSING DATA: 5 ENTER: [ RETURN] CONTINUE. [SO) START OVER. [EX) TO EXIT 03/15/95 13:23

~

SITE: PERRY UNIT: UNIT 1 HOURS AT EACH WIND SPEED AND DIRECTION ,

PERIOD OF RECORD = 94040101-94063024 STABILITY CLASS: ALL DT/DZ ELEVATION: SPEED *SPD10P DIRECTION:DIR10P LAPSE DT50M WIND SPEED (MPH)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 13 70 17 2 0 0 102 NNE 11 49 29 0 0 0 89 i NE 15 28 76 4 0 0 123 ENE 28 32 26 1 0 0 87 E 59 24 4 0 0 0 87 ESE 66 29 13 0 0 0 109 .

SE 58 28 19 0 0 0 105 SSE 54 46 15 6 1 0 122 ,

S 53 65 54 11 2 0 185 !

SSW 25 82 67 31 1 0 206 i SW 40 56 57 22 1 0 176 .

WSW 19 44 63 52 9 0 187 W 18 52 115 31 1 0 217 WNW 7 63 59 4 0 0 133 NW 4 68 49 14 0 0 135 NNW 10 60 40 6 0 0 116 TOTAL 480 796 703 184 15 0 2179 ,

PERIODS OF CALM (HOURS): 7 '

VARIABLE DIRECTION O HOURS OF MISSING DATA: 5

5 1

Attachment 7 (Page 9 of 20)

Joint Frequency Distribution Tables - 1994: Quarter 3 HOURS AT EACH WIND SPEED AND DIRECTION '

PERIOD Of RECORD = 94070101-94093024 STABILITY CLASS: A DT/DZ ELEVATION: SPEED:SPD10P DIRECTION:DIR10P LAPSE:DT50M WIND SPEED (MPH)

DIRECTION 1-3 4-7 >24 TOTAL

-____-..- ... --. 8-12 1 3 _ _1 8 19-24 N O O O O O O O NNE O O 2 0 0 0 2 NE O 2 7 0 0 0 9 ENE 1 0 0 0 0 0 1 ,

E O O O O O O O ESE O O O O O O O SE O O O O O O O SSE O 1 0 0 0 0 1 S 0 1 0 0 0 0 1 SSW 0 0 0 0 0 0 0 SW 0 0 0 0 0 0 0 WSW 0 0 0 0 0 0 0 0 0 2 W 0 1 1 0 WNW 0 0 0 0 0 0 0 NW D 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0 PERIODS OF CALM (HOURS): 0 [

VARIABLE DIRECTION O HOURS OF MISSING DATA: 1 ENTER: [ RETURN] CONTINUE. [SO] START OVER. [EX] TO EXIT ,

SITE: PERRY UNIT: UNIT 1 03/15/95 13:25 ;

HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 94070101-94093024 STABILITY CLASS: B DT/DZ ELEVATION: SPEED:SPD10P DIRECTION:DIR10P LAPSE:DT50M WIND SPEED (MPH)

WIND OIRECTION 1-3 8-12 13-18 19-24 >24 TOTAL

--.-__-.. ... 4 _7 N O 2 0 0 0 0 2 NNE O 10 14 0 0 0- 24 NE O 5 17 1 0 0 23 ENE O 2 0 0 0 0 2 E O 1 0 0 0 0 1 ESE O O O O O O O SE O O O O O O O SSE O O O O O O O S O O O O O O O SSW 0 0 0 0 0 0 0 SW 0 1 0 0 0 0 1 i WSW 0 1 2 0 0 0 3 W 0 0 12 0 0 0 12 WNW 0 0 10 0 0 0 10 NW 0 2 3 0 0 0 5 r NNW O O O O O O O TOTAL 0 24 58 1 0 0 83 PERIODS OF CALM (HOURS): 0 4 VARIABLE DIRECTION O !

HOURS OF MISSING DATA: 1 I

Attachment 7 (Page 10 of 20)

Joint Frequency Distribution Tables - 1994: Quarter 3 HOURS AT EACH WIND SPEED ANO DIRECTION PERIOD OF RECORD = 94070101-94093024 STABILITY CLASS: C DT/DZ ELEVATION: SPEED:SPD10P DIRECTION:DIR10P LAPSE:DT50M WIND SPEED (MPH) 1 WIND '

DIRECTION 1 4-7 8-12 13-18 19 24 >24 TOTAL l

___.__- _ __-3 ___ ___ _____ __ __ _ ___ ___ _

NNE O 11 10 0 0 0 21 !

NE O 10 9 0 0 0 19 .

ENE O 2 2 0 0 0 4 i E O 3 0 0 0 0 3 t ESE O O O O O O O ,

SE .0 1 0 0 0 0 1 ,

SSE O O 1 0 0 0 1 !

S 1 0 2 0 0 0 3 '

SSW O 1 4 0 0 0 5 SW 0 0 2 0 0 0 2 WSW 0 0 5 0 0 0 5 W 0 11 25 2 0 0 38 :

WNW 0 20 15 0 0 0 35 i NW 0 6 8 0 0 0 14 :

NNW 0 6 2 0 0 0 8 TOTAL 1 90 90 2 0 0 183 ;

PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION O HOURS OF MISSING DATA: 1 j.

ENTER: [ RETURN) CONTINUE. [SO) START OVER. [EX) TO EXIT t SITE: PERRY UNIT: UNIT 1 03/15/95 13:25 j HOURS AT EACH WIND SPEED AND DIRECTION l PERIOD OF RECORD = 94070101-94093024 j STABILITY CLASS: D DT/DZ r ELEVATION: 3 PEED:SPD10P DIRECTION:DIR10P LAPSE:DT50M !

___..___________________..__________ ____...___...___..._____.._ j WIND SPEED (MPH) t WIND i DIRECTION 1 3 4-7 8 >24 TOTAL

_________ _. _ ___ _ _- 1 2__...

__ ..__. 13 18 19-24 ... .....

l

[

N 7 37 12 0 0 0 56 t NNE 4 23 5 0 0 0- 32 NE i 2 20 4 0 0 0 26 i ENE 8 22 4 0 0 0 34 !

E 12 9 0 0 0 0 21 l ESE 3 15 0 0 0 0 18 i SE 3 9 0 0 0 0 12 '

SSE 4 14 1 0 0 0 19 :

S 6 20 18 1 0 0 45 ;

GSW 3 36 40 3 0 0 82 t SW 4 26 25 2 0 0 57 i WSW 3 27 42 5 0 0 77 l W 6 48 25 1 0 0 FO l WNW 3 41 20 10 0 0 <4 :

NW 6 33 31 5 0 0 75 I NNW 3 35 36 0 0 0 74 l TOTAL 77 415 263 27 0 0 782 i PERIODS OF CALM (HOURS): 1 i

VARIABLE DIRECTION O l HOURS OF MISSING DATA: 1 i i

l l

. - . - . _ . _ _ _ _ _ _ _ , , , _ _ , , , . _ .- - - _ - _ _ _ m __. - ._, m.m., -

t t

4

)

l l

\

Attachment 7 (Page 11 of 20) !

J Joint Frequency Distribution Tables - 1994: Quarter 3 HOURS AT'EACH WIND SPEED AND DIRECTION i PERIOD OF RECORD = 94070101-94093024 STABILITY CLASS: E DT/DZ ELEVATION: SPEED:SPD10P DIRECTION:DIR10P LAPSE:DT50M ;

WIND SPEED (MPH) }

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 > 2'4 TOTAL N 6 13 6 0 0 0 25 NNE 8 13 0 0 0 0 21 i NE 4 4 0 0 0 0 8 i ENE 18 12 1 0 0 0 31 E 24 4 0 0 0 0 28 .

ESE 18 9 0 0 0 0 27 t SE 9 28 0 0 0 0 37 SSE 14 29 3 0 0 0 46 S 15 65 26 0 0 0 106 SSW 9 100 16 0 0 0 125 SW 14 46 8 2 0 0 70 WSW 2 22 7 1 0 0 32 W' 2 7 3 1 0 0 13 WNW 1 8 12 3 0 0 24 NW 3 5 14 0 0 0 22 NNW 5 5 5 0 0 0 15 TOTAL 152 370 101 7 0 0 630 PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION O HOURS OF MISSING DATA: 1 ENTER: [ RETURN] CONTINUE. [SO] START OVER, [EX) TO EXIT SITE: PERRY UNIT: UNIT 1 03/15/95 13:26 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 94070101-94093024 STABILITY CLASS: F DT/DZ ELEVATION: SPEED:SPD10P DIRECTION DIR10P LAPSE:DT50M WIND SPEED (MPH)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 1 0 0 0 0 0 1 NNE 2 1 0 0 0 0 3 NE 5 0 0 0 0 0' 5 ENE 13 0 0 0 0 0 13 E 22 0 0 0 0 0 22 ESE 26 10 0 0 0 3 36 SE 14 13 0 0 0 0 27 SSE 17 18 0 0 0 0 35 S 14 15 0 0 0 0 29 SSW 7 13 0 0 0 0 20 SW 8 1 0 0 0 0 9 WSW 1 1 0 0 0 0 2 W 1 1 0 0 0 0 2 WNW 3 0 0 0 0 0 3 NW 1 0 0 0 0 0 1 NNW 3 0 0 0 0 0 3 TOTAL 138 73 0 0 0 0 211 PERIODS OF CALM (HOURS): 5 VARIABLE DIRECTION O HOURS OF MISSING DATA: 1

Attachment 7 (Page 12 of 20) l t

i Joint Frequency Distribution Tables - 1994: Quarter 3 HOURS AT EACH WIND SPEED AND DIRECTION :

PERIOD OF RECORD = 94070101-94093024 !

STABILITY CLASS: G DT/DZ ELEVATION: SPEED:SPD10P DIRECTION:DIR10P LAPSE DT50M :

WIND SPEED (MPH) i DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N O O O O O O O NNE 1 0 0 0 0 0 2 i NE 2 0 0 0 0 0 2. ;

ENE 9 1 0 0 0 0 10 E 32 0 0 0 0 0 32 ESE -

73 3 0 0 0 0 76 .

SE 65 5 0 0 0 0 70 l SSE 53 10 0 0 0 0 63 '

S 25 11 0 0 0 0 36- l SSW 5 0 0 0 0 0 5 .

SW 4 0 0 0 0 0 4 i WSW 0 0 0 0 0 0 0 i

~

W 0 1 0 0 0 0 1 WNW 1 0 0 0 0 0 1 i NW D 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0 i PERIODS OF CALM (HOURS): 6 ,

VARIABLE DIRECTION O i HOURS OF MISSING DATA: 1 i ENTER: [ RETURN] CONTINUE. [SO) START OVER. [EX] TO EXIT l SITE: PERRY UNIT: UNIT 1 03/15/95 13:26 HOURS AT EACH WIND SPEED AND DIRECTION }

PERIOD OF RECORD = 94070101-94093024 i STABILITY CLASS: ALL DT/DZ !

ELEVATION: SPEED:SPD10P DIRECTION:DIR10P LAPSE:DT50M i

_ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ . . . ~_______.._________.______________..... I

lD SPEED (MPH)

WIND ,

DIRECTION 1 3 4-7 8-12 13-18 19-24 >24 TOTAL !

N 14 71 23 0 0 0 108 !

NNE 15 58 31 0 0 0 105 NE 13 41 37 1 0 0 -~ 92 ENE 49 39 7 0 0 0 95 .

E 90 17 0 0 0 0 107 !

ESE 120 37 0 0 0 0 157 SE 91 56 0 0 0 0 147 i SSE 88 72 5 0 0 0 165 .

S 61 112 46 1 0 0 220 l SSW 24 150 60 3 0 0 237 l SW 30 74 35 4 0 0 143 )

WSW 6 51 56 6 0 0 119 -

W 9 69 66 4 0 0 148 ,

WNW 8 69 57 13 0 0 147 NW 10 46 56 5 0 0 117 NNW 11 46 43 0 0 0 100 .;

TOTAL 639 1008 522 37 0 0 2207 2

)

PERIODS OF CALM (HOURS): it2 VARIABLE DIRECTION O HOURS OF MISSING DATA _ 1 w-i*e -e-,-.-T---- --,.w % y,-- ,am-- c . - - ,.-7.-t-y --- w.---.g.,- * - . - - -T*-

Attachment 7 (Page 13 of 20)

Joint Frequency Distribution Tables - 1994: Quarter 4 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 94100101-94123124 STABILITY CLASS: A DT/DZ ELEVATION: SPEED:SPD10P DIRECTION:DIR10P LAPSE:DT50M WIND SPEED (MPH)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL NNE O O 3 0 0 0 3 NE O O 4 0 0 0 4 ENE 1 0 0 0 0 0 1 E O 2 1 0 0 0 3 ESF. 0 0 1 0 0 0 1 SE O O O O O O O SSE O O O O O O O S O 1 0 0 0 0 1 SSW 0 0 0 0 0 0 0 SW 1 0 0 0 0 0 1 WSW 0 1 1 0 0 0 2 W 0 0 2 0 0 0 2 WNW 0 0 0 0 0 0 0 '

NW 0 0 0 0 0 0 0 NNW 0 1 0 0 0 0 1 TOTAL 2 5 12 0 0 0 19 PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION O HOURS OF MISSING DATA: 0 ENTER: [ RETURN] CONTINUE. [SO] START OVER. [EX] TO EXIT e

SITE: PERRY UNIT: UNIT 1 03/15/95 13:28 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 94100101-94123124 STABILITY CLASS: B DT/DZ ELEVATION: SPEED:SPD10P DIRECTION:DIR10P LAPSE:DT50M WIND SPEED (MPH)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 1 0 0 0 0 0 1 NNE O 2 8 0 0 0 10

'NE O 2 9 0 0 0~ 11 ENE O 2 1 0 0 0 3 E O 3 1 0 0 0 4 ESE O 2 0 0 0 0 2 SE O O 1 3 0 0 4 SSE O O O O O O O S 0 0 2 0 0 0 2 SSW 0 0 4 3 0 0 7 SW 0 0 0 0 0 0 0 WSW O O 2 2 0 0 4 W O 1 13 4 0 0 18 WNW 0 0 7 0 0 0 7 NW 0 0 0 0 0 0 0 NNV 0 0 0 0 0 0 0 TOTAL 1 12 48 12 0 0 73 ,

PERIODS OF CALM (HOURS): 0 i VARIABLE DIRECTION O i HOURS OF MISSING DATA: 0 l l

l

Attachment 7 (Page 14 of 20)

Joint Frequency Distribution Tables - 1994: Quarter 4 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 94100101-94123124 STABILITY CLASS: C DT/DZ ELEVATION: SPEED:SPD10P DIRECTION:DIR10P LAPSE:DT50M WIND SPEED (MPH)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 424 TOTAL N O 1 3 1 0 0 5 NNE O 8 7 0 0 0 15 NE O 4 11 0 0 0 15 ENE O 2 1 0 0 0 3 E O 5 1 0 0 0 6 ESE O 6 2 0 0 0 8 SE O 2 2 1 0 0 5 SSE O O O O O O O S O 4 12 0 0 0 16 SSW 0 4 10 4 0 0 18 SW 0 2 5 3 0 0 10 WSW 0 0 2 2 0 0 4 W 0 1 5 3 0 0 9 WNW 0 3 6 0 0 0 9 NW 0 6 1 0 0 0 7 NNW 0 1 0 0 0 0 1 TOTAL 0 49 68 14 0 0 131 PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION O HO!)RS OF MISSING DATA: 0 ENTER: [ RETURN] CONTINUE, [SO] START OVER. [EX] TO EXIT SITE: PERRY UNIT: UNIT 1 03/15/95 13:28 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 94100101-94123124 STABILITY CLASS: D DT/DZ ELEVATION: SPEED:SPD10P DIRECTION:DIR10P LAPSE:DT50M WIND SPEED (MPH)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 3 23 38 2 J 0 66 NNE 1 19 11 0 0 0- 31 NE 2 13 16 6 0 0 37 ENE 1 24 16 0 0 0 41 E '4 30 3 0 0 0 37 ESE O 27 10 5 0 0 42 SE 3 11 19 14 4 0 51 SSE 6 17 6 9 3 0 41 S 1 34 30 6 0 0 71 SSW 0 37 36 5 0 0 78 SW 2 26 38 12 2 0 80 WSW 0 21 42 48 12 0 123 W 5 14 95 22 2 0 78 '

WNW 1 22 28 19 0 0 60 NW 6 27 55 33 3 0 124 NNW 4 28 31 5 1 0 69 TOTAL 39 373 404 186 27 0 1029 I PERIODS OF CALM (HOURS): 0 l VARIABLE DIRECTION O HOURS OF MISSING DATA: 0 1

1 l

_ ,_ _ . _ _ . _ _ m ._ .- . . _ _ . _

Attachment 7 (Page 15 of 20)

Joint Frequency Distribution Tables - 1994:' Quarter 4 ]

HOURS AT EACH WIND SPEED AND DIRECTION l PERIOD OF RECORD = 94100101-94123124 ,

STABILITY CLASS: . E DT/DZ LAPSE:DT50M

, ELEVATION: SPEED:SPD10P DIRECTION DIR10P WIND SPEED (MPH)

WIND DIRECTION 1 3 47 8-12 13-18 19 >24 TOTAL l N 2 2 10 2 0 0 16' NNE 1 10 1 1 0 0 13 NE -4 -12 2 0 0 0 18 ENE 8 21 4 0 0 0 33 E 20 34 0 0 0 0 54 ESE 14 36 8 2 0 0 60 SE 10 21 13 5 8 0 57 SSE 9 23 15 4 0 0 51 ;

S 18 42 34 8 0 0 102 SSW '12 42 38 3 0 0 95 SW 10 28 18 6 0 0 62

WSW 1 6 12 2 0 0 21 W 0 3 15 3 0 0 21 WNW 2 0 6 4 0 0 12 NW 3 1 1 2 0 0 7 ,

NNW 2 1 10 0 0 0 13 TOTAL 116 282 187 42 8 0 635 PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION O ;

HOURS OF MISSING DATA: 0 ,

ENTER: [ RETURN] CONTINUE, [$O] START OVER, [EX) TO EXIT i i

SITE: PERRY UNIT: UNIT 1 03/15/95 13:29 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 94100101-94123124 ;

STABILITY CLASS: F DT/DZ -

ELEVATION: SPEED:SPD10P DIRECTION:DIR10P LAPSE DT50M WIND SPEED (MPH) ,

WIND i DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL ;

N O O O O O O O 2 0 0 0 0 3 i NNE 1

'NE 4 1 0 0 0 0- 5 ENE 10 2 0 0 0 0 12 E 23 3 0 0 0 0 26 :

ESE 36 15 1 0 0 0 52.

SE 8 8 0 0 0 0 16 SSE 10 6 0 0 0 0 16 ,

S 10 11 0 0 0 0 21 i SSW 7 8 2 0 0 0 17 SW 4- 0 0 0 0 0 4 :

WSW 2 0 0 0 0 0 2 l W 0 0 0 0 0 0 0 WNW 1 0 0 0 0 0 1 ,

NW 1 0 0 0 0 0 1 NNW 0 0 0 0 0 0 0 "

TOTAL 118 55 3 0 0 0 176 ;

PERIODS OF CALM (HOURS): 0 !

VARIABLE DIRECTION O HOURS OF MISSING DATA: 0 !

+

i I

f

y -l Attachment 7 (Page 16 of 20) i Joint Frequency Distribution Tables - 1994: Quarter 4 J HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 94100101-94123124 '

STABILITY CLASS: G DT/DZ ELEVATION: SPEED:SPD10P DIRECTION:DIR10P LAPSE:DT50M WIND 'EED(MPH)

WIND DIRECTION 1-3 4-7 s-12 13-18 19-24 >24 TOTAL N 1 1 0 0 0 0 2 ;

NNE O O O O O O O NE 1 0 0 0 0 0 1 l ENE 8 0 0 0 0 0 8 E 11 0 0 0 0 0 11 ESE 41 2 0 0 0 0 43

SE 27 9 0 0 0 0 36 ,

SSE 15 8 0 0 0 0 23 !

S 4 3 0 0 0 0 7 SSW 7 1 2 0 0 0 10 SW 2 0 0 0 0 0 2 WSW 0 0 0 0 0 0 0 l W i 0 0 0 0 0 1 WNW 1 O O O O O 1 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0 l PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION O HOURS OF MISSING DATA: 0 t ENTER: [ RETURN) CONTINUE, [SOJ START OVER. [EX) TO EXIT t

SITE: PERRY UNIT: UNIT 1 03/15/95 13:30 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 94100101-94123124 STABILITY CLASS: ALL DT/DZ ELEVATION: SPEED:SPD10P DIRECTION:DIR10P LAPSE:DT50M WIND SPEED (MPH) ,

DIRECTION 1-3 4-7 13 19-24 >24 TOTAL

_________ ___ ___ 8_12 __-18 N 7 27 51 5 0 0 90 ;

-NNE 4 40 30 1 0 0 -

75 r NE 11 32 42 6 0 0 91 ;

ENE 28 51 22 0 0 0 101 E 58 77 6 0 0 0 141 ESE 91 88 22 7 0 0 208 SE 48 51 35 23 12 0 169 SSE 40 54 21 13 3 0 131 S 33 95 78 14 0 0 220 SSW 26 92 92 15 0 0 225 SW 19 56 61 21 2 0 159 i WSW 3 28 59 54 12 0 156 l W 6 19 70 32 2 0 129 !

WNW 5 25 37 23 0 0 90 NW 10 34 57 35 3 0 139 ;

NNW 6 31 41 5 1 0 84 '

______________________________________________________________ l TOTAL 395 800 724 254 35 0 2208 l

___________________________________________.__________________ j PERIODS OF CALM (HOURS):

0 VARIABLE DIRECTION O HOURS OF MISSING DATA: 0 {

1

L Attachment 7 (Page 17 of.20) !

Joint Frequency Distribution Tables - Year 1994 j HOURS AT EACH WIND SPEED AND DIRECTION l PERIOD OF RECORD = 94010101-94123124. -

STABILITY CLASS: A DT/DZ t ELEVATION: SPEED:SPD10P DIRECTION:DIR10P LAPSE:DT50M '

WIND SPEED (MPH) i WIND ;

DIRECTION 1-3 4-7 8 13 18 19-24 >24. TOTAL

_______.. ... __. . _- 1 2 _____ _____

N 0- 0 1 0 0 0 1 -

NNE 'O O 10 0 0 0 10 NE O 4 22 0 0 0 26 ENE 2 0 0 0 0 0 2 E 1 2 ' 1 0 0 0 4 ESE O O 1 0 0 0 1 ;

SE O 1 1 0 0 0 2 SSE O 1. 0 0 0 0 1 S O 2 0 0 0 0 2 ,

SSW 0 0 0 2 0 0 2 SW 3 0 0 0 0 0 3 W5W 0 2 1 1 0 0 4 W 0 2 17 7 0 0 26 WNW 0 0 4 0 0 0 4 :

NW 0 0 0 0 0 0 0 t NNW 0 1 0 0 0 0 1 TOTAL 6 15 58 10 0 0 89 PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION O HOURS OF MISSING DATA: 6 ENTER: [ RETURN] CONTINUE, [SO] START OVER. [EX) TO EXIT ,

SITE: PERRY UNIT: UNIT 1 03/15/95 13:32 !

HOURS AT EACH WIND SPEED AND DIRECflON PERIOD OF RECORD = 94010101-94123124 l STABILITY CLASS: B DT/DZ !

ELEVATION: SPEED:SPD10P DIRECTION:DIR10P LAPSE:DT50M j WIND SPEED (MPH) !

WIND i DIRECTION 1-3 4-7 >24 TOTAL

_.____.__ ... ___ 8 _12 13-18 19-24 1

j N 1 4 5 0 0 0 10 NNE O 16 29 0 0 0 45 l NE O 10 44 2 0 0 56 ~

ENE O 4 3 0 0' O 7 7 E O 5 2 0 0 0 7 !

ESE O 2 0 0 0 0 2 SE O O 4 3 0 0 7 SSE O O O O O O O S O 1 2 0 0 0 3 1 SSW 0 1 4 7 0 0 12 '

SW O 1 0 2 0 0 3 '

WSW 0 2 6 13 1 0 22 :

W' O 4 58 15 0 0 77 l WNW 0 0 33 0 0 0 33 NW 0 3 5 0 0 0 8 NNW 0 4 0 0 0 0 4 TOTAL 1 57 195 42 1 0 296 PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION O HOURS OF MISSING DATA: 6

Attachment 7 (Page 18 of 20) 1 Joint Frequency Distribution Tables - Year 1994 ,

HOURS AT EACH WIND SPEED AND DIRECTION t PERIOD OF RECORD = 94010101-94123124 :

STABILITY CLASS: C DT/DZ . i ELEVATION: SPEED:SPD10P DIRECTION: DIR10P LAPSE:DT50M ;

WIND SPEED (MPH)

WIND .

DIRECTION 1-3 4-7 8-12 13-18 19 >24 TOTAL

____.____ __ . . ... ____ __-24 NNE O 32 30 0 0 0 62 NE 1 15 42 2 0 0 60 ENE 1 5 8 4 0 0 18 ,

E O 11 1 0 0 0 12 i ESE O 6 8 1 0 0 15 SE O 5 8 1 0 0 14 SSE O O 1 2 0 0 3 S 1 4 16 1 1 0 23 ,

SSW 0 7 18 7 1 0 33 i SW 0 4 10 6 1 0 21 ;

WSW 0 1 13 18 3 0 35 i W O 18 61 18 1 0 98 ,

WNW 0 29 49 6 0 0 84 ,

NW 1 16 21 0 0 0 38 l NNW 0 16 10 2 0 0 28 TOTAL 4 203 306 70 7 0 590 5 PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION O !

HOURS OF MISSING DATA: 6 ENTER: [ RETURN] CONTINUE. [SO] START OVER. [EX) TO EXIT ,

t SITE: PERRY UNIT: UNIT 1 03/15/95 13:32 !

t HOURS AT EACH WIND SPEED AND DIRECTION !

PERIOD OF RECORD = 94010101-94123124 STABILITY CLASS: D DT/DZ i ELEVATION: SPEED SPD10P DIRECTION DIR10P LAPSE:DT50M ;

WIND SPEED (MPH) l WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL '

N 19 137 78 7 0 0 241 5

. NNE 17 100 51 4 0 O _. 172 ;

NE 15 77 108 24 7 0 231 '

ENE 16 87 99 27 2 0 231 i E 28 77 13 0 0 0 118 l ESE 6 65 33 5 0 0 109 i SE 14 42 43 36 4 0 139 .

SSE 15 54 26 23 5 0 123 S 14 75 93 27 1 0 210 ;

SSW 9 111 165 49 0 0 334 SW 13 95 162 55 3 0 328 :

WSW 12 112 223 171 35 0 553 < <

W 19 140 195 69 4 0 427 . I WNW 12 172 99 54 0 0 337 NW 17 150 151 64 5 0 387 NNW 18 146 128 15 1 0 308 TOTAL 244 1640 1667 S30 67 0 4248 PERIODS OF CALM (HOURS): 1 VARIABLE DIRECTION O HOURS OF MISSING DATA: 6 1

3

i i

Attachment 7 (Page 19 of 20) l r

Joint Frequency Distribution Tables - Year 1994 i i

HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = '94010101-94123124' i STABILITY CLASS: E DT/DZ ,

ELEVATION: SPEED:SPD10P DIRECTION:DIR10P LAPSE:DT50M WIND SPEED (MPH) l WIND -

DIRECTION 1-3 4-7 8-12 13 19-24 >24 TOTAL !

_________ ___ ___ .__. __-18 ___ _____ ___ . _ _ , .

N 16 26 17 2 0 0 at i NNE 14 36 2 1 0 0 o3 NE 13 26 3 0 0 0 42 ENE 34 69 9 0 0 0 112 '

E 64 50 2 0 0 0 116 t

.ESE 41 57 9 2 0 0 109 SE 26 69 21 6 8 0 130 SSE 36 83 38 6 0 0 163 S 44 168 123 30 0 0 365 SSW 38 232 111 13 0 0 394 SW 49 131 61 16 0 0 257 WSW 17 56 59 12 0 0 144 W 11 24 32 6 0 0 73 .*

WNW 7 19 21 ? O O 54 '

NW 7 11 18 3 0 0 39 NNW 12 9 16 0 0 0 37 '

TOTAL 429 1066 542 104 8 0 2149 PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION O HOURS OF MISSING DATA: 6 ENTER: [ RETURN] CONTINUE, [SO) START OVER. [EX] TO EXIT SITE: PERRY UNIT: UNIT 1 03/15/95 13:33 HOURS AT EACH WIND SPEED AND DIRECTION. !

PERIOD OF RECORD = 94010101-94123124 :

STABILITY CLASS: F DT/DZ ELEVATION: SPEED:SPD10P DIRECTION:DIR10P LAPSE:OT50M j WIND SPEED (MPH) l WIND i DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL .l N 4 0 'O O O O 4 .i NNE 6 2 0 0 0 O_ 8 1 NE 13 1 0 0 0 0 14 l ENE 34 9 0 0 0 0 43 l E 63 6 0 0 0 0 69 I ESE 75 37 1 0 0 0 113 SE 33 27 0 0 0 0 60 i SSE 37 39 0 0 0 0 76 S 44 43 2 0 0 0 89 ;

SSW 27 33 2 0 0 0 62 l SW 24 5 0 0 0 0 29 !

WSW 6 3 0 0 0 0 9 1 W 4 2 0 0 0 0 6 WNW 6 3 0 0 0 0 9.

NW 4 3 0 0 0 0 7.

NNW 3 0 0 0 0 0 3 TOTAL 383 213 5 0 0 0 601 PERIODS OF CALM (HOURS): 7 VARIABLE DIRECTION O HOURS OF MISSING DATA: 6 I

I

-I

i l

l Attachment 7 (Page 20 of 20)

Joint Frequency Distribution Tables - Year 1994 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 94010101-94123124 ,

STABILITY CLASS: G DT/DZ .

+

ELEVATION: SPEED:SPD10P DIRECTION:DIR10P LAPSE:DT50M -

WIND SPEED (MPH)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 4 1 1 0 0 0 6 ,

NNE 3 0 0 0 0 0 4

NE 7 1 0 0 0 0 8 ENE 34 1 0 0 0 0 35 -

E 83 1 0 0 0 0 84 ESE 168 9 0 0 0 0 178 SE 154 22 0 0 0 0 176 SSE 118 22 0 0 0 0 140 S 63 18 0 0 0 0 81 SSW 30 5 2 0 0 0 37 SW 19 0 0 0 0 0 19 WSW 3. 0 0 0 0 0 3 ,

W 5 1 0 0 0 0 6 WNW 3 0 0 0 0 0 3 NW 0 0 0 0 0 0 0 NNW 1 0 0 0 0 0 1 ,

PERIODS OF CALM (HOURS): lil VARIABLE DIRECTION O HOURS OF MISSING DATA: 6 ENTER: [ RETURN] CONTINUE, [SO) START OVER. [EX] TO EXIT f

SITE: PERRY UNIT: UNIT 1 03/15/95 13:33 ,

HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 94010101-94123124 STABILITY CLASS: ALL DT/DZ ELEVATION: SPEED:SPD10P DIRECTION:DIR10P LAPSE:DT50M WIND-SPEED (MPH)

WIND ,

DIRECTION 1-3 4-7 8-12 13 18 19-24 >24 TOTAL !

I N 44 202 112 11 0 0 369 NNE 40 186 122 5 0 0. 354 ;

NE 49 134 219 28 7 0 437 ;

ENE 121 175 119 31 2 0 448 E 239 152 19 0 0 0 410 ,

ESE 290 176 52 8 0 0 527 SE 227 166 77. 46' 12 0 528 l SSE 206 199 65 31 5 0 506 >

S 166 311 236 58 2 0 773 :

SSW 104 389 302 78 1 0 874 li SW 108 236 233 79 4 0 660 WSW 38 176 302 215 39 0 770 a W 39 191 363 115 5 0 713 i WNW 28 223 '206 67 0 0 524 NW 29 183 195 67 5 0 479 NNW 34 176 154 17 1 0 382 TOTAL 1762 3275 2776 856 83 0 8754 (

PERIODS OF CALM (HOURS): 20 VARIA8LE DIRECTION O HOURS OF MISSING DATA: 6 !

6 n - . . . . ..g,. .m r. -, .---e

l I

I Attachment 8 Annual Land Use Census m

6 LAND USE CENSUS LAND USE CENSUS 35 I

l l

INTRODUCTION Each year a land use census is conducted to identify the locations of the nearest milk animal, garden (of greater than 500 ft2), and residence in each of the meteorological sectors. The Land Use Census is required by the PNPP Technical Specifications, Section 3/4.12.2. The information gathered during the land Use Census is used for off-site dose assessment and to update sampling locations for the Radiological Environmental Monitoring Program.

The Land Use Census is conducted by traveling all roads within a five-mile radius of the plant site, and recording and mapping the location of the nearest resident, milk animal, and vegetable garden in each of the meteorological sectors around the plant that are over land. The 1994 Census was conducted on July 14,15 and 18. The location of the nearest residences, vegetable gardens (larger than 500 square feet), and milk producing animals were recorded. Produce growers, and recreational areas were also recorded.

A survey update was also completed this year. It included Identification of all public drinking water facilities, fish harvst and population within 50 miles of the plant.

The information has been tabulated below; garden, residence and milk animal locations are plotted on the map in Figure 1. Note that the W, WNW, NNW, NW, N, and NNE sectors extend over Lake Erie and therefore were not included in the survey.

DISCUSSION AND RESULTS in general, the predominant land use within the survey area continues to be rural / ,

agricultural.

There were no changes in nearest residences within five miles of the plant. Table 1 lists the nearest residence by sector. The residence with the highest X/O (highest dispersion factor and therefore highest possible calculated dose) is located at 3121 Center Road, in the south sector, approximately 0.9 miles from the plant. This is the same residence identified in the 1993 Land Use Survey.

Table 1: Nearest residence by sector Sector Location Miles XM Value Map Address from PNPP (Sec/m3) Locator NE 4385 Lockwood Rd 0.8 2.17E-6 1 ENE 4602 Lockwood Rd 1.0 1.13E-6 2 E 2684 Antloch Rd 1.1 6.77E-7 3 ESE 2774 Antioch Rd 1.2 4.44E-7 4 SE 4495 N. Ridge Rd 1.2 3.89E-7 5 SSE 3119 Parmly Rd 0.9 1.89E-6 6 S 3121 Center Rd 0.9 2.25E-6 7 SSW 3850 Clark Rd 0.9 1.11 E-6 8 SW 3440 Clark Rd 1.2 4.98E-7 9 WSW 2815 Perry Park 1.0 1.72E-6 10 LAND USE CENSUS 36

The following changes in nearest gardern were recorded in the 1994 census:

o ENE Sector - A new garden was identified at 4650 Lockwood Road.

o E Sector - A new garden was identified at 2740 Antioch Road, o SE Sector - A new garden was identified at 4679 Middle Ridge Road.

o SSW Sector - A new garden was identified at 3515 North Ridge Road.

o WSW Sector - A new garden was identified at 2975 Perry Park Road.

Table 2 lists the nearest gardens that occupy at least 500 square feet. The location with the highest DIO (h!ghest calculated deposition) value was 3121 Center Road in the south sector. This is the same garden identified in the 1993 Land Use Survey.

Table 2: Nearest garden by sector Location Miles DD Value Map Sector Address from PNPP per m2 Locator NE 4398 Lockwood Rd 0.8 1.09E-8 11 ENE* 4650 Lockwood Rd 1.2 4.11 E-9 12 E* 2740 Antioch Rd 1.2 4.56E-9 13 ESE 2774 Antioch Rd 1.2 3.41 E-9 4 SE* 4679 Middle Ridge Rd 1.9 1.31 E-9 14 SSE 3119 Parmly Rd 0.9 1.23E-8 6 S 3121 Center Rd 0.9 1.31 E-8 7 SSW* 3515 N. Ridge Rd 1.7 1.19E-9 15 SW 3440 Clark Rd 1.2 2.24E-9 9 WSW* 2975 Perry Park Rd 1.2 2.31 E-9 16

Indicates a new location for 1994 A milk animal (goat) was recorded during the 1994 census. There had been no milk animals within a five mile radius of the plant since 1991. At the time of the survey the goat was not being milked and would not be milked in 1994. For this reason, the location was not added to the REMP.

Table 3: Milk Animal Location Miles DD Value Map Sector Address imm PNPP perm 2 Locator E 2874 Burns 4.1 4.81 E-10 17 Produce growers are listed in Table 4; recreational areas are listed in Table 5. Survey update information on pubile drinking water facilities is included in Table 6. Fish harvest and population are discussed below. ,

i Table 4: Produce growers within the vicinity of PNPP Sector Name and Address of Facility Miles DD from PNPP LAND USE CENSUS 37 l

ENE Shreve Farm,2431 Antioch Rd . 1.2 4.1 E-09 ENE- Gerlica Farm,4860 Lockwood Rd 1.5 2.8E-09 ENE Rainbow Farms, Townline Rd 1.9 1.9E-09 ENE Rutand Farm,2210 Haines 2.0 1.7E-09 ENE Twins Creek Farm,2299 Haines Rd 3.2 7.4E-10 E Orosz Farm,2674 Antioch Rd 1.2 4.6E-09 i

E Sabo Farm,5674 N. Ridge Rd 2.9 8.9E-10 E Resident,6325 Middle Ridge Rd 3.9 5.3E E Woodworth Farm, Middle Ridge Rd 4.6 3.9E-10 E Wayman Farm, Across from 2605 4.8 3.6E-10 l

^

Hubbard Rd -

E Hub Ridge Market, Rt. 528 & 4.8 3 GE-10 Middle Ridge .

i ESE Secor Nursery, N. Ridge Rd 1.8 1.7E-09 .

ESE Resident,5674 Middle Ridge Rd 3.2 5.6E-10 _;

ESE Resident,5936 Middle Ridge Rd 3.3 5.3E-10 ESE Resident,6030 Middle Ridge Rd 3.9 3.9E-10 l ESE Hart's Acres, Rt 528 5.0 2.5E-10 :

SSE Peg's Produce, Rt 84 3.2 3.7E-10 j S Resident,4030 Middle Ridge Rd 1.5 2.4E 09 ;

Brookside Farm, Middle Rid 0e Rd 1.7 2.0E-09 S f SE* Resident,3815 Townline Rd 3.0 5.9E-10 SSW Golding Farm, North Ridge Rd 1.7 1.2E 09 l

SSW Champion Nursery, North Ridge Rd 1.8 1.1 E 09 -

SW Golding Farm, Perry Park Rd 1.5 1.5E-09 j SW West Orchard & Fruit Market 1.6 1.4E-09 [

i Perry Park / Clark ,

SW Resident,3191 N. Ridge Rd 2.4 6.7E-10 SW West Orchard & Fruit Market, !

N. Ridge Rd 2.7 5.5E-10.. j SW Garden Center, Corner Narrows Rd 3.6 3.3E-10

& North Ridge Rd j SW* Sycamore Row Farm,252 Hale Rd 4.2 2.5E-10 f SW' Resident,2503 Hale Rd. 4.2 2.5E-10 i i

Indicates a new location for 1994. t 6

h LAND USE CENSUS . 38 ,

1 l

l Table 5: Recreational areas Sector Name and Address of Facility Miles from PNPP NE North Perry Pk, Lockwood Rd 0.7 ENE N. Townline Pk, Townline Rd 2.3 1

ENE Lake Metro Pk, Lockwood Rd 1.7 ENE Chapel Cove Pk, Chapel Rd 3.2 ENE Tuttle Pk, Tuttle Park Rd 3.7 ENE Madison C.C., Chapel / Green Rd 4.0 S Lake County YMCA Outdoor Center, 4.6 4540 River Rd SW Fairway Pines Golf Course, Corner of Blase Nemeth and Bacon Rd 4.8 WSW Perry Township Pk, Perry Park Rd 1.1 WSW Camp Roosevelt, Perry Park Rd 1.4 Based on 1990 census data, the population within 50 miles of the plant is 2,981,927.

Information on fish harvest was obtained from the Ohio Department of Natural Fiesources and includes both sport and commercial data. The annual spod harvest of major fish species for the last five years is shown in Table 7. Annual commercial harvest of major fish species for the last five years in shown in Table 8. Public drinking water facilities within 50 miles of the plant are shown in Table 9.

Table 7: Annual sport fish harvest (in thousands of pounds of fish)

Species 1989 1990 1991 1992 1993 Walleye LO;$1Z 6,33i 5,170 5,997 7,428 Yellow perch 2 , 47 3 5'il 933 722 876 White bass to 6 64 31 85 Smallmouth bass Sy 66 66 77 y3 Freshwater drum g 63 133 63 54 Channel catfish gg S 30 63 54 White perch l43 11 175 93 36 Tabei 8: Annual commercial fish harvest (in thousands of pounds of fish)

Species 1989 1990 1991 1992 1993 Yellow perch 1,700 1,591 684 372 344 White bass 549 392 445 382 225 Carp 895 1,190 1,063 1,824 1,176 Freshwater drum 485 640 505 604 774 Channel catfish 342 365 376 333 326 White perch 521 796 1,007 848 338 Suckers 39 41 41 55 53 l

LAND USE CENSUS 39 l

Table 9: Public' drinking water facilties

- County Facility name Water source Ashtabula Andover Village Well Orwell Village W ell Roaming Shore Village Roan Rock Lake Rock Creek Village Grano ilver City of Conneaut Lake Erie Camplands Water Company Well Ohio American Water Service Lake Erie ,

Cuyahoga City of Berea Rocky River City of Cleveland Lake Erie Chagrin Falls Village Well Geauga Burton Village Well Chardon Village Bass Lake

- Middlefield Village Well Lake Fairport Harbor Village Lake Erie Lake Co. East Water District Lake Erie Lake Co. West Water District Lake Erie Ohio Water Service Lake Erie City of Painesville Lake Erie Mahoning Milton Township Well Portage Mantua Village Well Windham Village W ell City of Kent Well City of Ravenna Lake Hodgson Fairlane Water Company Well Citizens Utility Well Summit Lakemore Village Well City of Akron ..

Lake Rockwell City of Cuyahoga Falls Well Hudson Village Well Copley Square Water Company Well City of Barberton Wolf Creek Reservoir Peninsula Water & Sewer Well Shepard Hills Water Company Well Trumbull West Farmington Village Grand River City of Courtland Well City of Hubbard Well City of Newton Falls Mahoning Rher City of Warren Mosquito Reservoir Shenango/Masury Water Company Shenango River-Mercer (PA) Shanango Valley Water Company Shenango River l

Sharpsville Boro Water Company Shenango River Reynolds Water Company Big Run River I

l Greenville Municipal Water Shenango River Crawford (PA) Tuttle Point Pymatuning Pymatuning Reservoir Cambridge Springs Borough French Creek Erie (PA) Erie Bureau of Water Lake Erie LAND USE CENSUS 40

LfND.USE CENSUS YIAP""* w.

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Figure I: 1994 Land Use Census Map

Attachment 9 Abnormal Release

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1 QUART ER 3 : START DATE 94082112 END DATE 94082113 k

EFFLUENT AND WASTE DISPOSAL REPORT GASEOUS EFFLUENTS -- SUMMATION OF ALL RELEASES

UNITS : QUARTER :

3 : ,

...____._____________ t A. FISSION AND ACTIVATION GASES

1. TOTAL RELEASE : CI : 5.66E-03 :

2. AVERAGE RELEASE :UCI/SEC: 7.86E-01 :

RATE FOR FERIOD : : : ,

3. PERCENT OF TECHNICAL: % : 0.00E+00 :

SPECIFICATION LIMIT : : :

t CONTINUOUS MODE I

LOCEi6is ? UsiTS-I 50XRiiR-- I' RELEASED : : 3 :

1. FISSION AND ACTIVATION GASES

XE133 : CI : 2.25E-03 :

XE135M : CI : 4.28E-05 :

, : XE135 : CI : 3.37E 03 : --

TOTAL FOR : : :

PERIOD : CI : 5.66E-03 :

(ABOVE) : : :

9 l

}

5

I i

l HOURS AT EACH WIND SPEED AND DIRECTION {

PERIOD OF RECORD = 94082112-94082113 STABILITY CLASS: A DT/02 ELEVATION: SPEED:SPD10P DIRECTION:DIR10P LAPSE:DT50M WIND SPEED (MPH)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N O O O O O O O NNE O O O O O O O NE O O O O O O O ENE O O O O O O O E O O O O O O O ESE O O O O O O O SE O O O O O O O SSE O O O O O O O S 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 0 SW 0 0 0 0 0 0 0 WSW 0 0 0 0 0 0 0 W 0 0 0 0 0 0 0 WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0

--eii65S 6 CE ~ i 60Eii F ~ ~ ~ 5 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

VARIABLE DIRECTION O HOURS OF MISSING DATA: 0 ENTER: [ RETURN] CONTINUE. [SO] START OVER, [EX] TO EXIT SITE: PERRY UNIT: UNIT 1 03/27/95 12:51 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 94082112-94082113 STABILITY CLASS: B OT/DZ ELEVATION: SPEED:SPD10P DIRECTION:DIR10P LAPSE:DTSOM WIND SPEED (MPH)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL NNE O O O O O O O NE O O O O O O ~0 ENE O O O O O O O E O O O O O O O ESE O O O O O O O SE O O O O O O O SSE O O O O O O O S 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 0 SW 0 0 0 0 0 0 0 WSW 0 0 0 0 0 0 0 W 0 0 0 0 0 0 0 WNW 0 0 0 0 0 0 0 NW O O O O O O O NNW 0 0 0 0 0 0 0 TOTAL 0 0 0 0 0 0 0 PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION O HOURS OF MISSING DATA: 0 I

1 1

HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 94082112-94082113 STABILITY CLASS: C DT/DZ ELEVATION: SPEED:SPD10P DIRECTION: DIR10P LAPSE:DTSOM WIND SPEED (MPH)

WINO DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N O O O O O O O NNE O O O O O O O NL 0 0 0 0 0 0 0 ENE O O O O O O O E O O O O O O O ESE O O O O O O O SE O O O O O O O SSE O O O O O O O S 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 0 SW 0 0 0 0 0 0 0 WSW 0 0 0 0 0 0 0 W O O O O O O O WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW O O O O O O O TOTAL 0 0 0 0 0 0 0 PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION O HOURS OF MISSING DATA: 0 ENTER: [ RETURN) CONTINUE, [SO) START OVER. [EX) TO EXIT

' 03/27/95 12:S2 SITE: PERRY UNIT: UNIT 1 ,

HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 94082112-94082113 STABILITY CLASS: D DT/DZ ELEVATION: SPEED:SPD10P DIRECTION:DIR10P LAPSE:DTSOM WIND SPEED (MPH)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N O O O O O O O NNE O O O O O O O

'N E O O O O O O - -0 ENE O O O O O O O E O O O O O O O ESE O O O O O O O SE O O O O O O O SSE O O O O O O O S 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 0 SW O O O O O O O WSW 0 0 0 0 0 0 0 W 0 0 0 0 0 0 0 WNW 0 0 0 0 0 0 0 NW 0 0 1 0 0 0 1 NNW 0 0 1 0 0 0 1 PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION O HOURS OF MISSING DATA: 0

HOUK$ AT EACH WIND SPEED AND DIRECTION PERIOD Of RECORD - 94082112-94082113 STABILITY CLASS: E . DT/DZ ELEVATION: SPEED:SPD10P DIRECTION: DIR10P LAPSE:DTSOM

..-- ... --------------------- WIND SPEED (MPH)

.---- -------~~----

WIND >24 TOTAL DIRECTION 1-3 4-7 8-12 13-18 19-24 --- .---

O O O O O N O O O O O O O O O NNE O O O O NE O O O O O O O O O ENE O O O O O O O E O O O O O O O O ESE O O O O SE O O O O O O O O O SSE O 0 0 0 0 0 0 S 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 0 0 SW 0 0 0 0 0 WSW 0 0 0 0 0 0 0 0 W 0 0 0 0 0 0 0 VNW 0 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW

~ ~ iii655 ~6 FCH Ais5GRii! ~~~~5"~~~~~~~~~~~~~~~~~~~

VARIABLE DIRECTION O 0

HOURS OF MISSING DATA:

ENTER: [ RETURN] CONTINUE. [SO] START OVER. [EX] TO EXIT UNIT: UNIT 1 03/27/95 12:52

' SITE: PERRY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 94082112-94082113 STABILITY CLASS: F DT/DZ LAPSE:DTSOM ELEVATION: SPEED:SPD10P DIRECTION:DIR10P

---- ---------- WIND SPEED ---(MP H)

WIND >24 TOTAL DIRECTION 1-3 4-7 8-12 13-18 19-24 --- -----

O O O O O O NNE O O O O O O O O NE O O

~

0 O O O O ENE O O O E O O O O O O O O O O O ESE O O O SE O O O O O O O O O O O SSE 0 0 0 S 0 0 0 0 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 0 SW 0 0 0 WSW 0 0 0 0 0 0 0 0 0 0 0 W 0 0 0 WNW 0 0 0 0 0 0 0 0 0 0 0 NW 0 0 0 0 NNW 0 0 0 TOTAL 0 0 0 0 0 0 0 PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION O HOURS OF MISSING DATA: 0

HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 94082112-94082113 STABILITY CLASS: G DT/DZ ELEVATION: SPEED:SPD10P DIRECTION: DIR10P LAPSE:DT50M WIND SPEED (MPH)

WIND >24 TOTAL DIRECTION 1-3 4-7 8-12 13-18 19-24 .........

O O O O O O NNE O O O O O O O NE O O O O O O O O ENE O O O O O O O E O O O O O O O ESE O O O O SE O O O O O O O O O SSE O O O O O O O S O 0 0 0 0 0 0 0 SSW 0 0 0 0 0 SW 0 0 0 0 0 0 0 0 WSW 0 0 0 0 0 0 0 W 0 0 0 0 0 0 0 0 WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW

.......-- ............................ ...........--.......... 0 0 0 0 0 0 0 TOTAL PhkIbbb bF b LM(HbbRhO [ b VARIABLE DIRECTION HOURS OF MISSING DATA: 0 ENTER: [ RETURN] CONTINUE. [SO) START OVER. [EX) TO EXIT

, SITE: PERRV UNIT: UNIT 1 03/27/95 12:52 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 94082112-94082113 STABILITY CLASS: ALL DT/DZ LAPSE:DT50M ELEVATION: SPEED:SPD10P DIRECTION:DIR10P WIND SPEED (MPH)

WIND >24 TOTAL DIRECTION 1-3 4-7 8-12 13-18 19-24 ... .....

O O O O O O N 0 O O O O O O '

NNE O O O O O O O

.N E O O O O O O O -

0 ,

ENE O O O E O O O O O O O O O O O ESE O O O SE O O O O O O O O O O O SSE O O O S O O O O O O O O O O SSW O 0 0 0 0 SW 0 0 0 0 0 0 0 0 0 0 WSW 0 0 0 l W 0 0 0 0 0 0 0 0 0 0 0 WNW 0 0 1 NW 0 0 1 0 NNW 0 0 1 0 0 0 1 0 0 2 0 0 0 2 TOTAL ___ ........---- -

PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION O HOURS OF MISSING DATA: O

I 1

l l

Attachment 10 Process Control Program L

INENT DEIMITIW TD4EmARY QWE nmar awa to. ;

IWP to. 7310 Pcv. 2/92 PAP-0522 TG -

DCIMLTIW to. REV. DEIMLTIm TII1E Tuun. us, ,J W12E: PCP 5 PPfXESS GUI1OL PPOGPAri (PCP) P CtMHS 'IG(S):

CONTROLLED COPY A LIST E/OI ATTADIED PME No, d) ,f 11,2,3.4,7,10.11 L - - - 2 RFASfN: ,

1. Correct statement concerning Pad-aste Building Heating systen.

2. Ensured devatering of vaste vas provided as an option in all sections of the PCP.

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3. Permitted m ,. 4 ,m.,

the use of processing see w _: . .a u- m u techniques

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. - ,. m specificall,y m es % , nr ~~ s,.,m discuss,ed m xxpt~L in the P

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YwbM 9(C 5 5.]o5. W or e$.! $s$$

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4. Pennitted the use of the Special Transport Container in lieu of an IRC approved cask for processing in the Padwaste truck lay.

5. Allow processed wet solid radwaste to be transferred to the On Site Storage Area for storage.

6. Pganded the description of vaste preconditioning to include the process of treating devatered vaste streams to eliminate or reduce bacterial activity.

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/ dan K. Schwenk j04-01-94 A 7g l YhTV n ein u Em APIRNAL l l l l100 MIG. to.: ' ~ " lIUC MIG. IM"IE:

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finne an apprum! 10R50.59 Applicability Geck is attached prior to subnittal for PGC review or firn1 al3mwtl 11 fin-luc.

PCP I OM12E:

Page : ii l Rev. : 5 l

Process Control Program (PCP) l Table of Contents Page l Title Section 1 !

IlfrRODUCTION )

1.0 '

1 1.1 Definitions 2

2.0 WASTE TYPES 2 2.1 Evaporator Concentrate (Bottoms) 2 2.2 Bead Resins 2 2.3 Filter Demineralizer Medin Sludge 3 2.4 Traveling Belt Filter Caka 3 2.5 Filter Cartridges 3 2.6 Oily Waste 3 2.7 Dry Active Waste (DAW) 3 2.8 Other Mata. rials 3

3.0 PROCESS DESCRIPTION 3 3.1 Filling of Tanks 4 3.2 Sampling / Analysis 4 3.3 Preconditioning 4 3.4 Mixing Ratios 4 3.5 Dewatering 5 3.6 Solidification Processing 11 3.7 Cartridge Filteru 11 3.8 Dry Active Waste 11 pl 3.9 other Waste Forms and Processes 16 4 11a ff 4.0 PRODUCT CONTROL 12 4.1 Test Solidification 12 4.2 Product Quality 12 4.3 Acceptability 13 5.0 WASTE CLASSIFICATION, CHARACTERIZATION AND MANIFEST REQUIREMENTS _ 13 5.1 Waste Classification 13 5.2 Waste Characteristics and Manifest Requirements 14 6.0 ADMINISTRATIVE CONTROLS 14 7.0 QUALITY ASSURANCE 16 8.O RECORDS 16 )

9.0 ATTACHMENTS 16

10.0 REFERENCES

16 10.1 Commitments

. l

'IC/VAX/Page 1 of 9

/

OM12E: FCP ,

l Page : 2 Rev. : 5 :

SOLIDIFICATION: the conversion of radioactive materials from liquid ;

and solid systems to a monolithic, inmobilized solid with a definite volume and shape, bounded by a stable surface of distinct outline on j all sides (free standing), with a free water content of less than [ ,l 0.5% by volume. '

i 2.0 WASTE TYPES 1% i There are numerous types of radioactive waste expected to be I (,

generated at the Perry Plant that will require processing, including solidification or dewatering, prior to their disposal. These '

radwaste types can be categorized based on their chemical and physical properties. The waste types expected at PNPP are ;

evaporator concentrates (bottoms), bead resins, filter demineralizer media sludge, traveling belt filter cake, filter ;

cart.tidges, oily waste, and dry active waste (DAW). ,

The following waste typ=ts (other than DAW) may be solidified / 4gj dewatered individually oc in combination, with the provision that the chemistry of the wasto falls within the acceptable envelope for i solidification / dewatering.

2.1 Evaporator Concentrates (Bottoms) 1 Evaporator concentratas (bottoms) result from the processing of the l chemical waste tanks which contain condensate demineralizer regeneration solutions and/or low concentrations of the following:

trisodium phosphate, minute amounts of other chemicals used for chemistry analyses, or decontamination solutions. They will normally be in the range of 5% to 25% sodium sulfate by weight. <

2.2 Bead Resins Bead resins are collected from the condensate, liquid radwaste, and ,

suppression pool demineralizers and stored in the spent resin tank. ,

Bead resins are also collected from chemical decontamination processes.

2.3 Filter Demineralizer Media Sludge Sludge is the waste product generated by the backwash of the condensate filters, the reactor water cleanup filter /demineralizers, l and the fuel pool filter /demineralizers. Sludge may consist of powdered ion exchange resin at varying degrees of exhaustion,- ;

fibrous filter media, and small concentrations of various solids and corrosion products. .The media are decanted prior to solidification / dewatering in the appropriate settling tank.

t I

l i

TC/VAX/Page 2 of 9

1 l

OM12E: PCP l Page : 3 Rev. : 5 j 2.4 Traveling Belt Filter Cake l This is the product remaining on the liquid radwaste traveling belt filters used to process waste water streams. It consists of one or i more of the following; diatomaceous earth or powdered resin, various.

solids, dirt, and corrosion products in small concentrations.

2.5 Filter Cartridges !

I Filter cartridges from the detergent drain tank system, CRD pump !

suction and discharge filters, and any other disposable-type filter cartridge, or non metallic filter septa, that may be used in permanent or temporary, plant or vendor systems are included in this 8 ,

^

category.

2.6 Oily Waste Oily waste is that oil collected in liquid radwaste systems as a resulting from leakage and maintenance on various lubrication and hydraulic systems. r 2.7 Dry Active Waste (DAW)

Contaminated air filters, paper, rags, clothing, tools, equipment ;

and parts, that cannot be effectively decontaminated are contained in this category. Also included are laboratory wastes. i 2.8 Other Materials Various 6ther materials not specifically identified above, will be [

evaluated for solidification, dewatering, or other process on a 0 l case-by-case basis. .

i ;

3.0 PROCESS DESCRIPTION The following process descriptions apply to both plant and vender .,

supplied systems. Any ditferences between the two have been noted.

3.1 Filling of Tanks Once it is determined that a liquid radwaste system batch tank is to 3-be processed, it will be recirculated to ensure a homogeneous mix-ture. Eductors inside the tanks enhance the mixing capabilities. .

The tank will be isolated using the plant's tagout program to ensure that no additional waste is added.

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1 i q

'IC/VAX/Page 1 of 2

I OM12E: PCP Page : 4 Rev. : 5 3.2 Sampling / Analysis Samples will be obtained and analyzed for each batch of waste in accordance with OM12C: CHI-42, OM12A: CHI-78, and OM1A: PAP-1102, respectively for the plant system, or vendor procedures and PCP for vendor supplied systems. Prior to sampling, tanks will undergo sufficient mixing and/or recirculation to ensure representative sampling. At a minimum, fo solidification, analyses will be .

performed for radionuclide content, pH, oil content, and settled solids (oil and concentrates only). At a minimum, for dewatering, analyses will be performed for radionuclide and_ oil content. Th<sse L analyses are necessary to ensure that the waste falls within the acceptable envelopes for solidification / dewatering. ,

3.3 Preconditioning Waste preconditioning is the chemical or physical adjustment of the waste to bring it within an established acceptability envelope to ensure solidification. The need for and type of preconditioning shall be determined using sample analysis results and will be performed in accordance with OM12A: CHI-78 or vendor procedures and PCP. Upon completion of waste preconditioning, additional samples r shall be obtained, as required, to determine solidification mixing ratios.

Oily wastes may require special preconditioning. Handling of oily wastes will be conducted in accordance with burial ground ,

requirements.

Preconditioning may also be performed on waste streams which are or will be dewatered to eliminate or reduce bacterial activity in the 1T' ;

waste. Preconditioning of waste streams for this purpose will be { .

conducted in accordance with approved site and/or vendor procedures.

3.4 Mixing Ratios Mixing ratios give the respective amounts of waste and solidifica- '

l tion agents required for acceptable solidification. The determina- -

tion of mixing ratios shall be performed for each batch of waste to l be solidified. Solidification mixing ratios are dependent upon percent settled solids and sodium sulfate concentration. The waste type and ratios of cement, waste, sodium sulfate (for Class A waste), and water are determined in OM12A: CHI-78 or vendor procedures and PCP.

t 3.5 Dewatering

~

Dewatering is the removal of water from solid material to a concen- .

tration of less than 0.5% or 1.0% by volume, as applicable to con- ;

tainers used and burial site limits. Dewatering of radioactive spent resins, filter sludges and traveling belt filter cake shall be ,

performed in accordance with approved operating procedures which are based upon documented test data demonstrating the ability to achieve !

drainable water limits as specified in applicable regulations.

TC/VAX/Page 4 of 7

n OM12E: PCP Page : 7 Rev. : 5 After the proper amount of waste has been accumulated in a settling or waste tanks or has been transferred to the waste mixing tank, the tank is decanted to remove excess free water (except when the waste being handled is traveling belt filter cake, in which case a predetermined amount of water or other approved aqueous solution is added to the tank for slurry transfer of the contents). The waste slurry is transferred at a preset rate to the vendor's equipment, in accordance with OM13A: RWI-G51-(SRW), where it is either dewatered or solidified with cement. The waste mixing tanks and settling tanks have recirculation capabilities where a representative sample can be drawn. If needed, a dewatering connection is available which is routed to the liquid radwaste system. An additional connection has been provided back to the waste mixing tank for use in the event of a liner overfill condition.

Hot water flush connections are provided to thoroughly flush the plant and the vendor equipment into the liner used for processing. The waste transfer line and dewatering return lines are located behind a two foot thick shield wall to reduce exposure to the operator during processing.

3.6.2 Description of the Vendor's Waste Processing System The wet solid radioactive waste will be transferred to the vendor's equipment to be dewatered or solidified in accordance with site approved procedures. Table 1 lists the Topical Reports, procedures and any comments for each vendor.

The vendor's equipment is located in the Radwaste Uuilding in the fill aisle, storage area, and truck bay (see Figure 2).

Normal processing of radioactive waste will be performed in the fill aisle with only the vendor's cement transfer equipment being located in the cement silo room. Periodically, when determined prudent, waste will be processed in the truck bay.

When this is performed several restrictions will be imposed to minimize the potential for radioactive spill and ensure the principles of ALARA are maintained. These include; all TC processing to be performed in a High Integrity Container (HIC) 6"

% placed inside an NRC Approved cask, all hosing and associated connections to be placed in hose bags, truck bay access doors tf to have temporary curbing placed in front of them, locking all access areas (from outside) to the truck bay, and establishing 70 Positive Access Control to the truck bay from the inside in (g accordance with < PAP-0123>. The areas where the processing takes place are specifically designed to handle the movement, '

storage, and processing of radioactive waste. Concrete walls and floors in these areas have protective coatings and shield /

' cask walls are provided between the vendors equipment and potential radioactive sources to keep personnel exposures ALARA. The storage area is large enough to contain 15 liners.

This provides adequate storage before it is shipped to a burial site, or transferred to the on Site Storage Area. l% v TC/VAX/Page 3 of 9

i OM12E: PCP Page : 10 Rev. : 5 3.6.3 Radiological Effluent Controls and Monitoring All processing with the vendor's equipment will be performed in ,

a room with a volume sufficient to contain any postulated '

spill. A floor drain, routed to the liquid radwaste system, provides drainage in this area. All liquid radwaste discharges are sampled and monitored prior to their release to the environment. .

Gaseous discharges from liners are processed through the f vendor's off-gas blower system as described in the vendor's Topical Report. Ventilation from the areas housing the i radwaste treatment and processing equipment, including the vendor's off-gas blower system, is routed through HEPA filters and charcoal beds prior to release to the environment via the Unit 1 Vent. Radiological monitoring is provided for Regulatory Guide 1.21 compliance to meet applicable Federal Code requirements.

3.6.4 Health Physics Support i Health Physics personnel will provide radiological control during the solidification and dewatering process. All work will be conducted under a Radiation Work Permit to keep personnel exposures ALARA, t 3.6.5 Plant Utility Support

1. Fire Protection ,

Fire suppression is provided above the processing and '

storage area to protect against fires. A fire hose is available in the truck bay for miscellaneous uses.

2. Two-Way Communication A two-way communication system will be used for communication between the plant operator and the vendor '

equipment operator. This will-facilitate smooth '

coordination between the different segments of the waste processing system.

3. Heating and Ventilation The Radwaste Building Ventilation System will provide airflow patterns, in the processing areas, such that any radioactive gases released would pass into the radwaste ventilation system and be treated by a series of roughing, N'

HEPA and charcoal filters prior to the release to the hl environment. Heating is provided by the building heating 73 system. 4 TC/VAX/Page 4 of 9

OM12E: PCP Page : 11 Rev. : 5

4. Overhead Crane An overhead crane will be used to transfer equipment between the storage and processing area and the truck bay.

The crane has a 15 ton capacity which is fully capable of handling dewatered and solidified liners.

5. Closed Circuit Television -

Closed Circuit Television will be used, where applicable, for remote viewing of the processing and storage areas.

The overhead crane has an independent camera for viewing all lifting and placing operations.

3.7 Cartridge Filters Cartridge filters may be disposed of by encapsulation in a cement matrix in steel drums or liners. The encapsulation of cartridge filters shall be performed using approved procedures that provide reasonable assurance that the final waste form will meet the stability criteria of the Branch Technical Position on Waste Form.

Cartridge filters may also be disposed of by placement in HIC's that are certified by the land disposal facility's State Agency.

3.8 Dry Active Waste Potentially contaminated dry wastes will be collected in containers located through&2t the radiologically controlled areas within the l

plant. This waste will be collected and brought to one of two main .f4

) processing areas: the Waste Abatement and Reclamation Facility 4 (WARF) or the DAW handling area on the 623' lla elevation.of the Radwaste building. Other areas may be established temporarily based on operational needs. Waste segregation will be performed to reduce waste volume and to recover reusable materials (as per <0M1A:

PAP-190l>).

In order to reduce the waste volume, compressible waste will be compacted into shipping containers, when a sufficient amount of 110 material has accumulated, in accordance with <RPI-1314>, Operation 6 of the Combined Shredder Box Compactor. Caution will be taken to avoid items that would cause free water formation as well as other compressibility hazards. Noncompressible waste will be loaded manually into suitable shipping containers.

3.9 Other Waste Forms and Processes Tf-Waste forms and/or processes not previously discussed shall have an y approved PNPP or vendor procedure to govern the process.

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TC/VAX/Page 5 of 9 l

1

r g-OM12E: PCP Page : 11a Rev. : 5 Ig l

'4 . 0 PRODUCT CONTROL Dewatering / Solidification processes.will~be conducted by qualified ,

PNPP or vendor personnel in accordance with approved plant and/or ,

vendor operating instructions and procedures.

PAP-0525, Solid Radwaste Administration will ensure appropriate l documentation and compliance with this program. - i i

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ii s

i TC/VAX/Page 6 of 9 l l

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l INTENT '

"" "^"Y "^'5E "

INSTRUCTION TEMPORARY CHANGE PNPP No. 7310 Rev. 2/92 PAP.0522 INSihuCTeOrd NG REV. 1;CTGUCriOf4 TITCE ADAAly $_jSF ONIY

^

OM125 * /Yl2 S hrccess(c,4rei kcc, rcm (Pc,0) PNh' CONTROLLED %

cANcaS TcNcSt No.O_L$j[h A//4 UST EACH ATTACHED PAGE ,

Bi 7 REASON: ~

I. c la.c ,'Py &&% oP P;(Ier Cased 9e 2 &lete use ce the Cen krior Enere3y Sjoceral 77ansport con %er anci s,sast y Me use of a Hyl hkyrdy Conkkes ,

~

DATE PREPARER -, DATE 1P OEPT REVIE

/. j) 9L Y f'

PORC NO: / PORC MTG DATE: RECOMMENDED FOR APPROVAL

((, _/ { y"~ h 7,f.,f YES [3 NO [O"-k ,

IW DATE APPROVED DATE A APPF ED O

AP

/k L ud

~'

U M 5 lJo->-s DATE APPROVED V l t'* fN DATE

/

11 -

1

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APPROVED DATE M h ovED / DATfE [

j L

l Ensure an approved 10CFR5059 Applicabildy Check is attached prior to submittal for PORC Review or final approval if Non-PORC.

OM12E: PCP Page : 3 Rev. : 5 2.4 Traveling Belt Filter Cake This is the product remaining on the liquid radwaste traveling belt filters used to process waste water streams. It consists of one or more of the following; diatomaceous earth or powdered resin, various.

solids, dirt, and corrosion products in small concentrations.

2.5 Filter Cartridges Filter cartridges from the detergent drain tank system, CRD pump suction and discharge filters, and any other disposable-type filter q_

cartridge, or non metallic filter septa, that may be used in permanent or temporary, plant or vendor systems are included in this '8 category.

2.6 Oily Waste Oily waste is that oil collected in liquid radwaste systems as a resulting from leakage and maintenance on various lubrication and hydraulic systems.

2.7 Dry Active Waste (DAW)

Contaminated air filters, paper, rags, clothing, tools, equipment and parts, that cannot be effectively decontaminated are contained in this category. Also included are laboratory wastes.

2.8 Other Materials Various 6ther materials not specifically identified above, will be evaluated for solidification, dewatering, or other process on a 6 case-by-case basis. t 3.0 PROCESS DESCRIPTION The following process descriptions apply to both plant and vendor ..

supplied systems. Any differences between the two have been noted.

3.1 Filling of Tanks

Once it is determined that a liquid radwaste system batch tank is to 'e be processed, it will be recirculated to ensure a homogeneous mix-ture. Eductors inside the tanks enhance the mixing capabilities. '

The tank will be isolated using the plant's tagout program to ensure that no additional waste is added.

'IC/VAX/Page 1 of 2

OM12E: PCP Page : 7 Rev. : 5 After the proper amount of waste has been accumulated in a settling or waste tanks or has been transferred to the waste mixing tank, the tank is decanted to remove excess free water (except when the waste being handled is traveling belt filter cake, in which case a predetermined amount of water or other approved aqueous solution is added to the tank for slurry transfer of the contents). The waste slurry is transferred at a preset rate to the vendor's equipment, in accordance with OM13A: RWI-G51-(SRW), where it is either dewatered or solidified with cement. The waste mixing tanks and settling tanks have recirculation capabilities where a representative sample can be drawn. If needed, a dewatering connection is available which is routed to the liquid radwaste system. An additional connection has been provided back to the waste mixing tank for use in the event of a liner overfill condition.

Hot water flush connections are provided to thoroughly flush the plant and the vendor equipment into the liner used for processing. The waste transfer line and dewatering return lines are located behind a two foot thick shield wall to reduce exposure to the operator during processing.

3.6.2 Description of the Vendor's Waste Processing System The wet solid radioactive waste will be transferred to the vendor's equipment to be dewatered or solidified in accordance with site approved procedures. Table 1 lists the Topical ,

Reports, procedures and any comments for each vendor.

The vendor's equipment is located in the Radwaste Building in the fill aisle, storage area, and truck bay (see Figure 2).

Normal processing of radioactive waste will be performed in the fill aisle with only the vendor's cement transfer equipment being located in the cement silo room. Periodically, when determined prudent, waste will be processed in the truck bay.

When this is performed several restrictions will be imposed to minimize the potential for radioactive spill and ensure the principles of ALARA are maintained. These include; all TC processing to be performed in a High Integrity Container (HIC) f (6 placed inside an NRC Approved cask, all hosing and associated connections to be placed in hose bags, truck bay access doors 4 to have temporary curbing placed in front of them, locking all access areas (from outside) to the truck bay, and establishing 1L Positive Access Control to the truck' bay from the inside in (p accordance with < PAP-0123>. The areas where the processing takes place are specifically designed to handle the movement, '

storage, and processing of radioactive waste. Concrete walls and floors in these areas have protective coatings and shield /

cask walls are provided between the vendors equipment and potential radioactive sources to keep personnel exposures ALARA. The storage area is large enough to contain 15 liners.

This provides adequate storage before it is I, hipped to a burial site, or transferred to the On Site Storage Area. l% y TC/VAX/Page 3 of 9

l l

l Attachment 11 Offsite Dose Calculation Manual, ODCM j

i i

ODCM Page: i Rev.: 4 I

l l

The Cleveland Electric Illuminating Company l l

PERRY OPERATIONS MANUAL l

1 lMFORMATION .

j Off-Site Dose Calculation Manual OHLY !

i TITLE: OFFSITE DOSE CALCULATION MANUAL j l

l REVISION: 4 t;rrrrr1VE D' ATE: E-ld- 9 '}

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PREPARED: 4mue

/W (([ /f ) , ;-; h 2 4 M '/ . / Date 7 /2-9/ 9 Y

{}l A n T. G rs m oos 7 h[ 7'*'5

^

I REVIEWED:

v

/ { Date -

f PORC REVIEW AND RECOMMENDATION FOR APPROVAL MEETING NUMBER: k-/21 DATE: 7/N/W APPROVED: / . N 1fil[97 U l ,

/ ' Late

n 3'

ODCM-

'*f Page: ii Rev.: 4 Offsite Dose Calculation Manual _.

Table of Contents Section Title- ~..,*

Pge . _

1.0 INTRODUCTION

1 ,

2.0 LIQUID EFFLUENTS 2 2.1 Batch Releases 2 2,.1.1 Monitor Alarm Setpoint Determination 2 2 .~1.1.1 Determination of the Minimum Acceptable Dilution Factor .

3 2.1.1.2 Determination of the Maximum Allowable Radwaste Tank Discharge Flow Rate 3 2.1.1.3 Liquid Radwaste Discharge Flow Monitor Alarm Setpoint 4 2.1.1.4 Liquid Radwaste Discharge Radiation Monitor Alarm / Trip Setpoint 5 2.1.2 Compliance with 10CFR20 - Liquid Effluent Concentration 6 2.1.2.1 Concentration of Radionuclides in Prerelease 6 2.1.2.2 Post Release 7-2.2 Continuous Releases 8 2.3 Compliance with 10CFR50, Appendix I - Liquid Effluent. Dose 11 2.3.1 Dose Calculations 11 2.3.2 Cumulation of Doses 13 2.3.3 Projection of Doses 13 2.3.4 Population Dose 14 3.0 GASEOUS EFFLUENTS 32 3.1 Monitor Alarm Setpoint Determination .

34 3.1.1 Determination of the ' Mix" (Noble Gas Radio-nuclide Composition) of the Gaseous Effluent 35 3.1.2 Determination of the Maximum Acceptable Total Activity Release Rate of Noble Gas Radio- -

~~

nuclides in Gaseous Effluent Based on Total Body Dose Rate Limit) 35 * 'f[-[

3.1.3 Determination of the Maximum Acceptable Total

Activity Release Rate of Noble Gas Radio-nuclides in Gaseous Effluent Based on Skin 7 Dose Rate Limit) 36 3.1.4 Determination of the Maximum Acceptable Total ;

Radioactivity Concentration of all Noble Gas ,

Radionuclides in Gaseous Effluent 37 i 3.1.5 Determination of the Maximum Acceptable Monitor Count Rate Above Background Attributed to '

Noble Gas Radionuclides 37 ,

3.1.5.1 Determination of the Monitor High Alarm Setpoint 38 !

3.1.5.2 Determination of the Monitor Alert Setpoint _ 38 I 1

=-. -

c.

- -- ODCM Page: iii ,

Rev.: 4 Offsite Dose Calculation Manual _

Table of Contents (Cont.)

Section Title - *. Page 3.2 Compliance with 10CFR20 - Gaseous Effluent Dose Rate 41 3.2.1 Noble Gases 41 3.2.2' Radionuclides, Particulates, and Other Radionuclides 41 3 '. 2. 3 Dose Rate Calculations 42 3.3 Compliance with 10CFR50 Appendix I - Gaseous Effluent Dose 69 3.3.1 Noble Gases 69 3.3.2 Radionuclides, Particulates, and Other Radionuclides 70 3.3.3 Dose Calculations 70 3.3.4 Cumulation of Doses 71 3.3.5 Projection of Doses 72 3.4 Population Dose 72 4.0 'mTAL DOSE 74 4.1 Compliance with 40CFR190 - Uranium Fuel Cycle Dose 74 4.2 Direct Radiation Dose from PNPP 76 4.3 Dose to Members of the Public While Onsite 77 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 78 5.1 Monitoring Program 78 l 5.2 Land Use Census Program 79 5.3 Inter Laboratory Comparison Program 80 APPENDIX A Atmospheric Dispersion and Deposition Parameters. 92 APPENDIX B Lower Limit of Detection 108 .$-

T-:

i REFERENCES "

112 y.

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ODCM Page: iv Rev.: 4 List of Tables .

Table Title a Page 2.3-1 Organs Used for Liquid Effluent Dose CalculatibnY 8*

15 -

2.3-2 Age Groups Used for Liquid Effluent Dose Calculations 15 , ,

2.3-3 Liquid Effluent Dose Pathways 25 2 . 3. _4 Biaccumulation Factors (Bgp) (pCi/kg per pCi/ liter) 16 2.3-5 Ingestion Dose Factors for Adult (arem/pCi ingested) .17 2.3-6 Ingestion Dose Factors for Teenager (mrem /pCi ingested) 19 2.3-7 Ingestion Dose Factors for Child (mrem /pci ingested) 21 2.3-8 Ingestion Dose Factors for Infant (mrem /pci ingest'ed) 23 2.3-9 External Dose Factors for Standing on Contaminated Ground 25 2.3-10 Liquid Effluent Dilution Factors (Mp) 27 2.3-11 Transit Times Required for Nuclides to Reach the Point of Exposure (tp) 27 2.3-12 Usage Factors (U,p) 28 2.3-13 Dilution Factors for Each of the Potable Water -

Intakes within 50 Miles of PNPP 29 2.3-14 Dilution Factors for the Fish Ingestion Pathway Individual Grid Locations 30 2.3-15 Dilution Factors for the Shore Exposure Pathway

31 -

3.1-1 Total Body and Skin Dose Factors 40 -

3.2-1 Organs Used for Gaseous Effluent Dose Calculations 47 .,_

3.2-2 Age Groups Used for Gaseous' Effluent Dose Calculations 47

~

3.2-3 Gaseous Effluent Dose Pathways 48 3.2-4 Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gases 48 3.2-5 External Dose Factors for Standing on Contaminated Ground -

49 3.2-6 Inhalation Dose Factors for Adult (mrem /pci inhaled) 51 .

ODCM Page: v Rev.: 4 List of Tables (Cont.) _,.

Table Title Page

3.2-7 Inhalation Dose Factors for Teenager (mrem /pci-inteled) 53 --

)

3.2-8 Inhalation Dose Factors for Child (mrem /pci inhaled) 55- , ,

3.2-9 Inhalation Dose Factors for Infant (mrem /pci inhaled) 57 '

3.2.,10 Ingestion Dose Factors for Adult (arem/pCi inhaled) 59 3.2-11 Ingestion Dose Factors for Teenager (mrem /pci inhaled) 61 3.2-12 Ingestion Dose Factors for Child (mrem /pci inhaled) 63 3.2-13 Ingestion Dose Factors for Infant (mrem /pci inhaled) 65 3.2-14 Annual Usage Factors for the Maximum Exposed Individual 67 3.2-15 Annual Usage Factors for the Average Individual 67 3.3-1 Gamma and Beta Air Dose Factors for Semi-Infinite Plume 73 5.1-1 PNPP Radiological Environmental Monitoring Program 81 5.1-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples 86 5.1-3 Detection Capabilities for Environmental Sample Analysis and Lower Limit of Detection (LLD) 87 A-1 Atmospheric Depletion and Deposition Factors 95 A-2 Site Boundary Atmospheric Dispersion (z/Q) and Deposition Parameters (D/Q) for PNPP Unit 1

97 ..

A-3 Atmospheric Disgersion (x/Q) as a Function of . -

Distance (s/m ) 98 A-4 '

Atmospheric Distance (m-Dep)sition (D/Q) as a Function of 103 e

e

ODCM ;

Page: vi !

Rev.: 4 List of Figures .,. !

Figures Title Page 2.1-1, Liquid Radioactive Waste (LRW) Discharge System.- A .

10 _

l

'3.0-1 Gaseous Effluent System Flow Diagram 33 ,

3.2-1 PNPP Site Boundary and Unrestricted Area 68 ;

5.1-1 Technical Specification Required Radiological l Environmental Monitoring Program Sampling ;

Locations within Two Miles of the Plant Site 89 5.1-2 Technical Specification Required Radiological Environmental Monitoring Program Sampling ,

Locations Between Two and Eight Miles from t the Plant Site 90 5.1-3 Technical Specification Required Radiological Environmental Monitoring Program Sampling Locations Greater Than Eight Miles from the ,

Plant Site 91 ?

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(

ODCM Page: vii Rev.: 4 SCOPE OF REVISION:

Rev. 4 - 1. 'It's from previous revision that were evaluated for incorporation - TCN-1 through TCN-9 and TCN-11 through TCN-13. '_*. _

2. Replaced Table 5.1-1 PNPP Radiological Environmental Monitoring Program with PNPP Radiological Environmental Monitoring Program Table 3.12.1-1 from Tech Spec's. '

3. Delete Table 5.1-4. This information is subject to change and is only pertinent in relation to the sample points

. required by Tech. Spec's. Those points are shown on Figures 5.5-1, 5.1-2, and 5.1-3.

4. Nove note on sampling from the " Inter-Laboratory Comparison Program' to the ' Land Use Census Program."

5. Minor editorial changes where the text referenced Tables 5.1-1 and 5.1-4.

I

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' *'. C' 1- j i

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O

i ODCM Page: 1 ,

Rev.: 4 l

1.0 INTRODUCTION

This Offsite Dose Calculation Manual (ODCM) contains information and !

methodologies to be used by the Perry Nuclear Power Plant (PNPP), .

Unit 1, to ensure compliance with PNPP Radiologicalefiluent _

l Technical Specifications. %e Technical Specifications are written '

to satisfy 10CFR20,10CFR50.36 and Appendix I, and 40CFR190-requirements.

i Sections 2 and 3 of this manual deal with liquid and gaseous }

radiological effluents, respectively. Each of these sections '

' contain alarm setpoint determination, radiation dose and dose rate calculation methodologies, as well as limits and requirements. i 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 and 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.

The ODCM has been prepared, as generally as possible, in order to minimize future revisions. However, any such changes will be i reviewed and approved as per the Administrative Control Section of ;

the PNPP Technical Specifications. ;

Supplemental information needed to support calculations, both in I 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 i deposition parameters and Appendix B presents the methodology for determining the lower limit of detection (LLD). '.

=

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ODCM Page: 2 Rev.: 4 2.0 LIQUID EFFLUENTS . . ,

2.1' Batch Releases A batch release is the discharge liquid radioactive waste of a 1 discrete volume. Batch releases from the liquid radwaste system may occur from any of the following tanks: waste sample tank, floor drain sample tank, chemical waste 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 release tanks except the detergent drain tanks, which have a maximum release

' rate of 50 gallons per minute. All of the above liquid radwaste releases go to the Emergency Service Water discharge which is then released through the discharge tunnel after mixing with Service Water effluent and/or and blowdown from Circulating Water 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 thoroughly mixed to assure representative sampling. For mixing, the contents of the tank are recirculated 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 will be mixed and will 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 will be determined in order to ensure compliance with 10CFR20. The radioactive content of each batch :

release will be determined 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 will be those most recently determined (previous month / quarter).

2.1.1 Monitor Alarm Setpoint Determination .

]-

The following methodology is used to calculate the setpoints for the Radwaste Discharge Radiation Monitor - ESW Discharge and Liquid Radwaste Adjustable High Flow Trip Unit to ensure O

that liquid radwaste effluent releases from the site to unre-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/ml has been established for dissolved and entrained noble gases. The Radwaste Dis-charge Radiation Monitor - ESW Discharge provides alarm and automatic termination of releases prior to exceeding these limits.

4

5 5

. ODCM !

Page: 3 t Rev.: 4 NOTE: Liquid radwaste 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 Dilutio.~.e. n Factor

~

C. .

1 DF = I (2.1-1) '

i MPC; i

Where: ;

DF O

= the minimum acceptable dilution factor determined ,

from analysis of the liquid effluent to be released; C.

1

= the concentration of radionuclide 'i' in the batch to be released, in pCi/ml; l

MPC. I

= the limiting maximum permissible concentration of !

radionuclide 'i', from Appendix B, Table II, Column 2 of 10CFR20, in pCi/ml and (2.0E-4 pCi/ml )

for noble gases). !

DF = 10 DF, (2.1-2)

Where:

i DF = the conservative dilution factor used by PNPP to calculnte the maximum release rate prior to release in order to ensure compliance with 10CFR20;~

DF, = the minimum acceptable dilution factor, as per i equation 2.1-1, i

10 = a factor of ten less than 10CFR20 limits as.. r specified in Appendix B, Table II, Column 2; this -

~

factor represents an order of magnitude of ~.-

conservatism for liquid radwaste releases from PNPP. -

{

NOTE: If the' concentration of a radionuclide is below the :~ >

lower limit of detection the radionuclide shall not !

be included as a source term in the setpoint !

calculation. ,

2.1.1.2 Determination of the Maximum Allowable Radwaste Tank Discharge ;

Flow Rate ,

(0.64)( mdf) f max

= DF (2.1-3) l I

, ODCM t Page: 4 Rev.: 4 Where: ,.

f""* = the maximum allowable radwaste tank discharge flow rate for the batch to be released, in gpm; ,

DF =theconservativedilutionfactor,h equation 2.1-2; '

mdf = the minimum dilution flow - supplied by the Service Water system, Emergency Service Water system, or Circulating Water system blowdown, e.g., the low

"- flow alarm setpoint of the Service Water Flow Transmitter P41-N443 = 30,000 gpm; ,

0.64 = an engineering factor to prevent spurious alarms.

2.1.1.3 Liquid Radwaste Discharge Flow Monitor Alarm Setpoint Monitor alarm setpoints are determined to ensure that the concentration of radionuclides in the liquid radwaste 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 pCi/ml has been established for noble gases dissolved and entrained in liquid effluents.

SPg = (1.25)(fact) (2.1-4)

Where:

SP g = Liquid Radwaste Adjustable High Flow Trip Unit i (G50-K805A/B or G50-K926/7) alarm setpoint, in gpm; fact = the actual allowable radwaste tank discharge flow rate for the batch to be released, not to exceed the maximum allowable radwaste discharge flow rate (f,) as defined in equation 21-3; 1.25 = the engineering safety factor to prevent spurious *'C alarms. ;'

The liquid radwaste tank discharge flow should be maintained at M-or below this f value by proper regulation of the high volumeorlowv8bedischargethrottlevalves(G50-F153or G50-F155).

I' l .

ODCM Page: 5 Rev.: 4 2.1.1.4 Liquid Radwaste Discharge Radiation Monitor Alarm / Trip Setpoint -

Monitor alarm / trip setpoints are determined to ensure that the corcentration of radionuclides in the liquid radwaste effluent .

released from PNPP to unrestricted areas does-nttexceed 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 pCi/ml has been established for noble gases -

dissolved and entrained in liquid effluents.

CRg = I (Cg )(E;) (2.1-5) i Where:

I CR c = the calculated monitor count rate above background, in epm; Cg = the coacentration of radionuclide 'i' in the batch to be released, in pCi/ml; E

t

= the detector efficiency of the monitor for radionuclide 'i' in cpm /(pCi/ml).

l l

I CR, = (R3 ) (Fx )I Cg (2.1-6)

Where:

CR x = the cross-calibrated monitor count rate above background, in epm; F* = the cross-calibration factor used to ratio the Liquid Radwaste Discharge Radiation Monitor actual response to the Cs-137 calibrated response;

~ '

R 8 = the response of the Liquid Radwaste Dis' charge '

Radiation Monitor to a Cs-137 calibrated standard, '- ' '- ~

in cpm /(pCi/ml). 1I SPr = (1.25) (f ,/ fact) (CRn }

I*~}

Where: '

SP

= the Radwaste Discharge Radiation Monitor - ESW Discharge (OD17K0606) alarm / trip setpoint, in epm; BG = the background count rate due to internal contamination and radiation levels in the area of the monitor; -

vp- _

. ODCM =

Page: 6 i

~

Rev.: 4 ,

CR = the monitor net count rate, either CRg or CR , as I n

per equation 2.1-5 or 2.1-6; x _~ .

I 1.25 = the engineering safety factor to prevent spurious ,

alarms; - f_ , _

f""* = between an adjustment factor (to account.for the difference '

an actual radwaste discharge flow rate to -

f be used for the discharge and maximum allowable !

act radwaste discharge flow rate) to allow operational flexibility and to minimize spurious alarms; .

Where: i I

f act = the actual radwaste discharge flow rate; this value must always be less than or equal to i Emax' ;

=- the maximum allowable radwaste discharge-flow f""* rate, per equation 2.1-3.

i i

2.1.2 Compliance with 10CFR20 - Liquid Effluent Concentration ' j In order to show compliance with 10CFR20, the concentrations of. !

radionuclides in liquid effluents will be determined and j compared.with the limiting maximum permissible concentrations i (NPC) as defined in. Appendix B, Table II, Column 2 of 10CFR20 ..

(2.0E-4 pCi/ml for entrained and dissolved noble gases). l Concentrations of radioactivity in effluents prior to dilution l will be determined. Concentration in diluted effluent will be. ;

calculated using these results prior to each batch release, and !

following each batch release. PNPP has no continuous' releases. ;

2.1.2.1 Concentration of Radionuclides in Prerelease The radioactivity content of each batch release will be determined prior to release. PNPP will show compliance with l 10CFR20 in the following manner: -

. C-l

'the concentration of the various radionuclides in batch a 1 e releases prior to dilution is divided by the minimum dilution ' !

flow to obtain the concentration at the unrestricted area. :- ' !

This calculation is shown in the following equation:

l i

(Cg )(f) ~

Conc. 1

= (2.2-1) i adf I G

,.e w

,. - . _ . -. = . . - - - . - - . - - - - - - . - - - -.

-,r i

i l

.: occM Page: 7 ;

Rev.: 4 -

Where: .

Conc *. unrestricted

= the concentration of radionuclide 'i' at the-area, in pCi/ml; t

j

. - . . I

~ -

c.1 = the concentration of radionuclide 'Y in the batch !

to be released, in pCi/ml;

I l

f = the radwaste tank discharge flow rate for the i batch to be released, in gpm; ;

'- adf = the minimum dilution flow, per equation 2.1-3, in I gpm. !

I The projected radionuclide concentrations in the unrestricted

[

area are compared to the maximum permissible concentrations in ,

Appendix B, Table II, Column 2 of 10CFR20 (2.0E-4 pCi'/ml for '

dissolved and entrained noble gases) in order to give a' final ;

10CFR20 compliance check, i.e., the following equation must be met: .

L Conc. (2.2-2) 1 MPC g #

{

i i Where:

Conc. 1

= the-concentration of radionuclide 'i' at the !

unrestricted area, in pCi/ml; MPC g = the limiting maximum permissible concentration of !

radionuclide 81", from Appendix B, Table II, !

Column 2 of 10CFR20 (2.0E-4 pCi/al for dissolved l and entrained noble gases), in pCi/ml. !

~ j; 2.1.2.2 Post Release , -

l'!

S e actual radioactivity content of each batch release will be ' ' -~

l det' ermined following release to show final compliance with 17 :

i 10CFR20. =

l 7e, -

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 i calculation is shown in the following equation:

(C;)(Virt)

Conc. =

1 V (2.2-3) i dil !

i p

I

l ODCM l Page: 8 l Rev.: 4 l

1 Where, y,

conci = the the unrestricted actual concentration area for the of radionuclide release, in pCi/ml; 'i' at C.

1 = the concentration of radionuclide 'i' in the batch 1 released, in pCi/ml; V

dil = the actual volume of dilution water during the release (total plant discharge flow, including Service Water, Emergency Service Water, and cooling tower blowdown), in gallons; V

1It

= the actual volume of the liquid radwaste tank discharged for the batch, in gallons.

The concentrations in the unrestricted area are compared to the maximum permissible concentrations in Appendix B, Table II, Column 2 of 10CFR20 (2.0E-4 pCi/ml for dissolved and entrained noble gases). In order to demonstrate final compliance with 10CFR20, the following equation must be met:

Coney (2.2-4)

M?C g s1 i

Where:

Conc. 1 = the concentration of radionuclide 'i' at the unrestricted area, in pCi/ml; .

MPC.

1

= 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 wastes of a non- " '~

discrete volume, i.e., from a volume or system that has an input <

flow 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 Water system. 1 Potentially contaminated discharges from the ESW are monitored by an installed radiation monitoring system. This system consists of two channels, one for monitoring downstream of equipment in Emergency Service Water System Loop A and the other for Emergency Service Water Loop B. Monitors are set to alarm at three times background level. If radiation is detected, the affected Emergency Service Water line can be manually isolated. The decision of whether to isolate or not is dependent cpon other conditions. The'PNPP staff will take appropriate action to limit release.

ODCM Page: 9 Rev.: 4 The Emergency Service Water discharged will be sampled and analyzed _.

in accordance with 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 t batch releases divided by that isotope's MPC must agtig be less ~

than 1. ,

O

+

h*

e

. 7 e-

l 1

1 l

1 1

~ ODCM '

Page: 10 Rev.: 4 ;

Figure 2.1-1 -

Liquid Radioactive Waste (LRW) Discharoe System l i

. a0 ,.

sa !

0C i

~

44' I. 3 gU th F

_ EE -

r O L

., p _ _ _ ._ _ _ _ m __ . . ._-.___,

l od I

==

I . I o - '

= o . i t

_ L _ .o .g.____.s- D w

.i .;

I i I i 1 I, " I 1 S 1 E g kw l 1 e ce , I a

.o - -

3 '

j _ no w" ' '

! = ,

x i

I o.

st um olda l3 s o

,1 y ." 493 <

"lgz ^ a a +

i o la' s ao log

sig mo ,

7

. , _' ."L _ _. ._ 1"s !

Se ; I hp " gp 'h [

US a E: n I

.I.

a6 I

> a a u n

O O -

O O F- e

( ( ( ( f n

== a

n. a n- n n a T

. m

e. e Ea ,,

w

< < =

= ,n <w .-

- == = <=

w a <= o .*

g .-

u$

_> g*

H E

__> = '<-

o* __> <. -.* >

se g =< S= El w s- . 1 a <s

x. -o . < ' .

,t os a=

'h i

ODCM Page: 11 Rev.: 4 2.3 Compliance with 10CFR50, Appendix I - Liquid Effluent Dose .

Doses resulting from liquid effluents will be calculated at least monthly to show compliance with 10CFR50, Appendix I. A cumulative summation of total body and organ doses for each cal d ar quarter -

and calendar year will 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 pathways: potable water, aquatic foods (namely fresh water fish ingestion), and exposure to shoreline deposits. Irrigated food pathways, as discussed in Regulatory Guide 1.109, will not be of concern at PNPP as little or no water 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 do9e to members of the public for liquid radioactive releases from PNPP will be calculated for the potable water, aquatic food, and shoreline deposit pathways using the following equations:

1. Potable Water:

U R ajp =1100(gfp) p (Qg) (Daipj) 84 I~ AiU) p (2.3-1)

2. Aquatic Foods:

U Rajp =1100(gfp3 (0g)(Bip)(Daipj) exp (-Ag tp,) (2.3-2) p

3. Shoreline Deposits:

f (U,p)(W)

R,$p = 110,000 (M )(F) .E IOi )(Tg )(Daipj I* I*~I 1

P

[exp (-A g tp)] * [1 - exp (-Ag tbII Where:

R ].ap

= the dose to individuals of age group *a' to organ 'j' from all the radionuclides in pathway

'p', in mrem;

ODCM Page: 12 Rev.: 4 B.

1p

= the equilibrium biaccumulation factor for .~

radionuclide 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-Mkg; _

D.

alp 3

= 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 mrem /pCi; or from exposure to a given concentra': ion of a radionuclide in sediment, expressed as a ratio of the dose rate, in mrem /h,andthearealrgdionuclide concentration, in pCi/m , from Tables 2.3-5 through 2.3-9; F = the flow rate of the liquid effluent in ft /s; NOTE: The normal dilution flow will be between 30,000 and 61,500 gpm (USAR 11.2.3.2)

Mp = the dilution factor at the midpoint of exposure (or the point of withdrawal of drinking water or point of harvest of aquatic food), from Table 2.3-10, dimensionless; Og = the release of radionuclide 'i', in Ci; t

b

= the period of time for which the sediment or soilisepsedtothecontaminatedwater, 1.75 x 10 h (20 years);

Tg = the half-life of radionuclide 'i', in days; tp = the average transit tima. required for I' radionuclides to reach the point of exposure, '

from Table 2.3-11; for internal dose, t is the totaltimeelapsedbetweenreleaseoft$e 1 ';1_ _

radionuclides and the ingestion of food or #

water, in h; U

ap = the usage factor that specifies the exposure time or intake rate for an individual of age group a associated with pathway "p*, from Table 2.3-12, in h/yr, 1/yr, or kg/yr; W = the shoreline width factor, 0.3 (from Regulatory Guide 1.109);

A *. = the radioagtive decay constant of radionuclide

i', in h~ ;

1

ODCM ,

Page: 13 Rev.: 4 1100 3

= a factor to convert from (Ci/yr)/(ft /s) to -

pCi/1; 110,000 = a factor to convert from (Ci/yr)/(ft3 /s) to .

pCi/1 and to account for the propoetione.lity _

constant used in the sediment radioactivity model.

- .i 2.3.2 Cumulation of Doses

' The dose contribution from liquid effluents will be calculated at least monthly. Calculations will be performed to determine the maximum total body as well as the maximum organ dose to an individual. These dose calculations will be summed for comparison with quarterly and annual limits. These results will 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 quarter:

Dose s 1.5 mrems total body; Dose s 5 mrems any organ; for the calendar year: '

Dose s 3 mrems total body; Dose s 10 mrems any organ.

The quarterly limits given above represent one-half of the annual design objective. If these quarterly or annual limits are exceeded, a special report will be submitted to the NRC, in accordance with F' Technical Specifications, stating the reason and correc a ve action to be taken. -

2.3.3 Projection of Doses

' ".[_

Anticipated doses resulting from the release of liquid efflu-ents 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.

- ODCM Page: 14 Rev.: 4

[

If the projected dose, when averaged over 31 days, exceeds 0.06 mrem to the total body or 0.2 mrem to any organ, the liquid radwaste system will be used to process waste. The values for the projected dose impact levels correspond to approximately one forty-eighth of the Appendix t tiesign ~

objective. If continued at this rate for one year, the projected impact would correspond to less than one-fourth of the Appendix I limit. The projected doses will be calculated -

using equations 2.3-1, 2.3-2, and 2.3-3.

In this case, the source term will be adjusted to reflect this

~

information and the justification for the adjustment noted.

This adjustment should account for any radwaste equipment which was operated during the previous month that could be out of service in the coming month.

2.3.4 Pcpulation Dose PNPP's Annual Radioactive Effluent Release Reports, as required by Regulatory Guide 1.21, will include total population dose and average individual doses calculated for radioactive effluent releases. The total population dose and average individual doses will 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 will be calculated by dose pathway and organ, with pathway doses being corrected for the fraction of the population assumed to be in each age group (adult, teen,'

child and infant: 0.71, 0.11, 0.18, 0.0 respectively).

~

e l'

.a.

l l

e 1

l l

i

ODCM Page: 15 Rev.: 4 i Table 2.3-1 .

a

~

Organs Used for Liquid Effluent Dose Calculations

1. Bone _ - . .

2. GI Tract , l

3. Kidney

4. Liver *

5. Lung

6. Thyroid 4 i

7. Total Body '

i

8. Skin Table 2.3-2 !

Age Groups Used for Liquid Effluent Dose Calculations

1. Adult (17 yrs. and older)

2. Teen (11 - 17 yrs)

3. Child (1 - 11 yrs) i

4. Infant (0 - 1 yr) l Table 2.3-3 ' '.$ -

Liquid Effluent Dose Pathways

- - 1

1. Water Ingestion .

2. Shore Exposure

3. Fresh Wter Fish Ingestion 1

i 4

i k

~!

t ODCM Page: 16 Rev.: 4 Table 2.3-4 .

Blaccumulation Factors (By) (DCi/kg per DCi/ 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 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 .

No 1.0E+01 !

Tc 1.5E+01 Ru 1.0E+01 Rh 1.0E+01 !

Te 4.0E+02 I 1.5E+01 Cs 2.0E+03 -

i Ba 4.0E+00 '

La 2.5E+01 Ce 1.0E+00 Pr 2.5E+01 Nd 2.5E+01 '

W 1.2E+03 ~

- 4 I

Np 1.0E+01 . ',? ,_

r.

s.

/

l

I-l l

l 00CM 1 Page: 17 l

Rev.: 4 Table 2.3-5 .

l I

Ingestion Dose Factors for Adult (mrem /pCi ingested)

- a _

NUCLICE SONE liver T.RDCY THYR 010 R10NEY LUNG C1-LL1

$$ 3 NO DATA 1.05E-07 1.0bE-0 7 1.05E-07 1.05E-07 1.05E-07 1.05E-07 .

C 14 2.84E-06 5 6BE-07 5 6BE-07 5.6BE-07 5.68E-07 5 68E-07 5.68E-07 NA 24 1.70E-06 1.70E-06 1. 70E-06 1.70E-06 1 70E-06 1.70E-06 1.70E-06 t

P 32 ~1.93E-04 1.20E-05 7.4 6E -0 6 NO DATA NO DATA NO DATA 2 17E-05 CR 51 NO DATA NO DATA 2. 66E -0 9 't.59E-09 5.86E-10 3 53E-09 6.69E-07 MN 54 NO DATA 4.57E-06 0. 72 E-0 7 NO DATA 1.36E-06 NO DATA 1.40E-05 i

MN $6 NO DATA 1.150-07 2.04 E-0 8 NO DATA 1 46E-07 NO DATA 3.67E-06 rE 55 2.75E-06 1.90E-06 4.43E-07 NO DATA NO DATA 1 06E-06 1.09E-06 FE 59 4.34E-06 1.02E-05 3 91E-06 NO DATA NO DATA 2.85E-06 3.40E-05 CD 58 NO DATA 7.45d-07 1. 67E-0 6 NO DATA NO DATA NO DAT'A 1 51E-05 C0 60 NO DATA 2.14F-06 4.72E-06 NO DATA NO DATA NO DATA 4.02E-05 N163 1.30E-04 9.01E-06 4. 36 E-0 6 NO DATA NO DATA NO DATA 1.88E-06 NI 65 5.28E-07 6.86E-08 3.13E-08 NO DATA NO DATA NO DATA 1.74E-06 CU 64 NO DATA 8.33E-08 3.91E-08 NO DATA 2.10E-07 NO DATA 7.10E-06 ZN 65 4.84E-06 1.54E-05 6. 96 E-0 6 NO ATA 1.03E-05 NO DATA 9.70E-06 ZN 69 1.03E-08 1.97E-08 1. 3 7E-0 9 NO DATA 1.28E-08 NO DATA 2 96E-09 BR 83 NO DATA NO DATA 4.02 E-0 8 NO DATA NO DATA NO DATA 5.79E-08 BR 84 NO DATA NO DATA 5. 21E-0 8 MO DATA NO DATA NO DATA 4.09E-13 BR 85 NO DATA NO DATA 2.14E-0 9 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 2.11E-05 9. 83E-0 6 NO DATA NO DATA NO DATA 4.16E-06 j RB 88 NO DATA 6.05E-08 1.21E-0 8 NO DATA NO DATA NO DATA S.36E-19 i RB 89 WO DATA 4.01E-08

2.82E-0 8 NO DATA NO DATA NO DATA 2 33E-21 SR 89 3.08E-04 NO DATA 8. 84 E-0 6 NO DATA NO DATA NO DAT A 4.94E-05 SR 90 7.58E-03 NO DATA 1. 86 E-0 3 NO DATA NO DATA NO DATA 2.19E-04 SR 91 5.67E-06 NO DATA 2.29 E-0 7 NO DATA NO DATA NO DATA 2.70E-05 SR 92 2.15E-06 NO DATA 9 30E-08 NO DATA NO DATA NO DATA 4.2 6E-05 Y 90 9.62E-09 NO DATA 2 58E-10 NO DATA NO DATA NO DATA 1.02E-04 Y 91N 9.09E-11 NO DATA 3.52E-12 NO DATA NO DATA NO DATA 2.67E-10 Y 91 1.41E-02 NO DATA 3.77E-0 9 NO DATA NO DATA NO DATA 7.76E-05 Y 92 8 45E-10 NO DATA 2 47E-11 NO DATA NO DATA NO DATA- 1.48E -

Y 93 2.68E-09 NO DATA 7.40E-11 M0 DATA NO DATA NO DATA 8.50E-05 ". ' ;~

2R 95 3.04E-08 9.75E-09 6.60E-0 9 NO DATA 1.53E-08 MO DATA 3.09E-05 -J '-

IR 97 1.6BE-09 3.39E-10 1 55E-10 NO DATA 5.12E-10 NO DATA 1.05E-04 NB 95 6.22E-09 3.46E-09 1. 86E-0 9 NO DATA 3.42E-09 MO DATA 2.10E-05 -

NO 99 NO DATA 4.31E-06 8. 20E-07 NO DATA 9.76E-06 NO DATA 9 99E-06 TC 99M 2.47E-10 6.90E-10 8. 8 9 E-0 9 NO DATA 1 06E-08 3.42E-10 4.13E-07 i

1

ODCM Page: 18 Rev.: 4 Table 2.3-5 (Cont.) .

Ingestion Dose Factors for Adult (mrem /pCi ingested)

. NUCLIOE SONE LivfA T.80DY THYA010 KIONEY LUNG GI-LLI TC101 2.b4E-10 3.66E-10 3.59E-09 NO DATA 6.59E-09 1.87[-10 1.10E-21 AU103 1.85E-07 MO DATA 7. 9 f E-0 8 NO D A T A' 7.06E-07 NO DATA 2 16E-05 I-2U105 1.54E-08 NU OATA 6. 08 E -09 NO DATA 1.99E-07 NO DATA' 9.42E-06 AU106 2.75E-06 40 DATA 3. 4 0 E-0 7 NO DATA 5.31E-06 NO DATA 1.74E-04

,AG110M 1.60E-07 1.48E-07 8 79E-08 NO DATA 2.9tE-07 NO DATA 6.04E-05 TE125M 2 6SE-06 9.71E-07 3 59E-07 8.06E-07 1.09E-05 ND DATA 1.07E-05 TE127M 6.77E-06 2.42[-06 8 25E-07 1.73E-06 2.75E-05 NO DATA 2.2 7E-05 TE127 1.10E-07 3.95E-00 2 38E-08 8 15E-08 4.48E-07 NO DATA 8.68E-06 TE129M 1.15E-05 4 29E-06 1 82E-06 3.95E-06 4.80E-05 NO DATA 5.79E-05 i TE129 3.14E-08 1.18E-08 7. 6s E-0 9 2.41E-08 1.32E-07 NO DATA- 2.37E-08 I TC131N 1.73E-06 8.46E-07 7 05E-07 1.34E-06 8.57E-06 NO DATA 8.40E-05 !

TE131 1.97E-08 8.23E-09 6 22E-09 1.62E-08 8.63E-08 NO DATA 2.79E-09 I l

TE132 2.52E-06 1 63E-06 1. 53E-0 6 1.80E-06 1.57E-05 NO DATA 7.71E-05 '

t 130 7.56E-07 2.23E-06 8. 80E-0 7 1.89E-04 3.48E-06 NO DATA 1.92E-06 I I 131 4.16E-06 5.95E-06 3. 41E-0 6 1.95E-03 1.02E-05 NO DATA 1.57E-06 :'

. ... - . . - _ . _ ~ - .. _

I 132 2 031-07 5.43E-07 1.90 E-0 7 1.90E-05 8.65E-07 NO DATA 1.02E-07 '

I 133 1.42E-06 2.47E-06 7.53 E-0 7 3.63E-04 4.31E-06 NO DATA 2.22E-06 t 134 1.06 2.88E-07 1.03 E-0 7 4.99E-06 4.58E-07 NO DATA 2.51E-10 I L _ .. __.E-07

! 135 4.43E-07 1.16E-06 4. 2 8 E-0 7 7.65E-05 1.86E-06 NO DATA 1.3tE-06 C5134 6.22E-05 1.48E-04 1. 21 E-0 4 NO DATA 4.79E-05 1.59E-05 2.59E-06 C5136 6.51E-06 2.57E-05 1. 85 E-0 5 40 DATA 1.43E-05 1.96E-06 2.92E-06 C5137 7.97E-05 1.09E-04 7.14 E-0 5 NO DATA 3.70E-05 1.23E-05 2.11E-06 C5138 5.52E-08 1.09E-07 5.40E-08 NO DATA 8.01E-08 7.91E-09 4.65E-13 '

8A139 9.70E-08 6.91E-11 2. 8 4 E-0 9 NO DATA 6.46E-11 3.92E-11 1.72E-07 '

. _ ~ . _ . . . . . . . . . . . - - - . . . . . . . . ~

f' SA140 2.03[-05 2.55E-08 1. 3 3 E-0 6 NO DATA 8.67E-09 1.46E-08 4.18E-05 B A141. 4. 71 E-08 1.56E-11 1.59E-0 9 40 DATA 3.31E-11 2.0ZE-11 2.22E-17 '

4A142 2.13E-08 2 19E-11 1. 3 4 E-0 9 No DATA 1.85E-11 1.24E-11 3.00E-26 LA140 2.$0E-09 1.262-09 J.33[-10 N0 DATA NO DATA NO DATA 9.25E-05 L A142 1.28E-10 5.821-11 1.45E-11 NO DATA NO DATA 40 DATA 4.25E-07 CE141 9.36E-09 6.35E-09 7.18E-10 WO DATA 2 94E-09 N0 DATA 1 42E-05 CE143 1.65E-09 . 1 2FE-06 1.35E-10 NO DATA 5.37E-10 NO DATA 4.56E-05 '. ,-

CEles 4.48E-07 2.04E-07 2.62E-C8 NO DATA 1.21E-07 NO DATA 1 65E-04 -

PA143 9 20E-09 3.69E-09 4 56E-to N0 DATA 2.13E-09 NO DATA 4.03E-05 '.-

PA144 3.01E-11 1.25E-11 1. 5 sE-12 N0 DATA 7.05E-12 NO DATA 4.33E-18 N014 7 6.29E-09 7.27E-09 4. 35 E-10 NO DATA 4.25E-09 NO DATA 3 49E-05 -~ ' '

W 197 1.03E-07 8.61E-08 3.01 E-0 5 NO DATA NO DATA NO DATA 2.82E-05 NP239 1 19E-09 1.17[-10 6.45E-11 No DATA 3.65E-10 ' NO D ATA '2 40E-05

ODCM Page: 19 Rev.: 4 Table 2.3-6 .

-Ingestion Dose Factors for Teenager (mrem /DCi ingested)

.-"a NUCLIDE SONE LIVE 4 T.t00T THYA010 KIDNEY LUNG GI-LL1 l

3 NO DATA 1.06E-07 1.06E-0 7 1.06E-0 7 1.06E-07 1.06E-07 1.06E-07 *I .

L 14 4.06E-06 8.12E-07 8.12 E-0 7 8.12F-07 8.12E-07 8 12E-07 8 12F-07 i NA 24 2.30E-06 2.30E-04 2.30E-06 2.30E-06 2.30t-06 2.30E-06 2 30E-06 P 32 2.76E-04 1.71E-05 1.0 f E-05 NO DATA NO DATA NO DATA 2.32E-05

CA $1 NU DATA NO DATA 3 60E-09 2.00E-09 7.89E-10 5 14E-09 6.05E-er FN 54 NO DATA 5.90E-06 1.17E-06 NO DATA 1 76E-06 NO DATA 1 21E-05 MN 56 NO DATA 1.38E-07 2.41E-08 NO DATA 2.00E-07 NO DATA 1.04E-05 FE 56 3.78E-06 2.68F-06 6.2 5E-0 7 gn DATA NO DATA 1.70E-06 1 16E-06 FE 59 5.87E-06 1.JFE-05 5.29E-06 NO D A TA NO DATA 4.32E-06 3.24E-05 i CD 58 NO DATA 9.72E-0F 2.24E-06 No DATA NO DATA NO DATA 1.34E-05 !

CO 60 NO DATA 2.81E-06 6. 33 E-0 6 NO DATA NO DATA NO DATA 3.66E-05 i N163 1.77E-04 1.25E-05 6. 00 E-0 6 NO DATA NO DATA NO DATA 1.99E-06 i 41 65 7.49E-07 9.57E-08 4.3e E-0 8 NO DATA NO DATA NO DATA 5.19E-06 '

CU 64 NO DATA 1*15E-07 5.41E=OS NO DATA 2.91E-07 NO DATA 8.92E-06 -

IN 6b 5.76E-06 2.COE-05 9. 3 3 E-06 NO DATA 1.28E-05 NO DATA 8.47E-06 '

ZN 69 1.47E-08 2.50E-08 1.96E-0 9 40 DATA 1.81E-08 NO DATA 5 16E-08 BR 83 NO DATA NO DATA- S.74E-08 NO DATA NO DATAa NO DATA LT E-24 !

BA 54 NO DATA NO DATA 7.22 E-0 8 NO DATA NO DATA NO DATA LT E-24 ,

eA 85 NO DATA NO DATA 3.05 E-09 NO DATA NO DATA NO DATA LT E-24 R8 86 NO DATA .2.98E-05 1 40E-05 NO DATA NO DATA NO DATA 4.41E-06 48 88 NO DATA 8.52E-08 4.54E-00 NO DATA NO DATA NO DATA 7.30E-15 RB 89 NO DATA 5.50E-08 3 89E-08 NO DATA NO DATA NO DATA 8.43Ea17 I SR 89 4.40E-04 NO DATA 1 26E-05 NO DATA NO DATA NO DATA S.24E-05 i 5R 90 8.30E-03 NO DATA 2 05E-03 NO DATA NO DATA NO DATA 2.33E-04 i SR 91 8.07E-06 NO DATA 3 21E-07 NO DATA NO DATA NO DATA 3.66E-05 !

SR 92 3.05E-06 NO DATA 1. 30E-0 7 NO DATA NO DATA NO DATA 7.77E-05 :

Y 90 1.37E-08 NO DATA 3.69E-10 No DATA NO DATA NO DATA 1.13E-04 l Y 91N 1.29E-10 NO DATA 4.93E-12 NO DATA NO DATA No DATA 6.09E-09 Y 91 2 01E-07 40 DATA 5. 39E-4 9 NO DATA NO DATA NO DATA 8.24E-05 A Y 92 1.21E-09 NO DATA 3.50E-11 NO DATA NO DATA NO DATA ~3 32E-05 Y 93 3 83E=09" NO DATA 1.05E-10 NO DATA NO DATA NO DATA 1.17E-04 ..'I 2R 95 4.12E-08 1.30E-08 8.94E-09 No DATA 1.91E-08 NO DATA 3.00E-05 I 'J~

la 9F 2.37E-09 4.69E-10 2.16E-10 NO DATA 7 11E-10 NO DATA 1.27E-04 l

dit 95 8.22E-09 4.56!-09 L 51E-09 NO DATA 4.42E-09 ND' DATA 1.95F-05 i T' -

MD 99 NO DATA 6.03E-06 1.15 F-06 NO DATA 1.38E-05 NO DATA 1 08E-05 I TC 99M s.32E-10 9.2&E-10 1 20E-0 8 No DATA 1.38E-08 5.14E-10 6.08E-07 :

1 l

4

)

l 1

ODCM Page: 20 l Rev.: 4 l

Table 2.3-6 (Cont.)

Ingestion Dose Factors for Teenager (mrem /pCi ingested)

. .e a NUCL1DE DONE L1vig r.80Dr TNYRotD E1DNEY LUNC C1-LLI FC101 3.60E-10 5.12!-10 5. 0 lE-0 9 No DATA 9.26E-09 3.12E-10 8.75E-17 1 RU103 2.55E-07 NU OATA 1.09E-0 7 NO DATA 8.99E-07 NO DATA 2 13E-05 -

AU105 2 18E-08 NO DATA 8. 4 6 E -0 9 NO DATA 2.35E-07 NO DATA 1 76E-05 Aut06 3.92E-06 N0 DATA 4. 94 E-0 7 NO DATA 7.56E-06 NO DATA

.A0110M 2.05E-07 1.94E-07 1.18E-07 NO DATA 1 88E-04 8 3.70E-07 NO DATA 5.45E-05 TE125m 3.83E-06 1.38E-06 5.12E-07 1.07E-06 NO DATA NO DATA 1.13E-05 TE127M 9.67E-06 3.4AE-06 1 15E-06 2.30E-06 3.92E-05 NO DATA 2.41E-05 TE127 1.58E-07 5.60E-08 3. 40 E-0 8 1.09E-07 6.40E-07 NO DATA 1.22E-05 FE129M 1.63E-05 6.05E-06 2. 58 E-06 5 26E-06 6.R2E-05 NO 6 12E-05

.. ......... ................ .. .. .. ... .. . DATA ... .. ,

TE129 4.48E-08 1.67E-08 1. 01E-0 8 3 20E-08 1.88E-07 NO DATA TE131> 2.44E-06 1.17E 9.76E-07 2.45E-07 1 76E-06 1.22E-05 NO DATA 9.39E-05 TE131 2.79E-08 ~1 15E-08 8.72E-09 2 15E-08 1.22E-07 NO DATA 2.29E-09 TE132 3.49E-06 2.21E-06 2.08E-06 2.33E-06 2.12E-05 NO DATA .

1 130 7.00E-05 1 131 1.03E-06 2 98E-06 1.19E-06 2 4 3E-04 4 59E-06 NO DATA 2.29E-06 5.85E-06 8.19E-06 4. 4 0 E-0 6 2.39E-03 1.41E-05 NO DATA 1.62E-06 .

I 132 2.79E-07 7.30E-07 2. 62 E-0 7 2.46E-05 1.15E-06 NO DATA 3 18E-07 1 133 2.01E-06 3.41E-06 1. 04 E -0 6 4.76E-04 5.98E-06 NO DATA 1 134 1.46E-07 3 87E-07 2.58E-06

1. 3 9E-0 7 4.45E-06 6.10E-07 MO DATA 5 10E-09 1 135 6 10E-07 1 57E-06 5. 82 E-0 7 1.01E-04 2.48E-06 NO DATA C5134 8 37E-05 1.74E-06 1.97E-04 9 14 E-05 NO DATA 6.26E-05 2.39E-05 2.45E-06 C5136 8.59E-06 3.38E-05 2.2 7E-0 5 NO DATA 1.84E-05 2.90 E-06 2.72E-06 C5137 1.12E-04 1.49E-04 5.19 E-0 5 NO DATA ,5.07E-05. 1.97E-05 2.12E-06 C5138 7.76E-08 1.49E-07 7. 45E-08 NO DATA SA139 1.39E-07 9.78E-11 4.05E-0 9 NO DATA 1.10E-07 1.28E-08 4.76E-11 9.22E-11 6.74E 1.24E-06 84140 2.84E-05 3.4aE-08 ! . 8 3 E-0 6 No DATA BA141 6.71E-08 5.01E-11 1.18E-08 2.34E-08 4.30E-05

2. 2 4 E-0 9 40 DATA 4.65E-11 3443E-11 1.43E-13 DA142 2.99E-00 2.99E-11 1. 84E-0 9 NO DATA 2.53E-11 1.99E-11 9.18E-20 LA140 3.48E-09 1.71E-09 4. 5 5E-10 NO DATA NO DATA NO DATA 9.82E-05 LA142 1.79E-10 7.95E-11 1.98E-11 NO DATA NO DATA ho DATA 1 42E-06 CE141 1 33E-08. 8.88E-09 1. 02E-09 NO DATA 4.18E-09 NO DATA 7.54E CE143

... _ . . . . . . . - - ... - . _-05 e

, ,~- ,.

2.35E-09 1.71E-06 1.91 E-10 NO DATA 7.67E-10 NO DATA 5.14E-05 CE144 6.96E-07 2.88E-07 3.74 E-0 8 NO DATA 1.72E-07 NO DATA 1.75E-04 1 1~

PR143 1.31E-08 5. 2 3C-09 6. 52 E-10 NU DATA 3.04E-09 NO DATA 4.31E-05 PR144 4 30E-11 1.76E-11" 2.18E-12 NO DATA 1.01E-11 NO DATA 4.74E-14 I' N0147 9.38E-09 1.02E-08 6.11E-10 NO DATA 5. 99E-09 NO DATA 3.68E-05 k 187 1.46E-07 1.19E-07 4 17E-08 NO DATA NO DATA NO DATA 3.22E-05 NP239 1.76E-09 1.66E-10 1. 22 E-11 w0 DATA 5.21E-10 NO DATA 2.67E-05 l

1 l

1 i

I occM Page: 21 Rev.: 4 Table 2.3-7 _

Ingestion Dose Factors for Child (mrem /pCi ingested) l l

- *. i j NuCL1DE 00NF LIVER T.nDuf TMYA010 EIONEY LINeG GT-LLI ]

.. _ .. ........ ..._ . . .. _ .. - .. .. i H 3 40 DATA 2.03E-07 2.0 %E-0 7 2.03E-07 2 03E-07 2.03E-07 2.03E-07 . 1 C 14 1.21E-05 2.*2E-06 2.42E-06 2 42E-06 2 42E-06 2.42E-oe 2.42E-06 NA 24 S.00E-06 5.00E-06 5.80E-06 5.80E-06 5.80E-06 5 80E-06 5.80E-06 .... . .

]

,P 32 8.25E-04 3.065-05 3.18E-Ob 40 DATA 40 DATA NO DATA 2 28E-05 CR 51 NO DATA N0 DATA 8.90E-09 4.94E-09 1.35E-09 9.02E-09 4.72E-07 MN 54 NO CATA 1 0TE-05 2. 8 5E-06 NO DATA 3.00E-06 NO DATA 8.98E-06 MN 56 NO DATA 3.34E-0T 7.54E-08 N0 DATA 4.04E-07 40 DATA 4.04E-05 FE SS 1.15E-05 6 10E-06 1. 8 9 E-06 NO DATA NO DATA 3.45E-06 1.13E-06 FE $9 1.6SE-05 2.67E-05 1. 3 dE-0 5 NO DATA NO DATA 7.74E-06 2.7BE-05 CD 58 NO DATA 1.80E-06 5.51 E-0 6 NO DATA NO DATA NO DATA 1.05E-05 i CD 60 800 DATA 5 29E-06 1.56 E-0 5 NO DATA NO DATA NO DATA 2.93E-05 ! l NO DATA NO DATA N0 DATA 1.94E-06 '

N163 5.30E-C4 2.88F-05 *1.BJE-05 )

MI 65 2.22E-06 2.09F-07 1.22 E-0 7 NO DATA NO DATA No DATA 2.56E-05

5.92E-07 NO DATA 1.15E-05 '

CU 64 NO DATA 2.45E-07 1.48E-07 NO DATA I IN 65 1.37E-05 3.65E-0> 2.2 TE-0 5 NO DATA 2.50E-05 NO DATA 6.41E-06 '

ZN 69 4.38E-08 6.33E-08 5. 8 5 E-09 NO DATA 3.84E-08 NO DATA 3.99E-06 BR 83 NO DATA NO DATA 1. 71E-0 7 NO DATA NO DATA NO DATA LT E-24 i SR 84 NO DATA NO DATA 1. 98E-0 7 NO DATA NO DATA NO DATA LT E-24 i AR 85 NO DATA NO DATA 9.12 E-09 NO DATA NO DATA NO DATA LT E-24 i Nb $6 NO DATA 6.70E-05 4.12 E-0 5 N0'OATA NO DATA. NO DATA 4 31E-06 i R8 $$ NO DATA 1.90E-07 1. 32 E-0 7 NO DATA NO DATA NO DATA 9.32E-09 I R8 89 NO DATA 1.17E-07 1. 04 E-0 7 NO DATA NO DATA NO DATA 1.02E-09 1R 89 1.32E-03 NU DATA 3.77E-0 5 40 DATA 40 DATA NO DATA 5.11E-05 SR 90 1.70E-02 NO DATA 4.31 E-0 3 40 DATA NO DATA NO DATA 2.29E-04 SR 91 2.40E-05 NO DAT A 9. 06 E -0 7 NO DATA NO DATA NO DATA 5.30E-05 SR.92 9.03E-06 NO DATA 3.62 E -07 NO DATA NO DATA NO DATA 1.71E-04 I .

Y 90 4.11E-08 NO DATA 1.10E-0 9 NO DATA NO DATA NO DATA 1.17E-04 ! .

Y 91M 3.82E-10 NO DATA 1.39E-11 NO DATA 40 OATA No DATA 7.48E-07 '

e Y 91 6.02E-07 NO DATA 1.61 F=0 8 es0 DATA NO DATA No DATA S.02E-05 i r '

Y 92 3.60E-09 40 DATA 1.0 A E-10 NO DATA NO DATA NO DATA *1.04E-04 _

Y 93 1.14E-08 NO DATA 3.13E-10 NO DATA NO DATA NO DATA 1.70E-04 i< ,

2A 95 1.16E-07 2.dE-08 2.27E-08 M0 DATA 3 65E-08 NO DATA 2.66E-05 --

c 2R 97 6.99E-09 1.01E-09 5.96E-10 NO DATA 1.45E NO DATA 1.53E-04 48 95 2.25E-08 8.76E-09 6.26E-09 NO DATA 8.23E-09 N0 DATA 1.62E-05 ' -*

MO 99 NO DATA 1.33E-05 3. 29E-06 No DATA 2.84E-05 NO DATA 1.10E-05 TC goes 9.23E-10 1.81E-09 3 00E-08 eso DATA 2 63E-08 9.19E-10 1.03E-06 w,.-.-

4 ODCM Page: 22 Rev.: 4 Table 2.3-7 (Cont.)

Incestion Dose Factors for Child (mrem /DCi incested)

. ~.t a -

NUCLIUE SONE Livf4 T.800f THYROIO Ef0htY LUNG GI-Lt1 IC101 1.07E-09 1.12E-09 1.42E-08 NO DATA aut03 7.31E-07 No DATA 1.91E-08 5 92E-10 3.56E-09 I r.U105

2. 81E-07 NO DATA 1.84E-06 NO DATA 1.89E-05 6.45E-08 NO DATA 2.34E-08 No DATA 5.67E-07 NO DATA 4.21E-05 AU196 1 17E-05 NO DATA 1.46E-06 NO DATA i 1.58E-05 NO DATA 1.42E-04

< 'AC110M 5.39E-0F 3.64E-07 2.91E*07 NO DATA 6.74E-07 No DATA 4.33E-05 TE125M 1.14E-05 3.09E-06 1. 52 E-06 3.20E-06 NO DATA NO DATA 1.10E-05 TE!ZTM4.71E-07 TE127 2.89E-0517.78E-06 27F-07 3.4JE-06 6.91E-06 8.24E-05 NO DATA 2.34E-05

1. 01 E-0 7 3.26E-07 1 34E-06 No OATA 1.84E-05 TE1298 4.87E-05 1 36E-05 7.56E-06 1.57E-05 1.43E-04 NO DATA 5.94E-05 l

TE129 1.34E-07 3.74E-08 3 18E-08 9.56E-38 3.92E-07 NO DATA 4.34E-06 TE131M TE131 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.41E-05 NO DATA 1.01E-04 8 30E-08 2 53E-06, 2.47E-08 6.35E-08 2.51E-07 NO DATA 4 34E-07 TE132 1 130 1.01E-05 5.90E-06 2.92E-06 4.47E-06 5.40E-06 6.51E-06 4.15E-05 NO DATA 4.50E-05

' 3. 04 E-06 6.50E-04 8.82E-06 NO DATA 2.76E-06 I 131 1 72E-05 1.73E-05 9. 83E-06 5.72E-03 2. 84 E;-05 NO DATA 1.54E-06 8 132 8.00E-07 1.47E-06 6. 76 E-0 7 6.82E-05 2.25E-06 NO DATA 1.73E-06 1 1 133 5.92E-06 7.32E-06 2. 77E-06 1.36E-03 1.22E-05 NO DATA 2.95E-06 I 134 4 19E-07 7.78E-07 3.58 E-0 7 1.79E-05 1.19E-06 NO DAT4 5.16E-07 i .

1 135 1.75E-06 3.15E-06 1.49E-0 6 2.79E-04 4.83E-06 NO DATA C5134 2.34E-04 3.84E-04 8.10E-0 2.40E-06

C5136 5 NO DATA 1.19E-04 4.27E-05 2.0TE-06 j

......... 2.35E-05 6.46E-05 4.18E-0 5 NO DA

........... 3.44E-05 5.13E-06 2.27E-06 -

. - . .... .TA C5137 3.27E-04 3.13E-04 4.62E-05 NO DATA r' C5138 1.02E-04 3.67E-05 1.96E-06 '

2.28E-07 3.17E-07

2.01E-07 NO DATA i 8A139 4.14E-07 2.21E-10 1.20E-08 40 DATA 2.23E-07 2.40E-08 3.46E-07 1.93E-10 1.30E-10 ~ 2.39E-05 P.1140 '8.31E-05 7.24E-08 4.85E-06 40 DATA "A141 2.00E-07 1. ! N- 10 6 51E-09 40 DATA 2.3 7t-08 4.34E-08 4.21E-05 P i SA142 8.74E-04 6.295-11 4. 8 8 E-0 9 40 DATA 9.69E 6.58E-10 1 14E-0F 5.09E-11 3.70E-11 1 14E-09 l*

LA140 1.01E-Os 3.53E-09 1.19E-0 9 NO DATA LA142 NO OATA NO DATA 9 84E-05 5.24E-10 1.67E-10 S.23E-11 NO DATA 40 DAT4 NO DATA L31E-05 j CE141 h.97E-08 1.98E-00 2.94E-09 No DATA 8.68E-09 N0 OATA 2.4TE-05 g-e CE143 6.99E-09' 3.79E-06 5.49E-10 NO DATA 1,'

C E144 1.59E-09 NO DATA - 5.55E-05 -

2.08E-06 4.52E-07 1.1 t E-0 7 NO DATA 3.61E-07 NO DATA 1 70E-04

PR143 3.93E-08 1.18E-04 1.95E-09 40 DA TA 6.19E-09 40 DATA 4 24E-05

..... .~ _ .. i PR144 ., r N0147 1.29E-10 3.99E-11 6.49E-12 NO DATA 2.11E-11 No DATA 8.59E-08

~

2.79E-08 2.26E-08 1. 75E-0 9 40 DATA 1.24E-08 NO DATA 3 54E-05 W 187 4.29E-07 2.54f-07 1.16E-0 7 NO DATA NO DATA NO DATA 3.57E-05 NP239 5.2bE-09 3.77E-10 2.6bE-10 40 DATA 1.09E-09 No DATA 2.F9E-05 t

- ODCM Page: 23 Rev.: 4 i

Table 2.3-8 Incestion Dose Factors for Infant (mrem /pCi incested)

~ ~'

~ ~* -

NuCLIDE SONE Live 4 T.Sopy ' TNvROIO alDNEY LUNG OI-LLI N 3 NO DATA 3%08E-07 3.08 E-0 7 3. 0 ', E -0 7 3.08E-07 3.00E-07 3.08E-07

C to 2.3fE-05 S.c4f-06 5 06E-06 5.06E-06 5.06E-06 5 06F-06 5.06E-06 NA 24 1.01E-05 1.0!E-05 1 01E-05 1.0tE-05 1.01E-05 1.01E-Ob I.01E-05

.F 32 1.70E-03 1 00E-04 6.59E-05 40 UATA NO DATA N0 DATA 2.10E-05

- Ca 51 NO DATA No DATA 1.4tE-08 9.20E-09 2.01E-09 1.79E-08 4.11E-07 MN 54 40 DATA 1.99E-Ob 4.5tE-06 NO DATA 4.4tE-06 ND DATA T.31E-06 1

NN 56 NO DATA S.tSE-07 1 4 t E-0 7 90 OATA 7.01E-07 NO DATA 7.43E-05 c

TE 55 1.39E-05 8.981-06 2 40E-06 NO DATA NO DATA 4 19E-06 1.14E-06

( FE 59 3.00E-05 5.s82-05 2.12E-06 NO DATA NO DATA 1.59E-05 2.57E-05 CO 58 NO DATA 3.60E-06 8. 93 E -06 NO DATA NO DATA NO DATA 8.9fE-06 CD 60 NO DATA 1.08E-05 2 55E-05 NO DATA NO DATA NO DATA 2.5fE-05 NI 63 6.34E-04 3.92E-05 2. 20E-05 NO DATA NO DATA NO CATA 1.95E-06 f

NI 65 4.70E-06 5 32E-0T 2 426-07 NO DATA NO DATA NO DATA 4.05E-05 i CU 64 NO DATA 6.09E-0T ' 2 82 E-0 7 NO DATA 1.03E-06 NO DATA 1 25E-05 IN 65 1.84E-05 6.)1E-05 2 9tE-05 NO DATA 3.06E-05 NO DATA 5.33E-05 ZN 69 9.33E-08 1 68E-0T ! .25 E-0 8 N3 DATA 6.98E-08 NO DATA 1.37E-05 IIR 83 No DATA NO DATA 3 63E-07 NL' 04TA NO DATA NO DATA LT E-24 BR 84 NO DATA NO DATA J . 82 E-0 7 NO DATA NO DATA NO DATA LT E-24

- - ...... ~ . ~ ... .......... . . . ~ . -

WR 85 NO DATA NO DATA 1 94E-08 NO DATA NO DATA NO DATA LT E-26 R$ 86 NO DATA 1.T0E-04 8. 40 E -0 5 NO DATA NO DATA NO DATA 4.35E-06 N8 88 NO DATA 4.98E-07 2.73E-07 NO DATA NO DATA NO DATA 4.85E-07 RO 89 NO DATA 2.86E-07 1.97E-07 NO DATA NO DATA NO DATA 9.74E-08 SR 89 2.51E-03 NO DATA 7. 2 0 E-0 5 40 DATA NO DATA NO DATA 5.86E-05 SR 90 1.85E-02 NO DATA 4. 71 E-0 3 NO DATA NO DATA NO DATA - 2.3tE-04 SR 91 S.00E-05 NO DATA 1.81E-06 NO DATA NO DATA NO DATA 5.92E-05 SR 92 1 92E-05 NO DATA 7.13E-07 NO OATA NO DATA NO DATA. 2.07E-04 Y 90 8.69E-08 40 DATA 2. 3 sE-0 9 NO DATA NO DATA NO DATA 1 20E-04 Y 91m 8.10E-10 NO DATA 2.16E-11 NO DATA 40 DATA NO DATA 2.70E-06 Y 91 1.13E-06 40 DATA 3.01E-0 8 NO DATA NO DATA NO DATA 8.10E-05 ' '

Y 92 7.65E-09 NO DATA 2.15E-10 40 DATA NO DATA NO DATA -l.46E-04 -

Y 93 2.43E-08 NO DATA 6.62E-10 NO DATA NO DATA NO DATA t.92E-04 .L,

'2R 95 2 06E-07 5 02E-08 3.56E-0 8 NO DATA 5.41E-08 NO DATA 2.50E-05 . .

I (A 97 1 48E-08 2 54E-09 1.16E-0 9 NO DATA 2.56E-09 MO DATA t.62E-04 *

. . . . - . - - . . - . . . . . . . . . . . . ~ - - . - - - - . _ --p 18 95 4.20E-08 1 73E-08 8. c0E-0 8 NO DATA 1.74E-08 No DATA 1.46E-05 .,.

NO 99 NO DATA 1 40E-05 6. 63 E-0 6 NO DATA 5.00E-05 NO DATA 1.12E-05 TC 99M 1 92E-09 3 96E-09 5.10E-0 8 No DATA 4.26E-08 2.07E-09 1.15E-06 .

l l

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i.

ODCM Page: 24 Rev.: 4 Table 2.3-8 (Cont.)

Ingestion Dose Factors for Infant (mrem /DCi ingested)

NuCL:0E a0NE LIvtR T.000f TNyacID ' alDNEY LUNG gg.Ltg

. . .. ~ . . - - ...

- rC101 2.27E.09 2. 86E-09 a.83E-08 NO DATA 3.40E-08 1.56E-09 4.86E-07 2U103 1.48E-06 NO DATA 4.95E-07 40 DATA 3 08E-06 NO DATA 1.80E-05 4.58E-08 NO DATA 1.00E-06 No DATA 5,%1E-05 4Ul05 1.36E-67 NO CATA Rut 06 2.41E-05. NO DATA 3.01 E-0 6 No DATA 2.85E-05 NO DATA 1.03E-04 4Gilon 9196E-07 7.27E-07 4.stE-07 90 DATA 1 04E-06 NO DATA 3.77E-05 TE125M 2.33E-05 7.79E-06 3. Int-06 7.84E-06 NO DATA NO DATA 1.11E-05 TE12FM 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 NO DATA 2.36E-05 TE127 1.00E-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 NO DATA 2.10E-05 TE129M 1 00E-04 3 43E-05 1.54 E-0 5 3.84E-05 . 2.50E-04 NO DATA 5.97E-05 2.27E-05 TE129 2.84E-07 9.79E-08 6.63E-08 2.38E-07 7.0TE-07 'NO DATA TE131P 1.52E-05 6 12E-06 .5.05E-06 1 24E-05 4.21E-05 NO DATA 1.03E-04

- TE131 1.76E-07 6.50E-08 4.94E-08 1.t?E-07 4 50E-07 NO DATA 7.11E-06 TE132 2.08E-05 1.03E-05 9.61E-06 1 52E-05 6.44E-05 NO GATA 3.81E-05 1 130 6.00E-06 1 32E-05 5.30E-06 1 48E-03 1.45E-05 NO DATA 2.01E-06 1 131 3.59E-05 4.23E-05 1. 46E-0 5 1 39E-02 4.94E-05 NO DATA 1.51E-06 1 132 1.66E-06 3 37E-06 1.2 0E-06 1 5BE-04 3.76E-06 NO DATA 2.73E-06 1 133 1.25E-05 1.82E-05 5.3 3 E-06 3.31E-03 2.14E-35 NO DATA 3.08E I 134 8.69E-07 1 78E-06 6. 33 E-0 7 4 15E-05 1.99E-06 NO DATA 1.84E-06 I 135 3.64E-06 7.24E-06 2.64E-06 4.49E-04 0.07E-06 NO D AT A 2.62E-06 C5134 3.77E-04 7.03E-04 7.10E-0 5 NO DATA 1.81E-04 7.42E-05 1.91E-06 s

C5136 4.59E-05 1 35E-04 5 04 E-0 5 NO DATA 5.30E-05 1.10E-05 2.0$E-06 C5137 5.22E-04 6.11E-04 4.13E-0 5 NO DATA 1.64E-04 6.64E-05 1.91E-06

C5138 4.81E-07 7.82E-07 3.79E-0 7 NO DATA 3.90E-07 6.09E-08 1.25E-06 8A139 8.81E-07 5.84E-10 2.55E-08 No DATA 3.51E-10 3.54E-10 5.58E-05 84140 1.71E-04 1.71E-07 8. AIE-06 NO DATA 4.06E-08 1.05E-07 4 20E-05 P. A t 41 4 25E-07 2 91E-10 1.34E-08 No DATA 1 75E-10 1.77E-10 5 19E-06 8.81E-11 9.26E-11 7.59E-07

? e&142 1.04E-07 1.53E-10 9. 06E-0 9 NO CATA Lat40 2.11E-08 4 32E-09 2.14 E-09 NO DATA NO DATA NO DATA 9.77E-05 .

L A142 1.10E-09 4 04E-10 9.6tf-11 NO DATA NO DATA NO DATA. 6.06E-05 CC141 7.87E-08 4.80E-08 5.65E-09 NO DATA 1 40E-08 NO DATA 2.40E-05 _

CEt43 1 48E-00 9.82E-06 1 12E-09 N0 0ATA 2 96E-09 N0 0ATA 5.73E-05 .

CE144 2.90E-06 1.22E-06 1.67E-07 NO DATA 4.93E-07 NO DATA 1.7&E-04 1~

PR143 8.13E-00 1 04E-08 4.03E-09 NO DATA 1 13E.08 fs0 DATA 4.29E-05 PR144 2.74E-10 1.06E-10 1. 30E-11 NO DATA 3.84E-11 NO DATA 4.93E-06 N0147 5 53E-08 5.68E-08 3.48 E-09 NO DATA 2.19E-08 NO DATA 3.60E-05 W 187 9.03E-07 6.20E-07 2.17 E-0 7 No DATA NO DATA NO DATA 3.69E-05 NP239 1.1tE-08 9.93E-10 5.61 E-10 10 DATA 1 90E-09 No DATA 2.87E-05 i

ODCM Page: 25 Rev.: 4 Table 2.3-9 External Dose Factors for Standing on Contaminated Ground (mrem /h per pCi/m2 ) _ _ .

Element Total Body Skin H-3 0.0 0.0 C-14 0.0 0.0 4 24 2.50E-08 2.90E-08 P-3 O.0 0.0 >

Cr$'1 2.20E-10 2.60E-10 Mn-54 5.80E-09 6.80E-09 Mn-56 1.10E-08 1.30E-08 Fe-55 0.0 0.0 Fe 59 8.00E-09 9.40E-09 _

Co-58 7.00E-09 8.20E-09 Co-66 1.70E-08 2.00E-08 al-63 0.0 0.0 ar-65 3.70E-09 4.30E-09 tv-64 1.50E-09 1.70E-09 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 i Br-85 0.0 0.0 Rb 86 6.30E-10 7.20E-10 4 88 3.50E-09 4.00E-09 4 89 1.50E-08 1.80E-08 Sr-89 5.60E-13 6.50E-13 Sr-91 7.10E-09 8.30E-09 i Sr-92 9.00E-09 .1.00E-08 Y-90 2.20E-12 2.60E-12 Y-91M 3.80E-09 4.40E-09 Y-91 2.40E-11 2.70E-11 Y-92 1.60E-09 1.90E-09 Y 93 5.70E-10 7.80E-10 Zr-95 5.00E-09 5.80E-09 i Zr-97 5.50E-09 6.40E-09 :

5.10E-09 6.00E-09 i Mb-95 Mo-99 1.90E-09 2.20E-09 i Tc-99H 9.60E-10 1.10E-09 i Tc.101 ' 2.70E-09 3.00E-09 I tv 103 3.60E-09 4.20E-09 '*' '

Re-105 4.50E-09 ** 5.10E-09 )

'~

Re-106 1.50E-09 1.80E-09 ! .< ,

A9-110H 1.80E-08 2.10E-08 ' ; .J Te-125M 3.50E-11 4.80E-11 '

Te-127M 1.10E-12 1.30E-12 Te-127 1.00E-11 1.10E-11 Te-129H 7.70E-10 9.00E-10 7.10E-10 8.40E-10 l Te-129 Te-131M 8.40E-09 9.90E-09 l Te 131 2.20E-09 2.60E-06 l

.Te-132 1.70E-09 2.00E-09 4

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ODCM Page: 26 Rev.: 4 i Table 2.3-9 (Cont.) -

l External Dose Factors for Standing on Contaminated Ground j I

(mrem /h per pCi/m2 ) -. .',

1

. . 1 Element Total Sody SHn

l I-130 1.40E-08 1.70E'-08 '

I-131 2.80E-09 3.40E-09 I

, 1-132 1.70E-08 2.00E-08 i 1-133 3.70E-09 4.50E-09 l I-134 1.60E-08 1.90E-08 I-135 1.20E-08 1.40E-06 Cs 134 1.20E-08 1.40E-08 l <

Cs-136 1.50E-08 1.70E-08 ,

Cs-137 . 4.20E-09 4.90E-09'~ ;

Cs-138 2.10E-08 2.40E-08 l Sa-139 2.40E-09 2.70E-09 Ba-140 2.10E-09 '

2.40E-09 Ba-141 4.30E-09 4.90E-09 84-142 7.90E-09 9.00E-09 La-140 1.50E-08 1.70E-08 La 142 1.50E-08 1.80E-06 Ce-141 5.50E-10 6.20E-10 i Ce-143 2.20E-09 2.50E-09 Ce-144 3.20E-10 3.70E-10 Pr-143 0.0 0.0 i' Pr-144 2.00E-10 2.30E-10 Nd-147 1.00E-09 1.20E-09 <

W-187 3.10E-09 3.60E-09 l Np-239 9.50E-10 1.10E-09 l

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ODCM Page: 27 Rev.: 4 Table 2.3-10 l l

Liquid Effluent Dilution Factors (M ) ;

p

~~ "'

, Maximum Individual Dilution Factors Mp

Pathway Location Potable Water Ingestion 3.9 mile WSW of site 32.2 l Fresh Water Fish Ingestion Near Discharge Structure 10.9 Shoreline Exposure 0.7 mile ENE of Site 14.5 Population Dose Dilution Factors i

Pathway Location ,

Potable Water Ingestion Population Weighted Average 314 Fresh Water Fish Ingestion Catch Weighted Average 77.4 i Shoreline Exposure 7.7 mile WSW of site 162 t

Table 2.3-11 ,

Transit Times Required for Nuclides to Reach the Point of Exposure (t [ j Maximum Exposed Average Exposed Individual Individual * ,

Eventual transit time for water ingestion 12 h 24 h - ' -;

i Eventual transit time for fish ingestion 24 h 168 h Eventual transit time for shore exposure 0h 0h

for total population and average individual dose calculations

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ODCM :

Page: 28 Rev.: 4 Table 2.3-12 ,

Usage Factors (U_pl Maxim m Exposed -Average Exposed. .

f

,- Individual " ~ 1ndividual* --

i-730 370 , l Water ingestion (1/yr) Adult 510 260 ;

Water ingestion (1/yr) Teen 510 260 Water inghstion (1/yr) Child

~

Water ingestion (1/yr) Infant 330 21 6.9 Fresh water fish ingestion (kg/yr) Adult t 16 5.2 Fresh water fish ingestion (kg/yr) Teen ,

6.9 2.2 Fresh water fish ingestion (kg/yr) Child Fresh water fish ingestion (kg/yr) Infant 12 8.3 i Shore exposure (h/yr) Adult :

67 47 Shore exposure (h/yr) Teen ;

14 9.5 !

Shore exposure (h/yr) Child Shore exposure (h/yr) Infant i I

for total population and average individual dose calculations l i

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ODCM Page: 29 Rev.: 4 Table 2.3-13 .

Dilution Factors for Each of the Potable Water Intakes within 50 Miles of PNPP

% ~_'. _

The total population dilution factor of 314 is population weighted using

dilution factors for each of the potable water intakes within 50 miles of PNPP.

Weighted Dist. Fraction Dilution Dil.

Intake (Mi) Dir Population of Pop Factor Factor ,

Ohio American 20 ENE 38,500 2.12E-2 187.7 3.98E+0 Water Serv. Co.

Conneaut 33 ENE 13,500 7.43E-3 238.2 . 1.77E+0 Avon Lake 50 WSW 99,500 5.48E-2 388.5 2.13E+1 Cleveland 35 SW 1,437,000 7.92E-1 326.7 2.59E+2 Fairport Harbor 7 WSW 3,200 1.7 6E-3 154.2 2.71E-1 Lake County East 3.5 WSW 10,258 5.65E-3 107.4 6.07E-1 Lake County West 15 WSW 85,000 4.68E-2 220.0 1.03E+1 Ohio Water Serv. 10 WSW 60,000 3.30E-2 181.9 6.00E+0 Painesville 7.5 WSW 27,000 1.49E-2 159.3 2.37E+0 Kent County 50 NW 42,000 2.31E-2 388.5 8.97E+0' Water Supply TOTALS 1,815,958 1.00E+0 TOTAL D.F 3.14E+2 Dist, Dir Population = distance, direction, and population values obtained from the 1989 Engineering Report " Lake Erie Potable Water Facilities and Intakes within 50 Miles of PNPP' (Ref. S0-11552 "E').

Fraction of Population = The ratio of the population receiving drinking water from that intake to the total population number for all drinking water intakes located within 50 miles of PNPP.

Dilution Factor = Values obtained from the Perry Environmental Report.- .

Operating License Stage, Table 5.1-10 ' Annual Average Dilution Factors for Lake -

Water Intakes within 50 Miles of PNPP' and Q&R Page 2.1-2. Lake County West . - 1~ ~~

dilution factor per interpolation. Kent County Wuter Supply dilution factor was estimated. .

The Weighted Dilution Factor = (Fraction of Population) x (Dilution Factor),

based on the population for each drinking water intake; the sum of which is to be used as the potable water total population dilution factor for radioactive -

liquid effluent releases from PNPP.

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ODCM Page: 30 Rev.: 4 Table 2.3-14 _.

Dilution Factors for the Fish Ingestion Pathway Individual Grid Locations The total population dilution factor of 77.4 is catch di ailce'and volume weighted using dilution factors at those locations. Fish harvest is '

based on Ohio Department of Natural Resources the total angler catch (1987 annual) values for Lake Erie within 50 mile of PNPP.

No. of Fraction Dist. Dilution (FracFish)x Gri'd Fish of Fish (mi) Factor (DilFactor) 617 52823 3.91E-2 29 92 3.60E+0 618 76004 5.63E-2 36 100 5.63E+0 714 102522 7.59E-2 9 52 3.96E+0 715 10743 7.95E-3 9 52 4.13E-1 716 19817 1. 47E-2 11 56 8.21E-1 717 73401 5.43E-2 24 83 4.51E+0 718 118676 8.78E-2 33 95 8.34E+0 809 0 0.00E+0 48 115 0.00E+0 810 3953 2.93E-3 39 105 3.07E-1 811 13648 1.01E-2 30 92 9.29E-1 812 33923 2.51E-2 22 78 1.96E+0 813 182663 1.35E-1 13 61 8.25E+0 814 164369 1.22E-1 4 34 4.14E+0 909 80753 5.98E-2 50 116 6.93E+0 '

910 43800 3.24E-2 42 110 3.57E+0 911 117430 8.69E-2 33 95 8.26E+0 912 256529 1.90E-1 24 83 1.58E+1 TOTAL 1351054 1.00E+0 TOTAL D.F. 7.74E+1 Grid No. and No. of Fish = Total angler catch (1987 annual) for each grid location; per letter from Michael R. Rawson, Fairport Fisheries Research Station, Ohio Department of Natural Resources to Richard Cochnar (6/20/88). Comercial harvest data were not used as they were differentiated by harbor location only, not by geographical grid -

location. .< r l

'_= \

Fraction of Fish = The ratio of the fish caught in that grid to the total l number of fish caught in all grids located within 50 miles of PNPP. y l Distance = Distance to the center of that grid from PNPP, in miles.

i Dilution Factor = D .'ved, for the appropriate distance (center of each grid), from annual average dilution factor data (non-adjusted), per Perry t Environmental Report - Operating License Stage, Table 5.1-10 " Annual Average Dilution Factors for Lake Water Intakes within 50 Miles of PNPP.* l 1

(Fraction of Fish) x (Dilution Factor) = The weighted dilution factor, I based on catch, for each grid; the sum of which is to be used as the fish i ingestion total population dilution factor for radioactive liquid l effluent releases from PNPP.

~

ODCM Page: 31 Rev.: 4 Table 2.3-15 Dilution Factors for the Shore Exposure Pathway MAXIMUM EXPOSED INDIVIDUAL DILUTION FAC10R The point of exposure assumed for this pathway is the shoreline at the ,

PNPP site boundary 0.7 miles down shore from the plant discharge ,

i structure. Interpolation of the data presented in the Perry i Environmental Report - Operating License Stage, Table 5.1-10, ' Annual Average Dilution Factors for Lake Water Intakes within 50 Miles of PNPP' yields a maximum individual dose dilution factor of 14.5 (dilution factor unadjusted for current frequency).

i TOTAL POPULATION DILUTION FACTOR ^

The total population dilution factor of 162 is that of the Headlands i Beach State Park, 7.7 miles WSW of PNPP (interpolated, adjusted WSW '

dilution factor) . This location was selected because of its lake site location and it has, by far, the highest attendance of any park located in vicinity of PNPP (Perry Environmental Report - Operating License State, Table 2.1-2 " Major Camps and Parks within 10 Miles of the PNPP").

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Page: 32 ,

Rev.: 4 .

l 3.0 GASEOUS EFFLUENTS _-

Weie are four environmental release points for gaseous effluents ,

used for Unit 1 operation of the Perry Nuclear Power Plant: Heater j Bay / Turbine Building Vent, Offgas Vent Pipe, Unit {:M t,*:and Unit 2 l i

. Vents (see Figure 3.0-1). W e Unit 1 and Unit 2 Vents are located. l on the top of the Intermediate Building, Elevation 753'9". The i Heater Bay / Turbine Building Vent is located on the top of the Heater ..

Bay Building, Elevation 722'0'. The Offgas Vent Pipe is located on. !

the top of the Offgas Building, Elevation 723'0". Site ground level l i

elevation is 620'0". Radiological releases from each vent are :

' monitored by a noble gas radiation monitor. ,

All gaseous effluent releases from PNPP will be continuous releases.

Containment /drywell purges and vents will be considered periods of ,

increased radiological release as they are vented through.the Unit 1 l i

Vent concurrent with normal, continuous releases. All releases are considered to be long-term, i.e., greater than 500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months per year,- i and ground level.

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ODCM Page: 34 Rev.: 4 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 10CFR20 dose rate limits to areas at a beyond the .

site boundary for the following noble gas monitorsi " -

1. Heater Bay / Turbine Building Vent radiation monitor (1D17K0856)

2. Offgas Vent Pipe radiation monitor (1D17K0836)

3. Unit i Vent radiation monitor (1D17K0786)

4. Unit 2 Vent radiation monitor (2D17K0786).

The Unit 2 Vent Radiation Monitor is included for the operation of Unit 1 of the Perry Nuclear Power Plant because the second train of the Unit 1 Annulus Exhaust and the Control Complex and Intermediate Building ventilations are exhausted through the Unit 2 Vent.

The High Alarm Setpoint (HSP) for each release point radiation monitor will be set at 70 percent of the 10CFR20 dose rate limits and the Alert Setpoint (ASP) will 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-nuclides in gaseous effluent released from the site exceeds 500 mrem / year to the total body or 3000 mrem / year to the skin.

NOTE: The values of 70 percent for the HSP and 10 percent for the ASP are set as fractions of the total activity that may be released via the monitored pathways to ensure that the site boundary dose rate limits are not exceeded. Any single ASP can be exceeded without the 10CFR20 limits being exceeded. Upon receipt of an alert alarm a sample from the alarming effluent path will be obtaine) and.

analyzed. If two or more monitors exceed the ASP, or any - ;

one monitor exceeds the HSP, it is possible that the .s 7' limits have been exceeded. In this case all four effluent ;

paths will be sampled and analyzed. Appropriate action will be taken to limit gaseous releases to below 10CFR20 y limits. :

NOTE: If an HSP or two or more ASP's continue to be exceeded, ,

verification shall be made at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months via '

the gaseous effluent radiation monitors that plant releases are below Technical Specification 3.11.2.1 dose rate limits, and sampling and analysis shall be performed on the four gaseous effluent release points at least once -

per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . -

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ODCM Page: 35 Rev.: 4 3.1.1 Determination of the " Mix" (Noble Gas Radionuclide Composition) _.

of the Gaseous Effluent

a. The gaseous source terms that are representative of the '

" mix' of the gaseous effluent are determined. Gaseous source terms are the concentrations of tlie n6ble gas -

radionuclides in the effluent as determined by analysis of the various sources of gaseous effluents. During the early period of plant operation, before a sufficient operational effluent source term data base has been obtained, source terms will 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 in the gaseous effluent for each noble gas radionuclide in

~

the gaseous effluent.

A S. =

I (3.1-1) 1

? A; 1

Where:

S.1 = the fraction of the total for radionuclide 'i' in the effluent; A.1 = the activity of radionuclide 'i' in the gaseous effluent.

NOTE: If the activity of a noble gas radionuclide is below the lower limit of detection the noble gas radionuclide is not included as a source term in this setpoint calculation.

3.1.2 Determination of the Maximum Acceptable Total Activil;y Release.

Rate of Noble Gas Radionuclides in Gaseous Effluent Based on -

Total Body Dose Rate Limit .e T 1~

500 (3.1-2)

Qb = (x/Q) 1{ (Kg )(Sg) y Where:

Ob = the maximum acceptable total activity release rate of all noble gas. radionuclides in the effluent (for total body exposure), in pCi/s; K.

1

= the total body dose factor for a semi-infinite cloud -

ofragionuclide'i'(includestheattenuationof Sg/cm of tissue from Table 3.1-1, in (mrem /yr)/(pCi/m));

ODCM Page: 36 Rev.: 4 S. = the fraction of the total for radionuclide 'i', as .

1 per equation 3.1.1; ~

x/Q = the highest annual average relative dispersion facgor fgr areas at the site boundary-= 5.8 x 10 - s/m (from Appendix A, NE direction at the site -

boundary); .

NOTE: The dispersion parameters (x/Q) used in these calculations are the highest calculated site boundary values for any of the land-based

' sectors only. At PNPP the site boundary locations in the following sectors are totally over water: N, NNE, NNW, NW, W, WNW.

500 = the total body dose rate limit, in mrem /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)

Os

I%IOI 1* Ibi + 1'11 Hi l I31 I Where:

08 = the maximum acceptable total activity release rate of all noble gas radionuclides in the effluent (for skin exposure), in pCi/s; L.1 = the beta skin dose factor for a semi-infinite cloud of radionuclide 'i' (includes attenuation by the outer ' dead' layer of skin), in (mrem /yr)/(pCi/m3 ),

My = the gamma air dose factor for a uniform semi-infinitec1gudofradionuclide'i',in (mrad /yr)/(pCi/m ),

.g S. = the fraction of the total for radionuclide 'i', per ;-

1 equation 3.1.1;

P..

x/Q =thehighestannua1averggerelativedispersion 6

factor = 5.8 x 10 s/m , per equation 3.1-2 1.11 = the air dose to tissue dose equivalent conversion factor, in mrem / mrad; 3000 = the skin dose rate limit, in mrem /yr.

(L; + 1.11 Mi ) values are shown in Table 3.1-1.

. . . . . - - . . - ~ . .

- ODCM Page: 37 Rev.. 4 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)(0t)

C = " - ' (3 ~.1-4 ) --

f .

Where:

Ct = the maximum acceptable

- concentration of all nobletotal gasradioactivity radionuclides in the effluent, in pCi/cc; f = the flow rate for the release point fgom the respective flow rate recorders, in ft / min; NOTE: ' Design flow rate may be used in lieu of actual flow rate. These design flow rate values incorporate a 10% flow rate inaccuracy correction.

Release Path ' Flow Rate (cfs) ,

, J

- Heater Bay / Turbine Building Vent 400,000 (summer) 220,000 (winter) ,

- Offgas Vent Pipe 19,000

- Unit i Vent 140,000

- Unit 2 Vent 47,000 O 3 and 0 , calculated in equations 3.1-2 g = the smaller of 0and 3.1-3, respectively,, in pCi/s; 2.12 x 10~3 = th conversion factor to convert (pci/s) ~

ft / min) to pCi/cc. -

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3.1.5 Determination of the Maximum Acceptable Monitor Count Rate ~.-

Above Background Attributed to Noble Gas Radionuclides CR c = (0.8) (Ct)

(Em) (3.1-5)

Where:

CR = the calculated monitor count rate above background c attributed to noble gas radionuclides, in cpm; l

e rt - -

w -- -w- - ~ * - - - -+= = --

I ODCM Page: 38 ;

Rev.: 4 -

i I

C = the maximum acceptable radioactivity concentration, _.

t per equation 3.1-4, in pCi/cc; -

s E, = of the detector efficiency of the monitor for the ' mix' , l noble gas radionuclides in the "" effluent, in .

cpe/(pCi/cc);

- 'i

= the total pCi/cc concentration divided into the net '

i monitor count rate taken at the time the sample was i

taken; during the early period of operation, before !

a sufficient operational effluent source term data !

i ' base has been obtained, the value will be calculated j i using n.onitor calibration data; i 0.8 = an engineering safety factor. j

, 3.1.5.1 Determination of the Monitor High Alarm Setpoint HSP = (0.70)(CRc I + (*

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 cpm; CR = the calculated monitor net count rate, per c equation 3.1-5, in cpm; ;

0.70 = 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 3.1.5.2 Determination of the Monitor Alert Setpoint . $ _.

- " (3.1-7)

ASP = (0.10)(CR g )+M l

~

j Where:

ASP = the alert setp W t (including background), in !

I cpm; BG = the background count rate due to internal contamination and radiation levels in the area in which the monitor is installed when the -

i monitor chamber is filled with uncontaminated i air,Incpm; l

- .. . . . . _ . .~ . . - - .- - -.. -_

~ ,

I

~

ODCM !'

Page: 39 Rev.:

4 CR = the calculated nonitor net count rate, per -. >

c equation 3.1-5, in cpm; j 0.10 = the fraction of the maximum acceptable !

activity that may be released ttpn the vent to -

ensure that the site boundary dose rate limits ~

are not exceeded during concurrent releases ' l from several pathways. .

J e

\'

L h

i

g 7"' I

. e e.6 i

[

l 5

b l

' ODCM '

Page: 40 i

Rev.: 4 Table 3.1-1 .-

' Total Body and Skin Dose Factors 4

'Ibtal Body Total Skin _Dgg Factor -~

Dose Factor (L 1.11 M >

Radionuclide (Kg )(arem/yr/pci/m ) (mrek+/yr/pcifm)3) _

i Kr-83m' 7.56E-02 ' 2.14E+01 Kr-85m 1.17E+03 2.82E+03 1.36E+03 Kr-85 1.61E+01 .

1.66E+04 Kr-87 5.92E+03 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 !

Xe-133 2.94E+02 6.97E+02 ,

Xe-135m 3.12E+03 4.44E+03 Xe-135 1.81E+03 3.99E+03 Xe-137 1.42E+03 1.39E+04 '

Xe-138 8.83E+03 1.44E+04 Ar-41 8.84E+03 1.30E+04 ,

i i

e I

=r. s.

t A

=

i

ODCM Page: 41 Rev.: 4 3.2 Compliance With 10CFR20 - Usseous Effluent Dose Rate .

~

Dose rates resulting from tha release of noble gases, radioiodines, tritium, and radionuclides it. particulate form must be calculated to show compliance with 10CFR20. The limits of 10CFR20 ace-~

conservatively applied for the release period at the-controlling -

location.

l 3.2.1 Noble Gases The dose rate in unrestricted areas resulting from noble gas effluents is limited, by PNPP Technical Specifications, to 500 mrem /yr to the total body and 3000 mrem /yr to the skin.

Only the external dose pathway will 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 (I/Q). (See Appendix A for elaboration on atmospheric dispersion.)

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 nore alert alarms occur, the dose rates in unrestricted areas resulting from the release of noble gas radionuclides from all vents will be calculated. The calculations will 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 rate from these radio-nuclides will be performed based on results of analyses -

obtained pursuant to those Technical Specifications. The .- 7 centro 11ing location for this limit is the location of the ;-

highest relative depositio~n (D/Q) for the period of release as well as the actual receptor pathway. The receptor pathway ...

locations will 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.

'fl ODCM Page: 42 Rev.: 4 -

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 gaseous ,

for the l effluents purpose of showing compliance with PNPP Technicil Specification to areas at or beyond the site bmandasy* --

i as related to 10CFR20.

1 (3.2-1)

D,$p = (3.15 x 10 ) (x/Q or D/Q) I (DF,ggp) (Qg).

Where: .

D,3p

. = the organ "j' dose r te as a function of age group 'a' and pathway 'p",-in area /yr; l DF,g3p =.a',

the dose factor for organ type "j', age group pathway 'p' for isotope 'i' (see ;

Tables 3.2-1 through 3.2-3); units and equations i used (equations 3.2-2 thrcagh 3.2-6) are provided !

later in this section; ;

x/QorD/0=thenormalordepletprelativedispersion factor (x/Q)2 in s/n , or relative deposition !

(D/Q), in m , at the receptor distance (see j Appendix A); {

3.15 x 101 = the conversion factor to convert (arem

pCi)/(Ci

s) to ares /yr-I the release rate of isotope 'i', (annualized) in i Qg = pCi/s {

= (472)(Cg )(f)

Where: {

Cg = the concentration of radionuclile 'i' in . . I l '

the gaseous effluent, in pCi/cc*

f =thegaseousefjluentflowrateduringthe '(- i release, in ft / min; ' !

3 '

472 = the conversion factor (cc/ft )/(s/ min).

f The following relationships are used to derive the dose factors I (DF .. for noble gases, tritium, radioiodines and !

parflM)atesusedinequation3.2-1.

l l t

I

?

h i

ODCM Page: 43 ,

Rev.: 4 )

a. Total Body Dose Factors from Exposure to a Semi-Infinite .

Plume T

DFg = (Sp ) (xg) (DFB;) ; -- ; (3.2-2) _

Where: . .,

T DF. = the total body factor due to immersion in a ;

1 semi-infigitecloudofradionuclide'i',in ,

(mrem

m )/(Ci

s);

DFB. = the total body gamma dose factor for a '

1 semi-infinitecloudofradionuclige'i'which includes the attenuation of Sg/cm of fromTable3.2-4,inmrem/yrperpCi/m} issue ;

S F

= 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 (Regulatory Guide 1.109);

zg =theannualaverageconcentratignof radionuclide 'i' in air (pci/m ), for a ynit a L releasg) rate (Ci/yr)3)nd a unit x/Q (s/m ), in (pci/m /(Ci/yr)(s/m . :

b. Skin Dose Factors for Exposure to a Semi-Infinite Plume S y DF (S,) (DF ) +

(DFS g

)]g =. (x;) [(1.11) (3.2-3)g Where: ..

S .s c ~

DF.

l

= the skin dose factor due to immersion in a .

semi-infigitecloudofradionuclide'i',in (mrem

m )/(Ci

s); ,_

7 DF. = the gamma air dose factor for a uniform I

semi-infinitecloudofradionuclige'i',from Table 3.2-4, in mrad /yr per pCi/m ;

DFS. 1

= the beta skin dose factor for a semi-infinite cloud of radionuclide "i" (includes attenuation by the outer ' dead' layer of skin), from Table 3.2-4 in arem/yr per pCi/m3 , ;

i i

ODCM !

Page: 44 l Rev.: 4 l

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- l dose = 0.5 (Regulatory Guide 1.109); .

. i

%.1 = the annual average concentrati9 n of !

radionuclide'i'inair(pci/m),foraynit :

a 1

releasg) rate (Ci/yr)3)nd (pCi/m /(Ci/yr) (s/m ; a unit %/Q (s/m ), in 1.11 = the air dose to tissue dose equivalent <

conversion factor, in arem/arad. ;

~

I

c. Dose Factors from External Irradiation from Radionuclides i Deposited onto the Ground Surface G G DFig = (8760) (Cg) (DFGgg) (Sp) (3.2-4)

Where: <

l G

DF.. = the dose factor for radionuclide 'i' to organ 13 'j' resulting from exposure to radionuclides s deposited2 onto the ground surface, in ;

(mrem

a )/Ci; i

G !

= the ground plane concentration (pci/m2 ) og C*.

radionuclide 'i' for a unit release rate (Ci/yr) and a itD/Q,relgtiveground ;

deposition (m~p), in (pCi/m )/(Ci/yr)(m'2);

DFG g3

. = the open field ground plane dose conversion , .

factor.for organ "j" from radionuclide2 'I ~~

?

from Table 3.2-5, in arem/yr per pCi/m ; - ;{ l S

F

= the attenuation factor that accounts for the i dose reduction due to the shielding provided 7*

l by residential structures, optional, -

dimensionless: maximum exposed individual = ,

0.7, population dose = 0.5 (Regulatory Guide 1.109);-

8760 = the number.of hours in a year. J

d. Dose Factors from Inhalation of Radionuclides in Air .

A DFaij = (DFAaij II a} IIi

l,

ODCM Page: 45 Rev.: 4 Where:

A DF . . = the dose factor for radionuclide 'i' to ~

a13 organ aj' ofanindividual4n.agegroup'a' due to inhalation, in (mre'm T.m )/(Ci

s) -

[ -- equivalent to (mrem /yr)(yr/Ci)(m3/s)];

DFA .. = the inhalation dose factor for radionuclide al] "i", organ "j", and age group "a" (the value for skin is assumed to be 0), from Tables 3.2-6 through 3.2-9, in mrem /pci; R

= age the group annual'a',

air from intake for individuals 3.2-14, in m#n a

Table /yr; x.1 =theannualaverageconcentratignof radionuclide 'i' in air (pci/m ), for a unitrelgaserate(Cifyr)andaunig).

r/0 (s/m ), in (pCi/m )/(Ci/yr)(s/m

e. Dose Factors from the Ingestion of Atmospherically Released Radionuclides in Food D F F L L M M DFaij = DFIaij [(U,) (Cg ) + (Ug) (f L) (Cg ) + (U,) (Cg ) +

V V (U,)(fy)(Cg )] (3.2-6)

Where:

D DF .. = the dose factor for radionuclide 'i' to organ a13 'j' of an individual in age group 'a' from the ingestion of meat, leafy vegetables, milk, and produce (non-leafy veg'etables, fruits, and grains) in (mrem

m )/Ci, or in -

the cases3 f H-3 and C-14 in .<C (mrem

m )/(Ci

s);

F L M V .-

C;, C;, C;, C.1= the concentrations of radionuclide i

'i' in meat, leafy vegetables, milk, and produce, respectively (pCi/kg or ,

pCi/1) for a unit release rate (Ci/yr) and a unit D/

grounddeposition(m~g, ), relative or in cases of H-3 and C-14, a unit x/Q, l relagiveground-levelconcent3ation ]

(s/m),in(pCi/kg)(gi/yr)(m- ) or (pCi/kg)/(Ci/yr)(s m ) or (pCi/1)/(Ci/yr)(m ) or (pCi/1)(yr/Ci)(s/m /); I

m -

l'

~

l ODCM Page: 46 i Rev.: 4 DFI .. = the ingestion dose factor for radionuclide a13 'i', organ "j', and age group 'a', from Tables 3.2-10 through 3.2-13, in mrem /pci;

~

f,fy g = theratesrespective fractions of the ingestion of leafy vegetables ahd 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, a a leafy vegetables, milk, and produce ;

respectively, for individuals in age group *a", from Table 3.2-14, in kg/yr or 1/yr. .

f. Dose rate example problem:

1) For the purpose of this sample problem, the following assumptions are utilized: a release 3of Xe133 at 1.0E-5uci/cc, a flow rate of 1.0E5ft / min, and a 3 i

~

total body dose factor of 2.94E-4 mrem /yr per pCi/m .

A dose rate and 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months cumulative dose are calculated. ,

2) Total Body Dose Factor Dose factor per ODCM '

equation 3.2-2. '

l 2.94E-4 mrem x (.7) x 1.0E-12 pCi = 6.52 mrem m3 j yr m2 Ci sec -

pCi Ci 3.15E7sec m) yr m2

3) Dose Rate per ODCM equation 3.2-1.

3.15El x 5.8E-6s x 6.52 mrem m2 x 472cc min,x --> , !'

m2 Ci sec ft2 see --> -

1.0E-SuCi x 1E5ft3 = 0.562mren .

-f cc min yr -

(1hr) x 0.562 mrem x lyr = 6.42E-Smrem

yr 8760hr i

l

'" ODCM Page: 47 i Rev.: 4 l

Table 3.2-1 _. .

Organ Used for Gaseous Effluent Dose Calculations

1. Bone ; _.,- - ,

2. GI Tract' .

3. Kidney

4. Liver

5. Lung

6. Thyroid ,

7. Total Body

8. Skin $

Table 3.2-2 ,

Ace Groups Used for Gaseous Effluent Dose Calculations ,

1. Adult (17 yr and c' der)

2. Teen (11-17 yr)

3. Child (1-11 yr)

4. Infant (0-1 yr) e e

. e_-

i

. I

~

ODCM '

Page: 48 Rev.: 4 i Table 3.2-3 ,-

Gaseous Effluent Dose Pathways

1. Plume . _'. , ,

2. Ground Shine .

3. Vegetables ,

4. Meat

5. Cow Milk

6. Goat Milk ,

7. Inhalation Table 3.2-4 !

Dose Factors for W sure to a Semi-Infinite Cloud of Noble Gases Total Body Beta Skin Canna Air" Nuclide Gamma Dose Dose Factor Dose Factor Factor (DFB], (DFSp ) y g

(DFy )

7.56E-08 --- 1.93E-05 Kr-83m 1.23E-03 Kr-85m 1.17E-03 1.46E-03 1.61E-05 1.34E-03 1.72E-05 .,

Kr-85 6.17E-03 l Kr-87 5.92E-03 9.73E-03 1.47E-02 2.37E-03 1.52E-02 Kr-88 1.73E-02 Kr-89 1.66E-02 1.01E-02 1.56E-02 7.29E-03 1.'63E-02 Kr-90 ~1.56E-04

- t Xe-131m 9.15E-05 4.76E-04 9.94E-04 3.27E-04 - 'f l Xe-133m 2.51E-04 '

2.94E-04 3.06E-04 3.53E-04 >

Xe-133 3.12E-03 7.11E-04 3.36E-03 Xe-135m :--

1.81E-03 1.86E-03 1.92E-03 Xe-135 1.51E-03 Xe-137 1.42E-03 1.22E-02 ,

8.83E-03 4.13E-03 9.21E-03 i Xe-138 8.84E-03 2.69E-03 9.30E-03 l Ar-41

mrem /yr per pCi/

- mrad /yr per pCi/m

7 ODCM Page: 49 Rev.: 4 ,

Table 3.2-5 ,

External Dose Factors for Standing on Contaminated .

Ground 2 , _ _ , n (mrem /h per pCi/m ) _, .

Total Sedy $81n ,

g ,

0.0 0.0 :

M3 0.0 0.0 l C-14 2.50E-08 2.90E-08

,. nA 24 0.0 0.0 P 32 2.60E-10 Cr 51 2.20E 10 5.80E-09 6.80E-09 -

Mn 54 1.30E-08 Mn.56 1.10E-08 0.0 0.0 Fe.55 9.40E-09 8.00E-09 Fe 59 8.20E-09

- 7.00E-09 l' Cp 58 1.70E-08 2.00E-08 Co.46 0.0 0.0 gi 43 4.30E-09 :'

3.70E-09 Mr-65 1.50E-09 1.70E-09 '

tv-64 4.00E-09 4.60E-09 Zn-65 0.0 '.

Zn-69 0.0 6.40E-11 9.30E-11 Or-83 1.40E-08 Br-84 1.20E-08 i 0.0 0.0 i Br-85 7.20E-10 Rb-86 6.30E-10 :

3.50E-09 4.00E-09 ;

Rb-88 1.80E-08 Ab-89 1.50E-08 ,

5.60E 13 6.50E-13

$r 89 [

7.10E-09 8.30E-09 '

Sr-91 1.buE-08 Sr-92 . 9.00E-09 2.20E 12 2.60E 12 f 90 4.40E-09 T 91M 3.80E-Of 2.40E-11 2.70E-11 Y 91 1.90E-09 T 92 1.60E-09 '

5.70E 10 7.80E-10 Y-93 5.80E-09 Zr-95 5.00E-09 5.50E-09 6.40E-09 Zr-97 6.00E-09 Nb-95 5.10E-09 1.90E-09 2.20E-09 No-99 1.10E-09 Tc 99N 9.60E-10 2.70E 09 3.00E-09 Tc-101 4.20E-09 .

Re-103 3.60E-09 ;

4.50E-09 5.10E-09 Re-105 1.00E-09 ._'- i Re-106 1.50E-09 -

1.80E-08 2.10E-08 ;-

Ag-110N 4.80E-11 3.50E 11 Te-125N 1,30E-12 Te-12FM 1.10E-12 1.00E-11 1.10E-11 M Te-127 9.00E 10 Te-129N 7.70E-10 7.10E-10 8.40E-10 '

Te 129 9.90E-09 8.40E 09 fe-131M 2.60E-06 2.20E-09 Te.131 2.00E-09 1.7DE 09 Te-132

{

l

~

ODCM Page: 50 Rev.: 4 Table 3.2-5 (Cont.) .._

External Dose Factors for Standing on Contaminated Ground (mrem /h per pCi/m ) -+ -.-

- Element Total Body skin , ,

3-130 1.4K-08 1.y0E-08 l I-13I 2.8M-09 3.40E-09 4 3*132 1.70E-08 2.00E-08 I-133 3.70E-09 4.50E-09 3-134 1.60E.08 1.30E-08 I-135 1.20E-08 1.40E-08 I Cs-134 1.20E 08 1.40E 08 }

l. Cs-136 1.50E-08 1.70E-08 I Cs-137

4.20E-09 4.90E-09 )

Cs.138 2.10E-08 2.40E-08 .

84 139 2.40E-09 2.7M-09 '

54 140 2.1M.09 2.4M.09 '

8a-141 4.30E-09 4.90E 09 Ba.142 7.90E-09 9.00E-09 La-140 1.50E-08 1.70E-08 i i La 142 1.5M.08 1.8M-08 Ce-141 5.50E-10 6.20E.10 Ce 143 2.20E.09 2.50E 09 i j

Ce-144 3.20E-10 3.7M-10 l l

Pr-143 0.0 0.0 !

Pr-144 J.00E-10 2.30E-10 j 814-147 1.00E.09 1.2M-09 1 V-187 l 3.10E-09 3.60E-09 llP-239 5 *0E-10 1.1M-09 f l i

1- '.,

y a -

i I

- I l

l l

1 l

ODCM Page: 51 Rev.: 4 ,

Table 3.2-6 - .

t Inhalation Dose Factors for Adult (mrem /DCi inhaled) ,

NUCLIOE SONE Livf a T.A0pf THYaclO EIONEY - tWWWd Gl=LLI .

H 3 NO DATA 1 58E-07 1.58F-0 7 1.58E-07 1 58E-07 1.58E-0T 1.58E-07 C 14 2.27E-06 4.26E-07 .A.26E-0T 4.26E-07 4 26E-07 4 26E-07 4.2 6E-07 .i **

1 28E-04 1.28E-06 1.2 8E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 MA 24 )

1 65E-04 9.64E-06 6 26E-06 NO DATA NO DATA NO DATA 1.08E-05 P 32 CR 51 NO DATA NO DATA 1 25E-08 7.44E-09 2.85E-09 .1 80E-06 4.15E-07 WM 54 NO DATA 4.95E-06 F.8 FE-0 F NO DATA 1.23E-06 1.75E-04 9.67E-06 .

MN 56 NO DATA 1.55E-10 2.29E-11 10 DATA 1 63E-10 1.18E-04 2.53E-06 '

FE 55 3 07E-06 2.82E-06 4.9)E-0 7 NU OATA NO DATA 9.01E-06 7.54E-07 FE 59 1 47E-06 1.47E-on 1 32 E-06 NO DATA NO DATA 1 27E-04 2.35E-05 !

CD 58 40 DATA 1.98E-07 2.59E-07 NO DATA NO DATA 1 16E-04 1.33E-05 i CD 60 NO DATA 1.44E-06 1. 85E-0 6 NO DATA NO DATA 7.46E-04 1.56E-05 i N1 63 5.40E-05 3.9 3E-06 1 81E-06 NO DATA NO DATA 2.23E-05 1.67E-06

{

g3 65 1.92E-10 2.62E-11 1 14E-11 NO DATA NO DATA 7.00E-07 1.54E.06 ,

CU 64 NO DATA 1.83E-10 7.69E-11 NO DATA 5 78E-10 8.48E-07 6.12E-06 2N 65 4.05E-06 1.29E-05 5.82 E-06 No DATA 8.62E-06 1.08E-04 6.68E-06 2N 69 4.23E-12 8.14E-12 5. 65E-13 NO DATA 5 27E-12 1.15E-07 2.04E-09

$R 83 NO DATA No DATA 3.01E-0 8 NO DATA NO DATA NO DATA 2.90E-08 SR 84 NO DATA NO DATA 3.91E-08 NO DATA NO DATA NO DATA 2.05E-13 i i'

8R 85 NO DATA NO DATA 1. 60E-09 NO DATA NO DATA NO DATA ~ LT E 48 86 NO DATA 1.69E-05 7. 3fE-06 NO DATA NO DATA NO DATA 2.00E-06 i RD 88 NO DATA 4.84E-08 2 41E-04 NO DATA MO DATA ko DATA 4.18E-19 ,

R8 89 ^ NO DATA 3.20E-08 2.12E -0 8 WO DATA NO DATA NO DATA 1.16E-21 , ,

sa 89 3.80E-05 NO DATA. 1. 09E-0 6 NO DATA NO DATA 1.75E-04 4.37E-05 l SR 90 1.24E-02 40 DATA 7.62 E-0 4 NO DATA NO DATA. 1.20E-03 9.02E-05 i

.. . - ~ - . .

SR 91 7.74E-09 NO DATA 3. 3 3 E-10 NO DATA NO DATA 4.56E-06 2.39E-05 54 92 8.43E-10 NO CATA 3.64E-11 NO DATA NO DATA 2 06E-06 5.38E-06 ,

Y 90 2.61E-07 NO DATA 7 01E-09 NO DATA NO DATA 2.12E-05 6.32E-05 I

~ . - .

. . . . . . . . . . . . . . . . ~ . . . . . . .

Y 91M 3.26E-11 NO DATA 1 27E-12 NO DATA NO DATA 2 40E-07 1.66E-10 4 Y 91 5.78E-05 NO DATA 1 55E-06 NO DATA NO DATA 2.13E-04 4.81E-05 i Y 92 1 29E-09 MO DATA 3 77E-11 NO DATA NO DATA 1.96E-06 9.19E-06 l

_ , , J Y 93 1 18E-08 NO DATA 3 26E-10 NO DATA NO DATA 6.06E-06 5.27E-05 -

, =s ,e 2A 95 1.34E-05 4.30E-06 2.91E-06 NO DATA 6.77E-06 2.2tE-04 1.88E-05 '

24 97 1.21E-08 2.45E-09 1 13E-09 NO DATA 3 71E-09 9.84E-06 6.54E-05 s.

. . . ~ . . - . . -

NB 95 1.76E-06 9.77E-07 5.2 6E-07 NO DATA 9.67E-07 6.31E-05 1.30E-05 MD 99 NO DATA 1.51E-08 2. 8 ?E-09 NO DATA 3.64E-08 1.14E-05 3.10E-05' ef, FC 99m 1 29E-13 3.64E-13 4.63E-12 NO DATA 5.52E-12 9.55E-08 5.20E-07 -

h 1

i l

l l

l

ODCM Page: 52 Rev.: 4 Table 3.2-6 (Cont.) .

Inhalation Dose Factors for Adult (mrem /pci inhaled)

NUCLIDE SONE liver T.s00f -

THYA0!D E10NEY . 138%$ St-LLI TC101 5.22E-15 7.52E-15 7.38E-14 NO DATA 1.35E=ll 4.99E-08 f.36E-21

.Aut03 1.91E-07 NO DafA 8.23E-08 NO DATA 7.29E-07 6.31t=0! 1.38E-05 '

Rut 05 9.88E-11 NO DATA 3 89E-11 NO DATA 1.77E-10 1.37E-OS 4.02E-06 ,

Rut 06 8.64E-04 NO DATA 1.01E-0 6 NO DATA 1.67E-05 1.17E-03 1.14E-04 i AC110P 1.31E-06 1.25E-06 7.4 AC-0 7 NO DATA 2 46E-06 5.19E-04 3.78E-05 i

.fE125M 4.27E-07 1 98E-07 5 84E-05 1 3tt-07 1 55E-M 3.92E-05 8.83E-06 TE127p 1.58E-06 7.21E-07 1.96E-07 4.11E-07 5.72E-06 1.20E-04 1.87E-05 TE127 1.75E-10 8.03E-11 3 87E-11 1 32E-10 6.37E-10 8.14E-07 7.17E-06 IE129# 1 22E-06 5 84E-07 1 98E-0 7 4.30E-07 4.57E-06 1.45E-04 4.79E-05 TE129 6.22E-12 2.99E-12 1'.55E-12 4.87E-12 2.34E-11 2.42 E-07 , 1.96 E-08 TE13tn 8.74E-09 5.45E-09 3 63F-09 6.BSE-09 3.06E-08 1.82E-05 6.95E-05 J E131 1.39E-12 7.44E-13 4.49E-13 1 17E-12 5.46E-12 1.74f-07 2.30E-09 TE132 3.25E-08 2.69E-OS 2.0ZE-08 2 37E-08 1.82E-07 3.60E-05 4.37E-05 t 130 5.72E-07 1 68E-06 6.60E-07 1 42E-04 2.61E-M NO DATA 9.61E-07 1 1 131 3.15E-06 4.47E-06 2.56E-06 1 49E-03 7.HE-06 NO DATA 7.85E-07 1 45E-07 4.07E-07 1 4 bE-0 7 1 43E-05 4.48E-07 NO DATA 5.08E-00 <

J 132 1.11E-06 1 08E-06 1 85E-06 5. 65E-07 2 69E-04 3.23E-06 NO DATA l 133 1.26E.10 f I 134 0.05E-08 2 16E-07 7.69E-08 3.73E-06 3.44E-07 NO DATA 6.56E-07 3.35E-07 8.73E-07 3.21E-07 5 60E-05 1.39E-06 NO DATA t 135 '

4.HE-05 1.06E-04 9.10E-0 5 NO DATA 3.59E-05 1.22E-05 1.30E-06 I

C1134 C5136 4. 8 8E-M 1 83E-05 -. 1 38E-05 40 DATA 1 07E-05 1.50E-06 1 46E ..-..-. _ ... ._ ._

\

2.78E-05 9.40E-06 1 05E-06 i C5137 5.98E-05 7.76E-05 5.35E-0 5 NO DATA 6.00E-08 6.07E-09 2.33E-13 i C5138 4.14E-08 7.76E-08 4 0$E-08 NO DATA 7.78E-14 4.70E-07 1 12E-07 I SA139 1.17E-10 8.32E-14 3.42E-12 w.-...-._

NO DATA .. -. ... ;

2.091-09 1.59E-04 .2.73f-05 1

AA140 4.88E-06 6.13E-09 6.21E-0 7 NO DATA 8.75E-15 2.42E-07. 1 45E-17 i Aal41 1.25E-11 9.41E-15 4.20E-13 NO DATA 2.86E-15 1.49E-07 1 96E-26 i AA142 3.29E-12 3.38E-15.2. 07E-18 NO DATA

- - - - - - - - --- - - i 40 DATA 1.70E-05 5.73E-05 LA140 4.30E-CB 2 17E-08 5.73E-09 NO DAfa 40 DATA 7.91E-07 2 64E-07 L 4142 8.54E-11 3 88E-11 9.HE-12 NO DATA 2.49E-M 1.69E-M 1 9t E-07 NO DATA 7.83E-07 4.52E-05 1.50E-05 CE141 -.

7.60E-09 2.35E-04 1.72E-08 1 91E-09 NO DATA 1.06E-04 9.72E-04 1.02E-04 9.97E-06 2 83E-05 --

CE143 CE144 4.29C-04 1.79E-04 2.30E-0 5 No DATA 2.70E-07 3.51E-05 2.50E-05

7. _

pa143 1.17E-04 4.4,9E-07 5.80E-08 NG DATA . .. f.. f r.

~

PA144 3.76E-12 1.56E-12 1 91E-13 90 DATA 8.81E-13 1.27E-07 2 69E-18 N0147 6.b9E-07 7.62E-07 4.56E-08 40 DATA 4.45E-07 2.76E-05 2 16E-05 i .m NO DATA 3.63E-06 1.94E-05 { . r .-

et 187 1.ME-09 8.85E-10 3 10E-10 NO DATA :- _ . . . .

8.75E-09 4.70E-M l.49E-05 i NP239 2.97E-04 2 82E-09 1 55 E-09 NO DATA

-_,g -

ODCM Page: 53 Rev.: 4 Table 3.2-7

-Inhalation Dose Factors for Teenager (mrem /pci inhaled) 9UCL10E 80gf LIVER T.00cv TNyR010 RIONEY .; 4Uy0 GI-LLI ,

. ?

N 3 NO DATA 1. 59E-0 F 1.59E-07 1.59E-07 1 59f-07 1.59E-07 1 59E-07 C 14 3.2bE-06 6.C9E-07 6.09E-07 6.09E-07 6.f*9E-07 6.09E-07 6 09E-07 14 24 1.72E-06 f.72E-06 1.72E-06 8 72E-06 1 72E-06 1.72E-06 1.72E-06

P 32 2 36E-04 1.974-09 8.95E-06 NO DATA NC OATA NO DATA 1.16F-05 CR bl NO DATA NO DATA t.69F-08 9 37E-09 3.84E-09 2.62E-06 3.75E-07 PN 54 No DATA 4.39F-06 1.0DE-06 NO DATA 1.19E-06 2.48E-04 8.35E-06 NN 56 NO DATA 2.124-10 3.15E-11 NU OATA 2.24E-10 1.90E-06 7 18E-06 FE 55 4.18E-06 2 90E-06 6.93E-0F No DATA NO DATA 1.35E-05 7.99E-07 F E 19 1.99E-06 A.62E-06 1.79E-06 NO DATA NO DATA t.91E-04. 2.23E-05 CO SC NO DATA 2.t96-07 3.47E-07 NO DATA NO DATA 1.68E-04 1 19F-05 CO 60 NO DATA 1 8?E-06 2. 40 E -06 NO DATA NO DATA 1.09E-03 3.24E-05 NI 63 7.25E-05 '5 4)E-06 2 47E-06 NO DATA NO DATA 3.84E-05 1 77E-06 NI 6> 2.73E-10 3.e6F-11 1.59E-11 NO DATA NO DATA 1.17E-06 4.59E-06 CU 64 NO DATA 2.54E-10 1.06E-10 NO DATA S.01E-10 1.39E-06 7.68E-06 2N 65 4.82E-06 1.67E-05 7.80E-06 NO DAT A 1.08E-05 1.55E-04 5.83E-06 2N 69 6.04E-12 1 15F-11 0.07E-13 NO DATA 7.53E-12 1.98E-07 3.56E-08 .

AR 83 NO DATA NO DATA 4.30E-08 NO DATA NO DATA NO DATA LT E-24 SR 84 NO DATA NO DATA 5.41E-08 NO DATA NO DATA NO DATA LT E-24 SR 85 NO DATA NO DATA 2.29E-09 NO DATA NO DATA NO DATA LT E-24 48 86 NO DATA 2.38E-05 1. 0$ E-0 5 NO DATA NO DATA NO DATA 2.21E-06 RS 88 NO DATA 6.82E-08 3.40E-08 NO DATA NO DATA NO DATA 3.65E-15 48 89 NO DATA 4.40E-08 2.91E-08 NO DATA NO DATA NO DATA 4.22E-17 :

SR 89 5.43E-05 NO DATA 1. 56E-0 6 NO DATA NO DATA 3.02E-04 4 64E-05 '

54 9D 1*.35E-02 NO DATA 8.35E-04 NO DATA NO DATA 2.06E-03 9.56E-05 SR 91 1.10E-08 NO DATA 4.39E-10 NO DATA NO DATA 7.59E-06. 3.24E-05 SR 92 1 19E-C9 NO DATA 5.00E-11 NO DATA NO DATA 3 43E-06 1.49E-05 Y 90 3.F3E-07 NO DATA 1.00E-08 NO DATA NO DATA 3.66E-05 4.99E-05 ,

Y 9tN 4.63E-11 NO DATA 1. 77 E-12 NO DATA NO DATA 4.00E-07 3.77E-09 ,

Y 91 8.26E-05 NO DATA 2 21E-06 NO DATA NO DATA 3.67E-04 5.tlE-05 Y 92 1.84E-09 NO DATA 5.36E-18 NO DATA NO DATA 3.35E-06 2 94E-05 Y 93 1.69E-08 NO DATA 4.45E-10 NO DATA NO DATA 1.04E-05 7.24E-05 T-2A 95 1.82E-05 5.73E-04 3.94E-06, M0 DATA 8.42E-06 3.36E-04 8.86E-05 . . -; i-

~

la 97 1.72E-08 3.40E-09 1.57E-09 8 5.15E-09 1.62E-05 7.8BE-05 ~,'. -

. . .. . ... ._ ?.O DATL o

48 96 2.32E-06 1.29E-06 7.08 E-0 7 NO DATA 1.2SE-06 9.39E-05 1.21E-05 MO 99* NO DATA 2.11E-08 4 03E-09 NO DATA 5.14E-08 1.92E-c5 1.36E-05 .4 .

TC 998 1.73E-13 4.83E-13 6 24E-12 NO OAfA 7.20E-12 1.44E-07 7.66E-07

~

i .

l

ODCM Page: 54 Rev.: 4 Table 3.2-7 (Cont.)

Inhalation Dose Factors for Teenacer (mrem /pci inhaled)_

stuCL10E SONE Livf4 T.AODY _ _ .

THYA010 K10NEY TC101 ~ LU'NG . '01-LLI 4~

{ RU103 7.40E-15 2.63E-07 NO1.05E.14 DATA 1 03E-13 NO DATA .-~~~. \

1 AU105 1.40E 1 12E-0 7 NO DATA 1.90E*11 8.34E-08 1.09E-16 ,1

.. . _- 10 NO CATA 5 42E-11 9.29E-07 9.79E-05 1.36E-05 20106 ..... . ~ .. . NO DATA 1 23E-05 NO DATA 1.76

.. .... E-10 2.27E-06

.. 1 13E-05 P

1.5 5 E-06 NO DATA ..-- l, .

AC110n 1.73E-06 1.640-06 9 99E-07 NO2.38E-05 DA TA2.01E-03 1 20E-04_ /

TE125P 6.10E-07 2.80E-07 8 34E-08 3.75E-07 8.44E-04 40 DATA I

3 13E-06 3.41E-05 '

TE127 6.70E-05 9 38E-06 TE127M 2.51E-10 2 25E-06 1 14E-10 1.020-065 52E-11 2.73E-07 1.71E-10 5.48E-07 9.10E-10 8.17E 1.40E

! TE129N 1.74E-06 8.23E-07 2 81E-0 7 5.72E-07 TE129 f l'

6.49E TE131 TE131P 4.87E-12

._. _ 1.23E-08 1.97E-12 4.22E-12 2 20E-12 1 04E-12 6 30E-7.51E-09 5.03Ea09 9.06E-09 6.48E-12 3.32E-11 l 4.12E 5.49E

.. 13 1.55E-12 7.72E-12 2.92E-07 1.89E-09 TE132 4 50E-08 . ~ - - !

1 130 1.=3E-08 s .--

1 131 7.80E-07 2.24E-06 8.96E-07 2. 74 E-08 3.0?E-08 2.44E-07 5 61E-05' 5.79E-05 1.86E-04 3.44E-06 NO DATA 1 14E-06 I 132 4.43E-06 6 14E-06 3 30E-06 1.83E-03 1.05E-05 1.99E-07 5.47E-07 4 11F.-07 NO DATA 1 133 1 134 1.52E-06 2 36E-06 1.7897E-07

7. E-0 7 1.89E-05 8.65E-07 NO DATA 1.11E-07 2 90E-07 1 59E-07 3.65E-04 4.49E-06 MO DATA 1 29E-06 1 135 1. 05 E-0 7 4.94E-06 4.$8E-07 h0 DATA 2.55E-09 C5134 64.62E-07 1 18E-06 4 NO36E-07 DATA 7.76E-05 1 8.69E-07 86E-06 INO DATA C5116 28E-05 1.41E-04 6.SeE-05 C5137 6.44E-06 2.42E-05 1 71E-0 5 40 DATA4.69E-05 1.83E-05 1.22E-06 i 1.38E-05 2.22E-06 1 36E-06 i 54.38E-05 1.06E-04 3 489E-05 NO CATA C5134 SA139 82E-08 1.07E-07 67E- 5. 58 E-0 8 NO DATA 3.80E-05 1 51E-05 1.06E-06

.~~..~10 1.18E-13 4.87

.......E - 1 2 N0 DATA 8.28E-08 1 11E-13 9.84E-09 8.08E-07 3.38E-11 '

88140 .. .. .. 8.06E-07 58141 6.84E-06 8.38E-09 4. 40E-0 7 NO DATA bA142 1.F8E-11 1.s2E-14

...... . ...12 4 62E- 4.63E-15 2.84 5.9)E-13 WD DATA 2.85E-09 2.54E-04 2.86E-05

....... .E-13. ~ NO DATA 1 23E-14 4 11E-07 9.33E-14 3.

LA140 LA142 5 99E-04 2.950-08

.. - 92E-15~ . - -.5.99E-20 2 39E-07

7. 82E-0 9 40 DATA .. ~ .

t NO DATA 31 55E-06 20E-102.35.31E-11 1.32E-11 NO 04 TA CE141 2.68E-05 6.09E-05 7E-06 40 DATA

2. 71E-07 NO DATA 1 11E-06 1 27E-06 1.50E-06 '

CE143 7.67E-05~ ,1.58E-05 !;

CE144 3 32E-08 2.42E-08 2. 70E-09 NO DATA .

l Pt143 6 11E-04 2.53E-04 3 28E-05 40 DATA 1.08E-08 1.63E-05 3.19E-05 1.67E-06 6.64E-07 8 28E-08 40 DATA1.51E-04 1.67E-of 1 08E-04 . ( J.-

k ~-

PA144 3 86E-0T 6 047-05 2.67E-05 M0147

.I 1-W 187 5 37E-12 2.20E-12 2.72E-13 40 DATA 9.83E-07 1.07E-06 6.41E-08 40 DATA1 26E-12 2 19E-07 2.94E-14 1.50E-09

. ~ . .

.1 22E-09.. ... 4.29E-10 6 28E-07 4.65E-05 2 28E-05 l -

f PP23'

~

~ .., NO DATA --

NO DATA 5.92E-06 2.21 E-05 l 1~ ' '

f

.- 4.23E-08 3.99E-09 2.21 E-0 9 4D CATA .. _ i 1.25E-08 A.11E-06 1.65E-05 I

I u

I f

ODCM Page: 55 Rev.: 4 ;

Table 3.2-8 m .

c Inhalation Dose Factors for Child (mrem /DCi inhaled) i

~". i NUCLIOE D09E L!vta T.s00r THva0 0 'atDNEY Lums Ct.LL '

l

..... . . . ....... .. ~ . - ....... .. . ...- _. t H 3 NO DATA 3.04C-97 3.04E-OF 3.04f-07 3 04E-07 3.04E-07 1.04E-07 C to 9.70E-06 't.82E-06 1. 82E-06 1.82E-06 1.82E-06 1.87E-06 1 82E-06

,l -

%A 24 4.35C-06 4 35 -o6 4.3DE-06 4. 3 %E.06 4 35E-c6 4.35E-06 4 35E-06 ;

P '32 7.04E-04 1.09E-05 2.6 TC-0 5 40 DATA NO DATA Mn DATA 1 14E-05 CR 58 NO DATA NO DATA 4.17E-08 2.Atr-08 6.57E-09 4.59E-06 2 93E-07

,,MN 54 40 DATA 1.16E-05 2. 57E-06 MU DATA 2.71E-06 4.26E-04 6.19F-06 i MN $6 NO DATA 4.48E-10 8.4 3E-11 NO DAIA 4.52E-10 3.55E-06 3 33E-05 TE $5 1.28E-05 6.80E-06 2.10E-06 .40 DATA NO DATA 3.00E-05 7.75E-07 FE 59 5.59C-06 9.C4E-06 4.51E-06 40 DATA NO DATA 3.43C.04 1.91E-05 CD 58 NO DATA 4.F9E.07 8. 55E-0 7 NO DATA NO DATA 2.99E-04 9.29E-06 CO 60 NO DATA 3.55E-06 ' 6.12E-06 40 DATA NO DATA 1.91E-03 2.60E-05 NI 63 2.22E-04 1.)SE-05 7. 56E-06 NO DATA NO DATA 7.43E-05 1.71E-06

.... _ ., . . ~ .- -. -.. .. - . -... .. .

NI 45 8.08E-10 7.99E-11 4.44E-11 40 DATA NU DATA 2.21E-06 2.27E-05 CU 64 NO DATA 5.39E-10 2.90C-10 NO DATA 1.63E-09 2.59E-06 9.92E-06 ZN 45 1.15E-05 3. 06E-05 . 1.90E-0 5 NO DATA 1.93E-05 2.69E-04 4.4tE-06 r 2N 69 1.81E-11 2.61E-11 2.410-12 NO DATA 1.58E-11 3.84E-07 2.75E-06 '

MR 83 NO DATA NO DATA 1.28E-07 NO DATA l NO DATA Mb OATA LT E-24 i DR 84 NO DATA NU OATA 1.48E-07 No DATA NO DATA NO DATA LT E-24 '

SR 85 NO DATA NO DATA 6. 84E-09 No DATA NO DATA NO DATA LT E.24 RD 86 NO DATA 5.36C-05 3.09E-06 NO DATA NO DATA NO DATA 2 16E-06 '

At 88 NO DATA 1.52E-OF 9.90E-08 NO DATA 40 DATA Nb OATA 4.66E-09 '

i R8 89' NO DATA 9.33!-08 7.8)E NO DATA NO DATA NO DATA 5.11E-10 i SR 89 1.62 E-04 No CATA 4. 66 E-06 NO DATA NO DATA 5.81E-04 4 52E-05 I '

SR 90 2.73E-02 NO. DATA 1. 74 E-0 3 NO DATA NO DATA 3.99C-03 9 28E-05

+

SR 91 3.28E-08 40 CATA 1.24E-09 NO DATA NO DATA 1.44E-05 4.70E-05 54 92 3.54E-09 NO DATA 1.42 E-10 NO DATA NO DATA 6.49C-06 6 55E-05 Y 90 1 11E-06 NO DATA 2.99E-08 NO DATA NO DATA 7.07E-05 7.24E-05 ;

...... ... ...... ..- .. .-......... - .-.-....... 2 Y 91P 1.37E-10 NO DATA 4.98E-12 NO DATA NO DATA 7.60F-07 4.64E-07 !

Y 91 2 47E-04 40 DATA 6 59E-06 NO DATA NO DATA 7.10E-04 4.97E-05 I Y 92 5.50E-09 40 DATA 1 57E-10 NO DATA NO DATA 4.46E-os'.~ 6.46E-05 L '

.. ... _.a. .

c.. i Y 91 5.04E-08 40 DATA 1. 38E-09 NO DATA' NO DATA 2.etE-05 1.05E-04 L,7 j; ZA 95 5.13E-05 1.13E-05 1 00E-05 NO DATA 1.61d-05 6.03E-04 1.65C-05 -' -

}

IR 97 5.07C-08 7.A4E-09 4 32E-09 NO DATA 1.05E-08 3.06E-05 9.49E-05 ';- 4 48 96 6. 3 5E-06 2.48E-06 1.77E-06 NO DATA 2.33E-06 1.66E.04 1.00E-05 - i NO 99 N0 OATA 4.66E-04 1.1SE-08 WO caft t.06E-07 3.66E-05 1.42E-05 7< '

TC 997 4.81E-13 9.41t-13 1.56E-11 NO DATA 1.37E-11 2.57E.07 1.30E-06 ;

l l

--r-

_ . . _ . _ __ _ _ ._ _ _ _ . ~ . . - _ _ ~_ -

l ODCM Page:

56 Rev.: 4 l

Table 3.2-8 (Cont.) .

Inhalation Dose Factors for Child (mrem /pci inhaled)

~~

NUCLIOE ODmE L IVE R t. 600f THYA010 E10NEY LUNG ' GI-LLI

.1, ,

TC101 2.19E- t e. 2.30E-14 2 91E-13 NO DATA 3.92E-13 t.b8E-07 4.'41E-09 i :

AUt03 7.55E-07 NO DATA 2.90E-0 7 N0 DATA t.90E-06 1.79E-04 1.21E-05 *i .

AU105 4.83E-10 NU OATA 1.bOE-10 mn DATA 3.63E-10 4.30E-06 2.69E-05 t +

R0106 3 68E-0) NO DATA 4.5FE-06 NO DATA 4.9FE-05 3.87E-03 1.16E-04 i

. ACitor 4.56E-06 3.08E-De 2.47E-06 NO DATA 5.74L-06 1.48E-03 2.71E-05 TEt259 1.82E-06 6.29E-07 2.47E-0 7 5.205-07 NG DATA .. 1.29E-04 9 13E-06 ...

TE127M 6.72E-06 2.3tE-Oo 8. lee-07 1 64E-06 1.72E-05 4.00E-04 1.93E-05 i 7.49E-10 2.57E-10 1 65E-10 5.30E-10 1.91E-09 2.71E-06 1.52E-05 TE127 IEt23F 5.19E-C6 1.8bE-06 8.22 E -0 7 L.7tE-06 1.16E 4.'F6E-04--. 4.91E-05 l

.............. ... . ... . .. .. , .. p TE129 2.64E-11 9.45E-12 6.44E-12 1.93E-11 6.94E-11 7.9tE-07 6.89E-06 1 TE13tr 3.63E-08 1.60E-08 1. 3 7 E-0 5 2.64E-08 1.08E-07 5.5&E-05 8.32E-65 TE131 5.87E-12 2 20E-12 1.76E-12 4.59E-12 1.59E-11 5.55E-07 3.60E-07 , j g j TE132 1.30E-07 7.36E-08 7 12E-08 8.58E-08 4.79E-07 1.02E-04 3 72E-05 1 1 130 2.21E-06 4.43!-06 2.28 E-0 6 4.99E-04 6.61E-06 NO DATA 1 30E-06 i I 131 1.30E-05 1.30E-05 7. 37E-0 6 4.39E-03 2.13E-05 NO DATA 7.68E-07 ;

I 132 5.72E-07 1.10E-06 5.0 iE-0 7 5.23E-05 1 69E-06 NO DATA. 8.65E-07 i I 133 4.48E-06 5.49E-06 2. 00 E-0 6 1 04E-03 9.13E-06 NO DATA 1.48E-06 !

I 134 3.17E-07 5.84E-07 26 2.58E-07 I i

..-. --. . ... .. .?.E ...-0 7 1.37E-05 8.92E-07

_ .. _ NO DATA _. )'

I 135 1 33E-06 2.86E-06 1.12E-06 2.14E-04 3.62E-06 NO DATA 1 20E-04 .

C5134 1.76E-04 2.74E-04 6.0 7 E-0 5 90 DATA 8.93E-05 3.27E-05 1 04E-06 C5136 1.76E-05 4.62E-0) 3.14E-0 5 NO DATA. 2.58E-05 3.93E-06 1.43E-06 ,

C5137 2.45E-04 2.23E-04 3.47E-05 NO DATA 7.63E-05 2.81E-05 9.78E-07 i ;

C5138 1 7tE-07 2.2FE-07 1. 50E-0 7 NO DATA 1.68E-07 1.84E-05 7.29E-08 4 A4139 4.98E-10 2.66F-13 1.45E-11 NO DATA. 2.33E-13 1 56E-06 1.56E-05 [

OA140 2.00E-06 1.75E-08 1. l FE-0 6 - NO D AT A 5.71E-09 .4.71E-04' 2.75E-05 sat 41 5.29E-11 2 95E-14 1.72E-12 NO DATA 2.56E-14 7.89E-07 7.44E-08 -

84142 1 35E-11 9.73E-15 7.b4E-13. .NO DATA 7.87E-15 4.44E-07 7.41E-10 .-

. . . _ . . . - . . . _ . . . . . ~ . o LA140 1.74E-07 6.08E-08 204 E-08 NO DATA NO DATA 4.94E-05 6.10E-05 LA142 3 50E-10 1.41E-10 3.49E-11 No DATA NO DATA 2.35E-06 2.0$E-05 CElst 1.06E-05 5.20E-06 7. 83E-0 F WU OATA 2.31E-06 1.47E-0) 1.53E-05,

. . . - - - - .. _ ._ L.

CEt43 9.89E-08 5.37E-08 7.7 FE-09 NO DATA 2.26E-08 3 12E-05 3.44E-05 1..

CEt44 1 83E-03 5.72E-04 9.7FE-05 No DATA 3.17E-04 3.23E-03 1 05E-04 ' ~

!"! ' "!-*' .!:- 2:'!!:! ' "' !' ' * * * - ' ' 2 - -

Pat 44 1.61E.11 4.99E-12 0.10E-13 NO DATA 2.64E-12 4.23E-07 5.32E-08 : .

ND147 2.92E-06 2.36E-06 1.84 E-0 7 No DATA 1.30E-06 8.87E-05 2.22F. 05 l -Cy l

N IST 4.41E-09 2 6tE-09 8. l F E-09 NO DATA NO DATA 1.11E-05 2.46E-05 l l

. ... . .- , j WP239 -1.26E-07 9.04E-09 6.35E-09 NO DATA 2.63E-08 1.57E-05 1.73E-05 i 4

0

. , . ,,w- .-- .a:- - ,- -

ODCM Page: 57 Rev.: 4 Table 3.2-9 7

Inhalation Dose Factors for Infant (mrem /DCi inhaled)

.a

~~ l

~

NUCL10E SONE liver T.800Y TNYR010 EIONEY LUNO -CI-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 1.89E-05 3.79C-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 -

NA 24

~._

7.64E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 ,

= ..

P 32 1.45E-03 8 03E-05 5.5AE-OS NO DATA NO DATA NO DATA 1.15E-05 t CR 51 NO DATA M0 DATA 6.39E-08 4.Ut-08 9.45E-09 9.17E-06 2.55E-07 i

'- MN 54 NO DATA 1 81E-05 3.56C-06 NO 0=.? 3 561-06 7.14E-04 5.04E-06 '

...... . .. ......... ....._.... .... c, .. .. . .. _ j MN 56 NO DATA 1.10E-09 1.5 8E-10 NO DATA 7.86E-10 8.95E-06 5.12E-05 l FE 55 1.4tE-05 8.A9E-06 2.38E-06 NO DAIA 40 DATA 6.21E-05 7.82E-07 4 FE 59 9.69E-06 1.68E-05 6.7FE-06 NO DATA NO DATA 7.25E-04 1.77E-05 g i

CO 58 NU OATA 8. 71 E-07 1.30E-06 NO DATA NO DATA 5.55E-04 7.95E-06 i CO 60 NO DATA 5.7JE-06 8.4tE-06 NO DATA NO DATA 3.22E-03 2 28E-05 i NI 63 2.42E-04 1.46E-05 8.29E-0 6 NO DATA NO DATA 1.49E-04 1.73E-06 41 65 1.71E-09 2.03C-10 8.79E-11 40 DATA NO DATA 5.80E-06 3.58E-05 CU 64 NO DATA 1.34E-09 5. 53 E-10 NO DATA 2.84E-09 6.64E-06 1.07E-05 .

IN 65 1.38E-05 4.47E-05 2.22 E-0 5 NO DATA 2.32E-05 4.62E-04 3.67E-05 ; :

2N 69 3.85E-11 6.91E-11 5.13E-12 NO DATA 2.87E-11 1.0$E-06 9.44E-06 84 SS NO DATA" NO DATA 2. 72 E-0 7 No DATA NO DATA NO DATA L7 E-24 i SR 84 NO DATA NO O'ATA 2. 66E-0 7 NO DATA NO DATA NO DATA LT E-24 l g

OR 85 40 OATA NO DATA 1.46E-00' NO DATA NO DATA NO DATA LT.E-24 i A8 86 NO DATA 1.36E-04 6.30E-05 NO DATA NO DATA NO DATA 2.17E-06 i !

RS 88 NO DATA 3.98E-07 2. 05 E-0 7 NO DATA NO DATA NO DATA 2 42E-07 l RS 89 NO DATA 2.29E-07 1.4 7 E-0 7 NO DATA NO DATA NO DATA 4.87E-08 .

1R 89 2.84E-04 NO DATA S.15C-06 NO DATA NO DATA' 1.45E-03 4 57E-05 1 54 90 2.92E-02 NU DATA 1.85E-03 NO DATA NO DATA 8.03E-03 9 36E-05 {

SR 91 '6.83E-08 NO DATA 2 47E-09 NO DATS NO DATA 3.76E-05 5 24E-05 ,

5R 92 7.50E-09 NO DATA 2 79E-10 NO DATA NO DATA 1.70E-05 1 00E-04 Y 90 2.35E-06 NO DATA 6 30E-08 NO DAfA NO DATA 1.92E-04 7.43E-05 Y 91R 2.91E-10 NO DATA 9.90E-12 NO DATA NO DATA 1.99E-06 1.68E-04 '

Y 91 4.20E-04 40 DATA 1.12E-05 NO DATA NO DATA 1.75E-03 5.02E-05 Y 92 1.17E-08 NO DATA 3.29E 10 NO DATA NO DATA 1.75E% 9.04E '

Y 93 1.07E-07 NO DATA 2.91E-09 NO DATA NO DATA 5.46E-05 1.19E-04 -.s . -

AR 95 8 24E-05 1.99E-05 1.45EdiG NO DATA 2.22E-05 1.25E-03 1.55E-05 .

IR 9F 1.07E-07 1.83E-08 8. 36E-0 9 40 OATA .1.85E-08 7.88E-05 1.00E-04 7 !.

i !?

M8 tb 1.12E-05 4.59E-06 2.70E-06 NO DATA 3.87E-06 3.42E-04 9.05E-06 *

' *r-MD 99 NO DATA 1.18E-07 2.31E-08 NO DATA 1.89E-07 9.63E-05 3 48E-05

TC 99m 9.98E-13 2.06E-12 2.66E-11 NO DATA 2.22E-11 5.79E-07 1.45E-06 (

E a

9

l l

l ODCM i Page: 38 {

Rev.: 4 i

Table 3.2-9 (Cont.) 1 7

Inhalation Dose Factors for Infant (mrem /pCi inhaled)

.-r.

NUCL10E SONE LIVER T.50DY TNYA010 E10NEY LUNG 01-LLT 1C101 4.65E-14 5.98E-14 5 00E-13 NO DATA 6.99E-13 4.17E-07 4.03E-07 '

r Auto) 1.44E-06 NO DATA 4. 8 5 E -0 7 N0 DATA 3.03E-06 3.94E-04 1.15E-05 AU105 8.74E-10 NO DATA 2 93E-10 NO DATA 6.42E-10 1.12E-05 3.46E-05

,RU106 6.20E-05 MO LATA 7.77E-06 NO DATA 7.61E-05 8.2ef-03 1.17E-04

' A C 1104 7,*3E-05 5.16E-06 3. 5 7 E -0 6 ND DATA 7.80E-06 2.62E-03 2.36E-05 TE125M 3.40E-06 1.42E-06 4 70E-07 1.16E-06 NO DATA 3.19E-04 9.22E-06 TE12tM 1.19E-05 4.93E-06 1 48E-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05 - f TE127 1.59E-09 6.81E-10 3.49E-10 1.12E-09 3.47E-09 7.39E-06 1.74E-05 l 7E129r 1. elf-05 4.35[-06 1. 59E-06 3.91E-06 2.27E-05 1.20E-03 4.93E

/

.....- .. ~ .-..- ....-.---.~._.-05 t TE129 5.63E-11 2.48E-11 1. 3 4 E-11 4.82E-11 1.25E-10 2.14E-06 1.88E-05 I ,

TE131M 7.62E-08 3.93E-08. 2.59E-08 6.38E-08 1.89E-07 1.42E-04 8.51E-05 /

TE131 1.24E-11 5.87E-12 3.57E-12 1.13E-11 2.85E-11 1 47E-06 5.87E-06 8

. . - . . . . . . . . . . . - - . . - . . ~ . - - - - - - >

TE132 2.66E-07 1.69E-07 1 26 E-0 7 1.99E-07 7.39E-07 2.43E-04 1.15E-05 1 130 4.54E-06 9.91E-06 3.98 E-06 1.14E-03 1.09E-05 NO DATA 1.42E-06 1 131 2.71E-05 3.17E-c5 1 40E-05 1.06E-02' 3.70E-05 NO DATA 7 56E-07 1 132 1.21E-06 2.53E-06 8.99E-07 1.21E-04 2 42E-06 NO DATA 1.36E-06 1 133 9.46E-06 1.3ff-05 4.00E-06 2.54E-03 1.60E-05 NO DATA 't.54E-06 1 134 6.58E-07 1.34E-06 4.75E-07 5 18E-05 1.49E-06 ND DATA 9 21E-07 !

1 135 2.76E-06 5.43E-06 1.98E-06 4 97E-04 6.05E-06 NO DATA 1.31E-06 C5134 2.83E-04 5.02E-04 5.32E-05 NO DATA 1.36E-04 5.69E-05 9 53E-07 C5136 3.4 5 E-05, 9.61E-05 3.78E-05 NO DATA 4.03E-05 8.40E-06 1 02E-06 C5137 3.92E-04 4.37F-04 3.25 E-0 5 NO DATA 1.23E-04 5.09E-05 9 53E-07 '

C5138 3.61E-07 5 68E-07 2. 84 E-0 7 NO DATA 2.93E-07 4.67E-08 6 26F-07 UA139 1.06E-09 7.03E-13 3.07E-11 ' NO DATA 4.73E-13 4.25E-06 ' 3.64 E-05 BA140 4.00E-05 4.00E-08 2.07E-0 6 NO DATA 9.59C-09 1.14E-03 2.74E-05 FA141 1.12E-10 7.70f-14 3.55E-12 NO DATA 4.64E-14 2.12E-06 3.39E-06 {

pa142 2.84E-11 2.36E-14 1.40E-12 NO DATA 1.36E-14 1.11E-06 4.95E-07 L A140 3.61E-07 1. 4 3t-07 3.68E-08 NO DATA NO DATA 1.20E 4.06E-05 '

LA142 7.36E-10 2.69E-10 6.46E-11 NO DATA NO DATA 5.87E-06 ~4.25E-05 ..

CE141 1.98E-0) 1.19E-05 1.42E-06 40 DATA 3.75E-06 3.69E-04 1.54E-05

'...?

CE143 2.09E-07 1.18E-07 1.5aE.08 NO DATA 4.03E-08 8.30E-05 3.55E-05 '?-

CE144 2.28E-03 8.e5E-04 1.26E-04 40 DATA 3 84E-04 7.03E-03 1.06E-04

~

PR143 1.00E-05 1.74E-06 4. 99E-0 7 se0 DATA 1.41E-06 3.09E-04 2.66E-05

y.

PA144 3.42E-11 1.32E-11 1. 72 E-12 NO DATA 4.A0E-12 1.15E-06 3.06E-06 N014 T 5.67E-06 5 81F-06 3. 57E-0 7 NO DATA 2.25E-06 2.30E-04 2.23E-05 W 187 9.26E 6.44E-09 2.23 E -0 9 NO DATA NO DATA 2.83E-05 2.54E-05

. . . . . . . . . _ . . . . . . . . . . - . . _ . - - - - . . . . . . . . _ . . - . . . . . _ . . . I NP239 2 65E-07 2. 3 7E-08 1. 34 E-0 5 NO DATA 4.73L-08 4. 25 E-0 5 . 1. 7 8 E-05 ;

i I

ODCM Page: 59 i Rev.: 4 Tcble 3.2-10 ,

I Incestion Dose Factor for Adult (mrem /pCi incested)

T.AOCY THYRO 10 K10NEY

_4 LUNG G1=LL1 i

WUCLICE BONE liver l el 3 NO DATA 1.05E-07 1.CS E-0 7 1.05E-07 1.05E-07 1.05E-07 1.0$E-07 .

C 14 2 84E-06 5 68E-07 5 68E-07 5.68E-97 5.68E-07 5.68E-07 5.68E-07 NA 24 1.70E-06 1.70E-06 1.70 E-0 6 1.T0E-06 1.7CE-06 1.70E-06 1.70E-06 P 32 1.93E-04 1.20E-05 7.46E-06 , NO DAT A NC DATA NO DATA 2.17E-05

. CR 51 NO DATA 40 DATA 2. 64,E-0 9 1.59E-09 5.06E-10 3.53E-09 6.69E-07 I'

~

MN 54 40 DATA 4.57E-06 8.72 E-0 7 NO DATA 1.36E-06 NO DATA 1.40E-05 MN 56 NO DATA 1.15E-07 2.04 E-0 8 NO DATA 1 46E-07 NO DATA 3.67E-06 rE 55' 2.75E-06 1.90E-06 4.41,E"- 0 7 NO DATA NO DATA 1 06E-06 1.09E-06 FE 59 4.34E-06 1 02E-05 3. 91 E-0 6 40 DATA NO DATA 2.85E-06 3.40E-05 C0 58 NO DATA 7.456-07, 1.67E-0 6 40 DATA NO DATA NO DATA 1.51E-05 CO 60 NO DATA 2.14E-06 4. 72E-0 6 NO DATA NO DATA NO DATA 4.02E-05 i NI 63 1 30E-04 9.01E-06 4. 36E-06 NO DATA NO DATA NO DATA 1.88E-06 I

. . . . . - - . . . . . . . . . . . . . _ . . . - .... .. i N1 65 5.28E-07 6.06E-08 3.13E-05 40 DATA NO DATA NO DATA 1.74E-06 i CU 64 NO DATA 4.33E-08 3.91E-08 NO DATA 2.10E-07 No DATA 7.10E-06 2M 65 4.84E-06 1.54E-05 6. 96 E -0 6 NO DATA 1.D3E-05 NO DATA 9.70E-06 2N 69 1.03E-08 1 97E 1. 3 7E-0 9 NO DAT'A 1.28E-08 NO DATA 2.96E-09 '

BR 83 NO DATA NO DATA 4. 02 E-0 8 NO DATA NO DATA NO DATA 5.79E-08 BR 84 NO DATA NO CLTA 5.21E-0 8 NO DATA NO DATA NO DATA 4.09E-13 BR 85 NO DATA NO DATA 2.14 E-0 9 NO DATA NO DATA NO DATA L7 E-24 A8 86 NO DATA 2.11E-05 9. 83 E-0 6 NO DATA NO DATA NO DATA 4.16E-06 RB 88 NO DATA 6.05E-08 3 21E-08 NO DATA NO DATA NO DATA 8.36E-19 A8 89 HD DATA 4.01E-08*2.82E-08 NO DATA NO DATA N0 DATA 2.33E-21 !

SR 89 3.08E-04 NO DATA 8. 84 E-06 NO DATA NO DATA NO DATA 4.94E-05 SR 90 7.58E-03 NO DATA 1.86E-03 NO DATA NO DATA NO DATA 2.19E-04 SR 91 5.67E-06 NO DATA 2. 29E-0 7 40 0'ATA NO DATA NO DATA 2 70E-05 SR 92 2.15E-06 NO DATA 9.30E-08 MO DATA NO DATA NO DATA A.26E-05 i Y 90 9.62E-09 NO DATA 2.58E-10 40 DATA NO DATA NO DATA 1 02E-04 Y 91M 9.09E-11 NO DATA 3.52E.12 NO DATA MO DATA NO DATA 2 67E-10 Y 91 1 41E-02 40 DATA 3.77E-09 NO DATA NO DATA NO DATA 7.76E-05 Y 92 8 45E-10 NO DATA 2. 47E.11 NO DATA MO DATA NO DATA. 1.48E-05.

Y 93 2.68E-09 NO DATA 7.40E-11 NO DATA NO DATA NO DATA 4.50E-05 -

s _~- ,

2R 95 3.04E-08 9.75E-09 6.60E-09 NO DATA 1.53E.08 NO DATA 3.09E-05 ~.-

2a 97 1.68E-09 3.39E-10 1.55E-10 No DATA 5 12E-10 NO DATA 1.05E-04 "

NB 95 6.22E-09 3.46E-09 1. 86E-0 9 NO DATA 3.42E-09 NO DATA 2.10E-05 I c, ..

NO 99 NO DATA 4.31E-06 8.20E-07 NO DATA 9.76E-06 NO DATA 9.99E-06 l TC 99M 2.47E-10 6.98E-10 8. 8 9E-0 9 M0 DATA 1.06E-08 3.42E-10 4.13E-07

. . . . . . . . . . . . . . . . . . . . . . . - . - . . . . ~ -

t

_ - _ .l l

ODCM Page: 60 Rev.: 4 Table 3.2-10 (Cont.) :- )

Ingestion Dose Factor for Adult (mrem /pCi ingested) i NUCL 10E DONE liver T.800r THY 4080 Ef0NEY

- t9N80 G1-LL1 --

2.64E-10 3 66E-10 TC101 3. 59E-0 9 NO DATA autos 1.85E*07 NO DATA 6.59E-09 1.87E-10 1 10E-21 '

7. 97E-08 NO DATA T.06E-07 NO DATA 2.16E-05 AU10$ 1.54E-00' NU OATA 6.08E-09 NO DATA 1 99E-07 N 9.42E-06

......................-............--..-.ODATA AU106 2.75E-06 NO DATA 3.48E-07 NO DATA 5.31E-06 NO DATA 1.78E-04 AC110M 1.60E-07 1 48E-07 8.79E-08 NO DATA 2.91E-07 NO DATA 6.04E-05

.TE125M 2.69E-06 9.71E-07 3 59E-07 8.06f-07 1.09E-05 NO DATA - 1.07E-05 - ;

TE127M 6.77E-06 2.42E-06 8.25 E-0 7 1.73E-06 2.75E-05 NO DATA 2 17E-05 TE127 1.10E-07 3 95E-08 '2.38E-08 8.15E-08 4.48E-07 NO DATA TE129M 1.15E-05 4.29E-06 1. a2 E-0 6 3.95E-06 4.80E-05 NO DATA 8.68E-06 5.79E-05 TE129 3.14E-08 .1.18E-08 TE131M 1.73E-06 8.46E-07 7. 7.0 6* E-0 9 2.41E-08 1.32E-07 NO 0$fA

$ E-0 7 1.34E-06 8.57E-06 N0*0ATA 2.37E-08 8.40E-05 TE131 1 97E-08 8.23E-09 6 22E-09 1.62E-08 8.63E-08 NO DATA 2.79E-09 i TE132 2.52E-06 2.23E-061.63E-06 1.53E-06 1.80E-06 1.57E-05 NO DATA 7.71E-05 l 1 130 7.56E-07 8. 80E-0 7 1.89E-04 3.48E-06 NO DATA 1.92E-06 I 131 i 4 16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 NO DATA 1.57E-06. .

.-- -- -_.- ~..-.-

1 132 2.031-07 5.43E-07 1. 90E-0 7 1.90E-05 8.65E-07 NO DATA 1.02E-07 !

1 133 1.42E-06 2.47E-06 7. 53 E-0 7 3.63E-04 4.31E-06 NO DATA 2.22E-06 !

1 134 1.06E-07 2.88E-07 1.03 E-0 7 4.99E-06 4.58E-07 NO DATA 2.51E-10 ,

1 135 4.43E-07 1.16E-06 4. 2 8 E-0 7 7.65E-05 1.86E-06 NO DATA 1.31E-06 C5134 6.22E-05 1.48E-04 1.21E-04 NO DATA 4.79E-05 1.59E-05 2.59E-06 C5136 6.51E-05 2.57E-05 1. 85 E-0 5 NO DATA > i

. ~ . . . . ~ . . - . . . - -

1.43E-05 1.96E-06 2.92E-06 '

C1137 7.97E-05 1.09E-04 7.14 E-0 5 NO DATA I

C5138 5.52E-08 1.09E-07 5.40E-08 NO DATA 3.70E-05 1 23E-05 2.11E-06 /

SA139 9.70E-08 6.91E-11 2. 84 E-0 9 NO DATA 8.01E-08 7.91E-09 4.65E-13 i 6.46E-11 3.92E-11 1.72E-07 '

SA140 2 03E-05 2.55E-08 1 33E-06 NO DATA f BA141 4. 71E-08 9.56E-11 1 59E-09 NO DATA 8.67E.09 1.46E-08 4.18E-05 4 A 142 , 2 13E-08 2.19E-11 1 34E-09 NO DATA 3.315-11 2 0ZE-11 2.22E-17 1 85E-11 1.24E-11 3 00E-26 j LA140 2.SOE-09 1.262-01 J.33E-10 NO DATA NO DATA LA142 1.20E-10 5.82!-11 1 45E-11 NO DATA NO DATA 9.25E-05 CE141 NO DATA No CATA 4.25E-07

.---- 9.36E-09.6 13E-09 F.18E-10 NO DATA 2.94E-09 NO DAT4 2.42E-05 CE143 1.65E-09 1 22E-06 1.35E-10 NO DATA CE144 5.37E-10 NO DATA .4.56E-05 -u PA143 4.48E-07 2 04E-07 2.62Eac8 NO DATA 1.21E-07 NO DATA 1.65E-04 -

9.20E-09 3 69E-09 4 56E-10 NO DATA 2.13E*09 NO DATA 4 03E-05 a,,--

r w

PRl44 3.01E-11 1.25E-11' 1. 5 3E-12 40 OATA N0147 7.05E-12 NO DATA 4.33E-18 6.29E-09 7 27E-09 4. 3 5E-10 NO DATA 4.25E-09 NO DATA 3.49E-05 N 147 1.03E-07 8 61E-08 3.01 E-0 8 NO DATA NO DATA

%. e NO DATA 2.82E-05 ~

?

WP239 1.19E-09 1.17E-10 6. 4 5E-11 NO DATA S.65E-10 NO DATA 2.40E-05 .

4 i

8 P

t

ODCM Page: 61 Rev.: 4 Table 3.2-11 _

Incestion Dose Factors for Teenager (mrem /pCi ingested)

NUCLIDE SONE LIVE 4 T.ancf TNyaole KIDhtY LUNC CI-LLi H 3 NO DATA 1.06E-07 1 0eE-07 1.06C-0T 1.06E-07 1.06E-07 1.06E-07 ..

L 14 4.06E-06 8.12E-07 8. 8 2 E-0 7 0.12E-07 8.12E-07 8 12E-07 8.12F-07 NA 24 2.30E-06 2.30E-06 2.30E46 2.30E-06 2.30k-06 2.30E-06 2.300-06

...... . .. .. . ....-~...- .. . ...... .. .. ..- -.

P 32 2.76E-04 1.71C-05 1.0?E-0 5 NO DATA NO DATA se0 OATA 2.32E-05

-IR 5 t 40 DATA NO DATA 3.60E-0 9 2.00E-09 7.89E-10 5.14E-09 6.05C-0T PN 54 NO DATA 5 90E-0* 1.1TE-06 No DATA 1.76C-06 NO DATA 1.2tE-05 MN $6 NO DATA 1.SSC-07 2. 8 t E-0 8 WO DATA 2.00E-07 NO DATA , 1.04E-05 F E 5> 3.TSE-06 2.60F-06 6.2 5E-0 7 No DATA NO DATA 1.70E-06 1 16E-06 FE 59 5.87E-06 8.JTE-05 5.29E-06 No DATA No DATA 4.32E-06 3.24E-05 CO 58 NO DATA 9.72E-07 2.24 E-0 6 MU DATA NO DATA NO DATA ~ 1.34E-05 CD 60 NO DATA 2 81E-06 6.33E-06 Se0 DATA NO DATA' NO DATA 3.66E-05 NI 63 1.77E-04 1.25C-05 6.00E-06 8e0 DATA NO DATA NO DATA 1.99E-06 NI 65 7.49E-07 9.57E-08 4.36E-08 NO DATA NO DATA NO DATA 5.19E-06 l CU 64 NO DATA 1.15E-07 5.41E-08 NO DATA 2.91E-07 NO DATA 8.92E-06 IN ab 5.76E-06 2.00E-05 9.35E-06 suo DATA 1.28E-05 NO DATA 8.47E-06 lN 69 l'.4 7E-0 8 2 50E-08 1.96E-09 aso DATA 1.83E-08 NO DATA 5.16E-08 e2 83 NO DATA NO DATA 5.74E-08 WO DATA NO DATA

NO DATA LT E-24 .

l BA 84 NO DATA NO DATA 7.22E-08 NO DATA NO DATA NO DATA LT E-24 mR *85 NO DATA NO DATA 3.0$E-09 'O DATA N NO DATA NO DATA LT E-24 R8 86 NO DATA 2.98E-05 1 40E-05 NO DATA NO DATA NO DATA 4.41E-06 48 88 NO DATA 8.52E-08 4 54E-08 NO DATA NO O1TA NO DATA 7.30E-15 .

)

l 48 89 NO DATA 5.50E-08 3.'89E4 8 seo DATA NO DATA NO DATA '8.43Ea17 i 1R 89 4.40E-04 NO DATA 1.26E-0 5 NO DATA 40 DATA NO DATA S.24E-05 54 90 8.30E-03 NO DATA 2.0$E43 seo CATA No DATA NO DATA ,2.33E-04 54 11 8.07E-06 NO DATA 3.2 t E-07 NO Dal l NO DATA NO DATA 3.66E-05 SR 92 3.05E-06 N0'OATA 1.30E-07 NO DATA NO DATA WD DATA 7.77E-05 Y 90 1.37E-08 NO DATA 3.69E-10 NO DATA NO DATA NO DATA 1.13E-04 .

. . . . . ~ . . . - - - .. _ . . - . . , . - . ..._

V 91m 1.29E-10 .feo DATA 4.93E-12 NO DATA NO DATA NO DATA 6.09E-49 Y 91 2 01E-07 N0 DATA 5. 39E-09 NO DATA 8e0 DATA NO DATA 0.24E-d5 Y 92 1.21E-09 800 DATA 3.50E-11 NO DATA NO DATA 800 DATA

4.2* E-05 -

Y 93 3.03E-09 NO DATA 1.05E-10 NO DATA NO DATA NO DATA 1.17E-04 ' eD 2R 95 4.12E-08 1.30C-08 8.96E-09 800 DATA 1.98E-08 8se DATA 3 00E-05 t {-

~~

IR 9F 2.37E-09 4.69E-10 2.16E-10 NO DATA 7.ttE-10 8se DATA t.27E-04 6 NB 95 8.22E-09 4.561-09 2.51E-09 NO DATA 4.42E-09 8s0 DATA 1.95E-05 $

NO 99 NO DATA 6.c3C-06 1.16F 46 NO DATA t.35E-05 NO DATA 1.08E-05 .

TC 99n 3.32E-10 9.26E-10 1.20E-08 NO DATA 1.38E-08 5.14E-10 6.08E-07 i j l

s

m. - - - _... .. .i mm. .. ..._...___m. _ . ..____.--__.._m. _ . - .

ODCM Page: 62 Rev.: 4 Table 3.2-11 (Cont.) ._

Ingestion Dose Factor for Teenager (mrem /DCi ingested) ,

~

NUCL1DE SONE LIVER T.sopf THY 40f0 E10NEY ' 1 Nk' C1-LLI fC101 3.60E-10 5 12!-10 5. 0 3 E-0 9 No DATA 9 26E-09 3.12E-10 8.75E-11 4U103 2.55E-07 NU DATA 1. 09E-0 7 WO DATA S.99E-07 NO DATA 2.13E-05 *-

AU105 2.18E-04 N0 DATA 8. 46 E -0 9 NO DATA 2.75E-07 NO DATA 1 76E-05 Rut 06' 3 92E-06 NO CATA 4. 94 E -0 7 N0 DATA F.56E-06 NO DATA 1.88E-04 AC110m 2.05E-07 1.94E-07 1.18 E-0 7 NO DATA 3.70E -07 NO DATA 5.45E-05 TE12bM 3.83E-06 1.386-06 5.12 E-0 7 1 07E-06 N0 DATA N0 DATA 1.13E-05 TE127M 9.67E-06 3.43E-06 1.15 E-0 6 2.30E-06 3.92t-05 No DATA 2.41E-05 TE127 1.58E-07 5.6CE-08 3.4 0 E-0 8 1 09E-07 6.40E-07 NO DATA 1.22E-05 TE!Z9M 1.63E-05 6.05E-06 2. 58 E-0 6 5.26E-06 6.R2E-05 NO DATA &.12E-05 TE129 4.48E-08 1 67E-08 1.01E-08 3.20E-08 1.88E-07 NO DATA 2.456-07 !

- TE131p 2.44E-06 1.17E-06 9.76E-07 1.F6E-06 1.22E-05 NO DATA 9.39E-05 i TE131 2.79E-08 1.15E-08 8.72 E-0 9 2.15E-08 1.22E-07 .NO DATA 2.29E-09

.... - - _.. - -. ~. . .- .'

TE132 3.49E-06 2.21E-06 2.08E-06 2.33E-06 2.12E-05 NO DATA 7.00E-05 I I 130 1 03E-06 2.98E-06 1 19E-06 2.43E-04 4.59E-06 NO DATA 2.29E-06 f 131 5.85E-06 8.19E-06 4. 40E-0 6 2.39E-03 1.41E-05 NO DATA 1.62E-06 1 132 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E-06 NO DATA 3.18E-07 j f 133 2.01E-06 3.41E-06 1. 04 E -0 6 4.76E-04 5.98E-06 NO DATA 2.58E-06 i

! 134 1.46E-07 3.87E-07 1.39E-0 7 6.45E-06 6.10E-07 NO DATA 5 10E-09 i I 135 6.10E-07 1.57E-06 5. 82 E-0 7 1.01E-04 2.48E-06 NO DATA 1.74E-06 8 C5134 8.37E-05 1.97E-04 9.14 E-0 5 NO DATA 6 26E-05 2.39E-05 2.45E-06 l C5136 8.59E-06' 3.385-05 2.2 7 E-0 5 NO DATA 1.84E-05 2.90E-06 2.72E-06 l C5137 1.12E-04 1.49E-04 5.19E-05 NO DATA 5 07E-05" 1'97E-05

. 2.12E-06 .

C5138 7.76E-08 't.49E-07 7.45E-08 NO DATA 1.10E-07 1 28E-08 6.76E-11 SA139 1.39E-07 9.78E-11 4. CSE-0 9 WO DATA 9.22E-11 6 74E-11 1.24E-06 ,

BA140 2 84E-Ob 3 4AE-08 1. 8 3 E-0 6 NO DATA 1.18E-08 2.34E-08 4.30E-05 AA141 6.71E-08 5 01E-11 2. 24 E-0 9 40 OATA 4.65E-11 3.43E-11 1.43E-13 BA142 2.99E-08 2.99E-11 1. 84 E-09 90 OATA 2.53k-11 1.99E-11 9 18E-20 .

LA140 3.48!-09 1.71E-09 4. 5 5E-10 NO DATA 40 DATA NO DATA 9 82E-05 LA142 1.79E-10 7.95E-11 1.98E-11 NO DATA NO DATA NO DATA 2.42E-06 Ct141 1 33E-08 8.88E-09 1. 02 E-0 9 NO DATA 4.18E-09 NO DATA ,2.54F-05 CE143 2.35E-09 1.71E-06 1.91E-10 NO DATA 7.67E=10 NO DATA 5 14E-05 '. ;

CEles 6.96E-07 2.88E-07 3.74E-04 NO DATA 1.72E-07 WO DATA 1 75E-04 . ". d.- i_ i Palos 1 31E-08 5.23E-09 6.52E-10 NO DATA 3.n4E-09 NO DATA 4 31E i?-

.--4...... ... . _ . ~ - - -

PR144 4.30E-11 1.76E-11 2.18E-12 NO DATA 1.01E-11 NO DATA 4.74E-14 !

4014F 9.30E-09 1.02E-08 6.11E-10 NO DATA 5.99E-09 Mn DATA 3.6BE-05 ! 7'- !

k 187 1 46E-07 1.19E-07, 4 1TE-08 NO DATA NO DATA NO DATA 3.22E-05 I NP239 1.76E-09 1.66E-10 9.22E-11 NO DATA 5.21E-10 NO DATA 2 67E-05 i ,

1 l

i

s ODCM Page: 63 :

Rev.: 4 !

Table 3.2-12 r :

Ingestion Dose Factors for Cnild (area /DCi ingested)

.wa NUCLIDE SONE liver T.#0pr TNYAOIO KIONEY LUNC GI-LLI **

H 3 40 CATA ~ 2.03E-07 2. ole-0 7 2.03E-0T 2.93E-07 2.03E-07 2.03E-0T

C

14 1.2tE-05 2.*2E-06 2.42E-06 2.42E-06 2.42E-06 2.42E.n6 2 42E-06 ;

4A 24 S.00E-06 5.80E-06.' 5. 80E-06 ^5.80E-04 5.80E-06 5.80E-06 9 80E-06

, .. ... ............- . . .. .... .... .... ~ .

'P 32 8.25E-04 3.865-05 3. t SE-o f 40 DA TA 40 DATA NO DATA- 2.28E-05 CR 51 #0 DATA' NO 04TA 8.90E-09 ? '4'.94E-09 1.35E-09 9.02E-09 4.72E-07 '

r.N 54 40 DATA 1.0FE-05 2.85E-06;'NO DAT& 3.00C-06 NO DATA 8.98E-06 ;

NN 56 40 DATA- 3.34E-0F 7.54E-05 40 SATA 4.04E-07 NO DATA FE 55 4 84E-05 ;

1.tSE-05 6.10E-06 1 898-06 NO DATA NC OATA 3.45E-06 1.15E-06 !

FE 59 1.6bE-05 2.6FE-05 1.3AE-05 NO DATA NO DATA 7.74E-06 2.78E-05 :

CD 58 NO DATA 1.BOE-06 5.51E-06 NO DATA NO DA TA NO DATA 1.05E-05 '

CO 60 840 D AT A 5.29E-06

1.56E-05 NO DATA NO DATA NO DATA 41 63 2.93E-05 5.38E-C4 2.OSF-05 1.83E-05 NO DATA NO DATA NO DATA 1.94E-06 NI 65 2.22E-06 2.09F-07 1.22 E-0 7 NO DATA NO DATA . No DATA 2.56E-05 t CU 64 NO DATA 2.45E-07 1. 48E-0 7 NO DATA 5.92E-07 NO DATA 1.15E-05 2N 65 1.37E-05 3. e> 5 E - 0 > 2.2 FC-0 5 No DATA 2.30E-05 No DATA 6.4tE-06 l 2N 69 4.38E-08 6.s3E-08 5.85E-09 NO DATA 3.84E-08 NO DATA 3.99E-06 I 3R 43 NO DATA NO DATA 1. 7 t E-0 7 NO DATA NO DATA NO DATA LT E-24 SR 84 NO DATA NO DATA 1.98E-0 7 NO DATA NO DATA NO DATA LT E-24 l AR 85 NO DATA N0'OATA 9.12E-09 NO DATA 'NO DATA NO DATA LT E-24 MB 86 NO DATA' 6.70E-05 4.12E-0 5 NO DATA NO DATA' NO DATA 4.3tE-06 R8 80 "N0 DATA .1.90E-07 1.32E-07 NO DATA NO DATA NO DATA 9.32E-09

.. .. . ...- ...-.. ~ .. .. - - ..-. .... -- _

R8 $9 NO DATA 1.17E-07 1.04 E-0 7 NO DATA NO DATA NO DATA 1.02E-09 ;

3R 89 1.32Ea03 ND DATA 3.77E-0 5 40 DATA 40 DATA NO DATA 5.11E-05 3R 90 1.70E-02 NO DATA 4.31E-03 880 DATA NO DATA NO DATA 2.29E-04 {

SR 91 2.40E-05 NO DATA 9:06E-07 NO DATA NO DATA NO DATA 5.30E-05 SR 92 9 03E-06 NO DATA 3.62 E-0 7 40 DATA 40 DATA NO DATA 1.71E-04 Y 90 4.11E-08 MO DATA 1 10E-09 No OATA No DATA NO DATA 1.17E-04

. ~ . . . . . . - . . . - . . . . - . . . - . - . . . . -

Y 91N 3.82E-10 40 DATA 1.39E-11 #0 DATA 40 DATA No DATA ~T.40E-07 -

Y 91 6.02E-07 NO DATA 1.6 t f=4 8 NO DATA NO DATA NO DATA' 8.02545 . , .

Y 92 3.60E-09 40 DATA 1 0 AE-10 NO 04TA 90 DATA NO DATA 1.04E-04 -

. _ . . . . - - . ~ - . . - . . . . . . - - . - . . - .- ,?..*.

Y 93 1.14E-DO NO DAT& 3.13E-10 NO 04TA NO 04TA NO DATA I.70E-04 2R 95 1.16E-07 2.35E-08 2.27E-08 NO DATA 3.65E-08 NO DATA 2.66E-05 la 9F 6.99E-09 1.01E-09 *D.96E-10 NO DATA _ 1.45E-09 NO DATA 1.53E-04 .

48 95 2.25E-08 8.76E-09 6.26E-09 NO DATA no 99 - No a&TA 8.23E.09 NO DATA 1 62E-05 1.33E-05 3. 29E-06 No DATA 2.84E-05 NO DATA 1.10E-05 TC 99" 9.23E-10 1.8tE-09 3.00E-08 40 DATA 2.63E-08 9

...... ..... . .. ~ . ~ .. .. .... ..... .. 19E-10

..... 1.03E-06 4

+

b I

I j i

t

}

ODCM Page: 64 Rev.: 4 Table 3.2-12 (Cont.) '

Incestion Dose Factors for Child (mrem /pCi ingested)

NUCLIOE SONE LIVE 4 T.000f THYROIO Kf0 HEY LUNG GI-LLI I

... _ . . ~...... ... .. .. -.. .. .. _ ..- ... . <

TC101 1.07E-09 1 42E-09 1. 42 E-0 8 NO DATA 1.9tE-08 5.92E-10 3.56E-09 AU103 7.31E-07 No CATA 2.81E-07 NO DATA 1.84E-06' NO DATA 1.89E-05 ]-

RU105 6.45E-08 NO DATA 2.34E-08 NO DATA 5.67E-07 *ND DATA 4 21E-05 '

AU106 1 17E-05 NO DATA 1.46E-06 NO DATA 1.58E-05 NO DATA t.82E-04

,' AG110M 5.39E-07 3 64E-07 2.9tE-07 'MO DATA 6.78E-07 WO DATA 4.33E-05 TE125M 1.14E-05 3.09E-06 1. 52 E-0 6 3 20E-06 NO DATA NO DATA 1.10E-05 TE12TM 2.89E-05 7.74E-06 3.4 AE-06 6.91E-06 8.24E-05 NO DATA 2.34E-05 TE127 4.71E-07 1 27F-07 1.01E-07 3.26E-07 1.34E-06 N0 DATA 1.84E-05 i T E129a* 4.87E-05 1.36E-05 7.56E-06 1 57E-05 1.43E-04 NO D A T A

.. -.. _.,. 5.94E-05 !

TE129 *1.34E-07 3.74E-08 3.18E-08 9 56E-08 3.92E-07 NO DATA 8.34E-06 ! ,

TE131M 7.20E-06 2.49E-06 2.65E-06 5 12E-06 2.41E-05 NO DATA TEt31 1.01E-04 i 8.30E-08 2.53E-08 2.47E-08 6 35E-08 2.51E-07 NO DATA 4.36E-07 ! l TE132 1.01E-05 4.47E-Oo 5.40E-0 6 6.51E-06 4.15E-05 NO DATA 8 130 4.50E-05 I 131 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 NO DATA 2.76E:06 1.72E-05 1.73E-05 9.8JE-06 5.72E-03 2.84E-05 NO DATA 1.54E-06 I 132 8.00E-07 t.47E-06 6.76E-07 6.82E-05 2.25E-06 NO DATA

! 133 1.73E-06 i 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 WO DATA 2.95E-06 I 134 4 19E-07_ .7.78E-07 3.58E-07_ ..

1.79E-05 1619E-06 NO DAT4 5.16E-07 8

! 135 1.75E-063.84E-04 3.15E-06 1.49E-06 2.79E-04 4.03E-06 NO DATA 2.40E-06 ! l CK134 2.34E-04 8.10E-05 NO DATA 1.19E-04 4.27E-05 2.07E-06 3 C5136 2.35E-05 6.46E-05 4.18E-05 NO DATA l

^

3.44E-05 5 13E-06 2 27E-06 l ,

C5137 3 2FE-04 3.13E-04 4 62E-05 40 DATA - I C5138 1.02E-04 3.67E-05 t.96E-06 '

2.28E-07 3.17E-07

2.0tll-0 7 NO DATA 2.23E-07 2.40E-08 1.46E-07 SA139 4.14E-07 2.21E-10 1 20E-08 NO DATA 1.93E-10 1.30E-10 2 39E-05 : i l

RA140 8.JtE-05 7.28E-08 4 85E-06 NO DATA SA141 2.3 7t-08 4.34E-08 4.2tE-05

2.00E-07 1.120-16 6 5 t E-09 ND DATA 9.69E-11 6.58E-10 1 14E-07 OA142 8.F4E-08 6.29E-11 4. 88 E -09 NO DATA 5 3. 70E-11 1 14E-09

......... ... ..........- ..... ...... ...09E-11

... .. . ~ ...

t L 4140 1 01E-08 3.53E-09 1 19E-09 40 DATA LA142 NO OATA NO DATA 9.84E-05 5 24E-10 1.67E-10 5 23E-11 40 DATA NO 04T4 NO DATA . 3.31E-05 CE141 ).97E-08 1.98E-08 2.94E-09 NO DATA 8.68E-09 NO DATA ~2.4?E-05 -u CE143 6 99E-09 3.79E-06 5.49f-10 NO DATA CE144 t.59E-09 NO DATA 5.55E-05 t' 'I f .7 PA143 2.08E-06 6.52E-OF 1.tlE-07 NO DATA 3.61k-07 NO DATA 1.70E-04 ! 1~

3 93E 1.88E-08 1 95E-09 NO DATA 6.19E-09 NO DATA 4 24E-05

~

PA144 1.29E-10 1.97E-11 6.49E-12 NO DATA . ,# '

Not47 2.11E-11 NO DATA 8.59E-08 2.79E-08 2.26E-08 1 75E-09 40 DATA N 887 t.24E-08 NO DATA 3.58E-05 l-4 29E-07 2.54r-07 1. l'E-0 7 NO OATA NO DATA N0 DATA 3.57E-05 i NP239 5.2SE-09 3.77610 2.4 btH10 40 DATA 1 09E-09 .NO DATA 2 79E-05l l

1 Y

l

t ODCM Page: 65 l Rev.: 4 Table 3.2-13 ..

Incestion Dose Factors for Infant (arem/pCi incested)

NuCLIUE SONE LIVER T. Sour THv40!D KIONEY . Maut.

. Ct.LLI , i H 3 NO DATA 3.08E-07 A.00E-0F 3.08E-07 3.08E-07 3.00E-07 3.08E-07 ,

C 14 2 3ff-05 5.0&E-06 5. 06 E-0 6 5 06E-06 5.06t-06 5.06F-06 5.06E-06 ,**

NA 24 1.01E-05 1 0tE-05 1.01E-95 1.01E-05 1 0tE-05 1.0LE-0) 1.01E-05 , ,

32 1.70E-03 1 00E-04 6. 59E -0 5 NO DATA NO DATA NO DATA 2.10E-05 CA $1 NO DATA NO DATA 1.4tE-08 9 20E-09 2.ci t-09 1.79E-08 4.11E-07

, !4N $4 'NO DATA 1.99E-Ob 4.5tE-06 40 DATA 4.4tE-06 NO DATA T.3tE-06

. ............ ~ ................ ........... ........-.... . .........

MN 56 40 DATA 8.18E-07 1 4tE-0T NU OATA 7.01E-07 40 DATA 7.43E-05 ft 55 1.39E-05 8.98E-06 2.4CE-06 NO DATA NO DATA 4.19E-06 1.14E-06 FE 59 3.08E-05 5.se!-06 2.12E-05 40 CATA NO DATA 1.59E-05 2.57E-05 ;

CO 58 NO DATA 3.60E-06 a.98E-06 NO DATA NO DATA NO DATA 8.97E-06 CO 60 NO DATA 1.00E-05 2. 5 5 E-0 5 NO DATA NO DATA NO DATA 2.5FE-05 '

NI 63 6 34E-04 3.92E-05 2. 20E-0 5 NO DATA NO DATA NO DATA 1.95E-06 NI 6$ 4.70E-06 5 32E-07 2.42f-07 NO DATA NO DATA NO DATA 4.05E-05 CU 64 NO DATA 6.09E-07 2.82E-07 NO DATA 1.03E-06 NO DATA 1.25E-05 ZN 65 1.84E-05 6."J t E-0 5 2. 9 t E-0 5 NO DATA 3.06E-05 NO DATA 5.33E-05 lN 69 9.33E-08 1.00E-07 1.2 5 E-0 8 No DATA 6.98E-08 No DATA 1.37E-05 BR 83 40 DATA NO CATA 3.63 E-0 7 NO DATA NO DATA NO DATA LT E-24 84 84 NO DATA NO DATA J . 82 E-07 NO DATA NO DATA - NO DATA LT E-24 w._. ... . ............... . . _

WR 85 NO DATA NO DATA 1 94 E-0 8 NO DATA NO DATA NO DATA LT E-24 M8 86 NO DATA 1.70E-04 8.4 0 E-0 5 NO DATA NO DATA Nd DATA 4.35E-06 MS 48 .NO DATA 4.98E-07 2.73E-07 NO DATA NO DATA NO DATA 4.85E-07 l RC 59

NO DATA 2.86E-07 8 97E-07 NO DATA NO DATA N0'OATA 9.74E-08 SR 89 2.51E-03 NO DATA 7.20E-05 NO DATA NO DATA NO DATA 5.t&E-05 .

i 5R 90 1.05E-02 NO DATA 4.7 t E-0 3 NO DATA NO DATA NO DATA 2.3tE-04 ' '

SR 91 S.00E-05 NO DATA 1. 8 t E-0 6 NO DATA NO DATA NO DATA 5 92E-05 ,

ER 92 1.92E-05 NO DATA 7.13 E-0 7 NO DATA NO DATA NO DATA 2 07E-04 ;

Y 90 0.69E-08 NO DATA 2.3sE-09 NO DATA NO DATA 40 DATA 1.20E-04 1 8.10E-10' No DATA '

Y 9tm 2.76E-11 NO DATA NO DATA NO DATA 2.70E-06 Y 91 1 13E-06 NO DATA 3.0!E-08 NO DATA NO DATA NO DATA 8.10E-05 Y 92 7.65E-09 N0'OATA 2.15E-10 NO DATA NO DATA NO DATA 1.46E-04 l

Y 93 2.43E-08 NO DATA 6.62E-10 NO DATA NO DATA NO DATA D92E-04' ....

24 95 2.06E-07 5.02E-08 3. 56E-0 8 NO DATA 5.41E-08 NO DATA 2.50F-05 .

IR 97 1 48E-00 2.54E-09 1 16E-09 NO DATA 2.56E-09 NO DATA 1.62E-04 . -- ' ' ' _

'. * ~ ~ l 48 95 4 20E-08 1.71E-08 8.00E-08 NO DATA 1.74t-08 NO DATA 1.46E-05 MD 99 NO DATA 1.402-05 6.63E-06 40 DATA 5.08E-05 NO DATA 1.12E-05

TC 99M 1.92E-09 3.96E-09 5.10E-08 No DATA 4.26E-08 2.07E-09 1.15E-06 I .P'

ODCM Page: 66 Rev.: 4 Table 3.2-13 (Cont.)

Ingestion Dose Factors for Infant NuCLIDE SONE L IvE R T.000Y THYRotO KIONEY ~ ~ ~fthlG ~

0f-LL1 IC101 2.2TE-09 2.86E-09 2.83E-08 NO Data 3.40E-08 1.56E-09 4.86E-07 '

AU103 1.48E-06 NO DATA 4.95E-07 NO DATA 3.08E=06 NO DATA 1.80E-05

autos 1.36E-07 NO DATA 4.58E-08 40 0ATA 1.00E-06 NO DATA 5.4tE-05 Aut06 2.4tE-05 NO DATA' 3.0 t E-0 6 No DATA 2.85E-05 NO DAT4 1.83E-04 AC110M 9*96E-07 7.27E-07 4.8tE-07 10 DATA 1.04E-06 NO DATA 3.77E-05

.TE125N 2.33E-05 7.79C-06 3 1>E-0 6 7.84C-06 NO DATA NO DATA 1.IIE-05 TEt27M 5.85E-05 I.94E-05 f.08E-06 1 69E-05 1.44E-04 No DATA 2 16E-05 TE127 1.00E-06 3.35E-OF 2.15E-07 8.14E-07 2.44E-06 NO DATA 2.10E-05 TE129N 1.00E-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04 NO DATA 5.97E-05 TE129 2.84E-07 9. 79E-08 ' 6.6 3E-08 2.38E-07 7.07E-07 'ND DATA- 2.27E-05 TE131P 1.52E-05 6.12E-06 $.05E-06 1.24E-05 4 21E-0$ NO DATA 1.03E-04 TE131 1 76E-07 6. 50 E-08 4.94E-08 1.57E-07 4 50E-07 NO DATA 7.11E-06 '

TE132 2.08E-05 1.03E-05 9.6tE-06 1.52E-05 6.44E-05 NO DAT4 3.81E-05

! 1.30 6.00E-06 1.32E-05 5. 30E-0 6 1.48E-03 1.45E-05 NO DATA 2.83E-06 1 131 3.59E-05 4.2 3E-05 1. 4 6E -0 5 1.39E-02 4.94E-05 NO DATA 1.51E-06 1 132 1.66E-06 3.37E-06 1.2 0E-0 6 1.58E-04 3.76E-06 NO DATA 2.73E-06 1 133 1.25E-05 1.82E-05 5. 3 3 E-0 6 3.3tE-03 2 14E-05 NO DATA 3.08E-06 I 134 8.69E-07 1.78E-06 6 33E-0 7 4.15E-05 1.99E-06 NO DATA 1.84E-06 I 135 3.64E-06 7.24E-06 2. 64 E-0 6 6.49E-04 8.07E-06 NO DATA 2.62E-06 C5134 3.77E-04 7.03E-04 7.10 E-0 5 NO DATA 1.81E-04 7.42E-05 1.91E-96 C 5136

4.59E-05 't.35E-04 5. 04 E-0 5 NO DATA 5.38E-05 1.10E-05 2.05E-06 C5137 5.22E-04 6.11E-04 4. 3 3 E-0 5 NO DATA 1.64E-04 6.64E-05 1.91E-06 C5138 4.81E-07 7.82E-0F ' 3. 7 9 E-0 7 NO DATA 3.90E-07 6.09E-08 1.25E-06 '

8A139 8.81E-07 5.84E-10 2. 5 5 E-0 8 NO DATA 3.51E-10 3.54E-10 5.58E-05 m . --

Bat 40 1.71E-04 1.71E-07 8.A!E-06 N0 DATA 4.06E-08 1.05E-07 .4.20E-05 P. A t 41 4.25E-07 2.91E-10 1.34E-08 NO DATA 1.75E-10 1.77E-10 5.19E-06 Pat 42 1.84E-07 1.53E-10 9. 06 E -0 9 NO DA TA 8.81E-11 9.26E-Il 7.59E-07 LA140 2.llE-08 8.32E-09 2.14 E -0 9 NO DATA NO DATA LA142 NO DATA 9.77E-05 1 10E-09 4.04E-10 9.6tE-11 NO DATA NO DATA NO DATA 6.86E-05 CElet 7.0FE-08 4.80E-08 5. 65 E-0 9 NO DATA 1.48E-08 NO DATA - 2.48E-05 !

CEt43 1.48E-CA 9.82E-06 1.12E-0 9 NO DATA 7.96E-09 NO DATA 5.73E-05 ' ~ '

CE144 2.98E-06 1.22E-06 1. 67E-0 7 NO DATA 4.93C-07 NO DATA P4143 0.13E-08 1.04E-08 4. 03 E-0 9 NO DATA 1.13E-08 NO DATA 1.71E-04 4.29E-05

. t ;-

'~ l pat 44 2.74E-10 1.06E-10 1.38E-11 NO DATA 3.A45-11 NO DAff 4.93E-06 Nt 147 5 53E-08 5. c. 8 E-08 3.48E-09 NO DATA N 187 9.03E-07 6.28E-07 2.17E-0F 40 DATA 2.19E-08 NO DATA 3.402-05 D NO DATA NO DATA 3.69E-05 NP239 1 11E-08 9.93E-10 5.41E-10 10 DATA 1.98E-09 NO DATA 2 87E-05 l

- ~ _ -

ODCM Page: 67 Rev.: 4 Table 3.2-14 Annual Usage Factors for the Maximum Exposed Individual Pathway infant Child Teer. Adult _.

Fruits, vegetables &

grain (kg/yr)* --

520 630 520 Leafy vegetables (kg/,yr) --

26 42 64 Milk (1/yr) 330 330 400 310 Heat & poultry (kg/yr) --

41 65 . 110 3

Inhalation (m /yr) 1400 3700 8000 8000

Consists of the following (on a mass basis): 22% fruit, 54% vegetables (including leafy vegetables), and 24% grain.

Table 3.2-15 Annual Usage Factors for the Average Individual Pathway Child Teen Adult Fruits, vegetables, &

grain (kg/yr)* 200 240 190 Milk (1/yr) 170 200 110 Heat & poultry (kg/yr) 37 59 95 " --

3 Inhalation (m /yr) 3700 8000 8000 ' '"--

.l l

r.

Consists of the following (on a mass basis): 22% fruit, 54% vegetables (including leafy vegetables), and 24% grain.

- For total population and average individual dose calculations.

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ODCM Page: 69 l Rev.: 4 3.3 Compliance with 10CFR50 Appendix I - Gaseous Effluent Dose _..

Doses resulting from the release of noble gases, radioiodines, tritium and radionuclides in particulate form must be calculated to .

show compliance with Appendix I of 10CFR50. he-cale gations will . -

be performed at least monthly for all gaseous effluents. ~

3.3.1 Noble Gaspes *l Section II.B.1 of Appendix I of 10CFR50 limits the releases of gaseous effluents from each reactor to unrestricted areas such 1 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 pathway only will be considered for noble gases. He controlling location for the above stated dose :

limits is the site boundary location with the highest relative i dispersion factor (x/Q) for the period of release. l PNPP Technical Specifications limit the dose resulting from the release of noble gas radionuclides in gaseous effluents to the.

following.

a. For galana radiation, during any calendar quarter:

i D s 5 mrads, >

air

b. For beta radiation, during any calendar quarter: !

D air s 10 mrads, l

c. For gamma radiation, during any calendar year: . ;

D s 10 mrads, air ,

d. For beta radiation, during any calendar year: ,

~

D air s 20 mrads, r 'i 5-

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l

1 oDCM I Page: 70 :

Rev.: 4 l

3.3.2 Radioiodines, Particulates, and Other Radionuclides ..

- Section II.C of Appendix I of 10CFR50 limits the annual release' >

of radioiodines and radioactive materials in particulate form !

from each reactor such that estimated dose or.4ese commitment -

~

to an individual in an unrestricted area from all pathways of ,

exposure is not in excess of 15 mrem to any organ. The controlling location for this organ dose limit is the location :

of the highest relative dispersion (x/Q) or deposition (D/Q) for the period of release, as well as the actual receptor pathway. Receptor pathway locations will be reviewed once per j year following the performance of the Land Use Census to j 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 radionuclides in particulate form with half-lives greater than eight days to the following: i

a. During any calendar quarter: ;

Dose to Any Organ s 7.5 mrems ,

b. During any calendar year:

Dose to Any Organ s 15 mrems.

l 3.3.3 Dose Calculations f The following calculations are used to determine gamma and beta l air doses resultant from noble gas release to areas at or i beyond the site boundary'for purpose of showing compliance with -

10CFR50, Appendix I. The equations used to calculate organ doses resultant from the release of iodine-131, iodine-133, >

tritium, and radionuclides in particulate form withJnif-lives ;

greater than eight days are those found in Section 3.~2.3. '._

i Dose values are obtained by applying the dose rates over the ~ ' S-appropriate surveillance or sampling time period. N l P

P 4

h L

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ODCM -l Page: 71 _;

Rev.: 4 l

a. Ganuna Air Dose from Noble Gas Releases ..,_

7 1 7 !

Dair = (3.15) (10 ) (x/Q) I (Qg) (DFg) 1 .. .

Where: -w _ l 7 -

i D"l* = the annual gamma air dose due to noble gas radionuclides, in arad/yr; .

7 DF g = the gamma air dose factor for a unifom 1 semi-infinite cloud of radionuc Ki Table 3.3-1, in arad/s per Ci/m}ide ; "i", from {

Q.1 = the release rate of radionuclide 'i', in ;

pCi/s; .

x/Q = the normal relative dispersion factor, in s/m 3 {

(see Appendix A); i j i

3.15 x 101 = the conversion factor to convert (arad * '

pCi)/(Ci

s) to mrad /yr.

b. Beta Air dose from Noble Gas Releases !

I D i D

Dair = (3.15 x 10 ) (x/Q) E (Qg) (DFg) 1 l Where: ;

D i D. = the annual beta air dose due to noble gas -l air radionuclides, in arad/yr; l D

DF.

l

= the beta air dose factor for a uniform !

semi-infinitecloudofradionucjide,"i",from Table 3.3-1, in arad/s per Ci/m ;. t ' ( }

0-Q.1 = the release rate of radionuclide 'i', in pCi/s; i~ ;

~ >

x/Q = the 3normal relative dispersion factor, in M s/m ; (see Appendix A), ,

1 3.15 x 10 = the conversion factor to convert !

(mrad

pCi)/(Ci

s) to mrad /yr. j 3.3.4 Cumulation of Doses The dose contribution from gaseous effluents will be calculated at least monthly. Calculations will be perfomed.to determine -

the maximum air dose as well as the maximum organ dose to an i individual. These dose calculations will be sumed for ,

j comparison with quarterly and annual limits. To assure !

i i

h i

-. - - , - , . . - -, . , . - . . - - - . - , . - - . , , . . ~ . . . . -

4 ODCM Page: 72 Rev.: 4 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 are exceeded, a special report 611 be _

submitted to the NRC in accordance with PNPP Technical Specifications.

3.3.5 Projection of Doses

nticipated doses resulting from the release of gaseous

'- affluents 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 will 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 mrem to any organ, appropriate portions of the ventilation exhaust treatment system will 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 would correspond to less than one-fourth of the Appendix I limits.

3.4 Population Dose PNPP's Annual Radioactive Effluent Release Reports, as required by Regulatory Guide 1.21, will include total population dose and average individual doses calculated for all radioactive gaseous effluent releases. The total population dose and average individual dose will be computed, taking into account geographical population distribution and pathway (s) using the equations in Section 3.2. .

However, the dose factors, DF .. differ; total population and average individual doses are 8dl8u, lated in a manner similar to that '

used for maximum individuals except that Regulatory Guide-1.109,- .

Revision 1 assumptions for average individuals are used rather than

.'.p( i for maximum exposed individuals and they are averaged over all age -

i groups after weighting by the fraction of. population in each age 5' l group. -

., )

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1 I

i l

ODCM Page: 73-Rev.: 4 Figure 3.3-1 .

'Gansna and Beta Air Dose Factors for Semi-Infinite Plume (mrad /s per Ci/m3 ) . _ _ ,.

.,, _L Gamma Air Beta Air '

Dose Factor Dose Factor -

Nuclide (DF7i ) (DFf)

N 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 Kr-87 1.96+2 3.27+2 .

Kr-88 4.82+2 9.29+1 Kr-89 5.48+2 3.36+2 Kr-90 5.14+2 2.48+2 Xe-131m 4.95+0 3.53+1 Xe-133m 1.04+1 4.69+1 Xe-133 1.12+1 3.33+1 Xe-135m 1.07+2 2.34+1 Xe-135 6.09+1 7.80+1 Xe-137 4.79+1 4.03+2 Xe-138 2.92+2 1.51+2 F' . gp

- EC~-

^ .

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ODCH Page: 74 Rev.: 4 4.0 'IOTAL DOSE _.

4.1 Compliance With 40CFR190 - Uranium Fuel Cycle Dose Annual dose contributions from liquid and gaseous eftigent releases, a as discussed in Sections 2.3.2 and 3.3.4, are summed to evaluate compliance with the 40CFR190 annual limit of 25 mrem total body or -

any organ (except the thyroid, which is 75 mrem).

PNPP does not intend to exceed 40CFR190 limits during normal operation. However, if such a situation should occur, violations

' would be handed as per Technical Specification 3/4.11.4a. which requires the following:

With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the Ibnits.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 for achieving conformance with the above limits. This Special Report, as defined in 10CFR20.405c, shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that include. the release (s) covered by this report. It shall also describe levels of. radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose (s) exceeds the above limits, and if the release condition resulting in violation of 40CFR190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the ;_

provisions of 40CFR190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the 7-

'. <- C request is complete. 1~

This Special Report shall contain: .

1. A determination of which fuel cycle facilities 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 miles from PNPP need not be considered in this determination.

2. A determination of the maximum exposed individual.

ODCM Page: 75 Rev.: 4 +

3. A determination of the total annual dose to this person from -

all existing pathways and sources of radioactive effluents and Y direct radiation using the methodologies described in this ODCM. Where additional information on pathways and nuclides is needed, the best available information will be:1uned and e

~

documented.

4. A det.?.rmination of the dose resulting from direct radiation .

from the plant and storage facilities.

, The total body and organ doses resulting from liquid effluents from

' the PNPP will be sununed with the doses resulting from gaseous ;

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 of two. The doses from the PNPP will be sunned with the dose to the maximum exposed individual contributed from other operations of the i uranium fuel cycle.

r

'. 5

."; i

ODCM Page: 76 Rev.: 4 4.2 Direct Radiation Dose from PNPP .

Potential direct radiation dose to individuals outside PNPP will arise fron (a) skyshine and direct dose from the turbines, (b) direct dose from the external surfaces of buildings, and -1 (c) direct dose from stored radwaste.

Coolant activation by high energy neutrons, the 016 (n,p)N16 ,

reaction, is of interest in boiling water reactors, like PNPP, because it can result in turbine skyshine and direct dose. The N-16 oresent in the steam of a direct cycle BWR is carried with the steam into the turbine moisture separators, and associated equipment.

Although N-16 has a 7.13 second half-life, its ganea emission can present a radiation dose problem to the site boundary as a result of the high energy gamma scatter from structures and the atmosphere.

AllexternalwallsofbuildingsatPNPPhavebeendesigneilto 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 mrem /h.

Projected direct radiation dose assessment for normal operations was performed, based on 80% load factor and 100% occupancy, for the closest site boundary location (WSW sector). Direct dose from turbine skyshine was calculated to be 1.3 mrem /yr and direct dose from the surface of buildings was calculated to be 2.2 E-3 mrem /yr.

Direct radiation doses at PNPP will be measured by self-contained dosimeters encircling the site located in the general area of the site boundary. These self-contained dosimeters will be of the thermoluminescent variety (TLDs) with analyses performed quarterly-and annually.

l 1

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ODCM Page: 77 Rev.: '4 4.3 Dose to Members of the Public While Onsite -

i 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.' 'Miis assessment is included in Semiannual Radioactive '

Effluent Release Reporting.. ,

A member of the public is defined in Technical Specifications to in'clude anyone who is not occupationally associated with the plant, i.e., not a utility employee, contractor or vendor. Also excluded '

- from this category is any person who enters the site to service equipment or make deliveries.

Maximum dose to member of the ptblic while onsite is conservatively assessed relative to offsite dose values. The assessment.

methodology incorporates use of appropriate dilution,-dispersion, '

and occupancy factors for onsite activities.

The only liquid effluent dose pathway affecting members of.the public while onsite is shore exposure. Fishing on the Lake Erie' .

shoreline is the assumed activity for this exposure. Onsite dose- '

assessment is made via ratio to the maximum calculated offsite shore ,

exposure dose incorporating adjustments for occupancy factor and j liquid effluent dilution. '

Several cases are considered for gaseous effluent dose assessment to j member of the public while onsite including: traversing a public road within the site boundary, lakeshore fishing, non-PNPP related i training sessions at 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/Q' l (atmospheric dispersion) values. " Relative x/Q' values are the product of the highest annual average x/Q for the point of concern, and occupancy factor for the case. An adjustment factor is derived by ratioing this highest onsite ' relative x/Q' to the highest site boundary " relative x/Q'. (A unity occupancy factor is used in the i i determination of the highest site boundary " relative x/Q'). 'A_ ~

Conservative onsite dose determination is made by applying the -f_t

" relative g/Q' adjustment factor.for the highest potential onsite '

dose activity to the highest calculated gaseous effluent offsite .,.

dose. -, 'W 1

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ODCM Page: 78 Rev.: -4 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRA_M 5.1 Monitoring Program Environmental samples shall be collected and analyzed:.according to '_- i Table 5.1-1 at locations shown in Figures 5.1-1, 5.1-2 and 5.1-3.

The Radiological Environmental Monitoring Program (RENP) sample locations are controlled by REMP-0013. A list and figures of the '

specific locations are contained in the Master List of Sangling ,

Locations in the REMP file. Analytical techniques used shall ensure

, that the detection capabilities in Table 5.1-3 are achieved.

i Ground water sampling will not be conducted as part of PNPP's REMP l- 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 groundwater contamination. Se position of the plant and the underdrain system with respect to the hydraulic.

gradient is such that any leakage or overflow from the underdrain system will flow north towards Lake Erie. Local domestic wells outside the exclusion area boundary are up-gradient from the plant.

As part of the REMP, samples will be routinely collected from the closest potable water intakes on Lake Erie.

The results of the radiological environmental monitoring program are intended to supplement the results of the radiological effluent

! monitoring by verifying that the measurable concentrations of radioactive mats-ials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways. Thus, the specified environmental monitoring program provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides whi.% lead to the highest potential radiation exposures of individuals resulting from the station operation. Se 1 initial radiological environmental monitoring program was conducted .

for the first three years of commercial operation; program changes i may now be proposed based on operational experience. ., , ,

Deviations are permitted from the required sampling schedule if . T.3 specimens are unobtainable due to hazardous conditions, seasonal ' {.4^_

unavailability, malfunction of automatic sampling equipment and other legitimate reasons. If specimens are unobtainable due to .m sampling equipment malfunction, every reasonable effort shall be T made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the annual report. ~

=.

L ODCM Page: 79 ;

Rev.: 4 5

5.2 Land Use Census Program e i A Land l'se Census will be conducted annually to identify, within a -

distance of 8 km (5 miles), the location in each of the . :

i meteorologica1' sectors of the neargst residgnce, the-searest vegetable garden greater than 50m (500 ft ) producing broad leaf vegetation and the nearest milk-producing animal..

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 new location (s) will be added to the radiological environmental monitoring program within 30 days. The sangling location (s), excluding the control station location, having the ;

lowest calculated dose or dose commtitment(s), via the same exposure pathway, may be deleted from this monitoring program after j October 31 of the year in which this Land Use Census was conducted. i Any location from which milk can no longer be obtained may be dropped from 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 growing season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, aerial 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, f

Broad leaf vegetation sampling of at least three different types of vegetation may be performed at the site boundary in each of two different sectors with the highest predicted D/Qs ;

in lieu of the garden census. Specifications for broad leaf vegetation sampling in Table 5.1-1 shall be followed, including i analysis of control samples. i

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ODCM Page: 80 Rev.: 4 5.3 Inter-Laboratory Comparison Program 4

The' laboratories of the licensee and/or licensee's contractors which perform analyses shall participate in the Environmental Protection . .

Agency's (EPA) Environmental Radioactivity Laboratona.4ntercom- - _

t parisons Studies (Crosscheck) Program or equivalent program. This participation shall include all of the determinations (sample '

medium-radionuclide combinations) that arc 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. I If the results of a determination in the EPA crosscheck 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. ;

9 y . ., e

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em 4

i .

Table 5.1-1 RADIOWGICAL DNIROt44 ENTAL MNTIORING PROGUM Neber of Sanples e Exposure Pathway and Sangling and Type and Fregaency and/or samle Sam le Ia;ationIII Collection Frequency of Analysis.

1. Direction enty eight routine monitoring Quarterly Gamma dose quarterly.

Radiation I2) staticms either with two or more dosimeters or with one instrument for measurin2 and recording dose rate continuously, placed as follows:

An inner ring of stations, one in each meteorological sector, other than those sectors entirely over water (N, M , ItW, NN, W, NNN),

in the general area of the SITE BOUNDMtY; -

An outer ring of stations, one in l each meteorological sector, other than those sectors entirely over l water (N, ISE, l@M, Mf, W, NNN),

t in the 6- to 8- ha range fran the site; and the balance of the stations to be placed in special interest areas such as population centers, nearby residences, schools, and in one or .

2mo two areas to serve as control 'g

, stations. ,

y g-q' .

"m

.s

.. :..y, c a

_ . . , . __ - _ -. . ._ __ .-s .._ _ . .- _ ._. _

Table 5.1-1 (Cmt.)

RADIOIOGICAL DWIR0tNENTAL KNI'IORDG PR(XRAM Number of Sanples ,,

Exposure Pathway and Sanpling and Type and Frequency and/or Sanple Sanple location (1) Collection Frequency of Analysis.

2. Airborne Radiciodine and Sanples frm five locations: Continuous sanpler Radiciodine Canister:

Particulates operation with sanple I-131 analysis weekly

'Ihree sanples frm close to collection weekly, or the three SITE BOUNDARY loca- more frequently if tions, in different sectors, of required by dust Particulate Sanoler:

the highest calculated annual loading Gross beta radioactivity average ground-level D/Q: analysis following One sanple frm the vicinity filter change;(3) and of a ammunity having the highest ganna isotopic analysis I4I calculated annual avcu. age ground- of omposite (by location) level D/Q; and quarterly.

One sanple fr a a control location, as for exanple 15 to 30 km distant and in the least prevalent wind direction.

3. Waterborne

a. Surface Two sanples Couposite sanp1 Ganna isotopic analysis I4I 1-nonth period.T5p monthly. Ctmposite for tritium analysis quarterly. .a y o

, ',I. $$h

. 9

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-l

. l.$

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Table 5.1-1 (Cont.) 1 RADIOIOGICAL DNI1ONENI'AL 10NI'IORDG PROGPJM M mber of Sanples ,.

D @osure Pathway and Sanpling and Type and Frequency gy) and/or Sanole Sanole Iocation Collection Frequency of Analysis-

3. Waterborne (Continued)

b. Drinking One sanple of each of on to three Ctmposite sanple I 1 ysis en end of the nearest water supplies over 2-week period (5) conposite when the dose that could be affected by its when I-131 analysis calculated fra the -=rtion discharge. is performed; monthly ccuposite otherwise.

of the water is pter than 1 stem per year. Camposite One sangle from a control for gross beta and y isotopic analysis monthly.

location. Conposite for tritiurn analysis quarterly

c. Sediment one sanple fran area with existing Semiannually Ganna isotopic analysis III frm or potential recreational value. seniannually.

shoreline

6. Ingestion

a. Milk Sanples fra milking animals in Semimonthly when Genna isotopic I4I and I-131 three locations within Skm distance animals are on pasture; analysis senimanthly when animals

! having the highest dose potential. lenthly at other times. are on pasture; nonthly at other If there are none, then one sanple times.

fr m milking animals in each of three areas between 5 to 8 km distantwheredosesarecalculateg) to be greater tien 1 mrem per yr. . m,o One sample from milking animals at a ',. Q*R.

. control location 15 to 30 km distant 1

:.$M-and in the least prevalent wind direction.

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f* ki$

ee_ _ -mw -. ,w- ei c w e. um a g. e u- -2%-- g- -e .e "o -

,e-w-r -e- en- . n---- 7

Table 5.1-1 (Cont.)

RADIOIOGICAL DNIR0tMNTAL 10NTIORDG PRO @AM Ntznber of Sanples .

Exposure Pathway and Sanpling and Type and Frequency and/or Sa mle Samle Iccation(1) Collection Frequency of Analysis

4. Ingestion (Continued)

b. Fish and On sanple of each connercially Sanple in season, or Ganma isotopic analysis ( I Inverte- and recreationally inportant semiannually if they on edible portions.

brates species in vicinity of plant are not seasonal.

discharge area.

One sm ple of same species in areas not influenced by plant discharge,

c. Food Samples of three different kinds Monthly during Genua isotopic and I-131 products of broad leaf vegetation grown growing season. analysis.

nearest to each of two different offsite locations of highest predicted annual average ground level D/Q if milk sanpling is not performed.

One sanple of each of the similar Monthly during Genna isotopic I4I and I-131 broad leaf vegetation grown growing season. analysis.

15 to 30 km distant in the least prevalent wind direction if milk sanpling is not performed.

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- - - . . . = . - . . -.

ODCM i Page: 85 Rev.: 4 j Table 5.1-1 (Cont.). l RADIOLOGICAL ENVIRONMENTAL MONI10 RING PROGRAM Table Notations -m s {

I (1) Deviations are permitted from the required sampling schedule if -

specimens are unobtainable due to circumstances such as hazardous. ;

conditions, seasonal unavailability, and malfunction of automatic i sampling ~ equipment. If specimens are unobtainable due to sampling :

. equipment malfunction, effort shall be made to complete corrective l

~

' action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual ,

Radiological Environmental Operating. Report pursuant to < Technical :

Specification 6.9.1.6>. It is recognized that, at times, it may may not be possible or practicable to continue to obtain samples of the ;

media of choice at the most desired location or time. .In these ,

instances suitable specific alternative media and locations may be ,

chosen for the particular pathway in question and appropriate substitutions made with in the thirty days.

(2) One or more instruments, such as a pressurized ion chamber, for l measuring and recording dose rate continuously may.be used in place of, or in addition to, integrating dosimeters. For the purposes of !

this table, a thermoluminescent dosimeter (TLD) is considered to be !

one phosphor; two or more phosphors in a packet are considered as two or more dosimeters.

(3) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for radon and i thoron daughter decay.

1 (4) Gamma isotopic analysis means the identification and quantification ;

of gamma-emitting radionuclides that may be attributable to the ,

effluents from the facility.

l (5) A composite sample is one in which the quantity (aliquot)'sof liquid' c ?

sampled is proportional to the quantity of flowing liquid and in ._-

which the method of sampling employed results in a specimen that is ,J)3

/- .

representative of the liquid flow. In this program composite sample aliquots shall be collected at time-intervals that are very short . ,. I (e.g., hourly) relative to the compositing period (e.g., monthly) in ??

order to assure obtaining a representative sample. jl I

(6) The dose shall be calculated for the maximum organ and age group, using the methodology and parameters within this manual.

I i

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I Table 5.1-2

. Reporting levels for Radioactivity Concentrations in Environmental Sanoles

RTER FISH MIIK FOOD PRODUCTS ANALYSIS (pCi/1) AIRBORNE OR GASES (pCi/m PARTICUg')IE (pCi/kg, wet) (pCi/l) s (pCi/kg, wet)

H-3 2 x 104(a) 4 h 54 1 x 10 3 3.x 10 2 4 Fe-59 4 x 10 1 x 10 3 4 Co-58 1 x 10 3 x 10 4

Co-60 3 x 10 2 1 x 10 Zn-65 3 x 10 2

2 x 10 4 2

Zr-Nb-95 4 x 10

-1 3 x 10 0 2

2-13 1 2 x 10 0 9 x 10 1 x 10 Cs-134 3 x 10 1

1 x 10 1 1 x 10 3 6 x 10 1

1 x 10 3 Cs-137 5 x 10 1

2 x 10 1 2 x 10 3 7 x 10 1 2 x 10 3 i

Ba-La-140 2 x 10 2 3 x 10 2 I l

l (a) For drinking water sanples. 'Ihe value given is the 40CFR141 value. !

t :o o o a

Swba 3 . e i"):

_ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ . . . - _ . . _ _ . _ . _ _ _ _ . _ . _ _ _ _ . _ . . _ . _ _ . _ . ~._ , , _ . _ . . . . _ . . _ - . , . . . , . . . . . _ . __

Table 5.1-3 i

Detection Carnhilities for Environmental Sanole Analysis andI *I IDI Lower Limit of Detection (L2D)

ETER TE FISH MILK FOOD PRODUCTS SEDIMENP AtaLYSIS(c) (pCi/l) AIRBORNEPARTICg/m)

OR GASES (pCi (pCi/kg, wet) (pCi/l) (pCi/kg, wet) (pCi/kg, dry) 0 -2 i

Gross Beta 4 x 10 1 x 10 H-3 2 x 103(d) 2 Mn-54 1.5 x 10 1 1.3 x 10 1 2 Fe-59 3 x 10 2.6 x 10 2

Co-58, 60 1.5 x 10 1 1.3 x 10 1 2 Zn-65 3 x 10 2.6 x 10 1

16-95 3 x 10 1

Zr-95 1.'S x 10 i

I-131 1 x 100(e) 7 x 10 -2 1 x 10 0 6 x 10 1

-2 2 1 1 2 Cs-134 1.5 x 10 1 5 x 10 1.3 x 10 1.5 x 10 6 x 10 1.5 x 10 1 -2 1.5 x 10 2

1.8 x 10 1

6 x 10 1

1.8 x 10 2 ,

Cs-137 1.8 x 10 ,6 x 10 Ba-140 6 x 10 1

6 x 10 1 . xyo La-140 ,

1.5 x 10 1 ,

1.5 x 10 1 3

,,... " 3 5

. ph (t

. if

. _ . _ _ . - . _ . _ - - - . _ . - _ . _ _ _ _ , _ . . _ __ _.____._ . _ _ , , , , . _ - - - - _ _ . _ . _ . . __ _, __ . _ . _ _ . . ~ - - , _ . _ . . . _ .

i e

Table 5.1-3 (Cont.)

Table !btations aRequired detection capabilities for thermoluninescent dosimeters used for environmental measurements shall be in accordance with the rectanendations of Begulatory Guide 4.13, except for specification regarding energy deparwianca.

{

Correction factors shall be provided for energy ranges not meeting the energy dependence specification.

he methodology for determining the HD is mntained in Appendix B.

c7his 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 Ehvironmental Operating Report pursuant to Specifimtion 6.9.1.6. For these radionuclides in 'mchnical Specification 'mble 4.12-1 which are not detected, the typical Has for the measurenent system will be separately reported in the annual report.

d If no drinking water pathway exists, a value of 3 x 10 3pCi/l may be used.

1

'If no drinking water pathway exists, a value of 1.5 x 10 pCi/l may be used.

i a

. i? 2 1 ,

l, M. .B. E

+

k

\

. 't '.

g, ',

.y .th

l NNW N NNE

NW i NE LEGEND:

l ' STATION NO. MEDIA DIRECTION l 3 TLD SE 4 AIR, TLD S 5 TLD SW WNW '

ENE 7 AIR, TLD NE 34, f Lockw od \R l

PERR NUCLEAR :,58 62 5 9 TLD ESE

/ 10 TLD SSE W

j 2 MILES 1 MILE e *

=

E

" 11 TLD SSW 12 5 12 TLD WSW

= .

4 SED,FSH A

E i 11 Ngrth[Perry 20 25 NNW

?-

10e V Hag WSW / ,

5 ["'

'3 ESE 34 WTR NW i

, ;; ali 35 AIR, TLD E c 0- = pte6\ # u' e g N 53 TLD WSW

'7 6 58 TLD ENE

% 5 =

a E 20 3 62 FP ENE SW . . 3

_ o. SE 77 pp a SSW S SSE 1 0 1 2 MILES 11

' i **

,o

't' .. ..

TECHNICAL SPECIFICATION REQUIRED REMP SAMPLING LOCATIONS WITHIN TWO MILES OF THE PLANT SITE -

, .' i i 1 l 7y' .' 'tI *,

NW NNW N NNE NE LEGEND:

f STATIOf" NO. MEDIA DIRECTION 7

1 AIR, TLD ENE WNW N s 5

13 14

' 15 TLD TLD TLD TLD ENE E

ESE WSW 4 ENE 21 23 TLD WSW 3 _

t . - -- 29 TLD SSE 1 30 TLD SSW l

{ @1311.! -

. 31 TLD SE g

1 61'\

" g- rf j'I $

r... 33 36 TLD WATER, TLD S

WSW

E

c7 m bN ,

(Yl?"[2 wg p 54 55 TtD TLD Sw S

23 !

)g 15 w

j 56 TLD ESE 7,

g < . E WSW ~ -

33 Ny ESE

% jf -

__D/p K

\ N e y/ m SW SSW m S vs SSE SE i 0 1 2 3 4 5 10 MILES I

,5 TECHNICAL SPECIFICATION REQUIRED REMP Ei,.l SAMPLING LOCATIONS BETWEEN TWO AND EIGHT MILES FROM THE PLANT SITE.

"o

.. :, s i t' i- .c 6 "yQ ,,

_ _ _ _ . _ _ _ _ _ _ . - _ _ _ . _ _ _ _ ---_.____a-__m_ - - _ _ _ _ _-- _ __a- - _ mm- e

n ie im vv is imc isc 1

WNW conn , ENE 28 tabula Genm/ < 2

LAKE E E ,,,,j"f, ,,,

9 pl Mad, son 45 unass On- ha-Lak #'

g./ M e

n f -a. ~"' @roO .. qp W Mi es ro wnion-n E y,yg@rlo '

- '"'4 ;cun ~

2 aint -

/ uent!rc the-La

., ain vil[

52' S TA cIE N p

?-

, 4 cormt Tir?,g,s ij"~ .ww

= P s ",7 g &"

w y Willowie go. - -

, R84mias Eucli W i ill ughby i ,, f* * " ' " - go, .. ,, tA O N .

Ander ; w WsW '"

Kirtland 70 il

,,N es w i. ,. F ' ne.

e cw Vality ESE Wil ou b a- 4" *No '

Brate t'

1 H IS Chard East i

, 4e (e) M**'~

' N n,,,6 Euc g. .it g 3, -' Orwell g; '

W 't, I s meerton _l Leckwood Gustavus sw ssw s ssE sE' 5 0 5 10 15 20 MILES LEGEND: '

STATION NO. MEDIA DIRECTION 1/8" = 1 MILE I

'6 AIR, TLD SSW 24 TLD g 8

SW 28 WATER ENE :o y o 32 FISH WSW TECHNICAL SPECIFICATION REQUIRED <: to 70 FP SSW REMP SAMPLING LOCATIONS GREATER THAN EIGHT MILES FROM THE PLANT SITE *3 "3

, ,, l{ : if i' - o z., ., p,, . . _ . _. . . _ . .. ._ .

l ODCM Page: 92 -

Rev.: 4 -

--. _ *. ~ , -

t Appendiit A Atmospheric Dispersion and Deposition Parameters O*

P

, p 4 .e.

d I

v 6

4

.- . - . - - - - - . .- .. .. ~

ODCM Page: 93 Rev.: 4 The atmospheric dispersion and deposition parameters used to calculate .-

gaseous effluent doses will be calculated using the following equations.

Dose calculations will be performed using hourly meteorological and effluent data. All atmospheric releases at PNPP are considered to be ground-level releases. -* --

a. Constant Mean Wind Direction Relative Dispersion Factor j

.fg , (2.12) (Tf) (g_g) . :

. (6) (x) (a) '

Where:

x/Q = the3 relative dispersion factor at ground level,.in ;

s/m ,

Tg = the terrain correction factor, from FSAR Table 2.3-26, dimensionless; 6 = the wind speed (measured at 10m), in m/s; l t

x = the distance of calculation, in m; f

2.032 = (2/N) divided by the width in radians of a 22.5' sector 2 '

2 H H i o = the lesser of a, c

+

, 2n, or (o z) (3 N) [

Where:

Hc = the building height (44.8m); -

.s o* = the vertical dispersion coefficient, per Regdlatory f jy- l Guide 1.111, in m.

b. Depleted Relative Dispersion Factor '

..,, ^!

x/0d = (x/Q)(DPLj ) (A-2) [

Where:

x/Q d = halogens and particulates), in s/m ;the depleted relative dispersi i

I l

l i .

=c..n - -

, - . - , - , , . ... c . . _ _ , , , . . . . . - . . . , . .. .._.,.

ODCH Page: 94 Rev.: 4 DPL. = the ground depletion factor for the "j'th distance,

~

J interpolated from Table A-1, dimensionless:

z/0 = the relative dispersion factor, per equation A-1.

n !a _

c. Ground Deposition D/Q =

i (A-3)

(0.3927) (x)

" Where:

D/Q = the relative deposition _ger unit area (for halogens and particulates), in m ;

DEP. = the ground deposition factor for tge 'j'th ilistance, 3 interpolated from Table A-1, in m' ;

Tg = terrain correction factor, from FSAR Table 2.3-26, dimensionless; x = the "j'th distance, in m; 0.3927 = radians per 22.50 sector l

I

^

~k, ,

J

i' ,

i l i Table A-1 .

j A % ric Depletion and DeDosition Factors i

Pasquill Distance (meters)

Stability 1,000 2,000 3,000 6,000 10,000 30,000 50,000 80,000 Class' 200 500 0.936 0.900 0.860 0.832 0.770 0.714 0.590 0.517 0.440 Depletion Factors (DPLj ) All 0.970 Deposition Factors (IEP 1.2SE-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 j )(m-) All e ',

ggo

!! E3 E ECll-j ,

'l sl- .t

, , s. ') ; ' !

j-l i, i ) i

'y ___ _ _ _ _ , _ _ _ _

.~ - . , - . .. ~ - . - -- - .. . . . - . - .

s f

ODCM Page: 96 Rev.: 4 ;

. f The following tables contain at.uual average atmospheric dispersion Long-term and releases ,

deposition parameters for long-term releases at PNPP. We highest annual :

are those that occur greater than 500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months per year. . ,

- l

, average relativeWconcentration (x/Q) value at the site bol e dispersion model used was XOQD00, with PNPP i

setpoint calculations. Dispersion ,

FSAR site-specific terrain adjustment factors included. ;

values are based on seven years of :neteorological data (May 1,1972 :

through. April 30, 1974 and Septer.ber 1, 1977 through August 31, 1982), l ground-level releases, sector spread for purge calculations, and twelve .

wind speed classes. I h

t l

l i

r

t p

~

..,c

. ., n -

'.~_' -

. j j

i I

l l

- i

~

1

. _ _ - . . _ . . _ . _ .__ _ .__ _ _ .. _ . ~ .

ODCM Page: 97 1 Rev.: 4 Table A-2 Site Boundary Atmospheric Dispersion (y/0) and Deposition Parameters (D/0) for PNPP Unit 1 SECTOR DISTANCE X/O D/O (MILES) (SEC. /.CUS. METER) (PER SG. METER)

N O.18 5.7E-05' 1.6E-07 NNE O ~~ 1.8E-05 7.9E-08 NE O. 5.8E-06 3.1E-08 ENE O. 6. 2.1E-06 1.6E-08 E O.67 2.2E-06 1.BE-08 ESE O.67 1.6E-06 1.3E-08 .

SE O.79 1.4E-06 1.1E-08 SSE O.82 2.2E-06 1.4E-08 S 0.81 2.7E-06 1.6E-OB SSW O.80 1.3E-06 6.8E-09 SW O.65 2.3E-06 1.1E-08 WSW O.56 4.2E-06 1.5E-08 W O.27 2.5E-05 4.6E-08 ~

WNW O.18 5.9E-05 8.4E-08 NW O.17 6.6E-05 1.1E-07 NNW O.17 5.9E-05 1.2E-07 f

I

ODCM ;

Page: 98 :

Rev.: 4 ;

i Table A-3 ;

Atmospheric Dispersion (r/0) as a Function of Distance (s/m ) :

~. C l t

SECfot 0. 2 0. 3 . O. 4 0. 5 . 0. 6 *!

l (MILES) (MILES) (MILES) (MILES) (MILES) l N 4. 904E-05 2. 453E-05 1. 525E-05 1. 057E-05 7. 918E-06 [

NNE 2. 656E-05 1. 360E-05 8. 640E-06 6. 082E-06 4. 612E-06 I l NE 1. 859E-05 9. 760E-06 6. 293E-06 4. 460E-06 3. 383E-06 EtaE 1.327E-05 7.129E-06 4.636E-06 3.293E-06 2.490E-06 i E 1. 363E-05 . 7. 362E-06 4. 760E-06 3. 367E-06 2. 538E-06 '

I ESC 1. 025E-05 5. 566E-06 3. 602E-06 2. 547E-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. 2BSE-05 1. 227E-05 7. 932E-06 5. 615E-06 4. 238E-06 ,

SSW 1.142E-05 6. 079E-06 3. 925E-06 2. 777E-06 2. 097E-06 !

SW 1. 449E-05 7. 663E-06 4. 928E-06 3. 479E-06 2. 622E-06 !

WSW 2.153E-05 1.111E-05 7. 031E-06 4. 934E-06 3. 733E-06 i W 4.184E-05 2. OBIE-05 1. 281E-05 8. 833E-06 6. 606E-06 l WNW 4. 669E-05 2. 298E-05 1. 401E-05 9. 573E-06 7. 093E-06 l NW 4. 909E-05 2. 423E-05 1. 482E-05 1. 015E-05 7. 521E-06 l NNW 4. 5BOE-05 2. 266E-05 1. 390E-05 9. 541E-06 7. OB3E-06 i

.i I 1 SEC70R O. 7 0. 8 0. 9 1. 0 1.1 3 (MILES) (MILES) (MILES) (MILES) (MILES)

N 6.138E-06 4. 968E-06 4. 203E-06 3. 636E-05~~1. 949E-06 ~.,_

NNE 3. 622E-06 2. 947E-06 2. 481E-06 2.132E-06 1. 278E-06c3 d- , -

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. 7,68E-07 - , _

ESE 1.501E-06 1.215E-06 1.010E-06 8.571E-07 5.' OBOE-07 l-SE 1. 647E-06 1. 334E-06 1.108E-06 9. 402E-07 4. 456E-07 SSE 2.796E-06 2.266E-06 1.885E-06 1.601E-06 5l524E-07 S 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 5. 223E-07 SW 2. 053E-06 1. 664E-06 1. 391E-06 1.1BBE-06 5. 667E-07 '

WSW 2. 927E-06 2. 380E-06 2. OO2E-06 1. 719E-06 8. 671E-07 I W '

. 5.110E-06 4.135E-06 3. SO4E-06 3. 036E-06 1. 630E-06 WNN 5.434E-06 4.37BE-06 3.719E-06 3.235E-06 1.945E-06 '

NW 5.764E-06 4.643E-06 3.941E-06 3.42SE-06 1.952E-06 NNW 5.439E-06 4.385E-06 3.720E-06 3.230E-06 1.839E-06f

ODCM Page: 99 Rev.: 4 Table A-3 (Cont.)

Atmospheric Dispersion (r/0) as a Function of Distance (s/m )

~.~~.'.,

3

1. 4 1. 5 1. 6

'; 5ECTOR. 1. 2 1. 3 .

(MILES)

(MILES) (MILES) (MILES) (MILES) ,

N 1. 729E-06 1. 54'9E-06 1. 399E-06 1. 273E-06 1.166E-06 NNE 1.128E-06 1. OO6E-06 9. 050E-07 8. 202E-07 7. 485E-07 NE 8.150E-07 7. 243E-07 6. 494E-07 5. 867E-07 5. 340E-07 ENE 5. 878E-07 5.'205E-07 4. 652E-07 4.190E-07 3. BO3E-07 E 5.917E-07 5.230E-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 i S 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 i SW 4. 976E-07 4. 417E-07 3. 955E-07 3. 570E-07 3. 246E-07 '

WSW 7.648E-07 6.814E-07 6.125E-07 5.547E-07 5.060E-07 l W 1. 44SE-06.1. 299E-06 1.175E-06 1. 070E-06 9. BO9E-07 '

WNW 1. 444E-06 1. 479E-06 1. 341E-06 1. 224E-06 1.124E-06 NW 1. 733E-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

1. 8 1. 9 2. O 2. 1 SECTOR 1. 7 (MILES)

(MILES) '( MILES ). (MILES) (MILES) ,

l

~

N 1. 074E-06 9. 931E-07 9. 226E-07 8. 604E-07 8. 052E-07 NNE 6.867E-07 6'.331E-07 5.864E-07 5.453E-07~5.090E-07 '_ r.

c NE 4. 886E-07 4. 494E-07 4.153E-07 3. 854E-07 3. 263E-07 '. c_ # -

ENE 3. 471E-07 3.184E-07 2. 936E-07 2. 718E-07 2. 526E-07 ' ^ 3 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 1.[ j SE 2. 26BE-07 2. 076E-07 .1. 91CC-07 1. 765E-07 1. 637E-07 ll l SSE 2. 827E-07 2. 590E-07 2. 384E-07 2. 205E-07 1. 407E-07 l

S 3.' 780E-07 3. 466E-07 3.194E-07 2. 955E-07 1. 373E-07 i SSW 2. 706E-07 2. 494E-07 '2. 290E-07 2.121E-07 1. 409E-07 SW 2. 968E-07 2. 727E-07 2. 518E-07 2. 335E-07 2.173E-07 WSW -

4. 639E-07 4. 275E-07 3. 957E-07 3. 67BE-07 5. 303E-07 W 9.037E-07 8.365E-07 7.777E-07 7.258E-07 1.050E-06 WNW 1.038E-06 9.622E-07 8.960E-07 8.375E-07 1.142E-06 NW 1.095E-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

i ODCM Page: 100 ,

Rev.: 4 i Table A-3 (Cont.) :

3 ;

Atmospheric Dispersion (y/0) as a Function of Distance (s/m )

~ ="

a

~'

2. 3

2. 4 2. 5 2. 6 !

SECTOR 2. 2 .

(NILES) (MILES) _ ;

(MILES) (MILES) (MILES) ,

j N 7. 560E-07 7.118E-07 6. 720E-07 6. 359E-07 6. 033E-07 NNE 4,766E-07 4. 477E-07 4. 217E-07 3. 982E-07 3. 770E-07 ,

NF 3. 050E-07 2. 859E-07 2. 688E-07 2. 534Er07 2. 395E-07 '

ENE

2. 356E-07 2. 205E-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. 628E-07 1. 525E-07 1. 433E-07 1. 351E-07 i SE 1. 524E-07 1. 424E-07 1. 334E-07 1. 253E-07 1.181E-07 SSE' 1. 311E-07 1. 225E-07 1.149E-07 1. 080E-07 1. 018E-07

~

5 1. 280E-07 1.197E-07 1.123E-07 1. 056E-07 9. 963E-08 '

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 i WSW 4. 964E-07 4. 661E-07 4. 388E-07 4.142E-07 3. 920E-07 W 9.867E-07 9,296E-07 8.780E-07 8.313E-07 7.891E-07 :

basi 1. 075E-06 1. 014E-06 9. 587E-07 9. 088E-07 8. 636E-07 i NW 7. 782E-07 7. 339E-07 6. 939E-07 6. 576E-07 6. 247E-07 l

NfM 7. 297E-07 6. 879E-07 6. 502E-07 6.161E-07 5. 852E-07 t

2. 9 3. O ~ 3.1 SECTOR 2. 7 2. 8 ~(MILES)

(MILES) (NILES) (MILES)

(MILES) l N 5.734E-07 5.460E-07 5.208E-07 4.976E-07 4.762E-07 i g'

NfdE Q. 376E-07 3. 398E-07 3. 235E-07 3. 086E-97 2. 948E-07 NE 2. 268E-07 2.152E-07 2. 046E-07 1. 949E-07 1. 859E ENE E.

1. 737E-07 1. 645E-07 1. 562E-07 1. 485E-07 1. 415E-07.7 ;

1. 560E-07 1. 477E-07 1. 401E-07 1. 331E-07 1. 267E-Ot t fll ESE 1.275E-07 1.207E-07 1.144E-07 1.087E-07 9.399E-08' 1.115E-07 1.054E-07 9.996E-08 9.493E-08 9.031E-08 7 SE i SSE 9. 613E-08 9. 099E-08 8. 630E-08 8. 200E-08 7. 80SE-08 '

S 9. 415E-08 8. 917E-08 8. 462E-08 8. 044E-08 7. 661E-08_

SSN 9. 697E-08 9.189E-08 8. 725E-08 8. 299E-08 7. 907E-OS '

SW 1. 50SE-07 1. 428E-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 W 7. 503E-07 7.147E-07 6. 820E-07 6. 519E-07 5. 874E-07 8 220E-07 7. 830E-07 7. 487E-07 7.164E-07 7. 722E-07 ,

WNu NW 3. 945E-07 5. 668E-07 5. 413E-07 5.178E-07 5. 412E-07 NNW 3. 567E-07 5. 307E-07 5. 067E-07 4. 846E-07 4. 642E-07

ODCM '

Page: 101 Rev.: 4 t

Table A-3 (Cont.) -

Atmospheric Dispercien (t/0) as a Function of Distance (s/m )

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. E20E-07 2. 702E-07 2. 592E-07 2. 489E-07 2. 395E-07 i NE 1. 77?E-07 1. 700E-07 1. 629E-07 1. 562E-07 1. 501E-07 .

ElJE 1. 350E-07 1. 290E-07 1. 234E-07 1.182E-07 1.135E-07 i E 1. 208E-07 'i.154E-07 1.103E-07 1. 056E-07 1. 013E-07 '.

.ESE 8. 95BE-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 , 1 S 7. 307E-08 6. 980E-08 6. 67BE-08 6. 395E-08 6.136E-08 '

I SSW 7. 546E-08 7. 212E-08 6. 902E-08 6. 613E-08 6. 348E-08 '

SW 1.176E-07 1.125E-07 1. 077E-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 l WI4W 7. 409E-07 7.118E-07 6; 84BE-07 6. 593E-07 6. 359E-07 !

iM 5.192E-07 4. 987E-07 4. 797E-07 4. 618E-07 4. 454E-07 .

N!r.f 4. 452E-07 4. 276E-07 4.112E-07 3. 958E-07. 3. 817E-07 i t

SECTOR 3. 7 3. 8 3. 9 4. O 4.1 -

(MILES) (MILES) (MILES) (MILES) (NICES) l l N 3. 759E-07 3. 628E-07 3. 504E-07 3. 388E-07 EC981E'-07'. ;

NMF. 2. 336E-07 2. 222E-07 2.144E-07 2. 070E-07 1. 819E-07 .

NE 1. 44 4E-07 1. 390E-07 1. 339E-07 1. 292E-07 1. 247E-07 '.p'- C - -

ENE 1. 090E-07 1. 048E-07 1. 009E-07 9. 718E-08 9. 373E-08 I

E 9. 722E-08 9. 342E-OB 8. 987E-08 8. 653E-08 8. 341E-08 i.,

ESE 7.196E-08 6. 912E-08 6. 647E-08. 6. 399E-08 6.166E-OS %

SE 6. 908E-08 6. 635E-08 6. 380E-08. 6.140E-08 5. 378E-08

SSE 5. 987E-08 5. 753E-OB 5. 533E-08 5. 328E-08 5.135E-08 S

5. 892E-08 5. 664E-08 5. 451E-08 5. 251E-OB 5. 063E-08 l SSW 6. 09BE-08 5. 865E-08 5. 646E.-08 5. 441E-08 5. 248E-08 SW 9. 537E-08 9.178E-08 8. 841E-08 8. 525E-08 8. 228E-08 WSW 1. 967E-07 1. 896E-07 1. 028E-07' t. 765E-07 1. 462E-07 W . 4. 646E-07 4. 485E-07 4. 334E-07 4.191E-07 3. 043E-07 I Wic.J 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. 883E-07 3. 761E-07 i NN'.J 3. 682E-07 3. 556E-07 3. 43BE-07 3. 326E-07 2. 928E-07 l l

ODCM Page: 102 Rev.: 4 Table A-3 (Cont.) -

Atmospheric Dispersion (r/0Nf'a Function of Distance (s/m )

~

45' SECTOR 4. 2 / 4. 3 -

4. 4 4. 6 (MILES) (MILES) (MILES). (MILES) (MILES) ,

~

l N . 2.887E-07 2.798E-07 2.714E-07 2.634E-07 2.559E-07 I NNE 1.759E-07 1.703E-07 1.650E-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 E 8.046E-08 7.769E-08 7.508E-08 7.260E-08 7.030E-08 ESE 5. 946E-08 5. 740E-08 5. 545E-08 5. 361E-08 5.189E-08 l l SE 5.196E-08 5. 005E-08 4. 835E-08 4. 673E-08 4. 523E-08 ' i 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 SEW 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 WSW 1.413E-07 1.36BE-07 1.325E-07 1.284E-07 1.246E-07 ;

W 2.948E-07 2.85BE-07 2.773E-07 2.691E-07 2.616E-07 '

band 4.051E-07 3.930E-07 3.815E-07 3.706E-07 3.603E-07' '

NW 3. 645E-07 3. 536E-07 3. 432E-07 3. 333E-07 3. 241E-07 :

NrJW 2. 937E-07 2. 752E-07 2. 671E-07 2. 593E-07 2. 521E-07 ,

1 i

SECTOR , 4. 7 4, 8 4. 9 5. O I (MILES) (MILES) (MILES) (MILES) ,

7 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 [ ,,

NE 1.028E-07 9.975E-08 9.689E-08 9.416E-08 -

ENE 7. 676E-08 7. 4 43E-08 7. 223E-08 7. 014E-08 ,,_

-fe .7 '

E 6.809E-08 6.600E-08 6.402E-08 6.214E-08 f' ESE 5.025E-08 4.869E-08 4.722E-08 4.582E-08 l< ,,, ,

SE 4. 379E-08 4. 244E-08 4.115E-08 3. 992E-08 . >.' ,

4.191E-08 4: 063E-08 3. 941E-08 3. 825E-08 SSE !

S 4.141E-08 4. 015E-08 3. 896E-08 3. 782E-08 .

SSW 4.302E-08 4.173E-08 4.050E-08 3.934E-08 : ,

Su . 6.767E-08 6.567E-08 6.377E-08 6.196E-08 '

~

WSU 1.210E-07 1.175E-07 1.142E-07 1.110E-07 ,

W 2. 543E-07 2. 474E-07 2. 408E-07 2. 34SE-07

~

JaJ

3. 505E-07 3. 411E-07 3. 322E-07 3. 237E-07 NW 3.152E-07 3.06BE-07 2.987E-07 2.910E-07 :

NNW 2 452E-07 2 336E-07 2.323E-07 2.263E 107 ,

, t

ODCM Page: 103 Rev.: 4 Table A-4

~

Atmospheric Dispersion (D/Q) as a Function of Distance (m-)

- s. ,

0. 5 O. 6

0. 3 O. 4 SECTOR O. 2 .

(MILES) (NILES) -

(MILES) (' MILES ) ,

(MILES)

N 1.396E-07 7.578E-08 4.836E-08 3.383E-08 2.516E-08 )

NNE 1.107E-07 6. 008E-08 3. 834E-08 2. 682E-08 1. 995E-0 ,

NE 9. 733E-08 5. 284E-08 3. 372E-08 2. 359E-08 1. 755E-0 i ENE 1. 067E-07 5. 795E-08 3. 698E-08 2. 587E-08 1. 924E- : i E 1.184E-07 6. 429E-08 4.103E-08 2. 870E-08 2.135E-08 ESE 8. 865E-08 4. 813E-08 3. 071E-08 2.149E-08 1. 598E-0 SE 9. 402E-08 5.105E-08 3. 258E-08 2. 279E-08 1. 695E-08 SSE 1.338E-07 7.266E-08 4.637E-08 3.244E-08 2.413E-08 S 1.429E-07 7.757E-08 4.951E-08 3.463E-08 2.576E-08 SSW 6. 094E-08 3. 309E-08 2.111E-08 1. 477E-08 1. 099E-0 SW 7.267E-08 3.945E-08 2.518E-08 1.761E-08 1.310E-08 {

WSW 7.117E-08 3. 864E-08 2. 466E-08 1. 725E-08 1. 283E-0 7.129E-08 3.870E-08 2.470E-08 1.728,E-08 1.285E-08 i

J W

wNW 6. 970E-08 3. 784E-08 2. 415E-08 1. 689E-08 1. 256E-0 ;

NW 8 904E-08 4.834E-08 3.085E-08 2.~158E-DB 1.605E-0 9.623E-08 5.225E-08 3.334E-08 2.332,E-08 1.735E-08 NNN >

i .

l 0. 9 1. 0 1.1

0. 7 0. 8 (MILES)

SECTOR (MILES) (MILES) (MILES) .

(MILES)

~

N 1. 954E-08 1. 560E-De 1. 277E-08 1. 068E-08-5. 545E-09. ..- l NNE 1.549E-08 1.237E-08 1.013E-08 8.465E-09 4.945E-09. o e NE 1. 362E-08 1. 088E-08 8. 907E-09 7. 445E-09 4. 350l ENE 1,494E-08 1.193E-08 9.768E-09 8.164E-09 4.770E-09 ; j~t,,. ~

l l

E 1. 65BE-08 1. 323E-08 1. OS4E-08 9. 058E-09 5 292E-09 >-

ESE 1.241E-08 9.905E-09 8.112E-09 6.781E-09 3.961E-09 SE 1. 316E-08 1. 051E-08 8. 605E-09 7.192E-09 3. 361E-09 SSE

~

1. 874E-08 1. 496E-08 1. 225E-08 1. 024E-08 3. 480E-09 .

i S 2.000E-08 1.597E-08 1.30SE-08"1.093E-08 4.128E-09 -

SSW 8. 531E-09 6. 810E-09 5. 577E-09 4. 662E-09 2. 521E-09 SW 1.017E-08 8.120E-09 6.651E-09 5.559E-0? 2.598E-09 i wSW 9. 963E-09 7. 953E-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 www

9. 757E-09 7. 788E-09 6. 379E-09 5. 332E-09 2. 932E-0 NW 1. 246E-08 9. 949E-09 8.148E-09 6. 811E-09 7.361E-09 3. 745E-09 4.047E-09 Nrtw 1.347E-08 1.075E-08 8.807E-09 l

4

i ODCM Page: 104 Rev.: 4 ,

Table A-4 (Cont.)

l Atmospheric Deposition (D/0) as a Punction of Distance (m~2)

~'

~ IIS 1. 6 -

1. 3 1. 4 SEC70R 1. 2 .

(MILES) (MILES) . ,

(MILES) (MILES) f

~

(MILES) .

4 777E- 09 4.163E-09 3. 664E-09 3. 252E-09 2. 910E-O9 l N '

NNE 4. 260E-09 3. 713E-09 3. 268E-09 2. 900E-09 2. 595E-09 j

3. 747E-09 3. 265E-09 2. 874E-09 2. 531E-09 2. 283E-09 NE .

4.109E-09 3. 593 E-09 3,151E-09 2. 797E-09 2. 503E-09 ENE ;

E 4. 559E-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 <

SSE 2. 99BE-09 2. 612E-09 2. 299E-09 2. 041E-09 1. 826E-09

3. 556E-09 3. 099E-09 2. 7E,J-39 2. 421E-09 2.166E-09 S ,

SSN 2.172E-09 1. 892E-09 1. 666E-09 1. 478E-09 1. 323E-09 SH 2. 23SE-09 1. '950E-09 1. 717E-09 1. 524E-09 1. 363E-2, 307E-09 2. 011E-09 1. 770E-09 1. 571E-09 1. 406E-09 WSW N 2. 440E-09 2.126E-09 1. 871E-09 1. 661E-09 1. 486E-09 WNW 2. 325E-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 2.' 124E-09 NNW 3. 437E-09 3. 039E-O? 2. 674E-09 2. 374E-09

. 1 g,9 2. 0 2.1 3, g SECTOR g,7 (MILES) (MILES) i (MILES) (MILES) (MILES) I N 2, 619E-09 2. 371E-09 2.158E-09 '1. 973E-09,1. 812E-09 NNE 2.336E-09 2,115E-09 1.925E-09 1.760E-09 1.616E-09

~

NE 2. 055E-09 1. 860E-09 1. 693E-09 1. 548E-09 1. 292E-0 '

ENE

2. 253E-09 2. 040E-09 3. 856E-09 1. 697E-09 1. 558E-09. ;?-s. '

2. 500E-09 2. 263E-09 2. 059E-09 1. 983E-09 1. 572E-09 ~

E ESC 1. 871E-09 1. 694E-09 1. 542E-09 4. 410E-09 1. 294E-09 .," ~

SE

1. 58BE-09 1. 437E-09 1. 30BE-09 1.196E ,09 1. 098E-09 ,

SSE 1. 644E-09 1. 488E-09 1. 354E-09 1. 238E-D9 7. 816E-10 I

. S 1. 950E'-09 1. 765E-09 1. 606E-09 1. 469E-09 6. 743E-10 SSW 1.191E-09 1. 078E-09 9. 810E-10 B. 969E-10 5. 883E-10 >

SW 1. 227E-09 1.111E-09 1. 011E-09 9. 244E-10 B. 4BSE-10 I WSW

1. 265E-09 1.145E-09 1. 042E-09 9. 530E-10 1. 352E-09 W 1. 338E-09 1. 211E-09 1.102E-09 1. 008E-09 1. 430E-09 W:.*W 1. 385E-09 1. 254E-09 1.141E-09 1.043E-09 1.393E-09 NW 1.769E-09'1.601E-09 1.457E-09 1.333E-09 1.223E-09 NNW 1.912E-09 1.731E-09 1.573E-09 3.440E-09 1.322E-09 1

ODCM Page: 105 Rev.: 4 Table A-4 (Cont.)

~

Atmospheric Deposition (D/0) ad.a Function of Distance (m )

s .;

.-s SEMOR 2. 2 2. 3 . 2. 4 2. 5 2. 6 l-(MILES) (MILES) (MILES) (MILES) (MILES) i

(.

N 1. 670E-09 1. 544E-09 1. 433E-09 1. 334E-09 1. 245E-09 NNF 1.489E-09 1.377E-09 1.278E-09 1.189E-09 1.110E-09 NE' 1.191E-09 1.101E-09 1. 022E-09 9. 511E-10 8. 879E-10 ENE 1. 436E-09 1. 328E-09 1. 233E-09 1.147E-09 1. 071E-09 E 1. 449E-09 1. 340E-09 1. 243E-09 1.157E-09 1. OBOE-09 ESE 1.193E-09 1.103E-09 1. 024E-09 9. 52BE-10 8. 895E-10 i SE . 1.012E-09 9.362E-10 B.687E-10 8.085E-10 7.548E-10 !

SSE 7. 204E-10 6. 663E-10 6.183E-10 5. 754E-10 5. 372E-10 l S 6.215E-10 5.749E-10 5.334E-10 4.964E-10 4.634E-10 l SSW 5.422E-10 5.015E-10 4.653E-10 4.331E-10 4.043E-10 SW 7.823E-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-1.0 \

W 1.318E-09 1 219E-09 1.131E-09 1.053E-09 9.827E-10 1 WNW 1. 28 4E-09 1 188E-09 1.102E-09 1.026E-09 9.575E-10 i NW 1.128E-09 1. 043E-09 9. 678E-10 9. OO7E-10 8. 409E-10 i NNW 1.219E-09 1.127E-09 1.045E-09 9.735E-10 9.089E-10 i i

t SECTOR 2. 7 2. 8 2. 9 3. 0 3. 1 (MILES) (MILES) (MILES) (MILES) ? MILES) -

N 1.165E-09 1.092E-09 1.026E-09 9.666E-10 9 120E-10 "

NME 1. 03?E-09 9. 742E-10 9.155E-10 9. 621E-10 8.~134E-10 ' - t ';

NE B. 307E-10 7. 789E-10 7. 320E-10 6. 893E-10 6. 504E-10 -

ENF 1.OO2E-09 9.396E-10 8.830E-10 8.315E-10 7.845E-10 57-E - 1.011E-09 9.477E-10 8.906E-10 9.387E-10 7.913E-10 ESE 8.322E-10 7.804E-10 7.334E-10 6.906E-10 5.923E-10 ;7

~

SE 7.061E-10 6.622E-10 6.223E-10 5.860E-10 5.529E-10 -

j SSE' 5. 026E-10 4. 713E-10 4. 429E-10 4.171E-10 3. 935E-10 ;

i S 4. 336E-10 4. 066E-10 3. 821E-10 3. 598E-10 3. 395E-10 i SSW 3.782E-10 3.547E-10 3.333E-10 3.139E-10 2.961E-10 SW 3. 458E-10 5.118E-10 4. 810E-10 4. 529E-10 4. 273E-10 i ;

WSW 8.695E-10 8.154E-10 7.663E-10 7.216E-10 5.607E-10 l W 9.194E-10 a. 621E-10 B.102E-10 7. 630E-10 6. 775E-10 WNW 8.958E-10 8.400E-10 7.894E-10 7.434E-10 7.090E-10 NW 7.867E-10 7.377E-10 6.933E-10 6.528E-!O 6.719E-10 N!!W 8.503E-10 7.973E-10 7.493E-10 7.056E-10 6.657E-10 I

1 ODCH Page: 106 Rev.: 4 i

Table A-4 (Cont.)

Atmospheric Deposition (D/0) as a Function of Distance (m" )

. ::.f.,

SECTOR 3. ! 3. 3 . 3. 4 . 3. 5 3. 6 .

(MILES) (MILES) (MILES) (MILES) (MILES)

N 8.620E-10 8.161E-10 7.739E-10 7.347E-10 6.991E-10 ANE 7. 6BSE-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 4.985E-10 l ENE 7. 415E-10 7. 020E-10 6. 657E-10 6. 320E-10 6. 014E-10 E 7.479E-10 7.OB1E-10 6.714E-10 6.374E-10 6.066E-10 ESE 5. 59BE-10 5. 3OOE-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 i j l SSE 3. 719E-10 3. 521E-10 3. 339E-10 3.170E-!O 3. 016E-10 .

l 1

i S 3.209E-10 3.038E-10 2.BBOE-10 2.735E-10 2.602E-10 j SSW 2. 799E-10 2. 650E-10 2. 513E-10 2. 386E-10 2. 270E-10 l SW 4.039E-10 3.824E-10 3.626E-10 3.442E-10 3.276E-10 j 1 WSW -5.299E-10 5.017E-10 4,757E-10 4.516E-10 4.298E-10 j .

W' 6.403E-10 6.062E-10 5.749E-10 5.458E-10 5.193E-10 j LMJ 7. 457E-10 7. 060E-10 6. 695E-10 6. 356E-10 6. 04BE-10 ff.4 6. 351E-10 6. 013E-10 5,702E-10 5. 413E-10 5.151E-10 ,

NNW 6.292E-10 5.957E-10 5.649E-10 5.363E-10 5.103E-10 i

- i SECTOR 3. 7 3. 8 3. 9 4. O 4.1 (MILES) (MILES) (MILES) (MILES) , (MILES) I

- - ~ '

N 4. 657E-10 6. 347E-10 6. 059E-10 5. 791E-10 5. 036E-10 -h. h 'i NNE 5.937E-10 5.661E-10 5.404E-10 5.165E-10 4.492E-10 ?

NE *

4. 747E-10 4. 5262-10 4. 321E-10 4.129E-10 3. 951E-10 l ENt:.

E 5.727E-10 5.460E-10 5.212E-10 4.981E-10 4.766E-10

5. 776E-10 5. 507E-10 5. 257E-10 5. 024E-10 4. 807E-10 7l-ESE 4.324E-10 41122E-10 3.935E-10 3.761E-10 3.598E-10 SE 4. 036E-10 3. 84BE-10 3. 673E-10 3. 510E-10 3. 053E-10 :.

SSE 2. 872E-10 2. 739E-10 2. 614E-10 2. 49BE-10 2. 390E-10 t i

S 2.478E-10 2.363E-10 2.255E-10 2.155E-10 2.062E-10 SSW 2.162E-10. 2. 061E-10 1. 968E-10 1. BBOE-10 1. 799E-10 SW 3.119E-10 2.974E-10 2.839E-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.OB7E-10 l WNW 3. 759E-10 5. 491E-10 5. 242E-10 5. O!OE-10 3. 728E-10 i t."4 4. 905E-10 4. 677E-10 4. 464E-10 4. 266E-10 4. OB2E-10 i ,

NNW 4. 859E-10 4, 633E- 10 4. 423E-10 4. 227E-10 3. 676E-10 ;

i ODCM Page: 107 Rev.: 4 Table A-4 (Cont.) -

Atmospheric Deposition (D/0) as a Function of Distance (m~ ) ,

t

^

SECTOR 4. 2 4. 3 . 4. 4 . a. 5

~

4. 6 2 (MILES) (MILES) (MILES) (MIL'ES ) (M!LES) -

N 4.623E-10 4.624E-10 4.437E-10 4.260E-10 4.097E-10 NNE 4.302E-10 4.124E-10 3.957E-10 3.800E-10 3.654E-10 NE 3.784E-10 3.627E-10 3.480E-10 3.342E-10 3.214E-10 ENE . 4.564E-10 4.375E-10 4.19EE-!O 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.;303E-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 1.975E-10 1.893E-10 1.8176-10 1.744E-10 1.677E-10 1.723E-10 1.652E-10 1.585E-10 1.522E-10 1.463E-10 SSN SW 2.486E-10 2.333E-10 2.287E-10 2.196E-10 2.112E-10 i WSW 2.796E-10 2.690E-10 2.572E-10 2.469E-10 2.375E-10 i W 2.956E-10 2.834E-10 2.719E-10 2.611E-10 2.511E-10 i WNW 3.570E-10 3.422E-10 3.284E-10 3.153E-10 3.032E-10 l NW 3.909E-10 3.747E-10 3.596E-10 3.453E-10 3.320E-10 i NMW 3.521E-10 3.375E-10 3.239E-10 3.110E-10 2.991E-10 l SECTOR

4. 7 4. 8 4. 9 5. 0 (MILES) (MILES) (MILES) (MILES)

N 3.941E-10 3.795E-10 3.656E-10 3.525E-10 Nfd: 3.515E-10 3.384E-10 3.261E-10 3.144E-10h .,

NE 3. 092E-10 2. 977E-10 2. 86BE-10 2. 765E-10 7 -

ENE 3.729E-10 3.591E-10 3.460E-10 3.336E-10 ' e. C E 3.762E-10 3.622E-10 3.489E-10 3.364E-10 L' ESE 2.816E-10 2.711E-10 2.612E-10 2.51fE-10 !,. .

EL 2. 399E-10 2. 300E-10 2. 216E-10 2.137E-10 h SSE 1.871E-10 1.E01E-10 1.735E-10 1.673E-10 i E 1.614E-10 1.554E-10 1.497E-10 1.443E-10 SSN 1.40BE-10 1.355E-10 1.306E-10 1 259E-10 SW 2.031E-10 1.956E-10 1.894E-10 1.817E-10 WSW 2. 285E-10 2.199E-10 2.119E-10 2. 043E-10 u 2.415E-10 2.326E-10 2.241E-10 2.160E-10 beaJ 2. 917E-10 2. BO9E-10 2. 706E-10 2. 609E-10 NW 3.194E-10 3.075E-10 2.963E-10 2.857E-!O l NRW 2. 877E-10 2. 770E-10 2. 669E-10 2. 573E-10 !

l

ODCM Page: 108 Rev.: 4 Appendix B Iower Timit of Detection W e ew .e

- '*g P '

'a.5 ,

r* f k

1 1

ODCM Page: 109 Rev.: 4 The lower limit of detection (LLD) is the smallest concentration of _.

radioactive material in a sample that will be detected with a 95 percent j probability with a 5 percent probability of falsely concluding that a (

l- blank observation represents a "real' signal. )

-: ~;; *. -

1

\ ~

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 ". 4 sample (or blank sample) is subtracted from the gross sample count to obtain a net count due to samle activity:

b N b (B-1) 3.3 ,

D

' s bd ED=

(C)(E)(V)(Yc ) eXp (-1 At) l Where:

LLD = the "apriori' lower limit of detection, as defined above; C = the conversion factor of transformations per unit time per uCi or pCi; E = the detector efficiency; r = the background count rate in units of tranaformations per b unit time; t = the counting time of background; b

t = the counting time of the sample; 3

V = the sample size, in units of mass or volume; .

Y = the fractional radiochemical sample collection or .;-

e concentration yield (when applicable); -?

1 I

At = for plant effluents, the elapsed time between the .,.

midpoint of sample collection and time of counting; for W environmental samples, the elapsed time between sample . l collection (or end of the sample collection period) and time of counting; .

1 = the radioactive decay constant for the radionuclide in question.

b . . .

. ..l

i ODCM Page: 110 Rev.: 4 ,

For the purpose of routine analyses, cou .es for both the sample (s) .

and background (s) are equal. This satis. .. che given Technical Specification lower limit of detection definition, as the numerator of equation B-1 simplifies to 4.66 S g where S is the standard deviation of the background count rate or the count rate bof a blank s.angis 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) limit for a particular measurement.

For gamma ray spectroscopy analyses:

L D

exp (0.693 At/t H)

(C)(E)(t)(V)(Y g)(Yy) _

Where:

LLD = the lower limit of detection, in pCi or pCi per unit mass or volume; C = the conversion factor of transformations per unit time per pCi or pCi; -

E = the detector efficiency for the energy in question; t = the data collection (counting) time of sample; t H = 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 c concentration yield (when applicable); ,

Yy = the yield of the ganna ray in question; h . _

At = for plant effluents the elapsed time between midpoint of - 5 9" sample collection and time cf counting; for environmental .

samples, the elapsed time between sample collection (or .,_

end of the sample collection period) and the time of 9 counting; 5 L

D

= the detection limit 2'H

=k 2 + 2k (1+[) (B y + B2 I + I + "I (B-2a) 4

ODCM Page: 111 Rev.: 4 Where: .

B the number of counts in 'n' background channels below the y = peak due to Compton scattering, etc., determined at the same time a photopeak is measured; ..*. i B

2 = the

'n' background channels above the number peak; of counts in the k = an abscissa of the normal distribution corresponding to confidence level,

= 1.645 at a confidence level of 95t; 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 interest; oy = 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 gama-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 Perry Nuclear Power Plant kill J.-

be achieved under routine conditions. Occasionally, background fluctuations, unavoidably small sample sizes, the presence of interfering T'-T-nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors will be identified and described in the Annual Radiological Environmental Operating Report

'I.

or the Semiannual Radioactive Effluent Release Report.

l l

l

ODCM Page: 112 Rev.: 4 REFERENCES -

1. Title 10, " Energy,' Chapter 1, Code of Federal Regulations; Part 20, U.S. Government Printing Office, Washington, D.C. 20402, ;_

January 1, 1984.

2. Title 10, " Energy,' Chapter 1, Code of Federal Regulations; Part 50; 1 U.S. Government Printing Office, Washington, D.C. 20402, January 1, 1984.

3. Title 40, " Protection of Environment,' Chapter 1, Code of Federal Regulations, Part 190, Federal Register, Vol. 42, Washington, 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, Washington, D.C. 20555, October, 1981.

5. U.S. Nuclear Regulatory Comission, " Draft Radiological Effluent Technical Specifications for PWR's,' USNRC NUREG-0473, Revision 2, Washington, D.C. 20555, February, 1980.

6. Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants,' Revision 1, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, June 1974.

7. Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for theRevision Purpose0,ofU.-S.Evaluating Nuclear Compliance with 10CFR Part 50, Appendix 20555, I,' March 1976. l Regulatory Commission, Washington, D.C.

8. Regulatory Guide 1.109, ' Calculation of Annual Doses to H'an from Routine Releases of Reactor Effluents for theRevision Purpose1,ofU.S.Evaluating Nuclear Compliance with 10CFR Part 50, Appendix I,*

20555, October 1977. ~ ~.-

Regulatory Commission, Washington, D.C. -n -

9. Regulatory Guide 1.111, ' Methods for Estimating Atmospheric 'f' 1f*-

Transport and Dispersion of Gaseous Effluents in Routine Releases .,

from Light-Water-Cooled Reactors," Revision 1, U.S.

20555, JulyNuclear 1977. v-Regulatory Commission, Washington, D.C.

10. Regulatory 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, Washington, D.C. 20555, April 1977.

l

ODCM Page: 113 - LAST Rev.: 4 REFERENCES (Cont.)

11. Regulatory Guide 4.15, " Quality Assurance for Radiological Monitoring Programs (Normal Operation) - Effluent Strutuas and the _.

Environment," U.S. Nuclear Regulatory Commission, Washington, D.C.

20555, February 1979. ,

12. U.S. Nuclear Regulatory Consnission, " Branch Technical Position,"

Revision 1, Washington, D.C. 20555, November 1979.

13. Perry Nuclear Power Plant, Unit 1 and 2, " Final Safety Analysis Report,' Amendment 14, %e Cleveland Electric Illuminating Company, Perry, Ohio 44081, August 1984.

14. Perry Nuclear Power 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 Power Plant, Units 1 and 2, " Radiological Environmental Monitoring Program Manual,' he 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, Lowe and Garrick, Washington, D.C. 20036, July 1983.

17. Kocher, D.C., " Radioactive Decay Data Tables,* Technical Information Center, U.S. Department of Energy, Springfield, Virginia 22161, September 1985. l "

18. 1989 Engineering Report " Lake Erie Potable Water Facilities and Intakes within 50 Miles of PNPP, (Ref. S0-11552 'E').

19. Perry Environnental Report Operating License Stage, T Gle 5.1-10

' Annual Average Dilution Factors for Lake Water Intakes within

7.. .

50' Miles of PNPP and Q&R Page 2.1-2.

20. PNPP Ohio Power Siting Commission application of August 1974, k'f- '

~

Appendix 1304-C-2, Table IV-A-2.

21. Total Angler Catch (1987 annual) for Each Grid Location; per letter i from Michael R. Rawson, Fairport Fisheries Research Station, Ohio Department of Natural Resources (6-20-88).

4 4

PY-CEI-NRR-1948, Annual Radioactive Effluent Release Rept 1994:Quarter 1-4

Contents

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SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

10.0 REFERENCES

1.0 INTRODUCTION

1.0 INTRODUCTION

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PY-CEI-NRR-1948, Annual Radioactive Effluent Release Rept 1994:Quarter 1-4

Text

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

10.0 REFERENCES

1.0 INTRODUCTION

1.0 INTRODUCTION

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