Text

ODCM for Virgil C Summer Nuclear Station
	ML20058P670
Person / Time
Site:	Summer
Issue date:	06/29/1990
From:	Blue L; SOUTH CAROLINA ELECTRIC & GAS CO.
To:	;
Shared Package
ML20058P661	List: ML20058P658; ML20058P665; ML20058P670;
References
	PROC-900629, NUDOCS 9008170263
	Download: ML20058P670 (192)
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ELECTRIC AND GAS COMPANY VIRGliC. SUMMER NUCLEAR STATION

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j j.. J.- j-CONTROLLED COPY DISTRIBUTION - l y r. Person gooy # ' General Manager, Nuclear Plant Operations . 1' 1 Manager, CHP& EP-2- Manager, Nuclear Licensing 3 ) ' Associate Manager, Health Physics 4. . Senior Staff Health Physicist 5 Supervisor, Radiological Analytical Services. 6 Supervisor, Count Room '7; Manager, Chemistry.and Health Physics 8{ 1 General Manager, Operations and Maintenance - . 9- - i t Supervisor, Nuclear Licensing 110 l Document Control & Records '11 L l-Manager, Technical Oversight 12 Associate Manager, Quality Assurance .13 Supervisor, Environmental Programs - 14. Resident NRC Inspector 15 f i q ' 1 'l - 1 i ('~') H ODCM, V.C. Summer /SCE&G: Revision 13 (June 1990) iv -a m ,,r p ,,n p pg9g y p-- 9 ye.er -w 9 gli $ w

,4 Table of Contents f .Q. PAGE St of Effective Pages i Controlled Copy Distribution List ~iv Table of Contents. v List of Tables........ vii List of Figures viii References ix Introd u ction.................. x t. 1.0 SPECIFICATION OF LIMITING CONDITIONS FOR OPERATION 1.1 - Lio uid E ffluents,,.......................... 1.0 1: i 1.1.1 Radioactive Liquid Effluent Monitoring Instrumentation 1.0-1 '1.1.2 Liquid Effluents: Concentration 1.0 8-1.1.3 Liquid Effluents: Dose................. 1.0-14 1.1.4 - Liquid Waste Treatment 1.0 15 1.2 Gaseous Effluents..... 1.0 17 1.2.1 Radioactive Gaseous Effluent Monitoring Instrumentation 1.0 17 1.2.2 Gaseous Effluents: Dose Rate 1.0 l 1.2.3 Gaseous Effluents: Dose Noble Gas......... 1.0-27' [ 1 2.4 Gasecus Effluents: Dose - RadioiodinestTritium-and Radioactive Materials in Particulate Form.. 1.0 28 1.2.5 Gaseous Radwaste Treatment............,,. ,1.0 29 1.3 Radioactive EHluents: Total Dose 1.0... t 1.4 Radioloaical Environmental Monitorina'............. 1.0-33 1.4.1 Monitoring Program........ 1.0 33-1.4.2 Land Use Census 1.0 43 j -1.4.3 Interlaboratory Comparison Program 1.0 45 1.5 Bases 1.0 46 1.6 Reportina Reauirements 1.0 51 1.6.1 Annual Radiological Environmental Operating Report 1.0......... j 1.6.2 ' Semiannual Radioactive Effluent Release Report - 1.0 52 1.6.3 ~ Changes to the ODCM 1.0 54 1.6.4 Major Changes to Radioactive Waste Treatment System (Liquid and Gaseous) 1.0 55 a 1.7 Definitions 1.0 57' i ODCM, V.C. Summer /SCE&G: Revision 13 (June 1990) 4 V i i _~ u . =

o 2.0 LIOUID EFFLUENT-i 2.1. Liouid Effluent Monitor Setooint Calculation.......... 2.01 t 2.1.1-Liquid Effluent Monitor Setpoint; Calculation Parameters. 2.0-2 2.1.2: Liquid Radwaste Effluent Line Monitors....... 2.0 6 2.1.3 Liquid Radwaste Discharge Via Industrial and Sanitary Waste System....................... 2.0 14 2.1.4 Steam Generator Blowdown, Turbine Building Sump, and Condensate'Demineralizer Backwash. Effluent Lines.............................. : 2.0 15 1 2.2 Dose Calculation for Liould Effluents '.......... u..... - 2.0 31 2.2.1 Liquid Effluent Dose Calculation Parameters...- 2.0-31 3 2.2.2 ; Methodology............................. 2.0 3 2 3.0 G AS E O U S E F F L U E NT...................................... 3.0 1-3.1-

Gaseous Effluent Monitor Setooints.....:..............

'3.0 1 i 3.1.1 Gaseous EHluent Monitor Setpoint Calculation a Pa ra me te rs................................. 3.0-1 3.1.2 Station Vent Noble Gas Monitors,.............. - 3.0 5 3.1.3 . Waste Gas Decay System Monitor............. 3.0 7 3.1.4 Alternative Methodology for Establishing - O Conservati've Setpoints................... 2.0-8 r i V-3.2 Dose Calculation for Gaseous Effluent... 3.0 12' 3.2.1 Gaseous Effluent Dose Calculation Parameters. 3.0 12-l 3.2.2 Unrettricted Area Boundary Dose :,.....-, '3.0 14 ,j 3.2.3 Unrestricted Area Dose to Individu~alL,......... 3.0-15 l 3.3 Meteoroloaical Model for Dose Calculations......... 3.0 45 F 3.3.1 Meteorological Model Parameters.,.......... 3.0 45 i ) 3.3.2 Meteorological Model................... 3.0 46 [ 4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING........... 4.0 1 a 1,' t Appendix A -Worked Examples of Monitor Setooint Calculations and h Dose Calculations A. R fd L5, R M L7 a n d R M L9............. A. B. .RM L3, RM L8, RM L10 and RM L11.. A6 4 4; C. RM A3 and RM A4 A10 D. RM A10... A14-E. Alternate Methodology for Establishing Conservative Setpoints. A15 a p 1 ODCM, V.C. Summer /SCE&G: Revision 13 (June 1990) vi i e -~ v e

... f LIST OF TABLES - Table No.~ Page No. 1.1-1 Radioactive Liquid Effluent Monitoring instrumentation 1.0 2 1.1 2 Radioactive Liquid Effluent Monitoring Instrumentation 1.0 5 Surveillance Requirements 1.1 3 Frequency Notation 1.0 7 5 1.1 4 Radioactive Liquid Waste Sampl_ing and Analysis Program 1.0 10 1.2 1 Radioactive Gaseous Effluent Monitoring Instrumentation 1.018 1.2 2 Radioactive Gaseous Effluent Monitoring. f instrumentation Surveillance Requirements '........... 1.0 21 1,2 3 Radioactive Gaseous Waste Sampling and Analysis ..j Program...... 1.0 25, 1.4 1 Radiological Environmental Monitoring Program,...... 1.0 35-1.4.2 Reporting Levels for Radioactivity Concentrations'...... 1.0-40 in Environmental Samples Reporting Levels 1.4.3 Maximum Values for the Lower Limits of Detection 1 (LLD)a.c Reporting Levels........ 1.0-41 l 2.2-1 Bioaccumulation Factors........................... 2.0 34 2.2 2 Adult ingestion Dose Factors .................,...2.035 {' 2.2 3 Site Related Ingestion Dose Commitment Factor _(A,1) 2.0 37 3.1-1 Dose Factors for Exposure to a Semi Infinite Cloud of-Noble Gases 3.0-4 L 3.2 1 Pathway Dose Factors for Section 3.2.2.2 (P,) 3.0-18 3.2-2 Pathway Dose Factors for Section 3.2.3.'2 (R,) 3.0 21 L 3.2 3 - Pathway Dose Factors for Section 3.2.3.3 (R,)(Infant)... ^ 3.0 24-l [ 3.2 4 Pathway Dose Factors for Section 3.2.3.3 (R,) (Child) -3.0-27 i 3.2 5 Pathway Dose Factors for Section 3.2.3.3 (R,)(Teenager) 3.0-30 3.2 6 Pathway Dose Factors for Section 3.2.3.3 (R,)(Adult)- 3.0-33 -i 3.2-7 Controlling Receptors, Locations, and Pathways.. 3.0 37 l 3.2 Atmospheric Dispersion Parameters for Controlling Receptor Locations.. 3.0 39 3.2.9 Parameters Used in Dose Factor Calculations 3.0-40 1 ' 4.0-1 Radiological Environmental Monitoring Program.,. _4.0 2' ODCM, V.C.' Summer /SCE&G: Revision 13 (June 1990) I 4

E q ) i / LIST OF FIGURES ' Figure l I No. Pace No. 2.1 1 Example Liquid Monitor Calibration Curve........ 2.0 30 l l 2.2-1 Liquid Radwaste Treatment System............. 2.0 39 n 3.1 1 Example Noble Gas Monitor Calibration. Curve.... 3.0 11 l 3.2 1 Gaseous RedwasteTreatment System 3.0 44' 3.3 1 Plume Depletion Effect for Ground Level R e l e a se s (6) '................'......... ',......... 3.0 49- -3.3 2 Vertical Standard Deviation of Material'in a Pl u me ( y a)..................................... 3.0 50 3.3 3 Relative Deposition for Ground Level Releases : (D,). 3.0 51 'r ~ 3.3 4 Open Terrain Recirculation Factor......,..... 3.0 52! i ( i 4.0 1 Radiological Environmental Sampling Locations (Local)...................................... -4.0 12 4.0 2 Radiological Environmental Samplin (Remote)......................g Locations -~ 4.0 ;. I e [ a 4 f* 1

O ODCM, V.C. Summer /SCE&G: Revision 13 (June 1990) i vill

REFERENCES 1. Boegli, T.5;, R.R. Bellamy, W.L Britz, and R.L. Waterfield, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants" NUREG 0133 (October 1978). 1 2. " Calculation of Annual Doses to Man from Routine' Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR 50, Appendix I", U.S. NRC Regulatory Guide 1.109 (March 1976). 1 3. " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR 50, Appendix I", U.S. NRC Regulatory Guide 1. iO9i Rev.1 (October 1977). " Final Safety Analysis Report", South Carolina Electric and Gas Company. 4. Virgil C. Summer Nuclear Station. 5. "Operatin 1 Company,g License Environmental Report", South Carolina Electric and_ Gas Virgil C. Summer Nuclear Station. ~ 6. Wahlig, B,G., " Estimation of the Radioactivity Release Rate /Ecjuilibrium Concentration Relationship for the Parr Pumped Storage System. Applied Physical Technology, Inc., February 1981. 7. " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous O Effluents in Routine Releases from Li Regulatory Guide 1.111 (March 1976)ght - Water Cooled Reactors", U.S. NRC 1 8. " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light' Water Cooled Reactors", U.S; NRC Regulatory Guide 1.111, Rev.1 (July 1977).: ~ l i 9. Slade, D.H., (editor), " Meteorology and Atomic Energy"; U.S. Atomic Energy' Commission, AECTID 24190,1968. 10. " Measuring, Evaluating, and Reporting Radioactiv' ity in Solid Wastes and Releases of Radioactive Materials in-Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear. Power Plants", U.S. NRC Regulatory. Guide 1.21, Rev.1 (June 1974). 1 11. " Standard Radiolo ical Effluent Technical Specifications for Pressurized Water. Reactors", NUREG-472, Revision 3 (January 1983) 12. " Quality Assurance;for Radiological Monitoring Programs (Normal ] Operations) Effluent Streams and the.. Environment", USNRC Regulatory Guide 4.15, Revision 1 (February 1979) ODCM, V.C. Summer /SCE&G: Revision 13 (June 1990) ix i

.t-l- INTRODUCTION j The OFFSITE DOSE CALCULATION MANUAL (ODCM)is an implementing and j supporting document of the RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS (RETS), in accordance with USNRC Generic Letter 89-01, entitled " Implementation of ] Programmatic Controls for Radiological Effluent Technical Specifications in the Administrative Controls Section of the Technical Specifications and the Relocation of Procedural Details of Rets to the Offsite Dose Calculation Manual or to the Process ' Control Program", the procedural details for implementing the Radiological Limiting Conditions for Operation have been incorporated into the ODCM.. The ODCM describes the methodology.and parameters to be used in the calculation-of-offsite doses due to radioactive liquid and gaseous effluents and in the calculation of i liquid and gaseous effluent monitoring instrumentation alarm / trip setpoints. The ODCM contains a list and graphical description of the specific sample locations for the radiological environmental monitoring program. Configurations of the liquid - 1 i and gaseous radwaste treatment systems are also included. The existing RETS residing in the Technical Specifications will be the governing document for the Radiological Limiting Conditions for Operation until a Technical Specification change has been issued. Relocation of the RETS to the ODCM will not ? become official until that Technica: Specification change is issued. The ODCM will be rnaintained at the Station as the reference which details the Radiological Limiting Conditions for Operation of the V.'C, Summer Nuclear Station. Additionally the ODCM will be maintained as the guide for. accepted calculational-1 - methodologies. -Changes in the calculational methods or parameters will be incorporated into the ODCM in order to assure.that the ODCM represents the present methodology in all applicable areas. Computer software to perform the - described calculations will be maintained current with this ODCM. i 1 O ODCM, V.C. Summer /SCE&G: Revision 13 (June 1990)

'l I 1.0 SPECIFICATION OF LIMITING CONDITIONS FOR OPER ATION 1.1 LIOUID EFFLUENTS 1.1.1 Radioactive Liouid Effluent Monitorino Instrumentation LIMITING CONDITION FOR OPERATION 1.1.1.1 The radioactive liquid effluent monitoring instrumentation'chan-i nels shown in Table 1.1 1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of ODCM Specification 1.1.2,1 are'not exceeded. The-alarm / trip setpoints of these channels shall be determined in accorddnce with - ODCM, Section 2.1. l APPLICABLE: At all Times. ACTION: With a radioactive liquid effluent monitoring instrumentation a. channel alarm / trip setpoint less conservative than required by the above specification,immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the - channelinoperable. b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 1.1 1. Additionally if this condition prevails for more than 30 days, in the next semiannual effluent report explain why this condition was not corrected in a timely manner. The provisions of Technical Specifications 3.0.3.and 3.0.4 are not c. applicable. SURVEILLANCE REQUIREMENTS 1.1.1.2 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CAllBRATION and ANALOG CHANNEL-O OPERATIONAL TEST operations at the frequencies shown in Table 1.1-2. ODCM, V.C. Summer, SCE8G: Revision 13 (June 1990)- ( 1.0-1 ~

l J. ,u TAB LE' 1.1-1 ' RAGHOACTIVE LlOUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM. p CHANNELS' F INSTRUMENT - OPER ABLE ' ACTION 1. GROSS RADIOACTIVITY MONITs RS PROVID- -1 ING ALARM AND AUTOMATICT6 RMINA-TION OF RELEASE ~ a. . Liquid Radwaste Effluent Line - RN L5 1-1 l l or RM L9 ' f b. - Nuclear (Processed Stoain Generato r) - 1 .1 E Blowdown Effiuent 1:ne KM L7 or RM-o L9. .c. Steam Generstor Plowdcwn 5ffluent Line1 4 '1. Unprot.e'. sed during Power 1 2 Operati'an AM L10 or RM L3 2. Unprewsse i de ring Startup - RM-1 2 i L3= d, Turbine Stiilding : ump Effluent Line -- RM L8 1 3 e. Condensate Der.iineralizer Backwash Effluent Une P.M L11 1 6 ~, 2. FLOW RATE MEASUREMENT DEVICES

a.

Liquid Radwaste Effluent Line Tanks l' ,1/ tank 4 and 2 ~b, Penstock Minimum Flow Interlock *

1-4; c.

Nuclear Blowdown Effluent Line 1. 4-j' . d. Steam Generator (Unprocessed) ?1 4 j Blowdown Effluent Line - 3. TANK LEVEL INDICATING DEVICES - a. Condensate Storage Tank 1' S -In the event that simultaneous releases from both WMT.and NBMT 'are required (which normally will be prevented by procedure) the flow rate for monitor RM L9 will be determined by adding flow rates for monitors RM LS and RM L7. Minimum dilution flow is assured by an interlock that terminates liquid ' waste. a releases if the minimum dilution flow is not available. i 1 .s ODCM, V.C. Summer, SCE8G: Revision 13 (June 1990). 1.0 2 ~ _,

+ TABLE 1.1 1 (Continued) V 1 TABLE NOTATION l ACTION 1 With the number of channels OPERABLE less than required by the' 1 Minimum Channels OPERABLE requirement,' effluent. releases may - continue for up to 14 days provided that prior to initiating a release:

At lease two--independent samples 'are analyzed irt a.

accordance with ODCM Specification 1.1.2.4 and i b. At lease two technically qualified members of the Facility-Staff independently verify the release 1 rate calculations 1 ~ and clischarge line valving: i Otherwise, suspend release of radioactive effluents via'this path- ~1 way. 1 ACTION 2 With the number of channels OPERABLE less than required by the? Minimum Channels-OPERABLE requirement,. effluent release ~s vial this pathway may continue for up to 30 days ' rovided grab samples, p are analyzed for gross radioactivity (beta and gamma) at a limit'of j detection of at least 1E-7 microcuries/ gram:- I At least once per 8 hours when the' specific activity of the - a. secondary coolant is greater th'an;0.01' microcuries/ gram. ' i DOSE EQUIVALENT I 131'. b. At least once per 24 hours ~when th'e specific activity of the secondary coolant'.is less.than or.' equal; to' 0.01 microcuries/ gram DOSE EQUIVALENT l 131. O ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) 1.0 3 9

1 ,.t i -TABLE 1.1-1 (Continued) l . TABLE NOTATION - {

ACTION 3

'With' the number of channels OPERABLE less than required by the. I Minimum Channels OPERABLE requiremen.t effluent releases.via < this pathway may continue for up to 30 days provided that, at least1 y once per 8 hours, grab samples are collected and analyzed for gross-radioactivity.(beta and gamma) at a limit of detection of at least - 1E-7 microcuries/ gram: 1 8 ACTION 4 With the number of channels OPERABLE less than required by the; J . Minimum Channels OPERABLE: requirement, effluent releases via [ ' this pathway'may continue for up to 30 days provided the flow rate L is estimated at least once per 4 hours during; actual releases. ' Pump curves may be'used to estimate flow.: es . ACTION S With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement,Lliquid additions to this tank may continue for'up to 30 days provided the_ tank Ii_ quid level'is [ estimated during all liquid additions' to the tank to' prevent-lJ

overflow, i

ACTION 6 With the number of channels OPERABLE less than required by the . Minimum Channels OPERABLE req'uirement,i effluent releases may : i continue for up to 30 day's provided that samples are analyzed in' accordance with ODCM Specification 1.1.2.2 and Technical Specifi. 1 cation 4.11.1.5. I l ( .{ t i ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) 1.0 4 j y .2. .....,,,. _ ~.....

l- . TABLE 1.12 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION. - - ~ SURVEILLANCE REQUIREMENTS ANALOG CHANNEL CHANNEL - OPERA-CHANNEL. SOURCE CAllBRA-TIONAL INSTRUMENT CHECK CHECK . TION TEST 1. GROSS RADIOACTIVITY MONI-TORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE a. Liquid Radwaste Effluent D: P R(2) . Q(1) a Line RM LS or RM L9 - b. Nuclear Blowdown. D P R(2)- Q(1) Effluent Line RM L7 1 c. Steam Generator D M R(2) Q(1)) Blowdown Effluent Line -- RM L3, RM L10 d. Turbine Building Sump.' D M' R(2) Q(1) Effluent Line RM L8 e. Condensate Demineralizer D M 'R(2) Q(4). Backwash Effluent Line RM L11 1 2. FLOW RATE MEASUREMENT : l DEVICES. a. Liquid Radwaste Effluent 'D(3) N.A. R .O q. Line b. Penstocks Minimum Flow D(3). N.A. R Ql Interlock c. Nuclear Blowdown D(3)- N;A.~ l R. 'Q ^ Effluent Line i d. Steam Generator -D(3) N.A. . R' Q i Blowdown Effluent Line 3. TANK LEVEL INDICATING DEVICES' a. - Condensate Storage Tank-D. N. A.' R .Q See Table 1.13 for explanation of frequency notation. I 4 O ODCM, V.C. Summer, SCE&G: Revision '13 (June 1990)' I. 1,0 5 l 1

= -i TABLE 1.12 (Continued) TABLE NOTATION < j (1) The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that' automatic isolation of this pathway and control room alarm annunciation . occurs if any_of the following conditions exists: 1. Instrument indicates measured levels above the alarm / trip setpoint. 2. ' Loss of Power (alarm only); 3. Low flow (alarm only). 4. Instrument indicates a downscale failure (alarm only). 5. Normal / Bypass switch set in Bypass (alarm only). 6. Other instrument controls not set in operate mode. l (2) The initial CHANNEL CAllBRATION sh'all be performed using one or more of. the reference standards certified by the-National Institute of Standards and. t Technology (NIST) or using standards that have been obtained from suppliers; .that participate in measurement assurance' activities with NIST. These standards shall permit calibrating the' system over its intended range of g energy and ineasurement range.- For subsequent CHANNEL CAllBRATION sources that have been related to the initial calibration shall be used. = (3) CHANNEL CHECK shall consist of verifying indication of flow during periods of. L . release. CHANNEL CHECK shall be made at le'ast once per 24 hours on days on ~ which continuous, periodic, or batch releases are made. (4) The ANALOG CHANNEL' OPERATIONAL TEST shall a' Iso demonstrate that automatic isolation of this pathway and local panel alarm annunciation occurs a . if any of the following conditions exists: } 1. Instrument indicates measured levels above the alarm / trip setpoint. J 2. Loss of Power (alarm only). 3. Low flow (alarm only). 4. Instrument indicates a downscale failure (alarm only). 5. ' Normal / Bypass switch set in Bypass (alarm only). 6. ~Other instrument controls not set in operate mode. O ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) 1.0 6 (

^ 1 TAB LE 1.1 3 FREQUENCY NOTATION. NOTATION FREQUENCY. D-At least once per 24 hours.- W.- At least once per 7 days. M At least once per 31 days. Q At least once per 92 days. [ SA At least once per 184 days. l R At least once per 18 months. P Completed prior to each release. N.A. Not applicable, O l .I O ODCM, V.C. Summer, SCE&G: Revision 13'(June 1990)' 7_ i

.v j 1.1.2 Liauid Effluents: Concentration LIMITING CONQlIlON COR OPER ATION 1.1.2.1 The concentration of radioactive material released from the site (see Technical Specification Figure 5.1-4) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table 11, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2E 4 microcuries/ml total activity. APPLICABLE: At all Times. ACTION: With the concentration of radioactive material released from the site exceeding the above limits, immediately restore the concentration to within the above limits. g SURVEILLANCE REQUIREMENTS 1.1.2.2 The radioactivity content of each batch of radioactive liquid waste shall be determined prior to release by sampling and analysis in accordance with Table 1.1-4. The results or pre-release analyses shall be used with the calculat;onal methods in ODCM Section 2.1 to assure that the concentration at the point of release is maintained within the limits of ODCM Specification i 1.1.2.1. 1.1.2.3 Post-release analyses of samples composited from batch releases shall be pertormed in accordance with Table 1.1-4. The sesults of the previo'us ' post-release t.nalyses shall be used with the calculational methods in ODCM Section 2.1 to assure that the concentrations at the point of release were maintained within the limits of ODCM Specification 1.1.2.1. 1.1.2.4 The radioactivity concentration of liquids discharged from continu-ous release points shall be determined by collection and analysis of samples in ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) 1.0 8 I'

J. accordance with Table 1.1-4. The results of the analyses shall be used with the ] . calculational methods in ODCM Section 2.1 to assure that the concentrations at the point of release are maintained within the limits of ODCM Specification 1.1.2.1. 1 1.1.2.5 At least one Circulating Water Pump or the Circulating Water Jockey Pump shall be determined to be'in' operation and providing dilution to the ~ discharge structure at least once per 4 hours whenever dilution is required to meet the site radioactive effluent concentration limits of ODCM Specification 1.1.2.1. 1 l l i i I-t 4~ -i i ODCM, V.C. Summer. SCE&G: Revision 13 (June 1990) I 1'0 9 3 .._.,.i

~.... - - -. _.. i 'l TABLE 1.1-4 ' RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Lower uma Minimum of Detectioni -1 Liquid Release Sampling Analysis - Type of Activity (LLD) Type Frequency Frequency Analysis (pCl/mL)* L A. Batch Waste P-P ~ SX10 7 Released Each Batch Each Batch Principal Gamma Tanks Emitters' - 1. Waste I-131 1X10 6 Monitor l Tanks P M Dissolved and i One Batch /M Entrained Gases - 1X10 5 2. Condensate (Gamma emitters) t Demineralizer Backwash .P M H3 1X10-5 6 Receiving Each Bctch Composite Tank 3. Nuclear Gross Alpha 1X10 7 Blowdown Monitor P Q-Sr 89, Sr 90 5X10-8 ... j 6 Tank Each Batch Composite - ~ f Fe 55 1X10 6 B. Continuous D W Principal Gamma 5X10 7 Release' Grab 5' mpleComposite( Emitters' 1. Steam l131 1 X10-6 i Generator Blowdown M M. Dissolved and l Grab Sample Entrained Gases ~ 1X10 5. (Gamma emitters) L 2. Turbine i Building D M H3 1X10 5 3 Sump Grab SampleComposite' 3. Service . Gross Alpha 1X10 7 + Water ' Effluent D Q-Sr-89, Sr 90 5X108 Tank Grab Sample Composite ( Fe 55 1 X10-6

l' l

See Table 1.13 for explanation of frequency notation. 4 ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) l j-l 1.0 10 4 ,. _ _ ~ _.. ..-,...,,J_,._,,._

TABLE 1.1-4 (Continued) TABLE NOTATION a'. The Lower Limit of Detection (LLD)is the smallest concentration of radioactive material in a sample that will yield a net count above background that will be1 detected with a 95% probability. LLD also yields a 5% probability of falsely - concluding that a blank observation represents a "real". signal ' For a particular measurement system (which may; include radiochemical: - separation): 4.66s ] b LLLC = (E)(V)(2.22)(Y)(exp)( Aat) Where: LLD is the "a priori" lower limit of detection as defined above (as pCi-per unit mass or volume). Current literature defines the LLD as the - ~ detection capability for the instrumentation only and the MDC, the i minimum detectable concentration, as the detection capability for a given instrument procedure and type of sample. 4 4.66 is a factor which corrects for the smallest activity that~ has a, probability, p, of being detected, and a probabilhy,1 p, of falselyz concluding its presence. i 4.66 = 24 V 1 + u #'. IL 6 k = a constant whose value depends on theichosen confidence level (NRC recommends a confidence level of 95%) =.1.6545 at 95% confidence level' i tb = background time: ts = sample time - s is the standard deviation of the background counting rate or the j b counting rate of blank sample as appropriate (as counts per minute).- E is the counting efficiency (as counts per transformation), - O ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990)' -1.0 11

-.5 TABLE 1.14 (Continued) TABLE NOTATION' V is the sample size (in units of mass or volume), ( r 2.22 is the number of transformations per minute per picocurie,. Y is the fractional radiochemical yield (when applicable), i: kis the radioactive decay constant for the particular radionuclide,- and a t is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental samples). The value of s used in.th'e calculation of the.LLD for a detection b system shall be used on the actual observed variance of the back-l: l ground counting rate or of the counting rate of the blank samples: j' (as appropriate) rather.than on an unverified theoretically predicted l variance.. in calculating the LLD for a radionuclide determined by ~ gamma ray spectrometry the background should include th'e. typical contributions of other radionuclides normally present in the i samples. Typical values of E, V, Y, and a t shall-be used in the: 7: . calculation. ~ ! l It should be recognized that the Ll0 is defined as an a priori (before the fact)- 4 l limit representing the capability'of a -measurement. system;andlnot' as a. L,. posteriori (after the fact) hmit for particular measurement.* L

For a more complete discussion of the LLD, and 'other detection limits, see' the -

following: L - (1) HASL Procedures Manual, HASL-300 (revised annually) i (2)

Currie, L.' A.,'" Limits for Qualitative Detection and; Quantitative Deter-mination - Application to Radiochemistry" Anal. Chem' 40,586 93(1968).

4 n, (3) Hartwell,1 K., " Detection Limits for Radioisotopic Counting Techni 'l Atlantic Richfield Handford Company Report ARH 2537 (June 22,1972) ques, 4-1 ODCM, V.C. Summer, SCE &G: Revision 13 (June 1990) l' 1.0 12 -U, -x- ..v. ,_______~.,)

lp. 4 TABLE 1.1-4 (Continued) TABLE NOTATION b. A ' composite sample is one in which the quantity of !iquid sampled is? proportional to 'the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released, c. To be representative of the quantities and concentrations of radioactive materials in liquid effluents, samples shall be composited in proportion to the

I rate of flow of the effluent stream. Prior to analyses, all samples taken for the -

~ composite shall be thoroughly mixed in order for the composite sample to be [ representative of the effluent release. d. A batch release is the discharge of liquid wastes of a discrete volume. Prior to-sampling for analyses, each batch shall be isolated, and then thoroughly mixed, by a method described in ODCM Section 2.0, to assure representative 1 sampling. A continuous release is the discharge of liquid wastes of a nondiscrete e. volume; e.g., from a volume of system that has an input flow during the continuous release.- t f. The principal gamma. emitters for which the LLD specification applies-exclusively are the following radionuclides: Mn 54; Fe 59, Co 58; Co 60,:Zn-65, Mo 99, Cs 134, Cs 137, Ce 141, and Ce-144. This list does~not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. 1 O ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) 1.0 13

.I p a i 1.1.3 Liould Effluents: Dose . O.I LIMITING COtvDmON FOR OPER ATION l 1.1.3.1 The dose or dose commitment' to an individual from radioactive materials in liquid effluents released from the site (see Technical Specification - l Figure 5.1-4) shall be limited: .a. During any calendar quarter to less than or equal to 1.5 mrem to the 1i total body and to less than or equal to 5 mrem to any organ, and i. l l b. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ. APPLICABLE: At all Times. ACTION: a. With the calculated dose from the release of radioactive materials in l liquid effluents exceeding any of the above limie, in lieu of any other report required by ODCM Section 1.6, prepare and submit to l the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report which identifies the cause (s) for exceeding the limit (s) and defines the corrective actions to be taken to the releases and the proposed actions' to be taken to assure that subsequent releases will be in compliance with ODCM Specification. 1.1.3.1. } l b. The provisions of Technical Specifications 3.0.3 and 3.0.4 are not applicable. i-l- SURVEILLANCE REOUIREMENTS

l 1.1.3.2 Dose Calculations. Cumulative dose contributions from liquid effluents shall be determined in accordance with ODCM Section 2.2 i

at least once per 31 days. j ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) 43 1.0-14 F

t .4 I 1.1.4 Liouid Waste Treatment LIMITING CONOmON FOR OPER ATION - 1.1.4.1 The liquid radwaste treatment system shall be' OPERABLE. The appropriate portions of the system shall be used to reduce the radioactive-materials in liquid wastes prior to their dist.harge when the projected doses j due to the liquid effluent from the site (See Technical Specification Figure 5.1-

4) when averaged over 31 days, would exceed 0.06 mrem to the total body or O.2 mrem to any organ.

APPLICABLE: At all Times. ACTION: I With the liquid radwaste treatment system inoperable for more a. than 31 days or with radioactive liquid waste being discharged O. without treatrnent and in excess of the above limits, in lieu of any other report required by ODCM Section 1.6, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report which includes the following information: i 1. Identification of the inoperable equipment or subsystems and the reason for inoperability, 2. Action (s) taken to restore the inoperable, equipment to 3 OPERABLE status, and 3. Summary description of action (s) taken to prevent a recurrence, b. The provisions of Technical Specifications 3.0.3 and 3.0.4 are not - applicable. ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) 1.0 15

.i 0; SURVElLLANCE REQUIREMENTS - I 1.1 4.2 Doses due to liquid releases shall be projected at least once per 31 [ days, in accordance with ODCM Section 2.2.

\\

1 -1,1 4.3-The-liquid radwaste treatment system shall' be demonstrated ' i t. OPERABLE by operating the liquid radwaste treatment system equipment for at least 30 minutes at least once per 92 days unless.the liquid radwaste syster*. ' has been utilized to process radioactive liquid effluents during the previcus 92 ~ d ays.- .i ~ _} i k e' i - i s a 1 i-it 1 4-t i ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) - i j 1.0 16

i 1.2 GASEOUS EFFLUENTS - 1 1.2.1 _ Radioactive Gaseous Effluent Monitorina Instrurnentation LIMITING CONDITION FOR OPER ATION 1.2.1.1 -The radioactive gaseous' effluent monitoring instrumentation channels shown in. Table 1.231 shall be OPERABLE 'with their alarmttr>p -setpoints set to ensu' e that the limits of ODCM Specification 1.2.2.1'are nct I r exceeded. The ai3rm/ trip setpoints of these channels shall be determined in accordance with ODCM Section 3.1. APPLICABLE: As shov.n in Table 1.2 1 1 ACTION: With a radioactive gaseous _ effluent monitoring instrumentation-a. channel alarm / trip setpoint less conservative than required by the: above ODCM. Specification, immediately. suspend the r' lease' of e radioactive gaseous effluents monitored by the affected channel or-declare the channel inoperable, With less than the minimur., nuniber of radioactive gaseous effluent b. monitoring instrumentation channels OPERABLE, take,the ACTION q shown in Table 1.21.: Additionally if this condition prevails for more-1 than 30 days, in the next semiannual effluent report, explain why this condition was not corrected in a timely manner. t b. The provisions of Technical Specifications 3.0.3 and'3.0.4 are not - applicable.- [ SURVEILLANCE REOUIREMENTS I 1.2.1.2

Each radioactive gaseous-effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL

- ? CHECK, SOURCE CHECK, CHANNEL CALIBRATION and and ANALOG CHANNEL. OPERATIONAL TEST operations at the frequencies shown in Table 1.2-2. O l ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) 1.0 17 ,i

~. - -.... - ..H 'l . TABLE 1.21 RADIOACTIVE GASEOUS EFFLUENT ; --- - J MONITORING INSTRUMENTATION . MINIMUM' CHANNELSL 'APPLKA-INSTRUMENT OPERABLE BILITY, ACTION : l 1-WASTE GAS HOLDUP SYSTEM J i l~ a.- Noble Gas Activity Monitor-1 7 . Providing Alarm and Automatic 4 - Termination of Release (RM A10 - or RM A3) l 2. WASTE GAS HOLDUP SYSTEM EXPLO- ~ SIVE GAS MONITORING SYSTEM a. Oxygen Monitor

2:

13 . b. Hydrogen Monitor 1-11 3. MAIN PLANT VENT EXHAUST SYSTEM a. Noble Gas Activity Monitor-. 1 9 l Providing Alarm and Automatic Termination of Re'1ase from l Waste Gas Holdug :ystem(RM - A3) 1 12. b. ' lodine Sampler

1 -

12 j c. Particulate Sample '1 -8s 1 L__ d. - Flow Rate Measuring Device ' 1 8-e. Sampler Flow Rate Measuring Device' i i g 4. REACTOR BUILDING PURGE SYSTEM l a. ' Noble Gas Activity Monitor 1 10 Providing Alarm and Automatic Termination of Release (RM-A4)

b.

= lodine Sampler 1 12 c. Particulate Sample 1-12 d. Flow Rate Measuring Device 1 8-e. Sampler Flow Rate Measuring 1 8 Device. t ' ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) 'j I 1.0 18 .,..h

e* i 4 4 I TAgg 1.21 (Continued) TABLE NOTATION i At all times during releases via thi$ pathway. I t During waste gas holdup system operation (treatment for primary system off. cases). ACTION 7 - With the number of channels OPERABLE less than required by the Minimum Channels O*ERABLE requirement, the contents of the i tank (s) may be reieased to the environment for up to '14 days l provided that prior to initiating the release: i \\ a. At least two independent samples of the tank's contents-i are analyzed, and 1 l b. At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge valve lineup; i Otherwise, suspend release of radioactive effluents via this pathway. ACTION 8 - With the number 'f channels OPERABLE less than required by the Minimum Channels. OPERABLE requirement, efiluent releases via. this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours. ACTION 9 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples i are taken at least once per 8 hours and these samples are analyzed f for gross activity w thin 24 hours, ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) ~ 1.0 19 /

i 'l .s l TABLE 1.21 (Continued) ' TABLE NOTATION l i ACTION 10 With the number of channels OPERABLE less than required by the l l. Mini _ mum Channels OPERABLE requirement, immediately suspend j PURGING of radioactive effluents via this pathway. 1 l ACTION 11 - 'With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, suspend oxygen supply to the recombiner. l 4 ACTION 12 - With the number of channels OPERABLE less than. required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue for up to 30 days provided samples are continuously collected with auxiliary sampling equip-ment as required in Table 1.2 3. e ACTION 13-With the number of channels OPERABLE one less than required by ~ the Minimum Channels OPERABLE requirement, operation of this system may continue for up to 14 days provided one hydrogen analyzer upstream and.one hydrogen analyzer downstream are ] OPERABLE or grab samples are taken and analyzed at least once per 4 hours at the location of the inoperable hydrogen analyzer. With both the channels inoperable, be in at least HOT STANDBY within 6 hours. i + k O q ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) i 1.0 20 ] s 3 - ~,

l,. s l 1. TABLE 1.2 2 l RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREM ENTS 3 -~ MODESIN ANALOG CHANtJEL WHICH C NNEL CHANNEL SOURCE CAllBRA-SURVEILL i INSTRUMENT CHECK CHECK TlON ANCE RE. f TIONAL TEST QUIRED 1. WASTE GAS HOLDUP SYSTEM - ) i a. Noble Gas Activity P P R(3) O(1) ,~, Monitor RM A10 i or RM A3 i e 2. WASTE GA5 HOLDUP M N TOR N 5 STEM i a. Hydrogen Monitor D N.A O(4) M t f b. Oxygen Monitor D N.A Q(5) M 3. MAIN PLANT VENT EXHAUST SYSTEM a. Noble Gas Activity D M R(3) Q(2) Monitor RM A3 b. lodine Sampler W N.A. N.A N.A, c. Particulate Sampler W N.A. N.A. N.A. Flow Rate D N.A. R Q i Measuring Device e. Sampler Flow Rate D N.A. R Q Monitor 4. REACTOR BUILDING PURGE SYSTEM a. Noble Gas Activity D P,M R(3) Q(1) Monitor RM.A4 i i b. lodine Sampler W N.A. N.A N.A. c, Particulate Sampler W N.A. N.A. N.A. i 1 1 d. Flow Rate Measur. D N.A. R Q ing Device i e. Sampler Flow Rate D N.A. R Q I Monitor 3 See Table 1.13 for explanation of frequency notation. I v n ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) l 1.0 21

.w TABLE 1.2 2 (Continued) TABLE NOTATION At all times. During waste gas holdup system operation (treatment for primary system off j gases). (1) The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that i automatic isolation of this pathway and control room alarm annunciation' occurs if any of the following conditions exists: 1. Instrument ind' tes measured levels above the alarm / trip setpoint. 2. Loss of Powe . arm only). 3. Low flow (alarm only). 3 4. Instrument indicates a downscale f ailure (alarm only). i 5. Normal / Bypass switch set in Bypass (alarm only). j 6. Other instrument controls not set in operate mode. f (2) The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions g exists: 1. Instrument indicates measured levels above the alarm setpoint. 2. Loss of Power. 3. Low flow. 4. Instrument indicates a downscale failure. 5. Instrument controls not set in operate mode. (3) The initial CHANNEL CAllBRATION shall be performed using one or more of the reference standards certified by the National Institute of Standards and Techno!ogy (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of l energy and measurement range. For subsequent CHANNEL CAllBRATION, sources that have been related to the initial calibration shall be used. O ODCM, V.C. Summer, SCE&Gi Revision 13 (June 1990) 1.0 22

l,. TABLE 1.2 2 (Continued) TABLE NOTATION I t l (4) The CHANNEL CALIBRATION shall include the use of standard gas samples i containing a nominal: 1. 1500130 ppm hydrogen, balance nitrogen, for the outlet hydrogen monitor and I 2. 410.1 volume percent hydrogen, balance nitrogen, for the inlet hydrogen monitor. I J (5) The CHANNEL CAllBRATION shall include the use of standard gas samples containing a nominal: 1. 7511.5 ppm oxygeri, balance nitrogen, for the outlet oxygen 'f monitor and .l 2. 3.510.1 volume percent oxygen, balance nitrogen, for,the inlet oxygen monitor. I ~ O i ) 1 l O ODCM, V.C. Summer, SCE &G: Revision 13 (June 1990) i 1.0 23 i . _,.,.. ~,. . :..i.. L.,..

i 1.2.2 Easeous Effluents: Dose Rate LIMITING CONDITION FOR OPER ATION 1.2.2.1-the dose rate in unrestricted areas due to radioa'ctive materials j released in gaseous effluents from the site (see Technical Specification Figure 5.1 3) shall be limited to the following: a. For noble gases: Less than or equal to 500 mrem /yr to the total body j and less than or equal to 3000 mremlyr to the skin, and b. For all radioiodines and for all radioactive materials in particulate ) form and tritium with half lives greater than 8 days: Less than or l equal to 1500 mrem /yr to any organ. APPLICABLE: At all Times. ACTION: r i With the dose rate (s) exceeding the above limits, immediately decrease the release rate to within the above limit (s). l SLl".VEILLANCE REQUIREMENTS l 1.2.2.2 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methods and procedures of the ODCM. 1.2.2.3 The dose rate due to radioiodines, tritium and radioactive materials in part culate form with half lives greater than 8 days in gaseous effluents i shall be determined to be within the above limits in accordance with the methodt and procedures of ODCM Section 3.2.2 by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 1.2 3. O I ODCM, V.C. Summer, SCE 8G: Revision 13 (June 1990) i 1.0 24 I

/ g..- i TABLE 1.2 3 ( AADIOACTIVE GASEOUSWASTE SAMPL!NG AND ANALYSIS PROGRAM i Minimum Lower Limit Sampling Analysis Type of Activity of Detection Gaseous Release Type Frequency Frequency Analysis (LLD)(pCi/ml)* A. Waste Gas Stor-P P

}

age Tank Each Tank Each Tank Principal Gamma 1 X10-4 Grab Sample Emitterse i B1 Reactor Building P P Principal Gamma 36" Purge Line Each Purge *' Each Purge6 Emitterse ' 1X10 4 6" Purge Line H3 1X10 6 82 Reactor Building M' M' Principal Gamma i 6" Purge Line Grab Sample Emitterse 1X10 4 (if continuous) H3 1X10 6 r C. Main Plant Vent M*" M' Principal Gamma i Grab Sample Emitterse 1X10 4 H3 1X10 6 i D 1. Reactor Building Continuous . W' l131 1X1012 Purge Sampler' Charcoal 1133 1X1010 Sample 2. Main Plant Vent Continuous W' Principal Gamma 1X1011 i Samplerf Particulate Emitterse Sample 1 131, others Continuous M Sampler' Composite Gross Alpha 1X1011 Particulate Samole Continuous Q Sampler' Composite Sr 89,Sr 90 1X1011 ( Particulate i Sam ple Continuous Nob e Gas Noble Gases 2X10 6 Monitor Monitor Gross Beta i See Table 1.13 for explanation of frequency notation. O ODCM, V.C. Summer, SCE &G: Revision 13 (June 1990) J 1.0 25 t

1 I-TABLE 1.2 3(Continued) TABLE NOTATION a. See Table 1.14 notation (a) for definition of LLD. i t b. Analyses shall be also be performed within 24 hours following shutdeswn, l, startup, or a THERMAL POWER change exceeding 15 percent of the RATED. THERMAL POWER within a one hour period. l i l c. Tritium grab samples shall be taken at least once per 24 hours when the j refueling canalis flooded. [ s d Samples shall be changed at least once per 7 days and analyses shall be -l completed within 48 hours after changing (or after remova! from sampler). I Sampling shall also be performed at least once per 24 hours fo a least ? days following each shutdown, startup or THERMAL POWER change exceeding 15 l percent of RATED TH:RMAL POWER in one hour and analyses shall be completed within 48 hours of changing. When samples collected for 24 hours g; are analyzed, the corresponding LLD's may be increased by a factor of 10. e. Tritium grab samples shall be taken at least once per 7 days from the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in i the spent fuel pool. f. The ratio of the sample flow rate to the sampled stream flow rate shall be 1 known for the time period covered by each dose or dose rate calculation made in accordance with ODCM Specifications 1.2.2.1,1.2.3.1 and 1.2.4.1. g. The principal gamma emitters for which the LLD specification app: A exclusively are the following radionuclides: Kr 87, Kr 88, Xe 133, Xe 13!-, Xe 135, and Xe 138 for gaseous emissions and Mn 54, Fe 59, Co 58, Co 60,2n-65, Mo 99, Cs 134, Cs 137, Ce 141 and Ce 144 for particulate emissions. This list doe < not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above l nuclides, shall also be identified and reported. l ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990). 1.0 26 .-.-...,,_,...,,...,..r _,, -.,. _.,, _,. ~,,, _ -

).. l I f 1.2.3 Gaseous Effluents: Dose Noble Gas l LIMITING COblDlIlON FOR OPERATION l 1.2.3.1 The air dose due to noble gases released in caseous effluents from the site (see Technical Specification Figure 5.1-3) shall be limited to the following: a. During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and, b. During any calendar year: Less than or equal to 10 mrad for gamma t radiation and less than or equal to 20 mrad for beta radiation. l APPLICABLE: At all Times. ACTION: With the calculated air dose from radioactive noble gases in gaseous I a. O effluents exceeding any of the above limits, in lieu of any other report required by ODCM section 1.6, prepare and submit to the Commission within 30 days, pursuant to Technical Specification - I 6.9.2, a Special Report which identifies the cause(s) for exceeding ) the limit (s) and defines the corrective actions to be taken to releases i and the proposed corrective actions to be taken to assure that [ subsequent releases will be in compliance with ODCM Specification i 1.2.3.1. l b. The provisions of Technical Specifications 3.0.3 and 3.0.4 are not applicable. SURVElLLANCE REOUIREMENTS j 1.2.3.2 Dose Calculations Cumulative dose contributions for the current l calendar quarter and current calendar year shall be determined in accordance F l with ODCM Section 3.2.3 at least once per 31 days. .'[ ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) 1.0 27 I i u ._r

l 1.2.4 Gaseous Effluents: Dose - Radiciodines, Tritium, and Radioactive Materials in Particulate Form. 4 LIMITING CONDITION FOR QPER ATION 1.2.4.1 The dose to an individual from radioiodines, tritium, and radioactive materials in particulate form, and radionuclides (other than noble gases) with half lives greater than 8 days in gaseous effluents (see Technical Specification Figure 5.13) shall be limited to the following. t a. During any calendar quarter: Less than or equal to 7.5 mrem to any organ and, b. During any calendar year: Less than or equal to 15 mrem to any organ. l APPLICABLE: At allTimes, i ACTION: i With the calculated dose from the release of tritium, radioiodines, a. and radioactive materials in particulate form with half lives greater than 8 days in gaseous effluents exceeding any of the above limits, in lieu of any other report required by ODCM Section 1.6, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions to be taken to releases and the proposed actions to be taken to assure that subsequent release will be in compliance.with ODCM Specification i 1.2.4.1. b. The provisions of Technical Specifications 3.0.3 and 3.0.4 are not applicable. SURVElLLANCE REOUIREMENTS l 1.2.4.2 Dose Calculations Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in accordance with ODCM Section 3.2.3 at least once per 31 days. ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) l' 1.0 28 i

i 1 1.2.5 Gaseous Effluents: Gaseous Redwaste Treatment i LIMITING CONDITION FOR OPER ATION 1 (, t 1.2.5.1 The GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be OPERABLE. The appropriate portions of the GASEOUS RADWASTE TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releases from the site (See Technical Specification Figure 5.13), when-i averaged over 31 days, would exceed 0.2 mrad for gamma radiation and OA mrad for beta radiation. The appropriate portions of the VENTILATION j EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases from the site when averaged over 31 days would exceed 0.3 mrem to any organ.- APPLICABLE: At all Times. ACTION: a. With the GASEOUS RADWASTE TREATMENT SYSTEM and/or the VENTILATION EXHAUST TREATMENT SYSTEM inoperable for more .than 31 days or with gaseous waste being discharged without treatment and in excess of the above limits, in lieu of any other-report required by ODCM section 1.6, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report which includes the following information: l 1. Identification of the inoperable equipment or subsystems and the reason for inoperability, 2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and 1 1 3. Summary description of action (s) taken to prevent a recurrence. O l ODCM, V.C. Summer, SCESG: Revision 13 (June 1990) ll 1.0 29

.o i ~ i ) b. The provisions of Technical Specifications 3.0.3 and 3.0.4'are not W l applicable. I i SURVEllLANCE REOUIREMENTS I 1.2.5.2 Doses due to gaseous releases from the reactor shall be projected at least once per 31 days, in accordance with ODCM Section 3.2.2 for air doses and ODCM Section 3.2.3 for organ doses. l t 1.2.5.3 The GASEOUS RADWASTE TREATMENT SYSTEM and VENTILATION EXHAUST TREATMENT SYSTEM shall be demonstrated OPERABLE by opera-i ting the GASEOUS RADWASTE TREATMENT SYSTEM equipment and i l VENTILATION EXHAUST TREATMENT SYSTEM ' equipment for at least 30 minutes, at least once per 92 days unless the appropriate system has been utilized to process radioactive gaseous effluents during the previous 92 days. l l O i 1 i i e l ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) 1.0 30

- ~- . -. - -.. - -. ~. - i 1.3 RADIOACTIVE EFFLUENTS: TOTAL DOSE LIMITING CON 0 MON FOR OPER ATIC N i 1.3.1 The dose or dose corimitment to any member of the public, due to releases of radioactivity and radiation, from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 mrem) l over 12 consecutive months. APPLICABLE: At all Times, t ACTION: i 'i L a. With the calculated doses from the release of radioactive materials-in liquid or gaseous effluents exceeding twice the limits of ODCM i Speci ficatio n 1.1.3.1.a. 1.1.3.1.b, 1.2.3.1.a, 1.2.3.1. b, 1.2.4.1.a. o r. p 1.2.4.1.b,in lieu of any other report required and ODCM Section 1.6, prepare and submit to the Commission, within 30 days, pursuant to 4 Technical Specification 6.9.2, a Special Report which defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the limits of ODCM Specification 1.3.1. This Special Report shall include an analysis which estimates the radiation exposure (dose) to a member of the public from uranium fuel cycle sources (including all effluent pathways and direct radiation) for a 12 consecutive month period that includes the release (s) covered by this report, if the estimated dose (s) exceeds the limits of ODCM Specification 1.3.1, and if the release condition resulting in violation of 40 CFR 190 has not already been corrected. l the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR 190 and including information of i 190.11 (b). Submittal of the report is considered a l timely request, and a variance is granted until staH action.on the request is complete. The variance only relates to the limits of 40 CFR { 190, and does not apply in any way to the requirements for dose O r ODCM, V.C. Summer, SCE8G: Revision 13 (June 1990) { 1031 l

limitation of 10 CFR Part 20, as addressed in ODCM Specifications 1.1.2 and 1.2.2. b. The provisions of Technical Specifications 3.0.3 and 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS ) 1.3.2 Dose Calculations Cumulative dose contributions from liquid and i gaseous effluents shall be determined-in accordance with ODCM Specifications 1.1.3.2,1.2.3.2 and 1.2.4.2. j i l Ol i 1 i i i 4 i ODCM, V.C. Summer, SCE8G: Revision 13 (June 1990) 1.0 32 .e ..w,, .,. ~. - n v.. -,,. as --, ~ .. ~ ~-,,,, .-am._,-..

1 1 1.4 RADIOLOGICAL ENVIRONMENTAL MONITORING 1.4.1 - Monitorina Proaram LIMITING CONDITION FOR OPER ATION 1.4.1.1 The radiological environmental monitoring program shall be con. ducted as specified in Table 1.41. I l APPLICS3lLITY: At alltimes. l ACTION: With the radiological environmental monitoring program not being a. conducted as specified in Table 1.41 in lieu of any other report-required by ODCM Section 1.6, prepare and submit: to the Commission, in the Annual Radiological Operating Report, a O description of the reasons for not conducting the program as i required and the pians for preventing a recurrence. b. With the level of radioactivity in an environmental' sampling medium exceeding the reporting levels of Table -1.4 2 when averaged over any calendar quarter, in lieu of any other report i required by ODCM Section 1.6, prepare and submit to the' I Commission within 30 days from the end of the affected calendar j quarter a Special Report. When more than'one of the radionu'clides J in Table 1.4 2 are detected in the sampling medium, this report shall i be submitted if: concentration J1) e concentration (2) + ... s 1.0 limitleve (1) limit level (2) When radionuclides other than those in Table 1.4 2 are detected {

nd are the result of plant effluents, this report shall be submitted if the potential annual dose to an individual is equal to or greater

) q than the calendar year limits of ODCM Specifications 1.1.3.1, 1.2.3.1 (_/ t, ODCM, V.C. Summer, SCE8G: Revision 13 (June 1990) 1.0 33

I i

t i ? and 1.2.4.1. This report is not required if the measured level of radioactivity was not the result of plant effluents; however,in such l en event, the condition shall be ' reported and described in the Annual Radiological Environmental Operating Report. c. With milk or fresh leafy vegetable samples unavailable from one or i more of the sample locations required by Table 1.41,in lieu of any other report required by ODCM Section 1.6 prepare and submit to l the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report which identifies the cause of he unavailability l of samples and identifies locations for obtaining replacement samples. The locations from which samples were unavailable may j then be deleted from those required by Table 1.41, provided the i locations from which the replacement samples were obtained are - added to the environmental monitoring program as replacement f locations. .l d. The provisions of Technical Specifications 3.0.3 and 3.0.4 are not i applicable. SURVEILLANCE REOUIREMENTS The ra' iological environmental monitoring samples shall be I 1.4.1.2 d collected pursuant to Table 1.41 and shall be analyzed pursuant to the i requirements of Tables 1.41 and 1.4 3. t Y G c ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) 1.0 34

Tcble 1.41 RcdiclogiCal Envirenmental Monitering Progrcm Virgil C. Summer Nuclear Station Esposure Path. way and/or Minimum Number of Sample Locations and Sampling and Type & Frequency Sample Criteria for Selection Collection Frequency of Analysis Alasoncet 4 Particulates A) 3 Indicator tempies to be tal en at locations (in Continwows templer Gross beta following f dter ddferent te(' tors) beyond but as close to the operation with weekly change; Qwarterly estiwuon bowndary as practicable where the collection composite (by location) for highest offsitt senorial grow d level gamma ssotopic n concenteations are enacipated (1) t B) l indicator samp6e to be ta6 en in the sector Continwows templer Gross beta following f ater f beyond but as close to the esclusion bowndary as operation with weekly change. Qwarterly practicable corresponding to the repoence collection composite (by location) for j having the highest enticipated offsite ground gamma isotopic levelconcentration or dose (1) C) l indicator temple to be tak en at the location of Continwows sampler Gross beta f ollowing filter one of the dairies most likely to be effected (1) operation with weekly change owarterly I (2) collection composite (by location) for gamma itotopic D) 1 Contr01 sample to be talen at a location at least Continwows temp 6er Grott beta f ollowing filter i 10 aer miles from the site and not in the most operation with weekly thenge; owanerly prevalent wind directions (1) collection composite (by location) for gamma stotopic. 1 il Radio odine A) J anddator temples to be tak en at two locations Continuown tamper Gamma Isotc,pic for 6131 { algiven enl A above operation with weekly weekly I canister collennon B) 1 indicator sample to be tan en at the location as Continuous templer Gamma Isotc pic for 1 131 h given anl B above operation with weeb ly weekly canister collection C) 11ndicator sample to be ta6 en at the location 45 Continwows tampler Gamma isotopic for 1 131 giveniniC above operation with weekly weekly canister collection D) 1 Control temple to be ten en at a location as Continwows tampler Gamme isotopic for 1-131 givenin I D above operation with weekly weekly canister collection 111 Direct A) 13 indicator stations with two or more dosi-Monthly or Qwarterly (3.5) Gamma dose monthly or meters to form an inner ring of stations in the 13 quarterly l accessible sectors wrthin 1 to 2 miles of the plant l B) 16 Indicator stations with two or more dose-Monthly or awarterly (3.5) Gamma dose monthly or meters to form an outer ring of stations in the 16 quarterly accessible sectors within 3 to 5 miles of the plant C) 8 5tations with two or more dosimeters to be Monthly or awarterly (3.5) Gamma dote monthly or placed in specialinterest areas such as popula. gwarterly tion centers, nearby residences, schools and in 2 or 3 areas to serve as control stations C \\ ODCM, V.C. Summer, SCESG: Revisioin 13 (June 1990) 1.0 35 . _ ~ _

Tabl21.41 R di:lrgiCal EnvircnmsntalMonitcring Prcgram Virgil C. Summer Nuclear Station l 9! Esposure Path. way and/or Minimum Number of Sample Locations and Sampling and Type & Frequency Sample Criteria for Selection Collection Frequency of Analysis WAff Atohlet: I IV $wrface w ater A) 1 Indicator sample downstream to be ta6 en at a f ame composite samples Gamma isotopic monthly tor,ation which allows for mining and dilution in with coliection every with awarterly composite the wttimate receiving river monte (corresponds to (by location)or monthly U505 contin ows samphng sample to be analysed ior w site) (3) tritivm (5) 8) t Control sample to be teg en at a location on the Time composite samples Gamma isotopic monthly receiving river sufficiently far wpstream such that with collection every with Qwarterly composite no etf ects of pumped storage operation are montt. (corresponds to (by location) or monthly anticipated USG5 contenwows sampling sample to be analysed f or site) (3) tritium (5) 1 C) t indicator sample from a location immediately Time composite samples Gamma isotopic monthir upstream of the nearest downstream municipal with collection every with Quarterly composite water supply month (corresponds to (by location) or monthly USG5 tontin ows sampling sample to be analyred Ior w site) (3) tritswm (5) D) 1 Indicator sample to be tah eriin the upper f ame composite samples Gamma isotopic monthly reservoir of the pumped storage facehty in the with collection every with guarterly composite plant discharge canal month (corresponds to (bylocation)of monthly USG5 continwows sampling sample to be analyzed for site) (3) tritium (5) () 1 indicator sample to be tan en in the upper Grab sampi.ng monthly (3) Gamma isotopic monthly reservoir's non-fawetuating recreational area with awarterly composite (by location) or monthly sample to be analyzed fwt tritium (5) F) 1 Control sampie to be tan en at a location on a Grab sampling monthly (3) Gamma isotopic monthly separate una ffected watershed reservoir with awarterly composite (by 'ocation) or monthly sample to be analyzed f or tritsum (5) V Ground Water A) 2 Indicator samples to be tan en within the Qwarterly grab sampling Gamma isotopic and tre i esclusion boundary and in the direction of (5) tium andiyses awarterly (5) potentially a ffected ground water Supplies B) 1 Controi semple from unaffected location Qwarterly groo sampling Gamma ssotopic and tep (5) tium analyses awarterly (5) VI Drinking Water A) 1 indicator sample from a nearby public ground Monthly grab sampling (3) Monthly (3) gamma water supply source isotopic and gross beta analyses and quarterly (5) composite for tritium analyses B) 1 Indicator (finished *ater) sample from the Monthly composite Monthly (3) gamma nearest downstream water supply sampling isotopic and gross beta analyses and Qwarterly (5) composite for tritium analyses C) 1 Lontrol(finished water) sample from the Monthly composite Monthly (3) gamma nearest unaffected public water supply sampbng isotopic and gross beta analyses and Qwarterly (5) composite for tritium anaiysei O ODCM, V.C. Summer, SCE8G: Revision 13 (June 1990) t 1 1.0 36 1

d Table 1.41 Rcdialcgical Envircnmental Mcnitoring Pregrcm Virgil C. Summer Nuclear Station ( ~ Esposure Path. ~. way and/or Minimum Number of Samp!e Locations and Sampling and Type & Frequency Sample Criteria for Selection Collection Frequency of Analysis INGl 5 TION: 1 Vli Ma6 (2) A) Samples from mil 6 :ng enimais in 31ocations with-Semi monthly wten Gamma isotopic and s.131 en 5 t m distance having the highest dose poten. animals are on pastw e. (6) analysis semi monthly (6) r tial if there are mone then 1 sampie from missing monthly other times (3) when animal s are on animais in each of 3 areas between 5 to 6 6 m pastw e monthly (3)et r distante where doses are Calculated to be greater other times than 1 meem per year 8) 1 Contr01 sampM to be ten en at the location of a Semi monthly when Gamma isotopic and 6-131 dairy greater than 20 miles distante and not in animals are on pastw e.(6) analysis semi monthly (6) r the most prevalent wind direction (1) monthly other times (3) when animal s are on pastwre, monthly (3) at other times C) 1 Indicator grass (forage) sample to be tat en at Monthly when a.edable Gamma isotopic one of the locations beyond but as (lose to the (3) esclusion boundary as predicable where the highest offsite sectorial ground levei tontentra-tions are ente (spated (1) 0) 1 Indicator grass (forage) sample to be tal en at Gamma esotopic the lo(ation of Vil( A) above when animals are on Monthly when avsilable pastute (3) O 1 Control geass (forage) sample to be ta6 en at the Gamma isotopic location of Vil(B)above Monthly when availab6e (3) f Vill Food Products A) 2 samples of broadleaf vegetation grown in the 2 Monthly when available Gamma Isotopic on edible N nearest offsite location of highest Calculated (3) portion 1 annualaverage groundlevelDCif milk sampling es not performed within 3 h m or et milk sa'apling is not performed at a location within 510 h m where the doses are Calculated to be greater than i mrem /yr 8) 1 Control sample for the same iooos tak en at a Monthly when available Gamma isotopic on eo ble location at least 10 miles distante and not in the (3) portion most prevalent wind directionif miin sampimg is not performed withsn 3 6 m or of milk sampling is not at a location within 5 to 8 6 m where doses are calculated to be greater than i mremiyt IK Fish A) 1 Indicator sample to be tak en at a location in the Semiannual (7) tollection Gamma isotopic on edtble upper reservoir of the following specie portions semiennwally typesif available: bass; br ea m. Ctappie, tatfish. carp, forage fish (shad) 8) 1 Indicator sample to be tak en at a location in the $cmiannwal(7)tollection Gamma isotopi( on edible lower reservoir of the following specie portions semiannually typesif available: bass, bream (rappie, catfish. Corp forage fish (shed) C) 1 Indicator sample to be tak en at a location in the Semiannual (7)tollection Gamma isotopic on etene upper teservoir's non Itwetwating rett eational of the following specie portions semiannually area typesif available: bass; breart tra ppie; <atfish. Carp forage fish (thad) 1 l l l ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) 1.0 37 t l l i

l Tcbla 1.41 Rcdiclegical Envircnmentcl Monitcring Prcgrcm Virgil C. Summer Nuclear Station Erposure Path. way and/or Minimum Number of Sample Locations and $ampling and Type & Frequency Sample Criteria for Selection Collection Frequency of Analysis ex f eth(contin ed) D) 1 Control samp6e to be ta6 en at a location on the Semiennwal(7) collection Gamma isotopic on edible u retesving river tutticiently far wpttream such that of the following specie portions Semiannually j no effects of pumped storage operation are typesof available: ball. anticipated brea m, trappie, ta tfish. carp forage feth(tnad) AQUATIC: K 5ediment A) 1 indicator temple to be ta6 en at a location in the Semiannwel grab samp6e Gamma isotopic wpper relervoir (7) 6) 1 Indicator temple to be ta6 en at a location in the Semiannwel grab temple Gamma esotopit upper reservoir's non fluttwating retreational (7) area C) t indicator temple to be tal en on the shoreline of Semiannwel grab temple Gamma Autopic the lower reservoir (?) D) 1 Control temple to be tan en at a location on the Semiann elgrab temple Gamma isotopic w receiving river tutticiently f arwpttream such that (7) no ettects of pumped storage operation are l anticipated I O i 9 ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) 1.0 38 I

g.. l l 1 I NOTES Sampie site locations are based on the meteorological analysis for the period 1. l of record as presented in Chapters 5 and 6 of the OLER. 2. Milking animal and garden survey results will be analyzed annually. Should the survey indicate new dairying activity, the owners shall be contacted with regard to a contract for supplying sufficient samples. If contractual arrange-ments can be made, site (s) will be added for additional milk sampling up to a total of 3 Indicator locations. 3. Not to exceed 35 days. 4. Time composite samples are samples which are collected with equipment capable of collecting an aliquot at time intervals which are short (e.g.,' hourly) relative to the compositing period, 5. At least once per 100 days. 6. At least once per 18 days. I 7. At least once per 200 days. 1 \\ NOTE: Deviations from this sampling schedule may occasionally be necessary if [ ' i. sample media are unobtainable due to hazardous conditions, seasonal i unavailability, insufficient sample size, malfunctions of automatic { sampling or analysis equipment and other legitimate reasons. If specimens are unobtainable due to sampling equip. cent malfunction, every effort shall be made to complete corrective action prior to the end of the next sampling period. Deviations from sampling-analysis l schedules will be described in the annual report. l ODCM, V.C. Summer, SCE8G: Revision 13 (June 1990) i I-1.0 39 t _ ~.. _ _ ~. -

i TABLE 1.4 2 1 i Reportinytyvels for Radioactivity Concentrations in Environmental Samples { Reporting Levels i Airborne Par-Food i Water ticulate or Fish Milk Products i l Analysis (pCill) Gases (pCi/m3) (pCi/kg, wet) (pCi/l) (pCi/Kg, wet) 1 H3 20,000(a) N.A. N.A. N.A. N.A. l Mn 54 1,000 N.A. 30,000 N.A. N.A. l' Fe 59 400 N.A. 10,000 N.A. N.A. i Co 58 1,000 N.A. 30,000 N.A. N.A. j Co 60 300 N.A. 10,000 N.A. N.A. i Zn 65 300 N.A. 20,000, N.A. N.A. Zr 95 400 N.A. N.A. N.A. N.A. j Nb 95 400 N.A. N.A. N.A. N.A. 1131 2 0.9 N.A. 3 100 Cs134 30 10 1,000 60 1,000 t Cs 137 50 20 2,000 70 2,000 Ba 140 200 N.A. N.A. 300' N.A. i La 140 200 N.A. N.A. 300 N.A. l i (a) For drinking water samples. This is the 40 CFR Part 141 value. i l 9 i i ODCM, V.C. Summer, SCE & G: Revision 13 (June 1990) i 1.0 40 i j

i l f TABLE 1.4 3 + --Maximum Values for the Lower Limits of Detection (LLD)a.c Reporting Levels 1 1 Airborne Par-Food I Water ticulate or Fish Milk Products Sediment i Analysis (pCi/l) Gases (pCi/m3) (pCi/kg, wet) (pCi/l) (pCi/Kg, wet) (pCi/Kg, dry Gross Beta 4 1 X 10 2 N.A. N.A. N.A. N.A. H3 2000(b) N.A. N.A. N.A. N.A. N.A. lj Mn-54 15 N.A. 130 N.A. N.A. N.A. i t Fe 59 30 N.A. 260 N.A. N.A. N.A. i Co 58 15 N.A. 130 N.A. N.A. N.A. i t Co 60 15 N.A. 130 N.A. N.A. N.A. l l 2n 65 30 N.A. 260 N.A. N.A. -N.A. Zr 95 30 N.A. N.A. N.A. N.A; N.A.~ Nb 95 15 N.A. N.A. N. A.' N.A. N. A.- l131 1b 7 X 10 2 N.A. 1 F') N.A. Cs 134 15 5 X 10 2 130 15 60 150 Cs 137 18 6 X 10 2 150-18 80 180 I i Ba 140 60 N.A. N.A. 60 N.A. N.A, x La 140 15 N.A. N.A. 15 N.A. N.A. I

?

O ODCM, V.C. Summer, SCE8 G: Revision 13 (June 1990) 1.0 41 i e ..,,,__.-...-..,..,,...._..,._,_,_..._.__,.___.._.___.___m. i

TABLE 1.4 3 (Continued) ) g ? TABLE NOTATION a. Table 1,4 3 lists detection capabilities for radioactive materials in environmental I samples. These detection capabilities are tabulated in terms of the lower limits of detection (LLDs). See Table 1.1-4 notation (a) for definition of LLD. b. LLD for drinking water samples. c. Other peaks potentially due to reactor operations (fission arid activation products) which are measurable and identifiable,'together With the radio - nuclides in Table 1.4 3, shall be identified and reported. I 1 ~ o! I ) t i r i i ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) 1.0 42 -f

l 1.4.2 Land Use Census LIMITINCrEONDITION FOR OPERATION i 1.4.2.1 A land use census shall be conducted and shall identify the location of the nearest milk animal, the nearest residence and the nearest garden

of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of five miles.

~ APPLICABillTY: At all times. l ACTION: i With a land use census identifying a location (s) which yields a calculated dose or. a. dose commitment greater than the values currently being calculated in ODCM. Specification 1.2.4.2, in lieu of any other report required by ODCM Section 1.6, l prepare and submit to the Commission within 30 days, pursuant to Technical O Specification 6.9.2, a Specia! Report which identifies the new loca tion (s), i b. With a land use census identifying a location (s) which yie' Ids a calculated dose or f dose commitment (via the same exposure pathway) 20 percent greater than at a location from which samples are currently being obtained in accordance with ODCM Specification 1.4.1.1,in lieu of any other report required by ODCM Section - 1.6, prepare and submit to the Commission with in 30 days, pursusnt to Technical Specification 6.9.2, a Special Report which identifies the new location. The new location shall be added to the radiological environmental manitoring program within 30 days. The sampling location, excluding the cor of station location, i having the lowest i i The provisions of Technical Specifications 3.0.3 and 3.0.4 are not applicable. c. l t

Broad leaf vegetation sampling may be performus at the site boundary in the direction sector with the highest D/O in lieu of the garden census.

O a ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) 1.0 43 ? i .. - ~.., _. ,., ~. _. _,.. _. _ _ _ _ _ ~ -.

' ' ~ .g .l calculated dose or dose commitment (via the same exposure pathway) may be deleted from this monitoring program after October 31 of the year in which this i- - lantuse census was conducted. 1 1 SURVEILLANCE REQUIREMENTS i. 1.4.2.2-The land use census shall be conducted at least once per 12 months between the dates of June 1 and October 1 using that information which will provide l the best results, such as by a door to-door survey, aerial survey, or by consulting local -l agriculture authorities. t i i f t F 'j 1 1 91 ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) 2 1.0 44 7 [

I t 1.4.3 Interlaboratory Comparison Procram I i LIMITING 49NDITION FOR OPERATION - 1.4.3.1 Analyses shall be performed on radioactive materials supplied as part of an interlaboratory Comparison Program which has been approved by the Commission. t APPLICABillTY: At all times. i ACT!ON: l 3 With analyses not being performed as required above, report the corrective f a. actions taken to prevent a recurrence to the Commission in the Annual i Radiological Environmental Operating Report. t b. The provisions of Te:hnical Specifications 3.0.3 and 3.0.4 are not applicaole. SURVEILLANCE REOUIREMENTS O 1.4.3.2 A summary of the results obtained 'as part of the above required interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report (partidpants in the EPA crosscheck program shall provide the EPA program code designation for the unit). 1 I 9 I t I O i ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) 1.0 45 i 1 -n. , ~. - - - n +., --. ,-a ~. -,,,.. - - - -.. ~,,.,.. _. 5

I i 1.5 BASES 8/1.1 LIOUID FNLUENTS B/1.1.1 Radioactive Liovid Effluent Monitorino Instrumentation The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, tne releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The alarm / trip setpoints for these instruments shall be calculated in accordance with the procedures in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. The i OPERABit.lTY and use of this instrumentation is consistent with the requirements of ( General Design Criteria 60,63 and 64 of Appendix A to 10CFR Part 50. B/1.1.2 Concentration l This specification is provided to ensure that concentration of radioactive l materials released in liquid waste effluents from the site will be less than~ the concentration levels specified in 10 CFR Part 20, Appendix 8, Table ll, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will result in exposures within: (1) the Section ll.A design objectives of Appendix 1,10 CFR 50, to an individual, and. (2) the limits of 10 CFR 20.106 (e) to the population. l The concentration limit for dissolved or entrained r)oble gases is based upon the l assumption that Xe.135 the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described m International Commission on Radiological Protection (ICRP) Publication 2. B/1.1.3 Dose This specification is provided to implement the requirements of Sections ll.A, Ill.A and IV.A of Appendix 1,10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section ll.A. of Appendix 1. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonabiy achievable." Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR 141. The dose calculations in the ODCM implement the requirements in Section Ill.A of Appendix l that conformance with guides of Appendix i be shown by calculational procedures based on models and data, such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with ~ the methodology provided in NUREG 0133, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants", section 4.3. NUREG 0133 implements Regulatory Guide 1.109, Revision 1, October 1977 (section C.1 and Appendix A) and Regulatory Guide 1.113, April 1977. Regulatory Guide 1.109, October ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) 1.0 46 ..m _._,____m-m

6 Bases (centinusd) ~ 1 1977,is titled " Calculation of Annual Doses to Man from Routins Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I". e Regulatory Guide 1.113, April 1977,is titled " Estimating Aquatic Dispersion of Effluents i from Accite7ttal and Routine Reactor Releases for the Purpose of irriglementing U L Appendix I". 1 B/1.1.4 Liovid Waste Treatment I The OPERABILITY of the liquid radwaste treatment system ensures that this 1 system will. be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement that the appropriate portions of this l system be used whea specified provides assurance that the releases offradioactive materials in liquid effluents will be kept "as low as is reasonably achievable." This specification implements the requirements of 10 CFR Part 50.36a,' General Design j Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section ll.D of Appendix l to.10 CFR.Part 50. :The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the dose design objectives set forth in Section ll.A of Appendix 1,10 CFR E art 50, for liquid effluents.- 8/1.2 GASEOUS EFFLUENTS. B/1.2.1 Radioactive Gaseous Effluent Monitorino instrumentation. .I f^ The radioactive gaseous effluent instrumentation is provided to monitor and i control, as applicable, the releases af radioactive materials in gaseous effluents during. actual or potential releases of gam.us effluents. The" alarm / trip'setpoints for these i instruments shall be calculated in.secordance with the procedures in.the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. This - instrumentation also includes provisions for monitoring and controlling the'concen-l trations of potentially explosive gas' mixtures in the waste' gas holdup system. The l OPERABILITY and use of this instrumentation is consistent with.the requirements of General Design Criteria 60,63 and 64 of Appendix A to CFR Part 50. i B/1.2.2 Dose Rate This specification is provided to ensure that the dose at any time at the site boundary from gaseous effluents from all units on the site will be within the annual i dose limits of 10 CFR Part 20 for unrestricted areas.' The annual' dose limits are the doses i associated with the concentration ~ of 10 CFR Part 20, Appendix B Table 11, Column 1. These~ limits provide reasonable assurance that radioactive material discharged'in gaseous effluents will not result in the exposure of an individualin an unrestricted area, either within or cutside the site boundary, to annual average concentrations exceeding the limits specified in Appendix B, Table il of 10 CFR Part 20 (10 CFR Part 20.106 (b)). For-individuals who may at times be within the-site boundary,the occupancy.of the individual will be sufficiently low to compensate for anyl increase-inlthe atmospheric diffusion factor'above that for the site. boundary. The specified release rate limits. restrict, at all times, the corresponding gamme and beta dose rates above background + L g io an individual at or beyond the site boundary to less than or. equal to 500 mrem / year - ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) 1.0 47 t i .~. u -,,,

1 3 i BasGs (continuGd) l. to the total body or to less than or equal 3000 mrem / year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background l to a child via the inhalation pathway to less than or equal to 1500 mrem / year. I B/1.2.3 Dose. Noble Gases This specification is provided to implement the requirements of Sections ll.B', Illa and IV.A of Appendix 1,10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section ll.B of Appendix 1. The ACTION statements provide the required operating flexibility and at the same time implement the guides at forth in Section IV.A'of Appendix l to assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable" The Surveillance Requirements implement the requirements in Section Ill.A of Appendix 1 that. conformance with the guides of Appendix i be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The-dose calculations i established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in NUREG 0133," Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants", section 5.3. NUREG 0133 implements Regulatory Guide 1.109, Revision 1, October 1977 and Regulatory Guide 1.111, Revision 1, July 1977. Regulatory Guide 1.109 is entitled " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compi.ance with 10 CFR l Part 50, Appendix 1, " Revision 1, October 1977 and Regulatory Guide 1.111 is entitled " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light Water Cooled Reactors, " Revision 1, July 1977. The ODCM equations provided for determining the air doses at the site boundary are based upon the historical average atmospheric conditions. B/1.2.4 Dose Radioiodines, Tritium and Radioactive Materials in Particulate Form This specification is provided to implement the requirements of Sections ll.C, Ill.A and IV.A of Appendix 1,10 CFR Part 50. The Limiting Conditions for Operation are i the guides set forth in Section ll.C of Appendix 1. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A Appendix l to assure that the releases of radioactive materials in gaseous 3 1 effluents will be kept "as low as is reasonably achievable." The ODCM calculational methods specified in the Surveillence Requirements implement the requirements in Section Ill.A of Appendix Ithat conformance with the guides of Appendix i be shown by I calculational procedures based on models and data, mch that the actual expowre of an I individual through appropriate pathways in unlikely to be substantially underestimated. The ODCM calculational methods for calculating the doses due to the actual. release rates of the subject materials tre consistent with the methodology provided in NUREG-0133," Preparation of Radiolc gical Effluent Technical 5pecifications I for Nuclear Powe. lants", section 5.3. NUREG 0133 implements Regulatory Guide 1.109, Revision 1, October 1977 and Regulatory Guide.1.111, Revision 1, July 1977. Regulatory Guide 1.109 is entitled " Calculation of Annual Doses to Man from Routine g Releases of Reactor EHluents for the Purpose of Evaluating Compliance with 10 CFR Part W ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) 1.0 48 l'

jy Lo Bas:s (continued) 3 '( 50, Appendix 1, " Revision 1, October 1977 and RegulatoryLGuide 1.111 is entitled " Methods for Estimating Atmospheric Transport and Dispersion of of Gaseous Effluents in Routine Releases from Light Water Cooled Reactors, " Revision 1, July 1977. These equationsTm provide for determining the actual doses based upon the historical average atmospheric conditions. The reiuse rate specifications for radioiodines, i tritium, and radioactive materials in particulate form are dependent on the existing radionuclide pathways to man, in the unrestricted area. The pathways which were examined in the development of these calculations we e:- 1) individual inhalation of airborne radionuclides,

2) deposition of radionuclides onto green leafy vegetation

~

with subsequent consumption by man, 3) deposition onto grassy areas'where milk-animals and meat producing animals graze with consumption.of the milk and meat by t man, and 4)' deposition on the ground with subsequent exposure of man. B/1.2.5 Gaseous Radwaste Treatment The OPERABILITY of the GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREAT _ MENT SYSTEM ensures that the systems will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that the appropriate portions of these systems be used, when siecified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable" This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in'Section ll.D of O . Appendix I to 10 CFR Part 50. The specified limits governing'the use ot appropriate portions of the systems were. specified as a suitable fraction of'the dose design i objectives set forth in Sections ll.B and ll.C of Appendix I,10 CFR Part 50, for gaseous. ^i effluents. B/1.3 RADIOACTIVE EFFLUENTS: TOTAL DOSE The specification is provided to meet the dose limitations of 40 CFR 190. The. specification requires the preparation and submittal of a Special Report whenever the. calculated doses from plant radioactive effluents exceed twice the design objective doses of Appendix 1. For sites containing up to 4 reactors,it is highly unlikely that the u resultant dose to a member of the public will exceed the dose limits of 40 CFR 190 if the individual reactors remain within the reporting requirement level. The Special Report will describe a course of action'which should result'in the _ limitation of dose to a member of the public for 12 consecutive months to within the 40 CFR 190 limits. For the purposes of the Special. Report, it may be assumed that the dose commitment to the member of the public from other uranium. fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fue1 cycle facilities at'the same site or within a radius of 5 miles must be considered. If the dose to any member of the, public is estimated to exceed the requirements of 40 CFR 190, the Special Report with~a request for'a variance (provided the release. conditions resulting in violation of.40 CFR 190 have 'not already been corrected), in-accordance with the provisions of 40 CFR 190.11,is considered to be a timely request and fulfills the requirements of 40 CFR 190 until NRC staff action is completed. An individual is not considered a member of the ODCM, V.C. Summer, SCE8G; Revision 13 (June 1990). i l. L '1.0 49 L

+, i Basis (continued) public during any period in which he/she is engaged in carrying out any operation which is part of the nuclear fuel cycle. B/1.4.1 NroTiitorino Procram The radiological monitoring program required by this specification ~provides measurements of radiation of radioactive materials in those exposure pathways and for l those radionuclides..which lead to the highest potential radiation exposures of individuals resulting from the station operation. This monitoring program thereby f l. supplemer,ts the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the-environmental exposure pathways. The initially specified monitoring program will be l effective for at least the first three years of commercial operation. Following this period, program changes may be initiated based on' operational experience. The detection capabilities required by Table 1.4 3 are state of the art for routine environmental' measurements in industrial laboratories. It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the-capability of a measurement system and not as a posteriori (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated l LLDs wi!1 be achieved under routine conditions.- Occasionally background fluctuations 1 unavoidably small sample sizes, the presence of interfering nuclides, or. other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors will be identified and described in the Annual Radiological Environmental Operating Report. B/1.4.2 Land Use Census This specification is provided to ensure that changes in the use of unrestricted areas are identified and that modifications to the monitoring program are made if required by the results of this census. The best survey information fro _m the door to-door, aerial or consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the census to gardens of greater than 500 square feet provides assurance that - significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kglyear) i of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were used,1) that 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/ square meter. B/1.4.3 Interlaboratory Comparison Proaram The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are per-formed as part of the quality assurance program for environmental monitoring in order g_ to demonstrate that the results are reasonably valid. W.- ODCM, V.C. Summer, SCE &G: Revision 13 (June 1990) 1.0 50 1

W ~' 4 I J 1 1.6 REPORTING REOUIREMENTS 1.6.1 ATmual Radioloaical Environmental Operatino Report a 1.6.1.1 Routine radiological environmental operating reports covering the operation of the unit during the previous calendar year shall be submitted prior to May~1 of each year. The initial report shall be submitted prior to May 1 of the year following initial criticality. L i i. 1.6.1.2 The annual radiological environmental operating reports shall~ include i .t summaries, interpretations, and'an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including'a comparison i with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of land i use censuses required by ODCM Specification 1.4.2.1. If harmful effects or evidence of F irreversible damage are detected by the monitoring, the report shall provide'anL analysis of the problem and a planned course of action to alleviate the problem. The annual radiological-environmental operating reports shall include t summarized and tabulated results in the format of Regulatory Guide 4.8, December 1975 of all radiological environmental samples taken during_the report pericid. -In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the' reasons for missing results. Th'e missing data shall be submitted as soon as possible in a supplementary report.- l - 1 . } - The report shall also-include the following: ' a summary descriptioro of'the_ l. radiological environmental monitoring program) a map of all sampling locations keyed to a table giving distances and directions from one reactor;.and the results of '

i licensee participation in the Interlaboratory Comparison Program, required by ODCM Specification 1.4.3.1.

j f d .) 1 ODCM, V.C. Summer, SCE 8 G: Revision 13 (June 1990)- -I 1.0 51 1 li i

A 1.6.2 Semiannual Radioactive Effluent Release Report 1.6.E1 Reutine radioactive effluent release reports covering the operation of the unit d during the previous 6 months of operation shall be submitted within 60 days after

r. 3 January 1 and July 1 of each year. The' period of the first report shall begin with the date of initial criticality.

4 4 1.6.2.2 The radioactive effluent release reports shall include a summary of-the d quantities of radioactive liquid and gaseous effluents and solid waste released from I the unit as outlined in Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting ( Radioactivity in Solid Wastes and' Releases of Radioactive Materials-in Liquid and [ Gaseous Effluents from Light Water Cooled Nuclear Power Plants", Revision 1, June 1974, with data summarized on a. quarterly basis following the format of Appendix B thereof. l l The radioactive effluent release report to be submitted within 60 days after January 1 j of each year shallindude an annual summary of hourly meteorological data collected l over the previous year. This annual summary may be either in the form of a l hour listing of wind speed, wind direction, and atmospheric stability, and precipitation i (if measured) on magnetic tape, or in the form of joint frequency distributions of wind l speed,- wind direction, and atmospheric stability. This same report shall include an assessment of the. radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar-year. This same report ~ -shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to members of the public due to their activities inside the site I boundary (Figures 5.1-3 and 5.14 of the VCSNS Technical Specifications)lduring the l ~ [ year. All assumptions used in making these assessments (i.e., specific activity, exposure. 4 time and location) shall be included in these reports? Historical: annual average meteorology or meteorological-conditions concurrent with the time < of release'of radioactive materials in gaseous effluents (as determined by sampling frequency and L measurement) shall be used for determining the gaseous pathway doses. The assessment of radiation doses'shall be performed in accordance with th'e OFFSITE DOSE - ~ CALCULATION M ANUAL (ODCM). J ODCM, V.C. Summer, SCE8 G: Revision 13 (June 1990) L 1.0 52 !j;

+ 9 O '8e reo'e <1've e<<ieemtre' se reaert1 8 se8 ->11 o -i18'e so o x <1er> ee <v, 9 of each year shall also include an' assessment of radiation doses to the likely most I .. exposedeember of the public from reactor releases and other nearby uranium fuel j . cycle sources (including doses from primary effluent pathways and direct radiation) for. .the previous 12 consecutive months to show conformance with 40 CFR 190, Environmental Radiation. ProtectionLStandards for Nuclear Power Operation, i Acceptable methods for calculating the dose contribution from liquid and ' gaseous. effluents are given in Regulatory Guide 1.109, Rev.1. 1 The radioactive effluent release reports shallinclude unplanned releases from site to j unrestricted areas of radioactive materials in gaseous and liquid effluents on a quarterly basis. t. O 1 7 i i i q 9 l 0 ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) 1.0-53 =

m ll .o q H 1.6.3 ' Chanaes to the ODCM ~ 1 T.6.3.1 Weensee initiated changes to ODCMi a 1, Shall be submitted to the Commission in the Monthly Operating Report within : { 90 days of the date the change (s) was made effective. This submittal shall' ] contain: a. Sufficiently detailed information to totally support the rationale for the ] change _without benefit of' additional or supplemental _ infor'mation. ] 1 Information submitted.should consist of a package of these pages of i the ODCM to be~ changed with each page numbered and provided with an approva and date box, together with appropriate analyses or! l . evaluations justifying the change (s); - r. m j b. A determination that the change will not: reduce the accuracy or reliability of dose calculations or setpoint determinations; and' Documentation of the fact that the change has been-reviewe'd'a c. ~ found acceptable by the PSRC. l 2. Shall become effective upon review and acceptance as set forth in Technical l Specification 6.5. H' i 1 l 1! a 1 ODCM.'V.C. Su mmer, SCE & G : Revision 13 (June 1990) 1.0-54 .I-

g.. P o j. ~ 1.6.4 Maior Chances To Radioactive Waste Treatment Systems (Liquid and Gaseous) -i t 1.6.4.1 Literrsee initiated major changes to the radioactive waste systems (liquid and gaseous): 1. Shall be reported to the Commission in. the Monthly Operating Report for the period in which the evaluation was reviewed by the Plant Safety Review Committee. The discussion of each change shall contain a. A-summary of the evaluation that led to the determination that the change could be made in accordance i ith 10 CFR 50.59; b. Sufficient detailed information to totally support the~ reasorffor the - change without benefit of additional or supplementalinformation; A detailed description of the equipment, components abd processes c. . involved and the interfaces with other plant systems; i - A d. An evaluation of.the' change which shows the predicted releases or radioactive. materials in liq'uid and gaseous effluents that differs from! those 'previously predicted in the license application and amendments; thereto; An evaluation 'of the change which shows the expected maximum e. exposures to individual in the ~ unrestricted area and to the general population that differ from those-previously estimated in the license 1 - j. application and amendments thereto'; f. A comparison of the predicted releases of ~ radioactive materials, inL q liquid and gaseous effluents, to the actual releases for the pe'riod prior to when the changes are to be made,. 'q t g. An estimate of the exposure to plant operating personnel as a result of I the change; and u ODCM, V.C. Summer, SCE & G: Revision.13 (June 1990) 1'0 55 - l 1

9 -'E

s, b

I l - h.- Documentation of the fact that.the changelwas reviewed and found 1 -; acceptable by the PSRC; f ' ! 2.' > Shah become ' effective upon review and scceptance as. set.forth in-Technical: i C hecification 6.5. 5 e S ' = p 1 i. - i' f t 1 e i f t 4 'l 4 e ODCM, V.C. Summer, SCE&G: Revision 13 (Jun'e 1990). 1.0 56 1

7-g.. 1.7 Definitions ACTION -- L 1-7.1 ACTION shall be that part of a specification which prescribes measures required under designated conditions. ANALOG CHANNEL OPERATIONAL TEST I' 1.7.2 A'n ANALOG CHANNEL OPERATIONAL TEST shall be the injection of a simulated signal linto the channel as close to the sensor as' practicable to verify OPERABILITY of alarm, interlock and/or trip functions. The~ ANALOG CHANNEL OPERATIONAL TEST shall. include adjustments, as necessary, of the alarm, interlock and/or trip setpoints such that the setpoints.are within the required - 1 range and accuracy. CHANNEL CALIBRATION i

1.7.3 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel such that it responds within the required range and ' accuracy to known values of input. ' The CHANNEL CAllBRATION shall encompass the entire channel including the. sensors and alarm, interlock and/or trip functions, and may be

~ performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated. f CHANNEL CHECK 1.7.4 A CHANNEL CHECKS shall be the qualitative. assessment of channel behavior during operation by observation.' This determination shall include, 'where possible, comparison of the channel indication' and/or status with oth'er ~ indications and/or status' derived from-independent instrument channels measuring the same parameter. i GASEOUS RADWASTE TREATMENT SYSTEM 1.7.5 A GASEOUS RADWASTE TREATMENT SYSTEM is any system: designed, and j ' installed to reduce radioactive gaseous effluents by collecting primary coolant system off gases from the primary system'and providing for delay or holdup for the purpose of reducing the total radioactivity; prior tofrelease to 'the environment. I L ODCM, V.C. Summer, SCE& G: Revision 13 (June 1990) l 1.0 57 i l \\ 1

o.. O. OPERABLE OPERABlLITY 1.7.6. A system, subsystem, train, component or device shall be OPERABLE or have-OPERABILITY.when it is capable of performing its specified function (s), and. ' when all'necessary attendant instrumentation,' controls, electrical power,. - cooling or seal water, lubrication or other auxiliary. equipment that are required for the system, subsystem, train, component or device to perform its - fun'ction(s) are also capable of performing their related support function (s).- 1 SOURCE CHECK 1.7.7-A SOURCE CHECK shall be the qualitative assessment of channel response when .the channel sensor is exposed to a radioactive source. - VENTILATION EXHAUST TREATMENT SYSTEM 1.7.8 A VENTILATION EXHAUST TREATMENT SYSTEM'is any system designed and. installed to reduce gaseous radioiodine or radioactive materiakin particulate form in eHluents by' passing ventilation or vent exhaust gases through charcoal j absorbers and/or HEPA filters for the purpose of removing iodines or particu-i lates from the gaseous exhaust ' stream prior to the release to the environment gj (such a system is not considered to have any effect on noble gas effluents). Engineered: Safety Feature (ESF) atmospheric cleanup systems are:not j considered to be VENTILATION EXHAUST TREATMENT SYSTEM components. l

l o

,I l i i 1 .. j l I i ODCM, V.C. Summer SCE&G: Revision 13 (Jurie 1990)' 1.0 58 0 i

1 7 d 2.0 - LIQUID EFFLUENT 2.1 - Licuid Effluent Monitor Setooint Calculation ' The Virgil C. Summer Nuclear Station is located on the Monticello Reservoir which provides supply,and discharge; for the plant circulating i water..This reservoir also. provides supply and discharge capacity for.the - i Fairfield Pumped Storage Facility. The Parr Reservoir located below the pumped storage facility is #ormed by the Parr Dam. ~ There are two analyzed release pathways and sources of dilution for liquid efiluents: the circulating water discharge canal and the liquid effluent -line to the penstocks of the pumped storage facility. All1 liquid effluent pathways discharge to one of these release points. Generally speaking, very l low concentrations of radioactive waste are discharged.to the circulating water discharge while higher concentrations'of radioactive waste are ) released to the penstocks of the' pumped storage facility during the l 9eneration cycle. - The calculated setpoint values will be regarded as' upper bounds for the actual setpoint adjustments.,That is, setpoint adjustments are not required to be performed if the existing'setpoint level corresponds to a lower - count rate than the calculated value. Setpoints may be established at values - lower than the calculated valu'es. if desired. Calculated monitor setpoints may be added to the ' ambient back-ground count rate. GENERAL NOTE: If no ' discharge is planned for a specific pathway or if the ' sum of the eHluent concentrations of gamma emitting nuclides equals zero, the monitor setpoint should be established as close to background as practical to prevent spurious alarms and yet alarm should an inadvertent release occur. O ODCM, V. C. Summer, SCE&G: Revision 13 (June,1990) 2.0 1

2.1.1 Liouid Effluent Monitor Setooint Calculation' Parameters n of [',c ~ Term Definition *- Penstock discharge adjustment factor which will allow 2.1.2 A ~ = the set point to be established in a convenient manner and to prevent spurious >'.nm; = f /f x t d B Steam Generator Blowdown adjustment f actor which 2.1.4.1 = will allow the set point to be established in a convenient manner and to prevent spurious alarms. = f / fos d C ' the effluent concentration limit (Specification 1.1.2) 2.1.2 = implementing 10CFR 20 for the site, in uCi/ml. the effluent concentration of alpha emitting nuclides 2;1.2 C, = observed by gross alpha analysis of the monthly composite sample, in uCi/ml.. C,. the measured concentration of Fe 55 in liquid waste as -2.1.2 = determined by analysis of the most recent available quarterly composite sample, in uCi/ml. the effluent concentration of a gamma emitting nuclide,- 2.1.2 C, = g, observed by amma rayspectroscopy of the waste sample,in uCi/ l. the concentration of nuclide i,in uCi/ml, as determined 2.1.2 t C = by the analysis of the waste sample. t the concentration of radionuclide i,in uCi/ml,in the 2.1.2 C,, = Monticello Reservoir. Inclusion of this term will correct for possible long term buildup of radioactivity due to ; recirculation and for the presence of activity recently released to the Monticello Reservoir by plant activities. C, ' the concentration of Sr 89 or Sr-90 in liquid wastes as-2.1.2 = determined by analysis of the quarterly composite. l sample, in uCi/ml., L C, the measured concentration of H 3 in liquid waste as' >2.1.2 = L determined by analysis of the monthly composite,in L uCi/ml.. E the setpoint,in uCi/ml, of the radioactivity monitor 2.1.2f c = measuring the radioa'ctivity. concentration in the ef-L fluent line prior to dilution and sut sequent release. This L, setpoint which is proportional to the volumetric flow to. the effluent line and inversely proportional to the. volumetric flow of the dLlution stream plus the effluent - y L s'..eam, represents a value which, if exceed-ed, would 4 result in concentrations exceeding tho limits of 10CFR 20 in the unrestricted area. the monitor setpoint concentration for RM L7, the 2.1.2.2' l c,. = Nuclear Blowdown Monitor Tank discharge line monitor, in uCi/ml. ' All concentrations are in units of uCi/mi unless otherwise noted. 'ODCM, V. C. Summer, SCE&G: Revision 13 (June,1990) 2.0 2 1-j i s .A

p J i'*4 i Term Definition I'C ni 1, the mon' or set oint concentration for RM L the 2,1.2.3 1 p c = C combin Li ui Waste Process' System a Nuclear Blowdown 5 stem effluent disc arge line monitor,in l uCi/ml. i the monitor setpoint concentration for RM L11 the' 2.1.4.1.3 c D Condensate Demineralizer Backwash discharge,line - monitor,in uCi/ml. the monitor ketpoint concentration for RM L5'l. the Waste 2.1 2.1 c" = Monitor Tan discharge line monitor,in uCi/m ~t the initial l2.1.4.1.1 l . the monitor setpoint concentration for RM L3,itor,in' c* = 5 Steam Generator Blowdown Effluent line mon 4 uCi/ml. the monitor setpoint concentration for RM L10 the final 2.1.4;1.1 c = 5 Steam Generator Blowdown Effluent line moni,or,in : t utilml. 1 L the monitor setpoint concentration for RM L8, the 2.1.4.1;2 c'- = Turbine Building Sump Effluent line monitor, in uCi/ml. the Condensate Demineralize Backwash Effluent L2.1.4.1' l CF = Concentration Factor, t CF the Steam Generator Blowdown Effluent Concentration 2.1.4.1 = 3

Factor, CF the Turbine Building Sump Effluent Concentration

~ 2.1.4.1 = 7 Factor. I DF = the dilution factor, which is the ratio of the total dilution 2.1.2 flow rate to the effluent stream flow rate (s). F the dilution water flow setpoint as determined prior to-2.1.2 ~ = the release, in volume per. unit time. the flow rate of the Circulatina Water System during the 2.1.4.1 F = time of release of the T rbinelluildino Sump and/or the Steam Generator Blow own,in volurde per unit time. the dilution flow rate of the Circulating Water 5 stem. . 2.1.4.1 F( = used for effluent monitor setpoint calculations ased on 90 percent or expecte Circulating Water System flow - rate during t1e time o release and corrected for recir-culated Monticello Reservoir activity, in volume per unit time. t le radioactive liquid release upon which th(e)effluentle dilution flow rate th ~ 2.1.2 : F* t = monitor setpoint is based,in volume per unit time. as corrected for any recirculated radioactivity..

(Conservatively this value will be either zero, if no release is to be conducted from this system, or the maximum measured capacity of the discharge pump if a release is to be conducted.)-

ODCM, V. C. Summer, SCE&G: Revision 13 '(June,1990)- 2.0 3-i - - ~ -..~ _._

..q I',' " ',I Term Definition n g F, the flow rate of water through the Fairfield Pumped 2.1.2 = Storage Station penstock (s) to which radioactive liquids are being discharged during the period of effluent < release.T1is flow rate is dependent upon operational status of Fairfield Pumped Storage Station,in volume per unit time. f the effluent line flow setpoint as determined for the 2.1.2 - = radiation monitor location, in volume per unit time. . f, the maximum permissible discharge flow rate for re-2.1.4.1- =- leases to the Circulating' Water,in volume per unit time. f* = the flow rate of the Nuclear Blowdown Monitor Tank 2.1.2 o* discharge,in volume per unit time. f,,

the flow rate of a Waste Monitor Tank discharge,in 2.1.2

= volume per unit time, f'* the flow rate of the Steam Generator Blowdown - '2.1,4.1 = discharge,in volume per unit time. f, the flow rate of the tank discharge, either fdm or fob, in 2.1.2 = a volume per unit time. f' the recirculation flow rate used to mix the contents of a 2.1.2 = tank,in volume per unit time. f, the maximum permissible discharge flow rate for batch 2.1.2 = releases to the penstocks, in volume per unit time; M

MPC, MPC MPC,, MPC, MPC and MPC, = the. limiting.

_2.1.2- = conc %,ntrations of,the ap,,propriate gamma emitting, alpha emitting, and strontium radionuclides, Fe 55, and tritium, respectively, from 10CFR, Part 20, Ap sendix B, Table 11, Column 2. For gamma emitting nob e gas .i radionuclides, MPC, = 2 x 10 4 uCi/ml. SF the safety factor, a conservative factor used to compen; 2.1.2 = sate for engineering and measurement uncertainties. SF = 0.5, corresponding to a 100 percent variation. [ Cilu.o the Lower Limit of Detection (LLD) for radionuclide i in '2.1.3 = liquid waste in the Waste Monitor Tank,'as determined. t by the analysis required in ODCM Table 1.1-4, in uCi/ml; e ! Ci}y the concentration of radion'uclide iin the waste con- - 2.1.3 - = tained within the Waste Monitor Tank serving as the holding facility for sampling and analysis prior to discharge, in uCi/ml. 1 ) ODCM, V. C. Summer, SCE&G: Revision 13 (June,1990) 2.0 4

X p., i L o [';Ch" T,erm Definition-EC = the sum of the concentrations Cg of each measured 2.1.2 j g g gamma emitting nuclide observed by gamma ray spectroscopy of the waste sample,in uCi/ml. (E Cglo the gamma isotopic concentrations of the Nuclear 2[1.2 = g Blowdown Monitor Tank as obtained from the sum of the measured concentrations determined by the analysis required in ODCM Table;1.14, in uCi/ml. (ECalo the gamma isotopic concentrations of the Condensate '2.1.4.1 = g Demineralizer Backwash effluent (including solids) as' 4 i obtained from the sum of the measured concentrations ' i a determined by the analysis required in ODCM Table 1.1- ~4, in uCi/ml. (I Cg}u the gamma isoto'pic concentrations of the Waste -2.1.2 = g 1Aonitor Tank as obtained from the sum of the measured concentrations determined by the analysis required in ODCM Table 1.1-4,in uCi/ml. (I CgIs the gamma isotopic concentrations of the Steam 2.1.4.1 = -g Generator Blowdown as obtained from the sum of the measured concentra tions determined by the analysis required in ODCM Table 1.14,in uCi/ml. (E Cgl7 the gamma isotopic concentrations of the Turbine 2.1.4.1 = g Building Sump ~as obtained from the sum of the measured concentrations determined by the analysis required in ODCM Table 1,1-4,in uCi/ml. (E (Ci MPCi))o / = the sum of the ratios of the measured con centration of 2.1.4.1 nuclide i to its limiting value MPC for the Condensate 1 Demineralizer Backwash. (E (Ci MPC ))3 / i = .the sum of the ratios of the measured concentration of 2.1.~ 4.1 nuclide i to its limiting value MPC for the Steam Generator Blow down Effluent. ' F [E (Ci MPCi)]r / = the sum of the ratios of the measured con centration of 2.1.4.1 nuclide i to its limiting value MPC, for the Turbine ' Building Sump Effluent. (E (Ci MPCi)), / = the sum of the ratios of the measured con centration of 2.1.2 nuclide i to its limiting value MPC for the tank whose contents are being considered for release. For a WMT, X-i = M. For the NBMT, X = B. the minimum time for recirculating the contents of a _ L2.1.2 t, = tank prior to sampling,in minutes. H V-the volume of liquid in a tank to be sampled, in gallons. 2.1.2-l .= 1 1 l .1 t ODCM, V. C. Summer, SCE&G: Revision 13 (June,1990) 2.0 5 J.a, .i.i

.l,: ,o. 1 -2.1.2~- Liould Radweste Effluent Line Monitors - u -_,l '(RM-LS, RM L7, RM L9)' I ~ Liquid Radwaste Effluent Line Monitors provide _ alarm and auto-I 'matic termination of release functions prior.to exceeding the concentration n limits specified in.10CFR 20,' Appendix B; Table 11,' Column 2 at the release [ point:to the unrestricted area. To meet this specification, the alarm / trip setpoints for liquid effluent monitors and flow measurement devices are set to assure that the fol'Iowing equation is satisfied: i cf (1). ~U* .y+f where: 'C=- the effluent 4oncentration limit (Specification 1.1.2) implementing 10CFR 20 for the site in uCi/ml. I the setpoint, in uCi/ml, of the radioactivity monitor measuringithe-c= g; l radioactivity concentration in-the effluent line prior to dilution and ' W! subsequent release; the setpoint, which-is inversely proportional to j the volumetric flow of the. effluent line 'and proportional to the; i volumetric flow of the dilution' stream' plus the ~ effluent' stream,. represents a value which, if exceeded, would result in' concentrations exceeding the limiti of 10CFR 20 in the unrestricted area. F= the' dilution water flow setpoint as determined prior to the release point,in volume per unit time. f f= 'the effluent line flow se'tpoint.as determined at the radiation monitor location, in volume per unit time, ~ i At the Virgil C. Summer Nuclear Station the Liquid Waste Processing-1 System (LWPS) and the Nuclear: Blowdown System (NBS) both discharge to-the penstocks of the Fairfield Pump'ed. Storage-(FPS) Facility throUgh a - i ODCM, V C. Summer, SCE&G: Revision 13 (June,1990)' 2.0 6 l

i d common line. - The available dilution water flow (F,) is assumed to be 90 percent of the flow through the FPS penstock (s) to which liquid effluent is being discharged and is dependent upon operational status of the FPS Facility. The waste tank flow rates (f and f.) and the monitor setpoints (c, c, and c ) are set to meet the~ condition of equation (1) for a given. ~ u c effluent concentration, C. The three monitor setpoints are determined in u accordance with the monitor system configuration for this. discharge { pathway. The LWP5 discharges through RM L5i which has setpoint cs for alarm / control functions over releases from either Waste Monitor Tanks 1 or

2. The Nuclear Blowdown discharges through RM L7, which has setpoint c 7 for alarm / control functions over. releases from the Nuclear Blowdown Monitor Tank. These two release pathways merge into a common line i

monitored by RM L9, which has setpoint c for control functions over the. I c common effluent line. Although the piping is arranged so that simultaneous batch releases from the two systems could be practiced, operational releases j shall b, e from only one qf the two batch systems e any given time. ~ The n method by which their setpoints are determined is as follows:. I 1) The isotopic concentration for a waste tank to be released is obtained from the sum of the measured concentrations as determined by the analysis required in Table 1.14: C, = c, + c, + c, + cf + c7 g) { 3 4 where: C, the concentration of nuclide i, in uCi/ml, as determined by = the analysis of the waste sample. l 1 Values for Ca, Cs,- C and Cf will ~be based on most recent'available t composite sample analyses as required by Table 1.1-4. t ODCM, V. C. Summer, SCE&G: Revision 13 (June,1990) d 2.0 7

ECg . the sum of the concentrations C, of each measured gamma- ~; = g ,j 9~ emitting ~nuclide observed by gamma ray spectroscopy of the waste sample,in uCi/ml. ths ' effluent concentration-of. alpha emittinD nuclides C,*~ = j observed by gross alpha analysis of.the monthly composite -l sample,in uCi/mll. C,*' .the concentration of Sr 89 and Sr 90 in liquid waste as = .] determined by analysis of the quarterly composite sample, -in uCi/ml. C,* the measured concentration _ of _ H 3= in' liquid waste as: = ) determined by analysis of the monthly composite sample, ) in uCi/ml. I 1 C,* .the measured concentration of Fe 55. in liquid waste as = determined by analysis of the quarterly composite sample, in uCi/ml. The Cg term will be included in the analysis of each batc'h'; terms for) g-alphai strontium,' Fe 55, and tritium shall betincluded as appropriate *. Isotopic concentrations for. both the Waste Monitor Tanks (WMT) and the Nuclear Blowdown Monitor Tank (NBMT) may1 'be calculated using equation (2). l Prior to being sampled for analysis;the' contents of a tank shall be isolated and recirculated. The minimum recirculation time shall be: .t, = 2V/f, (3) tr the minimum time for recirculating the' contents.of a - I = j tank prior to sampling. l V = the volume of liquid in the tank to be sampled. f f, the recirculation flow rate used.to mix the. contents of a = tank. ~ ODCM, V. C. Summer, SCE&G:. Revision 13 -(June,1990) 2,0 8 a .. j

= i j. ~ i This is done to ensure that a representative sample will be obtained. . Me;hanical mixers shall ensure a similar minimurr turnover. l 1 1 2)~ Once isotopic concentrations for either Waste Monitor Tank or the Nuclear Blowdown Monitor Tank have been determined, these values are used to calculate a Dilution Factor, DF, which is the ratio of ' i dilution flow rate to' tank flow rate (s) required to assure that the ' I limiting concentratio~n of 10CFR, Part 20, Appendix B, Table 11, ~ ~ Column 2 are met at the point of discharge for whichever tank is i having its contents discharged, i, 1 -C or = V . sr (4): 1 t ~~ MPC, i i C C C C C' l MPC l MPC;

MPC, MPC.

MPC, ' where: V 1 -1 C O T the sum of the ratios of the measured concentration of = -- MPC, nuclide i to its limiting value MPC for the tank whose-8 contents are being considered for release. For a WMT, X = M. For the NBMT,X = B.

MPC,

= MPC,, MPC,, MPC,, MPC,, and. MPC(= limiting concen-trations of th.e appropriate gamma 1 emitting, alpha-emitting;.and strontium radionuclides,L Fe 55.. and l tritium, respectively, given in 10CFR, Part 20,' Appendix B, Table 11, Column' 2. lFor gamma emitting noble ' gas. radionuclides MPC,is to be set equal to 2 x'10'd pCi/ml, d. according to the Radiological Effluent Technical Speci-fications. SF =: the safety factor; a conservative-factor used to com-1 pensate for engineering and measurement uncer-tainties. 1 j = 0.5, Corresponding to a 100 percent variation. O ODCM, V. C. Summer, SCE&G: Revision 13 (June,1990) ' 2.0 9 1" ~

t m 3) The maximum permissible discharge flow rate, f,,Lmay be calculated for the release of either the WMT or NBMT. First the' appropriate-Dilution Factor is calculated by applying.equatio.n (4), using the appropriate concentration ratio term (i.e. M or' B), then,- lgp + /g_, Y, g . /, = = p /or f,,, > > /g (6) y where: F = dilution flow rate to be used in effluent monitor setpoint - op calculations, based on 90 percent FPS Station expected flow rate, as corrected for any recirculated radioactivity: C dp " # U (I - 1

F

) (7) 4 4 where: F, = the. flow-rate through the Fairfield Pumped Storage Station penstock (s) to which radioactive: liquids are^being discharged. F, should normally fall between 2500 and 448C0 cis. C,, = the concentration of radionuclide i,in uCi/ml,in-the intake of Fairfield Pumped Storage Station-(that is,in the Monticello Reservoir). Inclusion of this term will correct,for possible long term buildup of radioactivity due to ' recirculation and for the presence of activity recently released to the Monticello Reservoir by plant activities. For - expected discharges of liquid wastes, th'e. summation will be much less than 1.0 and can be ignored (Reference 6). O ODCM,V.C. Summer,SCE&G: Revision 13 (June,1990) 2.0 10 3

o ,p i f,, the flow rate of the tank discharge, either f,, or f,,.

{

= i f,, flow rate of Nuclear Blowdown Monitor Tank discharge. = (Conservatively this value will be either zero,if no release is to be conducted from this system, or -the maximum measured capacity of the discharge pump if a release is to be conducted.) - \\ f,, flow rate of Waste Monitor Tank discharge. '(Conserva- = tively this value will either be zero, if no release'.is to be I conducted from this system, or the maximum measuredi i capacity of-the discharge pump if a release is to be conducted.) 4 DF the Dilution Factor from Step 2. = If f, il f,, the release may be made as planned and the flow rate a monitor setpoints should be established as in Step 4 (below). Because F,,is normally very large compared to the maximum discharge pump capacities for the Waste Monitor Tank and the Nuclear Blowdown Monitor Tank, it is extremely _ unlikely.that f, <-f,. However, if ~a j a situation should arise such that fi< f,,, steps must_be taken to assure that equation (1) is satisfied prior to making the release. These steps may include decreasing f ',' by decreasing the flow rate of f, or f,,, e a and/or increasing F,. When new candidate flow rates are chosen, the calculation's above should be repeated to verify that they combine to form an' acceptable release.' If they do, the establishment of flow rate monitor setpoints- ] may proceed as follows'in Step 4. If they do not, the choice. of'- d candidate flow rates must be repeated until an acceptable set is identified. Note that if DF 51, the waste tank concentration for which the calculation is being performed includes safety factors in Step 2 and meets the limits of 10CFR 20 without furthe'r dilution. Even though O ODCM, V. C. Summer, SCE&G: Revision 13 (June,1990) j 2.0 11

I '. )

u..

a. (

i 1 no dilution would be required, there will be no discharge if minimum dilution flow is not available, since the penstock minimum flow' .j n interlock will prevent discharg. j 4) The dilution flow rate setpoint*, F, is established at 90 percent of the .i expected available dilution flow rate: -r i F = (0.9) F, (8) l The flow rate monitor setpoint* for the effluent stream shall be set at the selected discharge pump rate (normally the maximum ' discharge l pump rate or zero) f, or f chosen in Step 3 above. 5) The radiation monitor setpoints may now be determined based on. the values of E Ci, F, and f which were specified to provide compli - ~ ance with the limits of 10CFR 20, Appendix B, Table 11, Column 2. The monitor response is primarily to gemma radiation, therefore, the-actual setpoint is based on EC,. The setpoint concentration, c, is determined as follows! e s {c, ya (9) { l [ A= Adjustment factor which. will= allow the setpoint to'be~ ~ j p established in a practical manner for convenience and to-3 prevent spurious alarms.- - A = f,I[g 10 L if A E 1, Calculate c and. determine the maximum value for the actual monitor setpoint (cpm) from the monitor calibra-E . tion graph. i-p

Set points for flow rates a're administrative limits.

a 4 ODCM,V. C. Summer, SCE&G: Revision 13 (June,1990) [ j 2.0 12. + -. - + ..A, . + ~

a

K I

if A < 1, No release may be made. Reevaluate the alternatives presented in Step 3. i NOTE: If calculated setpoint values are near actual concentrations. l planned for release, it may be impractical to set the monitor alarm at this value, in this case a new setpoint may i be calculated following the remedial methodology presented in Step 3 for the case of f < f. i i Within the limits of the conditions stated above, the specific moniior setpoint concentrations for the three liquid radiation monitors RM-l L5;RM L7, and RM L9 are determined as follows: I 2.1.2.1 RM L5. Waste Mo' nitor Tank Discharae Line Monitor: c s' -1 c, ut y y (33) s Cu is in uCi/ml - i LO 'See GENERAL NOTE under 2.1. 1 L 2.1.2.2 RM L7, Nuclear Blowdown Monitor' Tank Dis charoe Line. ~ 4 Monitor: c, s 1 c,,idi (12) e i CB sin uCi/ml i t 'I NOTE: In no case should discharge be made directly from-the Nuclear Blowdown Holdup Tank. Its contents should_ always be processed via the. Nuclear Blowdown Monitoring Tank. 1

See GENERAL NOTE under 2.1.

.l-O 1 ODCM, V. C. Summer, SCE&G: Revision 13 (June,1990) 2.0 13 I a ~,.,

~ ai-

j. ;

l c, 2.1.2.3: RM L9, Combined Liouid Waste Proce';sino System-L and Nuclear-Blowdown Waste' Effluent Discharae i.ine-Monitor i The monitor setpoint' concentration-on-the common line, c. should be-the. same as the setpoint - c concentration' for the monitor on th'e active individual discharge line (i.e., c, or c, as Menned aboveh l I u c s M C,,c,t (13)._ t e r

See GENERAL NOTE under 211.

i l-NOTE: In-all cases, c, c, and c :are the setpoint y c concentration' values in uCi/ml. lThe actual i monitor setpoints (cpm) for RM LS, RM L7, and ~ t RM L9 are determined from the calibration graph. for the.particular monitor. -Initiallyi the calibra-i tion curves were determined conservatively from. families of[ response l curves supplied by :the monitor manufacturers. A sam'ple is shown.in l Figure 2.1-1. As releases occur,' a historical correlation will be prepared and placed in service d when sufficient data are accumulated. 2.1.3 Liould Radwaste Discharoe Via Industrial and Sanitary' Waste System (RM L5) i =i i l In the Virgil C. Summer Nuclear' Station?liqu'id waste ( L effluent system design, there exists a me'ch'anism for' discharging ~ liquid wastes via the Industrial Sanitary Waste System. The sample O point prior to. discharge is one of.the Waste' Monitor Tanks. The j analysis requirements are the requirements listed in Table 1.1 4. 1, ODCM, V. C. Summer, SCE&G: Revision 13 (June,1990) 2.0 14 ~.L r~., .m m

i t 1 This effluent pethway shall only be1used when the, nQ following condition is met for all radionuclides, i: C, u C. u.o (14) 5 s 1 the concentration of radionuclide i in'the waste con-c' = ' 8 tained within the Waste Monitor Tank serving as the holding facility for sampling and analysis prior to. discharge,in uCi/mi. q, i the Lower Limit of Detection,~ (LLD) for radionuclide i in ; c- =- ' g the liquid waste in the Waste Monitor Tank as deter-1 mined by the analysis required in Table 1.1-4,in uCi/ml. ] When the conditions of equation '(14) are met, liquid waste may be released via the industrial and Sanitary Waste System pathway. The RM L5 setpoint should be established as close to background as practical to prevent j spurious alarms and yet alarm should an' inadvertent high concentration release occur.- 2.1.4 Steam Generator Blowdown Turbin'e Buildina' Sumo, and Ccinden-g sate Demineralizer Backwash Effluent Lines: i (RM L3; RM-L10, RM L8; RM L11) I Concentrations of radionuclides in the~ liquid effluent discharges j made.via the Turbine Building Sump, Steam Generator Blowdown and Condensate Demineralizer Backwash are< expected to!be ~very low or nondetectable. The first two releases are expected to' be continuous in - ~ nature and the last a batch release. All will be samplediin an' appropriate' j h manner as specified in Table 1.1-4 of the ODCM. The Steam Generator. Blow. -i down Monitors,-the Turbine Building Sump Monitor, and the. Condensate Demineralizer Backwash Monitor provide alarm and automatic termination ~ of release prior to exceeding'the concentration limits specified in 10CFR 20, Appendix B, Table 11, Column 2 at the release point to the unrestricted area.' . -OL I L ODCM, V. C. Summer, SCE&G: Revision 13 (June,1990) s L 2.0 15 e .w ,, ~..

,w ^ T in' reality l all of these effluent' pathways' utilize.the circulating water as L dilution to the effluent stream, with the circulating water discharge canal being the point' of' release intofan unrestricted area. However, to. _. compensate for uncertainties in the transit times of activity discharge to the Industrial and Sanitary Waste System, discharges to that system will not be- - credited with dilution for the purpose of monitor setpoint calculations. The Turbine Building Sump and Condensate Damineralizer Backwash Effluents enter Circulating Water via the sumps and ponds of the Industrial ' and Sanitary, Waste System, Steam Generator Blowdown Effluent may be released to the Circulating Water either directly in the Condenser outfiow. (the normal flow path)'or in the first hours following startup via' the Industrial and Sanitary Waste System for chemical reasons. i For the sake of clarity,'two mutually exclusive setpoint calculation processes are outlined below. Section 2.1.'4.1 is tote used wher'ever Steam i Generator Clowdown is being released directly to-the Circulating Water in the Condenser outflow, which is the normal mode. Section 2.1'.4.2 is to be used whenever Steam Generator Blo~wdown is being released to the g_' industrial and Sanitary Waste System, or diverted to the Nuclear Blowdown Processing System, both of which are alternate modes. Each section covers d all four monitors (RM L3, RM L8, RM L10 and RM L11). NOTE: When Circulating Water is unavailable for effluent dilution, releases d containing activity above LLD should.be discouraged via pathways- -i which lead to it. Steam Generator Blowdown's'hould be diverted to ' I the Nuclear Blowdown Processing System.= Condensate Deminera-lizer Backwash may be diverted to the Turbine Building Sump or not l released. ; Turbine Building Sump effluent should be diverted to the I Excess Liquid Waste Processing System. (These steps are.to keep the calculated dose to individuals-as. low-as reasonably achievable.) y Furthermore, sampling and: analysis of the Industrial and Sanitary j Waste System is to be initiated and the measured concentrations i used in the dose calculations of Section 2.2. hj ODCM, V. C. Summer, SCE&G: Revision 13 (June,1990) 1 2.0 16 1

i

i e, i 2.1.4.1 Steam Generator C, owdown Effluent Direct to Circulatino O Water (Normal Mode)- 1 Equation (1) is again used to assure that effluents are in compliance with the aforementioned specification: {

F+ A

-The available dilution water flow (F,,) is dependent upon R the mode of operation of the Circulating Water System. Any change in this value will be accounted for in a recalculation of equation (1). The Steam Generator Blowdown flow rate (f,,) and the Steam j Generator Blowdown monitor setpoints (c and c,) are set to meet u 3 the condition of equation (1). The Turbin' e Building Sump _ and Condensate Dimeneralizer effluents will be limited to concentra-tions less than MPC without claiming dilution (see below). There-fore,it is not necessary to consider their flow rates or concentrations in determining the required dilution and monitor setpoints for Steam Generator Blowdown. l For conservatism, the Turbine Building Sump and Conden-J sate Darineralizer Backwash monitor setpoints (c and c ) will claim ( 3 3 no anuuun from the Circulating "fater, and will be set at the appli-cable concentration limit. That is. r i cbC (15) The Turbine Building Sump monitor, RM L8, alarms.and terminates release upon exceeding the monitor setpoint (c ). The i discharge can then be manually diverted to the.Euess Waste Processing System. RM L11, the Condensate Demineralizer Backwash I monitor, alarms and terminates release upon exceeding the monitor i setpoint (c ). The discharge may then be manually diverted to the i o Turbine Building Sump or simply delayed. .( ODCM,V.C. Summer,SCE&G: Revision 13 (June,1990) i 2.0 17.

-0 l RM L3, the first monitor in the Steam Generator Blowdown discharge pathway, alarms and terminates release of the stream. The discharge is then automatically diverted to the Nuclear Blowdown i Processing System. RM L10, the last monitor in the Steam Generator Blowdown discharge pathway, alarms and terminates the release. Thus, RM L10 is redundant to RM L3 and the setpoint (c,) will be 3 determined in the same manner as RM L3 (e,). s The method by which the monitor setpoints are i determined is as follows: i 1) The isotopic concentrations for any release source to be or being released are obtained from th'e sum of the measured concentrations as determined in Table 1.14. Equation (2)is again employed for this calculation: 1 C, = [ C, + C, + C, + C, + Cf n a where: EC, = the sum of the measured concentrations as determined by the antlysis of the waste s mple,in uCi/ml. {C, = the sum of the concentrations C, of each measured i gamma emitting r.uclide observed by gamma ray spectroscopy of the waste sample,in uCi/ml. 1 C, the measured concentration C, of alpha emitting = j composite sample, in uCi/ml. l C, the measured concentrations of 5 49 and Sr 90 in = y liquid waste as determined by analysis of the most recent available quarterly composite sample,in uCi/ml. l g. ODCM,V.C. Summer,SCE&G: Revision 13 (June,1990) l 2.0 18

p C, the measured cancentration of H 3 in liquid waste 'O = determined by analysis of the monthly composite sample,in uCi/ml. C, the measured concentration of Fe 55 in liquid waste as = determined by analysis of the most recent availaule i quarterly composite sample, in uCi/ml. Isotopic concentrations for the Steam Generator Blowdown System effluent, the Turbine Building Sump Effluent, and the Condensate Demineralizer Backwash effluent may be ~ calculated using equation (2). 2) Once isotopic concentrations for the Steam Generator } Blowdown have been determined, these values are used to calculate a Dilution Factor, DF, which is the ratio of the total dilution flow rate to effluent stream flow rate required to assure that the limiting concentrations of 10CFR, Part 20, Appendix B, Table ll, Column 2 are met at the point of discharge. ] c DF= 1 3 + SF (16) i C C C C C

MPC, AIPC,

AIPC, h!PC,

hfPC, S

where: C, C,, C, C,, C,, and C,; measured concentrations as = defined in Step 1. Terms C, C,, Cp and C, will be included in the calculation as appropriate. ? 'l C' V the sum of the ratios of the measured concen- = 7 MFC, tration of nuclide i to its limiting value MPC the Steam Generator Blowdown effluent.,for O i ODCM, V. C. Summer, SCE&G: Revision 13 (June,1990) I 2.0 19 i 1. i i i

.e M PC, ~ = MPC,, MPC,, MPC,, MPC,, and MPC, are limiting concentrations of the appropriate radionuclide from 10CFR, Part 20, Appendix B. Table 11, Column 2 limits. For gamma emitting noble gas radionuclides, MPC,is to be set equal to 2 x 10 8 uCi/mt. SF the same generic term as used in Section 2,1.2, = Step 2. 0.5 = 3) The maximum permissible effluent discharge flow rate, f,, may now be calculated for a release from the Steam Generator Blowdown. for V, > > f, ('05 f=- = a p s a F,, Dilution flow rate for use in effluent monitor setpoint i = calculations, based on 90 percent of the expected flow rate of the Circulating Water System during the time of release and corrected for any recirculated activity: C Fde = (0.91 F II ~ .I' d g s a where: F, = the flow rate of the Circulating Water System during the time of the release. F, should normally fall between 1.78 X 105 and 5.34 X 105 gpm when the plant is operating and should be 5000 gpm when the plant is shutdown and the circulating Water jockey pump is operating. O ODCM, V. C. Summer, SCE&G: Revision 13 (June,1990) 2.0 20

p C,, = the concentration of radionuclide i,in uti/ml,in the Circulating Water System intake, (that is, in the Monticello Reservoir). Inclusion of this term will correct for possible long term buildup of radioactivity due to recirculation and for the presence of activity recently released to the Monticello Reservoir by plant activities. For expected discharges of liquid wastes, the summa-tion will be much less than 1.0 and can be ignored (Reference 6). f,, Flow rate of Steam Generator Blowdown discharge. = 4 (This value normally will be either zero,if no release is to be conducted, or the maximum rated capacity of the discharge pump (250 gpm), if a release is to be conducted.) Note that the equation is valid only for DF > 1; for DF 51, the effluent concentration meets the limits of 10CFR 20 without dilution as well as being in compliance with the conservatism imposed by the Safety Factor in Step 2, if f,2 f,, releases may be made as planned. Because F,;is a normally very large compared to the maximum discharge-pump capacity of the Steam Generator Blowdown System, it is extremely unlikely that f, < f,,. However, if a situation should arise such that f, < f,,, steps must be taken to assure that equation (1) is satisfied prior to making the release. These steps may include diverting Steam. Generator Blowdown to the Nuclear Blowdown Processing System or decreasing the effluent flow rate. When new candidate flow rates are chosen, the calculations above should be repeated to verify that they combine to form an acceptable release. If they do, the ODCM, V. C. Summer, SCE&G: Revision 13 (June,1990) 2.0 21 l -.~..,-,~,,,__.,v. ,.,.y ..,,.,,.9,,_..., ,,....,.,.,,.-<w., ,., +,

1 I establishment of flow rate monitor setpoints should proceed as follows in Step 4.- If they do.ot provide an j acceptable release, the choice of candidate flow rates must i be repeated until an acceptable set is identified. S 4) The dilution flow rate setpoint for minimum flow rate, F, is established at 90 percent of the expected available dilution i l flow rate: ~ t l F = (0.9) (F,) (20) Flow rate rnonitor setpoints for the Steam Generator Blowdown effluent :;tream sha'll be set at the selected discharge pump rate (normally the maximum discharge pump rate) f, chosen in Step 3 above. o 5) The Steam Generator Monitor setpoints may be specified l based on the values of E Ci, F,and f which were specified to l provide compliance with the limits of 10CFR 20, Appendix B, Table 11, Column 2. The monitor response is primarily to gamma radiation, therefore, the actual setpoint is based on E C. The monitor setpoint in cpm which corresponds to g the calculated value c is taken from the monit or calibration-graph. (See NOTE, page 2.014.). The setpo nt concentra. I tion, c, is determined as follows: es1C,xn (21) l r B = f/f,, (22) l If B s: 1,- Calculate c and determine the maximum value-for the actual monitor setpoint (cpm) from the monitor calibration graph. -i ODCM, V. C. Summer, SCE&G: Revision 13 (June,1990) i i 2.0 22

_-_____---------,w,--,

.--,-sw ,-s a ~ w-w, -. ,,,e-- ,,n-, n y

i if B < 1, No release may be made. Reevaluate the alternatives presented in step 3. I P NOTE: If the calculated setpoint value is near actual concentrations being released or planned for release, it may be impractical to set the monitor I alarm at this value. In this case a new setpoint may [ be calculated following the remedial methodology. j presented in steps 3 and 4 for the case f, < f,,. 6) The Turbine Building Sump and Condensate Demineralizer t Backwash monitor setpoints are to be established l independently of each other and without crediting j dilution. They are to be based on the measured rallio-f nuclide concentrations of the effluent s*. ream and are to i - ensure c.ompliance with the limits of 10CFR 20, Appendix Bi Table il, Column 2 prior to dischatge. f ( For each effluent stream, a concentration factor CF must be l calculated, measuring the nearness of approach of the \\ undiluted waste stream to the specified limiting condition of the Maximum Permissible Conceritration. That is, C l CF = T + SF (23) ~~ MPC, I C CF = T-T + SF (24) i T - MFC t a C' CF3= 1 3 + SF (25) yp 4 4 where: 4 O 1 ODC.M, V. C. Summer, SCE&G: Revision 13 (June,1990) I 2.0 23 3 \\ I

m l C 1 the sum of the ratios of the measured concentration of = ypc r nuclide i to its limiting value MPC, for the Turbine i e Building Sump effluent. C V the sum of the measured concentration of nuclide i(in = -- MPC D liquid only) to its limiting value MPC, for the Condensate j Demineralizer Backwash effluent. CF, the concentration factor for the Turbine Building Sump = Effluent.- CF the concentration factor for the Condensate Demin- = o eralizer Backwash Effluent. SF the generic engineering safety factor used in Section i = 2.1.2, Step 2. i 0.5 = 9, ifCFt 1, calculate c and determine the actual monitor setpoint (cpm) from the calibration curve. If CF > 1 no release may be made via this path. The-release must either be delayed or diverted for' additional processing. Because of spurious i alarms, these remedial steps may be required if the monitor setpoints are only near the actual concentrations being released. With'in the limits of the conditions stated abov( the specific mon:1.cr setpoint concentrations for the two Steam Generator Blowdown monitors RM L3 and RM 1.10 and the-atpoint concentrations for RM L8 and RM L11 may now be calculated. Because they are primarily sens'tive to gamma { q ODCM, V. C. Summer, SCE&G: Revision 13 (June,1990) .2.0 24 i /

_y s

- [

s i 4 1 l radiation, their setpoints v.,ll be based on the concen-trations of gamma emitting radionuclides as followsi 2.1.4.1.1 For RM L3, Steam Generator Blowdown Dis-charoe initial monitor, and for RM L10, Steam Generator Blowdown Discharoa final monitor: % o'% 5 1 C, I 8) s (26) s j 1 the isotopic concentration of the Steam Generator = 5 C, Blowdown effluent as obtained from the sum of the s measured concentrations determined by the analysis s J required in ODCM Table 1.14,in uCi/ml.

See GENERAL h'OTE under 2.1.

1 1 2.1.4.1.2 For RM L8, Turbine Buildino Sumo Discharoe Monitor: I 1 C, r + CFr (27)- e5 r r sC The gamma isotopic concentration of the Turbine Building = -a r Sump effluent as obtained from the sum of the measured j 8 concentrations determined by the analysis required in ODCM Table 1.14,in uCi/ml. CFT = The Turbine Building Sump Effluent Concentration Factor l from equation (24). I

See GENERAL NOTE under 2.1.

2.1.4.1.3. For RM L11, Condensate Demineralizer Backwash l Discharoe Monitor: 't> ' 1 C, t>,- CF,, {gg) s C) i ODCM, V. C. Summer, SCE&G: Revision 13 (June,1990) i 2.0 25 i

t ~ The gamma isotopic concentration of the Condensate G4 = 1 C, tained from the sum of the measu(red concentrationsDemineralizer Bac o determined by the analysis required ODCM Table 1.14,in uCi/ml. CFo = The Condensate Demineralizer Backwash Effluent Concen-tration Factor from equation (25). 'See GENERAL NOTE under 2.1. 2.1.4.2 Steam Generator Blowdown Effluent Not Directiv to Circu-latina Water (Alternate Mode) Equation (15) is again used to assure that effluents are in compliance with the aforementioned specification before dilution in the receiving water: cGC Because dilution is not considered in'th' e setpoint calculation, it is not necessary to calculate maximum permissible discharge flow rates or anticipated available dilution flow rate. The functions of the four monitors whose setpoine.s are to be established are described in Section 2.1.4.1 above. The method for the deterrnination is as follows: 1) If a release is found to be permissible, flow rate monitors for the active effluent streams (Steam Generator Blowdown f,, Turbir.e Building Sump - f, and u Condensate Demineralizer - f ) may have their setpoints u established at any operationally convenient value. Since ~ 10CFR 20 is to be complied with before dilution, the flow rate of dischargesisirrelevant. g1 ODCM, V. C. Summer, SCE&G: Revision 13 (June,1990)- . s 2.0-26 t at

s. 2) The Concentration Factor of equations (23) - (25) is again used to ensure the permissibility of the release: C CF = 1 + SF 1 4 C CF

ypq T + SF T

G CF = Afpc, o + # p [C CF = + SF 3 3 (29) i e in which all terms are defined in subsection 1.1.3.1 an subscripts T, D, and S refer respectively to the Turbine Building Sump Effluent, the Condensate Demineralizer Backwash Effluent, and the Steam Generator Blowdown Effluent. If CF G 1, calculate c and determine the actual monitor setpoint (cpm) from tne calibr':tn curve, if CF > 1, no release may be made via this path. The release must either be delayed or diverted for additional processing. Because of spurious alarms, these remedial steps may be required if the monitor setpoints are only near the actual concentrations being released. Within the above limitation, setpoint concentrations may now be calculated for the four effluent monitors. Because they are primarily sensitive to gamma radiation, their setpoints will be based on the concentrations of gamma emitting radionuclides as follows: O ODCM, V. C. Summer, SCE&G: Revision 13 (June,1990) 2.0 27

t 2.1.4.2.1 For RM L8 Turbine Buildino Sumo Discharce Monitor (usino caustion (27) above): 1 C,

CF C5 7

r r s where: The gamma isotopic concentration of the Turs c hilding = VC Sump effluent as obtained from the sum of the memeted 7 .r concentrations determined by the analysis required in ODCM Table 1.14,in uCi/ml. CF, = The Turbine Building Sump Effluent Contentration Factor from equation (24).

See GENERAL NOTE under 2.1.

2.1.4.2.2 For RM L11. Condensate Demineralizer Backwash Discharae Monitor (usina ecuation (28) above): 1 C, n + CF cs u y e where: the gamma isotopic concentration of the Condensate Demin- = eralizer Backwash effluent (including solids) as obtained from 1 C, u the sum of the measured concentrations determined by the a analysis required in ODCM Table 1.14,in uCi/ml. CF = The Condensate Demineralizer Backwash Effluent Concen-o tration Factor from equation (25).

See GENERAL NOTE under 2.1.

O ODCM, V. C. Summer, SCE&G: Revision 13 (June,1990) 2.0 28 l

~ - - 1 1 4 2) The Concentration Fector of equations (23) - (25) is again ) used to ensure the permissibility of the release: [C', - SF CF u 1 C CF

1 r
SI r

ypc e e ) C CF = 1 o + SI 3 yp. 4 I C ( CF = T + SF (29) s b. -- MPC, in which all terms are defined in subsection 1.1.3.1 and i subscripts T, D, and S refer respectively to the Turbine l Building Sump Effluent, the Condensate Demineralizer } Backwash Effluent, and the Steam Generator Blowdown Effluent. i if CF G 1, calculate c and determine the actual monitor setoolnt (cpm) from the calibration curve. If CF > 1, no release may be made via this path. The release must either be delayed or diverted for additional processing.- Because of spurious alarms, these remedial steps may be required if the monitor setpoints are only near the actual concentrations being released. l 1 l Within the abow umitation, setpoint concentrations may now be calculated for the four effluent monitors. Because they are primarily sensitive to gamma radiation, their setpoints will be based on the concentrations of gamma emitting radionuclides as follows: 1 1. ODCM, V. C. Summer, SCE&G: Revision 13 (June,1990) i l 2.0 27 i )

i. l 2.1.4.2.1 & RM L8 Turbine Buildina Sump Discharae Monitor (usino eaustion (27) above) l 1 C, C5

CI 7

r 'l r e l where: a 1 The gamma isotopic concentration of the Turbine Building = Y C Sump effluent as obtained from the sum of the measured 7'# concentrations determined b ODCM Table 1.14, in uCi/ml. y the analysis required in i CF, = The Turbine Building Sump Effluent Concentration Factor-l from equation (24). j

See GENERAL NOTE under 2.1.

] 2.1.4.2.2 For RM.L11. Condensate Demineralizer Backwash Discharae Monitor (usino eaustion (28) above): 5 C, c5 r CV a o y I where: ' i t the gamma isotopic concentration of the Condensate Demin- = 1 C, eralize. Backwash effluent (including solids) as obtained from o the sum of the measured concentrations determined by the e analysis required in ODCM Table 1.1-4,in uCi/ml. j CF, = The Condensate Demineralizer Backwash Effluent Concen-tration Factor from equation (25). l l

See GENERAL NOTE under 2.1.

l ODCM,V.C. Summer, SCE&G: Revision 13 (June,1990) 2.0 28 i --w-4-.- p te, -,.3, ..-c.--.- ,,,-,..e w

1 Figure 2.1-1 Example Liquid Effluent Monitor Calibration Curve f k e- .4

: {-.'

i 55- ,.,$ e5,. A 4 A b-

... - ".: D.. *f..y - a.. pfik

.7 m x. gr h gy g,%.M C6.k y .}., ,.p s h x. ,? W .g , ;% "' E "'. ...t.';_.. :. Q _.,.. [~ t-g 1 u. -- ', - i.4 1t .[. ;. u l, ) 9 e a 0 -. - :., y +.-a i w-.-.yy+- c-. gM{"-~-... +,a e

n

-,s. g.;i ~ y,][ 'h p - .g, QfgM O' o y =.~5.. ' {... ' t. : ! e gg.--- .+.. -. g I' 10 ~ -^ '. -. .d l ^ v gg g4 a gp ; --t b7 Ak,,g kJ , p4 = -"6' ? , Q b 'k I 'n' ?.M- '..... _ $ v. i., h... . -.. ^ 4 Mima -' _' r' p.(, @.J.. .s.. #. .= c s . -... s j... -,. .....' r c.. O n e ' ' y. l N:v. uY n.-. 4.:. J:g. q c,- . e h5'.- .e =..,. -. .. Y'.. ...e 3-m f. 9 _ _' j. N Q f ,..t.. ig O k;N + -. 5 v - - ~4~ 4m..-v.mrm =n; a==:-m'u wY-w~ ' r.:...m x'd.-% m :wr. ~ - C

m..

' ' ' ' " ~ ~ 3 ~:..'- ,y e . y.. '.ma- + g:m :- s aa -. 1 - ~ - ~ --<.s _.m. ._.C ,. #._.# s,, je m A Q j.. ..,g n 3 4 . "4f e-g. p a m ; 4e - ". e l.W e.-g...,. ...y t .6

3 t

p.....j.... (* 4 a sn n.'.m.1, n:su.y. ; + y .g a# t m:a w ~ r%e.-- - - ~.. ;, '. c. :::m:.. : n y. y

e...~

7. c ' +}'m -., --- r-...--M-.7..,.-.. 5. .+ u --e.. _v :.y. ' - ' ~ ' ' ' M 1 ~- ny,.. _ jM-.~._.1 -

..u n.m

$.gg( p._. _ y. _ f '. :y ;'. ;.. ;._ _-.. [ C 'l ef ..m - g .... jg. g

O AO - ~'

'. -O' Y, p., .,Y'Oi5 .~ E.N : a-H. j..,,, - ~,,; #. gg g ;w. LG.k 4 m. lm w.im5r n-pWepM% '.e.3 mi ' 3,C ,tas # -s h g;.p.w+-5-4. ir j 4. 2:. (,, * .h 41 e., > e.:,, e n'y* f,/ --A'- 4. d.- - 4 t-\\ w. ..s. ...1 ME - L aA, T 4 D,.J. ).r.,,.t,.. # t ..L*4 g o., - 4 o [* I ' w..a. n, .so 9...- ' - 1 Q,m--,. +., 4 lr, .._,,.y M_.. w..m3%y vw e . 4 .g,,'a .,, '. +

~.- : v 9, y rJ%

. pg '; y y ' - ;_;. *. . w.4 --~ aw .w m..k. %........ M..m_ uzwa.% % =yW k i w =? M %:: ' ' N..= 3 y o. O 3. m s-.- r-- ,-g .-p e h E [ { pg..,, - 'gy " - 9.**--f>?- 8,,__ eN a' i

'.p'-

y, # ,e$- ', .,,y e +.-. a _u. .g...... s w.. ..w _.- x- -. 9 .'*s t . y s lL. --+.g ,- m j %' t C.es,,, (UCi/ml) TNs o g.... .g u%s M.,. ~ -- .,' GE.EQ"- E qgyg4.-mm. -@gg%cg..&.4._Wak M. ar ;a+d4; M.mbM";gy_y1 r -.W J:h 4 ..L g.4. g.ggppW ::. '.. +Wesw

..

' -r.

in 1.. J ' ' ' '.3 l $, &. % M *..,s.7 % y-l: * + E %.? -ds.-.. nk-& 0 m.c+ww.0'hd:$s:h 4Ekha:-- N e s,, 3 b h. g, 1. + - , m...,t.. w, g.4.:.:.-9_ $. ,,g,g -~. re., m e. w.,. a, g-,_, ;M.... g- , a,.._ -,s._4_ t p ._3_; ;,,.. g 3-.g- ." ' i , an -. o: .a g ,.. - ~.. .s ..g

4 '.-

. a ..s ', i _ h.4 y.h.. ,.e :

4, UT'f3 ggy ' - " ^ :w 4.y L ?.-4. ;f m,

~. _ 4 f) q. ._ _ 3 i ': 4.._.h.:4 g.n . y .a4= a W y:(b.'b; 77 n -~ 2 =:. .-.q.gpx-g.=.- . :. 'n pp:g_& - -. --.~ ~ ~ - > +. .g - --:. g) 0 ..i,' . ' ~. ' ' i...Q~i '..."? '. '..... i ~ f 4 10* 10 10 10 1:g Count Rate (cpm) 9 ODCM, V. C. Summer. SCE&G: Revision 13 (June,1990) 2.0 30

~ - - t g s. l l, l 2.1.4.2.3 For RM L3, Steam Generator Blowdown Dis-charoe initial monitor, and RML 10, Steam Generator '{ Blowdown Discharae final monitor: + l i 1 C, + CF s; % '>r r33 3 s (30) s where: i l Vc The isoto sic concentration of the Steam Generator Blow- = 78 . down eff uent as obtained from the sum of the measured concentrations determined b ODCM Table 1.1-4,in uti/ml. y the analysis required in .The Steam Generator Blowdown Effluent concentration I CF = 5 Factor from equation (29). j

See GENERAL NOTE under 2.1.

j O 1 ) i i I I t l i I j t q i ODCM, V. C. Summer SCE&G: Revision 13 (June,1990) 2.0 29 I-l [- l L

,s l 2.2 Qgig (alculation For Liauid Effluents The method of this section is to be used in all cases for calculating doses to individuals from routine liquid effluents. Four notes at the end of ^ the section confirm the values which certain parameters are to be assigned in some special cases: 2.2.1 Liauid Effluent Dose Calculation Parameters Term Definition Section of initial Use A,, ' the site related ingestion dose commitment 2.2.2 = factor to the total body or any organ t, for each identified principal gamma and beta emitter listed in Table 2.2 3 in mrem ml per ~ br pCi. B F, Bioaccumulation Factor for nuclide i,in fish, 2.2.2 = pCi/Kg per pCi/l, from Table 2.21. C,, the average concentration of radionuclide, 2.2.2 = i,in undiluted liquid effluent during time period At, from any liquid released,in uCi/ml. D F,, a dose conversion factor for nuclide, i, for 2.2.2 = adults in preselected organ, t,in mrem /pci found in Table 2.2 2. D' the cumulative dose commitment to the = 2.2.2 total body or any organ, t, from the liquid effluents for the total time period, I.itt in mrem (Ref.1). ~j D* Dilution Factor from the near field area = 2.2.2 within one quarter mile of the release points to the potable water intake for adult water consumption; for V. C. Summer, D, = 1. F, the near field average dilution factor for C,, = 2.2.2 during any liquid effluent release.- K 1.14 x 105, units conversion factor = = 2.2.2 (106 pCi/uci)(103 ml/l) + 8760 hr/yr 1 0 ODCM, V C. Summer, SCE&G: Revision 13 (June,1990) i I 2.0 31 i l 1

Liouid Effluent Dose Calculation Parameters (continued) Term Definition Section of i nitiaI Use the length (in hours) of a time period over 2.2.2 Atk = which concentrations and flow rates are averaged for dose calculations. 21 kg/yr, fish consumption (adult) 2.2.2 U, = (Reference 3). 730 kglyr, water consumption (adult) 2.2.2 U, = (Reference 3). applicable near field dilution factor when 2.2.2 2 = no additional dilution is to be considered; Z = 1. 2.2.2 Methodology The dose contribution from all radionuclides identified in liquid effluents released to unrestricted areas is calculated using the following expression: S

1.

A,, \\_ %%F4 (31) .i A,,

K,((U,/D ) + U,BF,) DF (32) n FL

(averaae undiluted liould waste flow) (33) (average flow from the discharge structure) (Z) NOTE 1: If radioactivity in the Monticello Reservcir (C,,) becomes > the LLD specified in ODCM, Table 1.14, that concentration must be included in the Dose determination. For this part of the dose calculation, F, = 1 and at, = the entire time period for which the dose is being calculated. NOTE 2: During periods when the Circulating Water Pumps are not in operation, the possibility of leakage of activity from the Industrial Water System will be accounted for as follows. Sampling of the liquid in the Sanitary and Industrial Waste O ODCM, V. C. Summer, SCE&G: Revision 13 (June,1990) 2.0 32-

s.

System will be initiated, and the measured concentrations of l radionuclides will be used in the dose calculations with F, = 1 and A t, = the entire time period for which the dose is being calculated. NOTE 3: During periods when the Circulating Water Pumps are in operation, any releases to the Sanitary and Iredustrial Waste System gig to be credited with dilution in Circulating Water for dose calculation purposes, even though such dilution was not . claimed in the setpoiat calculation. When taken in Onion with the note above, this procedure results in some overestimation of dose to the population because discharges made to the Sanitary and Industrial Waste System just before loss of Circulating Water will be counted twice in the dose calculatior process. NOTE 4: If radioactivity in the Service Water becomes > LLD as determined by the analysis required by ODCM, Table 1.1-4, that concentrati<>n must be included in the Dose determination. Fr,r this part of the dose calculation, F, = 1 l and A t, = the en;% time since the last Service Water sample l was taken. I l l l i I i 'l l O ODCM, V. C. Summer, SCE&G:' Revision 13 (June,1990) i 2.0 33 i I f . ~. . ~.

TABLE 2.2-1 BIOACCUMULATION FACTORS * (pCi/kg per pCi/ liter) ELEMENT FRESHWATER FISH H 9.0E 01 C 4.6E 03 F 1.0E 01 Na 1.0E 02 P 1.0E 05 Cr 2.0E 02 Mn 4.0E 02 Fe 1.0E 02 .Co 5.0E 01 - Ni 1.0E 02 Cu 5.0E 01 2n 2.0E 03 Br 4.2E 02 Rb 2.0E 03 Sr 3.0E 01 Y 2.5E 01 2r 3.3E 00 Nb 3.0E 04 Mo 1.0E 01 Tc 15E 01 Ru 1.0E 01 Rh 1.0E 01 Sb 1.0E 00 Te 4.0E 02 1 1.5E 01 Cs 2.0E 03 Ba 4.0E 00 La 2.5E 01 Ce ' 1.0E 00 l '? Pr 2.5E 01 Nd 2.5E 01 W 1.2E 03 Np 1.0E 01 ' Values in Table 2.21 are taken from Reference 3. Table A.1. O ODCM, V. C. Summer, SCE&G: Revision 13 (June,1990) 2.0 34

i TABLE 2.2 2 Page 1 of 2 ADULT INGESTION DOSE FACTOR 5* (mrem /pCiingested) NUCLlDE BONE LIVER T. BODY THYROID KIDNEY' LUNG GILLI H3 NO DATA 1.05E 07 1.05 E-07 1.05E 07 1.05E 07 1.05E 07 1.05E 07 C-14 2.84 E-06 5.6SE 07 5.68E 07 5.68E 07 5.68E 07 5.68E-07 5.68E-07 F 18 6.24E 07 NO DATA 6.92E 08 NO DATA NO DATA NO DATA 1.85E 08 NA 24 1.70E 06 1.70E 06 1.70E 06 1.70E 06 1.70E 06 1.07E 06 1.70E 06 P 32 1.93E 04 1.20E 05 7.46E 06 NO DATA NO DATA NO DATA 2.17E 05 i CR 51 NO DATA NO DATA 2.66E 09

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 FE 59 4.34E 06 1.02E 05 3.91E 06 NO DATA NO DATA 2.85E 06 3.40E 05 CO 57 NO DATA 1.15E 06 1.87E 06 NO DATA NO DATA NO DATA 3.92E 06 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 NI63 1.30E 04 9.01E 06 4.36E 06 NO DATA NO DATA NO DATA 1.88E 06 NI65 5.28E 07 6.86E 08 3.13E 08 NO DATA NO DATA NO DATA 1.74E 06 CU 64 NO DATA 8:33E 08 3.91E 08 NO DATA

' 2.10E 07 NO DATA 7.10E 06 ZN 65 4.84E 06 1.54E 05 6.76E 06 NO DATA 1.03E 05 NO DATA 9.70E 06 2N 69 1.03E 08 1.97E 08 1.37E 09 NO DATA 1.28E 08 NO DATA 2.96E 09 BR 83 NO DATA NO DATA 4.02E 08 NO DATA NO DATA NO DATA 5.79E 08 BR84 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 LT E 24" 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 SR 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 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 0? 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 l 2R 95 3.04E 08 9.75E 09 6.60E 09 NO DATA 1.53E 08 NO DATA 3.09E 05 2R 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 05 MO 99 NO DATA 4.31E 06 8.20E 07 NO DATA 9.76E 06 NO DATA 9.99E-06

Values in Table 2.2 2 are taken from Reference 3, Table E 11.

r "Less than E 24. ODCM, V.C. Summer, SCES G: Revision 13 (June 1990) 2.0 35

l TABl.E 2.2 2 (continued) Page 2 of 2 9-NUCLlDE BONE LIVER T. BODY THYROID KIDNEY. LUNG Gl LLI TC 99M 2.47E 10 6.98E 10 8.89E 09 NO DATA 1.06E-08 3 42E 10 4.13 E-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 07 NO DATA 2.16E 05 RU 105 1.54E 08 NO DATA 6.08E 07 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 07 NO DATA 6.04E 05 5B 124 2.80E 06 5.29E 08 1.11E 06 6.79E 09 NO DATA 2.18E 06 7.95E 05 58 125 1.79E 06 2.00E 08 1.82E 07 1.82E 09 NO DATA 1.38E 06 1.97E 05 TE 125M 2.69E 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 08 8.15E 08 4.48E 07 NO DATA 8.68E 06 TE 129M 1.15E 05 4.29E 06 1.82E 06 3.95E 06 4.80E 05 NO DATA S.79E 05 TE-129 3.14E 08 1.18E 08 7.65E 09 2.41E 08 1.32E 07 NO DATA 2.37E 08 l TE 131M 1.73E 06 8.46E 07 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 2.79E 09 TE 132 2.52E 08 1.63E 06 1.53E 06 1.80E 06 1.57E 05 NO DATA 7.71E 05 l130 7.56E 06 2.23E 06 8.80E 07 1.89E-04 3.48E 06 NO DATA 1.92E 06 I131 4.16E 06 5.95E 06 3.41E 06 1.95E 03 1.02E 05 NO DATA 1.57E 06 l l132 2.03E 07 5.43E 07 1.90E 07 1.90E 05 8.65E 07 NO DATA 1.02E 07 l133 1.42E vo 2.47E 06 7.53E 07 3.63E 04 4.31E 06 NO DATA 2.22E-06 l134 1.06E 07 2.88E 07 1.03E 07 4.99E 06 4.58E 07 NO DATA 2.51E 10 1135 4.43E 07 1.16E 06 4.28E 07 7.65E 05 1.86E 06 NO DATA 1.31E 06 C5134 6.22E 05 1.48E 04 1.21E 04 NO DATA 4.79E-05 1.59E 05 2.59E 06 C5136 6.51E 06 2.57E 05 1.85E 05 NO DATA 1.43E 05 1.96E 06 2.92E 06 C5137 7.97E 05 1.09E 04 7.14E 05 NO DATA 3.70E 05 1.23E 05 2.11E 06 C5138 5.52E 08 1.09E 07 5.40E 08 NO DATA 8.01E 08 7.91E 09 4.65E-13 B A 139 9.70E 08 6.91E 11 2.84E 09 NO DATA 6.46E 11 3.92E 11 1,72E 07 B A 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 B A 142 2.13E 08 2.19E 11 1.34E 09 NO DATA 1.85E 11 1.24E 1T 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 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 2.13 E-09 NO DATA 4.03E 05 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 W 197 1.03E 07 8.61E 08 3.01E 08 NO DATA NO DATA NO DATA 2.82E 05 NP 239 1.19E 09 1.17E 10 6.45 E-11 NO DATA 3.65E 10 NO DATA 2.40E 05 ODCM, V.C. Summer, SCE&G: Revmon 13 (June 1990) 2.0 36 1 ]

l TABLE 2.2 3 SITE RELATED INGESTION DOSE COMMITMENT FACTOR, A

ii

. O (mrem /hr per Ci/ml) u Page l of 2 NUCUDE SONE LIVER T. BODY THYROID KIDNEY LUNG GI LLI l H3 NO DATA 8.96E + 00 8.96E + 00 8.96E + 00 8.96E + 00 8.96E + 00 8.96E + 00 C 14 3.15E + 04 6.30E + 03 6.30E + 03 6.30E + 03 6.30E + 03 6.30E + 03 6.30E + 03 1 F 18 6.69F + 01 NO DATA 7.42E + 00 NO DATA NO DATA NO DATA 1.980 + 00 NA 24 5.48E + 02 5.48E + O2 5.48E + O2 5.48E + 02 5.48E + O2 5.48E + 02 5.48E + O2 P 32 4.62E + 07 2.87E + 06 1.79E + 06 NO DATA NO DATA NO DATA 5.20E + 06 CR 51 NO DATA NO DATA 1.49E + 00 8.94E 01 3.29E 01 1.98E + 00 3.76E + O2 MN 54 NO DAT A 4.76E + 03 9.08E + 02 NO DATA 1.42E + 03 NO DATA 1.46E + 04 MN 56 NO DATA 1.20E + 02 2.12E + 01 NO DATA 1.52E + O2 NO DATA 3.82E + 03 FE 55 8.87E + 02 6.13E + O2 1.43E + O2 NO DATA NO DATA 3.42E + 02 3.52E + O2 FE 59 1.40E + 03 3.29E + 03 1.26E + 03 NO DATA NO DATA 9.19E + O2 1.10E + 04 CO 57 NO DATA 2.33E + 02 3.79E + O2 NO DATA NO DATA NO DATA 7.95E + 02 _C_O 58 NO DATA 1.51E + O2 3.39E + 02 NO DATA NO DATA NO D ATA 3.06E + 03 CO 60 NO DAT A 4.34E + O2 9.58E + 02 NO DATA NO DATA NO DATA 8.16E + 03 NI63 4.19E + 04 2.91E + 03 1.41E + 03 NO DATA NO DATA NO DATA 6.07E + O2 NI65 1.70E + O2 2.21E + 01 1.01E + 01 NO DATA NO DATA NO DATA 5.61E + O2 CU 64 NO DATA 1.69E + 01 7.93E + 00 NO DATA 4.26E + 01 NO DATA 1.44E + 03 2N 65 2.36E + 04 7.50E + 04 3.39E + 04 NO DATA 5.02E + 04 NO D ATA 4.73E + 04 ZN 69 5.02E + 01 9.60E + 01 6.67E + 00 NO DATA 6.24E + 01 NO DATA 1.44E + 01 BR 83 NO DATA NO DATA 4.38E + 01 NO DATA NO DATA NO DATA 6.30E + 01 l BR 84 NO DATA NO DATA 5.67E + 01 NO DATA NO DATA NO DATA 4.45E 04 i BR 85 NO DATA NO DATA 2.33E + 00 NO DATA NO DATA NO DATA 1.09E - 15 RB 86 NO DATA 1.03E + 05 4.79E + 04 NO DATA NO DATA NO DATA 2.03E + 04 RB 88 NO DATA 2.95E + 02 1.56E + O2 NO DATA NO DATA NO DATA 4.07E 09 RB 89 NO DATA 1.95E + 02 1.37E + O2 NO DATA NO DATA NO DATA 1.13 E - 11 SR 89 4.78E + 04 NO DATA 137E + 03 NO DATA NO DATA NO DATA 7.66E + 03 SR 90 1.18E + 06 NO DATA 2.88E + 05 NO DATA NO DATA NO D ATA 3.48E + 04 SR 91 8.79E + 02 NO DATA 3.55E + 01 NO DATA NO DATA NO DATA 4.19E + 03 SR-92 3.33E + O2 NO DATA 1.44E + 01 NO DATA NO DATA NO DATA 6.60E t 03 i l Y 90 1.380 + 00 NO DATA 3.69E - 02 NO DATA NO DATA NO DATA 1.46E + 04 Y 91M 1.30E 02 NO DATA 5.04E 04 NO DATA NO DATA NO DATA 3.82E 02 Y 91 2.02E + 01 NO DATA 5.39E 01 NO DATA NO DATA NO DATA 1.11E + 04 Y 92 1.21E 01 NO DATA 3.53E 03 NO DATA NO DATA NO DATA 2.12E + 03 Y 93 3.83 E - 01 NO DATA 1.06E 02 NO DATA NO DATA NO DATA 1.22E + 04 ZR 95 2.77E + 00 8.88E - 01 6.01E 01 NO DATA 1.39E + 00 NO DATA 2.82E + 03 ZR 97 1.53 E - 01 3.09E - 02 1.41 E - 02 NO DATA 4.67E 02 NO DATA 9.57E + 03 NB 95 4.47E + 02 2.49E + 02 1.34E + 02 NO DATA 2.46E + 02 NO DATA 1.51E + 06 l

Calculated using equation (32) and Tables 2.21 and 2.2 2.

ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) 2.0 37

a TABLE 2.2 3 SITE RELATED INGESTION i DOSE COMMITMENT FACTOR, Au* j i (mrem /hr per pCi/ml) Page 2 of 2 4 NUCLIDE BONE LIVER T. BODY THYROID l KIDNEY l LUNG GILLI j MO 99 NO DATA 4.62E + O2 8.79E + 01 NO DATA 115E + 03 NO DATA 1.07E + 03 TC 99M 2.94E 02 8.32E 02 1.06E + 00 NO DATA 1.26E + 00 4.07E - 02 4.92E + 01 TC 101 3.03E 02 4.36E - 02 4.28E 01 NO DATA 7.85 E - 01 2.23E 02 1.31E 13 RU 103 1.98E + 01 NO DATA 8.54E 01 NO DATA 7.57E + 01 NO DATA 2.31E + 03 RU 105 1.65E + 00 NO DATA 6.52E 01 NO DATA 2.13E + 01 NO DATA 1.01E + 03 RU 106 2.95E + O2 NO DATA 3.73E + 01 NO DATA 5.69E + 02 NO DATA 1.91 E + 04 AG 110M 1.42E + 01 1.31E + 01 7.80E + 00 NO DATA 2.58E + 01 NO DATA 5.36E + 03 SB 124 2.40E + O2 4.53E + 00 9.50E + 01 5.81E 01 NO DATA 1.87E + O2 6.81E + 03 5B 125 1.53E + O2 1.7 I E + 00 3.65E + 01 1.56E 01 NO DATA 1.18E + O2 1.69E + 03 ~TE 125M 2.79E + 03 1.01E + 03 3.74E + O2 8.39E + O2 1.13E + 04 NO DATA 1.11 E + 04 TE 127M 7.05E + 03 2.52E + 03 8.59E + 02 1.80E + 03 2.86E + 04 NO D ATA 2.36E + 04 _ T E-127 1.14E + O2 4.11 E + 01 2.48E + 01 8.48E + 01 4.66E + O2 NO DATA 9.03E + 03 TE 129M 1.20E + 04 4.47E + 03 1.89E + 03 4.11E + 03 5.00E + 04 NO DATA 6.03E + 04 TE 129 3.27E + 01 1.23E + 01 7.96E + 00 2.51 E + 01 1.37E + O2 NO DATA 2.47E + 01 TE 131M 1.88E + 03 8.81 E + O2 7.34E + O2 1.39E + 01 8.92E + 03 NO DATA 8.74E 4 04 TE 131 2.05E + 01 8.57E + 00 6.47E + 00 1.69E + 01 8.98E + 01 NO DATA 2.90E + 00 TE 132 2.62E + 03 1.70E + 03 1.59E + 03 1.87E + 03 1.63E + 04 NO DATA 8.02E + 04 l130-9.01E + 01 2.66E + O2 1.05E + O2 2.25E + 04 4.15E + O2 NO DATA 2.29E + O2 I l131 4.96E + 02 7.09E + O2 4.06E + 02 2.32E + 05 1.22E + 03 NO DATA 1.87E + O2 h 1132 2.42E + 01 6.47E + 01 2.26E + 01 2.16E + 03 1.03E + O2 NO DATA 1.22E + 01 I133 1.69E + O2 2.94E + 02 8.97E + 01 4.32E + 04 5.13E + 02 NO DATA 2.64E + 02 1-134 1.26E + 01 3.43E + 01 1.23E + 01 5.94E + 02 5.46E + 01 NO DATA 2.99E - 02 1135 5.28E + 01 1.38E + 02 5.10E + 01 9.11E + 03 2.22E + 02 NO DATA 1.56E + 02 C5134 3.03E + 05 7.21 E + 05 5.89E + 05 NO DATA 2.33E + 05 7.75E + 04 1.26E + 04 C5136 3.17E + 04 1.25E + 05 9.01E + 04 NO DATA 6.97E + 04 9.55E + 03 1.42E + 04 C5137 3.88E + 05 5.31E + 05 3.48E + 05 NO DATA 1.88E + 05 5.99E + 04 1.03E + 04 C5138 2.69E + 02 5.31E + O2 2.63E + O2 NO DATA 3.90E + O2 3.85E + 01 2.27E - 03 BA 139 9.00E + 00 6.41 E - 03 2.64E 01 NO DATA 5.99E-03 3.64E 03 1.60E + 01 8A 140 1.88E + 03 2.37E + 00 1.23E e 02 NO DATA 8.05E - 01 1.35E + 00 3.88E + 03 B A 141 4.27E + 00 3.30E - 03 1.48E - 01 NO DATA 3.07E 03 1.87E 03 2.06E - 09 B A * -.2_ 1.98E + 00 2.03 E - 03 1.24E - 01 NO DATA 1.72E 03 1.15E 03 2.78E - 18 1 6.A 140 3.58E - 01 1.80E 01 4.76E 02 NO DATA NO DATA NO DATA 1.32E + 04 l LA 142 1.83E 02 8.33E 03 2.07E - 03 NO DATA NO DATA NO DATA 6.08E + 01 CE 141 8.01E 01 5.42E 01 6.15E 02 NO DATA 2.52E - 01 NO DATA 2.07E + 03 CE 143 1.41 E - 01 1.04E + 02 1.16E - 02 NO DATA 4.60E 02 NO DATA 3.90E + 03 _ C_E-144 4.18E + 01 1.77E + 01 2.24E + 00 NO DATA 1.04E + 01 NO DATA 1.41 E + 04 PR 143 1.32E + 00 5.28E - 01 6.52 E - 02 NO DATA 3.05E 01 NO DATA 5.77E + 03 PR 144 4.31E 03 1.79E 03 2.19E 04 NO DATA 1.01 E - 03 NO DATA 6.19E 10 ND 147 9.00E - 01 1.04E + 00 6.22 E - 02 NO DATA 6.08E - 01 NO DATA 4.99E + 03 W 187 3.04E + 02 2.55E + 02 8.90E + 01 NO DATA NO DATA NO DATA 8.34E + 04 NP 239 1.28E 01 1.25E 02 6.91E 03 NO DATA 3.91 E - 02 NO DATA 2.57E + 03 0 ODCM, V.C. Summer,5CE 8 G: Revision 13 (June 1990) 2.0-38 .-~. ----.-..

UQUID RADWASTE TREATMENT SYSTEM h l FIGURE 2.21 35g li j lji gi i n d i. i: .I r; j

O

~ + 1 e 1 IS "~1 \\ l i g- =, = 1 gk g! I lg ,lE h ys ,s[ t_ 11 o .I -i g 1 I I ri I i-

r i.

is a a i l J :: l ^ Ig [ p*

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i n o e i I l L--* i .......+ j +.. j l l l

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I r-h j E-Jj j i -i re-, ~ a i i i ~T i =i si L-i i II II I If ll l I,l el In g! }f i i il il I il vi is i -s -s rs hrs ,1 4. T r O u - u a. 4 I I E-D fg lgl lI lI i i r' r =_ t t 1 T 1r 7 5 I .I FI i .i -g.g El I! 8 s 1 f o i 5 1r i t rg.g f. F-I r 21 E-J l' ,, ~ ,,y j r-E! l I, int i a...: i i si l1 i 'i ,nt! I-I l I r i=. e i, e M........... 'T, t a E I I II 1111 i !4 i I: I'ril 115Ilji! d;j![ jig 9 11 i jiii jj !jiijllij! li k { O' ODCM, V.C. Summer, SCE&G; Revision 13 (June 1990) 2039 i; ,...,_,,...---.--,-.--~,--c~ ~ ~ - ' - - - - - - - -

m ap. A4emem + e.AwwNw----' 447..whaw-r r w a m a.h4 a.. 4m+ pay wam,.m._msm44.w-_,-mumnha.s_ma,wa 4.e.m mm enc _m.E.m=.M-4--ma- - We m Ja.245 se n. 3 em.apm.-m4w.w dsd..J.-We e g. at e.e,.e.M me m .e @ y. 1 e J B d 3 l i a b a 1 J 5 1 9 9 4 l e i 1 J . m ,.,,. ~,.

.p i 1 3.0 GASEOUS EFFLUENT ~ 31 Gaseous Effluent Monitor Setooints The calculated setpoint values will be regarded as upper j , bounds for the actual setpoint adjustments. That is, setpoint adjustments [ are not required to be performed if the ' existing setpoint level corresponds to a lower count rate than the calculated value. Setpoints may be established at values lower than the calculated values, if desired. Calculated monitor setpoints may be added to the ambient background count rate. 1 3.1.1 Gaseous Effluent Monitor Setooint Calculation Parameters Section of 1 Term Definition Initial Use C" count rate of a station vent monitor (3.1.2) = corresponding to grab sample radio-t nuclide concentrations, Xiv, as detesmined from the monitor's calibration curve,in cpm. b c'= the count rate of the monitor on vent v (3.1.4) ( corresponding to X,' uti/cc of Xe 133,in cpm. count rate of the gas decay system (3.1.3) c = monitor for measured radionuclide concentrations corrected to discharge pressure, in cpm. c' the count rate of the waste gas decay (3.1.4) = system monitor corresponding to the total noble gas concentration in cpm. ~ D = limiting dose rate to th'e skin (3000 (3.1.2) s3 mrem / year). D = limiting dose rate to the total body (3.1.2) 3 (500 mrem / year).- t F = the flow rate in vent v (cusec) (3.1.2) (1 cc/sec = 0.002119 cfm). f, the maximum permissible waste gas (3.1.3) = discharge rate, based on the actual radionuclide mix and skin dose rate (cusec). i O i ODCM, V. C. Summer, SCE&G: Revision 13 (June 1990) i 3.0 1 I

l Section of Term Definition Initial Use h-f, the maximum permissible waste gas (3.1.3) = discharge rate, based on the actual radionuclide mix and total body dose rate (cc/sec). f, the maximum permissible waste gas (3.1.3) = discharge rate, the lesser of f, and f,(cc/sec). f,' the conservative maximum per-(3.1.4). = missible waste gas discharge rate based on Kr-89 skin dose rate (cc/sec). 1,' the conservative maximum permissible (3.1.4) = waste gas discharge rate based on Kr-89 total body dose rate (cc/sec). K, total body' dose factor due to gamma (3.1.2) = emissions rom isotope i(mrem / year per uCi/m3) from Table 3.1 1. K,.,, = total body dose factor for Kr 89, the most (3.1.3) restrictive isotope from Table 3.1-1 (mrem /yr per uCi/m ). 3 L' Skin dose factor due to beta emissions (3.1.2) = from isotope i(mrem /yr per uCi/m ) 3 from Table 3.1 1. L,,,,,= Skin dose f actor for Kr-89, the most restrictive (3.1.3) isotope, from Table 3.1 1 (mrem /yr per uCi/m ). 3 i M, air dose factor due to gamma emissions (3.1.2) = from isotope i (mrad /yr per uCi/m ) from 3 Table 3.1 1. M,,,, s air dose factor for Kr 89, the most restrictive (3.1.3) isotope, from Table 3.1-1 (mradlyr per uCi/m ). 3 l R, count rate per mrem /yr to the skin. (3.1.2) j = R, count rate per mrem /yr to the total (3.1.2) I = body. 1 R,' conservative count rate per mrem to (3.1.4) = the skin (Xe 133 detection, Kr 89 dose). conservative count rate per mrem to (3.1.4) -] R,' = the total body (Xe 133 detection, Kr 89 dose). ODCM, V. C. Summer, SCE&G: Revision 13 (June 1990). I 3.0 2 h

l. ~~__ q .c t4 ~ .l Section of Term Definition initial Use ~ . 5, ' = count rate of the waste gas decay (3.1.3) system noble gas monitor at the alarm setpoint, in cpm. S". count rate of a station vent noble gas (3.1.2)' = monitor at the alarm setpoint, in cpm. 5,, count rate of the containment purtg (3.1.2) noble gas monitor at the alarm setpoit.(, in cpm. S,, count rate of the plant vent noble gas (3.1.2)' = monitor at the alarm setpoint, in cpm.- c 'the concentration of noble ~ gas radio- -(3.1.3) = nuci!Je ni% a waste gas decay tank, as corerteMo the pressure of the dis-j chatp sream at the point of its flow . measuaement in uCi/cc. 1' X,, = the measured concentration of noble - (3.1.2) g65 radionuclide iin the.last grab sample analyzed for vent v in uCi/cc.' X,' the total noble gas decay tank, gas concentration in a waste. (3.1.4).- = O~ as corrected to the pressure of the discharge stream at the point of its flow measurement in uCi/cc. j X" = a concentration of Xe 133 choscn to be in the (3.1.4)- 1 operating range of the monitor on vent vin uti/ct. '1 E= the highest annual average relative concentra-(3.1.2) I tion in any sector, at the site boundary in sec/m3 1.1 = mrem skin dose per marad air dose (3.1.2). 0.25 = the safety factor applied to each of the two -(3.1.2) vent noble gas monitors (plant vent and contain-ment purge) to assure that the sum of the releases has a combined safety factor of 0.5 which allows a 100 percent margin for cumula~ti~ve uncertainties of measurements. i i i ODCM, V. C. Summer, SCE&G: Revision 13 (June 1990) a 3.0 3 1

3 ), a-- TABLE 3.1 1 / DOSE FACTORS FOR EXPOSURE TO A SEMI INFINITE CLOUD O'r NOBLE GASES,* Nuclide - vBodv***gil D Skin * * *(Lil. v Air * *(Mill D Air * *(Nil'- ~ Kr-85m 1.17 E + 03 * * *

1.46E + 03 1.23E + 03 1.97E + 03 i Kr-85 1.61 E + 01 1.34E + 03 1.72 E + 01 '

1.95E + 03 '- Kr 87 5.92E + 03 9.73E + 03

6.17E + 03 1.03 E '+ 04 -

j-Kr 88 1.47E + 04 2.37E + 03 1.52E + 04 2.53E + 03 ] Kr-89 1.66E,04 1.01 E + 04 1,73E + 04 1.06E + 04 1 Kr 90 1.56E + 04 7.29E + 03 ~ 1.63E + 04 7.83E + 03 - Xe 131m 9.15E + 01 4.76E + 02 - 1.56E + O2 - 1.11 E + 03 : Xe 133m 2.51E + 02 - 934E + 02 3.27E + 02 1.48E + 031 Xe 133-2.94E + 02 - 3.06E + O2-3.53E + O2 1.05E + 03 Xe-13 fe, 3.12E + 03 7.11E + 02 3.36E + 03 7.39E + 02 Xe 135 1.81E + 03 1.86E + 03 1.92E + 03 - 2.46E + 03 .h Xe-137 1.42E + 03 1.22E + 04' 1.51 E + 03 1.27E + 04 ' Xe 138 8.83E + 03 4.13E + 03 9.21E + 03 - 4.75E ~+ 03 - Ar 41 8.84E + 03 2.69E + 03 - 9.30E + 03-3.28E + 03 -

Values taken from Reference 3, Table B-1 l
mrad m3 pCi yr

- 3 a

*
mrem m3

- pCi yr

* *
1.17E + 03 =' 'i 17 x 103 91 ODCM, V. C. Summer, SCE&G:- Revision 13 (June 1990)

} i 3.0 4 )

e .~ 4' . C01+ 3.1.2 Station Vent Noble Gas Monitors (RM A3 and RM-A4)- For the purpose of implementation of_ section 1.2.1 of the ODCM, the alarm setpoint level for the station vent noble gas monitors will be calculated as follows: - S, count rate of the plant vent noble gas monitor (= 5,, for - ~ = RM.A3) or the containment puige noble gas monitor (=~ 5,, for RM A4) at the alarm setpoint level. 0.25 x R, x D (34) re . 6 the lesser of - or 0.25 x R, x D (35) 33 0.2 5 = the safety factor applied to each of the two vent noble . gas monitors (plant vent and containment purge) to-assure.that the sum of the-releases has a combined safety factor of 15 which allows a 100 percent margin for cumulative uncertainties of measuremen,ts.' i O' D,, =' Dose rate limit to the total body of an individual - 500 mrem /yr = R, count rate per mrem /yr to the total bodyi =- C, / ({RTC) x F, x E K,X,,) - '(36) = i Dss 1 Dose rate limit to the skin'of the body of an individual = in ari unrestricted area, 3000 mrem / year. t. =: ' Rs count rate per_ mrem /yr to the skin. = C, + [WQ x F, x T (L, + 1 1 M ) X,,]- -(37) = i I X,, .the measured concentration of noble gas radionuclide'i = in the last grab sample analyzed for vent v,'pci/ml. (For the plant vent, grab samples are taken at least ODCM, V. C. Summer, SCE&G: Revision 13 (June 1990) 3.0 5 = -- a..

y monthly. For the 6" and 36" containment purge lines,. the sample is taken just prior tathe release and also monthly,if the release is continuous.) f Fl . the flow rate in vent v cc/sec. (1 cc/sec =' O.002119 cfm) ~ = I i. C, - count rate,-in cpm, of the monitor on station vent v = corresponding to grab sample noble gas concentra t tions, X,,, as determined from the monitor's calibration curve. (Initi. calibration curves of the type shown in Figure 2.1-1 have been determined conservatively from o families of response curves supplied by the monitor , manufacturers.. As releases occur, a historical'correla-tion will be prepared and. placed in-service: when sufficient data are accumulated.) X/Q =. the highest annual average relative concentration in. any sector, at the site boundary. = 5.3 x-104 3 sec/m in the SE sector

K, total body dose factor due to gamma emissions from-

= isotope i (mrem /yr per pCi/m ) from Table 3.1 1.' 3 L, = skin dose factor due to beta emissions from isotope i (mrem /yr per pCi/m ) from Table 3.1-1. 3 1.1 = mrem sWn dose per mrad air doc.e M, = air dose factor due to gam.na' emissions from isotope i (mradlyr oer pCi/m ) from Table 3.1 1. 3 Reference 4, Section 11.3.8 states that this is the annual average' relative - dispersion at the point on.the exclusion boundary where highest concentra-tions may be expected. Oi ODCM, V. C. Summer, SCE&G:- Revision 13 (June 1990) 3.0-6 ]

i j... q NOTE: At plant startups when no grab sample analysis is available for the: m. continuous releases, the Alternate Methodology of Section 3.1.4'must l be used. l. L 3.1.3 Waste Gas Decav System Monitor (RM A10) h The permissible conditions for discharge through thc. waste gas decay ~ system monitor (RM A10) will be calculated in a manner similar to that for the d plant vent noble gas monitor.. In the case of the waste gas system, however, the . discharge flow rate is continuously controllableL by valve HCV 014 and permissible release conditions are~ therefore defined in terms of both flow rate and concentration. Therefore, RM A10 is used only to insure that a repre- [ sentative sample was obtained. For operational convenience, (to prevent spurious alarms due' to - fluctuations in background) the setpoint level will be established'at 1.5 times the measured waste concentration. The maximum permissible flow rate will be set on the same basis but include the engineering safety' factor of 0.5. The RM A10 setpoint level 5, is defined as: j S.< 1.5c (38) o where: 1 = count rate in CPM of the. waste gas decay system monitor c corresponding _to the measured concentration (taken from the monitor calibration curves).' The maximum permissible waste gas flow rate f; (cc/sec) is calculated - from the maximum permissible dose rates at the site boundary according to: f, ;e the lesser of f, or f, (39) i I ODCM, V. C. Summer, SCE&G: Revision 13 (June 1990) 3.0 7 ,y i d-

m' f., 3 = 1 ,hA f, the maximum permissible discharge rate based on total body dose = rate. = - l 0.25 x D,, / [RTQ x 1.5,E X, K,] ~ (40)-' = a f, = : the maximum permissible' discharge rate based on skin dose rate. 0.25 x D / [@ x 1;5 I X;(i., + 1.1M,)]' 41) -i = 33 s i Xid =~ the concentration of noble gas radionuclide iin the waste gas decay tank'whose contents are to be discharged, as corrected i to the' pressure of the discharge stream at.the pointof the .j ~ flow rate measurement. The maximum discharge pressure as; . governed by the diaphragm valve,7896,is 30 psia. I i NOTE:~ The factor of 1.5 in the denominators of equations (40) and (41) places f, on the same basis as S. o When a discharge is to be conducted, valve HCV 014 is to be opened until (a) the waste. gas discharge flow rate reaches 0.9 x f, or (b) the count rate-4 of the plant vent noble gas monitor RM-A3 approaches its setpoint, whichever - h of the above conditions is reached first. 1 When no discharges are being;made from the. Waste' Gas Decay System, the RM A10 setpoint should be established as near background 'as practical to prevent spurious alarms and yet alarm in the event of an inadvertent release. 3.1.4 Alternative Methodotoov for Establishina Conservative S' tpoints 1 e A more. conservative Lsetpoint may; be-calculated :to minimize requirements for adjustment of the monitor as follows: For a plant vent: ' R,' conservative count rate per mrem /yr to the total body (Xe-133-i -=. detection, Kr-89 doses i ODCM, V. C. Summer, SCE&G: Revision 13 (June 1990) 1 3.0-8

y

(

C,' + [X7Q x K,,, x X,' x F,],-. (42)

1

= g V-where: p X,' - a concentration of Xe 133 chosen to be in the operating- = range of the monitor on vent v, pCi/cc.' the count rate lin CPM of the-monitor on vent = v i s; = corresponding to X,'pCi/cc of Xe 133. i K,,,,. - = total body dose factor for_ Kr 89, the. most restrictive g isotope from Table 3.1-1. R,'. count rate per mrem /yr to the skin. = C,' ' + [E x (L,,,,, + 1.1 M,,.,,) x X,'x F,)

(43)

= where: L,,.,, = skin dose factor for Kr-89, the most restrictive isotope l from Table 3.1 1. M,.., = air dose factor.for Kr-89, the most' restrictive ~ isotope. x from Table 3.1-1. For the waste gas decay system: f,' the conservative maximum permissible discharge rate based on Kr-89 = tota'. body dose rate. = 0.25 x D,, + QUQ x 1.5 x X;'x K,,,,) .(44) g I l,' the conservative maximum permissible discharge rate based on L r 89 = K skin dose rate. v .t = 0.25 x D + DUD x 1.5 x X,'x (L,.,, + 1.1 M,.,,)] (45) 33 g i l } l \\ ODCM, V. C. Summer, SCE&G: Revision 13 (June 1990) L 3.0 9 . I- , l, .s...

s . x -[ ..)' X,' the total concentration of noble gas radionuclides in the = waste gas decay tank whose contents' are to be - discharged, as corrected to the ' pressure of the discharge . stream at the point of the flow measurement. c = cour.t rate in cpm of the waste gas decay system monitor q co' responding to X,' pCi/cc of Kr 85.. ~;

\\

r i 'l', i i 1 i 4 i ODCM, V. C. Summer, SCE&G: Revision 13 (June 1990) 3.0 10

l 1 l Figure 3.1-1 Example Noble Gas Momtor Calibration Curve 1 1 g a-7g,, 7 r _p....

-. ~

4 ..- d . e- - m ..a ggg..c.w w ga p m(. ? , - maw.4g_m.g. qu,.4 y.. 4,, 4- .y

M N i. ;.:..

3.-.,. _ r l 9,3ge 9 :m ggg7g......., -.u.:,.-.1 .k. ".3g yg;.g:gn + ~ . - +. .. n m..; _. ...,..t a. W? 4 =mn-. .i;..up; '.~ +x ._w : - = -- LO 3 $.'m di. m O' ~ '? % ' L.' N=M2.. "H"Ha*.g@~~= W.. _...~~*C J 7"-P~~T. ' ' ' '.'"'.~l'.,' " ' - - ' ~ ' s i.6"d ' ' f; 'i -s1:1y% l' T' n C 1-- -. 2= O s -.=.= p.. hk8 s y g 4 .' ' 4 - v .: 9 < wiry... 9 g g m. Q >. p g,.,A. y s.,a.'.:.g e' y,_'q u y y n 2 +, 1...+..,,i<*.y 4 E P m .w .r s t.f- ..,.w 7.-. J. y # t.. .g _ _ gj g_.,1 y N4 ' '- -s.. ( l 4C. ?"'* '" y v.44gi. %.; ' y............. --yap g__'g;., q ?-s - L M, 5.14m-"-{ %#~:

--- = =-.- c T-4 WN2mWdd

-m- ,0.a, l- -- e .n., .nw : ,77MY-MSM My@@E5EadggjLW.EhdHEE-Diid&iERT c ,5.. 3 < myd da. 5 e ate t, ga :s'tu a s.4.

st'.

..?, ' T.. '. '1.' .1,,'.. '(,' 'y' ' " ' ' ' 3-t y_'. j t. m. e*8'* R g. "v. ,,_4 ,j 'Q y ggy -; .w._.. 3 ~ AY d ... 9 .g 7 ~. 1 i " u Mb -M-ri.s.A A-g y.. Ao M :,.- y < L.M ' ; }~2., ' %f -{,@g[ "I.p M 4.J.C.l "#" l* P ? Q ~'3*N^r < Nb.. i.., I& $n -~K NB$ ih-A h

a 4

q .... ~.. ..v .q e.:,... < <- a i ~.;,,xx : - ~ k w+=a=en.a n. _ w. c -.w, u ;.,.m,. ". =ty 4 ....m. t - 3 ;.; M. ;.n' 7 %_

7.. mm:c

...______._;.-.... m..yggy - g= ym... w _;_.__m_-.... 1,. d - y. se.m.. + ~ r j

4.. * ' 4..y@.&. j 7 ;4h.+. g{ "

_u. - -MTW.uw- .,_h M 4,3 3pf u g. e _;g g 3 'y. ~'. .( 0 + e O 1V- ?; ~ -.g n ..J.- .,s.. x. .',.,...,._,,.,1.g. g.m,q ^ 4,-.. w. g. gy s. Qf 5%.i~ ~"%.@;W _ g _ 32}, 2 .5 4 4,; .~ . p - 91W WM-MCQgyg' pr%.w.W t = - - ._-.....7. ,M.c hx-e.w .. w h w [Q.. eg m.m. _. ~. .), m, e, -

m -..y e:

1 - g"- .--.s.--".~%=u.- ,; 7 ,g-4.g, c.._; 1 ---f c. ?, f.... g, __,2 y.;..: l ' ' * '"- p -. .,..,C **""l b,Y~&-s M '.,. 9(llyl) "~G.-.. ? a t' 1 - 4 ' Yd ^

L.g".

W. ! k.

c-

-, n;; ;.,_.d....,

JJ L ' r. i.- .:m -.js. gg;rm. z: - ~ G. a +

4 e 'r ' ', & c ~..>.. -. -

~,.s . 4g. q.., . 4.. . ' w Z. ,y., .S h r-CT-4 .e 1-. ...u..._s.. JGS ' C J z M4M.f ~ b. w.33b,., 1jbMWMngh@$6_.%.;4 .r.'-_, ...,., -Q 6MW%,.._ 2Mi= ' ' 3 v y ..p-w: I,[ NiG M D I~N 6 Y W Y $4 __ k N h -- h h $ b S [-, A. e s. r o ('b,,f : a 1,d[._;.-1kh; .dj-j M[. [ g w.- , MM6 f (q 'dgy J.-%,.y ' h 5 c-. 'ig ..t s..' . 1 %C 3,c. ....a. _,, a 3.x # -.- 97. 7..t.,q _ %;9;d--s-,a i 21d"W

.. y n

.. r =.. r - e.m.+_.w: wm:.--.m...:y-. -

c: w V'

w- = . =., ;.. -= ~ .y a =.... -= . -o ..v... n _--- -R;M n 0 2 3 LO 10 10 10' 5 e 10 ig Count Rate (cpm) ODCM, V. C. Summer. SCE&G: Revision 13 (June 1990) 3.0-11

3.2 Dose Ca!culation for Gaseous Effluent - i j 3.2.1 - Gaseous Effluent Dose Calculation Parameters Section of Term Definition initial Use D = average organ dose rate in the curr'snt (3.2.2.2) o year (mrem /yr). D, dose to an individual from radioiodine (3.2.3.2) = and radionuclides in particalete form and radionuclides (other than noble - gases), with half lives greater than eight days (mrem). D, average skin dose rate in current year (3.2.2.1) = (mrem / year). -L O current total body dose rate (mrem /yr) (3.2.21). t = Op air dose'due to beta emissions from (3.2.3.1) = noble gas radionuclides (mrad). D = g air dose dut to gamma emissions from (3.2.3.1)- l -i noble gas radionuclides (mrad). i Ki total booy dose factor due to gamma emissions (3.2.2.1)- = from isotrspe i (mrem / year per uCi/m ) from - 3 Table 3.1-1. Li skin 00:4 factor due to beta emissim from-(3.2.2.1) i = noble as radionuclide i(mradlyr y pCi/m )- 3 from ble3.1-1. i M' air dose factor due to gamma emissions from (3.2.2.1) = noble gas radionuclide i(mradlyr per pCi/m ) 3 from Table 3.1-1. N, air dose factor due to beta emissions (3.2.3.1) a = from noble gas radionuclide i(mrad per uCi/m3) < rom Table 3.1-1. P, i dose parameter for radionuclide'i, (3.2.2.2)- = (mrem /yr per uCi/m ) for inhalation, 3 from Table 3.1-1. Section of Term Definition initial Use d, = the release rate of noble gas radio-(3.2.2.1) ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990)' 3.0 12

by nuclide i as determined from the concentrations

'I measured in the analysisof the appropriates sample required by Table 1.2-3 (pCi/sec). I = the release rate of non. noble gas radionuclide i (3.2.2.2) as determined from the concentrations measured in the analysis of the appropriate sample required by' Table 1.2 3 (pCi/sec). O' ~ cumulative release of noble gas radionuclide i-(3.2.3.1) = over the period of interest (pCi). j ~ 1 Q,' cumulative release of non noble gas radionuclide i _(3.2.3.2) =- (required by ODCM Specification 1.2.4.1) over the - period of interest (pCi). R dose factor for radion'uclide i and pathway j, (3.2.3.2)' i = (mremlyr per uCi/m ) or (m mrem /yr per pCi/sec) 3 2 _ fromTables 3.2 2 through 3.2 6.- W'= relative dispersion for the maximum exposed (3.2.3.2) ~ individual, as appropriate for his exposure pathway j and radionuclide i. 1 E' for inhalation and all tritium pathways - = 2.2 X 10 6 sec/m3 O = .l B7Q' for other pathways and non tritium radionuclides ' = 8.4 X 10 9m.2: '1 RTO = the highest annual average relative concentration. '(3.2.2.1)L in any sector, at the site boundary.in sec/m3 '3 3 3.17 x 10 8 = the fraction of one year per one second ' (3.2.3.1) J } T 7 ll O ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) '3.0 13

3.2.2 Unrestricted Area Boundary Dose- .O; 3.2.2,1 For the purpose of implementation of s'ection 1.2.2,1a,- ) (6 500 mrem / year _ total body,6 3000 mrem / year ' skin) the dose at the: unrestricted area-boundary l due to noble gases s' all be-g calculated as follows: l= t -1 D, = - current total body dose rate (mrem /yr); = E6 y K,k (46) I D,- = _ current skin dose rate (mrem /yr) X/Q ? (L + 1.1M,)k (47) = c i where: i 6, ' the release rate of noble gas radionuclide _i: as- = I ' determined from the concentration measured in-the analysis'of the appropriate. sample required 1 by Tab le 1~.2 3 (pCi/sec.),

j EQ the highest annualJaverage relative concen-

= tration in any sector, at the site boundary'(for q value, see Section 3.1;2).' d

t Ki, Li, and Mi will.be selected for the. appropriate d

radionuclide from Table 3.1-1-- 1 1 l [ 3.2.2.'2 For the purpose of implementation of.section 1.2.2.1.b (L 1500 mrem /yr - any organ) organ doses'due to radioiodines and all radioactive materials in particulate form and radionuclides (other ~j than noble gases) with half lives greater than eight days, will be .f - calculated as follows: D, current organ dose rate (mrem /yr)' = ? E P,3,' (48) '4 = i where: 1 ODCM u.C. Summer, SCE&G: Revision 13 (June 1990) i -l 3.0 14 i

+ 1 -.. = ~.X/Q. = the-highest annual average relative concentration in any sector, at the site boundary ) (for value, see Section 3.1.2) -t l P, dose parameter for radionuclide i, (mrem /yr per = 3 pCi/m ) for inhalation, from Table 3.1 1. 1 ( - d,' = the release rate of non noble gas radionuclide i as : determined from the concentrations measured in I the analysis of the appropriate sample required. by Table 1.2 3 (pci/sec). 3.2.3 Unrestricted Area Dose to Individual 3.2.3.1 For the purpose of implementation of section 1.2.3.1 l (Calendar quarter: L 5 mrad' y and L 10 mradip, Calendar year ~ G 10 mrad - y and n 20 mrad p) and section 1.2.5.1 (air dose averaged over 31 days: L.O.2 mrad. y and L 0.4 mrad.- ),the air dose in unrestricted areas shall be determined as follows: Dy air; dose due to gamma emissions-from noble gas. = radionuclide i(mrad) - l -3.17 x 10 8j M,WO Q, '(49). =- 1 7 where: 3.17 x 10 8 = the fraction of one year per one second k = cumulative rel' ease of noble gas. radionuclide;i over the period of interest (pCi). I l l ..l l ' ~ ODCM, V.C. Summer, SCE&G: Revision 13 (June 100) i 3.0 15

i

- ~ Dp .= air due to beta emissions from noble gas radionuclide-4 i(mrad). ?.17 x 10 8 E N ED 6l (50) 0 s.- 4

where,

_Ni air dose factor due to beta emission fre.n noble = gas radionuclide i (mrad per utilm3) from Table 3.1 1. '3.2.3.2 Dose to an individual from radiciodines and radioactive materials in particulate _ form and radionuclides (other than' noble - gases), with half lives greater than eight (8) days (Calendar quarter: 17.5 mrem any organ, Calendar year: := 15 mrem any organ) will be calculated for the purpose of implementation of section 1.2A.1 ~ as follows: 1 D, dose to an individual from radioiodines and radio'--- = nuclides in particulate form, with half lives g'reater than eight days (mrem): 3.17 x 10 8 E R,, W;,' Q,' (51) i = 4 where: W,,' relative concentration or relative deposition for = the maximum exposed individual, as appropriate for exposure pathway j and radionuclide i. r X/Q' for inhalation and all tritium pathways I 2.2 x 10 6 sec/m3 = 4 = l' E6' for other pathways and non-tritium radio nuclides 1 = 8.4 x 10 S m2 (See the' notes to Table ~3.2-7 and 3.2-8 for the origin of - these factors.) i ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) _ 3.0 16 1

i R,, dose factor for radionuclide i and pathway j,. = (mrem /yr per pCi/m ) or (m mrem /yr per pCi/sec) 3 2 from Table 3.2 2. { 1 Q' Cumulative release of non noble gas radionuclide = i (required by ODCM 5pecification 1.2.4.1) over f the period of interest (pCi), j 3.2.3.3 -For the purpose of initial assessments of the impact of unplanned gaseous releases, dose: calculations for the critical 'i receptor in each affected sector may be performed using section; q 3.2.3.1 and section 3.23.2 s.quations as follows: (1) For each location, X/Q' and D/Q' will be calculated according to 1 the methods of Se6 tion 3.3, using the measured meteoro - 4 logical parame.ters for the period of the unplanned release. 1 i (2) The location of the critical receptors and the pathways j which should be analyzed are shown in Table 3.2 7. (For very _ rough - calculations, the annual' aversge X/Q= and -D/Q for each ' receptor are shown in Table 3.2 8.). (3) The R,, for the appropriate exposure' pathways and age groups-will be selected from Tables 3.2 3 through 3.2 6.' R 1 i i ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) q 3.0 17 q

.y. -TABLE 3.21 PATHWAY DOSE FACTORS FOR SECTION 3.2.2.2 (P )* Page 1 of 3 - -{ AGE GROUPL (CHILD) - ISOTOPE INHALATION I H 3 '. - 1.12 5 E + 03. I C 14 3.589E + 04'. 1 NA-24 ' 1.610E + 04-P 32 2.605E + 06 ^ ' CR 51 1.698E + 04 MN 54 1.576E + 06 MN 56 - 1.232E + 05 a FE _ -55 _1.110E + 05 ' FE 59 1.269E + 06 CO 58 1.106E + 06 CO 60 7.067E + 06 - NI-63 8.214E + 05 ' NI65 8.399E + 04 l CU 64 3.670E + 04 2N 65 9.953E + 05 I ZN 69-1.018E + 04: BR 83 4.736E + 02 - E - BR 84 - 5.476E + 02 - 1 BR-85 2.531E + 01 - 4 RB 86 1.983E + 05 RB-88 5.624E + 02 RB 89 3.452E + 02 - SR 89 ' 2.157E + 06 SR 90 1.010E + 08 SR-91 1.739E + 05 - ' 'See note, page 3.0 20 i Onits mrem /yr per pCi/m3 ODCM, V.C. Summer, SCE&G:. Revision 13 (June 1990) h_1 t 3.0 18 1 L -(

,e TABLE 3.21 PATHWAY DOSE FACTORS FOR SECTION 3.2.2.2 (P,) ' Page 2 of 3 ;- AGE GROUP (CHILD) 'lSOTOPE - INHALATION - SR 92 2.424E + 05 Y-90 2.679E + 05 - Y 91M 2.812E + 03 Y 91 2.627E + 06 Y-92 2.390E + 05 Y 93 3.885E + 05 ZR 95

2.231 E + 06 =

ZR 97 3.511E + 05 NB-95 6.14?E + 05 I - MO 99 1.35sE + 05 i TC 99M 4.810E + 03 TC-101 -. 5.846E + O2. RU 103 6.623E + 05 RU 105 9.953E + 04 1 RU 106 1.476E + 07 ~ AG 110M-5.476E + 06 TE-125M 4.773E + 05 j TE-127M c 1.480E + 06 TE 127 - 5.624E + 04 TE 129M 1.761E + 06 'TE 129 2.549E + 04-3 TE-131M 3.078E + 05, I TE-131 2.054E + 03 TE-132 3.774E + 05-I I-130 1.846E + 06

See note, page 3.0 20 1

Units - mrem /yr per pCi/m3 ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) 3.0 19

< zo ' TABLE 3.21 1 \\ f PATHWAY DOSE FACTORS FOR SECTION 3.2.2.2 (P ) j Page 3'of 3 j AGE GROUP (CHILD)-

j ISOTOPE INHALATION -

1131 1.624E + 07 I l132 1.935E + 05 I133 3.848E + 06 1 l134 5.069E + 04-i 1135 7.918E + 05 ' 014E + 06 - } C5134 C5-136 1.709E + 05 I C5137 97b65E + 05 ^ C5138 - 8.399E + 02 BA 139 5.772E + 041 1 B A 140 1.743E + 06 ~ B A 141 2.919E + 03 BA 142 .1.643E + 03 LA 140 2.257E + 05 LA 142 - 7.585E + 04 CE 141 5.439E + 05 l. CE 143 1.273E + 05 I CE-144 1.195E + 07 - PR 143 4.329E + 05 PR 144 - 1.565E + 03 ND 147 3.282E + 05 W 187-9.102E + 04 ' a,. NP 239 6.401 E + 04 -OTE. The P, values of Table 3.21 were calculated acco'rding to the methods of Reference 1, Section-5.2.1, for children. The values used for the various parameters and the origins of those values are given in Table 3.2-9 and its notes. i Units mrem /yr per pCi/m3 ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) 3.0-20 i

TABLE 3.2 2 PATHWAY DOSE FACTORS FOR SECTION 3.2.3.2 (Ri)* O Page 1 of 3 AGE GROUP (CHILD) (N.A.) (CHILD) ~ ISOTOPE INHALATION GROUND Pt.ANE VEGETATION H3 1.125E + 03 (Total Body) 0.000E + 00 (Skin) 3.627E + 03 (Total Body) C 14 3.589E + 04 (Bone) 0.000E + 00 (Skia) 8.894E + 08 (Bone) NA 24. 1.610E + 04(Total Body) 3.33E + 08 (Skin) 3.729E + 05(Total Body) P 32 2.605E + 06 (Bone) 0.000E + 00 (Skin) 3.366E + 09 (Bone) CR 51 1.698E + 04 (Lung) 5.506E + 06 (Skin) 6.213E + 06 (GI LLI) MN 54 1.576E + 06 (Lung)- 1.625E + 09 (Skin) 6.648E + 08 (Liver) MN 56 1.232E + 05 (GI LU) 1.068E + 06 (Skin)- 2.723E + 03 (GI LLI). FE 55 1.110E + 05 (Lung)- 0.000E + 00 (Skin) 8.012E + 08 (Bone) FE 59 1.269E + 06 (Lung) 3.204E + 08 (Skin) 6.693E + 08 (GI LU) CO 58 1 106E + 06 (Lung) 4.464E + 08 (Skin) 3.771E + 08 (GI LU) CO 60 7T067E + 06 (Lung) 2.532E + 10 (Skin) 2.095E + 09 (GI LLI) Ni63 8.214E + 05 (Bone) 0.000E + 00 (Skin) 3.949E + 10 (Bone) NI65 8.399E + 04 (GI LLI) 3.451 E + 05 (Skin) 1.211E + 03 (GI LU) CU 64 3.670E + 04 (GI LU) 6.876E + 05 (Skin) 5.159E + 05 (GI LLI) O 2N 65 9.953E + 05 (Lung) 8.583E + 08 (Skin) 2.164E + 09 (Liver) 2N 69 1.018E + 04 (GI LU) 0.000E + 00 (Skin) 9.893E 04 (GI LLI)' BR 83 4.736E + O2(Total Body) ~ 7.079E + 03 (Skin) 5.369E + 00(Total Body) BR 84 5.476E + 02(Total Body) 2.363E + 05 (Skin) 3.822 E - 11(Total Body) BR-85 2.531 E + 01 (Total Body) 0.000E + 00 (Skin) 0.000E + 00(Total Body) RB 86 1.983E + 05 (Liver) 1.035E + 07 (Skin) 4.584E + 08 (Liver) RB 88 5.624E + 02 (Liver)- 3.779E + 04 (Skin) 4.374E - 22 (Liver) RB 89 3.452E + 02 (Liver) 1.452E + 05 (Skin) 1.642E - 26 (Liver) SR-89 2.157E + 06 (Lung) 2.509E + 04 (Skin) 3.593E + 10 (Bone). SR 90 1.010E + 08 (Bone) 0.000E + 00 (Skin) 1.243E + 12 (Bone) SR 91 1.739E + 05 (GI LU) 2.511E + 06 (Skin) 1.157E + 06 (GI-LU) 1 See note, page 3.0 36 Reference 1, section 5.3.1, page 30, paragraph 1 explains the logic used in selecting thes'e specific pathways. Critical organs for each pathway by nuclide in parentheses. Units - Inhalation and all tritium mrem /yr per pCi/m3 Other pathways for all other radionuclides -m2

mrem /yr per pCi/sec ODCM, V.C. Summer, SCE& G: Revision 13 (June 1990) 3.0 21 l

t ,m.

(; TABLE 3.2 2 (centinutd) l PATHWAY DOSE FACTORS FOR SECTION 3.2.3.2 (Ri) h Page 2 of 3 AGE GROUP (CHILD) (N.AJ (CHILD) i ISOTOPE INHALATION GROUND :ANE VEdETAilON f SR 92 2.424E + 05 (GI-LU) 8.631 E + 01, (Skin) 1.378E + 04 (GI LU) Y-90 2.679E + 05 (GI LU) 5.308E + 03 (Skin) 6.569E + 07 (GI LLI) Y - 91M 2.812E + 03 (Lung) 1.161 E + 05 (Skin) 1.737E 05 (GI LU)- Y 91 2.627E + 06 (Lung) 1.207E + 06 (Skin) 2.484E + 09 (GI LLI) C Y. - 92 2.390E + 05 (GI LU) 2.142E + 05 (Skin) 4.576E + 04 (GI LU). Y. 93 3.885E + 05 (GI LU) 2.534E + 05 (Skin) 4.482E + 06 (GI LLI) 2R 95 2.231E + 06 (Lung) 2.837E + 08 (Skin) 8.843E + 08 (GI LU) a 2R 97 3.511E + 05 (GI LU) 3.445E + 06 (Skin) 1.248E + 07 (GI LU) NB-95 6.142E + 05 (Lung) 1.605E + 08 (Skin) 2.949E + 08 (GI LU) MO 99 1.354E + 05 (Lung) 4.626E + 06(Skin) 1.647E + 07 (Kidney) TC - 99M 4.810E + 03 (GI LLI) 2.109E + 05 (Skin)- 5.255E + 03 (GI LLI) TC 101 5.846E + 02 (Lung) 2.277E + 04 (Skin) 4.123E - 29 (Kidney) RU 103 6.623E + 05 (Lung) 1.265E + 08 (Skin) 3.971E + 08 (GI LU) RU-105 9.953E + 04 (Gi LU) 7.212E + 05 (Skin) 5.981E + 04 (GI LU) RU 106 1.476E + 07 (Lung) 5.049E + 08 (Skin) 1 159E + 10 (GI LU) AG - 110M 5.476E + 06 (Lung) 4.019E + 09 (Skin) 2.581E + 09 (GI LLI) TE - 125M 4.773E + 05 (Lung) 2.128E + 06 (Skin) 3.506E + 08 (8one) t TE 127M 1.480E + 06 (Lung) 1.083E + 05 (Skin) 3.769E + 09 (Kidney) TE 127 5.624E + 04 (GI LU) 3.293E + 03 (Skin) 3.903E + 05 (GI LU)- TE - 129M 1.761E + 06 (Lung) 2.312E + 07 (Skin) 2.430E + 09 (GI LU) TE 129 2.549E + 04 (GI LLI) 3.076E + 04 (Skin) 7.200E - 02 (Gi LU) TE 131M 3.078E + 05 (GI LU) 9.459E + 06 (Skin) 2.163E + 07 (GI LLI) L TE 131 2.054E + 03 (Lung) 3.450E + 07 (Skin). 1.349E.14 (GI LU) [ 7 6-132 3.774E + 05 (Lung) 4.968E + 06(Skin) 3.111E + 07 (GI LU) 1-130 1.846E + 06 (Thyroid) 6.692E + 06 (Skin) 1.371 E + 08 (Thyroid) Units - l Inhalation and all tritium - mrem /yr per pCi/m3 Other pathways for all other radionuclides m2

mrem /yr per pCi/sec ODCM, V.C. Summer, SCE& G: Revision 13 (June 1990) hI 3.0 22 4

i

TABLE 3.2 2 (continue) PATHWAY DOSE FACTORS FOR SECTION 3.2.3.2 (R,) Page 3 of 3 AGE GROUP (CHILD) .- (N.A.) (CHILD). ISOTOPE INHALATION GROUND PLANE VEGETATION l131-1.624E + 07 (Thyroid) 2.089E + 07 (Skin) 4.754E + 10 (Thyroid) 1132 1.935E + 05 (Thyroid) 1.452E + 06 (Skin) 7.314E + 03 (Thyroid) l133 3.848E + 06 (Thyroid) 2.981E + 06 (Skin) 8.113E + 08 (Thyroid) 1134 5.069E + 04 (Thyroid). 5.305E + 05 (Skin) 6.622E 03 (Thyroid) l.135 7.918E + 05 (Thyroid). 2.947E + 06 (Skin) 9.973E + 06 (Thyroid)- C5134 1.014E + 06 (Liver) 8.007E + 09 (Skin) 2.631E + 10 (Liver) 3 C5136 1.709E + 05 (Liver) 1.710E + 08 (Skin) 2.247E + 08 (Liver); C5137 9.065E + 05 (Bone) 1.201E + 10(Skin) 2.392E + 10 (Bone)- C5138 8.399E + 02 (Liver) 4.102E + 05 (Skin) 9.133E -11 (Liver) BA 139 5.772E + 04 (GI-LLI) 1.194E + 05 (Skin) 2.950E + 00 (GI-LLI) 8A 140 1.743E'+ 06 (Lung) 2.346E + 07 (Skin) 2.767E t 08 (Bone) B A 141 2.919E + 03 (Lung) 4.734E + 04 (Skin) 1.605E 21(Bone) BA 142 1.643E + 03 (Lung) 5.064E + 04 (Skin) 4.105E - 39 (Bone) LA 140 2.257E + 05 (GI-LLI) 2.180E + 07 (Skin) 3.166E + 07 (GI-LLI) LA 142 7.585E + 04 (Lung) 9.117E + 05 (Skin) 2.141 E + 01 (GI-LLI)- s CE 141 5.439E + 05 (Lung) 1.540E + 07 (Skin) 4.082E + 08 (GI LLI) CE 143 1.273E + 05 (GI LLl) 2.627E + 06 (Skin) -1.364E + 07 (GI LLI) CE-144 1.195E + 07 (Lung) 8.042E + 07 (Skin) 1.039E + 10 (GI LLI): PR 143 4.329E + 05 (Lung) 0.000E + 00 (Skin) 1.575E + 08 (GI LLI)' PR 144 1.565E + 03 (Lung) 2.112E + 03 (Skin) 3.829E - 23 (GI-LLI) ND 147 3.282E + 05 (Lung) -1.009E + 07 (Skin) 9.197E + 07 (GI-LLI) l W 187 9.102E + 04 (GI LLI) 2.740E + 06 (Skin) 5.380E + 06 (GI LLI) - NP 239 6.401E + 04 (GI LLI) 1.976E + 06(Skin) 1.357E + 07 (GI LLI) l 1 l Units - l Inhalation and all tritium - mrem /yr per pCi/m3 ) i Other pathways for all other radionuclides -m2

mrem /yr per.pci/sec

) i-ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) 3.0 23 i

[ TABLE 3.2 3 l PATHWAY DOSE FACTORS FOR SECTION 3.2.3.3 (R )* i Page 1 of 3 e. AGt GAOUP pufAhD sh A.) qisef Ah4 Stefahh . Isant AssQ ishi Assh ties 5AhD le*eh slotoet, . assetALAtlOn Ga0use0 plant Gas tow Mits Gas tow MI At Gat tow Mna Ga5 Got Mt At GaSGOf Mns vtGETAtt00s H.3 4 4488 + 02 0 000E + 00 2.157i e 03 0.000( + 00 2.157t + 03 - 0.000E + 00 4.398t + 03 0.000t + 00 ' 'Y C.14 2.6464 + 04 - 0.000E + 00 2.340t + 09 0.0008 + 00 8.189E + 08 0 000t + 00 2.340E + 09 0.000t + 00 NA 24 1.056L + 04 1.3858 + 07 1.542i + 07 0.000E + 00 2.300t 37 ' O.000t + 00 _1.851t + 06 0.000t + 00 P 32 2.030E + 06 0.000( + 00 1.602i + 11 ' O.000t+00 7.084t + 08 0.000( + 00 - 1.924t + 11 0.000( + 00 CR 51 1.284E

04 5.506E + 06 '

4.700t + 06 0.000t + 00 1.729t + 05 ; 0.000t + 00 5.641E + 05 0.000t + 00 h4N 54 9.996E + 05 1.625E + 09 3 900E + 07 0.000t + 00 1.118f + 07 0.000( + 00 4.680E + 06 0.000E + 00 h4N 56 7.168E + 04 1.068E + 06 2.862t + 00 0.000E + 00 0.000t + 00 0.000E + 00 3.436E 01 0.000t + 00 1 1 FE 55 8.694E + 04 0.000E + 00 1.351E + 08 0.000E + 00 4.439E + 07 0.000t + 00 - 1.757E + 06. 0.000E + 00 i Ft 59 1.0158 + 06 3.204t + 08 3.919E + 08 0.000E + 00 3.344E + 07 0.000t + 00 5.006E + 06 0.000E + 00 1 CO 58 7.7701 + 05 4.444E + 08 6.G:5E + 07 0.000t + 00 8.824E + 06 0.000E + 00 7.251E + 06 0.000t + 00 C040 4.500E + 06 2.532E + 10 2.098E + 08 0.000t + 00 7.107E + 07 0.000( + 00 ' 2.517E + 0/ 0.000E + 00 .i N643 3.3881 + 05 0.000L + 00 3.4938 + 10 0.000t + 00 1.221t + 10 0.000t + 00 4.192t + 09 - 0.000t + 00 N645 5.012E + 04 3.451( + 05 3.020E + 01 - 0.000E + 00 0.000t + 00 0.000E + 00. 3.635E + 00 0.0008 + 00 CU44 1.498E + 04 6.876E + 05 3.8078 + 06 0.000t + 00 7.934E 46 0.000t + 00 4.246E + 05 0.000E + 00 -J 2N45 6.464E + 05 0.583t+08 1.904E + 10 0.000t + 00 5.160t + 09 0.0008 + 00 2.285E + 09 0.000t + 00 2N49-1.322E + 04 0.000E,00 3.855t 09 0.000E + 00 0.000t + 00 ' O.000E + 00 3.581E 10 0.000t + 00 BR-83 3.808E + O2 7.079E + 03 9J39E 01 0.000t + 00 0.000t + 00 0.000( + 00 - 1.124E 01 0.000t + 00 8R44 4.004t + 02 2.363t + 05 1.256t 22 0.000t + 00 ' O.000t+00 ' 0.000E + 00 1.5275 23 0.000t + 00 1 8R 85 2.044E + 01 0.000t + 00 0.00E + 00 0.000E + 00 0.000t + 00 0.0COE + 00 0.000E00 ' - 0.000t + 00 R8 86 1904E + 05 1.035E + 07 2J348 + 10 0.000t + 00 2.827E + 04 0.000E + 00 2.671 E + 09 0.000t + 00 RS-48 ' 5.572i + O2 3.779E + 04 1.874E44 0.000t + 00 0.000E + 00 0.000t + 00~ ' 2.304E 45 0.000E + 00 RS 89 3.206E + 02 1.452E + 05 3.414E.52 0.000E + 00 0.000t + 00 0.000E + 00 4.056E 53_ - 0.000( + 00 - SR 89 2.030E + 06 2.509E + 04 1.2584 + 10 0.000E + 00 1.280t + 09 - 0.000E + 00 2.643E + 10 0.0008 + 00 SR-90 4.088E + 07 0.000t + 00 1J16E + 11 0.000t + 00 4.2301 + 10 0.000t + 00 -2.553E + 11 0.000t + 00 SR 91 7.336t + 04 2.511E + 06 3.21st + 05 0.000t + 00 0.000f + 00 0.000E + 00 6.758t + 05 0.000E + 00 (PASTURE) (PASTURE) (Ft ED) (PASTURE) (PASTURE)

See note, page 3.0-36 Units -

Inhalation and all tr. tium - mrem /yr per pCi/m3 Other pathways fer all other radionuclides -m2

mrem /yr per pCi/sec ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) i 3.0 24

g TABLE 3.2 3 (continued)- PATHWAY DOSE FACTORS FOR SECTION 3.2.3 3 (R ) i Page 2 of 3 ~{ j AGIGaoup ens am 0 t= A1 tw ahD twAN4 tw ahh tw ahh tasak4 Insann notopt mnau fen Gaovho ptAnt san tow ens Gastow star Gasto* ugs GaSGofutat GhGof uu vtGEtation i 5R 92 1400t + 05 8.631E + 05 5.00$E*01-0 000E + 00 0.000t + 00 0.000E + 00 1054t + 02 0.000t + 00 Y 90 2 6881 + 05 5.308t + 03 9.4064 + 05 0 000f + 00 2.335f 05. 0.000t + 00 1.129E + 05 0.000E + 00 Y 91M - 2.7861 + 03 1.1615 + 05 1.8761 15 0.000E + 00 0 000t + 00 0 000E + 00 2.290f 16 0.000E + OC Y 91 2.450t + M 1.2071+ M 5.251t + 06 0.000t + 00 6.324E + 05 0 000t + 00 6.302I + 05 0.000E + 00 Y. 92 1.2661 + 05 2.142E + 05 1.026E + 01 0 000E + 00 0.000E + 00 0 0001 + 00 1.2 34 E + 00 ' O.0001 + 00 Y 93 1.M6E + 05 2.5348 + 05 '1.776( + 04 0 000( + 00 2J46E 61 0.0001 + 00 2.046E + 03 0.000t + 00 ZR 95 1.750t+ M 2.837i + 08 8.2571 + 05 0 000t + 00 1.090t + 05 0 000f + 00 9.910E + 04 0 000E

00 2R 97 1.400t + 05 3.445t + 06 4 446E + 04 0 000E,00 4 940E 35 0 000f + 00 5.3391 > 03 0.000t + 00 Det 95 4.748f + 05 1.6051 + 04 2.M2I + 08 0 000I + 00 1.213E + 07 0 000f + 00 -

2 475t + 07 - 0.000( + 00 I I MO 99 1.3441 + 05 4.6261 + 06 3.108t + 08 0.000E + 00 1.523E 02 0.0001 00 3.731E + 07 0.000E + 00 TC 99M 2.0301 + 03 - 2.1091 + 0$ 1.646E + 04 0 000f 00 0 0001 + 00 0 000f + 00 1.97BE + 03 0.000E + 00 TC 101 8442E+O2 2.277E + 04 1.423E 56 0 000E + 00 0 000f + 00 0.000f + 00 6.5301 58 - 0.000E + 00 RU 103 5 5161 + 05 1.265E + 04 1.0557 + 05 0 0004 + 00 7.573E,03 0 000E + 00 1.265E,04 0.000E + 00 p RU 105 4.4448 + 04 7.212E + 05 3.204E + 00 0.000E + 00 0 000f + 00 0.000E + 00 - 3.851E 01 0.000E + 00 1 RU 106 1.1541 + 07 5.049E + 08 1445E + 06 0.000( + 00 4.266E + 05 0.000E + 00 1.7341 + 05 0.000t + 00 AG 110M 3.668E + 06 4.019E + 09 1.461I + 10 0 000f + 00 3 9848 + 09 0.000E

00

-- 1.752E + 09 0.0001 + 00 tE 125M 4.4661 + 05 2.128L + 06 1.508E + 08 0.000E + 00 1.799E + 07 0.000( + 00 1.809E + 07 0.000E + 00 Tt.127M 1.312 E + 06 1.0431 + 05 1.0371 + 09 0000E+00-2 046E + 08 - 0.000E + 00 1.244E + 08 0.000f + 00 { Ti 127 2.436E + 04 3.293E + 03 1.3591 + 05 0 000E + 00 1.269t-65. 0 000t + 00 1.594E + 04 0 000E + 00 TE 129M 1.680t + M 2.3128 +07 1.3921 + 09 0 000E + 00 7.559E + 07 0.000E + 00 ' 1672i + 08 0 000E + 00 Yt t29 2.6321 + 04 3.0761 + 04 . 2.1871-07 0.000E,00 0.000t + 00 0.000( + 00 2.624E 08 0.000E + 00 TE 131M 1.948t + 05 9 459E + 06 2.288f + 07 0.000t + 00 1.653E 15 0 000t + 00 2.747E + 06 0 000E + 00 TE 131 8.2181 + 03 34Mt+07 1.344I 30 0.000E + 00 0 000t + 00 0.000E + 00 1.6486 31-0 000t + 00 t TE 132 3.402t + 05 4.M 8t + M 6.513t+n? 0.000!+00 1041E 01 0.000t + 00 7.442E + 06 0 000t + 00 1 1 130 1.5Mt + 06 6.692t +06 8.754f + 08 0 000t + 00 7115E45 0.000E + 00 1.051E + 09 0.000E + 00 (PASTURI) (PASTURI) (fttD) (PASTURE) (PASTURE) Unit 5 - Inhalation and all tritium - mrem /yr per pCi/m3 Other pathways for all other radionuClide$ -m2

mrem /yr per pCi/sec i

ODCM, V.C. Summer, SCE & G : Revi5 ion 13 (June 1990) 3.0 25 n

jf TABLE 3.2 3 (Continued) . PATHWAY DOSE FACTORS FOR SECTION 3.2.3.3 (R ) i Page 3 of 3 g isotoes = =.u no. caou.om.A.t Gascow uss cascom us.t cescow uns-cas cot ut.t ces Got uns vesti.no. 9 I 131' 1.4 H E*07 2.089E + 07 1.053E + 12 0.000E + 00 1.567E + 08 0.000E + 00 1.264E + 12 0.000E + 00 1 132 1.6HE + 05 1452E+06 1188E + 02 0 000E + 00 0.000E + 00 0 000E + 00 1.638E + 02 0.000E + 00 1 133' 3.556E + 06 2.981E + 06 9 601E + 09 - 0.000E + 00 1.776E 22 0.000E + 00 1.153 E + 10 0.000E + 00. 1 134 4.452E

04 5.30$E + 05 8 402E 10 0.000E + 00 0 000E + 00 0 000E + 00 1.017E 09 ~

0 000E* 00 I ..l 1,135 6.958E + 05 2.H71 + 06 2.002E + 07 0.000E + 00 0 000E + 00 0.000E + 00 2 406E + 07 0.000E + 00 . C5 - 134 ' 7.028E + 05 8.007E+09' 6 8011 + 10 0.000E + 00 2.191E + 10 0.000E + 00 - 2.040E + 11 0.000E + 00 - C5 136 1.345E + 05 1.710E + 08 5 795E + 09 - 0.000E + 00 1.729E + 07 0 000t + 00 1.7441 + 10 = 0 000E + 00 C5 137 6.118E + 05 1.201E + 10 6 0241 + 10 0.000E + 00 2 096E + 10 0.000E + 00 1.047E + 12 0.000E + 00 C5 138 8.764E+02 4.102E + 05 2.180E-22 0.000t + 00 0.000E + 00 0.000E,00 6.6281 22 0.000E + 00.- SA 139 5.096E + 04 1.1ME + 05. 2.874E 05 0.000E + 00 0 000E + 00 0.000E + 00 3.265E 06 0.000E + 00 8A 140 1.596E + 06 2.346E + 07 2.410E + 08 0.000E + 00 6 409E + 05 . 0.000E + 00. - 2.893I + 07 0 000E + 00 SA 141 4.746E + 03 4.734E + 04 4.916E 44 0.000E + 00 0 000E + 00 0.000E + 00

5.899; 45 0.000E + 00 t,

8 A 142 1.554E + 03 5 064E + 04 1.049E 78 - 0.000E + 00 0 000E + 00 0 000E + 00 1.259E 79 0 000E + 00 LA 140 - 1.680E + 05 2.180E + 07 1.840E + 05 0.000E + 00 4.563E 12 0.000E + 00 2.253E + 04 0.000E + 00 - LA 142 5.950E + 04 9.117E + 05 1.0788-05 0.000E + 00 0 000E + 00 ' O.000E + 00 - 1.278E 06 . 0 000E + 00 CE 141 5.166E + 05 1.540E + 07 1J66E + 07 0.0001 + 00 7.004E + 05 0.000E + 00 1.640E + 06 0 000E + 00 CE 143 1.162E + 05 - 2.627i + 06 1.536E + 06 0.000E + 00 1039E 14 0.000E + 00 - 1.844E + 05 - 0.000E + 00 CE 144 9.842E + 06 8.042E + 07 .1.334E + 08 0.000E + 00 3 749E + 07 0.000E + 00 1.601E + 07 0 000E + 00 ~.771E+03-0.000E + 00 4.407E*04 0 000E + 00 - [ PR 143 4.326E + 05 0 000E + 00 7.8458 + 05 0.000E + 00 2 PR 144 4.284E + 03 2.112t + 03 1.1711 48 0.000E + 00 0 000E + 00 0.000E 00 1.259E 49 0 000t + 00 ND 147 3.220E + 05 1.009E

07 '

$.743E + 05 0.000E,00 6.902E + 02 0.000E

00 6.885E + 04

' O.000E + 00 W 187 3 962E + CA 2.740E + 06 2.501 E + 06 0.000E + 00 5.275E-22 0.000E + 00 2.983E + 05 0.000E + 00 NP 239 5.950E + 04 1.976E + 06 9.400E + 04 0 000E + 00 1.0251 07 0.000E + 00 1.132E + 04 0 000E + 00 - 1 (PASTURE) (PASTURE) (FEED) (PASTURE) (PASTURI)- l Units - Inhalation and all tritium - mrem /yr per pCi/m3 Other pathways for all other radionuclides -m2

mrem /yr per pCi/seC

~ ODCM, V C. Summer, SCE&G: Revision 13 (June 1990) 3.0 26 1 t I

.s TABLE 3.2 4 PATHWAY DOSE FACTORS FOR SECTION 3.2.3.3 (R )* i O q Page 1 of 3 1 e AGE GaOUP Khn0s im A i Knn0p Knn De Kuk0s KunDe Kan0 KnaLD6 450f0*t. MinALAflon Ge0Vh0Ptant GAn C0e Mas GA% Cow Mtaf Gas tow Mna G4% GOf M4 AI G4t GOT Wnt VlG(TAfton H3 1.125E + 03 0.000E + 00 1.421E + 03 2.118E + 02 1.421E + 03 ' 2.543E + 01 2.899E + 03 3.627E + 03 C 14 3.589E + 04 0.000f + 00 1.195E + 09 3.834E + 04 4.181E+08 4 601E + 07 1.195E + 09 8 894E + 08 NA.24 1.610E + 04 1J85E + 07 8.853E + 06 1.725E 03 L321E 37 2.070E 04 1.063E

06 3.729E + 05 P.32 2.605E + 06 0.000E + 00 7.775E + 10 7.411E + 09 3.440E + 00 8.093E + OS 9.335E + 10 3.366E + 09 CF.51 1.490E + 04 5.506E + 06 -

5.390E + 06 4 661E + 05 1.985E + 05 5.593E + 04 6.478E + 05 6.213E + 04 M N.54 1.576E 06 1.625E + 09 2 097E + 07 8.011E + 06 6.012E + 06 9.613E + 05 2.517E + 06 6.648E + 08 MN.56 1.232E + 05 1.068E + 06 1.865E + 00 2 437E 51 0.000E + 00 2.924E 52 2.238E 01 - 2.723E + 03 FE 55 1.110E + 05 0.000E + 00 .1.118E + 08 - 4.571E + 08 3.673E + 07 5 486E + 07 1.451E + 06 0.012E+04 FE 59 1.269E + 06 3.204E + 08 2.025E + 00 6J38E + 08 1.749E + 07 7.605E + 07 2.633E + 06 6.693E + 08 CO 54 1.106E + 06 4.464E + OS 7.040E + 07 - ' 9 596E + 07 1.032E + 07 1.152E + 07 8.487E + 06 3.771E + 08 j C040 7.067E + 06 2.532E + 10 2.391E + 00 3.838E + OS 8.103E + 07 4.605E + 07 2.870E + 07 - 2.095E + 09. ~ Nk63 4.214E + 05 0.000E + 00 2.964E + 10 2.912E + 10 - 1.036E + 10 3.495E + 09 3.557E + 09 ' 3.949E + 10 N145 8.399E + 04 3.451E + 05 1909E + 01 4.061E 51 0.000E + 00 4.873E 52 - 2.290E + 00 - 1.211E + 03 ( CU44 3.670E + 04 6.476E+05 3.502E + 06 1.393E 05 7.299E 46 1.672E 06c 3.907E - 05 ' 5.159E + 05 ZN45 9.953E + 05 8.543E + 08 1.101E + 10 1.000E + 09 2.985E + 09 1.200E + (G 1.32P!,09 - 2.164E + 09 2N49 1.018E + 04 0.000E + CO 1.123E 09 0.000E + 00 0.000E + 00

0.000f + 00 1.0432 10 9.093E 04 -

5A43 4.736E + O2 7.079E + 03 4.399E 01 9.519E 57 0.000E + 00 - 1.142E 57 5.190E 02 4 5.369E + 00 8A44 5.476E + 02 2.363E + 05 6.500E 23 0.000E + 00 0.000E + 00 - 0.000E + 00 7.758E 24. 3.822E 11 ~ J 8A.85 ~ 2.531E + 01 0.000E + 00 0.000E + 00 0.000E + 00 0.000E + 00 0.000E + 00 , 0.000E + 00 0.000E + 00 ] At46 1.983E + 05 1.035E + 07 8.804E + 09 5.816E + 08 1.114E + 00 6.979E + 07 1.053E + 09

4.584E + 08 A8 88 5.624E + 02 3.779E + 04 7.150E 45 0.000E + 00 0 000E + 00 0.000E + 00 8.789E 46 4.374E 22 A849 3.452E + 02 1.452E + 05 1.397E 52 0.000E + 00 0.000E + 00 0.000E 00 1.659E 53

- 1.642E

26 5A 89 2.157E + 06 2.509E + 04 6.6ISE + 09 4.815E + 08 6.730E + 08 5.778E + 07 1.390E + 10 3.593E + 10 SA.90 1.010E + 08 0.000E + 00 1.117E + 11 1.040E + 10 3 887E + 10 1.248E + 09 '

' 2.346E + 11 1.243E + 12 i l l. SA 91 1.739E + 05 - 2.511E + 06 2.878E + 05 55.292E 10 0.000E + 00 6.351E 11 6.050E + 05 1.157E + 06 (PASTURE) (PASTURE) (FE ED) (PASTURE) -(PASTURE) j

See note, page 3.0 36 1'

L Units - l lehalation and all tritiurn - mrem /yr per pCi/m3 Otner pathways for all other radionuclides m2

mrem /yr per pCi/Sec t

ODCM, V.C. Summer, SCE&G: Revi5 ion 13 (June 1990) l p 3.0-27 j

'I s. TABLE 3 2 4 (Continusd) PATHWAY DOSE FACTORS FOR SECTION 3.2.3.3 (Ri) Page 2 of 3 aos caout gnnoe =ap KanDe danDi gnnos ~ gain. KanDe gano notoes maaution caou=otuas cas too uu can tow wm ces tow una ses cot usar sasnot una vacatabon SR 92~ 2.4241 + 05 8.6318 + 05 4.134E

01 3 49's 48-0 000t + 00 4.191E 49 8.706E + 01 1.3788 + 4 Y 90 2.6791 + 05 5.308E + 03 9171t + 05 4.8798 + 05 2.2771 05 5 855E + 04 1.101E + 05 6.569E + 7 Y 91M 2.812E + 03 1.161t + 05 5622t 16 0 000E 00 0 000E + 00 0 000t + 00

6. Met 17 1.737t 5 Y 91 2.627f + 06 1.207E + 06 5199E + 06 2.4008 + 00 6.261E + 05 2.880t + 07 6.2401 + 05 2.4841 + 9 Y 92 2.3908 + 05 2.142i + 05 7.310E + 00 6 9591 35 0 000t + 00 8.350t 36 0.791E 01 4.5768 + 4 Y 93 3.8851 + 05 2.534t + 05 1.573E + 04 1.5471 07 9134E 61 1.057f 08 1.8881 + 03 4.482t + 6 2R 95 2.231t + M 2.8371 + 00 8.7866 + 05 6.1061 + 08 1.1601 + 05 7J20t + 07 1.054E + 05 8.843E + 0 2R 97 3.5111 + 05 3.445E + 06 4.1991 + 04 7.015E 01 4.703t 35 -

8.410E 02 $ 042E + 03 1.248E +*/ - N8 95 6.142E + 05 1.605E + 09 2.287E + 08 2.208E + 09 1.346E + 07 - 2.673t

Os

' 2.74 71 + 07 2.949E + 8 MO 99 1.354E + 05 4.626E + 06 1.738E + 08 2 456E + 05 8512E 03 2.947E + 04 2 086E + 07 1.647i + 7 TC 99M 4.810E+03 2.109E + 05 1.4741 + 04 6 9151-10 0 000t + 00 8.298E 19 1.7711 + 03 5.255E A 3 TC 101 5.8468 + O2 2.277E + 04 5.5938 54 0.000E + 00 ' O 000E + 00 0.0001 + 00 2.5644 59 4.123t.29 RU 103 6 623t + 05 1.265E + 08 1.1088 + 05 4.009f*09 7.952E + 03 4.0 t i t + 08 1.329E + 04 3.971E+8-RU 105 9 953E + 04 7.212i + 05 2.493t + 00 5.8854-25 0.0001 + 00 7.061E 26 ' 2.997E 01 5.981E + 4 RU - 106 1.476E + 07 5.049E + 08 1.437E + 06 6 902t + 10 4.243E + 05 ' 8.282E + 09 1.725E + 05 1.1591 + 10 AG 110M 5.476E + 06 4.019E + 09 1.678E + 10 6.7421 + 08 4.576E + 09 8.090f+07 2.013t + 09 2.581 E + 9 - TE 125M 4.7731 + 05 2.1281 + 04 7.3771 + 07 5 690E + 08 8.802t + 06 6.82SE +07 8.853E + 06 - 3.506E + 8 Ti 127M 1.480t + 06 1.083E + 05 5.932E + 08 5 060E

09 1.171E + 08 6.072E + 08 7.118f,07 3.7696 + 9 TE 127 5.624E + 04 3.2936 + 03 1,191E + 05 1.6071 08 '

0.000E + 00 1.929 09 1.396E + 04 3.903E + 5 ft 129M 1.7611 + 06 2.3121 + 07 7.941E + 08 5.245E + 09 4.324E + 07 ~ 6.2948 + 0S - 9.5631 + 07 2.46E + 9 TE 129 2.5491 + 04 3.076E + 04 7 96E 08 0 Act + 00 0.000t + 00 0.000t + 00 9 641E 09 7.2041 2 TI 131M 3.0781 + 05 9.459E + 06 2.244E + 07 9 815E + 03 1.621E 15 1.178f + 03 2.094E + 06 2.163E + 7 TE 131 2.054E + 03 3.450E + 07 8.4898 32 0 000f + 00 0 000t + 00 0.000E + 00 - 1.036f 32 1.3496 14 TE 132 3 7744 + 05 4.968E + 06 4.551E + 07 9.325E + 06 7.272E 02 1.119E + 06 5 480E + 06 ' 3.111E + 7 1 130 1.846E + 06 6'6921 + 06 3.845E + 08 6 758E 04 3.125E 45 8.109E 05 4.617f + 08 1.3711 + 8 (PASTURE) (PA5 TURI) (F E ED) (PASTURE) (PASTURI) Units - Inhalation and all tritium - mrem /yr per pCum3 Other pathways for all other radionuclides m2

mrem /yr per pCi/sec ODCM, V.C. Summer, SG& ~. Devision 13 (June 1990) 3.0 2R

_ - - - ~ TABLE 3.2 4(continue) PATHWAY DOSE FACTORS FOR SECTION 3.2.3.3 (Ri) Page 3 of 3 y AGIG4098 KMet06 in Aj KnatD# KunDe KMnDs KultDi KnitDe EastDe 1%0f086 shmALAtioes .Gaoum08tAmt G#b CO* MILS GanCO* MIAT GH CO* Miss Get G0f M6Af GM Gof Mits vt Gt f a tion. b131 1.6241 + 07 2.089E + 07 4.333E + 11 5 503E

09 6 448i + 07 '

6.604E + 08 5.201E + 11 4.754E + to 0132 1.9351 + 05 1.452f + 06 5.1291 + 01 2.4296 57 0.000f + 00 2.9154 58 7.072t + 01 7.314E + 03 b133 3 448E + 06 2.981E + 06 3 M5E + 09 1.304E + 02 7.299t 23 1.564E + 01 4.737! + 09 . 8.113t + 08 1-134 5 0691 + 04 5J05E + 05 3.62eE 10 0.000t + 00 0.000E + 00 0.000t + 00 4.386E 10 6.6221 03 b135 7.914E + 05 2.M7E + 06 8607f+06 1.0398 14 0.000t + 00 1.2471 15 1.0344 + 07 9 973t + 06 C5134 1.0148 06 0.007E+09 3.715E + 10 1.513t + 09 1.197E + 10 1.816f + 08 1.1151 + 11 2.631t + to - s C5136. 1.7096 + 05 1.7104 + 08 2.773t + 09 4 426E + 07 8.2 76E + 06 ' 5J111 + 06 8.344E + 09 - 2.247E + 08 C5137 9 065E + 05 1.201t + 10 3.224f + 10 1.3ME + 09 1.122t + 10 1.600f + 08. ' 9.672t + 10 2.392E + 10 t (s.138 8.3991+02 4.102E + 05 5.520t 23 0.000E + 00 0.000E + 00 0.000E + 00 1.6818 22 9.1334 11 84 139 5.772i + 04 1.1ME,05 1.2311 05 0.000t + 00 0.000E + 00 0.000t + 00 1J98E 06 2.950E

00 :

S A.140 1.743E + 06 2.346E + 07 1.1711 + OS 4.3841 + 07 3114f + 05 5.261E + 06 1.406E + 07 2.7671 + 34 S A.141 2.919 + 03 4 7ME + 04 1.8Mt 45 0.000t + 00 0.000t + 00 0.000f,00 2.273t 44 ,1.605E.21 BA 142 ' t.643t + 03 5.064E+04 1.208E 79 0.000E + 00 0.0008 + 00 0.000t + 00 1.4501 80 4.1058 39 LA 140 2.257E + 05 2.180f + 07 1.8Mt + 05 5 4928 + O2 4.596t 12 6 590f+01 2.2698 + 04 3.166E + 07 L A 142 7.5851 + 04 9.117f + 05 5.2031 06 0.000t + 00 0 000t + 00 ' O.000f+00 6.1668 07 2.141E + 01 CE 141 5.439E + 05 1.540E + 07 1.361t + 07 1.3821 + 07 6 960 + 05 1.658E + 06 1.633t + 06 4.082f,04 Ci 43 1.273t + 05 2.627E + 06 1.488f + 06 2.516E + 02 - 1.006E 14 3.020f + 01 - 1.787E + 05 1.364f + 07 CE.144 1.195f + 07 8.042f + 07 1.326E + 08 1.8931 + 08 3.7271 + 07 ' 2.271f + 07 1.592t + 07 1.039E + 10 PR.143 4.3291 + 05 0.000f + 00 7.754E + 05 3.609t + 07 2.7381 + 03 , 4.331 E + 06 9.297E + 04 .1.575E + 08 3 -PR 144 1.545E + 03 2.112E + 03 2.040f 50 0.000E + 00 0.000f + 00 0.000t + 00 2J53E 51 3.829E 23 NO 147 3.282f + 05 1.009E + 07 5.712 E + 05 1.505E + 07 6.864f + 02 1.805E + 06 6.846t + 04 9.197E + 07 W.187 9.102I + 04 2.740E + 06 2.4208 + 06 2.7908 + 00 5.1031 22 3.348E 01 2.8864 + 05 5.380E + 06 NP.239 6.401t + 04 1.976E + 06 9.1386 + 04 2.232E + 03 9.336E. 08 2 679E +02 1.100t + 04 1.3571 + 07 (PASTURE) (PASTURE) (FitD) (PA5 YURT) (PASTURE) l. i l l. Units - Inhalation and all tritium - mrem /yr per pCi/m3 Other pathways for all other radionuclides m2

mrem /yr per pCi/5ec ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) 3.0 29

_ _ ~ - ~. ~. - - _. -.. - -.. ..~ .- -. ~ _ ~, r. TABLE 3.2 5 PATHWAY DOSE FACTORS FOR SECTION 3.2 3.3 (Ri)* L [ Page 1 of 3 - 1 AGt GAOUP Filh AGite th Al FilhAGl#1 FilhAGt46 FtthAGlas UlthAGet). Fitk 4t t) - FtthAGt46' l liOTOPI. ihesAtation G40Vh0 PLAkt Gal (OW MILE Gal CO* MI A T Ge% Cow Mus Ga5 Got MEAT GR5 G0t Mus v5Gt1AYaoh H3 1.272E + 03 0 000t + 00 8.M3E + 02 1.754E

02 B.993E + 02 2.104f + 01 1.835E + 03 L 2.342E + 03 -

C.14 2.600t + 04 0.000E + OS 4.059E+OS 2.040t + 08 1.700E + 00 2 4481 + 07 4.859t + 08 . 3.6908 + 04 It A.24 1J76t + 04 1.305E ' 07 4.255t + 06

1.084t 03 6.347E 38 1.301t 04 5.110E + 05

~ 2.389t + 05 - F + P 32 1.8884 + 06 0.000t + 00 3.153! + 10 3 931E + 09 - 1395E

08 4.717E + 08 3.705E + 10.

1.608E + 09 - i CR-51 2.0961 + 04 5 506t + 06 8.3871 + 06 9.4711 + 05 Mt + 05 1.137E + 05 1.0064 + 06 1.03 FE + 07 MN.54 1.984E + 06 1625E + 09 2.875E + 07 j 1436E + 07 8.240E + 06 1.723i + 06 3.450E + 06. 9.320t + 00 ' f MN.56 5.744C + 04 1.068E + 06 4.856E 01 0 302f 52 0.000f + 00 9962E 53 5.82M 02 9.451t + 02 FE 55 1.240E

05 0.000t + 00 4.454E + 07 2.382t + 08 1.463t + 07 2.8594 + 07 5.790E + 05 '

3 259t + 08 FE.59 1.520t + 06 3.204E + 08 ' 2.361E + 00 1.t i1 E + 09 2.470E,07 1.405t + 00 -. 3.720E + 06 9.095E + 08 CO-58 1.344E + 06 4.464E + 08 1.095E + 08 1.942E + 00 1.596E + 07 2J30E + 07 1.313E + 07 6 G34E 4 00 CO60 8.720E + 06 . 2.532E + 10 3.621E + 08 L 7.600t + 08 1.227E + OS 9.120t + 07 4.345E + 07 3.238E + 09 NI-63 5.800t + 05 0.000E + 00 1.182E + 10 1.519t + 10 4.130E + 09 1.823E + 09 - - 1.419E + 09 1.606E + 10 Ni-65 3.672E + 04 3 451E + 05 4.692i + 00 1.30$E 51 0.000E + 00 1.5664 52 5.647E 01 3.966E + O2 CU.64 6.144E + 04 6.876E + 05 3.293E + 06 1.713E 05 ' 6.4631 46. '2.072E 06 3.673t + 0's 6.445E + 05 - t 2N45 1.240t + 06 8.583E + 08 7.3154 + 09 8.688E + 08 1983t + 09 1.0431 + 08 ' 0.779E + 08 - 1.471E + 09 ~ I ZN.69 1.584E + 03 0.000E + 00 1.760f 11 0.000( > 00 0 000E + 00 0.000t + 00 1.635E 12 2.067E 05 SR 83 3 440t + 02 7.0791 03 1.790E 01. 5.066t 57 0.000t + 00 6.079E 58 2.112 E -02 2.911E + 00 SR.44 4.3284 + 02 ' 2.363E + 05 2.877E 23 0.000E + 00 0.000E + 00 0.000E + 00 - ' 3.4291 24 2.2511 11 GR-85 1.832E + 01 0.000t + 00 0.000f + 00 0.000E + 00 0.000i + 00 0.000 + 00 0.000t + 00 0.000E + 00 RS 86 1.9041 + 05 1.035E + 07 4.746t + 09 4.101E + 08 - 6.0061 + 07 4.921E + 07 - 5.675E + 08 2.772E + 08 l RS 48 5.456E

02 3.7794 + 04 3.886E 45 0.000t + 00 0.000E
00 0.000E + 00.

4.777E 46 3.168( 22 RS 89 3.520E + 02 1.452E + 05 7.957E 53 0.000E + 00 0.000E + 00 0.000f + 00 9.454t 54 - 1.2471 26 $R.st 2.416E + 06 2.509E + 04 2.674t + 09 2.545E + 08 2.719t + 08 3.054E + 07 5.617t + 09 1.513E + 10 SR 90 1.040E + 08 0.000f + 00 6.612E + to B.049E + 09 2.301t + 10 9.659E + 08 1.389t + 11 7.507E + 11 5R 91 2.5925 + 05 2.511f + 06 2.4094 + 05 5.7941 10 0.000t + 00 6.953t 11 5.064E + 05 1.291E + 06 (PASTURE) (PASTURE) (FE ED) (PASTURE) (PASTURE) ^

Sse note, page 3.0 36 i

Units - Inhalation and all tritium - mrem /yr per pCi/m3 i Other pathways for all other radionuclides m2 e mrem /yr per pCi/sec ODCM, V.C. Summer, SCE &G: Revision 13 (June 1990) 3.0-30 3 o I \\ t i m m. ,..r._ .,_..,.m .w.--. ,y .-,-,.,,-r,r. _,y.. m

i TABLE 3.2 5(ctntinu;d) PATHWAY DOSE FACTORS FOR SECTION 321.3 (R ) i Page 2 of 3 I au uou, nm.u., ,si me.w, nm.ue, cm.ua, m e =*u e. m e.,au n, ,, m.u i, i isotoes m aiart.m snou=ottani sestoo una sestoe wtat sescoe was ses sot sta t sesnotw u visitateos { $R.92 1.1628 + 05 8.6318+05 2.2778 + 01 2.5161 44 0 000t

00 3.019t.49 4.7957 + 01 1.0121
M I

l v.90 l5592t+06 5300t + 03 1074t

M 7 47H + 05 2 666t;05 8 H',t + 04 1289t + 05 1025t+08 l

Y. 91M 3.2001 + 03 1.1618 + C5 5 1298 18 0 000f + 00 PWiN + 00 ' 0 cost < 00 6.M61.i9 3.2851 07 V.91 2.tMt M 1.207t+ M 6147t + M 3 910t + 08 7.7M

05 4.tt t! + S7 7.700f + 05 3.2121 09 i

0.600t+Oh)4.2261.M Y 92 1 6441+05 2.1421

05 2 Sket + 00 3.522f. Al !

3 4Wtt 01 2.M04 + M I v.93 6 7021 05 2.lMt + M 1.312t + 04 160H. 07 7.6201.'61 2 026I DS L511t + 03 4 98H + 06 i 2A t$ 2 6tet + M 2.8378+08 1J018 + M 109H + 09 1.585f + 05 31H + 08 1.M i t + 05 1.25H + 09 2R 97 6.3048 + 05 3 444 + M 4.225t+04 9J318 01 4.732t H 1.1088 01

E,JI 4 ih 1.6?H + 07 J

l NO 95 7.5121 + 05 1.6054 + 08 3.3MI + 08 4.251t > H 196H + 07 5.1011 + 04 4.000f + 07 45511+08 Mo. 99 2.M H + n 46Mi+M iMH+M tMM.n 5 0iH.o inh +M 1 J

1. net.07 utH.07 TC 99M 6.12H + 03 2.109t + 05 1055E + 04 6 4718 18 0 000t + 00 7.7601 19 1.267t + 03 5.011t + 03 TC 101 6 672t + O2 2.2771

M 1J4H. $8 0 000t + 00 0 0004 + 00 0.000E + 00 1.60H St 3.22H 29 l

au.in 7.uM. 05 tMM.M tSiH.n 7.i6H + 09 uMi.M utH+M uiH + M 5.7Mt + M 1 AU.105 0 0404 + M 7.212t+05 s. 3: + 00 3.9004 25 0 0008 + 00 4 600t 26 1.5194 01 4.03H + M i RU 10(. 1.6088 + 07 5 Dett + 08 1799i + M 1.1308+11 5.312i + 05 1JS6E + 10 2.16H + 05 1 AME + 10 ~ j i A0 110M 6.752i + 06 4.01H + 09 2.llH + 10 1.3454 + H 6 902i + 09 1.614f + M 3.071t + 09 4 0318 + 09 TE.125M 5.M0 + 05 2.12H + M S 86H + 07 8 Mit + 08 10598 + 07 1 f'1! + 08 1.Mai + 07 4.37bi + 08 Ti 127M 1.656f + M 1 OSH + 05 3 420t + 08 3.816E + 09 6 7531 + 07 4.580t 4 0A 4.1054 + 07 2.236E + 09 Ti.127 8 08H + 04 3.2tH + 03 9.5728 + M 1.6098-08 0 00H + 00 N 278 09 1.122i + M 4 1801

05 e

TI 129M 19168 + 06 2.3128 + 07 4.602t+04 3 MH + 09 25002*Vr 4.75H + Os 5.520i + 07 1.514t + 09 TI 129 3.2ME + 03 3.07H + 04 2.8Mt. 00 0 000t + 00 0 0001 0.00H + JO 3.43H 10 3 916E o TI.131 M 6.2Mt + 05 9.459t + M 2.529t + 07 1.447t+tt 1827t.15 1.7Mt

03 3.0Mt + 06 3.248t + 07 ft.131 2.3Mi e 03 3.450t + 87 2.4798 42 0.000t
00 0.000t + 00 0.000t + 00 3.515t.nl 6.099t.15 i

78 132 LJ21 + 05 4 MH + 06 8.5818 + 07 2.3004 + 07 1.371t 01 2.760t + M 1.03H + 07 7.318E + 07 1 130 1400t + M 6.692t + 06 1.742t + 04 4 0651 04 1.4164 45 4.0Mt 05 2 H2t + 08 8.2Ml + 07 (PA57URI) (PASTUal) (FilD) (PA57UAE) (P45 TURI) Units-Inhalation and all tritium mrem /yr per pCi/m3 i Other pathways for all other radionuclides m2

mremlyr per pCi/sec d

ODCM, V.C. Summer, SCE&G: P 2 vision 13 (June 1990) i 3.0 31 l l r l-.

I r g TABLE 3.2 5 (C:ntinued) 'i PATHWAY DOSE FACTORS FOR SECTION 3.2.3.3 (th) Page 3 of 3 l A6tseove piwassai in a s stimastas painasami piensstes pinnast as pe.Ja6sas stima6:ei esotoet maAaros Geovep eans Gastow was ; segtoo want seg tow was 6enout wtat ses Got was vasttation ) 1 131 14Mt + 07 2 Otti + 07 2.1Mt+11 3 M58 + M 3.2Mt + 07 4.3 751 + 04 2.6Mt + 11 3.140k + 10 i 0 132 1.512f + 05 1.452f + 06 2.241 + 01 130H 57 0 000t + 00 1.M 7f. 50 3.0921 + 01 4.2628 + 03 ' l.133 2 9208 + 66 2.M IL.06 14748 + 09 7.2Mt + 01 3 OMt.23 0 6848 + 00 2.0098 + M 4 587E + 04 1 1M 3 952t + M $305t + 05 1.50H 10 0 000t + 00 0 000t + 00 0.00H + 00 1.9154. 'O 1.054t 03 1 135 6.204t

05 2 M7t + M 3.777t+06 5 9638 15 0 000t + 00 7iMt.16 4.530t + M 5.832t + M re

.~ C5 1M 1.1291+ 06 4 0071 + M 2J1H+10 1.2318 + M 7 edit + 09 1.4778 + 00 6 G318 + 10 16711 + 10 C5 1M 19Mt + 05 1.710t + 08 1.7598 + 09 3 6718 + 07 5.24H + M 4 4Mt + 06 5.2928 + 09 1.7044 + 04 C5 0 7 8 M06 + 05 1.2011 + 16 1.1611 + 10 9 6Mt + 00 6 1971+ 09 1.iMt + 08 5.3421 + 10 1344E,10 C5 1M 8 M0 + 02 4.102t + 05 3.14H. 23 0 000t + 00 0.000t + 00 0.0008 + 10 9.5768 23 6.935E 11 i 4A 1M ^ 464t + 03 1.1Mt + 05 7.74 II. 07 0 000I

00 0 0001 + M 0 0001 + 00 0.7Mt.00 2.403 t. 01 r

S A.140 2 OJ2t

M 2.M6t + 07 7.48H + 07 3 MH + 0?

1.9901+05 4.3Mt

M I 9811 + M 2.1ME + 08 i

S A.141 3.2888 + 03 4.7Mt + U 7.7tH.46 0 0Mt + 00 0 000t + 00 0.000t + 00 9.244 t. 47 8.699(.22 S A.142 19121 + 03 5 0Mt + M $ 010f. 00 0 000t + 00 0 0008 + 00 0 000t + 00 6 0128 81 5.613t. 39 LA 140 4 8728 + 05 2.100t + 07 2.2918 + 05 8 649t + 02 5 Mot.12 1.0438 + 02 2.745t + 04 5.1048 + 07 LA 142 1.20H + M t.1171 + 05 4 411t.07 0 0006

00 0 000t + 00 0.0008 + 00 5 4658 04 2.5298 + 00 CE 141 61Mt + 05 1.540( + 07 16t48 + 07 2.252t + 07 8 7008 + 05 2.701I + 06 2.0Mt+06 5404E*04 CE 143 2 552 + 05 2.6278 + 06 1.671t + 06 3 6951 + 02 1 1304 14 4 4348 + 01 2.006t + 05 2.040t + 07 C f.144 1.3Mt + 07 8 M24 + 07 1.6558 + 04 3Otti+ "

4 650t + 07 3 'rMt + 07 19861 + 07 IJ26E + 10 PA.143 4 8321 + 05 0.000t + 00 9 5538 < (r5 5 8178 + 07 3 314t + 03 6 900t + 06 1.146f + 05 2 3101 + 08 PA.144 1.752t + 03 2.112t + 03 1.2384 53 0 000t + 00 0.000t + 00 0 000t + 00 1.3311 54 3 097t. 26

D.147 3 7204 + 05 1.0098 + 07 7.116E + 05 2.45H + 07 8 552t + 02 2 H2t + 06 8 530t + 04 1424f + 00 W 187 1.7688 + 05 2.7405 + M 2.646E + 06 3 9098 + 00 5.5798 22 4 7871-01 3.1554 + 05 7 839t + M RP 239 1.3201 + 05 1.9768 + 06 1.0605 + 05 33874+03 1 0431 07 4 Met + 02 1.276f + 04 2 0978 + 07 (PA5TUAI)

(PASTUAI) (f ttD) (PA57Unt) (PA 5Tutt) 4 Unit 5 Inhalation and all tritium. mrem /yr per pCi/m3 Other pathway 5 for all other radionuclides m2

mrem /yr per pCillec ODCM, V.C. Summer, SCE& G: Revi5 ion 13 (June 1990) g 3.0 32 y

ei,i,. ~,

1 TABLE 3.2 6 i. PATHWAY DOSE FACTORS FOR SECTION 3.2.3.3 (R )*) i T Page 1 of 3 A666tOUP tabuth it a l taDuth IAOuth 6&Dutt) saDut h tabuth taputh tbOt 0*t me.Ata tIO4 6aoue0 psAapt un toe hka eet toe tst at 686(oetsatt Gen 60t hstat tel 601 MILE vt6tta tq0er i

H3 1JMt + 03 0 000t + 00 6 9048 + 02 2.MH + O2 6 teH + 02 3 l2tt + 01 1.4'.

! + 03 2telt+03 C.14 1.01H + 04 0.0006

90 2 6Mt + 00 2 4144 + 08 9.219t+07 2.8971 + 07 2.6ME + 00 2.27H + 08 N A.24 1.0241 M IJOH + 07 2 4Mt + M 1JMt.03 36Mt.M 14288.M 2.926f
05 2 690t + 05 P 32 1.D H + M W 0008+00 170H + 10 4 ellt + De 7.559E +I?

5 642I + 04 2.0$H + 10 140H + 09 t CR 51 1440t

M l.5Mt
W 71978 + M 1.77H + M 2 6448 + 06 2.1278 + 05 84248+05 1.16M +07 i

hess.54 14006

M i 62H + 09 25701+07 2.0128+07 7.30W + 06 3.3751 + M 3.0918 + M t 54SE + 04 j

h4N.56 2.024E + M 1.0606 + M 1J288 01 4 9644 52 0.00M + 00 5 Met.53 1J Mt.02 5.0828 + 02

t.55 7.2008 + M 0.000f + 00 2 $111 + 07 2 93H + 08 0.250f+ M 3 51H + 07 3.2651+DS 2.0Mt + 08 t

7I.59 1.0168+ M 3.2048+08 2.327I

De 2.00M + 09 2.00H + 07 2 A958 + OS 3.02H +06 9.8754+04 CO.58 9.200t+05 4.4Mt + 08 9.66SE + 07 3.70H + 00 1JMt + 07 4 MH + 07 1.1471 + 07 6.252t + 04 C040

$ t6tt + 06 2.$3M + 10 3.042i + 00, 1.41H + 09 1.0448 + 08 16958 + 08 3.7E + 06 3.13M + 09 N643 4.32H +05 0 00H + 00 6.7298 + 09 1.00M + 10 2.351t + 09 2.2HI + OS 9.0751 + 00 1.040f + 10 N645 1.2328 + 04 3 4514 + 05 1.219t + 00 7,4068 52 0 0001 + 00 8 8868 53 1 A648 01 2.02H + 02 CU44 4 GMt + 04 6.8764 + 05 2.03H + 06 2J07E 05 4.2HE. 46 2.76M. 06 2 tilt + 05 7.Mit + 05 2N45 4 M01 + 05 8 5831 08 3.?ME + 09 1.1328 + 09 1.10H + 09 1.3581

08 4.54H + 00 1.00M + 09 ZW49 9 200t + 02 0.00H + 00 4.0318 12 0 000t + 00 0.00M + 00 0.00H + 00 4.83M 13 1.2028 05 M43 2 404f + 02 7.079t + 03 1J9H.01 864M.57 0 00H + 00 1.0Mt.57 1.69H. 02 4 475t + 00 BR-84 3120t + 02 2.363t + 05 1 698 23 0 000g + 00 0 000t + 00 0.000t + 00 2.02H. 24 2 47t t.11 BR-85 1.200t + 01 0 000t + 00 0.000t + 00 0 00N
00 0.000t + 00 0.00H + 00 0.000t +.J 0.0 J04 + 00 M.H u5a + 05 uan.07 utH. 00 407 00 320u. 07 S MH.07 3.tiH + M TiMi. 0.

As te 3 P728 + 02 3.77M + 04 2.1998 45 0 000t + 00 0 000t + 00 0.0004 + 00 2.57H. 46 3 4281 22 AS.St 2 560t + 02 1.47H + 05 4.4Mt.53 0 00M

00 0 000t + 00 0.000t + 00 5.3Mt. 54 39611 26 14 09 1400t + 06 2.50H + 04 1.4518 + 06 3 0144 + 08 1475E + 08 3.6178 + 07 3.0461 + 09 9 Mit+09

$A 90 99208+07 0.00H + 00 4 6008 + 10 1.2448 + 10 14281 + 10 1.493 + 09 9.620t + 10 6.4461 + 11 1 $A 91 1912t + 05 2.5118 + M 1.3778 + 05 7.23H.10 0 000t + 00 86001 11 2.072t + 05. 1.451t + M (PASTURE) (P ASTURE) (f ttD) (PASTUAt) (PASTUAtl

See note, paga 3.0 36 Units -

5 Inhalation and all tritium mrem /y. per pCi/m3 Other pathways for all other radionuclides -m2

mrem /yr per pCi/sec ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) 3.0 33

l TABLE 3.2 6(continued) PATHWAY DOSE FACTORS FOR SECTION 3.2.3.3 (R,) Page 2 of 3 h ~n mn in on ~,n ..mn ebOf0*t Ihm.L. fK* 4400hD9L.hl 446 (OW M48 68%(DW bl.f 646 (OW W48 G246QTWl.I 6tb 6DT ME E YtG(f.fKim ou 4] i+ n 845n.{ u.u-um. 00 n m.48 0 00u. = no u... 2.ni. 0i

v. 0 in..e. mi.n nin. 05 udu.m i nu.05 tuu.n

.un.. uin.i. v.nM tun 3 u6u.n i nn. i. uen.00 u0u. 00 u0n. 00 uni.a tun.. 4 v.n out.. u0n.= um.

um+=

$ 6.n n wn.n $nn+n u m.0. v,u nut.. 2.un.. uni.0i 2 578.n 0 000i.00 l itet.x i.if e.0, i 40n.04 i v.n uut.n um.n u.u+n um.n u.a.u 2..n. = 84n+n uin.. n.n uni.. u3n.. .un.. uen. 0. um.* uui + 08 usu.05 u wi. 0. s n.n um.n 3 u+= uen. = u.n. = um.n um.n un.n uni.n 8.n lun.n u0u + = utn. 00 u.ti. 0. i 63.t. 07 ..>.7 00 3.nei. 07 4.7 8 04 uo.n 2 n.n um+w um.n um.n nin.n usu.= um.* um.n TC. 99M 4.1608 + 03 2.1Mt + 05 5.55n + 03 7.43M 18 0 0001 + 00 0.t278 19 6 641t+02 5.187E + 03 TC.101 3 H2t.02 2.2778 + 04 n068*lt 0 000t + 00 0 0001 e 00 0 000f. 00 $ Stet 60 3.5028 29 RU.102 5 0448 + 05 1.2658 + 08 1.10M. 05 1.229E.10 8 5378 03 1.4751

09 1426f. 04 5.5778 + 08 RU.105 4.8168 04 7.212t + 05 5.24M. 01 3.53n.25 0.000t + 00 4.23H. 26 6.2454 02 3.2Mt + 04 RU 1M t M06 + 06 5 Dett.06 1.3204 + M te t ti + 11 3 8941 + 05 2.173t + 10 1.5448 + 05 1.24n + 10 AG.110M 4.63n + 06 4.0198 + 09 2.1968 10 2.52n + 09 5.9Mt. 00 3.0288 00 2 utt + 09 3.97H + 09 TE.125M J.1Mt + 05 2.12H + 06 6.626t + 07 L460t.00 7.906t + M 1.75H + 08 7.955t + 06 3927t+08 f t.127M 9 600t + 05 1.0831 05 1.0608 00 d.5314 00 3.671E + 07 5 437E + 08 2.22n + 07 Latti+09 fI 127 5.7ME + 04 3.293t + 03 5.27H. 04 2 Het.00 0.0001 + 00 2 4414 De 61728 + 03 4.5n E. 09 n. u.M u.a. =

um.n um. = unt. 0, tuu.n 6unew uni.n u6 u,0. + ft.129 19Hf + 03 3.0768 + 04 1.1Bn. 09 0 000t + 00 0.0001 00 0 0004 00 1 421 10 2.00t.03 l TE - 131M 5.560t + 05 9.45n + 06 1.7538 07 2.190t. M 1.2ME.15 2.6284 + 03 2.102t + 06 4.428E

07 ft.131 1.392t + 03 3.450t + n 1.5768 32 0 000t + 00 0 000t + 00 0 00H + 00 192n.33 6.575(.15 ft.132 5 OME + 05 4 Met.06 7.3MI + 07 4.287f + 07 1.170t. 01 5 Met + M t.82n + M 1J12E + De 4 130 1.1Mt + M 6.692t + 06 1.0$M + 08 5.2 721. H 85Ht.46 6.3264 05 L254t + 08 9.409 07 (PA57UAt)

(PASTURI) tit t D) (PASTURE) (PASTURI) Units - Inhalation and all tritium. mrem /yr per pCi/m3 Other pathways for all other radionuclides.m2

mrem /yr per pCi/sec ODCM, V.C. Summer, SCE &G: Revision 13 (June 1990) 3.0 34 k

.m .e

.g TABLE 3.2 6(ctntinucd) I PATHWAY DOSE FACTORS FOR SECTION 3.2.3.3 (R,) 1 1 Page 3 of 3 .e~e .~, n .~, n .~< n .~, n .~, n .~, n .~ n esotopt

==4a tion enounoeune set toe wu centom weat eas tom wu 6e> 60t waat ses sot wo veostation 4 131 1.192t+07 2.009t + 07 IJtet + 11 5 0Mt + 09 2.0658 + 07 6 040t + 04 I M5I + 11 3.705t + 10 i 1 132 1 teet + 05 1.4524 + 06 1.541f + 01 1.0168 57 0.0001 + 00 2.179( $4 1 Met + 01 5.016t+03 1 133 21521 + 06 2 to1I + 06 9.0911+08 9 3Mt + 01 1.830f.23 1.120t + 01 1.1998 + 09 5.331t*08 1 1 1M 2 SMI + 04 5J05t + 05 4tMt.11 0 000t + 00 0.0008 + 00 0 0001 + 00 1 M61 10 4.5638 03 1 135 4 4401 + 05 2.M7f+06 2.217f + 06 7 Met.15 0 000t + 00 9 1728 16 2 6761 + 06 6.731t

M i

l C5 1M S 400 + 05 8007f+09 1.3451 + 10 15658 + 09 4.33H + H 1.8788 + 00 4 0351 + 10 1.1108 + 10 C5 1M i Met + 05 1.710t

00 1039t
09 4 724I + 07 3 093t + 06 5 M98+06 3.117E + 09 1.675E + 0e C5 137 6.2088 + 05 1.2011 + 10 1.010t + 10 1.itH + M 35138+09 14318 + OS 3.038 + 10 8 6Mt + Of C5 138 6 2081 + 02 4.1024 + 05 1.7861 23 0 0004 + 00 0.000( + 00 0 000t + 00 5.146E.23 7.730t 11 i

B A.139 3.40l + 03 1.1Mt + 05 7.06H. 00 0 000f + 00 0 000t + 00 0 000t + 00 9 4358 00 5.225t=02 S A.140 1.272t + 06 2.M68 + 07 5 535t + 07 5917t+07 1.472t + 05 7.100t + 06 6 643I + 06 2.M6t

00 B A.141 1.9MI + 03 4.7Mt + 04 4 3271 46 0 0001 + 00 0 000f + 00 0 0006 s,

519 H.47 9463E.22 B A.142 1.1921 + 03 5 0Mt + 04 2 509t.40 0 000t + 00 0 0008 + 00 0.0001 + 00 3 011E.01 2.443t. 39 L A.140 4 Stet + 05 2.1901 + 07 1672t + 05 1.3058 + 03 4.0598 12 1.M28+02 2.006t + 04 7.319t + 07 L A.142 6.328t + 03 9.117f + 05 6.273t. 00 0.0001

00 0 000t + 00 0 000t + 00 7.5318 00 6.764E. 01 CI 141 3 616E e 05 1.5401+07 1.25E + 07 3.632t + 07 6.4244 + 05 4.350t+06 1.50H + 06 5.0971 + 08 Ct 143 2.264E + 05 2.627E + 06 1154 + M 5.547f + 02 7.7648 15 6 6ME + 01 1.30t + 05 2.754E + 07 CE.144 7.776f + 06 8 0421 + 07 121I+08 4 928t + De 33988+07 5 tief + 07 1.451t + 07 1.1121 + 10 PR 143 2 tott + 05 0 0008 + 00 6 titt + 05 9.2Mt + 07 2 4458 + 03 1.104E + 07 8.297f + 04 2.744f + 04 PR.144 1.016E + 03 2.1128 + 03 6 716f. 54 0.000t + 00 0 000t + 00 0.000t + 00 7.7458 55 3.30H. 26 1

l ND 147 2.200f + 05 1.009t + 07 5.231t + 05 3 SME + 07 6.286E + 02 4.722E + 06 6.2738 + 04 1853E + 08 W 187 1.552I + 05 2.740t + M 1.7Mt.06 5 912t + 00 3 7071 22 7 0941 01 2.141 + 05 1 M6E + 07 NP 239 1.1928 + 05 1.9768 + 06 7.4094 + 04 5.152t + 03 7.5458 00 6.182t + 02 4 8764 + 03 2 8721 + 07 (P A57Unt) (PASTURE) (f ttD) (PA5Tunt) (PA5 TURI) Units - Inhalation and all tritium mrem /yr per pCi/m3 Other pathways for all other radionuclides m2

mrem /yr per pCi/see t

ODCM, V.C. Summer, SCESG: Revision 13 (June 1990) 3.0 35 t

O-NOTE: The R, values of Table 3.2.'. through 3.2 6 were calculated in accordance with the methocs of Section 5.3.1 of Reference 1. Columns in those tables marked " Pasture" are for freelp grazing - animals (f,= f,= 1). Columns marked " Feed" are for animals fed solely locally grown stored feed (f,= f,= 0). The values used for each parameter and the origins of the values are given in Table 3.2. 9 and its notes. O 9 ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) 3.0 36 I

fs l Table 3 N CONTROLLING RECEPTORS, LOCATIONS, AND PATHWAYS * \\ DISTANCE AGE ORIGIN SECTOR (METERS) PATHWAY GROUP (FOR INFORM ATION ONLY) N" 6,400 Vegetation Child Vegetable Garden i NNE 5,800 Vegetation Child Vegetable Garden ' l 5,300 Grass / Cow / Meat Child Grazing Beef Cattle NE 4,700 Vegetation Child Vegetable Garden 4,700 Grass / Cow / Meat Child Grazing Beef Cattle ENE 2,600 Vegetation Child Vegetable Garden E 2,900 Vegetation Child Vegetable Garden 2,700 Grass / Cow / Meat Child Grazing Beef Cattle L ESE 1,800 Vegetation Child Vegetable Garden I SE 2,400 Vegetation Child Vegetable Garden SSE 4,300 Vegetation Child -Vegetable Garden l t 5' 6,300 Vegetation Child Vegetable Garden l SSW*

5,500 Vegetation Child

-Vegetable Garden SW 5,300 Vegetation Child Vegetable Garden WSW 3,100 Grass / Cow / Meat Child Grazing Beef Cattle W 4,300 Vegetation Child Vegetable Garden 3,400 Grass / Cow / Meat Child - Grazing Beef Cattle 6 I WNW*

7,200 Vegetation Child Vegetable Garden 7,200 Grass / Cow / Meat Child Grazing Beef Cattle NW a
6,600 Vegetation Child Vegetable Garden 6,600 Grass / Cow / Meat Child Grazing Beef Cattle NNW 4,800 Vegetation Child Vegetable Garden 4,800 Grass / Cow / Meat Child Grazing Beef Cattle See note on the following page for the method of choice of these controlling receptors.

If a cow were located at 5.0 miles (8,000 meters) in this sector, an infant I consuming only its milk would receive a greater total radiation dose than would i the real receptor listed. However, such an infant would not be the Maximum Exposed Individual for the site. ) ODCM, V.C. Summer, SCE&G. Revision 13 (June 1990) 1 3 0-37 t ---r---- ~ _ _,. - _,...,,,, _. _ - ~,,, .--..._,--o n--y...

g. e NOTE: The controlling receptor in each sector was identified in the following way. Receptor locations and associated pathways were-obtained from the August 1989 field survey. A child was assumed at each location, except that where a milk cow was listed, an infant was assumed. X/Q' for each candidate receptor was obtained by interpolation of values in Table 6.1 10 of Reference SjEQ' for each candidate receptor was obtained by interpolation of values in Table 6.113 of Reference 5. Expected annuel. releases of each-nuclide were taken from Table 5.2 2 of Reference 5. The pathway - dose factors given above in Tables 3.2 3 and 3.2 4 were then used with the referenced values in the methodology of Section 5.3 of Reference 1 to compute total annual doses at each candidate receptor site for the pathways existing at that site. The controlling receptor for each sector was then chosen as the candidate receptor with the highest total annual dose of any candidate receptor in the. given sector. Alllisted pathways are in addition to inhalation and ground plane exposure. O I 'l O ODCM, V.C. Summer, SCE & G: Revision 13 (June 1990) l 3.0 38

L Table 3.2-8 ATMOSPHERIC >lSPERSION PARAMETERS FOR CONTROLLING RECEPTOR LOCATIONS

DISTANCE 1

SECTOR R R (MILES / METERS) i N 1.4 E 07 6.2 E-10 4.0/6,400 NNE 2.1 E 07 8.9 E 10 3.6/5,800 ') . NNE 2.5 E 07 1.1 E-09 3.3/5,300 1 NE 3.4 E 07 1.7 E.09 2.9/4,700 ] ENE 1.1 E 06 5.8 E-09 1.6/2,600 E 7.4 E 07 . 3.6 E 09 -1.8/2,900 s E 8.4 E 07 4.2 E 09 1.7/2,700-ESE 2.2 E 06 8.4 E 09 1.1/1,800 ) SE 1.6 E 06 5.8 E 09 1.5/2,400 i SSE 3.0 E 07 1.0 E 09 2.7/4,300 i S 1.7 E 07 3.7 E 10 3.9/6,300 O SSW 2.0 E 07 6.4 E 10 3.4/5,500 SW 2.6 E 07 1.0 E 09 3.3/5,300 WSW 6.4 E-07 3.2 E-09 1.9/3,100 W 2.2 E-07 9.3 E 10 2.7/4,300 W 3.6 E 07 1.7 E 09 2.1/3,400 l WNW 6.6 E 08 2.5 E 10 4.5/7,200 NW 9.8 E 08 4.1 E 10 4.1/6,600 NNW 1.8 E 07 9.7 E 10 3.0/4,800 2 Annual average relative dispersion and deposition values for the receptor locations in Table 3.2 7. Values were obtained by interpolation in Tables 6.1 10 ' and 6.113 of Reference 5. Those tables are based on one year (1975) of 1 meteorological readi;#p, and the FSAR dispersion model (ground level rel' ease, sector averaged model, with open terrain recirculation factors, dry depletion by j Figure 3.31, and using decay with a half life of 8.0 days). As a result of the. analysis described in the note to Table 3.2 7, the location of the maximum 1 exposed individual for the site was identified as being the vegetable garden at 1 1.1 miles in the ESE sector. Therefore, the site X/Q' and 50'(Section 3.2.3.2 and following) are those from this table for that location. ODCM, V.C. Summer, SCE& G: Revision 13 (June 1990) 3.0 39

I _- l. Table 3.2 9 Page 1 of 4 PARAMETERS USED IN DOSE FACTOR CALCULATIONS Oriain of Value Parameter Value 5 e ion f 3 R.G.1.109 Specific g

*
For P,* * *

DFA, Each radionuclide E9 Note 2

.BR 3700 m /yr E5 3

* *For Ri (Vegetation)* *
r Each element type E1 Y,

2.0 kg/m3 E 15 Aw 5.83 E 7 sec 5.3.1.3

DFL, Each age group and radio-E 11 thru Note 2 nuclide E 14 Ua' Each age group -

E5 f 1.0 t .5.3.1.5 t 8.6 E + 4 seconds - E 15 t U/ Each age group E5 f 0.76 y 5.3.1.5 t,, 5.18 E + 6 seconds E 15 H 8.84 gm/m3 Note 1

* *For Ri(Inhalation)"*

BR Each age group E5

DFA, Each age group and nuclide E-7 thru Note 2 E 10 0

ODCM, V.C. Summer, SCE & G: Revision 13 (June 1990) 3.0 40

y 4 i Table 3.2 9 P.gpe 2 of 4 PARAMETERS USED IN DOSE FACTOR CALCULATIONS 1 Oriain of Value carameter Value Section of Table.in Site-R.G.1 109 N REG- $,,cf;c ] Plane)* *g(Ground

- - For R 1

SF 0.7 E 15 DFC-Each radionuclide E6 t 4.73 E + 8 sec 5.3.1.2 1

- - For Ri (Grass / Animal / Meat)**
1 Q, (Cow) 50 kg/ day E3 l

Q, (Goat) 6 kg/ day E3 U,n Each age group E5 Aw 5.73 E 7 sec" 5.3.1.3 F,(8oth) tach element E1 r Each element type E 15 -

DFL, Each age group and nuclide E 11 thru Note 2 E 14 f

1.0 Note 3 n f. 1.0 Note 3 i Y, 0.7 kg/m3 E 15 l 7.} E + 6 m E 15 -t n Y, 2.0 k /mi E-15 1 tt 1.73 E + 6 5ec E 15 H 8.84 gm/m3 Note 1 ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) ~ 3041

p e f Table 3.2 9- ~ Page 3 of 4 - PARAMETERS USED IN DOSE FACTOR CALCULATIONS Oricin of Value Parameter Value Section'of Table in Site. N R.G.1.109 IDifiC 0133

*
For R Note 4 (Grass /Abimal/ Milk)***

Or (Cow) = 50 kg/ day E3 Or (Goat) 6 kg/ day E3 U,,, Each age group E5 Aw 5.73 E 7 sec ' 5.3.1.3 'F, Each element E1&E2 ^ Each element type E 15 r

DFL, Each age group and nuclide E 11 thru E-Note 2 14 Y,

0.7 kg/m E 15 j 2 t, 7.78 E + 6 sec E 15 Y, 2.0 kg/m E 15 2 t, 1.73 E + 5 sec E-15 f, 1.0 Note 5 f, 1.0 Note 5' f, 0.0 Note 5 - f, 0.0 Note 5 H 8.84 gm/m3 Note 1: I O i ODCM, V.C. Summer, SC E 8 G: Revision 13 (June 1990) 3042

t j i ( Table 3.2 9(Continued) Page 4 of 4 NOTES I 1. Site specific annual average absolute humidity. For each month, an average i absolute humidity was calculated from the 7 years of monthly average f temperatures in Table 2.3-49 of Reference 4 and the 5 years of monthly average dew points in Table 2.3-64 of Reference 4. The 12 monthly values were averaged to obtain the annual average of 8.84 gm/m. (Section 5.2.1.3 3 of Re 'erence'1 gives a default value of 8 gm/m..) 8 i 2. Inhal ation and ingestion dose factors were taken from the indicated source. For each age group, for each nuclide, the organ dose factor used was the highest dose factor for that nuclide and age group in the referenced table. 3. Typically beef cattle are raised all year on pasture. Armualland surveys have indicated that the small number of goats raised within 5 miles typically are used for grass control and not food or milk. Nevertheless, the goats were treated as full meat and milk sources where present, despite the fact that - f their numbers cannot fustain the meat consumption rates of Table E 5 of i Reference 3. 5 4. According to the August 1989 land use census, no cows or goats are kept for l milk within 5 miles of the Station. These values are included for reference i only. t 5. Two columns of R,'s were calculated - one for cows kept exclusively on local i pasture (f, = f, = 1), and one for cows kept exclusively on locally grown stored { feed (f, = f, = 0). See the note on page 2.0 37. l I L r l l. O I L ODCM, V.C. Summer, SCE8G: Revision 13 (June 1990) 3.0 43 v-*. v-- ,_-.m ,_-w --w,

GASEOUS RADWASTE TREATMENT SYST EM h>) e ! FIGURE 3.21 si eI g. e e s Il il il li li li il il Il il L. li li i i = a n a i n

+

lil *: i* lil +i i i e i* lil *i O !ll +:! + !!+ lil +i !!+ 1 +9 l i l + 1il + 2 lil + + +- Oh I, r i, qI,, g [ 1 i I Is li il I til ! lI . Il 1 1 6 ii' I! III 1 t............. I ! ? i II

NblIIf, f

I g ODCM, V.C. Summer, SCE&G; Revision 13 (June 1990) 3.0 44 i

_. -. ~ _. h j ~ l I 3.3 Meteorolooical Model for Dose Calculat'ons j O 3.3.1 Meteorolooical Model Parameters Section of Term Definition Initial Use b height of the containment building. (3.3.2.1) = 1 4eposition rate fcst ground level re-(3.3.2.2) D' = , )ses relative to the distance from Qe containment building (from c Figure 3.3 3). D/O = the sector averaged annual average (3.3.2.2) relative deposition for any distance in a given sector (m 2). i wind speed class. The wind speed classes are = given in Table 4A of Reference 10 as 13,4 7,812, 1 1318,19 24, and > 24 miles per hour. total hours of valid meteorological (3.3.2.1) N =

data, number of hours meteorological (3.3.3.1) n,'

= conditions are observed to be in a .l 7 given wind direction, wind speed ( class i, and atmospheric stability class J. 1 number of hours winc'is in given direction. (3.3.2.1) n = distance from the co itainment building (3.3.2.1) r = to the location of in terest for dispersion calculations (m). AT/AZ = temperature diHerential with vertical (3.3.2.1) separation ('K/100m). terrain recirculation factor, Figure (3.3.2.1) j T = 3.3 4. j I u, wind speed (midpoint of wind speed (3.3.2.1) = class i) at ground level (m/sec). X/Q = the highest annual average relative (3.3.2a) concentration at anE), distance in a given sector. (sec/m plume depletion factor at distance r (3.3.3.1)- 6 = l from Figure 3.3-1. a ODCM, V. C. Summer, SCE &G: Revision 13 (June 1990) g. 3.0 45 5

L Section of Term Definition initial Use vertical standard deviation of the plume (3.3.2.1) o, = (in meters), at distance r for ground level releases under the stability category indicated by.1T/ A2, from Figure 3.3 2. 2.032 (2/n)"2 divided by the width in radians of a (3.3.2.1) = 22.5' sector (0.3927 radians). 2.55 = the inverse of the number of radians in a 22.5' sector (3.3.2.2) 1 (22.5')(0.0175 Radiansf') 3.32 Meteoroloaical Model 3.3.2.1 Atmospheric dispersion for routine venting or other routine gaseous effluent releases is calculated using a ground level, wake corrected form of the straight line flow model. X/Q the sector averaged annual average relative concentra- = tion at any distance in the given sector (sec/m ) 3 i 2 032 6rT (52) = i Nru }.,,. where: 2.032 = (2/n)i 2 divided by the width in radians of a 22.5* sector (0.3927 radians). S= plume depletion factor at distance r for the appropriate stability class from Figiare 3.31. i = wind speed class. The wind speed classes are.given in Table 4A of Reference 10 as 13,4 7,812,1318,19 24, and > 24 miles per hour. number of hours meteorological conditions are observed to be n,, = in a given wind direction, wind speed class i, and atmospheric stability class j. 9 ODCM, V. C. Summer, SCE&G: Revision 13 (June 1990)- 3.0 46 !j

l,s. L. l total hours of valid meteorological data. l N = l distance from the t'ontainment building to location of interest r = (m) wind speed (midpoint of wind speed class i) at ground level l u, = (m/sec). l

Ac lawr of io,2 + 6 /2nd or. ( V3 o,)

l 1, 8 =- (53) where: vertical standard deviation of the plume (in meters) at o, = distance r for ground level releases under the stability l category indicated by AT/ AZ, from Figure 3.3 2. T = terrain recirculation factor, from Figure 3.3 4 l 3.1416 n = b = height of the containment building (50.9m) AT/AZ = temperature differential with vertical separation (*K/100m). l 3.3.2.2 Relative deposition per unit area for all releases is calculated for' a ground level release. I D/O the sector averaged annual average relative deposition = at any distance in a given sector (m ). 4 = 2.55 D n (54) g rN where D, deposition rate for ground level releases relative to = distance (r) from the containment building (from Figure 3.33). Pb ODCM, V. C. Summer, SCE&G: Revision 13 (June 1990) 3.0 47

G, 2.55 the inverse of the number of radians in a 22.5* sector =. 1 (22.5')(0.0175 Radiansf) number of hours wind is in given direction (sector). n = N total hours of valid meteorological data. = 4 O gj ODCM, V. C. Summer, SCE&G: Revision 13 (June 1990) 3.0 48

_ls l FIGURE 3.31 Plume DefAll Atmospheric Stability Classes)letion Effect for Gro Graph taken from Reference 8, Figure 2 I i l l / / / t { \\ I i / I t 1 - f / lO l L / l t i 7 I I i I I I I I E N 5 i FRACTION REMAINING IN PLUME ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) 3.0 49 ! l _. -.. _. - -. - -....., ~

l I FIGURE 3.3 2 Vertical Standard Deviation of Materialin a Plume (Br) (Letters denote Pasquill Stability Classes) Graph taken from Reference 8, Figure 1 100o l r l j j /- / y y [ f f f l /,/ f ,00 s l L / l / r / / ~, / / / gf/ / s-g ./// /i/ / / ~ /// // / _/ r f / ,,.c / y ,0 s s 1 / / / ,F )~ / / / '/ / / / / 0.1 1.0 10. 100 PLUME TRAVEL otSTANCE (KILOMETERS) Temperature Chang *e. Pasquill Stability with Heiaht AT/A2 ( K/100m) . Cateaories Classification < 1.9 A Extremely Unstable 1.9 to 1.7 B Moderately Unstable 1.7 to 1.5 C Slightly Unstable 1.5 to 0.5 D Neutral -0.5 to 1.5 E Slightly Stable 1.5 to 4.0 F Moderately Stable >4.0 G Extremely Stable ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) h 3.0 50

l s i FIGURE 3.3 3 t Relative De position for Ground Level Releases (Dg) i (Al Atmospheric Stability Classes) ,i 4 i Graph taken from Reference 8, Figure 6 i 10 3 t l t i h l is s i _8 h h.. ' b u g h E \\ i 1H N N { 4 ' k k 3 1 % w 3 T 1 tre s IF7 0.1 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS) ODCM, V.C. Summer. SCE&G: Revision 13 (June 1990) 3.0 51 j 1

I FIGURE 3.3-4 i .l Open Terrain Recirculation Factor @1 Graph taken from Reference 7, Figure 2 E l ') l l I J s ? I I j I / / a O! J I e / I .W + O k y e E

W h

CORRECTION FACTOR f 8 h; ODCM, V.C. Summer, SCE &G: Revision 13 (June 1990) 3.0 52 l ~.

A O 4.0 RADIOLOGIC Al. ENVIRONMENTAL MONITORING Sampling locations as required in section 1.4.1 of the ODCM Specifi-cetions are described in Table 4.01 and shown on Figures 4.01 and 4.0 2. As indicated by the ditto (") marks in the table, entries in the sampling frequer.cy and analysis frequency columns apply to all samples below the entry unto a new entry appears. l 1 l O i l l O ODCM, V.C. Summer, SCEandG: Revision 13 (June 1990) 4.0 1 l

l I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM VIRGilC. SUMMER NUCLEAR STATlON TA8LL 4.0-1 i t i. ,'Y Criteria for Selection Sampling and Samplet Locations Type & Frequency } of Sample Number & Location Collection Frequency Location Mi/Dir of Analysis AlftM: [ t Particulate A) 3 Indecator samples to be tak en at locations (in Continuous sampler opera-2 1.2SW Gross beta following filter i de f ferent sectors) beyond but as close to the tion with weekly collection. 5 0.9SE change; Quarterly. j e aclusion boundary as practicable where the 10 2.5 NNE Composite (bylocation) for highest offsite sectorial ground level gamma isotopec. { concentrations are anticipated 2 i i B) 1 Indecator sample to be taken in the sector Continuous sampler opera-6 1.0 ESE Gross beta followmg filter } beyond but as close to the exclusion boundary tion with weekly collection. change; Quarterly as practicable corresponding to the residence Composete (bylocation) for i having the highest anticipated ofIsite ground garnma isotope (. I level concentration or dose.2 i i C) 1 Indecator sample to be taken at the location Continuous sampler opera-148 6.3 W Gross beta following felter t of one of the dairies most likely to be af fected. teon with weekly collection. change, Quarterly { l 2.4 Composite (by location) for i gamma isotope (. t D) 1 Control sample to be taken at a location at Continuous sampler opera-17 24.7 5E Gross beta following filter t least 10 air miles from the site and not en the teon with weekly collection. change, Quarterly most prevaiend wind direction 2 Composite (bylocation) for gamma isotopec 1 1

i i

i 1 i ODCM, V.C. Summer, SCEandG: Revision 13 Oune 1990) 4 4.0-2 4 9 9 9., -c.+ e .m.., 4 - - + ,o e - - =.

\\ i i RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ' VIRGilC. SUMMER NUCLEAR STATION TABLE 4.0-1 ' 5 { i i Criteria for Selection Sampling and samplet Locations Type & Frequency athway of Sample Number & Location Collection Frequency. Location Mi/Dir of Analysis and/or Sample Il_ Radioiodme A) 3 Indicator samples to be taken at two locations Continuous samp8er opera-2 1.2 SW Gamma isotopic for I-13 I as givenin f(A) above tion with weekly canister 5' 0 9 SE weekly collection 10 2.5 NNE t i B) 1 Indicator sample to be taken at the location as Contmuous sampler opera-6 1.0ESE Gamma Isotopic for 1-131 i i l given in 1(B) above. tion with weekly canester weekly collection. l C) 1 Indicator sample to be taken at the location as Continuous sampler opera-14 6.3 W Ga.nma Isotopic for 8-131 given en f(C) above. tion with weekly caruster weekly collection. ) i l D) 1 Control sample to be taken at a location Continuous sampler opera-17 24.7 SE Gamma Isotopic for 1-131 l similar in nature to l(D) abova tion with weekly (anester wee 61y l l (ollection. i j. f l 111 Direct A) 13 Indicator stations to form an inner ring of Monthly or quarterly 1,2 1.2 5,1.2 SW Gamma dose monthly or stations in the 13 accessible sectors within 1 to 2 enchange 5.h two or more 3,4 1.2W,1.2 WNW quarterly. l miles of the plant. dosimeters at each location. 5.6 0.95 E,1.0 ESE 7.8 12 E.1.5 ENE -l 4 l 9.10 2.2 NE 2.5 NNE i 29. 0.9 W5W, f 30 1.0 55W 47 ~ 1.0MW i i i i [ ODCM, V.C. Summer, SCEandG: Revision 13 (June 1990) [ 4.0-3 l .,..-._--.-.-.-..,.....,-.a....-..-.-...a.-.,-.~-...---_.---...---...------.-----..:

i RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ' VIRGIL C. SUMMER NUCLEAR STATION I-TABLE 4.0-1 1 Criteria for sele (tion Sampling and Samplet Locations Type & Frequemy

Y l

of Sample Number & Location CoHettion Frequemy Location Ass / Der of Analysis ) i i B) 16 Indicator stations to form an inner ring of Monthly or quarterly 12.14 4.2 N 6.3 W Gamma dose monthly or stations in the 16 accessible sectors withen 3 io 5 enchange 51; two or more 32.33 4.5NNE.4.2ENE. quarterly. milesof the plant. dosameters at eachlocation. 34.35 4.8 E5E.4 8 SE 36.37 3.155E. 4.9 NW 41.42 3.9 5. 3 9 55W 43 5.25W 45 5 9 WSW t 46 3.7 WNW j 49 40NNW l 53.55 3 0 NE 2.8 E t C) 8 Stations to be placed in special interest areas Monthly or quarterly 11.13 3.3 N. 2.9 NNW Gamma dose month 8y or such as population centers, nearby residences, exchange 51; two or more 15.?6 2.555W 28 OW quarterly. .i schools and in 2 or 3 areas to serwe as controis dosimeters at each location 17.18 24.7 SE.16.5 5 31.54 5 8P.*NE.1.7ENE j WATER 80RNE: IV Surfa(e A) 1 Indicator sample downstream to be taken at a Time composite samples with 213F. 2.7 55W Gamma isotop.( monthly f < ~ WatGr location which allows for mining and dilution in collection every month 5 weth quarterly composite (by - the u;timate receiving river. location) to be analyzed for tritium 7 i B) 1 Controf sample to be taken at a lo(atson on Time compositesamples with 223 30 0 NNW. Gamma isotopec monthly i-the receiving river, suf ficiently far upstream collection every month.5 with quarterly (omposite (by su(h that no eIfects of pumped storage location) to be analyzed for operation are anticipated. tritium 7 j l f i ODCM, V.C. Summer, SCEandG: Revision 13 (June 1990) i 4.0-4 ~! O O O.,! a

1 I i N ~ f i I P.ADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM VIRGilC. SUMMER NUCLEAR STATION I TABLE 4.0-1 Em e Criteria for Sele tion Sampling and Sample 1 Locations Type & Frequency. p,, of Sample Number F. Location Collection Frequency Location R8i/Dir of Analyses g, i' C) 1 Indicator sample from a location immediately Timecomposite samples with 17 247 SE Gamma isotopic monthly upstream of the nearest downstream municipal collection every month 5 with quarterly composite (by water supply location) to be analyzed for ; i tritium.7 l I ( D) 1 Indicator sample to be taken in the upper Time composite samples with 233 0.5 ESE Gamma isotopec monthly' reservoir of the pumped storage facility at the collection every month 5 with quarterly composste (by i plarvt descharge canal. location) to be analyzed for ] Intium 7 I E) 1 Indecator sample to be taken in the upper Grab sampling monthly 5 243 5.5 N Gammaisotopic monthly I reservoet's non-fluctuating recreational atea with quarterly composite (by l location) to be analyred for i 4 intium 7 j t F) 1 Control sample to be tah en at a location on a Grab sampimg monthly 5 184 1655 Gamma esotopec monthly separated unaf fected watersheo reservoir. with quarterly composite (by J location) to be analyzed for 1 tritium.7 l G) 1 Indi(ator sample to be taken in the upper Time composite sampleswith 253 ' O8WNW Gamma isotopic monthly j reservoir at the intake of the pumped storage collection every month.5 with quarterly composite (by i

facility, location) to be analyzed for tritium.7 I

i ODCM, V.C. Summer, SCEandG: Revision 13 Oune 1990) 4.0-5 ...m .m. ~...-mm m. .r n w. m . m i _ m..,. 2e w. ,v.w .e.,- e-%-, -..,,..,. .-*r.

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ~ VIRGIL C. SUMMER NUCLEAR STATION TABLE 4.0-1 l l 1 Criteria for Selection Samplit g and Sample 1 Locations Type & Frequency - [ p Y of Sample Number & Location Collection Frequency Location Mi/Dit of Analysis i l V. Gic ind A) 2 indicator samples to be taken within the Quarterly grab sampling 7 26 Onsite Gammaisotopic and tritium lL Water exclusion boundary and in the direction of 27 Onsite analyses quarterly.7 potentially af fetted ground water supplies I l I j B) 1 Controf sample from unaffected location Quarterly grab sampling 7 16 .201 W Gamma isotopic and tritium i-analyses quarterly 7 l i t VI Drinking A) I fndicator sample from a nearby public giound Monthly grab sampling s 28 2 4 55E Mon.hlys gamma rsotopic Watce water supply source. and gross beta analyses anti quarterly 7 composste for } tritium analyses j i i B) 1 Indicalor (finished water) sample from the Monthly comnosite 17 24.7 5 Monthlys gamma isotopic nearest downstrcam water supply. sampling and gross beta analyses agd quarterly composite for [ 7 3 tritium analyses i C) 1 Control (finished water) sample from an Monthly composite 39 14.0 55E Monthlys gammaisotopi( I unalfe(ted water supply. sampling. and gross beta analyses and quarterly (omposite for l 7 e t tritium analyses. j i 4 + ODCM, U.C. Summer, SCEandG: Revision 13 (June 1990) ' 4.0-6 G O 9

7.- . RADIOLOGICAL ~ ENVIRONMENTAL MONITORING PROGRAM 7 V!RGIL C. SUMMER NUCLEAR STATION TABLE 4.0-1 i L " P" " Criteria for Selection Sampling and Sample 1. Locations Type & Frequency Pathway of Sample Number & Location Collection Frequency Location Mi/Dir .of Analysis ~ and/or Sample INGESTION: Vll. Milk 4 A) Samples from milking animals in 3 locations Semimor$thly when animals Gamma isotopic and A131 - analysis semimonthly #when within 5 km having the highest dose potential. age on pasture, monthly s ,*--e-animals are on pasture, if there are none then 1 sample from milking other times 5 ..*w-- monthly other times 5 animals in each of 3 areas between 5 to 8 km .u . distance where doses are calculated to be ..e greater than 1 mrem per year _10 ~ B) 1 Control sample to be taken at the location os semimonthly when animals 16 -20.1 W Gamma isotopic and 1-131 a dairy > 20 miles distance and not in the most are on pasture 8, monthly analysis semimonthlyewhen prevalent wind direction) other times.5 animals are on pasture, monthly other times. s C) .1 Indicator grass (forage) sample to be taken at. Monthly when 0 1.0 ESE - Gamma isotopic. one of the locations beyond but as close to the available 5 exclusion boundary as practicable where the : highest of fsite sectorial ground level corxentrations are anticipated? D) 1 Indicator grass (forage) sample to be taken at Monthly when i ,.e Gammaisotopic.. the location of Vil( A) above when animals are available 5 -+ *w on pasture. ODCM, V.C. Summer, SCEandG: Revision 13 Oune 1990) 4.0-7 ..c;

-~ l ' i RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ' I i . VIRGIL C. SUMMER NUCLEAR STATION . TABLE 4.0-1 l 4 ,i l i t . Criteria for Selection Sampling and Sample 1

Ocations Type & Frequency Pathway g

g ggg;_,, ,;g, g cnd/or Sample E) 1 Control grass (forage) sample to be taken at Monthly when 16 20.1 W Gamma isotopic. thelocation of Vil(B)above. available 5 i 'l Vill. Food A) 2 samples of broadleaf vegetation grown in the Montbly when available 5 6-10 ESE Gamma Isotopic on edible ; '( Products 2 nearest of fsite locations of highest calculated 8 1.5 ENE portion. annual average groemd level D/Q ii milk sampling is not performed within 3 km or if -2 milk sampling is not performed at a location ~l within 5-10 km where the doses are calculated to be greater than 1 mrem /yr.10 l t L B) 1 Controf sample for the same foods taken at a Monthly vwhen available 5 ' .18 16.5 5' Gamma isotopic on edible i location at least 10 miles distar:ce and not in portion. i l the most prevalent wind directionif milk q sampling is not performed within 3 km or if i milk sampling is not performed at a location. within 5-8 km where the doses are calculated to be greater than 1 mrem /yr.10 IX. Fish A) 1 Indicator sample to oe taken at a location in. Semiannual 9 collection of 233 0.3 Gamma isotopec on edible - the upper reservoir. the following specie types if portions semaannually 9 ' available: bass; bream, crappie; catfish, carp! forage fish (shad).- i ODCM, V.C. Summer, SCEandG: Revision 13 (June 1990). i .4.0-8 L e e e.:

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ^ - VIRGIL C. SUMMER NUCLEAR STATION TABLE 4.0-1 "E '" Criteria for Selection Sampfing and Sample 1 Locations Type & Frequency. 8 f Sample Number & Location Collectio y Frequency location 2 Mi/Dir of Analysis = , 5 B) 1 Indicator sample to be taken at a location in Semiannual 9 collection of ' '213 1-3 Gamma isotopic on. edible the lower reservoir. the following specie typesif portionssemiannually.9 available: bass; bream, crappie; catfish, carp; Iorage fish (shad). C) 1 Indicats e sarr: ole to be taken at a location in SemiannuaI9 collection of 24' 5.5-6.5. Gamma isotopic on edeble the upper reservoir's non-fluctuating the following specie typesif portions semiannually 9 recreationiI area. aJailable: bass; beeam, crappie; catfish, carp; forage fish (shad). Semiannual 9 collection of 223 30.0 NNW Gamma isotopic on edeble D) 1 Control sar iple to be taken at a location on ~ the receivirvg river sufficiently Iar upstream ' the following specie types if portions semiannually 9 such that r o ef fects of pumped storage avaitable: bass; bream, operatior are anticipated. crappie; catfish, carp; forage' fish (shad). AC. ATIC: X. Sediment - A) 1 Indicato, sample to be taken at a location in Semiannual grab sample.9 '233 0 $E5E Gamma isotopec. the upper r nervoir. B) 1 Indicator sample to be taken at a location in Semiannual grab sample.9 243 5.5 N Gamma isotopic ' the upper reservoir's non-fluctuating recreational area. - 1 ODCM, V.C. Summer, SCEandGi hevision 13 Dune 1990) ~'4.0-9 m_=..m._----. ~ or ,.---...-m.-._ ._.._m. -. -e.. ---m. .... = -.

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRh3F VIRGIL C. SUMMER NUCLEAR STATION TABLE 4.0-1 Criteria for Selection Sampling and Sample 1 ' Locations Type & Frequency f Sample Number & Location Collection Frequency - Location Mi/Dir of Analysis r SmW C) 1 Indicalor sample to be taken on the shoreline Semiannual grab sample 9 213 2.7 55W _ Gamma isotopic of thelower reservoir. i D) 1 Control sample to be taken at a location on Semiannual grab sample 9 223 30.0 NNW Gamma isotopic the receiving river sufficiently far upstream such that no effects of pumped storage operation are anticipated. / ) ODCM, V.C. Summer, SCEandG: Revision 13 (June 1990)- 4.0-10 e O-O., =

E.. ~ ~' .t ~ RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM i VIRGIL C. SUMMER NUCLEAR STATION ~ TABLE 4.0-1 NOTES 4 1 (1) location numbers refer to Figures 4.0-1 and 4.0-2. (2) Sample site locations are based on the meteorological analysis for the period of record a presented in Chapters 5 and 6, V.C. Summer Operatina License Environmental Report. ~ 1 i (3) . Though generalized areas are noted for simplicity:of_ sample site enumeration, airborne, water and sediment sampling is done at the same location whereas biological sampling sites are generahzed areas in order to reasonably assure availability of samples. 3 (4) Milking animal and garden survey results will be analyzed annually.' Should the survey indicate new dairying activity. 1 the owners shall be contacted with regard to a contract for supplying sufficient samples. If contractual arrangements can be made, site (s) will be added for additional milk sampling up to a total of 3 Indicator Locations. (5) Not to exceed 35 days. ~ (6) Time con:posite samples are samples which are collected with equipment capaole.of collecting an aliquot at time ~ intervals whicit are short (e.g hourly) relative to the composising period (7) At least once per 100 days. (8) -At least once per 18 days. (9) At least once per 200 days. The dose shall be~ calculated for the maximum organ and age group, using the guidance / methodology contained in / (10) ' Regulatory Guide 1.109, Rev.1 and the parameters particular to the Site. ({ . ODCM, V.C. Summer /SCEandG: Revision 13 (June 1990).- t ~4.0 : k +w s v ,_m.v-. w++ ow y4. .--e,- wy_.-- . k sn,. .#,c, e+ r _ -, + _ =.. .w .tv+ + m

FIGURE 4.01 Rtdiological Environm2ntal Sampling Locations (Local) D g,j/*9 6HI .~ %{.A %g e.' sl lg l Q I f I q/% g 5" ? ~ h 'p *il I, u <L ? ,T i.2 ' t h,5 i I a t, il Il,! 8 k 0 3 0g '( j} lg ~ je ~ ? s. 'a e 't ( $}' ... / .g !]a,. kj-. ( d l 3 =. w u a a w y.'f i ....!" !/ p _h-k '!hii$il ;

{s, h

e =' (:. izgun-,...... ,....q" ilk EM.-. r 'A g i )(; S. .b-3 I

!ll! -

.5 9 m ..l" gip li!!!!p,::, - . liii' . III::li"'" i al g'D -8 ..z a

re;.i: mi
g g -

,g - i-- ~

",i,

h I. .,jyf..[p'i 2, .:u 3 gg . u.3 g ms ,4 g..r i ilqs,... ~; 4 2 { /

h. _.o

? .s c.f l, ...c 2 s .n .. c.y

:. n.

%8 ,y e -) ,..s s l",- m r r , Y :.. l a .+ i i ' t,.S../+,*.> 7.'- ii 1 cr ,sla I .fJ. fi '/ N s aygi!ln , r..t n in" i s, e. l.,,,1 *,6[,,. l }g .d - an m ,h n o, u \\

1..

7..,,.

a s.v.

es e

si !

a / J : .2 ' . \\. .e i l.i.#,# r,. - Q\\

n:l!!

"t ..e / e .I . ' 6 l g, )".- l!!! o l e ,,.s ODCM, V. C. Summer, SCEandG Revision 13 (June 1990) 4.0 12

FIGURE 4.0 2'; Radiolo9ECel Environmental Sampling t c,,,ns 4 (Remote) a b is n n y! l} lJ y as qLi li gi i 1 -ar.- g n ,t, }t,.1. .a. n >- ~. a U 85[gll 5,j g i 'h'~%>;n w,,, ,'l f y :'* W 'y

,a

,i Al J_! ,/*..4 , !.)(( y, :- y M. ~. ,] 5. L e / 4 p M f, g n hf' f (" ", j 5xsyn t 4 j 'y 1,t 1 h h _/ Q' L ,s Jg >F g *, p gl' ~, T [ it x y T / 'x ~ s j 7 s j ? 0k"' ^ I { Y }r ftlkM vtm u l IsN\\ z l ODCM' V. C. Summer, SCEanda; peVIsion 13 (June 1990) 1 4.0 33 ,l = .....m

f; <..i. y Appendix A Worked Examples of Monitor Setooint Calculations and Dose Calculations ~ A.' RM LS, RM-L7 and RM L9 Given:- V = 5100 gal Nuclide Concentrations: fr = .100 GPM H3 2.70E 2 uCi/ml = Fop 2.1E6 GPM Mn 54 .= 3.59E 7 uCi/mI* =- fx e4.35E 6 uCi/ml' l. 60 GPM Fe SS: d = = Ft =- 2.33E6 GPM.- Fe 59 5.38E 7 uCi/ml* - = C r/MPCi 8.73E-6 Co 58 5.83E 7 uCi/ml*- i =- = Atk 1.25 hr Co 60 - 2.76E 6 uCi/inl* = = Sr 89 =, 6.50E 8 uCi/mi i Sr 90 = 1.74E 7 uCi/mi 1c 99m 2.10E 7 uCi/ml* = Sb 124 5.49E 7 uCi/ml* = Sb 125 3.24E-6 uCi/ml* =- l131 ' 3.83E 5 uCi/ml* = l133 5.92E 8 uCi/ml* = Xe 133 1.12E 4 uCi/ml* = Xe 133m = 8.46E 7 uCi/ml* La 140 1.77E 7 uCi/ml* =

= make up ECg 1)

Monitor Setpoint Calculations The method outlined in section 2.1.2 by which these monitor setpoints are l calculated is as follows (see Section 2.1.1 for definitions of terms): l a) The minimum recirculation time shall be: t, = 2V/f, = 2 (5100 gal) /100 gal / min = 102 min s ODCM, V.C. Summer, SCE&G:. Revision 13 (June 1990) Appendix A 1 -

s j L

J.) n l y b) .The isotopic concentration to be released is obtained from the sum of "I the measured concentrations. t [ C,' = T_ C, + C, + C,. + C,. + Cf =i e 1.60E 4 uCi/mi + 0 + 2.39E 7 Luci/ml + 2.70E-2' uCi/ml + j = '4.35E 6 uCi/ml = 2.71E-2 uCi/ml J c) ~ Once isotopic concentrations have been determined, these' values are - t l used to calculate a Dilution Factor, DF, C DF = T + SF - MPC l 4 C C C C . C' DF = T \\ + SF .l + + +: +.M PC,_* ~ MPC ' MPC, MPC,. MPC,- T.59E-7 5.38E-7 5.38E-7 3 = + + 1 1E-4 '6E-5 IE-4 .L 2.76E-6 2.1 E-7 5.49E-7 : + + + 5E 6E-3 ~2E-5 1 3.24E-6 3.83E-5 ~ 5.92E-8L lE-4 3E-7.. IE-6 1.12E-4 8,46E-7 1.77E-7 + +- + )+0 2E-4 2E-4' '2E-4 t 6.5E-8. 1.74 E-7 4.35E 2.7E-2 +t + )+ + + 0.5. . 3E 3E-7 BE-4' L3E-3 i = 138 / 0.5 = 276 I a -t ea ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) i Appendix A-2 6

P 1 ,pc 's 5 _d)= _ The maximum permissible discharge flow rate, f,, is now calculated, ~ c - F, + f, F,_ g g f, = = g -Jfor. P,> > (g; g 1 - 2.1 E6 gpm + 60 gpm 276- ,) = 7600gpm T and,.; C^ F, = (0.9)F, ( I - [ 'l-g a = (.912.33E6 (1 -0.00000873) - '= 2.1 E6 gpm - ^ e) The dilution flow rate setpoint, F, is established at 90 percent of the. I expected available dilution flow ratei O F = (0.9) F, = (,9)2,33E6 gpm- = 2,1E6 gpm The flow rate monitor setpoint_for the effluent stream shall be set at the selected discharge pump rate (normally the maximum discharge. pump rate or zero). f) The radiation monitor setpoints-is now. determined based on the values of ECi, F, and f which were specified, The monitor response is primarily to gamma radiation, therefore, the actual setpoint is based on EC,. f G ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) Appendix A-3 l ;- l 1

.. ~ ~.. p ' [. W^)

l p

j [f ,l l 1 L .The setpoint concentration, c,is determined as follows-I d es'[C,iA) ~ l.' '( A = f,If, 7600 gpm 60gpm. = '127, If A<1,. No, release may be madec Reevaluate the alternatives pre-sented in Step d). J If A 2; 1,-Calculate c:and determine the maximum 'value for, the - actual monitor setpoint.'(cpm) from the monitor calibra-tion graph. e s 1 c,iA> = ti 60E-4 uci/mh:1271' s 8 = 2.03E-2 ~uCi/ml c h cpm equivalent to 2.03E-2 uCi/mi Reading from Figure 2.1 1' yields: .C 512,000 cpm g) Within the limits of the conditions stated above, the. specific monitori i setpoints (in uCi/ml) for the three liquid ' radiation monitors RM L5, RM L7, and RM L9 are determined as follows:- RM LS, Waste MonitorTank Discharge Line Monitor: t il c,, s 1 c, 3, t A i RM L7, Nuclear Blowdown Monitor Tank Discharge Line Monito.r: c, s 5 c, gtAs ^ .a O ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990). Appendix A 4 = = ~

9 p 1 RM' L9, Combined Liquid Waste Processing System and Nuclear Blow-: - down Warte Effluent Discharge Line Monitor. j The monitor setpoint on the common line, c, should be the same~asc c the setpoint for the mo'nitor on the active individual discharge line -(i.e., c, or c, as determined above)i y C(, s MAX ( C,y, C ) {\\ y ~ Liquid Radwaste Discharge Via lndustrial and Sanitary Waste System (RM L5). ~I -l The RM L5 setpoint should be established as close to background as. ..oractical to prevent spurious alarms and yet-alarm should-an inadvertent high concentration release occur. j l 2) Dose Calculation 'l .e The dose contribution from' all radionuclides identified in' liquid effluents. released to unrestricted. areas is-calculated using the expression *: - j D, = { A,, [ At, C,[ F, j 4=l-where: 1 f g&-_ as 60gpm - (F,1(11 2.33E6 gpm 2.6 E = =1 (8.96)(1.25)(2'.7E-2)(276) t (908)i1.25)(3.59E-7)(276) + (143)(l.25) - - (4.35E-6)(2.6E-5) + (1260)(1.25)(5.38E-7)(2.6E-5)'+ (339)(1:2'5)(5.83E-7it2.6E-5) + (958)(1.25)(2.76E-6)(2.6E-5) + (1370)(1.25 n6.'5E-8)(2.6E-5) + (258,000)i1.25i . j (l.74E-7112.6E-5) + (1.06)(1.25)(2.1 E-7)(2.6E-5) t (95i(1.251t5.49E-7)(2.6E-5ft (36.51 t l.2 51 (3.24E-6)(2.6E-Si + (486):1.25 s t3.83E-5)(2.6E-51 + 189.7)(1.251: i i 4 ~ ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) Appendix A 5' 1;

s. 4 _ l 4 -(5.92E-8 (2.6E-5)'+ (0.0476)(1.25)(177E-7st2.6E-5 =- 1.025E 5 mrem (to the Whole Body)

Dose calculation example was done only for Whole' Body,' Bone, Liver,:

Thyroid, Kidney,' Lung and GI LLI also must be done to address all= dose, receptors. B, RM L3, RM L8, RM L10 and RM L11' Normal Mode-i 'Given: -Nuclide Concentrations: i fr 100 GPM H3 = 3.71E 2 uCitral. j =- Foc ' = 3.114E5 GPM - I1314 1.04E-5 uCi/ml* = for 250 GPM 4 1133 6.14E 7 uCi/ml* = = Fe 3.46ES GPM - Cs-134 ' 1.47E-6 uCilm1* = = Cir/MPC; 8.54E-6 ' Cs 137 '1,73E-6 uCi/ml* = = i Atk 2.5 hr ' = make up ECg = 1) Monitor Setpoint CalculationsL 1 The method outlined in section 2.1.4.1 by which these monitor setpoints are calculated is as follows: ] -i a) Totalisotopic concentration and the Dilution Factor are calculated as in steps a) and b) of example A. 1 C, = 1 C, + C, + C, + C, + C { f = 1.42E-5 uCi/ml +' 0 + 0 + 3.71E 2 uCi/mi + 0 - = 3.71E 2 uCi/ml - c N-DF = 1 ,-SF e s V.04E-5 6.14 E-7 1.4 7E-6 ' l.73E-6 f 1 =' + + - 3.0E-7 1.0 E-6 9.0E-6 + 2.0E-5 1 j j - ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) q ~l Appendix A 6 l 1

.fr; . /: o + 0 + 0 + 0 + 3.71 E-2 3.0E-3 = 48/0.5 = 96 - b). The maximum permissible effluent discharge flow rate, f,, is now ^ calculated. Fac+f,. ?sc s J? []f h-de do - _--3.I l4E5 GPM + 250 GPM-v 96 = 3,245 GPM.

and, I

C F,, = to.9) F - l 1 - '\\. s y =- (0.9)(3.46ES GPM)(18.54E 6) O = 3.11ES GPM-i If f, 2 f,, releases may be ma'de as planned, j i c) ^ The dilu' tion flow rate: setpoint for minimum flow rate, L, Lis; i F established at 90 percent of the expected available diiution flow- ^! rate: F = (0.9)(F[) - = 3.114E5 GPM q r Fir v rate monitor setpoints for the Steam-Generator. BI'owdown' i. - i effluent stream shall-be set at the selected discharge pump rate-(normally the maximum discharge pump rate) f, chosen in Step b)' above. d) The Steam Generator Monitor setpoints'are,specified based on the values of E Ci, F,and f which were specified. The monitor response is-primarily to gamma radiation, therefore, the actual setpoint is based O ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) 4 Appendix A 7 .g .l l l

, fll m on E Cg. The monitor setpoint in cpm which' corresponds to the calcu-lated value c is taken-from ~the monitor calibration _ graph.- The setpoint concentration, c,is determined as follows: l ', ~ c s ] C, @ a .? f/f,,- -[ -8 = ~, 3,245 GPM 250 GPM ^l = 13 if B 11, Calculate c'and determine the maximum value for-the ' actual monitor setpoint (cpm) from the monitor calibration graph. If B < 1, No release may be made. Reevaluate the alternatives-presented in step b). C, W = (I A2E-5 uCi/mh tt 3) es 1.85E-4 uCi/mi = c '- cpm equivalent to 1.85E 4 uCi/mi-Reading from Figure 2.1_-1 yields: j C) >105 cpm ] E e) The Turbine Building Su'mp and Cond'ensate Demineralizer Backwash I l monitor setpoints are established independently'of:each other-and ~ without crediting dilution.:They are based on the' measured radio-1 nuclide concentrations of the' effluent stream and areL to ensure. compliance with the limits'of 10CFR 20, Appendix B, Table 11, Column 2 prior to discharge. For each effluent stream, a concentration factor CF must bei calculated, measuring-the nearness of' approach'oi the undiluted ] ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) Appendix A 8 l 1 j - =.

.y 4 '

waste stream to the specified limiting condition of the Maximum - Permissible Concentration. That is, C CF = [. s SF 4 4-If CF :51, calculate c and determine the ' actual monitor. setpoint (cpm) from the calibration curve. If CF > 1,no release may be.made vic :his path. The release must L either be delayed or diverted for' additional processing. [ Because of spurio'us alarms, these remedial steps may be required if the monitor setpoints are only near'the actual. concentrations being released. f) Within the limits of the conditions stated above, the specific monitor setpoints (in uCi/ml) for 'the'two Steam Generator Blowdown monitors RM L3 and RM L10 and the setpoints for RM L8 and RM L11 - 'are now calculated. Because they are primaril sensitive to gamma - radiation, their setpoints will be. based on the concentrations gamma emitting radionuclides as follows: For RM L3, Steam-Generator Blowdown Discharge. initial me.nitor, and for RM L10, Steam Generator Blowdown Discharge fin'ai monitor: [ C, g (B) -c ore s gg e For RM LS, Turbine Building Sump Discharge Monitor: 5 C, 7 + CF cs 7 7 a For RM L11, Condensate Demineralizer Backwash Discharge Mon _itor: [ C, y + CFy cs y e ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) t Appendix A 9 i 4 -~

o. i

-f a 2) Dose Calculation -i -The dose contribution from all radionuclides identified in liquid effluents released to t,nrestricted areas is calculated using the 1 L expression *: D, =.: [. Aj.[.itgCjff where: i.'h lei 2500gpm-k. (F in ). ' 3.46E5 gpm g 7.2 E-41 = =V (8.96)(2.5)(3.7E-2)(7.2E-4) + (486)(2.5)(1.04E-5)(7.2E-4i + (89.7)(2.5) (6.14 E-7')(7.2E-4i + (589,000)(2.51'(1.47E-6)(7.2E-4 i + (34 8,000) .I (2.5)(1,73E-6)(7.2E-4) = 3.25E 4 mrem (to the Whole Body)

Dose calculation ' example was done only for Whole Body,' Bone, Liver, Thyroid, Kidney, Lung and GI-LLl'also must be ~done to address all-dose receptors.

A C. RM A3 and RM-A4 ' Given: . Nuclide Concentrations: X/Q = 5.3E-6 sec/m3 Kr-85m. .1.1E 6 uCi/mi-1 = 3.5E 7 uCi/ml-L, Fv 481 cc/sec Kr 88 = = l! 0.6 hr Xe 131m = 3.9E 6 'uCi/ml Atk = Xe-133 '8'5E-4 uCi/mi = t Xe 133m ~ = 1.2E 5 uCi/mi Xe-135 S.1E 5 uCi/ml = 1-131 -= f,.73E 8 uCi/ml I. (0.6 hr)(3600 sec/hr)(481 cc/sec) = 1.04E6 c: Cv = 3.54 cpm (summed Noble tias concentrations, used Example Noble Gas Calibration Curve, Figure 3.1 1). ODCM, V.C. Summer, SCE&G. Revision 13 (June 1990) 3 Appendix A 10 1 l.

p.. O.. 1) Monitor Setpoint Calculations a The method outlined in section 3.1.2 by which the Station Vent Noble Gas Monitor setpoints are calculated is as followsi a) Determine the count rate per mrem /yr to th'e total body (R )t R,= C,/ LX/ y e (F, ) ( [ K, X,,,i E {tl.17E3 M I.l E-61+11.47E4 H3.5E-7) k = 3.5E4 epm i 15.3 E-6 X481 l .g i + 19.15 El H3.9E-6) + t2.94 E2 W 8.5E - 4 ) + t2.51 E2 H l.2E - 5) + (1.8 t E3 H5. l E-5)) = 3.5E4 /(5.3E-6 H481 N0.352: = 3.9E7 cpm / mrem /yr - b).. Determine the count rate per' mrem /yr to the skin'(Rs) I R, = C, / (X/Qi (F,,1( .'( li, + 1.1 Af,") X,,) . i = 3.5E4 / 5.3E-6 X4 81 ) {I2.8E3x t.1 E-6) + t 1.9E4)(3.5E-7) +(64 8) (3.9E - 6 ) + (3.9 E2 X 8.5 E - 4 i + 11.4 E3 x t.2E-51 + t 4 E3 x 5.1 E-5 )} I = 3.5E4 /(5.3E-6 M481 H0.566) ~ N = 2.4E7 cpm / mRemlyr - t c) Determine the count rate at the alarm setpoint level. ~This will be less than or equal to the lesser of: O ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) Appendix A-11 i i L.J

= .,. l .c 4 i (0.25)(R )(500 mrem /yr), or.. i t 9 (0.25)(Rs)(3000 mrem /yr) i (0.25)(3.9E7)(500) = 4.9E9 cpm (0.25)(2.4E7)(3000) = 1.8E10 cpm so use 4.9E9 cpm 1 d)- If two simultaneous releases out of the main plant vent should occur,L ~ calculate the setpoint for each type of release and use-highest l' setpoint obtained. ? 2) Dose Calculation i a) Unrestricted Area Boundary Dose Rate (Section 3.2.2) ) D, = 5 ' 1 E, Q, (merm lyr) l l e = 5.3E-6 (1.2E3)(481)(1.lE-6) + t1.5E4)(481)(3.5E-7) + 19 2Eli(481)(3.9E-6) + 12.9E2)(481118 SE-41 + (2.5E2)i4816 (1.2E-5) + (1.8E3)(4811t5. l E-5). 9E 4 mrem /yr to total body. = -t D, = X/Q 1(L,.+ 1.1 M,nQiD, = X/Q 1 K Q, i(mremlyr) "8 i = 5.3E-6 [ (1460 t (1.1)(1.2E311:481 Jil.1E-6s - 12370 + (1.1)(1.5E4il t s ( (481l(3.5E-7) + (476 + (1.1:I1.5E2)lt4811(3 9E-6i + 1306 + (1.1) <3.5E2)l(481it8.5E-41 + 1994 + al;l1(3.3E21l4481 n1.2E-51 + (1860 + (1.llti.9E3)l(481)(5 l E-5) ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) - Appendix A-12 I-t (,' l

F- ,t. = 2.1E 3 mrem /yr to skin. D;=- XIQPf = (5.3E 6)(1.624E + 7)(6.73E 8)(481) = 2.8E 3 mrem /yr (Organ Dose Rate)- b) . Unrestricted Area Cbse to Individual (Section 3.2.3)- 4 D, n 3.17E-8 M,M Q, } = 317E-8 [ lil.2E36t5 3E-6Hl.lE-6sil t:4E61 + t l'.5E41:5 3E-6H3.5E-7:1 4 11.04 E61 + ti.6E2H5.3E-6.<3.9E-61tl.04 E6: + 1353H5.3E-6H8.5E-410.04E61 + 1327H5.3E-6tti,2E-5Hl.04E61 + tl.9E3it5.3E-61t5.lE-5itt.04E61) = 5.6E 8 mrad y air dose. D, = 3.17E-8 N, X/Q Q, = 317E-8 (t2.063H5.3E-6Hl lE-6)(ILO4E66 t (2.9E3H5.3E-6H3

E-7)

(104E6 + (I IE3H5.3E-6H3.9E-6Hl.04E6) + (1,lE3H5.3E-6H8.5E-4Hl.04E61 e (1.5E3H5.3E-61tl.2E-5Hl.04E61 + (2.5E3H5.3E-6H5,lE-5Hl.04E611 = 1.82E 7 mrad p air dose. Dj = 3.17E-8 R W Q' 9 = 317E-81 lll.624E7)(2.2E-6 t6.73E-81tl.04E6i + (2.087E7H8.4E-91 u O ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) Appendix A-13

yy -.. p -1 1 16.73E-8111.04 E6) + (4.754 El 0 H 8,4 E-9) t6.73 E-8it t.04E61 l 9 ;< 1.68E 7 mrem individual dose due to radioiodines and radionuclides = s in particulate form with tg > 8 days. j D. RM A10 i Given: X/O = 5.3E 6.5ec/m 3 . Kr 89 =~ 1E 5 uCi/ml 1) - Monitor Setpoint Calculation Permissible release conditions for the Waste' Gas System are defined in terms of both radionuclide concentration and waste gas flo'w rat'e (using previous: i nuclide concentrations), a) . The maximum ' permissible flow rate is set on the same basis but include the engineering safety factor of 0.5. The RM A10 setpoint. level 5,is Mned as: S, $ 1.ac i b). The maximum permissible' waste gas flow rate fg (cc/sec) is. calculated from the maximum permissible dose rates at'theisite boundary according to: i .e f, L the lesser ~of f, or f, f, =.the maximum permissible discharge rate' based lon total body dose rate. 0.25 X 500 mremlyr (X/Q X 1.5) (X X K) i g = (0.25)(500)/ 5.3E 6)(1.5((1E 5)(1.66E4)) l = 9.47E7 cc/sec .l ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990). Appendix A 14 1

^'a-g.. o I f, = the maximum permissible discharge rate based on skin dose rate. 0.25 X 3000 mrrmlyr ~ _ ex/Q)n.5)1X,a 86+IIM/ = (0.25)(3000) / 5.3E-6)(1.5((1E 5)(1.01E4 + 1.1(1.73E4))) b = 3.24E8 cc/sec - so-fw L 9.47E7 cc/sec c) When a discharge is to be conducted, valve HCV 014 is to be t opened until: (a). the waste gas discharge flow rate reaches (0.9) (f,) or - (b) the count rate of the plant vent noble gas monitor RM A3 1 approaches its setpoint, whichever is reached first. 4 O.1 Alternative Methodoloov for Establishino Conservative Setooints (using E. previous nuclide concentrations)- i A more conservative setpoint is calculated to minimize requirements;for adjustment of the monitor'as follows: -1. - For a plant vent: R,' = conservative count rate per mrem /yr to the total body (Xe-i 133 detection, Kr 89 dose). = C,' + [(X/Q) (K.g) (X,.') (F,)),' n i Note: C,'is based on the given Kr 89 concentration being applied to the Example Noble: Gas Monitor Calibration Curve, Figure 3.1-1. = 3.3E4 cpm /[(5.3E 6)(16,600)(8.5E-4)(481) = 9.2E5 cpm R,' = count rate per mremlyr to the skin, a ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) Appendix A 15

y .g7 ..c = lC,' '+ [(X/Q) ((L,,.,, +.1.1 M,,.,,)) (X,') (F,)) = -3.3E4 cpm![(5.3E 6)(29,130)(8.5E-4)(481), = 5.2E5 cpm-2. For the waste gas decay system: f,' the censervative maximum permissible discharge rate. = based on Kr 89 total body dose rate.- .(0.2 5) (0,,) + [(X/Q) (1.5) (X,')(K,,,,,)] = -(0.25)(500)/(5.3E-6)(1.5)(9.18E 4)(1.7E4) =' 1.01 E6 cc/sec. = f,' the conservative maximum permissible discharge rate- = based on Kr-89 skin dose rate. (0.2 5) (D ) + [(X/Q) (1.3) (X ') (L,,.,,'_ +.1.1 M,.,)) - = 33 _ o x (0.25)(3000)/(5.3E-6)(1.5)(9.18E 4)(2.9E4) = 3.54E6 cc/sec = U j ? N l i ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) Appendix A-16 -}}

ML20058P670

Text

K,((U,/D ) + U,BF,) DF (32) n FL

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