Text

Semiannual Radioactive Effluent Release Rept,Jul-Dec 1985
	ML20153H561
Person / Time
Site:	Waterford
Issue date:	12/31/1985
From:	Cook K; LOUISIANA POWER & LIGHT CO.
To:	Martin R; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
	RTR-NUREG-1117 W350004H, W3P86-0040, W3P86-40, NUDOCS 8603030212
	Download: ML20153H561 (150)
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Semiannual Radioactive Effluent Release Report CD p'?;<', :x.

July 1, 1985 - December 31, 1985 ,

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c TABLE OF CONTENTS 1.0 SCOPE 2.0 SUPPLEMENTAL INFORMATION 2.1 Regulatory Limits 2.2 Maximum Permissible Concentrations 2.3 Average Energy 2.4 Measurements and Approximations of Total Radioactivity 2.5 Batch Releases 3.0 GASEOUS EFFLUENTS 4.0 LIQUID EFFLUENTS 5.0 SOLID WASTES 6.0 METEOROLOGICAL DATA 7.0 ASSESSMENT OF DOSES 7.1 Dose at Site Boundary 7.2 Dose to the Critical Receptor 7.3 Doses due to Liquid Effluents 7.4 40 CFR 190 Dose Evaluation 7.5 Doses to Public inside the Site Boundary 8.0 RELATED INFORMATION 8.1 Changes to the Process Control Program 8.2 Changes to the Offsite Dose Calculation Manual 8.3 Unavailability of REMP Milk Sampling 8.4 Report of Technical Specification Required Instrument Inoperability 9.0 TABLES ,

10.0 ATTACRMENTS W350004H 1

l 1.0 SCOPE l

This Semi-Annual Release Report is submitted as required by Louisiana Power and Light's Waterford 3 Technical Specification 6.9.1.8. It covers l

the period from July 1, 1985 through December 31, 1985.

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Included in this report is a summary of the quantities of radioactive liquid and gaseous effluents and solid wastes released from the plant for the reporting period. In addition, a summary of the meteorological data l and results from the assessment of radiation doses due to the release of liquid and gaseous radioactive effluents, is reported for the entire 1985 year.

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Information in this report is presented in the format outlined in Appendix B of Regulatory Guide 1.21.

Other required information in this report includes: (1) explanation of why certain instrumentation was not restored to operable status within the time spec'ified in the ACTION Statement, as per Waterford 3 SES Tech-nical Specification 3/4.3.3.11; and, (2) changes to the Off-Site Dose Calculation Manual.

2.0 SUPPLEMENTAL INFORMATION 2.1 Regulatory Limits Specified as follows are the technical specification limits applicable to the release of radioactive material in liquid and gaseous effluents.

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E 2.1.1 Fission and Activation Gases (Noble Gases)

The dose rate due to radioactive noble gases released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to less than or equal to 500 mrem /yr to the total body and less than or equal to 3000 mrem /yr to the skin.

The air dose due to noble gases released in gaseous effluents from the site areas at or beyond the site boundary shall be limited to the following:

a. During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and,

b. During any calendar year: Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

2.1.2 Iodines; Particulates, llalf Lives > 8 Days; and Tritium The dose rate due to iodine 131 and 133, tritium, and all radionuclides in particulate form with half lives greater than eight (8) days, released in gaseous effluents from the site to areas at and beyond the site boundary, shall be limited to less than or equal to 1500 mrem /yr to any organ.

The dose to a member of the public from Iodine 131 and 133, tritium, and all radionuclides in particulate form with half lives greater than eight (8) days in gaseous effluent s released to areas at and beyond the site boundary shall be limited to the following:

a. During any calendar quarter: Less than or equal to 7.5 mrem to any organ and, W350004H 3

b. During any calendar year: Less than or equal to 15 mrem to any organ.

2.1.3 Liquid Effluents The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to the concentrations specified in 10CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-4 pCi/ml total activity.

The dose or dose commitment to a member of the public from radioactive materials in liquid effluents released to unrestricted areas shall be limited:

a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and less than or equal to 5 mrem to any organ, and

b. During any calendar year to less than or equal to 3 mrem to the whole body and to less than or equal to 10 mrem to any organ.

2.1.4 Uranium Fuel Cycle Sources 1

The dose or dose commitment to any member of the public due to releases of radioactivity and radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 mrem) over 12 consecutive months.

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r 2.2 Maximum Permissible Concentrations 2.2.1 Fission and Activation Gases; Iodines; and Particulates, Half Lives > 8 Days For gaseous effluents, maximum permissible concentrations are not directly used in release rate calculations since the applicable limits are expressed in terms of dose rate at the site boundary.

2.2.2 Liquid Effluents The maximum permissible concentration (MPC) values specified in 10CFR20, Appendix B, Table II, Column 2 are used as the permissible concentrations of liquid radioactive effluents at the unrestricted area boundary. A value of 2.0E-4 pCi/ml is used as the MPC for dissolved and entrained noble gases in liquid effluents.

2.3 Average Energy This is not applicable to Waterford 3 SES's radiological effluent technical specifications.

2.4 Measurements and Approximations of Total Radioactivity The quantification of radioactivity in liquid and gaseous effluents was accomplished by performing the sampling and radiological analysis of effluents in accordance with the requirements of Tables 4.11-1 and 4.11-2 of the amended Waterford 3 SES Plant Technical Specifications (see Attachments 1 and 2). These Technical Specifications include changes made May 16, 1985 to allow discharge of the Steam Generator Blowdown directly into the circulating water system.

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2.4.1 Fission and Activation Gases (Noble G.ises)

For continuous releases, a gas grab sanple was analyzed monthly for noble gases. Eachweeka(;asRatio(GR)was calculated according to the following squation:

GR = Average Weekly Noble Gas Monitor 13 ading Monitor Reading During Noble Gas Sampling ThemonthlysampleanalysisandweeklyabsRatiowerethen used to determine noble gases discharged continuously for the previous week. For gas decay tank and coratainment purge batch releases, a gas grab sample was analyzed prior to release to determine noble gas concentrat. ions in the batch.

In all cases the measured total radioactivity in gaseous effluents wan determined from measured coventrations of each radionuclide present and the total volume (ischarged.

2.4.2 Iodines and Particulates For continuous releases, iodines and partirulates were sampled using a continuous sampler. Each week the caarcoal cartridge and particulate filter were analyzed for gama emittera using gamma spectroscopy. The determined radionuclide concentrations andeffluentvolumedischargedwereusedtoc\1culatethe previous week's activity released.

Composites of the continuous particulate samplis were analyzed quarterly for Sr-89 and Sr-90 by a contract !al oratory (Teledyne l Isotopes). Gross alpha was measured weekly using gas flow proportional counting techniques. The determined activities were used to estimate effluent concentrations in subsequent releases until the next scheduled analysis was performed.

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Grab tritium samples for continuous and batch releases were analyzed monthly. The determined concentrations were used to estimate tritium activity in subsequent releases until the next scheduled analysis was performed.

2.4.3 Liquid Effluents For continuous releases, samples were collected weekly and analyzed using gamma spectroscopy. The measured concentra-tions were used to determine radionuclide concentrations in the previous week's releases. For batch releases, gamma

, analysis was performed on the sample prior to release.

For both continuous and batch releases, Sr-89, Sr-90, and Fe-55 composite samples were analyzed quarterly by a contract i

j laboratory (Teledyne Isotopes). Tritium and gross alpha l composite samples were analyzed monthly using liquid scintil-lation and gas flow proportional techniques respectively.

l for radionuclides analyzed in composite samples, the measured concentrations of the previous composite were used in deter-

] mining concentrations in liquid effluents.

l The measured total radioactivity in liquid ef fluent releases was determined from the measured concentrations of each radio-j nuclide present and the total volume of the effluent discharged.

2.5 Batch .9eleases The summarization of information for gaseous and liquid batch releases is included in Table 1.

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3.0 GASEOUS EFFLUENTS The quantities of radioactive material released in gaseous effluents are summarized in Tables IA, IB, and IC. Note that there are no elevated-releases at Waterford 3 SES.

4.0 LIQUID EFFLUENTS The quantities of radioactive material released in liquid effluents are summarized in Tables 2A and 2B, 5.0 SOLID WASTES The summary of radioactive solid wastes shipped offsite for disposal is listed Table 3.

6.0 METEUR1 LOGICAL DATA A summary of the hourly meteorological data from March 1, 1985 through December 31, 1985 is present in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability in Table 4, 7.0 ASSESSMENT OF DOSES 7.1 Dose at the Site Boundary An assessment of air doses from gaseous effluents was performed at the site boundary. Based on actual meteorological conditions existing during the reporting period and excluding any sectors over water, this location was determined to be the ESE sector at 1000 meters. Doses were assessed at this location considering only beta gamma exposures due to noble gas. The results of these assessments for the year 1985 are summarized as follows:

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l Beta air dose: 2.65 mead Gamma air dose: 0.96 mrad ,

A The beta and gamma air doses are 13.3% and 9.6% of the Technical Specification Dose Limits respectively. - ,

7.2 Dose to the Critical Receptor 7.2.1 The maximum organ dose to a NEMBER OF THE PUBLIC from I-131, I-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in-gaseous effluents released to areas at and beyond the site boundary was determined for 1985.

An assessment of the dose was performed for the residential location nearest to the plant with the highest dispersion ;

parameters. Using 1985 land use census data and actual ,

meteorological data, the critical receptor location for the nearest residence was determined to be in the NNE sector at a ,

distance of 1300 meters. The dose calculation was performed considering the inhalation, ground plane exposure, and cow's milk ingestion pathways. l 7.2.2 The maximum dose to the criticaa organ was determined to be 3.14 mrem to the infant thyroid. This represents 20.9% of the annual Technical Specification Dose Limit.

7.3 Doses Due to Liquid Effluents The total dose to the maximum exposed individual from liquid effluents l during 1985 from Waterford 3 SES is 1.32E-3 mrem total body and 1.14E-2 mrem to the maximum exposed organ (thyroid). These valuca ,

are 4.40E-2% and 1.14E-l% respectively of the annual Technical ,

Specification Dose Limit.

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7.4 40CFR190 Dose Evaluation In accordance with Waterford 3 Offsite Dose Calculation Mir.ual, ,

Section 8.15, dose evaluations to demons'. rate compliance with Surveil-lance Requirements 4.11.4.1 and 4.11.4.2 of the Waterford Technical Specifications, dealing with dose from the uranium fuel cycle, need to be performed only if quarterly doses exceed 3 mrem to the total body (liquid releases), 10 area to any organ (liquid releases), 10 mrad gamma air dose, 20 mrad beta air dose, or 15 aren to any organ from radioiodines and particulates.

At no time during 1985 were any of these limits exceeded; therefore, no evaluations are required.

7.5 Doses to Public inside the Site Boundary The member of the Public inside the Site Boundary expected to have the maximum exposure due to gaseous effluents is an employee at Waterford I and II fossil fuel plants, located in the NW sector, approximately 670 meters from t,he plant. Based on a assumption of 25% occupancy (40 hour4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months work week) and the fact all employees are adults the maximum thyroid dose was 0.13 mrem.

8.0 RELATED INFORMATION 8.1 Changes to the Process Control Program There were no changes to the Process Control Program for the period this report covers.

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8.2 Channes to the Offsite Dose Calculation Manual 8.2.1 On June 27, 1985 Revision 5 of the Waterford 3 Offsite Dose Calculation Manual was reviewed at Plant Operating Review l

Committee (PORC) meeting 85-119, and approved by the Plant l Manager for issue July 5, 1985.

f The changes made were to incorporate Waterford 3 Technical Specification Changes, allow other liquid pathways to be considered for dose calculations, and to correct a typographical error.

8.2.1.1 Sections 8.5.1.4 and 8.5.1.5 were modified to reflect the Emergency Technical Specification change made on May 16, 1985, allowing discharge of Steam Generator Blowdown to Waste Ponds and Circulating Water.

8.2.1.2 The note after 8.6.2 was added to allow for other liquid pathways besides fish and water ingestion via i

the Mississippi River to be used in liquid dose calculations.

8.2.1.3 In section 8.7.1.2 a typographical error was corrected.

8.2.2 On December 5,1985 Change 1 to Revision 5 of the Waterford 3 Offsite Dose Calculation Manual was reviewed at Plant Operating Committee (PORC) meeting 85-185, and approved by the Plant Manager for issue December 10, 1985.

The changes reflect updated information from the Land Use Census conducted July 10 and 11, 1985. l l

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4 8.2.2.1 Table 1 was changed to reflect milk cows, milk goats, vegetable gardens, and residences identified in the 1985 Land Use Census.

8.2.2.2 Changes to Table 2 include designation of a new Milk Sampling Location and a new Broad Leaf Control Sampling Location.

l j 8.2.2.3 The new Broad Leaf Control Sampling Location and the i new Milk Sampling Location were identified in Table l

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8.2.2.4 Figures 1, 2 and 3 were changed to reflect the changes described in Table 3.

8.2.2.5 Table 9 was changed to reflect the results of 1985 Annual Land Use Census as described for Table 1.

l 8.2.3 None of these described changed actually changed dose, dose rate, or setpoint calculations.

8.3 Unavailability of REMP Milk Samples i

Due to the unavailability of three milk sampling locations within five kilometers of the plant, Broad Leaf sampling is performed in accordance with Technical Specification Table 3.12-1. Milk is collected, when available, from the control location and two identi-fled sampling locations as indicated in ODCH, Table 2 and Table 3.

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8.4 Report of Technical Specification Required Instrument Inoperability i Technical Specification, Limiting Condition for Operation (LCO),

3.3.3.11 requires the reporting in the Semi-annual Effluent Release p Report of why designated inoperable instrumentation was not restored I I

to operability within the time specified in the ACTION Statement. -

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8.4.1 Monitor

Waste Gas Holdup System Hydrogen Monitor and Oxygen f

, Monitors Period of Inoperability: 3/21/85 - 12/31/85 I (At end of reporting period monitors were still inoperable) l Time Required by Technical Specifications to Restore .

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, Operability: 14 days !

Cause of Inoperability:

Due to design problems excess amounts of moisture were i i

allowed to leak into both the Beckman 02 2nd Delphi H2 and 0 2 [

analyzer systems.

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Reason Inoperability Not Restored Within Allotted Time:

Extensive hours were spent attempting to restore these l

analyzers to operable status. Several analyzer cells were ,

replaced, the solenoid and regulator were repaired, and the !

sample pump was both repaired and replaced. After these efforts failed to return the monitor to service, a station modification was initiated to replace the analyzer cells with less moisture sensitive models and to completely redesign the sample line condensate drain system.

This modification entailed work in several areas of the plant and en four different systems. All existing piping end electronics associated with the Waste Gas Holdup System ;

Hydrogen and Oxygen Monitors was essentially scrapped and redesigned.

4 Work included re-routing all sample lines in the Laundry Room, sodifying the existing drain header, and fabrication of a new drain header to tie into the Vent Gas Collection Header.

Re+ routing of the Gas Surge Header Sample line and fabrication of its drain was performed in Safeguards Room B. On Gas Decay Tank A a new separator and drain line on the Waste Gas Collec-tion Discharge Header war. added to the second low point.

Actual work on the Gas Analyrer Panel consisted of (1) adding !

12 new solenoid valves in the uample inlets; (2) modifying the panel to accomeadate the new exo-sensor units; (3) installing a new prep and its associited tubing; and (4) wiring of all new and relocated components.

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E__-_________________________-________-- _--_______________-____-_____A

l l It is estimated that 1.4 man-years have been expended on this

- project by Engineering, I&C, and Craft personnel. The i testing and calibration is all that remains to be performed be, fore the system is put in service. Anticipated completion

date is sometime in the first quarter, 1986.

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9.0 TABLES 1 Batch Release Summary 1A Semi-annual Summation of all Releases by Quarter - All Airborne Effluents IB Semi-annual Airborne Continuous Elevated and Ground Level Releases IC Semi-annual Airborne Batch Elevated and Ground Level Rele.nes 2A Semi-annual Summation of All Releases by Quarter - All Liquid Effluents 2B Semi-annual Liquid Continuous and Batch Releases 3 Solid Waste Shipped Offsite for Disposal 4 Joint Frequency Distribution of Meteorological Data 10.0 ATTACHMENTS

1. Technical Specification Table 4.11-1

2. Technical Specification Table 4.11-2

3. Offsite Dose Calculation Manual, HP-1-230, Revision 5 W350004H 15 l

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Table 1 (1 of 1)

EPWIT CATE0mY : BATCH ELEASE SUNIRY ELEASE POINT I ALL TYPE (F ELEASE : BAT 04 LIWID Ale GAGEOUS PERIOD START TIE 4344800 IRS = 12:00AM JLY 1 1995 PERIOD EIS TIE 8759:59 fftS = 11:59PM !)ECOWER 31,1995 LIQUID fELEASES IU SER OF RELEASES I 111 TOTAL TIE FGt ALL RELEASES 29767.0 MIETES MAIIM TIE FOR A RELEASE 486.0 MIW TES AWERAGE TIE FOR A RELEASE 268.2 MIWTES MINIM TIE FGt A RELEASE 1.0 MIWTES AVERAGE STREAM FLOW I 683642.2 GPM GASEOUS ELEASES WlEER OF RELEASES : 10 TOTAL TIE FOR ALL RELEASES 21432.0 MIWTES MAIIM TIE FOR A RELEASE 4547.0 MIWTES AVERACE TIE FOR A RELEASE 2143.2 MIWTES MINIM TIE FOR A RELEASE 492.0 MINUTES l

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Tabla 1A (1 of 1l lEPGli CATEORY SEMI SLMIATION OF ALL RELEASES BY QUARTER TYPE OF ACTIVITY ALL Al EFFLLENTS lEPORTING PERIOD t QUARTER 0 3 M QUARTER 4 4

LMIT QUARTER 3 IQUARTER 4 *E3T.TOTALt IH0lRS IHOLRS IERROR 1 :

TYPE OF EFFLLENT 4345-6552 86553-8760 A. FISSION afb ACTIVATION PRODUCTS

1. TOTAL IELEASE CLRIES 9.05E 02 6.01E 03 1 1.50E Ott

2. MERAGE lELEA6E RATE FOR PERIOD IUCI/SEC 8 5.69E 01 2 3.78E 02 8

3. PERCENT (F APPLICABLE LIMIT % N/A I N/A t B. R4010100!ES

1. TOTAL !00!E-131 ICURIES 2.83E-04 1 2.60E-03 1 1.50E 01:

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2. MERAGE lELEASE RATE FOR PERIOD IUCl/SEC i 1.79E-05 1.6 1-04

3. PERCENT OF APPLICABLE LIMIT 1 : N/A N/A C. PARTICtLATES

1. PARTICULATES(HALF-LIVES)8 DAYS) ICURIES 1.5 U h i

_ _ _ _ 7.61E-07 0.00E_01 .__ .- .

2. AVERAGE RELEASE RATE FOR PERIOD IUCl/SEC I 4.79E-08 0.00E-01 :

3. PERCENT OF APPLICABLE LIMIT I 1 i N/A I N/A t

4. GROSS ALPHA RADIDACTIVITY ICURIES I 9.81E-06 2.44E-06 i D. TRIT!tM

1. TOTAL RELEASE ICURIES : 0.00E-01 1 0.00E-01 1.*K 01

2. AVERAGE RELEASE RATE FOR FGIOD IUC!/SEC I 0.00E-01 0.00E-01

3. PERCENT OF APPLICABLE LIMIT I % 8 N/A N/A t

I Tabla 1B (1 of 4) I i

l EPORT CATEGORY SEMI AIRB0lWE CONT!WOUS ELEVATED AIS GRoue !

LEVEL . TOTALS FGt EACH WCLICE IELEASED.

TYPE OF ACTIVITY t FISSION OASES,100!ES, AIS PARTIClLATES l EPORTINO PERIOD t QUARTER I 3 AfC QUARTER I 4

ELEVATED flELEASES GR0ue ELEA6ES

LRIT IQUARTER 3 IQUARTER 4 IQUARTER 3 IQUARTER 4 1 IHOUIS IH0lRS IHOURS H0lRS I WQ.!DE I 4345-6552 16553-8760 t4345-6552 36553-0760 :

FISSION GASES 10t-85M I CtRIES 0.00E-01 0.00E-01 10.00E-018 4.01E 01 10t-85 : CURIES I 0.00E-01 8 0.00E-01 0.00E-01 I 0.00E-01 1 10t-07 C1 RIES 0.00E-01 1 0.00E-01 0.00E-01 8 0.00E-01 8 10t-88 : CURIES 0.00E-01 0.00E-01 1 0.00E-01 8 0.00E-01 IE-131M I Cut!ES 0.00E-01 0.00E-01 8 0.00E-01 1 0.00E-01 IE-133M Cut!ES I 0.00E-018 0.00E-01 0.00E-01 I 5.33E 00 t IE-133 : ClRIES I 0.00E-01 1 0.00E-01 8 3.3BE 02 8 5.64E 03 :

IE-135M CtRIES I 0.00E-01 10.00E-01 I 0.00E-01 0.00E-01 :

IE-135 t QRIES I 0.00E41 10.00E-01 13.55E 01 12.38E 02 IE-138 CtRIES 0.00E-01 0.00E-01 1 0.00E-01 8 0.00E-01 AR-41 : CtRIES 0.00E-01 10.00E41 0.00E-01 0.00E-01 I OTWR I CURIES I 0.00E-01 8 0.00E 41 0.00E-01 0.00E-01 :

TOTAL FOR PERIOD I Cut!ES 0.00E-0110.00E-018 3.73E 02 3 5.93E 03 100!ES I-130 : CtRIES I 0.00E-018 0.00E-01 0.00E-01 0.00E-01 :

I-131 1 CURIES I 0.00E418 0.00E-018 3.25E-0512.60E-03 8 1-132 : CLRIES I 0.00E-01 10.00E-01 I 0.00E-018 0.00E-01 1-133 : CtRIES 0.00E-01 0.00E-01 1 0.00E-01 1 2.68E-05 8 1-134 : CLRIES I 0.00E-01 I 0.00E-01 0.00E-01 8 0.00E-01 8 1-135 CLRIES t 0.00E-018 0.00E-01 0.00E-01 0.00E-01 OTER QRIES 0.00E-01 0.00E-0110.00E-0110.00E41 :

TOTAL FOR PERIOD CURIES 0.00E-01 : 0.00E-01 8 3.25E-05 8 2.62E-03

l Tablo 1B (2 of 4)

EPGli CATE0GtY SEMIAfetR. AIRB(NE CGITIMARIS ELEVATED M GR9El I LEVEL ELEASES. TOTALS FOR EACH lilCLIDE ELEASED.

TYPE (F ACTIVITY FISSIGI OA6ES. !0CIES. AfEl PARTIC1LATES EPORTING PERIOD t GUARTER 8 3 AIS QUARTER 8 4 ELEVATED ELEASES OR0l85 ftELEASES I (MIT IQUARTER 3 IQUARTER 4 IQUARTER 3 IQUARTER 4 I IHOUIS IN0 lfts IHOURS IH00tS :

MX2.!DE : 4345-6552 :6553-8760 4345-6552 6553-8760 :

PARTICULATES C-14 : CLAt!ES 0.00E-01 10.00E-01 0.00E-01 0.00E-01 :

NA-24 : cut!ES

0.00E-01 0.00E-01 0.00E-01 0.00E-01 :

P-32 : Cut!ES 0.00E-01 0.00E-01 1 0.00E-01 0.00E-01 :

CR-51 : Cut!ES 0.00E-01 8 0.00E-01 1 0.00E-01 0.00E-01 :

796-5 4 : cut!ES I 0.00E-01 0.00E-01 1 0.00E-01 0.00E-01 P96-56 : CUTIES I 0.00E-01 1 0.00E-01 8 0.00E-01 0.00E-01 :

FE-55 : Cut!ES 0.00E-01 1 0.00E-01 1 0.00E-01 I 0.00E-01 FE-59 : Cut!ES 0.00E-01 8 0.00E-01 I 0.00E-01 0.00E-01 :

CD-58 : Cut!ES 0.00E-018 0.00E-01 0.00E-01 10.00E-01 CD-60 t cut!ES I 0.00E-01 8 0.00E-01 I 0.00E-01 1 0,00E-01 NI-63 : Cut!ES 0.00E-01 1 0.00E-01 1 0.00E-01 1 0.00E-01 N!-65 : Cut!ES I 0.00E-01 10.00E-01 0.00E-01 0.00E-01 CU-64 Cut!ES 0.00E-01 1 0.00E-01 1 0.00E-01 1 0.00E-01 :

IN-65 : Cut!ES I 0.00E-01 0.00E-01 10.00E-01 I 0.00E-01 I R-83 : CUTIES I 0.00E-01 0.00E-01 1 0.00E-01 1 0.00E-01 :

Nt-84 I cut!ES I 0.00E-01 0.00E-01 1 0.00E-01 1 0.00E-01 :

BR-85 : Cut!ES 0.00E-01 8 0.00E-01 1 0.00E-01 1 0.00E-01 :

RB-86 : CUTIES I 0.00E-01 0.00E-01 I 0.00E-01 8 0.00E-01 :

RB-88 : Cut!ES 0.00E-01 I 0.00E-01 10.00E-01 10.00E-01 :

RB-89 : Cut!ES

0.00E-01 0.00E-01 0.00E-01 1 0.00E-01 SR-89 : Cut!ES 0.00E41 1 0.00E-01 8 0.00E-01 1 0.00E-01 SR-91 Cut!ES I 0.00E-01 10.00E-01 10.00E-01 0.00E-01 SR-92 Cut!ES 0.00E-01 1 0.00E-01 1 0.00E-01 1 0.00E-01 Y-91M Cut!ES I 0.00E-01 10.00E-01 10.00E-01 I 0.00E-01 Y-92 : Cut!ES 0.00E-01 8 0.00E-01 0.00E-01 I 0.00E-01

Y-93 I QAt!ES 0.00E-01 0.00E-01 0.00E-01 I 0.00E-01 IR-95 t Cut!ES I 0.00E-01 1 0.00E-01 1 0.00E-01 1 0.00E-01 ZR-97 : Ct. RIES I 0.00E-01 0.00E-01 0.00E-01 0.00E-01

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Table 1B (3 of 4)

ALS F TYPE & ACTIVITY FISSISI GAIES.10DIIES. AS PARTICLLATES lEPGtTil6 PERIDO I EMRTUt 8 3 AS MTER 8 4

E11 VAT 2D IELEAGES WI0lle IELEASES I TRIT IQuRRTER 3 IQUARTER 4 I M TER 3 I M TER 4 :

IN0WIS IHOWIS IN0l#ts IH0lRS MJCLIDE 14345-6552 6553-8760 4345-6552 I6553-8760 PARTICtLATES CONTI M W-95 CLRIES 0.00E-01 0.00E-01 10.00E-01 0.00E-01 1 2-99 : CtRIES 0.00E-01 0.00E-01 1 0.00E-01 0.00E-01 :

TC-99M I CtRIES I 0.00E-01 10.00E-01 8 0.00E-01 0.00E-01 :

TC-101 : CtRIES 0.00E-01 1 0.00E-01 0.00E-01 1 0.00E-01 :

RJ-103 : CtRIES 0.00E41 0.00E-018 0.00E-0110.00E-01 :

RJ-105 : CLR!ES 0.00E-01 0.00E-01 1 0.00E-01 1 0.00E-01 I RJ-106 : CtRIES 0.00E-01 1 0.00E-01 0.00E-01 1 0.00E-01 :

AG-110M I CtRIES 0.00E-01 0.00E-01 1 0.00E-01 0.00E-01 1 TE-125M I CLRIES 0.00E-Cl I 0.00E-01 1 0.00E-01 1 0.00E-01 :

TE-129 : CtRIES I 0.00E-01 1 0.00E-01 0.00E-01 0.00E-01 :

TE-131M I CLRIES I 0.00E-01 10.00E-01 0.00E-01 0.00E-01 :

TE-131 : CLRIES t 0.00E-01 0.00E-01 1 0.00E-01 1 0.00E-01 TE-132 : CLRIES I 0.00E-01 0.00E-01 0.00E41 0.N)E-01 CS-134 : CtRIES 0.00E-01 0.00E-01 10.00E-01 I 0.00E-01 :

CS-136 CtRIES 0.00E-018 0.00E-01 0.00E-01 t 0.00E-01 CS-137 : CLRIES 0.00E-01 10.00E-01 0.00E-01 0.00E-01 :

CS-138 : CtRIES

0.00E-01 0.00E-01 10.00E-018 0.00E-018 84-139 : CIR!ES I 0.00E-01 0.00E-018 0.00E-01 10.00E-01 I BA-140 t CtRIES 0.00E-01 1 0.00E-01 8 0.00E-01 0.00E41 1 84-141 CtRIES 0.00E-01 0.00E-01 I 0.00E-01 1 0.00E-01 1 84-142 : CtRIES I 0.00E-01 1 0.00E-01 8 0.00E-01 8 0.00E-01 :

LA-140 t " RIES 0.00E-01 0.00E-01 10.00E-01 0.00E-01 :

LA-142 IES I 0.00E-01 0.00E-01 1 0.00E-01 1 0.00E-01 :

CE-141 I (JllES 0.00E-01 10.00E-018 0.00E-01 0.00E-01 CE-143 : C1 RIES

0.00E-01 0.00E-01 8 0.00E-01 1 0.00E-01 :

CE-144 : CLRIES 0.00E-01 0.00E-01 1 0.00E-01 1 0.00E-01 :

PR-143 CtRIES I 0.00E-01 1 0.00E-01 0.00E-01 1 0.00E-01 PR-144 : CtRIES I 0.00E-01 1 0.00E-01 1 0.00E-01 0.00E-01 l

Ml Tablo IB (4 of 4)

EP(RT CATE0 CRY : SEM140tlAL AIRMUE CGITiltX11S ELEVATED #8 (R180

LEVEL IELEASES. TOTALS FOR EACH IWCLI!E lELEASED.

FISSICBI OASES,1(biles. Als PARTICIA.ATES TYPE OF ACTIVITY REPORTill0 PERIOD : QUARTER S 3 AIS QUARTER S 4 i

ELEVATED RELEASES : OR0 TBS RELEASES :

LBili QUARTER 3 lalARTER 4 QUARTER 3 QUARTER 4: ',

H0lRS : HOURS :H0lRS :

a H0lRS IWCLIDE : 84345-6552 :6553-8760 34345-6552 16553-8760 : [

l PARTICtLATES CGITIMED 16-147 : C1 RIES : 0.00E-01 : 0.00E-01 0.00E-01 0.00E-01 :

W-187 : CLRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :

W-239 : C1 RIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :

SR-90 : ORIES : 0.00E-01 0.00E-01 : 0.00E-01 : 0.00E-01 :

0 ALPHA : CLRIES : 0.00E-01 0.00E-01 9.81E46 3 2.44E-06 :

OT)ER : CLRIES : 0.00E-01 0.00E-01 : 0.00E-01 0.00E-01 :

TOTAL FOR PERIOD : CLRIES 0.00E-01 : 0.0CE-01 : 9.81E-06 2.44E-06 :

l 1

\

s k

Table 1C (1 of 4)

EPIRT CATE0(RY : SEMIAIMML AIRIRNE BATCH ELEVATED Ape (RUS LEVEL ELEASES. TOTALS FOR EACH leJCLIDE lELEASED.

TYPE OF ACTIVITY FISSI(31 GASES.100!IES. Afe PARTIC1LATES EPORTING PERIOD 1 QUARTER 8 3 Ale QUARTER 8 4

ELEVATED RELIASES 1 GROLN) RELEASES :

UNIT tQUARTER 3 IQUARTER 4 QUARTER 3 QUARTER 4 : l

HOLRS :H0 lfts IHutRS IH0 lfts :

14J(l!DE : 84345-6552 86553-8760 I4345-6552 86553-8760 :

FISSION GASES 10t-85M : CtRIES 0.00E-01 1 0.00E-01 1 0.00E-01 4.75E-03 KR-85 : CtRIES : 0.00E41 10.00E-01 3 5.83E-01 : 0.00E-01 IGt-87 : CIRIES I 0.00E-01 1 0.00E-01 1 0.00E-01 1 0.00E-01 :

KR-88 : CLRIES I 0.00E-01 10.00E-01 0.00E-01 : 0.00E-01 :

XE-131M : CLRIES : 0.00E-01 : 0.00E-01 : 1.06E 00 t 7.76E-012 XE-1331 : CURIES : 0.00E-01 : 0.00E-01 14.76E 00 t 8.75E-01 :

XE-133 : CLRIES : 0.00E-01 0.00E-01 5.24E 02 8 8.13E 01 :

XE-135M CtRIES : 0.00E-01 : 0.00E-01 10.00E-01 0.00E-01 XE-135 : C1 RIES 0.00E-01 1 0.00E-01 1.14E 00 t 3.50E-01 :

XE-138 : CtRIES 0.00E-01 10.00E-01 : 0.00E-01 0.00E-01 1 AR-41 : CtRIES : 0.00E-01 : 0.00E-01 1 0.00E-01 0.00E-01 :

OTER : CLRIES : 0.00E-01 0.00E-01 : 0.00E-01 10.00E-01 :

TOTAL FOR PERIOD : CLRIES 0.00E-01 : 0.00E-01 5.31E 02 8.33E 01 10 DIES I-130 : CLRIES : 0.00E-01 0.00E-01 : 0.00E-01 : 0.00E-01 :

I-131 : CtRIES : 0.00E-01 : 0.00E-01 : 2.50E-04 : 0.00E-01 :

I-132 : CUTIES : 0.00E-01 : 0.00E-01 10.00E-01 : 0.00E-01 1 1-133 : CtRIES : 0.00E-01 1 0.00E-01 : 1.29E-05 3 0.00E-01 1 I-134 : CtRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 10.00E-01 1 1-135 : CLRIES : 0.00E-01 0.00E-01 : 0.00E-013 0.00E-01 :

OTER : CtRIES : 0.00E-01 10.00E-01 0.00E-01 0.00E-01 :

TOTAL FOR PERIOD : CURIES 0.00E-01 0.00E-01 : 2.63E-04 0.00E-01 k

Table lc (2 of 4)

EPmi CATE0(RY : SEMIAletRL AIRENIE IIATDI ELEVATED Ale GOBS LEVEL REl. EASES. TOTALS F(R EADI WCLIDE RELEASED.

TYPE OF ACTIVITY : FISSICBI OASES,100llES. AfG PARTICtLATES EPORTING PERIOD : QUARTER 8 3 Ale MTER 8 4

ELEVATED RELEASES : GR0l#8 RELEASES :

(MIT iMTER 3 IMTER 4 : QUARTER 3 IMTER 4 :

: HOURS :lelRS :H0lRS 2H0tRS :

WCLIE : 84345-6552 :6553-6760 84345-6552 26553-6760 :

PARTICtt.ATES C-14 : ClRIES : 0.00E-01 0.00E-01 : 0.00E-01 : 0.00E-01 :

N&24 : C1 RIES : 0.00E-01 : 0.00E-01 0.00E-01 : 0.00E41 :

P-32 : CtRIES 0.00E-01 : 0.00E-01 0.00E-01 : 0.00E-01 :

(R-51 : ClRIES : 0.00E-01 0.00E-01 : 0.00E-01 : 0.00E-01 :

796-54 : CtRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 791-56 : CLRIES : 0.00E41 : 0.00E-01 : 0.00E-01 0.00E-01 :

FE-55 : CtRIES : 0.00E-01 0.00E-01 : 0.00E-01 0.00E-01 :

FE-59 : CLRIES 0.00E41 0.00E-01 : 0.00E-01 : 0.00E-01 :

C0-58 : CIRIES : 0.00E-01 : 0.00E-01 : 7.4!E-07 : 0.00E-01 :

CD-60 : CtRIES : 0.00E-01 : 0.00E-01 : 2.01-08 : 0.00E-01 NI-63 : 01 RIES : 0.00E-01 : 0.00E-0110.00E-01 : 0.00E-01 :

NI-65 : CLRIES : 0.00E-01 0.00E-01 : 0.00E-01 : 0.00E-01 :

CU-64 : CLRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 0.00E-01 ZN-65 : CtRIES : 0.00E-01 0.00E-01 : 0.00E-01 : 0.00E-01 :

BR-83 : CtRIES : 0.00E-01 0.00E-01 : 0.00E-01 : 0.00E-01 :

BR-84 : CtRIES : 0.00E-01 0.00E-01 : 0.00E-01 : 0.00E-41 :

BR-85 : CLRIES : 0.00E-41 : 0.00E-01 0.00E-01 : 0.00E-01 :

RB-86 : CIRIES : 0.00E-01 0.00E-01 : 0.00E-01 : 0.00E-01 :

RB-88 : CtRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 0.00E-01 :

RB-89 : CtRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :

SR-89 : CtRIES : 0.00E-01 0.00E-01 : 0.00E-01 : 0.00E-01 :

SR-91 : CLRIES : 0.00E-01 0.00E-01 : 0.00E-01 0.00E-01 :

SR-92 : CIRIES : 0.00E-01 0.00E-01 : 0.00E-01 : 0.00E-01 Y-91M : CLRIES : 0.00E-01 : 0.00E-01 0.00E-01 : 0.00E-01 :

Y-92 : CtRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :

Y-93 : CLRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :

ZR-95 : CLRIES : 0.00E-01 0.00E-01 : 0.00E-01 0.00E-01 :

ZR-97 : CLRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :

l I

Table 1C (3 of 4)

EPORT CATEGORY : SEMIANAL AIRB0ftE BATDI El.EVATED M GROLN)

LEVEL. ELEASES. TOTALS FOR EA01 MJCLIDE ELEASED.

TYPE F ACTIVITY : FISSION GASES.10 DIES. M PARTICtLATES REPORTING PERIOD QUARTER 8 3 M QUARTER 8 4

ELEVATED RELEASES : CROLN) E LEASES :

LMIT QUARTER 3 ! QUARTER 4 QUARTER 3 : QUARTER 4 :

:H0tRS :M)tRS :H0tRS :H0tRS :

MELIDE 84345-6552 :6553-8760 14345-6552 !6553-8760 :

PARTIC1LATES CONTIRED E-95 : CLRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 0.00E-01 :

M)-99 : CIRIES : 0.00E-01 : 0.00E-01 0.00E-01 : 0.00E-01 : '

TC-99M : CLRIES : 0.00E-01 0.00E-01 : 0.00E-01 : 0.00E-01 :

TC-101 : CtRIES : 0.00E-01 0.00E-01 : 0.00E-01 0.00E-01 :

RU-103 : CLRIES 0.00E-01 0.00E-01 0.00E-01 : 0.00E-01 :

RU-105 : CLRIES 0.00E-01 0.00E-01 0.00E-01 : 0.00E-01 :

RJ-106 : CLRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :

AG-110M : CLRIES : 0.00E-01 0.00E-01 : 0.'AE-012 0.00E-01 :

TE-125M : ClRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 0.00E-01 :

TE-129 : CtRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :

TE-131M : CtRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :

TE-131 : CLRIES : 0.00E-01 : 0.00E-01 0.00E-01 : 0.00E-01 :

TE-132 : CLRIES : 0.00E-01 : 0.00E-01 0.00E-01 : 0.00E-01 :

CS-134 : CLRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 0.00E-01 :

CS-136 : CtRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 0.00E-01 :

CS-137 : CLRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :

CS-138 : CLEIES : 0.00E-01 0.00E-01 : 0.00E-01 : 0.00E-01 :

BA-139 : CLRIES 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :

84-140 : CLRIES : 0.00E-01 : 0.00E-01 0.00E-01 : 0.00E-01 :

BA-141 : ClRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 10.00E-01 :

84-142 : CLRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :

LA-140 : CLRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :

LA-142 : CLRIES : 0.00E-01 0.00E-01 0.00E-01 : 0.00E-01 :

CE-141 : CLRIES : 0.00E-01 : 0.00E-01 0.00E-01 : 0.00E-01 :

CE-143 : CLRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :

CE-144 : CtRIES : 0.00E-01 0.00E-01 : 0.00E-01 : 0.00E-01 :

PR-143 : CLRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :

PR-144 : CLRIES : 0.00E-01 : 0.00E-01 0.00E-01 : 0.00E-01 :

i l

j Table 1C (4 of 4)

EPGIT CATE0(RY : SEMIA100L AIRBGDE BATCH ELEVATED AN) CR188

LEVEL lELEASES. TOTALS FOR EACH MJCLIDE RELEASED.

TYPE OF ACTIVITY : FISSION OASES.10 DIES. Ale PARTICtLATES MPORTINO PERIOD : QUARTER 8 3 AIS QUARTER 8 4

ELEVATED RELEASES : CROLSB RELEASES

(MIT : QUARTER 3 : QUARTER 4 QUARTER 3 : QUARTER 4 :

H0lRS :H0lRS : HOURS IHOURS :

MJCLIDE : :4345-6552 :6553-8760 14345-6552 :6553-8760 :

PARTIClLATES CONTIRED 2-147 : CtRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 0.00E-01 :

W-187 : CIRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :

IF-239 : CLRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :

SR-90 : ORIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :

G ALPHA ClRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 0.00E-01 :

OTER : CLRIES : 0.00E-013 0.00E-01 0.00E-01 0.00E-01 :

TOTAL FOR PERIOD : CtRIES 0.00E-01 : 0.00E-01 7.61E-07 : 0.00E-01 :

i i

1 Table 2A (1 og 1) l l

REPORT CATEGORY : SEMIANAL St# RATION OF ALL RELEASES BY MTER TYPE OF ACTIVITY : ALL LIQUID EFFLlENTS REP (RTING PERIOD : QUARTER 8 3 AM) QUARTER 8 4

lMIT : QUARTER 3 : QUARTER 4 :EST. TOTAL:

:H0lRS : HOURS : ERROR % :

TYPE OF EFFLLENT : :4345-6552 :6553-8760 : :

A. FISSION AM) ACTIVATION PRODLCTS

1. TOTAL RELEASE (NOT INCLLSING : : : : :

TRITIlm. GASES. ALPM) :CLRIES : 1.27E-01 : 1.19E-01 : 1.50E 01:

2. AVERAGE DILUTED CONCENTRATION : : : :

DlRING PERIOD :UCI/ft. : 3.29E-09 : 3.11E-09 : ,

3. PERCENT OF APPLICABLE LIMIT : I : N/A : N/A :

B. TRITILM

1. TOTAL RELEASE :CtRIES : 6.14E 00 1.47E 01 : 1.50E 01:

2. AVERAGE DILUTED CONCENTRATION : : : :

M ING PERIOD :UCI/Pt.

1.59E-07 : 3.83E-07 :

3. PERCENT OF APPLICABLE LIMIT : I : N/A : N/A C. DISSOLVED AM) ENTPAIED CASES

1. TOTAL RELEASE ICLRIES : 6.83E-01 : 8.35E 00 : 1.50E 01:

2. AVERAGE DILUTED CONCENTRATION : : : :

M ING PERIOD :UCI/71. : 1.77E-08 : 2.18E-07 :

3. PERCENT (F APPLICABLE LIMIT : I : N/A : N/A D. GROSS ALPHA RADI0 ACTIVITY

1. TOTAL RELEASE :ClRIES : 2.60E-05 : 0.00E-01 : 1.50E 01:

E. WASTE VOL RELEASED (PRE-DILUTION) : GAL : 8.82E 06 : 3.11E 06 : 2.00E 00:

F. VOLl#E OF DILUTION WATER USED : GAL : 1.02E 10 : 1.01E 10 : 2.00E 00:

6 Table 2B (1 of 4)

EPGli CATEGGtY : SEN!40t#t. LII111D CGITIltDJS AIS BAT 01 IIE1. EASES

TOTALS FGt EA01 WCLIE ELEASED.

TYPE (F ACTIVITY : ALL HADi(BRJCLIES E PORTING PERIOD : QUARTER 8 3 Ale QUARTUt 8 4 i

CONTIMJOUS IIELEASES : BATCH ELEASES : 1

LIlli : QUARTER 3 : QUARTER 4 QUARTER 3 QUARTER 4 :

H0 lfts IH)latS IH0lsts :M)L5tS leJQ.!E : 4345-6552 86553-8760 4345-6552 36553-6760 :

ALL MJCL1 DES H-3 : C15 TIES : 1.41E-01 0.00E-01 : 6.00E 00 1.47E 01 :

C-14 : ORIES : 0.00E-01 0.00E-01 0.00E-01 : 0.00E-01 :

NA-24 : CLRIES 0.00E-01 : 0.00E-01 : 9.81-06 0.00E-01 :

P-32 : C15 TIES 0.00E-01 0.00E-01 0.00E-01 : 0.00E-01 :

Ot-51 : CLAt!ES : 0.00E-01 : 0.00E-01 : 6.32E-03 : 1.09E-02 :

IW-54 : CtRIES : 0.00E-01 0.00E41 4.90E-04 : 6.06E-04 :

IW-56 : CIRIES : 0.00E-01 : 0.00E-01 0.00E-01 0.00E-01 :

FE-55 : CLRIES : 0.00E-01 0.00E-01 : 2.3E-03 : 0.00E-01 :

FE-59 : CLRIES : 0.00E-01 0.00E-01 : 4.0E-04 : 7.26E-04 :

CD-58 : CLRIES : 8.72E-03 0.00E-01 1.03E-018 7.30E-02 :

CIHO CtRIES 0.00E-01 : 0.00E-01 : 2.30E-03 1.63E-03 :

NI-63 : ClRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 0.00E-01 :

WI-65 : ORIES : 0.00E-01 : 0.00E-01 0.00E-012 0.00E-01 :

Cll-64 : CLRIES : 0.00E-01 : 0.00E-01 0.00E-01 0.00E-01 :

IN-65 : CtRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 3.21E-05 :

IN-69 : CLRIES 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :

IR-83 : CLRIES : 0.00E-013 0.00E41 0.00E-01 0.00E-01 :

BR-84 : CLRIES : 0.00E-01 0.00E-01 : 0.00E-01 : 0.00E-01 :

BR-85 : CtRIES : 0.00E-01 0.00E-01 : 0.00E-01 0.00E-01 :

RB-86 : ORIES : 0.00E-01 : 0.00E-01 : 0.00E-01 0.00E-01 :

RB-88 ft CLRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 0.00E-01 :

RB-89 ORIES : 0.00E-01 0.00E-01 0.00E-01 : 0.00E-01 :

SR-89 [ CLRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :

SR-91 "- CLRIES 0.00E-01 : 0.00E-01 0.00E41 : 0.00E-01 :

SR-92 ) CtRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 7.69E-06 :

Y-90 4 ORIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :

Y-91M : ORIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :

Y-91 - CLRIES : 0.00E-01 : 0.00E-01 : 0.00E41 : 0.00E-01 :

i l

P

Table 2B (2 of 4)

IEPORT CATE00RY : SEMIA10GJAL LIQUID CGITilijouS AIS BAT 01 RELEASES

TOTALS FOR EACH ltJCI.IDE ELEASED.

TWE (F ACTIVITY : ALL RADIGWCLIES EPORTING PERIOD QUARTER 8 3 Ale QUARTER S 4

CONTilRJ00S RELEASES : BATDI RELEASES :

t IRIT : QUARTER 3 IGJARTER 4 : QUARTER 3 QUARTER 4 :

HOUtS IHOWIS IH0utS IN0 Lits :

itJCLIDE 34345-6552 :6553-8760 :4345-6552 :6553-6760 :

ALL I4JCLIDES CONTIIRED Y-92 : cut!CS : 0.00E-01 0.00E-01 : 0.00E-01 : 0.00E-01 :

Y-93 : C15 TIE 3 0.00E-01 0.0E-01 a 0.00E-01 0.00E-01 ZR-95 : CutIEi 0.00E-01 : 0.00E-01 : 3.1 1-04 9.30E-04 :

ZR-97 : CUTIES : 0.00E-01 0.00E-01 : 0.00E-01 0.00E-01 :

18-95 : CtftIES : 3.02E-06 0.00E-01 5.10E-04 1.46E-03 :

MD-99 : C11t!ES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 1.67E-03 :

TC-99M : ClftIES : 0.00E-01 : 0.00E-01 : 6.59E-05 : 2.45E-03 :

TC-101 : Ct# TIES : 0.00E-01 : 0.00E-01 : 0.00E-013 0.00E-01 :

110-103 : CtstIES 0.00E-01 0.00E-01 0.00E-01 : 0.00E-01 :

RU-105 : Cut!ES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :

1U-1% : CUTIES : 0.00E-01 : 0.00E-01 : 0.00E-01 0.00E-01 :

AG-110M Ct1 TIES : 0.00E-01 0.00E-01 : 0.00E-01 0.00E-01 :

TE-125M : CtftIES 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :

TE-127M CUTIES : 0.00E-01 0.00E-01 : 0.00E-01 : 0.00E-01 :

TE-127 : CtRIES : 0.00E-01 0.00E-01 : 0.00E-01 0.00E-01 :

TE-129M : CtRIES : 0.00E-01 : 0.00E-01 0.00E-01 : 0.00E-01 :

TE-129 : CtRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 0.00E TE-131M CUTIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :

TE-131 : C1 RIES : 0.00E-01 : 0.00E-01 0.00E-01 : 0.00E-01 :

TE-132 : CtRIES 0.00E-01 0.00E41 : 0.00E-01 : 0.00E-01 1-130 : CtRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 1-131 : CtRIES 0.00E-01 : 0.00E-01 1.37E-03 : 1.42E-02 1-132 : CtRIES : 0.00E-01 0.00E-01 : 0.00E-01 : 0.00E-01 :

1-133 : CtRIES 0.00E-01 0.00E-01 : 4.14E-05 : 5.47E-04 :

I-134 : CLRIES 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :

I-135 : CtRIES : 0.00E-01 : 0.00E-01 0.00E-01 : 0.00E-01 :

CS-134 : CtRIES : 0.00E-01 0.00E-01 : 1.9 1-05 : 5.99E-05 :

CS-136 : ClRIES : 0.00E-01 0.00E-01 : 2.94E-05 : 9.87E43 :

l l

l Table 2B (3 of 4)

I I i EP(RT CATEGORY : SEMIA198JAL LIEllD CtWTIMJOUS Ale BATQi RE1 EASES

TOTALS F(R EACH MJCLIE RE1IAGED.

TYPE (F ACTIVITY : ALL RADIOMJCLIDES EPIRTING PERIOD QUARTER 8 3 AIS QUARTER 8 4

CONTIMJOUS RELEASES : BATCH RELEASES :

LMIT : QUARTER 3 QUARTER 4 : QUARTER 3 : QUARTER 4 :

H0lRS H0lRS :H0lRS :H0lRS :

MCLIE : 84345-6552 36553-8760 84345-6552 :6553-8760 :

ALL MJCLIDES CONTIMED CS-137 : CtRIES 0.00E-01 : 0.00E-01 5.19E-04 : 4.25E-04 :

CS-138 : CLRIES : 0.00E-01 10.00E-01 0.00E-01 : 0.00E-01 :

84-139 : 01 RIES : 0.00E-01 0.00E-01 : 0.00E-01 : 0.00E-01 :

84-140 : CIRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 4.58E-04 BA-141 : CLRIES : 0.00E-01 3 0.00E-01 0.00E-01 : 0.00E-01 :

84-142 QRIES : 0.00E-01 0.00E-01 : 0.00E-01 : 0.00E-01 :

LA-140 : C1 RIES 0.00E-01 : 0.00E-01 : 1.02E-04 : 6.48E-04 :

LA-142 : CLRIES 0.00E-01 : 0.00E-01 : 0.00E-01 0.00E-01 :

E-141 : C1 RIES : 0.00E-01 : 0.00E-01 0.00E-01 : 0.00E-01 :

& -143 : CLRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 0.00E-01 :

-144 : CtRIES 0.00E-01 0.00E-01 1.55E-04 : 4.25E-03 :

PR-143 : ClRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 0.00E-01 :

FR-144 : CLRIES : 0.00E-01 0.00E-01 : 0.00E-01 : 0.00E-01 :

M)-147 : CLRIES 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :

W-187 : CLRIES : 0.00E-01 : 0.00E-01 2.43E-04 5.33E-03 :

PP-239 : CtRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :

G-83M : CLRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 0.00E-01 :

G-85M : CLRIES <0.00E-01 : 0.00E-01 : 6.03E-06 : 3.82E-05 :

E-85 : ClRIES : 0.00E-01 : 0.00E-01 : 1.02E-04 : 1.21E-03 :

G-87 : CLRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 0.00E-01 :

G-88 : CtRIES : 0.006-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :

G-89 : CURIES : 0.0(c-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : -

G-90 : C! RIES : 0.0L E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :

IE-131M : CIRIES : 0.00E-01 : 0.00E-013 4.94E-04 : 2.3dE-03 :

IE-133M : CtRIES : 0.00E-01 : 0.00E-01 : 8.44E-04 : 7.94E-02 :

IE-133 : CURIES : 5.17E-01 : 1.60E-03 1.64E-01 : 8.25E 00 :

IE-135M : CLRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 :

IE-135 : CURIES : 0.00E-01 : 0.00E-01 : 1.38E-03 : 9.69E-03 :

1

Table 2B (4 of 4)

IEPORT CATEGORY : SEMIAMAL LIEl!D CGiTIMJOUS Ale BATCH RE1 EASES

TOTALS FGt EA04 MELIDE lELEASED.

TYPE OF ACTIVITY : ALL RADIGilCLIES IEPORTING PERIOD : QUARTER 0 3 Ale QUARTER 8 4

CONilleRIS IIELEASES : BAT 01 IELEASES

IMIT : QUARTER 3 QUARTER 4 QUARTER 3 : QUARTER 4 :

:HOWIS :HOWtS IHOWIS IH0lRS :

MJCLIIE :4345-6552 :6553-8760 :4345-6552 86553-8760 :

ALL MJCLIDES CONTIMED IE-137 : CtRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : I XE-138 : ClRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 0.00E-01 '

AR-41 : CtRIES : 0.00E-01 : 0.00E-01 : 1.35E-05 : 0.00E-01 :

SR-90 : ClRIES : 0.00E-01 : 0.00E-01 : 0.00E-01 0.00E-01 :

G ALPHA QRIES 0.00E-01 : 0.00E-01 : 2.60E-05 0.00E-01 :

OT}ER : QRIES : 0.00E-01 0.00E-01 0.00E-01 : 0.00E-01 :

TOTAL FOR PERIOD C1 RIES : 6.67E-01 : 1.60E-03 6.29E 00 3 2.32E 01 :

l l

1 i

l I

Table 3 (1 of 1)

- - RSCULAT0tY CUIDE 1.21 REPot? ***

SOLID WASTE SEIFFED OFFSITE FOR DISPOSAL

- DURIWC FERIOD FROM 7/1/85 - 12/31/85 ***

WASTE TYPE CUBIC NETERS Ct: RIES % ERROR (CI)

DAW C-NA Compacted Trash 40.3 9.1E-1 +/- 25%

EB-S-SM Solidified Bottone 144.2 9.8E-1 +/- 257.

SR-D-NA Blowdown /RCS Bead Resins 5.2 3.4E-2 +/- 25%

SR-D-NA Portable Desin Resin 5.2 5.9E-2 +/- 25%

(170 Cubic Foot Liner)

SR-D-NA RCS/ Purification Resins 15.2 2.9E+1 +/- 25%

SR D-NA Portable Desin Resin $1.5 2.1E+0 +/- 25%

(182 Cubic Foot Liner)

SR-D-NA Blowdown / Portable Domin 10.3 1.4E-1 +/- 25%

and RCS Bead Resin

- ESTIMATES OF MAJOE NUCLIDES BY WASTE TYPE **

VASTE TYPE NUCLIDE ASUNDANCE CURIES DAW C-NA Compacted Trash Co-58 33.% 3.0E-1 Co-60 2.% 1.6E-2 Cs-137 4.% 3.2E-2 1-131 49.% 4.4E-1 EB-S-CM Evaporator Bottone Co-58 86.% 8.4E-1 Solidified With Cement Co-60 2.% 2.3E-2 H-3 0.% 9.2E-4 Cs-137 3.1 3.3E-2 SR D-NA Dewatered Steam co-58 11.% 3.6E-3 Cenerator Blowdown and Co-60 1.% 1.8E-4 RCS Bead Resin H-3 5.% 1.7E-3 Cs-137 0.% 5.4-E6 1-131 75.% 2.6E-2 SR-D-NA Devatored Portable Co-58 26.% 1.5E-2 Domin Bead Resin in a 170 co-60 1.% 6.4E-4 Cubic Foot Liner H-3 24.% 1.4E-2

, I-131 44.% 2.6E-2 SR D-NA Devatored RCS and Co-58 45.% 1.3E+1 Purification Ion Exchange Co-60 3.% 8.9E-1 Sead Resin H-3 9.% 2.6E+0 Cs-137 9.% 2.5E+0 I-131 11.% 3.2E+0 SR-D-NA Dewatered Portable co-58 33.% 6.8E-1 Domin sead Resin in a 182 Co-60 2.% 3.7E-2 Cubic Foot Liner H-3 31.% 6.4E-1 Cs-137 18.% 3.7E-1 SR D-NA Dewatered Blowdown Co-58 20.% 2.9E 2 Portable Desin, and RCS Co-60 1.% 1.8E-3 Bead Resin H-3 45.% 6.4E-2 Ca-137 4.% 5.4E-3 I-131 13.% 1.8E-2

- - SOLID WASTE DISPOSITION StBetARY ***

NtlMBER OF TYPE OF TYPE OF MODE OF CLASS SHIPMENTS SHIPMENT CONTAINER TRANSPORTATION DESTINATION A 5. LSA Strong Tight Truck Barnwell A 2 LSA USNRC Certified Cask Truck Barnwell l

A 15 LSA Strong Tight Truck Richland i B * * * *

i C * * * *

l

- - IREIATED COMPONENTS / FUEL SEIPIENTS ***

NONE

NOT APPLICABLE l

I

Table 4 (1 of 4)

PAS 0 VILL CLASS A JOINT FREQUDCY DISTRIBUTI(N OF WIM) SPEED H DIRECT!W IN HOURS (NWlCH TO DECD9ER 1985)

WIND SPEED (WS) AT 10-e LEVEL WI@

DIRECTI(N .35 .50 .51 .75 ,76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10. 10.1-13 13.1-18.0 >18.0 TOTAL 3333333333333333333333333333333333333333333333333333333333333333333333333333333333333333333333333333333333333333333333333 6 6 11 6 0 0 0 0 30 N 0 0 0 1 5 12 15 2 0 0 0 0 35 MC 0 0 0 1 15 29 15 1 0 0 0 65 E 0 0 0 0 5 2 20 57 14 0 0 0 0 94 ENE 0 0 0 1 1 2 11 2 0 0 0 0 11 E 0 0 0 1 1 5 8 6 0 0 0 0 20 ESE O O O O 4 10 10 5 0 0 0 0 30 SE O O O 1 0 4 6 4 0 0 0 0 14 SSE O 0 0 0 0 3 18 0 0 0 0 0 23 S 0 0 0 2 10 28 5 0 0 0 0 45 SW 0 0 0 0 2 17 40 6 0 0 0 0 67 S4 0 0 1 0 3 24 39 9 0 0 0 0 75 6 0 0 0 0 3 34 50 7 0 0 0 0 99 W 0 0 0 1 7 4 21 41 3 0 0 0 0 69 M 0 0 0 0 13 8 1 0 0 0 0 24 144 0 0 0 1 1 4 17 4 0 0 0 0 26 fM4 0 0 0 0 1 E3333333333333333333333333333333333333333333333333333E3333333333333333333333333333333333333333333333333333333 0 0 0 733 0 1 9 45 200 388 89 1 TOTAL 0

! USER OF CALMS FOR A STABILITY 0 PASQUILL CIASS B JOINT FREQUENCY DISTRIBUT!(N OF WIM) SPEED H DIRECTi(N IN HOURS (NWtCH TO DECD9ER 1985)

WIM) SPEED (WS) AT 10-m LEVEL WIM) TOTAL DIRECTI(N .35 .50 .51 .75 .76-1.0 1.1-1,51.6-2.02.1-3.03.1-5.05.1-7.07.1-10. 10.1-13 13.1-18.0 >18.0 E3333333333333333333333333333333333333333333333333333333333333333333333333333333333333333333333333333333EEE33333*.33 3 5 6 0 0 0 0 14 N 0 0 0 0 0 8 1 0 0 0 0 14

!NE O O 1 2 1 1 5 12 1 1 0 0 0 23 E O 0 1 3 0

0 9 7 6 0 0 0 0 23 DE O 0 0 1 1 2 1 0 0 0 0 5 O O O O 1 E

0 4 1 1 0 0 0 0 6 i O 0 0 ESE O 0 1 4 2 4 2 1 0 0 0 14 J 0

SE O 0 0 0 0 1 6 5 0 0 0 0 12 1 SSE O 0 13 2 3 7 0 0 0 0 S 0 0 1 0 3 6 1 0 0 0 0 11 5 94 0 0 0 0 1 12 2 0 0 0 0 19 W 0 0 0

0 0 1

1 1 5 4

8 4 0 0 0 0 19 W94 0 0 1 8 12 0 0 0 0 0 22 W 0 0 0 1 4 5 0 0 0 0 0 11 M 0 0 0 1 1 0 0 0 0 8 W 0 0 0

1 0

0 0

0 2

4 3

3 4

0 5 1 0 0 0 15 Med 0 33333333333333333333333333333333333333333333333333333333333333333333333333333333333333333333333333333333333333333 0 0 229 4 10 15 60 102 35 3 0 TOTAL 0 0 IUSER (F CAMS FOR 8 STABILITY 0

Tcblo 4 (2 of 4) -

PA60UILL CLASS C +

JOINT FREQUENCY DISTRIOUTim W Wile SPEED Ne DIRECTim IN Hollt$ ( W CH TO DECD GER 198 ,

y Wife SPEED (WS) AT 10-e LEVEL W!le 3.0 3.1-5.0 5.1-7.0 7.1-10. 10.1-13 13.1-18.0 )18.0 TOTAL DIRECTim .35.50 .51 75 .76-1.0 1.1-1.5u===== 1.5-2.0 33 2 .1.33==S us3 -- 3=3 ======3=------ - -33=.33333,33333 3 3- - --

--=3:2:===3. u u s==33.

0 10 1 0 0 0 23 8 0 3 1 3 N O 7 0 0 0 0 0 16 1 6 M 0 0 1 1 4 7 4 1 1 0 0 0 N E O O O 3 0 0 0 24 O 1 8 11 3 1 DE O O O 0 0 0 0 0 7 l 1 0 1 5 E O O O 0 0 0 0 0 4 i 0 0 0 4 '

ESE O 8 0 0 0 0 22 0 1 3 15 2 1 SE O O O 0 0 0 16 0 11 4 0 0 0 0 1 0 SSE 9 2 0 0 0 0 14 0 1 1 1 S 0 0 0 0 0 13 2 1 6 4 0 0 0 SW 0 0 2 2 13 4 0 0 0 0 22 W 0 0 0 1 9 1 0 0 0 0 18 W 0 0 0

0 0

2 0

6 7 15 0 0 0 0 0 22 W 0 0 0 0 0 11 2 4 5 0 H 0 0 0 0 2 5 3 1 0 0 0 0 11 W 0 0 0 0 4 6 2 1 0 0 0 14 N O 0 0 0 1 33333333 333333333333 3333333333333 E33333333333333 333333333338888333333333333333333333333333331333333333333333 34 5 0 0 0 257 0 1 8 20 58 131 TOTAL 0 NLf9ER OF CAutS FOR C STABILITY 0 PASQUILL CLASS D JOINT FREQUENCY DISTRIBUTim 0F W!te SPEED NO DIRECTim IN HOURS O WtCH TO DECD 9ER 198 W!te SPEED (W S) AT 10 1 LEVEL W12 TOTAL DIRECTim .35 .50 .51 .75 .76-1.0 1.1-1.5 1.5-2.3 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10. 10.1-13 13.1-18.0 >18

535855333333333333333333333333333333 3333333333333223333331333333333333333333333333333333333322833333333333333333333335_

66 6 0 0 0 183 0 0 0 3 4 33 71 N 35 17 12 1 1 0 113 26 M 0 1 1 5 10 7 43 65 25 9 0 0 0 154 E O O 1 4 4 3 27 40 15 3 1 0 0 98 DE O 0 1 0 0 66 2 3 15 28 11 5 1 E O 0 1 0 0 67 2 4 15 35 3 5 2 ESE O O 1 15 62 25 9 0 0 0 114 O O O 2 1 SE 37 14 0 0 0 0 83 SSE O O O 2 1 29 51 12 1 0 0 0 81 0 0 0 3 2 12 -

S 52 19 0 0 0 0 99 0 0 0 3 4 22 SSW 42 7 0 0 0 0 87 0 0 1 0 10 27 SW 2 0 0 83 5 0 1 1 5 4 M 20 17 8 0 0

0 0 0 91 W 0 0 1 3 7 5 43 0 0 57 3 17 26 6 0 0 M 0 0 0 5 5 10 19 20 4 0 0 0 62 W 0 0 0 4 3 14 40 34 13 0 0 0 112 H 0 0 0 0 3333333333333 3333333333333333333333333333333333333333333333235328838833333283838833335323333338883333385353333 686 302 69 5 1 0 1550 0 2 8 47 71 359 TOTAL PRfGER OF CAUS FOR D STABILITY 0

Tablf4 (3 of 4) .

\i ...

MrJ.HL QMS E J0!NT FKQUENCY DISTRIOUTim F W12 SPEED NO DIECTim IN N0lets (tWtCH TO DECDGER 1905)

Wife SPEED ( W S) AT 10 1 LEVEL Wipe TOTAL DIECTim .35 .50 .51 .75 .76-1.0 1.1-1.5 1.5-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10. 10.1-13 13.1-10.0 >18.0 3333333333333333333333333333333333333333333333** ** * ***2333333 333333333333333333333333333333333333333333333333 38 54 6 0 0 0 0 143 N 1 1 5 16 22 ,

21 37 34 3 2 0 2 0 .116 POE 1 0 2 14 63 9 1 0 1 0 1 90 4 10 24 76 IE 2 0 66 57 9 0 1 0 0 157 DE 1 2 7 14 O

1 3 10 57 93 8 1 0 0 0- 173 E O O 151 9 58 70 1 1 0 0 0 ESE O 2 1 9 233 81 110 6 1 1 0 0 O 2 0 11 21 SE 77 SS 3 0 0 0 0 175 O O 5 16 15 SSE 4 0 0 0 0 148 4 6 24 58 49 S 2 1 2 0 0 0 0. 100 6 21 20 81 40 SW 2 0 67 28 2 0 0 0 0 172 W 0 2 9 25 39 97 20 1 0 0 0 0 204 12 30 40 6 1 3 30 57 18 1 0 0 0 0 145 W 0 4 8 27 0 86 0 0 0 0 W 2 4 4 5

19 12 11 11 26 16 20 9 0 0 0 0 0 60 144 2 5 0 0 0 98 22 33 13 1 M 2 1 6 9 11 333333333333333333333333333333333333333333333333333333333333333333333333333333333333333333333333333333333333333 7 2 3 0 2431 74 235 330 914 757 68 TOTAL 15 26 Hl}9ER OF CAL 1tS FOR E STABILITY 5 PASWILL CLASS F

JOINT FEQUD4CY DISTRl8UTim 0F WIP4 SPEED NG DIRECTim IN HolltS (ImRCH TO DECD9ER 1985)

WIM) SPEED (WS) AT 10-e LEVEL.

WDe DIRECTim .35 .50 .51 .75 .76-1.0 1.1-1.5 1.5-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10. ----33333333333333333333333333333333 3333333335323---

10.1-13 13.1-10.0 )10.0 TOTAL 333333333333333333333333333333333333333333333_

il 1 0 0 0 0 0 53 N 5 1 7 10 11 6 16 2 0 0 0 0 0 35

!#E O 1 1 9 13 4 0 0 0 0 0 59 NE 1 2 6 21 12 7 11 7 0 0 0 0 0 38 DE 2 0 3 8 12 1 0 0 0 0 0 36 E O 2 3 5 13 4 5 2 0 0 0 0 0 18 ESE 1 1 4 1 10 2 0 0 0 0 0 42 SE 1 4 4 10 11 21 4 0 0 0 0 0 07 SSE 1 4 9 17 31 20 2 0 0 0 0 0 107 5 1 4 8 33 39 49 47 25 5 0 0 0 0 0 138 SW 1 3 8 0 0 0 0 0 120 W 2 3 13 53 43 36 26 12 25 4 1

0 0 0 0 0 120 6 3 5 14 15 17 5 0 0 0 0 0 100 W 3 9 20 31 0 0 0 55 W 8 5 4

8 9

21 15 6

9 4

5 2

2 1

0 0

0 0 0 0 48 D64 4 0 37 9 2 0 0 0 0 1964 5 2 4 5 10 33333333333333333333333333333333333333333333333333333388333333838588833883333333333333883883338833333333333333333 0 0 1993 331 283 223 46 1 0 0 TOTAL 38 50 121 POSER OF CEMS FOR F STA8!LITY 12

Table 4 (4 of 4)

PASQUILL CLASS G JOINi REQUDCY DISTRIBUTim 0F WI@ SPEED #@ DIRECTim IN H0 Lits (f%RCH TO DECD9ER 1985)

W12 SPEED (M/S) AT 10-m LEVEL WIND DIRE 3136 .35 .50 .51 .75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10. 10.1-13 13.1-18.0 )18.0 E 333333333333333333333333333333333333333333333331323333333333333333333333333333333333333333 5 2 0 0 0 0 0 0 N N 1 3 6 3 0 0 0 10 0 0 0 0 2 0 4 1 l#C 3 0 0 0 0 0 8 0 2 1 1 E 2 1 1 3 1 2 0 0 0 0 0 0 8 DE 1 0 1 0 0 0 4 0 0 0 0 O 2 2 0 0 5 E 0 0 0 0 0 1 0 0 EE 0 1 2 1 0 0 0 0 6 1 1 0 0 2 1 1 0 0 0 12 SE 3 0 0 0 0 2 2 2 40 SK 2 1 10 5 0 0 0 0 0 0 0 3 10 12 0 0 0 36 S 4 0 0 0 2 3 12 13 SW 2 6 2 0 0 0 0 0 0 40 W 1 2 16 9 20 17 4 1 0 0 0 0 0 0 39 WW 0 1 6 7 2 0 0 0 0 0 0 36 t

W 4 4 13 0 0 0 0 21 6 3 1 0 0 bH4 4 1 6 0 0 0 0 13 0 2 0 0 24 3 1 5 5 0 0 14 1 0 0 0 0 5 4 0 4 0 333313333E M61 3323333333 33333333133213J333332333333333333333332323382233333333333333333333333333333 0 0 0 0 333 0 333 312333 332 29 77 95 56 27 1 TOTAL 27 MffER OF CALMS FOR 6 CTABILITY 13 TOTAL WLID HOURS FOR E ST ASLITIES = 6635 TOTAL IMLID HOURS FOR ALL .lTABLITIES = 637 1

I

1 of 6 AITACHMENT 1 j TABLE 4.11-1 RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM i

! LOWER LIMIT i

MINIHUM OF DETECTION LIQUID RELEASE SAMPLING ANALYSIS TYPE OF ACTIVITY (LLD)a !

TYPE FREQUENCY FREQUENCY ANALYSIS (pCi/mL)

A. Batch Waste P P Release Each Batch Each Batch Principal Gamma Sx10 7 Tanks b ,f,g,h,i Emitters e

1. Boric Acid I-131 1x10 6 ,

Condensate P M Dissolved and 1x10 5 4

i Entrained Gases

2. Waste One Batch /M (Gamma Emitters)

., Condensate P M H-3 1x10 5 d

Each Batch Composite

3. Laundry Gross Alpha 1x10 7 Waste 3

4. Turbine P Q Sr-89, Sr-90 5x10 8

) Building Each Batch Composite d Industrial Waste Fe-55 1x10 6 Sumps *

5. Dry Cooling

; Tower Sumps 1 #1 and #2a i .

6. Regenerative Waste

7. Filter Flush

8. Waste -

4

'When release from this source is batch in nature.

1 WATERFORD - UNIT 3 3/4 11-2 i

2 of 6 ATTAQMNT 1 r : -

TAB,LE 4.11-1 (Continued)

LOWER LIH1I MINIidM OF DETECTION LIQUID RELEASE SAMPLING ANALYSIS TYPE OF ACTIVITY (LLD)a TYPE FREQUENCY FREQUENCY ANALYSIS . (pci/mL)

8. Continuous W W Principal Ganna 5x10 7 Releases e.f I

. Grab Sample Emittars"

1. Turbine I-$1 MO*

Butiding -

Industrial h I Waste Sumpsaa. - --

M M Dissolved and 1x10 3

2. Dry Cooling Gr6 sample Entrained Gases . I Tower i (Gamma Emitters)

Sump #1** -

3. Def Cooling W . H H-3 Mps Tower i d i Grab Sample Composite '

- 3"P #

Grost Alpha Mo7

4. Circulating W q d

Sr-89, SW Wa i

. Watar , Grab Sample Composita Ofscharge- - Fe-55 1x10 8

. .. Steam Gene-rator Blow- -

. down HX ,

5. Auxiliary Component i Cooling i Vater Fumps

- Wn release free this source is continuous in nature. ,

WATERFORD - UNIT 3 3/4 11-3 M N M E No. 1

3 of 6 4 ATTAQMNr 1 TABLE 4.!!-1 (Continued)

, LOWER LIMIT MINIMUN LIQUID RELEASE $AMPLING ;',- OF DETECTION ANALYSIS TYPE OF ACTIVITY TYPE FREQ0ENCY (LLD)a FREQUENCY ANALYSIS (uC1/aL)

B. Continuous W W teleases e,f Princi al P Camma 5x10'I Continuoud Composited Emitters" -

6 ..

Steam Cenerator I-131 1xjo-6 Blowdowa Discharge j,1 '

H M Dissolvedand Crab Sample lx10-5 Entrained Gases (Gamma Emitters)

W M H-3 1x10-5 Continooask Composite Cross Alpha Ix10" l

W Continuousk Composite Q Sr-89, Sr-90 Sx!O'I

. Fe-55 .

lx10-6 1

i WATERFORD - UNIT 3 3/4 11-3a AMENDMENT NO. 1

4 of 6 ATTACHMENT 1 TABLE 4.11-1 (Continued)

TABLE NOTATION

The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system, which may include radiochemical separation:

LLD =

E V 2.22 x 106 Y exp (-Aat)

Where:

LLD is the "a priori" lower limit of detection as defined above, as microcuries per unit mass or volume, shis the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, as counts per minute, E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 2.22 x 108 is the number of disintegrations per minute per microcurie, Yisthefractiona(radiochemicalyield,whenapplicable, A is the radioactive decay constant for the particular radionuclide, and j at for plant effluents is the elapsed time between the midpoint of sample collection and the time of counting.

Typical values of E, V, Y, and at should be used in the calculation.

]

It should be recognized that the LLD is defined as an a priori (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.

b A batch release is the discharge of liquid wastes of a discrete volume.

Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed by a method described in the ODCM to assure representative sampling.

WATERFORD - UNIT 3 3/4 11-4

~

5 of 6 ATTACHMENT 1 TABLE 4.11-1 (Continued)

TABLE NOTATIONS c

The principal gamma emitters for which the LLD specification applies include the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Semiannual Radioactive Effluent Release Report pursuant to Specification 6.9.1.8.

d A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen that is representative of the liquids released.

'A continuous release is the discharge of liquid wastes of a nondiscrete volume, e.g., from a volume of a system that has an input flow during the continuous release.

Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.

U lf the contents of the filter flush tank or the regenerative waste tank contain detectable radioactivity, no discharges from these tanks shall be made to the UNRESTRICTED AREA and the contents of these tanks shall be directed to the liquid radwaste treatment system.

h Turbine Building Industrial Waste Sump (TBIWS)

The TBIWS shall be required to be sampled and analyzed in accordance with this table if any of the following conditions exist:

(1) Primary to secondary leakage is occurring; or, (2) Activity is present in the secondary system as indicated by either the SGB monitors or secondary sampling and analysis; or, (3) Activity was present in the TBIWS during the previous 4 weeks.

If none of the above situations exists, then the sampling and analysis of this stream need not be performed. .

I Sampling and analysis of the dry cooling tower sumps and the auxiliary component cooling water pump discharge will be required only when detectable activity exists in the CCW.

Sampling and analysis of the circulating water discharge-steam generator blowdown heat exchanger discharge (CWD-SGB) will be required only when i detectable activity exists in the secondary system. l WATERFORD - UNIT 3 3/4 11-5

6 of 6

~

, , A1TACHMLNI' 1 j Table 4.11-1 (Continued)

TABLE NOTATIONS s.

. .. ~ .

3 Sampling and analysis of the stes's generator blowdown vill be required only when the blowdown is directed to the circulating water system or Eaterford 3 waste pond. *

,, Steam generator blowdown to the Waterford 3 waste pond will be limited to ,

situations requiring secondary chemistry control where the Circulating Water system is not available or the " secondary chemistry is outside the requirements for. Circulating Water System discharge. Slowdown to the vasta poed will be terminated opeo , detection of sample a ' ctivity greater than the IID leFrels of Table 4.21-1 Section B. *

.. No be repres'entative of the quantities and concentration of radioactive materials in liquid effluents,tsamples shall be collected continuously -

in proportion to the rate of flow of the effluent stream.

I Steam generator bimodown discharge to the waste pond shall be limi,ted to a period of six months with the circulating water systen discharge'

,, path not available unless. radiation monitoring and automatic isolation capabilities are added to the waste pond discharge path.

I O

1 VATERMED - UNIT 3 3/4 11-Se AMFNTB&MT NO. 1

b TABLE 4.11-2 g RADI0 ACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM

= i o MINIMUM LOWER tlMIT OF i 5 SAMPLING ANALYSIS TYPE OF DETECTION (LLD)* ;

i GASEOUS RELEASE TYPE FREQUENCY FREQUENCY ACTIVITY ANALYSIS (pC1/mL) e P P b

5 A. Waste Gas Holdup Each Tank Each Tank Principal Gamma Emitters 1x10 4 '

I Tanks Grab Sample _

l P P >

c c Principal Gamma Emitters b

. B. Containment PURGE Each PURGE Each PURGE 1x10 4

] (Plant Stack) Grab Sample l M H-3 1x10.s c

C.1 Plant Stack M .d.i Principal Noble Gas Gamma b

1x10 4

Grab Sample M Emitters H-3 1x10 5 M C.2 Fuel Handling Md Principal Noble h

Gas Gamma lx10 4

Building Ven- Grab Sample M . Emitters U tilation H-3 1x10 6 i 4 (Normal)

Exhaust _ j D.1 All Release Types Continuous ,h.j f gg I-131 1xkO12 y .

i as listed in Charcoal !

j B., C.1, and Sample I-133 lx10 10 [

C.2 above -

D.2 Main Condenser Continuousf ,h,j gg PrincipafParticulateGamma 1x10 23 :

Evacuation and Particulate Emitters Turbine Gland Saniple !

Sealing System ,

l Continuous #'A'd M Gross Alpfla 1x10 83 ,

i Composite ,

Particulate !

j _

Sample _ _ _

! Continuous f h,j Q Sr-89, Sr-90 1x10 H !

Composite Particulate ;

1 __ __ _ _.

Sample _ _

r i

Continuousf ,h,j Noble Gas Noble Gases 1x10 8 !

Monitor Gross Beta or Gamma _ -

l

W 2 of 3 ATTACHMENT 2 TABLE 4.11-2 (Continued)

TABLE NOTATION a

The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system, which may include radiochemical separation:

LLD =

E V 2.22 x 10' Y exp (-Aat)

Where:

LLD is the "a priori" lower limit of detection as defined above, as microcuries per unit mass or volume, shis the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, as counts per minute, E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 2.22 x 108 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield, when applicable, A is the radioactive decay constant for the particular radionuclide, and at for plant ef fluents is the elapsed time between the midpoint of sample collection and the time of counting.

Typical values of E, V, Y, and at should be used in the calculation.

It should be recognized that the LLD is defined as an a priori (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.

WATERFORD - UNIT 3 3/4 11-11

3 of 3 ATTACHtENI' 2 TABLE 4.11-2 (Continued)

TABLE NOTATIONS b

The principal gamma emitters for which the LLD specification applies include the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 in noble gas releases and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, I-131, I-133, Cs-134, Cs-137, Ce-141, and Ce-144 in iodine .and particulate releases. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Semiannual Radioactive Effluent Release Report pursuant to Specification 6.9.1.8.

c Sam ling shall also be performed within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following shutdown, startup, or a THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour period. Analysis for principle gamma emitters as defined in (b) above shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of sampling.

d Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the refueling canal is flooded.

' Tritium grab samples shall be taken at least once per 7 days from the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool.

I The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Specifications 3.11.2.1, 3.11.2.2, and 3.11.2.3.

95amples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing, or after removal from sampler.

i Sampling shall also be performed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least 7 days following each shutdown, startup or THERMAL POWER change exceeding 15% of RATED THERMAL POWER in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing. When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding LLDs may be increased by a factor of 10. This requirement does not apply if (1) analysis shows that the DOSE EQUIVALENT I-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.

h If no primary to secondary leakage exists, then only the gross beta or gamma noble gases analysis need be performed for the main condenser evacuation and turbine gland sealing system. If a primary to secondary leak exists and the .

release from the main condenser evacuation and turbine gland sealing system $

has not been released via the plant stack, then the sampling and analysis must be performed.

I Note (c) above is not applicable for the plant stack unless the noble gas '

monitor shows that effluent activity has increased by a factor of 3.

IFuel Handling Building sampling is required whenever irradiated fuel is in the storage pool.

WATERFORD - UNIT 3 3/4 11-12

ATTACHMENT 3 0FFSITE DOSE CALCULATION MANUAL HP-1-230, Revision 5

I l

i I LouislANA

\

POWER & LIGHT l urorN sysYEM POM VOLUME 13

, HP-1-230 POM SECTION 3 REVISION 5

SURVEILLANCE PROCEDURE CFFSITE DOSE CALCULATION MANUAL i

LP&L W-3 RECORDS UNCONTROLLED 0 NOT USg ;g Agy SAF TY-RELATED TEyT{,W:,

COPY rin Oi:ERATIONA j)] , -

!/7 M AiNT..- . .. - :r.isnipogC heetins.No.

Reviewed '

A-% . / ~} 7&4'

.PORC Chairman DATE Approved lJ b /

Plant Manager-Nuclear DATE Effective Date l

l UNT-1-002 Revision 9 22 Attachment 6.3 (1 of 4) l l

l

3.C"JJ 00 P 3 = .

HP-1-230 - offsite Dose Calculation Manual (Rev. 5)

.C?.C LW1 he PC1C ha.s :ee.eved thi.s ites and determ1=ed that a saf ety evaluatian was perf:r=ad (as appl 14ahle), that an unreviewed saf ety question does not exist (as applicable),

that a chsage to the Tee w *=1 specifications is not required, and that nuclear saf er7 1.s/vas set adversely a.ffected.

P ca:xx Esc:neccci c C7 PCRC!G2SEE PCEC MEMBIE 701 AFFICTAL DA:Z 1Z7"l17 SI A tis l 40 sw artagandsat /

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~~ $/?J'l M l [2M7 re C x tsas se. 85-M Izan se.- 54' nass: 6 -d 7 #S Thi.s itas is r==had for approval? @ TIE O ==

his item requires s1C/NEC rev1.s prior to implemansattes2 O Tzs & so If yes, ensure doc.:zentation supporttag revisw is at.ar.hed.

This item requires QA review prior to FM-N approval? TZ: h No l CA M 7*ZU l 1aviewed W M / Ar na:E dA J Carperata QA Manager

?' A.T" MFACZ1 VC"*.?AR AFMC'14L (REFER TO 5.4.12.1)

C.mts :

Approved by N/v DATE M/N' Flaat :'. anger-Wucisar UNT-t-004, Revision 6 18 Attachment 6.1 (1 of 1)

l Raw COVII SEE:'

i HP-1-230 - (change 1) offsite Dose calculation Manual (Rev. 5)

IET:I3r CT: __

l

/ CRC 1. N.

i The PCEC has reviewed this itaa sad determined that a safety evaluation was perfor=ad (as applisabla), that an unreviewed saf ary questias does not exist (as appliaahla),

that a chsage to the T- w.4,.t Spesi!1aations is not required, and that muslaar safary is/was not adversely affected.

i canIn a m m a r'" 2

! or ranc mzu Et ranC uttexxx 7en a m oval cA:

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% TES l

This its requires SEC/3RC review prise to implasmatatisa? TES NC j If yes, assure doc u entatism supportins review is astsahed.

This itas requires QA review prior to F26-N approval? O TE: we i

C A I I T TIIT _

1eviewed Iry b/N DATE M / 4-cor,e =ta q. mana.or i

! 71.Mrf WACEIMJ.AR AF?tCTAL (RIFER TO S.4.12.1) i Cauments:

Approved by -

Nb Plant Manger <iusisar DATE I El10/c3L7' j

i UNT-1-004, Revision 6 18 , g l

i

)

l WATERFORD 3 SES PI. ANT OPERATING MANUAI, Check, Block Below l CE\NGE/ REVISION /DEIITION REQUEST glPOM I ((lPORC-S/C '

Procedure No. HP-/-03o Title orts,rs ocsa ca c< ments zeo./aec Effective Date (if different from appro' val date) t Ccmplete A. 3. and C

i. Expiration Date A. Change No.

l%h :nanent l[lDeviation B. Revision No. 9 ).A, 5 "Y [ ,

C. Deletion l[ LYES g l{lNO DESCRIPTION CF CHANGE OR REVISION he , AAmAJbt. mvvk- \[0 8"'3-A. Lhaa rn - \/ A X /G Dsln G

REASON FOR CHANGE REVISION. OR DEIITION

& n dlu Y nD aY _ r nlMd+, da n suuuL

~

ut M'M L REC >UIRED SIGNATJIS CRISINATOR f g --

a ! ,a L DATE /d ,

3 .[I^

SAFETY REVII'4 Caes this change, revision or deletion:

1. Change the facility as. described in the FSAR? YES NO

2. Change the procedures as described in the FSAR? YES N0

3. Concuct tests,' experiments not ddscribed in the FSAR7 'iIS 'N0 X

+. Require a change to the Technical Specifications? YES NO Y

f the answer, to any of the above is fes, complete and attach a 10CFR50.39 ::arcey - luat on.

SAFE ~T ?IVIEW cb / _

DATE /o/2.3/ff TEC*iNIC.C ?IVIEW ##__ , _Oh M % , DATE Jo/Es / rs, GPOUP EEAD REVII'4f

^

j DATE // /%Z((I TEMPORARY APPROIAUr I (SRO) d DATE TEMPORARY APPROVAU' DATE -

it!emporary approval must be followed by Plant Manager / APM-N - Nudlear approval within la days.

UNT-1-003 Revision 3 23 Attachment 6.7 (1 of 1)

WATERFORD 3 SES PIE T OPERATING MANUAL Check Block Below CFE GE/ REVISION / DELETION REQUEST @ 0M l((PORC-S/C Procedure No. M f -l - J 3 O IitleOG(<;4<- Dose _ C l<_ola t'e n Effective Date (if different from approval date) Now \

Cc:nolete A, 3. and C~ /

A. Change No. NA IMr:nanent I:lDeviation Expiration Date

3. Revision No. 5 C. Deletion i[ LEES l$NO DESCRI? TION OF CHANGE OR REVISION Ldi C.o n h n a co n E 4 4 1 o c n -f- T e c f o o r e v '. s e d % i n t I o d e_. I. 4 -6 REASON FOR CHANGE. REVISION. CR CELETION N s.w Tec h Soed-cc.4e e r r n . fo S. G. 8 .

O REOUIRED SIGNATURES ORIGINATOR j

(

% DATE la!/ V./ F S a

SAFEIT REV:EW Does :nis enange, revision, or deletion:

1. Change the facility as described in the FSAR? YES NO V

2. Change the procedures as described in the ESAR7 ES NG V

3. Conduct tests / experiments cot described in the FSAR? 'iES N0

' . . Recuire a change to the Technical Specifications? TES NO / i If One answer to any of .he above is yes, coreplete and attaca a i 10CIRSO.39 Sa'aty Evaluation.

SAFE ~Y REVIEW % DATI 4//1/r5 TECHNICAEPr.IEW hhO M DATE 6 I AO l MS~

GRCCP EEAD REVIEW UM' n d DATE G/24//f TEMPORARY APPR07AL* (SR0) DATE TEMPCRARY APPROVAL

DATE 1

Temporary approval must be followed by Plant P.anager/ APM-N - Nuclear approval within i

13. days.

Tl-1-003 Revision 3

3 Attachment 6.7 (1 of '.) l l

Survaillanca Prccedura HP-1-230 Offsite Dose Calculation Manual Revision 5 TABLE OF CONTENTS 1.0 PURPOSE

2.0 REFERENCES

3.0' PREREQUISITES 4.0 PRECAUTIONS AND LIMITATIONS 5.0 INITIAL CONDITIONS 6.0 MATERIAL AND TEST EQUIPMENT 7.0 ACCEPTANCE CRITERIA 8.0 PROCEDURE 8.1 Site Characteristics l

8.2 Radiological Environmental Monitoring Program 8.3 Radiological Environmental Monitoring Interlaboratory Comparison Program 8.4 Liquid and Gaseous Radwaste Block Flow Diagram 8.5 Liquid and Gaseous Waste Sampling and Analysis 8.6 Dose Calculations Due to Liquid Effluents 4

8.7 Determination of Alarm / Trip Setpoints for Liquid Monitors 8.8 Representative Sampling of Liquids 8.9 Projecting Dose for Radioactive Liquid Effluents 8.10 Dose Rate Due to Gaseous Effluents 8.11 Air Dose Calculations Due to Noble Gases 8.12 Dose Calculations Due to Radioiodines and Radioactive Materials in Particulate Form 1 8.13 Determination of Alarm / Trip Setpoints for Gaseous Monitors l 8.14 Projecting Dose for Radioactive Gaseous Effluents 8.15 40CFR190 Dose Evaluation 1

Survaillence Pracsdure HP-1-230 Offsite Dose Calculation Manual Revision 5 l

9.0 SETPOINTS q 10.0 ATTACHMENTS 10.1 Annual Average Dispersion and Deposition Parameters for Areas

at or Beyond the Unrestricted Area Boundary (Table 1) (1 page) 10.2 Radiological Environmental Monitoring Program (Table 2)

(2 pages) 10.3 Sample Location Table (Table 3) (9 pages) 10.4 Sector and Zone Designators for Radiological Sampling and Monitoring Points (Table 4) (1 page) 10.5 REMP Sample Location. 7'. thin 2 Miles of Waterford 3 (Figure 1) (1 page) 10.6 REMP Sample Locationa Within 10 Miles of Waterford 3

! (Figure 2) (1 page) 10.7 REMP Sample Locations Within 50 Miles of Waterford 3 (Figure 3) (1 page) 10.8 Liquid Waste Management System Effluent Sources and Release Pathways and Points (Figure 4) (2 pages) 10.9 Gaseous Effluent Sources, Gaseous Waste Management Systems Effluent Sources, and Exhaust Release Points (Figure 5)

(1 page) 10.10 Open Terrain Correction Factor (Figure 6) (1 page) 10.11 Site-Related Liquid Dose Factor (Table 5) (1 page) 10.12 Bioaccumulation Factor for Freshwater Fish and Invertebrate and Ingestion Dose Factors for Adults (Table 6) (5 pages) 10.13 Dose Factors for Exposure to a Semi-Infinite Cloud of Noble l Gases (Table 7) (1 page) s, 10.14 InhalationDoseFactorsforChip(Table 8)(3pages) hp 10.15 Values of L-Theta-V (Table 9) (44pages) ) qi ,

10.16 Pathway Dose Factors Due to Radionuclides Other Than Noble Gases, R (Table 10) (19 pages) 10.17 Relative Deposition for Ground-Level Releases (All Atmospheric Stability Classes) (Figure 7) (1 page) 2 1

Survaillanca Precidura HP-1-230 Offsite Dose Calculation Manual Revision 5 I

10.18 Annual Average Dispersion Parameters at or Beyond the Unrestricted Area Boundary (Table 11) (1 page) 10.19 Annual Average Deposition Parameters for Areas at or Beyond the Unrestricted Area Boundary (Table 12) (1 page)

10.20 ODCM Technical Specifications Cross-Reference (Table 13)

. (1 Page) 11.0 COMMITMENTS A D REFERENCES LIST OF EFFECTIVE PAGES i

Title Revision 5

, M Revision 5 FT-X

/-/03 Q t

a,3,4 c ,9 7, sr, cc , s1, co, <,e , n -so cq, 1. 'E y a

e, b

i e

3 .

-___.o, , , , . . , , . , . . . - _ , . -

Surveillt,nce Procedure HP-1-230 Offsite Dose Calculation Manual Revision 5 I l 4

1.0 PURPOSE 1.1 This document provides: (1) the general characteristics of the Waterford 3 site; (2) the detailed Radiological Environmental Moni-j toring Program (REMP); (3) the description of the Radiological

! Environmental Monitoring Interlaboratory Comparison Program; (4) the liquid and gaseous-radwaste block flow diagram; (5) the Radioactive Liquid and Gaseous Waste Sampling and Analysis Programs; (6) the

general methodology to be used to calculate dose to individuals due l to releases of radioactive gaseous and liquid effluents from the j' Waterford 3 site; (7) the general methodology to be used to calculate effluent monitor setpoints and allowable release rates to ensure j compliance with the Waterford 3 STS, 10CFR20, and 10CFR50 criteria; (8) the methodology to be used to ensure representative sampling of i liquids; and (9) the methodology to be used to comply with 40CFR190 criteria.

1.2 The Offsite Dose Calculation Manual (ODCM) follows the general models l

i suggested by NUREG 0133 (Nov., 1978) and Regulatory Guide 1.109

(Mar., 1976). However, alternate calculation methods from those i presented may be used provided the overall methodology is acceptable and consistent with regulation or provided the alternate methodology is conservative. In addition, the most up-to-date dose conversion f factors and bioaccumulation factors may be substituted in lieu of 1

j Regulatory Guide 1.109 values.

.I j 1.3 Actual step-by-step dose calculations will be performed by in plant j procedures which are consistent with the methodology presented in this document.

j

2.0 REFERENCES

l l 2.1 Waterford SES Unit 3 STS (Standard Technical Specifications), Chapter 16 of Waterford 3 FSAR l -

4

,-.---m. . -w---, rr---, , - - . . , . .,r-+..-, -w , - - . . ., ,--.w -w--,.., ,m--.- , ~.,w,, 4-,. - -.., -,--,, --~-- - . , , , - -,-r.,e v--,y. ,r, ,,

Survailltaca Pecctdure HP-1-230 Offsite Dose Calculation Manual Revision 5 2.1.1 Technical Specification Section 3/4 11.1 2.1.2 Technical Specification Section 3/4.11.2 2.1.3 Technical Specification Section 3/4.11.4 2.1.4 Technical Specification Section 3/4.12.1 2.1.5 Technical Specification Section 3/4.12.3 2.1.6 Technical Specification Section 6.14.1 2.1.7 Technical Specification Section 6.14.2 2.1.8 RP-1-215, NRC Radiological Reporting Requirements 2.2 USNRC Regulatory Guide 1.111, Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases of Gaseous Effluents from Light-Water-Cooled Reactors, July 1977 2.3 USNRC Regulatory Guide 1.113, Estimating Aquatic Dispersion of Ef-fluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I, April 1977 2.4 USNRC Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of i

Evaluating Compliance with 10CFR Part 50, Appendix I. Revision 1, OctcLer, 1977 2.5 USNRC NUREG 0133, Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants, October 1978 2.6 Title 10, Code of Federal Regulations, Parts 20, 50 and 100, Latest Edition 5

HP-1-230 Surv:;illance Pr:cidura R;visien 5 Offsite Dose Calculation Manual 2.7 Title 40, Code of Federal Regulations, Part 190, Latest Edition I u

1 3.0 PREREQUISITES 1 NONE en 4.0' PRECAUTIONS AND LIMITATIONS References 2.1.6 and 2.1.7 should be satisfied at all times 5.0 INITIAL CONDITIONS I

Reference 2.1.6 should be satisfied prior to implementation. ,

6.0 MATERIAL AND TEST EQUIPMENT NONE 7.0 ACCEPTANCE CRITERIA NONE l

8.0 PROCEDURE 8.1 SITE CHARACTERISTICS Waterford 3 SES is located on the west (right descending) bank of the Mississippi River at River Mile 129.6 between Baton Rouge, Louisiana, and New Orleans, Louisiana. The site is in the north-western section of St. Charles Parish, Louisiana, near the towns of Killona and Taft.

6

Survaillance Precadura HP-1-230 Offsita Dsca Calculstien M: nuel Rtvision 5 The geographic coordinates for the Waterford 3 reactor are Latitude

. 29' 59' 42" North, and Longitude 90' 28' 16" West. Based on the UTM (Universal Transverse Mercator) Zone 15, the UTM coordinates are Northing 3,320,743 meters and Easting 743,962 meters.

The Mississippi River is the closest prominent natural feature to Waterford 3, while other important natural features include Lac des Allemands, about 5.5 miles southwest of the site, and Lake Pontchar-train, about 7 miles northeast of the site. The land slopes gently from its high points near the Mississippi (10-15 ft. above mean sea level) to extensive wetlands located 1.5 to 2.5 miles inland from the river.

Most of the man-made features are located on the narrow strip of dry land between the Mississippi River and the wetlands. Near the Waterford 3 site are several large industrial facilities, including Waterford 1 and 2 (0.4 miles northwest of the site), Little Gypsy Steam Electric Station (0.8 miles northeast of the site, across the river from Waterford 3), Beker Industries, a fertilizer manufacturer (0.6 miles east-southeast), Occidental Chemical Company (0.8 miles east-southeast), and Union Carbide, a chemical manufacturer (1.2 miles east-southeast). Louisiana Power & Light Company (LP&L) owns and operates the above-mentioned steam electric stations.

A map of the UNRESTRICTED AREA and SITE B0UNDARY for radioactive ef-fluents (Figure 5.1-3) is provided in the STS. LP&L will have full control of all activities conducted within the exclusion area boundary of the Waterford 3 site. All of the property within the designated exclusion area is owned by LP&L with the exception of the bottom lands below mean low water of the Mississippi River.

LP&L owns, in title, all surface rights within the exclusion area boundary of the plant. There is presently no intention to allow ex-pioration for subsurface minerals from points on the surface of the exclusion area. .

I l

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

Surveillance-Procedure HP-1-230 Offsite Dose Calculation Manual ' Revision 5 1

4

.1

, The Mississippi River, Louisiana Highway 18, the Missouri Pacific Railroad right-of-way,.and the west (right descending) bank levee of the Mississippi River constitute traversals of the site exclusion 4

area as allowed by 10CFR100.3 (a). Refer to the Waterford 3 Emergency Plan Implementing Document for the arrangements which have been made l to give LP&L authority and control over these traversals. (Note that Louisiana Highway 3127 does traverse the SITE BOUNDARY but not the 1

! exclusion area. However, LP&L does have the authority to control 1'

this traversal in accordance with the Waterford 3 Emergency Plan Implementing Document.) j In addition to Waterford 3, there are two fossil-fueled units, l Waterford SES Units 1 and 2, which are owned by LP&L and which are j within the site exclusion area. The plant staff for these two units

 !                             consists of about 60 people. Since this includes workers assigned l                               to shif ts, it is a conservative estimate of the maximum number of l                             fossil plant personnel that would be within the exclusion area at

! any given time. Evacuation procedures for Waterford SES Units 1 and j 2 are described in the Waterford 3 Emergency Plan Implementing Document. A portion of the land within the SITE BOUNDARY is utilized for , agricultural activities. Farmers presently work the land but

can be expected to actually be in the field less than 10 percent of

 <                             the time.

1 I

Fishing in the Mississippi River from the batture is a rare practice ;

in the Waterford area. An estimated maximum of 2 people may be ex-pected to be engaged in this activity for a period less than 10 percent of the time within the exclusion area. i s 8 1

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

Surveillence Procedure HP-1-230 Offsite D2sa Calculetion Minus1 Revision 5 I Texaco maintains a gas valve station east-southeast of the Waterford 3 SES island structure juct within the radius of the exclusion area. This valve station is automated and requires only periodic monthly maintenance involving, typically, two persons. Evacuation procedures for these maintenance workers are described in the Waterford 3 Emergency Plan Implementing Document. The Waterford property is shown in Figure 5.1-3 of the STS and includes 3,561.3 acres. The plant area is about 48 acres and is defined as including the fenced area immediately adjacent to Waterford 3. The site area is shown in Figure 5.1-3 of the STS along with principal station structures and nearby features. The site includes only station structures and does not include any residential, recreational, or other industrial structures. There is a visitor center approximately 1.0 mile SSW of the plant. The SITE BOUNDARIES for establishing effluent release limits along with radioactive effluent release points are given in Figure 5.1-3 of the STS. The nearest distances to the boundary line are shown in Table 1 of this procedure. The release point elevations for gaseous effluents are provided in Figure 5.1-3 of the STS. The restricted area, defined for the purpose of controlling ingress into and egress from the site, coincides with the plant area which is enclosed by the plant perimeter fence. 9

1 Surv2illanca Proc: dura HP-1-230 Offsite Dose Calculation Manual Revision 5 For the purpose of establishing effluent release limits in accordance with 10CFR20 and Appendix I to 10CFR50, the concept of the restricted area, as defined above for the purpose of ingress and egres's control, is not applicable. The effluent release limits are established in order to ensure that: (1) the concentrations of the radionuclides in gaseous effluents discharged from the plant stack and exhaust systems do not result in exceeding the limits outside the site boundary set forth in Table II, Column 1 of Appendix B to 10CFR20; (2) the concen-tration of radionuclides in liquid effluent at the unrestricted area boundary does not exceed the limits set forth in Table II, Column 2 of Appendix B to 10CFR20; and (3) the cumulative liquid and gaseous radionuclide releases do'not result in exposures to individuals outside the UNRESTRICTED AREA or SITE BOUNDARY in excess of the limits set forth in Appendix I to 10CFR50. 1980 population by annular sectors within 5 miles of Waterford 3 can be found in the Environmental Report. Population was estimated for 1977 and projected for 1980. The methodology for estimating and projecting population is described in detail in section 6.1.4.2 of the Environmental Report. The closest town to Waterford 3 is Killona, 0.9 miles west-northwest. Other towns near the plant include Norco 2.5 miles east; Hahnville, 3.7 miles east-southeast; and Laplace, 4.7 miles north. There are also smaller settlements and homes along both banks of the river, the nearest such place to Waterford 3 being Montz, 1.0 mile northeast. 8.2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM This section satisfies Surveillance Requirement 4.12.1 of the Waterford 3 STS. 10

Survaillance Procsdure HP-1-230 Offsite Dose Calculation Manual Revision 5 Table I shows the average annual dispersion parameters for areas at or beyond the exclusion area boundary. This table will be subject to change based on the annual land-use census results. Tables 2, 3 and 4 are the detailed Radiological Environmental Monitoring Program, the Sample Location Table, and the sector and zone designations for the sample locations, respectively. Figures 1, 2 and 3 show the sample locations for samples within 2,10 and 50 miles of Waterford 3, respectively. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability,-malfunction of automatic sampling equipment and other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction, every effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be docu-mented in the Annual Radiological Environmental Operating Report. It is recognized that, at times, it may not be possible or practical to continue to obtain samples of the media of choice at the most desired location or time. In these instances, suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the Radiological Environmental Monitoring Program. 8.3 RADIOLOGICAL ENVIRONMENTAL MONITORING INTERLABORATORY COMPARISON PROGRAM This section satisfies Surveillance Requirement 4 12.3 of the Waterford 3 STS. 11

Survaillance Proccdure HP-t-230 Offsite Dose Calculation Manual Revision 5 Quality assurance in radiological environmental sampling will be maintained through participation in the Environmental Protection Agency's Radiological Laboratory Quality Assurance Program. The summary of results will be presented in tabular form and will detail the type of analysis, the preparation (collection) date, the date i the results are returned, the mean of the analyses (usually tripli- [ cate), the standard deviation, the date the values are released for information, the known value, the three standard deviation limit, and a two standard deviation /three standard deviation warning / action , flag. If the sample analysis indicates results outside the three l standard deviation range, then the corrective actions taken to prevent a recurrence will be documented and submitted along t/ith all results when the Annual Radiological Environmental Operating. Report is submitted. 8.4 LIQUID AND GASEOUS RADWASTE BLOCK FLOW DIAGRAM This section of the document presents the block flow diagrams for the radwaste systems. Any modifications to the radwaste systems

)               should be documented in the ODCH. In order to obtain a more detailed description of the various components, see the appropriate sections of the FSAR. Figures 4 and 5 show the existing radwaste systems, i

8.5 LIQUID AND GASEOUS WASTE SAMPLING AND ANALYSIS . 8.5.1 Liquids 8.5.1.1 At Waterford 3 there are four liquid holdup systems i that should always contain detectable activity. l These liquid radiological effluent batch release ( systems include: I s

!                                                          12

Survailitnca Precedura HP-1-230 Offsito Dosa Calculstien Manus 1 Rsvisicn 5 A. Boric Acid Condensate (BAC) - four tanks B. Waste Condensate (WC) - two tanks C. Laundry Waste (LW) - two tanks D. Waste Tanks (WT) - three tanks 8.5.1.2 In addition to the tanks above, there are other holdup tanks and sumps that may contain detectable activity. These tanks and sumps include the following: A. Regenerative Waste Tank (RWT) - one tank B. Filter Flush Tank (FFT) - one tank C. Turbine Building Industrial Waste Sump (TBIWS) - two sumps D. Dry Cooling Tower Sumps (DCTS) - two sumps NOTE If flow to the sump is isolated and volume of release is known, sump discharge may be treated as a batch release rather than a continuous release. 13 l 1

Survailicace Procsdura .HP-1-230 Offsite Dose Calculation Manual Revision 5 8.5.1.3 If the contents of the RWT or FFT contain detectable radioactivity, no discharges from these tanks shall be made to the UNRESTRICTED AREA and the contents of these tanks should be directed to the liquid radwaste treatment system. The TBIWS shall be required to be sampled and analyzed if any of the following condi-tions exists: (1) primary to secondary leakage is occurring or (2) activity is present in the j secondary system, as indicated by either the steam j generator blowdown monitor or secondary sampling and analysis; or (3) activity was present in the TBIWS during the previous four weeks. If none of these situations exists, then the sampling and analysis of this stream need not be performed. Sampling and I analysis of the DCTS will be required only when j detectable activity exists in the Component Cooling l Water System, i i ] 8.5.1.4 There are three additional liquid radiological effluent continuous releases at Waterford 3. These include: l A. Circulating Water Discharge

1. Steam Generator Blowdown 4 2. Steam Generator Blowdown Heat Exchanger i

i l B. Auxilliary Component Cooling Tower (Water) pumps ) (ACTP) i I 8.5.1.5' The Steam Generator blowdown will be analyzed weekly ! via an in-line continuous composite sampler when j blowdown is discharged to the waste ponds or 1 i circulating water discharge. i t I

1 l 14 i

i

Survaillsnca Pr:c2 dura HP-1-230 Of fsits Dose Calculatica M:nusi Rsvision 5 i i 1 8.5.1.5.1 Steam generator blowdown may be routed to the waste ponds only if no detectable radioactivity is present. i 8.5.1.6 Sampling and analysis of the steam generator I blowdown heat exchanger will be required only when 4 detectable activity exists in the secondary system, j i 8.5.1 7 Sampling and analysis of the ACTP discharge will be required only when detectable activity exists in the Component Cooling Water System.

;               8.5.2 Gases i

i 8.5.2.1 Waterford 3 gaseous radiological effluent batch releases include: s A. Waste Gas Holdup Tanks (WGHT) - three tanks l within the Gaseous Waste Management System (GWMS) B. Containment Purge (CP) 8.5.2.2 Gaseous radiological effluent continuous releases should include: i A. The Fuel Handling Building (FHB) ventilation exhaust B. The Containment Purge (CP)

;                               C. The Plant Stack (PS)

J D. The Main Condenser Evacuation and Turbine Gland Sealing System (MCE & TGSS) l l i j ! 15

Survailicace Procsdure HP-1-230 Offsite Dose Calculation Manual Revision 5 4

j 8.5.2.3 For the MCE & TGSS, if no primary to secondary 1eakage exists, then only the RETS Table 4.11-2 gross l beta or gamma analysis need be performed. If a 1 j primary to secondary leak exists and the release from the MCE & TGSS has not been released via the PS, then I the sampling and analysis found in Table 4.11-2 must be performed. A continuous permit should be issued if detectable activity is released through the MCE and TGSS. i

8.6 DOSE CALCULATIONS DUE TO LIQUID EFFLUENTS This rection presents the calculated methods used for calculating i liquid effluent doses in accordance with Surveillance Requirements

!                                               4.11.1.1.1, 4.11.1.2 and 4.11.1.3.1 of the Waterford 3 Standard Technical Specifications (STS).

I. i i i NOTE i l The Waterford 3 Radiological Effluent Technical l Specifications (RETS) are a subset of the Waterford 3 STS. For purposes of this document, RETS and STS are l interchangeable.

                                            ~
!                                                                                                                                          m j'                                               8.6.1      The dose contributions for the total time period g{ gat t

) should be determined by calculation at least once every 31 days and a cumulative summation of these total body and any organ doses should be maintained for each calendar quarter. I j These dose contributions should be calculated for all radio-nuclides identified in liquid effluents released to the i UNRESTRICTED AREA using the following expression: i

                                                                     -                                                                                                             j j                                                                                             16 l

I i

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

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

Survaillrnca Pescidura HP-1-230 Offsite Dose Calculation Manual Revision 5 Dtt

O A 1 ibi gg A C ig W m

( Dt *Ab1 D tt where: D gg = the cumulative dose commitment to the total body or any organ (t) from the liquid effluents for each liquid release in eres during time period (t) Dg = the cumulative dose commitment to the' total body or any organ (t) from the liquid effluents for all (t) time periods a g{g at gin mrem at g = the length of the 1 time period over which the release is made, in hours C gg = the concentration of radionuclide (i) in undiluted liquid effluent during time period Atg from any liquid release, in pCi/ml A = the site-related ingestion dose commitment factor to it , the total body or any organ (t) for each identified nuclide (i) listed in Table 4.11-1 of the Waterford 3 STS in aree-el per hr-pci (Table 5) Fg = the near field average dilution factor for C gg during any liquid effluent release. Defined as the ratio of the undiluted liquid waste flow during release to the average flow from the site discharge structure to site boundary receiving waters. i 17

i Surveillance Procedura HP-1-230 Offsite Dose Calculation Manual Revision 5 l Fg = liquid radioactive waste flow j discharge structure exit flow

The liquid radioactive waste flow is the maximum flow from the i effluent release. The discharge structure exit flow is the j flow during disposal from the discharge structure release 1
point into the receiving water body. For radionuclides not l determined in each batch or weekly composite,- the dose contri-

) - bution to the current calendar quarter cumulative summation may be approximated by using a ratio of concentrations based 1

   ;                                                                  on the previous monthly or quarterly composite analyses. When the current quarterly composite is analyze'd, these contribu-1                                                                      tions will be updated as appropriate.

i I 8.6.2 Equation (2) above for calculating the dose contributions i requires the use of a dose factor, Agg, for each nuclide (i) ! which embodies the dose factors and dilution factors for the r

}                                                                     points of pathway origin. The adult total body dose factor f                                                                      and the adult organ dose factor for each radionuclide will be used from Table E-11 of Regulatory Guide 1.109; thus the list contains critical organ dose factors for various organs. The

! dose factor is written: i A ge = K,(U,/D, + U BF (3) g f) DCFgg i i where: l U, = 730 kg/yr. adult water consumption 1 ! Dw = Dilution factor from near field area to potable water i intake = 220 i 4 l 220 = ava Mississippi flow i l maximum discharge flow i i 1 18 i \ L, , . . _ . , - - , - - - - , - - , , . - - - . . . . , , - - _ , - - - - - . - - . . - , - . - - - - - _ . - -

Survaillance Proctdura HP-1-230 Offsite Dora Calculatien M:nual Revision 5 A it = Composite dose parameter for the total body or critical organ (t) of an adult for nuclide (i) for all appro-j priate pathways (ares /hr per pCi/ml) K, = Units conversion factor,1.14E5 = 10s pCi/pci x 10 3 ml/l + 8760hr/yr Ug = 21 kg/yr, adult fish consumption BFi = Bioaccumulation factor for nuclide (i) in fish (pCi/kg per pCi/1) from Table A-1 of Regulatory Guide 1.109 (Table 6) DCFgg = Dose conversion factor for nuclide (i) and organ (t) for adults (mrem /pci). Values are from Table E-11 of i Regulatory Guide 1.109 (Table 6)

!                  Inserting the usage factors of Regulatory Guide 1.109 as appropriate into equation (3) gives:

Ag = [(3.78E + 5) + (2.39E + 6)BF g] DCF gg (4) i NOTE For other liquid pathways, the appropriate dose factors will be utilized. 1 4 l 19

Survaillcnca Precidura HP-1-230 , Offsite Dona Calculstien M:nu21 Revision 5 t I l 8.7 DETERMINATION OF ALARM / TRIP SETPOINTS FOR LIQUID MONITORS ! Waterford 3 STS 3.3.3.10 and 3.11.1.1 require that the liquid ef- ' l fluent monitoring instrumentation alarm / trip retpoints be set so that the concentration of radioactive material released from the site is limited to 10CFR20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. (For dis solved or entrained noble gases, the concentratioh shall be limited to 2E-4 pCi/ml total activity.) This section presents , the method to be used for determining setpoints in accordance with - Surveillance Requirements of 4.11.1.1.2 of the Waterford 3 STS. , 8.7.1 Determination of Liquid Monitor Setpoints 8.7.1.1 The calculated setpoints for the liquid effluent monitors satisfy the following equation: n i

                                                       "_~ (SF) (RF) (F + f)(Z Ci g

(5) TMPC (f) r where; + n IC g = the undiluted effluent gamma concentration in pCi/ml ;

                                       *l for all radionuclides (1). The value will be derived from radioanalysis of liquid effluent to be released.

This value will be supplied for each liquid release. 20

Survaillcnce Procedura HP-1-230 Offsite Dose Calculation Manual Revision 5

c= the setpoint, in pCi/ml, of the liquid effluent monitor measuring the radioactivity concentration in the effluent line prior to dilution and subsequent release. This setpoint represents a value which, if exceeded would result in concentrations exceeding the limits of 10CFR20, Appendix B, Table II. Column 2, to an UNRESTRICTED AREA.

f= the liquid effluents flow as measured at the liquid effluent monitor location in spa. 1 F= the dilution water flow as determined via pump curves or other apropriate measures that determine currect plant operating configuration in spa. j NOTE F is large compared to f; .". F + f 2 F. SF = Safety factor to en:;ure that the effluent limit is I not exceeded. Actual value is set by procedure (in the range 0.5 - 0.9). I RF = Release fraction allocated to this release (to be used only in situations of simultaneous or concur-4 rent release). n C m C TMPC = ({1MPC *j!1M j i k = the undiluted nongamma MPC) fraction for all MPC J nongamma radionuclides (j) l l

                                                                .                                                                                                          l l
,                                                                                        21 I

Survaillenc2 Preccdure HP-1-230 Offsite Dose Calculation Manual Revision 5 1 C i = undiluted gamma MPC g fraction for all gamma MC i radionuclides (i)

                          = Maximum Permissible Concentration for the applica-MPC) 1 ble nongamma-emitting isotope (j) from 10CFR20, Appendix B, table II, column 2.

MPC g = Maximum Permissible Concentration for the applica-ble gamma-emitting isotope (i) from 10CFR20, Appendix B, table II, Column 2. 8.7.1.2 The values of C f and C) will be measured for each release and the parameters for f and F will be supplied based on current plant operating configura-tions. The setpoint will be calculated in terms of pCi/ml and the liquid effluent monitor will be adjusted as necessary to ensure that liquid releases are secured prior to exceeding limits specified in 10CFR20, Appendix B. Table II, Column 2 to an UNRESTRICTED AREA. l l Example: { Assume Cg = 3E-4 pCL/mi C) = 3E-4 pCi/ml f = 50 spa F = 750,000 sps MPCg = 2E-5 pCi/ml NPC) = 3E-7 pCi/mi 22

                                                                                          .~.  -     .      -

Surv2illence Precedura HP-t-230.

Offsite D: ss Calculation M:nust Revision 5 ;

l 5 l t c = (g) ;TMPC = 3 = 1E+3 5+ i 3E-4 pCi/ml)(750.000 men) {

                                                          , , ((50 sym) (1E+3) c = 4.51E-3 pCi/ml Then the SF and RF values can be applied; e.g., SF =

0.8 and RF = 1 because normally concurrent releases ; will not occur. c = 3.61E-3 pCi/ml I 8.8 REPRESENTATIVE SAMPLING OF LIQUIDS 8.8.1 Prior to grab sampling liquid waste tanks, methods should be ! used to guarantee representative sampling. Large volumes of l liquid waste should be mixed in as short a time as possible f and uniformly distributed prior to sampling. To determine the minimum mixing time for tanks from which releases are made, the following tests were performed prior to initial use for ' release purposes. I i 8.8.1.1 The tank was filled to a known volume. l 8.8.1.2 A specific quantity of a selected chemical and/or ) sediments was added to the tank. ; i 8.8.1.3 Recirculation was initiated through the normal I path. 8.8.1.4 Periodic samples was taken until equilibrium is i reached. I t 23 !

Survai11caca Procsdure HP-1-230 Offsite Dose Calculation Manual Revision 5 l 8.8.1.5 The time observed to completely mix the tank is used as a minimum recirculation time prior to effluent sampling. Records of the test will be maintained, i 8.9 PROJECTING DOSE FOR RADIOACTIVE I.IQUID EFFLUENTS , i Technical Specification 3.11.1.3 requires that appropriate subsystems { of the liquid radwaste treatment system be used to reduce releases of radioactivity when the projected doses due to the liquid effluent ;

            ,           from each reactor unit to UNRESTRICTED AREAS would exceed 0.06 mrem total body or 0.2 mrem to any organ in a 31-day period. The following                               ;

calculational method is provided for performing this dose projection. fi At least once every 31 days, the total dose from all liquid releases ! for the quarter-to-date will be divided by the number .of days into ! the quarter and multiplied by 31. If this projected dose exceeds 0.06 mrem total body or 0.2 arem any organ, and the Liquid Waste Management System has not been operating, it shall be operated, if j operation would reduce the monthly projected doses below 0.06 mres ! total body or 0.2 mrem any organ. (This is performed in accordance with Surveillance Requirements 4.11.1.3.1 and 4.11.1.3.2.) ! l 8.10 DOSE RATE DUE TO GASEOUS EFFLUENTS [ i This section presents the calculational methods used for calculating l gaseous effluent doses in accordance with Surveillance Requirements ; 4.11.2.1.1 and 4.11.2.1.3 of the Waterford 3 STS. ; l i t l k i f 24

Survaillcres Prcesduro HP-1-230 - Offsite Dose Calculation Manual Revision 5 l l l 8.10.1 Real Time Meteorological input The instantaneous dose rate due to radioactive materials released in gaseous effluents from the site to areas at and ' beyond the SITE BOUNDARY shall be limited to the following values: 8.10.1.1 Release rate limit for noble gases: l n D eb 8 X'(X/Q)g,g{g Kg (Q)(y (6) n Des"X(X/Q)0viki(Li* I*IN ) (0)iv i II) 8.10.1.2 Release rate limit for Iodine-131, Iodine-133, , tritium, and radionuclides in particulate form with half-lives greater than 8 days: n i DOI * (X/030v(b1 Pit (0)iv (0) where: ' D eb a the instantaneous dose rate to the total body (b) due f to noble sases in sector 8 for the release in I ares /yr; not to e.xceed 500 mrea/yr l l l a D es the instantaneous dose rate to the skin (s) due to , noble gases in sector 6 for the release in eres/yr;

  .                                 not to excee1 3000 mres/yr a

25 i l

l. _ - - _ _ - _ _ . - . - -

Surv:111 taco Pr csdura HP-1-230 Offsite Dose Calculation Manual Revision 5 D6I = the instantaneous dose rate to the child thyroid (!) for Iodine-131, Iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days in sector 8 for the release in units of nres/yr; not to exceed 1500 area /yr. K' = a constant of unit conversion, IE6pci/pci. Kg= the total body dose factor due to gamma emissions for each identified radionuclide (i) in units of ares /yr per pCi/m 8 (Table 7). Lg a the skin dose factor due to beta emissions for each identified radionuclide (i) in units of arad/yr per pCi/m 8 (Table 7), Ng= the air dose factor due to gamma emissions for each identified radionuclide (i) in units of arad/yr per pCi/m 3 (Table 7). P a the thyroid dose parameter for Iodine-131, Iodine-133, gg tritium, and radionuclides in particulate form with half-lives greater than 8 days (i) for the inhalation pathway only, in mres/yr per pCi/m3 (Table 10, Page 2). The dose factor is based on the most restrictive group (child) and most restrictive organ at the SITE BOUNDARY. 8 Pg= (child breathing rate of 3700 m /yr)(DFA g) (K') where DFA g is the inhalation dose factor for each radio-nuclide from Table 8, l 26

3 s Survaillence Preccdure 2. j HP-1-230 Offsite Dosa; Calculation tirnual s Revision 5 n g3= I summation for all identified radionuclides (Q)gy = the average release rate of noble gas or of Iodine-131, Iodine-133, tritium, and radionuclides in the parti-

     .                                    culate form with half-lives gr: eater than 8 days (i) during the time of release from all vent releases (v). Value is averaged over one hour and is in units c,f pCi/sec.

(X/Q)0v = e average atmosphere dispersion factor at the SITE I BOUNDARY for the time of the release in sector 6 in 3 rec /m for all vent releases (v). hhen release time is greater than 1 hour, the average shall be based on observations of windspeed and atmospheric stability taken at least every hour during the release. (X/Q)0v *Lov/" 4 where:

                           "    =         the average wind speed determined at least hourly, during time of the release, in sector 0 , at 10 meters above grade, in m/sec and,               L ev = 2.032/r0 1 4*

2.032 = (2/n)b divided by the width in radians of a 22.5* sector. r the distance from the release to the receptor for 0= each sector (0) in m, and provided in Table 9.

                 ,                                      27

Survaillance Procedura HP-1-230 Offsite Dose Calculation Manual Revision 5 I.= zj the vertical (z) standard deviation of the materials in the plume, for stability class j, with a correc-tion for additional dispersion within the building wake cavity, restricted by the condition that 2 2 I zj = (ozj + 0.5Dz /n) < /3 ozj. furthermore, I zj. = Ji azj. when

(o,3 + 0.5Dz /n) > a zj and Dz = the maximum adjacent building height (z) either up or downwind from the release point. o = the vertical (z) standard deviation of the material zj in the plume at the downwind distance for stability class j. i 28

Survaillance Procedure HP-1-230 Offsite Dose Calculation Manual Revision 5 Time (X/Q) values to be calculated using the above model will be adjusted to reflect the results of analysis of the straight line trajectory model (Reference 2.2, R.G. 1.111, Sections C.1.c and C.2.c). This adjustment is accomplished by multiply-ing the (X/Q) values by the correction factors, found in Figure 6, which applies to areas with terrain features similar to those at the Waterford 3 site. NOTE The Radioactive Effluent Release Report, to be sub-mitted within 60 days after January 1, of each year, shall include an annual summary of hourly meteorological data collected over the previous year. The meteorolog-ical conditions concurrent with the time of release of radioactive materials in gaseous effluents, as deter-mined by sampling frequency and measurements, shall be used for determining the gaseous pathway doses. 8.10.2 No Real Time Meteorological Input (Used in Place of Real Time) The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY shall be limited to the following values and expressions: 8.10.2.1 Release rate limit for noble gases: n . K' (X/Q)y g[3 Kg Qgyi 500mres/yr, total body (9) n . l K' (X/Q)y g{y(L1 + 1.1M )gQgyi 3000 mrem /yr. skin (10) i

                                ~                                                         \

29

Surveillance Procedure HP-1-230 Offsite Dose Calculation Manual Revision 5 8.10.2.2 Release rate limit for Iodine-131, Iodine-133, tritium and for all radionuclides in particulate form with half-lives greater than 8 days: n . K' (X/Q)y i3 Z P it Niv< 1500 mrem /yr any organ (11) Where: Q gy = the average release rate of radionuclides (i) in gaseous effluent from all vent releases (v) in pCi/sec 3 (X/Q)y = 1.1E-5 sec/m in the ESE sector at 0.6 mile for all vent releases (v) (the highest calculated annual average dispersion factor at the SITE BOUNDARY) NOTE All radioiodines are assumed to be released in elemental form. 8.11 AIR DOSE CA1.CULATIONS DUE TO NOBLE GASES This section presents the calculational methods used for calculating noble gas effluent dose to air in accordance with Surveillance Requirement 4.11.2.2 of the Waterford 3 STS. 8.11.1 Real Time Meteorological Input The air dose due to noble gases released in gaseous effluents to areas at and beyond the SITE BOUNDARY will be determined by the following expressions: 30

Surveillence Procedure. HP-1-230 Offsite Dose Calculation Manual Revision 5 8.11.1.1 During any calendar quarter, for gamma radiation: n m D 0y =(1.14E2)g{g(M) g {1 (at)) (X/Q)jev (9)ijv (12) During any calendar quarter, for beta radiation: a m D 0 =(1.142)g{g(N)j{3(at)(X/O g j j0v(9)ijv (13) 8.11.1.2 During any calendar year, for gamma radiation: a m D 0y = (1.14E2) g{g (M g ) j{g (at)) (X/Q) jev(9)ijv (14) During any calendar year, for beta radiation: n m D OS = (1.14E2) f{g (N g ) ){g (at ) (X/Q) jov(9)ijv (15) where all terms are as previously defined; and D the total gamma (y) air dose in sector 6 from 0y = gaseous effluents for the total time period (e.g., quarter or year) m j b O'j 1 and not to exceed 5 mrad quarterly or 10 mrad yearly D = the total beta ( ) air dose in sector 0 from gaseous 0 effluents for the total time period (e.g., quarter or year) m jb1 0 j and not to exceed 10 mrad quarterly or 20 mrad yearly Y#* 1.14E2 = ( pct? ) (8760hr.) 31

Survaillence Procedure HP-1-230 Offsite Dose Calculation Manual Revision 5 (Q)gjy = the average release rate of radionuclides (i) during the time of release At. for vent releases (v) J Atj = the length of the j time period over which (X/Q)0v and Q gjy are accumulated for all gaseous releases (hours). Mg and Ng = the gamma and beta air dose factors (respectively) for a uniform semi-infinite cloud of radionuclide (i) (mrad /yr per pCi/m3 ) (Table 7) (X/Q)j0v = e average ato spheric dispersion factor at the site boundary for the time of the release (j), in sector (0), in sec/m3 , for all vent release s (v). When release time is greater than one hour, the average shall be based on observations of windspeed and atmospheric stability taken at least every hour during the release. 8.11.2 No Real Time Meteorological Input (Used in Place of Real Time) The air dose due to noble gases released in gaseous effluents to areas at or beyond the SITE BOUNDARY will be determined by the following expressions when the real time meteorological inputs are not applicable: 8.11.2.1 During any calendar quarter, for s.ma radiation: n m D = (1.14E2) (x/Q)y 1[3(M) g [g (At)) (Q) y (16) During any calendar quarter, for beta radiation: n m Dp = (1.14E2) (X/Q)y i[1(N))[3(At))(Q)gjy g (17) 4 32

Survaillance Procedure .HP-1-230 Offsite Dose Calculation Manual Revision 5 8.11.2.2 During any calendar year, for gamma radiation: n m De = (1.14E2) (X/Q)y il (M i) j{t (At j) (Q)ijy i (18) During any calendar year, for beta radiation; a m D = (1.14E2) (X/Q)y ijg(N)j{1(At)(Q)ijy g j (19) , where all values are as defined previously; and D = the total gamma (y) air dose from gaseous effluents for the total time period and not to exceed 5 mrad quarterly and 10 mrad yearly. D p= the total beta (S) air dose from gaseous effluents for the total time period and not to exceed 10 mrad quarter'y-and 20 mrad yearly. Q gy = the average release rate of radionuclides (i) in gaseous effluent fram all vent releases (v) in pCi/sec during the time periol At.. J (X/Q)y = 1.1E .* sec/m 3 in the ESE sector at 0.6 mile for all vent releases (v). 8.12 DOSE CALCULATIONS DUE TO RADI0 IODINES AND RADI0 ACTIVE MATERIALS IN PARTICULATE FORM This section presents the calculational methods used for calculating doses due to Iodine-131, Iodine-133, tritium, and radionuclides in particulate form in accordance with Surveillance Requirement 4.11.2.3 of the Waterford 3 STS. 33 f

Survaillance Procedure HP-1-230 Offsite Dose Calculation Manual Revision 5 8.12.1 Real Time Meteorological Input The dose to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released to areas at and beyond the SITE BOUNDARY will be determined by the following expressions: 8.12.1.1 During any calendar quarter for age group a: n m D 0ta =(1.14E-4).g{1(R ita) jE (O'j) I( 30jv (0)ijv] l (20) 8.12,1.2 During any calendar year for age group a: n a D (21) ata = (1.14E - 4)g{l (Rita) jEl (O'j) II )0jv (9)ijv] I where all terms are as previously defined; and 0ta = the cumulative dose due to Iodine-131, Iodine-133, D tritium, and radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents, to an organ (t), of an individual (a), in sector 8, for the total time period: m I at. j=1 3 not to exceed 7.5 mrem in any' calendar quarter or 15 mrem in any calendar year. 1.14E-4 = 87 hb. 34

Surveillance Procedure HP-1-230 Offsite Dose Calculation Manual Revision 5 Rg = the dose factor from each identified radiobuclide (i), for each applicable organ (t), and age group (a), in mrem /yr per pCi/m3 for the inhalation pathway and in mrem /yr per pCi/m2 .sec for the food and ground , plane pathway from Table 10. For sectors with real pathways within 5 miles of the plant, the values of

Rg are used based on these real pathways; for sectors with no real pathways within 5 miles from the plant, Rg is used assuming that the cow-grass-milk pathway exists at the 5-mile distance. (R g's were calculated using the methodology found in Reference 2.5, pages 31-36.) W0jv = dispersion parameter for time period (j) and release pt (v) for calculation of food pathway dose W = 0jv (X/Q)0vj f r the inhalation pathway W = 0jv (D/Q)0vj f r the food and ground plane pathway where (X/Q)0vj is as defined previously; and, (D/Q)0vj = relative deposition for the time period (at j ), in sector (0), for release pt (v), in square meters. When at. is greater than one hour, relative deposi-J tion shall be based on observation of atmospheric stability taken at least every hour during at). l fd (D/Q)0vj *(0. 92 )(re) 35

Surveillance Procedure HP-1-230 Offsite Dose Calculation Manual Revision 5 where: (0.3927)r0= are length of the 22.5* sector at distance r0 I" meters. f6= wind direction factor; equals 1 if wind in hour t is into sector 0; equals zero if wind is not into sector 0. i d ev = relative deposition rate for ground-level vent release (v) at distance (re ) in sector (0) for all stability classes of interest, (meters -1) taken from Figure 7. 8.12.2 No Real Time Meteorological Input (Used in Place of Real Time) 4 The dose to an individual from Iodine-131, Iodine-133, tritium, and radionuclides in particulate form with half-lives greater

than 8 days in gaseous effluents released to areas at and beyond the SITE BOUNDARY will be determined by the following expressions

8.12.2.1 During any calendar quarter: n D.ta I = 1.14E-4 at I R.ta I WvQ iv. (22) 8.12.2.2 During any calendar year: n

D.ta I 1.14E-4 atg,3I R.ta I Wy Q. tv (23) where all terms are as previously defined; and at = the time required for the release in hours for all releases per quarter or per year 36

Survaillence Procedure HP-1-230 Offsite Dose Calculation Manual Revision 5 D ita

                 =   the cumulative dose to an organ (t), age group (a), due to radionuclides (i) in gaseous effluents; not to exceed 7.5 mrem quarterly or 15 mres yearly Wy = the dispersion parameter for estimating the dose to an indi-vidual at the controlling location for long term vent releases (v)

Wy = (X/Q)y for the inhalation pathway from vent releases (v) in sec/m3 , from Table 11 or Table 1, for the critical receptor. W,= (D/Q)y for the food and ground plane pathways from vent releases (v) in m 2, from Table 12 or Table 1, for the critical receptor. 8.13 DETERMINATION OF ALARM / TRIP SETPOINTS FOR GASEOUS MONITORS Waterford 3 STS 3.3.3.11 states that the radioactive gaseous ef-fluent monitoring instrumentation alarm / trip setpoint be set to ensure that the limits of Waterford 3 STS 3.11.2.1 are not ex-ceeded. 9 6 37

j Survaillance Proccdure HP-1-230 Offsite Dose Calculation Manual Revision 5 8.13.1 Setpoint Calculations for Gaseous Monitors ! The calculated high level alarm and flow termination trip setpoints will be regarded as the limiting conditions for the actual setpoint adjustments. The gaseous effluent radiation monitor setpoints are usually expressed in pCi/cc. For conservatism, an administrative safety factor SF (% of dose rate limit) will be introduced into setpoint calculation. To allow for multiple sources of release from different or common release points, the allowable operating setpoints will be controlled administrative 1y by allocating a percentage of the total allowable release to each release source (RF). 8.13.2 General Gaseous Setpoint Bases Gaseous setpoints will be based on noble gas dose rate (less than or equal to 500 mrem /yr total body, and less than or equal to 3000 mrem /yr skin). Specifically, gaseous setpoints will be based.on the most limiting of the following equations: 8.13.2.1 Total Body 9 tb

                                    , (500 mrem /yr.)(RF)(SF)

(X/Q),(IE6pCi/pCi) n i=1

                                                           . i Oiv n

9 iv t=1 Then, based on maximum flow rate, the monitor setpoint SN in uCi/cc can be calculated: Q

                           'D SN = F max 38

Survaillance Procedure HP-1-230 - Offsite Dose Calculation Manual Revision 5 where: F,, = maximum effluent flow rate (cc/sec). n I = summation of all nuclides considered. i=1 Qth = maximum release rate allowed to give limiting total body (tb) dose of 500 mrem /yr (pCi/sec). Kg= the total body dose factor due to gamma emissions for each { identified radionuclide (i) in units of mres/yr per pCi/m3 (Table 7). Q gy = average release rate of isotope (i) from the release point (v) in pCi/sec. RF = release fraction allotted to release point in consideration. (X/Q)y = 1.1E-5 sec/m3 (in the ESE sector at 0.6 mile). The sector with highest value of annual average atmospheric dispersion r factor at the site boundary for the release point (v) in question. i SF = administrative safety factor to account for uncontrollable variables (sampling, monitoring errors, etc.). Usually, the SF takes on a value between 0.5-0.8. 39

1 Survaillance Precedure HP-1-230 Offsite Dose Calculation Manual Revision 5 J r 8.13.2.2 For skin i

_ (3000 ares /yr.)(RF)(SF) (25) 8 I" (X/Q),(IE6pci/pci) n I (L '+ g 1.1 M g )Qgy i=1 l n O iv

, i=1 i j SN = 0 skin Faax i

{ where all terms are as defined above except: a 1 j Q skin

                            =       maximum release rate allowed to give limiting skin dose of j                                    3000 mren/yr (pCi/sec).

l Lg = skin dose factor due to beta emissions for each identified i radionuclide (i) in units of ares /yr per pCi/m3 (Table 7). 1.1 = conversion factor to convert from air to skin dose. Mg= air dose factor due to gamma emissions for identified noble gas isotope (i) in units of mead /yr per pCi/m3 from Table 7. 8.13.3 Gaseous Setpoint Calculations Based on Kr-88. Since the noble gas dose rate is more limiting than the 4 radioiodine dose rate, the initial monitor setpoints can be i based on a conservative count rate using Kr-88 until operating l experience is accumulated. Total body dose will be more J limiting than skin dose; therefore, the release limit would l be: 40

Surveillance Procadure HP-1-230 Offsite Dose Calculation Manual Revision 5 (500 mrem /yr.)(RF)(SF) (24a)

#~

(X/Q)y(le6pCi/pci)(KKR-88) Then, based on maximum flow rate, the monitor setpoint SN in pCi/cc can be calculated: i #~ ( SN = F,,, where: F,,,= maximum effluent flow rate (cc/sec) NOTE To determine whether total body or skin dose is more limiting for Kr-88, equations (24) and (25) are solved for QKr-88 ince a lower Q Kr-88 is required to reach the total body limit of 500 mrem /yr, the total body dose is more limiting. 8.14 PROJECTING DOSE FOR RADIOACTIVE GASEOUS EFFLUENTS Technical Specification 3.11.2.4 requires that appropriate subsystems of the Gaseous Radwaste Treatment System be used to reduce releases of radioactivity when the projected doses due to the gaseous effluent to areas at and beyond the SITE BOUNDARY would exceed, in a 31-day l period, either: 0.2 mrad to air from gamma radiation; or 0.4 mrad to air from beta radiation; or 1 0.3 mrem to any organ of a MEMBER OF THE PUBLIC. ; l l 1 41 l

Survmillanca Procedura HP-1-230 Offsite Dose Calculation Manual Revision 5 The following calculational method is provided for performing this dose projection. At least once every 31 days the gamma air dose, beta air dose and the maximum organ dose for the month-to-quarter will be divided by the number of days into the quarter and multiplied by 31. If these projected doses exceed any of the values listed above and the Gaseous Waste Management System has not been operating, it shall be operated to reduce radioactivity levels prior to release. (This is performed in accordance with Surveillance Requirements 4.11.2.4.1 and 4.11.2.4.2.) 8.15 40CFR190 DOSE EVALUATION This section demonstrates compliance with Surveillance Requirements 4.11.4.1 and 4.11.4.2 of the Waterford 3 STS. Specifically, the dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 mrem) over 12 consecutive months. Dose evaluations to demonstrate compliance with the above dose limits need be performed only if the quarterly doses calculated in sections 8.6, 8.10, 8.11 and 8.12 excee.d twice the dose limits of STS 3.11.1.2.a, 3.11.1.2.b, 3.11.2.2.a, 3.11.2.2.b, 3.11.2.3.a or 3.11.2.3.b, respectively; i.e., quarterly doses exceeding 3 mrem to the total body (liquid releases), 10 mrem to any organ (liquid l releases), 10 mrad gamma air dose, 20 mrad beta air dose, or 15 mrem to the thyroid or any organ from radiciodines and particulates (gaseous releases). Otherwise, no evaluations are required. 42

Surveillanca Procedure HP.1-230 Offsite Dose Calculation Manual Revision 5 For the evaluation of doses to real individuals from liquid releases, the same calculational methods as employed in section 8.6 will be used. However, more encompassing and realistic assumptions will be made concerning the dilution and ingestion of radionuclides by individuals who live and fish in the Waterford 3 area. The results of the Radiological Environmental Monitoring Program will be used in determining the realistic dose based on actual measured radio-nuclide concentrations. For the evaluation of doses to real indivi-duals from gaseous releases, the same calculational methods as employed in sections 8.10, 8.11 and 8.12 will be used. In sections 8.10 and 8.11, the total body dose factor should be substituted for the gamma air dose factor (M g

                                                    ) to determine the total body dose.

Otherwise, the same calculational sequence applies. More realistic assumptions will be made concerning the actual location of real individuals, the meteorological conditions, and the consumption of l food. Data obtained from the latest land use census should be used l to determine locations for evaluating doses. The results of the Radiological Environmental Monitoring Program will be included in determining more realistic doses based on actual measured radio-nuclide concentrations. Cumulative dose contributions from direct radiation, from the reactor unit, and from Radwaste Storage Tanks shall be determined utilizing the results of routine plant perimeter surveys, TLD data, or a combination of both when necessary. 9.0 -SETPOINTS r 1 NONE . 10.0 ATTACHMENTS 10.1 Annual Average Dispersion and Deposition Parameters For Areas At or Beyond the Unrestricted Area Boundary (Table 1) 43

Survaillsace Procedure HP-1-230 Offsite Dose Calculation Manual Revision 5 10.2 Radiological Environmental Monitoring Program (Table 2) 10.3 Sample Location Table (Table 3) 10.4 Sector and Zone Designators for Radiological Sampling and Monitoring Points (Table 4) 10.5 REMP Sample Locations Within 2 Miles of Waterford 3 (Figure 1) 10.6 REMP Sample Locations Within 10 Miles of Waterford 3 (Figure 2) 10.7 REMP Sample Locations'Within 50 Miles of Waterford 3 (Figure 3) 10.8 Liquid Waste Management System Effluent Sources and Release pathways and Points (Figure 4) 10.9 Gaseous Effluent Sources, Gaseous Waste Management Systems Effluent Sources, and Exhaust Release Points (Figure 5) 10.10 Open Terrain Correction Factor (Figure 6) 10.11 Site-Related Liquid Dose Factor (Table 5) 10.12 Bisaccumulation Factor for Freshwater Fish and Invertebrate and Ingestion Dose Factors for Adults (Table 6) i l 10.13 Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gases I (Table 7) 10.14 Inhalation Dose Factors for Child (Table 8) 10.15 Values of L-Theta-V (Table 9) j r 44

Survaillance Procedure HP-t-230 Offsite Dose Calculation Manual Revision 5 10.16 Pathway Dose Factors Due to Radionuclides Other Than Noble Gases, R (Table 10) 10.17 Relative Deposition for Ground-Level Releases (All Atmospheric , Stability Classes) (Figure 7) 10.18 Annual Average Dispersion Parameters at or Beyond the Unrestricted Area Boundary (Table 11) 10.19 Annual Average Deposition Parameters for Areas at or Beyond the Unrestricted Area Boundary (Table 12) 10.20 ODCM Technical Specifications Cross-Reference (Table 13) J 11.0 COMMITMENTS AND REFERENCES 45

1 . ! TABLE 1 ANNUAL AVERAGE DISPERSION (X/0) AND DEPOSITION (D/0) VALUES I, GROUND LEVEL RELEASEE 0N CORRECTED USING STANDARD OPEN TERRAIN FACTORS SPECIFIC POINTS OF INTEREST l

RELEASE TYPE OF DIRECTION DISTANCE X/0 X/0 . X/0 D/0 i ID LOCATION FRON SITE (MILES) (NETERS) (SEC/ CUB.NETER) (SEC/CUS.NETER) (SEC/ CUB. HETER) (PER SG.NETER) j NO DECAY !

9 2.240 DAY DECAY I 8.000 DAY DECAY I UNDEPLETED DEPLETED ! UNDEPLETED G NILK COWS NW 1.10 1770. 4.7E-06 4 6E-06 4.0E-06 1.4E-08 ! G NILK C0WS NW 4.40 7081. 3.1E-07 2.9E-07 2 3E-07 5.1E-10 i i G NILK GDAT E , 3.30 5311. 3.4E-07 3.3E-07 2.7E-07 3.9E-10 ; 4.7E-06 4.1E-06 1.1E-08 l G VEGETABLE GARDEN N 1.10 1770. 4.7E-06 G VEGETABLE GARDEN NNE 1.30 2092. 2.9E-06 2.9E-06 2.5E-06 5.8E-09 G VEGETABLE GARDEN NE 1.00 1609. 4.8E-04 4 7E-06 4 1E-06 9.2E-09

;                         ,G       VEGETABLE GARDEN           ENE           0.90                 1448.                6.5E-06                      6.4E-06         5.7E-06         1.1E-08 G      VEGETABLE GARDEN             E           3.20                5149.                 3.6E-07                      3.4E-07         2.8E-07         4.2E-10 i                            G      VEGETAkLE GAkgEN           ESE           2.30                3701.                6.2E-07                       6.0E-07         5.0E-07         9.6E-10

G IKutTABLt unR.EN SE 2.30 3701. 6.0E-07 5 9E-07 4.9E-07 1.3E-09 ,' '
G VEGETABLE GARDEN S 0.90 1448. 3.1E-06 3.1E-06 2 8E-06 1.1E-08 G VEGETABLE GARDEN SSW 0.90 1448. 3.8E-06 3.8E-06 3.4E-06 1.6E-08 G UEGETABLE GARDEN SW 0.90 1448. 5.1E-06 5.0E-06 4 5E-06 2.3E-08 ,

! G UEGETABLE GARDEN WSW 0.90 1448. 5.1E-06 5.0E-06 4 5E-04 1.8E-08 me( ! 6 VEGETABLE GARDEN U 1.10 1770. 1.8E-06 1.8E-06 1.6E-06 5.7E-09

!                           G      VEGETABLE GARDEN           WNW           0.90                 1448.                5.5E-06                      5.4E-06         4.8E-06         2.0E-08         9 b b      Yhbb A bh ARhhN            NNW           h*.hh                ke                      '.9k h                      .$h h           *hk5h
                                                                                                                                                                     . 0               2
                                                                                                                                                                                   $'.!E0h          '   hc G      RESIDENCES                   N           0.80                 1287.                1.0E                     1 0E-05         8.9E-06         2.4E-08              '

2 G RESIDENCES NNE 0.80 1287. 9.1E-06 9.0E-06 8.1E-06 2.0E-08 . G RESIDENCES NE 0.90 1448. 6.1E-06 6.0E-06 5.4E-06 1.2E-08 \ 5.7E-06 1.1E-08

G RESIDENCES ENE 0.90 1448. 6.5E-04 6.4E-06 i G RESIDENCES E 2.60 4184. 5.2E-07 5 0E-07 4.2E-07 6.8E-10 G RESIDENCES ESE 3.40 5472. 3.0E-07 2.9E-07 2.4E-07 3.9E-10

, G RESIDENCES SE 3.90 6276. 2.3E-07 2.2E-07 1.7E-07 3.8E-10 G RESIDENCES W 1.30 2092. 1.3E-06 1.2E-06 1.1E-06 3.7E-09 i G RESIDENCES WNW 0.90 1448. 5.5E-06 5 4E-06 4.8E-06 2.0E-08 ) G RESIDENCES NW 0.90 1448. 7.4E-06 7.4E-06 6.5E-06 2.3E-08 ' G RESIDENCES NNU 2.00 3219. 1.6E-06 1.5E-06 1.3E-06 3.3E-09 1 G SITE BOUNDARY N 0.80 1297. 1.0E-05 1.0E-05 8.9E-06 2.4E-08 G SITE BOUNDARY NNE 0.60 966. 1.6E-05 1 6E-05 1.4E-05 3.4E-08 l 1.4E-05 1.3E-05 2.8E-08 L G SITE BOUNDARY NE 0.60 966. 1.4E-05

G SITE FOUNDARY ENE 0.60 964 1.5E-05 1.5E-05 1.4E-05 2.5E-08

G SITE BOUNDARY E 0.80 1287._ 4.6E-04 6.6E-04 5.9E-06 1.3E-08 j G SITE BOUNDARY ESE 0.60 966. 1.1E-05 1.1E-05 9.8E-06 2.3E-08 G SITE BOUNDARY SE 0.60 946. 1.0E-05 1.0E-05 9.3E-06 3.1E-08 i

G SITE BOUNDARY SSE 0.80 1297. 6.1E-06 6.0E-06 5.4E-06 2.4E-08 4 G SITE BOUNDARY S 1.60 2575. 8.6E-07' 8.5E-07 7.3E-07 2.7E-09 G SITE BOUNDARY SSW 3.10 4989. 2.9E-07 2 8E-07 2.2E-07 7.9E-10 G SITE BOUNDARY SW 3.40 5472. 3.2E-07 3.1E-07 2.5E-07 9.1E-10 G SITE BOUNDARY WSW 1.50 2414. 1.6E-06 1.6E-06 1.4E-04 4.9E-09 2.0E-06 7.3E-09 1 G SITE B0UNDARY W 1.00 1609. 2.3E-04 2.2E-06 l G SITE BOUNDARY WNW 0.80 1287. 7.3E-06 7.2E-06 6 4E-06 2.7E-08

;                           G      SITE B0UNDARY               NW 0.80                 1287.                  9.9E-06                    9.8E-06         8.8E-06          3.2E-08 G      SITE BOUNDARY              NNW           0.90                 1448.                 9.1E-06                     9.0E-06         8.0E-06         2.4E-08

{

                          . IIP-1-2 30, REV. 5                                                                           46                                        ATTACliMENT 10.1 (1 of 1)

Tchts 2 l l RADIOLOGICAL ENVIRONMENTAL HONITORING PROGRAH Sample Type Location . Analysis Frequency . Volume TLD A-2, B-1, C-1, D-2, E-1, TLD* Quarterly N/A F-2, G-2, H-2, J-2, K-1, L-1, M-1, N-1, P-1, Q-1, R-1, A-5, B-4, D-5, E-5, F-4, G-4, X-6, P-6, Q-5, . I R-6, F-9, G-9, E-15. J-15, E-30 Rrdiciodine and APP-1 APQ-1, APG-1, Gross beta, I-131 Weekly 285m a j,g Pert.iculates APC-1, APE-30 footopic Quarterly composite 3700 m s /qtr Ground Water ' GWJ-1 y isotopic, H-3 Quarterly 4 liters Crinking Water DWG-2, DWE-5 , DWP-7 H-3 Quarterly composite Homogeneous j Gross beta, y isotopic Honthly composite 4 liters j I-131 8 Semi-monthly composite ! Surface Water SWG-2, SWE-5 , SWP-7 H-3 Quarterly composite Homogeneous y isotopic Monthly composite 4 liters t Ti Shoreline Sediment SifWE-3 y isotopic Semi-annually 2 kilograma tie l t HKE-4, HKQ-5, HKQ-50 g /fusct-1 y isotopic, I-131 Semi-monthly / monthly 4 liters b4 { ; i F a sli FH-1, FH-2 y isotopic In season or g 500 grams i semi-annually ' J 50s grams Feod P$roducts FPP-1 y isotopic . At harvest time e i BLQ-1, BLB-1, bbE-te y isotopic, I-131 Monthly 500 grama *1 Broad Leaf 6'E '3 When milk samples p i not collected , i i 8 lil*- I - 2 30, Revisiou 5 47 Attachment 10.2 (1 of 2) I l t

   - - . - - _ .          - - - - .       - - - -_-_ - -             _. .=_ - - -            - _      .  .    .     -                                              - ..

i l Table 2 (Continu:d)

a. One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously .

may be used in place of, or in addition to, integrating dosimeters. A TLD is considered one phosphor, two or more phosphors in a packet are considered two or more dosimeters. Geographical limitations affect siting of dosimeters. j b. Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours or more after j sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than ten times the yearly mean of control samples, gamma isotopes analysis shall be performed on the individual samples. Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility. j c. Drinking Water and Surface Water samples are identical samples. d ., The downstream sample is beyond the mixing zone.

e. A composite sample will contain aliquots of sample taken proportional to the quantity of flowing liquid that results in a specimen representative of the liquid flow.

, f. Ground water samples shall be taken when this source is tapped for drinking or irrigation purposes in areas j where the hydraulic gradient or recharge properties are suitable for contamination. 2 3 This analysis will be performed when the dose calculated for the consumption of water is greater than 1 arem per year as calculated for maximum organ and age group as per the ODCM (see section 8.6).

h. Milk will be collected semimonthly when animals are on pasture, monthly otherwise. If milk sampling is not performed, broad leafy vegetation will be sampled.

i. Striped mullet, gizzard shad, freshwater drum, and catfish will be collected. If they are not available, substitute species will be collected and identified in reporting.

i , j. One sample of each principal class of food products will be sampled in an area irrigated by water in which plant wastes have been inadvertently discharged (see section 8.5 of this procedure). If harvest occurs more than once a year, sampling shall be performed during each discrete harvest. If harvesting occurs continuous-l ly, sampling shall be monthly. Tuberous and root products will be sampled when available. i 3 l 48 j HP-1-230, Revision 5 Attachment 10.2 (2 of 2) 4 I

TABLE 3 SAMPLE LOCATION TABLE LOCATION LGCATION MILES FROM SECTOR HUMBER DESCRIPTION PLHHT DIRECTION DIRECT RADIATION (TLD) 4-2' ( Eastbank ) On fence enclosure 1.1 H surrounding water teuer west of Little Gypsy opposite Etienne St. Access from River Road (LA 628). The TLD's are located on the (S) fence opposite the entrance gate to the water teuer. l B-1 ( East bank ) On fence enclosing the 0.8 HHE transmission tower 0.3 miles west (up-river) from Little Gypsy. Access from River Road (LA 628). TLD's are located at SW corner of fence enclosure. f C-1 (Eastbank) On fence enclosing the 0.8 NE , Little Gypsy Cooling Water Intake. Access is from River Road (LA 628) across f rom Lit tle Gypsy Power Station entrance. TLD's are on the . south side ' .nside) of the Coolang 4 Water Intake fence enclosure, directly opposite the entrance gate. 4 , D-2 ( Eartbank ) Located at USGS Uitness 1.1 Eh5 l Port Survey Marker approxinately , 0.3 miles east of Little Gypsy Power ; Station. Access from River Road (LA 628) near the west end of the Bonne Carre Spallway. TLD's are on the back of the Survey Marker Sign (lecated on levee), e I E-1 (Westbank) Located on utility pole 0.2 E , along River Road (LA 18) approxi- , mately 0.3 miles east of Waterford 3 plant entrance. Access from LA t

18. TLD*s are on the third utility pole east of the construction ,

entrance road. HP-1-230, Revision 5 49 Attachment 10.3 (I of 9)

Table 3 (continued) LOCATION LOCATION MILES FROM SECTOR HUMBER DESCRIPTION PLANT DIRECTION F-2 ( Westbank ) Located on fence 1.1 ESE enclosure surrounding the LP&L Jubstation on LA 3142. Accass from LA 3142 approximately 0.2 miles south of LA 18. TLD's are on the southeast corner of the fence enclosure. - G-2 ( Westbank ) Located on utility pole 1.2 SE on East side of LA 3142 near Witco entrance gate (Hext to Union Carbide ' Star Plant Gate 3). Access from LA 3142 approximately 0.2 miles north of railroad overpass. ' H-2 (Westbank) Located on fence enclosure 1.2 SSE to shell road off of LA 3142. Access from LA 3142 south of railroad overpass on east side of LA 3142. TLD's are on the south side of the gate for shell road. (Just south of Texaco pipeline i station) 1 i J-2 <Wastbank) Located on northeast 1.3 3 corner of fence enclosing Texaco valve station south of LA 3127. Access from LA 3127, approximately 0.6 miles west of LA 3127/3142 intersection, i K-1 < Westbank ) Located behind " Private 1.0 35W Road" sign at Gate 8 entrance off of LA 3127. Access from LA 3127, approximately 1.3 miles west of LA 3127/3142 intersection. (Gate G is the access to the Waterford 3 switchyard station) L-1 (Westbank) located behind " Private 1.0 SW Road" sign at LP&L Gate 9 entrance off of LA 3127, approximately 1.6 miles west of LA 3127/3142 inter-section. (Gate 9 is an access road for Waterford 3) , HP - t -23 0, Revision 5 50 Attachment 10.3 (2 of 9)

Table 3 (continued)

LOCATION LOCATION MILES FROM SECTOR HUMBER DESCRIPTION PLANT DIRECTION M-1 ( Westbank ) Located on south gate 0.7 WSW into the Waterford 1 and 2 fuel oil storage tank enclosure.

4 Access is either thru LP&L Gate 8, Gate 9 off of LA 3127, the shall access road from LA 19 between Waterford 3, or thru the Waterford I and 2 access road. H-1 ( Westbank ) Located Dehind the "No 0.9 W 4 Trespassing" sign off on Short i Street, in K111ona, just south of I the entrance to K111ona Elementary 1 School. P-t (Westbank) Located behind "No 0.8 WHW t Trespassing" sign on Short Street, l in Killona, approximately 0.1 4 miles south of air sample station, i Q-1 < Westbank ) Located on fence 0.8 ,HW enclosing air sample station approximately 0.5 milsts nest of Waterford 1 and 2 on Piver Road

,                         (LA 18 ) .

R-1 <Westbank) Located on fence 0.5 NHW enclosure for Waterford 1 and 2 Coeling Water Intake Structure, 1 Access is from River Road (LA 19) oppesite Waterford i and 2. TLD's are on the southwest corner of fence, i A-5 (Eastbank) Located on utility 4.5 H pole just east of the Shady Hook j Trailer Park on Hwy 61 in La Place. TLD's are on second utility pole east of trailer park on north side of Hwy 61 < eastern and of La Place). i i 4 l l 1 l HP-l-230, Revision 5 51 Attachment 10.3 < 3 of 9) l

Table 3 (continued) LOCATION LOCATION MILES FROM SECTOR HUMBER DESCRIPTION PLHHT DIRECTION B-4 ( Eastbank ) Located on utility pole 3.8 NHE just east of shell access road to South Central Bell transmission tower on south side of Hwy 61. Transmission tover is just east of Weigh Station at St. John /St. Charles Parish line. TLD's are on first utility pole east of access road. D-5 ( Eastbank ) Located on fence gate 4.2 EHE on shell access road to Big 3 Chemical Plant. Shell access road is approximately 0.1 miles west of Hwy 61/48 intersection (at black and yellow gate). TLD's are on fence gate 0.1 miles north on shall access road from Hwy 61. l 1 i E-5 (Eastbank) Located on the Horco 4.2 E Substation fence enclosure. Access from River Road (LA 48) onto Wesco St. (adjacent to Horce Shell Chemical Plant), take Wesco St. to the dead end. TLD's are located on sixth fence post south of the north substation gate. F-4 (Westbank) Located on utility pole 3.5 ESE I behind blonde brick house on Aquarius St. in Hahnv111e. Access from River Road (LA 18) and turn onto Oak St. Follow Oak St. to Hickory St., turn right on Hickory St. and follow to Aquarius St. and turn left. Blonde brick house is second house on right (west) side of Aquarius St. heading south. . G-4 <Westbank) Located on railroad sign 3.2 SE northwest side of LA 3160/ railroad track intersection. Access from either LA 3127 or River Road (LA 18) onto LA 3160. HP-t-230, Revision 5- *" **" ' ' 52

Table 3 (continued ) LOCATION LOCATION MILES FROM SECTOR HUMBER DESCRIPTION PlaHT DIRECTICH H-6 (Westbank ) Located on a construction 5,7 SSE sign on the southuest side of the second canal bridge east of LA 3160 along LA 3127. P < Westbank ) Located on utility pole 5.5 WHW at southwest corner of LA 640/ railroad track intersection. Utility pole is just utst of LA 640 nnd east of radio transmission touer. Q-5 < Westbank ) Located on fence post 5.0 HW surrounding (green) river marker on levee just east of Edgard. Fence post is located along River Road (LA 18) across from the Webre's house. R-6 (Eastbank) Located on fence 5.3 HHW enclosing LP&L Laydown Yard on LA 3223 in La Place. Access from Hwy 61 onto Elm St. (LA 3223), take Elm St. to the northeast corner of LA 3223/ railroad inter-section. TLD's are located on the southeast corner of fence enclosure. F-9 (Eastbank) Located on entrance 8.2 ESE gate to Destrehan Substation. Access from River Road (LA 48), approximate 0.3 miles east of Luling-Destrehan Ferry, onto ., Destrehan Road (west of Bunge - Corp. Grain Elevator), and

                  . proceed to substation gate.

G-9 (Westbank) Located on back fence 8.1 SE l of LP&L District Office in Luling. Access via Ellington St. from either River Road (LA 18); or Second or Third St. from Paul Mallard Rd. (LA 52) to Ellington St. , l HP-1-230, Revision 5 53 Attachment 10.3 (5 of 9)

Table 3 (continued) LOCATION LOCATION MILES FROM SECTOP HUMBER DESCRIPTION PLANT DIRECTION E-15 (Eastbank) Located on Kenner 11.8 E substation fence enclosure. Access from either River Road

                       < LA 48) or Hwy 61, turn onto Alliance Ave.        TLD's are located on the north side of the fence enclosure, near a light pole.               ,

J-15 < Westbank ) Located on fence 12.0 $ enclosure surrounding LP&L switchyard at LA 631/ Hwy 90 intersection in Das Allemands. TLD's are on the. northwest corner of fence. Access from LA 631 via shell road. E-30* ( Westbank ) Located on fence at 27.0 E LP&L General Off2ce on Delaronde St. in Algiers. TLD's are on the fence, facing the Mississippi River, in the passageway to the transformer shop. Airborne APP-1 <Westbank) Located in soybean 0.8 WHW field at northwest corner of Short St. in Ks11ona. APQ-1 (Nestbank) Located at northwest , 0.8 HW corner of soybean field on east side of Killona. Access from River Road (LA 18) approximately 0.6 miles east of LA 18/3141 intersection. APG-1 <Westbank) Located at the north 0.5 SE side of the Secondary Metrology Tower. 1 I l

                                       .                                                           l 1
                                                                                                   )

HP-1-230, Revision.5 Attachment 10.3 (6 of 9) 54

1 1 I Tcble 3 (continuad) ! LOCATION LOCATION MILES FROM SECTOR HUMBER DESCRIPTION PLANT DIRECTION APC-1 ( Eastbank ) Located inside the 0.8 HE Little Gypsy Cooling Water Intake Structure fence enclosure. APE-30* ( Westbank ) Located on the roof of 27.0 E the LP&L General Office building on Delaronde St. in Algiers. Food Products FPP-1 ( Westbank ) Located in soybean 0.8 WHW field on eastern edge of Killona, between air sample stations APP-1 and APQ-1. Broad Leaf BLQ-1 ( Westbank ) Located between LA 18 0.8 HW and soybean field on eastern edge Killona, near air sample station APQ-1. BLB-1 ( Eastbank ) Located at wooded area 0.8 HHE at the southwestern corner of the LP&L Little Gypsy plant along River Road. ; r3

5 BLK 15 (Westbank) Located 3.5 miles SSW 15.0 SSW 's of Das Allemands on Hwy. 90. 1 2 h HP-1-230, Revision 5 55 Attachment 10.3 (7 of 9)

Tcble 3 (continuad) LOCATION LOCATION NILES FROM SECTOR HUMBER DESCRIPTION PLANT DIRECTION Ingestion Milk MKE-4 ( Westbank ) located .8 miles west 4.0 E of the Time Saver in Hahnville off of River Road. NKQ-5 ( Westbank ) Located at the Webre's 5.0 HW house, just across LA 18 from river marker, at the eastern end of Edgard. MKQ-50* ( Eastbank ) Located at the LSU 52 HW Dairy in Baton Rouge.

                                                                                                       &  R MKQ-1             ( Westbank ) 1.0 miles west of                         1.0          NW    3  P Waterford 3 at the corner of                                              "={

River Road and Post Street in 3 Killona. $ h Fich FH-t* Upstream of the plant intake structure. FH-2 Downstream of the plant intake structure. Waterborne GWJ-l ( Westbank ) Located at 40 Arpent 0.3 S Canal south of the plant. Access from LA 3127 through LP&L Gate 8. The canal is northwest of the shell access road / railroad track inter-section. HP-t-230, Revision 5 56 Attachment 10.3 (8 of 9)

Table 3 (continued) 1 LOCATION LOCATION MILES FROM SECTOR HUMBER DESCRIPTION PLHHT DIRECTIGH DWC-2 < Westbank ) Located at the Urion 2.0 ESE SWG-2 Carbide drinking water canal. Access fr om LA 3142 through Gate 23. SHWE-3 < Westbank ) Located at the Foot 3.0 E Ferry Landing off of LA 18 in Taft. DWE-5 ( Eastbank ) Located at the 4.5 E SWE-5 St. Charles Parish Waterworks off of River Road < LA 48 ) near New Sarpy. DWP-?* < Westbank ) Located at the St. 6.5 HW SWP-7 John Parish Waterworks off of LA 18 in Edgard.

DEHOTES CONTROL LOCATIONS l

I i 1 1 l , HP-1-230, Revision .5 Attachment 10.3 (9 of 9)

57 l

Table 4 "ECTOR AND ZONE DESIGNATORS FOR RADIOLOGICAL SAMPLING AND MONITORING POINTS SECTOR NOMENCLATURE ZONE NOMENCLATURE CENTERLINE OF SECTOR IN DEGREES TRUE NORTH 22 \* HILES FROM FROM FACILITY SECTOR FACILITY ZONE , 0 & 360 . *A N 0-1 1 22 B NNE 1-2 2

,          45                              C         NE                             2-3                            3 67                              D         ENE                            3-4                            4 90                              E         E                              4-5                            5 112k                             F         ESE                            5-6                            6 135                              G         SE                             6-7                            7
     ,    157\                             H or SSE                                 7-8                            8 180                              J         S                              8-9                            9 202\                             K         SSW                            9-10                          10 225                              L         SW                            10-15                          15 2475                             M         WSW                           15-20                          20 270                              N         W                            20-25                           25 292\                             P         WNW                          25-30                           30 i

315 Q NW 35-40 40 337\ R NNW 40-45 45 45-50 50 AREA SEGMENT - An area is identified by a Sector and Zone designator. Thus, area N-1 is that area which lies between 348 3/4 and lik degrees true north from the facility out to a radius of 1 mile. Area G-4 would be that area between 123 3/4 to 146 \ degrees and the 3- and 4-mile arcs from the I facility. For Airborne, Ingestion (milk), and Food Products pathways, the sector designator will be preceded by acronyms AP, MK, and FP, respectively. .

The letters I and 0 have been omitted from these sector designators so as to eliminate possible confusion

between letters and numbers.

I HP-1-230, Revision 5 . 58 Attachment 10.4 (1 of 1)

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l 63 HP-I-230, Rev. 5 Attachment 10.8 (2 of 2)

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                                                        'd O 1 0 V 4 N ol1 0 3 H M O D HP-1-230, Revision 5                                                                                   65                                                     Attachment 10.10 (1 of 1)
                                                 -_. _ _.~.,. _ . .-.__. _ _.._..___.                                                                             _ . _ . . _ . _ _ . , _ .   .u. _ _ _ _--

TABLE 5 SITE RELATED LIOUD DOSE FACTORS A;, = (3.78E+05 + 2.39E+068Ff )DCF/ r (mres/hr per uCi/ml) UJ DCF(arem/pCif2.1 f At ELEMENT BF 7 GI LLI LIVER GI LLI LIVER Cr-51 2.0E+02 6.69E-07 -- 3.20E+02 -- Mn-54 4.0E+02 1.40E_05 4.57E-06 1.34E+04 4.37E+03 Mn-56 4.0E+02 3.67E_06 f.15E-07 3.51E+03 1.20E+02 Fe-55 1.0E+02 1.09E-06 1.90E-06 2.61E+02 4.55E+02 Fe-59 1.0E+02 3.40E-05 1.02E-05 8.14E+03 2.44E+03 Co-58 5.0E+01 1.5tE-05 7.45E-07 1.81E+03 8.93E+01 Co-60 5.0E+01 4.02E-05 2.14E-06 4.82E+03 2.57E+02 Hi-63 1.0E+02 1.88E-06 9.01E-06 4.50E+02 2.16E+03 Hi-65 1.0E+02 1.74E-06 6.86E-08 4.17E+02 f.64E+0! Cu-64 5.0E+01 7.10E-06 8.33E-08 8.5tE+02 9.99E 00 Zn-65 2.0E+03 9.70E-06 1.54E-05 4.64E+04 7.36E+04 Sr-89 3.0E+01 4.94E-05 -- 3.56E+03 -- Sr-90 3.0E+0! 2.19E-04 -- 1.58E+04 -- Y-90 2.5E+01 1.02E-04 -- 6.13E+03 -- 2r-95 3.3E 00 3.09E-05 9.75E-09 2.55E+02 8.06E-02 2r-97 3.3E 00 1.05E-04 3.39E-10 0.32E+03 2.80E-03 Hb-95 3.0E+04 2.10E-05 3.46E-09 1.51E+06 2.48E+03 1-131 1.5E+01 1.57E-06 5.95E-06 5.69E+01 2.16E+02 Cs-134 2.0E+03 2.59E-06 1.48E-04 1.24E+04 7.07E+05 Cs-137 2.0E+03 2.1tE-06 1.09E-04 1.01E+04 5.21E+05

1. Extracted from Table 4-1 of Regulatory Guide 1.109, Revision 1,1977.

2. Extracted from Table E-lI of Regulatory Guide t.109, Revision 1,1977.

i HP-t-230, Revision 5 attachment 10.11 (1 of 1) i 66 I

l TABLE 6 BIOACC N TION FACTOR FOR FRESHWATER ! FISH AND INVERTEBRATEL (pC1/Kg per pCi/ liter) FRESHWATER ELEMENT FISH INVERTEBRATE I H 9.0E-01 9.0E-01 C 4.6E 03 9.1E 03 Na 1.0E 02 2.0E 02 , P 1.0E 05 2.0E 04 Cr 2.0E 02 2.0E 03 i Mn 4.0E 02 9.0E 04 Fe 1.0E 02 3.2E 03 j Co 5.0E 01 2.02 02 Ni 1.0E 02 f. 0E 02 l Cu 5.0E 01 4.0E 02 i

 !                          Zn              2.0E 03              1.0E 04 Br             4.2E 02              3.3E 02 Rb             2.0E 03              1.0E 03 i

Sr 3.0E 01 1.0E 02 1 Y 2.5E 01 1.0E 03 Zr 3.3E 00 6.7E 00 i i

1. Extracted from Table A-1 of Regulatory Guide 1.109, Revision 1, 1977.

HP-1-230, Revision 5 Attachment 10.12 (1 of 5) 67

TABLE 6 BI0 ACCUMULATION FACTOR FOR FRESHWATER FISH AND INVERTEBRATEI (pCi/Kg per pCi/ liter) FRESHWATER ELEMENT FISH INVERTEBRATE Nb 3.0E-04 1.0E-02 Mo 1.0E 01 1.0E 01 Tc 1.5E 01 5.0E 00 Ru 1.0E 01 3.0E 02 Rh 1.0E 01 3.0E 02 Te 4.0E 02 6.1E 03 I 1.5E 01 5.0E 00 Cs 2.0E 03 1.0E 03 Ba 4.0E 00 2.0E 02 La 2.5E 01 1.0E 03 Ce 1.0E 00 1.0E 03 Pr 2.5E 01 1.0E 03 Nd 2.5E 01 1.0E 03 W 1.2E 03 1.0E 01 Np 1.0E 01 4.0E 02

1. Extracted from Table A-1 of Regulatory Guide 1.109, Revision 1, 1977.

HP-1-230 Revision Ys 68 Attachment 10.12 (2 of 5 )

TABLE 6 INCtlflT4 Oult FACTORS F0m 40utf5 t**Em PE4 *Cl INGE$fEDI teuCLILE SONE Llvte f.actv TMya010 al0NEY LUNG Gl.LLI ' d NO DATA 1.3SE.01 l .CS E.0 7 1.05E.07 i 1.0St.07 1.054 07 1.051 07 C 14 2.84E.06 S.68E.07 1.4 4 E.0 7 S.68E.07 S.68E.07 S.687 07 S.68E.07 Na 24 1.70E.06 1.70f.06 1. 70 E .0 6 1.70t.04 1.701 06 1.70E.04 1.70E.06 A P 32 1.938 04 1.20f.01 7. 4 et .0 e 40 UAfa NC CATA NO CATA 2.17E.05 CR St 40 Daf4 NO Cafa 2.668 09 1.$1E.09 S.86t*10 3. Sit.09 6.69E.07 i am S4 NO uata 4.578 06 0. 72 E .0 7 NG 04f4 1.36E.06 NO DATA 1.40E.05 mm 56 40 DafA l.llt.07 2.04!.04 40 Data 1.46E.07 N0 04f4 Ft SS 3.67f.06 2.79E.06 1.90F.06 4. 4 JC.0 7 NO 04f4 NO 04f4 1.06E.06 1.09E.06 i Ft 59 4.34E.06 1.02t.0$ 3. 9 t t .0 6 NO 04fA 40 04fA 2.8SE.06

                            . ..... ... .................. .............. ... ......... .3.40t-01                                                 .......

CO S8 NO OATA 7.45t.07 1. 6 7 E .0 6 90 04f4 40 04T4 NO 04f4 t CO 60 NO DATA 1.StE 0% 2.14f.06 4.72C.06 NO Defa NO 04f4 NO DAT4 4.028 09 } NI 63 1.308.C4 9.01E.06 4.J68 06 NO 04f4 NO DATA NO 04f4 1.888 06 l N1 65 $.20E.07 4.84E.08 1.11E .0 0 NO 04f4 NO Defa 40 04f4 t.74t.06 CU 64 No 04f4 8.33E.04 3. 9 t E .0 8 NO Oafa 2N el 4 845 04 2.10t.07 40 04f4 7.80E.06 l 1.24E.0% e . 9et .0 6 NO Defa 1.03E.0% 40 CATA 9. 7 0 f - 04 i i 24 69 1 014 08 1.17E.00 1. 3 7 f.0 9 NO 04f4 1.28E.00 NO Cara 2.968 09 1 84 83 to 04fA NO 04f4 4.02E.00 NO Da*A NO Cafe NO Data S.798 08 84 84 N0 Defa NO 0&f 4 , S.255 00 40 DATA s Ga SS 40 CAf4 NO DATA

                                                                                           ...................... . 04fA 2.14 E .0 9 NO oaf 4 N0 04fA         No 4.09E.13 i                                                                                                                  40 Defa         NO DATA       LT t.24 R8 86      40 Cafa                    2. Alt.0$          9. 4 3 E .0 6 40 DATA         NO 04f4         NO Defa NO 04f4                                                                                                   4.16E-06 48 88                                 6.0$E.08 1. 21 E .0 8 40 oaf 4 40 04fA Data t                           .                                                                                                      NO            8.36E.19 j                           at 89      40 DafA                    4.0tt.00 2. 82 C.0 8 NO O&fA                     NO 04f4         NO Defa       2.33E.21 l                           54 89      3.088 04 N0 04f4                              8. 84 E.06    40 04f4        NC cafa          No Daft 14 90                                                                                                                4.94E.01 4

7.$8E.03 NO Cara 1. 44E.0 3 NO DATA NO 0474 NO DATA 2.19E-04 SR 98 S.4ff.06 NO Defa 2.29E-1F 90 DATA NO 04f4 N0 04f4 2.70E.09

                           $4 92      2 1$E.06 NO DATA                              9. 30E .0 8 40 04f4          NC 04f4          NO Data       4.26t.0%                              '

j Y 90

                           ....... ~ .

9.62E.09 90 Defa 2.548 10 NO 04f4 NO DATA N 1.028 04

                                                         ..... .. .... . ..................                                    .   .O  04f4.

Y 9tm 9.09E.Il NO 04f4 3. 52 E.12 NO 04f4 NO DATA No 04f4 2.67E.10

                           ? 91       1.4tE.07 NO DAf4                              3. 7 7 E.0 9 NO 04f4         90 Data          40 04f4       7.76E.0%

l ? 92 8.*SE.10 40 cafa 2.4 7E.i t NO Data NO Dare 40 1.48E.09

. ~. - ~. .. -.-....... ...... .. ...............Cafa ....... .. -

i l ! l 1 1 1 l 1 4 1 1 4 l 1 - 1 1 r 4 HP.1-230, Rev. 5 Attachment 10.12 (3 of 5) 69

TABLE 6 (continued) l l INCt5flCN 00$E F4CT0*S FC# 40utf5 t=4EM Ph4 PCI INGESTE05 N'uCL ICE SONE LivEt f.Accv THv90lc EIONEY LumG GI.tLi Y 93 2.68E-C1 40 04f4 7.40E-t1 NO DATA NO 04f4 NO DATA 8.10E-05 24 95 3.04E-08 1.75E-09 6. 60 E-0 9 NO DATA 1.S3E-08 NO DATA 3.09E-45 2A 97 1.64E-09 1.392-10 1. S S t-10 NO DATA S.12E-10 NO DATA 1.09E-04

                                                                                                                                  .. . - . ~ .

N9 95 6 22E-09 3.44E-09 1. 86E -0 9 NO DATA 3.42E-09 NO DATA 2.10E=0S mn 99 NO DATA 4.3tE-06 8.2 0E-0 7 No DATA 9.76E-04 NO DATA 9.99E=06 TC 99a 2.478-10 6.98E-10 8. 8 9 E-0 9 NO DATA 1.06E-04 3.42E-te 4.135-07 FC101 2.S45-10 3.66E-10 3. 5 9 E -0 9 10 OATA 4.394-09 1.87t-10 1.10E-21 aut03 1.8SE-07 NO 04f4 7. 9 f E -0 8 40 OATA 7.06E-07 NO DATA 2.16E-01 tut 03 1 54E-08 Nu CAf4 6. 00 E-0 9 10 04f4 1.99E-07 NO DATA 9.428 06 1U106 2.FSE-06 10 04f4 3.40E-07 NO DATA S.1tE-06 NO DATA 1 78E-06 AC1 tom 1.60E-07 1.48E=0F 8. 79 E -0 8 10 O&fA 2.9tt=07 MO DATA 4.04E-OS TE12Sm 2.6SE-06 ,9.71E-07 3.51C-07 0 068-37 1.09E-05 NO 047A 1.07E-OS TE127= 4.77E-06 2.42C-06 8.2 9 t-0 7 1.73E-06 2.75E-OS NO 04f 4 ' 2.27E-OS TE127 1.10t-0F 3.95E-08 2. 3 8 E -0 8 8.LSE-04 4.484-07 NO 04f4 8.68E-06 TE1298 1.tSE-05 4.298-06 1.82E-04 3 95t-04 4.80E-05 NO DATA S.79E-OS fE129 3.14E-08 1.18E-08 7. 6 3 E -0 9 2.4tE-08 t.32E-07 NO DATA 2.37E-04 T[13tm 1.73t-04 8.44C-07 7.0SE-0 7 1.34E-04 8.57E-06 NO DATA 8.408-09 i ftt31 1.978-08. 4.2 3C-09 4.22E-09 1 62E-04 8.631-04 NO DATA 2.79E-09 f8132 2.52E-06 1.631-04 1. S J E -0 6 1.00E-06 1.57E-05 NO 04f4 7.7tE-05 1 130 7.548-07 2.21E-06 8.408-07 1.89E-04 3.44E-06 NO 04fA 1.928-06 1 111 4.86E-06 S.95t=04 3. 4 t E -0 6 1.91E-03 1.021-09 NO DATA 1.575-06 I 112 2.011-07 S.43F-07 L .90E-0 7 1.90E-05 8. 6 S k -07 NO DATA 1.02E-07 . I 133 1 42E-06 2.4fE-06 7.13E-0 7 3 63E-04 4.311-06 NO DATA 2.22E-06 1 134 1.068-07 2.48t-07 1.03E-0F 4.99E-04 4.184-07 NO OATA t.SLE+t0 ? I 135 4.43E-07 1.16l 06 4. 2 8E -0 7 7.6SE-0$ t . 448 -06 NO 047A 1 11E.04 CS134 6.22E-0$ t.48E-04 1. 2 t E *0 4 NO DafA 4.79t=0S 1.19E-OS 2.S 94 -04 i C1116 6.SLE-06 2.$7t-0S 1. 8 S E -0 5 NO O&fA 1 43E-09 1.96E-06 2.'4 2 E .04 CS137 7.97t=0S 1 09t-04 7 14 E-O S NO DATA ).701-05 1.23E-OS 2.11t-04 l cst 38 S.128-04 1.C9E-07 S . 40 E -0 8 NO 04f4 8.0tt-QA 7.9tE-09 4.495-13 sat 39 9.70E-08 4.91E-11 2. 84 E-0 9 NO DATA 6.468-tt 1.92E-st t.72E.07 I 1 i , , l I

i HP-1-230, Rev. 5 70 Attachment 10.12 (4 of 5 )

TABLE 6 (continued) INGE5ff04 00$E F ACToms Fca 40ults t=eEM PL4 PCI INCESTEDI MuCLICE 804E LIvfR f.AOCY THYt010 (10%EY LUNC Cl-LLI oat 40 2.0JC-05 2.SSE-08 1.33E-06 40 NATA R.6ft-09 1.46E-08 4.18E-OS A4141 4.itt-08 1.S6C-11 1 59f-0 9 40 0474 3.3tE-It 2.02E-It 2.22E-17 94142 2.13E-08 2.19E-11 1. 3 4 t -0 9 10 DATA 1.3SE-tt 1.24E-11 1.00E-26 Lal40 2.50L-09 1.262-09 J.3JC-10 90 DATA NO O&ra 40 nafA 9.2SE-OS L4142 1.28E-10 S.82E-It 1.4SE-11 NO DATA NC CATA 40 DATA 4.2SE-07 E141 9.36E-09 6.lsE-09 F.19C-10 NO DAT4 2.94E-09 h0 QAf4 2.42E-CS CE143 1.6SE-09 1.22F-04 1. 3 S E -10 40 CATA S.17E-10 NO Data 4.56E-OS l CE144 4.ASE-07 2.C4E-07 2.62E-04 NO DATA 1.21E-07 40 OATA 1. 41E-04 i 74t43 9.20E-09 3 49C-09 4.S4E-10 40 DATA 2.13E-09 90 O&fa 4.03E-OS pel44 3.018-11 1.2SE-11 t.SIE-12 90 Daf4 f.05E-12 40 04f4 4.33E-18 90147 6.29E-09 f.Jff-09 4.1S E -10 90 CAfa 4.2SE-09 90 04f4 3.49E-OS w tif 1.03E-Of 0.61E-08 3. 01 E-18 90 04f4 40 DATA Nn 04f4 2.82E-OS f4P2 39 1 19E-01 1.tfC-10 4.4SE-11 40 DATA 3.6SE-10 40 04fA '2.40E-01 l i 1 1 HP-1-230, Rev. 5 71 Attachment 10.12 (5 of 5)

TABLE 7 00$t F4C70t$ Foe Exp05URE TO A SEMI-tMFf4tTE CLOUD OF NOELE Catt5 Nuclide s.afr*( Nt ) s.$tta *

f _L,t ) -Air *( Mi) v ledy r Ky l tr683e 2.88t.04 -..

1.93C 0$ 1.56t-04 tr 85e 1.97C-03 1.46E-03 1.23C-03 1.17t-03 tr 85 . 95t-03 1.34t-03 1.72E-0$ 1.611-05 Er 87 1.03E 02 9.73t 03 6.17E-03 5.92C 03 tr 88 2.93t-03 2.37t 03 1.52E-02 1.47E 02 Er 89 1. 04t - 02 1.01t-02 1.73E-02 1.66t-02 tr-93 7.83t-03 7.29t 03 1.63t-02 1.56E-02 to-131e 1.11t 03 4.76t-04 1.54C-04 9.1$t-0$ te 133e 1.48t-03 9.94t 04 3.27t-04 2.51C-04 te 133 1.0$[ 03 3.06t 04 3.53E 04 2.94t-04 te 135e 7.39t-04 7.11t-04 3.34E-03 3.12 C -0 3 Ie-135 2.46t 03 1.86C 03 1.92C 03 1.81E-03 Ie-137 1.27t 02 1.22t 02 1.51t 03 1.42E 03 I e - 1,38 4.75E.03 4.13t-03 9.21t-03 8.83t-03 Ar 41 3.28t.03 2.49C-03 9.30E-03 8.84t-03 f

           'ere8. 3 pGI-pr eree-e 3 pGl-pr
      ***2.88t-04 = 2.48 a 10*4 l

HP-1-230, Rev.5 Attac ment 0.13 (tofO 72

TABLE 8 INMalafl0N I"4Em PE4 PCI IgnaLE03 005E 84Cf 0m1 FC4 CHILD (DFA1 ) NuCLICE 809E LtvEs T.morf thrunID stomtv LumG + cl.LLI

               ................................. .........................................                                                                          . ,p H     3   NO DefA         3.c4C-07 3. 04 E -31 1.04i-07 1.04C-07 3.04E-07 1.0 4 E -0 7 C- 14     9.70E-04 t.82E-06 1.92E-06                                             t.E2E-06 1.42t-06 1.87E-06 1.82E-04
               %4 24     4.35E-04 4.JS -06 4. 3 s t -0 6 4.3SE-ne 4.3SE-e6 4.3SE-04 4 3SE-04 P 32      7.04E.04        1.09E-03                      2. 6 f C -O S NO OATA             NC 04fA            Mn Data        1.14E.05 CR St     NO DATA       NO DAra                        4.17 E -0 8 2.Atr.oA               4.576-09           4.S9E-06       2.93E-07
               *M S4     40 04fA         1.165-05                      2. S 7 f-0 6 NU D&fA              2.7tE.06           4.26E=04       6.197-06 84 16     NU 04fA       4.48E-lo                        8.4 5 E-! ! NO DATO               4.52E-10           3.SSE-04        1.33E-05 FE SS     1.28t=0S       6 80E-06                       2. t G E-0 6 40 04f4              40 DATA            3.00E-05        f.7SE-07 PE 59     S.39C-06      9.L4E-06                       4.StC-06 90 04f4                   NO DafA            3.43C-04       1.9tE-09 CO $4     90 Data       4.19E-07                        0.SSE-07 40 04T%                  NC OATA            2.99E-04       9.29E-04 CO 60     NO DATA         3.SSE-04                     6 12 E -0 6 90 Defa                NO Caf4            1.9tE-03 2.60E-OS 48 6A     2.22E-04        1.2SF-05                      7.564-06                 40 DATA  NO 04f4            7.43E=0S 1 71E-04 i               :41 6S    8.08E-10       7.99E-Il                      4.44E-I t 40 DATA                  NU CATA            2.2tt=04 2.2 7E-OS Cu 64     40 04f4       S.J9E-10 2.90C-LO                                        NO 04f4  1.63E-09 2.59E-04 9.92E-04 2.4 6b    I.tSE-OS 3.04E-05                             1.90E-OS 40 DAT4                  t.91E-OS 2.49E-04 4.4tE-06 2 N 61    1.8tE-11 2.htt-11 2.4 t C-12 NO O&fA                                            1.58E-t!           3.84E-07 2.FSE-06 M9 83     40 04f4      40 04T4                          1. 2 8 E -0 7 40 Data             No caf4            ho DATA        LT E-24 on A4     NO DATA      Mu 04fA                          t . 4 n t-0 7 40 04f4             NO Data            NC 04fA        L7 E-24 E9 SS     NO DATA      N0 04fa                         4. 84E-09 NO DATA                  40 04f4            NO Cara        LT E-24 48 46     40 04f4       S.36C-OS                        1. 09E-0 3 90 CATA                NO DATA            k0 04f4        2.16E-06 EP 88     NO DATA        1.52E-Of 9.90C-04 40 04fA                                        NO Daft            NO CATA        4 64E-09 48 89     NO DATA      9.33C-08                        7. 8 4 E .0 4 40 04fA              9C 04fA            40 04f4        $.itt-te 59 89     1.62E-04     90 04f4                         4. 66 E -0 4 NO DATA               N0 04f4            S.81C-04 4 52E-99 SR 90     2.73{-02 40 DATA                             1. 74 E -0 3 NO 04f4               NC 04f4            1.99C-01 9 24E-05 Sa 91     3.28E-34 NO Caf4                             1. 2 4 E -0 9 40 DATA              MO 04fa            1.44E-05 4.70'-05 SR 92     3 34E-01 NO Daft                              1.42E=10 NO DAT4                  40 Defa            6.49C-06 6.SSE-05 Y 90      1.1tE                                        2. 9 4F -0 8 90 0474
               .. .... - .._-06.. NO             DATA NC catA            7.07E-05 7 244-01 Y-9t*     1.17E-10 40 DATA                             4.98E-12 NO 04f4                   40 04f4            7.60F-07 4.64E-07 Y 91      2.47E-04 90 DATA                             6.19 E -0 6 %0 DATA                90 04f4            7.10E-04       4.97E-05 Y 92      S.$0E-09 90 04fA                              1.STE-10 90 Data                  90 04TA            4.46E-C6       6.46E-OS I                                                      .

HP-1-230. Rev. 5 73 ACCachment 10.14 (1 of 3)

TABLE 8 (Continued) 11MALaf!ON DLSF F AC TURS FOR CHILO (DFAi ) teet* #C4 PCI I4 MALE 03 duCLICE BuME Livit f.dQCY Tetetuto a10mEY LUNC Cl-LLI Y 91 S.04t=04 40 04T4 1.lut-09 no caft 40 Daft 2.CtE-01 1.0SE-04 22 91 S.tJf-OS 1.13E-OS 1.00E-OS 40 DATA 1 44t-OS 6.01F-04 1.4SE-OS 2R 97 S.0fC-08 7.J46-09 4 12 E-0 9 NO 04f4 1.0SE-08 1.06E=0S 9.49E-OS 44 9% 6.3SE-06 2.4eE-04 1. 7 7 E -0 6 90 Data 2.33E-06 I.66f-04 1.00E-OS

                                #0 99   40 DATA      4.44E-04            1.15 E -0 4 NO Daft        1.06E-07      1.66E-05           1.42E=0S TC 99*  4.81E-13     9.4tt-13            1.56E-11 10 04fa           1.37E-11      7.57f-c7           L.30E-04 TC101   2.19E-14     2.30f-14            2.91!-13 NO UATA           3.17E-13      1.34E-47           4.41F-09 aut03   7. S S E-0 7 NO DAT4             2.90F-07      40 D4TA      1.10E-06      1.79E-04           1.2tt-CS 4                                autos   4.13E-10 90 DATA                 1 50E-10 en 047.4          3.63E-10      4.3nt-04 2.69E-01 Aut04   3.64E-OS NU 04TA                 4.Sff-06      NO 04f4      4.9FE-OS      3.87E-03           1.14E-04 4Citos  4.56E-06 3.08E-04                2. 4 rt-0 6 40 UATA        S.74L-06      1.48f-03           2.71E-09 TE1259  1.82E-04 6.295-07                2.4 7E-0 7    1.202-07 NC oaf 4          1 29E-04 9.15E-06 TE12Fm  6.72E-04     2.3tt-ce 8. l et-0 7              1.64E-04     8.72E-05      4.00C-04           L.93f=0S TE127   7.49E-10     2.37E-10 1.4SE-10                 S.30E-10     1.9tE=09      2.7tF-06           1 12E-OS TE127p  S.19E-C6     1 4SE-06 8.22 E -0 7              1.7tt-04     1 16E-09      4.76E-04           4.9tE-OS TE129   2.64E-11     9.4SE-12            6.44C-12      L.93E-It     6.94L-11      7.9tt-07           4.89E-06 j                                TEt3tp  3.43E-08     1 60E-08            1.3FE-00      2.64E-08     1.00E-07      1. Set-OS 4.32E-09 Tit 31  S.47C-12 2.28E-12                1.7tC-12      4.394-12     1.19C-It      1.SSE-07           3.60E-07              ,

fft32 1.306-07 7.34E-08 7.12 E -0 0 0.SSE-08 4.79E-07 1.02E-04 3.72E-09 1 130 2.21E-06 4.4A1-04 2 20E-06 4.99E-04 6.6th-04 NG 04fA 1.38E-04 I 131 1.30E=0S 1.30E-0$ 7. 3 7 E-0 6 4.39E-03 2.13d-01 NO 04f4 7.64E-07 1 132 S.72E-07 1.10E-06 S .0 FE -0 7 S.2SE-OS l.69E-06 40 DATA 3.41E-07

                                ! 133   4.44C-04     S.49C-06 2.086-06                 1 04E-03     9.138-06 #0 04f4                 1.40E-04 I 134   3.17E-07 5.84E-07 2 61E-0 7                    1.37E-OS     e.92E-07 ho DATA                 2. Set-07
!                               I 135   1.13E-06 2.14E-06                1.12 E -0 4 2.14C-04       3.62E-06      40 0474            1 20E-06

) CS134 1.768- 06 2 74C-04 6. 0 7 E -0 9 90 DATA e.93E-09 3.27E-01 1 04E-06 i CS t 16 1.76E-01 4.62E=0S 3 14 E-0 $ 40 OATA 2.18E-0$ 3.93E-06 1.13E-06 { C$137 2.4SE-04 2 23E-04 3.4FE=0S NO DATA 7.65E-05 2.4tE=0S 9.7AE-07 CSile 1.7tE-07 2.2FE-07 1. S O E -0 7 NO DATA 1.60E-07 8 84E-OS F .2 9E -0 8 44139 4.98E-10 2.667-13 1.45E-tt NO oaf 4 2.33E-13 l.56E-46 1. S 6E-O S i t

i i i HP-1-230. Rev. 5 74 AttachmenC 10.14 (2 of 3)

d TABLE 8 (continued) i . 1%waLafl04 OCS E p ac f 041 FOR CHILO (DFAi ) lptEm, P!4 *Cl INnatf05 NUCLluf SUNE Lt E4 f.30CY THveolc KICNEY Lu%C it-tLI 04140 2.00E-0) 1.FSL-00 1. t TC-0 6 NO DATA S.7th-09 4.7tE-04 2.71E-01 BAL41 S.290-11 2.95E-14 1.727-12 NO 04f4 2.56E-14 7.s9E.0F f.44E.0g 84142 1.3SE-it 1.73C-LS F.34C-13 40 Cafa 7.37E-11 4.44E-07 F.4tF-10 LAt40 1.74E-0F 6.08E-04 2 04 E-0 8 40 DATA NO 04f4 4.94E-05 4.10E-OS LA142 3.50E-10 1.11E-to 3.49E-11 90 04fA NO Cara 2.3SE.06 2.0SE-01 CE141 1 06E-0) 5.20E-06 f. 4 3 E -01 40 04f4 2.3tE-06 1.47E-04 1.SIE-OS ( CE143 9.89E-08 S.1FE-00 f . 7 7 E -19 40 DefA 2.26k-0R 3.12t=0S 1.44E-OS j CEt44 1 03E-03 S.72C-04 9.77E-05 40 O&fA 3.t?E-04 3.23C-03 t.0SE-04 i pat 43 4.99E-04 1.3CE-06 2. 4 F E -0 F 10 Daft 8.ttt-07 1.17E-04 2.63E-05 Pet 44 1.61E-11 4.99t-12 8.10 E -13 90 04f4 2.64k-L2 4.2SE-41 S.32E-04 40147 2.92E-06 2.36E-06 1 04 F-0 7 40 04f4 1 10E-C6 8.87k-01 2.22P-OS w ISF 4.4tE-09 2.6tC=09 1. l lP -0 9 40 Cefa MC Cafo 1.ttf-05 2.46E-05

         **2s9    1.26E-Or *.04*-09 6. 3 5 E .0 9 =0 04fa      2.63E.ca t.17E.0S t.73E-01 I

l HP.1 230, Rev. 5 75 Ace.ch ne to.14 (3 or 3)

TABLE 9 Values of L-Theta-V (Inverse Meters-Seuared) Calculated usind Oeen-Terrain Facters Pathwav: NILK SGAT E. Sector Distance Paseuill Cateserv M N (Miles) (heters) A B C D E F 8 s e 4 E 3.3 5311 5.23E-07 7.70E-07 1 87E-04 5.47E-64 f.01E-64 1.46E-05 2.35E-05 [g f:: M e lip-1-230 REVISICt: 5_ 76 I.TTACIAMD.T 10.15 (1 of 5)

                                                                       .     .                            _- , - _ =                        .. .                    --     .

TABLE 9 (COfff. )

  .                                                       Values of L-Theta-V (Inverse Noters-Severed)

Calculated usins aren-Terrain Facters Pathmaw: NILK COME > Sectar Sistance Pasevill Cateserv q y (Miles) (meters) A B C D E F S f J ' N 1.1 1779 3.2K-64 1.64E-45 3 1 M-05 7.etE-45 1 9M-94 1.5K-ti 2.42E-04 4' N 4.4 7941 3.4 K-97 3.7K-47 9.4K 3.1 K-44 5.1K-44 4.521-64 1.4K-05 2

                                                                                                                                                                                                                                               , j
                                                                                                                                                                                                                                            'R   "e 2
                          -                                                                                                                                                                                                                e Hr-l C E Ee**        3                                77                                                       Attactsrent 10.15 (2 Of 5) 3 l

TAitLL 9 Values of L-Theta-V llaverse Meters-Sovar:4) Calculated usins Cern-Tarrain factors l Pathuaw: VEGETA!LE EAADEN D Distance Passuill Eateserv i Sector (Malest (P.eterst A 8 C D E F G wi ( M 1.1 1770 3.2SE-06 1.60E-05 3.19E-05 7.01E-05 1.03E-c4 1.5tE-04 2.4?E-04 j : NNE 1.3 2092 2.42E-05 9.85E-04 2.02E-05 4.&tE-05 6.G5E-05 a.0&E-04 1.63E-04

1609 3.91E-06 2.12E-05 4.15E-05 S.91E-05 1.3cE-04 2.00E-04 3.06E-04 , 2 ME 1.0 4.83E-01 2.9CE-45 5.57E-05 1.17E-04 1.71E-44 2.41E-04 3 98E-04 : -.

ENE E 0.9 32 1443 5150 5.4SE-07 8.35E-07 2.01E-06 6.04E-04 9.57E-04 1.54E-05 2.4?E-05 .) 1 ESE 2.3 3701 9.17E-07 2.00E-04 4.55E-04 1.23E-05 1.S?E-05 2.99E-05 4.74E-05 SE 2.3 3701 9.17E-07 2 0CE-06 4.55E-06 1.23E-05 1.89E-05 2.9?E-05 4.74E-05 S 0.9 1448 4.83E-06 2.90E-05 5.57E-05 1.17E-04 1.71E-04 2.&lE-04 3.93E-04 55W 0.9 1443 4.S3E-06 2.90E-05 5.57E-05 1.17E-04 1.71E-04 2.61E-04 3.98E-04 SW 0.9 1448 4.83E-06 2.90E-05 5.57E-05 1.17E-04 1.71E-04 2.61E-04 3.99E-04 ESW 0.9 1448 4.83E-04 2.90E-05 5.57E-05 1.17E-04 1 71E-04 2.61E-04 3.98E-04 W 1.1 1770 3.2SE-04 1.&oE-05 3.19E-05 7.01E-05 1 03E-04 1.5SE-04 2.42E-04 krd 0.9 1449 4.83E-06 2.90E-05 5.57E-05 1.17E-04 1.71E-04 2.61E-04 3 93E-04 kW 0.9 1448 4.83E-04 2 90E-05 5.57E-05 1.17E-04 1.71E-04 2.61E-04 3 9EE-04 NrJ 2.9 4647 4.3&E-07 1.0SE-04 2.5&E-04 7.44E-06 1 17E-05 1 87E-G5 3 00E-05 7e ATTACID'JJC 10 15 (3 of 5) t:r- 1-2 20 Revisien 5

                                                                 ~~ w                          . -       __ .

TALIS 9 Values of L-Theta-V (Inverse heters-Sewared) Calculated usins Been-Terrain Factors ; Pathmaw! KSIMMCES

   .             Sectar               31 stance                                     Paseell! Catesers (Miles) (Noters)           A              B            C           D       E F         G N          S.3            1297 7.7 M-64 4.1M-65 7.7 K-45 1.59E-44 2.32E-04 3.54E-64 5.4K-04                      k'A mesE       4.5            1297 7.7M-44 4.1M-45 7 7K-45 1.5tE-44 2.32E-64 3.54E-44 5.40E-04 hE ENE 4.9 4.9 1448 1448 4.8M-64 2.90E-45 5.5M-45 1.1M-64 1.71E-94 2.61E-64 3.99E-04 4.SM-44 2.90E-05 5.57E-45 1.17E-44 1.7tE-44 2.41E-44 3.tK-44 3   (

E 2.4 4184 7.54E-47 1.44E-M 3.35E-44 9.41E-M 1.4K-45 2.3M-45 3.71E-45 y . ESE 3.4 5472 5.tK-47 7.1 M-47 1.7E-46 5.3N-44 8. 4tE-M 1.30E-45 2.2 M-05 g-,';- SE 3.9 6276 4.99E-47 5.tM-47 1.2E-66 4.tN-44 4.5K-44 1.6E-05 1.74E-45 u 1.3 2992 2.42E-44 9.tK-M 2.62E-45 4.64E-95 4.05E-05 1.6K-44 1.43E-04 t *,

                                                                                                                                ,T Weev       0.9            1448 4. SM-44 2.9K-45 5.5K-45 1.1M-44 1.71E-64 2.41E-64 3.9K-44                        S 4.SM-44 2 90E-45 5.57c.45 1.1M-64 1.71E-94 2.41E-44 3.9K-44                   '   4 Nu         4.9            1448 meu        2.0            3219 1 15E-M 2.9M-M 4.5K-44 1.69E-05 2.5M-05 4 4X-05 4.32E-05

IP-L 230, Ievision 5 79 Attac!mer.t 10.15 14 af 5)

TABLE 9 - ) Values of L-Theta-V (Inverse Meters-Seuared) Calculated usins Deen-Terrain Factors i Pathwaw! SITE BOUNSARY Sector 31 star.ce Paseuill Catesorw (Miles) (Noters) A B C 3 E F G N 0.3 1287 7.77E-04 4.13E-05 7.78E-05 1.59E-04 2.32E- 04 3.54E-04 5.40E-04 NME 4.4 944 2.61E-05 7.94E-45 1.42E-04 2.74E-44 4.GJI-04 4.21E-44 9.61E-04 NE 6.6 964 2.01E-95 7.94E-05 1.42E-04 2.74E-04 4.41E-44 6.21E-64 9.41E-04 m i ENE 4.4 944 2.91E-05 7.94E-45 1.42E-84 2.74E-04 4.41E-44 4.21E-44 9.61E-04 y i E 0.3 1207 7.77E-04 4.13E-45 7.7BE-05 1.59E-04 2.32E-94 3.54E-64 5.46E-04 i f ESE e.4 944 2.41E-45 7.94E-45 1.42E-44 -2.74E-04 4.01E-04 4.21E-04 9.41E-04 , % i SE 0.6 964 2.01E-45 7.94E-05 1.42E-04 2.74E-04 4.01E-04 4.21E-04 9.41E-04

i SSE 0.8 1287 7.77E-64 4.13E-95 7.7tE-95 1.59E-64 2.32E-04 3.54E-44 5.40E-04 $".

i S 1.4 2575 1.6SE-04 5.4&E-96 1.1kE-05 2 82E-45 4.21E-05 4.5&E-05 1.62E-04 ! SSW 3.1 4989 5.75E-07 9.37E-07 2.1DE-06 4.4&E-44 1.82E-45 1.64E-45 2.65E-05 y ;- SW 3.4 5472 5.06E-47 7.13E-07 1.74E-04 5.32E-44 8.49E-64 1.38E-45 2.23E-05 , .; s

,                        WSW      1.5       2414  1.SSE-44 4.551-86 1.3SE-05 3.2tE-05 4.89E-45 7.59E-05 1.1DE-04                                                                                     ','

W 1.0 16C9 3.91E-04 2.12E-05 4.15E-05 0.91E-65 1.30E-04 2.00E-44 3.0&E-04

;                        WNW      0.8       12S7  7.77E-04 4 13E-05 7.7BE-45 1.59E-04 2.32E-64 3.54E-04 5.40E-04 i                        NW       0.8       1287 7.77E-04 4.13E-05 7.70E-05 1:59E-44 2 32E-44 3.54E-94 5.40E-04 I                        NNW      e.9       1448  4.83E-04 2.96E-05 3.57E-05 1.17E-04 1.71E-44 2.41E-04 3.98E-04 IIP-1-230, Revision 5                                                                 80                                          Attachm$nt 10.15 (5 of 5)

TABLE 10 PATHWAY DOSE FACIORS DUE TO RAD 10NUCl.lDES OTHER THAN NOBLE GASES, R i ENVIR0HMENTHL PATHuaV-DOSE COHVERSIGH FACTORS R(I) FOR GASEOUS DISCHARGES PATHUAY: INHALATION AGE GROUP: INFANT (1 0F 4 ) HUCLIDE ORGAH D0SE FACTORS (MREM /YR PER UCI/CU. METER) TOTAL BODY BONE LIVER THYROID KIDHEY LUHG GI-LLI H----3 .647E+03 .000E+00 .647E+03 .647E+03 .647E+03 .647E+03 647Et03 CR--51 .892E+02 .000E+00 .000E+00 .575E+02 .132E+02 .128E+05 .357E403 MH--54 .498E+04 .000E+00 .253E+05 .000E+00 .490E+04 .100E+07 .766E+04 FE--59 .948E+04 .136E+05 .235E+05 .000E+00 .000E+00 .102E+07 .246E+05 i CO--58 .182E+04 .000E+00 .122E+04 .000E+00 .000E+00 .77?E+06 .111E+05 CO--60 .118E+05 .000E+00 .802E+04 .000E+00 .000E+00 .451E+07 .319E+05 l ZH--65 .311E+05 .193E+05 .626E+05 .000E+00 .32SE+05 .647E+06 .514E+05 SR--89 .114E+05 .398E+06 .000E+00 .000E+00 .000E+00 .203E+07 .612E.uS SR--90 .259E+07 .409E+08 .000E+00 .000E+00 .000E+00 .112E+08 .13tE*06 2R--95 .203E+05 .115E+06 .279E+05 .000E+00 .311E+05 .175E+07 .217E+05 I--131 .196E+05 .379E+05 7444E+05 .148E+08 .518E+05 .000E+00 .106E+n4 I--133 .560E+04 .132E+05 .192E+05 .356E+07 .224E+05 . 0 0 6E + 0 0 .216E4u4 l CS-334 .745E+05 .396E+06 .703E+06 .000E+00 .190E+06 .834E+05 .133Ep04 , CS-136 .529E405 .483E+05 .135E+06 .000E+00 .564E+05 .118E+05 . l 4 3E-104T CS-137 .455E+05 .549E+06 .612E+06 .000E+00 .172E+06 .713E+05 e."f33E+04 1-BA-140 .293E+04 .560E+05 .560E+02 .000E+00 .134E+02 .160E+07 1;-f384 E+ 05 - d< CE-141 .199E+04 .277E+05 .167E+05 .000E+00 .525E+04 .517E+06 7 0216E e 05 ' if BASED CH 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE I AHO A VALUE OF 1 FOR X/Q,

DEPLETED X/O AND RELATIVE DEPOSITION llP-I-230, Revision 5 Atta nt 10.16 (1 of to 81

TABLE 10 (CON'T) . PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER

                                                                                   .                                            TilAN N0BLE GASES, R                                          -

i ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS R(I) FOR GASEOUS DISCHARGES PATHWAY: INHALATION AGE GROUP: CHILD (2 0F 4) HUCLIDE ORCAN DOSE FA CTORS < MREM /YR PER UCI/CU. METER) TOTAL BODY BONE liver THYROID KIDHEY LUHG CI-LLI N----3 .tt2E+04 .000E+00 .112E+04 .tt2E+04 .112E+04 .112E+04 .it2E+04 CR--51 .154E+03 .000E+00 .000E+00 .855E+02 .243E+02 .170E+05 .108E+04 l MM--54 .951E+04 .000E+00 .429E+05 .000E+00 .100E+05 .158E+07 .229E+05 l FE--59 .167E+05 .207E+05 .334E+05 .000E+00 .000E+00 .127E+07 .707E+05 CO--58 .316E+04 .000E+00 .177E+04 .000E+00 .000E+00 .tt1E+07 .344E+05 CO--60 .226E+05 .000E+00 .131E+05 .000E+00 .000E+00 .707E+07 .962E+05 ZH--65 .703E+05 .426E+05 .it3E+06 .000E+00 .714E+05 .995E+06 .163E+05 SR--89 .172E+05 .599E+06 .000E+00 .000E+00 .000E+00 .216E+07 .167E+06 l SR--90 .644E+07 .101E+09 .000E+00 .000E+00 .000E+se .111E+08 .343E+06 l 2R--95 .370E+05 .190E+06 .418E+05 .000E+00 .596E+05 .223E+07 .610E+05 I--131 .273E+05 .481E+05 .48tE+05 .162E+08 .788E+05 .000E+00 .284E+04 l I--133 .770E+04 .166E+05 .203E+05 .385E+07 .338E+05 .000E+00 .548E+04 CS-134 .225E+06 .65tE+06 .10tE+07 .000E+00 .330E+46 .12tE+06 .395E+04 CS-136 .116E+06 .65tE+05 .17tE+06 .000E+00 .955E+05 .145E+05 .418E+04 CS-137 .128E+06 .907E+06 .825E+06 .000E+00 .28;E+06 .104E+06 .362E+04 j BA-14 0 .433E+04 .740E+05 .648E+02 .000E+00 .21tE+02 .174E+07 .102E+06 l CE-141 .290E+04 .392E+05 .195E+05 .000E+00 .855F+04 .544E+06 .566E+05 BASED ON 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE I AND A VALUE OF t FOR X/0, l DEPLETED X/Q AND RELATIVE DEPOSITION i l HP-1-230, Revision 5 82 Attachment 10.16 (2 of 19) l

TABLE 10 (CON'T) PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER . THAN NOBLE GASES, R i ENVIRONMENTAL PATHWAY-DOSE COHVERSION FA'CTORS R( I ) FOR GASE058 DISCHARGES - PATHWAY: INHALATION ACE GROUP: TEEH (3 0F 4 ) HUCLIDE ORGAN D0SE FA C TORS ( MREN/YR PER UCI/LU. METER ) TOTAL BODY BONE LIVER THYROID KIDHEY LUNG GI-LLI H----3 .127E+04 .000E+00 .127E+04 .127E+04 .t27E+04 .127E+04 .127E+04 CR--51 .135E+03 .000E+00 .000E+00 .750E+02 .307E+02 .210E+05 .300E+04 MN--54 . 84 0E + o4 .000E+00 .511E+05 .000E+00 .127E+05 .198E+07 .668E+05 FE--59 .143E+05 .159E+05 .370E+05 .000E+00 .000E+00 .153E+07 .178E+06 C0--58 .278E+04 .000E+00 .207E+04 .000E+00 .000E+00 .134E+07 .952E+05 C0--60 .198E+05 .000E+00 .15tE+05 .000E+00 .000E+00 .872E+07 .259E+06 2N--65 .624E+05 .386E+05 .134E+06 .000E+00 .864E+05 .124E+07 .466E+05 SR--89 .125E+05 .434E+06 .000E+00 .000E+00 .000E+00 .242E+07 .371E+06 SR--90 .668E+07 .108E+09 .000E+00 .000E+00 .000E+00 .165E+08 .765E+06 2R--95 .3tSE+05 .146F+06 .458E+05 .000E+00 .674E+05 .269E+07 .149E+06 I--131 .264E+05 .354E+05 .491E+05 .146E+08 .840E+05 .000E+00 .649E+04 I--133 .622E+04 .122E+05 .205E+05 .292E+07 .359E+05 .000E+00 .103E+05 CS-134 .549E+06 .502E+06 .it3E+07 .000E+00 .375E+06 .146E+06 .976E+04 CS-136 .137E+06 .515E+05 .194E+06 .000E+00 .110E+06 .t?8E+05 .109E+05 CS-137 .311E+06 .670E+06 .840E+06 .000E+00 .304E+06 .12tE+06 .848E+04 BA-140 .352E+04 .54?E+05 .670E+02 .000E+00 .228E+02 .203E+07 .229E+06 CE-141 .21?E+04 .284E+05 .190E+05 .000E+00 .888E+04 .614E+06 .126E+06 J l BASED OH 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE I AND A VALUE OF t FOR X/Q, DEPLETED X/O AND RELATIVE DEPOSITION i llP-1-230, Revision 5 63 Attachment 10.16 (3 Of 19) l - - __-____ _ _ - - - - . _ - - - - _ _ _ _ _ _ - - _ - _ _ - _ _ _ _ _ _ _

TABLE 10 (CON'T) PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTilER

                -                                   THAN NOBLE GASES, R 1

ENVIRONMENTAL PATHWAY-DOSE COHVERSION FACTORS R(I) FOR GASEOUS DISCHARGES PATHWAY: INHALATION ACE GROUP: ADULT (4 0F 4) HUCLIDE ORGAN D0SE FAC T0RS (MREM /YR PER UCI/CU.NETER) TOTAL BODY BONE LIVER THYROID KIDHEY LUHG GI-LLI H----3 126E+04 .000E+00 .126E+04 .126E+04 .f26E+04 .126E+04 .126E+04 CR--51 900E+03 .000E+00 .000E+00 .595E+02 .220E+02 .144E+05 .332E+04 MH--54 .630E+04 .000E+00 .396E+05 .000E+00 .984E+04 .140E+07 .774E+05 FE--59 .106E+05 .118E+05 .278E+05 .000E+00 .000E+00 .102E+07 .198E+06 CO--58 .207E+04 .000E+00 .158E+04 .000E+00 .000E+00 .928E+06 .106E+06 CO--60 .148E+05 .000E+00 .115E+05 .000E+00 .000E+00 .597E+07 .285E+06 2H--65 .466E+05 .324E+05 .103E+06 .000E+00 .690E+05 .864E+06 .534E+05 SR--89 .872E+04 .304E+06 .000E+00 .000E+00 .000E+00 .140E+07 .350E+06 SR--90 .610E+07 .992E+08 .000E+00 .000E+00 .000E+00 .960E+07 .722E+06 2R--95 .233E+05 .107E+06 .344E+05 .000E+00 .542E+05 .177E+07 .150E+06 , I--131 .205E+05 .252E+05 .358E+05 .119E+08 .613E+05 .000E+00 .628E+04 I--133 .452E+04 .864E+04 .148E+05 .215E+07 .258E+05 .000E+00 .888E+04 CS-134 .728E+06 .373E+06 .848E+06 .000E+00 .287E+06 .976E+05 .404E+05 CS-136 .110E+06 .390E+05 .146E+06 .000E+00 .856E+05 .120E+05 .117E+05 CS-137 .420E+06 .478E+06 .621E+06 .000E+00 .222E+06 .752E+05 .164E+05 BA-140 .257E+04 .390E+05 .490E+02 .000E+00 .167E+02 .127E+07 .218E+06 CE-141 .153E+04 .199E+05 .135E+05 .000E+00 .626E+04 .362E+06 ,120E+06 BASED ON 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE I HND A VALUE OF I FOR X/Q, DEPLETED X/Q AND RELATIVE DEPOSITION HP-1-230, Revision 5 84 Attachment 10.16 (4 of 19) 1 i J

TABLE 10 (CON'T)- PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER

                                            -                                                                                                                                   THAN NOBLE GASES, R 1

ENVIRONMENTAL PATHWAY-DOSE CONVERSIGH FACTORS R( I) FOR GASE05S DISCHARGES PATHWAY: GROUND-PLANE DEPOSITION AGE GROUP: ALL (1 0F 1) HUCLIDE ORGAN D0SE FACTORS ( SQ.NETER-MREM /YR PER UCI/SEC ) H----3 .000E+00 CR--51 .463E+07 NH--54 .138E+10 FE--59 .271E+09 CO--58 .376E+09 CO--60 .215E+18 2H--65 .74fE+09 SR--89 .2tSE+05 SR--90 .000E+00 2R--95 .243E+09 I--131 .172E+08 I--133 .245E+07 CS-134 .477E+10 CS-136 .150E+09 CS-137 .103E+11 BA-140 .204E+08 CE-141 .136E+08 BASED OH I UCI/SEC RELEASE RATE OF EACH ISOTOPE I AND A VALUE OF t FOR X/0, DEPLETED X/O AND RELATIVE DEPOSITION I I IIP-1-230, Revision 5 85 Attachment 10.16 (5 of 19)

TABLE l@ (CON'T) . PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER

                .                                           THAN N0BLE GASES, R 1

ENVIRONMENTAL PATHWAY-DOSE COHVERSION FACTORS R(I) FOR CASEOWS DISCHARGES PATHWAY: COWS NILK (CONTAMINATED FORAGE) 4GE GROUP: INFANT (1 0F 4 ) HUCLIDE ORCAH D0SE FACT 0RS (SQ. METER-NREM/YR PER UCI/SEC) TOTAL BODY BONE LIVER THYROID KIDHEY LUNG GI-LLI H----3 .230E+04 .000E+00 .238E+04 .238E+04 .238E+04 .238E+04 . 23 8E +' 0 4 CR--51 .804E+06 .000E+00 .000E+00 .525E+06 .115E+06 .102E+07 .234E+08 MH--54 .442E+08 .000E+00 .195E+09 .000E+00 .432E+08 .000E+00 .716E+08 FE--59 .770E+09 .ll2E+10 .196E+10 .000E+00 .000E+00 .578E+09 .934E+09 CO--58 .300E+09 .000E+00 .121E+09 .000E+00 .000E+00 .000E+00 .302E+09 CO--60 .104E+10 .000E+00 .441E+09 .000E+00 .000E+00 .000E+00 .105E+10 2H--65 .439E+11 .277E+11 .95tE+11 .000E+00 .46tE+ll .000E+00 .803E+t1 SR--89 .180E+10 .628E+11 .000E+00 .000E+00 .000E+00 .000E+00 .129E+10 SR--90 .155E+12 .608E+12 .000E+00 .000E+00 .000E+00 .000E+00 .759E+10 2R--95 .587E+04' .340E+05 .828E+04 .000E+00 .892E+04 .000E+00 .412E+07 I--131 .141E+10 .271E+10 .320E+10 .105E+13 .373E+10 .000E+00 .114E+09 I--133 .155E+08 .363E+08 .529E+08 .962E+10 .700E+08 .000E+00 .995E+07 CS-134 .340E+11 .181E+12 .337E+12 .000E+00 .867E+11 .356E+11 .915E+09 CS-136 .100E+tl .982E+10 .289E+11 .000E+00 .115E+11 .235E+10 .439E+09 CS-137 .283E+tt .257E+12 .30tE+12 .000E+00 .000E+11 .327E+11 .94tE+09 BA-140 .619E+08 .120E+10 .120E+07 .000E+00 .285E+06 .738E+06 .295E+09 CE-141 .155E+05 .216E+06 .132E+06 .000E+00 .407E+05 .000E+00 .682E+08 I BASED OH 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE I AND A VALUE OF 1 FOR X/Q, l DEPLETED X/Q AND RELATIVE DEPOSITION j HP-1-230, Revision 5 86 Attachment 10.16 (6 of 19)

TABLE 10 (CON'T) PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN N0BLE CASES, R 1 ENVIRONMENTAL PATHWAY-DOSE COHVERSIOH FACTORS R(I) FOR CASE 0WS DISCHARGES PATHWAY: COWS MILK (CONTANIHATED FORHGE) ACE CROUP: CHILD ( 2 0F 4 )

HUCLIDE ORGAN D0SE FACT 0RS ( SQ. METER-MREM /YR PER UCI/SEC )

TOTAL BODY SONE LIVER THYROID KIDHEY LUNG GI-LLI

                                                  .000E+00           .157E+04        .tS7E+04       .157E+04         .157E+04      .157E+04 H----3                 .157E+04
                                   .508E+06       .000E+00           .000E+00        .282E+06       .770E+05         .515E+06      .269E+08 CR--51                                                                                  .294E+08         .000E+00      .879E+08 MH--54                 .279E+08       .000E+00           .105E+09        .000E+00
                                   .483E+09       .600E+09           .970E+09        .000E+00       .000E+00         .28tE+09      .10tE+10 FE--59                                                                                                                 .353E+09 CO--58                 .185E+09       .000E+00           .605E+08        .000E+00       .000E+00         .000E+00
                                   .636E+09       .000E+00           .216E+09        .000E+00       .000E+00         .000E+06      .120E+10 CO--60                                                                                  .347E+11         .000E+00      .966E+10 ZN--65                 .342E+11       .207E+11           .550E+11        .000E+00
                                   .943E+09       .330E+11           .000E+00        .000E+00       .000E+00         .000E+00      .128E+10 SR--89                                                                                                   .000E+00 SR--90                 .142E+12       .558E+12           .000E+00        .000E+00       .900E+00                       .752E+10
                                   ,374E+04       .191E+05           .421E+04        .000E+00       .602E+04         .000E+00      .439E+0?

2R--95 .000E+00 I I--131 .743E+09 .130E+10 .13tE+10 .432E+12 .2tSE+10 .it6E+09

                                   ,805E+07       .t?2E+08           .213E+08        .395E+10       .354E+08         .000E+00      .857E+07 I--133                                                                                                                .992E+09
                                   .388E+11       .it2E+12           .te4E+12        .000E+00       .570E+11         .205E+11 CS-134                                                                                  .736E+10         .110E+10      .486E+09 CS-136                 .894E+10       .503E+10           .138E+11        .000E+00
                                   .228E+11       .16tE+12           .154E+12        .000E+00       .503E+11         .18tE+tt      .966E+09 CS-137                                                                                                    .305E+06      .296E+09 BA-140                 .341E+08       .584E+09           .511E+06        .000E+00       .167E+06
                                   .808E+04       .109E+06           .544E+05        .000E+00       .239E+05          .000E+00      .679E+08 CE-141 BASED OH 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE I AND A VALUE OF 1 FOR X/Q, DEPLETED X/O AND RELATIVE DEPOSITION llP-1-230, Revision 5                                                 87                                Attachment 10.16 (7 of 19)

I TABLE 10 (CON'T) . PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, R i ENVIROHNENTAL PATHWAY-DOSE CONVERSIGH FACTORS R( I ) FOR CASE 00S DISCHARGES AGE GROUP: TEEN ( 3 0F 4 ) PATHWAY: COWS MILK (COHTAMINATED FORAGE ) l ORGAH D0SE FAC T0RS ( SQ.NETER-MREM /YR PER UCI/SEC ) NUCLIDE ----- TOTAL 80DY BONE LIVER THYROID KIDHEY NG LU GI-LLI

                                .000E+00        .994E+03                  .994E+03                  .994E+03      .994E+03        .994E+03 H----3         .994E+03                                                                           .546E+05       .355E+06       .418E+08 CR--51          .249E+06      .000E+00         .000E+00                 .130E+06
                                .000E+00         .700E+08                 .000E+00                  .209E+08       .000E+00       .144E+09 MH--54          .139E+08                                                                          .000E+00       .190E+09       .143E+10 FE--59          .233E+09       .259E+09        ,604E+09                 .000E+00
                                 .000E+00        .396E+08                 .000E+00                  .000E+00       .000E+00       .546E+09 CO--58          .913E+08                                                                                         .0??C'00       .181E+10
                  .313E+09       .000E+00        .139E+09                 .000E+00                  .000E+00 CO--60                                                                  .000E+00                  .234E+11       .000E+00       .155E+11 2H--65          .170E+11       .105E+11        .365E+tl
                                                                                                                                  .159E+10
                                 .133E+11        .000E+00                 .000E+00                  .000E+00       .000E+00 SR--89          .382E+09                                                                          .000E+00       .000E+00       .928E+10 SR--90          .816E+11       .330E+12        .000E+00                 .000E+00
                                 .824E+04        .260E+04                 .000E+00                  .382E+04       .000E+00       .600E+07 2R--95          .179E+04                                                                                         .000E+00       .148E+09
                  .403E+09       .536E+09        .750E+09                 .219E+12                  .129E+10 I--131                                                                                            .211E+08       .000E+00      .908E+07 I--133         .366E+07       .708E+07        .120E+08                 .168E+10
                                                 .114E+12                 .000E+00                  .364E+11       .139E+11        .142E+10 CS-134          .53tE+11       .486E+11                                                                                          .705E+09
                                 .223E+10        .877E+10                 .000E+00                   .477E+10       .752E+09 CS-136          .589E+10                                                                           .303E+11       .118E+ll       .127E+10 CS-137          ,310E+11       .669E+11         .890E+ll                 .000E+00
                                 .242E+09         .296E+06                .000E+00                   .100E+06       .199E+06       .373E+09 8A-140           .156E+08                                                                          .139E+05       .000E+00       .846E+08 CE-141           .340E+04       .443E+05        .296E+05                 .000E+00 BASED OH 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE I AND A VALUE OF t FOR X/Q, DEPLETED X/Q AND RELATIVE DEPOSITION j     HP-1-230, Revision 5                                           88                                           Attachment 10.16 (8 of 19)

TABLE l@ (CON'T) PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER

                                      .                                THAN NOBLE GASESS 3R                                                             ,

i EHYIRONMENT AL PATHWAY-DOSE COHVERSION FACTORS R( I) FOR GASEOUS DISCHARCES AGE GROUP: ADULT (4 0F 4) PATHWAY: COWS HILK (CONTANIHATED FORAGE) ORGAH D0SE FACT 0RS ( SQ.NETER-NREM/YR PER UCI/SEC ) NUCLIDE ______________ _________________________________________________________Y BONE LIVER THYROID KIDHE LUNC GI-LLI TOTAL BODY _______. ________ ________ ________

                                                                         .763E+03       .763E+03       .763E+03            .763E+03      .763E+03 H----3         .763E+03        .000E+00                                                           .189E+06     .359E+08
                                        .143E+06'       .000E+00         .000E+00       .852E+05       .314E+05 CR--51                                                                        .125E+08            .000E+00      .129E+09 i                         NH--54         .802E+07        .000E+00         .420E+08       .000E+00
                                                        .f48E+09         .348E+09       .000E+00       .000E+00            .973E+08      .ll6E+10 FE--59         .f33E+09                                                                           .000E+00      .477E+09
                                        .528E+08         .000E+00        .235E+08       .000E+00       .000E+00 C0--58                                                         .000E+00       .000E+00            .000E+00      .154E+10 CD--60         .181E+09         .000E+00        .820E+08
                                                                         .218E+11       .000E+00       .146E+11            .000E+00      .137E+11 ZN--65         .986E+10         .685E+10
                                                                                                       .000E+00            .000E+00      .116E+10 SR--89         .208E+09,        .724E+10        .000E+00       .000E+00
                                                                         .000E+00       .000E+00       .000E+L0            .000E+00      .676E+10 SR--90         .574E+11        .234E+12                                                                         .479E+07 l
                                                         .471E+04        .151E+04       .000E+00       .237E+04            .000E+00 3

2R--95 .102E+04 .724E+09 .000E+00 .fl1E+09

                                        .242E+09         .295E+09        .423E+09       .138E+12 I--131
                                                                         .674E+07       .99tE+09       .118E+08             .000E+00     .606E+07 I--133        .205E+07         .388E+07                                                           .716E+f0     .117E+10 CS-134         .545E+11     . .280E+11          .666E+11       .000E+00        .216F+ft
                                                                          .517E+10       .000E+00       .287?+10-           .394E+09      .587E+09 CS-136          .372E+10        .131E+10                                                           .569E+10      .977E+09
                                                         .369E+11         .505E+ll       .000E+00       .171L+11 CS-137          .331E+11                                                       .572E+05            .964E+05      .276E+09
                                         .878E+07        ,134E+09         .168E+06       .000E+00 BA-140
                                                                          .163E+05       .000E+00       .759E+04            .000E+00      .625E+08 CE-141         .185E+04         .242E+05 SASED OH 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE I AND A VALUE OF 1 FOR X/Q, DEPLETED X/Q AND RELATIVE DEPOSITION t

il 89 Attachment 10.16 (9 of 19) llP-1-230, Revision 5 i

TABLE 10 (CON'T) . PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, R 3 FOR GASEOUS DISCHARCES ENVIRONMENTAL PATHWAY-DOSE COHVERSION FACTORS R(!) AGE CROUP: CHILD (1 0F 3) PATHWAY: MEAT (COHTAMIHATED FORAGE) D0SE FACT 0RS ( SQ . METER-MREM /YR PER UCI/SEC ) HUCLIDE ORCAN _____________________________ __________________________________________YROID TH KIDHEY LUNG GI-LLI TOTAL BODY BONE LIVER ________ ________ ________ ________ ________ ,234E+03

                                                .234E+03      -?24E+03         .234E+03          .234E+03 H----3         .234E+03      .000E+00                                         .133E+04          .887E+04      .464E+06
                                .000E+00        .000E+0G      .486E+04 CR--51         .875E+04                       ,80GE+07      .000E+00          ,224E+07          .000E+00      .672E+07 HH--54         .213E+07       .000E+00                                        .000E+00          .176E+09      .63fE+09
                                .375E+09        .606E+09      .000E+00 FE--59         .302E+09                                     .000E+00          .000E+00          .000E+00      .955E+08 C0--58         .501E+08       .000E+00        .164E+08                                          .000E+00      .384E+09
                                .000E+00        .693E+08      .000E+00          .000E+00 CO--60         .204E+09                                     .000E+06          .629E+09          .000E+00      .175E+09
                  .621E+09      .375E+09        .999E+09                                                         .186E+08 a  ZH--65                                        .000E+00      .000E+00          .000E+00           .000E+00 SR--89          .137E+08      .480E+09                                        .000E+00           .000E+00      .140E+09
                                 .104E+11       .000E+00      .000E+00                                           .609E+09 SR--90          .264E+10                                     .000E+00         .836E+06           .000E+00
                  .520E+06       .266E+07        .584E+06                                                        .147E+07 2R--95                                         .166E+08      .547E+10          .272E+08          .000E+00 I--131         .941E+07       .165E+08                                        .118E+01          .000E+00      .286E+00
                                 .574E+00        .7t0E+00      .132E+03 I--133         .269E+00                                     .000E+00          .461E+09          .165E+09      .802E+07 CS-134         .314E+09       .907E+09        .149E+f0                        ,234E+08          .349E+07      .154E+07
                                 .160E+08        .439E+08      .000E+00                                           .799E+07 CS-136         .284E+08                                     .000E+00          .416E+09           .150E+09
                  .188E+09       .133E+10        .128E+10                                           .227E+05      .220E+08 CS-137                                        .38fE+05      .000E+00          .124E+05 BA-140          .254E+07      .435E+08                                         .484E+04          .000E+00      .138E+08
                                  .22tE+05       .110E+05       .000E+00 CE-141          .164E+04 SASED OH t UCI/SEC RELEASE RATE OF EACH ISOTOPE I AND A VALUE OF 1 FOR X/Q, DEPLETED X/O AND RELATIVE DEPOSITION I

I .l 90 Attachment 10.16 (10 of 19) 1 HP-1-230, Revision 5

TABLE l@ (CON'T) . 1 PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, R 3

EHYIRONMENTAL PATHWAY-DOSE COHVERSION FACTORS R(I) FOR GASEOUS DISCHARGES I AGE GROUP: TEEN ( 2 0F 3 ) PATHWAY: MEAT ( CONTAMINATED FORAGE) ORCAN D0SE FACT 0RS (SQ METER-NREM/YR PER UCI/SEC ) HUCLIDE ------ TOTAL 80DY 80HE LIVER THYROID KIDHE" UNG L GI-LLI

                                          .000E+00       .194E+03        .194E+03      .194E+03      .194E+03           .194E+03 H----3           .f94E+03                                                                   .80tE+04           .943E+06
                          ,56fE+04        .000E+00        .000E+00       .312E+04      .123E+04 CR--51                                                                        .209E+07      .000E+08           .143E+08 MH--54            .139E+07       .000E+00        .700E+07       .000E+00
                           .190E+09       .211E+09        .493E+09       .000E+00      .000E+00      .156E+09           .tl7E+10 FE--59                                                                        .000E+00      .000E+00           .193E+09 CD--58           .323E+08        .000E+00        .140E+08       .000E+00
                                          .000E+00        .583E+08       .000E+00      .000E+00      .000E+00           .760E+09 CO--60           .13tE+09
                                                                                       .555E+09      .000E+00           .367E+09 ZH--65           .405E+09       .250E+09        .868E+09       .000E+00 l
                                          .253E+09        .000E+00       .000E+00      .000E+00      .000E+00           .302E+08 SR--09           .726E+07                                                                  .000E+00           .226E+09
                           .199E+10       .805E+10        .000E+00       .000E+00      .000E+00 SR--90                                                                       .693E+06      .000E+00           .109E+10 l

l 2R--95 .325E+06 .150E+07 .472E+06 .000E+00

                                          .887E+07        .124E+08       .363E+10      .214E+08      .000E+00           .246E+07 I--131          .667E+07                                                                   .000E+00           .397E+00
                           .160E+00       .309E+00        .524E+00       .732E+02      .920E+00 I--133                                                                       .385E+09      .147E+09           .151E+08 CS-134           .562E+09       .514E+09        .121E+10       .000E+00
                                          .926E+07        .365E+08       .000E+00       .198E+08      .313E+07           .293E+07 CS-136          .245E+08                                                                   .127E+09           .137E+08
                           .335E+09       .724E+09        .963E+09        .000E+00      .328E+09 CS-137                                                                        .980E+04      .194E+05           .364E+08 BA-140          .152E+07        .236E+08        .289E+05       .000E+00
                                                           .784E+04       .000E+00      .369E+04      .000E+00           .224E+08 CE-141           .901E+03       .117E+05 l                  SASED OH 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE I AND A VALUE OF 1 FOR X/Q, DEPLETED X/O AND RELATIVE DEPOSITION ilP-1-230, Revision 5                                                                     Attachment 10.16 (llof 19)      i 93

d TABLE 10 (CON'T) PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES DIllER . TilAN NOBLE GASES, R g ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS R(I) FOR GASEOUS DISCHARGES 1 AGE GROUP: ADULT ( 3 0F 3 ) PATHWAY: MEAT (CONTAMINATED FORAGE) 1 D0SE FACT 0RS (SQ.NETER-MREM /YR PER UCI/SEC) HU'CLIDE ORGAN _______..__________________ _____________________________________________ID THYRO KIDHEY LUNG CI-LLI TOTAL BODY BONE LIVER ________ ________ ________ l ________ ________ ________ ________

                                                                                                                                                                      .325E+03
                                                                                            .325E+03           .325E+03           ,325E+03        .325E+03 H----3           .325E+03                                          .000E+00                                                                   .931E+04            .t'/6E+07 t
                                                                       .000E+00             .000E+00           .419E+04           .155E+04 CR--51            .702E+04.                                                                                .000E+00           .273E+07        .000E+00            .281E+08 MH--54            .175E+07                                          .000E+00            .9t?E+07                                              .174E+09            .207E+10
                                                                        .264E+09            .62tE+09           .000E+00           .000E+00 FE--59            .238E+09                                                                                 ,000E+00           .000E+00        .000E+00            .368E+09 CO--58            .408E+08                                          .000E+00            .182E+08                                                                  .141E+10
                                                                                            .752E+08           .000E+00           .000E+00        .000E+00 CO--60           .166E+09                                           .000E+00                                                 .756E+09        .000E+00             .712E+09
                      .511E+09                                           .355E+09           .it3E+10           .000E+00 2H--65                                                                                                    .000E+00            .000E+00       .000E+00             .482E+08 SR--89           .862E+07                                            .300E+09          .000E+00                                                                   .359E+09 i
                                                                                            .000E+00            .000E+06           .000E+00        .000E+00 SR--90           .305E+10                                            .124E+11                                                 .940E+06        .000E+00            .190E+10
                       .406E+06                                           .187E+07          .599E+06            .000E+00 2R--95                                                                                                     .501E+10           .262E+08        .000E+00            .403E+07
                       .875E+07                                            .107E+08         .153E+08.                                                                  .578E+00 I--131
                                                                                             .643E+00           .945E+02           .ll2E+01        .000E+00 I--133            .196E+00                                            .370E+00                                                                .165E+09            .269E+08
                                                                           .647E+09          .154E+to           .000E+00           .498E+09 CS-134            .126E+10                                                                                 .000E+00           .26tE+08        .358E+07             .533E+07 CS-136            .338E+08                                            .119E+08          .469E+08                                              .135E+09             .23tE+08
                                                                            .872E+09         .it9E+10           .000E+00           .405E+09 CS-137            .781E+09                                                                                 .000E+00            .122E+05        .205E+05            .587E+08 i

BA-140 .187E+07 .285E+08 .358E+05 .362E+08

                                                                                             .946E+04           .000E+00             440E+04        .000E+00 l     CE-141            .107E+04                                             .140E+05 1

BASED ON 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE I AHO A VALUE OF 1 FOR X/0, I DEPLETED X/0 AND RELATIVE DEPOSITION l 92 Attachment 10.16 (12 of 19) HP-1-230. Revision 5 i

TABLE 10 (CON'T) PATIMAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER

                      -                                             THAN NOBLE GASES, R i

EHVIRONMENTAL PATHWAY-DOSE COHVERSIGH FACTORS R( I ) FOR CASEOUS DISGHbRGES PATHWAY: LEAFY VEGETABLES ACE GROUP: CHILD (1 0F 3) l HUCLIDE ORGAH D0SE FACT 0RS (SQ. METER-NREM/YR PER UCI/SEC ) TOTAL BODY B0NE LIVER THYROID KIDHEY LUNG CI-LLI H----3 .400E+04 .000E+00 .400E+04 .400E+04 .400E+04 .406E+04 .400E+04 CR--51 .116E+06 .000E+00 .000E+00 .645E+05 .176E+05 .118E+06 .617E+07 MH--54 .177E+09 .000E+00 .664E+09 .000E+00 .186E+09 .000E+00 .557E+09 FE--59 .318E+09 .395E+09 .639E+09 .000E+00 .000E+00 .185E+09 .665E+09 CO--58 .196E+09 .000E+00 .64tE+08 .000E+00 .000E+00 .000E+00 .374E+09 CO--60 .tl2E+10 .000E+00 .378E+09 .000E+00 .000E+00 .000E+00 .210E+10 2H--65 .134E+10 .811E+09 .216E+10 .000E+00 .136E+10 .000E+00 .380E+09 SR--89 .102E+10 .357E+11 .000E+00 .000E+00 .000E+00 .000E+00 .130E+10 SR--90 .315E+12 .124E+13 .000E+00 .000E+00 .000E+00 .000E+00 .167E+11 2R--95 .752E+06 .384E+07 .844E+06 .000E+00 .121E+07 .000E+00 .881E+09 I--131 .815E+08 .143E+09 .143E+09 .474E+11 .235E+09 .000E+00 .128E+08 I--133 .165E+0? .354E+07 .437E+0? .812E+09 .729E+07 .000E+00 .176E+07

                                                                                      .000E+00                           .284E+10 CS-134                  .538E+10                .155E+11            .255E+11                        .790E+10                                              .!38E+09 CS-136                  .144E+09                .811E+08            .223E+09        .000E+00        .119E+09           .177E+08                           .783E+07 CS-137                  .338E+10                .239E+11            .229E+11        .000E+00        .746E+10           .268E+10                           .143E+09 i

BA-140 .160E+08 .275E+09 .241E+06 .000E+00 .783E+05 .143E+06 .139E+09 CE-141 .483E+05 .652E+06 .325E+06 .000E+00 .143E+06 .000E+00 .406E+09 4 l i ' BASED OH 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE I AND A VALUE OF 1 FOR X/Q, DEPLETED X/G AND RELATIVE DEPOSITION $ HP-1-230, Revision 5 93 Attachment 10.16 (13 of 19) 4

TABLE 10 (CON'T) PATIMAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, R i

                           -                                                                        3 l                                                                                                                                                            i ENVIRONMENTAL PATHWAY-DOSE CONVERSIGH FACTORS R(I) FOR CASEOUS DISCHARGES AGE GROUP: TEEN         (2 0F 3)     ,

PATHWAY: LEAFY VEGETABLES l l ORGAH D0SE FACTORS ( SQ. METER-MREM /YR PER UCI/SEC ) N0CLIDE -----_--_--------- 2 _----------_-------------------_--_-_----_---------_IDHEY TOTAL BODY BONE LIVER THYROID K LUNG GI-LLI

                                                                        .259E+04        .259E+04            .259E+04             .259E+04       .259E+04 H----3         .259E+04            .000E+00                                                                        .875E+05      .103E+08
                                                   .000E+00              .000E+00        .340E+05           .134E+05 CR--51         .613E+05                                                                      .135E+09              .000E+00      .93tE+09
                               .900E+08            .000E+00              .454E+09        .000E+00 MH--54                                                                    .000E+00           .000E+00              .131E+09      .983E+09 FE--59          .16fE+09            .f78E+09              .416E+09
                                                                         .434E+08        .000E+00           .000E+00              .000E+00      .599E+09 CO--58          .100E+09            .000E+00                                                                       .000E+00      .324E+10
                                                   .000E+00              .249E+09        .000E+00           .000E+00 CO--60          .560E+09                                                                     .940E+09              .000E+00       .622E+09
                               .685E+09            .423E+09              .147E+10        .000E+00 ZH--65                                                                    .000E+00           .000E+00              .000E+00       .t?9E+10 SR--89           .431E+09           .f50E+11              .000E+00 4
                                                                         .000E+00        .000E+00           .000E+00              .000E+00       .211E+11 SR--90           .185E+12-          .751E+12                                                                        .000E+00      .125E+10

^

                                .372E+06           .171E+07              .54fE+06        .000E+00           .795E+06 2R--95
                                                                         .107E+09        .313E+11            .185E+09              .000E+00      .212E+08 I--131          .577E+08           .767E+08                                                                        .000E+00      .249E+07
                                                    .194E+07              .329E+07        .459E+09           .577E+07 I--133          .100E+07                                                                                           .197E+10      .202E+09
                                .752E+10            .689E+10              .162E+1I       .000E+00            .515E+f0 CS-134                                                                     .000E+00           .924E+08              .146E+08      .137E+08
                                                                          .l?OE+09

! CS-136 .114E+09 .43tE+08 .178E+10 .192E+09

                                                    .t0tE+11              .135E+11        .000E+00           .459E+10

) CS-137 .469E+10 .570E+05 .113E+06 .212E+09

                                .884E+07            .f37E+09              .f68E+06        .000E+00 BA-140                                                                    .000E+00           .884E+05              .000E+00       .537E+09 l'

CE-141 .216E+05 .28tE+06 .188E+06 f FOR X/Q, BASED OH 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE I AND A VALUE OF DEPLETED X/O AHD RELATIVE DEPOSITION ! l HP-1-230, Revision 5 94 Attac w nt 10.16 m of 10 ; 1

( TABLE 10 (CON'T) ' l l PATlWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, R 1 I FOR GASEOUS DISCHARGES l ENVIRONMENTAL PATHWAY-DOSE COHVERSION FACTORS R(I) 1 AGE GROUP: ADULT ( 3 0F 3 ) PATHWAY: LEAFY VECETABLES D0SE FACTORS ( SQ . METER-NREM/YR PER UCI/SEC ) j NOCLIDE ORGAH t LIVER THYROID KIDHEY LUNC CI-LLI

!                                                                                 TOTAL 80DY            BONE                             --__-___        ----__--                  _-______                _ --____
                                                                                                                                                          .226E+04                  .226E+04                .226E+04
                                                                                                   .000E+00              .226E+04        .226E+04 H----3           .226E+04                                               .276E+05         .102E+05                 .613E+05                .it6E+0B
                                                                                   .462E+05        .000E+00              .000E+00                                                   .000E+00                .958E+09 CR--51                                                 .313E+09         .000E+00         .930E+08 MH--54           .597E+08        .000E+00                                                .000E+00                 .823E+08                .982E+09 i
                                                                                                   .125E+09              .295E+09         .000E+00                                                          .62tE+09 FE--59           .113E+09                                               .000E+00         .000E+00                 .000E+00
                                                                                   .686E+08        .000E+00              .306E+08                                                    .000E+00               .314E+10 CO--58                                                 .167E+09         .000E+00         .000E+00 CD--60           .369E+09        .000E+00                                                .674E+09                  .000E+08                .635E+09
                                                                                                                                          .000E+00 i
                                                                                   .456E+09        .317E+09              .10tE+10                           ,000E+00                 .000E+00                .159E+10 2H--65                                                  .000E+00        .000E+00 SR--89           .284E+09        .990E+10                                                .000E+00                 .000E+00                .l?5E+11
                                                                                                    .605E+12              .000E+00         .000E+08                                                          .119E+10 SR--90           .148E+12                                               .000E+00         .589E+06                  .000E+00
                                                                                    .254E+06        .it7E+07              .375E+06                                                    .000E+00               .304E+08 2R--95                                                 .itSE+09         .378E+11         .198E+09 I -131           .661E+08        .806E+08                                                .634E+07                  .000E+00               .326E+07
                                                                                                    .209E+07              .363E+07         .534E+09                                                           .199E+09 I--133           .lllE+07                                               .000E+00         .349E+10                   .116E+10
                                                                                    .882E+10        .453E+10              .108E+11                                                     .127E+08               .189E+08 C5-134                                                 .16?E+09         .000E+00         .927E+08 4

CS-136 .120E+09 .422E+08 .295E+10 .981E+49 .16BE+09

                                                                                                     .636E+t0              .870E+10         .000E+00                                                          .263E+09 CS-137            .570E+10                                               .000E+00         .546E+05                  .919E+05
                                                                                     .837E+07        .128E+09              .161E+06                                                    .000E+00               .507E+09 BA-140                                                  .133E+06         .000E+00         .616E+05 CE-t41            .150E+05        .196E+06 i

enSED OH I UCI/SEC RELEASE RATE OF EACH ISOTOPE I AND A VALUE OF 1 FOR X/Q, DEPLETED X/0 AND RELATIVE DEPOSITION Attachment 10.16 (15 of 19) HP-1-230, Revision 5 95

     ' - - - - - - - - . - - - - - _ _ _ _ _ _ _ _ _ _ _ _ __ ___                                                                                                          - - - -            V ~ _ m: .r2-m R

TABLE 19 (CON'T) PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, R i i ENVIRONMENTAL PATHWAY-DOSE COHVERSION FACTORS R(I) FOR CASE 00S DISCHARCES AGE GROUP: INFANT (1 0F 4) PATHWAY: GOATS NILK (CONTAMINATED FORAGE) ORGAN D0SE FAC T0RS ( SQ . METER-NREM/YR PER UCI/SEC ) l HUCLIDE _______ BONE LIVER THYROID KIDHEY LUNG GI-LLI TOTAL BODY ________ ___-____ ________ ________

                                                                                                               .405E+05
                                 .000E+00       .405E+05        .405E+05        .405E+05        .405E+05 H----3          .405E+05                                                      .138E+05        .123E+06       .281E+07
                  .966E+05       .000E+00       .000E+00        .630E+05 CR--5:                                        .234E+08        .000E+00        .518E+07        .000E+00       .859E+07 MH--54          .530E+07       .000E+00                                                                      .121E+08
                  ,100E+08       .146E+08       .254E+08        .000E+00        .000E+00        .75tE+07 FE--5)                                                                        .000E+00        .000E+00       .362E+08
                  .360E+08       .000E+00       .145E+08         .000E+00 C0--53                                                         .000E+00       .000E+00        .000E+00       .126E+09 CO--60          .125E+09       .000E+00       .529E+08
                                                .114E+11         .000E+00       .554E+10        .000E+00       .964E+10 ZH--65          .527E+10       .333E+10                                                                      .271E+10
                                 .132E+12       .000E+00         .000E+00       .000E+00        .000E+00 SR--69          .378E+10                                                      .000E+00        .000E+00       .159E+11
                  .325E+12       .128E+13       .000E+00          .000E+00 SR--90                                        .994E+03          .000E+00      .107E+04        .000E+00        .495E+06 2R--95          .705E+03       .408E+04                                                                       .137E+09
                                 .326E+10        .384E+10         .126E+13       .448E+10        .000E+00 I--131         .169E+10.                                                      .840E+08        .000E+00       .107E+08 I--133         .186E+08       .436E+08        .635E+08         .fl5E+11
                                 .542E+12       .101E+13          .000E+00       .260E+12        .107E+12       .275E+10 CS-134          .102E+12                                                       .345E+11        .706E+10       .132E+10 CS-136         .324E+11       .295E+11        .867E+11         .000E+00
                                                 .903E+12         .000E+00       .242E+12        .982E+11       .282E+10 CS-137          .640E+11       .772E+12                                                       .885E+05       .354E+08
                                  .144E+09       .144E+06         .000E+00       .342E+05 BA- 14 0        .743E+07                                                      .488E+04        .000E+00       .818E+07 CE-141          .186E+04       .260E+05       .458E+05         .000E+00 BASED OH I UCI/SEC RELEASE RATE OF EACH ISOTOPE I AND A VALUE OF f FOR X/Q, DEPLETED X/Q AND RELATIVE DEPOSITION

' IIP-1-230, Revision 5 96 Attachment 10.16 (16 of 19)

1 ABLE 10 (CON'T) PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER , THAN NOBL5 GASES, R 1 ? ENVIRONMENTAL PATHWAY-DOSE COHVERSIGH FACTORS R(I) FOR GASE008 DISCHARCES , PATHWAY: GOATS MILK (CONTAMINATED FORAGE) AGE GROUP: CHILD (2 0F 4) HUCLIDE ORGAN D0SE FACT 0RS ( SQ. METER-MREM /YR PER UCI/SEC ) l TOTAL 80DY BONE LIVER THYROID KIDHEY LUNG GI-LLI j .267E+05 .000E+00 .26?E+05 .267E+05 .267E+05 .267E+05 .267E+05 H----3 .323E+07 CR--51 .609E+05 .000E+00 .000E+00 .338E+05 .924E+04 .618E+05

                                                                                                                                                                      .106E+08 MH--54          .335E+07                   .000E+00                  .126E+08        .000E+00                               .353E+07       .000E+00

) .780E+07 .126E+08 .000E+00 .000E+00 .366E+07 .131E+08 j FE--59 .629E+07 CO--58 .222E+08 .000E+00 .727E+07 .000E+00 .000E+00 .000E+00 .424E+08 , CO--60 .764E+08 .000E+00 .259E+08 .000E+00 .000E+00 .000E+00 .143E+09'

ZH--65 .411E+10 .248E+10 .660E+10 .000E+00 .416E+10 .000E+00 . .tl6E+10

                           .198E+10                   .694E+11                   . 0 0 0E+ 0 0  .000E+00                               .000E+00       .000E+00        .268E+10 t

SR--89 .000E+00 .158E+11 SR--90 .297E+12 .117E+13 .000E+00 .000E+00 .000E+00 l 2R--95 .449E+03 .230E+04 .505E+03 .000E+00 .722E+03 .000E+00 .527E+06

                            .892E+09                  .156E+10                   .157E+10       .519E+12                               .258E+10       .000E+00        .140E+09 I--131                                                                                                                                                     .103E+08 i

I--133 .966E+07 .206E+08 .255E+08 .474E+10 .425E+08 .000E+00

                            .116E+12                  ,337E+12                   .552E+12       .000E+00                               .171E+12       .614E+11         .298E+10   ;

I CS-134 .329E+10 .146E+10 ' CS-136 .268E+11 .151E+11 .415E+ll .000E+00 .221E+11 CS-137 .683E+11 ,484E+12 .463E+12 .000E+00 .tStE+12 .543E+11 .290E+10

                            .409E+07                  .701E+08                   .614E+05       .000E+00                                .200E+05       .366E+05        .355E+08 BA-140                                                                                                                                      .000E+00        .815E+07 CE-141           .970E+03                   .131E+05                  .653E+04       .000E+00                                .286E+04 l

BASED OH 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE I AND A VALUE OF 1 FOR X/Q, i DEPLETED X/O AND RELATIVE DEPOSITION l HP-1-230, Revision 5 Attachment 10.16 (17 of 19)

TABLE 10 (CON'T) PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, R 3 ENVIRONMENTAL PATHWAY-DOSE COHVERSION FACTORS R( I) FOR GASEOUS DISCHARCES AGE GROUP: TEEN < 3 0F 4 ) PATHUAY: GOATS MILK (CONTAMINATED FORAGE) ORGAN D0SE FACTORS ( SQ. METER-MREM /YR PER UCI/SEC ) NUCLIDE ----------------

                    ------------------------------------------------------HEY TOTAL BODY               BONE             LIVER      THYROID          KID LUNG CI-LLI
                                                          .169E+05     .169E+05         .169E+05                  .169E+05        .169E+05 H----3              .869E+05           .000E+00                                                                 .427E+05        .502E+07 1
                                         .000E+00         .000E+00     .166E+05         .655E+04 CR--51              .299E+05                                                                                    .000E+00        .172E+08
                      .167E+07           .000E+00         .841E+07     .000E+00         .25tE+07

! MH--54 .000E+00 .000E+00 .247E+07 .186E+08

                      .303E+07           .336E+07         .785E+07 l  FE--59
                                                          .476E+07     .000E+00         .000E+00                  .000E+00        .656E+08 CO--58              .110E+08           .000E+00                                                                 .000E+00        .217E+09
                                         .000E+00         .167E+08     .000E+00         .000E+00 CO--60              .376E+08                                                                                     . 0 0 0E+ 0 0   .186E+10
                      .205E+10           .126E+10         .439E+10     .000E+00          .28tE+10

< 2N--65

                                                          .000E+00     .000E+00          .000E+00                  .000E+00        .334E+10 SR--89              .802E+09           .280E+11                                                                  .000E+00        .195E+11
                                         .694E+12         .000E+00     .000E+00          .000E+00 SR--90              .171E+12                                                           .458E+03                  .000E+00        .720E+06
                      .214E+03            .988E+03         .312E+03    .000E+00 2R--95
                                                           .901E+09     .263E+12         .155E+10                  .000E+00        .178E+09 I--131             .484E+09            .643E+09                                                                 .000E+00        .109E+08
                                          .850E+07         .144E+08     .201E+10         .253E+08 I--133              . 44 0E+ 07                                                                                                 .427E+10
                                          .146E+12         .343E+12     .000E+00         .109E+12                   .417E+ll CS-134               .159E+12                                                          .143E+11                   .226E+10       .212E+10
                       .t??E+11           .669E+10         .263E+11     .000E+00 CS-136                                                   .267E+12     ,000E+00         .909E+11                   .353E+11        .300E+10 CS-137               .930E+11           .20tE+t2                                                                  .239E+05        .448E+08
                                          .290E+08         .356E+05     .000E+00         .12tE+05 BA-140              .187E+07                                                          .167E+04                   .000E+00        .102E+08
                       .408E+03           .532E+04         .355E+04     .000E+00 CE-141 BASED ON 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE I AND A VALUE OF 1 FOR X/Q, DEPLETED M/0 AND RELATIVE DEPOSITION 98                                 Attachment 10.16 (18 of 19) llP-1-230, Revision 5

TABLE 10 (CON'T) PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN N0BLE GASES, R i ENVIRONMENTAL PATHWAY-DOSE CONVERSION FACTORS R(I) FOR CASE 00S OfSCHARCES AGE GROUP: ADULT (4 OF 4) PATHWAY: GOATS MILK (COHTAMINATED FORACE) ORGAN D0SE FACT 0RS ( SQ . METER-NREM/YR PER UCI/bEC ) N'UCLIDE _______ _____________________--_____.---s____--__________________-_--___--__-__ LIVER THYROID KIDHEY LUNG GI-LLI TOTAL BODY BONE --___-__ ____--_- _-_ -__.

                                  .000E+00              .130E+05       .130E+05       .130E+05       .130E+05       .130E+05 H----3        .130E+05                                                           .37?E+04       .227E+05       .430E+07
                   .17tE+05       .000E+00              .000E+00         102E+05 CR--51                                                            .000E+00       .150E+07       .000E+00       .155E+08 NH--54        .963E+06       .000E+00              .505E+07 i
                                  .193E+07              .453E+07       .000E+00       .000E+00       .127E+07       .tStE+08 FE--59        .t?4E+07                                                                          .000E+00       .573E+08
                   .633E+07       .000E+00              .262E407       .000E+00       .000E+00 C0--58                                                                           .000E+00       .000E+00       .185E+09 CO--60        .217E+08       .000E+00              .984E+07       .000E+00
                                  .823E+09              .262E+10       .000E+00       .175E+10       .000E+00       .165E+10 ZH--65        .itSE+10                                                                          .000E+00       .244E+10
                    .436E+09      .152E+11              .000E+60       .000E+00       .000E+00 SR--89                                                            .000E+0S       .000E+00       .000E+00       .142E+11 SR--90         .12tE+12      .49tE+12              .000Et00                                                     .575E+06
                                  .565E+03              .18tE+03       .000E+00       .284E+03        .000E+00 2R--95         .123E+03                                                                          .000E+00       .134E+09
                    .29tE+09      .355E+09              ,507E+09        .166E+12       .869E+09 I--131
                                                        .809E+07        .it9E+10       .141E+08       .000E+00       .727E+07 I--133        .247E+07       .465E+07                                                           .215E+11       .350E+10
                    .163E+12      ,840E+11               .200E+12      .000E+00        .647E+11 CS-134                                                                            .863E+10       .118E+10       .176E+10 CS-136         .il2E+11      .393E+10               .155E+11       .000E+00
                                                         .151E+12       .000E+00       .514E+11       .l?tE+11       .293E+10 CS-137         .992E+11       .ittE+12                                                                          .331E+08
                    .105E+07       .16tE+08              .202E+05       .000E+00       .687E+04       .itdE+05 BA-140                                                             .000E+00       .9ttE+03       .000E+00       .750E+07 CE-141         .223E+03      .290E+04              .196E+04 BASED OH t UCI/SEC RELEASE RATE OF EACH ISOTOPE I AND A VALUE OF 1 FOR X/Q, DEPLETED X/O AND RELATIVE DEPOSITION HP-1-230, Revision 5 99                             Attachment 10.16 (19 of 19)

l l l FIGURE 7 Relative Deposition for Ground-Level Releases (All Atmospheric Stability Classes) 10-3 , l l 104 \

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I I IIi 11 ! I Ill I ! I Il 1 l lll l! l Il l l ll l l ! lII I ' 10-7 0.1 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS) Obtained from Regulatory Guide 1.111 (March, 1976) Attachment 10.17 (1 of 1) HP-1-230, Rev. 5 100

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                                                                                                                                                -         EEEEEEM74375MEEE 284031                                    053
                           ----------------                                 0 4773987324939737                                         ~

0 0 EEEEEEEEEEEEEEEE 0 0 EEEEEEEEEEMEEEEE4941S 14459913S6 0 3 0412828408403210 . - 0 4715441S4S0S3377 7005932S4S344095 5 10471079S5552512 1359033743230338 7811411221111111 4 4844364473024311 4 56SB591111111987 . 1122123433332222 99989S8888888899 88899988S8S88S88 , 7777777777777777 00000O0000000000

                                                                                       ----------------                                                    00000000O0O00O00

- 0 0000000000000000 EEEEEMMEEEEEEEEE 0 0 0 EEEEKEEEEEEEEEEEOSS74315843 1339 0 3- EEEEEEEEEEEEEEEE 442Oe702043S34e1 1 5 544S4 7940447416079973 930541844 31231SSe14448704 0 830S565849559124 3 8201735472000877 0 4 9 3 9 0 8 0 5. e. 7 5 4 510 6 0 5791511211111199 2 039.S.098407570974 1111112332222111 D 1233134544343222 99S898888S888888 E T 7777777777777777 0000000000000000 00O000000O000000

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EEEEEEEEEEEEEEEE 0 0 0 EEEEEEEEEEEEEEEE 4737789200421731 0 000O00O0O0000000 I R 0 0901S121244e6330 9441333299834042 257277e324939637 2 EEEEEEEEEEEEEEEE 3402321920048415 T 3 4001340415930844 5 3 041282.S.400603210 0 1992425596941004 S 7811411221111111 1544084972719631 - E R N 2344244745454333 7777777677777777 98889888S8888888 00000000O0000000 1 2233235455453333 ~ U 0 0000000000000000

                           ----------------                                   0 0

EEEEEEEEEEEEEEEE E 0 EEEEEEEEEEEEEEEE S782952547SS8877 0 424S832480054708 452S454332407279 SSSSS77777778S88 OOOOO00000000O00 ' - H T 5 2 1098845339201939 5367224067944210 3 0 5044352942024532 8111S12222221111 S E0 L1 EEEEEEEEEEEEEEEE 744S70753565e775 - D N 345536S1S7675555 S888884804888889 I - M5 421S109542984442 58133,03743127042 7777774e44447777 O000000000000000 O Y E S0 0000000O00000000

                            ----------------                            S0 E 0 EEEEEEEEEEEEEEEE                                    N               549951111111998S B        E0 L0 EEEEEEEEEEEEEEEE 120494e7eS135254                              L 0            87311777S33S5e83 7297553447448013 I

I S R 571044971S5214S4 M52 0378098407570974 7777777777777777 O Y I M2 44890625310150.S.8 N 1111112332222111 E I R 0000000000000000 TR N I 54SS59111111SS77 I 889888S8S0888888 A5 EEEMEEEEEEEEEEEE52049457737 919 S-1 AA 7446744444644466 000000O0O0000000 0841448089083007 1 D E SN C0 0000000000000000 E C 0 N0 EEEEEEEEEEEEEEEE N4 U 2490119707540987 ERU N0 EECEEEEEEEEEEEEE 4533eS4720403e00 A0 5598527195491304 3677904204393074 O S 1112122332222111 - LEOA5 2101744474?23533 BTBT T S0 4734367904357521 - AE TMAAS S1 I 9264173831S.05444 . I2 D 1122123443332222 T E N 7777777777777777 - 9111912222121111 N 0000000000000000 RE 46444e6444444446 88S8S8SS8888SSS8 00O0O0OO0000OOO0 G -------------- EEEEEEEEEEEEEEEE AR PA 00000O0000000000

                             ----------------                                   0          ---------------                          -          E4 S-             8544S5736S614197 9284882160422304
-                  0 0        EEEEEEEEEEEEEEEE                                    0 0        EEEEEEEEEEEKEEEE 945S2252955                    3157                        3 9301734773811987 N            0        4957S05381922930   193445544                                  753e147719307451 O

I 1 5078501 4099238183708455 5 1 0545073871718521 12331 34544343222 S R 2333245755453333 2233235455453333 - E 4464465555454446 S888S88788888886 7777777477777777 P S I 0 5 0000000000000000 EEEEEEEEEEEEEEEE 0 0 0 O000O00000000000 EKEEEEEEEEEEEEEE107207?S53S331 2 T 3 0000000000000000 EEEEEEEEKEEEEEEE 245e3e43 3772714 - D 7 S73715992003111S 540168528792982S 229985734S885734 N E 2 2344828440094384 . E S0 8999441410507310 ) 0 S1 5379339145733842 N 4489344080157422 345534819S784555 G C A S E 45774S1111917777 E S E 3455368180775555 S R E S U 6555455555555555 U 8888887777778888 0000000000000000 V C 0 0000000000000000 C R0 0 ---------------- EEEEEEEEEEEEEEEE H C 4444444444464464 0000000000000000 A R0 EEEEEEEEEEEEEEEE 902e434700728&85 E5 0487090454079772 A E -------------- - L E5 T 0534337444377797 T E 7 2218944807537917 3579053442123618 2 EEEEEEEEEEEEEEEF 90903791e647S797 A E0 3155442831905433 N R O 1 17023643S2594513 U N N

                 /           9111S12222121111                                 /

C 56S8591111119SS7 F 1388094244127444 N C 5555555555555555 E 7777877777777777 0000000000000000 ) 111111232222111s A E S (0 0000000000000000 S ( 0 0 EEEEEEEEEEEEEEEE - D E EEEEE S 02 5 EEEEEEEEEEK27229 S484098 S31 S0

3S578e44248272e2 0237198983950907 U 6464445555456664 0 0 0 0 0 0 0 0- n.

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TABLE 12 AVERACE ANNUAL DEPOSITION PARAMETERS FOR AREAS AT OR BEYOND UNRESTRICTED AREA BQUNDARY x esseesseesssesessess3 RELATIVE DEPOSITION PER UNIT AREA (N08-23 AT FIXED POICTS SV S0WNWING SECTOSS secesseessesteessess N SIEECT10N SIS 14NCES IN.NILES

d. FESN SITE 0.25 0.50 0.75 1.00 1.50 2.00 2.50 3.04 3.50 4.00 4.54 {

8 S 1.059E-07 3.582E-08 1.839E-08 S.744E-09 3.141E-09 1.55SE-09 9.172E-10 4.004E-10 4.22&E-10 3.132E-10 2.413E-10 '

  $$               SSW                           1.500E-07 5.072E-08 2 404E-08 1 23SE-08 4.447E-09 2.205E-09 1.299E-09 8.543E-16 5.993E-10 4.434E-10 3.417E-10 C)

SW 2.136E-07 7.222E-08 3.70SE-08 1.763E-08 4.334E-09 3.140E-09 1.849E-09 1.211E-09 8.519E-10 6.313E-10 4.065E-10 ' 98 ESW 1 450E-07 5.SSOC-08 2.se5E-08 1.342E-08 4.893E-09 2.42eE-09 1.429E-69 9.355E-10 4.503E-10 4.070E-10 3.759E-10 W S.780E-08 2.972E-OS 1.52&E-04 7.254E-09 2.eeeE-09 1.292E-09 7.409E-14 4.982E-14 3.506E-14 2.590E-14 2.042E-10 N WNW 1.835E-07 4.204E-08 3.185E-08 1.514E-08 5.440E-09 2.490E-09 1.5SSE-09 1.040E-09 7.319E-19 S.424E-14 4.186E-14 i

NW 2.144E-07 7.249E-OS 3.722E-00 1.769E-08 4.35eE-09 3.152E-09 1.85eE-09 1 215E-09 8 551E-10 4.337E-14 4.884E-10

 -Un'*

NNW 2 242E-07 7.582E-08 3.893E-08 1.851E-08 4.44SE-09 3.297E-09 1.941E-09 1.271E-09 e.945E-14 4.429E-10 5.1tBE-10 i N 1.443E-07 5.557E-OS 2.853E-Os 1.35&E-08 4.872E-09 2.41&E-09 1.423E-09 9.316E-14 4.555E-10 4.85SE-10 3.743E-10 NME 1.348E-07 4.427E-OS 2.37&E-08 1.129E-Os 4.057E-09 2.012E-09 1.te5E-09 7.754E-14 5.4SSE-10 4.045E-10 3 117E-10 NE 1.119E-07 3.784E-Os 1 944E-OS 9.240E-09 3.319E-09 1.e4eE-09 9.492E-10 4.34&E-10 4 44&E-10 3.309E-14 2.S54E-10 ENE 9.912E-OS 3.352E-08 1.721E-08 0.182E-09 2.939E-09 1.458E-09 S.582E-10 5.420E-10 3.954E-10 2.930E-16 2.25SE-10 t E 3.409E-OS 2.911E-08 1.495E-08 7.10eE-09 2.552E-09 1.2eeE-09 7.453E-10 4.884E-10 3.434E-14 2.545E-14 1 941E-10 ; ESE 9.049E-08 3.047E-OS 1.575E-08 7.48&E-09 2 409E-09 1 334E-09 7.852E-19 5.142E-10 3.410E-16 2.681E-10 2.946E-10 SE 1.225E-07 4.144E-00 2.12SE-08 1.011E-08 3.433E-09 1.002E-09 1.061E-09 4.947E-10 4.SSSE-10 3.423E-10 2.792E-10 SSE 1 401E-07 5.413E-OS 2.779E-08 1.321E-08 4.744E-09 2.354E-09 1.3SeE-09 9.075E-14 4.386E-10 4.733E-10 3.447E-10 SIKECTION DISTANCES IN NILES FRON SITE 5.00 7.50 10.00 15.00 20.00 25.00 30.00 35.00 44.60 45.64 54.00 i S 1.917E-10 0.517E-11 5.160E-11 2.40SE-11 1.57eE-11 1.05SE-11 7.583E-12 S.494E-12 4.427E-12 3.537E-12 2.SS7E-12 SSW 2.715E-10 1.20eE-10 7.305E-11 3.492E-11 2.235E-11 1.498E-11 1.074E-11 0.642E-12 4.24SE-12 S.DG7E-12 4.DS7E-12 SW 3.845E-10 L.717E-10 1.040E-14 5.257E-11 3.102E-11 2.133E-11 1.529E-11 1 14SE-11 S.92SE-12 7.129E-12 5.819E-12 WSW 2.997E-10 1.327E-10 s.037E-11 4.042E-11 2.459E-11 1.e4SE-11 1 181E-11 8.870E-12 6.896E-12 S.599E-12 4.496E-12 W 1.591E-10 7.0eeE-11 4.200E-11 2.163E-11 1.349E-11 0.779E-12 6.291E-12 4.724E-12 3.473E-12 2.934E-12 2.395E-12 WNW 3.321E-10 1.475E-10 S.935E-11 4.51eE-11 2.734E-11 1.033E-11 1 313E*11 9.341E-12 7 447E-12 4.12SE-12 4.999E-12 NW 3.SeOE-10 1.724E-10 1.044E-10 5.277E-11 3.194E-11 2.142E-11 1.534E-11 1 152E-11 S.959E-12 7.154E-12 5.641E-12 NNW 4.05SE-10 1.803E-10 1.092E-10 5.520E-11 3.341E-11 2.240E-11 1.405E-11 1.245E-11 9 371E-12 7.456E-12 4 110E-12 M 2.974E-14 1.321E-10 0.043E-11 4.045E-11 2 44SE-11 1 442E-11 1.17eE-11 0.832E-12 4.047E-12 S.484E-12 4.470E-12 NME 2 474E-10 1 100E-10 4.444E-11 3.34SE-h1 2 039E-11 1.347E-11 9 794E-12 7.354E-12 S.710E-12 4.54SE-12 3.72SE-12 NE 2.02&E-10 9.601E-11 5.452E-11 2.75eE-11 1 448E-11 1 118E-11 8.013E-12 4.01?E-12 4.479E-12 3.737E-12 3.056E-12 ENE 1.794E-10 7.970E-11 4.02SE-11 2.440E-11 1.477E-11 9.992E-12 7.095E-12 5.32SE-12 4.143E-12 3.349E-12 2.741E-12 4 E 1.55SE-10 4.921E-11 4.193E-11 2.119E-11 1.283E*11 3.600E-12 es te2E-12 4.427E-12 3.598E-12 2.874E-12 2.346E-12 ESE 1.441E-10 7.292E-11 4.417E-11 2.233E-11 1 351E-11 9.040E-12 4.492E-12 4.875E-12 3 796E-12 3 92SE=12 2.471E-12 i SE 2.218E-10 9.052E-11 5. feet-11 3.017E-11 1.82eE-11 1.224E-11 0.772E-12 4.SS7E-12 S.121E-12 4.991E-12 3 339E-12 l SSE 2.897E-10 1.207E-10 7.797E-11 3.941E-11 2.385E-11 1 599E-11 1 146E-11 S.404E-12 4.490E-12 5.344E-12 4.362E-12 888888888888888888888888 RELeTIVE BEPOSITION PER UNIT 4RE4 IM88-21 SV StuMWING BECTORS $88888888888448888884888 SEGNENT SOUNB4 RIES IN MILES

 > SICECTION                                 .5-1            1-2                          2-3                    3-4                4-5              S-10             10-20                            24-30       34-40        40-50 r'      FRON SITE O
                  $         1.798E-08                  3.4e3E-09                   9.413E-10       4.310E-10                   2.443E-10         9.393E-11        2.717E-11                    1.077E-11       S.751E-12    3.560E-12 SS3            2.545E-OS                   5.214E-09                   1.341E-09       4.113E-10                   3.45BE-10         1.330E-10        3.847E-11                    1.525E-11       0.143E-12    5.040E-12 SW          3.424E-08                   7.424E-09                   1.93SE-09       8.744E-10                   4.924E-10         1.e94E-19       5.478E-11                     2.171E-11       1.139E-11    7.17eE-12 f

g CS3 2.000E-OS 5.734E-09 1.497E-09 4.72&E-10 3.805E-10 1.443E-10 4.233E-11 1.478E-11 S.959E-12 5.345E-12 re U 1 491E-OS 3.055E-09 7.975E-10 3.582E-10 2.026E-10 7.792E-11 2 254E-11 0.934E-12 4.778E-12 2.953E-12

,,          WNW            3.114E-08                   4.378E-09                   1. 445E - 09     7.477E-10                  4.230E-10         1.427E-10        4.70&E-11                    1 845E-11       9.960E-12    4.145E-12 C)

NW 3.43SE-00 7.452E-09 1.945E-09 8.737E-10 4.943E-10 1.901E-10 S.499E-11 2.179E-11 1.144E-11 7 263E-12

,.          NNW            3 805E-08                   7. 79 4E -69               2.935E-09        9.139E-10                   5.170E-10         1.984E-10        5.752E-11                    2.200E-11       1.217E-11    7.535E-12     i wa               n         2.789E-08                   5.712E-09                   1.491E-09       4.497E-10                   3.789E-10         1.457E-10        4.215E-11                    1.471E-11       S.921E-12    S.522E-12

,s NNE 2.322E-08 4.75&E-09 1 242E-09 5.57&E-10 3.155E-10 1.213E-10 3.510E-11 1.391E-11 7.42SE-12 4.S99E-12 [

>-            NE           1.900E-08                   3.091E-09                   1.01eE-09       4.543E-10                   2.581E-10         9.92&E-11       2.872E-11                     1.13SE-11       4.070E-12    3. 742E-12 a            ENE            1 482E-08                   3.44&E-49                  8.995E-10        4.040E-10                   1. 2SSE-10        8 709E-11        2.543E-11                    1.00SE-11       5.301E-12    3.331E-12
>=               E         1.461E-08                   2.992E-09                  7.812E-10        3.509E-10                   1.985E-10         7.433E-11       2.200E-11                     8.752E-12       4 474E-12    2.893E-12
,.          ESE             1.539E-08                  3.153E-09                  8.230E-10        3.49&E-10                   2.091E-10         8.042E-11        2 326E-11                    9.220E-12       4.924E-12    3.04SE-12       '

SE 2.000E-08 4.260E-09 1.112E-09 4.994E-10 2.025E-10 1 00?E-10 3 143E-11 1 244E-11 6.453E-12 4.11SE-12 SSE 2.717E-08 5.545E-09 1 453E-09 4.524E-10 3.491E-10 1.419E-10 4.106E-11 1.427E-11 8.691E-12 5.379E-12 ;

ODCM TECHNICAL SPECIFICATIONS CROSS-REFERENCE (TABLE 13) Tech Spec ODCM Dose Calculation Section Section Methodology 3.3.3.10 8.7 Determination of Alarm / Trip 3.11.1.1 Setpoints for Liquid 4.11.1.1.2 Monitors 3.3.3.11 8.13 Determination of Alare/ Trip 3.11.2.1 Setpoints for Gaseous 3.11.2.4 Monitors 4.11.2.4.1 3.11.1.1 8.6 Liquid Effluents 4.11.1.1.1 3.11.1.2 4.11.1.2 3.11.1.3 4.11.1.3.1 3.11.2.1 8.10 Gaseous Effluents 4.11.2.1.3 (Dose rate due to Noble Gases, 4.11.2.4.1 Radioiodines, Particulates, and Radionuclides with half-lives greater than 8 days.) 3.11.2.1 8.11 Noble Gases 3.11.2.2 4.11.2.2 3.11.2.3 8.12 Radiciodines, Particulates, and - 4.11.2.3 Radionuclides with half-lives greater than 8 days 3.11.4 8.15 Total Dose 4.11.4.1 (40CFR190) 4.11.4.1 3.12.1 8.2 Radiological Environmental 4.12.1 Monitoring 3.12.3 8.3 Interlaboratory Comparison Program 4.12.3 - HP-1-230, Rev.5 Attachment 10.20 (1 of 1) 3

I I OUISIANA 142 ouAnoNoe SrnEer POWER & L1GHT P O BOX 6000

NEW OnLEANS. LOUIStANA 70174 + (504) 366-2345 E $ sysYEU February 26, 1986 W3P86-0040 A4.05 QA Mr. Robert D. Martin Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011

Subject:

Waterford 3 SES Docket No. 50-382 License No. NPF-38 Semiannual Radioactive Effluent Release Report

Dear Mr. Martin:

Enclosed is the subject report on effluent releases which covers the period of July 1 to December 31, 1985. This report is submitted per Section 6.9.1.8 in the Waterford 3 Technical Specifications (NUREG-lll7) of Appendix A to Facility Operating License No. NPF-38 and pursuant to 10 CFR 50.36a(a)(2). Very truly yours,

./

[ % K.W. Cook Nuclear Support & Licensing Manager KWC:CEW:ssf Enclosure cc (w/ enclosure): NRC, Director, Office of I&E NRC, Document Control Desk, Washington, D.C. T cc (w/o enclosure): C.W. Knighton, NRC-NRR J.H. Wilson, NRC-NRR NRC Resident Inspectors Office B.W. Churchill W.M. Stevenson 6 l \}}

W3P86-0040, Semiannual Radioactive Effluent Release Rept,Jul-Dec 1985

Contents

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Dear Mr. Martin:

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W3P86-0040, Semiannual Radioactive Effluent Release Rept,Jul-Dec 1985

Text

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Dear Mr. Martin:

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