ML20080G480

Rev 2 to Lilco Offsite Dose Calculation Manual

ML20080G480
Person / Time
Site:	Shoreham File:Long Island Lighting Company icon.png
Issue date:	09/30/1983
From:	James Smith LONG ISLAND LIGHTING CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
BN1-11600.02, SNRC-967, NUDOCS 8309200292
Download: ML20080G480 (145)

Text

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,IEO PDR ADOCK 05000322 7\\ A PDR i

LONG ISLAND LIGHTING COMPANY m(y\\ SHOREHAM NUCLEAR POWER STATION P.O. BOX 618, NORTH COUNTRY ROAD

• WADING RIVER. N.Y.11792 Direct Dial Number September 15, 1983 SNRC-967 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.

20555 Offsite Dose Calculation Manual Shoreham Nuclear Power Station - Unit 1 Docket No. 50-322

Dear Mr. Denton:

Long Island Lighting Company hereby submits Revision 2 to the O) Offsite Dose Calculation Manual (ODCM). For the convenience ('~, of review, the entire ODCM is enclosed with the revised pages incorporated; therefore, this submittal includes Revision 1 which was hand-carried to Mr. R. Caruso on August 15 and Revision 2 which is indicated by change bars in the page margin. These revisions are in response to several rounds of verbal questions expressed by members of your staff, and address all concerns identified to date with the exception of finalizing the upper range of several calibration curves. This additional information is forthcoming and will be submitted in the near future. Very truly yours, J. L. Smith l Manager, Special Projects RCW:jm cc: R. Caruso C. Petrone All Parties Listed in Attachment 1 FC-8 9 35.1

ATTACHMENT 1 -J' Lawrence Brenner,-Esq. Herbert H. Brown, Esq. Administrative Judge Lawrence Coe Lanpher, Esq. Atomic Safety and Licensing Karla J. Letsche, Esq. Board Panel Kirkpatrick, Lockhart, Hill U.S. Nuclear Regulatory Christopher & Phillips Commission 8th Floor Washington, D.C. 20555 1900 M. Street, N.W. Washington, D.C. 20036 Dr. Peter A. Morris Administrative Judge Mr. Marc W. Goldsmith Atomic Safety and Licensing Energy Research Group Board Panel 4001 Totten Pond Road U.S. Nuclear Regulatory Waltham, Massachusetts 02154 Commission Washington, D.C. 20555 MHB Technical Associates 1723 Hamilton Avenue Dr. George A. Ferguson Suite K School of Engineering San Jose, California 95125 Howard University 2300 Fifth Street . O) (,, Washington, D.C. 20059 Stephen B. Latham, Esq. Twomey, Latham & Shea 33 West Second Street l Daniel F. Brown, Esq. P.O. Box 398 Attorney Riverhead, New York 11901 E Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Ralph Shapiro, Esq. Commission Cammer and Shapiro, P.C. Washington, D.C. 20555 9 East 40th Street New York, New York 10016 Bernard M. Bordenick, Esq. David A. Repka, Esq. Matthew J. Kelly, Esq. U.S. Nuclear Regulatory State of New York Commission Department of Public Service Washington, D.C. 20555 Three Empire State Plaza Albany, New York 12223 Mr. James Dougherty 3045 Porter Street Washington, D.C. 20008 O - - - _... _ _.. _. _ _ _. -, _ ~ -

SNPS-1 ODCM O PLEASE NOTE Revision 1 - August 1983 of the LILCO, SNPS-1, Offsite Dose Calculation Manual has been totally revised from the Original - March 1983 Submittal - Therefore, Revision 1 - August 1983 has no change bars. CHANGE BARS have been used in Revision 2 - September 1983 to locate a change (additions, deletions, and/or modifi-cations) in engineering, design, methodology, etc. CHANGE BARS are not used for Errata (i.e., typos, format changes). lO l l DO NOT REEVE - KEEP IN YOUR ODCM i i i I 1 i i l0 N1-11eee.ez-e2 ay1s1on 2 - September 1ee> f i

SNPS-1 ODCM TABLE OF CONTENTS v Radiological Effluent Technical Specification Section Subj ect Section Page 1 INTRODUCTION-1-1 2 SET POINTS 2.1-1 2.1 LIQUID EFFLUENT SET POINT 3.11.1.1 2.1-1 2.1.1 Radiation Effluent Nbnitor (RE-13) High Alarm Set Point for Dishcarge Waste Sample Tanks, Recovery Sample Tanks, or Yard Piping ' Drain Sump 2.1 '+ 2.1.2 ' Radiation Ef fluent Nbnitor (RE-79) High/ Trip Alarm Set Point f or Reactor Building Salt Water Drain Tank 2.1-6 2.1.3 Residual Heat Removal Heat Exchanger Service Water Outlet Nbnitors (RE-23A.RE-23B)- High Alarm Set Points 2.1-7 2.2 CASEOUS EFFLUENT MDNITOR SET POINT 3.11.2.1 2.2-1 2.2.1 Gaseous, Effluent Pbnitor High Alarm Set Point f or Station Ventilation Exhaust Nbnitor (RE-42) 2.2-2 2.2.1.1 Gaseous Ef fluent Nbnitor High Alarm. . Set - Point for Station Ventilation Exhaust. -Nbnitor (RE-42) Based on Noble Gases Total Body Dose Rate 2.2-2 2.2.1.2 Gaseous Effluent Nbnitor High Alarm Set Point for Station Ventilation Exhaust Monitor (RE-42) Based on Noble Gases Skin Dose Rate (RE-42) 2.2-3 2.2.2 Main Condenser Offgas System Effluent Monitors (RE-65A,B) High Alarm Set Point 2.2-4 2.2.3 Main Condenser Air Ejector Nbnitors (RE-12A,B) High Alarm Set Point for Non-bypass Nbde Operation 2.2-5 2.2.3.1 Initial Set Point f or RE-12A,B Non-bypass Mbde Operation 2.2-5 2.2.3.2 Subsequent Adjustments of Set Points for RE-12A,B in Non-bypass Mode Operation 2.2-6 i l BN1-11600.02-92 111 Revision 1 - August 1983

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SNPS-1 ODCM tT TABLE OF CONTENTS (CONT) Radiological Effluent Technical Specification Section Subject Section Page 2.2.4 Main Condenser Air Ejector Nbnitors (RE-12A,B) High Alarm Set Point for Bypass Mode Operation 2.2-7 2.2.4.1 Initial Set Point for RE-12A,B in Bypass Mode Operation 2.2-7 2.2.4.2 Subsequent Adjustments of Set Points f or RE-12A,B in Bypass >bde Operation 2.2-8 3 DOSE CALCULATION PETHODS 3.0-1 3.1 LIQUID EFFLUENT, DOSE CALCULATION 3.11.1.2 3.1-1 3.1.1 Method 1: (Computerized Method) 3.1-1 3.1.2 Method 2: (Backup Method) 3.1-5 3.2 OPERATION OF LIQUID WASTE TREATNENT SUBSYSTEPE 3.11.1.3 3.2-1 3.3 DOSE RATE DUE TO GASEOUS EFFLUENTS 3.3-1 3.3.1 Method 1: (Computerized Nhthod) 3.3-1 3.3.1.1 Release Rate Estimation 3.11.2.1 3.3-1 (} 3.3.1.2 Total Body Dose Rate 3.11.2.1 3.3-2 (,/ 3.3.1.3 Skin Dose Rate 3.11.2.1 3.3-3 3.3.1.4 Organ Dose Rate (Particulate Releases) 3.11.2.1 3.3-4 3.3.2 Phtbod 2: (Backup ththod) 3.3-5 3.3.2.1 Noble Gas Total Body Dose Rate 3.11.2.1 3.3-5 3.3.2.2 Noble Gas Skin Dose Rate 3.11.2.1 3.3-7 3.3.2.3 Organ Dose Rate (Particulate Releases) 3.11.2.1 3.3-8 3.4 GASEOUS EFFLUENTS, NOBLE GAS AIR DOSE 3.11.2.2 3.4-1 3.4.1 Phthod 1: (Computerized Phthod) 3.4-1 5.4.1.1 Release Estimation 3.11.2.2 3.4-1 3.4.1.2 Noble Gas Gamma Air Dose 3.11.2.2 3.4-2 3.4.1.3 Noble Gas Beta Air Dose 3.11.2.2 3.4-2 3.4.2 Nhthod 2: (Backup Hethod) 3.4-3 3.4.2.1 Noble Gas Gamma Air Dose 3.11.2.2 3.4-3 3.4.2.2 Noble Gas Beta Air Dose 3.11.2.2 3.4-4 l 3.5 GASEOUS EFFLUENT. DOSE DUE TO RADIO-10 DINERS AND RADIOACTIVE NKTERIALS IN l PARTICULATE FORM AND RADIONUCLIDES WITH HALF-LIVES GREATER THAN 8 DAYS 3.11.2.3 3.5-1 3.5.1 Method 1: (Computerized Nhthod) 3.5-1 3.5.1.1 Release Estimation 3.11.2.3 3.5-1 3.5.1.2 Total Body Dose 3.11.2.3 3.5-2 /^"h' BN1-11600.02-92 iv Revision 1 - August 1983 i i

SNPS-1 ODCM ' TABLE OF CONTENTS (CONT) Radiological Effluent Technical Specification Section Subject Section Page 3.5.1.3 Skin Dose 3.11.2.3 3.5-3 3.5.1.4 Organ Dose Due to Inhalation 3.11.2.3 3.5-5 I 3.5.1.5 Organ Doses Due to Ingestion of ' +- Leafy Vegetables 3.11.2.3 3.5-5 3.5.1.6 Infant Thyroid Dose Due to Inhalation and Ingestion of Cow Milk 3.11.2.3 3.5-7 3.5.2 Method 2: (Backup Method) 3.5-11 3.5.2.1 Organ Doses 3.11.2.3 3.5-11 3.6 OPERATION OF VENTIIATION EXHAUST T' TREATMENT SYSTEM 3.11.2.5 3.6-1 3.7 TOTAL DOSE FOR THE URANIUM FUEL. CYCLE 3.11.4 3.7-1 3.7.1 Sources of Radiation and Radioactivity 3.7-1 3.7.2 . Radiological. Impact of Generation of Electricity 3.7-1 d O 4 RECEPTOR LOCATIONS, METEOROLOGY, AND HYDROLOGY-4-1 5 RADIOLOGICf.L ENVIRONIENTAL MONITORING PROGRAM SAMPLING LOCATIONS 5-1 '6-INTERIABORATORY COMPARISON PROGRAM 6-1 Appendix A DERIVATION OF A A-1 it Appendix B DERIVATION OF P B4 otj { l I BN1-11600.02-92 y Revision 1 - August 1983 \\

SNPS-1 ODCM M LIST OF TABLES Table Title 2.2-1 Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Cases l 2 3.1-1 Bioaccumulation Factors to be Used in the Absence of Site-Specific Data 3.1-2 Ingestion Dose Factors for Adults -3.1-3. Ingestion Dose Factors for Teenager 3.1-4 Ingestion Dose Factors for Child 3.1-5 Decay constants 3.1-6 External Dose Factors for Standing on Contaminated Ground for (Fish and 3.1-7 Dose Rate Conversion Factors, At7 Invertebrate) Ingestion Pathway (O - 3.3-1 Child Inhalation Dose Rate Conversion Factors, Pij ) 3.4-1 Noble Gas Dose Factors 3.5-1 Inhalation Dose Factors for Adults 3.5-2 Inhalation Dose Factors for Teenager 3.5-3 Inhalation Dose Factors for Child 3.5-4 Inhalation Dose Factors for Infant 3.5-5 Recommended Values for U,p to be Used for the Maximum Exposed Individual in Lieu of Site-Specific Data 3.5-6 Stable Element Transfer Data 3.5-7 Humidity Parameters at Receptors 3.5-8 Distance from Reactor Centerline by Sector Out to 8046 m 4 ('~'\\ BN1-11t00.02-92 vi Revision 2 - September 1983 LJ i i q .Ta -.n-9y--- T- - " - - v "'+4-P*r-'P M +-erw --"e -~Ta Mey w 7 4(Cee-m'-"-T--- rveW4 - P7-*-"v =xMer +TF--"=-ve7 v "*-"'w-

W ,i 7 SNPS-1 DDCM (~'s \\_,) LIST DF TABLES (CONT'D) Table Title Contaminated Ground, Ingestion of Leafy and Stored 3.5-9 P@ehe, tables Dose Rate Conversion Factors for child 3.5-10 P Child Ingestion' of Cow's Milk Dose Rate bokv,ersionFactors 3.5-11 P Child Ingestion of Goat's Milk Dose Rate Ookv,ersionFactors 3.5-12 P , Child Ingestion of That Dose Rate Conversion haktors 3.5-13 P , Infant Ingestion of Cow's Milk Dose Conversion kaktors J 3.5-14 P , Infant Ingestion of Goat's Milk Dose Conversion ~ hkktors s 4-1 Critical Receptor Locations for Gaseous Effluent Calculations ( 5-1 Radiological Environmental Monitoring Program - (,j}/ Sampling and Collection Frequency 5-2 Radiological Environmental Monitoring Program - Waterhirne Monitoring Stations 5-3 Radivlogical Environmental Monitoring Program - Particulates and Radioiodine 5-4 Radiological Environmental Nbnitoring Program - Direct f Radiation Monitoring Stations 5-5 Radiological Environmental Monitoring Program - Ingestion Monitoring Stations I l l BN1-11600.02-92 vii Revision 1 - August 1983 ~ r 4 m ___y y, .pm. ,7, y__y., ,,%,..wy.,,.._,__e.,,,,.,.,.,..v. _. _. ~.., y-

SNPS-1 ODCM ' ~ ~ LIST OF FIGURES

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~ Figure Title 2.1-1 Detector RE-13. Ef ficiency vs. Gamma Energy 2.1-2 Detector RE-79, Ef ficiency vs. Gamma Energy 2.1-3 Detector RE-23A, Ef ficiency vs. Gamma Energy 2,1-4 Detector RE-23B, Ef ficiency vs. Gamma Energy 2.2-1 Detector RE-42. Ef ficiency vs. Average Beta Energy 2.2-2 Linearity Response Curve f or Detector RE-42 2.2-3 Detectors RE-65A,B, Generic Efficiency vs. Average Beta Energy 2.2-4 Generic Linearity Response Curve f or Detectors RE-65A,B 2.2-5 Detectors RE-12A,B, Efficiency vs. Gamma Energy 2.2-6 Generic Linearity Response Curve for Detector RE-12A.B 3.1-1 Site Boundary for Liquid Effluents g' 3.1-2 Liould Radwaste System Pbdel \\ 3.2-1 Liquid Radwaste Treatment System 3.3-1 Gaseous Effluent Pbdel 3.6-1 Ventilation Exhaust Treatment System 5-1 OnSite Sampling Locations - Radiological Environmental Pbnitoring Program .5-2 off Site Sampling Locations - Radiological Environmental Nbnitoring Program i BN1-11600.02-92 viii Revision 1 - August 1983 O s ai ' m u

.SNPS-1 00CM SECTION 1 INTRODUCTION The purpose of this manual is to show the calculational methodology and parameters used to comply with the Radiological Effluent Technical Specification (RETS). Section 2 establishes methods to calculate the Liquid Effluent 2nitor set point and the Gaseous Effluent Monitor set point in order to comply with RETS Sections 3.11.1.1 and 3.11.2.1, respectively. Section 3 establishes dose calculational methods for liquid and gaseous effluents. The liquid effluents dose calculation methods are used to show compliance with RETS Sections 3.11.1.2 and 3.11.1.3. The dilution factor of 8.85 used in Section 3.1.2 calculation Method 2 is a calculated value based on a submerged, veuttiport diffuser with a port discharge velocity of 12 fps, a 300 ft radius mixing zone, and 4 recirculation pumps discharging. The gaseous effluent dose calculation methods are used to show compliance with RETS Sections 3.11.2.1, 3.11.2.2, and 3.11.2.3. The atmospheric dispersion and deposition factors used in calculation methods were calculated based on i onsite meteorological data for the 2-year period of October 1, 1973 through September 30, 1975. Section 4 identifies the receptor locations which represent critical pathway locatione: water dilution, atmospheric dispersion, and deposition factors used in calculacion Method 2. Table 4-1 summarizes the above factors for the Cs gaseous effluent pathways. 2 (V Section 5 indicates locations at which environmental sampling may be conducted. Section 6 addresses the Interlaboratory Comparison Program. Tables 3.5-10 through % 5-14 are incorporated only for future use if there is a change in the land use census which requires considering any combination of the following pathway (s): cow's milk; goat's milk; and meat. i^ l l l l f l l A BN1-11600.02-92 1-1 Revision 1 - August 1983 l l .-.m ,.__,___.,_...._.,..--c

SNPS-1 ODCM SECTION 2 SET POI!ES 2.1 LIQUID EFFLUENT SET POINT (Compliance with Section 3.11.1.1 of the Radiological Effluent Technical Specification (RETS)) h radionuclide concentrations released via liquid effluents to unrestricted areas shall be limited to the concentrations specified in 10CFR20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the total concentration shall 4 be limited to 2 x 10 pCi/al. The set points of the affluent monitors are dependent on: 1. Circulating water flow rate, a once-through system (the circulating water system is composed of four pumps and circulates sea water at a rate of $74,000 gpa) 2. Flow rates of effluents from tanks and/or from the RHR heat exchanger service water outlet, ar.d/or yard piping drain sump. 3. Individual concentrations of gamma esitters (other than dissolved or entrained noble gases) and Sr-89, Sr-90, Fe-55, and H-3; and the total concentration of dissolved or entrained noble gases and gross concentration of the sipha emitters in the liquids to be discharged. 4 Maximum allowable concentration of 2x 10-4 pCi/mi for the total O concentration of dissolved or entrained noble gases and maximum permissible concentrations (MPCs) of other gamma emitters, Sr-89, Sr-y0, Fe-55, H-3, and alpha emitters in the effluents as specified in 10CFR20, Appendix B, Table II, Column 2 for an unrestricted area. NOTE: Precautions should - be taken to assure that the circulation system flow rate used in determining the set point remains constant during the period of discharge. If the circulating water flow rate during discharge becomes less v.han the ? low rate that ~was used in calculating the discharge set point, the discharge must be terminated and a new set point calculated. l l . Service water via the RHR heat exchanger service water outlet will be released continuously to the environment when the RHR heat exchanger is in operation. Reactor building salt water ~ drain tank contents any be released to the environment either as a batch process or continously. The discharge wante sample tanks, recovery sample tanks, and yard piping drain sump contents will - always be released to the environment as batch processes. t BN1-11600.02-92 2.1-1 tevision 1 - August 0 83 i l i

SNPS-1 ODCM For batch as well as continuous releases, the sampling and analysis program shall. be in accordance with the minimum. requirements of RETS Table 4.11.1.1.1-1. Specifically, the analysis program will include the determination of gross alpha concentration of the alpha emitters. In -addition, it will include isotopic analysis for determination of individual concentrations of principal gamma emitters, and the specific radionuclides. l Sr-89, Sr-90, Fe-55, and H-3. It will also include the determination of total concentration of the dissolved and entrained noble gases (gamma emitters) in the liquids. The concentrations of individual gamma emitters are determined by gamma spectral analysis of 1) the batch sample prior to its release for the batch releases and 2) the weekly composite sample for continuous releases. For gross alpha and the specific radionuclides Sr-89 Sr-90, Fe-55, and H-3, 4 if analysis cannot be performed prior to discharge, then the following concentrations are used in the monitor set point calculations: Gross alpha and H-3 4 Gross alpha concentration and H-3 concentrations as determined by analysis of the previous monthly composite sample. Sr-89, Sr-90, Fe-55 Individual concentrations are determined by analysis of the previous quarterly j composite sample for batch releases. p Representative Samples V Representative composite samples utilized in determining the concentrations of H-3, Sr-89, Sr-90, Fe-55, and the gross alpha concentration both for batch and continuous releases,and in determining the concentrations of garmaa emitters I (excluding dissolved and entrained noble gases) for continuous releases are obtained in accordance with the method stated for obtaining such samples in the RETS Table 4.11.1.1.1-1. [ The tank contents are recirculated prior to obtaining samples for analysis. The minimum recirculation time t shall be: r tr" where: v = the volume of liquid in the tank to be sampled f = the recirculation flow rate being used to mix the tank contents. r For the yard drain sump, the above methodology will be used unless it can be i determined that there has been no condensate storage tank overflow events since the last batch release. Although designated a batch release, there 2 maybe times when' non-contaminated yard drain runof f to the sump will occur during the discharge period. This input will not increase the discharge concentration. .O 1 - ee.e2-e2 2.1-2 e.1sion 2 - eeFtember 19e3 4 v, v -=-1.~,-,- ,~ ,,..wy,--,vy,w ,.-<,,,--,--,v-esiw,--y,m1-,---w-, ,-,--y,,r-w e ,,y,,www- ,,%y-- ,,,w..,,=,-y...-,-t.-,-weev---

SNPS-1 ODCM This will ensure that a representative sample will be obtained for batch releases. Set Point Philosophy The philosophy of the set points will be based on the sum of the ratios of isotopic concentrations to MPCs being less than 1 for discharges into unrestricted areas. Specifically: C C g g MPC " i=1 MPCg U a b n a G " MeC, + MPC ' ' + MPC + MPC,+ MPC + b n g a t Fe + MPC + MPC + MPC i1 (2.1-1) s t Fe where: C,,C ,......C, = Concentration of the individual ganusa emitting b radionuclides identified ( Wi/ml) The gross alpha concentration ( $1/ml) C = a The total concentration of dissolved or entrained noble gases C = g (pCi/ml) C, The Sr-89 and Sr-90 concentrations ( Wi/ml) = The H-3 concentration ( $1/al) C = t C, The Fe-55 concentratica ( Wi/ml) = p MPCg= WC,, ECb * '.. EC, MC,, EC, WC,, MC, MC, n g t p the maximum permissDle concentration of the respective = radioisotope 1 ($1/ml) from 10CFR20, Appendix B, Table 11 Column 2. For dissolved or entrained noble gases, the maxitsum allowable concentration (MPCg) will be 2.00E-04 (pCi/si). For gross alpha, the MPC assumed will be 3.00E-08 (pCi/ml). If the C/MPC calculated is greater than 1, then no release is possible. The normalization factor (as defined in Section 2.1.1) must be greater than 1 t 2 permit teeleases. To permit releases, this factor can be increased to a value greater than 1 by increasing dilution flow Fe (by running more circulating water pumps in the applicable discharge structure), and/or decrease the f etc. (defined in Section 2.1.1), and f' I*fBA* HB, effluent flow rates D s recalculate C/MPC using new C in Equation 2.1-1. g \\b BN1-11600.02-92 2.1-3 Revision 2 - September 1983

SNPS-1 ODCM [V) 2.1.1 Radiation-Effluent Monitor (RE-13) High/ Trip Alara Set Point for Discharge Waste Sample Tanks, Recovery Sample Tanks, or Yard Piping Drain Sump he function of this monitor set point is to ensure that the sua of the ratios of the discharge concentrations to the MPCs of the corresponding radionuclides -of the discharges monitored by this isonitor and other liquid waste discharges, if any, does not exceed 1. If the monitor count rate is higher than the calculated set point, the radiation monitor will terminate the release. A sample is taken f rom - any of the following tanks or sump which is to be discharged along with any streams which are in the process of being discharged. 1. Discharge waste tanks 2. . Recovery sample tanks 3. Yard piping drain sump 4. Reactor building salt water drain tank 5. Residual heat removal heat exchanger service water only one of the first three items above is discharged at any one time, which can be combined with releases from item 4 and/or 5. b Obtain the circulating water flow rate from the control room (see NOTE in d Section 2.1). Define Normalizing factor ~IM)I [fg+fgg + fg + f, + (F, - FHA

• 0.8 F

= { (C HiB B + C,g,) f f f g1g MA + C f ggg+C i=1 MPC An isotopic analysis of each sample is performed. This analysis includes isotopic analysis for gamma emitters; gross alpha emitters; total dissolved or p entrained noble gases ; and Sr-89, St-90, Fe-55, and H-3. This should be done ' for all monitors. i l Ther. the set point (NOTE: the background (cpa), if it can' be determined, is also added to the set point value. If, however, it cannot be determined, it is considered as zero) for detector RE-13 is calculate 1 as: N S f F* [ C

• E (cpa) g3 i=1 l

r i BN1-11600.02-92 2.1-4 Revision 1 - August 1983 J

i SNPS-1 ODCM-l where: Di conceatration of radioisotope (1) (pCi/ml) in any of the following = . tanks or sump that is to be discharged: 1. discharge waste ranks 2. recovery sample tanks ' 3. yard piping drain sump D Discharge flow rate (gpa) from any of the following tanks or sump that f = is to be discharged:

1. - discharge waste tanks 2.

recovery sample ~ tanks 3. yard piping drain sump. (Maximum design discharge flow rate = 150 gpe) Reactor building salt water drain tank concentration of C = gt radioisotope (i) (pci/al) CHIA = RHR-heat exchanger service water outlet concentration of radioisotope (i) (pCi/al) from loop A. CHiB = RHR heat exchanger service water outlet concentration of radioisotope (i) (pCi/al) from loop B. Reactor building salt water drain tank discharge flow rate (gpa). f = 3 (Maximum design discharge flow rate = 50 gpe) HA RHR heat exchanger service water outlet discharge flow rate (gpa) from f = loop A (Maximum design discharge flow rate = 9340 gpa) f HB RHR. heat exchanger service water outlet discharge flow rate (gpa) from = loop B (Maximum design ' discharge flow rate 9340 gpa) C Total circulating water flow rate.(gpa) (this includes FHA and fHB) F = E Gamma counting efficiency of RE-13 for radionuclide (i) = t (cpa/ pCi/al). Figure 2.1-1 shows the energy response. For non gamma emitters, E =0. 1 0.8 Safety factor = All other parameters are as defined in Section 2.1.1. The above calculation - .is made for each batch to be released. Af ter each batch release, the high alarm set point should be reset as close to the background as practical to prevent spurious alarms and yet assure an alarm should an inadvertent release occur. BN1-ll600.02-92 2.1-5 Revision 1 - August 1983

SNPS-1 ODCM O t]' 2.1.2 Radiation Effluent Monitor High Alara Set Point (RE-79) for Reactor i Building Salt Water Drain Tank The function of this monitor set point is to ensure that the sum of the ratios of the discharge concentrations to the MPCs of the corresponding radionuclides of the discharges monitored by this monitor and other liquid waste discharges, if any, does not exceed 1.. If-the monitor counc rate is higher than the calculated set point, the radiation monitor will alarm in the control room. A sample will be. taken from the reactor building salt water drain tank discharge, along with individual samples of any of the following streams which may be in the process of being discharged: 1. Discharge waste sample tanks 2. Recovery sample tanks 3. Yard piping drain sump 4. Residual heat removal heat exchanger service water l In the case of continuous release, samples will be taken as per requirement RETS Table 4.11.1.1.1-1. A Obtain the circulating water flow rate from the control room (see NOTE in Section 2.1). 'The set point for continuous or batch release (see NOTE P. Section 2.1.1) will l2 be calculated as follows: i N S79 f, F

• Q,g gg g]

(cpa) C E ^ where: Et= Gamma counting efficiency of RE-79 for radionuclide i (cpm /nci/ml). Figure 2.1-2 shows the energy response. For non-gamma emitters, Et=0 I All other parameters are as defined in Section 2.1.1. When the tank operates in a batch mode, the above calculation is made for each batch to be released. 2 Af ter each batch release or continuous release period, the high alarm set point should be reset as close to the background as practical to prevent spurious alarms and yet assure an alarm should an inadvertent release occur. !O 1-11600-02-92 2.1-6 Revision 2 - September 1983

-f SNPS-1 ODCM i O 2.1.3 Residual Heat Removal Heat Exchanger Service Water Outlet Monitors (RE-23A, RE-238) High Alarm Set Points .The function of this monitor set point is to ensure that the sum of the ratios of the discharge concentrations to the MPCs of the corresponding radionuclides of the discharges monitored by this monitor and other liquid waste discharges, if any, does. not exceed 1. If the monitor count rate is higher than the calculated set point, the radiation monitor will alarm in the control room.- l2 Monitors RE-23A and RE-238 are independent. Each is dedicated to monitor its respective RHR loop. A sample will be taken from the RHR heat exchanger service water outlet (A and/or B), along with individual samples of any of the following streams which may be in the process of being discharged: 1. Discharge waste sample tanks 2. Recovery sample tanks 3. Yard piping drain sump 4. Reactor building salt water drain tank discharge Obtain - the circulating water flow rate from the control room (see NOTE in A Section 2.1). The set points for RE-23A and RE-238 are calculated as follows: S fF*[ C 2% g HiA iA fF*[gfg C I 238 HIB fB where: E = Gamma counting efficiency of RE-23A for radionuclide i iA ~ (cps / Wi/al). Figure 2.1-3 shows the gamma energy response. For non-gamma emitters, Egg = 0 E = Gamma counting efficiency of RE-238 for radionuclide 1 gg (cpm /$1/ml). Figure 2.1-4 shows the gamma energy response. For non-gamma emitters, EiB = 0 . All other parameters are as defined in Section 2.1. BN1-11600.02-92 2.1-7 Revision 2 - September 1983

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1. -

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+ 4

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n 1-I t: L tr JE...:.n: 1:: . _,_ _t t-. 4,.,. 4n,- ._1_.U1. .a ~ . t++ 2 y.,. . 44., . _.g_- +. p.. :..;py _.. +4++ . 4.. 4 4 ,.y a. t_ s. .l. ^ -- t44 tit +f +- f.t l ^ t--4 +ff+ +.-C-ty+. 4 1.J .~ -.f._ 4T.~$ m .ti + J i. 4 4.r. u. 4 __._.'.4_ + +- tt-*+ tt++ ++.- -t-4 t 4 '.1*+ 9 .4 1 11.a til. v.4 if'. }4 d' __ y.4.,,;,. w7 t ._. 4 _4 +. . I. i m u .._4 p. T.. i .u;,p. 2 9 t .,I;p 4 24 n.. 4 p..9p 4 y 94 4 4_.. L t t+ + 4 y 9 t -t t+--,t++ l-St TH -+-t- -i t.i ~: ::t. t - + : t-- t tt . t 107-10 10: [03 10* GAMMA ENERGY (KEV) SOURCE: FIGURE 2.1-1 BATTELLE COLUMBUS INSTITUTE COLUMBUS, OHIO DETECTOR RE-13 DATA SHEET IL-CP-600-D5 EFFICIENCY VS. GAMMA ENERGY EXTRAPOLATION FROM GENERAL ATOMIC CO. SHOREHAM NUCLEAR POWER STATION-UNIT 1

=---.

GENERIC CAllBRATION CURVE FOR RD-53 OFFSITE DOSE CALCULATION MANUAL REVISION 1-AUGUST 1983

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10 10 jo io. GAMMA ENERGY (KEV) SOURCE: FIGURE 2.1 -2 BATTELLE COLUMBUS INSTITUTE COLUMBUS, OHIO DETECTOR RE-79 OATA SHEET: IL-C P-600 -D 5 EFFICIENCY VS. GAMMA ENERGY EXTRAPOLATION FROM GENERAL ATOMIC CO. SHOREHAM NUCLEAR POWER STATION-UNIT 1 ---=== OFFSITE DOSE CALCULATION MANUAL GENERIC CALIBRATION CURVE FOR RD -53 REVISION 1-AUGUST 1985

n* /a m / k \\ e 4. . _m m

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• t++

1 -tt + .,t '.y_. i, p- _._q 2 ..+..4 _g 4 + 4 1 '4 + + + + - - + - - + - + -*+- +- ~ -+- +. F.'. '_. I+*tt 1 u I t' ~ f y;, m 4 49 4h tM; h.-}M+4 l l 7 y++p'd -T ^ i + 1 g. 2.-~ + _ a 4 t. '+ -+ + + + m 4 =,-..u. 24 4 4 10 7 - e i i i 10 108 108 10* GAMMA ENERGY (KEV) SOURCE: FIGURE 2.1 - 4 BATTELLE COLUMBU3 INSTITUTE COLUMBUS, OHIO DETECTOR R E-23 B DATA SHEET: I L-CP-600 -D 5 EFFICIENCY VS. GAMMA ENERGY EXTRAPOLATION FROM GENERAL ATOMIC CO. SHOREHAM NUCLEAR POWER STATION-UNIT 1

==---- OFFSITE DOSE CALCULATION MANUAL GENERIC CALIBRATION CURVE FOR RD-53 REVISION 1-AUGUST 1983 u

SNPS-1 ODCM 2.2 GASEOUS EFFLUENT MONITOR SET POINT (Compliance with Section 3.11.2.1 of the RETS) The high alarm set point for the Station Ventilation Exhaust Monitor- (RE-42) is set in accordance with the dose rate limLt for noble gases at the site boundary specified.in Section 3.11.2.1 of the RETS* Luss than or equal to 500 mres/yr to the total body and less than or equal to 3000 mrem /yr to the skin. The set point for this monitor will be determined based on the lower of the two set points calculated for: 1) the total body dose rate and 2) the skin dose rate, calculated respectively in Sections 2.2.1 and 2.2.2. i The high alarm set points for the Main Condenser Offgas System Effluent Monitors (RE-65A, B) is based on the MPC limit specified in 10CFR20 Appendix B, Table II, Column 1.which is in conformance with the dose rate limits specified above. The high alarm set point for. the Main Condenser Air Ejector Monitor (RE-12A, B) in normal operation is based on the RETS limited total noble gas (beta and gamma) release rato at the main condenser air ejector, which is 244,000 sci /see at 30 minutes delay. The high alarm set point for the Main Condenser Air Ejector Effluent Monitors in the bypass mode (RE-12A, B in the bypass mode) are based on 25% of the limit specified above. For all the above monitors, the initial set points are based on expected .p release rates (Ci/ year) for radionuclides given in. the Safety Evaluation ij Report (SER) for Shoreham (NUREG-420, April 1981, Table 11-2). An effective initial concentration, C (pC1/cc) for each' radionuclide, i, is obtained from g the release rate, Qg(Ci/yr) for the radionuclide and the appropriate flow rate V(cc/sec) as follows: 1 1 Q (Ci/yr)

• 10

( ) g g C (pCi/cc) = 1 g 7 (y,,,,) V(cc ) 3.15

• 10

,,e i (C1/yr) When the onechanical vacuum pump is in operation, the release rate Q, hanical the mec frommechanicalvacuumpumpexhaustwillbeusedasgumingthat j l vacuum pump operates for 100 hours or 3.6 x 10 seconds per year. The mechanical vacuum pump is in operatkon(,pCi/cc) effective initial concentration C for radionuclide, i, when the l-is calculated as: Qg (Ci/yr)

• 10

( ) Cg (pCi/cc) = 5 3.6

• 10 (sec) y

) Once operation,has begun, the concentration, C, for each radionuclide, will g be obtained as the measured value from a grab sample. O BN1-11600.02-92 2.2-1 Revision 1 - August 1983 .f-

SNPS-1 ODCM O The methodology of multipying the observed cpm by the calculated scale factor V will be used to obtain the set point in the range where the detector response 2 is linear with changes in nuclide concentration. In the non-linear region, appropriate correction as derived from Figure 2.2-2 or 2.2-4 will be made. 2.2.1 Gaseous Effluent Monitor High Alarm Set Point for Station Ventilation Exhaust Monitor (RE-42) 2.2.1.1 Gaseous Effluent Monitor High Alarm Set Point for Station Ventilation Exhaust Monitor (RE-42) Based on Noble Gases Total Body Dose Rate 1. During operation a gaseous sample from the monitor will be taken and analyzed for isotopic composition and concentration, C. Before g will be calculated as noted in Section 2.2. startup, Cg 2. At the time of sampling, the net count rate (excluding background), l2 CR (cpm), of the Station Ventilation Exhaust Noble Gas Radiation Monitor will be recorded. Before startup, the estimated CR is calculated as: 0 * (N

• E}

(cpm) gC g CR = 10 where: detector efficiency (cpm / $1/ce) for RE-42 for E = g radionuclide, i, as provided in Figure 2.2-1. The linearity 2 response for RE-42 is shown in Figure 2.2-2. O 3. The noble gas total body dose rate is calculated using the following equation: [ DRg X/Q*V*([DFB*C) (mrem /yr) = g g where: DR = predicted dose rate based on gas sample (arem/yr), g 3 X/Q = annual average x/Q (sec/m ) at 366 meters NNE due to releases via the station ventilation exhaust point 3 (6.6E-07 sec/m ), g=totalbodydosg)rateconversionfactor DFB (mres/yr/pCi/m, from Table 2.2-1, l l C = sampled isotope release concentration (pCi/ce), g V = station ventilation exhaust rate (cc/sec). (Maximum exhaust rate = 1.70E+08 cc/sec (3.60E+05 cfm).) l l l h I I BN1-11600.02-92 2.2-2 Revision 2 - September 1983 r

SNPS-1 ODCM /'N 4. The isotopic release activity concentration is normalized to a total body dose rate of 500 mres/yr by multiplying by the following normalizing factor: F =500/[DRg 3 5. From the above, the set point (see NOTE in Section 2.1.1) based on total body dose rate can be calculated as follows: 8 S 42 1 0.8

• Fg
• CR (cpm) where:

I high alarm set point that results in a total body dose rate of S = less than 500 mrem /yr, normalization factor (unitiess), and -F = B station ventilation exhaust noble gas radiation monitor count CR = rate (cpm). The above procedure and format will be used to calculate the set point for RE-42 when the mechanical vacuum pump is in operation or during containment purge. Under these conditions, the short term atmospheric dispersion factor 3 at 366 meters NNE (3.60E-06 sec/m ). shall be used instead of the annual average value. 2.2.1.2 Gaseous Effluent Monitor High Alarm Set Point for Station Ventilation Exhaust Monitor (RE-42) Based on Noble Gases Skin Dose Rate 1. During operation a gaseous sample from the monitor will be taken and analyzed for isotopic composition and concentration, C. Before g will be calculated as noted in Section 2.2. startup, Ci 2. At the time of sampling, the net count rate (excluding background), l2 CR (cpm), of the station ventilation exhaust noble gas radiation monitor will be recorded. Before startup, CR is calculated as noted in Section 2.2.1~. l 3. The noble gases beta and gamma skin dose rate is calculated using the l following equation: l {DRg =X/Q*V*([K,g,*C) (arem/yr) g where: DR = predicted dose rate based on gas sample, (arem/yr), g 3 X/Q = annual average x/Q (sec/m ) at 366 meters NNE. due to releases via the station ventilation exhaust point, 3 (6.6E-07 sec/m ), l BN1-11600.02-92 2.2-3 Revision 2 - September 1983 I

SNPS-1 ODCM 3 ) bim = skin dose rate conversion f actor (mrem /yr/pci/m ), from Table 2.2-1, v C = sampled isotope release concentration (pCi/cc), g V = station ventilation exhaust rate (cc/sec). (Maximum exhaust rate = 1.70E+08 cc/sec (3.66E+05 cfm).) 4. The isotopic release activity concentration is normalized to a skin dose rate of 3000 mrem /yr by multiplying by the following normalizing factor: F3=3000/pDRg 5. From the above, the alarm set point (see NOTE in Section 2.1.1), based on skin dose rate, can be calculated as follows: 8 S 10.8*F3

• CR (cpm) 43 where:

S high alarm set point that results in a skin dose rate S = 42 of less than 3000 mres/yr (cpm), normalization factor (unitiess), and F = 3 station ventilation exhaust noble gas radiation CR = fN monitor count rate (cpm). b The above procedure and format will be used to calculate the set point for RE-42 when the mechanical vacuum pump is in operation or during containment purge. Under these conditions, the short term atmospheric dispersion factor 3 at 366 meters NNE (3.60E-06 sec/m ) shall be used instead of the annual average value. 2.2.2 Main Condenser Of fgas System Ef fluent Monitor (RE-6SA,B) High Alarm Set Point The Main Condesner Offgas System Effluent Monitor has two chambers (65A, 65B) in series. Each chamber constitutes a separate independent output channel containing a detector composed of 3 GM tubes whose output are summed up. The 2 monitor set point will be based on a release rate which results in 0.1 MPC at the site boundary. The set point calculated shall be divided by a factor of 3 to account for the case when only one GM tube per chamber is functional. 1. During operation, a gaseous sample from the monitor will be taken and analyzed for isotopic composition and concentration, C. Before t will be calculated as noted in Section 2.2. startup, Cg /~N N BN1-11600.02-92 2.2-4 Revision 2 - September 1983

i SNPS-1 ODCM i I 2. At the time of sampling, the net count rate (excluding background), 2 CR (cpa), of the monitor will be recorded. Before startup, the estimatedcountrateCR(cpm)duetoconcentration,C[,iscalculated as: 6*(gg C*E) (cpm) CR = 10 g g where: E = detector efficiency (cpm / $1/cc) for RE-65A,B for t radionuclide, i, as provided in Figure 2.2-3. The generic linearity response for RE-65A,B is shown in Figure 2.2-4 3. The sum of the ratios of the released isotopic concentrations to MPC is normalized to 0.1 at the site boundary by multiplying by the following factor: 0.1 (t 1. gp )* V

• x/Q
• 3.0 where:

l V = Magn condenser offgas system ventilgtion flow rate (m /sec) (Maximum flow rate = 1.18E-02 m /sec (25 cfs).) dispersion factor at 366 O X/Q = annual average meteorologig)al sec/m due to releases via the

- Q meters NNE (6.6E-07 station ventilation exhaust point.

3.0 = Safety factor in case of 2 out of 3 GM tube failures. l2 I 4. From the above, the high alarm set point (see NOTE in Section 2.1.1) is' calculated as follows: S65 1 0.8

• F
• CR (cpa) 2.2.3 Main Condenser Air Ejector Monitor (RE-12A,B) Migh Alarm Set Point for Non-bypass Mode Operation (normal operation)

The Main Condenser Air Ejector Monitor System has two detectors looking at one chamber. The alarm will be set off by a signal from either 2 detector. 2.2.3.1 Initial Set Point for RE-124,B Non-bypass Mode Operation 1. Use the t=0 CE noble gas spectrum for off-gas system release rate prior to treatment (GE document 22A27038 Rev. 3 Table V), scale it to i the Shoreham RETS (3.11.2.7) limit of 244,000 tCi/sec at 30 minutes decay by multiplying by 2.44. Divide it by the air ejector flow rate ( (1.05E+06 cc/sec) to obtain the limiting concentrations C ( Wi/cc) of t each radioisotope 1. I BN1-11600.02 2.2-5 Revision 2 - September 1983 l 4 l l l l ~u. .u

SNPS-1 ODCM Q 2. Using _ the isotopic concentrations, Cg ( Wi/cc), defined above and the .() effective gamma energy per disintegration, Egg (MEV/ dis) calculate the specific gamma activity, Agg(MEV/cc-sec), for the i-th isotope in each of the following gamma ray energy bins: 0-0.4, 0.4-0.8, 0.8-1.3, 1.3-1.7, 1.7-2.2, 2.2-2.5, and 2.5-3.5 (MEV). Thus: A11=K*E

• C g

g where E is the total gamma energy (MEV) emitted per disintegration tg of the.1-th isotope by gamma rays belogging to the A-th energy bin defined above. The f actor K = 3.7 x 10 (dis /sec/ Wi) is introduced for unit conversion. The total specific - gamma activity, A g (MEV/cc-sec), for each gauna -energy bin, A, is calculated by summing the specific gamma activity, Agg, for bin 1, over all isotopes. AE"i1 it. 3. Using the response curve for RE-12A,8 given in Figure 2.2-5, calculate the dose rate. The generic linearity response curve for RE-12A,B is shown in Figure 2.2-6. 2 'N 7 DR = [ CF

• A (arad/hr) g g

A=1 i where: the ef ficiency ( g"g ) at the S-th energy group is 4. The high alarm set point (see NOTE in Section - 2.1.1, but note the background unit is in.arad/hr) for RE-12A,B in the non-bypass mode will be: (mrad /hr) S12 1 0.8

• DR

2.2.3.2 Subsequent Adjustments of Set Points for RE-12A,B in Non-bypass Mode Operation 1.

During operation, a gaseous sample from the monitor will be taken and analyzed for noble gases isotopic composition and concentration, C, g (pCi/cc) at t=30 minutes. Before startup, Cg will be calculated as noted in Section 2.2. r t

2. At the time of sampling, the net dose rate reading (excluding 2

background) of the monitor will be recorded, DR (ares /hr). O BN1-11600.02-92 2.2-6 Revision 2 - September 1983 .. -... _, _., _ _., _ _ -. _. _ _ _ _ _ _, ~.. _. _ _ _, _ _,, _ _. _ - _,,.. _... _... _ _.

SNPS-1 ODCM C, are summed and 3. The isotopic release activity concentrations. t multiplied by the air ejector flow rate, V (cc/sec) to obtain the s noble gas release rate, Wi/sec. 4. The release rate in step 3 is normalized to the RETS Section 3.11.2.7 release limit of 2.44E+05 ICi/sec at t=30 minutes as follows: 2.44E+0S 7, (p C )

• V g

5. From above, the high alarm set point (see NOTE in Section 2.1.1, but note the background is in arad/hr) based on a release rate of 2.44E+05 pCi/see at t=30 minutes can be caleclated as follows: S1210.8

• F
• DR (mrad /hr) 2.2.4 Main Condenser Air Ejector Monitor (RE-12A,B) High Alarm Set point for Bypass Mode Operation 2.2.4.1 Initial Set Point for RE-124,B in Bypass Mode Operation 1.

Same as steps 1, 2, and 3 in Section 2.2.3.1 l2 corresponding to the above 2. The off-site total body dose rate DT concentration is calculated as: D = 10~0

• X/Q
• V * ( DFB *C )

T g and the beta and ganuna skin dose rate is calculated as : D, = 10-0

• X/Q
• V * (

K

• C) sb g

where:

• predicted total body dose rate (mrem /yr)

DT D, = predicted beta and gamma skin dose rate (arem/yr) 366 meters X/Q = annual average atmosp)heric dispersion f actor at NNE (6.6E-07 sec/m due to releases via the station ventilation exhaust point V = Air ejector exhaust flow rate (cc/sec) (Maximum exhaust flow rate is 1.05E+06 cc/sec) total body dose rate conversion factor (*#**

1. ) from DFB t = Table 2.2-1 pCi/m b im = skin dose rate conversion factor (*#**
2. ) from Table 2.2-1 pCi/m BN1-11600.02-92 2.2-7 Revision 2 - September 1983

.. -= ~ l l SNFS-1 ODCM l D 3. The normalizing factor F is chosen to be the smaller of the two (to comply with 25% of the RETS (3.11.2.1) dose rate 11mit): , 125 rarets/yr_ p T D.7 750 inres/yr .p S D3 F = the smaller >f FT or F3 (unitiess) 4. The high alaria set point (see NOTE in Section 2.1.1, but note the background is in mead /hr) RE-12A,8 in bypass mode 'is set at: S12 < 0.8* F

• DR (mrad /hr) 2.2.4.2 Subsequent Adjustments of Set Points for RE-12A,8 in Bypass Mode Operatton 1.

A gaseous sample from the monitor will be taken and analyzed for isotopic composition and concentration, C1 ($1/cc) 2. At the time of sampling, the net dose rate reading, DR (mrad /hr), of 2 the monitor will be recorded. 3. Follow procedures 3, 4, and 5 of Section 2.2.4.1 to get the high alarm set point for RE-12A,8 in bypass mode. I J J 4 BN1-11600.02-92 2.2-8' Revision 2 - September 1983

O O O SNPS-1 ODCM TABLE 2.2-1 DOSE FACTORS FOR EXPOSURE TO A SEMI-INFINITE CLOUD OF NOBLE GASES Radio-(4) (5) 8-Air (I) (DFb ) GFSkin(2) (DFS ) 1" Air (I) (DFH ) 1F ody(2) (DFB ) B g Ski Dose (2) Skin D se (2) g g nuclide t_ Kr-83m 2.88E-04(3) 1.93E-05 7.56E-08 1.5E-05 2.1-05 Kr-85a 1.97E-03 1.46E-03 1.23E-03 1.17E-03 2.4E-03 2.8-03 4 } Kr-85 1.95E-03 1.34E-03 1.72E-05 1.61E-05 1.4E-03 1.4-03 l Kr-87 1.03E-02 9.73E-03 6.17E-03 5.92E-03 1.5E-02 1.7-02 i Kr-88 2.93E-03 2.37E-03 1.52E-02 1.47E-02 1.4E-02 1.9-02 i i Kr-89 1.06E-02 1.01E-02 1.73E-02 1.66E-02 2.4E-02 2.9-02 i Kr-90 7.83E-03 7.29E-03 1.63E-02 1.56E-02 2.0E-02 2.5-02 Ke-131m 1.11E-03 4.76E-04 1.56E-04 9.15E-05 6.0E-04 6.5-04 Xe-133m 1.48E-03 9.94E-04 3.27E-04 2.51E-04 1.2E-03 1.4-03 Xe-133 1.05E-03 3.06E-04 3.53E-04 2.94E-04 5.8E-04 7.0-04 Xe-135m 7.39E-04 7.11E-04 3.36E-03 3.12E-03 3.3E-03 4.4-03 Xe-135 2.46E-03 1.86E-03 1.92E-03 1.81E-03 3.4E-03 4.0-03 Xe-137 1.27E-02 1.22E-02 1.51E-03 1.42E-03 1.3E-02 1.4-02 4 l t BN1-11600.02-93 1 of 2 Revision 1 - August 1983

i i .SNPS-1 ODCM 4 TABLE 2.2-1-(CONT'D) J' (4) K,g (5) Radio-Kai S, Air (I) (DFb ) S-Skin (2) (DFS ) l' Air (I) (DFH ) y -Body (2) (DFB ) Skin Dose (2) Skin D se (2) t g g g nuclide l-Xe-138 4.75E-03 4.13E 9.21E-03 8.83E-03 1.1E-02 1.4-02 A'r-41 3.28E-03 2.69E-03 9.30E 8.84E-03 9.9E-03 1.3-02 4 4 (1) mead-a i -pCi-yr 3 a (2) arem-m l pCi-yr-i (3) 2.888 2.88

• 10-4 (4) K,1 = (0.7
• 1.11
• DFH ) + DFS g

g (5) gsim = (1.11'* DFH ) + DFSg g i 4 I i i i I i i BN1-11600.02-93 i 2 of 2 j Revision 1 - August 1983 1 )

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4 u. ,y y p 10 10' lo 10* s ENERGY (KEV)-+ SOURCE: FINAL REPORT ON RADIONUCLIDE SPECIFIC FIGURE 2 2 -1 NUCLEAR DETECTOR RESPONSE DETERMINATIONS TO N M C

• DETECTOR RE-42 Es'us, $i'"8U8

'"8 EFFICIENCY VS. AVERAGE BETA ENERGY E SHOREHAM NUCLEAR POWER STATION-UNIT I ~ ~ ~ CALCULATED CURVE OFFSITE DOSE CALCULATION MANUAL CALIBRATION CURVE M FIELD DATA TO BE QA VERIFIED REVISION 1 - AUGUST 1983

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g. m.

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:=fr O

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== t*

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.,.y. e ..r ..g ,y. p +... m u . 4. .a. . ~ ..9 +-+4 ~ m+ --+- t* -r 4 f + A *~ + t + s -M+ + 10 10 10* 10 10" 3 AVERAGE BETA ENERGY (KEV) SOURCE: GE MEM0(Pearson)-PROCESS RADIATION SAMPLING SENSITIVITIES. JUNE 26,1977 ( R EV.1 ) GENERIC CAllBRATION CURVE FIGURE 2.2-3 DETECTORS RE-65 A,B GENERIC EFFICIENCY VS. AVER AGE BETA ENERGY / h SHOREH AM NUCLEAR POWER STATION-UNIT 1 \\ l V OFFSITE DOSE CALCULATION MANUAL REVISION 1-AUGUST 1983

4 m r .. =;:.; 10 e l t i .-i. I i ry n i t \\ l t i 4_._g-q _..- .__-4 4 %/ a.._._ i 4_.--. .L.--.. _L..._..-.._ ...j. f __g._._ $..$,0 b l l )* I IO : r f__ 4_._._/ : i i i 1 i l l I /1 l i 2 ., p 4 -..y.+ ..f 9 ./.{

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-p_p _ i.p -m- . 9_4-.. ~ N 4 .. _ 4 4 .. _...__._{.ir-85 ) ' ~ d-~Y ~ ~ ~ X e -133 L-_. - 1L i n) [ l u!._ . 41_ f'. [ / l l i o 4,__ _-l ( 2 O lg8-3 i r i v A f=--- q_.r i Q i i 4 i f _.Lh... + -I-m.... f j _y.]...___ {_ .. j[.i. q.. p - y-- 7.--- a_. m h---- - h-- [..L. . [.+ )f r-f !. /,. / I' I l i i s' J'- r n .r i I I ( .J I I t i t i I-if i f , i j [ I ,i I it J'j __.y ... 3 .L.. p y y 4 ( hf-f M -~~ ~ ljj! 01 1 O 'i: ,il- 'i! m.: (( $1 _1. j{:4. jj:].::![iiEi? rr-7 10_s ,o-S g9 IO'3 10~2 10-1 4 CONCENTR ATION (pCl/cc) SOURCE LILCO DOCUMENT No. CS.630.OO5 l -- IDEAL CURVE GENERIC CAllBRATION CURVE I FIGURE 2.2-4 GENERIC LINEARITY RESPONSE CURVE c ) FOR DETECTORS RE-65 A, B V SHOREHAM NUCLEAR POWE9 STATION-UNIT I 0FFSITE DOSE CALCULATION MANUAL REVISION 1 - AUGUST 1983

b (V b =.

r

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w I l. .._u.__ 4 [_ _ }._. t'- i l-1 - -t- - -- -i - --- j --- -t ---- 1.5, O 1.0 2.0 3.0 4.0 GAMMA ENERGY (MEV) s FIGURE 2.2-5 DETECTORS RE-12A,B EFFICIENCY VS. GAMMA ENERGY SOURCES: SHOREHAM NUCLCl,!? PNFJ4 STATION-UNIT 1

1. LILCO STARTUP PACKAGE No. CS.630.OO4 OFFSITE DOSE C ALCULATION M ANUAL

2. SWEC CALCULATION II6 00.02 - S N P S U R B P

• GAMMA ENERGY BINS (CF )

I REVISION 1-AUGUST 1983

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~ ~ g i w i m ..h.. d-- Y' nrh q -g- .p._.. . _4 .... _ - p j. .._q__ .}. ... 4 4 E i i 1 .-.i_. . / L... I i i j i q. 2 /! i 4 10 - i . / i w 2 ._..__../ m' _g O i t / i .l I i s'f._._ ...( z i f ... + _...,.g. ...}. _ m_ -..-._i_4-_ h. _._. 9 _ j _.._.. 7_ ~ 10 '- --.[_ $ _1 . }. I d b ' f.._ . l. I l__ L !~ Al l l i } l, l. [ s j ';-r: .i / l l j 7 i 1 1i t/ I e i t i i w-4-;/ ~-y. y .4 3 ..y. [ j g ., L. i_q.. . _ [_' _. m / F j i _y/; h. N 3 .i i i. e e 1 .3 t !!!.2 p:1 i q.p.., .: I 2 4 v i 10 to 10' 10 10~ l SOURCEe LILCO DOCUMENT No. CS.630.004 --- IDE AL CURVE e ACTUAL DATA FIGURE 2.2-6 GENERIC LINE ARITY CURVE FOR DETECTORS RE-12 A,B SHOREHAM NUCLEAR POWER STATION-UNIT I OFFSITE DOSE CALCULATION MANUAL REVISION 1-AUGUST 1983

SNPSel ODCM SECTION 3 O DOSE CALCULATION METHODS 'Q 'Ihis section presents the calculationel specifics required to demonstrate compliance with the following Radiological Effinent Technical Specifications (RETS) sections: 3.11.1.2 - Liquid Effluent Dose Calculation 3.11.i.3 - Operation of Liquid Radwaste Treatment System 3.11.2.1 - Gaseous Effluent Dose Rate 3.11.2.2 - Nchle Gas Air Dose 3.11.2.3 - Gaseous Effluent Dose From Radioiodines, Radioactive Materials In Particulate Form 3.11.2.5 - Operation of Ventilation Exhaust Treatment System Calculation methods are based on the equation and calculational methods described in Regulatory Guide 1.109 " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I".

• 1Vo methods are provided for each analysis.

The first method is the method used by the computerized radiation monit, "hg system. Method 2 is 'a backup hand calculational method to be used only af the computer is not functional. OV i 'kJ BN1-11600.02-92 3.0-1 Revision 1 - August 1983

SNPS-1 ODCM -^ 3.1 LIQUID EFFLUENT, DOSE CALCULATION U To comply with Section 3.11.1.2 of the RETS, the liquid effluents released into Long Island Sound (see Figure 3.1-1) shall be limited: 1. During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 meen to any organ. 2. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 meen to any organ. . The liquid radwaste system model is shown in Figure 3.1-2. 3.1.1 Method 1: (Computerized Method) The equations which follow are used by the computer sof tware to calculate the offsite doses due to release of liquid radwaste. For this dose calculation the actual concentration to be discharged by isotope, the total volume of liquid to be discharged, and the number of circulating water pumps running, supplied by the operator, shall be used. The software computes the isotopic releases by multiplying the lab measurements by the volume of the liquid to be released: 3.785 x 10-3 V qi Q1 = where: total inventory of isotope i in the liquid to be released (Ci) Q1 = qi concentration of isotope i. in the liquid to be discharged (as = measured in laboratory) (pCi/cc) V ' volume of liquid to be discharged (gallons) = 3.785 x 10-3 = [(Ci/pci) (cc/ gal)] The dose equations which follow are from Regulatory Guide 1.109, with minor modifications. They are employed for the computation of dose from any single batch discharge. Weekly and quarterly cumulative doses are also calculated and stored in data files for reporting. ^ (a) Organ Dose due to Ingestion of Saltwater Fish ing ish is Hs = 0.344 Uap (gjg) g 9 g DFI e R i iP ija ja part+I where: R "E =. dose to organ j of individual in age group a due to 3" ingestion of fish contaminated with particulates and ratio-iodines (arem) (Ref. Reg. Guide 1.109, with the following special values: O BN1-11600.02 3.1-1 Revision 1 - August 1983 1p-w e 9.. ..v--. e y-m ,y a 9,-w.v-.u*i----om gy -*ewre --y-wF y

• is 3+gm.--

w---e w-T+-to* -in~-a ty--e m Mfme - mwas---p ee

i SNPS-1 ODCM t J t liquid effluent) is represented by product e F (flow' rate og/sec], C'I K* F ft where K is the number of pumps ' opera $1Sg a[nd Fpump is the flow rate per unit pump 3 i 'e Fpo,p = 1.435x105 [gpn] = 319.7 [ft /sec] e 4 (mixing : ratio (reciprocal of dilution f actor) at the j p6 int-of exposure) = 0.1 I eD aipj (dose f actor) = DFIg), (see below) transit time required for nuclides to reach the point of e(xposure) = 24 [hr] (see pg st 1.109-12 of the regulatory guide) fis U = fish consumption rate by individual in age group a [kg/yr] aP (from Table E-5 of the Guide, for maximum individual) K = number of pumps operating (circulating water system) .Qg- = total activity of isotope i released [Ci], f rom above fis e B = Bioaccumulation factor for saltwater fish [(pCi/kg)/ ip (pCi/ liter)] (from Table A-1 of the Guide) DFI ), = dose. conversion ' f actor for nuclide i to organ j of g individual in age, group. a.due to ingestion [arem/pCi 2 ingested] (from Tables E-11 through E-14 of the Guide) = radionuclide decay constant [hr-I] A g. 0.344 =.1100; M /F = 1100 x 0.1 / 319.7 p pump .part+1 = 68 particulates and 5 iodines in the summation sign- . (b) Organ dose due to ingestion of saltwater invertebrate i ~ . R ",3 '"# ' = 0.344 U,"*(1/K) I Q.B " DFI e i p g where: f E R = dose. to organ j of individual in age group a due to the d" ingestion of saltwater. invertebrate. contaminated with } radioactive particulates and iodines [ ares] (Ref. : Reg. } Guide ~ 1.109 Eq. A-3 with the special values identified in the fish-ingestion equation above) I 1 t. BN1-11600.02-92 3.1-2 -Revision 1 - August 1983 1 I 1 .~. .-...,_w.,....,._.,._,_..__._,_____.__......,_._..._......,,._,_,______.,..,...__..,__..,

SNPS-1 ODCM B "# = Bioaccumulation f actor f or saltwater invertebrate [(pCi/kg)/ iP ( (pCi/ liter)] (from Table A-1 of the guide) U "# = invertebrate consumption rate by individual in age group a ap~ -[kg/yr] (from Table E-5 of the

Guida, for maximum individual)

(c) Total body dose f rom shoreline deposits R* =0.496U"[p"*(1/K) il ( ) I Q DFG a t part+1 i where: shore R = total body dose to individual in age group a from shoreline deposits [ mrem] (Ref.: Reg. Guide 1.109 Eq. A-7 with the following special values: effluent) is represented by the

• F(flow rate of liquy/sec],

[f t where K is the number of product K F operating pumps and F,,p is the flow rate per unit pump p 3 pump " 1.435 x 105 [gpm] = 319.7 [f t /sec] eF e 4 (mixing ratio) = 0.1 e W (shore-width f actor that describes the geometry of the 0.5 f or ocean site (from Table A-2 of the exposure) = guide) p (transit time f rom source to shoreline) = 0 (see Reg. et Guide pg 1.109-69, for Eq. A-7) 0.693/(24A ) where (radionuclide half lif e, days) .e Tg = 1 0.693 = log,2 and At is the decay constant in [hr-I] e D,ipj = DFGil (see below) U* = shoreline exposure time for individual in age group a ap [hr/yr] (from Table E-5 of the

Guide, for maximum individual)-

R = number of pumps operating (circulating water system) 'Q = total activity of. isotope i released [Ci], f rom above 1 7 i sO BN1-11600.02 3.1-3 Revision 1 - August 1983 V: . -,_ _, -__,. _.., _, _ _, ~. _.. _ _ _ _... _, _,, _. _.,,..... _. _

i SNPS-1 ODCM contaminated DFG = total body conversion factor fog standing on gt x ground (shore) -[(area /hr)/(pCi/m )] (from Table E-6 of the guide) = time period oger which accumulation is evaluated (15 years, tb or 1.314 x 10 hours ) 0.496 = 110,000 M W (T A )/ F p g1 pump = 110,000 x 0.1' x 0.5 x (0.693/24)/ 319.7 part+1- = 68 particulates and 5 iodines in the summation sign (d) Skin dose from shoreline deposits R = 0.496 U"

• • (1/k)p,[t,g-Q DFG g

i2 A where: ahore 4 R = skin -dose to individual in age group a from shoreline shn,a deposits [ mrem]; (Ref.: Reg. Guide 1.109 Eq. A-7 with the special values listed for the total body dos'e) on contaminated = skin dose conversion factor fog standing DFGi2-ground (shore) [(area /hr)/(pCi/m )] (from Table E-6 of the Guide) 'u Other parameters are as defined earlier for the total body dose from shoreline deposits. (e). Total doses The individual dose components described in items (a), (b), (c), and (d) above are sunm.ed in the following way for the computation of total doses: R = R "E + R "E ja ja ja DE fish + R ng, iny shore +R R -R ub,a wb a wb a wb a ehore R =R skin,a skin,a g .1-11...,2 3.1 4 .ev1s,on 1.. g.st 1,,,

SNPS-1 ODCM where: R, = total dose to organ j (exclusive of the total body) of j individual in age group a due to the ingestion of fish and invertebrate (arem) R = total dose to the total body of individual in age group a wb a due to the ingestion of fish and invertebrates, and direct radiation from shoreline deposits and skin,a = t tal dose to the skin of an individual in age group a from R shoreline deposits (arem). 3.1.2 Method 2: (Backup Method) The dose contributions for the total release period shall be calculated for all radionuclides identified in liquid effluents released into Long Island Sound using the following expression: N M i[g[A gjl At C F] O.11 D = iT g iL where: '] the cumulative dose or dose commitment to the total body or an D = / 7 organ from the liquid effluents for the total release H period I Atg (arem), g,g g the length of the ith release period over which C and Fg are At = 1g averaged for all liquid released (minutes), C the average concentration of radionuclide C in undiluted = 1g 1 liquid effluent during release period At from any liquid g release (pC1/cc). 17 the site-related ingestion dose or dose commitment factor to A = the total body or any organ for each identified principal gamma and beta emitter listed in Table 3.1-7 (arem/ min per pCi/cc), see Appendix A for derivation F the near field average ' dilution factor for C during any = g 1 g, liquid effluent release, defined as the undiluted liquid waste flow rate during release divided by the product of the I circulating water flow rate times 8.85 *(N/4). (8.85 is the near field mixing factor for the mixing of the diffuser discharge into Long Island Sound based on 4 operating recirculating pumps. N is the number of recirculating pumps operating during discharge.) ' %,/ BN1-11600.02-92 3.1-5 Revision 1 - August 1983

SNPS-1 ODCM p The total dose from liquid effluents from all discharges, DTotal, is: DTotal.= DTD+DtR+DTH+D73 + D7p where: D Dose contribution from discharge waste sample tanks as = TD calculated in Equation 3.1-1 TR Dose contribution from recovery sample tanks as calculated in D = Equation 3.1-1 Dose contribution from RHR heat exchanger, service water as D = tH calculated in Equation 3.1-1 D73 Dose contribution from reactor building salt water drain tank = as calculated in Equation 3.1-1 D Dose contribution from yard piping drain sump at calculated in = 7p Equation 3.1-1. If the calculated total dose exceeds the limit specified in Section 3.1, consult RETS Section 3.11.1.2. i -[ BN1-11600.02-92 3.1-6 Revision 1 - August 1983 ( i ..,...m ,,,m,,,.,., _,,. _.., _ _, _.,,,,,,,... y,,,_,_ ,,.,,,,,m,,-, ..._..w

~. i? SNPS-1 ODCM i TABLE 3.1-1 BIOACCUMUIATION FACTORS TO BE USED IN THE ASSENCE' 0F SITE-SPECIFIC DATA (pCi/kg per pCi/ liter)l1) c 4 Saltwater Element Fish Invertebrate J H 9.0E-01 9.3E-01 C-1.8E+03 1.4E+03 Na 6.7E-02 1.9E-01 2 P 2.9E+04 3.0E+04 i Cr 4.0E+02 2.0E+03 -th 5.5E+02 4.0E+02 Fe - 3.0E+03 2.0E+04 Co 1.0E+02 1.0E+03 Ni 1.0E+02 2.5E+02 Cu 6.7E+02 1.7E+03 2h 2.0E+03 5.0E+04 i Br 1.5E-02 3.1E+00 Rb 8.3E+00 . 1.7E+01 Sr 2.0E+00 2.0E+01 Y 2.SE+01 1.0E+03-2r - 2.0E+02 8.0E+01 l' .Nb 3.0E+04 1.0E+02 i. No' 1.0E+01 1.0E+01 Tc 1.0E+01 5.0E+01 [- Ru 3.0E+00' 1.0E+03 Rh 1.0E+01 2.0E+03 l Te(2) 1.0E+01 1.0E+02 1 1.0E+01 5.0E+01 Cs 4.0E+01 2.5E+01 .Ba~ 1.0E+01' 1.0E+02 La 2.5E+01 1.0E+03 'Ce '1.0E+01- - 6.0E+02 i Pr 2.5E+01 1.0E+03 Nd 2.5E+01 1.0E+03 i ~W 3.0E+01 3.0E+01 Np -1.0E+01 1.0E+01 (I) Values in Table 3.1-1-are taken from Reference 6 of Regulatory l. Guide 1.109, Rev. 1, Oct. 1977 unless otherwise indicated. ? (2) Data taken from Reference 8 of Regulatory Guide 1.109, Rev. 1, Oct. 1977. BN1-11600.02-112 1 of 1 Revision 1 - August 1983 ' O 4 + .y e - = ,...d,. ...c.,,., ,-..,,s , ry nw-.--..eM++w,-+, to wi e w -+-, -, we r-w-v,w---wmg-,=-r,- .m y ,-+--m v s -e-w,:-,--ev+c-w,v-,e-' - w + -, -- r-w e t v v

rT m ( l 1 l i Q/ Q SNPS-1 ODCM TABLE 3.1-2 INGESTION DOSE FACTORS FOR ADULTS (arem per WCi ingested) Radio-nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 No Data 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 C-14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 Na-76 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 P-32 1.93E-04 1.20E-05 7.46E-06 No Data No Data No Data 2.17E-05 Cr-51 No Data No Data 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 Mn-54 No Data 4.57E-06 8.72E-07 No Data 1.36E-06 No Data 1.40E-05 Mn-56 No Data 1.15E-07 2.04E-08 No Data 1.46E-07 No Data 3.67E-06 Fe-55 2.75E-06 1.90E-06 4.43E-07 No Data No Data 1.06E-06 1.09E-06 L Fe-59 4.34E-06 1.02E-05 3.91E-06 No Data No Data 2.85E-06 3.40E-05 Co-58 No Data 7.45E-07 1.67E-06 No Data No Data No Data 1.51E-05 Co-60 No Data 2.14E-06 4.72E-06 No Data No Data No Data 4.02E-05 Ni-63 1.30E-04 9.01E-06 4.36E-06 No Data No Data No Data 1.88E-06 Ni-65 5.28E-07 6.86E-08 3.13E-03 No Data No Data No Data 1.74E-06 Cu-64 No Data 8.33E-08 3.91E-08 No Data 2.10E-07 No Data 7.10E-06 1 Zn-65 4.84E-06

1. 54F.-05 6.96E-06 No Data 1.03E-05 No Data 9.70E-06 Zn-69 1.03E-08 1.97E-08 1.37E-09 No bata 1.28E-08 No Data 2.96E-09 i

Br-83 .No Data No Data 4.02E-08 No Data No Data No Data 5.79E-08 i Br-84 No Data No Data 5.21E-08 No Data No Data No Data 4.09E-13 Br-85 No Data No Data 2.14E-09 No Data No Data No Data <1.00E-24 3 Rb-86 No Data 2.11E-05 9.83E-06 No Data-No Data No Data 4.16E-06 Rb-88 No Data 6.05E-08 3.21E-08 No Data No Data No Data 8.36E-19 Rb-89 No Data 4.01E-08 2.82E-08 No Data No Data No Data 2.33E-21 St-89 3.08E-04 No Data 8.84E-06 No Data No Data No Data 4.94E-05 Sr-90 7.58E-03 No Data 1.86E-03 No Data No Data No Data 2.19E-04 Sr-91 5.67E-06 No Data 2.29E-07 No Data No Data No Data 2.70E-05 t Sr-92 2.15E-06 No Data 9.30E-08 No Data No Data No Data 4.26E-05 Y-90 9.62E-09 No Data 2.58E-10 No Data No Data No Data 1.02E-04 Y-91m 9.09E-11 No Data 3.52E-12 No Data No Data No Data 2.67E-10 Y-91 1.41E-07 No Data 3.77E-09 No Data No Data No Data 7.76E-05 ) Y-92 8.45E-10 No Data 2.47E-11 No Data No Data No Data 1.48E-05 Y-93 2.68E-09 No Data 7.40E-11 No Data No Data No Data 8.50E-05 Revision 1 - August 1983 BN1-11600.02-94 1 of 3 1 4

SNPS-1 ODCM TABLE-3.1-2 (CONT'D) ~ Radio-nuclide Bone ~ Liver T. Body. Thyroid Udaey M ~GI-LLI Zr-95 3.04E-08 9.75E-09 6.60E-09 LNo Data 1.53E-08 No Data 3.09E-05 Zr-97' ~1.68E-09 3.39E-10 1.55E-10 No Data 5.12E-10 No Data '1.05E-04 =Nb-95 6.22E-09 3.46E-09 1.86E-09 No Data 3.42E-09 No Data. 2.10E Mo-99 No Data .4.31E-06 8.20E-07 No Data 19.76E-06 No Data 9.99E-06 Tc-993 .2.47E-10 6.98E-10 8.89E-09 No Data 1.06E-08 3.42E-10 4.13E-07 Tc-101 2.54E-10' 3.66E-10 3.59E-09 No Data 6.59E-09 1.87E-10 1.10E-21 Ru-103 1.85E-07 No Data 7.97E-08 No Data 7.06E.No Data-2.16E-05 Ru-105 1.54E-08 No Data 6.08E-09 No Data 1.99E-07 'No Data 9.42E-06 Ru-106' 2.75E-06 No Data 3.48E-07 No Data 5.31E-06 No Data 1.78E-04 Ag-110m .1.60E-07 1.48E-07 8.79E-08 No Data 2.91E No Data 6.04E-05 Te-125m 2.68E-06 '9.71E-07 3.59E-07 8.06E-07 1.09E-05 No Data 1.07E-05 Te-127m 6.77E-06' 2.42E-06. 8.25E-07 1.73E-06 2.75E-05. No Data 2.27E-05 Te-127 1.10E-07 3.95E-08 -2.38E 8.15E-08 4.48E-07 No Data. 8.68E-06 Te-129m 1.15E-05 4.29E-08 1.82E-06 13.95E-06 4.80E-05 No Data 5.79E-05 Te-129 .3.14E-08 1.18E-08 7.65E-09 .2.41E-08 1.32E-07 No Data 2.37E-08 Te-131m 1.73E-06 8.46E 7.05E-07 1.34E-06 8.57E-06 No Data 8.40E-05 -Te-131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 No Data L2.79E-09 Te-132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 No Data 7.71E-05 I-130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 No Data 1.92E-06 I-131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 No Data 1.57E-06 I-132 2.03E-07 5.43E-07. 1.90E-07 1.90E-C5 8.65E-07 No Data 1.02E-07 I-133 1.42E-06 2.47E-06 7.53E-07 -3.63E-04 4.31E-06 No Data 2.22E-06 I-134 1.06E-07 2.88E-07 -1.03E-07 4.99E-06 4.58E-07 No Data 2.51E-10 1-135 4.43E-07 1.16E-06 4.28E-07 -7.65E-05 1.86E-06 No Data 1.31E-06 Cs-134 6.22E-05 1.48E-04. 1.21E-04 No Data 4.79E-05 1.59E-05 2.59E-06 Cs-136 6.51E-06 2.57E-05 1.85E-05 No Data 1.43E-05 1.96E-06 2.92E-06 Cs-137 7.97E-05 1.09E-04 7.14E-05 No Data 3.70E-05 1.23E-05 2.11E-06 Cs-138 5.52E-08 1.09E-07 5.40E-08 No Data 8.01E-08 7.91E-09 4.65E-13 Ba-139 9.70E-08 6.91E-11 2.84E-09 No Data 6.46E-11 3.92E-11 1.72E-07 Ba-140 2.03E-05 2.55E-08 1.33E-06 No Data 8.67E-09 1.46E-08. 4.18E-05 Ba-141 4.71E-08 3.56E-11 1.59E-09 No Data 3.31E-11 2.02E-11 2.22E-17 Ba-142 2.13E-08 2.19E-11 1.34E-09 No Data 1.85E-11 1.24E-11 3.00E-26; La-140 2.50E-09 1.26E-09 3.33E-10 No Data No Data No Data

9.25E-05 La-142 1.28E-10 5.82E-11 1.45E-11 No Data No Data No Data 4.25E-07 Revision 1 - August 1983 BN1-11600.02-94 2 of 3 '

~ SNPS-1 ODCM TABLE 3.1-2 (CONT'D) 1 Radio-nuclide Bone Ilver T. Body Thyroid Kidney Lug [ GI-LLI Ce-141 9.36E-09 '6.33E-09 7.18E-10 No Data 2.94E-09 No Data 2.42E-05 Ce-143 1.65E-09 1.22E-06 1.35E-10 No Data 5.37E-10 No Data 4.56E-05 Ce-144 4.88E-07 2.04E-07 2.62E-08 No Data 1.21E-07 No Data 1.65E-04 Pr-143 9.20E-09 3.69E-09 4.56E-10 No Data 2.13E-09 No Data 4.03E-05 2 Pr-144 3.01E-11 1.25E-11 1.53E-12 No Data 7.05E-12 No Data 4.33E-18 Nd-147 6.29E-09 7.27E-09 4.35E-10 No Data 4.25E-09 No Data 3.49E-05 L l W-187 1.03E-07 8.61E-08 3.01E-08 No Data No Data No Data 2.82E-05 i Np-239 1.19E-09 1.17E-10 6.45E-11 No Data 3.65E-10 No Data 2.40E-05 i t i I t i l t i Revision 1 - August 1983 i 3 of 3 i BN1-11600.02-94 l i i

O p .g ) O N.Y SNPS-1 ODCM -TABLE 3.1-3 INGESTION DOSE FACTORS FOR TEENAGER (arem per WCi ingested) Radio-nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 No Data 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 C-14 4.06E-06 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 Na-24 2.30E-05 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 P-32 2.76E-04 1.71E-05 1.07E-05 No Data No Data No Data 2.32E-05 Cr-51 No Data No Data 3.60E-09 2.00E-09 7.89E-10 5.14E-09 6.05E-07 Mn-54 No Data 5.90E-06 1.17E-06 No Data 1.76E-06 No Data 1.21E-05 Mn-56 No Data 1.58E-07 2.81E-08 No Data 2.00E-07 No Data 1.04E-05 Fe-55 3.78E-06 2.08E-06 6.25E-07 No Data No Data 1.70E-06 1.16E-06 Fe-59 5.87E-06 1.37E-05 5.29E-06 No Data No Data 4.32E-06 3.24E-05 i Co-58 No Data 9.72E-07 2.24E-06 No Data No Data No Data 1.34E-05 l Co-60 No Data 2.81E-06 6.33E-06 No Data No Data No Data 3.66E-05 Ni-63 1.77E-04 1.25E-05 6.00E-06 No Data No Data No Data 1.99E-06 Ni-65 7.49E-07 9.57E-08 4.36E-08 No Data No Data No Data 5.19E-06 Cu-64 No Data 1.15E-07 5.41E-08 No Data 2.91E-07 No Data 8.92E-06 Zn-65 5.76E-06 2.00E-05 9.33E-06 No Data 1.23E-05 No Data. 8.47E-06 Zn-69 1.47E-08 2.80E-08 1.96E-09 No Data 1.83E-08 No Data 5.16E-08 Br-83 No Data No Data 5.74E-08 No Data No Data No Data <1.00E-24 Br-84 No Data No Data 7.22E-08 No Data No Data No Data <1.00E-24 Br-85 No Data No Data 3.05E-09 No Data No Data No Data <1.00E-24 Rb-86 No Data 2.98E-05 1.40E-05 No Data No Data No Data 4.41E-06 Rb-88 No Data 8.92E-08 4.54E-08 No Data No Data No Data 7.30E-15 Rb-89 No Data 5.50E-09 3.89E-08 No Data No Data No Data 8.43E-17 Sr-89 4.40E-04 No Data 1.26E-05 No Data No Data No Data 5.24E-05 Sr-90 8.30E-03 No Data 2.09E-03 No Data No Data No Data 2.33E-04 Sr-91 8.07E-06 No Data 3.21E-07 No Data No Data No Data 3.66E-05 Sr-92 3.05E-06 No Data 1.30E-07 No Data No Data No Data 7.77E-05 Y-90 1.37E-08 No Data 3.69E-10 No Data No Data No Data 1.13E-04 Y-91m 1.29E-10 No Data 4.93E-12 No Data No Data No Data 6.09E-09 Y-91 2.01E-07 No Data 5.39E-09 No Data No Data No Data 8.24E-05 i Y-92 1.21E-09 No Data 3.50E-11 No Data No Data No Data 3.32E-05 Y-93 3.83E-09 No Data 1.05E-10 No Daia No Data No Data 1.17E-04 Revision 1 - August 1983 1 of 3 BN1-11600.02-95

O O O SNPS-1 ODCM TABLE 3.1-3 (CONT'D) Radio-nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Zr-95 .4.12E-08 1.30E-08 8.94E-09 No Data 1.01E-08 No Data 3.00E-05 Zr-97 2.37E-09 4.69E-10 2.16E-10 No Data 7.11E-10 No Data 1.27E-04 Nb-95 8.22E-09 4.56E-09 2.51E-09 No Data 4.42E-09 No Data 1.95E-05 Mo-99 No Data 6.03E-06 1.15E-06 No Data 1.38E-05 No Data 1.08E-05 Tc-99m 3.32E-10 9.26E-10 1.20E-08 No Data 1.38E-08 5.14E-10 6.08E-07 Tc-101 3.60E-10 5.12E-10 5.03E-09 No Data 9.26E-09 3.12E-10 8.75E-17 Ra-103 2.55E-07 No Data 1.09E-07 No Data 8.99E-07 No Data 2.13E-05 Ru-105 2.18E-08 No Data 8.46E-09 No Data 2.75E-07 No Data 1.76E-05 3 Ra-106 3.92E-06 No Data 4.94E-07 No Data 7.56E-06 No Data 1.88E-04 Ag-110m 2.05E-07 1.94E-07 1.18E-07 No Data 3.70E-07 No Data 5.45E-05 i Te-125m 3.83E-06 1.38E-06 5.12E-07 1.07E-06 No Data No Data 1.13E-05 Te-127m 9.67E-06 3.43E-06 1.15E-06 2.30E-06 3.92E-05 No Data 2.41E-05 Te-127 1.58E-07 5.60E-08 3.40E-08 1.09E-07 6.40E-07 No Data 1.22E-05 Te-129m 1.63E-05 6.05E-06 2.58E-06 5.26E-06 6.82E-05 No Data 6.12E-05 Te-129 4.48E-08 1.67E-08 1.09E-08 3.20E-08 1.88E-07 No Data 2.45E-07 Te-131m 2.44E-06 1.17E-06 9.76E-07 1.75E-06 1.22E-05 No Data 9.39E-05 Te-131 2.79E-08 1.15E-08 5.72E-09 2.15E-08 1.22E-07 No Data 2.29E-09 Te-132 3.49E-06 2.21E-06 2.08E-06 2.33E-06 2.12E-05 No Data 7.00E-05 I-130 1.03E-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06 No Data 2.29E-06 I-131 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41E-05 No Data 1.62E-06 I-132 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E-06 No Data 3.18E-07 I-133 2.01E-06 3.41E-06 1.04E-06 4.76E-04 5.98E-06 No Data 2.58E-06 I-134 1.46E-07 3.87E-07 1.39E-07 6.45E-06 6.10E-07 No Data 5.10E-09 1-135 6.10E-07 1.57E-06 5.82E-07 1.01E-04 2.48E-06 No Data 1.74E-06 4 Cs-134 8.37E-05 1.97E-04 9.14E-05 No Data 6.26E-05 2.39E-05 2.45E-06 Cs-136 8.590-06 3.38E-09 2.27E-05 No Data 1.84E-05 2.90E-06 2.72E-06 Cs-137 1.12E-04 1.49E-04 5.19E-05 No Data 5.07E-05 1.97E-05 2.12E-06 Cs-138 7.76E-08 1.49E-07 7.45E-08 No Data 1.10E-07 1.28E-08 6.76E-11 4 Ba-139 1.39E-07 9.78E-11 4.05E-09 No Data 9.22E-11 6.74E-11 1.24E-06 Ba-140 2.84E-05 3.48E-08 1.88E-06 No Data 1.18E 2.34E-08 4.38E-05 4 i Ba-141 6.71E-08 5.01E-11 2.24E-09 .No Data 4.65E-11 3.43E-11 1.43E-13 Ba-142 2.99E-08 2.99E-11 1.54E-09 No Data 2.53E-11 1.99E-11 9.18E-20 La-140 3.48E-09 1.71E-09 4.55E-10 No Data No Data No Data 9.82E-05 La-142 1.79E-10 7.95E-11 1.98E-11 No Data No Data No Data 2.42E-06 i Revision 1 - August 1983 2 of 3 BN1-11600.02-95 4

SNPS-1 ODCM TABLE 3.1-3 (CONT'D) Radio-nuclide 'Boce Liver T. Body Thyroid Kidney Lynj[ CI-LLI Ce-141 1.33E-08 8.88E-09 1.02E-09 No Data 4.18E-98 No Data 2.54E-05 Ce-143 2.35E-09 ,1.71E-06 1.91E-10 No Data 7.67E-10 No Data. 5.14E-05 Ce-144 6.96E-07 2.88E-07 3.74E-08 No Data 1.72E-07 No Data 1.75E-04 Pr-143 1.31E-08

5.23E-09 6.52E-10 No Data 3.04E-09 No Data 4.31E-05 Pr-144 4.30E-11 1.76E-11 2.13E-12 No Data 1.01E-11 No Data 4.74E-14 Nd-147 9.38E-09 1.02E-08 6.11E-10 No Data 5.99E-09 No Data 3.68E-05 W-187 1.46E-07 1.19E-07

'4.17E-08 No Data No Data No Data 3.22E-05 Np-239 1.76E-09 1.66E-10 9.22E-11 No Data 5.21E-10 No Data 2.67E-05 l l l l l 9 Revision 1 - August 1983 3 of 3 BN1-11600.02-95

_( n ,a SNPS-1 ODCM TABLE 3.1-4 INGESTION DOSE FACTORS FOR CHILD (mrem per pCi ingested)' Radio-nuclide Bone Liver T. Bodr Thyroid Kidney Lung CI-LLI H-3 No Data 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 C-14 1.21E-05 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06~ Na-24 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 ~ P-32 8.25E-04 3.86E-05 3.18E-05 No Data No Data No Data 2.28E-05 Cr-51 No Data No Data 8.90E-09 4.84E-09 1.35E-09 9.02E-09 4.72E-07 Mn-54 No Data 1.07E-05 2.85E-06 No Data 3.00E-06 No Data 8.98E-06 Mn-56 No Data 3.34E-07 7.54E-08 No Data 4.04E-07 No Data 4.84E-05 Fe-55 1.15E-05 6.10E-06 1.89E-06 No Data No Data 3.45E-06 1.13E-06 Fe-59 1.65E-05 2.67E-05 1.35E-05 No Data No Data 7.74E-06 2.78E-05 Co-58 No Data 1.80E-06 5.51E-06 No Data No Data No Data 1.05E-05 Co-60 No Data 5.29E-06 1.56E-05 No Data No Data No Data 2.93E-05 Ni-63 5.38E-04 2.88E-05 1.83E-05 No Data No Data No Data 1.94E-06 Ni-65 2.22E-06 2.09E-07 1.22E-07 No Data No Data No Data 2.56E-05 Cu-64 No Data 2.45E-07 1.48E-07 No Data 5.92E-07 No Data 1.15E-05 Zn-65 1.37E-05 3.65E-05 2.27E-05 No Data 2.30E-05 No Data 6.41E-06 Zn-69 4.38E-08 6.33E-03 5.85E-09 No Data 3.84E-08 No Data 3.99E-06 Br-83 No Data No Data 1.71E-07 No Data No Data No Data <l.00E-24 Br-84 No Data No Data 1.93E-07 No Data No Data No Data <l.00E-24 Br-85 No Data No Data 9.12E-09 No Data No Data No Data <1.00E-24 Rb-86 No Data 6.70E-05 4.12E-05 No Data No Data No Data 4.31E-06 Rb-88 No Data 1.90E-07 1.32E-07 No Data No Data No Data 9.32E-09 Rb-89 No Data 1.17E-07 1.04E-07 No Data No Data No Data 1.02E-09 Sr-89 1.32E-03 No Data 3.77E-05 No Data No Data No Data 5.llE-05 Sr-90 1.70E-02 No Data 4.31E-03 No Data No Data No Jata 2.29E-04 Sr-91 2.40E-05 No Data 9.06E-07 No Data No Data No Jata 5.30E-05 Sr-92 9.03E-06 No Data 3.62E-07 No Data No Data No Data 1.71E-04 Y-90 4.11E-08 No Data 1.10E-09 No Data No Data No Data 1.17E-04 Y-91m 3.82E-10 No Data 1.37E-11 No Data No Data No Data 7.48E-07 Y-9L 6.02E-07 No Data 1.61E-08 No Data No Data No Data 8.02E-05 Y-92 3.60E-09 No Data 1.03E-10 No Data' No Data No Data 1.04E-04 Y-93 1.14E-08 No Data 3.13E-10 No Data No Data No Data 1.70E-04 i I BN1-11600.02-96

( p D U b-SNPS-1 ODCM TABLE 3.1-4 (CONT'D) Radio-nuclide Bone Liver T. Body Thyroid Kidney 1 ng( GI-LLI 3 Zr-95 1.16E-07 2.55E-08 2.27E-08 No Data 3.65E-08 No Data 2.66E-05 Zr-97 6.99E-09 1.01E-09 5.96E-10 No Data 1.45E-09 No Data 1.53E-04 Nb-95 2.25E-08 8.76E-09 6.26E-09 No Data 8.23E-09 No Data 1.62E-05. Mo-99 No Data 1.33E-05 3.29E-06 No Data 2.84E-05 No Data 1.10E-05 Tc-993 9.23E-10 1.81E-09 3.00E-08 No Data 2.63E-08 9.19E-10 1.03E-06 Tc-101 1.07E-09 1.12E-09 1.42E-08 No Data 1.91E-08 5.92E-10 3.56E-09 Ru-103 7.31E-07 No Data 2.81E-07 No Data 1.84E-06 No Data 1.89E-05 Ru-105 6.45E-08 No Data 2.34E-08 No Data 5.67E-07 No Data 4.21E-05 Ru-106 1.17E-05 No Data 1.46E-06 No Data 1.58E-05 No Data 1.82E-04 Ag-110m 5.39E-07 3.64E-07 2.91E-07 No Data 6.78E-07 No Data 4.33E-05 Te-125m 1.14E-05 3.09E-06 1.52E-06 3.20E-06 No Data No Data 1.10E-05 Te-127m 2.89E-05 7.78E-06 3.43E-06 6.91E-06 8.24E-05 No Data 2.34E-05 Te-127 4.71E-07 1.27E-07 1.01E-07 3.26E-07 1.34E-06 No Data 1.84E-05 Te-129m 4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 No Data 5.94E-05 Te-129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.928-07 No Data 8.34E-06 Te-131m 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.41E-05 No Data 1.01E-04 Te-131 8.30E-08 -2.53E-08 2.47E-08 6.35E-08 2.51E-07 No Data 4.36E-07 Te-132 1.01E-05 4.47E-06 5.40E-06 6.51E-06 4.15E-05 No Data 4.50E-05 1-130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 No Data 2.76E-06' I-131 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 No Data 1.54E-06 I-132 8.00E-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 No Data 1.73E-06 I-133 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 No Data 2.95E-06 I-134 4.19E-07 7.78E-07 3.58E-07 1.79E-05 1.19E-06 No Data 5.16E-07 I-135 1.75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 No Data 2.40E-06 Cs-134 2.34E-04 3.84E-04 8.10E-05 No Data 1.19E-04 4.27E-05 2.07E-06 Cs-136 2.35E-05 6.46E-05 4.18E-05 No Data 3.44E-05 5.13E-06 2.27E-06 Cs-137 3.27E-04 3.13E-04 .4.62E-05 No Data 1.02E-04 3.67E-05 1.96E-06 I Cs-138 2.28E-07 3.17E-07 2.01E-07 No Data 2.23E-07 2.402-08 1.46E-07 Ba-139 4.14E-07 2.21E-10 1.20E-03 No Data 1.93E-10 1.30E-10 2.39E-05 i Ba-140 8.31E-05 7.28E-08 4.85E-06 No Data 2.37E-08 4.34E-08 4.21E-05 Ba-141 2.00E-07 1.12E-10 6.51E-09 No Data 9.69E-11 6.58E-10 1.14E-07 Ba-142 8.74E-08 6.29E-11 4.88E-09 No Data 5.09E-11 3.70E-11 1.14E-09 La-140 1.01E-08 3.53E-09 1.10E-09 No Data No Data No Data 9.84E-05 4 La-142 5.24E-10 1.67E-10 5.23E-11 No Data No Data No Data 3.31E-05 3 Revision 1 - August 1983 BN1-11600.02-96

SNPS-1 ODCM -TABLE 3.1-4 (CONT'D) Radio-nuclide Bone Liver T. Body Thyroid Kidney 1 ng[ GI-LLI 3 f .Ce-141 3.97E-08 1.98E-08 2.94E-09 No Data 8.68E-08 No Data

2.47E-05 Ce-143 6.99E-09 3.79E-06 5.49E-10 No Data 1.59E-09 No Data 5.55E-05 Ce-144 2.08E-06

'6.52E-07 1.11E-07 No Data 3.61E-07 No Data 1.70E-04 Pr-143 3.93E-08 1.18E-08 1.95E-09 No Data 6.39E-09 No Data 4.24E-05 Pr-144 1.29E-10 3.99E-11 '6.49E-12 No Data 2.11E-11 No. Data 8.59E-08 i Nd-147 2.79E-08' 2.26E-08 1.75E-09 No Data 1.24E-08 No Data 3.58E-05 W-187 4.29E-07 2.54E-07 1.14E-07 No Data No Data No Data 3.57E-05 Np-239 5.25E-09 3.77E-10 2.65E-10 No Data 1.09E-09 No Data 2.79E-05 i i i l i i 1 t 4 I 1 4 v i i i I, t { Revision 1 - August 1983 3 of 3 i BN1-11600.02-96 I

m. SNPS-1 ODCM /' ~' TABLE 3.1-5 i-(}/ DECAY CONSTANTS (1/hr) Radio-Radio- -nuclide Constant nuclide Constant H-3 6.408E-06 Ru-103 7.300E-04 C-14 1.379E 08 Ru-105 1.600E-01 Na-24 4.600E-02 Ru-106 7.800E-05 P-32 2.000E-03 Ag-110m 1.100E-04 Cr-51 1.044E-03 Te-125m 5.000E-04 Mn-54 9.252E-05 Te-127m 2.600E-04 Mn-56 2.700E-01 Te-127 7.400E-02 Fe-55 2.930E-05 Te-129m 8.600E-04 Fe-59 6.480E-04 Te-129 5.900E-01 Co-58 4.068E-04 Te-131m 2.300E-02 Co-60 1.501E-05 Te-131 1.700E+00 Ni-63 8.600E-07 Te-132 8.900E-03 Ni-65 2.700E-01 1-130 5.600E-02 l. Cu-64 5.400E I-131 3.593E-03 l' Zn-65 1.184E I-132 3.000E-01 Zn-69 7.296E-01 1-133 3.334E-02 Br-83 2.900E-01 1-134 7.900E-01 Br-84 1.300E+00 1-135 1.100E-01 Br-85 1.449E+01 Cs-134 3.852E-05 '_/~'} Rb-86 1.500E-03 Cs-136 2.203E-03 's,/ Rb-88 2.400E+00 Cs-137 2.635E-06 Rb-89 2.700E+00 Cs-138 1.300E400 Sr-89 5.724E-04 Ba-139 5.000E-01 Sr-90 2.776E-06 Ba-140 2.257E-03 Sr-91 7.300E-02 Ba-141 2.300E+00 Sr-92 2.600E-01 Ba-142 3.900E+00 Y-90 1.100E-02 La-140 1.700E-02 Y-91m 8.300E-01 La-142 4.500E-01 Y-91 4.900E-04 Ce-141 8.892E-04 i l Y-92 2.00E-01 Ce-143 2.100E-02 Y-93 6.800E-02 Ce-144-1.019E-04 Zr-95 4.3928-04 Pr-143 2.100E-03 Zr-97 4.100E-02 Pr-144 2.400E+00 Nb-95 8.200E-04 Nd-147 2.600E-03 Mo-99 1.000E-02 W-187 2.900E-02 Tc-99m 1.200E-01 Np-239 1.200E-02 Tc-101 2.900E+00 i BN1-11600-02-112 1 of 1 Revision 1 - August 1983 \\_/ l

SNPS-1 ODCM [~'i TABLE 3.1-6 'd - EXTERNAL DOSE FACTORS FOR STANDING Og) CONTAMINATED GROUND (mres/hr per pCi/m Element Total Body Skin H-3. 0.0 0.0 C-14 0.0 0.0 Na-24 2.50E-08 2.90E-08 P-32 0.0 0.0 Cr-51 2.20E-10 2.60E-10 Mn-54 5.80E-09 6.80E-09 Mn-56 1.10E-08 1.30E-08 Fe-55 0.0 0.0 Fe-59 8.00E-09 9.40E-09 Co-58 7.00E-09 8.20E-09 Co-60 1.70E-08 2.00E-08 Ni 0.0 0.0 Ni-65 3.70E-09 4.30E-09 Cu-64 1.50E-09 1.70E-09 Zn-65 4.00E-09 4.60E-09 Zn-69 0.0 0.0 Br-83 6.40E-11 9.30E-11 Br-84 1.20E-08 1.40E-08 Br-85 0.0 0.0 Rb-86 6.30E-10 7.20E-10 Rb-88 3.50E-09 4.00E-09 _ ['] \\,/ Rb-89 1.50E-08 1.80E-08 Sr-89 5.60E-13 6.50E-13 .Sr-91 7.10E-09 8.30E-09 9--92 9.00E-09 1.00E-08 Y-90 2.20E-12 2.60E-12 Y-91m 3.80E-09 4.40E-09 Y-91 2.40E-11 2.70E-11 Y 1.60E-09 1.90E-09 Y-93 5.70E-10 7.80E-10 Zr 5.00E-09 5.80E-09 Zr-97 5.50E-09 6.40E-09 Nb-95 5.10E-09 6.00E-09 Mo-99 1.90E-09 2.20E-09 Tc-99m 9.60E-10 1.10E-09 .Tc-101 2.70E-09 3.00E-09 Ru-103 3.60E-09 4.20E-09 Ru-105 4.50E-09 5.10E-09 Ru-106 1.50E-09 1.80E-09 Ag-110m 1.80E-08 2.10E-08 BN1-11600.02-112 1 of 2 Revision 1 - August 1983 -Ok.)

SNPS-1 ODCM TABLE 3.1-6 (CONT'D) Element Total Body Skin Te-125m 3.50E-11 4.80E-11 Te-127m 1.10E-12 1.30E-12 Te-127 1.00E-11 1.10E-11 'Te-129m 7.70E-10 9.00E-10 .Te-129 7.10E-10 8.40E-10 Te-131m 8.40E-09 9.90E-09 Te-131 2.20E-09 2.60E-06 Te-132 1.70E-09 2.00E-09 I-130 1.40E-08 1.70E-08 I-131 2.80E-09 3.40E-09 I-132 1.70E-08 2.00E-08 I-133 3.70E-09 4.50E-09 I-134 1.60E-08 1.90E-08 I-135 1.20E-08 1.40E-08 Cs-134 1.20E-08 1.40E-08 Cs-136 1.50E-03 1.70E-08 Cs-137 4.20E-09 4.90E-09 Cs-138 2.10E-08 2.40E-08 Ba-139 2.40E-09 2.70E-09 Ba-140 2.10E-09 2.40E-09 Ba-141 4.30E-09 4.90E-09 Ba-142 7.90E-09 9.00E-09 La-140 1.50E-08 1.70E-08 ^/~ La-142 1.50E-08 1.80E-08 \\s Ce-141 5.50E-10 6.20E-10 Ce-143 2.20E-09 2.50E-09 Ce-144 3.20E-10 3.70E-10 Pr-143 0.0 0.0 Pr-144 2.00E-10 2.30E-10 Nd-147 1.00E-09 1.20E-09 W-187 3.10E-09 3.60E-09 Np-239 9.50E-10 1.10E-09 S BN1-11600.02-112 2 of 2 Revision 1 - August 1983 [V i

._..~ _. /) f U ,O ' V SNPS-1 ODCM TABLE 3.1-7. DOSE RATE CONVERSION FACTORS (I),Air FOR (FISil AND INVERTEBRATE) INGESTION PATHWAY (ares / min per LC1/cc) Isotope Bone Liver T. Body Thyroid Kidney Ignj( GI-LLI i 11 - 3 -(I) 5.9E-03 5.9E-03 5.9E-03 5.9E-03 5.9E-03 5.9E-03 C-14 Na-24 3.3E-03 3.3E-03 3.3E-03 3.3E-03 3.3E-03 3.3E-03 3.3E-03 J P-32 2.6E+05 1.6E+04 1.0E+04 3.0E+04 Cr-51 8.9E-02 5.3E-02 2.0E-02 1.2E-01 2.2E+01 1.2E+02 2.2E+01 3.4E+01 3.6E+02 Mn-54 Mn-56 4.6E-03 8.3E-04 5.6E-03 1.4E-01 Fe-55 1.9E+03 8.6E+03 2.2E+03 9.9E+03 3.3E+03 8.6E+02 1.0E+04 i Fe-59 1.3E+03 3.1E+03 1.2E+03 Co-58 9.8E+00 2.2E+01 '2.0E+02 l Co-60 2.8E+01 6.2E+01 5.3E+02 Ni-63 8.3E+02 5.8E+01 2.7E+01 1.2E+01 Ni-65 4.8E-03 6.3E-04 2.8E-04 1.6E-02 Cu-64 9.6E-01' 4.5E-01 2.4E+00 8.2E+01 5.6E+03

5. 2E +03 Zn-65 2.6E+03 8.3E+03

'3.8E+03 I Zn-69m 2.8E+01 6.7E+01 6.2E-00 4.1E+01 4.1E+03 Br-83 1.2E-06 1.7E-06 Br-84 2.8E-17 2.1E-22 Br-85 Rb-86 Rb-88 Rb-89 5.3E-31 3.8E-31 2.3E+00 1.3E+01 Sr-89 8.2E+01 Sr-90 2.0E+03 4.9E+02 2.7E+01 Sr-91 2.6E-01 1.2E-02 1.3E+00 l Sr-92 1.2E-03 5.3E-05 2.4E-02 Y-90 l Y-91m l Y-91 1.5E+00 3.8E-02 7.9E+02 Y-92 7.9E-05 2.3E-06 1.4E+00 Y-93 5.4E-03 1.5E-04 1.7E+02 4 BN1-11600.02-97 1 of 2 Revision 1 - August 1983 i. i I

m p L ( SNPS-1 ODCM TABLE 3.1-7 (CONT'D) Isotope Bone Liver T. Body Thyroid Kidney Lung GI-LLI Zr-95 2.6E-01 8.3E-02 5.6E-02 1.3E-01 2.6E+02 Zr-97 5.4E-03 1.1E-03 4.9E-04 1.6E-03 3.3E+02 3.9E+00 2.4E+04 Nb-95 7.2E+00 4.0E+00 1.6E+00 Mo-99 1.6E+00 3.2E-01 3.7E+00 3.7E+00 5.7E-04 1.9E-05 2.2E-02 Tc-99m 1.4E-05 3.8E-05 4.8E-04 Tc-101 6.3E-35' 9.0E-35 9.0E-34 1.6E-33 4.6E-35 Ru-103 1.7E+00 7.3E-01 6.6E+00 2.0E+02 Ru-105 3.5E-03 1.4E-03 4.4E-02 2.1E+00 Ru-106

2. 6E+01 3.3E+00 5.0E+01 1.7E+03 Ag-110m 2.5E+01 2.4E+01 1.4E+01 4.5E+01 9.8E+03 Te-129m 1.5E+01 5.5E+00 2.4E+00 5.2E+00 6.2E+01 7.5E+01 Te-131m 1.3E+00 6.4E-01 5.3E-01 1.0E+00 6.4E+00 6.3E+01 Te-132 2.7E+01 1.8E+00 1.6E+00 1.9E+00 1.7E+01 8.3E+01 1-131 3.3E+00 4.7E+00 2.7E+00 1.5E+03 8.0E+00 1.2E+00 1-132 1.2E-04 3.3E-04 1.1E-04 4.3E-02 5.1E-04 6.1E-05 I-133 5.5E-01 9.6E-01 2.9E-01 1.8E+02 1.7E+00 8.5E-01

'1.2E-12 1-134 5.0E-10 1.4E-09 4.9E-10 1.8E-07 2.2E-09 1-135 3.1E-02 8.2E-02 2.9E-02 1.1E+01 1.3E-01 8.9E-02 Cs-134 1.1E+02 2.7E+02 2.1E+02 8.6E+01 2.8E+01 4.6E+00 l Cs-136 1.1E+01 4.4E+01 3.2E+01 2.4E+01 3.3E+00 5.0E+00 Cs-137 1.5E+02 1.9E+02 1.3E+02 6.7E+01 2.2E+01 3.8E+00 Cs-138 3.5E-15 7.0E-15 3.5E-15 5.2E-15 5.2E-16 3.0E-20 Ba-139 8.1E-07 5.7E-10 2.4E-08 5.4E-10 3.3E-10 1.5E-06 Ba-140 2.5E+01 3.2E-02 1.7E+00 1.1E-02 1.8E-02 5.3E+01 Ba-141 1.0E-28 4.6E-27 9.7E-29 5.8E-29 6.4E-35 Ba-142 8.0E-43 8.2E-46 5.1E-44 7.0E-46 4.6E-46 La-142 2.6E-08 1.2E-08 3.0E-09 8.9E-05 Ce-141 5.5E-02 3.7E-02 4.2E-03 1.7E-02 1.4E+02 Ce-143 5.9E-03 4.4E+00 4.9E-04 2.0E-03 1.6E+02 Ce-144 2.9E+00 1.2E+00 1.6E-01 7.2E-01 9.7E+02 Pr-143 8.8E-02 3.6E-02 4.5E-03 2.1E-02 3.9E+02 Nd-147 6.1E-02 7.0E-02 4.2E-03 4.1E-02 3.4E+02 2 W-187 7.5E-02 6.3E-02 2.1E-02 2.0E+01 ] Np-239 4.4E-04 4.3E-05 2.3E-05 1.3E-04 8.7E+07 (1) The dash (-) indicates unsufficient data or that the dose factor is <1.0E-20. BN1-11600.02-97 2 of 2 Revision 1 - August 1983 4

r ,/- 7 \\ 'n,/ L0NG /SLAND SOUND k 4 } r 7 g_ -ti%*.O#fd' A j ** .T' \\ ~ r d. d 7 s . =- n]*y 'D. Y

• .k.

c' y

<?

f , - x. / + ,) u ' TQ W A, -- / ~ s_ a t-Q .? f, 'r y \\ Q \\ y'- s m n,

• • ' 'E

\\ s P&nK NG Y /.i O; ; -... ~., .c \\

1. J'

\\ \\ sanor c. s,, m,_ Y '} o y r.... ' q[ EL-25 \\ I a s ( s / f f

• ~

' TE y***

== -,. ~ ~ .., ~. y y I / / f lti ll / , + - ll 8 ( }[ f / g~ Q} // o FIGURE 3.1-1 /// G, /J, (/ -M. SITE BOUNDARY FOR LIQUID [ " ""/ EFFLUENTS s SHOREHAM NUCLEAR POWER STATION-UNIT 1 i= aa

==

g? \\ C OFFSITE DOSE CALCULATION M ANU AL / = + ' " ) l [ Y ox REVISION 1-AUGUST 1983

FLOOR DRAIN FLOOR DR AIN COLLECTOR TANK F1LTER w CIRCULATING WATER SYSTEM I f WASTE I DIS CH ARGE EVAPORATOR WASTE TANK I f I f WASTE RADWASTE RECOVERY I f< COLLECTOR DEMINERAllZER/ + SAMPLE e p TANK FILTER TANK I k - (./ l l I l l l YARD PIPING DRAIN SUMP REGENERANT EVA POR ATOR RESIDUAL HEAT REMOVAL SYSTEM REACTOR BUILDING SALT WATER r 1 f DRAIN TANK To DIFFUSER FIGURE 3.1-2 LIQUID RADWASTE SYSTEM MODEL SHOREHAM NUCLEAR POWER STATION-UNIT 1 O OFFSITE DOSE CALCULATION MANUAL REVISION 1-AUGUST 1983 l

I SNPS-1 ODCM 3.2 OPERATION OF LIQUID WASTE TREATMENT SUBSYSTEMS ' The dose project' ion analysis will 'be performed using the methodology described in. Section 3.1 'with the exception that the calculated doses will be compared with the limits specified in RETS Section 3.11.1.3. The liquid radwaste treatment-systea shall-be OPERABLE and appropriate portions of the system shall be used to reduce releases of radioactivity when the projected doses due - to the liquid effluent to UNRESTRICTED AREAS would exceed 0.06 arem to the total body or 0.2 ares to any organs in a 31-day period. Liquid radwaste treatment subsystems are shown on Figure 3.2-1. 3 O i I-l l t l i-O BN1-11600.02-92 3.2-1 Revision 1 - August 1983 4 9 -e,-- ce ,-----r, -,,,,---,-p,e--*:ee n+-y,v e-,,, c- -.=g-y-- ,--w,,--wr -r eww-w,mce+mw-y- --<y

---

v-r sr e

vy3-- wety*rv--

O FLOOR DRAIN FLOOR DRAIN COLLECTOR TANK F1LTER I f WASTE I DI S CH ARGE EVAPORATOR WASTE TANK I f ! f WASTE R A OWASTE RECOVERY COLLECTOR = DEMINERAll2ER/ + SAMPL E TANK FILTER TANK l l i l U TO DIFFUSER REGENERANT EVA POR ATOR FIGURE 3.2-1 LIQUID RADWASTE TREATMENT SY9 TEM SiiOREHAM NUCLEAR POWER STATION UNIT 1 OFFSITE DOSE CALCULATION MANUAL REVISION 1 AUGUST 1983

SNPS-1 ODCM ./ '] 3.3 DOSE RATE DUE TO CASEOUS EFFLUENTS A f To comply with Section 3.11. 2.1 of RETS, the dose crate at any time in the unrestricted area for noble gas dose and for organ dose due to radioactive materials in gaseous effluents released via the station ventilation exhaust duct shall be limited to the following values; 1. For noble gases: Less than or equal to 50 arem/yr to the total body and less than or equal to 3000 mrea/yr to the skin, and 2. For I-131, I-133, tritium, and-for all radionuclides in particulate form with half lives greater than 8 days: Less than or equal to 1500 arem/yr to any organ. The gaseous effluent model is shown in Figure 3.3-1. 3.3.1 Method 1: (Computerized Method) 3.3.1.1 Release Rate Estimation Dose rate estimation is carried out every 15 minutes by making use of a atmospheric dispersion data computed every hour, and of the following equation for the release rate (Ci/hr): Q = F* f 1 g where: Ch V F* =4k F,(j ) U (j ) At 3 f = 10-6 qi (r) /Cng(') t k = 2.832 x 104 (cc/ft3) F,(j) = vent flow during time interval j (cfm) 6ng (j) = noble gas effluent monitor count rate during time interval j (cpm) At = time interval (=1 minute) qi = concentration of isotope i in the effluent as measured in the lab at time r (;;Ci/cc) 15-minute average of the flow and countrate product (for F* = dose rate estimation every 15 minutes) assumed to apply for a 60-minute interval [(cc/hr) (cpm)) 4 x 15 = number of At intervalo per hour (1/hr) 'O v BN1-11600.02-92 3.3-1 Revision 1 - August 1983 ~ .~

h SNFS-1 OI,CM i- -3.3.1.2 Total Body Dose Rate E #"" D =D + D + D f wb wb wb wb r. /f where: <g l D, " ~ = (x/Q) ** F* 2.22 x 10 f DFB bles i g h/ ) f D = (X/Q)'" F* 3.11 x 10 R f DFA g pfgy g ij,ad b 37 g gy[1-e~ b i]/A (D/0) F* 7 x 10 f DFG = g cloud D = total body dose due to direct radiation from the radioactive cloud- [ mrem /hr] (Ref.: Reg. Guide 1.109 Eq. B-8;.also similar to Eq. B-6 if one pakes use of the gamma (x/Q) and the DFB instead of - DF dose conversion g factor) total body) due to inhalation D = total body dose (j = [mres/hr] (Ref. :. Reg. Guide 1.109 Eqs. C-3 and C-4. f or an adult) n,: 8# D = total body dose due to particulate and iodine b radioactivity depoatting on the ground - [mres/hr] (Ref. : g; - Reg. Guide 1.109, Eqs. C-1 and C-2 with the product 8760 [br/yr] (1/A ) [yr] replaced by (1/A ) [hr] and parameter 1 g 6 (r,0) represented by the (D/Q)) g 3 I' DFB = gamma dose to body conversion f actor [(ares /yr)/(pC1/m )j 1 (f rom Table B-1 of the guide) DFA = dose conversion f actor. f or nuclide i to organ j of an ij,ad v adult individual [mres/pCi inhaled] (from Tables E-7 through E-10 of Reg. Guide 1.109) DFG g

• total body conversion f agtor for standing on contaminated i

-ground [(arem/hr)/(pCi/m )]' (f rom Table E-6 of Reg. Guide 1.109) 4 (X /Q)sa = concentration dispersion factor (sector-average aojel) f or the period of release (site boundary only) (sec/m ) ^ (X/Q)T = gamma (X/Q) (finite cloud sector-average model) f or the 3 period of release (site boundary only) (sec/m ) 2 (D/Q) = particulate' deposition rate (site boundary only) (1/m ) F* f = o (C1/hr) (as defined in Section 3.3.1.1) .g g

L..)

T BN1-11600.02-92 3.3'-2 Revision 1 - August 1983 w --

SNPS-1 ODCM R = adult breathing rate (m /yr) (from Table E-5 of the ed d Guide) A = radionuclide decay constant (1/hr) g

• time poriod over which the accuylation is evaluated, tb which is 15 years (1.314 x 10 hours) (Reg. Guide

{ pg 1.109-24) 12 (8760 x 3600) [(pci/C1) (yr/sec)] 4 / 3.17x10 = 10 4 0 2.2x10 = 3.17 x 10 x 0.7, where 0.7 is the shielding factor which accounts for the dose redection due to the shielding effects of residential structures during occupancy (Ref.: Reg. Guide 1.109 Table E-15) 7x10 = 10 x 0.7, where 0.7 is the shielding f actor and 10I2 's ll 12 the number of pCi per CL (see Eqs. C-1 and C-2 of the guide) part+1 = 68 particulates and 5 iodines in the summation sign 3.3.1.3 Skit Dose Rate cloud ground D + D D = akin skin skin DFf D = 1.11 x 0.7 (X/Q)* F* 3,17 x 10 g,, fg 0 + (y/Q)sa F* 3.17 x 10 g, fg DFS j DFG12 [1 - e b1]/A D, = (D/Q) F* 7 x 10 g p et+1 i n D"1 "O = skin dose due to direct gamma radiation from the radioactive cloud (first component of the equation with finite cloud modeling) and beta radiation (second component, semi-infinite cloud immersion) [ mrem /hrl (Ref.: Reg. Guide 1.109 Eq. B-9; also similar to Ec. B-7 if one makes use of the gauna (x/Q)) gr und = skin dose due to particulate and iodine radioactivity Dskin depositing on the ground [mram/hr] (Ref.: Reg. Guide 1.109, Eqs. C-1 and C-2 with the product 8760 [hr/yr) (1/A ) [yr] replaced by (1/ A [h-] and parameter 6 (r,0) represented by the (D/Q))g) g 1 3 DFf = gassa dose to air conversion factor [(arad/yr)/(pCi/m )} (from Table B-1 of the Guide) O \\ t BN1-11600.02-92 3+3-3 Revision 1 - August 1983

~. SNPS-1 ODCM 3 p DFS beta dose to skin conversion f actor [(mrem /yr)/(pCi/m )] = g (f rom Table B-1 of the Guide) 12 skin dose conversion fagtor for standing on contaminated DFG = ground [(ares /hr)/(pCi/m )] (from Table E-6 of Reg. Guide 1.109) 1.11 average ratio of tissue to air energy absorption = coefficient (from Reg. Guide 1.109, pg 1.109-6) shielding dose-reduction factor (see pg 1.109-68) 0.7 = t radionuclide decay constant [hr~I] A = 3.3.1.4 Organ Dose Rate (Particulate Release) (x/Q"# F* 3.17 x 10 R) f DFA D" = where: D" dose to organ j of individual in age group a due to = 3" inhalation of airborne radioactivity [ mrem /hr] (Ref.: Reg. Guide 1.109. Eqs. C-3 and C-4.) dose conversion factor for nuclide i to organ j of DFA = gj, individual in age group a [ mrem /pCi inhaled] (from Tables E-7 through E-10 of the Guide) O 3 Q R, breathing rate of individual in age group a [m /yr] (from = Table E-5 of Reg. Guide 1.109, for the maximum individuals) The analysis is limited to the computation of the thyroid dose to an adult at the site boundary in the downwind sector for the period of the release (i.e., j = thyroid, a = adult). l O) zU BN1-11600.02-92 3.3-4 Revision 1 - August 1983 w t -y qe-v- ,.,,r ,y-r, v -m- - e+-- ,,-e<mr,-,,---+-,---r--,-,,--- e e--. .v-

SNPS-1 ODCM ~ /) 3.3.2 Method 2: (Backup Method) O 3.3.2.1 Noble Cas Total Body Dose Rate DT, = 0.7

• X/Q1 *k 8
• ( 11 1 - 12 2

13 3 ~ 1

• Cg]

+ 0.7

• V
• X /Q *{[DFBg 2

2

• Cg3]

(mres/yr) + 0.7

• V
• X/Q * { IMBt 3

3 During periods of no intermittent releases such ar no main condenser air removal pump operation and no containment drywell purge the above formula reduces to the f allowing:

• Cgg]

(aren/yr)

• X/Q * { IN81 DT, = 0.7
• Vg g

where DT, = total body dose rate f rom all radionuclides releases (arem/yr), = the total body dose rate f actor due to gamma emissions f or each DFBt 3 identified noble gas radionuclide (arem/yr per pCL/m ) (Table 2.2-1), C = the station ventilation - exhaust duct release concentration of gg radionuclide, i, (pC1/cc) (f rom the isotopic analyses performed on the gaseous sample taken from the station ventilation exhaust O monitor), C = the air removal. pump ventilation exhaust duct release 3 12 j concentration of radionuclide, i, (pC1/cc) (from the isotopic analysse perf ormed on' the. gaseous sample taken from the air removal pump discharge monitor), i = the containment drywell purge ventilation exhaust concontration of Ct3 radionuclide, i, (pC1/ce) (f rom the isotopic analyses perf ormed on the gaseous sample taken f rom the containment drywell filter train l exhaust monitor), i V = 1.70E+08 cc/sec (3.66E+05 cfm), station ventilation exhaust duct g. l ventilation exhaust flow rate. l' V = 5.70E+05 cc/sec (1200 efs), air removal pump exhaust duct 2 ventilation exhaust flow rate. l V = 5.70E+05 cc/sec (1200 cfm), containment drywell purge ventilation 3 exhaust flow rate, i !.I'ri k BN1-11600.02-92 3.3-5 Revision 1 - August 195 _ - _., _ _ _. _ ~.,

\\ SNPS-1 ODCM ~ = annual average WQ at 366 meters NNE due to release via the X/Qt station ventilation exhaust point (6.6E-07 sec/m ), l2 3 = annual average short term gQ at 366 meters NNE due to air removal X/Q2 pump release via the stLtion ventilation exhaust point (3.6E-06 sec/m ), l2 3 = annual average short term dQ at 366 meters NNE due to containment X/Q3 drywell purgg via the station ventilation exhaust point (3.6E-06 sec/m ). l2 0.70 = shielding factor that accounts for dose reduction due to shielding f rom residential structures. 4 4 O - BN1-11600-02-92 3.3-6 Revision 2 - September 1983 er er -~ s.- -r- --e a r., ,-m-me ,,-,,,-.e-- n, ,,,,,-,----.--,,,earm -,-ve .e-w+-,-we.w-w,,-w,-,->w ,-,--wg m-,-.---

SNPS-1 ODCM 3.3.2.2 Noble Ces Skin Dose Rate

• {(K
• (C
• V

-C ig g i2 2 13 3} DS, = X/Qg ~ g3)(arem/yr) 2)+V

• X/Q * [ (K,L

+V

• X/Q * [ (K
• C
• C 3

3 2 2 During periods of no intermittent releases such as no main condenser air removal pump operation and no containment drywell purge the above formula reduces to the following: gg) (arem/yr)

• y/Q * [ (K,1 *C DS, = Vg g

where: DS, = skin dose rate from all radionuclides released (arem/yr), frf each K,g = the. skin dose factor due to beta and gamma emissions identified noble gas radionuclide (ares /yr per pCi/m ) from Table 2.2-1, C = the station ventilation exhaust duct release concentration of gg radionuclide, i, (pCi/cc) (from isotopic analyses performed on the gaseous sample taken from the station ventilation exhaust monitor), C = the air removal pump ventilation exhaust duct release 12 d concentration of radionuclide, 1, (pCi/cc) (from the isotopic analyses performed or, the gaseous sample taken from the air removal pump discharge monitor), C = the containment drywell purge ventilation exhaust concentration of g3 radionuclide, i, (pCi/cc) (from the isotopic analyses performed _on the gaseous sample taken from the containment drywell filter train exhsust monitor), V = 1.7E+08 cc/sec (3.60E+05 cfa), station ve stilation exhaust duct g ventilation exhaust flow rate, V = 5.70E+05 cc/sec (1200 cfa), air removal pump exhaust duct 2 ventilation exhaust flow rate, V = 5.70E+05 cc/sec (1200 cfa), containment drywell purge ventilation i 3 exhaust flow rate, X/Q1 = annual ' average X/Q at 366 meters NNE due to release via the station ventilation exhaust puint (6.6E-07 sec/m)), 4 i h O BN1-11600.02-92 3.3-7 Revision. 1 - August 1983 _ -, - _,. -. _ _.. ~ - - _ _,. _.. - _ - -

SNPS-1 ODCM Cj N X/Q2 = annual average short tern X/Q at 366 meters NNE due to air removal pump release via the station ventilation exhaust point 3 (3.6E-06 sec/m ), x/Q3 = annual average short term x/Q at 366 meters NNE due to containment drywell purge via the station ventilation exhaust point 3 (3.6E-06 sec/m ). 3.3.2.3 Organ Dose Rate (particulate releases) 0 D = E (10 *R *P

• x/Q *(C V

-C V -C V )) g g g g 3 3 0 g] + V

• E (10 *R
• P
• X/Q
• C 2

2 g +V*E(106 *R, *P

• X/Q
• Cg3)

Imrem/yr) 3 3 During periods of no intermittent releases, such as no main condenser air removal pump operation and no containment drywell purge, the above formula reduces to the following: 0

• R,
• P
• X/Q
• C (mrem /yr)

D = V

• I 10 g

g where: 1 D,3 = total dose rate to organ, j, mrem /yr. O) P = the inhalation dose conversion factor, for radionuclides other ij than noble gases, i, and organ, j, in arem per pCi from Table 3.5-3. The dose factor P is based on the critical individual organ for the Child group, w ich is most restrictive. 3 R, = inhalation rate (m /yr), from Table 3.5-5. C = the station ventilation exhaust duct release concentration of gg radionuclide, i, (tCi/cc) (from the isotor".c analyses performed on the filter - paper and charcoal cartridge taken from the station ventilation exhaust monitor), C = the air removal pump ventilation exhaust duct release 12 concentration of radionuclide, i, (tCi/ce) (from the isotopic analyses performed on the iodine and filter cartridge taken from the air removal pump discharge monitor),

A Q

BN1-11600.02-92 3.3-8 Revision 1 - August 1983 5 n, -n -m-, w. ,,,e. .,--m ,---e --w

} SNPS-1 ODCM g3 the containment drywell purge ventilation exhaust concentration of C = \\ radionuclide, i,- (pci/cc) (f rom the isotopic analyses performed on the gaseous sample taken from the containment drywell filter train exhaust monitor), 1.70E+08 cc/sec (3.60E+05 cfa), station ventilation exhaust duct V I ventilation exhaust flow rate, 5.70E+05 cc/sec (1200 cfa), air removal pump exhaust duct V = 2 ventilation exhaust flow rate, 5.70E+05 cc/sec (1200 cfa), containment drywell purge ventilation V = 3 exhaust flow rate, annual average X/Q at 1931 meters ESE due t releases via the X/Q1 = 3 station ventilation exhaust point (6.6E-07 sec/m ), y/Q2 annual average short term X/Q at 1931 meters ESE due to condenser = airremovalpuy),releaseviathestationventilationexhaustpoint (3.6E-06 sec/m annual average short term X/Q at 1931 meters ESE due to X/Q3 = containment drywell purge via the station ventilation exhaust 3 point (3.6E-06 sec/m ). O l N BN1-11600.02-92 3.3-9 Revision 1 - August 1983 e s e.- ,,n ,.-r ,e-.. -c,,. ,,..,e .-m .,,-..,,,,.-,---e.,-.,

O O O SNPS-1 ODCM TABLE 3.3-1 CilILD INHA1ATION DOSE RATE CONVERgION FACTORS, P ) g (aree/yr per LCi/m ) Isotope Bone Liver T. Body Thyroid Kidney Lung CI-LLI Cr-51 CI) 3.4E+01 2.1E+01 7.9E+00 4.9E+03 1.1E+03 Mn-54 1.3E+04 2.1E+03 3.3E+03 4.9E+05 2.6E+04 Fe-59 4.0E+03 9.3E+06 3.5E+03 3.4E+05 6.5E+04 Co-58 1.1E+02 2.0E+02 1.1E+06 2.7E+04 Co-60 7.8E+02 1.3E+03 5.2E+06 7.0E+04 l 2h-65 1.1E+04

• 3.6E+04 1.5E+04 2.4E+04 2.9E+05 1.8E+04 Sr-89 3.9E+04 1.1E+03 1.6E+06 1.2E+05 3

Sr-90 1.2E+07 7.3E+05 1.1E+07 2.5E+05 2r-95 1.0E+04 2.4E+03 2.2E+03 1.8E+04 1.6E+06 4.3E+04 Sb-124 1.1E+04 2.0E+02 4.1E+03 2.6E+01 8.3E+05 1.4E+05 I-131 3.3E+04 3.4E+04 2.6E+04 1.1E+07 2.1E+04 1.9E+03 1-133 1.3E+04 1.5E+04 6.1E+03 3.7E+06 8.7E+03 i 4.1E+04 Cs-134 4.7E+05 7.3E+05 1.7E+05 9.9E+04 8.8E+04 3.8E+03 Cs-136 1.3E+04 4.8E+04 3.7E+04 2.9E+04 4.2E+03 1.7E+03 i Cs-137 6.4E+05 5.9E+05 9.1E+04 7.5E+04 7.3E+04 5.7E+03 i Ba-140 5.3E+03 3.4E+04 3.OE+02 5.7E+00 1.3E+06 7.3E+03 Ce-141 2.3E+03 1.1E+03 1.7E+02 2.2E+03 3.7E+05 4.1E+04 4 1 (I) The dash (-) indicates insufficient data or that the dose factor is <1.0E-20. l i i l l I 4 i BN1-11600.02-98 1 of 1 Revision 1 - August 1983

3 8 O I 9 ER T T 1 E I EM N T SP " U S g AS - L U R ,T Eo NA G E f/. ,IF RA LTA t gL Lw OU U Ef IN A. r u EAM N f E T T DS O S S O N I LR Y R S AE S MEIO IV De S N WT E CR A A TOA R R0 G F NPL A5 l ERC U M0 F CA FO UAL w LEA FLC tFCUE - E SNO

5. S R

3 MD S E 1 UAE p EOhT REEI o ~ USRS OF GA HF M FGSO I t G u m C o &v L l AR lu L IE T A CSS N S C FIRD E 4 sOE Mu E N E N aSB W e A T 8 M CO 4A AS N C TY U F NS T W OCEG TR Ru V =P l ll._ AF w a R P a 7 N _A A S F _F N F N l g A p F R T RE N ES E LN U OE L R OD F A B CN E F P S O T F E R L C E HI g P F T M l I s B L U F es P E O M G U R I U UB_ T A C P ) i A = l V g T g N L Eg Tg f A A v C g I E$ l N MN t a A RE u M ED p u R C PN ll 0 E uO 5 N W C E D ( N0 s$ G N G S G l N IN o E I R D eL D P !u e L R L P u U E tu B m B E _8 R D E T T A l S O N N A 8 e C L R A D L U R E A E T R R m Y RO .c) S R E T A E H E N N N R A A A P F F F s \\ l da R R S R E E R EO E T T L tL GT T I F L AC I F TE F E E SJ E R R E RP P P 2 aMq As f O s R "r \\ $c $[ I j i 4 i i i,. i

SNPS-1 ODCM [ 3.4 GASEOUS EFFLUENTS, NOBLE CAS AIR DOSE To comply with Section 3.11.2.2 of the RETS, the air dose in unrestricted area location due to releases via the station ventilation exhaust point shall be limited to the following: 1. During any calendar quarter: Imss than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation. 2. During any calendar year: Iass than or equal to 10 mrads for gamma radiation and less than or equal to 20 meads for beta radiation. 3.4.1 Method 1: (Computerized Method) Cumulative doses are calculated by making use of hourly dose rate equations presented in the following subsections. 3.4.1.1 Release Estimation Dose estiastion is carried out every hour by making use of the atmospheric dispersion data computed every hour, and of the following equation for the release ra;.e (Ci/hr): Q = F* f 1 t where: 60 F* =k I F (j) 0ng(j ) At e j.1 q (d / U,g M f = 10 g g 3 k = 2.832 x 104 (cc/ft ) F,(j) = vent flow rate during interval j (cfa) 6 (j ). = noble gas effluent monitor count rate during interval j ng (ep ) at = time interval (= 1 minute) e qt = concentration of isotope i in the effluent as measured in the lab at time t (pCi/cc) F* = 60-minute average of the flow and count-rate product [(cc/hr) (cpa)] 60 = number of at intervals per hour (1/hr) l l' BN1-11600.02-92 3.4-1 Revision 1 - August 1983 l _. _. ~. - _, _.. _ _ _. _ -_. _. ~ _., _. _ - _.. -.. _. _. _. _...... ~, - - _. _. _ _ _. _,,..

SNPS-1 ODCM - 3.4.1.2 Noble Gas Gamma Air Dose DY, air (X/Q)y F* 3.17 x 10 I f DF g g nobles where D, air y gamma dose to air at - the site boundary in the downwind = sector during the period of release (arad/hr) (Ref.: Reg. Guide 1.109 Eqs. B-4 and B-5, and also Eq. B-1 with the substitution of (X/Q)y (X/Q)Y finite-cloud sector-average 'ganga' dilution factor at = the downwind site-boundary [sec/m ] T gamma dose to air conversion f actor (f rom Table B-1 of DF = 3 Reg. Guide 1.109) [(arad/yr)/(pCi/m )] g Qg (Ci/hr) (see Section 3.4.1.1) F*f = 3.4.1.3 Noble Gas Beta Air Dose D[g (X/Q) F* 3.17 x 10 E f D, air S g nobles where beta dose to air at the site boundary in the downwind D, air = S sector during the period of release [arad/hr] (Ref.: Reg. Guide 1.109, Eqs. B-4 and B-5) conversion f actof (f rom Table B-1 of beta dose to air DF = Reg. Guide 1.109) [(arad/yr)/(pCi/m )] (Ci/hr) (see Section 3.4.1.1) F*f Qi = g (X/Q)88 sector-average concentration dilution factor at the site = 3 boundary during the period of release [sec/m ] O {. BN1-11600.02-92 3.4-2 Revision 1 - August 1983 ...m, ..y, _.-._..e, m.-_v._,-, ..,,..y_ om.f-,,-__-_,_._ _,. - _, -.., .-.......-__,.,--.y ,,-e.-.,,--.,--my

SNPS-1 ODCM /m ( 3.4.2 Method 2: (Backup Method) s 3.4.2.1 Noble Gas Gamma Air Dose The general equation is: 1 D = 3.17E-08 *X/4 *[ (M *(C 1 *1 12 2 *2 13 3 3* ) ~ ~ g 3 g il s 2 **2 *X/Q *f (M *C 2] + 3.17E-08 *V 2 i

• t
• x/Q * { [M
• Cg3)

(mrad ) + 3.17E-08 *V3 3 3 g During periods of no intermittent releases, such as no main condenser air removal pump operation and no containment drywell purge, the above formula reduces to the following: 13) (arad) D = 3.17E-08*V

• t
• X/Q *E(M
• C g

1 3 g g 1 where: D = the total gamma air dose from the releases (mrad), g 3.17E-08 = the inverse of number of seconds in a year, M - the air dose factor due to gamma emissions for eagh g identified noble gas radionuclide (arad/yr per pCi/m ) from Table 3.4-1, tg = 7.88E+06 see for quarterly dose calculation, = 3.15E+07 sec for yearly dose calculation = release period (sec) for condenser air removal pump t 2 = release period (sec) for containment drywell purge t 3 exhaust C = the station ventilation exhaust duct release gg concentration of radionuclida, i, (pCi/cc) (from the isotopic analyses performed on. the gaseous sample taken from the station ventilation exhaust monitor), C = the - air removal pump ventilation exhaust duct release 12 concentration of radionuclide, 1, (pCi/cc) (from the isotopic analyses performed on the gaseous sample taken from the air removal pump discharge monitor), C = the containment drywell purge ventilation exhaust g3 concentration of radionuclide, i, (pCi/cc) (from the isotopic analyses performed on the gaseous sample taken from the containment drywell filter train exhaust monitor), D) (%J BNi-11600.02-92 3.4-3 I:evision 1 - August 1983

SNPS-1 ODCM V - 1.70E+08 cc/sec (3.60E+05 cfa), station ventilation 3 exhaust duct ventilation exhaust flow rate, s V = 5.70E+05 cc/sec (1200 efm), air removal pump exhaust duct 2 ventilation exhaust flow rate, V - 5.70E+05 cc/sec (1200 cfa), containment drywell purge 3 ventilation exhaust flow rate, = annual average X/Q at 457 meters ESE due to release via X/Q1 3 the station ventilation exhaust point (8.44E-07 sec/m ), X/Q2 = annual average, short tern X/Q at 457 meters ESE due to the station condenser air removal pump release vga ventilation exhaust point (1.83E-06 sec/m ), X/Q3 = annual average, short term X/Q at 457 meters ESE due to containment drywell purge release via the station ventilation exhaust release point (1.83E-06 sec/m ). 3.4.2.2 Noble Gas Beta Air Dcse The general equation is: 3'3)) -08* x/Q M [N *(C Vt -C 2 '2 13 Y D ~ = g i ig gg 12 Bs i 2] + 3.17E-08* X/Q

• V *"2 *I(N
• C 2

2 g g3} (mrad) + 3.17E-08

• X/Q
• V *t *I(N
• C 3

3 3 g i During periods of no intermittent releases, such as no main condenser air removal pump operation and no containment drywell purge, the above formula reduces to the following: g) (arad) D = 3.17E-08 *X/Q *V

• t E[N
• C B

i i t g s i where: D = beta air dose from all radionuclides released (Brad), gs N = the air dose factor due to beta emissions for eagh i identified noble gas radionuclide (mrad /yr per pCi/m ) from Table 3.4-1, 3.17E-08 = the inverse of number of seconds in a year, t% \\ )- %/ BN1-11600.01-92 3.4-4 Revision 1 - August 1983 s

S;iPS-1 ODCM tg = 7.88E+06 see for quarterly dose calculation, O = 3.15E+07 sec for yearly dose calculation, = release period (sec) for condenser air removal pump, t 2 = release period (nac) for containment drywell purge t3

exhuast, C

= the station ventilation exhaust duct release tg concentration of radionuclide, i, (pCi/cc) (from the isotopic analyses performed on the gaseous sample taken from the station ventilation exhaust 2aonitor), 12 = the air removal pump ventilation exhauat duct release C concentration of radionuclide, 1, (pCi/cc) (from the isotopic analyses performed on the gaseous sample taken from the air removal pump discharge monitor), = the containment drywell purge ventilation exhaust C13 concentration of radionuclide, i, (pCi/cc) (from the isotopic analysis performed on.the gaseous sample taken from the containment drywell filter train exhaust monitor), V = 1.70E+08. cc/sec ~(3.60E+05 cfa), station ventilation i exhaust duct ventilation exhaust flow rate, V = 5.70E+05 cc/sec (1200 cfa), air removal pump exhaust duct 2 ventilation exhaust flow rate, V = 5.70E+05 cc/sec (1200 cfs), containment drywell purge 3 ventilation exhaust flow rate, - annual average X/Q at 457 meters ESE due to release via X/Q1 3 the station ventilation exhaust point (8.44E-07 sec/m ), X/Q2 = annual average short tern X/Q at 457 meters ESE due to i the station condenser air removal pump release 3a ventilation exhaust point (1.83-06 sec/m ), and X/Q3 = annual average short tern X/Q at 457 meters ESE due to containment drywell purge release vig the station ventilation exhaust point (1.83E-06 sec/m ). I BN1-11600.02-92 3.4-5 Revision 1 - August 1983 I

SNPS-1 ODCM TABLE 3.4-1 NOBLE GAS DOSE FACTORS Gauna Air Beta Air Dose Factor Dose Factor g N 3 g 3 Isotope (arad/yr per tCi/m ) (mrad /yr per ICi/m ) Kr - 83m 1.9E+01 2.9E+02 Kr - 85m 1.2E+03 2.0E+03 Kr - 85 1.7E+01 2.0E+03 Kr - 87 6.2E+03 1.0E+04 Kr - 88 1.5E+04 2.9E+03 Kr - 89 1.7E+04 1.1E+04 Kr - 90 1.6E+04 7.8E+03 Xe - 131m 1.6E+02 1.1E+03 Xe - 133m - 3.3E+02 1.5E+03 Xe - 133 3.5E+02 1.1E+03 Xe - 135m 3.4E+03 7.4E+02 Xe - 135 1.9E+03 2.5E+03 Xe - 137 1.5E+03 1.3E+02 Xe - 138 9.2E+03~ 4.8E+03 Ar - 41 9.3E+03 3.3E+03 BN1-11600.02-112 1 of 1 Revision 1 - August 1983

.m SNPS-1 ODCN O 3.5 GASEOUS EFFLUENT, DOSE DUE TO RADIOIODINES AND RADIOACTIVE MATERIALS IN Pt.RTICULATE FORM AND RADIONUCLIDES.(other than ' Noble Gases) WITH HALF-LIVES GREATER THAN 8 DAYS . To comply with Section 3.11.2.3 of the Radiological Effluent Technical ) Specifications, the organ dose to maximum individual in unrestricted area due i to radioiodines and particulates releases via the station ventilation exhaust I point shall be limited to the following: 1. During any calendar quarter Less than or equal to 7.5 mres to any organ, and 2. During any calendar year: Less-than or equal to 15 mrem to any organ. 3.5.1 Method 1: (Computerized Method) Cumulative doses are calculated by making use of hourly dose rate equations presented in the following subsections. 3.5.1.1 Release Estimation Dose. estimation is carried out every hour by making use of the atmospheric dispersion data computed every hour,- and of the following equation for the release rate (Ci/hr): = F* f Q1 t where: 60 r F,(j) d,g(j ) & l F* =k E j=1 -6 qi(T) j gng ( t) f = 10 t k = 2.832 x 100 (cc/ft3) F,(j ) = vent flow rate during interval j (cfa) l-ng(j ) = noble gas effluent monitor count rate during interval l .C j (ep ) At = time interval (= 1 minute) l qi = concentration of isotope i in the effluent as l-measured in the lab at time r ( $1/cc) F* = 60-minute - average of the flow and count-rate product [ [(cc/hr) (cpa)] 60 = number of at intervals per hour (1/hr) \\ BN1-11600.02-112 3.5-1 Revision 1 - August 1983 t I l u. _.. _. _ _... _ _. _ _. _. _ ~ ~ _ _, _.. -

SNPS-1 ODCM (~N 3.5.1.2 Total Body Dose elnd D "h + D i E#""E D =D + wb wb wb wb where: U" = (x/Q)*T* F* 2.22 x 10 E f DFB D i i nobles D = (X/Q) F* 3.17 x 10 R f DFA b ad i g = (D/Q) F* 7 x 10" I f DFGil [1 - eM]/ A D g i part+1 D" " = total body dose due to direct radiation from the radioactive cloud [mres/hr] (Ref.: Reg. Guide 1.109 Eq. B-8; also similar to Eq. d-6 if one makes use of DF[ dose the gamma (x/Q) and the DFB instead of g conversion factor) D "h = total body dose (j = total body) due to inhalation i a [ ares /hr] (Ref.: Reg. Guide 1.109, Eqs. C-3 and C-4, for an adult) grand D = total body dose due to particulate and iodine wb radioactivity depositing on the ground [mres/hr] (Ref.: Reg. Guide 1.109, Eqs. C-1 and C-2 with the product 8760 [hr/yr] (1/ A [yr] replaced by [1/ A [hr] and parameter 6 (r,0)g) represented by the (D/Q)g) g ). DF8 = gamma dose to body conversion factor g 3 [(ares /yr)/(pCi/m )] (from Table B-1 of the Reg. Guide) DFA = dose conversion f actor for nuclide i to organ j of an ij,ad adult individual [eres/pCi inhaled] (from Tables E-7 through E-10 of Reg. Guide 1.109) DFG = total body conversion factor for standing on ig 2 contaminated ground [(ares /hr)/(pCi/m )] (from Table E-6 of Reg. Guide 1.109) l - ( X/Q)88 = concentration dispersion factor (sector-average model)3)or the period of release (site boundary only) f (sec/m p ~BN1-11600.02-112 3.5-2 Revision 1 - August 1983 b 4

SNPS-1 ODCM C ( X/Q)*I = gamma ( X/Q) (finite cloud sector-average model) 3for the period of release (site boundary only) (sec/m ) (D/Q) =partgculate deposition rate (site boundary only) (1/n ) F* f = Qg (C1/hr) (as defined in Section 3.5.1.1) 4 i 3 R = adult breathing rate (m /yr) (from Table E-5) l ad A = radionuclide decay constant (1/hr) g b =timeperiodoverwhichtheacepulationisevaluated, t which is 15 years (1.314 x 10 hours) (Reg. Guide pg 1.109-24) 0 12 (8760 x 3600) [(pci/C1) (yr/sec)] / 3.17x10 = 10 '2.22x10 = 3.17 x 10' x 0.7, where 0.7 is the shielding f actor 0 which. accounts for the dose reduction due to the shielding effects of residential structures during occupancy (Ref.: Reg. Guide 1.109 Table E-15) 12 7x10ll = 10 x 0.7, where 0.7 is the shielding factor and 1012 is the number of pCi per C1 (see Eqs. C-1 and C-2 of the guide) part+1 = 68 particulates and 5 iodines in the summation sign 4 i Note that the total ' total body' dose as computed above is used only for hcurly assessment of plant operation within the specification limits. The reports prepared by the dose software include the total body dose due to inhalation - as a separate parameter. Also note that the equation conservatively includes the dose due to the airborne noble gases, even though this section addresses only the iodines and particulates. 3.5.1.3 h. Dose l E# "" = D" kin + D D s skin skin where: p Y D" kin 1.11 x 0.7 ( X/Q)Y F* 3.17 x 10 E f DF = s i i nobles + ( X/Q)* F* 3.17 x 10 E f DFS g i nobles i bN1-11600.02-112 3.5-3 Revision 1 - August 1983 i ,,. + + ....,,,,~~r- ,n ._,,_n, ,-,-,-,--,,,..,,...n..,--m.,,..,.-..,,-.c-g. ,,r,.

SNFS-1 ODCM /m nd D = (D/Q) F* 7 x 10 I f DFGi2[1 - e b i]/A g g part+I C " D = skin dose due to direct gamma radiation from the radioactive cloud (first component of the equation with finite cloud modeling) and beta radiation (second component, semi-infinite cloud immersion) [mrea/hr] (Ref. : Reg. Guide 1.109 Eq. B-9; also similar to Eq. B-7 if one makes use of the gamma (X/Q)) E# "" D = skin dose due to particulate and iodine radioactivity depositing on the ground [arem/hr] (Ref.: Reg. Guide 1.109, Eqs. C-1 and C-2 with the product 8760[hr/yr] (1/A )[yr] replaced by (1/A )[hr] and parameter o g 1 g (r,0) represented by the (D/Q)) T DF = gamma dose to air conversion factor 3 [(arad/yr)/(pCi/m )] (from Table B-1 of the Guide) skin conversion factor DFS = beta dose g go [(arem/yr)/(pCi/m )] (from Table B-1 of the Guide) DFG' = skin dose conversion factor for standing on 2 contaminated ground [(arem/hr)/(pCi/m )] (f rom Table E-6 of Reg. Guide 1.109) 1.11 = average ratio of tissue to air energy absorption coef ficient (f rom Reg. Guide 1.109, pg 1.109-6) 0.7 = shielding dose-reduction f actor (see pg 1.109-68) and the remaining parameters are as defined above in Section 3.5.1.2. Note that the total skin dose as described here includes the contribution of airborne noble gases, even though this section addresses only the iodines and particulates. I i l /7 BN1-11600.02-112 3.5-4 Revision 1 - August 1983 l

SNPS-1 ODCM 3.5.1.4 Organ Doses Due to Inhalation D" (X/Q) F* 3.17 x 10 R paht+1 ^ija = i a where: D" = dose to organ j of individual in age group a due to 38 inhalation of airborne radioactivity [ mrem /hr] (Ref.: Reg. Guide 1.109 Eqs. C-3 and C-4) DFA ), = dose conversion f actor for nuclide i to organ j of g individu*i in age group a [mrea/pCi inhaled] (from Tables E-7 through E-10 of ths Guide) R = breathing rate of individual in age group a [m /yr] a (f rom Table E-5 of Reg. Guide 1.109, f or the maximum individuals) 3.5.1.5 Organ Doses Due to Ingestion of Leafy Vegetables (gng) part + (D "E) iodines + (Dja ) C14 D "E ng = ja ja ja ng + (Dja)H3 where: (D,8) n (D/Q) F* 1.1 x 10 p{g g U f DFI = part 0.2 iv -241 2(Ag + 0.0020 240 A g (D (D/Q) F* 5.5 x 10 g,, U f DFI = g 1.0 iv -24A + l 2(A1 + 0.0021) 240 A g ( D ",E) = (x/Q)** F* 2.2 x 10 U f DFI C14 CNa C14 7 ( D "E) = (x/Q)sa * ( * ** )U f DFI F H '$

• ja H3 l

l BN1-11600.02-112 3.5-5 Revision 1 - August 1983 l l

SNPS-1 ODCM i (D ",8 ) dose to organ j of individual in age group a due to = g d part ingestion of lecfy vegetables contaminated with particulate radioactivity [ mrem /hr) (Ref.: Reg. Guide Eqs. C-5, C-6 and. C-13 for leafy vegetables only, j with the following: o r(fraction of deposited activity retained on crops) = 0.2 (see pg 1.109-68 of the Guide) e t, (time period that crops are exposed to contamination during growing season) = = [ hrs] b (tima period over which the accumulation is et evaluated) = = [ hrs] (tim delay between harvest of vegetation or et h crops and ingestion) = 24 [ hrs] 2 e Y,(agricultural productivity) = 2 [kg/m j 2 e P (soil effective surface density) = 240 [kg/m g t= Ag + 0.0021 [hr~I) (Ref.: Reg. Guide 1.109, e pgs 1.109-4 and 1.109-69) edi (r,0) = (D/Q) [m-2) O - e fg (fraction of leafy vegetables growing in garden of interest) = 1.0 (D "8 ) = dose to organ j of individual in age group a due to 3" iodines ingestion of leafy vegetables contaminated with radioiodines [mres/hr] (Ref.: Reg. Guide 1.109 Eqs. C-5, C-7 and C-13 for leafy vegetables only; similar to the organ dose due to particulate radioactivity 1.0 and different given above but with r- = multiplying constant) I (D ",8 ) dose to organ j of individual in age group a due to = C14 ingestion of leafy vegetables exposed to airborne Carbon-14 [erea/hr] (Ref.: Reg. Guide 1.109, Eqs. C-8 and C-13 for leafy vegetables only, with p (the ratio of the total' annual release time to the total annual time during which photosynthesis occurs) = 1) 8 (D3" )H3 dose to organ j of individual in age group a due to = ingestion of leafy vegetables exposed to airbarne tritium [mrea/hr] (Ref.: L.g. Guide 1.109 Eqs. C-9 and C-13 for leafy vegetables only) BN1-11600.02-112 3.5-6 Revision 1 - August 1983 ) 1 i d w - - --,-,-...,-wcy- ,.,.-w-vn.,e-nw-., -,-w -,---+y. -i.,-,.-.,, ,%-F c-..- .+.----pm,_-,. ,,w

• w,-

SNPS-1 ODCM f U = ingestion rate of leafy vegetables by individual in i age group a (from Table E-5 of the Guide, maximum individual) [kg/yr] B, = concentration factor for uptake of radionuclide i g from soil by edible parts of crops [(pC1/kg)(wet weight)/ (pCi/kg) (dry soil)] (Ref.: Reg. Guide 1.109, Table E-1) DFI = dose conversion factor for nuclide i to organ j of kja individual in age group a due to ingestion of contaminated food [ mrem /pCi ingested] (from Tables E-11 through E-14 of the Guide) DFI = OFIgj,for Carbon-14 C14,j a = DFI ),for tritium DFIg3,3, g F "f for Carbon-14 (see Section 3.5.1.1 above) C14 i f =f for tritium g3 g the atmosphere at the location = absolute humidity] of H of interest [g/m 3.5.1.6 Infant Thyroid Dose Due to inhalation and Ingestion of Cow Milk inh milk =D + j Dthy,inf thy,inf thy,inf where: milk ailk D = (Dthyinf) + (Dthy,inf) iodines thy,inf part + (Dthy,inf)H3 + (Dthy,inf)C14 D "hy A f. = (x/Q) F* 3.17 x 10 R E f DFA g gg g g (D "(! inf nf 'i DFli, thy,inf part part 0.2 iv -48A x 50 F g ai t.75(Ag + 0.0021) 240 Ag U" f (Dthy,inf) iodines f DFI = (D/Q) F* 5.5 x 10 I in i 1, thy,inf iodines 1.0 iv -48A x 50 F + ~* g oi b.75 ( Ag + 0.0021) 240 A g Ak) BN1-11600.02-112 3.5-7 Revision 1 - August 1983

_ _ _ = SNPS-1 ODCM (D inf C14 x 50 F exp(-48 AC14 7 ( tag)M3 } H nf H3 b3, thy,inf i x 50 F,,g3 exp(-48AH3) inh D = inf ant thyroid dose due to inhalation of airborne thy, int radioactivity [ area /hr] (Ref.: Reg. Guide 1.109 Eqs. C-3 and C-4) = inf ant thryoid dose due to ingestion of' milk (D*I'I")part contaminated with radioactive particulates [mres/hr] I (Reg. Guide Eqs. C-5, C-6, C-10, C-11 and C-13) f or milk, with the followings er (fraction of deposited activity retained on crops) = 0.2 (see pg 1.109-68 of the Guide) e t, (time period that crops are exposed to contamination during growing season) = = [ hrs] . b) (time period over which accumulation is V etb evaluated) = = [ hrs] h (time delay for ingestion of forage by animals) et= 0 [ hrs] (see pg 1.109-69 of Reg. Guide) e Y, (agricultural propuctivity, grass-cow-milk-man. pathway) = 0.75 [kg/m ] (Reg Guide 1.109, Rev. 0) 2 e P (soil eff ective surf ace density) = 240 [kg/m j A [hr-'] (see pgs 1.109-4 and 1N09-69f + 0.0021 eA =

• 61 (r,e) = (o/q) [a-2; e tg (average transport time of activity from the feed into the milk and to the receptor) = 48 [ hrs]

ef (fraction of the year that animals graze on pIsture)=1(conservativeassumption) f -'-"'o -" " ' " ' - ^" " ' '' O 4 A w 3- -,,,,..y.-e. ,,-.,w--+..,.,,,,,3 vw v,-c., ,y,,-w,-,-.-y. .----,,,w-, ,--,--m,..,-- ,y.-wy_,--wen gr, # -m,,-=**wvr' '*wW

• -----"we-'W-+"w'

l SNPS-1 ODCM w$en(f raction of daily feed that is pasture grass O ef the animal grazes on pasture) 1 ( = (conservative assumption) (D"hy,inf) iodines= infant thyroid dose due to ingestion of milk t contaminated with radio-iodines [ mrem /hr] (Ref. : Reg. Guide Eqs. C-5, C-7, C-10 C-11, and C-13 for milk; similar to the inf ant thyroid dose due to the ingestion of particulates given above, with the exception of a dif f erent multiplying factor and r = 1.0) (D**I'i")C14 = inf ant thyroid dose due to ingestion of milk contaminated with C14 [mres/hr] (Ref.: Reg. Guide 1.109. Eqs. C-8, C-10, C-11 and C-13 f or milk, with p (the ratio of the total annual release time to the total annual time during which photosynthesis occurs) = 1, and tg, f, and f, as given above f or p the particulates) (Dthy,inf)H3 = infant thyroid dose due to ingestion of milk contaminated with tritium [ mrem /hr] (Ref.: Reg. Guide 1.109, Eqs. C-9, C-10, C-11, and C-13 for milk, with e, f, and f, as given above f or the particulates)g p 3 [m /yr] (f rom Table E-5 of R,g = infant breathing rate g the Guide, for maximum individual) 'd DFA1. thy,inf = dose conversion f actor for nuclide i to the infant thyroid due to inhalation [ mrem /pCi inhaled] (f rom Table E-10 o6 the Guide) DFI, thy,inf = dose conversion f actor for nuclide i to the inf ant i thyroid due to ingestion [ ares /pCi ingested] (f rom Table E-14 of the Guide) = DFI, thy,inf for Carbon-14 DFIC14, thy,inf i DFI = DFI, thy,inf f or tritium i H3, thy,inf F "f for Carbon-14 (see Section 3.5.1.1 above) C14 i F "f for tritium H3 i U" = milk ingestion rate by inf ant [ liters /yr] (Ref. : Reg. Guide 1.109, Table E-5, aux ind.) F,1 = average fraction of the animal's daily intake of radionuclide i which appears in each liter of milk [ days / liter] f rom Table E-1 of the Guide, with F, = F,g, for cow) A) iv BN1-11600.02-112 3.5-9 Revision 1 - August 1983 t ,,,,,r...

SNPS-1 ODCM (O B = concentration factor for uptake of radionuclide i V) from soil by edible parts of crops [(pCi/kg) (wet gy weight) / (pCi/kg) (dry soil)] (from Tablo E-1 of. the Guide) =absolutehumidity]oftheatmosphereatthelocation H of interest [g/m 50 = amount of feed consumed by a cow per day [kg/ day] (from Table E-3 of the Guide, Qp factor) 48 = average transport time of activity from the feed into the milk and the receptor [ hrs] (see page 1.109-27 of the Guide) O BN1-11600.02-112 O 3.5-10 Revision 1 - August 1983 1

SNPS-1 ODCM [% Y 3,5.2 Method 2: (Backup Method) 3.5.2.1 Organ Doses: 0 =3.17E-08*p((10*R,*P

• dQg+P aD/Q )*

D g g ig g g i2 2 2 13 3 **3) (C

• V
• t

-C

• Y

~ 2 **2 *(((106 *R, *P

• dQ2+P
• D/Q )*Cg)

+ 3.17E-08* V g 2

• [((100
• R,
• P
• dQ3 + P,g) *D/Q )*Cg3)

(mrem) + 3.17E-08 *V

• t gj 3

3 3 (3.5.2-1) During periods of no intermittent releases, such as no main condenser air removal pump operation and no containment drywell purge, the above formula reduces to the following: g [ ((106

• R,
• P
• y/Qg+P
• D/Q )*Cgg )

(mrem) D) = 3.17E-08 *V

• t q

g t (3.5.2-2) where D = total dose to organ j (arem), j P = the inhalation dose conversion factor for radionuclides, i, (other ij than noble gases), and organ j, (arem per pCi inhaled) from Table 3.5-3, 3 R, = inhalation rate (m /yr) from Table 3.5-5, P = the dose conversion f actor for radionuclides, other than noble ogj stored

gases, i,

and organ j, for the leafy vegetpbles, vegetables, and contaminated ground pathways in n (arem/yr per ICi/see) respectively, from Table 3.5-9. P on the critical individual The dose factors P )g,roup, are based g agj organ for the child since this group is most restrictive. =[.88E+06seeforquarterlydosecalculation tg. '~ = 3.15E+07 see for yearly dose calculation, 2 = release period (sec) for condenser air removal pump, t c3 = releace period (sec) for containment drywell purge exhaust, BN1-11600.02-112 3.5-11 Revision 1 - August 1983

~ SNPS-1 ODCM ' p -C g = ths station ventilation exhaust duct release concentration of i 4 radionuclide, i, (Wi/cc) (from the isotopic analyses performed on the iodine and filter cartridge taken from the station ventilation exhaust monitor), C12 = the air removal pump ventilation exhaust duct-release i concentration of radionuclide, i, ( $1/cc) (from the isotopic analyses performed on the iodine and filter cartridge taken from the air removal pump discharge monitor), C = the contsinnent drywell purge ventilation exhaust concentration of g3 radionuclide, i, ( Wi/cc) (from the isotopic analyses performed on the gaseous sample taken from the containment drywell filter traia exhaust monitor), g 1.70E+08 cc/sec (3.60E+05 cfa), station ventilation - exhaust duct V i ventilation exhaust flow rate, V = 5.70E+05 ' cc/sec (1200 cfa), air removal pump exhaust duct 2 ventilation exhaust flow rate, V' = 5.70E+05 cc/sec (1200 efa), containment drywell purge ventilation 3 exhaust flow rate, 4 X/Q1 = annual average WQ at 1931 meters ESE due to releases via the 3 station ventilation exhaust point (1.3E-07 sec/m ), X/Q2 = annual average short tera x/Q at 1931 meters ESE due to condenaer airremovalpugpreleaseviathestationventilationexhaustpoint (6.0E-06 sec/a ), 1 X/43 = snnual average short tera x/Q at 1931 meters ESE due to containment drywell purge da the station ventilation exhaust 3 -point (6.0E-06 sec/a ) 4 D/Qt = annual-average D/Q deposition factor at.1931 meters ESE = dug)to releases via the station ventilation exhaust point (8.6E-09 a-D/Q2 = annual average short tera D/Q deposition factor at 1931 meters ESE i due to condenser air removal pump releases via the station ventilation exhaust point'(4.0E-08 a-2) I' 'D/Q3 = annual average short tera D/Q deposition factor at 1931 meters ESE due to containment drywell purge exhaust via the station ventilation exhaust point (4.0E-08 a~ ). 3.17E-08 = Inverse of 3.15E+07 sec/yr. i i BN1-11600.02-112-3.5-12 Revision 1 - August 1983 ... -,.. _. -.._._...,_.._.._-__.-.,, _.._...._.._ _ _ _.~._.. _ _..-._, _.

SNPS-1 OCCM ' NOTE: If the land use census (see Table 3.5-8) changes, the critical location, i.e., the location where an individual would be exposed to the highest dose, must be reevaluated using Equation 3.5.2-1 for each of the following locations: 1. nearest residence, 2. nearest vegetable garden, and 3. nearest milk cow or goat. P used in Equation 3.5.2-1 vill include the values in Tables 3.5-10 through ot 3.5)-14, if those pathways exist. At each location, the following pathways must be considered and dose (dose rates) reevaluated if any actual pathway exists: 1.- inhalation, 2. leafy vegetables (fresh), 3. stored vegetables, 4. goat's or cow's milk (if both exist choose the one resulting in a higher dose), and 5. deposition on ground. Since a person will always be present, pathways 1 and 5 must always be evaluated. 4 Once the location of the critical individual is determined and found to be other than the one at 1931 meters ESE, the values of x/Q and D/Q at the updated critical location must be used. h a 4 BN1-11600.02-112 3.5-13 Revision 1 - August 1983 0

f~ %J %J SNPS-1 ODCM i l TABLE 3.5-1 INHAIATION DOSE FACTORS FOR ADULTS (arem per pCi inhaled) Radio-nuclide Bone Liver T. Body Thyroid Kidney 1 :nj( GI-LLI 3 4 d H-3 No Data 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 C-14 2.27E-06 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 Na-24 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 P-32 1.65E-04 9.64E-06 6.26E-06 No Data No Data No Data 1.08E-05 i Cr-51 No Data No Data 1.25E-08 7.44E-09 2.85E-09 1.80E-06 4.15E-07 Mn-54 No Data 4.95E-06 7.87E-07 No Data 1.23E-06 1.75E-04 9.67E-06 I Mn-56 -No Data 1.55E-10 2.29E-11 No Data 1.63E-10 1.18E-06 2.53E-06 Fe-55 3.07E-06 2.12E-06 4.98E-07 No Data No Data 9.01E-06 7.54E-07 Fe-59 1.47E-06 3.47E-06 1.32E-06 No Data No Data 1.27E-04 2.35E-05 co-58 No Data 1.98E-07 2.59E-07 No Data No Data 1.16E-04 1.33E-05 00-60 No Data 1.44E-06 1.85E-06 No Data No Data 7.46E-04 3.56E-05 Ni-63 5.40E-05 3.03E-06 1.81E-06 No Data No Data 2.23E-05 '1.67E-06 Ni-65 1.92E-10 2.62E-11 1.14E-11 No Data No Data 7.00E-07 1.54E-06 i Cu-64 No Data 1.83E-10 7.69E-11 No Data 5.78E-10 8.48E-07 6.12E-06 I Zn-65 4.05E-06 1.29E-05 5.82E-06 No Data 8.62E-06 1.08E-04 6.68E-06 l Zn-69 4.23E-12 8.14E-12 5.65E-13 No Data 5.27E-12 1.15E-07 2.04E-09 ] Br-83 No Psta No Data 3.01E-08 No Data No Data No Data 2.90E-08 i Br-84 No Oaea No Data 3.91E-08 No Data No Data No Data 2.05E-13 Br-85 No beta No Data 1.60E-09 No Data No Data No Data <1.00E-24 i Rb-86 No Data 1.69E-05 7.37E-06 No Data No Data No Data 2.08E-06 Rb-68 No Data 4.S4E-08 2.41E-08 No Data No Data No Data ~ 4.18E-19 Rb-89 No Data 3.20E-08 2.12E-08 No Data No Data No Data 1.16E-21 Sr-89 3.80E-05 No Data 1.09E-06 No Data No Data 1.75E-04 4.37E-05 i Sr-90 1.24E-02 No Data 7.62E-04 No Data No Data 1.20E-03 9.02E-05 i Sr-91 7.74E-09 No Data 3.13E-10 No Data No Data 4.56E-06 2.39E-05 Sr-92 8.43E-10 No Data 3.64E-11 No Data No Data 2.06E-06 5.38E-06 4 Y-90 2.61E-07 No Data 7.01E-09 No Data No Data 2.12E-05 6.32E-05 Y-91m 3.26E-11 No Data 1.27E-12 No Data No Data 2.40E-07 1.66E-10 i Y-91 5.78E-05 No Data 1.55E-06 No Data No Data 2.13E-04 4.81E-05 4 Y-92 1.29E-09 No Data 3.77E-11 No Data No Data 1.96E-06 9.19E-06 l Y-93 1.18E-05 No Data 3.26E-10 No Data No Data 6.06E-06 5.27E-05 t BN1-11600.02-99 1 of 3 Revision 1 - August 1983 4 i 4

n SNPS-1 ODCM a TABLE 3.5-1 (CONT'D) Radio-1 gt t GI-LLI nuclide Bone . Liver T. Body Thyroid Kidney 3j 2r-95 1.34E-05 4.30E-06 2.91E-06 No Data 6.77E-06 2.21E-04 1.88E-05 i '2r-97 1.21E-08 2.45E-09 1.13E-09 No Data 3.71E-09 9.84E-06 6.54E-05 Nb-95 1.76E-06 9.77E-07 5.26E-07~ No Data 9.67E-07 6.31E-05 1.30E-05 No-99 No Data 1.51E-08 2.87E-09 No Data 3.64E-08 1.14E-05 3.10E-05 Tc-99m 1.29E-13 3.64E-13 4.63E-12 No Data 5.52E-12 9.55E-08 5.20E-07 Tc-101 5.22E-15 7.52E-15 7.38E-14 No Data 1.35E-13 4.99E-08 1.36E-21. Ru-103 1.91E-37 No Data 8.23E-08 No Data 7.29E-07 6.31E-05 1.38E-05 Ru-105 9.88E-11 No Data 3.89E-11 No Data 1.27E-10 1.37E-06 6.02E-06 Ru-106 8.64E-06 No Data 1.09E-06 No Data 1.67E-05 1.17E-03 1.14E-04 ~ Ag-110m 1.35E-06 1.25E-06 7.43E-07 No Data 2.46E-06 5.79E-04 3.78E-05 Te-125m 4.27E-07 1.98E-07 5.84E-08 1.31E-07 1.55E-06 3.92E-05 8.83E-06 i Te-127m 1.58E-06 7.212-07 1.96E-07 4.11E-07 5.72E-06 1.20E-04 1.87E-05 Te-127 1.75E-10 8.03E-11 3.87E-11 1.32E-10 6.37E-10 8.14E-07 7.17E-06 Te-129m 1.22E-06 5.84E-07 1.98E-07 4.30E-07 4.57E-06 1.45E-04 4.79E-05 Te-129 6.22E-12 2.99E-12 1.55E-12 4.87E-12 2.34E-11 2.42E-07 1.96E-08 Te-131m - 8.74E-09 5.45E-09 3.63E-09 6.88E-09 3.86E-08 1.82E-05 6.95E-05 l Te-131 1.39E-12 7.44E 4.49E-13 1.17E-12 5.46E-12 1.74E-07 2.30E-09 Te-132 3.25E-08 2.69E-08 2.02E-08 2.37E-08 1.82E-07 3.60E-05 6.37E-05 j I-130 5.72E-07 1.68E-06 6.60E-07 1.42E-04 2.61E-06 No Data 9.61E-07 i 1-131 3.15E 4.47E-06 2.56E-06 1.49E-03 7.66E-06 No Data 7.85E-07 I-132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 No Data 5.08E-08 I-133 1.08E-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 No Data 1.11E-06 I-134 8.05E-08 2.16E-07 7.69E-08 3.73E-06 3.44E-07 No Data 1.26E-10 I-135 3.35E-07 8.73E-07 3.21E-07 5.60E-05 1.39E-06 No Data 6.56E-07 i j .Cs-134 4.66E-05 1.06E-04 9.10E-05 No Data 3.59E-05 1.22E-05 1.30E-06 i Cs-136 4.88E-06 1.83E-05 1.38E-05 No Data 1.07E-05 1.50E-06 1.46E-06 i Cs-137 5.98E-05 7.76E-05 5.35E-05 No Data 2.78E-05 9.40E-06 1.05E-06 Cs-138 4.14E-05 7.76E-08 4.05E-08 No Data 6.00E-08 6.07E-09 2.33E-13 i Ba-139 1.17E-10' 8.32E-14 3.42E-12 No Data 7.78E-14 4.70E-07 1.12E-07 i Ba-140 4.88E-06 6.13E-09 3.21E-07 No Data 2.09E-09 1.59E-04 2.73E-05 l Ba-141 1.25E-11 9.41E-15 4.20E-13 No Data 8.75E-15 2.42E-07 1.45E-17 Ba-142 3.29E-12 3.38E-15 2.07E-13 No Data 2.86E-15 1.49E-07 1.96E-26 j La-140 4.30E-08 2.17E-08 5.73E-09 No Data No Data 1.70E-05 5.73E-05 l La-142 8.54E-11 3.88E-11 9.65E-12 No Data No Data 7.91E-07 2.64E-07 5 i L i BN1-11600.02-99 2 of 3 Revision 1 - August 1983 l i 4 i

~ SNPS-1 ODCM TABLE 3.5-1 (CONT'D) Radio-nuclide Bone Liver T. Body Thyroid Kidney g CI-LLI Ce-141 2.49E-06 1.69E-06 1.91E-07 Nc' Data 7.83E-07 4.52E-05 1.50E-05 Cc-143 2.33E-08 1.72E-08 1.91E-09 No Data 7.60E 9,97E-06 2.83E-05 Ce-144 4.29E-04 1.79E-04 2.30E-05 -No Data 1.06E-04 9.72E-04 1.02E-04 Pr-143 1.17E-06 4.69E-07 5.80E-08 No Data. 2.70E-07 3.51E-05 2.50E-05 Pr-144 3.76E-12 1.56E-12 1.91E-13 No Data 8.81E-13 1.27E-07 2.69E-18 Nd-147 6.59E-07 7.62E-07 4.56E-08 No Data 4.45E-07 2.76E-05 2.16E-05 W-187 1.06E-09 8.85E-10 3.10E-10 No Data No Data 3.63E-06 1.94EM)5 Np-239 2.87E-08 2.82E-09 1.55E-09 No Data 8.75E-09 4.70E-06 1.49E-05 l l BN1-11600.02-99 3 of 3 Revision 1 - August 1983 1 ]

O O O i SNPS-1 ODCM TABLE 3.5-2 INHALATION DOSE ' FACTORS FOR TEENAGER (arem per pCi inhaled) ~ Radio-nuclide Bone 'Ilver T. Body Thyroid Kidney

Inng, GI-LLI H-3 No Data 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 4

C-14 3.25E-06 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 .Na-24 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 P-32 2.36E-04 1.37E-05' 8.95E-06 No Data No Data No Data 1.16E-05 i Cr-51 No Data No Data 1.69E-08 9.37E-09 3.84E-09 2.62E-06 3.75E-07 i. Mn-54 lb Data 6.39E-06 1.05E-06 No Data 1.59E-06 2.48E-04 8.35E-06 i Mn-56 No Data 2.12E-10 3.15E-11 No Data 2.24E-10 1.90E-06 7.18E-06 Fe-55 4.18E-06 2.98E-06 6.93E-07 No Data No Data 1.55E 7.99E-07 Fe-59 1.99E-06 4.62E-06 1.79E-06 No Data No Data 1.91E-04 2.23E-05 Co-58 No Data 2.59E-07 3.47E-07 No Data No Data 1.68E-04 1.19E-05 Co-60 No Data 1.89E-06 2.48E-06 No Data No Data 1.09E-03 3.24E-05 } Ni-63 7.25E-05 -5.43E-06 2.47E-06 No Data No Data 3.84E-05 1.77E-06 j Ni-65 2.73E-10 3.66E-11 1.59E-11 No Data No Data 1.17E-06 4.59E-06 i Cu-64 No Data 2.54E-10 1.06E-10 No Data 8.01E-10 1.39E-06 7.68E-06 j Zn-65 4.82E-06 1.67E-05 7.80E-06 No Data 1.08E-05 1.55E-04 5.83E-06 i Zn-69 6.04E-12 1.15E-11 8.07E-13 No Data 7.53E-12 1.98E-07 3.56E-08 i Br-83 No Data No Data-4.30E-08 No Data No Data No Data <1.00E-24 Br-84 No Data No Data 5.41E-08 No Data No Data No Data <1.00E-24 Br-85 No Data No Data 2.29E No Date. No Data No Data <1.00E-24 i Rb-86 No Data 2.36E-05 1.05E-05 No Data No Data No Data 2.21E-06 Rb-88 No Data 6.82E-08 3.40E-08 No. Data No Data No Data 3.65E-15 i Rb-89 No Data 4.40E-08 2.91E-08 No Data No Data No Data 4.22E-17 { Sr-89 5.43E-05 No Data 1.56E-06 No Data No Data 3.02E-04 4.64E-05 i Sr-90 1.35E-02 No Data 8.35E-04 No Data No Data 2.06E-03 9.56E-05 l Sr-91 1.10E-08 No Data 4.39E-10 No Data No Data 7.59E-06 3.24E-05 j Sr-92 1.19E-09 No Data 5.08E-11 No Data No Data 3.43E-06 1.49E-03 Y-90 3.73E-07 No Data 1.00E-08 No Data No Data 3.66E-05 6.99E-05 Y-91m 4.638-11 No Data 1.77E-12 No Data No Data 4.00E-07 3.77E-09 Y-91 8.26E-05 No Data 2.21E-06 No Data No Data 3.67E-04 5.11E-05 j Y-92 1.84E-09 No Data 5.36E-11 No Data No Data 3.35E-06 2.06E-05 j Y-93 1.69E-08 No' Data 4.65E-10 No Data No Data 1.04E-05 7.24E-05 i i j BN1-11600.02-100 1 of 3 Revision 1 - August 1983 I i

1 p g d. k SNPS-1 ODCM TABLE 3.5-2 (CONT'D) Radio-nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI 2r-95 1.82E-05 5.73E-06 3.94E-06 No Data 8.42E-06 3.36E-04 1.86E-05 Zr-97 1.72E-08 3.40E-09 1.57E-09 No Data 5.15E-09 1.62E-05 7.88E-05 Nb-95 2.32E-06. 1.29E-06 7.08E-07 No Data 1.25E-06 9.39E-05 1.21E-05 Mo-99 No Data 2.11E-08 4.08E-09 No Data 5.14E-08 1.92E-05 3.36E-05 Tc-99m 1.73E-13 4.83E-13 6.24E-12 No Data 7.20E-12 1.44E-07 7.66E-07 Tc-101 7.40E-15 1.05E-14 1.03E-13 No Data 1.90E-13 8.34E-08 1.09E-16 Ru-103 2.63E-07 No Data 1.12E-07 No Data 9.29E-07 9.79E-05 1.36E-05 Ru-105 1.40E-10 No Data 5.42E-11 No Data 1.76E-10 2.27E-06 1.13E-05 Ru-106 1.23E-05 No Data .1.55E-06 No Data 2.38E-05 2.01E-03 1.20E-04 Ag-110m 1.73E-06 1.64E-06 9.99E-07 No Data 3.13E-06 8.44E-04 3.41E-05 Te-125m 6.10E-07 2.80E-07 8.34E-08 1.75E-07 No Data 6.70E-05 9.38E-06 Te-127m 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1.99E-05 Te-127 2.51E-10 1.14E-10 5.52E-11 1.77E-10 9.10E-10 1.40E-06 1.01E-05 Te-129m 1.74E-06 8.23E-07 2.81E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-05 Te-129 8.87E-12 4.22E-12 2.20E-12 6.48E-12 3.32E-11 4.12E-07 2.02E-07 Te-131m 1.23E-08 7.51E-09 5.03E-09 9.06E-09 5.49E-08 2.97E-05 7.76E-05 Te-131 1.97E-12 1.04E-12 6.30E-13 1.55E-12 7.72E-12 2.92E-07 1.89E-09 Te-132 4.50E-08 3.638-08 2.74E-08 3.07E-08 2.44E-07 5.61E-05 5.79E-05 I-130 7.80E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 No Data 1.14E-06 I-131 4.43E-06 6.14E-06 3.30E-06 1.838-03 1.05E-05 No Data 8.11E-07 I-132 1.99E-07 5.6/E-07 1.97E-07 1.89E-05 8.65E-07 No Data 1.59E-07 1-133 1.52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-06 No Data 1.29E-06 I-134 1.11E-07 2.90E-07 1.05E-07 4.94E-06 4.58E-07 No Data 2.55E-09 I-135 4.62E-07 1.18E-06 4.36E-07 7.76E-05 1.86E-06 No Data 8.69E-C7 Cs-134 6.28E-05 1.41E-04 6.86E-05 No Data 4.69E-05 1.83E-05 1.22E-06 Cs-136 6.44E-06 2.42E-05 1.71E-05 No Data 1.38E-05 2.22E-06 1.36E-06 Cs-137 8.38E-05 1.06E-04 3.89E-05 No Data 3.80E-05 1.51E-05 1.06E-06 Cs-138 5.82E-08 1.07E-07 5.58E-08 No Data 8.28E-08 9.84E-09 3.38E-11 Ba-139 1.67E-10 1.18E-13 4.87E-12 No Data 1.11E-13 8.08E-07 8.06E-07 Ba-140 6.84E-06 8.38E-09 4.40E-07 No Data 2.85E-09 2.54E-04 2.86E-05 Ba-141 1.78E-11 1.32E-14 5.93E-13 No Data 1.23E-14 4.11E-07 9.33E-14 Ba-142 4.62E-12 4.63E-15 2.84E-13 No Data 3.92E-15 2.39E-07 5.99E-20 La-140 5.99E-08 2.95E-08 7.82E-09 No Data No Data 2.68E-05 6.09E-05 La-142 1.20E-10 5.31E-11 1.32E-11 No Data No Data 1.27E-06 1.50E-06 BN1-11600.02-100 2 of 3 Revision 1 - August 1983

\\ SNPS-1 ODCM i-j- 1DLBLE 3.5-2 l[ CONT'D) Radio- ~ jL nuclide . Bone Liver T. Body ' Thyroid Kidney 14:ngg GI-LLI i Ce-141 3.55E-06 2.37E-06 2.71E-07 . No Data 1.11E-06 7.67E 1.58E-05. i Ce-143 3.32E-08 2.42E-08 2.70E-09 No Data 1.08E-08 1.63E-05 3.19E-05 Ce-144-6.11E-04 2.53E-04 .3.28E-05 No Data 1.51E-04 1.67E-03 1.08E-04 Pr-143 1.67E-06 6.64E-07 8.28E-08 No Data 3.86E-07 6.04E-05 2.67E-05 - Pr-144. 5.37E-12 2.20E-12 2.72E-13 No Data 1.26E-12 2.19E-07 2.94E-14 Nd-147 9.83E-07 1.07E-06 6.41E No Data 6.28E 4.55E-05 2.28E-05~ j W-187 1.50E-09 1.22E-09 4.29E-10 . No Data No Data 5.92E-06 2.21E-05 ] Np-239 .4.23E-08 3.99E-09 2.21E-09 No Data 1.25E-08 8.11E-06 1.65E-05 i. 1 i. j s 4 i I i I } l 1 l - BN1-11600.02-100 3 of 3 Revision 1 - August 1983 i 3 T .w

7 (s V] ( V SNPS-1 ODCM TABLE 3.5-3 INHA1ATION DOSE FACTORS FOR CHILD (arem per pCL inhaled) Radio-nuclide Bone-Ilver T. Body Thyroid Kldney Lung GI-LLI H-3 No Data 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 C-14 9.70E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 Na-24 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 L F-32 7.04E-04 3.09E-05 2.67E-05 No Data No Data No Data 1.14E-05 i Cr-51 No Data No Data 4.17E-08 2.31E-08 6.57E-09 4.59E-06 2.93E-07 Mn-54 No Data 1.16E-05 2.57E-06 No Data 2.71E-06 4.26E-04 6.19E-06 Hn-56 No Data 4.48E-10 8.43E-11 No Data 4.52E-10 3.55E-06 3.33E-05 Fe-55 1.28E-05 6.80E-06 2.10E-06 No Data No Data 3.00E-05 7.75E-07 Fe-59 5.59E-06 9.04E-06 4.51E-06 No Data No Data 3.43E-04 1.91E-05 Co-58 No Data 4.79E-07 8.55E-07 No Data No Data 2.99E-04 9.29E-06 Co-60 No Data 3.55E-06 6.12E-06 No Data No Data 1.91E-03 2.60E-05 Ni-63 2.22E-04 1.25E-05 7.56E-06 No Data No Data 7.43E-05 1.71E-06 Ni-65 8.08E-10 7.99E-11 4.44E-11 No Data No Data 2.21E-06 2.27E-05 Cu-64 No Data 5.39E-10 2.90E-10 No Data 1.63E-09 2.59E-06 9.92E-06 Zn-65 1.15E-05 3.06E-05 1.90E-05 No Data 1.93E-05 2.69E-04 4.41E-06 Zn-67 1.81E-11 2.61E-11 2.41E-12 No Data 1.58E-11 3.84E-07 2.75E-06 Br-83 No Data No Data 1.23E-07 No Data No Data No Data <1.00E-24 Br-84 No Data No Data 1.48E-07 No Data No Data No Data <1.00E-24 Br-85 No Data No Data 6.84E-09 No Data No Data No Data <1.00E-24 Rb-86 No Data 5.36E-05 3.09E-05 No Data No Data No Data 2.16E-06 Rb-88 No Data 1.52E-07 9.90E-08 No Data No Data No Data 4.66E-09 i Rb-89 No Data 9.33E-08 7.83E-08 No Data No Data No Data 5.11E-10 l Sr-89 1.62E-04 No Data 4.66E-06 No Data No Data 5.83E-04 4.52E-05 Sr-90 2.73E-02 No Data 1.74E-03 No Data No Data 3.99E-03 9.28E-05 Sr-91 3.23E-08 No Data 1.24E-09 No Data No Data 1.44E-05 4.70E-05 Sr-92 3.54E-09 No Data 1.42E-10 No Data No Data 6.49E-06 6.55E-05 Y-90 1.11E-06 No Data 2.99E-08 No Data No Data 7.07E-05 7.24E-05 Y-91m 1.378-10 No Data 4.98E-12 No Data No Data 7.60E-07 4.64E-07 Y-91 2.47E-04 No Data 6.59E-06 No Data No Data 7.10E-04 4.97E-05 Y-92 5.50E-09 No Data 1.57E-10 No Data No Data 6.46E-06 6.46E-05 Y-93 5.04E-08 No Data 1.38E-09 No Data No Data 2.01h-05 1.05E-04 BN1-11600.02-101 1 of 3 Revision 1 - August 1983

SNPS-1.ODCM TABLE 3.5-3 (CONT'D) Radio-nuclide Bone

Liver T. Body Thyroid Kidney g

GI-LLI j 2c-95' 5.13E-05 1.13E-05 1.00E-05 No Data 1.61E-05 6.03E-04 1.65E-05 2r-97 5.07E-08 7.34E-09 4.32E-09. No Data 1.05E-08 3.06E-05 9.49E-05 j Nb-95 6.35E 2.48E-06 1.77E No Data 2.33E-06 1.66E-04 1.00E-05 No-99 No Data. 4.66E-08 1.15E-08 No Data 1.06E-07 3.66E 3.42E-05 i Tc-993 4.81E-13. 9.41E-13 1.56E-11 No Data 1.37E-11 2.57E-07 1.30E-06 Tc-101 2.19E-14 2.30E-14' 2.91E-13 No Data 3.92E-13 1.58E-07 4.41E-09 .Ru-103 .7.55E-07 No Data 2.90E-07 No Data 1.90E-06 -1.79E-04 1.21E-05 { Ru-105 4.13E-10 No Data 1.50E-10 No Data 3.63E-10 4.30E-06 2.69E-05 [ Ru-106 3.68E-05 No Data 4.57E-06 No Data 4.97E-05 3.87E-03 1.16E-04 [ -Ag-110m 4.56E-06 3.08E-06 2.47E-06 No Data 5.74E-06 1.48E-03 2.71E-05 i Te-125m 1.82E-06 6.29E-07 2.47E-07 5.20E-07 No Data 1.29E-04 9.13EM6 i. .Te-127m 6.72E-06 '2.31E-06 8.16E-07 1.64E-06 1.72E-05 4.00E-04 1.93E-05 ) Te-127 -7.49E-10 2.57E-10 1.65E-10 5.30E 1.91E-09 2.71E-06 1.52E-05 l Te-129m 5.19E-06 1.85E-06 8.22E-07 1.71E-06 1.36E-05 4.76E-04 4.91E-05 i Te-129 2.64E-11 9.45E-12 6.44E-12 ~1.93E-11 6.94E-11 7.93E-07 6.89E-06 4 Te-131m 3.63E-08 1.60E-08 1.37E-08 2.64E-08 1.08E-07 5.56E-05 8.32E-05 j .Te-131 5.87E-12 _2.28E-12 1.78E-12 4.59E-12 1.59E-11 5.55E-07 3.60E-07 Te-132 .1.30E-07 7.36E-08 .7.12E-08 8.58E-08 4.79E-07 1.02E-04 3.72E-05 1-130 2.21E-06 4.43E-06 2.28E-06 4.99E-04 6.61E-06 No Data 1.38E-06 I-131 1.30E-05 1.30E-05 7.37F-06 4.39E-03 2.13E-05 No Data 7.68E-07 I-132 5.72E-07 1.10E-06 5.07E-07 5.23E-05 1.69E-06 No Data 8.65E-07 f' I-133 4.48E-06 5.49E-06 2.08E-06 1.04E-03 9.13E-06 No Data 1.48E-06 I I-134 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 No Data 2.58E-07 j 1-135 1.33E-06 -2.36E-06 1.12E-06 2.14E-04 3.62E-06 No Data 1.20E-06 Cs-134 1.76E-04 2.74E-04 6.07E-05 No Data 8.93E-05 3.27E-05 1.04E-06 i Cs-136 1.76E-05 4.62E-05 3.14E-05 No Data 2.58E-05 3.93E-06 1.13E-06 Cs-137 2.45E-04 2.23E-04 3.47E-05 No Data 7.63E-05 2.81R-05 9.78E-07 Cs-138 1.71E-07 2.27E-07 1.50E-07 No Data 1.68E-07 1.84E-08 7.29E-08 4 j. Ba-139 4.98E-10 2.66F-13 -1.45E-11 No Data 2.33E-13 1.56E-06 1.56E-05 i Ba-140 2.00E-05 1.75E-08 1.17E-06 No Data 5.71E--09 4.71E-04 2.75E-05 Ba-141 5.29E-11 2.95E-14 1.72E-12 No Data 2.56E-14 7.89E-07 7.44E-08 3l Ba-142 1.35E-11 9.73E-15 7.54E-13 No Data 7.87E-15 4.44E-07 7.41E-10 La-140 1.74E-07 6.08E-08 2.04E-08 No Data No Data 4.94E-05 6.10E-05 La-142 3.50E-10 1.11E-10 3.49E-11 No Data No Data 1.35E-06 2.05E-05 l 1 f -BN1-11600.02-101 2 of 3 Revision 1 - August 198' l l

O O O SNPS-1 ODCM TABLE 3.5-3 (CONT'D) Radio-1 nnj[ GI-LLI nuclide Bone Liver T. Body Thyroid Kidney 3 Ce-141 1.06E-05 5.28E-06 7.83E-07 No Data 2.31E-06 1.47E-04 1.53E-05 Ce-143 9.89E-08 5.37E-08 7.77E-09 No Data 2.26E-08 3.12E-05 3.44E-05 Ce-144 1.83E-03 5.72E-04 9.77E-05 No Data 3.17E-04 3.23E-03 1.05E-04 Pr-143 4.99E-06 1.50E-06 ~ 2.47E-07 No Data 8.11E-07 1.17E-04 2.63E-05 Pr-144 1.61E-11 4.99E-12 8.10E-13 No Data 2.64E-12 4.23E-07 5.32E-08 Nd-147 2.92E-06 2.36E-06 1.84E-07 No Data 1.30E-06 8.87E-05 2.22F-05 W-187 4.41E-09 2.61E-09 1.17E-09 No Data No Data 1.11E-05 2.46E-05 Np-239 1.26E-07 9.04E-09 6.35E-09 No Data 2.63E-08 1.57E-05 1.73E-05 .I l l l l l I I BN1-11600.02-101 3 of 3 Revision 1 - August 1983

Q) %) G SNPS-1 ODCM TABLE 3.5-4 INHAIATION DOSE FACTORS FOR INFANT (mrem per pCi inhaled) Radio-nuclide Bone Liver T. Body Thyroid Kidney 1 try( GI-LLI 3 H-3 No Data 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 C-14 1.89E-05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 Na-24 7.5&E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 P-32 1.45E-03 8.03E-05 5.53E-05 No Data No Data No Data 1.15E-05 Cr-51 No Data No Data 6.39E-08 4.11E-08 9.45E-09 9.17E-06 2.55E-07 Ma-54 No Data 1.81E-05 3.56E-06 No Data 3.56E-06 7.14E-04 5.04E-06 Mn-56 No Data 1.10E-09 1.58E-10 No Data 7.86E-10 8.95E-06 5.12E-05 Fe-55 1.41E-05 S.39E-06 2.38E-06 No Data No Data 6.21E-05 7.82E-07 Fe-59 9.69E-06 1.68E-05 6.77E-06 No Data No Data 7.25E-04 1.77E-05 Co-58 No Data 8.71E-07 1.30E-06 No Data No Data 5.55E-04 7.95E-06 Co-60 No Data 5.73E-06 8.41E-06 No Data No Data 3.22E-03 2.28E-05 Ni-63 2.42E-04 1.46E-05 8.29E-06 No Data No Data 1.49E-04 1.73E-06 Ni-65 1.71E-09 2.03E-10 8.79E-11 No Data No Data 5.80E-06 3.58E-05 Cu-64 No Data 1.34E-09 5.53E-10 No Data 2.84E-09 6.64E-06 1.07E-05 Zn-65 1.38E-05 4.47E-05 2.22E-05 No Data 2.32E-05 4.62E-04 3.67E-05 Zn-69 3.85E-11 6.91E-11 5.13E-12 No Data 2.87E-11 1.05E-06 9.44E-06 Br-83 No Data No Data 2.72E-07 No Data No Data No Data <1.00E-24 Br-84 No Data No Data 2.86E-07 No Data No Data No Data <1.00E-24 Br-85 .No Data No Data 1.46E-08 No Data No Data No Data <1.00E-24 Rb-86 No Data 1.36E-04 6.30E-05 No Data No Data No Data 2.17E-06 Rb-88 No Data 3.98E-07 2.05E-07 No Data No Data No Data 2.42E-07 Rb-89 No Data 2.29E-07 1.47E-07 No Data No Data No Data 4.87E-08 Sr-89 2.84E-04 No Data 8.15E-06 No Data No Data 1.45E-03 4.57E-05 Sr-90 2.92E-02 No Data 1.85E-03 No Data No Data 8.038-03 9.36E-05 Sr-91 6.83E-08 No Data 2.47E-09 No Data No Data 3.76E-05 5.24E-05 Sr-92 7.50E-09 No Data 2.79E-10 No Data No Data 1.70E-05 1.00E-04 Y-90 2.35E-06 No Data 6.30E-08 No Data No Data 1.92E-04 7.43E-05 Y-91m 2.91E-10 No Data 9.90E-12 No Data No Data 1.99E-06 1.68E-06 Y-91 4.20E-04 No Data 1.12E-05 No Data No Data 1.75E-03 5.02E-05 Y-92 1.17E-08 No Data 3.29E-10 No Data No Data 1.75E-05 9.04E-05 Y-93 1.07E-07 No Data 2.91E-09 No Data No Data 5.46E-05 1.19E-04 Revision 1 - August 1983 BN1-11600.02-102 1 of 3

SNPS-1 ODCM 1 TABLE 3.5-4 (CONT'D) Radio-nuclide Bone Liver T. Body Thyroid Kidney Lynj[ GI-LLI Zr-95 8.24E-05 1.99E-05 1.45E-05 No Data 2.22E-05 1.25E-03 1.55E-05 Zr-97 1.07E-07 1.83E-08 8.36E-09 No Data 1.85E-08 7.88E-05 1.00E-04 Nb-95 1.12E-05 4.59E-06 2.70E-06 No Data 3.37E-06 3.42E-04 9.05E-06 Mo-99 No Data 1.18E-07 2.31E-08 No Data 1.89E-07 9.63E-05 3.48E-05 Tc-993 9.98E-13 2.06E-12 2.66E-11 No Data 2.22E-11 5.79E-07 1.45E-06 Tc-101 4.65E-14 5.88E-14 5.80E-13 No Data 6.99E-13 4.17E-07 6.03E-07 Ru-103 1.44E-06 No Data 4.85E-07 No Data 3.03E-06 3.94E-04 1.15E-05 Ru-105 8.74E-10 No Data' 2.93E-10 No Data 6.42E-10 1.12E-05 3.46E-05 Ru-106 6.20E-05 No Data 7.77E-06 No Data 7.61E-05 8.26E-03 1.17E-04 Ag-110m 7.13E-06 5.16E-06 3.57E-06 No Data 7.80E-06 2.62E-03 2.36E-05 Te-125m 3.40E-06 1.42E-06 4.70E-07 1.16E-06 No Data 3.19E-04 9.22E-06 Te-127m 1.19E-05 4.93E-06 1.48E-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05 Te-127 1.59E-09 6.81E-10 3.49E-10 1.32E-09 3.47E-09 7.39E-06 1.74E-05 Te-129m 1.01E-05 4.35E-06 1.59E-06 3.91E-06 2.27E-05 1.20E-03 4.93E-05 Te-129 5.63E-11 2.48E-11 1.34E-11 4.82E-11 1.25E-10 2.14E-06 1.88E-05 Te-131m 7.62E-08 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 8.51E-05 Te-131 1.24E-11 5.87E-12 3.57E-12 1.13E-11 2.85E-11 1.47E-06 5.87E-06 Tc-132 2.66E-07 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 3.15E-05 I-130 4.54E-06 9.91E-06 3.98E-06 1.14E-03 1.09E No Data 1.42E-06 I-131 2.71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 No Data 7.56E-07 I-132 1.21E-06 2.53E-06 8.99E-07 1.21E-04 2.82E-06 No Data 1.36E-06 I-133 9.46E-06 1.37E-05 4.00E-06 2.54E-03 1.60E-05 No Data 1.54E-06 I-134 6.58E-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 No Data 9.21E-07 1-135 2.76E-06 5.43E-06 1.98E-06 4.97E-04 6.05E-06 No Data 1.31E-06 Cs-134 2.83E-04 5.02E-04 5.32E-05 No Data 1.36E-04 5.69E-05 9.53E-07 l Cs-136 3.45E-05 9.61E-05 3.78E-05 No Data 4.03E-05 8.40E-06 1.02E-06 d Cs-137 3.92E-04 4.37E-04 3.25E-05 No Data 1.23E-04 5.09E-05 9.53E-07 Cs-138 3.61E-07 5.58E-07 2.84E-07 No Data 2.93E-07 4.67E-08 6.26E-07 Ba-139 1.06E-09 7.03E-13 3.07E-11 No Data 4.23E-13 4.25E-06 3.643-05 Ba-140 4.00E-05 4.00E-08 2.07E-06 No Data 9.59E-09 1.14E-03 2.74E-05 Ba-141 1.12E-10 7.70E-14 3.55E-12 No Data 4.64E-14 2.12E-06 3.39E-06 Ba-142 2.84E-11 2.36E-14 1.40E-12 No Data 1.36E-14 1.11E-06 4.95E-07 i La-140 3.61E-07 1.43E-07 3.68E-08 No Data No Data 1.20E-04 6.06E-05 La-142 7.36E-10 2.69E-10 6.46E-11 No Data No Data 5.87E-06 4.25E-05 Revision 1 - August 1983 2 of 3 BN1-11600.02-102 4

.... ~ - O O C SNPS-1 ODCM 1 TABLE.3.5-4 (CONT'D)- Radio - nuclide Bone Liver - T. Bog Thyroid Kidney h CI-LLI Ce-141 j Ce-143 . 1.98E-05 1.19E-05 1.42E-06 No Data 3.75E-06 3.69E-04 1.54E-05. 2.09E-07 1.38E-07 i Ce-144 . 2.28E-03 8.65E-04 . 1.58E-08 No Data ' 4.03E-08 8.30E-05 3.55E-05 Pr-143 1.00E-05 3.74E-06 . 1.26E-04 No Data 3.84E-04 7.03E-03 1.06E-04 4.99E-07 No Data 1.41E-06 3.09E-04' 2.66E-05 Pr-144 - 3.42E-11 1.32E-11 1.72E-12 No Data . 4.80E-12 1.15E-06 3.06E-06 i Nd-147 5.67E-06 5.81E-06 -3.575-07 No Data 2.25E-06 2.30E-04 2.23E-05 i - W-187 9.26E-09 6.44E-09 2.23E-09 No Data No Data 2.83E-05 2.54E-05 Np-239 2.65E-07 2.37E-08 1.34E-08 No Data 4.73E-08 4.25E-05 1.78E-05 i i i t I i 5 l s I i r i t i A 5 I i i I J j Revision 1 - August 1983 j 3 of 3 BN1-11600.02-102 4 i k e .n m e-w n -.- s

SNPS-1 ODCM j TABLE 3.5-5 v RECOMMENDED VALUES FOR U,p TO BE USED FOR THE E XIMUM EXPOSED INDIVIDUAL IN LIEU OF SITE-SPECIFIC DATA Pathway Infant Child Teen Adult Fruits, vege-tables 4 ri (kg/yr)(1,f27 520 630 520 Leafy vege-tables (1) (kg/yr) 26 42 64 Milk (1/yr)(I) 330 330 400 310 Meat &p9ptry (kg/yr)\\ 41 65 110 Fish (fresh or salt) (kg/yr)(3) 6.9 16 21 Othersegod (kg/yr) 1.7 3.8 5 Drinkin ater (A/yr) 4 330 510 510 730 Shoreline re-creatiog4) (hr/yr) 14 67 12 lation Inhg/yr) 1400(5) 3700(6) 8000(6) 8000(5) (m (1) Consumption rate obtained fres Reference 19 for average individual and age-prorated and maximised using techniques contained in Reference 10 of Regulatory Guide 1.109, Rev 1, Oct. 1977. (2) Consists of the following (on a mass basis): 22% fruit. 54% vegetables (including leafy vegetables), and 24% grain. p BN1-11600.02-112 1 of 2 Revision 1 - August 1983 N./]

SNPS-1 ODCM ( TABLE 3.5-5 (CONT'D) (3) Consumption rate for adult obtained by averaging data from References 10 and 21-24 of Regulatory Guide 1.109, Rev. 1, Oct. 1977 and age-prorated using techniques contained in Reference 10. (4) Data obtained directly from Reference 10 of Regulatory Guide 1.109, Rev. 1, Oct 1977. (5) Data obtained directly from Reference 20 of Regulatory Guide 1.109, Rev. 1, Oct. 1977.

50) Inhalation rate derived from data provided in Reference 20 of Regulatory Guide 1.109, Rev. 1, Oct. 1977.

O BN1-11600.02-112 2 of 2 Revision 1 - August 19143 O . - _,.. ~. _ _ _ _ _ - -. _ - - ~. _,. _.., _ _.. _ - _ _ _ _ _ _ _ _ -... - -... _ _. _, _ _. - _.. _. - -. - _ _ -.

SNPS-1 ODCM TABLE 3.5-6 L/ STABLE ELEMENT TRANSFER DATA (I) B F (Cow) F Element Veg/ Soil Milk (d/1) Meat (d/kg) 1 H((2) 2) 4.8E+00 1.0E-02 1.2E-02 C 5.5E+00 L.2E-02 3.1E-0? Na 5.2E-02 4.0E-02(3) 3.0E-02 P 1.1E+00 2.5E-02 4.6E-02 Cr 2.5E-04 2.2E-03 2.4E-03 Mn 2.9E-02 2.5E-04 8.0E-04 Fe 6.6E-04 1.2E-03 4.0E-02 Co 9.4E-03 1.0E-03 1.3E-02 Ni 1.9E-02 6.7E-03 5.3E-02 Cu 1.2E-01 1.4E-02 8.0E-03 Za 4.0E-01 3.9E-02 3.0E-02 Rb 1.3E-01 3.0E-02(3) 3.1E-02 Sr 1.7E-02 8.0E-04 6.0E-0/ Y 2.6E-03 1.0E-05 4.6E-0, 2r 1.7E-04 5.0E-06 3.4E-02 Nb 9.4E-03 2.5E-03 2.8E-01 Mo 1.2E-01 7.5E-03 8.0E-03 Tc 2.5E-01 2.5E-02 4.0E-01 Ru 5.0E-02 1.0E-06 4.0E-01 Rh 1.3E-01 1.0E-02 1.5E-03 'O Ag 1.5E-01 5.0E-02 1.7E-02 I Te 1.3E-00 1.0E-03 7.7E-02 I 2.0E-02 6.0E-03(4) 2.9E-03 Cs 1.0E-02 1.2E-02(3) 4.0E-03 Ba 5.0E-03 4.0E-04(3) 3.2E-03 La 2.5E-03 5.0E-06(3) 2.0E-04 Ce 2.5E-03 1.0E-04 1.2E-03 Pr 2.5E 03 5.0E-06 4.7E-03 Nd 2.4E-03 5.0E-06 3.3E-03 W 1.8E-02 5.0E-04 1.3E-03 Np 2.5E-03 5.0E-06 2.0E-04(5) (1) Data presented in this table is from Reference 1 of Regulatory Guide 1.109, Rev. 1, Oct. 1977.. (2) Meat and milk coefficients are based on specific accivity considerations. (3)From Reference 15 of Regulatory Guide 1.109, Rev.1 Oct. 1977. (4)See text (Regulatory Guide 1.109, Rev. 1, Oct. 1977). (5)Frca Reference 13 of Regulatory Guide 1.109, Rev. 1, Oct. 1977. BN1-11600.02-112 1 of 1 Revision 1 - August 1983

d SNPS-1 ODCM TABLE 3.5-7 HUMIDITY PARAMETERS AT RECEPTORS 3 Monthly Average Absolute Humidity (gm/m ) - January 3.06 l Febtvary 3.09 March 3.83 April 5.71 May 8.19 June 12.62 July 15.53 August' 14.62 September 11.68 October 8.11 November-5.37 December 3.73 L 4 4 4 6 4 4 BN1-11600.02-112 1 of 1 Revision 1 - August 1983 4 a e ...w>g _.,-w--.y,---,_,,,w,.,y,_,,,~ ,,,,yw%_,,y_,_,-,p,,yr-w,w-,m.,,w,,,m_.,,,,.w%,,,,wmoww-w ,,,m, ,,,y, 9.m%,y.,.._,m,

SNPS-1 ODCM TABLE 3.5-8 DISTANCE FROM REACTOR CENTERLINE BY SECTOR OUT TO 8046 m (Meters) Nearest Nearcst Nearest Sector Residence Vegetable Garden Site Boundary 436 N NNE 381 365 332 NE~ 518 ENE-884 1,932 311 E 1,128 3,867 346 ESE 914 1,932 457 SE 1,097 2,091 1,105 SSE 914 1,771 876 S 610 1,771 610 ~ 'N SSW 518 7,080 457 N SW 549 4,073 533 WSW 1,585 2,252 457 4 W 1,570 2,252 360 354 WNW 610 419 'NW 436 NNW NOTE: There are no milk cows, milk goats, or meat animals within the 8,046 m radius of the site. The nearest milk cow and milk goat are located 8,690 m east of the site. 1 BN1-11600.02-112 1 of 1 Revision 1 - August 1983 - - -, _. ~... --. _ _. - _, _. _ - _ _ - -, -. _ _ -.. - -.. - ~ _. _. _. _ -. - - - -.. -., _,.. -.. -. _. _. _.

f w. SNPS-1 ODCM TABLE 3.5-9 P STORE 3 b GETABLES DOSE RATE CONVERSION FACTORS FOR CHILD INGESTION OF LEAFY y(area /yr/pCi/sec) i CONTAMINATED GROUND, m Isotope Bone Liver T. Body Thyroid Kidney g GI-LLI i Cr-51 4.9E+06 4.9E+06 4.9E+06 4.9E+06 4.9E+06 4.9E+06 1.5E+07 4 l l Mn-54 1.3E+09 1.7E+09 1.4E+09 1.3E+09 1.4E+09 1.3d+09 2.3E+09 Fe-59 a.9E+08 5.5E+08 3.8E+08 2.7E+08 2.7E+08 3.5E+08 1.2E+O9 Co-58 3.8E+08 4.6E+08 6.1E+08 3.8E+08 3.8E+08 3.8E+08 8.3E+04 i i Co-60 2.2E+10 2.2E+10 2.3E+10 2.2E+10 2.2E+10 2.2E+10 2.4E+10 1 Zn-65 1.3E+09 2.2E+09 1.4E+09 8.4E+08 1.7E+09 8.4E+08 1.7E+09 Sr-89 4.3E+10 2.1E+04 1.2E+09 2.lE404 2.lE+C4 2.lE+0<* 1.6E+09 Sr-90 1.7E+12 5.3E+06 4.1E+11 5.3E+06 5.3E+06 5.3E+06 2.2E+10 Zr-95 5.0E+08 4.9E+08 4.9E+08 4.9E+08 5.0E+08 4.9E+08 1.4E+09 Sb-124 7.lE+08 6.lE+08 6.5E+08 6.1E+08 6.1E+08 6.9E+08 3.5E+09 I-131 7.2E+07 7.2E+07 9.3E+06 2.2E+10 4.7E+07 4.3E+06 1.0E+07 l I-133 2.3E+06 2.7E+06 1.4E+06 5.1E+08 1.8E+06 6.0E+05 1.5E+06 Cs-134 2.4E+10 3.5E+10 1.3E+10 6.9E+09 1.1E+10 1.0E+10 7.1E+09 Cs-136 1.7E+08 2.4E+08 2.2E+08 1.5E+08 2.0E+08 1.6E+08 1.6E+08 Cs-137 3.9E+10 3.7E+10 1.4E+10 1.0E+10 1.4E+10 1.4E+10 1.0E+10 i Revision 1 - August 1983 1 of 2 1 l BN1-11600.02-103

SNPS-1 ODCM-TADLE 3.5-9 (CONT'lk)- Isotope Bone Liver T. Body Thyroid Kidney h CI-LLI Ba-140 4.5Ev08 .1.7E+08 1.9E+08 1.7E+08 1.7E+08 1.7E+08 1.8E+08 Ce-141 1.4E+07 1.4E+07 1.4E+07 1.4E+07-1$4E+07 1.4E+07 4.6E+08 i 'i i i f f l I Revision 1 - August 1983 2 of 2 BN1-II600.02-103

' Q SNPS-1 ODCM IABLE 3.5-10 P,g) CHILD INGESTION OF COW'S MILK DOSE RATE CONVERSION FACTORS 2 m (ares /yr/nci/sec) 1 anj( GI-LLI Isotope Bone Liver T. Body Thyroid Kidney 3 -(I) 1.3E+04 7.7E+03 2.8E+03 1.7E+04 3.2E+06 Cr-51 Mn-54 4.2E+06 7.9E+05 1.2E+06 1.3E+07 Fe-59 1.4E+07 3.1E+07 .1.2E+07 8.8E+06 1.0E+08 J -Co-58 5.3E+06 1.6E+07 3.2E+07 Co-60 2.0E+07 6.1E+07 1,1E+08 Zn-65 -7.9E+08 2.6E+09 1.1E+09 1.7E+09 1.6E+09 Sr-89 2.9E+09 8.4E+07 1.1E+08 Sr-90 6.2E+10 1.5E+10 1.8E+08 2.3E+02 3.5E+05 Zr-95 1.5L+03 3.5E+02 3.1E+02 Sb-124 1.2E+07 2.2E+05 4.5E+06 2.9E+04 9.0E+06 3.2E+08 I-131 2.7E+08 2.8E+08 2.1E+07 8.9E+10 1.7E+08 2.4E+07 I-133 3.9E406 4.8E+06 1.9E+06 -1.9E+09 2.8E+06 1.9E+06 Cs-134 1.0E+10 1.7E+10 3.6E+09 2.2E+09 1.9E+09 9.4E+07 Cs-136 1.2E+08 4.6E+08 3.4E+08 2.6E+08 3.7E+07 5.4E+07 Cs-137 1.5E+10 1.5E+10 2.2E+09 1.9E+09 1.7E+09 9.1E+07 BN1-11600.02-104 1 of 2 Revision 1 - August 1983

_,._.-_m O 3 SNPS-1 ODCM i TABLE 3.5-10 (CONT'D) i

Isotope Bone Liver T. Body Thyroid Kidney g

CI-LLI i Ba-140 4.9E+07 4.3E+04-2.9E+06 5.2E+03 2.6E+04 2.5E+06-l' 1 J Ce-141 5.1E+04 2.7E+04 3.8E+03 4.0E+03 3.1E+07 I' 1 (1)The dash (-) indicates insufficient data or that the dose factor is.<1.0E-20. t 4 e' I l 1 1, 1 3 l 1 i f l 4 i l l 1 } 1 i 1 ) i BN1-11600.02-104 .2 of 2 Revision 1 - August 1983 4 m 1-. - + -- m- --+ e

O O O SNPS-1 ODCM TABLE 3.5-11 P gy o CHILD INGESTION OF QT'S MILK DOSE RATE CONVERSION FACTORS (area /yr/>Ci/sec) a Icotope Bone Liver T. Body Thyroid Kidney-Lung GI-LLI cr-51 -(I) .1.6E+03 9.1E+02 3.4E+02 2.0E+03 3.8E+05 Mn-54 5.0E+05 9.5E+04 1.5E+05 1.5E+06 Fe-59 1.7E+05 4.1E+05 1.6E+05 1.1E+05 1.4E+06 Co-58 6.4E+05 2.0E+06 3.8E+06 Co-60 2.5E+06 7.4E+06 1.4E+07 Zn-65 9.7E+07 3.0E+08 1.4E+08 2.0E+08 1.9E+08 Sr-89 6.0E+09 1.7E+08 2.3E+08 Sr-90 1.2E+11 3.1E+10 1.7E+09 Zr-95 1.7E+02 4.0E+01 3.7E+01 2.7E+01 4.3E+04 Sb-124 1.4E+06 2.6E+04

5. 6E+05 3.4E+03 1.1E+06 4.0E+07 I-131 3.2E+08 3.2E+08 2.;E+07 1.1E+11 2.0E+08 2.8E+07 I-133 4.7E+06 5.8E+06 2.3E+06 1.4E+09 3.4E+06 2.3E+06 Cs-134 3.1E+10 5.1E+10 1.1E+10 6.7E+09 5.8E+09 2.9E+08 Cs-136 3.7E+08 1.4E+09 1.0E+09 7.7E+08 1.1E+08 1.6E+08 Cs-137 4.7E+10 4.5E+10 6.7E+09 5.6E+09 5.2E+09 2.7E+08 BN1-11600.02-105 1 of 2 Revision 1 - August 1983

O O O-j. SNPS-1 ODCM M BLE 3.5-11 (C0Kf'D) 1 Isotope' Bone Liver T. Body Thyroid Kidney M GI-LLI 4 i l Ba-140 6.0E+06 5.2E+03-3.5E+05 6.3E+02 3.1E+03 3.1E+05 i Ce-141-6.2E+03 3.1E+03 4.7E+02 4.9E+02 3.8E+06 i 1 l (1)The dash (-) indicates insufficient. data or that the dose factor is <1.0E-20. i i 1 I i j' l 3 t ) i BN1-11600.02-105 2 of 2 Revision 1 - August 1983 l i .m

O O O SNPS-1 ODCM TABLE 3.5-12 P,g) . CHILD INGESTION OE MEAT DOSE RATE CONVERSION FACTORS m' (ares /yr/ICi/sec) Isotope Bone Liver T. Body Thyroid Kidney -g CI-LLI 1.1E+03 6.7E+02 ,2.5E+02 1.5E+03 2.8E W -(1) Cr-51 Mn-54 1.2E+06 2.3E+05 3.4E+05 3.7E+06 2.7E+07 3.2E+08 Fe-59 4.2E+07 9.9E+07 3.7E+07 Co-58 7.2E+06 2.2E+07 '4.3E+07 Co-60 3.3E+07 9.7E+07 1.9E+08 1.5E+08 1.5E+08 Zn-65 7.0E+07 2.3E+08 1.1E+08 6.0E+06 ~- 7.8E+06 Sr-89 2.IE+08 7.3E+07 1.4E+09 Sr-90 5.6E+09 2.5E+08 Zr-95 1.0E+06 2.5E+05 2.3E+05 1.5E+05 Sb-124 3.2E+06 5.8E+04 1.2E+06 7.7E+03 2.4E+06 9.0E+07 1-131 3.5E+06 3.5E+06 2.7E+05 1.1E+09 2.2E+06 3.0E+05 1-133 1.3E-01 1.6C-01 6.4E-02 3.9E+01 9.7E-02 6.6E-02 Cs-134 4.2E+08 7.1E+08 1.5E+08 8.9E+07 7.8E+07 3.8E+06 Cs-136 1.9E+06 7.4E+06 5.4E+06 4.3E+06 5.7E+05 8.5E+05 7.6E+07 7.2E+07 3.7E+06 Cs-137 6.4E+08 6.2E+08 9.3E+07 BN1-11600.02-106 1 of 2 Revision 1 - August 1983

i' i i j SNPS-1 ODCM 4 i-TABLE'3.5-12.(CONT'D) i i Isotope Bone Liver T. Body Thyroid Kidney Igrg[ CI-LLI Ba-140 1.9E+07 1.7E+04 1.1E+06 2.0E+03 9.7E+03 9.4E+05 Ce-141 8.7E+03 4.2E+03 6.5E+02 6.7E+02 5.3E+06 P 1 i \\^1The dash (-) indicates insufficient data or that the dose factor is <1.0E-20. i i } 1 i. t i 1 k i i } L l I -i i I i i i i e BN1-11600.02-106 2 of 2 Revision 1 - August 1983 l ~ \\

k SNPS-1 ODCM TABLE 3.5-13 Pog) i INFANTINGESIIONO{ COW'SHILKDOSECONVERSIONFACTORS (aremfyr/LCi/sec) a Isotope Bone Liver T. Body Thyroid Kidney Iarry( GI-LLI - (I) 1.3E+04 7.7E+03 2.8E+03 1.7E+04 3.2E+06 Cr-51 Mn-54 4.2E+06 7.9E+05 1.2E+06 1.3E+07 Fe-59 1.4E+07 3.1E+07 1.2E+07 8.8E+06 1.0E+08 j 1 Co-58 1.1E+07 2.7E+07 2.8E+07 Co-60 4.3E+07 1.0E+08 1.0E+08 l 2h-65 7.9E+08 2.6E+09 1.1E+09 1.7E+09 1.6E+09 1 ) Sr-89 6.3E+09 1.8E+08 1.2E+08 Sr-90 -8.4E+10 2.2E+10 8.4E+08 Zr-95 2.9E+03 7.4E+02 5.3E+02 2.3E+02 3.3E+05 Sb-124 1.2E+07 2.2E+05 4.5E+06 2.9E+04 9.0E+06 3.2E+08 I-131 5.7E+08 0.7E+08 3.8E+08 2.2E+11 1.7E+08 2.6E+07 j I-133 8.0E+06 1.2E+07 3.6E+06 2.8E+09 2.8E+06 2.2E+06 Cs-134 2.1E+10 3.8E+10 3.1E+09 2.2E+09 4.2E+09 8.9E+07 Cs-136 1.2E+08 4.6E+08 3.4E+08 2.6E+08 3.7E+07 5.4E+07 Cs-137 3.2E+10 3.7E+10 2.0E+09 1.9E+09 4.4E+09 9.4E+07 i BN1-11600.02-107 1 of 2 Revision 1 - August 1983 i )

.. ~,, -.,.. ~,.. --. - =. . ~. 1 I ) i 4 I i SNPS-1 ODCM l TABLE 3.5-13 (CONT'D) j } j Isotope Bone Liver T. Body Thyroid Kidney M CI-LLI i Ba-140 1.0E+08 1.0E+05 8.4E+06 5.2E+03 6.5E+04 2.6E+06 ( i 3.3E+07 Ce-141 1.1F+05 '6.7E+04 7.8E+03 4.0E+03 s i (1)The dash (-) indicates insufficient data or that the dose factor is <1.0E-20. i i I 4 t l i I i i i l I BN1-11600.02-107 2 of 2 Revision 1 - August 1983

O O D 0 0 SNPS-1 ODCM TABLE 3.5-14 k i oij INFANT INGESTION OF GOAT'S. MILK DOSE CONVERSION FACTORS 2 (mres/yr/tci/sec) m Isotope Bone Liver T. Body Thyroid Kidney Lung CI-LLI i i Cr-51 CI) 1.6E+03 9.1E+02 3.4E+02 2.0E+03 3.8E+05 Mn-54 5.0E+05 9.5E+04 1.5E+05 1.5E+06 1 j Fe-59 1.7E+05 4.1E+05 1.6E+05 1.1E+05 1.4E+06 Co-58 1.3E+06 3.2E+06 3.4E+06 i j Co-60 5.1E+06 1.2E+07 1.3E+07 l Zn-65 9.7E+07 3.0E+08 1.4E+08 2.0E+08 1.9E+08 3 Sr-89 1.3E+10 3.6E+08 2.4E+08 4 j Sr-90 1.8E+11 4.7E+10 1.7E+09 1 j Zr-95 3.5E+02 9.0E+01 6.4E+01 2.7E+01 4.1E+04 i Sb-124 1.4E+06 2.6E+05 5.6E+05 3.4E+03 1.1E+06 4.0E+07 l I-131 6.7E+08 8.0E+08 4.8E+08 2.6E+11 2.0E+08 3.1E+07 i 1-133 9.7E+06 1.4E+07 4.3E+06 3.4E+09 3.4E+06 2.6E+06 l Cs-134 6.2E+10 1.1E+11 9.6E+09 6.7E+09 1.3E+10 2.7E+05 i Cs-136 3.7E+08 1.4E+09 1.0E+09 7.7E+08 1.1E+08 1.6E+08 1 Cs-137 9.8E+10 1.1E+11 6.2E+09 5.6E+09 1.3E+10 2.9E+08 4 i BN1-11600.02-108 1 of 2 Revision 1 - August 1983 I a

~ 4 SNPS-1 ODCM TABLE 3.5-14 (CONT'D) I 1 Isotope Bone Liver T. Body _ Thyroid Kidney M GI-LLI I Ba-140 1.2E+07 1.3E+04 6.5E+05 6.3E+02 7.7E+03 3.2E+05 2 Ce-141 1.3E+04 8.0E+03 9.4E+02 4.9E+02 3.8E+06 l 3 j (1)The dash (-) indicates insufficient data or that the dose factor is <1.0E-20. r l I i I I.. I 1 I k t ) 1 BN1-11600.02-108 2 of 2 Revision 1 - August 1983 i e

SNPS-1 ODCM O 3.6 OPERATION OF VENTILATION EXHAUST TREAT)ENT SYSTEM 4 The Ventilation Exhaust Treatment System (see Figure 3.6-1) shall be used to reduce radioactive materials in gaseous waste prior to their discharge as specified in R8TS Section 3.11.2.5. The dose analysis will be performed as described in Sections 3.5.1 or 3.5.2. If the calculated doses exceed the limits specified above consult RETS Section 3.11.2.5. 4 1 I V s on 1 - August 1983 ~ --.4 -..-,-,....,_._..r-,,_.m ,y .--,-.,...r.. e.,-. ,.,-.,w.m....

O O O STATION VENTILATION i I EXHAUST HEPA 4300 CFM J k CHEM. LABORATORY EXHAUST CHEM. LABORATORY FILTER .i DRYWELL PURGE 1200 CFM PRIMARY AND I CONTAINMENT HEPA 1 FILTERS 1 i BUILDING VENTILATION HEPA 40,000 CFM F ILTE R R AD WASTE d ' BUILDING 22T0 CFM N [ENT AND RADWASTE TANK HEPA j VENT FILTE R S I l OFFGAS i TREATMENT } SYSTE M OFFGAS TRE ATMENT EXHAUST H EPA (CH AR COAL) p i FIGURE 3.6-1 VENTILATION EXHAUST l TREATMENT SYSTEM SHOREH AM NUCLE AR POWER STATION - UNIT-1 OFFSITE DOSE CALCULATION MANUAL i REVISION 1-AUGUST 1983 1 l i,

SNPS-1 ODCM O 3.7 TOTAL DOSE FOR THE URANIUM FUEL CYCLE V To comply with Section 3.11.4 of the RETS which implements 40CFR190, radiation doses shall be limited as follows: The dose or dose commitment to a member of the public, due to releases of radioactivity and radiation, from uranium fuel cycle sources shall be limited to 25 mrem, or less, to the total body and/or any organ (except the tnyroid, which shall be limited to 75 mres, or less), over any 12 consecutive months. 3.7.1 Sources of Radiation and Radioactivity The uranium fuel cycle is defined in 40CFR190 to include: a. operations of milling of uranium ore, b. chemical conversion of uranium, c. isotopic enrichment of uranium, d. fabrication of uranium fuel, e. generation of electricity by a nuclear power plant using uranium fuel, and f. reprocessing of spent uranium fuel. d The maximum individual doses due to each of the processing facilities for items a, b, c, d, and f above are required to be less than 10CFR20 limits. Therefore, the dose contribution to any person living in the Shoreham service area due to the abore facilities, which are all more than 125 kilometers distance away, is expected tu be negligible compare to 40CFR190 limits. The only radiological source of concern will be due to item e above. The nearest nuclear power plant using uranium fuel is more than 75 kilometers away. 3.7.2 Radiological Impact of Generation of Electricity The generation of electricity using a nuclear power plant results in radicactivity released in gaseous and liquid effluents. The ' dose rate assessment of these is done in Section 3.3. The radiological impact of direct radiation (including skyshine) from the plant can be determined by measurement. The direct radiation measuring devices (TLD systems) are provided by the Radiological Environmental Monitoring Program (REMP) and listed in Tables 5-1 and 5-4. Dose regis.tered by the TLDs will be added to the doses calculated in Sections 3.1.1 (Dose From Liquid Ef fluent) and 3.5.1 (dose to maximum individual due to 2 inhalation and ingestion from gaseous effluents) to determine the total body dose due to all sources of radiation in the uranium fuel cycle. BN1-11600.02-112 3.7-1 Revision 2 - September 1983 o

SNPS-1 ODCM SECTION 4 RECEPTOR LOCATIONS, METEOROLOGY, AND HYDROLOGY s The purpose of this section is to identify those receptor locations which represent critical pathway locations and to specify the dilution, dispersion, and deposition f actors at these locations to be used in Calculation Method 2 when computerized radiation monitoring system is inoperable. For liquid effluent psthways a calculated dilution f actor of 8.85 is used in the backup method. For gaseous effluent pathways, Table 4-1 lists the critical locations for receptors and their respective dispersion and deposition factors. The atmospheric dispersion and deposition factors were calculated based on onsite meteorological data for the 2-year period of October 1,1973 through September 30, 1975 and the Final Environmental Statement, NUREG-0285, - dated October 2 1977, docket No. 50-322, Regulatory Guide 1.109 (March 1976) methodology and parameters, excep as noted above, were used in the backup method dose rate conversion factors. I O i l l t l l f 11600-112 4-1 Revision 2 - September 1983 ,\\ e l l

O O O i SNPS-1 ODCM TABLE 4-1 l CRITICAL RECEPTOR LOCATIONS FOR GASEOUS EFFLUENT CALCULATIONS Technical Specification 3.11.2.1 '3.11.2.2 3.11.2.3 3.11.2.5 Section 1 Sections in this Manual 3.3 3.4 3.5 3.6 j Limiting Criteria Instantaneous Dose Quarterly and Annual Quarterly and Dose to any organ . Rate to Whole Body Air Doses due to Annual Dose due due to radionuclides-and Skin due to Gamma and Beta to radionuclides other than' Noble Gas Noble Gas and Dose radiation other than Noble for 31 day period j to any organ due Gas i to radionuclides l other than Noble Gas { Distance and Direction

1) Noble Gas:

457 meters, ESE' 1931 meters, ESE 1931 meters, ESE j of Receptor from the 366 meters, NNE i. Plant

2) Organ:

1931 meters, ESE Description of Location Location of highest Location of highest Location of Location of highest { Dose Rate Dose highest Dose Dose f Long Tern Atmospheric

1) 6.6E-07 sec/m 8.44E-07 sec/m 1.3E-07 sec/m 1.3E-07 sec/m3 3

3 3 3 Dispersion Factor for

2) 1.3E-07 sec/m Station Ventilation 4

Exhaust X/Qt 3 3 3 3 Short Tern Atmospheric

1) 3.6E-06 sec/m 1.83E-06 sec/m 6.0E-06 rsec/m 6.0E-06 sec/m 3

i Dispersion Factor for

2) 6.0E-06 sec/m j

Air Removal Pump X/Q2 i 3 3 3 3 ) Short Tera Atmospheric

1) 3.6E-06 sec/m 1.83E-06 sec/m 6.0E-06 sec/m 6.0E-06 sec/m 3

1 Dispersion Factor for

2) 6.0E-06 sec/m

) Containment Drywell j Purge X/Q3 1 Revision 1 - August 1983 4 1 of 2 BN1-11600.02-109 f i

.~ _ __. __ x i i j SNPS-1 ODCM ] TABLE 4-1 (CONT'D) i l Long Tern Relative

1) NA NA 8.6E-09 m-2 8.6E-09m-2

{ Deposition Factor for

2) 8.6E-09 m-2 Station Ventilation Exhaust D/Qg Short Tern Relative

1) NA NA 4.0E-08 m-2 4.0E-08 m-2 Deposition Factor for

2) 4.0E-08 m-2 l

Air Removal Pump D/Q2 i Short Tern Relative

1) NA NA 4.0E-08 m-2 4.0E-08 m-2 Deposition Factor f,e

2) 4.0E-08 m-2 l

Containment Drywell j Purge D/Q3 i i i i i i 5 Revision 1 - August 1983 l 2 of 2 l BN1-11600.02-109

SNPS-1 ODCM SECTION 5 RADIOLOGICAL ENVIRON! ENTAL PONITORING PROGRAM SAMPLING LOCATIONS a The purpose of this section is to identify those sampling locations from which the radiological environmental monitoring samples shall be collected pursuant to Technical Specification 3/4.12. Sampling locations for on site and off site locations are shown on. Figures 5-1 and 5-2, respectively. The number and frequency for samplit.g at these t locations is given in Table 5-1 which is taken from Technical Specification j Table 3.12.1-1. Radiological Environmental Monitoring Program monitoring stations are given in Tables 5-2, 5-3, 5-4, and 5-5. k ) I h l BN1-11600.02 5-1 Revision 1 - August 1983 il

O SNPS-1 ODCM TABLE 5-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM * (SAMPLING AND COLLECTION PREQUENCY) EXPOSURE PATHWAY NIMBER OF REPRESElffATIVE . SAMPLING AND . TYPE'AND FREQUENCY AND/OR SAMPLE SAMPLES AND SAMPLE IDCATIONa COLLECTION FREQUENCY OF ANALYSIS 1. DIRECT RADIATIONb 36 routine monitoring stations, Quarterly. Gamma dose quarterly. DRI-DR36, either with two or more dosimeters or with one instrument for measuring and recording dose rate continuously, placed as follows: a. An inner ring of stations, one in each meteorological sector in the general area of the SITE BOUNDARY, DRI-DR16; b. An outer ring of stations, one in each meteorological sector in the 6-to 8-km range from the site, DR17-DR25; c. The balance of the stations, DR26-DR36, to be placed in special interest areas such as population centers, nearby residences, schools, and in 1 or 2 areas to serve as control stations.

• The number, media, frequency, and location of samples may vary from site to site. This table presents an acceptable minimum program for a site at which each entry is applicable. Local site characteristics must be examined to determine if pathways not covered by this table may significantly contribute to an individual's dose and should be included in the sampling program. The code letters in parentheses, e.g., DR1, Al, provide one way of defining generic sample locations in this specification that can be used to identify the specific locations in the map (s) and tables in the ODCM.

1 of 5 BN1-11600.02-Il3 Revision 1 - August 1983

m k SNPS-1 ODCM i TABLE 5-1 (cont) EXPOSURE PATHWAY NUlBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY AND/OR SAWLE SAWLES AND SAMPLE LOCATIONa COLLECTION FREQUENCY OF ANALYSIS + 2. AIRBORNE -Radioiodine and Samples from 5 locations, Al-AS: Continuous sampler Radioiodine Cannit ter: } Particulates operatin with sample 1-131 analysis weekly. i 3 samples, Al-A3* from close collection weekly, or to the 3 SITE BOUNDARY locations, more frequently if in different sectors, of the required by dust Particulate Sampler: l highest calculated annual average loading. ~ Gross beta radioactivity j groundlevel D/Q. analysis following i filter change; d 1 sample, A4, from the vicir.ity Gamma isotopic analysis

• i of a community having the highest of composite (by calculated annual average groundlevel location).

l D/Q. { 1 sample, AS, from a control location, as for example 15-30 km distant and in j the least prevalent wind direction. ) 3. WATERBORNE a. Surface 1 sample control, WAl Grab sample semi-Gamma isotopic analysis' I (Long Island I sample discharge, WA2 or WA3 annually. and tritium analysia Sound) semi-annually. i b. Ground Samples from 1 or 2 sources, Wbl. Quarterly. Gamma isotopic" and i Wb2, only if likely to be affected. tritium analysis j quarterly. 1 } c. Sediment form I sample from downstream area with Semi-annually. Gamma isotopic analysis * { shoreline existing or potential recreational semi-annually. j value, Wdl. 1 The first and second highest D/Q sectors have radioiodine and particulate samples. 'The third highest D/Q sector at the SITE BOUNDARY is approximately 150 ft from the first highest sector, 4 a k 2 of 5 l BN1-11600.02-113 Revision 1 - August 1,983

r f (h /~ (~ %/ ) SNPS-1 ODCM TABLE 5-1 (cont) EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLES AND SAMPLE LOCATIONa COLLECTION FREQUENCY OF ANALYSIS 1 4. INGESTION a. Milk Samples from milking animals in Semi-monthly when Gamma isotopic" and I-131 I location, Ial, within 5 km distance animals are on analysis semi-monthly when having the highest dose potential. pasture, monthly at animals are on pasture; If there are none, then, I sample other times. monthly at other times. from milking animals in each of 4 3 areas, Ial, betw2en 5 to 8 km or 8 to 17 km if none are 2 1 available within 8 km distant where doses are calculated g to be greater than 1 arem per yr. I 1 sample from milking animals at a control location, Ia2, 15-30 km distant and not in the least 2 ] prevalent wind directions. 1 b. Fish and i sample of each commercially and Sa ple semi-Gamma isotopic analysis

• Invertebrates recreationally important species in annually.

on edible portions. vicinity of plant discharge area, l Ib1 - Ib2. { 1 sample of same species in areas not j influenced by plant discharge, Ib3. i c. Food Products Samples of 3 different kinds of broad At time of Gamma Isotopic" and leak vegetation grown nearest each of harvest.8 I-131 analysis. two different offsite locations of highest predicted annual average j ground-level D/Q, if milk sampling is not performed, Ic1 - Ic3. i i sample of each of the similar broad At time of Gamma isotopic" leak vegetation grown 15-30 km distant harvest 8 and 1-131 analysis. g in the least prevalent wind direction if milk sampling is not perform, Ic3. i BN1-11600-113 3 of 5 Revision 2 - September 1983 h

O O O bHPS-1 ODCM i TABLE 5-1 (cont) TABLE NOTATION

• Specific parameters of distance and direction sector from the centerline of one reactor, and additional description where pertinent, are provided for each and every sample location in Table 3.12.1-1 in a table and figure in the ODCM.

Refer to NUREG-0133, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978, and to Radiological Assessment Branch Technical Position, Revision 1, November 1979. 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 i 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 documented in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.7. It is recognized that, at times, it may not be possible or practicable co 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. In lieu of a Licensee Event Report and pursuant to Specification. 6.9.1.9, identify the cause 1-of the unavailability of samples for that pathway and identify the new location (s) for obtaining ' replacement j samples in the next Semi-annual Radioactive Effluent Release Report and also included in the report a revised. l figure (s) and table for the GDOt reflecting the new location (s). a j h One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously any l be used in place of, or in addition to, integrating dosimeters. For the purposes of this table, a i thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors in packet are considered E j as two or more dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation. The i frequency of analysis or readout for TLD systems will depend upon the characteristics of the specific system used' } and should be selected to obtain optimia dose information with minimal fading. I J c The purpose of this sample is to obtain background information. If it is not practical to establish' control j locations in accordance with the distance and wind direction criteria, other sites that provide valid background j data may be substituted. i S a 1 1 3 E 4 1 l i j 4 of 5 3 BN1-ll600.02-Il3 Revision 1 - August 1983 + 4

O O O j - i ) SNPS-1 ODCM I -TABLE 5-1 (cont) TABLE NOTATION

• Specific parameters.of distance and direction sector from the centerline of one reactor, and additional description where pertinent, are provided for each and every sample location in Table 3.12.1-1 in a table and figure in 'the ODCN.

Refer - to NUREG-0133, " Preparation of Radiological Effluent Technical Specifications for Nuclear. Power - t Plants," October 1978, and to Radiological Assessment Branch Technical Position, Revision 1, November 1979. 1 Deviations a::e permitted from the required sampling schedule if specimens are unobtainable due to hazardous j conditions, seasonal unavailability, malfunction of automatic sampling equipment, and other legitimate reasons. LIf 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 documented i in the Annual Radiological. Environmental Operating Report pursuant to Specification 6.9.1.7. It is recognized 3 1 that, at times, it may not be possible :or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances suitable alternative media and locations any be chosen ' for ' the 4 particular pathway in question and appropriate substitutions made within 30 days in the radiological environmental j monitoring program. In lieu of a Licensee Event ~ Report and pursuar.c to Specification 6.9.1.9, identify the cause of the unavailability of samples for that pathway and identify the new location (s) for ' obtaining replacement l samples in the next Semi-annual Radioactive, Effluent Release Report and also included in the report a revised figure (s) and table for the ODQi reflecting the new location (s). b j One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously any i be used in place of, or in addition to.. integrating dosimeters. For the purposes '.of this ' table, a j thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors in packet are considered j as two or more dosimeters. Film badges. shall not be used as dosimeters for measuring direct radiation. The frequency of analysis or readout. for TLD systems will depend upon the characteristics of the specific. system used I and should be selected to obtain optimum dose information with minimal fading. s c The purpose of this sample is to obtain background information. If it is not practical to establish control-locations in accordance with the distance.and wind direction criteria, other sites that provide valid background data may be substituted. 1 y l i i i ). i l l 1 a 4 of 5 BN1-11600.02-113 Revision 1 - August 1983

m . ) { CV) T SNPS-1 ODCM TABE 5-1 (cont). TABE NOTATION d Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours or more af ter sampling - l to allow for radon and thc aughter decay. If gross beta activity in air particulate samples is greater than 10 times the yearly mean of control samples, gauma isotopic analysis shall be performed on individual samples. 1

• Camma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents.from the facility.

f The dose shall be calculated for the maximum organ and age group, using the methodology and parameters in the ODCM. 8 If harvest occurs more than once a year, sampling shall be performed during each discrete harvest. If harvest occurs continuously, sampling shall be monthly. Attention shall be paid to including samples of tuberous and root food products. I T 4 i i i e 4 a W i 4 l 5 of 5 BN1-11600.02-Il3 Revision 1 - August 1983

=. SNPS-1 ODCM p TABLE 5-2 O RALIOLOGICAL ENVIRON) ENTAL MONITORING PROGRAM (REMP) WATERBORNE 20NITORING STATIONS Location Codes NUREG-0473 Shoreham REMP Location Description WA1 3Cl Surface, outfall area, 2.9 mi. NE WA2 14Cl Surface, outfall area, 2.1 31. WNW WA3 13G2 Surface, background area, 13,3 mi. W Wbl 2S1 Potable Water, well on site, 0.1 mi. NNE Wb2 13S2 Potable Water, well on site, 0.2 mi. W Wb3 1081 Potable Water, background well, 1.5 mi. SSW Wdi 2A4 Sediment, beach, 0.4 mi NNE bU I BN1-11600.02-112 1 of 1 Revision 1 - August 1983 O ,.-_.__..____..._,.,.,_.._,...___-..____.-mm. .,__,..__,_,...,_.m__.._,..,m-. ._.,m,.

SNPS-1 ODCM TABLE 5-3 L RADIOLOGICAL ENVIRONENTAL MONITORING PROGRAM (REMP) (PARTICULATES AND RADI0 IODINE) Location Codes NUREG-0473 Shoreham REMP Location Description j A1 6S2 Site Boundary, 0.1 mi. ESE A2 2A2 West end of Creek Road, 0.2 mi. NNE A3 3S1 Site Boundary, 0.1 mi, NE A4 7B1 Overhill Road, 1.5 mi. SE i. A5 1101 MacArthur Substation, 16,6 mi. SW i L + 4 i k t t BN1-11600.02-112 1 of 1 Revision 1 - August 1983 J 1 i

SNPS-1 ODCM 4 TABLE 5-4 RADIOLOGICAL ENVIRONENTAL }ONITORING PROGRAM (REW) DIRECT RADIATION MONITORING STATIONS Location Codes NUREG-0473 -Shoreham RE W Location Description . DR1 ISI

Beach east of intake, 0.3 mi. N DR2 2A2 West end of Creek Road. 0.2 mi. NNE l

DR3 3Si Site Boundary, 0.1 mi. NE DR4 4S1 Site Boundary, 0.1 mi. ENE DRS SS2 Site Boundary, 0.1 mi. E DR6 6S2 Site Boundary, 0.1 mi. ESE DR7 7A2 North Country Road, 0.7 mi. SE DR8 _8A3 North Country Road, 0.6 mi. SSE DR9 9S1 Service Road SNPS, 0.3 mi. S DR10 10A1 North Country Road, 0.3 mi. SSW 4 DR11 11A1 Site Boundary, 0.2 mi. SW DR12 _12A1 Meteorological Tower, 0.9 mi, WSW DR13 13S3 Site Boundary, 0.3 mi. W DR14 14S2 St. Joseph's Villa, 0.4 mi. WNW DR15 15S1 Beach west of intake, 0.3 mi. NW DR16 16S2 Site Boundary 0.2 mi. NNW -DR17 SD3 Wildwood State Park, 3.4 mi. E DR18 6El LILCO ROW, 4.8 mi. ESE O. DR19 7El Calverton, 5.0 mi. SE DR20 8E1 Calverton, 4.4 mi. SSE DR21 9El Brookhaven National Laboratory, 5.0 mi. S-I DR22 10E1 Ridge Substation, 4.0 mi. SSW DR23 11El LILCO ROW. 4.7 mi. SW DR24 12D1 North Shore Beach Substation, 1-3.7 mi. WSW DR25 13E1 Sound Way Drive, 4.5 mi. W DR26 SD1 Wildwood State Park, 3.4 mi. E DR27 SF3 Dairy Farm, 7.8 mi. E DR28 781 Overhill Road, 1.5 mi. SE DR29 12G2 Flowerfield Substation, 15.4 mi. WSW DR30 12G1 Central Islip Substation, 19.9 mi. WSW DR31 11G1 MacArthur Substation, 16.6 mi. SW DR32 8G1 Wading River Road, 10.1 mi. SSE DR33 6G1 Dairy Farm, 7.2 mi. ESE DR34 6Al Sound Road, 0.7 mi. ESE DR35 2A3 Nearest Residence, 0.3 mi. NNE i DR36 9S2 East Gate SNPS, 0.3 mi. S BN1-11600.02-112 1 of 1 Revision 1 - August 1983

~ SNPS-1 ODCM TABLE 5-5 RADIOLOGICAL ENVIRONIENTAL MONITORING PROGRAM (REMP) INGESTION HONITORING STATIONS Location Codes NUREG-0473 Shoreham REMP Location Description Ia1 6F1 Dairy Farm, 7.2 mi. ESE Ia2 10F1 Goat Farm, 9.2 mi. SSW Ia3 8G3 Goat Farm, 9.8 mi. SSE Ib1 3C1 Fish and Invertebrates, outfall area, 2.9 mi. NE Ib2 14C1 Fish and Invertebrates, outfall area 2.1 vai. WNW Ib3 13G2 Fish and Invertebretes, background, 13.3 mi. W Ic1 881 Local Farm, 1.2 mi. SSE Ic2 SC2 Local Farm, 2.8 mi. E Ic3 12H1 Background Farm, 26 mi. WSW O l l l l-i i f 1 BN1-11600.02-112 1 of 1 Revision 1 - August 1983 i \\

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• /

/ y \\ i g \\ s 07m 12At y f g \\ N s T ,/ I \\ \\ I \\ 's / / no.sS2g s s W / i \\ \\ / g \\ / f I \\ 7A2 Ih / / \\ / I \\ e \\ ,s' / l l ,e / \\ \\g 1 / / 1 a

• SCHEDULED FOR INSTALLATION 5 ARLY 1982 FIGURE 5-1 ONSITE SAMPLING LOCATIONS RADIOLOGICAL ENVIRONMENTAL i

i MONITORING PROGRAM 25 SCALE - MILES SHOREHAM NUCLEAR POWER S'ATION -UNIT 1 OFFSITE DOSE CALCULATION k'ANUAL REVISION 1-AUGUST 1983 e 4

/'% \\ U \\ a e>r / 's 'g l / N,' / N + s s l sb, N \\ si.oxalisuso,' souso 3GIs l s s ,,s / / s 's \\ s s s%6'B)( f ,I I x14C1 %A,.3g i m_____ ists* t b HOREHAMO l e 12G2 I 30 27 -- --- -.__,_ ' D ~~~~- k, 05: eg ci ~P~ 6Et'k 5 m / 73 V I;I ,/ -- / m ',' \\ 'N p 23 12GI,, 12 / 46 / \\ / / f \\ \\ 's CAY s IOFI '9 / q g N d l k \\ v/

• s'd

/ N z(, 2 27.., 'iisi / s 1 / /

• oz

~~ s / / / s s \\ GREA T,/ SOUTH BAY t \\ \\ / / \\ / I \\ l \\ \\ FIGURE 5-2 ~ '\\ - 1 RADIOLOGICAL ENVIRONMENTAL l / OFFSITE SAMPLING LOCATIONS MONITORING PROGRAM o 5 to S!!OREHAM NUCLEAR POWER STATION-UNIT 1 OFFSITE DOSE CALCULATION MANUAL SC A LE - MILF S REVISION 1-AUGUST 1983

. ~... - -, . -. - ~ - -. - - - - _ _ -.. t i t SNPS-1 ODCM SECTION'6' J INTERLABORATORY COMPARISON PROGRAM j - The interlaboratory comparison program is done in accordance with ~ EPA 1 recornmendations. - i: i; i t i 4 r i l 4 l t i i I i, G I t r t BN1-11600.02-112 6-1 Revision 1 - August 1983 5 9 1 1. . ~..... ~.

SNPS-1 ODCM APPENDIX A . d DERIVATION OF Ag7 -(ares / min per pCi/cc) is the dose conversion f actor for the combined fish _ Air plus seaf ood pathways due to a liquid radwaste system discharge. The doses to organ, j, due to ingestion of fish and seafood (contribution f rom shoreline deposit is considered insignificant) containing. isotope, i, were calculated by a computer code based on Regulatory Guide 1.109 methodology and default parameters. The results have been submitted to the NRC in document, "Shoreham Nuclear Power Station Unit 1 Compliance with 10CFR50 Appendix I" ' Docket 50-322, which also discusses in detail input data such as the radwaste system radioactive discharge and near field dilution fqtor of 8.85. i The computer isotopic dose rates output were normalized to unit intake concentration with the following equation: i Fij + sij A = Tij C /F g where: Dyij = Calculated fish ingestion dose rate (arem/ min) to organ, j, f rom isotope, i, (Ref. Reg. Guide 1.109, Eq. ( A-3)) } = Calculated seafood ingestion dose rate (mrem / min) to organ, j, D,g) from isotope, i, (Ref. Reg. Guide 1.109, Eq. (A-3)) C = Discharge concentration of isotope, i, (pCi/cc) 1 F = Near field dilution f actor, 8.85 (unitiess) 4 t' 4 f 4 BN1-11600.02-112 A-1 Revision 1 - August 1983 L -.m.

SNPS-1 ODCM APPENDIX B s ( ) DERIVATION OF Pogj P (" Y#) is the dose conversion f actor due to combined ef fect of ggj ingestion of leafy vegetables, ingestion of stored vegetables, (fruits, vegetables, and grains), and contaminated ground pathways, The dose delivered to organ, j, due to the combined effect of the 3 pathways we're calculated for each radioisotope, i, using a computer code based on Regulatory Guide 1.109 methodology and def ault parameters. The results have been submitted to the NRC in document, "Shoreham Nuclear Power Station Unit 1 Compliance with 10CFR50 Appendix I" Docket 50-322, which also discusses in detail input data such as radioactive gaseous effluents and deposition factors. The computer isotopic dose rates output were normalized to unit isotopic release rate and deposition factor with the equation: Degj + DLgj + Dsij p oij 3.17*10-2

• C
• D/Q where:

D = Calculated contaminated ground dose to organ, j, from cij /] isotope, i, ( / D = Calculated leafy vegetable ingestion dose to organ, j, from gg) isotope,i, D = Calculated stored vegetables dose to organ, j, from isotope, sij 1, C - Gaseous effluent release rate of isotope, i, (Ci/yr) g D/Q = Deposition factor (m-2) as used in calculation of Dcij ' Dgg), D,gy. 3.17*10-2 = The aumber of years peg second (3.17 x 10-8) times.the number of pCi per C1 (10 ). BN1-11600.02.112 B-1 Revision 1 - August 1983

y b 8 LONG ISLAND LIGHTING COMPANY AM SHOREHAM NUCLEAR POWER STATION _1__ 11---_;cc_4 P.O. BOX 618, NORTH COUNTRY ROAD e WADING RIVER, N.Y.11792 Direct Dial Number September 15, 1983 SNRC-967 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Offsite Dose Calculation Manual Shoreham Nuclear Power Station - Unit 1 Docket No. 50-322

Dear Mr. Denton:

Long Island Lighting Company hereby submits Revision 2 to the Offsite Dose Calculation Manual (ODCM). For the convenience of review, the entire ODCM is enclosed with the revised pages incorporated; therefore, this submittal includes Revision 1 which was hand-carried to Mr. R. Caruso on August 15 and Revision 2 which is indicated by change bars in the page margin. These revisions are in response to several rounds of verbal questions expressed by members of your staff,'and address all concerns identified to date with the exception of finalizing the upper range of several calibration curves. This additional information is forthcoming and will be submitted in the near future. l l Very truly yours, ] ps -0% J. L. Smith Manager, Special Projects RCW:jm / /[ cc: R. Caruso C. Petrone All Parties Listed in Attachment 1 FC 8935.1

c- .P o ATTACHMENT 1 Lawrence Brenner, Esq. Herbert H. Brown, Esq. Administrative Judge Lawrence Coe Lanpher, Esq. Atomic Safety and Licensing Karla J. Letsche, Esq. Board Panel Kirkpatrick, Lockhart, Hill U.S. Nuclear Regulatory Christopher & Phillips Commission 8th Floor . Washington, D.C. 20555 1900 M. Street, N.W. Washington, D.C. 20036 Dr. Peter A. Morris Administrative Judge Mr. Marc W. Goldsmith Atomic Safety and Licensing Energy Research Group Board Panel 4001 Totten Pond Road U.S. Nuclear Regulatory Waltham, Massachusetts 02154 Commission Washington, D.C. 20555 MHB Technical Associates 1723 Hamilton Avenue Dr. George A. Ferguson Suite K School of Engineering San Jose, California 95125 Howard University 2300 Fifth Street Washington, D.C. 20059 Stephen B. Latham, Esq. Twomey, Latham & Shea 33 West Second Street Daniel F. Brown, Esq. P.O. Box 398 Attorney Riverhead, New York 11901 Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Ralph Shapiro, Esq. Commission Cammer and Shapiro, P.C. Washington, D.C. 20555 9 East 40th Street New York, New York 10016 Bernard M. Bordenick, Esq. David A. Repka, Esq._ Matthew J. Kelly, Esq. I U.S. Nuclear-Regulatory State of New York Commission Department of Public Service Washingtor., D.C. 20555 Three Empire State Plaza Albany, New York 12223 Mr. James Dougherty 3045 Porter Street l Washington, D.C. 20008 l _}}