ML20138H719

Rev 22 to ODCM for VC Summer Nuclear Station

ML20138H719
Person / Time
Site:	Summer
Issue date:	09/06/1996
From:	Blue L, Sowell J SOUTH CAROLINA ELECTRIC & GAS CO.
To:
Shared Package
ML20138H706	List: ML20138H708 ML20138H714 ML20138H719 RC-97-0089, Forwards Annual Effluent & Waste Disposal Rept for Operating Period Jan-Dec 1996 & Revs 21 & 22 to ODCM for VC Summer Nuclear Station
References
PROC-960906, NUDOCS 9705070258
Download: ML20138H719 (180)

Text

{{#Wiki_filter:-. ~, FORMATION ON_Y O l Control Copy No. l OFFSITE DOSE CALCULATION MANUAL FOR SOUTH CAROLINA ELECTRIC AND GAS COMPANY l VIRGIL C. SUMMER NUCLEAR STATION Approval 6 M [M / //s/ft General Manager, Date Nuclear Plant Operations l 4 PSRC Approval Date Revision 22 August 1996 Reviewed by: M / g/zg/96 9 6 Date Approved by: v4__ / 9.J% V V %i Date !O l g50 gggg y8 5 R

.~ O LIST OF EFFECTIVE PAGES Pace Revision Pace Revision i 21 1.0-34 21 ii 21 1.0-35 21 iii 21 1.0-36 21 iv 21 1.0-37 21 v 21 1.0-38 21 vi 21 1.0-39 21 vii 21 1.0-40 21 viii 21 1.0-41 21 ix 17 1.0-42 21 x 21 1.0-43 21 xi 21 1.0-44 21 1.0-45 21 i 1.0-46 21 j 1.0-47 21 1.0-1 21 1.0-48 21 1.0-2 21 1.0-49 21 1.0-3 21 1.0-50 21 l 1.0-4 21 1.0-51 21 1.0-5 21 1.0-52 21 1.0-6 21 1.0-53 21 1.0-7 21 1.0-54 21 i 1.0-8 21 1.0-55 21 L 1.0-9 21 1.0-56 21 l 1.0-10 21 1.0-57 21 1.0-11 21 1.0-12 21 2.0-1 21 1.0-13 21 2.0-2 21 3 1.0-14 21 2.0-3 21 1 1.0-15 21 2.0-4 21 1.0-16 21 2.0-5 21 1.0-17 21 2.0-6 21 1 1.0-18 21 2.0-7 21 1.0-19 21 2.0-8 21 1.0-20 21 2.0-9 21 1 1.0-21 21 2.0-10 21 1.0-22 21 2.0-11 21 1.0-23 21 2.0-12 21 1.0-24 21 2.0-13 21 1.0.25 21 2.0-14 21 1.0-26 21 2.0-15 21 1.0-27 21 2.0-16 21 1.0-28 21 2.0-17 21 1.0-29 21 2.0-18 21 1.0-30 21 2.0-19 21 1.0-31 21 2.0-20 21 1.0-32 21 2.0-21 21 1.0-33 21 2.0-22 21 1 O ODCM, V.C. Summer /SCE&G: Revision 21 (March 1996) i ~

~. . -. ~ ~~ e, O LIST OF EFFECTIVE PAGES (continued) Pace Revision Pace Revision 2.0-23 21 3.0-26 13 2.0-24 21 3.0-27 13 2.0-25 21 3.0-28 13 2.0-26 21 3.0-29 13 2.0-27 21 3.0-30 13 2.0-28 21 3.0-31 13 2.0-29 21 3.0-32 13 2.0-30 21 3.0-33 13 2.0-31 21 ~ 3.0-34 13 2.0-32 21 3.0-35 13 2.0-33 21 3.0-36 13 2.0-34 21 3.0-37 16 2.0-35 21 3.0-38 17 2.0-36 22 1 3.0-39 17 2.0-37 21 3.0-40 13 2.0-38 21 3.0-41 13 2.0-39 21-3.0-42 13 2.0-40 21 3.0-43 14 2.0-41 21 3.0-44 13 2.0-42 21 3.0-45 16 2.0-43 21 3.0-46 16 3.0-47 16 ( 3.0-1 13 3.0-48 13 3.0-2 13 3.0-49 13 3.0-3 17 3.0-50 13 3.0-4 13 3.0-51 13 3.0-5 13 3.0-52 13 3.0-6 17 3.0-7 13 4.0-1 13 3.0-8 18 4.0-2 20 3.0-9 13 4.0-3 20 3.0-10 19 4.0-4 20 3.0-10A 16 4.0-5 20 3.0-11 13 4.0-6 20 3.0-12 15 4.0-7 20 3.0-13 14 4.0-8 20 3.0-14 13 4.0-9 20 3.0-15 16 4.0-10 13 3.0-16 17 4.0-11 18 3.0-17 16 4.0-12 18 3.0-18 13 .4.0-13 18 3.0-19 13 3.0-20 13 3.0-21 13 3.0-22 13 3.0-23 13 3.0-24 13 3.0-25 13 O ODCM, V.C. Summer /5CE&G: Revision 22 (August 1996) ii

O Table of Contents PAGE List of Effective Pages i Table of Contents. iii Li st of Ta b l es................................................ v Vi List of Figures References vii i ntrod u cti o n.................................................... viii Responsibilities ix 1.0 SPECIFICATION OF CONTROLS l 1.1 Ll a uid E fflu ents.................................... 1.0-1 1.1.1 Radioactive Liquid Effluent Monitoring Instrumentation 1.0-1 1.1.2 Liquid Effluents: Concentration 1.0.............. 1.1.3 Uquid Effluents: Dose....................... 1.0-14 ( 1.1.4 Liquid Waste Treatment 1.0-15 1.2 Gaseous Effluents.................................. 1.0-17 l 1.2.1 Radioactive Gaseous Effluent Monitoring Instrumentation 1.0-17 1.2.2 Gaseous Effluents: Dose Rate................ 1.0-22 12.3 Gaseous Effluents: Dose - Noble Gas.......... 1.0-25 1.2.4 Gaseous Effluents: Dose-Radioiodines, Tritium I and Radioactive Materials in Particulate Form.. 1.0-26 l 12.5 Gaseous RadwasteTreatment 1.0-27 1.3 Radioactive Effluents: Total Dose................... 1.0-29 l 1.4 Radiolcaical Environmental Monitorina.............. 1.0-31 1 1.4.1 Monitorin g Progra m......................... 1.0-31 1.4.2 Land Use Census 1.0-41 1.4.3 Interlaboratory Com parison Program 1.0-43 1.5 Bases 1.0-44 l 1.6 Reportina Reauirements........................... 1.0-52 1.6.1 Annual Radiological Environmental Operating Report 1.0-52 1.6.2 Annual Radioactive Effluent Release Report 1.0-53 1.6.3 Major Changes to Radioactive Waste Treat.... ment System (Liquid and Gaseous)............ 1.0-54 1.7 D e fi niti on s........................................ 1.0-56 1 O ODCM, V.C. Summer /SCE&G: Revision 21 (March 1996) l iii

~. s. a 3 4 2.0 UOUID EFFLUENT l 2.1 Liauid Effluent Monitor Setpoint Calculation.......... 2.0-1 l 2.1.1 Liquid Effluent Monitor Setpoint Calculation Pa ra m eters................................. 2.0-2 4 2.1.2 Liquid Radwaste Effluent Line Monitors....... 2.0-6 2.1.3 Liquid Radwaste Discharge Via industrial and i Sanitary Waste System....................... 2.0-14 2.1.4 Steam Generator Blowdown, Turbine Building Sump, and Condensate Demineralizer Backwash l Efflu ent Lin es............................... 2.0-15 4 2.2 Dose Calculation for Liauid Effluents................. 2.0-32 l 2.2.1 Liquid Effluent Dose Calculation Parameters... 2.0-32 2.2.2 Meth od ology............................... 2.0-33 2.3 Liouid Effluent Releases throuah the Neutralization j Basin 2.0-35 l 2.3.1 Rai nwater Ta n k............................. 2.0-35 l 2.3.2 NaOH Spray Tank and Stored NaOH........... 2.0-36 i j 3.0 GASEOUS EFFLUENT i 3.1 Gaseous Effluent Monitor Setooints.................. 3.0-1 i 3.1.1 Gaseous Effluent Monitor Setpoint Calculation i Pa ramete rs................................. 3.0-1 ]t 3.1.2 Station Vent Noble Gas Monitors............. 3.0-5 3.1.3 Waste Gas Decay System Monitor............. 3.0-7 l 3.1.4 Alternative Methodology for Establishing i Conservative 5etpoints....................... 3.0-8 j 3.1.5 Oilincineratic 3.0-10 3.1.6 Meteorological Release Criteria for Batch Re l eas es.................................... 3.0-10 3 3.2 Dose Calculation for Gaseous Effluent................ 3.0-12 i 3.2.1 Gaseous Effluent Dose Calculation Parameters. 3.0-12 l 3.2.2 Unrestricted Area Boundary Dose............. 3.0-14 3.2.3 Unrestricted Area Dose to individual.......... 3.0 15. 33 Meteoroloaical Model for Dose Calculations.......... 3.0-45 3.3.1 Meteorological Model Parameters............ 3.0-45 3.3.2 Meteorological Model....................... 3.0-46 4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING............. 4.0-1 ODCM,V.C. Summer /SCE&G: Revision 21 (March 1996) iv

.l .~ . '~ l 9 1 \\ LIST OF TABLES i l Table No. Paoe No. 1.1-1 Radioactive Liquid Effluent Monitoring Instrumentation.. 1.0-2 l 1.1-2 Radioactive Uquid Effluent Monitoring instrumentation Surveillance Requirements............................. 1.0-5 1.1-3 Freq u ency N otation................................... 1.0-7 ) l 1.1-4 Radioactive Liquid Waste Sampling and Analysis Program. 1.0-10 l 1.2-1 Radioactive Gaseous Effluent Monitoring instrumentation 1.0-18 l 1.2-2 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements............................. 1.0-20 1.2-3 Radioactive Gaseous Waste Sampling and Analysis P r og ra m.............................................. 1.0-23 1.4-1 Radiological Environmental Monitoring Program......... 1.0-33 1.4-2 Reporting Levels for Radioactivity Concentrations in Environ-l mental Samples Reporting Levels....................... 1.0-38 1.4-3 Maximum Values for the Lower Limits of Detection (LLD) a,c Reporting Levels 1.0-39 h 2.2-1 Bioaccumulation Factors............................... 2.0-37 2.2-2 Adult ingestion Dose Factors........................... 2.0-38 2.2-3 Site Related Ingestion Dose Commitment Factor (A9..... 2.0-40 3.1-1 Dose Factors for Exposure to a Semi-Infinite Cloud of N ob l e G as es.......................................... 3.0-4 3.1-2 Favorable Meteorology................................ 3.0-10A 3.2-1 Pathway Dose Factors for Section 3.2.2.2. (Pi)............. 3.0-18 3.2-2 Pathway Dose Factors for Section 3.2.3.2. (Ri)............. 3.0-21 3.2-3 Pathway Dose Factors for Section 3.2.3.3. (Ri) (Infant)..... 3.0-24 3.2-4 Pathway Dose Factors for Section 3.2.3.3. (Ri) (Child)...... 3.0-27 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. (Ri) (Adult)...... 3.0-33 l 3.2-7 Controlling Receptors, Locations, and Pathways.......... 3.0-37 3.2-8 Atmospheric Dispersion Parameters for Controlling Receptor Locations.................................... 3.0-39 3.2-9 Parameters Used in Dose Factor Calculations............. 3.0-40 4.0-1 Radiological Environmental Monitoring Program........ 4.0-2 O ODCM,V.C. Summer /SCE&G: Revision 21(March 1996) v

~. e-LIST OF FIGURES Fiaure No. Paae No. 2.1-1 Exam ple Liquid Monitor Calibration Curve................... 2.0-31 t 2.2-1 Liquid RadwasteTreatment System 2.0-42 3.1-1 Example Noble Gas Monitor Calibration Curve............... 3.0-11 3.2-1 Gaseous RadwasteTreatment System 3.0-44 3.3-1 Plume Depletion Effect for Ground Level Releases (6) 3.0-49 t 3.3-2 Vertical Standard Deviation of Materialin a Plume (o )........ 3.0-50 z 3.3-3 Relative Deposition for Ground Level Releases (Dg) 3.0-51 3.3-4 Open Terrain Recirculation Factor........................... 3.0-52 i ? ( 4.0-1 Radiological Environmental Sampling Locations (Local),....... 4.0-12 l 4.0-2 Radiological Environmental Sampling Locations (Remote)..... 4.0-13 i i O v ODCM,V.C. Summer /SCE&G: Revision 21 (March 1996) vi

~ ~ e O REFERENCES Boegli, T.S., R.R. Bellamy,hnical Specifications for Nuclear Power Plants"W.L B 1. Radiological Effluent Tec NUREG-0133 (October 1978). 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). 3. " Calculation of Annual Doses to Man from Routihe Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR 50, Appendix I", U.S. NRC Regulatory Guide 1.109, Rev.1 (October 1977). 4. " Final Safety Analysis Report", South Carolina Electric and Gas Company, Virgil C. Surnmer Nuclear Station. "Operatin 5. 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 / Equilibrium Concentration Relationship for the Parr Pumped Storage System", Applied Physical Technology, Inc., February 1981. 7. " 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(March 1976) 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). 9. Slade, D.H., (editor), " Meteorology and Atomic Energy"; U.S. Atomic Energy Commission, AEC TID-24190,1968. 10. " 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", U.S. NRC Regulatory Guide 1.21, Rev.1 (June 1974). 11. " Standard Radiological Effluent Technical Specifications for Pressurized Water Reactors", NUREG-0472, 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). 13. " Age-5pecific Radiation Dose Commitment Factors for a One-Year Chronic Intake", NUREG-0172 (November 1977). 14. Generic Letter 89-01, " Implementation of Programmatic Controls for Radiological Effluent Tech nical Specifications", January 31,1989. 15. "Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors", Generic Letter 89-01, Supplement No.1, NUREG-1301, April 1,1991. ODCM,V.C. Summer /SCE&G: Revision 21 (March 1996) vil

~ O INTRODUCTION The OFFSITE DOSE CALCULATION MANUAL (ODCM) is an implementing and supporting document of the RADIOLOGICAL EFFLUENT TECHNICAL 5PECIFICA-CO2* TIONS (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 Controls have been incorporated into l! 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 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 and gaseous radwaste treatment systems are also included. O The ODCM will be maintained at the Station as the reference which details the Radiological Effluent Controls of the V. C. Summer Nuclear Station. l Additionally the ODCM will be maintained as the guide for accepte:I j calculational methodologies. Changes in calculation methods or parameters will be incorporated into the ODCM in order to ensure that the ODCM represents the j current methodology in all applicable areas. Computer software to perform described calculations will be maintained current with this ODCM. I h ODCM,V.C. SummerISCE&G: Revision 21 (March 1996) vill )

V O RESPONSIBILITIES The ODCM contains the radiological effluent controls, their applicability, remedial actions, surveillance requirements, and their bases. Plant procedures implement responsibilities for compliance with the ODCM that include: The Operations group is responsible for: Declaring radioactive liquid and gaseous effluent monitor channels operable e or inoperable. Ensuring the minimum number of operable channels for radioactive liquid e and gaseous effluent monitors. the m,ng the responsible group to implement appropriate action if less than Notifyi e inimum number of radioactive liquid and gaseous effluent monitor channels are operable. initiating an Off Normal Occurrence Report in accordance with SAP-132,when e less than the minimum number of channels operable condition prevails for more than 30 days, e Restoring to within limits, the concentration of liquid radioactive material exceeding ODCM limits released from the site. e Ensurin radioactive liquid and gaseous effluent monitor setpoints are set as prescribed in the effluent release permit. i e Suspending release if radioactive liquid and gaseous effluent monitor l setpoints are less conservative than ODCM requirements. .Deciaring liquid and gaseous radwaste treatment systems operable or moperable. Ensuring operability of gaseous and liquid radwaste treatment systems and e ventilation exhaust treatment system. e Ensuring appropriate portions of the gaseous and liquid radwaste treatment systems are used to reduce the radioactive materials in liquid and gaseous waste prior to their discharge when the projected doses exceed limits specified by the ODCM. l e initiating an Off Normal Occurrence Report in accordance with SAP-132,when l liquid or gaseous radwaste system is inoperable for more than 31 days. e Performing channel check and source check at the frequencies shown in Tables 1.1-2 and 1.2-2 for each radioactive liquid and gaseous effluent monitoring instrumentation channel. O ODCM,V.C. Summer /SCE&G: Revision 17 (April 1993) ix

. _ _ _ _. - _ _ _ _ _ ~ _ _ _ _ _ _ _ _ _ __ ~' l j )

O instrumentation and Controls group is responsible for

j Performing channel calibration and analog channel operational test at the e frequencies shown in Tables 1.1-2 and 1.2 2 for each radioactive liquid and gaseous effluent monitoring instrumentation channel. e informing the Operations group of surveillance test results. l l The Health Physics group is responsible for: e l e Establishing setpoints for radioactive liquid and gaseous effluent monitors, consistent with ODCM methodology, and providing setpoint information to Operations. l e implementing remedial actions as requested by Operations. These actions include grab sampling and analysis and providing the results to Operations. Performing periodic radioactive effluent monitor checks to determine e l backgrounds, normal indications and verifying monitor correlation graphs, and providing this information as necessary to Operations. l implementing radioactive gaseous and liquid waste sampling and analysis e program m accordance with ODCM Tables 1.1-4 and 1.2-3. jp e Informing Operations when at least one Circulating Water Pump or the - l Circulating Water Jockey Pump is required to provide dilution to the discharge structure. Calculating cumulative dose contributions and performing dose projections e i from liquid and gaseous effluents in accordance with the ODCM and l providing the information to Operations. l e initiating an Off Normal Occurrence Report in accordance with SAP-132, when i calculated dose from the discharge of radioactive materials in liquid or gaseous effluents are in excess of the limits specified by ODCM Sections 1.1.3.1 or 1.2.3.1. 4 i Initiating an Off Normal Occurrence Report in accordance with SAP-132, when e l liquid or gaseous waste is discharged without treatment and is in excess of the 3 limits specified by ODCM 5ections 1.1.4.1 or 1.2.3.1. e Initiating an Off Normal Occurrence Report in accordance with SAP-132, when i the dose or dose commitment to any member of the public due to releases of radioactivity and radiation is in excess of 25 mrem to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 mrem) over 12 consecutive months. i J O ODCM.v.C summe,,sC. e: evision 24 <Ma,ch 4 e> 3 X J l 1

~ e-implementing the Radiological Environmental Monitoring Program as speci-e fied in Section 1.4 of the ODCM. initiating an Off Normal Occurrence Report in accordance with SAP-132,when e the Radiological Environmental Monitoring Program limiting conditions for operation are exceeded. Preparation of the Annual Radioactive Effluent Release Report and the l e Annual Environmental Report. i f O' O ODCM,V.C. Summer /SCE&G: Revision 21 (March 1996) xi

-. _ _ _ _ _ _.. _. _ _ _ _. =. _. _ _ _ _ _ _. _ _. _ _ _. _ - l \\ lO I l 1.0 SPECIFICATION OF CONTROLS l l 1.1 1.lOUID EFFLUENTS l 1.1.1 Radioactive Liould Effluent Monitorina instrumentation CONTROLS [ ] i 1.1.1.1 The radioactive liquid effluent monitoring instrumentation chan-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 accordance with ODCM, Section 2.1. APPLICABLE: At all times. ACTION: a. With a radioactive liquid effluent monitoring instrumentation 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 Annual Radioactive Effluent Release Report explain why this condition was not corrected in a timely

manner, c.

The provisions of Technical Specifications 3.0.3 and 3.0.4 are not applicable. SURVEILLANCE REOUIREMENTS 1.1.1.2 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL j CHECK, SOURCE CHECK, CHANNEL CAUBRATION and ANALOG CHANNEL OPERATIONAL TEST operations at the frequencies shown in Table 1.1-2. ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) i 1.0-1

l l e-1 O l Table 1.1-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMEPfT OPERABLE ACTION l 1. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATICTERMINATION OF RELEASE a. Liquid Radwaste Effluent Line RM-L5 or RM-L9 1 1 b. Nuclear (Processed Steam Generator) Blowdown 1 1 Effluent Line RM-L7 or RM-L9 i l c. Steam Generator Blowdown Effluent une 1. Unprocessed during Power Operation - 1 2 RM-L10 or RM-L3 2. Unprocessed during Startup-RM-L3 1 2 j d. Turbine B uilding Sump Effluent Line - RM-LB 1 3 e. Condensate Demineralizer Backwash Effluent Line 1 6 RM-L11 2. FLOW RATE MEASUREMENT DEVICE 5* a. Liquid Radwaste Effluent Line -Tanks 1 and 2 1/ tank 4 b. Penstock Minimum Flow interlock'* 1 4 c. Nudear Blowdown k/ fluent Line 1 4 d. Steam Generator (Unprocessed) Blowd own 1 4 Effluent Line 3. TANK LEVEL INDICATING DEVICES a. Condensate Storage Tank 1 5 [ 1 In the event that simultaneous releases from both WMT and NBMT are required (which normally will be prevented by procedure) the flow rate for l monitor RM-L9 will be determined by adding flow rates for monitors RM-L5 l and RM-L7. Minimum dilution flow is assured by an interlock that terminates liquid waste releases if the minimum dilution flow is not available. O ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-2 l

e-O Table 1.1-1 (Continued) TABLE NOTATION ACTION 1 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue for up to 14 days provided that prior to initiating a release: a. At lease two independent samples are analyzed in accordance with ODCM Specification 1.1.2.4 and b. At lease two technically qualified members of the Facility Staff independently verify the release rate calculations and dischargelinevalving. Otherwise, suspend release of radioactive effluents via this path-way. ACTION 2 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 are analyzed by gamma spectroscopy for radioactivity at the LLD specified in Table 1.1-4 or samples are analyzed for gross radioactivity (beta and gamma) at a limit of detection of at least 1E-7 micro curies / gram, a. At least once per 12 hours when the specific activity of tho l secondary coolant is greater than 0.01 microcuries/ gram DOSE EQUIVALENT l-131. b. At least once per 24 hours when the specific activity of the secondary coolant is less than or equal to 0.01 micro-curies / gram DOSE EQUIVALENT l-131. ACTION 3 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 that, at least once per 12 hours, grab samples are collected and analyzed by gamma spectroscopy for radioactivity at the LLD specified in Table 1.1-4 or samples are analyzed for gross radioactivity (beta and 9amma) at a limit of detection of at least 1E-7 micro curies / gram. ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-3

l 1 e-O l l l Table 1.1-1 (Continued) l l TABLE NOTATION i ACTION 4 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 the flow rate I is estimated at least once per 4 hours during actual releases. Pump curves may be used to estimate flow. ACTION 5 With the number of channels OPERABLE less than required by the 4 Minimum Channels OPERABLE requirement, liquid additions to this tank may continue for up to 30 days provided the tank liquid level is estimated during all liquid additions to the tank to prevent overflow. l O ACTION 6 With the number of channels OPERABLE less than requvW by the j Minimum Channels OPERABLE requirement, effluent releases may continue for up to 30 days provided that samples are analyzed in accordance with ODCM Specification 1.1.2.2 and Technical Specifi-l' cation 4.11.1.5. d i h l i I l ) O ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-4

Table 1.1-2 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ANALOG l CHANNEL CHANNEL l CHANNEL SOURCE CAUBRA-OPERATIONAL lNSTRUMENT C,tj[,g CHECK TION E T l 1. GROSS RADIOACTIVITY MONITORS ( PROVIDING ALARM AND AUTOMATIC l TERMINATION OF RELEASE a. Liquid Radwaste Effluent Line-D P R(2) Q(1) l RM-L5 or RM-L9 b. Nudear Blowdown Effluent D P R(2) Q(1) Line RM-L7 I c. Steam Generator Blowdown D M R(2) Q(1) Effluent Line -RM-L3, RM-L10 i d. Turbine Building Sump Effluent D M R(2) Q(1) Line - RM-LB e. Condensate Demineralizer D M R(2) Q(4) l Backwash Effluent Line RM-L11 i 2. FLOW RATE MEASUREMENT DEVICES l a. Liquid Radwaste E4iuent Line D(3) N.A. R Q b. Penstocks Minimum Flow D(3) NA R Q interlock ) c. Nuclear Blowdown Effluent D(3) N.A. R Q l Line d. Steam Generator Blowdown D(3) N.A. R Q Effluent Line l 3. TANK LEVELINDICATING DEVICES l a. Condensate StorageTank D N.A. R Q l See Table 1.1-3 ior explanation of frequency notation. l l l l l ODCM, V.C. Sumrner,5CE&G: Revision 21 (March 1996) j 1.0-5

.j O1 Table 1.12 (Continued) j TABLE NOTATION (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. (2) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National institute of Standards and 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 energy and measurement range. For subsequent CHANNEL CAUBRATION, 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 release. CHANNEL CHECK shall be made at least once per 24 hours on days on which continuous, periodic or batch releases are made. (4) The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this patb iay and local panel 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 indicates a Downscale Failure (alarm only). 5. Normal / Bypass switch set in Bypass (alarm only). 6. Other instrument controls not set in On trate mode. O ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-6

<~ ~ r O Table 1.13 FREQUENCY NOTATION Notation Frequency D Atleast once per 24 hours. W Atleast once per 7 days. M Atleast once per 31 days. Q Atleast once per 92 days. i 1 + l SA Atleast once per 184 days. R Atleast once per 18 months. l P Completed prior to each release. [ l lO N.A. Not applicable. j l l l Note: Each surveillance requirement shall be performed within l the specified surveillance interval with a maximum allowable extension of 25% of the specified surveillanceinterval. i l i i 4 i f ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-7

l l l e O 1.1.2 Liauid Effluents: Concentration CONTROLS l 1 1.1.2.1 The concentration of radioactive material released from the site (see Technical Specification Figure 5.1-4) shall be limited to 10 times the concentration values specified in 10 CFR Part 20, Appendix B, Table 2, 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 to unrestricted areas exceeding the above limits, immediately restore the concentration to within the above limits. SURVEILLANCE REOUIREMENTS 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 calculational methods in ODCM Section 2.1 to assure that the concentration at the point of release is maintained within the limits of ODCM Specification 1.1.2.1. 1.1.2.3 Post-release analyses of samples composited from batch releases shall be performed in accordance with Table 1.1-4. The results of the previous post-release analyses shall be used with the calculational methods in ODCM j 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. O ODCM, V.C. Summer, SCE &G: Revision 21 (March 1996) 1.0-8 l

~ e-6 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 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. 1.1.2.5 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 I 1.1.2.1. t O I O ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-9 i ) l

e~ O l Table 1.1-4 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit Minimum Type of of Detection Liquid Release Sampling Analysis Activity (LLD) Type Frequency Frequency Analysts (pCi/mi)* A. Batch Waste Release' P P Principal Gamma 5X10 7 Tanks Each Batch Each Batch Emitters' l-131 1X10-6 1. Waste Monitor Tanks P M Dissolved and 1X10-s One Batch /M Entrained Gases (Gamma Emitters) 2. Condensate Demin-P M H-3 1X104 eralizer Backwash Each Batch Composite

• Receiving Tank Gross Alpha 1X10-7 3.

Nuclear Blowdown P Q Sr-89,5r-90 SX104 MonitorTank Each Batch Composite

• Fe-55 1X104 B.

Continuous Release

• D W

Principal Gamma 5X10 7 Grab 5 ample Composite

• Emrtters' l-131 1X10-6 1.

Steam Generator M M Dissolved and 1X104 Blowdown Grab Sample Entrained Gases (Gamma Emitters)

2. TurbineBuilding D

M H-3 1X10-5 Sump Grab Sample Composite' GrossAlpha 1X10-7

3. Service Water D

Q Sr-89, Sr-90 5X10-a Grab Sample Composite

• Fe-55 1X104 See Table 1.1-3 for explanation of frequency notation.

l O ODCM, V.C. Summer, SCE &G: Revision 21 (March 1996) 1.0-10

4 O Table 1.1-4 (Continued) l 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 be l detected with a 95% probability. LLD also yields a 5% probability of falsely concluding that a blank observation represents a "real" signal. l i For a particular measurement system (which may include radiochemical l separation): 4.66sh LLD = (E) (V) (2.22)(Y)(exp)(-Mt) ' Where: l l LLD is the "a priori" lower limit of detection as defined above (as pCi l per unit mass or volume). Current literature defines the LLD as the detection capability for the instrumentation only and the MDC, the O minimum detectable concentration, as the detection capability for a given instrument procedure and type of sample. 4.66 is a factor which corrects for the smallest activity that has a j probability, p, of being detected, and a probability,1 p, of falsely l concluding its presence, i /ts) { 4.66 = 2k V 1 + ( tb l k= a constant whose value depends on the chosen ( confidence level (NRC recommends a confidence l levelof 95%) = 1.6545 at 95% confidence level tb = background time ts = sample time sb s the standard deviation of the background counting rate or the i l I. counting rate of blank sample as appropriate (as counts per minute). j E is the counting efficiency (as counts per transformation). i ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 4 1.0-11 l t

c-O Table 1.1-4 (Continued) TABLE NOTATION V is the sample size (in units of mass or volume). 2.22 is the number of transformations per minute per picocurie. Y is the fractional radiochemical yield (when applicable). A is the radioactive d ecay, constant for the particular radionuclide. 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 b used in the calculation of the LLD for a detection system shall be used on the actual observed variance of the back-ground counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. In calculating the LLD for a radionuclide determined by gamma-ray spectrometry the background should indude the typical contributions of other radionuclides normally present in the samples. Typical values of E, V, Y and At shall be used in the calculation. It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as a. posteriori (after the fact) limit for particular measurement.* l

• For a more complete discussion of the LLD, and other detection limits, see the following (1)

HASL Procedures Manual, HASL-300 (revised annually). (2) Currie, L. A., "Umits for Qualitative Detectio') and Quantitative Deter-mination - Application to Radiochemistry" Anal. Chem.40,586-93 (1968). j (3) Hartwell, J. K., " Detection Limits for Radioisotopic Counting Techniques," Atlantic Richfield Handford Company Report ARH 2537 (June 22,1972). O ODCM, V.C. Summer,5CE &G: Revision 21 (March 1996) 1.0-12

m. I e-O Table 1.1-4 (Continued) TABLE NOTATION b. A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen 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 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 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. f. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60,2n-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. i ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-13

~~ Ol 1.1.3 Liould Effluents: Dose CONTROLS 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 Figure 5.1-4)shall be limited: a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 rarem to any organ. 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 liquid 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 (s) and defines the corrective actions to be taken to the releases and the pre;,osed actions to be taken to assure that subsequent releases will be in compliance with ODCM Specification 1.1.3.1. b. The provisions of Technical Specifications 3.0.3 and 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS 1.1.3.2 Dose Calculations Cumulative dose contributions from liquid effluents shall be determined in accordance with ODCM Section 2.2 atleast once per 31 days. ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-14

c' i O 1.1.4 Liould Waste Treatment l i CONTROLS 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 I materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent from the site (See Technical Specification Figure 5.1-

4) when averaged on a sliding 31 day calendar basis, would exceed 0.06 rnrem l

to the total body or 0.2 mrem to any organ. l t APPLICABLE: At all times. ACTION: a. With the liquid radwaste treatment system inoperable for more i than 31 days or with radioactive liquid 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 j the Commission within 30 days, pursuant to Technical Specification w 6.9.2, a Special Report which indudes the following information: 1. Identification of the inoperable equipment or subsystems and the reason forinoperability. 2. Action (s) taken to restore the inoperable equipment to OPERABLE status. 3. Summary description of action (s) taken to prevent a recurrence. b. With radioactive waste being discharged, the requiraments to process effluents are: 1. If all streams are unprocessed and projected dose (s) exceed the limits of ODCM Specification 1.1.4.1, process the appropriate streams to the point that the projected dose iswithin limits. t ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-15 i

~ c-O' 2. With a combination of processed and unprocessed streams producing a dose projection exceeding the limits of specification 1.1.4.1, process the unprocessed streams if they contribute greater than or equal to 10 percent of 1 Specification 1.1.4.1 limits. c. The provisions of Technical Specifications 3.0.3 and 3.0.4 are not applicable. i SURVEILLANCE REOUIREMENTS 1.1.4.2 Doses due to liquid releases shall be projected at least once per 31 days. 1.1.4.3 The liquid radwaste treatment system shall be demonstrated OPERABLE by operating the liquid radwaste treatment system equipment for at least 30 minutes at least once per 92 days unless the liquid radwaste system has been utilized to process radioactiveliquid effluents during the previous 92 days. i i l l O ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-16

_-.-...-.-- -.-.- -_. --.~..-.- ....~_.-.-.- - e-O 1.2 GASEOUS EFFLUENTS 1.2.1 Radioactive Gaseous Effluent Monitorina instrumentation CONTROLS 12.1.1 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 1.2.-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of ODCM Specification 1.2.2.1 are not l exceeded. The alarm / trip setpoints of these channels shall be determined in accordance with ODCM Section 3.1. APPUCABLE: As shown in Table 1.2-1 I ACTION: a. With a radioactive gaseous effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above ODCM Specification, immediately suspend the release of O radioactive gaseous effluents monitored by the affected channel or declare the channelinoperable. b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 1.2-1. Additionally if this condition prevails for more than 30 days, in the next Annual Radioactive Effluent Release Report, explain why this condition was not corrected in a timely manner. i b. The provisions of Technical Specifications 3.0.3 and 3.0.4 are not applicable. SURVEILLANCE REOUIREMENTS 1 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 l OPE RATIONAL TEST operations at the frequencies shown in Table 1.2-2. I f ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-17 l 1

l l e l O I Table 1.2-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS APPLICA-INSTRUMENT OPERABLE BILITY ACTION 1. WASTE GAS HOLDUP SYSTEM i

a. Noble Gas ActivityMonitor-Providing 1

7 Alarm and AutomaticTermination of v Release (RM-A10 or RM-A3) { 2. MAIN PLANT VENT EXHAUST SYSTEM t

a. Noble Gas ActivityMonitor-Providing 1

9 7 Alarm and AutomaticTermination of Release from Waste Gas Holdup System i (RM-A3) h

b. lodine Sampler 1

11

c. Particulate Sample 1

11

d. Flow Rate Measuring Device 1

8

e. Sampler Flow Rate Measuring Device 1

8 l 1' 3. REACTOR BUILDING PURGE SYSTEM

a. Noble Gas Activity Monitor Providing 1

10 Alarm & AutomaticTermination of Release (RM-A4) I

b. lodineSampler 1

11 I

c. ParticulateSample 1

11

d. Flow Rate Measuring Device i

1. For 36 Purge (IFT09287) 1 8 2. For 6" Purge (IFT08252) 1 8

e. Sampler Flow Rate Measuring Device 1

8 i O' ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-18

r-OO Table 1.2-1 (Continued) TABLE NOTATION At all times during releases via this pathway. ACTION 7 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank (s) may be released to the environment for up to 14 days provided that prior to initiating the release: At least two independent samples of the tank's contents a. are analyzed. b. At least two technically qualified members of the Facility Staff independently verify the release rate calculations l and discharge valve lineup. Otherwise, suspend release of radioactive effluents via this pathway. ACTION 8-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 the flow rate is estimated at least once per 4 hours. ACTION 9-With the number of channels OPERABLE less than required by the h Minimum Channels OPERABLE requirement, effluent releases via d this pathway may continue for up to 30 days provided grab samples are taken at least once per 12 hours and these samples are analyzed l for gross activitywithin 24 hours. ACTION 10 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, immediately suspend PURGING of radioactive effluents via this pathway. ACTION 11 - 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, as specified in Table 1.2-3, are continuously collected with auxiliary sampling equipment. With the monitor taken out of service, by a condition a. other than a planned action, the action statement is considered met if a conscious, concerted and continuous effort is being made to initiate the collection of the required sample (s) with auxiliary sampling equipment. b. A planned removal of the monitor from service requires that the auxiliary sampling equipment be staged in the area to reduce the amount of time for the change over from sampling by the installed monitor to the auxiliary sampling equipment. ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-19

i e-O Table 1.2-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS MODES IN ANALOG WHICH CHANNEL CHANNEL SURVEIL-CHANNEL SOURCE CAllBRA-OPERATION LANCE RE-INSTRUMENT CHECK CHECK TION -AL TEST QUIRED 1. WASTE GAS HOLDUP SYSTEM a. Noble Gas Activity P P R(3) Q(1) Monitor-RM-A10 or RM-A3 2. MAIN PLANT S/ENT EXHAUSTSYSTEM a. Noble Gas Activity D M R(3) Q(2) Monitor-RM-A3 b. lodine Sampler W N.A. N.A NA c. Particulate Sampler W N.A. NA N.A. d. Flow Rate D N.A. R Q Measuring Device j e. Sampler Flow Rate D N.A. R Q Monitor 3. REACTOR BUILDING PURGE SYSTEM a. Noble Gas Activity D P,M R(3) Q(1) Monitor-RM-A4 b. lodine St.11pler W N.A. N.A NA c. Particulate 5 ampler W N.A. N.A. NA d. Flow Rate Measur-ing Device

1. For 36" Purge D

NA R Q (IFT09287)

2. For 6" Purge D

NA R Q l (IFT08252) e. Sampler Flow Rate D NA R Q Monitor See Table 1.1-3 for explanation of frequency notation. O ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-20

O Table 1.2-2 (Continued) TABLE NOTATION At all times. (1) The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occursif 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. (2) The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions 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 pelformed using one or more of the reference standards certified by the National Institute of Standards and 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 energy and measurement. For subsequent CHANNEL CAllBRATION, sources l that have been related to the initial calibration shall be used. ODCM, V.C. Summer, SCE &G: Revision 21 (March 1996) 1.0-21

1 l l 1 O' 1.2.2 Gaseous Effluents: Dose Rate CONTROLS l l 1.2.2.1 The dose rate in unrestricted areas due to radioactive materials released in gaseous effluents from the site induding effluents from oil incineration (see Technical Specification Figure 5.13) shall be limited to the following: a. For noble gases: Less than or equal to 500 mrem /yr to the total body and less than or equal to 3000 mremlyr to the skin. b. For lodine-131, lodine-133 and for all radioactive materials in l particulate form and tritium with half lives greater than 8 days: Less than or equal to 1500 mremlyr to any organ. c. Less than 0.1% of the limits in 1.2.2.1 (a) and (b) as a result of oil incineration. O APPLICABLE: At all times. ACTION: With the doce rate (s) exceeding the above limits, immediately decrease the release rate to within the above limit (s). SURVEILLANCE REOUIREMENTS 1.2.2.2 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above lirnits in accordance with the methods and procedures of the ODCM. 1.2.2.3 The dose rate due to radiciodines, tritium and radioactive materials in particulate form with half lives greater than 8 days in gaseous effluents shall be determined to be within the above limits in accordance with the methods and procedures of ODCM Section 3.2.2 by obtaining representative l samples and performing analyses in accordance with the sampling and analysis program specified in Table 1.2-3. O ( ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-22

~ O Table 1.2-3 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limitof Minimum Type of Detection Gaseous Release.Sa mpl.ing Analysis Activity (LLD) .-requeng Frequency Analysis (pCI/ml)* Type A Waste Gas Storage P P Principal Gamma 1X104 Tank Each Tank Each Tank Emitters' Grab Sample B1 Reactor Building P P PrincipalGamma 1X104 36' Purge Line Each Purge

• Each' Purge" Emitters' H-3 1X10 6

- 6" Purge Line B2 Reactor Building M* M* PrincipalGamma 1X104 -6" Purge Line Grab Sample Emitters' H-3 1X10-6 (if continuous) C Main Plant Vent M** M* Principal Gamma 1Y1&d Grab Sample Emitters

• H-3 1X1&6 D1.. Reactor Building Continuous W

I-131 1X1012 Purge Sampler' Charcoal 5 ample 1-133 1X10-10 2. Main Plant Vent Continuous W Principal Gamma 1X10-11 Sampler' Particulate Emitters' Sample I 131, others Continuous M Sampler' Composite Parti-Gross Alpha 1X1011 culate Sample Continuous Q Sampler' Composite Parti-Sr-89,5r-90 1X10-11 culate Sample Continuous Noble Gas Noble Gases 2X106 Monitor Monitor GrossBeta E Oillncinerator P P i Each Batch" Each Batch PrincipalGamma 5 X107 Grab Sample Emitters' I Noble Gases 1E-5 l-131 1E-6 i 8 H-3 3E-5 I Sr-89,5r-90 3E 7 i Fe-55 1E-6 See Table 1.1-3 for explanation of frequency notation. ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-23 O

r-O Table 1.2 3 (Continued) TABLE NOTATION a. See Table 1.1-4 notation (a) for definition of LLD. b. Analyses shall be also be performed within 24 hours following shutdown, startup, or a THERMAL POWER change exceeding 15 percent of the RATED THERMAL POWER within a one hour period. Tritium grab samples shall be taken at least once per 24 hours when the c. refueling canalis flooded. d. Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours after changing (or after removal from sampler). Sampling shall also be performed at least once per 24 hours for at least 7 days following each shutdown, startup or THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER in one hour and analyses shall be completed within 48 hours of changing. When samples collected for 24 hours are analyzed, the corresponding LLD's may be increased by a factor of 10. Tritium grab samples shall be taken at least once per 7 days from the e. ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool. f. The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation { made in accordance with 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 applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135 and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions. 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. h. Prior to sampling for analysis, each batch of oil shall be isolated and representative samples obtained by methods described in ASTM D 4057-81, Volume 05.03, " Standard Practice for Manual Sampling of Petroleum and Petroleum Products". i. This LLD refer to theliquid sample. 9 ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-24

O 1.2.3 Gaseous Effluer ?ose-Noble Gas I CONTROLS 1.2.3.1 The air dose due to noble gases released in gaseous 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 9amma radiation and less than or equal to 10 mrad for beta i radiation. b. During any calendar year: Less than or equal to 10 mrad for gamma l radiation and less than or equal to 20 mrad for beta radiation. APPLICABLE: At alltimes. 1 ACTION-l a. With the calculated air dose from radioactive noble gases in gaseous ( effluents exceeding any of the above limits, in lieu of any other O 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 (s) and defines the corrective actions to be taken to releases l and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with ODCM Specification 1 1.2.3.1. s l i b. The provisions of Technical Specifications 3.0.3 and 3.0.4 are not I applicable. SURVEILLANCE REQUIREMENTS i 1.2.3.2 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. r I ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-25 l l l.

c" O 1.2.4 Gaseous Effluents: Dose - Radiolodines, Tritium, and Radioactive Materials in Particulate Form. CONTROLS l 1.2.4.1 The dose to an individual from radiciodines, tritium, and radioactive materials in particulate form, and radionuclides (other than noble gases) with half-lives greater than 8 days in gaseous effluents including effluents from oil incineration (see Technical Specification Figure 5.1-3) shall be limited to the following: a. During any calendar quarter: Less than or equal to 7.5 mrem to any organ. b. During any calendar year: Less than or equal to 15 mrem to any organ. c. Less than 0.1% of the limits in 12.4.1 (a) and (b) as a result of oil incineration. APPLICABLE: Atalltimes. ACTION. a. With the calculated dose from the release of tritium, radioiodines, i 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 1.2.4.1. b. The provisions of Technical Specifications 3.0.3 and 3.0.4 are not applicable. SURVEILLANCE REOUIREMENTS 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. O ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-26

O 1.2.5 Gaseous Effluents: Gaseous Radwaste Treatment CONTROLS _ l 1.2.5.1 The GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILA-TION 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 5.1-3), when averaged over 31 days, would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation. The aopropriate portions of the VENTILATION EXHAUST TREAT-MENT 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. APPUCABLE: At all times *. O ACTION: With the GASEOUS RADWASTE TREATMENT SYSTEM and/or the a 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: 1. Identification cf the inoperable equipment or subsystems and the reason forinoperability. 2. Action (s) taken to restore the inoperable equipment to OPERABLE status.

• The Waste Gas System may be secured during refueling and defueled operations since there is no gas in the system to be removed and processed. The system is l

considered " inoperable" during these conditions due to the instrumentation being out of calibration when flow is stopped through the recombiner. This " inoperable" state is the normal system condition during ref ueling and defueled modes. ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-27

. ~ - '~ O 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. SURVEILLANCE REQUIREMENTS 1.2.5.2 Doses due to gaseous releases from the reactor shall be projected at least once per 31 days. 1.2.5.3 The GASEOUS RADWASTE TREATMENT SYSTEM and VENTILATION EXHAUST TREATMENT SYSTEM shall be demonstrated OPERABLE by opera-ting the GASEOUS RADWASTE TREATMENT SYSTEM equipment and 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. 1 l G ODCM, V.C. Summer, SCE &G: Revision 21 (March 1996) 1.0-28 2 W

O 1.3 RADIOACTIVE EFFLUENTS: TOTAL. DOSE CONTROLS 1.3.1 The dose or dose commitment to any member of the public, due to releases of radioactivity and radiation, from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 mrem) over 12 consecutive months. APPLICABLE: At alltimes. ACTION: With the calculated doses from the release of radioactive materials a. in liquid or gaseous effluents exceeding twice the limits of ODCM Specification 1.1.3.1.a, 1.1.3.1.b, 1.23.1.a, 1.2.3.1.b, 1.2.4.1.a or O 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 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, defined in 10 CFR 20.2203(a)(4), shall l 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. The report shall also describe levels of radiation and concentrations of radioactive materialinvolved and the cause of the exposure levels or concentrations. If the estimated dose (s) exceeds the limits of ODCM 5pecification 13.1, and if the release condition resulting in l violation of 40 CFR 190 has not already been corrected, 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 timely request, and a variance is granted until staff action on the request is complete. The ODCM,V.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-29

r~ O il variance only relates to the limits of 40 CFR 190, and does not apply in any way to the requirements for dose limitation of 10 CFR Part 20, as addressed in ODCM Specifications 1.1.2 and 1.22. 3 b. The provisions of Technical Specifications 3.0.3 and 3.0.4 are not applicable. SURVEILLANCE REOUIREMENTS 1.3.2 Dose Calculations Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with ODCM Specifica-tions 1.1.32,1.2.3.2 and 1.2.4.2. O O ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-30

e" \\ O i 1.4 RADIOLOGICAL ENVIRONMENTAL MONITORING l l 1.4.1 Monitorina Proaram I CONTROLS l l 1.4.1.1 The radiological environmental monitoring program shall be con-j ducted as specified in Table 1.4-1. J APPLICABILITY: Atalltimes. j l l ACTION: a. With the radiological environmental monitoring program not being conducted as specified in Table 1.4-1 in lieu of any other report required by ODCM Section 1.6, prepare and submit to the l Commission, in the Annual Radiological Operating Report, a description of the reasons for not conducting the program as required and the plans 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 required by ODCM Section 1.6, prepare and submit to the Commission within 30 days from the end of the affected calendar . quarter a Special Report. When more than one of the radionuclides in Table 1.4-2 are detected in the sampling medium, this report shall be submitted if: Concentration (1) Concentration (2) +.. 2: 1.0 t Limit Level (1) Limit Level (2) When radionuclides other than those in Table 1.4-2 are detected and are the result of plant effluents, this report shall be submitted if i the potential annual dose to an individual is equal to or greater than the calendar year limits of ODCM Specifications 1.1.3.1,1.2.3.1 4 l l ODCM, V.C. Summer, SCE &G: Revision 21 (March 1996) 1.0-31 i

e O 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 an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report. c. With milk or fresh leafy vegetable samples permanently unavailable l from one or more of the sample locations required by Table 1.4-1,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 of the unavailability of samples and identifies locations for obtaining j replacement samples. The locations from which samples were unavailable may then be deleted from those required byTable 1.4-1, provided the locations from which the replacement samples were [ obtained are added to the environmental monitoring program as j replacementlocations. p O, d. The provisions of Technical Specifications 3.0.3 and 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS { 1.4.1.2 The radiological environmental monitoring samples shall be j collected pursuant to Table 1.4-1 and shall be analyzed pursuant to the requirements of Tables 1.4-1 and 1.4-3. l l O ODCM, V.C. Summer,5CE&G: Revision 21 (March 1996) 1.0-32

r ~ i { Table 1.4-1 Radiological Environmental Monitoring Program i Virgil C. Summer Nuclear Station Exposure Path. wayand/or Minimum Number of Sample Locations and Sampling and Type & Frequency Sample Criteria forSelection Collection Frequency of Analysis ANtBOltNE: 1. Particulates A) 3 indicator sa mples to be taken at locations (in Continuous sampler Gross beta following filter different sectors) beyond but as close to the operation with wtekly change; quarterty exd usion boundary as practicaole where the collection. composite (by location) for hig hest offsite sectorial ground level gamma isotopic. concentrations are anticipated. B) 1 Indicator sample to be taken in the sector Continuous sampler Gross beta following filter beyond but as close to the exd usion boundary as operationwithweekly change; quarterly practicable corresponding to the residence collection. composite (by location) for having the highest anticipated offsite ground gamma isotopic. level concentration ordose. C) 1 Indicator sa mple to be taken at the location of Continuous sampler Gross beta following filter one of the dairies being sampled meeting the operation with weekfy change; quarterty criteria of Vil(A).2 collection. composite (by location) for gamma isotopic. D) 1 Control sample to be taken at a location at least Continuoussampler Gross beta following filter 10 air miles from the srte a nd not in the mcst operation with weekly change; quarterly prevalent wind directions. collection. compaite r>y location) for gamma isotopic. IL Radeoiodine A) 3 Indicator samples to be taken at two locations Continuous sampler Gamma isotopicfor1131 as given in 1(A) above. operationwith weekly weekly. l canister collection. B) 'e indicator sa mple to be ta ken at the location as Continuous sampler Gemena Isotopicfor L131 i given in 1(B)above. operatenwith weekly weekly. canistercollection. C) 1 Indiator sa mple to be taken at the location as Continuous sampler Gamma isotopicfor1131 given in1(Q above. operation with weekly weekly. canister cohection. D) 1 Control sample to be taken at a location as Continuous sampler Gamma isotopic for1131 givenin I(D)above. operatson with weekly weekly. ca nister collection. Ill. Direct A) 13 IndH:stor stations withtwo or more desi-Monthlyor quarterlyD8 Gamrna dose mor'thly or meters to form a n inner ring of stations in the 13 quarterly, accessible sectors within 1 to 2 miles of the plant, B) 16 Indicator stations with two or more dosi-Monthly or quartertyDA Gamma dose mcmthly or meters to form an outer ring of stations in the 16 quarterly. accessible sectors within 3 to 5 miles of the plant. Q 11 Stations with two or more dosirneters to be Monthly ce quartertyDA Gamma riose moethly or placed in special interest a reas such as popula. quarteny. ~ tion centers, nea rby residences. schools and in 4 or 5 a reas to serve as control stations, i i 4 i i ODCM, V.C. Summer, SCE &G: Revision 21 (March 1996) 1.0-33 4

i Table 1.4-1 Radiological Environmental Monitoring Program Virgil C. Summer Nuclear Station Exposure Path-wayand/or Minimum Number of Sample Locations and Sampling and T)pe & Frequency Sample Criteria for Selection Collection Frequency of Analysis 1 WATERSORNE: IV. SurfaceWater A) 1 tndicator sa mple downstream to be taken at a Time composite samples Gamma isotopic monthly location which allows for mixmg a nd dilution in with collection every with quarterly composite the ultimate receiving river. month. D1 (by location)or monthly sa mple to be analyzed for tritium.D) B) 1 Control sample to be taken at a location on the Time composite samples Gamma isotopic monthly receiving river sufficiently far upstream such that with collection every with quarterfy composite no effects of purnped storage operation are month. D) (bylocation) or monthly anticpated. sample to be analyzed for tritium.S j Q t indicator sample to be taken in the upper Time composite samples Gamrnaisotopicmonthly reservoir crf the pumped storage facility in the with collection every with quarterfy composite t plant d scharge canal. month. D) (bylocation)or monthly sampleto be analyzed for tritium.(S V. Ground Water A) 2 indicator sa mples to be taken within the Quarterty grab sampling.(S Gamma isotopic and tri-exdusson boundary and in the direction of tium analyses quarterty.(3) potentialty affected ground water supplies. B) 1 Control sample from unaffected mcation. Quarterlygrabsampling (S Gamma isotopic and trb tium analyses quarterfy.(S VI. Drinking Water A) 1 Indicator sample from a nearby public ground Monthly grab sampling.D) Monthly W gamena water supply source. isotopicand gross beta analysesand quartertym . temposrte fortritium j6atres. B) 1 Indicator (finished water) sample from the Monthly composite LAorMlyC# gamma nearest downstream watersupply. sampimg. mMcand gross beta analyses and quarterty(8 composite fortntium analyses. O 1 Control (finish water) sample from the nearest Monthly composite Monthly D) gamma unaffected publicwatersupply. sampling. isotopicand gross beta analyses and quarterty(5) composite fortntium analyses. O ODCM, V.C. Summer, SCE &G: Revision 21 (March 1996) 1.0-34

Table 1.4-1 Radiological Environmental Monitoring Program \\ Virgil C. Summer Nuclear Station Exposure Path-way and/or Min *wnum Number of Sample Locations and Sarnpling and Type & Frequency Sample Criteria for Selection Collection Frequency of Analysis GetSTloN: Vll. Milk (2) A) $a mples from milkirg animals in 3 locations with-Semimonthlywhen Gamrna isotopic and 1-131 in 5 km dstance having the highest dose potere anirnals are on pasture,W analysis semimonthlyW tial. If there are none then 1 sample from milking monthly other times.W when animals are on a nimals in each of 3 areas between 5 to 8 km pasture; monthly W at datance where doses a re calculated to be greater othertimes. than 1 mrem peryear. B) 1 Control sa mple to be taken at the locaton of a Semimonthlywhen Gamma isotopic and 1-131 dairy greater than 20 miles data nce and not in animals are on pasture,W analysis semimonthly W the most prevalentwind directiort enonthly other times.OJO when animal s are on pasture; monthly W at othertimes. Q i lndicator g rass (forage) sample to be ta ken at Monthly when available W Gamma isotopic. the location of one of the dairies being sampled meeting the cnteria of Vil(A),above,when animals are on pasture. D) 1 Control grass (forag e) sa mple to be taken at the Monthlywhenavaitable Gamma isotopic-location of Vil(B) above. OE Vill. Food Prod ucts A) 2 samples of brcadleaf vegetation grown inthe 2 Monthly when available. Gamma Isotopic on edible nearest offsite locations of highest calculated (3) portion. annual average ground level D/Q if milk sampling is not performed within 3 km or if milk sampling is not performed at a location wrthin 5 to 8 km where the doses are calculated to be greater than g j 1 mrem /yr.(1) B) 1 Control sample for the same foods taken at a Monthly when available. Gamma Isotopic on edible location at least 10 miles distance a nd not in the (3) portior. most prevalentwind direction if milk sampling is not performed within 3 km or if milk sampling is not at a location within 5 to 8 km where doses are calculated to be greaterthan 1 mrem /yr.(1) IX. Fish A) 11ndicator sa rnple to be taken at a location in the Semiannual Mcollection of Gamma isotopic on edible upper reservoir. thefollowing specietypes portiors semiannutily. if available: bass; bream, l crappie; canh, carp. B) i nndicator sa rnpie to be taken at a location in the Semiannua. llection Gamma isotopic on edible lower reservoir. of thefollowyspecie portiers semiannually, typesif available: bass; bream, crappie; catfish, carp. C) 1 Control sample to be taken at a locaum on the SemiannualM collection Gamma isotopic on edible recemng nver sufficiently far upstreem such that of thefollowingspecie portions semiannually. l no effects of pumped storage operation are typesif available: bass; anticipated. bream, crappie; catfish, carp. C ODCM, V.C. Summer, SCE &G: Revision 21 (March 1996) 1.0-35

e' Ol Table 1.4-1 Radiological Environmental Monitoring Program Virgil C. Summer Nuclear Station Exposure Path-way and/or Minimum Number of Sample Locations and Sampling and Type & Frequency Sample Criteria for Selection Collection Frequency ofAnalysis AQUAMC: X. Sediment A) 1 Indicator sample to be taken at a location in the Serniannual grab Gamma isotopic. upper reservoir. .sy sie.M B) i lndicator sample to be taken on or near the ser,.snnual grab Gamma isotopic. shoreline of the lower reservoir. sampie.M l Q 1 Control sa mple to be taken at a location on the Semiannual grab Gamma isotopic. recetving river sufficiently far upstream such that sarnple.M no effects of pumped storage operation are a nticipated. l 4 O i O 1 ODCM, V.C. Summer, SCE &G: Revision 21 (March 1996) 1.0-36

_.~..__ _ _. l I ~ O l l Table 1.4-1 (Continued) l TABLE NOTATION l 1. The dose shall be calculated for the maximum organ and age group, using the guidance / methodology contained in Regulatory Guide 1.109, Revision 1 j l and the parameters particular to the Site. The locations are selected based on potentialfor highest exposure. 2. Milking animal and garden survey results will be analyzed annually. Should 1 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 totalof 3Indicatorlocations. 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. Atleast once per 100 days. 6. At least once per 18 days. 7. At least once per 200 days. 8. Milk and grass (forage) sampling at the control location is only required when locations meeting the criteria of Vil(A) are being sampled. .N.,QH: Deviations from this sampling schedule may occasionally be necessary if sample media are unobtainable due to hazardous conditions, seasonal unavailability, insufficient sample size, malfunctions of automatic sampling or analysis equipment and other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction, every effort shall be made to complete corrective action prior to the end of the next sampling period. Deviations from sampling analysis schedu'es will be described in the annual report. ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) l 1.0-37

i l Table 1.4-2 Reporting Levels for Radioactivity Concentrations in Environmental 5amples I Airborne Par-Fish Food Water ticulate or (pCi/kg, Milk Products Analysis (pCi/l) Gases (pCi/m3) wet) (pCi/I) (pCi/Kg, wet) i l H-3 20,000(a) NA NA NA NA Mn-54 1,000 NA 30,000 NA N.A. Fe-59 400 NA 10,000 NA N.A. t Co-58 1,000 NA 30,000 NA NA Co-60 300 N.A. 10,000 NA NA Zn-65 300 N.A. 10,000 NA N.A. Zr-95 400 NA 20,000 NA N.A. 4 Nb-95 400 N.A. 20,000 NA N.A. i ) 1-131 2 0.9 NA 3 100 l Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-140 200 NA NA 300 N.A. I i La-140 200 N.A. NA 300 NA i (a) For drinking water samples. This is the 40 CFR Part 141 value. i ODCM, V.C. Summer, SCE&G: Revision 21(March 1996) 1.0-38

i ~- ? 1 lO i i Table 1.4-3 1 3 l Maximum Values for the Lower Limits of Detection (LLD)a,c i l k. j Airborne Par-Food ticulate or Fish Products I Water Gases (pCi/kg, Milk (pCi/Kg, Sediment { Analysis (pCl/I) (pCi/m3) wet) (pCi/l) wet) (pCi/Kg, dry) i Gross Beta 4 1 X 10 2 NA N.A. N.A. N.A. 1 i H-3 2000(b) N.A. N.A. NA NA NA l J Mn-54 15 NA 130 NA NA N.A. I Fe-59 30 NA 260 NA N.A. N.A. t Co 58 15 NA 130 NA NA N.A. ( 0; I Co.60 15 N.A. 130 NA N.A. N.A. l 2n 65 30 NA 260 NA NA NA 8 Zr-95 30 N.A. N.A. NA N.A. NA Nb-95 15 NA NA N.A. N.A. NA l-131 1b 7 X 10 2 NA 1 60 N.A Cs-134 15 5 X 10 2 130 15 60 150 l Cs-137 18 6 X 10 2 150 18 80 180 Ba 140 60 N.A. N.A. 60 N.A. N.A. La-140 15 NA N.A. 15 NA NA ODCM, v.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-39

c-O Table 1.4-3 (Continued) TABLE NOTATION a. Table 1.4-3 lists detection capabilities for radioactive materials in environmental samples. These detection capabilities are tabulated in terms of the lower limits of detection (LLDs). See Table 1.14 notation (a) for definition of LLD. b. LLD for drinking water samples. c. Other peaks potentially due to reactor operations (fission and activation products) which are measurable and identifiable, together with the radionuclides in Table 1.4 3, shall be identified and reported. O 4 l i ODCM, V.C. Summer,SCE&G: Revision 21 (March 1996) 1.0-40 1

j 4 f 1.4.2 Land Use Census l CONTROLS { j 1.4.2.1 A land use cersus shall be conducted and shall identify the j location of the nearest milk animal, the nearest residence and the nearest j garden

• of greater than 500 square feet producing fresh leafy vegetables in i

each of the 16 meteorological sectors within a distance of five miles. 4 APPLICABILITY: Atalltimes. i i' ACTION: 4 a. With a land use census identifying a location (s) which yields a calculated dose or commitment greater than the values s f currently being ca. ..ted in ODCM Specification 1.2.4.2,'in lieu of j any other report required by ODCM Secti.on 1.6, prepare and submit j to the Commission within 30 days, pursuant to Technical Specification j j 6.9.2, a Special Report which identifies the new location (s). 1 b. With a land use census identifying a location (s) which yields a l calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location from which samples j are currently being obtained in accordance with ODCM Specification l 1.4.1.1, in lieu of any other report required by ODCM Section 1.6, j prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report which identifies the ( new location. The new location shall be added to the radiological environmental monitoring program within 30 days. The sampling l location, excluding the control station location, having the lowest l calculated dose or dose commitment (via the same exposure path-way) may be deleted frorn this monitoring program after October 31 of the year in which this land use census was conducted.

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

ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-41

'~ G ~ The provisions of Technical Specifications 3.0.3 and 3.0.4 are not c. applicable. SURVEILLANCE REOUIREMENTS 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 the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. O ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-42 l

1.4.3 Interlaboratory Comparison Procram l CONTROLS 1.4.3.1 Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Prcgram which has been approved by the Commission. APPLICABILITY: Atalltimes. ACTION: With analyses not being performed as required above, report the a. corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report. b. The provisions of Technical Specifications 3.0.3 and 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS 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 (participants in the EPA crosscheck program shall provide the EPA program code designation for the unit). ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-43

c-O 1.5 BASES B/1.1 LIOUID EFFLUENTS B/1.1.1 Radioactive Liauid Effluent Monitorino Instrumentation The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential relee cs of liquid effluents. The 1 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 10 times the concentration levels specified in 10 CFR 20, Appen-dix B, Table 2, Column 2. The OPERABILITY and use of this instrumentation is [ consistent with the requirements of General Design Criteria 60,63 and 64 of Appendix A to 10 CFR Part 50. B/1.1.2 Concentration This control is provided to ensure that concentration of radioactive materials released in liquid waste effluents from the site (see Technical Specification Figure 5.14) will be less than 10 times the concentration levels specified in 10 CFR Part 20, Appendix B, Table 2, Column 2. It provides operational flexibility for releasing liquid effluents in concentrations to follow the Section llA design objectives of Appendix i to 10 CFR 50. 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) restrictions authorized by 10 CFR 20.1301 (e). l The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radionuclide and its Effluent concentration in air (submersion) was converted to an equivalent concentra-tior, in water. This specification does not affect the requirement to comply w ith the annual limitations of 10 CFR 20.1301(a). B/1.1.3 Dose This control is provided to implement the requirements of Sections II.A, Ill.A and IV.A of Appendix 1,10 CFR Part 50. The CONTROLS ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1.044

~

O d

j implement the guides set forth in Section ll.A. of Appendix 1. The ACTION i 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 l releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable". Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is j reasonable assurance that the operation of the facility will not result in j radionuclide concentrations in the finished drinking water that are in excess l 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 l be shown by calculational procedures based on j models and data, such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The l equations specified in the ODCM for calculating the doses due to the actual l release rates of radioactive materials in liquid effluents are consistent with the l methodology provided in NUREG-0133, " Preparation of Radiological Effluent } Technical Specifications for Nuclear Power Plants", section 4.3. NUREG-0133 f implements Regulatory Guide 1.109, Revision 1, October 1977 (Section C.1 and Appendix A) and Regulatory Guide 1.113, April,1977. Regulatory Guide l 1.109, October 1977, is titled " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I". Regulatory Guide 1.113, April 1977,is titled " Estimating Aquatic Dispersion of Effluents from Accidental and } Routine Reactor Releases for the Purpose of Implementing Appendix I". B/1.1.4 Liould WasteTreatment l The OPERABILITY of the liquid radwaste treatment system ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement that the i j appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable" This control implements the requirements of l 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 4 l 50 and the design objective given in Section ll.D of Appendix 1 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 j

ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 4 ~ 1.0-45 l

e O fraction of the dose design objectives set forth in Section ll.A of Appendix 1,10 CFR Part 50, for liquid effluents. B/1.2 GASEOUS EFFLUENTS B/1.2.1 Radioactive Gaseous Effluent Monitorino Instrumentation The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in qaseous effluents during actual or potential releases of gaseous 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 OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60,63 and 64 of Appendix A to 10 CFR Part 50. t i B/1.2.2 Dose Rate This control along with controls 1.2.3 and 12.4 provide reasonable l assurance that radioactive material discharged in gaseous effluents, including radioactive effluent resulting from oil incineration, will not result in the exposure of a member of the public in an unrestricted area, either at or beyond the site boundary in excess of the design objectives of Appendix 1 to j 10 CFR 50. This control is provided to ensure that gaseous effluent from all units on the site will be appropriately controlled yet provides operational flexibility for releasing gaseous effluents to satisfy the section ll.B and li.C design objectives of Appendix 1 to 10 CFR 50. f The restrictions of Control 1.2.3 along with limited occupancy times I for a member of the public within the site boundary are sufficient to control exposure to gaseous effluent within 10 CFR 20, Appendix B, Table 2, Column 1 effluent concentrations. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the site boundary to less than or equal to 500 mrem / year 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 ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-46

j ~ c' v i 1 background to a child via the inhalation pathway to less than or equal to 1500 mrem / year. q l. This control does not affect the requimment to comply with the l 3 annual limitations of 10 CFR 20.1301(a). B/1.2.3 Dose-Noble Gases This control is provided to implement the requirements of Sections l lI.B, I!!A and IV.A of Appendix 1,10 CFR Part 50. The CONTROLS implement the j guides set forth in Section ll.B of Appendix 1. The ACTION statements provide j the required operating flexibility and at the same time implement the guides I set forth in Section IV.A of Appendix I to assure that the release 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 l Appendix 1 that conformance with the guides of Appendix l be shown by calculational procedures based on models and data such that the actual i exposure of an individual through appropriate pathways is unlikely to be lt substantially underestimated. The dose calcu'ations established in the ODCM j for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in l NUREG-0133, " Preparation of Radiological Effluent Technical Specifications l for Nuclear Power Plants", section 5.3. NUREG-0133 implements Regulatory i Guide 1.109, Revision 1, October 1977 and Regulatory Guide 1.111, Revision 1, j 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 l Compliance with 10 CFR 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. This control applies to the release of gaseous effluents from all reactors at the site and from the incineration of oil. O ODCM,V.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-47

a.- O B/1.2.4 Dose-Radioiodines, Tritium and Radioactive Materials in Particulate Form This control is provided to implement the requirements of Sections l II.C, Ill.A and IV.A of Appendix 1,10 CFR Part 50. The Limiting Conditions for Operation are 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 I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable". The ODCM calculational methods specified in the Surveillance Requirements implement the requirements in Section Ill.A of Appendix 1 that conformance with the guides of Appendix 1 be shown by calculational procedures based on models and data, such that the actual exposure of an individual through appropriate pathways in unlikely to be substantially underestimated. The ODCM calculational methods for calcula-ting the doses due to the actual release rates of the subject materials 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, R' vision 1, e 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 Compliance with 10 CFR Part 50, Appendix ", Revision 1, October 1977 and Regulatory Guide 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 equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate controls for radioiodines, tritium, and radioactive l materials in particulete 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 were:

1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition l

onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man and 4) deposition on the ground with subsequent exposure of man. O ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-48 j

O This specification applies to the release of gaseous effluents from all reactors at the site and from the incineration of oil. B/1.2.5 Gaseous Radwaste Treatment The OPERABILIT( of the GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT 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 specified, 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 II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections ll.B and ll.C of Appendix 1,10 CFR Part 50,for gaseous effluents. V B/1.3 RADIOACTIVE EFFLUENTS: TOTAL DOSE The control is provided to meet the dose limitations of 40 CFR 190 which have been incorporated into 10 CFR 20.1301(d). 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 resultant dose to a member of the public will exceed the dose limits of 40 CFR 190 if the individual reactors remain within twice the 10 CFR 50 Appendix I dose design objectives and if direct radiation doses from the units (induding outside storage tanks, etc.) are kept small. 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 ccmmitment to the member of the public from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 5 miles must be considered. If the dose to any member of V ODCM, V.C. Summer, SCE&G: Revision 21(March 1996) i i 1.0-49

e-O 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. The variance only relates to the limits of 40 CFR 190 and does not applyin any way to other dose requirements for dose limitation of 10 CFR 20, as addressed in " ODCM Controls 1.1.2.1 and 1.2.2.1. An individualis not considered a member of the public during any period in which he/she is engaged in carrying out any operation which is part of the nuclear fuel cycle. Demonstration of compliance with the limits of 40 CFR 190 or with the design objectives of Appendix 1 to 10 CFR 50 will be considered to demonstrate compliance with the 0.1 rem limit of 10 CFR 20.1301. B/1.4.1 Monitorino Procram The radiological monitoring program required by this control provides measurements of radiation of radioactive materials in those exposure pathways and for those radionuclides, which lead to the highest { potential radiation exposures of individuals resulting from the station operation. This monitoring program thereby supplements 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 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 LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidably small ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-50

y. O l 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 control is provided to ensure that changes in the use of l 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 from the door-to-door, aerial or consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section l IV.B.3 of Appendix 1 to 10 CFR Part 50. Restricting the census to gardens of l greater than 500 square feet provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden l of this size is the minimum required to produce the quantity (26 kg/ year) of l leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a j child. To determine this minimum garden size, the following assumptions l 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 ComDarison Procram i The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and l accuracy of the measurements of radioactive material in environmental sample matrices are performed as par' of the quality assurance program for t l environmental monitoring in order to demonstrate that the results are reasonablyvalid. l l j-ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-51

l r~ i O 1.6 REPORTING REOUIREMENTS 1.6.1 Annual Radioloaical Environmental Operatina Report 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 reportshall be submitted prior to May 1 of the year following initial criticality. 1.6.1.2 The Annual Radiological Environmental Operating Report shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison 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 use censuses required by ODCM Specification 1.4.2.1. If harmful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the problem. The Annual Radiological Environmental Operating Report shall include summarized and tabulated results in the format of Regulatory Guide 4.8, December 1975 of all radiological environmental samples taken during the report period. 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. The missing data shall be submitted as soon as possible in a supplementary report. The report shall also include the following: a summary description of the 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 licensee participation in the interlaboratory Comparison Program, required by ODCM Specification 1.4.3.1. O ODCM, V.C. Summer, SCE &G: Revision 21 (March 1996) 1.0-52

1.6.2 Annual Radioactive Effluent Release Report 1.6.2.1 A radioactive effluent release report covering the operation of the unit during the previous year of operation shall be submitted prior to May 1 of each year. The period of the first report shall begin with the date ofinitial criticality. 1.6.2.2 The Radioactive Effluent Release Report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as' outlined in Regulatory Guide 1.21, " Measuring, i 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. The j summary will also include quantities of radioactive gaseous effluent and solid waste (ash) released as a result of on-site oil incineration. The Radioactive Effluent Release Report shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by. hour listing of wind speed, wind direction, and atmospheric stability, and precipitation (if measured) on j magnetic tape, or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability. This same report shall include an j assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station and oil incinerator during the f 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 boundary (Figures 5.1-3 and 5.1-4 of the VCSNS Technical Specifications) during the year. All assumptions used in making these assessments (i.e., specific activity, exposure time and location) shall be included in these reports. Historical annual average meteorology or meteorological conditions concurrent with the time of release of radioactive materiais in gaseous effluents (as determined by sampling frequency and measurement) shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be l ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-53

O performed in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM). The Radioactive Effluent Release Report shall also include an assessment of radiation doses to the likely most exposed member of the public from reactor releases and other nearby uranium fuel cycle sources (including doses from 1 primary effluent pathways and dir=ct radiation) for the previous 12 consecutive months to show conformance with 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operation. Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev.1. The Radioactive. Effluent Release Report shall include unplanned releases from site to unrestricted areas of radioactive materials in gaseous and liquid effluents on a quarterly basis. The Radioactive. Effluent Release Report shall also include the following: an explanation as to why the inoperability of liquid or gaseous effluent monitoring instrumentation was not corrected within the time specified in ODCM Specifications 1.1.1.1 and 1.2.1.1, respectively. 1.6.3 Maior Chances To Radioactive Waste Treatment Systems (Liquid and Gaseous) 1.6.3.1 Licensee 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 with 10 CFR 50.59. b. Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information. ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-54

I e-O c. A detailed description of the equipment, components and processes involved and the interfaces with other plant systems. d. An evaluation of the change which shows the predicted releases or radioactive materials in liquid and gaseous effluents that differs from those previously predicted in the license application and amendments thereto. e. An evaluation of the change which shows the expected maximum exposures to individual in the unrestricted area and to the general population that differ from those previously estimated in the license application and amendments thereto. f. A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents, to the actual releases for the period prior to when the changes are to be made. g. An estimate of the exposure to plant operating personnel as a O result of the change. h. Documentation of the fact that the change was reviewed and found acceptable bythe PSRC. 2. Shall become effective upon review and acceptance as set forth m l Technical Specification 6.5. 1 [ l t i O ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-55 i l l

l e 0 1.7 Definitions ACTION 1.7.1 ACTION shall be that part of a specification which prescribes measures required under designated conditions. ANALOG CHANNEL OPERATIONALTEST 1.7.2 An ANALOG CHANNEL OPERATIONAL TEST shall be the injection of a simulated signal into 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 range and accuracy. CHANNEL CAllBRATION L'.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 channelis calibrated. CHANNELCHECK 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 channelindication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter. GASEOUS RADWASTE TREATMENT SYSTEM 1.7.5 A GASEOUS RADWASTE TREATMENT SYSTEM is any system designed and installed to reduce radioactive gaseous effluents by collecting j primary coolant system off gases from the primary system and j providing fo' delay or holdup for the purpose of reducing the total radioactiv j prior to release to the environneent. j ODCM, V.C. Su. I er, SCE&G: Revision 11 (March 1996) 1.456

e- \\ O OPERABLE - OPERABILITV 1.7.6 A system, subsystem, train, component or device shall be OPERABLE or have OPERABluTY when it is capable of performing its specified function (s), and when all necessary attendant instrumentation, con-trols, 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 function (s) are also capable of performing their related support function (s). 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 re+ e gaseour radioiodine or radicsctive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal absorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment (such a system is not considered to have any effect on noble gas effluents). Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM corn-j ponents. ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) 1.0-57

l e r l O l l 1 I 2.0 UOUID EFFLUENT l 2.1 Liauid Effluent Monitor Setpoint Calculation l The Virgil C. Summer Nuclear Station is located on the Monticello Reservoir which provides supply and discharge for the plant circulating water. This reservoir also provides supply and discharge capacity for the j Fairfield Pumped Storage Facility. The Parr Reservoir located below the pumped storage facility is formed by the Parr Dam. There are two analyzed release pathways and sources of dilution for liquid effluents: the circulating water discharge canal and the liquid effluent line to the penstocks of the pumped :,torage facility. All liquid effluent pathwayr discharge to one of these release points. Generally speaking,very low concentrations of radioactive waste are discharged to the circulating l water discharge while higher concentrations of radioactive waste are released to the penstocks of the pumped storage facility during the h l generation cycle. l The calculated setpoint values will be regarded as apper 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 back-ground count rate. l i l GENERAL NOTE: If no discharge is planned for a specific pathway or if the sum of the effluent 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 21 (March 19%) 2.0-1

i e-2.1.1 1.lould Effluent Monitor Setooint Calculation Parameters .TKm Definition

• M A

Penstock discharge a djustment factor which will allow the 2.1.2 l = l set point to be established in a convenient manner and to j prevent spurious alanns. = f /f x } t d B = Steam Generator Blowdown adjustment factor which will 2.1.4.1 allow the set point to be established in a convenient i manner and to prevent spurious alarms. l =fds l dd l CECL the effluent concentration limit (ODCM Control 1.1.2.1) 2.1.2 = j implementing 10 CFR 20 for the site,in uCi/ml. J C, l the effluent concentration of alpha emitting nuclides 2.1.2 i = i observed by gross alpha analysis of the monthly composite sample,in uCi/ml. l C, the measured concentration of Fe-55 in liquid waste as 2.1.2 = i determined by analysis of the most recent available quarterly composite sample, in uCi/ml. C = the effluent concentration of a gamma emitting nudide, g, 2.1.2 8 observed by gamma-ray spectroscopy of the waste sample, j in uCi/mL J C the concentration of nuclide i,in uCi/ml, as determined by 2.1.2 = i j the analysis of thewastesample. C, 3 the concentration of radionuclide 1, in uCi/ml, in the 2.1.2 l = 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. the concentration of Sr-89 or Sr-90 in liquid wastes as 2.1.2 C, = determined by analysis of the quarterly composite sample, in uCi/ml. C, the measured concentration of H-3 in liquid waste as 2.1.2 = determined by analysis of the monthly composite, in uCi/ml. the setpoint, in uCi/mi, of the radioactivity monitor 2.1.2 j c = measuring the radioactivity concentration in the effluent line ; ior to dilution and subsequent release. This setpoint which is proportional to the volumetric flow to the effluent line and inversely proportional to the volumetric flow of the dilution stream plus the effluent stream, represents a value which, if exceeded, would result in concentrations exceeding the limits of 10 CFR 20 in the unrestricted area.

• All concentrations are in units of uCi/ml unless otherwise noted.

O o C.v.c su--e,.sc

Re ision 21 < a ch1 e>

2.0-2

e. O Section of Term Definition initial Use the monitor setpoint concentration for RM-L7, the Nuclear 2.1.2.2 c, = Blowdown Monitor Tank discharge line raonitor, in uCi/ml. the onitor setooint concentration fc,r RM-L9, the 2.1.2 3 c = ned Liquid Waste Processing System and Nuclegir C com BI own System effluent discharge ime monitor, in pCi/ml. the monitor setpoint, concentration for RM-L11, the 2.1.4.2.2 c = Condensate Demineralizer Backwash discharge line moni-D tor,in uCi/ml. the rponitor setpoint concentration for Riy/ml., the Waste l-LS 2.1.2.1 c = Monitor Tank discharge line monitor, in uCi M the monitor setpoint concentration for RM-L3, the initial 2.1.4.1.1 c' = Steam Generator Blowdown Effluent line monitor, in 5 pCi/ml. 8 the monitor setpoin}owgcentration for RM-L10, the final j co 2.1.4.1.1 c* = own Effluent line monitor, in Stg Generator B the monitor setooint concentration for RM-L8, the Turbine 2.1.4.2.1 c = Building Sump Effluent line monitor,in uCi/ml. 7 the, Condensate Demineralize Backwash Effluent Concen-2.1.4.2 f CF = o tration Factor. the Steam Generator Blowdown Effluent Concentration 2.1.4.3 CF_ = Factor. the Turbine Building Sump Effluent Concentration Factor. 2.1.4.2 CF = 7 the dilution factor, which is the ratio of the total dilution 2.1.2 DF = flow rate to the effluent stream flow rate (s). the dilution water flow setpoint as determined prior to the 2.1.2 F = release,in volume per unit time. r$e oYrke s o th rie ding /o! d Steam Generator Blowdo"wn,in volume per unit t,me. i the dilution flow rate of the, Circulating Water System used 2.1.4.1 F' = for effluent monitor setpoint calculations, based on 90 d percent of expected Circulatina Water System flow rate s during the time of release and' corrected for,ttime. recirculated i Monticello Reservoir activity, in volume per uni w the dilution flow rate through the pens.tock(s) receivin 2.1.2 i F* = the radioactive I quid release upon which the ett ue monitor setpoint 's based, as corrected for at:y recircu latc radioactivity, in volume per unit time. The near field dilution factor for Ci during release from 2.1.4.4.1 F = u Turbine Building sump. the flow rate of water through the Fairfield Pumped 2.1.2 F, = Storage Station pennock(s) to which radioactive liquids are being discharged during the period of effluent release.This flow rate is dependent upon operational status of Fairfield Pumped Storage Station, in volume per unit time. O ODCM, V. C. Summer, SCE&G: Revision 21 (March 1996) 2.0-3

\\ i O C Term Definition 3, the effluent line flow setpoint as determined for the 2.1.2 f = radiation monitor location, in volume per unit time. the maximum permissible discharge flow rate for releases 2.1.4.1 f, = i to the Circulating Water,in volume per unit time. the flow rate of the Nuclear Blowdown Monitor Tank 2.1.2 f,3* = discharge,in volume per unit time. j the flow rate of a Waste Monitor Tank discharge, in 2.1.2 i f,* = a volume per unit time. the flow rate of the Steam Generator Blowdown 2.1.4.1 f,* = o discharge,in volume per unittime. the flow rate of the tank discharge, either f m or fdb,in 2.1.2 f, d = volume gr unit time. the recirculation flow rate used to mix the contents of a 2.1.2 f, = tank,in volume per unit time. the maximum permissible discharge flow rate for batch 2.1.2 f, = releases to the penstocks,in volume per unit time. ECL, ECL,, ECL,, ECL,, and ECL, = the limiting concen. 2.1.2 ECL; = trat, ions of the appropriate gamma emitting, alpha emitting, and strontium radionuclides, Fe-55, and tritium, respectively, from 10 CFR, Part 20, Appendix B, Table 2, V] [ Column 2. 'the safety factor, a conservative factor used to compensate 2.1.2 SF = for engineering and measurement uncertainties. SF = 0.5, corresponding to a 100 percent variation. the Lower Limit of Detection (LLD) for radionuclide i in 2.1.3 [Cle i = liquid waste in the Waste Monitor Tank, as determined by the analysis required in ODCM Table 1.1-4, in uCi/ml. the concentration of radionuclide i in the waste contained 2.1.3 [Cilu = within the Waste Monitor Tank serving as the holding facility for sampling and analysis prior to discharge, in pCi/mi. the sum of the concentrations Cg of each measured 2.1.2 ICg = g gamma emitting nuclide observed by gamma-ray spectro-scopy of the waste sample,in uCi/ml. = the gamma isotopic concentrations of the Nuclear 2.1.2 [E C ]3 r Blowdown Monitor Tank as obtained from the sum of the g measured concentrations determined by the analysis required in ODCM Table 1.1-4,in uCi/ml. (Conservatively this value will be either zero, if no release is to be conducted from this syste.m, or the maximum measured capacity of the discharge pump if a release is to be conducted.) ODCM,V. C. Summer, SCE&G: Revision 21 (March 19%) 2.0-4

~ e-O Term Definition Use [E C lo g the gamma isotopic concentrations of the Condensate 2.1.4.2.2 = g Demmeralizer Backwash effluent (including solids) as obtained from the sum of the measured concentrations determined by the analysis required in ODCM Table 1.1-4,in uCi/ml. [E C lu e the gamma isotopic concentrations of the Waste 2.1.2 = Monitor Tank as obtained from the sum of the measured g concentrations determined by the analysis required in ODCM Table 1.14,in uCi/ml. [E C ls e the gamma isotopic concentrations of the Steam 2.1.4.1.1 = Generator Blowdown as obtained from the sum of the g measured concentrations determined by the analysis required in ODCM Table 1.1-4,in uCi/ml. g the gamma isotopic concentrations of the Turbine 2.1.4.2.1 [E C h = Building Sump as obtained from the sum of the ' g measured concentrations determined by the analysis required in ODCM Table 1.1-4,in uCi/ml. I the minimum time for recirculating the contents of a 2.1.2 tr = tank prior to sampling,in minutes. the volume of liquid in a tank to be sampled,in gallons. 2.1.2 V = VJ release volume for Turbine Building sump release permit 2.1.4.4.1' = J,in gallons. O ODCM, V. C. Summer, SCE&G: Revision 21 (March 1996) 2.0-5

l i ~. ~ e-OG 2.1.2 Licuid Radwaste Effluent Line Monitors (RM-L5, RM-L7, RM L9) Liquid Radwaste Effluent Line Monitors provide alarm and auto-matic termination of release functions prior to exceeding 10 times the concentration limits specified in 10 CFR 20, Appendix B, Table 2, 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 following equation is satisfied: cf (1) 10CEct 2 pg where: { CEct= the effluent concentration limit specified in 10 CFR 20 Appendix B, l Table 2, Column 2. Note that Control 1.1.2.1 limits release l concentrations to 10 times the Appendix B, Table 2, Column 2 values. the setpoint, in uCi/ml, of the radioactivity monitor measuring the c= radioactivity concentration in the effluent line prior to dilution and subsequent release; the setpoint, which is inversely proportional to l the volumetric flow of the eff'uent line and proportional to the volumetric flow of the dilution stream plus the effluent stream, represents a value which, if exceeded, would result in concentrations exceeding 10 times the effluent concentrations of 10 CFR 20 in the unrestricted area. F= the dilution water flow setpoint as determined prior to the release point,in volume rier unit time. f= the effluent line flow setpoint as determined at the radiation monitor location,in volume per unit time. i At the Virgil C. Summer Nuclear Station the Liquid Waste Processing l System (LWPS) and the Nuclear Blowdown System (NBS) both discharge to 1 the penstocks of the Fairfield Pumped Storage (FPS) Facility through a l ODCM,V. C. Summer, SCE&G: Revision 21 (March 1996) 2.0-6 s

O common line. The available dilution water flow (F ) is assumed to be 90 d 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 y c effluent concentration, C. The three monitor setpoints are determined in accordance with the monitor system configuration for this discharge pathway. The LWPS discharges through RM-L5, which has setpoint c for u alarm / control functions over releases from either Waste Monitor Tanks 1 or

2. The Nuclear Blowdown discharges through RM-L7, which has setpoint c, for alarm / control functions over releases from the Nuclear Blowdown Monitor Tank. These two release pathways merge into a common line monitored by RM-L9, which has setpoint c for control functions over the c

common effluent line. Although the piping is arranged so that simultaneous batch releases from the two systems could be practiced, operational releases shall be from only one of the two batch systems at any civen time. The method bywhich their setpoints are determined is as follows: h 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 in1able 1.1-4: C; = Cg+Ca+Cs+Ct+Cf (2) 1 1 l where: l C = the concentration of nuclide i,in uCi/mi, as determined by 3 l the analysis of thewaste sample.* {Cg the sum of the concentrations C, of each measured gamma = emitting nuclide observed by gamma-ray spectroscopy of the waste sample,in uCi/ml. l 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. 9 ODCM, V. C. Summer, SCE&G: Revision 21 (March 1996) 2.0-7 i L

i I C,* the effluent concentration of alpha emitting nuclides = observed by gross alpha analysis of the monthly composite sample,in uCi/ml. C,* the concentration of Sr-89 and Sr-90 in liquid waste as = determined by analysis of the quarterly composite sample, in uCi/ml. the measured concentration of H-3 in liquid waste as C,* = 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 quarterly composite sample, in uCi/ml. The Ce term will be included in the analysis of each batch; terms for alpha, strontium, Fe-55, and tritium shall be included as appropriate *. Isotopic concentrations for both the Waste Monitor Tanks (WMT) and the Nudear Blowdown Monitor. Tank (NBMT) may be calculated using equation (2). Prior to being sampled for analysis, the contents of a tank shall be j isolated and recirculated. The minimum recirculation time shall be: i t, = 2V/f, (3) the minimum time for recirculating the contents of a tr = tank priorto sampling. the volume of liquid in the tank to be sampled. V = f, the recirculation flow rate used to mix the contents of a = tank. This is done to ensure that a representative sample will be obtained. Mechanical mixers shall ensure a similar minimum turnover.

• Based on most recent available composite sample analysis as required by j

Table 1.1-4. ODCM,V. C. Summer, SCE&G: Revision 21 (March 1996) 2.0-8 i I 5

i l e- \\ O 2) Once isotopic concentrations for either Waste Monitor Tank or the l Nuclear Blowdown Monitor Tank have been deterrr.ined, these values are used to calculate a Dilution Factor, DF,which is the ratio of dilution flow rate to tank flow rate (s) required to assure that 10 times the limiting concentration of 10 CFR 20, Appendix B, Table 2, Column l 2 are met at the point of discharge fer whichever tank is having its contents discharged. b (C. DF = X + SF (4) i 10 E CL); (5) C C C, C C 9 a f t -{ 10(ECL)g - 10 (E CL)a + 10 (E Cl)3_ + 10 (E CL)f DF = + g where: 1 O l = C. the sum of the ratios of the measured concentration of nuclide i to 10 times its limiting ECL value for the tank 10(E CL); x whose contents are being considered for release. For a WMT, X = M. For the NBMT,X = B. ECl = ECL,, ECL,, ECL,, ECL,, and ECL, = effluent cor:cen-l i tration limits of the appropriate gamma emitting, alpha emitting, and strontium radionudides, Fe-55, l and tritium, respectively, given in 10 CFR, Part 20, l Appendix B, Table 2, Column 2. SF = the safety factor; a conservative factor used to com-pensate for engineering and measurement uncer-tainties. l = 0.5, Corresponding to a 100 percent variation. O ODCM, V. C. Summer, SCE&G: Revision 21 (March 19%) 2.0-9

_ _~.. _ j e" O 3 3) The maximum permissible discharge flow rate, f,, may be calculated 4 for the release of either the WMT or NBMT. First the appropriate Dilution Factor is calculated by applying equation (4), using the j appropriate concentration ratio term (i.e. M or B). i

Then, f=

for F t op op dp > > Idx where: l F,, dilution flow rate to be used in effluent n:onitor setpoint = i j calculations, based on 90 percent FPS Station expected flow l rate, as corrected for any recirculated radioactivity: l C \\ i Fdp = (0.9) F I I - 10(E CL); (7) { t where: j l F, = the flow rate through the Fairfield Pumped [ .( Storage Station penstock (s) to which radioactive L !\\ liquids are being discharged. F, should normally fall between 2500 and 44800 cfs. i i C, = the concentration of radionuclide i, in uCi/ml,in l i the intake of Fairfield Pumped Storage Station I (thatis,in the Monticello Reservoir). Indusion of 5 this term will correct for possible long-term j buildup of radioactivity due to recirculation and [ { for the presence of activity recently released to j j the Monticello Reservoir by plant activities. For j. summation will be much less than 1.0 and can be expected discharges of liquid wastes, the ignored (Reference 6). f, the flow rate of the tank discharge, either f, or f,,. = f,3 flow rate of Nuclear Blowdown Monitor Tank discharge. = (Conservatively this value will be either zero, if no release is i ODCM,V. C. Summer, SCE&G: Revision 21 (March 1996) 2.0 10

O to be conducted from this system, or the maximum measured capacity of the discharge pump if a release is to be conducted.) Ce rse of Wane Monk Tad dshge. Konsena-f,, = tively this value will either be 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.) the Dilution Factor from Step 2. DF = If f, 2: fg, the release may be made as planned and the flow rate 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 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 inc8ude decreasing f, by decreasing the flow rate of f,, or f,,, and/or increasing F,p. 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 establishment of flow rate monitor setpoints may proceed as follows in Step 4. If they do not, the choice of candidate flow rates must be repeated until an acceptable set is identified. Note that if DF s 1, the waste tank concentration for which the calculation is being performed indudes safety factors in Step 2 and meets the instantaneous release rate limits without further dilution. Even though no dilution would be required, there will be no l discharge if minimum dilution flow is not available, since the penstock minimum flow interlock will prevent discharge. O ODCM, V. C. Summer, SCE&G: Revision 21 (March 1996) 2.0-11

OV l 4) The dilution flow rate setpoint*, F, is established at 90 percent of the expected available dilution flow rate: F = (0.9) F, (8) The flow rate monitor setpoint* for the effluent stream shall be set at the elected discharge pump rate (normally the maximum j discharge pump rate or zero)f or f. chosen in Step 3 above. g 5) The radiation monitor setpoints may now be determined based on the values of E Ci, F, and f which were specified to ensure releases are limited to 10 times the values of 10 CFR 20, Appendix B, Table 2, Column 2. The monitor response is primarily to gamma radiation, therefore,the actual setpoint is based on EC,. l The setpoint concentration, c, is determined as follows: II) cs C XA g A= Adjustment factor which will allow the setpoint to be established in a practical manner for convenience and to prevent spurious alarms. i (10) l A=fII t dx If A 21,. Calculate c and determine the maximum value for the actual monitor setpoint (cpm) from the monitor calibra-tion graph. l

• Setpoints for flow rates are administrative limits.

j ODCM,V. C. Summer, SCE&G: Revision 21 (March 1996) 2.0-12 i I 3 )

I l h l l If A < 1, No release may be made. Reevaluate the alternatives presented in Step 3. NOTE: If calculated setpoint values are near actual concentrations planned for release, it may be impractical to set the monitor alarm at this value. In this case a new setpoint may be calculated following the remedial methodology presented in Step 3 for the case of f, < f,. Within the limits of the conditions stated above, the specific monitor setpoint concentrations for the three liquid radiation monitors RM. L5, RM-L7, and RM-L9 are determined as follows: 2.1.2.1 RM-L5, Waste Monitor Tank Discharae Line Monitor: C s C M (A) M g O Cu is in uCi/mi

• See GENEPAL NOTE under 2.1.

2.1.2.2 RM-L7, Nuclear Blowdown Monitor Tank Discharae Line Monitor: C s C B ( A) (12) B g Cs is in uCi/mi l NOTE: In no case should discharge be made directly from the Nuclear Blowdown Holdup Tank to the l penstocks.

• See GENERAL NOTE under 2.1.

2.1.2.3 RM-L9, Combined Liauid Waste Processina System and Nudear Blowdown Waste Effluent Discharae Line Monitor The monitor setpoint concentration on the common line, c, should be the same as the setooint c ODCM,V. C. Summer, SCE&G: Revision 21 (March 19%) 2.0-13

e-concentration for the monitor on the active individual discharge line (i.e., c, or c, as determined above): u (13) C s MAX (CM,C ) C B

• 5ee GENERAL NOTE under 2.1.

j NOTE: In all cases, c, c,, and c are the setpoint y c l concentration values in uCi/ml. The actual l monitor setpoints (cpm) for RM-L5, RM-L7, and RM-L9 are determined from the calibration graph for the particular monitor. Initially, the calibra-tion curves were determined conservatively from families of response curves supplied by the monitor manufacturers. A sample is shown in l Figure 2.1-1. As releases occur, a historical correlation will be prepared and placed in service when sufficient data are accumulated. l 2.1.3 Llauid Radwaste Discharae Via industrial and Sanitarv Waste System l (RM-L5) in the Virgil C. Summer Nuclear Station liquid waste effluent system design, there exists a mechanism for discharging l l liquid wastes via the Industrial Sanitary Waste System. The sample l point prior to discharge is one of the Waste Monitor Tanks. The j analysis requirements are the requirements listed in Table 1.1-4. l l 4l' ODCM, V. C. Summer, SCE&G: Revision 21 (Ma rch 1996) 2.0-14 i

? O This effluent pathway shall only be used when the following condition is met for all radionuclides,i: Ci, M i.LLD (14) s C the concentration of radionuclide i in the waste con-Ci, M = tained within the Waste Monitor Tank serving as the holding facility for sampling and analysis prior to discharge,in uCi/ml. Ci, LLD = the Lower Limit of Detection,(LLD) for radionuclide i in the liquid waste in the Waste Monitor Tank as deter-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 h spurious cl arms and yet alarm should an inadvertent high concentration release occur. 2.1.4 Steam Generator Blowdown, Turbine Buildina Sump, and Conden-sate Demineralizer Backwash Effluent Lines (RM-L3, RM-L10, RM-L8, RM-L11) Concentrations of radionuclides in the liquid effluent discharges 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 sampled in an appropriate manner as specified in Table 1.1-4 of the ODCM. The Steam Generator Blow-down Monitors, the Turbine Building Sump Monitor, and the Condensate Demineralizer Backwash Monitor provide alarm and automatic termination. O ODCM,V. C. Summer, SCE&G: Revision 21 (March 1996) 2.0-15

.~ /- In reality, all of these effluent pathways utilize the circulating water as dilution to the effluent stream, with the circulating water discharge canal being the point of release into an unrestricted area. Steam Generator Blowdorun Effluent may be released to the Circulating Water either directly in the Condenser outflow (the normal flow path) or in the first hours following startup via the Industrial and Sanitary Waste i System (ISWS) for chemical reasons. The Turbine Building Sump and Condensate Demineralizer Backwash Effluents enter Circulating Water via the sumps and ponds of the Industrial and Sanitary Waste System. CO31 To ensure compliance with ODCM specification 1.1.2.1, normally no dilution is assumed for discharges to the Industrial and Sanitary Wact System. Additionally, releases are normally limited to 1 ECL to ensure that the conditions of 10 CFR 20.1301 are met. These administrative controls provide assurance that ODCM specification 1.1.2.1 would not be compromised in the event circulating water dilution is lost. To add operational flexibility for abnormal conditions (radionuclide concentration in l Turbine Building sump > 1 ECL), discharges from the Turbine Building sump and j concentrations in the discharging ponds of the ISWS may exceed the operational j objective,1 ECL, provided circulating water dilution is sufficient to ensure compliance } with ODCM specification 1.1.2.1 and liquid effluents are being discharged in } compliance with ODCM specification 1.1.4.1. Two separate setpoint calculations are given for Turbine Building sump j p discharges (RM.L8). Section 2.1.4.2.1 describes the setpoint calculation normally used, l j\\d limiting discharges to 1 ECL Section 2.1.4.4 provides an altamate setpoint j methodology which may be used during abnormal conditions. RM-L8 setpoints are considered in compliance with ODCM specification 1.1.1.1 provided the setpoints are j CO3 i adequate to prevent releases in excess of ODCM specification 1.1.2.1. i ) Two mutually exclusive setpoint calculation processes are outlined below for steam generator blowdown. Section 2.1.4.1 is to be used whenever Steam Generator Blowdown 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 Blowdown is being released to the Industrial and Sanitary Waste System, or diverted to the Nuclear Blowdown Processing System, both of which are alternate modes. Normally, water collected by the Nuclear Blowdown Processing System has very low specific activity. This water may be processed to the Turbine Building sump. NOTE: When Circulating Water is unavailable for effluent dilution and water is being directed to a releasing ISWS pond, releases containing activity above LLD (excluding tritium) should be discouraged via pathways which lead to it. Steam Generator Blowdown should be diverted to the Nuclear Blowdown ODCM, V. C. Summer, SCE8rG: Revision 21 (March 1996) 2.0-16

e-O Processing System. Condensate Demineralizer Backwash may be diverted to the Turbine Building sump or not released. Turbine Building sump effluent should be processed thrcugh temporary demineralizers or diverted to the Excess Liquid Waste Processing System. (These steps are to keep the calculated dose to individuals as low as reasonably achievable.) An option for directing water from the TBS with specific activity >LLD to a non releasing pond is provided in Section 2.1.4.5. 2.1.4.1 Steam Generator Blowdown Effluent Direct to Circ ~ulatina Water (Normal Mode) t Equation (1) is again used to assure that effluents are in i com pliance with the aforementioned specification: i cf 10 Cect 2: I The available dilution water flow (F ) is dependent upon ( d 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 Generator Blowdown monitor setpoints (c, and c ) are set to meet 3 the condition of equation (1). I RM-13, the first monitor in the Steam Generator Blowdown discharge pathway, alarms and terminates release of the stream. The j discharge is then automatically diverted to the Nuclear Blowdown ( Processing System. RM-L10, the last monitor in the Steam Generator i Blowdown discharge pathway, alarms and terminates the release. Thus, RM-L10 is redundant to RM-13 and the setpoint (c ) will be 3 determined in the same manner as RM-L3 (c,). s The method by which the monitor setpoints are determined is as follows: 1) The isotopic concentrations for any release source to be or being released are obtained from the sum of the measured ODCM,V. C. Summer, SCE&G: Revision 21 (March 1996) 2.0-17

o t O concentrations as determined in Table 1.1-4. Equation (2) is again employed for this calculation: h C; = Cg+C,+Cs+Ct+Cf { where: EC = the sum of the measured concentrations as determined i I bytheanalysis of thewastesample,in uCi/ml. d I {C, = the sum of the concentrations C, of each measured gamma emitting nuclide observed by gamma-ray spectroscopyof thewastesample,in uCi/ml. the measured concentration C, of alpha emitting C, = composite sample,in uCi/ml. the measured concentrations of Sr-89 and Sr-90 in C, = liquid waste as determined by analysis of the most recent available quarterly composite sample, in uCi/ml. the measured concentration of H-3 in liquid waste C, = determined by analysis of the monthly composite sample,in uCi/ml. the measured concentration of Fe-55 in liquid waste as C, = determined by analysis of the most recent available quarterly com posite sample, in uCi/ml. Isotopic concentrations for the Steam Generator Blowdown System effluent, the Turbine Building Sump Effluent, and j the Condensate Demineralizer Backwash effluent may be i 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 j total dilution flow rate to effluent stream flow rate ODCM,V C. Summer, SCE8rG: Revision 21 (March 1996) 2.0-18 )

O required to limit the effluent concentration at the point of discharge to less than 10 times the values in 10 CFR 20, Appendix B, Table 2, Column 2. E (ECL); + SF DF = 1 10 s (16) C C C C C 10 (E CL)a + 10 (E CL)s + 10 (E CL)[ 10 (E CL)t ' 10(E L) where: C,, C, C,, C,, and C,; measured concentrations as C = i defined in Step 1. Terms C,, C,, C,, and C, will be included in the calculation as appropriate. O C*. E (ECL)i the sum of the ratios of the measured concen- = 1 10 s tration of r aclide i to its limiting value ECL; for the Steam Generator Blowdown effluent. ECL,, ECL,, ECL,, ECL and ECL, are limiting l ECL; = g concentrations of the appropriate radionuclide from 10 CFR, Part 20, Appendix B, Table 2, l Column 2 limits. i SF = the same generic term as used in Section 2.1.2, Step 2. = 0.5 3) The maximum permissible effluent discharge flow rate, l f, may now be calculated for a release from the Steam e Generator Blowdown. O ODCM, V. C. Summer, SCE&G: Revision 21 (March 19%) 2.0-19 l

c, O F Il7) Fdc + Ids dc fd= op op frFdc > > Ids where: Dilution flow rate for use in effluent monitor setpoint F, = 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: Fdc = (0.9) Fd II~ 10 (E CL); where: F = the flow rate of the Circulating Water System d 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. C, = theconcentration of radionudidei,in uCi/mi,inthe 3 Circulating Water System intake, (that is, in the Monticello Reservoir). Inclusion of this term will correct for possible long term buildup of radio-activity due to recirculation and for the presence of activity recently released to the Monticello-Reservoir by plant activities. For expected dis-charges of liquid wastes, the summation will be much less than 1.0 and can be ignored (Reference 6). f, Flow rate of Steam Generator Blowdown discharge. = e (This value normelly 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.) ODCM, V. C. Summer, SCE&G: Revision 21 (March 1996) l O 2.0-20 !V l I m.. m

.l ~ O Note that the equation is valid only for DF > 1; for DF s 1, the effluent concentration meets the release criteria without dilution as well as being in compliance with the conservatism imposed by the Safety Factor in Step 2. 11f, a f,,, releases may be made as planned. Becatae F,1s e 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 establishment of flow rate monitor setpoints should proceed as follows in Step 4. If they do not. provide an acceptable release, the choice of candidate flow rates must be repeated until an acceptable set is identified. 4) The dilution flow rate setpoint for minimum flow rate, F,is established at 90 percent of the expected available dilution flow rate: F = (0.9)(F,) (19) Flow rate monitor setpoints for the Steam Generator Blowdown effluent stream shall be set at the selected discharge pump rate (normally the maximum discharge pump rate) f chosen in Step 3 above. ds 5) The Steam Generator Monitor setpoints may be specified based on the values of E Ci, F,and f which were specified to g, ODCM, V. C. Summer, SCE&G: Revision 21 (March 1996) 2.0-21

Ov limit discharge within 10 times the limits of 10CFR 20, Appendix B, Table 2, Column 2. Since the monitor responds primarily to gamma radiation, therefore, the actual setpoint is based on E Cg. The monitor setpoint in cpm which corresponds to the calculated value c is taken from the monitor calibration graph. (See NOTE, page 2.0-14.) The setpoint concentration, c, is determined as follows: (20) csEC XB 9 9 B = f,H,, W) Ifi: 2: 1, 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 alter-natives presented in step 3. (D %J NOTE: If the calculated setpoint value is near actual concentrations being released or planned for release, it may be impractical to set the monitor alarm at this value. In this case a new setpoint may be calculated following the remedid methodology presented in steps 3 and 4 forthe ca: f, < f.. Wohin the conditioris stated above, the specific monitor setpoint concentrations for the two steam generator blowdown monitors RM-L3 and RM-L10 are calculated as shown on the followmg page. J I 2.1.4.1.1 For RM-L3. Steam Generator Blowdown Dis-I charoe initial monitor, and for RM-L10, Steam Generator Blowdown Discharce final monitor: l ODCM,V. C. Summer, SCE&G: Revision 21 (March 19%) 2.0-22 C i

e O 5a orc 5b ' C 5 (B) (22) C s EC the isotopic concentration of the Steam Generator = 9 g 5 Blowdown effluent as obtained from the sum of the measured concentrations determir.ed y the analysis required in ODCM Table 1.1-4,in uCi/ml.

• See GENERAL NOTE under 2.1.

2.1.4.2 Turbine Buildina Sump and Condensate Demineralizer Saclgyash(Normal Mode) i For conservatism, the Turbine Building Sump and Conden-sate Demineralizer Backwash monitor setpoints (c and c ) will claim r o no dilution from the Circulating Water, and will be set at the appli-cable concentration limit. Thatis: CECL 2: c (23) The Turbine Building sump monitor, RM-L8, alarms and terminates release upon exceeding the monitor setpoint (c). The t discharge can then be manually diverted to the Excess Waste Processing System. RM-L11, the Condensate Demineralizer Backwash monitor, alarms and terminates release upon exceeding the monitor setpoint (c ). The discharge may then be manually diverted to the o Turbine Building sump or simply delayed. The Turbine Building Sump and Condensate Demineralizer Backwash monitor setpoints are to be established independently of each other and without crediting dilution. They are to be based on the measured radionuclide concentrations of the effluent stream and are to ensure that discharge concentrations do not exceed the ECLs specified in 10 CFR 20, Appendix B, Table 2, Column 2 prior to discharge. For each effluent stream, a concentration factor (CF) is calculated by summing the ratios of detected radionuclides in the ODCM,V. C. Summer, SCE8 G: Revision 21 (March 1996) 2.0-23

l l 1 effluent stream to the applicable ECLs, the calculated values i normalize the effluent mixture to terms of ODCM Control 1.1.2.1 re-1 lease criteria and includes a safety factor for engineering uncertainty. b (ECL); f CF = + 5F i j C-b (ECL);T + SF (25) } CFT= b (ECL);D + 5F I CFD= (20 j i where: C. t { (ECL); l the sum of the ratios of the measured concentration of = i T nuclide i to its limiting value ECL for the Turbine Build-i ing sump effluent. \\ C-E (ECL); the sum of the measured concentration of nuclide i = s D (in liquid only) to its limiting value ECL for the i Condensate Demineralizer Backwash effluent. CF the concentration factor for the Turbine Building Sump = 7 Effluent. I the concentration factor for the Condensate Demin-h CF = o eralizer Backwash Effluent. the generic engineering safety factor used in Section SF = 2.1.2, Step 2. 0.5 =

ifCFs1, 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, diverted, or processed. ODCM,V.C. Summer,SCE&G: Revision 21(March 1996) 2.0-24

e-e O If the concentration factor cannot be reduced to less than or equal to 1, proceed to section 2.1.4.4 or 2.1.4.5 for additional guidance for processing Turbine Building Sump releases. Within the limits of the conditions stated above, the specific monitor setpoint concentrations for RM-L8 and RM-L11 may now be calculated. Because they are primarily sensitive to gamma radiation, their setpoints will be based on the concentrations of gamma emitting radionuclides as follows: 2.1.4.2.1 For RM-LB. Turbine Buildina Sump Discharae ' Monitor: c s C T + CFT (27) T g Where: yC. The gamma isotopic concentration of the Turbine Building = - g g T sump effluent as obtained from the sum of the measured concentrations determined by the analysis required in ODCM Table 1.1-4,in uCi/ml. The Turbine Building sump Effluent Concentration Factor CFT = from equation (25).

• See GENERAL NOTE under 2.1.

O ODCM, V. C. Summer, SCE&G: Revision 21 (March 1996) 2.0-25

1 ~ e-O l 2.1.4.2.2 For RM L11, Condensate Demineralizer Backwash Discharoe Monitor: ( c s C D + CFD (28) D g l where: .Eg The gamma isotopic concentration of the Condensate = - 9 9 D Domineralizer Backwash effluent (including solids) as ob-tained from the sum of the measured concentrations j determined by the analysis required ODCM Table 1.1-4, in i uCi/ml. CFo = The Condensate Demineralizer Backwash Effluent Concen-tration Factor from equation (26). j

• See GENERAL NOTE under 2.1.

i 2.1.4.3 Steam Generator Blowdown Effluent Not Directly to Circu-latina Water (Alternate Mode) O Equation (23) is again used to assure that effluents are in compliance with the aforementioned specification before dilution in 4 the receiving water: CECL 2c Because dilution is not considered in the setpoint calculation, it is not necessary to calculate maximum permissible discherge flow rates or anticipated available dilution flow rate. The functions of the two monitors whose setpoints are to be established are described in Section 2.1.4.1 above. The method for the determination is as follows: 1) If a release is found to be permissible, flow rate monitors for the active effluent streams (Steam Generator Blow-down - f,,, Turbine Building sump - f, and Condensate dt Demineralizer - fed) may have their setpoints established at l any operationally convenient value. ODCM, V. C. Summer, SCE8 G: Revision 21 (March 1996) 2.0-26

e. -

9 ~ 2) The Concentration Factor of equation (24) is again used to ensure the permissibility of the release. C-1 b (ECL); + 5F CF = i C. 5 + SF (29) CFS* (E CL); L All terms are defined in subsection 1.1.3.1 and subscript 5 refers to the Steam Generator Blowdown Effluent. If CF s 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. i Within the above limitation, setpoint concentrations may now be calculated for the two effluent monitors. Because they are primarily sensitive to gamma radiation, their setpoints will be based on the concentrations of gamma emitting radionuclides as follows: 2.1.4.3.1 For RM-L3, Steam Generator Blowdown Dis.' charoe initial monitor, and RML-10, Steam Generator Blowdown Discharoe final monitor: 1 s C 5b g 5 + CFS (30) c5a 'C O l ODCM, V. C. Summer, SCE&G: Revision 21 (March 19%) 2.0-27

I l e-O Where: 1C The isotopic concentration of the Steam Generator = - 9 g 5 Blowdown effluent as obtained from the sum of the measured concentrations determined by the analysis required in ODCM Table 1.1-4,in uCi/ml. CF = The Steam Generator Blowdown Effluent Concentration s Factor from equation (29).

• 5ee GENERAL NOTE under 2.1.

CO3-+ 2.1.4.4 Turbine Buildino Sumo (Abnormal Conditions) Provided circulating water is available,1 to 3 circulating water pumps, effluent exceeding 1 ECL may be released from the Turbine Building l sump to the industrial and sanitary waste system, using the setpoint in this section, provided the following conditions are met: 1) Instantaneous release rate limits of ODCM Specification 1.1.2.1 are not exceeded in the circulating water discharge canal. 2) Annual average concentrations of radioactivity in 15WS ponds will not exceed 1 ECL 3) The limits of ODCM specification 1.1.4.1 will not be exceeded with j actual liquid effluent releases over a 31 day period. 4) Average discharge flow does not exceed values used in setpoint i determination. In addition, the source of radioactivity should be identified and j isolated. Radionuclide concentration in Turbine Building sump effluent should be restored to <1 ECL as soon as possible and normal setpoint reestablished. Radionuclide concentration in Pond 6B should be restored to < LLD (excluding tritium) using dilution as necessary (normal flow from the TBS would normally be adequate). Turbine Building sump samples should be obtained and analyzed every twelve hours while the alternd-setpoint is l being used to ensure that the setpoint remains conservative with respect to the isotopic mixture and to ensure offsite doses are within ODCM limits. ODCM, V. C. Summer, SCE&G: Revision 21 (March 1996) 2.0-28

~ e-O Alternate setpoint methodology for Turbine Building sump (RM-L8) is available to ensure operational flexibility in the event radioactivity is detected in the Turbine Building sump > 1 ECL and the release would result l in minimal offsite dose. The alternate setpoint methodology is not intended to be used continuously. To remove restrictions on operation of circulating water, pond concentrations should be restored to < LLD as soon as possible. The setpoint methodologyfollows: 2.1.4.4.1 For RM-L8, Turbine Buildino Sump (alternate methodoloav) (57) Lc X T '= 0 c

where, The near field dilution factor for Ci during release F

= e from Turbine Building sump. (averaae undiluted waste flow) = (average flow from discharge structure) For purpose of implementing section 2.1.4.4 release condition 2, the following must be satisfied. n x [ (C1/ECLi). T

• Vl i[=1 J

(58) i=1 < 1.0 n 3 1 (I(Ci ECLi)]Tj = the sum of the ratios of the measured concentration l w~ / of nuclide i to its limiting value ECLi or the Turbine Building sump f effluent for release permit j, including proposed permit, Vj = Release volume for Turbine Building sump release permit j (gal),and j = index for batch release permits during the calendar year. ODCM,V. C. Summer,5CE&G: Revision 21 (March 19%) 2.0-29

.~ OO 2.1.4.5 Turbine Buildino Sumo - Soecial Considerations Durino Station Shut-downs During periods in which circulating water (CW) is not availab!e for diluting Turbine Building Sump (TBS) discharges, effluent from the TBS rnay be directed to a non-releasing pond and offsite dose calcelations required by Specification 1.1.3.1 deferred until CW is restored. RM-L8 setpoint require-1 ment specified by Specification 1.1.1.1 is not applicable when directing water from the TBS to a non-releasing 15W5 pond provided the following condi-l tions are met. 1) Sufficient freeboard is available in the non-releasing pond to ensure that pond contents will not be released to the CW discharge canal prior to reestablishing CW flow. 2) Release of 15W5 contents will be in compliance with Specifications 1.1.2.1,1.1.3.1 and 1.1.4.1 once CW flow has been reestablished. 3) 15W5 pond radioactivity will not exceed 1 ECL 4) TBS samples are obtained and analyzed every 12 hours while water is being directed to a non-releasing pond. 5) Sample non-releasing pond within 12 hours of adding water >1 ECL and every 12 hours thereafter while TBS discharge concentrations exceed 1 ECL Once samples have been obtained and release acceptability determined, RM-L8 setpoint may be increased to 2 times indication to allow release of sump contents to a non-releasing pond. Demonstrating compliance with item 3 can be performed by calculations using TBS samples and discharge volumes or bysampling 15W5 ponds. ODCM, V. C. Summer, SCE&G: Revision 21 (March 19%) 2.0-30 L s

e-f Ol Figure 2.1-1 Example Liquid Effluent Monitor Calibration Curve 1E.02 G ) / / / 1E-03 / / t o I / / = 1EO E } 5 O 3 6 / v I l l 2 1 O / / t F 1E@ <C i CC / l O Z O / / O 1E-06 l l I f l / l 1 s L / 1E-07 J 6 I, / 1 / 1EG, 1E + 00 1E+01 1E+02 1E+03 1E+04 1E+0S 1E+06 COUNT RATE (cpm) l l l l ODCM,V. C. Summer, SCE&G: Revision 21 (March 1996) 2.0-31 i Ol l

1 d 2.2 Dose Calculation For Liould Effluents The rnethod of this section is to oe used in all cases for calculating ooses 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 Liould Effluent Dose Calculation Parameters Term Definition "ye A' - the site related ingestion dose commitment 2.2.2 factor to the total body or any orga n 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 pCill, from Table 2.2-1. C the average concentration of radionuclide,i,in 2.2.2 = a undiluted liquid effluent during time At from anyliquid released,in uCi/ml. period g 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. O(d D' the cumulatise dose commitment to the total 2.2.2 = body or any organ, t, from the liquid effluents for the total time period, eat in mrem (Ref.1). k D* Dilution Factor from the near field area within 2.2.2 = one-quarter mile of the release points to the potable water intake for adult w;ter consumption; for V. C. Summer, D, = 1. F, the near field average dilution factor for C, 22.2 = during any liquid effluerit release. K = 1.14 x 105, units conversion factor = 2.2.2 (106 pCi/uCi)(103 ml/l) + 3760 hr/yr Atk = the length (in hours) of a time period over 2.2.2 which concentrations and flow rates are averaged for dose calculations. U, 21 kglyr, fish consumption (adult) (Reference 2.2.2 = 3). U, 730 kg/yr, water consurr.ption (adult) (Refer-2.2.2 = ence 3). Z = apolicable near-field dilution fact:r when no 2.73 additional dilution is to be considered; 2 = 1. .p ODCM, V. C. Sum.ner, SCE&G: Ftevision 21 (Mar:h 1996) 2.0-32

0 2.2.2 Methodology The dose contribution from a!! radionuclides identified in. liquid effluents released to unrestricted areas is calculated using the following expression: t it k k C F D= A i kk An = Ko((Uw / Dw) + U BFi) DFn (32) F fk= (average undiluted licuid waste flow) (33) (averagellow from the discharge structure) (Z) NOTE 1: If radioactivity in the Monticello Reservoir (C) becomes > the LLD specified in ODCM, Table 1.1-4, that concentration must be included in the Dose determination. For this part of the dose calculation, Fk = 1 and Atk = the entire time period for which the doseis bemg calculated. NOTE 2: Prior to termination of Circulating Water Pumps, an assess, ment of the dose resulting from pond radioactivity concentrations and discharge flow rates from the Industrial And Sanitary Waste System (15WS) will be performed as follows. Sampling of the liquid in the 15WS will be initiated, and the measured concentrations of radionuclides will be used in the dose calculations with Fk = 1 and A tk = the entire t me period for wh!ch the dose is being calculated. NOTE 3: For releases through the 15WS pathway when circulating water is not available, dose projections for assessment of release acceptability should be based on the most representative samples obtained from in plant sumps. Normally sump samples are also used to asser actual release. However, due to the ultraconservative assumptions when circulating water is not available, i.e. dose calculations are based on radioactive mnerial concentration in the discharge stream regardless of release voluene, representative samples from the 15WS may be used to evaluate imract of releases. O DCM, V. C. Cummer, SCE&G: Revision 21 (March 1996) 2.0-33

j i () l NOTE 4: During periorb when the Circulating Water Pumps are in 1 operation, any releases to the ISWS.a_re to be credited with dilution in Circulating Water for dose calculation purposes, i even though such dilution is normally not claimed in the setpoint calculation. When taken in union with the note above, this procedure results in some overestimation of dose 3 to the population because discharges made to the ISWS just before loss of Circulating Water will be counted twice in the dose calculation process. NOTE 5: If radioactivity in the Service V/ater becomes > LLD as determined by the analysis required b/ ODCM, Table 1.1-4, that concentration must be included in the Dose determination. For this part of the dose calculation, F = 1 g and A t, = the entire time since the inst Service Wr+er sample was taken.

• O

,V l i l 1 r') ODCM, V. C. Summer, SCE&G: Revision 21 (March 1996) 2.0 34 v

e-9 2.3 t.icuid Effluent Releases throuah the Neutralization Basin Releases of slightly contaminated licuids from pathways feeding the Neutralization Basin (Pond 007) through Circulating Water (CW) may be made under strictly controlled conditions. Releases from these pathways (e.g., NaOH sump, RWST sump) will be allowed if the following conditions are adhered to in contro!!ing the radioactive materials released. 2.3.1 Rainwater Tank l Rainwater coilected in the RWST sump is pumped to the RW5T Pit Drain Tank (Painwater Tank) for analysis and subsequent release. Normally the rainwater is sampled, found to contain no detectable radioactivity, and is released to the environment via the storm drain system. If measurable amounts of radioactive materials are found in Rainwater Tank samples, the tank may be pumped to a Waste l Monitor Tank and released without processing. In order to allow'for operational flexibility, the Rainwater Tank containing radioactive materials may be drained to the NaOH sump and discharged to the circulating water (CW) system via the Neutralization basin (007). The following cons +raints are to be applied for releases through this pathway: (1) At least one CW pump must be used for dilution to release through this pathway. (2) Chemistry Services must be notified to verify that conditions in the Neutralization Basin are such that additions to the basin can be made. (3) Using the Rainwater Tank analysis and available circulating water, a release calculation must be performed that shows that.eleases will be less than 6.0E-4 mrem (whole body) and 2.0E-3 mrem (any organ). These limits represent 1% of unprocessed effluent 31-day dose limits (ODCM Section 1.1.4.1). ODCM, V. C. Summer, SCE&G: Re vision 21 (March 1996) 2.0-35

. _ ~ - _ - -. - -. - = _ - ] ..T i i i } (4) If these limits are met, the Rainwater Tank may be drained through the NaOH sump to the Neutralization Basin. Chemistry will then release the Neutralization Basin contents through circulating water as soon as t possible once their procedural and NPDES release criteria are met. i i j 2.3.2 NaOH Sptav Tank af.d Sjt dpj, NaOH f i (1) The same limits and conditbns as 2.3.1 (1-4) apply for releases from i i the NaOH sump. 1 (2) Samples should be obtained and analyzed during performance of j NaOH Soray Tank activhies that require the draining of NaOH from the tank or sight glass. t ) (3) 11 the sample show concentrations of radionuclides that would exceed i the dose limits above and the tank must have liquid removed from it, 1 the contaminated NaOH may be drained to appropriate holding l containern for temporary storage. Once the conditions for release j become favorable (e.g. retum of CW), the contamers used for j temporary storage may be sampled and analyzed for release if the i dose limitations in 2.3.1 (3) are met and Chemetry approval is 1 obtained, a release permit is generated and the containers can be drained throtch the NaOH sump or ernptied direc3y to the l j Neutralization Basin for release through CW. i I i "a 2 ODCM, V. C. Sumn'er, SCE&G: Revision 22 (August 1996) i 2.0-3S 4 k a i rm

i e*l e-O TABLE 2.2-1 BtOACCUMULATION FACTOR 5* (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 1 Cr 2.0E 02 i 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 Zr 3.3E 00 Nb 3.0E 04 Mo 1.0E 01 Tc 1.5E 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 i Ce 1.0E 00 Pr 2.5E 01 Nd 2.5E 01 W 1.2E 03 Np 1.0E 01 ' Values in Table 2.2-1 are taken from Reference 3, Table A-1. ODCM, V. C. Summer, SCE&G: Revision 21 (March 1996) h 2.0-37

~ g ^ TABLE 2.2-2 g Page 1 of 2 ADULTINGESTION DOSE FACTORS * (mrem /pCiingested) NUCLIDE BONE UVER T. BODY THYROID KIDNEY LUNG GI LLI H-3 NO DATA 1.05E-07 1.05E-07 1.05E 07 1.05E-07 1.05E-07 1.05E-07 C-14 2.84E-06 5.68E-07 5.680-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 t F-18 6.24E-07 NO DATA 6.975-08 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 12 n.-05 7.46E-05 NO DATA NO DATA NO DATA 2.17E-05 CR-51 NO DATA NO DATA 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 MN-54 NO DATA 4.37E-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 3.91 E-06 NO DATA NO DATA 2.85E-06 3.40E-05 tCO-57 NO DATA 1.75E-07 2.91E-07 NO DATA NO DATA NO DATA 4.44E-06 CO-58 NO DATA 7.45E-07 1.67E 06 NO DATA NO DATA NO DATA 1.51 E-05 CO-60 NO DATA 2.14E-06 4.72E-06 NO DAl A NO DATA NO DATA 4.02E-05 ! N1-63 1.30E-04 9.G1E-06 4.36E-06 NO DATA NO DATA NO DATA 1.88E-06 I NI-65 5.28E-07 6.86E-08 3.13E-08 NO DATA NO DATA NO DATA 1.74E-06 CU-64 NO DATA 8.33E-08 3.91 E-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 ZN-69 1.03E-08 1.97E-08 1.37E-09 NO DATA 1.28E-08 NO DATA 2.96E-09 }: tZn-69m? 1.70E-07 4.0SE-07 3.37E-08 NO DATA 2.47E-07 NO DATA 2.49E-05 tBR-82 NO DATA NO DATA 2.26E-06 NO DATA NO DATA NO DATA 2.59E-06. BR-83% NO DATA NO DATA 4.02E-08 NO DATA NO DATA NO DATA 5.79E-08 ( O (V BR-84 NO DATA NO DATA 5.21E-08 NO DATA NO DATA NO DATA 4.09E-13 i BR-85 t NO DATA NO DATA 2.14E-09 NO DATA NO DATA NO DATA LT E-24** RB-86 NO DATA 2.11 E-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-89t NO DATA 4.01E-08 2.82E-08 NO DATA NO DATA NO DATA 2.33E-21 SR-897 3.08E-04 NO DATA 8.84E-06 NO DATA NO DATA NO DATA 4.94E-05 l 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 SR-92% 2.15E-06 NO DATA 9.30E-08 NO DATA NO DATA NO DATA 4.26E-05 I Y-90 9.62E-09 NO DATA 2.58E-10 NO DATA NO DATA NO DATA 1.02E-04 i Y-91Mt 9.09E-11 NO DATA 3.52E-12 NO DATA NO DATA NO DATA 2.67E-10 l Y-91 1.41 E-07 NO DATA 3.77E-09 NO DATA NO DATA NO DATA 7.76E-05 e 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 8.50.~-05 ZR 95% 3.04 E-08 9.75E-09 6.60E-09 NO DATA 1.53E-03 NO DATA 3.09E-05 ZR-97* 1.68E-09 3.39E-10 1.55E-10 NO DATA 5.12E-10 NO DATA 1.05 E-04 NB-95 6.22E-09 3.46E-09 1.86E-09 NO DATA 3.42E-09 NO DATA 2 102-05 ' t NB-97 5.22E-11 1.32E-11 4.82E-12 NO DATA 1.54E-11 NO DATA 4.87E-08 MO-99? NO DATA 4.31E-06 8.20E-07 NO DATA 9.76E-06 NO DATA 9.99E-06 $ Daughter contributions are included (see Reference 13). 1 Values taken from Reference 13, Table 4.

• Values other than those footnoted in Table 2.2-2 are taken from Reference 3, Table E-11.
  • Less than E-24.

i ODCM, V.C. Summer, SCE& G: Revision 21 (March 1996) n 2.0-38

a. -

~ TABI E 2.2-2 (continued) Page 2 of 2 NUCLIDE BONE LIVER T. BODY ' THYROID KIDNEY l LUNG GI-LLI TC-99M 2.47E-10 6.98E-10 8.89E 09 NO DATA 1.06E-08 3.42E-10 4.13E-07 TC-101 2.54E-10 3.66E-10 3.59E-09 NO DATA 6.59E-09 1.87E-10 1.10E-21 RU-103? 1.85 E-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 531E 06 NO DATA 1.78E-04 AG 110Mt 1.60E-07 1.48E-07 8.79E-08 NO DATA 2.91 E-07 NO DATA 6.04E-05 tSB-124 2.80E-06 5.29E-08 1.11E 06 6.79E-09 NO DATA 2.18E-06 7.95E-05 tSB-125 1.79E-06 2.00E 08 4.26E-07 1.82E-09 NO DATA 138E-06 1.97E-05 15B-126 1.15E-06 234E-08 4.15E-07 7.04E-09 NO DATA 7.05E-07 9.40E-05 158-127 2.58E-07 5.65E-09 9.90E 08 3.10E-09 NO DATA 1.53E-07 5.90E-05 TE-125M 2.68E-06 9.71E-07 3.59E-07 8.06E-07 1.09E-05 NO DATA 1.07E-05 TE-127Mt 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 238E-08 8.15E-08 4.48E-07 NO DATA 8.68E-06 TE-129Mt 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 NO DATA 5.79E-05 TE-129 3.14E-08 1.18E-08 7.65E-09 2.41 E-08 132E-07 NO DATA 237E-08 TE-131M; 1.73 E-06 8.46E-07 7.05E-07 134E-06 8.57E-06 NO DATA 8.40E-05 l 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-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 NO DATA 7.71 E-05 l-130 7.56E-06 2.23E-06 8.80E-07 1.89E-04 3.48E-06 NO DATA 1.92E-06 l-131* 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 NO DATA 1.57E 06 l-132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E.07 NO DATA 1.02E-07 l-133; 1.42E-06 2.47E-06 7.53E-07 3.63E-04 431E-06 NO DATA 2.22E-06 l-134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 NO DATA 2.51E-10 1-1352 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 NO DATA 131E-06 I C5-134 6.22E-05 1.48E-04 1.21E-04 NO DATA 4.79E-05 1.59E-05 2.59E-06 C5-136 6.51 E.06 2.57E-05 1.85E-05 NO DATA 1.43 E-05 1.96E-06 2.92E-06 C5-137% 7.97E-05 1.09F-04 7.14E-05 NO DATA 3.70E-05 1.23E-05 2.11E-06 CS-138 5.52E-08 1.09E-07 5.40E-08 NO DATA 8.01 E-08 7.91E-09 4.65E-13 BA-139 9.70E-08 6.91E-11 2.84E-09 NO DATA 6.46E-11 3.92E-11 1.72E-07 BA-140t 2.03E-05 2.55E 08 133E-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 331E-11 2.02E-11 2.22E-17 BA 142$ 2.13E-08 2.19E-11 134E-09 NO DATA 1.85E-11 1.24E-11 3.00E-26 LA-140 2.50E-09 1.26E-09 333E-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 936E-09 633E-09 7.18E-10 NO DATA 2.94E-09 NO DATA 2.42E-05 CE-143t 1.65E-09 1.22E-06 135E-10 NO DATA 537E-10 NO DATA 4.56E-05 l CE-144% 4.88E-07 2.04E-07 2.62E-08 NO DATA 1.21E-07 NO DATA 1.65E-04 l PR-143 9.20E-09 3.69E-09 4.56E-10 NO DATA 2.13E-09 NO DATA 4.03E-05 l PR-144 3.01E-11 1.25E-11 1.53E-12 NO DATA 7.05E-12 NO DATA 433E % ND-147$ 6.29E-09 7.27E-09 435E-10 NO DATA 4.25E-09 NO DATA 3.49E-05 W-187 1.03 E-07 8.61E-08 3.01E-08 NO DATA NO DATA NO DATA 2.82E-05 NP-239 1.19E-09 1.17E-10 6.45E-11 NO DATA 3.65E 10 NO DATA 2.40E-05 l ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) l 2.0-39

TABLE 2.2-3 O SITE RELATED INGESTION i V DOSE COMMITMENTFACTOR, A

• h (mrem /hr per Ci/ml) u Page 1 of 2 NUCUDE BONE UVER T. BODY THYROID KIDNEY LUNG GI-LLI H-3 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 630E + 03 630E + 03 630E + 03 630E + 03 630E + 03 630E + 03 F-18 6.69E + 01 NO DATA 7.42E + 00 NO DATA NO DATA NO DATA 1.9BE + 00 i

NA 24 5.48E + 02 5.48E + 02 5.48E + 02 5.48E + 02 5.48E + 02 5.48E + 02 5.48E + 02 P-32 4.62 E + 07 2.87E + 06 1.79 E + 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 + 02 MN-54 NO DATA 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 + 02 NO DATA 3.82E + 03 i FE-55 8.87E + 02 6.13E + 02 1.43E + 02 NO DATA NO DATA 3.42E + 02 3.52E + 02 FE-59 1.40E + 03 3.29E + 03 1.26E + 03 NO DATA NO DATA 9.19E + 02 1.10E+ 04 CO-57 NO DATA 3.55E + 01 5.91 E + 01 NO DATA NO DATA NO DATA 9.01E + 02 CO-58 NO DATA 1.51 E + 02 339E + 02 NO DATA NO DATA NO DATA 3.06E + 03 CO-60 NO 0ATA 434E + 02 9.58E + 02 50 DATA NO DATA NO DATA 8.16E + 03 ~ NI-63 4.19E + 04 - 2.91 E + 03 1.41 E + 03 NO DATA NO DATA NO DATA 6.07E + 02 Ni-65__ 1.70E + 02 2.21E + 01 1.01E+ 01, NO DATA NO DATA NO DATA 5.61E + 02 CU-64 NO DATA 1.69E + 01. 7.93 E + 00 NO DATA 4.26E + 01 NO DATA 1.44E + 03 ZN-65 2.36E + 04 7.50E + 04 339E + 04 NO DATA 5.02E + 04 NO DATA 4.73E + 04 2N 69 5.02E + 01 9.60E+ 01 6.67E + 00 NO DATA 6.24E + 01 NO DATA 1.44E + 01 ZN-69m? 8.28E + 02 1.99E + 03 1.82E + 02 NO DATA 1.20E + 03 NO DATA 1.21E+ 05 BR-82 NO DATA NO DATA 2.46E + 03 NO DATA NO DATA NO DATA 2.82E+ 03 io) BR-831 NO DATA NO DATA '4'~ME + 01 NO DATA NO DATA NO DATA 630E+01 BR-84 NO DATA NO DATA 5.67E + 01 NO DATA NO DATA NO DATA 4.45E - 04 BR-85 NO DATA NO DATA 233E + 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'.03 E + 04 RB-88 NO DATA 2.95E + 02 156E + 02 NO DATA NO DATA NO DATA 4.07E - 09 RB-89% NO DATA 1.95E + 02 137E + 02 NO DATA NO DATA NO DATA 1.13E - 11 SR-89$ 4.78E + 04 NO DATA 137E + 03 NO DATA NO DATA NO DATA 7.66E + 03 SR-90t 1.18E + 06 NO DATA 2.88E + 05 NO DATA NO DATA NO DATA 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 + 02 NO DATA 1.44E + 01 NO DATA NO DATA NO DATA 6.60E + 0T Y-90 1.38E + 00 NO DATA 3.69E - 02 NO DATA NO DATA NO DATA 1.46E + 04 Y-91 Mt 1.30E - 02 NO DATA 5.04E - 04 NO DATA NO DATA NO DATA 3.82E - 02 Y-91 2.02E-IO1 NO DATA 539E-01 NO DATA NO DATA NO DATA 1.11E t-04 ~ Y-92 1.21E - 01 NO DATA 3.53E - 03 NO DATA NO DATA NO DATA 2.12E+ 03 Y-93 3.83E - 01 NO DATA 1.06E - 02 NO DATA NO DATA NO DATA 1.22E + 04 ZR-95t 2.77 E + 00 8.8SE - 01 6.01 E - 01 NO DATA 139E + 00 NO DA7 A 2.82E + 03 2R-97* 1.53E - 01 3.09E - 02 1.41 E - 02 NO DATA 4.67E - 02 NO DATA 9.E7E + 03 NS-95 4.47E + 02 2.49E + 02 134E+ 02 NO DATA 2.46E + 02 NO DATA 1.51E + 06 NB-97 3.75E+ 00 9.49E-01 3.47E-01 NO DATA 1.11E + 00 NO DATA 3.50E + 03 $ Daughter contributions are included (see Reference 13).

• Calculated using equation (32) and Tables 2.2-1 and 2.2-2.

ODCM, V.C. Jmmer, SCE&G: Revision 21 (March 1996) 2.0-40

~ TABLE 2.2-3 SITE RELATED INGESTION DOSE COMMITMENT FACTOR, Ais* (mrem /hrper Ci/ml) u Page 2 of 2 NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI MO-997 NO DATA 4.62E + 02 8.79 E + 01 NO DATA 1.05E + 03 NO DATA 1.07E + 03 TC-99 M 2.94E - 02 8.32E - 02 1.06E + 00 NO DATA 1.26E + 00 4.07E - 02 4.92E + 01 TC-101 3.03 E - 02 4.36E - 02 4_28E - 01 NO DATA 7.85E 01 2.23E-02 1.31 E - 13 RU-103; 1.98E + 01 NO DATA' 8.54E - 01 NO DATA 7.57E + 01 NO DATA 2.31 E + 03 RU-105$ 1.65E + 00 NO DATA 6.52E - 01 NO DATA 2.13E + 01 NO DATA 1.01 E + 03 RU.106t 2.95E + 02 NO DATA 3.73E + 01 NO DATA 5.69E + 02 NO DATA 1.91E + 04 AG-110Mi 1.42E + 01 1.31E + 01 7.80E + 00 NO DATA 2.58E + 01 NO DATA 5.36E + 03 SB-124 2.40E + 02 4.53 E + 00 9.50E + 01 5.81 E-01 NO DATA 1.87E + 02 6.81 E + 03 58-125? 1.53E + 02 1.71 E-1-00 3.65E + 01 1.56E-01 NO DATA 1.18E + 02 1.69E + 03 58-126 9.85E + 01 2.00E + 00 3.55E + 01 6.03 E-01 NO DATA 6.04E + 01 8.05E + 03 5B-127 2.21 E + 01. 4.84E-01 8.47E + 00 2.65E-01 NO DATA 1.31 E + 01 5.05E + 03 TE-125M 2.79E + 0's 1.01 E + 03 3.74E + 02 8.39E + 02 1.13E + 04 NO DATA 1.11E + 04 i TE-127Mt 7.05E + 03 2.52E+03 : 8.59E+02 1.80E + 03 2.86E + 04 NO DATA 2.36E + 04 TE-127 1.14E + 02 4.11 E + 01 2.48E + 01 8.48E + 01 4.66E + 02 NO DATA 9.03E + 03 ~ TE-129Mt 1.20E + 04 4.47 E + 03 1.89E + 03 4.11 E + 03 5.00E + 04 NO DATA 6.0Th + d4 TE-129 3.27E-F 01 1.23E + 01 7.96E + 00 2.51 E + 01 1.37E + 02 NO DATA 2.47E + 01 TE-131Mt 1.88E + 03 8.81 E + 02 ' 7.34E + 02 1.39E + 01 8.92E + 03 NO DATA. 8.74E + 04 TE-131* 2.0SE + 0i - 8.57E + 00 6.47 E + 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 l l-130 9.01E + 01 2.66E + 02 1.05E + 02 2.25E + 04 4.15E + 02 NO DATA 2.29E + 02 l T131; 4.96E + 02 7.09E+3T 4.06E + 02 2.32E + 05 1.22E + 03 NO DATA 1.87 E + 02~ l-132 2.42 E + 01 6.47E + 01 2.26E + 01 2.26E + 03 1.03E + 02 NO DATA 1.22E + 01 1.133? 1.69E + 02 2.94E + 02 8.97E + 01 4.32E + 04 5.13E + 02 NO DATA 2.64E + 02 1-134 1.261!+ 01 3.43E + 01 1.23E + 01 5.94E + 02 5.46E"+ 01 NO DATA 2.99E - 02 1-135% 5.28E + 01 1.38E+ 02 5.10E + 01 9.11E+03 222E+ 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 C5-136 3.17h + 04 1.25E + 05 9.01E + 04 NO DATA 6 57E + 04 9.55E + 03 1.42E + 04 ~ l C5-137% 3.88E +05 5.31E + 05 3.48E + 05 NO DATA 1.88E + 05 5.99E + 04 1.03E + 04 I C5-138 2.69E + 02 5.31E + 02 2.63E + C'2 NO DATA 3.90E + 02 3.85E + 01 2.27E - 03 ~ BA-139 9.06E + 00 6.41E - 03 2.64E - O t NO DAT A 5.99E-03 3.64E - 03 1.60E + 01 BA-140t 1.88E + 03 2.37E + 00 1.23E + 02 NO DATA 8.05E - 01 1.35E + 00 3.88E + 03 BA-141? 4.27E + 00 3.30E - 03 1.48E - G1 NO DATA 3.07E - 03 1.87E - 03 2.06E - 09 l BA-142% 13BE + 00 2.03E - 03 1.24E - 01 NO DATA 1.77f- 03 1.15E - 03 2.78E - 18 i LA-140 3.5SE - 01 1.80E - 01 4.76E - 02 NO DATA ' NO DATA NO DATA 1.32E + 04 LA-142 1.83 E - 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 CE-144? 4.18E + 01 1.77E + 01 2.24E + 00 NO DATA 1.04E + 01 NO DATA 1.41E + 04 I PR-14"$ 1,32E + 00 5.28E - 01 6.52E - 02 NO DATI 3.05E - 01 NO DATA 5.77E + 03 l PR-144 4.31E - 03 1.79E - 03 2.19E - 04 NO DATA 1.01E - 03 NO DATA 6.19E - 10 E ( ND-147: 9.00E - 01 1.04E + 00 6.22E - 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 l 3.91E - 02 NO DATA 2.57E + 03 ODCM,V.C. Summer,SCE&G: Revision 21(March 1996) 2.0-41

-- ~_ i t 7+ (m) LIQUID RADWASTE TREATMENTSYSTEM v FIGURE 2.2-1 1 t E Y,' .E*' ,~ 3 6 4 J \\ D 1 m 3 I n 8 l i-3 E !! llg g

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,}, a........... g J6 g g Ek vi e s E I 1-r an se e I a. g g- - 35 IHWW ii .I 'sI a ~ ~ h^ ODCM, V.C. Summer, SCE&G: Revision 21 (March 1996) j 24 42 4

Ol ~ l FIGURE 2.2-1 j NOTES: 1 Turbine Building Sump contents may be processed to the main condenser cleaning sump through a portable demineralizer. This is an optional tre.itment pathway which provides processing flexibility in the event processing through excess liquid waste is not desirable. Since a temporary demineralizer is used for this optional treatment pathway, operability tests specified in ODCM specification 1.1.4.1 are not required. To ensure adequacy of the RM-L8 setpoint while using the alternate process pathway, samples must be obtained frorn the discharge side of the dernineralizers or condenser cleaning sump and analyzed everytwelve Sours. l i l i O' ODCM,V.C. SUMMEli SCEandG: Revision 21 (March 1996) 2.0-43

l 3.0 GASEOUS EFFLUENT 3.1 Gaseous Effluent Monitor Setpoints l The calculated setpoint values will be regarded as upper i 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 detired. Calculated monitor setpoints may be added to the ambient j background count rate. l 3.1.1 Gaseous Efflue nt Monitor Setooint Calculation Parameters j Term Dehnition Section of 1. initial Use i C-= count rate of a statior, vent monitor (3.1.2) corresponding to grab sample radio-4 nuclide concentrations, X;v, as detesmined j from the monitor's calibration curve, in cpm. C*= the count rate of the monitor on vent v (3.1.4) corresponding to X,' uCi/cc of Xe-133,in cpm. c = count rateof thegasdecaysystem (3.1.3) monitor for measured radionuclide concentrations corrected to discharge pretsure,in cpm. i c' the count rate of the waste gas decay (3.1.4) = system monitor corresporading to the i total noble gas concentration in cpm. d. Dg lirniting dose rate to the skin (3000 (3.1.2) i = mrem / year). D,, = limiting dose rate to the total body (3.1.2) (500 mrem / year). the flow rate in vent v (cc/sec) (3.1.2) I: = (1 cc/sec = 0.002119 cfm). f, the maximum permissible waste gas (3.1.3) = discharge rate, based on the actual radionuclide rnix and skin dose rate (cosec). 1 [ ODCM, V. C. Summer SCE&G. Revision 13 (June 1990) 3.0-1 ] 1 4 4

a. Section of Term Definition initial Use the maximum permissible waste gas (3.1.3) f, = discharge rate, based on the actual radionuclide mix anc total body dose rate (cc/sec). the maximum permissible waste gas (3.1.3) f = ^ discharge rate, the lesser of f, and f,(cc/sec). the conservative maximum per-(3.1.4) f,' = missible waste gas discharge rate based on Kr-89 skin dose rate (cc/sec). the conservative maximum permissible (3.1.4) 1,' = waste gas discharge rate based en Kr-89 total body dose rate (cc/sec). total body dose factor due to gamma (3.1.2) K, = emissions from isotope i (mrem / year 3 per uCi/m ) from Table 3.1-1. K,,,, a total body dose factor for Kr-89, the most (3.1.3) restrictive isotope f rom Table 3.1-1 3 (mrem /yr per uCi/m ). Skin dose factor due to beta emissions (3.1.2) L = 3 from isotope i(mrem /yr per uCi/m ) from Table 3.1-1. L,,,,, = Skin dose factor for Kr-89, the most restrictive (3.1.3) 3 isotope, from Table 3.1-1 (mrem /yr per uCi/m ). air dose factor due to gamma emissions (3.1.2) M, = 3 from isotope i (mrad /yr per uCi/m ) from Table 3.1 1. M,,.,, = s &w her 6 bH, & mu mMdn 0.1.M 3 isotope, from Table 3.1-1 (mradlyr per uCi/m ). count rate per mrem /yr to the skin. (3.1.2) R, = count rate per mrem /yr to the total (3.1.2) R, = body. R,' conservative count rate per mrem to (3.1.4) = the skin (Xe-133 detection, Kr-89 dose). R,' conservative count rate per mrem to (3.14) = the total body (Xe-133 detection, Kr-89 dose). ODCM,V C. 5 Jmmer, SCE&G. Revision 13 (June 1990) 3.0 2 J

~= O l t Section of Term Definition - Initial Use f i 5d count rate of the waste gas decay (3.1.3) I = system noble gas monitorat the alarm setpoint,in cpm. ,x S, count rate of a station vent noble gas (3.1.2) h = monitor at the alarm setpoint, in cpm. i i 5,, count rate of the containment purge (3.1.2) noble gas monitor at the alarm setpoint, in cpm. l 5* = count rate of the plant vent noble gas (3.1.2) monitor at the alarm setpoint, in cpm. i X = the concentration of noble gas radio-(3.1.3) g nuclideiin a waste gas decaytank,as corrected to the pressure of the dis-charge stream at the point of its flow l i measurementin uCi/cc. I 1 t X*. the measured concentration of noble (3.1.2) = i gas radionuclide iin thelast grab j sample analyzed for vent vin uCi/cc. i X,' = thetotalnoble gas decay tank, gas concentration in a waste (3.1.4) as corrected to the r,ressure of the discharge stream at the point of its flowmeasurementin uCi/cc. X'= a concentration of Xe-133 chosen to be in the (3.1.4) y l operating range of the monitor on vent v Ir. Ci/cc. XTQ= the highest annual average relative concentra-(3.1.2) i tion in any sector, at the site boundary in sec/m3, i i 1.1 = mrem skin dose per mrad air dose (3.1.2) 0.25 = the safety factor applied to each of the two (3.1.2) i vent noble gas monitors (plant vent and contain-8 ment purge) to assure that the sum of the releases has a combined safety factor of 0.5 which allows a 100 percent margin forcumulaTve uncertainties of measurements. ODCM, V. C. Summer, SCE&G: Revision 17 (Aoril 1993) 3.0-3 i

I O TABLE 3.1-1 DOSE FACTORS FOR EXPOSURE TO A SEMI-INFINITE CLOUO OF NOBLE GASE5,* Nuclide y-Bodv * * * (Ki} 6-Skin * * *(Lil y-Air * * (M,} B-Air * * (Ni} Kr-85m 1.17 E + 03 * * *

• 1.46E + 03 1.23E + 03 1.97E + 03 Kr-85 1.61E + 01 1.34E + 03 1.72E + 01 1.95E + 03 Kr-87 5.92E + 03 9.73E + 03 6.17E + 03 1.03E + 04 Kr-88 1.47E + 04 2.37E + 03 1.52E + 04 2.93E + 03 Kr-89 1.66E + 04 1.01E + 04 1.73E + 04 1.06E + 04 Kr-90 1.56E + 04 7.29E + 03 1.63E + 04 7.83E + 03 Xe-131m 9.15E + 01 4.76E + O2 1.56E + O2 1.11 E + 03 Xe-133m 2.51E + O2 9 94E + O2 3.27E + 02 1.48E + 03 Xe-133 2.94E + O2 3.06E + 02 3.53E + 02 1.05E + 03 Xe-135m 3.12E + 03 7.11 E + O2 3.36E + 03 7.39E + 02 Xe-135 1.81E + 03 1.86E + 03 1.92E + 03 2.46E + 03 Xe-137 1.42E + 03 1.22E + 04 1.51E + 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
• mrad-m3 pCi-yr
• " mrem-m3 pCi yr
• * *
• 1.17E + 03 = 1.17 x 103 ODCM, V. C. Summer, SCE&G: Revision 13 (June 1990) 3.0-4 b

t

. -. ~ e~ /~T col + 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: 5, count rate of the plant vent noble gas monitor (= 5,, for = RM.A3) or the containment purge noble gas monitor ( = 5,, for RM-A4) at the alarm setpoint level. 0.25 x R, x D, (34) 1 & thelesserof or 0.25 x R, x D (35) 33 0.25 = the safety factor applied to each of the two vent noble l gas monitors (plant vent and containment purge) to assure that the sum of the releases has a combined safety factor of M which allows a 100 percent margin for cumulative uncertainties of measurements. J l D, Dose rate limit to the total body of an individual = 1 500 mrem /yr = i R, count rate per mrem /yr to the total body = C, /((X/Q) x F, x E K,X,,) (36) = I Dose rate limit to the skin of the body of an individual Dss = in an unrestricted area. 3000 mrem / year. = count rate per mrem /yr to the skin. Rs = C, + (WQ x F, x T (L, + 1.1 M ) X,,] (37) = i the measured concentration of noble gas radionuclide i X,, = in the last grab sample analyzed for vent v, pCi/mt. (For the plant vent, grab samples are taken at least (R) ODCM, V. C. Summer, SCE &G: Revision 13 (June 1990) v 3.0-5

O: monthly. For the 6" and 36" containment purge lines, the sample is taken just prior to the release and also monthly,if the releaseis continuous.) the floN rate in vent v, cc/sec. (1 cc/sec = 0.002119 cfm) F, = count rate, (cpm) of the monitor on station vent v C, = corresponding to grab sardhle noble gas concen-

trations, X,, as determined from the monitor's calibration curve. i.e. product of the monitor response curve slope (CP*/uCi/mi) and the sum of the noble gas concentrations in the grab sample (uCi/ml). (initial calibration curves of the type shown in Figure 2.1-1 have been determined conservatively from families of response curves supplied by the monitor manufac-turers. As releases occur, a historical correlation will be prepared and placed in service when sufficient data are accumulated.)

the highest annual average relative concentration in X/Q = any sector, at the site boundary (seven year average). 6.3E-6 sec/m3 in the ENE sector. = total body dose factor due to gamma emissions from K = 3 3 isotope 1 (mrem /yr per pCi/m ) frem Table 3.1-1. skin dose factor due to beta emissions from isotope I L, = 3 (mremlyr per pCi/m ) from Table 3.1-1. mrem skin dose per mrad air dose. 1.1 = air dose fattor due to gamma emissions from isotope 1 M, = (mradlyr per pCi/m3) from Table 3.1-1. ODCM, V. C. Summer, SCE &G: Revision 17 (April 1993) 3.0-6

... ~' e' 4 NOTE: At plant startups when no grab sample analysis is available for the continuous releases, the Alternate Methodology of Section 3.1.4 must I be used. 3.1.3 Waste Gas Decay System Monitor (RM-A10) ] The permissible conditions for discharge through the waste gas dr: cay system monitor (RM-A10) will be calculated in a manner similar to that for the I plant vent noble gas monitor. In the case of the waste gas system, however, the j discharge flow rate is continuously controllable 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-l 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 j 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: S,< 1.5c (38) o_ I where: l c = count rate in CPM of the waste gas decay system monitor corresponding to the measured concentration (taken from I 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) OW4, V. C. Summer, SCE &G: Revision 13 (June 1990) 3.0 7

O the maximu.n permissible discharge rate based on total body dose f, = rate. 0.25 x D, / [XTQ x 1.5,E X K) (40) = 7 g I the maximum permissible discharge rate based on skin dose rate. f, = 0.25 x D / [R7Q x 1.5 I X,g (L, + 1.1 M,)] (41) = 33 i Xid = the concentration of nobic gas radionuclide i 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 rate measurement. The rhaximum discharge pressure as govemed by the diaphragm valve,7396, is 30 psia. NOTE: The factor of 1.5 in the denominators of equations (40) and (41) places f, on the same basis as 5,. 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 of the plant vent noble gas monitor RM-A3 approaches its setpoint, whichever of the above conditions is reached first. l 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 j release. 3.1.4 Alternative Methodoloav for Establishina Conservative Setpoints As an alternate to the methodology of section 3.1.2, to minimize necessity for frequent adjustment of setpoint, a conservative setpoint may be calculated as follows: For a plant vent: R,' conservative count rate per mrem /yr to the total body (Xe-133 = detection, Kr-89 dose). O ODCM, V. C. Summer, SCE&G: Revision 18 (September 1994) 3.0-8 l

e-O C,' + (X7Q x K,,.,, x X,' x F,], (42) = where: X,' a concentration of Xe-133 chosen to be in the operating = range of the monitor on vent v, pCi/cc. C,' the count rate in CPM of the monitor on vent v s corresponding to X,'pCi/cc of Xe-133. K,,,,, total body dose factor for Kr 89, the most restrictive = isotope from Table 3.1-1. R,' count rate per mrem /yr to the skin. = C,' + [E6 x (L,,.,, + 1.1M,,.3,) x X,'x F,] (43) = where: L,,,, = skin dose factor for Kr-89, the most restrictive isotope x from Table 3.1-1. M,,, = air dose factor for Kr-89, the most restrictive isotope, from Table 3.1-1. For the waste gas decay system: f,' the conservative maximum permissible discharge rate based on Kr 89 = total body dose rate. = 0.25 x D rs + [WQ x 1.5 x X,'x K,,.,,) W) f,' the conservative maximum permissible discharge rate based on Kr-89 = skin dose rate. 0.25 x D,, + DUD x 1.5 x X,'x (L ,.3, + 1.1M,,.,,)] (45) = g ODCM, V. C. Summer, SCE&G: Revision 13 (June 1990) 3.0 9

c-O X,' = the total concentration of noble gas radionuclides in the waste gas decay tank whose contents are to be dis-charged, as corrected to the pressure of the discharge stream at the point of the flow measurement. count rate in cpm of the waste gas decay system monitor c' = corresponding to X ' pCi/cc of Kr-85. d 3.1.5 Oilincineration 3.1.5.1 Releases from the oil incinerator will be limited such that Eq. (60) Yl6(oir) E Pi Q(oii) < 1.5 mrem /yr. where: highest annual average dispersion coefficient X/Q(oii) = (sec/m3) at the site boundary 3.3E-5 sec/m3 = dose parameter for radionudide ; for inhalation, Pi = from Table 3.21 (mrem / yr per uCi/m3), Ci(ol0XR Q(oil) = where: concentration of radionuclide iln oil (uCi/ml), and Ci(ois) = burn rate'(ml/s). R = 3.1.5.2 incinerator operation will be administratively controlled such that the combination of gaseous releases from the station and oil incineration will be less than Specifications 1.2.2.1(b) and 1.2.5.1. If noble gases are detected in waste oil, an assessment of release acceptability should be performed using the general methodology described in sections 3.2.2.1 and 3.2.3.1. 3.1.6 Meteorotocical Release Criteria for Batch Releases Planned gaseous batch releases (WGDT) and oilincineration will be performed during favorable meteorology. Limiting releases to favorable meteorology provides assurance that release conditions will be conservative with respect to annual average dispersion values (X/Q, X/Q'). Favorable meteorology is defined in Table 3.1-2. ODCM, V. C. Summer, SCE&G: Revision 19 (January 1995) 3.0-10

1 e' 1 i O b. } Table 3.1-2 i Favorable Meteorology I i i Differential Te,mperature (AT)1 Stability Wind speed 2(mph) l Class 61m - 10m 40m - 10m 10m 61m 1 l AT 5 -1.74 AT 5 -1.03 A -1.74 < AT 5 -1.56 -1.03 < AT 5 -0.92 8 -1.55 < AT 5 -1.38 -0.92 < AT 5 -0.81 C 1.3 1.6 j -1.38 < AT 5 -0.46 -0.81 < AT 5 -0.27 D 3.1 4.1 -0.46 < AT 5 1.38 ^ 0.27 < AT 5 0.81 E 3.5 6.6 l l 1.38 < AT 5 3.67 0.81 < AT $ 2.16 F 5.2 14.0 i 3.67 < AT 2.16 < AT G 7.0 18.9 i i l Notes: 1 1 The AT values for 61m - 10m are considered as primary indicators for j j determination of stability class. The 40m - 10m AT values are used only when l 61m - 10m values are not available. All AT values are listed in *F and are based on values in USNRC Regulatory Guide 1.23. l 2 The 10m wind speed is considered the primary indication for windspeed. The I j 61m wind speed indication should only be used if 10m is not available. No wind is required for planned releases. I iO oDC.v.c.summe,.sce e: Re ision 1sts ,4 ') l 3.0-10A 4 4

1 y-1 O Figure 3.1-1 Example Noble Gas Monitor Calibration Curve 1 .:z= .. =l I .* = =21 : =.. ;;=_=:-.:: :- $ =. e : .l _g g ~:._,,. ._;_.I----- -m = ;-- - 7_--.-_..','3--_g L-e 1 -.r _[ _. '.~ ; ~ j FJ_.,-'_ , =a' il: : 12. - _ ___. ;. :..-.. _..,. _ ~ ~. s c 8 ., - L N $2Y-$2 'l - --$N. - - _l l ._.___l__,_..f__;- ; L _. [._ _ _ _:;y & l -1 10 g. - - s ^ -- 3 _ ?.. 3 ?_ 3-(

• :; :-- u ~. I._ ^:

. _ _ ~ O ~ - ? ) - Anw_ A.m _2 o. ; - n.. -. -..1 ---. _ A i l ...-_'_1== .. ~ _.. _.. %__..-,-..._ 7, n E. ;.--. c __4. = _ _. . _ 1-3 -s # i 9 e 10 * * ' - . = - . - _. = _. _ = _-. 1 n s t , Mi __ 1 l_. i. $ _ _. _. _... _.

=

2==-- '.=..._'._: i e s. [- ~ 1 ) r ... = 1 :. f .. - -__:-_= g (= .0 4 m. ~ ~ -. - ' E ^' '~.~.-'-.-.--^g'"*. l 7 J J ,..n..rz_._'-. sf O L. .A. n EE=' =- 11^ ^ - -

A.

~ ' - === -----~ = = =- - :. -d= b i== - = = = & = := = = _ W ^ 10.;

... W -

~'.. .4._ .i (uCi/ml) ~~;r '~ ^ ^ ~ - ~ ~ ~ - , =.. ~ 10*I ^~ ~ ~ ~ - ~ ~ ~~ i 2. -r t .+ = t 'O..'... -. : 4, -- _. _ _j f 7 - - ; _ : - : =: -..-.z.:. -.- m ; __ _ : = = = --- _;_5v - : = = _= - _ _ ____-:::-=--. 0*o s 2 10 go 10 10' 3 10 ga? Count Rate (cpm) O ODCM, V. C. Summer, SCE &G: Revision 13 Oune 1990) 3.0-11

. :~ 4 !o 4 3.2 Dose Calculation for Gaseous Effluent j 3.2.1 Gaseous Effluent Dose Calculation Parameters 4 Section of Term Definition initial Use D, year (ge organ dose rate in the current (3.2.2.2) avera = mrem /yr). 1 D' dose to an individual from ra:fioiodine (3.2.3.2) = and radionuclides in particulate 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). Dt = current total body dose rate (mrem /yr) (3.2.21) Dp air dote due to beta emissions from (3.2.3.1) = noble gas radionuclides (mrad). D = y air dose due to gamrna emissions from (3.2.3.1) noble gas radionuclides (mrad). Ki total body dose factor due to gamma emissions (3.2.2.1) = from isotope i (mrem / year per uCi/m ) from 3 Table 3.1-1. skin dose factor due to beta emissions from (3.2.2.1) Li = noble gas radionuclide i(mrad /yr per pCi/m ) 3 from Table 3.1-1. 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) = from noble gas radionudide i(mrad per uCi/m3) from Table 3.1-1. dose parameter for radionuclide i, (3.2.2.2) P, = (mrem /yr per uCi/m ) forinhalation, 3 from Table 3.2-1. D, = the release rate of noble gas radionuclide (3.2.2.1) i as determined from the concentrations measured in the analysisof the appropriate sample required by Table 1.2 3 (pCi/sec). ODCM, V. C. Summer, SCE&G: Revision 15 (February 1991) 3.0-12

i O Section of Term Definition initial Use the release rate of non-noble gas radionuclide i (3.2.2.2) Q,' = 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). ~ Q,' cumulative release of non-no' le gas radionuclide i (3.2.3.2) = (required by ODCM Specificat.on 1.2.4.1) over the period of interest (pCi). dose factor for radionuclide i and pathway j, (3.2.3.2) R,' = 3 2 (mrem /yr per uCi/m ) or(m -mrem /yr per pCi/sec) from Tables 3.2-2 through 3.2-6. W. ' = relative dispersion parameter for the maximum (3.2.3.2) exposed individual, as appropriate for his exposure pathway j and radionuclide i. RIQ' for inhalation and all tritium pathways = O b7Q' for other pathways and non-tritium radionuclides = SUQ = the highest annual average relative concentration (3.2.2.1) in any sector, at the site boundary in sec/m3 3.17 x 10.a = the fraction of one year per one second (3.2.3.1) X/Q'2 Annual average relative concentration for the (3.2.3.2) location of the maximum exposed individual for the site (sec/m3). D/Q'= Annual average relative deposition for the location (3.2.3.2) or the maximum exposed individual for the site (m-2). D-ODCM, V. C. Summer, SCE&G: Revision 14 (December 1990) 3.0-13

1 i 3.2.2 Unrestricted Area Boundarv Dose 3.2.2.1 For the purpose of implementation of section 1.2.2.la, (6 500 mrem / year - total body, 6 3000 mrem / year - skin) the dose at the unrestricted area boundary due to noble gases shall be calculated as follows: D, current total body dose rate (mrem /yr) = X/Q ? K,k (46) = 1 D, current skin dose rate (mrem /yr) = X/Q (L, + 1.1 M,) d, (47) = where: d, the release rate of noble gas radionuclide i as = determined from the concentration measured in the analysis of the appropriate sample required by Table 1.2-3 (pCi/sec.). X/Q the highest annual average relative concen- = tration in any sector, at the site boundary (for value, see Section 3.1.2). K;, Li, and Mi will be selected for the appropriate radionuclide from Table 3.1-1. 3.2.2.2 For the purpose of implementation of section 1.2.2.1.b (E 1500 mrem /yr - any organ) organ doses due to radioiodines and all radioactive materials in particulate form and radionuclides (other than noble gases) with half lives greater than eight days, will be calculated as follows: D, current organ dose rate (mrem /yr) = p3DQ P, (48) = I where: ODCM,V.C. Summer, SCE&G: Revision 13 (June 1990) 3.0 14

r-O the highest annual average relative concentra-X/Q = tion in any sector, at the site boundary (for value, see Section 3.1.2) dose parameter for radionuclide i, (mrem /yr per P, = pCi/m ) for inhalation, from Table 3.2-1. l i r-the release rate of non-noble gas radionuclide i as Q,' = determined from the concentrations measured in the analysisof 4he appropriate sample required by Table 1.2-3 (pCi/sec). 3.2.3 Unrestricted Area Dose (Air Dose and Dose to Individual) 3.2.3.1 For the purpose of implementation of section 1.2.3.1 (Calendar quarter: :i 5 mrad - y and 510 mrad - p, Calendar year: 510 mrad - y and 5 20 mrad - ) and section 1.2.5.1 (air dose averaged over 31 days: 5 0.2 mrad - y and 5 0.4 rnrad - p),the air dose in unrestricted areas shall be determined as follows: air dose due to gamma emissions from noble gas Dy = radionuclide i (mrad) 3.17 x 10-s E M,3DQ Q, (49) = I where: 3.17 x 10 8 = the fraction of one year per one second D, cumulative release of noble gas radionuclide i = over the period of interest (pCi). O' l ODCM, V. C. Summer, SCE&G: Revision 16 (September 1991) 3.0-15

~ _ _ _ _ __ _._. _ _. _. _ _ _ _ _ _ _... i O i i l Dp air dose due to beta emissions from noble gas radio- = nudide I(mrad). ) 3.17 x 10-SIN;RTQ 6; (50) = .p 4

where, Ni

= air dose factor due to beta emission from noble l gas radionudide i (mradlyr per uCi/m3) from ) Table 3.1-1. I 3.2.3.2 For all gaseous effluents including oil incineration, dose I to an individual from radioiodines and radioactive materials in i ] particulate form and radionudides (other than noble gases), with half-lives greater than eight (8) days (Calendar quarter: s7.5 mrem any organ, Calendar year: s 15 mrem any organ) will be calculated j for the purpose of implementation of section 1.2.4.1 as follows: i D = dose to an individual from radioiodines and radio-nudides in particulate form, with half-lives greater j j than eightdays (mrem) i 3.17 x 10-8 I R,; W,;' Q ' (51) = 3 'l I where: ) W,j' relative concentration or relative deposition for j = the maximum exposed individual, as appropriate for exposure pathway j and radionudide i. j RTQ' for inhalation and all tritium pathways 3.5 x 104 sec/m3 = i DTQ' for other pathways and non-tritium radionudides 4 1.1 x 10-8 m.2 l = (See the notes to Table 3.2-7 and 3.2-8 for the origin of these factors.) [ ODCM, V. C. Summer, SCE&G: Revision 17 (Aprl! 1993) y 3.0-16 t i

e-O R,, dose factor for radionuclide i and pathway j, = 3 2 (mrem /yr per pCi/m ) or (m - mrem /yr per pCi/sec) from Table 3.2-2. Q,' Cumulative release of non-noble gas radionuclide = i (required by ODCM Specification 1.2.4.1) over the period of interest (pCi). 3.2.4 For the purpose of initial assessments of the impact of unplanned l gaseous releases, dose calculations for the critical receptor in each affected sector may be performed using section 3.2.3.1 and section 3.2.3.2 equations as follows: (1) For each affected sector, X/Q and D/Q will be calculated for one mile and critical receptor locations using actual meteorological conditions occurring during the unplanned release. Actual X/Q and D/O values will be compared to annual average dispersion coefficients (X/Q, X/Q', and D/Q'). The more limiting dispersion coefficients will be used along with methodology in sections 3.2.3.1 and 3.2.3.2 for the initial assessment. (2) The location of the critical recept. ;and the pathways j which should be analyzed are shown in Table 3.2-7. (For very rough ~ calculations, the annual average dispersion coefficients (X/Q and D7Q) 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. ODCM, V. C. Summer, SCE&G: Revision 16 (September 1991) 3.0-17

i 4 TABLE 3.2-1 PATHWAY DOSE FACTORS FOR SECTION 3.2.2.2 (P )* l Page 1 of 3 AGE GROUP (CHILD) 1 ISOTOPE INHALATION H-3 1.125E + 03 C-14 3.589E + 04 NA-24 1.610E + 04 P-32 2.605E + 06 CR-51 1.698E + 04 i MN-54 1.576E + 06 MN-56 1.232E + 05 l FE-55 1.110E + 05 4 FE-59 1.269E + 06 CO 58 1.106E + 06 CO-60 7.067E + 06 NI-63 8.214E + 05 N1-65 8.399E + 04 CU-64 3.670E + 04 2N-65 9.953E + 05 ZN-69 1.018E + 04 i BR-83 4.736E + 02 B R-84 5.476E + 02 1 BR-85 2.531 E + 01 1 RB-86 1.983E + 05 RB-88 5.624E + O2 RB-89 3.452 E + 02 l SR-89 2.157E + 06 l SR-90 1.010E + 08 i SR-91 1.739E + 05 l

• See note, page 3.0-20 Units - mrem /yr per pCi/m3 ODCM, V.C. Summer,5CE&G: Revision 13 (June 1990) 3.0 18 O

e-TABLE 3.2-1 PATHWAY DOSE FACTORS FOR SECTION 3.2.2.2 (P;) l Page 2 of 3 ) AGE GROUP (CHILD) ISOTOPE INHALAT!ON j SR-92 2.424E + 05 l Y-90 2.679E + 05 Y-91 M 2.812E + 03 Y-91 2.627E + 06 Y-92 2.390E + 05 Y-93 3.885E + 05 ZR 95 2.231E + OS ZR-97 3.511E + 05 NB-95 6.142E + 05 MO-99 1.354E + 05 l TC-99M 4.810E + 03 TC _ -101 5.846E + 02 RU-103 6.623E + 05 RU-105 9.953E + 04 RU-106 1.476E + 07 AG-110M 5.476E + 06 i TE-125M 4.773E + 05 l TE 127M 1.480E + 06 TE 127 5.624E + 04 TE-129M 1.761E 4 06 TE-129 2.549E + 04 TE-131 M 3.078E + 05 TE-131 2.054E + 03 TE 132 3.774E + 05 ~ l-130 l 1.846E + 06

• 5ee note, page 3.0-20 1

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

i ~ ~~ ~ TABLE 3.2-1 j PATHWAY DOSE FACTORS FOR SECTION 3.2.2.2 (P,) Page 3 of 3 i j AGE GROUP l (CHILD) ISOTOPE l lNHALATIOE 1.624E707 { I-131 l _ l-132 1.935E + 05 1 1-133 3.848E + 06 l-134 5.069E + 04 l-135 7.918E + 05 C5-134 1.014E + 06 C5-136 1.709E + 05 ) 7 C5-137 9.065E + 05 l C5138 8.339E + 02 4 B A-139 5.772E + 04 ) i BA-140 1.743E + 06 j ~ _ -141 2.919E + 03 BA 2 3 BA-142 1.6435 + 03 l LA-140 2.257E + 05 LA-142 7.585E + G4 i CE-141 5.439E + 05 CE-143 1.273E + 05 ^ CE-144 1.195E + 07 l FR-143 4.329E + 05 PR-144 1.565E + 03 ND-147 3.282E + 05 2 W-187 9.102E + 04 i NP-239 6.401E + 04 i NOTE: The P, values of Table 3.2-1 were calculated according 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. 4 i Units - mrem /yr per pCitm3 ODCM, V.C. Summer,5CE&G: Revision 13 (June 1990) 3.0 20

l TABLE 3.2-2 PATHWAY DOSE FACTORS FOR SECTION 3.2.3.2 (Ri)* i Page 1 of 3 AGE GROUP l (CHILD) l (M.A.) l (CHILD) ISOTOPE INHALATION GROUND PIANE VEGETATION ~ H-3 1.125E + 03 (Total Body) 0.000E + 00 (Skin) 3.627E + 03 (Total Body) C-14 3.589E + 04 (Bone) 0.000E + 00 (Skin) 8.894E + 08 (Bone) I NA-24 1.610E + 04(Total Body) 3.33E + 08 (Skin) 3.729E + 05(Total Body) P-32 2.605E + 06 (Bone) 0.000E 700 (Skin) 3.366E + 09 (Bone) CR 51 1.698E + 04 (Lung) 5.506E + 06 (Skin) 6.213E + 06 (Gi-LU) i MN-54 1.576E + 06 (Lung) 1.625E + 09 (Skin) l 6.648E + 08 (Liver) MN-56 1.232E + 05 (GI-LU) 1.068E + 06 (Skin) 2.723E + 03 (Gi-LU) ~ 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 + OG (Skin) . 3.771E + 08 (GI-LU) CO 60 7.067E + 06 (Lung) 2.532E + 10 (Skin) 2.095E + 09 (GI-LLI) ~ NI-63 8.214E C05 (Bone) 0 000E + 00 (Skin) 3.949E + 10 (Bone) ~N!-65 8.399E + 04 (GI-LLI) 3.451E + 05 (Skin) i 1.211 E + 03 (GI-LLI) ) CU-64 1.670E + 04 (GI-LU) 6.876E + 05 (Skin)

5. 59E + 05 (Gi-LU)

ZN 65 9.953E + 05 (Lung) 8.583E + 08 (Skin) 2.164E + 09 (Liver) ZN-69 1.018E + 04 (GI-LU) 0.000E + 00 (Skin) 9.893E 04 (GI-LU) BR 83 4.736E + O2(Total Body) 7.079E + 03 (Skin) 5.369E + 00(Total Body) ~ BR-84 5.476E + O2(Total Body) 2.363E + 05 (Skin) 3.822E - 11(Total body) BR-85 2.531E + 01 (Total Body) 0.000E + 00 (Skin) 0.000E + 00(Tota! Body) RB-86 1.983E + 05 (Liver) 1.035E + 07 (Skin) 4.584E + 08 (Liver) RB-88 5.624E + O2 (Uver) 3.779E + 04 (Skin) 4.374E - 22 (Liver) RB-89 . 3.452E + O2 (Uver) 1.452E + 05 (Skin) 1.642 E - 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) See note, page 3.0 36 Reference 1, section 5.3.1, page 30, paragraph 1 explains the logic used in selecting these 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 Ol ODCM, V.C. Sumrner, SCE & G Revision 13 (June 1990) 3.0 21

~ TABLE 3.2 2 (continued) 1 1 PATHWAY DOSE FACTORS FOR SECTION 3.2.3.2 (R ) i Page 2 of 3 j j AGE GROUP (CHILD) l (N.A.) l (CHILD) 1 ISOTOPE INHALATION l GROUND PLANE l VEGETATION SR-92 2.424E + 05 (GI-LLI) l 8.631E + 05 (Skin) 1.378E + 04 (GI-LLI) Y-90 2.679E + 05 (GI-LL1) 5.308E + 03 (Skin) 6.569E + 07 (Gi LLI) Y - 91 M 2.812E + 03 (Lung) 1.161E + 05 (Skin) 1.737E - 05 (GI-LLI) i Y-91 2.627E + 06 (Lung) 1.207E + 06 (Skin) 2.484E + 09 (GI-LLI) Y 2.390E + 05 (GI-LLI) 2.142E + 05 (Skin) 4.576E + 04 (GI-LLI) Y-93 3.885E + 05 (Gi-LLI) 2.534E + 05 (Skin) 4.482E + 06 (GI LLI) l 2R-95 2.231 E + 06 (Lung) 2.837E + 08 (Skin) 8.843E + 08 (GI-LLI) ] 2R-97 3.511E + 05 (Gi-LLI) 3 445E + 06 (Skin) 1.248E + 07 (Gi-LLI) NB-95 6.142E + 05 (Lung) 1.605E + 08 (Skin) 2.949E + 08 (GI-LLI) 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) 4.123 E - 29 (Kid ney) R U - 103 6.623E + 05 (Lung) 1.265E + 08 (Skin) 3.971E + 08 (GI-LLI) RU-105 9.953E + 04 (GI-LLI) '/.212E + 05 (Skin) 5.981F + 04 (GI-LLI) RU - 106 1.476E + 07 (Lung) 5.049E + 08 (Skin) 1.159E + 10 (Gi-LLI) 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 (Bone) TE - 127M 1.480E + 06 (Lung) 1.083E + 05 (Skin) 3.769E + 09 (Kidney) TE-127 5.624E + 04 (GI-LLI) 3.293E + 03 (Skin) 3.903E + 05 (Gi-LLI) 4 TE - 129M 1.761 E + 06 (Lung) 2.312E + 07 (Skin) 2.430E + 09 (GI-LLI) TE-129 2.549E + 04 (GI-LLI) 3.076E + 04 (Skin) 7.200 E - 02 (GI-LLI) k TE 131M 3.078E + 05 (GI-LLI) 9.459E + OG (Skin) - 2.163E + 07 (Gi LLl) TE-131 2.054E + 03 (Lung) 3.450E + 07 (Skin) 1.349E - 14 (GI-LLI) l TE-132 3.774E + 05 (Lung) 4.968E + 06 (Skin) 3.111 E + 07 (GI-LLI) 1-130 1.846E + 06 (Thyroid) 6.692E + 06 (Skin) 1.371E + 08 (Thyroid) 4 Units - Inhalation and all tritium - mrem /yr per pCi/m3 Other pathways for all other radionuclides -m2

• mrem /yr per pCi/sec 1

ODCM V.C. Summer,5CE& G: Revision 13 (June 1990) 3.0-22 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) 4 750 TOPE INHALATION GROUND PLANE VEGETATION l-131 1.624E + 07 (Thyroid) 2.089E + 07 (Skin) 4.754E + 10 (Thyroid) l-132 1.935E + 05 (Thyroid) 1.452E + 06 (Skin) 7.314E + 03 (Thyroid) 1-133 3.848E + 06 (Thyroid) 2.981 E + 06 (Skin) 8.113E + 08 (Thyroid) i-134 5.069E + 04 (Thyroid) 5.305E + 05 (Skin) 6.622 E - 03 (Thyroid) l-135 7.918E + 05 (Thyroid) 2.947E + 06 (Skin) 9.973E + 06 (Thyroid) CS-134 1.014E + 06 (Liver) 8.007E + 09 (Skin) 2.631E + 10 (Liver) C5-136 1.709E + 05 (Liver) 1.710E + 08 (Skin) 2.247E + 08 (Liver) C5-137 19.065E + 05 (Bone) 1.201E + 10 (Skin) 2.392E + 10 (Bone) C5-138 ! 8.399E + O2 (Liver) 4.102E + 05 (Skin) 9.133 E - 11 (Liver) 8A-139 l 5.772E + 04 (GI-LLI) 1.194E + 05 (Skin) 2.950E + 00 (Gi-LLI) B A-140 l 1.743E + 06 (Lung) 2.346E + 07 (Skin) 2.767E + 08 (Bone) B A-141 l 2.919E + 03 (Lung) 4.734E + 04 (Skin) 1.605E - 21 (Bone) B A-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-LLl) CE-141 5.439E + 05 (Lung) 1.540E + 07 (Skin) 4.082E + 08 (GI-LLI) CE 143 1.275E + 05 (GI-LLI) 2.627E + 06 (Skin) 1.364E i 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) 4 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) W-187 9.102E + 04 (GI-LLI) 2.740E + 06 (Skin) 5.380E + 06 (GI-LLI) NP-239 6.401 E + 04 (GI-LLI) 1.976E + 06 (Skin) 1.357E + 07 (GI-LLI) Units - Inhalation and all tntium - mrem /yr per pCi/m3 Other pathways for all other radionuclides -m2

• mrem /yr per pCi/sec ODCM, V.C. Summer,5CE&G Reosion 13 (June 1990) 3.0 23

e i TABLE 3.2-3 ((,) PATHWAY DOSE FACTORS FOR SECTION 3.2.3.3 (R )* \\ i 4 Page 1 of 3 aca cnous swann an a.: twann msman swann swann twann tmsun actoes manu non onovmo et.ame cas tom uu canoe utar Genow uu Ges cor utar cas.cor wu vestTatom j N.3 6.468f + 02 0.000f + 00 2.157E + 03 0.000f + 00 2.157E + 03 0 000f + 00 4.394t + 03 0.000E + 00 j C-14 2.646E + 04 0.000E + 00 2.340! + 09 0 000E + 00 8.189E + 08 0.000E + 00 2.3401, 09 0.000E 4 00 NA 24 1.0561 + 04 1.385E + 07 1.542t + 07 0.000! + 00 2J00E.37 O M0f + 00 1.851E + M 0.000E+00 P-32 2.030E

• 06 0 000f + 00 1.602f
• 11 0.000! + 00 7.088t + 08 0.00DE + 00 1.924E.11 0.000! + 00 l

CR 51 1.284t + 04 5.506t + 06 4 700E + 06 0.00Ct + 00 1.729t + 05 o r J! + 00 5441E + 05 0400f + 00 MN-54 9.9961 + C5 162SE + 09 3 900f + Ot 0400E + 00 1.1181 + 07 0 009E + D6 4.640E + 06 0.000E + 00 ] MN-56 7.166f + 04 1.068E + 06 2.862E + 00 0 000E + 00 0400E + 00 0 000E + 00 3.436f 01 0.000E + 00 FE-55 8.694f + 04 0.000E + 00 1.251E + 08 0 000E + 00 4 4391 + 07 0.000E + 00 1.757E + 06 0400E + 00 FE 59 1.015E + 06 3204E +08 3.919i + 08 0.000E + 00 3.3&4E + 07 0.000E + 00 5.0961 + 06 0.0'J0E + 00 CO 58 7.770E + 05 4 A6.4E + 08 6.055E

• 17 0.000E
• 00 8.E241 + 06 0.0001 + 00 7.251 E + 06 0.0001 + 00 l

C040 4.508E + 05 2.532f + 10 2.090f + D8 0.000E + 00 7.107t + 07 0.000E + 00 2.517E

• 07 0.000E + 00 NH3 3J88t + 05 OA00E + 00 3.493E + 10 0 000E + 00 1.221E + 10 0.000E + 00 4.192 E + 09 0.000E + 00 N45 5.012E*04 3.4511 + 05 3.020E + 01 0.000E + 00 0 000E + 00 0.000E + 00 3435 E + 00 0 000E + 00 (j

CU44 1.498E

• G4 6.8767 + 05 3.807E + 06 0.000t + 00 7.934 E.46 0.000E+00 4246E
• 05 0.0001 + 00 ZN45 6468E
• 05 8.583E+08 1.904E + 10 0 000E + 00 5.160E+09 0400E + 00 2285E + 09 0.000E,00 1

ZN49 il22E + 04 0.000f + 00 3.8551 09 0.000E + 00 OS00f + 00 0400E + 00 3.581f - 10 0.000f + 00 SR43 3.808t + 02 7.07 91 + 03 93391 01 0.000E + 00 0.000E + 00 0.000f + 00 1.124E - 01 0.000E + 00 8R44 4.0041 + O2 2J63E

• 05 1.2561-22 0.000E + 00 ChocE + 00 0.000E + 00 1.527E - 23 0 000E + 00 BR45 2.044E + 01 0.000t + 00 0.00'i + 00 0 000t + 00 0.000E + 00 0.000E
• 00 0 000E00 0.000E + 00 R&46 1.904f + 05 1.035f + 07 2234E + 10 0 0')CE + 0G 2.827t + 08 0 000E + 00 2.671E + 09 0.000E + 00 R844 5.5728 + 02 3179E + 04 1.474E44 0.000E + 00 0400E + 04 0.000E +00 2.304E 45 0400E + 00 R849 3.206E + O2 1.452t + 05 3.414b52 0.000f + 00 0.000E + OC 0.000E + 00 4.05&E - 53 0.000E + 00 5849 2.030E + 06 2 5091 + 04 1258E + 10 0.000E*00 12801 + 09 0.000E +00 2 EA3E + 10 0 000E + 00 SR-90 4 0$El > 07 0400f + 00 1J16t+11 0.000!*00 4.230E + 10 0400E,00 2.553t + 11 0.000t + 00 SR-91 7J364 + 04 2.5112 e 55 3.215E + 05 0 0001 + 00 0.000E + 00 OS00E + 00 6.758f + 05 0.000E + 00 (P45TURE)

(PASTURf) (FEED) (PA5TURE) (PA$TURL)

• See note, page 3.0 36 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 Revi5 ion 13 (June 1990)

/,,\\ 'd 3.0-24

f ~ TABLE 3.2 3 (continued) PATHWAY DOSE FACTORS FOR SECTION 3.2.3.3 (Ri) Page 2 of 3 l w.m l ...on l.n as..ou, ..... n u, .n .m on l cauer usat l sawot uu Scroes .. w ncu saouwo Maat seuoeuu cas cow usat canow uu vacetaron SR 92 1400E +05 8.631f + 05 5.005E + 01 0 000E + 00 0.0001 + C0 0.000E + 00 1.054E + O2 0.000E + 00 Y 90 2348E + OS 5.308E + 03 9.4064 + 05 0.000E + 00 2.3354 05 0 000E + 00 1.129E + 05 0.000E + 00 Y 9fM 2.784k + 03 1.161E + 05 1.87M 15 1 0 000E + 00 0.000E + 00 0.000E + 00 2.290E 16 0.000E + 00 Y 91 1.450E 1207E

• M 5.25tE+06 0.000E + 00 4.324t*05

- 0.000E + 00 6.302E + 05 0.000E

• 00 92 1266f. 05 2.142E + 05 1.0261
• 01 0 000E 00 l 0.000E + 00 0 000E
• 00 1.2 34E + 00 0 000E + 00 l0.000E*00 2 046E + 03 0.000E + 00 Y.93 166H + 05 2.534t + 05 1.776E + 04 0 000E + 00 2386E41 1.090E + 05 l 0.000E + 00 IR 95 1750t +06 2.8375 08 8.25 7f + 05 0 000E + 00 9.910E + 04 0.000E + 00 20 97 1.400E + 05 3.445E + 06 4 444E + 04 0.000E + 00 4.980E 35 l0.000E00 5J39E.03 0.000E
• 00 NE 95 4.785E + 05 140$E+08 2.062E + 08 0 000E + 00 1.213E + 07 ! 0 0001 + 00 2.4751 + 07 0 000f + 00 MO 99 1.3 toI + 05 4C6E + 06 3.108E + 08 0 000E + 00 1.5234-02 l0.0004e00 3.731E
• 07 0.000E + 00 l 0.0001 + 00 TC 99M 2.030E + 03 2.109E + 05

1. Wit

• 04 0.000E + 00 0.000E + 00 1.9785 + 03 0 000E + 00 1C 101 8 MJf + 02 2 277E + 04 1423 E-56 0 GCCE
• 00 0.000E + 00 0.000E + 00 6.530! 58 01;00E + 00 RU - 103 5 516E+05 1.265E
• 06 1.055E + 05 0 000E
• 00 7.573I + 03 0.000E + 00 1.265E + 04 0 000E + 00 AU 105 4.844E + 04 7.21kE + 05 3.204E + 00 0.000E + 00 0.000E + 00 0.000E + 00 1.851E 01 0.000E
• 00 RU 1%

1.154E + 07 544M + 08 1445E + 06 0.003f. + 0C 4.266t + 05 0.000E + 00 1.734E + 05 0.000E + 00 AG 11DM 3.M8i + 06 4.0ISE+ 09 1.441E + 10 0.000E

• 00 3 984E,09 0400E+00 1.7521 + 09 0.000E + 00

~ TE 12SM 4 A661 + 05 2.128 E + 06 1.508E + 08 0.000E +00 1.7991 + 07 0.000E + 00 1.809E + 07 0 000E+00 1E 127M 1312t + % 1483E + 05 1.037t + 09 0.000E + 00 2.046E

• 08 0.000E,00 1244E+08 0.000E + 00 TE 127 2.436t + 04 3.293ti + 03 1.359E + 05 0.000E+00 1.269E45 0 000E + 00 1.594 5 54 0.000E + 00 TE 129M l 1.6N& a %

E + 07 1J32f +09 0.000E+00 7.559E,07 0.000! + 00 1.6726 08 0100f + 00 TE-129 2.6321 + 04 3.0 76E

• 04 2.187447 0.000E + 00 0.000E + 00 l 0.0001
• 90 2.024 E - 08 0 000E + 00 TE 131M 1.988t + 05 9.459E + 06 2.288E + U F 0400E
• 00 1.653E.15 l0.000f00 2.747E + 06 0 000E + 00 0.000E + 00 f 0.000E + 00 T1+131 8.21H + 03

}450E + 07 1J84E 30 0 000E + 00 1.688f 31 0 000E

• 00 l0.000E+00 ft 137 3.4a2i + 05 4.9681 +06 6.513E + 07 0 000t + 00 1.041E 01 7.842E 06 0 000E
• 00 1 130 1.5M4 + 06 6.692 E. 06 8.754E + 08 0.000f + 00 7115E 45 0400! + 00 1.051E + 09 0.000! + 00 l

(P45TURE) (PAstustE) (Filo) (PASTURO (PASTUR8.) Units - Inhalation and all tritium - mrem /yr per pCi/m3 Other pathways for all other radionuclides -m2

• mrern/yr per pCi/sec ODCM, V.C. Summer,5CE & G Revision 13 (June 1990) 3.0 25

t i I i l TABLE 3.2-3 (continued) j Og PATHWAY DOSE FACTORS FOR SECTION 3.2.3.3 (R,) i Page 3 of 3 l l mf aND l astsaove me+=n mM mf ahQ DNFAmn tmfA4 0 UWAb9 pefAND nes. cow usar l c.ns cow una rsorces mi uAre caounocune ses cow uam ens sor usar uns cor uu vtottance 4 131 1.484E + 07 2.089E

• 07 1.053E + 12 0.000E + 00 1.567E + 08 0.000F + 00 1.264E + 12 0.000E + 00 t.

1 1 132 1.694E + 05 1452E + 06 1188G + 02 0 000E + 00 0.000E + 00 0.000E + 00 1.638E + 02 0.000E + 00 l.133 3.556E,06 2.981E + M 9 6011 + 09 0 000E + 00 1.776E 22 0.000E

• 00 1.153 E + 10 0.000E + 00 l 134 4.452E+04 5J05E + 05 8.402E 10 0.000E + 00 0.000E + 00 0.000E + 00 1.017E 09 0.000E 00 4-135 6.958E
• 05 2.947E + 06 2.002E
• 07 0.000E + 00 l 0.000E + 00 000E + 00 2.406E + 07 0 000E + 00 j

0.000E + 00 f 2.191E + 10 CS-134 7.028E

• 05 8.007E+00 6.801E + 10 0.000E + 00 2.040E + 11 0.000E + 00 t

C5 136 1.345E + 05 1.710E + 08 5 795E + 09 0 000E + 00 1.729E + 07 0.000E + 00 1.744E + 10 0 000E a 00 4 C5 137 6.118E + 05 1.201E + 10 6 024E + 10 05,1CE + 00 2 096E + 10 0.000E,00 1.087E + 12 0.000E,00 g I i C5 138 8 764E + O2 4102E + 05 2.180E-22 0 000E + 30 l0.000E+00 0400E,00 6.628E 22 - 0.04%E + 00 l 0.000E +00 SA 139 5.096E + 04 1.194E + 0S 2.874 E-05 0.000E + 00 0.0GJE + 00 3.265E 06 0 000E + 00 SA + 140 1.596t + 06 2.346E + 07 2.410E + 08 0.0001 00 I 6.409E*05 0.000E + 00 2 A93E. 07 C 000E

• 00 SA lat 4.7461 + 03 4.734E + 04 4.916E-44 0 000E + 00 l 0.000 00 0 000E + 0c 5.899E-45 0 000E 00 0.000E
• 00 l 0 000E
• 00 SA-142 1.554E + 03 5.064E + 04 1849E 78 0.000E
• 00 1.259E 79 0.000E + 00 ii C W 140 1.680E + 05 2.180E + 07 1.280E + 05 0.000E + 00 4.563E-12 0.000E + 00 2.253E + 04 0000E+00

( E.A 142 5.950E* 04 9.117E + 05 147aE45 0.000E + 00 04001 + 00 0.000E + 00 1.278E 06 0 000E + 00 l 4 CE 141 5.166E +05 1.540E+07 1.366E + 07 0 000E + 00 7.039E + 05 0.000Ee00 1.640E + 0E 0.000E 00 CE 143 1.162E + 05 2.627E + 06 1.536E + 06 0.000E + 00 1.029E 14 0.00h

• 00 1.&44E + 05 0.0001 00 i

C1 144 9.812E + 06 8.042E+07 1.334E + 08 0.000E + C0 3 74$E + 07 0.000 E + 00 1.601E + 07 0 0C0E + 00 PR 143 4326E + 05 0400E + 00 7.845E + 05 0 000E + 00 2.771 E + 03 0400E + 00 9.4071 + 04 0 000E + 00 PR.144 4.284E + 03 2.112E+03 1.17 t E 48 0.000E + 00 0 000E + 00 0.000E + 00 1259E 49 0.000E + 00 ND 147 3.220E + 05 1409E + 07 5.743E + 05 0.000E + 00 1 0 902E + O2 0.0001 + 00 6 885E + 04 0.0001 + 00 { vv.187 3 962E + 04 2.740E + 06 2.501 E + 06 0.000E + 00 5275E 22 0.000l + 00 2.943E + 05 0.0Nf + 00 NP 239 5.950E. 04 1.976E + 06 9 400E + 04 0.000E + 00 1.325E 07 0.000E + 00 1.132E + 04 0.000& + 00 l (PASTURE) (PA5TURE) l (P41TURE) l (FEED) (PASTURE) Units-Inhalation and all tritium mrem /yr per pCi/m3 Other pathways for all other radionuchdes -m2

• mrem /yr per pCi/sec ODCM, V.C. Summer, SCE &G: Revision 13 (June 1990) p 3.0-25 C

s

} .s. f TABLE 3.2-4 PATHWAY DOSE FACTORS FOR SECTION 3.2.3.3 (R )* i Page 1 of 3 l l l l ua oOu, x,e. ,o

e. o.

nmo, ea we o.a.

o.o, l Gacunopund 441(ow uns l M5 Com uts? f GAS COW Fu l Ga th0TM4M ) 4.45 40f uu it4TOtt A f 60s, I vfCmMO4 H-3 1.125E + 03 0.000E + 00 I A21E + 03 l 2.119E + 02 1.421E + 03 2.543 E + 0* 2.899t + 03 3.627E + 03 C 14 3 5398 + 04 0.000E + 00 1.195E + 09 l 3.834E + 084.181E + 08 4 601E + 07 1.195E + 09 8.894E + 08 N A 24 1410! + 04 1385E + 07 8.853E + 04 1.725E 03 L321E 37 2.070 E - 04 1.063E + 0'1 3.72SE + 05 P.32 2.605! + D6 0.0006 + 00 7.7751 + 10 7.4118 + 09 3.440E + 08 8.4938 + 00 9JJ5E + 10 3.366E + 09 CF 51 1.694E + 04 5.506E + 06 5.398E + 06 4.661E + C5 1.945E + 05 5.3ft3E + 0s 64788 + 05 6.213E + 06 MN 54 1.5 76E + C,6 1.625E + 09 2.097E + 07 8.011E + 0% 6 012E + 06 9.613E + 05 2.517E + 06 J 6.640E + 08 MN-56 1.232 E + 05 .e68E+06 18658 + 00 2 A37E - 51 0.00DE *04 2.Wal-52 2.2388 01 2.723E + 03 FE 55 1.1108 + 05 0.0008 + 00 1.t188 + 25 ' 4.571E + 04 3.673E + 07 5 48st + 07 1.453E + 06 8.0127 + 08 FE 50 L269E + 06 3J04E + 08 2.025E + 08 6J30Ee06 1.749E + 07 7.605E + 07 2.633E + 06 6.693E + 08 C0 58 1.1068 + 06 4.464E

• 04 7.040E v07 9.5961 07 LO32E + 07 1.152E + 07 8A37E* 06 f.771E + 08 i

C040 1.0618 06 2.532 E + 10 2.191E + 0A 3.830E + 04 8.103E

• 07 4.605E + 01 2.870E + 0 7 2.t/05E + 09 N643 8.214E + 05 0.000E + 00 2364E+10 2.912E + 10 143ET. + 10 3495E +09 3.5570 + 09 ' 3 949t + 10 NS 65 8.3998 + 04 3.451E + 05 lW9E + 01 4.061E 51 0.0008 + 04 4.873E
• 52 2.298E + 00 1.211E + 03 I

CU44 3.670! + 04 6.876E + 05 3.502E

• 06 1393E US 7299E 46 1 4724 06 -

3:907E + 05 5.1598+05 1 ZN 65 9 953E + 05 8.583E + 08 1.101E + 10 1.000f. + 09 2385E + 09 1.200E + 08 1.322( + 09 2164E + 09 J ZN49 1.018E + G4 0.000E

• 00 1.123E 09 0.000E + 00 0.000E
• 00 0.000f + 00 1.043 E.10 9.393E 04 BR.43 4.7368+O2 7.079E +03 4399E 491 9.519E 57 OM0E + 00 1.142E - 57 S.190E 02 5 lG1E + 00 SR-84 5 476E + J2 2J67E +05 6.500E 23 0.000E + 00 0.0008 + 00 9.00a.E + 00 7.758 E - 24 3.82'2E 11 5A-85 2.531E + 01 0.000E + 00 0.000E + 00 0.0004 + 00 0 000E + 00 0.000E + DD 0 000* + 00 0.0001 + 0'J R8 86 L983E,05 1.035E + 07 8.364E + 09 5 856f +08 1.114f + 08 6 579E + 07 t.053E*09 4 584E + 08 RS-46 5.628.E + 02 3l779E + 04 7.150f. 40 0.000T + 00 0 000f + 00 0 000E + 00 8.7698 46 4.374E 22 p _.._

j ,'.3 A52 E + 02 1.45tt +05 l 1J97E 52 0.000E E4 0.000E + 30 0.000E + 00 1.A$$E 53 1.642 E. 26 RS 49 4., Sk-89 2.857E e 06 2.509E + 04 6.6t f E + 09 4.315E + 0J 6.730E

• 0W 5.778E + 07 1.395E
• 10 3.593E + 10 5090 1410E + OS 0.E00E
• 00 1.117E + n 1040E e 10 3 Salt + 10 1.248E + 09 2.346E + 11 1.243E
• 12 i

] $R _-91 1.*39C + &5 2.511E + 0E 2.875E 05 55J92E 10 0.000E + 00 6.3516. 11 6 0W + % 1.157E + 06 (PASTU AE) (PA$ tut!) (FEED) (PA57bHE) (PASTURE) i "See note, page 3.0-36 I IJnits - Inhalation and all tritium - mrem /yr per pCi/m3 Other pathways for all othel radionuclides -m2

• mrem /yr per pCi/sec Ol ODCM, V.C. Summer,5CE &C : Revision 13 Oune 1990) 3.0 27

e-TABLE 3.2-4 (continued) (] PATHWAY DOSE FACTORS FOR SECTION 3.2.3.3 (R ) i 1 7 s/ Page 2 of 3 l l l .a caous . c. w ic oi .o o. ma ,w, oo, um f ses cor u.u r.oron me.Aat r.ve Gaounc p.m su cow una sascom ute ses cow una sas sov usar may i $R-92 2 424t + 05 1 8 631E + 05 4.134f + 01 3.492E 48 l 0 000! + 00 4.191E 49 5 706E + 01 1.378E ei4 Y 90 2.6191! + t:5 53081 + 03 9171E + 05 4.879E + 05 2.277E 05 5.855!+04 1.t01E + 05 6.5 69i + 7 i V 91M 2.412i + 03 1161E + 05 5 622f - 16 e0001+C0 0 000E + 00 0.0001 + 00 6.3441 17 1.7 3? E.5 v-91 21171 + 06 1J07E e06 5199E + 06 2.400t + 04 6.261E+05 2A80f 07 EJ4UE 65 2 At4E + 9 Y-92 2.390E + 05 1.1421 + 05 7.310E + 00 6.959i-35 0 000E + 00 8J501 36 8.791E 01 4.57bt + 4 Y.93 3.845E + 05 J 5341 + 05 15735 + 04 1.5475- 07 9134E -41 1457E -ons 1.8Eftf + 03 4 A82 f + f. 2n-95 2.231 E.> 06 2.837E + 08 4.786E + 05 6.1ME + 08 1.1600 + 05 7J281 > 07 1.0541 + 05 8#41t + 8 l 3.5111-05 3 445E + 06 4.199E + 04 7 015E 01 4.703E - 35 8A18E 02 S M2f + 03 1J48E + 7 22-97 l f 6142E +05 N8 95 1.605( + 00 2 281L,08 ? Jt4E,09 ' 1 J46E + 07 2.6731 + 08 2 7s?f +07 2.949E 8 -4.- l23471+04 MO 99 1.354E + C5 4 62(f + 06 1.7364 + 08 2 416E + 05 8 5121 03 208H.07 14471+7 fc-99M, 4.810E + Q3 2.1Mf e 05 1.4741 + 04 6 915E 18 0 000E + 00 %.W8E 19 1.rtif +03 5.255E + 3 TC 191 l 5.844E + O2 2J771 -. 04 S.5931 58 0.000E + 00 0.0001 + C4 l Q.000f 00 2.5661 59 4.122E 29 4 4.0096 + J3 l 7 952f + 03 l 4.811E + 06 f 1.2 91 + 04 RU 103 6 6235 + 05 1J655*08 1.1($1 + 05 3.9711 + 8 [D RU 105 9 953E + 04 7.1:12 E + 05 2.493*+00 l 5.885E 25 0.000E + 00 7.061E 26 2.1197 E - 01 5 9411 +4 t,_ L Ar i-106 1476 E + 07 5 049f *06 1.437E +06 6 902f + 10 4.243t + 05 8.281/. + 09 1.725E + 05 1.15 5E + 10 AG - 110M 5 4*/6E + 06 4.049f*09 1.470! + 10 6 742E + 08 4.576f + 09 ILO90f +07 2.017E + 09 2 581( + 9 a ft 125M 4.17M + 05 2.u SE+G6 7377t

• 07 5.690E + C4 8.002E.e04 6.8281 07 8 tS;1E
• 06 3.506E + 8 ff 127M 1.480f + D6 1 A13f
• 05 1 5.93JE + 08 5.040E + 09 1.1P1( + 0*

6.0721. D8 7.1184 + 07 3.769 t v 9 4-TE 127 5 621E > 04 3.293t + 03 1.191f + 0% 1.6076-08 Oh00f e 00 t.S?9 09 1396E + 04 1 3 90JE + 5 t! - 129M 1.7 61 E + 06 23'22 f + 07 7.9612 *00 $J451 + 09 4J248 +G7 6,254K + 04 9.M34 + 07 2.46f + 9 TE 129 2.549E + 44 3276t+08 7.%E-OS 0 000E + 00 0.00N +00 0.0004 e 00 9 6410 09 7.t041 2 TE-13tM 3/;79E+05 9.459E + 04 2Jt41 + 07 9 815E

• 03 1 14.21E 15 1.1791 03 2.0942 + D6 2163t + 7 f 0.0M4 + C0 TE-131 2 0548 + 03 3A5cE+07 j M &M 32 0 0004 + 00 0.000! + 00 1.6341 32 1.3451 14 TE 132 27747.*05 6.96Af + 06 4 L1( + 37 9323E 05 T.272 E - 02 1.1191 06 5 480E
• 06 3.111E + 7 6 130 1846t + 06 6 M12E
• 96 3.f45f + 06 4 758f - 04 3.12M - 45 8.10ti: 05 4 61M + 08

' t.3 71 E + 8 (P A$ f uk'i) (PA570W) (F t(D) (PAST1/4E) UA$tWtE) Units - Inhalation and all tritium mrem /yr per pCi/m3 Other pathways for all c ther radionuclides -m2 a mrem /yr per pCi/sec ODCM, V.C. Sum mer, SCE &G: 9 evision 13 (June 1990) (vO 3.0-28

l { ~ TABLE 3.2-4 (Continue) PATHWAY DOSE FACTORS FOR SECTION 3.2.3.3 (R ) 1 i Page 3 of 3 f nacs f gason f zwei aGs uove

m. u gaoa Kuoi

etno, gnos l u.marica lGacuno*Laat lcascowwascas(ow waar j cauo* u.6s l ses sorusar sus ser man vicevano.

.+ notoes t131 1.6241 + 07 2.083E + 07 4J33i + 11 5.5031 + 09 6 4481 + 07 6.604E + 08 5.2016 + 11 4.7541 + 10 b.'32 1935f + 05 1 AS2E + 06 5.12M,01 2.4291 57 0.000E + 00 2.915f 58 7.072E + 01 7Jitt + 03 .e. b'33 36481 66 2.981t + 06 3 945f + 09 1.304E + 02 ?J99f 23 1.5611 + 01 4.737f + 09 8.113t + 08 kne 5 r491 + 04 5.3051,05 3 42st 10 0.000E + 00 0.0ME 00 0400f 00 AJ868 10 6 622E 03 \\ 7 18E + 05 2.$41E + 06 4.6471,06 1.039E 14 ft0%E + 03 1J47E 15 1.034t

• 07 9.97M +06 C$.134 1.014f.06 4.0071*09 3.715E + 10 1.513f + 09

1.197E*10 1.816'i + 08 1.115E.11 2.631E + 10

_~ C54% 1.709E + 05 ) 1.7101 + 08 2.773f + M 4.426f+07 8.2761 + 0h 5.311E + 06 8.344f + 09 2.2471 + 08 i C!137 9 065i + 05 l 1.201f + 10 3.224E + 10 1.334I + 09 1.122E + to 1.600E + 08 9 672E + 10 2.392i + 10 1 CS-138 4.399t + 02 l 4102 t + 05 5.528f -23 0.000f 00 0.000E + 00 0.000K + 00 1.681E 22 9.1331 11 1 f kA 139 5 772E + 04 l 1.104E + 05 1231E 05 0.000 E + 00 0.000f + 00 0.000E + 00 1J98f 06 2 950f + 00 SA.140 1.743E + 06 l 2.346f. 07 1.171E + 08 4 384f + 07 3114f + 05 5.261E + 06 1.406f 07 2.767I + 08 64 14 2.919 + 03 l 4.734t + 04 1JS4f-45 0.000t + 03 0 000f + 00 0.000f 0n 2J73E 46 1.605E.21 d BA442 1.643E + 03 l 5.0641 04 1.204E 79 0.000f + 00 0 000E

• 00 0 000E + GO 1.45ct-80 4.10$E 39 LA 180 2.257E + 05 2.180E + 07 1.8941 05 5 4921 02 4.556f 12 6.0901 01 2Jb9E. 04 3.166t + C7

{ 1 A 1M ?.585f

• 44 9.117E
• 05 5J03E 06 0.000E + 00 0 000E D 0.000f+00 6.1661-07 2.141E + 01 i

CMA1 5.434E + 05 1.540f + 07 1.3611 + 07 1 1821 + 07 6 980 + 05 1.658E + 06 1.633E + 06 4.082E*PS -.~ C1 143 1.773E + 05 1.627X + 0e 1.488t + 06 2.516f + 02 1.006f 18 3 020E

• 01 1.787E + 05 1.364( + 07 CL 144 1.1%5E +07 6.DA21 + 7/

1.3 MI.+08 1 b)3 L + 08 3 727f + tJ7 2.271f + 07 1.592E + 07 1.0391 + 10 PR-t 43 4.329E*05 0.0001 + 00 7.154E + 05 3.609E*07 2.7ME+03 4?3 E + 06 9297f.04 1.575E

• 08 PR-144 1.565f + 03 2.1121 03 2.0401 50 0.000E + 00 0 00H + 00 0 000E + 00 2.3HE - 51 3 4291-23 NO-147 3.2821 e Os 1.0091+07 5.7121 + 05 1.545C + 07 6 85st + 02 1.805E + 06 6.846ti + 04 9197E + 07

~ W 187 $ 102E + 04 2.7404 + 06 2 A10E + 06 2.790f

• 00 5.103E 22 3.3486 01 2.8861
• 05 5.380t + 06 HP 239 4.4011 + 04 1.9761 >04 91HI + 04 2.232E + 03 9 3361 08 2 6791 + O2 1 1001 + 04 1.357E
• 07 (ftS*URE)

(PASTUR() (FtED) (PASTUR() (P A STURI) i 1 I Units - \\ inhalation and all tritium mrem /yr per pCi/m? Other pathways, for all other rarJionuclides -m2

• mrem /yr per pCi/sec i

i ODCM, V.C. Summer, SCE &G. Revision 13 (Jurae 1990) 3029 1

4 i 1 TABLE 3.2 5 .a 1 PATHWAY DOSE FACTORS FOR SECTION 3.2.3.3 (Ri)* Page l of 3 l l astenoue traenassai m.a. rrienastae tras=astas trannaceas ( senassas mamaGeal trianastas l waaut on lcassotwaat soroet o.ouso eums ans com em6s cascowwost castow was oss cor enn vecrTarion H3 1.272E + 03 0.000E + 00 8.993E* 02 1.754E + 02 8.993E

• 02 2.104E + 01 1.835E + U3 2J42E + 03 C 14 2.600E + 04 0.000E + 08 4.859E + 08 2.040E + 08 1.700E
• 08 2448E+07 4 869E + 08 3 690E + 08 l 1.375E + 04 NA24 1.385E
• 07 4.255E + 06 1Ae4E 03 6.347E 38 1.301E 04 5.110E + 05 2.309E + 05 P-32 1 ASSE,06 0.000E 00 3.153E + 10 3.931 E,09 1J95E + 08 4 717E + OS 3.785E
• 10 1408E + 09

? CA 51 2 A96E + 04 5.506t

• 06 SJs7E + 06 9A71E + 05 3.085E,05 1.137E + 05 1.006E + 06 1 A37t + 07

) l MN 54 1.984E + 06 1.625E

• 09 2375E
• 07 1.436E
• 07 8.240E+06 1.723 E. 06 3 A50E + 06 9J20E
• 06

{ MN-M 5.744E + 04 1.068t + 06 4 AME -01 SJ02E 52 C A00E + 00 9 M2E 53 5A29E 02 9 A51E + 02 FE-55 1.240E

• 05 0.000E
• 00 4AS4E + 07 2.182E + 08 1 A63E + 07 2 A59E + 07 5.790E. 03 3259E + 08 FE.59 1.528E + 06 3.204E
• 08 2361E + OS 1.171E+09 2.4701 + 07 1405E + 06 3.720E + 06 9 A95E + OS f

CO 58 1J44E + 06 4 464E + 08 1 A95E + 08 1.542 E + 08 1.596E + 07 2.330E + 07 1J13E + 07 6434E+08 j C040 8.720E*06 2.532E + 10 3621E 08 7.6001

• 08 1.2271 + 06 5.120E,07 4.345E
• 07 3238E + 09 2

3 NM3 5.800E

• 05 0.000E 00 1.182E + 10 1.519E + 10 4.1301 + 09 1 A23E + 09 1.419E + 09 1406E e 10 NM5 3.672 E + 04 3 451E
• 05 4.692E+00 1.305E 51 0 A00E + 00 1.M6E 52 5447E -01 3.966E + 02 s

1 CU44 6.144E + 04 6A76E

• 05 3293E,06 1.713E 05 6.863E 46 2 A72E -06 3473E + 05.

6.465E + 05 l 2h45 1.240E 06 8.583E

• OS 7.315E
• 09 8.648E + Os 1.983E + 09 1.043E + 08 8.779E+CJ 1.471E + 09 i

2N49 1.584E + 03 0.000E

• 00 1.760E 11 0A00E+00 0.000E
• 00 0000E+00 1435E 12 2.067E -05

] BA43 3 440E + O2 7.079E + 03 1.790E - 01 5.066E 57 0.000E

• 00 6.079E - 58 2.112E 02 2.911E,00 SA-84 4.328E
• 02 2.363E + 05 2 A77E - 23 0.000E
• 00 0 000E + 00 0.000E+00 3A29E 24 2.251E 11 l

SA45 1 A32E

• 01 OA00E*00 0.000E + 00 0.000E + 00 0.000E
• 00 0 000 + 00 0.000E + 00 0.000E + 00 s'

1 RS46 1.904E + 05 1.035E + 07 4.746E +09 4.101 E

• OS 6.006E
• 07 4.921E
• 07 5.675E + 08 2.772E
• 08 1

RS48 5AME + 02 3.779E

• 04 3486E-45 0000E
• 90 0.000E 00 0.000E + 00 4.777E 44 3.168E 22 i

l AS49 3.520E + O2 1.452E

• 05 7.957E - 53 0 A00E + 00 0.000E
• 00 0.000E + 00

$ASAE 51 1.247E 26 5A49 2.416E + 06 2.509E

• 04 2 A74E.e 09 2.545E + 0S 2.719E + 08 3.054E
• 07 5.617E + 09 1.513E 10 l

52-90 1.000E + 08 1.000E + 00 6 A12E + 10 8SeeE + 09 2.3011 + 10 9 A59E + 08 1Je9E + 11 7.507E + 11 5R-91 2.592E + 05 2.511E + 06 2.409E + 05 5.794E 10 0.000E

• 00 6.953E 11 5.064E + 05 1.291E 06 (PASTURE)

(PASTURE) (FEED) (PAiTuRE) (PASTURE) ) a i

• See note, page 3.0-36 l

Units - inhalation and all tritium - mrem /yr per pCi/m3 j' Other pathways for all other radionuclides -m2

• mrem /yr per pCi/Sec ODCM, V.C. Summer, SCE & G Revision 13 (June 1990) j 3030 I

B v e e-c-n- ~ --g-w

r ~ TABLE 3.2-5 (continued) O PATHWAY DOSE FACTORS FOR SECTION 3.2.3.3 (R,) Page 2 of 3 A(sI G4008 FtthAGits th a.) ('Ek h AGE R) FitnAGian FifnAGlaj fitthAGree f linAGle) (TithAGEBI ISOToet maAu fsch GaouhD pt.Aht GAS CDw M4E G85 CO* WE AT GAS Cow Mna Gai G0' utaf gas GOT Ms.s wtGETAtlom SR 92 1.192E + 05 8.631E + 05 2.277E + 01 2.516f 48 0.000f 00 3.0191 49 4.795E + 01 1.012E + 04 Y 90 5.592E + 05 5.30RE + 03 1.074E + 06 7.470f + 05 2.666E 05 8.965E. 04 1.289E + 05 1.025E + 08 Y - 91 M 3200E + 03 1.161E + 05 5.129Ed3 0.000E + 00 0.000E

• 00 0.000E + 00 6.260E 19 2.285E 07 Y-91 2.936E + 06 1.207E + 06 6.147E + 06 3.910E + 08 7.797E + 05 4.6911 + 07 7.780E + 05 3.212f + 09 Y - 92 1.6481 + 05 2.142E + 05 2.828E + 00 3.5221 35 D D00E + 00 4J26E 36 3.402E Of 2J60E + 04 T 93 5.792E + 05 2.534E + 05 1J12E+04 1.688E 07 7.620E 61 2.026E 08 1.511E + 03 4.983E + 06 ZR-95 2 688E + 06 2.837E + 08 1.201 E
• 06 1.0921 + 09 1.585E + 05 1J10f+08 1.441E + 05 1.253E + 09 IR 97 6.304! + 05 3 44E + 06 4J25E + 04 9.231E 01 4.732f-35 1.108E 01 5.073! + 03 1.6731 + 07 h8 95 7.512f + 05 1.605E + 08 3.3381 + 08 4251E + 09 1.963 E + 07 5.101E + 08 4.008E + 07 4.551E + 08 Mo 99 2.6881 + 05 4.626E + 06 1023E + 08 1.892 E + 05 5.013E 03 2.270E + 04 1.223E + 07 1.293E + 07 TC 99k 6.128t + 03 2.109E + 05 1455E + 04 6.471E 18 0.000E + 00 7.7661 19 1.267t + 03 5.011E
• 03 0.000E + 00 l 0 000E + 00 TC - 101 6.672E
• 02 2.277E + 04 1.343E 58 0.000E + 00 1.508E 59 3.229E 29 RU 103 7.832E + 05 1.265E + 08 1.513E + 05 7.162 E + 09 1.086E + 04 8.5954 + 08 1.815E + 04 5.706E + 08 RU 105 9.040E + 04 7.212E + 05 -

1263E + 00 3.900E 25 0 000E + 00 4.6801 26 1.519E 01 4.039f + 04 RU 106 1.6081 + 07 5.049E+08 1.799f + 06 1.130E + 11 5.312E + 05 1.356t + 10 2.159E + 05 1.484E + 10 4G 110M 6.752E + 06 4.019E+09 2.559E + 10 1.3451 + 09 6.982E + 09 1.614E

• 08 3.071E + 09 4.031E + 09 TE - 125M 5360 + 05 2.128E
• M 8.863E
• 07 8941E+08 1.0581 + 07 1.073E + 08 1.064E + 07 4.375E + 08 TE 127M 1.656t + 06 1.083E + 05 3 A20! + 08 3J16t+09 6.753f + 07 4.580t + 08 4.105E + 07 2.236E + 09 TE-127 8.080E + 04 3.293E 03 9.572d + 04 1.689E 08 0.000E + 00 2.0271 09 1.122E + 04 4180E + 05 TE-129M 1.976E + 06 2.312E + 07 4.602E + 08 3.964E + 09 2.500E + 07 4.759E + 08 5.528E + 07 1.514E + 09 TE - 129 3.296E + 03 3.076E + 04 2.834 E - 09 0.000E + 00 0.000E + 00 0.000E + 00 3.433E 10 3.916E 03 TE 131M 6208E + 05 9459E
• 06 2.529E + 07 1.447t+04 1.827E 15 1.736t + 03 3.036E + 06 3J48E + 07 TE - 131 2.336E + 03 3.450E + 07 2 A79E 32 0.000E + 00 0.000E + 00 0.000E + 00 3.515E 33 6.099E 15 TE 132 4.632E e05 4.9681 + 06 8.541E + 07 2.300E + 07 1J71E 01 2.760E + 06 1.033E + 07 7.818E + C7 1 130 1.448E + 06 6.692E + 06 1.742f + 08 4.005E 04 1.416E 45 4.806E 05 2.092t + 08 SJ76E + 07 (PASTURE)

(PASTUR() (F E E D) (PASTURE) (PASTURE) Units - Inhalation and all tritium - mrem /yr per pCi/m3 Other pathways for all other radionuclides -m2

• mremlyr per pCi/5ec ODCM, V.C. Summer, SCESG Revi5 ion 13 (June 1990) 3.0 31

~ TABLE 3.2-5 (Continued) p PATHWAY DCSE FACTORS FOR SECTION 3.2.3.3 (Ri) d i Page 3 of 3 l rrtenauni aGesaoup trianacta in.a.3 rrtemassen animacean trianasta, tritmasten tratmacea l l Gas cow utar i isotopt maa4.arion c.aovmo Plana cascowwas Gas cow uns Gas Got usar cas not esas vastianon 1 131 1.464E 07 2.089E + 07 2.195E + 11 l 3.645E 09 3.266E+07 4375E + 08 2.634E 11 3.140f + 10 4 132 1.512E + 05 1.452E + 06 2.242E + 01 1.383E 57 0.000f + 00 1.667E 58 3.092E + 01 4.262 f. 03 1-133 2.920t + 06 2.981E + 06 1.674E + 09 7;f 54E + 01 3 0961 23 8.680E + 00 2.009t + 09 4.587E + 08 l - 134 3.9521 04 5.30$f. 05 1.563E - 10 0.000! + 00 0.000f + 00 0.000f +00 1.915 E - 10 3.854E 03 1 135 6.208E

• 05 2.947E + 06 3.777E + 06 5.9631 15 0.000E
• 00 7.156E 16 4.5316t + 06 5.8321 + 06 C5 134 1.128t + 06 8.007E,09 2J10f + 10 1.231 E + 09 7 443t + 09 1.477E + 08 6.931E 10 1.671t + 10 1.759E +09 l 3.6711 +07 C5 136 1.936E + 05 1.710E + 08 5J49E + 06 4405E + 06 5.2921+09 1.708E + 08 1781E
• 10 l 9 634f + 08 6.197f + 09 1.156E + 08 5.342f + 10 1J48E + 10 CO 137 8.480E + 05 1.201f + 10 C5-138 8.560 + O2 4.102E + 05 3.149E - 23 l 0.000E +00 0 000f + 00 0000f + 10 9.576 E - 23 6.535E - 11 l 0 000f +00 SA 139 6 464E + 03 1.194E + 05 7.741E 07 0 000E + 00 0.000E + 00 8.7941-08 2.403E 01 SA 140 2.032E + 06 2.346E + 07 7.4836 + 07 3 663E + 07 1990E + 05 43964 + 06 8 9811 + 06 2.130E + 08 BA 141 3288E + 03 4.734E + 04 7.703E 46 0 000f 00 0.000E + 00 0.000E + 00 9.244E 47 8.699E 22 8A 142 1.912E + 03 5.064E
• 04 5.0101 80 0 000E + 00 0.000f + 00 0.000E + 00 6.012E 81 5.613E 39 m

LA 140 4.872f.05 2.180E + 07 - 2.2911 + 05 8 6894 + 02 5.5601-12 1.043E + O2 2.745E + 04 5.104E + 07 LA 142 1.200E + 04 9.117E + 05 4.611E 07 0.000f + 00 0.000E

• 00 0.000E + 00 5.465E 08 2.529E + 00 CE 141 6.1361 + 05 1.540E + 07 1.696E + 07 2.252E + 07 8.700E + 05 2.7031 + 06 2.036E + 06 5404f +08 CE-143 2.552 + 05 2.627E + 06 1.671E + 06 3.695E + O2 1.1301 14 4 434E + 01 2.006E + 05 2.040E + 07 CE 144 1J36E + 07 8.042E + 07 1.655E + 08 3.089E + 08 4 650f + 07 3.706E + 07 1.986E + 07 1.326E + 10 PR 143 4.832E + 05 0.000f + 00 9 553E + 05 5 817E + 07 3374f +03 6 980E + 06 1.146f + 05 2.3101 + 08 PR 144 1.7521 + 03 2.112E + 03 1.238E 53 0.000f + 00 0Doof + 00 0.000f + 00 1J315 54 3.097E 26 ND 147 3.720E + 05 1.009E + 07 7.116t + 05 2.453f +07 8.552 E + 02 2.942E
• 06 8.530E+04 1424E + 08 W 187 1.768E + 05 2.740E
• 06 2.646E + 06 3 989E + 00 5.579E 22 4.787E 01 3.155E + 05 7.839E + 06 NP 239 1J20f *05 1.976E 06 1.060E + 05 3.387E + 03 1.083E 07 4.064E + 02 1.276E 04 2.097E + 07 (PA5 TURF)

(PASTURE) (FEED) (PASTURE) (P ASTURE) 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) p 3.0-32 V

l TABLE 3.2-6 PATHWA DOSE FACTORS FOR SECTION 3.2.3.3 (R )*) 9i i Page 1 of 3 l Asasaoup noutn m A.: inoutn noutn noutn moutn (Aoutn (Aoutn lonouema.Amt rsorops w=Ataru:n ses cow una san ow usar 2auow.uu ses ser usar sas cor uns wsuare H3 1.264E + 03 0 000E

• 00 6 904E + O2 2.940E + O2 6.904E + 02 3.528E + 01 1 A06E
• 03 2.845E + 03 C 14 1.816E + 04 0.000E + 00 2 654E + 08 2.414t + 08 9.219E + 07 2 897E + 07 2.634E + 08 2.276E + 08 N4 24 1424E + 04 1.385E + 07 2 438E + 06 1.356E + 03 3.636E - 38 1.628E 04 2.926E + 05 2.690E + 05 P 32 1.320E + 06 0.000E + 00 1709E + 10 4 651E + 09 7.559E + 07 5.582 E + 08 2.052E
• 10 1 A03E + 09 CR.51 1 A40E
• 04 5.506E + 06 7187E,06 1.772 E + 06 2.644E + 05 2.127E + 05 8.624E + 05 1.168E + 07 MN 54 1.400E + 06 1.625E + 09 2.578E + 07 2J12E
• 07 7.389E + 06 3.375E + 06 3.091E + 06 9.585E + 08 MN.56 2.024E
• 04 1.068E + 06 1.328E 01 4.958E 52 0.000E + 00 5.949E 53 1.594E 02 5.082E + 02 FE 55 7.208 E
• 04 0.000E
• 00 2 511E + 07 2.9331 08 8250E + 06 3.519E + 07 3J65t
• 05 2.0%E + 08 FE 59 1.016E
• 06 3J04E + 08 2.327E + 08 2.080E + 09 2.009E + 07 2.495E
• 08 3.024E + 06 9.875E + 08 l

CO-58 9280E + 0S 4 A44E + 08 9.565E

• 07 3.703E + 08 1JWE + 07 4.443E + 07 1.147E + 07 6252E + 08 C040 5.968t + 06 2.532E + 10 3.082E + 08 1413E + 09 1.044E + 08 1.695E + 08 3.7E + 06 3.139E + 09 N143 4 320E + 05 0.000E 00 6 729E + 09 1.888E + 10 2.351E + 09 226GE + 09 8.075E + 08 1.040E + 10 NM5 1.232E + 04 3.451E + 05 1219E + 00 7.405E 52 0.000E + 00 8 686E 53 1A64E 01 2.0261 + O2 CU44 4J96E +04 6J76E
• 05 2.031E + 06 2.3071-05 4.233E 46 2.769E 06 2.415E + M 7.841E
• 05 2k45 8 640E
• 05 8.583E + 08 3.708E + 09 1.132E
• 09 1.183E
• 09 1358E + 08 4.588 E + 08 1.009E
• 09 2N49 9.200E + 02 0.000E + 00 4.031 E - 12 0.000E + 00 0.000E + 00 0.000E + 00 4.837E 13 1.202E - 05 8843 2 A08 E + 02 7.079E
• 03 1.399E 01 8.648E 57 0.000E
• 00 1.03EE 57 1.698E 02 4475E + 00 BR44 3.128E
• 02 2J63E
• 05 1.69E 23 0.000E + 00 0.000E + 00 0.000E + 00 2.029E 24 2.475E 11 8R.85 1.280E + 01 0.000E + 00 0.000E + 00 0.000E + 00 0.000E + 00 0 000E
• 00 0.000E + 00 0.000E + 00 R8 86 1.352E + 05 1.027E + 07 2.595E + 09 4.870E
• 00 3.201E + 07 5.845E + 07 3.113 E + 08 2.194E + 08 RS48 3.872E + 02 3.779 E + 04 2.139E 45 0.0GOE + 00 0.C00E + 00 0.000E + 00 2.573E 46 3.428E 22 RB49 2.560E
• 02 1 A76E + 05 4A96E 53 0.000E + 00 0.000E + 00 0.000E + 00 5.396 E. 54 3.961E 26 SR49 1400E + 06 2.509E + 04 1 A51 E
• 09 3.014E + 08 1 A75E + 08 3.617t + 07 3.046E + 09 9.961E + 09 SR.90 9.920E + 07 0.000E + 00 4.680E + 10 1.244E + ?0 1.628E + 10 1 A93E + 09 9.828E + 10 6.846E + 11 SR.91 1.912E + 05 2.511 E + 06 1J77E
• 05 7.233E.10 0.000E + 00 8.680E - 11 2.872E + 05 1A51E+06 (PASTURE)

(PA57URE) (FEED) (PA57URE) (PA57URE)

• See note, page 3.0-36 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) 3.0-33 i

r TABLE 3.2-6 (continued) h PATHWAY DOSE FACTORS FOR SECTION 3.2.3.3 (Ri) Page 2 of 3 AGsGaoue snouLn m.A.) saoutn moutn soutn inomr) nou6n inoutn s10 Tort usmaLATKHs Gaoun0 Plast GanCow usLs Ga6(De utAt Gas Cow ests Gang 0futar Gas GoT usta vtGttatiom SR 92 4.304E + 04 8 631E*05 9 675E + 00 2.334E 48 0 000f + 00 2.801 E - 49 2.05E

• 01 8.452E e 03 Y to 5.8%E + 05 5.308E + 03 7.511E + 05 1.1411 + 06 1.865E 05 1.369E + 05 9.02SE + 04 1.410E + 08 Y 91M 1.920! + 03 1.161E + 05 1.833E 19 0.000E + 00 0.000E 00 0.000f + 00 2.262f 20 1.527E 08 Y 91 1.704E + 06 1207E
• 06 4.726E*06 6.231 E + 08 5 691 E. 05 7.477t + 0?

5.672E + 05 2.814E + 09 Y 92 7J52E + 04 2.1421 + 05 9 7721 01 2.657E 35 0.000f. 00 3.18M 36 1.17E 01 1.6031 + 04 Y 93 4.216E + 05 2 SME

• 05 7.091E
• 03 2 0751-07 4.290E 61 2 490E 08 BAZE + 02 5.517E + 06 ZR 95 1.768E
• 06 2437E*08 9 587E + 05 19031 + 09 1.265E + 05 2284E + 08 1.151E + 05 1.104f,09 ZR.97 5.232E
• 05 3 445E + 06 2.707E + 04 1.292E + 00 3.032E 35 1.550E 01 3.24E
• 03 2.108E +07

[ NS 95 5.048t+05 1.605E

• 00 2.787E
• 08 7.748E + 09 1.6ME 07 9.297 + 08 3.344E
• 07 4.798 + 08 M O 99 2.480E
• 05 4.626t+06 5.741E+07 2.3181 + 05 2.813E 03 2.7811 04 6.878E + 06 1.426E
• 07 TC 99M 4.160f+03 2.109E
• 05 5.553E
• 03 7.43M 18 0.000E 00 8.927E 19 6.641 E + 02 5.187t + 03 TC 101 3 992E + 02 2.277E + 04 7A06E 59 0 000f
• 00 0 000f.00 0.000E,00 8 888E 60 3.502E 29 Ru - 103 5 048f + 05 1.265E
• 08 1.189E + 05 1.229E + 10 9.537E
• D3 14751 + 09 1426E + 04 5.577E + 08 RU 105 4.8161+04 7.212E
• 05 '

SJ40E 01 3.533E 25 0.000E

• 00 4.2ME 26 6.245E 02 3.294E + 04 Ru 106 9360E + 06 5.0a91 + 08 1J20E + 06 1.811E + 11 3.898E + 05 2.173E
• 10 1.5844 + 05 1.247E + to AG-110M 4.6325 + 06 4.019E+09 2.190E + 10 2.52M + 09 5 996E
• 09 3.020E
• 08 2134 09 3.9791 + 09 TE 125M 3136f +C5 2.128E + 06 6.626E + 07 1.440E + 09 7.906E + 06 1.751E + 04 7.955E + D6 3.927E + 08 TE 127M W 600E
• 05 1.083! + 05 1.860E
• 08 4.531E + 09 3 6711 e 07 5 A375 + 08 2.223 E + 07 1.418E + 09 Y! 127 5 736E + 04 3.293E + 03 5.278E+04 2.3345 08 0.000E
• 00 2 A411 09 6172E + 03 4.532E + 09 TE 129M 1.160E + 06 2312E + 07 3.028E + 08 5 694E
• 09 1.645E + OT 6.5ME + 04 3.636E + 07 1.261 E,09 TE-129 1.936E + 03 3.076E + 04 1.183 E - 09 0 000E
• 00 0.000E + 00 0.000E
• 00 142E 10 2.80543 TI -131M 5.560E + 05 9 A5M + 06 1.75 M +07

. 190E* 04 1.266E 15 2.628E + 03 2.102E + 06 4.428E + 07 TE 131 1J92E,03 3.450E

• 07 1.578E - 32 0.000E + 00 0 0001 00 0.000F,00 1.927E 33 6.5755 1b

?E-132 5.096E + 05 4.968E*06 7.356E + 07 4.287E+07 1 1701 01 5.144E + 06 8.827E+06 1.312 E + 08 130 1.136t

• 06 EM2E + 06 1.050E +08 5.272E 04 8.535E 46 6.326E - 05 1.254E
• 08 9.809 + 07 (PASTURE)

, (PASTURE) (F E ED) (PASTURE) (PASTURE) Units - Inhalation and all tritium - mrem /yr per pCi/m3 s Other pathway 5 for all other radionuclides -m2

• mrem /yr per pCi/Sec ODCM, V.C. Summer 5CE&G Revision 13 (June 1990)

[ 3.0 31 (

.~ e-TABLE 3.2-6 (Continued) PATHWAY DOSE FACTORS FOR SECTION 3.2 3.3 (R;) Page 3 of 3 asisaout Soutn in a s wou6n wouth woutn Soutn Soutn Soutn novoes mauno+ snouno stans cascow was l canowwaar { ses ser uus cascom usa ensat unat vesstanoa s 131 1.1921 + 07 2 089E + 07 1.388E + 11 l 5.0341 + 09 2.065E + 07 6.040E + 08 1.665E + 11 3.785E

• 10 A 132 1.144E + 05 1.452E + 06 1541 E + 01 l 1.816E 57 0.000E + 00 2.179E + 58 1.849E
• O',

5.0161 + 03 l 9.336E + 01 1 133 2.152E + 06 2.981E+06 9.891 E + 08 1.830E 23 1.120t + 01 1.1 E ?'. 09 5J31E + 08 l0.000E+00 1 134 2.9648

• 04 5.305E + 05 8.886E 11 0.000E + 00 0.000E + 00 1.066E 10 4.563E-03 l 7.644E 15 1 135 4.480f + 05 2.9471 + 06 2.217E + 06 0.000E + 00 9.172E 16 2.676E + 06 6.731E + 06 C5 134 8.480 05 8.007E + 09 1.345E + 10 l 1.565E
• 09 AJ33E+09 ( 1.878E+08 4.035E.10 1.110E
• 10 l 4 724E,07 C5 136 1464E + 05 1.710E
• 08 1.039E + 09 3.093E + 06 5 669E + 06 3117E + 09 1.675E + 08 l 1.010E + 10 C5 137 6.2081 + 05 1.201E
• 10 1.193E + 09 3313E + 09 1431E + 08 3.03E + to 8 696E + 09 C5 138 6.208E + O2 4102E + 05 1.786E 23 0.000E + 00 0.000E + 00 0.0001 + 00 5.146E 13 7.730E 11 8A 139 3.760E + 03 1.194E + 05 l 7.863E 08 0.000E + 00 0.000E + 00 0 000E + 00 9 4355-09

$J25E 02 8A 140 1.272E + 06 2.346E + 07 5.535E + 07 5.9178 + 07 1.472E

• 05 7.100E + 06 6 643E + 06 2.646E + 08 8A 141 1.936f + 03 4.734E+04 4.327I 46 0.000f + 00 0_000E +00 0.000E
• 00 5.193 E-47 9.463E 22 l 2.509E 80 E4 142 1.192t + 03 5.064E 04 0 000E + 00 0.0001 00 0.000E 00 3.011 E-81 2.463f 39 LA 140 4.584E + 05 2.180E + 07 1.672 E + 05 1J85E + 01 4 059E 12 1.662E + O2 2.006E + 04 7.319E + 07 LA 142 6J28E + 03 9.117E + 05 6.273 E - 08 0.000E,00 0.000E + 00 0.000E,00 7.531E49 6.768E 01 Cl 141 3.616E + 05 1.540E
• 07 1.25f + 07 3 632E 07 6.424E + 05 4.358t + 06 1.503E + 06 5.097t + 08 CE 143 2.264E +05 2.627E + 06 115E + 06 5.547E + 02 7.768E - 15 6456E 01 IJ8E + 05 2.758t + 07 CE 144 7.776E + 06 8.042t+07 1J1E + 08 4.928t + 0B 3.398t + 07 5.914E + 07 1.451t + 07 1112f + 10 PR 143 2.808E + 05 0.000E + 00 6.918E
• 05 9.204E + 07 2.445E + 03 1.104E + 07 8.297E + 04 2.748E + 08 1

PR 144 1.016E

• 03 2.112t + 03 6.716t + 54 0.000E + 00 0.000E + 00 0.0001 00 7.745E 55 3.3031-26 NO 147 2.208E + 05 1.009E
• 07 5.231t + 05 3935E+07 6.296E + 02 4.722E+06 6.273f + 04 1.853E + 08 W - 187 1.552E + 05 2.740E
• 06 1.79664 06 5.912 E + 00 3.787E - 22 7.0$4E 01 2.14I + 05 1.046E + 07 NP 239 1.192E + 05 1.9761 + 06 7.409E + 04 5.1521 + 03 7.545E - 08 6.182E,02 8.8761 + 03 2.872E + 07 (PASTURE)

(PA57URE) (FEED) (PASTURf) (PASTURE) i 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) 3.0-35

d 1 !O 4 NOTE: The R, values of Table 3.2 2 through 3.2 6 were calculated in i accordance with the methods of Section 5.3.1 of Reference 1. Columns in those tables marked " Pasture" are for freely-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. 1 i i i l 4 !O 1 W ODCM, v.C. Summer, SCE8G. Revision 13 (June 1990) 3.0-36

1 O Table 3.2-7 CONTROLLING RECEPTORS, LOCATIONS, AND PATHWAYS

• DISTANCE AGE ORIGIN SECTOR (METERS)

PATHWAY GROUP (FOR INFORM ATION ONLY) N** 6,100 Vegetation Child -Vegetable Garden NNE*

• 5,300 Vegetation Child

-Vegetable Garden NE 4,500 Vegetation Child Vegetable Garden 4,500 Grass / Cow / Meat Child Grazing Beef Cattle j ENE 2,600 Vegetation Child -Vegetable Garden 2,600 Grass / Cow / Meat Child Grazing Beef Cattle E 1,800 Vegetation Child -Vegetable Garden ESE 1,800 Vegetation Child -Vegetable Garden SE 2,400 Vegetation Child Vegetable Garden SSE 4,300 Vegetation Child -Vegetable Garden 5** 6,300 Vegetation Child -Vegetable Garden 55W** 5,500 Vegetation Child -Vegt; table Garden SW *

• 5,300 Vegetation Child

-Vegetable Garden W5W 3,100 Grass / Cow / Meat Child -Grazing Beef Cattle W 4,300 Vegetation Child -Vegetable Garden 3,500 Grass / Cow / Meat Child Grazing Beef Cattle WNW*

• 7,700 Vegetation Child

-Vegetable Garden NW*

• 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 used to identify these control-ling receptors. If a cow were located at 5,0 miles (8,000 meters) in this sector, an infant , consuming only its milk would receive a greater total radiation dose than would the real receptor listed. However, such an infant would not be the Maximum Exposed Individual for the site. i l ODCM, V. C. Summer, SCE&G: Revision 16 (September 1991) 3.0-37 t i

4 et f**# 4 4 4 NOTE: The controlling receptor in each sector was identified in the following way. Receptor locations and associated pathways were i i obtained from the August 1991 field survey. A child was assumed j at each location, except that where a milk cow was listed, an infant was assumed. X/Q' and D/Q' for each cai$idate receptor was J j calculated using five year average'. meteorological data. XOQDOQ-82 software was used to analyze the meteo-rological data. Expected annual releases of each nuclide were taken from Table 5.2-2 of Reference 5. The specific dispersion values for each candidate are used with the methodology of ODCM section 3.2.3.2 to calculate a hypothetical dose. The controlling receptor for each j sector was then chosen as the candidate receptor with the highest j total annual dose of any candidate receptor in the given sector. All listed pathways are in addition to inhalation and ground plane exposure. 1l0 1 1 i } i 1 i i l \\ i i J i; O ODc. v. c. s.. e,. sce.e: Re.ision,2 <.p,ii,,,3>

3. ass I

4

\\ ^ O l Table 3.2-8 ATMOSPHERIC DISPER510N PARAMETERS FOR CONTROLLING RECEPTOR LOCATION 5* i . DISTANCE SECTOR XTO' 1570' '* (MILES / METERS) N 2.3 E-7 6.3 E-10 3.8/ 6,100 NNE 2.9 E-7 8.5 E-10 3.3 / 5,300 NE 5.4 E-7 1.5 E-9 2.8 / 4,500 ENE 1.8 E 6 5.4 E-9 1.6/ 2,600 E 3.5 E-6 1.1E-8 1.1 /1,800 ESE 2.1 E-6 6.8 E 9 1.1 /1,800 SE 6.5E-7 2.4 E 9 1.5/ 2,400 SSE 1.2E-7 5.3 E-10 2.7 /4,300 5 7.6 E-8 3.5 E-10 3.9 /6,300 55W 1.2E-7 7.0 E-10 3.4 / 5,500 l SW 1.3E-7 9.6 E-10 33 /5,300 W5W 3.6E-7 2.5 E-9 1.9/3,100 W 1.8E-7 7.7 E-10 2.7 /4,300 W 2.8 E-7 1.3E-9 2.2 / 3,500 WNW 3.8 E 8 1.3 E-10 4.8/7,700 NW 9.8E-8 2.8 E-10 4.1 / 6,600 NNW 3.3E-7 9.0 E-10 3.0/ 4,800 Annual average relative dispersion and deposition values for the receptor locations in Table 3.2-7. Values were calculated from 5 year averaged meteorological data using the XOQDOQ-82 software. Dispersion values were calculated assuming ground-level release, open terrain recirculation, dry depletion, 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 exposed individual for the site is assumed to be the vegetable garden at 1.1 miles in the E sector. Therefore, the site X/Q' and D/Q' (Section 3.2.3.2 and following) are those from this table for that location. O ODCM, V. C. Summer, SCE&G: Revision 17 (April 1993) 3.0-39

( f 4 Table 3.2-9 Page 1 of 4 PARAMETERS USED IN DOSE FACTOR CALCULATIONS Oriain of Value l Parameter Value Section of Table.in Site-N REG R.G.1.109 5_pecific 1 0133

• *
• Fo r P.* *
• a

DFA, Each radionuclide E-9 Note 2 3

BR 3700 m /yr E-5

• *
• For Ri (Vegetation)* *
• r Each element type E1 2

Y, 2.0 kg/m E-15 Aw 5.83 E-7 sec ' 5.3.1.3 t i i V

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

i V a' Each age group E-5 f 1.0 5.3.1.5 t ) t; 8.6 E + 4 seconds E-15 5 l Ua Each age group E-5 f, 0.76 5.3.1.5 t, 5.18 E + 6 seconds E-15 3 H 8.84 gm/m Note 1

• *
• For Ri (Inhalation)* *
• BR Each age group E-5

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

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

e-O Table 3.2-9 Pace 2 of 4 PARAMETERS USED IN DOSE FACTOR CALCULATIONS Oriain of Value Parameter Value Section of Table in Site-NUREG-R.G.1 109 Specific 0133

• * *For R Plane)** g(Ground SF 0.7 E-15

DFG, Each radionuclide E-6 1

4.73 E + 8 sec 5.3.1.2

• **For Ri (Grass / Animal / Meat)* **

O, (Cow) 50 kg/ day E-3 Q, (Goat) 6 kg/ day E-3 U,3 Each age group E-5 Aw 5.73 E-7 sec ' 5.3.1.3 F, (Both) Each element E-1 r Each element type E-15

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

1.0 Note 3 f, 1.0 Note 3 3 Y, 0.7 kg/m E-15 t, 7.78 E + 6 sec E-15 2 Y, 2.0 kg/m E-15 ~ tf 1.73 E + 6 sec E-15 3 H 8.84 gm/m Note 1 6 ODCM, V.C. Summer,5CE & G Revision 13 (June 1990) 3.0-41

~ ."~ ' O Table 3.2-9 Page 3 of 4 PARAMETERS USED IN DOSE FACTOR CALCULATIONS Oriain of Value Parameter Value Section of 4 Table in Site-N G R.G.1.109 bD'C C 0133 4

• • • For R Note 4 (Grass /Ahimal/ Milk)* **

Op (Cow) 50 kg/ day E-3 QF (Goat) 6 kg/ day E-3 { U,, Each age group E-5 Aw 5.73 E-7 sec ' 5.3.1.3 F, Each element _ -1 & E-2 E r Each element type E-15 4

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

Y, 0.7 kg/m E-15 ) t, 7.78 E + 6 sec E-15 2 Y, 2.0 kg/m E-15 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 3 H E.34 gm/m Note 1 O ODCM, V.C. Summer, SCE&G: Revision 13 (June 1990) 3 0-42

1 ,1 O Table 3.2-9 (Continued) Page 4 of 4 NOTES 1. Site-specific annual average absolute humidity. For each month, an average absolute humidity was calculated from the 7 years of monthly average 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 a of Reference 1 gives a default value of 8 gm/m3.) 2. Inhalation and ingestion dose factors were taken from the indicated source. For each age group, for each nuclide, the organ dose factor useo was the highest dose factor for that nuclide and age group in the referenced table. 3. Typically beef cattle are raised all year nn pasture. Annualland 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 their numbers cannot sustain the meat. consumption rates of Table t-5 of Reference 3. 4. According to the August 1990 land use censas, dairy cattle possibly graze at 4.9 miles in the West sector. If dairy cattle graze at this location, the dose to an infant consuming milk from these animals would be less than the dose received by the critical receptor identified for the sector. No other milking activity within five miles of the plant was identified. These values are included for reference only. 5. Two columns of R,'s were calculated - one for cows kept exclusively on local 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. O ODCM, V. C. Summer, SCE&G: Revision 14 (December 1990) 3.0-43 l e s

1 a .b* ~ ~ GASEOUS RADWASTE TRE ATMENT SYSTEM Q-l 3 3 - A FIGURE 3.21 is U 1 a a w j fa j i l il i l I! i 4 i s! I il il 11 11 il 15 51, 1 I 5 I 4 l is r a a n a 1 4 i 4 E A lil +i exi +: li-l T / i ill e. .'+ e-glj 4. !. + ii* Ill 'i ? Ii

• ii*

111 +' 1gl + g li! + 4 4 l J6 d6 lI, 1,1, +.............. 1 i y,e j............ I8 i ,s i I, i ist i I ii a t i iln! !! l,[ 1 ii il .= I t............." iI ?!lI li i! iI {

85

,: i a lei g. I Ej 3 I I 1. It! gl g J d .I 3333:1! (; ll. .t w ( ) CDCM, V.C. Summer, SCE&G. Revision 13 (June 1990) + 3.0-44

l 4

c" a O: 3.3 Meteorolooical Model for Dose Calculations 3.3.1 Meteorolooical Model Parameters l i Seciion of Term Definition Initial Use i b height of the containment building. (3.3.2.1) = deposition rate for ground-level releases relative (3.3.2.2) D' = to the distance from the containment building (from Figure 3.3-3). i D/O = the sector averaged relative deposition for (3.3.2.2) any distance in a given sector (m.2), i wind speed class. The wind speed classes are (3.3.2.1) = given in Table 4A of Reference 10 as 1-3,4-7,8-12, 13-18,19-24, 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,' = conditiore are observed to be in a given wind direction, wind speed i class i, and atmospheric stability class j. number of hours wind is in given direction. (33.2.1) n = distance from the containment building (3.3.2.1) r = to the location ofinterest for dispersion calculations (m). AT/A2 = temperature differential with vertical (3.3.2.1) separation (*K/100m). T terrain recirculation factor, Figure (3.3.2.1) = 3.3-4. 4 wind speed (midpoint of wind speed (3.3.2.1) u, = class i) at ground level (m/sec). X/O = the sector average relative concenttation at (3.3.2.1) 3 any dktance in a given sector. (sec/m ). ) plume depletion factor at distance r (3.3.3.1) 8 = from Figure 3.3-1. i e ODCM, V. C. Summer, SCE&G: Revision 16 (September 1991) 3.0-45

-. - ~. ~. O(,) Section of Term Definition initial Use vertical standard deviation of the plume (3.3.2.1) o, = 4 (in meters), at distance r for ground level i releases under the stability category i indicated by AT/ A2,ftom Figure 3.3-2. (2/n)u2 divided by the width in radians of a (3.3.2.1) 2.032 = 22.5" sector (0.3927 radians). J 5 2.55 = ' the inverse of the number of.adians in a 22.5* scctor (3.3.2.2) j 1 (22.5*)(0.0175 Radianst') 3.3 2 Meteoroloaical Model i a f 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 relative concentration at any dis- = l tance in the given sector (sec/m ) 3 U 2.032 6TT (52) = y Nru h where: 2.032 = (2/r:)"2 divided by the width in radians of a 22.5 sector (0.3927 radians) 8= plume depletion factor at distance r for the appropriate stability class from Hgure 3.3-1. wind speed class. The wind speed classes are given in Table 4A i = of Reference 10 as 1-3,4-7,8-12,13-18,19-24, 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 classJ. ODCM, V. C. Summer, SCE&G: Revision 16 (September 1991) 3.0-46

i l c 0 l \\ l N total hours of valid meteorological data. = distance from the containment building to location of interest r = (m) wind speed (midpoint of wind speed class i) at ground level u, = (m/sec). (' (V3o,) 1, the lesser of w,8 + 6 /2n)* 2 = or l where: vertical standard deviation of the plume (in meters) at o, = distance r for ground level releases under the stability category indicated by AT/ AZ, from Figure 3.3-2. terrain recirculation factor, from Figure 3.3-4 T = l 3.1416 n = b height of the containment building (50.9m) = AT/A2 temperature differential with vertical separation = (*K1100rn). ] Note: For calculation of X/O using actual meteorological data for a particular release, ui = the average wind speed for hour i and nij = number of hours with wind speed i and stability class J. 3.3.2.2 Relative deposition per unit area for all releases is calculated for a ground-level release. D/O the sector-averaged relative deposition at any distance in = 4 a given sector (m ). 2.55 D n (54) = g rN

where, deposition rate for ground-level releases relative to D,

= distance (r) from the containment building (from Figure 3.3-3). O ODCM, V. C. Summer, SCE&G: Revision 16 (September 1991) 3.0-47

dV 2.55 the inverse of the number of radians in a 22.5 sector = 1 (22.5*)(0.0175 Radiansr) number of hours wind is in given direction (sector). n = N = total hours of valid meteorological data. r (L ODCM, V. C. Summer, SCE &G: Revision 13 (June 1990) q 3.0-48

\\ Y FIGURE 3.3-1 1 Plume Depletion Effect for Ground Level Releases (6) (All Atmospheric Stability Classes) l l i Graph taken from Reference 8, Figure 2 l l A j j l 58 1 / / / ~~ / l \\ / E i E t o 9 j s / =< r J g / a .a / i ew E o i 1 I I I I I v 's o R N A w n. N e s o o o o o d o o d FRACTION REMAINING IN PLUME ODCM, V.C, Summer, SCE & G : Revision 13 (June 1990) 3.0-49

4 v-FIGURE 3.3-2 a Vertical Standard Deviation of Materialin a Plume (6 ) 2 (Letters denote Pasquill Stability Classes) e i' i Graph taken from E lerence 8, Figure 1 t 1000 l l j I / / l / / j / -/ f f { / / / i l / / // ~ 100 / / / / / 1 1 r r 1 / 7 s / / y /' / e / / / c// / s f'// /k! / / ~ / / // of / e

/ / /

l c/ l j. s' 7 / / / sf J / / / j / / i /) / / i s 2 1 i of 1.D 10 100 l PLUME TRAVEL D43rrANCE mlLOMt.TERS) l Temperature Change Pasquill Stability { with Heicht AT/a7 PK/10ld Catecories Classification i < - 1.9 A Extremely Unstable -1.9 to -1.7 B Moderately Unstable j -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 l > 4.0 G Extremely Stable 1 ) ODCM, V.C. Summer, SCE&G Revision 13 (June 1990) j. '3050 . _ = _ -.,

p., FIGURE 3.3-3 Relative Deposition for Ground Level Releases (D ) g (All Atmospheric Stability Classes) Graph taken from Reference 8, Figure 6 4 10-3 4 N l e 's g 'u x i w (. \\ m T E h \\ w E \\ a s $ 10-5 \\ ~ \\ w i p si h c s 5 \\ 5" .5 j \\ g N 1 1r8 x 177 .i 0.1 1.0 10.0 100.0 200.0 l 1 PLUME TRAVEL DISTANCE (KILOMETERS) i ODCM, V.C. Summer, SCESG Revision 13 (June 1990) 3.0 51 l

.-~ 4 p.* ) i j FIGURE 3.3-4 l a i 1 ., t l Open Terrain Recirculation Factor 4 5 Graph taken from Reference 7, Figure 2 l l i i l 1 -r

e..

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l a l O 3 i 4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING i Sampling locations as required in section 1 A.1 of the ODCM Specifi-cations are described in Table 4.0-1 and shown on Figures 4.01 and 4.0-2. As indicated oy the ditto (") marks in the table, entries in the sampling l frequene.y and analysis frequency columns apply to all samples below the entry until a new entry appears. i i l i n i d i -t 4 O i l i i f I-- 1 1 4 L 9 ODCM, V.C. Summer, SCEandG; Revision 13 Oune 1990) j 4.0 1 f

m p ,3 h Q ]' i 4 g RADIOLOGICAL ENVIRONMENTAL MONITORING FROGRAM V!RGILC.5!!MMER NUCLEAR STATION TABLE 4.0-1 a P Type h Frequency Emposise Crlierie forSelection Sampilt g end Sempiel locations of Sample Number & Location Ccitection Frequency Location Mi/Dir l ofAnalysis 1w AiABORNE: 1. Paiticulate iA) 3 Indicator:amples to be taken at locations Gn

• Centinuous sampler opera-2 1.15W Gross beta fo! lowing filter l

different seciof5) beyond but as close to the tion with weekly cettection. 7 1.0E change; Quarterly excitision boundary as pract! cable where the 30 h 1.055W Compite (bylocation) for i highest affSite.ectoria!gecundlevei l gamma isotopk. l concentretiens are anticipstad.2 I i i g !B) 1 indicador samp!e to be taken I the sector l Continuous sampier opcra-6 1.0 ESE Gro,s beta fo!!owing filter beyond but as close to the exciosion boundary l tion withweeldy re!!ection. change; Quartarfy as practicable correspeding to the residence i Composite (bylocation) for having the highest enticipated offsite grouat! I gamma isotopic. levelconcer:tratien er dose.2 I i I oritinuoussampler ocera-g N/A N/A Gross beta to!!owing fitter G 1 Indkator sample to be taken at the location C 3 change; Qustterly } of one of the dstries being sampled meeting tion with weekly ce!!ection. the criteria of Vn(A). 2,4 g Composite (bylocation) for l 3 g g:.mma isotopic. I i g 1 8 I eI I i l IO) 1 Control sample to be taken at a location at iContinuous sampler opera-17 25.0 SE Gross betafoliov.hg fiiter l l teast 10 air m!ies from th* site e.d not in the j tionwithweekly cofiection. change; Quarterly most prevelant wind direction.2 Composite (bylocation) for l gsmma isotopic. I I i t-ODCM.V.C. Summer,SCEandG: Revision 20 (November 1995) 4.0-2

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RADIOLOGICAL ENVIRONMENTAL MON!TORING PROGRAM ~ VitiGilC. SUMMER NUCLEAR STATION TABLE 4.0-1 i I I"E " ' Crieeris forSafection Sampling and Sampiet l Locations l Type & Frequercy of Sampfs N-aber& Lcretten Cc!!ection Frequency Lot.ation Mi/Dir ofAnalyth ed 5 pk ~ --_e = j Gamrnaisotopic monthly O 1 Indicator sample to be taken in the uopsr Time composite sampicswith l 23' O.5 ESE with quarterly compm;te(by reservoir of the pumped storage ferility et the rottec"lon every r=ot-th.5 plantdischerga canet Ictstion)to be analyzed for trit"_%7 I V. Ground A) 2 indicator sarop!el to be taken within.he Quarterlygf ab samp!!wg 7 26 Onsite Gammsisotopicandtritium I Water exc! Won boundary and in the die ction of 27 Onsite analyses quarterly.7 a potentia!!y affacted ground water stpplies. El 1 Cor: trol sample from unaffected locat on. Quarterty greb ssmpling 7 59 2.6 55E Gammalsctopic and tritium ' s . analysescuarterty.7 1, i e i g Month!ys gamms!setork Vt. Drinking A) 1 todicatr>r. ample from a nearby public ground ' Monthly grab samp!!ng.5 28 2.6 SSE i Water water supp!y source. ervigross beta analyses and cuarterly composite for 7 3 iritium analyses. a B) 1 Indicator 4 finished water) sample from the Monthlycornposite 17 25.0 SE Monthly 5 gamma isotopic + 1 nearest downstreamwater supply. . sampling, and gross beta analyses and l quarteriyf composite for l tritium analyses. O S Controt (finish wate] sampte i.om an Month!ycomposite 39 14.0 55E Morith:y5gammaisotop!c 3 unaffected water supply. sampling. y and gms; beta analyses sad s quarterly 7 compositeior e ' tritium analyses. GDCM,V.C. Summer,SCEandG: Revirbn 20 (November 1995) 4.0-5

m __. _ __ _ _ _ _ _ _.... _ ____ m_- O. h RADIOLOGICAL ENVIRONMENTAL MOtWTORING PROGRAM VIRGIL C. SUMMER NUCLEAR STATION TABLE 4.0-1 h pm ure Criterle for Selection hmpling and Sample 1 Locations Type & Frequency i way of 3empleihmber&LotaUon Collection Frequency Lo(etaco MI/Dir ofAnalysis ,g INGESTION: Vil M!!k 4 A) Samples from milking animals in 3 locations Semimonthlywhen animals v.w mes Gamma isotopic and 1-131 analysis semimonthly when 8 within 5 km having the highest dose potential. are on pasture, monthly s .n e animals are on pasture, i if there are none then 1 sample from miiting other times.5 wm animals in each of 3 areas between 5 to 5 km e monthly other times 5 distance where doses are calculated to be aw.mm greater than 1 mrem per year.10 i B) 1 Contre,isample to be taken at the location of Semimonthlywhen animals 16 20.0 W Gamma isotopic and 1-131 l a dairy > 20 miles distance and not in the most are on pasture, rnonthly analysis semimonthlyawhen s prevalent wind direction.2 other times.5.11 animals are on pasture, monthly othertimes5 Q 1 Indicator grass (forage) sample to be taken at Monthlywhen i.we Gamma isotopic. l the location of one of the dairies being available 5

• mm sampled meeting the criteria of Vil(A), above, sm when animals are on pasture.

.-ee m.

==.viw [ D) 1 Contro! grass (forage) sample to be taken at Monthlywhen 16 20.0 W Gamma isotopic. thelocation of Vil(B) above. available L11 i l i ? ODCM,V.C. Summer, SCEandG: Revision 20 (November 1995) 4.0-6 f m m... i a-- -m .---. ---. e't

t i RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM VIRGIL C. SUMMER NUCLEAR STATION TABLE 4.0-1 l Criteria for Selection Sar.ipling and Semple 1 Locations Type & Frequency P h* I ,gf,,3,',pg of Sample Number & Location Collection Frequency Location MI/Dir ofAnalysis VIII. Food A) 2 samples of broadleaf vegetation grown in the Monthlywhen available.5 6 1.0 ESE Gamma Isotopic on edible Products 2 nearest offsite locations of highest calculated 7 1.0 E portion. annual average giound level D/Q if milk sampling is not performed within 3 km or if milk sampling is not performed at a location within 5 to 8 km where the doses are calculated to be greater than 1 mrem /yr.10 B) 1 Control sample for the same foods taken at a Monthlywhen available.5 18 16.5 5 Gamma Isotopic on edible location at least 10 miles distance and not in portion. the most prevalent wind direction if milk sampling is not performed within 3 km or if milk sampling is not performed at a location within 5 to 8 km where the doses are calculated to be greater than 1 mrem /yr.10 IX. Fish A) 1 Indicator sample to be taken at a location in SemiannuaI9 collection of 233 0.3-5 Gamma isotopic on edible the upper reservoir. the following specie types if portions semiannustly.9 available: bass; bream, crappie; catfish, carp. B) 1 Indicator sample to be taken at a location in Semiannual' collection of 213 1-3 Gamma isotopic on edible i the lower reservoir. the following specie types if portions semiannually 9 available: bass; bream, crapple; catfish, carp). i ODCM, V.C. Summer, SCEandG: Revision 20 (November 1995) 4.0-7 O 9 e.

~ O O O+- t RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM VIRGilC. SUMMER NUCLEAR STATION TABLE 4.0-1 Criteria for Selection Sampling and Sample 1 Locations Type & Frequency P h a f Sample Number & Location Collection Frequency Location Mi/Dir ofAnalysis and/or Sample O 1 Controf sample to be taken at a location on Semiannual 9 collection of 223 26.0 NNW Gamma !sotopic on edible the receiving river sufficiently far upstream the following specie types if portions semiannually 9 such that no effects of pumped storage available: bass; bream, operation are anticipated. crappie; catfish, carp. AQUATIC: X. Sediment A) I lndicator sample to be taken at a location in Semiannualgrab sample.9 233 0.5 ESE Gamma isotopic. the upper reservoir. B) I fndicator sample to be taken on or near the Semiannualgrab sample.9 213 2.7 SSW Gamma isotopic. shoreline of the lower reservoir. Q 1 Control sample to be taken at a location on Semiannualgrab sample.9 223 26.0 NNW Gamma isotopic. the receiving river sufficiently far upstrearn such that no effects of pumped storage operation are anticipated. 1 l T l ODCM, V.C. Summer, SCEandG: Revision 20 (November 1995) 4.0-8

b p RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM V'RGIL C. SUMMER NUCLEAR STATION TABLE 4.0-1 NOTES (1) Location numbers refer to Figures 4.0-1 and 4.0-2. (2) Sample site locations are based on 5 year average meteorological analysts. (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 generalized areas in order to reaso:stbly assure availability of samples. (4) 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 anangements 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 composite samples are samples which are collected with sguipment capable of collecting an aliquot at time intervals which are g ort (e.g. hourly) relative to the compositing period. (7) Atle.ast once per 100 days. (8) Atleast once per18 days. l (9) Atleast once per200 days. (10) The dose shall be calculated for the maximum organ and age group, using the guidance / methodology contained in Regulatory Gmde 1.109, Rev.1 and the parameters particular to the Site. (11) Milk and forage sampling at the controllocation is only required when locations meeting the criteria of VII(A) are being sampled. 1 l 9 ODCM,V.C. Summer /SCEandG: Revision 20 (November 1995) 4.0-9

,mg ,g (V 4 r k/ R ADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM VIRGIL C. SUMMER NUCLEAR STATION TfsBLE 4.0-1 + Exposure Criteria for Selection Sampiing and Sample 1 Locations Type & Frequency I way of Samp!e Number & tmation Co!!ection Frequesey Location Mi/Dir of Analysis l I) 1 indicator sample to be taken on the shoreline Semiannual grab sample 9 213 2.7 SSW Gamma isotopic. C of thelower reservoir. D) 1 Contro! Sample tc be taken et a location en Semiannual grab sample 9 221 30.0 NNW Gamma isotopic. the reteiving fiver suf ficiently iat upstream suth that no effects of pumped storage operation are anticipated. i s ') ODCM, V.C. Summer, SCEandG: Revision 13 (June 1990) 4.0-10

-. -. ~. i RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM VIRGIL C. SUMMER NUCLEAR STATION TABLE 4.0-1 l ( NOTES ^ l j (1) Location numbers refer to Figures 4.0-1 and 4.0-2. (2) Sample site locations are based on 5 year average meteorological analysis. (3) Though generalized areas are noted for simplicity of sample site enumeration, airborne, water and sediment sampfmg is done at the same location whereas biological sampling sites are generalized areas in order to reasonably assure availability of samples. (4) 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 arrangements can be made, site (s) will be added for additional milk sampling up to a total of 3 Indicator Locations. (5) Notto exceed 35 days. (6) 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. 4 (7) At least once per 100 days. j l (8) At least once per 18 days. (9) At least once per 200 days. i (10) The dose shall be caiculated for the maximum organ and age group, using the guidance / methodology contained in [ Regulatory Guide 1.109, Rev.1 and the parameters particular to the site, ODCM, V.C. Summer /SCEandG: Revision 18 (September 1994) i 4.0-11 3 1 I 5 l I

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